diff --git a/doc/fileformatspec/depcode_input.rst b/doc/fileformatspec/depcode_input.rst index 043f89ba2..b7035750c 100644 --- a/doc/fileformatspec/depcode_input.rst +++ b/doc/fileformatspec/depcode_input.rst @@ -95,6 +95,22 @@ Serpent-specific properties :pattern: ``^(.\\/)*(.*)$`` +``zaid_convention`` +~~~~~~~~~~~~~~~~~~~ + + :description: + ZAID naming convention for nuclide codes. 'serpent': The third digit in ZA for nuclides in isomeric states is 3 (e.g. 47310 for for Ag-110m). 'mcnp': ZA = Z*1000 + A + (300 + 100*m). where m is the mth isomeric state (e.g. 47510 for Ag-110m). 'nndc': Identical to 'mcnp', except Am242m1 is 95242 and Am242 is 95642 + + + :type: + ``string`` + + :enum: + "serpent", "mcnp", "nndc" + + :default: + "mcnp" + .. _openmc_specific_properties: diff --git a/doc/releasenotes/v0.5.0.rst b/doc/releasenotes/v0.5.0.rst index aa044cf76..d93615e27 100644 --- a/doc/releasenotes/v0.5.0.rst +++ b/doc/releasenotes/v0.5.0.rst @@ -64,6 +64,8 @@ Bug Fixes .. Describe any bug fixes. +- `Fix bug where Serpent2 material temperatures are hardcoded to 900K in the JEFF 3.1.2 library format. ` +- `Fix bug where using MCNP-style ZAID codes results in an error in various SerpentDepcode functions ` @@ -98,6 +100,7 @@ Python API Changes - Input file format changes: - Added default values for certain input parameters + - Adds a ``zaid_convention`` input parameter - Added depletion settings for OpenMC - ``num_depsteps`` → ``n_depletion_steps`` - ``depcode['template_inputfile_path']`` → ``depcode['template_input_file_path']`` @@ -167,6 +170,7 @@ Python API Changes - (new function) → ``get_neutron_settings()`` - (new function) → ``_get_burnable_materials_file()`` - (new function) → ``_get_burnable_material_card_data()`` + - (new parameter) → ``zaid_convention`` - ``OpenMCDepcode`` is a ``Depcode`` subclass that interfaces with ``openmc``. This class implements the following functions diff --git a/examples/msbr/msbr_main.json b/examples/msbr/msbr_main.json index 4862d4b53..cd933b0bb 100644 --- a/examples/msbr/msbr_main.json +++ b/examples/msbr/msbr_main.json @@ -5,7 +5,8 @@ "depcode": { "codename": "serpent", "template_input_file_path": "msbr.serpent", - "geo_file_paths": ["geometry/msbr_full.ini"] + "geo_file_paths": ["geometry/msbr_full.ini"], + "zaid_convention": "serpent" }, "simulation": { "sim_name": "msbr_kl_100_simulation" diff --git a/examples/tap/tap_main.json b/examples/tap/tap_main.json index d90380961..2e56de124 100644 --- a/examples/tap/tap_main.json +++ b/examples/tap/tap_main.json @@ -21,7 +21,8 @@ "geometry/1338.ini", "geometry/1498.ini", "geometry/1668_all.ini" - ] + ], + "zaid_convention": "serpent" }, "simulation": { "sim_name": "tap_example_simulation", diff --git a/saltproc/input_schema.json b/saltproc/input_schema.json index 73ca0936e..ff5558679 100644 --- a/saltproc/input_schema.json +++ b/saltproc/input_schema.json @@ -54,7 +54,13 @@ "exec_path": { "default": "sss2"}, "template_input_file_path": { - "pattern": "^(.\\/)*(.*)$"} + "pattern": "^(.\\/)*(.*)$"}, + "zaid_convention": { + "description": "ZAID naming convention for nuclide codes. 'serpent': The third digit in ZA for nuclides in isomeric states is 3 (e.g. 47310 for for Ag-110m). 'mcnp': ZA = Z*1000 + A + (300 + 100*m). where m is the mth isomeric state (e.g. 47510 for Ag-110m). 'nndc': Identical to 'mcnp', except Am242m1 is 95242 and Am242 is 95642", + "type": "string", + "enum": ["serpent", "mcnp", "nndc"], + "default": "mcnp" + } } } }, diff --git a/saltproc/serpent_depcode.py b/saltproc/serpent_depcode.py index 6f6dea171..4c2247d8d 100644 --- a/saltproc/serpent_depcode.py +++ b/saltproc/serpent_depcode.py @@ -41,7 +41,8 @@ def __init__(self, output_path, exec_path, template_input_file_path, - geo_file_paths): + geo_file_paths, + zaid_convention): """Initialize a SerpentDepcode object. Parameters @@ -52,10 +53,21 @@ def __init__(self, Path to Serpent2 executable. template_input_file_path : str Path to user input file for Serpent2 - geo_file_paths : str or list, optional + geo_file_paths : str or list Path to file that contains the reactor geometry. List of `str` if reactivity control by switching geometry is `On` or just `str` otherwise. + zaid_convention : str + ZAID naming convention for nuclide codes. + + 'serpent' - The third digit in ZA for nuclides in isomeric states + is 3 (e.g. 47310 for for Ag-110m). + + 'mcnp' - ZA = Z*1000 + A + (300 + 100*m). where m is the mth + isomeric state (e.g. 47510 for Ag-110m) + + 'nndc' - Identical to 'mcnp', except Am242m1 is 95242 and Am242 + is 95642 """ super().__init__("serpent", @@ -66,6 +78,7 @@ def __init__(self, self.runtime_inputfile = \ str((output_path / 'runtime_input.serpent').resolve()) self.runtime_matfile = str((output_path / 'runtime_mat.ini').resolve()) + self.zaid_convention = zaid_convention def get_neutron_settings(self, file_lines): """Get neutron settings (no. of neutrons per cycle, no. of active and @@ -175,20 +188,33 @@ def convert_nuclide_code_to_name(self, nuc_code): """ if '.' in str(nuc_code): - nuc_code = pyname.zzzaaa_to_id(int(nuc_code.split('.')[0])) + nuc_code = int(nuc_code.split('.')[0]) + if self.zaid_convention == 'serpent': + nuc_code = pyname.zzzaaa_to_id(nuc_code) + if self.zaid_convention in ('mcnp', 'nndc'): + if self.zaid_convention == 'mcnp' and nuc_code in (95242, 95642): + if nuc_code == 95242: + nuc_code = 95642 + else: + nuc_code = 95242 + nuc_code = pyname.mcnp_to_id(nuc_code) + zz = pyname.znum(nuc_code) aa = pyname.anum(nuc_code) aa_str = str(aa) - if aa > 300: - if zz > 76: - aa_str = str(aa - 100) + 'm1' - aa = aa - 100 - else: - aa_str = str(aa - 200) + 'm1' - aa = aa - 200 - nuc_zzaaam = str(zz) + str(aa) + '1' - elif aa == 0: - aa_str = 'nat' + if self.zaid_convention == 'serpent': + if aa > 300: + if zz > 76: + aa_str = str(aa - 100) + 'm1' + else: + aa_str = str(aa - 200) + 'm1' + elif aa == 0: + aa_str = 'nat' + if self.zaid_convention in ('mcnp', 'nndc'): + mm = pyname.snum(nuc_code) + if mm != 0: + aa_str = str(aa) + f'm{mm}' + nuc_name = pyname.zz_name[zz] + aa_str else: meta_flag = pyname.snum(nuc_code) @@ -233,10 +259,23 @@ def map_nuclide_code_zam_to_serpent(self): line = line.split() nuc_code = line[2] if '.' in str(nuc_code): - nuc_code = pyname.zzzaaa_to_id(int(nuc_code.split('.')[0])) - - zzaaam = \ - self.convert_nuclide_code_to_zam(pyname.zzaaam(nuc_code)) + nuc_code = int(nuc_code.split('.')[0]) + # In MCNP format the ground state of Am-242 is 95242, + # but PyNE seems to disagree + if self.zaid_convention == 'serpent': + nuc_code = pyname.zzzaaa_to_id(nuc_code) + zzaaam = \ + self.convert_nuclide_code_to_zam(pyname.zzaaam(nuc_code)) + if self.zaid_convention == 'nndc' or self.zaid_convention == 'mcnp': + if self.zaid_convention == 'mcnp' and nuc_code in (95242, 95642): + if nuc_code == 95242: + nuc_code = 95642 + else: + nuc_code = 95242 + nuc_code = pyname.mcnp_to_id(nuc_code) + zzaaam = pyname.zzaaam(nuc_code) + else: + zzaaam = int(nuc_code) nuc_code_map.update({zzaaam: line[2]}) return nuc_code_map @@ -436,15 +475,15 @@ def run_depletion_step(self, cores, nodes): args = (self.exec_path, '-omp', str(cores), self.runtime_inputfile) print('Running %s' % (self.codename)) try: - subprocess.check_output( + subprocess.run( args, cwd=os.path.split(self.template_input_file_path)[0], - stderr=subprocess.STDOUT) + capture_output=True) + print('Finished Serpent2 Run') except subprocess.CalledProcessError as error: print(error.output.decode("utf-8")) raise RuntimeError('\n %s RUN FAILED\n see error message above' % (self.codename)) - print('Finished Serpent2 Run') def convert_nuclide_code_to_zam(self, nuc_code): """Converts nuclide code from Serpent2 format to zam format. diff --git a/tests/integration_tests/run_constant_reprocessing/tap_input.json b/tests/integration_tests/run_constant_reprocessing/tap_input.json index 730ad0d84..02bb3db04 100644 --- a/tests/integration_tests/run_constant_reprocessing/tap_input.json +++ b/tests/integration_tests/run_constant_reprocessing/tap_input.json @@ -5,7 +5,8 @@ "depcode": { "codename": "serpent", "template_input_file_path": "tap_template.ini", - "geo_file_paths": ["tap_geometry_base.ini"] + "geo_file_paths": ["tap_geometry_base.ini"], + "zaid_convention": "serpent" }, "simulation": { "sim_name": "tap_constant_reprocessing" diff --git a/tests/integration_tests/run_no_reprocessing/test_input.json b/tests/integration_tests/run_no_reprocessing/test_input.json index 31e0ac209..dbd0e3732 100644 --- a/tests/integration_tests/run_no_reprocessing/test_input.json +++ b/tests/integration_tests/run_no_reprocessing/test_input.json @@ -5,7 +5,8 @@ "depcode": { "codename": "serpent", "template_input_file_path": "test_input.ini", - "geo_file_paths": ["../../serpent_data/tap_geometry_base.ini"] + "geo_file_paths": ["../../serpent_data/tap_geometry_base.ini"], + "zaid_convention": "serpent" }, "simulation": { "sim_name": "test_no_reprocessing", diff --git a/tests/serpent_data/tap_input.json b/tests/serpent_data/tap_input.json index 41525d03e..bccee399d 100644 --- a/tests/serpent_data/tap_input.json +++ b/tests/serpent_data/tap_input.json @@ -5,7 +5,8 @@ "depcode": { "codename": "serpent", "template_input_file_path": "tap_template.ini", - "geo_file_paths": ["tap_geometry_base.ini"] + "geo_file_paths": ["tap_geometry_base.ini"], + "zaid_convention": "serpent" }, "simulation": { "sim_name": "tap_test_simulation_serpent" diff --git a/tests/serpent_data/tap_reference_mcnp.out b/tests/serpent_data/tap_reference_mcnp.out new file mode 100644 index 000000000..040a7c2b4 --- /dev/null +++ b/tests/serpent_data/tap_reference_mcnp.out @@ -0,0 +1,136448 @@ + + --- Table 1: Summary of nuclide data: + + Data for 1657 nuclides included in calculation: + + - 314 Transport nuclides + - No dosimetry nuclides + - 1343 Decay nuclides + - 7339 reaction channels + - 3577 special reactions + - 2521 transmutation reactions + - 1903 transmutation branch reactions + - 1930 decay reactions + - 120 decay branch reactions + - All reaction linked to target + + Columns: + + 1. Index + 2. Level (first occurence in transmutation paths) + 3. Name (nuclide identifier data) + 4. Library ID + 5. Primary data type: TRA = transport + DOS = dosimetry + SAB = thermal scattering + DEC = only decay data + STR = only structural data (mass) + PHO = photon interaction data + 6. Z (atomic number) + 7. A (isotope number) + 8. I (isomeric state) + 9. Atomic weight + 10. Temperature (in Kelvin) + 11. Decay constant (1/s) + 12. Flags: I - nuclide is present in initial composition + B - nuclide is involved in burnup calculation + A - nuclide is produced as activation product + D - nuclide is produced as decay product + F - nuclide is produced as fission product + B - nuclide is produced in decay or transmutation branching + T - nuclide has neutron transport cross section data + S - nuclide has S(a,b) data + I - nuclide has isomeric branching reactions + F - nuclide is fissile + P - nuclide is a delayed neutron precursor + D - nuclide has delayed neutron data + U - nuclide has uses ures ptable data + T - nuclide cross sections are adjusted by TMS + D - nuclide has dosimetry cross section data + R - nuclide has radioactive decay data + N - nuclide has neutron-induced fission yield data + S - nuclide has spontaneous fission yield data + P - nuclide has photon transport cross section data + T - nuclide has supplementary transmutation cross section data + + 1 0 1001.82c 82c TRA 1 1 0 1.00783 900.0 stable IBA-FBT--------R---- hydrogen (H-1) + 2 0 1001.82s 82s TRA 1 1 0 1.00783 900.0 stable IBA-FBTS-------R---- hydrogen (H-1) + 3 0 1002.82c 82c TRA 1 2 0 2.01410 900.0 stable IBA-FBT--------R---- deuterium (H-2) + 4 0 1003.82c 82c TRA 1 3 0 3.01605 900.0 1.78139E-09 IBA-FBT--------R---- tritium (H-3) + 5 0 2003.82c 82c TRA 2 3 0 3.01493 900.0 stable IB-D-BT--------R---- helium 3 (He-3) + 6 0 2004.82c 82c TRA 2 4 0 4.00258 900.0 stable IBADFBT--------R---- helium 4 (He-4) + 7 0 3006.82c 82c TRA 3 6 0 6.01507 900.0 stable IBAD--T--------R---- lithium 6 (Li-6) + 8 0 3007.82c 82c TRA 3 7 0 7.01600 900.0 stable IBADF-T--------R---- lithium 7 (Li-7) + 9 0 4009.82c 82c TRA 4 9 0 9.01220 900.0 stable IBADF-T--------R---- beryllium 9 (Be-9) + 10 0 5010.82c 82c TRA 5 10 0 10.01294 900.0 stable IBADF-T--------R---- boron 10 (B-10) + 11 0 5011.82c 82c TRA 5 11 0 11.00928 900.0 stable IBAD--T--------R---- boron 11 (B-11) + 12 0 6000.82c 82c TRA 6 0 0 12.00110 900.0 N/A I-----T------------- natural carbon (C-nat) + 13 0 7014.82c 82c TRA 7 14 0 14.00307 900.0 stable IBAD--T--------R---- nitrogen 14 (N-14) + 14 0 7015.82c 82c TRA 7 15 0 14.99986 900.0 stable IBAD--T--------R---- nitrogen 15 (N-15) + 15 0 8016.82c 82c TRA 8 16 0 15.99492 900.0 stable IBAD--T--------R---- oxygen 16 (O-16) + 16 0 8017.82c 82c TRA 8 17 0 16.99913 900.0 stable IBAD--T--------R---- oxygen 17 (O-17) + 17 0 9019.82c 82c TRA 9 19 0 18.99820 900.0 stable IBAD--T--------R---- fluorine 19 (F-19) + 18 0 11022.82c 82c TRA 11 22 0 21.99444 900.0 8.43866E-09 IBA---T--------R---- sodium 22 (Na-22) + 19 0 11023.82c 82c TRA 11 23 0 22.98980 900.0 stable IBAD--T-I------R---- sodium 23 (Na-23) + 20 0 12024.82c 82c TRA 12 24 0 23.98504 900.0 stable IBAD--T--------R---- magnesium 24 (Mg-24) + 21 0 12025.82c 82c TRA 12 25 0 24.98584 900.0 stable IBAD--T--------R---- magnesium 25 (Mg-25) + 22 0 12026.82c 82c TRA 12 26 0 25.98260 900.0 stable IBAD--T--------R---- magnesium 26 (Mg-26) + 23 0 13027.82c 82c TRA 13 27 0 26.98154 900.0 stable IBAD--T--------R---- aluminum 27 (Al-27) + 24 0 14028.82c 82c TRA 14 28 0 27.97734 900.0 stable IBAD--T--------R---- silicon 28 (Si-28) + 25 0 14029.82c 82c TRA 14 29 0 28.97652 900.0 stable IBAD--T--------R---- silicon 29 (Si-29) + 26 0 14030.82c 82c TRA 14 30 0 30.00002 900.0 stable IBAD--T--------R---- silicon 30 (Si-30) + 27 0 15031.82c 82c TRA 15 31 0 30.97378 900.0 stable IBAD--T--------R---- phosphorus 31 (P-31) + 28 0 16034.82c 82c TRA 16 34 0 33.96800 900.0 stable IBAD--T--------R---- sulfur 34 (S-34) + 29 0 16036.82c 82c TRA 16 36 0 35.96697 900.0 stable IBAD--T--------R---- sulfur 36 (S-36) + 30 0 17035.82c 82c TRA 17 35 0 34.96885 900.0 stable IBAD--T--------R---- chlorine 35 (Cl-35) + 31 0 17037.82c 82c TRA 17 37 0 36.96586 900.0 stable IBAD--T-I------R---- chlorine 37 (Cl-37) + 32 0 18038.82c 82c TRA 18 38 0 37.96272 900.0 stable IBAD--T--------R---- argon 38 (Ar-38) + 33 0 18040.82c 82c TRA 18 40 0 39.96240 900.0 stable IBAD--T--------R---- argon 40 (Ar-40) + 34 0 19039.82c 82c TRA 19 39 0 38.96402 900.0 stable IBAD--T--------R---- potassium 39 (K-39) + 35 0 19040.82c 82c TRA 19 40 0 39.96401 900.0 1.75664E-17 IBA---T--------R---- potassium 40 (K-40) + 36 0 19041.82c 82c TRA 19 41 0 40.96198 900.0 stable IBAD--T--------R---- potassium 41 (K-41) + 37 0 20042.82c 82c TRA 20 42 0 41.95863 900.0 stable IBAD--T--------R---- calcium 42 (Ca-42) + 38 0 20043.82c 82c TRA 20 43 0 42.95877 900.0 stable IBAD--T--------R---- calcium 43 (Ca-43) + 39 0 20044.82c 82c TRA 20 44 0 43.95548 900.0 stable IBAD--T--------R---- calcium 44 (Ca-44) + 40 0 21045.82c 82c TRA 21 45 0 44.95591 900.0 stable IBAD--T-I------R---- scandium 45 (Sc-45) + 41 0 22046.82c 82c TRA 22 46 0 45.95276 900.0 stable IBAD--T--------R---- titanium 46 (Ti-46) + 42 0 22047.82c 82c TRA 22 47 0 46.95134 900.0 stable IBAD--T--------R---- titanium 47 (Ti-47) + 43 0 22048.82c 82c TRA 22 48 0 47.94795 900.0 stable IBAD--T--------R---- titanium 48 (Ti-48) + 44 0 22049.82c 82c TRA 22 49 0 48.94788 900.0 stable IBAD--T--------R---- titanium 49 (Ti-49) + 45 0 22050.82c 82c TRA 22 50 0 49.94480 900.0 stable IBADF-T--------R---- titanium 50 (Ti-50) + 46 0 23000.82c 82c TRA 23 0 0 50.94161 900.0 N/A I-----T------------- natural vanadium (V-nat) + 47 0 24050.82c 82c TRA 24 50 0 49.94606 900.0 1.22025E-25 IBAD--T--------R---- chromium 50 (Cr-50) + 48 0 24052.82c 82c TRA 24 52 0 51.93999 900.0 stable IBADF-T--------R---- chromium 52 (Cr-52) + 49 0 24053.82c 82c TRA 24 53 0 52.94079 900.0 stable IBADF-T--------R---- chromium 53 (Cr-53) + 50 0 24054.82c 82c TRA 24 54 0 53.93937 900.0 stable IBADF-T--------R---- chromium 54 (Cr-54) + 51 0 25055.82c 82c TRA 25 55 0 54.93805 900.0 stable IBADF-T--------R---- manganese 55 (Mn-55) + 52 0 26054.82c 82c TRA 26 54 0 53.93962 900.0 stable IBA---T--------R---- iron 54 (Fe-54) + 53 0 26056.82c 82c TRA 26 56 0 55.93491 900.0 stable IBADF-T--------R---- iron 56 (Fe-56) + 54 0 26057.82c 82c TRA 26 57 0 56.93541 900.0 stable IBADF-T--------R---- iron 57 (Fe-57) + 55 0 26058.82c 82c TRA 26 58 0 57.93329 900.0 stable IBADF-T--------R---- iron 58 (Fe-58) + 56 0 27059.82c 82c TRA 27 59 0 58.93317 900.0 stable IBADF-T-I------R---- cobalt 59 (Co-59) + 57 0 28058.82c 82c TRA 28 58 0 57.93570 900.0 3.13779E-29 IBA---T--------R---- nickel 58 (Ni-58) + 58 0 28059.82c 82c TRA 28 59 0 58.93438 900.0 2.89012E-13 IBA---T--------R---- nickel 59 (Ni-59) + 59 0 28060.82c 82c TRA 28 60 0 59.93079 900.0 stable IBAD--T--------R---- nickel 60 (Ni-60) + 60 0 28061.82c 82c TRA 28 61 0 60.93143 900.0 stable IBADF-T--------R---- nickel 61 (Ni-61) + 61 0 28062.82c 82c TRA 28 62 0 61.92799 900.0 stable IBADF-T--------R---- nickel 62 (Ni-62) + 62 0 28064.82c 82c TRA 28 64 0 63.92818 900.0 stable IBADF-T--------R---- nickel 64 (Ni-64) + 63 0 29065.82c 82c TRA 29 65 0 64.92776 900.0 stable IBADF-T--------R---- copper 65 (Cu-65) + 64 0 32070.82c 82c TRA 32 70 0 69.92426 900.0 stable IBADF-T--------R---- germanium 70 (Ge-70) + 65 0 32072.82c 82c TRA 32 72 0 71.92209 900.0 stable IBADF-T-I------R---- germanium 72 (Ge-72) + 66 0 32073.82c 82c TRA 32 73 0 72.92347 900.0 stable IBADF-T--------R---- germanium 73 (Ge-73) + 67 0 32074.82c 82c TRA 32 74 0 73.92118 900.0 stable IBADF-T-I------R---- germanium 74 (Ge-74) + 68 0 32076.82c 82c TRA 32 76 0 75.92140 900.0 1.39016E-29 IBADF-T-I------R---- germanium 76 (Ge-76) + 69 0 33075.82c 82c TRA 33 75 0 74.92162 900.0 stable IBADF-T--------R---- arsenic 75 (As-75) + 70 0 34076.82c 82c TRA 34 76 0 75.91919 900.0 stable IB-DF-T-I------R---- selenium 76 (Se-76) + 71 0 34077.82c 82c TRA 34 77 0 76.91988 900.0 stable IBADF-T--------R---- selenium 77 (Se-77) + 72 0 34078.82c 82c TRA 34 78 0 77.91735 900.0 stable IBADF-T-I------R---- selenium 78 (Se-78) + 73 0 34079.82c 82c TRA 34 79 0 78.91845 900.0 5.82624E-14 IBADF-T--------R---- selenium 79 (Se-79) + 74 0 34080.82c 82c TRA 34 80 0 79.91652 900.0 stable IBADF-T-I------R---- selenium 80 (Se-80) + 75 0 34082.82c 82c TRA 34 82 0 81.91671 900.0 2.26443E-28 IBADF-T-I------R---- selenium 82 (Se-82) + 76 0 35079.82c 82c TRA 35 79 0 78.91835 900.0 stable IBADF-T-I------R---- bromine 79 (Br-79) + 77 0 35081.82c 82c TRA 35 81 0 80.91631 900.0 stable IBADF-T-I------R---- bromine 81 (Br-81) + 78 0 36080.82c 82c TRA 36 80 0 79.91632 900.0 stable IB-DF-T-I------R---- krypton 80 (Kr-80) + 79 0 36082.82c 82c TRA 36 82 0 81.91348 900.0 stable IBADF-T-I------R---- krypton 82 (Kr-82) + 80 0 36083.82c 82c TRA 36 83 0 82.91428 900.0 stable IBADF-T--------R---- krypton 83 (Kr-83) + 81 0 36084.82c 82c TRA 36 84 0 83.91144 900.0 stable IBADF-T-I------R---- krypton 84 (Kr-84) + 82 0 36085.82c 82c TRA 36 85 0 84.91254 900.0 2.04287E-09 IBADF-T--------R---- krypton 85 (Kr-85) + 83 0 36086.82c 82c TRA 36 86 0 85.91062 900.0 stable IBADF-T--------R---- krypton 86 (Kr-86) + 84 0 37085.82c 82c TRA 37 85 0 84.91184 900.0 stable IBADF-T-I------R---- rubidium 85 (Rb-85) + 85 0 37086.82c 82c TRA 37 86 0 85.91122 900.0 4.30393E-07 IBADF-T--------R---- rubidium 86 (Rb-86) + 86 0 37087.82c 82c TRA 37 87 0 86.90920 900.0 4.56652E-19 IBADF-T--------R---- rubidium 87 (Rb-87) + 87 0 38086.82c 82c TRA 38 86 0 85.90931 900.0 stable IBADF-T-I------R---- strontium 86 (Sr-86) + 88 0 38087.82c 82c TRA 38 87 0 86.90889 900.0 stable IBADF-T--------R---- strontium 87 (Sr-87) + 89 0 38088.82c 82c TRA 38 88 0 87.90566 900.0 stable IBADF-T--------R---- strontium 88 (Sr-88) + 90 0 38089.82c 82c TRA 38 89 0 88.90746 900.0 1.58642E-07 IBADF-T--------R---- strontium 89 (Sr-89) + 91 0 38090.82c 82c TRA 38 90 0 89.90775 900.0 7.62673E-10 IBADF-T--------R---- strontium 90 (Sr-90) + 92 0 39089.82c 82c TRA 39 89 0 88.90585 900.0 stable IBADF-T-I------R---- yttrium 89 (Y-89) + 93 0 39090.82c 82c TRA 39 90 0 89.90716 900.0 3.00845E-06 IBADF-T-I------R---- yttrium 90 (Y-90) + 94 0 39091.82c 82c TRA 39 91 0 90.90735 900.0 1.37114E-07 IBADF-T--------R---- yttrium 91 (Y-91) + 95 0 40090.82c 82c TRA 40 90 0 89.90473 900.0 stable IBADF-T--------R---- zirconium 90 (Zr-90) + 96 0 40091.82c 82c TRA 40 91 0 90.90563 900.0 stable IBADF-T--------R---- zirconium 91 (Zr-91) + 97 0 40092.82c 82c TRA 40 92 0 91.90501 900.0 stable IBADF-T--------R---- zirconium 92 (Zr-92) + 98 0 40093.82c 82c TRA 40 93 0 92.90652 900.0 1.36428E-14 IBADF-T--------R---- zirconium 93 (Zr-93) + 99 0 40094.82c 82c TRA 40 94 0 93.90631 900.0 1.99682E-25 IBADF-T--------R---- zirconium 94 (Zr-94) + 100 0 40095.82c 82c TRA 40 95 0 94.90801 900.0 1.25290E-07 IBADF-T--------R---- zirconium 95 (Zr-95) + 101 0 40096.82c 82c TRA 40 96 0 95.90830 900.0 1.09825E-27 IBADF-T--------R---- zirconium 96 (Zr-96) + 102 0 41093.82c 82c TRA 41 93 0 92.90319 900.0 stable IBADF-T-I------R---- niobium 93 (Nb-93) + 103 0 41094.82c 82c TRA 41 94 0 93.90731 900.0 1.09898E-12 IBADF-T-I------R---- niobium 94 (Nb-94) + 104 0 41095.82c 82c TRA 41 95 0 94.90680 900.0 2.29274E-07 IBADF-T--------R---- niobium 95 (Nb-95) + 105 0 42092.82c 82c TRA 42 92 0 91.90683 900.0 1.15603E-28 IBA---T-I------R---- molybdenum 92 (Mo-92) + 106 0 42094.82c 82c TRA 42 94 0 93.90510 900.0 stable IBAD--T--------R---- molybdenum 94 (Mo-94) + 107 0 42095.82c 82c TRA 42 95 0 94.90589 900.0 stable IBADF-T--------R---- molybdenum 95 (Mo-95) + 108 0 42096.82c 82c TRA 42 96 0 95.90467 900.0 stable IBADF-T--------R---- molybdenum 96 (Mo-96) + 109 0 42097.82c 82c TRA 42 97 0 96.90597 900.0 stable IBADF-T--------R---- molybdenum 97 (Mo-97) + 110 0 42098.82c 82c TRA 42 98 0 97.90536 900.0 2.19650E-22 IBADF-T--------R---- molybdenum 98 (Mo-98) + 111 0 42099.82c 82c TRA 42 99 0 98.90767 900.0 2.91951E-06 IBADF-T--------R---- molybdenum 99 (Mo-99) + 112 0 42100.82c 82c TRA 42 100 0 99.90746 900.0 3.00890E-27 IBADF-T--------R---- molybdenum 100 (Mo-100) + 113 0 43099.82c 82c TRA 43 99 0 98.90627 900.0 1.03853E-13 IBADF-T--------R---- technetium 99 (Tc-99) + 114 0 44100.82c 82c TRA 44 100 0 99.90423 900.0 stable IBADF-T--------R---- ruthenium 100 (Ru-100) + 115 0 44101.82c 82c TRA 44 101 0 100.90583 900.0 stable IBADF-T--------R---- ruthenium 101 (Ru-101) + 116 0 44102.82c 82c TRA 44 102 0 101.90542 900.0 stable IBADF-T--------R---- ruthenium 102 (Ru-102) + 117 0 44103.82c 82c TRA 44 103 0 102.90400 900.0 2.04344E-07 IBADF-T--------R---- ruthenium 103 (Ru-103) + 118 0 44104.82c 82c TRA 44 104 0 103.90258 900.0 stable IBADF-T--------R---- ruthenium 104 (Ru-104) + 119 0 44105.82c 82c TRA 44 105 0 104.91124 900.0 4.33651E-05 IBADF-T--------R---- ruthenium 105 (Ru-105) + 120 0 44106.82c 82c TRA 44 106 0 105.90780 900.0 2.15950E-08 IBADF-T--------R---- ruthenium 106 (Ru-106) + 121 0 45103.82c 82c TRA 45 103 0 102.90551 900.0 stable IBADF-T-I------R---- rhodium 103 (Rh-103) + 122 0 45105.82c 82c TRA 45 105 0 104.90116 900.0 5.44516E-06 IBADF-T-I------R---- rhodium 105 (Rh-105) + 123 0 46105.82c 82c TRA 46 105 0 104.90519 900.0 stable IBADF-T--------R---- palladium 105 (Pd-105) + 124 0 46106.82c 82c TRA 46 106 0 105.90347 900.0 stable IBADF-T-I------R---- palladium 106 (Pd-106) + 125 0 46107.82c 82c TRA 46 107 0 106.90537 900.0 3.37923E-15 IBADF-T--------R---- palladium 107 (Pd-107) + 126 0 46108.82c 82c TRA 46 108 0 107.90385 900.0 stable IBADF-T-I------R---- palladium 108 (Pd-108) + 127 0 46110.82c 82c TRA 46 110 0 109.90514 900.0 3.66082E-26 IBADF-T-I------R---- palladium 110 (Pd-110) + 128 0 47109.82c 82c TRA 47 109 0 108.90455 900.0 stable IBADF-T-I------R---- silver 109 (Ag-109) + 129 0 47510.82c 82c TRA 47 110 1 109.90615 900.0 3.21184E-08 IBA-F-T--------R---- silver 110m (Ag-110m) + 130 0 47111.82c 82c TRA 47 111 0 110.90574 900.0 1.07685E-06 IBADF-T--------R---- silver 111 (Ag-111) + 131 0 48110.82c 82c TRA 48 110 0 109.90313 900.0 stable IBADF-T-I------R---- cadmium 110 (Cd-110) + 132 0 48111.82c 82c TRA 48 111 0 110.90473 900.0 stable IBADF-T--------R---- cadmium 111 (Cd-111) + 133 0 48112.82c 82c TRA 48 112 0 111.90331 900.0 stable IBADF-T-I------R---- cadmium 112 (Cd-112) + 134 0 48113.82c 82c TRA 48 113 0 112.89987 900.0 2.73196E-24 IBADF-T--------R---- cadmium 113 (Cd-113) + 135 0 48114.82c 82c TRA 48 114 0 113.90349 900.0 2.38750E-25 IBADF-T-I------R---- cadmium 114 (Cd-114) + 136 0 48515.82c 82c TRA 48 115 1 114.90610 900.0 1.80039E-07 IBADF-T--------R---- cadmium 115m (Cd-115m) + 137 0 48116.82c 82c TRA 48 116 0 115.90468 900.0 7.32166E-28 IBADF-T-I------R---- cadmium 116 (Cd-116) + 138 0 49113.82c 82c TRA 49 113 0 112.90390 900.0 stable IBADF-T-I------R---- indium 113 (In-113) + 139 0 49115.82c 82c TRA 49 115 0 114.90409 900.0 4.98072E-23 IBADF-T--------R---- indium 115 (In-115) + 140 0 50115.82c 82c TRA 50 115 0 114.90308 900.0 stable IBADF-T--------R---- tin 115 (Sn-115) + 141 0 50116.82c 82c TRA 50 116 0 115.90166 900.0 stable IBADF-T-I------R---- tin 116 (Sn-116) + 142 0 50117.82c 82c TRA 50 117 0 116.90326 900.0 stable IBADF-T--------R---- tin 117 (Sn-117) + 143 0 50118.82c 82c TRA 50 118 0 117.90184 900.0 stable IBADF-T-I------R---- tin 118 (Sn-118) + 144 0 50119.82c 82c TRA 50 119 0 118.90344 900.0 stable IBADF-T--------R---- tin 119 (Sn-119) + 145 0 50120.82c 82c TRA 50 120 0 119.90202 900.0 stable IBADF-T-I------R---- tin 120 (Sn-120) + 146 0 50122.82c 82c TRA 50 122 0 121.90321 900.0 stable IBADF-T-I------R---- tin 122 (Sn-122) + 147 0 50123.82c 82c TRA 50 123 0 122.90583 900.0 6.20938E-08 IBADF-T--------R---- tin 123 (Sn-123) + 148 0 50124.82c 82c TRA 50 124 0 123.90541 900.0 2.19650E-25 IBADF-T-I------R---- tin 124 (Sn-124) + 149 0 50125.82c 82c TRA 50 125 0 124.90803 900.0 8.32213E-07 IBADF-T--------R---- tin 125 (Sn-125) + 150 0 50126.82c 82c TRA 50 126 0 125.90761 900.0 9.54999E-14 IBADF-T-I------R---- tin 126 (Sn-126) + 151 0 51121.82c 82c TRA 51 121 0 120.90363 900.0 stable IBADF-T-I------R---- antimony 121 (Sb-121) + 152 0 51123.82c 82c TRA 51 123 0 122.90381 900.0 stable IBADF-T--------R---- antimony 123 (Sb-123) + 153 0 51124.82c 82c TRA 51 124 0 123.90642 900.0 1.33247E-07 IBADF-T--------R---- antimony 124 (Sb-124) + 154 0 51125.82c 82c TRA 51 125 0 124.90500 900.0 7.96250E-09 IBADF-T--------R---- antimony 125 (Sb-125) + 155 0 51126.82c 82c TRA 51 126 0 125.90761 900.0 6.46460E-07 IBADF-T--------R---- antimony 126 (Sb-126) + 156 0 52120.82c 82c TRA 52 120 0 119.90000 900.0 stable IB--F-T-I------R---- tellurium 120 (Te-120) + 157 0 52122.82c 82c TRA 52 122 0 121.90321 900.0 stable IB-DF-T-I------R---- tellurium 122 (Te-122) + 158 0 52123.82c 82c TRA 52 123 0 122.90482 900.0 2.38750E-25 IBADF-T--------R---- tellurium 123 (Te-123) + 159 0 52124.82c 82c TRA 52 124 0 123.90340 900.0 stable IBADF-T-I------R---- tellurium 124 (Te-124) + 160 0 52125.82c 82c TRA 52 125 0 124.90399 900.0 stable IBADF-T--------R---- tellurium 125 (Te-125) + 161 0 52126.82c 82c TRA 52 126 0 125.90358 900.0 stable IBADF-T-I------R---- tellurium 126 (Te-126) + 162 0 52527.82c 82c TRA 52 127 1 126.90518 900.0 7.56130E-08 IBADF-T--------R---- tellurium 127m (Te-127m) + 163 0 52128.82c 82c TRA 52 128 0 127.90477 900.0 9.98409E-33 IBADF-T-I------R---- tellurium 128 (Te-128) + 164 0 52529.82c 82c TRA 52 129 1 128.90738 900.0 2.38766E-07 IBADF-T--------R---- tellurium 129m (Te-129m) + 165 0 52130.82c 82c TRA 52 130 0 129.90596 900.0 2.78037E-29 IBADF-T-I------R---- tellurium 130 (Te-130) + 166 0 52132.82c 82c TRA 52 132 0 131.90816 900.0 2.48376E-06 IBADF-T-I------R---- tellurium 132 (Te-132) + 167 0 53127.82c 82c TRA 53 127 0 126.90448 900.0 stable IBADF-T--------R---- iodine 127 (I-127) + 168 0 53129.82c 82c TRA 53 129 0 128.90496 900.0 1.36428E-15 IBADF-T-I------R---- iodine 129 (I-129) + 169 0 53130.82c 82c TRA 53 130 0 129.90697 900.0 1.55777E-05 IBADF-T--------R---- iodine 130 (I-130) + 170 0 53131.82c 82c TRA 53 131 0 130.90555 900.0 9.99905E-07 IBADF-T-I------R---- iodine 131 (I-131) + 171 0 53135.82c 82c TRA 53 135 0 134.90894 900.0 2.92615E-05 IBADF-T--------R---- iodine 135 (I-135) + 172 0 54128.82c 82c TRA 54 128 0 127.90275 900.0 stable IBADF-T-I------R---- xenon 128 (Xe-128) + 173 0 54129.82c 82c TRA 54 129 0 128.90536 900.0 stable IBADF-T--------R---- xenon 129 (Xe-129) + 174 0 54130.82c 82c TRA 54 130 0 129.90394 900.0 stable IBADF-T-I------R---- xenon 130 (Xe-130) + 175 0 54131.82c 82c TRA 54 131 0 130.90555 900.0 stable IBADF-T--------R---- xenon 131 (Xe-131) + 176 0 54132.82c 82c TRA 54 132 0 131.90312 900.0 stable IBADF-T-I------R---- xenon 132 (Xe-132) + 177 0 54133.82c 82c TRA 54 133 0 132.90573 900.0 1.52886E-06 IBADF-T-I------R---- xenon 133 (Xe-133) + 178 0 54134.82c 82c TRA 54 134 0 133.91036 900.0 1.99682E-24 IBADF-T-I------R---- xenon 134 (Xe-134) + 179 0 54135.82c 82c TRA 54 135 0 134.90692 900.0 2.10657E-05 IBADF-T--------R---- xenon 135 (Xe-135) + 180 0 54136.82c 82c TRA 54 136 0 135.90752 900.0 2.19650E-30 IBADF-T--------R---- xenon 136 (Xe-136) + 181 0 55133.82c 82c TRA 55 133 0 132.90573 900.0 stable IBADF-T-I------R---- cesium 133 (Cs-133) + 182 0 55134.82c 82c TRA 55 134 0 133.90733 900.0 1.06399E-08 IBADF-T-I------R---- cesium 134 (Cs-134) + 183 0 55135.82c 82c TRA 55 135 0 134.90591 900.0 9.54999E-15 IBADF-T-I------R---- cesium 135 (Cs-135) + 184 0 55136.82c 82c TRA 55 136 0 135.90752 900.0 6.15698E-07 IBADF-T--------R---- cesium 136 (Cs-136) + 185 0 55137.82c 82c TRA 55 137 0 136.90711 900.0 7.30947E-10 IBADF-T-I------R---- cesium 137 (Cs-137) + 186 0 56134.82c 82c TRA 56 134 0 133.90431 900.0 stable IBADF-T-I------R---- barium 134 (Ba-134) + 187 0 56135.82c 82c TRA 56 135 0 134.90591 900.0 stable IBADF-T-I------R---- barium 135 (Ba-135) + 188 0 56136.82c 82c TRA 56 136 0 135.90449 900.0 stable IBADF-T-I------R---- barium 136 (Ba-136) + 189 0 56137.82c 82c TRA 56 137 0 136.90610 900.0 stable IBADF-T--------R---- barium 137 (Ba-137) + 190 0 56138.82c 82c TRA 56 138 0 137.90467 900.0 stable IBADF-T--------R---- barium 138 (Ba-138) + 191 0 56140.82c 82c TRA 56 140 0 139.90990 900.0 6.29070E-07 IBADF-T--------R---- barium 140 (Ba-140) + 192 0 57138.82c 82c TRA 57 138 0 137.90669 900.0 2.12017E-19 IBA-F-T--------R---- lanthanum 138 (La-138) + 193 0 57139.82c 82c TRA 57 139 0 138.90325 900.0 stable IBADF-T--------R---- lanthanum 139 (La-139) + 194 0 57140.82c 82c TRA 57 140 0 139.90990 900.0 4.77937E-06 IBADF-T--------R---- lanthanum 140 (La-140) + 195 0 58140.82c 82c TRA 58 140 0 139.90587 900.0 stable IBADF-T--------R---- cerium 140 (Ce-140) + 196 0 58141.82c 82c TRA 58 141 0 140.91050 900.0 2.46824E-07 IBADF-T--------R---- cerium 141 (Ce-141) + 197 0 58142.82c 82c TRA 58 142 0 141.90907 900.0 4.39299E-25 IBADF-T--------R---- cerium 142 (Ce-142) + 198 0 58143.82c 82c TRA 58 143 0 142.91270 900.0 5.82770E-06 IBADF-T--------R---- cerium 143 (Ce-143) + 199 0 58144.82c 82c TRA 58 144 0 143.91430 900.0 2.81601E-08 IBADF-T--------R---- cerium 144 (Ce-144) + 200 0 59141.82c 82c TRA 59 141 0 140.90747 900.0 stable IBADF-T-I------R---- praseodymium 141 (Pr-141) + 201 0 59142.82c 82c TRA 59 142 0 141.91008 900.0 1.00701E-05 IBADF-T--------R---- praseodymium 142 (Pr-142) + 202 0 59143.82c 82c TRA 59 143 0 142.91068 900.0 5.91635E-07 IBADF-T-I------R---- praseodymium 143 (Pr-143) + 203 0 60144.82c 82c TRA 60 144 0 143.91027 900.0 9.59169E-24 IBADF-T--------R---- neodymium 144 (Nd-144) + 204 0 60145.82c 82c TRA 60 145 0 144.91288 900.0 stable IBADF-T--------R---- neodymium 145 (Nd-145) + 205 0 60146.82c 82c TRA 60 146 0 145.91347 900.0 stable IBADF-T--------R---- neodymium 146 (Nd-146) + 206 0 60147.82c 82c TRA 60 147 0 146.91609 900.0 7.27998E-07 IBADF-T--------R---- neodymium 147 (Nd-147) + 207 0 60148.82c 82c TRA 60 148 0 147.91668 900.0 7.32166E-27 IBADF-T--------R---- neodymium 148 (Nd-148) + 208 0 60150.82c 82c TRA 60 150 0 149.92090 900.0 3.27836E-27 IBADF-T--------R---- neodymium 150 (Nd-150) + 209 0 61147.82c 82c TRA 61 147 0 146.91508 900.0 8.37701E-09 IBADF-T-I------R---- promethium 147 (Pm-147) + 210 0 61148.82c 82c TRA 61 148 0 147.91668 900.0 1.49395E-06 IBADF-T--------R---- promethium 148 (Pm-148) + 211 0 61548.82c 82c TRA 61 148 1 147.92072 900.0 1.94297E-07 IBA-F-T--------R---- promethium 148m (Pm-148m) + 212 0 61149.82c 82c TRA 61 149 0 148.91829 900.0 3.62737E-06 IBADF-T--------R---- promethium 149 (Pm-149) + 213 0 61151.82c 82c TRA 61 151 0 150.92150 900.0 6.77961E-06 IBADF-T--------R---- promethium 151 (Pm-151) + 214 0 62147.82c 82c TRA 62 147 0 146.91508 900.0 2.05280E-19 IBAD--T--------R---- samarium 147 (Sm-147) + 215 0 62148.82c 82c TRA 62 148 0 147.91467 900.0 3.13786E-24 IBAD--T--------R---- samarium 148 (Sm-148) + 216 0 62149.82c 82c TRA 62 149 0 148.91728 900.0 1.09823E-23 IBADF-T--------R---- samarium 149 (Sm-149) + 217 0 62150.82c 82c TRA 62 150 0 149.91687 900.0 stable IBADF-T--------R---- samarium 150 (Sm-150) + 218 0 62151.82c 82c TRA 62 151 0 150.91645 900.0 2.31943E-10 IBADF-T--------R---- samarium 151 (Sm-151) + 219 0 62152.82c 82c TRA 62 152 0 151.92007 900.0 stable IBADF-T--------R---- samarium 152 (Sm-152) + 220 0 62153.82c 82c TRA 62 153 0 152.92168 900.0 4.15987E-06 IBADF-T--------R---- samarium 153 (Sm-153) + 221 0 62154.82c 82c TRA 62 154 0 153.92227 900.0 stable IBADF-T--------R---- samarium 154 (Sm-154) + 222 0 63151.82c 82c TRA 63 151 0 150.91948 900.0 stable IBADF-T--------R---- europium 151 (Eu-151) + 223 0 63152.82c 82c TRA 63 152 0 151.92209 900.0 1.62439E-09 IBADF-T--------R---- europium 152 (Eu-152) + 224 0 63153.82c 82c TRA 63 153 0 152.92168 900.0 stable IBADF-T-I------R---- europium 153 (Eu-153) + 225 0 63154.82c 82c TRA 63 154 0 153.92227 900.0 2.55377E-09 IBADF-T--------R---- europium 154 (Eu-154) + 226 0 63155.82c 82c TRA 63 155 0 154.92287 900.0 4.62129E-09 IBADF-T--------R---- europium 155 (Eu-155) + 227 0 63156.82c 82c TRA 63 156 0 155.92548 900.0 5.28144E-07 IBADF-T--------R---- europium 156 (Eu-156) + 228 0 63157.82c 82c TRA 63 157 0 156.92507 900.0 1.26839E-05 IBADF-T--------R---- europium 157 (Eu-157) + 229 0 64152.82c 82c TRA 64 152 0 151.92007 900.0 2.03379E-22 IB-D--T--------R---- gadolinium 152 (Gd-152) + 230 0 64154.82c 82c TRA 64 154 0 153.92127 900.0 stable IB-DF-T--------R---- gadolinium 154 (Gd-154) + 231 0 64155.82c 82c TRA 64 155 0 154.92287 900.0 stable IBADF-T--------R---- gadolinium 155 (Gd-155) + 232 0 64156.82c 82c TRA 64 156 0 155.92205 900.0 stable IBADF-T--------R---- gadolinium 156 (Gd-156) + 233 0 64157.82c 82c TRA 64 157 0 156.92406 900.0 stable IBADF-T--------R---- gadolinium 157 (Gd-157) + 234 0 64158.82c 82c TRA 64 158 0 157.92466 900.0 stable IBADF-T--------R---- gadolinium 158 (Gd-158) + 235 0 64160.82c 82c TRA 64 160 0 159.92686 900.0 1.68958E-25 IBADF-T--------R---- gadolinium 160 (Gd-160) + 236 0 65159.82c 82c TRA 65 159 0 158.92525 900.0 stable IBADF-T--------R---- terbium 159 (Tb-159) + 237 0 65160.82c 82c TRA 65 160 0 159.92686 900.0 1.10962E-07 IBA-F-T--------R---- terbium 160 (Tb-160) + 238 0 66160.82c 82c TRA 66 160 0 159.92484 900.0 stable IBADF-T--------R---- dysprosium 160 (Dy-160) + 239 0 66161.82c 82c TRA 66 161 0 160.92644 900.0 stable IBADF-T--------R---- dysprosium 161 (Dy-161) + 240 0 66162.82c 82c TRA 66 162 0 161.92704 900.0 stable IBADF-T--------R---- dysprosium 162 (Dy-162) + 241 0 66163.82c 82c TRA 66 163 0 162.92864 900.0 stable IBADF-T--------R---- dysprosium 163 (Dy-163) + 242 0 66164.82c 82c TRA 66 164 0 163.92823 900.0 stable IBADF-T-I------R---- dysprosium 164 (Dy-164) + 243 0 67165.82c 82c TRA 67 165 0 164.92983 900.0 stable IBADF-T-I------R---- holmium 165 (Ho-165) + 244 0 68164.82c 82c TRA 68 164 0 163.92924 900.0 stable IBADF-T--------R---- erbium 164 (Er-164) + 245 0 68166.82c 82c TRA 68 166 0 165.93043 900.0 stable IBADF-T-I------R---- erbium 166 (Er-166) + 246 0 68167.82c 82c TRA 68 167 0 166.93204 900.0 stable IBADF-T--------R---- erbium 167 (Er-167) + 247 0 68168.82c 82c TRA 68 168 0 167.92960 900.0 stable IBADF-T--------R---- erbium 168 (Er-168) + 248 0 68170.82c 82c TRA 68 170 0 169.93584 900.0 stable IB-DF-T--------R---- erbium 170 (Er-170) + 249 0 71175.82c 82c TRA 71 175 0 174.94083 900.0 stable IBADF-T-I------R---- lutetium 175 (Lu-175) + 250 0 71176.82c 82c TRA 71 176 0 175.94143 900.0 5.84175E-19 IBA-F-T-I------R---- lutetium 176 (Lu-176) + 251 0 72176.82c 82c TRA 72 176 0 175.94042 900.0 stable IBADF-T--------R---- hafnium 176 (Hf-176) + 252 0 72177.82c 82c TRA 72 177 0 176.94001 900.0 stable IBADF-T--------R---- hafnium 177 (Hf-177) + 253 0 72178.82c 82c TRA 72 178 0 177.93959 900.0 stable IBADF-T--------R---- hafnium 178 (Hf-178) + 254 0 72179.82c 82c TRA 72 179 0 178.95028 900.0 stable IBADF-T-I------R---- hafnium 179 (Hf-179) + 255 0 72180.82c 82c TRA 72 180 0 179.94986 900.0 stable IBADF-T--------R---- hafnium 180 (Hf-180) + 256 0 73181.82c 82c TRA 73 181 0 180.94844 900.0 stable IBADF-T--------R---- tantalum 181 (Ta-181) + 257 0 73182.82c 82c TRA 73 182 0 181.95005 900.0 6.99437E-08 IBADF-T--------R---- tantalum 182 (Ta-182) + 258 0 74182.82c 82c TRA 74 182 0 181.94803 900.0 stable IBADF-T-I------R---- tungsten 182 (W-182) + 259 0 74183.82c 82c TRA 74 183 0 182.95064 900.0 1.99677E-25 IBADF-T--------R---- tungsten 183 (W-183) + 260 0 74184.82c 82c TRA 74 184 0 183.95124 900.0 5.49114E-26 IBADF-T-I------R---- tungsten 184 (W-184) + 261 0 74186.82c 82c TRA 74 186 0 185.95445 900.0 3.72279E-26 IB-DF-T--------R---- tungsten 186 (W-186) + 262 0 75185.82c 82c TRA 75 185 0 184.95284 900.0 stable IBADF-T-I------R---- rhenium 185 (Re-185) + 263 0 75187.82c 82c TRA 75 187 0 186.95605 900.0 5.07276E-19 IB-DF-T-I------R---- rhenium 187 (Re-187) + 264 0 77191.82c 82c TRA 77 191 0 190.96045 900.0 stable IBADF-T--------R---- iridium 191 (Ir-191) + 265 0 77193.82c 82c TRA 77 193 0 192.96265 900.0 stable IB-DF-T--------R---- iridium 193 (Ir-193) + 266 0 79197.82c 82c TRA 79 197 0 196.96604 900.0 stable IBADF-T-I------R---- gold 197 (Au-197) + 267 0 80198.82c 82c TRA 80 198 0 197.96664 900.0 stable IBADF-T-I------R---- mercury 198 (Hg-198) + 268 0 80199.82c 82c TRA 80 199 0 198.96824 900.0 stable IBADF-T--------R---- mercury 199 (Hg-199) + 269 0 80200.82c 82c TRA 80 200 0 199.96783 900.0 stable IBADF-T--------R---- mercury 200 (Hg-200) + 270 0 90227.82c 82c TRA 90 227 0 227.02729 900.0 4.28599E-07 IBAD--T--F-D---RN--- thorium 227 (Th-227) + 271 0 90228.82c 82c TRA 90 228 0 228.02889 900.0 1.14844E-08 IBAD--T--F-----RN--- thorium 228 (Th-228) + 272 0 90229.82c 82c TRA 90 229 0 229.03150 900.0 2.99244E-12 IBAD--T--F-D---RN--- thorium 229 (Th-229) + 273 0 90230.82c 82c TRA 90 230 0 230.03613 900.0 2.91307E-13 IBAD--T--F-----RN--- thorium 230 (Th-230) + 274 0 91231.82c 82c TRA 91 231 0 231.03471 900.0 6.70465E-13 IBAD--T--F-D---RN--- protactinium 231 (Pa-231) + 275 0 91232.82c 82c TRA 91 232 0 232.03833 900.0 6.12407E-06 IBAD--T--F-----RN--- protactinium 232 (Pa-232) + 276 0 91233.82c 82c TRA 91 233 0 233.03994 900.0 2.97352E-07 IBAD--T-IF-----RN--- protactinium 233 (Pa-233) + 277 0 92232.82c 82c TRA 92 232 0 232.03329 900.0 3.14678E-10 IBAD--T--F-D---RN--- uranium 232 (U-232) + 278 0 92233.82c 82c TRA 92 233 0 233.03994 900.0 1.37925E-13 IBAD--T--F-D---RN--- uranium 233 (U-233) + 279 0 92234.82c 82c TRA 92 234 0 234.04053 900.0 8.93957E-14 IBAD--T-IF-D---RN--- uranium 234 (U-234) + 280 0 92235.82c 82c TRA 92 235 0 235.04415 900.0 3.12085E-17 IBAD--T--F-D---RN--- uranium 235 (U-235) + 281 0 92236.82c 82c TRA 92 236 0 236.04556 900.0 9.26773E-16 IBAD--T--F-D---RN--- uranium 236 (U-236) + 282 0 92237.82c 82c TRA 92 237 0 237.04878 900.0 1.18870E-06 IBAD--T--F-D---RN--- uranium 237 (U-237) + 283 0 92238.82c 82c TRA 92 238 0 238.05078 900.0 4.91608E-18 IBAD--T--F-D---RN--- uranium 238 (U-238) + 284 0 93235.82c 82c TRA 93 235 0 235.04415 900.0 2.02629E-08 IBAD--T-IF-----RN--- neptunium 235 (Np-235) + 285 0 93236.82c 82c TRA 93 236 0 236.04677 900.0 1.41710E-13 IBAD--T--F-----RN--- neptunium 236 (Np-236) + 286 0 93237.82c 82c TRA 93 237 0 237.04817 900.0 1.02449E-14 IBAD--T--F-D---RN--- neptunium 237 (Np-237) + 287 0 93238.82c 82c TRA 93 238 0 238.05098 900.0 3.81662E-06 IBAD--T--F-D---RN--- neptunium 238 (Np-238) + 288 0 93239.82c 82c TRA 93 239 0 239.05259 900.0 3.40516E-06 IBAD--T-IF-----RN--- neptunium 239 (Np-239) + 289 0 94236.82c 82c TRA 94 236 0 236.04576 900.0 7.68527E-09 IBAD--T-IF-----RN--- plutonium 236 (Pu-236) + 290 0 94237.82c 82c TRA 94 237 0 237.04837 900.0 1.77098E-07 IBAD--T--F-----RN--- plutonium 237 (Pu-237) + 291 0 94238.82c 82c TRA 94 238 0 238.04998 900.0 2.50456E-10 IBAD--T--F-D---RN--- plutonium 238 (Pu-238) + 292 0 94239.82c 82c TRA 94 239 0 239.05198 900.0 9.10900E-13 IBAD--T--F-D---RN--- plutonium 239 (Pu-239) + 293 0 94240.82c 82c TRA 94 240 0 240.05379 900.0 3.34679E-12 IBAD--T--F-D---RN--- plutonium 240 (Pu-240) + 294 0 94241.82c 82c TRA 94 241 0 241.05681 900.0 1.53280E-09 IBAD--T--F-D---RN--- plutonium 241 (Pu-241) + 295 0 94242.82c 82c TRA 94 242 0 242.05841 900.0 5.88071E-14 IBAD--T--F-D---RN--- plutonium 242 (Pu-242) + 296 0 94243.82c 82c TRA 94 243 0 243.06203 900.0 3.88501E-05 IBAD--T--F-----RN--- plutonium 243 (Pu-243) + 297 0 94244.82c 82c TRA 94 244 0 244.06465 900.0 2.74556E-16 IBAD--T--F-----RN--- plutonium 244 (Pu-244) + 298 0 95241.82c 82c TRA 95 241 0 241.05681 900.0 5.07499E-11 IBAD--T-IF-D---RN--- americium 241 (Am-241) + 299 0 95242.82c 82c TRA 95 242 0 242.05942 900.0 1.20263E-05 IBAD--T--F-----RN--- americium 242 (Am-242) + 300 0 95642.82c 82c TRA 95 242 1 242.05942 900.0 1.55777E-10 IBA---T--F-D---RN--- americium 242m (Am-242m) + 301 0 95243.82c 82c TRA 95 243 0 243.06102 900.0 2.98236E-12 IBAD--T-IF-D---RN--- americium 243 (Am-243) + 302 0 95244.82c 82c TRA 95 244 0 244.06465 900.0 1.90635E-05 IBA---T--F-----RN--- americium 244 (Am-244) + 303 0 95644.82c 82c TRA 95 244 1 244.06465 900.0 4.44325E-04 IBA---T--F-----RN--- americium 244m (Am-244m) + 304 0 96240.82c 82c TRA 96 240 0 240.05520 900.0 2.97131E-07 IBA---T--F-----RN--- curium 240 (Cm-240) + 305 0 96241.82c 82c TRA 96 241 0 241.05781 900.0 2.44590E-07 IBA---T--F-----RN--- curium 241 (Cm-241) + 306 0 96242.82c 82c TRA 96 242 0 242.05841 900.0 4.92390E-08 IBAD--T--F-D---RNS-- curium 242 (Cm-242) + 307 0 96243.82c 82c TRA 96 243 0 243.06102 900.0 7.60034E-10 IBA---T--F-D---RN--- curium 243 (Cm-243) + 308 0 96244.82c 82c TRA 96 244 0 244.06263 900.0 1.22025E-09 IBAD--T--F-D---RNS-- curium 244 (Cm-244) + 309 0 96245.82c 82c TRA 96 245 0 245.06524 900.0 2.66242E-12 IBAD--T--F-D---RN--- curium 245 (Cm-245) + 310 0 96246.82c 82c TRA 96 246 0 246.06685 900.0 4.64367E-12 IBAD--T--F-D---RN--- curium 246 (Cm-246) + 311 0 96247.82c 82c TRA 96 247 0 247.06946 900.0 1.37278E-15 IBAD--T--F-----RN--- curium 247 (Cm-247) + 312 0 96248.82c 82c TRA 96 248 0 248.07207 900.0 6.46014E-14 IBA---T--F-D---RN--- curium 248 (Cm-248) + 313 0 96249.82c 82c TRA 96 249 0 249.07569 900.0 1.80085E-04 IBA---T--F-----RN--- curium 249 (Cm-249) + 314 0 96250.82c 82c TRA 96 250 0 250.07831 900.0 2.74556E-12 IBA---T--F-----RN--- curium 250 (Cm-250) + 315 0 20060 82c DEC 2 6 0 6.01889 900.0 8.57749E-01 IBA-F----------R---- helium 6 (He-6) + 316 0 20080 82c DEC 2 8 0 8.03393 900.0 5.68153E+00 IB--F-----P----R---- helium 8 (He-8) + 317 0 30080 82c DEC 3 8 0 8.02249 900.0 8.27145E-01 IBADF----------R---- lithium 8 (Li-8) + 318 0 30090 82c DEC 3 9 0 9.02679 900.0 3.88753E+00 IBA-F-----P----R---- lithium 9 (Li-9) + 319 0 40060 82c DEC 4 6 0 6.01972 900.0 1.38629E+20 IB-D-----------R---- beryllium 6 (Be-6) + 320 0 40080 82c DEC 4 8 0 8.00531 900.0 9.90210E+15 IBADF----------R---- beryllium 8 (Be-8) + 321 0 40100 82c DEC 4 10 0 10.01353 900.0 1.37278E-14 IBA-F----------R---- beryllium 10 (Be-10) + 322 0 40110 82c DEC 4 11 0 11.02168 900.0 5.01917E-02 IBA-F----------R---- beryllium 11 (Be-11) + 323 0 40120 82c DEC 4 12 0 12.02692 900.0 3.25421E+01 IB--F----------R---- beryllium 12 (Be-12) + 324 0 50090 82c DEC 5 9 0 9.01333 900.0 8.66434E+17 IB--F----------R---- boron 9 (B-9) + 325 0 50120 82c DEC 5 12 0 12.01431 900.0 3.43142E+01 IBADF----------R---- boron 12 (B-12) + 326 0 60080 82c DEC 6 8 0 8.03768 900.0 3.46574E+20 IB--F----------R---- carbon 8 (C-8) + 327 0 60120 82c DEC 6 12 0 11.99999 900.0 stable IBAD-----------R---- carbon 12 (C-12) + 328 0 60130 82c DEC 6 13 0 13.00331 900.0 stable IBAD-----------R---- carbon 13 (C-13) + 329 0 60140 82c DEC 6 14 0 14.00319 900.0 3.85352E-12 IBA-F----------R---- carbon 14 (C-14) + 330 0 60150 82c DEC 6 15 0 15.01065 900.0 2.83033E-01 IBA-F----------R---- carbon 15 (C-15) + 331 0 70130 82c DEC 7 13 0 13.00573 900.0 1.15907E-03 IBA------------R---- nitrogen 13 (N-13) + 332 0 70160 82c DEC 7 16 0 16.00610 900.0 9.72156E-02 IBA------------R---- nitrogen 16 (N-16) + 333 0 70170 82c DEC 7 17 0 17.00841 900.0 1.66222E-01 IBA-------P----R---- nitrogen 17 (N-17) + 334 0 80150 82c DEC 8 15 0 15.00308 900.0 5.66019E-03 IBA------------R---- oxygen 15 (O-15) + 335 0 80180 82c DEC 8 18 0 17.99912 900.0 stable IBAD-----------R---- oxygen 18 (O-18) + 336 0 80190 82c DEC 8 19 0 19.00355 900.0 2.57580E-02 IBA------------R---- oxygen 19 (O-19) + 337 0 90180 82c DEC 9 18 0 18.00094 900.0 1.05277E-04 IBA------------R---- fluorine 18 (F-18) + 338 0 90200 82c DEC 9 20 0 20.00001 900.0 6.28420E-02 IBA------------R---- fluorine 20 (F-20) + 339 0 100200 82c DEC 10 20 0 19.99245 900.0 stable IBAD-----------R---- neon 20 (Ne-20) + 340 0 100210 82c DEC 10 21 0 20.99385 900.0 stable IBADF----------R---- neon 21 (Ne-21) + 341 0 100220 82c DEC 10 22 0 21.99142 900.0 stable IBAD-----------R---- neon 22 (Ne-22) + 342 0 100230 82c DEC 10 23 0 22.99443 900.0 1.86330E-02 IBA------------R---- neon 23 (Ne-23) + 343 0 110210 82c DEC 11 21 0 20.99768 900.0 3.08202E-02 IBA------------R---- sodium 21 (Na-21) + 344 0 110240 82c DEC 11 24 0 23.99100 900.0 1.28721E-05 IBAD-----------R---- sodium 24 (Na-24) + 345 0 110241 82c DEC 11 24 1 23.99100 900.0 3.43142E+01 IBA------------R---- sodium 24m (Na-24m) + 346 0 110250 82c DEC 11 25 0 24.98998 900.0 1.16300E-02 IBA------------R---- sodium 25 (Na-25) + 347 0 110260 82c DEC 11 26 0 25.99259 900.0 6.41803E-01 IBA------------R---- sodium 26 (Na-26) + 348 0 120230 82c DEC 12 23 0 22.99413 900.0 6.12483E-02 IBA------------R---- magnesium 23 (Mg-23) + 349 0 120270 82c DEC 12 27 0 26.98431 900.0 1.22145E-03 IBA------------R---- magnesium 27 (Mg-27) + 350 0 120280 82c DEC 12 28 0 27.98390 900.0 9.21248E-06 IBA------------R---- magnesium 28 (Mg-28) + 351 0 120290 82c DEC 12 29 0 28.98863 900.0 5.33190E-01 IBA------------R---- magnesium 29 (Mg-29) + 352 0 130260 82c DEC 13 26 0 25.98684 900.0 3.06346E-14 IBA------------R---- aluminum 26 (Al-26) + 353 0 130280 82c DEC 13 28 0 27.98188 900.0 5.15504E-03 IBAD-----------R---- aluminum 28 (Al-28) + 354 0 130290 82c DEC 13 29 0 28.98046 900.0 1.76104E-03 IBAD-----------R---- aluminum 29 (Al-29) + 355 0 130300 82c DEC 13 30 0 29.98297 900.0 1.89903E-01 IBA------------R---- aluminum 30 (Al-30) + 356 0 140270 82c DEC 14 27 0 26.98673 900.0 1.66622E-01 IBA------------R---- silicon 27 (Si-27) + 357 0 140310 82c DEC 14 31 0 30.97540 900.0 7.34889E-05 IBA------------R---- silicon 31 (Si-31) + 358 0 140320 82c DEC 14 32 0 31.97418 900.0 6.65592E-11 IBA------------R---- silicon 32 (Si-32) + 359 0 140330 82c DEC 14 33 0 32.97800 900.0 1.12160E-01 IBA------------R---- silicon 33 (Si-33) + 360 0 150300 82c DEC 15 30 0 29.97833 900.0 4.62468E-03 IBA------------R---- phosphorus 30 (P-30) + 361 0 150320 82c DEC 15 32 0 31.97387 900.0 5.62195E-07 IBAD-----------R---- phosphorus 32 (P-32) + 362 0 150330 82c DEC 15 33 0 32.97174 900.0 3.16060E-07 IBAD-----------R---- phosphorus 33 (P-33) + 363 0 150340 82c DEC 15 34 0 33.97365 900.0 5.58990E-02 IBA------------R---- phosphorus 34 (P-34) + 364 0 150350 82c DEC 15 35 0 34.97334 900.0 1.46543E-02 IBA------------R---- phosphorus 35 (P-35) + 365 0 150360 82c DEC 15 36 0 35.97827 900.0 1.23776E-01 IBA------------R---- phosphorus 36 (P-36) + 366 0 160320 82c DEC 16 32 0 31.97206 900.0 stable IB-D-----------R---- sulfur 32 (S-32) + 367 0 160330 82c DEC 16 33 0 32.97144 900.0 stable IBAD-----------R---- sulfur 33 (S-33) + 368 0 160350 82c DEC 16 35 0 34.96900 900.0 9.19488E-08 IBAD-----------R---- sulfur 35 (S-35) + 369 0 160370 82c DEC 16 37 0 36.97110 900.0 2.31512E-03 IBA------------R---- sulfur 37 (S-37) + 370 0 160380 82c DEC 16 38 0 37.97119 900.0 6.78359E-05 IBA------------R---- sulfur 38 (S-38) + 371 0 170340 82c DEC 17 34 0 33.97375 900.0 4.54225E-01 IBA------------R---- chlorine 34 (Cl-34) + 372 0 170360 82c DEC 17 36 0 35.96829 900.0 7.27317E-14 IBA------------R---- chlorine 36 (Cl-36) + 373 0 170380 82c DEC 17 38 0 37.96796 900.0 3.10550E-04 IBAD-----------R---- chlorine 38 (Cl-38) + 374 0 170381 82c DEC 17 38 1 37.96796 900.0 9.69437E-01 IBA------------R---- chlorine 38m (Cl-38m) + 375 0 170390 82c DEC 17 39 0 38.96806 900.0 2.07778E-04 IBA------------R---- chlorine 39 (Cl-39) + 376 0 170400 82c DEC 17 40 0 39.97037 900.0 8.55737E-03 IBA------------R---- chlorine 40 (Cl-40) + 377 0 180360 82c DEC 18 36 0 35.96758 900.0 stable IB-D-----------R---- argon 36 (Ar-36) + 378 0 180370 82c DEC 18 37 0 36.96676 900.0 2.29150E-07 IBA------------R---- argon 37 (Ar-37) + 379 0 180390 82c DEC 18 39 0 38.96432 900.0 8.16525E-11 IBAD-----------R---- argon 39 (Ar-39) + 380 0 180410 82c DEC 18 41 0 40.96451 900.0 1.05398E-04 IBA------------R---- argon 41 (Ar-41) + 381 0 180420 82c DEC 18 42 0 41.96309 900.0 6.65592E-10 IBA------------R---- argon 42 (Ar-42) + 382 0 180430 82c DEC 18 43 0 42.96560 900.0 2.15129E-03 IBA------------R---- argon 43 (Ar-43) + 383 0 190380 82c DEC 19 38 0 37.96907 900.0 1.51806E-03 IBA------------R---- potassium 38 (K-38) + 384 0 190420 82c DEC 19 42 0 41.96238 900.0 1.55790E-05 IBAD-----------R---- potassium 42 (K-42) + 385 0 190430 82c DEC 19 43 0 42.96076 900.0 8.67301E-06 IBAD-----------R---- potassium 43 (K-43) + 386 0 190440 82c DEC 19 44 0 43.96155 900.0 5.22027E-04 IBA------------R---- potassium 44 (K-44) + 387 0 190500 82c DEC 19 50 0 49.97279 900.0 1.46853E+00 IB--F-----P----R---- potassium 50 (K-50) + 388 0 190510 82c DEC 19 51 0 50.97641 900.0 1.89903E+00 IB--F-----P----R---- potassium 51 (K-51) + 389 0 200400 82c DEC 20 40 0 39.96260 900.0 stable IB-D-----------R---- calcium 40 (Ca-40) + 390 0 200410 82c DEC 20 41 0 40.96229 900.0 2.19212E-13 IBA------------R---- calcium 41 (Ca-41) + 391 0 200450 82c DEC 20 45 0 44.95620 900.0 4.93269E-08 IBA------------R---- calcium 45 (Ca-45) + 392 0 200460 82c DEC 20 46 0 45.95367 900.0 stable IBA------------R---- calcium 46 (Ca-46) + 393 0 200470 82c DEC 20 47 0 46.95456 900.0 1.76786E-06 IBA------------R---- calcium 47 (Ca-47) + 394 0 200480 82c DEC 20 48 0 47.95254 900.0 4.14425E-28 IBA------------R---- calcium 48 (Ca-48) + 395 0 200490 82c DEC 20 49 0 48.95566 900.0 1.32482E-03 IB-D-----------R---- calcium 49 (Ca-49) + 396 0 200500 82c DEC 20 50 0 49.95756 900.0 4.98667E-02 IB-DF----------R---- calcium 50 (Ca-50) + 397 0 200510 82c DEC 20 51 0 50.96149 900.0 6.93147E-02 IB-DF----------R---- calcium 51 (Ca-51) + 398 0 200520 82c DEC 20 52 0 51.96511 900.0 1.50684E-01 IB--F-----P----R---- calcium 52 (Ca-52) + 399 0 200530 82c DEC 20 53 0 52.97004 900.0 7.70164E+00 IB--F-----P----R---- calcium 53 (Ca-53) + 400 0 200540 82c DEC 20 54 0 53.97437 900.0 1.38629E+01 IB--F----------R---- calcium 54 (Ca-54) + 401 0 210440 82c DEC 21 44 0 43.95943 900.0 4.84990E-05 IBA------------R---- scandium 44 (Sc-44) + 402 0 210451 82c DEC 21 45 1 44.95589 900.0 2.13276E+00 IB-D-----------R---- scandium 45m (Sc-45m) + 403 0 210460 82c DEC 21 46 0 45.95518 900.0 9.57491E-08 IBAD-----------R---- scandium 46 (Sc-46) + 404 0 210461 82c DEC 21 46 1 45.95518 900.0 3.70667E-02 IBA------------R---- scandium 46m (Sc-46m) + 405 0 210470 82c DEC 21 47 0 46.95245 900.0 2.39586E-06 IBAD-----------R---- scandium 47 (Sc-47) + 406 0 210480 82c DEC 21 48 0 47.95224 900.0 4.40900E-06 IBAD-----------R---- scandium 48 (Sc-48) + 407 0 210490 82c DEC 21 49 0 48.95001 900.0 2.01966E-04 IBAD-----------R---- scandium 49 (Sc-49) + 408 0 210500 82c DEC 21 50 0 49.95222 900.0 6.76241E-03 IBADF----------R---- scandium 50 (Sc-50) + 409 0 210501 82c DEC 21 50 1 49.95222 900.0 1.98042E+00 IB-DF----------R---- scandium 50m (Sc-50m) + 410 0 210510 82c DEC 21 51 0 50.95362 900.0 5.58990E-02 IB-DF----------R---- scandium 51 (Sc-51) + 411 0 210520 82c DEC 21 52 0 51.95664 900.0 8.45301E-02 IB-DF----------R---- scandium 52 (Sc-52) + 412 0 210530 82c DEC 21 53 0 52.95965 900.0 2.31049E-01 IB-DF----------R---- scandium 53 (Sc-53) + 413 0 210540 82c DEC 21 54 0 53.96327 900.0 2.66595E+00 IB-DF----------R---- scandium 54 (Sc-54) + 414 0 210550 82c DEC 21 55 0 54.96821 900.0 5.77623E+00 IB--F----------R---- scandium 55 (Sc-55) + 415 0 210560 82c DEC 21 56 0 55.97284 900.0 8.66434E+00 IB--F----------R---- scandium 56 (Sc-56) + 416 0 210570 82c DEC 21 57 0 56.97777 900.0 5.33190E+01 IB--F-----P----R---- scandium 57 (Sc-57) + 417 0 220450 82c DEC 22 45 0 44.95811 900.0 6.25133E-05 IBA------------R---- titanium 45 (Ti-45) + 418 0 220510 82c DEC 22 51 0 50.94666 900.0 1.99180E-03 IBADF----------R---- titanium 51 (Ti-51) + 419 0 220520 82c DEC 22 52 0 51.94685 900.0 6.79556E-03 IB-DF----------R---- titanium 52 (Ti-52) + 420 0 220530 82c DEC 22 53 0 52.94977 900.0 2.11972E-02 IB-DF----------R---- titanium 53 (Ti-53) + 421 0 220540 82c DEC 22 54 0 53.95107 900.0 4.62098E-01 IB-DF----------R---- titanium 54 (Ti-54) + 422 0 220550 82c DEC 22 55 0 54.95530 900.0 1.41459E+00 IB-DF----------R---- titanium 55 (Ti-55) + 423 0 220560 82c DEC 22 56 0 55.95821 900.0 4.22651E+00 IB-DF----------R---- titanium 56 (Ti-56) + 424 0 220570 82c DEC 22 57 0 56.96395 900.0 1.15525E+01 IB-DF-----P----R---- titanium 57 (Ti-57) + 425 0 220580 82c DEC 22 58 0 57.96697 900.0 1.28361E+01 IB--F----------R---- titanium 58 (Ti-58) + 426 0 220590 82c DEC 22 59 0 58.97291 900.0 2.31049E+01 IB--F----------R---- titanium 59 (Ti-59) + 427 0 220600 82c DEC 22 60 0 59.97673 900.0 3.15067E+01 IB--F----------R---- titanium 60 (Ti-60) + 428 0 220610 82c DEC 22 61 0 60.98318 900.0 6.93147E+01 IB--F----------R---- titanium 61 (Ti-61) + 429 0 230490 82c DEC 23 49 0 48.94849 900.0 2.43107E-08 IBAD-----------R---- vanadium 49 (V-49) + 430 0 230500 82c DEC 23 50 0 49.94717 900.0 1.56893E-25 IBA-F----------R---- vanadium 50 (V-50) + 431 0 230510 82c DEC 23 51 0 50.94394 900.0 stable IBADF----------R---- vanadium 51 (V-51) + 432 0 230520 82c DEC 23 52 0 51.94473 900.0 3.08477E-03 IBADF----------R---- vanadium 52 (V-52) + 433 0 230530 82c DEC 23 53 0 52.94432 900.0 7.13114E-03 IBADF----------R---- vanadium 53 (V-53) + 434 0 230540 82c DEC 23 54 0 53.94643 900.0 1.39186E-02 IBADF----------R---- vanadium 54 (V-54) + 435 0 230550 82c DEC 23 55 0 54.94723 900.0 1.05986E-01 IB-DF----------R---- vanadium 55 (V-55) + 436 0 230560 82c DEC 23 56 0 55.95054 900.0 3.20901E+00 IB-DF----------R---- vanadium 56 (V-56) + 437 0 230570 82c DEC 23 57 0 56.95255 900.0 1.98042E+00 IB-DF-----P----R---- vanadium 57 (V-57) + 438 0 230580 82c DEC 23 58 0 57.95688 900.0 3.62904E+00 IB-DF-----P----R---- vanadium 58 (V-58) + 439 0 230590 82c DEC 23 59 0 58.96020 900.0 9.24196E+00 IB-DF----------R---- vanadium 59 (V-59) + 440 0 230600 82c DEC 23 60 0 59.96503 900.0 5.68153E+00 IB-DF----------R---- vanadium 60 (V-60) + 441 0 230610 82c DEC 23 61 0 60.96845 900.0 1.47478E+01 IB-DF-----P----R---- vanadium 61 (V-61) + 442 0 230620 82c DEC 23 62 0 61.97379 900.0 2.06910E+01 IB--F----------R---- vanadium 62 (V-62) + 443 0 230630 82c DEC 23 63 0 62.97751 900.0 4.07734E+01 IB--F-----P----R---- vanadium 63 (V-63) + 444 0 230640 82c DEC 23 64 0 63.98345 900.0 6.93147E+01 IB--F----------R---- vanadium 64 (V-64) + 445 0 230650 82c DEC 23 65 0 64.98788 900.0 6.93147E+01 IB--F----------R---- vanadium 65 (V-65) + 446 0 240490 82c DEC 24 49 0 48.95132 900.0 2.75715E-04 IBA------------R---- chromium 49 (Cr-49) + 447 0 240510 82c DEC 24 51 0 50.94474 900.0 2.89580E-07 IBA------------R---- chromium 51 (Cr-51) + 448 0 240550 82c DEC 24 55 0 54.94087 900.0 3.26340E-03 IBADF----------R---- chromium 55 (Cr-55) + 449 0 240560 82c DEC 24 56 0 55.94066 900.0 1.94486E-03 IBADF----------R---- chromium 56 (Cr-56) + 450 0 240570 82c DEC 24 57 0 56.94358 900.0 3.28506E-02 IB-DF----------R---- chromium 57 (Cr-57) + 451 0 240580 82c DEC 24 58 0 57.94437 900.0 9.90210E-02 IB-DF----------R---- chromium 58 (Cr-58) + 452 0 240590 82c DEC 24 59 0 58.94860 900.0 1.50684E+00 IB-DF----------R---- chromium 59 (Cr-59) + 453 0 240600 82c DEC 24 60 0 59.95010 900.0 1.23776E+00 IB-DF----------R---- chromium 60 (Cr-60) + 454 0 240610 82c DEC 24 61 0 60.95473 900.0 2.65574E+00 IB-DF----------R---- chromium 61 (Cr-61) + 455 0 240620 82c DEC 24 62 0 61.95664 900.0 3.48315E+00 IB-DF----------R---- chromium 62 (Cr-62) + 456 0 240630 82c DEC 24 63 0 62.96188 900.0 5.37323E+00 IB-DF----------R---- chromium 63 (Cr-63) + 457 0 240640 82c DEC 24 64 0 63.96439 900.0 1.61197E+01 IB-DF----------R---- chromium 64 (Cr-64) + 458 0 240650 82c DEC 24 65 0 64.97013 900.0 2.56721E+01 IB-DF----------R---- chromium 65 (Cr-65) + 459 0 240660 82c DEC 24 66 0 65.97335 900.0 6.93147E+01 IB--F----------R---- chromium 66 (Cr-66) + 460 0 240670 82c DEC 24 67 0 66.97959 900.0 6.93147E+01 IB--F----------R---- chromium 67 (Cr-67) + 461 0 250520 82c DEC 25 52 0 51.94554 900.0 1.43388E-06 IBA------------R---- manganese 52 (Mn-52) + 462 0 250530 82c DEC 25 53 0 52.94129 900.0 5.96861E-15 IBAD-----------R---- manganese 53 (Mn-53) + 463 0 250540 82c DEC 25 54 0 53.94038 900.0 2.56976E-08 IBA-F----------R---- manganese 54 (Mn-54) + 464 0 250560 82c DEC 25 56 0 55.93895 900.0 7.46635E-05 IBADF----------R---- manganese 56 (Mn-56) + 465 0 250570 82c DEC 25 57 0 56.93833 900.0 8.11648E-03 IBADF----------R---- manganese 57 (Mn-57) + 466 0 250580 82c DEC 25 58 0 57.94004 900.0 1.06311E-02 IBADF----------R---- manganese 58 (Mn-58) + 467 0 250581 82c DEC 25 58 1 57.94004 900.0 2.56721E-01 IB--F----------R---- manganese 58m (Mn-58m) + 468 0 250590 82c DEC 25 59 0 58.94043 900.0 1.51012E-01 IB-DF----------R---- manganese 59 (Mn-59) + 469 0 250600 82c DEC 25 60 0 59.94294 900.0 1.35911E-02 IB-DF----------R---- manganese 60 (Mn-60) + 470 0 250601 82c DEC 25 60 1 59.94294 900.0 3.91609E-01 IB--F----------R---- manganese 60m (Mn-60m) + 471 0 250610 82c DEC 25 61 0 60.94465 900.0 1.03455E+00 IB-DF----------R---- manganese 61 (Mn-61) + 472 0 250620 82c DEC 25 62 0 61.94847 900.0 7.87667E-01 IB-DF----------R---- manganese 62 (Mn-62) + 473 0 250621 82c DEC 25 62 1 61.94847 900.0 7.53421E+00 IB-DF----------R---- manganese 62m (Mn-62m) + 474 0 250630 82c DEC 25 63 0 62.95028 900.0 2.52054E+00 IB-DF----------R---- manganese 63 (Mn-63) + 475 0 250640 82c DEC 25 64 0 63.95420 900.0 7.80571E+00 IB-DF----------R---- manganese 64 (Mn-64) + 476 0 250650 82c DEC 25 65 0 64.95631 900.0 7.53421E+00 IB-DF----------R---- manganese 65 (Mn-65) + 477 0 250660 82c DEC 25 66 0 65.96104 900.0 1.07632E+01 IB-DF----------R---- manganese 66 (Mn-66) + 478 0 250670 82c DEC 25 67 0 66.96416 900.0 1.54033E+01 IB-DF----------R---- manganese 67 (Mn-67) + 479 0 250680 82c DEC 25 68 0 67.96929 900.0 2.47553E+01 IB--F----------R---- manganese 68 (Mn-68) + 480 0 250690 82c DEC 25 69 0 68.97281 900.0 4.95105E+01 IB--F-----P----R---- manganese 69 (Mn-69) + 481 0 260530 82c DEC 26 53 0 52.94533 900.0 1.35752E-03 IBA------------R---- iron 53 (Fe-53) + 482 0 260550 82c DEC 26 55 0 54.93825 900.0 7.99599E-09 IBA------------R---- iron 55 (Fe-55) + 483 0 260590 82c DEC 26 59 0 58.93488 900.0 1.80306E-07 IBADF----------R---- iron 59 (Fe-59) + 484 0 260600 82c DEC 26 60 0 59.93407 900.0 1.46430E-14 IBADF----------R---- iron 60 (Fe-60) + 485 0 260610 82c DEC 26 61 0 60.93678 900.0 1.93185E-03 IBADF----------R---- iron 61 (Fe-61) + 486 0 260620 82c DEC 26 62 0 61.93677 900.0 1.01933E-02 IB-DF----------R---- iron 62 (Fe-62) + 487 0 260630 82c DEC 26 63 0 62.94009 900.0 1.13631E-01 IB-DF----------R---- iron 63 (Fe-63) + 488 0 260640 82c DEC 26 64 0 63.94119 900.0 3.46574E-01 IB-DF----------R---- iron 64 (Fe-64) + 489 0 260650 82c DEC 26 65 0 64.94542 900.0 5.33190E-01 IB-DF----------R---- iron 65 (Fe-65) + 490 0 260660 82c DEC 26 66 0 65.94682 900.0 1.57533E+00 IB-DF----------R---- iron 66 (Fe-66) + 491 0 260670 82c DEC 26 67 0 66.95094 900.0 1.75926E+00 IB-DF----------R---- iron 67 (Fe-67) + 492 0 260680 82c DEC 26 68 0 67.95366 900.0 3.70667E+00 IB-DF----------R---- iron 68 (Fe-68) + 493 0 260690 82c DEC 26 69 0 68.95879 900.0 6.35915E+00 IB-DF-----P----R---- iron 69 (Fe-69) + 494 0 260700 82c DEC 26 70 0 69.96151 900.0 7.37391E+00 IB--F----------R---- iron 70 (Fe-70) + 495 0 260710 82c DEC 26 71 0 70.96674 900.0 2.31049E+01 IB--F----------R---- iron 71 (Fe-71) + 496 0 260720 82c DEC 26 72 0 71.96966 900.0 6.93147E+01 IB--F----------R---- iron 72 (Fe-72) + 497 0 270560 82c DEC 27 56 0 55.93985 900.0 1.03870E-07 IBA------------R---- cobalt 56 (Co-56) + 498 0 270570 82c DEC 27 57 0 56.93631 900.0 2.95163E-08 IBAD-----------R---- cobalt 57 (Co-57) + 499 0 270580 82c DEC 27 58 0 57.93580 900.0 1.13233E-07 IBA------------R---- cobalt 58 (Co-58) + 500 0 270600 82c DEC 27 60 0 59.93386 900.0 4.16705E-09 IBADF----------R---- cobalt 60 (Co-60) + 501 0 270601 82c DEC 27 60 1 59.93386 900.0 1.10370E-03 IBADF----------R---- cobalt 60m (Co-60m) + 502 0 270610 82c DEC 27 61 0 60.93244 900.0 1.16691E-04 IBADF----------R---- cobalt 61 (Co-61) + 503 0 270620 82c DEC 27 62 0 61.93405 900.0 7.50159E-03 IBADF----------R---- cobalt 62 (Co-62) + 504 0 270621 82c DEC 27 62 1 61.93405 900.0 8.30514E-04 IB--F----------R---- cobalt 62m (Co-62m) + 505 0 270630 82c DEC 27 63 0 62.93363 900.0 2.52973E-02 IBADF----------R---- cobalt 63 (Co-63) + 506 0 270640 82c DEC 27 64 0 63.93584 900.0 2.31049E+00 IBADF----------R---- cobalt 64 (Co-64) + 507 0 270650 82c DEC 27 65 0 64.93644 900.0 5.77623E-01 IB-DF----------R---- cobalt 65 (Co-65) + 508 0 270660 82c DEC 27 66 0 65.93976 900.0 3.46574E+00 IB-DF----------R---- cobalt 66 (Co-66) + 509 0 270670 82c DEC 27 67 0 66.94086 900.0 1.63093E+00 IB-DF----------R---- cobalt 67 (Co-67) + 510 0 270680 82c DEC 27 68 0 67.94488 900.0 3.46574E+00 IB-DF----------R---- cobalt 68 (Co-68) + 511 0 270681 82c DEC 27 68 1 67.94488 900.0 4.33217E-01 IB-DF----------R---- cobalt 68m (Co-68m) + 512 0 270690 82c DEC 27 69 0 68.94629 900.0 3.05351E+00 IB-DF-----P----R---- cobalt 69 (Co-69) + 513 0 270700 82c DEC 27 70 0 69.95102 900.0 5.82477E+00 IB--F----------R---- cobalt 70 (Co-70) + 514 0 270701 82c DEC 27 70 1 69.95102 900.0 1.38629E+00 IB-DF----------R---- cobalt 70m (Co-70m) + 515 0 270710 82c DEC 27 71 0 70.95292 900.0 7.14585E+00 IB-DF----------R---- cobalt 71 (Co-71) + 516 0 270720 82c DEC 27 72 0 71.95786 900.0 7.70164E+00 IB-DF----------R---- cobalt 72 (Co-72) + 517 0 270730 82c DEC 27 73 0 72.96027 900.0 8.66434E+00 IB--F----------R---- cobalt 73 (Co-73) + 518 0 270740 82c DEC 27 74 0 73.96540 900.0 1.38629E+01 IB--F----------R---- cobalt 74 (Co-74) + 519 0 270750 82c DEC 27 75 0 74.96832 900.0 1.73287E+01 IB--F----------R---- cobalt 75 (Co-75) + 520 0 280570 82c DEC 28 57 0 56.93974 900.0 5.36267E-06 IBA------------R---- nickel 57 (Ni-57) + 521 0 280630 82c DEC 28 63 0 62.92970 900.0 2.22543E-10 IBADF----------R---- nickel 63 (Ni-63) + 522 0 280650 82c DEC 28 65 0 64.93008 900.0 7.64051E-05 IBADF----------R---- nickel 65 (Ni-65) + 523 0 280660 82c DEC 28 66 0 65.92917 900.0 3.53935E-06 IBADF----------R---- nickel 66 (Ni-66) + 524 0 280670 82c DEC 28 67 0 66.93158 900.0 3.30070E-02 IB-DF----------R---- nickel 67 (Ni-67) + 525 0 280680 82c DEC 28 68 0 67.93187 900.0 2.39016E-02 IB-DF----------R---- nickel 68 (Ni-68) + 526 0 280690 82c DEC 28 69 0 68.93559 900.0 6.08024E-02 IB-DF----------R---- nickel 69 (Ni-69) + 527 0 280691 82c DEC 28 69 1 68.93559 900.0 1.98042E-01 IB--F----------R---- nickel 69m (Ni-69m) + 528 0 280700 82c DEC 28 70 0 69.93649 900.0 1.15525E-01 IB-DF----------R---- nickel 70 (Ni-70) + 529 0 280710 82c DEC 28 71 0 70.94072 900.0 2.70761E-01 IB-DF----------R---- nickel 71 (Ni-71) + 530 0 280720 82c DEC 28 72 0 71.94212 900.0 4.41495E-01 IB-DF----------R---- nickel 72 (Ni-72) + 531 0 280730 82c DEC 28 73 0 72.94645 900.0 8.25175E-01 IB-DF----------R---- nickel 73 (Ni-73) + 532 0 280740 82c DEC 28 74 0 73.94805 900.0 1.01933E+00 IB-DF----------R---- nickel 74 (Ni-74) + 533 0 280750 82c DEC 28 75 0 74.95289 900.0 1.15525E+00 IB-DF-----P----R---- nickel 75 (Ni-75) + 534 0 280760 82c DEC 28 76 0 75.95530 900.0 1.47478E+00 IB--F----------R---- nickel 76 (Ni-76) + 535 0 280770 82c DEC 28 77 0 76.96053 900.0 2.31049E+00 IB--F----------R---- nickel 77 (Ni-77) + 536 0 280780 82c DEC 28 78 0 77.96314 900.0 3.46574E+00 IB--F----------R---- nickel 78 (Ni-78) + 537 0 290630 82c DEC 29 63 0 62.92960 900.0 stable IB-D-----------R---- copper 63 (Cu-63) + 538 0 290640 82c DEC 29 64 0 63.92979 900.0 1.51602E-05 IBA-F----------R---- copper 64 (Cu-64) + 539 0 290660 82c DEC 29 66 0 65.92886 900.0 2.26519E-03 IBADF----------R---- copper 66 (Cu-66) + 540 0 290670 82c DEC 29 67 0 66.92774 900.0 3.11052E-06 IB-DF----------R---- copper 67 (Cu-67) + 541 0 290680 82c DEC 29 68 0 67.92965 900.0 2.22877E-02 IBADF----------R---- copper 68 (Cu-68) + 542 0 290681 82c DEC 29 68 1 67.92965 900.0 3.08065E-03 IB--F----------R---- copper 68m (Cu-68m) + 543 0 290690 82c DEC 29 69 0 68.92944 900.0 4.05349E-03 IBADF----------R---- copper 69 (Cu-69) + 544 0 290700 82c DEC 29 70 0 69.93236 900.0 1.55763E-02 IB-DF----------R---- copper 70 (Cu-70) + 545 0 290701 82c DEC 29 70 1 69.93236 900.0 2.10045E-02 IB-DF----------R---- copper 70m (Cu-70m) + 546 1 290702 82c DEC 29 70 2 69.93236 900.0 1.05022E-01 -B-DF----------R---- copper 70m (Cu-70m) + 547 0 290710 82c DEC 29 71 0 70.93265 900.0 3.57292E-02 IB-DF----------R---- copper 71 (Cu-71) + 548 0 290720 82c DEC 29 72 0 71.93587 900.0 1.04547E-01 IB-DF----------R---- copper 72 (Cu-72) + 549 0 290730 82c DEC 29 73 0 72.93666 900.0 1.65035E-01 IB-DF----------R---- copper 73 (Cu-73) + 550 0 290740 82c DEC 29 74 0 73.93988 900.0 4.34848E-01 IB-DF----------R---- copper 74 (Cu-74) + 551 0 290750 82c DEC 29 75 0 74.94189 900.0 5.66297E-01 IB-DF-----P----R---- copper 75 (Cu-75) + 552 0 290760 82c DEC 29 76 0 75.94531 900.0 1.08135E+00 IB-DF-----P----R---- copper 76 (Cu-76) + 553 0 290761 82c DEC 29 76 1 75.94531 900.0 5.45785E-01 IB-DF----------R---- copper 76m (Cu-76m) + 554 0 290770 82c DEC 29 77 0 76.94782 900.0 1.47793E+00 IB-DF----------R---- copper 77 (Cu-77) + 555 0 290780 82c DEC 29 78 0 77.95195 900.0 2.02675E+00 IB-DF----------R---- copper 78 (Cu-78) + 556 0 290790 82c DEC 29 79 0 78.95456 900.0 3.68695E+00 IB--F-----P----R---- copper 79 (Cu-79) + 557 0 290800 82c DEC 29 80 0 79.96091 900.0 6.93147E+00 IB--F----------R---- copper 80 (Cu-80) + 558 0 300640 82c DEC 30 64 0 63.92919 900.0 9.54978E-27 IB-D-----------R---- zinc 64 (Zn-64) + 559 0 300650 82c DEC 30 65 0 64.92928 900.0 3.28778E-08 IBA------------R---- zinc 65 (Zn-65) + 560 0 300660 82c DEC 30 66 0 65.92604 900.0 stable IBADF----------R---- zinc 66 (Zn-66) + 561 0 300670 82c DEC 30 67 0 66.92714 900.0 stable IBADF----------R---- zinc 67 (Zn-67) + 562 0 300680 82c DEC 30 68 0 67.92481 900.0 stable IBADF----------R---- zinc 68 (Zn-68) + 563 0 300690 82c DEC 30 69 0 68.92652 900.0 2.04831E-04 IBADF----------R---- zinc 69 (Zn-69) + 564 0 300691 82c DEC 30 69 1 68.92652 900.0 1.39725E-05 IB--F----------R---- zinc 69m (Zn-69m) + 565 0 300700 82c DEC 30 70 0 69.92530 900.0 stable IBADF----------R---- zinc 70 (Zn-70) + 566 0 300710 82c DEC 30 71 0 70.92771 900.0 4.71529E-03 IBADF----------R---- zinc 71 (Zn-71) + 567 0 300711 82c DEC 30 71 1 70.92771 900.0 4.86214E-05 IB--F----------R---- zinc 71m (Zn-71m) + 568 0 300720 82c DEC 30 72 0 71.92689 900.0 4.14066E-06 IBADF----------R---- zinc 72 (Zn-72) + 569 0 300730 82c DEC 30 73 0 72.92981 900.0 2.94956E-02 IBADF----------R---- zinc 73 (Zn-73) + 570 0 300731 82c DEC 30 73 1 72.92981 900.0 5.33190E-02 IB-DF----------R---- zinc 73m (Zn-73m) + 571 1 300732 82c DEC 30 73 2 72.92981 900.0 1.19508E-01 -B--F----------R---- zinc 73m (Zn-73m) + 572 0 300740 82c DEC 30 74 0 73.92949 900.0 7.25049E-03 IB-DF----------R---- zinc 74 (Zn-74) + 573 0 300750 82c DEC 30 75 0 74.93291 900.0 6.79556E-02 IB-DF----------R---- zinc 75 (Zn-75) + 574 0 300760 82c DEC 30 76 0 75.93331 900.0 1.21605E-01 IB-DF----------R---- zinc 76 (Zn-76) + 575 0 300770 82c DEC 30 77 0 76.93693 900.0 3.33244E-01 IB-DF----------R---- zinc 77 (Zn-77) + 576 0 300771 82c DEC 30 77 1 76.93693 900.0 6.60140E-01 IB--F----------R---- zinc 77m (Zn-77m) + 577 0 300780 82c DEC 30 78 0 77.93843 900.0 4.71529E-01 IB-DF----------R---- zinc 78 (Zn-78) + 578 0 300790 82c DEC 30 79 0 78.94266 900.0 6.96630E-01 IB-DF-----P----R---- zinc 79 (Zn-79) + 579 0 300800 82c DEC 30 80 0 79.94436 900.0 1.28361E+00 IB-DF----------R---- zinc 80 (Zn-80) + 580 0 300810 82c DEC 30 81 0 80.95051 900.0 2.39016E+00 IB--F-----P----R---- zinc 81 (Zn-81) + 581 0 300820 82c DEC 30 82 0 81.95443 900.0 6.93147E+00 IB--F----------R---- zinc 82 (Zn-82) + 582 0 300830 82c DEC 30 83 0 82.96108 900.0 8.66434E+00 IB--F----------R---- zinc 83 (Zn-83) + 583 0 310680 82c DEC 31 68 0 67.92794 900.0 1.70315E-04 IBA-F----------R---- gallium 68 (Ga-68) + 584 0 310690 82c DEC 31 69 0 68.92561 900.0 stable IBADF----------R---- gallium 69 (Ga-69) + 585 0 310700 82c DEC 31 70 0 69.92600 900.0 5.46474E-04 IBA-F----------R---- gallium 70 (Ga-70) + 586 0 310710 82c DEC 31 71 0 70.92468 900.0 stable IBADF----------R---- gallium 71 (Ga-71) + 587 0 310720 82c DEC 31 72 0 71.92639 900.0 1.36554E-05 IBADF----------R---- gallium 72 (Ga-72) + 588 0 310721 82c DEC 31 72 1 71.92639 900.0 1.74684E+01 IB-DF----------R---- gallium 72m (Ga-72m) + 589 0 310730 82c DEC 31 73 0 72.92517 900.0 3.96175E-05 IBADF----------R---- gallium 73 (Ga-73) + 590 0 310740 82c DEC 31 74 0 73.92697 900.0 1.42272E-03 IBADF----------R---- gallium 74 (Ga-74) + 591 0 310741 82c DEC 31 74 1 73.92697 900.0 7.29629E-02 IB-DF----------R---- gallium 74m (Ga-74m) + 592 0 310750 82c DEC 31 75 0 74.92646 900.0 5.50117E-03 IBADF----------R---- gallium 75 (Ga-75) + 593 0 310760 82c DEC 31 76 0 75.92887 900.0 2.12622E-02 IBADF----------R---- gallium 76 (Ga-76) + 594 0 310770 82c DEC 31 77 0 76.92926 900.0 5.33190E-02 IB-DF----------R---- gallium 77 (Ga-77) + 595 0 310780 82c DEC 31 78 0 77.93157 900.0 1.36178E-01 IB-DF----------R---- gallium 78 (Ga-78) + 596 0 310790 82c DEC 31 79 0 78.93288 900.0 2.43466E-01 IB-DF-----P----R---- gallium 79 (Ga-79) + 597 0 310800 82c DEC 31 80 0 79.93650 900.0 4.13572E-01 IB-DF----------R---- gallium 80 (Ga-80) + 598 0 310810 82c DEC 31 81 0 80.93780 900.0 5.69554E-01 IB-DF-----P----R---- gallium 81 (Ga-81) + 599 0 310820 82c DEC 31 82 0 81.94303 900.0 1.15717E+00 IB-DF-----P----R---- gallium 82 (Ga-82) + 600 0 310830 82c DEC 31 83 0 82.94696 900.0 2.25048E+00 IB-DF-----P----R---- gallium 83 (Ga-83) + 601 0 310840 82c DEC 31 84 0 83.95270 900.0 8.15467E+00 IB--F-----P----R---- gallium 84 (Ga-84) + 602 0 310850 82c DEC 31 85 0 84.95703 900.0 1.38629E+01 IB--F----------R---- gallium 85 (Ga-85) + 603 0 310860 82c DEC 31 86 0 85.96317 900.0 2.31049E+01 IB--F----------R---- gallium 86 (Ga-86) + 604 0 320690 82c DEC 32 69 0 68.92793 900.0 4.93062E-06 IBA------------R---- germanium 69 (Ge-69) + 605 0 320710 82c DEC 32 71 0 70.92498 900.0 7.01884E-07 IBADF----------R---- germanium 71 (Ge-71) + 606 0 320711 82c DEC 32 71 1 70.92498 900.0 3.39778E+01 IB--F----------R---- germanium 71m (Ge-71m) + 607 0 320731 82c DEC 32 73 1 72.92345 900.0 1.38629E+00 IBADF----------R---- germanium 73m (Ge-73m) + 608 0 320750 82c DEC 32 75 0 74.92283 900.0 1.39556E-04 IBADF----------R---- germanium 75 (Ge-75) + 609 0 320751 82c DEC 32 75 1 74.92283 900.0 1.44406E-02 IBADF----------R---- germanium 75m (Ge-75m) + 610 0 320770 82c DEC 32 77 0 76.92351 900.0 1.71743E-05 IBADF----------R---- germanium 77 (Ge-77) + 611 0 320771 82c DEC 32 77 1 76.92351 900.0 1.29078E-02 IBADF----------R---- germanium 77m (Ge-77m) + 612 0 320780 82c DEC 32 78 0 77.92290 900.0 1.31278E-04 IBADF----------R---- germanium 78 (Ge-78) + 613 0 320790 82c DEC 32 79 0 78.92541 900.0 3.65199E-02 IBADF----------R---- germanium 79 (Ge-79) + 614 0 320791 82c DEC 32 79 1 78.92541 900.0 1.77730E-02 IB-DF----------R---- germanium 79m (Ge-79m) + 615 0 320800 82c DEC 32 80 0 79.92540 900.0 2.34965E-02 IBADF----------R---- germanium 80 (Ge-80) + 616 0 320810 82c DEC 32 81 0 80.92882 900.0 8.66434E-02 IBADF----------R---- germanium 81 (Ge-81) + 617 0 320811 82c DEC 32 81 1 80.92882 900.0 9.12036E-02 IB-DF----------R---- germanium 81m (Ge-81m) + 618 0 320820 82c DEC 32 82 0 81.92952 900.0 1.52340E-01 IB-DF----------R---- germanium 82 (Ge-82) + 619 0 320830 82c DEC 32 83 0 82.93465 900.0 3.74674E-01 IB-DF----------R---- germanium 83 (Ge-83) + 620 0 320840 82c DEC 32 84 0 83.93747 900.0 7.26569E-01 IB-DF-----P----R---- germanium 84 (Ge-84) + 621 0 320850 82c DEC 32 85 0 84.94301 900.0 1.28361E+00 IB-DF-----P----R---- germanium 85 (Ge-85) + 622 0 320860 82c DEC 32 86 0 85.94653 900.0 2.31049E+00 IB-DF----------R---- germanium 86 (Ge-86) + 623 0 320870 82c DEC 32 87 0 86.95247 900.0 4.62098E+00 IB--F----------R---- germanium 87 (Ge-87) + 624 0 320880 82c DEC 32 88 0 87.95690 900.0 8.66434E+00 IB--F----------R---- germanium 88 (Ge-88) + 625 0 320890 82c DEC 32 89 0 88.96385 900.0 1.38629E+01 IB--F----------R---- germanium 89 (Ge-89) + 626 0 330730 82c DEC 33 73 0 72.92385 900.0 9.99071E-08 IB--F----------R---- arsenic 73 (As-73) + 627 0 330740 82c DEC 33 74 0 73.92395 900.0 4.51212E-07 IBA-F----------R---- arsenic 74 (As-74) + 628 0 330751 82c DEC 33 75 1 74.92162 900.0 3.93387E+01 IB-DF----------R---- arsenic 75m (As-75m) + 629 0 330760 82c DEC 33 76 0 75.92241 900.0 7.34328E-06 IBA-F----------R---- arsenic 76 (As-76) + 630 0 330770 82c DEC 33 77 0 76.92069 900.0 4.96367E-06 IBADF----------R---- arsenic 77 (As-77) + 631 0 330780 82c DEC 33 78 0 77.92179 900.0 1.27370E-04 IBADF----------R---- arsenic 78 (As-78) + 632 0 330790 82c DEC 33 79 0 78.92097 900.0 1.28218E-03 IBADF----------R---- arsenic 79 (As-79) + 633 0 330800 82c DEC 33 80 0 79.92258 900.0 4.56018E-02 IBADF----------R---- arsenic 80 (As-80) + 634 0 330810 82c DEC 33 81 0 80.92216 900.0 2.08152E-02 IBADF----------R---- arsenic 81 (As-81) + 635 0 330820 82c DEC 33 82 0 81.92447 900.0 3.62904E-02 IBADF----------R---- arsenic 82 (As-82) + 636 0 330821 82c DEC 33 82 1 81.92447 900.0 5.09667E-02 IB--F----------R---- arsenic 82m (As-82m) + 637 0 330830 82c DEC 33 83 0 82.92497 900.0 5.17274E-02 IB-DF----------R---- arsenic 83 (As-83) + 638 0 330840 82c DEC 33 84 0 83.92910 900.0 1.72425E-01 IB-DF-----P----R---- arsenic 84 (As-84) + 639 0 330841 82c DEC 33 84 1 83.92910 900.0 1.06638E+00 IB-DF----------R---- arsenic 84m (As-84m) + 640 0 330850 82c DEC 33 85 0 84.93181 900.0 3.39778E-01 IB-DF-----P----R---- arsenic 85 (As-85) + 641 0 330860 82c DEC 33 86 0 85.93654 900.0 7.33489E-01 IB-DF-----P----R---- arsenic 86 (As-86) + 642 0 330870 82c DEC 33 87 0 86.93986 900.0 1.13631E+00 IB-DF-----P----R---- arsenic 87 (As-87) + 643 0 330880 82c DEC 33 88 0 87.94489 900.0 2.31049E+00 IB-DF----------R---- arsenic 88 (As-88) + 644 0 330890 82c DEC 33 89 0 88.94942 900.0 3.46574E+00 IB-DF----------R---- arsenic 89 (As-89) + 645 0 330900 82c DEC 33 90 0 89.95547 900.0 8.66434E+00 IB--F----------R---- arsenic 90 (As-90) + 646 0 330910 82c DEC 33 91 0 90.96040 900.0 1.38629E+01 IB--F----------R---- arsenic 91 (As-91) + 647 0 340740 82c DEC 34 74 0 73.92243 900.0 stable IB-D-----------R---- selenium 74 (Se-74) + 648 0 340750 82c DEC 34 75 0 74.92252 900.0 6.69766E-08 IB--F----------R---- selenium 75 (Se-75) + 649 0 340771 82c DEC 34 77 1 76.91988 900.0 3.94956E-02 IBA-F----------R---- selenium 77m (Se-77m) + 650 0 340791 82c DEC 34 79 1 78.91855 900.0 2.96217E-03 IBA-F----------R---- selenium 79m (Se-79m) + 651 0 340810 82c DEC 34 81 0 80.91803 900.0 6.28192E-04 IBADF----------R---- selenium 81 (Se-81) + 652 0 340811 82c DEC 34 81 1 80.91803 900.0 2.01684E-04 IBADF----------R---- selenium 81m (Se-81m) + 653 0 340830 82c DEC 34 83 0 82.91912 900.0 5.18047E-04 IBADF----------R---- selenium 83 (Se-83) + 654 0 340831 82c DEC 34 83 1 82.91912 900.0 9.88798E-03 IBADF----------R---- selenium 83m (Se-83m) + 655 0 340840 82c DEC 34 84 0 83.91850 900.0 3.54370E-03 IBADF----------R---- selenium 84 (Se-84) + 656 0 340850 82c DEC 34 85 0 84.92223 900.0 2.18658E-02 IBADF----------R---- selenium 85 (Se-85) + 657 0 340860 82c DEC 34 86 0 85.92423 900.0 4.53037E-02 IB-DF----------R---- selenium 86 (Se-86) + 658 0 340870 82c DEC 34 87 0 86.92856 900.0 1.26027E-01 IB-DF----------R---- selenium 87 (Se-87) + 659 0 340880 82c DEC 34 88 0 87.93138 900.0 4.53037E-01 IB-DF-----P----R---- selenium 88 (Se-88) + 660 0 340890 82c DEC 34 89 0 88.93641 900.0 1.69060E+00 IB-DF-----P----R---- selenium 89 (Se-89) + 661 0 340900 82c DEC 34 90 0 89.93993 900.0 2.31049E+00 IB-DF----------R---- selenium 90 (Se-90) + 662 0 340910 82c DEC 34 91 0 90.94597 900.0 2.56721E+00 IB-DF-----P----R---- selenium 91 (Se-91) + 663 0 340920 82c DEC 34 92 0 91.94990 900.0 6.93147E+00 IB--F----------R---- selenium 92 (Se-92) + 664 0 340930 82c DEC 34 93 0 92.95624 900.0 1.38629E+01 IB--F----------R---- selenium 93 (Se-93) + 665 0 340940 82c DEC 34 94 0 93.96047 900.0 3.46574E+01 IB--F----------R---- selenium 94 (Se-94) + 666 0 350780 82c DEC 35 78 0 77.92118 900.0 1.79108E-03 IBA-F----------R---- bromine 78 (Br-78) + 667 0 350791 82c DEC 35 79 1 78.91835 900.0 1.42506E-01 IB--F----------R---- bromine 79m (Br-79m) + 668 0 350800 82c DEC 35 80 0 79.91854 900.0 6.56389E-04 IBADF----------R---- bromine 80 (Br-80) + 669 0 350801 82c DEC 35 80 1 79.91854 900.0 4.36601E-05 IBA-F----------R---- bromine 80m (Br-80m) + 670 0 350820 82c DEC 35 82 0 81.91681 900.0 5.45133E-06 IBADF----------R---- bromine 82 (Br-82) + 671 0 350821 82c DEC 35 82 1 81.91681 900.0 1.89695E-03 IBA-F----------R---- bromine 82m (Br-82m) + 672 0 350830 82c DEC 35 83 0 82.91519 900.0 8.02254E-05 IBADF----------R---- bromine 83 (Br-83) + 673 0 350840 82c DEC 35 84 0 83.91649 900.0 3.63742E-04 IBADF----------R---- bromine 84 (Br-84) + 674 0 350841 82c DEC 35 84 1 83.91649 900.0 1.92541E-03 IB--F----------R---- bromine 84m (Br-84m) + 675 0 350850 82c DEC 35 85 0 84.91557 900.0 3.98360E-03 IBADF----------R---- bromine 85 (Br-85) + 676 0 350860 82c DEC 35 86 0 85.91879 900.0 1.26027E-02 IBADF----------R---- bromine 86 (Br-86) + 677 0 350870 82c DEC 35 87 0 86.92069 900.0 1.24443E-02 IB-DF-----P----R---- bromine 87 (Br-87) + 678 0 350880 82c DEC 35 88 0 87.92411 900.0 4.20089E-02 IB-DF-----P----R---- bromine 88 (Br-88) + 679 0 350890 82c DEC 35 89 0 88.92643 900.0 1.58615E-01 IB-DF-----P----R---- bromine 89 (Br-89) + 680 0 350900 82c DEC 35 90 0 89.93065 900.0 3.64814E-01 IB-DF-----P----R---- bromine 90 (Br-90) + 681 0 350910 82c DEC 35 91 0 90.93397 900.0 1.28838E+00 IB-DF-----P----R---- bromine 91 (Br-91) + 682 0 350920 82c DEC 35 92 0 91.93931 900.0 2.02084E+00 IB-DF-----P----R---- bromine 92 (Br-92) + 683 0 350930 82c DEC 35 93 0 92.94303 900.0 6.79556E+00 IB-DF-----P----R---- bromine 93 (Br-93) + 684 0 350940 82c DEC 35 94 0 93.94867 900.0 9.90210E+00 IB-DF-----P----R---- bromine 94 (Br-94) + 685 0 350950 82c DEC 35 95 0 94.95290 900.0 1.38629E+01 IB--F----------R---- bromine 95 (Br-95) + 686 0 350960 82c DEC 35 96 0 95.95853 900.0 3.46574E+01 IB--F----------R---- bromine 96 (Br-96) + 687 0 360790 82c DEC 36 79 0 78.92007 900.0 5.49489E-06 IBA------------R---- krypton 79 (Kr-79) + 688 0 360810 82c DEC 36 81 0 80.91662 900.0 1.04593E-13 IBADF----------R---- krypton 81 (Kr-81) + 689 0 360811 82c DEC 36 81 1 80.91662 900.0 5.25112E-02 IBA-F----------R---- krypton 81m (Kr-81m) + 690 0 360831 82c DEC 36 83 1 82.91418 900.0 1.05214E-04 IBADF----------R---- krypton 83m (Kr-83m) + 691 0 360851 82c DEC 36 85 1 84.91254 900.0 4.29779E-05 IBADF----------R---- krypton 85m (Kr-85m) + 692 0 360870 82c DEC 36 87 0 86.91333 900.0 1.51408E-04 IBADF----------R---- krypton 87 (Kr-87) + 693 0 360880 82c DEC 36 88 0 87.91443 900.0 6.77961E-05 IBADF----------R---- krypton 88 (Kr-88) + 694 0 360890 82c DEC 36 89 0 88.91765 900.0 3.66745E-03 IBADF----------R---- krypton 89 (Kr-89) + 695 0 360900 82c DEC 36 90 0 89.91956 900.0 2.14464E-02 IB-DF----------R---- krypton 90 (Kr-90) + 696 0 360910 82c DEC 36 91 0 90.92348 900.0 8.08807E-02 IB-DF----------R---- krypton 91 (Kr-91) + 697 0 360920 82c DEC 36 92 0 91.92619 900.0 3.76710E-01 IB-DF----------R---- krypton 92 (Kr-92) + 698 0 360930 82c DEC 36 93 0 92.93123 900.0 5.38995E-01 IB-DF----------R---- krypton 93 (Kr-93) + 699 0 360940 82c DEC 36 94 0 93.93435 900.0 3.30070E+00 IB-DF-----P----R---- krypton 94 (Kr-94) + 700 0 360950 82c DEC 36 95 0 94.93988 900.0 6.08024E+00 IB-DF-----P----R---- krypton 95 (Kr-95) + 701 0 360960 82c DEC 36 96 0 95.94310 900.0 8.66434E+00 IB-DF-----P----R---- krypton 96 (Kr-96) + 702 0 360970 82c DEC 36 97 0 96.94854 900.0 1.10023E+01 IB--F-----P----R---- krypton 97 (Kr-97) + 703 0 360980 82c DEC 36 98 0 97.95196 900.0 1.50684E+01 IB--F-----P----R---- krypton 98 (Kr-98) + 704 0 360990 82c DEC 36 99 0 98.95760 900.0 1.73287E+01 IB--F-----P----R---- krypton 99 (Kr-99) + 705 0 370830 82c DEC 37 83 0 82.91508 900.0 9.30689E-08 IB-DF----------R---- rubidium 83 (Rb-83) + 706 0 370831 82c DEC 37 83 1 82.91508 900.0 8.88650E+01 IB--F----------R---- rubidium 83m (Rb-83m) + 707 0 370840 82c DEC 37 84 0 83.91437 900.0 2.39479E-07 IBADF----------R---- rubidium 84 (Rb-84) + 708 0 370841 82c DEC 37 84 1 83.91437 900.0 5.66297E-04 IB--F----------R---- rubidium 84m (Rb-84m) + 709 0 370861 82c DEC 37 86 1 85.91122 900.0 1.13631E-02 IBA-F----------R---- rubidium 86m (Rb-86m) + 710 0 370880 82c DEC 37 88 0 87.91130 900.0 6.49014E-04 IBADF----------R---- rubidium 88 (Rb-88) + 711 0 370890 82c DEC 37 89 0 88.91230 900.0 7.50159E-04 IBADF----------R---- rubidium 89 (Rb-89) + 712 0 370900 82c DEC 37 90 0 89.91482 900.0 4.41495E-03 IBADF----------R---- rubidium 90 (Rb-90) + 713 0 370901 82c DEC 37 90 1 89.91482 900.0 2.68662E-03 IB-DF----------R---- rubidium 90m (Rb-90m) + 714 0 370910 82c DEC 37 91 0 90.91652 900.0 1.18690E-02 IB-DF----------R---- rubidium 91 (Rb-91) + 715 0 370920 82c DEC 37 92 0 91.91974 900.0 1.54720E-01 IB-DF----------R---- rubidium 92 (Rb-92) + 716 0 370930 82c DEC 37 93 0 92.92205 900.0 1.19508E-01 IB-DF-----P----R---- rubidium 93 (Rb-93) + 717 0 370940 82c DEC 37 94 0 93.92648 900.0 2.56531E-01 IB-DF-----P----R---- rubidium 94 (Rb-94) + 718 0 370950 82c DEC 37 95 0 94.92929 900.0 1.81928E+00 IB-DF-----P----R---- rubidium 95 (Rb-95) + 719 0 370960 82c DEC 37 96 0 95.93433 900.0 3.48315E+00 IB-DF-----P----R---- rubidium 96 (Rb-96) + 720 0 370961 82c DEC 37 96 1 95.93433 900.0 3.46574E+00 IB-DF----------R---- rubidium 96m (Rb-96m) + 721 0 370970 82c DEC 37 97 0 96.93734 900.0 4.07974E+00 IB-DF-----P----R---- rubidium 97 (Rb-97) + 722 0 370980 82c DEC 37 98 0 97.94177 900.0 6.08024E+00 IB-DF-----P----R---- rubidium 98 (Rb-98) + 723 0 370981 82c DEC 37 98 1 97.94177 900.0 7.22028E+00 IB-DF----------R---- rubidium 98m (Rb-98m) + 724 0 370990 82c DEC 37 99 0 98.94539 900.0 1.37803E+01 IB-DF-----P----R---- rubidium 99 (Rb-99) + 725 0 371000 82c DEC 37 100 0 99.94982 900.0 1.35911E+01 IB--F-----P----R---- rubidium 100 (Rb-100) + 726 0 371010 82c DEC 37 101 0 100.95324 900.0 2.16608E+01 IB--F----------R---- rubidium 101 (Rb-101) + 727 0 380840 82c DEC 38 84 0 83.91346 900.0 stable IB-D-----------R---- strontium 84 (Sr-84) + 728 0 380850 82c DEC 38 85 0 84.91295 900.0 1.23709E-07 IB-DF----------R---- strontium 85 (Sr-85) + 729 0 380851 82c DEC 38 85 1 84.91295 900.0 1.70869E-04 IB--F----------R---- strontium 85m (Sr-85m) + 730 0 380871 82c DEC 38 87 1 86.90889 900.0 6.83739E-05 IBA-F----------R---- strontium 87m (Sr-87m) + 731 0 380910 82c DEC 38 91 0 90.91017 900.0 1.99524E-05 IBADF----------R---- strontium 91 (Sr-91) + 732 0 380920 82c DEC 38 92 0 91.91106 900.0 7.10483E-05 IBADF----------R---- strontium 92 (Sr-92) + 733 0 380930 82c DEC 38 93 0 92.91398 900.0 1.55631E-03 IBADF----------R---- strontium 93 (Sr-93) + 734 0 380940 82c DEC 38 94 0 93.91538 900.0 9.20514E-03 IB-DF----------R---- strontium 94 (Sr-94) + 735 0 380950 82c DEC 38 95 0 94.91931 900.0 2.90020E-02 IB-DF----------R---- strontium 95 (Sr-95) + 736 0 380960 82c DEC 38 96 0 95.92172 900.0 6.47801E-01 IB-DF----------R---- strontium 96 (Sr-96) + 737 0 380970 82c DEC 38 97 0 96.92615 900.0 1.61573E+00 IB-DF-----P----R---- strontium 97 (Sr-97) + 738 0 380980 82c DEC 38 98 0 97.92846 900.0 1.06148E+00 IB-DF----------R---- strontium 98 (Sr-98) + 739 0 380990 82c DEC 38 99 0 98.93319 900.0 2.56721E+00 IB-DF----------R---- strontium 99 (Sr-99) + 740 0 381000 82c DEC 38 100 0 99.93540 900.0 3.43142E+00 IB-DF-----P----R---- strontium 100 (Sr-100) + 741 0 381010 82c DEC 38 101 0 100.94013 900.0 5.87413E+00 IB-DF-----P----R---- strontium 101 (Sr-101) + 742 0 381020 82c DEC 38 102 0 101.94274 900.0 1.00456E+01 IB--F-----P----R---- strontium 102 (Sr-102) + 743 0 381030 82c DEC 38 103 0 102.94939 900.0 1.38629E+01 IB--F----------R---- strontium 103 (Sr-103) + 744 0 381040 82c DEC 38 104 0 103.95200 900.0 2.31049E+01 IB--F----------R---- strontium 104 (Sr-104) + 745 0 390880 82c DEC 39 88 0 87.90949 900.0 7.52372E-08 IBADF----------R---- yttrium 88 (Y-88) + 746 0 390881 82c DEC 39 88 1 87.90949 900.0 4.98667E+01 IB--F----------R---- yttrium 88m (Y-88m) + 747 0 390891 82c DEC 39 89 1 88.90585 900.0 4.42538E-02 IB-DF----------R---- yttrium 89m (Y-89m) + 748 0 390901 82c DEC 39 90 1 89.90715 900.0 6.03576E-05 IBA-F----------R---- yttrium 90m (Y-90m) + 749 0 390911 82c DEC 39 91 1 90.90734 900.0 2.32397E-04 IBADF----------R---- yttrium 91m (Y-91m) + 750 0 390920 82c DEC 39 92 0 91.90895 900.0 5.43901E-05 IBADF----------R---- yttrium 92 (Y-92) + 751 0 390930 82c DEC 39 93 0 92.90954 900.0 1.89136E-05 IBADF----------R---- yttrium 93 (Y-93) + 752 0 390931 82c DEC 39 93 1 92.90954 900.0 8.45301E-01 IB-DF----------R---- yttrium 93m (Y-93m) + 753 0 390940 82c DEC 39 94 0 93.91155 900.0 6.17778E-04 IBADF----------R---- yttrium 94 (Y-94) + 754 0 390950 82c DEC 39 95 0 94.91285 900.0 1.12160E-03 IBADF----------R---- yttrium 95 (Y-95) + 755 0 390960 82c DEC 39 96 0 95.91587 900.0 1.29803E-01 IBADF----------R---- yttrium 96 (Y-96) + 756 0 390961 82c DEC 39 96 1 95.91587 900.0 7.20527E-02 IB-DF----------R---- yttrium 96m (Y-96m) + 757 0 390970 82c DEC 39 97 0 96.91818 900.0 1.84839E-01 IB-DF-----P----R---- yttrium 97 (Y-97) + 758 0 390971 82c DEC 39 97 1 96.91818 900.0 5.92433E-01 IB-DF-----P----R---- yttrium 97m (Y-97m) + 759 1 390972 82c DEC 39 97 2 96.91818 900.0 4.88132E+00 -B--F----------R---- yttrium 97m (Y-97m) + 760 0 390980 82c DEC 39 98 0 97.92220 900.0 1.17483E+00 IB-DF-----P----R---- yttrium 98 (Y-98) + 761 0 390981 82c DEC 39 98 1 97.92220 900.0 3.46574E-01 IB--F-----P----R---- yttrium 98m (Y-98m) + 762 0 390990 82c DEC 39 99 0 98.92461 900.0 4.69294E-01 IB-DF-----P----R---- yttrium 99 (Y-99) + 763 0 391000 82c DEC 39 100 0 99.92773 900.0 9.43057E-01 IB-DF-----P----R---- yttrium 100 (Y-100) + 764 0 391001 82c DEC 39 100 1 99.92773 900.0 7.37391E-01 IB-DF----------R---- yttrium 100m (Y-100m) + 765 0 391010 82c DEC 39 101 0 100.93004 900.0 1.54033E+00 IB-DF----------R---- yttrium 101 (Y-101) + 766 0 391020 82c DEC 39 102 0 101.93366 900.0 2.31049E+00 IB-DF-----P----R---- yttrium 102 (Y-102) + 767 0 391021 82c DEC 39 102 1 101.93366 900.0 1.92541E+00 IB-DF-----P----R---- yttrium 102m (Y-102m) + 768 0 391030 82c DEC 39 103 0 102.93628 900.0 3.09441E+00 IB-DF-----P----R---- yttrium 103 (Y-103) + 769 0 391040 82c DEC 39 104 0 103.94091 900.0 5.33190E+00 IB-DF-----P----R---- yttrium 104 (Y-104) + 770 0 391050 82c DEC 39 105 0 104.94352 900.0 4.62098E+00 IB--F-----P----R---- yttrium 105 (Y-105) + 771 0 391060 82c DEC 39 106 0 105.95017 900.0 1.38629E+01 IB--F----------R---- yttrium 106 (Y-106) + 772 0 391070 82c DEC 39 107 0 106.95379 900.0 2.31049E+01 IB--F----------R---- yttrium 107 (Y-107) + 773 0 400880 82c DEC 40 88 0 87.91020 900.0 9.61935E-08 IBA------------R---- zirconium 88 (Zr-88) + 774 0 400890 82c DEC 40 89 0 88.90887 900.0 2.45525E-06 IBA------------R---- zirconium 89 (Zr-89) + 775 0 400901 82c DEC 40 90 1 89.90473 900.0 8.57643E-01 IB-DF----------R---- zirconium 90m (Zr-90m) + 776 0 400970 82c DEC 40 97 0 96.91092 900.0 1.14991E-05 IBADF----------R---- zirconium 97 (Zr-97) + 777 0 400980 82c DEC 40 98 0 97.91272 900.0 2.25781E-02 IB-DF----------R---- zirconium 98 (Zr-98) + 778 0 400990 82c DEC 40 99 0 98.91655 900.0 3.15067E-01 IB-DF----------R---- zirconium 99 (Zr-99) + 779 0 401000 82c DEC 40 100 0 99.91775 900.0 9.76264E-02 IB-DF----------R---- zirconium 100 (Zr-100) + 780 0 401010 82c DEC 40 101 0 100.92096 900.0 3.01368E-01 IB-DF----------R---- zirconium 101 (Zr-101) + 781 0 401020 82c DEC 40 102 0 101.92257 900.0 2.39016E-01 IB-DF----------R---- zirconium 102 (Zr-102) + 782 0 401030 82c DEC 40 103 0 102.92619 900.0 5.33190E-01 IB-DF----------R---- zirconium 103 (Zr-103) + 783 0 401040 82c DEC 40 104 0 103.92880 900.0 5.77623E-01 IB-DF----------R---- zirconium 104 (Zr-104) + 784 0 401050 82c DEC 40 105 0 104.93243 900.0 1.15525E+00 IB-DF-----P----R---- zirconium 105 (Zr-105) + 785 0 401060 82c DEC 40 106 0 105.93504 900.0 7.70164E-01 IB-DF-----P----R---- zirconium 106 (Zr-106) + 786 0 401070 82c DEC 40 107 0 106.94068 900.0 2.88811E+00 IB-DF-----P----R---- zirconium 107 (Zr-107) + 787 0 401080 82c DEC 40 108 0 107.94430 900.0 8.66434E+00 IB--F----------R---- zirconium 108 (Zr-108) + 788 0 401090 82c DEC 40 109 0 108.94893 900.0 1.15525E+01 IB--F----------R---- zirconium 109 (Zr-109) + 789 0 410900 82c DEC 41 90 0 89.91129 900.0 1.31968E-05 IBA------------R---- niobium 90 (Nb-90) + 790 0 410910 82c DEC 41 91 0 90.90704 900.0 3.23007E-11 IBAD-----------R---- niobium 91 (Nb-91) + 791 0 410911 82c DEC 41 91 1 90.90704 900.0 1.31733E-07 IB-D-----------R---- niobium 91m (Nb-91m) + 792 0 410920 82c DEC 41 92 0 91.90723 900.0 6.27555E-16 IBA------------R---- niobium 92 (Nb-92) + 793 0 410931 82c DEC 41 93 1 92.90642 900.0 1.36259E-09 IB-DF----------R---- niobium 93m (Nb-93m) + 794 0 410941 82c DEC 41 94 1 93.90731 900.0 1.84544E-03 IBA-F----------R---- niobium 94m (Nb-94m) + 795 0 410951 82c DEC 41 95 1 94.90680 900.0 2.22231E-06 IBADF----------R---- niobium 95m (Nb-95m) + 796 0 410960 82c DEC 41 96 0 95.90810 900.0 8.24586E-06 IBA-F----------R---- niobium 96 (Nb-96) + 797 0 410970 82c DEC 41 97 0 96.90809 900.0 1.60228E-04 IBADF----------R---- niobium 97 (Nb-97) + 798 0 410971 82c DEC 41 97 1 96.90809 900.0 1.31527E-02 IB-DF----------R---- niobium 97m (Nb-97m) + 799 0 410980 82c DEC 41 98 0 97.91030 900.0 2.42359E-01 IBADF----------R---- niobium 98 (Nb-98) + 800 0 410981 82c DEC 41 98 1 97.91030 900.0 2.25194E-04 IB--F----------R---- niobium 98m (Nb-98m) + 801 0 410990 82c DEC 41 99 0 98.91160 900.0 4.62098E-02 IBADF----------R---- niobium 99 (Nb-99) + 802 0 410991 82c DEC 41 99 1 98.91160 900.0 4.44325E-03 IB-DF----------R---- niobium 99m (Nb-99m) + 803 0 411000 82c DEC 41 100 0 99.91422 900.0 4.62098E-01 IBADF----------R---- niobium 100 (Nb-100) + 804 0 411001 82c DEC 41 100 1 99.91422 900.0 2.39016E-01 IB--F----------R---- niobium 100m (Nb-100m) + 805 0 411010 82c DEC 41 101 0 100.91491 900.0 9.76264E-02 IB-DF----------R---- niobium 101 (Nb-101) + 806 0 411020 82c DEC 41 102 0 101.91853 900.0 5.33190E-01 IB-DF----------R---- niobium 102 (Nb-102) + 807 0 411021 82c DEC 41 102 1 101.91853 900.0 1.61197E-01 IB--F----------R---- niobium 102m (Nb-102m) + 808 0 411030 82c DEC 41 103 0 102.91913 900.0 4.62098E-01 IB-DF----------R---- niobium 103 (Nb-103) + 809 0 411040 82c DEC 41 104 0 103.92275 900.0 1.41459E-01 IB-DF-----P----R---- niobium 104 (Nb-104) + 810 0 411041 82c DEC 41 104 1 103.92275 900.0 7.37391E-01 IB--F-----P----R---- niobium 104m (Nb-104m) + 811 0 411050 82c DEC 41 105 0 104.92436 900.0 2.34965E-01 IB-DF-----P----R---- niobium 105 (Nb-105) + 812 0 411060 82c DEC 41 106 0 105.92798 900.0 7.53421E-01 IB-DF-----P----R---- niobium 106 (Nb-106) + 813 0 411070 82c DEC 41 107 0 106.93059 900.0 2.31049E+00 IB-DF-----P----R---- niobium 107 (Nb-107) + 814 0 411080 82c DEC 41 108 0 107.93522 900.0 3.59144E+00 IB-DF-----P----R---- niobium 108 (Nb-108) + 815 0 411090 82c DEC 41 109 0 108.93783 900.0 3.64814E+00 IB-DF-----P----R---- niobium 109 (Nb-109) + 816 0 411100 82c DEC 41 110 0 109.94246 900.0 4.07734E+00 IB--F-----P----R---- niobium 110 (Nb-110) + 817 0 411110 82c DEC 41 111 0 110.94609 900.0 8.66434E+00 IB--F----------R---- niobium 111 (Nb-111) + 818 0 411120 82c DEC 41 112 0 111.95072 900.0 1.15525E+01 IB--F----------R---- niobium 112 (Nb-112) + 819 0 420910 82c DEC 42 91 0 90.91178 900.0 7.45801E-04 IBA------------R---- molybdenum 91 (Mo-91) + 820 0 420930 82c DEC 42 93 0 92.90682 900.0 7.29322E-12 IBAD-----------R---- molybdenum 93 (Mo-93) + 821 0 420931 82c DEC 42 93 1 92.90682 900.0 2.81082E-05 IBA------------R---- molybdenum 93m (Mo-93m) + 822 0 421010 82c DEC 42 101 0 100.90987 900.0 7.90722E-04 IBADF----------R---- molybdenum 101 (Mo-101) + 823 0 421020 82c DEC 42 102 0 101.91046 900.0 1.02234E-03 IBADF----------R---- molybdenum 102 (Mo-102) + 824 0 421030 82c DEC 42 103 0 102.91308 900.0 1.02084E-02 IBADF----------R---- molybdenum 103 (Mo-103) + 825 0 421040 82c DEC 42 104 0 103.91367 900.0 1.15525E-02 IBADF----------R---- molybdenum 104 (Mo-104) + 826 0 421050 82c DEC 42 105 0 104.91730 900.0 1.94704E-02 IBADF----------R---- molybdenum 105 (Mo-105) + 827 0 421060 82c DEC 42 106 0 105.91789 900.0 7.93983E-02 IB-DF----------R---- molybdenum 106 (Mo-106) + 828 0 421070 82c DEC 42 107 0 106.92151 900.0 1.98042E-01 IB-DF----------R---- molybdenum 107 (Mo-107) + 829 0 421080 82c DEC 42 108 0 107.92312 900.0 6.35915E-01 IB-DF----------R---- molybdenum 108 (Mo-108) + 830 0 421090 82c DEC 42 109 0 108.92775 900.0 1.38629E+00 IB-DF-----P----R---- molybdenum 109 (Mo-109) + 831 0 421100 82c DEC 42 110 0 109.92935 900.0 2.31049E+00 IB-DF----------R---- molybdenum 110 (Mo-110) + 832 0 421110 82c DEC 42 111 0 110.93499 900.0 1.38629E+00 IB-DF-----P----R---- molybdenum 111 (Mo-111) + 833 0 421120 82c DEC 42 112 0 111.93760 900.0 6.93147E-01 IB-DF-----P----R---- molybdenum 112 (Mo-112) + 834 0 421130 82c DEC 42 113 0 112.94223 900.0 6.93147E+00 IB--F----------R---- molybdenum 113 (Mo-113) + 835 0 421140 82c DEC 42 114 0 113.94485 900.0 8.66434E+00 IB--F----------R---- molybdenum 114 (Mo-114) + 836 0 421150 82c DEC 42 115 0 114.95049 900.0 1.15525E+01 IB--F----------R---- molybdenum 115 (Mo-115) + 837 0 430970 82c DEC 43 97 0 96.90638 900.0 8.44788E-15 IBA------------R---- technetium 97 (Tc-97) + 838 0 430980 82c DEC 43 98 0 97.90728 900.0 5.10813E-15 IBA-F----------R---- technetium 98 (Tc-98) + 839 0 430991 82c DEC 43 99 1 98.90626 900.0 3.20544E-05 IB-DF----------R---- technetium 99m (Tc-99m) + 840 0 431000 82c DEC 43 100 0 99.90766 900.0 4.48349E-02 IBA-F----------R---- technetium 100 (Tc-100) + 841 0 431010 82c DEC 43 101 0 100.90684 900.0 8.13553E-04 IBADF----------R---- technetium 101 (Tc-101) + 842 0 431020 82c DEC 43 102 0 101.90946 900.0 1.31278E-01 IBADF----------R---- technetium 102 (Tc-102) + 843 0 431021 82c DEC 43 102 1 101.90946 900.0 2.65574E-03 IB--F----------R---- technetium 102m (Tc-102m) + 844 0 431030 82c DEC 43 103 0 102.90904 900.0 1.27887E-02 IBADF----------R---- technetium 103 (Tc-103) + 845 0 431040 82c DEC 43 104 0 103.91166 900.0 6.31282E-04 IBADF----------R---- technetium 104 (Tc-104) + 846 0 431050 82c DEC 43 105 0 104.91124 900.0 1.52006E-03 IBADF----------R---- technetium 105 (Tc-105) + 847 0 431060 82c DEC 43 106 0 105.91386 900.0 1.94704E-02 IBADF----------R---- technetium 106 (Tc-106) + 848 0 431070 82c DEC 43 107 0 106.91546 900.0 3.26956E-02 IB-DF----------R---- technetium 107 (Tc-107) + 849 0 431080 82c DEC 43 108 0 107.91807 900.0 1.34071E-01 IB-DF----------R---- technetium 108 (Tc-108) + 850 0 431090 82c DEC 43 109 0 108.91968 900.0 8.05985E-01 IB-DF-----P----R---- technetium 109 (Tc-109) + 851 0 431100 82c DEC 43 110 0 109.92431 900.0 7.53421E-01 IB-DF-----P----R---- technetium 110 (Tc-110) + 852 0 431110 82c DEC 43 111 0 110.92591 900.0 2.39016E+00 IB-DF----------R---- technetium 111 (Tc-111) + 853 0 431120 82c DEC 43 112 0 111.92953 900.0 2.39016E+00 IB-DF-----P----R---- technetium 112 (Tc-112) + 854 0 431130 82c DEC 43 113 0 112.93215 900.0 5.33190E+00 IB-DF-----P----R---- technetium 113 (Tc-113) + 855 0 431140 82c DEC 43 114 0 113.93678 900.0 3.46574E+00 IB-DF-----P----R---- technetium 114 (Tc-114) + 856 0 431150 82c DEC 43 115 0 114.93939 900.0 2.56721E+00 IB-DF-----P----R---- technetium 115 (Tc-115) + 857 0 431160 82c DEC 43 116 0 115.94402 900.0 5.77623E+00 IB--F-----P----R---- technetium 116 (Tc-116) + 858 0 431170 82c DEC 43 117 0 116.94663 900.0 1.73287E+01 IB--F----------R---- technetium 117 (Tc-117) + 859 0 431180 82c DEC 43 118 0 117.95126 900.0 2.31049E+01 IB--F----------R---- technetium 118 (Tc-118) + 860 0 440980 82c DEC 44 98 0 97.90526 900.0 stable IBAD-----------R---- ruthenium 98 (Ru-98) + 861 0 440990 82c DEC 44 99 0 98.90595 900.0 stable IBAD-----------R---- ruthenium 99 (Ru-99) + 862 0 441031 82c DEC 44 103 1 102.90602 900.0 4.10146E+02 IB--F----------R---- ruthenium 103m (Ru-103m) + 863 0 441070 82c DEC 44 107 0 106.90941 900.0 3.08065E-03 IBADF----------R---- ruthenium 107 (Ru-107) + 864 0 441080 82c DEC 44 108 0 107.91000 900.0 2.53900E-03 IBADF----------R---- ruthenium 108 (Ru-108) + 865 0 441090 82c DEC 44 109 0 108.91363 900.0 2.00912E-02 IBADF----------R---- ruthenium 109 (Ru-109) + 866 0 441100 82c DEC 44 110 0 109.91422 900.0 5.75704E-02 IB-DF----------R---- ruthenium 110 (Ru-110) + 867 0 441110 82c DEC 44 111 0 110.91784 900.0 3.26956E-01 IB-DF----------R---- ruthenium 111 (Ru-111) + 868 0 441120 82c DEC 44 112 0 111.91945 900.0 3.96084E-01 IB-DF----------R---- ruthenium 112 (Ru-112) + 869 0 441130 82c DEC 44 113 0 112.92206 900.0 8.66434E-01 IB-DF----------R---- ruthenium 113 (Ru-113) + 870 0 441131 82c DEC 44 113 1 112.92206 900.0 1.35911E+00 IB--F----------R---- ruthenium 113m (Ru-113m) + 871 0 441140 82c DEC 44 114 0 113.92467 900.0 1.30782E+00 IB-DF----------R---- ruthenium 114 (Ru-114) + 872 0 441150 82c DEC 44 115 0 114.92830 900.0 9.90210E-01 IB-DF-----P----R---- ruthenium 115 (Ru-115) + 873 0 441160 82c DEC 44 116 0 115.93091 900.0 4.07734E-01 IB-DF-----P----R---- ruthenium 116 (Ru-116) + 874 0 441170 82c DEC 44 117 0 116.93554 900.0 2.03867E+00 IB-DF-----P----R---- ruthenium 117 (Ru-117) + 875 0 441180 82c DEC 44 118 0 117.93714 900.0 9.90210E-01 IB-DF-----P----R---- ruthenium 118 (Ru-118) + 876 0 441190 82c DEC 44 119 0 118.94177 900.0 3.64814E+00 IB--F-----P----R---- ruthenium 119 (Ru-119) + 877 0 441200 82c DEC 44 120 0 119.94539 900.0 8.66434E+00 IB--F----------R---- ruthenium 120 (Ru-120) + 878 0 451010 82c DEC 45 101 0 100.90583 900.0 6.86407E-09 IBA------------R---- rhodium 101 (Rh-101) + 879 0 451020 82c DEC 45 102 0 101.90643 900.0 7.56843E-09 IBA------------R---- rhodium 102 (Rh-102) + 880 0 451031 82c DEC 45 103 1 102.90602 900.0 2.05871E-04 IB-DF----------R---- rhodium 103m (Rh-103m) + 881 0 451040 82c DEC 45 104 0 103.90661 900.0 1.63865E-02 IBADF----------R---- rhodium 104 (Rh-104) + 882 0 451041 82c DEC 45 104 1 103.90661 900.0 2.66186E-03 IBA-F----------R---- rhodium 104m (Rh-104m) + 883 0 451051 82c DEC 45 105 1 104.90519 900.0 1.73287E-02 IB-DF----------R---- rhodium 105m (Rh-105m) + 884 0 451060 82c DEC 45 106 0 105.90680 900.0 2.30281E-02 IBADF----------R---- rhodium 106 (Rh-106) + 885 0 451061 82c DEC 45 106 1 105.90780 900.0 8.75186E-05 IBA-F----------R---- rhodium 106m (Rh-106m) + 886 0 451070 82c DEC 45 107 0 106.90638 900.0 5.32371E-04 IBADF----------R---- rhodium 107 (Rh-107) + 887 0 451080 82c DEC 45 108 0 107.90900 900.0 4.12588E-02 IBADF----------R---- rhodium 108 (Rh-108) + 888 0 451081 82c DEC 45 108 1 107.90900 900.0 1.92541E-03 IB--F----------R---- rhodium 108m (Rh-108m) + 889 0 451090 82c DEC 45 109 0 108.90858 900.0 8.66434E-03 IBADF----------R---- rhodium 109 (Rh-109) + 890 0 451100 82c DEC 45 110 0 109.91120 900.0 2.43210E-02 IBADF----------R---- rhodium 110 (Rh-110) + 891 0 451101 82c DEC 45 110 1 109.91120 900.0 2.16608E-01 IB--F----------R---- rhodium 110m (Rh-110m) + 892 0 451110 82c DEC 45 111 0 110.91179 900.0 5.77623E-02 IB-DF----------R---- rhodium 111 (Rh-111) + 893 0 451120 82c DEC 45 112 0 111.91440 900.0 3.30070E-01 IB-DF----------R---- rhodium 112 (Rh-112) + 894 0 451121 82c DEC 45 112 1 111.91440 900.0 1.01933E-01 IB--F----------R---- rhodium 112m (Rh-112m) + 895 0 451130 82c DEC 45 113 0 112.91601 900.0 2.47553E-01 IB-DF----------R---- rhodium 113 (Rh-113) + 896 0 451140 82c DEC 45 114 0 113.91862 900.0 3.74674E-01 IB-DF----------R---- rhodium 114 (Rh-114) + 897 0 451141 82c DEC 45 114 1 113.91862 900.0 3.74674E-01 IB--F----------R---- rhodium 114m (Rh-114m) + 898 0 451150 82c DEC 45 115 0 114.92023 900.0 7.00149E-01 IB-DF----------R---- rhodium 115 (Rh-115) + 899 0 451160 82c DEC 45 116 0 115.92385 900.0 1.01933E+00 IB-DF----------R---- rhodium 116 (Rh-116) + 900 0 451161 82c DEC 45 116 1 115.92385 900.0 1.21605E+00 IB--F----------R---- rhodium 116m (Rh-116m) + 901 0 451170 82c DEC 45 117 0 116.92646 900.0 1.57533E+00 IB-DF----------R---- rhodium 117 (Rh-117) + 902 0 451180 82c DEC 45 118 0 117.93008 900.0 2.16608E+00 IB-DF-----P----R---- rhodium 118 (Rh-118) + 903 0 451190 82c DEC 45 119 0 118.93169 900.0 2.31049E+00 IB-DF----------R---- rhodium 119 (Rh-119) + 904 0 451200 82c DEC 45 120 0 119.93632 900.0 4.07734E+00 IB-DF-----P----R---- rhodium 120 (Rh-120) + 905 0 451210 82c DEC 45 121 0 120.93792 900.0 2.77259E+00 IB--F-----P----R---- rhodium 121 (Rh-121) + 906 0 451220 82c DEC 45 122 0 121.94356 900.0 1.38629E+01 IB--F----------R---- rhodium 122 (Rh-122) + 907 0 461030 82c DEC 46 103 0 102.90602 900.0 4.72470E-07 IBA------------R---- palladium 103 (Pd-103) + 908 0 461040 82c DEC 46 104 0 103.90359 900.0 stable IBAD-----------R---- palladium 104 (Pd-104) + 909 0 461071 82c DEC 46 107 1 106.90537 900.0 3.25421E-02 IBA-F----------R---- palladium 107m (Pd-107m) + 910 0 461090 82c DEC 46 109 0 108.90556 900.0 1.41783E-05 IBADF----------R---- palladium 109 (Pd-109) + 911 0 461091 82c DEC 46 109 1 108.90556 900.0 2.46321E-03 IBADF----------R---- palladium 109m (Pd-109m) + 912 0 461110 82c DEC 46 111 0 110.90776 900.0 4.93695E-04 IBADF----------R---- palladium 111 (Pd-111) + 913 0 461111 82c DEC 46 111 1 110.90776 900.0 3.50074E-05 IBA-F----------R---- palladium 111m (Pd-111m) + 914 0 461120 82c DEC 46 112 0 111.90734 900.0 9.48477E-06 IBADF----------R---- palladium 112 (Pd-112) + 915 0 461130 82c DEC 46 113 0 112.91097 900.0 7.61700E-03 IBADF----------R---- palladium 113 (Pd-113) + 916 0 461131 82c DEC 46 113 1 112.91097 900.0 2.31049E+00 IB--F----------R---- palladium 113m (Pd-113m) + 917 0 461140 82c DEC 46 114 0 113.91055 900.0 4.77374E-03 IBADF----------R---- palladium 114 (Pd-114) + 918 0 461150 82c DEC 46 115 0 114.91417 900.0 2.77259E-02 IB-DF----------R---- palladium 115 (Pd-115) + 919 0 461151 82c DEC 46 115 1 114.91417 900.0 1.38629E-02 IB-DF----------R---- palladium 115m (Pd-115m) + 920 0 461160 82c DEC 46 116 0 115.91376 900.0 5.87413E-02 IB-DF----------R---- palladium 116 (Pd-116) + 921 0 461170 82c DEC 46 117 0 116.91738 900.0 1.61197E-01 IB-DF----------R---- palladium 117 (Pd-117) + 922 0 461171 82c DEC 46 117 1 116.91738 900.0 3.62904E+01 IB--F----------R---- palladium 117m (Pd-117m) + 923 0 461180 82c DEC 46 118 0 117.91899 900.0 3.64814E-01 IB-DF----------R---- palladium 118 (Pd-118) + 924 0 461190 82c DEC 46 119 0 118.92362 900.0 7.53421E-01 IB-DF----------R---- palladium 119 (Pd-119) + 925 0 461200 82c DEC 46 120 0 119.92421 900.0 1.38629E+00 IB-DF----------R---- palladium 120 (Pd-120) + 926 0 461210 82c DEC 46 121 0 120.92783 900.0 1.15525E+00 IB-DF-----P----R---- palladium 121 (Pd-121) + 927 0 461220 82c DEC 46 122 0 121.93045 900.0 2.31049E+00 IB-DF----------R---- palladium 122 (Pd-122) + 928 0 461230 82c DEC 46 123 0 122.93508 900.0 3.46574E+00 IB--F----------R---- palladium 123 (Pd-123) + 929 0 461240 82c DEC 46 124 0 123.93668 900.0 6.93147E+00 IB--F----------R---- palladium 124 (Pd-124) + 930 0 471070 82c DEC 47 107 0 106.90537 900.0 stable IBAD-----------R---- silver 107 (Ag-107) + 931 0 471080 82c DEC 47 108 0 107.90597 900.0 4.84990E-03 IBADF----------R---- silver 108 (Ag-108) + 932 0 471081 82c DEC 47 108 1 107.90597 900.0 5.01485E-11 IB--F----------R---- silver 108m (Ag-108m) + 933 0 471091 82c DEC 47 109 1 108.90455 900.0 1.74596E-02 IB-DF----------R---- silver 109m (Ag-109m) + 934 0 471100 82c DEC 47 110 0 109.90615 900.0 2.82226E-02 IBADF----------R---- silver 110 (Ag-110) + 935 0 471111 82c DEC 47 111 1 110.90574 900.0 1.06967E-02 IB-DF----------R---- silver 111m (Ag-111m) + 936 0 471120 82c DEC 47 112 0 111.90734 900.0 6.15147E-05 IBADF----------R---- silver 112 (Ag-112) + 937 0 471130 82c DEC 47 113 0 112.90693 900.0 3.58549E-05 IBADF----------R---- silver 113 (Ag-113) + 938 0 471131 82c DEC 47 113 1 112.90693 900.0 1.00895E-02 IB-DF----------R---- silver 113m (Ag-113m) + 939 0 471140 82c DEC 47 114 0 113.90853 900.0 1.50684E-01 IBADF----------R---- silver 114 (Ag-114) + 940 0 471141 82c DEC 47 114 1 113.90853 900.0 4.62098E+02 IB--F----------R---- silver 114m (Ag-114m) + 941 0 471150 82c DEC 47 115 0 114.90913 900.0 5.77623E-04 IBADF----------R---- silver 115 (Ag-115) + 942 0 471151 82c DEC 47 115 1 114.90913 900.0 3.72660E-02 IB-DF----------R---- silver 115m (Ag-115m) + 943 0 471160 82c DEC 47 116 0 115.91174 900.0 2.92467E-03 IBADF----------R---- silver 116 (Ag-116) + 944 0 471161 82c DEC 47 116 1 115.91174 900.0 8.05985E-02 IB--F----------R---- silver 116m (Ag-116m) + 945 0 471170 82c DEC 47 117 0 116.91133 900.0 9.41776E-03 IB-DF----------R---- silver 117 (Ag-117) + 946 0 471171 82c DEC 47 117 1 116.91133 900.0 1.29803E-01 IB-DF----------R---- silver 117m (Ag-117m) + 947 0 471180 82c DEC 47 118 0 117.91495 900.0 1.84348E-01 IB-DF----------R---- silver 118 (Ag-118) + 948 0 471181 82c DEC 47 118 1 117.91495 900.0 3.46574E-01 IB-DF----------R---- silver 118m (Ag-118m) + 949 0 471190 82c DEC 47 119 0 118.91555 900.0 1.15525E-01 IB-DF----------R---- silver 119 (Ag-119) + 950 0 471191 82c DEC 47 119 1 118.91555 900.0 3.30070E-01 IB-DF----------R---- silver 119m (Ag-119m) + 951 0 471200 82c DEC 47 120 0 119.91917 900.0 5.63534E-01 IB-DF-----P----R---- silver 120 (Ag-120) + 952 0 471201 82c DEC 47 120 1 119.91917 900.0 1.86832E+00 IB-DF----------R---- silver 120m (Ag-120m) + 953 0 471210 82c DEC 47 121 0 120.91976 900.0 8.88650E-01 IB-DF----------R---- silver 121 (Ag-121) + 954 0 471220 82c DEC 47 122 0 121.92339 900.0 1.31030E+00 IB-DF----------R---- silver 122 (Ag-122) + 955 0 471221 82c DEC 47 122 1 121.92339 900.0 4.62098E-01 IB--F----------R---- silver 122m (Ag-122m) + 956 0 471230 82c DEC 47 123 0 122.92499 900.0 2.31049E+00 IB-DF----------R---- silver 123 (Ag-123) + 957 0 471240 82c DEC 47 124 0 123.92861 900.0 4.02993E+00 IB-DF-----P----R---- silver 124 (Ag-124) + 958 0 471241 82c DEC 47 124 1 123.92861 900.0 3.46574E+00 IB--F----------R---- silver 124m (Ag-124m) + 959 0 471250 82c DEC 47 125 0 124.93022 900.0 4.17559E+00 IB--F----------R---- silver 125 (Ag-125) + 960 0 471260 82c DEC 47 126 0 125.93485 900.0 6.47801E+00 IB--F----------R---- silver 126 (Ag-126) + 961 0 471270 82c DEC 47 127 0 126.93645 900.0 8.77401E+00 IB--F----------R---- silver 127 (Ag-127) + 962 0 471280 82c DEC 47 128 0 127.94108 900.0 1.19508E+01 IB--F----------R---- silver 128 (Ag-128) + 963 0 471290 82c DEC 47 129 0 128.94369 900.0 1.57533E+01 IB--F----------R---- silver 129 (Ag-129) + 964 0 471300 82c DEC 47 130 0 129.95034 900.0 1.38629E+01 IB--F----------R---- silver 130 (Ag-130) + 965 0 481080 82c DEC 48 108 0 107.90395 900.0 5.35720E-26 IBAD-----------R---- cadmium 108 (Cd-108) + 966 0 481090 82c DEC 48 109 0 108.90455 900.0 1.73685E-08 IBA------------R---- cadmium 109 (Cd-109) + 967 0 481111 82c DEC 48 111 1 110.90372 900.0 2.37999E-04 IBADF----------R---- cadmium 111m (Cd-111m) + 968 0 481131 82c DEC 48 113 1 112.90390 900.0 1.55780E-09 IBADF----------R---- cadmium 113m (Cd-113m) + 969 0 481150 82c DEC 48 115 0 114.90510 900.0 3.60159E-06 IBADF----------R---- cadmium 115 (Cd-115) + 970 0 481170 82c DEC 48 117 0 116.90730 900.0 7.73257E-05 IBADF----------R---- cadmium 117 (Cd-117) + 971 0 481171 82c DEC 48 117 1 116.90730 900.0 5.73038E-05 IBADF----------R---- cadmium 117m (Cd-117m) + 972 0 481180 82c DEC 48 118 0 117.90688 900.0 2.29671E-04 IBADF----------R---- cadmium 118 (Cd-118) + 973 0 481190 82c DEC 48 119 0 118.90950 900.0 4.29459E-03 IBADF----------R---- cadmium 119 (Cd-119) + 974 0 481191 82c DEC 48 119 1 118.90950 900.0 5.25112E-03 IB-DF----------R---- cadmium 119m (Cd-119m) + 975 0 481200 82c DEC 48 120 0 119.91009 900.0 1.36446E-02 IBADF----------R---- cadmium 120 (Cd-120) + 976 0 481210 82c DEC 48 121 0 120.91270 900.0 5.13442E-02 IBADF----------R---- cadmium 121 (Cd-121) + 977 0 481211 82c DEC 48 121 1 120.91270 900.0 8.35117E-02 IB-DF----------R---- cadmium 121m (Cd-121m) + 978 0 481220 82c DEC 48 122 0 121.91330 900.0 1.32280E-01 IBADF----------R---- cadmium 122 (Cd-122) + 979 0 481230 82c DEC 48 123 0 122.91692 900.0 3.30070E-01 IBADF----------R---- cadmium 123 (Cd-123) + 980 0 481231 82c DEC 48 123 1 122.91692 900.0 3.80850E-01 IB-DF----------R---- cadmium 123m (Cd-123m) + 981 0 481240 82c DEC 48 124 0 123.91752 900.0 5.54518E-01 IBADF----------R---- cadmium 124 (Cd-124) + 982 0 481250 82c DEC 48 125 0 124.92114 900.0 1.01933E+00 IBADF----------R---- cadmium 125 (Cd-125) + 983 0 481251 82c DEC 48 125 1 124.92114 900.0 1.44406E+00 IB-DF----------R---- cadmium 125m (Cd-125m) + 984 0 481260 82c DEC 48 126 0 125.92274 900.0 1.34592E+00 IB-DF----------R---- cadmium 126 (Cd-126) + 985 0 481270 82c DEC 48 127 0 126.92636 900.0 1.87337E+00 IB-DF----------R---- cadmium 127 (Cd-127) + 986 0 481280 82c DEC 48 128 0 127.92797 900.0 2.47553E+00 IB-DF----------R---- cadmium 128 (Cd-128) + 987 0 481290 82c DEC 48 129 0 128.93260 900.0 2.86424E+00 IB-DF----------R---- cadmium 129 (Cd-129) + 988 0 481291 82c DEC 48 129 1 128.93260 900.0 6.66488E+00 IB-DF----------R---- cadmium 129m (Cd-129m) + 989 0 481300 82c DEC 48 130 0 129.93420 900.0 4.27869E+00 IB-DF-----P----R---- cadmium 130 (Cd-130) + 990 0 481310 82c DEC 48 131 0 130.94085 900.0 1.01933E+01 IB--F-----P----R---- cadmium 131 (Cd-131) + 991 0 481320 82c DEC 48 132 0 131.94548 900.0 7.14585E+00 IB--F-----P----R---- cadmium 132 (Cd-132) + 992 0 491110 82c DEC 49 111 0 110.90473 900.0 2.86019E-06 IBA------------R---- indium 111 (In-111) + 993 0 491120 82c DEC 49 112 0 111.90533 900.0 7.85881E-04 IBA------------R---- indium 112 (In-112) + 994 0 491131 82c DEC 49 113 1 112.90390 900.0 1.16135E-04 IB-DF----------R---- indium 113m (In-113m) + 995 0 491140 82c DEC 49 114 0 113.90450 900.0 9.64043E-03 IBADF----------R---- indium 114 (In-114) + 996 0 491141 82c DEC 49 114 1 113.90450 900.0 1.60451E-07 IBADF----------R---- indium 114m (In-114m) + 997 1 491142 82c DEC 49 114 2 113.90450 900.0 1.61197E+01 -B--F----------R---- indium 114m (In-114m) + 998 0 491151 82c DEC 49 115 1 114.90409 900.0 4.29204E-05 IB-DF----------R---- indium 115m (In-115m) + 999 0 491160 82c DEC 49 116 0 115.90569 900.0 4.88132E-02 IBA-F----------R---- indium 116 (In-116) + 1000 0 491161 82c DEC 49 116 1 115.90569 900.0 2.11583E-04 IB-DF----------R---- indium 116m (In-116m) + 1001 1 491162 82c DEC 49 116 2 115.90569 900.0 3.19423E-01 -B--F----------R---- indium 116m (In-116m) + 1002 0 491170 82c DEC 49 117 0 116.90427 900.0 2.67418E-04 IBADF----------R---- indium 117 (In-117) + 1003 0 491171 82c DEC 49 117 1 116.90427 900.0 9.94187E-05 IB-DF----------R---- indium 117m (In-117m) + 1004 0 491180 82c DEC 49 118 0 117.90587 900.0 1.38629E-01 IBADF----------R---- indium 118 (In-118) + 1005 0 491181 82c DEC 49 118 1 117.90587 900.0 2.59606E-03 IB-DF----------R---- indium 118m (In-118m) + 1006 1 491182 82c DEC 49 118 2 117.90587 900.0 8.15467E-02 -B--F----------R---- indium 118m (In-118m) + 1007 0 491190 82c DEC 49 119 0 118.90546 900.0 4.81352E-03 IBADF----------R---- indium 119 (In-119) + 1008 0 491191 82c DEC 49 119 1 118.90546 900.0 6.41803E-04 IB-DF----------R---- indium 119m (In-119m) + 1009 0 491200 82c DEC 49 120 0 119.90807 900.0 2.25048E-01 IBADF----------R---- indium 120 (In-120) + 1010 0 491201 82c DEC 49 120 1 119.90807 900.0 1.50032E-02 IB--F----------R---- indium 120m (In-120m) + 1011 1 491202 82c DEC 49 120 2 119.90807 900.0 1.46543E-02 -B--F----------R---- indium 120m (In-120m) + 1012 0 491210 82c DEC 49 121 0 120.90766 900.0 3.00064E-02 IBADF----------R---- indium 121 (In-121) + 1013 0 491211 82c DEC 49 121 1 120.90766 900.0 2.97744E-03 IB-DF----------R---- indium 121m (In-121m) + 1014 0 491220 82c DEC 49 122 0 121.91027 900.0 4.62098E-01 IBADF----------R---- indium 122 (In-122) + 1015 0 491221 82c DEC 49 122 1 121.91027 900.0 6.41803E-02 IB--F----------R---- indium 122m (In-122m) + 1016 1 491222 82c DEC 49 122 2 121.91027 900.0 6.41803E-02 -B--F----------R---- indium 122m (In-122m) + 1017 0 491230 82c DEC 49 123 0 122.91087 900.0 1.12342E-01 IBADF----------R---- indium 123 (In-123) + 1018 0 491231 82c DEC 49 123 1 122.91087 900.0 1.45010E-02 IB-DF----------R---- indium 123m (In-123m) + 1019 0 491240 82c DEC 49 124 0 123.91348 900.0 2.22163E-01 IBADF----------R---- indium 124 (In-124) + 1020 0 491241 82c DEC 49 124 1 123.91348 900.0 1.87337E-01 IB--F----------R---- indium 124m (In-124m) + 1021 0 491250 82c DEC 49 125 0 124.91408 900.0 2.93706E-01 IBADF----------R---- indium 125 (In-125) + 1022 0 491251 82c DEC 49 125 1 124.91408 900.0 5.68153E-02 IB-DF----------R---- indium 125m (In-125m) + 1023 0 491260 82c DEC 49 126 0 125.91669 900.0 4.53037E-01 IBADF----------R---- indium 126 (In-126) + 1024 0 491261 82c DEC 49 126 1 125.91669 900.0 4.22651E-01 IB--F----------R---- indium 126m (In-126m) + 1025 0 491270 82c DEC 49 127 0 126.91729 900.0 6.35915E-01 IB--F----------R---- indium 127 (In-127) + 1026 0 491271 82c DEC 49 127 1 126.91729 900.0 1.88868E-01 IB-DF-----P----R---- indium 127m (In-127m) + 1027 0 491280 82c DEC 49 128 0 127.91990 900.0 8.25175E-01 IB-DF----------R---- indium 128 (In-128) + 1028 0 491281 82c DEC 49 128 1 127.91990 900.0 6.93147E+01 IB-DF----------R---- indium 128m (In-128m) + 1029 1 491282 82c DEC 49 128 2 127.91990 900.0 9.62704E-01 -B--F----------R---- indium 128m (In-128m) + 1030 0 491290 82c DEC 49 129 0 128.92150 900.0 1.13631E+00 IB-DF----------R---- indium 129 (In-129) + 1031 0 491291 82c DEC 49 129 1 128.92150 900.0 5.63534E-01 IB-DF----------R---- indium 129m (In-129m) + 1032 0 491300 82c DEC 49 130 0 129.92513 900.0 2.39016E+00 IB-DF----------R---- indium 130 (In-130) + 1033 0 491301 82c DEC 49 130 1 129.92513 900.0 1.28361E+00 IB--F----------R---- indium 130m (In-130m) + 1034 1 491302 82c DEC 49 130 2 129.92513 900.0 1.28361E+00 -B--F----------R---- indium 130m (In-130m) + 1035 0 491310 82c DEC 49 131 0 130.92673 900.0 2.47553E+00 IB-DF----------R---- indium 131 (In-131) + 1036 0 491311 82c DEC 49 131 1 130.92673 900.0 1.98042E+00 IB-DF-----P----R---- indium 131m (In-131m) + 1037 1 491312 82c DEC 49 131 2 130.92673 900.0 2.16608E+00 -B--F-----P----R---- indium 131m (In-131m) + 1038 0 491320 82c DEC 49 132 0 131.93338 900.0 3.34854E+00 IB-DF----------R---- indium 132 (In-132) + 1039 0 491330 82c DEC 49 133 0 132.93801 900.0 4.20089E+00 IB-DF-----P----R---- indium 133 (In-133) + 1040 0 491331 82c DEC 49 133 1 132.93801 900.0 3.85082E+00 IB--F----------R---- indium 133m (In-133m) + 1041 0 491340 82c DEC 49 134 0 133.94466 900.0 4.95105E+00 IB--F-----P----R---- indium 134 (In-134) + 1042 0 491350 82c DEC 49 135 0 134.94929 900.0 7.53421E+00 IB--F----------R---- indium 135 (In-135) + 1043 0 501120 82c DEC 50 112 0 111.90533 900.0 stable IB-D-----------R---- tin 112 (Sn-112) + 1044 0 501130 82c DEC 50 113 0 112.90491 900.0 6.97066E-08 IBA------------R---- tin 113 (Sn-113) + 1045 0 501140 82c DEC 50 114 0 113.90248 900.0 stable IBAD-----------R---- tin 114 (Sn-114) + 1046 0 501171 82c DEC 50 117 1 116.90326 900.0 5.73038E-07 IBADF----------R---- tin 117m (Sn-117m) + 1047 0 501191 82c DEC 50 119 1 118.90344 900.0 2.73807E-08 IBADF----------R---- tin 119m (Sn-119m) + 1048 0 501210 82c DEC 50 121 0 120.90463 900.0 7.12323E-06 IBADF----------R---- tin 121 (Sn-121) + 1049 0 501211 82c DEC 50 121 1 120.90463 900.0 5.00341E-10 IBADF----------R---- tin 121m (Sn-121m) + 1050 0 501231 82c DEC 50 123 1 122.90583 900.0 2.88379E-04 IBADF----------R---- tin 123m (Sn-123m) + 1051 0 501251 82c DEC 50 125 1 124.90803 900.0 1.21349E-03 IBADF----------R---- tin 125m (Sn-125m) + 1052 0 501270 82c DEC 50 127 0 126.91023 900.0 9.16861E-05 IBADF----------R---- tin 127 (Sn-127) + 1053 0 501271 82c DEC 50 127 1 126.91023 900.0 2.79720E-03 IBADF----------R---- tin 127m (Sn-127m) + 1054 0 501280 82c DEC 50 128 0 127.91082 900.0 1.95572E-04 IBADF----------R---- tin 128 (Sn-128) + 1055 0 501281 82c DEC 50 128 1 127.91082 900.0 1.06638E-01 IB-DF----------R---- tin 128m (Sn-128m) + 1056 0 501290 82c DEC 50 129 0 128.91343 900.0 5.18047E-03 IBADF----------R---- tin 129 (Sn-129) + 1057 0 501291 82c DEC 50 129 1 128.91343 900.0 1.60451E-03 IB-DF----------R---- tin 129m (Sn-129m) + 1058 0 501300 82c DEC 50 130 0 129.91403 900.0 3.09717E-03 IBADF----------R---- tin 130 (Sn-130) + 1059 0 501301 82c DEC 50 130 1 129.91403 900.0 6.79556E-03 IB-DF----------R---- tin 130m (Sn-130m) + 1060 0 501310 82c DEC 50 131 0 130.91664 900.0 1.23776E-02 IBADF----------R---- tin 131 (Sn-131) + 1061 0 501311 82c DEC 50 131 1 130.91664 900.0 1.18690E-02 IB-DF----------R---- tin 131m (Sn-131m) + 1062 0 501320 82c DEC 50 132 0 131.91825 900.0 1.74596E-02 IB-DF----------R---- tin 132 (Sn-132) + 1063 0 501330 82c DEC 50 133 0 132.92389 900.0 4.74758E-01 IB-DF----------R---- tin 133 (Sn-133) + 1064 0 501340 82c DEC 50 134 0 133.92852 900.0 6.60140E-01 IB-DF-----P----R---- tin 134 (Sn-134) + 1065 0 501350 82c DEC 50 135 0 134.93516 900.0 1.30782E+00 IB-DF-----P----R---- tin 135 (Sn-135) + 1066 0 501360 82c DEC 50 136 0 135.93979 900.0 2.77259E+00 IB--F-----P----R---- tin 136 (Sn-136) + 1067 0 501370 82c DEC 50 137 0 136.94644 900.0 3.64814E+00 IB--F-----P----R---- tin 137 (Sn-137) + 1068 0 511180 82c DEC 51 118 0 117.90587 900.0 3.20901E-03 IBA-F----------R---- antimony 118 (Sb-118) + 1069 0 511181 82c DEC 51 118 1 117.90587 900.0 3.85082E-05 IB--F----------R---- antimony 118m (Sb-118m) + 1070 0 511190 82c DEC 51 119 0 118.90445 900.0 5.02718E-06 IBADF----------R---- antimony 119 (Sb-119) + 1071 0 511191 82c DEC 51 119 1 118.90445 900.0 8.15467E-01 IB--F----------R---- antimony 119m (Sb-119m) + 1072 0 511200 82c DEC 51 120 0 119.90505 900.0 7.26569E-04 IBA-F----------R---- antimony 120 (Sb-120) + 1073 0 511201 82c DEC 51 120 1 119.90505 900.0 1.39280E-06 IB--F----------R---- antimony 120m (Sb-120m) + 1074 0 511220 82c DEC 51 122 0 121.90523 900.0 2.97590E-06 IBADF----------R---- antimony 122 (Sb-122) + 1075 0 511221 82c DEC 51 122 1 121.90523 900.0 2.75715E-03 IBA-F----------R---- antimony 122m (Sb-122m) + 1076 0 511241 82c DEC 51 124 1 123.90642 900.0 7.45320E-03 IB-DF----------R---- antimony 124m (Sb-124m) + 1077 1 511242 82c DEC 51 124 2 123.90642 900.0 5.71904E-04 -B--F----------R---- antimony 124m (Sb-124m) + 1078 0 511261 82c DEC 51 126 1 125.90761 900.0 6.04840E-04 IB-DF----------R---- antimony 126m (Sb-126m) + 1079 1 511262 82c DEC 51 126 2 125.90761 900.0 6.30134E-02 -B-DF----------R---- antimony 126m (Sb-126m) + 1080 0 511270 82c DEC 51 127 0 126.90720 900.0 2.08378E-06 IBADF----------R---- antimony 127 (Sb-127) + 1081 0 511280 82c DEC 51 128 0 127.90880 900.0 2.13697E-05 IBADF----------R---- antimony 128 (Sb-128) + 1082 0 511281 82c DEC 51 128 1 127.90880 900.0 1.11081E-03 IB--F----------R---- antimony 128m (Sb-128m) + 1083 0 511290 82c DEC 51 129 0 128.90940 900.0 4.41608E-05 IBADF----------R---- antimony 129 (Sb-129) + 1084 0 511291 82c DEC 51 129 1 128.90940 900.0 6.52681E-04 IB-DF----------R---- antimony 129m (Sb-129m) + 1085 0 511300 82c DEC 51 130 0 129.91201 900.0 2.92467E-04 IBADF----------R---- antimony 130 (Sb-130) + 1086 0 511301 82c DEC 51 130 1 129.91201 900.0 1.83372E-03 IB-DF----------R---- antimony 130m (Sb-130m) + 1087 0 511310 82c DEC 51 131 0 130.91160 900.0 5.01626E-04 IBADF----------R---- antimony 131 (Sb-131) + 1088 0 511320 82c DEC 51 132 0 131.91421 900.0 4.14066E-03 IBADF----------R---- antimony 132 (Sb-132) + 1089 0 511321 82c DEC 51 132 1 131.91421 900.0 2.81767E-03 IB--F----------R---- antimony 132m (Sb-132m) + 1090 0 511330 82c DEC 51 133 0 132.91481 900.0 4.62098E-03 IB-DF----------R---- antimony 133 (Sb-133) + 1091 0 511340 82c DEC 51 134 0 133.92045 900.0 8.88650E-01 IB-DF----------R---- antimony 134 (Sb-134) + 1092 0 511341 82c DEC 51 134 1 133.92045 900.0 6.88329E-02 IB-DF-----P----R---- antimony 134m (Sb-134m) + 1093 0 511350 82c DEC 51 135 0 134.92508 900.0 3.98360E-01 IB-DF-----P----R---- antimony 135 (Sb-135) + 1094 0 511360 82c DEC 51 136 0 135.93072 900.0 7.50972E-01 IB-DF-----P----R---- antimony 136 (Sb-136) + 1095 0 511370 82c DEC 51 137 0 136.93535 900.0 1.54033E+00 IB-DF-----P----R---- antimony 137 (Sb-137) + 1096 0 511380 82c DEC 51 138 0 137.94099 900.0 1.38629E+00 IB--F----------R---- antimony 138 (Sb-138) + 1097 0 511390 82c DEC 51 139 0 138.94562 900.0 2.31049E+00 IB--F----------R---- antimony 139 (Sb-139) + 1098 0 521210 82c DEC 52 121 0 120.90463 900.0 4.18714E-07 IBADF----------R---- tellurium 121 (Te-121) + 1099 0 521211 82c DEC 52 121 1 120.90463 900.0 5.20944E-08 IBA-F----------R---- tellurium 121m (Te-121m) + 1100 0 521231 82c DEC 52 123 1 122.90381 900.0 6.71342E-08 IBA-F----------R---- tellurium 123m (Te-123m) + 1101 0 521251 82c DEC 52 125 1 124.90399 900.0 1.39765E-07 IBADF----------R---- tellurium 125m (Te-125m) + 1102 0 521270 82c DEC 52 127 0 126.90518 900.0 2.05926E-05 IBADF----------R---- tellurium 127 (Te-127) + 1103 0 521290 82c DEC 52 129 0 128.90637 900.0 1.65984E-04 IBADF----------R---- tellurium 129 (Te-129) + 1104 0 521310 82c DEC 52 131 0 130.90857 900.0 4.62098E-04 IBADF----------R---- tellurium 131 (Te-131) + 1105 0 521311 82c DEC 52 131 1 130.90857 900.0 6.41803E-06 IBADF----------R---- tellurium 131m (Te-131m) + 1106 0 521330 82c DEC 52 133 0 132.91077 900.0 9.27908E-04 IBADF----------R---- tellurium 133 (Te-133) + 1107 0 521331 82c DEC 52 133 1 132.91077 900.0 2.08528E-04 IBADF----------R---- tellurium 133m (Te-133m) + 1108 0 521340 82c DEC 52 134 0 133.91137 900.0 2.76374E-04 IBADF----------R---- tellurium 134 (Te-134) + 1109 0 521350 82c DEC 52 135 0 134.91600 900.0 3.64814E-02 IBADF----------R---- tellurium 135 (Te-135) + 1110 0 521360 82c DEC 52 136 0 135.91962 900.0 3.96084E-02 IB-DF----------R---- tellurium 136 (Te-136) + 1111 0 521370 82c DEC 52 137 0 136.92526 900.0 2.78372E-01 IB-DF-----P----R---- tellurium 137 (Te-137) + 1112 0 521380 82c DEC 52 138 0 137.92888 900.0 4.95105E-01 IB-DF-----P----R---- tellurium 138 (Te-138) + 1113 0 521390 82c DEC 52 139 0 138.93452 900.0 1.38629E+00 IB-DF----------R---- tellurium 139 (Te-139) + 1114 0 521400 82c DEC 52 140 0 139.93915 900.0 2.31049E+00 IB--F----------R---- tellurium 140 (Te-140) + 1115 0 521410 82c DEC 52 141 0 140.94479 900.0 6.93147E+00 IB--F----------R---- tellurium 141 (Te-141) + 1116 0 521420 82c DEC 52 142 0 141.94942 900.0 1.38629E+01 IB--F----------R---- tellurium 142 (Te-142) + 1117 0 531250 82c DEC 53 125 0 124.90500 900.0 1.35087E-07 IBA------------R---- iodine 125 (I-125) + 1118 0 531260 82c DEC 53 126 0 125.90560 900.0 6.18070E-07 IBA-F----------R---- iodine 126 (I-126) + 1119 0 531280 82c DEC 53 128 0 127.90578 900.0 4.62283E-04 IBA-F----------R---- iodine 128 (I-128) + 1120 0 531301 82c DEC 53 130 1 129.90697 900.0 1.30684E-03 IBA-F----------R---- iodine 130m (I-130m) + 1121 0 531320 82c DEC 53 132 0 131.90816 900.0 8.38958E-05 IBADF----------R---- iodine 132 (I-132) + 1122 0 531321 82c DEC 53 132 1 131.90816 900.0 1.39186E-04 IBA-F----------R---- iodine 132m (I-132m) + 1123 0 531330 82c DEC 53 133 0 132.90775 900.0 9.22573E-06 IBADF----------R---- iodine 133 (I-133) + 1124 0 531331 82c DEC 53 133 1 132.90775 900.0 7.70164E-02 IB--F----------R---- iodine 133m (I-133m) + 1125 0 531340 82c DEC 53 134 0 133.90935 900.0 2.20047E-04 IBADF----------R---- iodine 134 (I-134) + 1126 0 531341 82c DEC 53 134 1 133.91036 900.0 3.20901E-03 IB--F----------R---- iodine 134m (I-134m) + 1127 0 531360 82c DEC 53 136 0 135.91458 900.0 8.30116E-03 IBADF----------R---- iodine 136 (I-136) + 1128 0 531361 82c DEC 53 136 1 135.91458 900.0 1.47478E-02 IB-DF----------R---- iodine 136m (I-136m) + 1129 0 531370 82c DEC 53 137 0 136.91820 900.0 2.82802E-02 IB-DF-----P----R---- iodine 137 (I-137) + 1130 0 531380 82c DEC 53 138 0 137.92283 900.0 1.07298E-01 IB-DF-----P----R---- iodine 138 (I-138) + 1131 0 531390 82c DEC 53 139 0 138.92645 900.0 3.01368E-01 IB-DF-----P----R---- iodine 139 (I-139) + 1132 0 531400 82c DEC 53 140 0 139.93108 900.0 8.05985E-01 IB-DF-----P----R---- iodine 140 (I-140) + 1133 0 531410 82c DEC 53 141 0 140.93470 900.0 1.61197E+00 IB-DF-----P----R---- iodine 141 (I-141) + 1134 0 531420 82c DEC 53 142 0 141.94034 900.0 3.46574E+00 IB-DF-----P----R---- iodine 142 (I-142) + 1135 0 531430 82c DEC 53 143 0 142.94497 900.0 6.93147E+00 IB--F-----P----R---- iodine 143 (I-143) + 1136 0 531440 82c DEC 53 144 0 143.94960 900.0 1.38629E+01 IB--F-----P----R---- iodine 144 (I-144) + 1137 0 541260 82c DEC 54 126 0 125.90459 900.0 stable IBAD-----------R---- xenon 126 (Xe-126) + 1138 0 541270 82c DEC 54 127 0 126.90518 900.0 2.20654E-07 IBA------------R---- xenon 127 (Xe-127) + 1139 0 541291 82c DEC 54 129 1 128.90436 900.0 9.03439E-07 IBA-F----------R---- xenon 129m (Xe-129m) + 1140 0 541311 82c DEC 54 131 1 130.90555 900.0 6.70666E-07 IBADF----------R---- xenon 131m (Xe-131m) + 1141 0 541321 82c DEC 54 132 1 131.90413 900.0 8.26159E+01 IB--F----------R---- xenon 132m (Xe-132m) + 1142 0 541331 82c DEC 54 133 1 132.90573 900.0 3.64993E-06 IBADF----------R---- xenon 133m (Xe-133m) + 1143 0 541341 82c DEC 54 134 1 133.90532 900.0 2.39016E+00 IBADF----------R---- xenon 134m (Xe-134m) + 1144 0 541351 82c DEC 54 135 1 134.90692 900.0 7.55062E-04 IBADF----------R---- xenon 135m (Xe-135m) + 1145 0 541370 82c DEC 54 137 0 136.91114 900.0 3.02579E-03 IBADF----------R---- xenon 137 (Xe-137) + 1146 0 541380 82c DEC 54 138 0 137.91375 900.0 8.20487E-04 IBADF----------R---- xenon 138 (Xe-138) + 1147 0 541390 82c DEC 54 139 0 138.91838 900.0 1.74640E-02 IBADF----------R---- xenon 139 (Xe-139) + 1148 0 541400 82c DEC 54 140 0 139.92200 900.0 5.09667E-02 IB-DF----------R---- xenon 140 (Xe-140) + 1149 0 541410 82c DEC 54 141 0 140.92663 900.0 4.00663E-01 IB-DF-----P----R---- xenon 141 (Xe-141) + 1150 0 541420 82c DEC 54 142 0 141.92925 900.0 5.68153E-01 IB-DF-----P----R---- xenon 142 (Xe-142) + 1151 0 541430 82c DEC 54 143 0 142.93489 900.0 1.35645E+00 IB-DF-----P----R---- xenon 143 (Xe-143) + 1152 0 541440 82c DEC 54 144 0 143.93851 900.0 1.78646E+00 IB-DF-----P----R---- xenon 144 (Xe-144) + 1153 0 541450 82c DEC 54 145 0 144.94415 900.0 3.68695E+00 IB--F-----P----R---- xenon 145 (Xe-145) + 1154 0 541460 82c DEC 54 146 0 145.94777 900.0 4.74758E+00 IB--F-----P----R---- xenon 146 (Xe-146) + 1155 0 541470 82c DEC 54 147 0 146.95341 900.0 5.33190E+00 IB--F-----P----R---- xenon 147 (Xe-147) + 1156 0 551310 82c DEC 55 131 0 130.90555 900.0 8.27919E-07 IB--F----------R---- cesium 131 (Cs-131) + 1157 0 551320 82c DEC 55 132 0 131.90614 900.0 1.22857E-06 IBA-F----------R---- cesium 132 (Cs-132) + 1158 0 551341 82c DEC 55 134 1 133.90633 900.0 6.62108E-05 IBA-F----------R---- cesium 134m (Cs-134m) + 1159 0 551351 82c DEC 55 135 1 134.90591 900.0 2.17971E-04 IBA-F----------R---- cesium 135m (Cs-135m) + 1160 0 551361 82c DEC 55 136 1 135.90752 900.0 3.64814E-02 IBA-F----------R---- cesium 136m (Cs-136m) + 1161 0 551380 82c DEC 55 138 0 137.91073 900.0 3.45778E-04 IBADF----------R---- cesium 138 (Cs-138) + 1162 0 551381 82c DEC 55 138 1 137.91073 900.0 3.96992E-03 IBA-F----------R---- cesium 138m (Cs-138m) + 1163 0 551390 82c DEC 55 139 0 138.91334 900.0 1.24622E-03 IBADF----------R---- cesium 139 (Cs-139) + 1164 0 551400 82c DEC 55 140 0 139.91696 900.0 1.08304E-02 IBADF----------R---- cesium 140 (Cs-140) + 1165 0 551410 82c DEC 55 141 0 140.91957 900.0 2.79045E-02 IB-DF----------R---- cesium 141 (Cs-141) + 1166 0 551420 82c DEC 55 142 0 141.92420 900.0 4.11608E-01 IB-DF----------R---- cesium 142 (Cs-142) + 1167 0 551430 82c DEC 55 143 0 142.92783 900.0 3.87017E-01 IB-DF-----P----R---- cesium 143 (Cs-143) + 1168 0 551440 82c DEC 55 144 0 143.93246 900.0 6.97331E-01 IB-DF-----P----R---- cesium 144 (Cs-144) + 1169 0 551441 82c DEC 55 144 1 143.93246 900.0 6.93147E-01 IB-DF----------R---- cesium 144m (Cs-144m) + 1170 0 551450 82c DEC 55 145 0 144.93507 900.0 1.16691E+00 IB-DF-----P----R---- cesium 145 (Cs-145) + 1171 0 551460 82c DEC 55 146 0 145.94071 900.0 2.14597E+00 IB-DF-----P----R---- cesium 146 (Cs-146) + 1172 0 551470 82c DEC 55 147 0 146.94433 900.0 3.08065E+00 IB-DF-----P----R---- cesium 147 (Cs-147) + 1173 0 551480 82c DEC 55 148 0 147.94896 900.0 4.74758E+00 IB--F-----P----R---- cesium 148 (Cs-148) + 1174 0 551490 82c DEC 55 149 0 148.95258 900.0 4.62098E+00 IB--F----------R---- cesium 149 (Cs-149) + 1175 0 551500 82c DEC 55 150 0 149.95822 900.0 6.93147E+00 IB--F----------R---- cesium 150 (Cs-150) + 1176 0 561320 82c DEC 56 132 0 131.90514 900.0 stable IBAD-----------R---- barium 132 (Ba-132) + 1177 0 561330 82c DEC 56 133 0 132.90573 900.0 2.08416E-09 IBADF----------R---- barium 133 (Ba-133) + 1178 0 561331 82c DEC 56 133 1 132.90573 900.0 5.04034E-06 IB--F----------R---- barium 133m (Ba-133m) + 1179 0 561351 82c DEC 56 135 1 134.90591 900.0 6.70874E-06 IBA-F----------R---- barium 135m (Ba-135m) + 1180 0 561361 82c DEC 56 136 1 135.90449 900.0 2.24756E+00 IBA-F----------R---- barium 136m (Ba-136m) + 1181 0 561371 82c DEC 56 137 1 136.90610 900.0 4.52682E-03 IBADF----------R---- barium 137m (Ba-137m) + 1182 0 561390 82c DEC 56 139 0 138.90930 900.0 1.39086E-04 IBADF----------R---- barium 139 (Ba-139) + 1183 0 561410 82c DEC 56 141 0 140.91453 900.0 6.32318E-04 IBADF----------R---- barium 141 (Ba-141) + 1184 0 561420 82c DEC 56 142 0 141.91613 900.0 1.08985E-03 IBADF----------R---- barium 142 (Ba-142) + 1185 0 561430 82c DEC 56 143 0 142.92077 900.0 4.78033E-02 IB-DF----------R---- barium 143 (Ba-143) + 1186 0 561440 82c DEC 56 144 0 143.92338 900.0 6.02737E-02 IB-DF----------R---- barium 144 (Ba-144) + 1187 0 561450 82c DEC 56 145 0 144.92801 900.0 1.60823E-01 IB-DF----------R---- barium 145 (Ba-145) + 1188 0 561460 82c DEC 56 146 0 145.93062 900.0 3.12228E-01 IB-DF----------R---- barium 146 (Ba-146) + 1189 0 561470 82c DEC 56 147 0 146.93525 900.0 7.75332E-01 IB-DF----------R---- barium 147 (Ba-147) + 1190 0 561480 82c DEC 56 148 0 147.93786 900.0 1.13259E+00 IB-DF-----P----R---- barium 148 (Ba-148) + 1191 0 561490 82c DEC 56 149 0 148.94250 900.0 2.01496E+00 IB-DF-----P----R---- barium 149 (Ba-149) + 1192 0 561500 82c DEC 56 150 0 149.94612 900.0 2.31049E+00 IB-DF----------R---- barium 150 (Ba-150) + 1193 0 561510 82c DEC 56 151 0 150.95075 900.0 3.46574E+00 IB--F----------R---- barium 151 (Ba-151) + 1194 0 561520 82c DEC 56 152 0 151.95437 900.0 6.93147E+00 IB--F----------R---- barium 152 (Ba-152) + 1195 0 561530 82c DEC 56 153 0 152.96001 900.0 8.66434E+00 IB--F----------R---- barium 153 (Ba-153) + 1196 0 571360 82c DEC 57 136 0 135.90752 900.0 1.17046E-03 IBADF----------R---- lanthanum 136 (La-136) + 1197 0 571361 82c DEC 57 136 1 135.90752 900.0 6.08024E+00 IB--F----------R---- lanthanum 136m (La-136m) + 1198 0 571370 82c DEC 57 137 0 136.90610 900.0 3.66074E-13 IBA-F----------R---- lanthanum 137 (La-137) + 1199 0 571410 82c DEC 57 141 0 140.91050 900.0 4.91176E-05 IBADF----------R---- lanthanum 141 (La-141) + 1200 0 571420 82c DEC 57 142 0 141.91412 900.0 1.26811E-04 IBADF----------R---- lanthanum 142 (La-142) + 1201 0 571430 82c DEC 57 143 0 142.91572 900.0 8.17005E-04 IBADF----------R---- lanthanum 143 (La-143) + 1202 0 571440 82c DEC 57 144 0 143.91934 900.0 1.69889E-02 IBADF----------R---- lanthanum 144 (La-144) + 1203 0 571450 82c DEC 57 145 0 144.92196 900.0 2.79495E-02 IB-DF----------R---- lanthanum 145 (La-145) + 1204 0 571460 82c DEC 57 146 0 145.92558 900.0 1.10550E-01 IB-DF----------R---- lanthanum 146 (La-146) + 1205 0 571461 82c DEC 57 146 1 145.92558 900.0 6.93147E-02 IB--F----------R---- lanthanum 146m (La-146m) + 1206 0 571470 82c DEC 57 147 0 146.92819 900.0 1.70726E-01 IB-DF----------R---- lanthanum 147 (La-147) + 1207 0 571480 82c DEC 57 148 0 147.93181 900.0 5.50117E-01 IB-DF----------R---- lanthanum 148 (La-148) + 1208 0 571490 82c DEC 57 149 0 148.93443 900.0 6.60140E-01 IB-DF-----P----R---- lanthanum 149 (La-149) + 1209 0 571500 82c DEC 57 150 0 149.93906 900.0 1.35911E+00 IB-DF-----P----R---- lanthanum 150 (La-150) + 1210 0 571510 82c DEC 57 151 0 150.94167 900.0 2.31049E+00 IB-DF----------R---- lanthanum 151 (La-151) + 1211 0 571520 82c DEC 57 152 0 151.94428 900.0 2.47553E+00 IB-DF-----P----R---- lanthanum 152 (La-152) + 1212 0 571530 82c DEC 57 153 0 152.94992 900.0 4.62098E+00 IB-DF----------R---- lanthanum 153 (La-153) + 1213 0 571540 82c DEC 57 154 0 153.95455 900.0 6.93147E+00 IB--F----------R---- lanthanum 154 (La-154) + 1214 0 571550 82c DEC 57 155 0 154.95817 900.0 1.15525E+01 IB--F----------R---- lanthanum 155 (La-155) + 1215 0 581380 82c DEC 58 138 0 137.90568 900.0 stable IB-DF----------R---- cerium 138 (Ce-138) + 1216 0 581381 82c DEC 58 138 1 137.90568 900.0 8.01326E+01 IB--F----------R---- cerium 138m (Ce-138m) + 1217 0 581390 82c DEC 58 139 0 138.90628 900.0 5.82819E-08 IBADF----------R---- cerium 139 (Ce-139) + 1218 0 581391 82c DEC 58 139 1 138.90628 900.0 1.23556E-02 IB-DF----------R---- cerium 139m (Ce-139m) + 1219 0 581450 82c DEC 58 145 0 144.91691 900.0 3.91609E-03 IBADF----------R---- cerium 145 (Ce-145) + 1220 0 581460 82c DEC 58 146 0 145.91852 900.0 8.54471E-04 IBADF----------R---- cerium 146 (Ce-146) + 1221 0 581470 82c DEC 58 147 0 146.92214 900.0 1.21605E-02 IBADF----------R---- cerium 147 (Ce-147) + 1222 0 581480 82c DEC 58 148 0 147.92475 900.0 1.23776E-02 IBADF----------R---- cerium 148 (Ce-148) + 1223 0 581490 82c DEC 58 149 0 148.92837 900.0 1.30782E-01 IBADF----------R---- cerium 149 (Ce-149) + 1224 0 581500 82c DEC 58 150 0 149.92998 900.0 1.73287E-01 IB-DF----------R---- cerium 150 (Ce-150) + 1225 0 581510 82c DEC 58 151 0 150.93360 900.0 6.79556E-01 IB-DF----------R---- cerium 151 (Ce-151) + 1226 0 581520 82c DEC 58 152 0 151.93621 900.0 6.30134E-01 IB-DF----------R---- cerium 152 (Ce-152) + 1227 0 581530 82c DEC 58 153 0 152.93883 900.0 4.62098E-01 IB-DF-----P----R---- cerium 153 (Ce-153) + 1228 0 581540 82c DEC 58 154 0 153.94043 900.0 3.46574E-01 IB-DF-----P----R---- cerium 154 (Ce-154) + 1229 0 581550 82c DEC 58 155 0 154.94809 900.0 3.46574E+00 IB-DF----------R---- cerium 155 (Ce-155) + 1230 0 581560 82c DEC 58 156 0 155.95171 900.0 4.62098E+00 IB--F----------R---- cerium 156 (Ce-156) + 1231 0 581570 82c DEC 58 157 0 156.95634 900.0 1.38629E+01 IB--F----------R---- cerium 157 (Ce-157) + 1232 0 591390 82c DEC 59 139 0 138.90930 900.0 4.36601E-05 IBA------------R---- praseodymium 139 (Pr-139) + 1233 0 591400 82c DEC 59 140 0 139.90889 900.0 3.40780E-03 IBA------------R---- praseodymium 140 (Pr-140) + 1234 0 591421 82c DEC 59 142 1 141.91008 900.0 7.91264E-04 IBA-F----------R---- praseodymium 142m (Pr-142m) + 1235 0 591440 82c DEC 59 144 0 143.91329 900.0 6.68158E-04 IBADF----------R---- praseodymium 144 (Pr-144) + 1236 0 591441 82c DEC 59 144 1 143.91329 900.0 1.60451E-03 IBADF----------R---- praseodymium 144m (Pr-144m) + 1237 0 591450 82c DEC 59 145 0 144.91490 900.0 3.21759E-05 IBADF----------R---- praseodymium 145 (Pr-145) + 1238 0 591460 82c DEC 59 146 0 145.91751 900.0 4.78362E-04 IBADF----------R---- praseodymium 146 (Pr-146) + 1239 0 591470 82c DEC 59 147 0 146.91911 900.0 8.62123E-04 IBADF----------R---- praseodymium 147 (Pr-147) + 1240 0 591480 82c DEC 59 148 0 147.92173 900.0 5.04474E-03 IBADF----------R---- praseodymium 148 (Pr-148) + 1241 0 591481 82c DEC 59 148 1 147.92173 900.0 5.71904E-03 IB--F----------R---- praseodymium 148m (Pr-148m) + 1242 0 591490 82c DEC 59 149 0 148.92333 900.0 5.11170E-03 IBADF----------R---- praseodymium 149 (Pr-149) + 1243 0 591500 82c DEC 59 150 0 149.92695 900.0 1.13631E-01 IBADF----------R---- praseodymium 150 (Pr-150) + 1244 0 591510 82c DEC 59 151 0 150.92856 900.0 3.66745E-02 IB-DF----------R---- praseodymium 151 (Pr-151) + 1245 0 591520 82c DEC 59 152 0 151.93117 900.0 1.90950E-01 IB-DF----------R---- praseodymium 152 (Pr-152) + 1246 0 591530 82c DEC 59 153 0 152.93378 900.0 1.61950E-01 IB-DF----------R---- praseodymium 153 (Pr-153) + 1247 0 591540 82c DEC 59 154 0 153.93740 900.0 3.01368E-01 IB-DF----------R---- praseodymium 154 (Pr-154) + 1248 0 591550 82c DEC 59 155 0 154.94002 900.0 6.93147E-01 IB-DF----------R---- praseodymium 155 (Pr-155) + 1249 0 591560 82c DEC 59 156 0 155.94263 900.0 1.38629E+00 IB-DF-----P----R---- praseodymium 156 (Pr-156) + 1250 0 591570 82c DEC 59 157 0 156.94524 900.0 2.31049E+00 IB-DF-----P----R---- praseodymium 157 (Pr-157) + 1251 0 591580 82c DEC 59 158 0 157.95189 900.0 3.46574E+00 IB--F----------R---- praseodymium 158 (Pr-158) + 1252 0 591590 82c DEC 59 159 0 158.95551 900.0 6.93147E+00 IB--F----------R---- praseodymium 159 (Pr-159) + 1253 0 601420 82c DEC 60 142 0 141.90807 900.0 stable IBAD-----------R---- neodymium 142 (Nd-142) + 1254 0 601430 82c DEC 60 143 0 142.90967 900.0 stable IBAD-----------R---- neodymium 143 (Nd-143) + 1255 0 601490 82c DEC 60 149 0 148.92030 900.0 1.11424E-04 IBADF----------R---- neodymium 149 (Nd-149) + 1256 0 601510 82c DEC 60 151 0 150.92351 900.0 9.28654E-04 IBADF----------R---- neodymium 151 (Nd-151) + 1257 0 601520 82c DEC 60 152 0 151.92512 900.0 1.01337E-03 IB-DF----------R---- neodymium 152 (Nd-152) + 1258 0 601530 82c DEC 60 153 0 152.92773 900.0 2.19350E-02 IB-DF----------R---- neodymium 153 (Nd-153) + 1259 0 601540 82c DEC 60 154 0 153.92933 900.0 2.67624E-02 IB-DF----------R---- neodymium 154 (Nd-154) + 1260 0 601550 82c DEC 60 155 0 154.93296 900.0 7.78817E-02 IB-DF----------R---- neodymium 155 (Nd-155) + 1261 0 601560 82c DEC 60 156 0 155.93456 900.0 1.26256E-01 IB-DF----------R---- neodymium 156 (Nd-156) + 1262 0 601570 82c DEC 60 157 0 156.93717 900.0 2.77259E-01 IB-DF----------R---- neodymium 157 (Nd-157) + 1263 0 601580 82c DEC 60 158 0 157.93979 900.0 9.90210E-01 IB-DF-----P----R---- neodymium 158 (Nd-158) + 1264 0 601590 82c DEC 60 159 0 158.94442 900.0 1.38629E+00 IB-DF-----P----R---- neodymium 159 (Nd-159) + 1265 0 601600 82c DEC 60 160 0 159.94703 900.0 2.31049E+00 IB--F-----P----R---- neodymium 160 (Nd-160) + 1266 0 601610 82c DEC 60 161 0 160.95368 900.0 3.46574E+00 IB--F----------R---- neodymium 161 (Nd-161) + 1267 0 611450 82c DEC 61 145 0 144.91288 900.0 1.24093E-09 IBA------------R---- promethium 145 (Pm-145) + 1268 0 611460 82c DEC 61 146 0 145.91448 900.0 3.97155E-09 IBA-F----------R---- promethium 146 (Pm-146) + 1269 0 611500 82c DEC 61 150 0 149.92090 900.0 7.13643E-05 IBA-F----------R---- promethium 150 (Pm-150) + 1270 0 611520 82c DEC 61 152 0 151.92310 900.0 2.80399E-03 IBADF----------R---- promethium 152 (Pm-152) + 1271 0 611521 82c DEC 61 152 1 151.92310 900.0 1.53623E-03 IB--F----------R---- promethium 152m (Pm-152m) + 1272 1 611522 82c DEC 61 152 2 151.92310 900.0 8.02254E-04 -B--F----------R---- promethium 152m (Pm-152m) + 1273 0 611530 82c DEC 61 153 0 152.92370 900.0 2.20047E-03 IBADF----------R---- promethium 153 (Pm-153) + 1274 0 611540 82c DEC 61 154 0 153.92631 900.0 6.67772E-03 IBADF----------R---- promethium 154 (Pm-154) + 1275 0 611541 82c DEC 61 154 1 153.92631 900.0 4.31062E-03 IB--F----------R---- promethium 154m (Pm-154m) + 1276 0 611550 82c DEC 61 155 0 154.92791 900.0 1.67023E-02 IB-DF----------R---- promethium 155 (Pm-155) + 1277 0 611560 82c DEC 61 156 0 155.93153 900.0 2.59606E-02 IB-DF----------R---- promethium 156 (Pm-156) + 1278 0 611570 82c DEC 61 157 0 156.93314 900.0 6.56389E-02 IB-DF----------R---- promethium 157 (Pm-157) + 1279 0 611580 82c DEC 61 158 0 157.93676 900.0 1.44406E-01 IB-DF----------R---- promethium 158 (Pm-158) + 1280 0 611590 82c DEC 61 159 0 158.93836 900.0 2.31049E-01 IB-DF-----P----R---- promethium 159 (Pm-159) + 1281 0 611600 82c DEC 61 160 0 159.94199 900.0 3.46574E-01 IB-DF-----P----R---- promethium 160 (Pm-160) + 1282 0 611610 82c DEC 61 161 0 160.94561 900.0 9.90210E-01 IB-DF----------R---- promethium 161 (Pm-161) + 1283 0 611620 82c DEC 61 162 0 161.95024 900.0 1.38629E+00 IB--F----------R---- promethium 162 (Pm-162) + 1284 0 611630 82c DEC 61 163 0 162.95386 900.0 3.46574E+00 IB--F----------R---- promethium 163 (Pm-163) + 1285 0 621460 82c DEC 62 146 0 145.91347 900.0 2.19645E-16 IBAD-----------R---- samarium 146 (Sm-146) + 1286 0 621531 82c DEC 62 153 1 152.92168 900.0 6.53912E+01 IB--F----------R---- samarium 153m (Sm-153m) + 1287 0 621550 82c DEC 62 155 0 154.92489 900.0 5.18047E-04 IBADF----------R---- samarium 155 (Sm-155) + 1288 0 621560 82c DEC 62 156 0 155.92548 900.0 2.04831E-05 IBADF----------R---- samarium 156 (Sm-156) + 1289 0 621570 82c DEC 62 157 0 156.92810 900.0 1.43866E-03 IBADF----------R---- samarium 157 (Sm-157) + 1290 0 621580 82c DEC 62 158 0 157.92970 900.0 2.17971E-03 IB-DF----------R---- samarium 158 (Sm-158) + 1291 0 621590 82c DEC 62 159 0 158.93332 900.0 6.09628E-02 IB-DF----------R---- samarium 159 (Sm-159) + 1292 0 621600 82c DEC 62 160 0 159.93493 900.0 7.22028E-02 IB-DF----------R---- samarium 160 (Sm-160) + 1293 0 621610 82c DEC 62 161 0 160.93855 900.0 1.44406E-01 IB-DF----------R---- samarium 161 (Sm-161) + 1294 0 621620 82c DEC 62 162 0 161.94116 900.0 2.88811E-01 IB-DF----------R---- samarium 162 (Sm-162) + 1295 0 621630 82c DEC 62 163 0 162.94579 900.0 6.93147E-01 IB-DF----------R---- samarium 163 (Sm-163) + 1296 0 621640 82c DEC 62 164 0 163.94840 900.0 1.38629E+00 IB--F----------R---- samarium 164 (Sm-164) + 1297 0 621650 82c DEC 62 165 0 164.95303 900.0 3.46574E+00 IB--F----------R---- samarium 165 (Sm-165) + 1298 0 631490 82c DEC 63 149 0 148.91829 900.0 8.61712E-08 IBA------------R---- europium 149 (Eu-149) + 1299 0 631500 82c DEC 63 150 0 149.91989 900.0 6.04108E-10 IBA------------R---- europium 150 (Eu-150) + 1300 0 631521 82c DEC 63 152 1 151.92209 900.0 2.07591E-05 IB--F----------R---- europium 152m (Eu-152m) + 1301 1 631522 82c DEC 63 152 2 151.92209 900.0 1.20338E-04 -B--F----------R---- europium 152m (Eu-152m) + 1302 0 631541 82c DEC 63 154 1 153.92328 900.0 2.48975E-04 IBA-F----------R---- europium 154m (Eu-154m) + 1303 0 631580 82c DEC 63 158 0 157.92768 900.0 2.51687E-04 IBADF----------R---- europium 158 (Eu-158) + 1304 0 631590 82c DEC 63 159 0 158.92929 900.0 6.38257E-04 IBADF----------R---- europium 159 (Eu-159) + 1305 0 631600 82c DEC 63 160 0 159.93190 900.0 1.82407E-02 IBADF----------R---- europium 160 (Eu-160) + 1306 0 631610 82c DEC 63 161 0 160.93350 900.0 2.66595E-02 IB-DF----------R---- europium 161 (Eu-161) + 1307 0 631620 82c DEC 63 162 0 161.93713 900.0 6.53912E-02 IB-DF----------R---- europium 162 (Eu-162) + 1308 0 631630 82c DEC 63 163 0 162.93873 900.0 1.15525E-01 IB-DF----------R---- europium 163 (Eu-163) + 1309 0 631640 82c DEC 63 164 0 163.94336 900.0 3.46574E-01 IB-DF----------R---- europium 164 (Eu-164) + 1310 0 631650 82c DEC 63 165 0 164.94597 900.0 6.93147E-01 IB-DF----------R---- europium 165 (Eu-165) + 1311 0 631660 82c DEC 63 166 0 165.94960 900.0 1.73287E+00 IB--F----------R---- europium 166 (Eu-166) + 1312 0 631670 82c DEC 63 167 0 166.95322 900.0 3.46574E+00 IB--F----------R---- europium 167 (Eu-167) + 1313 0 641500 82c DEC 64 150 0 149.91888 900.0 1.20684E-14 IBA------------R---- gadolinium 150 (Gd-150) + 1314 0 641510 82c DEC 64 151 0 150.92049 900.0 6.46979E-08 IBA------------R---- gadolinium 151 (Gd-151) + 1315 0 641530 82c DEC 64 153 0 152.92168 900.0 3.33577E-08 IBA------------R---- gadolinium 153 (Gd-153) + 1316 0 641551 82c DEC 64 155 1 154.92287 900.0 2.16608E+01 IB--F----------R---- gadolinium 155m (Gd-155m) + 1317 0 641590 82c DEC 64 159 0 158.92626 900.0 1.04194E-05 IBADF----------R---- gadolinium 159 (Gd-159) + 1318 0 641610 82c DEC 64 161 0 160.92947 900.0 3.15641E-03 IBADF----------R---- gadolinium 161 (Gd-161) + 1319 0 641620 82c DEC 64 162 0 161.93107 900.0 1.37529E-03 IB-DF----------R---- gadolinium 162 (Gd-162) + 1320 0 641630 82c DEC 64 163 0 162.93369 900.0 1.01933E-02 IB-DF----------R---- gadolinium 163 (Gd-163) + 1321 0 641640 82c DEC 64 164 0 163.93630 900.0 1.54033E-02 IB-DF----------R---- gadolinium 164 (Gd-164) + 1322 0 641650 82c DEC 64 165 0 164.93891 900.0 6.72958E-02 IB-DF----------R---- gadolinium 165 (Gd-165) + 1323 0 641660 82c DEC 64 166 0 165.94153 900.0 1.44406E-01 IB-DF----------R---- gadolinium 166 (Gd-166) + 1324 0 641670 82c DEC 64 167 0 166.94515 900.0 2.31049E-01 IB-DF----------R---- gadolinium 167 (Gd-167) + 1325 0 641680 82c DEC 64 168 0 167.94877 900.0 2.31049E+00 IB--F----------R---- gadolinium 168 (Gd-168) + 1326 0 641690 82c DEC 64 169 0 168.95239 900.0 6.93147E-01 IB--F----------R---- gadolinium 169 (Gd-169) + 1327 0 651560 82c DEC 65 156 0 155.92447 900.0 1.55175E-06 IB-DF----------R---- terbium 156 (Tb-156) + 1328 0 651561 82c DEC 65 156 1 155.92447 900.0 7.89102E-06 IB--F----------R---- terbium 156m (Tb-156m) + 1329 1 651562 82c DEC 65 156 2 155.92447 900.0 3.77531E-05 -B--F----------R---- terbium 156m (Tb-156m) + 1330 0 651570 82c DEC 65 157 0 156.92406 900.0 2.21864E-10 IBA-F----------R---- terbium 157 (Tb-157) + 1331 0 651580 82c DEC 65 158 0 157.92567 900.0 1.22028E-10 IBADF----------R---- terbium 158 (Tb-158) + 1332 0 651581 82c DEC 65 158 1 157.92567 900.0 6.41803E-02 IB--F----------R---- terbium 158m (Tb-158m) + 1333 0 651610 82c DEC 65 161 0 160.92745 900.0 1.16437E-06 IBADF----------R---- terbium 161 (Tb-161) + 1334 0 651620 82c DEC 65 162 0 161.92906 900.0 1.52006E-03 IBADF----------R---- terbium 162 (Tb-162) + 1335 0 651630 82c DEC 65 163 0 162.93066 900.0 5.92433E-04 IBADF----------R---- terbium 163 (Tb-163) + 1336 0 651640 82c DEC 65 164 0 163.93327 900.0 3.85082E-03 IBADF----------R---- terbium 164 (Tb-164) + 1337 0 651650 82c DEC 65 165 0 164.93488 900.0 5.47510E-03 IB-DF----------R---- terbium 165 (Tb-165) + 1338 0 651660 82c DEC 65 166 0 165.93850 900.0 2.70761E-02 IB-DF----------R---- terbium 166 (Tb-166) + 1339 0 651670 82c DEC 65 167 0 166.94010 900.0 3.64814E-02 IB-DF----------R---- terbium 167 (Tb-167) + 1340 0 651680 82c DEC 65 168 0 167.94373 900.0 8.45301E-02 IB-DF----------R---- terbium 168 (Tb-168) + 1341 0 651690 82c DEC 65 169 0 168.94634 900.0 3.46574E-01 IB-DF----------R---- terbium 169 (Tb-169) + 1342 0 651700 82c DEC 65 170 0 169.94996 900.0 2.31049E-01 IB--F----------R---- terbium 170 (Tb-170) + 1343 0 651710 82c DEC 65 171 0 170.95358 900.0 1.38629E+00 IB--F----------R---- terbium 171 (Tb-171) + 1344 0 661580 82c DEC 66 158 0 157.92466 900.0 stable IB-DF----------R---- dysprosium 158 (Dy-158) + 1345 0 661590 82c DEC 66 159 0 158.92626 900.0 5.55576E-08 IBA-F----------R---- dysprosium 159 (Dy-159) + 1346 0 661650 82c DEC 66 165 0 164.93185 900.0 8.24940E-05 IBADF----------R---- dysprosium 165 (Dy-165) + 1347 0 661651 82c DEC 66 165 1 164.93185 900.0 9.19050E-03 IBA-F----------R---- dysprosium 165m (Dy-165m) + 1348 0 661660 82c DEC 66 166 0 165.93245 900.0 2.35957E-06 IBADF----------R---- dysprosium 166 (Dy-166) + 1349 0 661670 82c DEC 66 167 0 166.93607 900.0 1.86330E-03 IBADF----------R---- dysprosium 167 (Dy-167) + 1350 0 661680 82c DEC 66 168 0 167.93667 900.0 1.32787E-03 IB-DF----------R---- dysprosium 168 (Dy-168) + 1351 0 661690 82c DEC 66 169 0 168.94029 900.0 1.77730E-02 IB-DF----------R---- dysprosium 169 (Dy-169) + 1352 0 661700 82c DEC 66 170 0 169.94290 900.0 2.31049E-02 IB-DF----------R---- dysprosium 170 (Dy-170) + 1353 0 661710 82c DEC 66 171 0 170.94652 900.0 1.15525E-01 IB-DF----------R---- dysprosium 171 (Dy-171) + 1354 0 661720 82c DEC 66 172 0 171.94913 900.0 2.31049E-01 IB--F----------R---- dysprosium 172 (Dy-172) + 1355 0 661730 82c DEC 66 173 0 172.95276 900.0 3.46574E-01 IB--F----------R---- dysprosium 173 (Dy-173) + 1356 0 671610 82c DEC 67 161 0 160.92745 900.0 7.76375E-05 IB-DF----------R---- holmium 161 (Ho-161) + 1357 0 671611 82c DEC 67 161 1 160.92745 900.0 1.02385E-01 IB--F----------R---- holmium 161m (Ho-161m) + 1358 0 671620 82c DEC 67 162 0 161.92906 900.0 7.70164E-04 IBADF----------R---- holmium 162 (Ho-162) + 1359 0 671621 82c DEC 67 162 1 161.92906 900.0 1.72425E-04 IB--F----------R---- holmium 162m (Ho-162m) + 1360 0 671630 82c DEC 67 163 0 162.92864 900.0 4.80625E-12 IBADF----------R---- holmium 163 (Ho-163) + 1361 0 671631 82c DEC 67 163 1 162.92864 900.0 6.30134E-01 IB-DF----------R---- holmium 163m (Ho-163m) + 1362 0 671640 82c DEC 67 164 0 163.93025 900.0 4.03932E-04 IBADF----------R---- holmium 164 (Ho-164) + 1363 0 671641 82c DEC 67 164 1 163.93025 900.0 3.07246E-04 IB--F----------R---- holmium 164m (Ho-164m) + 1364 0 671660 82c DEC 67 166 0 165.93245 900.0 7.18570E-06 IBADF----------R---- holmium 166 (Ho-166) + 1365 0 671661 82c DEC 67 166 1 165.93245 900.0 1.93866E-11 IBA-F----------R---- holmium 166m (Ho-166m) + 1366 0 671670 82c DEC 67 167 0 166.93304 900.0 6.21100E-05 IBADF----------R---- holmium 167 (Ho-167) + 1367 0 671680 82c DEC 67 168 0 167.93566 900.0 3.86370E-03 IBADF----------R---- holmium 168 (Ho-168) + 1368 0 671681 82c DEC 67 168 1 167.93566 900.0 5.25112E-03 IB--F----------R---- holmium 168m (Ho-168m) + 1369 0 671690 82c DEC 67 169 0 168.93726 900.0 2.45797E-03 IBADF----------R---- holmium 169 (Ho-169) + 1370 0 671700 82c DEC 67 170 0 169.93987 900.0 4.15556E-03 IBA-F----------R---- holmium 170 (Ho-170) + 1371 0 671701 82c DEC 67 170 1 169.93987 900.0 1.61197E-02 IB-DF----------R---- holmium 170m (Ho-170m) + 1372 0 671710 82c DEC 67 171 0 170.94148 900.0 1.30782E-02 IB-DF----------R---- holmium 171 (Ho-171) + 1373 0 671720 82c DEC 67 172 0 171.94510 900.0 2.77259E-02 IB-DF----------R---- holmium 172 (Ho-172) + 1374 0 671730 82c DEC 67 173 0 172.94771 900.0 6.93147E-02 IB-DF----------R---- holmium 173 (Ho-173) + 1375 0 671740 82c DEC 67 174 0 173.95133 900.0 8.66434E-02 IB--F----------R---- holmium 174 (Ho-174) + 1376 0 671750 82c DEC 67 175 0 174.95395 900.0 1.38629E-01 IB--F----------R---- holmium 175 (Ho-175) + 1377 0 681620 82c DEC 68 162 0 161.92906 900.0 1.56889E-22 IBA------------R---- erbium 162 (Er-162) + 1378 0 681630 82c DEC 68 163 0 162.92965 900.0 1.54033E-04 IBA------------R---- erbium 163 (Er-163) + 1379 0 681650 82c DEC 68 165 0 164.93084 900.0 1.85850E-05 IBA-F----------R---- erbium 165 (Er-165) + 1380 0 681671 82c DEC 68 167 1 166.93203 900.0 3.05351E-01 IBADF----------R---- erbium 167m (Er-167m) + 1381 0 681690 82c DEC 68 169 0 168.93423 900.0 8.55281E-07 IBADF----------R---- erbium 169 (Er-169) + 1382 0 681710 82c DEC 68 171 0 170.93845 900.0 2.56175E-05 IBADF----------R---- erbium 171 (Er-171) + 1383 0 681720 82c DEC 68 172 0 171.93905 900.0 3.90549E-06 IB-DF----------R---- erbium 172 (Er-172) + 1384 0 681730 82c DEC 68 173 0 172.94267 900.0 8.25175E-03 IB-DF----------R---- erbium 173 (Er-173) + 1385 0 681740 82c DEC 68 174 0 173.94427 900.0 3.61014E-03 IB-DF----------R---- erbium 174 (Er-174) + 1386 0 681750 82c DEC 68 175 0 174.94790 900.0 9.62704E-03 IB-DF----------R---- erbium 175 (Er-175) + 1387 0 681760 82c DEC 68 176 0 175.95051 900.0 3.46574E-02 IB--F----------R---- erbium 176 (Er-176) + 1388 0 681770 82c DEC 68 177 0 176.95413 900.0 2.31049E-01 IB--F----------R---- erbium 177 (Er-177) + 1389 0 691660 82c DEC 69 166 0 165.93346 900.0 2.50053E-05 IB--F----------R---- thulium 166 (Tm-166) + 1390 0 691670 82c DEC 69 167 0 166.93304 900.0 8.67301E-07 IB--F----------R---- thulium 167 (Tm-167) + 1391 0 691680 82c DEC 69 168 0 167.93465 900.0 8.91393E-08 IB--F----------R---- thulium 168 (Tm-168) + 1392 0 691690 82c DEC 69 169 0 168.93423 900.0 stable IB-DF----------R---- thulium 169 (Tm-169) + 1393 0 691700 82c DEC 69 170 0 169.93584 900.0 6.23839E-08 IB--F----------R---- thulium 170 (Tm-170) + 1394 0 691710 82c DEC 69 171 0 170.93643 900.0 1.14608E-08 IB-DF----------R---- thulium 171 (Tm-171) + 1395 0 691720 82c DEC 69 172 0 171.93804 900.0 3.02737E-06 IBADF----------R---- thulium 172 (Tm-172) + 1396 0 691730 82c DEC 69 173 0 172.93964 900.0 2.33666E-05 IBADF----------R---- thulium 173 (Tm-173) + 1397 0 691740 82c DEC 69 174 0 173.94226 900.0 2.13934E-03 IB-DF----------R---- thulium 174 (Tm-174) + 1398 0 691750 82c DEC 69 175 0 174.94386 900.0 7.60030E-04 IB-DF----------R---- thulium 175 (Tm-175) + 1399 0 691760 82c DEC 69 176 0 175.94748 900.0 6.24457E-03 IB-DF----------R---- thulium 176 (Tm-176) + 1400 0 691770 82c DEC 69 177 0 176.94909 900.0 7.70164E-03 IB-DF----------R---- thulium 177 (Tm-177) + 1401 0 691780 82c DEC 69 178 0 177.95271 900.0 2.31049E-02 IB--F----------R---- thulium 178 (Tm-178) + 1402 0 691790 82c DEC 69 179 0 178.95532 900.0 3.46574E-02 IB--F----------R---- thulium 179 (Tm-179) + 1403 0 701680 82c DEC 70 168 0 167.93364 900.0 1.68958E-22 IB-D-----------R---- ytterbium 168 (Yb-168) + 1404 0 701690 82c DEC 70 169 0 168.93524 900.0 2.50563E-07 IB--F----------R---- ytterbium 169 (Yb-169) + 1405 0 701700 82c DEC 70 170 0 169.93483 900.0 stable IB-DF----------R---- ytterbium 170 (Yb-170) + 1406 0 701710 82c DEC 70 171 0 170.93643 900.0 stable IB-DF----------R---- ytterbium 171 (Yb-171) + 1407 0 701711 82c DEC 70 171 1 170.93643 900.0 1.32028E+02 IB--F----------R---- ytterbium 171m (Yb-171m) + 1408 0 701720 82c DEC 70 172 0 171.93602 900.0 stable IB-DF----------R---- ytterbium 172 (Yb-172) + 1409 0 701730 82c DEC 70 173 0 172.93863 900.0 stable IBADF----------R---- ytterbium 173 (Yb-173) + 1410 0 701740 82c DEC 70 174 0 173.93923 900.0 stable IBADF----------R---- ytterbium 174 (Yb-174) + 1411 0 701750 82c DEC 70 175 0 174.94083 900.0 1.91697E-06 IBADF----------R---- ytterbium 175 (Yb-175) + 1412 0 701751 82c DEC 70 175 1 174.94083 900.0 1.01634E+01 IB-DF----------R---- ytterbium 175m (Yb-175m) + 1413 0 701760 82c DEC 70 176 0 175.94244 900.0 stable IBADF----------R---- ytterbium 176 (Yb-176) + 1414 0 701761 82c DEC 70 176 1 175.94244 900.0 6.08024E-02 IB-DF----------R---- ytterbium 176m (Yb-176m) + 1415 0 701770 82c DEC 70 177 0 176.94505 900.0 1.00754E-04 IBADF----------R---- ytterbium 177 (Yb-177) + 1416 0 701771 82c DEC 70 177 1 176.94505 900.0 1.08135E-01 IB-DF----------R---- ytterbium 177m (Yb-177m) + 1417 0 701780 82c DEC 70 178 0 177.94666 900.0 1.56114E-04 IB-DF----------R---- ytterbium 178 (Yb-178) + 1418 0 701790 82c DEC 70 179 0 178.95028 900.0 1.44406E-03 IB-DF----------R---- ytterbium 179 (Yb-179) + 1419 0 701800 82c DEC 70 180 0 179.95188 900.0 4.81352E-03 IB--F----------R---- ytterbium 180 (Yb-180) + 1420 0 701810 82c DEC 70 181 0 180.95651 900.0 1.15525E-02 IB--F----------R---- ytterbium 181 (Yb-181) + 1421 0 711720 82c DEC 71 172 0 171.93905 900.0 1.19739E-06 IB--F----------R---- lutetium 172 (Lu-172) + 1422 0 711730 82c DEC 71 173 0 172.93863 900.0 1.64396E-08 IBA-F----------R---- lutetium 173 (Lu-173) + 1423 0 711740 82c DEC 71 174 0 173.94024 900.0 6.17118E-09 IBADF----------R---- lutetium 174 (Lu-174) + 1424 0 711741 82c DEC 71 174 1 173.94024 900.0 5.64967E-08 IB--F----------R---- lutetium 174m (Lu-174m) + 1425 0 711761 82c DEC 71 176 1 175.94244 900.0 5.29686E-05 IBA-F----------R---- lutetium 176m (Lu-176m) + 1426 0 711770 82c DEC 71 177 0 176.94404 900.0 1.20694E-06 IBADF----------R---- lutetium 177 (Lu-177) + 1427 0 711771 82c DEC 71 177 1 176.94404 900.0 5.00471E-08 IBADF----------R---- lutetium 177m (Lu-177m) + 1428 1 711772 82c DEC 71 177 2 176.94404 900.0 1.65035E-03 -B--F----------R---- lutetium 177m (Lu-177m) + 1429 0 711780 82c DEC 71 178 0 177.94565 900.0 4.06777E-04 IBADF----------R---- lutetium 178 (Lu-178) + 1430 0 711781 82c DEC 71 178 1 177.94565 900.0 5.00106E-04 IB--F----------R---- lutetium 178m (Lu-178m) + 1431 0 711790 82c DEC 71 179 0 178.94725 900.0 4.19479E-05 IBADF----------R---- lutetium 179 (Lu-179) + 1432 0 711791 82c DEC 71 179 1 178.94725 900.0 2.23596E+02 IB-DF----------R---- lutetium 179m (Lu-179m) + 1433 0 711800 82c DEC 71 180 0 179.94986 900.0 2.02675E-03 IBADF----------R---- lutetium 180 (Lu-180) + 1434 0 711801 82c DEC 71 180 1 179.94986 900.0 6.93147E-01 IB-DF----------R---- lutetium 180m (Lu-180m) + 1435 1 711802 82c DEC 71 180 2 179.94986 900.0 6.93147E+02 -B--F----------R---- lutetium 180m (Lu-180m) + 1436 0 711810 82c DEC 71 181 0 180.95248 900.0 3.30070E-03 IB-DF----------R---- lutetium 181 (Lu-181) + 1437 0 711820 82c DEC 71 182 0 181.95509 900.0 5.77623E-03 IB--F----------R---- lutetium 182 (Lu-182) + 1438 0 711830 82c DEC 71 183 0 182.95770 900.0 1.19508E-02 IB--F----------R---- lutetium 183 (Lu-183) + 1439 0 711840 82c DEC 71 184 0 183.96133 900.0 3.46574E-02 IB--F----------R---- lutetium 184 (Lu-184) + 1440 0 721740 82c DEC 72 174 0 173.94024 900.0 1.09823E-23 IBA------------R---- hafnium 174 (Hf-174) + 1441 0 721750 82c DEC 72 175 0 174.94184 900.0 1.14608E-07 IBA-F----------R---- hafnium 175 (Hf-175) + 1442 0 721771 82c DEC 72 177 1 176.94303 900.0 6.41803E-01 IB-DF----------R---- hafnium 177m (Hf-177m) + 1443 1 721772 82c DEC 72 177 2 176.94303 900.0 2.24756E-04 -B-DF----------R---- hafnium 177m (Hf-177m) + 1444 0 721781 82c DEC 72 178 1 177.94363 900.0 1.73287E-01 IB-DF----------R---- hafnium 178m (Hf-178m) + 1445 1 721782 82c DEC 72 178 2 177.94363 900.0 7.08532E-10 -B--F----------R---- hafnium 178m (Hf-178m) + 1446 0 721791 82c DEC 72 179 1 178.94624 900.0 3.71263E-02 IB-DF----------R---- hafnium 179m (Hf-179m) + 1447 1 721792 82c DEC 72 179 2 178.94624 900.0 3.19623E-07 -B-DF----------R---- hafnium 179m (Hf-179m) + 1448 0 721801 82c DEC 72 180 1 179.94684 900.0 3.50074E-05 IBADF----------R---- hafnium 180m (Hf-180m) + 1449 0 721810 82c DEC 72 181 0 180.94945 900.0 1.89300E-07 IBADF----------R---- hafnium 181 (Hf-181) + 1450 0 721820 82c DEC 72 182 0 181.95005 900.0 2.46797E-15 IBADF----------R---- hafnium 182 (Hf-182) + 1451 0 721821 82c DEC 72 182 1 181.95106 900.0 1.87845E-04 IB--F----------R---- hafnium 182m (Hf-182m) + 1452 0 721830 82c DEC 72 183 0 182.95367 900.0 1.80451E-04 IBADF----------R---- hafnium 183 (Hf-183) + 1453 0 721840 82c DEC 72 184 0 183.95527 900.0 4.67332E-05 IB-DF----------R---- hafnium 184 (Hf-184) + 1454 0 721841 82c DEC 72 184 1 183.95527 900.0 1.44406E-02 IB-DF----------R---- hafnium 184m (Hf-184m) + 1455 0 721850 82c DEC 72 185 0 184.95889 900.0 3.30070E-03 IB--F----------R---- hafnium 185 (Hf-185) + 1456 0 721860 82c DEC 72 186 0 185.96050 900.0 4.44325E-03 IB--F----------R---- hafnium 186 (Hf-186) + 1457 0 721870 82c DEC 72 187 0 186.96412 900.0 2.31049E-02 IB--F----------R---- hafnium 187 (Hf-187) + 1458 0 721880 82c DEC 72 188 0 187.96673 900.0 3.46574E-02 IB--F----------R---- hafnium 188 (Hf-188) + 1459 0 731780 82c DEC 73 178 0 177.94565 900.0 1.24086E-03 IB--F----------R---- tantalum 178 (Ta-178) + 1460 0 731781 82c DEC 73 178 1 177.94565 900.0 8.15851E-05 IB--F----------R---- tantalum 178m (Ta-178m) + 1461 0 731790 82c DEC 73 179 0 178.94624 900.0 1.36438E-08 IBADF----------R---- tantalum 179 (Ta-179) + 1462 0 731791 82c DEC 73 179 1 178.94624 900.0 7.70164E+01 IB-DF----------R---- tantalum 179m (Ta-179m) + 1463 1 731792 82c DEC 73 179 2 178.94624 900.0 1.28123E+01 -B--F----------R---- tantalum 179m (Ta-179m) + 1464 0 731800 82c DEC 73 180 0 179.94785 900.0 2.38293E-05 IBA-F----------R---- tantalum 180 (Ta-180) + 1465 0 731801 82c DEC 73 180 1 179.94785 900.0 1.22025E-23 IB-DF----------R---- tantalum 180m (Ta-180m) + 1466 0 731821 82c DEC 73 182 1 181.95005 900.0 2.44928E+00 IB-DF----------R---- tantalum 182m (Ta-182m) + 1467 1 731822 82c DEC 73 182 2 181.95005 900.0 7.29322E-04 -B--F----------R---- tantalum 182m (Ta-182m) + 1468 0 731830 82c DEC 73 183 0 182.95165 900.0 1.57614E-06 IBADF----------R---- tantalum 183 (Ta-183) + 1469 0 731840 82c DEC 73 184 0 183.95426 900.0 2.21311E-05 IBADF----------R---- tantalum 184 (Ta-184) + 1470 0 731850 82c DEC 73 185 0 184.95587 900.0 2.33855E-04 IBADF----------R---- tantalum 185 (Ta-185) + 1471 0 731851 82c DEC 73 185 1 184.95587 900.0 6.93147E+02 IB--F----------R---- tantalum 185m (Ta-185m) + 1472 0 731860 82c DEC 73 186 0 185.95848 900.0 1.10023E-03 IBADF----------R---- tantalum 186 (Ta-186) + 1473 0 731870 82c DEC 73 187 0 186.96009 900.0 5.77623E-03 IB-DF----------R---- tantalum 187 (Ta-187) + 1474 0 731880 82c DEC 73 188 0 187.96371 900.0 3.46574E-02 IB-DF----------R---- tantalum 188 (Ta-188) + 1475 0 731890 82c DEC 73 189 0 188.96632 900.0 2.31049E-01 IB--F----------R---- tantalum 189 (Ta-189) + 1476 0 731900 82c DEC 73 190 0 189.96893 900.0 2.31049E+00 IB--F----------R---- tantalum 190 (Ta-190) + 1477 0 741800 82c DEC 74 180 0 179.94684 900.0 stable IBADF----------R---- tungsten 180 (W-180) + 1478 0 741810 82c DEC 74 181 0 180.94844 900.0 6.63127E-08 IBA-F----------R---- tungsten 181 (W-181) + 1479 0 741831 82c DEC 74 183 1 182.95064 900.0 1.32028E-01 IBADF----------R---- tungsten 183m (W-183m) + 1480 0 741850 82c DEC 74 185 0 184.95385 900.0 1.06825E-07 IBADF----------R---- tungsten 185 (W-185) + 1481 0 741851 82c DEC 74 185 1 184.95385 900.0 6.93147E-03 IBA-F----------R---- tungsten 185m (W-185m) + 1482 0 741861 82c DEC 74 186 1 185.95445 900.0 2.31049E+02 IB--F----------R---- tungsten 186m (W-186m) + 1483 0 741870 82c DEC 74 187 0 186.95706 900.0 8.07299E-06 IBADF----------R---- tungsten 187 (W-187) + 1484 0 741880 82c DEC 74 188 0 187.95866 900.0 1.14969E-07 IB-DF----------R---- tungsten 188 (W-188) + 1485 0 741890 82c DEC 74 189 0 188.96229 900.0 1.07967E-03 IB-DF----------R---- tungsten 189 (W-189) + 1486 0 741900 82c DEC 74 190 0 189.96288 900.0 3.85082E-04 IB-DF----------R---- tungsten 190 (W-190) + 1487 0 741901 82c DEC 74 190 1 189.96288 900.0 2.23596E+02 IB--F----------R---- tungsten 190m (W-190m) + 1488 0 741910 82c DEC 74 191 0 190.96650 900.0 3.46574E-02 IB--F----------R---- tungsten 191 (W-191) + 1489 0 741920 82c DEC 74 192 0 191.96811 900.0 6.93147E-02 IB--F----------R---- tungsten 192 (W-192) + 1490 0 751830 82c DEC 75 183 0 182.95064 900.0 1.14608E-07 IBA-F----------R---- rhenium 183 (Re-183) + 1491 0 751840 82c DEC 75 184 0 183.95225 900.0 2.26625E-07 IBADF----------R---- rhenium 184 (Re-184) + 1492 0 751841 82c DEC 75 184 1 183.95225 900.0 4.77532E-08 IB--F----------R---- rhenium 184m (Re-184m) + 1493 0 751860 82c DEC 75 186 0 185.95546 900.0 2.13934E-06 IBADF----------R---- rhenium 186 (Re-186) + 1494 0 751861 82c DEC 75 186 1 185.95546 900.0 1.15605E-13 IBA-F----------R---- rhenium 186m (Re-186m) + 1495 0 751880 82c DEC 75 188 0 187.95766 900.0 1.13226E-05 IBADF----------R---- rhenium 188 (Re-188) + 1496 0 751881 82c DEC 75 188 1 187.95766 900.0 6.21434E-04 IBA-F----------R---- rhenium 188m (Re-188m) + 1497 0 751890 82c DEC 75 189 0 188.95926 900.0 7.92349E-06 IB-DF----------R---- rhenium 189 (Re-189) + 1498 0 751900 82c DEC 75 190 0 189.96187 900.0 3.72660E-03 IBADF----------R---- rhenium 190 (Re-190) + 1499 0 751901 82c DEC 75 190 1 189.96187 900.0 6.01690E-05 IB--F----------R---- rhenium 190m (Re-190m) + 1500 0 751910 82c DEC 75 191 0 190.96348 900.0 1.19097E-03 IB-DF----------R---- rhenium 191 (Re-191) + 1501 0 751920 82c DEC 75 192 0 191.96609 900.0 1.11798E-01 IB-DF----------R---- rhenium 192 (Re-192) + 1502 0 751930 82c DEC 75 193 0 192.96769 900.0 2.31049E-02 IB--F----------R---- rhenium 193 (Re-193) + 1503 0 751940 82c DEC 75 194 0 193.97031 900.0 3.46574E-01 IB--F----------R---- rhenium 194 (Re-194) + 1504 0 761860 82c DEC 76 186 0 185.95344 900.0 1.09823E-23 IB-DF----------R---- osmium 186 (Os-186) + 1505 0 761870 82c DEC 76 187 0 186.95605 900.0 stable IB-DF----------R---- osmium 187 (Os-187) + 1506 0 761880 82c DEC 76 188 0 187.95564 900.0 stable IB-DF----------R---- osmium 188 (Os-188) + 1507 0 761890 82c DEC 76 189 0 188.95825 900.0 stable IB-DF----------R---- osmium 189 (Os-189) + 1508 0 761891 82c DEC 76 189 1 188.95825 900.0 3.31396E-05 IB-DF----------R---- osmium 189m (Os-189m) + 1509 0 761900 82c DEC 76 190 0 189.95885 900.0 stable IB-DF----------R---- osmium 190 (Os-190) + 1510 0 761901 82c DEC 76 190 1 189.95885 900.0 1.16691E-03 IB-DF----------R---- osmium 190m (Os-190m) + 1511 0 761910 82c DEC 76 191 0 190.96146 900.0 5.24349E-07 IBADF----------R---- osmium 191 (Os-191) + 1512 0 761911 82c DEC 76 191 1 190.96146 900.0 1.46978E-05 IB--F----------R---- osmium 191m (Os-191m) + 1513 0 761920 82c DEC 76 192 0 191.96105 900.0 stable IB-DF----------R---- osmium 192 (Os-192) + 1514 0 761921 82c DEC 76 192 1 191.96105 900.0 1.17483E-01 IB--F----------R---- osmium 192m (Os-192m) + 1515 0 761930 82c DEC 76 193 0 192.96366 900.0 6.39458E-06 IBADF----------R---- osmium 193 (Os-193) + 1516 0 761940 82c DEC 76 194 0 193.96526 900.0 3.66082E-09 IB-DF----------R---- osmium 194 (Os-194) + 1517 0 761950 82c DEC 76 195 0 194.96788 900.0 1.77730E-03 IB--F----------R---- osmium 195 (Os-195) + 1518 0 761960 82c DEC 76 196 0 195.96948 900.0 3.31016E-04 IB--F----------R---- osmium 196 (Os-196) + 1519 0 771890 82c DEC 77 189 0 188.95825 900.0 6.07768E-07 IBADF----------R---- iridium 189 (Ir-189) + 1520 0 771891 82c DEC 77 189 1 188.95825 900.0 5.21163E+01 IB--F----------R---- iridium 189m (Ir-189m) + 1521 0 771900 82c DEC 77 190 0 189.96086 900.0 6.68545E-07 IBADF----------R---- iridium 190 (Ir-190) + 1522 0 771901 82c DEC 77 190 1 189.96086 900.0 1.71912E-04 IB--F----------R---- iridium 190m (Ir-190m) + 1523 1 771902 82c DEC 77 190 2 189.96086 900.0 6.23715E-05 -B--F----------R---- iridium 190m (Ir-190m) + 1524 0 771911 82c DEC 77 191 1 190.96045 900.0 1.41459E-01 IB-DF----------R---- iridium 191m (Ir-191m) + 1525 1 771912 82c DEC 77 191 2 190.96045 900.0 1.26027E-01 -B--F----------R---- iridium 191m (Ir-191m) + 1526 0 771920 82c DEC 77 192 0 191.96306 900.0 1.08674E-07 IBADF----------R---- iridium 192 (Ir-192) + 1527 0 771921 82c DEC 77 192 1 191.96306 900.0 8.02254E-03 IB-DF----------R---- iridium 192m (Ir-192m) + 1528 1 771922 82c DEC 77 192 2 191.96306 900.0 9.11410E-11 -B--F----------R---- iridium 192m (Ir-192m) + 1529 0 771931 82c DEC 77 193 1 192.96265 900.0 7.61874E-07 IB-DF----------R---- iridium 193m (Ir-193m) + 1530 0 771940 82c DEC 77 194 0 193.96526 900.0 9.97621E-06 IBADF----------R---- iridium 194 (Ir-194) + 1531 0 771941 82c DEC 77 194 1 193.96526 900.0 2.17765E+01 IB--F----------R---- iridium 194m (Ir-194m) + 1532 1 771942 82c DEC 77 194 2 193.96526 900.0 4.69154E-08 -B--F----------R---- iridium 194m (Ir-194m) + 1533 0 771950 82c DEC 77 195 0 194.96586 900.0 7.70164E-05 IB-DF----------R---- iridium 195 (Ir-195) + 1534 0 771951 82c DEC 77 195 1 194.96586 900.0 5.06687E-05 IB--F----------R---- iridium 195m (Ir-195m) + 1535 0 771960 82c DEC 77 196 0 195.96847 900.0 1.33298E-02 IB-DF----------R---- iridium 196 (Ir-196) + 1536 0 771961 82c DEC 77 196 1 195.96847 900.0 1.37529E-04 IB--F----------R---- iridium 196m (Ir-196m) + 1537 0 771970 82c DEC 77 197 0 196.97008 900.0 1.99180E-03 IB-DF----------R---- iridium 197 (Ir-197) + 1538 0 771971 82c DEC 77 197 1 196.97008 900.0 1.29803E-03 IB--F----------R---- iridium 197m (Ir-197m) + 1539 0 781920 82c DEC 78 192 0 191.96105 900.0 stable IB-DF----------R---- platinum 192 (Pt-192) + 1540 0 781930 82c DEC 78 193 0 192.96265 900.0 4.39290E-10 IB-DF----------R---- platinum 193 (Pt-193) + 1541 0 781931 82c DEC 78 193 1 192.96265 900.0 1.84851E-06 IB--F----------R---- platinum 193m (Pt-193m) + 1542 0 781940 82c DEC 78 194 0 193.96224 900.0 stable IBADF----------R---- platinum 194 (Pt-194) + 1543 0 781950 82c DEC 78 195 0 194.96485 900.0 stable IBADF----------R---- platinum 195 (Pt-195) + 1544 0 781951 82c DEC 78 195 1 194.96485 900.0 1.95672E-06 IB-DF----------R---- platinum 195m (Pt-195m) + 1545 0 781960 82c DEC 78 196 0 195.96545 900.0 stable IBADF----------R---- platinum 196 (Pt-196) + 1546 0 781970 82c DEC 78 197 0 196.96705 900.0 9.67956E-06 IBADF----------R---- platinum 197 (Pt-197) + 1547 0 781971 82c DEC 78 197 1 196.96705 900.0 1.21222E-04 IB-DF----------R---- platinum 197m (Pt-197m) + 1548 0 781980 82c DEC 78 198 0 197.96765 900.0 stable IB--F----------R---- platinum 198 (Pt-198) + 1549 0 781990 82c DEC 78 199 0 198.97026 900.0 3.75080E-04 IB-DF----------R---- platinum 199 (Pt-199) + 1550 0 781991 82c DEC 78 199 1 198.97026 900.0 5.09667E-02 IB--F----------R---- platinum 199m (Pt-199m) + 1551 0 791950 82c DEC 79 195 0 194.95476 900.0 4.31102E-08 IBA-F----------R---- gold 195 (Au-195) + 1552 0 791960 82c DEC 79 196 0 195.96646 900.0 1.30090E-06 IBADF----------R---- gold 196 (Au-196) + 1553 0 791961 82c DEC 79 196 1 195.96646 900.0 8.55737E-02 IB--F----------R---- gold 196m (Au-196m) + 1554 0 791971 82c DEC 79 197 1 196.96705 900.0 8.95539E-02 IB-DF----------R---- gold 197m (Au-197m) + 1555 0 791980 82c DEC 79 198 0 197.96866 900.0 2.97759E-06 IBADF----------R---- gold 198 (Au-198) + 1556 0 791981 82c DEC 79 198 1 197.96866 900.0 3.48806E-06 IBA-F----------R---- gold 198m (Au-198m) + 1557 0 791990 82c DEC 79 199 0 198.96925 900.0 2.55576E-06 IBADF----------R---- gold 199 (Au-199) + 1558 0 792000 82c DEC 79 200 0 199.97086 900.0 2.38687E-04 IBADF----------R---- gold 200 (Au-200) + 1559 0 792001 82c DEC 79 200 1 199.97086 900.0 1.02963E-05 IB--F----------R---- gold 200m (Au-200m) + 1560 0 801960 82c DEC 80 196 0 195.96545 900.0 8.78580E-27 IBAD-----------R---- mercury 196 (Hg-196) + 1561 0 801970 82c DEC 80 197 0 196.96705 900.0 2.98051E-06 IBA------------R---- mercury 197 (Hg-197) + 1562 0 801991 82c DEC 80 199 1 198.96824 900.0 2.74405E-04 IBA-F----------R---- mercury 199m (Hg-199m) + 1563 0 802010 82c DEC 80 201 0 200.97044 900.0 stable IBA------------R---- mercury 201 (Hg-201) + 1564 0 802060 82c DEC 80 206 0 205.97746 900.0 1.38852E-03 IB-D-----------R---- mercury 206 (Hg-206) + 1565 0 812050 82c DEC 81 205 0 204.97484 900.0 stable IB-D-----------R---- thallium 205 (Tl-205) + 1566 0 812060 82c DEC 81 206 0 205.97645 900.0 2.74927E-03 IB-D-----------R---- thallium 206 (Tl-206) + 1567 0 812070 82c DEC 81 207 0 206.97704 900.0 2.41987E-03 IB-D-----------R---- thallium 207 (Tl-207) + 1568 0 812080 82c DEC 81 208 0 207.98167 900.0 3.77778E-03 IB-D-----------R---- thallium 208 (Tl-208) + 1569 0 812090 82c DEC 81 209 0 208.98529 900.0 5.34588E-03 IB-D-----------R---- thallium 209 (Tl-209) + 1570 0 812100 82c DEC 81 210 0 209.98992 900.0 8.88650E-03 IB-D-----------R---- thallium 210 (Tl-210) + 1571 0 822060 82c DEC 82 206 0 205.97443 900.0 stable IB-D-----------R---- lead 206 (Pb-206) + 1572 0 822070 82c DEC 82 207 0 206.97603 900.0 stable IB-D-----------R---- lead 207 (Pb-207) + 1573 0 822080 82c DEC 82 208 0 207.97663 900.0 stable IB-D-----------R---- lead 208 (Pb-208) + 1574 0 822090 82c DEC 82 209 0 208.98126 900.0 5.87552E-05 IB-D-----------R---- lead 209 (Pb-209) + 1575 0 822100 82c DEC 82 210 0 209.98387 900.0 9.88079E-10 IB-D-----------R---- lead 210 (Pb-210) + 1576 0 822110 82c DEC 82 211 0 210.98850 900.0 3.20013E-04 IB-D-----------R---- lead 211 (Pb-211) + 1577 0 822120 82c DEC 82 212 0 211.99212 900.0 1.80959E-05 IB-D-----------R---- lead 212 (Pb-212) + 1578 0 822140 82c DEC 82 214 0 213.99937 900.0 4.29204E-04 IB-D-----------R---- lead 214 (Pb-214) + 1579 0 832090 82c DEC 83 209 0 208.98025 900.0 1.15603E-27 IB-D-----------R---- bismuth 209 (Bi-209) + 1580 0 832100 82c DEC 83 210 0 209.98387 900.0 1.60099E-06 IB-D-----------R---- bismuth 210 (Bi-210) + 1581 0 832110 82c DEC 83 211 0 210.98749 900.0 5.37323E-03 IB-D-----------R---- bismuth 211 (Bi-211) + 1582 0 832120 82c DEC 83 212 0 211.99112 900.0 1.90823E-04 IB-D-----------R---- bismuth 212 (Bi-212) + 1583 0 832130 82c DEC 83 213 0 212.99474 900.0 2.53399E-04 IB-D-----------R---- bismuth 213 (Bi-213) + 1584 0 832140 82c DEC 83 214 0 213.99836 900.0 5.83457E-04 IB-D-----------R---- bismuth 214 (Bi-214) + 1585 0 832150 82c DEC 83 215 0 215.00198 900.0 1.52006E-03 IB-D-----------R---- bismuth 215 (Bi-215) + 1586 0 842100 82c DEC 84 210 0 209.98286 900.0 5.79763E-08 IB-D-----------R---- polonium 210 (Po-210) + 1587 0 842110 82c DEC 84 211 0 210.98649 900.0 1.34331E+00 IB-D-----------R---- polonium 211 (Po-211) + 1588 0 842120 82c DEC 84 212 0 211.98910 900.0 2.31049E+06 IB-D-----------R---- polonium 212 (Po-212) + 1589 0 842130 82c DEC 84 213 0 212.99272 900.0 1.87337E+05 IB-D-----------R---- polonium 213 (Po-213) + 1590 0 842140 82c DEC 84 214 0 213.99533 900.0 4.27078E+03 IB-D-----------R---- polonium 214 (Po-214) + 1591 0 842150 82c DEC 84 215 0 214.99896 900.0 3.89190E+02 IB-D-----------R---- polonium 215 (Po-215) + 1592 0 842160 82c DEC 84 216 0 216.00157 900.0 4.68343E+00 IB-D-----------R---- polonium 216 (Po-216) + 1593 0 842180 82c DEC 84 218 0 218.00881 900.0 3.76179E-03 IB-D-----------R---- polonium 218 (Po-218) + 1594 0 852150 82c DEC 85 215 0 214.99896 900.0 6.93147E+03 IB-D-----------R---- astatine 215 (At-215) + 1595 0 852170 82c DEC 85 217 0 217.00519 900.0 2.14597E+01 IB-D-----------R---- astatine 217 (At-217) + 1596 0 852180 82c DEC 85 218 0 218.00881 900.0 4.95105E-01 IB-D-----------R---- astatine 218 (At-218) + 1597 0 852190 82c DEC 85 219 0 219.01142 900.0 1.23776E-02 IB-D-----------R---- astatine 219 (At-219) + 1598 0 862160 82c DEC 86 216 0 216.00056 900.0 1.54033E+04 IB-D-----------R---- radon 216 (Rn-216) + 1599 0 862170 82c DEC 86 217 0 217.00418 900.0 1.28361E+03 IB-D-----------R---- radon 217 (Rn-217) + 1600 0 862180 82c DEC 86 218 0 218.00579 900.0 1.92541E+01 IB-D-----------R---- radon 218 (Rn-218) + 1601 0 862190 82c DEC 86 219 0 219.00941 900.0 1.74158E-01 IB-D-----------R---- radon 219 (Rn-219) + 1602 0 862200 82c DEC 86 220 0 220.01101 900.0 1.24220E-02 IB-D-----------R---- radon 220 (Rn-220) + 1603 0 862220 82c DEC 86 222 0 222.01725 900.0 2.09839E-06 IB-D-----------R---- radon 222 (Rn-222) + 1604 0 872210 82c DEC 87 221 0 221.01463 900.0 2.41179E-03 IB-D-----------R---- francium 221 (Fr-221) + 1605 0 872220 82c DEC 87 222 0 222.01725 900.0 8.13553E-04 IB-D-----------R---- francium 222 (Fr-222) + 1606 0 872230 82c DEC 87 223 0 223.01986 900.0 5.25112E-04 IB-D-----------R---- francium 223 (Fr-223) + 1607 0 872240 82c DEC 87 224 0 224.02348 900.0 3.46921E-03 IB-D-----------R---- francium 224 (Fr-224) + 1608 0 882200 82c DEC 88 220 0 220.01101 900.0 3.85082E+01 IB-D-----------R---- radium 220 (Ra-220) + 1609 0 882210 82c DEC 88 221 0 221.01362 900.0 2.47553E-02 IB-D-----------R---- radium 221 (Ra-221) + 1610 0 882220 82c DEC 88 222 0 222.01523 900.0 1.91636E-02 IB-D-----------R---- radium 222 (Ra-222) + 1611 0 882230 82c DEC 88 223 0 223.01885 900.0 7.01884E-07 IB-D-----------R---- radium 223 (Ra-223) + 1612 0 882240 82c DEC 88 224 0 224.02045 900.0 2.20946E-06 IB-D-----------R---- radium 224 (Ra-224) + 1613 0 882250 82c DEC 88 225 0 225.02408 900.0 5.41331E-07 IB-D-----------R---- radium 225 (Ra-225) + 1614 0 882260 82c DEC 88 226 0 226.02568 900.0 1.37281E-11 IB-D-----------R---- radium 226 (Ra-226) + 1615 0 882280 82c DEC 88 228 0 228.03091 900.0 3.82000E-09 IB-D-----------R---- radium 228 (Ra-228) + 1616 0 892250 82c DEC 89 225 0 225.02307 900.0 8.02254E-07 IB-D-----------R---- actinium 225 (Ac-225) + 1617 0 892260 82c DEC 89 226 0 226.02568 900.0 6.55570E-06 IB-D-----------R---- actinium 226 (Ac-226) + 1618 0 892270 82c DEC 89 227 0 227.02728 900.0 1.00886E-09 IB-D-----------R---- actinium 227 (Ac-227) + 1619 0 892280 82c DEC 89 228 0 228.03091 900.0 3.13075E-05 IB-D-----------R---- actinium 228 (Ac-228) + 1620 0 902240 82c DEC 90 224 0 224.02146 900.0 6.60140E-01 IBA------------R---- thorium 224 (Th-224) + 1621 0 902250 82c DEC 90 225 0 225.02408 900.0 1.32482E-03 IBA------------R---- thorium 225 (Th-225) + 1622 0 902260 82c DEC 90 226 0 226.02467 900.0 3.77902E-04 IBAD-----------R---- thorium 226 (Th-226) + 1623 0 902310 82c DEC 90 231 0 231.03673 900.0 7.54411E-06 IBAD-----------R---- thorium 231 (Th-231) + 1624 0 902320 82c DEC 90 232 0 232.03833 900.0 1.56331E-18 IB-D-----------R---- thorium 232 (Th-232) + 1625 0 902340 82c DEC 90 234 0 234.04356 900.0 3.32885E-07 IB-D-----------R---- thorium 234 (Th-234) + 1626 0 912290 82c DEC 91 229 0 229.03251 900.0 5.34836E-06 IBA------------R---- protactinium 229 (Pa-229) + 1627 0 912300 82c DEC 91 230 0 230.03412 900.0 4.61065E-07 IBA------------R---- protactinium 230 (Pa-230) + 1628 0 912340 82c DEC 91 234 0 234.04356 900.0 2.87374E-05 IBAD-----------R---- protactinium 234 (Pa-234) + 1629 0 912341 82c DEC 91 234 1 234.04356 900.0 9.96760E-03 IBAD-----------R---- protactinium 234m (Pa-234m) + 1630 0 922300 82c DEC 92 230 0 230.03412 900.0 3.85699E-07 IBAD-----------R---- uranium 230 (U-230) + 1631 0 922310 82c DEC 92 231 0 231.03673 900.0 1.91013E-06 IBAD-----------R---- uranium 231 (U-231) + 1632 0 922351 82c DEC 92 235 1 235.04415 900.0 4.44325E-04 IBAD-----------R---- uranium 235m (U-235m) + 1633 0 922390 82c DEC 92 239 0 239.05461 900.0 4.92432E-04 IBA------------R---- uranium 239 (U-239) + 1634 0 922400 82c DEC 92 240 0 240.05621 900.0 1.36554E-05 IB-D-----------R---- uranium 240 (U-240) + 1635 0 932330 82c DEC 93 233 0 233.04095 900.0 3.19129E-04 IBA------------R---- neptunium 233 (Np-233) + 1636 0 932340 82c DEC 93 234 0 234.04255 900.0 1.82330E-06 IBAD-----------R---- neptunium 234 (Np-234) + 1637 0 932361 82c DEC 93 236 1 236.04677 900.0 8.55737E-06 IBA------------R---- neptunium 236m (Np-236m) + 1638 0 932400 82c DEC 93 240 0 240.05621 900.0 1.77730E-04 IBAD-----------R---- neptunium 240 (Np-240) + 1639 0 932401 82c DEC 93 240 1 240.05621 900.0 1.56114E-03 IBA------------R---- neptunium 240m (Np-240m) + 1640 0 942340 82c DEC 94 234 0 234.04356 900.0 2.18796E-05 IBAD-----------R---- plutonium 234 (Pu-234) + 1641 0 942350 82c DEC 94 235 0 235.04516 900.0 4.56619E-04 IBAD-----------R---- plutonium 235 (Pu-235) + 1642 0 942371 82c DEC 94 237 1 237.04837 900.0 3.85082E+00 IBA------------R---- plutonium 237m (Pu-237m) + 1643 0 942450 82c DEC 94 245 0 245.06827 900.0 1.83372E-05 IBA------------R---- plutonium 245 (Pu-245) + 1644 0 942460 82c DEC 94 246 0 246.06987 900.0 7.39404E-07 IB-D-----------R---- plutonium 246 (Pu-246) + 1645 0 952380 82c DEC 95 238 0 238.05199 900.0 1.17882E-04 IB-D-----------R---- americium 238 (Am-238) + 1646 0 952390 82c DEC 95 239 0 239.05259 900.0 1.61799E-05 IBAD-----------R---- americium 239 (Am-239) + 1647 0 952400 82c DEC 95 240 0 240.05520 900.0 3.79017E-06 IBA------------R---- americium 240 (Am-240) + 1648 0 952450 82c DEC 95 245 0 245.06625 900.0 9.39224E-05 IBAD-----------R---- americium 245 (Am-245) + 1649 0 952461 82c DEC 95 246 1 246.06987 900.0 4.62098E-04 IB-D-----------R---- americium 246m (Am-246m) + 1650 0 962380 82c DEC 96 238 0 238.05300 900.0 8.02254E-05 IBA------------R---- curium 238 (Cm-238) + 1651 0 962390 82c DEC 96 239 0 239.05461 900.0 6.63934E-05 IBA------------R---- curium 239 (Cm-239) + 1652 0 962441 82c DEC 96 244 1 244.06263 900.0 2.03867E+01 IB-D-----------R---- curium 244m (Cm-244m) + 1653 0 962510 82c DEC 96 251 0 251.08193 900.0 6.87646E-04 IBA------------R---- curium 251 (Cm-251) + 1654 0 972490 82c DEC 97 249 0 249.07468 900.0 2.50704E-08 IB-D-----------R---- berkelium 249 (Bk-249) + 1655 0 972510 82c DEC 97 251 0 251.08092 900.0 2.07778E-04 IB-D-----------R---- berkelium 251 (Bk-251) + 1656 0 982490 82c DEC 98 249 0 249.07468 900.0 6.25770E-11 IB-D-----------R---- californium 249 (Cf-249) + 1657 0 982510 82c DEC 98 251 0 251.07991 900.0 2.44594E-11 IB-D-----------R---- californium 251 (Cf-251) + + --- Table 2: Reaction and decay data: + + Nuclide 1 / 1657 : 1001.82c -- hydrogen (H-1) + + Pointers : 49939 25100 + Primary type : Transport + Nuclide ZAI : 10010 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/H1.ACE + Atomic weight (AW) : 1.00783 + Atomic weight ratio (AWR) : 0.99917 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 1.50000E+02 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 2 reaction channels + - 2 special reactions + - 1 transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 102 Q = 2.22460E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,gamma) + + 2 special reactions: + + 1 MT = 204 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total deuteron production + 2 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + + Nuclide 2 / 1657 : 1001.82s -- hydrogen (H-1) + + Pointers : 3524041 25100 + Primary type : Transport + Nuclide ZAI : 10010 + Library ID : 82s + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/H1.ACE + Atomic weight (AW) : 1.00783 + Atomic weight ratio (AWR) : 0.99917 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 1.50000E+02 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has inelastic S(a,b) channel between 1.00E-11 and 3.75E-06 MeV + - Nuclide has elastic S(a,b) channel between 1.00E-11 and 3.88E-06 MeV + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 4 reaction channels + - 2 special reactions + - 1 transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 4 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 102 Q = 2.22460E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,gamma) + 3 MT = 1004 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : S(a,b) inelastic scattering + 4 MT = 1002 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : S(a,b) elastic scattering + + 2 special reactions: + + 1 MT = 204 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total deuteron production + 2 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + + Nuclide 3 / 1657 : 1002.82c -- deuterium (H-2) + + Pointers : 50347 25146 + Primary type : Transport + Nuclide ZAI : 10020 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/H2.ACE + Atomic weight (AW) : 2.01410 + Atomic weight ratio (AWR) : 1.99680 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 1.50000E+02 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 3 reaction channels + - 3 special reactions + - 2 transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -2.22500E+00 MeV Emin = 3.33929E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82s : (n,2n) + 3 MT = 102 Q = 6.25740E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,gamma) + + 3 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.33929E+00 MeV : total proton production + 2 MT = 205 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total triton production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + + Nuclide 4 / 1657 : 1003.82c -- tritium (H-3) + + Pointers : 50896 25445 + Primary type : Transport + Nuclide ZAI : 10030 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/H3.ACE + Atomic weight (AW) : 3.01605 + Atomic weight ratio (AWR) : 2.99014 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 3.89E+08 seconds (12.3 years) + Specific ingestion toxicity : 4.20E-11 Sv/Bq + Specific inhalation toxicity : 2.60E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 3 reaction channels + - 3 special reactions + - 2 transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.25760E+00 MeV Emin = 8.35035E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,2n) + 3 MT = 17 Q = -8.47500E+00 MeV Emin = 1.13093E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,3n) + + 3 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.13093E+01 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.35035E+00 MeV : total deuteron production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 2.00000E-05 MeV : damage-energy production + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.85710E-02 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : beta- + + Nuclide 5 / 1657 : 2003.82c -- helium 3 (He-3) + + Pointers : 51551 25491 + Primary type : Transport + Nuclide ZAI : 20030 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/He3.ACE + Atomic weight (AW) : 3.01493 + Atomic weight ratio (AWR) : 2.98903 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 4 reaction channels + - 5 special reactions + - 3 transmutation reactions + - 2 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 4 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 102 Q = 2.05778E+01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,gamma) + 3 MT = 103 Q = 7.63752E-01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,p) + 4 MT = 104 Q = -3.26895E+00 MeV Emin = 4.36261E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + + 2 additional transport branches: + + 1 MT = 103 Q = 7.63752E-01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -3.26895E+00 MeV Emin = 4.36261E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + + 5 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 4.36261E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + + Nuclide 6 / 1657 : 2004.82c -- helium 4 (He-4) + + Pointers : 52465 25537 + Primary type : Transport + Nuclide ZAI : 20040 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/He4.ACE + Atomic weight (AW) : 4.00258 + Atomic weight ratio (AWR) : 3.96820 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 1 reaction channels + - 1 special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + 1 reaction channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + + 1 special reaction: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 3.50000E-05 MeV : damage-energy production + + Nuclide 7 / 1657 : 3006.82c -- lithium 6 (Li-6) + + Pointers : 53299 27423 + Primary type : Transport + Nuclide ZAI : 30060 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Li6.ACE + Atomic weight (AW) : 6.01507 + Atomic weight ratio (AWR) : 5.96340 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 36 reaction channels + - 6 special reactions + - 4 transmutation reactions + - 3 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 36 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 24 Q = -3.69800E+00 MeV Emin = 4.31812E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,2nalpha) + 3 MT = 51 Q = -1.50000E+00 MeV Emin = 1.70000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 4 MT = 52 Q = -2.00000E+00 MeV Emin = 2.33540E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 5 MT = 53 Q = -2.18500E+00 MeV Emin = 2.55140E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 6 MT = 54 Q = -2.50000E+00 MeV Emin = 2.91922E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 7 MT = 55 Q = -3.00000E+00 MeV Emin = 3.50310E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 8 MT = 56 Q = -3.50000E+00 MeV Emin = 4.08692E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 9 MT = 57 Q = -3.56200E+00 MeV Emin = 4.15931E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 10 MT = 58 Q = -4.00000E+00 MeV Emin = 4.67080E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 11 MT = 59 Q = -4.50000E+00 MeV Emin = 5.25460E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 12 MT = 60 Q = -5.00000E+00 MeV Emin = 5.83845E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 13 MT = 61 Q = -5.50000E+00 MeV Emin = 6.42230E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 14 MT = 62 Q = -6.00000E+00 MeV Emin = 7.00614E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 15 MT = 63 Q = -6.50000E+00 MeV Emin = 7.59000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 16 MT = 64 Q = -7.00000E+00 MeV Emin = 8.17383E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 17 MT = 65 Q = -7.50000E+00 MeV Emin = 8.75770E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 18 MT = 66 Q = -8.00000E+00 MeV Emin = 9.34152E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 19 MT = 67 Q = -8.50000E+00 MeV Emin = 9.92536E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 20 MT = 68 Q = -9.00000E+00 MeV Emin = 1.05092E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 21 MT = 69 Q = -9.50000E+00 MeV Emin = 1.10931E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 22 MT = 70 Q = -1.00000E+01 MeV Emin = 1.16770E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 23 MT = 71 Q = -1.05000E+01 MeV Emin = 1.22610E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 24 MT = 72 Q = -1.10000E+01 MeV Emin = 1.28450E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 25 MT = 73 Q = -1.15000E+01 MeV Emin = 1.34284E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 26 MT = 74 Q = -1.20000E+01 MeV Emin = 1.40123E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 27 MT = 75 Q = -1.25000E+01 MeV Emin = 1.45961E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 28 MT = 76 Q = -1.30000E+01 MeV Emin = 1.51800E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 29 MT = 77 Q = -1.35000E+01 MeV Emin = 1.57640E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 27. excited state + 30 MT = 78 Q = -1.40000E+01 MeV Emin = 1.63480E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 28. excited state + 31 MT = 79 Q = -1.45000E+01 MeV Emin = 1.69315E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 29. excited state + 32 MT = 80 Q = -1.50000E+01 MeV Emin = 1.75154E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 30. excited state + 33 MT = 81 Q = -1.55000E+01 MeV Emin = 1.80992E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 31. excited state + 34 MT = 102 Q = 7.25060E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 3007.82c : (n,gamma) + 35 MT = 103 Q = -2.72730E+00 MeV Emin = 3.18464E+00 MeV frac = 1.00000E+00 Product nuclide = 20060 : (n,p) + 36 MT = 105 Q = 4.78380E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,t) + + 3 additional transport branches: + + 1 MT = 24 Q = -3.69800E+00 MeV Emin = 4.31812E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,2nalpha) + 2 MT = 103 Q = -2.72730E+00 MeV Emin = 3.18464E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 105 Q = 4.78380E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.18464E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.70000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 1.70000E+00 MeV : total inelastic scattering + + Nuclide 8 / 1657 : 3007.82c -- lithium 7 (Li-7) + + Pointers : 56695 27469 + Primary type : Transport + Nuclide ZAI : 30070 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Li7.ACE + Atomic weight (AW) : 7.01600 + Atomic weight ratio (AWR) : 6.95573 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 11 reaction channels + - 6 special reactions + - 6 transmutation reactions + - 4 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 11 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.25050E+00 MeV Emin = 8.29288E+00 MeV frac = 1.00000E+00 Product nuclide = 3006.82c : (n,2n) + 3 MT = 24 Q = -8.72400E+00 MeV Emin = 9.97823E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,2nalpha) + 4 MT = 25 Q = -1.09486E+01 MeV Emin = 1.25227E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,3nalpha) + 5 MT = 28 Q = -7.75320E+00 MeV Emin = 8.86790E+00 MeV frac = 1.00000E+00 Product nuclide = 20060 : (n,np) + 6 MT = 51 Q = -4.77610E-01 MeV Emin = 5.43750E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -4.63000E+00 MeV Emin = 5.29564E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -6.68000E+00 MeV Emin = 7.64036E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 91 Q = -2.46670E+00 MeV Emin = 3.14540E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 10 MT = 102 Q = 2.03280E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 30080 : (n,gamma) + 11 MT = 104 Q = -7.75320E+00 MeV Emin = 8.86790E+00 MeV frac = 1.00000E+00 Product nuclide = 20060 : (n,d) + + 4 additional transport branches: + + 1 MT = 24 Q = -8.72400E+00 MeV Emin = 9.97823E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,2nalpha) + 2 MT = 25 Q = -1.09486E+01 MeV Emin = 1.25227E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,3nalpha) + 3 MT = 28 Q = -7.75320E+00 MeV Emin = 8.86790E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 4 MT = 104 Q = -7.75320E+00 MeV Emin = 8.86790E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 8.86790E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.86790E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 5.29564E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 5.29564E+00 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 5.43750E-01 MeV : total inelastic scattering + + Nuclide 9 / 1657 : 4009.82c -- beryllium 9 (Be-9) + + Pointers : 59623 20017 + Primary type : Transport + Nuclide ZAI : 40090 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Be9.ACE + Atomic weight (AW) : 9.01220 + Atomic weight ratio (AWR) : 8.93478 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 22 reaction channels + - 5 special reactions + - 21 transmutation reactions + - 4 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 22 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 875 Q = -1.68400E+00 MeV Emin = 2.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 40080 : (n,2n) to ground state + 3 MT = 876 Q = -2.42940E+00 MeV Emin = 2.70130E+00 MeV frac = 1.00000E+00 Product nuclide = 40080 : (n,2n) to 1. excited state + 4 MT = 877 Q = -2.78000E+00 MeV Emin = 3.09114E+00 MeV frac = 1.00000E+00 Product nuclide = 40080 : (n,2n) to 2. excited state + 5 MT = 878 Q = -3.04900E+00 MeV Emin = 3.39030E+00 MeV frac = 1.00000E+00 Product nuclide = 40080 : (n,2n) to 3. excited state + 6 MT = 879 Q = -4.70400E+00 MeV Emin = 5.23050E+00 MeV frac = 1.00000E+00 Product nuclide = 40080 : (n,2n) to 4. excited state + 7 MT = 880 Q = -5.59000E+00 MeV Emin = 6.21565E+00 MeV frac = 1.00000E+00 Product nuclide = 40080 : (n,2n) to 5. excited state + 8 MT = 881 Q = -6.38000E+00 MeV Emin = 7.09410E+00 MeV frac = 1.00000E+00 Product nuclide = 40080 : (n,2n) to 6. excited state + 9 MT = 882 Q = -6.76000E+00 MeV Emin = 7.51660E+00 MeV frac = 1.00000E+00 Product nuclide = 40080 : (n,2n) to 7. excited state + 10 MT = 883 Q = -7.94000E+00 MeV Emin = 8.82870E+00 MeV frac = 1.00000E+00 Product nuclide = 40080 : (n,2n) to 8. excited state + 11 MT = 884 Q = -1.12830E+01 MeV Emin = 1.25460E+01 MeV frac = 1.00000E+00 Product nuclide = 40080 : (n,2n) to 9. excited state + 12 MT = 885 Q = -1.18100E+01 MeV Emin = 1.31320E+01 MeV frac = 1.00000E+00 Product nuclide = 40080 : (n,2n) to 10. excited state + 13 MT = 886 Q = -2.39700E+00 MeV Emin = 2.80000E+00 MeV frac = 1.00000E+00 Product nuclide = 40080 : (n,2n) to 11. excited state + 14 MT = 887 Q = -4.00000E+00 MeV Emin = 4.44770E+00 MeV frac = 1.00000E+00 Product nuclide = 40080 : (n,2n) to 12. excited state + 15 MT = 888 Q = -3.35000E+00 MeV Emin = 3.72494E+00 MeV frac = 1.00000E+00 Product nuclide = 40080 : (n,2n) to 13. excited state + 16 MT = 889 Q = -1.66540E+00 MeV Emin = 1.86000E+00 MeV frac = 1.00000E+00 Product nuclide = 40080 : (n,2n) to 14. excited state + 17 MT = 890 Q = -2.46360E+00 MeV Emin = 2.73933E+00 MeV frac = 1.00000E+00 Product nuclide = 40080 : (n,2n) to 15. excited state + 18 MT = 102 Q = 6.81300E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 40100 : (n,gamma) + 19 MT = 103 Q = -1.28300E+01 MeV Emin = 1.42700E+01 MeV frac = 1.00000E+00 Product nuclide = 30090 : (n,p) + 20 MT = 104 Q = -1.46600E+01 MeV Emin = 1.63010E+01 MeV frac = 1.00000E+00 Product nuclide = 30080 : (n,d) + 21 MT = 105 Q = -1.04400E+01 MeV Emin = 1.16085E+01 MeV frac = 1.00000E+00 Product nuclide = 3007.82c : (n,t) + 22 MT = 107 Q = -6.00000E-01 MeV Emin = 6.65000E-01 MeV frac = 1.00000E+00 Product nuclide = 20060 : (n,alpha) + + 4 additional transport branches: + + 1 MT = 103 Q = -1.28300E+01 MeV Emin = 1.42700E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -1.46600E+01 MeV Emin = 1.63010E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -1.04400E+01 MeV Emin = 1.16085E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 107 Q = -6.00000E-01 MeV Emin = 6.65000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 5 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.42700E+01 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.63010E+01 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.16085E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 6.65000E-01 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + + Nuclide 10 / 1657 : 5010.82c -- boron 10 (B-10) + + Pointers : 63275 19373 + Primary type : Transport + Nuclide ZAI : 50100 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/B10.ACE + Atomic weight (AW) : 10.01294 + Atomic weight ratio (AWR) : 9.92692 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 41 reaction channels + - 14 special reactions + - 5 transmutation reactions + - 4 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 41 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -7.18350E-01 MeV Emin = 7.70357E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -1.74015E+00 MeV Emin = 1.91500E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -2.15430E+00 MeV Emin = 2.37132E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -3.58710E+00 MeV Emin = 3.94845E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -4.77400E+00 MeV Emin = 5.25491E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -5.11030E+00 MeV Emin = 5.62509E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 57 Q = -5.16390E+00 MeV Emin = 5.68409E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 9 MT = 58 Q = -5.18000E+00 MeV Emin = 5.70181E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 10 MT = 59 Q = -5.91950E+00 MeV Emin = 6.51581E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 11 MT = 60 Q = -6.02500E+00 MeV Emin = 6.63194E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 12 MT = 61 Q = -6.12720E+00 MeV Emin = 6.74443E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 13 MT = 62 Q = -6.50000E+00 MeV Emin = 7.15500E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 14 MT = 63 Q = -7.00000E+00 MeV Emin = 7.70515E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 15 MT = 64 Q = -7.50000E+00 MeV Emin = 8.25600E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 16 MT = 65 Q = -8.00000E+00 MeV Emin = 8.80600E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 17 MT = 66 Q = -8.50000E+00 MeV Emin = 9.35626E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 18 MT = 67 Q = -9.00000E+00 MeV Emin = 9.90700E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 19 MT = 68 Q = -9.50000E+00 MeV Emin = 1.04570E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 20 MT = 69 Q = -1.00000E+01 MeV Emin = 1.10074E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 21 MT = 70 Q = -1.05000E+01 MeV Emin = 1.15580E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 22 MT = 71 Q = -1.10000E+01 MeV Emin = 1.21081E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 23 MT = 72 Q = -1.15000E+01 MeV Emin = 1.26585E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 24 MT = 73 Q = -1.20000E+01 MeV Emin = 1.32090E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 25 MT = 74 Q = -1.25000E+01 MeV Emin = 1.37592E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 26 MT = 75 Q = -1.30000E+01 MeV Emin = 1.43100E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 27 MT = 76 Q = -1.35000E+01 MeV Emin = 1.48600E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 28 MT = 77 Q = -1.40000E+01 MeV Emin = 1.54103E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 27. excited state + 29 MT = 78 Q = -1.45000E+01 MeV Emin = 1.59610E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 28. excited state + 30 MT = 79 Q = -1.50000E+01 MeV Emin = 1.65111E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 29. excited state + 31 MT = 80 Q = -1.55000E+01 MeV Emin = 1.70614E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 30. excited state + 32 MT = 81 Q = -1.60000E+01 MeV Emin = 1.76120E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 31. excited state + 33 MT = 82 Q = -1.65000E+01 MeV Emin = 1.81622E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 32. excited state + 34 MT = 83 Q = -1.70000E+01 MeV Emin = 1.87130E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 33. excited state + 35 MT = 84 Q = -1.75000E+01 MeV Emin = 1.92630E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 34. excited state + 36 MT = 85 Q = -1.80000E+01 MeV Emin = 1.98133E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 35. excited state + 37 MT = 102 Q = 1.14560E+01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 5011.82c : (n,gamma) + 38 MT = 103 Q = 2.26241E-01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 40100 : (n,p) + 39 MT = 104 Q = -4.36100E+00 MeV Emin = 4.80031E+00 MeV frac = 1.00000E+00 Product nuclide = 4009.82c : (n,d) + 40 MT = 107 Q = 2.79000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 3007.82c : (n,alpha) + 41 MT = 113 Q = 3.24000E-01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t2alpha) + + 4 additional transport branches: + + 1 MT = 103 Q = 2.26241E-01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -4.36100E+00 MeV Emin = 4.80031E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 107 Q = 2.79000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 4 MT = 113 Q = 3.24000E-01 MeV Emin = 1.00000E-11 MeV frac = 2.00000E+00 Product nuclide = 2004.82c : (n,t2alpha) + + 14 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 4.80031E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 600 Q = 2.26241E-01 MeV Emin = 1.00000E-11 MeV : (n,p) to ground state + 7 MT = 601 Q = -3.14179E+00 MeV Emin = 3.45828E+00 MeV : (n,p1) + 8 MT = 602 Q = -5.73215E+00 MeV Emin = 6.30959E+00 MeV : (n,p2) + 9 MT = 603 Q = -5.73366E+00 MeV Emin = 6.31125E+00 MeV : (n,p3) + 10 MT = 604 Q = -5.95306E+00 MeV Emin = 6.55275E+00 MeV : (n,p4) + 11 MT = 605 Q = -6.03706E+00 MeV Emin = 6.64521E+00 MeV : (n,p5) + 12 MT = 800 Q = 2.79000E+00 MeV Emin = 1.00000E-11 MeV : (n,alpha) to ground state + 13 MT = 801 Q = 2.31239E+00 MeV Emin = 1.00000E-11 MeV : (n,a1) + 14 MT = 4 Q = 0.00000E+00 MeV Emin = 7.70357E-01 MeV : total inelastic scattering + + Nuclide 11 / 1657 : 5011.82c -- boron 11 (B-11) + + Pointers : 67693 19419 + Primary type : Transport + Nuclide ZAI : 50110 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/B11.ACE + Atomic weight (AW) : 11.00928 + Atomic weight ratio (AWR) : 10.91470 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 19 reaction channels + - 5 special reactions + - 7 transmutation reactions + - 5 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 19 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.14541E+01 MeV Emin = 1.25036E+01 MeV frac = 1.00000E+00 Product nuclide = 5010.82c : (n,2n) + 3 MT = 22 Q = -8.66370E+00 MeV Emin = 9.45750E+00 MeV frac = 1.00000E+00 Product nuclide = 3007.82c : (n,nalpha) + 4 MT = 28 Q = -1.12280E+01 MeV Emin = 1.22567E+01 MeV frac = 1.00000E+00 Product nuclide = 40100 : (n,np) + 5 MT = 51 Q = -2.12469E+00 MeV Emin = 2.31935E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -4.44489E+00 MeV Emin = 4.85213E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -5.02031E+00 MeV Emin = 5.48027E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -6.74290E+00 MeV Emin = 7.36070E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -6.79180E+00 MeV Emin = 7.41410E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -7.28551E+00 MeV Emin = 7.95301E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -7.97784E+00 MeV Emin = 8.70880E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -8.56030E+00 MeV Emin = 9.34460E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -8.92020E+00 MeV Emin = 9.73750E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -9.18500E+00 MeV Emin = 1.00270E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 91 Q = -9.18500E+00 MeV Emin = 1.00270E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 16 MT = 102 Q = 3.36987E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 50120 : (n,gamma) + 17 MT = 103 Q = -1.07237E+01 MeV Emin = 1.17062E+01 MeV frac = 1.00000E+00 Product nuclide = 40110 : (n,p) + 18 MT = 105 Q = -9.55824E+00 MeV Emin = 1.04340E+01 MeV frac = 1.00000E+00 Product nuclide = 4009.82c : (n,t) + 19 MT = 107 Q = -6.63095E+00 MeV Emin = 7.23850E+00 MeV frac = 1.00000E+00 Product nuclide = 30080 : (n,alpha) + + 5 additional transport branches: + + 1 MT = 22 Q = -8.66370E+00 MeV Emin = 9.45750E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.12280E+01 MeV Emin = 1.22567E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -1.07237E+01 MeV Emin = 1.17062E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 105 Q = -9.55824E+00 MeV Emin = 1.04340E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 5 MT = 107 Q = -6.63095E+00 MeV Emin = 7.23850E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 5 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.17062E+01 MeV : total proton production + 2 MT = 205 Q = 0.00000E+00 MeV Emin = 1.04340E+01 MeV : total triton production + 3 MT = 207 Q = 0.00000E+00 MeV Emin = 7.23850E+00 MeV : total alpha production + 4 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 5 MT = 4 Q = 0.00000E+00 MeV Emin = 2.31935E+00 MeV : total inelastic scattering + + Nuclide 12 / 1657 : 6000.82c -- natural carbon (C-nat) + + Pointers : 3496705 20339 + Primary type : Transport + Nuclide ZAI : 60000 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/C0.ACE + Atomic weight (AW) : 12.00110 + Atomic weight ratio (AWR) : 11.89800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 1.50000E+02 + Half-life : N/A + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is not involved in burnup calculation + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has no decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 20 reaction channels + - 5 special reactions + - No transmutation reactions + - 4 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + 20 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 : elastic scattering + 2 MT = 5 Q = 0.00000E+00 MeV Emin = 2.00000E+01 MeV frac = 1.00000E+00 : anything + 3 MT = 28 Q = -1.59570E+01 MeV Emin = 1.72982E+01 MeV frac = 1.00000E+00 : (n,np) + 4 MT = 51 Q = -4.43900E+00 MeV Emin = 4.81209E+00 MeV frac = 1.00000E+00 : inelastic scatt. to 1. excited state + 5 MT = 52 Q = -7.65300E+00 MeV Emin = 8.29622E+00 MeV frac = 1.00000E+00 : inelastic scatt. to 2. excited state + 6 MT = 53 Q = -9.63800E+00 MeV Emin = 1.04481E+01 MeV frac = 1.00000E+00 : inelastic scatt. to 3. excited state + 7 MT = 54 Q = -1.08000E+01 MeV Emin = 1.17080E+01 MeV frac = 1.00000E+00 : inelastic scatt. to 4. excited state + 8 MT = 55 Q = -1.18000E+01 MeV Emin = 1.27920E+01 MeV frac = 1.00000E+00 : inelastic scatt. to 5. excited state + 9 MT = 56 Q = -1.27000E+01 MeV Emin = 1.37674E+01 MeV frac = 1.00000E+00 : inelastic scatt. to 6. excited state + 10 MT = 57 Q = -1.33500E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 : inelastic scatt. to 7. excited state + 11 MT = 58 Q = -1.40800E+01 MeV Emin = 1.52634E+01 MeV frac = 1.00000E+00 : inelastic scatt. to 8. excited state + 12 MT = 59 Q = -1.50800E+01 MeV Emin = 1.63474E+01 MeV frac = 1.00000E+00 : inelastic scatt. to 9. excited state + 13 MT = 60 Q = -1.60800E+01 MeV Emin = 1.74315E+01 MeV frac = 1.00000E+00 : inelastic scatt. to 10. excited state + 14 MT = 61 Q = -1.70800E+01 MeV Emin = 1.85160E+01 MeV frac = 1.00000E+00 : inelastic scatt. to 11. excited state + 15 MT = 62 Q = -1.80800E+01 MeV Emin = 1.96000E+01 MeV frac = 1.00000E+00 : inelastic scatt. to 12. excited state + 16 MT = 91 Q = -7.27500E+00 MeV Emin = 7.88645E+00 MeV frac = 1.00000E+00 : inelastic scattering to continuum + 17 MT = 102 Q = 4.94700E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 : (n,gamma) + 18 MT = 103 Q = -1.25880E+01 MeV Emin = 1.44720E+01 MeV frac = 1.00000E+00 : (n,p) + 19 MT = 104 Q = -1.37330E+01 MeV Emin = 1.52630E+01 MeV frac = 1.00000E+00 : (n,d) + 20 MT = 107 Q = -5.70200E+00 MeV Emin = 6.18124E+00 MeV frac = 1.00000E+00 : (n,alpha) + + 4 additional transport branches: + + 1 MT = 28 Q = -1.59570E+01 MeV Emin = 1.72982E+01 MeV frac = 1.00000E+00 : (n,np) + 2 MT = 103 Q = -1.25880E+01 MeV Emin = 1.44720E+01 MeV frac = 1.00000E+00 : (n,p) + 3 MT = 104 Q = -1.37330E+01 MeV Emin = 1.52630E+01 MeV frac = 1.00000E+00 : (n,d) + 4 MT = 107 Q = -5.70200E+00 MeV Emin = 6.18124E+00 MeV frac = 1.00000E+00 : (n,alpha) + + 5 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.44720E+01 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.52630E+01 MeV : total deuteron production + 3 MT = 207 Q = 0.00000E+00 MeV Emin = 6.18124E+00 MeV : total alpha production + 4 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 5 MT = 4 Q = 0.00000E+00 MeV Emin = 4.81209E+00 MeV : total inelastic scattering + + Nuclide 13 / 1657 : 7014.82c -- nitrogen 14 (N-14) + + Pointers : 71785 28159 + Primary type : Transport + Nuclide ZAI : 70140 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/N14.ACE + Atomic weight (AW) : 14.00307 + Atomic weight ratio (AWR) : 13.88278 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 1.50000E+02 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 36 reaction channels + - 30 special reactions + - 7 transmutation reactions + - 5 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 36 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 5 Q = 0.00000E+00 MeV Emin = 2.00000E+01 MeV frac = 1.00000E+00 Product nuclide = self : anything + 3 MT = 16 Q = -1.05535E+01 MeV Emin = 1.13137E+01 MeV frac = 1.00000E+00 Product nuclide = 70130 : (n,2n) + 4 MT = 51 Q = -2.31280E+00 MeV Emin = 2.47939E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 5 MT = 52 Q = -3.94810E+00 MeV Emin = 4.23249E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 6 MT = 53 Q = -4.91510E+00 MeV Emin = 5.26914E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 7 MT = 54 Q = -5.10589E+00 MeV Emin = 5.47368E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 8 MT = 55 Q = -5.69144E+00 MeV Emin = 6.10141E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 9 MT = 56 Q = -5.83425E+00 MeV Emin = 6.25450E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 10 MT = 57 Q = -6.20350E+00 MeV Emin = 6.65035E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 11 MT = 58 Q = -6.44617E+00 MeV Emin = 6.91050E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 12 MT = 59 Q = -7.02912E+00 MeV Emin = 7.53544E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 13 MT = 60 Q = -7.96690E+00 MeV Emin = 8.54077E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 14 MT = 61 Q = -8.06200E+00 MeV Emin = 8.64272E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 15 MT = 62 Q = -8.48990E+00 MeV Emin = 9.10145E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 16 MT = 63 Q = -8.75000E+00 MeV Emin = 9.38028E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 17 MT = 64 Q = -9.25000E+00 MeV Emin = 9.91630E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 18 MT = 65 Q = -9.75000E+00 MeV Emin = 1.04523E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 19 MT = 66 Q = -1.02500E+01 MeV Emin = 1.09883E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 20 MT = 67 Q = -1.07500E+01 MeV Emin = 1.15244E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 21 MT = 68 Q = -1.12500E+01 MeV Emin = 1.20604E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 22 MT = 69 Q = -1.17500E+01 MeV Emin = 1.25964E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 23 MT = 70 Q = -1.22500E+01 MeV Emin = 1.31324E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 24 MT = 71 Q = -1.27500E+01 MeV Emin = 1.36684E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 25 MT = 72 Q = -1.32500E+01 MeV Emin = 1.42044E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 26 MT = 73 Q = -1.40000E+01 MeV Emin = 1.50084E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 27 MT = 74 Q = -1.50000E+01 MeV Emin = 1.60805E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 28 MT = 75 Q = -1.60000E+01 MeV Emin = 1.71525E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 29 MT = 76 Q = -1.70000E+01 MeV Emin = 1.82246E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 30 MT = 77 Q = -1.80000E+01 MeV Emin = 1.92970E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 27. excited state + 31 MT = 102 Q = 1.08334E+01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 7015.82c : (n,gamma) + 32 MT = 103 Q = 6.25876E-01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 60140 : (n,p) + 33 MT = 104 Q = -5.32604E+00 MeV Emin = 5.70969E+00 MeV frac = 1.00000E+00 Product nuclide = 60130 : (n,d) + 34 MT = 105 Q = -4.01510E+00 MeV Emin = 4.30432E+00 MeV frac = 1.00000E+00 Product nuclide = 60120 : (n,t) + 35 MT = 107 Q = -1.58297E-01 MeV Emin = 2.75000E-01 MeV frac = 1.00000E+00 Product nuclide = 5011.82c : (n,alpha) + 36 MT = 108 Q = -8.82201E+00 MeV Emin = 9.45747E+00 MeV frac = 1.00000E+00 Product nuclide = 3007.82c : (n,2alpha) + + 5 additional transport branches: + + 1 MT = 103 Q = 6.25876E-01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -5.32604E+00 MeV Emin = 5.70969E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -4.01510E+00 MeV Emin = 4.30432E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 107 Q = -1.58297E-01 MeV Emin = 2.75000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 5 MT = 108 Q = -8.82201E+00 MeV Emin = 9.45747E+00 MeV frac = 2.00000E+00 Product nuclide = 2004.82c : (n,2alpha) + + 30 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.70969E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 4.30432E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 2.75000E-01 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 600 Q = 6.25876E-01 MeV Emin = 1.00000E-11 MeV : (n,p) to ground state + 7 MT = 601 Q = -5.46793E+00 MeV Emin = 5.86179E+00 MeV : (n,p1) + 8 MT = 602 Q = -5.96352E+00 MeV Emin = 6.39309E+00 MeV : (n,p2) + 9 MT = 603 Q = -6.10233E+00 MeV Emin = 6.54189E+00 MeV : (n,p3) + 10 MT = 604 Q = -6.27672E+00 MeV Emin = 6.72885E+00 MeV : (n,p4) + 11 MT = 605 Q = -6.38612E+00 MeV Emin = 6.84613E+00 MeV : (n,p5) + 12 MT = 606 Q = -6.71553E+00 MeV Emin = 7.19926E+00 MeV : (n,p6) + 13 MT = 650 Q = -5.32604E+00 MeV Emin = 5.70969E+00 MeV : (n,d) to ground state + 14 MT = 651 Q = -8.41545E+00 MeV Emin = 9.02163E+00 MeV : (n,d1) + 15 MT = 652 Q = -9.01055E+00 MeV Emin = 9.65959E+00 MeV : (n,d2) + 16 MT = 653 Q = -9.17985E+00 MeV Emin = 9.84109E+00 MeV : (n,d3) + 17 MT = 700 Q = -4.01510E+00 MeV Emin = 4.30432E+00 MeV : (n,t) to ground state + 18 MT = 701 Q = -8.45401E+00 MeV Emin = 9.06297E+00 MeV : (n,t1) + 19 MT = 800 Q = -1.58297E-01 MeV Emin = 2.75000E-01 MeV : (n,alpha) to ground state + 20 MT = 801 Q = -2.28299E+00 MeV Emin = 2.44744E+00 MeV : (n,a1) + 21 MT = 802 Q = -4.60319E+00 MeV Emin = 4.93476E+00 MeV : (n,a2) + 22 MT = 803 Q = -5.17861E+00 MeV Emin = 5.55163E+00 MeV : (n,a3) + 23 MT = 804 Q = -6.90120E+00 MeV Emin = 7.39830E+00 MeV : (n,a4) + 24 MT = 805 Q = -6.95010E+00 MeV Emin = 7.45073E+00 MeV : (n,a5) + 25 MT = 806 Q = -7.44381E+00 MeV Emin = 7.98000E+00 MeV : (n,a6) + 26 MT = 807 Q = -8.13614E+00 MeV Emin = 8.72220E+00 MeV : (n,a7) + 27 MT = 808 Q = -8.71860E+00 MeV Emin = 9.34661E+00 MeV : (n,a8) + 28 MT = 809 Q = -9.07850E+00 MeV Emin = 9.73244E+00 MeV : (n,a9) + 29 MT = 810 Q = -9.34330E+00 MeV Emin = 1.00163E+01 MeV : (n,a10) + 30 MT = 4 Q = 0.00000E+00 MeV Emin = 2.47939E+00 MeV : total inelastic scattering + + Nuclide 14 / 1657 : 7015.82c -- nitrogen 15 (N-15) + + Pointers : 77079 28205 + Primary type : Transport + Nuclide ZAI : 70150 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/N15.ACE + Atomic weight (AW) : 14.99986 + Atomic weight ratio (AWR) : 14.87100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 17 reaction channels + - 6 special reactions + - 8 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 17 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.08330E+01 MeV Emin = 1.15615E+01 MeV frac = 1.00000E+00 Product nuclide = 7014.82c : (n,2n) + 3 MT = 22 Q = -1.09910E+01 MeV Emin = 1.17301E+01 MeV frac = 1.00000E+00 Product nuclide = 5011.82c : (n,nalpha) + 4 MT = 28 Q = -1.02070E+01 MeV Emin = 1.08934E+01 MeV frac = 1.00000E+00 Product nuclide = 60140 : (n,np) + 5 MT = 51 Q = -5.27010E+00 MeV Emin = 5.62450E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -5.29880E+00 MeV Emin = 5.65512E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -6.32390E+00 MeV Emin = 6.74915E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -7.15510E+00 MeV Emin = 7.63625E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -7.30110E+00 MeV Emin = 7.79210E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -7.56710E+00 MeV Emin = 8.07595E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -8.31280E+00 MeV Emin = 8.87180E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 91 Q = -8.31280E+00 MeV Emin = 8.87180E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 13 MT = 102 Q = 2.49000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 70160 : (n,gamma) + 14 MT = 103 Q = -8.98930E+00 MeV Emin = 9.59380E+00 MeV frac = 1.00000E+00 Product nuclide = 60150 : (n,p) + 15 MT = 104 Q = -7.98280E+00 MeV Emin = 8.51960E+00 MeV frac = 1.00000E+00 Product nuclide = 60140 : (n,d) + 16 MT = 105 Q = -9.90200E+00 MeV Emin = 1.05680E+01 MeV frac = 1.00000E+00 Product nuclide = 60130 : (n,t) + 17 MT = 107 Q = -7.62150E+00 MeV Emin = 8.13401E+00 MeV frac = 1.00000E+00 Product nuclide = 50120 : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = -1.09910E+01 MeV Emin = 1.17301E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.02070E+01 MeV Emin = 1.08934E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -8.98930E+00 MeV Emin = 9.59380E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -7.98280E+00 MeV Emin = 8.51960E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -9.90200E+00 MeV Emin = 1.05680E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 107 Q = -7.62150E+00 MeV Emin = 8.13401E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 9.59380E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.51960E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.05680E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 8.13401E+00 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 5.62450E+00 MeV : total inelastic scattering + + Nuclide 15 / 1657 : 8016.82c -- oxygen 16 (O-16) + + Pointers : 80953 29355 + Primary type : Transport + Nuclide ZAI : 80160 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/O16.ACE + Atomic weight (AW) : 15.99492 + Atomic weight ratio (AWR) : 15.85751 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 1.50000E+02 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 25 reaction channels + - 45 special reactions + - 10 transmutation reactions + - 15 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 25 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 5 Q = 0.00000E+00 MeV Emin = 3.00000E+01 MeV frac = 1.00000E+00 Product nuclide = self : anything + 3 MT = 16 Q = -1.56638E+01 MeV Emin = 1.66516E+01 MeV frac = 1.00000E+00 Product nuclide = 80150 : (n,2n) + 4 MT = 22 Q = -7.16195E+00 MeV Emin = 7.61360E+00 MeV frac = 1.00000E+00 Product nuclide = 60120 : (n,nalpha) + 5 MT = 23 Q = -1.44368E+01 MeV Emin = 1.64100E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,n3alpha) + 6 MT = 28 Q = -1.21276E+01 MeV Emin = 1.28924E+01 MeV frac = 1.00000E+00 Product nuclide = 7015.82c : (n,np) + 7 MT = 32 Q = -2.07363E+01 MeV Emin = 2.20440E+01 MeV frac = 1.00000E+00 Product nuclide = cut: N-14 : (n,nd) + 8 MT = 41 Q = -2.29609E+01 MeV Emin = 2.44089E+01 MeV frac = 1.00000E+00 Product nuclide = cut: N-14 : (n,2np) + 9 MT = 44 Q = -2.23350E+01 MeV Emin = 2.37435E+01 MeV frac = 1.00000E+00 Product nuclide = cut: C-14 : (n,n2p) + 10 MT = 45 Q = -2.31192E+01 MeV Emin = 2.45771E+01 MeV frac = 1.00000E+00 Product nuclide = cut: B-11 : (n,npalpha) + 11 MT = 51 Q = -6.04940E+00 MeV Emin = 6.43089E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 12 MT = 52 Q = -6.12989E+00 MeV Emin = 6.51646E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 13 MT = 53 Q = -6.91710E+00 MeV Emin = 7.35330E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 14 MT = 54 Q = -7.11685E+00 MeV Emin = 7.56565E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 15 MT = 55 Q = -8.87190E+00 MeV Emin = 9.43138E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 16 MT = 56 Q = -1.09570E+01 MeV Emin = 1.16480E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 17 MT = 57 Q = -1.10800E+01 MeV Emin = 1.17787E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 18 MT = 91 Q = -9.58500E+00 MeV Emin = 1.01895E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 19 MT = 102 Q = 4.14342E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 8017.82c : (n,gamma) + 20 MT = 103 Q = -9.63680E+00 MeV Emin = 1.02445E+01 MeV frac = 1.00000E+00 Product nuclide = 70160 : (n,p) + 21 MT = 104 Q = -9.90300E+00 MeV Emin = 1.05275E+01 MeV frac = 1.00000E+00 Product nuclide = 7015.82c : (n,d) + 22 MT = 105 Q = -1.44790E+01 MeV Emin = 1.53921E+01 MeV frac = 1.00000E+00 Product nuclide = 7014.82c : (n,t) + 23 MT = 107 Q = -2.21430E+00 MeV Emin = 2.35532E+00 MeV frac = 1.00000E+00 Product nuclide = 60130 : (n,alpha) + 24 MT = 108 Q = -1.28632E+01 MeV Emin = 1.36744E+01 MeV frac = 1.00000E+00 Product nuclide = 4009.82c : (n,2alpha) + 25 MT = 112 Q = -1.97491E+01 MeV Emin = 2.09945E+01 MeV frac = 1.00000E+00 Product nuclide = cut: B-12 : (n,palpha) + + 15 additional transport branches: + + 1 MT = 22 Q = -7.16195E+00 MeV Emin = 7.61360E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 23 Q = -1.44368E+01 MeV Emin = 1.64100E+01 MeV frac = 3.00000E+00 Product nuclide = 2004.82c : (n,n3alpha) + 3 MT = 28 Q = -1.21276E+01 MeV Emin = 1.28924E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 4 MT = 32 Q = -2.07363E+01 MeV Emin = 2.20440E+01 MeV frac = 1.00000E+00 Product nuclide = cut: H-2 : (n,nd) + 5 MT = 41 Q = -2.29609E+01 MeV Emin = 2.44089E+01 MeV frac = 1.00000E+00 Product nuclide = cut: H-1 : (n,2np) + 6 MT = 44 Q = -2.23350E+01 MeV Emin = 2.37435E+01 MeV frac = 2.00000E+00 Product nuclide = cut: H-1 : (n,n2p) + 7 MT = 45 Q = -2.31192E+01 MeV Emin = 2.45771E+01 MeV frac = 1.00000E+00 Product nuclide = cut: He-4 : (n,npalpha) + 8 MT = 45 Q = -2.31192E+01 MeV Emin = 2.45771E+01 MeV frac = 1.00000E+00 Product nuclide = cut: H-1 : (n,npalpha) + 9 MT = 103 Q = -9.63680E+00 MeV Emin = 1.02445E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 10 MT = 104 Q = -9.90300E+00 MeV Emin = 1.05275E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 11 MT = 105 Q = -1.44790E+01 MeV Emin = 1.53921E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 12 MT = 107 Q = -2.21430E+00 MeV Emin = 2.35532E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 13 MT = 108 Q = -1.28632E+01 MeV Emin = 1.36744E+01 MeV frac = 2.00000E+00 Product nuclide = 2004.82c : (n,2alpha) + 14 MT = 112 Q = -1.97491E+01 MeV Emin = 2.09945E+01 MeV frac = 1.00000E+00 Product nuclide = cut: He-4 : (n,palpha) + 15 MT = 112 Q = -1.97491E+01 MeV Emin = 2.09945E+01 MeV frac = 1.00000E+00 Product nuclide = cut: H-1 : (n,palpha) + + 45 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.02445E+01 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.05275E+01 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.53921E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 2.35532E+00 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 600 Q = -9.63680E+00 MeV Emin = 1.02445E+01 MeV : (n,p) to ground state + 7 MT = 601 Q = -9.75690E+00 MeV Emin = 1.03722E+01 MeV : (n,p1) + 8 MT = 602 Q = -9.93380E+00 MeV Emin = 1.05602E+01 MeV : (n,p2) + 9 MT = 603 Q = -1.00343E+01 MeV Emin = 1.06671E+01 MeV : (n,p3) + 10 MT = 650 Q = -9.90300E+00 MeV Emin = 1.05275E+01 MeV : (n,d) to ground state + 11 MT = 651 Q = -1.51731E+01 MeV Emin = 1.61300E+01 MeV : (n,d1) + 12 MT = 652 Q = -1.52018E+01 MeV Emin = 1.61610E+01 MeV : (n,d2) + 13 MT = 653 Q = -1.62269E+01 MeV Emin = 1.72502E+01 MeV : (n,d3) + 14 MT = 654 Q = -1.70581E+01 MeV Emin = 1.81338E+01 MeV : (n,d4) + 15 MT = 655 Q = -1.72041E+01 MeV Emin = 1.82890E+01 MeV : (n,d5) + 16 MT = 656 Q = -1.74701E+01 MeV Emin = 1.85718E+01 MeV : (n,d6) + 17 MT = 657 Q = -1.82158E+01 MeV Emin = 1.93645E+01 MeV : (n,d7) + 18 MT = 658 Q = -1.84744E+01 MeV Emin = 1.96394E+01 MeV : (n,d8) + 19 MT = 659 Q = -1.89530E+01 MeV Emin = 2.01482E+01 MeV : (n,d9) + 20 MT = 660 Q = -1.90546E+01 MeV Emin = 2.02562E+01 MeV : (n,d10) + 21 MT = 661 Q = -1.90579E+01 MeV Emin = 2.02597E+01 MeV : (n,d11) + 22 MT = 662 Q = -1.91280E+01 MeV Emin = 2.03343E+01 MeV : (n,d12) + 23 MT = 663 Q = -1.96630E+01 MeV Emin = 2.09030E+01 MeV : (n,d13) + 24 MT = 664 Q = -1.97320E+01 MeV Emin = 2.09763E+01 MeV : (n,d14) + 25 MT = 665 Q = -1.98310E+01 MeV Emin = 2.10816E+01 MeV : (n,d15) + 26 MT = 666 Q = -1.99730E+01 MeV Emin = 2.12325E+01 MeV : (n,d16) + 27 MT = 667 Q = -2.03527E+01 MeV Emin = 2.16362E+01 MeV : (n,d17) + 28 MT = 668 Q = -2.04363E+01 MeV Emin = 2.17251E+01 MeV : (n,d18) + 29 MT = 669 Q = -2.05962E+01 MeV Emin = 2.18950E+01 MeV : (n,d19) + 30 MT = 700 Q = -1.44790E+01 MeV Emin = 1.53921E+01 MeV : (n,t) to ground state + 31 MT = 701 Q = -1.67918E+01 MeV Emin = 1.78507E+01 MeV : (n,t1) + 32 MT = 702 Q = -1.84271E+01 MeV Emin = 1.95892E+01 MeV : (n,t2) + 33 MT = 703 Q = -1.93941E+01 MeV Emin = 2.06171E+01 MeV : (n,t3) + 34 MT = 704 Q = -1.95849E+01 MeV Emin = 2.08200E+01 MeV : (n,t4) + 35 MT = 705 Q = -2.01704E+01 MeV Emin = 2.14424E+01 MeV : (n,t5) + 36 MT = 706 Q = -2.03132E+01 MeV Emin = 2.15942E+01 MeV : (n,t6) + 37 MT = 707 Q = -2.06825E+01 MeV Emin = 2.19868E+01 MeV : (n,t7) + 38 MT = 708 Q = -2.09252E+01 MeV Emin = 2.22448E+01 MeV : (n,t8) + 39 MT = 709 Q = -2.15081E+01 MeV Emin = 2.28645E+01 MeV : (n,t9) + 40 MT = 749 Q = -2.15081E+01 MeV Emin = 2.28645E+01 MeV : (n,t) to continuum + 41 MT = 800 Q = -2.21430E+00 MeV Emin = 2.35532E+00 MeV : (n,alpha) to ground state + 42 MT = 801 Q = -5.30500E+00 MeV Emin = 5.63954E+00 MeV : (n,a1) + 43 MT = 802 Q = -5.90010E+00 MeV Emin = 6.27217E+00 MeV : (n,a2) + 44 MT = 803 Q = -6.06940E+00 MeV Emin = 6.45215E+00 MeV : (n,a3) + 45 MT = 4 Q = 0.00000E+00 MeV Emin = 6.43089E+00 MeV : total inelastic scattering + + Nuclide 16 / 1657 : 8017.82c -- oxygen 17 (O-17) + + Pointers : 87269 29401 + Primary type : Transport + Nuclide ZAI : 80170 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/O17.ACE + Atomic weight (AW) : 16.99913 + Atomic weight ratio (AWR) : 16.85310 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 21 reaction channels + - 5 special reactions + - 7 transmutation reactions + - 5 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 21 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -4.14430E+00 MeV Emin = 7.76000E+00 MeV frac = 1.00000E+00 Product nuclide = 8016.82c : (n,2n) + 3 MT = 22 Q = -6.35300E+00 MeV Emin = 7.76000E+00 MeV frac = 1.00000E+00 Product nuclide = 60130 : (n,nalpha) + 4 MT = 28 Q = -1.37810E+01 MeV Emin = 1.45987E+01 MeV frac = 1.00000E+00 Product nuclide = 70160 : (n,np) + 5 MT = 51 Q = -8.70800E-01 MeV Emin = 9.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -3.05500E+00 MeV Emin = 3.23627E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -3.84100E+00 MeV Emin = 4.06980E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -4.55300E+00 MeV Emin = 4.82316E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -5.08600E+00 MeV Emin = 5.38779E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -5.21500E+00 MeV Emin = 5.52444E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -5.38000E+00 MeV Emin = 5.69923E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -5.69800E+00 MeV Emin = 6.03610E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -5.73400E+00 MeV Emin = 6.07423E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -5.87000E+00 MeV Emin = 6.21830E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -5.94000E+00 MeV Emin = 6.29246E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -6.35700E+00 MeV Emin = 6.73420E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 91 Q = -6.35700E+00 MeV Emin = 6.90000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 18 MT = 102 Q = 8.04700E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 80180 : (n,gamma) + 19 MT = 103 Q = -7.89600E+00 MeV Emin = 8.36452E+00 MeV frac = 1.00000E+00 Product nuclide = 70170 : (n,p) + 20 MT = 104 Q = -1.15550E+01 MeV Emin = 1.22412E+01 MeV frac = 1.00000E+00 Product nuclide = 70160 : (n,d) + 21 MT = 107 Q = 1.81940E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 60140 : (n,alpha) + + 5 additional transport branches: + + 1 MT = 22 Q = -6.35300E+00 MeV Emin = 7.76000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.37810E+01 MeV Emin = 1.45987E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -7.89600E+00 MeV Emin = 8.36452E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -1.15550E+01 MeV Emin = 1.22412E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 107 Q = 1.81940E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 5 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 8.36452E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.22412E+01 MeV : total deuteron production + 3 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 4 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 5 MT = 4 Q = 0.00000E+00 MeV Emin = 9.00000E-01 MeV : total inelastic scattering + + Nuclide 17 / 1657 : 9019.82c -- fluorine 19 (F-19) + + Pointers : 90379 23973 + Primary type : Transport + Nuclide ZAI : 90190 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/F19.ACE + Atomic weight (AW) : 18.99820 + Atomic weight ratio (AWR) : 18.83500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 31 reaction channels + - 6 special reactions + - 8 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 31 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.04310E+01 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 90180 : (n,2n) + 3 MT = 22 Q = -4.01290E+00 MeV Emin = 4.22600E+00 MeV frac = 1.00000E+00 Product nuclide = 7015.82c : (n,nalpha) + 4 MT = 28 Q = -7.99300E+00 MeV Emin = 8.41740E+00 MeV frac = 1.00000E+00 Product nuclide = 80180 : (n,np) + 5 MT = 51 Q = -1.09900E-01 MeV Emin = 1.15125E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -1.97100E-01 MeV Emin = 2.05000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -1.34600E+00 MeV Emin = 1.41650E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -1.45900E+00 MeV Emin = 1.52000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -1.55400E+00 MeV Emin = 1.62825E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -2.78000E+00 MeV Emin = 2.92760E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -3.90700E+00 MeV Emin = 4.11443E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -3.99900E+00 MeV Emin = 4.21132E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -4.03200E+00 MeV Emin = 4.24610E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -4.37800E+00 MeV Emin = 4.61044E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -4.54900E+00 MeV Emin = 4.79052E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -4.55800E+00 MeV Emin = 4.80000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 63 Q = -4.64800E+00 MeV Emin = 4.89480E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 18 MT = 64 Q = -4.68300E+00 MeV Emin = 4.93163E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 19 MT = 65 Q = -5.10600E+00 MeV Emin = 5.37710E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 20 MT = 66 Q = -5.36600E+00 MeV Emin = 5.65090E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 21 MT = 67 Q = -5.43000E+00 MeV Emin = 5.71830E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 22 MT = 68 Q = -5.46400E+00 MeV Emin = 5.75410E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 23 MT = 69 Q = -5.49900E+00 MeV Emin = 5.79100E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 24 MT = 70 Q = -5.54000E+00 MeV Emin = 5.83413E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 25 MT = 71 Q = -5.62100E+00 MeV Emin = 5.91944E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 26 MT = 91 Q = -5.64000E+00 MeV Emin = 5.93944E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 27 MT = 102 Q = 6.60130E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 90200 : (n,gamma) + 28 MT = 103 Q = -4.03600E+00 MeV Emin = 4.25030E+00 MeV frac = 1.00000E+00 Product nuclide = 80190 : (n,p) + 29 MT = 104 Q = -5.76800E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 80180 : (n,d) + 30 MT = 105 Q = -7.55700E+00 MeV Emin = 9.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 8017.82c : (n,t) + 31 MT = 107 Q = -1.52300E+00 MeV Emin = 1.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 70160 : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = -4.01290E+00 MeV Emin = 4.22600E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -7.99300E+00 MeV Emin = 8.41740E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -4.03600E+00 MeV Emin = 4.25030E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -5.76800E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -7.55700E+00 MeV Emin = 9.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 107 Q = -1.52300E+00 MeV Emin = 1.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.25030E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.50000E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 1.60000E+00 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 1.15125E-01 MeV : total inelastic scattering + + Nuclide 18 / 1657 : 11022.82c -- sodium 22 (Na-22) + + Pointers : 94850 28251 + Primary type : Transport + Nuclide ZAI : 110220 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Na22.ACE + Atomic weight (AW) : 21.99444 + Atomic weight ratio (AWR) : 21.80550 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 8.21E+07 seconds (2.6 years) + Specific ingestion toxicity : 3.20E-09 Sv/Bq + Specific inhalation toxicity : 1.30E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 21 reaction channels + - 5 special reactions + - 8 transmutation reactions + - 6 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 21 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.05840E+01 MeV Emin = 1.10696E+01 MeV frac = 1.00000E+00 Product nuclide = 110210 : (n,2n) + 3 MT = 22 Q = -1.05180E+01 MeV Emin = 1.10004E+01 MeV frac = 1.00000E+00 Product nuclide = 90180 : (n,nalpha) + 4 MT = 28 Q = -6.69310E+00 MeV Emin = 7.00005E+00 MeV frac = 1.00000E+00 Product nuclide = 100210 : (n,np) + 5 MT = 51 Q = -5.83000E-01 MeV Emin = 6.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -6.57000E-01 MeV Emin = 6.57000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -8.90900E-01 MeV Emin = 9.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -1.52800E+00 MeV Emin = 1.57500E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -1.93700E+00 MeV Emin = 2.02583E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -1.95200E+00 MeV Emin = 2.04152E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -1.98400E+00 MeV Emin = 2.07499E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -2.21200E+00 MeV Emin = 2.31344E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -2.57200E+00 MeV Emin = 2.68995E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -2.96900E+00 MeV Emin = 3.10516E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -3.06000E+00 MeV Emin = 3.20033E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 91 Q = -3.36470E+00 MeV Emin = 3.51901E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 17 MT = 102 Q = 1.24200E+01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 11023.82c : (n,gamma) + 18 MT = 103 Q = 3.62500E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 100220 : (n,p) + 19 MT = 104 Q = -3.82460E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 100210 : (n,d) + 20 MT = 107 Q = 1.95000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 9019.82c : (n,alpha) + 21 MT = 108 Q = -2.06400E+00 MeV Emin = 2.15900E+00 MeV frac = 1.00000E+00 Product nuclide = 7015.82c : (n,2alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = -1.05180E+01 MeV Emin = 1.10004E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -6.69310E+00 MeV Emin = 7.00005E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = 3.62500E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -3.82460E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 107 Q = 1.95000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 108 Q = -2.06400E+00 MeV Emin = 2.15900E+00 MeV frac = 2.00000E+00 Product nuclide = 2004.82c : (n,2alpha) + + 5 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 4.00000E+00 MeV : total deuteron production + 3 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 4 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 5 MT = 4 Q = 0.00000E+00 MeV Emin = 6.00000E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 2 Q = 2.84302E+00 MeV frac = 1.00000E+00 Product nuclide = 100220 : EC/beta+ + + Nuclide 19 / 1657 : 11023.82c -- sodium 23 (Na-23) + + Pointers : 97473 28297 + Primary type : Transport + Nuclide ZAI : 110230 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Na23.ACE + Atomic weight (AW) : 22.98980 + Atomic weight ratio (AWR) : 22.79230 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 35 reaction channels + - 4 special reactions + - 6 transmutation reactions + - 5 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 35 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.24180E+01 MeV Emin = 1.29628E+01 MeV frac = 1.00000E+00 Product nuclide = 11022.82c : (n,2n) + 3 MT = 22 Q = -1.04680E+01 MeV Emin = 1.09273E+01 MeV frac = 1.00000E+00 Product nuclide = 9019.82c : (n,nalpha) + 4 MT = 28 Q = -8.79310E+00 MeV Emin = 9.17889E+00 MeV frac = 1.00000E+00 Product nuclide = 100220 : (n,np) + 5 MT = 51 Q = -4.39900E-01 MeV Emin = 4.58754E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -2.07640E+00 MeV Emin = 2.16750E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -2.39090E+00 MeV Emin = 2.49580E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -2.63980E+00 MeV Emin = 2.75562E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -2.70370E+00 MeV Emin = 2.82232E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -2.98240E+00 MeV Emin = 3.11325E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -3.67830E+00 MeV Emin = 3.83968E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -3.84800E+00 MeV Emin = 4.01683E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -3.91470E+00 MeV Emin = 4.08646E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -4.43200E+00 MeV Emin = 4.62645E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -4.77560E+00 MeV Emin = 4.98513E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -5.38000E+00 MeV Emin = 5.61605E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 63 Q = -5.53600E+00 MeV Emin = 5.77889E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 18 MT = 64 Q = -5.74100E+00 MeV Emin = 5.99288E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 19 MT = 65 Q = -5.76600E+00 MeV Emin = 6.01898E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 20 MT = 66 Q = -5.93100E+00 MeV Emin = 6.19122E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 21 MT = 67 Q = -5.96700E+00 MeV Emin = 6.22880E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 22 MT = 68 Q = -6.04300E+00 MeV Emin = 6.30813E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 23 MT = 69 Q = -6.11700E+00 MeV Emin = 6.38538E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 24 MT = 70 Q = -6.19100E+00 MeV Emin = 6.46263E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 25 MT = 71 Q = -6.23600E+00 MeV Emin = 6.50960E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 26 MT = 72 Q = -6.30800E+00 MeV Emin = 6.58476E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 27 MT = 73 Q = -6.35060E+00 MeV Emin = 6.62923E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 28 MT = 74 Q = -6.57700E+00 MeV Emin = 6.86556E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 29 MT = 75 Q = -6.61700E+00 MeV Emin = 6.90732E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 30 MT = 76 Q = -6.73400E+00 MeV Emin = 7.02945E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 31 MT = 77 Q = -6.86800E+00 MeV Emin = 7.16933E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 27. excited state + 32 MT = 91 Q = -6.90000E+00 MeV Emin = 7.20273E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 33 MT = 102 Q = 6.95930E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 110240 : (n,gamma) + 34 MT = 103 Q = -3.59650E+00 MeV Emin = 3.75430E+00 MeV frac = 1.00000E+00 Product nuclide = 100230 : (n,p) + 35 MT = 107 Q = -3.86660E+00 MeV Emin = 4.03625E+00 MeV frac = 1.00000E+00 Product nuclide = 90200 : (n,alpha) + + 5 additional transport branches: + + 1 MT = 22 Q = -1.04680E+01 MeV Emin = 1.09273E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -8.79310E+00 MeV Emin = 9.17889E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 102 Q = 6.95930E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 110241 : (n,gamma) + 4 MT = 103 Q = -3.59650E+00 MeV Emin = 3.75430E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 107 Q = -3.86660E+00 MeV Emin = 4.03625E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 4 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.75430E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 4.03625E+00 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 4 MT = 4 Q = 0.00000E+00 MeV Emin = 4.58754E-01 MeV : total inelastic scattering + + Nuclide 20 / 1657 : 12024.82c -- magnesium 24 (Mg-24) + + Pointers : 103107 27607 + Primary type : Transport + Nuclide ZAI : 120240 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Mg24.ACE + Atomic weight (AW) : 23.98504 + Atomic weight ratio (AWR) : 23.77900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 19 reaction channels + - 4 special reactions + - 6 transmutation reactions + - 4 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 19 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.65306E+01 MeV Emin = 1.72258E+01 MeV frac = 1.00000E+00 Product nuclide = 120230 : (n,2n) + 3 MT = 22 Q = -9.31453E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 100200 : (n,nalpha) + 4 MT = 28 Q = -1.16915E+01 MeV Emin = 1.21832E+01 MeV frac = 1.00000E+00 Product nuclide = 11023.82c : (n,np) + 5 MT = 51 Q = -1.36860E+00 MeV Emin = 1.41439E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -4.11999E+00 MeV Emin = 4.29330E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -4.23839E+00 MeV Emin = 4.41664E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -5.23609E+00 MeV Emin = 5.45630E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -6.01029E+00 MeV Emin = 6.26306E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -6.43219E+00 MeV Emin = 6.70270E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -7.34789E+00 MeV Emin = 7.65691E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -7.55299E+00 MeV Emin = 7.87063E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -7.61619E+00 MeV Emin = 7.93649E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -7.74719E+00 MeV Emin = 8.07300E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -7.81199E+00 MeV Emin = 8.14053E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 91 Q = -1.00000E+01 MeV Emin = 1.04206E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 17 MT = 102 Q = 7.33189E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 12025.82c : (n,gamma) + 18 MT = 103 Q = -4.73209E+00 MeV Emin = 4.93113E+00 MeV frac = 1.00000E+00 Product nuclide = 110240 : (n,p) + 19 MT = 107 Q = -2.55335E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 100210 : (n,alpha) + + 4 additional transport branches: + + 1 MT = 22 Q = -9.31453E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.16915E+01 MeV Emin = 1.21832E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -4.73209E+00 MeV Emin = 4.93113E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 107 Q = -2.55335E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 4 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.93113E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 4.00000E+00 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 4 MT = 4 Q = 0.00000E+00 MeV Emin = 1.41439E+00 MeV : total inelastic scattering + + Nuclide 21 / 1657 : 12025.82c -- magnesium 25 (Mg-25) + + Pointers : 105189 27653 + Primary type : Transport + Nuclide ZAI : 120250 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Mg25.ACE + Atomic weight (AW) : 24.98584 + Atomic weight ratio (AWR) : 24.77120 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 25 reaction channels + - 4 special reactions + - 6 transmutation reactions + - 4 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 25 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.33188E+00 MeV Emin = 7.62787E+00 MeV frac = 1.00000E+00 Product nuclide = 12024.82c : (n,2n) + 3 MT = 22 Q = -9.88523E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 100210 : (n,nalpha) + 4 MT = 28 Q = -1.20640E+01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 110240 : (n,np) + 5 MT = 51 Q = -5.85099E-01 MeV Emin = 6.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -9.74799E-01 MeV Emin = 1.00707E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -1.61180E+00 MeV Emin = 1.67243E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -1.96470E+00 MeV Emin = 2.04401E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -2.56380E+00 MeV Emin = 2.66730E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -2.73770E+00 MeV Emin = 2.84822E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -2.80110E+00 MeV Emin = 2.91418E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -3.40519E+00 MeV Emin = 3.54267E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -3.41369E+00 MeV Emin = 3.55151E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -3.90779E+00 MeV Emin = 4.06556E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -3.97069E+00 MeV Emin = 4.13100E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -4.05959E+00 MeV Emin = 4.22348E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 63 Q = -4.27699E+00 MeV Emin = 4.44966E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 18 MT = 64 Q = -4.35939E+00 MeV Emin = 4.53539E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 19 MT = 65 Q = -4.71139E+00 MeV Emin = 4.90160E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 20 MT = 66 Q = -4.72199E+00 MeV Emin = 4.91262E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 21 MT = 67 Q = -5.01219E+00 MeV Emin = 5.21454E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 22 MT = 91 Q = -7.99999E+00 MeV Emin = 8.32296E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 23 MT = 102 Q = 1.10933E+01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 12026.82c : (n,gamma) + 24 MT = 103 Q = -3.05303E+00 MeV Emin = 3.17628E+00 MeV frac = 1.00000E+00 Product nuclide = 110250 : (n,p) + 25 MT = 107 Q = 4.80349E-01 MeV Emin = 9.50000E-01 MeV frac = 1.00000E+00 Product nuclide = 100220 : (n,alpha) + + 4 additional transport branches: + + 1 MT = 22 Q = -9.88523E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.20640E+01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -3.05303E+00 MeV Emin = 3.17628E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 107 Q = 4.80349E-01 MeV Emin = 9.50000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 4 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.17628E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 9.50000E-01 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 4 MT = 4 Q = 0.00000E+00 MeV Emin = 6.00000E-01 MeV : total inelastic scattering + + Nuclide 22 / 1657 : 12026.82c -- magnesium 26 (Mg-26) + + Pointers : 107709 27699 + Primary type : Transport + Nuclide ZAI : 120260 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Mg26.ACE + Atomic weight (AW) : 25.98260 + Atomic weight ratio (AWR) : 25.75940 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 21 reaction channels + - 4 special reactions + - 6 transmutation reactions + - 4 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 21 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.10936E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 12025.82c : (n,2n) + 3 MT = 22 Q = -1.06132E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 100220 : (n,nalpha) + 4 MT = 28 Q = -1.41466E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 110250 : (n,np) + 5 MT = 51 Q = -1.80870E+00 MeV Emin = 1.68946E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -2.93840E+00 MeV Emin = 3.05247E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -3.58799E+00 MeV Emin = 3.72729E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -3.94049E+00 MeV Emin = 4.09347E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -4.31799E+00 MeV Emin = 4.48563E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -4.33199E+00 MeV Emin = 4.50017E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -4.34999E+00 MeV Emin = 4.51887E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -4.83399E+00 MeV Emin = 5.02166E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -4.89999E+00 MeV Emin = 5.09022E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -4.97199E+00 MeV Emin = 5.16502E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -5.29099E+00 MeV Emin = 5.49640E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -5.47399E+00 MeV Emin = 5.68650E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 63 Q = -5.68999E+00 MeV Emin = 5.91089E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 18 MT = 91 Q = -7.99999E+00 MeV Emin = 8.31057E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 19 MT = 102 Q = 6.44429E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 120270 : (n,gamma) + 20 MT = 103 Q = -7.92092E+00 MeV Emin = 8.22843E+00 MeV frac = 1.00000E+00 Product nuclide = 110260 : (n,p) + 21 MT = 107 Q = -5.41664E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 100230 : (n,alpha) + + 4 additional transport branches: + + 1 MT = 22 Q = -1.06132E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.41466E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -7.92092E+00 MeV Emin = 8.22843E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 107 Q = -5.41664E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 4 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 8.22843E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 7.00000E+00 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 4 MT = 4 Q = 0.00000E+00 MeV Emin = 1.68946E+00 MeV : total inelastic scattering + + Nuclide 23 / 1657 : 13027.82c -- aluminum 27 (Al-27) + + Pointers : 111687 18821 + Primary type : Transport + Nuclide ZAI : 130270 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Al27.ACE + Atomic weight (AW) : 26.98154 + Atomic weight ratio (AWR) : 26.74975 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 1.50000E+02 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 57 reaction channels + - 81 special reactions + - 15 transmutation reactions + - 16 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 57 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 5 Q = 0.00000E+00 MeV Emin = 2.00000E+01 MeV frac = 1.00000E+00 Product nuclide = self : anything + 3 MT = 16 Q = -1.30582E+01 MeV Emin = 1.35464E+01 MeV frac = 1.00000E+00 Product nuclide = 130260 : (n,2n) + 4 MT = 22 Q = -1.00898E+01 MeV Emin = 1.04670E+01 MeV frac = 1.00000E+00 Product nuclide = 11023.82c : (n,nalpha) + 5 MT = 28 Q = -8.27213E+00 MeV Emin = 8.58137E+00 MeV frac = 1.00000E+00 Product nuclide = 12026.82c : (n,np) + 6 MT = 32 Q = -1.71402E+01 MeV Emin = 1.77810E+01 MeV frac = 1.00000E+00 Product nuclide = 12025.82c : (n,nd) + 7 MT = 33 Q = -1.82136E+01 MeV Emin = 1.88945E+01 MeV frac = 1.00000E+00 Product nuclide = 12024.82c : (n,nt) + 8 MT = 45 Q = -1.88839E+01 MeV Emin = 1.95899E+01 MeV frac = 1.00000E+00 Product nuclide = 100220 : (n,npalpha) + 9 MT = 51 Q = -8.43750E-01 MeV Emin = 8.74000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 10 MT = 52 Q = -1.01445E+00 MeV Emin = 1.05000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 11 MT = 53 Q = -2.21110E+00 MeV Emin = 2.29376E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 12 MT = 54 Q = -2.73480E+00 MeV Emin = 2.83704E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 13 MT = 55 Q = -2.98110E+00 MeV Emin = 3.09254E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 14 MT = 56 Q = -3.00400E+00 MeV Emin = 3.11630E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 15 MT = 57 Q = -3.68010E+00 MeV Emin = 3.81768E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 16 MT = 58 Q = -3.95680E+00 MeV Emin = 4.10472E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 17 MT = 59 Q = -4.05430E+00 MeV Emin = 4.20587E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 18 MT = 60 Q = -4.41020E+00 MeV Emin = 4.57507E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 19 MT = 61 Q = -4.51030E+00 MeV Emin = 4.67891E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 20 MT = 62 Q = -4.58000E+00 MeV Emin = 4.75122E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 21 MT = 63 Q = -4.81170E+00 MeV Emin = 4.99158E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 22 MT = 64 Q = -5.15630E+00 MeV Emin = 5.34906E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 23 MT = 65 Q = -5.24820E+00 MeV Emin = 5.44440E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 24 MT = 66 Q = -5.41990E+00 MeV Emin = 5.62252E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 25 MT = 67 Q = -5.43280E+00 MeV Emin = 5.63590E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 26 MT = 68 Q = -5.43840E+00 MeV Emin = 5.64171E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 27 MT = 69 Q = -5.49980E+00 MeV Emin = 5.70540E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 28 MT = 70 Q = -5.55070E+00 MeV Emin = 5.75821E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 29 MT = 71 Q = -5.66700E+00 MeV Emin = 5.87885E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 30 MT = 72 Q = -5.75130E+00 MeV Emin = 5.96631E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 31 MT = 73 Q = -5.82680E+00 MeV Emin = 6.04463E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 32 MT = 74 Q = -5.95960E+00 MeV Emin = 6.18239E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 33 MT = 75 Q = -6.08000E+00 MeV Emin = 6.30729E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 34 MT = 76 Q = -6.11540E+00 MeV Emin = 6.34402E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 35 MT = 77 Q = -6.15920E+00 MeV Emin = 6.38945E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 27. excited state + 36 MT = 78 Q = -6.28700E+00 MeV Emin = 6.52203E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 28. excited state + 37 MT = 79 Q = -6.46400E+00 MeV Emin = 6.70565E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 29. excited state + 38 MT = 80 Q = -6.47730E+00 MeV Emin = 6.71945E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 30. excited state + 39 MT = 81 Q = -6.51180E+00 MeV Emin = 6.75523E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 31. excited state + 40 MT = 82 Q = -6.53300E+00 MeV Emin = 6.77723E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 32. excited state + 41 MT = 83 Q = -6.60530E+00 MeV Emin = 6.85223E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 33. excited state + 42 MT = 84 Q = -6.65150E+00 MeV Emin = 6.90016E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 34. excited state + 43 MT = 85 Q = -6.71300E+00 MeV Emin = 6.96396E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 35. excited state + 44 MT = 86 Q = -6.76500E+00 MeV Emin = 7.01790E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 36. excited state + 45 MT = 87 Q = -6.77540E+00 MeV Emin = 7.02869E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 37. excited state + 46 MT = 88 Q = -6.81420E+00 MeV Emin = 7.06894E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 38. excited state + 47 MT = 89 Q = -6.82000E+00 MeV Emin = 7.07496E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 39. excited state + 48 MT = 91 Q = -6.82000E+00 MeV Emin = 7.07496E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 49 MT = 102 Q = 7.72520E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 130280 : (n,gamma) + 50 MT = 103 Q = -1.82855E+00 MeV Emin = 1.89625E+00 MeV frac = 1.00000E+00 Product nuclide = 120270 : (n,p) + 51 MT = 104 Q = -6.04754E+00 MeV Emin = 6.27362E+00 MeV frac = 1.00000E+00 Product nuclide = 12026.82c : (n,d) + 52 MT = 105 Q = -1.08829E+01 MeV Emin = 1.12898E+01 MeV frac = 1.00000E+00 Product nuclide = 12025.82c : (n,t) + 53 MT = 107 Q = -3.13033E+00 MeV Emin = 3.24735E+00 MeV frac = 1.00000E+00 Product nuclide = 110240 : (n,alpha) + 54 MT = 108 Q = -1.39583E+01 MeV Emin = 1.44801E+01 MeV frac = 1.00000E+00 Product nuclide = 90200 : (n,2alpha) + 55 MT = 111 Q = -1.67999E+01 MeV Emin = 1.74279E+01 MeV frac = 1.00000E+00 Product nuclide = 110260 : (n,2p) + 56 MT = 112 Q = -1.36838E+01 MeV Emin = 1.41954E+01 MeV frac = 1.00000E+00 Product nuclide = 100230 : (n,palpha) + 57 MT = 117 Q = -1.66594E+01 MeV Emin = 1.72822E+01 MeV frac = 1.00000E+00 Product nuclide = 100220 : (n,dalpha) + + 16 additional transport branches: + + 1 MT = 22 Q = -1.00898E+01 MeV Emin = 1.04670E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -8.27213E+00 MeV Emin = 8.58137E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.71402E+01 MeV Emin = 1.77810E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.82136E+01 MeV Emin = 1.88945E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 45 Q = -1.88839E+01 MeV Emin = 1.95899E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,npalpha) + 6 MT = 45 Q = -1.88839E+01 MeV Emin = 1.95899E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,npalpha) + 7 MT = 103 Q = -1.82855E+00 MeV Emin = 1.89625E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 8 MT = 104 Q = -6.04754E+00 MeV Emin = 6.27362E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 9 MT = 105 Q = -1.08829E+01 MeV Emin = 1.12898E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 10 MT = 107 Q = -3.13033E+00 MeV Emin = 3.24735E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 11 MT = 108 Q = -1.39583E+01 MeV Emin = 1.44801E+01 MeV frac = 2.00000E+00 Product nuclide = 2004.82c : (n,2alpha) + 12 MT = 111 Q = -1.67999E+01 MeV Emin = 1.74279E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + 13 MT = 112 Q = -1.36838E+01 MeV Emin = 1.41954E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,palpha) + 14 MT = 112 Q = -1.36838E+01 MeV Emin = 1.41954E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,palpha) + 15 MT = 117 Q = -1.66594E+01 MeV Emin = 1.72822E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,dalpha) + 16 MT = 117 Q = -1.66594E+01 MeV Emin = 1.72822E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,dalpha) + + 81 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.89625E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.27362E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.12898E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 3.24735E+00 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 600 Q = -1.82855E+00 MeV Emin = 1.89625E+00 MeV : (n,p) to ground state + 7 MT = 601 Q = -2.81321E+00 MeV Emin = 2.91838E+00 MeV : (n,p1) + 8 MT = 602 Q = -3.52655E+00 MeV Emin = 3.65838E+00 MeV : (n,p2) + 9 MT = 603 Q = -3.76855E+00 MeV Emin = 3.90943E+00 MeV : (n,p3) + 10 MT = 604 Q = -4.93795E+00 MeV Emin = 5.12255E+00 MeV : (n,p4) + 11 MT = 605 Q = -5.25545E+00 MeV Emin = 5.45192E+00 MeV : (n,p5) + 12 MT = 606 Q = -5.30385E+00 MeV Emin = 5.50213E+00 MeV : (n,p6) + 13 MT = 607 Q = -5.31925E+00 MeV Emin = 5.51810E+00 MeV : (n,p7) + 14 MT = 608 Q = -5.38775E+00 MeV Emin = 5.58916E+00 MeV : (n,p8) + 15 MT = 609 Q = -5.58895E+00 MeV Emin = 5.79788E+00 MeV : (n,p9) + 16 MT = 610 Q = -5.61445E+00 MeV Emin = 5.82434E+00 MeV : (n,p10) + 17 MT = 611 Q = -5.71255E+00 MeV Emin = 5.92610E+00 MeV : (n,p11) + 18 MT = 612 Q = -5.97835E+00 MeV Emin = 6.20184E+00 MeV : (n,p12) + 19 MT = 613 Q = -6.22675E+00 MeV Emin = 6.45953E+00 MeV : (n,p13) + 20 MT = 614 Q = -6.38135E+00 MeV Emin = 6.61991E+00 MeV : (n,p14) + 21 MT = 615 Q = -6.60465E+00 MeV Emin = 6.85156E+00 MeV : (n,p15) + 22 MT = 616 Q = -6.65585E+00 MeV Emin = 6.90467E+00 MeV : (n,p16) + 23 MT = 617 Q = -6.82085E+00 MeV Emin = 7.07584E+00 MeV : (n,p17) + 24 MT = 618 Q = -6.85655E+00 MeV Emin = 7.11287E+00 MeV : (n,p18) + 25 MT = 619 Q = -7.00055E+00 MeV Emin = 7.26226E+00 MeV : (n,p19) + 26 MT = 649 Q = -7.00055E+00 MeV Emin = 7.26226E+00 MeV : (n,p) to continuum + 27 MT = 650 Q = -6.04754E+00 MeV Emin = 6.27362E+00 MeV : (n,d) to ground state + 28 MT = 651 Q = -7.85622E+00 MeV Emin = 8.14992E+00 MeV : (n,d1) + 29 MT = 652 Q = -8.98590E+00 MeV Emin = 9.32183E+00 MeV : (n,d2) + 30 MT = 653 Q = -9.63584E+00 MeV Emin = 9.99607E+00 MeV : (n,d3) + 31 MT = 654 Q = -9.98804E+00 MeV Emin = 1.03614E+01 MeV : (n,d4) + 32 MT = 655 Q = -1.03659E+01 MeV Emin = 1.07535E+01 MeV : (n,d5) + 33 MT = 656 Q = -1.03794E+01 MeV Emin = 1.07675E+01 MeV : (n,d6) + 34 MT = 657 Q = -1.03973E+01 MeV Emin = 1.07860E+01 MeV : (n,d7) + 35 MT = 658 Q = -1.08818E+01 MeV Emin = 1.12887E+01 MeV : (n,d8) + 36 MT = 659 Q = -1.09478E+01 MeV Emin = 1.13571E+01 MeV : (n,d9) + 37 MT = 660 Q = -1.10197E+01 MeV Emin = 1.14317E+01 MeV : (n,d10) + 38 MT = 661 Q = -1.13383E+01 MeV Emin = 1.17622E+01 MeV : (n,d11) + 39 MT = 662 Q = -1.15214E+01 MeV Emin = 1.19522E+01 MeV : (n,d12) + 40 MT = 663 Q = -1.17376E+01 MeV Emin = 1.21764E+01 MeV : (n,d13) + 41 MT = 664 Q = -1.17630E+01 MeV Emin = 1.22028E+01 MeV : (n,d14) + 42 MT = 665 Q = -1.21727E+01 MeV Emin = 1.26278E+01 MeV : (n,d15) + 43 MT = 666 Q = -1.23035E+01 MeV Emin = 1.27635E+01 MeV : (n,d16) + 44 MT = 667 Q = -1.26685E+01 MeV Emin = 1.31421E+01 MeV : (n,d17) + 45 MT = 668 Q = -1.27915E+01 MeV Emin = 1.32697E+01 MeV : (n,d18) + 46 MT = 669 Q = -1.29252E+01 MeV Emin = 1.34084E+01 MeV : (n,d19) + 47 MT = 699 Q = -1.29252E+01 MeV Emin = 1.34084E+01 MeV : (n,d) to continuum + 48 MT = 700 Q = -1.08829E+01 MeV Emin = 1.12898E+01 MeV : (n,t) to ground state + 49 MT = 701 Q = -1.14680E+01 MeV Emin = 1.18968E+01 MeV : (n,t1) + 50 MT = 702 Q = -1.18577E+01 MeV Emin = 1.23010E+01 MeV : (n,t2) + 51 MT = 703 Q = -1.24947E+01 MeV Emin = 1.29618E+01 MeV : (n,t3) + 52 MT = 704 Q = -1.28476E+01 MeV Emin = 1.33279E+01 MeV : (n,t4) + 53 MT = 705 Q = -1.34467E+01 MeV Emin = 1.39494E+01 MeV : (n,t5) + 54 MT = 706 Q = -1.36206E+01 MeV Emin = 1.41298E+01 MeV : (n,t6) + 55 MT = 707 Q = -1.36840E+01 MeV Emin = 1.41956E+01 MeV : (n,t7) + 56 MT = 708 Q = -1.42881E+01 MeV Emin = 1.48223E+01 MeV : (n,t8) + 57 MT = 709 Q = -1.42966E+01 MeV Emin = 1.48311E+01 MeV : (n,t9) + 58 MT = 710 Q = -1.47907E+01 MeV Emin = 1.53437E+01 MeV : (n,t10) + 59 MT = 749 Q = -1.47907E+01 MeV Emin = 1.53437E+01 MeV : (n,t) to continuum + 60 MT = 800 Q = -3.13033E+00 MeV Emin = 3.24735E+00 MeV : (n,alpha) to ground state + 61 MT = 801 Q = -3.60262E+00 MeV Emin = 3.73730E+00 MeV : (n,a1) + 62 MT = 802 Q = -3.69362E+00 MeV Emin = 3.83170E+00 MeV : (n,a2) + 63 MT = 803 Q = -4.47173E+00 MeV Emin = 4.63890E+00 MeV : (n,a3) + 64 MT = 804 Q = -4.47483E+00 MeV Emin = 4.64212E+00 MeV : (n,a4) + 65 MT = 805 Q = -4.47683E+00 MeV Emin = 4.64419E+00 MeV : (n,a5) + 66 MT = 806 Q = -4.64287E+00 MeV Emin = 4.81644E+00 MeV : (n,a6) + 67 MT = 807 Q = -4.97643E+00 MeV Emin = 5.16247E+00 MeV : (n,a7) + 68 MT = 808 Q = -5.01577E+00 MeV Emin = 5.20328E+00 MeV : (n,a8) + 69 MT = 809 Q = -5.64373E+00 MeV Emin = 5.85471E+00 MeV : (n,a9) + 70 MT = 810 Q = -5.69283E+00 MeV Emin = 5.90565E+00 MeV : (n,a10) + 71 MT = 811 Q = -6.03403E+00 MeV Emin = 6.25960E+00 MeV : (n,a11) + 72 MT = 812 Q = -6.10813E+00 MeV Emin = 6.33647E+00 MeV : (n,a12) + 73 MT = 813 Q = -6.34713E+00 MeV Emin = 6.58441E+00 MeV : (n,a13) + 74 MT = 814 Q = -6.50223E+00 MeV Emin = 6.74531E+00 MeV : (n,a14) + 75 MT = 815 Q = -6.54373E+00 MeV Emin = 6.78836E+00 MeV : (n,a15) + 76 MT = 816 Q = -6.71943E+00 MeV Emin = 6.97063E+00 MeV : (n,a16) + 77 MT = 817 Q = -6.75883E+00 MeV Emin = 7.01150E+00 MeV : (n,a17) + 78 MT = 818 Q = -6.78683E+00 MeV Emin = 7.04055E+00 MeV : (n,a18) + 79 MT = 819 Q = -6.81203E+00 MeV Emin = 7.06669E+00 MeV : (n,a19) + 80 MT = 849 Q = -6.81203E+00 MeV Emin = 7.06669E+00 MeV : (n,alpha) to continuum + 81 MT = 4 Q = 0.00000E+00 MeV Emin = 8.74000E-01 MeV : total inelastic scattering + + Nuclide 24 / 1657 : 14028.82c -- silicon 28 (Si-28) + + Pointers : 124393 32805 + Primary type : Transport + Nuclide ZAI : 140280 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Si28.ACE + Atomic weight (AW) : 27.97734 + Atomic weight ratio (AWR) : 27.73700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 29 reaction channels + - 39 special reactions + - 10 transmutation reactions + - 8 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 29 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.71770E+01 MeV Emin = 1.77963E+01 MeV frac = 1.00000E+00 Product nuclide = 140270 : (n,2n) + 3 MT = 22 Q = -9.98560E+00 MeV Emin = 1.03460E+01 MeV frac = 1.00000E+00 Product nuclide = 12024.82c : (n,nalpha) + 4 MT = 28 Q = -1.15860E+01 MeV Emin = 1.20037E+01 MeV frac = 1.00000E+00 Product nuclide = 13027.82c : (n,np) + 5 MT = 51 Q = -1.77900E+00 MeV Emin = 1.84213E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -4.61700E+00 MeV Emin = 4.89210E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -4.97900E+00 MeV Emin = 5.15851E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -6.27600E+00 MeV Emin = 6.50230E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -6.69100E+00 MeV Emin = 6.93223E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -6.87900E+00 MeV Emin = 7.12701E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -6.88900E+00 MeV Emin = 7.13740E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -7.38100E+00 MeV Emin = 7.64711E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -7.41700E+00 MeV Emin = 7.68441E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -7.79900E+00 MeV Emin = 8.08020E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -7.93300E+00 MeV Emin = 8.21901E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -8.25900E+00 MeV Emin = 8.55680E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 63 Q = -8.32800E+00 MeV Emin = 8.62830E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 18 MT = 64 Q = -8.41300E+00 MeV Emin = 8.71631E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 19 MT = 65 Q = -8.54300E+00 MeV Emin = 8.85100E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 20 MT = 66 Q = -8.58900E+00 MeV Emin = 8.89870E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 21 MT = 67 Q = -8.90400E+00 MeV Emin = 9.22502E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 22 MT = 91 Q = -9.00000E+00 MeV Emin = 9.32448E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 23 MT = 102 Q = 8.47390E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 14029.82c : (n,gamma) + 24 MT = 103 Q = -3.86000E+00 MeV Emin = 4.03128E+00 MeV frac = 1.00000E+00 Product nuclide = 130280 : (n,p) + 25 MT = 104 Q = -9.36130E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 13027.82c : (n,d) + 26 MT = 105 Q = -1.16000E+01 MeV Emin = 1.20182E+01 MeV frac = 1.00000E+00 Product nuclide = 130260 : (n,t) + 27 MT = 106 Q = -1.20700E+01 MeV Emin = 1.25052E+01 MeV frac = 1.00000E+00 Product nuclide = 12026.82c : (n,He-3) + 28 MT = 107 Q = -2.65000E+00 MeV Emin = 2.82000E+00 MeV frac = 1.00000E+00 Product nuclide = 12025.82c : (n,alpha) + 29 MT = 111 Q = -1.34130E+01 MeV Emin = 1.38966E+01 MeV frac = 1.00000E+00 Product nuclide = 120270 : (n,2p) + + 8 additional transport branches: + + 1 MT = 22 Q = -9.98560E+00 MeV Emin = 1.03460E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.15860E+01 MeV Emin = 1.20037E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -3.86000E+00 MeV Emin = 4.03128E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -9.36130E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -1.16000E+01 MeV Emin = 1.20182E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 106 Q = -1.20700E+01 MeV Emin = 1.25052E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 7 MT = 107 Q = -2.65000E+00 MeV Emin = 2.82000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 8 MT = 111 Q = -1.34130E+01 MeV Emin = 1.38966E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 39 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.03128E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.00000E+01 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.20182E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.25052E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 2.82000E+00 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 600 Q = -3.86000E+00 MeV Emin = 4.03128E+00 MeV : (n,p) to ground state + 8 MT = 601 Q = -3.89100E+00 MeV Emin = 4.03128E+00 MeV : (n,p1) + 9 MT = 602 Q = -4.83200E+00 MeV Emin = 5.00621E+00 MeV : (n,p2) + 10 MT = 603 Q = -4.87400E+00 MeV Emin = 5.04972E+00 MeV : (n,p3) + 11 MT = 604 Q = -5.23300E+00 MeV Emin = 5.42167E+00 MeV : (n,p4) + 12 MT = 605 Q = -5.48000E+00 MeV Emin = 5.67757E+00 MeV : (n,p5) + 13 MT = 606 Q = -5.48300E+00 MeV Emin = 5.68068E+00 MeV : (n,p6) + 14 MT = 607 Q = -5.99900E+00 MeV Emin = 6.21528E+00 MeV : (n,p7) + 15 MT = 608 Q = -6.06200E+00 MeV Emin = 6.28055E+00 MeV : (n,p8) + 16 MT = 609 Q = -6.13200E+00 MeV Emin = 6.35308E+00 MeV : (n,p9) + 17 MT = 610 Q = -6.34500E+00 MeV Emin = 6.57376E+00 MeV : (n,p10) + 18 MT = 611 Q = -6.44100E+00 MeV Emin = 6.67322E+00 MeV : (n,p11) + 19 MT = 612 Q = -6.51600E+00 MeV Emin = 6.75092E+00 MeV : (n,p12) + 20 MT = 613 Q = -6.84700E+00 MeV Emin = 7.09385E+00 MeV : (n,p13) + 21 MT = 649 Q = -6.86000E+00 MeV Emin = 7.10732E+00 MeV : (n,p) to continuum + 22 MT = 800 Q = -2.65000E+00 MeV Emin = 2.82000E+00 MeV : (n,alpha) to ground state + 23 MT = 801 Q = -3.23500E+00 MeV Emin = 3.35163E+00 MeV : (n,a1) + 24 MT = 802 Q = -3.62500E+00 MeV Emin = 3.75569E+00 MeV : (n,a2) + 25 MT = 803 Q = -4.26200E+00 MeV Emin = 4.41566E+00 MeV : (n,a3) + 26 MT = 804 Q = -4.61500E+00 MeV Emin = 4.78139E+00 MeV : (n,a4) + 27 MT = 805 Q = -5.21400E+00 MeV Emin = 5.40198E+00 MeV : (n,a5) + 28 MT = 806 Q = -5.38800E+00 MeV Emin = 5.58225E+00 MeV : (n,a6) + 29 MT = 807 Q = -5.45100E+00 MeV Emin = 5.64752E+00 MeV : (n,a7) + 30 MT = 808 Q = -6.05500E+00 MeV Emin = 6.27330E+00 MeV : (n,a8) + 31 MT = 809 Q = -6.06400E+00 MeV Emin = 6.28263E+00 MeV : (n,a9) + 32 MT = 810 Q = -6.55800E+00 MeV Emin = 6.79444E+00 MeV : (n,a10) + 33 MT = 811 Q = -6.62100E+00 MeV Emin = 6.85971E+00 MeV : (n,a11) + 34 MT = 812 Q = -6.71000E+00 MeV Emin = 6.95192E+00 MeV : (n,a12) + 35 MT = 813 Q = -6.92700E+00 MeV Emin = 7.17674E+00 MeV : (n,a13) + 36 MT = 814 Q = -7.00900E+00 MeV Emin = 7.26170E+00 MeV : (n,a14) + 37 MT = 815 Q = -7.36100E+00 MeV Emin = 7.62640E+00 MeV : (n,a15) + 38 MT = 849 Q = -7.45000E+00 MeV Emin = 7.71860E+00 MeV : (n,alpha) to continuum + 39 MT = 4 Q = 0.00000E+00 MeV Emin = 1.84213E+00 MeV : total inelastic scattering + + Nuclide 25 / 1657 : 14029.82c -- silicon 29 (Si-29) + + Pointers : 130052 32851 + Primary type : Transport + Nuclide ZAI : 140290 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Si29.ACE + Atomic weight (AW) : 28.97652 + Atomic weight ratio (AWR) : 28.72760 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 38 reaction channels + - 4 special reactions + - 7 transmutation reactions + - 5 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 38 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.47388E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 14028.82c : (n,2n) + 3 MT = 22 Q = -1.11267E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 12025.82c : (n,nalpha) + 4 MT = 28 Q = -1.23337E+01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 130280 : (n,np) + 5 MT = 51 Q = -1.27300E+00 MeV Emin = 1.15864E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -2.02800E+00 MeV Emin = 2.09859E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -2.42500E+00 MeV Emin = 2.50942E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -3.06700E+00 MeV Emin = 3.17376E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -3.62399E+00 MeV Emin = 3.75014E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -4.07999E+00 MeV Emin = 4.22201E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -4.74099E+00 MeV Emin = 4.90602E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -4.83999E+00 MeV Emin = 5.00847E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -4.89499E+00 MeV Emin = 5.06538E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -4.93399E+00 MeV Emin = 5.10574E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -5.25499E+00 MeV Emin = 5.43792E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -5.28599E+00 MeV Emin = 5.46999E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 63 Q = -5.65199E+00 MeV Emin = 5.84873E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 18 MT = 64 Q = -5.81299E+00 MeV Emin = 6.01534E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 19 MT = 65 Q = -5.94899E+00 MeV Emin = 6.15607E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 20 MT = 66 Q = -6.10699E+00 MeV Emin = 6.31957E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 21 MT = 67 Q = -6.19199E+00 MeV Emin = 6.40753E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 22 MT = 68 Q = -6.37799E+00 MeV Emin = 6.60001E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 23 MT = 69 Q = -6.42299E+00 MeV Emin = 6.64657E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 24 MT = 70 Q = -6.49599E+00 MeV Emin = 6.72211E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 25 MT = 71 Q = -6.52199E+00 MeV Emin = 6.74902E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 26 MT = 72 Q = -6.61499E+00 MeV Emin = 6.84526E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 27 MT = 73 Q = -6.69699E+00 MeV Emin = 6.93011E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 28 MT = 74 Q = -6.70999E+00 MeV Emin = 6.94356E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 29 MT = 75 Q = -6.71499E+00 MeV Emin = 6.94874E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 30 MT = 76 Q = -6.78199E+00 MeV Emin = 7.01807E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 31 MT = 77 Q = -6.90699E+00 MeV Emin = 7.14742E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 27. excited state + 32 MT = 78 Q = -6.92099E+00 MeV Emin = 7.16191E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 28. excited state + 33 MT = 79 Q = -7.01399E+00 MeV Emin = 7.25815E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 29. excited state + 34 MT = 91 Q = -7.05699E+00 MeV Emin = 7.30264E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 35 MT = 102 Q = 1.06143E+01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 14030.82c : (n,gamma) + 36 MT = 103 Q = -2.89783E+00 MeV Emin = 3.10000E+00 MeV frac = 1.00000E+00 Product nuclide = 130290 : (n,p) + 37 MT = 107 Q = -3.31500E-02 MeV Emin = 3.99455E-02 MeV frac = 1.00000E+00 Product nuclide = 12026.82c : (n,alpha) + 38 MT = 111 Q = -1.33831E+01 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 120280 : (n,2p) + + 5 additional transport branches: + + 1 MT = 22 Q = -1.11267E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.23337E+01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -2.89783E+00 MeV Emin = 3.10000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 107 Q = -3.31500E-02 MeV Emin = 3.99455E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 5 MT = 111 Q = -1.33831E+01 MeV Emin = 1.40000E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 4 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.10000E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 3.99455E-02 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 4 MT = 4 Q = 0.00000E+00 MeV Emin = 1.15864E+00 MeV : total inelastic scattering + + Nuclide 26 / 1657 : 14030.82c -- silicon 30 (Si-30) + + Pointers : 133594 32897 + Primary type : Transport + Nuclide ZAI : 140300 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Si30.ACE + Atomic weight (AW) : 30.00002 + Atomic weight ratio (AWR) : 29.74230 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 28 reaction channels + - 4 special reactions + - 7 transmutation reactions + - 5 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 28 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.06097E+01 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 14029.82c : (n,2n) + 3 MT = 22 Q = -1.06428E+01 MeV Emin = 1.10009E+01 MeV frac = 1.00000E+00 Product nuclide = 12026.82c : (n,nalpha) + 4 MT = 28 Q = -1.35075E+01 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 130290 : (n,np) + 5 MT = 51 Q = -2.23500E+00 MeV Emin = 2.31015E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -3.49819E+00 MeV Emin = 3.61582E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -3.76959E+00 MeV Emin = 3.89634E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -3.78769E+00 MeV Emin = 3.91505E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -4.80899E+00 MeV Emin = 4.97069E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -4.83049E+00 MeV Emin = 4.99291E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -5.22999E+00 MeV Emin = 5.40584E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -5.27899E+00 MeV Emin = 5.45649E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -5.37199E+00 MeV Emin = 5.55262E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -5.48759E+00 MeV Emin = 5.67211E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -5.61299E+00 MeV Emin = 5.80172E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -5.94999E+00 MeV Emin = 6.15005E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 63 Q = -6.50299E+00 MeV Emin = 6.72164E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 18 MT = 64 Q = -6.53699E+00 MeV Emin = 6.75679E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 19 MT = 65 Q = -6.63399E+00 MeV Emin = 6.85705E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 20 MT = 66 Q = -6.63999E+00 MeV Emin = 6.86325E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 21 MT = 67 Q = -6.74469E+00 MeV Emin = 6.97147E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 22 MT = 68 Q = -6.86499E+00 MeV Emin = 7.09582E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 23 MT = 69 Q = -6.91399E+00 MeV Emin = 7.14646E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 24 MT = 91 Q = -6.99899E+00 MeV Emin = 7.23432E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 25 MT = 102 Q = 6.59199E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 140310 : (n,gamma) + 26 MT = 103 Q = -7.75882E+00 MeV Emin = 8.01993E+00 MeV frac = 1.00000E+00 Product nuclide = 130300 : (n,p) + 27 MT = 107 Q = -4.19984E+00 MeV Emin = 4.40000E+00 MeV frac = 1.00000E+00 Product nuclide = 120270 : (n,alpha) + 28 MT = 111 Q = -1.83851E+01 MeV Emin = 1.90038E+01 MeV frac = 1.00000E+00 Product nuclide = 120290 : (n,2p) + + 5 additional transport branches: + + 1 MT = 22 Q = -1.06428E+01 MeV Emin = 1.10009E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.35075E+01 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -7.75882E+00 MeV Emin = 8.01993E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 107 Q = -4.19984E+00 MeV Emin = 4.40000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 5 MT = 111 Q = -1.83851E+01 MeV Emin = 1.90038E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 4 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 8.01993E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 4.40000E+00 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 4 MT = 4 Q = 0.00000E+00 MeV Emin = 2.31015E+00 MeV : total inelastic scattering + + Nuclide 27 / 1657 : 15031.82c -- phosphorus 31 (P-31) + + Pointers : 137409 29493 + Primary type : Transport + Nuclide ZAI : 150310 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/P31.ACE + Atomic weight (AW) : 30.97378 + Atomic weight ratio (AWR) : 30.70770 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 14 reaction channels + - 4 special reactions + - 6 transmutation reactions + - 4 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 14 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.23074E+01 MeV Emin = 1.32000E+01 MeV frac = 1.00000E+00 Product nuclide = 150300 : (n,2n) + 3 MT = 22 Q = -9.66952E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 13027.82c : (n,nalpha) + 4 MT = 28 Q = -7.29751E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 14030.82c : (n,np) + 5 MT = 51 Q = -1.26600E+00 MeV Emin = 1.15370E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -2.23400E+00 MeV Emin = 2.30675E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -3.13400E+00 MeV Emin = 3.23606E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -3.29500E+00 MeV Emin = 3.40230E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -3.41499E+00 MeV Emin = 3.52621E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -3.50599E+00 MeV Emin = 3.62017E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 91 Q = -3.99999E+00 MeV Emin = 4.13026E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 12 MT = 102 Q = 7.93699E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 150320 : (n,gamma) + 13 MT = 103 Q = -7.09229E-01 MeV Emin = 7.30000E-01 MeV frac = 1.00000E+00 Product nuclide = 140310 : (n,p) + 14 MT = 107 Q = -1.94352E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 130280 : (n,alpha) + + 4 additional transport branches: + + 1 MT = 22 Q = -9.66952E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -7.29751E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -7.09229E-01 MeV Emin = 7.30000E-01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 107 Q = -1.94352E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 4 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 7.30000E-01 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 3.00000E+00 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 4 MT = 4 Q = 0.00000E+00 MeV Emin = 1.15370E+00 MeV : total inelastic scattering + + Nuclide 28 / 1657 : 16034.82c -- sulfur 34 (S-34) + + Pointers : 140511 32115 + Primary type : Transport + Nuclide ZAI : 160340 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/S34.ACE + Atomic weight (AW) : 33.96800 + Atomic weight ratio (AWR) : 33.67620 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 13 reaction channels + - 4 special reactions + - 6 transmutation reactions + - 4 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 13 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.14149E+01 MeV Emin = 1.17539E+01 MeV frac = 1.00000E+00 Product nuclide = 160330 : (n,2n) + 3 MT = 22 Q = -7.92283E+00 MeV Emin = 8.20000E+00 MeV frac = 1.00000E+00 Product nuclide = 14030.82c : (n,nalpha) + 4 MT = 28 Q = -1.08814E+01 MeV Emin = 1.12045E+01 MeV frac = 1.00000E+00 Product nuclide = 150330 : (n,np) + 5 MT = 51 Q = -2.12700E+00 MeV Emin = 2.19016E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -3.30400E+00 MeV Emin = 3.40211E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -3.91399E+00 MeV Emin = 4.03022E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -4.07199E+00 MeV Emin = 4.19292E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -4.11499E+00 MeV Emin = 4.23719E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 91 Q = -4.49999E+00 MeV Emin = 4.63363E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 11 MT = 102 Q = 6.98699E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 160350 : (n,gamma) + 12 MT = 103 Q = -4.31672E+00 MeV Emin = 4.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 150340 : (n,p) + 13 MT = 107 Q = -1.33455E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 140310 : (n,alpha) + + 4 additional transport branches: + + 1 MT = 22 Q = -7.92283E+00 MeV Emin = 8.20000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.08814E+01 MeV Emin = 1.12045E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -4.31672E+00 MeV Emin = 4.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 107 Q = -1.33455E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 4 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.50000E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 4 MT = 4 Q = 0.00000E+00 MeV Emin = 2.19016E+00 MeV : total inelastic scattering + + Nuclide 29 / 1657 : 16036.82c -- sulfur 36 (S-36) + + Pointers : 142372 32161 + Primary type : Transport + Nuclide ZAI : 160360 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/S36.ACE + Atomic weight (AW) : 35.96697 + Atomic weight ratio (AWR) : 35.65800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 13 reaction channels + - 4 special reactions + - 6 transmutation reactions + - 4 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 13 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -9.89198E+00 MeV Emin = 1.02000E+01 MeV frac = 1.00000E+00 Product nuclide = 160350 : (n,2n) + 3 MT = 22 Q = -8.99983E+00 MeV Emin = 1.02000E+01 MeV frac = 1.00000E+00 Product nuclide = 140320 : (n,nalpha) + 4 MT = 28 Q = -1.30419E+01 MeV Emin = 1.34077E+01 MeV frac = 1.00000E+00 Product nuclide = 150350 : (n,np) + 5 MT = 51 Q = -3.29100E+00 MeV Emin = 3.38329E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -3.34600E+00 MeV Emin = 3.43984E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -4.19199E+00 MeV Emin = 4.30956E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -4.52299E+00 MeV Emin = 4.64984E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -4.57499E+00 MeV Emin = 4.70330E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 91 Q = -4.99999E+00 MeV Emin = 5.14022E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 11 MT = 102 Q = 4.31399E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 160370 : (n,gamma) + 12 MT = 103 Q = -8.99092E+00 MeV Emin = 9.24307E+00 MeV frac = 1.00000E+00 Product nuclide = 150360 : (n,p) + 13 MT = 107 Q = -3.95404E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 140330 : (n,alpha) + + 4 additional transport branches: + + 1 MT = 22 Q = -8.99983E+00 MeV Emin = 1.02000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.30419E+01 MeV Emin = 1.34077E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -8.99092E+00 MeV Emin = 9.24307E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 107 Q = -3.95404E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 4 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 9.24307E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 5.00000E+00 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 4 MT = 4 Q = 0.00000E+00 MeV Emin = 3.38329E+00 MeV : total inelastic scattering + + Nuclide 30 / 1657 : 17035.82c -- chlorine 35 (Cl-35) + + Pointers : 145031 21581 + Primary type : Transport + Nuclide ZAI : 170350 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Cl35.ACE + Atomic weight (AW) : 34.96885 + Atomic weight ratio (AWR) : 34.66845 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 43 reaction channels + - 123 special reactions + - 11 transmutation reactions + - 10 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 43 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.26450E+01 MeV Emin = 1.30098E+01 MeV frac = 1.00000E+00 Product nuclide = 170340 : (n,2n) + 3 MT = 22 Q = -6.99745E+00 MeV Emin = 7.19929E+00 MeV frac = 1.00000E+00 Product nuclide = 15031.82c : (n,nalpha) + 4 MT = 28 Q = -6.37040E+00 MeV Emin = 6.55415E+00 MeV frac = 1.00000E+00 Product nuclide = 16034.82c : (n,np) + 5 MT = 32 Q = -1.55629E+01 MeV Emin = 1.60118E+01 MeV frac = 1.00000E+00 Product nuclide = 160330 : (n,nd) + 6 MT = 51 Q = -1.21944E+00 MeV Emin = 1.25000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.76315E+00 MeV Emin = 1.79797E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -2.64560E+00 MeV Emin = 2.72191E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -2.69360E+00 MeV Emin = 2.77130E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -3.00274E+00 MeV Emin = 3.08935E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -3.16800E+00 MeV Emin = 3.25938E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -3.91848E+00 MeV Emin = 4.03151E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -3.94290E+00 MeV Emin = 4.05663E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -3.96750E+00 MeV Emin = 4.08194E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -4.05920E+00 MeV Emin = 4.17629E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -4.11330E+00 MeV Emin = 4.23195E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -4.17345E+00 MeV Emin = 4.29383E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -4.17790E+00 MeV Emin = 4.29841E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -4.34770E+00 MeV Emin = 4.47311E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -4.62440E+00 MeV Emin = 4.75779E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 21 MT = 66 Q = -4.76990E+00 MeV Emin = 4.90749E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 22 MT = 67 Q = -4.83909E+00 MeV Emin = 4.97867E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 23 MT = 68 Q = -4.85440E+00 MeV Emin = 4.99442E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 24 MT = 69 Q = -4.88110E+00 MeV Emin = 5.02189E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 25 MT = 70 Q = -5.01040E+00 MeV Emin = 5.15492E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 26 MT = 71 Q = -5.16331E+00 MeV Emin = 5.31224E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 27 MT = 72 Q = -5.21580E+00 MeV Emin = 5.36625E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 28 MT = 73 Q = -5.40360E+00 MeV Emin = 5.55947E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 29 MT = 74 Q = -5.40670E+00 MeV Emin = 5.56266E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 30 MT = 75 Q = -5.58600E+00 MeV Emin = 5.74713E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 31 MT = 76 Q = -5.59970E+00 MeV Emin = 5.76122E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 32 MT = 77 Q = -5.64600E+00 MeV Emin = 5.80886E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 27. excited state + 33 MT = 78 Q = -5.65400E+00 MeV Emin = 5.81709E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 28. excited state + 34 MT = 79 Q = -5.68300E+00 MeV Emin = 5.84692E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 29. excited state + 35 MT = 80 Q = -5.72352E+00 MeV Emin = 5.88861E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 30. excited state + 36 MT = 91 Q = -5.72352E+00 MeV Emin = 5.88861E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 37 MT = 102 Q = 8.57977E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 170360 : (n,gamma) + 38 MT = 103 Q = 6.15220E-01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 160350 : (n,p) + 39 MT = 104 Q = -4.14581E+00 MeV Emin = 4.29383E+00 MeV frac = 1.00000E+00 Product nuclide = 16034.82c : (n,d) + 40 MT = 105 Q = -9.30564E+00 MeV Emin = 9.64317E+00 MeV frac = 1.00000E+00 Product nuclide = 160330 : (n,t) + 41 MT = 107 Q = 9.38230E-01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 150320 : (n,alpha) + 42 MT = 111 Q = -1.09627E+01 MeV Emin = 1.12789E+01 MeV frac = 1.00000E+00 Product nuclide = 150340 : (n,2p) + 43 MT = 112 Q = -7.70570E+00 MeV Emin = 7.92797E+00 MeV frac = 1.00000E+00 Product nuclide = 140310 : (n,palpha) + + 10 additional transport branches: + + 1 MT = 22 Q = -6.99745E+00 MeV Emin = 7.19929E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -6.37040E+00 MeV Emin = 6.55415E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.55629E+01 MeV Emin = 1.60118E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 103 Q = 6.15220E-01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -4.14581E+00 MeV Emin = 4.29383E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -9.30564E+00 MeV Emin = 9.64317E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 107 Q = 9.38230E-01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 8 MT = 111 Q = -1.09627E+01 MeV Emin = 1.12789E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + 9 MT = 112 Q = -7.70570E+00 MeV Emin = 7.92797E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,palpha) + 10 MT = 112 Q = -7.70570E+00 MeV Emin = 7.92797E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,palpha) + + 123 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 4.29383E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.64317E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 600 Q = 6.15220E-01 MeV Emin = 1.00000E-11 MeV : (n,p) to ground state + 7 MT = 601 Q = -9.56759E-01 MeV Emin = 1.22000E+00 MeV : (n,p1) + 8 MT = 602 Q = -1.37568E+00 MeV Emin = 1.76597E+00 MeV : (n,p2) + 9 MT = 603 Q = -1.73198E+00 MeV Emin = 2.06309E+00 MeV : (n,p3) + 10 MT = 604 Q = -2.10198E+00 MeV Emin = 2.25000E+00 MeV : (n,p4) + 11 MT = 605 Q = -2.32368E+00 MeV Emin = 2.39286E+00 MeV : (n,p5) + 12 MT = 606 Q = -2.80548E+00 MeV Emin = 2.94113E+00 MeV : (n,p6) + 13 MT = 607 Q = -2.94528E+00 MeV Emin = 3.06748E+00 MeV : (n,p7) + 14 MT = 608 Q = -2.98148E+00 MeV Emin = 3.08935E+00 MeV : (n,p8) + 15 MT = 609 Q = -3.05948E+00 MeV Emin = 3.15739E+00 MeV : (n,p9) + 16 MT = 610 Q = -3.18668E+00 MeV Emin = 3.29496E+00 MeV : (n,p10) + 17 MT = 611 Q = -3.20258E+00 MeV Emin = 3.36482E+00 MeV : (n,p11) + 18 MT = 612 Q = -3.27048E+00 MeV Emin = 3.38642E+00 MeV : (n,p12) + 19 MT = 613 Q = -3.29148E+00 MeV Emin = 3.50000E+00 MeV : (n,p13) + 20 MT = 614 Q = -3.40648E+00 MeV Emin = 3.51091E+00 MeV : (n,p14) + 21 MT = 615 Q = -3.41248E+00 MeV Emin = 3.59219E+00 MeV : (n,p15) + 22 MT = 616 Q = -3.49148E+00 MeV Emin = 3.66730E+00 MeV : (n,p16) + 23 MT = 617 Q = -3.56448E+00 MeV Emin = 3.67748E+00 MeV : (n,p17) + 24 MT = 618 Q = -3.57438E+00 MeV Emin = 3.75000E+00 MeV : (n,p18) + 25 MT = 619 Q = -3.68648E+00 MeV Emin = 3.97595E+00 MeV : (n,p19) + 26 MT = 620 Q = -3.86448E+00 MeV Emin = 4.00000E+00 MeV : (n,p20) + 27 MT = 621 Q = -3.96048E+00 MeV Emin = 4.08194E+00 MeV : (n,p21) + 28 MT = 622 Q = -4.00148E+00 MeV Emin = 4.17629E+00 MeV : (n,p22) + 29 MT = 623 Q = -4.22348E+00 MeV Emin = 4.41166E+00 MeV : (n,p23) + 30 MT = 624 Q = -4.28798E+00 MeV Emin = 4.47309E+00 MeV : (n,p24) + 31 MT = 625 Q = -4.34768E+00 MeV Emin = 4.47311E+00 MeV : (n,p25) + 32 MT = 626 Q = -4.37448E+00 MeV Emin = 4.57062E+00 MeV : (n,p26) + 33 MT = 627 Q = -4.44248E+00 MeV Emin = 4.64161E+00 MeV : (n,p27) + 34 MT = 628 Q = -4.51148E+00 MeV Emin = 4.75000E+00 MeV : (n,p28) + 35 MT = 629 Q = -4.72748E+00 MeV Emin = 4.86384E+00 MeV : (n,p29) + 36 MT = 649 Q = -4.72748E+00 MeV Emin = 4.86384E+00 MeV : (n,p) to continuum + 37 MT = 650 Q = -4.14581E+00 MeV Emin = 4.29383E+00 MeV : (n,d) to ground state + 38 MT = 651 Q = -6.27311E+00 MeV Emin = 6.50000E+00 MeV : (n,d1) + 39 MT = 652 Q = -7.44901E+00 MeV Emin = 7.92797E+00 MeV : (n,d2) + 40 MT = 653 Q = -8.06001E+00 MeV Emin = 8.45691E+00 MeV : (n,d3) + 41 MT = 654 Q = -8.21981E+00 MeV Emin = 8.49817E+00 MeV : (n,d4) + 42 MT = 655 Q = -8.25991E+00 MeV Emin = 8.50000E+00 MeV : (n,d5) + 43 MT = 656 Q = -8.76851E+00 MeV Emin = 9.08821E+00 MeV : (n,d6) + 44 MT = 657 Q = -8.83341E+00 MeV Emin = 9.28184E+00 MeV : (n,d7) + 45 MT = 658 Q = -9.02161E+00 MeV Emin = 9.29573E+00 MeV : (n,d8) + 46 MT = 659 Q = -9.03511E+00 MeV Emin = 9.50000E+00 MeV : (n,d9) + 47 MT = 660 Q = -9.37281E+00 MeV Emin = 9.73680E+00 MeV : (n,d10) + 48 MT = 661 Q = -9.46381E+00 MeV Emin = 9.80264E+00 MeV : (n,d11) + 49 MT = 662 Q = -9.52781E+00 MeV Emin = 1.00000E+01 MeV : (n,d12) + 50 MT = 663 Q = -9.82581E+00 MeV Emin = 1.01185E+01 MeV : (n,d13) + 51 MT = 664 Q = -9.83481E+00 MeV Emin = 1.01843E+01 MeV : (n,d14) + 52 MT = 665 Q = -9.89881E+00 MeV Emin = 1.02821E+01 MeV : (n,d15) + 53 MT = 666 Q = -9.99381E+00 MeV Emin = 1.04313E+01 MeV : (n,d16) + 54 MT = 667 Q = -1.01388E+01 MeV Emin = 1.04392E+01 MeV : (n,d17) + 55 MT = 668 Q = -1.02658E+01 MeV Emin = 1.05619E+01 MeV : (n,d18) + 56 MT = 669 Q = -1.03193E+01 MeV Emin = 1.06957E+01 MeV : (n,d19) + 57 MT = 670 Q = -1.03958E+01 MeV Emin = 1.06957E+01 MeV : (n,d20) + 58 MT = 671 Q = -1.03968E+01 MeV Emin = 1.06967E+01 MeV : (n,d21) + 59 MT = 672 Q = -1.04908E+01 MeV Emin = 1.07934E+01 MeV : (n,d22) + 60 MT = 673 Q = -1.05618E+01 MeV Emin = 1.08665E+01 MeV : (n,d23) + 61 MT = 674 Q = -1.06258E+01 MeV Emin = 1.09868E+01 MeV : (n,d24) + 62 MT = 675 Q = -1.06788E+01 MeV Emin = 1.10000E+01 MeV : (n,d25) + 63 MT = 676 Q = -1.07848E+01 MeV Emin = 1.10959E+01 MeV : (n,d26) + 64 MT = 677 Q = -1.08288E+01 MeV Emin = 1.11412E+01 MeV : (n,d27) + 65 MT = 678 Q = -1.08338E+01 MeV Emin = 1.11885E+01 MeV : (n,d28) + 66 MT = 679 Q = -1.08748E+01 MeV Emin = 1.12019E+01 MeV : (n,d29) + 67 MT = 680 Q = -1.08878E+01 MeV Emin = 1.12019E+01 MeV : (n,d30) + 68 MT = 699 Q = -1.08878E+01 MeV Emin = 1.12019E+01 MeV : (n,d) to continuum + 69 MT = 700 Q = -9.30564E+00 MeV Emin = 9.64317E+00 MeV : (n,t) to ground state + 70 MT = 701 Q = -1.01466E+01 MeV Emin = 1.04392E+01 MeV : (n,t1) + 71 MT = 702 Q = -1.12719E+01 MeV Emin = 1.19533E+01 MeV : (n,t2) + 72 MT = 703 Q = -1.16181E+01 MeV Emin = 1.20000E+01 MeV : (n,t3) + 73 MT = 704 Q = -1.21720E+01 MeV Emin = 1.25924E+01 MeV : (n,t4) + 74 MT = 705 Q = -1.22393E+01 MeV Emin = 1.26283E+01 MeV : (n,t5) + 75 MT = 706 Q = -1.22742E+01 MeV Emin = 1.28868E+01 MeV : (n,t6) + 76 MT = 707 Q = -1.25255E+01 MeV Emin = 1.30000E+01 MeV : (n,t7) + 77 MT = 708 Q = -1.31372E+01 MeV Emin = 1.36221E+01 MeV : (n,t8) + 78 MT = 709 Q = -1.32402E+01 MeV Emin = 1.37384E+01 MeV : (n,t9) + 79 MT = 710 Q = -1.33532E+01 MeV Emin = 1.37440E+01 MeV : (n,t10) + 80 MT = 711 Q = -1.33586E+01 MeV Emin = 1.37861E+01 MeV : (n,t11) + 81 MT = 712 Q = -1.33996E+01 MeV Emin = 1.38373E+01 MeV : (n,t12) + 82 MT = 713 Q = -1.34493E+01 MeV Emin = 1.39059E+01 MeV : (n,t13) + 83 MT = 714 Q = -1.35160E+01 MeV Emin = 1.40000E+01 MeV : (n,t14) + 84 MT = 715 Q = -1.36805E+01 MeV Emin = 1.41262E+01 MeV : (n,t15) + 85 MT = 716 Q = -1.37301E+01 MeV Emin = 1.44399E+01 MeV : (n,t16) + 86 MT = 717 Q = -1.40350E+01 MeV Emin = 1.44570E+01 MeV : (n,t17) + 87 MT = 718 Q = -1.40516E+01 MeV Emin = 1.44570E+01 MeV : (n,t18) + 88 MT = 719 Q = -1.41713E+01 MeV Emin = 1.46349E+01 MeV : (n,t19) + 89 MT = 720 Q = -1.42246E+01 MeV Emin = 1.46586E+01 MeV : (n,t20) + 90 MT = 721 Q = -1.42476E+01 MeV Emin = 1.49004E+01 MeV : (n,t21) + 91 MT = 722 Q = -1.44826E+01 MeV Emin = 1.49333E+01 MeV : (n,t22) + 92 MT = 723 Q = -1.45146E+01 MeV Emin = 1.49992E+01 MeV : (n,t23) + 93 MT = 724 Q = -1.45786E+01 MeV Emin = 1.50000E+01 MeV : (n,t24) + 94 MT = 725 Q = -1.45876E+01 MeV Emin = 1.50650E+01 MeV : (n,t25) + 95 MT = 726 Q = -1.46426E+01 MeV Emin = 1.50650E+01 MeV : (n,t26) + 96 MT = 727 Q = -1.46526E+01 MeV Emin = 1.51247E+01 MeV : (n,t27) + 97 MT = 728 Q = -1.47006E+01 MeV Emin = 1.52071E+01 MeV : (n,t28) + 98 MT = 729 Q = -1.47807E+01 MeV Emin = 1.53325E+01 MeV : (n,t29) + 99 MT = 730 Q = -1.49026E+01 MeV Emin = 1.53325E+01 MeV : (n,t30) + 100 MT = 749 Q = -1.49026E+01 MeV Emin = 1.53325E+01 MeV : (n,t) to continuum + 101 MT = 800 Q = 9.38230E-01 MeV Emin = 1.00000E-11 MeV : (n,alpha) to ground state + 102 MT = 801 Q = 8.60130E-01 MeV Emin = 9.99658E-01 MeV : (n,a1) + 103 MT = 802 Q = 4.25230E-01 MeV Emin = 1.45768E+00 MeV : (n,a2) + 104 MT = 803 Q = -2.11470E-01 MeV Emin = 1.90700E+00 MeV : (n,a3) + 105 MT = 804 Q = -3.84970E-01 MeV Emin = 2.06309E+00 MeV : (n,a4) + 106 MT = 805 Q = -8.16270E-01 MeV Emin = 2.06309E+00 MeV : (n,a5) + 107 MT = 806 Q = -1.23957E+00 MeV Emin = 2.06309E+00 MeV : (n,a6) + 108 MT = 807 Q = -1.28067E+00 MeV Emin = 2.06309E+00 MeV : (n,a7) + 109 MT = 808 Q = -1.29157E+00 MeV Emin = 2.06309E+00 MeV : (n,a8) + 110 MT = 809 Q = -1.71957E+00 MeV Emin = 2.06309E+00 MeV : (n,a9) + 111 MT = 810 Q = -1.80647E+00 MeV Emin = 2.06309E+00 MeV : (n,a10) + 112 MT = 811 Q = -2.06657E+00 MeV Emin = 2.16261E+00 MeV : (n,a11) + 113 MT = 812 Q = -2.21117E+00 MeV Emin = 2.39071E+00 MeV : (n,a12) + 114 MT = 813 Q = -2.32577E+00 MeV Emin = 2.45284E+00 MeV : (n,a13) + 115 MT = 814 Q = -2.38407E+00 MeV Emin = 2.50000E+00 MeV : (n,a14) + 116 MT = 815 Q = -2.50477E+00 MeV Emin = 2.57908E+00 MeV : (n,a15) + 117 MT = 816 Q = -2.50677E+00 MeV Emin = 2.72191E+00 MeV : (n,a16) + 118 MT = 817 Q = -2.85867E+00 MeV Emin = 3.00000E+00 MeV : (n,a17) + 119 MT = 818 Q = -2.94177E+00 MeV Emin = 3.03023E+00 MeV : (n,a18) + 120 MT = 819 Q = -3.05127E+00 MeV Emin = 3.14773E+00 MeV : (n,a19) + 121 MT = 820 Q = -3.06887E+00 MeV Emin = 3.15739E+00 MeV : (n,a20) + 122 MT = 849 Q = -3.06887E+00 MeV Emin = 3.15739E+00 MeV : (n,alpha) to continuum + 123 MT = 4 Q = 0.00000E+00 MeV Emin = 1.25000E+00 MeV : total inelastic scattering + + Nuclide 31 / 1657 : 17037.82c -- chlorine 37 (Cl-37) + + Pointers : 158336 21627 + Primary type : Transport + Nuclide ZAI : 170370 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Cl37.ACE + Atomic weight (AW) : 36.96586 + Atomic weight ratio (AWR) : 36.64830 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 39 reaction channels + - 44 special reactions + - 10 transmutation reactions + - 8 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 39 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.03111E+01 MeV Emin = 1.05925E+01 MeV frac = 1.00000E+00 Product nuclide = 170360 : (n,2n) + 3 MT = 17 Q = -1.88908E+01 MeV Emin = 1.94063E+01 MeV frac = 1.00000E+00 Product nuclide = 17035.82c : (n,3n) + 4 MT = 22 Q = -7.84859E+00 MeV Emin = 8.06275E+00 MeV frac = 1.00000E+00 Product nuclide = 150330 : (n,nalpha) + 5 MT = 28 Q = -8.38656E+00 MeV Emin = 8.61540E+00 MeV frac = 1.00000E+00 Product nuclide = 16036.82c : (n,np) + 6 MT = 32 Q = -1.60507E+01 MeV Emin = 1.64887E+01 MeV frac = 1.00000E+00 Product nuclide = 160350 : (n,nd) + 7 MT = 51 Q = -1.72658E+00 MeV Emin = 1.75000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 8 MT = 52 Q = -3.08614E+00 MeV Emin = 3.17035E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 9 MT = 53 Q = -3.10350E+00 MeV Emin = 3.18818E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 10 MT = 54 Q = -3.62682E+00 MeV Emin = 3.72578E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 11 MT = 55 Q = -3.70779E+00 MeV Emin = 3.80896E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 12 MT = 56 Q = -3.74122E+00 MeV Emin = 3.84330E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 13 MT = 57 Q = -4.00987E+00 MeV Emin = 4.11929E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 14 MT = 58 Q = -4.01629E+00 MeV Emin = 4.12588E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 15 MT = 59 Q = -4.17664E+00 MeV Emin = 4.29061E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 16 MT = 60 Q = -4.26887E+00 MeV Emin = 4.38535E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 17 MT = 61 Q = -4.27259E+00 MeV Emin = 4.38917E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 18 MT = 62 Q = -4.39630E+00 MeV Emin = 4.51626E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 19 MT = 63 Q = -4.45997E+00 MeV Emin = 4.58167E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 20 MT = 64 Q = -4.54560E+00 MeV Emin = 4.66963E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 21 MT = 65 Q = -4.80121E+00 MeV Emin = 4.93222E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 22 MT = 66 Q = -4.81090E+00 MeV Emin = 4.94217E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 23 MT = 67 Q = -4.83761E+00 MeV Emin = 4.96961E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 24 MT = 68 Q = -4.85396E+00 MeV Emin = 4.98641E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 25 MT = 69 Q = -4.90420E+00 MeV Emin = 5.03802E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 26 MT = 70 Q = -4.92060E+00 MeV Emin = 5.05487E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 27 MT = 71 Q = -4.92300E+00 MeV Emin = 5.05733E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 28 MT = 72 Q = -4.96080E+00 MeV Emin = 5.09616E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 29 MT = 73 Q = -4.97400E+00 MeV Emin = 5.10972E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 30 MT = 74 Q = -5.00930E+00 MeV Emin = 5.14599E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 31 MT = 75 Q = -5.05520E+00 MeV Emin = 5.19314E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 32 MT = 76 Q = -5.05910E+00 MeV Emin = 5.19715E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 33 MT = 77 Q = -5.14300E+00 MeV Emin = 5.28334E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 27. excited state + 34 MT = 91 Q = -5.14300E+00 MeV Emin = 5.28334E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 35 MT = 102 Q = 6.10783E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 170380 : (n,gamma) + 36 MT = 103 Q = -4.08295E+00 MeV Emin = 4.19436E+00 MeV frac = 1.00000E+00 Product nuclide = 160370 : (n,p) + 37 MT = 104 Q = -6.16197E+00 MeV Emin = 6.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 16036.82c : (n,d) + 38 MT = 105 Q = -9.79340E+00 MeV Emin = 1.05000E+01 MeV frac = 1.00000E+00 Product nuclide = 160350 : (n,t) + 39 MT = 107 Q = -1.55761E+00 MeV Emin = 3.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 150340 : (n,alpha) + + 8 additional transport branches: + + 1 MT = 22 Q = -7.84859E+00 MeV Emin = 8.06275E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -8.38656E+00 MeV Emin = 8.61540E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.60507E+01 MeV Emin = 1.64887E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 102 Q = 6.10783E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 170381 : (n,gamma) + 5 MT = 103 Q = -4.08295E+00 MeV Emin = 4.19436E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 104 Q = -6.16197E+00 MeV Emin = 6.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 7 MT = 105 Q = -9.79340E+00 MeV Emin = 1.05000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 8 MT = 107 Q = -1.55761E+00 MeV Emin = 3.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 44 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.19436E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.50000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.05000E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 3.50000E+00 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 649 Q = -4.08295E+00 MeV Emin = 4.19436E+00 MeV : (n,p) to continuum + 7 MT = 650 Q = -6.16197E+00 MeV Emin = 6.50000E+00 MeV : (n,d) to ground state + 8 MT = 651 Q = -9.45297E+00 MeV Emin = 1.00000E+01 MeV : (n,d1) + 9 MT = 652 Q = -9.50797E+00 MeV Emin = 1.00000E+01 MeV : (n,d2) + 10 MT = 653 Q = -1.03545E+01 MeV Emin = 1.10000E+01 MeV : (n,d3) + 11 MT = 654 Q = -1.06850E+01 MeV Emin = 1.10000E+01 MeV : (n,d4) + 12 MT = 655 Q = -1.07372E+01 MeV Emin = 1.15000E+01 MeV : (n,d5) + 13 MT = 656 Q = -1.14132E+01 MeV Emin = 1.17246E+01 MeV : (n,d6) + 14 MT = 657 Q = -1.15534E+01 MeV Emin = 1.20000E+01 MeV : (n,d7) + 15 MT = 658 Q = -1.16711E+01 MeV Emin = 1.20000E+01 MeV : (n,d8) + 16 MT = 659 Q = -1.17351E+01 MeV Emin = 1.20553E+01 MeV : (n,d9) + 17 MT = 660 Q = -1.23489E+01 MeV Emin = 1.27252E+01 MeV : (n,d10) + 18 MT = 661 Q = -1.23872E+01 MeV Emin = 1.30000E+01 MeV : (n,d11) + 19 MT = 699 Q = -1.23872E+01 MeV Emin = 1.27252E+01 MeV : (n,d) to continuum + 20 MT = 700 Q = -9.79340E+00 MeV Emin = 1.05000E+01 MeV : (n,t) to ground state + 21 MT = 701 Q = -1.13657E+01 MeV Emin = 1.20000E+01 MeV : (n,t1) + 22 MT = 702 Q = -1.17846E+01 MeV Emin = 1.24722E+01 MeV : (n,t2) + 23 MT = 703 Q = -1.21409E+01 MeV Emin = 1.25000E+01 MeV : (n,t3) + 24 MT = 704 Q = -1.25109E+01 MeV Emin = 1.30000E+01 MeV : (n,t4) + 25 MT = 705 Q = -1.27326E+01 MeV Emin = 1.35000E+01 MeV : (n,t5) + 26 MT = 706 Q = -1.32144E+01 MeV Emin = 1.35750E+01 MeV : (n,t6) + 27 MT = 707 Q = -1.33542E+01 MeV Emin = 1.37558E+01 MeV : (n,t7) + 28 MT = 708 Q = -1.33904E+01 MeV Emin = 1.38359E+01 MeV : (n,t8) + 29 MT = 709 Q = -1.34684E+01 MeV Emin = 1.38359E+01 MeV : (n,t9) + 30 MT = 710 Q = -1.35956E+01 MeV Emin = 1.39666E+01 MeV : (n,t10) + 31 MT = 711 Q = -1.36115E+01 MeV Emin = 1.40000E+01 MeV : (n,t11) + 32 MT = 712 Q = -1.36794E+01 MeV Emin = 1.40742E+01 MeV : (n,t12) + 33 MT = 713 Q = -1.37004E+01 MeV Emin = 1.40742E+01 MeV : (n,t13) + 34 MT = 714 Q = -1.38154E+01 MeV Emin = 1.41924E+01 MeV : (n,t14) + 35 MT = 715 Q = -1.38214E+01 MeV Emin = 1.45000E+01 MeV : (n,t15) + 36 MT = 749 Q = -1.38214E+01 MeV Emin = 1.41985E+01 MeV : (n,t) to continuum + 37 MT = 800 Q = -1.55761E+00 MeV Emin = 3.50000E+00 MeV : (n,alpha) to ground state + 38 MT = 801 Q = -1.98668E+00 MeV Emin = 4.00000E+00 MeV : (n,a1) + 39 MT = 802 Q = -3.16521E+00 MeV Emin = 5.00000E+00 MeV : (n,a2) + 40 MT = 803 Q = -3.78261E+00 MeV Emin = 5.50000E+00 MeV : (n,a3) + 41 MT = 804 Q = -3.86661E+00 MeV Emin = 5.50000E+00 MeV : (n,a4) + 42 MT = 805 Q = -4.90261E+00 MeV Emin = 7.00000E+00 MeV : (n,a5) + 43 MT = 849 Q = -4.90261E+00 MeV Emin = 5.03639E+00 MeV : (n,alpha) to continuum + 44 MT = 4 Q = 0.00000E+00 MeV Emin = 1.75000E+00 MeV : total inelastic scattering + + Nuclide 32 / 1657 : 18038.82c -- argon 38 (Ar-38) + + Pointers : 168624 19189 + Primary type : Transport + Nuclide ZAI : 180380 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ar38.ACE + Atomic weight (AW) : 37.96272 + Atomic weight ratio (AWR) : 37.63660 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 29 reaction channels + - 5 special reactions + - 8 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 29 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.16890E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 180370 : (n,2n) + 3 MT = 22 Q = -7.20900E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 16034.82c : (n,nalpha) + 4 MT = 28 Q = -1.02400E+01 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 17037.82c : (n,np) + 5 MT = 51 Q = -2.16800E+00 MeV Emin = 2.22560E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -3.37800E+00 MeV Emin = 3.46775E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -3.81000E+00 MeV Emin = 3.91123E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -3.93700E+00 MeV Emin = 4.04161E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -4.48000E+00 MeV Emin = 4.59903E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -4.56500E+00 MeV Emin = 4.68629E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -4.58600E+00 MeV Emin = 4.70785E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -4.71000E+00 MeV Emin = 4.83514E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -4.87700E+00 MeV Emin = 5.00658E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -5.08400E+00 MeV Emin = 5.21908E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -5.15700E+00 MeV Emin = 5.29402E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -5.35000E+00 MeV Emin = 5.49215E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 63 Q = -5.51300E+00 MeV Emin = 5.65948E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 18 MT = 64 Q = -5.55200E+00 MeV Emin = 5.69952E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 19 MT = 65 Q = -5.59500E+00 MeV Emin = 5.74366E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 20 MT = 66 Q = -5.65800E+00 MeV Emin = 5.80833E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 21 MT = 67 Q = -5.73400E+00 MeV Emin = 5.88635E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 22 MT = 68 Q = -5.82500E+00 MeV Emin = 5.97977E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 23 MT = 69 Q = -5.85700E+00 MeV Emin = 6.01262E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 24 MT = 91 Q = -5.90000E+00 MeV Emin = 6.05676E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 25 MT = 102 Q = 6.59970E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 180390 : (n,gamma) + 26 MT = 103 Q = -4.87060E+00 MeV Emin = 5.00001E+00 MeV frac = 1.00000E+00 Product nuclide = 170380 : (n,p) + 27 MT = 104 Q = -7.79290E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 17037.82c : (n,d) + 28 MT = 107 Q = -2.22200E-01 MeV Emin = 2.12517E-01 MeV frac = 1.00000E+00 Product nuclide = 160350 : (n,alpha) + 29 MT = 108 Q = -8.54500E+00 MeV Emin = 8.77204E+00 MeV frac = 1.00000E+00 Product nuclide = 140310 : (n,2alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = -7.20900E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.02400E+01 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -4.87060E+00 MeV Emin = 5.00001E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -7.79290E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 107 Q = -2.22200E-01 MeV Emin = 2.12517E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 108 Q = -8.54500E+00 MeV Emin = 8.77204E+00 MeV frac = 2.00000E+00 Product nuclide = 2004.82c : (n,2alpha) + + 5 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 5.00001E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.00000E+00 MeV : total deuteron production + 3 MT = 207 Q = 0.00000E+00 MeV Emin = 2.12517E-01 MeV : total alpha production + 4 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 5 MT = 4 Q = 0.00000E+00 MeV Emin = 2.22560E+00 MeV : total inelastic scattering + + Nuclide 33 / 1657 : 18040.82c -- argon 40 (Ar-40) + + Pointers : 171872 19235 + Primary type : Transport + Nuclide ZAI : 180400 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ar40.ACE + Atomic weight (AW) : 39.96240 + Atomic weight ratio (AWR) : 39.61910 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 37 reaction channels + - 7 special reactions + - 10 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 37 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -9.87088E+00 MeV Emin = 1.01200E+01 MeV frac = 1.00000E+00 Product nuclide = 180390 : (n,2n) + 3 MT = 17 Q = -1.64682E+01 MeV Emin = 1.68839E+01 MeV frac = 1.00000E+00 Product nuclide = 18038.82c : (n,3n) + 4 MT = 22 Q = -6.79823E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 16036.82c : (n,nalpha) + 5 MT = 28 Q = -1.25264E+01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 170390 : (n,np) + 6 MT = 51 Q = -1.46090E+00 MeV Emin = 1.49730E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -2.12080E+00 MeV Emin = 2.17433E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -2.52410E+00 MeV Emin = 2.58781E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -2.89300E+00 MeV Emin = 2.96602E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -3.20830E+00 MeV Emin = 3.28928E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -3.46449E+00 MeV Emin = 3.55194E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -3.51129E+00 MeV Emin = 3.59992E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -3.51499E+00 MeV Emin = 3.60371E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -3.68099E+00 MeV Emin = 3.77390E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -3.91879E+00 MeV Emin = 4.01770E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -3.94199E+00 MeV Emin = 4.04149E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -4.04199E+00 MeV Emin = 4.14401E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -4.08249E+00 MeV Emin = 4.18553E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -4.17899E+00 MeV Emin = 4.28447E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -4.22599E+00 MeV Emin = 4.33266E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 21 MT = 66 Q = -4.22899E+00 MeV Emin = 4.33573E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 22 MT = 67 Q = -4.30119E+00 MeV Emin = 4.40975E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 23 MT = 68 Q = -4.32449E+00 MeV Emin = 4.43364E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 24 MT = 69 Q = -4.35799E+00 MeV Emin = 4.46799E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 25 MT = 70 Q = -4.41899E+00 MeV Emin = 4.53053E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 26 MT = 71 Q = -4.42699E+00 MeV Emin = 4.53873E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 27 MT = 72 Q = -4.48099E+00 MeV Emin = 4.59409E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 28 MT = 73 Q = -4.49399E+00 MeV Emin = 4.60742E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 29 MT = 74 Q = -4.56199E+00 MeV Emin = 4.67714E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 30 MT = 75 Q = -4.57799E+00 MeV Emin = 4.69354E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 31 MT = 91 Q = -4.57999E+00 MeV Emin = 4.69559E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 32 MT = 102 Q = 6.09939E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 180410 : (n,gamma) + 33 MT = 103 Q = -6.71672E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 170400 : (n,p) + 34 MT = 104 Q = -1.03018E+01 MeV Emin = 1.05618E+01 MeV frac = 1.00000E+00 Product nuclide = 170390 : (n,d) + 35 MT = 105 Q = -1.21179E+01 MeV Emin = 1.24238E+01 MeV frac = 1.00000E+00 Product nuclide = 170380 : (n,t) + 36 MT = 106 Q = -1.50362E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 160380 : (n,He-3) + 37 MT = 107 Q = -2.48545E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 160370 : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -6.79823E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.25264E+01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -6.71672E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -1.03018E+01 MeV Emin = 1.05618E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -1.21179E+01 MeV Emin = 1.24238E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 106 Q = -1.50362E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 7 MT = 107 Q = -2.48545E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 7.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.05618E+01 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.24238E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.60000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 3.00000E+00 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 1.49730E+00 MeV : total inelastic scattering + + Nuclide 34 / 1657 : 19039.82c -- potassium 39 (K-39) + + Pointers : 178044 26825 + Primary type : Transport + Nuclide ZAI : 190390 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/K39.ACE + Atomic weight (AW) : 38.96402 + Atomic weight ratio (AWR) : 38.62930 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 12 reaction channels + - 4 special reactions + - 6 transmutation reactions + - 4 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 12 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.30850E+01 MeV Emin = 1.35000E+01 MeV frac = 1.00000E+00 Product nuclide = 190380 : (n,2n) + 3 MT = 22 Q = -7.21723E+00 MeV Emin = 7.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 17035.82c : (n,nalpha) + 4 MT = 28 Q = -6.38011E+00 MeV Emin = 6.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 18038.82c : (n,np) + 5 MT = 51 Q = -2.52300E+00 MeV Emin = 2.58831E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -2.81400E+00 MeV Emin = 2.88685E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -3.01900E+00 MeV Emin = 3.09715E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -3.59799E+00 MeV Emin = 3.69114E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 91 Q = -3.79999E+00 MeV Emin = 3.89837E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 10 MT = 102 Q = 7.80099E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 19040.82c : (n,gamma) + 11 MT = 103 Q = 2.17170E-01 MeV Emin = 9.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 180390 : (n,p) + 12 MT = 107 Q = 1.36325E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 170360 : (n,alpha) + + 4 additional transport branches: + + 1 MT = 22 Q = -7.21723E+00 MeV Emin = 7.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -6.38011E+00 MeV Emin = 6.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = 2.17170E-01 MeV Emin = 9.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 107 Q = 1.36325E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 4 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 9.00000E-01 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 4 MT = 4 Q = 0.00000E+00 MeV Emin = 2.58831E+00 MeV : total inelastic scattering + + Nuclide 35 / 1657 : 19040.82c -- potassium 40 (K-40) + + Pointers : 179615 26871 + Primary type : Transport + Nuclide ZAI : 190400 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/K40.ACE + Atomic weight (AW) : 39.96401 + Atomic weight ratio (AWR) : 39.62070 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 3.95E+16 seconds (1.25 billion years) + Specific ingestion toxicity : 6.20E-09 Sv/Bq + Specific inhalation toxicity : 2.10E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 13 reaction channels + - 4 special reactions + - 6 transmutation reactions + - 4 transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 13 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.80048E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 19039.82c : (n,2n) + 3 MT = 22 Q = -6.43723E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 170360 : (n,nalpha) + 4 MT = 28 Q = -7.58331E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 180390 : (n,np) + 5 MT = 51 Q = -3.00000E-02 MeV Emin = 3.05078E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -7.99999E-01 MeV Emin = 8.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -8.91999E-01 MeV Emin = 9.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -1.64400E+00 MeV Emin = 1.59275E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -1.95900E+00 MeV Emin = 2.00845E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 91 Q = -2.10000E+00 MeV Emin = 2.15300E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 11 MT = 102 Q = 1.00960E+01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 19041.82c : (n,gamma) + 12 MT = 103 Q = 2.28757E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 18040.82c : (n,p) + 13 MT = 107 Q = 3.87414E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 17037.82c : (n,alpha) + + 4 additional transport branches: + + 1 MT = 22 Q = -6.43723E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -7.58331E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = 2.28757E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 107 Q = 3.87414E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 4 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 4 MT = 4 Q = 0.00000E+00 MeV Emin = 3.05078E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 2 Q = 1.50469E+00 MeV frac = 1.07500E-01 Product nuclide = 18040.82c : EC/beta+ + 2 RTYP = 1 Q = 1.31107E+00 MeV frac = 8.92500E-01 Product nuclide = 200400 : beta- + + Nuclide 36 / 1657 : 19041.82c -- potassium 41 (K-41) + + Pointers : 181550 26917 + Primary type : Transport + Nuclide ZAI : 190410 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/K41.ACE + Atomic weight (AW) : 40.96198 + Atomic weight ratio (AWR) : 40.61010 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 10 reaction channels + - 4 special reactions + - 6 transmutation reactions + - 4 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 10 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.00959E+01 MeV Emin = 1.03445E+01 MeV frac = 1.00000E+00 Product nuclide = 19040.82c : (n,2n) + 3 MT = 22 Q = -6.22173E+00 MeV Emin = 6.40000E+00 MeV frac = 1.00000E+00 Product nuclide = 17037.82c : (n,nalpha) + 4 MT = 28 Q = -7.80831E+00 MeV Emin = 8.00059E+00 MeV frac = 1.00000E+00 Product nuclide = 18040.82c : (n,np) + 5 MT = 51 Q = -9.79999E-01 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -1.29400E+00 MeV Emin = 1.28793E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 91 Q = -1.50000E+00 MeV Emin = 1.52459E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 8 MT = 102 Q = 7.53499E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 190420 : (n,gamma) + 9 MT = 103 Q = -1.70973E+00 MeV Emin = 1.75000E+00 MeV frac = 1.00000E+00 Product nuclide = 180410 : (n,p) + 10 MT = 107 Q = -1.11550E-01 MeV Emin = 1.14284E-01 MeV frac = 1.00000E+00 Product nuclide = 170380 : (n,alpha) + + 4 additional transport branches: + + 1 MT = 22 Q = -6.22173E+00 MeV Emin = 6.40000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -7.80831E+00 MeV Emin = 8.00059E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -1.70973E+00 MeV Emin = 1.75000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 107 Q = -1.11550E-01 MeV Emin = 1.14284E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 4 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.75000E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 1.14284E-01 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 4 MT = 4 Q = 0.00000E+00 MeV Emin = 1.00000E+00 MeV : total inelastic scattering + + Nuclide 37 / 1657 : 20042.82c -- calcium 42 (Ca-42) + + Pointers : 188411 20431 + Primary type : Transport + Nuclide ZAI : 200420 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ca42.ACE + Atomic weight (AW) : 41.95863 + Atomic weight ratio (AWR) : 41.59818 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+02 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 39 reaction channels + - 52 special reactions + - 16 transmutation reactions + - 17 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 39 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 5 Q = 0.00000E+00 MeV Emin = 2.99795E-01 MeV frac = 1.00000E+00 Product nuclide = self : anything + 3 MT = 16 Q = -1.14806E+01 MeV Emin = 1.17566E+01 MeV frac = 1.00000E+00 Product nuclide = 200410 : (n,2n) + 4 MT = 22 Q = -6.25691E+00 MeV Emin = 7.20000E+00 MeV frac = 1.00000E+00 Product nuclide = 18038.82c : (n,nalpha) + 5 MT = 28 Q = -1.02769E+01 MeV Emin = 1.05240E+01 MeV frac = 1.00000E+00 Product nuclide = 19041.82c : (n,np) + 6 MT = 29 Q = -1.34647E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 16034.82c : (n,n2alpha) + 7 MT = 32 Q = -1.81475E+01 MeV Emin = 1.85838E+01 MeV frac = 1.00000E+00 Product nuclide = 19040.82c : (n,nd) + 8 MT = 51 Q = -1.52473E+00 MeV Emin = 1.53069E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -1.83730E+00 MeV Emin = 1.85601E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -2.42417E+00 MeV Emin = 2.48245E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -2.75241E+00 MeV Emin = 2.81858E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -3.18933E+00 MeV Emin = 3.26600E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -3.25390E+00 MeV Emin = 3.33212E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -3.30000E+00 MeV Emin = 3.37933E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -3.39200E+00 MeV Emin = 3.47354E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -3.44696E+00 MeV Emin = 3.52982E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -3.65400E+00 MeV Emin = 3.74184E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -3.88500E+00 MeV Emin = 3.97839E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 62 Q = -3.95441E+00 MeV Emin = 4.04947E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 20 MT = 63 Q = -3.99967E+00 MeV Emin = 4.09582E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 21 MT = 64 Q = -4.04700E+00 MeV Emin = 4.14429E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 22 MT = 65 Q = -4.09970E+00 MeV Emin = 4.19826E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 23 MT = 66 Q = -4.11700E+00 MeV Emin = 4.21597E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 24 MT = 67 Q = -4.23200E+00 MeV Emin = 4.33374E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 25 MT = 68 Q = -4.35400E+00 MeV Emin = 4.45867E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 26 MT = 69 Q = -4.41800E+00 MeV Emin = 4.52421E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 27 MT = 70 Q = -4.44300E+00 MeV Emin = 4.54981E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 28 MT = 91 Q = -4.44300E+00 MeV Emin = 4.54981E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 29 MT = 102 Q = 7.93300E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 20043.82c : (n,gamma) + 30 MT = 103 Q = -2.74309E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 190420 : (n,p) + 31 MT = 104 Q = -8.05229E+00 MeV Emin = 8.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 19041.82c : (n,d) + 32 MT = 105 Q = -1.18902E+01 MeV Emin = 1.21761E+01 MeV frac = 1.00000E+00 Product nuclide = 19040.82c : (n,t) + 33 MT = 106 Q = -1.03668E+01 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 18040.82c : (n,He-3) + 34 MT = 107 Q = 3.41482E-01 MeV Emin = 6.50000E-01 MeV frac = 1.00000E+00 Product nuclide = 180390 : (n,alpha) + 35 MT = 108 Q = -6.47890E+00 MeV Emin = 9.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 160350 : (n,2alpha) + 36 MT = 111 Q = -1.19861E+01 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 180410 : (n,2p) + 37 MT = 112 Q = -1.03913E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 170380 : (n,palpha) + 38 MT = 115 Q = -1.58602E+01 MeV Emin = 1.70000E+01 MeV frac = 1.00000E+00 Product nuclide = 18040.82c : (n,pd) + 39 MT = 117 Q = -1.42746E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 17037.82c : (n,dalpha) + + 17 additional transport branches: + + 1 MT = 22 Q = -6.25691E+00 MeV Emin = 7.20000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.02769E+01 MeV Emin = 1.05240E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 29 Q = -1.34647E+01 MeV Emin = 1.60000E+01 MeV frac = 2.00000E+00 Product nuclide = 2004.82c : (n,n2alpha) + 4 MT = 32 Q = -1.81475E+01 MeV Emin = 1.85838E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 5 MT = 103 Q = -2.74309E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 104 Q = -8.05229E+00 MeV Emin = 8.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 7 MT = 105 Q = -1.18902E+01 MeV Emin = 1.21761E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 8 MT = 106 Q = -1.03668E+01 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 9 MT = 107 Q = 3.41482E-01 MeV Emin = 6.50000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 10 MT = 108 Q = -6.47890E+00 MeV Emin = 9.50000E+00 MeV frac = 2.00000E+00 Product nuclide = 2004.82c : (n,2alpha) + 11 MT = 111 Q = -1.19861E+01 MeV Emin = 1.25000E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + 12 MT = 112 Q = -1.03913E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,palpha) + 13 MT = 112 Q = -1.03913E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,palpha) + 14 MT = 115 Q = -1.58602E+01 MeV Emin = 1.70000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,pd) + 15 MT = 115 Q = -1.58602E+01 MeV Emin = 1.70000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,pd) + 16 MT = 117 Q = -1.42746E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,dalpha) + 17 MT = 117 Q = -1.42746E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,dalpha) + + 52 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.50000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.21761E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.10000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 6.50000E-01 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 3.87500E-04 MeV : damage-energy production + 7 MT = 600 Q = -2.74309E+00 MeV Emin = 3.00000E+00 MeV : (n,p) to ground state + 8 MT = 601 Q = -2.84992E+00 MeV Emin = 3.20000E+00 MeV : (n,p1) + 9 MT = 602 Q = -3.00135E+00 MeV Emin = 3.20000E+00 MeV : (n,p2) + 10 MT = 603 Q = -3.38182E+00 MeV Emin = 3.60000E+00 MeV : (n,p3) + 11 MT = 604 Q = -3.42504E+00 MeV Emin = 3.80000E+00 MeV : (n,p4) + 12 MT = 605 Q = -3.44217E+00 MeV Emin = 3.80000E+00 MeV : (n,p5) + 13 MT = 606 Q = -3.52696E+00 MeV Emin = 3.80000E+00 MeV : (n,p6) + 14 MT = 607 Q = -3.58503E+00 MeV Emin = 3.80000E+00 MeV : (n,p7) + 15 MT = 608 Q = -3.85384E+00 MeV Emin = 4.20000E+00 MeV : (n,p8) + 16 MT = 609 Q = -3.88668E+00 MeV Emin = 4.20000E+00 MeV : (n,p9) + 17 MT = 610 Q = -3.94099E+00 MeV Emin = 4.20000E+00 MeV : (n,p10) + 18 MT = 649 Q = -3.94099E+00 MeV Emin = 4.40000E+00 MeV : (n,p) to continuum + 19 MT = 650 Q = -8.05229E+00 MeV Emin = 8.50000E+00 MeV : (n,d) to ground state + 20 MT = 651 Q = -9.03277E+00 MeV Emin = 9.24991E+00 MeV : (n,d1) + 21 MT = 652 Q = -9.34590E+00 MeV Emin = 9.57057E+00 MeV : (n,d2) + 22 MT = 653 Q = -9.61219E+00 MeV Emin = 1.00000E+01 MeV : (n,d3) + 23 MT = 654 Q = -9.63429E+00 MeV Emin = 1.00000E+01 MeV : (n,d4) + 24 MT = 655 Q = -9.64540E+00 MeV Emin = 1.00000E+01 MeV : (n,d5) + 25 MT = 699 Q = -9.64540E+00 MeV Emin = 1.00000E+01 MeV : (n,d) to continuum + 26 MT = 700 Q = -1.18902E+01 MeV Emin = 1.21761E+01 MeV : (n,t) to ground state + 27 MT = 701 Q = -1.19201E+01 MeV Emin = 1.25000E+01 MeV : (n,t1) + 28 MT = 702 Q = -1.26904E+01 MeV Emin = 1.30000E+01 MeV : (n,t2) + 29 MT = 703 Q = -1.27816E+01 MeV Emin = 1.30889E+01 MeV : (n,t3) + 30 MT = 704 Q = -1.35339E+01 MeV Emin = 1.38593E+01 MeV : (n,t4) + 31 MT = 705 Q = -1.38493E+01 MeV Emin = 1.41822E+01 MeV : (n,t5) + 32 MT = 749 Q = -1.38493E+01 MeV Emin = 1.50000E+01 MeV : (n,t) to continuum + 33 MT = 750 Q = -1.03668E+01 MeV Emin = 1.10000E+01 MeV : (n,He-3) to ground state + 34 MT = 751 Q = -1.18276E+01 MeV Emin = 1.21119E+01 MeV : (n,He-3_1) + 35 MT = 752 Q = -1.24876E+01 MeV Emin = 1.30000E+01 MeV : (n,He-3_2) + 36 MT = 753 Q = -1.28909E+01 MeV Emin = 1.40000E+01 MeV : (n,He-3_3) + 37 MT = 754 Q = -1.32594E+01 MeV Emin = 1.40000E+01 MeV : (n,He-3_4) + 38 MT = 755 Q = -1.35748E+01 MeV Emin = 1.45000E+01 MeV : (n,He-3_5) + 39 MT = 799 Q = -1.35748E+01 MeV Emin = 1.50000E+01 MeV : (n,He-3) to continuum + 40 MT = 800 Q = 3.41482E-01 MeV Emin = 6.50000E-01 MeV : (n,alpha) to ground state + 41 MT = 801 Q = -9.25728E-01 MeV Emin = 2.00000E+00 MeV : (n,a1) + 42 MT = 802 Q = -1.17606E+00 MeV Emin = 2.00000E+00 MeV : (n,a2) + 43 MT = 803 Q = -1.75127E+00 MeV Emin = 2.60000E+00 MeV : (n,a3) + 44 MT = 804 Q = -2.00072E+00 MeV Emin = 2.80000E+00 MeV : (n,a4) + 45 MT = 805 Q = -2.01680E+00 MeV Emin = 2.80000E+00 MeV : (n,a5) + 46 MT = 806 Q = -2.09200E+00 MeV Emin = 2.80000E+00 MeV : (n,a6) + 47 MT = 807 Q = -2.14001E+00 MeV Emin = 3.00000E+00 MeV : (n,a7) + 48 MT = 808 Q = -2.16194E+00 MeV Emin = 3.00000E+00 MeV : (n,a8) + 49 MT = 809 Q = -2.18226E+00 MeV Emin = 3.00000E+00 MeV : (n,a9) + 50 MT = 810 Q = -2.29008E+00 MeV Emin = 3.00000E+00 MeV : (n,a10) + 51 MT = 849 Q = -2.29008E+00 MeV Emin = 4.00000E+00 MeV : (n,alpha) to continuum + 52 MT = 4 Q = 0.00000E+00 MeV Emin = 1.53069E+00 MeV : total inelastic scattering + + Nuclide 38 / 1657 : 20043.82c -- calcium 43 (Ca-43) + + Pointers : 196406 20477 + Primary type : Transport + Nuclide ZAI : 200430 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ca43.ACE + Atomic weight (AW) : 42.95877 + Atomic weight ratio (AWR) : 42.58973 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+02 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 39 reaction channels + - 52 special reactions + - 16 transmutation reactions + - 14 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 39 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 5 Q = 0.00000E+00 MeV Emin = 3.99661E-02 MeV frac = 1.00000E+00 Product nuclide = self : anything + 3 MT = 16 Q = -7.93300E+00 MeV Emin = 8.11927E+00 MeV frac = 1.00000E+00 Product nuclide = 20042.82c : (n,2n) + 4 MT = 17 Q = -1.94136E+01 MeV Emin = 1.98694E+01 MeV frac = 1.00000E+00 Product nuclide = 200410 : (n,3n) + 5 MT = 22 Q = -7.59152E+00 MeV Emin = 8.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 180390 : (n,nalpha) + 6 MT = 24 Q = -1.41899E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 18038.82c : (n,2nalpha) + 7 MT = 28 Q = -1.06761E+01 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 190420 : (n,np) + 8 MT = 32 Q = -1.59853E+01 MeV Emin = 1.63606E+01 MeV frac = 1.00000E+00 Product nuclide = 19041.82c : (n,nd) + 9 MT = 41 Q = -1.82099E+01 MeV Emin = 1.86375E+01 MeV frac = 1.00000E+00 Product nuclide = 19041.82c : (n,2np) + 10 MT = 51 Q = -3.72762E-01 MeV Emin = 3.65757E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 11 MT = 52 Q = -5.93394E-01 MeV Emin = 6.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 12 MT = 53 Q = -9.90257E-01 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 13 MT = 54 Q = -1.39447E+00 MeV Emin = 1.40000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 14 MT = 55 Q = -1.67780E+00 MeV Emin = 1.70000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 15 MT = 56 Q = -1.90180E+00 MeV Emin = 1.93193E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 16 MT = 57 Q = -1.93130E+00 MeV Emin = 1.96721E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 17 MT = 58 Q = -1.95740E+00 MeV Emin = 2.00336E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 18 MT = 59 Q = -2.04625E+00 MeV Emin = 2.09430E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 19 MT = 60 Q = -2.06730E+00 MeV Emin = 2.11584E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 20 MT = 61 Q = -2.09390E+00 MeV Emin = 2.14306E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 21 MT = 62 Q = -2.10270E+00 MeV Emin = 2.15207E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 22 MT = 63 Q = -2.22400E+00 MeV Emin = 2.27622E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 23 MT = 64 Q = -2.24900E+00 MeV Emin = 2.30181E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 24 MT = 65 Q = -2.27270E+00 MeV Emin = 2.32606E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 25 MT = 66 Q = -2.40980E+00 MeV Emin = 2.46638E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 26 MT = 67 Q = -2.52300E+00 MeV Emin = 2.58224E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 27 MT = 68 Q = -2.61100E+00 MeV Emin = 2.67231E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 28 MT = 69 Q = -2.67370E+00 MeV Emin = 2.73648E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 29 MT = 70 Q = -2.69690E+00 MeV Emin = 2.76022E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 30 MT = 91 Q = -2.69690E+00 MeV Emin = 2.76022E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 31 MT = 102 Q = 1.11320E+01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 20044.82c : (n,gamma) + 32 MT = 103 Q = -1.03305E+00 MeV Emin = 1.18437E+00 MeV frac = 1.00000E+00 Product nuclide = 190430 : (n,p) + 33 MT = 104 Q = -8.45152E+00 MeV Emin = 8.64996E+00 MeV frac = 1.00000E+00 Product nuclide = 190420 : (n,d) + 34 MT = 105 Q = -9.72804E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 19041.82c : (n,t) + 35 MT = 106 Q = -1.22011E+01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 180410 : (n,He-3) + 36 MT = 107 Q = 2.27786E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 18040.82c : (n,alpha) + 37 MT = 108 Q = -4.52299E+00 MeV Emin = 7.40000E+00 MeV frac = 1.00000E+00 Product nuclide = 16036.82c : (n,2alpha) + 38 MT = 111 Q = -1.04930E+01 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 180420 : (n,2p) + 39 MT = 112 Q = -1.02503E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 170390 : (n,palpha) + + 14 additional transport branches: + + 1 MT = 22 Q = -7.59152E+00 MeV Emin = 8.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 24 Q = -1.41899E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,2nalpha) + 3 MT = 28 Q = -1.06761E+01 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 4 MT = 32 Q = -1.59853E+01 MeV Emin = 1.63606E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 5 MT = 41 Q = -1.82099E+01 MeV Emin = 1.86375E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,2np) + 6 MT = 103 Q = -1.03305E+00 MeV Emin = 1.18437E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 7 MT = 104 Q = -8.45152E+00 MeV Emin = 8.64996E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 8 MT = 105 Q = -9.72804E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 9 MT = 106 Q = -1.22011E+01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 10 MT = 107 Q = 2.27786E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 11 MT = 108 Q = -4.52299E+00 MeV Emin = 7.40000E+00 MeV frac = 2.00000E+00 Product nuclide = 2004.82c : (n,2alpha) + 12 MT = 111 Q = -1.04930E+01 MeV Emin = 1.10000E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + 13 MT = 112 Q = -1.02503E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,palpha) + 14 MT = 112 Q = -1.02503E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,palpha) + + 52 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.18437E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.64996E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.00000E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.30000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 600 Q = -1.03305E+00 MeV Emin = 1.18437E+00 MeV : (n,p) to ground state + 8 MT = 601 Q = -1.59425E+00 MeV Emin = 1.77412E+00 MeV : (n,p1) + 9 MT = 602 Q = -1.77115E+00 MeV Emin = 1.98541E+00 MeV : (n,p2) + 10 MT = 603 Q = -2.00805E+00 MeV Emin = 2.20000E+00 MeV : (n,p3) + 11 MT = 604 Q = -2.14335E+00 MeV Emin = 2.40000E+00 MeV : (n,p4) + 12 MT = 605 Q = -2.23995E+00 MeV Emin = 2.40000E+00 MeV : (n,p5) + 13 MT = 606 Q = -2.54295E+00 MeV Emin = 2.60266E+00 MeV : (n,p6) + 14 MT = 607 Q = -2.58265E+00 MeV Emin = 2.80000E+00 MeV : (n,p7) + 15 MT = 608 Q = -2.84805E+00 MeV Emin = 2.91492E+00 MeV : (n,p8) + 16 MT = 609 Q = -2.88315E+00 MeV Emin = 3.00000E+00 MeV : (n,p9) + 17 MT = 610 Q = -2.89905E+00 MeV Emin = 3.00000E+00 MeV : (n,p10) + 18 MT = 649 Q = -2.89905E+00 MeV Emin = 3.20000E+00 MeV : (n,p) to continuum + 19 MT = 650 Q = -8.45152E+00 MeV Emin = 8.64996E+00 MeV : (n,d) to ground state + 20 MT = 651 Q = -8.55835E+00 MeV Emin = 9.00000E+00 MeV : (n,d1) + 21 MT = 652 Q = -8.70978E+00 MeV Emin = 9.00000E+00 MeV : (n,d2) + 22 MT = 653 Q = -9.09025E+00 MeV Emin = 9.30369E+00 MeV : (n,d3) + 23 MT = 654 Q = -9.13346E+00 MeV Emin = 9.50000E+00 MeV : (n,d4) + 24 MT = 655 Q = -9.15060E+00 MeV Emin = 9.50000E+00 MeV : (n,d5) + 25 MT = 699 Q = -9.15060E+00 MeV Emin = 9.50000E+00 MeV : (n,d) to continuum + 26 MT = 700 Q = -9.72804E+00 MeV Emin = 1.00000E+01 MeV : (n,t) to ground state + 27 MT = 701 Q = -1.07085E+01 MeV Emin = 1.09600E+01 MeV : (n,t1) + 28 MT = 702 Q = -1.10217E+01 MeV Emin = 1.15000E+01 MeV : (n,t2) + 29 MT = 703 Q = -1.12879E+01 MeV Emin = 1.15530E+01 MeV : (n,t3) + 30 MT = 704 Q = -1.13100E+01 MeV Emin = 1.15756E+01 MeV : (n,t4) + 31 MT = 705 Q = -1.13212E+01 MeV Emin = 1.15870E+01 MeV : (n,t5) + 32 MT = 749 Q = -1.13212E+01 MeV Emin = 1.20000E+01 MeV : (n,t) to continuum + 33 MT = 750 Q = -1.22011E+01 MeV Emin = 1.30000E+01 MeV : (n,He-3) to ground state + 34 MT = 751 Q = -1.23684E+01 MeV Emin = 1.35000E+01 MeV : (n,He-3_1) + 35 MT = 752 Q = -1.27171E+01 MeV Emin = 1.35000E+01 MeV : (n,He-3_2) + 36 MT = 753 Q = -1.32358E+01 MeV Emin = 1.40000E+01 MeV : (n,He-3_3) + 37 MT = 754 Q = -1.35551E+01 MeV Emin = 1.45000E+01 MeV : (n,He-3_4) + 38 MT = 755 Q = -1.38361E+01 MeV Emin = 1.50000E+01 MeV : (n,He-3_5) + 39 MT = 799 Q = -1.38361E+01 MeV Emin = 1.50000E+01 MeV : (n,He-3) to continuum + 40 MT = 800 Q = 2.27786E+00 MeV Emin = 1.00000E-11 MeV : (n,alpha) to ground state + 41 MT = 801 Q = 8.16999E-01 MeV Emin = 1.00000E-11 MeV : (n,a1) + 42 MT = 802 Q = 1.57059E-01 MeV Emin = 1.01445E+00 MeV : (n,a2) + 43 MT = 803 Q = -2.46241E-01 MeV Emin = 1.35000E+00 MeV : (n,a3) + 44 MT = 804 Q = -6.14741E-01 MeV Emin = 1.70000E+00 MeV : (n,a4) + 45 MT = 805 Q = -9.30141E-01 MeV Emin = 2.00000E+00 MeV : (n,a5) + 46 MT = 806 Q = -1.18662E+00 MeV Emin = 2.00000E+00 MeV : (n,a6) + 47 MT = 807 Q = -1.23344E+00 MeV Emin = 2.00000E+00 MeV : (n,a7) + 48 MT = 808 Q = -1.23714E+00 MeV Emin = 2.00000E+00 MeV : (n,a8) + 49 MT = 809 Q = -1.40294E+00 MeV Emin = 2.20000E+00 MeV : (n,a9) + 50 MT = 810 Q = -1.64094E+00 MeV Emin = 2.40000E+00 MeV : (n,a10) + 51 MT = 849 Q = -1.64094E+00 MeV Emin = 2.60000E+00 MeV : (n,alpha) to continuum + 52 MT = 4 Q = 0.00000E+00 MeV Emin = 3.65757E-01 MeV : total inelastic scattering + + Nuclide 39 / 1657 : 20044.82c -- calcium 44 (Ca-44) + + Pointers : 204182 20523 + Primary type : Transport + Nuclide ZAI : 200440 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ca44.ACE + Atomic weight (AW) : 43.95548 + Atomic weight ratio (AWR) : 43.57788 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+02 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 35 reaction channels + - 48 special reactions + - 12 transmutation reactions + - 9 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 35 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 5 Q = 0.00000E+00 MeV Emin = 4.99742E-01 MeV frac = 1.00000E+00 Product nuclide = self : anything + 3 MT = 16 Q = -1.11320E+01 MeV Emin = 1.13875E+01 MeV frac = 1.00000E+00 Product nuclide = 20043.82c : (n,2n) + 4 MT = 17 Q = -1.90650E+01 MeV Emin = 1.95025E+01 MeV frac = 1.00000E+00 Product nuclide = 20042.82c : (n,3n) + 5 MT = 22 Q = -8.85411E+00 MeV Emin = 9.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 18040.82c : (n,nalpha) + 6 MT = 28 Q = -1.21650E+01 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 190430 : (n,np) + 7 MT = 51 Q = -1.15705E+00 MeV Emin = 1.14180E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 8 MT = 52 Q = -1.88351E+00 MeV Emin = 1.90000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 9 MT = 53 Q = -2.28314E+00 MeV Emin = 2.33553E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 10 MT = 54 Q = -2.65650E+00 MeV Emin = 2.71746E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 11 MT = 55 Q = -3.04433E+00 MeV Emin = 3.11419E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 12 MT = 56 Q = -3.28500E+00 MeV Emin = 3.36038E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 13 MT = 57 Q = -3.30130E+00 MeV Emin = 3.37706E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 14 MT = 58 Q = -3.30786E+00 MeV Emin = 3.38377E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 15 MT = 59 Q = -3.35720E+00 MeV Emin = 3.43424E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 16 MT = 60 Q = -3.58040E+00 MeV Emin = 3.66256E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 17 MT = 61 Q = -3.66153E+00 MeV Emin = 3.74555E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 18 MT = 62 Q = -3.67607E+00 MeV Emin = 3.76043E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 19 MT = 63 Q = -3.71180E+00 MeV Emin = 3.79698E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 20 MT = 64 Q = -3.77620E+00 MeV Emin = 3.86286E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 21 MT = 65 Q = -3.86500E+00 MeV Emin = 3.95369E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 22 MT = 66 Q = -3.91355E+00 MeV Emin = 4.00336E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 23 MT = 67 Q = -3.92260E+00 MeV Emin = 4.01262E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 24 MT = 68 Q = -4.01140E+00 MeV Emin = 4.10345E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 25 MT = 69 Q = -4.09200E+00 MeV Emin = 4.18590E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 26 MT = 70 Q = -4.16900E+00 MeV Emin = 4.26467E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 27 MT = 91 Q = -4.16900E+00 MeV Emin = 4.26467E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 28 MT = 102 Q = 7.41477E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 200450 : (n,gamma) + 29 MT = 103 Q = -4.87652E+00 MeV Emin = 5.20000E+00 MeV frac = 1.00000E+00 Product nuclide = 190440 : (n,p) + 30 MT = 104 Q = -9.94044E+00 MeV Emin = 1.01686E+01 MeV frac = 1.00000E+00 Product nuclide = 190430 : (n,d) + 31 MT = 105 Q = -1.33262E+01 MeV Emin = 1.36320E+01 MeV frac = 1.00000E+00 Product nuclide = 190420 : (n,t) + 32 MT = 106 Q = -1.39069E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 180420 : (n,He-3) + 33 MT = 107 Q = -2.75541E+00 MeV Emin = 3.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 180410 : (n,alpha) + 34 MT = 108 Q = -1.13514E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 160370 : (n,2alpha) + 35 MT = 111 Q = -1.59982E+01 MeV Emin = 1.70000E+01 MeV frac = 1.00000E+00 Product nuclide = 180430 : (n,2p) + + 9 additional transport branches: + + 1 MT = 22 Q = -8.85411E+00 MeV Emin = 9.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.21650E+01 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -4.87652E+00 MeV Emin = 5.20000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -9.94044E+00 MeV Emin = 1.01686E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -1.33262E+01 MeV Emin = 1.36320E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 106 Q = -1.39069E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 7 MT = 107 Q = -2.75541E+00 MeV Emin = 3.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 8 MT = 108 Q = -1.13514E+01 MeV Emin = 1.50000E+01 MeV frac = 2.00000E+00 Product nuclide = 2004.82c : (n,2alpha) + 9 MT = 111 Q = -1.59982E+01 MeV Emin = 1.70000E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 48 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 5.20000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.01686E+01 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.36320E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.50000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 3.60000E+00 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 4.25000E-04 MeV : damage-energy production + 7 MT = 600 Q = -4.87652E+00 MeV Emin = 5.20000E+00 MeV : (n,p) to ground state + 8 MT = 601 Q = -5.05912E+00 MeV Emin = 5.40000E+00 MeV : (n,p1) + 9 MT = 602 Q = -5.25942E+00 MeV Emin = 5.60000E+00 MeV : (n,p2) + 10 MT = 603 Q = -5.39652E+00 MeV Emin = 5.80000E+00 MeV : (n,p3) + 11 MT = 604 Q = -5.68812E+00 MeV Emin = 5.81865E+00 MeV : (n,p4) + 12 MT = 605 Q = -5.84532E+00 MeV Emin = 6.00000E+00 MeV : (n,p5) + 13 MT = 606 Q = -5.88992E+00 MeV Emin = 6.20000E+00 MeV : (n,p6) + 14 MT = 607 Q = -5.92782E+00 MeV Emin = 6.20000E+00 MeV : (n,p7) + 15 MT = 608 Q = -5.95322E+00 MeV Emin = 6.20000E+00 MeV : (n,p8) + 16 MT = 609 Q = -6.11732E+00 MeV Emin = 6.25770E+00 MeV : (n,p9) + 17 MT = 610 Q = -6.24422E+00 MeV Emin = 6.40000E+00 MeV : (n,p10) + 18 MT = 649 Q = -6.24422E+00 MeV Emin = 6.60000E+00 MeV : (n,p) to continuum + 19 MT = 650 Q = -9.94044E+00 MeV Emin = 1.01686E+01 MeV : (n,d) to ground state + 20 MT = 651 Q = -1.05016E+01 MeV Emin = 1.07426E+01 MeV : (n,d1) + 21 MT = 652 Q = -1.06785E+01 MeV Emin = 1.10000E+01 MeV : (n,d2) + 22 MT = 653 Q = -1.09154E+01 MeV Emin = 1.11659E+01 MeV : (n,d3) + 23 MT = 654 Q = -1.10507E+01 MeV Emin = 1.15000E+01 MeV : (n,d4) + 24 MT = 655 Q = -1.11473E+01 MeV Emin = 1.15000E+01 MeV : (n,d5) + 25 MT = 699 Q = -1.11473E+01 MeV Emin = 1.15000E+01 MeV : (n,d) to continuum + 26 MT = 700 Q = -1.33262E+01 MeV Emin = 1.36320E+01 MeV : (n,t) to ground state + 27 MT = 701 Q = -1.34331E+01 MeV Emin = 1.40000E+01 MeV : (n,t1) + 28 MT = 702 Q = -1.35845E+01 MeV Emin = 1.40000E+01 MeV : (n,t2) + 29 MT = 703 Q = -1.39650E+01 MeV Emin = 1.45000E+01 MeV : (n,t3) + 30 MT = 704 Q = -1.40082E+01 MeV Emin = 1.45000E+01 MeV : (n,t4) + 31 MT = 705 Q = -1.40253E+01 MeV Emin = 1.45000E+01 MeV : (n,t5) + 32 MT = 749 Q = -1.40253E+01 MeV Emin = 1.45000E+01 MeV : (n,t) to continuum + 33 MT = 750 Q = -1.39069E+01 MeV Emin = 1.50000E+01 MeV : (n,He-3) to ground state + 34 MT = 751 Q = -1.51151E+01 MeV Emin = 1.54620E+01 MeV : (n,He-3_1) + 35 MT = 752 Q = -1.63219E+01 MeV Emin = 1.70000E+01 MeV : (n,He-3_2) + 36 MT = 800 Q = -2.75541E+00 MeV Emin = 3.60000E+00 MeV : (n,alpha) to ground state + 37 MT = 801 Q = -2.92271E+00 MeV Emin = 3.80000E+00 MeV : (n,a1) + 38 MT = 802 Q = -3.27141E+00 MeV Emin = 4.00000E+00 MeV : (n,a2) + 39 MT = 803 Q = -3.79011E+00 MeV Emin = 4.60000E+00 MeV : (n,a3) + 40 MT = 804 Q = -4.10942E+00 MeV Emin = 5.00000E+00 MeV : (n,a4) + 41 MT = 805 Q = -4.39042E+00 MeV Emin = 5.20000E+00 MeV : (n,a5) + 42 MT = 806 Q = -4.62441E+00 MeV Emin = 5.40000E+00 MeV : (n,a6) + 43 MT = 807 Q = -4.74042E+00 MeV Emin = 5.60000E+00 MeV : (n,a7) + 44 MT = 808 Q = -5.07642E+00 MeV Emin = 6.00000E+00 MeV : (n,a8) + 45 MT = 809 Q = -5.15372E+00 MeV Emin = 6.00000E+00 MeV : (n,a9) + 46 MT = 810 Q = -5.32442E+00 MeV Emin = 6.20000E+00 MeV : (n,a10) + 47 MT = 849 Q = -5.32442E+00 MeV Emin = 7.00000E+00 MeV : (n,alpha) to continuum + 48 MT = 4 Q = 0.00000E+00 MeV Emin = 1.14180E+00 MeV : total inelastic scattering + + Nuclide 40 / 1657 : 21045.82c -- scandium 45 (Sc-45) + + Pointers : 214163 32437 + Primary type : Transport + Nuclide ZAI : 210450 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Sc45.ACE + Atomic weight (AW) : 44.95591 + Atomic weight ratio (AWR) : 44.56972 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+02 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 39 reaction channels + - 52 special reactions + - 16 transmutation reactions + - 17 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 39 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 5 Q = 0.00000E+00 MeV Emin = 9.98750E-02 MeV frac = 1.00000E+00 Product nuclide = self : anything + 3 MT = 16 Q = -1.13248E+01 MeV Emin = 1.15789E+01 MeV frac = 1.00000E+00 Product nuclide = 210440 : (n,2n) + 4 MT = 22 Q = -7.93538E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 19041.82c : (n,nalpha) + 5 MT = 28 Q = -6.88922E+00 MeV Emin = 7.20000E+00 MeV frac = 1.00000E+00 Product nuclide = 20044.82c : (n,np) + 6 MT = 32 Q = -1.57966E+01 MeV Emin = 1.61510E+01 MeV frac = 1.00000E+00 Product nuclide = 20043.82c : (n,nd) + 7 MT = 33 Q = -1.74724E+01 MeV Emin = 1.80000E+01 MeV frac = 1.00000E+00 Product nuclide = 20042.82c : (n,nt) + 8 MT = 41 Q = -1.80212E+01 MeV Emin = 1.84256E+01 MeV frac = 1.00000E+00 Product nuclide = 20043.82c : (n,2np) + 9 MT = 51 Q = -1.24000E-02 MeV Emin = 1.26259E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 10 MT = 52 Q = -3.76500E-01 MeV Emin = 3.72474E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 11 MT = 53 Q = -5.43060E-01 MeV Emin = 5.41325E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 12 MT = 54 Q = -7.20120E-01 MeV Emin = 7.18100E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 13 MT = 55 Q = -9.39240E-01 MeV Emin = 9.30050E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 14 MT = 56 Q = -9.74380E-01 MeV Emin = 9.78278E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 15 MT = 57 Q = -1.06760E+00 MeV Emin = 1.09100E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 16 MT = 58 Q = -1.23670E+00 MeV Emin = 1.23826E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 17 MT = 59 Q = -1.30318E+00 MeV Emin = 1.33200E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 18 MT = 60 Q = -1.40887E+00 MeV Emin = 1.44000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 19 MT = 61 Q = -1.43348E+00 MeV Emin = 1.45601E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 20 MT = 62 Q = -1.47250E+00 MeV Emin = 1.50234E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 21 MT = 63 Q = -1.55620E+00 MeV Emin = 1.57987E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 22 MT = 64 Q = -1.66200E+00 MeV Emin = 1.68353E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 23 MT = 65 Q = -1.71600E+00 MeV Emin = 1.73725E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 24 MT = 66 Q = -1.80000E+00 MeV Emin = 1.83000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 25 MT = 67 Q = -1.90070E+00 MeV Emin = 1.93658E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 26 MT = 68 Q = -1.93060E+00 MeV Emin = 1.96914E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 27 MT = 69 Q = -1.93550E+00 MeV Emin = 1.97643E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 28 MT = 70 Q = -1.93550E+00 MeV Emin = 1.97643E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 29 MT = 91 Q = -1.93550E+00 MeV Emin = 1.97643E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 30 MT = 102 Q = 8.76062E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 210460 : (n,gamma) + 31 MT = 103 Q = 5.25545E-01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 200450 : (n,p) + 32 MT = 104 Q = -4.66465E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 20044.82c : (n,d) + 33 MT = 105 Q = -9.53937E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 20043.82c : (n,t) + 34 MT = 106 Q = -1.13362E+01 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 190430 : (n,He-3) + 35 MT = 107 Q = -4.01608E-01 MeV Emin = 1.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 190420 : (n,alpha) + 36 MT = 108 Q = -8.04986E+00 MeV Emin = 1.15000E+01 MeV frac = 1.00000E+00 Product nuclide = 170380 : (n,2alpha) + 37 MT = 111 Q = -1.17657E+01 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 190440 : (n,2p) + 38 MT = 112 Q = -9.64464E+00 MeV Emin = 1.15000E+01 MeV frac = 1.00000E+00 Product nuclide = 180410 : (n,palpha) + 39 MT = 117 Q = -1.35188E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 18040.82c : (n,dalpha) + + 17 additional transport branches: + + 1 MT = 22 Q = -7.93538E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -6.88922E+00 MeV Emin = 7.20000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.57966E+01 MeV Emin = 1.61510E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.74724E+01 MeV Emin = 1.80000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 41 Q = -1.80212E+01 MeV Emin = 1.84256E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,2np) + 6 MT = 102 Q = 8.76062E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 210461 : (n,gamma) + 7 MT = 103 Q = 5.25545E-01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 8 MT = 104 Q = -4.66465E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 9 MT = 105 Q = -9.53937E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 10 MT = 106 Q = -1.13362E+01 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 11 MT = 107 Q = -4.01608E-01 MeV Emin = 1.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 12 MT = 108 Q = -8.04986E+00 MeV Emin = 1.15000E+01 MeV frac = 2.00000E+00 Product nuclide = 2004.82c : (n,2alpha) + 13 MT = 111 Q = -1.17657E+01 MeV Emin = 1.25000E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + 14 MT = 112 Q = -9.64464E+00 MeV Emin = 1.15000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,palpha) + 15 MT = 112 Q = -9.64464E+00 MeV Emin = 1.15000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,palpha) + 16 MT = 117 Q = -1.35188E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,dalpha) + 17 MT = 117 Q = -1.35188E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,dalpha) + + 52 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.00000E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.25000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.60000E+00 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 600 Q = 5.25545E-01 MeV Emin = 1.00000E-11 MeV : (n,p) to ground state + 8 MT = 601 Q = 3.51279E-01 MeV Emin = 1.00000E-11 MeV : (n,p1) + 9 MT = 602 Q = -9.09165E-01 MeV Emin = 1.17289E+00 MeV : (n,p2) + 10 MT = 603 Q = -1.02882E+00 MeV Emin = 1.17289E+00 MeV : (n,p3) + 11 MT = 604 Q = -1.03245E+00 MeV Emin = 1.17289E+00 MeV : (n,p4) + 12 MT = 605 Q = -1.05845E+00 MeV Emin = 1.20000E+00 MeV : (n,p5) + 13 MT = 606 Q = -1.35436E+00 MeV Emin = 1.59556E+00 MeV : (n,p6) + 14 MT = 607 Q = -1.35885E+00 MeV Emin = 1.59556E+00 MeV : (n,p7) + 15 MT = 608 Q = -1.37432E+00 MeV Emin = 1.59556E+00 MeV : (n,p8) + 16 MT = 609 Q = -1.41464E+00 MeV Emin = 1.59556E+00 MeV : (n,p9) + 17 MT = 610 Q = -1.44745E+00 MeV Emin = 1.59556E+00 MeV : (n,p10) + 18 MT = 649 Q = -1.44745E+00 MeV Emin = 1.78578E+00 MeV : (n,p) to continuum + 19 MT = 650 Q = -4.66465E+00 MeV Emin = 5.00000E+00 MeV : (n,d) to ground state + 20 MT = 651 Q = -5.82170E+00 MeV Emin = 5.95232E+00 MeV : (n,d1) + 21 MT = 652 Q = -6.54816E+00 MeV Emin = 6.69508E+00 MeV : (n,d2) + 22 MT = 653 Q = -6.94779E+00 MeV Emin = 7.20000E+00 MeV : (n,d3) + 23 MT = 654 Q = -7.32115E+00 MeV Emin = 7.60000E+00 MeV : (n,d4) + 24 MT = 655 Q = -7.70898E+00 MeV Emin = 7.88195E+00 MeV : (n,d5) + 25 MT = 699 Q = -7.70898E+00 MeV Emin = 8.00000E+00 MeV : (n,d) to continuum + 26 MT = 700 Q = -9.53937E+00 MeV Emin = 1.00000E+01 MeV : (n,t) to ground state + 27 MT = 701 Q = -9.91213E+00 MeV Emin = 1.01345E+01 MeV : (n,t1) + 28 MT = 702 Q = -1.01328E+01 MeV Emin = 1.05000E+01 MeV : (n,t2) + 29 MT = 703 Q = -1.05296E+01 MeV Emin = 1.07659E+01 MeV : (n,t3) + 30 MT = 704 Q = -1.09338E+01 MeV Emin = 1.11792E+01 MeV : (n,t4) + 31 MT = 705 Q = -1.12172E+01 MeV Emin = 1.15000E+01 MeV : (n,t5) + 32 MT = 749 Q = -1.12172E+01 MeV Emin = 1.20000E+01 MeV : (n,t) to continuum + 33 MT = 750 Q = -1.13362E+01 MeV Emin = 1.25000E+01 MeV : (n,He-3) to ground state + 34 MT = 751 Q = -1.18974E+01 MeV Emin = 1.30000E+01 MeV : (n,He-3_1) + 35 MT = 752 Q = -1.20743E+01 MeV Emin = 1.30000E+01 MeV : (n,He-3_2) + 36 MT = 753 Q = -1.23112E+01 MeV Emin = 1.35000E+01 MeV : (n,He-3_3) + 37 MT = 754 Q = -1.24465E+01 MeV Emin = 1.35000E+01 MeV : (n,He-3_4) + 38 MT = 755 Q = -1.25431E+01 MeV Emin = 1.35000E+01 MeV : (n,He-3_5) + 39 MT = 799 Q = -1.25431E+01 MeV Emin = 1.40000E+01 MeV : (n,He-3) to continuum + 40 MT = 800 Q = -4.01608E-01 MeV Emin = 1.60000E+00 MeV : (n,alpha) to ground state + 41 MT = 801 Q = -5.08436E-01 MeV Emin = 1.64950E+00 MeV : (n,a1) + 42 MT = 802 Q = -6.59869E-01 MeV Emin = 1.81000E+00 MeV : (n,a2) + 43 MT = 803 Q = -1.04033E+00 MeV Emin = 2.00000E+00 MeV : (n,a3) + 44 MT = 804 Q = -1.08355E+00 MeV Emin = 2.00000E+00 MeV : (n,a4) + 45 MT = 805 Q = -1.10069E+00 MeV Emin = 2.00000E+00 MeV : (n,a5) + 46 MT = 806 Q = -1.18548E+00 MeV Emin = 2.00000E+00 MeV : (n,a6) + 47 MT = 807 Q = -1.24355E+00 MeV Emin = 2.00000E+00 MeV : (n,a7) + 48 MT = 808 Q = -1.51236E+00 MeV Emin = 2.40000E+00 MeV : (n,a8) + 49 MT = 809 Q = -1.54520E+00 MeV Emin = 2.40000E+00 MeV : (n,a9) + 50 MT = 810 Q = -1.59951E+00 MeV Emin = 2.40000E+00 MeV : (n,a10) + 51 MT = 849 Q = -1.59951E+00 MeV Emin = 2.80000E+00 MeV : (n,alpha) to continuum + 52 MT = 4 Q = 0.00000E+00 MeV Emin = 1.26259E-02 MeV : total inelastic scattering + + Nuclide 41 / 1657 : 22046.82c -- titanium 46 (Ti-46) + + Pointers : 228374 35289 + Primary type : Transport + Nuclide ZAI : 220460 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ti46.ACE + Atomic weight (AW) : 45.95276 + Atomic weight ratio (AWR) : 45.55800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 32 reaction channels + - 52 special reactions + - 10 transmutation reactions + - 8 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 32 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.31897E+01 MeV Emin = 1.34793E+01 MeV frac = 1.00000E+00 Product nuclide = 220450 : (n,2n) + 3 MT = 22 Q = -8.00348E+00 MeV Emin = 8.17920E+00 MeV frac = 1.00000E+00 Product nuclide = 20042.82c : (n,nalpha) + 4 MT = 28 Q = -1.03450E+01 MeV Emin = 1.05721E+01 MeV frac = 1.00000E+00 Product nuclide = 21045.82c : (n,np) + 5 MT = 51 Q = -8.89290E-01 MeV Emin = 9.07910E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -2.00990E+00 MeV Emin = 2.05402E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -2.61100E+00 MeV Emin = 2.66831E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -2.96180E+00 MeV Emin = 3.02681E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -3.05860E+00 MeV Emin = 3.12574E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -3.16818E+00 MeV Emin = 3.23772E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -3.21300E+00 MeV Emin = 3.28353E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -3.23570E+00 MeV Emin = 3.30673E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -3.29900E+00 MeV Emin = 3.37141E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -3.33800E+00 MeV Emin = 3.41127E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -3.44120E+00 MeV Emin = 3.51674E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -3.56940E+00 MeV Emin = 3.64775E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 63 Q = -3.57170E+00 MeV Emin = 3.65010E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 18 MT = 64 Q = -3.58200E+00 MeV Emin = 3.66063E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 19 MT = 65 Q = -3.60800E+00 MeV Emin = 3.68720E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 20 MT = 66 Q = -3.67700E+00 MeV Emin = 3.75771E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 21 MT = 67 Q = -3.69600E+00 MeV Emin = 3.77713E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 22 MT = 68 Q = -3.72390E+00 MeV Emin = 3.80564E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 23 MT = 69 Q = -3.73100E+00 MeV Emin = 3.81290E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 24 MT = 70 Q = -3.73790E+00 MeV Emin = 3.81995E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 25 MT = 91 Q = -3.73790E+00 MeV Emin = 3.81995E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 26 MT = 102 Q = 8.51370E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 22047.82c : (n,gamma) + 27 MT = 103 Q = -1.58500E+00 MeV Emin = 1.79700E+00 MeV frac = 1.00000E+00 Product nuclide = 210460 : (n,p) + 28 MT = 104 Q = -8.12040E+00 MeV Emin = 8.29864E+00 MeV frac = 1.00000E+00 Product nuclide = 21045.82c : (n,d) + 29 MT = 105 Q = -1.31890E+01 MeV Emin = 1.34785E+01 MeV frac = 1.00000E+00 Product nuclide = 210440 : (n,t) + 30 MT = 106 Q = -9.51780E+00 MeV Emin = 9.72672E+00 MeV frac = 1.00000E+00 Product nuclide = 20044.82c : (n,He-3) + 31 MT = 107 Q = -7.07340E-02 MeV Emin = 7.22009E-02 MeV frac = 1.00000E+00 Product nuclide = 20043.82c : (n,alpha) + 32 MT = 111 Q = -9.81940E+00 MeV Emin = 1.00350E+01 MeV frac = 1.00000E+00 Product nuclide = 200450 : (n,2p) + + 8 additional transport branches: + + 1 MT = 22 Q = -8.00348E+00 MeV Emin = 8.17920E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.03450E+01 MeV Emin = 1.05721E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -1.58500E+00 MeV Emin = 1.79700E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -8.12040E+00 MeV Emin = 8.29864E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -1.31890E+01 MeV Emin = 1.34785E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 106 Q = -9.51780E+00 MeV Emin = 9.72672E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 7 MT = 107 Q = -7.07340E-02 MeV Emin = 7.22009E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 8 MT = 111 Q = -9.81940E+00 MeV Emin = 1.00350E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 52 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.79700E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.29864E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.34785E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 9.72672E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 7.22009E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 4.09510E-04 MeV : damage-energy production + 7 MT = 600 Q = -1.58440E+00 MeV Emin = 1.79700E+00 MeV : (n,p) to ground state + 8 MT = 601 Q = -1.63640E+00 MeV Emin = 1.80000E+00 MeV : (n,p1) + 9 MT = 602 Q = -1.72690E+00 MeV Emin = 1.99900E+00 MeV : (n,p2) + 10 MT = 603 Q = -1.81210E+00 MeV Emin = 1.99900E+00 MeV : (n,p3) + 11 MT = 604 Q = -1.86510E+00 MeV Emin = 2.20000E+00 MeV : (n,p4) + 12 MT = 605 Q = -1.87390E+00 MeV Emin = 2.20000E+00 MeV : (n,p5) + 13 MT = 606 Q = -2.02850E+00 MeV Emin = 2.20000E+00 MeV : (n,p6) + 14 MT = 607 Q = -2.16910E+00 MeV Emin = 2.40000E+00 MeV : (n,p7) + 15 MT = 608 Q = -2.21180E+00 MeV Emin = 2.40000E+00 MeV : (n,p8) + 16 MT = 609 Q = -2.35840E+00 MeV Emin = 2.60000E+00 MeV : (n,p9) + 17 MT = 610 Q = -2.41940E+00 MeV Emin = 2.60000E+00 MeV : (n,p10) + 18 MT = 649 Q = -2.41940E+00 MeV Emin = 2.47260E+00 MeV : (n,p) to continuum + 19 MT = 650 Q = -8.12040E+00 MeV Emin = 8.29864E+00 MeV : (n,d) to ground state + 20 MT = 651 Q = -8.13280E+00 MeV Emin = 8.31132E+00 MeV : (n,d1) + 21 MT = 652 Q = -8.49690E+00 MeV Emin = 8.68341E+00 MeV : (n,d2) + 22 MT = 653 Q = -8.66350E+00 MeV Emin = 8.85366E+00 MeV : (n,d3) + 23 MT = 654 Q = -8.84050E+00 MeV Emin = 9.03460E+00 MeV : (n,d4) + 24 MT = 655 Q = -9.05960E+00 MeV Emin = 9.25850E+00 MeV : (n,d5) + 25 MT = 699 Q = -9.05960E+00 MeV Emin = 9.25850E+00 MeV : (n,d) to continuum + 26 MT = 700 Q = -1.31880E+01 MeV Emin = 1.34780E+01 MeV : (n,t) to ground state + 27 MT = 701 Q = -1.32560E+01 MeV Emin = 1.35470E+01 MeV : (n,t1) + 28 MT = 702 Q = -1.33340E+01 MeV Emin = 1.37490E+01 MeV : (n,t2) + 29 MT = 703 Q = -1.34230E+01 MeV Emin = 1.37490E+01 MeV : (n,t3) + 30 MT = 704 Q = -1.34590E+01 MeV Emin = 1.37550E+01 MeV : (n,t4) + 31 MT = 705 Q = -1.35380E+01 MeV Emin = 1.38352E+01 MeV : (n,t5) + 32 MT = 749 Q = -1.35380E+01 MeV Emin = 1.38352E+01 MeV : (n,t) to continuum + 33 MT = 750 Q = -9.51610E+00 MeV Emin = 9.72500E+00 MeV : (n,He-3) to ground state + 34 MT = 751 Q = -1.06730E+01 MeV Emin = 1.09080E+01 MeV : (n,He-3_1) + 35 MT = 752 Q = -1.14000E+01 MeV Emin = 1.16502E+01 MeV : (n,He-3_2) + 36 MT = 753 Q = -1.17990E+01 MeV Emin = 1.20580E+01 MeV : (n,He-3_3) + 37 MT = 754 Q = -1.21730E+01 MeV Emin = 1.24402E+01 MeV : (n,He-3_4) + 38 MT = 755 Q = -1.25610E+01 MeV Emin = 1.28367E+01 MeV : (n,He-3_5) + 39 MT = 799 Q = -1.25610E+01 MeV Emin = 1.28367E+01 MeV : (n,He-3) to continuum + 40 MT = 800 Q = -7.04850E-02 MeV Emin = 7.19549E-02 MeV : (n,alpha) to ground state + 41 MT = 801 Q = -4.43250E-01 MeV Emin = 4.50000E-01 MeV : (n,a1) + 42 MT = 802 Q = -6.63880E-01 MeV Emin = 6.77800E-01 MeV : (n,a2) + 43 MT = 803 Q = -1.06070E+00 MeV Emin = 1.08350E+00 MeV : (n,a3) + 44 MT = 804 Q = -1.46500E+00 MeV Emin = 1.49308E+00 MeV : (n,a4) + 45 MT = 805 Q = -1.74830E+00 MeV Emin = 1.78450E+00 MeV : (n,a5) + 46 MT = 806 Q = -1.97230E+00 MeV Emin = 2.01560E+00 MeV : (n,a6) + 47 MT = 807 Q = -2.00180E+00 MeV Emin = 2.04574E+00 MeV : (n,a7) + 48 MT = 808 Q = -2.02790E+00 MeV Emin = 2.07241E+00 MeV : (n,a8) + 49 MT = 809 Q = -2.11670E+00 MeV Emin = 2.16320E+00 MeV : (n,a9) + 50 MT = 810 Q = -2.13780E+00 MeV Emin = 2.18473E+00 MeV : (n,a10) + 51 MT = 849 Q = -2.13780E+00 MeV Emin = 2.18473E+00 MeV : (n,alpha) to continuum + 52 MT = 4 Q = 0.00000E+00 MeV Emin = 9.07910E-01 MeV : total inelastic scattering + + Nuclide 42 / 1657 : 22047.82c -- titanium 47 (Ti-47) + + Pointers : 235201 35335 + Primary type : Transport + Nuclide ZAI : 220470 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ti47.ACE + Atomic weight (AW) : 46.95134 + Atomic weight ratio (AWR) : 46.54800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 32 reaction channels + - 52 special reactions + - 10 transmutation reactions + - 8 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 32 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.87770E+00 MeV Emin = 9.06842E+00 MeV frac = 1.00000E+00 Product nuclide = 22046.82c : (n,2n) + 3 MT = 22 Q = -8.94820E+00 MeV Emin = 9.14044E+00 MeV frac = 1.00000E+00 Product nuclide = 20043.82c : (n,nalpha) + 4 MT = 28 Q = -1.04620E+01 MeV Emin = 1.06870E+01 MeV frac = 1.00000E+00 Product nuclide = 210460 : (n,np) + 5 MT = 51 Q = -1.59380E-01 MeV Emin = 1.62320E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -1.25060E+00 MeV Emin = 1.27632E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -1.25210E+00 MeV Emin = 1.27844E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -1.44425E+00 MeV Emin = 1.47300E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -1.54980E+00 MeV Emin = 1.58154E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -1.67000E+00 MeV Emin = 1.70200E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -1.79390E+00 MeV Emin = 1.82700E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -1.82500E+00 MeV Emin = 1.86000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -2.16320E+00 MeV Emin = 2.20967E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -2.16670E+00 MeV Emin = 2.21325E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -2.25950E+00 MeV Emin = 2.30804E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -2.29710E+00 MeV Emin = 2.34645E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 63 Q = -2.34400E+00 MeV Emin = 2.39436E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 18 MT = 64 Q = -2.36490E+00 MeV Emin = 2.41571E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 19 MT = 65 Q = -2.40620E+00 MeV Emin = 2.45789E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 20 MT = 66 Q = -2.41630E+00 MeV Emin = 2.46821E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 21 MT = 67 Q = -2.49940E+00 MeV Emin = 2.55310E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 22 MT = 68 Q = -2.52000E+00 MeV Emin = 2.57414E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 23 MT = 69 Q = -2.52580E+00 MeV Emin = 2.58006E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 24 MT = 70 Q = -2.54820E+00 MeV Emin = 2.60294E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 25 MT = 91 Q = -2.54820E+00 MeV Emin = 2.60294E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 26 MT = 102 Q = 1.16266E+01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 22048.82c : (n,gamma) + 27 MT = 103 Q = 1.82252E-01 MeV Emin = 6.59300E-01 MeV frac = 1.00000E+00 Product nuclide = 210470 : (n,p) + 28 MT = 104 Q = -8.23749E+00 MeV Emin = 8.41450E+00 MeV frac = 1.00000E+00 Product nuclide = 210460 : (n,d) + 29 MT = 105 Q = -1.07410E+01 MeV Emin = 1.09718E+01 MeV frac = 1.00000E+00 Product nuclide = 21045.82c : (n,t) + 30 MT = 106 Q = -1.09790E+01 MeV Emin = 1.12200E+01 MeV frac = 1.00000E+00 Product nuclide = 200450 : (n,He-3) + 31 MT = 107 Q = 2.18380E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 20044.82c : (n,alpha) + 32 MT = 111 Q = -8.30340E+00 MeV Emin = 8.48180E+00 MeV frac = 1.00000E+00 Product nuclide = 200460 : (n,2p) + + 8 additional transport branches: + + 1 MT = 22 Q = -8.94820E+00 MeV Emin = 9.14044E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.04620E+01 MeV Emin = 1.06870E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = 1.82252E-01 MeV Emin = 6.59300E-01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -8.23749E+00 MeV Emin = 8.41450E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -1.07410E+01 MeV Emin = 1.09718E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 106 Q = -1.09790E+01 MeV Emin = 1.12200E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 7 MT = 107 Q = 2.18380E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 8 MT = 111 Q = -8.30340E+00 MeV Emin = 8.48180E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 52 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 6.59300E-01 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.41450E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.09718E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.12200E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 600 Q = 1.82250E-01 MeV Emin = 6.59300E-01 MeV : (n,p) to ground state + 8 MT = 601 Q = -5.84580E-01 MeV Emin = 8.79822E-01 MeV : (n,p1) + 9 MT = 602 Q = -6.25640E-01 MeV Emin = 8.79881E-01 MeV : (n,p2) + 10 MT = 603 Q = -9.40750E-01 MeV Emin = 1.19969E+00 MeV : (n,p3) + 11 MT = 604 Q = -9.62750E-01 MeV Emin = 1.19969E+00 MeV : (n,p4) + 12 MT = 605 Q = -9.64740E-01 MeV Emin = 1.19984E+00 MeV : (n,p5) + 13 MT = 606 Q = -1.11490E+00 MeV Emin = 1.39900E+00 MeV : (n,p6) + 14 MT = 607 Q = -1.13380E+00 MeV Emin = 1.39900E+00 MeV : (n,p7) + 15 MT = 608 Q = -1.20910E+00 MeV Emin = 1.39900E+00 MeV : (n,p8) + 16 MT = 609 Q = -1.22220E+00 MeV Emin = 1.39900E+00 MeV : (n,p9) + 17 MT = 610 Q = -1.45670E+00 MeV Emin = 1.59900E+00 MeV : (n,p10) + 18 MT = 649 Q = -1.45670E+00 MeV Emin = 1.48750E+00 MeV : (n,p) to continuum + 19 MT = 650 Q = -8.23750E+00 MeV Emin = 8.41450E+00 MeV : (n,d) to ground state + 20 MT = 651 Q = -8.28950E+00 MeV Emin = 8.46760E+00 MeV : (n,d1) + 21 MT = 652 Q = -8.38000E+00 MeV Emin = 8.56010E+00 MeV : (n,d2) + 22 MT = 653 Q = -8.46530E+00 MeV Emin = 8.64716E+00 MeV : (n,d3) + 23 MT = 654 Q = -8.51820E+00 MeV Emin = 9.00000E+00 MeV : (n,d4) + 24 MT = 655 Q = -8.52700E+00 MeV Emin = 9.00000E+00 MeV : (n,d5) + 25 MT = 699 Q = -8.52700E+00 MeV Emin = 8.71020E+00 MeV : (n,d) to continuum + 26 MT = 700 Q = -1.07410E+01 MeV Emin = 1.10000E+01 MeV : (n,t) to ground state + 27 MT = 701 Q = -1.07530E+01 MeV Emin = 1.10000E+01 MeV : (n,t1) + 28 MT = 702 Q = -1.11170E+01 MeV Emin = 1.13560E+01 MeV : (n,t2) + 29 MT = 703 Q = -1.12840E+01 MeV Emin = 1.15264E+01 MeV : (n,t3) + 30 MT = 704 Q = -1.14610E+01 MeV Emin = 1.20000E+01 MeV : (n,t4) + 31 MT = 705 Q = -1.16800E+01 MeV Emin = 1.20000E+01 MeV : (n,t5) + 32 MT = 749 Q = -1.16800E+01 MeV Emin = 1.19310E+01 MeV : (n,t) to continuum + 33 MT = 750 Q = -1.09790E+01 MeV Emin = 1.12150E+01 MeV : (n,He-3) to ground state + 34 MT = 751 Q = -1.11530E+01 MeV Emin = 1.13930E+01 MeV : (n,He-3_1) + 35 MT = 752 Q = -1.24140E+01 MeV Emin = 1.26810E+01 MeV : (n,He-3_2) + 36 MT = 753 Q = -1.25340E+01 MeV Emin = 1.28033E+01 MeV : (n,He-3_3) + 37 MT = 754 Q = -1.25370E+01 MeV Emin = 1.28063E+01 MeV : (n,He-3_4) + 38 MT = 755 Q = -1.25630E+01 MeV Emin = 1.28330E+01 MeV : (n,He-3_5) + 39 MT = 799 Q = -1.25630E+01 MeV Emin = 1.28330E+01 MeV : (n,He-3) to continuum + 40 MT = 800 Q = 2.18377E+00 MeV Emin = 1.00000E-11 MeV : (n,alpha) to ground state + 41 MT = 801 Q = 1.02672E+00 MeV Emin = 1.00000E-11 MeV : (n,a1) + 42 MT = 802 Q = 3.00255E-01 MeV Emin = 1.02050E+00 MeV : (n,a2) + 43 MT = 803 Q = -9.93745E-02 MeV Emin = 1.38288E+00 MeV : (n,a3) + 44 MT = 804 Q = -4.72735E-01 MeV Emin = 1.79700E+00 MeV : (n,a4) + 45 MT = 805 Q = -8.60564E-01 MeV Emin = 2.00000E+00 MeV : (n,a5) + 46 MT = 806 Q = -1.10123E+00 MeV Emin = 2.00000E+00 MeV : (n,a6) + 47 MT = 807 Q = -1.11753E+00 MeV Emin = 2.00000E+00 MeV : (n,a7) + 48 MT = 808 Q = -1.12409E+00 MeV Emin = 2.00000E+00 MeV : (n,a8) + 49 MT = 809 Q = -1.17343E+00 MeV Emin = 2.00000E+00 MeV : (n,a9) + 50 MT = 810 Q = -1.39663E+00 MeV Emin = 2.40000E+00 MeV : (n,a10) + 51 MT = 849 Q = -1.39663E+00 MeV Emin = 1.42645E+00 MeV : (n,alpha) to continuum + 52 MT = 4 Q = 0.00000E+00 MeV Emin = 1.62320E-01 MeV : total inelastic scattering + + Nuclide 43 / 1657 : 22048.82c -- titanium 48 (Ti-48) + + Pointers : 242028 35381 + Primary type : Transport + Nuclide ZAI : 220480 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ti48.ACE + Atomic weight (AW) : 47.94795 + Atomic weight ratio (AWR) : 47.53605 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 32 reaction channels + - 52 special reactions + - 10 transmutation reactions + - 8 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 32 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.16270E+01 MeV Emin = 1.18716E+01 MeV frac = 1.00000E+00 Product nuclide = 22047.82c : (n,2n) + 3 MT = 22 Q = -9.44280E+00 MeV Emin = 9.64150E+00 MeV frac = 1.00000E+00 Product nuclide = 20044.82c : (n,nalpha) + 4 MT = 28 Q = -1.14440E+01 MeV Emin = 1.16850E+01 MeV frac = 1.00000E+00 Product nuclide = 210470 : (n,np) + 5 MT = 51 Q = -9.83520E-01 MeV Emin = 1.00200E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -2.29560E+00 MeV Emin = 2.34390E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -2.42100E+00 MeV Emin = 2.47200E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -2.46500E+00 MeV Emin = 2.51690E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -2.99720E+00 MeV Emin = 3.06025E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -3.06200E+00 MeV Emin = 3.12642E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -3.22390E+00 MeV Emin = 3.29172E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -3.23970E+00 MeV Emin = 3.30790E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -3.33320E+00 MeV Emin = 3.40332E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -3.35880E+00 MeV Emin = 3.42950E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -3.37080E+00 MeV Emin = 3.44180E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -3.50850E+00 MeV Emin = 3.58240E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 63 Q = -3.61680E+00 MeV Emin = 3.69290E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 18 MT = 64 Q = -3.63300E+00 MeV Emin = 3.70943E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 19 MT = 65 Q = -3.69950E+00 MeV Emin = 3.77733E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 20 MT = 66 Q = -3.71100E+00 MeV Emin = 3.78910E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 21 MT = 67 Q = -3.73850E+00 MeV Emin = 3.81720E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 22 MT = 68 Q = -3.78240E+00 MeV Emin = 3.86200E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 23 MT = 69 Q = -3.80280E+00 MeV Emin = 3.88280E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 24 MT = 70 Q = -3.85200E+00 MeV Emin = 3.93303E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 25 MT = 91 Q = -3.85200E+00 MeV Emin = 3.93303E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 26 MT = 102 Q = 8.14240E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 22049.82c : (n,gamma) + 27 MT = 103 Q = -3.21180E+00 MeV Emin = 3.27940E+00 MeV frac = 1.00000E+00 Product nuclide = 210480 : (n,p) + 28 MT = 104 Q = -9.21980E+00 MeV Emin = 9.41376E+00 MeV frac = 1.00000E+00 Product nuclide = 210470 : (n,d) + 29 MT = 105 Q = -1.36070E+01 MeV Emin = 1.38933E+01 MeV frac = 1.00000E+00 Product nuclide = 210460 : (n,t) + 30 MT = 106 Q = -1.22120E+01 MeV Emin = 1.24690E+01 MeV frac = 1.00000E+00 Product nuclide = 200460 : (n,He-3) + 31 MT = 107 Q = -2.02810E+00 MeV Emin = 2.07077E+00 MeV frac = 1.00000E+00 Product nuclide = 200450 : (n,alpha) + 32 MT = 111 Q = -1.26540E+01 MeV Emin = 1.29202E+01 MeV frac = 1.00000E+00 Product nuclide = 200470 : (n,2p) + + 8 additional transport branches: + + 1 MT = 22 Q = -9.44280E+00 MeV Emin = 9.64150E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.14440E+01 MeV Emin = 1.16850E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -3.21180E+00 MeV Emin = 3.27940E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -9.21980E+00 MeV Emin = 9.41376E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -1.36070E+01 MeV Emin = 1.38933E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 106 Q = -1.22120E+01 MeV Emin = 1.24690E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 7 MT = 107 Q = -2.02810E+00 MeV Emin = 2.07077E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 8 MT = 111 Q = -1.26540E+01 MeV Emin = 1.29202E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 52 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.27940E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 9.41376E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.38933E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.24690E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 2.07077E+00 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 4.32133E-04 MeV : damage-energy production + 7 MT = 600 Q = -3.21180E+00 MeV Emin = 3.40000E+00 MeV : (n,p) to ground state + 8 MT = 601 Q = -3.34280E+00 MeV Emin = 3.60000E+00 MeV : (n,p1) + 9 MT = 602 Q = -3.46420E+00 MeV Emin = 3.80000E+00 MeV : (n,p2) + 10 MT = 603 Q = -3.59980E+00 MeV Emin = 3.80000E+00 MeV : (n,p3) + 11 MT = 604 Q = -3.83450E+00 MeV Emin = 4.20000E+00 MeV : (n,p4) + 12 MT = 605 Q = -4.30780E+00 MeV Emin = 4.39850E+00 MeV : (n,p5) + 13 MT = 606 Q = -4.35440E+00 MeV Emin = 4.60000E+00 MeV : (n,p6) + 14 MT = 607 Q = -4.61350E+00 MeV Emin = 4.71060E+00 MeV : (n,p7) + 15 MT = 608 Q = -4.64380E+00 MeV Emin = 4.80000E+00 MeV : (n,p8) + 16 MT = 609 Q = -5.10290E+00 MeV Emin = 5.21030E+00 MeV : (n,p9) + 17 MT = 610 Q = -5.27590E+00 MeV Emin = 5.40000E+00 MeV : (n,p10) + 18 MT = 649 Q = -5.27590E+00 MeV Emin = 5.38690E+00 MeV : (n,p) to continuum + 19 MT = 650 Q = -9.21980E+00 MeV Emin = 9.50000E+00 MeV : (n,d) to ground state + 20 MT = 651 Q = -9.98660E+00 MeV Emin = 1.01970E+01 MeV : (n,d1) + 21 MT = 652 Q = -1.00280E+01 MeV Emin = 1.05000E+01 MeV : (n,d2) + 22 MT = 653 Q = -1.03430E+01 MeV Emin = 1.05606E+01 MeV : (n,d3) + 23 MT = 654 Q = -1.03650E+01 MeV Emin = 1.05831E+01 MeV : (n,d4) + 24 MT = 655 Q = -1.03670E+01 MeV Emin = 1.05851E+01 MeV : (n,d5) + 25 MT = 699 Q = -1.03670E+01 MeV Emin = 1.05851E+01 MeV : (n,d) to continuum + 26 MT = 700 Q = -1.36070E+01 MeV Emin = 1.40000E+01 MeV : (n,t) to ground state + 27 MT = 701 Q = -1.36590E+01 MeV Emin = 1.40000E+01 MeV : (n,t1) + 28 MT = 702 Q = -1.37490E+01 MeV Emin = 1.40390E+01 MeV : (n,t2) + 29 MT = 703 Q = -1.38350E+01 MeV Emin = 1.45000E+01 MeV : (n,t3) + 30 MT = 704 Q = -1.38880E+01 MeV Emin = 1.45000E+01 MeV : (n,t4) + 31 MT = 705 Q = -1.38960E+01 MeV Emin = 1.45000E+01 MeV : (n,t5) + 32 MT = 749 Q = -1.38960E+01 MeV Emin = 1.41890E+01 MeV : (n,t) to continuum + 33 MT = 750 Q = -1.22120E+01 MeV Emin = 1.35000E+01 MeV : (n,He-3) to ground state + 34 MT = 751 Q = -1.35580E+01 MeV Emin = 1.40000E+01 MeV : (n,He-3_1) + 35 MT = 752 Q = -1.46350E+01 MeV Emin = 1.50000E+01 MeV : (n,He-3_2) + 36 MT = 753 Q = -1.47870E+01 MeV Emin = 1.60000E+01 MeV : (n,He-3_3) + 37 MT = 754 Q = -1.51860E+01 MeV Emin = 1.60000E+01 MeV : (n,He-3_4) + 38 MT = 755 Q = -1.52350E+01 MeV Emin = 1.60000E+01 MeV : (n,He-3_5) + 39 MT = 799 Q = -1.52350E+01 MeV Emin = 1.55555E+01 MeV : (n,He-3) to continuum + 40 MT = 800 Q = -2.02810E+00 MeV Emin = 3.00000E+00 MeV : (n,alpha) to ground state + 41 MT = 801 Q = -2.20230E+00 MeV Emin = 3.20000E+00 MeV : (n,a1) + 42 MT = 802 Q = -3.46280E+00 MeV Emin = 4.00000E+00 MeV : (n,a2) + 43 MT = 803 Q = -3.58240E+00 MeV Emin = 4.60000E+00 MeV : (n,a3) + 44 MT = 804 Q = -3.58610E+00 MeV Emin = 4.60000E+00 MeV : (n,a4) + 45 MT = 805 Q = -3.61210E+00 MeV Emin = 4.60000E+00 MeV : (n,a5) + 46 MT = 806 Q = -3.90800E+00 MeV Emin = 5.00000E+00 MeV : (n,a6) + 47 MT = 807 Q = -3.91250E+00 MeV Emin = 5.00000E+00 MeV : (n,a7) + 48 MT = 808 Q = -3.92790E+00 MeV Emin = 5.00000E+00 MeV : (n,a8) + 49 MT = 809 Q = -3.96830E+00 MeV Emin = 5.00000E+00 MeV : (n,a9) + 50 MT = 810 Q = -4.00110E+00 MeV Emin = 5.00000E+00 MeV : (n,a10) + 51 MT = 849 Q = -4.00110E+00 MeV Emin = 4.08527E+00 MeV : (n,alpha) to continuum + 52 MT = 4 Q = 0.00000E+00 MeV Emin = 1.00200E+00 MeV : total inelastic scattering + + Nuclide 44 / 1657 : 22049.82c -- titanium 49 (Ti-49) + + Pointers : 248855 35427 + Primary type : Transport + Nuclide ZAI : 220490 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ti49.ACE + Atomic weight (AW) : 48.94788 + Atomic weight ratio (AWR) : 48.52739 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 32 reaction channels + - 50 special reactions + - 10 transmutation reactions + - 8 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 32 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.14240E+00 MeV Emin = 8.31020E+00 MeV frac = 1.00000E+00 Product nuclide = 22048.82c : (n,2n) + 3 MT = 22 Q = -1.01700E+01 MeV Emin = 1.03800E+01 MeV frac = 1.00000E+00 Product nuclide = 200450 : (n,nalpha) + 4 MT = 28 Q = -1.13540E+01 MeV Emin = 1.15880E+01 MeV frac = 1.00000E+00 Product nuclide = 210480 : (n,np) + 5 MT = 51 Q = -1.38180E+00 MeV Emin = 1.40900E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -1.54215E+00 MeV Emin = 1.57250E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -1.58597E+00 MeV Emin = 1.61721E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -1.61000E+00 MeV Emin = 1.64041E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -1.62293E+00 MeV Emin = 1.65210E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -1.72347E+00 MeV Emin = 1.75850E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -1.76201E+00 MeV Emin = 1.79700E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -2.26130E+00 MeV Emin = 2.30790E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -2.47140E+00 MeV Emin = 2.52233E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -2.50444E+00 MeV Emin = 2.55605E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -2.50550E+00 MeV Emin = 2.55713E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -2.51337E+00 MeV Emin = 2.56516E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 63 Q = -2.52010E+00 MeV Emin = 2.57203E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 18 MT = 64 Q = -2.66434E+00 MeV Emin = 2.71924E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 19 MT = 65 Q = -2.72060E+00 MeV Emin = 2.77666E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 20 MT = 66 Q = -2.72130E+00 MeV Emin = 2.77738E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 21 MT = 67 Q = -2.98050E+00 MeV Emin = 3.04192E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 22 MT = 68 Q = -3.03868E+00 MeV Emin = 3.10130E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 23 MT = 69 Q = -3.04250E+00 MeV Emin = 3.10520E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 24 MT = 70 Q = -3.17529E+00 MeV Emin = 3.24072E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 25 MT = 91 Q = -3.17530E+00 MeV Emin = 3.24073E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 26 MT = 102 Q = 1.09391E+01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 22050.82c : (n,gamma) + 27 MT = 103 Q = -1.22280E+00 MeV Emin = 1.49900E+00 MeV frac = 1.00000E+00 Product nuclide = 210490 : (n,p) + 28 MT = 104 Q = -9.12960E+00 MeV Emin = 9.31780E+00 MeV frac = 1.00000E+00 Product nuclide = 210480 : (n,d) + 29 MT = 105 Q = -1.11050E+01 MeV Emin = 1.13338E+01 MeV frac = 1.00000E+00 Product nuclide = 210470 : (n,t) + 30 MT = 106 Q = -1.30780E+01 MeV Emin = 1.33500E+01 MeV frac = 1.00000E+00 Product nuclide = 200470 : (n,He-3) + 31 MT = 107 Q = 2.23280E-01 MeV Emin = 1.07400E+00 MeV frac = 1.00000E+00 Product nuclide = 200460 : (n,alpha) + 32 MT = 111 Q = -1.08500E+01 MeV Emin = 1.10740E+01 MeV frac = 1.00000E+00 Product nuclide = 200480 : (n,2p) + + 8 additional transport branches: + + 1 MT = 22 Q = -1.01700E+01 MeV Emin = 1.03800E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.13540E+01 MeV Emin = 1.15880E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -1.22280E+00 MeV Emin = 1.49900E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -9.12960E+00 MeV Emin = 9.31780E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -1.11050E+01 MeV Emin = 1.13338E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 106 Q = -1.30780E+01 MeV Emin = 1.33500E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 7 MT = 107 Q = 2.23280E-01 MeV Emin = 1.07400E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 8 MT = 111 Q = -1.08500E+01 MeV Emin = 1.10740E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 50 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.49900E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 9.31780E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.13338E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.33500E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.07400E+00 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 4.54755E-04 MeV : damage-energy production + 7 MT = 600 Q = -1.22340E+00 MeV Emin = 1.49900E+00 MeV : (n,p) to ground state + 8 MT = 601 Q = -3.45150E+00 MeV Emin = 3.52263E+00 MeV : (n,p1) + 9 MT = 602 Q = -3.59470E+00 MeV Emin = 3.66880E+00 MeV : (n,p2) + 10 MT = 603 Q = -4.30790E+00 MeV Emin = 4.39670E+00 MeV : (n,p3) + 11 MT = 604 Q = -4.52340E+00 MeV Emin = 4.61662E+00 MeV : (n,p4) + 12 MT = 605 Q = -4.73960E+00 MeV Emin = 4.83730E+00 MeV : (n,p5) + 13 MT = 606 Q = -4.77340E+00 MeV Emin = 5.00000E+00 MeV : (n,p6) + 14 MT = 607 Q = -4.80440E+00 MeV Emin = 5.00000E+00 MeV : (n,p7) + 15 MT = 608 Q = -4.97840E+00 MeV Emin = 5.08100E+00 MeV : (n,p8) + 16 MT = 609 Q = -5.03180E+00 MeV Emin = 5.13550E+00 MeV : (n,p9) + 17 MT = 610 Q = -5.14440E+00 MeV Emin = 5.25041E+00 MeV : (n,p10) + 18 MT = 649 Q = -5.14440E+00 MeV Emin = 5.25041E+00 MeV : (n,p) to continuum + 19 MT = 650 Q = -9.12960E+00 MeV Emin = 9.31780E+00 MeV : (n,d) to ground state + 20 MT = 651 Q = -9.26060E+00 MeV Emin = 9.45144E+00 MeV : (n,d1) + 21 MT = 652 Q = -9.38200E+00 MeV Emin = 9.57534E+00 MeV : (n,d2) + 22 MT = 653 Q = -9.51760E+00 MeV Emin = 9.71380E+00 MeV : (n,d3) + 23 MT = 654 Q = -9.75230E+00 MeV Emin = 1.00000E+01 MeV : (n,d4) + 24 MT = 655 Q = -1.02260E+01 MeV Emin = 1.05000E+01 MeV : (n,d5) + 25 MT = 699 Q = -1.02260E+01 MeV Emin = 1.04367E+01 MeV : (n,d) to continuum + 26 MT = 700 Q = -1.11050E+01 MeV Emin = 1.15000E+01 MeV : (n,t) to ground state + 27 MT = 701 Q = -1.18720E+01 MeV Emin = 1.21167E+01 MeV : (n,t1) + 28 MT = 702 Q = -1.19130E+01 MeV Emin = 1.25000E+01 MeV : (n,t2) + 29 MT = 703 Q = -1.22280E+01 MeV Emin = 1.25000E+01 MeV : (n,t3) + 30 MT = 704 Q = -1.22500E+01 MeV Emin = 1.25024E+01 MeV : (n,t4) + 31 MT = 705 Q = -1.22520E+01 MeV Emin = 1.25045E+01 MeV : (n,t5) + 32 MT = 749 Q = -1.22520E+01 MeV Emin = 1.25045E+01 MeV : (n,t) to continuum + 33 MT = 750 Q = -1.30780E+01 MeV Emin = 1.40000E+01 MeV : (n,He-3) to ground state + 34 MT = 751 Q = -1.50920E+01 MeV Emin = 1.54030E+01 MeV : (n,He-3_1) + 35 MT = 752 Q = -1.56570E+01 MeV Emin = 1.60000E+01 MeV : (n,He-3_2) + 36 MT = 753 Q = -1.56780E+01 MeV Emin = 1.70000E+01 MeV : (n,He-3_3) + 37 MT = 799 Q = -1.56780E+01 MeV Emin = 1.60011E+01 MeV : (n,He-3) to continuum + 38 MT = 800 Q = 2.23281E-01 MeV Emin = 1.07400E+00 MeV : (n,alpha) to ground state + 39 MT = 801 Q = -1.12272E+00 MeV Emin = 2.00000E+00 MeV : (n,a1) + 40 MT = 802 Q = -2.19982E+00 MeV Emin = 3.00000E+00 MeV : (n,a2) + 41 MT = 803 Q = -2.35142E+00 MeV Emin = 3.20000E+00 MeV : (n,a3) + 42 MT = 804 Q = -2.75062E+00 MeV Emin = 3.60000E+00 MeV : (n,a4) + 43 MT = 805 Q = -2.79932E+00 MeV Emin = 3.80000E+00 MeV : (n,a5) + 44 MT = 806 Q = -3.39072E+00 MeV Emin = 4.20000E+00 MeV : (n,a6) + 45 MT = 807 Q = -3.41562E+00 MeV Emin = 4.40000E+00 MeV : (n,a7) + 46 MT = 808 Q = -3.63642E+00 MeV Emin = 4.60000E+00 MeV : (n,a8) + 47 MT = 809 Q = -3.72872E+00 MeV Emin = 4.80000E+00 MeV : (n,a9) + 48 MT = 810 Q = -3.76472E+00 MeV Emin = 4.80000E+00 MeV : (n,a10) + 49 MT = 849 Q = -3.76472E+00 MeV Emin = 3.84230E+00 MeV : (n,alpha) to continuum + 50 MT = 4 Q = 0.00000E+00 MeV Emin = 1.40900E+00 MeV : total inelastic scattering + + Nuclide 45 / 1657 : 22050.82c -- titanium 50 (Ti-50) + + Pointers : 255536 35473 + Primary type : Transport + Nuclide ZAI : 220500 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ti50.ACE + Atomic weight (AW) : 49.94480 + Atomic weight ratio (AWR) : 49.51575 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 31 reaction channels + - 47 special reactions + - 9 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 31 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.09390E+01 MeV Emin = 1.11600E+01 MeV frac = 1.00000E+00 Product nuclide = 22049.82c : (n,2n) + 3 MT = 22 Q = -1.07160E+01 MeV Emin = 1.09324E+01 MeV frac = 1.00000E+00 Product nuclide = 200460 : (n,nalpha) + 4 MT = 28 Q = -1.21630E+01 MeV Emin = 1.24086E+01 MeV frac = 1.00000E+00 Product nuclide = 210490 : (n,np) + 5 MT = 51 Q = -1.55380E+00 MeV Emin = 1.58480E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -2.67490E+00 MeV Emin = 2.72892E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -3.19870E+00 MeV Emin = 3.26330E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -3.86279E+00 MeV Emin = 3.94080E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -3.86820E+00 MeV Emin = 3.94632E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -3.97490E+00 MeV Emin = 4.05518E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -4.14700E+00 MeV Emin = 4.23075E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -4.14719E+00 MeV Emin = 4.23095E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -4.17197E+00 MeV Emin = 4.25623E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -4.17250E+00 MeV Emin = 4.25677E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -4.30985E+00 MeV Emin = 4.39689E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -4.40999E+00 MeV Emin = 4.49905E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 63 Q = -4.48671E+00 MeV Emin = 4.57732E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 18 MT = 64 Q = -4.53600E+00 MeV Emin = 4.62761E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 19 MT = 65 Q = -4.57600E+00 MeV Emin = 4.66842E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 20 MT = 66 Q = -4.78995E+00 MeV Emin = 4.88669E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 21 MT = 67 Q = -4.88068E+00 MeV Emin = 4.97925E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 22 MT = 68 Q = -4.92800E+00 MeV Emin = 5.02752E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 23 MT = 69 Q = -4.94000E+00 MeV Emin = 5.03977E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 24 MT = 70 Q = -5.12500E+00 MeV Emin = 5.22850E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 25 MT = 91 Q = -5.12500E+00 MeV Emin = 5.22850E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 26 MT = 102 Q = 6.37680E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 220510 : (n,gamma) + 27 MT = 103 Q = -6.10610E+00 MeV Emin = 6.22950E+00 MeV frac = 1.00000E+00 Product nuclide = 210500 : (n,p) + 28 MT = 104 Q = -9.93800E+00 MeV Emin = 1.01390E+01 MeV frac = 1.00000E+00 Product nuclide = 210490 : (n,d) + 29 MT = 105 Q = -1.38120E+01 MeV Emin = 1.49200E+01 MeV frac = 1.00000E+00 Product nuclide = 210480 : (n,t) + 30 MT = 106 Q = -1.40710E+01 MeV Emin = 1.43600E+01 MeV frac = 1.00000E+00 Product nuclide = 200480 : (n,He-3) + 31 MT = 107 Q = -3.44390E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 200470 : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -1.07160E+01 MeV Emin = 1.09324E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.21630E+01 MeV Emin = 1.24086E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -6.10610E+00 MeV Emin = 6.22950E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -9.93800E+00 MeV Emin = 1.01390E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -1.38120E+01 MeV Emin = 1.49200E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 106 Q = -1.40710E+01 MeV Emin = 1.43600E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 7 MT = 107 Q = -3.44390E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 47 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 6.22950E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.01390E+01 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.49200E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.43600E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 5.00000E+00 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 4.54755E-04 MeV : damage-energy production + 7 MT = 600 Q = -6.10600E+00 MeV Emin = 6.22931E+00 MeV : (n,p) to ground state + 8 MT = 601 Q = -6.36290E+00 MeV Emin = 6.49140E+00 MeV : (n,p1) + 9 MT = 602 Q = -6.43440E+00 MeV Emin = 6.56440E+00 MeV : (n,p2) + 10 MT = 603 Q = -6.86200E+00 MeV Emin = 7.00060E+00 MeV : (n,p3) + 11 MT = 604 Q = -7.95380E+00 MeV Emin = 8.11443E+00 MeV : (n,p4) + 12 MT = 605 Q = -8.33300E+00 MeV Emin = 8.50130E+00 MeV : (n,p5) + 13 MT = 606 Q = -8.43700E+00 MeV Emin = 8.60740E+00 MeV : (n,p6) + 14 MT = 607 Q = -8.63300E+00 MeV Emin = 8.80735E+00 MeV : (n,p7) + 15 MT = 608 Q = -8.72000E+00 MeV Emin = 9.00000E+00 MeV : (n,p8) + 16 MT = 609 Q = -9.13400E+00 MeV Emin = 9.31850E+00 MeV : (n,p9) + 17 MT = 610 Q = -9.19600E+00 MeV Emin = 9.38172E+00 MeV : (n,p10) + 18 MT = 649 Q = -9.19600E+00 MeV Emin = 9.38172E+00 MeV : (n,p) to continuum + 19 MT = 650 Q = -9.93800E+00 MeV Emin = 1.01390E+01 MeV : (n,d) to ground state + 20 MT = 651 Q = -1.21660E+01 MeV Emin = 1.24120E+01 MeV : (n,d1) + 21 MT = 652 Q = -1.23090E+01 MeV Emin = 1.25580E+01 MeV : (n,d2) + 22 MT = 653 Q = -1.30230E+01 MeV Emin = 1.32860E+01 MeV : (n,d3) + 23 MT = 654 Q = -1.32380E+01 MeV Emin = 1.35054E+01 MeV : (n,d4) + 24 MT = 655 Q = -1.34540E+01 MeV Emin = 1.37260E+01 MeV : (n,d5) + 25 MT = 699 Q = -1.34540E+01 MeV Emin = 1.37260E+01 MeV : (n,d) to continuum + 26 MT = 700 Q = -1.38120E+01 MeV Emin = 1.45000E+01 MeV : (n,t) to ground state + 27 MT = 701 Q = -1.39420E+01 MeV Emin = 1.45000E+01 MeV : (n,t1) + 28 MT = 702 Q = -1.40640E+01 MeV Emin = 1.47260E+01 MeV : (n,t2) + 29 MT = 703 Q = -1.42000E+01 MeV Emin = 1.47260E+01 MeV : (n,t3) + 30 MT = 704 Q = -1.44340E+01 MeV Emin = 1.50000E+01 MeV : (n,t4) + 31 MT = 705 Q = -1.49080E+01 MeV Emin = 1.52091E+01 MeV : (n,t5) + 32 MT = 749 Q = -1.49080E+01 MeV Emin = 1.52091E+01 MeV : (n,t) to continuum + 33 MT = 750 Q = -1.40710E+01 MeV Emin = 1.50000E+01 MeV : (n,He-3) to ground state + 34 MT = 751 Q = -1.79030E+01 MeV Emin = 1.82646E+01 MeV : (n,He-3_1) + 35 MT = 800 Q = -3.43970E+00 MeV Emin = 5.00000E+00 MeV : (n,alpha) to ground state + 36 MT = 801 Q = -5.45330E+00 MeV Emin = 5.56343E+00 MeV : (n,a1) + 37 MT = 802 Q = -6.01810E+00 MeV Emin = 7.00000E+00 MeV : (n,a2) + 38 MT = 803 Q = -6.03930E+00 MeV Emin = 7.00000E+00 MeV : (n,a3) + 39 MT = 804 Q = -6.28870E+00 MeV Emin = 7.00000E+00 MeV : (n,a4) + 40 MT = 805 Q = -6.31500E+00 MeV Emin = 7.00000E+00 MeV : (n,a5) + 41 MT = 806 Q = -6.70670E+00 MeV Emin = 7.00000E+00 MeV : (n,a6) + 42 MT = 807 Q = -6.73570E+00 MeV Emin = 7.00000E+00 MeV : (n,a7) + 43 MT = 808 Q = -6.86470E+00 MeV Emin = 8.00000E+00 MeV : (n,a8) + 44 MT = 809 Q = -7.00570E+00 MeV Emin = 8.00000E+00 MeV : (n,a9) + 45 MT = 810 Q = -7.28370E+00 MeV Emin = 8.00000E+00 MeV : (n,a10) + 46 MT = 849 Q = -7.28370E+00 MeV Emin = 7.43080E+00 MeV : (n,alpha) to continuum + 47 MT = 4 Q = 0.00000E+00 MeV Emin = 1.58480E+00 MeV : total inelastic scattering + + Nuclide 46 / 1657 : 23000.82c -- natural vanadium (V-nat) + + Pointers : 3498933 35887 + Primary type : Transport + Nuclide ZAI : 230000 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/V0.ACE + Atomic weight (AW) : 50.94161 + Atomic weight ratio (AWR) : 50.50400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : N/A + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is not involved in burnup calculation + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has no decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 38 reaction channels + - 7 special reactions + - No transmutation reactions + - 11 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + 38 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 : elastic scattering + 2 MT = 16 Q = -1.10510E+01 MeV Emin = 1.12700E+01 MeV frac = 1.00000E+00 : (n,2n) + 3 MT = 22 Q = -1.02940E+01 MeV Emin = 1.04978E+01 MeV frac = 1.00000E+00 : (n,nalpha) + 4 MT = 28 Q = -8.05700E+00 MeV Emin = 8.21653E+00 MeV frac = 1.00000E+00 : (n,np) + 5 MT = 32 Q = -1.67760E+01 MeV Emin = 1.71082E+01 MeV frac = 1.00000E+00 : (n,nd) + 6 MT = 51 Q = -3.20000E-01 MeV Emin = 3.26150E-01 MeV frac = 1.00000E+00 : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -9.29000E-01 MeV Emin = 9.47000E-01 MeV frac = 1.00000E+00 : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -1.60900E+00 MeV Emin = 1.64017E+00 MeV frac = 1.00000E+00 : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -1.81300E+00 MeV Emin = 1.84831E+00 MeV frac = 1.00000E+00 : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -2.41100E+00 MeV Emin = 2.45874E+00 MeV frac = 1.00000E+00 : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -2.54700E+00 MeV Emin = 2.59743E+00 MeV frac = 1.00000E+00 : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -2.67700E+00 MeV Emin = 2.73001E+00 MeV frac = 1.00000E+00 : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -2.69900E+00 MeV Emin = 2.75244E+00 MeV frac = 1.00000E+00 : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -3.08500E+00 MeV Emin = 3.14608E+00 MeV frac = 1.00000E+00 : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -3.15000E+00 MeV Emin = 3.21237E+00 MeV frac = 1.00000E+00 : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -3.19500E+00 MeV Emin = 3.25826E+00 MeV frac = 1.00000E+00 : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -3.21500E+00 MeV Emin = 3.27866E+00 MeV frac = 1.00000E+00 : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -3.26400E+00 MeV Emin = 3.32863E+00 MeV frac = 1.00000E+00 : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -3.28000E+00 MeV Emin = 3.34495E+00 MeV frac = 1.00000E+00 : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -3.37200E+00 MeV Emin = 3.43877E+00 MeV frac = 1.00000E+00 : inelastic scatt. to 15. excited state + 21 MT = 66 Q = -3.37700E+00 MeV Emin = 3.44387E+00 MeV frac = 1.00000E+00 : inelastic scatt. to 16. excited state + 22 MT = 67 Q = -3.37800E+00 MeV Emin = 3.44489E+00 MeV frac = 1.00000E+00 : inelastic scatt. to 17. excited state + 23 MT = 68 Q = -3.38100E+00 MeV Emin = 3.44795E+00 MeV frac = 1.00000E+00 : inelastic scatt. to 18. excited state + 24 MT = 69 Q = -3.38300E+00 MeV Emin = 3.44999E+00 MeV frac = 1.00000E+00 : inelastic scatt. to 19. excited state + 25 MT = 70 Q = -3.38600E+00 MeV Emin = 3.45304E+00 MeV frac = 1.00000E+00 : inelastic scatt. to 20. excited state + 26 MT = 71 Q = -3.39600E+00 MeV Emin = 3.46324E+00 MeV frac = 1.00000E+00 : inelastic scatt. to 21. excited state + 27 MT = 72 Q = -3.44400E+00 MeV Emin = 3.51219E+00 MeV frac = 1.00000E+00 : inelastic scatt. to 22. excited state + 28 MT = 73 Q = -3.44500E+00 MeV Emin = 3.51321E+00 MeV frac = 1.00000E+00 : inelastic scatt. to 23. excited state + 29 MT = 74 Q = -3.45400E+00 MeV Emin = 3.52239E+00 MeV frac = 1.00000E+00 : inelastic scatt. to 24. excited state + 30 MT = 91 Q = -3.38400E+00 MeV Emin = 3.45101E+00 MeV frac = 1.00000E+00 : inelastic scattering to continuum + 31 MT = 102 Q = 7.31100E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 : (n,gamma) + 32 MT = 103 Q = -1.68400E+00 MeV Emin = 1.71697E+00 MeV frac = 1.00000E+00 : (n,p) + 33 MT = 104 Q = -5.83200E+00 MeV Emin = 5.94748E+00 MeV frac = 1.00000E+00 : (n,d) + 34 MT = 105 Q = -1.05190E+01 MeV Emin = 1.07300E+01 MeV frac = 1.00000E+00 : (n,t) + 35 MT = 106 Q = -1.25040E+01 MeV Emin = 1.27516E+01 MeV frac = 1.00000E+00 : (n,He-3) + 36 MT = 107 Q = -2.05500E+00 MeV Emin = 2.09569E+00 MeV frac = 1.00000E+00 : (n,alpha) + 37 MT = 111 Q = -1.41690E+01 MeV Emin = 1.44500E+01 MeV frac = 1.00000E+00 : (n,2p) + 38 MT = 112 Q = -1.17255E+01 MeV Emin = 1.19600E+01 MeV frac = 1.00000E+00 : (n,palpha) + + 11 additional transport branches: + + 1 MT = 22 Q = -1.02940E+01 MeV Emin = 1.04978E+01 MeV frac = 1.00000E+00 : (n,nalpha) + 2 MT = 28 Q = -8.05700E+00 MeV Emin = 8.21653E+00 MeV frac = 1.00000E+00 : (n,np) + 3 MT = 32 Q = -1.67760E+01 MeV Emin = 1.71082E+01 MeV frac = 1.00000E+00 : (n,nd) + 4 MT = 103 Q = -1.68400E+00 MeV Emin = 1.71697E+00 MeV frac = 1.00000E+00 : (n,p) + 5 MT = 104 Q = -5.83200E+00 MeV Emin = 5.94748E+00 MeV frac = 1.00000E+00 : (n,d) + 6 MT = 105 Q = -1.05190E+01 MeV Emin = 1.07300E+01 MeV frac = 1.00000E+00 : (n,t) + 7 MT = 106 Q = -1.25040E+01 MeV Emin = 1.27516E+01 MeV frac = 1.00000E+00 : (n,He-3) + 8 MT = 107 Q = -2.05500E+00 MeV Emin = 2.09569E+00 MeV frac = 1.00000E+00 : (n,alpha) + 9 MT = 111 Q = -1.41690E+01 MeV Emin = 1.44500E+01 MeV frac = 2.00000E+00 : (n,2p) + 10 MT = 112 Q = -1.17255E+01 MeV Emin = 1.19600E+01 MeV frac = 1.00000E+00 : (n,palpha) + 11 MT = 112 Q = -1.17255E+01 MeV Emin = 1.19600E+01 MeV frac = 1.00000E+00 : (n,palpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.71697E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.94748E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.07300E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.27516E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 2.09569E+00 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 3.26150E-01 MeV : total inelastic scattering + + Nuclide 47 / 1657 : 24050.82c -- chromium 50 (Cr-50) + + Pointers : 270085 22317 + Primary type : Transport + Nuclide ZAI : 240500 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Cr50.ACE + Atomic weight (AW) : 49.94606 + Atomic weight ratio (AWR) : 49.51700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 5.68E+24 seconds (1.8E+17 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 15 reaction channels + - 5 special reactions + - 7 transmutation reactions + - 5 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 15 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.30000E+01 MeV Emin = 1.32630E+01 MeV frac = 1.00000E+00 Product nuclide = 240490 : (n,2n) + 3 MT = 22 Q = -8.56000E+00 MeV Emin = 8.73290E+00 MeV frac = 1.00000E+00 Product nuclide = 22046.82c : (n,nalpha) + 4 MT = 28 Q = -9.59000E+00 MeV Emin = 9.78370E+00 MeV frac = 1.00000E+00 Product nuclide = 230490 : (n,np) + 5 MT = 51 Q = -7.83000E-01 MeV Emin = 7.98189E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -1.88100E+00 MeV Emin = 1.91322E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -2.92500E+00 MeV Emin = 2.98410E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -3.16100E+00 MeV Emin = 3.22484E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -3.16400E+00 MeV Emin = 3.22790E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -3.32500E+00 MeV Emin = 3.39215E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 91 Q = -3.59500E+00 MeV Emin = 3.66760E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 12 MT = 102 Q = 9.26170E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 240510 : (n,gamma) + 13 MT = 103 Q = -2.56300E-01 MeV Emin = 9.99460E-01 MeV frac = 1.00000E+00 Product nuclide = 230500 : (n,p) + 14 MT = 104 Q = -7.36400E+00 MeV Emin = 7.51272E+00 MeV frac = 1.00000E+00 Product nuclide = 230490 : (n,d) + 15 MT = 107 Q = 3.19500E-01 MeV Emin = 2.25000E+00 MeV frac = 1.00000E+00 Product nuclide = 22047.82c : (n,alpha) + + 5 additional transport branches: + + 1 MT = 22 Q = -8.56000E+00 MeV Emin = 8.73290E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -9.59000E+00 MeV Emin = 9.78370E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -2.56300E-01 MeV Emin = 9.99460E-01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -7.36400E+00 MeV Emin = 7.51272E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 107 Q = 3.19500E-01 MeV Emin = 2.25000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 5 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 9.99460E-01 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.51272E+00 MeV : total deuteron production + 3 MT = 207 Q = 0.00000E+00 MeV Emin = 2.25000E+00 MeV : total alpha production + 4 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 5 MT = 4 Q = 0.00000E+00 MeV Emin = 7.98189E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 22 Q = 1.16720E+00 MeV frac = 1.00000E+00 Product nuclide = 22050.82c : EC/beta+ + EC/beta+ + + Nuclide 48 / 1657 : 24052.82c -- chromium 52 (Cr-52) + + Pointers : 272465 22363 + Primary type : Transport + Nuclide ZAI : 240520 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Cr52.ACE + Atomic weight (AW) : 51.93999 + Atomic weight ratio (AWR) : 51.49380 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 21 reaction channels + - 7 special reactions + - 9 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 21 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.20350E+01 MeV Emin = 1.22730E+01 MeV frac = 1.00000E+00 Product nuclide = 240510 : (n,2n) + 3 MT = 22 Q = -9.35300E+00 MeV Emin = 9.53463E+00 MeV frac = 1.00000E+00 Product nuclide = 22048.82c : (n,nalpha) + 4 MT = 28 Q = -1.05050E+01 MeV Emin = 1.07090E+01 MeV frac = 1.00000E+00 Product nuclide = 230510 : (n,np) + 5 MT = 51 Q = -1.43400E+00 MeV Emin = 1.46134E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -2.37000E+00 MeV Emin = 2.41603E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -2.64700E+00 MeV Emin = 2.69841E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -2.76800E+00 MeV Emin = 2.82176E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -2.96500E+00 MeV Emin = 3.02258E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -3.11400E+00 MeV Emin = 3.17447E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -3.16200E+00 MeV Emin = 3.22341E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -3.41500E+00 MeV Emin = 3.48132E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -3.47200E+00 MeV Emin = 3.53943E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -3.61600E+00 MeV Emin = 3.68622E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 91 Q = -3.70073E+00 MeV Emin = 3.77260E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 16 MT = 102 Q = 7.94010E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 24053.82c : (n,gamma) + 17 MT = 103 Q = -3.19270E+00 MeV Emin = 3.25600E+00 MeV frac = 1.00000E+00 Product nuclide = 230520 : (n,p) + 18 MT = 104 Q = -8.28000E+00 MeV Emin = 8.44080E+00 MeV frac = 1.00000E+00 Product nuclide = 230510 : (n,d) + 19 MT = 105 Q = -1.30740E+01 MeV Emin = 1.33279E+01 MeV frac = 1.00000E+00 Product nuclide = 230500 : (n,t) + 20 MT = 106 Q = -1.08470E+01 MeV Emin = 1.10577E+01 MeV frac = 1.00000E+00 Product nuclide = 22050.82c : (n,He-3) + 21 MT = 107 Q = -1.20970E+00 MeV Emin = 1.23325E+00 MeV frac = 1.00000E+00 Product nuclide = 22049.82c : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -9.35300E+00 MeV Emin = 9.53463E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.05050E+01 MeV Emin = 1.07090E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -3.19270E+00 MeV Emin = 3.25600E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -8.28000E+00 MeV Emin = 8.44080E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -1.30740E+01 MeV Emin = 1.33279E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 106 Q = -1.08470E+01 MeV Emin = 1.10577E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 7 MT = 107 Q = -1.20970E+00 MeV Emin = 1.23325E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.25600E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.44080E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.33279E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.10577E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.23325E+00 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 1.46134E+00 MeV : total inelastic scattering + + Nuclide 49 / 1657 : 24053.82c -- chromium 53 (Cr-53) + + Pointers : 275131 22409 + Primary type : Transport + Nuclide ZAI : 240530 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Cr53.ACE + Atomic weight (AW) : 52.94079 + Atomic weight ratio (AWR) : 52.48600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 21 reaction channels + - 4 special reactions + - 6 transmutation reactions + - 4 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 21 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.94000E+00 MeV Emin = 8.09130E+00 MeV frac = 1.00000E+00 Product nuclide = 24052.82c : (n,2n) + 3 MT = 22 Q = -9.15000E+00 MeV Emin = 9.32433E+00 MeV frac = 1.00000E+00 Product nuclide = 22049.82c : (n,nalpha) + 4 MT = 28 Q = -1.11340E+01 MeV Emin = 1.13461E+01 MeV frac = 1.00000E+00 Product nuclide = 230520 : (n,np) + 5 MT = 51 Q = -5.64000E-01 MeV Emin = 5.74507E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -1.00600E+00 MeV Emin = 1.02484E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -1.29000E+00 MeV Emin = 1.31421E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -1.53700E+00 MeV Emin = 1.56583E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -1.97400E+00 MeV Emin = 2.01161E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -2.17200E+00 MeV Emin = 2.21340E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -2.23300E+00 MeV Emin = 2.27555E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -2.32100E+00 MeV Emin = 2.36522E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -2.45300E+00 MeV Emin = 2.49974E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -2.65600E+00 MeV Emin = 2.70661E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -2.67000E+00 MeV Emin = 2.72090E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -2.70600E+00 MeV Emin = 2.75760E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 63 Q = -2.70700E+00 MeV Emin = 2.75860E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 18 MT = 91 Q = -2.77200E+00 MeV Emin = 2.82482E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 19 MT = 102 Q = 9.71990E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 24054.82c : (n,gamma) + 20 MT = 103 Q = -2.64000E+00 MeV Emin = 2.69030E+00 MeV frac = 1.00000E+00 Product nuclide = 230530 : (n,p) + 21 MT = 107 Q = 1.79500E+00 MeV Emin = 9.99018E-01 MeV frac = 1.00000E+00 Product nuclide = 22050.82c : (n,alpha) + + 4 additional transport branches: + + 1 MT = 22 Q = -9.15000E+00 MeV Emin = 9.32433E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.11340E+01 MeV Emin = 1.13461E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -2.64000E+00 MeV Emin = 2.69030E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 107 Q = 1.79500E+00 MeV Emin = 9.99018E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 4 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.69030E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 9.99018E-01 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 4 MT = 4 Q = 0.00000E+00 MeV Emin = 5.74507E-01 MeV : total inelastic scattering + + Nuclide 50 / 1657 : 24054.82c -- chromium 54 (Cr-54) + + Pointers : 277359 22455 + Primary type : Transport + Nuclide ZAI : 240540 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Cr54.ACE + Atomic weight (AW) : 53.93937 + Atomic weight ratio (AWR) : 53.47600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 10 reaction channels + - 4 special reactions + - 4 transmutation reactions + - 2 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 10 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -9.71900E+00 MeV Emin = 9.90075E+00 MeV frac = 1.00000E+00 Product nuclide = 24053.82c : (n,2n) + 3 MT = 51 Q = -8.35000E-01 MeV Emin = 8.50300E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 4 MT = 52 Q = -1.82400E+00 MeV Emin = 1.85595E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 5 MT = 53 Q = -2.62000E+00 MeV Emin = 2.66900E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 6 MT = 54 Q = -2.82900E+00 MeV Emin = 2.88190E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 7 MT = 91 Q = -3.07400E+00 MeV Emin = 3.13150E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 8 MT = 102 Q = 6.24630E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 240550 : (n,gamma) + 9 MT = 103 Q = -6.21400E+00 MeV Emin = 6.33020E+00 MeV frac = 1.00000E+00 Product nuclide = 230540 : (n,p) + 10 MT = 107 Q = -1.55200E+00 MeV Emin = 1.58078E+00 MeV frac = 1.00000E+00 Product nuclide = 220510 : (n,alpha) + + 2 additional transport branches: + + 1 MT = 103 Q = -6.21400E+00 MeV Emin = 6.33020E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 107 Q = -1.55200E+00 MeV Emin = 1.58078E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 4 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 6.33020E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 1.58078E+00 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 4 MT = 4 Q = 0.00000E+00 MeV Emin = 8.50300E-01 MeV : total inelastic scattering + + Nuclide 51 / 1657 : 25055.82c -- manganese 55 (Mn-55) + + Pointers : 283631 27745 + Primary type : Transport + Nuclide ZAI : 250550 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Mn55.ACE + Atomic weight (AW) : 54.93805 + Atomic weight ratio (AWR) : 54.46610 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 27 reaction channels + - 7 special reactions + - 9 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 27 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.02270E+01 MeV Emin = 1.04148E+01 MeV frac = 1.00000E+00 Product nuclide = 250540 : (n,2n) + 3 MT = 22 Q = -7.93579E+00 MeV Emin = 8.08150E+00 MeV frac = 1.00000E+00 Product nuclide = 230510 : (n,nalpha) + 4 MT = 28 Q = -8.06789E+00 MeV Emin = 8.21602E+00 MeV frac = 1.00000E+00 Product nuclide = 24054.82c : (n,np) + 5 MT = 51 Q = -1.26000E-01 MeV Emin = 1.28188E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -9.83999E-01 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -1.29000E+00 MeV Emin = 1.31156E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -1.29200E+00 MeV Emin = 1.31536E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -1.29300E+00 MeV Emin = 1.31620E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -1.52800E+00 MeV Emin = 1.54974E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -1.88400E+00 MeV Emin = 1.91754E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -2.01500E+00 MeV Emin = 2.05200E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -2.19800E+00 MeV Emin = 2.23836E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -2.21500E+00 MeV Emin = 2.25567E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -2.25200E+00 MeV Emin = 2.29335E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -2.26700E+00 MeV Emin = 2.30862E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 63 Q = -2.31200E+00 MeV Emin = 2.35445E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 18 MT = 64 Q = -2.36600E+00 MeV Emin = 2.40944E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 19 MT = 65 Q = -2.39800E+00 MeV Emin = 2.44203E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 20 MT = 66 Q = -2.42700E+00 MeV Emin = 2.47156E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 21 MT = 91 Q = -3.04600E+00 MeV Emin = 3.10193E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 22 MT = 102 Q = 7.27053E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 250560 : (n,gamma) + 23 MT = 103 Q = -1.82120E+00 MeV Emin = 1.85420E+00 MeV frac = 1.00000E+00 Product nuclide = 240550 : (n,p) + 24 MT = 104 Q = -5.84329E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 24054.82c : (n,d) + 25 MT = 105 Q = -9.30499E+00 MeV Emin = 1.15000E+01 MeV frac = 1.00000E+00 Product nuclide = 24053.82c : (n,t) + 26 MT = 106 Q = -1.27070E+01 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 230530 : (n,He-3) + 27 MT = 107 Q = -6.24299E-01 MeV Emin = 6.35000E-01 MeV frac = 1.00000E+00 Product nuclide = 230520 : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -7.93579E+00 MeV Emin = 8.08150E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -8.06789E+00 MeV Emin = 8.21602E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -1.82120E+00 MeV Emin = 1.85420E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -5.84329E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -9.30499E+00 MeV Emin = 1.15000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 106 Q = -1.27070E+01 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 7 MT = 107 Q = -6.24299E-01 MeV Emin = 6.35000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.85420E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.15000E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.40000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 6.35000E-01 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 1.28188E-01 MeV : total inelastic scattering + + Nuclide 52 / 1657 : 26054.82c -- iron 54 (Fe-54) + + Pointers : 294256 24019 + Primary type : Transport + Nuclide ZAI : 260540 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Fe54.ACE + Atomic weight (AW) : 53.93962 + Atomic weight ratio (AWR) : 53.47625 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+02 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 37 reaction channels + - 52 special reactions + - 14 transmutation reactions + - 14 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 37 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 5 Q = 0.00000E+00 MeV Emin = 6.99790E-01 MeV frac = 1.00000E+00 Product nuclide = self : anything + 3 MT = 16 Q = -1.33785E+01 MeV Emin = 1.36287E+01 MeV frac = 1.00000E+00 Product nuclide = 260530 : (n,2n) + 4 MT = 22 Q = -8.41886E+00 MeV Emin = 9.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 24050.82c : (n,nalpha) + 5 MT = 28 Q = -8.85375E+00 MeV Emin = 9.01932E+00 MeV frac = 1.00000E+00 Product nuclide = 250530 : (n,np) + 6 MT = 44 Q = -1.54136E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 24052.82c : (n,n2p) + 7 MT = 51 Q = -1.40819E+00 MeV Emin = 1.43385E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 8 MT = 52 Q = -2.53810E+00 MeV Emin = 2.58556E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 9 MT = 53 Q = -2.56130E+00 MeV Emin = 2.60920E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 10 MT = 54 Q = -2.94920E+00 MeV Emin = 3.00435E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 11 MT = 55 Q = -2.95900E+00 MeV Emin = 3.01433E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 12 MT = 56 Q = -3.16600E+00 MeV Emin = 3.22520E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 13 MT = 57 Q = -3.29480E+00 MeV Emin = 3.35641E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 14 MT = 58 Q = -3.34480E+00 MeV Emin = 3.40735E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 15 MT = 59 Q = -3.43740E+00 MeV Emin = 3.50168E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 16 MT = 60 Q = -3.79380E+00 MeV Emin = 3.86475E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 17 MT = 61 Q = -3.83320E+00 MeV Emin = 3.90488E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 18 MT = 62 Q = -3.84100E+00 MeV Emin = 3.91283E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 19 MT = 63 Q = -4.03090E+00 MeV Emin = 4.10628E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 20 MT = 64 Q = -4.04780E+00 MeV Emin = 4.12349E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 21 MT = 65 Q = -4.07160E+00 MeV Emin = 4.14774E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 22 MT = 66 Q = -4.09970E+00 MeV Emin = 4.17636E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 23 MT = 67 Q = -4.10340E+00 MeV Emin = 4.18013E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 24 MT = 68 Q = -4.26780E+00 MeV Emin = 4.34761E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 25 MT = 69 Q = -4.29080E+00 MeV Emin = 4.37104E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 26 MT = 70 Q = -4.57850E+00 MeV Emin = 4.66412E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 27 MT = 91 Q = -4.57850E+00 MeV Emin = 4.66412E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 28 MT = 102 Q = 9.29792E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 260550 : (n,gamma) + 29 MT = 103 Q = 8.52127E-02 MeV Emin = 3.39318E-01 MeV frac = 1.00000E+00 Product nuclide = 250540 : (n,p) + 30 MT = 104 Q = -6.62918E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 250530 : (n,d) + 31 MT = 105 Q = -1.24257E+01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 250520 : (n,t) + 32 MT = 106 Q = -7.69549E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 24052.82c : (n,He-3) + 33 MT = 107 Q = 8.42760E-01 MeV Emin = 6.75946E-01 MeV frac = 1.00000E+00 Product nuclide = 240510 : (n,alpha) + 34 MT = 108 Q = -8.09518E+00 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 22047.82c : (n,2alpha) + 35 MT = 111 Q = -7.47439E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 24053.82c : (n,2p) + 36 MT = 112 Q = -8.67343E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 230500 : (n,palpha) + 37 MT = 115 Q = -1.31890E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 24052.82c : (n,pd) + + 14 additional transport branches: + + 1 MT = 22 Q = -8.41886E+00 MeV Emin = 9.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -8.85375E+00 MeV Emin = 9.01932E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 44 Q = -1.54136E+01 MeV Emin = 1.60000E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,n2p) + 4 MT = 103 Q = 8.52127E-02 MeV Emin = 3.39318E-01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -6.62918E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -1.24257E+01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 106 Q = -7.69549E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 8 MT = 107 Q = 8.42760E-01 MeV Emin = 6.75946E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 9 MT = 108 Q = -8.09518E+00 MeV Emin = 1.25000E+01 MeV frac = 2.00000E+00 Product nuclide = 2004.82c : (n,2alpha) + 10 MT = 111 Q = -7.47439E+00 MeV Emin = 8.00000E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + 11 MT = 112 Q = -8.67343E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,palpha) + 12 MT = 112 Q = -8.67343E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,palpha) + 13 MT = 115 Q = -1.31890E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,pd) + 14 MT = 115 Q = -1.31890E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,pd) + + 52 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.39318E-01 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.30000E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 9.00000E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 6.75946E-01 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 5.00000E-04 MeV : damage-energy production + 7 MT = 600 Q = 8.52127E-02 MeV Emin = 3.40533E-01 MeV : (n,p) to ground state + 8 MT = 601 Q = 3.03427E-02 MeV Emin = 3.43705E-01 MeV : (n,p1) + 9 MT = 602 Q = -7.10873E-02 MeV Emin = 3.99862E-01 MeV : (n,p2) + 10 MT = 603 Q = -2.83077E-01 MeV Emin = 5.99924E-01 MeV : (n,p3) + 11 MT = 604 Q = -3.22337E-01 MeV Emin = 6.99893E-01 MeV : (n,p4) + 12 MT = 605 Q = -7.53697E-01 MeV Emin = 9.99868E-01 MeV : (n,p5) + 13 MT = 606 Q = -9.24407E-01 MeV Emin = 1.19983E+00 MeV : (n,p6) + 14 MT = 607 Q = -9.88087E-01 MeV Emin = 1.39979E+00 MeV : (n,p7) + 15 MT = 608 Q = -1.05153E+00 MeV Emin = 1.39979E+00 MeV : (n,p8) + 16 MT = 609 Q = -1.28978E+00 MeV Emin = 1.59892E+00 MeV : (n,p9) + 17 MT = 610 Q = -1.29037E+00 MeV Emin = 1.59892E+00 MeV : (n,p10) + 18 MT = 649 Q = -1.29037E+00 MeV Emin = 1.79960E+00 MeV : (n,p) to continuum + 19 MT = 650 Q = -6.62918E+00 MeV Emin = 7.00000E+00 MeV : (n,d) to ground state + 20 MT = 651 Q = -7.00707E+00 MeV Emin = 7.20000E+00 MeV : (n,d1) + 21 MT = 652 Q = -7.91885E+00 MeV Emin = 8.06693E+00 MeV : (n,d2) + 22 MT = 653 Q = -8.07030E+00 MeV Emin = 8.50000E+00 MeV : (n,d3) + 23 MT = 654 Q = -8.25038E+00 MeV Emin = 8.50000E+00 MeV : (n,d4) + 24 MT = 655 Q = -8.90295E+00 MeV Emin = 9.06944E+00 MeV : (n,d5) + 25 MT = 699 Q = -8.90295E+00 MeV Emin = 1.00000E+01 MeV : (n,d) to continuum + 26 MT = 700 Q = -1.24257E+01 MeV Emin = 1.30000E+01 MeV : (n,t) to ground state + 27 MT = 701 Q = -1.28035E+01 MeV Emin = 1.35000E+01 MeV : (n,t1) + 28 MT = 702 Q = -1.29722E+01 MeV Emin = 1.35000E+01 MeV : (n,t2) + 29 MT = 703 Q = -1.31574E+01 MeV Emin = 1.35000E+01 MeV : (n,t3) + 30 MT = 704 Q = -1.32509E+01 MeV Emin = 1.35000E+01 MeV : (n,t4) + 31 MT = 705 Q = -1.32956E+01 MeV Emin = 1.40000E+01 MeV : (n,t5) + 32 MT = 749 Q = -1.32956E+01 MeV Emin = 1.40000E+01 MeV : (n,t) to continuum + 33 MT = 750 Q = -7.69549E+00 MeV Emin = 9.00000E+00 MeV : (n,He-3) to ground state + 34 MT = 751 Q = -9.12958E+00 MeV Emin = 9.50000E+00 MeV : (n,He-3_1) + 35 MT = 752 Q = -1.00651E+01 MeV Emin = 1.10000E+01 MeV : (n,He-3_2) + 36 MT = 753 Q = -1.03424E+01 MeV Emin = 1.15000E+01 MeV : (n,He-3_3) + 37 MT = 754 Q = -1.04633E+01 MeV Emin = 1.15000E+01 MeV : (n,He-3_4) + 38 MT = 755 Q = -1.06603E+01 MeV Emin = 1.20000E+01 MeV : (n,He-3_5) + 39 MT = 799 Q = -1.06603E+01 MeV Emin = 1.30000E+01 MeV : (n,He-3) to continuum + 40 MT = 800 Q = 8.42760E-01 MeV Emin = 6.75946E-01 MeV : (n,alpha) to ground state + 41 MT = 801 Q = 9.36601E-02 MeV Emin = 1.47795E+00 MeV : (n,a1) + 42 MT = 802 Q = 6.58101E-02 MeV Emin = 1.54416E+00 MeV : (n,a2) + 43 MT = 803 Q = -3.21830E-01 MeV Emin = 1.98065E+00 MeV : (n,a3) + 44 MT = 804 Q = -5.09890E-01 MeV Emin = 2.00178E+00 MeV : (n,a4) + 45 MT = 805 Q = -6.37310E-01 MeV Emin = 2.00178E+00 MeV : (n,a5) + 46 MT = 806 Q = -7.14500E-01 MeV Emin = 2.00178E+00 MeV : (n,a6) + 47 MT = 807 Q = -1.05644E+00 MeV Emin = 2.20000E+00 MeV : (n,a7) + 48 MT = 808 Q = -1.15915E+00 MeV Emin = 2.40000E+00 MeV : (n,a8) + 49 MT = 809 Q = -1.41274E+00 MeV Emin = 2.60000E+00 MeV : (n,a9) + 50 MT = 810 Q = -1.46982E+00 MeV Emin = 2.60000E+00 MeV : (n,a10) + 51 MT = 849 Q = -1.46982E+00 MeV Emin = 2.80000E+00 MeV : (n,alpha) to continuum + 52 MT = 4 Q = 0.00000E+00 MeV Emin = 1.43385E+00 MeV : total inelastic scattering + + Nuclide 53 / 1657 : 26056.82c -- iron 56 (Fe-56) + + Pointers : 302201 24065 + Primary type : Transport + Nuclide ZAI : 260560 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Fe56.ACE + Atomic weight (AW) : 55.93491 + Atomic weight ratio (AWR) : 55.45440 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+02 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 44 reaction channels + - 34 special reactions + - 9 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 44 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 5 Q = 0.00000E+00 MeV Emin = 2.00000E+01 MeV frac = 1.00000E+00 Product nuclide = self : anything + 3 MT = 16 Q = -1.11970E+01 MeV Emin = 1.13989E+01 MeV frac = 1.00000E+00 Product nuclide = 260550 : (n,2n) + 4 MT = 22 Q = -7.61310E+00 MeV Emin = 7.75039E+00 MeV frac = 1.00000E+00 Product nuclide = 24052.82c : (n,nalpha) + 5 MT = 28 Q = -1.01840E+01 MeV Emin = 1.03677E+01 MeV frac = 1.00000E+00 Product nuclide = 25055.82c : (n,np) + 6 MT = 51 Q = -8.47000E-01 MeV Emin = 8.61932E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -2.08500E+00 MeV Emin = 2.12260E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -2.65800E+00 MeV Emin = 2.70593E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -2.94200E+00 MeV Emin = 2.99510E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -2.96000E+00 MeV Emin = 3.01340E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -3.12000E+00 MeV Emin = 3.17630E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -3.12300E+00 MeV Emin = 3.17932E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -3.37000E+00 MeV Emin = 3.43080E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -3.38900E+00 MeV Emin = 3.45011E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -3.44500E+00 MeV Emin = 3.50712E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -3.44900E+00 MeV Emin = 3.51120E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -3.59900E+00 MeV Emin = 3.66390E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -3.60100E+00 MeV Emin = 3.66594E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -3.60700E+00 MeV Emin = 3.67204E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -3.74800E+00 MeV Emin = 3.81560E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 21 MT = 66 Q = -3.75600E+00 MeV Emin = 3.82373E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 22 MT = 67 Q = -3.76000E+00 MeV Emin = 3.82780E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 23 MT = 68 Q = -3.83000E+00 MeV Emin = 3.89910E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 24 MT = 69 Q = -3.85600E+00 MeV Emin = 3.92554E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 25 MT = 70 Q = -4.04900E+00 MeV Emin = 4.12202E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 26 MT = 71 Q = -4.10000E+00 MeV Emin = 4.17394E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 27 MT = 72 Q = -4.12000E+00 MeV Emin = 4.19430E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 28 MT = 73 Q = -4.29800E+00 MeV Emin = 4.37551E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 29 MT = 74 Q = -4.30000E+00 MeV Emin = 4.37754E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 30 MT = 75 Q = -4.32000E+00 MeV Emin = 4.39790E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 31 MT = 76 Q = -4.37000E+00 MeV Emin = 4.44880E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 32 MT = 77 Q = -4.39200E+00 MeV Emin = 4.47120E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 27. excited state + 33 MT = 78 Q = -4.39500E+00 MeV Emin = 4.47430E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 28. excited state + 34 MT = 79 Q = -4.40100E+00 MeV Emin = 4.48040E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 29. excited state + 35 MT = 80 Q = -4.44700E+00 MeV Emin = 4.52719E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 30. excited state + 36 MT = 81 Q = -4.45800E+00 MeV Emin = 4.53840E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 31. excited state + 37 MT = 82 Q = -4.51000E+00 MeV Emin = 4.59133E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 32. excited state + 38 MT = 91 Q = -4.53600E+00 MeV Emin = 4.61780E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 39 MT = 102 Q = 7.64670E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 26057.82c : (n,gamma) + 40 MT = 103 Q = -2.91310E+00 MeV Emin = 4.09950E+00 MeV frac = 1.00000E+00 Product nuclide = 250560 : (n,p) + 41 MT = 104 Q = -7.95900E+00 MeV Emin = 8.10252E+00 MeV frac = 1.00000E+00 Product nuclide = 25055.82c : (n,d) + 42 MT = 105 Q = -1.19280E+01 MeV Emin = 1.21431E+01 MeV frac = 1.00000E+00 Product nuclide = 250540 : (n,t) + 43 MT = 106 Q = -1.05330E+01 MeV Emin = 1.07230E+01 MeV frac = 1.00000E+00 Product nuclide = 24054.82c : (n,He-3) + 44 MT = 107 Q = 3.26050E-01 MeV Emin = 3.43110E+00 MeV frac = 1.00000E+00 Product nuclide = 24053.82c : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -7.61310E+00 MeV Emin = 7.75039E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.01840E+01 MeV Emin = 1.03677E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -2.91310E+00 MeV Emin = 4.09950E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -7.95900E+00 MeV Emin = 8.10252E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -1.19280E+01 MeV Emin = 1.21431E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 106 Q = -1.05330E+01 MeV Emin = 1.07230E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 7 MT = 107 Q = 3.26050E-01 MeV Emin = 3.43110E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 34 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.09950E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.10252E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.21431E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.07230E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 3.43110E+00 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 600 Q = -2.91310E+00 MeV Emin = 4.09950E+00 MeV : (n,p) to ground state + 8 MT = 601 Q = -2.94010E+00 MeV Emin = 4.09950E+00 MeV : (n,p1) + 9 MT = 602 Q = -3.02410E+00 MeV Emin = 4.17440E+00 MeV : (n,p2) + 10 MT = 603 Q = -3.12510E+00 MeV Emin = 4.37590E+00 MeV : (n,p3) + 11 MT = 604 Q = -3.12810E+00 MeV Emin = 4.37590E+00 MeV : (n,p4) + 12 MT = 605 Q = -3.24910E+00 MeV Emin = 4.47170E+00 MeV : (n,p5) + 13 MT = 606 Q = -3.25410E+00 MeV Emin = 4.37590E+00 MeV : (n,p6) + 14 MT = 607 Q = -3.36710E+00 MeV Emin = 4.52760E+00 MeV : (n,p7) + 15 MT = 608 Q = -3.39910E+00 MeV Emin = 4.53880E+00 MeV : (n,p8) + 16 MT = 609 Q = -3.45410E+00 MeV Emin = 4.69560E+00 MeV : (n,p9) + 17 MT = 610 Q = -3.57310E+00 MeV Emin = 4.79450E+00 MeV : (n,p10) + 18 MT = 611 Q = -3.62910E+00 MeV Emin = 5.00000E+00 MeV : (n,p11) + 19 MT = 612 Q = -3.66610E+00 MeV Emin = 5.00000E+00 MeV : (n,p12) + 20 MT = 613 Q = -3.75310E+00 MeV Emin = 5.00000E+00 MeV : (n,p13) + 21 MT = 649 Q = -3.79810E+00 MeV Emin = 5.00000E+00 MeV : (n,p) to continuum + 22 MT = 800 Q = 3.26047E-01 MeV Emin = 3.43110E+00 MeV : (n,alpha) to ground state + 23 MT = 801 Q = -2.37953E-01 MeV Emin = 4.17440E+00 MeV : (n,a1) + 24 MT = 802 Q = -6.79953E-01 MeV Emin = 4.59200E+00 MeV : (n,a2) + 25 MT = 803 Q = -9.63953E-01 MeV Emin = 5.00000E+00 MeV : (n,a3) + 26 MT = 804 Q = -1.21095E+00 MeV Emin = 5.25000E+00 MeV : (n,a4) + 27 MT = 805 Q = -1.64795E+00 MeV Emin = 6.00000E+00 MeV : (n,a5) + 28 MT = 806 Q = -1.83895E+00 MeV Emin = 6.50000E+00 MeV : (n,a6) + 29 MT = 807 Q = -1.84595E+00 MeV Emin = 6.50000E+00 MeV : (n,a7) + 30 MT = 808 Q = -1.90695E+00 MeV Emin = 6.50000E+00 MeV : (n,a8) + 31 MT = 809 Q = -1.99495E+00 MeV Emin = 6.50000E+00 MeV : (n,a9) + 32 MT = 810 Q = -2.12695E+00 MeV Emin = 6.50000E+00 MeV : (n,a10) + 33 MT = 849 Q = -2.19295E+00 MeV Emin = 6.50000E+00 MeV : (n,alpha) to continuum + 34 MT = 4 Q = 0.00000E+00 MeV Emin = 8.61932E-01 MeV : total inelastic scattering + + Nuclide 54 / 1657 : 26057.82c -- iron 57 (Fe-57) + + Pointers : 308517 24111 + Primary type : Transport + Nuclide ZAI : 260570 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Fe57.ACE + Atomic weight (AW) : 56.93541 + Atomic weight ratio (AWR) : 56.44630 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+02 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 39 reaction channels + - 52 special reactions + - 16 transmutation reactions + - 14 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 39 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 5 Q = 0.00000E+00 MeV Emin = 1.99844E-01 MeV frac = 1.00000E+00 Product nuclide = self : anything + 3 MT = 16 Q = -7.64603E+00 MeV Emin = 7.78149E+00 MeV frac = 1.00000E+00 Product nuclide = 26056.82c : (n,2n) + 4 MT = 17 Q = -1.88433E+01 MeV Emin = 1.91772E+01 MeV frac = 1.00000E+00 Product nuclide = 260550 : (n,3n) + 5 MT = 22 Q = -7.31998E+00 MeV Emin = 8.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 24053.82c : (n,nalpha) + 6 MT = 24 Q = -1.52591E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 24052.82c : (n,2nalpha) + 7 MT = 28 Q = -1.05591E+01 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 250560 : (n,np) + 8 MT = 32 Q = -1.56050E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 25055.82c : (n,nd) + 9 MT = 41 Q = -1.78296E+01 MeV Emin = 1.81455E+01 MeV frac = 1.00000E+00 Product nuclide = 25055.82c : (n,2np) + 10 MT = 51 Q = -1.44130E-02 MeV Emin = 1.46227E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 11 MT = 52 Q = -1.36474E-01 MeV Emin = 1.38698E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 12 MT = 53 Q = -3.66759E-01 MeV Emin = 3.50363E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 13 MT = 54 Q = -7.06416E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 14 MT = 55 Q = -1.00713E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 15 MT = 56 Q = -1.13990E+00 MeV Emin = 1.14131E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 16 MT = 57 Q = -1.19781E+00 MeV Emin = 1.20000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 17 MT = 58 Q = -1.26552E+00 MeV Emin = 1.26632E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 18 MT = 59 Q = -1.35683E+00 MeV Emin = 1.38023E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 19 MT = 60 Q = -1.62726E+00 MeV Emin = 1.63856E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 20 MT = 61 Q = -1.72538E+00 MeV Emin = 1.73847E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 21 MT = 62 Q = -1.97663E+00 MeV Emin = 2.01165E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 22 MT = 63 Q = -1.98966E+00 MeV Emin = 2.02491E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 23 MT = 64 Q = -1.99100E+00 MeV Emin = 2.02627E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 24 MT = 65 Q = -2.11311E+00 MeV Emin = 2.15055E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 25 MT = 66 Q = -2.11860E+00 MeV Emin = 2.15613E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 26 MT = 67 Q = -2.20688E+00 MeV Emin = 2.24598E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 27 MT = 68 Q = -2.21766E+00 MeV Emin = 2.25695E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 28 MT = 69 Q = -2.22020E+00 MeV Emin = 2.25953E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 29 MT = 70 Q = -2.33041E+00 MeV Emin = 2.37170E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 30 MT = 91 Q = -2.33041E+00 MeV Emin = 2.37170E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 31 MT = 102 Q = 1.00445E+01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 26058.82c : (n,gamma) + 32 MT = 103 Q = -1.90850E+00 MeV Emin = 2.20000E+00 MeV frac = 1.00000E+00 Product nuclide = 250570 : (n,p) + 33 MT = 104 Q = -8.33455E+00 MeV Emin = 8.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 250560 : (n,d) + 34 MT = 105 Q = -9.34780E+00 MeV Emin = 9.51341E+00 MeV frac = 1.00000E+00 Product nuclide = 25055.82c : (n,t) + 35 MT = 106 Q = -1.19323E+01 MeV Emin = 1.35000E+01 MeV frac = 1.00000E+00 Product nuclide = 240550 : (n,He-3) + 36 MT = 107 Q = 2.39902E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 24054.82c : (n,alpha) + 37 MT = 108 Q = -5.52836E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 22050.82c : (n,2alpha) + 38 MT = 111 Q = -1.13937E+01 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 240560 : (n,2p) + 39 MT = 112 Q = -9.97366E+00 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 230530 : (n,palpha) + + 14 additional transport branches: + + 1 MT = 22 Q = -7.31998E+00 MeV Emin = 8.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 24 Q = -1.52591E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,2nalpha) + 3 MT = 28 Q = -1.05591E+01 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 4 MT = 32 Q = -1.56050E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 5 MT = 41 Q = -1.78296E+01 MeV Emin = 1.81455E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,2np) + 6 MT = 103 Q = -1.90850E+00 MeV Emin = 2.20000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 7 MT = 104 Q = -8.33455E+00 MeV Emin = 8.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 8 MT = 105 Q = -9.34780E+00 MeV Emin = 9.51341E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 9 MT = 106 Q = -1.19323E+01 MeV Emin = 1.35000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 10 MT = 107 Q = 2.39902E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 11 MT = 108 Q = -5.52836E+00 MeV Emin = 1.00000E+01 MeV frac = 2.00000E+00 Product nuclide = 2004.82c : (n,2alpha) + 12 MT = 111 Q = -1.13937E+01 MeV Emin = 1.25000E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + 13 MT = 112 Q = -9.97366E+00 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,palpha) + 14 MT = 112 Q = -9.97366E+00 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,palpha) + + 52 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.20000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.50000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.51341E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.35000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 600 Q = -1.90850E+00 MeV Emin = 2.20000E+00 MeV : (n,p) to ground state + 8 MT = 601 Q = -1.99169E+00 MeV Emin = 2.20000E+00 MeV : (n,p1) + 9 MT = 602 Q = -2.75857E+00 MeV Emin = 2.80744E+00 MeV : (n,p2) + 10 MT = 603 Q = -2.96433E+00 MeV Emin = 3.20000E+00 MeV : (n,p3) + 11 MT = 604 Q = -2.98140E+00 MeV Emin = 3.20000E+00 MeV : (n,p4) + 12 MT = 605 Q = -3.13600E+00 MeV Emin = 3.40000E+00 MeV : (n,p5) + 13 MT = 606 Q = -3.28350E+00 MeV Emin = 3.40000E+00 MeV : (n,p6) + 14 MT = 607 Q = -3.38550E+00 MeV Emin = 3.60000E+00 MeV : (n,p7) + 15 MT = 608 Q = -3.40117E+00 MeV Emin = 3.60000E+00 MeV : (n,p8) + 16 MT = 609 Q = -3.44333E+00 MeV Emin = 3.60000E+00 MeV : (n,p9) + 17 MT = 610 Q = -3.52650E+00 MeV Emin = 3.80000E+00 MeV : (n,p10) + 18 MT = 649 Q = -3.52650E+00 MeV Emin = 4.00000E+00 MeV : (n,p) to continuum + 19 MT = 650 Q = -8.33455E+00 MeV Emin = 8.50000E+00 MeV : (n,d) to ground state + 20 MT = 651 Q = -8.36116E+00 MeV Emin = 8.50929E+00 MeV : (n,d1) + 21 MT = 652 Q = -8.44506E+00 MeV Emin = 9.00000E+00 MeV : (n,d2) + 22 MT = 653 Q = -8.54658E+00 MeV Emin = 9.00000E+00 MeV : (n,d3) + 23 MT = 654 Q = -8.54968E+00 MeV Emin = 9.00000E+00 MeV : (n,d4) + 24 MT = 655 Q = -8.67008E+00 MeV Emin = 9.00000E+00 MeV : (n,d5) + 25 MT = 699 Q = -8.67008E+00 MeV Emin = 9.00000E+00 MeV : (n,d) to continuum + 26 MT = 700 Q = -9.34780E+00 MeV Emin = 9.51341E+00 MeV : (n,t) to ground state + 27 MT = 701 Q = -9.47374E+00 MeV Emin = 1.00000E+01 MeV : (n,t1) + 28 MT = 702 Q = -1.03321E+01 MeV Emin = 1.05152E+01 MeV : (n,t2) + 29 MT = 703 Q = -1.06369E+01 MeV Emin = 1.10000E+01 MeV : (n,t3) + 30 MT = 704 Q = -1.06399E+01 MeV Emin = 1.10000E+01 MeV : (n,t4) + 31 MT = 705 Q = -1.06408E+01 MeV Emin = 1.10000E+01 MeV : (n,t5) + 32 MT = 749 Q = -1.06408E+01 MeV Emin = 1.15000E+01 MeV : (n,t) to continuum + 33 MT = 750 Q = -1.19323E+01 MeV Emin = 1.35000E+01 MeV : (n,He-3) to ground state + 34 MT = 751 Q = -1.21742E+01 MeV Emin = 1.35000E+01 MeV : (n,He-3_1) + 35 MT = 752 Q = -1.24500E+01 MeV Emin = 1.40000E+01 MeV : (n,He-3_2) + 36 MT = 753 Q = -1.24982E+01 MeV Emin = 1.40000E+01 MeV : (n,He-3_3) + 37 MT = 754 Q = -1.28130E+01 MeV Emin = 1.40000E+01 MeV : (n,He-3_4) + 38 MT = 755 Q = -1.30633E+01 MeV Emin = 1.45000E+01 MeV : (n,He-3_5) + 39 MT = 799 Q = -1.30633E+01 MeV Emin = 1.50000E+01 MeV : (n,He-3) to continuum + 40 MT = 800 Q = 2.39902E+00 MeV Emin = 1.00000E-11 MeV : (n,alpha) to ground state + 41 MT = 801 Q = 1.56417E+00 MeV Emin = 1.00000E-11 MeV : (n,a1) + 42 MT = 802 Q = 5.75104E-01 MeV Emin = 1.06812E+00 MeV : (n,a2) + 43 MT = 803 Q = -2.20656E-01 MeV Emin = 1.91575E+00 MeV : (n,a3) + 44 MT = 804 Q = -4.30596E-01 MeV Emin = 2.00000E+00 MeV : (n,a4) + 45 MT = 805 Q = -6.75046E-01 MeV Emin = 2.00000E+00 MeV : (n,a5) + 46 MT = 806 Q = -7.60536E-01 MeV Emin = 2.00000E+00 MeV : (n,a6) + 47 MT = 807 Q = -8.23256E-01 MeV Emin = 2.00000E+00 MeV : (n,a7) + 48 MT = 808 Q = -9.94386E-01 MeV Emin = 2.20000E+00 MeV : (n,a8) + 49 MT = 809 Q = -1.03786E+00 MeV Emin = 2.20000E+00 MeV : (n,a9) + 50 MT = 810 Q = -1.06898E+00 MeV Emin = 2.20000E+00 MeV : (n,a10) + 51 MT = 849 Q = -1.06898E+00 MeV Emin = 3.00000E+00 MeV : (n,alpha) to continuum + 52 MT = 4 Q = 0.00000E+00 MeV Emin = 1.46227E-02 MeV : total inelastic scattering + + Nuclide 55 / 1657 : 26058.82c -- iron 58 (Fe-58) + + Pointers : 316293 24157 + Primary type : Transport + Nuclide ZAI : 260580 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Fe58.ACE + Atomic weight (AW) : 57.93329 + Atomic weight ratio (AWR) : 57.43561 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+02 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 34 reaction channels + - 48 special reactions + - 11 transmutation reactions + - 8 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 34 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 5 Q = 0.00000E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : anything + 3 MT = 16 Q = -1.00445E+01 MeV Emin = 1.02194E+01 MeV frac = 1.00000E+00 Product nuclide = 26057.82c : (n,2n) + 4 MT = 17 Q = -1.76905E+01 MeV Emin = 1.80000E+01 MeV frac = 1.00000E+00 Product nuclide = 26056.82c : (n,3n) + 5 MT = 22 Q = -7.64543E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 24054.82c : (n,nalpha) + 6 MT = 28 Q = -1.19530E+01 MeV Emin = 1.21611E+01 MeV frac = 1.00000E+00 Product nuclide = 250570 : (n,np) + 7 MT = 51 Q = -8.10784E-01 MeV Emin = 8.20858E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 8 MT = 52 Q = -1.67475E+00 MeV Emin = 1.70322E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 9 MT = 53 Q = -2.07654E+00 MeV Emin = 2.11269E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 10 MT = 54 Q = -2.13391E+00 MeV Emin = 2.17106E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 11 MT = 55 Q = -2.25796E+00 MeV Emin = 2.29727E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 12 MT = 56 Q = -2.60042E+00 MeV Emin = 2.64570E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 13 MT = 57 Q = -2.78214E+00 MeV Emin = 2.83058E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 14 MT = 58 Q = -2.86472E+00 MeV Emin = 2.91460E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 15 MT = 59 Q = -2.87646E+00 MeV Emin = 2.92654E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 16 MT = 60 Q = -2.96200E+00 MeV Emin = 3.01357E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 17 MT = 61 Q = -3.08371E+00 MeV Emin = 3.13740E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 18 MT = 62 Q = -3.13500E+00 MeV Emin = 3.18958E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 19 MT = 63 Q = -3.23328E+00 MeV Emin = 3.28958E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 20 MT = 64 Q = -3.24411E+00 MeV Emin = 3.30059E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 21 MT = 65 Q = -3.38300E+00 MeV Emin = 3.44190E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 22 MT = 66 Q = -3.44980E+00 MeV Emin = 3.50987E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 23 MT = 67 Q = -3.53799E+00 MeV Emin = 3.60000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 24 MT = 68 Q = -3.59690E+00 MeV Emin = 3.65953E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 25 MT = 69 Q = -3.62960E+00 MeV Emin = 3.69279E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 26 MT = 70 Q = -3.70300E+00 MeV Emin = 3.76747E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 27 MT = 91 Q = -3.70300E+00 MeV Emin = 3.76747E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 28 MT = 102 Q = 6.58090E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 260590 : (n,gamma) + 29 MT = 103 Q = -5.46424E+00 MeV Emin = 5.80000E+00 MeV frac = 1.00000E+00 Product nuclide = 250580 : (n,p) + 30 MT = 104 Q = -9.72839E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 250570 : (n,d) + 31 MT = 105 Q = -1.21218E+01 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 250560 : (n,t) + 32 MT = 106 Q = -1.37201E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 240560 : (n,He-3) + 33 MT = 107 Q = -1.39914E+00 MeV Emin = 2.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 240550 : (n,alpha) + 34 MT = 108 Q = -9.20049E+00 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 220510 : (n,2alpha) + + 8 additional transport branches: + + 1 MT = 22 Q = -7.64543E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.19530E+01 MeV Emin = 1.21611E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -5.46424E+00 MeV Emin = 5.80000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -9.72839E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -1.21218E+01 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 106 Q = -1.37201E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 7 MT = 107 Q = -1.39914E+00 MeV Emin = 2.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 8 MT = 108 Q = -9.20049E+00 MeV Emin = 1.40000E+01 MeV frac = 2.00000E+00 Product nuclide = 2004.82c : (n,2alpha) + + 48 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 5.80000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.00000E+01 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.25000E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.50000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 2.60000E+00 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 5.62500E-04 MeV : damage-energy production + 7 MT = 600 Q = -5.46424E+00 MeV Emin = 5.80000E+00 MeV : (n,p) to ground state + 8 MT = 601 Q = -5.53602E+00 MeV Emin = 5.80000E+00 MeV : (n,p1) + 9 MT = 602 Q = -5.62424E+00 MeV Emin = 6.00000E+00 MeV : (n,p2) + 10 MT = 603 Q = -5.71924E+00 MeV Emin = 6.00000E+00 MeV : (n,p3) + 11 MT = 604 Q = -5.82544E+00 MeV Emin = 6.20000E+00 MeV : (n,p4) + 12 MT = 605 Q = -5.91247E+00 MeV Emin = 6.20000E+00 MeV : (n,p5) + 13 MT = 606 Q = -5.99944E+00 MeV Emin = 6.40000E+00 MeV : (n,p6) + 14 MT = 607 Q = -6.19230E+00 MeV Emin = 6.40000E+00 MeV : (n,p7) + 15 MT = 608 Q = -6.21914E+00 MeV Emin = 6.60000E+00 MeV : (n,p8) + 16 MT = 609 Q = -6.28424E+00 MeV Emin = 6.60000E+00 MeV : (n,p9) + 17 MT = 610 Q = -6.34574E+00 MeV Emin = 6.60000E+00 MeV : (n,p10) + 18 MT = 649 Q = -6.34574E+00 MeV Emin = 6.60000E+00 MeV : (n,p) to continuum + 19 MT = 650 Q = -9.72839E+00 MeV Emin = 1.00000E+01 MeV : (n,d) to ground state + 20 MT = 651 Q = -9.81158E+00 MeV Emin = 1.00000E+01 MeV : (n,d1) + 21 MT = 652 Q = -1.05785E+01 MeV Emin = 1.07627E+01 MeV : (n,d2) + 22 MT = 653 Q = -1.07842E+01 MeV Emin = 1.10000E+01 MeV : (n,d3) + 23 MT = 654 Q = -1.08013E+01 MeV Emin = 1.10000E+01 MeV : (n,d4) + 24 MT = 655 Q = -1.09559E+01 MeV Emin = 1.15000E+01 MeV : (n,d5) + 25 MT = 699 Q = -1.09559E+01 MeV Emin = 1.15000E+01 MeV : (n,d) to continuum + 26 MT = 700 Q = -1.21218E+01 MeV Emin = 1.25000E+01 MeV : (n,t) to ground state + 27 MT = 701 Q = -1.21484E+01 MeV Emin = 1.25000E+01 MeV : (n,t1) + 28 MT = 702 Q = -1.22323E+01 MeV Emin = 1.25000E+01 MeV : (n,t2) + 29 MT = 703 Q = -1.23338E+01 MeV Emin = 1.25486E+01 MeV : (n,t3) + 30 MT = 704 Q = -1.23369E+01 MeV Emin = 1.25517E+01 MeV : (n,t4) + 31 MT = 705 Q = -1.24573E+01 MeV Emin = 1.30000E+01 MeV : (n,t5) + 32 MT = 749 Q = -1.24573E+01 MeV Emin = 1.30000E+01 MeV : (n,t) to continuum + 33 MT = 750 Q = -1.37201E+01 MeV Emin = 1.50000E+01 MeV : (n,He-3) to ground state + 34 MT = 751 Q = -1.47267E+01 MeV Emin = 1.50000E+01 MeV : (n,He-3_1) + 35 MT = 752 Q = -1.55517E+01 MeV Emin = 1.60000E+01 MeV : (n,He-3_2) + 36 MT = 800 Q = -1.39914E+00 MeV Emin = 2.60000E+00 MeV : (n,alpha) to ground state + 37 MT = 801 Q = -1.64105E+00 MeV Emin = 2.80000E+00 MeV : (n,a1) + 38 MT = 802 Q = -1.91684E+00 MeV Emin = 3.00000E+00 MeV : (n,a2) + 39 MT = 803 Q = -1.96505E+00 MeV Emin = 3.20000E+00 MeV : (n,a3) + 40 MT = 804 Q = -2.27985E+00 MeV Emin = 3.40000E+00 MeV : (n,a4) + 41 MT = 805 Q = -2.53014E+00 MeV Emin = 3.80000E+00 MeV : (n,a5) + 42 MT = 806 Q = -2.61389E+00 MeV Emin = 3.80000E+00 MeV : (n,a6) + 43 MT = 807 Q = -2.83795E+00 MeV Emin = 4.00000E+00 MeV : (n,a7) + 44 MT = 808 Q = -2.87334E+00 MeV Emin = 4.00000E+00 MeV : (n,a8) + 45 MT = 809 Q = -2.87817E+00 MeV Emin = 4.00000E+00 MeV : (n,a9) + 46 MT = 810 Q = -3.40714E+00 MeV Emin = 4.60000E+00 MeV : (n,a10) + 47 MT = 849 Q = -3.40714E+00 MeV Emin = 5.40000E+00 MeV : (n,alpha) to continuum + 48 MT = 4 Q = 0.00000E+00 MeV Emin = 8.20858E-01 MeV : total inelastic scattering + + Nuclide 56 / 1657 : 27059.82c -- cobalt 59 (Co-59) + + Pointers : 329547 22271 + Primary type : Transport + Nuclide ZAI : 270590 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Co59.ACE + Atomic weight (AW) : 58.93317 + Atomic weight ratio (AWR) : 58.42690 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 35 reaction channels + - 7 special reactions + - 14 transmutation reactions + - 14 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 35 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.04540E+01 MeV Emin = 1.06329E+01 MeV frac = 1.00000E+00 Product nuclide = 270580 : (n,2n) + 3 MT = 22 Q = -6.94200E+00 MeV Emin = 1.05000E+01 MeV frac = 1.00000E+00 Product nuclide = 25055.82c : (n,nalpha) + 4 MT = 28 Q = -7.36400E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 26058.82c : (n,np) + 5 MT = 32 Q = -1.51830E+01 MeV Emin = 1.67500E+01 MeV frac = 1.00000E+00 Product nuclide = 26057.82c : (n,nd) + 6 MT = 33 Q = -1.65730E+01 MeV Emin = 1.90000E+01 MeV frac = 1.00000E+00 Product nuclide = 26056.82c : (n,nt) + 7 MT = 51 Q = -1.09990E+00 MeV Emin = 1.11840E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 8 MT = 52 Q = -1.19030E+00 MeV Emin = 1.20980E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 9 MT = 53 Q = -1.29190E+00 MeV Emin = 1.31305E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 10 MT = 54 Q = -1.43400E+00 MeV Emin = 1.45814E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 11 MT = 55 Q = -1.45890E+00 MeV Emin = 1.48330E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 12 MT = 56 Q = -1.48150E+00 MeV Emin = 1.50644E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 13 MT = 57 Q = -1.74450E+00 MeV Emin = 1.77390E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 14 MT = 58 Q = -2.06130E+00 MeV Emin = 2.09658E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 15 MT = 59 Q = -2.08790E+00 MeV Emin = 2.12364E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 16 MT = 60 Q = -2.15280E+00 MeV Emin = 2.18965E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 17 MT = 61 Q = -2.18240E+00 MeV Emin = 2.21975E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 18 MT = 62 Q = -2.20500E+00 MeV Emin = 2.24280E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 19 MT = 63 Q = -2.39500E+00 MeV Emin = 2.43599E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 20 MT = 64 Q = -2.47830E+00 MeV Emin = 2.52072E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 21 MT = 65 Q = -2.54020E+00 MeV Emin = 2.58368E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 22 MT = 66 Q = -2.58420E+00 MeV Emin = 2.62843E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 23 MT = 67 Q = -2.71280E+00 MeV Emin = 2.75923E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 24 MT = 68 Q = -2.78070E+00 MeV Emin = 2.82829E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 25 MT = 69 Q = -2.82520E+00 MeV Emin = 2.87356E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 26 MT = 91 Q = -2.95000E+00 MeV Emin = 3.00049E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 27 MT = 102 Q = 7.49000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 270600 : (n,gamma) + 28 MT = 103 Q = -7.82000E-01 MeV Emin = 1.49900E+00 MeV frac = 1.00000E+00 Product nuclide = 260590 : (n,p) + 29 MT = 104 Q = -5.13900E+00 MeV Emin = 5.22696E+00 MeV frac = 1.00000E+00 Product nuclide = 26058.82c : (n,d) + 30 MT = 105 Q = -8.92700E+00 MeV Emin = 9.07979E+00 MeV frac = 1.00000E+00 Product nuclide = 26057.82c : (n,t) + 31 MT = 106 Q = -1.16000E+01 MeV Emin = 1.17986E+01 MeV frac = 1.00000E+00 Product nuclide = 250570 : (n,He-3) + 32 MT = 107 Q = 3.29000E-01 MeV Emin = 3.90000E+00 MeV frac = 1.00000E+00 Product nuclide = 250560 : (n,alpha) + 33 MT = 108 Q = -7.56600E+00 MeV Emin = 1.82500E+01 MeV frac = 1.00000E+00 Product nuclide = 230520 : (n,2alpha) + 34 MT = 111 Q = -1.29040E+01 MeV Emin = 1.65000E+01 MeV frac = 1.00000E+00 Product nuclide = 250580 : (n,2p) + 35 MT = 112 Q = -8.76400E+00 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 240550 : (n,palpha) + + 14 additional transport branches: + + 1 MT = 22 Q = -6.94200E+00 MeV Emin = 1.05000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -7.36400E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.51830E+01 MeV Emin = 1.67500E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.65730E+01 MeV Emin = 1.90000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 102 Q = 7.49000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 270601 : (n,gamma) + 6 MT = 103 Q = -7.82000E-01 MeV Emin = 1.49900E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 7 MT = 104 Q = -5.13900E+00 MeV Emin = 5.22696E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 8 MT = 105 Q = -8.92700E+00 MeV Emin = 9.07979E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 9 MT = 106 Q = -1.16000E+01 MeV Emin = 1.17986E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 10 MT = 107 Q = 3.29000E-01 MeV Emin = 3.90000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 11 MT = 108 Q = -7.56600E+00 MeV Emin = 1.82500E+01 MeV frac = 2.00000E+00 Product nuclide = 2004.82c : (n,2alpha) + 12 MT = 111 Q = -1.29040E+01 MeV Emin = 1.65000E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + 13 MT = 112 Q = -8.76400E+00 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,palpha) + 14 MT = 112 Q = -8.76400E+00 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,palpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.49900E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.22696E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.07979E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.17986E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 3.90000E+00 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 1.11840E+00 MeV : total inelastic scattering + + Nuclide 57 / 1657 : 28058.82c -- nickel 58 (Ni-58) + + Pointers : 341784 28849 + Primary type : Transport + Nuclide ZAI : 280580 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ni58.ACE + Atomic weight (AW) : 57.93570 + Atomic weight ratio (AWR) : 57.43800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.21E+28 seconds (7E+20 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 20 reaction channels + - 7 special reactions + - 10 transmutation reactions + - 9 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 20 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.22000E+01 MeV Emin = 1.24124E+01 MeV frac = 1.00000E+00 Product nuclide = 280570 : (n,2n) + 3 MT = 22 Q = -6.39800E+00 MeV Emin = 6.50940E+00 MeV frac = 1.00000E+00 Product nuclide = 26054.82c : (n,nalpha) + 4 MT = 28 Q = -8.17100E+00 MeV Emin = 9.23610E+00 MeV frac = 1.00000E+00 Product nuclide = 270570 : (n,np) + 5 MT = 51 Q = -1.45400E+00 MeV Emin = 1.47886E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -2.45900E+00 MeV Emin = 2.50280E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -2.77600E+00 MeV Emin = 2.82840E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -2.90300E+00 MeV Emin = 2.95354E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -2.94300E+00 MeV Emin = 2.99424E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -3.03800E+00 MeV Emin = 3.09090E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -3.26500E+00 MeV Emin = 3.32185E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -3.42100E+00 MeV Emin = 3.48056E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 91 Q = -3.52000E+00 MeV Emin = 3.58540E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 14 MT = 102 Q = 9.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 28059.82c : (n,gamma) + 15 MT = 103 Q = 4.00820E-01 MeV Emin = 3.99858E-01 MeV frac = 1.00000E+00 Product nuclide = 270580 : (n,p) + 16 MT = 104 Q = -5.94630E+00 MeV Emin = 6.04983E+00 MeV frac = 1.00000E+00 Product nuclide = 270570 : (n,d) + 17 MT = 105 Q = -1.10620E+01 MeV Emin = 1.35000E+01 MeV frac = 1.00000E+00 Product nuclide = 270560 : (n,t) + 18 MT = 106 Q = -6.47790E+00 MeV Emin = 1.80000E+01 MeV frac = 1.00000E+00 Product nuclide = 26056.82c : (n,He-3) + 19 MT = 107 Q = 2.90100E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 260550 : (n,alpha) + 20 MT = 112 Q = -6.31340E+00 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 250540 : (n,palpha) + + 9 additional transport branches: + + 1 MT = 22 Q = -6.39800E+00 MeV Emin = 6.50940E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -8.17100E+00 MeV Emin = 9.23610E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = 4.00820E-01 MeV Emin = 3.99858E-01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -5.94630E+00 MeV Emin = 6.04983E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -1.10620E+01 MeV Emin = 1.35000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 106 Q = -6.47790E+00 MeV Emin = 1.80000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 7 MT = 107 Q = 2.90100E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 8 MT = 112 Q = -6.31340E+00 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,palpha) + 9 MT = 112 Q = -6.31340E+00 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,palpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.99858E-01 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.04983E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.35000E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.79543E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 1.47886E+00 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 22 Q = 1.92570E+00 MeV frac = 1.00000E+00 Product nuclide = 26058.82c : EC/beta+ + EC/beta+ + + Nuclide 58 / 1657 : 28059.82c -- nickel 59 (Ni-59) + + Pointers : 344596 28895 + Primary type : Transport + Nuclide ZAI : 280590 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ni59.ACE + Atomic weight (AW) : 58.93438 + Atomic weight ratio (AWR) : 58.42810 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.40E+12 seconds (76,051 years) + Specific ingestion toxicity : 6.30E-11 Sv/Bq + Specific inhalation toxicity : 4.40E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 13 reaction channels + - 7 special reactions + - 12 transmutation reactions + - 10 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 13 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.99720E+00 MeV Emin = 9.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 28058.82c : (n,2n) + 3 MT = 22 Q = -6.09740E+00 MeV Emin = 6.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 260550 : (n,nalpha) + 4 MT = 28 Q = -8.59500E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 270580 : (n,np) + 5 MT = 32 Q = -1.49410E+01 MeV Emin = 1.55000E+01 MeV frac = 1.00000E+00 Product nuclide = 270570 : (n,nd) + 6 MT = 34 Q = -1.54750E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 26056.82c : (n,nHe-3) + 7 MT = 102 Q = 1.12400E+01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 28060.82c : (n,gamma) + 8 MT = 103 Q = 1.58400E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 27059.82c : (n,p) + 9 MT = 104 Q = -6.37090E+00 MeV Emin = 6.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 270580 : (n,d) + 10 MT = 105 Q = -8.68560E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 270570 : (n,t) + 11 MT = 106 Q = -7.83110E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 26057.82c : (n,He-3) + 12 MT = 107 Q = 4.87800E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 26056.82c : (n,alpha) + 13 MT = 111 Q = -5.50560E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 26058.82c : (n,2p) + + 10 additional transport branches: + + 1 MT = 22 Q = -6.09740E+00 MeV Emin = 6.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -8.59500E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.49410E+01 MeV Emin = 1.55000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 34 Q = -1.54750E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,nHe-3) + 5 MT = 103 Q = 1.58400E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 104 Q = -6.37090E+00 MeV Emin = 6.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 7 MT = 105 Q = -8.68560E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 8 MT = 106 Q = -7.83110E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 9 MT = 107 Q = 4.87800E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 10 MT = 111 Q = -5.50560E+00 MeV Emin = 6.00000E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.50000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.00000E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 8.00000E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 3 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : nonelastic + + 1 decay reaction: + + 1 RTYP = 2 Q = 1.07276E+00 MeV frac = 1.00000E+00 Product nuclide = 27059.82c : EC/beta+ + + Nuclide 59 / 1657 : 28060.82c -- nickel 60 (Ni-60) + + Pointers : 347101 28941 + Primary type : Transport + Nuclide ZAI : 280600 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ni60.ACE + Atomic weight (AW) : 59.93079 + Atomic weight ratio (AWR) : 59.41595 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 22 reaction channels + - 7 special reactions + - 9 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 22 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.13850E+01 MeV Emin = 1.16960E+01 MeV frac = 1.00000E+00 Product nuclide = 28059.82c : (n,2n) + 3 MT = 22 Q = -6.29100E+00 MeV Emin = 6.39690E+00 MeV frac = 1.00000E+00 Product nuclide = 26056.82c : (n,nalpha) + 4 MT = 28 Q = -9.52960E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 27059.82c : (n,np) + 5 MT = 51 Q = -1.33300E+00 MeV Emin = 1.35515E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -2.15900E+00 MeV Emin = 2.19540E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -2.28500E+00 MeV Emin = 2.32350E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -2.50600E+00 MeV Emin = 2.54820E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -2.62600E+00 MeV Emin = 2.67020E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -3.12000E+00 MeV Emin = 3.17251E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -3.12400E+00 MeV Emin = 3.17660E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -3.18600E+00 MeV Emin = 3.23962E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -3.19400E+00 MeV Emin = 3.24780E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -3.27000E+00 MeV Emin = 3.32504E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -3.31800E+00 MeV Emin = 3.37385E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 91 Q = -3.33900E+00 MeV Emin = 3.39520E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 17 MT = 102 Q = 7.82000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 28061.82c : (n,gamma) + 18 MT = 103 Q = -2.04150E+00 MeV Emin = 2.20000E+00 MeV frac = 1.00000E+00 Product nuclide = 270600 : (n,p) + 19 MT = 104 Q = -7.30830E+00 MeV Emin = 7.43130E+00 MeV frac = 1.00000E+00 Product nuclide = 27059.82c : (n,d) + 20 MT = 105 Q = -1.15010E+01 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 270580 : (n,t) + 21 MT = 106 Q = -9.17420E+00 MeV Emin = 9.32861E+00 MeV frac = 1.00000E+00 Product nuclide = 26058.82c : (n,He-3) + 22 MT = 107 Q = 1.35530E+00 MeV Emin = 2.55250E+00 MeV frac = 1.00000E+00 Product nuclide = 26057.82c : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -6.29100E+00 MeV Emin = 6.39690E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -9.52960E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -2.04150E+00 MeV Emin = 2.20000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -7.30830E+00 MeV Emin = 7.43130E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -1.15010E+01 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 106 Q = -9.17420E+00 MeV Emin = 9.32861E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 7 MT = 107 Q = 1.35530E+00 MeV Emin = 2.55250E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.20000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.43130E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.39914E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 9.32861E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 2.55240E+00 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 1.35515E+00 MeV : total inelastic scattering + + Nuclide 60 / 1657 : 28061.82c -- nickel 61 (Ni-61) + + Pointers : 349840 28987 + Primary type : Transport + Nuclide ZAI : 280610 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ni61.ACE + Atomic weight (AW) : 60.93143 + Atomic weight ratio (AWR) : 60.40800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 1.50000E+02 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 17 reaction channels + - 6 special reactions + - 6 transmutation reactions + - 4 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 17 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 5 Q = 0.00000E+00 MeV Emin = 2.00000E+01 MeV frac = 1.00000E+00 Product nuclide = self : anything + 3 MT = 16 Q = -7.82030E+00 MeV Emin = 7.94980E+00 MeV frac = 1.00000E+00 Product nuclide = 28060.82c : (n,2n) + 4 MT = 28 Q = -9.86200E+00 MeV Emin = 1.00253E+01 MeV frac = 1.00000E+00 Product nuclide = 270600 : (n,np) + 5 MT = 51 Q = -6.70000E-02 MeV Emin = 6.98727E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -2.83000E-01 MeV Emin = 2.85000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -6.56000E-01 MeV Emin = 6.66610E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -9.09000E-01 MeV Emin = 9.23622E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -1.01500E+00 MeV Emin = 1.03120E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -1.10000E+00 MeV Emin = 1.11788E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -1.13200E+00 MeV Emin = 1.15041E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -1.18500E+00 MeV Emin = 1.20422E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 91 Q = -1.45500E+00 MeV Emin = 1.47871E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 14 MT = 102 Q = 1.05973E+01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 28062.82c : (n,gamma) + 15 MT = 103 Q = -5.39700E-01 MeV Emin = 5.25000E-01 MeV frac = 1.00000E+00 Product nuclide = 270610 : (n,p) + 16 MT = 107 Q = 3.57900E+00 MeV Emin = 6.99363E-02 MeV frac = 1.00000E+00 Product nuclide = 26058.82c : (n,alpha) + 17 MT = 111 Q = -9.28870E+00 MeV Emin = 9.44250E+00 MeV frac = 1.00000E+00 Product nuclide = 260600 : (n,2p) + + 4 additional transport branches: + + 1 MT = 28 Q = -9.86200E+00 MeV Emin = 1.00253E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 2 MT = 103 Q = -5.39700E-01 MeV Emin = 5.25000E-01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 107 Q = 3.57900E+00 MeV Emin = 6.99363E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 4 MT = 111 Q = -9.28870E+00 MeV Emin = 9.44250E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 5.25000E-01 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 2.00000E+01 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 2.00000E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 6.99363E-02 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 6.98727E-02 MeV : total inelastic scattering + + Nuclide 61 / 1657 : 28062.82c -- nickel 62 (Ni-62) + + Pointers : 351922 29033 + Primary type : Transport + Nuclide ZAI : 280620 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ni62.ACE + Atomic weight (AW) : 61.92799 + Atomic weight ratio (AWR) : 61.39600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 1.50000E+02 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 14 reaction channels + - 6 special reactions + - 7 transmutation reactions + - 5 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 14 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 5 Q = 0.00000E+00 MeV Emin = 2.00000E+01 MeV frac = 1.00000E+00 Product nuclide = self : anything + 3 MT = 16 Q = -1.05980E+01 MeV Emin = 1.07710E+01 MeV frac = 1.00000E+00 Product nuclide = 28061.82c : (n,2n) + 4 MT = 22 Q = -7.01860E+00 MeV Emin = 7.13292E+00 MeV frac = 1.00000E+00 Product nuclide = 26058.82c : (n,nalpha) + 5 MT = 28 Q = -1.11380E+01 MeV Emin = 1.13194E+01 MeV frac = 1.00000E+00 Product nuclide = 270610 : (n,np) + 6 MT = 51 Q = -1.17300E+00 MeV Emin = 1.19168E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -2.04900E+00 MeV Emin = 2.08240E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -2.30200E+00 MeV Emin = 2.33950E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -2.33600E+00 MeV Emin = 2.37405E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 91 Q = -2.89100E+00 MeV Emin = 2.93810E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 11 MT = 102 Q = 6.83791E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 280630 : (n,gamma) + 12 MT = 103 Q = -4.45900E+00 MeV Emin = 4.53163E+00 MeV frac = 1.00000E+00 Product nuclide = 270620 : (n,p) + 13 MT = 104 Q = -8.91287E+00 MeV Emin = 9.05804E+00 MeV frac = 1.00000E+00 Product nuclide = 270610 : (n,d) + 14 MT = 107 Q = -4.37400E-01 MeV Emin = 4.44358E-01 MeV frac = 1.00000E+00 Product nuclide = 260590 : (n,alpha) + + 5 additional transport branches: + + 1 MT = 22 Q = -7.01860E+00 MeV Emin = 7.13292E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.11380E+01 MeV Emin = 1.13194E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -4.45900E+00 MeV Emin = 4.53163E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -8.91287E+00 MeV Emin = 9.05804E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 107 Q = -4.37400E-01 MeV Emin = 4.44358E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.53163E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 9.05804E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 2.00000E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 4.44358E-01 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 1.19168E+00 MeV : total inelastic scattering + + Nuclide 62 / 1657 : 28064.82c -- nickel 64 (Ni-64) + + Pointers : 354075 29079 + Primary type : Transport + Nuclide ZAI : 280640 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ni64.ACE + Atomic weight (AW) : 63.92818 + Atomic weight ratio (AWR) : 63.37900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 1.50000E+02 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 12 reaction channels + - 6 special reactions + - 7 transmutation reactions + - 5 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 12 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 5 Q = 0.00000E+00 MeV Emin = 2.00000E+01 MeV frac = 1.00000E+00 Product nuclide = self : anything + 3 MT = 16 Q = -9.65700E+00 MeV Emin = 9.80940E+00 MeV frac = 1.00000E+00 Product nuclide = 280630 : (n,2n) + 4 MT = 22 Q = -8.08200E+00 MeV Emin = 8.20952E+00 MeV frac = 1.00000E+00 Product nuclide = 260600 : (n,nalpha) + 5 MT = 28 Q = -1.25360E+01 MeV Emin = 1.27340E+01 MeV frac = 1.00000E+00 Product nuclide = 270630 : (n,np) + 6 MT = 51 Q = -1.34600E+00 MeV Emin = 1.36647E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -2.27700E+00 MeV Emin = 2.31293E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 91 Q = -2.60800E+00 MeV Emin = 2.64915E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 9 MT = 102 Q = 6.09806E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 280650 : (n,gamma) + 10 MT = 103 Q = -6.52400E+00 MeV Emin = 6.62694E+00 MeV frac = 1.00000E+00 Product nuclide = 270640 : (n,p) + 11 MT = 104 Q = -1.03114E+01 MeV Emin = 1.04741E+01 MeV frac = 1.00000E+00 Product nuclide = 270630 : (n,d) + 12 MT = 107 Q = -2.44200E+00 MeV Emin = 2.48053E+00 MeV frac = 1.00000E+00 Product nuclide = 260610 : (n,alpha) + + 5 additional transport branches: + + 1 MT = 22 Q = -8.08200E+00 MeV Emin = 8.20952E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.25360E+01 MeV Emin = 1.27340E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -6.52400E+00 MeV Emin = 6.62694E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -1.03114E+01 MeV Emin = 1.04741E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 107 Q = -2.44200E+00 MeV Emin = 2.48053E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 6.62694E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.04741E+01 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 2.00000E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 2.48053E+00 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 1.36647E+00 MeV : total inelastic scattering + + Nuclide 63 / 1657 : 29065.82c -- copper 65 (Cu-65) + + Pointers : 360503 22777 + Primary type : Transport + Nuclide ZAI : 290650 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Cu65.ACE + Atomic weight (AW) : 64.92776 + Atomic weight ratio (AWR) : 64.37000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 1.50000E+02 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 25 reaction channels + - 7 special reactions + - 9 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 25 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 5 Q = 0.00000E+00 MeV Emin = 2.00000E+01 MeV frac = 1.00000E+00 Product nuclide = self : anything + 3 MT = 16 Q = -9.91000E+00 MeV Emin = 1.00640E+01 MeV frac = 1.00000E+00 Product nuclide = 290640 : (n,2n) + 4 MT = 22 Q = -6.79000E+00 MeV Emin = 6.89550E+00 MeV frac = 1.00000E+00 Product nuclide = 270610 : (n,nalpha) + 5 MT = 28 Q = -7.45000E+00 MeV Emin = 7.56574E+00 MeV frac = 1.00000E+00 Product nuclide = 28064.82c : (n,np) + 6 MT = 51 Q = -7.71000E-01 MeV Emin = 7.82600E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.11600E+00 MeV Emin = 1.13262E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -1.48200E+00 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -1.62300E+00 MeV Emin = 1.64101E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -1.72500E+00 MeV Emin = 1.75000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -2.09400E+00 MeV Emin = 2.12653E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -2.10800E+00 MeV Emin = 2.14075E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -2.21300E+00 MeV Emin = 2.24740E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -2.27800E+00 MeV Emin = 2.31340E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -2.32700E+00 MeV Emin = 2.36320E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -2.40700E+00 MeV Emin = 2.44440E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -2.53300E+00 MeV Emin = 2.57240E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -2.53400E+00 MeV Emin = 2.57340E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 91 Q = -2.59400E+00 MeV Emin = 2.63430E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 20 MT = 102 Q = 7.06599E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 290660 : (n,gamma) + 21 MT = 103 Q = -1.35400E+00 MeV Emin = 1.37254E+00 MeV frac = 1.00000E+00 Product nuclide = 280650 : (n,p) + 22 MT = 104 Q = -5.22800E+00 MeV Emin = 5.30922E+00 MeV frac = 1.00000E+00 Product nuclide = 28064.82c : (n,d) + 23 MT = 105 Q = -8.62200E+00 MeV Emin = 8.75595E+00 MeV frac = 1.00000E+00 Product nuclide = 280630 : (n,t) + 24 MT = 106 Q = -1.22710E+01 MeV Emin = 1.24620E+01 MeV frac = 1.00000E+00 Product nuclide = 270630 : (n,He-3) + 25 MT = 107 Q = -1.10000E-01 MeV Emin = 1.11699E-01 MeV frac = 1.00000E+00 Product nuclide = 270620 : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -6.79000E+00 MeV Emin = 6.89550E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -7.45000E+00 MeV Emin = 7.56574E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -1.35400E+00 MeV Emin = 1.37254E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -5.22800E+00 MeV Emin = 5.30922E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -8.62200E+00 MeV Emin = 8.75595E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 106 Q = -1.22710E+01 MeV Emin = 1.24620E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 7 MT = 107 Q = -1.10000E-01 MeV Emin = 1.11699E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.37254E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.30922E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 8.75595E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.24620E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.11699E-01 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 7.82600E-01 MeV : total inelastic scattering + + Nuclide 64 / 1657 : 32070.82c -- germanium 70 (Ge-70) + + Pointers : 400688 24617 + Primary type : Transport + Nuclide ZAI : 320700 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ge70.ACE + Atomic weight (AW) : 69.92426 + Atomic weight ratio (AWR) : 69.32357 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+02 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 42 reaction channels + - 52 special reactions + - 19 transmutation reactions + - 21 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 42 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 5 Q = 0.00000E+00 MeV Emin = 1.49811E-02 MeV frac = 1.00000E+00 Product nuclide = self : anything + 3 MT = 16 Q = -1.15380E+01 MeV Emin = 1.17044E+01 MeV frac = 1.00000E+00 Product nuclide = 320690 : (n,2n) + 4 MT = 22 Q = -4.08893E+00 MeV Emin = 5.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 300660 : (n,nalpha) + 5 MT = 24 Q = -1.51488E+01 MeV Emin = 1.70000E+01 MeV frac = 1.00000E+00 Product nuclide = 300650 : (n,2nalpha) + 6 MT = 28 Q = -8.52837E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 310690 : (n,np) + 7 MT = 29 Q = -8.66746E+00 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 28062.82c : (n,n2alpha) + 8 MT = 32 Q = -1.66131E+01 MeV Emin = 1.70000E+01 MeV frac = 1.00000E+00 Product nuclide = 310680 : (n,nd) + 9 MT = 44 Q = -1.51342E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 300680 : (n,n2p) + 10 MT = 45 Q = -1.30145E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 29065.82c : (n,npalpha) + 11 MT = 51 Q = -1.03925E+00 MeV Emin = 1.02712E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 12 MT = 52 Q = -1.21541E+00 MeV Emin = 1.20000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 13 MT = 53 Q = -1.70790E+00 MeV Emin = 1.73125E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 14 MT = 54 Q = -2.15350E+00 MeV Emin = 2.18457E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 15 MT = 55 Q = -2.15740E+00 MeV Emin = 2.18852E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 16 MT = 56 Q = -2.30690E+00 MeV Emin = 2.34018E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 17 MT = 57 Q = -2.45150E+00 MeV Emin = 2.48686E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 18 MT = 58 Q = -2.53570E+00 MeV Emin = 2.57228E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 19 MT = 59 Q = -2.56140E+00 MeV Emin = 2.59835E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 20 MT = 60 Q = -2.80670E+00 MeV Emin = 2.84719E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 21 MT = 61 Q = -2.88780E+00 MeV Emin = 2.92946E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 22 MT = 62 Q = -2.94520E+00 MeV Emin = 2.98769E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 23 MT = 63 Q = -3.04680E+00 MeV Emin = 3.09075E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 24 MT = 64 Q = -3.05890E+00 MeV Emin = 3.10303E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 25 MT = 65 Q = -3.10700E+00 MeV Emin = 3.15182E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 26 MT = 66 Q = -3.18040E+00 MeV Emin = 3.22628E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 27 MT = 67 Q = -3.19420E+00 MeV Emin = 3.24028E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 28 MT = 68 Q = -3.24200E+00 MeV Emin = 3.28877E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 29 MT = 69 Q = -3.29610E+00 MeV Emin = 3.34365E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 30 MT = 70 Q = -3.29730E+00 MeV Emin = 3.34486E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 31 MT = 91 Q = -3.29730E+00 MeV Emin = 3.34486E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 32 MT = 102 Q = 7.41590E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 320710 : (n,gamma) + 33 MT = 103 Q = -8.73261E-01 MeV Emin = 1.20000E+00 MeV frac = 1.00000E+00 Product nuclide = 310700 : (n,p) + 34 MT = 104 Q = -6.30379E+00 MeV Emin = 6.80000E+00 MeV frac = 1.00000E+00 Product nuclide = 310690 : (n,d) + 35 MT = 105 Q = -1.03559E+01 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 310680 : (n,t) + 36 MT = 106 Q = -7.41617E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 300680 : (n,He-3) + 37 MT = 107 Q = 2.96325E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 300670 : (n,alpha) + 38 MT = 108 Q = -1.82960E+00 MeV Emin = 7.40000E+00 MeV frac = 1.00000E+00 Product nuclide = 280630 : (n,2alpha) + 39 MT = 111 Q = -8.65201E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 300690 : (n,2p) + 40 MT = 112 Q = -5.94855E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 290660 : (n,palpha) + 41 MT = 115 Q = -1.29097E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 300680 : (n,pd) + 42 MT = 117 Q = -1.07899E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 29065.82c : (n,dalpha) + + 21 additional transport branches: + + 1 MT = 22 Q = -4.08893E+00 MeV Emin = 5.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 24 Q = -1.51488E+01 MeV Emin = 1.70000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,2nalpha) + 3 MT = 28 Q = -8.52837E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 4 MT = 29 Q = -8.66746E+00 MeV Emin = 1.40000E+01 MeV frac = 2.00000E+00 Product nuclide = 2004.82c : (n,n2alpha) + 5 MT = 32 Q = -1.66131E+01 MeV Emin = 1.70000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 6 MT = 44 Q = -1.51342E+01 MeV Emin = 1.60000E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,n2p) + 7 MT = 45 Q = -1.30145E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,npalpha) + 8 MT = 45 Q = -1.30145E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,npalpha) + 9 MT = 103 Q = -8.73261E-01 MeV Emin = 1.20000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 10 MT = 104 Q = -6.30379E+00 MeV Emin = 6.80000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 11 MT = 105 Q = -1.03559E+01 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 12 MT = 106 Q = -7.41617E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 13 MT = 107 Q = 2.96325E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 14 MT = 108 Q = -1.82960E+00 MeV Emin = 7.40000E+00 MeV frac = 2.00000E+00 Product nuclide = 2004.82c : (n,2alpha) + 15 MT = 111 Q = -8.65201E+00 MeV Emin = 1.00000E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + 16 MT = 112 Q = -5.94855E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,palpha) + 17 MT = 112 Q = -5.94855E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,palpha) + 18 MT = 115 Q = -1.29097E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,pd) + 19 MT = 115 Q = -1.29097E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,pd) + 20 MT = 117 Q = -1.07899E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,dalpha) + 21 MT = 117 Q = -1.07899E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,dalpha) + + 52 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.20000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.80000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.10000E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 9.00000E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 600 Q = -8.73261E-01 MeV Emin = 1.20000E+00 MeV : (n,p) to ground state + 8 MT = 601 Q = -1.38146E+00 MeV Emin = 1.77500E+00 MeV : (n,p1) + 9 MT = 602 Q = -1.52436E+00 MeV Emin = 1.80113E+00 MeV : (n,p2) + 10 MT = 603 Q = -1.56416E+00 MeV Emin = 1.81420E+00 MeV : (n,p3) + 11 MT = 604 Q = -1.75236E+00 MeV Emin = 2.00000E+00 MeV : (n,p4) + 12 MT = 605 Q = -1.77466E+00 MeV Emin = 2.20000E+00 MeV : (n,p5) + 13 MT = 606 Q = -1.86876E+00 MeV Emin = 2.20000E+00 MeV : (n,p6) + 14 MT = 607 Q = -1.87586E+00 MeV Emin = 2.20000E+00 MeV : (n,p7) + 15 MT = 608 Q = -1.88246E+00 MeV Emin = 2.20000E+00 MeV : (n,p8) + 16 MT = 609 Q = -1.88266E+00 MeV Emin = 2.20000E+00 MeV : (n,p9) + 17 MT = 610 Q = -1.88816E+00 MeV Emin = 2.20000E+00 MeV : (n,p10) + 18 MT = 649 Q = -1.88816E+00 MeV Emin = 2.20000E+00 MeV : (n,p) to continuum + 19 MT = 650 Q = -6.30379E+00 MeV Emin = 6.80000E+00 MeV : (n,d) to ground state + 20 MT = 651 Q = -6.62248E+00 MeV Emin = 7.00000E+00 MeV : (n,d1) + 21 MT = 652 Q = -6.87800E+00 MeV Emin = 7.40000E+00 MeV : (n,d2) + 22 MT = 653 Q = -7.17592E+00 MeV Emin = 7.60000E+00 MeV : (n,d3) + 23 MT = 654 Q = -7.33237E+00 MeV Emin = 7.80000E+00 MeV : (n,d4) + 24 MT = 655 Q = -7.41082E+00 MeV Emin = 8.00000E+00 MeV : (n,d5) + 25 MT = 699 Q = -7.41082E+00 MeV Emin = 8.00000E+00 MeV : (n,d) to continuum + 26 MT = 700 Q = -1.03559E+01 MeV Emin = 1.10000E+01 MeV : (n,t) to ground state + 27 MT = 701 Q = -1.05309E+01 MeV Emin = 1.10000E+01 MeV : (n,t1) + 28 MT = 702 Q = -1.06768E+01 MeV Emin = 1.10000E+01 MeV : (n,t2) + 29 MT = 703 Q = -1.07304E+01 MeV Emin = 1.15000E+01 MeV : (n,t3) + 30 MT = 704 Q = -1.07314E+01 MeV Emin = 1.15000E+01 MeV : (n,t4) + 31 MT = 705 Q = -1.08520E+01 MeV Emin = 1.15000E+01 MeV : (n,t5) + 32 MT = 749 Q = -1.08520E+01 MeV Emin = 1.15000E+01 MeV : (n,t) to continuum + 33 MT = 750 Q = -7.41617E+00 MeV Emin = 9.00000E+00 MeV : (n,He-3) to ground state + 34 MT = 751 Q = -8.49354E+00 MeV Emin = 9.50000E+00 MeV : (n,He-3_1) + 35 MT = 752 Q = -9.07211E+00 MeV Emin = 1.05000E+01 MeV : (n,He-3_2) + 36 MT = 753 Q = -9.29931E+00 MeV Emin = 1.10000E+01 MeV : (n,He-3_3) + 37 MT = 754 Q = -9.75446E+00 MeV Emin = 1.15000E+01 MeV : (n,He-3_4) + 38 MT = 755 Q = -9.78647E+00 MeV Emin = 1.15000E+01 MeV : (n,He-3_5) + 39 MT = 799 Q = -9.78647E+00 MeV Emin = 1.20000E+01 MeV : (n,He-3) to continuum + 40 MT = 800 Q = 2.96325E+00 MeV Emin = 1.00000E-11 MeV : (n,alpha) to ground state + 41 MT = 801 Q = 2.86994E+00 MeV Emin = 1.00000E-11 MeV : (n,a1) + 42 MT = 802 Q = 2.77867E+00 MeV Emin = 1.00000E-11 MeV : (n,a2) + 43 MT = 803 Q = 2.56972E+00 MeV Emin = 1.00000E-11 MeV : (n,a3) + 44 MT = 804 Q = 2.35876E+00 MeV Emin = 1.00000E-11 MeV : (n,a4) + 45 MT = 805 Q = 2.14848E+00 MeV Emin = 1.00000E-11 MeV : (n,a5) + 46 MT = 806 Q = 2.09234E+00 MeV Emin = 1.00000E-11 MeV : (n,a6) + 47 MT = 807 Q = 2.07555E+00 MeV Emin = 1.00000E-11 MeV : (n,a7) + 48 MT = 808 Q = 1.98341E+00 MeV Emin = 1.00000E-11 MeV : (n,a8) + 49 MT = 809 Q = 1.97325E+00 MeV Emin = 1.00000E-11 MeV : (n,a9) + 50 MT = 810 Q = 1.90325E+00 MeV Emin = 1.00000E-11 MeV : (n,a10) + 51 MT = 849 Q = 1.90325E+00 MeV Emin = 1.00000E-11 MeV : (n,alpha) to continuum + 52 MT = 4 Q = 0.00000E+00 MeV Emin = 1.02712E+00 MeV : total inelastic scattering + + Nuclide 65 / 1657 : 32072.82c -- germanium 72 (Ge-72) + + Pointers : 409936 24663 + Primary type : Transport + Nuclide ZAI : 320720 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ge72.ACE + Atomic weight (AW) : 71.92209 + Atomic weight ratio (AWR) : 71.30424 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+02 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 38 reaction channels + - 52 special reactions + - 15 transmutation reactions + - 14 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 38 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 5 Q = 0.00000E+00 MeV Emin = 3.99702E-02 MeV frac = 1.00000E+00 Product nuclide = self : anything + 3 MT = 16 Q = -1.07520E+01 MeV Emin = 1.09028E+01 MeV frac = 1.00000E+00 Product nuclide = 320710 : (n,2n) + 4 MT = 17 Q = -1.81679E+01 MeV Emin = 1.84227E+01 MeV frac = 1.00000E+00 Product nuclide = 32070.82c : (n,3n) + 5 MT = 22 Q = -5.00644E+00 MeV Emin = 6.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 300680 : (n,nalpha) + 6 MT = 24 Q = -1.52046E+01 MeV Emin = 1.70000E+01 MeV frac = 1.00000E+00 Product nuclide = 300670 : (n,2nalpha) + 7 MT = 28 Q = -9.73771E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 310710 : (n,np) + 8 MT = 32 Q = -1.68166E+01 MeV Emin = 1.70525E+01 MeV frac = 1.00000E+00 Product nuclide = 310700 : (n,nd) + 9 MT = 51 Q = -6.91430E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 10 MT = 52 Q = -8.34011E-01 MeV Emin = 8.43750E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 11 MT = 53 Q = -1.46399E+00 MeV Emin = 1.45811E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 12 MT = 54 Q = -1.72830E+00 MeV Emin = 1.73612E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 13 MT = 55 Q = -2.02900E+00 MeV Emin = 2.05746E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 14 MT = 56 Q = -2.04900E+00 MeV Emin = 2.07774E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 15 MT = 57 Q = -2.06493E+00 MeV Emin = 2.09389E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 16 MT = 58 Q = -2.39610E+00 MeV Emin = 2.42970E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 17 MT = 59 Q = -2.40230E+00 MeV Emin = 2.43599E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 18 MT = 60 Q = -2.46390E+00 MeV Emin = 2.49846E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 19 MT = 61 Q = -2.50500E+00 MeV Emin = 2.54013E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 20 MT = 62 Q = -2.51479E+00 MeV Emin = 2.55006E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 21 MT = 63 Q = -2.57200E+00 MeV Emin = 2.60807E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 22 MT = 64 Q = -2.58350E+00 MeV Emin = 2.61973E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 23 MT = 65 Q = -2.75426E+00 MeV Emin = 2.79289E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 24 MT = 66 Q = -2.77211E+00 MeV Emin = 2.81099E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 25 MT = 67 Q = -2.87561E+00 MeV Emin = 2.91594E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 26 MT = 68 Q = -2.89700E+00 MeV Emin = 2.93763E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 27 MT = 69 Q = -2.93996E+00 MeV Emin = 2.98119E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 28 MT = 70 Q = -2.94347E+00 MeV Emin = 2.98475E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 29 MT = 91 Q = -2.94347E+00 MeV Emin = 2.98475E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 30 MT = 102 Q = 6.78290E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 32073.82c : (n,gamma) + 31 MT = 103 Q = -3.21671E+00 MeV Emin = 3.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 310720 : (n,p) + 32 MT = 104 Q = -7.51313E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 310710 : (n,d) + 33 MT = 105 Q = -1.05593E+01 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 310700 : (n,t) + 34 MT = 106 Q = -9.88601E+00 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 300700 : (n,He-3) + 35 MT = 107 Q = 1.47578E+00 MeV Emin = 5.25000E-01 MeV frac = 1.00000E+00 Product nuclide = 300690 : (n,alpha) + 36 MT = 108 Q = -4.24147E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 280650 : (n,2alpha) + 37 MT = 111 Q = -1.17705E+01 MeV Emin = 1.35000E+01 MeV frac = 1.00000E+00 Product nuclide = 300710 : (n,2p) + 38 MT = 112 Q = -8.68623E+00 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 290680 : (n,palpha) + + 14 additional transport branches: + + 1 MT = 22 Q = -5.00644E+00 MeV Emin = 6.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 24 Q = -1.52046E+01 MeV Emin = 1.70000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,2nalpha) + 3 MT = 28 Q = -9.73771E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 4 MT = 32 Q = -1.68166E+01 MeV Emin = 1.70525E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 5 MT = 102 Q = 6.78290E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 320731 : (n,gamma) + 6 MT = 103 Q = -3.21671E+00 MeV Emin = 3.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 7 MT = 104 Q = -7.51313E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 8 MT = 105 Q = -1.05593E+01 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 9 MT = 106 Q = -9.88601E+00 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 10 MT = 107 Q = 1.47578E+00 MeV Emin = 5.25000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 11 MT = 108 Q = -4.24147E+00 MeV Emin = 1.00000E+01 MeV frac = 2.00000E+00 Product nuclide = 2004.82c : (n,2alpha) + 12 MT = 111 Q = -1.17705E+01 MeV Emin = 1.35000E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + 13 MT = 112 Q = -8.68623E+00 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,palpha) + 14 MT = 112 Q = -8.68623E+00 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,palpha) + + 52 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.60000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.10000E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.20000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 5.25000E-01 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 4.34147E-04 MeV : damage-energy production + 7 MT = 600 Q = -3.21671E+00 MeV Emin = 3.60000E+00 MeV : (n,p) to ground state + 8 MT = 601 Q = -3.23315E+00 MeV Emin = 3.60000E+00 MeV : (n,p1) + 9 MT = 602 Q = -3.33637E+00 MeV Emin = 3.60000E+00 MeV : (n,p2) + 10 MT = 603 Q = -3.34550E+00 MeV Emin = 3.60000E+00 MeV : (n,p3) + 11 MT = 604 Q = -3.37824E+00 MeV Emin = 3.80000E+00 MeV : (n,p4) + 12 MT = 605 Q = -3.38222E+00 MeV Emin = 3.80000E+00 MeV : (n,p5) + 13 MT = 606 Q = -3.41465E+00 MeV Emin = 3.80000E+00 MeV : (n,p6) + 14 MT = 607 Q = -3.42516E+00 MeV Emin = 3.80000E+00 MeV : (n,p7) + 15 MT = 608 Q = -3.44557E+00 MeV Emin = 3.80000E+00 MeV : (n,p8) + 16 MT = 609 Q = -3.46565E+00 MeV Emin = 3.80000E+00 MeV : (n,p9) + 17 MT = 610 Q = -3.48861E+00 MeV Emin = 3.80000E+00 MeV : (n,p10) + 18 MT = 649 Q = -3.48861E+00 MeV Emin = 3.80000E+00 MeV : (n,p) to continuum + 19 MT = 650 Q = -7.51313E+00 MeV Emin = 8.00000E+00 MeV : (n,d) to ground state + 20 MT = 651 Q = -7.90315E+00 MeV Emin = 8.01399E+00 MeV : (n,d1) + 21 MT = 652 Q = -8.00042E+00 MeV Emin = 8.50000E+00 MeV : (n,d2) + 22 MT = 653 Q = -8.02466E+00 MeV Emin = 8.50000E+00 MeV : (n,d3) + 23 MT = 654 Q = -8.22713E+00 MeV Emin = 8.50000E+00 MeV : (n,d4) + 24 MT = 655 Q = -8.42324E+00 MeV Emin = 9.00000E+00 MeV : (n,d5) + 25 MT = 699 Q = -8.42324E+00 MeV Emin = 9.00000E+00 MeV : (n,d) to continuum + 26 MT = 700 Q = -1.05593E+01 MeV Emin = 1.10000E+01 MeV : (n,t) to ground state + 27 MT = 701 Q = -1.10675E+01 MeV Emin = 1.15000E+01 MeV : (n,t1) + 28 MT = 702 Q = -1.12104E+01 MeV Emin = 1.20000E+01 MeV : (n,t2) + 29 MT = 703 Q = -1.12502E+01 MeV Emin = 1.20000E+01 MeV : (n,t3) + 30 MT = 704 Q = -1.14384E+01 MeV Emin = 1.20000E+01 MeV : (n,t4) + 31 MT = 705 Q = -1.14607E+01 MeV Emin = 1.20000E+01 MeV : (n,t5) + 32 MT = 749 Q = -1.14607E+01 MeV Emin = 1.25000E+01 MeV : (n,t) to continuum + 33 MT = 750 Q = -9.88601E+00 MeV Emin = 1.20000E+01 MeV : (n,He-3) to ground state + 34 MT = 751 Q = -1.07708E+01 MeV Emin = 1.25000E+01 MeV : (n,He-3_1) + 35 MT = 752 Q = -1.09543E+01 MeV Emin = 1.30000E+01 MeV : (n,He-3_2) + 36 MT = 753 Q = -1.14400E+01 MeV Emin = 1.30000E+01 MeV : (n,He-3_3) + 37 MT = 754 Q = -1.16451E+01 MeV Emin = 1.35000E+01 MeV : (n,He-3_4) + 38 MT = 755 Q = -1.16725E+01 MeV Emin = 1.35000E+01 MeV : (n,He-3_5) + 39 MT = 799 Q = -1.16725E+01 MeV Emin = 1.40000E+01 MeV : (n,He-3) to continuum + 40 MT = 800 Q = 1.47578E+00 MeV Emin = 5.25000E-01 MeV : (n,alpha) to ground state + 41 MT = 801 Q = 1.03714E+00 MeV Emin = 1.03438E+00 MeV : (n,a1) + 42 MT = 802 Q = 9.44482E-01 MeV Emin = 1.10000E+00 MeV : (n,a2) + 43 MT = 803 Q = 6.41322E-01 MeV Emin = 1.42905E+00 MeV : (n,a3) + 44 MT = 804 Q = 6.03782E-01 MeV Emin = 1.50000E+00 MeV : (n,a4) + 45 MT = 805 Q = 5.08782E-01 MeV Emin = 1.60000E+00 MeV : (n,a5) + 46 MT = 806 Q = 4.68122E-01 MeV Emin = 1.66719E+00 MeV : (n,a6) + 47 MT = 807 Q = 3.39782E-01 MeV Emin = 1.85000E+00 MeV : (n,a7) + 48 MT = 808 Q = 2.95052E-01 MeV Emin = 1.80000E+00 MeV : (n,a8) + 49 MT = 809 Q = 2.51782E-01 MeV Emin = 2.00000E+00 MeV : (n,a9) + 50 MT = 810 Q = 2.24112E-01 MeV Emin = 1.95000E+00 MeV : (n,a10) + 51 MT = 849 Q = 2.24112E-01 MeV Emin = 1.95000E+00 MeV : (n,alpha) to continuum + 52 MT = 4 Q = 0.00000E+00 MeV Emin = 7.00000E-01 MeV : total inelastic scattering + + Nuclide 66 / 1657 : 32073.82c -- germanium 73 (Ge-73) + + Pointers : 417658 24709 + Primary type : Transport + Nuclide ZAI : 320730 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ge73.ACE + Atomic weight (AW) : 72.92347 + Atomic weight ratio (AWR) : 72.29702 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+02 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 40 reaction channels + - 52 special reactions + - 17 transmutation reactions + - 15 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 40 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 5 Q = 0.00000E+00 MeV Emin = 8.51279E-03 MeV frac = 1.00000E+00 Product nuclide = self : anything + 3 MT = 16 Q = -6.78290E+00 MeV Emin = 6.87672E+00 MeV frac = 1.00000E+00 Product nuclide = 32072.82c : (n,2n) + 4 MT = 17 Q = -1.75349E+01 MeV Emin = 1.77775E+01 MeV frac = 1.00000E+00 Product nuclide = 320710 : (n,3n) + 5 MT = 22 Q = -5.30712E+00 MeV Emin = 7.20000E+00 MeV frac = 1.00000E+00 Product nuclide = 300690 : (n,nalpha) + 6 MT = 24 Q = -1.17893E+01 MeV Emin = 1.35000E+01 MeV frac = 1.00000E+00 Product nuclide = 300680 : (n,2nalpha) + 7 MT = 28 Q = -9.99961E+00 MeV Emin = 1.05000E+01 MeV frac = 1.00000E+00 Product nuclide = 310720 : (n,np) + 8 MT = 32 Q = -1.42960E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 310710 : (n,nd) + 9 MT = 33 Q = -1.73422E+01 MeV Emin = 1.80000E+01 MeV frac = 1.00000E+00 Product nuclide = 310700 : (n,nt) + 10 MT = 41 Q = -1.65206E+01 MeV Emin = 1.70000E+01 MeV frac = 1.00000E+00 Product nuclide = 310710 : (n,2np) + 11 MT = 51 Q = -1.32750E-02 MeV Emin = 1.25939E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 12 MT = 52 Q = -6.67160E-02 MeV Emin = 6.38194E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 13 MT = 53 Q = -6.87520E-02 MeV Emin = 6.86709E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 14 MT = 54 Q = -3.53560E-01 MeV Emin = 3.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 15 MT = 55 Q = -3.64020E-01 MeV Emin = 3.63753E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 16 MT = 56 Q = -3.92450E-01 MeV Emin = 3.83467E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 17 MT = 57 Q = -4.99110E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 18 MT = 58 Q = -5.01450E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 19 MT = 59 Q = -5.51000E-01 MeV Emin = 5.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 20 MT = 60 Q = -5.54910E-01 MeV Emin = 5.60603E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 21 MT = 61 Q = -5.97620E-01 MeV Emin = 6.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 22 MT = 62 Q = -6.59000E-01 MeV Emin = 6.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 23 MT = 63 Q = -7.41700E-01 MeV Emin = 7.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 24 MT = 64 Q = -7.77000E-01 MeV Emin = 7.69853E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 25 MT = 65 Q = -8.09000E-01 MeV Emin = 8.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 26 MT = 66 Q = -8.20000E-01 MeV Emin = 8.26750E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 27 MT = 67 Q = -8.25770E-01 MeV Emin = 8.36007E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 28 MT = 68 Q = -8.68040E-01 MeV Emin = 8.72506E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 29 MT = 69 Q = -8.94100E-01 MeV Emin = 9.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 30 MT = 70 Q = -9.04000E-01 MeV Emin = 9.11486E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 31 MT = 91 Q = -9.04000E-01 MeV Emin = 9.11486E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 32 MT = 102 Q = 1.01962E+01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 32074.82c : (n,gamma) + 33 MT = 103 Q = -8.10941E-01 MeV Emin = 1.20000E+00 MeV frac = 1.00000E+00 Product nuclide = 310730 : (n,p) + 34 MT = 104 Q = -7.77504E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 310720 : (n,d) + 35 MT = 105 Q = -8.03879E+00 MeV Emin = 8.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 310710 : (n,t) + 36 MT = 106 Q = -1.08353E+01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 300710 : (n,He-3) + 37 MT = 107 Q = 3.90870E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 300700 : (n,alpha) + 38 MT = 108 Q = -2.04691E+00 MeV Emin = 8.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 280660 : (n,2alpha) + 39 MT = 111 Q = -9.67534E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 300720 : (n,2p) + 40 MT = 112 Q = -7.19978E+00 MeV Emin = 1.05000E+01 MeV frac = 1.00000E+00 Product nuclide = 290690 : (n,palpha) + + 15 additional transport branches: + + 1 MT = 22 Q = -5.30712E+00 MeV Emin = 7.20000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 24 Q = -1.17893E+01 MeV Emin = 1.35000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,2nalpha) + 3 MT = 28 Q = -9.99961E+00 MeV Emin = 1.05000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 4 MT = 32 Q = -1.42960E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 5 MT = 33 Q = -1.73422E+01 MeV Emin = 1.80000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 6 MT = 41 Q = -1.65206E+01 MeV Emin = 1.70000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,2np) + 7 MT = 103 Q = -8.10941E-01 MeV Emin = 1.20000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 8 MT = 104 Q = -7.77504E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 9 MT = 105 Q = -8.03879E+00 MeV Emin = 8.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 10 MT = 106 Q = -1.08353E+01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 11 MT = 107 Q = 3.90870E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 12 MT = 108 Q = -2.04691E+00 MeV Emin = 8.50000E+00 MeV frac = 2.00000E+00 Product nuclide = 2004.82c : (n,2alpha) + 13 MT = 111 Q = -9.67534E+00 MeV Emin = 1.10000E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + 14 MT = 112 Q = -7.19978E+00 MeV Emin = 1.05000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,palpha) + 15 MT = 112 Q = -7.19978E+00 MeV Emin = 1.05000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,palpha) + + 52 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.20000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 8.50000E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.30000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 600 Q = -8.10941E-01 MeV Emin = 1.20000E+00 MeV : (n,p) to ground state + 8 MT = 601 Q = -1.00894E+00 MeV Emin = 1.40000E+00 MeV : (n,p1) + 9 MT = 602 Q = -1.02889E+00 MeV Emin = 1.40000E+00 MeV : (n,p2) + 10 MT = 603 Q = -1.30676E+00 MeV Emin = 1.60625E+00 MeV : (n,p3) + 11 MT = 604 Q = -1.72191E+00 MeV Emin = 2.00000E+00 MeV : (n,p4) + 12 MT = 605 Q = -1.76694E+00 MeV Emin = 2.00000E+00 MeV : (n,p5) + 13 MT = 606 Q = -1.92794E+00 MeV Emin = 2.20000E+00 MeV : (n,p6) + 14 MT = 607 Q = -2.04594E+00 MeV Emin = 2.40000E+00 MeV : (n,p7) + 15 MT = 608 Q = -2.20694E+00 MeV Emin = 2.40000E+00 MeV : (n,p8) + 16 MT = 609 Q = -2.33894E+00 MeV Emin = 2.60000E+00 MeV : (n,p9) + 17 MT = 610 Q = -2.38894E+00 MeV Emin = 2.80000E+00 MeV : (n,p10) + 18 MT = 649 Q = -2.38894E+00 MeV Emin = 3.00000E+00 MeV : (n,p) to continuum + 19 MT = 650 Q = -7.77504E+00 MeV Emin = 8.00000E+00 MeV : (n,d) to ground state + 20 MT = 651 Q = -7.79148E+00 MeV Emin = 8.00000E+00 MeV : (n,d1) + 21 MT = 652 Q = -7.89470E+00 MeV Emin = 8.50000E+00 MeV : (n,d2) + 22 MT = 653 Q = -7.90383E+00 MeV Emin = 8.50000E+00 MeV : (n,d3) + 23 MT = 654 Q = -7.93657E+00 MeV Emin = 8.50000E+00 MeV : (n,d4) + 24 MT = 655 Q = -7.94055E+00 MeV Emin = 8.50000E+00 MeV : (n,d5) + 25 MT = 699 Q = -7.94055E+00 MeV Emin = 8.50000E+00 MeV : (n,d) to continuum + 26 MT = 700 Q = -8.03879E+00 MeV Emin = 8.50000E+00 MeV : (n,t) to ground state + 27 MT = 701 Q = -8.42881E+00 MeV Emin = 9.00000E+00 MeV : (n,t1) + 28 MT = 702 Q = -8.52607E+00 MeV Emin = 9.00000E+00 MeV : (n,t2) + 29 MT = 703 Q = -8.55031E+00 MeV Emin = 9.00000E+00 MeV : (n,t3) + 30 MT = 704 Q = -8.75279E+00 MeV Emin = 9.00000E+00 MeV : (n,t4) + 31 MT = 705 Q = -8.94890E+00 MeV Emin = 9.50000E+00 MeV : (n,t5) + 32 MT = 749 Q = -8.94890E+00 MeV Emin = 9.50000E+00 MeV : (n,t) to continuum + 33 MT = 750 Q = -1.08353E+01 MeV Emin = 1.30000E+01 MeV : (n,He-3) to ground state + 34 MT = 751 Q = -1.09930E+01 MeV Emin = 1.30000E+01 MeV : (n,He-3_1) + 35 MT = 752 Q = -1.11216E+01 MeV Emin = 1.30000E+01 MeV : (n,He-3_2) + 36 MT = 753 Q = -1.13003E+01 MeV Emin = 1.30000E+01 MeV : (n,He-3_3) + 37 MT = 754 Q = -1.13251E+01 MeV Emin = 1.35000E+01 MeV : (n,He-3_4) + 38 MT = 755 Q = -1.15100E+01 MeV Emin = 1.35000E+01 MeV : (n,He-3_5) + 39 MT = 799 Q = -1.15100E+01 MeV Emin = 1.40000E+01 MeV : (n,He-3) to continuum + 40 MT = 800 Q = 3.90870E+00 MeV Emin = 1.00000E-11 MeV : (n,alpha) to ground state + 41 MT = 801 Q = 3.02390E+00 MeV Emin = 1.00000E-11 MeV : (n,a1) + 42 MT = 802 Q = 2.84040E+00 MeV Emin = 1.00000E-11 MeV : (n,a2) + 43 MT = 803 Q = 2.35470E+00 MeV Emin = 1.00000E-11 MeV : (n,a3) + 44 MT = 804 Q = 2.14960E+00 MeV Emin = 1.00000E-11 MeV : (n,a4) + 45 MT = 805 Q = 2.12220E+00 MeV Emin = 1.00000E-11 MeV : (n,a5) + 46 MT = 806 Q = 1.95100E+00 MeV Emin = 1.00000E-11 MeV : (n,a6) + 47 MT = 807 Q = 1.76830E+00 MeV Emin = 8.00000E-01 MeV : (n,a7) + 48 MT = 808 Q = 1.53370E+00 MeV Emin = 9.00000E-01 MeV : (n,a8) + 49 MT = 809 Q = 1.37070E+00 MeV Emin = 1.09200E+00 MeV : (n,a9) + 50 MT = 810 Q = 1.24370E+00 MeV Emin = 1.25000E+00 MeV : (n,a10) + 51 MT = 849 Q = 1.24370E+00 MeV Emin = 1.17578E+00 MeV : (n,alpha) to continuum + 52 MT = 4 Q = 0.00000E+00 MeV Emin = 1.25939E-02 MeV : total inelastic scattering + + Nuclide 67 / 1657 : 32074.82c -- germanium 74 (Ge-74) + + Pointers : 426021 24755 + Primary type : Transport + Nuclide ZAI : 320740 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ge74.ACE + Atomic weight (AW) : 73.92118 + Atomic weight ratio (AWR) : 73.28616 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+02 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 35 reaction channels + - 50 special reactions + - 12 transmutation reactions + - 10 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 35 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 5 Q = 0.00000E+00 MeV Emin = 6.19220E-02 MeV frac = 1.00000E+00 Product nuclide = self : anything + 3 MT = 16 Q = -1.01962E+01 MeV Emin = 1.03353E+01 MeV frac = 1.00000E+00 Product nuclide = 32073.82c : (n,2n) + 4 MT = 17 Q = -1.69791E+01 MeV Emin = 1.72108E+01 MeV frac = 1.00000E+00 Product nuclide = 32072.82c : (n,3n) + 5 MT = 22 Q = -6.28750E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 300700 : (n,nalpha) + 6 MT = 28 Q = -1.10071E+01 MeV Emin = 1.15000E+01 MeV frac = 1.00000E+00 Product nuclide = 310730 : (n,np) + 7 MT = 32 Q = -1.79712E+01 MeV Emin = 1.82165E+01 MeV frac = 1.00000E+00 Product nuclide = 310720 : (n,nd) + 8 MT = 51 Q = -5.95850E-01 MeV Emin = 6.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -1.20420E+00 MeV Emin = 1.20000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -1.46376E+00 MeV Emin = 1.44186E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -1.48281E+00 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -1.69714E+00 MeV Emin = 1.70000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -1.72495E+00 MeV Emin = 1.73750E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -1.91300E+00 MeV Emin = 1.91980E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -2.16500E+00 MeV Emin = 2.19454E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -2.16526E+00 MeV Emin = 2.19481E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -2.19793E+00 MeV Emin = 2.22792E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -2.22777E+00 MeV Emin = 2.25817E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 62 Q = -2.30000E+00 MeV Emin = 2.33139E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 20 MT = 63 Q = -2.49000E+00 MeV Emin = 2.52398E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 21 MT = 64 Q = -2.53631E+00 MeV Emin = 2.57092E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 22 MT = 65 Q = -2.56933E+00 MeV Emin = 2.60439E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 23 MT = 66 Q = -2.60032E+00 MeV Emin = 2.63580E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 24 MT = 67 Q = -2.66962E+00 MeV Emin = 2.70605E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 25 MT = 68 Q = -2.69368E+00 MeV Emin = 2.73044E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 26 MT = 69 Q = -2.69692E+00 MeV Emin = 2.73372E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 27 MT = 70 Q = -2.71100E+00 MeV Emin = 2.74799E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 28 MT = 91 Q = -2.71100E+00 MeV Emin = 2.74799E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 29 MT = 102 Q = 6.50522E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 320750 : (n,gamma) + 30 MT = 103 Q = -4.58565E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 310740 : (n,p) + 31 MT = 104 Q = -8.78257E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 310730 : (n,d) + 32 MT = 105 Q = -1.17140E+01 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 310720 : (n,t) + 33 MT = 106 Q = -1.21535E+01 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 300720 : (n,He-3) + 34 MT = 107 Q = -4.53927E-01 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 300710 : (n,alpha) + 35 MT = 111 Q = -1.45186E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 300730 : (n,2p) + + 10 additional transport branches: + + 1 MT = 22 Q = -6.28750E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.10071E+01 MeV Emin = 1.15000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.79712E+01 MeV Emin = 1.82165E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 102 Q = 6.50522E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 320751 : (n,gamma) + 5 MT = 103 Q = -4.58565E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 104 Q = -8.78257E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 7 MT = 105 Q = -1.17140E+01 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 8 MT = 106 Q = -1.21535E+01 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 9 MT = 107 Q = -4.53927E-01 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 10 MT = 111 Q = -1.45186E+01 MeV Emin = 1.60000E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 50 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 5.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 9.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.25000E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.40000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 4.25000E-04 MeV : damage-energy production + 7 MT = 600 Q = -4.58565E+00 MeV Emin = 5.00000E+00 MeV : (n,p) to ground state + 8 MT = 601 Q = -4.64220E+00 MeV Emin = 5.00000E+00 MeV : (n,p1) + 9 MT = 602 Q = -4.64522E+00 MeV Emin = 5.00000E+00 MeV : (n,p2) + 10 MT = 603 Q = -4.68792E+00 MeV Emin = 5.00000E+00 MeV : (n,p3) + 11 MT = 604 Q = -4.69430E+00 MeV Emin = 5.00000E+00 MeV : (n,p4) + 12 MT = 605 Q = -4.72698E+00 MeV Emin = 5.00000E+00 MeV : (n,p5) + 13 MT = 606 Q = -4.73068E+00 MeV Emin = 5.00000E+00 MeV : (n,p6) + 14 MT = 607 Q = -4.81345E+00 MeV Emin = 5.20000E+00 MeV : (n,p7) + 15 MT = 608 Q = -4.83743E+00 MeV Emin = 5.20000E+00 MeV : (n,p8) + 16 MT = 609 Q = -5.04071E+00 MeV Emin = 5.40000E+00 MeV : (n,p9) + 17 MT = 610 Q = -5.47976E+00 MeV Emin = 5.60000E+00 MeV : (n,p10) + 18 MT = 649 Q = -5.47976E+00 MeV Emin = 6.00000E+00 MeV : (n,p) to continuum + 19 MT = 650 Q = -8.78257E+00 MeV Emin = 9.00000E+00 MeV : (n,d) to ground state + 20 MT = 651 Q = -8.98057E+00 MeV Emin = 9.50000E+00 MeV : (n,d1) + 21 MT = 652 Q = -9.00052E+00 MeV Emin = 9.50000E+00 MeV : (n,d2) + 22 MT = 653 Q = -9.27839E+00 MeV Emin = 9.50000E+00 MeV : (n,d3) + 23 MT = 654 Q = -9.69354E+00 MeV Emin = 1.00000E+01 MeV : (n,d4) + 24 MT = 655 Q = -9.73857E+00 MeV Emin = 1.00000E+01 MeV : (n,d5) + 25 MT = 699 Q = -9.73857E+00 MeV Emin = 1.05000E+01 MeV : (n,d) to continuum + 26 MT = 700 Q = -1.17140E+01 MeV Emin = 1.25000E+01 MeV : (n,t) to ground state + 27 MT = 701 Q = -1.17304E+01 MeV Emin = 1.25000E+01 MeV : (n,t1) + 28 MT = 702 Q = -1.18336E+01 MeV Emin = 1.25000E+01 MeV : (n,t2) + 29 MT = 703 Q = -1.18428E+01 MeV Emin = 1.25000E+01 MeV : (n,t3) + 30 MT = 704 Q = -1.18755E+01 MeV Emin = 1.25000E+01 MeV : (n,t4) + 31 MT = 705 Q = -1.18795E+01 MeV Emin = 1.25000E+01 MeV : (n,t5) + 32 MT = 749 Q = -1.18795E+01 MeV Emin = 1.25000E+01 MeV : (n,t) to continuum + 33 MT = 750 Q = -1.21535E+01 MeV Emin = 1.40000E+01 MeV : (n,He-3) to ground state + 34 MT = 751 Q = -1.28060E+01 MeV Emin = 1.45000E+01 MeV : (n,He-3_1) + 35 MT = 752 Q = -1.36526E+01 MeV Emin = 1.50000E+01 MeV : (n,He-3_2) + 36 MT = 753 Q = -1.38109E+01 MeV Emin = 1.50000E+01 MeV : (n,He-3_3) + 37 MT = 754 Q = -1.43453E+01 MeV Emin = 1.60000E+01 MeV : (n,He-3_4) + 38 MT = 800 Q = -4.53927E-01 MeV Emin = 2.00000E+00 MeV : (n,alpha) to ground state + 39 MT = 801 Q = -6.11627E-01 MeV Emin = 2.20000E+00 MeV : (n,a1) + 40 MT = 802 Q = -7.40227E-01 MeV Emin = 2.40000E+00 MeV : (n,a2) + 41 MT = 803 Q = -9.18927E-01 MeV Emin = 2.60000E+00 MeV : (n,a3) + 42 MT = 804 Q = -9.43727E-01 MeV Emin = 2.60000E+00 MeV : (n,a4) + 43 MT = 805 Q = -1.12863E+00 MeV Emin = 2.80000E+00 MeV : (n,a5) + 44 MT = 806 Q = -1.30693E+00 MeV Emin = 3.00000E+00 MeV : (n,a6) + 45 MT = 807 Q = -1.50593E+00 MeV Emin = 3.20000E+00 MeV : (n,a7) + 46 MT = 808 Q = -1.53193E+00 MeV Emin = 3.20000E+00 MeV : (n,a8) + 47 MT = 809 Q = -1.71523E+00 MeV Emin = 3.40000E+00 MeV : (n,a9) + 48 MT = 810 Q = -1.87493E+00 MeV Emin = 3.60000E+00 MeV : (n,a10) + 49 MT = 849 Q = -1.87493E+00 MeV Emin = 4.00000E+00 MeV : (n,alpha) to continuum + 50 MT = 4 Q = 0.00000E+00 MeV Emin = 6.00000E-01 MeV : total inelastic scattering + + Nuclide 68 / 1657 : 32076.82c -- germanium 76 (Ge-76) + + Pointers : 435161 24801 + Primary type : Transport + Nuclide ZAI : 320760 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ge76.ACE + Atomic weight (AW) : 75.92140 + Atomic weight ratio (AWR) : 75.26920 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+02 + Half-life : 4.99E+28 seconds (1.58E+21 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 32 reaction channels + - 39 special reactions + - 9 transmutation reactions + - 7 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 32 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 5 Q = 0.00000E+00 MeV Emin = 4.99445E-02 MeV frac = 1.00000E+00 Product nuclide = self : anything + 3 MT = 16 Q = -9.42830E+00 MeV Emin = 9.55356E+00 MeV frac = 1.00000E+00 Product nuclide = 320750 : (n,2n) + 4 MT = 17 Q = -1.59335E+01 MeV Emin = 1.61452E+01 MeV frac = 1.00000E+00 Product nuclide = 32074.82c : (n,3n) + 5 MT = 22 Q = -7.50938E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 300720 : (n,nalpha) + 6 MT = 28 Q = -1.20377E+01 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 310750 : (n,np) + 7 MT = 51 Q = -5.62930E-01 MeV Emin = 5.68750E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 8 MT = 52 Q = -1.10844E+00 MeV Emin = 1.10000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 9 MT = 53 Q = -1.41008E+00 MeV Emin = 1.40000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 10 MT = 54 Q = -1.53946E+00 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 11 MT = 55 Q = -1.91107E+00 MeV Emin = 1.90000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 12 MT = 56 Q = -2.01987E+00 MeV Emin = 2.04671E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 13 MT = 57 Q = -2.20490E+00 MeV Emin = 2.23420E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 14 MT = 58 Q = -2.28422E+00 MeV Emin = 2.31457E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 15 MT = 59 Q = -2.45600E+00 MeV Emin = 2.48863E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 16 MT = 60 Q = -2.47820E+00 MeV Emin = 2.51112E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 17 MT = 61 Q = -2.50360E+00 MeV Emin = 2.53686E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 18 MT = 62 Q = -2.55400E+00 MeV Emin = 2.58793E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 19 MT = 63 Q = -2.59110E+00 MeV Emin = 2.62553E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 20 MT = 64 Q = -2.62400E+00 MeV Emin = 2.65886E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 21 MT = 65 Q = -2.65451E+00 MeV Emin = 2.68978E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 22 MT = 66 Q = -2.69240E+00 MeV Emin = 2.72817E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 23 MT = 67 Q = -2.73340E+00 MeV Emin = 2.76972E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 24 MT = 68 Q = -2.74776E+00 MeV Emin = 2.78427E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 25 MT = 69 Q = -2.76876E+00 MeV Emin = 2.80555E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 26 MT = 70 Q = -2.84157E+00 MeV Emin = 2.87932E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 27 MT = 91 Q = -2.84157E+00 MeV Emin = 2.87932E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 28 MT = 102 Q = 6.07257E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 320770 : (n,gamma) + 29 MT = 103 Q = -6.22765E+00 MeV Emin = 6.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 310760 : (n,p) + 30 MT = 104 Q = -9.81309E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 310750 : (n,d) + 31 MT = 105 Q = -1.20373E+01 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 310740 : (n,t) + 32 MT = 107 Q = -2.15648E+00 MeV Emin = 3.80000E+00 MeV frac = 1.00000E+00 Product nuclide = 300730 : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -7.50938E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.20377E+01 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 102 Q = 6.07257E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 320771 : (n,gamma) + 4 MT = 103 Q = -6.22765E+00 MeV Emin = 6.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -9.81309E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -1.20373E+01 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 107 Q = -2.15648E+00 MeV Emin = 3.80000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 39 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 6.60000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.00000E+01 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.25000E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 2.00000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 3.80000E+00 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 4.45508E-04 MeV : damage-energy production + 7 MT = 600 Q = -6.22765E+00 MeV Emin = 6.60000E+00 MeV : (n,p) to ground state + 8 MT = 601 Q = -6.39994E+00 MeV Emin = 6.80000E+00 MeV : (n,p1) + 9 MT = 602 Q = -6.42715E+00 MeV Emin = 6.80000E+00 MeV : (n,p2) + 10 MT = 603 Q = -6.50293E+00 MeV Emin = 6.80000E+00 MeV : (n,p3) + 11 MT = 604 Q = -6.50922E+00 MeV Emin = 7.00000E+00 MeV : (n,p4) + 12 MT = 605 Q = -6.59746E+00 MeV Emin = 7.00000E+00 MeV : (n,p5) + 13 MT = 606 Q = -6.79318E+00 MeV Emin = 7.00000E+00 MeV : (n,p6) + 14 MT = 607 Q = -6.90848E+00 MeV Emin = 7.20000E+00 MeV : (n,p7) + 15 MT = 608 Q = -7.00920E+00 MeV Emin = 7.40000E+00 MeV : (n,p8) + 16 MT = 609 Q = -7.25795E+00 MeV Emin = 7.60000E+00 MeV : (n,p9) + 17 MT = 610 Q = -7.33368E+00 MeV Emin = 7.60000E+00 MeV : (n,p10) + 18 MT = 649 Q = -7.33368E+00 MeV Emin = 7.80000E+00 MeV : (n,p) to continuum + 19 MT = 650 Q = -9.81309E+00 MeV Emin = 1.00000E+01 MeV : (n,d) to ground state + 20 MT = 651 Q = -9.83559E+00 MeV Emin = 1.00000E+01 MeV : (n,d1) + 21 MT = 652 Q = -9.99145E+00 MeV Emin = 1.05000E+01 MeV : (n,d2) + 22 MT = 653 Q = -1.00417E+01 MeV Emin = 1.05000E+01 MeV : (n,d3) + 23 MT = 654 Q = -1.02453E+01 MeV Emin = 1.05000E+01 MeV : (n,d4) + 24 MT = 655 Q = -1.04195E+01 MeV Emin = 1.10000E+01 MeV : (n,d5) + 25 MT = 699 Q = -1.04195E+01 MeV Emin = 1.10000E+01 MeV : (n,d) to continuum + 26 MT = 700 Q = -1.20373E+01 MeV Emin = 1.25000E+01 MeV : (n,t) to ground state + 27 MT = 701 Q = -1.20939E+01 MeV Emin = 1.25000E+01 MeV : (n,t1) + 28 MT = 702 Q = -1.20969E+01 MeV Emin = 1.30000E+01 MeV : (n,t2) + 29 MT = 703 Q = -1.21396E+01 MeV Emin = 1.30000E+01 MeV : (n,t3) + 30 MT = 704 Q = -1.21460E+01 MeV Emin = 1.30000E+01 MeV : (n,t4) + 31 MT = 705 Q = -1.21787E+01 MeV Emin = 1.30000E+01 MeV : (n,t5) + 32 MT = 749 Q = -1.21787E+01 MeV Emin = 1.30000E+01 MeV : (n,t) to continuum + 33 MT = 800 Q = -2.15648E+00 MeV Emin = 3.80000E+00 MeV : (n,alpha) to ground state + 34 MT = 801 Q = -2.35198E+00 MeV Emin = 4.00000E+00 MeV : (n,a1) + 35 MT = 802 Q = -2.43648E+00 MeV Emin = 4.20000E+00 MeV : (n,a2) + 36 MT = 803 Q = -2.65648E+00 MeV Emin = 4.40000E+00 MeV : (n,a3) + 37 MT = 804 Q = -3.29648E+00 MeV Emin = 5.00000E+00 MeV : (n,a4) + 38 MT = 849 Q = -3.29648E+00 MeV Emin = 5.40000E+00 MeV : (n,alpha) to continuum + 39 MT = 4 Q = 0.00000E+00 MeV Emin = 5.68750E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 11 Q = 2.03910E+00 MeV frac = 1.00000E+00 Product nuclide = 34076.82c : beta- + beta- + + Nuclide 69 / 1657 : 33075.82c -- arsenic 75 (As-75) + + Pointers : 452491 19281 + Primary type : Transport + Nuclide ZAI : 330750 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/As75.ACE + Atomic weight (AW) : 74.92162 + Atomic weight ratio (AWR) : 74.27800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 22 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 22 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -1.98600E-01 MeV Emin = 2.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -2.64600E-01 MeV Emin = 2.63980E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -2.79500E-01 MeV Emin = 2.75711E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -3.03700E-01 MeV Emin = 3.04947E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -4.00500E-01 MeV Emin = 4.03089E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -4.68900E-01 MeV Emin = 4.57881E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 57 Q = -5.72100E-01 MeV Emin = 5.59850E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 9 MT = 58 Q = -6.17700E-01 MeV Emin = 6.21406E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 10 MT = 59 Q = -8.21800E-01 MeV Emin = 7.66430E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 11 MT = 60 Q = -1.02000E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 12 MT = 61 Q = -1.30000E+00 MeV Emin = 1.24656E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 13 MT = 62 Q = -1.60000E+00 MeV Emin = 1.60000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 14 MT = 63 Q = -1.80000E+00 MeV Emin = 1.81712E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 15 MT = 91 Q = -1.78600E+00 MeV Emin = 1.71577E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 16 MT = 102 Q = 7.32820E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 330760 : (n,gamma) + 17 MT = 103 Q = -3.94970E-01 MeV Emin = 3.85095E-01 MeV frac = 1.00000E+00 Product nuclide = 320750 : (n,p) + 18 MT = 104 Q = -4.67440E+00 MeV Emin = 4.73733E+00 MeV frac = 1.00000E+00 Product nuclide = 32074.82c : (n,d) + 19 MT = 105 Q = -8.61550E+00 MeV Emin = 8.73149E+00 MeV frac = 1.00000E+00 Product nuclide = 32073.82c : (n,t) + 20 MT = 106 Q = -1.01600E+01 MeV Emin = 1.02968E+01 MeV frac = 1.00000E+00 Product nuclide = 310730 : (n,He-3) + 21 MT = 107 Q = 1.20310E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 310720 : (n,alpha) + 22 MT = 111 Q = -1.15160E+01 MeV Emin = 1.16710E+01 MeV frac = 1.00000E+00 Product nuclide = 310740 : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = -3.94970E-01 MeV Emin = 3.85095E-01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -4.67440E+00 MeV Emin = 4.73733E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -8.61550E+00 MeV Emin = 8.73149E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -1.01600E+01 MeV Emin = 1.02968E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 1.20310E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -1.15160E+01 MeV Emin = 1.16710E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.85095E-01 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 4.73733E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 8.73149E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.02968E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.62500E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 2.00000E-01 MeV : total inelastic scattering + + Nuclide 70 / 1657 : 34076.82c -- selenium 76 (Se-76) + + Pointers : 469592 32529 + Primary type : Transport + Nuclide ZAI : 340760 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Se76.ACE + Atomic weight (AW) : 75.91919 + Atomic weight ratio (AWR) : 75.26700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 13 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 13 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -5.59000E-01 MeV Emin = 5.45347E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -1.11000E+00 MeV Emin = 1.06235E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -1.22000E+00 MeV Emin = 1.18047E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -1.34000E+00 MeV Emin = 1.35000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 91 Q = -2.96070E+00 MeV Emin = 3.00004E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 7 MT = 102 Q = 7.41800E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 34077.82c : (n,gamma) + 8 MT = 103 Q = -2.18520E+00 MeV Emin = 2.21423E+00 MeV frac = 1.00000E+00 Product nuclide = 330760 : (n,p) + 9 MT = 104 Q = -7.28710E+00 MeV Emin = 7.38392E+00 MeV frac = 1.00000E+00 Product nuclide = 33075.82c : (n,d) + 10 MT = 105 Q = -1.12740E+01 MeV Emin = 1.14238E+01 MeV frac = 1.00000E+00 Product nuclide = 330740 : (n,t) + 11 MT = 106 Q = -8.69400E+00 MeV Emin = 8.80951E+00 MeV frac = 1.00000E+00 Product nuclide = 32074.82c : (n,He-3) + 12 MT = 107 Q = 1.68020E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 32073.82c : (n,alpha) + 13 MT = 111 Q = -9.90610E+00 MeV Emin = 1.00377E+01 MeV frac = 1.00000E+00 Product nuclide = 320750 : (n,2p) + + 7 additional transport branches: + + 1 MT = 102 Q = 7.41800E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 340771 : (n,gamma) + 2 MT = 103 Q = -2.18520E+00 MeV Emin = 2.21423E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 104 Q = -7.28710E+00 MeV Emin = 7.38392E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 4 MT = 105 Q = -1.12740E+01 MeV Emin = 1.14238E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 5 MT = 106 Q = -8.69400E+00 MeV Emin = 8.80951E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 6 MT = 107 Q = 1.68020E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 7 MT = 111 Q = -9.90610E+00 MeV Emin = 1.00377E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.21423E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.38392E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.14238E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 8.80951E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.62500E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 5.45347E-01 MeV : total inelastic scattering + + Nuclide 71 / 1657 : 34077.82c -- selenium 77 (Se-77) + + Pointers : 471693 32575 + Primary type : Transport + Nuclide ZAI : 340770 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Se77.ACE + Atomic weight (AW) : 76.91988 + Atomic weight ratio (AWR) : 76.25910 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 19 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 19 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -1.61000E-01 MeV Emin = 1.47333E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -2.39000E-01 MeV Emin = 2.31598E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -2.50000E-01 MeV Emin = 2.52768E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -3.10000E-01 MeV Emin = 3.05937E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -4.40000E-01 MeV Emin = 4.35000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -5.22000E-01 MeV Emin = 5.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 57 Q = -6.80000E-01 MeV Emin = 6.87500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 9 MT = 58 Q = -8.20000E-01 MeV Emin = 7.65375E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 10 MT = 59 Q = -9.60000E-01 MeV Emin = 9.15377E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 11 MT = 60 Q = -1.00000E+00 MeV Emin = 1.01000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 12 MT = 91 Q = -1.57930E+00 MeV Emin = 1.55000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 13 MT = 102 Q = 1.04970E+01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 34078.82c : (n,gamma) + 14 MT = 103 Q = 9.21570E-02 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 330770 : (n,p) + 15 MT = 104 Q = -7.37720E+00 MeV Emin = 7.47394E+00 MeV frac = 1.00000E+00 Product nuclide = 330760 : (n,d) + 16 MT = 105 Q = -8.44740E+00 MeV Emin = 8.55817E+00 MeV frac = 1.00000E+00 Product nuclide = 33075.82c : (n,t) + 17 MT = 106 Q = -9.60660E+00 MeV Emin = 9.73257E+00 MeV frac = 1.00000E+00 Product nuclide = 320750 : (n,He-3) + 18 MT = 107 Q = 4.46100E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 32074.82c : (n,alpha) + 19 MT = 111 Q = -7.89630E+00 MeV Emin = 7.99985E+00 MeV frac = 1.00000E+00 Product nuclide = 32076.82c : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = 9.21570E-02 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -7.37720E+00 MeV Emin = 7.47394E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -8.44740E+00 MeV Emin = 8.55817E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -9.60660E+00 MeV Emin = 9.73257E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 4.46100E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -7.89630E+00 MeV Emin = 7.99985E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.62500E-02 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.47394E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 8.55817E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 9.73257E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.62500E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 1.47333E-01 MeV : total inelastic scattering + + Nuclide 72 / 1657 : 34078.82c -- selenium 78 (Se-78) + + Pointers : 474525 32621 + Primary type : Transport + Nuclide ZAI : 340780 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Se78.ACE + Atomic weight (AW) : 77.91735 + Atomic weight ratio (AWR) : 77.24800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 18 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 18 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -6.14000E-01 MeV Emin = 6.17902E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -1.31000E+00 MeV Emin = 1.31250E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -1.51000E+00 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -1.51001E+00 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -1.71000E+00 MeV Emin = 1.66605E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -1.88000E+00 MeV Emin = 1.81822E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 57 Q = -1.97000E+00 MeV Emin = 1.94992E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 9 MT = 58 Q = -2.03000E+00 MeV Emin = 2.05630E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 10 MT = 59 Q = -2.22000E+00 MeV Emin = 2.24874E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 11 MT = 91 Q = -2.96170E+00 MeV Emin = 3.00004E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 12 MT = 102 Q = 6.97800E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 34079.82c : (n,gamma) + 13 MT = 103 Q = -3.50770E+00 MeV Emin = 3.55311E+00 MeV frac = 1.00000E+00 Product nuclide = 330780 : (n,p) + 14 MT = 104 Q = -8.17730E+00 MeV Emin = 8.28316E+00 MeV frac = 1.00000E+00 Product nuclide = 330770 : (n,d) + 15 MT = 105 Q = -1.16150E+01 MeV Emin = 1.17654E+01 MeV frac = 1.00000E+00 Product nuclide = 330760 : (n,t) + 16 MT = 106 Q = -1.06740E+01 MeV Emin = 1.08122E+01 MeV frac = 1.00000E+00 Product nuclide = 32076.82c : (n,He-3) + 17 MT = 107 Q = 4.70960E-01 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 320750 : (n,alpha) + 18 MT = 111 Q = -1.23190E+01 MeV Emin = 1.24785E+01 MeV frac = 1.00000E+00 Product nuclide = 320770 : (n,2p) + + 7 additional transport branches: + + 1 MT = 102 Q = 6.97800E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 340791 : (n,gamma) + 2 MT = 103 Q = -3.50770E+00 MeV Emin = 3.55311E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 104 Q = -8.17730E+00 MeV Emin = 8.28316E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 4 MT = 105 Q = -1.16150E+01 MeV Emin = 1.17654E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 5 MT = 106 Q = -1.06740E+01 MeV Emin = 1.08122E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 6 MT = 107 Q = 4.70960E-01 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 7 MT = 111 Q = -1.23190E+01 MeV Emin = 1.24785E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.55311E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.28316E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.17654E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.08122E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.62500E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 6.17902E-01 MeV : total inelastic scattering + + Nuclide 73 / 1657 : 34079.82c -- selenium 79 (Se-79) + + Pointers : 476991 32667 + Primary type : Transport + Nuclide ZAI : 340790 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Se79.ACE + Atomic weight (AW) : 78.91845 + Atomic weight ratio (AWR) : 78.24050 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.19E+13 seconds (377,251 years) + Specific ingestion toxicity : 2.90E-09 Sv/Bq + Specific inhalation toxicity : 6.80E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 42 reaction channels + - 7 special reactions + - 11 transmutation reactions + - 8 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 42 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.96520E+00 MeV Emin = 7.05423E+00 MeV frac = 1.00000E+00 Product nuclide = 34078.82c : (n,2n) + 3 MT = 17 Q = -1.74667E+01 MeV Emin = 1.76900E+01 MeV frac = 1.00000E+00 Product nuclide = 34077.82c : (n,3n) + 4 MT = 22 Q = -6.48638E+00 MeV Emin = 7.05423E+00 MeV frac = 1.00000E+00 Product nuclide = 320750 : (n,nalpha) + 5 MT = 28 Q = -1.04742E+01 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 330780 : (n,np) + 6 MT = 32 Q = -1.50645E+01 MeV Emin = 1.52571E+01 MeV frac = 1.00000E+00 Product nuclide = 330770 : (n,nd) + 7 MT = 51 Q = -9.56999E-02 MeV Emin = 9.26924E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 8 MT = 52 Q = -1.28000E-01 MeV Emin = 1.24079E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 9 MT = 53 Q = -1.37000E-01 MeV Emin = 1.34194E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 10 MT = 54 Q = -3.64999E-01 MeV Emin = 3.52249E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 11 MT = 55 Q = -4.98999E-01 MeV Emin = 5.05029E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 12 MT = 56 Q = -5.27899E-01 MeV Emin = 5.30173E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 13 MT = 57 Q = -5.71999E-01 MeV Emin = 5.78423E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 14 MT = 58 Q = -6.29999E-01 MeV Emin = 6.36851E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 15 MT = 59 Q = -7.28599E-01 MeV Emin = 7.28769E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 16 MT = 60 Q = -7.90399E-01 MeV Emin = 8.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 17 MT = 61 Q = -8.18799E-01 MeV Emin = 8.28501E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 18 MT = 62 Q = -8.97099E-01 MeV Emin = 9.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 19 MT = 63 Q = -9.74599E-01 MeV Emin = 9.69886E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 20 MT = 64 Q = -9.82899E-01 MeV Emin = 9.95084E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 21 MT = 65 Q = -1.00820E+00 MeV Emin = 1.01055E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 22 MT = 66 Q = -1.07210E+00 MeV Emin = 1.06962E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 23 MT = 67 Q = -1.08000E+00 MeV Emin = 1.08980E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 24 MT = 68 Q = -1.08880E+00 MeV Emin = 1.09826E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 25 MT = 69 Q = -1.11010E+00 MeV Emin = 1.12099E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 26 MT = 70 Q = -1.14500E+00 MeV Emin = 1.14675E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 27 MT = 71 Q = -1.23130E+00 MeV Emin = 1.24469E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 28 MT = 72 Q = -1.25340E+00 MeV Emin = 1.25971E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 29 MT = 73 Q = -1.25670E+00 MeV Emin = 1.27109E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 30 MT = 74 Q = -1.33990E+00 MeV Emin = 1.33860E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 31 MT = 75 Q = -1.38500E+00 MeV Emin = 1.38557E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 32 MT = 76 Q = -1.49100E+00 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 33 MT = 77 Q = -1.58900E+00 MeV Emin = 1.56279E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 27. excited state + 34 MT = 78 Q = -1.66700E+00 MeV Emin = 1.65868E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 28. excited state + 35 MT = 79 Q = -1.73770E+00 MeV Emin = 1.75000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 29. excited state + 36 MT = 91 Q = -1.76010E+00 MeV Emin = 1.77126E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 37 MT = 102 Q = 9.91209E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 34080.82c : (n,gamma) + 38 MT = 103 Q = -1.41813E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 330790 : (n,p) + 39 MT = 104 Q = -8.16410E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 330780 : (n,d) + 40 MT = 105 Q = -8.87936E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 330770 : (n,t) + 41 MT = 106 Q = -1.15621E+01 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 320770 : (n,He-3) + 42 MT = 107 Q = 2.94712E+00 MeV Emin = 9.99543E-02 MeV frac = 1.00000E+00 Product nuclide = 32076.82c : (n,alpha) + + 8 additional transport branches: + + 1 MT = 22 Q = -6.48638E+00 MeV Emin = 7.05423E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.04742E+01 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.50645E+01 MeV Emin = 1.52571E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 103 Q = -1.41813E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -8.16410E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -8.87936E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 106 Q = -1.15621E+01 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 8 MT = 107 Q = 2.94712E+00 MeV Emin = 9.99543E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 9.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.00000E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.40000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 9.99543E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 9.26924E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.50900E-01 MeV frac = 1.00000E+00 Product nuclide = 35079.82c : beta- + + Nuclide 74 / 1657 : 34080.82c -- selenium 80 (Se-80) + + Pointers : 481841 32713 + Primary type : Transport + Nuclide ZAI : 340800 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Se80.ACE + Atomic weight (AW) : 79.91652 + Atomic weight ratio (AWR) : 79.23000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 17 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 17 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -6.66000E-01 MeV Emin = 6.36359E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -1.35000E+00 MeV Emin = 1.27525E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -1.44000E+00 MeV Emin = 1.45014E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -1.48000E+00 MeV Emin = 1.48338E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -1.69000E+00 MeV Emin = 1.65565E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -1.77000E+00 MeV Emin = 1.75182E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 57 Q = -1.86000E+00 MeV Emin = 1.88117E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 9 MT = 58 Q = -1.96000E+00 MeV Emin = 1.97000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 10 MT = 91 Q = -2.96270E+00 MeV Emin = 3.00009E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 11 MT = 102 Q = 6.70120E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 340810 : (n,gamma) + 12 MT = 103 Q = -4.91700E+00 MeV Emin = 4.97906E+00 MeV frac = 1.00000E+00 Product nuclide = 330800 : (n,p) + 13 MT = 104 Q = -9.10240E+00 MeV Emin = 9.21729E+00 MeV frac = 1.00000E+00 Product nuclide = 330790 : (n,d) + 14 MT = 105 Q = -1.18950E+01 MeV Emin = 1.20451E+01 MeV frac = 1.00000E+00 Product nuclide = 330780 : (n,t) + 15 MT = 106 Q = -1.28570E+01 MeV Emin = 1.30193E+01 MeV frac = 1.00000E+00 Product nuclide = 320780 : (n,He-3) + 16 MT = 107 Q = -9.00200E-01 MeV Emin = 9.11356E-01 MeV frac = 1.00000E+00 Product nuclide = 320770 : (n,alpha) + 17 MT = 111 Q = -1.46930E+01 MeV Emin = 1.48785E+01 MeV frac = 1.00000E+00 Product nuclide = 320790 : (n,2p) + + 7 additional transport branches: + + 1 MT = 102 Q = 6.70120E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 340811 : (n,gamma) + 2 MT = 103 Q = -4.91700E+00 MeV Emin = 4.97906E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 104 Q = -9.10240E+00 MeV Emin = 9.21729E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 4 MT = 105 Q = -1.18950E+01 MeV Emin = 1.20451E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 5 MT = 106 Q = -1.28570E+01 MeV Emin = 1.30193E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 6 MT = 107 Q = -9.00200E-01 MeV Emin = 9.11356E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 7 MT = 111 Q = -1.46930E+01 MeV Emin = 1.48785E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.97906E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 9.21729E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.20451E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.30193E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 9.11356E-01 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 6.36359E-01 MeV : total inelastic scattering + + Nuclide 75 / 1657 : 34082.82c -- selenium 82 (Se-82) + + Pointers : 486183 32759 + Primary type : Transport + Nuclide ZAI : 340820 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Se82.ACE + Atomic weight (AW) : 81.91671 + Atomic weight ratio (AWR) : 81.21300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 3.06E+27 seconds (9.71E+19 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 12 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 7 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 12 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -6.55000E-01 MeV Emin = 6.26436E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -1.49000E+00 MeV Emin = 1.38122E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -1.75000E+00 MeV Emin = 1.76000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 91 Q = -2.96360E+00 MeV Emin = 3.00009E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 6 MT = 102 Q = 5.92500E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 340830 : (n,gamma) + 7 MT = 103 Q = -6.61110E+00 MeV Emin = 6.69250E+00 MeV frac = 1.00000E+00 Product nuclide = 330820 : (n,p) + 8 MT = 104 Q = -1.00070E+01 MeV Emin = 1.01302E+01 MeV frac = 1.00000E+00 Product nuclide = 330810 : (n,d) + 9 MT = 105 Q = -1.24000E+01 MeV Emin = 1.25527E+01 MeV frac = 1.00000E+00 Product nuclide = 330800 : (n,t) + 10 MT = 106 Q = -1.50110E+01 MeV Emin = 1.51958E+01 MeV frac = 1.00000E+00 Product nuclide = 320800 : (n,He-3) + 11 MT = 107 Q = -2.36870E+00 MeV Emin = 2.39787E+00 MeV frac = 1.00000E+00 Product nuclide = 320790 : (n,alpha) + 12 MT = 111 Q = -1.77460E+01 MeV Emin = 1.79645E+01 MeV frac = 1.00000E+00 Product nuclide = 320810 : (n,2p) + + 7 additional transport branches: + + 1 MT = 102 Q = 5.92500E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 340831 : (n,gamma) + 2 MT = 103 Q = -6.61110E+00 MeV Emin = 6.69250E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 104 Q = -1.00070E+01 MeV Emin = 1.01302E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 4 MT = 105 Q = -1.24000E+01 MeV Emin = 1.25527E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 5 MT = 106 Q = -1.50110E+01 MeV Emin = 1.51958E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 6 MT = 107 Q = -2.36870E+00 MeV Emin = 2.39787E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 7 MT = 111 Q = -1.77460E+01 MeV Emin = 1.79645E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 6.69250E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.01302E+01 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.25527E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.51958E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 2.39787E+00 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 6.26436E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 11 Q = 2.99640E+00 MeV frac = 1.00000E+00 Product nuclide = 36082.82c : beta- + beta- + + Nuclide 76 / 1657 : 35079.82c -- bromine 79 (Br-79) + + Pointers : 492457 20247 + Primary type : Transport + Nuclide ZAI : 350790 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Br79.ACE + Atomic weight (AW) : 78.91835 + Atomic weight ratio (AWR) : 78.24040 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 20 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 20 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -2.08000E-01 MeV Emin = 2.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -2.17300E-01 MeV Emin = 2.19877E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -2.61300E-01 MeV Emin = 2.62224E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -3.06700E-01 MeV Emin = 2.96793E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -3.97400E-01 MeV Emin = 3.86250E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -5.23000E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 57 Q = -6.06100E-01 MeV Emin = 5.93553E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 9 MT = 58 Q = -7.61000E-01 MeV Emin = 7.37500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 10 MT = 59 Q = -8.33000E-01 MeV Emin = 8.12500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 11 MT = 60 Q = -1.16500E+00 MeV Emin = 1.17100E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 12 MT = 61 Q = -1.33200E+00 MeV Emin = 1.34552E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 13 MT = 91 Q = -1.32510E+00 MeV Emin = 1.25650E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 14 MT = 102 Q = 7.88300E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 350800 : (n,gamma) + 15 MT = 103 Q = 6.33090E-01 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 34079.82c : (n,p) + 16 MT = 104 Q = -4.10130E+00 MeV Emin = 4.15372E+00 MeV frac = 1.00000E+00 Product nuclide = 34078.82c : (n,d) + 17 MT = 105 Q = -8.33900E+00 MeV Emin = 8.44558E+00 MeV frac = 1.00000E+00 Product nuclide = 34077.82c : (n,t) + 18 MT = 106 Q = -9.01110E+00 MeV Emin = 9.12627E+00 MeV frac = 1.00000E+00 Product nuclide = 330770 : (n,He-3) + 19 MT = 107 Q = 1.86650E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 330760 : (n,alpha) + 20 MT = 111 Q = -9.83300E+00 MeV Emin = 9.95868E+00 MeV frac = 1.00000E+00 Product nuclide = 330780 : (n,2p) + + 7 additional transport branches: + + 1 MT = 102 Q = 7.88300E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 350801 : (n,gamma) + 2 MT = 103 Q = 6.33090E-01 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 104 Q = -4.10130E+00 MeV Emin = 4.15372E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 4 MT = 105 Q = -8.33900E+00 MeV Emin = 8.44558E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 5 MT = 106 Q = -9.01110E+00 MeV Emin = 9.12627E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 6 MT = 107 Q = 1.86650E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 7 MT = 111 Q = -9.83300E+00 MeV Emin = 9.95868E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.62500E-02 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 4.15372E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 8.44558E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 9.12627E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.62500E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 2.00000E-01 MeV : total inelastic scattering + + Nuclide 77 / 1657 : 35081.82c -- bromine 81 (Br-81) + + Pointers : 496787 20293 + Primary type : Transport + Nuclide ZAI : 350810 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Br81.ACE + Atomic weight (AW) : 80.91631 + Atomic weight ratio (AWR) : 80.22120 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 13 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 13 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -2.80000E-01 MeV Emin = 2.62618E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -5.50000E-01 MeV Emin = 5.33490E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -5.60000E-01 MeV Emin = 5.33490E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -8.30000E-01 MeV Emin = 8.40000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 91 Q = -8.30000E-01 MeV Emin = 8.40000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 7 MT = 102 Q = 7.60100E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 350820 : (n,gamma) + 8 MT = 103 Q = -8.02080E-01 MeV Emin = 7.55949E-01 MeV frac = 1.00000E+00 Product nuclide = 340810 : (n,p) + 9 MT = 104 Q = -5.27710E+00 MeV Emin = 5.34288E+00 MeV frac = 1.00000E+00 Product nuclide = 34080.82c : (n,d) + 10 MT = 105 Q = -8.93030E+00 MeV Emin = 9.04162E+00 MeV frac = 1.00000E+00 Product nuclide = 34079.82c : (n,t) + 11 MT = 106 Q = -1.11120E+01 MeV Emin = 1.12505E+01 MeV frac = 1.00000E+00 Product nuclide = 330790 : (n,He-3) + 12 MT = 107 Q = 4.10310E-01 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 330780 : (n,alpha) + 13 MT = 111 Q = -1.24180E+01 MeV Emin = 1.25728E+01 MeV frac = 1.00000E+00 Product nuclide = 330800 : (n,2p) + + 7 additional transport branches: + + 1 MT = 102 Q = 7.60100E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 350821 : (n,gamma) + 2 MT = 103 Q = -8.02080E-01 MeV Emin = 7.55949E-01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 104 Q = -5.27710E+00 MeV Emin = 5.34288E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 4 MT = 105 Q = -8.93030E+00 MeV Emin = 9.04162E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 5 MT = 106 Q = -1.11120E+01 MeV Emin = 1.12505E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 6 MT = 107 Q = 4.10310E-01 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 7 MT = 111 Q = -1.24180E+01 MeV Emin = 1.25728E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 7.55949E-01 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.34288E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.04162E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.12505E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.62500E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 2.62618E-01 MeV : total inelastic scattering + + Nuclide 78 / 1657 : 36080.82c -- krypton 80 (Kr-80) + + Pointers : 529500 27009 + Primary type : Transport + Nuclide ZAI : 360800 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Kr80.ACE + Atomic weight (AW) : 79.91632 + Atomic weight ratio (AWR) : 79.22980 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 16 reaction channels + - 7 special reactions + - 8 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 16 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.15250E+01 MeV Emin = 1.16900E+01 MeV frac = 1.00000E+00 Product nuclide = 360790 : (n,2n) + 3 MT = 51 Q = -6.16000E-01 MeV Emin = 6.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 4 MT = 52 Q = -1.25600E+00 MeV Emin = 1.25000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 5 MT = 53 Q = -1.32000E+00 MeV Emin = 1.33666E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 6 MT = 54 Q = -1.43600E+00 MeV Emin = 1.42706E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 7 MT = 55 Q = -2.39000E+00 MeV Emin = 2.42017E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 8 MT = 56 Q = -3.40000E+00 MeV Emin = 3.44291E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 9 MT = 91 Q = -6.16000E-01 MeV Emin = 1.34350E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 10 MT = 102 Q = 7.85000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 360810 : (n,gamma) + 11 MT = 103 Q = -1.22800E+00 MeV Emin = 1.95000E+00 MeV frac = 1.00000E+00 Product nuclide = 350800 : (n,p) + 12 MT = 104 Q = -6.88640E+00 MeV Emin = 9.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 35079.82c : (n,d) + 13 MT = 105 Q = -1.13220E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 350780 : (n,t) + 14 MT = 106 Q = -7.72960E+00 MeV Emin = 7.82716E+00 MeV frac = 1.00000E+00 Product nuclide = 34078.82c : (n,He-3) + 15 MT = 107 Q = 2.35600E+00 MeV Emin = 1.95000E+00 MeV frac = 1.00000E+00 Product nuclide = 34077.82c : (n,alpha) + 16 MT = 111 Q = -8.47990E+00 MeV Emin = 8.58693E+00 MeV frac = 1.00000E+00 Product nuclide = 34079.82c : (n,2p) + + 7 additional transport branches: + + 1 MT = 102 Q = 7.85000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 360811 : (n,gamma) + 2 MT = 103 Q = -1.22800E+00 MeV Emin = 1.95000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 104 Q = -6.88640E+00 MeV Emin = 9.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 4 MT = 105 Q = -1.13220E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 5 MT = 106 Q = -7.72960E+00 MeV Emin = 7.82716E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 6 MT = 107 Q = 2.35600E+00 MeV Emin = 1.95000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 7 MT = 111 Q = -8.47990E+00 MeV Emin = 8.58693E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.95000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 9.50000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.45000E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 7.82716E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.95000E+00 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 6.00000E-01 MeV : total inelastic scattering + + Nuclide 79 / 1657 : 36082.82c -- krypton 82 (Kr-82) + + Pointers : 532789 27055 + Primary type : Transport + Nuclide ZAI : 360820 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Kr82.ACE + Atomic weight (AW) : 81.91348 + Atomic weight ratio (AWR) : 81.20980 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 19 reaction channels + - 7 special reactions + - 8 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 19 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.09800E+01 MeV Emin = 1.12000E+01 MeV frac = 1.00000E+00 Product nuclide = 360810 : (n,2n) + 3 MT = 51 Q = -7.77000E-01 MeV Emin = 6.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 4 MT = 52 Q = -1.47500E+00 MeV Emin = 1.40000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 5 MT = 53 Q = -1.82000E+00 MeV Emin = 1.70000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 6 MT = 54 Q = -2.09400E+00 MeV Emin = 2.11979E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 7 MT = 55 Q = -2.17200E+00 MeV Emin = 2.19875E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 8 MT = 56 Q = -2.42700E+00 MeV Emin = 2.45689E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 9 MT = 57 Q = -2.64800E+00 MeV Emin = 2.68061E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 10 MT = 58 Q = -2.82800E+00 MeV Emin = 2.86282E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 11 MT = 59 Q = -2.92000E+00 MeV Emin = 2.95596E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 12 MT = 91 Q = -7.77000E-01 MeV Emin = 2.45600E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 13 MT = 102 Q = 7.46700E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 36083.82c : (n,gamma) + 14 MT = 103 Q = -2.30600E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 350820 : (n,p) + 15 MT = 104 Q = -7.76610E+00 MeV Emin = 7.86173E+00 MeV frac = 1.00000E+00 Product nuclide = 35081.82c : (n,d) + 16 MT = 105 Q = -1.15850E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 350800 : (n,t) + 17 MT = 106 Q = -9.69460E+00 MeV Emin = 1.70000E+01 MeV frac = 1.00000E+00 Product nuclide = 34080.82c : (n,He-3) + 18 MT = 107 Q = 1.11050E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 34079.82c : (n,alpha) + 19 MT = 111 Q = -1.07030E+01 MeV Emin = 1.08348E+01 MeV frac = 1.00000E+00 Product nuclide = 340810 : (n,2p) + + 7 additional transport branches: + + 1 MT = 102 Q = 7.46700E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 360831 : (n,gamma) + 2 MT = 103 Q = -2.30600E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 104 Q = -7.76610E+00 MeV Emin = 7.86173E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 4 MT = 105 Q = -1.15850E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 5 MT = 106 Q = -9.69460E+00 MeV Emin = 1.70000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 6 MT = 107 Q = 1.11050E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 7 MT = 111 Q = -1.07030E+01 MeV Emin = 1.08348E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.86173E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.45000E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.70000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 5.00000E+00 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 6.00000E-01 MeV : total inelastic scattering + + Nuclide 80 / 1657 : 36083.82c -- krypton 83 (Kr-83) + + Pointers : 535328 27101 + Primary type : Transport + Nuclide ZAI : 360830 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Kr83.ACE + Atomic weight (AW) : 82.91428 + Atomic weight ratio (AWR) : 82.20200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 28 reaction channels + - 7 special reactions + - 11 transmutation reactions + - 8 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 28 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.46240E+00 MeV Emin = 7.55320E+00 MeV frac = 1.00000E+00 Product nuclide = 36082.82c : (n,2n) + 3 MT = 17 Q = -1.84280E+01 MeV Emin = 1.86522E+01 MeV frac = 1.00000E+00 Product nuclide = 360810 : (n,3n) + 4 MT = 22 Q = -6.48720E+00 MeV Emin = 1.22500E+01 MeV frac = 1.00000E+00 Product nuclide = 34079.82c : (n,nalpha) + 5 MT = 28 Q = -9.77250E+00 MeV Emin = 1.17500E+01 MeV frac = 1.00000E+00 Product nuclide = 350820 : (n,np) + 6 MT = 51 Q = -9.40000E-03 MeV Emin = 9.25000E-03 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -4.15600E-02 MeV Emin = 4.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -5.62000E-01 MeV Emin = 5.66002E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -5.71200E-01 MeV Emin = 5.77175E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -6.90150E-01 MeV Emin = 6.96888E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -7.98900E-01 MeV Emin = 7.57543E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -8.11000E-01 MeV Emin = 8.20410E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -1.01190E+00 MeV Emin = 9.16410E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -1.10290E+00 MeV Emin = 1.07026E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -1.12200E+00 MeV Emin = 1.12596E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -1.17040E+00 MeV Emin = 1.16013E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -1.22190E+00 MeV Emin = 1.23562E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -1.27790E+00 MeV Emin = 1.26621E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -1.51680E+00 MeV Emin = 1.53190E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -1.52920E+00 MeV Emin = 1.53985E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 21 MT = 91 Q = -1.52920E+00 MeV Emin = 1.53985E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 22 MT = 102 Q = 1.05206E+01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 36084.82c : (n,gamma) + 23 MT = 103 Q = -1.90030E-01 MeV Emin = 1.53985E+00 MeV frac = 1.00000E+00 Product nuclide = 350830 : (n,p) + 24 MT = 104 Q = -7.54790E+00 MeV Emin = 1.02500E+01 MeV frac = 1.00000E+00 Product nuclide = 350820 : (n,d) + 25 MT = 105 Q = -8.88320E+00 MeV Emin = 8.99130E+00 MeV frac = 1.00000E+00 Product nuclide = 35081.82c : (n,t) + 26 MT = 106 Q = -1.04500E+01 MeV Emin = 1.65000E+01 MeV frac = 1.00000E+00 Product nuclide = 340810 : (n,He-3) + 27 MT = 107 Q = 3.42600E+00 MeV Emin = 2.28125E-07 MeV frac = 1.00000E+00 Product nuclide = 34080.82c : (n,alpha) + 28 MT = 111 Q = -8.89320E+00 MeV Emin = 1.72500E+01 MeV frac = 1.00000E+00 Product nuclide = 34082.82c : (n,2p) + + 8 additional transport branches: + + 1 MT = 22 Q = -6.48720E+00 MeV Emin = 1.22500E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -9.77250E+00 MeV Emin = 1.17500E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -1.90030E-01 MeV Emin = 1.53985E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -7.54790E+00 MeV Emin = 1.02500E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -8.88320E+00 MeV Emin = 8.99130E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 106 Q = -1.04500E+01 MeV Emin = 1.65000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 7 MT = 107 Q = 3.42600E+00 MeV Emin = 2.28125E-07 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 8 MT = 111 Q = -8.89320E+00 MeV Emin = 1.72500E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.53985E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.02500E+01 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 8.99130E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.65000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 2.28125E-07 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 2.18750E-07 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 9.25000E-03 MeV : total inelastic scattering + + Nuclide 81 / 1657 : 36084.82c -- krypton 84 (Kr-84) + + Pointers : 538977 27147 + Primary type : Transport + Nuclide ZAI : 360840 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Kr84.ACE + Atomic weight (AW) : 83.91144 + Atomic weight ratio (AWR) : 83.19060 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 23 reaction channels + - 7 special reactions + - 8 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 23 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.05180E+01 MeV Emin = 1.06444E+01 MeV frac = 1.00000E+00 Product nuclide = 36083.82c : (n,2n) + 3 MT = 51 Q = -8.82000E-01 MeV Emin = 8.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 4 MT = 52 Q = -1.83400E+00 MeV Emin = 1.70000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 5 MT = 53 Q = -1.90000E+00 MeV Emin = 1.90000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 6 MT = 54 Q = -2.08600E+00 MeV Emin = 2.11108E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 7 MT = 55 Q = -2.33700E+00 MeV Emin = 2.36509E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 8 MT = 56 Q = -2.70500E+00 MeV Emin = 2.73752E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 9 MT = 57 Q = -2.77500E+00 MeV Emin = 2.80836E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 10 MT = 58 Q = -3.04800E+00 MeV Emin = 3.08464E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 11 MT = 59 Q = -3.22500E+00 MeV Emin = 3.26377E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 12 MT = 60 Q = -3.44700E+00 MeV Emin = 3.48844E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 13 MT = 61 Q = -3.57000E+00 MeV Emin = 3.61292E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 14 MT = 62 Q = -3.65000E+00 MeV Emin = 3.69388E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 15 MT = 63 Q = -3.72100E+00 MeV Emin = 3.76573E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 16 MT = 91 Q = -8.82000E-01 MeV Emin = 8.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 17 MT = 102 Q = 7.11100E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 36085.82c : (n,gamma) + 18 MT = 103 Q = -3.92000E+00 MeV Emin = 5.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 350840 : (n,p) + 19 MT = 104 Q = -8.48040E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 350830 : (n,d) + 20 MT = 105 Q = -1.18080E+01 MeV Emin = 1.19499E+01 MeV frac = 1.00000E+00 Product nuclide = 350820 : (n,t) + 21 MT = 106 Q = -1.17070E+01 MeV Emin = 1.90000E+01 MeV frac = 1.00000E+00 Product nuclide = 34082.82c : (n,He-3) + 22 MT = 107 Q = -3.94400E-01 MeV Emin = 3.99000E-01 MeV frac = 1.00000E+00 Product nuclide = 340810 : (n,alpha) + 23 MT = 111 Q = -1.35240E+01 MeV Emin = 1.36866E+01 MeV frac = 1.00000E+00 Product nuclide = 340830 : (n,2p) + + 7 additional transport branches: + + 1 MT = 102 Q = 7.11100E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 360851 : (n,gamma) + 2 MT = 103 Q = -3.92000E+00 MeV Emin = 5.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 104 Q = -8.48040E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 4 MT = 105 Q = -1.18080E+01 MeV Emin = 1.19499E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 5 MT = 106 Q = -1.17070E+01 MeV Emin = 1.90000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 6 MT = 107 Q = -3.94400E-01 MeV Emin = 3.99000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 7 MT = 111 Q = -1.35240E+01 MeV Emin = 1.36866E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 5.50000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.10000E+01 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.19499E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.90000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 3.99000E-01 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 8.00000E-01 MeV : total inelastic scattering + + Nuclide 82 / 1657 : 36085.82c -- krypton 85 (Kr-85) + + Pointers : 541808 27193 + Primary type : Transport + Nuclide ZAI : 360850 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Kr85.ACE + Atomic weight (AW) : 84.91254 + Atomic weight ratio (AWR) : 84.18310 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 3.39E+08 seconds (10.8 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 10 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 6 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 10 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -3.05000E-01 MeV Emin = 2.81465E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 91 Q = -9.88270E-01 MeV Emin = 9.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 4 MT = 102 Q = 9.98000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 36086.82c : (n,gamma) + 5 MT = 103 Q = -2.01850E+00 MeV Emin = 2.04248E+00 MeV frac = 1.00000E+00 Product nuclide = 350850 : (n,p) + 6 MT = 104 Q = -8.77410E+00 MeV Emin = 8.87833E+00 MeV frac = 1.00000E+00 Product nuclide = 350840 : (n,d) + 7 MT = 105 Q = -9.32170E+00 MeV Emin = 9.43243E+00 MeV frac = 1.00000E+00 Product nuclide = 350830 : (n,t) + 8 MT = 106 Q = -1.29170E+01 MeV Emin = 1.30704E+01 MeV frac = 1.00000E+00 Product nuclide = 340830 : (n,He-3) + 9 MT = 107 Q = 1.76000E+00 MeV Emin = 4.81250E-02 MeV frac = 1.00000E+00 Product nuclide = 34082.82c : (n,alpha) + 10 MT = 111 Q = -1.20320E+01 MeV Emin = 1.21749E+01 MeV frac = 1.00000E+00 Product nuclide = 340840 : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = -2.01850E+00 MeV Emin = 2.04248E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -8.77410E+00 MeV Emin = 8.87833E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -9.32170E+00 MeV Emin = 9.43243E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -1.29170E+01 MeV Emin = 1.30704E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 1.76000E+00 MeV Emin = 4.81250E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -1.20320E+01 MeV Emin = 1.21749E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.04248E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.87833E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.43243E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.30704E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.81250E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 2.81465E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.87100E-01 MeV frac = 1.00000E+00 Product nuclide = 37085.82c : beta- + + Nuclide 83 / 1657 : 36086.82c -- krypton 86 (Kr-86) + + Pointers : 544694 27239 + Primary type : Transport + Nuclide ZAI : 360860 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Kr86.ACE + Atomic weight (AW) : 85.91062 + Atomic weight ratio (AWR) : 85.17260 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 25 reaction channels + - 7 special reactions + - 9 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 25 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -9.86000E+00 MeV Emin = 9.99000E+00 MeV frac = 1.00000E+00 Product nuclide = 36085.82c : (n,2n) + 3 MT = 17 Q = -1.69710E+01 MeV Emin = 1.73000E+01 MeV frac = 1.00000E+00 Product nuclide = 36084.82c : (n,3n) + 4 MT = 51 Q = -1.56300E+00 MeV Emin = 1.58000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 5 MT = 52 Q = -2.24800E+00 MeV Emin = 2.27439E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 6 MT = 53 Q = -2.35500E+00 MeV Emin = 2.38265E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 7 MT = 54 Q = -2.73300E+00 MeV Emin = 2.76509E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 8 MT = 55 Q = -3.10900E+00 MeV Emin = 3.14550E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 9 MT = 56 Q = -3.54200E+00 MeV Emin = 3.58359E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 10 MT = 57 Q = -3.83200E+00 MeV Emin = 3.87699E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 11 MT = 58 Q = -3.95900E+00 MeV Emin = 4.00548E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 12 MT = 59 Q = -4.11100E+00 MeV Emin = 4.15927E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 13 MT = 60 Q = -4.19400E+00 MeV Emin = 4.24324E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 14 MT = 61 Q = -4.29800E+00 MeV Emin = 4.34846E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 15 MT = 62 Q = -4.66800E+00 MeV Emin = 4.72281E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 16 MT = 63 Q = -4.82600E+00 MeV Emin = 4.88266E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 17 MT = 64 Q = -4.94800E+00 MeV Emin = 5.00610E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 18 MT = 91 Q = -1.56300E+00 MeV Emin = 1.58601E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 19 MT = 102 Q = 5.51100E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 360870 : (n,gamma) + 20 MT = 103 Q = -6.52000E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 350860 : (n,p) + 21 MT = 104 Q = -9.65540E+00 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 350850 : (n,d) + 22 MT = 105 Q = -1.24100E+01 MeV Emin = 1.55000E+01 MeV frac = 1.00000E+00 Product nuclide = 350840 : (n,t) + 23 MT = 106 Q = -1.41760E+01 MeV Emin = 1.43424E+01 MeV frac = 1.00000E+00 Product nuclide = 340840 : (n,He-3) + 24 MT = 107 Q = -2.20580E+00 MeV Emin = 2.23170E+00 MeV frac = 1.00000E+00 Product nuclide = 340830 : (n,alpha) + 25 MT = 111 Q = -1.71930E+01 MeV Emin = 1.73949E+01 MeV frac = 1.00000E+00 Product nuclide = 340850 : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = -6.52000E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -9.65540E+00 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -1.24100E+01 MeV Emin = 1.55000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -1.41760E+01 MeV Emin = 1.43424E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = -2.20580E+00 MeV Emin = 2.23170E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -1.71930E+01 MeV Emin = 1.73949E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 8.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.25000E+01 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.55000E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.43424E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 2.23170E+00 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 1.58000E+00 MeV : total inelastic scattering + + Nuclide 84 / 1657 : 37085.82c -- rubidium 85 (Rb-85) + + Pointers : 572577 31241 + Primary type : Transport + Nuclide ZAI : 370850 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Rb85.ACE + Atomic weight (AW) : 84.91184 + Atomic weight ratio (AWR) : 84.18240 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 12 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 12 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -1.51300E-01 MeV Emin = 1.52500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -5.14000E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -8.70000E-01 MeV Emin = 8.80000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 91 Q = -9.88270E-01 MeV Emin = 9.70084E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 6 MT = 102 Q = 8.65040E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 37086.82c : (n,gamma) + 7 MT = 103 Q = 9.56580E-02 MeV Emin = 4.75000E-02 MeV frac = 1.00000E+00 Product nuclide = 36085.82c : (n,p) + 8 MT = 104 Q = -4.78950E+00 MeV Emin = 4.84640E+00 MeV frac = 1.00000E+00 Product nuclide = 36084.82c : (n,d) + 9 MT = 105 Q = -9.04910E+00 MeV Emin = 9.15659E+00 MeV frac = 1.00000E+00 Product nuclide = 36083.82c : (n,t) + 10 MT = 106 Q = -9.99030E+00 MeV Emin = 1.01090E+01 MeV frac = 1.00000E+00 Product nuclide = 350830 : (n,He-3) + 11 MT = 107 Q = 9.85360E-01 MeV Emin = 4.75000E-02 MeV frac = 1.00000E+00 Product nuclide = 350820 : (n,alpha) + 12 MT = 111 Q = -1.09020E+01 MeV Emin = 1.10315E+01 MeV frac = 1.00000E+00 Product nuclide = 350840 : (n,2p) + + 7 additional transport branches: + + 1 MT = 102 Q = 8.65040E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 370861 : (n,gamma) + 2 MT = 103 Q = 9.56580E-02 MeV Emin = 4.75000E-02 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 104 Q = -4.78950E+00 MeV Emin = 4.84640E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 4 MT = 105 Q = -9.04910E+00 MeV Emin = 9.15659E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 5 MT = 106 Q = -9.99030E+00 MeV Emin = 1.01090E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 6 MT = 107 Q = 9.85360E-01 MeV Emin = 4.75000E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 7 MT = 111 Q = -1.09020E+01 MeV Emin = 1.10315E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.75000E-02 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 4.84640E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.15659E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.01090E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.75000E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 1.52500E-01 MeV : total inelastic scattering + + Nuclide 85 / 1657 : 37086.82c -- rubidium 86 (Rb-86) + + Pointers : 574605 31287 + Primary type : Transport + Nuclide ZAI : 370860 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Rb86.ACE + Atomic weight (AW) : 85.91122 + Atomic weight ratio (AWR) : 85.17320 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.61E+06 seconds (18.6 days) + Specific ingestion toxicity : 2.80E-09 Sv/Bq + Specific inhalation toxicity : 9.30E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 10 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 6 transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 10 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -5.60000E-01 MeV Emin = 5.49928E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 91 Q = -5.63390E-01 MeV Emin = 5.68287E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 4 MT = 102 Q = 1.03600E+01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 37087.82c : (n,gamma) + 5 MT = 103 Q = 1.30750E+00 MeV Emin = 4.81250E-02 MeV frac = 1.00000E+00 Product nuclide = 36086.82c : (n,p) + 6 MT = 104 Q = -6.32790E+00 MeV Emin = 6.40219E+00 MeV frac = 1.00000E+00 Product nuclide = 36085.82c : (n,d) + 7 MT = 105 Q = -7.18140E+00 MeV Emin = 7.26572E+00 MeV frac = 1.00000E+00 Product nuclide = 36084.82c : (n,t) + 8 MT = 106 Q = -1.18350E+01 MeV Emin = 1.19740E+01 MeV frac = 1.00000E+00 Product nuclide = 350840 : (n,He-3) + 9 MT = 107 Q = 1.93310E+00 MeV Emin = 4.81250E-02 MeV frac = 1.00000E+00 Product nuclide = 350830 : (n,alpha) + 10 MT = 111 Q = -1.05700E+01 MeV Emin = 1.06941E+01 MeV frac = 1.00000E+00 Product nuclide = 350850 : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = 1.30750E+00 MeV Emin = 4.81250E-02 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -6.32790E+00 MeV Emin = 6.40219E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -7.18140E+00 MeV Emin = 7.26572E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -1.18350E+01 MeV Emin = 1.19740E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 1.93310E+00 MeV Emin = 4.81250E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -1.05700E+01 MeV Emin = 1.06941E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.81250E-02 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.40219E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 7.26572E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.19740E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.81250E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 5.49928E-01 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 2 Q = 5.18000E-01 MeV frac = 5.20000E-05 Product nuclide = 36086.82c : EC/beta+ + 2 RTYP = 1 Q = 1.77430E+00 MeV frac = 9.99950E-01 Product nuclide = 38086.82c : beta- + + Nuclide 86 / 1657 : 37087.82c -- rubidium 87 (Rb-87) + + Pointers : 577113 31333 + Primary type : Transport + Nuclide ZAI : 370870 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Rb87.ACE + Atomic weight (AW) : 86.90920 + Atomic weight ratio (AWR) : 86.16260 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.52E+18 seconds (48.1 billion years) + Specific ingestion toxicity : 1.50E-09 Sv/Bq + Specific inhalation toxicity : 5.00E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 11 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 6 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 11 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -4.05000E-01 MeV Emin = 3.89850E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -8.50000E-01 MeV Emin = 8.19902E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 91 Q = -8.50000E-01 MeV Emin = 8.19902E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 5 MT = 102 Q = 6.08300E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 370880 : (n,gamma) + 6 MT = 103 Q = -3.10500E+00 MeV Emin = 3.14104E+00 MeV frac = 1.00000E+00 Product nuclide = 360870 : (n,p) + 7 MT = 104 Q = -6.39480E+00 MeV Emin = 6.46902E+00 MeV frac = 1.00000E+00 Product nuclide = 36086.82c : (n,d) + 8 MT = 105 Q = -9.99850E+00 MeV Emin = 1.01145E+01 MeV frac = 1.00000E+00 Product nuclide = 36085.82c : (n,t) + 9 MT = 106 Q = -1.27810E+01 MeV Emin = 1.29293E+01 MeV frac = 1.00000E+00 Product nuclide = 350850 : (n,He-3) + 10 MT = 107 Q = -1.18980E+00 MeV Emin = 1.20336E+00 MeV frac = 1.00000E+00 Product nuclide = 350840 : (n,alpha) + 11 MT = 111 Q = -1.51370E+01 MeV Emin = 1.53127E+01 MeV frac = 1.00000E+00 Product nuclide = 350860 : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = -3.10500E+00 MeV Emin = 3.14104E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -6.39480E+00 MeV Emin = 6.46902E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -9.99850E+00 MeV Emin = 1.01145E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -1.27810E+01 MeV Emin = 1.29293E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = -1.18980E+00 MeV Emin = 1.20336E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -1.51370E+01 MeV Emin = 1.53127E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.14104E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.46902E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.01145E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.29293E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.20336E+00 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 3.89850E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.83300E-01 MeV frac = 1.00000E+00 Product nuclide = 38087.82c : beta- + + Nuclide 87 / 1657 : 38086.82c -- strontium 86 (Sr-86) + + Pointers : 618703 34001 + Primary type : Transport + Nuclide ZAI : 380860 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Sr86.ACE + Atomic weight (AW) : 85.90931 + Atomic weight ratio (AWR) : 85.17130 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 16 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 16 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -1.08000E+00 MeV Emin = 1.09020E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -1.86000E+00 MeV Emin = 1.74090E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -2.23000E+00 MeV Emin = 2.25620E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -2.48000E+00 MeV Emin = 2.50912E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -2.68000E+00 MeV Emin = 2.71150E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -3.00000E+00 MeV Emin = 3.03522E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 57 Q = -3.19000E+00 MeV Emin = 3.22750E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 9 MT = 91 Q = -3.16280E+00 MeV Emin = 3.20000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 10 MT = 102 Q = 8.42830E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 38087.82c : (n,gamma) + 11 MT = 103 Q = -9.91450E-01 MeV Emin = 1.00288E+00 MeV frac = 1.00000E+00 Product nuclide = 37086.82c : (n,p) + 12 MT = 104 Q = -7.41500E+00 MeV Emin = 7.50206E+00 MeV frac = 1.00000E+00 Product nuclide = 37085.82c : (n,d) + 13 MT = 105 Q = -1.16340E+01 MeV Emin = 1.17706E+01 MeV frac = 1.00000E+00 Product nuclide = 370840 : (n,t) + 14 MT = 106 Q = -8.93710E+00 MeV Emin = 9.04203E+00 MeV frac = 1.00000E+00 Product nuclide = 36084.82c : (n,He-3) + 15 MT = 107 Q = 1.11860E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 36083.82c : (n,alpha) + 16 MT = 111 Q = -9.54340E+00 MeV Emin = 9.65545E+00 MeV frac = 1.00000E+00 Product nuclide = 36085.82c : (n,2p) + + 7 additional transport branches: + + 1 MT = 102 Q = 8.42830E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 380871 : (n,gamma) + 2 MT = 103 Q = -9.91450E-01 MeV Emin = 1.00288E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 104 Q = -7.41500E+00 MeV Emin = 7.50206E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 4 MT = 105 Q = -1.16340E+01 MeV Emin = 1.17706E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 5 MT = 106 Q = -8.93710E+00 MeV Emin = 9.04203E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 6 MT = 107 Q = 1.11860E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 7 MT = 111 Q = -9.54340E+00 MeV Emin = 9.65545E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.00288E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.50206E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.17706E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 9.04203E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.62500E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 1.09020E+00 MeV : total inelastic scattering + + Nuclide 88 / 1657 : 38087.82c -- strontium 87 (Sr-87) + + Pointers : 621023 34047 + Primary type : Transport + Nuclide ZAI : 380870 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Sr87.ACE + Atomic weight (AW) : 86.90889 + Atomic weight ratio (AWR) : 86.16230 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 16 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 16 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -3.88000E-01 MeV Emin = 3.70000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -8.71000E-01 MeV Emin = 8.79006E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -1.22000E+00 MeV Emin = 1.12500E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -1.70000E+00 MeV Emin = 1.60000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -2.10000E+00 MeV Emin = 2.12440E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -2.39000E+00 MeV Emin = 2.41774E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 57 Q = -2.61000E+00 MeV Emin = 2.64030E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 9 MT = 91 Q = -2.58990E+00 MeV Emin = 2.62000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 10 MT = 102 Q = 1.11130E+01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 38088.82c : (n,gamma) + 11 MT = 103 Q = 5.09310E-01 MeV Emin = 4.81250E-02 MeV frac = 1.00000E+00 Product nuclide = 37087.82c : (n,p) + 12 MT = 104 Q = -7.19290E+00 MeV Emin = 7.27638E+00 MeV frac = 1.00000E+00 Product nuclide = 37086.82c : (n,d) + 13 MT = 105 Q = -9.58480E+00 MeV Emin = 9.69604E+00 MeV frac = 1.00000E+00 Product nuclide = 37085.82c : (n,t) + 14 MT = 106 Q = -1.02530E+01 MeV Emin = 1.03720E+01 MeV frac = 1.00000E+00 Product nuclide = 36085.82c : (n,He-3) + 15 MT = 107 Q = 3.20840E+00 MeV Emin = 4.81250E-02 MeV frac = 1.00000E+00 Product nuclide = 36084.82c : (n,alpha) + 16 MT = 111 Q = -8.10950E+00 MeV Emin = 8.20362E+00 MeV frac = 1.00000E+00 Product nuclide = 36086.82c : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = 5.09310E-01 MeV Emin = 4.81250E-02 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -7.19290E+00 MeV Emin = 7.27638E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -9.58480E+00 MeV Emin = 9.69604E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -1.02530E+01 MeV Emin = 1.03720E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 3.20840E+00 MeV Emin = 4.81250E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -8.10950E+00 MeV Emin = 8.20362E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.81250E-02 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.27638E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.69604E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.03720E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.81250E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 3.70000E-01 MeV : total inelastic scattering + + Nuclide 89 / 1657 : 38088.82c -- strontium 88 (Sr-88) + + Pointers : 623849 34093 + Primary type : Transport + Nuclide ZAI : 380880 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Sr88.ACE + Atomic weight (AW) : 87.90566 + Atomic weight ratio (AWR) : 87.15050 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 14 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 14 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -1.84000E+00 MeV Emin = 1.79583E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -2.73000E+00 MeV Emin = 2.76133E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -3.24000E+00 MeV Emin = 3.27720E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -3.52000E+00 MeV Emin = 3.56040E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -3.68000E+00 MeV Emin = 3.72223E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 91 Q = -3.64820E+00 MeV Emin = 3.69006E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 8 MT = 102 Q = 6.36010E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 38089.82c : (n,gamma) + 9 MT = 103 Q = -4.52440E+00 MeV Emin = 4.57632E+00 MeV frac = 1.00000E+00 Product nuclide = 370880 : (n,p) + 10 MT = 104 Q = -8.37630E+00 MeV Emin = 8.47241E+00 MeV frac = 1.00000E+00 Product nuclide = 37087.82c : (n,d) + 11 MT = 105 Q = -1.20470E+01 MeV Emin = 1.21852E+01 MeV frac = 1.00000E+00 Product nuclide = 37086.82c : (n,t) + 12 MT = 106 Q = -1.15040E+01 MeV Emin = 1.16360E+01 MeV frac = 1.00000E+00 Product nuclide = 36086.82c : (n,He-3) + 13 MT = 107 Q = -7.92030E-01 MeV Emin = 8.00953E-01 MeV frac = 1.00000E+00 Product nuclide = 36085.82c : (n,alpha) + 14 MT = 111 Q = -1.37050E+01 MeV Emin = 1.38623E+01 MeV frac = 1.00000E+00 Product nuclide = 360870 : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = -4.52440E+00 MeV Emin = 4.57632E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -8.37630E+00 MeV Emin = 8.47241E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -1.20470E+01 MeV Emin = 1.21852E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -1.15040E+01 MeV Emin = 1.16360E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = -7.92030E-01 MeV Emin = 8.00953E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -1.37050E+01 MeV Emin = 1.38623E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.57632E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.47241E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.21852E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.16360E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 8.00953E-01 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 1.79583E+00 MeV : total inelastic scattering + + Nuclide 90 / 1657 : 38089.82c -- strontium 89 (Sr-89) + + Pointers : 625931 34139 + Primary type : Transport + Nuclide ZAI : 380890 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Sr89.ACE + Atomic weight (AW) : 88.90746 + Atomic weight ratio (AWR) : 88.14370 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 4.37E+06 seconds (50.6 days) + Specific ingestion toxicity : 2.60E-09 Sv/Bq + Specific inhalation toxicity : 7.90E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 21 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 6 transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 21 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -1.05000E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -2.00000E+00 MeV Emin = 2.02270E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -2.31000E+00 MeV Emin = 2.33621E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -2.44000E+00 MeV Emin = 2.46770E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -2.59000E+00 MeV Emin = 2.61940E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -2.67000E+00 MeV Emin = 2.70030E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 57 Q = -2.75000E+00 MeV Emin = 2.78120E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 9 MT = 58 Q = -2.99000E+00 MeV Emin = 3.02392E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 10 MT = 59 Q = -3.18000E+00 MeV Emin = 3.21610E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 11 MT = 60 Q = -3.25000E+00 MeV Emin = 3.28690E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 12 MT = 61 Q = -3.50000E+00 MeV Emin = 3.53971E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 13 MT = 62 Q = -3.74000E+00 MeV Emin = 3.78243E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 14 MT = 91 Q = -3.70800E+00 MeV Emin = 3.75007E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 15 MT = 102 Q = 7.71000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 38090.82c : (n,gamma) + 16 MT = 103 Q = -3.70210E+00 MeV Emin = 3.74410E+00 MeV frac = 1.00000E+00 Product nuclide = 370890 : (n,p) + 17 MT = 104 Q = -8.66230E+00 MeV Emin = 8.76058E+00 MeV frac = 1.00000E+00 Product nuclide = 370880 : (n,d) + 18 MT = 105 Q = -8.48240E+00 MeV Emin = 8.57864E+00 MeV frac = 1.00000E+00 Product nuclide = 37087.82c : (n,t) + 19 MT = 106 Q = -1.23520E+01 MeV Emin = 1.24921E+01 MeV frac = 1.00000E+00 Product nuclide = 360870 : (n,He-3) + 20 MT = 107 Q = 2.70550E+00 MeV Emin = 4.75000E-02 MeV frac = 1.00000E+00 Product nuclide = 36086.82c : (n,alpha) + 21 MT = 111 Q = -1.30160E+01 MeV Emin = 1.31637E+01 MeV frac = 1.00000E+00 Product nuclide = 360880 : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = -3.70210E+00 MeV Emin = 3.74410E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -8.66230E+00 MeV Emin = 8.76058E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -8.48240E+00 MeV Emin = 8.57864E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -1.23520E+01 MeV Emin = 1.24921E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 2.70550E+00 MeV Emin = 4.75000E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -1.30160E+01 MeV Emin = 1.31637E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.74410E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.76058E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 8.57864E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.24921E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.75000E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 1.00000E+00 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.49510E+00 MeV frac = 9.99904E-01 Product nuclide = 39089.82c : beta- + 2 RTYP = 1 Q = 5.86100E-01 MeV frac = 9.64000E-05 Product nuclide = 390891 : beta- + + Nuclide 91 / 1657 : 38090.82c -- strontium 90 (Sr-90) + + Pointers : 628717 34185 + Primary type : Transport + Nuclide ZAI : 380900 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Sr90.ACE + Atomic weight (AW) : 89.90775 + Atomic weight ratio (AWR) : 89.13540 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 9.09E+08 seconds (28.8 years) + Specific ingestion toxicity : 2.80E-08 Sv/Bq + Specific inhalation toxicity : 1.60E-07 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 13 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 6 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 13 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -8.30000E-01 MeV Emin = 8.21896E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -1.69000E+00 MeV Emin = 1.70000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -1.94000E+00 MeV Emin = 1.90000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -2.23000E+00 MeV Emin = 2.25502E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 91 Q = -2.21520E+00 MeV Emin = 2.24005E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 7 MT = 102 Q = 5.96000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 380910 : (n,gamma) + 8 MT = 103 Q = -5.58020E+00 MeV Emin = 5.64281E+00 MeV frac = 1.00000E+00 Product nuclide = 370900 : (n,p) + 9 MT = 104 Q = -9.27870E+00 MeV Emin = 9.38280E+00 MeV frac = 1.00000E+00 Product nuclide = 370890 : (n,d) + 10 MT = 105 Q = -1.02070E+01 MeV Emin = 1.03215E+01 MeV frac = 1.00000E+00 Product nuclide = 370880 : (n,t) + 11 MT = 106 Q = -1.31010E+01 MeV Emin = 1.32480E+01 MeV frac = 1.00000E+00 Product nuclide = 360880 : (n,He-3) + 12 MT = 107 Q = 4.18620E-01 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 360870 : (n,alpha) + 13 MT = 111 Q = -1.56460E+01 MeV Emin = 1.58215E+01 MeV frac = 1.00000E+00 Product nuclide = 360890 : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = -5.58020E+00 MeV Emin = 5.64281E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -9.27870E+00 MeV Emin = 9.38280E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -1.02070E+01 MeV Emin = 1.03215E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -1.31010E+01 MeV Emin = 1.32480E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 4.18620E-01 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -1.56460E+01 MeV Emin = 1.58215E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 5.64281E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 9.38280E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.03215E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.32480E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.62500E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 8.21896E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.45900E-01 MeV frac = 1.00000E+00 Product nuclide = 39090.82c : beta- + + Nuclide 92 / 1657 : 39089.82c -- yttrium 89 (Y-89) + + Pointers : 646829 36623 + Primary type : Transport + Nuclide ZAI : 390890 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Y89.ACE + Atomic weight (AW) : 88.90585 + Atomic weight ratio (AWR) : 88.14210 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 42 reaction channels + - 82 special reactions + - 7 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 42 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.14760E+01 MeV Emin = 1.16062E+01 MeV frac = 1.00000E+00 Product nuclide = 390880 : (n,2n) + 3 MT = 22 Q = -7.95900E+00 MeV Emin = 1.15000E+01 MeV frac = 1.00000E+00 Product nuclide = 37085.82c : (n,nalpha) + 4 MT = 28 Q = -7.07100E+00 MeV Emin = 8.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 38088.82c : (n,np) + 5 MT = 41 Q = -1.81840E+01 MeV Emin = 1.95000E+01 MeV frac = 1.00000E+00 Product nuclide = 38087.82c : (n,2np) + 6 MT = 51 Q = -9.08960E-01 MeV Emin = 9.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.50726E+00 MeV Emin = 1.51218E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -1.74457E+00 MeV Emin = 1.70000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -2.22239E+00 MeV Emin = 2.24761E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -2.52987E+00 MeV Emin = 2.55857E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -2.56624E+00 MeV Emin = 2.59536E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -2.62204E+00 MeV Emin = 2.65179E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -2.87180E+00 MeV Emin = 2.90438E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -2.88120E+00 MeV Emin = 2.91389E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -2.89470E+00 MeV Emin = 2.92754E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -3.06760E+00 MeV Emin = 3.10240E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -3.10706E+00 MeV Emin = 3.14231E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -3.13890E+00 MeV Emin = 3.17451E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -3.24750E+00 MeV Emin = 3.28435E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -3.34308E+00 MeV Emin = 3.38101E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 21 MT = 66 Q = -3.41050E+00 MeV Emin = 3.44919E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 22 MT = 67 Q = -3.45120E+00 MeV Emin = 3.49036E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 23 MT = 68 Q = -3.50360E+00 MeV Emin = 3.54335E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 24 MT = 69 Q = -3.51560E+00 MeV Emin = 3.55549E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 25 MT = 70 Q = -3.55710E+00 MeV Emin = 3.59746E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 26 MT = 71 Q = -3.56000E+00 MeV Emin = 3.60039E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 27 MT = 72 Q = -3.62100E+00 MeV Emin = 3.66208E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 28 MT = 73 Q = -3.63030E+00 MeV Emin = 3.67149E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 29 MT = 74 Q = -3.71530E+00 MeV Emin = 3.75745E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 30 MT = 75 Q = -3.74770E+00 MeV Emin = 3.79022E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 31 MT = 76 Q = -3.75270E+00 MeV Emin = 3.79528E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 32 MT = 77 Q = -3.84810E+00 MeV Emin = 3.89176E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 27. excited state + 33 MT = 78 Q = -3.86230E+00 MeV Emin = 3.90612E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 28. excited state + 34 MT = 79 Q = -3.92400E+00 MeV Emin = 3.96852E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 29. excited state + 35 MT = 80 Q = -3.97690E+00 MeV Emin = 4.02202E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 30. excited state + 36 MT = 81 Q = -3.99160E+00 MeV Emin = 4.03689E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 31. excited state + 37 MT = 82 Q = -4.01530E+00 MeV Emin = 4.06086E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 32. excited state + 38 MT = 83 Q = -4.02280E+00 MeV Emin = 4.06844E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 33. excited state + 39 MT = 91 Q = -9.78894E-01 MeV Emin = 9.54642E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 40 MT = 102 Q = 6.85704E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 39090.82c : (n,gamma) + 41 MT = 103 Q = 0.00000E+00 MeV Emin = 1.88240E+00 MeV frac = 1.00000E+00 Product nuclide = 38089.82c : (n,p) + 42 MT = 107 Q = 0.00000E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 37086.82c : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = -7.95900E+00 MeV Emin = 1.15000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -7.07100E+00 MeV Emin = 8.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 41 Q = -1.81840E+01 MeV Emin = 1.95000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,2np) + 4 MT = 102 Q = 6.85704E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 390901 : (n,gamma) + 5 MT = 103 Q = 0.00000E+00 MeV Emin = 1.88240E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 107 Q = 0.00000E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 82 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.88240E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 3.00000E+00 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 5.31250E-04 MeV : damage-energy production + 4 MT = 600 Q = -7.13000E-01 MeV Emin = 1.88240E+00 MeV : (n,p) to ground state + 5 MT = 601 Q = -1.74500E+00 MeV Emin = 3.00000E+00 MeV : (n,p1) + 6 MT = 602 Q = -2.18636E+00 MeV Emin = 3.50000E+00 MeV : (n,p2) + 7 MT = 603 Q = -2.65321E+00 MeV Emin = 4.00000E+00 MeV : (n,p3) + 8 MT = 604 Q = -2.72060E+00 MeV Emin = 4.00000E+00 MeV : (n,p4) + 9 MT = 605 Q = -2.77040E+00 MeV Emin = 4.00000E+00 MeV : (n,p5) + 10 MT = 606 Q = -2.77440E+00 MeV Emin = 4.00000E+00 MeV : (n,p6) + 11 MT = 607 Q = -2.79180E+00 MeV Emin = 4.00000E+00 MeV : (n,p7) + 12 MT = 608 Q = -2.99319E+00 MeV Emin = 4.00000E+00 MeV : (n,p8) + 13 MT = 609 Q = -3.16464E+00 MeV Emin = 4.50000E+00 MeV : (n,p9) + 14 MT = 610 Q = -3.28312E+00 MeV Emin = 4.50000E+00 MeV : (n,p10) + 15 MT = 611 Q = -3.38800E+00 MeV Emin = 4.50000E+00 MeV : (n,p11) + 16 MT = 612 Q = -3.42013E+00 MeV Emin = 4.50000E+00 MeV : (n,p12) + 17 MT = 613 Q = -3.51800E+00 MeV Emin = 4.50000E+00 MeV : (n,p13) + 18 MT = 614 Q = -3.62900E+00 MeV Emin = 5.00000E+00 MeV : (n,p14) + 19 MT = 615 Q = -3.64360E+00 MeV Emin = 5.00000E+00 MeV : (n,p15) + 20 MT = 616 Q = -3.67470E+00 MeV Emin = 5.00000E+00 MeV : (n,p16) + 21 MT = 617 Q = -3.78600E+00 MeV Emin = 5.00000E+00 MeV : (n,p17) + 22 MT = 618 Q = -3.83900E+00 MeV Emin = 5.00000E+00 MeV : (n,p18) + 23 MT = 619 Q = -3.91300E+00 MeV Emin = 5.00000E+00 MeV : (n,p19) + 24 MT = 620 Q = -3.94091E+00 MeV Emin = 5.00000E+00 MeV : (n,p20) + 25 MT = 621 Q = -3.96200E+00 MeV Emin = 5.00000E+00 MeV : (n,p21) + 26 MT = 622 Q = -4.01612E+00 MeV Emin = 5.00000E+00 MeV : (n,p22) + 27 MT = 623 Q = -4.10080E+00 MeV Emin = 5.50000E+00 MeV : (n,p23) + 28 MT = 624 Q = -4.11680E+00 MeV Emin = 5.50000E+00 MeV : (n,p24) + 29 MT = 625 Q = -4.13400E+00 MeV Emin = 5.50000E+00 MeV : (n,p25) + 30 MT = 626 Q = -4.14606E+00 MeV Emin = 5.50000E+00 MeV : (n,p26) + 31 MT = 627 Q = -4.22168E+00 MeV Emin = 5.50000E+00 MeV : (n,p27) + 32 MT = 628 Q = -4.23710E+00 MeV Emin = 5.50000E+00 MeV : (n,p28) + 33 MT = 629 Q = -4.24900E+00 MeV Emin = 5.50000E+00 MeV : (n,p29) + 34 MT = 630 Q = -4.31180E+00 MeV Emin = 5.50000E+00 MeV : (n,p30) + 35 MT = 631 Q = -4.34700E+00 MeV Emin = 5.50000E+00 MeV : (n,p31) + 36 MT = 632 Q = -4.36472E+00 MeV Emin = 5.50000E+00 MeV : (n,p32) + 37 MT = 633 Q = -4.38480E+00 MeV Emin = 5.50000E+00 MeV : (n,p33) + 38 MT = 634 Q = -4.38900E+00 MeV Emin = 5.50000E+00 MeV : (n,p34) + 39 MT = 635 Q = -4.41282E+00 MeV Emin = 5.50000E+00 MeV : (n,p35) + 40 MT = 636 Q = -4.44070E+00 MeV Emin = 5.50000E+00 MeV : (n,p36) + 41 MT = 637 Q = -4.45800E+00 MeV Emin = 5.50000E+00 MeV : (n,p37) + 42 MT = 638 Q = -4.46330E+00 MeV Emin = 5.50000E+00 MeV : (n,p38) + 43 MT = 639 Q = -4.46800E+00 MeV Emin = 5.50000E+00 MeV : (n,p39) + 44 MT = 649 Q = -4.46800E+00 MeV Emin = 4.51869E+00 MeV : (n,p) to continuum + 45 MT = 800 Q = 6.91000E-01 MeV Emin = 3.00000E+00 MeV : (n,alpha) to ground state + 46 MT = 801 Q = 2.02800E-01 MeV Emin = 3.50000E+00 MeV : (n,a1) + 47 MT = 802 Q = 1.34950E-01 MeV Emin = 3.50000E+00 MeV : (n,a2) + 48 MT = 803 Q = 1.34000E-01 MeV Emin = 3.50000E+00 MeV : (n,a3) + 49 MT = 804 Q = -8.93000E-02 MeV Emin = 3.70000E+00 MeV : (n,a4) + 50 MT = 805 Q = -1.82200E-01 MeV Emin = 3.70000E+00 MeV : (n,a5) + 51 MT = 806 Q = -2.87700E-01 MeV Emin = 4.00000E+00 MeV : (n,a6) + 52 MT = 807 Q = -3.36200E-01 MeV Emin = 4.00000E+00 MeV : (n,a7) + 53 MT = 808 Q = -3.41700E-01 MeV Emin = 4.00000E+00 MeV : (n,a8) + 54 MT = 809 Q = -4.01800E-01 MeV Emin = 4.00000E+00 MeV : (n,a9) + 55 MT = 810 Q = -4.14600E-01 MeV Emin = 4.00000E+00 MeV : (n,a10) + 56 MT = 811 Q = -4.31000E-01 MeV Emin = 4.00000E+00 MeV : (n,a11) + 57 MT = 812 Q = -4.65000E-01 MeV Emin = 4.00000E+00 MeV : (n,a12) + 58 MT = 813 Q = -5.05400E-01 MeV Emin = 4.00000E+00 MeV : (n,a13) + 59 MT = 814 Q = -5.57000E-01 MeV Emin = 4.00000E+00 MeV : (n,a14) + 60 MT = 815 Q = -6.14100E-01 MeV Emin = 4.00000E+00 MeV : (n,a15) + 61 MT = 816 Q = -6.18000E-01 MeV Emin = 4.00000E+00 MeV : (n,a16) + 62 MT = 817 Q = -6.98400E-01 MeV Emin = 4.50000E+00 MeV : (n,a17) + 63 MT = 818 Q = -7.21000E-01 MeV Emin = 4.50000E+00 MeV : (n,a18) + 64 MT = 819 Q = -7.48000E-01 MeV Emin = 4.50000E+00 MeV : (n,a19) + 65 MT = 820 Q = -7.79800E-01 MeV Emin = 4.50000E+00 MeV : (n,a20) + 66 MT = 821 Q = -8.10700E-01 MeV Emin = 4.50000E+00 MeV : (n,a21) + 67 MT = 822 Q = -8.59000E-01 MeV Emin = 4.50000E+00 MeV : (n,a22) + 68 MT = 823 Q = -8.67500E-01 MeV Emin = 4.50000E+00 MeV : (n,a23) + 69 MT = 824 Q = -9.75800E-01 MeV Emin = 4.50000E+00 MeV : (n,a24) + 70 MT = 825 Q = -9.92700E-01 MeV Emin = 4.50000E+00 MeV : (n,a25) + 71 MT = 826 Q = -1.01820E+00 MeV Emin = 4.50000E+00 MeV : (n,a26) + 72 MT = 827 Q = -1.04700E+00 MeV Emin = 4.50000E+00 MeV : (n,a27) + 73 MT = 828 Q = -1.07000E+00 MeV Emin = 4.50000E+00 MeV : (n,a28) + 74 MT = 829 Q = -1.12900E+00 MeV Emin = 4.50000E+00 MeV : (n,a29) + 75 MT = 830 Q = -1.19830E+00 MeV Emin = 4.50000E+00 MeV : (n,a30) + 76 MT = 831 Q = -1.21000E+00 MeV Emin = 4.50000E+00 MeV : (n,a31) + 77 MT = 832 Q = -1.22610E+00 MeV Emin = 5.00000E+00 MeV : (n,a32) + 78 MT = 833 Q = -1.23510E+00 MeV Emin = 5.00000E+00 MeV : (n,a33) + 79 MT = 834 Q = -1.26210E+00 MeV Emin = 5.00000E+00 MeV : (n,a34) + 80 MT = 835 Q = -1.33390E+00 MeV Emin = 5.00000E+00 MeV : (n,a35) + 81 MT = 849 Q = -1.33390E+00 MeV Emin = 5.00000E+00 MeV : (n,alpha) to continuum + 82 MT = 4 Q = 0.00000E+00 MeV Emin = 9.00000E-01 MeV : total inelastic scattering + + Nuclide 93 / 1657 : 39090.82c -- yttrium 90 (Y-90) + + Pointers : 656820 36669 + Primary type : Transport + Nuclide ZAI : 390900 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Y90.ACE + Atomic weight (AW) : 89.90716 + Atomic weight ratio (AWR) : 89.13481 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.30E+05 seconds (2.67 days) + Specific ingestion toxicity : 2.70E-09 Sv/Bq + Specific inhalation toxicity : 1.50E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 11 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 7 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 11 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -2.02000E-01 MeV Emin = 2.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -6.92240E-01 MeV Emin = 6.95000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 91 Q = -6.92240E-01 MeV Emin = 6.95000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 5 MT = 102 Q = 8.17000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 39091.82c : (n,gamma) + 6 MT = 103 Q = 2.36580E-01 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 38090.82c : (n,p) + 7 MT = 104 Q = -5.34010E+00 MeV Emin = 5.40001E+00 MeV frac = 1.00000E+00 Product nuclide = 38089.82c : (n,d) + 8 MT = 105 Q = -5.44620E+00 MeV Emin = 5.50730E+00 MeV frac = 1.00000E+00 Product nuclide = 38088.82c : (n,t) + 9 MT = 106 Q = -1.07350E+01 MeV Emin = 1.08554E+01 MeV frac = 1.00000E+00 Product nuclide = 370880 : (n,He-3) + 10 MT = 107 Q = 3.76020E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 37087.82c : (n,alpha) + 11 MT = 111 Q = -1.12660E+01 MeV Emin = 1.13924E+01 MeV frac = 1.00000E+00 Product nuclide = 370890 : (n,2p) + + 7 additional transport branches: + + 1 MT = 102 Q = 8.17000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 390911 : (n,gamma) + 2 MT = 103 Q = 2.36580E-01 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 104 Q = -5.34010E+00 MeV Emin = 5.40001E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 4 MT = 105 Q = -5.44620E+00 MeV Emin = 5.50730E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 5 MT = 106 Q = -1.07350E+01 MeV Emin = 1.08554E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 6 MT = 107 Q = 3.76020E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 7 MT = 111 Q = -1.12660E+01 MeV Emin = 1.13924E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.62500E-02 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.40001E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 5.50730E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.08554E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.62500E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 2.00000E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.28010E+00 MeV frac = 1.00000E+00 Product nuclide = 40090.82c : beta- + + Nuclide 94 / 1657 : 39091.82c -- yttrium 91 (Y-91) + + Pointers : 659448 36715 + Primary type : Transport + Nuclide ZAI : 390910 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Y91.ACE + Atomic weight (AW) : 90.90735 + Atomic weight ratio (AWR) : 90.12641 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 5.06E+06 seconds (58.5 days) + Specific ingestion toxicity : 2.40E-09 Sv/Bq + Specific inhalation toxicity : 8.90E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 16 reaction channels + - 7 special reactions + - 6 transmutation reactions + - 5 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 16 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -5.55600E-01 MeV Emin = 5.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -6.52900E-01 MeV Emin = 6.53000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -9.25800E-01 MeV Emin = 8.93035E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -1.18690E+00 MeV Emin = 1.18750E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -1.30540E+00 MeV Emin = 1.30000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -1.47370E+00 MeV Emin = 1.44257E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 57 Q = -1.54590E+00 MeV Emin = 1.54500E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 9 MT = 58 Q = -1.58000E+00 MeV Emin = 1.59000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 10 MT = 91 Q = -1.58250E+00 MeV Emin = 1.59969E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 11 MT = 102 Q = 6.50000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 390920 : (n,gamma) + 12 MT = 104 Q = -5.47720E+00 MeV Emin = 5.53797E+00 MeV frac = 1.00000E+00 Product nuclide = 38090.82c : (n,d) + 13 MT = 105 Q = -7.02210E+00 MeV Emin = 7.10001E+00 MeV frac = 1.00000E+00 Product nuclide = 38089.82c : (n,t) + 14 MT = 106 Q = -1.14880E+01 MeV Emin = 1.16155E+01 MeV frac = 1.00000E+00 Product nuclide = 370890 : (n,He-3) + 15 MT = 107 Q = 1.89840E+00 MeV Emin = 4.75000E-02 MeV frac = 1.00000E+00 Product nuclide = 370880 : (n,alpha) + 16 MT = 111 Q = -1.32810E+01 MeV Emin = 1.34284E+01 MeV frac = 1.00000E+00 Product nuclide = 370900 : (n,2p) + + 5 additional transport branches: + + 1 MT = 104 Q = -5.47720E+00 MeV Emin = 5.53797E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 2 MT = 105 Q = -7.02210E+00 MeV Emin = 7.10001E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 3 MT = 106 Q = -1.14880E+01 MeV Emin = 1.16155E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 4 MT = 107 Q = 1.89840E+00 MeV Emin = 4.75000E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 5 MT = 111 Q = -1.32810E+01 MeV Emin = 1.34284E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.34284E+01 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.53797E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 7.10001E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.16155E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.75000E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 5.50000E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.54480E+00 MeV frac = 1.00000E+00 Product nuclide = 40091.82c : beta- + + Nuclide 95 / 1657 : 40090.82c -- zirconium 90 (Zr-90) + + Pointers : 710624 36807 + Primary type : Transport + Nuclide ZAI : 400900 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Zr90.ACE + Atomic weight (AW) : 89.90473 + Atomic weight ratio (AWR) : 89.13240 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 20 reaction channels + - 7 special reactions + - 11 transmutation reactions + - 9 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 20 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.19812E+01 MeV Emin = 1.21156E+01 MeV frac = 1.00000E+00 Product nuclide = 400890 : (n,2n) + 3 MT = 22 Q = -6.67438E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 38086.82c : (n,nalpha) + 4 MT = 28 Q = -8.36293E+00 MeV Emin = 8.45677E+00 MeV frac = 1.00000E+00 Product nuclide = 39089.82c : (n,np) + 5 MT = 32 Q = -1.76099E+01 MeV Emin = 1.80000E+01 MeV frac = 1.00000E+00 Product nuclide = 390880 : (n,nd) + 6 MT = 51 Q = -1.76070E+00 MeV Emin = 1.77649E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -2.18650E+00 MeV Emin = 2.21103E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -2.31910E+00 MeV Emin = 2.34512E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -2.73880E+00 MeV Emin = 2.76953E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -2.74790E+00 MeV Emin = 2.77873E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -3.07720E+00 MeV Emin = 3.11172E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -3.30870E+00 MeV Emin = 3.34582E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 91 Q = -3.30900E+00 MeV Emin = 3.34613E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 14 MT = 102 Q = 7.19929E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 40091.82c : (n,gamma) + 15 MT = 103 Q = -1.50143E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 39090.82c : (n,p) + 16 MT = 104 Q = -6.05281E+00 MeV Emin = 6.74928E+00 MeV frac = 1.00000E+00 Product nuclide = 39089.82c : (n,d) + 17 MT = 105 Q = -1.13411E+01 MeV Emin = 1.21156E+01 MeV frac = 1.00000E+00 Product nuclide = 390880 : (n,t) + 18 MT = 106 Q = -7.70983E+00 MeV Emin = 9.17457E+00 MeV frac = 1.00000E+00 Product nuclide = 38088.82c : (n,He-3) + 19 MT = 107 Q = 1.75851E+00 MeV Emin = 6.75000E-01 MeV frac = 1.00000E+00 Product nuclide = 38087.82c : (n,alpha) + 20 MT = 111 Q = -9.07277E+00 MeV Emin = 1.14683E+01 MeV frac = 1.00000E+00 Product nuclide = 38089.82c : (n,2p) + + 9 additional transport branches: + + 1 MT = 22 Q = -6.67438E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -8.36293E+00 MeV Emin = 8.45677E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82s : (n,np) + 3 MT = 32 Q = -1.76099E+01 MeV Emin = 1.80000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 103 Q = -1.50143E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82s : (n,p) + 5 MT = 104 Q = -6.05281E+00 MeV Emin = 6.74928E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -1.13411E+01 MeV Emin = 1.21156E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 106 Q = -7.70983E+00 MeV Emin = 9.17457E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 8 MT = 107 Q = 1.75851E+00 MeV Emin = 6.75000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 9 MT = 111 Q = -9.07277E+00 MeV Emin = 1.14683E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82s : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.74928E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.21156E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 9.17457E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 6.75000E-01 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 1.77649E+00 MeV : total inelastic scattering + + Nuclide 96 / 1657 : 40091.82c -- zirconium 91 (Zr-91) + + Pointers : 713902 36853 + Primary type : Transport + Nuclide ZAI : 400910 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Zr91.ACE + Atomic weight (AW) : 90.90563 + Atomic weight ratio (AWR) : 90.12470 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 27 reaction channels + - 7 special reactions + - 11 transmutation reactions + - 8 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 27 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.20258E+00 MeV Emin = 7.28251E+00 MeV frac = 1.00000E+00 Product nuclide = 40090.82c : (n,2n) + 3 MT = 17 Q = -1.91859E+01 MeV Emin = 1.93988E+01 MeV frac = 1.00000E+00 Product nuclide = 400890 : (n,3n) + 4 MT = 22 Q = -5.45233E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 38087.82c : (n,nalpha) + 5 MT = 28 Q = -8.70881E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 39090.82c : (n,np) + 6 MT = 32 Q = -1.33442E+01 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 39089.82c : (n,nd) + 7 MT = 51 Q = -1.20480E+00 MeV Emin = 1.16363E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 8 MT = 52 Q = -1.46630E+00 MeV Emin = 1.44037E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 9 MT = 53 Q = -1.88210E+00 MeV Emin = 1.88514E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 10 MT = 54 Q = -2.04220E+00 MeV Emin = 2.06486E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 11 MT = 55 Q = -2.13130E+00 MeV Emin = 2.15495E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 12 MT = 56 Q = -2.17000E+00 MeV Emin = 2.19408E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 13 MT = 57 Q = -2.18990E+00 MeV Emin = 2.21420E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 14 MT = 58 Q = -2.20070E+00 MeV Emin = 2.22512E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 15 MT = 59 Q = -2.25970E+00 MeV Emin = 2.28477E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 16 MT = 60 Q = -2.28760E+00 MeV Emin = 2.31298E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 17 MT = 61 Q = -2.32010E+00 MeV Emin = 2.34584E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 18 MT = 62 Q = -2.35580E+00 MeV Emin = 2.38194E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 19 MT = 63 Q = -2.36690E+00 MeV Emin = 2.39316E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 20 MT = 64 Q = -2.39490E+00 MeV Emin = 2.42147E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 21 MT = 91 Q = -2.39500E+00 MeV Emin = 2.42157E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 22 MT = 102 Q = 8.63480E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 40092.82c : (n,gamma) + 23 MT = 103 Q = -7.60531E-01 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 39091.82c : (n,p) + 24 MT = 104 Q = -6.48420E+00 MeV Emin = 6.55616E+00 MeV frac = 1.00000E+00 Product nuclide = 39090.82c : (n,d) + 25 MT = 105 Q = -7.08660E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 39089.82c : (n,t) + 26 MT = 106 Q = -8.55750E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 38089.82c : (n,He-3) + 27 MT = 107 Q = 5.67229E+00 MeV Emin = 9.49999E-02 MeV frac = 1.00000E+00 Product nuclide = 38088.82c : (n,alpha) + + 8 additional transport branches: + + 1 MT = 22 Q = -5.45233E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -8.70881E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82s : (n,np) + 3 MT = 32 Q = -1.33442E+01 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 103 Q = -7.60531E-01 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82s : (n,p) + 5 MT = 104 Q = -6.48420E+00 MeV Emin = 6.55616E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -7.08660E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 106 Q = -8.55750E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 8 MT = 107 Q = 5.67229E+00 MeV Emin = 9.49999E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.55616E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 8.00000E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.00000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 9.49999E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 8.53457E-04 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 1.16363E+00 MeV : total inelastic scattering + + Nuclide 97 / 1657 : 40092.82c -- zirconium 92 (Zr-92) + + Pointers : 717079 36899 + Primary type : Transport + Nuclide ZAI : 400920 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Zr92.ACE + Atomic weight (AW) : 91.90501 + Atomic weight ratio (AWR) : 91.11550 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 30 reaction channels + - 6 special reactions + - 11 transmutation reactions + - 8 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 30 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.63508E+00 MeV Emin = 8.72986E+00 MeV frac = 1.00000E+00 Product nuclide = 40091.82c : (n,2n) + 3 MT = 17 Q = -1.58377E+01 MeV Emin = 1.60115E+01 MeV frac = 1.00000E+00 Product nuclide = 40090.82c : (n,3n) + 4 MT = 22 Q = -2.96741E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 38088.82c : (n,nalpha) + 5 MT = 28 Q = -9.40023E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 39091.82c : (n,np) + 6 MT = 32 Q = -1.50350E+01 MeV Emin = 1.58838E+01 MeV frac = 1.00000E+00 Product nuclide = 39090.82c : (n,nd) + 7 MT = 33 Q = -1.57114E+01 MeV Emin = 1.60176E+01 MeV frac = 1.00000E+00 Product nuclide = 39089.82c : (n,nt) + 8 MT = 51 Q = -9.34499E-01 MeV Emin = 9.41128E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -1.38280E+00 MeV Emin = 1.39702E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -1.49540E+00 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -1.84730E+00 MeV Emin = 1.86708E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -2.06670E+00 MeV Emin = 2.08938E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -2.15000E+00 MeV Emin = 2.17360E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -2.33970E+00 MeV Emin = 2.36538E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -2.39830E+00 MeV Emin = 2.42462E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -2.48590E+00 MeV Emin = 2.51318E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -2.74350E+00 MeV Emin = 2.77361E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -2.81970E+00 MeV Emin = 2.85065E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 62 Q = -2.86400E+00 MeV Emin = 2.89543E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 20 MT = 63 Q = -2.90360E+00 MeV Emin = 2.93547E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 21 MT = 64 Q = -2.90950E+00 MeV Emin = 2.94143E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 22 MT = 65 Q = -2.95780E+00 MeV Emin = 2.99026E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 23 MT = 66 Q = -3.03970E+00 MeV Emin = 3.07306E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 24 MT = 67 Q = -3.05780E+00 MeV Emin = 3.09136E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 25 MT = 91 Q = -3.05800E+00 MeV Emin = 3.09156E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 26 MT = 102 Q = 6.73199E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 40093.82c : (n,gamma) + 27 MT = 103 Q = -2.85164E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 390920 : (n,p) + 28 MT = 104 Q = -7.09011E+00 MeV Emin = 7.16794E+00 MeV frac = 1.00000E+00 Product nuclide = 39091.82c : (n,d) + 29 MT = 105 Q = -8.84985E+00 MeV Emin = 9.50341E+00 MeV frac = 1.00000E+00 Product nuclide = 39090.82c : (n,t) + 30 MT = 107 Q = 3.40109E+00 MeV Emin = 1.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 38089.82c : (n,alpha) + + 8 additional transport branches: + + 1 MT = 22 Q = -2.96741E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -9.40023E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82s : (n,np) + 3 MT = 32 Q = -1.50350E+01 MeV Emin = 1.58838E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.57114E+01 MeV Emin = 1.60176E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 103 Q = -2.85164E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82s : (n,p) + 6 MT = 104 Q = -7.09011E+00 MeV Emin = 7.16794E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 7 MT = 105 Q = -8.84985E+00 MeV Emin = 9.50341E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 8 MT = 107 Q = 3.40109E+00 MeV Emin = 1.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.16794E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.50341E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-01 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 9.41128E-01 MeV : total inelastic scattering + + Nuclide 98 / 1657 : 40093.82c -- zirconium 93 (Zr-93) + + Pointers : 720402 36945 + Primary type : Transport + Nuclide ZAI : 400930 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Zr93.ACE + Atomic weight (AW) : 92.90652 + Atomic weight ratio (AWR) : 92.10840 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 5.08E+13 seconds (1.61 million years) + Specific ingestion toxicity : 1.10E-09 Sv/Bq + Specific inhalation toxicity : 3.30E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 23 reaction channels + - 6 special reactions + - 11 transmutation reactions + - 8 transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 23 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.73669E+00 MeV Emin = 6.80984E+00 MeV frac = 1.00000E+00 Product nuclide = 40092.82c : (n,2n) + 3 MT = 17 Q = -1.53764E+01 MeV Emin = 1.55434E+01 MeV frac = 1.00000E+00 Product nuclide = 40091.82c : (n,3n) + 4 MT = 22 Q = -3.33560E+00 MeV Emin = 3.37181E+00 MeV frac = 1.00000E+00 Product nuclide = 38089.82c : (n,nalpha) + 5 MT = 28 Q = -9.58833E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 390920 : (n,np) + 6 MT = 32 Q = -1.38268E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 39091.82c : (n,nd) + 7 MT = 33 Q = -1.55866E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 39090.82c : (n,nt) + 8 MT = 51 Q = -2.67100E-01 MeV Emin = 2.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -9.48999E-01 MeV Emin = 9.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -1.42310E+00 MeV Emin = 1.36784E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -1.48000E+00 MeV Emin = 1.48169E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -1.60000E+00 MeV Emin = 1.58803E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -1.65000E+00 MeV Emin = 1.65528E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -1.92000E+00 MeV Emin = 1.89314E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -2.04000E+00 MeV Emin = 2.06215E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -2.08000E+00 MeV Emin = 2.10258E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -2.10000E+00 MeV Emin = 2.12280E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 91 Q = -2.18000E+00 MeV Emin = 2.20367E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 19 MT = 102 Q = 8.22112E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 40094.82c : (n,gamma) + 20 MT = 103 Q = -2.10723E+00 MeV Emin = 2.13011E+00 MeV frac = 1.00000E+00 Product nuclide = 390930 : (n,p) + 21 MT = 104 Q = -7.27821E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 390920 : (n,d) + 22 MT = 105 Q = -7.64165E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 39091.82c : (n,t) + 23 MT = 107 Q = 4.47221E+00 MeV Emin = 9.49999E-02 MeV frac = 1.00000E+00 Product nuclide = 38090.82c : (n,alpha) + + 8 additional transport branches: + + 1 MT = 22 Q = -3.33560E+00 MeV Emin = 3.37181E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -9.58833E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.38268E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.55866E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 103 Q = -2.10723E+00 MeV Emin = 2.13011E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 104 Q = -7.27821E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 7 MT = 105 Q = -7.64165E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 8 MT = 107 Q = 4.47221E+00 MeV Emin = 9.49999E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.13011E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 8.00000E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 9.49999E-02 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 8.54206E-04 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 2.50000E-01 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 1 Q = 9.03000E-02 MeV frac = 2.70000E-01 Product nuclide = 41093.82c : beta- + 2 RTYP = 1 Q = 5.95300E-02 MeV frac = 7.30000E-01 Product nuclide = 410931 : beta- + + Nuclide 99 / 1657 : 40094.82c -- zirconium 94 (Zr-94) + + Pointers : 723407 36991 + Primary type : Transport + Nuclide ZAI : 400940 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Zr94.ACE + Atomic weight (AW) : 93.90631 + Atomic weight ratio (AWR) : 93.09960 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 3.47E+24 seconds (1.1E+17 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 26 reaction channels + - 6 special reactions + - 10 transmutation reactions + - 7 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 26 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.19108E+00 MeV Emin = 8.27907E+00 MeV frac = 1.00000E+00 Product nuclide = 40093.82c : (n,2n) + 3 MT = 17 Q = -1.49496E+01 MeV Emin = 1.51102E+01 MeV frac = 1.00000E+00 Product nuclide = 40092.82c : (n,3n) + 4 MT = 22 Q = -3.75108E+00 MeV Emin = 4.14346E+00 MeV frac = 1.00000E+00 Product nuclide = 38090.82c : (n,nalpha) + 5 MT = 28 Q = -1.03305E+01 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 390930 : (n,np) + 6 MT = 32 Q = -1.55015E+01 MeV Emin = 1.60354E+01 MeV frac = 1.00000E+00 Product nuclide = 390920 : (n,nd) + 7 MT = 51 Q = -9.18699E-01 MeV Emin = 9.28063E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 8 MT = 52 Q = -1.30020E+00 MeV Emin = 1.31250E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 9 MT = 53 Q = -1.46960E+00 MeV Emin = 1.48407E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 10 MT = 54 Q = -1.67140E+00 MeV Emin = 1.68878E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 11 MT = 55 Q = -2.05760E+00 MeV Emin = 2.07970E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 12 MT = 56 Q = -2.15130E+00 MeV Emin = 2.17441E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 13 MT = 57 Q = -2.33020E+00 MeV Emin = 2.35523E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 14 MT = 58 Q = -2.36610E+00 MeV Emin = 2.39152E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 15 MT = 59 Q = -2.50770E+00 MeV Emin = 2.53464E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 16 MT = 60 Q = -2.60450E+00 MeV Emin = 2.63248E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 17 MT = 61 Q = -2.69850E+00 MeV Emin = 2.72749E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 18 MT = 62 Q = -2.82600E+00 MeV Emin = 2.85636E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 19 MT = 63 Q = -2.84630E+00 MeV Emin = 2.87687E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 20 MT = 64 Q = -2.86060E+00 MeV Emin = 2.89133E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 21 MT = 91 Q = -2.86100E+00 MeV Emin = 2.89173E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 22 MT = 102 Q = 6.47089E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 40095.82c : (n,gamma) + 23 MT = 103 Q = -4.09942E+00 MeV Emin = 4.14346E+00 MeV frac = 1.00000E+00 Product nuclide = 390940 : (n,p) + 24 MT = 104 Q = -8.02041E+00 MeV Emin = 8.31164E+00 MeV frac = 1.00000E+00 Product nuclide = 390930 : (n,d) + 25 MT = 105 Q = -9.31636E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 390920 : (n,t) + 26 MT = 107 Q = 2.05631E+00 MeV Emin = 1.71000E-01 MeV frac = 1.00000E+00 Product nuclide = 380910 : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -3.75108E+00 MeV Emin = 4.14346E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.03305E+01 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82s : (n,np) + 3 MT = 32 Q = -1.55015E+01 MeV Emin = 1.60354E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 103 Q = -4.09942E+00 MeV Emin = 4.14346E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82s : (n,p) + 5 MT = 104 Q = -8.02041E+00 MeV Emin = 8.31164E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -9.31636E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 107 Q = 2.05631E+00 MeV Emin = 1.71000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.14346E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.31164E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.00000E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 1.71000E-01 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 9.28063E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 11 Q = 1.14190E+00 MeV frac = 1.00000E+00 Product nuclide = 42094.82c : beta- + beta- + + Nuclide 100 / 1657 : 40095.82c -- zirconium 95 (Zr-95) + + Pointers : 726438 37037 + Primary type : Transport + Nuclide ZAI : 400950 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Zr95.ACE + Atomic weight (AW) : 94.90801 + Atomic weight ratio (AWR) : 94.09270 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 5.53E+06 seconds (64 days) + Specific ingestion toxicity : 9.50E-10 Sv/Bq + Specific inhalation toxicity : 5.90E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 35 reaction channels + - 6 special reactions + - 10 transmutation reactions + - 7 transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 35 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.47560E+00 MeV Emin = 6.54443E+00 MeV frac = 1.00000E+00 Product nuclide = 40094.82c : (n,2n) + 3 MT = 17 Q = -1.46989E+01 MeV Emin = 1.48551E+01 MeV frac = 1.00000E+00 Product nuclide = 40093.82c : (n,3n) + 4 MT = 22 Q = -4.41929E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 380910 : (n,nalpha) + 5 MT = 28 Q = -1.05750E+01 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 390940 : (n,np) + 6 MT = 32 Q = -1.44960E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 390930 : (n,nd) + 7 MT = 51 Q = -9.52999E-01 MeV Emin = 9.54260E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 8 MT = 52 Q = -1.17300E+00 MeV Emin = 1.18390E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 9 MT = 53 Q = -1.31900E+00 MeV Emin = 1.31227E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 10 MT = 54 Q = -1.61800E+00 MeV Emin = 1.56760E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 11 MT = 55 Q = -1.61826E+00 MeV Emin = 1.56760E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 12 MT = 56 Q = -1.71800E+00 MeV Emin = 1.71106E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 13 MT = 57 Q = -1.78900E+00 MeV Emin = 1.79351E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 14 MT = 58 Q = -1.89600E+00 MeV Emin = 1.88912E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 15 MT = 59 Q = -1.94000E+00 MeV Emin = 1.95909E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 16 MT = 60 Q = -2.01800E+00 MeV Emin = 2.03945E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 17 MT = 61 Q = -2.25200E+00 MeV Emin = 2.27594E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 18 MT = 62 Q = -2.28000E+00 MeV Emin = 2.30423E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 19 MT = 63 Q = -2.29100E+00 MeV Emin = 2.31535E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 20 MT = 64 Q = -2.37600E+00 MeV Emin = 2.40125E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 21 MT = 65 Q = -2.45000E+00 MeV Emin = 2.47604E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 22 MT = 66 Q = -2.62500E+00 MeV Emin = 2.65290E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 23 MT = 67 Q = -2.62550E+00 MeV Emin = 2.65340E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 24 MT = 68 Q = -2.72400E+00 MeV Emin = 2.75295E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 25 MT = 69 Q = -2.83400E+00 MeV Emin = 2.86412E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 26 MT = 70 Q = -2.83500E+00 MeV Emin = 2.86513E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 27 MT = 71 Q = -2.99600E+00 MeV Emin = 3.02784E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 28 MT = 72 Q = -3.06200E+00 MeV Emin = 3.09454E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 29 MT = 73 Q = -3.11700E+00 MeV Emin = 3.15013E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 30 MT = 91 Q = -3.20500E+00 MeV Emin = 3.23906E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 31 MT = 102 Q = 7.85635E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 40096.82c : (n,gamma) + 32 MT = 103 Q = -3.64793E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 390950 : (n,p) + 33 MT = 104 Q = -8.26491E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 390940 : (n,d) + 34 MT = 105 Q = -8.31086E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 390930 : (n,t) + 35 MT = 107 Q = 2.88281E+00 MeV Emin = 1.01563E-01 MeV frac = 1.00000E+00 Product nuclide = 380920 : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -4.41929E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.05750E+01 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.44960E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 103 Q = -3.64793E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -8.26491E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -8.31086E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 107 Q = 2.88281E+00 MeV Emin = 1.01563E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 9.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.00000E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 1.01563E-01 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 9.00000E-04 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 9.54260E-01 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.12480E+00 MeV frac = 9.89196E-01 Product nuclide = 41095.82c : beta- + 2 RTYP = 1 Q = 8.89110E-01 MeV frac = 1.08035E-02 Product nuclide = 410951 : beta- + + Nuclide 101 / 1657 : 40096.82c -- zirconium 96 (Zr-96) + + Pointers : 730456 37083 + Primary type : Transport + Nuclide ZAI : 400960 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Zr96.ACE + Atomic weight (AW) : 95.90830 + Atomic weight ratio (AWR) : 95.08440 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 6.31E+26 seconds (2E+19 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 18 reaction channels + - 6 special reactions + - 9 transmutation reactions + - 6 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 18 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.83168E+00 MeV Emin = 7.91406E+00 MeV frac = 1.00000E+00 Product nuclide = 40095.82c : (n,2n) + 3 MT = 17 Q = -1.43063E+01 MeV Emin = 1.44568E+01 MeV frac = 1.00000E+00 Product nuclide = 40094.82c : (n,3n) + 4 MT = 22 Q = -4.97458E+00 MeV Emin = 5.02691E+00 MeV frac = 1.00000E+00 Product nuclide = 380920 : (n,nalpha) + 5 MT = 28 Q = -1.15053E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 390950 : (n,np) + 6 MT = 51 Q = -1.59400E+00 MeV Emin = 1.60314E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.75050E+00 MeV Emin = 1.75000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -1.89710E+00 MeV Emin = 1.91003E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -2.22590E+00 MeV Emin = 2.24931E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -2.33000E+00 MeV Emin = 2.35451E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -2.44000E+00 MeV Emin = 2.46566E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -2.85740E+00 MeV Emin = 2.88745E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 91 Q = -2.85700E+00 MeV Emin = 2.88705E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 14 MT = 102 Q = 5.57518E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 400970 : (n,gamma) + 15 MT = 103 Q = -6.23222E+00 MeV Emin = 6.29777E+00 MeV frac = 1.00000E+00 Product nuclide = 390960 : (n,p) + 16 MT = 104 Q = -9.19521E+00 MeV Emin = 1.00417E+01 MeV frac = 1.00000E+00 Product nuclide = 390950 : (n,d) + 17 MT = 105 Q = -9.93715E+00 MeV Emin = 1.00417E+01 MeV frac = 1.00000E+00 Product nuclide = 390940 : (n,t) + 18 MT = 107 Q = 2.90000E-01 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 380930 : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = -4.97458E+00 MeV Emin = 5.02691E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.15053E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82s : (n,np) + 3 MT = 103 Q = -6.23222E+00 MeV Emin = 6.29777E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82s : (n,p) + 4 MT = 104 Q = -9.19521E+00 MeV Emin = 1.00417E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -9.93715E+00 MeV Emin = 1.00417E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 107 Q = 2.90000E-01 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 6.29777E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.00417E+01 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.00417E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 9.35566E-04 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 1.60314E+00 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 11 Q = 3.34900E+00 MeV frac = 1.00000E+00 Product nuclide = 42096.82c : beta- + beta- + + Nuclide 102 / 1657 : 41093.82c -- niobium 93 (Nb-93) + + Pointers : 759781 28343 + Primary type : Transport + Nuclide ZAI : 410930 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Nb93.ACE + Atomic weight (AW) : 92.90319 + Atomic weight ratio (AWR) : 92.10510 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 1.50000E+02 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 37 reaction channels + - 6 special reactions + - 11 transmutation reactions + - 9 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 37 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 5 Q = 0.00000E+00 MeV Emin = 2.00000E+01 MeV frac = 1.00000E+00 Product nuclide = self : anything + 3 MT = 16 Q = -8.83300E+00 MeV Emin = 8.92900E+00 MeV frac = 1.00000E+00 Product nuclide = 410920 : (n,2n) + 4 MT = 17 Q = -1.67150E+01 MeV Emin = 1.69000E+01 MeV frac = 1.00000E+00 Product nuclide = 410910 : (n,3n) + 5 MT = 22 Q = -1.93800E+00 MeV Emin = 1.95000E+00 MeV frac = 1.00000E+00 Product nuclide = 39089.82c : (n,nalpha) + 6 MT = 28 Q = -6.04200E+00 MeV Emin = 6.10760E+00 MeV frac = 1.00000E+00 Product nuclide = 40092.82c : (n,np) + 7 MT = 32 Q = -1.24600E+01 MeV Emin = 1.25953E+01 MeV frac = 1.00000E+00 Product nuclide = 40091.82c : (n,nd) + 8 MT = 33 Q = -1.33400E+01 MeV Emin = 1.34848E+01 MeV frac = 1.00000E+00 Product nuclide = 40090.82c : (n,nt) + 9 MT = 51 Q = -3.07300E-02 MeV Emin = 3.10000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 10 MT = 52 Q = -6.79900E-01 MeV Emin = 6.80000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 11 MT = 53 Q = -7.44000E-01 MeV Emin = 7.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 12 MT = 54 Q = -8.01000E-01 MeV Emin = 8.08000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 13 MT = 55 Q = -8.08000E-01 MeV Emin = 8.13350E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 14 MT = 56 Q = -9.49900E-01 MeV Emin = 9.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 15 MT = 57 Q = -9.79000E-01 MeV Emin = 9.84750E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 16 MT = 58 Q = -1.08000E+00 MeV Emin = 1.08000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 17 MT = 59 Q = -1.30000E+00 MeV Emin = 1.30000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 18 MT = 60 Q = -1.32000E+00 MeV Emin = 1.33400E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 19 MT = 61 Q = -1.33000E+00 MeV Emin = 1.34400E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 20 MT = 62 Q = -1.37000E+00 MeV Emin = 1.37000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 21 MT = 63 Q = -1.39000E+00 MeV Emin = 1.40000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 22 MT = 64 Q = -1.48000E+00 MeV Emin = 1.49000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 23 MT = 65 Q = -1.48400E+00 MeV Emin = 1.49804E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 24 MT = 66 Q = -1.50000E+00 MeV Emin = 1.51600E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 25 MT = 67 Q = -1.60000E+00 MeV Emin = 1.61700E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 26 MT = 68 Q = -1.67000E+00 MeV Emin = 1.68000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 27 MT = 69 Q = -1.68000E+00 MeV Emin = 1.69400E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 28 MT = 70 Q = -1.68100E+00 MeV Emin = 1.69862E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 29 MT = 71 Q = -1.69000E+00 MeV Emin = 1.70800E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 30 MT = 72 Q = -1.95000E+00 MeV Emin = 1.96000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 31 MT = 73 Q = -2.15500E+00 MeV Emin = 2.17840E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 32 MT = 91 Q = -2.17700E+00 MeV Emin = 2.20064E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 33 MT = 102 Q = 7.21400E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 41094.82c : (n,gamma) + 34 MT = 103 Q = 6.93000E-01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 40093.82c : (n,p) + 35 MT = 104 Q = -3.81700E+00 MeV Emin = 3.85900E+00 MeV frac = 1.00000E+00 Product nuclide = 40092.82c : (n,d) + 36 MT = 105 Q = -6.19500E+00 MeV Emin = 6.26300E+00 MeV frac = 1.00000E+00 Product nuclide = 40091.82c : (n,t) + 37 MT = 107 Q = 4.91800E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 39090.82c : (n,alpha) + + 9 additional transport branches: + + 1 MT = 22 Q = -1.93800E+00 MeV Emin = 1.95000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -6.04200E+00 MeV Emin = 6.10760E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.24600E+01 MeV Emin = 1.25953E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.33400E+01 MeV Emin = 1.34848E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 102 Q = 7.21400E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 410941 : (n,gamma) + 6 MT = 103 Q = 6.93000E-01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 7 MT = 104 Q = -3.81700E+00 MeV Emin = 3.85900E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 8 MT = 105 Q = -6.19500E+00 MeV Emin = 6.26300E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 9 MT = 107 Q = 4.91800E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 3.85900E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 6.26300E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 3.10000E-02 MeV : total inelastic scattering + + Nuclide 103 / 1657 : 41094.82c -- niobium 94 (Nb-94) + + Pointers : 764106 28389 + Primary type : Transport + Nuclide ZAI : 410940 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Nb94.ACE + Atomic weight (AW) : 93.90731 + Atomic weight ratio (AWR) : 93.10060 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 6.31E+11 seconds (19,1000 years) + Specific ingestion toxicity : 1.70E-09 Sv/Bq + Specific inhalation toxicity : 4.90E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 43 reaction channels + - 7 special reactions + - 12 transmutation reactions + - 10 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 43 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.23420E+00 MeV Emin = 7.31191E+00 MeV frac = 1.00000E+00 Product nuclide = 41093.82c : (n,2n) + 3 MT = 17 Q = -1.60712E+01 MeV Emin = 1.62438E+01 MeV frac = 1.00000E+00 Product nuclide = 410920 : (n,3n) + 4 MT = 22 Q = -2.30829E+00 MeV Emin = 2.33309E+00 MeV frac = 1.00000E+00 Product nuclide = 39090.82c : (n,nalpha) + 5 MT = 28 Q = -6.54404E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 40093.82c : (n,np) + 6 MT = 32 Q = -1.09706E+01 MeV Emin = 1.10885E+01 MeV frac = 1.00000E+00 Product nuclide = 40092.82c : (n,nd) + 7 MT = 33 Q = -1.34252E+01 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 40091.82c : (n,nt) + 8 MT = 51 Q = -4.09999E-02 MeV Emin = 4.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -5.86999E-02 MeV Emin = 5.87500E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -7.86999E-02 MeV Emin = 7.75000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -1.13400E-01 MeV Emin = 1.10964E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -1.40300E-01 MeV Emin = 1.38408E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -3.01600E-01 MeV Emin = 3.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -3.11900E-01 MeV Emin = 3.11346E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -3.34200E-01 MeV Emin = 3.32859E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -3.96299E-01 MeV Emin = 3.93201E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -4.50199E-01 MeV Emin = 4.42267E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -6.31699E-01 MeV Emin = 6.21174E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 62 Q = -6.40899E-01 MeV Emin = 6.43135E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 20 MT = 63 Q = -6.65699E-01 MeV Emin = 6.72458E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 21 MT = 64 Q = -7.84899E-01 MeV Emin = 7.69998E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 22 MT = 65 Q = -7.92899E-01 MeV Emin = 8.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 23 MT = 66 Q = -8.17799E-01 MeV Emin = 8.14001E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 24 MT = 67 Q = -8.95699E-01 MeV Emin = 9.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 25 MT = 68 Q = -9.23999E-01 MeV Emin = 9.23199E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 26 MT = 69 Q = -9.35199E-01 MeV Emin = 9.39585E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 27 MT = 70 Q = -9.58599E-01 MeV Emin = 9.51158E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 28 MT = 71 Q = -9.78999E-01 MeV Emin = 9.79206E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 29 MT = 72 Q = -1.00770E+00 MeV Emin = 1.00926E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 30 MT = 73 Q = -1.06120E+00 MeV Emin = 1.05908E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 31 MT = 74 Q = -1.08570E+00 MeV Emin = 1.08807E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 32 MT = 75 Q = -1.16330E+00 MeV Emin = 1.15619E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 33 MT = 76 Q = -1.17070E+00 MeV Emin = 1.17954E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 34 MT = 77 Q = -1.20200E+00 MeV Emin = 1.20304E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 27. excited state + 35 MT = 78 Q = -1.23270E+00 MeV Emin = 1.23430E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 28. excited state + 36 MT = 79 Q = -1.25690E+00 MeV Emin = 1.26020E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 29. excited state + 37 MT = 91 Q = -1.26390E+00 MeV Emin = 1.27394E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 38 MT = 102 Q = 8.49079E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 41095.82c : (n,gamma) + 39 MT = 103 Q = 1.67926E+00 MeV Emin = 9.76563E-02 MeV frac = 1.00000E+00 Product nuclide = 40094.82c : (n,p) + 40 MT = 104 Q = -4.23392E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 40093.82c : (n,d) + 41 MT = 105 Q = -4.78546E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 40092.82c : (n,t) + 42 MT = 106 Q = -8.40093E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 390920 : (n,He-3) + 43 MT = 107 Q = 5.63660E+00 MeV Emin = 9.76563E-02 MeV frac = 1.00000E+00 Product nuclide = 39091.82c : (n,alpha) + + 10 additional transport branches: + + 1 MT = 22 Q = -2.30829E+00 MeV Emin = 2.33309E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -6.54404E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.09706E+01 MeV Emin = 1.10885E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.34252E+01 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 102 Q = 8.49079E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 410951 : (n,gamma) + 6 MT = 103 Q = 1.67926E+00 MeV Emin = 9.76563E-02 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 7 MT = 104 Q = -4.23392E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 8 MT = 105 Q = -4.78546E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 9 MT = 106 Q = -8.40093E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 10 MT = 107 Q = 5.63660E+00 MeV Emin = 9.76563E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 9.76563E-02 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 5.00000E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.00000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 9.76563E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 4.00000E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.04530E+00 MeV frac = 1.00000E+00 Product nuclide = 42094.82c : beta- + + Nuclide 104 / 1657 : 41095.82c -- niobium 95 (Nb-95) + + Pointers : 769656 28435 + Primary type : Transport + Nuclide ZAI : 410950 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Nb95.ACE + Atomic weight (AW) : 94.90680 + Atomic weight ratio (AWR) : 94.09150 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 3.02E+06 seconds (35 days) + Specific ingestion toxicity : 5.80E-10 Sv/Bq + Specific inhalation toxicity : 1.80E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 34 reaction channels + - 7 special reactions + - 12 transmutation reactions + - 9 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 34 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.49549E+00 MeV Emin = 8.58579E+00 MeV frac = 1.00000E+00 Product nuclide = 41094.82c : (n,2n) + 3 MT = 17 Q = -1.57297E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 41093.82c : (n,3n) + 4 MT = 22 Q = -2.85889E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 39091.82c : (n,nalpha) + 5 MT = 28 Q = -6.81623E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 40094.82c : (n,np) + 6 MT = 32 Q = -1.27294E+01 MeV Emin = 1.34221E+01 MeV frac = 1.00000E+00 Product nuclide = 40093.82c : (n,nd) + 7 MT = 33 Q = -1.32810E+01 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 40092.82c : (n,nt) + 8 MT = 51 Q = -2.35700E-01 MeV Emin = 2.19103E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -7.24199E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -7.27999E-01 MeV Emin = 7.34501E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -7.56699E-01 MeV Emin = 7.64444E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -7.98999E-01 MeV Emin = 8.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -1.00000E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -1.08800E+00 MeV Emin = 1.08567E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -1.22300E+00 MeV Emin = 1.21681E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -1.27400E+00 MeV Emin = 1.27581E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -1.41900E+00 MeV Emin = 1.43253E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -1.51400E+00 MeV Emin = 1.51504E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 62 Q = -1.59000E+00 MeV Emin = 1.60350E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 20 MT = 63 Q = -1.64500E+00 MeV Emin = 1.64858E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 21 MT = 64 Q = -1.69100E+00 MeV Emin = 1.69444E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 22 MT = 65 Q = -1.81000E+00 MeV Emin = 1.82549E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 23 MT = 66 Q = -1.91300E+00 MeV Emin = 1.90406E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 24 MT = 67 Q = -1.98000E+00 MeV Emin = 2.00104E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 25 MT = 68 Q = -2.07000E+00 MeV Emin = 2.09200E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 26 MT = 69 Q = -2.12100E+00 MeV Emin = 2.14354E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 27 MT = 70 Q = -2.16500E+00 MeV Emin = 2.18801E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 28 MT = 91 Q = -2.26000E+00 MeV Emin = 2.28402E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 29 MT = 102 Q = 6.89312E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 410960 : (n,gamma) + 30 MT = 103 Q = -3.40631E-01 MeV Emin = 1.27581E+00 MeV frac = 1.00000E+00 Product nuclide = 40095.82c : (n,p) + 31 MT = 104 Q = -4.50611E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 40094.82c : (n,d) + 32 MT = 105 Q = -6.54426E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 40093.82c : (n,t) + 33 MT = 106 Q = -9.41532E+00 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 390930 : (n,He-3) + 34 MT = 107 Q = 3.68970E+00 MeV Emin = 9.49999E-02 MeV frac = 1.00000E+00 Product nuclide = 390920 : (n,alpha) + + 9 additional transport branches: + + 1 MT = 22 Q = -2.85889E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -6.81623E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.27294E+01 MeV Emin = 1.34221E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.32810E+01 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 103 Q = -3.40631E-01 MeV Emin = 1.27581E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 104 Q = -4.50611E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 7 MT = 105 Q = -6.54426E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 8 MT = 106 Q = -9.41532E+00 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 9 MT = 107 Q = 3.68970E+00 MeV Emin = 9.49999E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.27581E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 7.00000E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.20000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 9.49999E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 9.00000E-04 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 2.19103E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.25600E-01 MeV frac = 1.00000E+00 Product nuclide = 42095.82c : beta- + + Nuclide 105 / 1657 : 42092.82c -- molybdenum 92 (Mo-92) + + Pointers : 804864 27837 + Primary type : Transport + Nuclide ZAI : 420920 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Mo92.ACE + Atomic weight (AW) : 91.90683 + Atomic weight ratio (AWR) : 91.11730 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 6.00E+27 seconds (1.9E+20 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 28 reaction channels + - 7 special reactions + - 10 transmutation reactions + - 9 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 28 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.26921E+01 MeV Emin = 1.28314E+01 MeV frac = 1.00000E+00 Product nuclide = 420910 : (n,2n) + 3 MT = 22 Q = -5.62333E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 400880 : (n,nalpha) + 4 MT = 28 Q = -7.46561E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 410910 : (n,np) + 5 MT = 51 Q = -1.50950E+00 MeV Emin = 1.52556E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -2.28260E+00 MeV Emin = 2.30765E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -2.51970E+00 MeV Emin = 2.54735E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -2.52710E+00 MeV Emin = 2.55484E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -2.61240E+00 MeV Emin = 2.64107E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -2.76040E+00 MeV Emin = 2.79070E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -2.84970E+00 MeV Emin = 2.88098E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -3.00700E+00 MeV Emin = 3.04000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -3.06410E+00 MeV Emin = 3.09773E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -3.09130E+00 MeV Emin = 3.12523E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -3.36910E+00 MeV Emin = 3.40608E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -3.54199E+00 MeV Emin = 3.58087E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 63 Q = -3.58029E+00 MeV Emin = 3.61959E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 18 MT = 64 Q = -3.62119E+00 MeV Emin = 3.66094E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 19 MT = 65 Q = -3.62479E+00 MeV Emin = 3.66458E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 20 MT = 66 Q = -3.68799E+00 MeV Emin = 3.72848E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 21 MT = 91 Q = -3.68799E+00 MeV Emin = 3.72848E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 22 MT = 102 Q = 8.06739E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 420930 : (n,gamma) + 23 MT = 103 Q = 4.23561E-01 MeV Emin = 1.03125E-01 MeV frac = 1.00000E+00 Product nuclide = 410920 : (n,p) + 24 MT = 104 Q = -5.15362E+00 MeV Emin = 5.66944E+00 MeV frac = 1.00000E+00 Product nuclide = 410910 : (n,d) + 25 MT = 105 Q = -1.10275E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 410900 : (n,t) + 26 MT = 106 Q = -4.89824E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 40090.82c : (n,He-3) + 27 MT = 107 Q = 3.70670E+00 MeV Emin = 8.00000E-02 MeV frac = 1.00000E+00 Product nuclide = 400890 : (n,alpha) + 28 MT = 111 Q = -5.42568E+00 MeV Emin = 7.54566E+00 MeV frac = 1.00000E+00 Product nuclide = 40091.82c : (n,2p) + + 9 additional transport branches: + + 1 MT = 22 Q = -5.62333E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -7.46561E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 102 Q = 8.06739E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 420931 : (n,gamma) + 4 MT = 103 Q = 4.23561E-01 MeV Emin = 1.03125E-01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -5.15362E+00 MeV Emin = 5.66944E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -1.10275E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 106 Q = -4.89824E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 8 MT = 107 Q = 3.70670E+00 MeV Emin = 8.00000E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 9 MT = 111 Q = -5.42568E+00 MeV Emin = 7.54566E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.03125E-01 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.66944E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.20000E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 6.00000E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 8.00000E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 1.52556E+00 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 22 Q = 1.64890E+00 MeV frac = 1.00000E+00 Product nuclide = 40092.82c : EC/beta+ + EC/beta+ + + Nuclide 106 / 1657 : 42094.82c -- molybdenum 94 (Mo-94) + + Pointers : 809545 27883 + Primary type : Transport + Nuclide ZAI : 420940 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Mo94.ACE + Atomic weight (AW) : 93.90510 + Atomic weight ratio (AWR) : 93.09840 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 32 reaction channels + - 7 special reactions + - 11 transmutation reactions + - 8 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 32 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -9.67258E+00 MeV Emin = 9.77649E+00 MeV frac = 1.00000E+00 Product nuclide = 420930 : (n,2n) + 3 MT = 17 Q = -1.77449E+01 MeV Emin = 1.79355E+01 MeV frac = 1.00000E+00 Product nuclide = 42092.82c : (n,3n) + 4 MT = 22 Q = -2.07224E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 40090.82c : (n,nalpha) + 5 MT = 28 Q = -8.49201E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 41093.82c : (n,np) + 6 MT = 51 Q = -8.71099E-01 MeV Emin = 8.75000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.57370E+00 MeV Emin = 1.57995E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -1.74250E+00 MeV Emin = 1.76071E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -1.86430E+00 MeV Emin = 1.88390E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -2.06740E+00 MeV Emin = 2.08961E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -2.29520E+00 MeV Emin = 2.31985E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -2.39320E+00 MeV Emin = 2.41891E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -2.42350E+00 MeV Emin = 2.44953E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -2.53390E+00 MeV Emin = 2.56112E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -2.56680E+00 MeV Emin = 2.59437E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -2.61150E+00 MeV Emin = 2.63955E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -2.73980E+00 MeV Emin = 2.76923E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -2.76810E+00 MeV Emin = 2.79783E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -2.80580E+00 MeV Emin = 2.83594E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -2.83590E+00 MeV Emin = 2.86636E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 21 MT = 66 Q = -2.87020E+00 MeV Emin = 2.90103E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 22 MT = 67 Q = -2.87240E+00 MeV Emin = 2.90325E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 23 MT = 68 Q = -2.95580E+00 MeV Emin = 2.98755E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 24 MT = 69 Q = -2.96510E+00 MeV Emin = 2.99695E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 25 MT = 91 Q = -2.96500E+00 MeV Emin = 2.99685E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 26 MT = 102 Q = 7.37119E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 42095.82c : (n,gamma) + 27 MT = 103 Q = -1.26274E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 41094.82c : (n,p) + 28 MT = 104 Q = -6.18682E+00 MeV Emin = 6.88521E+00 MeV frac = 1.00000E+00 Product nuclide = 41093.82c : (n,d) + 29 MT = 105 Q = -8.83866E+00 MeV Emin = 9.78944E+00 MeV frac = 1.00000E+00 Product nuclide = 410920 : (n,t) + 30 MT = 106 Q = -6.81203E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 40092.82c : (n,He-3) + 31 MT = 107 Q = 5.13439E+00 MeV Emin = 9.49999E-02 MeV frac = 1.00000E+00 Product nuclide = 40091.82c : (n,alpha) + 32 MT = 111 Q = -7.80678E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 40093.82c : (n,2p) + + 8 additional transport branches: + + 1 MT = 22 Q = -2.07224E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -8.49201E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -1.26274E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -6.18682E+00 MeV Emin = 6.88521E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -8.83866E+00 MeV Emin = 9.78944E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 106 Q = -6.81203E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 7 MT = 107 Q = 5.13439E+00 MeV Emin = 9.49999E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 8 MT = 111 Q = -7.80678E+00 MeV Emin = 1.00000E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.88521E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.78944E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 9.00000E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 9.49999E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 8.75000E-01 MeV : total inelastic scattering + + Nuclide 107 / 1657 : 42095.82c -- molybdenum 95 (Mo-95) + + Pointers : 813087 27929 + Primary type : Transport + Nuclide ZAI : 420950 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Mo95.ACE + Atomic weight (AW) : 94.90589 + Atomic weight ratio (AWR) : 94.09060 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 14 reaction channels + - 14 special reactions + - 8 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 14 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.36900E+00 MeV Emin = 7.44732E+00 MeV frac = 1.00000E+00 Product nuclide = 42094.82c : (n,2n) + 3 MT = 17 Q = -1.70470E+01 MeV Emin = 1.72282E+01 MeV frac = 1.00000E+00 Product nuclide = 420930 : (n,3n) + 4 MT = 22 Q = -2.24200E+00 MeV Emin = 2.26583E+00 MeV frac = 1.00000E+00 Product nuclide = 40091.82c : (n,nalpha) + 5 MT = 28 Q = -8.63200E+00 MeV Emin = 8.72374E+00 MeV frac = 1.00000E+00 Product nuclide = 41094.82c : (n,np) + 6 MT = 51 Q = -2.04000E-01 MeV Emin = 2.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -7.66000E-01 MeV Emin = 7.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -7.86000E-01 MeV Emin = 7.87071E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -8.21000E-01 MeV Emin = 8.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 91 Q = -8.21000E-01 MeV Emin = 8.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 11 MT = 102 Q = 9.15433E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 42096.82c : (n,gamma) + 12 MT = 103 Q = 0.00000E+00 MeV Emin = 1.60000E-01 MeV frac = 1.00000E+00 Product nuclide = 41095.82c : (n,p) + 13 MT = 107 Q = 6.56751E+00 MeV Emin = 7.50000E-07 MeV frac = 1.00000E+00 Product nuclide = 40092.82c : (n,alpha) + 14 MT = 112 Q = -3.67000E+00 MeV Emin = 3.70901E+00 MeV frac = 1.00000E+00 Product nuclide = 39091.82c : (n,palpha) + + 6 additional transport branches: + + 1 MT = 22 Q = -2.24200E+00 MeV Emin = 2.26583E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -8.63200E+00 MeV Emin = 8.72374E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = 0.00000E+00 MeV Emin = 1.60000E-01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 107 Q = 6.56751E+00 MeV Emin = 7.50000E-07 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 5 MT = 112 Q = -3.67000E+00 MeV Emin = 3.70901E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,palpha) + 6 MT = 112 Q = -3.67000E+00 MeV Emin = 3.70901E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,palpha) + + 14 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.60000E-01 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 7.50000E-07 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 9.90999E-04 MeV : damage-energy production + 4 MT = 600 Q = -1.44000E-01 MeV Emin = 1.60000E-01 MeV : (n,p) to ground state + 5 MT = 601 Q = -3.80000E-01 MeV Emin = 3.50000E-01 MeV : (n,p1) + 6 MT = 649 Q = -3.80000E-01 MeV Emin = 3.50000E-01 MeV : (n,p) to continuum + 7 MT = 800 Q = 6.39300E+00 MeV Emin = 9.91599E-04 MeV : (n,alpha) to ground state + 8 MT = 801 Q = 5.45900E+00 MeV Emin = 9.91599E-04 MeV : (n,a1) + 9 MT = 802 Q = 5.01000E+00 MeV Emin = 9.92199E-04 MeV : (n,a2) + 10 MT = 803 Q = 4.89800E+00 MeV Emin = 9.91599E-04 MeV : (n,a3) + 11 MT = 804 Q = 4.54600E+00 MeV Emin = 9.92199E-04 MeV : (n,a4) + 12 MT = 805 Q = 4.32600E+00 MeV Emin = 1.48949E-03 MeV : (n,a5) + 13 MT = 849 Q = 4.32600E+00 MeV Emin = 1.54611E-03 MeV : (n,alpha) to continuum + 14 MT = 4 Q = 0.00000E+00 MeV Emin = 2.00000E-01 MeV : total inelastic scattering + + Nuclide 108 / 1657 : 42096.82c -- molybdenum 96 (Mo-96) + + Pointers : 815680 27975 + Primary type : Transport + Nuclide ZAI : 420960 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Mo96.ACE + Atomic weight (AW) : 95.90467 + Atomic weight ratio (AWR) : 95.08080 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 28 reaction channels + - 6 special reactions + - 9 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 28 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -9.15428E+00 MeV Emin = 9.25057E+00 MeV frac = 1.00000E+00 Product nuclide = 42095.82c : (n,2n) + 3 MT = 17 Q = -1.65294E+01 MeV Emin = 1.67033E+01 MeV frac = 1.00000E+00 Product nuclide = 42094.82c : (n,3n) + 4 MT = 22 Q = -2.76394E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 40092.82c : (n,nalpha) + 5 MT = 28 Q = -9.29661E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 41095.82c : (n,np) + 6 MT = 51 Q = -7.78199E-01 MeV Emin = 7.73648E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.14790E+00 MeV Emin = 1.15377E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -1.49770E+00 MeV Emin = 1.50673E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -1.62590E+00 MeV Emin = 1.64021E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -1.62810E+00 MeV Emin = 1.64411E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -1.86950E+00 MeV Emin = 1.88674E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -1.97840E+00 MeV Emin = 1.99239E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -2.09560E+00 MeV Emin = 2.11764E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -2.21930E+00 MeV Emin = 2.24264E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -2.23450E+00 MeV Emin = 2.25800E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -2.42610E+00 MeV Emin = 2.45162E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -2.43840E+00 MeV Emin = 2.46405E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -2.44060E+00 MeV Emin = 2.46627E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -2.48100E+00 MeV Emin = 2.50710E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -2.50150E+00 MeV Emin = 2.52781E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 21 MT = 66 Q = -2.54040E+00 MeV Emin = 2.56712E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 22 MT = 67 Q = -2.59430E+00 MeV Emin = 2.62159E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 23 MT = 91 Q = -2.59400E+00 MeV Emin = 2.62128E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 24 MT = 102 Q = 6.82127E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 42097.82c : (n,gamma) + 25 MT = 103 Q = -2.40443E+00 MeV Emin = 2.78973E+00 MeV frac = 1.00000E+00 Product nuclide = 410960 : (n,p) + 26 MT = 104 Q = -6.99191E+00 MeV Emin = 7.06546E+00 MeV frac = 1.00000E+00 Product nuclide = 41095.82c : (n,d) + 27 MT = 105 Q = -9.30226E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 41094.82c : (n,t) + 28 MT = 107 Q = 3.97600E+00 MeV Emin = 9.99218E-02 MeV frac = 1.00000E+00 Product nuclide = 40093.82c : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = -2.76394E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -9.29661E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -2.40443E+00 MeV Emin = 2.78973E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -6.99191E+00 MeV Emin = 7.06546E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -9.30226E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 107 Q = 3.97600E+00 MeV Emin = 9.99218E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.78973E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.06546E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.00000E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 9.99218E-02 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.32897E-03 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 7.73648E-01 MeV : total inelastic scattering + + Nuclide 109 / 1657 : 42097.82c -- molybdenum 97 (Mo-97) + + Pointers : 818711 28021 + Primary type : Transport + Nuclide ZAI : 420970 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Mo97.ACE + Atomic weight (AW) : 96.90597 + Atomic weight ratio (AWR) : 96.07350 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 25 reaction channels + - 7 special reactions + - 10 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 25 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.81598E+00 MeV Emin = 6.88694E+00 MeV frac = 1.00000E+00 Product nuclide = 42096.82c : (n,2n) + 3 MT = 17 Q = -1.59703E+01 MeV Emin = 1.61365E+01 MeV frac = 1.00000E+00 Product nuclide = 42095.82c : (n,3n) + 4 MT = 22 Q = -2.82144E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 40093.82c : (n,nalpha) + 5 MT = 28 Q = -9.22041E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 410960 : (n,np) + 6 MT = 51 Q = -4.80899E-01 MeV Emin = 4.52953E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -6.57899E-01 MeV Emin = 6.44874E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -6.79599E-01 MeV Emin = 6.81207E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -7.19199E-01 MeV Emin = 7.14194E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -7.20799E-01 MeV Emin = 7.27646E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -7.52999E-01 MeV Emin = 7.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -7.94999E-01 MeV Emin = 8.01827E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -8.40899E-01 MeV Emin = 8.49306E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -8.88099E-01 MeV Emin = 8.88902E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -9.92999E-01 MeV Emin = 1.00167E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -1.02450E+00 MeV Emin = 1.02323E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -1.09280E+00 MeV Emin = 1.09475E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -1.11680E+00 MeV Emin = 1.11927E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 91 Q = -1.11700E+00 MeV Emin = 1.12839E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 20 MT = 102 Q = 8.64260E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 42098.82c : (n,gamma) + 21 MT = 103 Q = -1.15043E+00 MeV Emin = 2.00149E+00 MeV frac = 1.00000E+00 Product nuclide = 410970 : (n,p) + 22 MT = 104 Q = -6.92001E+00 MeV Emin = 7.71191E+00 MeV frac = 1.00000E+00 Product nuclide = 410960 : (n,d) + 23 MT = 105 Q = -7.63246E+00 MeV Emin = 8.70061E+00 MeV frac = 1.00000E+00 Product nuclide = 41095.82c : (n,t) + 24 MT = 106 Q = -8.73692E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 40095.82c : (n,He-3) + 25 MT = 107 Q = 5.37360E+00 MeV Emin = 9.49999E-02 MeV frac = 1.00000E+00 Product nuclide = 40094.82c : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -2.82144E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -9.22041E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -1.15043E+00 MeV Emin = 2.00149E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -6.92001E+00 MeV Emin = 7.71191E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -7.63246E+00 MeV Emin = 8.70061E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 106 Q = -8.73692E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 7 MT = 107 Q = 5.37360E+00 MeV Emin = 9.49999E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.00149E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.71191E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 8.70061E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.10000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 9.49999E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.46367E-03 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 4.52953E-01 MeV : total inelastic scattering + + Nuclide 110 / 1657 : 42098.82c -- molybdenum 98 (Mo-98) + + Pointers : 821669 28067 + Primary type : Transport + Nuclide ZAI : 420980 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Mo98.ACE + Atomic weight (AW) : 97.90536 + Atomic weight ratio (AWR) : 97.06430 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 3.16E+21 seconds (1E+14 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 25 reaction channels + - 6 special reactions + - 9 transmutation reactions + - 6 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 25 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.64238E+00 MeV Emin = 8.73143E+00 MeV frac = 1.00000E+00 Product nuclide = 42097.82c : (n,2n) + 3 MT = 17 Q = -1.54584E+01 MeV Emin = 1.56177E+01 MeV frac = 1.00000E+00 Product nuclide = 42096.82c : (n,3n) + 4 MT = 22 Q = -3.27274E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 40094.82c : (n,nalpha) + 5 MT = 28 Q = -9.79511E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 410970 : (n,np) + 6 MT = 51 Q = -7.34800E-01 MeV Emin = 7.35488E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -7.87400E-01 MeV Emin = 7.94556E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -1.43230E+00 MeV Emin = 1.44396E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -1.51000E+00 MeV Emin = 1.51955E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -1.75850E+00 MeV Emin = 1.76892E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -1.88090E+00 MeV Emin = 1.89217E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -1.96500E+00 MeV Emin = 1.97737E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -2.01750E+00 MeV Emin = 2.03829E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -2.03760E+00 MeV Emin = 2.05859E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -2.10480E+00 MeV Emin = 2.12649E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -2.20630E+00 MeV Emin = 2.22903E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -2.22380E+00 MeV Emin = 2.24671E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -2.33340E+00 MeV Emin = 2.35744E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -2.34360E+00 MeV Emin = 2.36775E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 91 Q = -2.34400E+00 MeV Emin = 2.36815E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 21 MT = 102 Q = 5.92544E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 42099.82c : (n,gamma) + 22 MT = 103 Q = -3.80292E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 410980 : (n,p) + 23 MT = 104 Q = -7.48730E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 410970 : (n,d) + 24 MT = 105 Q = -9.38185E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 410960 : (n,t) + 25 MT = 107 Q = 3.20222E+00 MeV Emin = 1.00098E-01 MeV frac = 1.00000E+00 Product nuclide = 40095.82c : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = -3.27274E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -9.79511E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -3.80292E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -7.48730E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -9.38185E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 107 Q = 3.20222E+00 MeV Emin = 1.00098E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.00000E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00098E-01 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.46259E-03 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 7.35488E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 11 Q = 1.10000E-01 MeV frac = 1.00000E+00 Product nuclide = 440980 : beta- + beta- + + Nuclide 111 / 1657 : 42099.82c -- molybdenum 99 (Mo-99) + + Pointers : 824554 28113 + Primary type : Transport + Nuclide ZAI : 420990 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Mo99.ACE + Atomic weight (AW) : 98.90767 + Atomic weight ratio (AWR) : 98.05800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.37E+05 seconds (2.75 days) + Specific ingestion toxicity : 6.00E-10 Sv/Bq + Specific inhalation toxicity : 9.90E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 29 reaction channels + - 6 special reactions + - 11 transmutation reactions + - 8 transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 29 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.93020E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 42098.82c : (n,2n) + 3 MT = 17 Q = -1.45772E+01 MeV Emin = 1.47259E+01 MeV frac = 1.00000E+00 Product nuclide = 42097.82c : (n,3n) + 4 MT = 22 Q = -2.72799E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 40095.82c : (n,nalpha) + 5 MT = 28 Q = -9.73313E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 410980 : (n,np) + 6 MT = 32 Q = -1.34175E+01 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 410970 : (n,nd) + 7 MT = 33 Q = -1.53121E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 410960 : (n,nt) + 8 MT = 51 Q = -9.79999E-02 MeV Emin = 9.87499E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -2.35500E-01 MeV Emin = 2.18951E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -3.52000E-01 MeV Emin = 3.41693E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -5.25499E-01 MeV Emin = 5.29357E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -5.48999E-01 MeV Emin = 5.50325E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -6.14999E-01 MeV Emin = 6.08771E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -6.86999E-01 MeV Emin = 6.93045E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -7.53499E-01 MeV Emin = 7.45888E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -7.92999E-01 MeV Emin = 8.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -8.89499E-01 MeV Emin = 8.80293E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -9.04999E-01 MeV Emin = 9.13176E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 62 Q = -9.12999E-01 MeV Emin = 9.21411E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 20 MT = 63 Q = -9.44999E-01 MeV Emin = 9.42515E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 21 MT = 64 Q = -9.51999E-01 MeV Emin = 9.60566E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 22 MT = 65 Q = -1.03300E+00 MeV Emin = 1.02177E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 23 MT = 66 Q = -1.15000E+00 MeV Emin = 1.13403E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 24 MT = 91 Q = -1.19900E+00 MeV Emin = 1.20896E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 25 MT = 102 Q = 8.29089E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 42100.82c : (n,gamma) + 26 MT = 103 Q = -2.84103E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 410990 : (n,p) + 27 MT = 104 Q = -7.42301E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 410980 : (n,d) + 28 MT = 105 Q = -7.23235E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 410970 : (n,t) + 29 MT = 107 Q = 5.12940E+00 MeV Emin = 9.99608E-02 MeV frac = 1.00000E+00 Product nuclide = 40096.82c : (n,alpha) + + 8 additional transport branches: + + 1 MT = 22 Q = -2.72799E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -9.73313E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.34175E+01 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.53121E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 103 Q = -2.84103E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 104 Q = -7.42301E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 7 MT = 105 Q = -7.23235E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 8 MT = 107 Q = 5.12940E+00 MeV Emin = 9.99608E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 8.00000E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 9.99608E-02 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 9.87499E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.35720E+00 MeV frac = 1.21895E-01 Product nuclide = 43099.82c : beta- + 2 RTYP = 1 Q = 1.21452E+00 MeV frac = 8.78105E-01 Product nuclide = 430991 : beta- + + Nuclide 112 / 1657 : 42100.82c -- molybdenum 100 (Mo-100) + + Pointers : 829439 27791 + Primary type : Transport + Nuclide ZAI : 421000 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Mo100.ACE + Atomic weight (AW) : 99.90746 + Atomic weight ratio (AWR) : 99.04920 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.30E+26 seconds (7.3E+18 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 15 reaction channels + - 6 special reactions + - 9 transmutation reactions + - 6 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 15 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.30078E+00 MeV Emin = 8.38459E+00 MeV frac = 1.00000E+00 Product nuclide = 42099.82c : (n,2n) + 3 MT = 17 Q = -1.42176E+01 MeV Emin = 1.43612E+01 MeV frac = 1.00000E+00 Product nuclide = 42098.82c : (n,3n) + 4 MT = 22 Q = -3.18404E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 40096.82c : (n,nalpha) + 5 MT = 28 Q = -1.06143E+01 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 410990 : (n,np) + 6 MT = 51 Q = -5.35599E-01 MeV Emin = 5.36129E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -6.94399E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -1.06370E+00 MeV Emin = 1.07119E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -1.13610E+00 MeV Emin = 1.13810E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 91 Q = -1.13600E+00 MeV Emin = 1.13810E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 11 MT = 102 Q = 5.39825E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 421010 : (n,gamma) + 12 MT = 103 Q = -5.44653E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 411000 : (n,p) + 13 MT = 104 Q = -8.82651E+00 MeV Emin = 9.62972E+00 MeV frac = 1.00000E+00 Product nuclide = 410990 : (n,d) + 14 MT = 105 Q = -9.53346E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 410980 : (n,t) + 15 MT = 107 Q = 2.41940E+00 MeV Emin = 1.37500E-01 MeV frac = 1.00000E+00 Product nuclide = 400970 : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = -3.18404E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.06143E+01 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -5.44653E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -8.82651E+00 MeV Emin = 9.62972E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -9.53346E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 107 Q = 2.41940E+00 MeV Emin = 1.37500E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 6.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 9.62972E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.00000E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 1.37500E-01 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.46067E-03 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 5.36129E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 11 Q = 3.03437E+00 MeV frac = 1.00000E+00 Product nuclide = 44100.82c : beta- + beta- + + Nuclide 113 / 1657 : 43099.82c -- technetium 99 (Tc-99) + + Pointers : 857962 34415 + Primary type : Transport + Nuclide ZAI : 430990 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Tc99.ACE + Atomic weight (AW) : 98.90627 + Atomic weight ratio (AWR) : 98.05661 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+02 + Half-life : 6.67E+12 seconds (211,640 years) + Specific ingestion toxicity : 6.40E-10 Sv/Bq + Specific inhalation toxicity : 1.30E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 40 reaction channels + - 52 special reactions + - 17 transmutation reactions + - 15 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 40 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 5 Q = 0.00000E+00 MeV Emin = 8.50000E-02 MeV frac = 1.00000E+00 Product nuclide = self : anything + 3 MT = 16 Q = -8.96662E+00 MeV Emin = 9.05806E+00 MeV frac = 1.00000E+00 Product nuclide = 430980 : (n,2n) + 4 MT = 17 Q = -1.62454E+01 MeV Emin = 1.64111E+01 MeV frac = 1.00000E+00 Product nuclide = 430970 : (n,3n) + 5 MT = 22 Q = -2.96576E+00 MeV Emin = 5.40000E+00 MeV frac = 1.00000E+00 Product nuclide = 41095.82c : (n,nalpha) + 6 MT = 24 Q = -1.14546E+01 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 41094.82c : (n,2nalpha) + 7 MT = 28 Q = -6.50027E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 42098.82c : (n,np) + 8 MT = 32 Q = -1.29182E+01 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 42097.82c : (n,nd) + 9 MT = 33 Q = -1.34821E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 42096.82c : (n,nt) + 10 MT = 41 Q = -1.51428E+01 MeV Emin = 1.52972E+01 MeV frac = 1.00000E+00 Product nuclide = 42097.82c : (n,2np) + 11 MT = 51 Q = -1.40511E-01 MeV Emin = 1.36701E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 12 MT = 52 Q = -1.42683E-01 MeV Emin = 1.43041E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 13 MT = 53 Q = -1.81094E-01 MeV Emin = 1.75000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 14 MT = 54 Q = -5.09105E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 15 MT = 55 Q = -5.34430E-01 MeV Emin = 5.29910E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 16 MT = 56 Q = -5.36900E-01 MeV Emin = 5.41128E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 17 MT = 57 Q = -6.12490E-01 MeV Emin = 6.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 18 MT = 58 Q = -6.25410E-01 MeV Emin = 6.26571E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 19 MT = 59 Q = -6.52770E-01 MeV Emin = 6.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 20 MT = 60 Q = -6.71543E-01 MeV Emin = 6.69570E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 21 MT = 61 Q = -7.19800E-01 MeV Emin = 7.26524E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 22 MT = 62 Q = -7.26700E-01 MeV Emin = 7.31191E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 23 MT = 63 Q = -7.61690E-01 MeV Emin = 7.60194E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 24 MT = 64 Q = -7.61910E-01 MeV Emin = 7.69458E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 25 MT = 65 Q = -9.20596E-01 MeV Emin = 9.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 26 MT = 66 Q = -9.86150E-01 MeV Emin = 9.73104E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 27 MT = 67 Q = -1.00406E+00 MeV Emin = 1.00715E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 28 MT = 68 Q = -1.01746E+00 MeV Emin = 1.02291E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 29 MT = 69 Q = -1.07221E+00 MeV Emin = 1.04872E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 30 MT = 70 Q = -1.08147E+00 MeV Emin = 1.08782E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 31 MT = 91 Q = -1.08147E+00 MeV Emin = 1.08782E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 32 MT = 102 Q = 6.76441E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 431000 : (n,gamma) + 33 MT = 103 Q = -5.74874E-01 MeV Emin = 1.24138E+00 MeV frac = 1.00000E+00 Product nuclide = 42099.82c : (n,p) + 34 MT = 104 Q = -4.27569E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 42098.82c : (n,d) + 35 MT = 105 Q = -6.66095E+00 MeV Emin = 7.80000E+00 MeV frac = 1.00000E+00 Product nuclide = 42097.82c : (n,t) + 36 MT = 106 Q = -8.57624E+00 MeV Emin = 1.15000E+01 MeV frac = 1.00000E+00 Product nuclide = 410970 : (n,He-3) + 37 MT = 107 Q = 3.92732E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 410960 : (n,alpha) + 38 MT = 108 Q = 7.13659E-01 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 390920 : (n,2alpha) + 39 MT = 111 Q = -1.03035E+01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 410980 : (n,2p) + 40 MT = 112 Q = -3.30824E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 40095.82c : (n,palpha) + + 15 additional transport branches: + + 1 MT = 22 Q = -2.96576E+00 MeV Emin = 5.40000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 24 Q = -1.14546E+01 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,2nalpha) + 3 MT = 28 Q = -6.50027E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 4 MT = 32 Q = -1.29182E+01 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 5 MT = 33 Q = -1.34821E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 6 MT = 41 Q = -1.51428E+01 MeV Emin = 1.52972E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,2np) + 7 MT = 103 Q = -5.74874E-01 MeV Emin = 1.24138E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 8 MT = 104 Q = -4.27569E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 9 MT = 105 Q = -6.66095E+00 MeV Emin = 7.80000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 10 MT = 106 Q = -8.57624E+00 MeV Emin = 1.15000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 11 MT = 107 Q = 3.92732E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 12 MT = 108 Q = 7.13659E-01 MeV Emin = 2.00000E+00 MeV frac = 2.00000E+00 Product nuclide = 2004.82c : (n,2alpha) + 13 MT = 111 Q = -1.03035E+01 MeV Emin = 1.30000E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + 14 MT = 112 Q = -3.30824E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,palpha) + 15 MT = 112 Q = -3.30824E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,palpha) + + 52 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.24138E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 7.80000E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.15000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 600 Q = 0.00000E+00 MeV Emin = 1.30000E+00 MeV : (n,p) to ground state + 8 MT = 601 Q = -9.77850E-02 MeV Emin = 1.30000E+00 MeV : (n,p1) + 9 MT = 602 Q = -2.35508E-01 MeV Emin = 1.40000E+00 MeV : (n,p2) + 10 MT = 603 Q = -3.51240E-01 MeV Emin = 1.60000E+00 MeV : (n,p3) + 11 MT = 604 Q = -5.25197E-01 MeV Emin = 1.80000E+00 MeV : (n,p4) + 12 MT = 605 Q = -5.48680E-01 MeV Emin = 1.80000E+00 MeV : (n,p5) + 13 MT = 606 Q = -6.15080E-01 MeV Emin = 1.80000E+00 MeV : (n,p6) + 14 MT = 607 Q = -6.31770E-01 MeV Emin = 1.95000E+00 MeV : (n,p7) + 15 MT = 608 Q = -6.84500E-01 MeV Emin = 1.80000E+00 MeV : (n,p8) + 16 MT = 609 Q = -6.97970E-01 MeV Emin = 1.95000E+00 MeV : (n,p9) + 17 MT = 610 Q = -7.52400E-01 MeV Emin = 2.00000E+00 MeV : (n,p10) + 18 MT = 649 Q = -7.52400E-01 MeV Emin = 2.00000E+00 MeV : (n,p) to continuum + 19 MT = 650 Q = 0.00000E+00 MeV Emin = 5.00000E+00 MeV : (n,d) to ground state + 20 MT = 651 Q = -7.34750E-01 MeV Emin = 5.40000E+00 MeV : (n,d1) + 21 MT = 652 Q = -7.87384E-01 MeV Emin = 5.80000E+00 MeV : (n,d2) + 22 MT = 653 Q = -1.43221E+00 MeV Emin = 6.20000E+00 MeV : (n,d3) + 23 MT = 654 Q = -1.51004E+00 MeV Emin = 6.60000E+00 MeV : (n,d4) + 24 MT = 655 Q = -1.75848E+00 MeV Emin = 6.80000E+00 MeV : (n,d5) + 25 MT = 699 Q = -1.75848E+00 MeV Emin = 7.20000E+00 MeV : (n,d) to continuum + 26 MT = 700 Q = 0.00000E+00 MeV Emin = 7.80000E+00 MeV : (n,t) to ground state + 27 MT = 701 Q = -4.80900E-01 MeV Emin = 8.00000E+00 MeV : (n,t1) + 28 MT = 702 Q = -6.58130E-01 MeV Emin = 8.00000E+00 MeV : (n,t2) + 29 MT = 703 Q = -6.79590E-01 MeV Emin = 8.50000E+00 MeV : (n,t3) + 30 MT = 704 Q = -7.19190E-01 MeV Emin = 8.50000E+00 MeV : (n,t4) + 31 MT = 705 Q = -7.20920E-01 MeV Emin = 8.50000E+00 MeV : (n,t5) + 32 MT = 749 Q = -7.20920E-01 MeV Emin = 8.50000E+00 MeV : (n,t) to continuum + 33 MT = 750 Q = 0.00000E+00 MeV Emin = 1.15000E+01 MeV : (n,He-3) to ground state + 34 MT = 751 Q = -7.43350E-01 MeV Emin = 1.20000E+01 MeV : (n,He-3_1) + 35 MT = 752 Q = -1.14796E+00 MeV Emin = 1.25000E+01 MeV : (n,He-3_2) + 36 MT = 753 Q = -1.16000E+00 MeV Emin = 1.25000E+01 MeV : (n,He-3_3) + 37 MT = 754 Q = -1.25101E+00 MeV Emin = 1.25000E+01 MeV : (n,He-3_4) + 38 MT = 755 Q = -1.27609E+00 MeV Emin = 1.30000E+01 MeV : (n,He-3_5) + 39 MT = 799 Q = -1.27609E+00 MeV Emin = 1.35000E+01 MeV : (n,He-3) to continuum + 40 MT = 800 Q = 3.92732E+00 MeV Emin = 1.00000E-11 MeV : (n,alpha) to ground state + 41 MT = 801 Q = 3.88313E+00 MeV Emin = 1.00000E-11 MeV : (n,a1) + 42 MT = 802 Q = 3.78122E+00 MeV Emin = 1.00000E-11 MeV : (n,a2) + 43 MT = 803 Q = 3.74274E+00 MeV Emin = 1.00000E-11 MeV : (n,a3) + 44 MT = 804 Q = 3.69432E+00 MeV Emin = 1.00000E-11 MeV : (n,a4) + 45 MT = 805 Q = 3.41545E+00 MeV Emin = 1.00000E-11 MeV : (n,a5) + 46 MT = 806 Q = 3.29237E+00 MeV Emin = 1.00000E-11 MeV : (n,a6) + 47 MT = 807 Q = 3.23269E+00 MeV Emin = 1.00000E-11 MeV : (n,a7) + 48 MT = 808 Q = 3.05944E+00 MeV Emin = 1.00000E-11 MeV : (n,a8) + 49 MT = 809 Q = 2.92466E+00 MeV Emin = 1.00000E-11 MeV : (n,a9) + 50 MT = 810 Q = 2.88190E+00 MeV Emin = 1.00000E-11 MeV : (n,a10) + 51 MT = 849 Q = 2.88190E+00 MeV Emin = 1.00000E-11 MeV : (n,alpha) to continuum + 52 MT = 4 Q = 0.00000E+00 MeV Emin = 1.36701E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.93800E-01 MeV frac = 1.00000E+00 Product nuclide = 440990 : beta- + + Nuclide 114 / 1657 : 44100.82c -- ruthenium 100 (Ru-100) + + Pointers : 914002 31563 + Primary type : Transport + Nuclide ZAI : 441000 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ru100.ACE + Atomic weight (AW) : 99.90423 + Atomic weight ratio (AWR) : 99.04600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 28 reaction channels + - 6 special reactions + - 10 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 28 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -9.67789E+00 MeV Emin = 9.86186E+00 MeV frac = 1.00000E+00 Product nuclide = 440990 : (n,2n) + 3 MT = 17 Q = -1.71478E+01 MeV Emin = 1.73209E+01 MeV frac = 1.00000E+00 Product nuclide = 440980 : (n,3n) + 4 MT = 22 Q = -2.84860E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 42096.82c : (n,nalpha) + 5 MT = 28 Q = -9.18903E+00 MeV Emin = 9.75962E+00 MeV frac = 1.00000E+00 Product nuclide = 43099.82c : (n,np) + 6 MT = 32 Q = -1.58472E+01 MeV Emin = 1.60072E+01 MeV frac = 1.00000E+00 Product nuclide = 430980 : (n,nd) + 7 MT = 51 Q = -5.39599E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 8 MT = 52 Q = -1.13040E+00 MeV Emin = 1.07090E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 9 MT = 53 Q = -1.22650E+00 MeV Emin = 1.21461E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 10 MT = 54 Q = -1.36210E+00 MeV Emin = 1.34439E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 11 MT = 55 Q = -1.74070E+00 MeV Emin = 1.75000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 12 MT = 56 Q = -1.86530E+00 MeV Emin = 1.85660E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 13 MT = 57 Q = -1.88120E+00 MeV Emin = 1.89216E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 14 MT = 58 Q = -2.05170E+00 MeV Emin = 2.07242E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 15 MT = 59 Q = -2.06390E+00 MeV Emin = 2.08474E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 16 MT = 60 Q = -2.07770E+00 MeV Emin = 2.09868E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 17 MT = 61 Q = -2.09930E+00 MeV Emin = 2.12050E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 18 MT = 62 Q = -2.16730E+00 MeV Emin = 2.18918E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 19 MT = 63 Q = -2.24060E+00 MeV Emin = 2.26322E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 20 MT = 64 Q = -2.38720E+00 MeV Emin = 2.41130E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 21 MT = 65 Q = -2.46940E+00 MeV Emin = 2.49433E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 22 MT = 66 Q = -2.51680E+00 MeV Emin = 2.54221E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 23 MT = 91 Q = -2.61330E+00 MeV Emin = 2.63969E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 24 MT = 102 Q = 6.80206E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 44101.82c : (n,gamma) + 25 MT = 103 Q = -2.42034E+00 MeV Emin = 2.87736E+00 MeV frac = 1.00000E+00 Product nuclide = 431000 : (n,p) + 26 MT = 104 Q = -6.87891E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 43099.82c : (n,d) + 27 MT = 105 Q = -9.66206E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 430980 : (n,t) + 28 MT = 107 Q = 3.97709E+00 MeV Emin = 9.96875E-02 MeV frac = 1.00000E+00 Product nuclide = 42097.82c : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -2.84860E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -9.18903E+00 MeV Emin = 9.75962E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.58472E+01 MeV Emin = 1.60072E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 103 Q = -2.42034E+00 MeV Emin = 2.87736E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -6.87891E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -9.66206E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 107 Q = 3.97709E+00 MeV Emin = 9.96875E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.87736E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.00000E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 9.96875E-02 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 5.78125E-04 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 5.00000E-01 MeV : total inelastic scattering + + Nuclide 115 / 1657 : 44101.82c -- ruthenium 101 (Ru-101) + + Pointers : 917106 31609 + Primary type : Transport + Nuclide ZAI : 441010 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ru101.ACE + Atomic weight (AW) : 100.90583 + Atomic weight ratio (AWR) : 100.03900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 24 reaction channels + - 4 special reactions + - 7 transmutation reactions + - 4 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 24 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.80150E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 44100.82c : (n,2n) + 3 MT = 17 Q = -1.64750E+01 MeV Emin = 1.66397E+01 MeV frac = 1.00000E+00 Product nuclide = 440990 : (n,3n) + 4 MT = 22 Q = -2.83210E+00 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 42097.82c : (n,nalpha) + 5 MT = 28 Q = -9.22190E+00 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 431000 : (n,np) + 6 MT = 51 Q = -1.27200E-01 MeV Emin = 1.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -3.06800E-01 MeV Emin = 3.09007E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -3.11300E-01 MeV Emin = 3.12611E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -3.25200E-01 MeV Emin = 3.28314E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -3.44100E-01 MeV Emin = 3.45552E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -4.22100E-01 MeV Emin = 4.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -4.62300E-01 MeV Emin = 4.46620E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -5.27500E-01 MeV Emin = 5.30261E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -5.35000E-01 MeV Emin = 5.35304E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -5.45100E-01 MeV Emin = 5.49669E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -6.16300E-01 MeV Emin = 6.22224E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -6.23400E-01 MeV Emin = 6.25928E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -6.23500E-01 MeV Emin = 6.25928E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -6.43800E-01 MeV Emin = 6.48731E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -6.84000E-01 MeV Emin = 6.85000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 21 MT = 91 Q = -6.95000E-01 MeV Emin = 6.97660E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 22 MT = 102 Q = 9.21965E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 44102.82c : (n,gamma) + 23 MT = 103 Q = -8.42330E-01 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 431010 : (n,p) + 24 MT = 107 Q = 5.81030E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 42098.82c : (n,alpha) + + 4 additional transport branches: + + 1 MT = 22 Q = -2.83210E+00 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -9.22190E+00 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -8.42330E-01 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 107 Q = 5.81030E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 4 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.00000E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 5.00000E+00 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 6.05093E-04 MeV : damage-energy production + 4 MT = 4 Q = 0.00000E+00 MeV Emin = 1.00000E-01 MeV : total inelastic scattering + + Nuclide 116 / 1657 : 44102.82c -- ruthenium 102 (Ru-102) + + Pointers : 919553 31655 + Primary type : Transport + Nuclide ZAI : 441020 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ru102.ACE + Atomic weight (AW) : 101.90542 + Atomic weight ratio (AWR) : 101.03000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 18 reaction channels + - 7 special reactions + - 10 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 18 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -9.22060E+00 MeV Emin = 9.31190E+00 MeV frac = 1.00000E+00 Product nuclide = 44101.82c : (n,2n) + 3 MT = 17 Q = -1.60220E+01 MeV Emin = 1.61810E+01 MeV frac = 1.00000E+00 Product nuclide = 44100.82c : (n,3n) + 4 MT = 22 Q = -3.41130E+00 MeV Emin = 9.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 42098.82c : (n,nalpha) + 5 MT = 28 Q = -1.00510E+01 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 431010 : (n,np) + 6 MT = 51 Q = -4.75100E-01 MeV Emin = 4.75000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -9.43700E-01 MeV Emin = 9.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -1.10320E+00 MeV Emin = 1.05705E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -1.10640E+00 MeV Emin = 1.11624E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -1.52170E+00 MeV Emin = 1.53608E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -1.58060E+00 MeV Emin = 1.57215E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 91 Q = -1.58060E+00 MeV Emin = 1.75000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 13 MT = 102 Q = 6.23205E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 44103.82c : (n,gamma) + 14 MT = 103 Q = -3.74750E+00 MeV Emin = 6.25000E+00 MeV frac = 1.00000E+00 Product nuclide = 431020 : (n,p) + 15 MT = 104 Q = -7.82620E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 431010 : (n,d) + 16 MT = 105 Q = -9.96060E+00 MeV Emin = 1.35000E+01 MeV frac = 1.00000E+00 Product nuclide = 431000 : (n,t) + 17 MT = 106 Q = -9.77250E+00 MeV Emin = 1.95000E+01 MeV frac = 1.00000E+00 Product nuclide = 42100.82c : (n,He-3) + 18 MT = 107 Q = 2.65136E+00 MeV Emin = 1.75000E-01 MeV frac = 1.00000E+00 Product nuclide = 42099.82c : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -3.41130E+00 MeV Emin = 9.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.00510E+01 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -3.74750E+00 MeV Emin = 6.25000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -7.82620E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -9.96060E+00 MeV Emin = 1.35000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 106 Q = -9.77250E+00 MeV Emin = 1.95000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 7 MT = 107 Q = 2.65136E+00 MeV Emin = 1.75000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 6.25000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.10000E+01 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.35000E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.95000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.75000E-01 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 6.42994E-04 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 4.75000E-01 MeV : total inelastic scattering + + Nuclide 117 / 1657 : 44103.82c -- ruthenium 103 (Ru-103) + + Pointers : 922000 31701 + Primary type : Transport + Nuclide ZAI : 441030 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ru103.ACE + Atomic weight (AW) : 102.90400 + Atomic weight ratio (AWR) : 102.02000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 3.39E+06 seconds (39.3 days) + Specific ingestion toxicity : 7.30E-10 Sv/Bq + Specific inhalation toxicity : 3.00E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 33 reaction channels + - 6 special reactions + - 9 transmutation reactions + - 6 transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 33 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.23240E+00 MeV Emin = 6.29350E+00 MeV frac = 1.00000E+00 Product nuclide = 44102.82c : (n,2n) + 3 MT = 17 Q = -1.54530E+01 MeV Emin = 1.57500E+01 MeV frac = 1.00000E+00 Product nuclide = 44101.82c : (n,3n) + 4 MT = 22 Q = -3.71780E+00 MeV Emin = 1.42500E+01 MeV frac = 1.00000E+00 Product nuclide = 42099.82c : (n,nalpha) + 5 MT = 28 Q = -9.97990E+00 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 431020 : (n,np) + 6 MT = 51 Q = -2.70000E-03 MeV Emin = 2.50000E-03 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.36100E-01 MeV Emin = 1.30000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -1.74300E-01 MeV Emin = 1.75660E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -2.13600E-01 MeV Emin = 1.99267E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -2.38200E-01 MeV Emin = 2.28112E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -2.97500E-01 MeV Emin = 3.00289E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -3.46400E-01 MeV Emin = 3.22484E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -4.04100E-01 MeV Emin = 3.78930E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -4.06100E-01 MeV Emin = 4.09071E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -4.32100E-01 MeV Emin = 4.23210E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -5.01200E-01 MeV Emin = 4.71225E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -5.35400E-01 MeV Emin = 5.40223E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -5.48200E-01 MeV Emin = 5.47638E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -5.54600E-01 MeV Emin = 5.59871E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -5.57700E-01 MeV Emin = 5.61971E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 21 MT = 66 Q = -5.62900E-01 MeV Emin = 5.65795E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 22 MT = 67 Q = -5.68200E-01 MeV Emin = 5.73470E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 23 MT = 68 Q = -5.92000E-01 MeV Emin = 5.83110E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 24 MT = 69 Q = -6.22000E-01 MeV Emin = 6.24119E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 25 MT = 70 Q = -6.53700E-01 MeV Emin = 6.59208E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 26 MT = 71 Q = -6.61500E-01 MeV Emin = 6.59208E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 27 MT = 72 Q = -6.97200E-01 MeV Emin = 6.86007E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 28 MT = 91 Q = -6.97200E-01 MeV Emin = 6.86007E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 29 MT = 102 Q = 8.90142E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 44104.82c : (n,gamma) + 30 MT = 103 Q = -1.87710E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 431030 : (n,p) + 31 MT = 104 Q = -7.75540E+00 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 431020 : (n,d) + 32 MT = 105 Q = -7.80150E+00 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 431010 : (n,t) + 33 MT = 107 Q = 4.57230E+00 MeV Emin = 2.25000E+00 MeV frac = 1.00000E+00 Product nuclide = 42100.82c : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = -3.71780E+00 MeV Emin = 1.42500E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -9.97990E+00 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -1.87710E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -7.75540E+00 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -7.80150E+00 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 107 Q = 4.57230E+00 MeV Emin = 2.25000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 5.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.25000E+01 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.20000E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 2.25000E+00 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 6.00000E-04 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 2.50000E-03 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 1 Q = 7.66200E-01 MeV frac = 1.19763E-02 Product nuclide = 45103.82c : beta- + 2 RTYP = 1 Q = 7.26441E-01 MeV frac = 9.88024E-01 Product nuclide = 451031 : beta- + + Nuclide 118 / 1657 : 44104.82c -- ruthenium 104 (Ru-104) + + Pointers : 926926 31747 + Primary type : Transport + Nuclide ZAI : 441040 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ru104.ACE + Atomic weight (AW) : 103.90258 + Atomic weight ratio (AWR) : 103.01000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 16 reaction channels + - 6 special reactions + - 9 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 16 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.90390E+00 MeV Emin = 8.99034E+00 MeV frac = 1.00000E+00 Product nuclide = 44103.82c : (n,2n) + 3 MT = 17 Q = -1.51360E+01 MeV Emin = 1.52830E+01 MeV frac = 1.00000E+00 Product nuclide = 44102.82c : (n,3n) + 4 MT = 22 Q = -4.33160E+00 MeV Emin = 1.12500E+01 MeV frac = 1.00000E+00 Product nuclide = 42100.82c : (n,nalpha) + 5 MT = 28 Q = -1.07810E+01 MeV Emin = 1.32500E+01 MeV frac = 1.00000E+00 Product nuclide = 431030 : (n,np) + 6 MT = 51 Q = -3.58000E-01 MeV Emin = 3.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -8.88500E-01 MeV Emin = 8.75000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -8.93100E-01 MeV Emin = 9.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -9.88300E-01 MeV Emin = 9.75000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -1.24240E+00 MeV Emin = 1.25000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 91 Q = -1.24240E+00 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 12 MT = 102 Q = 5.91010E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 44105.82c : (n,gamma) + 13 MT = 103 Q = -4.82050E+00 MeV Emin = 7.25000E+00 MeV frac = 1.00000E+00 Product nuclide = 431040 : (n,p) + 14 MT = 104 Q = -8.55640E+00 MeV Emin = 1.17500E+01 MeV frac = 1.00000E+00 Product nuclide = 431030 : (n,d) + 15 MT = 105 Q = -1.04020E+01 MeV Emin = 1.37500E+01 MeV frac = 1.00000E+00 Product nuclide = 431020 : (n,t) + 16 MT = 107 Q = 1.13096E+00 MeV Emin = 6.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 421010 : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = -4.33160E+00 MeV Emin = 1.12500E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.07810E+01 MeV Emin = 1.32500E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -4.82050E+00 MeV Emin = 7.25000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -8.55640E+00 MeV Emin = 1.17500E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -1.04020E+01 MeV Emin = 1.37500E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 107 Q = 1.13096E+00 MeV Emin = 6.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 7.25000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.17500E+01 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.37500E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 6.50000E+00 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 6.42771E-04 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 3.50000E-01 MeV : total inelastic scattering + + Nuclide 119 / 1657 : 44105.82c -- ruthenium 105 (Ru-105) + + Pointers : 929081 31793 + Primary type : Transport + Nuclide ZAI : 441050 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ru105.ACE + Atomic weight (AW) : 104.91124 + Atomic weight ratio (AWR) : 104.01000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.60E+04 seconds (4.44 hours) + Specific ingestion toxicity : 2.60E-10 Sv/Bq + Specific inhalation toxicity : 1.80E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 17 reaction channels + - 6 special reactions + - 9 transmutation reactions + - 6 transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 17 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.91010E+00 MeV Emin = 5.96700E+00 MeV frac = 1.00000E+00 Product nuclide = 44104.82c : (n,2n) + 3 MT = 17 Q = -1.48140E+01 MeV Emin = 1.49564E+01 MeV frac = 1.00000E+00 Product nuclide = 44103.82c : (n,3n) + 4 MT = 22 Q = -4.84390E+00 MeV Emin = 1.15000E+01 MeV frac = 1.00000E+00 Product nuclide = 421010 : (n,nalpha) + 5 MT = 28 Q = -1.07310E+01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 431040 : (n,np) + 6 MT = 51 Q = -2.06000E-02 MeV Emin = 2.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.07900E-01 MeV Emin = 1.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -1.59500E-01 MeV Emin = 1.43015E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -1.63800E-01 MeV Emin = 1.63202E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -2.08600E-01 MeV Emin = 2.09375E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -2.29500E-01 MeV Emin = 2.31250E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 91 Q = -2.29500E-01 MeV Emin = 2.31250E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 13 MT = 102 Q = 8.46575E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 44106.82c : (n,gamma) + 14 MT = 103 Q = -2.79920E+00 MeV Emin = 5.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 431050 : (n,p) + 15 MT = 104 Q = -8.50610E+00 MeV Emin = 1.15000E+01 MeV frac = 1.00000E+00 Product nuclide = 431040 : (n,d) + 16 MT = 105 Q = -8.20950E+00 MeV Emin = 1.17500E+01 MeV frac = 1.00000E+00 Product nuclide = 431030 : (n,t) + 17 MT = 107 Q = 3.27380E+00 MeV Emin = 3.25000E+00 MeV frac = 1.00000E+00 Product nuclide = 421020 : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = -4.84390E+00 MeV Emin = 1.15000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.07310E+01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -2.79920E+00 MeV Emin = 5.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -8.50610E+00 MeV Emin = 1.15000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -8.20950E+00 MeV Emin = 1.17500E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 107 Q = 3.27380E+00 MeV Emin = 3.25000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 5.50000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.15000E+01 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.17500E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 3.25000E+00 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 6.25000E-04 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 2.00000E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.91800E+00 MeV frac = 7.16433E-01 Product nuclide = 45105.82c : beta- + 2 RTYP = 1 Q = 1.78822E+00 MeV frac = 2.83567E-01 Product nuclide = 451051 : beta- + + Nuclide 120 / 1657 : 44106.82c -- ruthenium 106 (Ru-106) + + Pointers : 933504 31839 + Primary type : Transport + Nuclide ZAI : 441060 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ru106.ACE + Atomic weight (AW) : 105.90780 + Atomic weight ratio (AWR) : 104.99800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 3.21E+07 seconds (1.02 years) + Specific ingestion toxicity : 7.00E-09 Sv/Bq + Specific inhalation toxicity : 6.60E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 13 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 6 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 13 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -2.70000E-01 MeV Emin = 2.64427E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -7.11000E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -7.91000E-01 MeV Emin = 7.58151E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -9.89000E-01 MeV Emin = 9.61315E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 91 Q = -2.37740E+00 MeV Emin = 2.40004E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 7 MT = 102 Q = 5.48000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 441070 : (n,gamma) + 8 MT = 103 Q = -5.51850E+00 MeV Emin = 5.57106E+00 MeV frac = 1.00000E+00 Product nuclide = 431060 : (n,p) + 9 MT = 104 Q = -8.85420E+00 MeV Emin = 8.93853E+00 MeV frac = 1.00000E+00 Product nuclide = 431050 : (n,d) + 10 MT = 105 Q = -1.05070E+01 MeV Emin = 1.06071E+01 MeV frac = 1.00000E+00 Product nuclide = 431040 : (n,t) + 11 MT = 106 Q = -1.26890E+01 MeV Emin = 1.28099E+01 MeV frac = 1.00000E+00 Product nuclide = 421040 : (n,He-3) + 12 MT = 107 Q = -7.64950E-02 MeV Emin = 7.00000E-02 MeV frac = 1.00000E+00 Product nuclide = 421030 : (n,alpha) + 13 MT = 111 Q = -1.56940E+01 MeV Emin = 1.58435E+01 MeV frac = 1.00000E+00 Product nuclide = 421050 : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = -5.51850E+00 MeV Emin = 5.57106E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -8.85420E+00 MeV Emin = 8.93853E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -1.05070E+01 MeV Emin = 1.06071E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -1.26890E+01 MeV Emin = 1.28099E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = -7.64950E-02 MeV Emin = 7.00000E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -1.56940E+01 MeV Emin = 1.58435E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 5.57106E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.93853E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.06071E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.28099E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 7.00000E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 2.64427E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.94000E-02 MeV frac = 1.00000E+00 Product nuclide = 451060 : beta- + + Nuclide 121 / 1657 : 45103.82c -- rhodium 103 (Rh-103) + + Pointers : 977468 31471 + Primary type : Transport + Nuclide ZAI : 451030 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Rh103.ACE + Atomic weight (AW) : 102.90551 + Atomic weight ratio (AWR) : 102.02150 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 3.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 45 reaction channels + - 92 special reactions + - 25 transmutation reactions + - 29 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 45 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 11 Q = -2.00105E+01 MeV Emin = 2.02067E+01 MeV frac = 1.00000E+00 Product nuclide = self : (n,2nd) + 3 MT = 16 Q = -9.31828E+00 MeV Emin = 9.40962E+00 MeV frac = 1.00000E+00 Product nuclide = 451020 : (n,2n) + 4 MT = 17 Q = -1.67568E+01 MeV Emin = 1.69211E+01 MeV frac = 1.00000E+00 Product nuclide = 451010 : (n,3n) + 5 MT = 22 Q = -3.12388E+00 MeV Emin = 3.15450E+00 MeV frac = 1.00000E+00 Product nuclide = 43099.82c : (n,nalpha) + 6 MT = 24 Q = -1.20905E+01 MeV Emin = 1.22090E+01 MeV frac = 1.00000E+00 Product nuclide = 430980 : (n,2nalpha) + 7 MT = 25 Q = -1.93693E+01 MeV Emin = 1.95592E+01 MeV frac = 1.00000E+00 Product nuclide = 430970 : (n,3nalpha) + 8 MT = 28 Q = -6.21339E+00 MeV Emin = 6.27429E+00 MeV frac = 1.00000E+00 Product nuclide = 44102.82c : (n,np) + 9 MT = 29 Q = -6.08964E+00 MeV Emin = 6.14933E+00 MeV frac = 1.00000E+00 Product nuclide = 41095.82c : (n,n2alpha) + 10 MT = 32 Q = -1.32084E+01 MeV Emin = 1.33379E+01 MeV frac = 1.00000E+00 Product nuclide = 44101.82c : (n,nd) + 11 MT = 33 Q = -1.37533E+01 MeV Emin = 1.38881E+01 MeV frac = 1.00000E+00 Product nuclide = 44100.82c : (n,nt) + 12 MT = 34 Q = -1.69371E+01 MeV Emin = 1.71031E+01 MeV frac = 1.00000E+00 Product nuclide = 431000 : (n,nHe-3) + 13 MT = 37 Q = -2.66474E+01 MeV Emin = 2.69086E+01 MeV frac = 1.00000E+00 Product nuclide = cut: Rh-100 : (n,4n) + 14 MT = 41 Q = -1.54330E+01 MeV Emin = 1.55843E+01 MeV frac = 1.00000E+00 Product nuclide = 44101.82c : (n,2np) + 15 MT = 42 Q = -2.22351E+01 MeV Emin = 2.24531E+01 MeV frac = 1.00000E+00 Product nuclide = cut: Ru-100 : (n,3np) + 16 MT = 44 Q = -1.62641E+01 MeV Emin = 1.64235E+01 MeV frac = 1.00000E+00 Product nuclide = 431010 : (n,n2p) + 17 MT = 45 Q = -9.62414E+00 MeV Emin = 9.71848E+00 MeV frac = 1.00000E+00 Product nuclide = 42098.82c : (n,npalpha) + 18 MT = 51 Q = -3.97560E-02 MeV Emin = 4.00653E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 19 MT = 52 Q = -9.30410E-02 MeV Emin = 9.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 20 MT = 53 Q = -2.94980E-01 MeV Emin = 2.89855E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 21 MT = 54 Q = -3.57408E-01 MeV Emin = 3.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 22 MT = 55 Q = -5.36838E-01 MeV Emin = 5.40832E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 23 MT = 56 Q = -6.07450E-01 MeV Emin = 6.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 24 MT = 57 Q = -6.50085E-01 MeV Emin = 6.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 25 MT = 58 Q = -6.51798E-01 MeV Emin = 6.57322E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 26 MT = 59 Q = -6.57720E-01 MeV Emin = 6.61177E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 27 MT = 60 Q = -7.80500E-01 MeV Emin = 7.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 28 MT = 61 Q = -8.03070E-01 MeV Emin = 8.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 29 MT = 62 Q = -8.21460E-01 MeV Emin = 8.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 30 MT = 63 Q = -8.47580E-01 MeV Emin = 8.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 31 MT = 64 Q = -8.80470E-01 MeV Emin = 8.69550E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 32 MT = 65 Q = -9.20100E-01 MeV Emin = 9.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 33 MT = 91 Q = -9.20100E-01 MeV Emin = 9.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 34 MT = 102 Q = 6.99896E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 451040 : (n,gamma) + 35 MT = 103 Q = 1.89981E-02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 44103.82c : (n,p) + 36 MT = 104 Q = -3.98882E+00 MeV Emin = 4.02792E+00 MeV frac = 1.00000E+00 Product nuclide = 44102.82c : (n,d) + 37 MT = 105 Q = -6.95116E+00 MeV Emin = 7.01930E+00 MeV frac = 1.00000E+00 Product nuclide = 44101.82c : (n,t) + 38 MT = 106 Q = -8.54607E+00 MeV Emin = 8.62984E+00 MeV frac = 1.00000E+00 Product nuclide = 431010 : (n,He-3) + 39 MT = 107 Q = 3.64052E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 431000 : (n,alpha) + 40 MT = 108 Q = 8.03440E-01 MeV Emin = 1.09993E-04 MeV frac = 1.00000E+00 Product nuclide = 410960 : (n,2alpha) + 41 MT = 111 Q = -9.96130E+00 MeV Emin = 1.00589E+01 MeV frac = 1.00000E+00 Product nuclide = 431020 : (n,2p) + 42 MT = 112 Q = -3.69875E+00 MeV Emin = 3.73501E+00 MeV frac = 1.00000E+00 Product nuclide = 42099.82c : (n,palpha) + 43 MT = 115 Q = -1.40396E+01 MeV Emin = 1.41772E+01 MeV frac = 1.00000E+00 Product nuclide = 431010 : (n,pd) + 44 MT = 116 Q = -1.61733E+01 MeV Emin = 1.63319E+01 MeV frac = 1.00000E+00 Product nuclide = 431000 : (n,pt) + 45 MT = 117 Q = -7.39957E+00 MeV Emin = 7.47210E+00 MeV frac = 1.00000E+00 Product nuclide = 42098.82c : (n,dalpha) + + 29 additional transport branches: + + 1 MT = 22 Q = -3.12388E+00 MeV Emin = 3.15450E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 24 Q = -1.20905E+01 MeV Emin = 1.22090E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,2nalpha) + 3 MT = 25 Q = -1.93693E+01 MeV Emin = 1.95592E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,3nalpha) + 4 MT = 28 Q = -6.21339E+00 MeV Emin = 6.27429E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 5 MT = 29 Q = -6.08964E+00 MeV Emin = 6.14933E+00 MeV frac = 2.00000E+00 Product nuclide = 2004.82c : (n,n2alpha) + 6 MT = 32 Q = -1.32084E+01 MeV Emin = 1.33379E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 7 MT = 33 Q = -1.37533E+01 MeV Emin = 1.38881E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 8 MT = 34 Q = -1.69371E+01 MeV Emin = 1.71031E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,nHe-3) + 9 MT = 41 Q = -1.54330E+01 MeV Emin = 1.55843E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,2np) + 10 MT = 42 Q = -2.22351E+01 MeV Emin = 2.24531E+01 MeV frac = 1.00000E+00 Product nuclide = cut: H-1 : (n,3np) + 11 MT = 44 Q = -1.62641E+01 MeV Emin = 1.64235E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,n2p) + 12 MT = 45 Q = -9.62414E+00 MeV Emin = 9.71848E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,npalpha) + 13 MT = 45 Q = -9.62414E+00 MeV Emin = 9.71848E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,npalpha) + 14 MT = 102 Q = 6.99896E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 451041 : (n,gamma) + 15 MT = 103 Q = 1.89981E-02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 16 MT = 104 Q = -3.98882E+00 MeV Emin = 4.02792E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 17 MT = 105 Q = -6.95116E+00 MeV Emin = 7.01930E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 18 MT = 106 Q = -8.54607E+00 MeV Emin = 8.62984E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 19 MT = 107 Q = 3.64052E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 20 MT = 108 Q = 8.03440E-01 MeV Emin = 1.09993E-04 MeV frac = 2.00000E+00 Product nuclide = 2004.82c : (n,2alpha) + 21 MT = 111 Q = -9.96130E+00 MeV Emin = 1.00589E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + 22 MT = 112 Q = -3.69875E+00 MeV Emin = 3.73501E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,palpha) + 23 MT = 112 Q = -3.69875E+00 MeV Emin = 3.73501E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,palpha) + 24 MT = 115 Q = -1.40396E+01 MeV Emin = 1.41772E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,pd) + 25 MT = 115 Q = -1.40396E+01 MeV Emin = 1.41772E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,pd) + 26 MT = 116 Q = -1.61733E+01 MeV Emin = 1.63319E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,pt) + 27 MT = 116 Q = -1.61733E+01 MeV Emin = 1.63319E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,pt) + 28 MT = 117 Q = -7.39957E+00 MeV Emin = 7.47210E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,dalpha) + 29 MT = 117 Q = -7.39957E+00 MeV Emin = 7.47210E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,dalpha) + + 92 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 4.02792E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 7.01930E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 8.62984E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 600 Q = 1.89981E-02 MeV Emin = 1.00000E+00 MeV : (n,p) to ground state + 8 MT = 601 Q = 1.61881E-02 MeV Emin = 6.00000E-02 MeV : (n,p1) + 9 MT = 602 Q = -1.17081E-01 MeV Emin = 6.17979E-01 MeV : (n,p2) + 10 MT = 603 Q = -1.55262E-01 MeV Emin = 1.00000E+00 MeV : (n,p3) + 11 MT = 604 Q = -1.94562E-01 MeV Emin = 1.02500E+00 MeV : (n,p4) + 12 MT = 605 Q = -2.19202E-01 MeV Emin = 1.10000E+00 MeV : (n,p5) + 13 MT = 606 Q = -2.78102E-01 MeV Emin = 1.10000E+00 MeV : (n,p6) + 14 MT = 607 Q = -2.79102E-01 MeV Emin = 1.20000E+00 MeV : (n,p7) + 15 MT = 608 Q = -3.27382E-01 MeV Emin = 1.20000E+00 MeV : (n,p8) + 16 MT = 609 Q = -3.85152E-01 MeV Emin = 1.20000E+00 MeV : (n,p9) + 17 MT = 610 Q = -3.87082E-01 MeV Emin = 1.20000E+00 MeV : (n,p10) + 18 MT = 611 Q = -4.13062E-01 MeV Emin = 1.30000E+00 MeV : (n,p11) + 19 MT = 612 Q = -4.82152E-01 MeV Emin = 1.40000E+00 MeV : (n,p12) + 20 MT = 613 Q = -5.16402E-01 MeV Emin = 1.40000E+00 MeV : (n,p13) + 21 MT = 614 Q = -5.29212E-01 MeV Emin = 1.40000E+00 MeV : (n,p14) + 22 MT = 615 Q = -5.35582E-01 MeV Emin = 1.60000E+00 MeV : (n,p15) + 23 MT = 649 Q = -5.35582E-01 MeV Emin = 5.37616E-01 MeV : (n,p) to continuum + 24 MT = 650 Q = -3.98882E+00 MeV Emin = 4.02792E+00 MeV : (n,d) to ground state + 25 MT = 651 Q = -4.46390E+00 MeV Emin = 4.50766E+00 MeV : (n,d1) + 26 MT = 652 Q = -4.93251E+00 MeV Emin = 4.98086E+00 MeV : (n,d2) + 27 MT = 653 Q = -5.09197E+00 MeV Emin = 5.14188E+00 MeV : (n,d3) + 28 MT = 654 Q = -5.09518E+00 MeV Emin = 5.14512E+00 MeV : (n,d4) + 29 MT = 655 Q = -5.51049E+00 MeV Emin = 5.56450E+00 MeV : (n,d5) + 30 MT = 656 Q = -5.56938E+00 MeV Emin = 5.62397E+00 MeV : (n,d6) + 31 MT = 657 Q = -5.59172E+00 MeV Emin = 5.64653E+00 MeV : (n,d7) + 32 MT = 658 Q = -5.78749E+00 MeV Emin = 5.84422E+00 MeV : (n,d8) + 33 MT = 659 Q = -5.82592E+00 MeV Emin = 5.88303E+00 MeV : (n,d9) + 34 MT = 660 Q = -5.86205E+00 MeV Emin = 5.91951E+00 MeV : (n,d10) + 35 MT = 661 Q = -5.95748E+00 MeV Emin = 6.01588E+00 MeV : (n,d11) + 36 MT = 662 Q = -6.02572E+00 MeV Emin = 6.08478E+00 MeV : (n,d12) + 37 MT = 663 Q = -6.03302E+00 MeV Emin = 6.09216E+00 MeV : (n,d13) + 38 MT = 664 Q = -6.17882E+00 MeV Emin = 6.23939E+00 MeV : (n,d14) + 39 MT = 665 Q = -6.20799E+00 MeV Emin = 6.26884E+00 MeV : (n,d15) + 40 MT = 699 Q = -6.20799E+00 MeV Emin = 6.26884E+00 MeV : (n,d) to continuum + 41 MT = 700 Q = -6.95116E+00 MeV Emin = 7.01930E+00 MeV : (n,t) to ground state + 42 MT = 701 Q = -7.07839E+00 MeV Emin = 7.14777E+00 MeV : (n,t1) + 43 MT = 702 Q = -7.25801E+00 MeV Emin = 7.32915E+00 MeV : (n,t2) + 44 MT = 703 Q = -7.26249E+00 MeV Emin = 7.33368E+00 MeV : (n,t3) + 45 MT = 704 Q = -7.27596E+00 MeV Emin = 7.34728E+00 MeV : (n,t4) + 46 MT = 705 Q = -7.29516E+00 MeV Emin = 7.36667E+00 MeV : (n,t5) + 47 MT = 706 Q = -7.37346E+00 MeV Emin = 7.44573E+00 MeV : (n,t6) + 48 MT = 707 Q = -7.47866E+00 MeV Emin = 7.55197E+00 MeV : (n,t7) + 49 MT = 708 Q = -7.48616E+00 MeV Emin = 7.55954E+00 MeV : (n,t8) + 50 MT = 709 Q = -7.49624E+00 MeV Emin = 7.56972E+00 MeV : (n,t9) + 51 MT = 710 Q = -7.54946E+00 MeV Emin = 7.62346E+00 MeV : (n,t10) + 52 MT = 711 Q = -7.56746E+00 MeV Emin = 7.64164E+00 MeV : (n,t11) + 53 MT = 712 Q = -7.57416E+00 MeV Emin = 7.64840E+00 MeV : (n,t12) + 54 MT = 713 Q = -7.57516E+00 MeV Emin = 7.64941E+00 MeV : (n,t13) + 55 MT = 714 Q = -7.63516E+00 MeV Emin = 7.71000E+00 MeV : (n,t14) + 56 MT = 715 Q = -7.66916E+00 MeV Emin = 7.74433E+00 MeV : (n,t15) + 57 MT = 749 Q = -7.66916E+00 MeV Emin = 7.74433E+00 MeV : (n,t) to continuum + 58 MT = 750 Q = -8.54607E+00 MeV Emin = 8.62984E+00 MeV : (n,He-3) to ground state + 59 MT = 751 Q = -8.55539E+00 MeV Emin = 8.63925E+00 MeV : (n,He-3_1) + 60 MT = 752 Q = -8.56167E+00 MeV Emin = 8.64559E+00 MeV : (n,He-3_2) + 61 MT = 753 Q = -8.75360E+00 MeV Emin = 8.83940E+00 MeV : (n,He-3_3) + 62 MT = 754 Q = -8.83452E+00 MeV Emin = 8.92112E+00 MeV : (n,He-3_4) + 63 MT = 755 Q = -8.94097E+00 MeV Emin = 9.02861E+00 MeV : (n,He-3_5) + 64 MT = 756 Q = -9.04652E+00 MeV Emin = 9.13519E+00 MeV : (n,He-3_6) + 65 MT = 757 Q = -9.06133E+00 MeV Emin = 9.15015E+00 MeV : (n,He-3_7) + 66 MT = 758 Q = -9.06667E+00 MeV Emin = 9.15554E+00 MeV : (n,He-3_8) + 67 MT = 759 Q = -9.07957E+00 MeV Emin = 9.16857E+00 MeV : (n,He-3_9) + 68 MT = 760 Q = -9.13597E+00 MeV Emin = 9.22552E+00 MeV : (n,He-3_10) + 69 MT = 761 Q = -9.15257E+00 MeV Emin = 9.24228E+00 MeV : (n,He-3_11) + 70 MT = 762 Q = -9.16232E+00 MeV Emin = 9.25213E+00 MeV : (n,He-3_12) + 71 MT = 763 Q = -9.16487E+00 MeV Emin = 9.25470E+00 MeV : (n,He-3_13) + 72 MT = 764 Q = -9.16817E+00 MeV Emin = 9.25804E+00 MeV : (n,He-3_14) + 73 MT = 765 Q = -9.18827E+00 MeV Emin = 9.27833E+00 MeV : (n,He-3_15) + 74 MT = 799 Q = -9.18827E+00 MeV Emin = 9.27833E+00 MeV : (n,He-3) to continuum + 75 MT = 800 Q = 3.64052E+00 MeV Emin = 2.10675E-01 MeV : (n,alpha) to ground state + 76 MT = 801 Q = 3.46837E+00 MeV Emin = 3.40296E-01 MeV : (n,a1) + 77 MT = 802 Q = 3.43985E+00 MeV Emin = 1.05000E+00 MeV : (n,a2) + 78 MT = 803 Q = 3.41705E+00 MeV Emin = 1.10000E+00 MeV : (n,a3) + 79 MT = 804 Q = 3.39656E+00 MeV Emin = 1.10000E+00 MeV : (n,a4) + 80 MT = 805 Q = 3.37696E+00 MeV Emin = 1.10000E+00 MeV : (n,a5) + 81 MT = 806 Q = 3.35299E+00 MeV Emin = 1.10000E+00 MeV : (n,a6) + 82 MT = 807 Q = 3.34559E+00 MeV Emin = 1.60000E+00 MeV : (n,a7) + 83 MT = 808 Q = 3.34082E+00 MeV Emin = 1.30000E+00 MeV : (n,a8) + 84 MT = 809 Q = 3.32103E+00 MeV Emin = 1.10000E+00 MeV : (n,a9) + 85 MT = 810 Q = 3.30532E+00 MeV Emin = 1.60000E+00 MeV : (n,a10) + 86 MT = 811 Q = 3.29955E+00 MeV Emin = 1.60000E+00 MeV : (n,a11) + 87 MT = 812 Q = 3.28500E+00 MeV Emin = 1.20000E+00 MeV : (n,a12) + 88 MT = 813 Q = 3.23989E+00 MeV Emin = 1.20000E+00 MeV : (n,a13) + 89 MT = 814 Q = 3.21616E+00 MeV Emin = 1.30000E+00 MeV : (n,a14) + 90 MT = 815 Q = 3.20012E+00 MeV Emin = 1.80000E+00 MeV : (n,a15) + 91 MT = 849 Q = 3.20012E+00 MeV Emin = 1.00000E-11 MeV : (n,alpha) to continuum + 92 MT = 4 Q = 0.00000E+00 MeV Emin = 4.00653E-02 MeV : total inelastic scattering + + Nuclide 122 / 1657 : 45105.82c -- rhodium 105 (Rh-105) + + Pointers : 992585 31517 + Primary type : Transport + Nuclide ZAI : 451050 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Rh105.ACE + Atomic weight (AW) : 104.90116 + Atomic weight ratio (AWR) : 104.00000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.27E+05 seconds (1.47 days) + Specific ingestion toxicity : 3.70E-10 Sv/Bq + Specific inhalation toxicity : 3.50E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 19 reaction channels + - 7 special reactions + - 10 transmutation reactions + - 8 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 19 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.96820E+00 MeV Emin = 9.05443E+00 MeV frac = 1.00000E+00 Product nuclide = 451040 : (n,2n) + 3 MT = 17 Q = -1.59670E+01 MeV Emin = 1.61210E+01 MeV frac = 1.00000E+00 Product nuclide = 45103.82c : (n,3n) + 4 MT = 22 Q = -3.93660E+00 MeV Emin = 1.05000E+01 MeV frac = 1.00000E+00 Product nuclide = 431010 : (n,nalpha) + 5 MT = 28 Q = -7.04480E+00 MeV Emin = 9.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 44104.82c : (n,np) + 6 MT = 51 Q = -1.29800E-01 MeV Emin = 1.25315E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.49200E-01 MeV Emin = 1.37973E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -3.92700E-01 MeV Emin = 3.96002E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -4.55600E-01 MeV Emin = 4.56699E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -4.69400E-01 MeV Emin = 4.66946E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -4.74000E-01 MeV Emin = 4.77687E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -4.99300E-01 MeV Emin = 4.89007E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 91 Q = -4.99300E-01 MeV Emin = 4.89007E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 14 MT = 102 Q = 6.58716E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 451060 : (n,gamma) + 15 MT = 103 Q = -1.13470E+00 MeV Emin = 3.40000E+00 MeV frac = 1.00000E+00 Product nuclide = 44105.82c : (n,p) + 16 MT = 104 Q = -4.82030E+00 MeV Emin = 8.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 44104.82c : (n,d) + 17 MT = 105 Q = -7.46710E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 44103.82c : (n,t) + 18 MT = 106 Q = -1.01080E+01 MeV Emin = 1.95000E+01 MeV frac = 1.00000E+00 Product nuclide = 431030 : (n,He-3) + 19 MT = 107 Q = 2.36660E+00 MeV Emin = 4.20000E+00 MeV frac = 1.00000E+00 Product nuclide = 431020 : (n,alpha) + + 8 additional transport branches: + + 1 MT = 22 Q = -3.93660E+00 MeV Emin = 1.05000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -7.04480E+00 MeV Emin = 9.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 102 Q = 6.58716E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 451061 : (n,gamma) + 4 MT = 103 Q = -1.13470E+00 MeV Emin = 3.40000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -4.82030E+00 MeV Emin = 8.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -7.46710E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 106 Q = -1.01080E+01 MeV Emin = 1.95000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 8 MT = 107 Q = 2.36660E+00 MeV Emin = 4.20000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.40000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.50000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.10000E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.95000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.20000E+00 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 6.30000E-04 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 1.25315E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.67200E-01 MeV frac = 1.00000E+00 Product nuclide = 46105.82c : beta- + + Nuclide 123 / 1657 : 46105.82c -- palladium 105 (Pd-105) + + Pointers : 1036342 29953 + Primary type : Transport + Nuclide ZAI : 461050 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Pd105.ACE + Atomic weight (AW) : 104.90519 + Atomic weight ratio (AWR) : 104.00400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 27 reaction channels + - 52 special reactions + - 9 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 27 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.09400E+00 MeV Emin = 7.16221E+00 MeV frac = 1.00000E+00 Product nuclide = 461040 : (n,2n) + 3 MT = 17 Q = -1.70770E+01 MeV Emin = 1.72412E+01 MeV frac = 1.00000E+00 Product nuclide = 461030 : (n,3n) + 4 MT = 22 Q = -2.88900E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 44101.82c : (n,nalpha) + 5 MT = 24 Q = -9.69100E+00 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 44100.82c : (n,2nalpha) + 6 MT = 28 Q = -8.75300E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 451040 : (n,np) + 7 MT = 41 Q = -1.57520E+01 MeV Emin = 1.70000E+01 MeV frac = 1.00000E+00 Product nuclide = 45103.82c : (n,2np) + 8 MT = 51 Q = -2.80510E-01 MeV Emin = 2.83030E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -3.06250E-01 MeV Emin = 3.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -3.19220E-01 MeV Emin = 3.15742E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -3.44510E-01 MeV Emin = 3.35056E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -4.42380E-01 MeV Emin = 4.46067E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -4.47000E-01 MeV Emin = 4.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -4.89140E-01 MeV Emin = 4.72571E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -5.35000E-01 MeV Emin = 5.16994E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -5.60750E-01 MeV Emin = 5.53143E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -6.44530E-01 MeV Emin = 6.25363E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -6.50700E-01 MeV Emin = 6.53842E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 62 Q = -6.73170E-01 MeV Emin = 6.68451E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 20 MT = 63 Q = -6.96660E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 21 MT = 64 Q = -7.27220E-01 MeV Emin = 7.18785E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 22 MT = 65 Q = -7.81940E-01 MeV Emin = 7.61835E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 23 MT = 66 Q = -7.87000E-01 MeV Emin = 7.92013E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 24 MT = 91 Q = -4.41257E-01 MeV Emin = 3.96661E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 25 MT = 102 Q = 9.56097E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 46106.82c : (n,gamma) + 26 MT = 103 Q = 0.00000E+00 MeV Emin = 9.50000E-01 MeV frac = 1.00000E+00 Product nuclide = 45105.82c : (n,p) + 27 MT = 107 Q = 0.00000E+00 MeV Emin = 1.80000E-01 MeV frac = 1.00000E+00 Product nuclide = 44102.82c : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = -2.88900E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 24 Q = -9.69100E+00 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,2nalpha) + 3 MT = 28 Q = -8.75300E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 4 MT = 41 Q = -1.57520E+01 MeV Emin = 1.70000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,2np) + 5 MT = 103 Q = 0.00000E+00 MeV Emin = 9.50000E-01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 107 Q = 0.00000E+00 MeV Emin = 1.80000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 52 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 9.50000E-01 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 1.80000E-01 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 6.05044E-04 MeV : damage-energy production + 4 MT = 600 Q = 2.15000E-01 MeV Emin = 9.50000E-01 MeV : (n,p) to ground state + 5 MT = 601 Q = 8.52200E-02 MeV Emin = 9.50000E-01 MeV : (n,p1) + 6 MT = 602 Q = 6.58100E-02 MeV Emin = 9.50000E-01 MeV : (n,p2) + 7 MT = 603 Q = -1.77650E-01 MeV Emin = 9.50000E-01 MeV : (n,p3) + 8 MT = 604 Q = -2.40610E-01 MeV Emin = 9.50000E-01 MeV : (n,p4) + 9 MT = 605 Q = -2.54380E-01 MeV Emin = 9.50000E-01 MeV : (n,p5) + 10 MT = 606 Q = -2.59000E-01 MeV Emin = 9.50000E-01 MeV : (n,p6) + 11 MT = 607 Q = -2.84310E-01 MeV Emin = 9.50000E-01 MeV : (n,p7) + 12 MT = 608 Q = -3.09000E-01 MeV Emin = 9.50000E-01 MeV : (n,p8) + 13 MT = 609 Q = -4.23680E-01 MeV Emin = 9.50000E-01 MeV : (n,p9) + 14 MT = 610 Q = -5.09330E-01 MeV Emin = 1.50481E+00 MeV : (n,p10) + 15 MT = 611 Q = -5.47110E-01 MeV Emin = 1.50481E+00 MeV : (n,p11) + 16 MT = 612 Q = -5.68000E-01 MeV Emin = 1.50481E+00 MeV : (n,p12) + 17 MT = 613 Q = -5.70930E-01 MeV Emin = 1.50481E+00 MeV : (n,p13) + 18 MT = 614 Q = -5.90940E-01 MeV Emin = 1.50481E+00 MeV : (n,p14) + 19 MT = 615 Q = -6.02000E-01 MeV Emin = 1.50481E+00 MeV : (n,p15) + 20 MT = 616 Q = -6.15000E-01 MeV Emin = 1.50481E+00 MeV : (n,p16) + 21 MT = 617 Q = -6.27610E-01 MeV Emin = 1.50481E+00 MeV : (n,p17) + 22 MT = 618 Q = -6.51000E-01 MeV Emin = 1.50481E+00 MeV : (n,p18) + 23 MT = 619 Q = -6.83000E-01 MeV Emin = 1.50481E+00 MeV : (n,p19) + 24 MT = 620 Q = -7.09000E-01 MeV Emin = 1.50481E+00 MeV : (n,p20) + 25 MT = 621 Q = -7.54450E-01 MeV Emin = 1.50481E+00 MeV : (n,p21) + 26 MT = 622 Q = -7.61000E-01 MeV Emin = 1.50481E+00 MeV : (n,p22) + 27 MT = 623 Q = -8.04000E-01 MeV Emin = 1.50481E+00 MeV : (n,p23) + 28 MT = 624 Q = -8.09000E-01 MeV Emin = 1.50481E+00 MeV : (n,p24) + 29 MT = 625 Q = -9.32000E-01 MeV Emin = 1.50481E+00 MeV : (n,p25) + 30 MT = 626 Q = -9.75000E-01 MeV Emin = 1.50481E+00 MeV : (n,p26) + 31 MT = 627 Q = -1.00000E+00 MeV Emin = 1.00962E+00 MeV : (n,p27) + 32 MT = 649 Q = -1.00000E+00 MeV Emin = 1.00962E+00 MeV : (n,p) to continuum + 33 MT = 800 Q = 6.33000E+00 MeV Emin = 1.80000E-01 MeV : (n,alpha) to ground state + 34 MT = 801 Q = 5.85492E+00 MeV Emin = 1.80000E-01 MeV : (n,a1) + 35 MT = 802 Q = 5.38631E+00 MeV Emin = 1.80000E-01 MeV : (n,a2) + 36 MT = 803 Q = 5.22685E+00 MeV Emin = 1.80000E-01 MeV : (n,a3) + 37 MT = 804 Q = 5.22364E+00 MeV Emin = 1.80000E-01 MeV : (n,a4) + 38 MT = 805 Q = 4.80833E+00 MeV Emin = 1.80000E-01 MeV : (n,a5) + 39 MT = 806 Q = 4.74944E+00 MeV Emin = 1.80000E-01 MeV : (n,a6) + 40 MT = 807 Q = 4.72710E+00 MeV Emin = 1.80000E-01 MeV : (n,a7) + 41 MT = 808 Q = 4.53133E+00 MeV Emin = 1.80000E-01 MeV : (n,a8) + 42 MT = 809 Q = 4.49290E+00 MeV Emin = 1.80000E-01 MeV : (n,a9) + 43 MT = 810 Q = 4.45677E+00 MeV Emin = 1.80000E-01 MeV : (n,a10) + 44 MT = 811 Q = 4.36134E+00 MeV Emin = 1.80000E-01 MeV : (n,a11) + 45 MT = 812 Q = 4.29310E+00 MeV Emin = 2.00000E-01 MeV : (n,a12) + 46 MT = 813 Q = 4.28580E+00 MeV Emin = 2.91604E-01 MeV : (n,a13) + 47 MT = 814 Q = 4.14000E+00 MeV Emin = 4.48317E-01 MeV : (n,a14) + 48 MT = 815 Q = 4.11083E+00 MeV Emin = 4.48317E-01 MeV : (n,a15) + 49 MT = 816 Q = 4.08700E+00 MeV Emin = 4.48317E-01 MeV : (n,a16) + 50 MT = 817 Q = 4.06876E+00 MeV Emin = 4.48317E-01 MeV : (n,a17) + 51 MT = 849 Q = 4.06876E+00 MeV Emin = 1.80000E-01 MeV : (n,alpha) to continuum + 52 MT = 4 Q = 0.00000E+00 MeV Emin = 2.83030E-01 MeV : total inelastic scattering + + Nuclide 124 / 1657 : 46106.82c -- palladium 106 (Pd-106) + + Pointers : 1042658 29999 + Primary type : Transport + Nuclide ZAI : 461060 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Pd106.ACE + Atomic weight (AW) : 105.90347 + Atomic weight ratio (AWR) : 104.99370 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 3.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 38 reaction channels + - 50 special reactions + - 11 transmutation reactions + - 9 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 38 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -9.56238E+00 MeV Emin = 9.65346E+00 MeV frac = 1.00000E+00 Product nuclide = 46105.82c : (n,2n) + 3 MT = 17 Q = -1.66568E+01 MeV Emin = 1.68155E+01 MeV frac = 1.00000E+00 Product nuclide = 461040 : (n,3n) + 4 MT = 22 Q = -3.23251E+00 MeV Emin = 3.26330E+00 MeV frac = 1.00000E+00 Product nuclide = 44102.82c : (n,nalpha) + 5 MT = 24 Q = -1.24529E+01 MeV Emin = 1.25715E+01 MeV frac = 1.00000E+00 Product nuclide = 44101.82c : (n,2nalpha) + 6 MT = 28 Q = -9.34703E+00 MeV Emin = 9.43606E+00 MeV frac = 1.00000E+00 Product nuclide = 45105.82c : (n,np) + 7 MT = 32 Q = -1.60908E+01 MeV Emin = 1.62441E+01 MeV frac = 1.00000E+00 Product nuclide = 451040 : (n,nd) + 8 MT = 37 Q = -2.66501E+01 MeV Emin = 2.69040E+01 MeV frac = 1.00000E+00 Product nuclide = cut: Pd-103 : (n,4n) + 9 MT = 41 Q = -1.83154E+01 MeV Emin = 1.84899E+01 MeV frac = 1.00000E+00 Product nuclide = 451040 : (n,2np) + 10 MT = 51 Q = -5.11851E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 11 MT = 52 Q = -1.12801E+00 MeV Emin = 1.10000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 12 MT = 53 Q = -1.13377E+00 MeV Emin = 1.14166E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 13 MT = 54 Q = -1.22925E+00 MeV Emin = 1.20000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 14 MT = 55 Q = -1.55765E+00 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 15 MT = 56 Q = -1.56225E+00 MeV Emin = 1.57481E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 16 MT = 57 Q = -1.70639E+00 MeV Emin = 1.70000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 17 MT = 58 Q = -1.90947E+00 MeV Emin = 1.90000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 18 MT = 59 Q = -1.93228E+00 MeV Emin = 1.93917E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 19 MT = 60 Q = -2.00149E+00 MeV Emin = 2.02055E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 20 MT = 61 Q = -2.07629E+00 MeV Emin = 2.09607E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 21 MT = 62 Q = -2.07663E+00 MeV Emin = 2.09641E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 22 MT = 63 Q = -2.08386E+00 MeV Emin = 2.10371E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 23 MT = 64 Q = -2.24249E+00 MeV Emin = 2.26385E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 24 MT = 65 Q = -2.27811E+00 MeV Emin = 2.29981E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 25 MT = 66 Q = -2.28294E+00 MeV Emin = 2.30469E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 26 MT = 67 Q = -2.30556E+00 MeV Emin = 2.32752E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 27 MT = 68 Q = -2.30881E+00 MeV Emin = 2.33080E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 28 MT = 69 Q = -2.35081E+00 MeV Emin = 2.37320E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 29 MT = 70 Q = -2.36596E+00 MeV Emin = 2.38849E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 30 MT = 71 Q = -2.39750E+00 MeV Emin = 2.42034E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 31 MT = 72 Q = -2.40140E+00 MeV Emin = 2.42427E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 32 MT = 73 Q = -2.43910E+00 MeV Emin = 2.46233E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 33 MT = 74 Q = -2.47270E+00 MeV Emin = 2.49625E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 34 MT = 91 Q = -2.47270E+00 MeV Emin = 2.49625E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 35 MT = 102 Q = 6.53644E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 46107.82c : (n,gamma) + 36 MT = 103 Q = -2.75965E+00 MeV Emin = 2.78593E+00 MeV frac = 1.00000E+00 Product nuclide = 451060 : (n,p) + 37 MT = 104 Q = -7.12244E+00 MeV Emin = 7.19028E+00 MeV frac = 1.00000E+00 Product nuclide = 45105.82c : (n,d) + 38 MT = 107 Q = 2.99987E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 44103.82c : (n,alpha) + + 9 additional transport branches: + + 1 MT = 22 Q = -3.23251E+00 MeV Emin = 3.26330E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 24 Q = -1.24529E+01 MeV Emin = 1.25715E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,2nalpha) + 3 MT = 28 Q = -9.34703E+00 MeV Emin = 9.43606E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 4 MT = 32 Q = -1.60908E+01 MeV Emin = 1.62441E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 5 MT = 41 Q = -1.83154E+01 MeV Emin = 1.84899E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,2np) + 6 MT = 102 Q = 6.53644E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 461071 : (n,gamma) + 7 MT = 103 Q = -2.75965E+00 MeV Emin = 2.78593E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 8 MT = 104 Q = -7.12244E+00 MeV Emin = 7.19028E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 9 MT = 107 Q = 2.99987E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 50 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.78593E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.19028E+00 MeV : total deuteron production + 3 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 4 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 5 MT = 600 Q = -2.75965E+00 MeV Emin = 2.78593E+00 MeV : (n,p) to ground state + 6 MT = 601 Q = -2.80159E+00 MeV Emin = 2.82827E+00 MeV : (n,p1) + 7 MT = 649 Q = -2.80159E+00 MeV Emin = 2.82827E+00 MeV : (n,p) to continuum + 8 MT = 650 Q = -7.12244E+00 MeV Emin = 7.19028E+00 MeV : (n,d) to ground state + 9 MT = 651 Q = -7.25223E+00 MeV Emin = 7.32130E+00 MeV : (n,d1) + 10 MT = 652 Q = -7.27163E+00 MeV Emin = 7.34089E+00 MeV : (n,d2) + 11 MT = 653 Q = -7.51509E+00 MeV Emin = 7.58667E+00 MeV : (n,d3) + 12 MT = 654 Q = -7.57805E+00 MeV Emin = 7.65023E+00 MeV : (n,d4) + 13 MT = 655 Q = -7.59182E+00 MeV Emin = 7.66413E+00 MeV : (n,d5) + 14 MT = 656 Q = -7.59644E+00 MeV Emin = 7.66880E+00 MeV : (n,d6) + 15 MT = 657 Q = -7.62175E+00 MeV Emin = 7.69435E+00 MeV : (n,d7) + 16 MT = 658 Q = -7.64644E+00 MeV Emin = 7.71927E+00 MeV : (n,d8) + 17 MT = 659 Q = -7.76112E+00 MeV Emin = 7.83505E+00 MeV : (n,d9) + 18 MT = 660 Q = -7.84677E+00 MeV Emin = 7.92151E+00 MeV : (n,d10) + 19 MT = 661 Q = -7.88455E+00 MeV Emin = 7.95965E+00 MeV : (n,d11) + 20 MT = 662 Q = -7.90544E+00 MeV Emin = 7.98074E+00 MeV : (n,d12) + 21 MT = 663 Q = -7.90837E+00 MeV Emin = 7.98370E+00 MeV : (n,d13) + 22 MT = 664 Q = -7.92838E+00 MeV Emin = 8.00390E+00 MeV : (n,d14) + 23 MT = 665 Q = -7.93944E+00 MeV Emin = 8.01506E+00 MeV : (n,d15) + 24 MT = 666 Q = -7.95244E+00 MeV Emin = 8.02819E+00 MeV : (n,d16) + 25 MT = 667 Q = -7.96505E+00 MeV Emin = 8.04092E+00 MeV : (n,d17) + 26 MT = 668 Q = -7.98844E+00 MeV Emin = 8.06453E+00 MeV : (n,d18) + 27 MT = 669 Q = -8.02044E+00 MeV Emin = 8.09684E+00 MeV : (n,d19) + 28 MT = 699 Q = -8.02044E+00 MeV Emin = 8.09684E+00 MeV : (n,d) to continuum + 29 MT = 800 Q = 2.99987E+00 MeV Emin = 1.00000E-11 MeV : (n,alpha) to ground state + 30 MT = 801 Q = 2.99706E+00 MeV Emin = 1.00000E-11 MeV : (n,a1) + 31 MT = 802 Q = 2.86379E+00 MeV Emin = 1.00000E-11 MeV : (n,a2) + 32 MT = 803 Q = 2.82561E+00 MeV Emin = 1.00000E-11 MeV : (n,a3) + 33 MT = 804 Q = 2.78631E+00 MeV Emin = 1.00000E-11 MeV : (n,a4) + 34 MT = 805 Q = 2.76167E+00 MeV Emin = 1.00000E-11 MeV : (n,a5) + 35 MT = 806 Q = 2.70239E+00 MeV Emin = 1.00000E-11 MeV : (n,a6) + 36 MT = 807 Q = 2.65349E+00 MeV Emin = 1.00000E-11 MeV : (n,a7) + 37 MT = 808 Q = 2.59572E+00 MeV Emin = 1.00000E-11 MeV : (n,a8) + 38 MT = 809 Q = 2.59379E+00 MeV Emin = 1.00000E-11 MeV : (n,a9) + 39 MT = 810 Q = 2.56781E+00 MeV Emin = 1.00000E-11 MeV : (n,a10) + 40 MT = 811 Q = 2.49872E+00 MeV Emin = 1.00000E-11 MeV : (n,a11) + 41 MT = 812 Q = 2.46447E+00 MeV Emin = 1.00000E-11 MeV : (n,a12) + 42 MT = 813 Q = 2.45166E+00 MeV Emin = 1.00000E-11 MeV : (n,a13) + 43 MT = 814 Q = 2.44529E+00 MeV Emin = 2.87734E-08 MeV : (n,a14) + 44 MT = 815 Q = 2.44217E+00 MeV Emin = 2.19875E-08 MeV : (n,a15) + 45 MT = 816 Q = 2.43700E+00 MeV Emin = 1.93750E-08 MeV : (n,a16) + 46 MT = 817 Q = 2.43170E+00 MeV Emin = 1.81250E-08 MeV : (n,a17) + 47 MT = 818 Q = 2.40790E+00 MeV Emin = 1.81250E-08 MeV : (n,a18) + 48 MT = 819 Q = 2.37787E+00 MeV Emin = 2.13250E-08 MeV : (n,a19) + 49 MT = 849 Q = 2.37787E+00 MeV Emin = 1.00000E-11 MeV : (n,alpha) to continuum + 50 MT = 4 Q = 0.00000E+00 MeV Emin = 5.00000E-01 MeV : total inelastic scattering + + Nuclide 125 / 1657 : 46107.82c -- palladium 107 (Pd-107) + + Pointers : 1049869 30045 + Primary type : Transport + Nuclide ZAI : 461070 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Pd107.ACE + Atomic weight (AW) : 106.90537 + Atomic weight ratio (AWR) : 105.98700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.05E+14 seconds (6.5 million years) + Specific ingestion toxicity : 3.70E-11 Sv/Bq + Specific inhalation toxicity : 5.90E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 32 reaction channels + - 6 special reactions + - 10 transmutation reactions + - 7 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 32 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.53410E+00 MeV Emin = 6.59576E+00 MeV frac = 1.00000E+00 Product nuclide = 46106.82c : (n,2n) + 3 MT = 17 Q = -1.61012E+01 MeV Emin = 1.62531E+01 MeV frac = 1.00000E+00 Product nuclide = 46105.82c : (n,3n) + 4 MT = 22 Q = -3.53149E+00 MeV Emin = 3.56482E+00 MeV frac = 1.00000E+00 Product nuclide = 44103.82c : (n,nalpha) + 5 MT = 28 Q = -9.29263E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 451060 : (n,np) + 6 MT = 32 Q = -1.35756E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 45105.82c : (n,nd) + 7 MT = 51 Q = -1.15700E-01 MeV Emin = 1.09151E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 8 MT = 52 Q = -2.14000E-01 MeV Emin = 2.08010E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 9 MT = 53 Q = -3.02800E-01 MeV Emin = 3.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 10 MT = 54 Q = -3.12200E-01 MeV Emin = 3.11588E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 11 MT = 55 Q = -3.48200E-01 MeV Emin = 3.42968E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 12 MT = 56 Q = -3.65999E-01 MeV Emin = 3.65523E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 13 MT = 57 Q = -3.81899E-01 MeV Emin = 3.85017E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 14 MT = 58 Q = -3.92399E-01 MeV Emin = 3.95186E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 15 MT = 59 Q = -4.11999E-01 MeV Emin = 4.11559E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 16 MT = 60 Q = -4.71199E-01 MeV Emin = 4.68410E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 17 MT = 61 Q = -5.67699E-01 MeV Emin = 5.54792E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 18 MT = 62 Q = -6.70099E-01 MeV Emin = 6.63905E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 19 MT = 63 Q = -6.84999E-01 MeV Emin = 6.85823E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 20 MT = 64 Q = -6.97999E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 21 MT = 65 Q = -7.58999E-01 MeV Emin = 7.51730E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 22 MT = 66 Q = -7.80999E-01 MeV Emin = 7.80041E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 23 MT = 67 Q = -8.05999E-01 MeV Emin = 8.06802E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 24 MT = 68 Q = -8.08999E-01 MeV Emin = 8.15624E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 25 MT = 69 Q = -8.88999E-01 MeV Emin = 8.77199E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 26 MT = 70 Q = -1.02300E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 27 MT = 91 Q = -1.03000E+00 MeV Emin = 1.03619E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 28 MT = 102 Q = 9.22803E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 46108.82c : (n,gamma) + 29 MT = 103 Q = -7.28534E-01 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 451070 : (n,p) + 30 MT = 104 Q = -6.98251E+00 MeV Emin = 7.46020E+00 MeV frac = 1.00000E+00 Product nuclide = 451060 : (n,d) + 31 MT = 105 Q = -7.39046E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 45105.82c : (n,t) + 32 MT = 107 Q = 5.38220E+00 MeV Emin = 9.98893E-02 MeV frac = 1.00000E+00 Product nuclide = 44104.82c : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -3.53149E+00 MeV Emin = 3.56482E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -9.29263E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.35756E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 103 Q = -7.28534E-01 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -6.98251E+00 MeV Emin = 7.46020E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -7.39046E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 107 Q = 5.38220E+00 MeV Emin = 9.98893E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.46020E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 8.00000E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 9.98893E-02 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 6.42872E-04 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 1.09151E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.41000E-02 MeV frac = 1.00000E+00 Product nuclide = 471070 : beta- + + Nuclide 126 / 1657 : 46108.82c -- palladium 108 (Pd-108) + + Pointers : 1053742 30091 + Primary type : Transport + Nuclide ZAI : 461080 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Pd108.ACE + Atomic weight (AW) : 107.90385 + Atomic weight ratio (AWR) : 106.97690 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 3.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 38 reaction channels + - 35 special reactions + - 11 transmutation reactions + - 9 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 38 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -9.22038E+00 MeV Emin = 9.30657E+00 MeV frac = 1.00000E+00 Product nuclide = 46107.82c : (n,2n) + 3 MT = 17 Q = -1.57588E+01 MeV Emin = 1.59061E+01 MeV frac = 1.00000E+00 Product nuclide = 46106.82c : (n,3n) + 4 MT = 22 Q = -3.85491E+00 MeV Emin = 3.89095E+00 MeV frac = 1.00000E+00 Product nuclide = 44104.82c : (n,nalpha) + 5 MT = 24 Q = -1.27589E+01 MeV Emin = 1.28782E+01 MeV frac = 1.00000E+00 Product nuclide = 44103.82c : (n,2nalpha) + 6 MT = 28 Q = -9.95003E+00 MeV Emin = 1.00430E+01 MeV frac = 1.00000E+00 Product nuclide = 451070 : (n,np) + 7 MT = 32 Q = -1.62938E+01 MeV Emin = 1.64461E+01 MeV frac = 1.00000E+00 Product nuclide = 451060 : (n,nd) + 8 MT = 37 Q = -2.53211E+01 MeV Emin = 2.55578E+01 MeV frac = 1.00000E+00 Product nuclide = cut: Pd-105 : (n,4n) + 9 MT = 41 Q = -1.85184E+01 MeV Emin = 1.86915E+01 MeV frac = 1.00000E+00 Product nuclide = 451060 : (n,2np) + 10 MT = 51 Q = -4.33938E-01 MeV Emin = 4.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 11 MT = 52 Q = -9.31200E-01 MeV Emin = 9.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 12 MT = 53 Q = -1.04822E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 13 MT = 54 Q = -1.05278E+00 MeV Emin = 1.06032E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 14 MT = 55 Q = -1.31421E+00 MeV Emin = 1.30000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 15 MT = 56 Q = -1.33520E+00 MeV Emin = 1.33709E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 16 MT = 57 Q = -1.44118E+00 MeV Emin = 1.40000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 17 MT = 58 Q = -1.53996E+00 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 18 MT = 59 Q = -1.62510E+00 MeV Emin = 1.60000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 19 MT = 60 Q = -1.77116E+00 MeV Emin = 1.70000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 20 MT = 61 Q = -1.95600E+00 MeV Emin = 1.90000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 21 MT = 62 Q = -1.98985E+00 MeV Emin = 2.00845E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 22 MT = 63 Q = -2.01500E+00 MeV Emin = 2.03384E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 23 MT = 64 Q = -2.04665E+00 MeV Emin = 2.06578E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 24 MT = 65 Q = -2.09867E+00 MeV Emin = 2.11829E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 25 MT = 66 Q = -2.14100E+00 MeV Emin = 2.16101E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 26 MT = 67 Q = -2.21800E+00 MeV Emin = 2.23873E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 27 MT = 68 Q = -2.28119E+00 MeV Emin = 2.30252E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 28 MT = 69 Q = -2.28247E+00 MeV Emin = 2.30381E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 29 MT = 70 Q = -2.31800E+00 MeV Emin = 2.33967E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 30 MT = 71 Q = -2.36200E+00 MeV Emin = 2.38408E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 31 MT = 72 Q = -2.39150E+00 MeV Emin = 2.41386E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 32 MT = 73 Q = -2.40410E+00 MeV Emin = 2.42657E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 33 MT = 74 Q = -2.41800E+00 MeV Emin = 2.44060E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 34 MT = 91 Q = -2.41800E+00 MeV Emin = 2.44060E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 35 MT = 102 Q = 6.15361E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 461090 : (n,gamma) + 36 MT = 103 Q = -3.66065E+00 MeV Emin = 3.69487E+00 MeV frac = 1.00000E+00 Product nuclide = 451080 : (n,p) + 37 MT = 104 Q = -7.72544E+00 MeV Emin = 7.79766E+00 MeV frac = 1.00000E+00 Product nuclide = 451070 : (n,d) + 38 MT = 107 Q = 2.05547E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 44105.82c : (n,alpha) + + 9 additional transport branches: + + 1 MT = 22 Q = -3.85491E+00 MeV Emin = 3.89095E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 24 Q = -1.27589E+01 MeV Emin = 1.28782E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,2nalpha) + 3 MT = 28 Q = -9.95003E+00 MeV Emin = 1.00430E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 4 MT = 32 Q = -1.62938E+01 MeV Emin = 1.64461E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 5 MT = 41 Q = -1.85184E+01 MeV Emin = 1.86915E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,2np) + 6 MT = 102 Q = 6.15361E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 461091 : (n,gamma) + 7 MT = 103 Q = -3.66065E+00 MeV Emin = 3.69487E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 8 MT = 104 Q = -7.72544E+00 MeV Emin = 7.79766E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 9 MT = 107 Q = 2.05547E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 35 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.69487E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.79766E+00 MeV : total deuteron production + 3 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 4 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 5 MT = 600 Q = -3.66065E+00 MeV Emin = 3.69487E+00 MeV : (n,p) to ground state + 6 MT = 601 Q = -3.70165E+00 MeV Emin = 3.73625E+00 MeV : (n,p1) + 7 MT = 649 Q = -3.70165E+00 MeV Emin = 3.73625E+00 MeV : (n,p) to continuum + 8 MT = 650 Q = -7.72544E+00 MeV Emin = 7.79766E+00 MeV : (n,d) to ground state + 9 MT = 651 Q = -7.91955E+00 MeV Emin = 7.99359E+00 MeV : (n,d1) + 10 MT = 652 Q = -8.00544E+00 MeV Emin = 8.08028E+00 MeV : (n,d2) + 11 MT = 653 Q = -8.13134E+00 MeV Emin = 8.20735E+00 MeV : (n,d3) + 12 MT = 654 Q = -8.18804E+00 MeV Emin = 8.26459E+00 MeV : (n,d4) + 13 MT = 699 Q = -8.18804E+00 MeV Emin = 8.26458E+00 MeV : (n,d) to continuum + 14 MT = 800 Q = 2.05547E+00 MeV Emin = 5.15625E-08 MeV : (n,alpha) to ground state + 15 MT = 801 Q = 2.03486E+00 MeV Emin = 4.03516E-08 MeV : (n,a1) + 16 MT = 802 Q = 1.94753E+00 MeV Emin = 4.13164E-08 MeV : (n,a2) + 17 MT = 803 Q = 1.89595E+00 MeV Emin = 8.75000E-08 MeV : (n,a3) + 18 MT = 804 Q = 1.89166E+00 MeV Emin = 5.62500E-08 MeV : (n,a4) + 19 MT = 805 Q = 1.84687E+00 MeV Emin = 7.50000E-08 MeV : (n,a5) + 20 MT = 806 Q = 1.82599E+00 MeV Emin = 5.00000E-08 MeV : (n,a6) + 21 MT = 807 Q = 1.81106E+00 MeV Emin = 4.61406E-08 MeV : (n,a7) + 22 MT = 808 Q = 1.80910E+00 MeV Emin = 5.00000E-08 MeV : (n,a8) + 23 MT = 809 Q = 1.78275E+00 MeV Emin = 5.93750E-08 MeV : (n,a9) + 24 MT = 810 Q = 1.75379E+00 MeV Emin = 5.15625E-08 MeV : (n,a10) + 25 MT = 811 Q = 1.73388E+00 MeV Emin = 5.78125E-08 MeV : (n,a11) + 26 MT = 812 Q = 1.61352E+00 MeV Emin = 6.56250E-08 MeV : (n,a12) + 27 MT = 813 Q = 1.58920E+00 MeV Emin = 6.87500E-08 MeV : (n,a13) + 28 MT = 814 Q = 1.56458E+00 MeV Emin = 6.56250E-08 MeV : (n,a14) + 29 MT = 815 Q = 1.47747E+00 MeV Emin = 6.56250E-08 MeV : (n,a15) + 30 MT = 816 Q = 1.47736E+00 MeV Emin = 6.25000E-08 MeV : (n,a16) + 31 MT = 817 Q = 1.47335E+00 MeV Emin = 7.81250E-08 MeV : (n,a17) + 32 MT = 818 Q = 1.42964E+00 MeV Emin = 6.87500E-08 MeV : (n,a18) + 33 MT = 819 Q = 1.42420E+00 MeV Emin = 1.34375E-07 MeV : (n,a19) + 34 MT = 849 Q = 1.42420E+00 MeV Emin = 1.00000E-11 MeV : (n,alpha) to continuum + 35 MT = 4 Q = 0.00000E+00 MeV Emin = 4.00000E-01 MeV : total inelastic scattering + + Nuclide 127 / 1657 : 46110.82c -- palladium 110 (Pd-110) + + Pointers : 1062955 30137 + Primary type : Transport + Nuclide ZAI : 461100 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Pd110.ACE + Atomic weight (AW) : 109.90514 + Atomic weight ratio (AWR) : 108.96100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.89E+25 seconds (6E+17 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 20 reaction channels + - 7 special reactions + - 8 transmutation reactions + - 7 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 20 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.72590E+00 MeV Emin = 8.80600E+00 MeV frac = 1.00000E+00 Product nuclide = 461090 : (n,2n) + 3 MT = 51 Q = -3.73800E-01 MeV Emin = 3.73800E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 4 MT = 52 Q = -8.13800E-01 MeV Emin = 8.20469E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 5 MT = 53 Q = -9.20500E-01 MeV Emin = 9.20500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 6 MT = 54 Q = -9.46300E-01 MeV Emin = 9.46711E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 7 MT = 55 Q = -1.17100E+00 MeV Emin = 1.17375E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 8 MT = 56 Q = -1.21200E+00 MeV Emin = 1.21881E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 9 MT = 57 Q = -1.21500E+00 MeV Emin = 1.22464E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 10 MT = 58 Q = -1.30900E+00 MeV Emin = 1.30915E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 11 MT = 59 Q = -1.39800E+00 MeV Emin = 1.40522E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 12 MT = 60 Q = -1.47000E+00 MeV Emin = 1.47441E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 13 MT = 91 Q = -1.55960E+00 MeV Emin = 1.53695E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 14 MT = 102 Q = 5.76600E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 461110 : (n,gamma) + 15 MT = 103 Q = -4.57880E+00 MeV Emin = 4.62082E+00 MeV frac = 1.00000E+00 Product nuclide = 451100 : (n,p) + 16 MT = 104 Q = -8.21110E+00 MeV Emin = 8.28646E+00 MeV frac = 1.00000E+00 Product nuclide = 451090 : (n,d) + 17 MT = 105 Q = -1.00970E+01 MeV Emin = 1.01897E+01 MeV frac = 1.00000E+00 Product nuclide = 451080 : (n,t) + 18 MT = 106 Q = -1.12680E+01 MeV Emin = 1.13714E+01 MeV frac = 1.00000E+00 Product nuclide = 441080 : (n,He-3) + 19 MT = 107 Q = 1.02100E+00 MeV Emin = 4.50000E-01 MeV frac = 1.00000E+00 Product nuclide = 441070 : (n,alpha) + 20 MT = 111 Q = -1.40270E+01 MeV Emin = 1.41557E+01 MeV frac = 1.00000E+00 Product nuclide = 441090 : (n,2p) + + 7 additional transport branches: + + 1 MT = 102 Q = 5.76600E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 461111 : (n,gamma) + 2 MT = 103 Q = -4.57880E+00 MeV Emin = 4.62082E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 104 Q = -8.21110E+00 MeV Emin = 8.28646E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 4 MT = 105 Q = -1.00970E+01 MeV Emin = 1.01897E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 5 MT = 106 Q = -1.12680E+01 MeV Emin = 1.13714E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 6 MT = 107 Q = 1.02100E+00 MeV Emin = 4.50000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 7 MT = 111 Q = -1.40270E+01 MeV Emin = 1.41557E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.62082E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.28646E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.01897E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.13714E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.50000E-01 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 3.73800E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 11 Q = 2.01720E+00 MeV frac = 1.00000E+00 Product nuclide = 48110.82c : beta- + beta- + + Nuclide 128 / 1657 : 47109.82c -- silver 109 (Ag-109) + + Pointers : 1083317 18683 + Primary type : Transport + Nuclide ZAI : 471090 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ag109.ACE + Atomic weight (AW) : 108.90455 + Atomic weight ratio (AWR) : 107.96900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 24 reaction channels + - 7 special reactions + - 8 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 24 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -9.10370E+00 MeV Emin = 9.18802E+00 MeV frac = 1.00000E+00 Product nuclide = 471080 : (n,2n) + 3 MT = 51 Q = -8.80000E-02 MeV Emin = 8.80000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 4 MT = 52 Q = -1.32800E-01 MeV Emin = 1.32800E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 5 MT = 53 Q = -3.11400E-01 MeV Emin = 3.10713E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 6 MT = 54 Q = -4.15300E-01 MeV Emin = 4.16753E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 7 MT = 55 Q = -6.97000E-01 MeV Emin = 7.01900E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 8 MT = 56 Q = -7.01900E-01 MeV Emin = 7.07000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 9 MT = 57 Q = -7.07000E-01 MeV Emin = 7.10974E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 10 MT = 58 Q = -7.24400E-01 MeV Emin = 7.24400E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 11 MT = 59 Q = -7.35300E-01 MeV Emin = 7.39360E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 12 MT = 60 Q = -8.11000E-01 MeV Emin = 8.11000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 13 MT = 61 Q = -8.39800E-01 MeV Emin = 8.43945E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 14 MT = 62 Q = -8.62700E-01 MeV Emin = 8.69500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 15 MT = 63 Q = -8.69500E-01 MeV Emin = 8.74122E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 16 MT = 64 Q = -9.11000E-01 MeV Emin = 9.16355E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 17 MT = 91 Q = -9.20000E-01 MeV Emin = 9.24466E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 18 MT = 102 Q = 6.80921E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 471100 : (n,gamma) + 19 MT = 103 Q = -3.33500E-01 MeV Emin = 3.35713E-01 MeV frac = 1.00000E+00 Product nuclide = 461090 : (n,p) + 20 MT = 104 Q = -4.26170E+00 MeV Emin = 4.30117E+00 MeV frac = 1.00000E+00 Product nuclide = 46108.82c : (n,d) + 21 MT = 105 Q = -7.22650E+00 MeV Emin = 7.29343E+00 MeV frac = 1.00000E+00 Product nuclide = 46107.82c : (n,t) + 22 MT = 106 Q = -8.71890E+00 MeV Emin = 8.79965E+00 MeV frac = 1.00000E+00 Product nuclide = 451070 : (n,He-3) + 23 MT = 107 Q = 3.29700E+00 MeV Emin = 7.20000E+00 MeV frac = 1.00000E+00 Product nuclide = 451060 : (n,alpha) + 24 MT = 111 Q = -1.02050E+01 MeV Emin = 1.02995E+01 MeV frac = 1.00000E+00 Product nuclide = 451080 : (n,2p) + + 7 additional transport branches: + + 1 MT = 102 Q = 6.80921E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 47510.82c : (n,gamma) + 2 MT = 103 Q = -3.33500E-01 MeV Emin = 3.35713E-01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 104 Q = -4.26170E+00 MeV Emin = 4.30117E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 4 MT = 105 Q = -7.22650E+00 MeV Emin = 7.29343E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 5 MT = 106 Q = -8.71890E+00 MeV Emin = 8.79965E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 6 MT = 107 Q = 3.29700E+00 MeV Emin = 7.20000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 7 MT = 111 Q = -1.02050E+01 MeV Emin = 1.02995E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.35713E-01 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 4.30117E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 7.29343E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 8.79965E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 7.20000E+00 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.50000E-03 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 8.80000E-02 MeV : total inelastic scattering + + Nuclide 129 / 1657 : 47510.82c -- silver 110m (Ag-110m) + + Pointers : 1087680 18729 + Primary type : Transport + Nuclide ZAI : 471101 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ag110M.ACE + Atomic weight (AW) : 109.90615 + Atomic weight ratio (AWR) : 108.96200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.16E+07 seconds (250 days) + Specific ingestion toxicity : 2.80E-09 Sv/Bq + Specific inhalation toxicity : 1.20E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 43 reaction channels + - 7 special reactions + - 12 transmutation reactions + - 9 transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 43 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.81009E+00 MeV Emin = 6.87260E+00 MeV frac = 1.00000E+00 Product nuclide = 47109.82c : (n,2n) + 3 MT = 17 Q = -1.60062E+01 MeV Emin = 1.61531E+01 MeV frac = 1.00000E+00 Product nuclide = 471080 : (n,3n) + 4 MT = 22 Q = -3.50589E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 451060 : (n,nalpha) + 5 MT = 28 Q = -7.14363E+00 MeV Emin = 7.20920E+00 MeV frac = 1.00000E+00 Product nuclide = 461090 : (n,np) + 6 MT = 32 Q = -1.09926E+01 MeV Emin = 1.10935E+01 MeV frac = 1.00000E+00 Product nuclide = 46108.82c : (n,nd) + 7 MT = 33 Q = -1.40356E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 46107.82c : (n,nt) + 8 MT = 51 Q = 1.17600E-01 MeV Emin = 4.75000E-03 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = 1.06600E-01 MeV Emin = 2.65625E-06 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -1.10000E-03 MeV Emin = 1.10156E-03 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -7.35999E-02 MeV Emin = 7.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -7.39999E-02 MeV Emin = 7.44595E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -8.10999E-02 MeV Emin = 8.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -1.19300E-01 MeV Emin = 1.14729E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -1.19400E-01 MeV Emin = 1.20395E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -1.49600E-01 MeV Emin = 1.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -1.51400E-01 MeV Emin = 1.51881E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -1.53900E-01 MeV Emin = 1.53420E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 62 Q = -1.84100E-01 MeV Emin = 1.78409E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 20 MT = 63 Q = -1.86900E-01 MeV Emin = 1.85790E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 21 MT = 64 Q = -2.19400E-01 MeV Emin = 2.10707E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 22 MT = 65 Q = -2.21300E-01 MeV Emin = 2.22373E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 23 MT = 66 Q = -2.43000E-01 MeV Emin = 2.34965E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 24 MT = 67 Q = -2.60400E-01 MeV Emin = 2.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 25 MT = 68 Q = -2.63600E-01 MeV Emin = 2.64404E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 26 MT = 69 Q = -2.94400E-01 MeV Emin = 2.81561E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 27 MT = 70 Q = -3.07100E-01 MeV Emin = 3.04959E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 28 MT = 71 Q = -3.14800E-01 MeV Emin = 3.11861E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 29 MT = 72 Q = -3.38900E-01 MeV Emin = 3.30610E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 30 MT = 73 Q = -3.49300E-01 MeV Emin = 3.47258E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 31 MT = 74 Q = -3.51300E-01 MeV Emin = 3.52506E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 32 MT = 75 Q = -3.53600E-01 MeV Emin = 3.55483E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 33 MT = 76 Q = -3.66399E-01 MeV Emin = 3.64111E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 34 MT = 77 Q = -3.68199E-01 MeV Emin = 3.70917E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 27. excited state + 35 MT = 78 Q = -3.79299E-01 MeV Emin = 3.74379E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 28. excited state + 36 MT = 79 Q = -4.08099E-01 MeV Emin = 3.98221E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 29. excited state + 37 MT = 91 Q = -4.09899E-01 MeV Emin = 4.12974E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 38 MT = 102 Q = 8.84139E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 47111.82c : (n,gamma) + 39 MT = 103 Q = 1.66146E+00 MeV Emin = 9.99438E-02 MeV frac = 1.00000E+00 Product nuclide = 46110.82c : (n,p) + 40 MT = 104 Q = -4.83351E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 461090 : (n,d) + 41 MT = 105 Q = -4.80746E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 46108.82c : (n,t) + 42 MT = 106 Q = -9.29182E+00 MeV Emin = 1.10935E+01 MeV frac = 1.00000E+00 Product nuclide = 451080 : (n,He-3) + 43 MT = 107 Q = 5.05820E+00 MeV Emin = 9.99438E-02 MeV frac = 1.00000E+00 Product nuclide = 451070 : (n,alpha) + + 9 additional transport branches: + + 1 MT = 22 Q = -3.50589E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -7.14363E+00 MeV Emin = 7.20920E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.09926E+01 MeV Emin = 1.10935E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.40356E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 103 Q = 1.66146E+00 MeV Emin = 9.99438E-02 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 104 Q = -4.83351E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 7 MT = 105 Q = -4.80746E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 8 MT = 106 Q = -9.29182E+00 MeV Emin = 1.10935E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 9 MT = 107 Q = 5.05820E+00 MeV Emin = 9.99438E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 9.99438E-02 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 6.00000E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.10935E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 9.99438E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 4.75000E-03 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 3 Q = 1.17600E-01 MeV frac = 1.36000E-02 Product nuclide = 471100 : IT + 2 RTYP = 1 Q = 3.00979E+00 MeV frac = 9.86400E-01 Product nuclide = 48110.82c : beta- + + Nuclide 130 / 1657 : 47111.82c -- silver 111 (Ag-111) + + Pointers : 1094237 18775 + Primary type : Transport + Nuclide ZAI : 471110 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ag111.ACE + Atomic weight (AW) : 110.90574 + Atomic weight ratio (AWR) : 109.95300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 6.44E+05 seconds (7.45 days) + Specific ingestion toxicity : 1.30E-09 Sv/Bq + Specific inhalation toxicity : 1.70E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 19 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 6 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 19 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -5.99000E-02 MeV Emin = 5.89987E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -1.30000E-01 MeV Emin = 1.23385E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -2.90000E-01 MeV Emin = 2.69480E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -3.77000E-01 MeV Emin = 3.79670E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -3.91000E-01 MeV Emin = 3.89340E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -4.05000E-01 MeV Emin = 4.03845E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 57 Q = -5.46000E-01 MeV Emin = 5.42195E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 9 MT = 58 Q = -5.69000E-01 MeV Emin = 5.70325E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 10 MT = 59 Q = -6.07000E-01 MeV Emin = 5.98455E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 11 MT = 60 Q = -6.42000E-01 MeV Emin = 6.32260E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 12 MT = 91 Q = -9.90990E-01 MeV Emin = 9.62500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 13 MT = 102 Q = 6.36000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 471120 : (n,gamma) + 14 MT = 103 Q = -1.41290E+00 MeV Emin = 1.42552E+00 MeV frac = 1.00000E+00 Product nuclide = 461110 : (n,p) + 15 MT = 104 Q = -4.95350E+00 MeV Emin = 4.99855E+00 MeV frac = 1.00000E+00 Product nuclide = 46110.82c : (n,d) + 16 MT = 105 Q = -7.49540E+00 MeV Emin = 7.56357E+00 MeV frac = 1.00000E+00 Product nuclide = 461090 : (n,t) + 17 MT = 106 Q = -9.97250E+00 MeV Emin = 1.00632E+01 MeV frac = 1.00000E+00 Product nuclide = 451090 : (n,He-3) + 18 MT = 107 Q = 2.43960E+00 MeV Emin = 4.76796E-01 MeV frac = 1.00000E+00 Product nuclide = 451080 : (n,alpha) + 19 MT = 111 Q = -1.17980E+01 MeV Emin = 1.19053E+01 MeV frac = 1.00000E+00 Product nuclide = 451100 : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = -1.41290E+00 MeV Emin = 1.42552E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -4.95350E+00 MeV Emin = 4.99855E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -7.49540E+00 MeV Emin = 7.56357E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -9.97250E+00 MeV Emin = 1.00632E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 2.43960E+00 MeV Emin = 4.76796E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -1.17980E+01 MeV Emin = 1.19053E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.42552E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 4.99855E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 7.56357E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.00632E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.76796E-01 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 5.89987E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.03680E+00 MeV frac = 1.00000E+00 Product nuclide = 48111.82c : beta- + + Nuclide 131 / 1657 : 48110.82c -- cadmium 110 (Cd-110) + + Pointers : 1121751 20753 + Primary type : Transport + Nuclide ZAI : 481100 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Cd110.ACE + Atomic weight (AW) : 109.90313 + Atomic weight ratio (AWR) : 108.95900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 28 reaction channels + - 7 special reactions + - 12 transmutation reactions + - 10 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 28 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -9.88030E+00 MeV Emin = 9.97100E+00 MeV frac = 1.00000E+00 Product nuclide = 481090 : (n,2n) + 3 MT = 17 Q = -1.72430E+01 MeV Emin = 1.74013E+01 MeV frac = 1.00000E+00 Product nuclide = 481080 : (n,3n) + 4 MT = 22 Q = -2.86100E+00 MeV Emin = 2.88726E+00 MeV frac = 1.00000E+00 Product nuclide = 46106.82c : (n,nalpha) + 5 MT = 28 Q = -8.91690E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 47109.82c : (n,np) + 6 MT = 32 Q = -1.58860E+01 MeV Emin = 1.60318E+01 MeV frac = 1.00000E+00 Product nuclide = 471080 : (n,nd) + 7 MT = 33 Q = -1.68960E+01 MeV Emin = 1.70511E+01 MeV frac = 1.00000E+00 Product nuclide = 471070 : (n,nt) + 8 MT = 51 Q = -6.58020E-01 MeV Emin = 6.60000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -1.47500E+00 MeV Emin = 1.40000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -1.47600E+00 MeV Emin = 1.40000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -1.54600E+00 MeV Emin = 1.53000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -1.73400E+00 MeV Emin = 1.67500E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -1.78300E+00 MeV Emin = 1.77500E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -1.81300E+00 MeV Emin = 1.81500E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -2.07900E+00 MeV Emin = 2.10000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -2.08000E+00 MeV Emin = 2.10000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -2.16000E+00 MeV Emin = 2.18000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -2.22000E+00 MeV Emin = 2.24038E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 62 Q = -2.28700E+00 MeV Emin = 2.31000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 20 MT = 63 Q = -2.32900E+00 MeV Emin = 2.35038E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 21 MT = 64 Q = -2.35600E+00 MeV Emin = 2.38000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 22 MT = 91 Q = -2.35860E+00 MeV Emin = 2.38025E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 23 MT = 102 Q = 6.97585E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 48111.82c : (n,gamma) + 24 MT = 103 Q = -2.11080E+00 MeV Emin = 2.13017E+00 MeV frac = 1.00000E+00 Product nuclide = 471100 : (n,p) + 25 MT = 104 Q = -6.69220E+00 MeV Emin = 6.75362E+00 MeV frac = 1.00000E+00 Product nuclide = 47109.82c : (n,d) + 26 MT = 105 Q = -9.88000E+00 MeV Emin = 9.97100E+00 MeV frac = 1.00000E+00 Product nuclide = 471080 : (n,t) + 27 MT = 106 Q = -7.68710E+00 MeV Emin = 7.75765E+00 MeV frac = 1.00000E+00 Product nuclide = 46108.82c : (n,He-3) + 28 MT = 107 Q = 3.70100E+00 MeV Emin = 1.68750E-04 MeV frac = 1.00000E+00 Product nuclide = 46107.82c : (n,alpha) + + 10 additional transport branches: + + 1 MT = 22 Q = -2.86100E+00 MeV Emin = 2.88726E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -8.91690E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.58860E+01 MeV Emin = 1.60318E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.68960E+01 MeV Emin = 1.70511E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 102 Q = 6.97585E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 481111 : (n,gamma) + 6 MT = 103 Q = -2.11080E+00 MeV Emin = 2.13017E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 7 MT = 104 Q = -6.69220E+00 MeV Emin = 6.75362E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 8 MT = 105 Q = -9.88000E+00 MeV Emin = 9.97100E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 9 MT = 106 Q = -7.68710E+00 MeV Emin = 7.75765E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 10 MT = 107 Q = 3.70100E+00 MeV Emin = 1.68750E-04 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.13017E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.75362E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.97100E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 7.75765E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.68750E-04 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.65625E-04 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 6.60000E-01 MeV : total inelastic scattering + + Nuclide 132 / 1657 : 48111.82c -- cadmium 111 (Cd-111) + + Pointers : 1125166 20799 + Primary type : Transport + Nuclide ZAI : 481110 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Cd111.ACE + Atomic weight (AW) : 110.90473 + Atomic weight ratio (AWR) : 109.95200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 25 reaction channels + - 7 special reactions + - 12 transmutation reactions + - 9 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 25 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.97560E+00 MeV Emin = 7.03904E+00 MeV frac = 1.00000E+00 Product nuclide = 48110.82c : (n,2n) + 3 MT = 17 Q = -1.68580E+01 MeV Emin = 1.70113E+01 MeV frac = 1.00000E+00 Product nuclide = 481090 : (n,3n) + 4 MT = 22 Q = -3.30820E+00 MeV Emin = 3.33829E+00 MeV frac = 1.00000E+00 Product nuclide = 46107.82c : (n,nalpha) + 5 MT = 28 Q = -9.08710E+00 MeV Emin = 9.16975E+00 MeV frac = 1.00000E+00 Product nuclide = 471100 : (n,np) + 6 MT = 32 Q = -1.36670E+01 MeV Emin = 1.37913E+01 MeV frac = 1.00000E+00 Product nuclide = 47109.82c : (n,nd) + 7 MT = 33 Q = -1.66000E+01 MeV Emin = 1.67510E+01 MeV frac = 1.00000E+00 Product nuclide = 471080 : (n,nt) + 8 MT = 51 Q = -2.44790E-01 MeV Emin = 2.40000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -3.45000E-01 MeV Emin = 3.48000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -3.96000E-01 MeV Emin = 3.87035E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -4.17000E-01 MeV Emin = 4.12500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -6.20400E-01 MeV Emin = 6.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -6.80000E-01 MeV Emin = 6.86000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -7.00000E-01 MeV Emin = 7.06000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -7.53000E-01 MeV Emin = 7.53183E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -7.55000E-01 MeV Emin = 7.53183E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -8.54000E-01 MeV Emin = 8.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -8.65000E-01 MeV Emin = 8.72656E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 91 Q = -8.54000E-01 MeV Emin = 8.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 20 MT = 102 Q = 9.39432E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 48112.82c : (n,gamma) + 21 MT = 103 Q = -2.44800E-01 MeV Emin = 2.40000E-01 MeV frac = 1.00000E+00 Product nuclide = 47111.82c : (n,p) + 22 MT = 104 Q = -6.86320E+00 MeV Emin = 6.92562E+00 MeV frac = 1.00000E+00 Product nuclide = 471100 : (n,d) + 23 MT = 105 Q = -7.41120E+00 MeV Emin = 7.47861E+00 MeV frac = 1.00000E+00 Product nuclide = 47109.82c : (n,t) + 24 MT = 106 Q = -8.50930E+00 MeV Emin = 8.58669E+00 MeV frac = 1.00000E+00 Product nuclide = 461090 : (n,He-3) + 25 MT = 107 Q = 5.96930E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 46108.82c : (n,alpha) + + 9 additional transport branches: + + 1 MT = 22 Q = -3.30820E+00 MeV Emin = 3.33829E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -9.08710E+00 MeV Emin = 9.16975E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.36670E+01 MeV Emin = 1.37913E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.66000E+01 MeV Emin = 1.67510E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 103 Q = -2.44800E-01 MeV Emin = 2.40000E-01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 104 Q = -6.86320E+00 MeV Emin = 6.92562E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 7 MT = 105 Q = -7.41120E+00 MeV Emin = 7.47861E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 8 MT = 106 Q = -8.50930E+00 MeV Emin = 8.58669E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 9 MT = 107 Q = 5.96930E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.40000E-01 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.92562E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 7.47861E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 8.58669E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 2.40000E-01 MeV : total inelastic scattering + + Nuclide 133 / 1657 : 48112.82c -- cadmium 112 (Cd-112) + + Pointers : 1128711 20845 + Primary type : Transport + Nuclide ZAI : 481120 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Cd112.ACE + Atomic weight (AW) : 111.90331 + Atomic weight ratio (AWR) : 110.94200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 22 reaction channels + - 7 special reactions + - 12 transmutation reactions + - 10 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 22 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -9.39710E+00 MeV Emin = 9.48181E+00 MeV frac = 1.00000E+00 Product nuclide = 48111.82c : (n,2n) + 3 MT = 17 Q = -1.63740E+01 MeV Emin = 1.65216E+01 MeV frac = 1.00000E+00 Product nuclide = 48110.82c : (n,3n) + 4 MT = 22 Q = -3.47990E+00 MeV Emin = 3.51127E+00 MeV frac = 1.00000E+00 Product nuclide = 46108.82c : (n,nalpha) + 5 MT = 28 Q = -9.64190E+00 MeV Emin = 9.72881E+00 MeV frac = 1.00000E+00 Product nuclide = 47111.82c : (n,np) + 6 MT = 32 Q = -1.62650E+01 MeV Emin = 1.64116E+01 MeV frac = 1.00000E+00 Product nuclide = 471100 : (n,nd) + 7 MT = 33 Q = -1.68100E+01 MeV Emin = 1.69615E+01 MeV frac = 1.00000E+00 Product nuclide = 47109.82c : (n,nt) + 8 MT = 51 Q = -6.18000E-01 MeV Emin = 6.20000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -1.22900E+00 MeV Emin = 1.20000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -1.30800E+00 MeV Emin = 1.28004E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -1.41700E+00 MeV Emin = 1.40000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -1.43700E+00 MeV Emin = 1.44000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -1.46700E+00 MeV Emin = 1.46500E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -1.87300E+00 MeV Emin = 1.80000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -2.00200E+00 MeV Emin = 2.02005E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 91 Q = -1.98230E+00 MeV Emin = 2.00017E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 17 MT = 102 Q = 6.53980E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 48113.82c : (n,gamma) + 18 MT = 103 Q = -3.17600E+00 MeV Emin = 3.20463E+00 MeV frac = 1.00000E+00 Product nuclide = 471120 : (n,p) + 19 MT = 104 Q = -7.41680E+00 MeV Emin = 7.48366E+00 MeV frac = 1.00000E+00 Product nuclide = 47111.82c : (n,d) + 20 MT = 105 Q = -1.00030E+01 MeV Emin = 1.00932E+01 MeV frac = 1.00000E+00 Product nuclide = 471100 : (n,t) + 21 MT = 106 Q = -9.10470E+00 MeV Emin = 9.18677E+00 MeV frac = 1.00000E+00 Product nuclide = 46110.82c : (n,He-3) + 22 MT = 107 Q = 2.69800E+00 MeV Emin = 1.81811E-03 MeV frac = 1.00000E+00 Product nuclide = 461090 : (n,alpha) + + 10 additional transport branches: + + 1 MT = 22 Q = -3.47990E+00 MeV Emin = 3.51127E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -9.64190E+00 MeV Emin = 9.72881E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.62650E+01 MeV Emin = 1.64116E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.68100E+01 MeV Emin = 1.69615E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 102 Q = 6.53980E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 481131 : (n,gamma) + 6 MT = 103 Q = -3.17600E+00 MeV Emin = 3.20463E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 7 MT = 104 Q = -7.41680E+00 MeV Emin = 7.48366E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 8 MT = 105 Q = -1.00030E+01 MeV Emin = 1.00932E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 9 MT = 106 Q = -9.10470E+00 MeV Emin = 9.18677E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 10 MT = 107 Q = 2.69800E+00 MeV Emin = 1.81811E-03 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.20463E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.48366E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.00932E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 9.18677E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.81811E-03 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 6.20000E-01 MeV : total inelastic scattering + + Nuclide 134 / 1657 : 48113.82c -- cadmium 113 (Cd-113) + + Pointers : 1131688 20891 + Primary type : Transport + Nuclide ZAI : 481130 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Cd113.ACE + Atomic weight (AW) : 112.89987 + Atomic weight ratio (AWR) : 111.93000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.54E+23 seconds (8.05E+15 years) + Specific ingestion toxicity : 2.50E-08 Sv/Bq + Specific inhalation toxicity : 1.20E-07 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 26 reaction channels + - 7 special reactions + - 12 transmutation reactions + - 9 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 26 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.54410E+00 MeV Emin = 6.60257E+00 MeV frac = 1.00000E+00 Product nuclide = 48112.82c : (n,2n) + 3 MT = 17 Q = -1.59390E+01 MeV Emin = 1.60814E+01 MeV frac = 1.00000E+00 Product nuclide = 48111.82c : (n,3n) + 4 MT = 22 Q = -3.86970E+00 MeV Emin = 3.90428E+00 MeV frac = 1.00000E+00 Product nuclide = 461090 : (n,nalpha) + 5 MT = 28 Q = -9.71990E+00 MeV Emin = 9.80674E+00 MeV frac = 1.00000E+00 Product nuclide = 471120 : (n,np) + 6 MT = 32 Q = -1.39660E+01 MeV Emin = 1.40908E+01 MeV frac = 1.00000E+00 Product nuclide = 47111.82c : (n,nd) + 7 MT = 33 Q = -1.65440E+01 MeV Emin = 1.66918E+01 MeV frac = 1.00000E+00 Product nuclide = 471100 : (n,nt) + 8 MT = 51 Q = -2.63660E-01 MeV Emin = 2.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -2.98330E-01 MeV Emin = 3.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -3.16000E-01 MeV Emin = 3.10000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -4.58000E-01 MeV Emin = 4.26250E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -5.22000E-01 MeV Emin = 5.25546E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -5.30000E-01 MeV Emin = 5.33478E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -5.84000E-01 MeV Emin = 5.89000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -6.38000E-01 MeV Emin = 6.43500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -6.81000E-01 MeV Emin = 6.65250E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -7.08000E-01 MeV Emin = 7.14000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -7.60000E-01 MeV Emin = 7.42494E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 62 Q = -8.20000E-01 MeV Emin = 8.27000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 20 MT = 91 Q = -9.91200E-01 MeV Emin = 9.13663E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 21 MT = 102 Q = 9.04298E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 48114.82c : (n,gamma) + 22 MT = 103 Q = -1.22800E+00 MeV Emin = 1.80000E+00 MeV frac = 1.00000E+00 Product nuclide = 471130 : (n,p) + 23 MT = 104 Q = -7.49570E+00 MeV Emin = 7.56267E+00 MeV frac = 1.00000E+00 Product nuclide = 471120 : (n,d) + 24 MT = 105 Q = -7.70380E+00 MeV Emin = 7.77263E+00 MeV frac = 1.00000E+00 Product nuclide = 47111.82c : (n,t) + 25 MT = 106 Q = -9.88250E+00 MeV Emin = 9.97080E+00 MeV frac = 1.00000E+00 Product nuclide = 461110 : (n,He-3) + 26 MT = 107 Q = 5.31030E+00 MeV Emin = 1.85906E-07 MeV frac = 1.00000E+00 Product nuclide = 46110.82c : (n,alpha) + + 9 additional transport branches: + + 1 MT = 22 Q = -3.86970E+00 MeV Emin = 3.90428E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -9.71990E+00 MeV Emin = 9.80674E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.39660E+01 MeV Emin = 1.40908E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.65440E+01 MeV Emin = 1.66918E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 103 Q = -1.22800E+00 MeV Emin = 1.80000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 104 Q = -7.49570E+00 MeV Emin = 7.56267E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 7 MT = 105 Q = -7.70380E+00 MeV Emin = 7.77263E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 8 MT = 106 Q = -9.88250E+00 MeV Emin = 9.97080E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 9 MT = 107 Q = 5.31030E+00 MeV Emin = 1.85906E-07 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.80000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.56267E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 7.77263E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 9.97080E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.85906E-07 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.84875E-07 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 2.50000E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.22000E-01 MeV frac = 1.00000E+00 Product nuclide = 49113.82c : beta- + + Nuclide 135 / 1657 : 48114.82c -- cadmium 114 (Cd-114) + + Pointers : 1135429 20937 + Primary type : Transport + Nuclide ZAI : 481140 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Cd114.ACE + Atomic weight (AW) : 113.90349 + Atomic weight ratio (AWR) : 112.92500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.90E+24 seconds (9.21E+16 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 24 reaction channels + - 7 special reactions + - 12 transmutation reactions + - 10 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 24 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -9.04070E+00 MeV Emin = 9.12076E+00 MeV frac = 1.00000E+00 Product nuclide = 48113.82c : (n,2n) + 3 MT = 17 Q = -1.55830E+01 MeV Emin = 1.57210E+01 MeV frac = 1.00000E+00 Product nuclide = 48112.82c : (n,3n) + 4 MT = 22 Q = -4.07700E+00 MeV Emin = 4.11311E+00 MeV frac = 1.00000E+00 Product nuclide = 46110.82c : (n,nalpha) + 5 MT = 28 Q = -1.02700E+01 MeV Emin = 1.03610E+01 MeV frac = 1.00000E+00 Product nuclide = 471130 : (n,np) + 6 MT = 32 Q = -1.65350E+01 MeV Emin = 1.66814E+01 MeV frac = 1.00000E+00 Product nuclide = 471120 : (n,nd) + 7 MT = 33 Q = -1.67430E+01 MeV Emin = 1.68913E+01 MeV frac = 1.00000E+00 Product nuclide = 47111.82c : (n,nt) + 8 MT = 51 Q = -5.58100E-01 MeV Emin = 5.60000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -1.13000E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -1.21000E+00 MeV Emin = 1.22000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -1.27900E+00 MeV Emin = 1.29000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -1.30800E+00 MeV Emin = 1.30516E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -1.36800E+00 MeV Emin = 1.35000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -1.73500E+00 MeV Emin = 1.75000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -1.84200E+00 MeV Emin = 1.80000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -1.86300E+00 MeV Emin = 1.87000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -1.86310E+00 MeV Emin = 1.87000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 91 Q = -1.86310E+00 MeV Emin = 1.87000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 19 MT = 102 Q = 6.14800E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 481150 : (n,gamma) + 20 MT = 103 Q = -4.07700E+00 MeV Emin = 4.11311E+00 MeV frac = 1.00000E+00 Product nuclide = 471140 : (n,p) + 21 MT = 104 Q = -8.04440E+00 MeV Emin = 8.11564E+00 MeV frac = 1.00000E+00 Product nuclide = 471130 : (n,d) + 22 MT = 105 Q = -1.02790E+01 MeV Emin = 1.03700E+01 MeV frac = 1.00000E+00 Product nuclide = 471120 : (n,t) + 23 MT = 106 Q = -9.04000E+00 MeV Emin = 9.12005E+00 MeV frac = 1.00000E+00 Product nuclide = 461120 : (n,He-3) + 24 MT = 107 Q = 1.67150E+00 MeV Emin = 1.40000E-02 MeV frac = 1.00000E+00 Product nuclide = 461110 : (n,alpha) + + 10 additional transport branches: + + 1 MT = 22 Q = -4.07700E+00 MeV Emin = 4.11311E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.02700E+01 MeV Emin = 1.03610E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.65350E+01 MeV Emin = 1.66814E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.67430E+01 MeV Emin = 1.68913E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 102 Q = 6.14800E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 48515.82c : (n,gamma) + 6 MT = 103 Q = -4.07700E+00 MeV Emin = 4.11311E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 7 MT = 104 Q = -8.04440E+00 MeV Emin = 8.11564E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 8 MT = 105 Q = -1.02790E+01 MeV Emin = 1.03700E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 9 MT = 106 Q = -9.04000E+00 MeV Emin = 9.12005E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 10 MT = 107 Q = 1.67150E+00 MeV Emin = 1.40000E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.11311E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.11564E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.03700E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 9.12005E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.40000E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 5.60000E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 11 Q = 5.42500E-01 MeV frac = 1.00000E+00 Product nuclide = 501140 : beta- + beta- + + Nuclide 136 / 1657 : 48515.82c -- cadmium 115m (Cd-115m) + + Pointers : 1139741 20983 + Primary type : Transport + Nuclide ZAI : 481151 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Cd115M.ACE + Atomic weight (AW) : 114.90610 + Atomic weight ratio (AWR) : 113.91900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 3.85E+06 seconds (44.6 days) + Specific ingestion toxicity : 3.30E-09 Sv/Bq + Specific inhalation toxicity : 7.70E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 9 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 6 transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 9 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 91 Q = -6.93890E-01 MeV Emin = 6.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 3 MT = 102 Q = 8.79000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 48116.82c : (n,gamma) + 4 MT = 103 Q = -2.58050E+00 MeV Emin = 2.60315E+00 MeV frac = 1.00000E+00 Product nuclide = 471150 : (n,p) + 5 MT = 104 Q = -8.17550E+00 MeV Emin = 8.24727E+00 MeV frac = 1.00000E+00 Product nuclide = 471140 : (n,d) + 6 MT = 105 Q = -8.10930E+00 MeV Emin = 8.18049E+00 MeV frac = 1.00000E+00 Product nuclide = 471130 : (n,t) + 7 MT = 106 Q = -1.14900E+01 MeV Emin = 1.15909E+01 MeV frac = 1.00000E+00 Product nuclide = 461130 : (n,He-3) + 8 MT = 107 Q = 3.69720E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 461120 : (n,alpha) + 9 MT = 111 Q = -1.06310E+01 MeV Emin = 1.07243E+01 MeV frac = 1.00000E+00 Product nuclide = 461140 : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = -2.58050E+00 MeV Emin = 2.60315E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -8.17550E+00 MeV Emin = 8.24727E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -8.10930E+00 MeV Emin = 8.18049E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -1.14900E+01 MeV Emin = 1.15909E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 3.69720E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -1.06310E+01 MeV Emin = 1.07243E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.60315E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.24727E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 8.18049E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.15909E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.62500E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 6.50000E-01 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.62970E+00 MeV frac = 9.99894E-01 Product nuclide = 49115.82c : beta- + 2 RTYP = 1 Q = 1.29345E+00 MeV frac = 1.05757E-04 Product nuclide = 491151 : beta- + + Nuclide 137 / 1657 : 48116.82c -- cadmium 116 (Cd-116) + + Pointers : 1142757 21029 + Primary type : Transport + Nuclide ZAI : 481160 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Cd116.ACE + Atomic weight (AW) : 115.90468 + Atomic weight ratio (AWR) : 114.90900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 9.47E+26 seconds (3E+19 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 20 reaction channels + - 7 special reactions + - 12 transmutation reactions + - 10 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 20 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.69700E+00 MeV Emin = 8.77269E+00 MeV frac = 1.00000E+00 Product nuclide = 481150 : (n,2n) + 3 MT = 17 Q = -1.48420E+01 MeV Emin = 1.49712E+01 MeV frac = 1.00000E+00 Product nuclide = 48114.82c : (n,3n) + 4 MT = 22 Q = -4.81750E+00 MeV Emin = 4.85942E+00 MeV frac = 1.00000E+00 Product nuclide = 461120 : (n,nalpha) + 5 MT = 28 Q = -1.10940E+01 MeV Emin = 1.11906E+01 MeV frac = 1.00000E+00 Product nuclide = 471150 : (n,np) + 6 MT = 32 Q = -1.66960E+01 MeV Emin = 1.68413E+01 MeV frac = 1.00000E+00 Product nuclide = 471140 : (n,nd) + 7 MT = 33 Q = -1.66250E+01 MeV Emin = 1.67700E+01 MeV frac = 1.00000E+00 Product nuclide = 471130 : (n,nt) + 8 MT = 51 Q = -5.12580E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -1.20900E+00 MeV Emin = 1.20000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -1.21900E+00 MeV Emin = 1.22500E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -1.27900E+00 MeV Emin = 1.26000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -1.37800E+00 MeV Emin = 1.34007E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -1.64600E+00 MeV Emin = 1.66000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 91 Q = -1.78460E+00 MeV Emin = 1.73016E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 15 MT = 102 Q = 5.76500E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 481170 : (n,gamma) + 16 MT = 103 Q = -5.31600E+00 MeV Emin = 5.36226E+00 MeV frac = 1.00000E+00 Product nuclide = 471160 : (n,p) + 17 MT = 104 Q = -8.87350E+00 MeV Emin = 8.95072E+00 MeV frac = 1.00000E+00 Product nuclide = 471150 : (n,d) + 18 MT = 105 Q = -1.04380E+01 MeV Emin = 1.05300E+01 MeV frac = 1.00000E+00 Product nuclide = 471140 : (n,t) + 19 MT = 106 Q = -1.12330E+01 MeV Emin = 1.13308E+01 MeV frac = 1.00000E+00 Product nuclide = 461140 : (n,He-3) + 20 MT = 107 Q = 5.72900E-01 MeV Emin = 2.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 461130 : (n,alpha) + + 10 additional transport branches: + + 1 MT = 22 Q = -4.81750E+00 MeV Emin = 4.85942E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.10940E+01 MeV Emin = 1.11906E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.66960E+01 MeV Emin = 1.68413E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.66250E+01 MeV Emin = 1.67700E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 102 Q = 5.76500E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 481171 : (n,gamma) + 6 MT = 103 Q = -5.31600E+00 MeV Emin = 5.36226E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 7 MT = 104 Q = -8.87350E+00 MeV Emin = 8.95072E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 8 MT = 105 Q = -1.04380E+01 MeV Emin = 1.05300E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 9 MT = 106 Q = -1.12330E+01 MeV Emin = 1.13308E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 10 MT = 107 Q = 5.72900E-01 MeV Emin = 2.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 5.36226E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.95072E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.05300E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.13308E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 2.00000E-01 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 5.00000E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 11 Q = 2.81344E+00 MeV frac = 1.00000E+00 Product nuclide = 50116.82c : beta- + beta- + + Nuclide 138 / 1657 : 49113.82c -- indium 113 (In-113) + + Pointers : 1166336 26641 + Primary type : Transport + Nuclide ZAI : 491130 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/In113.ACE + Atomic weight (AW) : 112.90390 + Atomic weight ratio (AWR) : 111.93400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 38 reaction channels + - 7 special reactions + - 12 transmutation reactions + - 10 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 38 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -9.44809E+00 MeV Emin = 9.53251E+00 MeV frac = 1.00000E+00 Product nuclide = 491120 : (n,2n) + 3 MT = 17 Q = -1.71192E+01 MeV Emin = 1.72722E+01 MeV frac = 1.00000E+00 Product nuclide = 491110 : (n,3n) + 4 MT = 22 Q = -3.07190E+00 MeV Emin = 3.09935E+00 MeV frac = 1.00000E+00 Product nuclide = 47109.82c : (n,nalpha) + 5 MT = 28 Q = -6.08773E+00 MeV Emin = 7.05494E+00 MeV frac = 1.00000E+00 Product nuclide = 48112.82c : (n,np) + 6 MT = 32 Q = -1.31776E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 48111.82c : (n,nd) + 7 MT = 33 Q = -1.39736E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 48110.82c : (n,nt) + 8 MT = 51 Q = -3.91699E-01 MeV Emin = 3.47600E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -6.46799E-01 MeV Emin = 6.49517E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -1.02420E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -1.02970E+00 MeV Emin = 1.03613E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -1.06420E+00 MeV Emin = 1.06066E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -1.10640E+00 MeV Emin = 1.09766E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -1.13150E+00 MeV Emin = 1.13211E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -1.17310E+00 MeV Emin = 1.17440E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -1.19110E+00 MeV Emin = 1.19266E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -1.34480E+00 MeV Emin = 1.32343E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -1.35100E+00 MeV Emin = 1.35994E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 62 Q = -1.38070E+00 MeV Emin = 1.38554E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 20 MT = 63 Q = -1.47180E+00 MeV Emin = 1.48453E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 21 MT = 64 Q = -1.50940E+00 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 22 MT = 65 Q = -1.53610E+00 MeV Emin = 1.53972E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 23 MT = 66 Q = -1.56700E+00 MeV Emin = 1.56541E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 24 MT = 67 Q = -1.56950E+00 MeV Emin = 1.58320E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 25 MT = 68 Q = -1.63050E+00 MeV Emin = 1.61814E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 26 MT = 69 Q = -1.68820E+00 MeV Emin = 1.69055E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 27 MT = 70 Q = -1.70000E+00 MeV Emin = 1.70924E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 28 MT = 71 Q = -1.70700E+00 MeV Emin = 1.71872E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 29 MT = 72 Q = -1.75800E+00 MeV Emin = 1.75000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 30 MT = 73 Q = -1.76800E+00 MeV Emin = 1.77876E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 31 MT = 74 Q = -1.82270E+00 MeV Emin = 1.81139E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 32 MT = 91 Q = -1.83610E+00 MeV Emin = 1.84574E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 33 MT = 102 Q = 7.27539E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 491140 : (n,gamma) + 34 MT = 103 Q = 4.60756E-01 MeV Emin = 1.56541E+00 MeV frac = 1.00000E+00 Product nuclide = 48113.82c : (n,p) + 35 MT = 104 Q = -3.77761E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 48112.82c : (n,d) + 36 MT = 105 Q = -6.99246E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 48111.82c : (n,t) + 37 MT = 106 Q = -8.00183E+00 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 47111.82c : (n,He-3) + 38 MT = 107 Q = 3.73819E+00 MeV Emin = 1.00098E-01 MeV frac = 1.00000E+00 Product nuclide = 471100 : (n,alpha) + + 10 additional transport branches: + + 1 MT = 22 Q = -3.07190E+00 MeV Emin = 3.09935E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -6.08773E+00 MeV Emin = 7.05494E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.31776E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.39736E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 102 Q = 7.27539E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 491141 : (n,gamma) + 6 MT = 103 Q = 4.60756E-01 MeV Emin = 1.56541E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 7 MT = 104 Q = -3.77761E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 8 MT = 105 Q = -6.99246E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 9 MT = 106 Q = -8.00183E+00 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 10 MT = 107 Q = 3.73819E+00 MeV Emin = 1.00098E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.56541E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.00000E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.20000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00098E-01 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 3.47600E-01 MeV : total inelastic scattering + + Nuclide 139 / 1657 : 49115.82c -- indium 115 (In-115) + + Pointers : 1171964 26687 + Primary type : Transport + Nuclide ZAI : 491150 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/In115.ACE + Atomic weight (AW) : 114.90409 + Atomic weight ratio (AWR) : 113.91700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.39E+22 seconds (4.41E+14 years) + Specific ingestion toxicity : 3.20E-08 Sv/Bq + Specific inhalation toxicity : 3.90E-07 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 26 reaction channels + - 6 special reactions + - 11 transmutation reactions + - 8 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 26 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -9.04110E+00 MeV Emin = 9.12048E+00 MeV frac = 1.00000E+00 Product nuclide = 491140 : (n,2n) + 3 MT = 17 Q = -1.63212E+01 MeV Emin = 1.64645E+01 MeV frac = 1.00000E+00 Product nuclide = 49113.82c : (n,3n) + 4 MT = 22 Q = -3.73689E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 47111.82c : (n,nalpha) + 5 MT = 28 Q = -6.81504E+00 MeV Emin = 7.42983E+00 MeV frac = 1.00000E+00 Product nuclide = 48114.82c : (n,np) + 6 MT = 32 Q = -1.35503E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 48113.82c : (n,nd) + 7 MT = 33 Q = -1.39137E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 48112.82c : (n,nt) + 8 MT = 51 Q = -3.36200E-01 MeV Emin = 3.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -5.96999E-01 MeV Emin = 6.00488E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -8.28399E-01 MeV Emin = 8.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -8.63999E-01 MeV Emin = 8.64284E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -9.33599E-01 MeV Emin = 9.20898E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -9.41199E-01 MeV Emin = 9.45628E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -1.07800E+00 MeV Emin = 1.06560E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -1.13250E+00 MeV Emin = 1.12870E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -1.29050E+00 MeV Emin = 1.30081E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -1.41800E+00 MeV Emin = 1.42919E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -1.44870E+00 MeV Emin = 1.45677E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 62 Q = -1.46250E+00 MeV Emin = 1.46605E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 20 MT = 63 Q = -1.48580E+00 MeV Emin = 1.48709E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 21 MT = 91 Q = -1.50000E+00 MeV Emin = 1.51286E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 22 MT = 102 Q = 6.78473E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 491160 : (n,gamma) + 23 MT = 103 Q = -6.65537E-01 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 481150 : (n,p) + 24 MT = 104 Q = -4.50492E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 48114.82c : (n,d) + 25 MT = 105 Q = -7.36516E+00 MeV Emin = 9.43898E+00 MeV frac = 1.00000E+00 Product nuclide = 48113.82c : (n,t) + 26 MT = 107 Q = 2.73321E+00 MeV Emin = 1.18750E-01 MeV frac = 1.00000E+00 Product nuclide = 471120 : (n,alpha) + + 8 additional transport branches: + + 1 MT = 22 Q = -3.73689E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -6.81504E+00 MeV Emin = 7.42983E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.35503E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.39137E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 103 Q = -6.65537E-01 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 104 Q = -4.50492E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 7 MT = 105 Q = -7.36516E+00 MeV Emin = 9.43898E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 8 MT = 107 Q = 2.73321E+00 MeV Emin = 1.18750E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.43898E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 1.18750E-01 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 7.07357E-04 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 3.00000E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.97489E-01 MeV frac = 1.00000E+00 Product nuclide = 50115.82c : beta- + + Nuclide 140 / 1657 : 50115.82c -- tin 115 (Sn-115) + + Pointers : 1205655 33449 + Primary type : Transport + Nuclide ZAI : 501150 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Sn115.ACE + Atomic weight (AW) : 114.90308 + Atomic weight ratio (AWR) : 113.91600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 29 reaction channels + - 7 special reactions + - 11 transmutation reactions + - 8 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 29 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.55119E+00 MeV Emin = 7.61749E+00 MeV frac = 1.00000E+00 Product nuclide = 501140 : (n,2n) + 3 MT = 17 Q = -1.78553E+01 MeV Emin = 1.80121E+01 MeV frac = 1.00000E+00 Product nuclide = 501130 : (n,3n) + 4 MT = 22 Q = -3.20300E+00 MeV Emin = 3.23112E+00 MeV frac = 1.00000E+00 Product nuclide = 48111.82c : (n,nalpha) + 5 MT = 28 Q = -8.75274E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 491140 : (n,np) + 6 MT = 32 Q = -1.37227E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 49113.82c : (n,nd) + 7 MT = 51 Q = -4.97299E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 8 MT = 52 Q = -6.12799E-01 MeV Emin = 6.03615E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 9 MT = 53 Q = -7.13399E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 10 MT = 54 Q = -9.86499E-01 MeV Emin = 9.71370E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 11 MT = 55 Q = -1.28010E+00 MeV Emin = 1.25000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 12 MT = 56 Q = -1.41680E+00 MeV Emin = 1.42896E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 13 MT = 57 Q = -1.63380E+00 MeV Emin = 1.60185E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 14 MT = 58 Q = -1.73390E+00 MeV Emin = 1.71756E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 15 MT = 59 Q = -1.78560E+00 MeV Emin = 1.78845E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 16 MT = 60 Q = -1.82500E+00 MeV Emin = 1.82115E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 17 MT = 61 Q = -1.85750E+00 MeV Emin = 1.85740E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 18 MT = 62 Q = -1.94400E+00 MeV Emin = 1.93380E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 19 MT = 63 Q = -1.96400E+00 MeV Emin = 1.97115E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 20 MT = 64 Q = -1.97380E+00 MeV Emin = 1.99062E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 21 MT = 65 Q = -2.02460E+00 MeV Emin = 2.04237E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 22 MT = 66 Q = -2.06010E+00 MeV Emin = 2.07818E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 23 MT = 91 Q = -2.08420E+00 MeV Emin = 2.10250E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 24 MT = 102 Q = 9.56239E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 50116.82c : (n,gamma) + 25 MT = 103 Q = 2.88364E-01 MeV Emin = 1.75080E+00 MeV frac = 1.00000E+00 Product nuclide = 49115.82c : (n,p) + 26 MT = 104 Q = -6.44262E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 491140 : (n,d) + 27 MT = 105 Q = -7.53756E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 49113.82c : (n,t) + 28 MT = 106 Q = -7.84063E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 48113.82c : (n,He-3) + 29 MT = 107 Q = 6.19700E+00 MeV Emin = 9.49999E-02 MeV frac = 1.00000E+00 Product nuclide = 48112.82c : (n,alpha) + + 8 additional transport branches: + + 1 MT = 22 Q = -3.20300E+00 MeV Emin = 3.23112E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -8.75274E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.37227E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 103 Q = 2.88364E-01 MeV Emin = 1.75080E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -6.44262E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -7.53756E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 106 Q = -7.84063E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 8 MT = 107 Q = 6.19700E+00 MeV Emin = 9.49999E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.75080E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.00000E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.10000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 9.49999E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 5.00000E-01 MeV : total inelastic scattering + + Nuclide 141 / 1657 : 50116.82c -- tin 116 (Sn-116) + + Pointers : 1208978 33495 + Primary type : Transport + Nuclide ZAI : 501160 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Sn116.ACE + Atomic weight (AW) : 115.90166 + Atomic weight ratio (AWR) : 114.90600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 21 reaction channels + - 6 special reactions + - 9 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 21 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -9.56709E+00 MeV Emin = 9.65036E+00 MeV frac = 1.00000E+00 Product nuclide = 50115.82c : (n,2n) + 3 MT = 17 Q = -1.71183E+01 MeV Emin = 1.72673E+01 MeV frac = 1.00000E+00 Product nuclide = 501140 : (n,3n) + 4 MT = 22 Q = -3.37009E+00 MeV Emin = 3.39942E+00 MeV frac = 1.00000E+00 Product nuclide = 48112.82c : (n,nalpha) + 5 MT = 28 Q = -9.27873E+00 MeV Emin = 1.00308E+01 MeV frac = 1.00000E+00 Product nuclide = 49115.82c : (n,np) + 6 MT = 51 Q = -1.29350E+00 MeV Emin = 1.25000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.75680E+00 MeV Emin = 1.76523E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -2.02730E+00 MeV Emin = 2.04494E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -2.11230E+00 MeV Emin = 2.13068E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -2.22530E+00 MeV Emin = 2.24467E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -2.26610E+00 MeV Emin = 2.28582E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -2.36590E+00 MeV Emin = 2.38649E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -2.39080E+00 MeV Emin = 2.41161E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -2.39220E+00 MeV Emin = 2.41302E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -2.52910E+00 MeV Emin = 2.55111E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 91 Q = -2.54600E+00 MeV Emin = 2.56816E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 17 MT = 102 Q = 6.94419E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 50117.82c : (n,gamma) + 18 MT = 103 Q = -2.49064E+00 MeV Emin = 3.39942E+00 MeV frac = 1.00000E+00 Product nuclide = 491160 : (n,p) + 19 MT = 104 Q = -6.96861E+00 MeV Emin = 8.43511E+00 MeV frac = 1.00000E+00 Product nuclide = 49115.82c : (n,d) + 20 MT = 105 Q = -9.82456E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 491140 : (n,t) + 21 MT = 107 Q = 3.17841E+00 MeV Emin = 1.04375E-01 MeV frac = 1.00000E+00 Product nuclide = 48113.82c : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -3.37009E+00 MeV Emin = 3.39942E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -9.27873E+00 MeV Emin = 1.00308E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 102 Q = 6.94419E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 501171 : (n,gamma) + 4 MT = 103 Q = -2.49064E+00 MeV Emin = 3.39942E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -6.96861E+00 MeV Emin = 8.43511E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -9.82456E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 107 Q = 3.17841E+00 MeV Emin = 1.04375E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.39942E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.43511E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.10000E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 1.04375E-01 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 1.25000E+00 MeV : total inelastic scattering + + Nuclide 142 / 1657 : 50117.82c -- tin 117 (Sn-117) + + Pointers : 1211590 33541 + Primary type : Transport + Nuclide ZAI : 501170 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Sn117.ACE + Atomic weight (AW) : 116.90326 + Atomic weight ratio (AWR) : 115.89900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 24 reaction channels + - 6 special reactions + - 10 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 24 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.94890E+00 MeV Emin = 7.00886E+00 MeV frac = 1.00000E+00 Product nuclide = 50116.82c : (n,2n) + 3 MT = 17 Q = -1.65160E+01 MeV Emin = 1.66585E+01 MeV frac = 1.00000E+00 Product nuclide = 50115.82c : (n,3n) + 4 MT = 22 Q = -3.77049E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 48113.82c : (n,nalpha) + 5 MT = 28 Q = -9.43953E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 491160 : (n,np) + 6 MT = 32 Q = -1.39175E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 49115.82c : (n,nd) + 7 MT = 51 Q = -1.58600E-01 MeV Emin = 1.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 8 MT = 52 Q = -3.14600E-01 MeV Emin = 3.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 9 MT = 53 Q = -7.11599E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 10 MT = 54 Q = -1.00450E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 11 MT = 55 Q = -1.01990E+00 MeV Emin = 1.02093E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 12 MT = 56 Q = -1.17960E+00 MeV Emin = 1.18855E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 13 MT = 57 Q = -1.30430E+00 MeV Emin = 1.28277E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 14 MT = 58 Q = -1.44640E+00 MeV Emin = 1.42305E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 15 MT = 59 Q = -1.49720E+00 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 16 MT = 60 Q = -1.57830E+00 MeV Emin = 1.57147E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 17 MT = 61 Q = -1.66800E+00 MeV Emin = 1.65977E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 18 MT = 62 Q = -1.77000E+00 MeV Emin = 1.75000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 19 MT = 91 Q = -1.94800E+00 MeV Emin = 1.92273E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 20 MT = 102 Q = 9.32619E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 50118.82c : (n,gamma) + 21 MT = 103 Q = -6.72430E-01 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 491170 : (n,p) + 22 MT = 104 Q = -7.12941E+00 MeV Emin = 8.26316E+00 MeV frac = 1.00000E+00 Product nuclide = 491160 : (n,d) + 23 MT = 105 Q = -7.73235E+00 MeV Emin = 9.52099E+00 MeV frac = 1.00000E+00 Product nuclide = 49115.82c : (n,t) + 24 MT = 107 Q = 5.27490E+00 MeV Emin = 9.99804E-02 MeV frac = 1.00000E+00 Product nuclide = 48114.82c : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -3.77049E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -9.43953E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.39175E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 103 Q = -6.72430E-01 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -7.12941E+00 MeV Emin = 8.26316E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -7.73235E+00 MeV Emin = 9.52099E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 107 Q = 5.27490E+00 MeV Emin = 9.99804E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.26316E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.52099E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 9.99804E-02 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 1.50000E-01 MeV : total inelastic scattering + + Nuclide 143 / 1657 : 50118.82c -- tin 118 (Sn-118) + + Pointers : 1214913 33587 + Primary type : Transport + Nuclide ZAI : 501180 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Sn118.ACE + Atomic weight (AW) : 117.90184 + Atomic weight ratio (AWR) : 116.88900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 18 reaction channels + - 6 special reactions + - 9 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 18 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -9.33080E+00 MeV Emin = 9.41063E+00 MeV frac = 1.00000E+00 Product nuclide = 50117.82c : (n,2n) + 3 MT = 17 Q = -1.62797E+01 MeV Emin = 1.64190E+01 MeV frac = 1.00000E+00 Product nuclide = 50116.82c : (n,3n) + 4 MT = 22 Q = -4.05589E+00 MeV Emin = 4.09060E+00 MeV frac = 1.00000E+00 Product nuclide = 48114.82c : (n,nalpha) + 5 MT = 28 Q = -1.00032E+01 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 491170 : (n,np) + 6 MT = 51 Q = -1.22960E+00 MeV Emin = 1.16508E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.75780E+00 MeV Emin = 1.76705E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -2.04310E+00 MeV Emin = 2.06058E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -2.05650E+00 MeV Emin = 2.07409E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -2.28030E+00 MeV Emin = 2.29981E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -2.31000E+00 MeV Emin = 2.32976E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -2.32110E+00 MeV Emin = 2.34096E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 91 Q = -2.32650E+00 MeV Emin = 2.34640E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 14 MT = 102 Q = 6.48449E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 50119.82c : (n,gamma) + 15 MT = 103 Q = -3.42113E+00 MeV Emin = 4.09060E+00 MeV frac = 1.00000E+00 Product nuclide = 491180 : (n,p) + 16 MT = 104 Q = -7.69311E+00 MeV Emin = 9.41063E+00 MeV frac = 1.00000E+00 Product nuclide = 491170 : (n,d) + 17 MT = 105 Q = -1.02751E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 491160 : (n,t) + 18 MT = 107 Q = 2.09361E+00 MeV Emin = 1.08254E+00 MeV frac = 1.00000E+00 Product nuclide = 481150 : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -4.05589E+00 MeV Emin = 4.09060E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.00032E+01 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 102 Q = 6.48449E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 501191 : (n,gamma) + 4 MT = 103 Q = -3.42113E+00 MeV Emin = 4.09060E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -7.69311E+00 MeV Emin = 9.41063E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -1.02751E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 107 Q = 2.09361E+00 MeV Emin = 1.08254E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.09060E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 9.41063E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.20000E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 1.08254E+00 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 1.16508E+00 MeV : total inelastic scattering + + Nuclide 144 / 1657 : 50119.82c -- tin 119 (Sn-119) + + Pointers : 1217306 33633 + Primary type : Transport + Nuclide ZAI : 501190 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Sn119.ACE + Atomic weight (AW) : 118.90344 + Atomic weight ratio (AWR) : 117.88200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 32 reaction channels + - 6 special reactions + - 10 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 32 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.48919E+00 MeV Emin = 6.54425E+00 MeV frac = 1.00000E+00 Product nuclide = 50118.82c : (n,2n) + 3 MT = 17 Q = -1.58200E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 50117.82c : (n,3n) + 4 MT = 22 Q = -4.39558E+00 MeV Emin = 4.43288E+00 MeV frac = 1.00000E+00 Product nuclide = 481150 : (n,nalpha) + 5 MT = 28 Q = -9.91033E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 491180 : (n,np) + 6 MT = 32 Q = -1.41823E+01 MeV Emin = 1.59542E+01 MeV frac = 1.00000E+00 Product nuclide = 491170 : (n,nd) + 7 MT = 51 Q = -2.39000E-02 MeV Emin = 2.20514E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 8 MT = 52 Q = -8.94999E-02 MeV Emin = 8.87824E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 9 MT = 53 Q = -7.86999E-01 MeV Emin = 7.70257E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 10 MT = 54 Q = -9.20499E-01 MeV Emin = 9.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 11 MT = 55 Q = -9.21399E-01 MeV Emin = 9.28975E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 12 MT = 56 Q = -1.06240E+00 MeV Emin = 1.03571E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 13 MT = 57 Q = -1.08940E+00 MeV Emin = 1.08843E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 14 MT = 58 Q = -1.18770E+00 MeV Emin = 1.19110E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 15 MT = 59 Q = -1.24970E+00 MeV Emin = 1.25000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 16 MT = 60 Q = -1.35490E+00 MeV Emin = 1.33987E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 17 MT = 61 Q = -1.55440E+00 MeV Emin = 1.53371E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 18 MT = 62 Q = -1.57160E+00 MeV Emin = 1.57626E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 19 MT = 63 Q = -1.61730E+00 MeV Emin = 1.61374E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 20 MT = 64 Q = -1.63100E+00 MeV Emin = 1.63793E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 21 MT = 65 Q = -1.71840E+00 MeV Emin = 1.71094E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 22 MT = 66 Q = -1.77470E+00 MeV Emin = 1.76988E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 23 MT = 67 Q = -1.78970E+00 MeV Emin = 1.79732E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 24 MT = 68 Q = -1.90500E+00 MeV Emin = 1.89391E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 25 MT = 69 Q = -1.92960E+00 MeV Emin = 1.94230E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 26 MT = 70 Q = -1.93880E+00 MeV Emin = 1.95463E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 27 MT = 91 Q = -1.98300E+00 MeV Emin = 1.97754E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 28 MT = 102 Q = 9.10659E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 50120.82c : (n,gamma) + 29 MT = 103 Q = -1.55424E+00 MeV Emin = 2.00351E+00 MeV frac = 1.00000E+00 Product nuclide = 491190 : (n,p) + 30 MT = 104 Q = -7.60021E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 491180 : (n,d) + 31 MT = 105 Q = -7.99715E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 491170 : (n,t) + 32 MT = 107 Q = 4.30510E+00 MeV Emin = 1.00148E-01 MeV frac = 1.00000E+00 Product nuclide = 48116.82c : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -4.39558E+00 MeV Emin = 4.43288E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -9.91033E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.41823E+01 MeV Emin = 1.59542E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 103 Q = -1.55424E+00 MeV Emin = 2.00351E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -7.60021E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -7.99715E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 107 Q = 4.30510E+00 MeV Emin = 1.00148E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.00351E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 9.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.00000E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00148E-01 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 2.20514E-02 MeV : total inelastic scattering + + Nuclide 145 / 1657 : 50120.82c -- tin 120 (Sn-120) + + Pointers : 1221143 33679 + Primary type : Transport + Nuclide ZAI : 501200 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Sn120.ACE + Atomic weight (AW) : 119.90202 + Atomic weight ratio (AWR) : 118.87200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 27 reaction channels + - 6 special reactions + - 9 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 27 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -9.11120E+00 MeV Emin = 9.18785E+00 MeV frac = 1.00000E+00 Product nuclide = 50119.82c : (n,2n) + 3 MT = 17 Q = -1.56004E+01 MeV Emin = 1.57317E+01 MeV frac = 1.00000E+00 Product nuclide = 50118.82c : (n,3n) + 4 MT = 22 Q = -4.80608E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 48116.82c : (n,nalpha) + 5 MT = 28 Q = -1.06654E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 491190 : (n,np) + 6 MT = 51 Q = -1.17150E+00 MeV Emin = 1.10201E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.87500E+00 MeV Emin = 1.75000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -2.09750E+00 MeV Emin = 2.11515E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -2.15980E+00 MeV Emin = 2.17797E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -2.19460E+00 MeV Emin = 2.21306E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -2.28460E+00 MeV Emin = 2.30382E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -2.29000E+00 MeV Emin = 2.30926E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -2.35560E+00 MeV Emin = 2.37542E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -2.39970E+00 MeV Emin = 2.41989E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -2.42110E+00 MeV Emin = 2.44147E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -2.46610E+00 MeV Emin = 2.48685E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -2.48200E+00 MeV Emin = 2.50288E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -2.58680E+00 MeV Emin = 2.60856E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -2.64270E+00 MeV Emin = 2.66493E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -2.69720E+00 MeV Emin = 2.71989E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 21 MT = 66 Q = -2.72130E+00 MeV Emin = 2.74419E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 22 MT = 91 Q = -2.76000E+00 MeV Emin = 2.78322E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 23 MT = 102 Q = 6.17139E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 501210 : (n,gamma) + 24 MT = 103 Q = -4.61932E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 491200 : (n,p) + 25 MT = 104 Q = -8.35531E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 491190 : (n,d) + 26 MT = 105 Q = -1.05263E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 491180 : (n,t) + 27 MT = 107 Q = 9.68414E-01 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 481170 : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -4.80608E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.06654E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 102 Q = 6.17139E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 501211 : (n,gamma) + 4 MT = 103 Q = -4.61932E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -8.35531E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -1.05263E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 107 Q = 9.68414E-01 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 6.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.00000E+01 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.20000E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 1.10201E+00 MeV : total inelastic scattering + + Nuclide 146 / 1657 : 50122.82c -- tin 122 (Sn-122) + + Pointers : 1224994 33725 + Primary type : Transport + Nuclide ZAI : 501220 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Sn122.ACE + Atomic weight (AW) : 121.90321 + Atomic weight ratio (AWR) : 120.85600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 20 reaction channels + - 6 special reactions + - 9 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 20 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.82030E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 501210 : (n,2n) + 3 MT = 17 Q = -1.49964E+01 MeV Emin = 1.51205E+01 MeV frac = 1.00000E+00 Product nuclide = 50120.82c : (n,3n) + 4 MT = 22 Q = -5.66088E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 481180 : (n,nalpha) + 5 MT = 28 Q = -1.13976E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 491210 : (n,np) + 6 MT = 51 Q = -1.14020E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -2.09000E+00 MeV Emin = 2.10729E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -2.14500E+00 MeV Emin = 2.16275E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -2.15300E+00 MeV Emin = 2.17082E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -2.24900E+00 MeV Emin = 2.26761E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -2.33600E+00 MeV Emin = 2.35533E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -2.40000E+00 MeV Emin = 2.41986E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -2.41500E+00 MeV Emin = 2.43498E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -2.49200E+00 MeV Emin = 2.51262E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 91 Q = -2.55600E+00 MeV Emin = 2.57715E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 16 MT = 102 Q = 5.94639E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 50123.82c : (n,gamma) + 17 MT = 103 Q = -5.56352E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 491220 : (n,p) + 18 MT = 104 Q = -9.08751E+00 MeV Emin = 1.12125E+01 MeV frac = 1.00000E+00 Product nuclide = 491210 : (n,d) + 19 MT = 105 Q = -1.11205E+01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 491200 : (n,t) + 20 MT = 107 Q = -6.17863E-02 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 481190 : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -5.66088E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.13976E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 102 Q = 5.94639E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 501231 : (n,gamma) + 4 MT = 103 Q = -5.56352E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -9.08751E+00 MeV Emin = 1.12125E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -1.11205E+01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 107 Q = -6.17863E-02 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 7.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.12125E+01 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.30000E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 1.00000E+00 MeV : total inelastic scattering + + Nuclide 147 / 1657 : 50123.82c -- tin 123 (Sn-123) + + Pointers : 1227533 33771 + Primary type : Transport + Nuclide ZAI : 501230 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Sn123.ACE + Atomic weight (AW) : 122.90583 + Atomic weight ratio (AWR) : 121.85000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.12E+07 seconds (129 days) + Specific ingestion toxicity : 2.10E-09 Sv/Bq + Specific inhalation toxicity : 8.10E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 18 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 6 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 18 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -2.40000E-02 MeV Emin = 2.32268E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -1.98370E-01 MeV Emin = 1.82090E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -9.30000E-01 MeV Emin = 8.18815E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -1.03000E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -1.16000E+00 MeV Emin = 1.08475E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -1.20000E+00 MeV Emin = 1.18966E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 57 Q = -1.49000E+00 MeV Emin = 1.35603E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 9 MT = 58 Q = -1.78000E+00 MeV Emin = 1.60000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 10 MT = 59 Q = -1.83000E+00 MeV Emin = 1.84250E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 11 MT = 91 Q = -1.82500E+00 MeV Emin = 1.81730E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 12 MT = 102 Q = 8.56000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 50124.82c : (n,gamma) + 13 MT = 103 Q = -3.59710E+00 MeV Emin = 3.62662E+00 MeV frac = 1.00000E+00 Product nuclide = 491230 : (n,p) + 14 MT = 104 Q = -9.28210E+00 MeV Emin = 9.35828E+00 MeV frac = 1.00000E+00 Product nuclide = 491220 : (n,d) + 15 MT = 105 Q = -8.85400E+00 MeV Emin = 8.92666E+00 MeV frac = 1.00000E+00 Product nuclide = 491210 : (n,t) + 16 MT = 106 Q = -1.09130E+01 MeV Emin = 1.10026E+01 MeV frac = 1.00000E+00 Product nuclide = 481210 : (n,He-3) + 17 MT = 107 Q = 1.80590E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 481200 : (n,alpha) + 18 MT = 111 Q = -1.14630E+01 MeV Emin = 1.15571E+01 MeV frac = 1.00000E+00 Product nuclide = 481220 : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = -3.59710E+00 MeV Emin = 3.62662E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -9.28210E+00 MeV Emin = 9.35828E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -8.85400E+00 MeV Emin = 8.92666E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -1.09130E+01 MeV Emin = 1.10026E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 1.80590E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -1.14630E+01 MeV Emin = 1.15571E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.62662E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 9.35828E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 8.92666E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.10026E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 2.32268E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.40360E+00 MeV frac = 1.00000E+00 Product nuclide = 51123.82c : beta- + + Nuclide 148 / 1657 : 50124.82c -- tin 124 (Sn-124) + + Pointers : 1230832 33817 + Primary type : Transport + Nuclide ZAI : 501240 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Sn124.ACE + Atomic weight (AW) : 123.90541 + Atomic weight ratio (AWR) : 122.84100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 3.16E+24 seconds (1E+17 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 31 reaction channels + - 6 special reactions + - 9 transmutation reactions + - 7 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 31 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.49509E+00 MeV Emin = 8.56426E+00 MeV frac = 1.00000E+00 Product nuclide = 50123.82c : (n,2n) + 3 MT = 17 Q = -1.44462E+01 MeV Emin = 1.45638E+01 MeV frac = 1.00000E+00 Product nuclide = 50122.82c : (n,3n) + 4 MT = 22 Q = -6.68088E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 481200 : (n,nalpha) + 5 MT = 28 Q = -1.20936E+01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 491230 : (n,np) + 6 MT = 51 Q = -1.13160E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -2.10160E+00 MeV Emin = 2.11871E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -2.12930E+00 MeV Emin = 2.14663E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -2.12940E+00 MeV Emin = 2.14674E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -2.19200E+00 MeV Emin = 2.20985E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -2.20450E+00 MeV Emin = 2.22245E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -2.22150E+00 MeV Emin = 2.23958E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -2.32490E+00 MeV Emin = 2.34383E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -2.36640E+00 MeV Emin = 2.38566E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -2.42640E+00 MeV Emin = 2.44615E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -2.44690E+00 MeV Emin = 2.46682E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -2.56800E+00 MeV Emin = 2.58891E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -2.60240E+00 MeV Emin = 2.62359E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -2.61420E+00 MeV Emin = 2.63548E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -2.68660E+00 MeV Emin = 2.70847E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 21 MT = 66 Q = -2.68870E+00 MeV Emin = 2.71059E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 22 MT = 67 Q = -2.70290E+00 MeV Emin = 2.72490E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 23 MT = 68 Q = -2.83630E+00 MeV Emin = 2.85939E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 24 MT = 69 Q = -2.87510E+00 MeV Emin = 2.89851E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 25 MT = 70 Q = -2.87830E+00 MeV Emin = 2.90173E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 26 MT = 91 Q = -2.90000E+00 MeV Emin = 2.92361E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 27 MT = 102 Q = 5.73339E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 50125.82c : (n,gamma) + 28 MT = 103 Q = -6.35752E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 491240 : (n,p) + 29 MT = 104 Q = -9.78351E+00 MeV Emin = 1.21921E+01 MeV frac = 1.00000E+00 Product nuclide = 491230 : (n,d) + 30 MT = 105 Q = -1.15145E+01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 491220 : (n,t) + 31 MT = 107 Q = -1.25822E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 481210 : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -6.68088E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.20936E+01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 102 Q = 5.73339E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 501251 : (n,gamma) + 4 MT = 103 Q = -6.35752E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -9.78351E+00 MeV Emin = 1.21921E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -1.15145E+01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 107 Q = -1.25822E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 8.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.21921E+01 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.30000E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 3.00000E+00 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 1.00000E+00 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 11 Q = 2.29110E+00 MeV frac = 1.00000E+00 Product nuclide = 52124.82c : beta- + beta- + + Nuclide 149 / 1657 : 50125.82c -- tin 125 (Sn-125) + + Pointers : 1234247 33863 + Primary type : Transport + Nuclide ZAI : 501250 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Sn125.ACE + Atomic weight (AW) : 124.90803 + Atomic weight ratio (AWR) : 123.83500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 8.33E+05 seconds (9.64 days) + Specific ingestion toxicity : 3.10E-09 Sv/Bq + Specific inhalation toxicity : 3.10E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 12 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 6 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 12 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -2.60000E-02 MeV Emin = 2.56327E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -2.10000E-01 MeV Emin = 2.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -9.36000E-01 MeV Emin = 8.23000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 91 Q = -9.91990E-01 MeV Emin = 9.73000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 6 MT = 102 Q = 8.16000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 50126.82c : (n,gamma) + 7 MT = 103 Q = -4.61780E+00 MeV Emin = 4.65509E+00 MeV frac = 1.00000E+00 Product nuclide = 491250 : (n,p) + 8 MT = 104 Q = -9.86280E+00 MeV Emin = 9.94245E+00 MeV frac = 1.00000E+00 Product nuclide = 491240 : (n,d) + 9 MT = 105 Q = -9.33680E+00 MeV Emin = 9.41220E+00 MeV frac = 1.00000E+00 Product nuclide = 491230 : (n,t) + 10 MT = 106 Q = -1.25660E+01 MeV Emin = 1.26675E+01 MeV frac = 1.00000E+00 Product nuclide = 481230 : (n,He-3) + 11 MT = 107 Q = 4.80000E-01 MeV Emin = 1.06250E-08 MeV frac = 1.00000E+00 Product nuclide = 481220 : (n,alpha) + 12 MT = 111 Q = -1.32970E+01 MeV Emin = 1.34044E+01 MeV frac = 1.00000E+00 Product nuclide = 481240 : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = -4.61780E+00 MeV Emin = 4.65509E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -9.86280E+00 MeV Emin = 9.94245E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -9.33680E+00 MeV Emin = 9.41220E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -1.25660E+01 MeV Emin = 1.26675E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 4.80000E-01 MeV Emin = 1.06250E-08 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -1.32970E+01 MeV Emin = 1.34044E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.65509E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 9.94245E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.41220E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.26675E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.06250E-08 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 2.56327E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.35700E+00 MeV frac = 1.00000E+00 Product nuclide = 51125.82c : beta- + + Nuclide 150 / 1657 : 50126.82c -- tin 126 (Sn-126) + + Pointers : 1238858 33909 + Primary type : Transport + Nuclide ZAI : 501260 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Sn126.ACE + Atomic weight (AW) : 125.90761 + Atomic weight ratio (AWR) : 124.82600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 7.26E+12 seconds (230,153 years) + Specific ingestion toxicity : 4.70E-09 Sv/Bq + Specific inhalation toxicity : 2.80E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 19 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 7 transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 19 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -1.14000E+00 MeV Emin = 1.11183E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -2.05000E+00 MeV Emin = 2.06642E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -2.17000E+00 MeV Emin = 2.18740E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -2.22000E+00 MeV Emin = 2.23780E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -2.38000E+00 MeV Emin = 2.39910E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -2.66000E+00 MeV Emin = 2.68131E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 57 Q = -2.72000E+00 MeV Emin = 2.74180E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 9 MT = 58 Q = -2.89000E+00 MeV Emin = 2.91320E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 10 MT = 59 Q = -3.28000E+00 MeV Emin = 3.30630E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 11 MT = 60 Q = -3.42000E+00 MeV Emin = 3.44740E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 12 MT = 91 Q = -3.40270E+00 MeV Emin = 3.43000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 13 MT = 102 Q = 5.62000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 501270 : (n,gamma) + 14 MT = 103 Q = -7.33890E+00 MeV Emin = 7.39769E+00 MeV frac = 1.00000E+00 Product nuclide = 491260 : (n,p) + 15 MT = 104 Q = -1.05850E+01 MeV Emin = 1.06698E+01 MeV frac = 1.00000E+00 Product nuclide = 491250 : (n,d) + 16 MT = 105 Q = -1.17980E+01 MeV Emin = 1.18925E+01 MeV frac = 1.00000E+00 Product nuclide = 491240 : (n,t) + 17 MT = 106 Q = -1.37720E+01 MeV Emin = 1.38823E+01 MeV frac = 1.00000E+00 Product nuclide = 481240 : (n,He-3) + 18 MT = 107 Q = -1.86100E-01 MeV Emin = 1.65683E-01 MeV frac = 1.00000E+00 Product nuclide = 481230 : (n,alpha) + 19 MT = 111 Q = -1.64250E+01 MeV Emin = 1.65566E+01 MeV frac = 1.00000E+00 Product nuclide = 481250 : (n,2p) + + 7 additional transport branches: + + 1 MT = 102 Q = 5.62000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 501271 : (n,gamma) + 2 MT = 103 Q = -7.33890E+00 MeV Emin = 7.39769E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 104 Q = -1.05850E+01 MeV Emin = 1.06698E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 4 MT = 105 Q = -1.17980E+01 MeV Emin = 1.18925E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 5 MT = 106 Q = -1.37720E+01 MeV Emin = 1.38823E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 6 MT = 107 Q = -1.86100E-01 MeV Emin = 1.65683E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 7 MT = 111 Q = -1.64250E+01 MeV Emin = 1.65566E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 7.39769E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.06698E+01 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.18925E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.38823E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.65683E-01 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 1.11183E+00 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 1 Q = 3.60300E-01 MeV frac = 3.30685E-01 Product nuclide = 511261 : beta- + 2 RTYP = 1 Q = 3.37600E-01 MeV frac = 6.69315E-01 Product nuclide = 511262 : beta- + + Nuclide 151 / 1657 : 51121.82c -- antimony 121 (Sb-121) + + Pointers : 1263591 32207 + Primary type : Transport + Nuclide ZAI : 511210 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Sb121.ACE + Atomic weight (AW) : 120.90363 + Atomic weight ratio (AWR) : 119.86500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 24 reaction channels + - 6 special reactions + - 9 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 24 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -9.24758E+00 MeV Emin = 9.32474E+00 MeV frac = 1.00000E+00 Product nuclide = 511200 : (n,2n) + 3 MT = 17 Q = -1.62503E+01 MeV Emin = 1.63859E+01 MeV frac = 1.00000E+00 Product nuclide = 511190 : (n,3n) + 4 MT = 22 Q = -3.08584E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 491170 : (n,nalpha) + 5 MT = 28 Q = -5.78481E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 50120.82c : (n,np) + 6 MT = 51 Q = -3.70999E-02 MeV Emin = 3.55500E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -5.07599E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -5.73099E-01 MeV Emin = 5.61369E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -9.46999E-01 MeV Emin = 9.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -1.02400E+00 MeV Emin = 1.01625E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -1.03540E+00 MeV Emin = 1.03829E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -1.13930E+00 MeV Emin = 1.12427E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -1.14470E+00 MeV Emin = 1.15150E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -1.38620E+00 MeV Emin = 1.36082E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -1.40750E+00 MeV Emin = 1.40850E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -1.41050E+00 MeV Emin = 1.42076E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -1.42720E+00 MeV Emin = 1.43068E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -1.44800E+00 MeV Emin = 1.44959E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 91 Q = -1.44900E+00 MeV Emin = 1.46084E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 20 MT = 102 Q = 6.80643E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 511220 : (n,gamma) + 21 MT = 103 Q = 3.95269E-01 MeV Emin = 4.50000E-01 MeV frac = 1.00000E+00 Product nuclide = 501210 : (n,p) + 22 MT = 104 Q = -3.56020E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 50120.82c : (n,d) + 23 MT = 105 Q = -6.39616E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 50119.82c : (n,t) + 24 MT = 107 Q = 3.50684E+00 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 491180 : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -3.08584E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -5.78481E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 102 Q = 6.80643E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 511221 : (n,gamma) + 4 MT = 103 Q = 3.95269E-01 MeV Emin = 4.50000E-01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -3.56020E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -6.39616E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 107 Q = 3.50684E+00 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.50000E-01 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 4.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 8.00000E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 5.00000E-01 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 3.55500E-02 MeV : total inelastic scattering + + Nuclide 152 / 1657 : 51123.82c -- antimony 123 (Sb-123) + + Pointers : 1267545 32253 + Primary type : Transport + Nuclide ZAI : 511230 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Sb123.ACE + Atomic weight (AW) : 122.90381 + Atomic weight ratio (AWR) : 121.84800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 19 reaction channels + - 6 special reactions + - 9 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 19 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.96518E+00 MeV Emin = 9.03877E+00 MeV frac = 1.00000E+00 Product nuclide = 511220 : (n,2n) + 3 MT = 17 Q = -1.57726E+01 MeV Emin = 1.59020E+01 MeV frac = 1.00000E+00 Product nuclide = 51121.82c : (n,3n) + 4 MT = 22 Q = -3.93003E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 491190 : (n,nalpha) + 5 MT = 28 Q = -6.57271E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 50122.82c : (n,np) + 6 MT = 51 Q = -1.60300E-01 MeV Emin = 1.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -5.41799E-01 MeV Emin = 5.44833E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -7.12799E-01 MeV Emin = 7.12500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -1.03020E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -1.08860E+00 MeV Emin = 1.08280E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -1.18130E+00 MeV Emin = 1.18968E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -1.26090E+00 MeV Emin = 1.25000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -1.33740E+00 MeV Emin = 1.33151E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 91 Q = -1.33800E+00 MeV Emin = 1.34869E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 15 MT = 102 Q = 6.46843E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 51124.82c : (n,gamma) + 16 MT = 103 Q = -6.27629E-01 MeV Emin = 1.46460E+00 MeV frac = 1.00000E+00 Product nuclide = 50123.82c : (n,p) + 17 MT = 104 Q = -4.34810E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 50122.82c : (n,d) + 18 MT = 105 Q = -6.89017E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 501210 : (n,t) + 19 MT = 107 Q = 1.91765E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 491200 : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = -3.93003E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -6.57271E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -6.27629E-01 MeV Emin = 1.46460E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -4.34810E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -6.89017E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 107 Q = 1.91765E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.46460E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.00000E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 1.50000E-01 MeV : total inelastic scattering + + Nuclide 153 / 1657 : 51124.82c -- antimony 124 (Sb-124) + + Pointers : 1269919 32299 + Primary type : Transport + Nuclide ZAI : 511240 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Sb124.ACE + Atomic weight (AW) : 123.90642 + Atomic weight ratio (AWR) : 122.84200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 5.20E+06 seconds (60.2 days) + Specific ingestion toxicity : 2.50E-09 Sv/Bq + Specific inhalation toxicity : 8.60E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 16 reaction channels + - 6 special reactions + - 6 transmutation reactions + - 5 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 16 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -1.07000E-02 MeV Emin = 1.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -3.50000E-02 MeV Emin = 3.31803E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -4.08000E-02 MeV Emin = 3.82085E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -7.71000E-02 MeV Emin = 7.42620E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -8.07000E-02 MeV Emin = 8.03742E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -8.76000E-02 MeV Emin = 8.56667E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 57 Q = -1.04000E-01 MeV Emin = 1.04134E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 9 MT = 58 Q = -1.32000E-01 MeV Emin = 1.24802E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 10 MT = 91 Q = -1.40860E-01 MeV Emin = 1.37537E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 11 MT = 102 Q = 8.77000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 51125.82c : (n,gamma) + 12 MT = 103 Q = 1.40880E+00 MeV Emin = 4.55661E-02 MeV frac = 1.00000E+00 Product nuclide = 50124.82c : (n,p) + 13 MT = 104 Q = -4.85490E+00 MeV Emin = 4.89442E+00 MeV frac = 1.00000E+00 Product nuclide = 50123.82c : (n,d) + 14 MT = 105 Q = -4.54380E+00 MeV Emin = 4.58079E+00 MeV frac = 1.00000E+00 Product nuclide = 50122.82c : (n,t) + 15 MT = 107 Q = 3.87380E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 491210 : (n,alpha) + 16 MT = 111 Q = -1.06760E+01 MeV Emin = 1.07629E+01 MeV frac = 1.00000E+00 Product nuclide = 491230 : (n,2p) + + 5 additional transport branches: + + 1 MT = 103 Q = 1.40880E+00 MeV Emin = 4.55661E-02 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -4.85490E+00 MeV Emin = 4.89442E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -4.54380E+00 MeV Emin = 4.58079E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 107 Q = 3.87380E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 5 MT = 111 Q = -1.06760E+01 MeV Emin = 1.07629E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.55661E-02 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 4.89442E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 4.58079E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 1.00000E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.90430E+00 MeV frac = 1.00000E+00 Product nuclide = 52124.82c : beta- + + Nuclide 154 / 1657 : 51125.82c -- antimony 125 (Sb-125) + + Pointers : 1276247 32345 + Primary type : Transport + Nuclide ZAI : 511250 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Sb125.ACE + Atomic weight (AW) : 124.90500 + Atomic weight ratio (AWR) : 123.83200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 8.71E+07 seconds (2.76 years) + Specific ingestion toxicity : 1.10E-09 Sv/Bq + Specific inhalation toxicity : 1.20E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 28 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 6 transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 28 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -3.31900E-01 MeV Emin = 3.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -6.43000E-01 MeV Emin = 5.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -9.21600E-01 MeV Emin = 8.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -1.06660E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -1.08890E+00 MeV Emin = 1.08926E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -1.34920E+00 MeV Emin = 1.30000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 57 Q = -1.41950E+00 MeV Emin = 1.40475E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 9 MT = 58 Q = -1.48390E+00 MeV Emin = 1.47458E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 10 MT = 59 Q = -1.56000E+00 MeV Emin = 1.54441E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 11 MT = 60 Q = -1.59100E+00 MeV Emin = 1.60000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 12 MT = 61 Q = -1.66000E+00 MeV Emin = 1.64048E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 13 MT = 62 Q = -1.70080E+00 MeV Emin = 1.69395E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 14 MT = 63 Q = -1.73600E+00 MeV Emin = 1.73227E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 15 MT = 64 Q = -1.80570E+00 MeV Emin = 1.81450E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 16 MT = 65 Q = -1.80571E+00 MeV Emin = 1.81450E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 17 MT = 66 Q = -1.88990E+00 MeV Emin = 1.89165E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 18 MT = 67 Q = -1.91350E+00 MeV Emin = 1.92732E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 19 MT = 68 Q = -1.94730E+00 MeV Emin = 1.94516E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 20 MT = 69 Q = -1.98210E+00 MeV Emin = 1.98056E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 21 MT = 91 Q = -1.98211E+00 MeV Emin = 1.99953E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 22 MT = 102 Q = 6.19000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 51126.82c : (n,gamma) + 23 MT = 103 Q = -1.56680E+00 MeV Emin = 1.54441E+00 MeV frac = 1.00000E+00 Product nuclide = 50125.82c : (n,p) + 24 MT = 104 Q = -5.07450E+00 MeV Emin = 5.11548E+00 MeV frac = 1.00000E+00 Product nuclide = 50124.82c : (n,d) + 25 MT = 105 Q = -7.30650E+00 MeV Emin = 7.36550E+00 MeV frac = 1.00000E+00 Product nuclide = 50123.82c : (n,t) + 26 MT = 106 Q = -1.16680E+01 MeV Emin = 1.17622E+01 MeV frac = 1.00000E+00 Product nuclide = 491230 : (n,He-3) + 27 MT = 107 Q = 9.94120E-01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 491220 : (n,alpha) + 28 MT = 111 Q = -1.36540E+01 MeV Emin = 1.37643E+01 MeV frac = 1.00000E+00 Product nuclide = 491240 : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = -1.56680E+00 MeV Emin = 1.54441E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -5.07450E+00 MeV Emin = 5.11548E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -7.30650E+00 MeV Emin = 7.36550E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -1.16680E+01 MeV Emin = 1.17622E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 9.94120E-01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -1.36540E+01 MeV Emin = 1.37643E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.54441E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.11548E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 7.36550E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.17622E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 3.00000E-01 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 1 Q = 7.66700E-01 MeV frac = 7.69044E-01 Product nuclide = 52125.82c : beta- + 2 RTYP = 1 Q = 6.21869E-01 MeV frac = 2.30956E-01 Product nuclide = 521251 : beta- + + Nuclide 155 / 1657 : 51126.82c -- antimony 126 (Sb-126) + + Pointers : 1281112 32391 + Primary type : Transport + Nuclide ZAI : 511260 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Sb126.ACE + Atomic weight (AW) : 125.90761 + Atomic weight ratio (AWR) : 124.82600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.07E+06 seconds (12.4 days) + Specific ingestion toxicity : 2.40E-09 Sv/Bq + Specific inhalation toxicity : 3.20E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 14 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 6 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 14 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -1.77000E-02 MeV Emin = 1.68617E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -8.31000E-02 MeV Emin = 7.95452E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -1.05000E-01 MeV Emin = 1.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -1.05001E-01 MeV Emin = 1.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -3.67050E-01 MeV Emin = 3.54692E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 91 Q = -1.98400E-01 MeV Emin = 1.84500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 8 MT = 102 Q = 8.31000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 511270 : (n,gamma) + 9 MT = 103 Q = 4.04520E-01 MeV Emin = 4.76810E-02 MeV frac = 1.00000E+00 Product nuclide = 50126.82c : (n,p) + 10 MT = 104 Q = -5.56230E+00 MeV Emin = 5.60686E+00 MeV frac = 1.00000E+00 Product nuclide = 50125.82c : (n,d) + 11 MT = 105 Q = -5.03830E+00 MeV Emin = 5.07866E+00 MeV frac = 1.00000E+00 Product nuclide = 50124.82c : (n,t) + 12 MT = 106 Q = -1.21580E+01 MeV Emin = 1.22554E+01 MeV frac = 1.00000E+00 Product nuclide = 491240 : (n,He-3) + 13 MT = 107 Q = 2.68350E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 491230 : (n,alpha) + 14 MT = 111 Q = -1.24040E+01 MeV Emin = 1.25034E+01 MeV frac = 1.00000E+00 Product nuclide = 491250 : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = 4.04520E-01 MeV Emin = 4.76810E-02 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -5.56230E+00 MeV Emin = 5.60686E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -5.03830E+00 MeV Emin = 5.07866E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -1.21580E+01 MeV Emin = 1.22554E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 2.68350E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -1.24040E+01 MeV Emin = 1.25034E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.76810E-02 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.60686E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 5.07866E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.22554E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 1.68617E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.67200E+00 MeV frac = 1.00000E+00 Product nuclide = 52126.82c : beta- + + Nuclide 156 / 1657 : 52120.82c -- tellurium 120 (Te-120) + + Pointers : 1305439 34461 + Primary type : Transport + Nuclide ZAI : 521200 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Te120.ACE + Atomic weight (AW) : 119.90000 + Atomic weight ratio (AWR) : 118.87000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 9 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 9 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 91 Q = -4.96000E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 3 MT = 102 Q = 7.17600E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 521210 : (n,gamma) + 4 MT = 103 Q = -2.00270E-01 MeV Emin = 2.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 511200 : (n,p) + 5 MT = 104 Q = -4.98350E+00 MeV Emin = 5.02543E+00 MeV frac = 1.00000E+00 Product nuclide = 511190 : (n,d) + 6 MT = 105 Q = -8.31210E+00 MeV Emin = 8.38203E+00 MeV frac = 1.00000E+00 Product nuclide = 511180 : (n,t) + 7 MT = 106 Q = -4.60870E+00 MeV Emin = 4.64747E+00 MeV frac = 1.00000E+00 Product nuclide = 50118.82c : (n,He-3) + 8 MT = 107 Q = 6.63910E+00 MeV Emin = 4.51500E-02 MeV frac = 1.00000E+00 Product nuclide = 50117.82c : (n,alpha) + 9 MT = 111 Q = -5.84170E+00 MeV Emin = 5.89084E+00 MeV frac = 1.00000E+00 Product nuclide = 50119.82c : (n,2p) + + 7 additional transport branches: + + 1 MT = 102 Q = 7.17600E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 521211 : (n,gamma) + 2 MT = 103 Q = -2.00270E-01 MeV Emin = 2.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 104 Q = -4.98350E+00 MeV Emin = 5.02543E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 4 MT = 105 Q = -8.31210E+00 MeV Emin = 8.38203E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 5 MT = 106 Q = -4.60870E+00 MeV Emin = 4.64747E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 6 MT = 107 Q = 6.63910E+00 MeV Emin = 4.51500E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 7 MT = 111 Q = -5.84170E+00 MeV Emin = 5.89084E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.00000E-01 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.02543E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 8.38203E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 4.64747E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.51500E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 5.00000E-01 MeV : total inelastic scattering + + Nuclide 157 / 1657 : 52122.82c -- tellurium 122 (Te-122) + + Pointers : 1309099 34507 + Primary type : Transport + Nuclide ZAI : 521220 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Te122.ACE + Atomic weight (AW) : 121.90321 + Atomic weight ratio (AWR) : 120.85600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 13 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 13 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -5.64000E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -1.17000E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -1.25000E+00 MeV Emin = 1.23391E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -1.35000E+00 MeV Emin = 1.36000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 91 Q = -1.98350E+00 MeV Emin = 1.90000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 7 MT = 102 Q = 6.92990E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 52123.82c : (n,gamma) + 8 MT = 103 Q = -1.19760E+00 MeV Emin = 1.20733E+00 MeV frac = 1.00000E+00 Product nuclide = 511220 : (n,p) + 9 MT = 104 Q = -5.77790E+00 MeV Emin = 5.82571E+00 MeV frac = 1.00000E+00 Product nuclide = 51121.82c : (n,d) + 10 MT = 105 Q = -8.75800E+00 MeV Emin = 8.83047E+00 MeV frac = 1.00000E+00 Product nuclide = 511200 : (n,t) + 11 MT = 106 Q = -6.06000E+00 MeV Emin = 6.11014E+00 MeV frac = 1.00000E+00 Product nuclide = 50120.82c : (n,He-3) + 12 MT = 107 Q = 5.40730E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 50119.82c : (n,alpha) + 13 MT = 111 Q = -7.60600E+00 MeV Emin = 7.66894E+00 MeV frac = 1.00000E+00 Product nuclide = 501210 : (n,2p) + + 7 additional transport branches: + + 1 MT = 102 Q = 6.92990E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 521231 : (n,gamma) + 2 MT = 103 Q = -1.19760E+00 MeV Emin = 1.20733E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 104 Q = -5.77790E+00 MeV Emin = 5.82571E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 4 MT = 105 Q = -8.75800E+00 MeV Emin = 8.83047E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 5 MT = 106 Q = -6.06000E+00 MeV Emin = 6.11014E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 6 MT = 107 Q = 5.40730E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 7 MT = 111 Q = -7.60600E+00 MeV Emin = 7.66894E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.20733E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.82571E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 8.83047E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 6.11014E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.62500E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 5.00000E-01 MeV : total inelastic scattering + + Nuclide 158 / 1657 : 52123.82c -- tellurium 123 (Te-123) + + Pointers : 1311200 34553 + Primary type : Transport + Nuclide ZAI : 521230 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Te123.ACE + Atomic weight (AW) : 122.90482 + Atomic weight ratio (AWR) : 121.84900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.90E+24 seconds (9.21E+16 years) + Specific ingestion toxicity : 4.40E-09 Sv/Bq + Specific inhalation toxicity : 3.90E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 17 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 6 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 17 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -1.59000E-01 MeV Emin = 1.52762E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -2.48000E-01 MeV Emin = 2.43510E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -4.40000E-01 MeV Emin = 4.06805E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -5.10000E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -6.90000E-01 MeV Emin = 6.50293E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -7.00000E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 57 Q = -7.80000E-01 MeV Emin = 7.46073E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 9 MT = 58 Q = -8.90000E-01 MeV Emin = 8.41851E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 10 MT = 91 Q = -8.92680E-01 MeV Emin = 8.98652E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 11 MT = 102 Q = 9.42380E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 52124.82c : (n,gamma) + 12 MT = 103 Q = 8.34390E-01 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 51123.82c : (n,p) + 13 MT = 104 Q = -5.90440E+00 MeV Emin = 5.95286E+00 MeV frac = 1.00000E+00 Product nuclide = 511220 : (n,d) + 14 MT = 105 Q = -6.45290E+00 MeV Emin = 6.50586E+00 MeV frac = 1.00000E+00 Product nuclide = 51121.82c : (n,t) + 15 MT = 106 Q = -6.82120E+00 MeV Emin = 6.87718E+00 MeV frac = 1.00000E+00 Product nuclide = 501210 : (n,He-3) + 16 MT = 107 Q = 7.58020E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 50120.82c : (n,alpha) + 17 MT = 111 Q = -5.72390E+00 MeV Emin = 5.77088E+00 MeV frac = 1.00000E+00 Product nuclide = 50122.82c : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = 8.34390E-01 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -5.90440E+00 MeV Emin = 5.95286E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -6.45290E+00 MeV Emin = 6.50586E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -6.82120E+00 MeV Emin = 6.87718E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 7.58020E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -5.72390E+00 MeV Emin = 5.77088E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.62500E-02 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.95286E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 6.50586E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 6.87718E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.62500E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 1.52762E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 2 Q = 5.22000E-02 MeV frac = 1.00000E+00 Product nuclide = 51123.82c : EC/beta+ + + Nuclide 159 / 1657 : 52124.82c -- tellurium 124 (Te-124) + + Pointers : 1314202 34599 + Primary type : Transport + Nuclide ZAI : 521240 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Te124.ACE + Atomic weight (AW) : 123.90340 + Atomic weight ratio (AWR) : 122.83900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 20 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 20 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -6.03000E-01 MeV Emin = 5.53955E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -1.16000E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -1.25000E+00 MeV Emin = 1.25512E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -1.33000E+00 MeV Emin = 1.29796E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -1.66000E+00 MeV Emin = 1.60000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -1.75000E+00 MeV Emin = 1.71886E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 57 Q = -1.88000E+00 MeV Emin = 1.82977E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 9 MT = 58 Q = -1.96000E+00 MeV Emin = 1.94765E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 10 MT = 59 Q = -2.02000E+00 MeV Emin = 2.03645E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 11 MT = 60 Q = -2.04000E+00 MeV Emin = 2.05661E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 12 MT = 61 Q = -2.09000E+00 MeV Emin = 2.10702E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 13 MT = 91 Q = -2.08310E+00 MeV Emin = 2.10006E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 14 MT = 102 Q = 6.58490E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 52125.82c : (n,gamma) + 15 MT = 103 Q = -2.12160E+00 MeV Emin = 2.13887E+00 MeV frac = 1.00000E+00 Product nuclide = 51124.82c : (n,p) + 16 MT = 104 Q = -6.36280E+00 MeV Emin = 6.41460E+00 MeV frac = 1.00000E+00 Product nuclide = 51123.82c : (n,d) + 17 MT = 105 Q = -9.06990E+00 MeV Emin = 9.14374E+00 MeV frac = 1.00000E+00 Product nuclide = 511220 : (n,t) + 18 MT = 106 Q = -7.42970E+00 MeV Emin = 7.49018E+00 MeV frac = 1.00000E+00 Product nuclide = 50122.82c : (n,He-3) + 19 MT = 107 Q = 4.32850E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 501210 : (n,alpha) + 20 MT = 111 Q = -9.20050E+00 MeV Emin = 9.27540E+00 MeV frac = 1.00000E+00 Product nuclide = 50123.82c : (n,2p) + + 7 additional transport branches: + + 1 MT = 102 Q = 6.58490E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 521251 : (n,gamma) + 2 MT = 103 Q = -2.12160E+00 MeV Emin = 2.13887E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 104 Q = -6.36280E+00 MeV Emin = 6.41460E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 4 MT = 105 Q = -9.06990E+00 MeV Emin = 9.14374E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 5 MT = 106 Q = -7.42970E+00 MeV Emin = 7.49018E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 6 MT = 107 Q = 4.32850E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 7 MT = 111 Q = -9.20050E+00 MeV Emin = 9.27540E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.13887E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.41460E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.14374E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 7.49018E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.62500E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 5.53955E-01 MeV : total inelastic scattering + + Nuclide 160 / 1657 : 52125.82c -- tellurium 125 (Te-125) + + Pointers : 1316814 34645 + Primary type : Transport + Nuclide ZAI : 521250 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Te125.ACE + Atomic weight (AW) : 124.90399 + Atomic weight ratio (AWR) : 123.83100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 15 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 15 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -3.55000E-02 MeV Emin = 3.38136E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -1.98400E-01 MeV Emin = 1.86542E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -3.21000E-01 MeV Emin = 2.92693E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -4.43000E-01 MeV Emin = 4.42555E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -4.63000E-01 MeV Emin = 4.54647E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -5.25000E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 91 Q = -6.94390E-01 MeV Emin = 6.58750E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 9 MT = 102 Q = 9.10930E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 52126.82c : (n,gamma) + 10 MT = 103 Q = 1.56250E-02 MeV Emin = 4.64468E-02 MeV frac = 1.00000E+00 Product nuclide = 51125.82c : (n,p) + 11 MT = 104 Q = -6.46770E+00 MeV Emin = 6.51993E+00 MeV frac = 1.00000E+00 Product nuclide = 51124.82c : (n,d) + 12 MT = 105 Q = -6.67730E+00 MeV Emin = 6.73122E+00 MeV frac = 1.00000E+00 Product nuclide = 51123.82c : (n,t) + 13 MT = 106 Q = -8.05520E+00 MeV Emin = 8.12025E+00 MeV frac = 1.00000E+00 Product nuclide = 50123.82c : (n,He-3) + 14 MT = 107 Q = 6.57120E+00 MeV Emin = 4.64468E-02 MeV frac = 1.00000E+00 Product nuclide = 50122.82c : (n,alpha) + 15 MT = 111 Q = -7.28290E+00 MeV Emin = 7.34171E+00 MeV frac = 1.00000E+00 Product nuclide = 50124.82c : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = 1.56250E-02 MeV Emin = 4.64468E-02 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -6.46770E+00 MeV Emin = 6.51993E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -6.67730E+00 MeV Emin = 6.73122E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -8.05520E+00 MeV Emin = 8.12025E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 6.57120E+00 MeV Emin = 4.64468E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -7.28290E+00 MeV Emin = 7.34171E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.64468E-02 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.51993E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 6.73122E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 8.12025E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.64468E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 3.38136E-02 MeV : total inelastic scattering + + Nuclide 161 / 1657 : 52126.82c -- tellurium 126 (Te-126) + + Pointers : 1319382 34691 + Primary type : Transport + Nuclide ZAI : 521260 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Te126.ACE + Atomic weight (AW) : 125.90358 + Atomic weight ratio (AWR) : 124.82200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 22 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 22 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -6.66000E-01 MeV Emin = 5.85670E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -1.36000E+00 MeV Emin = 1.20560E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -1.40000E+00 MeV Emin = 1.20560E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -1.42000E+00 MeV Emin = 1.42231E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -1.68000E+00 MeV Emin = 1.60000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -1.78000E+00 MeV Emin = 1.74572E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 57 Q = -1.78001E+00 MeV Emin = 1.74572E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 9 MT = 58 Q = -1.88000E+00 MeV Emin = 1.84573E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 10 MT = 59 Q = -2.01000E+00 MeV Emin = 2.02610E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 11 MT = 60 Q = -2.04000E+00 MeV Emin = 2.05634E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 12 MT = 61 Q = -2.05000E+00 MeV Emin = 2.06642E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 13 MT = 62 Q = -2.06000E+00 MeV Emin = 2.07651E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 14 MT = 63 Q = -2.08000E+00 MeV Emin = 2.09670E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 15 MT = 91 Q = -2.07340E+00 MeV Emin = 2.09001E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 16 MT = 102 Q = 6.28900E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 521270 : (n,gamma) + 17 MT = 103 Q = -2.88030E+00 MeV Emin = 2.90338E+00 MeV frac = 1.00000E+00 Product nuclide = 51126.82c : (n,p) + 18 MT = 104 Q = -6.87580E+00 MeV Emin = 6.93089E+00 MeV frac = 1.00000E+00 Product nuclide = 51125.82c : (n,d) + 19 MT = 105 Q = -9.32740E+00 MeV Emin = 9.40213E+00 MeV frac = 1.00000E+00 Product nuclide = 51124.82c : (n,t) + 20 MT = 106 Q = -8.68290E+00 MeV Emin = 8.75246E+00 MeV frac = 1.00000E+00 Product nuclide = 50124.82c : (n,He-3) + 21 MT = 107 Q = 3.40030E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 50123.82c : (n,alpha) + 22 MT = 111 Q = -1.06670E+01 MeV Emin = 1.07525E+01 MeV frac = 1.00000E+00 Product nuclide = 50125.82c : (n,2p) + + 7 additional transport branches: + + 1 MT = 102 Q = 6.28900E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 52527.82c : (n,gamma) + 2 MT = 103 Q = -2.88030E+00 MeV Emin = 2.90338E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 104 Q = -6.87580E+00 MeV Emin = 6.93089E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 4 MT = 105 Q = -9.32740E+00 MeV Emin = 9.40213E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 5 MT = 106 Q = -8.68290E+00 MeV Emin = 8.75246E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 6 MT = 107 Q = 3.40030E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 7 MT = 111 Q = -1.06670E+01 MeV Emin = 1.07525E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.90338E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.93089E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.40213E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 8.75246E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 5.85670E-01 MeV : total inelastic scattering + + Nuclide 162 / 1657 : 52527.82c -- tellurium 127m (Te-127m) + + Pointers : 1323141 34737 + Primary type : Transport + Nuclide ZAI : 521271 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Te127M.ACE + Atomic weight (AW) : 126.90518 + Atomic weight ratio (AWR) : 125.81500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 9.17E+06 seconds (106 days) + Specific ingestion toxicity : 2.30E-09 Sv/Bq + Specific inhalation toxicity : 9.80E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 3 reaction channels + - 2 special reactions + - 1 transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 91 Q = -6.94510E-01 MeV Emin = 6.58750E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 3 MT = 102 Q = 8.68000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 52128.82c : (n,gamma) + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 6.58750E-01 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 3 Q = 8.82300E-02 MeV frac = 9.72700E-01 Product nuclide = 521270 : IT + 2 RTYP = 1 Q = 7.90030E-01 MeV frac = 2.73000E-02 Product nuclide = 53127.82c : beta- + + Nuclide 163 / 1657 : 52128.82c -- tellurium 128 (Te-128) + + Pointers : 1324440 34783 + Primary type : Transport + Nuclide ZAI : 521280 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Te128.ACE + Atomic weight (AW) : 127.90477 + Atomic weight ratio (AWR) : 126.80600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 6.94E+31 seconds (2.2E+24 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 18 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 7 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 18 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -7.43200E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -1.49710E+00 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -1.52320E+00 MeV Emin = 1.52206E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -1.81110E+00 MeV Emin = 1.78769E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -1.97220E+00 MeV Emin = 1.94716E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -1.98220E+00 MeV Emin = 1.99279E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 57 Q = -2.03000E+00 MeV Emin = 2.04601E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 9 MT = 58 Q = -2.13200E+00 MeV Emin = 2.14881E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 10 MT = 59 Q = -2.13350E+00 MeV Emin = 2.15033E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 11 MT = 91 Q = -2.19700E+00 MeV Emin = 2.21433E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 12 MT = 102 Q = 6.08600E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 521290 : (n,gamma) + 13 MT = 103 Q = -3.47850E+00 MeV Emin = 3.50593E+00 MeV frac = 1.00000E+00 Product nuclide = 511280 : (n,p) + 14 MT = 104 Q = -7.35010E+00 MeV Emin = 7.40806E+00 MeV frac = 1.00000E+00 Product nuclide = 511270 : (n,d) + 15 MT = 105 Q = -9.46510E+00 MeV Emin = 9.53974E+00 MeV frac = 1.00000E+00 Product nuclide = 51126.82c : (n,t) + 16 MT = 106 Q = -9.82480E+00 MeV Emin = 9.90228E+00 MeV frac = 1.00000E+00 Product nuclide = 50126.82c : (n,He-3) + 17 MT = 107 Q = 2.55530E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 50125.82c : (n,alpha) + 18 MT = 111 Q = -1.18950E+01 MeV Emin = 1.19888E+01 MeV frac = 1.00000E+00 Product nuclide = 501270 : (n,2p) + + 7 additional transport branches: + + 1 MT = 102 Q = 6.08600E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 52529.82c : (n,gamma) + 2 MT = 103 Q = -3.47850E+00 MeV Emin = 3.50593E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 104 Q = -7.35010E+00 MeV Emin = 7.40806E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 4 MT = 105 Q = -9.46510E+00 MeV Emin = 9.53974E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 5 MT = 106 Q = -9.82480E+00 MeV Emin = 9.90228E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 6 MT = 107 Q = 2.55530E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 7 MT = 111 Q = -1.18950E+01 MeV Emin = 1.19888E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.50593E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.40806E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.53974E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 9.90228E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 7.00000E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 11 Q = 8.66500E-01 MeV frac = 1.00000E+00 Product nuclide = 54128.82c : beta- + beta- + + Nuclide 164 / 1657 : 52529.82c -- tellurium 129m (Te-129m) + + Pointers : 1328820 34829 + Primary type : Transport + Nuclide ZAI : 521291 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Te129M.ACE + Atomic weight (AW) : 128.90738 + Atomic weight ratio (AWR) : 127.80000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.90E+06 seconds (33.6 days) + Specific ingestion toxicity : 3.00E-09 Sv/Bq + Specific inhalation toxicity : 7.90E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 9 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 6 transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 9 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 91 Q = -9.92260E-01 MeV Emin = 9.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 3 MT = 102 Q = 8.41000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 52130.82c : (n,gamma) + 4 MT = 103 Q = -1.69880E+00 MeV Emin = 1.65599E+00 MeV frac = 1.00000E+00 Product nuclide = 511290 : (n,p) + 5 MT = 104 Q = -7.44370E+00 MeV Emin = 7.50195E+00 MeV frac = 1.00000E+00 Product nuclide = 511280 : (n,d) + 6 MT = 105 Q = -7.28360E+00 MeV Emin = 7.34059E+00 MeV frac = 1.00000E+00 Product nuclide = 511270 : (n,t) + 7 MT = 106 Q = -1.03680E+01 MeV Emin = 1.04491E+01 MeV frac = 1.00000E+00 Product nuclide = 501270 : (n,He-3) + 8 MT = 107 Q = 4.55690E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 50126.82c : (n,alpha) + 9 MT = 111 Q = -1.01750E+01 MeV Emin = 1.02546E+01 MeV frac = 1.00000E+00 Product nuclide = 501280 : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = -1.69880E+00 MeV Emin = 1.65599E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -7.44370E+00 MeV Emin = 7.50195E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -7.28360E+00 MeV Emin = 7.34059E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -1.03680E+01 MeV Emin = 1.04491E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 4.55690E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -1.01750E+01 MeV Emin = 1.02546E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.65599E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.50195E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 7.34059E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.04491E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.62500E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 9.25000E-01 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.60340E+00 MeV frac = 3.70000E-01 Product nuclide = 53129.82c : beta- + 2 RTYP = 3 Q = 1.05500E-01 MeV frac = 6.30000E-01 Product nuclide = 521290 : IT + + Nuclide 165 / 1657 : 52130.82c -- tellurium 130 (Te-130) + + Pointers : 1332186 34875 + Primary type : Transport + Nuclide ZAI : 521300 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Te130.ACE + Atomic weight (AW) : 129.90596 + Atomic weight ratio (AWR) : 128.79000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.49E+28 seconds (7.91E+20 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 19 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 7 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 19 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -8.40000E-01 MeV Emin = 8.09890E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -1.60000E+00 MeV Emin = 1.60000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -1.63000E+00 MeV Emin = 1.63636E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -1.81000E+00 MeV Emin = 1.80391E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -1.88000E+00 MeV Emin = 1.85178E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -1.97000E+00 MeV Emin = 1.94753E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 57 Q = -1.98000E+00 MeV Emin = 1.94753E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 9 MT = 58 Q = -2.10000E+00 MeV Emin = 2.11631E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 10 MT = 59 Q = -2.19000E+00 MeV Emin = 2.20701E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 11 MT = 60 Q = -2.19001E+00 MeV Emin = 2.20702E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 12 MT = 91 Q = -2.18310E+00 MeV Emin = 2.20005E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 13 MT = 102 Q = 5.92700E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 521310 : (n,gamma) + 14 MT = 103 Q = -4.18400E+00 MeV Emin = 4.21649E+00 MeV frac = 1.00000E+00 Product nuclide = 511300 : (n,p) + 15 MT = 104 Q = -7.77960E+00 MeV Emin = 7.84001E+00 MeV frac = 1.00000E+00 Product nuclide = 511290 : (n,d) + 16 MT = 105 Q = -9.49280E+00 MeV Emin = 9.56651E+00 MeV frac = 1.00000E+00 Product nuclide = 511280 : (n,t) + 17 MT = 106 Q = -1.07640E+01 MeV Emin = 1.08476E+01 MeV frac = 1.00000E+00 Product nuclide = 501280 : (n,He-3) + 18 MT = 107 Q = 1.89780E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 501270 : (n,alpha) + 19 MT = 111 Q = -1.32100E+01 MeV Emin = 1.33126E+01 MeV frac = 1.00000E+00 Product nuclide = 501290 : (n,2p) + + 7 additional transport branches: + + 1 MT = 102 Q = 5.92700E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 521311 : (n,gamma) + 2 MT = 103 Q = -4.18400E+00 MeV Emin = 4.21649E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 104 Q = -7.77960E+00 MeV Emin = 7.84001E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 4 MT = 105 Q = -9.49280E+00 MeV Emin = 9.56651E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 5 MT = 106 Q = -1.07640E+01 MeV Emin = 1.08476E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 6 MT = 107 Q = 1.89780E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 7 MT = 111 Q = -1.32100E+01 MeV Emin = 1.33126E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.21649E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.84001E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.56651E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.08476E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 8.09890E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 11 Q = 2.52751E+00 MeV frac = 1.00000E+00 Product nuclide = 54130.82c : beta- + beta- + + Nuclide 166 / 1657 : 52132.82c -- tellurium 132 (Te-132) + + Pointers : 1338483 34921 + Primary type : Transport + Nuclide ZAI : 521320 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Te132.ACE + Atomic weight (AW) : 131.90816 + Atomic weight ratio (AWR) : 130.77500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.79E+05 seconds (3.23 days) + Specific ingestion toxicity : 3.80E-09 Sv/Bq + Specific inhalation toxicity : 2.00E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 15 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 7 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 15 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -9.75000E-01 MeV Emin = 9.11845E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -1.67000E+00 MeV Emin = 1.60000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -1.78000E+00 MeV Emin = 1.74520E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -1.98480E+00 MeV Emin = 1.89681E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -2.05000E+00 MeV Emin = 2.06570E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -2.11000E+00 MeV Emin = 2.12614E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 91 Q = -2.10390E+00 MeV Emin = 2.12000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 9 MT = 102 Q = 5.81000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 521330 : (n,gamma) + 10 MT = 103 Q = -4.81870E+00 MeV Emin = 4.85555E+00 MeV frac = 1.00000E+00 Product nuclide = 511320 : (n,p) + 11 MT = 104 Q = -8.17440E+00 MeV Emin = 8.23691E+00 MeV frac = 1.00000E+00 Product nuclide = 511310 : (n,d) + 12 MT = 105 Q = -9.70770E+00 MeV Emin = 9.78193E+00 MeV frac = 1.00000E+00 Product nuclide = 511300 : (n,t) + 13 MT = 106 Q = -1.16890E+01 MeV Emin = 1.17784E+01 MeV frac = 1.00000E+00 Product nuclide = 501300 : (n,He-3) + 14 MT = 107 Q = 1.07310E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 501290 : (n,alpha) + 15 MT = 111 Q = -1.42350E+01 MeV Emin = 1.43439E+01 MeV frac = 1.00000E+00 Product nuclide = 501310 : (n,2p) + + 7 additional transport branches: + + 1 MT = 102 Q = 5.81000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 521331 : (n,gamma) + 2 MT = 103 Q = -4.81870E+00 MeV Emin = 4.85555E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 104 Q = -8.17440E+00 MeV Emin = 8.23691E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 4 MT = 105 Q = -9.70770E+00 MeV Emin = 9.78193E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 5 MT = 106 Q = -1.16890E+01 MeV Emin = 1.17784E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 6 MT = 107 Q = 1.07310E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 7 MT = 111 Q = -1.42350E+01 MeV Emin = 1.43439E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.85555E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.23691E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.78193E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.17784E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 9.11845E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.18000E-01 MeV frac = 1.00000E+00 Product nuclide = 531320 : beta- + + Nuclide 167 / 1657 : 53127.82c -- iodine 127 (I-127) + + Pointers : 1354394 26411 + Primary type : Transport + Nuclide ZAI : 531270 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/I127.ACE + Atomic weight (AW) : 126.90448 + Atomic weight ratio (AWR) : 125.81430 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 3.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 43 reaction channels + - 92 special reactions + - 23 transmutation reactions + - 26 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 43 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 11 Q = -1.96711E+01 MeV Emin = 1.98275E+01 MeV frac = 1.00000E+00 Product nuclide = self : (n,2nd) + 3 MT = 16 Q = -9.14344E+00 MeV Emin = 9.21612E+00 MeV frac = 1.00000E+00 Product nuclide = 531260 : (n,2n) + 4 MT = 17 Q = -1.62877E+01 MeV Emin = 1.64172E+01 MeV frac = 1.00000E+00 Product nuclide = 531250 : (n,3n) + 5 MT = 22 Q = -2.18950E+00 MeV Emin = 2.20690E+00 MeV frac = 1.00000E+00 Product nuclide = 51123.82c : (n,nalpha) + 6 MT = 24 Q = -1.11548E+01 MeV Emin = 1.12435E+01 MeV frac = 1.00000E+00 Product nuclide = 511220 : (n,2nalpha) + 7 MT = 25 Q = -1.79617E+01 MeV Emin = 1.81045E+01 MeV frac = 1.00000E+00 Product nuclide = 51121.82c : (n,3nalpha) + 8 MT = 28 Q = -6.20576E+00 MeV Emin = 6.25509E+00 MeV frac = 1.00000E+00 Product nuclide = 52126.82c : (n,np) + 9 MT = 32 Q = -1.30950E+01 MeV Emin = 1.31991E+01 MeV frac = 1.00000E+00 Product nuclide = 52125.82c : (n,nd) + 10 MT = 33 Q = -1.34138E+01 MeV Emin = 1.35204E+01 MeV frac = 1.00000E+00 Product nuclide = 52124.82c : (n,nt) + 11 MT = 34 Q = -1.62997E+01 MeV Emin = 1.64293E+01 MeV frac = 1.00000E+00 Product nuclide = 51124.82c : (n,nHe-3) + 12 MT = 37 Q = -2.58376E+01 MeV Emin = 2.60430E+01 MeV frac = 1.00000E+00 Product nuclide = cut: I-124 : (n,4n) + 13 MT = 41 Q = -1.53196E+01 MeV Emin = 1.54414E+01 MeV frac = 1.00000E+00 Product nuclide = 52125.82c : (n,2np) + 14 MT = 42 Q = -2.18956E+01 MeV Emin = 2.20697E+01 MeV frac = 1.00000E+00 Product nuclide = cut: Te-124 : (n,3np) + 15 MT = 44 Q = -1.53039E+01 MeV Emin = 1.54256E+01 MeV frac = 1.00000E+00 Product nuclide = 51125.82c : (n,n2p) + 16 MT = 45 Q = -8.75604E+00 MeV Emin = 8.82564E+00 MeV frac = 1.00000E+00 Product nuclide = 50122.82c : (n,npalpha) + 17 MT = 51 Q = -5.76080E-02 MeV Emin = 5.78370E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 18 MT = 52 Q = -2.02860E-01 MeV Emin = 2.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 19 MT = 53 Q = -2.95000E-01 MeV Emin = 2.91725E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 20 MT = 54 Q = -3.74992E-01 MeV Emin = 3.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 21 MT = 55 Q = -4.17990E-01 MeV Emin = 4.10656E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 22 MT = 56 Q = -4.73000E-01 MeV Emin = 4.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 23 MT = 57 Q = -6.18310E-01 MeV Emin = 6.14357E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 24 MT = 58 Q = -6.28690E-01 MeV Emin = 6.28456E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 25 MT = 59 Q = -6.50920E-01 MeV Emin = 6.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 26 MT = 60 Q = -7.16500E-01 MeV Emin = 7.17365E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 27 MT = 61 Q = -7.44710E-01 MeV Emin = 7.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 28 MT = 62 Q = -8.31000E-01 MeV Emin = 8.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 29 MT = 63 Q = -8.83000E-01 MeV Emin = 8.89119E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 30 MT = 64 Q = -9.90940E-01 MeV Emin = 9.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 31 MT = 65 Q = -1.04410E+00 MeV Emin = 1.05000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 32 MT = 91 Q = -1.04410E+00 MeV Emin = 1.05000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 33 MT = 102 Q = 6.82614E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 531280 : (n,gamma) + 34 MT = 103 Q = 8.47855E-02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 521270 : (n,p) + 35 MT = 104 Q = -3.98118E+00 MeV Emin = 4.01283E+00 MeV frac = 1.00000E+00 Product nuclide = 52126.82c : (n,d) + 36 MT = 105 Q = -6.83776E+00 MeV Emin = 6.89211E+00 MeV frac = 1.00000E+00 Product nuclide = 52125.82c : (n,t) + 37 MT = 106 Q = -7.58587E+00 MeV Emin = 7.64617E+00 MeV frac = 1.00000E+00 Product nuclide = 51125.82c : (n,He-3) + 38 MT = 107 Q = 4.27795E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 51124.82c : (n,alpha) + 39 MT = 111 Q = -9.09592E+00 MeV Emin = 9.16822E+00 MeV frac = 1.00000E+00 Product nuclide = 51126.82c : (n,2p) + 40 MT = 112 Q = -2.81017E+00 MeV Emin = 2.83251E+00 MeV frac = 1.00000E+00 Product nuclide = 50123.82c : (n,palpha) + 41 MT = 115 Q = -1.30794E+01 MeV Emin = 1.31834E+01 MeV frac = 1.00000E+00 Product nuclide = 51125.82c : (n,pd) + 42 MT = 116 Q = -1.55359E+01 MeV Emin = 1.56594E+01 MeV frac = 1.00000E+00 Product nuclide = 51124.82c : (n,pt) + 43 MT = 117 Q = -6.53147E+00 MeV Emin = 6.58338E+00 MeV frac = 1.00000E+00 Product nuclide = 50122.82c : (n,dalpha) + + 26 additional transport branches: + + 1 MT = 22 Q = -2.18950E+00 MeV Emin = 2.20690E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 24 Q = -1.11548E+01 MeV Emin = 1.12435E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,2nalpha) + 3 MT = 25 Q = -1.79617E+01 MeV Emin = 1.81045E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,3nalpha) + 4 MT = 28 Q = -6.20576E+00 MeV Emin = 6.25509E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 5 MT = 32 Q = -1.30950E+01 MeV Emin = 1.31991E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 6 MT = 33 Q = -1.34138E+01 MeV Emin = 1.35204E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 7 MT = 34 Q = -1.62997E+01 MeV Emin = 1.64293E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,nHe-3) + 8 MT = 41 Q = -1.53196E+01 MeV Emin = 1.54414E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,2np) + 9 MT = 42 Q = -2.18956E+01 MeV Emin = 2.20697E+01 MeV frac = 1.00000E+00 Product nuclide = cut: H-1 : (n,3np) + 10 MT = 44 Q = -1.53039E+01 MeV Emin = 1.54256E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,n2p) + 11 MT = 45 Q = -8.75604E+00 MeV Emin = 8.82564E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,npalpha) + 12 MT = 45 Q = -8.75604E+00 MeV Emin = 8.82564E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,npalpha) + 13 MT = 103 Q = 8.47855E-02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 14 MT = 104 Q = -3.98118E+00 MeV Emin = 4.01283E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 15 MT = 105 Q = -6.83776E+00 MeV Emin = 6.89211E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 16 MT = 106 Q = -7.58587E+00 MeV Emin = 7.64617E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 17 MT = 107 Q = 4.27795E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 18 MT = 111 Q = -9.09592E+00 MeV Emin = 9.16822E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + 19 MT = 112 Q = -2.81017E+00 MeV Emin = 2.83251E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,palpha) + 20 MT = 112 Q = -2.81017E+00 MeV Emin = 2.83251E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,palpha) + 21 MT = 115 Q = -1.30794E+01 MeV Emin = 1.31834E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,pd) + 22 MT = 115 Q = -1.30794E+01 MeV Emin = 1.31834E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,pd) + 23 MT = 116 Q = -1.55359E+01 MeV Emin = 1.56594E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,pt) + 24 MT = 116 Q = -1.55359E+01 MeV Emin = 1.56594E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,pt) + 25 MT = 117 Q = -6.53147E+00 MeV Emin = 6.58338E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,dalpha) + 26 MT = 117 Q = -6.53147E+00 MeV Emin = 6.58338E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,dalpha) + + 92 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 4.01283E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 6.89211E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 7.64617E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 600 Q = 8.47855E-02 MeV Emin = 1.20000E+00 MeV : (n,p) to ground state + 8 MT = 601 Q = 2.36655E-02 MeV Emin = 1.20000E+00 MeV : (n,p1) + 9 MT = 602 Q = -3.47454E-03 MeV Emin = 1.20000E+00 MeV : (n,p2) + 10 MT = 603 Q = -2.55815E-01 MeV Emin = 1.40000E+00 MeV : (n,p3) + 11 MT = 604 Q = -2.81215E-01 MeV Emin = 1.50000E+00 MeV : (n,p4) + 12 MT = 605 Q = -3.88485E-01 MeV Emin = 1.60000E+00 MeV : (n,p5) + 13 MT = 606 Q = -4.18115E-01 MeV Emin = 1.60000E+00 MeV : (n,p6) + 14 MT = 607 Q = -5.18215E-01 MeV Emin = 1.70000E+00 MeV : (n,p7) + 15 MT = 608 Q = -5.46715E-01 MeV Emin = 1.80000E+00 MeV : (n,p8) + 16 MT = 609 Q = -5.47715E-01 MeV Emin = 1.80000E+00 MeV : (n,p9) + 17 MT = 610 Q = -6.00715E-01 MeV Emin = 1.80000E+00 MeV : (n,p10) + 18 MT = 611 Q = -6.78915E-01 MeV Emin = 1.90000E+00 MeV : (n,p11) + 19 MT = 612 Q = -6.98615E-01 MeV Emin = 2.00000E+00 MeV : (n,p12) + 20 MT = 613 Q = -7.00915E-01 MeV Emin = 2.00000E+00 MeV : (n,p13) + 21 MT = 614 Q = -8.39715E-01 MeV Emin = 2.00000E+00 MeV : (n,p14) + 22 MT = 615 Q = -8.81215E-01 MeV Emin = 2.00000E+00 MeV : (n,p15) + 23 MT = 649 Q = -8.81215E-01 MeV Emin = 8.69109E-01 MeV : (n,p) to continuum + 24 MT = 650 Q = -3.98118E+00 MeV Emin = 4.01283E+00 MeV : (n,d) to ground state + 25 MT = 651 Q = -4.64752E+00 MeV Emin = 4.68446E+00 MeV : (n,d1) + 26 MT = 652 Q = -5.34261E+00 MeV Emin = 5.38508E+00 MeV : (n,d2) + 27 MT = 653 Q = -5.40138E+00 MeV Emin = 5.44432E+00 MeV : (n,d3) + 28 MT = 654 Q = -5.56118E+00 MeV Emin = 5.60539E+00 MeV : (n,d4) + 29 MT = 655 Q = -5.66118E+00 MeV Emin = 5.70618E+00 MeV : (n,d5) + 30 MT = 656 Q = -5.75743E+00 MeV Emin = 5.80320E+00 MeV : (n,d6) + 31 MT = 657 Q = -5.85457E+00 MeV Emin = 5.90111E+00 MeV : (n,d7) + 32 MT = 658 Q = -5.99437E+00 MeV Emin = 6.04202E+00 MeV : (n,d8) + 33 MT = 659 Q = -6.02634E+00 MeV Emin = 6.07424E+00 MeV : (n,d9) + 34 MT = 660 Q = -6.03418E+00 MeV Emin = 6.08215E+00 MeV : (n,d10) + 35 MT = 661 Q = -6.06118E+00 MeV Emin = 6.10936E+00 MeV : (n,d11) + 36 MT = 662 Q = -6.09476E+00 MeV Emin = 6.14321E+00 MeV : (n,d12) + 37 MT = 663 Q = -6.10958E+00 MeV Emin = 6.15815E+00 MeV : (n,d13) + 38 MT = 664 Q = -6.16270E+00 MeV Emin = 6.21169E+00 MeV : (n,d14) + 39 MT = 665 Q = -6.16555E+00 MeV Emin = 6.21456E+00 MeV : (n,d15) + 40 MT = 699 Q = -6.16555E+00 MeV Emin = 6.21456E+00 MeV : (n,d) to continuum + 41 MT = 700 Q = -6.83776E+00 MeV Emin = 6.89211E+00 MeV : (n,t) to ground state + 42 MT = 701 Q = -6.87325E+00 MeV Emin = 6.92788E+00 MeV : (n,t1) + 43 MT = 702 Q = -6.98256E+00 MeV Emin = 7.03806E+00 MeV : (n,t2) + 44 MT = 703 Q = -7.15887E+00 MeV Emin = 7.21577E+00 MeV : (n,t3) + 45 MT = 704 Q = -7.28132E+00 MeV Emin = 7.33920E+00 MeV : (n,t4) + 46 MT = 705 Q = -7.30113E+00 MeV Emin = 7.35916E+00 MeV : (n,t5) + 47 MT = 706 Q = -7.36301E+00 MeV Emin = 7.42153E+00 MeV : (n,t6) + 48 MT = 707 Q = -7.37576E+00 MeV Emin = 7.43439E+00 MeV : (n,t7) + 49 MT = 708 Q = -7.47385E+00 MeV Emin = 7.53326E+00 MeV : (n,t8) + 50 MT = 709 Q = -7.47997E+00 MeV Emin = 7.53942E+00 MeV : (n,t9) + 51 MT = 710 Q = -7.50921E+00 MeV Emin = 7.56890E+00 MeV : (n,t10) + 52 MT = 711 Q = -7.56704E+00 MeV Emin = 7.62719E+00 MeV : (n,t11) + 53 MT = 712 Q = -7.62376E+00 MeV Emin = 7.68436E+00 MeV : (n,t12) + 54 MT = 713 Q = -7.64176E+00 MeV Emin = 7.70250E+00 MeV : (n,t13) + 55 MT = 714 Q = -7.67869E+00 MeV Emin = 7.73972E+00 MeV : (n,t14) + 56 MT = 715 Q = -7.85476E+00 MeV Emin = 7.91719E+00 MeV : (n,t15) + 57 MT = 749 Q = -7.85476E+00 MeV Emin = 7.91719E+00 MeV : (n,t) to continuum + 58 MT = 750 Q = -7.58587E+00 MeV Emin = 7.64617E+00 MeV : (n,He-3) to ground state + 59 MT = 751 Q = -7.91801E+00 MeV Emin = 7.98095E+00 MeV : (n,He-3_1) + 60 MT = 752 Q = -8.22907E+00 MeV Emin = 8.29448E+00 MeV : (n,He-3_2) + 61 MT = 753 Q = -8.50757E+00 MeV Emin = 8.57519E+00 MeV : (n,He-3_3) + 62 MT = 754 Q = -8.65317E+00 MeV Emin = 8.72195E+00 MeV : (n,He-3_4) + 63 MT = 755 Q = -8.67550E+00 MeV Emin = 8.74446E+00 MeV : (n,He-3_5) + 64 MT = 756 Q = -8.93533E+00 MeV Emin = 9.00635E+00 MeV : (n,He-3_6) + 65 MT = 757 Q = -9.00573E+00 MeV Emin = 9.07731E+00 MeV : (n,He-3_7) + 66 MT = 758 Q = -9.06997E+00 MeV Emin = 9.14206E+00 MeV : (n,He-3_8) + 67 MT = 759 Q = -9.14587E+00 MeV Emin = 9.21856E+00 MeV : (n,He-3_9) + 68 MT = 760 Q = -9.17745E+00 MeV Emin = 9.25040E+00 MeV : (n,He-3_10) + 69 MT = 761 Q = -9.24587E+00 MeV Emin = 9.31936E+00 MeV : (n,He-3_11) + 70 MT = 762 Q = -9.28677E+00 MeV Emin = 9.36058E+00 MeV : (n,He-3_12) + 71 MT = 763 Q = -9.32157E+00 MeV Emin = 9.39566E+00 MeV : (n,He-3_13) + 72 MT = 764 Q = -9.38587E+00 MeV Emin = 9.46047E+00 MeV : (n,He-3_14) + 73 MT = 765 Q = -9.39258E+00 MeV Emin = 9.46724E+00 MeV : (n,He-3_15) + 74 MT = 799 Q = -9.39258E+00 MeV Emin = 9.46724E+00 MeV : (n,He-3) to continuum + 75 MT = 800 Q = 4.27795E+00 MeV Emin = 1.20000E+00 MeV : (n,alpha) to ground state + 76 MT = 801 Q = 4.26709E+00 MeV Emin = 1.20000E+00 MeV : (n,a1) + 77 MT = 802 Q = 4.24111E+00 MeV Emin = 1.20000E+00 MeV : (n,a2) + 78 MT = 803 Q = 4.23715E+00 MeV Emin = 1.20000E+00 MeV : (n,a3) + 79 MT = 804 Q = 4.19719E+00 MeV Emin = 1.20000E+00 MeV : (n,a4) + 80 MT = 805 Q = 4.19035E+00 MeV Emin = 1.20000E+00 MeV : (n,a5) + 81 MT = 806 Q = 4.17430E+00 MeV Emin = 1.20000E+00 MeV : (n,a6) + 82 MT = 807 Q = 4.15272E+00 MeV Emin = 1.20000E+00 MeV : (n,a7) + 83 MT = 808 Q = 4.14626E+00 MeV Emin = 1.20000E+00 MeV : (n,a8) + 84 MT = 809 Q = 4.12795E+00 MeV Emin = 1.20000E+00 MeV : (n,a9) + 85 MT = 810 Q = 4.09790E+00 MeV Emin = 1.20000E+00 MeV : (n,a10) + 86 MT = 811 Q = 4.08197E+00 MeV Emin = 1.40000E+00 MeV : (n,a11) + 87 MT = 812 Q = 4.06335E+00 MeV Emin = 1.40000E+00 MeV : (n,a12) + 88 MT = 813 Q = 4.05645E+00 MeV Emin = 1.40000E+00 MeV : (n,a13) + 89 MT = 814 Q = 4.04645E+00 MeV Emin = 1.40000E+00 MeV : (n,a14) + 90 MT = 815 Q = 4.02958E+00 MeV Emin = 1.40000E+00 MeV : (n,a15) + 91 MT = 849 Q = 4.02958E+00 MeV Emin = 1.00000E-11 MeV : (n,alpha) to continuum + 92 MT = 4 Q = 0.00000E+00 MeV Emin = 5.78370E-02 MeV : total inelastic scattering + + Nuclide 168 / 1657 : 53129.82c -- iodine 129 (I-129) + + Pointers : 1366968 26457 + Primary type : Transport + Nuclide ZAI : 531290 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/I129.ACE + Atomic weight (AW) : 128.90496 + Atomic weight ratio (AWR) : 127.79760 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 3.00000E+01 + Half-life : 5.08E+14 seconds (16.1 million years) + Specific ingestion toxicity : 1.10E-07 Sv/Bq + Specific inhalation toxicity : 3.60E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 43 reaction channels + - 82 special reactions + - 23 transmutation reactions + - 27 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 43 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 11 Q = -1.96403E+01 MeV Emin = 1.97940E+01 MeV frac = 1.00000E+00 Product nuclide = self : (n,2nd) + 3 MT = 16 Q = -8.83307E+00 MeV Emin = 8.90219E+00 MeV frac = 1.00000E+00 Product nuclide = 531280 : (n,2n) + 4 MT = 17 Q = -1.56591E+01 MeV Emin = 1.57817E+01 MeV frac = 1.00000E+00 Product nuclide = 53127.82c : (n,3n) + 5 MT = 22 Q = -2.66740E+00 MeV Emin = 2.68827E+00 MeV frac = 1.00000E+00 Product nuclide = 51125.82c : (n,nalpha) + 6 MT = 24 Q = -1.13812E+01 MeV Emin = 1.14703E+01 MeV frac = 1.00000E+00 Product nuclide = 51124.82c : (n,2nalpha) + 7 MT = 25 Q = -1.78486E+01 MeV Emin = 1.79883E+01 MeV frac = 1.00000E+00 Product nuclide = 51123.82c : (n,3nalpha) + 8 MT = 28 Q = -6.79891E+00 MeV Emin = 6.85211E+00 MeV frac = 1.00000E+00 Product nuclide = 52128.82c : (n,np) + 9 MT = 32 Q = -1.33498E+01 MeV Emin = 1.34543E+01 MeV frac = 1.00000E+00 Product nuclide = 521270 : (n,nd) + 10 MT = 33 Q = -1.33831E+01 MeV Emin = 1.34878E+01 MeV frac = 1.00000E+00 Product nuclide = 52126.82c : (n,nt) + 11 MT = 34 Q = -1.70370E+01 MeV Emin = 1.71703E+01 MeV frac = 1.00000E+00 Product nuclide = 51126.82c : (n,nHe-3) + 12 MT = 37 Q = -2.48026E+01 MeV Emin = 2.49967E+01 MeV frac = 1.00000E+00 Product nuclide = cut: I-126 : (n,4n) + 13 MT = 41 Q = -1.55744E+01 MeV Emin = 1.56963E+01 MeV frac = 1.00000E+00 Product nuclide = 521270 : (n,2np) + 14 MT = 42 Q = -2.18649E+01 MeV Emin = 2.20360E+01 MeV frac = 1.00000E+00 Product nuclide = cut: Te-126 : (n,3np) + 15 MT = 44 Q = -1.63730E+01 MeV Emin = 1.65011E+01 MeV frac = 1.00000E+00 Product nuclide = 511270 : (n,n2p) + 16 MT = 45 Q = -9.98135E+00 MeV Emin = 1.00595E+01 MeV frac = 1.00000E+00 Product nuclide = 50124.82c : (n,npalpha) + 17 MT = 51 Q = -2.78000E-02 MeV Emin = 2.79088E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 18 MT = 52 Q = -2.78380E-01 MeV Emin = 2.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 19 MT = 53 Q = -4.87350E-01 MeV Emin = 4.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 20 MT = 54 Q = -5.59620E-01 MeV Emin = 5.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 21 MT = 55 Q = -6.95890E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 22 MT = 56 Q = -7.29570E-01 MeV Emin = 7.28391E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 23 MT = 57 Q = -7.68760E-01 MeV Emin = 7.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 24 MT = 58 Q = -8.29920E-01 MeV Emin = 8.31964E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 25 MT = 59 Q = -8.44820E-01 MeV Emin = 8.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 26 MT = 60 Q = -1.04735E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 27 MT = 61 Q = -1.05021E+00 MeV Emin = 1.05699E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 28 MT = 62 Q = -1.11165E+00 MeV Emin = 1.11994E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 29 MT = 63 Q = -1.19665E+00 MeV Emin = 1.20000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 30 MT = 64 Q = -1.20361E+00 MeV Emin = 1.21264E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 31 MT = 65 Q = -1.20980E+00 MeV Emin = 1.21596E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 32 MT = 91 Q = -1.20980E+00 MeV Emin = 1.21596E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 33 MT = 102 Q = 6.50033E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 53130.82c : (n,gamma) + 34 MT = 103 Q = -7.15589E-01 MeV Emin = 7.11261E-01 MeV frac = 1.00000E+00 Product nuclide = 521290 : (n,p) + 35 MT = 104 Q = -4.57434E+00 MeV Emin = 4.61013E+00 MeV frac = 1.00000E+00 Product nuclide = 52128.82c : (n,d) + 36 MT = 105 Q = -7.09253E+00 MeV Emin = 7.14803E+00 MeV frac = 1.00000E+00 Product nuclide = 521270 : (n,t) + 37 MT = 106 Q = -8.65494E+00 MeV Emin = 8.72267E+00 MeV frac = 1.00000E+00 Product nuclide = 511270 : (n,He-3) + 38 MT = 107 Q = 3.54061E+00 MeV Emin = 1.81250E-08 MeV frac = 1.00000E+00 Product nuclide = 51126.82c : (n,alpha) + 39 MT = 111 Q = -1.04001E+01 MeV Emin = 1.04815E+01 MeV frac = 1.00000E+00 Product nuclide = 511280 : (n,2p) + 40 MT = 112 Q = -4.24835E+00 MeV Emin = 4.28160E+00 MeV frac = 1.00000E+00 Product nuclide = 50125.82c : (n,palpha) + 41 MT = 115 Q = -1.41484E+01 MeV Emin = 1.42591E+01 MeV frac = 1.00000E+00 Product nuclide = 511270 : (n,pd) + 42 MT = 116 Q = -1.62732E+01 MeV Emin = 1.64006E+01 MeV frac = 1.00000E+00 Product nuclide = 51126.82c : (n,pt) + 43 MT = 117 Q = -7.75678E+00 MeV Emin = 7.81748E+00 MeV frac = 1.00000E+00 Product nuclide = 50124.82c : (n,dalpha) + + 27 additional transport branches: + + 1 MT = 22 Q = -2.66740E+00 MeV Emin = 2.68827E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 24 Q = -1.13812E+01 MeV Emin = 1.14703E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,2nalpha) + 3 MT = 25 Q = -1.78486E+01 MeV Emin = 1.79883E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,3nalpha) + 4 MT = 28 Q = -6.79891E+00 MeV Emin = 6.85211E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 5 MT = 32 Q = -1.33498E+01 MeV Emin = 1.34543E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 6 MT = 33 Q = -1.33831E+01 MeV Emin = 1.34878E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 7 MT = 34 Q = -1.70370E+01 MeV Emin = 1.71703E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,nHe-3) + 8 MT = 41 Q = -1.55744E+01 MeV Emin = 1.56963E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,2np) + 9 MT = 42 Q = -2.18649E+01 MeV Emin = 2.20360E+01 MeV frac = 1.00000E+00 Product nuclide = cut: H-1 : (n,3np) + 10 MT = 44 Q = -1.63730E+01 MeV Emin = 1.65011E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,n2p) + 11 MT = 45 Q = -9.98135E+00 MeV Emin = 1.00595E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,npalpha) + 12 MT = 45 Q = -9.98135E+00 MeV Emin = 1.00595E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,npalpha) + 13 MT = 102 Q = 6.50033E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 531301 : (n,gamma) + 14 MT = 103 Q = -7.15589E-01 MeV Emin = 7.11261E-01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 15 MT = 104 Q = -4.57434E+00 MeV Emin = 4.61013E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 16 MT = 105 Q = -7.09253E+00 MeV Emin = 7.14803E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 17 MT = 106 Q = -8.65494E+00 MeV Emin = 8.72267E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 18 MT = 107 Q = 3.54061E+00 MeV Emin = 1.81250E-08 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 19 MT = 111 Q = -1.04001E+01 MeV Emin = 1.04815E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + 20 MT = 112 Q = -4.24835E+00 MeV Emin = 4.28160E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,palpha) + 21 MT = 112 Q = -4.24835E+00 MeV Emin = 4.28160E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,palpha) + 22 MT = 115 Q = -1.41484E+01 MeV Emin = 1.42591E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,pd) + 23 MT = 115 Q = -1.41484E+01 MeV Emin = 1.42591E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,pd) + 24 MT = 116 Q = -1.62732E+01 MeV Emin = 1.64006E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,pt) + 25 MT = 116 Q = -1.62732E+01 MeV Emin = 1.64006E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,pt) + 26 MT = 117 Q = -7.75678E+00 MeV Emin = 7.81748E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,dalpha) + 27 MT = 117 Q = -7.75678E+00 MeV Emin = 7.81748E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,dalpha) + + 82 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 7.11261E-01 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 4.61013E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 7.14803E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 8.72267E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.81250E-08 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 600 Q = -7.15589E-01 MeV Emin = 2.00000E+00 MeV : (n,p) to ground state + 8 MT = 601 Q = -8.21089E-01 MeV Emin = 2.00000E+00 MeV : (n,p1) + 9 MT = 602 Q = -8.95889E-01 MeV Emin = 2.00000E+00 MeV : (n,p2) + 10 MT = 603 Q = -9.60089E-01 MeV Emin = 2.00000E+00 MeV : (n,p3) + 11 MT = 604 Q = -1.07559E+00 MeV Emin = 2.00000E+00 MeV : (n,p4) + 12 MT = 605 Q = -1.17059E+00 MeV Emin = 2.00000E+00 MeV : (n,p5) + 13 MT = 606 Q = -1.18049E+00 MeV Emin = 2.00000E+00 MeV : (n,p6) + 14 MT = 607 Q = -1.26009E+00 MeV Emin = 2.00000E+00 MeV : (n,p7) + 15 MT = 608 Q = -1.34949E+00 MeV Emin = 2.00000E+00 MeV : (n,p8) + 16 MT = 609 Q = -1.47559E+00 MeV Emin = 2.00000E+00 MeV : (n,p9) + 17 MT = 610 Q = -1.49059E+00 MeV Emin = 2.00000E+00 MeV : (n,p10) + 18 MT = 611 Q = -1.52839E+00 MeV Emin = 2.00000E+00 MeV : (n,p11) + 19 MT = 612 Q = -1.53459E+00 MeV Emin = 2.00000E+00 MeV : (n,p12) + 20 MT = 613 Q = -1.58259E+00 MeV Emin = 2.00000E+00 MeV : (n,p13) + 21 MT = 614 Q = -1.58759E+00 MeV Emin = 2.00000E+00 MeV : (n,p14) + 22 MT = 615 Q = -1.59159E+00 MeV Emin = 2.00000E+00 MeV : (n,p15) + 23 MT = 649 Q = -1.59159E+00 MeV Emin = 1.60203E+00 MeV : (n,p) to continuum + 24 MT = 650 Q = -4.57434E+00 MeV Emin = 4.61013E+00 MeV : (n,d) to ground state + 25 MT = 651 Q = -5.31764E+00 MeV Emin = 5.35925E+00 MeV : (n,d1) + 26 MT = 652 Q = -6.07164E+00 MeV Emin = 6.11915E+00 MeV : (n,d2) + 27 MT = 653 Q = -6.09443E+00 MeV Emin = 6.14212E+00 MeV : (n,d3) + 28 MT = 654 Q = -6.38570E+00 MeV Emin = 6.43567E+00 MeV : (n,d4) + 29 MT = 655 Q = -6.54308E+00 MeV Emin = 6.59428E+00 MeV : (n,d5) + 30 MT = 656 Q = -6.55339E+00 MeV Emin = 6.60467E+00 MeV : (n,d6) + 31 MT = 657 Q = -6.60242E+00 MeV Emin = 6.65408E+00 MeV : (n,d7) + 32 MT = 658 Q = -6.61434E+00 MeV Emin = 6.66610E+00 MeV : (n,d8) + 33 MT = 659 Q = -6.70788E+00 MeV Emin = 6.76037E+00 MeV : (n,d9) + 34 MT = 660 Q = -6.71234E+00 MeV Emin = 6.76486E+00 MeV : (n,d10) + 35 MT = 661 Q = -6.73802E+00 MeV Emin = 6.79075E+00 MeV : (n,d11) + 36 MT = 662 Q = -6.76793E+00 MeV Emin = 6.82089E+00 MeV : (n,d12) + 37 MT = 663 Q = -6.79238E+00 MeV Emin = 6.84553E+00 MeV : (n,d13) + 38 MT = 664 Q = -6.84496E+00 MeV Emin = 6.89852E+00 MeV : (n,d14) + 39 MT = 665 Q = -6.88264E+00 MeV Emin = 6.93650E+00 MeV : (n,d15) + 40 MT = 699 Q = -6.88264E+00 MeV Emin = 6.93650E+00 MeV : (n,d) to continuum + 41 MT = 700 Q = -7.09253E+00 MeV Emin = 7.14803E+00 MeV : (n,t) to ground state + 42 MT = 701 Q = -7.15365E+00 MeV Emin = 7.20963E+00 MeV : (n,t1) + 43 MT = 702 Q = -7.18079E+00 MeV Emin = 7.23698E+00 MeV : (n,t2) + 44 MT = 703 Q = -7.43313E+00 MeV Emin = 7.49130E+00 MeV : (n,t3) + 45 MT = 704 Q = -7.45853E+00 MeV Emin = 7.51690E+00 MeV : (n,t4) + 46 MT = 705 Q = -7.56580E+00 MeV Emin = 7.62500E+00 MeV : (n,t5) + 47 MT = 706 Q = -7.59543E+00 MeV Emin = 7.65487E+00 MeV : (n,t6) + 48 MT = 707 Q = -7.69553E+00 MeV Emin = 7.75575E+00 MeV : (n,t7) + 49 MT = 708 Q = -7.72403E+00 MeV Emin = 7.78447E+00 MeV : (n,t8) + 50 MT = 709 Q = -7.72503E+00 MeV Emin = 7.78548E+00 MeV : (n,t9) + 51 MT = 710 Q = -7.77803E+00 MeV Emin = 7.83890E+00 MeV : (n,t10) + 52 MT = 711 Q = -7.85623E+00 MeV Emin = 7.91771E+00 MeV : (n,t11) + 53 MT = 712 Q = -7.87593E+00 MeV Emin = 7.93756E+00 MeV : (n,t12) + 54 MT = 713 Q = -7.87823E+00 MeV Emin = 7.93988E+00 MeV : (n,t13) + 55 MT = 714 Q = -8.01703E+00 MeV Emin = 8.07976E+00 MeV : (n,t14) + 56 MT = 715 Q = -8.05853E+00 MeV Emin = 8.12159E+00 MeV : (n,t15) + 57 MT = 749 Q = -8.05853E+00 MeV Emin = 8.12159E+00 MeV : (n,t) to continuum + 58 MT = 750 Q = -8.65494E+00 MeV Emin = 8.72267E+00 MeV : (n,He-3) to ground state + 59 MT = 751 Q = -9.14614E+00 MeV Emin = 9.21771E+00 MeV : (n,He-3_1) + 60 MT = 752 Q = -9.43294E+00 MeV Emin = 9.50675E+00 MeV : (n,He-3_2) + 61 MT = 753 Q = -9.75042E+00 MeV Emin = 9.82672E+00 MeV : (n,He-3_3) + 62 MT = 754 Q = -9.76494E+00 MeV Emin = 9.84135E+00 MeV : (n,He-3_4) + 63 MT = 755 Q = -9.76929E+00 MeV Emin = 9.84574E+00 MeV : (n,He-3_5) + 64 MT = 756 Q = -9.84994E+00 MeV Emin = 9.92702E+00 MeV : (n,He-3_6) + 65 MT = 757 Q = -1.01263E+01 MeV Emin = 1.02056E+01 MeV : (n,He-3_7) + 66 MT = 758 Q = -1.02393E+01 MeV Emin = 1.03194E+01 MeV : (n,He-3_8) + 67 MT = 759 Q = -1.02649E+01 MeV Emin = 1.03453E+01 MeV : (n,He-3_9) + 68 MT = 760 Q = -1.03666E+01 MeV Emin = 1.04478E+01 MeV : (n,He-3_10) + 69 MT = 761 Q = -1.05751E+01 MeV Emin = 1.06579E+01 MeV : (n,He-3_11) + 70 MT = 762 Q = -1.05924E+01 MeV Emin = 1.06753E+01 MeV : (n,He-3_12) + 71 MT = 763 Q = -1.06100E+01 MeV Emin = 1.06930E+01 MeV : (n,He-3_13) + 72 MT = 764 Q = -1.06455E+01 MeV Emin = 1.07288E+01 MeV : (n,He-3_14) + 73 MT = 765 Q = -1.06584E+01 MeV Emin = 1.07418E+01 MeV : (n,He-3_15) + 74 MT = 799 Q = -1.06584E+01 MeV Emin = 1.07418E+01 MeV : (n,He-3) to continuum + 75 MT = 800 Q = 3.54061E+00 MeV Emin = 2.00000E+00 MeV : (n,alpha) to ground state + 76 MT = 801 Q = 3.52291E+00 MeV Emin = 2.00000E+00 MeV : (n,a1) + 77 MT = 802 Q = 3.50021E+00 MeV Emin = 2.00000E+00 MeV : (n,a2) + 78 MT = 803 Q = 3.45761E+00 MeV Emin = 2.00000E+00 MeV : (n,a3) + 79 MT = 804 Q = 3.43601E+00 MeV Emin = 2.00000E+00 MeV : (n,a4) + 80 MT = 805 Q = 3.41271E+00 MeV Emin = 2.00000E+00 MeV : (n,a5) + 81 MT = 849 Q = 3.41271E+00 MeV Emin = 1.00000E-11 MeV : (n,alpha) to continuum + 82 MT = 4 Q = 0.00000E+00 MeV Emin = 2.79088E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.90800E-01 MeV frac = 1.00000E+00 Product nuclide = 54129.82c : beta- + + Nuclide 169 / 1657 : 53130.82c -- iodine 130 (I-130) + + Pointers : 1378482 26503 + Primary type : Transport + Nuclide ZAI : 531300 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/I130.ACE + Atomic weight (AW) : 129.90697 + Atomic weight ratio (AWR) : 128.79100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 4.45E+04 seconds (12.4 hours) + Specific ingestion toxicity : 2.00E-09 Sv/Bq + Specific inhalation toxicity : 6.70E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 9 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 6 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 9 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 91 Q = -4.96130E-02 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 3 MT = 102 Q = 8.43000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 53131.82c : (n,gamma) + 4 MT = 103 Q = 1.23330E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 52130.82c : (n,p) + 5 MT = 104 Q = -4.95250E+00 MeV Emin = 4.99095E+00 MeV frac = 1.00000E+00 Product nuclide = 521290 : (n,d) + 6 MT = 105 Q = -4.78100E+00 MeV Emin = 4.81812E+00 MeV frac = 1.00000E+00 Product nuclide = 52128.82c : (n,t) + 7 MT = 106 Q = -9.02380E+00 MeV Emin = 9.09387E+00 MeV frac = 1.00000E+00 Product nuclide = 511280 : (n,He-3) + 8 MT = 107 Q = 5.45160E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 511270 : (n,alpha) + 9 MT = 111 Q = -8.77040E+00 MeV Emin = 8.83850E+00 MeV frac = 1.00000E+00 Product nuclide = 511290 : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = 1.23330E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -4.95250E+00 MeV Emin = 4.99095E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -4.78100E+00 MeV Emin = 4.81812E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -9.02380E+00 MeV Emin = 9.09387E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 5.45160E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -8.77040E+00 MeV Emin = 8.83850E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.62500E-02 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 4.99095E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 4.81812E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 9.09387E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.62500E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 4.62500E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.94900E+00 MeV frac = 1.00000E+00 Product nuclide = 54130.82c : beta- + + Nuclide 170 / 1657 : 53131.82c -- iodine 131 (I-131) + + Pointers : 1381640 26549 + Primary type : Transport + Nuclide ZAI : 531310 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/I131.ACE + Atomic weight (AW) : 130.90555 + Atomic weight ratio (AWR) : 129.78100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 6.93E+05 seconds (8.02 days) + Specific ingestion toxicity : 2.20E-08 Sv/Bq + Specific inhalation toxicity : 7.40E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 28 reaction channels + - 6 special reactions + - 11 transmutation reactions + - 9 transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 28 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.63010E+00 MeV Emin = 8.69660E+00 MeV frac = 1.00000E+00 Product nuclide = 53130.82c : (n,2n) + 3 MT = 17 Q = -1.50982E+01 MeV Emin = 1.52146E+01 MeV frac = 1.00000E+00 Product nuclide = 53129.82c : (n,3n) + 4 MT = 22 Q = -3.16890E+00 MeV Emin = 3.19332E+00 MeV frac = 1.00000E+00 Product nuclide = 511270 : (n,nalpha) + 5 MT = 28 Q = -7.39664E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 52130.82c : (n,np) + 6 MT = 32 Q = -1.35036E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 521290 : (n,nd) + 7 MT = 33 Q = -1.34093E+01 MeV Emin = 1.52146E+01 MeV frac = 1.00000E+00 Product nuclide = 52128.82c : (n,nt) + 8 MT = 51 Q = -1.49700E-01 MeV Emin = 1.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -4.92699E-01 MeV Emin = 4.47372E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -6.01999E-01 MeV Emin = 5.93309E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -7.73699E-01 MeV Emin = 7.59746E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -8.52199E-01 MeV Emin = 8.44074E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -8.76699E-01 MeV Emin = 8.74197E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -1.00580E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -1.05970E+00 MeV Emin = 1.05429E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -1.09830E+00 MeV Emin = 1.09218E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -1.14690E+00 MeV Emin = 1.13737E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -1.14890E+00 MeV Emin = 1.15750E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 62 Q = -1.28400E+00 MeV Emin = 1.25000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 20 MT = 63 Q = -1.29820E+00 MeV Emin = 1.30105E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 21 MT = 64 Q = -1.31520E+00 MeV Emin = 1.31677E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 22 MT = 65 Q = -1.34650E+00 MeV Emin = 1.34110E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 23 MT = 91 Q = -1.37680E+00 MeV Emin = 1.37596E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 24 MT = 102 Q = 6.32685E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 531320 : (n,gamma) + 25 MT = 103 Q = -1.46754E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 521310 : (n,p) + 26 MT = 104 Q = -5.08652E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 52130.82c : (n,d) + 27 MT = 105 Q = -7.31846E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 521290 : (n,t) + 28 MT = 107 Q = 2.93321E+00 MeV Emin = 2.37500E-01 MeV frac = 1.00000E+00 Product nuclide = 511280 : (n,alpha) + + 9 additional transport branches: + + 1 MT = 22 Q = -3.16890E+00 MeV Emin = 3.19332E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -7.39664E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.35036E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.34093E+01 MeV Emin = 1.52146E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 102 Q = 6.32685E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 531321 : (n,gamma) + 6 MT = 103 Q = -1.46754E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 7 MT = 104 Q = -5.08652E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 8 MT = 105 Q = -7.31846E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 9 MT = 107 Q = 2.93321E+00 MeV Emin = 2.37500E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.00000E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 2.37500E-01 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 7.60000E-04 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 1.50000E-01 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 1 Q = 9.70800E-01 MeV frac = 9.89105E-01 Product nuclide = 54131.82c : beta- + 2 RTYP = 1 Q = 8.06870E-01 MeV frac = 1.08945E-02 Product nuclide = 541311 : beta- + + Nuclide 171 / 1657 : 53135.82c -- iodine 135 (I-135) + + Pointers : 1396941 26595 + Primary type : Transport + Nuclide ZAI : 531350 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/I135.ACE + Atomic weight (AW) : 134.90894 + Atomic weight ratio (AWR) : 133.75000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.37E+04 seconds (6.58 hours) + Specific ingestion toxicity : 9.30E-10 Sv/Bq + Specific inhalation toxicity : 3.20E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 13 reaction channels + - 6 special reactions + - 9 transmutation reactions + - 6 transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 13 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.90260E+00 MeV Emin = 7.96170E+00 MeV frac = 1.00000E+00 Product nuclide = 531340 : (n,2n) + 3 MT = 17 Q = -1.40750E+01 MeV Emin = 1.41810E+01 MeV frac = 1.00000E+00 Product nuclide = 531330 : (n,3n) + 4 MT = 22 Q = -4.22630E+00 MeV Emin = 1.22500E+01 MeV frac = 1.00000E+00 Product nuclide = 511310 : (n,nalpha) + 5 MT = 28 Q = -8.67950E+00 MeV Emin = 1.17480E+01 MeV frac = 1.00000E+00 Product nuclide = 521340 : (n,np) + 6 MT = 51 Q = -6.03500E-01 MeV Emin = 5.54006E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -8.70300E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 91 Q = -8.70300E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 9 MT = 102 Q = 3.78098E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 531360 : (n,gamma) + 10 MT = 103 Q = -5.16890E+00 MeV Emin = 8.25000E+00 MeV frac = 1.00000E+00 Product nuclide = 521350 : (n,p) + 11 MT = 104 Q = -6.45500E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 521340 : (n,d) + 12 MT = 105 Q = -7.72970E+00 MeV Emin = 1.22500E+01 MeV frac = 1.00000E+00 Product nuclide = 521330 : (n,t) + 13 MT = 107 Q = 1.55530E+00 MeV Emin = 6.75000E+00 MeV frac = 1.00000E+00 Product nuclide = 511320 : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = -4.22630E+00 MeV Emin = 1.22500E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -8.67950E+00 MeV Emin = 1.17480E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -5.16890E+00 MeV Emin = 8.25000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -6.45500E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -7.72970E+00 MeV Emin = 1.22500E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 107 Q = 1.55530E+00 MeV Emin = 6.75000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 8.25000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.00000E+01 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.22500E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 6.75000E+00 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 8.12500E-04 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 5.54006E-01 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 1 Q = 2.62700E+00 MeV frac = 8.34918E-01 Product nuclide = 54135.82c : beta- + 2 RTYP = 1 Q = 2.10045E+00 MeV frac = 1.65082E-01 Product nuclide = 541351 : beta- + + Nuclide 172 / 1657 : 54128.82c -- xenon 128 (Xe-128) + + Pointers : 1426636 36209 + Primary type : Transport + Nuclide ZAI : 541280 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Xe128.ACE + Atomic weight (AW) : 127.90275 + Atomic weight ratio (AWR) : 126.80400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 34 reaction channels + - 6 special reactions + - 9 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 34 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -9.62129E+00 MeV Emin = 9.69717E+00 MeV frac = 1.00000E+00 Product nuclide = 541270 : (n,2n) + 3 MT = 17 Q = -1.68514E+01 MeV Emin = 1.70000E+01 MeV frac = 1.00000E+00 Product nuclide = 541260 : (n,3n) + 4 MT = 22 Q = -1.76480E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 52124.82c : (n,nalpha) + 5 MT = 28 Q = -8.17483E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 53127.82c : (n,np) + 6 MT = 51 Q = -4.42899E-01 MeV Emin = 3.73196E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -9.69499E-01 MeV Emin = 9.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -1.03310E+00 MeV Emin = 1.02062E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -1.42960E+00 MeV Emin = 1.41949E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -1.58300E+00 MeV Emin = 1.54774E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -1.60340E+00 MeV Emin = 1.60576E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -1.73700E+00 MeV Emin = 1.75000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -1.87730E+00 MeV Emin = 1.85675E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -1.99650E+00 MeV Emin = 2.01225E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -1.99960E+00 MeV Emin = 2.01537E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -2.12710E+00 MeV Emin = 2.14388E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -2.22900E+00 MeV Emin = 2.24658E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -2.25290E+00 MeV Emin = 2.27067E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -2.27280E+00 MeV Emin = 2.29073E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -2.28090E+00 MeV Emin = 2.29889E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 21 MT = 66 Q = -2.36180E+00 MeV Emin = 2.38043E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 22 MT = 67 Q = -2.42110E+00 MeV Emin = 2.44019E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 23 MT = 68 Q = -2.43070E+00 MeV Emin = 2.44987E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 24 MT = 69 Q = -2.44390E+00 MeV Emin = 2.46317E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 25 MT = 70 Q = -2.48250E+00 MeV Emin = 2.50208E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 26 MT = 71 Q = -2.50080E+00 MeV Emin = 2.52052E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 27 MT = 72 Q = -2.51070E+00 MeV Emin = 2.53050E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 28 MT = 73 Q = -2.51250E+00 MeV Emin = 2.53232E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 29 MT = 91 Q = -2.52140E+00 MeV Emin = 2.54128E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 30 MT = 102 Q = 6.90867E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 54129.82c : (n,gamma) + 31 MT = 103 Q = -1.34473E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 531280 : (n,p) + 32 MT = 104 Q = -5.86471E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 53127.82c : (n,d) + 33 MT = 105 Q = -8.82466E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 531260 : (n,t) + 34 MT = 107 Q = 4.81200E+00 MeV Emin = 8.99999E-02 MeV frac = 1.00000E+00 Product nuclide = 52125.82c : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -1.76480E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -8.17483E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 102 Q = 6.90867E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 541291 : (n,gamma) + 4 MT = 103 Q = -1.34473E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -5.86471E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -8.82466E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 107 Q = 4.81200E+00 MeV Emin = 8.99999E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.00000E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 8.99999E-02 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 7.77933E-04 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 3.73196E-01 MeV : total inelastic scattering + + Nuclide 173 / 1657 : 54129.82c -- xenon 129 (Xe-129) + + Pointers : 1430197 36255 + Primary type : Transport + Nuclide ZAI : 541290 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Xe129.ACE + Atomic weight (AW) : 128.90536 + Atomic weight ratio (AWR) : 127.79800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 29 reaction channels + - 7 special reactions + - 11 transmutation reactions + - 8 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 29 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.91240E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 54128.82c : (n,2n) + 3 MT = 17 Q = -1.65337E+01 MeV Emin = 1.66631E+01 MeV frac = 1.00000E+00 Product nuclide = 541270 : (n,3n) + 4 MT = 22 Q = -2.10040E+00 MeV Emin = 2.11684E+00 MeV frac = 1.00000E+00 Product nuclide = 52125.82c : (n,nalpha) + 5 MT = 28 Q = -8.25713E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 531280 : (n,np) + 6 MT = 32 Q = -1.27771E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 53127.82c : (n,nd) + 7 MT = 51 Q = -3.95999E-02 MeV Emin = 3.74550E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 8 MT = 52 Q = -2.36100E-01 MeV Emin = 2.18973E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 9 MT = 53 Q = -3.18200E-01 MeV Emin = 3.10345E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 10 MT = 54 Q = -3.21700E-01 MeV Emin = 3.23335E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 11 MT = 55 Q = -4.11499E-01 MeV Emin = 4.13986E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 12 MT = 56 Q = -5.18699E-01 MeV Emin = 5.15894E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 13 MT = 57 Q = -5.72699E-01 MeV Emin = 5.63576E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 14 MT = 58 Q = -5.88499E-01 MeV Emin = 5.89124E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 15 MT = 59 Q = -6.24499E-01 MeV Emin = 6.20317E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 16 MT = 60 Q = -6.65399E-01 MeV Emin = 6.61590E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 17 MT = 61 Q = -7.71099E-01 MeV Emin = 7.57850E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 18 MT = 62 Q = -8.22199E-01 MeV Emin = 8.14317E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 19 MT = 63 Q = -8.23199E-01 MeV Emin = 8.29389E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 20 MT = 64 Q = -8.67999E-01 MeV Emin = 8.73680E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 21 MT = 65 Q = -9.04299E-01 MeV Emin = 9.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 22 MT = 66 Q = -9.45999E-01 MeV Emin = 9.37642E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 23 MT = 91 Q = -9.85799E-01 MeV Emin = 9.92719E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 24 MT = 102 Q = 9.25565E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 54130.82c : (n,gamma) + 25 MT = 103 Q = 5.89955E-01 MeV Emin = 1.67188E+00 MeV frac = 1.00000E+00 Product nuclide = 53129.82c : (n,p) + 26 MT = 104 Q = -5.94701E+00 MeV Emin = 7.32521E+00 MeV frac = 1.00000E+00 Product nuclide = 531280 : (n,d) + 27 MT = 105 Q = -6.59196E+00 MeV Emin = 8.32175E+00 MeV frac = 1.00000E+00 Product nuclide = 53127.82c : (n,t) + 28 MT = 106 Q = -7.26833E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 521270 : (n,He-3) + 29 MT = 107 Q = 7.02269E+00 MeV Emin = 9.99608E-02 MeV frac = 1.00000E+00 Product nuclide = 52126.82c : (n,alpha) + + 8 additional transport branches: + + 1 MT = 22 Q = -2.10040E+00 MeV Emin = 2.11684E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -8.25713E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.27771E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 103 Q = 5.89955E-01 MeV Emin = 1.67188E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -5.94701E+00 MeV Emin = 7.32521E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -6.59196E+00 MeV Emin = 8.32175E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 106 Q = -7.26833E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 8 MT = 107 Q = 7.02269E+00 MeV Emin = 9.99608E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.67188E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.32521E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 8.32175E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.10000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 9.99608E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 7.78058E-04 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 3.74550E-02 MeV : total inelastic scattering + + Nuclide 174 / 1657 : 54130.82c -- xenon 130 (Xe-130) + + Pointers : 1433947 36301 + Primary type : Transport + Nuclide ZAI : 541300 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Xe130.ACE + Atomic weight (AW) : 129.90394 + Atomic weight ratio (AWR) : 128.78800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 15 reaction channels + - 6 special reactions + - 7 transmutation reactions + - 5 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 15 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -9.25800E+00 MeV Emin = 9.32990E+00 MeV frac = 1.00000E+00 Product nuclide = 54129.82c : (n,2n) + 3 MT = 17 Q = -1.61630E+01 MeV Emin = 1.62889E+01 MeV frac = 1.00000E+00 Product nuclide = 54128.82c : (n,3n) + 4 MT = 51 Q = -5.36000E-01 MeV Emin = 5.40000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 5 MT = 52 Q = -1.12200E+00 MeV Emin = 1.06550E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 6 MT = 53 Q = -1.20400E+00 MeV Emin = 1.21000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 7 MT = 54 Q = -1.63300E+00 MeV Emin = 1.60950E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 8 MT = 55 Q = -1.80800E+00 MeV Emin = 1.82100E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 9 MT = 56 Q = -1.94400E+00 MeV Emin = 1.94750E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 10 MT = 91 Q = -2.08382E+00 MeV Emin = 2.10000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 11 MT = 102 Q = 6.60482E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 54131.82c : (n,gamma) + 12 MT = 103 Q = -2.20970E+00 MeV Emin = 2.22686E+00 MeV frac = 1.00000E+00 Product nuclide = 53130.82c : (n,p) + 13 MT = 104 Q = -6.44140E+00 MeV Emin = 6.49142E+00 MeV frac = 1.00000E+00 Product nuclide = 53129.82c : (n,d) + 14 MT = 105 Q = -9.02370E+00 MeV Emin = 9.09380E+00 MeV frac = 1.00000E+00 Product nuclide = 531280 : (n,t) + 15 MT = 107 Q = 4.05500E+00 MeV Emin = 6.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 521270 : (n,alpha) + + 5 additional transport branches: + + 1 MT = 102 Q = 6.60482E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 541311 : (n,gamma) + 2 MT = 103 Q = -2.20970E+00 MeV Emin = 2.22686E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 104 Q = -6.44140E+00 MeV Emin = 6.49142E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 4 MT = 105 Q = -9.02370E+00 MeV Emin = 9.09380E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 5 MT = 107 Q = 4.05500E+00 MeV Emin = 6.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.22686E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.49142E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.09380E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 6.50000E+00 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 7.99056E-04 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 5.40000E-01 MeV : total inelastic scattering + + Nuclide 175 / 1657 : 54131.82c -- xenon 131 (Xe-131) + + Pointers : 1435975 36347 + Primary type : Transport + Nuclide ZAI : 541310 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Xe131.ACE + Atomic weight (AW) : 130.90555 + Atomic weight ratio (AWR) : 129.78100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 17 reaction channels + - 7 special reactions + - 9 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 17 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.60560E+00 MeV Emin = 6.65650E+00 MeV frac = 1.00000E+00 Product nuclide = 54130.82c : (n,2n) + 3 MT = 17 Q = -1.58640E+01 MeV Emin = 1.59863E+01 MeV frac = 1.00000E+00 Product nuclide = 54129.82c : (n,3n) + 4 MT = 51 Q = -8.00000E-02 MeV Emin = 8.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 5 MT = 52 Q = -1.64000E-01 MeV Emin = 1.64750E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 6 MT = 53 Q = -3.64000E-01 MeV Emin = 3.48000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 7 MT = 54 Q = -6.37000E-01 MeV Emin = 6.31000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 8 MT = 55 Q = -7.23000E-01 MeV Emin = 7.28000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 9 MT = 56 Q = -8.06000E-01 MeV Emin = 8.12000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 10 MT = 91 Q = -9.42740E-01 MeV Emin = 9.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 11 MT = 102 Q = 8.93659E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 54132.82c : (n,gamma) + 12 MT = 103 Q = -1.88400E-01 MeV Emin = 1.82000E-01 MeV frac = 1.00000E+00 Product nuclide = 53131.82c : (n,p) + 13 MT = 104 Q = -6.59040E+00 MeV Emin = 6.64120E+00 MeV frac = 1.00000E+00 Product nuclide = 53130.82c : (n,d) + 14 MT = 105 Q = -6.78900E+00 MeV Emin = 6.84131E+00 MeV frac = 1.00000E+00 Product nuclide = 53129.82c : (n,t) + 15 MT = 106 Q = -8.27110E+00 MeV Emin = 8.33483E+00 MeV frac = 1.00000E+00 Product nuclide = 521290 : (n,He-3) + 16 MT = 107 Q = 6.22100E+00 MeV Emin = 4.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 52128.82c : (n,alpha) + 17 MT = 111 Q = -7.57680E+00 MeV Emin = 7.63518E+00 MeV frac = 1.00000E+00 Product nuclide = 52130.82c : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = -1.88400E-01 MeV Emin = 1.82000E-01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -6.59040E+00 MeV Emin = 6.64120E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -6.78900E+00 MeV Emin = 6.84131E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -8.27110E+00 MeV Emin = 8.33483E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 6.22100E+00 MeV Emin = 4.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -7.57680E+00 MeV Emin = 7.63518E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.82000E-01 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.64120E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 6.84131E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 8.33483E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.50000E+00 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 7.99069E-04 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 8.00000E-02 MeV : total inelastic scattering + + Nuclide 176 / 1657 : 54132.82c -- xenon 132 (Xe-132) + + Pointers : 1438647 36393 + Primary type : Transport + Nuclide ZAI : 541320 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Xe132.ACE + Atomic weight (AW) : 131.90312 + Atomic weight ratio (AWR) : 130.77000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 28 reaction channels + - 6 special reactions + - 9 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 28 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.93460E+00 MeV Emin = 9.00300E+00 MeV frac = 1.00000E+00 Product nuclide = 54131.82c : (n,2n) + 3 MT = 17 Q = -1.55540E+01 MeV Emin = 1.56730E+01 MeV frac = 1.00000E+00 Product nuclide = 54130.82c : (n,3n) + 4 MT = 22 Q = -2.72480E+00 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 52128.82c : (n,nalpha) + 5 MT = 28 Q = -9.12390E+00 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 53131.82c : (n,np) + 6 MT = 51 Q = -6.67700E-01 MeV Emin = 6.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.29790E+00 MeV Emin = 1.15000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -1.44030E+00 MeV Emin = 1.37956E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -1.80370E+00 MeV Emin = 1.60000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -1.96300E+00 MeV Emin = 1.89775E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -1.98570E+00 MeV Emin = 2.00090E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -2.04040E+00 MeV Emin = 2.05600E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -2.11030E+00 MeV Emin = 2.12644E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -2.11190E+00 MeV Emin = 2.12805E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -2.16710E+00 MeV Emin = 2.18370E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -2.18720E+00 MeV Emin = 2.20393E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -2.21410E+00 MeV Emin = 2.23103E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -2.30340E+00 MeV Emin = 2.32102E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -2.35060E+00 MeV Emin = 2.36860E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -2.39490E+00 MeV Emin = 2.41322E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 21 MT = 66 Q = -2.42480E+00 MeV Emin = 2.44334E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 22 MT = 67 Q = -2.46910E+00 MeV Emin = 2.48800E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 23 MT = 91 Q = -2.46910E+00 MeV Emin = 2.48800E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 24 MT = 102 Q = 6.43444E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 54133.82c : (n,gamma) + 25 MT = 103 Q = -2.79460E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 531320 : (n,p) + 26 MT = 104 Q = -6.89930E+00 MeV Emin = 1.07500E+01 MeV frac = 1.00000E+00 Product nuclide = 53131.82c : (n,d) + 27 MT = 105 Q = -9.27320E+00 MeV Emin = 1.35000E+01 MeV frac = 1.00000E+00 Product nuclide = 53130.82c : (n,t) + 28 MT = 107 Q = 3.36050E+00 MeV Emin = 7.20000E+00 MeV frac = 1.00000E+00 Product nuclide = 521290 : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -2.72480E+00 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -9.12390E+00 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 102 Q = 6.43444E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 541331 : (n,gamma) + 4 MT = 103 Q = -2.79460E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -6.89930E+00 MeV Emin = 1.07500E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -9.27320E+00 MeV Emin = 1.35000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 107 Q = 3.36050E+00 MeV Emin = 7.20000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 6.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.07500E+01 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.35000E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 7.20000E+00 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 8.04891E-04 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 6.00000E-01 MeV : total inelastic scattering + + Nuclide 177 / 1657 : 54133.82c -- xenon 133 (Xe-133) + + Pointers : 1442309 36439 + Primary type : Transport + Nuclide ZAI : 541330 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Xe133.ACE + Atomic weight (AW) : 132.90573 + Atomic weight ratio (AWR) : 131.76400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 4.53E+05 seconds (5.25 days) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 26 reaction channels + - 6 special reactions + - 10 transmutation reactions + - 8 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 26 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.45210E+00 MeV Emin = 6.50108E+00 MeV frac = 1.00000E+00 Product nuclide = 54132.82c : (n,2n) + 3 MT = 17 Q = -1.53932E+01 MeV Emin = 1.55100E+01 MeV frac = 1.00000E+00 Product nuclide = 54131.82c : (n,3n) + 4 MT = 22 Q = -3.07689E+00 MeV Emin = 3.10025E+00 MeV frac = 1.00000E+00 Product nuclide = 521290 : (n,nalpha) + 5 MT = 28 Q = -9.24963E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 531320 : (n,np) + 6 MT = 32 Q = -1.32706E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 53131.82c : (n,nd) + 7 MT = 51 Q = -2.33200E-01 MeV Emin = 2.34375E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 8 MT = 52 Q = -2.62700E-01 MeV Emin = 2.64152E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 9 MT = 53 Q = -5.29899E-01 MeV Emin = 5.22678E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 10 MT = 54 Q = -6.80199E-01 MeV Emin = 6.61699E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 11 MT = 55 Q = -7.43799E-01 MeV Emin = 7.37084E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 12 MT = 56 Q = -8.75299E-01 MeV Emin = 8.61457E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 13 MT = 57 Q = -9.11499E-01 MeV Emin = 9.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 14 MT = 58 Q = -1.05230E+00 MeV Emin = 1.03015E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 15 MT = 59 Q = -1.23640E+00 MeV Emin = 1.22404E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 16 MT = 60 Q = -1.29820E+00 MeV Emin = 1.29354E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 17 MT = 61 Q = -1.35030E+00 MeV Emin = 1.34086E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 18 MT = 62 Q = -1.38500E+00 MeV Emin = 1.38240E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 19 MT = 63 Q = -1.40480E+00 MeV Emin = 1.40549E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 20 MT = 64 Q = -1.59010E+00 MeV Emin = 1.55109E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 21 MT = 91 Q = -1.65000E+00 MeV Emin = 1.63989E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 22 MT = 102 Q = 8.55221E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 54134.82c : (n,gamma) + 23 MT = 103 Q = -9.77534E-01 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 531330 : (n,p) + 24 MT = 104 Q = -6.93951E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 531320 : (n,d) + 25 MT = 105 Q = -7.08545E+00 MeV Emin = 9.02818E+00 MeV frac = 1.00000E+00 Product nuclide = 53131.82c : (n,t) + 26 MT = 107 Q = 5.34020E+00 MeV Emin = 1.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 52130.82c : (n,alpha) + + 8 additional transport branches: + + 1 MT = 22 Q = -3.07689E+00 MeV Emin = 3.10025E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -9.24963E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.32706E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 102 Q = 8.55221E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 541341 : (n,gamma) + 5 MT = 103 Q = -9.77534E-01 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 104 Q = -6.93951E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 7 MT = 105 Q = -7.08545E+00 MeV Emin = 9.02818E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 8 MT = 107 Q = 5.34020E+00 MeV Emin = 1.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.02818E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-01 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 7.60000E-04 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 2.34375E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.27400E-01 MeV frac = 1.00000E+00 Product nuclide = 55133.82c : beta- + + Nuclide 178 / 1657 : 54134.82c -- xenon 134 (Xe-134) + + Pointers : 1446382 36485 + Primary type : Transport + Nuclide ZAI : 541340 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Xe134.ACE + Atomic weight (AW) : 133.91036 + Atomic weight ratio (AWR) : 132.76000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 3.47E+23 seconds (1.1E+16 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 30 reaction channels + - 6 special reactions + - 9 transmutation reactions + - 7 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 30 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.53690E+00 MeV Emin = 8.60120E+00 MeV frac = 1.00000E+00 Product nuclide = 54133.82c : (n,2n) + 3 MT = 17 Q = -1.49750E+01 MeV Emin = 1.50880E+01 MeV frac = 1.00000E+00 Product nuclide = 54132.82c : (n,3n) + 4 MT = 22 Q = -3.20170E+00 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 52130.82c : (n,nalpha) + 5 MT = 28 Q = -9.52530E+00 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 531330 : (n,np) + 6 MT = 51 Q = -8.47000E-01 MeV Emin = 8.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.61380E+00 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -1.73120E+00 MeV Emin = 1.68510E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -1.91960E+00 MeV Emin = 1.93235E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -1.96550E+00 MeV Emin = 1.95079E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -2.13660E+00 MeV Emin = 2.15270E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -2.27200E+00 MeV Emin = 2.28911E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -2.30220E+00 MeV Emin = 2.31954E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -2.35300E+00 MeV Emin = 2.37073E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -2.40850E+00 MeV Emin = 2.42664E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -2.54750E+00 MeV Emin = 2.56670E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -2.58850E+00 MeV Emin = 2.60800E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -2.65390E+00 MeV Emin = 2.67390E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -2.77290E+00 MeV Emin = 2.79380E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -2.86740E+00 MeV Emin = 2.88900E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 21 MT = 66 Q = -3.08380E+00 MeV Emin = 3.10703E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 22 MT = 67 Q = -3.25570E+00 MeV Emin = 3.28022E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 23 MT = 68 Q = -3.31450E+00 MeV Emin = 3.33950E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 24 MT = 69 Q = -3.36050E+00 MeV Emin = 3.38581E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 25 MT = 91 Q = -3.36050E+00 MeV Emin = 3.38581E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 26 MT = 102 Q = 6.36387E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 54135.82c : (n,gamma) + 27 MT = 103 Q = -3.35250E+00 MeV Emin = 6.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 531340 : (n,p) + 28 MT = 104 Q = -7.30080E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 531330 : (n,d) + 29 MT = 105 Q = -9.28810E+00 MeV Emin = 1.35000E+01 MeV frac = 1.00000E+00 Product nuclide = 531320 : (n,t) + 30 MT = 107 Q = 2.72800E+00 MeV Emin = 7.35580E+00 MeV frac = 1.00000E+00 Product nuclide = 521310 : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -3.20170E+00 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -9.52530E+00 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 102 Q = 6.36387E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 541351 : (n,gamma) + 4 MT = 103 Q = -3.35250E+00 MeV Emin = 6.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -7.30080E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -9.28810E+00 MeV Emin = 1.35000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 107 Q = 2.72800E+00 MeV Emin = 7.35580E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 6.50000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.10000E+01 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.35000E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 7.35580E+00 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 8.01105E-04 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 8.00000E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 11 Q = 8.25800E-01 MeV frac = 1.00000E+00 Product nuclide = 56134.82c : beta- + beta- + + Nuclide 179 / 1657 : 54135.82c -- xenon 135 (Xe-135) + + Pointers : 1450235 36531 + Primary type : Transport + Nuclide ZAI : 541350 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Xe135.ACE + Atomic weight (AW) : 134.90692 + Atomic weight ratio (AWR) : 133.74800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 3.29E+04 seconds (9.14 hours) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 4 reaction channels + - 2 special reactions + - 1 transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 4 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -5.27000E-01 MeV Emin = 5.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 91 Q = -5.27000E-01 MeV Emin = 9.62500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 4 MT = 102 Q = 8.07943E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 54136.82c : (n,gamma) + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 7.80000E-04 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 5.25000E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.16500E+00 MeV frac = 1.00000E+00 Product nuclide = 55135.82c : beta- + + Nuclide 180 / 1657 : 54136.82c -- xenon 136 (Xe-136) + + Pointers : 1451950 36577 + Primary type : Transport + Nuclide ZAI : 541360 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Xe136.ACE + Atomic weight (AW) : 135.90752 + Atomic weight ratio (AWR) : 134.74000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 3.16E+29 seconds (1E+22 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 27 reaction channels + - 6 special reactions + - 9 transmutation reactions + - 6 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 27 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.99480E+00 MeV Emin = 8.05414E+00 MeV frac = 1.00000E+00 Product nuclide = 54135.82c : (n,2n) + 3 MT = 17 Q = -1.44470E+01 MeV Emin = 1.45542E+01 MeV frac = 1.00000E+00 Product nuclide = 54134.82c : (n,3n) + 4 MT = 22 Q = -3.63210E+00 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 52132.82c : (n,nalpha) + 5 MT = 28 Q = -9.89700E+00 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 53135.82c : (n,np) + 6 MT = 51 Q = -1.31300E+00 MeV Emin = 1.25000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.69440E+00 MeV Emin = 1.55000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -1.89170E+00 MeV Emin = 1.80635E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -2.12570E+00 MeV Emin = 2.14150E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -2.26150E+00 MeV Emin = 2.27830E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -2.28950E+00 MeV Emin = 2.30650E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -2.41480E+00 MeV Emin = 2.43272E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -2.46500E+00 MeV Emin = 2.48330E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -2.55990E+00 MeV Emin = 2.57890E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -2.60850E+00 MeV Emin = 2.62790E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -2.63420E+00 MeV Emin = 2.65380E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -2.84930E+00 MeV Emin = 2.87045E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -2.86900E+00 MeV Emin = 2.89030E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -2.97910E+00 MeV Emin = 3.00121E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -3.21190E+00 MeV Emin = 3.23574E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 21 MT = 66 Q = -3.27520E+00 MeV Emin = 3.29951E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 22 MT = 91 Q = -3.27520E+00 MeV Emin = 3.29951E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 23 MT = 102 Q = 4.02554E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 541370 : (n,gamma) + 24 MT = 103 Q = -6.09670E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 531360 : (n,p) + 25 MT = 104 Q = -7.67250E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 53135.82c : (n,d) + 26 MT = 105 Q = -9.31790E+00 MeV Emin = 1.35000E+01 MeV frac = 1.00000E+00 Product nuclide = 531340 : (n,t) + 27 MT = 107 Q = 2.18680E+00 MeV Emin = 7.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 521330 : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = -3.63210E+00 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -9.89700E+00 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -6.09670E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -7.67250E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -9.31790E+00 MeV Emin = 1.35000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 107 Q = 2.18680E+00 MeV Emin = 7.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 9.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.10000E+01 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.35000E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 7.50000E+00 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 7.50000E-04 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 1.25000E+00 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 11 Q = 2.45799E+00 MeV frac = 1.00000E+00 Product nuclide = 56136.82c : beta- + beta- + + Nuclide 181 / 1657 : 55133.82c -- cesium 133 (Cs-133) + + Pointers : 1470109 22501 + Primary type : Transport + Nuclide ZAI : 551330 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Cs133.ACE + Atomic weight (AW) : 132.90573 + Atomic weight ratio (AWR) : 131.76400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 11 reaction channels + - 4 special reactions + - 4 transmutation reactions + - 3 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 11 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -9.03800E+00 MeV Emin = 9.10659E+00 MeV frac = 1.00000E+00 Product nuclide = 551320 : (n,2n) + 3 MT = 51 Q = -8.10000E-02 MeV Emin = 7.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 4 MT = 52 Q = -1.61000E-01 MeV Emin = 1.52610E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 5 MT = 53 Q = -3.84000E-01 MeV Emin = 3.44000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 6 MT = 54 Q = -4.37000E-01 MeV Emin = 4.37000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 7 MT = 55 Q = -6.33000E-01 MeV Emin = 6.18900E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 8 MT = 91 Q = -6.45000E-01 MeV Emin = 6.44000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 9 MT = 102 Q = 6.89155E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 55134.82c : (n,gamma) + 10 MT = 103 Q = 1.21000E-01 MeV Emin = 2.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 54133.82c : (n,p) + 11 MT = 107 Q = 3.69500E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 53130.82c : (n,alpha) + + 3 additional transport branches: + + 1 MT = 102 Q = 6.89155E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 551341 : (n,gamma) + 2 MT = 103 Q = 1.21000E-01 MeV Emin = 2.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 107 Q = 3.69500E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 4 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.50000E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 6.00000E+00 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 8.00000E-04 MeV : damage-energy production + 4 MT = 4 Q = 0.00000E+00 MeV Emin = 7.00000E-02 MeV : total inelastic scattering + + Nuclide 182 / 1657 : 55134.82c -- cesium 134 (Cs-134) + + Pointers : 1471553 22547 + Primary type : Transport + Nuclide ZAI : 551340 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Cs134.ACE + Atomic weight (AW) : 133.90733 + Atomic weight ratio (AWR) : 132.75700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 6.51E+07 seconds (2.07 years) + Specific ingestion toxicity : 1.90E-08 Sv/Bq + Specific inhalation toxicity : 2.00E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 14 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 7 transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 14 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -1.10000E-02 MeV Emin = 1.06250E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -6.30000E-02 MeV Emin = 6.29078E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -1.38000E-01 MeV Emin = 1.37577E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -1.76000E-01 MeV Emin = 1.75154E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -1.93000E-01 MeV Emin = 1.85890E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 91 Q = -2.01490E-01 MeV Emin = 2.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 8 MT = 102 Q = 8.76199E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 55135.82c : (n,gamma) + 9 MT = 103 Q = 1.99800E+00 MeV Emin = 4.54004E-02 MeV frac = 1.00000E+00 Product nuclide = 54134.82c : (n,p) + 10 MT = 104 Q = -4.30980E+00 MeV Emin = 4.34227E+00 MeV frac = 1.00000E+00 Product nuclide = 54133.82c : (n,d) + 11 MT = 105 Q = -4.49950E+00 MeV Emin = 4.53339E+00 MeV frac = 1.00000E+00 Product nuclide = 54132.82c : (n,t) + 12 MT = 106 Q = -8.06010E+00 MeV Emin = 8.12081E+00 MeV frac = 1.00000E+00 Product nuclide = 531320 : (n,He-3) + 13 MT = 107 Q = 6.18640E+00 MeV Emin = 4.54004E-02 MeV frac = 1.00000E+00 Product nuclide = 53131.82c : (n,alpha) + 14 MT = 111 Q = -7.51090E+00 MeV Emin = 7.56748E+00 MeV frac = 1.00000E+00 Product nuclide = 531330 : (n,2p) + + 7 additional transport branches: + + 1 MT = 102 Q = 8.76199E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 551351 : (n,gamma) + 2 MT = 103 Q = 1.99800E+00 MeV Emin = 4.54004E-02 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 104 Q = -4.30980E+00 MeV Emin = 4.34227E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 4 MT = 105 Q = -4.49950E+00 MeV Emin = 4.53339E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 5 MT = 106 Q = -8.06010E+00 MeV Emin = 8.12081E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 6 MT = 107 Q = 6.18640E+00 MeV Emin = 4.54004E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 7 MT = 111 Q = -7.51090E+00 MeV Emin = 7.56748E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.54004E-02 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 4.34227E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 4.53339E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 8.12081E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.54004E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 7.86321E-04 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 1.06250E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 2 Q = 1.23330E+00 MeV frac = 3.00000E-06 Product nuclide = 54134.82c : EC/beta+ + 2 RTYP = 1 Q = 2.05898E+00 MeV frac = 9.99997E-01 Product nuclide = 56134.82c : beta- + + Nuclide 183 / 1657 : 55135.82c -- cesium 135 (Cs-135) + + Pointers : 1475411 22593 + Primary type : Transport + Nuclide ZAI : 551350 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Cs135.ACE + Atomic weight (AW) : 134.90591 + Atomic weight ratio (AWR) : 133.74700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 7.26E+13 seconds (2.3 million years) + Specific ingestion toxicity : 2.00E-09 Sv/Bq + Specific inhalation toxicity : 8.60E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 17 reaction channels + - 6 special reactions + - 11 transmutation reactions + - 9 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 17 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.83209E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 55134.82c : (n,2n) + 3 MT = 17 Q = -1.57282E+01 MeV Emin = 1.58458E+01 MeV frac = 1.00000E+00 Product nuclide = 55133.82c : (n,3n) + 4 MT = 22 Q = -2.63589E+00 MeV Emin = 2.65560E+00 MeV frac = 1.00000E+00 Product nuclide = 53131.82c : (n,nalpha) + 5 MT = 28 Q = -6.83363E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 54134.82c : (n,np) + 6 MT = 32 Q = -1.30626E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 54133.82c : (n,nd) + 7 MT = 33 Q = -1.33296E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 54132.82c : (n,nt) + 8 MT = 51 Q = -2.49800E-01 MeV Emin = 2.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -4.07999E-01 MeV Emin = 4.04466E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -6.08199E-01 MeV Emin = 5.84560E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -7.86899E-01 MeV Emin = 7.69587E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 91 Q = -9.80999E-01 MeV Emin = 9.44168E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 13 MT = 102 Q = 6.82818E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 55136.82c : (n,gamma) + 14 MT = 103 Q = -3.76530E-01 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 54135.82c : (n,p) + 15 MT = 104 Q = -4.52351E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 54134.82c : (n,d) + 16 MT = 105 Q = -6.87746E+00 MeV Emin = 8.89814E+00 MeV frac = 1.00000E+00 Product nuclide = 54133.82c : (n,t) + 17 MT = 107 Q = 3.69520E+00 MeV Emin = 1.01563E-01 MeV frac = 1.00000E+00 Product nuclide = 531320 : (n,alpha) + + 9 additional transport branches: + + 1 MT = 22 Q = -2.63589E+00 MeV Emin = 2.65560E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -6.83363E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.30626E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.33296E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 102 Q = 6.82818E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 551361 : (n,gamma) + 6 MT = 103 Q = -3.76530E-01 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 7 MT = 104 Q = -4.52351E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 8 MT = 105 Q = -6.87746E+00 MeV Emin = 8.89814E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 9 MT = 107 Q = 3.69520E+00 MeV Emin = 1.01563E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 8.89814E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 1.01563E-01 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 7.60000E-04 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 2.50000E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.68700E-01 MeV frac = 1.00000E+00 Product nuclide = 56135.82c : beta- + + Nuclide 184 / 1657 : 55136.82c -- cesium 136 (Cs-136) + + Pointers : 1478424 22639 + Primary type : Transport + Nuclide ZAI : 551360 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Cs136.ACE + Atomic weight (AW) : 135.90752 + Atomic weight ratio (AWR) : 134.74000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.13E+06 seconds (13 days) + Specific ingestion toxicity : 3.00E-09 Sv/Bq + Specific inhalation toxicity : 2.80E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 9 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 6 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 9 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 91 Q = -3.67280E-01 MeV Emin = 3.48750E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 3 MT = 102 Q = 8.27640E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 55137.82c : (n,gamma) + 4 MT = 103 Q = 8.49380E-01 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 54136.82c : (n,p) + 5 MT = 104 Q = -4.91450E+00 MeV Emin = 4.95097E+00 MeV frac = 1.00000E+00 Product nuclide = 54135.82c : (n,d) + 6 MT = 105 Q = -5.10920E+00 MeV Emin = 5.14712E+00 MeV frac = 1.00000E+00 Product nuclide = 54134.82c : (n,t) + 7 MT = 106 Q = -9.24470E+00 MeV Emin = 9.31331E+00 MeV frac = 1.00000E+00 Product nuclide = 531340 : (n,He-3) + 8 MT = 107 Q = 5.18870E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 531330 : (n,alpha) + 9 MT = 111 Q = -9.06530E+00 MeV Emin = 9.13258E+00 MeV frac = 1.00000E+00 Product nuclide = 53135.82c : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = 8.49380E-01 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -4.91450E+00 MeV Emin = 4.95097E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -5.10920E+00 MeV Emin = 5.14712E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -9.24470E+00 MeV Emin = 9.31331E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 5.18870E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -9.06530E+00 MeV Emin = 9.13258E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.62500E-02 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 4.95097E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 5.14712E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 9.31331E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 3.48750E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.54850E+00 MeV frac = 1.00000E+00 Product nuclide = 56136.82c : beta- + + Nuclide 185 / 1657 : 55137.82c -- cesium 137 (Cs-137) + + Pointers : 1481848 22685 + Primary type : Transport + Nuclide ZAI : 551370 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Cs137.ACE + Atomic weight (AW) : 136.90711 + Atomic weight ratio (AWR) : 135.73100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 9.48E+08 seconds (30.1 years) + Specific ingestion toxicity : 1.30E-08 Sv/Bq + Specific inhalation toxicity : 3.90E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 20 reaction channels + - 6 special reactions + - 11 transmutation reactions + - 9 transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 20 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.27810E+00 MeV Emin = 8.33910E+00 MeV frac = 1.00000E+00 Product nuclide = 55136.82c : (n,2n) + 3 MT = 17 Q = -1.50472E+01 MeV Emin = 1.51581E+01 MeV frac = 1.00000E+00 Product nuclide = 55135.82c : (n,3n) + 4 MT = 22 Q = -3.07990E+00 MeV Emin = 3.10259E+00 MeV frac = 1.00000E+00 Product nuclide = 531330 : (n,nalpha) + 5 MT = 28 Q = -7.42864E+00 MeV Emin = 8.33910E+00 MeV frac = 1.00000E+00 Product nuclide = 54136.82c : (n,np) + 6 MT = 32 Q = -1.31136E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 54135.82c : (n,nd) + 7 MT = 33 Q = -1.33856E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 54134.82c : (n,nt) + 8 MT = 51 Q = -4.55999E-01 MeV Emin = 4.56250E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -8.48999E-01 MeV Emin = 8.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -9.79999E-01 MeV Emin = 9.65415E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -1.49000E+00 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -1.87000E+00 MeV Emin = 1.81689E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -2.07000E+00 MeV Emin = 2.08525E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -2.15000E+00 MeV Emin = 2.16584E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 91 Q = -2.30000E+00 MeV Emin = 2.31695E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 16 MT = 102 Q = 4.41313E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 551380 : (n,gamma) + 17 MT = 103 Q = -3.56252E+00 MeV Emin = 5.15624E+00 MeV frac = 1.00000E+00 Product nuclide = 541370 : (n,p) + 18 MT = 104 Q = -5.11852E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 54136.82c : (n,d) + 19 MT = 105 Q = -6.92846E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 54135.82c : (n,t) + 20 MT = 107 Q = 3.06421E+00 MeV Emin = 2.75000E-01 MeV frac = 1.00000E+00 Product nuclide = 531340 : (n,alpha) + + 9 additional transport branches: + + 1 MT = 22 Q = -3.07990E+00 MeV Emin = 3.10259E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -7.42864E+00 MeV Emin = 8.33910E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.31136E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.33856E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 102 Q = 4.41313E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 551381 : (n,gamma) + 6 MT = 103 Q = -3.56252E+00 MeV Emin = 5.15624E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 7 MT = 104 Q = -5.11852E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 8 MT = 105 Q = -6.92846E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 9 MT = 107 Q = 3.06421E+00 MeV Emin = 2.75000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 5.15624E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.00000E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 2.75000E-01 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 8.12500E-04 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 4.56250E-01 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.17563E+00 MeV frac = 5.64058E-02 Product nuclide = 56137.82c : beta- + 2 RTYP = 1 Q = 5.13971E-01 MeV frac = 9.43594E-01 Product nuclide = 561371 : beta- + + Nuclide 186 / 1657 : 56134.82c -- barium 134 (Ba-134) + + Pointers : 1514109 19557 + Primary type : Transport + Nuclide ZAI : 561340 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ba134.ACE + Atomic weight (AW) : 133.90431 + Atomic weight ratio (AWR) : 132.75400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 24 reaction channels + - 6 special reactions + - 9 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 24 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -9.47510E+00 MeV Emin = 9.54648E+00 MeV frac = 1.00000E+00 Product nuclide = 561330 : (n,2n) + 3 MT = 17 Q = -1.66672E+01 MeV Emin = 1.67928E+01 MeV frac = 1.00000E+00 Product nuclide = 561320 : (n,3n) + 4 MT = 22 Q = -1.50880E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 54130.82c : (n,nalpha) + 5 MT = 28 Q = -8.17264E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 55133.82c : (n,np) + 6 MT = 51 Q = -6.04699E-01 MeV Emin = 5.54628E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.16790E+00 MeV Emin = 1.17425E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -1.40060E+00 MeV Emin = 1.37086E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -1.64330E+00 MeV Emin = 1.63949E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -1.76050E+00 MeV Emin = 1.75000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -1.96990E+00 MeV Emin = 1.94518E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -2.02920E+00 MeV Emin = 2.04449E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -2.08830E+00 MeV Emin = 2.10403E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -2.15970E+00 MeV Emin = 2.17597E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -2.25460E+00 MeV Emin = 2.27158E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -2.33680E+00 MeV Emin = 2.35440E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -2.37910E+00 MeV Emin = 2.39702E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -2.48860E+00 MeV Emin = 2.50735E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 91 Q = -2.54000E+00 MeV Emin = 2.55913E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 20 MT = 102 Q = 6.97197E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 56135.82c : (n,gamma) + 21 MT = 103 Q = -1.27654E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 55134.82c : (n,p) + 22 MT = 104 Q = -5.86252E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 55133.82c : (n,d) + 23 MT = 105 Q = -8.66746E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 551320 : (n,t) + 24 MT = 107 Q = 5.10720E+00 MeV Emin = 9.99804E-02 MeV frac = 1.00000E+00 Product nuclide = 54131.82c : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -1.50880E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -8.17264E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 102 Q = 6.97197E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 561351 : (n,gamma) + 4 MT = 103 Q = -1.27654E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -5.86252E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -8.66746E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 107 Q = 5.10720E+00 MeV Emin = 9.99804E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.00000E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 9.99804E-02 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 7.77217E-04 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 5.54628E-01 MeV : total inelastic scattering + + Nuclide 187 / 1657 : 56135.82c -- barium 135 (Ba-135) + + Pointers : 1516940 19603 + Primary type : Transport + Nuclide ZAI : 561350 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ba135.ACE + Atomic weight (AW) : 134.90591 + Atomic weight ratio (AWR) : 133.74700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 20 reaction channels + - 7 special reactions + - 11 transmutation reactions + - 9 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 20 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.97810E+00 MeV Emin = 7.11666E+00 MeV frac = 1.00000E+00 Product nuclide = 56134.82c : (n,2n) + 3 MT = 17 Q = -1.64532E+01 MeV Emin = 1.65762E+01 MeV frac = 1.00000E+00 Product nuclide = 561330 : (n,3n) + 4 MT = 22 Q = -1.87090E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 54131.82c : (n,nalpha) + 5 MT = 28 Q = -8.25464E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 55134.82c : (n,np) + 6 MT = 32 Q = -1.28406E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 55133.82c : (n,nd) + 7 MT = 51 Q = -2.21000E-01 MeV Emin = 2.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 8 MT = 52 Q = -2.68200E-01 MeV Emin = 2.60103E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 9 MT = 53 Q = -4.80599E-01 MeV Emin = 4.83983E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 10 MT = 54 Q = -5.87899E-01 MeV Emin = 5.91338E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 11 MT = 55 Q = -8.54999E-01 MeV Emin = 8.30696E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 12 MT = 56 Q = -8.74499E-01 MeV Emin = 8.80696E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 13 MT = 57 Q = -9.79999E-01 MeV Emin = 9.81956E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 14 MT = 91 Q = -1.17000E+00 MeV Emin = 1.17566E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 15 MT = 102 Q = 9.10739E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 56136.82c : (n,gamma) + 16 MT = 103 Q = 5.77454E-01 MeV Emin = 1.67188E+00 MeV frac = 1.00000E+00 Product nuclide = 55135.82c : (n,p) + 17 MT = 104 Q = -5.94452E+00 MeV Emin = 7.11666E+00 MeV frac = 1.00000E+00 Product nuclide = 55134.82c : (n,d) + 18 MT = 105 Q = -6.65546E+00 MeV Emin = 8.31636E+00 MeV frac = 1.00000E+00 Product nuclide = 55133.82c : (n,t) + 19 MT = 106 Q = -7.06383E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 54133.82c : (n,He-3) + 20 MT = 107 Q = 7.07019E+00 MeV Emin = 9.49999E-02 MeV frac = 1.00000E+00 Product nuclide = 54132.82c : (n,alpha) + + 9 additional transport branches: + + 1 MT = 22 Q = -1.87090E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -8.25464E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.28406E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 102 Q = 9.10739E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 561361 : (n,gamma) + 5 MT = 103 Q = 5.77454E-01 MeV Emin = 1.67188E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 104 Q = -5.94452E+00 MeV Emin = 7.11666E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 7 MT = 105 Q = -6.65546E+00 MeV Emin = 8.31636E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 8 MT = 106 Q = -7.06383E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 9 MT = 107 Q = 7.07019E+00 MeV Emin = 9.49999E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.67188E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.11666E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 8.31636E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.10000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 9.49999E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 2.00000E-01 MeV : total inelastic scattering + + Nuclide 188 / 1657 : 56136.82c -- barium 136 (Ba-136) + + Pointers : 1520069 19649 + Primary type : Transport + Nuclide ZAI : 561360 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ba136.ACE + Atomic weight (AW) : 135.90449 + Atomic weight ratio (AWR) : 134.73700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 21 reaction channels + - 6 special reactions + - 9 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 21 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -9.11209E+00 MeV Emin = 9.17973E+00 MeV frac = 1.00000E+00 Product nuclide = 56135.82c : (n,2n) + 3 MT = 17 Q = -1.60902E+01 MeV Emin = 1.62096E+01 MeV frac = 1.00000E+00 Product nuclide = 56134.82c : (n,3n) + 4 MT = 22 Q = -2.04190E+00 MeV Emin = 2.05706E+00 MeV frac = 1.00000E+00 Product nuclide = 54132.82c : (n,nalpha) + 5 MT = 28 Q = -8.53464E+00 MeV Emin = 9.17973E+00 MeV frac = 1.00000E+00 Product nuclide = 55135.82c : (n,np) + 6 MT = 51 Q = -8.18599E-01 MeV Emin = 8.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.55050E+00 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -1.57920E+00 MeV Emin = 1.58008E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -1.86630E+00 MeV Emin = 1.81507E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -2.05400E+00 MeV Emin = 2.06925E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -2.07990E+00 MeV Emin = 2.09534E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -2.12800E+00 MeV Emin = 2.14379E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -2.14020E+00 MeV Emin = 2.15609E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -2.14150E+00 MeV Emin = 2.15740E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -2.20710E+00 MeV Emin = 2.22348E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 91 Q = -2.28400E+00 MeV Emin = 2.30095E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 17 MT = 102 Q = 6.89839E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 56137.82c : (n,gamma) + 18 MT = 103 Q = -1.76554E+00 MeV Emin = 2.05706E+00 MeV frac = 1.00000E+00 Product nuclide = 55136.82c : (n,p) + 19 MT = 104 Q = -6.22452E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 55135.82c : (n,d) + 20 MT = 105 Q = -8.87146E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 55134.82c : (n,t) + 21 MT = 107 Q = 4.41020E+00 MeV Emin = 1.00098E-01 MeV frac = 1.00000E+00 Product nuclide = 54133.82c : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -2.04190E+00 MeV Emin = 2.05706E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -8.53464E+00 MeV Emin = 9.17973E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 102 Q = 6.89839E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 561371 : (n,gamma) + 4 MT = 103 Q = -1.76554E+00 MeV Emin = 2.05706E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -6.22452E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -8.87146E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 107 Q = 4.41020E+00 MeV Emin = 1.00098E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.05706E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.00000E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00098E-01 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 8.00000E-01 MeV : total inelastic scattering + + Nuclide 189 / 1657 : 56137.82c -- barium 137 (Ba-137) + + Pointers : 1523262 19695 + Primary type : Transport + Nuclide ZAI : 561370 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ba137.ACE + Atomic weight (AW) : 136.90610 + Atomic weight ratio (AWR) : 135.73000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 20 reaction channels + - 6 special reactions + - 10 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 20 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.90309E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 56136.82c : (n,2n) + 3 MT = 17 Q = -1.60152E+01 MeV Emin = 1.61332E+01 MeV frac = 1.00000E+00 Product nuclide = 56135.82c : (n,3n) + 4 MT = 22 Q = -2.49290E+00 MeV Emin = 2.51127E+00 MeV frac = 1.00000E+00 Product nuclide = 54133.82c : (n,nalpha) + 5 MT = 28 Q = -8.66863E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 55136.82c : (n,np) + 6 MT = 32 Q = -1.31276E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 55135.82c : (n,nd) + 7 MT = 51 Q = -2.79200E-01 MeV Emin = 2.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 8 MT = 52 Q = -6.61599E-01 MeV Emin = 6.24856E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 9 MT = 53 Q = -1.29000E+00 MeV Emin = 1.29652E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 10 MT = 54 Q = -1.46290E+00 MeV Emin = 1.45191E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 11 MT = 55 Q = -1.79000E+00 MeV Emin = 1.79934E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 12 MT = 56 Q = -1.84000E+00 MeV Emin = 1.83467E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 13 MT = 57 Q = -1.90000E+00 MeV Emin = 1.91282E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 14 MT = 58 Q = -2.04000E+00 MeV Emin = 2.05503E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 15 MT = 91 Q = -2.12000E+00 MeV Emin = 2.13562E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 16 MT = 102 Q = 8.61139E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 56138.82c : (n,gamma) + 17 MT = 103 Q = -3.90530E-01 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 55137.82c : (n,p) + 18 MT = 104 Q = -6.35851E+00 MeV Emin = 8.14238E+00 MeV frac = 1.00000E+00 Product nuclide = 55136.82c : (n,d) + 19 MT = 105 Q = -6.94246E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 55135.82c : (n,t) + 20 MT = 107 Q = 6.04620E+00 MeV Emin = 9.00000E-02 MeV frac = 1.00000E+00 Product nuclide = 54134.82c : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -2.49290E+00 MeV Emin = 2.51127E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -8.66863E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.31276E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 103 Q = -3.90530E-01 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -6.35851E+00 MeV Emin = 8.14238E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -6.94246E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 107 Q = 6.04620E+00 MeV Emin = 9.00000E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.14238E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.00000E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 9.00000E-02 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 2.50000E-01 MeV : total inelastic scattering + + Nuclide 190 / 1657 : 56138.82c -- barium 138 (Ba-138) + + Pointers : 1526125 19741 + Primary type : Transport + Nuclide ZAI : 561380 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ba138.ACE + Atomic weight (AW) : 137.90467 + Atomic weight ratio (AWR) : 136.72000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 30 reaction channels + - 6 special reactions + - 9 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 30 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.61609E+00 MeV Emin = 8.76750E+00 MeV frac = 1.00000E+00 Product nuclide = 56137.82c : (n,2n) + 3 MT = 17 Q = -1.55192E+01 MeV Emin = 1.56724E+01 MeV frac = 1.00000E+00 Product nuclide = 56136.82c : (n,3n) + 4 MT = 22 Q = -2.56990E+00 MeV Emin = 2.58870E+00 MeV frac = 1.00000E+00 Product nuclide = 54134.82c : (n,nalpha) + 5 MT = 28 Q = -9.00663E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 55137.82c : (n,np) + 6 MT = 51 Q = -1.43590E+00 MeV Emin = 1.38502E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.89870E+00 MeV Emin = 1.83129E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -2.09070E+00 MeV Emin = 2.10599E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -2.18960E+00 MeV Emin = 2.20562E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -2.20320E+00 MeV Emin = 2.21932E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -2.21800E+00 MeV Emin = 2.23422E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -2.30770E+00 MeV Emin = 2.32458E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -2.41560E+00 MeV Emin = 2.43327E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -2.44570E+00 MeV Emin = 2.46359E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -2.58320E+00 MeV Emin = 2.60209E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -2.58400E+00 MeV Emin = 2.60290E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -2.63960E+00 MeV Emin = 2.65891E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -2.77950E+00 MeV Emin = 2.79983E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -2.85170E+00 MeV Emin = 2.87256E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -2.88100E+00 MeV Emin = 2.90207E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 21 MT = 66 Q = -2.93150E+00 MeV Emin = 2.95294E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 22 MT = 67 Q = -2.99120E+00 MeV Emin = 3.01308E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 23 MT = 68 Q = -3.05000E+00 MeV Emin = 3.07231E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 24 MT = 69 Q = -3.15600E+00 MeV Emin = 3.17909E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 25 MT = 91 Q = -3.16360E+00 MeV Emin = 3.18674E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 26 MT = 102 Q = 4.72339E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 561390 : (n,gamma) + 27 MT = 103 Q = -4.72052E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 551380 : (n,p) + 28 MT = 104 Q = -6.69651E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 55137.82c : (n,d) + 29 MT = 105 Q = -8.78946E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 55136.82c : (n,t) + 30 MT = 107 Q = 3.88720E+00 MeV Emin = 1.03125E-01 MeV frac = 1.00000E+00 Product nuclide = 54135.82c : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = -2.56990E+00 MeV Emin = 2.58870E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -9.00663E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -4.72052E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -6.69651E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -8.78946E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 107 Q = 3.88720E+00 MeV Emin = 1.03125E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 6.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.00000E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 1.03125E-01 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 1.38502E+00 MeV : total inelastic scattering + + Nuclide 191 / 1657 : 56140.82c -- barium 140 (Ba-140) + + Pointers : 1530191 19787 + Primary type : Transport + Nuclide ZAI : 561400 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ba140.ACE + Atomic weight (AW) : 139.90990 + Atomic weight ratio (AWR) : 138.70800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.10E+06 seconds (12.8 days) + Specific ingestion toxicity : 2.60E-09 Sv/Bq + Specific inhalation toxicity : 5.80E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 11 reaction channels + - 7 special reactions + - 9 transmutation reactions + - 6 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 11 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.24110E+00 MeV Emin = 6.28700E+00 MeV frac = 1.00000E+00 Product nuclide = 561390 : (n,2n) + 3 MT = 17 Q = -1.09590E+01 MeV Emin = 1.10390E+01 MeV frac = 1.00000E+00 Product nuclide = 56138.82c : (n,3n) + 4 MT = 91 Q = -1.00000E-01 MeV Emin = 1.00350E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 5 MT = 102 Q = 4.82520E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 561410 : (n,gamma) + 6 MT = 103 Q = -5.26050E+00 MeV Emin = 5.29843E+00 MeV frac = 1.00000E+00 Product nuclide = 551400 : (n,p) + 7 MT = 104 Q = -7.71660E+00 MeV Emin = 7.77223E+00 MeV frac = 1.00000E+00 Product nuclide = 551390 : (n,d) + 8 MT = 105 Q = -7.39040E+00 MeV Emin = 7.44368E+00 MeV frac = 1.00000E+00 Product nuclide = 551380 : (n,t) + 9 MT = 106 Q = -1.01110E+01 MeV Emin = 1.01839E+01 MeV frac = 1.00000E+00 Product nuclide = 541380 : (n,He-3) + 10 MT = 107 Q = 4.57490E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 541370 : (n,alpha) + 11 MT = 111 Q = -1.40370E+01 MeV Emin = 1.41382E+01 MeV frac = 1.00000E+00 Product nuclide = 541390 : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = -5.26050E+00 MeV Emin = 5.29843E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -7.71660E+00 MeV Emin = 7.77223E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -7.39040E+00 MeV Emin = 7.44368E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -1.01110E+01 MeV Emin = 1.01839E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 4.57490E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -1.40370E+01 MeV Emin = 1.41382E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 5.29843E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.77223E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 7.44368E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.01839E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 1.00350E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.04800E+00 MeV frac = 1.00000E+00 Product nuclide = 57140.82c : beta- + + Nuclide 192 / 1657 : 57138.82c -- lanthanum 138 (La-138) + + Pointers : 1543591 27285 + Primary type : Transport + Nuclide ZAI : 571380 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/La138.ACE + Atomic weight (AW) : 137.90669 + Atomic weight ratio (AWR) : 136.72200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 3.27E+18 seconds (104 billion years) + Specific ingestion toxicity : 1.10E-09 Sv/Bq + Specific inhalation toxicity : 1.50E-07 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 29 reaction channels + - 7 special reactions + - 12 transmutation reactions + - 9 transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 29 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.47010E+00 MeV Emin = 7.52475E+00 MeV frac = 1.00000E+00 Product nuclide = 571370 : (n,2n) + 3 MT = 17 Q = -1.66362E+01 MeV Emin = 1.67579E+01 MeV frac = 1.00000E+00 Product nuclide = 571360 : (n,3n) + 4 MT = 22 Q = -2.03690E+00 MeV Emin = 2.05180E+00 MeV frac = 1.00000E+00 Product nuclide = 55134.82c : (n,nalpha) + 5 MT = 28 Q = -6.08464E+00 MeV Emin = 7.07320E+00 MeV frac = 1.00000E+00 Product nuclide = 56137.82c : (n,np) + 6 MT = 32 Q = -1.06776E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 56136.82c : (n,nd) + 7 MT = 33 Q = -1.36046E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 56135.82c : (n,nt) + 8 MT = 51 Q = -7.25999E-02 MeV Emin = 7.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -1.16200E-01 MeV Emin = 1.14518E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -1.61200E-01 MeV Emin = 1.56190E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -1.92200E-01 MeV Emin = 1.92900E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -2.30400E-01 MeV Emin = 2.24064E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -2.93000E-01 MeV Emin = 2.83857E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -4.13299E-01 MeV Emin = 3.99965E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -4.79299E-01 MeV Emin = 4.81834E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -5.10499E-01 MeV Emin = 5.07117E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -5.18699E-01 MeV Emin = 5.22083E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -6.42299E-01 MeV Emin = 6.27544E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 62 Q = -7.37699E-01 MeV Emin = 7.21548E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 20 MT = 63 Q = -7.38699E-01 MeV Emin = 7.43596E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 21 MT = 64 Q = -8.23399E-01 MeV Emin = 8.14711E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 22 MT = 65 Q = -8.35999E-01 MeV Emin = 8.35769E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 23 MT = 91 Q = -8.42789E-01 MeV Emin = 8.48446E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 24 MT = 102 Q = 8.77839E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 57139.82c : (n,gamma) + 25 MT = 103 Q = 2.53145E+00 MeV Emin = 1.00182E-01 MeV frac = 1.00000E+00 Product nuclide = 56138.82c : (n,p) + 26 MT = 104 Q = -3.77452E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 56137.82c : (n,d) + 27 MT = 105 Q = -4.49247E+00 MeV Emin = 6.12916E+00 MeV frac = 1.00000E+00 Product nuclide = 56136.82c : (n,t) + 28 MT = 106 Q = -7.02183E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 55136.82c : (n,He-3) + 29 MT = 107 Q = 6.79519E+00 MeV Emin = 9.56249E-02 MeV frac = 1.00000E+00 Product nuclide = 55135.82c : (n,alpha) + + 9 additional transport branches: + + 1 MT = 22 Q = -2.03690E+00 MeV Emin = 2.05180E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -6.08464E+00 MeV Emin = 7.07320E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.06776E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.36046E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 103 Q = 2.53145E+00 MeV Emin = 1.00182E-01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 104 Q = -3.77452E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 7 MT = 105 Q = -4.49247E+00 MeV Emin = 6.12916E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 8 MT = 106 Q = -7.02183E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 9 MT = 107 Q = 6.79519E+00 MeV Emin = 9.56249E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.00182E-01 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 6.12916E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.00000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 9.56249E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 7.00000E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 2 Q = 1.74000E+00 MeV frac = 6.52000E-01 Product nuclide = 56138.82c : EC/beta+ + 2 RTYP = 1 Q = 1.05170E+00 MeV frac = 3.48000E-01 Product nuclide = 581380 : beta- + + Nuclide 193 / 1657 : 57139.82c -- lanthanum 139 (La-139) + + Pointers : 1547474 27331 + Primary type : Transport + Nuclide ZAI : 571390 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/La139.ACE + Atomic weight (AW) : 138.90325 + Atomic weight ratio (AWR) : 137.71000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 23 reaction channels + - 7 special reactions + - 10 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 23 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.77820E+00 MeV Emin = 8.84195E+00 MeV frac = 1.00000E+00 Product nuclide = 57138.82c : (n,2n) + 3 MT = 17 Q = -1.62500E+01 MeV Emin = 1.63680E+01 MeV frac = 1.00000E+00 Product nuclide = 571370 : (n,3n) + 4 MT = 22 Q = -2.00100E+00 MeV Emin = 1.22500E+01 MeV frac = 1.00000E+00 Product nuclide = 55135.82c : (n,nalpha) + 5 MT = 28 Q = -6.25490E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 56138.82c : (n,np) + 6 MT = 51 Q = -1.65900E-01 MeV Emin = 1.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.20900E+00 MeV Emin = 1.21366E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -1.21900E+00 MeV Emin = 1.22434E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -1.25680E+00 MeV Emin = 1.24690E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -1.38130E+00 MeV Emin = 1.32861E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -1.42000E+00 MeV Emin = 1.41082E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -1.42050E+00 MeV Emin = 1.43056E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -1.47630E+00 MeV Emin = 1.45891E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -1.53770E+00 MeV Emin = 1.54503E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -1.53790E+00 MeV Emin = 1.54503E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -1.55840E+00 MeV Emin = 1.55940E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 91 Q = -1.55840E+00 MeV Emin = 2.50000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 18 MT = 102 Q = 5.16098E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 57140.82c : (n,gamma) + 19 MT = 103 Q = -1.53150E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 561390 : (n,p) + 20 MT = 104 Q = -4.03040E+00 MeV Emin = 8.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 56138.82c : (n,d) + 21 MT = 105 Q = -6.38470E+00 MeV Emin = 1.12500E+01 MeV frac = 1.00000E+00 Product nuclide = 56137.82c : (n,t) + 22 MT = 106 Q = -7.54160E+00 MeV Emin = 1.70000E+01 MeV frac = 1.00000E+00 Product nuclide = 55137.82c : (n,He-3) + 23 MT = 107 Q = 4.76230E+00 MeV Emin = 5.25000E+00 MeV frac = 1.00000E+00 Product nuclide = 55136.82c : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -2.00100E+00 MeV Emin = 1.22500E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -6.25490E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -1.53150E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -4.03040E+00 MeV Emin = 8.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -6.38470E+00 MeV Emin = 1.12500E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 106 Q = -7.54160E+00 MeV Emin = 1.70000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 7 MT = 107 Q = 4.76230E+00 MeV Emin = 5.25000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 5.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.50000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.12500E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.70000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 5.25000E+00 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 8.03178E-04 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 1.50000E-01 MeV : total inelastic scattering + + Nuclide 194 / 1657 : 57140.82c -- lanthanum 140 (La-140) + + Pointers : 1550286 27377 + Primary type : Transport + Nuclide ZAI : 571400 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/La140.ACE + Atomic weight (AW) : 139.90990 + Atomic weight ratio (AWR) : 138.70800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.45E+05 seconds (1.68 days) + Specific ingestion toxicity : 2.00E-09 Sv/Bq + Specific inhalation toxicity : 1.10E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 14 reaction channels + - 7 special reactions + - 6 transmutation reactions + - 5 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 14 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -3.00000E-02 MeV Emin = 2.89390E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -4.38000E-02 MeV Emin = 4.38176E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -1.63000E-01 MeV Emin = 1.63993E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -2.50000E-01 MeV Emin = 2.38850E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -4.68000E-01 MeV Emin = 4.20685E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -5.81000E-01 MeV Emin = 5.45500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 91 Q = -5.86770E-01 MeV Emin = 5.45500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 9 MT = 102 Q = 6.73000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 571410 : (n,gamma) + 10 MT = 104 Q = -4.45770E+00 MeV Emin = 4.48984E+00 MeV frac = 1.00000E+00 Product nuclide = 561390 : (n,d) + 11 MT = 105 Q = -2.92400E+00 MeV Emin = 2.94508E+00 MeV frac = 1.00000E+00 Product nuclide = 56138.82c : (n,t) + 12 MT = 106 Q = -8.40700E+00 MeV Emin = 8.46761E+00 MeV frac = 1.00000E+00 Product nuclide = 551380 : (n,He-3) + 13 MT = 107 Q = 7.88380E+00 MeV Emin = 4.87635E-02 MeV frac = 1.00000E+00 Product nuclide = 55137.82c : (n,alpha) + 14 MT = 111 Q = -1.01930E+01 MeV Emin = 1.02665E+01 MeV frac = 1.00000E+00 Product nuclide = 551390 : (n,2p) + + 5 additional transport branches: + + 1 MT = 104 Q = -4.45770E+00 MeV Emin = 4.48984E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 2 MT = 105 Q = -2.92400E+00 MeV Emin = 2.94508E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 3 MT = 106 Q = -8.40700E+00 MeV Emin = 8.46761E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 4 MT = 107 Q = 7.88380E+00 MeV Emin = 4.87635E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 5 MT = 111 Q = -1.01930E+01 MeV Emin = 1.02665E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.02665E+01 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 4.48984E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 2.94508E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 8.46761E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.87635E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 2.89390E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.76090E+00 MeV frac = 1.00000E+00 Product nuclide = 58140.82c : beta- + + Nuclide 195 / 1657 : 58140.82c -- cerium 140 (Ce-140) + + Pointers : 1583778 21075 + Primary type : Transport + Nuclide ZAI : 581400 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ce140.ACE + Atomic weight (AW) : 139.90587 + Atomic weight ratio (AWR) : 138.70400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 17 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 17 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -1.59600E+00 MeV Emin = 1.60000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -1.90200E+00 MeV Emin = 1.88760E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -2.08300E+00 MeV Emin = 2.09802E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -2.10000E+00 MeV Emin = 2.11514E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -2.35000E+00 MeV Emin = 2.36694E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -2.41200E+00 MeV Emin = 2.42940E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 57 Q = -2.52100E+00 MeV Emin = 2.53920E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 9 MT = 58 Q = -2.65300E+00 MeV Emin = 2.67213E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 10 MT = 91 Q = -2.64400E+00 MeV Emin = 2.66306E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 11 MT = 102 Q = 5.42850E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 58141.82c : (n,gamma) + 12 MT = 103 Q = -2.97740E+00 MeV Emin = 2.99887E+00 MeV frac = 1.00000E+00 Product nuclide = 57140.82c : (n,p) + 13 MT = 104 Q = -5.91220E+00 MeV Emin = 5.95483E+00 MeV frac = 1.00000E+00 Product nuclide = 57139.82c : (n,d) + 14 MT = 105 Q = -8.43220E+00 MeV Emin = 8.49299E+00 MeV frac = 1.00000E+00 Product nuclide = 57138.82c : (n,t) + 15 MT = 106 Q = -6.66560E+00 MeV Emin = 6.71366E+00 MeV frac = 1.00000E+00 Product nuclide = 56138.82c : (n,He-3) + 16 MT = 107 Q = 5.29670E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 56137.82c : (n,alpha) + 17 MT = 111 Q = -9.65910E+00 MeV Emin = 9.72874E+00 MeV frac = 1.00000E+00 Product nuclide = 561390 : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = -2.97740E+00 MeV Emin = 2.99887E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -5.91220E+00 MeV Emin = 5.95483E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -8.43220E+00 MeV Emin = 8.49299E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -6.66560E+00 MeV Emin = 6.71366E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 5.29670E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -9.65910E+00 MeV Emin = 9.72874E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.99887E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.95483E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 8.49299E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 6.71366E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 1.60000E+00 MeV : total inelastic scattering + + Nuclide 196 / 1657 : 58141.82c -- cerium 141 (Ce-141) + + Pointers : 1586079 21121 + Primary type : Transport + Nuclide ZAI : 581410 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ce141.ACE + Atomic weight (AW) : 140.91050 + Atomic weight ratio (AWR) : 139.70000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.81E+06 seconds (32.5 days) + Specific ingestion toxicity : 7.10E-10 Sv/Bq + Specific inhalation toxicity : 3.80E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 26 reaction channels + - 7 special reactions + - 10 transmutation reactions + - 7 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 26 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.42760E+00 MeV Emin = 5.46650E+00 MeV frac = 1.00000E+00 Product nuclide = 58140.82c : (n,2n) + 3 MT = 17 Q = -1.46140E+01 MeV Emin = 1.47186E+01 MeV frac = 1.00000E+00 Product nuclide = 581390 : (n,3n) + 4 MT = 22 Q = -1.38080E-01 MeV Emin = 8.73990E+00 MeV frac = 1.00000E+00 Product nuclide = 56137.82c : (n,nalpha) + 5 MT = 28 Q = -8.40660E+00 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 57140.82c : (n,np) + 6 MT = 51 Q = -6.62100E-01 MeV Emin = 6.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.13700E+00 MeV Emin = 1.13657E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -1.35450E+00 MeV Emin = 1.27315E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -1.36870E+00 MeV Emin = 1.37135E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -1.37800E+00 MeV Emin = 1.38320E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -1.49700E+00 MeV Emin = 1.44780E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -1.62650E+00 MeV Emin = 1.57291E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -1.69330E+00 MeV Emin = 1.69699E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -1.73900E+00 MeV Emin = 1.72841E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -1.78500E+00 MeV Emin = 1.79749E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -1.80870E+00 MeV Emin = 1.81283E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -1.81200E+00 MeV Emin = 1.82416E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -1.91500E+00 MeV Emin = 1.87685E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -1.94200E+00 MeV Emin = 1.94230E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 91 Q = -1.94200E+00 MeV Emin = 1.97795E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 21 MT = 102 Q = 7.16970E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 58142.82c : (n,gamma) + 22 MT = 103 Q = -1.67960E+00 MeV Emin = 4.75000E+00 MeV frac = 1.00000E+00 Product nuclide = 571410 : (n,p) + 23 MT = 104 Q = -6.18210E+00 MeV Emin = 9.75000E+00 MeV frac = 1.00000E+00 Product nuclide = 57140.82c : (n,d) + 24 MT = 105 Q = -5.08530E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 57139.82c : (n,t) + 25 MT = 106 Q = -7.38050E+00 MeV Emin = 1.70000E+01 MeV frac = 1.00000E+00 Product nuclide = 561390 : (n,He-3) + 26 MT = 107 Q = 8.47330E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 56138.82c : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -1.38080E-01 MeV Emin = 8.73990E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -8.40660E+00 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -1.67960E+00 MeV Emin = 4.75000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -6.18210E+00 MeV Emin = 9.75000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -5.08530E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 106 Q = -7.38050E+00 MeV Emin = 1.70000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 7 MT = 107 Q = 8.47330E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.75000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 9.75000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.00000E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.70000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 6.00000E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.80400E-01 MeV frac = 1.00000E+00 Product nuclide = 59141.82c : beta- + + Nuclide 197 / 1657 : 58142.82c -- cerium 142 (Ce-142) + + Pointers : 1589398 21167 + Primary type : Transport + Nuclide ZAI : 581420 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ce142.ACE + Atomic weight (AW) : 141.90907 + Atomic weight ratio (AWR) : 140.69000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.58E+24 seconds (5E+16 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 22 reaction channels + - 6 special reactions + - 11 transmutation reactions + - 8 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 22 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.17310E+00 MeV Emin = 7.22409E+00 MeV frac = 1.00000E+00 Product nuclide = 58141.82c : (n,2n) + 3 MT = 17 Q = -1.26062E+01 MeV Emin = 1.26958E+01 MeV frac = 1.00000E+00 Product nuclide = 58140.82c : (n,3n) + 4 MT = 22 Q = 1.31609E+00 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 56138.82c : (n,nalpha) + 5 MT = 28 Q = -8.82063E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 571410 : (n,np) + 6 MT = 32 Q = -1.32746E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 57140.82c : (n,nd) + 7 MT = 33 Q = -1.22546E+01 MeV Emin = 1.33690E+01 MeV frac = 1.00000E+00 Product nuclide = 57139.82c : (n,nt) + 8 MT = 51 Q = -6.41199E-01 MeV Emin = 6.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -1.21930E+00 MeV Emin = 1.17188E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -1.53610E+00 MeV Emin = 1.54107E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -1.65260E+00 MeV Emin = 1.64062E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -2.00420E+00 MeV Emin = 2.01845E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -2.03000E+00 MeV Emin = 2.04443E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -2.18700E+00 MeV Emin = 2.20255E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -2.36400E+00 MeV Emin = 2.38080E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -2.39800E+00 MeV Emin = 2.41505E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 91 Q = -2.50000E+00 MeV Emin = 2.51777E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 18 MT = 102 Q = 5.14484E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 58143.82c : (n,gamma) + 19 MT = 103 Q = -3.73452E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 571420 : (n,p) + 20 MT = 104 Q = -6.51051E+00 MeV Emin = 8.16345E+00 MeV frac = 1.00000E+00 Product nuclide = 571410 : (n,d) + 21 MT = 105 Q = -7.08946E+00 MeV Emin = 8.88334E+00 MeV frac = 1.00000E+00 Product nuclide = 57140.82c : (n,t) + 22 MT = 107 Q = 6.04420E+00 MeV Emin = 8.99999E-02 MeV frac = 1.00000E+00 Product nuclide = 561390 : (n,alpha) + + 8 additional transport branches: + + 1 MT = 22 Q = 1.31609E+00 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -8.82063E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.32746E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.22546E+01 MeV Emin = 1.33690E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 103 Q = -3.73452E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 104 Q = -6.51051E+00 MeV Emin = 8.16345E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 7 MT = 105 Q = -7.08946E+00 MeV Emin = 8.88334E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 8 MT = 107 Q = 6.04420E+00 MeV Emin = 8.99999E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 5.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.16345E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 8.88334E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 8.99999E-02 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 8.55469E-04 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 6.25000E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 11 Q = 1.41720E+00 MeV frac = 1.00000E+00 Product nuclide = 601420 : beta- + beta- + + Nuclide 198 / 1657 : 58143.82c -- cerium 143 (Ce-143) + + Pointers : 1592210 21213 + Primary type : Transport + Nuclide ZAI : 581430 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ce143.ACE + Atomic weight (AW) : 142.91270 + Atomic weight ratio (AWR) : 141.68500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.19E+05 seconds (1.38 days) + Specific ingestion toxicity : 1.10E-09 Sv/Bq + Specific inhalation toxicity : 8.30E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 9 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 6 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 9 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 91 Q = -6.95070E-01 MeV Emin = 6.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 3 MT = 102 Q = 6.94000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 58144.82c : (n,gamma) + 4 MT = 103 Q = -2.51650E+00 MeV Emin = 2.53426E+00 MeV frac = 1.00000E+00 Product nuclide = 571430 : (n,p) + 5 MT = 104 Q = -6.65390E+00 MeV Emin = 6.70086E+00 MeV frac = 1.00000E+00 Product nuclide = 571420 : (n,d) + 6 MT = 105 Q = -5.47810E+00 MeV Emin = 5.51677E+00 MeV frac = 1.00000E+00 Product nuclide = 571410 : (n,t) + 7 MT = 106 Q = -8.48700E+00 MeV Emin = 8.54690E+00 MeV frac = 1.00000E+00 Product nuclide = 561410 : (n,He-3) + 8 MT = 107 Q = 7.31900E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 56140.82c : (n,alpha) + 9 MT = 111 Q = -1.02930E+01 MeV Emin = 1.03657E+01 MeV frac = 1.00000E+00 Product nuclide = 561420 : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = -2.51650E+00 MeV Emin = 2.53426E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -6.65390E+00 MeV Emin = 6.70086E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -5.47810E+00 MeV Emin = 5.51677E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -8.48700E+00 MeV Emin = 8.54690E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 7.31900E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -1.02930E+01 MeV Emin = 1.03657E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.53426E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.70086E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 5.51677E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 8.54690E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.62500E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 6.50000E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.46190E+00 MeV frac = 1.00000E+00 Product nuclide = 59143.82c : beta- + + Nuclide 199 / 1657 : 58144.82c -- cerium 144 (Ce-144) + + Pointers : 1596399 21259 + Primary type : Transport + Nuclide ZAI : 581440 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ce144.ACE + Atomic weight (AW) : 143.91430 + Atomic weight ratio (AWR) : 142.67800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.46E+07 seconds (285 days) + Specific ingestion toxicity : 5.20E-09 Sv/Bq + Specific inhalation toxicity : 5.30E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 15 reaction channels + - 6 special reactions + - 11 transmutation reactions + - 8 transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 15 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.89710E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 58143.82c : (n,2n) + 3 MT = 17 Q = -1.20482E+01 MeV Emin = 1.21327E+01 MeV frac = 1.00000E+00 Product nuclide = 58142.82c : (n,3n) + 4 MT = 22 Q = 4.32094E-01 MeV Emin = 1.38519E+00 MeV frac = 1.00000E+00 Product nuclide = 56140.82c : (n,nalpha) + 5 MT = 28 Q = -9.41463E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 571430 : (n,np) + 6 MT = 32 Q = -1.34726E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 571420 : (n,nd) + 7 MT = 33 Q = -1.23736E+01 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 571410 : (n,nt) + 8 MT = 51 Q = -3.97299E-01 MeV Emin = 3.50042E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -9.38399E-01 MeV Emin = 9.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 91 Q = -1.24220E+00 MeV Emin = 1.25000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 11 MT = 102 Q = 4.73117E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 581450 : (n,gamma) + 12 MT = 103 Q = -4.71852E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 571440 : (n,p) + 13 MT = 104 Q = -7.10451E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 571430 : (n,d) + 14 MT = 105 Q = -7.28746E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 571420 : (n,t) + 15 MT = 107 Q = 5.20319E+00 MeV Emin = 1.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 561410 : (n,alpha) + + 8 additional transport branches: + + 1 MT = 22 Q = 4.32094E-01 MeV Emin = 1.38519E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -9.41463E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.34726E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.23736E+01 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 103 Q = -4.71852E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 104 Q = -7.10451E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 7 MT = 105 Q = -7.28746E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 8 MT = 107 Q = 5.20319E+00 MeV Emin = 1.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 6.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 9.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.00000E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-01 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 8.50000E-04 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 3.50042E-01 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 1 Q = 3.18600E-01 MeV frac = 9.88508E-01 Product nuclide = 591440 : beta- + 2 RTYP = 1 Q = 2.59569E-01 MeV frac = 1.14915E-02 Product nuclide = 591441 : beta- + + Nuclide 200 / 1657 : 59141.82c -- praseodymium 141 (Pr-141) + + Pointers : 1619693 30413 + Primary type : Transport + Nuclide ZAI : 591410 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Pr141.ACE + Atomic weight (AW) : 140.90747 + Atomic weight ratio (AWR) : 139.69700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 24 reaction channels + - 28 special reactions + - 9 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 24 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -9.39700E+00 MeV Emin = 9.46427E+00 MeV frac = 1.00000E+00 Product nuclide = 591400 : (n,2n) + 3 MT = 17 Q = -1.73390E+01 MeV Emin = 1.74631E+01 MeV frac = 1.00000E+00 Product nuclide = 591390 : (n,3n) + 4 MT = 22 Q = -1.32400E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 571370 : (n,nalpha) + 5 MT = 24 Q = -1.05000E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 571360 : (n,2nalpha) + 6 MT = 28 Q = -5.22700E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 58140.82c : (n,np) + 7 MT = 41 Q = -1.44280E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 581390 : (n,2np) + 8 MT = 51 Q = -1.45440E-01 MeV Emin = 1.43235E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -1.11770E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -1.12680E+00 MeV Emin = 1.13028E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -1.29260E+00 MeV Emin = 1.30000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -1.29860E+00 MeV Emin = 1.30395E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -1.43630E+00 MeV Emin = 1.37724E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -1.45220E+00 MeV Emin = 1.45459E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -1.45550E+00 MeV Emin = 1.46521E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -1.45740E+00 MeV Emin = 1.46718E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -1.49410E+00 MeV Emin = 1.50240E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -1.51300E+00 MeV Emin = 1.51432E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 62 Q = -1.52100E+00 MeV Emin = 1.52786E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 20 MT = 63 Q = -1.58000E+00 MeV Emin = 1.56160E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 21 MT = 91 Q = -1.27785E+00 MeV Emin = 1.23621E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 22 MT = 102 Q = 5.84315E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 59142.82c : (n,gamma) + 23 MT = 103 Q = 0.00000E+00 MeV Emin = 1.29350E+00 MeV frac = 1.00000E+00 Product nuclide = 58141.82c : (n,p) + 24 MT = 107 Q = 0.00000E+00 MeV Emin = 1.10000E-01 MeV frac = 1.00000E+00 Product nuclide = 57138.82c : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -1.32400E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 24 Q = -1.05000E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,2nalpha) + 3 MT = 28 Q = -5.22700E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 4 MT = 41 Q = -1.44280E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,2np) + 5 MT = 102 Q = 5.84315E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 591421 : (n,gamma) + 6 MT = 103 Q = 0.00000E+00 MeV Emin = 1.29350E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 7 MT = 107 Q = 0.00000E+00 MeV Emin = 1.10000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 28 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.29350E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 1.10000E-01 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 8.85156E-04 MeV : damage-energy production + 4 MT = 600 Q = 2.01000E-01 MeV Emin = 1.29350E+00 MeV : (n,p) to ground state + 5 MT = 601 Q = -4.61060E-01 MeV Emin = 1.90000E+00 MeV : (n,p1) + 6 MT = 602 Q = -9.36000E-01 MeV Emin = 2.00000E+00 MeV : (n,p2) + 7 MT = 603 Q = -1.15352E+00 MeV Emin = 2.60000E+00 MeV : (n,p3) + 8 MT = 604 Q = -1.16770E+00 MeV Emin = 2.60000E+00 MeV : (n,p4) + 9 MT = 605 Q = -1.17700E+00 MeV Emin = 2.60000E+00 MeV : (n,p5) + 10 MT = 606 Q = -1.29600E+00 MeV Emin = 2.60000E+00 MeV : (n,p6) + 11 MT = 607 Q = -1.42550E+00 MeV Emin = 3.00000E+00 MeV : (n,p7) + 12 MT = 608 Q = -1.49230E+00 MeV Emin = 3.00000E+00 MeV : (n,p8) + 13 MT = 609 Q = -1.53800E+00 MeV Emin = 3.00000E+00 MeV : (n,p9) + 14 MT = 610 Q = -1.58400E+00 MeV Emin = 3.00000E+00 MeV : (n,p10) + 15 MT = 611 Q = -1.60770E+00 MeV Emin = 3.00000E+00 MeV : (n,p11) + 16 MT = 612 Q = -1.61100E+00 MeV Emin = 3.00000E+00 MeV : (n,p12) + 17 MT = 613 Q = -1.71400E+00 MeV Emin = 3.00000E+00 MeV : (n,p13) + 18 MT = 614 Q = -1.74100E+00 MeV Emin = 3.00000E+00 MeV : (n,p14) + 19 MT = 649 Q = -1.74100E+00 MeV Emin = 3.00000E+00 MeV : (n,p) to continuum + 20 MT = 800 Q = 6.14900E+00 MeV Emin = 1.10000E-01 MeV : (n,alpha) to ground state + 21 MT = 801 Q = 6.07643E+00 MeV Emin = 1.10000E-01 MeV : (n,a1) + 22 MT = 802 Q = 6.03283E+00 MeV Emin = 1.10000E-01 MeV : (n,a2) + 23 MT = 803 Q = 5.98782E+00 MeV Emin = 1.10000E-01 MeV : (n,a3) + 24 MT = 804 Q = 5.95681E+00 MeV Emin = 1.10000E-01 MeV : (n,a4) + 25 MT = 805 Q = 5.91859E+00 MeV Emin = 1.10000E-01 MeV : (n,a5) + 26 MT = 806 Q = 5.85602E+00 MeV Emin = 1.70000E-01 MeV : (n,a6) + 27 MT = 849 Q = 5.85602E+00 MeV Emin = 1.70000E-01 MeV : (n,alpha) to continuum + 28 MT = 4 Q = 0.00000E+00 MeV Emin = 1.43235E-01 MeV : total inelastic scattering + + Nuclide 201 / 1657 : 59142.82c -- praseodymium 142 (Pr-142) + + Pointers : 1624130 30459 + Primary type : Transport + Nuclide ZAI : 591420 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Pr142.ACE + Atomic weight (AW) : 141.91008 + Atomic weight ratio (AWR) : 140.69100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 6.88E+04 seconds (19.1 hours) + Specific ingestion toxicity : 1.30E-09 Sv/Bq + Specific inhalation toxicity : 5.50E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 9 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 6 transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 9 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 91 Q = -1.98590E-01 MeV Emin = 1.87500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 3 MT = 102 Q = 7.21000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 59143.82c : (n,gamma) + 4 MT = 103 Q = 1.52720E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 58142.82c : (n,p) + 5 MT = 104 Q = -3.41500E+00 MeV Emin = 3.43927E+00 MeV frac = 1.00000E+00 Product nuclide = 58141.82c : (n,d) + 6 MT = 105 Q = -2.58610E+00 MeV Emin = 2.60448E+00 MeV frac = 1.00000E+00 Product nuclide = 58140.82c : (n,t) + 7 MT = 106 Q = -6.32770E+00 MeV Emin = 6.37268E+00 MeV frac = 1.00000E+00 Product nuclide = 57140.82c : (n,He-3) + 8 MT = 107 Q = 9.08440E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 57139.82c : (n,alpha) + 9 MT = 111 Q = -7.28590E+00 MeV Emin = 7.33769E+00 MeV frac = 1.00000E+00 Product nuclide = 571410 : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = 1.52720E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -3.41500E+00 MeV Emin = 3.43927E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -2.58610E+00 MeV Emin = 2.60448E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -6.32770E+00 MeV Emin = 6.37268E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 9.08440E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -7.28590E+00 MeV Emin = 7.33769E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.62500E-02 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 3.43927E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 2.60448E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 6.37268E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.62500E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 1.87500E-01 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 2 Q = 7.45800E-01 MeV frac = 1.64000E-04 Product nuclide = 58142.82c : EC/beta+ + 2 RTYP = 1 Q = 2.16220E+00 MeV frac = 9.99800E-01 Product nuclide = 601420 : beta- + + Nuclide 202 / 1657 : 59143.82c -- praseodymium 143 (Pr-143) + + Pointers : 1626378 30505 + Primary type : Transport + Nuclide ZAI : 591430 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Pr143.ACE + Atomic weight (AW) : 142.91068 + Atomic weight ratio (AWR) : 141.68300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.17E+06 seconds (13.6 days) + Specific ingestion toxicity : 1.20E-09 Sv/Bq + Specific inhalation toxicity : 2.40E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 24 reaction channels + - 7 special reactions + - 12 transmutation reactions + - 10 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 24 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.35110E+00 MeV Emin = 7.40299E+00 MeV frac = 1.00000E+00 Product nuclide = 59142.82c : (n,2n) + 3 MT = 17 Q = -1.31992E+01 MeV Emin = 1.32924E+01 MeV frac = 1.00000E+00 Product nuclide = 59141.82c : (n,3n) + 4 MT = 22 Q = 1.74409E+00 MeV Emin = 9.99804E-02 MeV frac = 1.00000E+00 Product nuclide = 57139.82c : (n,nalpha) + 5 MT = 28 Q = -5.82363E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 58142.82c : (n,np) + 6 MT = 32 Q = -1.06866E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 58141.82c : (n,nd) + 7 MT = 33 Q = -9.93458E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 58140.82c : (n,nt) + 8 MT = 51 Q = -5.73999E-02 MeV Emin = 5.58538E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -3.50600E-01 MeV Emin = 3.26537E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -4.90399E-01 MeV Emin = 4.74063E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -7.21899E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -7.40099E-01 MeV Emin = 7.38451E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -9.37799E-01 MeV Emin = 9.38525E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -1.06030E+00 MeV Emin = 1.03389E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -1.16040E+00 MeV Emin = 1.14496E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -1.38200E+00 MeV Emin = 1.35631E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -1.39770E+00 MeV Emin = 1.40163E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 91 Q = -1.52600E+00 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 19 MT = 102 Q = 5.75347E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 591440 : (n,gamma) + 20 MT = 103 Q = -6.72533E-01 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 58143.82c : (n,p) + 21 MT = 104 Q = -3.51351E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 58142.82c : (n,d) + 22 MT = 105 Q = -4.50146E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 58141.82c : (n,t) + 23 MT = 106 Q = -6.91283E+00 MeV Emin = 1.00047E+01 MeV frac = 1.00000E+00 Product nuclide = 571410 : (n,He-3) + 24 MT = 107 Q = 6.90920E+00 MeV Emin = 9.99608E-02 MeV frac = 1.00000E+00 Product nuclide = 57140.82c : (n,alpha) + + 10 additional transport branches: + + 1 MT = 22 Q = 1.74409E+00 MeV Emin = 9.99804E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -5.82363E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.06866E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -9.93458E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 102 Q = 5.75347E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 591441 : (n,gamma) + 6 MT = 103 Q = -6.72533E-01 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 7 MT = 104 Q = -3.51351E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 8 MT = 105 Q = -4.50146E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 9 MT = 106 Q = -6.91283E+00 MeV Emin = 1.00047E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 10 MT = 107 Q = 6.90920E+00 MeV Emin = 9.99608E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 6.00000E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.00047E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 9.99608E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 8.50000E-04 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 5.58538E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.33900E-01 MeV frac = 1.00000E+00 Product nuclide = 601430 : beta- + + Nuclide 203 / 1657 : 60144.82c -- neodymium 144 (Nd-144) + + Pointers : 1657626 28573 + Primary type : Transport + Nuclide ZAI : 601440 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Nd144.ACE + Atomic weight (AW) : 143.91027 + Atomic weight ratio (AWR) : 142.67400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 7.23E+22 seconds (2.29E+15 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 50 reaction channels + - 18 special reactions + - 9 transmutation reactions + - 6 transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 50 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.81600E+00 MeV Emin = 7.87078E+00 MeV frac = 1.00000E+00 Product nuclide = 601430 : (n,2n) + 3 MT = 17 Q = -1.39390E+01 MeV Emin = 1.40367E+01 MeV frac = 1.00000E+00 Product nuclide = 601420 : (n,3n) + 4 MT = 22 Q = 1.90600E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 58140.82c : (n,nalpha) + 5 MT = 24 Q = -7.29500E+00 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 581390 : (n,2nalpha) + 6 MT = 28 Q = -7.96800E+00 MeV Emin = 8.02385E+00 MeV frac = 1.00000E+00 Product nuclide = 59143.82c : (n,np) + 7 MT = 41 Q = -1.53200E+01 MeV Emin = 1.70000E+01 MeV frac = 1.00000E+00 Product nuclide = 59142.82c : (n,2np) + 8 MT = 51 Q = -6.96510E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -1.31454E+00 MeV Emin = 1.30000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -1.51053E+00 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -1.56091E+00 MeV Emin = 1.54649E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -1.79145E+00 MeV Emin = 1.80000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -2.07274E+00 MeV Emin = 2.08727E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -2.08445E+00 MeV Emin = 2.09906E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -2.09346E+00 MeV Emin = 2.10813E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -2.10946E+00 MeV Emin = 2.12425E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -2.17837E+00 MeV Emin = 2.19364E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -2.18568E+00 MeV Emin = 2.20100E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 62 Q = -2.20458E+00 MeV Emin = 2.22003E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 20 MT = 63 Q = -2.21812E+00 MeV Emin = 2.23367E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 21 MT = 64 Q = -2.27012E+00 MeV Emin = 2.28603E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 22 MT = 65 Q = -2.29510E+00 MeV Emin = 2.31119E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 23 MT = 66 Q = -2.32170E+00 MeV Emin = 2.33797E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 24 MT = 67 Q = -2.36823E+00 MeV Emin = 2.38483E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 25 MT = 68 Q = -2.39940E+00 MeV Emin = 2.41622E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 26 MT = 69 Q = -2.41993E+00 MeV Emin = 2.43689E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 27 MT = 70 Q = -2.44720E+00 MeV Emin = 2.46435E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 28 MT = 71 Q = -2.45127E+00 MeV Emin = 2.46845E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 29 MT = 72 Q = -2.50841E+00 MeV Emin = 2.52599E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 30 MT = 73 Q = -2.52692E+00 MeV Emin = 2.54463E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 31 MT = 74 Q = -2.56384E+00 MeV Emin = 2.58181E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 32 MT = 75 Q = -2.58165E+00 MeV Emin = 2.59975E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 33 MT = 76 Q = -2.59177E+00 MeV Emin = 2.60994E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 34 MT = 77 Q = -2.60079E+00 MeV Emin = 2.61902E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 27. excited state + 35 MT = 78 Q = -2.60508E+00 MeV Emin = 2.62334E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 28. excited state + 36 MT = 79 Q = -2.61257E+00 MeV Emin = 2.63088E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 29. excited state + 37 MT = 80 Q = -2.61390E+00 MeV Emin = 2.63222E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 30. excited state + 38 MT = 81 Q = -2.65460E+00 MeV Emin = 2.67321E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 31. excited state + 39 MT = 82 Q = -2.65478E+00 MeV Emin = 2.67339E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 32. excited state + 40 MT = 83 Q = -2.67533E+00 MeV Emin = 2.69408E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 33. excited state + 41 MT = 84 Q = -2.68134E+00 MeV Emin = 2.70013E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 34. excited state + 42 MT = 85 Q = -2.69264E+00 MeV Emin = 2.71151E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 35. excited state + 43 MT = 86 Q = -2.70988E+00 MeV Emin = 2.72887E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 36. excited state + 44 MT = 87 Q = -2.71537E+00 MeV Emin = 2.73440E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 37. excited state + 45 MT = 88 Q = -2.71910E+00 MeV Emin = 2.73816E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 38. excited state + 46 MT = 89 Q = -2.73208E+00 MeV Emin = 2.75123E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 39. excited state + 47 MT = 91 Q = -6.88177E-01 MeV Emin = 6.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 48 MT = 102 Q = 5.75529E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 60145.82c : (n,gamma) + 49 MT = 103 Q = 0.00000E+00 MeV Emin = 3.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 591440 : (n,p) + 50 MT = 107 Q = 0.00000E+00 MeV Emin = 2.75000E-01 MeV frac = 1.00000E+00 Product nuclide = 58141.82c : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = 1.90600E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 24 Q = -7.29500E+00 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,2nalpha) + 3 MT = 28 Q = -7.96800E+00 MeV Emin = 8.02385E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 4 MT = 41 Q = -1.53200E+01 MeV Emin = 1.70000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,2np) + 5 MT = 103 Q = 0.00000E+00 MeV Emin = 3.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 107 Q = 0.00000E+00 MeV Emin = 2.75000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 18 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.50000E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 2.75000E-01 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 8.83648E-04 MeV : damage-energy production + 4 MT = 600 Q = -2.21500E+00 MeV Emin = 3.50000E+00 MeV : (n,p) to ground state + 5 MT = 649 Q = -2.21500E+00 MeV Emin = 3.50000E+00 MeV : (n,p) to continuum + 6 MT = 800 Q = 7.33400E+00 MeV Emin = 2.75000E-01 MeV : (n,alpha) to ground state + 7 MT = 801 Q = 6.67194E+00 MeV Emin = 2.75000E-01 MeV : (n,a1) + 8 MT = 802 Q = 6.19700E+00 MeV Emin = 2.75000E-01 MeV : (n,a2) + 9 MT = 803 Q = 5.97948E+00 MeV Emin = 2.75000E-01 MeV : (n,a3) + 10 MT = 804 Q = 5.96530E+00 MeV Emin = 3.00000E-01 MeV : (n,a4) + 11 MT = 805 Q = 5.95600E+00 MeV Emin = 2.75000E-01 MeV : (n,a5) + 12 MT = 806 Q = 5.83700E+00 MeV Emin = 2.75000E-01 MeV : (n,a6) + 13 MT = 807 Q = 5.70750E+00 MeV Emin = 3.00000E-01 MeV : (n,a7) + 14 MT = 808 Q = 5.64070E+00 MeV Emin = 4.00000E-01 MeV : (n,a8) + 15 MT = 809 Q = 5.59500E+00 MeV Emin = 5.00000E-01 MeV : (n,a9) + 16 MT = 810 Q = 5.54900E+00 MeV Emin = 5.00000E-01 MeV : (n,a10) + 17 MT = 849 Q = 5.54900E+00 MeV Emin = 2.75000E-01 MeV : (n,alpha) to continuum + 18 MT = 4 Q = 0.00000E+00 MeV Emin = 6.00000E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 4 Q = 1.90520E+00 MeV frac = 1.00000E+00 Product nuclide = 58140.82c : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 1.90520E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 204 / 1657 : 60145.82c -- neodymium 145 (Nd-145) + + Pointers : 1663318 28619 + Primary type : Transport + Nuclide ZAI : 601450 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Nd145.ACE + Atomic weight (AW) : 144.91288 + Atomic weight ratio (AWR) : 143.66800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 24 reaction channels + - 7 special reactions + - 8 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 24 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.71550E+00 MeV Emin = 5.75530E+00 MeV frac = 1.00000E+00 Product nuclide = 60144.82c : (n,2n) + 3 MT = 51 Q = -6.72000E-02 MeV Emin = 6.72000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 4 MT = 52 Q = -7.24000E-02 MeV Emin = 7.24000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 5 MT = 53 Q = -5.06600E-01 MeV Emin = 5.06600E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 6 MT = 54 Q = -6.57600E-01 MeV Emin = 6.57600E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 7 MT = 55 Q = -7.48200E-01 MeV Emin = 7.50400E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 8 MT = 56 Q = -7.80300E-01 MeV Emin = 7.80300E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 9 MT = 57 Q = -8.40700E-01 MeV Emin = 8.40733E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 10 MT = 58 Q = -9.20200E-01 MeV Emin = 9.23552E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 11 MT = 59 Q = -9.20500E-01 MeV Emin = 9.26681E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 12 MT = 60 Q = -9.34000E-01 MeV Emin = 9.34000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 13 MT = 61 Q = -1.05100E+00 MeV Emin = 1.05120E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 14 MT = 62 Q = -1.08500E+00 MeV Emin = 1.08490E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 15 MT = 63 Q = -1.11200E+00 MeV Emin = 1.11200E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 16 MT = 64 Q = -1.15000E+00 MeV Emin = 1.15000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 17 MT = 91 Q = -1.15300E+00 MeV Emin = 1.16096E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 18 MT = 102 Q = 7.56524E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 60146.82c : (n,gamma) + 19 MT = 103 Q = -7.24300E-01 MeV Emin = 6.95759E-01 MeV frac = 1.00000E+00 Product nuclide = 591450 : (n,p) + 20 MT = 104 Q = -6.06970E+00 MeV Emin = 6.11195E+00 MeV frac = 1.00000E+00 Product nuclide = 591440 : (n,d) + 21 MT = 105 Q = -5.24730E+00 MeV Emin = 5.28383E+00 MeV frac = 1.00000E+00 Product nuclide = 59143.82c : (n,t) + 22 MT = 106 Q = -7.00850E+00 MeV Emin = 7.05730E+00 MeV frac = 1.00000E+00 Product nuclide = 58143.82c : (n,He-3) + 23 MT = 107 Q = 8.75200E+00 MeV Emin = 4.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 58142.82c : (n,alpha) + 24 MT = 111 Q = -7.50280E+00 MeV Emin = 7.55502E+00 MeV frac = 1.00000E+00 Product nuclide = 58144.82c : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = -7.24300E-01 MeV Emin = 6.95759E-01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -6.06970E+00 MeV Emin = 6.11195E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -5.24730E+00 MeV Emin = 5.28383E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -7.00850E+00 MeV Emin = 7.05730E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 8.75200E+00 MeV Emin = 4.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -7.50280E+00 MeV Emin = 7.55502E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 6.95759E-01 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.11195E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 5.28383E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 7.05730E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.00000E-01 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 8.85850E-04 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 6.72000E-02 MeV : total inelastic scattering + + Nuclide 205 / 1657 : 60146.82c -- neodymium 146 (Nd-146) + + Pointers : 1666130 28665 + Primary type : Transport + Nuclide ZAI : 601460 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Nd146.ACE + Atomic weight (AW) : 145.91347 + Atomic weight ratio (AWR) : 144.66000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 33 reaction channels + - 24 special reactions + - 9 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 33 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.56500E+00 MeV Emin = 7.61730E+00 MeV frac = 1.00000E+00 Product nuclide = 60145.82c : (n,2n) + 3 MT = 17 Q = -1.33210E+01 MeV Emin = 1.34131E+01 MeV frac = 1.00000E+00 Product nuclide = 60144.82c : (n,3n) + 4 MT = 22 Q = 1.18200E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 58142.82c : (n,nalpha) + 5 MT = 24 Q = -5.98700E+00 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 58141.82c : (n,2nalpha) + 6 MT = 28 Q = -8.58900E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 591450 : (n,np) + 7 MT = 41 Q = -1.55360E+01 MeV Emin = 1.70000E+01 MeV frac = 1.00000E+00 Product nuclide = 591440 : (n,2np) + 8 MT = 51 Q = -4.53860E-01 MeV Emin = 4.56000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -9.15500E-01 MeV Emin = 9.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -1.04317E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -1.18951E+00 MeV Emin = 1.10000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -1.30320E+00 MeV Emin = 1.30000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -1.37675E+00 MeV Emin = 1.34924E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -1.47060E+00 MeV Emin = 1.44038E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -1.51770E+00 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -1.60270E+00 MeV Emin = 1.60000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -1.69710E+00 MeV Emin = 1.70000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -1.74510E+00 MeV Emin = 1.73300E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 62 Q = -1.76970E+00 MeV Emin = 1.76955E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 20 MT = 63 Q = -1.77720E+00 MeV Emin = 1.78571E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 21 MT = 64 Q = -1.78010E+00 MeV Emin = 1.79095E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 22 MT = 65 Q = -1.78740E+00 MeV Emin = 1.79608E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 23 MT = 66 Q = -1.81200E+00 MeV Emin = 1.81226E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 24 MT = 67 Q = -1.83400E+00 MeV Emin = 1.83560E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 25 MT = 68 Q = -1.88470E+00 MeV Emin = 1.87220E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 26 MT = 69 Q = -1.90540E+00 MeV Emin = 1.90928E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 27 MT = 70 Q = -1.91890E+00 MeV Emin = 1.92537E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 28 MT = 71 Q = -1.97794E+00 MeV Emin = 1.96189E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 29 MT = 72 Q = -1.98930E+00 MeV Emin = 2.00305E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 30 MT = 91 Q = -6.88242E-01 MeV Emin = 6.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 31 MT = 102 Q = 5.29221E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 60147.82c : (n,gamma) + 32 MT = 103 Q = 0.00000E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 591460 : (n,p) + 33 MT = 107 Q = 0.00000E+00 MeV Emin = 1.70000E-02 MeV frac = 1.00000E+00 Product nuclide = 58143.82c : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = 1.18200E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 24 Q = -5.98700E+00 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,2nalpha) + 3 MT = 28 Q = -8.58900E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 4 MT = 41 Q = -1.55360E+01 MeV Emin = 1.70000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,2np) + 5 MT = 103 Q = 0.00000E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 107 Q = 0.00000E+00 MeV Emin = 1.70000E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 24 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.00000E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 1.70000E-02 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 8.85156E-04 MeV : damage-energy production + 4 MT = 600 Q = -3.38800E+00 MeV Emin = 4.00000E+00 MeV : (n,p) to ground state + 5 MT = 601 Q = -3.40023E+00 MeV Emin = 4.00000E+00 MeV : (n,p1) + 6 MT = 602 Q = -3.42305E+00 MeV Emin = 5.00000E+00 MeV : (n,p2) + 7 MT = 603 Q = -3.47519E+00 MeV Emin = 5.00000E+00 MeV : (n,p3) + 8 MT = 604 Q = -3.48888E+00 MeV Emin = 5.00000E+00 MeV : (n,p4) + 9 MT = 605 Q = -3.52152E+00 MeV Emin = 5.00000E+00 MeV : (n,p5) + 10 MT = 649 Q = -3.52152E+00 MeV Emin = 5.00000E+00 MeV : (n,p) to continuum + 11 MT = 800 Q = 6.32600E+00 MeV Emin = 1.70000E-02 MeV : (n,alpha) to ground state + 12 MT = 801 Q = 6.30710E+00 MeV Emin = 1.70000E-02 MeV : (n,a1) + 13 MT = 802 Q = 6.28372E+00 MeV Emin = 1.70000E-02 MeV : (n,a2) + 14 MT = 803 Q = 5.69350E+00 MeV Emin = 4.00000E-01 MeV : (n,a3) + 15 MT = 804 Q = 5.68570E+00 MeV Emin = 4.00000E-01 MeV : (n,a4) + 16 MT = 805 Q = 5.66330E+00 MeV Emin = 4.78499E-01 MeV : (n,a5) + 17 MT = 806 Q = 5.51780E+00 MeV Emin = 5.50000E-01 MeV : (n,a6) + 18 MT = 807 Q = 5.50900E+00 MeV Emin = 5.50000E-01 MeV : (n,a7) + 19 MT = 808 Q = 5.46390E+00 MeV Emin = 6.00000E-01 MeV : (n,a8) + 20 MT = 809 Q = 5.23070E+00 MeV Emin = 8.00000E-01 MeV : (n,a9) + 21 MT = 810 Q = 5.20920E+00 MeV Emin = 8.00000E-01 MeV : (n,a10) + 22 MT = 811 Q = 5.17190E+00 MeV Emin = 8.00000E-01 MeV : (n,a11) + 23 MT = 849 Q = 5.17190E+00 MeV Emin = 7.00000E-02 MeV : (n,alpha) to continuum + 24 MT = 4 Q = 0.00000E+00 MeV Emin = 4.56000E-01 MeV : total inelastic scattering + + Nuclide 206 / 1657 : 60147.82c -- neodymium 147 (Nd-147) + + Pointers : 1670840 28711 + Primary type : Transport + Nuclide ZAI : 601470 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Nd147.ACE + Atomic weight (AW) : 146.91609 + Atomic weight ratio (AWR) : 145.65400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 9.52E+05 seconds (11 days) + Specific ingestion toxicity : 1.10E-09 Sv/Bq + Specific inhalation toxicity : 2.40E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 34 reaction channels + - 42 special reactions + - 9 transmutation reactions + - 6 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 34 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.29100E+00 MeV Emin = 5.32733E+00 MeV frac = 1.00000E+00 Product nuclide = 60146.82c : (n,2n) + 3 MT = 17 Q = -1.28560E+01 MeV Emin = 1.29443E+01 MeV frac = 1.00000E+00 Product nuclide = 60145.82c : (n,3n) + 4 MT = 22 Q = 1.03500E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 58143.82c : (n,nalpha) + 5 MT = 24 Q = -4.10900E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 58142.82c : (n,2nalpha) + 6 MT = 28 Q = -8.67900E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 591460 : (n,np) + 7 MT = 41 Q = -1.38800E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 591450 : (n,2np) + 8 MT = 51 Q = -4.99300E-02 MeV Emin = 5.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -1.27920E-01 MeV Emin = 1.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -1.90290E-01 MeV Emin = 1.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -2.14600E-01 MeV Emin = 2.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -3.14670E-01 MeV Emin = 3.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -4.63620E-01 MeV Emin = 4.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -5.16710E-01 MeV Emin = 5.10129E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -5.81310E-01 MeV Emin = 5.52779E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -6.04520E-01 MeV Emin = 6.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -6.31490E-01 MeV Emin = 6.22248E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -6.56000E-01 MeV Emin = 6.48165E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 62 Q = -7.49000E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 20 MT = 63 Q = -7.69180E-01 MeV Emin = 7.65107E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 21 MT = 64 Q = -7.92560E-01 MeV Emin = 7.87036E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 22 MT = 65 Q = -8.09000E-01 MeV Emin = 8.07277E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 23 MT = 66 Q = -8.59000E-01 MeV Emin = 8.39726E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 24 MT = 67 Q = -9.04000E-01 MeV Emin = 9.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 25 MT = 68 Q = -9.34000E-01 MeV Emin = 9.25310E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 26 MT = 69 Q = -9.42060E-01 MeV Emin = 9.44470E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 27 MT = 70 Q = -9.57260E-01 MeV Emin = 9.56180E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 28 MT = 71 Q = -9.83000E-01 MeV Emin = 9.81916E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 29 MT = 72 Q = -1.02900E+00 MeV Emin = 1.01803E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 30 MT = 73 Q = -1.04148E+00 MeV Emin = 1.04235E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 31 MT = 91 Q = -4.91625E-01 MeV Emin = 4.80902E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 32 MT = 102 Q = 7.33279E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 60148.82c : (n,gamma) + 33 MT = 103 Q = 0.00000E+00 MeV Emin = 3.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 591470 : (n,p) + 34 MT = 107 Q = 0.00000E+00 MeV Emin = 1.50000E-02 MeV frac = 1.00000E+00 Product nuclide = 58144.82c : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = 1.03500E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 24 Q = -4.10900E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,2nalpha) + 3 MT = 28 Q = -8.67900E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 4 MT = 41 Q = -1.38800E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,2np) + 5 MT = 103 Q = 0.00000E+00 MeV Emin = 3.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 107 Q = 0.00000E+00 MeV Emin = 1.50000E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 42 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.50000E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 1.50000E-02 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 8.50000E-04 MeV : damage-energy production + 4 MT = 600 Q = -1.90300E+00 MeV Emin = 3.50000E+00 MeV : (n,p) to ground state + 5 MT = 601 Q = -1.90560E+00 MeV Emin = 3.50000E+00 MeV : (n,p1) + 6 MT = 602 Q = -1.93110E+00 MeV Emin = 3.50000E+00 MeV : (n,p2) + 7 MT = 603 Q = -1.99590E+00 MeV Emin = 3.50000E+00 MeV : (n,p3) + 8 MT = 604 Q = -2.14900E+00 MeV Emin = 3.50000E+00 MeV : (n,p4) + 9 MT = 605 Q = -2.19500E+00 MeV Emin = 3.50000E+00 MeV : (n,p5) + 10 MT = 606 Q = -2.26470E+00 MeV Emin = 3.50000E+00 MeV : (n,p6) + 11 MT = 607 Q = -2.28730E+00 MeV Emin = 3.50000E+00 MeV : (n,p7) + 12 MT = 608 Q = -2.35400E+00 MeV Emin = 4.00000E+00 MeV : (n,p8) + 13 MT = 609 Q = -2.37010E+00 MeV Emin = 4.00000E+00 MeV : (n,p9) + 14 MT = 610 Q = -2.37370E+00 MeV Emin = 4.00000E+00 MeV : (n,p10) + 15 MT = 611 Q = -2.44860E+00 MeV Emin = 4.00000E+00 MeV : (n,p11) + 16 MT = 612 Q = -2.48350E+00 MeV Emin = 4.00000E+00 MeV : (n,p12) + 17 MT = 613 Q = -2.51000E+00 MeV Emin = 4.00000E+00 MeV : (n,p13) + 18 MT = 614 Q = -2.53990E+00 MeV Emin = 4.00000E+00 MeV : (n,p14) + 19 MT = 649 Q = -2.53990E+00 MeV Emin = 4.00000E+00 MeV : (n,p) to continuum + 20 MT = 800 Q = 7.93100E+00 MeV Emin = 1.50000E-02 MeV : (n,alpha) to ground state + 21 MT = 801 Q = 7.53356E+00 MeV Emin = 1.50000E-02 MeV : (n,a1) + 22 MT = 802 Q = 6.99235E+00 MeV Emin = 1.50000E-02 MeV : (n,a2) + 23 MT = 803 Q = 6.68879E+00 MeV Emin = 1.50000E-02 MeV : (n,a3) + 24 MT = 804 Q = 6.58490E+00 MeV Emin = 1.50000E-02 MeV : (n,a4) + 25 MT = 805 Q = 6.44200E+00 MeV Emin = 1.50000E-02 MeV : (n,a5) + 26 MT = 806 Q = 6.40733E+00 MeV Emin = 1.50000E-02 MeV : (n,a6) + 27 MT = 807 Q = 6.25733E+00 MeV Emin = 1.50000E-02 MeV : (n,a7) + 28 MT = 808 Q = 6.23947E+00 MeV Emin = 1.50000E-02 MeV : (n,a8) + 29 MT = 809 Q = 6.11200E+00 MeV Emin = 6.00000E-02 MeV : (n,a9) + 30 MT = 810 Q = 6.10199E+00 MeV Emin = 6.00000E-02 MeV : (n,a10) + 31 MT = 811 Q = 6.06650E+00 MeV Emin = 6.00000E-02 MeV : (n,a11) + 32 MT = 812 Q = 6.04008E+00 MeV Emin = 9.00000E-02 MeV : (n,a12) + 33 MT = 813 Q = 5.93945E+00 MeV Emin = 1.95798E-01 MeV : (n,a13) + 34 MT = 814 Q = 5.90990E+00 MeV Emin = 1.95798E-01 MeV : (n,a14) + 35 MT = 815 Q = 5.90230E+00 MeV Emin = 2.00000E-01 MeV : (n,a15) + 36 MT = 816 Q = 5.89030E+00 MeV Emin = 2.00000E-01 MeV : (n,a16) + 37 MT = 817 Q = 5.81890E+00 MeV Emin = 2.50000E-01 MeV : (n,a17) + 38 MT = 818 Q = 5.80400E+00 MeV Emin = 2.50000E-01 MeV : (n,a18) + 39 MT = 819 Q = 5.77820E+00 MeV Emin = 3.00000E-01 MeV : (n,a19) + 40 MT = 820 Q = 5.71020E+00 MeV Emin = 3.58415E-01 MeV : (n,a20) + 41 MT = 849 Q = 5.71020E+00 MeV Emin = 1.50000E-02 MeV : (n,alpha) to continuum + 42 MT = 4 Q = 0.00000E+00 MeV Emin = 5.00000E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.96100E-01 MeV frac = 1.00000E+00 Product nuclide = 61147.82c : beta- + + Nuclide 207 / 1657 : 60148.82c -- neodymium 148 (Nd-148) + + Pointers : 1677953 28757 + Primary type : Transport + Nuclide ZAI : 601480 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Nd148.ACE + Atomic weight (AW) : 147.91668 + Atomic weight ratio (AWR) : 146.64600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 9.47E+25 seconds (3E+18 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 17 reaction channels + - 7 special reactions + - 8 transmutation reactions + - 6 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 17 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.27450E+00 MeV Emin = 7.32411E+00 MeV frac = 1.00000E+00 Product nuclide = 60147.82c : (n,2n) + 3 MT = 51 Q = -3.01700E-01 MeV Emin = 3.02136E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 4 MT = 52 Q = -7.52000E-01 MeV Emin = 7.52000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 5 MT = 53 Q = -7.91100E-01 MeV Emin = 7.91100E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 6 MT = 54 Q = -9.16900E-01 MeV Emin = 9.16900E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 7 MT = 55 Q = -9.98800E-01 MeV Emin = 1.00280E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 8 MT = 56 Q = -1.02000E+00 MeV Emin = 1.02000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 9 MT = 57 Q = -1.17100E+00 MeV Emin = 1.17050E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 10 MT = 91 Q = -3.01700E-01 MeV Emin = 1.22050E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 11 MT = 102 Q = 5.03879E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 601490 : (n,gamma) + 12 MT = 103 Q = -4.90780E+00 MeV Emin = 4.94127E+00 MeV frac = 1.00000E+00 Product nuclide = 591480 : (n,p) + 13 MT = 104 Q = -7.11150E+00 MeV Emin = 7.16003E+00 MeV frac = 1.00000E+00 Product nuclide = 591470 : (n,d) + 14 MT = 105 Q = -7.31710E+00 MeV Emin = 7.36700E+00 MeV frac = 1.00000E+00 Product nuclide = 591460 : (n,t) + 15 MT = 106 Q = -8.35920E+00 MeV Emin = 8.41620E+00 MeV frac = 1.00000E+00 Product nuclide = 581460 : (n,He-3) + 16 MT = 107 Q = 5.36000E+00 MeV Emin = 4.50000E-01 MeV frac = 1.00000E+00 Product nuclide = 581450 : (n,alpha) + 17 MT = 111 Q = -1.16690E+01 MeV Emin = 1.17486E+01 MeV frac = 1.00000E+00 Product nuclide = 581470 : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = -4.90780E+00 MeV Emin = 4.94127E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -7.11150E+00 MeV Emin = 7.16003E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -7.31710E+00 MeV Emin = 7.36700E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -8.35920E+00 MeV Emin = 8.41620E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 5.36000E+00 MeV Emin = 4.50000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -1.16690E+01 MeV Emin = 1.17486E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.94127E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.16003E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 7.36700E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 8.41620E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.50000E-01 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 8.87549E-04 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 3.02136E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 11 Q = 1.92830E+00 MeV frac = 1.00000E+00 Product nuclide = 62148.82c : beta- + beta- + + Nuclide 208 / 1657 : 60150.82c -- neodymium 150 (Nd-150) + + Pointers : 1687278 28803 + Primary type : Transport + Nuclide ZAI : 601500 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Nd150.ACE + Atomic weight (AW) : 149.92090 + Atomic weight ratio (AWR) : 148.63300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.11E+26 seconds (6.7E+18 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 22 reaction channels + - 7 special reactions + - 11 transmutation reactions + - 8 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 22 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.95320E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 601490 : (n,2n) + 3 MT = 17 Q = -1.24230E+01 MeV Emin = 1.25066E+01 MeV frac = 1.00000E+00 Product nuclide = 60148.82c : (n,3n) + 4 MT = 22 Q = -3.67530E-01 MeV Emin = 3.52500E-01 MeV frac = 1.00000E+00 Product nuclide = 581460 : (n,nalpha) + 5 MT = 28 Q = -9.43660E+00 MeV Emin = 9.50009E+00 MeV frac = 1.00000E+00 Product nuclide = 591490 : (n,np) + 6 MT = 51 Q = -1.29130E-01 MeV Emin = 1.30000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -3.67530E-01 MeV Emin = 3.90002E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -5.46330E-01 MeV Emin = 6.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -6.95320E-01 MeV Emin = 8.45313E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -8.44320E-01 MeV Emin = 8.87500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -9.10000E-01 MeV Emin = 9.85938E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -9.93350E-01 MeV Emin = 1.03693E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -1.05990E+00 MeV Emin = 1.11078E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -1.29130E+00 MeV Emin = 1.30000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 91 Q = -1.35000E+00 MeV Emin = 1.48000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 16 MT = 102 Q = 5.33456E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 601510 : (n,gamma) + 17 MT = 103 Q = -7.94650E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 591500 : (n,p) + 18 MT = 104 Q = -1.14230E+01 MeV Emin = 1.15000E+01 MeV frac = 1.00000E+00 Product nuclide = 591490 : (n,d) + 19 MT = 105 Q = -1.29130E+01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 591480 : (n,t) + 20 MT = 106 Q = -9.82850E+00 MeV Emin = 9.89463E+00 MeV frac = 1.00000E+00 Product nuclide = 581480 : (n,He-3) + 21 MT = 107 Q = 4.21650E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 581470 : (n,alpha) + 22 MT = 111 Q = -1.27140E+01 MeV Emin = 1.27995E+01 MeV frac = 1.00000E+00 Product nuclide = 581490 : (n,2p) + + 8 additional transport branches: + + 1 MT = 22 Q = -3.67530E-01 MeV Emin = 3.52500E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -9.43660E+00 MeV Emin = 9.50009E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -7.94650E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -1.14230E+01 MeV Emin = 1.15000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -1.29130E+01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 106 Q = -9.82850E+00 MeV Emin = 9.89463E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 7 MT = 107 Q = 4.21650E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 8 MT = 111 Q = -1.27140E+01 MeV Emin = 1.27995E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 8.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.15000E+01 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.30000E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 9.89463E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 1.30000E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 11 Q = 3.37138E+00 MeV frac = 1.00000E+00 Product nuclide = 62150.82c : beta- + beta- + + Nuclide 209 / 1657 : 61147.82c -- promethium 147 (Pm-147) + + Pointers : 1719452 30183 + Primary type : Transport + Nuclide ZAI : 611470 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Pm147.ACE + Atomic weight (AW) : 146.91508 + Atomic weight ratio (AWR) : 145.65300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 8.27E+07 seconds (2.62 years) + Specific ingestion toxicity : 2.60E-10 Sv/Bq + Specific inhalation toxicity : 5.00E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 20 reaction channels + - 7 special reactions + - 12 transmutation reactions + - 10 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 20 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.67410E+00 MeV Emin = 7.72679E+00 MeV frac = 1.00000E+00 Product nuclide = 611460 : (n,2n) + 3 MT = 17 Q = -1.39222E+01 MeV Emin = 1.40178E+01 MeV frac = 1.00000E+00 Product nuclide = 611450 : (n,3n) + 4 MT = 22 Q = 1.60309E+00 MeV Emin = 1.02590E-01 MeV frac = 1.00000E+00 Product nuclide = 59143.82c : (n,nalpha) + 5 MT = 28 Q = -5.41064E+00 MeV Emin = 6.31389E+00 MeV frac = 1.00000E+00 Product nuclide = 60146.82c : (n,np) + 6 MT = 32 Q = -1.06696E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 60145.82c : (n,nd) + 7 MT = 33 Q = -1.02446E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 60144.82c : (n,nt) + 8 MT = 51 Q = -9.10999E-02 MeV Emin = 8.99999E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -4.10499E-01 MeV Emin = 4.09606E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -4.89299E-01 MeV Emin = 4.87947E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -5.30999E-01 MeV Emin = 5.25984E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -6.79999E-01 MeV Emin = 6.65916E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -6.85799E-01 MeV Emin = 6.87589E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 91 Q = -6.99999E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 15 MT = 102 Q = 5.89528E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 61148.82c : (n,gamma) + 16 MT = 103 Q = -1.13541E-01 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 60147.82c : (n,p) + 17 MT = 104 Q = -3.10053E+00 MeV Emin = 4.51526E+00 MeV frac = 1.00000E+00 Product nuclide = 60146.82c : (n,d) + 18 MT = 105 Q = -4.48446E+00 MeV Emin = 6.31389E+00 MeV frac = 1.00000E+00 Product nuclide = 60145.82c : (n,t) + 19 MT = 106 Q = -6.27083E+00 MeV Emin = 1.03149E+01 MeV frac = 1.00000E+00 Product nuclide = 591450 : (n,He-3) + 20 MT = 107 Q = 7.36420E+00 MeV Emin = 9.99218E-02 MeV frac = 1.00000E+00 Product nuclide = 591440 : (n,alpha) + + 10 additional transport branches: + + 1 MT = 22 Q = 1.60309E+00 MeV Emin = 1.02590E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -5.41064E+00 MeV Emin = 6.31389E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.06696E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.02446E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 102 Q = 5.89528E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 61548.82c : (n,gamma) + 6 MT = 103 Q = -1.13541E-01 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 7 MT = 104 Q = -3.10053E+00 MeV Emin = 4.51526E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 8 MT = 105 Q = -4.48446E+00 MeV Emin = 6.31389E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 9 MT = 106 Q = -6.27083E+00 MeV Emin = 1.03149E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 10 MT = 107 Q = 7.36420E+00 MeV Emin = 9.99218E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 4.51526E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 6.31389E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.03149E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 9.99218E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 8.50000E-04 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 8.99999E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.24100E-01 MeV frac = 1.00000E+00 Product nuclide = 62147.82c : beta- + + Nuclide 210 / 1657 : 61148.82c -- promethium 148 (Pm-148) + + Pointers : 1722725 30229 + Primary type : Transport + Nuclide ZAI : 611480 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Pm148.ACE + Atomic weight (AW) : 147.91668 + Atomic weight ratio (AWR) : 146.64600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 4.64E+05 seconds (5.37 days) + Specific ingestion toxicity : 2.70E-09 Sv/Bq + Specific inhalation toxicity : 2.20E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 16 reaction channels + - 7 special reactions + - 12 transmutation reactions + - 9 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 16 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.90610E+00 MeV Emin = 6.06070E+00 MeV frac = 1.00000E+00 Product nuclide = 61147.82c : (n,2n) + 3 MT = 17 Q = -1.35802E+01 MeV Emin = 1.36728E+01 MeV frac = 1.00000E+00 Product nuclide = 611460 : (n,3n) + 4 MT = 22 Q = 1.45810E+00 MeV Emin = 1.92188E+00 MeV frac = 1.00000E+00 Product nuclide = 591440 : (n,nalpha) + 5 MT = 28 Q = -6.01964E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 60147.82c : (n,np) + 6 MT = 32 Q = -9.00663E+00 MeV Emin = 1.04614E+01 MeV frac = 1.00000E+00 Product nuclide = 60146.82c : (n,nd) + 7 MT = 33 Q = -1.03906E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 60145.82c : (n,nt) + 8 MT = 51 Q = -7.56999E-02 MeV Emin = 7.50000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -1.37000E-01 MeV Emin = 1.28451E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 91 Q = -2.00000E-01 MeV Emin = 2.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 11 MT = 102 Q = 7.27067E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 61149.82c : (n,gamma) + 12 MT = 103 Q = 1.31946E+00 MeV Emin = 1.04297E+00 MeV frac = 1.00000E+00 Product nuclide = 60148.82c : (n,p) + 13 MT = 104 Q = -3.70952E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 60147.82c : (n,d) + 14 MT = 105 Q = -2.82148E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 60146.82c : (n,t) + 15 MT = 106 Q = -6.88583E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 591460 : (n,He-3) + 16 MT = 107 Q = 8.40919E+00 MeV Emin = 9.99218E-02 MeV frac = 1.00000E+00 Product nuclide = 591450 : (n,alpha) + + 9 additional transport branches: + + 1 MT = 22 Q = 1.45810E+00 MeV Emin = 1.92188E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -6.01964E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -9.00663E+00 MeV Emin = 1.04614E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.03906E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 103 Q = 1.31946E+00 MeV Emin = 1.04297E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 104 Q = -3.70952E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 7 MT = 105 Q = -2.82148E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 8 MT = 106 Q = -6.88583E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 9 MT = 107 Q = 8.40919E+00 MeV Emin = 9.99218E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.04297E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 4.00000E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.00000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 9.99218E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 8.50000E-04 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 7.50000E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.47100E+00 MeV frac = 1.00000E+00 Product nuclide = 62148.82c : beta- + + Nuclide 211 / 1657 : 61548.82c -- promethium 148m (Pm-148m) + + Pointers : 1726902 30275 + Primary type : Transport + Nuclide ZAI : 611481 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Pm148M.ACE + Atomic weight (AW) : 147.92072 + Atomic weight ratio (AWR) : 146.65000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 3.57E+06 seconds (41.3 days) + Specific ingestion toxicity : 1.70E-09 Sv/Bq + Specific inhalation toxicity : 5.70E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 13 reaction channels + - 6 special reactions + - 9 transmutation reactions + - 6 transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 13 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.75550E+00 MeV Emin = 5.79475E+00 MeV frac = 1.00000E+00 Product nuclide = 61147.82c : (n,2n) + 3 MT = 17 Q = -1.34210E+01 MeV Emin = 1.35125E+01 MeV frac = 1.00000E+00 Product nuclide = 611460 : (n,3n) + 4 MT = 22 Q = 1.59920E+00 MeV Emin = 2.33125E-08 MeV frac = 1.00000E+00 Product nuclide = 591440 : (n,nalpha) + 5 MT = 28 Q = -5.86920E+00 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 60147.82c : (n,np) + 6 MT = 51 Q = 1.37900E-01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = 6.22000E-02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 91 Q = 0.00000E+00 MeV Emin = 1.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 9 MT = 102 Q = 7.34637E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 61149.82c : (n,gamma) + 10 MT = 103 Q = 1.46420E+00 MeV Emin = 2.06625E-08 MeV frac = 1.00000E+00 Product nuclide = 60148.82c : (n,p) + 11 MT = 104 Q = -3.64470E+00 MeV Emin = 1.15000E+01 MeV frac = 1.00000E+00 Product nuclide = 60147.82c : (n,d) + 12 MT = 105 Q = -2.67920E+00 MeV Emin = 1.15000E+01 MeV frac = 1.00000E+00 Product nuclide = 60146.82c : (n,t) + 13 MT = 107 Q = 8.54600E+00 MeV Emin = 2.13250E-08 MeV frac = 1.00000E+00 Product nuclide = 591450 : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = 1.59920E+00 MeV Emin = 2.33125E-08 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -5.86920E+00 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = 1.46420E+00 MeV Emin = 2.06625E-08 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -3.64470E+00 MeV Emin = 1.15000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -2.67920E+00 MeV Emin = 1.15000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 107 Q = 8.54600E+00 MeV Emin = 2.13250E-08 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.06625E-08 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.15000E+01 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.15000E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 2.13250E-08 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 3 Q = 1.37100E-01 MeV frac = 5.60000E-02 Product nuclide = 61148.82c : IT + 2 RTYP = 1 Q = 2.60800E+00 MeV frac = 9.44000E-01 Product nuclide = 62148.82c : beta- + + Nuclide 212 / 1657 : 61149.82c -- promethium 149 (Pm-149) + + Pointers : 1730851 30321 + Primary type : Transport + Nuclide ZAI : 611490 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Pm149.ACE + Atomic weight (AW) : 148.91829 + Atomic weight ratio (AWR) : 147.63900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.91E+05 seconds (2.21 days) + Specific ingestion toxicity : 9.90E-10 Sv/Bq + Specific inhalation toxicity : 7.30E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 27 reaction channels + - 6 special reactions + - 11 transmutation reactions + - 8 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 27 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.26910E+00 MeV Emin = 7.31835E+00 MeV frac = 1.00000E+00 Product nuclide = 61148.82c : (n,2n) + 3 MT = 17 Q = -1.31752E+01 MeV Emin = 1.32645E+01 MeV frac = 1.00000E+00 Product nuclide = 61147.82c : (n,3n) + 4 MT = 22 Q = 1.14009E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 591450 : (n,nalpha) + 5 MT = 28 Q = -5.94964E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 60148.82c : (n,np) + 6 MT = 32 Q = -1.09786E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 60147.82c : (n,nd) + 7 MT = 33 Q = -1.00906E+01 MeV Emin = 1.10530E+01 MeV frac = 1.00000E+00 Product nuclide = 60146.82c : (n,nt) + 8 MT = 51 Q = -1.14300E-01 MeV Emin = 1.07537E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -1.88600E-01 MeV Emin = 1.69938E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -2.11300E-01 MeV Emin = 2.06366E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -2.40200E-01 MeV Emin = 2.38304E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -2.70200E-01 MeV Emin = 2.66522E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -2.88200E-01 MeV Emin = 2.85905E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -3.60000E-01 MeV Emin = 3.46828E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -3.87599E-01 MeV Emin = 3.83278E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -3.96799E-01 MeV Emin = 3.99059E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -4.25299E-01 MeV Emin = 4.21008E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -4.62199E-01 MeV Emin = 4.57205E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 62 Q = -5.15599E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 20 MT = 63 Q = -5.37899E-01 MeV Emin = 5.37334E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 21 MT = 64 Q = -6.54799E-01 MeV Emin = 6.58393E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 22 MT = 91 Q = -6.99999E-01 MeV Emin = 7.03859E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 23 MT = 102 Q = 5.60342E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 611500 : (n,gamma) + 24 MT = 103 Q = -9.06544E-01 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 601490 : (n,p) + 25 MT = 104 Q = -3.63952E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 60148.82c : (n,d) + 26 MT = 105 Q = -4.79347E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 60147.82c : (n,t) + 27 MT = 107 Q = 6.43119E+00 MeV Emin = 8.99999E-02 MeV frac = 1.00000E+00 Product nuclide = 591460 : (n,alpha) + + 8 additional transport branches: + + 1 MT = 22 Q = 1.14009E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -5.94964E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.09786E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.00906E+01 MeV Emin = 1.10530E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 103 Q = -9.06544E-01 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 104 Q = -3.63952E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 7 MT = 105 Q = -4.79347E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 8 MT = 107 Q = 6.43119E+00 MeV Emin = 8.99999E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 7.00000E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 8.99999E-02 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 8.50000E-04 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 1.07537E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.07100E+00 MeV frac = 1.00000E+00 Product nuclide = 62149.82c : beta- + + Nuclide 213 / 1657 : 61151.82c -- promethium 151 (Pm-151) + + Pointers : 1739444 30367 + Primary type : Transport + Nuclide ZAI : 611510 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Pm151.ACE + Atomic weight (AW) : 150.92150 + Atomic weight ratio (AWR) : 149.62500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.02E+05 seconds (1.18 days) + Specific ingestion toxicity : 7.30E-10 Sv/Bq + Specific inhalation toxicity : 4.60E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 22 reaction channels + - 20 special reactions + - 9 transmutation reactions + - 6 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 22 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.86300E+00 MeV Emin = 7.91555E+00 MeV frac = 1.00000E+00 Product nuclide = 611500 : (n,2n) + 3 MT = 17 Q = -1.34650E+01 MeV Emin = 1.35550E+01 MeV frac = 1.00000E+00 Product nuclide = 61149.82c : (n,3n) + 4 MT = 22 Q = -3.53000E-01 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 591470 : (n,nalpha) + 5 MT = 24 Q = -7.12900E+00 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 591460 : (n,2nalpha) + 6 MT = 28 Q = -6.99400E+00 MeV Emin = 7.04075E+00 MeV frac = 1.00000E+00 Product nuclide = 60150.82c : (n,np) + 7 MT = 41 Q = -1.43740E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 601490 : (n,2np) + 8 MT = 51 Q = -8.51200E-02 MeV Emin = 8.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -1.16790E-01 MeV Emin = 1.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -1.75080E-01 MeV Emin = 1.46910E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -1.97270E-01 MeV Emin = 1.87419E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -2.55690E-01 MeV Emin = 2.56162E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -2.61160E-01 MeV Emin = 2.60000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -3.24680E-01 MeV Emin = 3.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -3.29600E-01 MeV Emin = 3.29327E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -3.43800E-01 MeV Emin = 3.38950E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -4.26450E-01 MeV Emin = 3.87699E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -4.27150E-01 MeV Emin = 4.29653E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 91 Q = -4.27150E-01 MeV Emin = 4.29653E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 20 MT = 102 Q = 5.93837E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 611520 : (n,gamma) + 21 MT = 103 Q = 0.00000E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 601510 : (n,p) + 22 MT = 107 Q = 0.00000E+00 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 591480 : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = -3.53000E-01 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 24 Q = -7.12900E+00 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,2nalpha) + 3 MT = 28 Q = -6.99400E+00 MeV Emin = 7.04075E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 4 MT = 41 Q = -1.43740E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,2np) + 5 MT = 103 Q = 0.00000E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 107 Q = 0.00000E+00 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 20 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.00000E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 1.50000E+00 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 8.50000E-04 MeV : damage-energy production + 4 MT = 600 Q = -1.66000E+00 MeV Emin = 3.00000E+00 MeV : (n,p) to ground state + 5 MT = 601 Q = -1.68245E+00 MeV Emin = 3.00000E+00 MeV : (n,p1) + 6 MT = 602 Q = -1.71767E+00 MeV Emin = 3.00000E+00 MeV : (n,p2) + 7 MT = 603 Q = -1.73586E+00 MeV Emin = 3.00000E+00 MeV : (n,p3) + 8 MT = 604 Q = -1.75590E+00 MeV Emin = 3.00000E+00 MeV : (n,p4) + 9 MT = 649 Q = -1.75590E+00 MeV Emin = 3.00000E+00 MeV : (n,p) to continuum + 10 MT = 800 Q = 4.73300E+00 MeV Emin = 1.50000E+00 MeV : (n,alpha) to ground state + 11 MT = 801 Q = 4.64300E+00 MeV Emin = 1.60000E+00 MeV : (n,a1) + 12 MT = 802 Q = 4.63483E+00 MeV Emin = 1.60000E+00 MeV : (n,a2) + 13 MT = 803 Q = 4.63401E+00 MeV Emin = 1.60000E+00 MeV : (n,a3) + 14 MT = 804 Q = 4.62780E+00 MeV Emin = 1.60000E+00 MeV : (n,a4) + 15 MT = 805 Q = 4.61183E+00 MeV Emin = 1.60000E+00 MeV : (n,a5) + 16 MT = 806 Q = 4.53700E+00 MeV Emin = 1.70000E+00 MeV : (n,a6) + 17 MT = 807 Q = 4.45920E+00 MeV Emin = 1.70000E+00 MeV : (n,a7) + 18 MT = 808 Q = 4.44570E+00 MeV Emin = 1.80000E+00 MeV : (n,a8) + 19 MT = 849 Q = 4.44570E+00 MeV Emin = 1.80000E+00 MeV : (n,alpha) to continuum + 20 MT = 4 Q = 0.00000E+00 MeV Emin = 8.00000E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.18700E+00 MeV frac = 1.00000E+00 Product nuclide = 62151.82c : beta- + + Nuclide 214 / 1657 : 62147.82c -- samarium 147 (Sm-147) + + Pointers : 1771072 32989 + Primary type : Transport + Nuclide ZAI : 621470 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Sm147.ACE + Atomic weight (AW) : 146.91508 + Atomic weight ratio (AWR) : 145.65300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 3.38E+18 seconds (107 billion years) + Specific ingestion toxicity : 4.90E-08 Sv/Bq + Specific inhalation toxicity : 9.60E-06 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 24 reaction channels + - 7 special reactions + - 8 transmutation reactions + - 6 transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 24 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.32950E+00 MeV Emin = 6.37300E+00 MeV frac = 1.00000E+00 Product nuclide = 621460 : (n,2n) + 3 MT = 51 Q = -1.23000E-01 MeV Emin = 1.23000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 4 MT = 52 Q = -1.97300E-01 MeV Emin = 1.97300E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 5 MT = 53 Q = -7.15500E-01 MeV Emin = 7.15500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 6 MT = 54 Q = -7.98800E-01 MeV Emin = 8.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 7 MT = 55 Q = -8.08000E-01 MeV Emin = 8.10774E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 8 MT = 56 Q = -9.00000E-01 MeV Emin = 9.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 9 MT = 57 Q = -9.25000E-01 MeV Emin = 9.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 10 MT = 58 Q = -1.00700E+00 MeV Emin = 1.00696E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 11 MT = 59 Q = -1.02900E+00 MeV Emin = 1.02900E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 12 MT = 60 Q = -1.05400E+00 MeV Emin = 1.05400E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 13 MT = 61 Q = -1.06500E+00 MeV Emin = 1.06865E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 14 MT = 62 Q = -1.07700E+00 MeV Emin = 1.08069E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 15 MT = 63 Q = -1.10300E+00 MeV Emin = 1.10300E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 16 MT = 64 Q = -1.16600E+00 MeV Emin = 1.16600E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 17 MT = 91 Q = -1.17200E+00 MeV Emin = 1.17850E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 18 MT = 102 Q = 8.14142E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 62148.82c : (n,gamma) + 19 MT = 103 Q = 5.57400E-01 MeV Emin = 4.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 61147.82c : (n,p) + 20 MT = 104 Q = -4.79300E+00 MeV Emin = 4.82592E+00 MeV frac = 1.00000E+00 Product nuclide = 611460 : (n,d) + 21 MT = 105 Q = -4.20050E+00 MeV Emin = 4.22936E+00 MeV frac = 1.00000E+00 Product nuclide = 611450 : (n,t) + 22 MT = 106 Q = -4.21260E+00 MeV Emin = 4.24152E+00 MeV frac = 1.00000E+00 Product nuclide = 60145.82c : (n,He-3) + 23 MT = 107 Q = 1.01300E+01 MeV Emin = 4.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 60144.82c : (n,alpha) + 24 MT = 111 Q = -4.84670E+00 MeV Emin = 4.87998E+00 MeV frac = 1.00000E+00 Product nuclide = 60146.82c : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = 5.57400E-01 MeV Emin = 4.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -4.79300E+00 MeV Emin = 4.82592E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -4.20050E+00 MeV Emin = 4.22936E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -4.21260E+00 MeV Emin = 4.24152E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 1.01300E+01 MeV Emin = 4.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -4.84670E+00 MeV Emin = 4.87998E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.00000E-01 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 4.82592E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 4.22936E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 4.24152E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.00000E-01 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 9.00000E-04 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 1.23000E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 4 Q = 2.31100E+00 MeV frac = 1.00000E+00 Product nuclide = 601430 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 2.31100E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 215 / 1657 : 62148.82c -- samarium 148 (Sm-148) + + Pointers : 1774063 33035 + Primary type : Transport + Nuclide ZAI : 621480 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Sm148.ACE + Atomic weight (AW) : 147.91467 + Atomic weight ratio (AWR) : 146.64400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.21E+23 seconds (7E+15 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 24 reaction channels + - 67 special reactions + - 9 transmutation reactions + - 6 transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 24 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.14200E+00 MeV Emin = 8.19752E+00 MeV frac = 1.00000E+00 Product nuclide = 62147.82c : (n,2n) + 3 MT = 17 Q = -1.44830E+01 MeV Emin = 1.45818E+01 MeV frac = 1.00000E+00 Product nuclide = 621460 : (n,3n) + 4 MT = 22 Q = 1.98500E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 60144.82c : (n,nalpha) + 5 MT = 24 Q = -5.83100E+00 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 601430 : (n,2nalpha) + 6 MT = 28 Q = -7.58400E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 61147.82c : (n,np) + 7 MT = 41 Q = -1.52430E+01 MeV Emin = 1.70000E+01 MeV frac = 1.00000E+00 Product nuclide = 611460 : (n,2np) + 8 MT = 51 Q = -5.50270E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -1.16154E+00 MeV Emin = 1.10000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -1.18026E+00 MeV Emin = 1.17889E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -1.42445E+00 MeV Emin = 1.40000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -1.43420E+00 MeV Emin = 1.43907E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -1.45412E+00 MeV Emin = 1.45401E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -1.46512E+00 MeV Emin = 1.46958E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -1.59429E+00 MeV Emin = 1.60000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -1.64860E+00 MeV Emin = 1.63250E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -1.65930E+00 MeV Emin = 1.66523E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -1.66424E+00 MeV Emin = 1.67410E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 62 Q = -1.71800E+00 MeV Emin = 1.71486E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 20 MT = 63 Q = -1.73349E+00 MeV Emin = 1.73751E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 21 MT = 91 Q = -3.93318E-01 MeV Emin = 3.77000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 22 MT = 102 Q = 5.87108E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 62149.82c : (n,gamma) + 23 MT = 103 Q = 0.00000E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 61148.82c : (n,p) + 24 MT = 107 Q = 0.00000E+00 MeV Emin = 1.80000E-02 MeV frac = 1.00000E+00 Product nuclide = 60145.82c : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = 1.98500E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 24 Q = -5.83100E+00 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,2nalpha) + 3 MT = 28 Q = -7.58400E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 4 MT = 41 Q = -1.52430E+01 MeV Emin = 1.70000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,2np) + 5 MT = 103 Q = 0.00000E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 107 Q = 0.00000E+00 MeV Emin = 1.80000E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 67 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.00000E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 1.80000E-02 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 8.85907E-04 MeV : damage-energy production + 4 MT = 600 Q = -1.68700E+00 MeV Emin = 3.00000E+00 MeV : (n,p) to ground state + 5 MT = 601 Q = -1.76270E+00 MeV Emin = 3.00000E+00 MeV : (n,p1) + 6 MT = 602 Q = -1.82420E+00 MeV Emin = 3.00000E+00 MeV : (n,p2) + 7 MT = 603 Q = -1.82490E+00 MeV Emin = 3.00000E+00 MeV : (n,p3) + 8 MT = 604 Q = -1.90240E+00 MeV Emin = 3.00000E+00 MeV : (n,p4) + 9 MT = 605 Q = -1.90690E+00 MeV Emin = 3.00000E+00 MeV : (n,p5) + 10 MT = 606 Q = -1.97900E+00 MeV Emin = 3.00000E+00 MeV : (n,p6) + 11 MT = 607 Q = -1.98930E+00 MeV Emin = 3.00000E+00 MeV : (n,p7) + 12 MT = 608 Q = -1.99170E+00 MeV Emin = 3.00000E+00 MeV : (n,p8) + 13 MT = 609 Q = -1.99590E+00 MeV Emin = 3.00000E+00 MeV : (n,p9) + 14 MT = 610 Q = -2.05040E+00 MeV Emin = 3.00000E+00 MeV : (n,p10) + 15 MT = 611 Q = -2.06670E+00 MeV Emin = 3.00000E+00 MeV : (n,p11) + 16 MT = 612 Q = -2.07250E+00 MeV Emin = 3.00000E+00 MeV : (n,p12) + 17 MT = 613 Q = -2.07510E+00 MeV Emin = 3.00000E+00 MeV : (n,p13) + 18 MT = 614 Q = -2.09660E+00 MeV Emin = 3.00000E+00 MeV : (n,p14) + 19 MT = 615 Q = -2.10060E+00 MeV Emin = 3.00000E+00 MeV : (n,p15) + 20 MT = 616 Q = -2.12710E+00 MeV Emin = 3.00000E+00 MeV : (n,p16) + 21 MT = 617 Q = -2.13900E+00 MeV Emin = 3.00000E+00 MeV : (n,p17) + 22 MT = 618 Q = -2.14900E+00 MeV Emin = 3.00000E+00 MeV : (n,p18) + 23 MT = 619 Q = -2.21350E+00 MeV Emin = 3.00000E+00 MeV : (n,p19) + 24 MT = 620 Q = -2.21650E+00 MeV Emin = 3.00000E+00 MeV : (n,p20) + 25 MT = 621 Q = -2.23040E+00 MeV Emin = 3.00000E+00 MeV : (n,p21) + 26 MT = 622 Q = -2.23270E+00 MeV Emin = 3.00000E+00 MeV : (n,p22) + 27 MT = 623 Q = -2.23730E+00 MeV Emin = 3.00000E+00 MeV : (n,p23) + 28 MT = 624 Q = -2.24820E+00 MeV Emin = 3.00000E+00 MeV : (n,p24) + 29 MT = 625 Q = -2.25120E+00 MeV Emin = 3.00000E+00 MeV : (n,p25) + 30 MT = 626 Q = -2.26010E+00 MeV Emin = 3.00000E+00 MeV : (n,p26) + 31 MT = 627 Q = -2.29820E+00 MeV Emin = 3.00000E+00 MeV : (n,p27) + 32 MT = 628 Q = -2.30970E+00 MeV Emin = 3.00000E+00 MeV : (n,p28) + 33 MT = 629 Q = -2.32890E+00 MeV Emin = 4.00000E+00 MeV : (n,p29) + 34 MT = 630 Q = -2.34220E+00 MeV Emin = 3.00000E+00 MeV : (n,p30) + 35 MT = 631 Q = -2.34730E+00 MeV Emin = 3.00000E+00 MeV : (n,p31) + 36 MT = 632 Q = -2.35650E+00 MeV Emin = 3.00000E+00 MeV : (n,p32) + 37 MT = 633 Q = -2.35990E+00 MeV Emin = 3.00000E+00 MeV : (n,p33) + 38 MT = 634 Q = -2.38700E+00 MeV Emin = 3.00000E+00 MeV : (n,p34) + 39 MT = 649 Q = -2.38700E+00 MeV Emin = 4.00000E+00 MeV : (n,p) to continuum + 40 MT = 800 Q = 7.74100E+00 MeV Emin = 1.80000E-02 MeV : (n,alpha) to ground state + 41 MT = 801 Q = 7.67378E+00 MeV Emin = 1.80000E-02 MeV : (n,a1) + 42 MT = 802 Q = 7.66850E+00 MeV Emin = 1.80000E-02 MeV : (n,a2) + 43 MT = 803 Q = 7.08333E+00 MeV Emin = 2.10000E-02 MeV : (n,a3) + 44 MT = 804 Q = 6.99272E+00 MeV Emin = 1.90000E-02 MeV : (n,a4) + 45 MT = 805 Q = 6.96055E+00 MeV Emin = 1.80000E-02 MeV : (n,a5) + 46 MT = 806 Q = 6.82117E+00 MeV Emin = 1.80000E-02 MeV : (n,a6) + 47 MT = 807 Q = 6.82028E+00 MeV Emin = 2.20000E-02 MeV : (n,a7) + 48 MT = 808 Q = 6.80395E+00 MeV Emin = 1.80000E-02 MeV : (n,a8) + 49 MT = 809 Q = 6.72978E+00 MeV Emin = 1.17000E-01 MeV : (n,a9) + 50 MT = 810 Q = 6.68959E+00 MeV Emin = 1.80000E-02 MeV : (n,a10) + 51 MT = 811 Q = 6.65575E+00 MeV Emin = 1.80000E-02 MeV : (n,a11) + 52 MT = 812 Q = 6.62980E+00 MeV Emin = 1.17000E-01 MeV : (n,a12) + 53 MT = 813 Q = 6.59074E+00 MeV Emin = 1.80000E-02 MeV : (n,a13) + 54 MT = 814 Q = 6.57995E+00 MeV Emin = 1.80000E-02 MeV : (n,a14) + 55 MT = 815 Q = 6.57868E+00 MeV Emin = 2.60000E-02 MeV : (n,a15) + 56 MT = 816 Q = 6.52730E+00 MeV Emin = 1.80000E-02 MeV : (n,a16) + 57 MT = 817 Q = 6.49127E+00 MeV Emin = 1.80000E-02 MeV : (n,a17) + 58 MT = 818 Q = 6.45540E+00 MeV Emin = 1.80000E-02 MeV : (n,a18) + 59 MT = 819 Q = 6.42420E+00 MeV Emin = 1.80000E-02 MeV : (n,a19) + 60 MT = 820 Q = 6.41470E+00 MeV Emin = 1.80000E-02 MeV : (n,a20) + 61 MT = 821 Q = 6.40240E+00 MeV Emin = 1.90000E-02 MeV : (n,a21) + 62 MT = 822 Q = 6.34010E+00 MeV Emin = 1.80000E-02 MeV : (n,a22) + 63 MT = 823 Q = 6.33970E+00 MeV Emin = 3.27000E-01 MeV : (n,a23) + 64 MT = 824 Q = 6.33708E+00 MeV Emin = 1.90000E-02 MeV : (n,a24) + 65 MT = 825 Q = 6.31340E+00 MeV Emin = 3.27000E-01 MeV : (n,a25) + 66 MT = 849 Q = 6.31340E+00 MeV Emin = 1.80000E-02 MeV : (n,alpha) to continuum + 67 MT = 4 Q = 0.00000E+00 MeV Emin = 3.77000E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 4 Q = 1.98600E+00 MeV frac = 1.00000E+00 Product nuclide = 60144.82c : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 1.98600E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 216 / 1657 : 62149.82c -- samarium 149 (Sm-149) + + Pointers : 1781434 33081 + Primary type : Transport + Nuclide ZAI : 621490 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Sm149.ACE + Atomic weight (AW) : 148.91728 + Atomic weight ratio (AWR) : 147.63800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 6.31E+22 seconds (2E+15 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 17 reaction channels + - 4 special reactions + - 5 transmutation reactions + - 2 transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 17 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.86000E+00 MeV Emin = 5.90000E+00 MeV frac = 1.00000E+00 Product nuclide = 62148.82c : (n,2n) + 3 MT = 17 Q = -1.40700E+01 MeV Emin = 1.41653E+01 MeV frac = 1.00000E+00 Product nuclide = 62147.82c : (n,3n) + 4 MT = 51 Q = -2.20000E-02 MeV Emin = 2.20000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 5 MT = 52 Q = -2.77000E-01 MeV Emin = 2.68994E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 6 MT = 53 Q = -2.86000E-01 MeV Emin = 2.83388E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 7 MT = 54 Q = -3.50000E-01 MeV Emin = 3.26150E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 8 MT = 55 Q = -3.98000E-01 MeV Emin = 4.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 9 MT = 56 Q = -5.29000E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 10 MT = 57 Q = -5.58000E-01 MeV Emin = 5.47142E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 11 MT = 58 Q = -5.82000E-01 MeV Emin = 5.73840E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 12 MT = 59 Q = -6.50000E-01 MeV Emin = 6.27150E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 13 MT = 60 Q = -8.53000E-01 MeV Emin = 8.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 14 MT = 91 Q = -1.98654E+00 MeV Emin = 1.90000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 15 MT = 102 Q = 7.98674E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 62150.82c : (n,gamma) + 16 MT = 103 Q = -2.77000E-01 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 61149.82c : (n,p) + 17 MT = 107 Q = 9.60000E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 60146.82c : (n,alpha) + + 2 additional transport branches: + + 1 MT = 103 Q = -2.77000E-01 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 107 Q = 9.60000E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 4 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.00000E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 4.00000E+00 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 8.50000E-04 MeV : damage-energy production + 4 MT = 4 Q = 0.00000E+00 MeV Emin = 2.20000E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 4 Q = 1.86970E+00 MeV frac = 1.00000E+00 Product nuclide = 60145.82c : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 1.86970E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 217 / 1657 : 62150.82c -- samarium 150 (Sm-150) + + Pointers : 1783403 33127 + Primary type : Transport + Nuclide ZAI : 621500 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Sm150.ACE + Atomic weight (AW) : 149.91687 + Atomic weight ratio (AWR) : 148.62900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 25 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 25 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -3.34000E-01 MeV Emin = 3.36018E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -7.37000E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -7.40000E-01 MeV Emin = 7.43470E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -7.73000E-01 MeV Emin = 7.61590E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -1.05000E+00 MeV Emin = 1.04195E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -1.07000E+00 MeV Emin = 1.07341E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 57 Q = -1.16000E+00 MeV Emin = 1.12585E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 9 MT = 58 Q = -1.19000E+00 MeV Emin = 1.18290E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 10 MT = 59 Q = -1.26000E+00 MeV Emin = 1.24330E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 11 MT = 60 Q = -1.28000E+00 MeV Emin = 1.24330E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 12 MT = 61 Q = -1.36000E+00 MeV Emin = 1.36788E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 13 MT = 62 Q = -1.42000E+00 MeV Emin = 1.42073E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 14 MT = 63 Q = -1.45000E+00 MeV Emin = 1.44715E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 15 MT = 64 Q = -1.50000E+00 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 16 MT = 65 Q = -1.64000E+00 MeV Emin = 1.60000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 17 MT = 66 Q = -1.67000E+00 MeV Emin = 1.68000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 18 MT = 91 Q = -1.67000E+00 MeV Emin = 1.68000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 19 MT = 102 Q = 5.59646E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 62151.82c : (n,gamma) + 20 MT = 103 Q = -2.71540E+00 MeV Emin = 2.73367E+00 MeV frac = 1.00000E+00 Product nuclide = 611500 : (n,p) + 21 MT = 104 Q = -6.04810E+00 MeV Emin = 6.08879E+00 MeV frac = 1.00000E+00 Product nuclide = 61149.82c : (n,d) + 22 MT = 105 Q = -7.05460E+00 MeV Emin = 7.10206E+00 MeV frac = 1.00000E+00 Product nuclide = 61148.82c : (n,t) + 23 MT = 106 Q = -6.49960E+00 MeV Emin = 6.54333E+00 MeV frac = 1.00000E+00 Product nuclide = 60148.82c : (n,He-3) + 24 MT = 107 Q = 6.73920E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 60147.82c : (n,alpha) + 25 MT = 111 Q = -9.17820E+00 MeV Emin = 9.23995E+00 MeV frac = 1.00000E+00 Product nuclide = 601490 : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = -2.71540E+00 MeV Emin = 2.73367E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -6.04810E+00 MeV Emin = 6.08879E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -7.05460E+00 MeV Emin = 7.10206E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -6.49960E+00 MeV Emin = 6.54333E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 6.73920E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -9.17820E+00 MeV Emin = 9.23995E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.73367E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.08879E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 7.10206E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 6.54333E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 3.36018E-01 MeV : total inelastic scattering + + Nuclide 218 / 1657 : 62151.82c -- samarium 151 (Sm-151) + + Pointers : 1786288 33173 + Primary type : Transport + Nuclide ZAI : 621510 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Sm151.ACE + Atomic weight (AW) : 150.91645 + Atomic weight ratio (AWR) : 149.62000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.99E+09 seconds (94.8 years) + Specific ingestion toxicity : 9.80E-11 Sv/Bq + Specific inhalation toxicity : 4.00E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 50 reaction channels + - 7 special reactions + - 8 transmutation reactions + - 6 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 50 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.60960E+00 MeV Emin = 5.64800E+00 MeV frac = 1.00000E+00 Product nuclide = 62150.82c : (n,2n) + 3 MT = 51 Q = -4.80000E-03 MeV Emin = 4.62408E-03 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 4 MT = 52 Q = -6.58000E-02 MeV Emin = 6.61250E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 5 MT = 53 Q = -6.97000E-02 MeV Emin = 7.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 6 MT = 54 Q = -9.16000E-02 MeV Emin = 9.14877E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 7 MT = 55 Q = -1.04800E-01 MeV Emin = 1.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 8 MT = 56 Q = -1.47900E-01 MeV Emin = 1.45943E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 9 MT = 57 Q = -1.67800E-01 MeV Emin = 1.59500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 10 MT = 58 Q = -1.68400E-01 MeV Emin = 1.69250E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 11 MT = 59 Q = -1.75400E-01 MeV Emin = 1.73285E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 12 MT = 60 Q = -2.09000E-01 MeV Emin = 2.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 13 MT = 61 Q = -2.20000E-01 MeV Emin = 2.16103E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 14 MT = 62 Q = -2.30000E-01 MeV Emin = 2.26770E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 15 MT = 63 Q = -2.45600E-01 MeV Emin = 2.39620E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 16 MT = 64 Q = -2.61100E-01 MeV Emin = 2.56500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 17 MT = 65 Q = -2.70000E-01 MeV Emin = 2.67500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 18 MT = 66 Q = -2.80000E-01 MeV Emin = 2.80000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 19 MT = 67 Q = -2.85000E-01 MeV Emin = 2.84500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 20 MT = 68 Q = -2.94800E-01 MeV Emin = 2.92000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 21 MT = 69 Q = -3.02500E-01 MeV Emin = 3.02260E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 22 MT = 70 Q = -3.06800E-01 MeV Emin = 3.07000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 23 MT = 71 Q = -3.13400E-01 MeV Emin = 3.12245E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 24 MT = 72 Q = -3.15300E-01 MeV Emin = 3.16452E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 25 MT = 73 Q = -3.24000E-01 MeV Emin = 3.22085E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 26 MT = 74 Q = -3.30000E-01 MeV Emin = 3.31497E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 27 MT = 75 Q = -3.34000E-01 MeV Emin = 3.34615E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 28 MT = 76 Q = -3.36000E-01 MeV Emin = 3.37000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 29 MT = 77 Q = -3.40000E-01 MeV Emin = 3.40635E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 27. excited state + 30 MT = 78 Q = -3.44900E-01 MeV Emin = 3.45105E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 28. excited state + 31 MT = 79 Q = -3.50000E-01 MeV Emin = 3.51500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 29. excited state + 32 MT = 80 Q = -3.55000E-01 MeV Emin = 3.55185E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 30. excited state + 33 MT = 81 Q = -3.57600E-01 MeV Emin = 3.59000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 31. excited state + 34 MT = 82 Q = -3.60000E-01 MeV Emin = 3.61205E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 32. excited state + 35 MT = 83 Q = -3.65000E-01 MeV Emin = 3.64925E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 33. excited state + 36 MT = 84 Q = -3.70000E-01 MeV Emin = 3.70235E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 34. excited state + 37 MT = 85 Q = -3.75000E-01 MeV Emin = 3.76255E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 35. excited state + 38 MT = 86 Q = -3.80000E-01 MeV Emin = 3.80492E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 36. excited state + 39 MT = 87 Q = -3.85000E-01 MeV Emin = 3.85285E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 37. excited state + 40 MT = 88 Q = -3.86000E-01 MeV Emin = 3.88000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 38. excited state + 41 MT = 89 Q = -3.90000E-01 MeV Emin = 3.90000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 39. excited state + 42 MT = 90 Q = -3.92000E-01 MeV Emin = 3.94000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 40. excited state + 43 MT = 91 Q = -3.93000E-01 MeV Emin = 3.95315E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 44 MT = 102 Q = 8.25761E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 62152.82c : (n,gamma) + 45 MT = 103 Q = -4.05190E-01 MeV Emin = 4.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 61151.82c : (n,p) + 46 MT = 104 Q = -6.08610E+00 MeV Emin = 6.12678E+00 MeV frac = 1.00000E+00 Product nuclide = 611500 : (n,d) + 47 MT = 105 Q = -5.38720E+00 MeV Emin = 5.42321E+00 MeV frac = 1.00000E+00 Product nuclide = 61149.82c : (n,t) + 48 MT = 106 Q = -7.05750E+00 MeV Emin = 7.10467E+00 MeV frac = 1.00000E+00 Product nuclide = 601490 : (n,He-3) + 49 MT = 107 Q = 8.47660E+00 MeV Emin = 4.50000E-02 MeV frac = 1.00000E+00 Product nuclide = 60148.82c : (n,alpha) + 50 MT = 111 Q = -7.39590E+00 MeV Emin = 7.44533E+00 MeV frac = 1.00000E+00 Product nuclide = 60150.82c : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = -4.05190E-01 MeV Emin = 4.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -6.08610E+00 MeV Emin = 6.12678E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -5.38720E+00 MeV Emin = 5.42321E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -7.05750E+00 MeV Emin = 7.10467E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 8.47660E+00 MeV Emin = 4.50000E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -7.39590E+00 MeV Emin = 7.44533E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.00000E-01 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.12678E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 5.42321E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 7.10467E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.50000E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 8.50000E-04 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 4.62408E-03 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.64000E-02 MeV frac = 1.00000E+00 Product nuclide = 63151.82c : beta- + + Nuclide 219 / 1657 : 62152.82c -- samarium 152 (Sm-152) + + Pointers : 1791216 33219 + Primary type : Transport + Nuclide ZAI : 621520 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Sm152.ACE + Atomic weight (AW) : 151.92007 + Atomic weight ratio (AWR) : 150.61500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 23 reaction channels + - 7 special reactions + - 8 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 23 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.20350E+00 MeV Emin = 8.25800E+00 MeV frac = 1.00000E+00 Product nuclide = 62151.82c : (n,2n) + 3 MT = 51 Q = -1.21800E-01 MeV Emin = 1.22500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 4 MT = 52 Q = -3.66400E-01 MeV Emin = 3.65625E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 5 MT = 53 Q = -6.84800E-01 MeV Emin = 6.84800E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 6 MT = 54 Q = -7.06900E-01 MeV Emin = 7.06900E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 7 MT = 55 Q = -8.10400E-01 MeV Emin = 8.10400E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 8 MT = 56 Q = -9.63400E-01 MeV Emin = 9.63400E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 9 MT = 57 Q = -1.02300E+00 MeV Emin = 1.02300E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 10 MT = 58 Q = -1.04100E+00 MeV Emin = 1.04110E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 11 MT = 59 Q = -1.08300E+00 MeV Emin = 1.08280E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 12 MT = 60 Q = -1.12600E+00 MeV Emin = 1.12560E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 13 MT = 61 Q = -1.22200E+00 MeV Emin = 1.22200E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 14 MT = 62 Q = -1.23400E+00 MeV Emin = 1.23799E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 15 MT = 63 Q = -1.29300E+00 MeV Emin = 1.29280E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 16 MT = 91 Q = -1.30240E+00 MeV Emin = 1.30629E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 17 MT = 102 Q = 5.86840E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 62153.82c : (n,gamma) + 18 MT = 103 Q = -4.36770E+00 MeV Emin = 4.39670E+00 MeV frac = 1.00000E+00 Product nuclide = 611520 : (n,p) + 19 MT = 104 Q = -6.51660E+00 MeV Emin = 6.55987E+00 MeV frac = 1.00000E+00 Product nuclide = 61151.82c : (n,d) + 20 MT = 105 Q = -7.95900E+00 MeV Emin = 8.01188E+00 MeV frac = 1.00000E+00 Product nuclide = 611500 : (n,t) + 21 MT = 106 Q = -7.96510E+00 MeV Emin = 8.01798E+00 MeV frac = 1.00000E+00 Product nuclide = 60150.82c : (n,He-3) + 22 MT = 107 Q = 5.25900E+00 MeV Emin = 4.50000E-01 MeV frac = 1.00000E+00 Product nuclide = 601490 : (n,alpha) + 23 MT = 111 Q = -1.03190E+01 MeV Emin = 1.03875E+01 MeV frac = 1.00000E+00 Product nuclide = 601510 : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = -4.36770E+00 MeV Emin = 4.39670E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -6.51660E+00 MeV Emin = 6.55987E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -7.95900E+00 MeV Emin = 8.01188E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -7.96510E+00 MeV Emin = 8.01798E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 5.25900E+00 MeV Emin = 4.50000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -1.03190E+01 MeV Emin = 1.03875E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.39670E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.55987E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 8.01188E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 8.01798E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.50000E-01 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 8.84701E-04 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 1.22500E-01 MeV : total inelastic scattering + + Nuclide 220 / 1657 : 62153.82c -- samarium 153 (Sm-153) + + Pointers : 1793955 33265 + Primary type : Transport + Nuclide ZAI : 621530 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Sm153.ACE + Atomic weight (AW) : 152.92168 + Atomic weight ratio (AWR) : 151.60800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.67E+05 seconds (1.93 days) + Specific ingestion toxicity : 7.40E-10 Sv/Bq + Specific inhalation toxicity : 6.30E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 27 reaction channels + - 21 special reactions + - 9 transmutation reactions + - 6 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 27 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.86700E+00 MeV Emin = 5.90570E+00 MeV frac = 1.00000E+00 Product nuclide = 62152.82c : (n,2n) + 3 MT = 17 Q = -1.41250E+01 MeV Emin = 1.42182E+01 MeV frac = 1.00000E+00 Product nuclide = 62151.82c : (n,3n) + 4 MT = 22 Q = -6.09000E-01 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 601490 : (n,nalpha) + 5 MT = 24 Q = -5.64700E+00 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 60148.82c : (n,2nalpha) + 6 MT = 28 Q = -8.59000E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 611520 : (n,np) + 7 MT = 41 Q = -1.45300E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 61151.82c : (n,2np) + 8 MT = 51 Q = -7.54000E-03 MeV Emin = 7.00000E-03 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -3.58400E-02 MeV Emin = 3.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -5.35300E-02 MeV Emin = 5.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -6.54800E-02 MeV Emin = 5.98975E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -9.08700E-02 MeV Emin = 8.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -9.84000E-02 MeV Emin = 9.52592E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -1.12950E-01 MeV Emin = 1.06847E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -1.27300E-01 MeV Emin = 1.20917E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -1.74170E-01 MeV Emin = 1.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -1.82900E-01 MeV Emin = 1.79712E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -1.89200E-01 MeV Emin = 1.87277E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 62 Q = -1.94650E-01 MeV Emin = 1.93820E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 20 MT = 63 Q = -1.95900E-01 MeV Emin = 1.93820E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 21 MT = 64 Q = -2.37000E-01 MeV Emin = 2.19281E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 22 MT = 65 Q = -2.46300E-01 MeV Emin = 2.43244E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 23 MT = 66 Q = -2.61000E-01 MeV Emin = 2.55323E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 24 MT = 91 Q = -2.61000E-01 MeV Emin = 2.55323E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 25 MT = 102 Q = 7.96707E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 62154.82c : (n,gamma) + 26 MT = 103 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 611530 : (n,p) + 27 MT = 107 Q = 0.00000E+00 MeV Emin = 4.00000E-03 MeV frac = 1.00000E+00 Product nuclide = 60150.82c : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = -6.09000E-01 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 24 Q = -5.64700E+00 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,2nalpha) + 3 MT = 28 Q = -8.59000E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 4 MT = 41 Q = -1.45300E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,2np) + 5 MT = 103 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 107 Q = 0.00000E+00 MeV Emin = 4.00000E-03 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 21 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 4.00000E-03 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 8.50000E-04 MeV : damage-energy production + 4 MT = 600 Q = -1.09900E+00 MeV Emin = 2.00000E+00 MeV : (n,p) to ground state + 5 MT = 601 Q = -1.13100E+00 MeV Emin = 2.00000E+00 MeV : (n,p1) + 6 MT = 602 Q = -1.16500E+00 MeV Emin = 2.00000E+00 MeV : (n,p2) + 7 MT = 603 Q = -1.20600E+00 MeV Emin = 2.00000E+00 MeV : (n,p3) + 8 MT = 604 Q = -1.25000E+00 MeV Emin = 2.00000E+00 MeV : (n,p4) + 9 MT = 605 Q = -1.29900E+00 MeV Emin = 2.00000E+00 MeV : (n,p5) + 10 MT = 606 Q = -1.35400E+00 MeV Emin = 3.00000E+00 MeV : (n,p6) + 11 MT = 649 Q = -1.35400E+00 MeV Emin = 3.00000E+00 MeV : (n,p) to continuum + 12 MT = 800 Q = 6.77100E+00 MeV Emin = 4.00000E-03 MeV : (n,alpha) to ground state + 13 MT = 801 Q = 6.64079E+00 MeV Emin = 4.00000E-03 MeV : (n,a1) + 14 MT = 802 Q = 6.38955E+00 MeV Emin = 4.50000E-03 MeV : (n,a2) + 15 MT = 803 Q = 6.09563E+00 MeV Emin = 3.00000E-01 MeV : (n,a3) + 16 MT = 804 Q = 6.05060E+00 MeV Emin = 3.01563E-01 MeV : (n,a4) + 17 MT = 805 Q = 5.92034E+00 MeV Emin = 4.00000E-01 MeV : (n,a5) + 18 MT = 806 Q = 5.91806E+00 MeV Emin = 4.00000E-01 MeV : (n,a6) + 19 MT = 807 Q = 5.83614E+00 MeV Emin = 5.00000E-01 MeV : (n,a7) + 20 MT = 849 Q = 5.83614E+00 MeV Emin = 4.00000E-03 MeV : (n,alpha) to continuum + 21 MT = 4 Q = 0.00000E+00 MeV Emin = 7.00000E-03 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.07600E-01 MeV frac = 1.00000E+00 Product nuclide = 63153.82c : beta- + + Nuclide 221 / 1657 : 62154.82c -- samarium 154 (Sm-154) + + Pointers : 1800314 33311 + Primary type : Transport + Nuclide ZAI : 621540 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Sm154.ACE + Atomic weight (AW) : 153.92227 + Atomic weight ratio (AWR) : 152.60000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 36 reaction channels + - 21 special reactions + - 9 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 36 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.96700E+00 MeV Emin = 8.01921E+00 MeV frac = 1.00000E+00 Product nuclide = 62153.82c : (n,2n) + 3 MT = 17 Q = -1.38340E+01 MeV Emin = 1.39247E+01 MeV frac = 1.00000E+00 Product nuclide = 62152.82c : (n,3n) + 4 MT = 22 Q = -1.19600E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 60150.82c : (n,nalpha) + 5 MT = 24 Q = -8.57600E+00 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 601490 : (n,2nalpha) + 6 MT = 28 Q = -9.06600E+00 MeV Emin = 9.12541E+00 MeV frac = 1.00000E+00 Product nuclide = 611530 : (n,np) + 7 MT = 41 Q = -1.65570E+01 MeV Emin = 1.80000E+01 MeV frac = 1.00000E+00 Product nuclide = 611520 : (n,2np) + 8 MT = 51 Q = -8.19800E-02 MeV Emin = 8.24546E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -2.66790E-01 MeV Emin = 2.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -5.43730E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -9.02640E-01 MeV Emin = 9.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -9.21400E-01 MeV Emin = 9.17997E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -1.01239E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -1.09933E+00 MeV Emin = 1.10000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -1.10400E+00 MeV Emin = 1.10888E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -1.12000E+00 MeV Emin = 1.11929E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -1.17781E+00 MeV Emin = 1.15644E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -1.18065E+00 MeV Emin = 1.18696E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 62 Q = -1.20238E+00 MeV Emin = 1.20000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 20 MT = 63 Q = -1.28636E+00 MeV Emin = 1.25253E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 21 MT = 64 Q = -1.29500E+00 MeV Emin = 1.30000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 22 MT = 65 Q = -1.33280E+00 MeV Emin = 1.32251E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 23 MT = 66 Q = -1.33764E+00 MeV Emin = 1.34397E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 24 MT = 67 Q = -1.36500E+00 MeV Emin = 1.36018E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 25 MT = 68 Q = -1.37100E+00 MeV Emin = 1.37696E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 26 MT = 69 Q = -1.43100E+00 MeV Emin = 1.40000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 27 MT = 70 Q = -1.44005E+00 MeV Emin = 1.44493E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 28 MT = 71 Q = -1.47213E+00 MeV Emin = 1.46563E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 29 MT = 72 Q = -1.47500E+00 MeV Emin = 1.48322E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 30 MT = 73 Q = -1.47571E+00 MeV Emin = 1.48467E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 31 MT = 74 Q = -1.51519E+00 MeV Emin = 1.51256E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 32 MT = 75 Q = -1.53926E+00 MeV Emin = 1.53723E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 33 MT = 91 Q = -3.93422E-01 MeV Emin = 3.48000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 34 MT = 102 Q = 5.80697E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 621550 : (n,gamma) + 35 MT = 103 Q = 0.00000E+00 MeV Emin = 3.28338E+00 MeV frac = 1.00000E+00 Product nuclide = 611540 : (n,p) + 36 MT = 107 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 601510 : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = -1.19600E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 24 Q = -8.57600E+00 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,2nalpha) + 3 MT = 28 Q = -9.06600E+00 MeV Emin = 9.12541E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 4 MT = 41 Q = -1.65570E+01 MeV Emin = 1.80000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,2np) + 5 MT = 103 Q = 0.00000E+00 MeV Emin = 3.28338E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 107 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 21 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.28338E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 8.84982E-04 MeV : damage-energy production + 4 MT = 600 Q = -3.26200E+00 MeV Emin = 3.28338E+00 MeV : (n,p) to ground state + 5 MT = 601 Q = -3.26300E+00 MeV Emin = 3.28438E+00 MeV : (n,p1) + 6 MT = 602 Q = -3.31269E+00 MeV Emin = 3.33440E+00 MeV : (n,p2) + 7 MT = 603 Q = -3.33001E+00 MeV Emin = 5.00000E+00 MeV : (n,p3) + 8 MT = 604 Q = -3.34138E+00 MeV Emin = 5.00000E+00 MeV : (n,p4) + 9 MT = 605 Q = -3.36769E+00 MeV Emin = 5.00000E+00 MeV : (n,p5) + 10 MT = 606 Q = -3.41370E+00 MeV Emin = 5.00000E+00 MeV : (n,p6) + 11 MT = 607 Q = -3.41690E+00 MeV Emin = 5.00000E+00 MeV : (n,p7) + 12 MT = 608 Q = -3.43579E+00 MeV Emin = 5.00000E+00 MeV : (n,p8) + 13 MT = 609 Q = -3.44269E+00 MeV Emin = 5.00000E+00 MeV : (n,p9) + 14 MT = 610 Q = -3.44749E+00 MeV Emin = 5.00000E+00 MeV : (n,p10) + 15 MT = 611 Q = -3.45619E+00 MeV Emin = 5.00000E+00 MeV : (n,p11) + 16 MT = 612 Q = -3.50660E+00 MeV Emin = 5.00000E+00 MeV : (n,p12) + 17 MT = 613 Q = -3.53080E+00 MeV Emin = 5.00000E+00 MeV : (n,p13) + 18 MT = 649 Q = -3.53080E+00 MeV Emin = 5.00000E+00 MeV : (n,p) to continuum + 19 MT = 800 Q = 4.13800E+00 MeV Emin = 2.00000E+00 MeV : (n,alpha) to ground state + 20 MT = 849 Q = 4.13800E+00 MeV Emin = 2.00000E+00 MeV : (n,alpha) to continuum + 21 MT = 4 Q = 0.00000E+00 MeV Emin = 8.24546E-02 MeV : total inelastic scattering + + Nuclide 222 / 1657 : 63151.82c -- europium 151 (Eu-151) + + Pointers : 1819649 23651 + Primary type : Transport + Nuclide ZAI : 631510 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Eu151.ACE + Atomic weight (AW) : 150.91948 + Atomic weight ratio (AWR) : 149.62300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 22 reaction channels + - 7 special reactions + - 11 transmutation reactions + - 8 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 22 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.97050E+00 MeV Emin = 8.02377E+00 MeV frac = 1.00000E+00 Product nuclide = 631500 : (n,2n) + 3 MT = 17 Q = -1.44140E+01 MeV Emin = 1.45104E+01 MeV frac = 1.00000E+00 Product nuclide = 631490 : (n,3n) + 4 MT = 22 Q = 1.96400E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 61147.82c : (n,nalpha) + 5 MT = 28 Q = -4.89000E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 62150.82c : (n,np) + 6 MT = 51 Q = -2.20000E-02 MeV Emin = 2.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.94000E-01 MeV Emin = 1.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -1.96000E-01 MeV Emin = 1.96299E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -2.43000E-01 MeV Emin = 2.22307E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -3.08000E-01 MeV Emin = 3.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -3.50000E-01 MeV Emin = 3.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -5.05000E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -5.10000E-01 MeV Emin = 5.10881E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -6.20000E-01 MeV Emin = 6.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 91 Q = -6.95380E-01 MeV Emin = 6.67072E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 16 MT = 102 Q = 6.35100E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 63152.82c : (n,gamma) + 17 MT = 103 Q = 7.06440E-01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 62151.82c : (n,p) + 18 MT = 104 Q = -2.66540E+00 MeV Emin = 2.68322E+00 MeV frac = 1.00000E+00 Product nuclide = 62150.82c : (n,d) + 19 MT = 105 Q = -4.39350E+00 MeV Emin = 4.42286E+00 MeV frac = 1.00000E+00 Product nuclide = 62149.82c : (n,t) + 20 MT = 106 Q = -5.44680E+00 MeV Emin = 5.48320E+00 MeV frac = 1.00000E+00 Product nuclide = 61149.82c : (n,He-3) + 21 MT = 107 Q = 7.86550E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 61148.82c : (n,alpha) + 22 MT = 111 Q = -7.60380E+00 MeV Emin = 7.65462E+00 MeV frac = 1.00000E+00 Product nuclide = 611500 : (n,2p) + + 8 additional transport branches: + + 1 MT = 22 Q = 1.96400E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -4.89000E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = 7.06440E-01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -2.66540E+00 MeV Emin = 2.68322E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -4.39350E+00 MeV Emin = 4.42286E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 106 Q = -5.44680E+00 MeV Emin = 5.48320E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 7 MT = 107 Q = 7.86550E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 8 MT = 111 Q = -7.60380E+00 MeV Emin = 7.65462E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 2.68322E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 4.42286E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 5.48320E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 2.00000E-02 MeV : total inelastic scattering + + Nuclide 223 / 1657 : 63152.82c -- europium 152 (Eu-152) + + Pointers : 1822461 23697 + Primary type : Transport + Nuclide ZAI : 631520 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Eu152.ACE + Atomic weight (AW) : 151.92209 + Atomic weight ratio (AWR) : 150.61700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 4.27E+08 seconds (13.5 years) + Specific ingestion toxicity : 1.40E-09 Sv/Bq + Specific inhalation toxicity : 4.20E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 25 reaction channels + - 7 special reactions + - 12 transmutation reactions + - 9 transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 25 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.31010E+00 MeV Emin = 6.35201E+00 MeV frac = 1.00000E+00 Product nuclide = 63151.82c : (n,2n) + 3 MT = 17 Q = -1.42802E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 631500 : (n,3n) + 4 MT = 22 Q = 1.56409E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 61148.82c : (n,nalpha) + 5 MT = 28 Q = -5.60364E+00 MeV Emin = 6.35201E+00 MeV frac = 1.00000E+00 Product nuclide = 62151.82c : (n,np) + 6 MT = 32 Q = -8.89463E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 62150.82c : (n,nd) + 7 MT = 33 Q = -1.06996E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 62149.82c : (n,nt) + 8 MT = 51 Q = -4.84999E-02 MeV Emin = 4.44110E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -6.81999E-02 MeV Emin = 6.43264E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -7.22999E-02 MeV Emin = 7.18231E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -8.98999E-02 MeV Emin = 9.04342E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -9.22999E-02 MeV Emin = 9.28341E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -1.08100E-01 MeV Emin = 1.04409E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -1.14800E-01 MeV Emin = 1.12612E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -1.25800E-01 MeV Emin = 1.24213E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -1.42700E-01 MeV Emin = 1.39660E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -1.47800E-01 MeV Emin = 1.46856E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -1.50700E-01 MeV Emin = 1.51458E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 91 Q = -1.70000E-01 MeV Emin = 1.66576E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 20 MT = 102 Q = 8.55039E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 63153.82c : (n,gamma) + 21 MT = 103 Q = 2.65945E+00 MeV Emin = 1.00138E-01 MeV frac = 1.00000E+00 Product nuclide = 62152.82c : (n,p) + 22 MT = 104 Q = -3.29353E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 62151.82c : (n,d) + 23 MT = 105 Q = -2.70948E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 62150.82c : (n,t) + 24 MT = 106 Q = -6.18984E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 611500 : (n,He-3) + 25 MT = 107 Q = 8.83319E+00 MeV Emin = 9.83389E-02 MeV frac = 1.00000E+00 Product nuclide = 61149.82c : (n,alpha) + + 9 additional transport branches: + + 1 MT = 22 Q = 1.56409E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -5.60364E+00 MeV Emin = 6.35201E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -8.89463E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.06996E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 103 Q = 2.65945E+00 MeV Emin = 1.00138E-01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 104 Q = -3.29353E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 7 MT = 105 Q = -2.70948E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 8 MT = 106 Q = -6.18984E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 9 MT = 107 Q = 8.83319E+00 MeV Emin = 9.83389E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.00138E-01 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 4.00000E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 9.00000E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 9.83389E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 4.44110E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 2 Q = 1.87430E+00 MeV frac = 7.21000E-01 Product nuclide = 62152.82c : EC/beta+ + 2 RTYP = 1 Q = 1.81880E+00 MeV frac = 2.79000E-01 Product nuclide = 64152.82c : beta- + + Nuclide 224 / 1657 : 63153.82c -- europium 153 (Eu-153) + + Pointers : 1836114 23743 + Primary type : Transport + Nuclide ZAI : 631530 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Eu153.ACE + Atomic weight (AW) : 152.92168 + Atomic weight ratio (AWR) : 151.60800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 20 reaction channels + - 4 special reactions + - 7 transmutation reactions + - 5 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 20 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.55568E+00 MeV Emin = 8.61212E+00 MeV frac = 1.00000E+00 Product nuclide = 63152.82c : (n,2n) + 3 MT = 17 Q = -1.48614E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 63151.82c : (n,3n) + 4 MT = 22 Q = 2.74060E-01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 61149.82c : (n,nalpha) + 5 MT = 28 Q = -5.88721E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 62152.82c : (n,np) + 6 MT = 51 Q = -8.33999E-02 MeV Emin = 8.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -9.73999E-02 MeV Emin = 9.63414E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -1.03200E-01 MeV Emin = 1.01941E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -1.51600E-01 MeV Emin = 1.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -1.72900E-01 MeV Emin = 1.71445E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -1.93100E-01 MeV Emin = 1.89293E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -2.35300E-01 MeV Emin = 2.27639E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -2.69700E-01 MeV Emin = 2.66109E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -3.21900E-01 MeV Emin = 3.12011E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -3.25100E-01 MeV Emin = 3.26122E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -3.96399E-01 MeV Emin = 3.90046E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 91 Q = -3.99999E-01 MeV Emin = 4.01330E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 18 MT = 102 Q = 6.44223E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 63154.82c : (n,gamma) + 19 MT = 103 Q = -2.05300E-02 MeV Emin = 9.50000E-01 MeV frac = 1.00000E+00 Product nuclide = 62153.82c : (n,p) + 20 MT = 107 Q = 5.87529E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 611500 : (n,alpha) + + 5 additional transport branches: + + 1 MT = 22 Q = 2.74060E-01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -5.88721E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 102 Q = 6.44223E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 631541 : (n,gamma) + 4 MT = 103 Q = -2.05300E-02 MeV Emin = 9.50000E-01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 107 Q = 5.87529E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 4 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 9.50000E-01 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 4 MT = 4 Q = 0.00000E+00 MeV Emin = 8.00000E-02 MeV : total inelastic scattering + + Nuclide 225 / 1657 : 63154.82c -- europium 154 (Eu-154) + + Pointers : 1838361 23789 + Primary type : Transport + Nuclide ZAI : 631540 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Eu154.ACE + Atomic weight (AW) : 153.92227 + Atomic weight ratio (AWR) : 152.60000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.71E+08 seconds (8.61 years) + Specific ingestion toxicity : 2.00E-09 Sv/Bq + Specific inhalation toxicity : 5.30E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 17 reaction channels + - 7 special reactions + - 10 transmutation reactions + - 7 transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 17 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.43800E+00 MeV Emin = 6.80000E+00 MeV frac = 1.00000E+00 Product nuclide = 63153.82c : (n,2n) + 3 MT = 17 Q = -1.49900E+01 MeV Emin = 1.50882E+01 MeV frac = 1.00000E+00 Product nuclide = 63152.82c : (n,3n) + 4 MT = 22 Q = -6.07000E-01 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 611500 : (n,nalpha) + 5 MT = 28 Q = -6.46500E+00 MeV Emin = 6.50737E+00 MeV frac = 1.00000E+00 Product nuclide = 62153.82c : (n,np) + 6 MT = 51 Q = -6.80000E-02 MeV Emin = 6.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -8.28000E-02 MeV Emin = 8.16695E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -1.22100E-01 MeV Emin = 1.11450E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -1.72200E-01 MeV Emin = 1.53114E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -1.80000E-01 MeV Emin = 1.77755E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 91 Q = -2.31900E-01 MeV Emin = 2.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 12 MT = 102 Q = 8.15141E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 63155.82c : (n,gamma) + 13 MT = 103 Q = 1.51240E+00 MeV Emin = 9.25000E-03 MeV frac = 1.00000E+00 Product nuclide = 62154.82c : (n,p) + 14 MT = 104 Q = -4.24040E+00 MeV Emin = 4.26819E+00 MeV frac = 1.00000E+00 Product nuclide = 62153.82c : (n,d) + 15 MT = 105 Q = -3.84950E+00 MeV Emin = 3.87473E+00 MeV frac = 1.00000E+00 Product nuclide = 62152.82c : (n,t) + 16 MT = 106 Q = -7.33190E+00 MeV Emin = 7.37995E+00 MeV frac = 1.00000E+00 Product nuclide = 611520 : (n,He-3) + 17 MT = 107 Q = 7.30150E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 61151.82c : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -6.07000E-01 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -6.46500E+00 MeV Emin = 6.50737E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = 1.51240E+00 MeV Emin = 9.25000E-03 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -4.24040E+00 MeV Emin = 4.26819E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -3.84950E+00 MeV Emin = 3.87473E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 106 Q = -7.33190E+00 MeV Emin = 7.37995E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 7 MT = 107 Q = 7.30150E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 9.25000E-03 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 4.26819E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 3.87473E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 7.37995E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 6.00000E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 2 Q = 7.17300E-01 MeV frac = 1.80000E-04 Product nuclide = 62154.82c : EC/beta+ + 2 RTYP = 1 Q = 1.96840E+00 MeV frac = 9.99820E-01 Product nuclide = 64154.82c : beta- + + Nuclide 226 / 1657 : 63155.82c -- europium 155 (Eu-155) + + Pointers : 1845163 23835 + Primary type : Transport + Nuclide ZAI : 631550 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Eu155.ACE + Atomic weight (AW) : 154.92287 + Atomic weight ratio (AWR) : 153.59200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.50E+08 seconds (4.76 years) + Specific ingestion toxicity : 3.20E-10 Sv/Bq + Specific inhalation toxicity : 6.90E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 21 reaction channels + - 7 special reactions + - 10 transmutation reactions + - 7 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 21 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.94820E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 63154.82c : (n,2n) + 3 MT = 17 Q = -1.44060E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 63153.82c : (n,3n) + 4 MT = 22 Q = -8.70000E-01 MeV Emin = 8.50000E-01 MeV frac = 1.00000E+00 Product nuclide = 61151.82c : (n,nalpha) + 5 MT = 28 Q = -6.45800E+00 MeV Emin = 6.50005E+00 MeV frac = 1.00000E+00 Product nuclide = 62154.82c : (n,np) + 6 MT = 51 Q = -6.95470E-02 MeV Emin = 7.37500E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -9.93530E-02 MeV Emin = 1.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -1.58960E-01 MeV Emin = 1.70000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -2.38450E-01 MeV Emin = 2.47500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -2.98060E-01 MeV Emin = 3.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -6.95470E-01 MeV Emin = 7.32475E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -8.44510E-01 MeV Emin = 8.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -9.93530E-01 MeV Emin = 1.09625E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -1.09000E+00 MeV Emin = 1.27781E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 91 Q = -1.27000E+00 MeV Emin = 1.27891E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 16 MT = 102 Q = 6.33968E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 63156.82c : (n,gamma) + 17 MT = 103 Q = -4.96770E+00 MeV Emin = 5.00004E+00 MeV frac = 1.00000E+00 Product nuclide = 621550 : (n,p) + 18 MT = 104 Q = -8.94190E+00 MeV Emin = 9.00012E+00 MeV frac = 1.00000E+00 Product nuclide = 62154.82c : (n,d) + 19 MT = 105 Q = -1.09290E+01 MeV Emin = 1.10002E+01 MeV frac = 1.00000E+00 Product nuclide = 62153.82c : (n,t) + 20 MT = 106 Q = -1.88770E+01 MeV Emin = 1.90000E+01 MeV frac = 1.00000E+00 Product nuclide = 611530 : (n,He-3) + 21 MT = 107 Q = 5.07850E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 611520 : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -8.70000E-01 MeV Emin = 8.50000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -6.45800E+00 MeV Emin = 6.50005E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -4.96770E+00 MeV Emin = 5.00004E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -8.94190E+00 MeV Emin = 9.00012E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -1.09290E+01 MeV Emin = 1.10002E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 106 Q = -1.88770E+01 MeV Emin = 1.90000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 7 MT = 107 Q = 5.07850E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 5.00004E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 9.00012E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.10002E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.90000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 7.37500E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.52100E-01 MeV frac = 1.00000E+00 Product nuclide = 64155.82c : beta- + + Nuclide 227 / 1657 : 63156.82c -- europium 156 (Eu-156) + + Pointers : 1848705 23881 + Primary type : Transport + Nuclide ZAI : 631560 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Eu156.ACE + Atomic weight (AW) : 155.92548 + Atomic weight ratio (AWR) : 154.58600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.31E+06 seconds (15.2 days) + Specific ingestion toxicity : 2.20E-09 Sv/Bq + Specific inhalation toxicity : 3.40E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 18 reaction channels + - 6 special reactions + - 11 transmutation reactions + - 8 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 18 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.33410E+00 MeV Emin = 6.37508E+00 MeV frac = 1.00000E+00 Product nuclide = 63155.82c : (n,2n) + 3 MT = 17 Q = -1.45092E+01 MeV Emin = 1.46031E+01 MeV frac = 1.00000E+00 Product nuclide = 63154.82c : (n,3n) + 4 MT = 22 Q = -1.21490E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 611520 : (n,nalpha) + 5 MT = 28 Q = -7.18063E+00 MeV Emin = 8.54375E+00 MeV frac = 1.00000E+00 Product nuclide = 621550 : (n,np) + 6 MT = 32 Q = -1.06886E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 62154.82c : (n,nd) + 7 MT = 33 Q = -1.24766E+01 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 62153.82c : (n,nt) + 8 MT = 51 Q = -2.26000E-02 MeV Emin = 2.22183E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -4.77999E-02 MeV Emin = 4.40546E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -8.71999E-02 MeV Emin = 8.38820E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -1.25300E-01 MeV Emin = 1.19583E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -2.91100E-01 MeV Emin = 2.71491E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 91 Q = -3.30000E-01 MeV Emin = 3.24101E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 14 MT = 102 Q = 7.44592E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 63157.82c : (n,gamma) + 15 MT = 103 Q = 6.74684E-02 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 621560 : (n,p) + 16 MT = 104 Q = -4.87051E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 621550 : (n,d) + 17 MT = 105 Q = -4.50346E+00 MeV Emin = 6.37508E+00 MeV frac = 1.00000E+00 Product nuclide = 62154.82c : (n,t) + 18 MT = 107 Q = 6.33120E+00 MeV Emin = 9.99883E-02 MeV frac = 1.00000E+00 Product nuclide = 611530 : (n,alpha) + + 8 additional transport branches: + + 1 MT = 22 Q = -1.21490E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -7.18063E+00 MeV Emin = 8.54375E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.06886E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.24766E+01 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 103 Q = 6.74684E-02 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 104 Q = -4.87051E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 7 MT = 105 Q = -4.50346E+00 MeV Emin = 6.37508E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 8 MT = 107 Q = 6.33120E+00 MeV Emin = 9.99883E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 6.37508E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 9.99883E-02 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 9.00000E-04 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 2.22183E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.44900E+00 MeV frac = 1.00000E+00 Product nuclide = 64156.82c : beta- + + Nuclide 228 / 1657 : 63157.82c -- europium 157 (Eu-157) + + Pointers : 1855178 23927 + Primary type : Transport + Nuclide ZAI : 631570 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Eu157.ACE + Atomic weight (AW) : 156.92507 + Atomic weight ratio (AWR) : 155.57700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 5.46E+04 seconds (15.2 hours) + Specific ingestion toxicity : 6.00E-10 Sv/Bq + Specific inhalation toxicity : 2.80E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 46 reaction channels + - 21 special reactions + - 9 transmutation reactions + - 6 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 46 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.44800E+00 MeV Emin = 7.49587E+00 MeV frac = 1.00000E+00 Product nuclide = 63156.82c : (n,2n) + 3 MT = 17 Q = -1.37850E+01 MeV Emin = 1.38736E+01 MeV frac = 1.00000E+00 Product nuclide = 63155.82c : (n,3n) + 4 MT = 22 Q = -1.20800E+00 MeV Emin = 7.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 611530 : (n,nalpha) + 5 MT = 24 Q = -8.69900E+00 MeV Emin = 1.55000E+01 MeV frac = 1.00000E+00 Product nuclide = 611520 : (n,2nalpha) + 6 MT = 28 Q = -7.38800E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 621560 : (n,np) + 7 MT = 41 Q = -1.46300E+01 MeV Emin = 1.65000E+01 MeV frac = 1.00000E+00 Product nuclide = 621550 : (n,2np) + 8 MT = 51 Q = -7.67100E-02 MeV Emin = 7.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -1.77000E-01 MeV Emin = 1.74566E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -1.97860E-01 MeV Emin = 1.86849E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -2.63230E-01 MeV Emin = 2.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -2.96000E-01 MeV Emin = 2.81413E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -3.50000E-01 MeV Emin = 3.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -3.94330E-01 MeV Emin = 3.93750E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -4.53500E-01 MeV Emin = 4.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -4.57000E-01 MeV Emin = 4.58176E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -5.39000E-01 MeV Emin = 5.21232E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -5.84000E-01 MeV Emin = 5.75000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 62 Q = -6.45000E-01 MeV Emin = 6.24573E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 20 MT = 63 Q = -6.70420E-01 MeV Emin = 6.62365E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 21 MT = 64 Q = -7.16310E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 22 MT = 65 Q = -7.24000E-01 MeV Emin = 7.28186E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 23 MT = 66 Q = -9.71990E-01 MeV Emin = 9.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 24 MT = 67 Q = -9.88380E-01 MeV Emin = 9.86486E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 25 MT = 68 Q = -1.02127E+00 MeV Emin = 1.01391E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 26 MT = 69 Q = -1.05700E+00 MeV Emin = 1.04581E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 27 MT = 70 Q = -1.07300E+00 MeV Emin = 1.07285E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 28 MT = 71 Q = -1.09800E+00 MeV Emin = 1.10000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 29 MT = 72 Q = -1.14500E+00 MeV Emin = 1.12871E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 30 MT = 73 Q = -1.24700E+00 MeV Emin = 1.20000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 31 MT = 74 Q = -1.30000E+00 MeV Emin = 1.28890E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 32 MT = 75 Q = -1.32200E+00 MeV Emin = 1.32224E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 33 MT = 76 Q = -1.36092E+00 MeV Emin = 1.35557E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 34 MT = 77 Q = -1.36900E+00 MeV Emin = 1.35557E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 27. excited state + 35 MT = 78 Q = -1.37732E+00 MeV Emin = 1.38199E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 28. excited state + 36 MT = 79 Q = -1.38294E+00 MeV Emin = 1.38900E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 29. excited state + 37 MT = 80 Q = -1.40400E+00 MeV Emin = 1.40243E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 30. excited state + 38 MT = 81 Q = -1.41847E+00 MeV Emin = 1.42046E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 31. excited state + 39 MT = 82 Q = -1.46312E+00 MeV Emin = 1.44277E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 32. excited state + 40 MT = 83 Q = -1.56200E+00 MeV Emin = 1.53602E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 33. excited state + 41 MT = 84 Q = -1.60300E+00 MeV Emin = 1.59267E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 34. excited state + 42 MT = 85 Q = -1.63500E+00 MeV Emin = 1.63498E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 35. excited state + 43 MT = 91 Q = -4.91839E-01 MeV Emin = 4.77469E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 44 MT = 102 Q = 5.81557E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 631580 : (n,gamma) + 45 MT = 103 Q = 0.00000E+00 MeV Emin = 3.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 621570 : (n,p) + 46 MT = 107 Q = 0.00000E+00 MeV Emin = 1.70000E+00 MeV frac = 1.00000E+00 Product nuclide = 611540 : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = -1.20800E+00 MeV Emin = 7.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 24 Q = -8.69900E+00 MeV Emin = 1.55000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,2nalpha) + 3 MT = 28 Q = -7.38800E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 4 MT = 41 Q = -1.46300E+01 MeV Emin = 1.65000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,2np) + 5 MT = 103 Q = 0.00000E+00 MeV Emin = 3.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 107 Q = 0.00000E+00 MeV Emin = 1.70000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 21 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.50000E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 1.70000E+00 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 9.00000E-04 MeV : damage-energy production + 4 MT = 600 Q = -1.95200E+00 MeV Emin = 3.50000E+00 MeV : (n,p) to ground state + 5 MT = 649 Q = -1.95200E+00 MeV Emin = 3.70000E+00 MeV : (n,p) to continuum + 6 MT = 800 Q = 4.59600E+00 MeV Emin = 1.70000E+00 MeV : (n,alpha) to ground state + 7 MT = 801 Q = 4.59500E+00 MeV Emin = 4.75000E+00 MeV : (n,a1) + 8 MT = 802 Q = 4.54531E+00 MeV Emin = 1.70000E+00 MeV : (n,a2) + 9 MT = 803 Q = 4.52799E+00 MeV Emin = 1.70000E+00 MeV : (n,a3) + 10 MT = 804 Q = 4.51662E+00 MeV Emin = 1.70000E+00 MeV : (n,a4) + 11 MT = 805 Q = 4.49031E+00 MeV Emin = 1.70000E+00 MeV : (n,a5) + 12 MT = 806 Q = 4.44430E+00 MeV Emin = 2.00000E+00 MeV : (n,a6) + 13 MT = 807 Q = 4.44110E+00 MeV Emin = 2.00000E+00 MeV : (n,a7) + 14 MT = 808 Q = 4.42221E+00 MeV Emin = 2.00000E+00 MeV : (n,a8) + 15 MT = 809 Q = 4.41531E+00 MeV Emin = 2.00000E+00 MeV : (n,a9) + 16 MT = 810 Q = 4.41051E+00 MeV Emin = 2.00000E+00 MeV : (n,a10) + 17 MT = 811 Q = 4.40181E+00 MeV Emin = 2.00000E+00 MeV : (n,a11) + 18 MT = 812 Q = 4.35140E+00 MeV Emin = 2.00000E+00 MeV : (n,a12) + 19 MT = 813 Q = 4.32720E+00 MeV Emin = 2.00000E+00 MeV : (n,a13) + 20 MT = 849 Q = 4.32720E+00 MeV Emin = 2.20000E+00 MeV : (n,alpha) to continuum + 21 MT = 4 Q = 0.00000E+00 MeV Emin = 7.00000E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.36300E+00 MeV frac = 1.00000E+00 Product nuclide = 64157.82c : beta- + + Nuclide 229 / 1657 : 64152.82c -- gadolinium 152 (Gd-152) + + Pointers : 1873153 24295 + Primary type : Transport + Nuclide ZAI : 641520 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Gd152.ACE + Atomic weight (AW) : 151.92007 + Atomic weight ratio (AWR) : 150.61500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 3.41E+21 seconds (1.08E+14 years) + Specific ingestion toxicity : 4.10E-08 Sv/Bq + Specific inhalation toxicity : 1.90E-05 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 43 reaction channels + - 7 special reactions + - 12 transmutation reactions + - 9 transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 43 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.61109E+00 MeV Emin = 8.66828E+00 MeV frac = 1.00000E+00 Product nuclide = 641510 : (n,2n) + 3 MT = 17 Q = -1.50902E+01 MeV Emin = 1.51904E+01 MeV frac = 1.00000E+00 Product nuclide = 641500 : (n,3n) + 4 MT = 22 Q = 2.21009E+00 MeV Emin = 1.01563E-01 MeV frac = 1.00000E+00 Product nuclide = 62148.82c : (n,nalpha) + 5 MT = 28 Q = -7.34664E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 63151.82c : (n,np) + 6 MT = 32 Q = -1.30066E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 631500 : (n,nd) + 7 MT = 33 Q = -1.32146E+01 MeV Emin = 1.51904E+01 MeV frac = 1.00000E+00 Product nuclide = 631490 : (n,nt) + 8 MT = 51 Q = -3.44300E-01 MeV Emin = 3.23293E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -6.15399E-01 MeV Emin = 6.16736E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -7.55399E-01 MeV Emin = 7.60156E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -9.30599E-01 MeV Emin = 9.18389E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -1.04780E+00 MeV Emin = 1.04909E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -1.10920E+00 MeV Emin = 1.10111E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -1.12320E+00 MeV Emin = 1.12361E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -1.22730E+00 MeV Emin = 1.21089E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -1.28230E+00 MeV Emin = 1.27551E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -1.31470E+00 MeV Emin = 1.31120E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -1.31840E+00 MeV Emin = 1.32529E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 62 Q = -1.43400E+00 MeV Emin = 1.41625E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 20 MT = 63 Q = -1.46050E+00 MeV Emin = 1.46020E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 21 MT = 64 Q = -1.47050E+00 MeV Emin = 1.47523E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 22 MT = 65 Q = -1.55020E+00 MeV Emin = 1.53025E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 23 MT = 66 Q = -1.60560E+00 MeV Emin = 1.59535E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 24 MT = 67 Q = -1.64340E+00 MeV Emin = 1.63529E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 25 MT = 68 Q = -1.66810E+00 MeV Emin = 1.66675E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 26 MT = 69 Q = -1.69240E+00 MeV Emin = 1.69141E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 27 MT = 70 Q = -1.74670E+00 MeV Emin = 1.75000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 28 MT = 71 Q = -1.75600E+00 MeV Emin = 1.75830E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 29 MT = 72 Q = -1.77160E+00 MeV Emin = 1.77551E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 30 MT = 73 Q = -1.80770E+00 MeV Emin = 1.80607E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 31 MT = 74 Q = -1.83960E+00 MeV Emin = 1.83576E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 32 MT = 75 Q = -1.86150E+00 MeV Emin = 1.86284E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 33 MT = 76 Q = -1.86200E+00 MeV Emin = 1.87411E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 34 MT = 77 Q = -1.88020E+00 MeV Emin = 1.88352E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 27. excited state + 35 MT = 78 Q = -1.91540E+00 MeV Emin = 1.91483E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 28. excited state + 36 MT = 79 Q = -1.94120E+00 MeV Emin = 1.94541E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 29. excited state + 37 MT = 91 Q = -1.97540E+00 MeV Emin = 1.97561E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 38 MT = 102 Q = 6.48739E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 641530 : (n,gamma) + 39 MT = 103 Q = -1.03654E+00 MeV Emin = 2.00391E+00 MeV frac = 1.00000E+00 Product nuclide = 63152.82c : (n,p) + 40 MT = 104 Q = -5.03652E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 63151.82c : (n,d) + 41 MT = 105 Q = -6.82147E+00 MeV Emin = 8.66828E+00 MeV frac = 1.00000E+00 Product nuclide = 631500 : (n,t) + 42 MT = 106 Q = -4.50984E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 62150.82c : (n,He-3) + 43 MT = 107 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 62149.82c : (n,alpha) + + 9 additional transport branches: + + 1 MT = 22 Q = 2.21009E+00 MeV Emin = 1.01563E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -7.34664E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.30066E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.32146E+01 MeV Emin = 1.51904E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 103 Q = -1.03654E+00 MeV Emin = 2.00391E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 104 Q = -5.03652E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 7 MT = 105 Q = -6.82147E+00 MeV Emin = 8.66828E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 8 MT = 106 Q = -4.50984E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 9 MT = 107 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.00391E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 8.66828E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 9.00000E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 3.23293E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 4 Q = 2.20460E+00 MeV frac = 1.00000E+00 Product nuclide = 62148.82c : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 2.20460E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 230 / 1657 : 64154.82c -- gadolinium 154 (Gd-154) + + Pointers : 1878961 24341 + Primary type : Transport + Nuclide ZAI : 641540 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Gd154.ACE + Atomic weight (AW) : 153.92127 + Atomic weight ratio (AWR) : 152.59900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 24 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 24 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -1.23000E-01 MeV Emin = 1.12500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -3.71000E-01 MeV Emin = 3.70000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -6.81000E-01 MeV Emin = 5.27731E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -7.18000E-01 MeV Emin = 7.15169E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -8.16000E-01 MeV Emin = 7.60675E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -9.99000E-01 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 57 Q = -1.05000E+00 MeV Emin = 1.03122E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 9 MT = 58 Q = -1.06000E+00 MeV Emin = 1.06190E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 10 MT = 59 Q = -1.13000E+00 MeV Emin = 1.10217E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 11 MT = 60 Q = -1.26000E+00 MeV Emin = 1.23552E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 12 MT = 61 Q = -1.40000E+00 MeV Emin = 1.38415E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 13 MT = 62 Q = -1.62000E+00 MeV Emin = 1.60000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 14 MT = 63 Q = -1.65000E+00 MeV Emin = 1.64571E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 15 MT = 64 Q = -1.72000E+00 MeV Emin = 1.72041E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 16 MT = 65 Q = -1.77000E+00 MeV Emin = 1.78000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 17 MT = 91 Q = -1.77000E+00 MeV Emin = 1.78000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 18 MT = 102 Q = 6.44600E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 64155.82c : (n,gamma) + 19 MT = 103 Q = -1.19490E+00 MeV Emin = 1.17000E+00 MeV frac = 1.00000E+00 Product nuclide = 63154.82c : (n,p) + 20 MT = 104 Q = -5.40330E+00 MeV Emin = 5.43871E+00 MeV frac = 1.00000E+00 Product nuclide = 63153.82c : (n,d) + 21 MT = 105 Q = -7.69540E+00 MeV Emin = 7.74583E+00 MeV frac = 1.00000E+00 Product nuclide = 63152.82c : (n,t) + 22 MT = 106 Q = -5.80080E+00 MeV Emin = 5.83881E+00 MeV frac = 1.00000E+00 Product nuclide = 62152.82c : (n,He-3) + 23 MT = 107 Q = 6.51430E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 62151.82c : (n,alpha) + 24 MT = 111 Q = -7.65080E+00 MeV Emin = 7.70094E+00 MeV frac = 1.00000E+00 Product nuclide = 62153.82c : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = -1.19490E+00 MeV Emin = 1.17000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -5.40330E+00 MeV Emin = 5.43871E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -7.69540E+00 MeV Emin = 7.74583E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -5.80080E+00 MeV Emin = 5.83881E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 6.51430E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -7.65080E+00 MeV Emin = 7.70094E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.17000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.43871E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 7.74583E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 5.83881E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 1.12500E-01 MeV : total inelastic scattering + + Nuclide 231 / 1657 : 64155.82c -- gadolinium 155 (Gd-155) + + Pointers : 1881773 24387 + Primary type : Transport + Nuclide ZAI : 641550 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Gd155.ACE + Atomic weight (AW) : 154.92287 + Atomic weight ratio (AWR) : 153.59200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 38 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 38 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -6.00000E-02 MeV Emin = 6.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -8.65000E-02 MeV Emin = 8.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -1.05300E-01 MeV Emin = 1.02993E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -1.07600E-01 MeV Emin = 1.07433E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -1.18000E-01 MeV Emin = 1.16478E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -1.21500E-01 MeV Emin = 1.21631E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 57 Q = -1.46100E-01 MeV Emin = 1.41635E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 9 MT = 58 Q = -2.14300E-01 MeV Emin = 2.07847E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 10 MT = 59 Q = -2.35200E-01 MeV Emin = 2.27528E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 11 MT = 60 Q = -2.51000E-01 MeV Emin = 2.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 12 MT = 61 Q = -2.66700E-01 MeV Emin = 2.64485E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 13 MT = 62 Q = -2.68600E-01 MeV Emin = 2.69393E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 14 MT = 63 Q = -2.86900E-01 MeV Emin = 2.84739E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 15 MT = 64 Q = -3.21500E-01 MeV Emin = 3.11796E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 16 MT = 65 Q = -3.26000E-01 MeV Emin = 3.25858E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 17 MT = 66 Q = -3.67700E-01 MeV Emin = 3.62225E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 18 MT = 67 Q = -3.90000E-01 MeV Emin = 3.86928E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 19 MT = 68 Q = -3.93000E-01 MeV Emin = 3.94049E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 20 MT = 69 Q = -4.22500E-01 MeV Emin = 4.17828E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 21 MT = 70 Q = -4.27200E-01 MeV Emin = 4.27616E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 22 MT = 71 Q = -4.51300E-01 MeV Emin = 4.48174E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 23 MT = 72 Q = -4.87000E-01 MeV Emin = 4.81188E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 24 MT = 73 Q = -4.88800E-01 MeV Emin = 4.91077E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 25 MT = 74 Q = -5.33000E-01 MeV Emin = 5.27353E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 26 MT = 75 Q = -5.56000E-01 MeV Emin = 5.50939E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 27 MT = 76 Q = -5.59900E-01 MeV Emin = 5.61583E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 28 MT = 77 Q = -5.92400E-01 MeV Emin = 5.88079E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 27. excited state + 29 MT = 78 Q = -6.15500E-01 MeV Emin = 6.10788E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 28. excited state + 30 MT = 79 Q = -6.17000E-01 MeV Emin = 6.20828E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 29. excited state + 31 MT = 91 Q = -6.48000E-01 MeV Emin = 6.44419E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 32 MT = 102 Q = 8.53640E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 64156.82c : (n,gamma) + 33 MT = 103 Q = 5.36450E-01 MeV Emin = 4.00000E-02 MeV frac = 1.00000E+00 Product nuclide = 63155.82c : (n,p) + 34 MT = 104 Q = -5.40740E+00 MeV Emin = 5.44261E+00 MeV frac = 1.00000E+00 Product nuclide = 63154.82c : (n,d) + 35 MT = 105 Q = -5.58410E+00 MeV Emin = 5.62046E+00 MeV frac = 1.00000E+00 Product nuclide = 63153.82c : (n,t) + 36 MT = 106 Q = -6.37170E+00 MeV Emin = 6.41319E+00 MeV frac = 1.00000E+00 Product nuclide = 62153.82c : (n,He-3) + 37 MT = 107 Q = 8.33370E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 62152.82c : (n,alpha) + 38 MT = 111 Q = -6.12130E+00 MeV Emin = 6.16115E+00 MeV frac = 1.00000E+00 Product nuclide = 62154.82c : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = 5.36450E-01 MeV Emin = 4.00000E-02 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -5.40740E+00 MeV Emin = 5.44261E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -5.58410E+00 MeV Emin = 5.62046E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -6.37170E+00 MeV Emin = 6.41319E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 8.33370E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -6.12130E+00 MeV Emin = 6.16115E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.00000E-02 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.44261E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 5.62046E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 6.41319E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 6.00000E-02 MeV : total inelastic scattering + + Nuclide 232 / 1657 : 64156.82c -- gadolinium 156 (Gd-156) + + Pointers : 1885791 24433 + Primary type : Transport + Nuclide ZAI : 641560 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Gd156.ACE + Atomic weight (AW) : 155.92205 + Atomic weight ratio (AWR) : 154.58260 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 24 reaction channels + - 7 special reactions + - 8 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 24 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.52690E+00 MeV Emin = 8.58210E+00 MeV frac = 1.00000E+00 Product nuclide = 64155.82c : (n,2n) + 3 MT = 51 Q = -8.90000E-02 MeV Emin = 8.82875E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 4 MT = 52 Q = -2.88000E-01 MeV Emin = 2.44930E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 5 MT = 53 Q = -5.85000E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 6 MT = 54 Q = -9.60000E-01 MeV Emin = 1.27660E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 7 MT = 55 Q = -1.04950E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 8 MT = 56 Q = -1.13200E+00 MeV Emin = 1.09815E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 9 MT = 57 Q = -1.15400E+00 MeV Emin = 1.15075E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 10 MT = 58 Q = -1.16800E+00 MeV Emin = 1.16880E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 11 MT = 59 Q = -1.24200E+00 MeV Emin = 1.20000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 12 MT = 60 Q = -1.24900E+00 MeV Emin = 1.25405E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 13 MT = 61 Q = -1.26800E+00 MeV Emin = 1.26710E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 14 MT = 62 Q = -1.32000E+00 MeV Emin = 1.30275E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 15 MT = 63 Q = -1.35800E+00 MeV Emin = 1.34790E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 16 MT = 64 Q = -1.36600E+00 MeV Emin = 1.37090E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 17 MT = 91 Q = -1.40800E+00 MeV Emin = 1.40000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 18 MT = 102 Q = 6.35980E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 64157.82c : (n,gamma) + 19 MT = 103 Q = -1.66980E+00 MeV Emin = 1.68041E+00 MeV frac = 1.00000E+00 Product nuclide = 63156.82c : (n,p) + 20 MT = 104 Q = -5.77330E+00 MeV Emin = 5.81065E+00 MeV frac = 1.00000E+00 Product nuclide = 63155.82c : (n,d) + 21 MT = 105 Q = -7.68540E+00 MeV Emin = 7.73512E+00 MeV frac = 1.00000E+00 Product nuclide = 63154.82c : (n,t) + 22 MT = 106 Q = -6.93950E+00 MeV Emin = 6.98439E+00 MeV frac = 1.00000E+00 Product nuclide = 62154.82c : (n,He-3) + 23 MT = 107 Q = 5.66550E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 62153.82c : (n,alpha) + 24 MT = 111 Q = -8.84330E+00 MeV Emin = 8.90051E+00 MeV frac = 1.00000E+00 Product nuclide = 621550 : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = -1.66980E+00 MeV Emin = 1.68041E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -5.77330E+00 MeV Emin = 5.81065E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -7.68540E+00 MeV Emin = 7.73512E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -6.93950E+00 MeV Emin = 6.98439E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 5.66550E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -8.84330E+00 MeV Emin = 8.90051E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.68041E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.81065E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 7.73512E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 6.98439E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 8.82875E-02 MeV : total inelastic scattering + + Nuclide 233 / 1657 : 64157.82c -- gadolinium 157 (Gd-157) + + Pointers : 1888603 24479 + Primary type : Transport + Nuclide ZAI : 641570 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Gd157.ACE + Atomic weight (AW) : 156.92406 + Atomic weight ratio (AWR) : 155.57600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 37 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 37 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -5.45000E-02 MeV Emin = 5.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -6.40000E-02 MeV Emin = 6.32163E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -1.15800E-01 MeV Emin = 1.08272E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -1.31500E-01 MeV Emin = 1.28642E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -1.81000E-01 MeV Emin = 1.74122E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -2.27400E-01 MeV Emin = 2.21646E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 57 Q = -3.46000E-01 MeV Emin = 3.36168E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 9 MT = 58 Q = -3.60000E-01 MeV Emin = 3.57030E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 10 MT = 59 Q = -4.25000E-01 MeV Emin = 4.17511E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 11 MT = 60 Q = -4.36600E-01 MeV Emin = 4.35028E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 12 MT = 61 Q = -4.77200E-01 MeV Emin = 4.71329E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 13 MT = 62 Q = -5.17000E-01 MeV Emin = 5.10162E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 14 MT = 63 Q = -5.27000E-01 MeV Emin = 5.25355E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 15 MT = 64 Q = -6.17000E-01 MeV Emin = 6.00896E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 16 MT = 65 Q = -6.39000E-01 MeV Emin = 6.34804E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 17 MT = 66 Q = -6.83000E-01 MeV Emin = 6.65249E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 18 MT = 67 Q = -6.85000E-01 MeV Emin = 6.88397E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 19 MT = 68 Q = -6.87000E-01 MeV Emin = 6.90410E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 20 MT = 69 Q = -7.00000E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 21 MT = 70 Q = -7.04000E-01 MeV Emin = 7.07519E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 22 MT = 71 Q = -7.21000E-01 MeV Emin = 7.19218E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 23 MT = 72 Q = -7.45000E-01 MeV Emin = 7.40731E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 24 MT = 73 Q = -7.51000E-01 MeV Emin = 7.52808E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 25 MT = 74 Q = -7.65000E-01 MeV Emin = 7.62872E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 26 MT = 75 Q = -7.91000E-01 MeV Emin = 7.86272E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 27 MT = 76 Q = -8.10000E-01 MeV Emin = 8.07603E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 28 MT = 77 Q = -8.13000E-01 MeV Emin = 8.16716E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 27. excited state + 29 MT = 78 Q = -8.39000E-01 MeV Emin = 8.43638E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 28. excited state + 30 MT = 91 Q = -8.50000E-01 MeV Emin = 8.49928E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 31 MT = 102 Q = 7.93740E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 64158.82c : (n,gamma) + 32 MT = 103 Q = -5.77180E-01 MeV Emin = 5.69004E-01 MeV frac = 1.00000E+00 Product nuclide = 63157.82c : (n,p) + 33 MT = 104 Q = -5.80430E+00 MeV Emin = 5.84161E+00 MeV frac = 1.00000E+00 Product nuclide = 63156.82c : (n,d) + 34 MT = 105 Q = -5.87600E+00 MeV Emin = 5.91377E+00 MeV frac = 1.00000E+00 Product nuclide = 63155.82c : (n,t) + 35 MT = 106 Q = -7.48630E+00 MeV Emin = 7.53442E+00 MeV frac = 1.00000E+00 Product nuclide = 621550 : (n,He-3) + 36 MT = 107 Q = 7.27300E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 62154.82c : (n,alpha) + 37 MT = 111 Q = -7.96070E+00 MeV Emin = 8.01187E+00 MeV frac = 1.00000E+00 Product nuclide = 621560 : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = -5.77180E-01 MeV Emin = 5.69004E-01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -5.80430E+00 MeV Emin = 5.84161E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -5.87600E+00 MeV Emin = 5.91377E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -7.48630E+00 MeV Emin = 7.53442E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 7.27300E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -7.96070E+00 MeV Emin = 8.01187E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 5.69004E-01 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.84161E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 5.91377E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 7.53442E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 5.00000E-02 MeV : total inelastic scattering + + Nuclide 234 / 1657 : 64158.82c -- gadolinium 158 (Gd-158) + + Pointers : 1892364 24525 + Primary type : Transport + Nuclide ZAI : 641580 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Gd158.ACE + Atomic weight (AW) : 157.92466 + Atomic weight ratio (AWR) : 156.56800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 20 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 20 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -7.95000E-02 MeV Emin = 7.81262E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -2.61000E-01 MeV Emin = 2.42500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -5.39000E-01 MeV Emin = 6.17500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -8.98000E-01 MeV Emin = 1.56500E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -9.78000E-01 MeV Emin = 9.13188E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -1.02000E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 57 Q = -1.04000E+00 MeV Emin = 1.03656E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 9 MT = 58 Q = -1.18000E+00 MeV Emin = 1.11707E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 10 MT = 59 Q = -1.27000E+00 MeV Emin = 1.23282E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 11 MT = 60 Q = -1.40000E+00 MeV Emin = 1.34351E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 12 MT = 61 Q = -1.52000E+00 MeV Emin = 1.46932E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 13 MT = 91 Q = -1.52000E+00 MeV Emin = 1.56500E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 14 MT = 102 Q = 5.94310E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 641590 : (n,gamma) + 15 MT = 103 Q = -2.66740E+00 MeV Emin = 2.68444E+00 MeV frac = 1.00000E+00 Product nuclide = 631580 : (n,p) + 16 MT = 104 Q = -6.28810E+00 MeV Emin = 6.32826E+00 MeV frac = 1.00000E+00 Product nuclide = 63157.82c : (n,d) + 17 MT = 105 Q = -7.48350E+00 MeV Emin = 7.53130E+00 MeV frac = 1.00000E+00 Product nuclide = 63156.82c : (n,t) + 18 MT = 106 Q = -8.18010E+00 MeV Emin = 8.23235E+00 MeV frac = 1.00000E+00 Product nuclide = 621560 : (n,He-3) + 19 MT = 107 Q = 5.14970E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 621550 : (n,alpha) + 20 MT = 111 Q = -1.03340E+01 MeV Emin = 1.04000E+01 MeV frac = 1.00000E+00 Product nuclide = 621570 : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = -2.66740E+00 MeV Emin = 2.68444E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -6.28810E+00 MeV Emin = 6.32826E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -7.48350E+00 MeV Emin = 7.53130E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -8.18010E+00 MeV Emin = 8.23235E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 5.14970E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -1.03340E+01 MeV Emin = 1.04000E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.68444E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.32826E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 7.53130E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 8.23235E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 7.81262E-02 MeV : total inelastic scattering + + Nuclide 235 / 1657 : 64160.82c -- gadolinium 160 (Gd-160) + + Pointers : 1896501 24571 + Primary type : Transport + Nuclide ZAI : 641600 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Gd160.ACE + Atomic weight (AW) : 159.92686 + Atomic weight ratio (AWR) : 158.55300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 4.10E+24 seconds (1.3E+17 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 13 reaction channels + - 6 special reactions + - 5 transmutation reactions + - 4 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 13 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -7.53000E-02 MeV Emin = 7.11702E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -2.48000E-01 MeV Emin = 2.24780E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -5.13000E-01 MeV Emin = 4.52500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -8.70000E-01 MeV Emin = 1.40000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -1.01000E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -1.19000E+00 MeV Emin = 1.10695E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 91 Q = -1.19000E+00 MeV Emin = 1.40000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 9 MT = 102 Q = 5.63300E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 641610 : (n,gamma) + 10 MT = 103 Q = -3.61910E+00 MeV Emin = 3.64193E+00 MeV frac = 1.00000E+00 Product nuclide = 631600 : (n,p) + 11 MT = 104 Q = -7.07480E+00 MeV Emin = 7.11942E+00 MeV frac = 1.00000E+00 Product nuclide = 631590 : (n,d) + 12 MT = 105 Q = -7.57840E+00 MeV Emin = 7.62620E+00 MeV frac = 1.00000E+00 Product nuclide = 631580 : (n,t) + 13 MT = 107 Q = 4.56190E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 621570 : (n,alpha) + + 4 additional transport branches: + + 1 MT = 103 Q = -3.61910E+00 MeV Emin = 3.64193E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -7.07480E+00 MeV Emin = 7.11942E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -7.57840E+00 MeV Emin = 7.62620E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 107 Q = 4.56190E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.64193E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.11942E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 7.62620E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 7.11702E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 11 Q = 1.72950E+00 MeV frac = 1.00000E+00 Product nuclide = 66160.82c : beta- + beta- + + Nuclide 236 / 1657 : 65159.82c -- terbium 159 (Tb-159) + + Pointers : 1911567 34323 + Primary type : Transport + Nuclide ZAI : 651590 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Tb159.ACE + Atomic weight (AW) : 158.92525 + Atomic weight ratio (AWR) : 157.56000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 35 reaction channels + - 6 special reactions + - 11 transmutation reactions + - 8 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 35 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.13710E+00 MeV Emin = 8.18875E+00 MeV frac = 1.00000E+00 Product nuclide = 651580 : (n,2n) + 3 MT = 17 Q = -1.49212E+01 MeV Emin = 1.50159E+01 MeV frac = 1.00000E+00 Product nuclide = 651570 : (n,3n) + 4 MT = 22 Q = -1.32906E-01 MeV Emin = 3.37581E-01 MeV frac = 1.00000E+00 Product nuclide = 63155.82c : (n,nalpha) + 5 MT = 28 Q = -6.13864E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 64158.82c : (n,np) + 6 MT = 32 Q = -1.17706E+01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 64157.82c : (n,nd) + 7 MT = 33 Q = -1.19506E+01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 64156.82c : (n,nt) + 8 MT = 51 Q = -5.79999E-02 MeV Emin = 5.41840E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -1.37500E-01 MeV Emin = 1.33750E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -2.41400E-01 MeV Emin = 2.32199E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -3.47900E-01 MeV Emin = 3.37581E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -3.62599E-01 MeV Emin = 3.59354E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -3.63699E-01 MeV Emin = 3.65731E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -3.89499E-01 MeV Emin = 3.86292E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -4.28999E-01 MeV Emin = 4.23792E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -4.55199E-01 MeV Emin = 4.52321E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -5.10599E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -5.33999E-01 MeV Emin = 5.28559E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 62 Q = -5.45699E-01 MeV Emin = 5.43276E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 20 MT = 63 Q = -5.48299E-01 MeV Emin = 5.50843E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 21 MT = 64 Q = -5.80899E-01 MeV Emin = 5.76385E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 22 MT = 65 Q = -6.17699E-01 MeV Emin = 6.13519E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 23 MT = 66 Q = -6.68999E-01 MeV Emin = 6.62692E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 24 MT = 67 Q = -6.74299E-01 MeV Emin = 6.73246E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 25 MT = 68 Q = -6.78699E-01 MeV Emin = 6.80794E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 26 MT = 69 Q = -7.61299E-01 MeV Emin = 7.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 27 MT = 70 Q = -7.77999E-01 MeV Emin = 7.74535E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 28 MT = 71 Q = -8.22999E-01 MeV Emin = 8.14111E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 29 MT = 72 Q = -8.54999E-01 MeV Emin = 8.48351E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 30 MT = 91 Q = -8.59999E-01 MeV Emin = 8.62942E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 31 MT = 102 Q = 6.37521E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 65160.82c : (n,gamma) + 32 MT = 103 Q = -1.91535E-01 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 641590 : (n,p) + 33 MT = 104 Q = -3.82852E+00 MeV Emin = 5.62092E+00 MeV frac = 1.00000E+00 Product nuclide = 64158.82c : (n,d) + 34 MT = 105 Q = -5.58546E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 64157.82c : (n,t) + 35 MT = 107 Q = 6.20119E+00 MeV Emin = 9.99463E-02 MeV frac = 1.00000E+00 Product nuclide = 63156.82c : (n,alpha) + + 8 additional transport branches: + + 1 MT = 22 Q = -1.32906E-01 MeV Emin = 3.37581E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -6.13864E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.17706E+01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.19506E+01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 103 Q = -1.91535E-01 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 104 Q = -3.82852E+00 MeV Emin = 5.62092E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 7 MT = 105 Q = -5.58546E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 8 MT = 107 Q = 6.20119E+00 MeV Emin = 9.99463E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.62092E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 7.00000E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 9.99463E-02 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 9.41508E-04 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 5.41840E-02 MeV : total inelastic scattering + + Nuclide 237 / 1657 : 65160.82c -- terbium 160 (Tb-160) + + Pointers : 1915255 34369 + Primary type : Transport + Nuclide ZAI : 651600 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Tb160.ACE + Atomic weight (AW) : 159.92686 + Atomic weight ratio (AWR) : 158.55300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 6.25E+06 seconds (72.3 days) + Specific ingestion toxicity : 1.60E-09 Sv/Bq + Specific inhalation toxicity : 7.00E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 3 reaction channels + - 2 special reactions + - 1 transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 91 Q = -9.93740E-02 MeV Emin = 9.68750E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 3 MT = 102 Q = 7.85000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 651610 : (n,gamma) + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 9.68750E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.83510E+00 MeV frac = 1.00000E+00 Product nuclide = 66160.82c : beta- + + Nuclide 238 / 1657 : 66160.82c -- dysprosium 160 (Dy-160) + + Pointers : 1930622 23007 + Primary type : Transport + Nuclide ZAI : 661600 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Dy160.ACE + Atomic weight (AW) : 159.92484 + Atomic weight ratio (AWR) : 158.55100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 17 reaction channels + - 2 special reactions + - 1 transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 17 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -8.68000E-02 MeV Emin = 7.80103E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -2.84000E-01 MeV Emin = 2.64342E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -6.95620E-01 MeV Emin = 6.17500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -9.66000E-01 MeV Emin = 8.36049E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -1.05000E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -1.16000E+00 MeV Emin = 1.11196E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 57 Q = -1.26000E+00 MeV Emin = 1.21761E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 9 MT = 58 Q = -1.29000E+00 MeV Emin = 1.28302E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 10 MT = 59 Q = -1.29001E+00 MeV Emin = 1.28302E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 11 MT = 60 Q = -1.36000E+00 MeV Emin = 1.33337E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 12 MT = 61 Q = -1.39000E+00 MeV Emin = 1.38370E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 13 MT = 62 Q = -1.40000E+00 MeV Emin = 1.40380E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 14 MT = 63 Q = -1.59000E+00 MeV Emin = 1.52500E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 15 MT = 64 Q = -1.49060E+01 MeV Emin = 1.75000E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 16 MT = 91 Q = -1.59000E+00 MeV Emin = 1.52500E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 17 MT = 102 Q = 6.45110E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 66161.82c : (n,gamma) + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 7.80103E-02 MeV : total inelastic scattering + + Nuclide 239 / 1657 : 66161.82c -- dysprosium 161 (Dy-161) + + Pointers : 1932120 23053 + Primary type : Transport + Nuclide ZAI : 661610 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Dy161.ACE + Atomic weight (AW) : 160.92644 + Atomic weight ratio (AWR) : 159.54400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 30 reaction channels + - 38 special reactions + - 9 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 30 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.45400E+00 MeV Emin = 6.49445E+00 MeV frac = 1.00000E+00 Product nuclide = 66160.82c : (n,2n) + 3 MT = 17 Q = -1.50300E+01 MeV Emin = 1.51242E+01 MeV frac = 1.00000E+00 Product nuclide = 661590 : (n,3n) + 4 MT = 22 Q = 3.44000E-01 MeV Emin = 6.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 64157.82c : (n,nalpha) + 5 MT = 24 Q = -6.01600E+00 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 64156.82c : (n,2nalpha) + 6 MT = 28 Q = -7.50800E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 65160.82c : (n,np) + 7 MT = 41 Q = -1.38830E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 65159.82c : (n,2np) + 8 MT = 51 Q = -2.56500E-02 MeV Emin = 2.25000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -4.38200E-02 MeV Emin = 4.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -7.45700E-02 MeV Emin = 7.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -1.00400E-01 MeV Emin = 1.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -1.03060E-01 MeV Emin = 1.02368E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -1.31760E-01 MeV Emin = 1.20000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -1.84230E-01 MeV Emin = 1.67692E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -2.01090E-01 MeV Emin = 2.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -2.12950E-01 MeV Emin = 2.08318E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -2.67440E-01 MeV Emin = 2.41701E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -3.14940E-01 MeV Emin = 3.11943E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 62 Q = -3.20690E-01 MeV Emin = 3.19807E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 20 MT = 63 Q = -3.66970E-01 MeV Emin = 3.50166E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 21 MT = 64 Q = -4.06990E-01 MeV Emin = 4.04770E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 22 MT = 65 Q = -4.18240E-01 MeV Emin = 4.16595E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 23 MT = 66 Q = -4.43400E-01 MeV Emin = 4.33520E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 24 MT = 67 Q = -4.51430E-01 MeV Emin = 4.51814E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 25 MT = 68 Q = -4.57230E-01 MeV Emin = 4.57178E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 26 MT = 69 Q = -4.85560E-01 MeV Emin = 4.74349E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 27 MT = 91 Q = -2.95150E-01 MeV Emin = 2.92955E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 28 MT = 102 Q = 8.19700E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 66162.82c : (n,gamma) + 29 MT = 103 Q = 0.00000E+00 MeV Emin = 1.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 651610 : (n,p) + 30 MT = 107 Q = 0.00000E+00 MeV Emin = 1.75000E-02 MeV frac = 1.00000E+00 Product nuclide = 64158.82c : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = 3.44000E-01 MeV Emin = 6.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 24 Q = -6.01600E+00 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,2nalpha) + 3 MT = 28 Q = -7.50800E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 4 MT = 41 Q = -1.38830E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,2np) + 5 MT = 103 Q = 0.00000E+00 MeV Emin = 1.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 107 Q = 0.00000E+00 MeV Emin = 1.75000E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 38 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.60000E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 1.75000E-02 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 9.74491E-04 MeV : damage-energy production + 4 MT = 600 Q = 1.89000E-01 MeV Emin = 1.60000E+00 MeV : (n,p) to ground state + 5 MT = 601 Q = 1.32710E-01 MeV Emin = 1.60000E+00 MeV : (n,p1) + 6 MT = 602 Q = 5.53200E-02 MeV Emin = 1.70000E+00 MeV : (n,p2) + 7 MT = 603 Q = -4.17200E-02 MeV Emin = 1.80000E+00 MeV : (n,p3) + 8 MT = 604 Q = -1.25910E-01 MeV Emin = 1.90000E+00 MeV : (n,p4) + 9 MT = 605 Q = -2.05370E-01 MeV Emin = 2.00000E+00 MeV : (n,p5) + 10 MT = 606 Q = -2.28230E-01 MeV Emin = 2.00000E+00 MeV : (n,p6) + 11 MT = 607 Q = -2.91130E-01 MeV Emin = 2.00000E+00 MeV : (n,p7) + 12 MT = 608 Q = -2.99790E-01 MeV Emin = 2.00000E+00 MeV : (n,p8) + 13 MT = 609 Q = -3.10000E-01 MeV Emin = 2.00000E+00 MeV : (n,p9) + 14 MT = 610 Q = -3.29000E-01 MeV Emin = 2.00000E+00 MeV : (n,p10) + 15 MT = 611 Q = -3.69000E-01 MeV Emin = 2.00000E+00 MeV : (n,p11) + 16 MT = 612 Q = -3.95000E-01 MeV Emin = 2.00000E+00 MeV : (n,p12) + 17 MT = 613 Q = -3.96770E-01 MeV Emin = 2.00000E+00 MeV : (n,p13) + 18 MT = 614 Q = -4.14000E-01 MeV Emin = 2.00000E+00 MeV : (n,p14) + 19 MT = 615 Q = -4.49000E-01 MeV Emin = 2.00000E+00 MeV : (n,p15) + 20 MT = 616 Q = -5.09000E-01 MeV Emin = 2.00000E+00 MeV : (n,p16) + 21 MT = 649 Q = -5.09000E-01 MeV Emin = 2.00000E+00 MeV : (n,p) to continuum + 22 MT = 800 Q = 8.28100E+00 MeV Emin = 1.75000E-02 MeV : (n,alpha) to ground state + 23 MT = 801 Q = 8.20149E+00 MeV Emin = 1.75000E-02 MeV : (n,a1) + 24 MT = 802 Q = 8.01956E+00 MeV Emin = 1.75000E-02 MeV : (n,a2) + 25 MT = 803 Q = 7.74202E+00 MeV Emin = 1.75000E-02 MeV : (n,a3) + 26 MT = 804 Q = 7.37660E+00 MeV Emin = 4.00000E-02 MeV : (n,a4) + 27 MT = 805 Q = 7.30391E+00 MeV Emin = 1.75000E-02 MeV : (n,a5) + 28 MT = 806 Q = 7.25735E+00 MeV Emin = 1.75000E-02 MeV : (n,a6) + 29 MT = 807 Q = 7.23941E+00 MeV Emin = 1.75000E-02 MeV : (n,a7) + 30 MT = 808 Q = 7.12208E+00 MeV Emin = 1.75000E-02 MeV : (n,a8) + 31 MT = 809 Q = 7.10457E+00 MeV Emin = 1.75000E-02 MeV : (n,a9) + 32 MT = 810 Q = 7.09390E+00 MeV Emin = 1.75000E-02 MeV : (n,a10) + 33 MT = 811 Q = 7.08490E+00 MeV Emin = 1.75000E-02 MeV : (n,a11) + 34 MT = 812 Q = 7.02119E+00 MeV Emin = 1.75000E-02 MeV : (n,a12) + 35 MT = 813 Q = 7.01754E+00 MeV Emin = 1.75000E-02 MeV : (n,a13) + 36 MT = 814 Q = 7.01552E+00 MeV Emin = 1.75000E-02 MeV : (n,a14) + 37 MT = 849 Q = 7.01552E+00 MeV Emin = 1.75000E-02 MeV : (n,alpha) to continuum + 38 MT = 4 Q = 0.00000E+00 MeV Emin = 2.25000E-02 MeV : total inelastic scattering + + Nuclide 240 / 1657 : 66162.82c -- dysprosium 162 (Dy-162) + + Pointers : 1937633 23099 + Primary type : Transport + Nuclide ZAI : 661620 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Dy162.ACE + Atomic weight (AW) : 161.92704 + Atomic weight ratio (AWR) : 160.53600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 43 reaction channels + - 23 special reactions + - 9 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 43 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.19600E+00 MeV Emin = 8.24705E+00 MeV frac = 1.00000E+00 Product nuclide = 66161.82c : (n,2n) + 3 MT = 17 Q = -1.46500E+01 MeV Emin = 1.47413E+01 MeV frac = 1.00000E+00 Product nuclide = 66160.82c : (n,3n) + 4 MT = 22 Q = 8.50000E-02 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 64158.82c : (n,nalpha) + 5 MT = 24 Q = -7.85200E+00 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 64157.82c : (n,2nalpha) + 6 MT = 28 Q = -8.00700E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 651610 : (n,np) + 7 MT = 41 Q = -1.57040E+01 MeV Emin = 1.70000E+01 MeV frac = 1.00000E+00 Product nuclide = 65160.82c : (n,2np) + 8 MT = 51 Q = -8.06600E-02 MeV Emin = 7.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -2.65660E-01 MeV Emin = 2.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -5.48530E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -8.88190E-01 MeV Emin = 8.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -9.20990E-01 MeV Emin = 9.13363E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -9.62970E-01 MeV Emin = 9.47848E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -1.06102E+00 MeV Emin = 1.05000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -1.14826E+00 MeV Emin = 1.12770E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -1.18279E+00 MeV Emin = 1.17279E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -1.21012E+00 MeV Emin = 1.20000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -1.27610E+00 MeV Emin = 1.27941E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 62 Q = -1.29704E+00 MeV Emin = 1.30000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 20 MT = 63 Q = -1.32443E+00 MeV Emin = 1.31890E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 21 MT = 64 Q = -1.35777E+00 MeV Emin = 1.34946E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 22 MT = 65 Q = -1.37491E+00 MeV Emin = 1.37485E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 23 MT = 66 Q = -1.39069E+00 MeV Emin = 1.39141E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 24 MT = 67 Q = -1.40014E+00 MeV Emin = 1.40443E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 25 MT = 68 Q = -1.40833E+00 MeV Emin = 1.41298E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 26 MT = 69 Q = -1.45344E+00 MeV Emin = 1.43980E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 27 MT = 70 Q = -1.48571E+00 MeV Emin = 1.47873E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 28 MT = 71 Q = -1.49027E+00 MeV Emin = 1.49726E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 29 MT = 72 Q = -1.51880E+00 MeV Emin = 1.51413E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 30 MT = 73 Q = -1.53017E+00 MeV Emin = 1.53398E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 31 MT = 74 Q = -1.53586E+00 MeV Emin = 1.54257E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 32 MT = 75 Q = -1.57120E+00 MeV Emin = 1.56321E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 33 MT = 76 Q = -1.57410E+00 MeV Emin = 1.58245E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 34 MT = 77 Q = -1.57611E+00 MeV Emin = 1.58492E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 27. excited state + 35 MT = 78 Q = -1.63461E+00 MeV Emin = 1.62240E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 28. excited state + 36 MT = 79 Q = -1.63710E+00 MeV Emin = 1.64605E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 29. excited state + 37 MT = 80 Q = -1.63774E+00 MeV Emin = 1.64763E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 30. excited state + 38 MT = 81 Q = -1.63841E+00 MeV Emin = 1.64796E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 31. excited state + 39 MT = 82 Q = -1.66492E+00 MeV Emin = 1.66196E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 32. excited state + 40 MT = 91 Q = -3.93549E-01 MeV Emin = 3.48000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 41 MT = 102 Q = 6.27101E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 66163.82c : (n,gamma) + 42 MT = 103 Q = 0.00000E+00 MeV Emin = 3.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 651620 : (n,p) + 43 MT = 107 Q = 0.00000E+00 MeV Emin = 7.50000E-01 MeV frac = 1.00000E+00 Product nuclide = 641590 : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = 8.50000E-02 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 24 Q = -7.85200E+00 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,2nalpha) + 3 MT = 28 Q = -8.00700E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 4 MT = 41 Q = -1.57040E+01 MeV Emin = 1.70000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,2np) + 5 MT = 103 Q = 0.00000E+00 MeV Emin = 3.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 107 Q = 0.00000E+00 MeV Emin = 7.50000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 23 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.50000E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 7.50000E-01 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 9.73504E-04 MeV : damage-energy production + 4 MT = 600 Q = -1.72400E+00 MeV Emin = 3.50000E+00 MeV : (n,p) to ground state + 5 MT = 601 Q = -1.76310E+00 MeV Emin = 3.50000E+00 MeV : (n,p1) + 6 MT = 602 Q = -1.82100E+00 MeV Emin = 3.50000E+00 MeV : (n,p2) + 7 MT = 603 Q = -1.90000E+00 MeV Emin = 3.50000E+00 MeV : (n,p3) + 8 MT = 604 Q = -1.94000E+00 MeV Emin = 3.50000E+00 MeV : (n,p4) + 9 MT = 605 Q = -1.99100E+00 MeV Emin = 3.50000E+00 MeV : (n,p5) + 10 MT = 606 Q = -2.03400E+00 MeV Emin = 3.50000E+00 MeV : (n,p6) + 11 MT = 649 Q = -2.03400E+00 MeV Emin = 3.50000E+00 MeV : (n,p) to continuum + 12 MT = 800 Q = 6.02800E+00 MeV Emin = 7.50000E-01 MeV : (n,alpha) to ground state + 13 MT = 801 Q = 5.97734E+00 MeV Emin = 7.50000E-01 MeV : (n,a1) + 14 MT = 802 Q = 5.96021E+00 MeV Emin = 7.50000E-01 MeV : (n,a2) + 15 MT = 803 Q = 5.90908E+00 MeV Emin = 8.96861E-01 MeV : (n,a3) + 16 MT = 804 Q = 5.90607E+00 MeV Emin = 8.96861E-01 MeV : (n,a4) + 17 MT = 805 Q = 5.88161E+00 MeV Emin = 9.84484E-01 MeV : (n,a5) + 18 MT = 806 Q = 5.84260E+00 MeV Emin = 9.84484E-01 MeV : (n,a6) + 19 MT = 807 Q = 5.81570E+00 MeV Emin = 1.00000E+00 MeV : (n,a7) + 20 MT = 808 Q = 5.80051E+00 MeV Emin = 9.84484E-01 MeV : (n,a8) + 21 MT = 809 Q = 5.75500E+00 MeV Emin = 1.00000E+00 MeV : (n,a9) + 22 MT = 849 Q = 5.75500E+00 MeV Emin = 1.08750E+00 MeV : (n,alpha) to continuum + 23 MT = 4 Q = 0.00000E+00 MeV Emin = 7.00000E-02 MeV : total inelastic scattering + + Nuclide 241 / 1657 : 66163.82c -- dysprosium 163 (Dy-163) + + Pointers : 1943000 23145 + Primary type : Transport + Nuclide ZAI : 661630 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Dy163.ACE + Atomic weight (AW) : 162.92864 + Atomic weight ratio (AWR) : 161.52900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 37 reaction channels + - 30 special reactions + - 9 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 37 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.27100E+00 MeV Emin = 6.30982E+00 MeV frac = 1.00000E+00 Product nuclide = 66162.82c : (n,2n) + 3 MT = 17 Q = -1.44670E+01 MeV Emin = 1.45566E+01 MeV frac = 1.00000E+00 Product nuclide = 66161.82c : (n,3n) + 4 MT = 22 Q = -2.43000E-01 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 641590 : (n,nalpha) + 5 MT = 24 Q = -6.18600E+00 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 64158.82c : (n,2nalpha) + 6 MT = 28 Q = -7.99500E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 651620 : (n,np) + 7 MT = 41 Q = -1.42780E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 651610 : (n,2np) + 8 MT = 51 Q = -7.34400E-02 MeV Emin = 6.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -1.67340E-01 MeV Emin = 1.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -2.50880E-01 MeV Emin = 2.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -2.81560E-01 MeV Emin = 2.67868E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -2.85580E-01 MeV Emin = 2.85326E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -3.36540E-01 MeV Emin = 3.19312E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -3.51140E-01 MeV Emin = 3.52006E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -3.89740E-01 MeV Emin = 3.78771E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -4.12390E-01 MeV Emin = 4.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -4.15240E-01 MeV Emin = 4.16377E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -4.21830E-01 MeV Emin = 4.21126E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 62 Q = -4.27670E-01 MeV Emin = 4.27380E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 20 MT = 63 Q = -4.50000E-01 MeV Emin = 4.41552E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 21 MT = 64 Q = -4.62580E-01 MeV Emin = 4.59115E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 22 MT = 65 Q = -4.75380E-01 MeV Emin = 4.71884E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 23 MT = 66 Q = -4.97000E-01 MeV Emin = 4.89162E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 24 MT = 67 Q = -5.14540E-01 MeV Emin = 5.08901E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 25 MT = 68 Q = -5.14600E-01 MeV Emin = 5.08901E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 26 MT = 69 Q = -5.53010E-01 MeV Emin = 5.37110E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 27 MT = 70 Q = -5.68710E-01 MeV Emin = 5.64333E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 28 MT = 71 Q = -5.73990E-01 MeV Emin = 5.74887E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 29 MT = 72 Q = -5.91000E-01 MeV Emin = 5.86102E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 30 MT = 73 Q = -6.12000E-01 MeV Emin = 6.07895E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 31 MT = 74 Q = -6.17300E-01 MeV Emin = 6.18455E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 32 MT = 75 Q = -6.45000E-01 MeV Emin = 6.35058E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 33 MT = 76 Q = -6.51000E-01 MeV Emin = 6.52012E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 34 MT = 91 Q = -2.95173E-01 MeV Emin = 2.92174E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 35 MT = 102 Q = 7.65812E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 66164.82c : (n,gamma) + 36 MT = 103 Q = 0.00000E+00 MeV Emin = 2.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 651630 : (n,p) + 37 MT = 107 Q = 0.00000E+00 MeV Emin = 1.70000E-02 MeV frac = 1.00000E+00 Product nuclide = 64160.82c : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = -2.43000E-01 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 24 Q = -6.18600E+00 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,2nalpha) + 3 MT = 28 Q = -7.99500E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 4 MT = 41 Q = -1.42780E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,2np) + 5 MT = 103 Q = 0.00000E+00 MeV Emin = 2.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 107 Q = 0.00000E+00 MeV Emin = 1.70000E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 30 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.50000E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 1.70000E-02 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 9.74487E-04 MeV : damage-energy production + 4 MT = 600 Q = -1.00300E+00 MeV Emin = 2.50000E+00 MeV : (n,p) to ground state + 5 MT = 601 Q = -1.06000E+00 MeV Emin = 2.50000E+00 MeV : (n,p1) + 6 MT = 602 Q = -1.12500E+00 MeV Emin = 2.50000E+00 MeV : (n,p2) + 7 MT = 603 Q = -1.23800E+00 MeV Emin = 3.00000E+00 MeV : (n,p3) + 8 MT = 604 Q = -1.34600E+00 MeV Emin = 3.00000E+00 MeV : (n,p4) + 9 MT = 605 Q = -1.39940E+00 MeV Emin = 3.00000E+00 MeV : (n,p5) + 10 MT = 606 Q = -1.44000E+00 MeV Emin = 3.00000E+00 MeV : (n,p6) + 11 MT = 607 Q = -1.46800E+00 MeV Emin = 3.00000E+00 MeV : (n,p7) + 12 MT = 608 Q = -1.54000E+00 MeV Emin = 3.00000E+00 MeV : (n,p8) + 13 MT = 609 Q = -1.57810E+00 MeV Emin = 3.00000E+00 MeV : (n,p9) + 14 MT = 610 Q = -1.67700E+00 MeV Emin = 3.00000E+00 MeV : (n,p10) + 15 MT = 611 Q = -1.67700E+00 MeV Emin = 3.00000E+00 MeV : (n,p11) + 16 MT = 612 Q = -1.71200E+00 MeV Emin = 3.50000E+00 MeV : (n,p12) + 17 MT = 649 Q = -1.71200E+00 MeV Emin = 3.50000E+00 MeV : (n,p) to continuum + 18 MT = 800 Q = 7.20800E+00 MeV Emin = 1.70000E-02 MeV : (n,alpha) to ground state + 19 MT = 801 Q = 7.13274E+00 MeV Emin = 1.70000E-02 MeV : (n,a1) + 20 MT = 802 Q = 6.95948E+00 MeV Emin = 1.70000E-02 MeV : (n,a2) + 21 MT = 803 Q = 6.69325E+00 MeV Emin = 1.20000E-01 MeV : (n,a3) + 22 MT = 804 Q = 6.34010E+00 MeV Emin = 4.00000E-01 MeV : (n,a4) + 23 MT = 805 Q = 6.29500E+00 MeV Emin = 4.89162E-01 MeV : (n,a5) + 24 MT = 806 Q = 6.26200E+00 MeV Emin = 5.97329E-01 MeV : (n,a6) + 25 MT = 807 Q = 6.21960E+00 MeV Emin = 5.97329E-01 MeV : (n,a7) + 26 MT = 808 Q = 6.19200E+00 MeV Emin = 6.00000E-01 MeV : (n,a8) + 27 MT = 809 Q = 6.15046E+00 MeV Emin = 6.00000E-01 MeV : (n,a9) + 28 MT = 810 Q = 6.13758E+00 MeV Emin = 6.99989E-01 MeV : (n,a10) + 29 MT = 849 Q = 6.13758E+00 MeV Emin = 1.70000E-02 MeV : (n,alpha) to continuum + 30 MT = 4 Q = 0.00000E+00 MeV Emin = 6.00000E-02 MeV : total inelastic scattering + + Nuclide 242 / 1657 : 66164.82c -- dysprosium 164 (Dy-164) + + Pointers : 1948440 23191 + Primary type : Transport + Nuclide ZAI : 661640 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Dy164.ACE + Atomic weight (AW) : 163.92823 + Atomic weight ratio (AWR) : 162.52000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 19 reaction channels + - 4 special reactions + - 5 transmutation reactions + - 3 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 19 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.64000E+00 MeV Emin = 7.68701E+00 MeV frac = 1.00000E+00 Product nuclide = 66163.82c : (n,2n) + 3 MT = 17 Q = -1.38950E+01 MeV Emin = 1.39805E+01 MeV frac = 1.00000E+00 Product nuclide = 66162.82c : (n,3n) + 4 MT = 51 Q = -7.33900E-02 MeV Emin = 7.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 5 MT = 52 Q = -2.42200E-01 MeV Emin = 2.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 6 MT = 53 Q = -5.01300E-01 MeV Emin = 7.83250E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 7 MT = 54 Q = -7.61800E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 8 MT = 55 Q = -8.28200E-01 MeV Emin = 8.31250E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 9 MT = 56 Q = -8.39000E-01 MeV Emin = 8.43750E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 10 MT = 57 Q = -9.16000E-01 MeV Emin = 9.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 11 MT = 58 Q = -9.76900E-01 MeV Emin = 9.52268E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 12 MT = 59 Q = -1.02500E+00 MeV Emin = 1.03100E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 13 MT = 60 Q = -1.03900E+00 MeV Emin = 1.04500E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 14 MT = 61 Q = -1.12300E+00 MeV Emin = 1.10000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 15 MT = 62 Q = -1.15700E+00 MeV Emin = 1.16393E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 16 MT = 91 Q = -1.98800E+00 MeV Emin = 2.00023E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 17 MT = 102 Q = 5.63440E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 661650 : (n,gamma) + 18 MT = 103 Q = -2.98200E+00 MeV Emin = 3.00035E+00 MeV frac = 1.00000E+00 Product nuclide = 651640 : (n,p) + 19 MT = 107 Q = 5.19000E+00 MeV Emin = 1.40000E+00 MeV frac = 1.00000E+00 Product nuclide = 641610 : (n,alpha) + + 3 additional transport branches: + + 1 MT = 102 Q = 5.63440E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 661651 : (n,gamma) + 2 MT = 103 Q = -2.98200E+00 MeV Emin = 3.00035E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 107 Q = 5.19000E+00 MeV Emin = 1.40000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 4 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.00035E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 1.40000E+00 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 4 MT = 4 Q = 0.00000E+00 MeV Emin = 7.00000E-02 MeV : total inelastic scattering + + Nuclide 243 / 1657 : 67165.82c -- holmium 165 (Ho-165) + + Pointers : 1965977 26181 + Primary type : Transport + Nuclide ZAI : 671650 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ho165.ACE + Atomic weight (AW) : 164.92983 + Atomic weight ratio (AWR) : 163.51300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 3.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 19 reaction channels + - 2 special reactions + - 3 transmutation reactions + - 1 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 19 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.03040E+00 MeV Emin = 8.07951E+00 MeV frac = 1.00000E+00 Product nuclide = 671640 : (n,2n) + 3 MT = 17 Q = -1.46600E+01 MeV Emin = 1.47500E+01 MeV frac = 1.00000E+00 Product nuclide = 671630 : (n,3n) + 4 MT = 37 Q = -2.30630E+01 MeV Emin = 2.32041E+01 MeV frac = 1.00000E+00 Product nuclide = cut: Ho-162 : (n,4n) + 5 MT = 51 Q = -9.47000E-02 MeV Emin = 8.76395E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -2.09800E-01 MeV Emin = 2.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -3.45000E-01 MeV Emin = 3.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -3.61700E-01 MeV Emin = 3.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -4.19500E-01 MeV Emin = 4.21875E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -4.29400E-01 MeV Emin = 4.31250E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -4.49200E-01 MeV Emin = 4.51562E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -4.91000E-01 MeV Emin = 4.75000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -4.99200E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -5.15500E-01 MeV Emin = 5.10452E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -5.39000E-01 MeV Emin = 5.30476E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -5.66800E-01 MeV Emin = 5.68750E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 63 Q = -5.89800E-01 MeV Emin = 5.92969E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 18 MT = 91 Q = -5.89800E-01 MeV Emin = 5.92969E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 19 MT = 102 Q = 6.24240E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 671660 : (n,gamma) + + 1 additional transport branch: + + 1 MT = 102 Q = 6.24240E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 671661 : (n,gamma) + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 8.76395E-02 MeV : total inelastic scattering + + Nuclide 244 / 1657 : 68164.82c -- erbium 164 (Er-164) + + Pointers : 1984341 23283 + Primary type : Transport + Nuclide ZAI : 681640 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Er164.ACE + Atomic weight (AW) : 163.92924 + Atomic weight ratio (AWR) : 162.52100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 27 reaction channels + - 6 special reactions + - 9 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 27 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.84637E+00 MeV Emin = 8.90080E+00 MeV frac = 1.00000E+00 Product nuclide = 681630 : (n,2n) + 3 MT = 17 Q = -1.57477E+01 MeV Emin = 1.58446E+01 MeV frac = 1.00000E+00 Product nuclide = 681620 : (n,3n) + 4 MT = 22 Q = 1.30691E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 66160.82c : (n,nalpha) + 5 MT = 28 Q = -6.85403E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 671630 : (n,np) + 6 MT = 51 Q = -9.13900E-02 MeV Emin = 9.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -2.99470E-01 MeV Emin = 3.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -6.14400E-01 MeV Emin = 6.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -8.60310E-01 MeV Emin = 8.32802E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -9.46350E-01 MeV Emin = 9.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -1.02460E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -1.05830E+00 MeV Emin = 1.04786E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -1.19750E+00 MeV Emin = 1.20000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -1.24600E+00 MeV Emin = 1.24539E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -1.31460E+00 MeV Emin = 1.28591E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -1.35860E+00 MeV Emin = 1.34670E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -1.38680E+00 MeV Emin = 1.38115E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -1.41660E+00 MeV Emin = 1.42141E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -1.43400E+00 MeV Emin = 1.43212E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -1.46990E+00 MeV Emin = 1.46088E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 21 MT = 66 Q = -1.48390E+00 MeV Emin = 1.48599E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 22 MT = 91 Q = -1.50000E+00 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 23 MT = 102 Q = 6.64970E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 681650 : (n,gamma) + 24 MT = 103 Q = -2.30661E-01 MeV Emin = 1.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 671640 : (n,p) + 25 MT = 104 Q = -4.62946E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 671630 : (n,d) + 26 MT = 105 Q = -6.77872E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 671620 : (n,t) + 27 MT = 107 Q = 7.76028E+00 MeV Emin = 1.50000E-01 MeV frac = 1.00000E+00 Product nuclide = 66161.82c : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = 1.30691E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -6.85403E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -2.30661E-01 MeV Emin = 1.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -4.62946E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -6.77872E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 107 Q = 7.76028E+00 MeV Emin = 1.50000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.60000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 8.00000E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 1.50000E-01 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 9.00000E-02 MeV : total inelastic scattering + + Nuclide 245 / 1657 : 68166.82c -- erbium 166 (Er-166) + + Pointers : 1987600 23329 + Primary type : Transport + Nuclide ZAI : 681660 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Er166.ACE + Atomic weight (AW) : 165.93043 + Atomic weight ratio (AWR) : 164.50500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 36 reaction channels + - 6 special reactions + - 10 transmutation reactions + - 8 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 36 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.47537E+00 MeV Emin = 8.52689E+00 MeV frac = 1.00000E+00 Product nuclide = 681650 : (n,2n) + 3 MT = 17 Q = -1.51257E+01 MeV Emin = 1.52177E+01 MeV frac = 1.00000E+00 Product nuclide = 68164.82c : (n,3n) + 4 MT = 22 Q = 8.30908E-01 MeV Emin = 5.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 66162.82c : (n,nalpha) + 5 MT = 28 Q = -7.31603E+00 MeV Emin = 8.75000E+00 MeV frac = 1.00000E+00 Product nuclide = 67165.82c : (n,np) + 6 MT = 32 Q = -1.31318E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 671640 : (n,nd) + 7 MT = 51 Q = -8.05800E-02 MeV Emin = 8.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 8 MT = 52 Q = -2.65000E-01 MeV Emin = 2.60000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 9 MT = 53 Q = -5.45500E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 10 MT = 54 Q = -7.85900E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 11 MT = 55 Q = -8.59400E-01 MeV Emin = 8.32312E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 12 MT = 56 Q = -9.11200E-01 MeV Emin = 9.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 13 MT = 57 Q = -9.56200E-01 MeV Emin = 9.58370E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 14 MT = 58 Q = -1.07530E+00 MeV Emin = 1.07817E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 15 MT = 59 Q = -1.21600E+00 MeV Emin = 1.20000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 16 MT = 60 Q = -1.34960E+00 MeV Emin = 1.30000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 17 MT = 61 Q = -1.37600E+00 MeV Emin = 1.37108E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 18 MT = 62 Q = -1.45820E+00 MeV Emin = 1.43353E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 19 MT = 63 Q = -1.45990E+00 MeV Emin = 1.46792E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 20 MT = 64 Q = -1.51340E+00 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 21 MT = 65 Q = -1.52840E+00 MeV Emin = 1.53015E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 22 MT = 66 Q = -1.55570E+00 MeV Emin = 1.55327E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 23 MT = 67 Q = -1.57220E+00 MeV Emin = 1.56885E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 24 MT = 68 Q = -1.59620E+00 MeV Emin = 1.60000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 25 MT = 69 Q = -1.66240E+00 MeV Emin = 1.63921E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 26 MT = 70 Q = -1.66580E+00 MeV Emin = 1.67422E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 27 MT = 71 Q = -1.67880E+00 MeV Emin = 1.68796E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 28 MT = 72 Q = -1.69230E+00 MeV Emin = 1.70000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 29 MT = 73 Q = -1.70310E+00 MeV Emin = 1.70802E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 30 MT = 74 Q = -1.78700E+00 MeV Emin = 1.75566E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 31 MT = 91 Q = -1.80000E+00 MeV Emin = 1.80547E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 32 MT = 102 Q = 6.43670E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 68167.82c : (n,gamma) + 33 MT = 103 Q = -1.07166E+00 MeV Emin = 2.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 671660 : (n,p) + 34 MT = 104 Q = -5.09146E+00 MeV Emin = 6.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 67165.82c : (n,d) + 35 MT = 105 Q = -6.87372E+00 MeV Emin = 8.75000E+00 MeV frac = 1.00000E+00 Product nuclide = 671640 : (n,t) + 36 MT = 107 Q = 7.10228E+00 MeV Emin = 3.75000E-01 MeV frac = 1.00000E+00 Product nuclide = 66163.82c : (n,alpha) + + 8 additional transport branches: + + 1 MT = 22 Q = 8.30908E-01 MeV Emin = 5.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -7.31603E+00 MeV Emin = 8.75000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.31318E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 102 Q = 6.43670E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 681671 : (n,gamma) + 5 MT = 103 Q = -1.07166E+00 MeV Emin = 2.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 104 Q = -5.09146E+00 MeV Emin = 6.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 7 MT = 105 Q = -6.87372E+00 MeV Emin = 8.75000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 8 MT = 107 Q = 7.10228E+00 MeV Emin = 3.75000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.50000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.50000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 8.75000E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 3.75000E-01 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 8.00000E-02 MeV : total inelastic scattering + + Nuclide 246 / 1657 : 68167.82c -- erbium 167 (Er-167) + + Pointers : 1991380 23375 + Primary type : Transport + Nuclide ZAI : 681670 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Er167.ACE + Atomic weight (AW) : 166.93204 + Atomic weight ratio (AWR) : 165.49800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 35 reaction channels + - 6 special reactions + - 10 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 35 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.43537E+00 MeV Emin = 6.47426E+00 MeV frac = 1.00000E+00 Product nuclide = 68166.82c : (n,2n) + 3 MT = 17 Q = -1.49107E+01 MeV Emin = 1.50008E+01 MeV frac = 1.00000E+00 Product nuclide = 681650 : (n,3n) + 4 MT = 22 Q = 6.66908E-01 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 66163.82c : (n,nalpha) + 5 MT = 28 Q = -7.50703E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 671660 : (n,np) + 6 MT = 32 Q = -1.15268E+01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 67165.82c : (n,nd) + 7 MT = 51 Q = -7.93200E-02 MeV Emin = 7.50000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 8 MT = 52 Q = -1.78000E-01 MeV Emin = 1.70000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 9 MT = 53 Q = -2.07800E-01 MeV Emin = 2.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 10 MT = 54 Q = -2.64900E-01 MeV Emin = 2.60000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 11 MT = 55 Q = -2.81600E-01 MeV Emin = 2.80000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 12 MT = 56 Q = -2.94900E-01 MeV Emin = 2.90000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 13 MT = 57 Q = -3.46600E-01 MeV Emin = 3.36847E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 14 MT = 58 Q = -4.13300E-01 MeV Emin = 4.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 15 MT = 59 Q = -4.30000E-01 MeV Emin = 4.24198E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 16 MT = 60 Q = -4.34400E-01 MeV Emin = 4.34774E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 17 MT = 61 Q = -4.42000E-01 MeV Emin = 4.41299E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 18 MT = 62 Q = -5.31500E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 19 MT = 63 Q = -5.35800E-01 MeV Emin = 5.36874E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 20 MT = 64 Q = -5.73800E-01 MeV Emin = 5.63634E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 21 MT = 65 Q = -5.87400E-01 MeV Emin = 5.84108E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 22 MT = 66 Q = -6.40800E-01 MeV Emin = 6.22336E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 23 MT = 67 Q = -6.45200E-01 MeV Emin = 6.46886E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 24 MT = 68 Q = -6.62400E-01 MeV Emin = 6.58201E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 25 MT = 69 Q = -6.67900E-01 MeV Emin = 6.69169E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 26 MT = 70 Q = -6.83300E-01 MeV Emin = 6.85968E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 27 MT = 71 Q = -7.11000E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 28 MT = 72 Q = -7.11100E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 29 MT = 73 Q = -7.45300E-01 MeV Emin = 7.32600E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 30 MT = 91 Q = -7.50000E-01 MeV Emin = 7.52168E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 31 MT = 102 Q = 7.77070E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 68168.82c : (n,gamma) + 32 MT = 103 Q = -2.24661E-01 MeV Emin = 1.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 671670 : (n,p) + 33 MT = 104 Q = -5.28246E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 671660 : (n,d) + 34 MT = 105 Q = -5.26872E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 67165.82c : (n,t) + 35 MT = 107 Q = 8.32528E+00 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 66164.82c : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = 6.66908E-01 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -7.50703E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.15268E+01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 103 Q = -2.24661E-01 MeV Emin = 1.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -5.28246E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -5.26872E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 107 Q = 8.32528E+00 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.60000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 7.00000E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 1.50000E+00 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 7.50000E-02 MeV : total inelastic scattering + + Nuclide 247 / 1657 : 68168.82c -- erbium 168 (Er-168) + + Pointers : 1995394 23421 + Primary type : Transport + Nuclide ZAI : 681680 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Er168.ACE + Atomic weight (AW) : 167.92960 + Atomic weight ratio (AWR) : 166.48700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 41 reaction channels + - 6 special reactions + - 10 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 41 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.77137E+00 MeV Emin = 7.81805E+00 MeV frac = 1.00000E+00 Product nuclide = 68167.82c : (n,2n) + 3 MT = 17 Q = -1.42067E+01 MeV Emin = 1.42920E+01 MeV frac = 1.00000E+00 Product nuclide = 68166.82c : (n,3n) + 4 MT = 22 Q = 5.53908E-01 MeV Emin = 5.25000E+00 MeV frac = 1.00000E+00 Product nuclide = 66164.82c : (n,nalpha) + 5 MT = 28 Q = -7.99603E+00 MeV Emin = 9.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 671670 : (n,np) + 6 MT = 32 Q = -1.30538E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 671660 : (n,nd) + 7 MT = 51 Q = -7.98000E-02 MeV Emin = 8.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 8 MT = 52 Q = -2.64100E-01 MeV Emin = 2.60000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 9 MT = 53 Q = -5.48700E-01 MeV Emin = 5.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 10 MT = 54 Q = -8.21800E-01 MeV Emin = 8.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 11 MT = 55 Q = -8.95800E-01 MeV Emin = 9.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 12 MT = 56 Q = -9.28300E-01 MeV Emin = 9.25886E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 13 MT = 57 Q = -9.94800E-01 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 14 MT = 58 Q = -1.09400E+00 MeV Emin = 1.10000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 15 MT = 59 Q = -1.11760E+00 MeV Emin = 1.11244E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 16 MT = 60 Q = -1.19300E+00 MeV Emin = 1.16216E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 17 MT = 61 Q = -1.21720E+00 MeV Emin = 1.21234E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 18 MT = 62 Q = -1.26390E+00 MeV Emin = 1.24800E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 19 MT = 63 Q = -1.27630E+00 MeV Emin = 1.27862E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 20 MT = 64 Q = -1.31150E+00 MeV Emin = 1.31676E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 21 MT = 65 Q = -1.35890E+00 MeV Emin = 1.35030E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 22 MT = 66 Q = -1.39680E+00 MeV Emin = 1.40000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 23 MT = 67 Q = -1.40370E+00 MeV Emin = 1.40866E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 24 MT = 68 Q = -1.41110E+00 MeV Emin = 1.41676E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 25 MT = 69 Q = -1.42210E+00 MeV Emin = 1.42601E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 26 MT = 70 Q = -1.43150E+00 MeV Emin = 1.43537E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 27 MT = 71 Q = -1.43300E+00 MeV Emin = 1.44085E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 28 MT = 72 Q = -1.44900E+00 MeV Emin = 1.44965E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 29 MT = 73 Q = -1.49310E+00 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 30 MT = 74 Q = -1.54160E+00 MeV Emin = 1.52646E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 31 MT = 75 Q = -1.54170E+00 MeV Emin = 1.52646E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 32 MT = 76 Q = -1.56950E+00 MeV Emin = 1.56726E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 33 MT = 77 Q = -1.57410E+00 MeV Emin = 1.56726E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 27. excited state + 34 MT = 78 Q = -1.60590E+00 MeV Emin = 1.60000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 28. excited state + 35 MT = 79 Q = -1.61530E+00 MeV Emin = 1.60000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 29. excited state + 36 MT = 91 Q = -1.62000E+00 MeV Emin = 1.62737E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 37 MT = 102 Q = 6.00370E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 681690 : (n,gamma) + 38 MT = 103 Q = -1.93666E+00 MeV Emin = 3.25000E+00 MeV frac = 1.00000E+00 Product nuclide = 671680 : (n,p) + 39 MT = 104 Q = -5.77146E+00 MeV Emin = 7.25000E+00 MeV frac = 1.00000E+00 Product nuclide = 671670 : (n,d) + 40 MT = 105 Q = -6.79572E+00 MeV Emin = 8.75000E+00 MeV frac = 1.00000E+00 Product nuclide = 671660 : (n,t) + 41 MT = 107 Q = 6.27028E+00 MeV Emin = 3.75000E-01 MeV frac = 1.00000E+00 Product nuclide = 661650 : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = 5.53908E-01 MeV Emin = 5.25000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -7.99603E+00 MeV Emin = 9.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.30538E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 103 Q = -1.93666E+00 MeV Emin = 3.25000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -5.77146E+00 MeV Emin = 7.25000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -6.79572E+00 MeV Emin = 8.75000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 107 Q = 6.27028E+00 MeV Emin = 3.75000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.25000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.25000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 8.75000E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 3.75000E-01 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 8.00000E-02 MeV : total inelastic scattering + + Nuclide 248 / 1657 : 68170.82c -- erbium 170 (Er-170) + + Pointers : 1999972 23467 + Primary type : Transport + Nuclide ZAI : 681700 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Er170.ACE + Atomic weight (AW) : 169.93584 + Atomic weight ratio (AWR) : 168.47600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 26 reaction channels + - 6 special reactions + - 10 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 26 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.25837E+00 MeV Emin = 7.30145E+00 MeV frac = 1.00000E+00 Product nuclide = 681690 : (n,2n) + 3 MT = 17 Q = -1.32617E+01 MeV Emin = 1.33407E+01 MeV frac = 1.00000E+00 Product nuclide = 68168.82c : (n,3n) + 4 MT = 22 Q = 5.19080E-02 MeV Emin = 5.75000E+00 MeV frac = 1.00000E+00 Product nuclide = 661660 : (n,nalpha) + 5 MT = 28 Q = -8.60103E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 671690 : (n,np) + 6 MT = 32 Q = -1.29738E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 671680 : (n,nd) + 7 MT = 51 Q = -7.86800E-02 MeV Emin = 7.50000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 8 MT = 52 Q = -2.60200E-01 MeV Emin = 2.60000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 9 MT = 53 Q = -5.40800E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 10 MT = 54 Q = -8.91000E-01 MeV Emin = 8.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 11 MT = 55 Q = -9.12300E-01 MeV Emin = 9.08857E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 12 MT = 56 Q = -9.34000E-01 MeV Emin = 9.38286E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 13 MT = 57 Q = -9.59900E-01 MeV Emin = 9.58858E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 14 MT = 58 Q = -1.01040E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 15 MT = 59 Q = -1.10330E+00 MeV Emin = 1.10000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 16 MT = 60 Q = -1.12720E+00 MeV Emin = 1.12542E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 17 MT = 61 Q = -1.21740E+00 MeV Emin = 1.20000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 18 MT = 62 Q = -1.23620E+00 MeV Emin = 1.23696E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 19 MT = 63 Q = -1.26640E+00 MeV Emin = 1.25544E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 20 MT = 64 Q = -1.26860E+00 MeV Emin = 1.27503E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 21 MT = 91 Q = -1.30000E+00 MeV Emin = 1.30000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 22 MT = 102 Q = 5.68170E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 681710 : (n,gamma) + 23 MT = 103 Q = -3.08566E+00 MeV Emin = 4.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 671700 : (n,p) + 24 MT = 104 Q = -6.37645E+00 MeV Emin = 7.75000E+00 MeV frac = 1.00000E+00 Product nuclide = 671690 : (n,d) + 25 MT = 105 Q = -6.71572E+00 MeV Emin = 8.75000E+00 MeV frac = 1.00000E+00 Product nuclide = 671680 : (n,t) + 26 MT = 107 Q = 5.46928E+00 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 661670 : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = 5.19080E-02 MeV Emin = 5.75000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -8.60103E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.29738E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 103 Q = -3.08566E+00 MeV Emin = 4.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -6.37645E+00 MeV Emin = 7.75000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -6.71572E+00 MeV Emin = 8.75000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 107 Q = 5.46928E+00 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.50000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.75000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 8.75000E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 5.00000E-01 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 7.50000E-02 MeV : total inelastic scattering + + Nuclide 249 / 1657 : 71175.82c -- lutetium 175 (Lu-175) + + Pointers : 2055486 27515 + Primary type : Transport + Nuclide ZAI : 711750 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Lu175.ACE + Atomic weight (AW) : 174.94083 + Atomic weight ratio (AWR) : 173.43800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 15 reaction channels + - 4 special reactions + - 5 transmutation reactions + - 3 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 15 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.81000E+00 MeV Emin = 7.85503E+00 MeV frac = 1.00000E+00 Product nuclide = 711740 : (n,2n) + 3 MT = 17 Q = -1.44200E+01 MeV Emin = 1.45031E+01 MeV frac = 1.00000E+00 Product nuclide = 711730 : (n,3n) + 4 MT = 51 Q = -1.14000E-01 MeV Emin = 1.10000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 5 MT = 52 Q = -2.52000E-01 MeV Emin = 2.52832E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 6 MT = 53 Q = -3.43000E-01 MeV Emin = 3.22500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 7 MT = 54 Q = -3.45000E-01 MeV Emin = 3.46853E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 8 MT = 55 Q = -3.96000E-01 MeV Emin = 3.85000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 9 MT = 56 Q = -4.32000E-01 MeV Emin = 4.17250E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 10 MT = 57 Q = -5.05000E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 11 MT = 58 Q = -7.50000E-01 MeV Emin = 7.48332E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 12 MT = 91 Q = -1.98900E+00 MeV Emin = 2.00047E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 13 MT = 102 Q = 6.19140E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 71176.82c : (n,gamma) + 14 MT = 103 Q = 3.12500E-01 MeV Emin = 2.77250E-01 MeV frac = 1.00000E+00 Product nuclide = 701750 : (n,p) + 15 MT = 107 Q = 7.80000E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 691720 : (n,alpha) + + 3 additional transport branches: + + 1 MT = 102 Q = 6.19140E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 711761 : (n,gamma) + 2 MT = 103 Q = 3.12500E-01 MeV Emin = 2.77250E-01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 107 Q = 7.80000E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 4 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.77250E-01 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 1.10000E+01 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 4 MT = 4 Q = 0.00000E+00 MeV Emin = 1.10000E-01 MeV : total inelastic scattering + + Nuclide 250 / 1657 : 71176.82c -- lutetium 176 (Lu-176) + + Pointers : 2057222 27561 + Primary type : Transport + Nuclide ZAI : 711760 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Lu176.ACE + Atomic weight (AW) : 175.94143 + Atomic weight ratio (AWR) : 174.43000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.19E+18 seconds (37.6 billion years) + Specific ingestion toxicity : 1.80E-09 Sv/Bq + Specific inhalation toxicity : 7.00E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 15 reaction channels + - 4 special reactions + - 5 transmutation reactions + - 3 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 15 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.34000E+00 MeV Emin = 6.37635E+00 MeV frac = 1.00000E+00 Product nuclide = 71175.82c : (n,2n) + 3 MT = 17 Q = -1.41500E+01 MeV Emin = 1.42311E+01 MeV frac = 1.00000E+00 Product nuclide = 711740 : (n,3n) + 4 MT = 51 Q = -1.27000E-01 MeV Emin = 1.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 5 MT = 52 Q = -1.84000E-01 MeV Emin = 1.75000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 6 MT = 53 Q = -2.43000E-01 MeV Emin = 2.22200E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 7 MT = 54 Q = -2.75000E-01 MeV Emin = 2.63300E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 8 MT = 55 Q = -3.88000E-01 MeV Emin = 3.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 9 MT = 56 Q = -4.45000E-01 MeV Emin = 4.47214E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 10 MT = 57 Q = -5.10000E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 11 MT = 58 Q = -6.21000E-01 MeV Emin = 6.24037E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 12 MT = 91 Q = -1.98900E+00 MeV Emin = 2.00040E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 13 MT = 102 Q = 7.07200E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 711770 : (n,gamma) + 14 MT = 103 Q = 7.62500E-01 MeV Emin = 2.90000E-01 MeV frac = 1.00000E+00 Product nuclide = 701760 : (n,p) + 15 MT = 107 Q = 8.49100E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 691730 : (n,alpha) + + 3 additional transport branches: + + 1 MT = 102 Q = 7.07200E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 711771 : (n,gamma) + 2 MT = 103 Q = 7.62500E-01 MeV Emin = 2.90000E-01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 107 Q = 8.49100E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 4 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.90000E-01 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 1.10000E+01 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 4 MT = 4 Q = 0.00000E+00 MeV Emin = 1.25000E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.19020E+00 MeV frac = 1.00000E+00 Product nuclide = 72176.82c : beta- + + Nuclide 251 / 1657 : 72176.82c -- hafnium 176 (Hf-176) + + Pointers : 2069430 25629 + Primary type : Transport + Nuclide ZAI : 721760 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Hf176.ACE + Atomic weight (AW) : 175.94042 + Atomic weight ratio (AWR) : 174.42900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 30 reaction channels + - 4 special reactions + - 5 transmutation reactions + - 2 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 30 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.08868E+00 MeV Emin = 8.13506E+00 MeV frac = 1.00000E+00 Product nuclide = 721750 : (n,2n) + 3 MT = 17 Q = -1.49424E+01 MeV Emin = 1.50281E+01 MeV frac = 1.00000E+00 Product nuclide = 721740 : (n,3n) + 4 MT = 51 Q = -8.82999E-02 MeV Emin = 8.81777E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 5 MT = 52 Q = -2.90200E-01 MeV Emin = 2.70932E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 6 MT = 53 Q = -5.96999E-01 MeV Emin = 6.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 7 MT = 54 Q = -9.97999E-01 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 8 MT = 55 Q = -1.14990E+00 MeV Emin = 1.14800E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 9 MT = 56 Q = -1.22660E+00 MeV Emin = 1.22002E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 10 MT = 57 Q = -1.24770E+00 MeV Emin = 1.25000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 11 MT = 58 Q = -1.29320E+00 MeV Emin = 1.29824E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 12 MT = 59 Q = -1.31330E+00 MeV Emin = 1.32047E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 13 MT = 60 Q = -1.34130E+00 MeV Emin = 1.34425E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 14 MT = 61 Q = -1.37940E+00 MeV Emin = 1.38203E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 15 MT = 62 Q = -1.40460E+00 MeV Emin = 1.40244E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 16 MT = 63 Q = -1.44580E+00 MeV Emin = 1.45348E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 17 MT = 64 Q = -1.57770E+00 MeV Emin = 1.57538E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 18 MT = 65 Q = -1.64340E+00 MeV Emin = 1.64930E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 19 MT = 66 Q = -1.67230E+00 MeV Emin = 1.67007E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 20 MT = 67 Q = -1.70460E+00 MeV Emin = 1.69813E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 21 MT = 68 Q = -1.71020E+00 MeV Emin = 1.71719E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 22 MT = 69 Q = -1.72210E+00 MeV Emin = 1.72599E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 23 MT = 70 Q = -1.76750E+00 MeV Emin = 1.75000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 24 MT = 71 Q = -1.78610E+00 MeV Emin = 1.78699E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 25 MT = 72 Q = -1.79370E+00 MeV Emin = 1.80016E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 26 MT = 73 Q = -1.81900E+00 MeV Emin = 1.82727E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 27 MT = 91 Q = -1.84000E+00 MeV Emin = 1.83891E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 28 MT = 102 Q = 6.38369E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 72177.82c : (n,gamma) + 29 MT = 103 Q = -4.06529E-01 MeV Emin = 1.32990E+00 MeV frac = 1.00000E+00 Product nuclide = 71176.82c : (n,p) + 30 MT = 107 Q = 8.62274E+00 MeV Emin = 4.75000E-01 MeV frac = 1.00000E+00 Product nuclide = 701730 : (n,alpha) + + 2 additional transport branches: + + 1 MT = 103 Q = -4.06529E-01 MeV Emin = 1.32990E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 107 Q = 8.62274E+00 MeV Emin = 4.75000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 4 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.32990E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 4.75000E-01 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 4 MT = 4 Q = 0.00000E+00 MeV Emin = 8.81777E-02 MeV : total inelastic scattering + + Nuclide 252 / 1657 : 72177.82c -- hafnium 177 (Hf-177) + + Pointers : 2072169 25675 + Primary type : Transport + Nuclide ZAI : 721770 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Hf177.ACE + Atomic weight (AW) : 176.94001 + Atomic weight ratio (AWR) : 175.42000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 23 reaction channels + - 4 special reactions + - 5 transmutation reactions + - 2 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 23 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.38068E+00 MeV Emin = 6.41706E+00 MeV frac = 1.00000E+00 Product nuclide = 72176.82c : (n,2n) + 3 MT = 17 Q = -1.44694E+01 MeV Emin = 1.45519E+01 MeV frac = 1.00000E+00 Product nuclide = 721750 : (n,3n) + 4 MT = 51 Q = -1.13000E-01 MeV Emin = 1.10000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 5 MT = 52 Q = -2.49700E-01 MeV Emin = 2.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 6 MT = 53 Q = -3.21300E-01 MeV Emin = 3.16731E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 7 MT = 54 Q = -4.09499E-01 MeV Emin = 4.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 8 MT = 55 Q = -4.26699E-01 MeV Emin = 4.29021E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 9 MT = 56 Q = -5.08099E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 10 MT = 57 Q = -5.55199E-01 MeV Emin = 5.44474E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 11 MT = 58 Q = -5.91299E-01 MeV Emin = 5.82700E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 12 MT = 59 Q = -6.04399E-01 MeV Emin = 6.07614E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 13 MT = 60 Q = -7.08499E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 14 MT = 61 Q = -7.45899E-01 MeV Emin = 7.33696E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 15 MT = 62 Q = -7.94499E-01 MeV Emin = 7.88337E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 16 MT = 63 Q = -8.05699E-01 MeV Emin = 8.05146E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 17 MT = 64 Q = -8.47399E-01 MeV Emin = 8.43166E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 18 MT = 65 Q = -8.72999E-01 MeV Emin = 8.75105E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 19 MT = 66 Q = -8.82799E-01 MeV Emin = 8.82904E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 20 MT = 91 Q = -9.47999E-01 MeV Emin = 9.40053E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 21 MT = 102 Q = 7.62669E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 72178.82c : (n,gamma) + 22 MT = 103 Q = 2.85470E-01 MeV Emin = 1.92528E+00 MeV frac = 1.00000E+00 Product nuclide = 711770 : (n,p) + 23 MT = 107 Q = 9.71174E+00 MeV Emin = 1.92528E+00 MeV frac = 1.00000E+00 Product nuclide = 701740 : (n,alpha) + + 2 additional transport branches: + + 1 MT = 103 Q = 2.85470E-01 MeV Emin = 1.92528E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 107 Q = 9.71174E+00 MeV Emin = 1.92528E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 4 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.92528E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 1.92528E+00 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 4 MT = 4 Q = 0.00000E+00 MeV Emin = 1.10000E-01 MeV : total inelastic scattering + + Nuclide 253 / 1657 : 72178.82c -- hafnium 178 (Hf-178) + + Pointers : 2076896 25721 + Primary type : Transport + Nuclide ZAI : 721780 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Hf178.ACE + Atomic weight (AW) : 177.93959 + Atomic weight ratio (AWR) : 176.41100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 28 reaction channels + - 4 special reactions + - 5 transmutation reactions + - 2 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 28 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.62568E+00 MeV Emin = 7.66892E+00 MeV frac = 1.00000E+00 Product nuclide = 72177.82c : (n,2n) + 3 MT = 17 Q = -1.40064E+01 MeV Emin = 1.40858E+01 MeV frac = 1.00000E+00 Product nuclide = 72176.82c : (n,3n) + 4 MT = 51 Q = -9.31999E-02 MeV Emin = 9.07623E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 5 MT = 52 Q = -3.06600E-01 MeV Emin = 3.04169E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 6 MT = 53 Q = -6.32199E-01 MeV Emin = 6.34758E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 7 MT = 54 Q = -1.05850E+00 MeV Emin = 1.03678E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 8 MT = 55 Q = -1.14740E+00 MeV Emin = 1.14800E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 9 MT = 56 Q = -1.17460E+00 MeV Emin = 1.15649E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 10 MT = 57 Q = -1.19930E+00 MeV Emin = 1.19368E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 11 MT = 58 Q = -1.26020E+00 MeV Emin = 1.25867E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 12 MT = 59 Q = -1.27660E+00 MeV Emin = 1.27919E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 13 MT = 60 Q = -1.30990E+00 MeV Emin = 1.31629E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 14 MT = 61 Q = -1.32240E+00 MeV Emin = 1.32393E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 15 MT = 62 Q = -1.36240E+00 MeV Emin = 1.35692E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 16 MT = 63 Q = -1.36410E+00 MeV Emin = 1.37098E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 17 MT = 64 Q = -1.43400E+00 MeV Emin = 1.44134E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 18 MT = 65 Q = -1.44380E+00 MeV Emin = 1.45127E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 19 MT = 66 Q = -1.47900E+00 MeV Emin = 1.47906E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 20 MT = 67 Q = -1.49610E+00 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 21 MT = 68 Q = -1.51360E+00 MeV Emin = 1.52050E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 22 MT = 69 Q = -1.56130E+00 MeV Emin = 1.55260E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 23 MT = 70 Q = -1.56650E+00 MeV Emin = 1.57277E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 24 MT = 71 Q = -1.60150E+00 MeV Emin = 1.61020E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 25 MT = 91 Q = -1.64000E+00 MeV Emin = 1.63366E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 26 MT = 102 Q = 6.09969E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 72179.82c : (n,gamma) + 27 MT = 103 Q = -1.46953E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 711780 : (n,p) + 28 MT = 107 Q = 7.90574E+00 MeV Emin = 4.75000E-01 MeV frac = 1.00000E+00 Product nuclide = 701750 : (n,alpha) + + 2 additional transport branches: + + 1 MT = 103 Q = -1.46953E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 107 Q = 7.90574E+00 MeV Emin = 4.75000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 4 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 4.75000E-01 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 4 MT = 4 Q = 0.00000E+00 MeV Emin = 9.07623E-02 MeV : total inelastic scattering + + Nuclide 254 / 1657 : 72179.82c -- hafnium 179 (Hf-179) + + Pointers : 2080112 25767 + Primary type : Transport + Nuclide ZAI : 721790 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Hf179.ACE + Atomic weight (AW) : 178.95028 + Atomic weight ratio (AWR) : 177.41300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 19 reaction channels + - 4 special reactions + - 5 transmutation reactions + - 3 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 19 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.09968E+00 MeV Emin = 6.13407E+00 MeV frac = 1.00000E+00 Product nuclide = 72178.82c : (n,2n) + 3 MT = 17 Q = -1.37254E+01 MeV Emin = 1.38028E+01 MeV frac = 1.00000E+00 Product nuclide = 72177.82c : (n,3n) + 4 MT = 51 Q = -1.22700E-01 MeV Emin = 1.16696E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 5 MT = 52 Q = -2.14300E-01 MeV Emin = 2.13900E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 6 MT = 53 Q = -2.68800E-01 MeV Emin = 2.60157E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 7 MT = 54 Q = -3.37700E-01 MeV Emin = 3.19802E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 8 MT = 55 Q = -3.74999E-01 MeV Emin = 3.76111E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 9 MT = 56 Q = -4.38599E-01 MeV Emin = 4.30804E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 10 MT = 57 Q = -5.18399E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 11 MT = 58 Q = -6.16899E-01 MeV Emin = 6.11928E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 12 MT = 59 Q = -6.31199E-01 MeV Emin = 6.27567E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 13 MT = 60 Q = -8.48299E-01 MeV Emin = 8.52231E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 14 MT = 61 Q = -8.70199E-01 MeV Emin = 8.66846E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 15 MT = 62 Q = -1.00340E+00 MeV Emin = 1.00372E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 16 MT = 91 Q = -1.07000E+00 MeV Emin = 1.06836E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 17 MT = 102 Q = 7.38869E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 72180.82c : (n,gamma) + 18 MT = 103 Q = -5.67529E-01 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 711790 : (n,p) + 19 MT = 107 Q = 8.68174E+00 MeV Emin = 4.85728E-01 MeV frac = 1.00000E+00 Product nuclide = 701760 : (n,alpha) + + 3 additional transport branches: + + 1 MT = 102 Q = 7.38869E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 721801 : (n,gamma) + 2 MT = 103 Q = -5.67529E-01 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 107 Q = 8.68174E+00 MeV Emin = 4.85728E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 4 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 4.85728E-01 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 4 MT = 4 Q = 0.00000E+00 MeV Emin = 1.16696E-01 MeV : total inelastic scattering + + Nuclide 255 / 1657 : 72180.82c -- hafnium 180 (Hf-180) + + Pointers : 2082651 25813 + Primary type : Transport + Nuclide ZAI : 721800 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Hf180.ACE + Atomic weight (AW) : 179.94986 + Atomic weight ratio (AWR) : 178.40400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 18 reaction channels + - 4 special reactions + - 5 transmutation reactions + - 2 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 18 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.38768E+00 MeV Emin = 7.42910E+00 MeV frac = 1.00000E+00 Product nuclide = 72179.82c : (n,2n) + 3 MT = 17 Q = -1.34874E+01 MeV Emin = 1.35630E+01 MeV frac = 1.00000E+00 Product nuclide = 72178.82c : (n,3n) + 4 MT = 51 Q = -9.32999E-02 MeV Emin = 9.08451E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 5 MT = 52 Q = -3.08600E-01 MeV Emin = 3.05165E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 6 MT = 53 Q = -6.40899E-01 MeV Emin = 6.40138E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 7 MT = 54 Q = -1.08390E+00 MeV Emin = 1.07603E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 8 MT = 55 Q = -1.14160E+00 MeV Emin = 1.12262E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 9 MT = 56 Q = -1.18320E+00 MeV Emin = 1.15649E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 10 MT = 57 Q = -1.19970E+00 MeV Emin = 1.20610E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 11 MT = 58 Q = -1.29100E+00 MeV Emin = 1.27655E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 12 MT = 59 Q = -1.37440E+00 MeV Emin = 1.37696E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 13 MT = 60 Q = -1.40920E+00 MeV Emin = 1.39960E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 14 MT = 61 Q = -1.53930E+00 MeV Emin = 1.52218E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 15 MT = 91 Q = -1.60760E+00 MeV Emin = 1.61058E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 16 MT = 102 Q = 5.69569E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 721810 : (n,gamma) + 17 MT = 103 Q = -2.51353E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 711800 : (n,p) + 18 MT = 107 Q = 6.85574E+00 MeV Emin = 4.75000E-01 MeV frac = 1.00000E+00 Product nuclide = 701770 : (n,alpha) + + 2 additional transport branches: + + 1 MT = 103 Q = -2.51353E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 107 Q = 6.85574E+00 MeV Emin = 4.75000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 4 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.00000E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 4.75000E-01 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 4 MT = 4 Q = 0.00000E+00 MeV Emin = 9.08451E-02 MeV : total inelastic scattering + + Nuclide 256 / 1657 : 73181.82c -- tantalum 181 (Ta-181) + + Pointers : 2092281 34231 + Primary type : Transport + Nuclide ZAI : 731810 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ta181.ACE + Atomic weight (AW) : 180.94844 + Atomic weight ratio (AWR) : 179.39400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 22 reaction channels + - 4 special reactions + - 6 transmutation reactions + - 3 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 22 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.64368E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 731800 : (n,2n) + 3 MT = 17 Q = -1.42244E+01 MeV Emin = 1.43037E+01 MeV frac = 1.00000E+00 Product nuclide = 731790 : (n,3n) + 4 MT = 28 Q = -5.93521E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 72180.82c : (n,np) + 5 MT = 51 Q = -6.20000E-03 MeV Emin = 6.00000E-03 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -1.36000E-01 MeV Emin = 1.27569E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -1.59000E-01 MeV Emin = 1.59585E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -3.01000E-01 MeV Emin = 3.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -3.38000E-01 MeV Emin = 3.21482E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -4.81999E-01 MeV Emin = 4.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -4.94999E-01 MeV Emin = 4.91273E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -5.42999E-01 MeV Emin = 5.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -6.14999E-01 MeV Emin = 6.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -6.18999E-01 MeV Emin = 6.20490E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -7.16999E-01 MeV Emin = 7.20595E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -7.72999E-01 MeV Emin = 7.49153E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 63 Q = -9.64999E-01 MeV Emin = 9.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 18 MT = 64 Q = -1.02800E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 19 MT = 91 Q = -1.03000E+00 MeV Emin = 1.03474E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 20 MT = 102 Q = 6.06369E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 73182.82c : (n,gamma) + 21 MT = 103 Q = -2.40530E-01 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 721810 : (n,p) + 22 MT = 107 Q = 7.40474E+00 MeV Emin = 4.98930E-01 MeV frac = 1.00000E+00 Product nuclide = 711780 : (n,alpha) + + 3 additional transport branches: + + 1 MT = 28 Q = -5.93521E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 2 MT = 103 Q = -2.40530E-01 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 107 Q = 7.40474E+00 MeV Emin = 4.98930E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 4 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.50000E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 4.98930E-01 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 4 MT = 4 Q = 0.00000E+00 MeV Emin = 6.00000E-03 MeV : total inelastic scattering + + Nuclide 257 / 1657 : 73182.82c -- tantalum 182 (Ta-182) + + Pointers : 2094509 34277 + Primary type : Transport + Nuclide ZAI : 731820 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ta182.ACE + Atomic weight (AW) : 181.95005 + Atomic weight ratio (AWR) : 180.38700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 9.91E+06 seconds (115 days) + Specific ingestion toxicity : 1.50E-09 Sv/Bq + Specific inhalation toxicity : 1.00E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 14 reaction channels + - 3 special reactions + - 4 transmutation reactions + - 1 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 14 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.06640E+00 MeV Emin = 6.10003E+00 MeV frac = 1.00000E+00 Product nuclide = 73181.82c : (n,2n) + 3 MT = 17 Q = -1.37240E+01 MeV Emin = 1.38001E+01 MeV frac = 1.00000E+00 Product nuclide = 731800 : (n,3n) + 4 MT = 51 Q = -9.70000E-02 MeV Emin = 8.56250E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 5 MT = 52 Q = -1.14000E-01 MeV Emin = 1.05000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 6 MT = 53 Q = -1.73000E-01 MeV Emin = 1.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 7 MT = 54 Q = -2.37000E-01 MeV Emin = 2.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 8 MT = 55 Q = -2.70000E-01 MeV Emin = 2.71140E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 9 MT = 56 Q = -2.92000E-01 MeV Emin = 2.79778E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 10 MT = 57 Q = -3.15000E-01 MeV Emin = 3.08350E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 11 MT = 58 Q = -3.60000E-01 MeV Emin = 3.39373E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 12 MT = 91 Q = -3.97800E-01 MeV Emin = 3.81000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 13 MT = 102 Q = 6.93000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 731830 : (n,gamma) + 14 MT = 107 Q = 8.29400E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 711790 : (n,alpha) + + 1 additional transport branch: + + 1 MT = 107 Q = 8.29400E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 3 special reactions: + + 1 MT = 207 Q = 0.00000E+00 MeV Emin = 1.10000E+01 MeV : total alpha production + 2 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 3 MT = 4 Q = 0.00000E+00 MeV Emin = 8.56250E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.81360E+00 MeV frac = 1.00000E+00 Product nuclide = 74182.82c : beta- + + Nuclide 258 / 1657 : 74182.82c -- tungsten 182 (W-182) + + Pointers : 2104563 35933 + Primary type : Transport + Nuclide ZAI : 741820 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/W182.ACE + Atomic weight (AW) : 181.94803 + Atomic weight ratio (AWR) : 180.38500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 30 reaction channels + - 5 special reactions + - 8 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 30 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.05468E+00 MeV Emin = 8.09934E+00 MeV frac = 1.00000E+00 Product nuclide = 741810 : (n,2n) + 3 MT = 17 Q = -1.47014E+01 MeV Emin = 1.47829E+01 MeV frac = 1.00000E+00 Product nuclide = 741800 : (n,3n) + 4 MT = 22 Q = 1.78906E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 72178.82c : (n,nalpha) + 5 MT = 28 Q = -7.08521E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 73181.82c : (n,np) + 6 MT = 51 Q = -1.00100E-01 MeV Emin = 1.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -3.29400E-01 MeV Emin = 3.15613E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -6.80500E-01 MeV Emin = 6.63204E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -1.13570E+00 MeV Emin = 1.12100E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -1.14450E+00 MeV Emin = 1.15000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -1.22140E+00 MeV Emin = 1.20000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -1.33110E+00 MeV Emin = 1.31924E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -1.44280E+00 MeV Emin = 1.43000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -1.71190E+00 MeV Emin = 1.68000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -1.75680E+00 MeV Emin = 1.75000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -1.76540E+00 MeV Emin = 1.77496E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -1.76900E+00 MeV Emin = 1.77661E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -1.80970E+00 MeV Emin = 1.79987E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -1.81090E+00 MeV Emin = 1.82064E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -1.81340E+00 MeV Emin = 1.82282E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 21 MT = 66 Q = -1.82950E+00 MeV Emin = 1.83000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 22 MT = 67 Q = -1.83310E+00 MeV Emin = 1.84145E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 23 MT = 68 Q = -1.85600E+00 MeV Emin = 1.85814E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 24 MT = 69 Q = -1.85690E+00 MeV Emin = 1.86674E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 25 MT = 70 Q = -1.87120E+00 MeV Emin = 1.87579E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 26 MT = 91 Q = -1.87200E+00 MeV Emin = 1.88198E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 27 MT = 102 Q = 6.19070E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 74183.82c : (n,gamma) + 28 MT = 103 Q = -1.02253E+00 MeV Emin = 2.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 73182.82c : (n,p) + 29 MT = 104 Q = -4.86060E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 73181.82c : (n,d) + 30 MT = 107 Q = 7.88874E+00 MeV Emin = 9.00000E-02 MeV frac = 1.00000E+00 Product nuclide = 72179.82c : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = 1.78906E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -7.08521E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 102 Q = 6.19070E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 741831 : (n,gamma) + 4 MT = 103 Q = -1.02253E+00 MeV Emin = 2.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -4.86060E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 107 Q = 7.88874E+00 MeV Emin = 9.00000E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 5 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.50000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.00000E+00 MeV : total deuteron production + 3 MT = 207 Q = 0.00000E+00 MeV Emin = 9.00000E-02 MeV : total alpha production + 4 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 5 MT = 4 Q = 0.00000E+00 MeV Emin = 1.00000E-01 MeV : total inelastic scattering + + Nuclide 259 / 1657 : 74183.82c -- tungsten 183 (W-183) + + Pointers : 2107686 35979 + Primary type : Transport + Nuclide ZAI : 741830 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/W183.ACE + Atomic weight (AW) : 182.95064 + Atomic weight ratio (AWR) : 181.37900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 3.47E+24 seconds (1.1E+17 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 20 reaction channels + - 5 special reactions + - 8 transmutation reactions + - 5 transmutation branch reactions + - 3 decay reactions + - 3 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 20 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.19139E+00 MeV Emin = 6.22553E+00 MeV frac = 1.00000E+00 Product nuclide = 74182.82c : (n,2n) + 3 MT = 17 Q = -1.42454E+01 MeV Emin = 1.43239E+01 MeV frac = 1.00000E+00 Product nuclide = 741810 : (n,3n) + 4 MT = 22 Q = 1.69806E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 72179.82c : (n,nalpha) + 5 MT = 28 Q = -7.21322E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 73182.82c : (n,np) + 6 MT = 51 Q = -4.65000E-02 MeV Emin = 4.58782E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -9.91000E-02 MeV Emin = 9.34406E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -2.07000E-01 MeV Emin = 2.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -2.08800E-01 MeV Emin = 2.09046E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -2.91700E-01 MeV Emin = 2.90206E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -3.08900E-01 MeV Emin = 3.05302E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -3.09500E-01 MeV Emin = 3.10905E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -4.12100E-01 MeV Emin = 4.07186E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -4.87000E-01 MeV Emin = 4.81264E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -5.50000E-01 MeV Emin = 5.39774E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 91 Q = -6.24000E-01 MeV Emin = 6.27000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 17 MT = 102 Q = 7.41170E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 74184.82c : (n,gamma) + 18 MT = 103 Q = -2.85530E-01 MeV Emin = 1.75000E+00 MeV frac = 1.00000E+00 Product nuclide = 731830 : (n,p) + 19 MT = 104 Q = -4.98860E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 73182.82c : (n,d) + 20 MT = 107 Q = 9.08574E+00 MeV Emin = 7.25000E-01 MeV frac = 1.00000E+00 Product nuclide = 72180.82c : (n,alpha) + + 5 additional transport branches: + + 1 MT = 22 Q = 1.69806E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -7.21322E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -2.85530E-01 MeV Emin = 1.75000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -4.98860E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 107 Q = 9.08574E+00 MeV Emin = 7.25000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 5 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.75000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.00000E+00 MeV : total deuteron production + 3 MT = 207 Q = 0.00000E+00 MeV Emin = 7.25000E-01 MeV : total alpha production + 4 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 5 MT = 4 Q = 0.00000E+00 MeV Emin = 4.58782E-02 MeV : total inelastic scattering + + 3 decay reactions: + + 1 RTYP = 4 Q = 1.68000E+00 MeV frac = 3.34000E-01 Product nuclide = 72179.82c : alpha + 2 RTYP = 4 Q = 1.30496E+00 MeV frac = 3.33000E-01 Product nuclide = 721791 : alpha + 3 RTYP = 4 Q = 5.74160E-01 MeV frac = 3.33000E-01 Product nuclide = 721792 : alpha + + 3 additional decay branches: + + 1 RTYP = 4 Q = 1.68000E+00 MeV frac = 3.34000E-01 Product nuclide = 2004.82c : alpha + 2 RTYP = 4 Q = 1.30496E+00 MeV frac = 3.33000E-01 Product nuclide = 2004.82c : alpha + 3 RTYP = 4 Q = 5.74160E-01 MeV frac = 3.33000E-01 Product nuclide = 2004.82c : alpha + + Nuclide 260 / 1657 : 74184.82c -- tungsten 184 (W-184) + + Pointers : 2111076 36025 + Primary type : Transport + Nuclide ZAI : 741840 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/W184.ACE + Atomic weight (AW) : 183.95124 + Atomic weight ratio (AWR) : 182.37100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.26E+25 seconds (4E+17 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 20 reaction channels + - 5 special reactions + - 8 transmutation reactions + - 6 transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 20 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.41168E+00 MeV Emin = 7.45233E+00 MeV frac = 1.00000E+00 Product nuclide = 74183.82c : (n,2n) + 3 MT = 17 Q = -1.36024E+01 MeV Emin = 1.36770E+01 MeV frac = 1.00000E+00 Product nuclide = 74182.82c : (n,3n) + 4 MT = 22 Q = 1.67406E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 72180.82c : (n,nalpha) + 5 MT = 28 Q = -7.69721E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 731830 : (n,np) + 6 MT = 51 Q = -1.11200E-01 MeV Emin = 1.10905E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -3.64100E-01 MeV Emin = 3.33048E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -7.48300E-01 MeV Emin = 7.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -9.03300E-01 MeV Emin = 9.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -1.00230E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -1.00590E+00 MeV Emin = 1.01000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -1.12140E+00 MeV Emin = 1.10000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -1.22130E+00 MeV Emin = 1.20000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -1.28500E+00 MeV Emin = 1.27103E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -1.32210E+00 MeV Emin = 1.31000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 91 Q = -1.43200E+00 MeV Emin = 1.43885E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 17 MT = 102 Q = 5.75470E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 741850 : (n,gamma) + 18 MT = 103 Q = -2.24753E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 731840 : (n,p) + 19 MT = 104 Q = -5.47260E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 731830 : (n,d) + 20 MT = 107 Q = 7.36874E+00 MeV Emin = 9.00000E-02 MeV frac = 1.00000E+00 Product nuclide = 721810 : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = 1.67406E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -7.69721E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 102 Q = 5.75470E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 741851 : (n,gamma) + 4 MT = 103 Q = -2.24753E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -5.47260E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 107 Q = 7.36874E+00 MeV Emin = 9.00000E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 5 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.00000E+00 MeV : total deuteron production + 3 MT = 207 Q = 0.00000E+00 MeV Emin = 9.00000E-02 MeV : total alpha production + 4 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 5 MT = 4 Q = 0.00000E+00 MeV Emin = 1.10905E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 4 Q = 1.65620E+00 MeV frac = 1.00000E+00 Product nuclide = 72180.82c : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 1.65620E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 261 / 1657 : 74186.82c -- tungsten 186 (W-186) + + Pointers : 2115071 36071 + Primary type : Transport + Nuclide ZAI : 741860 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/W186.ACE + Atomic weight (AW) : 185.95445 + Atomic weight ratio (AWR) : 184.35700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.86E+25 seconds (5.9E+17 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 22 reaction channels + - 5 special reactions + - 8 transmutation reactions + - 5 transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 22 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.19537E+00 MeV Emin = 7.23440E+00 MeV frac = 1.00000E+00 Product nuclide = 741850 : (n,2n) + 3 MT = 17 Q = -1.29514E+01 MeV Emin = 1.30217E+01 MeV frac = 1.00000E+00 Product nuclide = 74184.82c : (n,3n) + 4 MT = 22 Q = 1.12190E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 721820 : (n,nalpha) + 5 MT = 28 Q = -8.38421E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 731850 : (n,np) + 6 MT = 51 Q = -1.22600E-01 MeV Emin = 1.21633E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -3.96800E-01 MeV Emin = 3.74214E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -7.37700E-01 MeV Emin = 7.20850E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -8.08800E-01 MeV Emin = 8.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -8.61800E-01 MeV Emin = 8.40237E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -8.82000E-01 MeV Emin = 8.76892E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -9.52600E-01 MeV Emin = 9.28883E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -1.00700E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -1.03160E+00 MeV Emin = 1.03000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -1.04520E+00 MeV Emin = 1.04000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -1.15000E+00 MeV Emin = 1.15250E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -1.28400E+00 MeV Emin = 1.25000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 91 Q = -1.32300E+00 MeV Emin = 1.32917E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 19 MT = 102 Q = 5.46670E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 741870 : (n,gamma) + 20 MT = 103 Q = -3.11253E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 731860 : (n,p) + 21 MT = 104 Q = -6.15960E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 731850 : (n,d) + 22 MT = 107 Q = 6.39074E+00 MeV Emin = 1.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 721830 : (n,alpha) + + 5 additional transport branches: + + 1 MT = 22 Q = 1.12190E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -8.38421E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -3.11253E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -6.15960E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 107 Q = 6.39074E+00 MeV Emin = 1.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 5 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.00000E+00 MeV : total deuteron production + 3 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-01 MeV : total alpha production + 4 MT = 444 Q = 0.00000E+00 MeV Emin = 2.46375E-08 MeV : damage-energy production + 5 MT = 4 Q = 0.00000E+00 MeV Emin = 1.21633E-01 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 11 Q = 4.89998E-01 MeV frac = 5.00000E-01 Product nuclide = 761860 : beta- + beta- + 2 RTYP = 4 Q = 1.12460E+00 MeV frac = 5.00000E-01 Product nuclide = 721820 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 1.12460E+00 MeV frac = 5.00000E-01 Product nuclide = 2004.82c : alpha + + Nuclide 262 / 1657 : 75185.82c -- rhenium 185 (Re-185) + + Pointers : 2129090 31379 + Primary type : Transport + Nuclide ZAI : 751850 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Re185.ACE + Atomic weight (AW) : 184.95284 + Atomic weight ratio (AWR) : 183.36400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 14 reaction channels + - 2 special reactions + - 3 transmutation reactions + - 1 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 14 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.67738E+00 MeV Emin = 7.71925E+00 MeV frac = 1.00000E+00 Product nuclide = 751840 : (n,2n) + 3 MT = 17 Q = -1.41558E+01 MeV Emin = 1.42330E+01 MeV frac = 1.00000E+00 Product nuclide = 751830 : (n,3n) + 4 MT = 51 Q = -1.25400E-01 MeV Emin = 1.08042E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 5 MT = 52 Q = -2.84100E-01 MeV Emin = 2.84375E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 6 MT = 53 Q = -3.68200E-01 MeV Emin = 3.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 7 MT = 54 Q = -4.75600E-01 MeV Emin = 4.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 8 MT = 55 Q = -5.46900E-01 MeV Emin = 5.24940E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 9 MT = 56 Q = -6.46100E-01 MeV Emin = 6.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 10 MT = 57 Q = -6.97000E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 11 MT = 58 Q = -7.17400E-01 MeV Emin = 7.11056E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 12 MT = 59 Q = -7.57400E-01 MeV Emin = 7.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 13 MT = 91 Q = -7.57400E-01 MeV Emin = 7.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 14 MT = 102 Q = 6.17800E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 751860 : (n,gamma) + + 1 additional transport branch: + + 1 MT = 102 Q = 6.17800E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 751861 : (n,gamma) + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 1.08042E-01 MeV : total inelastic scattering + + Nuclide 263 / 1657 : 75187.82c -- rhenium 187 (Re-187) + + Pointers : 2132046 31425 + Primary type : Transport + Nuclide ZAI : 751870 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Re187.ACE + Atomic weight (AW) : 186.95605 + Atomic weight ratio (AWR) : 185.35000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.37E+18 seconds (43.3 billion years) + Specific ingestion toxicity : 5.10E-12 Sv/Bq + Specific inhalation toxicity : 6.30E-12 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 21 reaction channels + - 2 special reactions + - 3 transmutation reactions + - 1 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 21 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.36038E+00 MeV Emin = 7.40009E+00 MeV frac = 1.00000E+00 Product nuclide = 751860 : (n,2n) + 3 MT = 17 Q = -1.35388E+01 MeV Emin = 1.36118E+01 MeV frac = 1.00000E+00 Product nuclide = 75185.82c : (n,3n) + 4 MT = 51 Q = -1.34200E-01 MeV Emin = 9.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 5 MT = 52 Q = -2.06200E-01 MeV Emin = 2.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 6 MT = 53 Q = -3.02700E-01 MeV Emin = 3.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 7 MT = 54 Q = -3.90000E-01 MeV Emin = 3.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 8 MT = 55 Q = -5.09000E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 9 MT = 56 Q = -5.11600E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 10 MT = 57 Q = -5.89000E-01 MeV Emin = 5.87500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 11 MT = 58 Q = -6.18300E-01 MeV Emin = 6.14435E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 12 MT = 59 Q = -6.25500E-01 MeV Emin = 6.25261E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 13 MT = 60 Q = -6.47300E-01 MeV Emin = 6.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 14 MT = 61 Q = -6.85700E-01 MeV Emin = 6.87698E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 15 MT = 62 Q = -7.43000E-01 MeV Emin = 7.23505E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 16 MT = 63 Q = -7.71000E-01 MeV Emin = 7.62580E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 17 MT = 64 Q = -7.72900E-01 MeV Emin = 7.76115E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 18 MT = 65 Q = -8.16600E-01 MeV Emin = 8.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 19 MT = 66 Q = -8.26600E-01 MeV Emin = 8.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 20 MT = 91 Q = -8.26600E-01 MeV Emin = 8.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 21 MT = 102 Q = 5.87300E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 751880 : (n,gamma) + + 1 additional transport branch: + + 1 MT = 102 Q = 5.87300E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 751881 : (n,gamma) + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 9.00000E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.46900E-03 MeV frac = 1.00000E+00 Product nuclide = 761870 : beta- + + Nuclide 264 / 1657 : 77191.82c -- iridium 191 (Ir-191) + + Pointers : 2156450 26733 + Primary type : Transport + Nuclide ZAI : 771910 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ir191.ACE + Atomic weight (AW) : 190.96045 + Atomic weight ratio (AWR) : 189.32000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 11 reaction channels + - 4 special reactions + - 5 transmutation reactions + - 2 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 11 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.76500E+00 MeV Emin = 7.80602E+00 MeV frac = 1.00000E+00 Product nuclide = 771900 : (n,2n) + 3 MT = 17 Q = -1.39640E+01 MeV Emin = 1.40378E+01 MeV frac = 1.00000E+00 Product nuclide = 771890 : (n,3n) + 4 MT = 51 Q = -8.24000E-02 MeV Emin = 7.71251E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 5 MT = 52 Q = -1.29400E-01 MeV Emin = 1.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 6 MT = 53 Q = -1.71000E-01 MeV Emin = 1.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 7 MT = 54 Q = -1.78900E-01 MeV Emin = 1.75872E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 8 MT = 91 Q = -1.89006E-01 MeV Emin = 2.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 9 MT = 102 Q = 6.19808E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 771920 : (n,gamma) + 10 MT = 103 Q = 4.72400E-01 MeV Emin = 8.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 761910 : (n,p) + 11 MT = 107 Q = 7.95480E+00 MeV Emin = 8.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 751880 : (n,alpha) + + 2 additional transport branches: + + 1 MT = 103 Q = 4.72400E-01 MeV Emin = 8.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 107 Q = 7.95480E+00 MeV Emin = 8.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 4 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 8.00000E-01 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 8.00000E-01 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 4 MT = 4 Q = 0.00000E+00 MeV Emin = 7.71251E-02 MeV : total inelastic scattering + + Nuclide 265 / 1657 : 77193.82c -- iridium 193 (Ir-193) + + Pointers : 2161203 26779 + Primary type : Transport + Nuclide ZAI : 771930 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ir193.ACE + Atomic weight (AW) : 192.96265 + Atomic weight ratio (AWR) : 191.30500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 11 reaction channels + - 4 special reactions + - 5 transmutation reactions + - 2 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 11 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.76500E+00 MeV Emin = 7.80600E+00 MeV frac = 1.00000E+00 Product nuclide = 771920 : (n,2n) + 3 MT = 17 Q = -1.39640E+01 MeV Emin = 1.40370E+01 MeV frac = 1.00000E+00 Product nuclide = 77191.82c : (n,3n) + 4 MT = 51 Q = -7.30000E-02 MeV Emin = 7.25000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 5 MT = 52 Q = -8.03000E-02 MeV Emin = 8.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 6 MT = 53 Q = -1.38000E-01 MeV Emin = 1.37500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 7 MT = 54 Q = -1.80000E-01 MeV Emin = 1.70000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 8 MT = 91 Q = -1.89006E-01 MeV Emin = 2.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 9 MT = 102 Q = 6.06680E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 771940 : (n,gamma) + 10 MT = 103 Q = 4.72400E-01 MeV Emin = 8.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 761930 : (n,p) + 11 MT = 107 Q = 6.79000E+00 MeV Emin = 8.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 751900 : (n,alpha) + + 2 additional transport branches: + + 1 MT = 103 Q = 4.72400E-01 MeV Emin = 8.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 107 Q = 6.79000E+00 MeV Emin = 8.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 4 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 8.00000E-01 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 8.00000E-01 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 4 MT = 4 Q = 0.00000E+00 MeV Emin = 7.25000E-02 MeV : total inelastic scattering + + Nuclide 266 / 1657 : 79197.82c -- gold 197 (Au-197) + + Pointers : 2180021 19327 + Primary type : Transport + Nuclide ZAI : 791970 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Au197.ACE + Atomic weight (AW) : 196.96604 + Atomic weight ratio (AWR) : 195.27400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 3.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 21 reaction channels + - 4 special reactions + - 5 transmutation reactions + - 3 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 21 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.05940E+00 MeV Emin = 8.10070E+00 MeV frac = 1.00000E+00 Product nuclide = 791960 : (n,2n) + 3 MT = 17 Q = -1.47210E+01 MeV Emin = 1.47964E+01 MeV frac = 1.00000E+00 Product nuclide = 791950 : (n,3n) + 4 MT = 37 Q = -2.31080E+01 MeV Emin = 2.32270E+01 MeV frac = 1.00000E+00 Product nuclide = cut: Au-194 : (n,4n) + 5 MT = 51 Q = -7.74000E-02 MeV Emin = 7.77500E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -2.69000E-01 MeV Emin = 2.70000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -2.79000E-01 MeV Emin = 2.80000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -4.09000E-01 MeV Emin = 4.10000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -5.03000E-01 MeV Emin = 5.05000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -5.48000E-01 MeV Emin = 5.50625E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -7.37000E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -8.55000E-01 MeV Emin = 8.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -8.88000E-01 MeV Emin = 8.92384E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -9.36000E-01 MeV Emin = 9.40000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -1.04500E+00 MeV Emin = 1.05000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -1.15000E+00 MeV Emin = 1.15000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 63 Q = -1.21740E+00 MeV Emin = 1.20000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 18 MT = 91 Q = -9.94900E-02 MeV Emin = 9.95000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 19 MT = 102 Q = 6.51238E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 791980 : (n,gamma) + 20 MT = 103 Q = 6.34000E-02 MeV Emin = 5.75000E-03 MeV frac = 1.00000E+00 Product nuclide = 781970 : (n,p) + 21 MT = 107 Q = 7.01050E+00 MeV Emin = 5.75000E-03 MeV frac = 1.00000E+00 Product nuclide = 771940 : (n,alpha) + + 3 additional transport branches: + + 1 MT = 102 Q = 6.51238E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 791981 : (n,gamma) + 2 MT = 103 Q = 6.34000E-02 MeV Emin = 5.75000E-03 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 107 Q = 7.01050E+00 MeV Emin = 5.75000E-03 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 4 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 5.75000E-03 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 5.75000E-03 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 4 MT = 4 Q = 0.00000E+00 MeV Emin = 7.77500E-02 MeV : total inelastic scattering + + Nuclide 267 / 1657 : 80198.82c -- mercury 198 (Hg-198) + + Pointers : 2191904 25905 + Primary type : Transport + Nuclide ZAI : 801980 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Hg198.ACE + Atomic weight (AW) : 197.96664 + Atomic weight ratio (AWR) : 196.26600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 29 reaction channels + - 5 special reactions + - 8 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 29 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.30069E+00 MeV Emin = 8.34298E+00 MeV frac = 1.00000E+00 Product nuclide = 801970 : (n,2n) + 3 MT = 17 Q = -1.52814E+01 MeV Emin = 1.53593E+01 MeV frac = 1.00000E+00 Product nuclide = 801960 : (n,3n) + 4 MT = 22 Q = 1.33306E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 781940 : (n,nalpha) + 5 MT = 28 Q = -7.10322E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 79197.82c : (n,np) + 6 MT = 51 Q = -4.11800E-01 MeV Emin = 3.81949E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.04850E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -1.08770E+00 MeV Emin = 1.08336E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -1.40150E+00 MeV Emin = 1.36898E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -1.41940E+00 MeV Emin = 1.41766E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -1.54850E+00 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -1.61240E+00 MeV Emin = 1.60015E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -1.63560E+00 MeV Emin = 1.63296E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -1.68330E+00 MeV Emin = 1.66791E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -1.76000E+00 MeV Emin = 1.75000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -1.81580E+00 MeV Emin = 1.81103E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -1.83250E+00 MeV Emin = 1.83345E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -1.83490E+00 MeV Emin = 1.84302E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -1.84720E+00 MeV Emin = 1.85128E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -1.85880E+00 MeV Emin = 1.86244E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 21 MT = 66 Q = -1.89930E+00 MeV Emin = 1.88863E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 22 MT = 67 Q = -1.90140E+00 MeV Emin = 1.91003E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 23 MT = 68 Q = -1.90970E+00 MeV Emin = 1.91526E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 24 MT = 69 Q = -1.91080E+00 MeV Emin = 1.92010E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 25 MT = 91 Q = -1.91100E+00 MeV Emin = 1.92010E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 26 MT = 102 Q = 6.64900E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 80199.82c : (n,gamma) + 27 MT = 103 Q = -5.90530E-01 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 791980 : (n,p) + 28 MT = 104 Q = -4.87861E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 79197.82c : (n,d) + 29 MT = 107 Q = 7.45775E+00 MeV Emin = 1.00000E-02 MeV frac = 1.00000E+00 Product nuclide = 781950 : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = 1.33306E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -7.10322E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 102 Q = 6.64900E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 801991 : (n,gamma) + 4 MT = 103 Q = -5.90530E-01 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -4.87861E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 107 Q = 7.45775E+00 MeV Emin = 1.00000E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 5 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.00000E+00 MeV : total deuteron production + 3 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-02 MeV : total alpha production + 4 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 5 MT = 4 Q = 0.00000E+00 MeV Emin = 3.81949E-01 MeV : total inelastic scattering + + Nuclide 268 / 1657 : 80199.82c -- mercury 199 (Hg-199) + + Pointers : 2194954 25951 + Primary type : Transport + Nuclide ZAI : 801990 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Hg199.ACE + Atomic weight (AW) : 198.96824 + Atomic weight ratio (AWR) : 197.25900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 23 reaction channels + - 5 special reactions + - 8 transmutation reactions + - 5 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 23 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.64869E+00 MeV Emin = 6.68240E+00 MeV frac = 1.00000E+00 Product nuclide = 80198.82c : (n,2n) + 3 MT = 17 Q = -1.49494E+01 MeV Emin = 1.50252E+01 MeV frac = 1.00000E+00 Product nuclide = 801970 : (n,3n) + 4 MT = 22 Q = 8.09060E-01 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 781950 : (n,nalpha) + 5 MT = 28 Q = -7.23922E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 791980 : (n,np) + 6 MT = 51 Q = -1.58380E-01 MeV Emin = 1.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -2.08200E-01 MeV Emin = 2.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -4.03500E-01 MeV Emin = 4.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -4.13900E-01 MeV Emin = 4.11998E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -4.55500E-01 MeV Emin = 4.47356E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -4.92300E-01 MeV Emin = 4.89452E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -5.32500E-01 MeV Emin = 5.26400E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -6.38000E-01 MeV Emin = 6.20617E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -6.68900E-01 MeV Emin = 6.64527E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -6.95900E-01 MeV Emin = 6.94403E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -7.12900E-01 MeV Emin = 7.05458E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -7.37400E-01 MeV Emin = 7.28826E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -7.50400E-01 MeV Emin = 7.54003E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 91 Q = -7.50000E-01 MeV Emin = 7.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 20 MT = 102 Q = 8.02900E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 80200.82c : (n,gamma) + 21 MT = 103 Q = 3.29470E-01 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 791990 : (n,p) + 22 MT = 104 Q = -5.01461E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 791980 : (n,d) + 23 MT = 107 Q = 8.72975E+00 MeV Emin = 5.84812E-01 MeV frac = 1.00000E+00 Product nuclide = 781960 : (n,alpha) + + 5 additional transport branches: + + 1 MT = 22 Q = 8.09060E-01 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -7.23922E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = 3.29470E-01 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -5.01461E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 107 Q = 8.72975E+00 MeV Emin = 5.84812E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 5 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.00000E+00 MeV : total deuteron production + 3 MT = 207 Q = 0.00000E+00 MeV Emin = 5.84812E-01 MeV : total alpha production + 4 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 5 MT = 4 Q = 0.00000E+00 MeV Emin = 1.50000E-01 MeV : total inelastic scattering + + Nuclide 269 / 1657 : 80200.82c -- mercury 200 (Hg-200) + + Pointers : 2198041 25997 + Primary type : Transport + Nuclide ZAI : 802000 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Hg200.ACE + Atomic weight (AW) : 199.96783 + Atomic weight ratio (AWR) : 198.25000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 44 reaction channels + - 5 special reactions + - 8 transmutation reactions + - 5 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 44 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.02869E+00 MeV Emin = 8.06919E+00 MeV frac = 1.00000E+00 Product nuclide = 80199.82c : (n,2n) + 3 MT = 17 Q = -1.46774E+01 MeV Emin = 1.47514E+01 MeV frac = 1.00000E+00 Product nuclide = 80198.82c : (n,3n) + 4 MT = 22 Q = 7.01060E-01 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 781960 : (n,nalpha) + 5 MT = 28 Q = -7.69922E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 791990 : (n,np) + 6 MT = 51 Q = -3.67900E-01 MeV Emin = 3.40000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -9.47200E-01 MeV Emin = 8.75989E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -1.02930E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -1.25410E+00 MeV Emin = 1.25000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -1.51520E+00 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -1.57030E+00 MeV Emin = 1.56438E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -1.57370E+00 MeV Emin = 1.57993E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -1.59340E+00 MeV Emin = 1.59792E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -1.63090E+00 MeV Emin = 1.63048E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -1.64140E+00 MeV Emin = 1.64676E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -1.65900E+00 MeV Emin = 1.65940E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -1.70670E+00 MeV Emin = 1.70332E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -1.71830E+00 MeV Emin = 1.72114E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -1.73090E+00 MeV Emin = 1.73726E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -1.73430E+00 MeV Emin = 1.74134E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 21 MT = 66 Q = -1.77560E+00 MeV Emin = 1.76754E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 22 MT = 67 Q = -1.84580E+00 MeV Emin = 1.84441E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 23 MT = 68 Q = -1.85150E+00 MeV Emin = 1.85796E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 24 MT = 69 Q = -1.85680E+00 MeV Emin = 1.86433E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 25 MT = 70 Q = -1.88290E+00 MeV Emin = 1.88875E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 26 MT = 71 Q = -1.96260E+00 MeV Emin = 1.94459E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 27 MT = 72 Q = -1.97230E+00 MeV Emin = 1.97738E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 28 MT = 73 Q = -1.97430E+00 MeV Emin = 1.98325E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 29 MT = 74 Q = -2.04910E+00 MeV Emin = 2.05944E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 30 MT = 75 Q = -2.06130E+00 MeV Emin = 2.07170E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 31 MT = 76 Q = -2.07430E+00 MeV Emin = 2.08476E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 32 MT = 77 Q = -2.11430E+00 MeV Emin = 2.12497E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 27. excited state + 33 MT = 78 Q = -2.11650E+00 MeV Emin = 2.12718E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 28. excited state + 34 MT = 79 Q = -2.12690E+00 MeV Emin = 2.13763E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 29. excited state + 35 MT = 80 Q = -2.12790E+00 MeV Emin = 2.13863E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 30. excited state + 36 MT = 81 Q = -2.13550E+00 MeV Emin = 2.14627E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 31. excited state + 37 MT = 82 Q = -2.14380E+00 MeV Emin = 2.15462E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 32. excited state + 38 MT = 83 Q = -2.15140E+00 MeV Emin = 2.16225E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 33. excited state + 39 MT = 84 Q = -2.18950E+00 MeV Emin = 2.20054E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 34. excited state + 40 MT = 91 Q = -2.12700E+00 MeV Emin = 2.13773E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 41 MT = 102 Q = 6.22500E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 802010 : (n,gamma) + 42 MT = 103 Q = -1.41653E+00 MeV Emin = 2.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 792000 : (n,p) + 43 MT = 104 Q = -5.47461E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 791990 : (n,d) + 44 MT = 107 Q = 6.55175E+00 MeV Emin = 4.20000E-01 MeV frac = 1.00000E+00 Product nuclide = 781970 : (n,alpha) + + 5 additional transport branches: + + 1 MT = 22 Q = 7.01060E-01 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -7.69922E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -1.41653E+00 MeV Emin = 2.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -5.47461E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 107 Q = 6.55175E+00 MeV Emin = 4.20000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 5 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.50000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.00000E+00 MeV : total deuteron production + 3 MT = 207 Q = 0.00000E+00 MeV Emin = 4.20000E-01 MeV : total alpha production + 4 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 5 MT = 4 Q = 0.00000E+00 MeV Emin = 3.40000E-01 MeV : total inelastic scattering + + Nuclide 270 / 1657 : 90227.82c -- thorium 227 (Th-227) + + Pointers : 2284498 34967 + Primary type : Transport + Nuclide ZAI : 902270 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Th227.ACE + Atomic weight (AW) : 227.02729 + Atomic weight ratio (AWR) : 225.07700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.62E+06 seconds (18.7 days) + Specific ingestion toxicity : 8.80E-09 Sv/Bq + Specific inhalation toxicity : 1.00E-05 Sv/Bq + Energy deposited per fission : 208.83 MeV + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has delayed neutron data in 8 precursor groups + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide is using NFY data from U-233 + - Nuclide has no SFY data + + - 7 reaction channels + - 2 special reactions + - 5 transmutation reactions + - 2 transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 7 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.45439E+00 MeV Emin = 5.47862E+00 MeV frac = 1.00000E+00 Product nuclide = 902260 : (n,2n) + 3 MT = 17 Q = -1.26401E+01 MeV Emin = 1.26963E+01 MeV frac = 1.00000E+00 Product nuclide = 902250 : (n,3n) + 4 MT = 18 Q = 1.99999E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : total fission + 5 MT = 37 Q = -1.84018E+01 MeV Emin = 1.84836E+01 MeV frac = 1.00000E+00 Product nuclide = 902240 : (n,4n) + 6 MT = 91 Q = -2.45000E-02 MeV Emin = 2.34567E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 7 MT = 102 Q = 7.12869E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 90228.82c : (n,gamma) + + 2 additional transport branches: + + 1 MT = 18 Q = 1.99999E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 1.40000E+01 MeV) : total fission + 2 MT = 18 Q = 1.99999E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 2.34567E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 4 Q = 6.14643E+00 MeV frac = 1.00000E+00 Product nuclide = 882230 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 6.14643E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 271 / 1657 : 90228.82c -- thorium 228 (Th-228) + + Pointers : 2319326 35013 + Primary type : Transport + Nuclide ZAI : 902280 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Th228.ACE + Atomic weight (AW) : 228.02889 + Atomic weight ratio (AWR) : 226.07000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 6.04E+07 seconds (1.91 years) + Specific ingestion toxicity : 7.20E-08 Sv/Bq + Specific inhalation toxicity : 4.00E-05 Sv/Bq + Energy deposited per fission : 193.16 MeV + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide is using NFY data from U-233 + - Nuclide has no SFY data + + - 18 reaction channels + - 2 special reactions + - 4 transmutation reactions + - 2 transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 18 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.11998E+00 MeV Emin = 7.15149E+00 MeV frac = 1.00000E+00 Product nuclide = 90227.82c : (n,2n) + 3 MT = 17 Q = -1.25744E+01 MeV Emin = 1.26300E+01 MeV frac = 1.00000E+00 Product nuclide = 902260 : (n,3n) + 4 MT = 18 Q = 1.84999E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : total fission + 5 MT = 51 Q = -5.75999E-02 MeV Emin = 5.39274E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -1.86900E-01 MeV Emin = 1.87500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -3.28000E-01 MeV Emin = 3.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -3.96099E-01 MeV Emin = 3.86426E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -5.19299E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -8.31699E-01 MeV Emin = 8.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -8.74599E-01 MeV Emin = 8.75000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -9.44099E-01 MeV Emin = 9.36638E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -9.51999E-01 MeV Emin = 9.53106E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -9.68798E-01 MeV Emin = 9.64668E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -1.01600E+00 MeV Emin = 1.02000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -1.02240E+00 MeV Emin = 1.02537E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 91 Q = -1.02500E+00 MeV Emin = 1.02823E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 18 MT = 102 Q = 5.24879E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 90229.82c : (n,gamma) + + 2 additional transport branches: + + 1 MT = 18 Q = 1.84999E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 1.40000E+01 MeV) : total fission + 2 MT = 18 Q = 1.84999E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 5.39274E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 4 Q = 5.52008E+00 MeV frac = 1.00000E+00 Product nuclide = 882240 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.52008E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 272 / 1657 : 90229.82c -- thorium 229 (Th-229) + + Pointers : 2349973 35059 + Primary type : Transport + Nuclide ZAI : 902290 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Th229.ACE + Atomic weight (AW) : 229.03150 + Atomic weight ratio (AWR) : 227.06400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.32E+11 seconds (7,345 years) + Specific ingestion toxicity : 4.90E-07 Sv/Bq + Specific inhalation toxicity : 2.40E-04 Sv/Bq + Energy deposited per fission : 208.83 MeV + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has delayed neutron data in 8 precursor groups + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide is using NFY data from U-233 + - Nuclide has no SFY data + + - 11 reaction channels + - 2 special reactions + - 5 transmutation reactions + - 2 transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 11 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.24879E+00 MeV Emin = 5.27191E+00 MeV frac = 1.00000E+00 Product nuclide = 90228.82c : (n,2n) + 3 MT = 17 Q = -1.23688E+01 MeV Emin = 1.24233E+01 MeV frac = 1.00000E+00 Product nuclide = 90227.82c : (n,3n) + 4 MT = 18 Q = 1.99999E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : total fission + 5 MT = 37 Q = -1.78232E+01 MeV Emin = 1.79017E+01 MeV frac = 1.00000E+00 Product nuclide = 902260 : (n,4n) + 6 MT = 51 Q = -1.00000E-04 MeV Emin = 9.43750E-05 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -2.00000E-02 MeV Emin = 2.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -2.92000E-02 MeV Emin = 2.84623E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -4.24999E-02 MeV Emin = 4.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 91 Q = -6.69999E-02 MeV Emin = 6.46036E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 11 MT = 102 Q = 6.78969E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 90230.82c : (n,gamma) + + 2 additional transport branches: + + 1 MT = 18 Q = 1.99999E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 1.40000E+01 MeV) : total fission + 2 MT = 18 Q = 1.99999E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 9.43750E-05 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 4 Q = 5.16860E+00 MeV frac = 1.00000E+00 Product nuclide = 882250 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.16860E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 273 / 1657 : 90230.82c -- thorium 230 (Th-230) + + Pointers : 2381425 35105 + Primary type : Transport + Nuclide ZAI : 902300 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Th230.ACE + Atomic weight (AW) : 230.03613 + Atomic weight ratio (AWR) : 228.06000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.38E+12 seconds (75,452 years) + Specific ingestion toxicity : 2.10E-07 Sv/Bq + Specific inhalation toxicity : 1.00E-04 Sv/Bq + Energy deposited per fission : 198.85 MeV + Spontaneous fission nubar : 1.39000 + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide is using NFY data from U-233 + - Nuclide has no SFY data + + - 23 reaction channels + - 2 special reactions + - 4 transmutation reactions + - 2 transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 23 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.79110E+00 MeV Emin = 6.82088E+00 MeV frac = 1.00000E+00 Product nuclide = 90229.82c : (n,2n) + 3 MT = 17 Q = -1.20400E+01 MeV Emin = 1.20930E+01 MeV frac = 1.00000E+00 Product nuclide = 90228.82c : (n,3n) + 4 MT = 18 Q = 1.90442E+02 MeV Emin = 2.45654E-04 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : total fission + 5 MT = 51 Q = -5.27690E-02 MeV Emin = 5.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -1.73240E-01 MeV Emin = 1.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -3.55440E-01 MeV Emin = 3.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -5.04790E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -5.69500E-01 MeV Emin = 5.39502E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -6.30240E-01 MeV Emin = 6.02500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -6.74040E-01 MeV Emin = 6.55002E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -6.79020E-01 MeV Emin = 6.79500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -7.67630E-01 MeV Emin = 7.35500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -7.77590E-01 MeV Emin = 7.76000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -8.26380E-01 MeV Emin = 8.05500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -8.48280E-01 MeV Emin = 8.41002E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 63 Q = -8.77150E-01 MeV Emin = 8.52000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 18 MT = 64 Q = -9.29920E-01 MeV Emin = 9.07500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 19 MT = 65 Q = -9.47840E-01 MeV Emin = 9.43000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 20 MT = 66 Q = -9.49840E-01 MeV Emin = 9.53000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 21 MT = 67 Q = -9.68750E-01 MeV Emin = 9.63503E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 22 MT = 91 Q = -9.95630E-01 MeV Emin = 9.86500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 23 MT = 102 Q = 5.12100E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 902310 : (n,gamma) + + 2 additional transport branches: + + 1 MT = 18 Q = 1.90442E+02 MeV Emin = 2.45654E-04 MeV frac = 1.00000E+00 NFY (E = 1.40000E+01 MeV) : total fission + 2 MT = 18 Q = 1.90442E+02 MeV Emin = 2.45654E-04 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 5.00000E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 4 Q = 4.77060E+00 MeV frac = 1.00000E+00 Product nuclide = 882260 : alpha + 2 RTYP = 6 Q = 1.69700E+02 MeV frac = 2.50000E-13 SF without yield : spontaneous fission + + 1 additional decay branch: + + 1 RTYP = 4 Q = 4.77060E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 274 / 1657 : 91231.82c -- protactinium 231 (Pa-231) + + Pointers : 2420509 29539 + Primary type : Transport + Nuclide ZAI : 912310 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Pa231.ACE + Atomic weight (AW) : 231.03471 + Atomic weight ratio (AWR) : 229.05000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.03E+12 seconds (32,783 years) + Specific ingestion toxicity : 7.10E-07 Sv/Bq + Specific inhalation toxicity : 1.40E-04 Sv/Bq + Energy deposited per fission : 208.83 MeV + Spontaneous fission nubar : 1.71000 + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has delayed neutron data in 8 precursor groups + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide is using NFY data from U-233 + - Nuclide has no SFY data + + - 18 reaction channels + - 2 special reactions + - 4 transmutation reactions + - 2 transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 18 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.81380E+00 MeV Emin = 6.84360E+00 MeV frac = 1.00000E+00 Product nuclide = 912300 : (n,2n) + 3 MT = 17 Q = -1.26060E+01 MeV Emin = 1.26610E+01 MeV frac = 1.00000E+00 Product nuclide = 912290 : (n,3n) + 4 MT = 18 Q = 2.00000E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : total fission + 5 MT = 51 Q = -8.96090E-03 MeV Emin = 5.00000E-03 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -5.77480E-02 MeV Emin = 5.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -7.76610E-02 MeV Emin = 6.80001E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -8.46310E-02 MeV Emin = 8.15000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -1.00560E-01 MeV Emin = 1.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -1.01560E-01 MeV Emin = 1.01500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -1.11510E-01 MeV Emin = 1.07002E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -1.33420E-01 MeV Emin = 1.23000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -1.71250E-01 MeV Emin = 1.53001E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -1.73240E-01 MeV Emin = 1.72000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -1.83200E-01 MeV Emin = 1.79000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -1.88180E-01 MeV Emin = 1.86500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 91 Q = -2.98700E-01 MeV Emin = 2.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 18 MT = 102 Q = 5.56100E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 91232.82c : (n,gamma) + + 2 additional transport branches: + + 1 MT = 18 Q = 2.00000E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 1.40000E+01 MeV) : total fission + 2 MT = 18 Q = 2.00000E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 5.00000E-03 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 4 Q = 5.14820E+00 MeV frac = 1.00000E+00 Product nuclide = 892270 : alpha + 2 RTYP = 6 Q = 1.77100E+02 MeV frac = 3.00000E-12 SF without yield : spontaneous fission + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.14820E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 275 / 1657 : 91232.82c -- protactinium 232 (Pa-232) + + Pointers : 2453838 29585 + Primary type : Transport + Nuclide ZAI : 912320 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Pa232.ACE + Atomic weight (AW) : 232.03833 + Atomic weight ratio (AWR) : 230.04500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.13E+05 seconds (1.31 days) + Specific ingestion toxicity : 7.20E-10 Sv/Bq + Specific inhalation toxicity : 1.00E-08 Sv/Bq + Energy deposited per fission : 208.83 MeV + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide is using NFY data from U-233 + - Nuclide has no SFY data + + - 7 reaction channels + - 2 special reactions + - 5 transmutation reactions + - 2 transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 7 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.56079E+00 MeV Emin = 5.58500E+00 MeV frac = 1.00000E+00 Product nuclide = 91231.82c : (n,2n) + 3 MT = 17 Q = -1.23749E+01 MeV Emin = 1.24287E+01 MeV frac = 1.00000E+00 Product nuclide = 912300 : (n,3n) + 4 MT = 18 Q = 1.99999E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : total fission + 5 MT = 37 Q = -1.81681E+01 MeV Emin = 1.82471E+01 MeV frac = 1.00000E+00 Product nuclide = 912290 : (n,4n) + 6 MT = 91 Q = -4.99999E-02 MeV Emin = 5.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 7 MT = 102 Q = 6.51669E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 91233.82c : (n,gamma) + + 2 additional transport branches: + + 1 MT = 18 Q = 1.99999E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 1.40000E+01 MeV) : total fission + 2 MT = 18 Q = 1.99999E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 5.00000E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.33700E+00 MeV frac = 9.99970E-01 Product nuclide = 92232.82c : beta- + 2 RTYP = 2 Q = 4.80000E-01 MeV frac = 3.00000E-05 Product nuclide = 902320 : EC/beta+ + + Nuclide 276 / 1657 : 91233.82c -- protactinium 233 (Pa-233) + + Pointers : 2484998 29631 + Primary type : Transport + Nuclide ZAI : 912330 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Pa233.ACE + Atomic weight (AW) : 233.03994 + Atomic weight ratio (AWR) : 231.03800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.33E+06 seconds (27 days) + Specific ingestion toxicity : 8.70E-10 Sv/Bq + Specific inhalation toxicity : 3.90E-09 Sv/Bq + Energy deposited per fission : 203.98 MeV + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide is using NFY data from Th-232 + - Nuclide has no SFY data + + - 11 reaction channels + - 2 special reactions + - 4 transmutation reactions + - 2 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 11 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.65560E+00 MeV Emin = 6.68441E+00 MeV frac = 1.00000E+00 Product nuclide = 91232.82c : (n,2n) + 3 MT = 17 Q = -1.21790E+01 MeV Emin = 1.22322E+01 MeV frac = 1.00000E+00 Product nuclide = 91231.82c : (n,3n) + 4 MT = 18 Q = 1.95361E+02 MeV Emin = 4.60000E-01 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + 5 MT = 51 Q = -1.87000E-02 MeV Emin = 1.80000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -5.69000E-02 MeV Emin = 5.50000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -7.12000E-02 MeV Emin = 7.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -8.68000E-02 MeV Emin = 8.50000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -1.04000E-01 MeV Emin = 1.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 91 Q = -1.99140E-01 MeV Emin = 1.80000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 11 MT = 102 Q = 5.19700E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 912340 : (n,gamma) + + 2 additional transport branches: + + 1 MT = 18 Q = 1.95361E+02 MeV Emin = 4.60000E-01 MeV frac = 1.00000E+00 NFY (E = 1.40000E+01 MeV) : total fission + 2 MT = 102 Q = 5.19700E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 912341 : (n,gamma) + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 1.80000E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.70100E-01 MeV frac = 1.00000E+00 Product nuclide = 92233.82c : beta- + + Nuclide 277 / 1657 : 92232.82c -- uranium 232 (U-232) + + Pointers : 2528048 35565 + Primary type : Transport + Nuclide ZAI : 922320 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/U232.ACE + Atomic weight (AW) : 232.03329 + Atomic weight ratio (AWR) : 230.04000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.20E+09 seconds (69.8 years) + Specific ingestion toxicity : 3.30E-07 Sv/Bq + Specific inhalation toxicity : 3.70E-05 Sv/Bq + Energy deposited per fission : 208.83 MeV + Spontaneous fission nubar : 1.71000 + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has delayed neutron data in 8 precursor groups + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide is using NFY data from U-233 + - Nuclide has no SFY data + + - 19 reaction channels + - 2 special reactions + - 4 transmutation reactions + - 2 transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 19 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.26000E+00 MeV Emin = 7.29160E+00 MeV frac = 1.00000E+00 Product nuclide = 922310 : (n,2n) + 3 MT = 17 Q = -1.31530E+01 MeV Emin = 1.32102E+01 MeV frac = 1.00000E+00 Product nuclide = 922300 : (n,3n) + 4 MT = 18 Q = 2.00000E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : total fission + 5 MT = 51 Q = -4.77920E-02 MeV Emin = 4.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -1.56320E-01 MeV Emin = 1.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -3.20610E-01 MeV Emin = 3.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -5.60560E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -6.26280E-01 MeV Emin = 5.96000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -6.88010E-01 MeV Emin = 6.60001E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -7.06930E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -7.31820E-01 MeV Emin = 7.22502E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -8.31390E-01 MeV Emin = 7.85001E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -8.63250E-01 MeV Emin = 8.51002E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -9.08050E-01 MeV Emin = 8.89501E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -9.66800E-01 MeV Emin = 9.41500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 63 Q = -9.82730E-01 MeV Emin = 9.79001E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 18 MT = 91 Q = -9.95670E-01 MeV Emin = 9.93501E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 19 MT = 102 Q = 5.75400E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 92233.82c : (n,gamma) + + 2 additional transport branches: + + 1 MT = 18 Q = 2.00000E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 1.40000E+01 MeV) : total fission + 2 MT = 18 Q = 2.00000E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 4.00000E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 4 Q = 5.41362E+00 MeV frac = 1.00000E+00 Product nuclide = 90228.82c : alpha + 2 RTYP = 6 Q = 1.76600E+02 MeV frac = 9.00000E-13 SF without yield : spontaneous fission + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.41362E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 278 / 1657 : 92233.82c -- uranium 233 (U-233) + + Pointers : 2558888 35611 + Primary type : Transport + Nuclide ZAI : 922330 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/U233.ACE + Atomic weight (AW) : 233.03994 + Atomic weight ratio (AWR) : 231.03800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 5.03E+12 seconds (159,359 years) + Specific ingestion toxicity : 5.10E-08 Sv/Bq + Specific inhalation toxicity : 9.60E-06 Sv/Bq + Energy deposited per fission : 199.27 MeV + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has delayed neutron data in 8 precursor groups + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has NFY data + - Nuclide has no SFY data + + - 25 reaction channels + - 2 special reactions + - 4 transmutation reactions + - 2 transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 25 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.75369E+00 MeV Emin = 5.77860E+00 MeV frac = 1.00000E+00 Product nuclide = 92232.82c : (n,2n) + 3 MT = 17 Q = -1.30080E+01 MeV Emin = 1.30645E+01 MeV frac = 1.00000E+00 Product nuclide = 922310 : (n,3n) + 4 MT = 18 Q = 1.90850E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : total fission + 5 MT = 51 Q = -4.03999E-02 MeV Emin = 4.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -9.21999E-02 MeV Emin = 9.25000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -1.55100E-01 MeV Emin = 1.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -2.28000E-01 MeV Emin = 2.26993E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -2.98800E-01 MeV Emin = 3.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -3.11900E-01 MeV Emin = 3.10000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -3.18000E-01 MeV Emin = 3.17079E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -3.20000E-01 MeV Emin = 3.20692E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -3.20800E-01 MeV Emin = 3.21938E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -3.40500E-01 MeV Emin = 3.40000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -3.53700E-01 MeV Emin = 3.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -3.96999E-01 MeV Emin = 3.90000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 63 Q = -3.98499E-01 MeV Emin = 4.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 18 MT = 64 Q = -4.15799E-01 MeV Emin = 4.13800E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 19 MT = 65 Q = -4.24999E-01 MeV Emin = 4.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 20 MT = 66 Q = -5.03899E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 21 MT = 67 Q = -5.46699E-01 MeV Emin = 5.40000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 22 MT = 68 Q = -5.59999E-01 MeV Emin = 5.60000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 23 MT = 69 Q = -5.97099E-01 MeV Emin = 5.90000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 24 MT = 91 Q = -5.99999E-01 MeV Emin = 6.01298E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 25 MT = 102 Q = 6.84380E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 92234.82c : (n,gamma) + + 2 additional transport branches: + + 1 MT = 18 Q = 1.90850E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 1.40000E+01 MeV) : total fission + 2 MT = 18 Q = 1.90850E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 4.00000E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 4 Q = 4.90890E+00 MeV frac = 1.00000E+00 Product nuclide = 90229.82c : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 4.90890E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 279 / 1657 : 92234.82c -- uranium 234 (U-234) + + Pointers : 2594414 35657 + Primary type : Transport + Nuclide ZAI : 922340 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/U234.ACE + Atomic weight (AW) : 234.04053 + Atomic weight ratio (AWR) : 232.03000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 7.75E+12 seconds (245,868 years) + Specific ingestion toxicity : 4.90E-08 Sv/Bq + Specific inhalation toxicity : 9.40E-06 Sv/Bq + Energy deposited per fission : 198.70 MeV + Spontaneous fission nubar : 1.80000 + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has delayed neutron data in 8 precursor groups + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has NFY data + - Nuclide has no SFY data + + - 45 reaction channels + - 2 special reactions + - 7 transmutation reactions + - 1 transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 45 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.84320E+00 MeV Emin = 6.87269E+00 MeV frac = 1.00000E+00 Product nuclide = 92233.82c : (n,2n) + 3 MT = 17 Q = -1.25872E+01 MeV Emin = 1.26415E+01 MeV frac = 1.00000E+00 Product nuclide = 92232.82c : (n,3n) + 4 MT = 19 Q = 1.90300E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : (n,f) + 5 MT = 20 Q = 1.90300E+02 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : (n,nf) + 6 MT = 21 Q = 1.90300E+02 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : (n,2nf) + 7 MT = 38 Q = 1.90300E+02 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : (n,3nf) + 8 MT = 51 Q = -4.34980E-02 MeV Emin = 4.25000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -1.43350E-01 MeV Emin = 1.41982E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -2.96070E-01 MeV Emin = 2.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -4.97040E-01 MeV Emin = 4.99164E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -7.41200E-01 MeV Emin = 8.13370E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -7.86290E-01 MeV Emin = 7.44368E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -8.09880E-01 MeV Emin = 8.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -8.49300E-01 MeV Emin = 8.33150E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -8.51700E-01 MeV Emin = 8.54150E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -9.26740E-01 MeV Emin = 9.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -9.47850E-01 MeV Emin = 9.41318E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 62 Q = -9.62600E-01 MeV Emin = 9.59325E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 20 MT = 63 Q = -9.68600E-01 MeV Emin = 9.69744E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 21 MT = 64 Q = -9.89450E-01 MeV Emin = 9.83226E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 22 MT = 65 Q = -1.02370E+00 MeV Emin = 1.01404E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 23 MT = 66 Q = -1.02380E+00 MeV Emin = 1.30556E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 24 MT = 67 Q = -1.02383E+00 MeV Emin = 1.02807E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 25 MT = 68 Q = -1.04450E+00 MeV Emin = 1.03862E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 26 MT = 69 Q = -1.06930E+00 MeV Emin = 1.06144E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 27 MT = 70 Q = -1.08530E+00 MeV Emin = 1.08193E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 28 MT = 71 Q = -1.09090E+00 MeV Emin = 1.09277E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 29 MT = 72 Q = -1.09590E+00 MeV Emin = 1.09809E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 30 MT = 73 Q = -1.12520E+00 MeV Emin = 1.11533E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 31 MT = 74 Q = -1.12670E+00 MeV Emin = 1.13077E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 32 MT = 75 Q = -1.12760E+00 MeV Emin = 1.13222E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 33 MT = 76 Q = -1.15000E+00 MeV Emin = 1.14369E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 34 MT = 77 Q = -1.16520E+00 MeV Emin = 1.16257E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 27. excited state + 35 MT = 78 Q = -1.17210E+00 MeV Emin = 1.17367E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 28. excited state + 36 MT = 79 Q = -1.17420E+00 MeV Emin = 1.17819E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 29. excited state + 37 MT = 80 Q = -1.19470E+00 MeV Emin = 1.18955E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 30. excited state + 38 MT = 81 Q = -1.21460E+00 MeV Emin = 1.20989E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 31. excited state + 39 MT = 82 Q = -1.23720E+00 MeV Emin = 1.23118E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 32. excited state + 40 MT = 83 Q = -1.26180E+00 MeV Emin = 1.25488E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 33. excited state + 41 MT = 84 Q = -1.27440E+00 MeV Emin = 1.27353E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 34. excited state + 42 MT = 85 Q = -1.27750E+00 MeV Emin = 1.28142E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 35. excited state + 43 MT = 86 Q = -1.29260E+00 MeV Emin = 1.29056E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 36. excited state + 44 MT = 91 Q = -1.30000E+00 MeV Emin = 1.30187E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 45 MT = 102 Q = 5.29790E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 92235.82c : (n,gamma) + + 1 additional transport branch: + + 1 MT = 102 Q = 5.29790E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 922351 : (n,gamma) + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 4.25000E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 4 Q = 4.85790E+00 MeV frac = 1.00000E+00 Product nuclide = 90230.82c : alpha + 2 RTYP = 6 Q = 1.76100E+02 MeV frac = 1.70000E-11 SF without yield : spontaneous fission + + 1 additional decay branch: + + 1 RTYP = 4 Q = 4.85790E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 280 / 1657 : 92235.82c -- uranium 235 (U-235) + + Pointers : 2606584 35703 + Primary type : Transport + Nuclide ZAI : 922350 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/U235.ACE + Atomic weight (AW) : 235.04415 + Atomic weight ratio (AWR) : 233.02500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.22E+16 seconds (704 million years) + Specific ingestion toxicity : 4.70E-08 Sv/Bq + Specific inhalation toxicity : 8.50E-06 Sv/Bq + Energy deposited per fission : 202.27 MeV + Spontaneous fission nubar : 1.87000 + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has delayed neutron data in 8 precursor groups + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has NFY data + - Nuclide has no SFY data + + - 41 reaction channels + - 2 special reactions + - 5 transmutation reactions + - 2 transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 41 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.29778E+00 MeV Emin = 5.32052E+00 MeV frac = 1.00000E+00 Product nuclide = 92234.82c : (n,2n) + 3 MT = 17 Q = -1.21423E+01 MeV Emin = 1.21944E+01 MeV frac = 1.00000E+00 Product nuclide = 92233.82c : (n,3n) + 4 MT = 18 Q = 1.93720E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : total fission + 5 MT = 37 Q = -1.78856E+01 MeV Emin = 1.79624E+01 MeV frac = 1.00000E+00 Product nuclide = 92232.82c : (n,4n) + 6 MT = 51 Q = -7.68000E-05 MeV Emin = 2.24303E-03 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.30400E-02 MeV Emin = 1.28000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -4.62000E-02 MeV Emin = 4.60000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -5.17010E-02 MeV Emin = 5.15000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -8.17000E-02 MeV Emin = 8.20000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -1.03000E-01 MeV Emin = 1.01717E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -1.29300E-01 MeV Emin = 1.20000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -1.50500E-01 MeV Emin = 1.50630E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -1.70700E-01 MeV Emin = 1.70000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -1.71400E-01 MeV Emin = 1.71718E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -1.97100E-01 MeV Emin = 1.97827E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -2.25400E-01 MeV Emin = 2.25945E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -2.49100E-01 MeV Emin = 2.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -2.91400E-01 MeV Emin = 2.80000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -2.94700E-01 MeV Emin = 2.94305E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 21 MT = 66 Q = -3.32800E-01 MeV Emin = 3.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 22 MT = 67 Q = -3.38500E-01 MeV Emin = 3.37175E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 23 MT = 68 Q = -3.57300E-01 MeV Emin = 3.54111E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 24 MT = 69 Q = -3.67100E-01 MeV Emin = 3.68541E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 25 MT = 70 Q = -3.93200E-01 MeV Emin = 3.81785E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 26 MT = 71 Q = -4.14800E-01 MeV Emin = 4.15739E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 27 MT = 72 Q = -4.26700E-01 MeV Emin = 4.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 28 MT = 73 Q = -4.30000E-01 MeV Emin = 4.30317E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 29 MT = 74 Q = -4.38500E-01 MeV Emin = 4.36113E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 30 MT = 75 Q = -4.45700E-01 MeV Emin = 4.43996E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 31 MT = 76 Q = -4.74300E-01 MeV Emin = 4.75991E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 32 MT = 77 Q = -5.50000E-01 MeV Emin = 5.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 27. excited state + 33 MT = 78 Q = -6.50000E-01 MeV Emin = 6.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 28. excited state + 34 MT = 79 Q = -7.70000E-01 MeV Emin = 7.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 29. excited state + 35 MT = 80 Q = -9.00000E-01 MeV Emin = 9.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 30. excited state + 36 MT = 81 Q = -1.04000E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 31. excited state + 37 MT = 82 Q = -1.08500E+00 MeV Emin = 1.06708E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 32. excited state + 38 MT = 83 Q = -1.33000E+00 MeV Emin = 1.30000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 33. excited state + 39 MT = 84 Q = -1.43000E+00 MeV Emin = 1.40000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 34. excited state + 40 MT = 91 Q = -4.97864E-01 MeV Emin = 4.88170E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 41 MT = 102 Q = 6.54520E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 92236.82c : (n,gamma) + + 2 additional transport branches: + + 1 MT = 18 Q = 1.93720E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 1.40000E+01 MeV) : total fission + 2 MT = 18 Q = 1.93720E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 2.24303E-03 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 4 Q = 4.67870E+00 MeV frac = 1.00000E+00 Product nuclide = 902310 : alpha + 2 RTYP = 6 Q = 1.76400E+02 MeV frac = 7.20000E-11 SF without yield : spontaneous fission + + 1 additional decay branch: + + 1 RTYP = 4 Q = 4.67870E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 281 / 1657 : 92236.82c -- uranium 236 (U-236) + + Pointers : 2639462 35749 + Primary type : Transport + Nuclide ZAI : 922360 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/U236.ACE + Atomic weight (AW) : 236.04556 + Atomic weight ratio (AWR) : 234.01780 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 3.00000E+01 + Half-life : 7.48E+14 seconds (23.7 million years) + Specific ingestion toxicity : 4.70E-08 Sv/Bq + Specific inhalation toxicity : 8.70E-06 Sv/Bq + Energy deposited per fission : 206.68 MeV + Spontaneous fission nubar : 1.90000 + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has delayed neutron data in 8 precursor groups + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has NFY data + - Nuclide has no SFY data + + - 38 reaction channels + - 2 special reactions + - 5 transmutation reactions + - 1 transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 38 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.54520E+00 MeV Emin = 6.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 92235.82c : (n,2n) + 3 MT = 17 Q = -1.18430E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 92234.82c : (n,3n) + 4 MT = 18 Q = 1.97939E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : total fission + 5 MT = 37 Q = -1.86874E+01 MeV Emin = 1.90000E+01 MeV frac = 1.00000E+00 Product nuclide = 92233.82c : (n,4n) + 6 MT = 51 Q = -4.52420E-02 MeV Emin = 4.51800E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.49476E-01 MeV Emin = 1.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -3.09784E-01 MeV Emin = 3.10000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -5.22240E-01 MeV Emin = 5.20000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -6.87600E-01 MeV Emin = 6.90000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -7.44150E-01 MeV Emin = 7.40000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -7.82300E-01 MeV Emin = 7.90000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -8.48300E-01 MeV Emin = 8.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -9.19210E-01 MeV Emin = 9.20000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -9.57990E-01 MeV Emin = 9.60000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -9.60300E-01 MeV Emin = 9.63244E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -9.66630E-01 MeV Emin = 9.70000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -9.87670E-01 MeV Emin = 9.90000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -9.99800E-01 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -1.00150E+00 MeV Emin = 1.00493E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 21 MT = 66 Q = -1.03560E+00 MeV Emin = 1.02290E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 22 MT = 67 Q = -1.05085E+00 MeV Emin = 1.04768E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 23 MT = 68 Q = -1.05289E+00 MeV Emin = 1.05688E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 24 MT = 69 Q = -1.05861E+00 MeV Emin = 1.06026E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 25 MT = 70 Q = -1.06610E+00 MeV Emin = 1.06690E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 26 MT = 71 Q = -1.07000E+00 MeV Emin = 1.07262E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 27 MT = 72 Q = -1.08530E+00 MeV Emin = 1.09924E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 28 MT = 73 Q = -1.09380E+00 MeV Emin = 1.09250E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 29 MT = 74 Q = -1.10440E+00 MeV Emin = 1.10456E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 30 MT = 75 Q = -1.11067E+00 MeV Emin = 1.11227E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 31 MT = 76 Q = -1.12690E+00 MeV Emin = 1.12357E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 32 MT = 77 Q = -1.14700E+00 MeV Emin = 1.14181E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 27. excited state + 33 MT = 78 Q = -1.14940E+00 MeV Emin = 1.15311E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 28. excited state + 34 MT = 79 Q = -1.16400E+00 MeV Emin = 1.16164E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 29. excited state + 35 MT = 80 Q = -1.17180E+00 MeV Emin = 1.17289E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 30. excited state + 36 MT = 81 Q = -1.19860E+00 MeV Emin = 1.20000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 31. excited state + 37 MT = 91 Q = -1.20000E+00 MeV Emin = 1.20443E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 38 MT = 102 Q = 5.12580E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 92237.82c : (n,gamma) + + 1 additional transport branch: + + 1 MT = 18 Q = 1.97939E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 4.51800E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 4 Q = 4.57200E+00 MeV frac = 1.00000E+00 Product nuclide = 902320 : alpha + 2 RTYP = 6 Q = 1.75600E+02 MeV frac = 9.00000E-10 SF without yield : spontaneous fission + + 1 additional decay branch: + + 1 RTYP = 4 Q = 4.57200E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 282 / 1657 : 92237.82c -- uranium 237 (U-237) + + Pointers : 2657840 35795 + Primary type : Transport + Nuclide ZAI : 922370 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/U237.ACE + Atomic weight (AW) : 237.04878 + Atomic weight ratio (AWR) : 235.01240 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 3.00000E+01 + Half-life : 5.83E+05 seconds (6.75 days) + Specific ingestion toxicity : 7.60E-10 Sv/Bq + Specific inhalation toxicity : 1.90E-09 Sv/Bq + Energy deposited per fission : 208.83 MeV + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has delayed neutron data in 8 precursor groups + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide is using NFY data from Np-238 + - Nuclide has no SFY data + + - 41 reaction channels + - 2 special reactions + - 5 transmutation reactions + - 1 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 41 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.12580E+00 MeV Emin = 5.20000E+00 MeV frac = 1.00000E+00 Product nuclide = 92236.82c : (n,2n) + 3 MT = 17 Q = -1.16710E+01 MeV Emin = 1.18000E+01 MeV frac = 1.00000E+00 Product nuclide = 92235.82c : (n,3n) + 4 MT = 18 Q = 2.00000E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : total fission + 5 MT = 37 Q = -1.69687E+01 MeV Emin = 1.70409E+01 MeV frac = 1.00000E+00 Product nuclide = 92234.82c : (n,4n) + 6 MT = 51 Q = -1.13900E-02 MeV Emin = 1.07192E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -5.63000E-02 MeV Emin = 5.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -8.28600E-02 MeV Emin = 8.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -1.59960E-01 MeV Emin = 1.60000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -1.63000E-01 MeV Emin = 1.62167E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -2.04190E-01 MeV Emin = 2.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -2.05000E-01 MeV Emin = 2.05669E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -2.60950E-01 MeV Emin = 2.60000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -2.74000E-01 MeV Emin = 2.70000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -3.16000E-01 MeV Emin = 3.10000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -3.27000E-01 MeV Emin = 3.24196E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -3.67000E-01 MeV Emin = 3.60000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -4.26150E-01 MeV Emin = 4.20000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -4.32000E-01 MeV Emin = 4.30000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -4.82000E-01 MeV Emin = 4.80000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 21 MT = 66 Q = -4.84000E-01 MeV Emin = 4.85055E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 22 MT = 67 Q = -5.06000E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 23 MT = 68 Q = -5.30000E-01 MeV Emin = 5.30000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 24 MT = 69 Q = -5.40620E-01 MeV Emin = 5.40000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 25 MT = 70 Q = -5.45000E-01 MeV Emin = 5.45120E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 26 MT = 71 Q = -5.51000E-01 MeV Emin = 5.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 27 MT = 72 Q = -5.54980E-01 MeV Emin = 5.55343E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 28 MT = 73 Q = -5.75000E-01 MeV Emin = 5.80000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 29 MT = 74 Q = -5.78010E-01 MeV Emin = 5.80000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 30 MT = 75 Q = -6.32000E-01 MeV Emin = 6.30000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 31 MT = 76 Q = -6.57000E-01 MeV Emin = 6.60000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 32 MT = 77 Q = -6.64270E-01 MeV Emin = 6.63548E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 27. excited state + 33 MT = 78 Q = -6.66450E-01 MeV Emin = 6.68191E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 28. excited state + 34 MT = 79 Q = -6.77590E-01 MeV Emin = 6.80000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 29. excited state + 35 MT = 80 Q = -6.88000E-01 MeV Emin = 6.90000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 30. excited state + 36 MT = 81 Q = -6.97650E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 31. excited state + 37 MT = 82 Q = -6.98000E-01 MeV Emin = 7.00882E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 32. excited state + 38 MT = 83 Q = -7.18000E-01 MeV Emin = 7.49375E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 33. excited state + 39 MT = 84 Q = -7.20450E-01 MeV Emin = 7.21055E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 34. excited state + 40 MT = 91 Q = -7.21450E-01 MeV Emin = 7.27260E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 41 MT = 102 Q = 6.15280E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 92238.82c : (n,gamma) + + 1 additional transport branch: + + 1 MT = 18 Q = 2.00000E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 1.07192E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.18600E-01 MeV frac = 1.00000E+00 Product nuclide = 93237.82c : beta- + + Nuclide 283 / 1657 : 92238.82c -- uranium 238 (U-238) + + Pointers : 2680079 35841 + Primary type : Transport + Nuclide ZAI : 922380 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/U238.ACE + Atomic weight (AW) : 238.05078 + Atomic weight ratio (AWR) : 236.00580 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 3.00000E+01 + Half-life : 1.41E+17 seconds (4.47 billion years) + Specific ingestion toxicity : 4.50E-08 Sv/Bq + Specific inhalation toxicity : 8.00E-06 Sv/Bq + Energy deposited per fission : 206.02 MeV + Spontaneous fission nubar : 2.00000 + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has delayed neutron data in 8 precursor groups + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has NFY data + - Nuclide has no SFY data + + - 47 reaction channels + - 2 special reactions + - 5 transmutation reactions + - 1 transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 47 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.15280E+00 MeV Emin = 6.20000E+00 MeV frac = 1.00000E+00 Product nuclide = 92237.82c : (n,2n) + 3 MT = 17 Q = -1.12786E+01 MeV Emin = 1.14000E+01 MeV frac = 1.00000E+00 Product nuclide = 92236.82c : (n,3n) + 4 MT = 18 Q = 1.97314E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + 5 MT = 37 Q = -1.78237E+01 MeV Emin = 1.80000E+01 MeV frac = 1.00000E+00 Product nuclide = 92235.82c : (n,4n) + 6 MT = 51 Q = -4.49100E-02 MeV Emin = 4.50000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.48410E-01 MeV Emin = 1.40000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -3.07200E-01 MeV Emin = 2.99251E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -5.17800E-01 MeV Emin = 5.10000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -6.80100E-01 MeV Emin = 6.80000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -7.31900E-01 MeV Emin = 7.30000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -7.75700E-01 MeV Emin = 7.70000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -8.26700E-01 MeV Emin = 8.30000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -9.27200E-01 MeV Emin = 9.30000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -9.30500E-01 MeV Emin = 9.32786E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -9.49900E-01 MeV Emin = 9.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -9.66300E-01 MeV Emin = 9.70000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -9.67300E-01 MeV Emin = 9.70395E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -9.93000E-01 MeV Emin = 9.90000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -9.97500E-01 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 21 MT = 66 Q = -1.03730E+00 MeV Emin = 1.02171E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 22 MT = 67 Q = -1.05500E+00 MeV Emin = 1.05058E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 23 MT = 68 Q = -1.05950E+00 MeV Emin = 1.06173E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 24 MT = 69 Q = -1.06020E+00 MeV Emin = 1.06452E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 25 MT = 70 Q = -1.07650E+00 MeV Emin = 1.07288E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 26 MT = 71 Q = -1.10560E+00 MeV Emin = 1.10000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 27 MT = 72 Q = -1.10700E+00 MeV Emin = 1.11152E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 28 MT = 73 Q = -1.12700E+00 MeV Emin = 1.12173E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 29 MT = 74 Q = -1.12830E+00 MeV Emin = 1.13292E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 30 MT = 75 Q = -1.15030E+00 MeV Emin = 1.14413E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 31 MT = 76 Q = -1.16750E+00 MeV Emin = 1.16381E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 32 MT = 77 Q = -1.16890E+00 MeV Emin = 1.17368E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 27. excited state + 33 MT = 78 Q = -1.20900E+00 MeV Emin = 1.20000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 28. excited state + 34 MT = 79 Q = -1.25000E+00 MeV Emin = 1.23521E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 29. excited state + 35 MT = 80 Q = -1.44000E+00 MeV Emin = 1.40000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 30. excited state + 36 MT = 81 Q = -1.75000E+00 MeV Emin = 1.70000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 31. excited state + 37 MT = 82 Q = -1.95000E+00 MeV Emin = 1.90000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 32. excited state + 38 MT = 83 Q = -2.15000E+00 MeV Emin = 2.15911E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 33. excited state + 39 MT = 84 Q = -2.30000E+00 MeV Emin = 2.30975E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 34. excited state + 40 MT = 85 Q = -2.49280E+00 MeV Emin = 2.50336E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 35. excited state + 41 MT = 86 Q = -2.94000E+00 MeV Emin = 2.95246E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 36. excited state + 42 MT = 87 Q = -3.18900E+00 MeV Emin = 3.20251E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 37. excited state + 43 MT = 88 Q = -3.38800E+00 MeV Emin = 3.40236E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 38. excited state + 44 MT = 89 Q = -3.53800E+00 MeV Emin = 3.55299E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 39. excited state + 45 MT = 90 Q = -3.73700E+00 MeV Emin = 3.75284E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 40. excited state + 46 MT = 91 Q = -1.21000E+00 MeV Emin = 1.27765E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 47 MT = 102 Q = 4.80650E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 922390 : (n,gamma) + + 1 additional transport branch: + + 1 MT = 18 Q = 1.97314E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 1.40000E+01 MeV) : total fission + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 4.50000E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 4 Q = 4.27000E+00 MeV frac = 9.99999E-01 Product nuclide = 902340 : alpha + 2 RTYP = 6 Q = 1.73600E+02 MeV frac = 5.46000E-07 SF without yield : spontaneous fission + + 1 additional decay branch: + + 1 RTYP = 4 Q = 4.27000E+00 MeV frac = 9.99999E-01 Product nuclide = 2004.82c : alpha + + Nuclide 284 / 1657 : 93235.82c -- neptunium 235 (Np-235) + + Pointers : 2709992 29125 + Primary type : Transport + Nuclide ZAI : 932350 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Np235.ACE + Atomic weight (AW) : 235.04415 + Atomic weight ratio (AWR) : 233.02500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 3.42E+07 seconds (1.08 years) + Specific ingestion toxicity : 5.30E-11 Sv/Bq + Specific inhalation toxicity : 6.30E-10 Sv/Bq + Energy deposited per fission : 208.83 MeV + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide is using NFY data from Th-232 + - Nuclide has no SFY data + + - 22 reaction channels + - 2 special reactions + - 4 transmutation reactions + - 2 transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 22 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.98340E+00 MeV Emin = 7.01337E+00 MeV frac = 1.00000E+00 Product nuclide = 932340 : (n,2n) + 3 MT = 17 Q = -1.31047E+01 MeV Emin = 1.31609E+01 MeV frac = 1.00000E+00 Product nuclide = 932330 : (n,3n) + 4 MT = 18 Q = 2.00000E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + 5 MT = 51 Q = -3.42300E-02 MeV Emin = 3.21885E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -4.91000E-02 MeV Emin = 4.69830E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -7.91000E-02 MeV Emin = 7.57595E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -9.16000E-02 MeV Emin = 9.04940E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -1.33000E-01 MeV Emin = 1.29375E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -1.46800E-01 MeV Emin = 1.44182E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -2.00000E-01 MeV Emin = 2.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -3.52000E-01 MeV Emin = 3.51229E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -3.71000E-01 MeV Emin = 3.67822E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -4.08000E-01 MeV Emin = 4.09552E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -4.41000E-01 MeV Emin = 4.35643E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -5.20000E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 63 Q = -5.65000E-01 MeV Emin = 5.56127E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 18 MT = 64 Q = -6.02000E-01 MeV Emin = 5.95294E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 19 MT = 65 Q = -6.44000E-01 MeV Emin = 6.36219E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 20 MT = 66 Q = -7.00000E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 21 MT = 91 Q = -7.50000E-01 MeV Emin = 7.42235E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 22 MT = 102 Q = 5.73943E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 93236.82c : (n,gamma) + + 2 additional transport branches: + + 1 MT = 18 Q = 2.00000E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 1.40000E+01 MeV) : total fission + 2 MT = 102 Q = 5.73943E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 932361 : (n,gamma) + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 3.21885E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 2 Q = 1.23700E-01 MeV frac = 9.99985E-01 Product nuclide = 92235.82c : EC/beta+ + 2 RTYP = 4 Q = 5.19140E+00 MeV frac = 1.40000E-05 Product nuclide = 91231.82c : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.19140E+00 MeV frac = 1.40000E-05 Product nuclide = 2004.82c : alpha + + Nuclide 285 / 1657 : 93236.82c -- neptunium 236 (Np-236) + + Pointers : 2727748 29171 + Primary type : Transport + Nuclide ZAI : 932360 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Np236.ACE + Atomic weight (AW) : 236.04677 + Atomic weight ratio (AWR) : 234.01900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 4.89E+12 seconds (155,103 years) + Specific ingestion toxicity : 1.70E-08 Sv/Bq + Specific inhalation toxicity : 8.00E-06 Sv/Bq + Energy deposited per fission : 208.83 MeV + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide is using NFY data from U-235 + - Nuclide has no SFY data + + - 10 reaction channels + - 2 special reactions + - 4 transmutation reactions + - 2 transmutation branch reactions + - 3 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 10 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.72979E+00 MeV Emin = 5.75428E+00 MeV frac = 1.00000E+00 Product nuclide = 93235.82c : (n,2n) + 3 MT = 17 Q = -1.27090E+01 MeV Emin = 1.27633E+01 MeV frac = 1.00000E+00 Product nuclide = 932340 : (n,3n) + 4 MT = 18 Q = 1.99999E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : total fission + 5 MT = 51 Q = -5.99999E-02 MeV Emin = 5.51282E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -2.31000E-01 MeV Emin = 2.15994E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -2.73000E-01 MeV Emin = 2.62084E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -3.24000E-01 MeV Emin = 3.19039E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 91 Q = -3.69999E-01 MeV Emin = 3.71154E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 10 MT = 102 Q = 6.57335E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 93237.82c : (n,gamma) + + 2 additional transport branches: + + 1 MT = 18 Q = 1.99999E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 1.40000E+01 MeV) : total fission + 2 MT = 18 Q = 1.99999E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 5.51282E-02 MeV : total inelastic scattering + + 3 decay reactions: + + 1 RTYP = 2 Q = 9.30000E-01 MeV frac = 8.78000E-01 Product nuclide = 92236.82c : EC/beta+ + 2 RTYP = 4 Q = 5.01000E+00 MeV frac = 1.60000E-03 Product nuclide = 91232.82c : alpha + 3 RTYP = 1 Q = 4.80000E-01 MeV frac = 1.20000E-01 Product nuclide = 94236.82c : beta- + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.01000E+00 MeV frac = 1.60000E-03 Product nuclide = 2004.82c : alpha + + Nuclide 286 / 1657 : 93237.82c -- neptunium 237 (Np-237) + + Pointers : 2756600 29217 + Primary type : Transport + Nuclide ZAI : 932370 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Np237.ACE + Atomic weight (AW) : 237.04817 + Atomic weight ratio (AWR) : 235.01180 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 6.77E+13 seconds (2.15 million years) + Specific ingestion toxicity : 1.10E-07 Sv/Bq + Specific inhalation toxicity : 5.00E-05 Sv/Bq + Energy deposited per fission : 205.04 MeV + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has delayed neutron data in 8 precursor groups + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has NFY data + - Nuclide has no SFY data + + - 37 reaction channels + - 2 special reactions + - 4 transmutation reactions + - 1 transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 37 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.64600E+00 MeV Emin = 6.67428E+00 MeV frac = 1.00000E+00 Product nuclide = 93236.82c : (n,2n) + 3 MT = 17 Q = -1.23630E+01 MeV Emin = 1.24156E+01 MeV frac = 1.00000E+00 Product nuclide = 93235.82c : (n,3n) + 4 MT = 18 Q = 1.96370E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : total fission + 5 MT = 51 Q = -3.31920E-02 MeV Emin = 3.25000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -5.95370E-02 MeV Emin = 5.97500E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -7.58900E-02 MeV Emin = 7.61200E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -1.02960E-01 MeV Emin = 1.02500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -1.30000E-01 MeV Emin = 1.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -1.58510E-01 MeV Emin = 1.58700E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -1.91500E-01 MeV Emin = 1.80000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -2.25960E-01 MeV Emin = 2.20000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -2.67540E-01 MeV Emin = 2.60000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -2.69900E-01 MeV Emin = 2.70888E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -2.81350E-01 MeV Emin = 2.82200E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -3.05060E-01 MeV Emin = 3.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 63 Q = -3.16800E-01 MeV Emin = 3.12255E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 18 MT = 64 Q = -3.24420E-01 MeV Emin = 3.25400E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 19 MT = 65 Q = -3.32360E-01 MeV Emin = 3.33400E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 20 MT = 66 Q = -3.48500E-01 MeV Emin = 3.40000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 21 MT = 67 Q = -3.59700E-01 MeV Emin = 3.60000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 22 MT = 68 Q = -3.68590E-01 MeV Emin = 3.65830E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 23 MT = 69 Q = -3.70930E-01 MeV Emin = 3.71555E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 24 MT = 70 Q = -3.95520E-01 MeV Emin = 3.80000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 25 MT = 71 Q = -4.34120E-01 MeV Emin = 4.35800E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 26 MT = 72 Q = -4.52530E-01 MeV Emin = 4.53900E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 27 MT = 73 Q = -4.54400E-01 MeV Emin = 4.55395E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 28 MT = 74 Q = -4.59680E-01 MeV Emin = 4.60000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 29 MT = 75 Q = -4.86000E-01 MeV Emin = 4.87100E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 30 MT = 76 Q = -4.97000E-01 MeV Emin = 4.95000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 31 MT = 77 Q = -5.14200E-01 MeV Emin = 5.16200E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 27. excited state + 32 MT = 78 Q = -5.45600E-01 MeV Emin = 5.47300E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 28. excited state + 33 MT = 79 Q = -5.46900E-01 MeV Emin = 5.48576E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 29. excited state + 34 MT = 80 Q = -9.84000E-01 MeV Emin = 9.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 30. excited state + 35 MT = 81 Q = -1.01300E+00 MeV Emin = 1.00866E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 31. excited state + 36 MT = 91 Q = -5.46900E-01 MeV Emin = 5.48576E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 37 MT = 102 Q = 5.48200E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 93238.82c : (n,gamma) + + 1 additional transport branch: + + 1 MT = 18 Q = 1.96370E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 3.25000E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 4 Q = 4.95830E+00 MeV frac = 1.00000E+00 Product nuclide = 91233.82c : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 4.95830E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 287 / 1657 : 93238.82c -- neptunium 238 (Np-238) + + Pointers : 2779342 29263 + Primary type : Transport + Nuclide ZAI : 932380 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Np238.ACE + Atomic weight (AW) : 238.05098 + Atomic weight ratio (AWR) : 236.00600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.82E+05 seconds (2.1 days) + Specific ingestion toxicity : 9.10E-10 Sv/Bq + Specific inhalation toxicity : 3.50E-09 Sv/Bq + Energy deposited per fission : 208.83 MeV + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has delayed neutron data in 8 precursor groups + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has NFY data + - Nuclide has no SFY data + + - 6 reaction channels + - 2 special reactions + - 4 transmutation reactions + - 1 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 6 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.48800E+00 MeV Emin = 5.51200E+00 MeV frac = 1.00000E+00 Product nuclide = 93237.82c : (n,2n) + 3 MT = 17 Q = -1.21160E+01 MeV Emin = 1.21674E+01 MeV frac = 1.00000E+00 Product nuclide = 93236.82c : (n,3n) + 4 MT = 18 Q = 2.00000E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : total fission + 5 MT = 91 Q = -3.48520E-02 MeV Emin = 3.37500E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 6 MT = 102 Q = 6.22700E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 93239.82c : (n,gamma) + + 1 additional transport branch: + + 1 MT = 18 Q = 2.00000E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 3.37500E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.29150E+00 MeV frac = 1.00000E+00 Product nuclide = 94238.82c : beta- + + Nuclide 288 / 1657 : 93239.82c -- neptunium 239 (Np-239) + + Pointers : 2799334 29309 + Primary type : Transport + Nuclide ZAI : 932390 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Np239.ACE + Atomic weight (AW) : 239.05259 + Atomic weight ratio (AWR) : 236.99900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.04E+05 seconds (2.36 days) + Specific ingestion toxicity : 8.00E-10 Sv/Bq + Specific inhalation toxicity : 1.00E-09 Sv/Bq + Energy deposited per fission : 198.39 MeV + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide is using NFY data from U-238 + - Nuclide has no SFY data + + - 14 reaction channels + - 2 special reactions + - 4 transmutation reactions + - 2 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 14 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.22702E+00 MeV Emin = 6.25330E+00 MeV frac = 1.00000E+00 Product nuclide = 93238.82c : (n,2n) + 3 MT = 17 Q = -1.17056E+01 MeV Emin = 1.17550E+01 MeV frac = 1.00000E+00 Product nuclide = 93237.82c : (n,3n) + 4 MT = 18 Q = 1.90000E+02 MeV Emin = 2.87500E-02 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + 5 MT = 51 Q = -3.11400E-02 MeV Emin = 3.06250E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -7.11200E-02 MeV Emin = 7.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -7.46700E-02 MeV Emin = 7.40976E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -1.17659E-01 MeV Emin = 1.13617E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -1.23000E-01 MeV Emin = 1.23438E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -1.73050E-01 MeV Emin = 1.67835E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -2.41400E-01 MeV Emin = 2.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -3.20000E-01 MeV Emin = 3.10675E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 91 Q = -4.30000E-01 MeV Emin = 4.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 14 MT = 102 Q = 5.16810E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 932400 : (n,gamma) + + 2 additional transport branches: + + 1 MT = 18 Q = 1.90000E+02 MeV Emin = 2.87500E-02 MeV frac = 1.00000E+00 NFY (E = 1.40000E+01 MeV) : total fission + 2 MT = 102 Q = 5.16810E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 932401 : (n,gamma) + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 3.06250E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.22500E-01 MeV frac = 1.00000E+00 Product nuclide = 94239.82c : beta- + + Nuclide 289 / 1657 : 94236.82c -- plutonium 236 (Pu-236) + + Pointers : 2823662 30597 + Primary type : Transport + Nuclide ZAI : 942360 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Pu236.ACE + Atomic weight (AW) : 236.04576 + Atomic weight ratio (AWR) : 234.01800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 9.02E+07 seconds (2.86 years) + Specific ingestion toxicity : 8.70E-08 Sv/Bq + Specific inhalation toxicity : 4.00E-05 Sv/Bq + Energy deposited per fission : 211.56 MeV + Spontaneous fission nubar : 2.12000 + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide is using NFY data from Th-232 + - Nuclide has no SFY data + + - 10 reaction channels + - 2 special reactions + - 4 transmutation reactions + - 2 transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 10 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.35725E+00 MeV Emin = 7.38869E+00 MeV frac = 1.00000E+00 Product nuclide = 942350 : (n,2n) + 3 MT = 17 Q = -1.35872E+01 MeV Emin = 1.36453E+01 MeV frac = 1.00000E+00 Product nuclide = 942340 : (n,3n) + 4 MT = 18 Q = 2.02618E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + 5 MT = 51 Q = -4.46300E-02 MeV Emin = 4.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -1.47450E-01 MeV Emin = 1.36060E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -3.05800E-01 MeV Emin = 3.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -5.15700E-01 MeV Emin = 5.17304E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 91 Q = -6.40000E-01 MeV Emin = 6.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 10 MT = 102 Q = 5.87702E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 94237.82c : (n,gamma) + + 2 additional transport branches: + + 1 MT = 18 Q = 2.02618E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 1.40000E+01 MeV) : total fission + 2 MT = 102 Q = 5.87702E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 942371 : (n,gamma) + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 4.00000E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 4 Q = 5.86707E+00 MeV frac = 1.00000E+00 Product nuclide = 92232.82c : alpha + 2 RTYP = 6 Q = 1.85300E+02 MeV frac = 8.20000E-10 SF without yield : spontaneous fission + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.86707E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 290 / 1657 : 94237.82c -- plutonium 237 (Pu-237) + + Pointers : 2842045 30643 + Primary type : Transport + Nuclide ZAI : 942370 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Pu237.ACE + Atomic weight (AW) : 237.04837 + Atomic weight ratio (AWR) : 235.01200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 3.91E+06 seconds (45.3 days) + Specific ingestion toxicity : 1.00E-10 Sv/Bq + Specific inhalation toxicity : 3.90E-10 Sv/Bq + Energy deposited per fission : 212.55 MeV + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide is using NFY data from U-235 + - Nuclide has no SFY data + + - 17 reaction channels + - 2 special reactions + - 5 transmutation reactions + - 4 transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 17 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.83420E+00 MeV Emin = 5.85903E+00 MeV frac = 1.00000E+00 Product nuclide = 94236.82c : (n,2n) + 3 MT = 17 Q = -1.32200E+01 MeV Emin = 1.32763E+01 MeV frac = 1.00000E+00 Product nuclide = 942350 : (n,3n) + 4 MT = 19 Q = 2.03565E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : (n,f) + 5 MT = 20 Q = 2.03565E+02 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : (n,nf) + 6 MT = 51 Q = -4.77970E-02 MeV Emin = 4.75000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.02560E-01 MeV Emin = 1.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -1.45380E-01 MeV Emin = 1.35500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -1.56330E-01 MeV Emin = 1.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -1.70280E-01 MeV Emin = 1.65750E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -1.99150E-01 MeV Emin = 1.95000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -2.28030E-01 MeV Emin = 2.15000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -2.78810E-01 MeV Emin = 2.70000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -3.09680E-01 MeV Emin = 3.03000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -3.19640E-01 MeV Emin = 3.15000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 91 Q = -3.19640E-01 MeV Emin = 3.15000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 17 MT = 102 Q = 6.99800E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 94238.82c : (n,gamma) + + 4 additional transport branches: + + 1 MT = 19 Q = 2.03565E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 1.40000E+01 MeV) : (n,f) + 2 MT = 19 Q = 2.03565E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : (n,f) + 3 MT = 20 Q = 2.03565E+02 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 NFY (E = 1.40000E+01 MeV) : (n,nf) + 4 MT = 20 Q = 2.03565E+02 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : (n,nf) + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 4.75000E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 2 Q = 2.22000E-01 MeV frac = 9.99958E-01 Product nuclide = 93237.82c : EC/beta+ + 2 RTYP = 4 Q = 5.74700E+00 MeV frac = 4.20000E-05 Product nuclide = 92233.82c : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.74700E+00 MeV frac = 4.20000E-05 Product nuclide = 2004.82c : alpha + + Nuclide 291 / 1657 : 94238.82c -- plutonium 238 (Pu-238) + + Pointers : 2872327 30689 + Primary type : Transport + Nuclide ZAI : 942380 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Pu238.ACE + Atomic weight (AW) : 238.04998 + Atomic weight ratio (AWR) : 236.00500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.77E+09 seconds (87.8 years) + Specific ingestion toxicity : 2.30E-07 Sv/Bq + Specific inhalation toxicity : 1.10E-04 Sv/Bq + Energy deposited per fission : 206.09 MeV + Spontaneous fission nubar : 2.21000 + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has delayed neutron data in 8 precursor groups + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has NFY data + - Nuclide has no SFY data + + - 34 reaction channels + - 2 special reactions + - 4 transmutation reactions + - 1 transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 34 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.99789E+00 MeV Emin = 7.02755E+00 MeV frac = 1.00000E+00 Product nuclide = 94237.82c : (n,2n) + 3 MT = 17 Q = -1.28716E+01 MeV Emin = 1.29261E+01 MeV frac = 1.00000E+00 Product nuclide = 94236.82c : (n,3n) + 4 MT = 18 Q = 1.97381E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : total fission + 5 MT = 51 Q = -4.40799E-02 MeV Emin = 4.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -1.45980E-01 MeV Emin = 1.40000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -3.03400E-01 MeV Emin = 2.94519E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -5.13999E-01 MeV Emin = 4.97291E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -6.05099E-01 MeV Emin = 6.07130E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -6.61399E-01 MeV Emin = 6.45939E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -7.63199E-01 MeV Emin = 7.42667E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -9.41499E-01 MeV Emin = 9.10119E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -9.62769E-01 MeV Emin = 9.58839E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -9.68199E-01 MeV Emin = 9.69576E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -9.82999E-01 MeV Emin = 9.79734E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -9.85499E-01 MeV Emin = 9.88421E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 63 Q = -1.02860E+00 MeV Emin = 1.02349E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 18 MT = 64 Q = -1.07000E+00 MeV Emin = 1.06544E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 19 MT = 65 Q = -1.08260E+00 MeV Emin = 1.08086E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 20 MT = 66 Q = -1.12580E+00 MeV Emin = 1.10953E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 21 MT = 67 Q = -1.17450E+00 MeV Emin = 1.16114E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 22 MT = 68 Q = -1.20270E+00 MeV Emin = 1.19364E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 23 MT = 69 Q = -1.22860E+00 MeV Emin = 1.22080E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 24 MT = 70 Q = -1.26420E+00 MeV Emin = 1.25615E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 25 MT = 71 Q = -1.31030E+00 MeV Emin = 1.29849E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 26 MT = 72 Q = -1.42660E+00 MeV Emin = 1.39846E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 27 MT = 73 Q = -1.44730E+00 MeV Emin = 1.44304E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 28 MT = 74 Q = -1.45850E+00 MeV Emin = 1.45906E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 29 MT = 75 Q = -1.56000E+00 MeV Emin = 1.54113E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 30 MT = 76 Q = -1.59650E+00 MeV Emin = 1.58494E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 31 MT = 77 Q = -1.62140E+00 MeV Emin = 1.61577E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 27. excited state + 32 MT = 78 Q = -1.63660E+00 MeV Emin = 1.63590E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 28. excited state + 33 MT = 91 Q = -1.65000E+00 MeV Emin = 1.65026E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 34 MT = 102 Q = 5.64739E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 94239.82c : (n,gamma) + + 1 additional transport branch: + + 1 MT = 18 Q = 1.97381E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 4.00000E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 4 Q = 5.59327E+00 MeV frac = 1.00000E+00 Product nuclide = 92234.82c : alpha + 2 RTYP = 6 Q = 1.84500E+02 MeV frac = 1.86000E-09 SF without yield : spontaneous fission + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.59327E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 292 / 1657 : 94239.82c -- plutonium 239 (Pu-239) + + Pointers : 2895957 30735 + Primary type : Transport + Nuclide ZAI : 942390 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Pu239.ACE + Atomic weight (AW) : 239.05198 + Atomic weight ratio (AWR) : 236.99840 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 3.00000E+01 + Half-life : 7.61E+11 seconds (24,130 years) + Specific ingestion toxicity : 2.50E-07 Sv/Bq + Specific inhalation toxicity : 1.20E-04 Sv/Bq + Energy deposited per fission : 207.86 MeV + Spontaneous fission nubar : 2.32000 + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has delayed neutron data in 8 precursor groups + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has NFY data + - Nuclide has no SFY data + + - 34 reaction channels + - 2 special reactions + - 5 transmutation reactions + - 1 transmutation branch reactions + - 3 decay reactions + - 2 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 34 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.64668E+00 MeV Emin = 5.70000E+00 MeV frac = 1.00000E+00 Product nuclide = 94238.82c : (n,2n) + 3 MT = 17 Q = -1.26480E+01 MeV Emin = 1.28000E+01 MeV frac = 1.00000E+00 Product nuclide = 94237.82c : (n,3n) + 4 MT = 18 Q = 1.99073E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : total fission + 5 MT = 37 Q = -1.85083E+01 MeV Emin = 1.90000E+01 MeV frac = 1.00000E+00 Product nuclide = 94236.82c : (n,4n) + 6 MT = 51 Q = -7.86000E-03 MeV Emin = 7.87500E-03 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -5.73000E-02 MeV Emin = 5.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -7.57000E-02 MeV Emin = 7.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -1.63800E-01 MeV Emin = 1.60000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -1.92800E-01 MeV Emin = 1.90000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -2.85500E-01 MeV Emin = 2.80000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -3.18100E-01 MeV Emin = 3.10000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -3.30100E-01 MeV Emin = 3.30000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -3.58100E-01 MeV Emin = 3.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -3.87400E-01 MeV Emin = 3.80000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -3.91600E-01 MeV Emin = 3.92500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -4.34000E-01 MeV Emin = 4.30000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -4.62000E-01 MeV Emin = 4.60000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -4.69800E-01 MeV Emin = 4.70000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -4.87000E-01 MeV Emin = 4.80000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 21 MT = 66 Q = -4.92200E-01 MeV Emin = 4.92500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 22 MT = 67 Q = -5.05500E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 23 MT = 68 Q = -5.11800E-01 MeV Emin = 5.12500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 24 MT = 69 Q = -5.19200E-01 MeV Emin = 5.20000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 25 MT = 70 Q = -5.38000E-01 MeV Emin = 5.40000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 26 MT = 71 Q = -5.56100E-01 MeV Emin = 5.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 27 MT = 72 Q = -5.65000E-01 MeV Emin = 5.65000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 28 MT = 73 Q = -5.70100E-01 MeV Emin = 5.70000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 29 MT = 74 Q = -5.83000E-01 MeV Emin = 5.80000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 30 MT = 75 Q = -6.20000E-01 MeV Emin = 6.20000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 31 MT = 76 Q = -6.34000E-01 MeV Emin = 6.30000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 32 MT = 77 Q = -6.59000E-01 MeV Emin = 6.60000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 27. excited state + 33 MT = 91 Q = -6.59972E-01 MeV Emin = 6.61781E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 34 MT = 102 Q = 6.53300E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 94240.82c : (n,gamma) + + 1 additional transport branch: + + 1 MT = 18 Q = 1.99073E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 7.87500E-03 MeV : total inelastic scattering + + 3 decay reactions: + + 1 RTYP = 4 Q = 5.24450E+00 MeV frac = 6.00000E-04 Product nuclide = 92235.82c : alpha + 2 RTYP = 4 Q = 5.24442E+00 MeV frac = 9.99400E-01 Product nuclide = 922351 : alpha + 3 RTYP = 6 Q = 1.84300E+02 MeV frac = 3.10000E-12 SF without yield : spontaneous fission + + 2 additional decay branches: + + 1 RTYP = 4 Q = 5.24450E+00 MeV frac = 6.00000E-04 Product nuclide = 2004.82c : alpha + 2 RTYP = 4 Q = 5.24442E+00 MeV frac = 9.99400E-01 Product nuclide = 2004.82c : alpha + + Nuclide 293 / 1657 : 94240.82c -- plutonium 240 (Pu-240) + + Pointers : 2930085 30781 + Primary type : Transport + Nuclide ZAI : 942400 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Pu240.ACE + Atomic weight (AW) : 240.05379 + Atomic weight ratio (AWR) : 237.99160 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 3.00000E+01 + Half-life : 2.07E+11 seconds (6,567 years) + Specific ingestion toxicity : 2.50E-07 Sv/Bq + Specific inhalation toxicity : 1.20E-04 Sv/Bq + Energy deposited per fission : 211.96 MeV + Spontaneous fission nubar : 2.15100 + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has delayed neutron data in 8 precursor groups + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has NFY data + - Nuclide has no SFY data + + - 31 reaction channels + - 2 special reactions + - 5 transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 31 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.53370E+00 MeV Emin = 6.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 94239.82c : (n,2n) + 3 MT = 17 Q = -1.21804E+01 MeV Emin = 1.24000E+01 MeV frac = 1.00000E+00 Product nuclide = 94238.82c : (n,3n) + 4 MT = 18 Q = 2.03004E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + 5 MT = 37 Q = -1.91816E+01 MeV Emin = 1.95000E+01 MeV frac = 1.00000E+00 Product nuclide = 94237.82c : (n,4n) + 6 MT = 51 Q = -4.28200E-02 MeV Emin = 4.15000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.41690E-01 MeV Emin = 1.40000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -2.94310E-01 MeV Emin = 2.90000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -4.97600E-01 MeV Emin = 4.90000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -5.97400E-01 MeV Emin = 5.90000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -6.48900E-01 MeV Emin = 6.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -7.42500E-01 MeV Emin = 7.40000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -7.47800E-01 MeV Emin = 7.90000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -8.60700E-01 MeV Emin = 8.60000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -9.00300E-01 MeV Emin = 9.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -9.38100E-01 MeV Emin = 9.40000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -9.58900E-01 MeV Emin = 9.60000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -9.93000E-01 MeV Emin = 9.90000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -1.00210E+00 MeV Emin = 1.00316E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -1.03060E+00 MeV Emin = 1.02062E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 21 MT = 66 Q = -1.03790E+00 MeV Emin = 1.03860E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 22 MT = 67 Q = -1.04180E+00 MeV Emin = 1.09714E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 23 MT = 68 Q = -1.07640E+00 MeV Emin = 1.06159E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 24 MT = 69 Q = -1.08970E+00 MeV Emin = 1.09214E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 25 MT = 70 Q = -1.11570E+00 MeV Emin = 1.11019E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 26 MT = 71 Q = -1.13130E+00 MeV Emin = 1.12822E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 27 MT = 72 Q = -1.13750E+00 MeV Emin = 1.13917E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 28 MT = 73 Q = -1.16130E+00 MeV Emin = 1.15423E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 29 MT = 74 Q = -1.17780E+00 MeV Emin = 1.17447E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 30 MT = 91 Q = -1.17880E+00 MeV Emin = 1.18350E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 31 MT = 102 Q = 5.24190E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 94241.82c : (n,gamma) + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 4.15000E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 4 Q = 5.25590E+00 MeV frac = 1.00000E+00 Product nuclide = 92236.82c : alpha + 2 RTYP = 6 Q = 1.84700E+02 MeV frac = 5.70000E-08 SF without yield : spontaneous fission + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.25590E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 294 / 1657 : 94241.82c -- plutonium 241 (Pu-241) + + Pointers : 2942310 30827 + Primary type : Transport + Nuclide ZAI : 942410 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Pu241.ACE + Atomic weight (AW) : 241.05681 + Atomic weight ratio (AWR) : 238.98600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 4.52E+08 seconds (14.3 years) + Specific ingestion toxicity : 4.80E-09 Sv/Bq + Specific inhalation toxicity : 2.30E-06 Sv/Bq + Energy deposited per fission : 210.89 MeV + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has delayed neutron data in 8 precursor groups + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has NFY data + - Nuclide has no SFY data + + - 18 reaction channels + - 2 special reactions + - 5 transmutation reactions + - 1 transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 18 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.23999E+00 MeV Emin = 5.26192E+00 MeV frac = 1.00000E+00 Product nuclide = 94240.82c : (n,2n) + 3 MT = 17 Q = -1.17700E+01 MeV Emin = 1.18193E+01 MeV frac = 1.00000E+00 Product nuclide = 94239.82c : (n,3n) + 4 MT = 18 Q = 2.01980E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : total fission + 5 MT = 37 Q = -1.74300E+01 MeV Emin = 1.75030E+01 MeV frac = 1.00000E+00 Product nuclide = 94238.82c : (n,4n) + 6 MT = 51 Q = -4.17999E-02 MeV Emin = 4.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -9.39999E-02 MeV Emin = 9.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -1.61500E-01 MeV Emin = 1.60000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -1.70800E-01 MeV Emin = 1.70000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -2.23100E-01 MeV Emin = 2.20000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -2.30000E-01 MeV Emin = 2.30000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -2.42700E-01 MeV Emin = 2.40000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -3.00000E-01 MeV Emin = 3.00628E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -3.35000E-01 MeV Emin = 3.28201E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -3.67999E-01 MeV Emin = 3.60000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -4.44999E-01 MeV Emin = 4.40000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 91 Q = -4.89999E-01 MeV Emin = 4.80000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 18 MT = 102 Q = 6.31000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 94242.82c : (n,gamma) + + 1 additional transport branch: + + 1 MT = 18 Q = 2.01980E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 4.00000E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 4 Q = 5.14000E+00 MeV frac = 2.44000E-05 Product nuclide = 92237.82c : alpha + 2 RTYP = 1 Q = 2.08000E-02 MeV frac = 9.99976E-01 Product nuclide = 95241.82c : beta- + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.14000E+00 MeV frac = 2.44000E-05 Product nuclide = 2004.82c : alpha + + Nuclide 295 / 1657 : 94242.82c -- plutonium 242 (Pu-242) + + Pointers : 2962100 30873 + Primary type : Transport + Nuclide ZAI : 942420 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Pu242.ACE + Atomic weight (AW) : 242.05841 + Atomic weight ratio (AWR) : 239.97900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.18E+13 seconds (373,757 years) + Specific ingestion toxicity : 2.40E-07 Sv/Bq + Specific inhalation toxicity : 1.10E-04 Sv/Bq + Energy deposited per fission : 210.48 MeV + Spontaneous fission nubar : 2.14100 + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has delayed neutron data in 8 precursor groups + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has NFY data + - Nuclide has no SFY data + + - 27 reaction channels + - 2 special reactions + - 5 transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 27 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.30969E+00 MeV Emin = 6.33599E+00 MeV frac = 1.00000E+00 Product nuclide = 94241.82c : (n,2n) + 3 MT = 17 Q = -1.15512E+01 MeV Emin = 1.15994E+01 MeV frac = 1.00000E+00 Product nuclide = 94240.82c : (n,3n) + 4 MT = 18 Q = 2.01580E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + 5 MT = 37 Q = -1.80852E+01 MeV Emin = 1.81606E+01 MeV frac = 1.00000E+00 Product nuclide = 94239.82c : (n,4n) + 6 MT = 51 Q = -4.45400E-02 MeV Emin = 4.20000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.47300E-01 MeV Emin = 1.47800E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -3.06400E-01 MeV Emin = 3.05900E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -5.18100E-01 MeV Emin = 5.19500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -7.78780E-01 MeV Emin = 8.35789E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -7.80460E-01 MeV Emin = 7.81945E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -8.32300E-01 MeV Emin = 8.27576E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -9.27000E-01 MeV Emin = 9.29996E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -9.56000E-01 MeV Emin = 9.49988E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -9.92500E-01 MeV Emin = 9.94175E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -1.01940E+00 MeV Emin = 1.02300E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -1.03920E+00 MeV Emin = 1.04100E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -1.06400E+00 MeV Emin = 1.06800E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -1.08400E+00 MeV Emin = 1.38000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -1.09210E+00 MeV Emin = 1.09599E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 21 MT = 66 Q = -1.10200E+00 MeV Emin = 1.10100E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 22 MT = 67 Q = -1.12200E+00 MeV Emin = 1.11684E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 23 MT = 68 Q = -1.15010E+00 MeV Emin = 1.15000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 24 MT = 69 Q = -1.15460E+00 MeV Emin = 1.15715E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 25 MT = 70 Q = -1.18160E+00 MeV Emin = 1.17297E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 26 MT = 91 Q = -1.19000E+00 MeV Emin = 1.19074E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 27 MT = 102 Q = 5.03419E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 94243.82c : (n,gamma) + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 4.20000E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 4 Q = 4.98310E+00 MeV frac = 1.00000E+00 Product nuclide = 92238.82c : alpha + 2 RTYP = 6 Q = 1.84700E+02 MeV frac = 5.50000E-06 SF without yield : spontaneous fission + + 1 additional decay branch: + + 1 RTYP = 4 Q = 4.98310E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 296 / 1657 : 94243.82c -- plutonium 243 (Pu-243) + + Pointers : 2973673 30919 + Primary type : Transport + Nuclide ZAI : 942430 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Pu243.ACE + Atomic weight (AW) : 243.06203 + Atomic weight ratio (AWR) : 240.97400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.78E+04 seconds (4.96 hours) + Specific ingestion toxicity : 8.50E-11 Sv/Bq + Specific inhalation toxicity : 8.60E-11 Sv/Bq + Energy deposited per fission : 208.83 MeV + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide is using NFY data from Cm-245 + - Nuclide has no SFY data + + - 7 reaction channels + - 2 special reactions + - 5 transmutation reactions + - 1 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 7 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.03920E+00 MeV Emin = 5.06011E+00 MeV frac = 1.00000E+00 Product nuclide = 94242.82c : (n,2n) + 3 MT = 17 Q = -1.13330E+01 MeV Emin = 1.13800E+01 MeV frac = 1.00000E+00 Product nuclide = 94241.82c : (n,3n) + 4 MT = 18 Q = 2.00000E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : total fission + 5 MT = 37 Q = -1.65810E+01 MeV Emin = 1.66500E+01 MeV frac = 1.00000E+00 Product nuclide = 94240.82c : (n,4n) + 6 MT = 91 Q = -5.97520E-02 MeV Emin = 5.50355E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 7 MT = 102 Q = 6.02000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 94244.82c : (n,gamma) + + 1 additional transport branch: + + 1 MT = 18 Q = 2.00000E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 5.50355E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.82000E-01 MeV frac = 1.00000E+00 Product nuclide = 95243.82c : beta- + + Nuclide 297 / 1657 : 94244.82c -- plutonium 244 (Pu-244) + + Pointers : 2996177 30965 + Primary type : Transport + Nuclide ZAI : 942440 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Pu244.ACE + Atomic weight (AW) : 244.06465 + Atomic weight ratio (AWR) : 241.96800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.52E+15 seconds (80.1 million years) + Specific ingestion toxicity : 2.40E-07 Sv/Bq + Specific inhalation toxicity : 1.10E-04 Sv/Bq + Energy deposited per fission : 216.82 MeV + Spontaneous fission nubar : 2.29000 + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide is using NFY data from U-233 + - Nuclide has no SFY data + + - 13 reaction channels + - 2 special reactions + - 6 transmutation reactions + - 4 transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 13 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.99320E+00 MeV Emin = 6.01800E+00 MeV frac = 1.00000E+00 Product nuclide = 94243.82c : (n,2n) + 3 MT = 17 Q = -1.10550E+01 MeV Emin = 1.11007E+01 MeV frac = 1.00000E+00 Product nuclide = 94242.82c : (n,3n) + 4 MT = 19 Q = 2.07654E+02 MeV Emin = 2.46932E-04 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : (n,f) + 5 MT = 20 Q = 2.07654E+02 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : (n,nf) + 6 MT = 37 Q = -1.73560E+01 MeV Emin = 1.74280E+01 MeV frac = 1.00000E+00 Product nuclide = 94241.82c : (n,4n) + 7 MT = 51 Q = -4.38190E-02 MeV Emin = 4.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 8 MT = 52 Q = -1.42410E-01 MeV Emin = 1.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 9 MT = 53 Q = -2.94780E-01 MeV Emin = 2.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 10 MT = 54 Q = -5.97530E-01 MeV Emin = 5.91000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 11 MT = 55 Q = -6.47320E-01 MeV Emin = 6.40000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 12 MT = 91 Q = -6.47320E-01 MeV Emin = 6.40000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 13 MT = 102 Q = 4.72000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 942450 : (n,gamma) + + 4 additional transport branches: + + 1 MT = 19 Q = 2.07654E+02 MeV Emin = 2.46932E-04 MeV frac = 1.00000E+00 NFY (E = 1.40000E+01 MeV) : (n,f) + 2 MT = 19 Q = 2.07654E+02 MeV Emin = 2.46932E-04 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : (n,f) + 3 MT = 20 Q = 2.07654E+02 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 NFY (E = 1.40000E+01 MeV) : (n,nf) + 4 MT = 20 Q = 2.07654E+02 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : (n,nf) + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 4.00000E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 4 Q = 4.66580E+00 MeV frac = 9.98750E-01 Product nuclide = 922400 : alpha + 2 RTYP = 6 Q = 1.84200E+02 MeV frac = 1.25000E-03 SF without yield : spontaneous fission + + 1 additional decay branch: + + 1 RTYP = 4 Q = 4.66580E+00 MeV frac = 9.98750E-01 Product nuclide = 2004.82c : alpha + + Nuclide 298 / 1657 : 95241.82c -- americium 241 (Am-241) + + Pointers : 3034095 18867 + Primary type : Transport + Nuclide ZAI : 952410 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Am241.ACE + Atomic weight (AW) : 241.05681 + Atomic weight ratio (AWR) : 238.98600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.37E+10 seconds (433 years) + Specific ingestion toxicity : 2.00E-07 Sv/Bq + Specific inhalation toxicity : 9.60E-05 Sv/Bq + Energy deposited per fission : 210.87 MeV + Spontaneous fission nubar : 2.50000 + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has delayed neutron data in 8 precursor groups + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has NFY data + - Nuclide has no SFY data + + - 16 reaction channels + - 2 special reactions + - 4 transmutation reactions + - 2 transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 16 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.64114E+00 MeV Emin = 6.66893E+00 MeV frac = 1.00000E+00 Product nuclide = 952400 : (n,2n) + 3 MT = 17 Q = -1.26060E+01 MeV Emin = 1.26590E+01 MeV frac = 1.00000E+00 Product nuclide = 952390 : (n,3n) + 4 MT = 18 Q = 2.01960E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : total fission + 5 MT = 51 Q = -4.11760E-02 MeV Emin = 4.06742E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -9.36500E-02 MeV Emin = 9.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -1.58000E-01 MeV Emin = 1.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -2.05880E-01 MeV Emin = 2.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -2.34000E-01 MeV Emin = 2.20861E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -2.35000E-01 MeV Emin = 2.35481E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -2.39000E-01 MeV Emin = 2.37992E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -2.72000E-01 MeV Emin = 2.61569E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -2.73000E-01 MeV Emin = 2.73640E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -3.12000E-01 MeV Emin = 3.12500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 91 Q = -3.13000E-01 MeV Emin = 3.14063E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 16 MT = 102 Q = 5.54100E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 95242.82c : (n,gamma) + + 2 additional transport branches: + + 1 MT = 18 Q = 2.01960E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + 2 MT = 102 Q = 5.54100E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 95642.82c : (n,gamma) + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 4.06742E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 4 Q = 5.63781E+00 MeV frac = 1.00000E+00 Product nuclide = 93237.82c : alpha + 2 RTYP = 6 Q = 1.88100E+02 MeV frac = 4.30000E-12 SF without yield : spontaneous fission + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.63781E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 299 / 1657 : 95242.82c -- americium 242 (Am-242) + + Pointers : 3065598 18913 + Primary type : Transport + Nuclide ZAI : 952420 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Am242G.ACE + Atomic weight (AW) : 242.05942 + Atomic weight ratio (AWR) : 239.98000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 5.76E+04 seconds (16 hours) + Specific ingestion toxicity : 3.00E-10 Sv/Bq + Specific inhalation toxicity : 2.00E-08 Sv/Bq + Energy deposited per fission : 208.83 MeV + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide is using NFY data from Am-242m + - Nuclide has no SFY data + + - 33 reaction channels + - 2 special reactions + - 6 transmutation reactions + - 3 transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 33 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.53900E+00 MeV Emin = 5.56208E+00 MeV frac = 1.00000E+00 Product nuclide = 95241.82c : (n,2n) + 3 MT = 17 Q = -1.21801E+01 MeV Emin = 1.22309E+01 MeV frac = 1.00000E+00 Product nuclide = 952400 : (n,3n) + 4 MT = 19 Q = 2.00000E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : (n,f) + 5 MT = 20 Q = 2.00000E+02 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : (n,nf) + 6 MT = 21 Q = 2.00000E+02 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : (n,2nf) + 7 MT = 51 Q = -4.41000E-02 MeV Emin = 3.50000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 8 MT = 52 Q = -4.86300E-02 MeV Emin = 4.65582E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 9 MT = 53 Q = -5.29000E-02 MeV Emin = 5.15602E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 10 MT = 54 Q = -7.58000E-02 MeV Emin = 7.50000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 11 MT = 55 Q = -1.14000E-01 MeV Emin = 1.07237E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 12 MT = 56 Q = -1.40000E-01 MeV Emin = 1.34056E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 13 MT = 57 Q = -1.48000E-01 MeV Emin = 1.47813E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 14 MT = 58 Q = -1.49900E-01 MeV Emin = 1.49621E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 15 MT = 59 Q = -1.90000E-01 MeV Emin = 1.90741E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 16 MT = 60 Q = -1.97600E-01 MeV Emin = 1.94808E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 17 MT = 61 Q = -2.17000E-01 MeV Emin = 2.08952E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 18 MT = 62 Q = -2.20000E-01 MeV Emin = 2.19411E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 19 MT = 63 Q = -2.30500E-01 MeV Emin = 2.26188E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 20 MT = 64 Q = -2.42000E-01 MeV Emin = 2.37234E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 21 MT = 65 Q = -2.44100E-01 MeV Emin = 2.44063E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 22 MT = 66 Q = -2.63000E-01 MeV Emin = 2.54607E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 23 MT = 67 Q = -2.63100E-01 MeV Emin = 2.64096E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 24 MT = 68 Q = -2.70100E-01 MeV Emin = 2.70910E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 25 MT = 69 Q = -2.75000E-01 MeV Emin = 2.75945E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 26 MT = 70 Q = -2.83300E-01 MeV Emin = 2.84336E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 27 MT = 71 Q = -2.88400E-01 MeV Emin = 2.89371E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 28 MT = 72 Q = -2.91800E-01 MeV Emin = 2.92168E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 29 MT = 73 Q = -3.05000E-01 MeV Emin = 3.06134E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 30 MT = 74 Q = -3.06900E-01 MeV Emin = 3.06134E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 31 MT = 75 Q = -3.19000E-01 MeV Emin = 3.14254E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 32 MT = 91 Q = -3.20000E-01 MeV Emin = 3.20831E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 33 MT = 102 Q = 6.36710E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 95243.82c : (n,gamma) + + 3 additional transport branches: + + 1 MT = 19 Q = 2.00000E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : (n,f) + 2 MT = 20 Q = 2.00000E+02 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : (n,nf) + 3 MT = 21 Q = 2.00000E+02 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : (n,2nf) + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 3.50000E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 2 Q = 7.51300E-01 MeV frac = 1.69000E-01 Product nuclide = 94242.82c : EC/beta+ + 2 RTYP = 1 Q = 6.64500E-01 MeV frac = 8.31000E-01 Product nuclide = 96242.82c : beta- + + Nuclide 300 / 1657 : 95642.82c -- americium 242m (Am-242m) + + Pointers : 3088156 18959 + Primary type : Transport + Nuclide ZAI : 952421 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Am242M.ACE + Atomic weight (AW) : 242.05942 + Atomic weight ratio (AWR) : 239.98000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 4.45E+09 seconds (141 years) + Specific ingestion toxicity : 1.90E-07 Sv/Bq + Specific inhalation toxicity : 9.20E-05 Sv/Bq + Energy deposited per fission : 219.75 MeV + Spontaneous fission nubar : 2.56000 + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has delayed neutron data in 8 precursor groups + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has NFY data + - Nuclide has no SFY data + + - 31 reaction channels + - 2 special reactions + - 4 transmutation reactions + - 1 transmutation branch reactions + - 3 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 31 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.53900E+00 MeV Emin = 5.56208E+00 MeV frac = 1.00000E+00 Product nuclide = 95241.82c : (n,2n) + 3 MT = 17 Q = -1.21801E+01 MeV Emin = 1.22309E+01 MeV frac = 1.00000E+00 Product nuclide = 952400 : (n,3n) + 4 MT = 18 Q = 2.10464E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : total fission + 5 MT = 51 Q = 4.86300E-02 MeV Emin = 4.20473E-05 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = 4.53000E-03 MeV Emin = 9.00000E-03 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -4.27000E-03 MeV Emin = 4.01889E-03 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -2.71700E-02 MeV Emin = 2.72475E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -6.53700E-02 MeV Emin = 6.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -9.13700E-02 MeV Emin = 9.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -9.93700E-02 MeV Emin = 9.48921E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -1.01270E-01 MeV Emin = 1.00846E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -1.41370E-01 MeV Emin = 1.31892E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -1.48970E-01 MeV Emin = 1.45775E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -1.68370E-01 MeV Emin = 1.66563E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -1.71370E-01 MeV Emin = 1.70704E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 63 Q = -1.81870E-01 MeV Emin = 1.81159E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 18 MT = 64 Q = -1.93370E-01 MeV Emin = 1.94015E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 19 MT = 65 Q = -1.95470E-01 MeV Emin = 1.95528E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 20 MT = 66 Q = -2.14370E-01 MeV Emin = 2.07631E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 21 MT = 67 Q = -2.14470E-01 MeV Emin = 2.15288E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 22 MT = 68 Q = -2.21470E-01 MeV Emin = 2.22085E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 23 MT = 69 Q = -2.26370E-01 MeV Emin = 2.24326E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 24 MT = 70 Q = -2.34670E-01 MeV Emin = 2.31481E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 25 MT = 71 Q = -2.39770E-01 MeV Emin = 2.38208E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 26 MT = 72 Q = -2.43170E-01 MeV Emin = 2.42476E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 27 MT = 73 Q = -2.56370E-01 MeV Emin = 2.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 28 MT = 74 Q = -2.58270E-01 MeV Emin = 2.58392E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 29 MT = 75 Q = -2.70370E-01 MeV Emin = 2.71364E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 30 MT = 91 Q = -2.73000E-01 MeV Emin = 2.73213E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 31 MT = 102 Q = 6.37000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 95243.82c : (n,gamma) + + 1 additional transport branch: + + 1 MT = 18 Q = 2.10464E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 4.20473E-05 MeV : total inelastic scattering + + 3 decay reactions: + + 1 RTYP = 3 Q = 4.86300E-02 MeV frac = 9.95370E-01 Product nuclide = 95242.82c : IT + 2 RTYP = 4 Q = 5.63690E+00 MeV frac = 4.63000E-03 Product nuclide = 93238.82c : alpha + 3 RTYP = 6 Q = 1.88400E+02 MeV frac = 1.60000E-10 SF without yield : spontaneous fission + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.63690E+00 MeV frac = 4.63000E-03 Product nuclide = 2004.82c : alpha + + Nuclide 301 / 1657 : 95243.82c -- americium 243 (Am-243) + + Pointers : 3114955 19005 + Primary type : Transport + Nuclide ZAI : 952430 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Am243.ACE + Atomic weight (AW) : 243.06102 + Atomic weight ratio (AWR) : 240.97300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.32E+11 seconds (7,370 years) + Specific ingestion toxicity : 2.00E-07 Sv/Bq + Specific inhalation toxicity : 9.60E-05 Sv/Bq + Energy deposited per fission : 212.61 MeV + Spontaneous fission nubar : 2.61000 + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has delayed neutron data in 8 precursor groups + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has NFY data + - Nuclide has no SFY data + + - 16 reaction channels + - 2 special reactions + - 4 transmutation reactions + - 2 transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 16 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.36400E+00 MeV Emin = 6.39041E+00 MeV frac = 1.00000E+00 Product nuclide = 95242.82c : (n,2n) + 3 MT = 17 Q = -1.19030E+01 MeV Emin = 1.19524E+01 MeV frac = 1.00000E+00 Product nuclide = 95241.82c : (n,3n) + 4 MT = 18 Q = 2.03620E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : total fission + 5 MT = 51 Q = -4.22000E-02 MeV Emin = 4.23175E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -8.40000E-02 MeV Emin = 8.37500E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -9.64000E-02 MeV Emin = 9.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -1.09200E-01 MeV Emin = 1.04827E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -1.43500E-01 MeV Emin = 1.43533E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -1.62300E-01 MeV Emin = 1.62591E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -1.89300E-01 MeV Emin = 1.88707E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -2.38000E-01 MeV Emin = 2.38794E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -2.44000E-01 MeV Emin = 2.44823E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -2.66000E-01 MeV Emin = 2.58716E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 91 Q = -2.67000E-01 MeV Emin = 2.67606E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 16 MT = 102 Q = 5.16000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 95244.82c : (n,gamma) + + 2 additional transport branches: + + 1 MT = 18 Q = 2.03620E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + 2 MT = 102 Q = 5.16000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 95644.82c : (n,gamma) + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 4.23175E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 4 Q = 5.43870E+00 MeV frac = 1.00000E+00 Product nuclide = 93239.82c : alpha + 2 RTYP = 6 Q = 1.92900E+02 MeV frac = 3.70000E-11 SF without yield : spontaneous fission + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.43870E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 302 / 1657 : 95244.82c -- americium 244 (Am-244) + + Pointers : 3136399 19051 + Primary type : Transport + Nuclide ZAI : 952440 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Am244.ACE + Atomic weight (AW) : 244.06465 + Atomic weight ratio (AWR) : 241.96800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 3.64E+04 seconds (10.1 hours) + Specific ingestion toxicity : 4.60E-10 Sv/Bq + Specific inhalation toxicity : 3.70E-09 Sv/Bq + Energy deposited per fission : 208.83 MeV + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide is using NFY data from Cm-245 + - Nuclide has no SFY data + + - 32 reaction channels + - 2 special reactions + - 5 transmutation reactions + - 1 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 32 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.36319E+00 MeV Emin = 5.38540E+00 MeV frac = 1.00000E+00 Product nuclide = 95243.82c : (n,2n) + 3 MT = 17 Q = -1.17275E+01 MeV Emin = 1.17760E+01 MeV frac = 1.00000E+00 Product nuclide = 95242.82c : (n,3n) + 4 MT = 18 Q = 1.99999E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : total fission + 5 MT = 37 Q = -1.72687E+01 MeV Emin = 1.73401E+01 MeV frac = 1.00000E+00 Product nuclide = 95241.82c : (n,4n) + 6 MT = 51 Q = -8.79999E-02 MeV Emin = 8.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.00309E-01 MeV Emin = 1.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -1.23281E-01 MeV Emin = 1.20000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -1.48283E-01 MeV Emin = 1.44448E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -1.75657E-01 MeV Emin = 1.72287E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -1.83511E-01 MeV Emin = 1.80000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -1.97295E-01 MeV Emin = 1.95082E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -2.28299E-01 MeV Emin = 2.20000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -2.61696E-01 MeV Emin = 2.60000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -2.72202E-01 MeV Emin = 2.68712E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -2.89212E-01 MeV Emin = 2.85203E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -2.96658E-01 MeV Emin = 2.94146E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -3.22751E-01 MeV Emin = 3.18064E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -3.35575E-01 MeV Emin = 3.31328E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -3.42650E-01 MeV Emin = 3.38738E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 21 MT = 66 Q = -3.43658E-01 MeV Emin = 3.44572E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 22 MT = 67 Q = -3.48405E-01 MeV Emin = 3.47462E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 23 MT = 68 Q = -3.61837E-01 MeV Emin = 3.62519E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 24 MT = 69 Q = -3.77056E-01 MeV Emin = 3.71461E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 25 MT = 70 Q = -3.90027E-01 MeV Emin = 3.91356E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 26 MT = 71 Q = -3.98742E-01 MeV Emin = 4.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 27 MT = 72 Q = -4.14688E-01 MeV Emin = 4.15897E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 28 MT = 73 Q = -4.18956E-01 MeV Emin = 4.20478E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 29 MT = 74 Q = -4.20130E-01 MeV Emin = 4.21712E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 30 MT = 75 Q = -4.21203E-01 MeV Emin = 4.22240E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 31 MT = 91 Q = -4.34999E-01 MeV Emin = 4.36547E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 32 MT = 102 Q = 6.05299E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 952450 : (n,gamma) + + 1 additional transport branch: + + 1 MT = 18 Q = 1.99999E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 8.00000E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.87111E-01 MeV frac = 1.00000E+00 Product nuclide = 962441 : beta- + + Nuclide 303 / 1657 : 95644.82c -- americium 244m (Am-244m) + + Pointers : 3159538 19097 + Primary type : Transport + Nuclide ZAI : 952441 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Am244M.ACE + Atomic weight (AW) : 244.06465 + Atomic weight ratio (AWR) : 241.96800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.56E+03 seconds (26 minutes) + Specific ingestion toxicity : 2.90E-11 Sv/Bq + Specific inhalation toxicity : 1.60E-10 Sv/Bq + Energy deposited per fission : 208.83 MeV + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide is using NFY data from Cm-245 + - Nuclide has no SFY data + + - 32 reaction channels + - 2 special reactions + - 5 transmutation reactions + - 1 transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 32 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.36319E+00 MeV Emin = 5.38540E+00 MeV frac = 1.00000E+00 Product nuclide = 95243.82c : (n,2n) + 3 MT = 17 Q = -1.17275E+01 MeV Emin = 1.17760E+01 MeV frac = 1.00000E+00 Product nuclide = 95242.82c : (n,3n) + 4 MT = 18 Q = 1.99999E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : total fission + 5 MT = 37 Q = -1.72687E+01 MeV Emin = 1.73401E+01 MeV frac = 1.00000E+00 Product nuclide = 95241.82c : (n,4n) + 6 MT = 51 Q = 8.79999E-02 MeV Emin = 1.90000E-03 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.23090E-02 MeV Emin = 1.20000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -3.52810E-02 MeV Emin = 3.50000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -6.02829E-02 MeV Emin = 6.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -8.76569E-02 MeV Emin = 8.40097E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -9.55109E-02 MeV Emin = 9.36911E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -1.09295E-01 MeV Emin = 1.04873E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -1.40299E-01 MeV Emin = 1.40000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -1.73696E-01 MeV Emin = 1.70811E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -1.84202E-01 MeV Emin = 1.82481E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -2.01212E-01 MeV Emin = 2.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -2.08658E-01 MeV Emin = 2.06716E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -2.34751E-01 MeV Emin = 2.31791E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -2.47575E-01 MeV Emin = 2.44299E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -2.54650E-01 MeV Emin = 2.53038E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 21 MT = 66 Q = -2.55658E-01 MeV Emin = 2.56366E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 22 MT = 67 Q = -2.60405E-01 MeV Emin = 2.60000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 23 MT = 68 Q = -2.73838E-01 MeV Emin = 2.69069E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 24 MT = 69 Q = -2.89057E-01 MeV Emin = 2.85126E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 25 MT = 70 Q = -3.02028E-01 MeV Emin = 3.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 26 MT = 71 Q = -3.10743E-01 MeV Emin = 3.07652E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 27 MT = 72 Q = -3.26689E-01 MeV Emin = 3.20033E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 28 MT = 73 Q = -3.30957E-01 MeV Emin = 3.32138E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 29 MT = 74 Q = -3.32131E-01 MeV Emin = 3.32821E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 30 MT = 75 Q = -3.33204E-01 MeV Emin = 3.34043E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 31 MT = 91 Q = -3.47000E-01 MeV Emin = 3.43239E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 32 MT = 102 Q = 6.14099E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 952450 : (n,gamma) + + 1 additional transport branch: + + 1 MT = 18 Q = 1.99999E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 1.90000E-03 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 2 Q = 1.64000E-01 MeV frac = 3.60000E-04 Product nuclide = 94244.82c : EC/beta+ + 2 RTYP = 1 Q = 1.51600E+00 MeV frac = 9.99640E-01 Product nuclide = 96244.82c : beta- + + Nuclide 304 / 1657 : 96240.82c -- curium 240 (Cm-240) + + Pointers : 3190564 21673 + Primary type : Transport + Nuclide ZAI : 962400 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Cm240.ACE + Atomic weight (AW) : 240.05520 + Atomic weight ratio (AWR) : 237.99300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.33E+06 seconds (27 days) + Specific ingestion toxicity : 7.60E-09 Sv/Bq + Specific inhalation toxicity : 3.50E-06 Sv/Bq + Energy deposited per fission : 208.83 MeV + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide is using NFY data from U-236 + - Nuclide has no SFY data + + - 7 reaction channels + - 2 special reactions + - 4 transmutation reactions + - 1 transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 7 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.44964E+00 MeV Emin = 7.48094E+00 MeV frac = 1.00000E+00 Product nuclide = 962390 : (n,2n) + 3 MT = 17 Q = -1.38173E+01 MeV Emin = 1.38754E+01 MeV frac = 1.00000E+00 Product nuclide = 962380 : (n,3n) + 4 MT = 18 Q = 2.00000E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : total fission + 5 MT = 51 Q = -3.80000E-02 MeV Emin = 3.81250E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 91 Q = -6.00000E-02 MeV Emin = 5.51261E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 7 MT = 102 Q = 6.07643E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 96241.82c : (n,gamma) + + 1 additional transport branch: + + 1 MT = 18 Q = 2.00000E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 3.81250E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 4 Q = 6.39780E+00 MeV frac = 9.97000E-01 Product nuclide = 94236.82c : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 6.39780E+00 MeV frac = 9.97000E-01 Product nuclide = 2004.82c : alpha + + Nuclide 305 / 1657 : 96241.82c -- curium 241 (Cm-241) + + Pointers : 3206251 21719 + Primary type : Transport + Nuclide ZAI : 962410 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Cm241.ACE + Atomic weight (AW) : 241.05781 + Atomic weight ratio (AWR) : 238.98700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.83E+06 seconds (32.8 days) + Specific ingestion toxicity : 9.10E-10 Sv/Bq + Specific inhalation toxicity : 3.70E-08 Sv/Bq + Energy deposited per fission : 218.09 MeV + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide is using NFY data from Np-238 + - Nuclide has no SFY data + + - 11 reaction channels + - 2 special reactions + - 5 transmutation reactions + - 2 transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 11 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.04470E+00 MeV Emin = 6.07000E+00 MeV frac = 1.00000E+00 Product nuclide = 96240.82c : (n,2n) + 3 MT = 17 Q = -1.35300E+01 MeV Emin = 1.35866E+01 MeV frac = 1.00000E+00 Product nuclide = 962390 : (n,3n) + 4 MT = 19 Q = 2.08867E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : (n,f) + 5 MT = 20 Q = 2.08867E+02 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : (n,nf) + 6 MT = 51 Q = -1.59330E-02 MeV Emin = 1.50000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -5.27790E-02 MeV Emin = 5.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -1.03570E-01 MeV Emin = 1.03750E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -2.53940E-01 MeV Emin = 2.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 91 Q = -2.53940E-01 MeV Emin = 2.65001E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 11 MT = 102 Q = 6.96800E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 96242.82c : (n,gamma) + + 2 additional transport branches: + + 1 MT = 19 Q = 2.08867E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : (n,f) + 2 MT = 20 Q = 2.08867E+02 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : (n,nf) + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 1.50000E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 2 Q = 7.69000E-01 MeV frac = 9.90000E-01 Product nuclide = 95241.82c : EC/beta+ + 2 RTYP = 4 Q = 6.18430E+00 MeV frac = 1.00000E-02 Product nuclide = 94237.82c : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 6.18430E+00 MeV frac = 1.00000E-02 Product nuclide = 2004.82c : alpha + + Nuclide 306 / 1657 : 96242.82c -- curium 242 (Cm-242) + + Pointers : 3227751 21765 + Primary type : Transport + Nuclide ZAI : 962420 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Cm242.ACE + Atomic weight (AW) : 242.05841 + Atomic weight ratio (AWR) : 239.97900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.41E+07 seconds (163 days) + Specific ingestion toxicity : 1.20E-08 Sv/Bq + Specific inhalation toxicity : 5.90E-06 Sv/Bq + Energy deposited per fission : 220.44 MeV + Spontaneous fission nubar : 2.52800 + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has delayed neutron data in 8 precursor groups + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide is using NFY data from U-238 + - Nuclide has SFY data + + - 9 reaction channels + - 2 special reactions + - 4 transmutation reactions + - 1 transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 9 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.96900E+00 MeV Emin = 6.99804E+00 MeV frac = 1.00000E+00 Product nuclide = 96241.82c : (n,2n) + 3 MT = 17 Q = -1.30539E+01 MeV Emin = 1.31083E+01 MeV frac = 1.00000E+00 Product nuclide = 96240.82c : (n,3n) + 4 MT = 18 Q = 2.11122E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + 5 MT = 51 Q = -4.22000E-02 MeV Emin = 4.20000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -1.38000E-01 MeV Emin = 1.30000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -2.84000E-01 MeV Emin = 2.82000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 91 Q = -2.90000E-01 MeV Emin = 2.90000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 9 MT = 102 Q = 5.69329E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 96243.82c : (n,gamma) + + 1 additional transport branch: + + 1 MT = 18 Q = 2.11122E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 1.40000E+01 MeV) : total fission + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 4.20000E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 4 Q = 6.21556E+00 MeV frac = 1.00000E+00 Product nuclide = 94238.82c : alpha + 2 RTYP = 6 Q = 1.93200E+02 MeV frac = 6.10000E-08 SFY (E = 0.00000E+00 MeV) : spontaneous fission + + 1 additional decay branch: + + 1 RTYP = 4 Q = 6.21556E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 307 / 1657 : 96243.82c -- curium 243 (Cm-243) + + Pointers : 3256600 21811 + Primary type : Transport + Nuclide ZAI : 962430 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Cm243.ACE + Atomic weight (AW) : 243.06102 + Atomic weight ratio (AWR) : 240.97300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 9.12E+08 seconds (28.9 years) + Specific ingestion toxicity : 1.50E-07 Sv/Bq + Specific inhalation toxicity : 6.90E-05 Sv/Bq + Energy deposited per fission : 221.65 MeV + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has delayed neutron data in 8 precursor groups + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has NFY data + - Nuclide has no SFY data + + - 19 reaction channels + - 2 special reactions + - 5 transmutation reactions + - 1 transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 19 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.70100E+00 MeV Emin = 5.72470E+00 MeV frac = 1.00000E+00 Product nuclide = 96242.82c : (n,2n) + 3 MT = 17 Q = -1.26620E+01 MeV Emin = 1.27146E+01 MeV frac = 1.00000E+00 Product nuclide = 96241.82c : (n,3n) + 4 MT = 18 Q = 2.12282E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : total fission + 5 MT = 37 Q = -1.87497E+01 MeV Emin = 1.88275E+01 MeV frac = 1.00000E+00 Product nuclide = 96240.82c : (n,4n) + 6 MT = 51 Q = -4.20000E-02 MeV Emin = 4.10000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -8.70000E-02 MeV Emin = 8.50000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -9.30000E-02 MeV Emin = 9.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -9.40000E-02 MeV Emin = 9.40000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -1.33000E-01 MeV Emin = 1.26776E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -1.53000E-01 MeV Emin = 1.46817E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -1.56000E-01 MeV Emin = 1.55325E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -1.64000E-01 MeV Emin = 1.60000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -1.73000E-01 MeV Emin = 1.69360E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -2.19000E-01 MeV Emin = 2.10000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -2.28000E-01 MeV Emin = 2.24475E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -2.60000E-01 MeV Emin = 2.56000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 91 Q = -2.70000E-01 MeV Emin = 2.70000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 19 MT = 102 Q = 6.79949E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 96244.82c : (n,gamma) + + 1 additional transport branch: + + 1 MT = 18 Q = 2.12282E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 4.10000E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 2 Q = 7.50000E-03 MeV frac = 2.90000E-03 Product nuclide = 95243.82c : EC/beta+ + 2 RTYP = 4 Q = 6.16880E+00 MeV frac = 9.97100E-01 Product nuclide = 94239.82c : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 6.16880E+00 MeV frac = 9.97100E-01 Product nuclide = 2004.82c : alpha + + Nuclide 308 / 1657 : 96244.82c -- curium 244 (Cm-244) + + Pointers : 3281310 21857 + Primary type : Transport + Nuclide ZAI : 962440 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Cm244.ACE + Atomic weight (AW) : 244.06263 + Atomic weight ratio (AWR) : 241.96600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 5.68E+08 seconds (18 years) + Specific ingestion toxicity : 1.20E-07 Sv/Bq + Specific inhalation toxicity : 5.70E-05 Sv/Bq + Energy deposited per fission : 213.43 MeV + Spontaneous fission nubar : 2.68750 + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has delayed neutron data in 8 precursor groups + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has NFY data + - Nuclide has SFY data + + - 10 reaction channels + - 2 special reactions + - 5 transmutation reactions + - 2 transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 10 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.77100E+00 MeV Emin = 6.79900E+00 MeV frac = 1.00000E+00 Product nuclide = 96243.82c : (n,2n) + 3 MT = 17 Q = -1.24987E+01 MeV Emin = 1.25504E+01 MeV frac = 1.00000E+00 Product nuclide = 96242.82c : (n,3n) + 4 MT = 19 Q = 2.04409E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : (n,f) + 5 MT = 20 Q = 2.04409E+02 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : (n,nf) + 6 MT = 51 Q = -4.28230E-02 MeV Emin = 4.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.41420E-01 MeV Emin = 1.40000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -2.94780E-01 MeV Emin = 2.60000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 91 Q = -2.94780E-01 MeV Emin = 2.60000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 10 MT = 102 Q = 5.52000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 96245.82c : (n,gamma) + + 2 additional transport branches: + + 1 MT = 19 Q = 2.04409E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : (n,f) + 2 MT = 20 Q = 2.04409E+02 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : (n,nf) + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 4.00000E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 4 Q = 5.90161E+00 MeV frac = 9.99999E-01 Product nuclide = 94240.82c : alpha + 2 RTYP = 6 Q = 1.91800E+02 MeV frac = 1.38000E-06 SFY (E = 0.00000E+00 MeV) : spontaneous fission + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.90161E+00 MeV frac = 9.99999E-01 Product nuclide = 2004.82c : alpha + + Nuclide 309 / 1657 : 96245.82c -- curium 245 (Cm-245) + + Pointers : 3314766 21903 + Primary type : Transport + Nuclide ZAI : 962450 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Cm245.ACE + Atomic weight (AW) : 245.06524 + Atomic weight ratio (AWR) : 242.96000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.60E+11 seconds (8,255 years) + Specific ingestion toxicity : 2.10E-07 Sv/Bq + Specific inhalation toxicity : 9.90E-05 Sv/Bq + Energy deposited per fission : 208.83 MeV + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has delayed neutron data in 8 precursor groups + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has NFY data + - Nuclide has no SFY data + + - 23 reaction channels + - 2 special reactions + - 4 transmutation reactions + - 1 transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 23 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.52000E+00 MeV Emin = 5.54272E+00 MeV frac = 1.00000E+00 Product nuclide = 96244.82c : (n,2n) + 3 MT = 17 Q = -1.23200E+01 MeV Emin = 1.23707E+01 MeV frac = 1.00000E+00 Product nuclide = 96243.82c : (n,3n) + 4 MT = 18 Q = 2.00000E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : total fission + 5 MT = 51 Q = -5.47300E-02 MeV Emin = 5.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -1.21400E-01 MeV Emin = 1.20000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -1.97100E-01 MeV Emin = 1.85933E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -2.52850E-01 MeV Emin = 2.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -2.92300E-01 MeV Emin = 2.73697E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -2.95840E-01 MeV Emin = 2.96955E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -3.50500E-01 MeV Emin = 3.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -3.55950E-01 MeV Emin = 3.54679E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -3.61500E-01 MeV Emin = 3.62738E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -3.87950E-01 MeV Emin = 3.89354E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -3.95700E-01 MeV Emin = 3.94677E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -4.17000E-01 MeV Emin = 4.09358E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 63 Q = -4.18800E-01 MeV Emin = 4.19595E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 18 MT = 64 Q = -4.31000E-01 MeV Emin = 4.25745E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 19 MT = 65 Q = -4.42800E-01 MeV Emin = 4.38699E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 20 MT = 66 Q = -4.98000E-01 MeV Emin = 4.87500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 21 MT = 67 Q = -5.08700E-01 MeV Emin = 5.05422E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 22 MT = 91 Q = -5.11000E-01 MeV Emin = 5.11949E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 23 MT = 102 Q = 6.45000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 96246.82c : (n,gamma) + + 1 additional transport branch: + + 1 MT = 18 Q = 2.00000E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 5.00000E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 4 Q = 5.62230E+00 MeV frac = 1.00000E+00 Product nuclide = 94241.82c : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.62230E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 310 / 1657 : 96246.82c -- curium 246 (Cm-246) + + Pointers : 3338567 21949 + Primary type : Transport + Nuclide ZAI : 962460 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Cm246.ACE + Atomic weight (AW) : 246.06685 + Atomic weight ratio (AWR) : 243.95300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.49E+11 seconds (4,733 years) + Specific ingestion toxicity : 2.10E-07 Sv/Bq + Specific inhalation toxicity : 9.80E-05 Sv/Bq + Energy deposited per fission : 208.83 MeV + Spontaneous fission nubar : 2.94800 + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has delayed neutron data in 8 precursor groups + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide is using NFY data from U-233 + - Nuclide has no SFY data + + - 28 reaction channels + - 2 special reactions + - 6 transmutation reactions + - 6 transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 28 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.45800E+00 MeV Emin = 6.48447E+00 MeV frac = 1.00000E+00 Product nuclide = 96245.82c : (n,2n) + 3 MT = 17 Q = -1.19780E+01 MeV Emin = 1.20271E+01 MeV frac = 1.00000E+00 Product nuclide = 96244.82c : (n,3n) + 4 MT = 19 Q = 2.00000E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : (n,f) + 5 MT = 20 Q = 2.00000E+02 MeV Emin = 5.50000E+00 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : (n,nf) + 6 MT = 21 Q = 2.00000E+02 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : (n,2nf) + 7 MT = 51 Q = -4.28520E-02 MeV Emin = 3.75000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 8 MT = 52 Q = -1.42010E-01 MeV Emin = 1.21296E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 9 MT = 53 Q = -2.94900E-01 MeV Emin = 2.48055E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 10 MT = 54 Q = -5.00400E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 11 MT = 55 Q = -7.82070E-01 MeV Emin = 7.75000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 12 MT = 56 Q = -8.41670E-01 MeV Emin = 8.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 13 MT = 57 Q = -8.76430E-01 MeV Emin = 8.62572E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 14 MT = 58 Q = -9.23310E-01 MeV Emin = 9.26912E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 15 MT = 59 Q = -9.80000E-01 MeV Emin = 9.63013E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 16 MT = 60 Q = -1.05170E+00 MeV Emin = 1.02801E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 17 MT = 61 Q = -1.07885E+00 MeV Emin = 1.06964E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 18 MT = 62 Q = -1.10485E+00 MeV Emin = 1.10893E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 19 MT = 63 Q = -1.12427E+00 MeV Emin = 1.11748E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 20 MT = 64 Q = -1.12802E+00 MeV Emin = 1.13076E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 21 MT = 65 Q = -1.12940E+00 MeV Emin = 1.13334E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 22 MT = 66 Q = -1.16549E+00 MeV Emin = 1.16997E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 23 MT = 67 Q = -1.17474E+00 MeV Emin = 1.17934E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 24 MT = 68 Q = -1.17920E+00 MeV Emin = 1.18247E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 25 MT = 69 Q = -1.19590E+00 MeV Emin = 1.20000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 26 MT = 70 Q = -1.21053E+00 MeV Emin = 1.20815E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 27 MT = 91 Q = -1.22000E+00 MeV Emin = 1.22025E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 28 MT = 102 Q = 5.16000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 96247.82c : (n,gamma) + + 6 additional transport branches: + + 1 MT = 19 Q = 2.00000E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 1.40000E+01 MeV) : (n,f) + 2 MT = 19 Q = 2.00000E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : (n,f) + 3 MT = 20 Q = 2.00000E+02 MeV Emin = 5.50000E+00 MeV frac = 1.00000E+00 NFY (E = 1.40000E+01 MeV) : (n,nf) + 4 MT = 20 Q = 2.00000E+02 MeV Emin = 5.50000E+00 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : (n,nf) + 5 MT = 21 Q = 2.00000E+02 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 NFY (E = 1.40000E+01 MeV) : (n,2nf) + 6 MT = 21 Q = 2.00000E+02 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : (n,2nf) + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 3.75000E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 4 Q = 5.47620E+00 MeV frac = 9.99739E-01 Product nuclide = 94242.82c : alpha + 2 RTYP = 6 Q = 1.90400E+02 MeV frac = 2.61400E-04 SF without yield : spontaneous fission + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.47620E+00 MeV frac = 9.99739E-01 Product nuclide = 2004.82c : alpha + + Nuclide 311 / 1657 : 96247.82c -- curium 247 (Cm-247) + + Pointers : 3369474 21995 + Primary type : Transport + Nuclide ZAI : 962470 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Cm247.ACE + Atomic weight (AW) : 247.06946 + Atomic weight ratio (AWR) : 244.94700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 5.05E+14 seconds (16 million years) + Specific ingestion toxicity : 1.90E-07 Sv/Bq + Specific inhalation toxicity : 9.00E-05 Sv/Bq + Energy deposited per fission : 208.83 MeV + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide is using NFY data from U-233 + - Nuclide has no SFY data + + - 22 reaction channels + - 2 special reactions + - 5 transmutation reactions + - 2 transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 22 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.15769E+00 MeV Emin = 5.17876E+00 MeV frac = 1.00000E+00 Product nuclide = 96246.82c : (n,2n) + 3 MT = 17 Q = -1.16147E+01 MeV Emin = 1.16621E+01 MeV frac = 1.00000E+00 Product nuclide = 96245.82c : (n,3n) + 4 MT = 18 Q = 1.99999E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : total fission + 5 MT = 37 Q = -1.71347E+01 MeV Emin = 1.72047E+01 MeV frac = 1.00000E+00 Product nuclide = 96244.82c : (n,4n) + 6 MT = 51 Q = -6.14999E-02 MeV Emin = 6.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.35000E-01 MeV Emin = 1.26663E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -2.17000E-01 MeV Emin = 2.08943E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -2.27000E-01 MeV Emin = 2.23534E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -2.66000E-01 MeV Emin = 2.58543E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -2.85000E-01 MeV Emin = 2.81394E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -3.18000E-01 MeV Emin = 3.09649E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -3.44000E-01 MeV Emin = 3.39286E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -3.60999E-01 MeV Emin = 3.56237E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -3.95999E-01 MeV Emin = 3.89380E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -4.03599E-01 MeV Emin = 4.02624E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -4.32999E-01 MeV Emin = 4.27849E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -4.48999E-01 MeV Emin = 4.50663E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -5.05999E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -5.19999E-01 MeV Emin = 5.16852E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 21 MT = 91 Q = -5.49999E-01 MeV Emin = 5.39067E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 22 MT = 102 Q = 6.45699E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 96248.82c : (n,gamma) + + 2 additional transport branches: + + 1 MT = 18 Q = 1.99999E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 1.40000E+01 MeV) : total fission + 2 MT = 18 Q = 1.99999E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 6.00000E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 4 Q = 5.35300E+00 MeV frac = 1.00000E+00 Product nuclide = 94243.82c : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.35300E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 312 / 1657 : 96248.82c -- curium 248 (Cm-248) + + Pointers : 3399881 22041 + Primary type : Transport + Nuclide ZAI : 962480 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Cm248.ACE + Atomic weight (AW) : 248.07207 + Atomic weight ratio (AWR) : 245.94100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.07E+13 seconds (340,233 years) + Specific ingestion toxicity : 7.70E-07 Sv/Bq + Specific inhalation toxicity : 3.60E-04 Sv/Bq + Energy deposited per fission : 225.00 MeV + Spontaneous fission nubar : 3.16100 + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has delayed neutron data in 8 precursor groups + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide is using NFY data from U-233 + - Nuclide has no SFY data + + - 15 reaction channels + - 2 special reactions + - 5 transmutation reactions + - 2 transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 15 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.21269E+00 MeV Emin = 6.23800E+00 MeV frac = 1.00000E+00 Product nuclide = 96247.82c : (n,2n) + 3 MT = 17 Q = -1.13704E+01 MeV Emin = 1.14166E+01 MeV frac = 1.00000E+00 Product nuclide = 96246.82c : (n,3n) + 4 MT = 18 Q = 2.15490E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : total fission + 5 MT = 37 Q = -1.78274E+01 MeV Emin = 1.78999E+01 MeV frac = 1.00000E+00 Product nuclide = 96245.82c : (n,4n) + 6 MT = 51 Q = -4.33999E-02 MeV Emin = 4.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.43600E-01 MeV Emin = 1.37092E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -2.97000E-01 MeV Emin = 2.86156E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -5.09999E-01 MeV Emin = 5.06037E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -1.04800E+00 MeV Emin = 1.02613E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -1.05000E+00 MeV Emin = 1.05358E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -1.08400E+00 MeV Emin = 1.07561E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -1.09400E+00 MeV Emin = 1.09792E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 91 Q = -1.12600E+00 MeV Emin = 1.12936E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 15 MT = 102 Q = 4.71269E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 96249.82c : (n,gamma) + + 2 additional transport branches: + + 1 MT = 18 Q = 2.15490E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 1.40000E+01 MeV) : total fission + 2 MT = 18 Q = 2.15490E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 4.00000E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 4 Q = 5.16180E+00 MeV frac = 9.17400E-01 Product nuclide = 94244.82c : alpha + 2 RTYP = 6 Q = 1.89600E+02 MeV frac = 8.26000E-02 SF without yield : spontaneous fission + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.16180E+00 MeV frac = 9.17400E-01 Product nuclide = 2004.82c : alpha + + Nuclide 313 / 1657 : 96249.82c -- curium 249 (Cm-249) + + Pointers : 3429575 22087 + Primary type : Transport + Nuclide ZAI : 962490 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Cm249.ACE + Atomic weight (AW) : 249.07569 + Atomic weight ratio (AWR) : 246.93600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 3.85E+03 seconds (1.07 hours) + Specific ingestion toxicity : 3.10E-11 Sv/Bq + Specific inhalation toxicity : 4.00E-11 Sv/Bq + Energy deposited per fission : 208.83 MeV + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide is using NFY data from U-233 + - Nuclide has no SFY data + + - 25 reaction channels + - 2 special reactions + - 4 transmutation reactions + - 2 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 25 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -4.71340E+00 MeV Emin = 4.73249E+00 MeV frac = 1.00000E+00 Product nuclide = 96248.82c : (n,2n) + 3 MT = 17 Q = -1.09248E+01 MeV Emin = 1.09690E+01 MeV frac = 1.00000E+00 Product nuclide = 96247.82c : (n,3n) + 4 MT = 18 Q = 2.00000E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : total fission + 5 MT = 51 Q = -2.62340E-02 MeV Emin = 2.56701E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -4.82030E-02 MeV Emin = 4.60984E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -4.87430E-02 MeV Emin = 4.88988E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -1.09000E-01 MeV Emin = 1.04720E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -1.10160E-01 MeV Emin = 1.10024E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -1.46000E-01 MeV Emin = 1.42980E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -2.07990E-01 MeV Emin = 2.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -2.20000E-01 MeV Emin = 2.17876E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -2.42010E-01 MeV Emin = 2.37465E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -2.88990E-01 MeV Emin = 2.80120E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -3.00000E-01 MeV Emin = 3.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -3.50000E-01 MeV Emin = 3.42004E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 63 Q = -4.70210E-01 MeV Emin = 4.57027E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 18 MT = 64 Q = -4.94490E-01 MeV Emin = 4.90398E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 19 MT = 65 Q = -4.98000E-01 MeV Emin = 4.98246E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 20 MT = 66 Q = -5.29610E-01 MeV Emin = 5.23821E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 21 MT = 67 Q = -5.46860E-01 MeV Emin = 5.42580E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 22 MT = 68 Q = -5.78430E-01 MeV Emin = 5.72848E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 23 MT = 69 Q = -6.34000E-01 MeV Emin = 6.24362E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 24 MT = 91 Q = -6.88000E-01 MeV Emin = 6.78926E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 25 MT = 102 Q = 5.83243E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 96250.82c : (n,gamma) + + 2 additional transport branches: + + 1 MT = 18 Q = 2.00000E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 1.40000E+01 MeV) : total fission + 2 MT = 18 Q = 2.00000E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 2.56701E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.03000E-01 MeV frac = 1.00000E+00 Product nuclide = 972490 : beta- + + Nuclide 314 / 1657 : 96250.82c -- curium 250 (Cm-250) + + Pointers : 3460870 22133 + Primary type : Transport + Nuclide ZAI : 962500 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Cm250.ACE + Atomic weight (AW) : 250.07831 + Atomic weight ratio (AWR) : 247.93000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.52E+11 seconds (8,005 years) + Specific ingestion toxicity : 4.40E-06 Sv/Bq + Specific inhalation toxicity : 2.10E-03 Sv/Bq + Energy deposited per fission : 208.83 MeV + Spontaneous fission nubar : 3.30000 + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide is using NFY data from U-233 + - Nuclide has no SFY data + + - 8 reaction channels + - 2 special reactions + - 4 transmutation reactions + - 2 transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 8 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.82930E+00 MeV Emin = 5.85281E+00 MeV frac = 1.00000E+00 Product nuclide = 96249.82c : (n,2n) + 3 MT = 17 Q = -1.05482E+01 MeV Emin = 1.05908E+01 MeV frac = 1.00000E+00 Product nuclide = 96248.82c : (n,3n) + 4 MT = 18 Q = 2.00000E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : total fission + 5 MT = 51 Q = -4.30000E-02 MeV Emin = 4.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -1.42000E-01 MeV Emin = 1.37251E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 91 Q = -1.60000E-01 MeV Emin = 1.57984E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 8 MT = 102 Q = 4.40643E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 962510 : (n,gamma) + + 2 additional transport branches: + + 1 MT = 18 Q = 2.00000E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 1.40000E+01 MeV) : total fission + 2 MT = 18 Q = 2.00000E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 4.00000E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 4 Q = 5.17000E+00 MeV frac = 3.00000E-01 Product nuclide = 942460 : alpha + 2 RTYP = 6 Q = 1.89900E+02 MeV frac = 7.00000E-01 SF without yield : spontaneous fission + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.17000E+00 MeV frac = 3.00000E-01 Product nuclide = 2004.82c : alpha + + Nuclide 315 / 1657 : 20060 -- helium 6 (He-6) + + Pointers : 52722 -1000000 + Primary type : Decay + Nuclide ZAI : 20060 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 6.01889 + Atomic weight ratio (AWR) : 5.96718 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.808 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.50700E+00 MeV frac = 1.00000E+00 Product nuclide = 3006.82c : beta- + + Nuclide 316 / 1657 : 20080 -- helium 8 (He-8) + + Pointers : 52939 -1000000 + Primary type : Decay + Nuclide ZAI : 20080 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 8.03393 + Atomic weight ratio (AWR) : 7.96491 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.122 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.06490E+01 MeV frac = 8.80000E-01 Product nuclide = 30080 : beta- + 2 RTYP = 15 Q = 8.61600E+00 MeV frac = 1.20000E-01 Product nuclide = 3007.82c : beta- + neutron emission + + Nuclide 317 / 1657 : 30080 -- lithium 8 (Li-8) + + Pointers : 58339 -1000000 + Primary type : Decay + Nuclide ZAI : 30080 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 8.02249 + Atomic weight ratio (AWR) : 7.95357 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.838 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 14 Q = 1.60970E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : beta- + alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 1.60970E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 318 / 1657 : 30090 -- lithium 9 (Li-9) + + Pointers : 58657 -1000000 + Primary type : Decay + Nuclide ZAI : 30090 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 9.02679 + Atomic weight ratio (AWR) : 8.94925 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.178 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.36060E+01 MeV frac = 5.05000E-01 Product nuclide = 4009.82c : beta- + 2 RTYP = 15 Q = 1.19410E+01 MeV frac = 4.95000E-01 Product nuclide = 40080 : beta- + neutron emission + + Nuclide 319 / 1657 : 40060 -- beryllium 6 (Be-6) + + Pointers : 59003 -1000000 + Primary type : Decay + Nuclide ZAI : 40060 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 6.01972 + Atomic weight ratio (AWR) : 5.96801 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5E-12 nanoseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 2 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 77 Q = 1.37208E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : proton emission + proton emission + + 2 additional decay branches: + + 1 RTYP = 7 Q = 1.37208E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : proton emission + 2 RTYP = 7 Q = 1.37208E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : proton emission + + Nuclide 320 / 1657 : 40080 -- beryllium 8 (Be-8) + + Pointers : 59333 -1000000 + Primary type : Decay + Nuclide ZAI : 40080 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 8.00531 + Atomic weight ratio (AWR) : 7.93654 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7E-08 nanoseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 4 Q = 9.18900E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 9.18900E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 321 / 1657 : 40100 -- beryllium 10 (Be-10) + + Pointers : 61997 -1000000 + Primary type : Decay + Nuclide ZAI : 40100 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 10.01353 + Atomic weight ratio (AWR) : 9.92751 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.05E+13 seconds (1.6 million years) + Specific ingestion toxicity : 1.10E-09 Sv/Bq + Specific inhalation toxicity : 3.50E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.55900E-01 MeV frac = 1.00000E+00 Product nuclide = 5010.82c : beta- + + Nuclide 322 / 1657 : 40110 -- beryllium 11 (Be-11) + + Pointers : 62214 -1000000 + Primary type : Decay + Nuclide ZAI : 40110 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 11.02168 + Atomic weight ratio (AWR) : 10.92700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 13.8 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.15080E+01 MeV frac = 9.70000E-01 Product nuclide = 5011.82c : beta- + 2 RTYP = 14 Q = 2.84300E+00 MeV frac = 3.00000E-02 Product nuclide = 3007.82c : beta- + alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 2.84300E+00 MeV frac = 3.00000E-02 Product nuclide = 2004.82c : alpha + + Nuclide 323 / 1657 : 40120 -- beryllium 12 (Be-12) + + Pointers : 62801 -1000000 + Primary type : Decay + Nuclide ZAI : 40120 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 12.02692 + Atomic weight ratio (AWR) : 11.92360 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 21.3 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.17080E+01 MeV frac = 1.00000E+00 Product nuclide = 50120 : beta- + + Nuclide 324 / 1657 : 50090 -- boron 9 (B-9) + + Pointers : 63018 -1000000 + Primary type : Decay + Nuclide ZAI : 50090 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 9.01333 + Atomic weight ratio (AWR) : 8.93590 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8E-10 nanoseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 7 Q = 1.85031E-01 MeV frac = 1.00000E+00 Product nuclide = 40080 : proton emission + + 1 additional decay branch: + + 1 RTYP = 7 Q = 1.85031E-01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : proton emission + + Nuclide 325 / 1657 : 50120 -- boron 12 (B-12) + + Pointers : 69921 -1000000 + Primary type : Decay + Nuclide ZAI : 50120 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 12.01431 + Atomic weight ratio (AWR) : 11.91110 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 20.2 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.33700E+01 MeV frac = 9.84200E-01 Product nuclide = 60120 : beta- + 2 RTYP = 14 Q = 6.00300E+00 MeV frac = 1.58000E-02 Product nuclide = 40080 : beta- + alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 6.00300E+00 MeV frac = 1.58000E-02 Product nuclide = 2004.82c : alpha + + Nuclide 326 / 1657 : 60080 -- carbon 8 (C-8) + + Pointers : 70396 -1000000 + Primary type : Decay + Nuclide ZAI : 60080 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 8.03768 + Atomic weight ratio (AWR) : 7.96863 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2E-12 nanoseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 2 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 77 Q = 2.14100E+00 MeV frac = 1.00000E+00 Product nuclide = 40060 : proton emission + proton emission + + 2 additional decay branches: + + 1 RTYP = 7 Q = 2.14100E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : proton emission + 2 RTYP = 7 Q = 2.14100E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : proton emission + + Nuclide 327 / 1657 : 60120 -- carbon 12 (C-12) + + Pointers : 70726 -1000000 + Primary type : Decay + Nuclide ZAI : 60120 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 11.99999 + Atomic weight ratio (AWR) : 11.89690 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 328 / 1657 : 60130 -- carbon 13 (C-13) + + Pointers : 70832 -1000000 + Primary type : Decay + Nuclide ZAI : 60130 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 13.00331 + Atomic weight ratio (AWR) : 12.89160 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 329 / 1657 : 60140 -- carbon 14 (C-14) + + Pointers : 70938 -1000000 + Primary type : Decay + Nuclide ZAI : 60140 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 14.00319 + Atomic weight ratio (AWR) : 13.88290 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.80E+11 seconds (5,704 years) + Specific ingestion toxicity : 5.80E-10 Sv/Bq + Specific inhalation toxicity : 5.80E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.56476E-01 MeV frac = 1.00000E+00 Product nuclide = 7014.82c : beta- + + Nuclide 330 / 1657 : 60150 -- carbon 15 (C-15) + + Pointers : 71155 -1000000 + Primary type : Decay + Nuclide ZAI : 60150 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 15.01065 + Atomic weight ratio (AWR) : 14.88170 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.45 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.77170E+00 MeV frac = 1.00000E+00 Product nuclide = 7015.82c : beta- + + Nuclide 331 / 1657 : 70130 -- nitrogen 13 (N-13) + + Pointers : 71526 -1000000 + Primary type : Decay + Nuclide ZAI : 70130 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 13.00573 + Atomic weight ratio (AWR) : 12.89400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.98E+02 seconds (9.97 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 2.22045E+00 MeV frac = 1.00000E+00 Product nuclide = 60130 : EC/beta+ + + Nuclide 332 / 1657 : 70160 -- nitrogen 16 (N-16) + + Pointers : 79307 -1000000 + Primary type : Decay + Nuclide ZAI : 70160 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 16.00610 + Atomic weight ratio (AWR) : 15.86860 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.13 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.04180E+01 MeV frac = 9.99988E-01 Product nuclide = 8016.82c : beta- + 2 RTYP = 14 Q = 3.25600E+00 MeV frac = 1.20000E-05 Product nuclide = 60120 : beta- + alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 3.25600E+00 MeV frac = 1.20000E-05 Product nuclide = 2004.82c : alpha + + Nuclide 333 / 1657 : 70170 -- nitrogen 17 (N-17) + + Pointers : 79964 -1000000 + Primary type : Decay + Nuclide ZAI : 70170 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 17.00841 + Atomic weight ratio (AWR) : 16.86230 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.17 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 1 Q = 8.68000E+00 MeV frac = 5.00000E-02 Product nuclide = 8017.82c : beta- + 2 RTYP = 15 Q = 4.53700E+00 MeV frac = 9.49975E-01 Product nuclide = 8016.82c : beta- + neutron emission + 3 RTYP = 14 Q = 2.32100E+00 MeV frac = 2.50000E-05 Product nuclide = 60130 : beta- + alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 2.32100E+00 MeV frac = 2.50000E-05 Product nuclide = 2004.82c : alpha + + Nuclide 334 / 1657 : 80150 -- oxygen 15 (O-15) + + Pointers : 80694 -1000000 + Primary type : Decay + Nuclide ZAI : 80150 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 15.00308 + Atomic weight ratio (AWR) : 14.87420 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.22E+02 seconds (2.04 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 2.75700E+00 MeV frac = 1.00000E+00 Product nuclide = 7015.82c : EC/beta+ + + Nuclide 335 / 1657 : 80180 -- oxygen 18 (O-18) + + Pointers : 89643 -1000000 + Primary type : Decay + Nuclide ZAI : 80180 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 17.99912 + Atomic weight ratio (AWR) : 17.84450 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 336 / 1657 : 80190 -- oxygen 19 (O-19) + + Pointers : 89749 -1000000 + Primary type : Decay + Nuclide ZAI : 80190 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 19.00355 + Atomic weight ratio (AWR) : 18.84030 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 26.9 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.81900E+00 MeV frac = 1.00000E+00 Product nuclide = 9019.82c : beta- + + Nuclide 337 / 1657 : 90180 -- fluorine 18 (F-18) + + Pointers : 90120 -1000000 + Primary type : Decay + Nuclide ZAI : 90180 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 18.00094 + Atomic weight ratio (AWR) : 17.84630 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.58E+03 seconds (1.83 hours) + Specific ingestion toxicity : 4.90E-11 Sv/Bq + Specific inhalation toxicity : 5.90E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 1.65590E+00 MeV frac = 1.00000E+00 Product nuclide = 80180 : EC/beta+ + + Nuclide 338 / 1657 : 90200 -- fluorine 20 (F-20) + + Pointers : 93629 -1000000 + Primary type : Decay + Nuclide ZAI : 90200 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 20.00001 + Atomic weight ratio (AWR) : 19.82820 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 11 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.02590E+00 MeV frac = 1.00000E+00 Product nuclide = 100200 : beta- + + Nuclide 339 / 1657 : 100200 -- neon 20 (Ne-20) + + Pointers : 93902 -1000000 + Primary type : Decay + Nuclide ZAI : 100200 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 19.99245 + Atomic weight ratio (AWR) : 19.82070 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 340 / 1657 : 100210 -- neon 21 (Ne-21) + + Pointers : 94008 -1000000 + Primary type : Decay + Nuclide ZAI : 100210 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 20.99385 + Atomic weight ratio (AWR) : 20.81350 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 341 / 1657 : 100220 -- neon 22 (Ne-22) + + Pointers : 94114 -1000000 + Primary type : Decay + Nuclide ZAI : 100220 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 21.99142 + Atomic weight ratio (AWR) : 21.80250 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 342 / 1657 : 100230 -- neon 23 (Ne-23) + + Pointers : 94220 -1000000 + Primary type : Decay + Nuclide ZAI : 100230 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 22.99443 + Atomic weight ratio (AWR) : 22.79690 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 37.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.37500E+00 MeV frac = 1.00000E+00 Product nuclide = 11023.82c : beta- + + Nuclide 343 / 1657 : 110210 -- sodium 21 (Na-21) + + Pointers : 94563 -1000000 + Primary type : Decay + Nuclide ZAI : 110210 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 20.99768 + Atomic weight ratio (AWR) : 20.81730 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 22.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 3.54760E+00 MeV frac = 1.00000E+00 Product nuclide = 100210 : EC/beta+ + + Nuclide 344 / 1657 : 110240 -- sodium 24 (Na-24) + + Pointers : 100815 -1000000 + Primary type : Decay + Nuclide ZAI : 110240 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 23.99100 + Atomic weight ratio (AWR) : 23.78490 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.38E+04 seconds (15 hours) + Specific ingestion toxicity : 4.30E-10 Sv/Bq + Specific inhalation toxicity : 2.70E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.51561E+00 MeV frac = 1.00000E+00 Product nuclide = 12024.82c : beta- + + Nuclide 345 / 1657 : 110241 -- sodium 24m (Na-24m) + + Pointers : 101452 -1000000 + Primary type : Decay + Nuclide ZAI : 110241 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 23.99100 + Atomic weight ratio (AWR) : 23.78490 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 20.2 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 4.72300E-01 MeV frac = 9.95000E-01 Product nuclide = 110240 : IT + 2 RTYP = 1 Q = 5.98810E+00 MeV frac = 5.00000E-03 Product nuclide = 12024.82c : beta- + + Nuclide 346 / 1657 : 110250 -- sodium 25 (Na-25) + + Pointers : 101770 -1000000 + Primary type : Decay + Nuclide ZAI : 110250 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 24.98998 + Atomic weight ratio (AWR) : 24.77530 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 59.6 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.83300E+00 MeV frac = 1.00000E+00 Product nuclide = 12025.82c : beta- + + Nuclide 347 / 1657 : 110260 -- sodium 26 (Na-26) + + Pointers : 102197 -1000000 + Primary type : Decay + Nuclide ZAI : 110260 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 25.99259 + Atomic weight ratio (AWR) : 25.76930 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.08 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.32500E+00 MeV frac = 1.00000E+00 Product nuclide = 12026.82c : beta- + + Nuclide 348 / 1657 : 120230 -- magnesium 23 (Mg-23) + + Pointers : 102806 -1000000 + Primary type : Decay + Nuclide ZAI : 120230 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 22.99413 + Atomic weight ratio (AWR) : 22.79660 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 11.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 4.05610E+00 MeV frac = 1.00000E+00 Product nuclide = 11023.82c : EC/beta+ + + Nuclide 349 / 1657 : 120270 -- magnesium 27 (Mg-27) + + Pointers : 109937 -1000000 + Primary type : Decay + Nuclide ZAI : 120270 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 26.98431 + Atomic weight ratio (AWR) : 26.75250 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.67E+02 seconds (9.46 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.60930E+00 MeV frac = 1.00000E+00 Product nuclide = 13027.82c : beta- + + Nuclide 350 / 1657 : 120280 -- magnesium 28 (Mg-28) + + Pointers : 110224 -1000000 + Primary type : Decay + Nuclide ZAI : 120280 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 27.98390 + Atomic weight ratio (AWR) : 27.74350 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.52E+04 seconds (20.9 hours) + Specific ingestion toxicity : 2.20E-09 Sv/Bq + Specific inhalation toxicity : 1.20E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.83180E+00 MeV frac = 1.00000E+00 Product nuclide = 130280 : beta- + + Nuclide 351 / 1657 : 120290 -- magnesium 29 (Mg-29) + + Pointers : 110707 -1000000 + Primary type : Decay + Nuclide ZAI : 120290 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 28.98863 + Atomic weight ratio (AWR) : 28.73960 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.61300E+00 MeV frac = 1.00000E+00 Product nuclide = 130290 : beta- + + Nuclide 352 / 1657 : 130260 -- aluminum 26 (Al-26) + + Pointers : 111302 -1000000 + Primary type : Decay + Nuclide ZAI : 130260 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 25.98684 + Atomic weight ratio (AWR) : 25.76360 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.26E+13 seconds (717,475 years) + Specific ingestion toxicity : 3.50E-09 Sv/Bq + Specific inhalation toxicity : 2.00E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 4.00419E+00 MeV frac = 1.00000E+00 Product nuclide = 12026.82c : EC/beta+ + + Nuclide 353 / 1657 : 130280 -- aluminum 28 (Al-28) + + Pointers : 123040 -1000000 + Primary type : Decay + Nuclide ZAI : 130280 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 27.98188 + Atomic weight ratio (AWR) : 27.74150 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.34E+02 seconds (2.24 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.64310E+00 MeV frac = 1.00000E+00 Product nuclide = 14028.82c : beta- + + Nuclide 354 / 1657 : 130290 -- aluminum 29 (Al-29) + + Pointers : 123285 -1000000 + Primary type : Decay + Nuclide ZAI : 130290 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 28.98046 + Atomic weight ratio (AWR) : 28.73150 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.94E+02 seconds (6.56 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.68100E+00 MeV frac = 1.00000E+00 Product nuclide = 14029.82c : beta- + + Nuclide 355 / 1657 : 130300 -- aluminum 30 (Al-30) + + Pointers : 123656 -1000000 + Primary type : Decay + Nuclide ZAI : 130300 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 29.98297 + Atomic weight ratio (AWR) : 29.72540 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.65 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.53900E+00 MeV frac = 1.00000E+00 Product nuclide = 14030.82c : beta- + + Nuclide 356 / 1657 : 140270 -- silicon 27 (Si-27) + + Pointers : 124209 -1000000 + Primary type : Decay + Nuclide ZAI : 140270 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 26.98673 + Atomic weight ratio (AWR) : 26.75490 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.16 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 4.81236E+00 MeV frac = 1.00000E+00 Product nuclide = 13027.82c : EC/beta+ + + Nuclide 357 / 1657 : 140310 -- silicon 31 (Si-31) + + Pointers : 136406 -1000000 + Primary type : Decay + Nuclide ZAI : 140310 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 30.97540 + Atomic weight ratio (AWR) : 30.70930 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.43E+03 seconds (2.62 hours) + Specific ingestion toxicity : 1.60E-10 Sv/Bq + Specific inhalation toxicity : 7.90E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.49080E+00 MeV frac = 1.00000E+00 Product nuclide = 15031.82c : beta- + + Nuclide 358 / 1657 : 140320 -- silicon 32 (Si-32) + + Pointers : 136665 -1000000 + Primary type : Decay + Nuclide ZAI : 140320 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 31.97418 + Atomic weight ratio (AWR) : 31.69950 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.04E+10 seconds (330 years) + Specific ingestion toxicity : 5.60E-10 Sv/Bq + Specific inhalation toxicity : 1.10E-07 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.13000E-01 MeV frac = 1.00000E+00 Product nuclide = 150320 : beta- + + Nuclide 359 / 1657 : 140330 -- silicon 33 (Si-33) + + Pointers : 136882 -1000000 + Primary type : Decay + Nuclide ZAI : 140330 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 32.97800 + Atomic weight ratio (AWR) : 32.69470 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.18 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.84450E+00 MeV frac = 1.00000E+00 Product nuclide = 150330 : beta- + + Nuclide 360 / 1657 : 150300 -- phosphorus 30 (P-30) + + Pointers : 137066 -1000000 + Primary type : Decay + Nuclide ZAI : 150300 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 29.97833 + Atomic weight ratio (AWR) : 29.72080 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.50E+02 seconds (2.5 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 4.23240E+00 MeV frac = 1.00000E+00 Product nuclide = 14030.82c : EC/beta+ + + Nuclide 361 / 1657 : 150320 -- phosphorus 32 (P-32) + + Pointers : 139126 -1000000 + Primary type : Decay + Nuclide ZAI : 150320 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 31.97387 + Atomic weight ratio (AWR) : 31.69920 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.23E+06 seconds (14.3 days) + Specific ingestion toxicity : 2.40E-09 Sv/Bq + Specific inhalation toxicity : 3.40E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.71040E+00 MeV frac = 1.00000E+00 Product nuclide = 160320 : beta- + + Nuclide 362 / 1657 : 150330 -- phosphorus 33 (P-33) + + Pointers : 139343 -1000000 + Primary type : Decay + Nuclide ZAI : 150330 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 32.97174 + Atomic weight ratio (AWR) : 32.68850 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.19E+06 seconds (25.4 days) + Specific ingestion toxicity : 2.40E-10 Sv/Bq + Specific inhalation toxicity : 1.50E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.48500E-01 MeV frac = 1.00000E+00 Product nuclide = 160330 : beta- + + Nuclide 363 / 1657 : 150340 -- phosphorus 34 (P-34) + + Pointers : 139560 -1000000 + Primary type : Decay + Nuclide ZAI : 150340 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 33.97365 + Atomic weight ratio (AWR) : 33.68180 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 12.4 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.37430E+00 MeV frac = 1.00000E+00 Product nuclide = 16034.82c : beta- + + Nuclide 364 / 1657 : 150350 -- phosphorus 35 (P-35) + + Pointers : 139931 -1000000 + Primary type : Decay + Nuclide ZAI : 150350 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 34.97334 + Atomic weight ratio (AWR) : 34.67290 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 47.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.98866E+00 MeV frac = 1.00000E+00 Product nuclide = 160350 : beta- + + Nuclide 365 / 1657 : 150360 -- phosphorus 36 (P-36) + + Pointers : 140115 -1000000 + Primary type : Decay + Nuclide ZAI : 150360 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 35.97827 + Atomic weight ratio (AWR) : 35.66920 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.6 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.04131E+01 MeV frac = 1.00000E+00 Product nuclide = 16036.82c : beta- + + Nuclide 366 / 1657 : 160320 -- sulfur 32 (S-32) + + Pointers : 140299 -1000000 + Primary type : Decay + Nuclide ZAI : 160320 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 31.97206 + Atomic weight ratio (AWR) : 31.69740 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 367 / 1657 : 160330 -- sulfur 33 (S-33) + + Pointers : 140405 -1000000 + Primary type : Decay + Nuclide ZAI : 160330 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 32.97144 + Atomic weight ratio (AWR) : 32.68820 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 368 / 1657 : 160350 -- sulfur 35 (S-35) + + Pointers : 142155 -1000000 + Primary type : Decay + Nuclide ZAI : 160350 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 34.96900 + Atomic weight ratio (AWR) : 34.66860 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.54E+06 seconds (87.2 days) + Specific ingestion toxicity : 7.70E-10 Sv/Bq + Specific inhalation toxicity : 1.90E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.67330E-01 MeV frac = 1.00000E+00 Product nuclide = 17035.82c : beta- + + Nuclide 369 / 1657 : 160370 -- sulfur 37 (S-37) + + Pointers : 144016 -1000000 + Primary type : Decay + Nuclide ZAI : 160370 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 36.97110 + Atomic weight ratio (AWR) : 36.65350 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.99E+02 seconds (4.99 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.85400E+00 MeV frac = 1.00000E+00 Product nuclide = 17037.82c : beta- + + Nuclide 370 / 1657 : 160380 -- sulfur 38 (S-38) + + Pointers : 144345 -1000000 + Primary type : Decay + Nuclide ZAI : 160380 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 37.97119 + Atomic weight ratio (AWR) : 37.64500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.02E+04 seconds (2.84 hours) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.93700E+00 MeV frac = 1.00000E+00 Product nuclide = 170380 : beta- + + Nuclide 371 / 1657 : 170340 -- chlorine 34 (Cl-34) + + Pointers : 144730 -1000000 + Primary type : Decay + Nuclide ZAI : 170340 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 33.97375 + Atomic weight ratio (AWR) : 33.68190 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.53 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 5.49230E+00 MeV frac = 1.00000E+00 Product nuclide = 16034.82c : EC/beta+ + + Nuclide 372 / 1657 : 170360 -- chlorine 36 (Cl-36) + + Pointers : 157990 -1000000 + Primary type : Decay + Nuclide ZAI : 170360 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 35.96829 + Atomic weight ratio (AWR) : 35.65930 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.53E+12 seconds (302,200 years) + Specific ingestion toxicity : 9.30E-10 Sv/Bq + Specific inhalation toxicity : 7.30E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 1.14214E+00 MeV frac = 1.90000E-02 Product nuclide = 16036.82c : EC/beta+ + 2 RTYP = 1 Q = 7.09550E-01 MeV frac = 9.81000E-01 Product nuclide = 180360 : beta- + + Nuclide 373 / 1657 : 170380 -- chlorine 38 (Cl-38) + + Pointers : 165109 -1000000 + Primary type : Decay + Nuclide ZAI : 170380 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 37.96796 + Atomic weight ratio (AWR) : 37.64180 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.23E+03 seconds (37.2 minutes) + Specific ingestion toxicity : 1.20E-10 Sv/Bq + Specific inhalation toxicity : 4.50E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.91700E+00 MeV frac = 1.00000E+00 Product nuclide = 18038.82c : beta- + + Nuclide 374 / 1657 : 170381 -- chlorine 38m (Cl-38m) + + Pointers : 165410 -1000000 + Primary type : Decay + Nuclide ZAI : 170381 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 37.96796 + Atomic weight ratio (AWR) : 37.64180 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.715 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 6.71300E-01 MeV frac = 1.00000E+00 Product nuclide = 170380 : IT + + Nuclide 375 / 1657 : 170390 -- chlorine 39 (Cl-39) + + Pointers : 165753 -1000000 + Primary type : Decay + Nuclide ZAI : 170390 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 38.96806 + Atomic weight ratio (AWR) : 38.63330 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.34E+03 seconds (55.6 minutes) + Specific ingestion toxicity : 8.50E-11 Sv/Bq + Specific inhalation toxicity : 4.60E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.44200E+00 MeV frac = 1.00000E+00 Product nuclide = 180390 : beta- + + Nuclide 376 / 1657 : 170400 -- chlorine 40 (Cl-40) + + Pointers : 166544 -1000000 + Primary type : Decay + Nuclide ZAI : 170400 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 39.97037 + Atomic weight ratio (AWR) : 39.62700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.10E+01 seconds (1.35 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.48000E+00 MeV frac = 1.00000E+00 Product nuclide = 18040.82c : beta- + + Nuclide 377 / 1657 : 180360 -- argon 36 (Ar-36) + + Pointers : 168273 -1000000 + Primary type : Decay + Nuclide ZAI : 180360 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 35.96758 + Atomic weight ratio (AWR) : 35.65860 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 378 / 1657 : 180370 -- argon 37 (Ar-37) + + Pointers : 168379 -1000000 + Primary type : Decay + Nuclide ZAI : 180370 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 36.96676 + Atomic weight ratio (AWR) : 36.64920 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.02E+06 seconds (35 days) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 8.13870E-01 MeV frac = 1.00000E+00 Product nuclide = 17037.82c : EC/beta+ + + Nuclide 379 / 1657 : 180390 -- argon 39 (Ar-39) + + Pointers : 171655 -1000000 + Primary type : Decay + Nuclide ZAI : 180390 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 38.96432 + Atomic weight ratio (AWR) : 38.62960 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.49E+09 seconds (269 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.65000E-01 MeV frac = 1.00000E+00 Product nuclide = 19039.82c : beta- + + Nuclide 380 / 1657 : 180410 -- argon 41 (Ar-41) + + Pointers : 175706 -1000000 + Primary type : Decay + Nuclide ZAI : 180410 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 40.96451 + Atomic weight ratio (AWR) : 40.61260 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.58E+03 seconds (1.83 hours) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.49160E+00 MeV frac = 1.00000E+00 Product nuclide = 19041.82c : beta- + + Nuclide 381 / 1657 : 180420 -- argon 42 (Ar-42) + + Pointers : 176077 -1000000 + Primary type : Decay + Nuclide ZAI : 180420 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 41.96309 + Atomic weight ratio (AWR) : 41.60260 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.04E+09 seconds (33 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 190420 : beta- + + Nuclide 382 / 1657 : 180430 -- argon 43 (Ar-43) + + Pointers : 176294 -1000000 + Primary type : Decay + Nuclide ZAI : 180430 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 42.96560 + Atomic weight ratio (AWR) : 42.59650 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.22E+02 seconds (5.37 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.61600E+00 MeV frac = 1.00000E+00 Product nuclide = 190430 : beta- + + Nuclide 383 / 1657 : 190380 -- potassium 38 (K-38) + + Pointers : 177687 -1000000 + Primary type : Decay + Nuclide ZAI : 190380 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 37.96907 + Atomic weight ratio (AWR) : 37.64290 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.57E+02 seconds (7.61 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 5.91300E+00 MeV frac = 1.00000E+00 Product nuclide = 18038.82c : EC/beta+ + + Nuclide 384 / 1657 : 190420 -- potassium 42 (K-42) + + Pointers : 182975 -1000000 + Primary type : Decay + Nuclide ZAI : 190420 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 41.96238 + Atomic weight ratio (AWR) : 41.60190 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.45E+04 seconds (12.4 hours) + Specific ingestion toxicity : 4.30E-10 Sv/Bq + Specific inhalation toxicity : 1.20E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.52540E+00 MeV frac = 1.00000E+00 Product nuclide = 20042.82c : beta- + + Nuclide 385 / 1657 : 190430 -- potassium 43 (K-43) + + Pointers : 183472 -1000000 + Primary type : Decay + Nuclide ZAI : 190430 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 42.96076 + Atomic weight ratio (AWR) : 42.59170 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.99E+04 seconds (22.2 hours) + Specific ingestion toxicity : 2.50E-10 Sv/Bq + Specific inhalation toxicity : 1.40E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.81700E+00 MeV frac = 1.00000E+00 Product nuclide = 20043.82c : beta- + + Nuclide 386 / 1657 : 190440 -- potassium 44 (K-44) + + Pointers : 184109 -1000000 + Primary type : Decay + Nuclide ZAI : 190440 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 43.96155 + Atomic weight ratio (AWR) : 43.58390 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.33E+03 seconds (22.1 minutes) + Specific ingestion toxicity : 8.40E-11 Sv/Bq + Specific inhalation toxicity : 2.00E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.65900E+00 MeV frac = 1.00000E+00 Product nuclide = 20044.82c : beta- + + Nuclide 387 / 1657 : 190500 -- potassium 50 (K-50) + + Pointers : 187546 -1000000 + Primary type : Decay + Nuclide ZAI : 190500 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 49.97279 + Atomic weight ratio (AWR) : 49.54350 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.472 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.42210E+01 MeV frac = 7.10000E-01 Product nuclide = 200500 : beta- + 2 RTYP = 15 Q = 7.86770E+00 MeV frac = 2.90000E-01 Product nuclide = 200490 : beta- + neutron emission + + Nuclide 388 / 1657 : 190510 -- potassium 51 (K-51) + + Pointers : 187803 -1000000 + Primary type : Decay + Nuclide ZAI : 190510 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 50.97641 + Atomic weight ratio (AWR) : 50.53850 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.365 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.38600E+01 MeV frac = 5.30000E-01 Product nuclide = 200510 : beta- + 2 RTYP = 15 Q = 9.49970E+00 MeV frac = 4.70000E-01 Product nuclide = 200500 : beta- + neutron emission + + Nuclide 389 / 1657 : 200400 -- calcium 40 (Ca-40) + + Pointers : 188060 -1000000 + Primary type : Decay + Nuclide ZAI : 200400 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 39.96260 + Atomic weight ratio (AWR) : 39.61930 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 390 / 1657 : 200410 -- calcium 41 (Ca-41) + + Pointers : 188166 -1000000 + Primary type : Decay + Nuclide ZAI : 200410 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 40.96229 + Atomic weight ratio (AWR) : 40.61040 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.16E+12 seconds (100,266 years) + Specific ingestion toxicity : 1.90E-10 Sv/Bq + Specific inhalation toxicity : 1.80E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 4.21630E-01 MeV frac = 1.00000E+00 Product nuclide = 19041.82c : EC/beta+ + + Nuclide 391 / 1657 : 200450 -- calcium 45 (Ca-45) + + Pointers : 211009 -1000000 + Primary type : Decay + Nuclide ZAI : 200450 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 44.95620 + Atomic weight ratio (AWR) : 44.57000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.41E+07 seconds (163 days) + Specific ingestion toxicity : 7.10E-10 Sv/Bq + Specific inhalation toxicity : 3.70E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 2.58000E-01 MeV frac = 9.99980E-01 Product nuclide = 21045.82c : beta- + 2 RTYP = 1 Q = 2.45600E-01 MeV frac = 2.00000E-05 Product nuclide = 210451 : beta- + + Nuclide 392 / 1657 : 200460 -- calcium 46 (Ca-46) + + Pointers : 211313 -1000000 + Primary type : Decay + Nuclide ZAI : 200460 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 45.95367 + Atomic weight ratio (AWR) : 45.55890 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 393 / 1657 : 200470 -- calcium 47 (Ca-47) + + Pointers : 211419 -1000000 + Primary type : Decay + Nuclide ZAI : 200470 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 46.95456 + Atomic weight ratio (AWR) : 46.55120 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.92E+05 seconds (4.54 days) + Specific ingestion toxicity : 1.60E-09 Sv/Bq + Specific inhalation toxicity : 2.10E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.98800E+00 MeV frac = 1.00000E+00 Product nuclide = 210470 : beta- + + Nuclide 394 / 1657 : 200480 -- calcium 48 (Ca-48) + + Pointers : 211916 -1000000 + Primary type : Decay + Nuclide ZAI : 200480 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 47.95254 + Atomic weight ratio (AWR) : 47.54060 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.67E+27 seconds (5.3E+19 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 11 Q = 4.27370E+00 MeV frac = 5.00000E-01 Product nuclide = 22048.82c : beta- + beta- + 2 RTYP = 1 Q = 2.82002E-01 MeV frac = 5.00000E-01 Product nuclide = 210480 : beta- + + Nuclide 395 / 1657 : 200490 -- calcium 49 (Ca-49) + + Pointers : 212173 -1000000 + Primary type : Decay + Nuclide ZAI : 200490 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 48.95566 + Atomic weight ratio (AWR) : 48.53510 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.23E+02 seconds (8.72 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.26800E+00 MeV frac = 1.00000E+00 Product nuclide = 210490 : beta- + + Nuclide 396 / 1657 : 200500 -- calcium 50 (Ca-50) + + Pointers : 212628 -1000000 + Primary type : Decay + Nuclide ZAI : 200500 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 49.95756 + Atomic weight ratio (AWR) : 49.52840 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 13.9 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.70911E+00 MeV frac = 1.00000E+00 Product nuclide = 210501 : beta- + + Nuclide 397 / 1657 : 200510 -- calcium 51 (Ca-51) + + Pointers : 212812 -1000000 + Primary type : Decay + Nuclide ZAI : 200510 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 50.96149 + Atomic weight ratio (AWR) : 50.52370 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 10 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.35800E+00 MeV frac = 1.00000E+00 Product nuclide = 210510 : beta- + + Nuclide 398 / 1657 : 200520 -- calcium 52 (Ca-52) + + Pointers : 212996 -1000000 + Primary type : Decay + Nuclide ZAI : 200520 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 51.96511 + Atomic weight ratio (AWR) : 51.51870 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.6 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 7.85000E+00 MeV frac = 9.80000E-01 Product nuclide = 210520 : beta- + 2 RTYP = 15 Q = 2.63670E+00 MeV frac = 2.00000E-02 Product nuclide = 210510 : beta- + neutron emission + + Nuclide 399 / 1657 : 200530 -- calcium 53 (Ca-53) + + Pointers : 213253 -1000000 + Primary type : Decay + Nuclide ZAI : 200530 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 52.97004 + Atomic weight ratio (AWR) : 52.51500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 90 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 9.72000E+00 MeV frac = 7.00000E-01 Product nuclide = 210530 : beta- + 2 RTYP = 15 Q = 4.38870E+00 MeV frac = 3.00000E-01 Product nuclide = 210520 : beta- + neutron emission + + Nuclide 400 / 1657 : 200540 -- calcium 54 (Ca-54) + + Pointers : 213510 -1000000 + Primary type : Decay + Nuclide ZAI : 200540 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 53.97437 + Atomic weight ratio (AWR) : 53.51070 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 50 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.03300E+01 MeV frac = 1.00000E+00 Product nuclide = 210540 : beta- + + Nuclide 401 / 1657 : 210440 -- scandium 44 (Sc-44) + + Pointers : 213694 -1000000 + Primary type : Decay + Nuclide ZAI : 210440 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 43.95943 + Atomic weight ratio (AWR) : 43.58180 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.43E+04 seconds (3.97 hours) + Specific ingestion toxicity : 3.50E-10 Sv/Bq + Specific inhalation toxicity : 1.80E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 3.65330E+00 MeV frac = 1.00000E+00 Product nuclide = 20044.82c : EC/beta+ + + Nuclide 402 / 1657 : 210451 -- scandium 45m (Sc-45m) + + Pointers : 222177 -1000000 + Primary type : Decay + Nuclide ZAI : 210451 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 44.95589 + Atomic weight ratio (AWR) : 44.56970 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.325 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.24000E-02 MeV frac = 1.00000E+00 Product nuclide = 21045.82c : IT + + Nuclide 403 / 1657 : 210460 -- scandium 46 (Sc-46) + + Pointers : 222534 -1000000 + Primary type : Decay + Nuclide ZAI : 210460 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 45.95518 + Atomic weight ratio (AWR) : 45.56040 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.24E+06 seconds (83.8 days) + Specific ingestion toxicity : 1.50E-09 Sv/Bq + Specific inhalation toxicity : 6.80E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.36650E+00 MeV frac = 1.00000E+00 Product nuclide = 22046.82c : beta- + + Nuclide 404 / 1657 : 210461 -- scandium 46m (Sc-46m) + + Pointers : 223073 -1000000 + Primary type : Decay + Nuclide ZAI : 210461 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 45.95518 + Atomic weight ratio (AWR) : 45.56040 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 18.7 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.42530E-01 MeV frac = 1.00000E+00 Product nuclide = 210460 : IT + + Nuclide 405 / 1657 : 210470 -- scandium 47 (Sc-47) + + Pointers : 223430 -1000000 + Primary type : Decay + Nuclide ZAI : 210470 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 46.95245 + Atomic weight ratio (AWR) : 46.54910 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.89E+05 seconds (3.35 days) + Specific ingestion toxicity : 5.40E-10 Sv/Bq + Specific inhalation toxicity : 7.30E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.00800E-01 MeV frac = 1.00000E+00 Product nuclide = 22047.82c : beta- + + Nuclide 406 / 1657 : 210480 -- scandium 48 (Sc-48) + + Pointers : 223829 -1000000 + Primary type : Decay + Nuclide ZAI : 210480 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 47.95224 + Atomic weight ratio (AWR) : 47.54030 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.57E+05 seconds (1.82 days) + Specific ingestion toxicity : 1.70E-09 Sv/Bq + Specific inhalation toxicity : 1.10E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.99000E+00 MeV frac = 1.00000E+00 Product nuclide = 22048.82c : beta- + + Nuclide 407 / 1657 : 210490 -- scandium 49 (Sc-49) + + Pointers : 224144 -1000000 + Primary type : Decay + Nuclide ZAI : 210490 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 48.95001 + Atomic weight ratio (AWR) : 48.52950 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.43E+03 seconds (57.2 minutes) + Specific ingestion toxicity : 8.20E-11 Sv/Bq + Specific inhalation toxicity : 4.00E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.00400E+00 MeV frac = 1.00000E+00 Product nuclide = 22049.82c : beta- + + Nuclide 408 / 1657 : 210500 -- scandium 50 (Sc-50) + + Pointers : 224431 -1000000 + Primary type : Decay + Nuclide ZAI : 210500 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 49.95222 + Atomic weight ratio (AWR) : 49.52310 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.02E+02 seconds (1.71 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.88800E+00 MeV frac = 1.00000E+00 Product nuclide = 22050.82c : beta- + + Nuclide 409 / 1657 : 210501 -- scandium 50m (Sc-50m) + + Pointers : 224900 -1000000 + Primary type : Decay + Nuclide ZAI : 210501 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 49.95222 + Atomic weight ratio (AWR) : 49.52310 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.35 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 7.14500E+00 MeV frac = 1.25000E-02 Product nuclide = 22050.82c : beta- + 2 RTYP = 3 Q = 2.56895E-01 MeV frac = 9.87500E-01 Product nuclide = 210500 : IT + + Nuclide 410 / 1657 : 210510 -- scandium 51 (Sc-51) + + Pointers : 225358 -1000000 + Primary type : Decay + Nuclide ZAI : 210510 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 50.95362 + Atomic weight ratio (AWR) : 50.51590 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 12.4 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.51000E+00 MeV frac = 1.00000E+00 Product nuclide = 220510 : beta- + + Nuclide 411 / 1657 : 210520 -- scandium 52 (Sc-52) + + Pointers : 226149 -1000000 + Primary type : Decay + Nuclide ZAI : 210520 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 51.95664 + Atomic weight ratio (AWR) : 51.51030 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.11000E+00 MeV frac = 1.00000E+00 Product nuclide = 220520 : beta- + + Nuclide 412 / 1657 : 210530 -- scandium 53 (Sc-53) + + Pointers : 226814 -1000000 + Primary type : Decay + Nuclide ZAI : 210530 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 52.95965 + Atomic weight ratio (AWR) : 52.50470 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.21000E+00 MeV frac = 1.00000E+00 Product nuclide = 220530 : beta- + + Nuclide 413 / 1657 : 210540 -- scandium 54 (Sc-54) + + Pointers : 226998 -1000000 + Primary type : Decay + Nuclide ZAI : 210540 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 53.96327 + Atomic weight ratio (AWR) : 53.49970 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.26 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.13700E+01 MeV frac = 1.00000E+00 Product nuclide = 220540 : beta- + + Nuclide 414 / 1657 : 210550 -- scandium 55 (Sc-55) + + Pointers : 227182 -1000000 + Primary type : Decay + Nuclide ZAI : 210550 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 54.96821 + Atomic weight ratio (AWR) : 54.49600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.12 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.20900E+01 MeV frac = 1.00000E+00 Product nuclide = 220550 : beta- + + Nuclide 415 / 1657 : 210560 -- scandium 56 (Sc-56) + + Pointers : 227366 -1000000 + Primary type : Decay + Nuclide ZAI : 210560 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 55.97284 + Atomic weight ratio (AWR) : 55.49200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 80 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.36700E+01 MeV frac = 1.00000E+00 Product nuclide = 220560 : beta- + + Nuclide 416 / 1657 : 210570 -- scandium 57 (Sc-57) + + Pointers : 227550 -1000000 + Primary type : Decay + Nuclide ZAI : 210570 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 56.97777 + Atomic weight ratio (AWR) : 56.48830 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 13 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.28500E+01 MeV frac = 6.70000E-01 Product nuclide = 220570 : beta- + 2 RTYP = 15 Q = 1.01787E+01 MeV frac = 3.30000E-01 Product nuclide = 220560 : beta- + neutron emission + + Nuclide 417 / 1657 : 220450 -- titanium 45 (Ti-45) + + Pointers : 227807 -1000000 + Primary type : Decay + Nuclide ZAI : 220450 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 44.95811 + Atomic weight ratio (AWR) : 44.57190 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.11E+04 seconds (3.08 hours) + Specific ingestion toxicity : 1.50E-10 Sv/Bq + Specific inhalation toxicity : 9.30E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 2.06260E+00 MeV frac = 1.00000E+00 Product nuclide = 21045.82c : EC/beta+ + + Nuclide 418 / 1657 : 220510 -- titanium 51 (Ti-51) + + Pointers : 261852 -1000000 + Primary type : Decay + Nuclide ZAI : 220510 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 50.94666 + Atomic weight ratio (AWR) : 50.50900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.48E+02 seconds (5.8 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.47260E+00 MeV frac = 1.00000E+00 Product nuclide = 230510 : beta- + + Nuclide 419 / 1657 : 220520 -- titanium 52 (Ti-52) + + Pointers : 262265 -1000000 + Primary type : Decay + Nuclide ZAI : 220520 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 51.94685 + Atomic weight ratio (AWR) : 51.50060 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.02E+02 seconds (1.7 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.97600E+00 MeV frac = 1.00000E+00 Product nuclide = 230520 : beta- + + Nuclide 420 / 1657 : 220530 -- titanium 53 (Ti-53) + + Pointers : 262524 -1000000 + Primary type : Decay + Nuclide ZAI : 220530 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 52.94977 + Atomic weight ratio (AWR) : 52.49490 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 32.7 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.01900E+00 MeV frac = 1.00000E+00 Product nuclide = 230530 : beta- + + Nuclide 421 / 1657 : 220540 -- titanium 54 (Ti-54) + + Pointers : 262708 -1000000 + Primary type : Decay + Nuclide ZAI : 220540 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 53.95107 + Atomic weight ratio (AWR) : 53.48760 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.30100E+00 MeV frac = 1.00000E+00 Product nuclide = 230540 : beta- + + Nuclide 422 / 1657 : 220550 -- titanium 55 (Ti-55) + + Pointers : 262892 -1000000 + Primary type : Decay + Nuclide ZAI : 220550 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 54.95530 + Atomic weight ratio (AWR) : 54.48320 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.49 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.48000E+00 MeV frac = 1.00000E+00 Product nuclide = 230550 : beta- + + Nuclide 423 / 1657 : 220560 -- titanium 56 (Ti-56) + + Pointers : 263076 -1000000 + Primary type : Decay + Nuclide ZAI : 220560 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 55.95821 + Atomic weight ratio (AWR) : 55.47750 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.164 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.14000E+00 MeV frac = 1.00000E+00 Product nuclide = 230560 : beta- + + Nuclide 424 / 1657 : 220570 -- titanium 57 (Ti-57) + + Pointers : 263260 -1000000 + Primary type : Decay + Nuclide ZAI : 220570 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 56.96395 + Atomic weight ratio (AWR) : 56.47460 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 60 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.06500E+01 MeV frac = 9.97000E-01 Product nuclide = 230570 : beta- + 2 RTYP = 15 Q = 4.46870E+00 MeV frac = 3.00000E-03 Product nuclide = 230560 : beta- + neutron emission + + Nuclide 425 / 1657 : 220580 -- titanium 58 (Ti-58) + + Pointers : 263517 -1000000 + Primary type : Decay + Nuclide ZAI : 220580 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 57.96697 + Atomic weight ratio (AWR) : 57.46900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 54 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.44000E+00 MeV frac = 1.00000E+00 Product nuclide = 230580 : beta- + + Nuclide 426 / 1657 : 220590 -- titanium 59 (Ti-59) + + Pointers : 263701 -1000000 + Primary type : Decay + Nuclide ZAI : 220590 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 58.97291 + Atomic weight ratio (AWR) : 58.46630 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 30 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.18500E+01 MeV frac = 1.00000E+00 Product nuclide = 230590 : beta- + + Nuclide 427 / 1657 : 220600 -- titanium 60 (Ti-60) + + Pointers : 263885 -1000000 + Primary type : Decay + Nuclide ZAI : 220600 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 59.97673 + Atomic weight ratio (AWR) : 59.46150 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 22 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.09300E+01 MeV frac = 1.00000E+00 Product nuclide = 230600 : beta- + + Nuclide 428 / 1657 : 220610 -- titanium 61 (Ti-61) + + Pointers : 264069 -1000000 + Primary type : Decay + Nuclide ZAI : 220610 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 60.98318 + Atomic weight ratio (AWR) : 60.45930 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 10 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.37100E+01 MeV frac = 1.00000E+00 Product nuclide = 230610 : beta- + + Nuclide 429 / 1657 : 230490 -- vanadium 49 (V-49) + + Pointers : 264253 -1000000 + Primary type : Decay + Nuclide ZAI : 230490 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 48.94849 + Atomic weight ratio (AWR) : 48.52800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.85E+07 seconds (330 days) + Specific ingestion toxicity : 1.80E-11 Sv/Bq + Specific inhalation toxicity : 3.40E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 6.02000E-01 MeV frac = 1.00000E+00 Product nuclide = 22049.82c : EC/beta+ + + Nuclide 430 / 1657 : 230500 -- vanadium 50 (V-50) + + Pointers : 264554 -1000000 + Primary type : Decay + Nuclide ZAI : 230500 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 49.94717 + Atomic weight ratio (AWR) : 49.51810 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.42E+24 seconds (1.4E+17 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.03790E+00 MeV frac = 1.70000E-01 Product nuclide = 24050.82c : beta- + 2 RTYP = 2 Q = 2.20510E+00 MeV frac = 8.30000E-01 Product nuclide = 22050.82c : EC/beta+ + + Nuclide 431 / 1657 : 230510 -- vanadium 51 (V-51) + + Pointers : 264970 -1000000 + Primary type : Decay + Nuclide ZAI : 230510 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 50.94394 + Atomic weight ratio (AWR) : 50.50630 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 432 / 1657 : 230520 -- vanadium 52 (V-52) + + Pointers : 265076 -1000000 + Primary type : Decay + Nuclide ZAI : 230520 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 51.94473 + Atomic weight ratio (AWR) : 51.49850 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.25E+02 seconds (3.74 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.97570E+00 MeV frac = 1.00000E+00 Product nuclide = 24052.82c : beta- + + Nuclide 433 / 1657 : 230530 -- vanadium 53 (V-53) + + Pointers : 265853 -1000000 + Primary type : Decay + Nuclide ZAI : 230530 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 52.94432 + Atomic weight ratio (AWR) : 52.48950 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.72E+01 seconds (1.62 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.43600E+00 MeV frac = 1.00000E+00 Product nuclide = 24053.82c : beta- + + Nuclide 434 / 1657 : 230540 -- vanadium 54 (V-54) + + Pointers : 266210 -1000000 + Primary type : Decay + Nuclide ZAI : 230540 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 53.94643 + Atomic weight ratio (AWR) : 53.48300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 49.8 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.04200E+00 MeV frac = 1.00000E+00 Product nuclide = 24054.82c : beta- + + Nuclide 435 / 1657 : 230550 -- vanadium 55 (V-55) + + Pointers : 266875 -1000000 + Primary type : Decay + Nuclide ZAI : 230550 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 54.94723 + Atomic weight ratio (AWR) : 54.47520 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.54 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.98000E+00 MeV frac = 1.00000E+00 Product nuclide = 240550 : beta- + + Nuclide 436 / 1657 : 230560 -- vanadium 56 (V-56) + + Pointers : 267344 -1000000 + Primary type : Decay + Nuclide ZAI : 230560 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 55.95054 + Atomic weight ratio (AWR) : 55.46990 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.216 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.20120E+00 MeV frac = 1.00000E+00 Product nuclide = 240560 : beta- + + Nuclide 437 / 1657 : 230570 -- vanadium 57 (V-57) + + Pointers : 267528 -1000000 + Primary type : Decay + Nuclide ZAI : 230570 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 56.95255 + Atomic weight ratio (AWR) : 56.46330 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.35 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.33410E+00 MeV frac = 9.96000E-01 Product nuclide = 240570 : beta- + 2 RTYP = 15 Q = 3.01990E+00 MeV frac = 4.00000E-03 Product nuclide = 240560 : beta- + neutron emission + + Nuclide 438 / 1657 : 230580 -- vanadium 58 (V-58) + + Pointers : 267785 -1000000 + Primary type : Decay + Nuclide ZAI : 230580 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 57.95688 + Atomic weight ratio (AWR) : 57.45900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.191 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.16200E+01 MeV frac = 2.00000E-01 Product nuclide = 240580 : beta- + 2 RTYP = 15 Q = 4.24280E+00 MeV frac = 8.00000E-01 Product nuclide = 240570 : beta- + neutron emission + + Nuclide 439 / 1657 : 230590 -- vanadium 59 (V-59) + + Pointers : 268042 -1000000 + Primary type : Decay + Nuclide ZAI : 230590 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 58.96020 + Atomic weight ratio (AWR) : 58.45370 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 75 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.08200E+01 MeV frac = 1.00000E+00 Product nuclide = 240590 : beta- + + Nuclide 440 / 1657 : 230600 -- vanadium 60 (V-60) + + Pointers : 268226 -1000000 + Primary type : Decay + Nuclide ZAI : 230600 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 59.96503 + Atomic weight ratio (AWR) : 59.44990 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.122 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.39200E+01 MeV frac = 1.00000E+00 Product nuclide = 240600 : beta- + + Nuclide 441 / 1657 : 230610 -- vanadium 61 (V-61) + + Pointers : 268410 -1000000 + Primary type : Decay + Nuclide ZAI : 230610 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 60.96845 + Atomic weight ratio (AWR) : 60.44470 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 47 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.28200E+01 MeV frac = 9.40000E-01 Product nuclide = 240610 : beta- + 2 RTYP = 15 Q = 9.06870E+00 MeV frac = 6.00000E-02 Product nuclide = 240600 : beta- + neutron emission + + Nuclide 442 / 1657 : 230620 -- vanadium 62 (V-62) + + Pointers : 268667 -1000000 + Primary type : Decay + Nuclide ZAI : 230620 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 61.97379 + Atomic weight ratio (AWR) : 61.44140 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 33.5 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.59900E+01 MeV frac = 1.00000E+00 Product nuclide = 240620 : beta- + + Nuclide 443 / 1657 : 230630 -- vanadium 63 (V-63) + + Pointers : 268851 -1000000 + Primary type : Decay + Nuclide ZAI : 230630 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 62.97751 + Atomic weight ratio (AWR) : 62.43650 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 17 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.46200E+01 MeV frac = 6.50000E-01 Product nuclide = 240630 : beta- + 2 RTYP = 15 Q = 1.14287E+01 MeV frac = 3.50000E-01 Product nuclide = 240620 : beta- + neutron emission + + Nuclide 444 / 1657 : 230640 -- vanadium 64 (V-64) + + Pointers : 269108 -1000000 + Primary type : Decay + Nuclide ZAI : 230640 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 63.98345 + Atomic weight ratio (AWR) : 63.43380 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 10 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.77500E+01 MeV frac = 1.00000E+00 Product nuclide = 240640 : beta- + + Nuclide 445 / 1657 : 230650 -- vanadium 65 (V-65) + + Pointers : 269292 -1000000 + Primary type : Decay + Nuclide ZAI : 230650 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 64.98788 + Atomic weight ratio (AWR) : 64.42960 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 10 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.65500E+01 MeV frac = 1.00000E+00 Product nuclide = 240650 : beta- + + Nuclide 446 / 1657 : 240490 -- chromium 49 (Cr-49) + + Pointers : 269476 -1000000 + Primary type : Decay + Nuclide ZAI : 240490 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 48.95132 + Atomic weight ratio (AWR) : 48.53080 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.51E+03 seconds (41.9 minutes) + Specific ingestion toxicity : 6.10E-11 Sv/Bq + Specific inhalation toxicity : 3.50E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 2.62800E+00 MeV frac = 1.00000E+00 Product nuclide = 230490 : EC/beta+ + + Nuclide 447 / 1657 : 240510 -- chromium 51 (Cr-51) + + Pointers : 272094 -1000000 + Primary type : Decay + Nuclide ZAI : 240510 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 50.94474 + Atomic weight ratio (AWR) : 50.50710 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.39E+06 seconds (27.7 days) + Specific ingestion toxicity : 3.80E-11 Sv/Bq + Specific inhalation toxicity : 3.70E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 7.52620E-01 MeV frac = 1.00000E+00 Product nuclide = 230510 : EC/beta+ + + Nuclide 448 / 1657 : 240550 -- chromium 55 (Cr-55) + + Pointers : 278638 -1000000 + Primary type : Decay + Nuclide ZAI : 240550 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 54.94087 + Atomic weight ratio (AWR) : 54.46890 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.12E+02 seconds (3.54 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.60320E+00 MeV frac = 1.00000E+00 Product nuclide = 25055.82c : beta- + + Nuclide 449 / 1657 : 240560 -- chromium 56 (Cr-56) + + Pointers : 279149 -1000000 + Primary type : Decay + Nuclide ZAI : 240560 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 55.94066 + Atomic weight ratio (AWR) : 55.46010 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.56E+02 seconds (5.94 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.62850E+00 MeV frac = 1.00000E+00 Product nuclide = 250560 : beta- + + Nuclide 450 / 1657 : 240570 -- chromium 57 (Cr-57) + + Pointers : 279548 -1000000 + Primary type : Decay + Nuclide ZAI : 240570 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 56.94358 + Atomic weight ratio (AWR) : 56.45440 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 21.1 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.09000E+00 MeV frac = 1.00000E+00 Product nuclide = 250570 : beta- + + Nuclide 451 / 1657 : 240580 -- chromium 58 (Cr-58) + + Pointers : 280409 -1000000 + Primary type : Decay + Nuclide ZAI : 240580 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 57.94437 + Atomic weight ratio (AWR) : 57.44660 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.08000E+00 MeV frac = 1.00000E+00 Product nuclide = 250580 : beta- + + Nuclide 452 / 1657 : 240590 -- chromium 59 (Cr-59) + + Pointers : 280593 -1000000 + Primary type : Decay + Nuclide ZAI : 240590 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 58.94860 + Atomic weight ratio (AWR) : 58.44220 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.46 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.59000E+00 MeV frac = 1.00000E+00 Product nuclide = 250590 : beta- + + Nuclide 453 / 1657 : 240600 -- chromium 60 (Cr-60) + + Pointers : 280777 -1000000 + Primary type : Decay + Nuclide ZAI : 240600 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 59.95010 + Atomic weight ratio (AWR) : 59.43510 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.56 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.68000E+00 MeV frac = 1.00000E+00 Product nuclide = 250600 : beta- + + Nuclide 454 / 1657 : 240610 -- chromium 61 (Cr-61) + + Pointers : 280961 -1000000 + Primary type : Decay + Nuclide ZAI : 240610 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 60.95473 + Atomic weight ratio (AWR) : 60.43110 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.261 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.38000E+00 MeV frac = 1.00000E+00 Product nuclide = 250610 : beta- + + Nuclide 455 / 1657 : 240620 -- chromium 62 (Cr-62) + + Pointers : 281145 -1000000 + Primary type : Decay + Nuclide ZAI : 240620 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 61.95664 + Atomic weight ratio (AWR) : 61.42440 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.199 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 7.63000E+00 MeV frac = 5.00000E-01 Product nuclide = 250620 : beta- + 2 RTYP = 1 Q = 7.62900E+00 MeV frac = 5.00000E-01 Product nuclide = 250621 : beta- + + Nuclide 456 / 1657 : 240630 -- chromium 63 (Cr-63) + + Pointers : 281402 -1000000 + Primary type : Decay + Nuclide ZAI : 240630 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 62.96188 + Atomic weight ratio (AWR) : 62.42100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.129 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.08200E+01 MeV frac = 1.00000E+00 Product nuclide = 250630 : beta- + + Nuclide 457 / 1657 : 240640 -- chromium 64 (Cr-64) + + Pointers : 281586 -1000000 + Primary type : Decay + Nuclide ZAI : 240640 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 63.96439 + Atomic weight ratio (AWR) : 63.41490 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 43 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.47000E+00 MeV frac = 1.00000E+00 Product nuclide = 250640 : beta- + + Nuclide 458 / 1657 : 240650 -- chromium 65 (Cr-65) + + Pointers : 281770 -1000000 + Primary type : Decay + Nuclide ZAI : 240650 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 64.97013 + Atomic weight ratio (AWR) : 64.41200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 27 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.28700E+01 MeV frac = 1.00000E+00 Product nuclide = 250650 : beta- + + Nuclide 459 / 1657 : 240660 -- chromium 66 (Cr-66) + + Pointers : 281954 -1000000 + Primary type : Decay + Nuclide ZAI : 240660 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 65.97335 + Atomic weight ratio (AWR) : 65.40660 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 10 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.14500E+01 MeV frac = 1.00000E+00 Product nuclide = 250660 : beta- + + Nuclide 460 / 1657 : 240670 -- chromium 67 (Cr-67) + + Pointers : 282138 -1000000 + Primary type : Decay + Nuclide ZAI : 240670 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 66.97959 + Atomic weight ratio (AWR) : 66.40420 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 10 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.43500E+01 MeV frac = 1.00000E+00 Product nuclide = 250670 : beta- + + Nuclide 461 / 1657 : 250520 -- manganese 52 (Mn-52) + + Pointers : 282322 -1000000 + Primary type : Decay + Nuclide ZAI : 250520 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 51.94554 + Atomic weight ratio (AWR) : 51.49930 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.83E+05 seconds (5.59 days) + Specific ingestion toxicity : 1.80E-09 Sv/Bq + Specific inhalation toxicity : 1.40E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 4.71170E+00 MeV frac = 1.00000E+00 Product nuclide = 24052.82c : EC/beta+ + + Nuclide 462 / 1657 : 250530 -- manganese 53 (Mn-53) + + Pointers : 282945 -1000000 + Primary type : Decay + Nuclide ZAI : 250530 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 52.94129 + Atomic weight ratio (AWR) : 52.48650 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.16E+14 seconds (3.68 million years) + Specific ingestion toxicity : 3.00E-11 Sv/Bq + Specific inhalation toxicity : 5.40E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 5.96100E-01 MeV frac = 1.00000E+00 Product nuclide = 24053.82c : EC/beta+ + + Nuclide 463 / 1657 : 250540 -- manganese 54 (Mn-54) + + Pointers : 283246 -1000000 + Primary type : Decay + Nuclide ZAI : 250540 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 53.94038 + Atomic weight ratio (AWR) : 53.47700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.70E+07 seconds (312 days) + Specific ingestion toxicity : 7.10E-10 Sv/Bq + Specific inhalation toxicity : 1.50E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 1.37720E+00 MeV frac = 1.00000E+00 Product nuclide = 24054.82c : EC/beta+ + + Nuclide 464 / 1657 : 250560 -- manganese 56 (Mn-56) + + Pointers : 286735 -1000000 + Primary type : Decay + Nuclide ZAI : 250560 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 55.93895 + Atomic weight ratio (AWR) : 55.45840 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.28E+03 seconds (2.58 hours) + Specific ingestion toxicity : 2.50E-10 Sv/Bq + Specific inhalation toxicity : 1.20E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.69550E+00 MeV frac = 1.00000E+00 Product nuclide = 26056.82c : beta- + + Nuclide 465 / 1657 : 250570 -- manganese 57 (Mn-57) + + Pointers : 287442 -1000000 + Primary type : Decay + Nuclide ZAI : 250570 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 56.93833 + Atomic weight ratio (AWR) : 56.44920 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.54E+01 seconds (1.42 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.69100E+00 MeV frac = 1.00000E+00 Product nuclide = 26057.82c : beta- + + Nuclide 466 / 1657 : 250580 -- manganese 58 (Mn-58) + + Pointers : 288275 -1000000 + Primary type : Decay + Nuclide ZAI : 250580 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 57.94004 + Atomic weight ratio (AWR) : 57.44230 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.52E+01 seconds (1.09 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.24700E+00 MeV frac = 1.00000E+00 Product nuclide = 26058.82c : beta- + + Nuclide 467 / 1657 : 250581 -- manganese 58m (Mn-58m) + + Pointers : 289654 -1000000 + Primary type : Decay + Nuclide ZAI : 250581 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 57.94004 + Atomic weight ratio (AWR) : 57.44230 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.7 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.32000E+00 MeV frac = 1.00000E+00 Product nuclide = 26058.82c : beta- + + Nuclide 468 / 1657 : 250590 -- manganese 59 (Mn-59) + + Pointers : 290221 -1000000 + Primary type : Decay + Nuclide ZAI : 250590 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 58.94043 + Atomic weight ratio (AWR) : 58.43410 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.59 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.18500E+00 MeV frac = 1.00000E+00 Product nuclide = 260590 : beta- + + Nuclide 469 / 1657 : 250600 -- manganese 60 (Mn-60) + + Pointers : 291040 -1000000 + Primary type : Decay + Nuclide ZAI : 250600 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 59.94294 + Atomic weight ratio (AWR) : 59.42800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 51 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.24000E+00 MeV frac = 1.00000E+00 Product nuclide = 260600 : beta- + + Nuclide 470 / 1657 : 250601 -- manganese 60m (Mn-60m) + + Pointers : 291257 -1000000 + Primary type : Decay + Nuclide ZAI : 250601 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 59.94294 + Atomic weight ratio (AWR) : 59.42800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.77 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.50390E+00 MeV frac = 8.85000E-01 Product nuclide = 260600 : beta- + 2 RTYP = 3 Q = 2.71900E-01 MeV frac = 1.15000E-01 Product nuclide = 250600 : IT + + Nuclide 471 / 1657 : 250610 -- manganese 61 (Mn-61) + + Pointers : 291514 -1000000 + Primary type : Decay + Nuclide ZAI : 250610 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 60.94465 + Atomic weight ratio (AWR) : 60.42110 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.67 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.18000E+00 MeV frac = 1.00000E+00 Product nuclide = 260610 : beta- + + Nuclide 472 / 1657 : 250620 -- manganese 62 (Mn-62) + + Pointers : 291857 -1000000 + Primary type : Decay + Nuclide ZAI : 250620 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 61.94847 + Atomic weight ratio (AWR) : 61.41630 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.88 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.04000E+01 MeV frac = 1.00000E+00 Product nuclide = 260620 : beta- + + Nuclide 473 / 1657 : 250621 -- manganese 62m (Mn-62m) + + Pointers : 292214 -1000000 + Primary type : Decay + Nuclide ZAI : 250621 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 61.94847 + Atomic weight ratio (AWR) : 61.41630 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 92 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.08620E+01 MeV frac = 1.00000E+00 Product nuclide = 260620 : beta- + + Nuclide 474 / 1657 : 250630 -- manganese 63 (Mn-63) + + Pointers : 292398 -1000000 + Primary type : Decay + Nuclide ZAI : 250630 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 62.95028 + Atomic weight ratio (AWR) : 62.40950 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.275 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.20000E+00 MeV frac = 1.00000E+00 Product nuclide = 260630 : beta- + + Nuclide 475 / 1657 : 250640 -- manganese 64 (Mn-64) + + Pointers : 292582 -1000000 + Primary type : Decay + Nuclide ZAI : 250640 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 63.95420 + Atomic weight ratio (AWR) : 63.40480 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 88.8 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.21500E+01 MeV frac = 1.00000E+00 Product nuclide = 260640 : beta- + + Nuclide 476 / 1657 : 250650 -- manganese 65 (Mn-65) + + Pointers : 292766 -1000000 + Primary type : Decay + Nuclide ZAI : 250650 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 64.95631 + Atomic weight ratio (AWR) : 64.39830 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 92 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.02100E+01 MeV frac = 1.00000E+00 Product nuclide = 260650 : beta- + + Nuclide 477 / 1657 : 250660 -- manganese 66 (Mn-66) + + Pointers : 292950 -1000000 + Primary type : Decay + Nuclide ZAI : 250660 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 65.96104 + Atomic weight ratio (AWR) : 65.39440 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 64.4 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.33200E+01 MeV frac = 1.00000E+00 Product nuclide = 260660 : beta- + + Nuclide 478 / 1657 : 250670 -- manganese 67 (Mn-67) + + Pointers : 293134 -1000000 + Primary type : Decay + Nuclide ZAI : 250670 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 66.96416 + Atomic weight ratio (AWR) : 66.38890 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 45 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.22900E+01 MeV frac = 1.00000E+00 Product nuclide = 260670 : beta- + + Nuclide 479 / 1657 : 250680 -- manganese 68 (Mn-68) + + Pointers : 293318 -1000000 + Primary type : Decay + Nuclide ZAI : 250680 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 67.96929 + Atomic weight ratio (AWR) : 67.38540 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 28 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.45300E+01 MeV frac = 1.00000E+00 Product nuclide = 260680 : beta- + + Nuclide 480 / 1657 : 250690 -- manganese 69 (Mn-69) + + Pointers : 293502 -1000000 + Primary type : Decay + Nuclide ZAI : 250690 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 68.97281 + Atomic weight ratio (AWR) : 68.38030 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 14 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.31000E+01 MeV frac = 7.60000E-01 Product nuclide = 260690 : beta- + 2 RTYP = 15 Q = 9.75870E+00 MeV frac = 2.40000E-01 Product nuclide = 260680 : beta- + neutron emission + + Nuclide 481 / 1657 : 260530 -- iron 53 (Fe-53) + + Pointers : 293759 -1000000 + Primary type : Decay + Nuclide ZAI : 260530 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 52.94533 + Atomic weight ratio (AWR) : 52.49050 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.11E+02 seconds (8.51 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 3.74360E+00 MeV frac = 1.00000E+00 Product nuclide = 250530 : EC/beta+ + + Nuclide 482 / 1657 : 260550 -- iron 55 (Fe-55) + + Pointers : 301886 -1000000 + Primary type : Decay + Nuclide ZAI : 260550 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 54.93825 + Atomic weight ratio (AWR) : 54.46630 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.67E+07 seconds (2.75 years) + Specific ingestion toxicity : 3.30E-10 Sv/Bq + Specific inhalation toxicity : 3.80E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 2.31210E-01 MeV frac = 1.00000E+00 Product nuclide = 25055.82c : EC/beta+ + + Nuclide 483 / 1657 : 260590 -- iron 59 (Fe-59) + + Pointers : 322974 -1000000 + Primary type : Decay + Nuclide ZAI : 260590 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 58.93488 + Atomic weight ratio (AWR) : 58.42860 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.84E+06 seconds (44.5 days) + Specific ingestion toxicity : 1.80E-09 Sv/Bq + Specific inhalation toxicity : 4.00E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.56500E+00 MeV frac = 1.00000E+00 Product nuclide = 27059.82c : beta- + + Nuclide 484 / 1657 : 260600 -- iron 60 (Fe-60) + + Pointers : 323835 -1000000 + Primary type : Decay + Nuclide ZAI : 260600 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 59.93407 + Atomic weight ratio (AWR) : 59.41920 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.73E+13 seconds (1.5 million years) + Specific ingestion toxicity : 1.10E-07 Sv/Bq + Specific inhalation toxicity : 2.80E-07 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.40000E-01 MeV frac = 1.00000E+00 Product nuclide = 270601 : beta- + + Nuclide 485 / 1657 : 260610 -- iron 61 (Fe-61) + + Pointers : 324052 -1000000 + Primary type : Decay + Nuclide ZAI : 260610 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 60.93678 + Atomic weight ratio (AWR) : 60.41330 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.59E+02 seconds (5.98 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.97740E+00 MeV frac = 1.00000E+00 Product nuclide = 270610 : beta- + + Nuclide 486 / 1657 : 260620 -- iron 62 (Fe-62) + + Pointers : 324236 -1000000 + Primary type : Decay + Nuclide ZAI : 260620 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 61.93677 + Atomic weight ratio (AWR) : 61.40470 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.80E+01 seconds (1.13 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.55300E+00 MeV frac = 1.00000E+00 Product nuclide = 270620 : beta- + + Nuclide 487 / 1657 : 260630 -- iron 63 (Fe-63) + + Pointers : 324481 -1000000 + Primary type : Decay + Nuclide ZAI : 260630 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 62.94009 + Atomic weight ratio (AWR) : 62.39940 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.1 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.05700E+00 MeV frac = 1.00000E+00 Product nuclide = 270630 : beta- + + Nuclide 488 / 1657 : 260640 -- iron 64 (Fe-64) + + Pointers : 325496 -1000000 + Primary type : Decay + Nuclide ZAI : 260640 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 63.94119 + Atomic weight ratio (AWR) : 63.39190 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.02000E+00 MeV frac = 1.00000E+00 Product nuclide = 270640 : beta- + + Nuclide 489 / 1657 : 260650 -- iron 65 (Fe-65) + + Pointers : 325783 -1000000 + Primary type : Decay + Nuclide ZAI : 260650 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 64.94542 + Atomic weight ratio (AWR) : 64.38750 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.29000E+00 MeV frac = 1.00000E+00 Product nuclide = 270650 : beta- + + Nuclide 490 / 1657 : 260660 -- iron 66 (Fe-66) + + Pointers : 325967 -1000000 + Primary type : Decay + Nuclide ZAI : 260660 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 65.94682 + Atomic weight ratio (AWR) : 65.38030 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.44 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.54000E+00 MeV frac = 1.00000E+00 Product nuclide = 270660 : beta- + + Nuclide 491 / 1657 : 260670 -- iron 67 (Fe-67) + + Pointers : 326151 -1000000 + Primary type : Decay + Nuclide ZAI : 260670 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 66.95094 + Atomic weight ratio (AWR) : 66.37580 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.394 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.37000E+00 MeV frac = 1.00000E+00 Product nuclide = 270670 : beta- + + Nuclide 492 / 1657 : 260680 -- iron 68 (Fe-68) + + Pointers : 326335 -1000000 + Primary type : Decay + Nuclide ZAI : 260680 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 67.95366 + Atomic weight ratio (AWR) : 67.36990 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.187 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.07000E+00 MeV frac = 1.00000E+00 Product nuclide = 270681 : beta- + + Nuclide 493 / 1657 : 260690 -- iron 69 (Fe-69) + + Pointers : 326519 -1000000 + Primary type : Decay + Nuclide ZAI : 260690 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 68.95879 + Atomic weight ratio (AWR) : 68.36640 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.109 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.16000E+01 MeV frac = 9.30000E-01 Product nuclide = 270690 : beta- + 2 RTYP = 15 Q = 4.72870E+00 MeV frac = 7.00000E-02 Product nuclide = 270681 : beta- + neutron emission + + Nuclide 494 / 1657 : 260700 -- iron 70 (Fe-70) + + Pointers : 326776 -1000000 + Primary type : Decay + Nuclide ZAI : 260700 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 69.96151 + Atomic weight ratio (AWR) : 69.36050 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 94 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.54000E+00 MeV frac = 1.00000E+00 Product nuclide = 270701 : beta- + + Nuclide 495 / 1657 : 260710 -- iron 71 (Fe-71) + + Pointers : 326960 -1000000 + Primary type : Decay + Nuclide ZAI : 260710 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 70.96674 + Atomic weight ratio (AWR) : 70.35710 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 30 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.28700E+01 MeV frac = 1.00000E+00 Product nuclide = 270710 : beta- + + Nuclide 496 / 1657 : 260720 -- iron 72 (Fe-72) + + Pointers : 327144 -1000000 + Primary type : Decay + Nuclide ZAI : 260720 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 71.96966 + Atomic weight ratio (AWR) : 71.35140 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 10 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 270720 : beta- + + Nuclide 497 / 1657 : 270560 -- cobalt 56 (Co-56) + + Pointers : 327328 -1000000 + Primary type : Decay + Nuclide ZAI : 270560 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 55.93985 + Atomic weight ratio (AWR) : 55.45930 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.67E+06 seconds (77.2 days) + Specific ingestion toxicity : 2.50E-09 Sv/Bq + Specific inhalation toxicity : 6.70E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 4.56600E+00 MeV frac = 1.00000E+00 Product nuclide = 26056.82c : EC/beta+ + + Nuclide 498 / 1657 : 270570 -- cobalt 57 (Co-57) + + Pointers : 328287 -1000000 + Primary type : Decay + Nuclide ZAI : 270570 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 56.93631 + Atomic weight ratio (AWR) : 56.44720 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.35E+07 seconds (272 days) + Specific ingestion toxicity : 2.10E-10 Sv/Bq + Specific inhalation toxicity : 1.00E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 8.36000E-01 MeV frac = 1.00000E+00 Product nuclide = 26057.82c : EC/beta+ + + Nuclide 499 / 1657 : 270580 -- cobalt 58 (Co-58) + + Pointers : 329106 -1000000 + Primary type : Decay + Nuclide ZAI : 270580 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 57.93580 + Atomic weight ratio (AWR) : 57.43810 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.12E+06 seconds (70.8 days) + Specific ingestion toxicity : 7.40E-10 Sv/Bq + Specific inhalation toxicity : 2.10E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 2.30790E+00 MeV frac = 1.00000E+00 Product nuclide = 26058.82c : EC/beta+ + + Nuclide 500 / 1657 : 270600 -- cobalt 60 (Co-60) + + Pointers : 333765 -1000000 + Primary type : Decay + Nuclide ZAI : 270600 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 59.93386 + Atomic weight ratio (AWR) : 59.41900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.66E+08 seconds (5.27 years) + Specific ingestion toxicity : 3.40E-09 Sv/Bq + Specific inhalation toxicity : 3.10E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.82307E+00 MeV frac = 1.00000E+00 Product nuclide = 28060.82c : beta- + + Nuclide 501 / 1657 : 270601 -- cobalt 60m (Co-60m) + + Pointers : 334360 -1000000 + Primary type : Decay + Nuclide ZAI : 270601 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 59.93386 + Atomic weight ratio (AWR) : 59.41900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.28E+02 seconds (10.5 minutes) + Specific ingestion toxicity : 1.70E-12 Sv/Bq + Specific inhalation toxicity : 1.40E-12 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 5.86030E-02 MeV frac = 9.97600E-01 Product nuclide = 270600 : IT + 2 RTYP = 1 Q = 2.88224E+00 MeV frac = 2.40000E-03 Product nuclide = 28060.82c : beta- + + Nuclide 502 / 1657 : 270610 -- cobalt 61 (Co-61) + + Pointers : 334846 -1000000 + Primary type : Decay + Nuclide ZAI : 270610 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 60.93244 + Atomic weight ratio (AWR) : 60.40900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.94E+03 seconds (1.65 hours) + Specific ingestion toxicity : 7.40E-11 Sv/Bq + Specific inhalation toxicity : 5.10E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.32170E+00 MeV frac = 1.00000E+00 Product nuclide = 28061.82c : beta- + + Nuclide 503 / 1657 : 270620 -- cobalt 62 (Co-62) + + Pointers : 335245 -1000000 + Primary type : Decay + Nuclide ZAI : 270620 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 61.93405 + Atomic weight ratio (AWR) : 61.40200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.24E+01 seconds (1.54 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.31500E+00 MeV frac = 1.00000E+00 Product nuclide = 28062.82c : beta- + + Nuclide 504 / 1657 : 270621 -- cobalt 62m (Co-62m) + + Pointers : 336204 -1000000 + Primary type : Decay + Nuclide ZAI : 270621 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 61.93405 + Atomic weight ratio (AWR) : 61.40200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.35E+02 seconds (13.9 minutes) + Specific ingestion toxicity : 4.70E-11 Sv/Bq + Specific inhalation toxicity : 2.10E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 5.33610E+00 MeV frac = 9.90000E-01 Product nuclide = 28062.82c : beta- + 2 RTYP = 3 Q = 2.20000E-02 MeV frac = 1.00000E-02 Product nuclide = 270620 : IT + + Nuclide 505 / 1657 : 270630 -- cobalt 63 (Co-63) + + Pointers : 336461 -1000000 + Primary type : Decay + Nuclide ZAI : 270630 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 62.93363 + Atomic weight ratio (AWR) : 62.39300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 27.4 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.67200E+00 MeV frac = 1.00000E+00 Product nuclide = 280630 : beta- + + Nuclide 506 / 1657 : 270640 -- cobalt 64 (Co-64) + + Pointers : 337042 -1000000 + Primary type : Decay + Nuclide ZAI : 270640 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 63.93584 + Atomic weight ratio (AWR) : 63.38660 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.30700E+00 MeV frac = 1.00000E+00 Product nuclide = 28064.82c : beta- + + Nuclide 507 / 1657 : 270650 -- cobalt 65 (Co-65) + + Pointers : 337329 -1000000 + Primary type : Decay + Nuclide ZAI : 270650 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 64.93644 + Atomic weight ratio (AWR) : 64.37860 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.95800E+00 MeV frac = 1.00000E+00 Product nuclide = 280650 : beta- + + Nuclide 508 / 1657 : 270660 -- cobalt 66 (Co-66) + + Pointers : 337840 -1000000 + Primary type : Decay + Nuclide ZAI : 270660 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 65.93976 + Atomic weight ratio (AWR) : 65.37330 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.89000E+00 MeV frac = 1.00000E+00 Product nuclide = 280660 : beta- + + Nuclide 509 / 1657 : 270670 -- cobalt 67 (Co-67) + + Pointers : 338141 -1000000 + Primary type : Decay + Nuclide ZAI : 270670 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 66.94086 + Atomic weight ratio (AWR) : 66.36580 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.425 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.68000E+00 MeV frac = 1.00000E+00 Product nuclide = 280670 : beta- + + Nuclide 510 / 1657 : 270680 -- cobalt 68 (Co-68) + + Pointers : 338442 -1000000 + Primary type : Decay + Nuclide ZAI : 270680 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 67.94488 + Atomic weight ratio (AWR) : 67.36120 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.15500E+01 MeV frac = 1.00000E+00 Product nuclide = 280680 : beta- + + Nuclide 511 / 1657 : 270681 -- cobalt 68m (Co-68m) + + Pointers : 339093 -1000000 + Primary type : Decay + Nuclide ZAI : 270681 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 67.94488 + Atomic weight ratio (AWR) : 67.36120 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.6 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.22638E+01 MeV frac = 5.00000E-01 Product nuclide = 280680 : beta- + 2 RTYP = 3 Q = 1.50000E-01 MeV frac = 5.00000E-01 Product nuclide = 270680 : IT + + Nuclide 512 / 1657 : 270690 -- cobalt 69 (Co-69) + + Pointers : 339350 -1000000 + Primary type : Decay + Nuclide ZAI : 270690 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 68.94629 + Atomic weight ratio (AWR) : 68.35400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.227 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 9.97900E+00 MeV frac = 9.90000E-01 Product nuclide = 280690 : beta- + 2 RTYP = 15 Q = 5.39250E+00 MeV frac = 1.00000E-02 Product nuclide = 280680 : beta- + neutron emission + + Nuclide 513 / 1657 : 270700 -- cobalt 70 (Co-70) + + Pointers : 339607 -1000000 + Primary type : Decay + Nuclide ZAI : 270700 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 69.95102 + Atomic weight ratio (AWR) : 69.35010 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.119 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.35100E+01 MeV frac = 1.00000E+00 Product nuclide = 280700 : beta- + + Nuclide 514 / 1657 : 270701 -- cobalt 70m (Co-70m) + + Pointers : 339791 -1000000 + Primary type : Decay + Nuclide ZAI : 270701 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 69.95102 + Atomic weight ratio (AWR) : 69.35010 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.37100E+01 MeV frac = 1.00000E+00 Product nuclide = 280700 : beta- + + Nuclide 515 / 1657 : 270710 -- cobalt 71 (Co-71) + + Pointers : 339975 -1000000 + Primary type : Decay + Nuclide ZAI : 270710 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 70.95292 + Atomic weight ratio (AWR) : 70.34340 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 97 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.13300E+01 MeV frac = 1.00000E+00 Product nuclide = 280710 : beta- + + Nuclide 516 / 1657 : 270720 -- cobalt 72 (Co-72) + + Pointers : 340159 -1000000 + Primary type : Decay + Nuclide ZAI : 270720 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 71.95786 + Atomic weight ratio (AWR) : 71.33970 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 90 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.46400E+01 MeV frac = 1.00000E+00 Product nuclide = 280720 : beta- + + Nuclide 517 / 1657 : 270730 -- cobalt 73 (Co-73) + + Pointers : 340343 -1000000 + Primary type : Decay + Nuclide ZAI : 270730 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 72.96027 + Atomic weight ratio (AWR) : 72.33350 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 80 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.28200E+01 MeV frac = 1.00000E+00 Product nuclide = 280730 : beta- + + Nuclide 518 / 1657 : 270740 -- cobalt 74 (Co-74) + + Pointers : 340527 -1000000 + Primary type : Decay + Nuclide ZAI : 270740 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 73.96540 + Atomic weight ratio (AWR) : 73.33000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 50 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.61200E+01 MeV frac = 1.00000E+00 Product nuclide = 280740 : beta- + + Nuclide 519 / 1657 : 270750 -- cobalt 75 (Co-75) + + Pointers : 340711 -1000000 + Primary type : Decay + Nuclide ZAI : 270750 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 74.96832 + Atomic weight ratio (AWR) : 74.32430 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 40 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.44000E+01 MeV frac = 1.00000E+00 Product nuclide = 280750 : beta- + + Nuclide 520 / 1657 : 280570 -- nickel 57 (Ni-57) + + Pointers : 340895 -1000000 + Primary type : Decay + Nuclide ZAI : 280570 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 56.93974 + Atomic weight ratio (AWR) : 56.45060 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.29E+05 seconds (1.5 days) + Specific ingestion toxicity : 8.70E-10 Sv/Bq + Specific inhalation toxicity : 5.30E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 3.26420E+00 MeV frac = 1.00000E+00 Product nuclide = 270570 : EC/beta+ + + Nuclide 521 / 1657 : 280630 -- nickel 63 (Ni-63) + + Pointers : 353858 -1000000 + Primary type : Decay + Nuclide ZAI : 280630 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 62.92970 + Atomic weight ratio (AWR) : 62.38910 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.11E+09 seconds (98.8 years) + Specific ingestion toxicity : 1.50E-10 Sv/Bq + Specific inhalation toxicity : 1.30E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.69800E-02 MeV frac = 1.00000E+00 Product nuclide = 290630 : beta- + + Nuclide 522 / 1657 : 280650 -- nickel 65 (Ni-65) + + Pointers : 355865 -1000000 + Primary type : Decay + Nuclide ZAI : 280650 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 64.93008 + Atomic weight ratio (AWR) : 64.37230 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.07E+03 seconds (2.52 hours) + Specific ingestion toxicity : 1.80E-10 Sv/Bq + Specific inhalation toxicity : 9.00E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.13620E+00 MeV frac = 1.00000E+00 Product nuclide = 29065.82c : beta- + + Nuclide 523 / 1657 : 280660 -- nickel 66 (Ni-66) + + Pointers : 356586 -1000000 + Primary type : Decay + Nuclide ZAI : 280660 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 65.92917 + Atomic weight ratio (AWR) : 65.36280 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.96E+05 seconds (2.27 days) + Specific ingestion toxicity : 3.00E-09 Sv/Bq + Specific inhalation toxicity : 1.80E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.27000E-01 MeV frac = 1.00000E+00 Product nuclide = 290660 : beta- + + Nuclide 524 / 1657 : 280670 -- nickel 67 (Ni-67) + + Pointers : 356803 -1000000 + Primary type : Decay + Nuclide ZAI : 280670 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 66.93158 + Atomic weight ratio (AWR) : 66.35660 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 21 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.55800E+00 MeV frac = 1.00000E+00 Product nuclide = 290670 : beta- + + Nuclide 525 / 1657 : 280680 -- nickel 68 (Ni-68) + + Pointers : 357202 -1000000 + Primary type : Decay + Nuclide ZAI : 280680 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 67.93187 + Atomic weight ratio (AWR) : 67.34830 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 29 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.10320E+00 MeV frac = 1.00000E+00 Product nuclide = 290680 : beta- + + Nuclide 526 / 1657 : 280690 -- nickel 69 (Ni-69) + + Pointers : 357386 -1000000 + Primary type : Decay + Nuclide ZAI : 280690 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 68.93559 + Atomic weight ratio (AWR) : 68.34340 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 11.4 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.36000E+00 MeV frac = 1.00000E+00 Product nuclide = 290690 : beta- + + Nuclide 527 / 1657 : 280691 -- nickel 69m (Ni-69m) + + Pointers : 357967 -1000000 + Primary type : Decay + Nuclide ZAI : 280691 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 68.93559 + Atomic weight ratio (AWR) : 68.34340 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.07820E+00 MeV frac = 1.00000E+00 Product nuclide = 290690 : beta- + + Nuclide 528 / 1657 : 280700 -- nickel 70 (Ni-70) + + Pointers : 358151 -1000000 + Primary type : Decay + Nuclide ZAI : 280700 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 69.93649 + Atomic weight ratio (AWR) : 69.33570 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.58350E+00 MeV frac = 1.00000E+00 Product nuclide = 290702 : beta- + + Nuclide 529 / 1657 : 280710 -- nickel 71 (Ni-71) + + Pointers : 358335 -1000000 + Primary type : Decay + Nuclide ZAI : 280710 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 70.94072 + Atomic weight ratio (AWR) : 70.33130 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.56 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.51111E+00 MeV frac = 1.00000E+00 Product nuclide = 290710 : beta- + + Nuclide 530 / 1657 : 280720 -- nickel 72 (Ni-72) + + Pointers : 358519 -1000000 + Primary type : Decay + Nuclide ZAI : 280720 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 71.94212 + Atomic weight ratio (AWR) : 71.32410 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.57 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.84300E+00 MeV frac = 1.00000E+00 Product nuclide = 290720 : beta- + + Nuclide 531 / 1657 : 280730 -- nickel 73 (Ni-73) + + Pointers : 358703 -1000000 + Primary type : Decay + Nuclide ZAI : 280730 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 72.94645 + Atomic weight ratio (AWR) : 72.31980 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.84 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.12700E+00 MeV frac = 1.00000E+00 Product nuclide = 290730 : beta- + + Nuclide 532 / 1657 : 280740 -- nickel 74 (Ni-74) + + Pointers : 358887 -1000000 + Primary type : Decay + Nuclide ZAI : 280740 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 73.94805 + Atomic weight ratio (AWR) : 73.31280 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.68 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.63600E+00 MeV frac = 1.00000E+00 Product nuclide = 290740 : beta- + + Nuclide 533 / 1657 : 280750 -- nickel 75 (Ni-75) + + Pointers : 359071 -1000000 + Primary type : Decay + Nuclide ZAI : 280750 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 74.95289 + Atomic weight ratio (AWR) : 74.30900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.6 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.02200E+01 MeV frac = 9.84000E-01 Product nuclide = 290750 : beta- + 2 RTYP = 15 Q = 4.03470E+00 MeV frac = 1.60000E-02 Product nuclide = 290740 : beta- + neutron emission + + Nuclide 534 / 1657 : 280760 -- nickel 76 (Ni-76) + + Pointers : 359328 -1000000 + Primary type : Decay + Nuclide ZAI : 280760 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 75.95530 + Atomic weight ratio (AWR) : 75.30280 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.47 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 9.36600E+00 MeV frac = 5.00000E-01 Product nuclide = 290760 : beta- + 2 RTYP = 1 Q = 9.36600E+00 MeV frac = 5.00000E-01 Product nuclide = 290761 : beta- + + Nuclide 535 / 1657 : 280770 -- nickel 77 (Ni-77) + + Pointers : 359585 -1000000 + Primary type : Decay + Nuclide ZAI : 280770 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 76.96053 + Atomic weight ratio (AWR) : 76.29940 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.18300E+01 MeV frac = 1.00000E+00 Product nuclide = 290770 : beta- + + Nuclide 536 / 1657 : 280780 -- nickel 78 (Ni-78) + + Pointers : 359769 -1000000 + Primary type : Decay + Nuclide ZAI : 280780 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 77.96314 + Atomic weight ratio (AWR) : 77.29340 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.04500E+01 MeV frac = 1.00000E+00 Product nuclide = 290780 : beta- + + Nuclide 537 / 1657 : 290630 -- copper 63 (Cu-63) + + Pointers : 359953 -1000000 + Primary type : Decay + Nuclide ZAI : 290630 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 62.92960 + Atomic weight ratio (AWR) : 62.38900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 538 / 1657 : 290640 -- copper 64 (Cu-64) + + Pointers : 360059 -1000000 + Primary type : Decay + Nuclide ZAI : 290640 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 63.92979 + Atomic weight ratio (AWR) : 63.38060 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.57E+04 seconds (12.7 hours) + Specific ingestion toxicity : 1.20E-10 Sv/Bq + Specific inhalation toxicity : 1.20E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 1.67503E+00 MeV frac = 6.15200E-01 Product nuclide = 28064.82c : EC/beta+ + 2 RTYP = 1 Q = 5.79400E-01 MeV frac = 3.84800E-01 Product nuclide = 300640 : beta- + + Nuclide 539 / 1657 : 290660 -- copper 66 (Cu-66) + + Pointers : 363461 -1000000 + Primary type : Decay + Nuclide ZAI : 290660 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 65.92886 + Atomic weight ratio (AWR) : 65.36250 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.06E+02 seconds (5.1 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.64160E+00 MeV frac = 1.00000E+00 Product nuclide = 300660 : beta- + + Nuclide 540 / 1657 : 290670 -- copper 67 (Cu-67) + + Pointers : 363776 -1000000 + Primary type : Decay + Nuclide ZAI : 290670 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 66.92774 + Atomic weight ratio (AWR) : 66.35280 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.23E+05 seconds (2.58 days) + Specific ingestion toxicity : 3.40E-10 Sv/Bq + Specific inhalation toxicity : 6.10E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.76000E-01 MeV frac = 1.00000E+00 Product nuclide = 300670 : beta- + + Nuclide 541 / 1657 : 290680 -- copper 68 (Cu-68) + + Pointers : 364469 -1000000 + Primary type : Decay + Nuclide ZAI : 290680 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 67.92965 + Atomic weight ratio (AWR) : 67.34610 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 31.1 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.46200E+00 MeV frac = 1.00000E+00 Product nuclide = 300680 : beta- + + Nuclide 542 / 1657 : 290681 -- copper 68m (Cu-68m) + + Pointers : 365344 -1000000 + Primary type : Decay + Nuclide ZAI : 290681 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 67.92965 + Atomic weight ratio (AWR) : 67.34610 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.25E+02 seconds (3.75 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 7.21600E-01 MeV frac = 8.40000E-01 Product nuclide = 290680 : IT + 2 RTYP = 1 Q = 5.16181E+00 MeV frac = 1.60000E-01 Product nuclide = 300680 : beta- + + Nuclide 543 / 1657 : 290690 -- copper 69 (Cu-69) + + Pointers : 365601 -1000000 + Primary type : Decay + Nuclide ZAI : 290690 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 68.92944 + Atomic weight ratio (AWR) : 68.33730 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.71E+02 seconds (2.85 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.67500E+00 MeV frac = 1.00000E+00 Product nuclide = 300690 : beta- + + Nuclide 544 / 1657 : 290700 -- copper 70 (Cu-70) + + Pointers : 366378 -1000000 + Primary type : Decay + Nuclide ZAI : 290700 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 69.93236 + Atomic weight ratio (AWR) : 69.33160 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 44.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.58850E+00 MeV frac = 1.00000E+00 Product nuclide = 300700 : beta- + + Nuclide 545 / 1657 : 290701 -- copper 70m (Cu-70m) + + Pointers : 367337 -1000000 + Primary type : Decay + Nuclide ZAI : 290701 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 69.93236 + Atomic weight ratio (AWR) : 69.33160 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 33 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 6.68960E+00 MeV frac = 5.20000E-01 Product nuclide = 300700 : beta- + 2 RTYP = 3 Q = 1.01100E-01 MeV frac = 4.80000E-01 Product nuclide = 290700 : IT + + Nuclide 546 / 1657 : 290702 -- copper 70m (Cu-70m) + + Pointers : 3503132 -1000000 + Primary type : Decay + Nuclide ZAI : 290702 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 69.93236 + Atomic weight ratio (AWR) : 69.33160 + Temperature : 900.0 Kelvin + XS temperature : -1.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.6 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is not present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 6.83110E+00 MeV frac = 9.32000E-01 Product nuclide = 300700 : beta- + 2 RTYP = 3 Q = 1.41500E-01 MeV frac = 6.80000E-02 Product nuclide = 290701 : IT + + Nuclide 547 / 1657 : 290710 -- copper 71 (Cu-71) + + Pointers : 367594 -1000000 + Primary type : Decay + Nuclide ZAI : 290710 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 70.93265 + Atomic weight ratio (AWR) : 70.32330 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 19.4 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.61590E+00 MeV frac = 1.00000E+00 Product nuclide = 300710 : beta- + + Nuclide 548 / 1657 : 290720 -- copper 72 (Cu-72) + + Pointers : 367778 -1000000 + Primary type : Decay + Nuclide ZAI : 290720 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 71.93587 + Atomic weight ratio (AWR) : 71.31790 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.63 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.36200E+00 MeV frac = 1.00000E+00 Product nuclide = 300720 : beta- + + Nuclide 549 / 1657 : 290730 -- copper 73 (Cu-73) + + Pointers : 369171 -1000000 + Primary type : Decay + Nuclide ZAI : 290730 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 72.93666 + Atomic weight ratio (AWR) : 72.31010 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.60620E+00 MeV frac = 1.00000E+00 Product nuclide = 300730 : beta- + + Nuclide 550 / 1657 : 290740 -- copper 74 (Cu-74) + + Pointers : 369542 -1000000 + Primary type : Decay + Nuclide ZAI : 290740 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 73.93988 + Atomic weight ratio (AWR) : 73.30470 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.59 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.70400E+00 MeV frac = 1.00000E+00 Product nuclide = 300740 : beta- + + Nuclide 551 / 1657 : 290750 -- copper 75 (Cu-75) + + Pointers : 369726 -1000000 + Primary type : Decay + Nuclide ZAI : 290750 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 74.94189 + Atomic weight ratio (AWR) : 74.29810 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.22 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.35000E+00 MeV frac = 9.65000E-01 Product nuclide = 300750 : beta- + 2 RTYP = 15 Q = 3.51870E+00 MeV frac = 3.50000E-02 Product nuclide = 300740 : beta- + neutron emission + + Nuclide 552 / 1657 : 290760 -- copper 76 (Cu-76) + + Pointers : 369983 -1000000 + Primary type : Decay + Nuclide ZAI : 290760 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 75.94531 + Atomic weight ratio (AWR) : 75.29290 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.641 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.11640E+01 MeV frac = 9.70000E-01 Product nuclide = 300760 : beta- + 2 RTYP = 15 Q = 3.42270E+00 MeV frac = 3.00000E-02 Product nuclide = 300750 : beta- + neutron emission + + Nuclide 553 / 1657 : 290761 -- copper 76m (Cu-76m) + + Pointers : 370240 -1000000 + Primary type : Decay + Nuclide ZAI : 290761 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 75.94531 + Atomic weight ratio (AWR) : 75.29290 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.27 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.11640E+01 MeV frac = 1.00000E+00 Product nuclide = 300760 : beta- + + Nuclide 554 / 1657 : 290770 -- copper 77 (Cu-77) + + Pointers : 370424 -1000000 + Primary type : Decay + Nuclide ZAI : 290770 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 76.94782 + Atomic weight ratio (AWR) : 76.28680 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.469 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.01400E+01 MeV frac = 1.00000E+00 Product nuclide = 300770 : beta- + + Nuclide 555 / 1657 : 290780 -- copper 78 (Cu-78) + + Pointers : 370608 -1000000 + Primary type : Decay + Nuclide ZAI : 290780 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 77.95195 + Atomic weight ratio (AWR) : 77.28230 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.342 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.25900E+01 MeV frac = 1.00000E+00 Product nuclide = 300780 : beta- + + Nuclide 556 / 1657 : 290790 -- copper 79 (Cu-79) + + Pointers : 370792 -1000000 + Primary type : Decay + Nuclide ZAI : 290790 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 78.95456 + Atomic weight ratio (AWR) : 78.27630 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.188 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.10900E+01 MeV frac = 4.50000E-01 Product nuclide = 300790 : beta- + 2 RTYP = 15 Q = 6.93870E+00 MeV frac = 5.50000E-01 Product nuclide = 300780 : beta- + neutron emission + + Nuclide 557 / 1657 : 290800 -- copper 80 (Cu-80) + + Pointers : 371049 -1000000 + Primary type : Decay + Nuclide ZAI : 290800 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 79.96091 + Atomic weight ratio (AWR) : 79.27400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 100 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.53900E+01 MeV frac = 1.00000E+00 Product nuclide = 300800 : beta- + + Nuclide 558 / 1657 : 300640 -- zinc 64 (Zn-64) + + Pointers : 371233 -1000000 + Primary type : Decay + Nuclide ZAI : 300640 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 63.92919 + Atomic weight ratio (AWR) : 63.38000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.26E+25 seconds (2.3E+18 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 22 Q = 1.09570E+00 MeV frac = 1.00000E+00 Product nuclide = 28064.82c : EC/beta+ + EC/beta+ + + Nuclide 559 / 1657 : 300650 -- zinc 65 (Zn-65) + + Pointers : 371417 -1000000 + Primary type : Decay + Nuclide ZAI : 300650 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 64.92928 + Atomic weight ratio (AWR) : 64.37150 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.11E+07 seconds (244 days) + Specific ingestion toxicity : 3.90E-09 Sv/Bq + Specific inhalation toxicity : 2.20E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 1.35210E+00 MeV frac = 1.00000E+00 Product nuclide = 29065.82c : EC/beta+ + + Nuclide 560 / 1657 : 300660 -- zinc 66 (Zn-66) + + Pointers : 371858 -1000000 + Primary type : Decay + Nuclide ZAI : 300660 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 65.92604 + Atomic weight ratio (AWR) : 65.35970 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 561 / 1657 : 300670 -- zinc 67 (Zn-67) + + Pointers : 371964 -1000000 + Primary type : Decay + Nuclide ZAI : 300670 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 66.92714 + Atomic weight ratio (AWR) : 66.35220 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 562 / 1657 : 300680 -- zinc 68 (Zn-68) + + Pointers : 372070 -1000000 + Primary type : Decay + Nuclide ZAI : 300680 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 67.92481 + Atomic weight ratio (AWR) : 67.34130 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 563 / 1657 : 300690 -- zinc 69 (Zn-69) + + Pointers : 372176 -1000000 + Primary type : Decay + Nuclide ZAI : 300690 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 68.92652 + Atomic weight ratio (AWR) : 68.33440 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.38E+03 seconds (56.4 minutes) + Specific ingestion toxicity : 3.10E-11 Sv/Bq + Specific inhalation toxicity : 2.80E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.09800E-01 MeV frac = 1.00000E+00 Product nuclide = 310690 : beta- + + Nuclide 564 / 1657 : 300691 -- zinc 69m (Zn-69m) + + Pointers : 372631 -1000000 + Primary type : Decay + Nuclide ZAI : 300691 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 68.92652 + Atomic weight ratio (AWR) : 68.33440 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.96E+04 seconds (13.8 hours) + Specific ingestion toxicity : 3.30E-10 Sv/Bq + Specific inhalation toxicity : 2.70E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.34840E+00 MeV frac = 3.30000E-04 Product nuclide = 310690 : beta- + 2 RTYP = 3 Q = 4.38636E-01 MeV frac = 9.99670E-01 Product nuclide = 300690 : IT + + Nuclide 565 / 1657 : 300700 -- zinc 70 (Zn-70) + + Pointers : 373215 -1000000 + Primary type : Decay + Nuclide ZAI : 300700 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 69.92530 + Atomic weight ratio (AWR) : 69.32460 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 566 / 1657 : 300710 -- zinc 71 (Zn-71) + + Pointers : 373321 -1000000 + Primary type : Decay + Nuclide ZAI : 300710 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 70.92771 + Atomic weight ratio (AWR) : 70.31840 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.47E+02 seconds (2.45 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.81020E+00 MeV frac = 1.00000E+00 Product nuclide = 310710 : beta- + + Nuclide 567 / 1657 : 300711 -- zinc 71m (Zn-71m) + + Pointers : 374252 -1000000 + Primary type : Decay + Nuclide ZAI : 300711 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 70.92771 + Atomic weight ratio (AWR) : 70.31840 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.43E+04 seconds (3.96 hours) + Specific ingestion toxicity : 2.40E-10 Sv/Bq + Specific inhalation toxicity : 1.60E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.96790E+00 MeV frac = 1.00000E+00 Product nuclide = 310710 : beta- + + Nuclide 568 / 1657 : 300720 -- zinc 72 (Zn-72) + + Pointers : 375953 -1000000 + Primary type : Decay + Nuclide ZAI : 300720 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 71.92689 + Atomic weight ratio (AWR) : 71.30900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.67E+05 seconds (1.94 days) + Specific ingestion toxicity : 1.40E-09 Sv/Bq + Specific inhalation toxicity : 1.30E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 4.42800E-01 MeV frac = 9.66406E-01 Product nuclide = 310720 : beta- + 2 RTYP = 1 Q = 3.23600E-01 MeV frac = 3.35941E-02 Product nuclide = 310721 : beta- + + Nuclide 569 / 1657 : 300730 -- zinc 73 (Zn-73) + + Pointers : 377013 -1000000 + Primary type : Decay + Nuclide ZAI : 300730 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 72.92981 + Atomic weight ratio (AWR) : 72.30330 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 23.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.29400E+00 MeV frac = 1.00000E+00 Product nuclide = 310730 : beta- + + Nuclide 570 / 1657 : 300731 -- zinc 73m (Zn-73m) + + Pointers : 377664 -1000000 + Primary type : Decay + Nuclide ZAI : 300731 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 72.92981 + Atomic weight ratio (AWR) : 72.30330 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 13 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.95500E-01 MeV frac = 1.00000E+00 Product nuclide = 300730 : IT + + Nuclide 571 / 1657 : 300732 -- zinc 73m (Zn-73m) + + Pointers : 3506326 -1000000 + Primary type : Decay + Nuclide ZAI : 300732 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 72.92981 + Atomic weight ratio (AWR) : 72.30330 + Temperature : 900.0 Kelvin + XS temperature : -1.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.8 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is not present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 4.21000E-02 MeV frac = 5.00000E-01 Product nuclide = 300731 : IT + 2 RTYP = 1 Q = 4.52690E+00 MeV frac = 5.00000E-01 Product nuclide = 310730 : beta- + + Nuclide 572 / 1657 : 300740 -- zinc 74 (Zn-74) + + Pointers : 377848 -1000000 + Primary type : Decay + Nuclide ZAI : 300740 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 73.92949 + Atomic weight ratio (AWR) : 73.29440 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.56E+01 seconds (1.59 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.28043E+00 MeV frac = 1.00000E+00 Product nuclide = 310741 : beta- + + Nuclide 573 / 1657 : 300750 -- zinc 75 (Zn-75) + + Pointers : 378032 -1000000 + Primary type : Decay + Nuclide ZAI : 300750 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 74.93291 + Atomic weight ratio (AWR) : 74.28920 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 10.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.90600E+00 MeV frac = 1.00000E+00 Product nuclide = 310750 : beta- + + Nuclide 574 / 1657 : 300760 -- zinc 76 (Zn-76) + + Pointers : 380209 -1000000 + Primary type : Decay + Nuclide ZAI : 300760 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 75.93331 + Atomic weight ratio (AWR) : 75.28100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.7 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.16000E+00 MeV frac = 1.00000E+00 Product nuclide = 310760 : beta- + + Nuclide 575 / 1657 : 300770 -- zinc 77 (Zn-77) + + Pointers : 381546 -1000000 + Primary type : Decay + Nuclide ZAI : 300770 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 76.93693 + Atomic weight ratio (AWR) : 76.27600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.08 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.27230E+00 MeV frac = 1.00000E+00 Product nuclide = 310770 : beta- + + Nuclide 576 / 1657 : 300771 -- zinc 77m (Zn-77m) + + Pointers : 381730 -1000000 + Primary type : Decay + Nuclide ZAI : 300771 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 76.93693 + Atomic weight ratio (AWR) : 76.27600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.05 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 7.72390E-01 MeV frac = 5.00000E-01 Product nuclide = 300770 : IT + 2 RTYP = 1 Q = 8.04469E+00 MeV frac = 5.00000E-01 Product nuclide = 310770 : beta- + + Nuclide 577 / 1657 : 300780 -- zinc 78 (Zn-78) + + Pointers : 381987 -1000000 + Primary type : Decay + Nuclide ZAI : 300780 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 77.93843 + Atomic weight ratio (AWR) : 77.26890 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.47 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.36660E+00 MeV frac = 1.00000E+00 Product nuclide = 310780 : beta- + + Nuclide 578 / 1657 : 300790 -- zinc 79 (Zn-79) + + Pointers : 382171 -1000000 + Primary type : Decay + Nuclide ZAI : 300790 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 78.94266 + Atomic weight ratio (AWR) : 78.26450 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.995 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 9.09000E+00 MeV frac = 9.87000E-01 Product nuclide = 310790 : beta- + 2 RTYP = 15 Q = 2.21530E+00 MeV frac = 1.30000E-02 Product nuclide = 310780 : beta- + neutron emission + + Nuclide 579 / 1657 : 300800 -- zinc 80 (Zn-80) + + Pointers : 382428 -1000000 + Primary type : Decay + Nuclide ZAI : 300800 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 79.94436 + Atomic weight ratio (AWR) : 79.25760 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.54 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.29000E+00 MeV frac = 1.00000E+00 Product nuclide = 310800 : beta- + + Nuclide 580 / 1657 : 300810 -- zinc 81 (Zn-81) + + Pointers : 383163 -1000000 + Primary type : Decay + Nuclide ZAI : 300810 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 80.95051 + Atomic weight ratio (AWR) : 80.25510 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.29 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.18500E+01 MeV frac = 9.25000E-01 Product nuclide = 310810 : beta- + 2 RTYP = 15 Q = 4.93870E+00 MeV frac = 7.50000E-02 Product nuclide = 310800 : beta- + neutron emission + + Nuclide 581 / 1657 : 300820 -- zinc 82 (Zn-82) + + Pointers : 383420 -1000000 + Primary type : Decay + Nuclide ZAI : 300820 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 81.95443 + Atomic weight ratio (AWR) : 81.25040 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 100 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.06400E+01 MeV frac = 1.00000E+00 Product nuclide = 310820 : beta- + + Nuclide 582 / 1657 : 300830 -- zinc 83 (Zn-83) + + Pointers : 383604 -1000000 + Primary type : Decay + Nuclide ZAI : 300830 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 82.96108 + Atomic weight ratio (AWR) : 82.24840 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 80 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.30900E+01 MeV frac = 1.00000E+00 Product nuclide = 310830 : beta- + + Nuclide 583 / 1657 : 310680 -- gallium 68 (Ga-68) + + Pointers : 383788 -1000000 + Primary type : Decay + Nuclide ZAI : 310680 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 67.92794 + Atomic weight ratio (AWR) : 67.34440 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.07E+03 seconds (1.13 hours) + Specific ingestion toxicity : 1.00E-10 Sv/Bq + Specific inhalation toxicity : 4.90E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 2.92110E+00 MeV frac = 1.00000E+00 Product nuclide = 300680 : EC/beta+ + + Nuclide 584 / 1657 : 310690 -- gallium 69 (Ga-69) + + Pointers : 385013 -1000000 + Primary type : Decay + Nuclide ZAI : 310690 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 68.92561 + Atomic weight ratio (AWR) : 68.33350 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 585 / 1657 : 310700 -- gallium 70 (Ga-70) + + Pointers : 385119 -1000000 + Primary type : Decay + Nuclide ZAI : 310700 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 69.92600 + Atomic weight ratio (AWR) : 69.32530 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.27E+03 seconds (21.1 minutes) + Specific ingestion toxicity : 3.10E-11 Sv/Bq + Specific inhalation toxicity : 1.60E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.65300E+00 MeV frac = 9.95900E-01 Product nuclide = 32070.82c : beta- + 2 RTYP = 2 Q = 6.54500E-01 MeV frac = 4.10000E-03 Product nuclide = 300700 : EC/beta+ + + Nuclide 586 / 1657 : 310710 -- gallium 71 (Ga-71) + + Pointers : 385773 -1000000 + Primary type : Decay + Nuclide ZAI : 310710 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 70.92468 + Atomic weight ratio (AWR) : 70.31540 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 587 / 1657 : 310720 -- gallium 72 (Ga-72) + + Pointers : 385879 -1000000 + Primary type : Decay + Nuclide ZAI : 310720 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 71.92639 + Atomic weight ratio (AWR) : 71.30850 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.08E+04 seconds (14.1 hours) + Specific ingestion toxicity : 1.10E-09 Sv/Bq + Specific inhalation toxicity : 5.30E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.99750E+00 MeV frac = 1.00000E+00 Product nuclide = 32072.82c : beta- + + Nuclide 588 / 1657 : 310721 -- gallium 72m (Ga-72m) + + Pointers : 388266 -1000000 + Primary type : Decay + Nuclide ZAI : 310721 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 71.92639 + Atomic weight ratio (AWR) : 71.30850 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 39.7 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.19660E-01 MeV frac = 1.00000E+00 Product nuclide = 310720 : IT + + Nuclide 589 / 1657 : 310730 -- gallium 73 (Ga-73) + + Pointers : 388450 -1000000 + Primary type : Decay + Nuclide ZAI : 310730 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 72.92517 + Atomic weight ratio (AWR) : 72.29870 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.75E+04 seconds (4.86 hours) + Specific ingestion toxicity : 2.60E-10 Sv/Bq + Specific inhalation toxicity : 1.40E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.59300E+00 MeV frac = 1.46824E-02 Product nuclide = 32073.82c : beta- + 2 RTYP = 1 Q = 1.52626E+00 MeV frac = 9.85318E-01 Product nuclide = 320731 : beta- + + Nuclide 590 / 1657 : 310740 -- gallium 74 (Ga-74) + + Pointers : 389216 -1000000 + Primary type : Decay + Nuclide ZAI : 310740 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 73.92697 + Atomic weight ratio (AWR) : 73.29190 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.87E+02 seconds (8.12 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.37300E+00 MeV frac = 1.00000E+00 Product nuclide = 32074.82c : beta- + + Nuclide 591 / 1657 : 310741 -- gallium 74m (Ga-74m) + + Pointers : 391463 -1000000 + Primary type : Decay + Nuclide ZAI : 310741 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 73.92697 + Atomic weight ratio (AWR) : 73.29190 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 5.95710E-02 MeV frac = 7.50000E-01 Product nuclide = 310740 : IT + 2 RTYP = 1 Q = 5.43197E+00 MeV frac = 2.50000E-01 Product nuclide = 32074.82c : beta- + + Nuclide 592 / 1657 : 310750 -- gallium 75 (Ga-75) + + Pointers : 391720 -1000000 + Primary type : Decay + Nuclide ZAI : 310750 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 74.92646 + Atomic weight ratio (AWR) : 74.28280 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.26E+02 seconds (2.1 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 3.39179E+00 MeV frac = 9.60000E-01 Product nuclide = 320750 : beta- + 2 RTYP = 1 Q = 3.25210E+00 MeV frac = 4.00000E-02 Product nuclide = 320751 : beta- + + Nuclide 593 / 1657 : 310760 -- gallium 76 (Ga-76) + + Pointers : 391977 -1000000 + Primary type : Decay + Nuclide ZAI : 310760 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 75.92887 + Atomic weight ratio (AWR) : 75.27660 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 32.6 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.01000E+00 MeV frac = 1.00000E+00 Product nuclide = 32076.82c : beta- + + Nuclide 594 / 1657 : 310770 -- gallium 77 (Ga-77) + + Pointers : 394140 -1000000 + Primary type : Decay + Nuclide ZAI : 310770 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 76.92926 + Atomic weight ratio (AWR) : 76.26840 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 13 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.18000E+00 MeV frac = 1.00000E+00 Product nuclide = 320771 : beta- + + Nuclide 595 / 1657 : 310780 -- gallium 78 (Ga-78) + + Pointers : 395043 -1000000 + Primary type : Decay + Nuclide ZAI : 310780 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 77.93157 + Atomic weight ratio (AWR) : 77.26210 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.09 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.15600E+00 MeV frac = 1.00000E+00 Product nuclide = 320780 : beta- + + Nuclide 596 / 1657 : 310790 -- gallium 79 (Ga-79) + + Pointers : 396520 -1000000 + Primary type : Decay + Nuclide ZAI : 310790 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 78.93288 + Atomic weight ratio (AWR) : 78.25480 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.85 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 1 Q = 6.98000E+00 MeV frac = 9.97611E-01 Product nuclide = 320790 : beta- + 2 RTYP = 1 Q = 6.79405E+00 MeV frac = 1.49867E-03 Product nuclide = 320791 : beta- + 3 RTYP = 15 Q = 1.28071E+00 MeV frac = 8.90000E-04 Product nuclide = 320780 : beta- + neutron emission + + Nuclide 597 / 1657 : 310800 -- gallium 80 (Ga-80) + + Pointers : 396850 -1000000 + Primary type : Decay + Nuclide ZAI : 310800 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 79.93650 + Atomic weight ratio (AWR) : 79.24980 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.68 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.03800E+01 MeV frac = 1.00000E+00 Product nuclide = 320800 : beta- + + Nuclide 598 / 1657 : 310810 -- gallium 81 (Ga-81) + + Pointers : 398299 -1000000 + Primary type : Decay + Nuclide ZAI : 310810 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 80.93780 + Atomic weight ratio (AWR) : 80.24250 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.22 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 1 Q = 8.32000E+00 MeV frac = 4.65256E-01 Product nuclide = 320810 : beta- + 2 RTYP = 1 Q = 7.64087E+00 MeV frac = 4.15744E-01 Product nuclide = 320811 : beta- + 3 RTYP = 15 Q = 3.46370E+00 MeV frac = 1.19000E-01 Product nuclide = 320800 : beta- + neutron emission + + Nuclide 599 / 1657 : 310820 -- gallium 82 (Ga-82) + + Pointers : 398629 -1000000 + Primary type : Decay + Nuclide ZAI : 310820 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 81.94303 + Atomic weight ratio (AWR) : 81.23910 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.599 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 1 Q = 1.25200E+01 MeV frac = 7.87000E-01 Product nuclide = 320820 : beta- + 2 RTYP = 15 Q = 5.12870E+00 MeV frac = 1.06500E-01 Product nuclide = 320810 : beta- + neutron emission + 3 RTYP = 15 Q = 4.44957E+00 MeV frac = 1.06500E-01 Product nuclide = 320811 : beta- + neutron emission + + Nuclide 600 / 1657 : 310830 -- gallium 83 (Ga-83) + + Pointers : 398959 -1000000 + Primary type : Decay + Nuclide ZAI : 310830 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 82.94696 + Atomic weight ratio (AWR) : 82.23440 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.308 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.15100E+01 MeV frac = 6.30000E-01 Product nuclide = 320830 : beta- + 2 RTYP = 15 Q = 8.15870E+00 MeV frac = 3.70000E-01 Product nuclide = 320820 : beta- + neutron emission + + Nuclide 601 / 1657 : 310840 -- gallium 84 (Ga-84) + + Pointers : 399216 -1000000 + Primary type : Decay + Nuclide ZAI : 310840 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 83.95270 + Atomic weight ratio (AWR) : 83.23150 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 85 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.41400E+01 MeV frac = 3.00000E-01 Product nuclide = 320840 : beta- + 2 RTYP = 15 Q = 8.71870E+00 MeV frac = 7.00000E-01 Product nuclide = 320830 : beta- + neutron emission + + Nuclide 602 / 1657 : 310850 -- gallium 85 (Ga-85) + + Pointers : 399473 -1000000 + Primary type : Decay + Nuclide ZAI : 310850 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 84.95703 + Atomic weight ratio (AWR) : 84.22720 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 50 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.30200E+01 MeV frac = 1.00000E+00 Product nuclide = 320850 : beta- + + Nuclide 603 / 1657 : 310860 -- gallium 86 (Ga-86) + + Pointers : 399657 -1000000 + Primary type : Decay + Nuclide ZAI : 310860 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 85.96317 + Atomic weight ratio (AWR) : 85.22470 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 30 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.54900E+01 MeV frac = 1.00000E+00 Product nuclide = 320860 : beta- + + Nuclide 604 / 1657 : 320690 -- germanium 69 (Ge-69) + + Pointers : 399841 -1000000 + Primary type : Decay + Nuclide ZAI : 320690 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 68.92793 + Atomic weight ratio (AWR) : 68.33580 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.41E+05 seconds (1.63 days) + Specific ingestion toxicity : 2.40E-10 Sv/Bq + Specific inhalation toxicity : 2.90E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 2.22730E+00 MeV frac = 1.00000E+00 Product nuclide = 310690 : EC/beta+ + + Nuclide 605 / 1657 : 320710 -- germanium 71 (Ge-71) + + Pointers : 409194 -1000000 + Primary type : Decay + Nuclide ZAI : 320710 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 70.92498 + Atomic weight ratio (AWR) : 70.31570 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.88E+05 seconds (11.4 days) + Specific ingestion toxicity : 1.20E-11 Sv/Bq + Specific inhalation toxicity : 1.10E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 2.33000E-01 MeV frac = 1.00000E+00 Product nuclide = 310710 : EC/beta+ + + Nuclide 606 / 1657 : 320711 -- germanium 71m (Ge-71m) + + Pointers : 409495 -1000000 + Primary type : Decay + Nuclide ZAI : 320711 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 70.92498 + Atomic weight ratio (AWR) : 70.31570 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 20.4 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.98367E-01 MeV frac = 1.00000E+00 Product nuclide = 320710 : IT + + Nuclide 607 / 1657 : 320731 -- germanium 73m (Ge-73m) + + Pointers : 425580 -1000000 + Primary type : Decay + Nuclide ZAI : 320731 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 72.92345 + Atomic weight ratio (AWR) : 72.29700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 6.67260E-02 MeV frac = 1.00000E+00 Product nuclide = 32073.82c : IT + + Nuclide 608 / 1657 : 320750 -- germanium 75 (Ge-75) + + Pointers : 433086 -1000000 + Primary type : Decay + Nuclide ZAI : 320750 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 74.92283 + Atomic weight ratio (AWR) : 74.27920 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.97E+03 seconds (1.38 hours) + Specific ingestion toxicity : 4.60E-11 Sv/Bq + Specific inhalation toxicity : 3.60E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.17600E+00 MeV frac = 1.00000E+00 Product nuclide = 33075.82c : beta- + + Nuclide 609 / 1657 : 320751 -- germanium 75m (Ge-75m) + + Pointers : 433849 -1000000 + Primary type : Decay + Nuclide ZAI : 320751 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 74.92283 + Atomic weight ratio (AWR) : 74.27920 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 48 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.31600E+00 MeV frac = 3.30000E-04 Product nuclide = 33075.82c : beta- + 2 RTYP = 3 Q = 1.39690E-01 MeV frac = 9.99670E-01 Product nuclide = 320750 : IT + + Nuclide 610 / 1657 : 320770 -- germanium 77 (Ge-77) + + Pointers : 441058 -1000000 + Primary type : Decay + Nuclide ZAI : 320770 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 76.92351 + Atomic weight ratio (AWR) : 76.26270 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.04E+04 seconds (11.2 hours) + Specific ingestion toxicity : 3.30E-10 Sv/Bq + Specific inhalation toxicity : 3.70E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.70250E+00 MeV frac = 1.00000E+00 Product nuclide = 330770 : beta- + + Nuclide 611 / 1657 : 320771 -- germanium 77m (Ge-77m) + + Pointers : 444593 -1000000 + Primary type : Decay + Nuclide ZAI : 320771 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 76.92351 + Atomic weight ratio (AWR) : 76.26270 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 53.7 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 1.59700E-01 MeV frac = 1.90000E-01 Product nuclide = 320770 : IT + 2 RTYP = 1 Q = 2.86220E+00 MeV frac = 8.10000E-01 Product nuclide = 330770 : beta- + + Nuclide 612 / 1657 : 320780 -- germanium 78 (Ge-78) + + Pointers : 445639 -1000000 + Primary type : Decay + Nuclide ZAI : 320780 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 77.92290 + Atomic weight ratio (AWR) : 77.25350 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.28E+03 seconds (1.47 hours) + Specific ingestion toxicity : 1.20E-10 Sv/Bq + Specific inhalation toxicity : 9.50E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.55000E-01 MeV frac = 1.00000E+00 Product nuclide = 330780 : beta- + + Nuclide 613 / 1657 : 320790 -- germanium 79 (Ge-79) + + Pointers : 445912 -1000000 + Primary type : Decay + Nuclide ZAI : 320790 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 78.92541 + Atomic weight ratio (AWR) : 78.24740 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 19 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.14800E+00 MeV frac = 1.00000E+00 Product nuclide = 330790 : beta- + + Nuclide 614 / 1657 : 320791 -- germanium 79m (Ge-79m) + + Pointers : 446661 -1000000 + Primary type : Decay + Nuclide ZAI : 320791 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 78.92541 + Atomic weight ratio (AWR) : 78.24740 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 39 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 4.33400E+00 MeV frac = 9.60000E-01 Product nuclide = 330790 : beta- + 2 RTYP = 3 Q = 1.86020E-01 MeV frac = 4.00000E-02 Product nuclide = 320790 : IT + + Nuclide 615 / 1657 : 320800 -- germanium 80 (Ge-80) + + Pointers : 447651 -1000000 + Primary type : Decay + Nuclide ZAI : 320800 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 79.92540 + Atomic weight ratio (AWR) : 79.23880 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 29.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.64400E+00 MeV frac = 1.00000E+00 Product nuclide = 330800 : beta- + + Nuclide 616 / 1657 : 320810 -- germanium 81 (Ge-81) + + Pointers : 448092 -1000000 + Primary type : Decay + Nuclide ZAI : 320810 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 80.92882 + Atomic weight ratio (AWR) : 80.23360 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.23300E+00 MeV frac = 1.00000E+00 Product nuclide = 330810 : beta- + + Nuclide 617 / 1657 : 320811 -- germanium 81m (Ge-81m) + + Pointers : 448276 -1000000 + Primary type : Decay + Nuclide ZAI : 320811 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 80.92882 + Atomic weight ratio (AWR) : 80.23360 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.6 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.92114E+00 MeV frac = 1.00000E+00 Product nuclide = 330810 : beta- + + Nuclide 618 / 1657 : 320820 -- germanium 82 (Ge-82) + + Pointers : 449375 -1000000 + Primary type : Decay + Nuclide ZAI : 320820 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 81.92952 + Atomic weight ratio (AWR) : 81.22570 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.55 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.70000E+00 MeV frac = 1.00000E+00 Product nuclide = 330820 : beta- + + Nuclide 619 / 1657 : 320830 -- germanium 83 (Ge-83) + + Pointers : 449690 -1000000 + Primary type : Decay + Nuclide ZAI : 320830 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 82.93465 + Atomic weight ratio (AWR) : 82.22220 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.85 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.98000E+00 MeV frac = 1.00000E+00 Product nuclide = 330830 : beta- + + Nuclide 620 / 1657 : 320840 -- germanium 84 (Ge-84) + + Pointers : 449874 -1000000 + Primary type : Decay + Nuclide ZAI : 320840 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 83.93747 + Atomic weight ratio (AWR) : 83.21640 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.954 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 1 Q = 7.83000E+00 MeV frac = 4.46000E-01 Product nuclide = 330840 : beta- + 2 RTYP = 1 Q = 7.83000E+00 MeV frac = 4.46000E-01 Product nuclide = 330841 : beta- + 3 RTYP = 15 Q = 3.55870E+00 MeV frac = 1.08000E-01 Product nuclide = 330830 : beta- + neutron emission + + Nuclide 621 / 1657 : 320850 -- germanium 85 (Ge-85) + + Pointers : 450204 -1000000 + Primary type : Decay + Nuclide ZAI : 320850 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 84.94301 + Atomic weight ratio (AWR) : 84.21330 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.54 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 1 Q = 1.02500E+01 MeV frac = 8.60000E-01 Product nuclide = 330850 : beta- + 2 RTYP = 15 Q = 4.93870E+00 MeV frac = 7.00000E-02 Product nuclide = 330840 : beta- + neutron emission + 3 RTYP = 15 Q = 4.93870E+00 MeV frac = 7.00000E-02 Product nuclide = 330841 : beta- + neutron emission + + Nuclide 622 / 1657 : 320860 -- germanium 86 (Ge-86) + + Pointers : 450534 -1000000 + Primary type : Decay + Nuclide ZAI : 320860 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 85.94653 + Atomic weight ratio (AWR) : 85.20820 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.31000E+00 MeV frac = 1.00000E+00 Product nuclide = 330860 : beta- + + Nuclide 623 / 1657 : 320870 -- germanium 87 (Ge-87) + + Pointers : 450718 -1000000 + Primary type : Decay + Nuclide ZAI : 320870 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 86.95247 + Atomic weight ratio (AWR) : 86.20550 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.15 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.17400E+01 MeV frac = 1.00000E+00 Product nuclide = 330870 : beta- + + Nuclide 624 / 1657 : 320880 -- germanium 88 (Ge-88) + + Pointers : 450902 -1000000 + Primary type : Decay + Nuclide ZAI : 320880 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 87.95690 + Atomic weight ratio (AWR) : 87.20130 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 80 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.11500E+01 MeV frac = 1.00000E+00 Product nuclide = 330880 : beta- + + Nuclide 625 / 1657 : 320890 -- germanium 89 (Ge-89) + + Pointers : 451086 -1000000 + Primary type : Decay + Nuclide ZAI : 320890 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 88.96385 + Atomic weight ratio (AWR) : 88.19960 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 50 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.34500E+01 MeV frac = 1.00000E+00 Product nuclide = 330890 : beta- + + Nuclide 626 / 1657 : 330730 -- arsenic 73 (As-73) + + Pointers : 451270 -1000000 + Primary type : Decay + Nuclide ZAI : 330730 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 72.92385 + Atomic weight ratio (AWR) : 72.29740 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.94E+06 seconds (80.3 days) + Specific ingestion toxicity : 2.60E-10 Sv/Bq + Specific inhalation toxicity : 1.00E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 2.74000E-01 MeV frac = 1.00000E+00 Product nuclide = 320731 : EC/beta+ + + Nuclide 627 / 1657 : 330740 -- arsenic 74 (As-74) + + Pointers : 451599 -1000000 + Primary type : Decay + Nuclide ZAI : 330740 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 73.92395 + Atomic weight ratio (AWR) : 73.28890 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.54E+06 seconds (17.8 days) + Specific ingestion toxicity : 1.30E-09 Sv/Bq + Specific inhalation toxicity : 2.10E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.35390E+00 MeV frac = 3.40000E-01 Product nuclide = 340740 : beta- + 2 RTYP = 2 Q = 2.56220E+00 MeV frac = 6.60000E-01 Product nuclide = 32074.82c : EC/beta+ + + Nuclide 628 / 1657 : 330751 -- arsenic 75m (As-75m) + + Pointers : 455157 -1000000 + Primary type : Decay + Nuclide ZAI : 330751 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 74.92162 + Atomic weight ratio (AWR) : 74.27800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 17.6 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 3.03920E-01 MeV frac = 1.00000E+00 Product nuclide = 33075.82c : IT + + Nuclide 629 / 1657 : 330760 -- arsenic 76 (As-76) + + Pointers : 455808 -1000000 + Primary type : Decay + Nuclide ZAI : 330760 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 75.92241 + Atomic weight ratio (AWR) : 75.27020 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.44E+04 seconds (1.09 days) + Specific ingestion toxicity : 1.60E-09 Sv/Bq + Specific inhalation toxicity : 7.40E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.96250E+00 MeV frac = 1.00000E+00 Product nuclide = 34076.82c : beta- + + Nuclide 630 / 1657 : 330770 -- arsenic 77 (As-77) + + Pointers : 458223 -1000000 + Primary type : Decay + Nuclide ZAI : 330770 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 76.92069 + Atomic weight ratio (AWR) : 76.25990 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.40E+05 seconds (1.62 days) + Specific ingestion toxicity : 4.00E-10 Sv/Bq + Specific inhalation toxicity : 3.90E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.83000E-01 MeV frac = 1.00000E+00 Product nuclide = 34077.82c : beta- + + Nuclide 631 / 1657 : 330780 -- arsenic 78 (As-78) + + Pointers : 459504 -1000000 + Primary type : Decay + Nuclide ZAI : 330780 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 77.92179 + Atomic weight ratio (AWR) : 77.25240 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.44E+03 seconds (1.51 hours) + Specific ingestion toxicity : 2.10E-10 Sv/Bq + Specific inhalation toxicity : 8.90E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.20900E+00 MeV frac = 1.00000E+00 Product nuclide = 34078.82c : beta- + + Nuclide 632 / 1657 : 330790 -- arsenic 79 (As-79) + + Pointers : 460869 -1000000 + Primary type : Decay + Nuclide ZAI : 330790 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 78.92097 + Atomic weight ratio (AWR) : 78.24300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.41E+02 seconds (9.01 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.28090E+00 MeV frac = 1.00000E+00 Product nuclide = 34079.82c : beta- + + Nuclide 633 / 1657 : 330800 -- arsenic 80 (As-80) + + Pointers : 461478 -1000000 + Primary type : Decay + Nuclide ZAI : 330800 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 79.92258 + Atomic weight ratio (AWR) : 79.23600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 15.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.60100E+00 MeV frac = 1.00000E+00 Product nuclide = 34080.82c : beta- + + Nuclide 634 / 1657 : 330810 -- arsenic 81 (As-81) + + Pointers : 462157 -1000000 + Primary type : Decay + Nuclide ZAI : 330810 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 80.92216 + Atomic weight ratio (AWR) : 80.22700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 33.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 3.85600E+00 MeV frac = 9.64110E-01 Product nuclide = 340810 : beta- + 2 RTYP = 1 Q = 3.75310E+00 MeV frac = 3.58897E-02 Product nuclide = 340811 : beta- + + Nuclide 635 / 1657 : 330820 -- arsenic 82 (As-82) + + Pointers : 463273 -1000000 + Primary type : Decay + Nuclide ZAI : 330820 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 81.92447 + Atomic weight ratio (AWR) : 81.22070 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 19.1 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.27000E+00 MeV frac = 1.00000E+00 Product nuclide = 34082.82c : beta- + + Nuclide 636 / 1657 : 330821 -- arsenic 82m (As-82m) + + Pointers : 463714 -1000000 + Primary type : Decay + Nuclide ZAI : 330821 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 81.92447 + Atomic weight ratio (AWR) : 81.22070 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 13.6 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.51500E+00 MeV frac = 1.00000E+00 Product nuclide = 34082.82c : beta- + + Nuclide 637 / 1657 : 330830 -- arsenic 83 (As-83) + + Pointers : 464477 -1000000 + Primary type : Decay + Nuclide ZAI : 330830 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 82.92497 + Atomic weight ratio (AWR) : 82.21260 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 13.4 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 5.46100E+00 MeV frac = 3.60000E-01 Product nuclide = 340830 : beta- + 2 RTYP = 1 Q = 5.23250E+00 MeV frac = 6.40000E-01 Product nuclide = 340831 : beta- + + Nuclide 638 / 1657 : 330840 -- arsenic 84 (As-84) + + Pointers : 464734 -1000000 + Primary type : Decay + Nuclide ZAI : 330840 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 83.92910 + Atomic weight ratio (AWR) : 83.20810 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.02 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 1 Q = 9.87200E+00 MeV frac = 9.97200E-01 Product nuclide = 340840 : beta- + 2 RTYP = 15 Q = 1.18970E+00 MeV frac = 1.40000E-03 Product nuclide = 340830 : beta- + neutron emission + 3 RTYP = 15 Q = 9.61202E-01 MeV frac = 1.40000E-03 Product nuclide = 340831 : beta- + neutron emission + + Nuclide 639 / 1657 : 330841 -- arsenic 84m (As-84m) + + Pointers : 465064 -1000000 + Primary type : Decay + Nuclide ZAI : 330841 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 83.92910 + Atomic weight ratio (AWR) : 83.20810 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.65 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.87200E+00 MeV frac = 1.00000E+00 Product nuclide = 340840 : beta- + + Nuclide 640 / 1657 : 330850 -- arsenic 85 (As-85) + + Pointers : 465248 -1000000 + Primary type : Decay + Nuclide ZAI : 330850 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 84.93181 + Atomic weight ratio (AWR) : 84.20220 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.04 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.91000E+00 MeV frac = 7.80000E-01 Product nuclide = 340850 : beta- + 2 RTYP = 15 Q = 4.37000E+00 MeV frac = 2.20000E-01 Product nuclide = 340840 : beta- + neutron emission + + Nuclide 641 / 1657 : 330860 -- arsenic 86 (As-86) + + Pointers : 466448 -1000000 + Primary type : Decay + Nuclide ZAI : 330860 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 85.93654 + Atomic weight ratio (AWR) : 85.19830 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.945 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.13910E+01 MeV frac = 6.70000E-01 Product nuclide = 340860 : beta- + 2 RTYP = 15 Q = 5.20670E+00 MeV frac = 3.30000E-01 Product nuclide = 340850 : beta- + neutron emission + + Nuclide 642 / 1657 : 330870 -- arsenic 87 (As-87) + + Pointers : 466705 -1000000 + Primary type : Decay + Nuclide ZAI : 330870 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 86.93986 + Atomic weight ratio (AWR) : 86.19300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.61 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.06000E+01 MeV frac = 8.46000E-01 Product nuclide = 340870 : beta- + 2 RTYP = 15 Q = 6.48970E+00 MeV frac = 1.54000E-01 Product nuclide = 340860 : beta- + neutron emission + + Nuclide 643 / 1657 : 330880 -- arsenic 88 (As-88) + + Pointers : 466962 -1000000 + Primary type : Decay + Nuclide ZAI : 330880 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 87.94489 + Atomic weight ratio (AWR) : 87.18940 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.25900E+01 MeV frac = 1.00000E+00 Product nuclide = 340880 : beta- + + Nuclide 644 / 1657 : 330890 -- arsenic 89 (As-89) + + Pointers : 467146 -1000000 + Primary type : Decay + Nuclide ZAI : 330890 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 88.94942 + Atomic weight ratio (AWR) : 88.18530 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.20600E+01 MeV frac = 1.00000E+00 Product nuclide = 340890 : beta- + + Nuclide 645 / 1657 : 330900 -- arsenic 90 (As-90) + + Pointers : 467330 -1000000 + Primary type : Decay + Nuclide ZAI : 330900 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 89.95547 + Atomic weight ratio (AWR) : 89.18270 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 80 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.44800E+01 MeV frac = 1.00000E+00 Product nuclide = 340900 : beta- + + Nuclide 646 / 1657 : 330910 -- arsenic 91 (As-91) + + Pointers : 467514 -1000000 + Primary type : Decay + Nuclide ZAI : 330910 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 90.96040 + Atomic weight ratio (AWR) : 90.17900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 50 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.34800E+01 MeV frac = 1.00000E+00 Product nuclide = 340910 : beta- + + Nuclide 647 / 1657 : 340740 -- selenium 74 (Se-74) + + Pointers : 467698 -1000000 + Primary type : Decay + Nuclide ZAI : 340740 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 73.92243 + Atomic weight ratio (AWR) : 73.28740 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 648 / 1657 : 340750 -- selenium 75 (Se-75) + + Pointers : 467804 -1000000 + Primary type : Decay + Nuclide ZAI : 340750 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 74.92252 + Atomic weight ratio (AWR) : 74.27890 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.03E+07 seconds (120 days) + Specific ingestion toxicity : 2.60E-09 Sv/Bq + Specific inhalation toxicity : 1.30E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 8.63600E-01 MeV frac = 9.39590E-01 Product nuclide = 33075.82c : EC/beta+ + 2 RTYP = 2 Q = 5.59676E-01 MeV frac = 6.04100E-02 Product nuclide = 330751 : EC/beta+ + + Nuclide 649 / 1657 : 340771 -- selenium 77m (Se-77m) + + Pointers : 474140 -1000000 + Primary type : Decay + Nuclide ZAI : 340771 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 76.91988 + Atomic weight ratio (AWR) : 76.25910 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 17.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.61922E-01 MeV frac = 1.00000E+00 Product nuclide = 34077.82c : IT + + Nuclide 650 / 1657 : 340791 -- selenium 79m (Se-79m) + + Pointers : 481369 -1000000 + Primary type : Decay + Nuclide ZAI : 340791 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 78.91855 + Atomic weight ratio (AWR) : 78.24060 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.34E+02 seconds (3.9 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 9.57700E-02 MeV frac = 9.99440E-01 Product nuclide = 34079.82c : IT + 2 RTYP = 1 Q = 2.46800E-01 MeV frac = 5.60000E-04 Product nuclide = 35079.82c : beta- + + Nuclide 651 / 1657 : 340810 -- selenium 81 (Se-81) + + Pointers : 484234 -1000000 + Primary type : Decay + Nuclide ZAI : 340810 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 80.91803 + Atomic weight ratio (AWR) : 80.22290 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.10E+03 seconds (18.4 minutes) + Specific ingestion toxicity : 2.70E-11 Sv/Bq + Specific inhalation toxicity : 1.50E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.58500E+00 MeV frac = 1.00000E+00 Product nuclide = 35081.82c : beta- + + Nuclide 652 / 1657 : 340811 -- selenium 81m (Se-81m) + + Pointers : 485193 -1000000 + Primary type : Decay + Nuclide ZAI : 340811 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 80.91803 + Atomic weight ratio (AWR) : 80.22290 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.44E+03 seconds (57.3 minutes) + Specific ingestion toxicity : 5.30E-11 Sv/Bq + Specific inhalation toxicity : 5.10E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.68800E+00 MeV frac = 6.80000E-04 Product nuclide = 35081.82c : beta- + 2 RTYP = 3 Q = 1.02990E-01 MeV frac = 9.99320E-01 Product nuclide = 340810 : IT + + Nuclide 653 / 1657 : 340830 -- selenium 83 (Se-83) + + Pointers : 488284 -1000000 + Primary type : Decay + Nuclide ZAI : 340830 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 82.91912 + Atomic weight ratio (AWR) : 82.20680 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.34E+03 seconds (22.3 minutes) + Specific ingestion toxicity : 4.70E-11 Sv/Bq + Specific inhalation toxicity : 3.40E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.66800E+00 MeV frac = 1.00000E+00 Product nuclide = 350830 : beta- + + Nuclide 654 / 1657 : 340831 -- selenium 83m (Se-83m) + + Pointers : 488468 -1000000 + Primary type : Decay + Nuclide ZAI : 340831 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 82.91912 + Atomic weight ratio (AWR) : 82.20680 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.01E+01 seconds (1.17 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.89750E+00 MeV frac = 1.00000E+00 Product nuclide = 350830 : beta- + + Nuclide 655 / 1657 : 340840 -- selenium 84 (Se-84) + + Pointers : 489217 -1000000 + Primary type : Decay + Nuclide ZAI : 340840 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 83.91850 + Atomic weight ratio (AWR) : 83.19760 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.96E+02 seconds (3.26 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.86300E+00 MeV frac = 1.00000E+00 Product nuclide = 350840 : beta- + + Nuclide 656 / 1657 : 340850 -- selenium 85 (Se-85) + + Pointers : 489476 -1000000 + Primary type : Decay + Nuclide ZAI : 340850 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 84.92223 + Atomic weight ratio (AWR) : 84.19270 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 31.7 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.18200E+00 MeV frac = 1.00000E+00 Product nuclide = 350850 : beta- + + Nuclide 657 / 1657 : 340860 -- selenium 86 (Se-86) + + Pointers : 489660 -1000000 + Primary type : Decay + Nuclide ZAI : 340860 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 85.92423 + Atomic weight ratio (AWR) : 85.18610 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 15.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.09901E+00 MeV frac = 1.00000E+00 Product nuclide = 350860 : beta- + + Nuclide 658 / 1657 : 340870 -- selenium 87 (Se-87) + + Pointers : 489844 -1000000 + Primary type : Decay + Nuclide ZAI : 340870 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 86.92856 + Atomic weight ratio (AWR) : 86.18180 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.27500E+00 MeV frac = 1.00000E+00 Product nuclide = 350870 : beta- + + Nuclide 659 / 1657 : 340880 -- selenium 88 (Se-88) + + Pointers : 490355 -1000000 + Primary type : Decay + Nuclide ZAI : 340880 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 87.93138 + Atomic weight ratio (AWR) : 87.17600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.53 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 6.85000E+00 MeV frac = 9.90100E-01 Product nuclide = 350880 : beta- + 2 RTYP = 15 Q = 1.90570E+00 MeV frac = 9.90000E-03 Product nuclide = 350870 : beta- + neutron emission + + Nuclide 660 / 1657 : 340890 -- selenium 89 (Se-89) + + Pointers : 490612 -1000000 + Primary type : Decay + Nuclide ZAI : 340890 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 88.93641 + Atomic weight ratio (AWR) : 88.17240 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.41 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 9.37000E+00 MeV frac = 9.22000E-01 Product nuclide = 350890 : beta- + 2 RTYP = 15 Q = 3.45870E+00 MeV frac = 7.80000E-02 Product nuclide = 350880 : beta- + neutron emission + + Nuclide 661 / 1657 : 340900 -- selenium 90 (Se-90) + + Pointers : 490869 -1000000 + Primary type : Decay + Nuclide ZAI : 340900 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 89.93993 + Atomic weight ratio (AWR) : 89.16730 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.69000E+00 MeV frac = 1.00000E+00 Product nuclide = 350900 : beta- + + Nuclide 662 / 1657 : 340910 -- selenium 91 (Se-91) + + Pointers : 491053 -1000000 + Primary type : Decay + Nuclide ZAI : 340910 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 90.94597 + Atomic weight ratio (AWR) : 90.16470 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.27 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.11700E+01 MeV frac = 7.90000E-01 Product nuclide = 350910 : beta- + 2 RTYP = 15 Q = 6.20870E+00 MeV frac = 2.10000E-01 Product nuclide = 350900 : beta- + neutron emission + + Nuclide 663 / 1657 : 340920 -- selenium 92 (Se-92) + + Pointers : 491310 -1000000 + Primary type : Decay + Nuclide ZAI : 340920 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 91.94990 + Atomic weight ratio (AWR) : 91.16000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 100 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.93000E+00 MeV frac = 1.00000E+00 Product nuclide = 350920 : beta- + + Nuclide 664 / 1657 : 340930 -- selenium 93 (Se-93) + + Pointers : 491494 -1000000 + Primary type : Decay + Nuclide ZAI : 340930 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 92.95624 + Atomic weight ratio (AWR) : 92.15770 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 50 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.23300E+01 MeV frac = 1.00000E+00 Product nuclide = 350930 : beta- + + Nuclide 665 / 1657 : 340940 -- selenium 94 (Se-94) + + Pointers : 491678 -1000000 + Primary type : Decay + Nuclide ZAI : 340940 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 93.96047 + Atomic weight ratio (AWR) : 93.15330 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 20 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 350940 : beta- + + Nuclide 666 / 1657 : 350780 -- bromine 78 (Br-78) + + Pointers : 491862 -1000000 + Primary type : Decay + Nuclide ZAI : 350780 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 77.92118 + Atomic weight ratio (AWR) : 77.25180 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.87E+02 seconds (6.45 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 3.57400E+00 MeV frac = 1.00000E+00 Product nuclide = 34078.82c : EC/beta+ + + Nuclide 667 / 1657 : 350791 -- bromine 79m (Br-79m) + + Pointers : 495069 -1000000 + Primary type : Decay + Nuclide ZAI : 350791 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 78.91835 + Atomic weight ratio (AWR) : 78.24040 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.86 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 2.07200E-01 MeV frac = 1.00000E+00 Product nuclide = 35079.82c : IT + + Nuclide 668 / 1657 : 350800 -- bromine 80 (Br-80) + + Pointers : 495412 -1000000 + Primary type : Decay + Nuclide ZAI : 350800 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 79.91854 + Atomic weight ratio (AWR) : 79.23200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.06E+03 seconds (17.6 minutes) + Specific ingestion toxicity : 3.10E-11 Sv/Bq + Specific inhalation toxicity : 9.40E-12 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 2.00600E+00 MeV frac = 9.17000E-01 Product nuclide = 36080.82c : beta- + 2 RTYP = 2 Q = 1.87030E+00 MeV frac = 8.30000E-02 Product nuclide = 34080.82c : EC/beta+ + + Nuclide 669 / 1657 : 350801 -- bromine 80m (Br-80m) + + Pointers : 496346 -1000000 + Primary type : Decay + Nuclide ZAI : 350801 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 79.91854 + Atomic weight ratio (AWR) : 79.23200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.59E+04 seconds (4.41 hours) + Specific ingestion toxicity : 1.10E-10 Sv/Bq + Specific inhalation toxicity : 7.60E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 8.58500E-02 MeV frac = 1.00000E+00 Product nuclide = 350800 : IT + + Nuclide 670 / 1657 : 350820 -- bromine 82 (Br-82) + + Pointers : 498888 -1000000 + Primary type : Decay + Nuclide ZAI : 350820 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 81.91681 + Atomic weight ratio (AWR) : 81.21310 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.27E+05 seconds (1.47 days) + Specific ingestion toxicity : 5.40E-10 Sv/Bq + Specific inhalation toxicity : 6.30E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.09250E+00 MeV frac = 1.00000E+00 Product nuclide = 36082.82c : beta- + + Nuclide 671 / 1657 : 350821 -- bromine 82m (Br-82m) + + Pointers : 500589 -1000000 + Primary type : Decay + Nuclide ZAI : 350821 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 81.91681 + Atomic weight ratio (AWR) : 81.21310 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.65E+02 seconds (6.09 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 3.13840E+00 MeV frac = 2.40000E-02 Product nuclide = 36082.82c : beta- + 2 RTYP = 3 Q = 4.59490E-02 MeV frac = 9.76000E-01 Product nuclide = 350820 : IT + + Nuclide 672 / 1657 : 350830 -- bromine 83 (Br-83) + + Pointers : 502013 -1000000 + Primary type : Decay + Nuclide ZAI : 350830 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 82.91519 + Atomic weight ratio (AWR) : 82.20290 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.64E+03 seconds (2.4 hours) + Specific ingestion toxicity : 4.30E-11 Sv/Bq + Specific inhalation toxicity : 4.80E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 9.73000E-01 MeV frac = 8.89466E-04 Product nuclide = 36083.82c : beta- + 2 RTYP = 1 Q = 9.31445E-01 MeV frac = 9.99111E-01 Product nuclide = 360831 : beta- + + Nuclide 673 / 1657 : 350840 -- bromine 84 (Br-84) + + Pointers : 502499 -1000000 + Primary type : Decay + Nuclide ZAI : 350840 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 83.91649 + Atomic weight ratio (AWR) : 83.19560 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.91E+03 seconds (31.8 minutes) + Specific ingestion toxicity : 8.80E-11 Sv/Bq + Specific inhalation toxicity : 3.70E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.62900E+00 MeV frac = 1.00000E+00 Product nuclide = 36084.82c : beta- + + Nuclide 674 / 1657 : 350841 -- bromine 84m (Br-84m) + + Pointers : 504298 -1000000 + Primary type : Decay + Nuclide ZAI : 350841 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 83.91649 + Atomic weight ratio (AWR) : 83.19560 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.60E+02 seconds (6 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.94900E+00 MeV frac = 1.00000E+00 Product nuclide = 36084.82c : beta- + + Nuclide 675 / 1657 : 350850 -- bromine 85 (Br-85) + + Pointers : 504865 -1000000 + Primary type : Decay + Nuclide ZAI : 350850 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 84.91557 + Atomic weight ratio (AWR) : 84.18610 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.74E+02 seconds (2.9 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 2.87000E+00 MeV frac = 1.62621E-03 Product nuclide = 36085.82c : beta- + 2 RTYP = 1 Q = 2.56512E+00 MeV frac = 9.98374E-01 Product nuclide = 360851 : beta- + + Nuclide 676 / 1657 : 350860 -- bromine 86 (Br-86) + + Pointers : 505631 -1000000 + Primary type : Decay + Nuclide ZAI : 350860 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 85.91879 + Atomic weight ratio (AWR) : 85.18070 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 55 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.62600E+00 MeV frac = 1.00000E+00 Product nuclide = 36086.82c : beta- + + Nuclide 677 / 1657 : 350870 -- bromine 87 (Br-87) + + Pointers : 506352 -1000000 + Primary type : Decay + Nuclide ZAI : 350870 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 86.92069 + Atomic weight ratio (AWR) : 86.17400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 55.7 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 6.85300E+00 MeV frac = 9.74900E-01 Product nuclide = 360870 : beta- + 2 RTYP = 15 Q = 1.33700E+00 MeV frac = 2.51000E-02 Product nuclide = 36086.82c : beta- + neutron emission + + Nuclide 678 / 1657 : 350880 -- bromine 88 (Br-88) + + Pointers : 515560 -1000000 + Primary type : Decay + Nuclide ZAI : 350880 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 87.92411 + Atomic weight ratio (AWR) : 87.16880 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 16.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.96000E+00 MeV frac = 9.33000E-01 Product nuclide = 360880 : beta- + 2 RTYP = 15 Q = 1.92000E+00 MeV frac = 6.70000E-02 Product nuclide = 360870 : beta- + neutron emission + + Nuclide 679 / 1657 : 350890 -- bromine 89 (Br-89) + + Pointers : 520288 -1000000 + Primary type : Decay + Nuclide ZAI : 350890 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 88.92643 + Atomic weight ratio (AWR) : 88.16250 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.37 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.15500E+00 MeV frac = 8.59000E-01 Product nuclide = 360890 : beta- + 2 RTYP = 15 Q = 3.05100E+00 MeV frac = 1.41000E-01 Product nuclide = 360880 : beta- + neutron emission + + Nuclide 680 / 1657 : 350900 -- bromine 90 (Br-90) + + Pointers : 523588 -1000000 + Primary type : Decay + Nuclide ZAI : 350900 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 89.93065 + Atomic weight ratio (AWR) : 89.15810 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.9 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.03500E+01 MeV frac = 7.54000E-01 Product nuclide = 360900 : beta- + 2 RTYP = 15 Q = 4.04000E+00 MeV frac = 2.46000E-01 Product nuclide = 360890 : beta- + neutron emission + + Nuclide 681 / 1657 : 350910 -- bromine 91 (Br-91) + + Pointers : 525936 -1000000 + Primary type : Decay + Nuclide ZAI : 350910 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 90.93397 + Atomic weight ratio (AWR) : 90.15280 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.538 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 9.80200E+00 MeV frac = 8.00000E-01 Product nuclide = 360910 : beta- + 2 RTYP = 15 Q = 5.70000E+00 MeV frac = 2.00000E-01 Product nuclide = 360900 : beta- + neutron emission + + Nuclide 682 / 1657 : 350920 -- bromine 92 (Br-92) + + Pointers : 526688 -1000000 + Primary type : Decay + Nuclide ZAI : 350920 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 91.93931 + Atomic weight ratio (AWR) : 91.14950 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.343 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.22050E+01 MeV frac = 6.69000E-01 Product nuclide = 360920 : beta- + 2 RTYP = 15 Q = 6.65870E+00 MeV frac = 3.31000E-01 Product nuclide = 360910 : beta- + neutron emission + + Nuclide 683 / 1657 : 350930 -- bromine 93 (Br-93) + + Pointers : 526945 -1000000 + Primary type : Decay + Nuclide ZAI : 350930 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 92.94303 + Atomic weight ratio (AWR) : 92.14460 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.102 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.09700E+01 MeV frac = 3.20000E-01 Product nuclide = 360930 : beta- + 2 RTYP = 15 Q = 7.66370E+00 MeV frac = 6.80000E-01 Product nuclide = 360920 : beta- + neutron emission + + Nuclide 684 / 1657 : 350940 -- bromine 94 (Br-94) + + Pointers : 527202 -1000000 + Primary type : Decay + Nuclide ZAI : 350940 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 93.94867 + Atomic weight ratio (AWR) : 93.14160 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 70 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.33400E+01 MeV frac = 3.00000E-01 Product nuclide = 360940 : beta- + 2 RTYP = 15 Q = 8.14870E+00 MeV frac = 7.00000E-01 Product nuclide = 360930 : beta- + neutron emission + + Nuclide 685 / 1657 : 350950 -- bromine 95 (Br-95) + + Pointers : 527459 -1000000 + Primary type : Decay + Nuclide ZAI : 350950 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 94.95290 + Atomic weight ratio (AWR) : 94.13720 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 50 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.21400E+01 MeV frac = 1.00000E+00 Product nuclide = 360950 : beta- + + Nuclide 686 / 1657 : 350960 -- bromine 96 (Br-96) + + Pointers : 527643 -1000000 + Primary type : Decay + Nuclide ZAI : 350960 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 95.95853 + Atomic weight ratio (AWR) : 95.13420 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 20 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.44000E+01 MeV frac = 1.00000E+00 Product nuclide = 360960 : beta- + + Nuclide 687 / 1657 : 360790 -- krypton 79 (Kr-79) + + Pointers : 527827 -1000000 + Primary type : Decay + Nuclide ZAI : 360790 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 78.92007 + Atomic weight ratio (AWR) : 78.24210 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.26E+05 seconds (1.46 days) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 1.63100E+00 MeV frac = 1.00000E+00 Product nuclide = 35079.82c : EC/beta+ + + Nuclide 688 / 1657 : 360810 -- krypton 81 (Kr-81) + + Pointers : 531820 -1000000 + Primary type : Decay + Nuclide ZAI : 360810 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 80.91662 + Atomic weight ratio (AWR) : 80.22150 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.63E+12 seconds (210,144 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 2.80800E-01 MeV frac = 1.00000E+00 Product nuclide = 35081.82c : EC/beta+ + + Nuclide 689 / 1657 : 360811 -- krypton 81m (Kr-81m) + + Pointers : 532205 -1000000 + Primary type : Decay + Nuclide ZAI : 360811 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 80.91662 + Atomic weight ratio (AWR) : 80.22150 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 13.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 4.71300E-01 MeV frac = 2.50000E-05 Product nuclide = 35081.82c : EC/beta+ + 2 RTYP = 3 Q = 1.90530E-01 MeV frac = 9.99975E-01 Product nuclide = 360810 : IT + + Nuclide 690 / 1657 : 360831 -- krypton 83m (Kr-83m) + + Pointers : 538578 -1000000 + Primary type : Decay + Nuclide ZAI : 360831 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 82.91418 + Atomic weight ratio (AWR) : 82.20190 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.59E+03 seconds (1.83 hours) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 4.15430E-02 MeV frac = 1.00000E+00 Product nuclide = 36083.82c : IT + + Nuclide 691 / 1657 : 360851 -- krypton 85m (Kr-85m) + + Pointers : 544026 -1000000 + Primary type : Decay + Nuclide ZAI : 360851 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 84.91254 + Atomic weight ratio (AWR) : 84.18310 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.61E+04 seconds (4.48 hours) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 9.92260E-01 MeV frac = 7.86000E-01 Product nuclide = 37085.82c : beta- + 2 RTYP = 3 Q = 3.04870E-01 MeV frac = 2.14000E-01 Product nuclide = 36085.82c : IT + + Nuclide 692 / 1657 : 360870 -- krypton 87 (Kr-87) + + Pointers : 547579 -1000000 + Primary type : Decay + Nuclide ZAI : 360870 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 86.91333 + Atomic weight ratio (AWR) : 86.16670 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.58E+03 seconds (1.27 hours) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.88700E+00 MeV frac = 1.00000E+00 Product nuclide = 37087.82c : beta- + + Nuclide 693 / 1657 : 360880 -- krypton 88 (Kr-88) + + Pointers : 548482 -1000000 + Primary type : Decay + Nuclide ZAI : 360880 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 87.91443 + Atomic weight ratio (AWR) : 87.15920 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.02E+04 seconds (2.84 hours) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.91700E+00 MeV frac = 1.00000E+00 Product nuclide = 370880 : beta- + + Nuclide 694 / 1657 : 360890 -- krypton 89 (Kr-89) + + Pointers : 550407 -1000000 + Primary type : Decay + Nuclide ZAI : 360890 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 88.91765 + Atomic weight ratio (AWR) : 88.15380 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.89E+02 seconds (3.15 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.17650E+00 MeV frac = 1.00000E+00 Product nuclide = 370890 : beta- + + Nuclide 695 / 1657 : 360900 -- krypton 90 (Kr-90) + + Pointers : 555454 -1000000 + Primary type : Decay + Nuclide ZAI : 360900 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 89.91956 + Atomic weight ratio (AWR) : 89.14710 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 32.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 4.40600E+00 MeV frac = 8.72000E-01 Product nuclide = 370900 : beta- + 2 RTYP = 1 Q = 4.29900E+00 MeV frac = 1.28000E-01 Product nuclide = 370901 : beta- + + Nuclide 696 / 1657 : 360910 -- krypton 91 (Kr-91) + + Pointers : 558194 -1000000 + Primary type : Decay + Nuclide ZAI : 360910 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 90.92348 + Atomic weight ratio (AWR) : 90.14240 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.57 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.77100E+00 MeV frac = 1.00000E+00 Product nuclide = 370910 : beta- + + Nuclide 697 / 1657 : 360920 -- krypton 92 (Kr-92) + + Pointers : 562541 -1000000 + Primary type : Decay + Nuclide ZAI : 360920 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 91.92619 + Atomic weight ratio (AWR) : 91.13650 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.84 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.00300E+00 MeV frac = 1.00000E+00 Product nuclide = 370920 : beta- + + Nuclide 698 / 1657 : 360930 -- krypton 93 (Kr-93) + + Pointers : 564410 -1000000 + Primary type : Decay + Nuclide ZAI : 360930 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 92.93123 + Atomic weight ratio (AWR) : 92.13290 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.29 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.48500E+00 MeV frac = 1.00000E+00 Product nuclide = 370930 : beta- + + Nuclide 699 / 1657 : 360940 -- krypton 94 (Kr-94) + + Pointers : 568617 -1000000 + Primary type : Decay + Nuclide ZAI : 360940 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 93.93435 + Atomic weight ratio (AWR) : 93.12740 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.21 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 7.41300E+00 MeV frac = 9.88900E-01 Product nuclide = 370940 : beta- + 2 RTYP = 15 Q = 3.40670E+00 MeV frac = 1.11000E-02 Product nuclide = 370930 : beta- + neutron emission + + Nuclide 700 / 1657 : 360950 -- krypton 95 (Kr-95) + + Pointers : 568874 -1000000 + Primary type : Decay + Nuclide ZAI : 360950 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 94.93988 + Atomic weight ratio (AWR) : 94.12430 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.114 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 9.81400E+00 MeV frac = 9.71300E-01 Product nuclide = 370950 : beta- + 2 RTYP = 15 Q = 4.44170E+00 MeV frac = 2.87000E-02 Product nuclide = 370940 : beta- + neutron emission + + Nuclide 701 / 1657 : 360960 -- krypton 96 (Kr-96) + + Pointers : 569131 -1000000 + Primary type : Decay + Nuclide ZAI : 360960 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 95.94310 + Atomic weight ratio (AWR) : 95.11890 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 80 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 1 Q = 8.19500E+00 MeV frac = 4.81500E-01 Product nuclide = 370960 : beta- + 2 RTYP = 1 Q = 8.19500E+00 MeV frac = 4.81500E-01 Product nuclide = 370961 : beta- + 3 RTYP = 15 Q = 4.75270E+00 MeV frac = 3.70000E-02 Product nuclide = 370950 : beta- + neutron emission + + Nuclide 702 / 1657 : 360970 -- krypton 97 (Kr-97) + + Pointers : 569461 -1000000 + Primary type : Decay + Nuclide ZAI : 360970 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 96.94854 + Atomic weight ratio (AWR) : 96.11570 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 63 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 1 Q = 1.04400E+01 MeV frac = 9.33000E-01 Product nuclide = 370970 : beta- + 2 RTYP = 15 Q = 5.23370E+00 MeV frac = 3.35000E-02 Product nuclide = 370960 : beta- + neutron emission + 3 RTYP = 15 Q = 5.23370E+00 MeV frac = 3.35000E-02 Product nuclide = 370961 : beta- + neutron emission + + Nuclide 703 / 1657 : 360980 -- krypton 98 (Kr-98) + + Pointers : 569791 -1000000 + Primary type : Decay + Nuclide ZAI : 360980 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 97.95196 + Atomic weight ratio (AWR) : 97.11050 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 46 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 9.03000E+00 MeV frac = 9.30000E-01 Product nuclide = 370981 : beta- + 2 RTYP = 15 Q = 5.48870E+00 MeV frac = 7.00000E-02 Product nuclide = 370970 : beta- + neutron emission + + Nuclide 704 / 1657 : 360990 -- krypton 99 (Kr-99) + + Pointers : 570048 -1000000 + Primary type : Decay + Nuclide ZAI : 360990 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 98.95760 + Atomic weight ratio (AWR) : 98.10750 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 40 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 1 Q = 1.13800E+01 MeV frac = 8.90000E-01 Product nuclide = 370990 : beta- + 2 RTYP = 15 Q = 6.64870E+00 MeV frac = 5.50000E-02 Product nuclide = 370980 : beta- + neutron emission + 3 RTYP = 15 Q = 6.25870E+00 MeV frac = 5.50000E-02 Product nuclide = 370981 : beta- + neutron emission + + Nuclide 705 / 1657 : 370830 -- rubidium 83 (Rb-83) + + Pointers : 570378 -1000000 + Primary type : Decay + Nuclide ZAI : 370830 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 82.91508 + Atomic weight ratio (AWR) : 82.20280 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.45E+06 seconds (86.2 days) + Specific ingestion toxicity : 1.90E-09 Sv/Bq + Specific inhalation toxicity : 6.90E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 9.40000E-01 MeV frac = 2.50000E-01 Product nuclide = 36083.82c : EC/beta+ + 2 RTYP = 2 Q = 8.98000E-01 MeV frac = 7.50000E-01 Product nuclide = 360831 : EC/beta+ + + Nuclide 706 / 1657 : 370831 -- rubidium 83m (Rb-83m) + + Pointers : 571396 -1000000 + Primary type : Decay + Nuclide ZAI : 370831 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 82.91508 + Atomic weight ratio (AWR) : 82.20280 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.8 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 4.21100E-02 MeV frac = 1.00000E+00 Product nuclide = 370830 : IT + + Nuclide 707 / 1657 : 370840 -- rubidium 84 (Rb-84) + + Pointers : 571580 -1000000 + Primary type : Decay + Nuclide ZAI : 370840 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 83.91437 + Atomic weight ratio (AWR) : 83.19350 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.89E+06 seconds (33.5 days) + Specific ingestion toxicity : 2.80E-09 Sv/Bq + Specific inhalation toxicity : 1.00E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.94000E-01 MeV frac = 3.20000E-02 Product nuclide = 380840 : beta- + 2 RTYP = 2 Q = 2.68500E+00 MeV frac = 9.68000E-01 Product nuclide = 36084.82c : EC/beta+ + + Nuclide 708 / 1657 : 370841 -- rubidium 84m (Rb-84m) + + Pointers : 572066 -1000000 + Primary type : Decay + Nuclide ZAI : 370841 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 83.91437 + Atomic weight ratio (AWR) : 83.19350 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.22E+03 seconds (20.4 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 4.63600E-01 MeV frac = 1.00000E+00 Product nuclide = 370840 : IT + + Nuclide 709 / 1657 : 370861 -- rubidium 86m (Rb-86m) + + Pointers : 576714 -1000000 + Primary type : Decay + Nuclide ZAI : 370861 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 85.91122 + Atomic weight ratio (AWR) : 85.17320 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.10E+01 seconds (1.02 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 5.56000E-01 MeV frac = 1.00000E+00 Product nuclide = 37086.82c : IT + + Nuclide 710 / 1657 : 370880 -- rubidium 88 (Rb-88) + + Pointers : 579082 -1000000 + Primary type : Decay + Nuclide ZAI : 370880 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 87.91130 + Atomic weight ratio (AWR) : 87.15610 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.07E+03 seconds (17.8 minutes) + Specific ingestion toxicity : 9.00E-11 Sv/Bq + Specific inhalation toxicity : 1.60E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.31600E+00 MeV frac = 1.00000E+00 Product nuclide = 38088.82c : beta- + + Nuclide 711 / 1657 : 370890 -- rubidium 89 (Rb-89) + + Pointers : 579985 -1000000 + Primary type : Decay + Nuclide ZAI : 370890 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 88.91230 + Atomic weight ratio (AWR) : 88.14850 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.24E+02 seconds (15.4 minutes) + Specific ingestion toxicity : 4.70E-11 Sv/Bq + Specific inhalation toxicity : 1.40E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.49600E+00 MeV frac = 1.00000E+00 Product nuclide = 38089.82c : beta- + + Nuclide 712 / 1657 : 370900 -- rubidium 90 (Rb-90) + + Pointers : 583058 -1000000 + Primary type : Decay + Nuclide ZAI : 370900 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 89.91482 + Atomic weight ratio (AWR) : 89.14240 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.57E+02 seconds (2.62 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.58400E+00 MeV frac = 1.00000E+00 Product nuclide = 38090.82c : beta- + + Nuclide 713 / 1657 : 370901 -- rubidium 90m (Rb-90m) + + Pointers : 585683 -1000000 + Primary type : Decay + Nuclide ZAI : 370901 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 89.91482 + Atomic weight ratio (AWR) : 89.14240 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.58E+02 seconds (4.3 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 1.06900E-01 MeV frac = 2.60000E-02 Product nuclide = 370900 : IT + 2 RTYP = 1 Q = 6.69390E+00 MeV frac = 9.74000E-01 Product nuclide = 38090.82c : beta- + + Nuclide 714 / 1657 : 370910 -- rubidium 91 (Rb-91) + + Pointers : 588241 -1000000 + Primary type : Decay + Nuclide ZAI : 370910 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 90.91652 + Atomic weight ratio (AWR) : 90.13550 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 58.4 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.89100E+00 MeV frac = 1.00000E+00 Product nuclide = 380910 : beta- + + Nuclide 715 / 1657 : 370920 -- rubidium 92 (Rb-92) + + Pointers : 591020 -1000000 + Primary type : Decay + Nuclide ZAI : 370920 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 91.91974 + Atomic weight ratio (AWR) : 91.13010 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.48 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.09500E+00 MeV frac = 1.00000E+00 Product nuclide = 380920 : beta- + + Nuclide 716 / 1657 : 370930 -- rubidium 93 (Rb-93) + + Pointers : 592875 -1000000 + Primary type : Decay + Nuclide ZAI : 370930 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 92.92205 + Atomic weight ratio (AWR) : 92.12380 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.8 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 7.46200E+00 MeV frac = 9.86000E-01 Product nuclide = 380930 : beta- + 2 RTYP = 15 Q = 2.20600E+00 MeV frac = 1.40000E-02 Product nuclide = 380920 : beta- + neutron emission + + Nuclide 717 / 1657 : 370940 -- rubidium 94 (Rb-94) + + Pointers : 599409 -1000000 + Primary type : Decay + Nuclide ZAI : 370940 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 93.92648 + Atomic weight ratio (AWR) : 93.11960 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.7 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.02910E+01 MeV frac = 8.99000E-01 Product nuclide = 380940 : beta- + 2 RTYP = 15 Q = 3.46500E+00 MeV frac = 1.01000E-01 Product nuclide = 380930 : beta- + neutron emission + + Nuclide 718 / 1657 : 370950 -- rubidium 95 (Rb-95) + + Pointers : 604389 -1000000 + Primary type : Decay + Nuclide ZAI : 370950 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 94.92929 + Atomic weight ratio (AWR) : 94.11380 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.381 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 9.27900E+00 MeV frac = 9.14000E-01 Product nuclide = 380950 : beta- + 2 RTYP = 15 Q = 4.93200E+00 MeV frac = 8.60000E-02 Product nuclide = 380940 : beta- + neutron emission + + Nuclide 719 / 1657 : 370960 -- rubidium 96 (Rb-96) + + Pointers : 610587 -1000000 + Primary type : Decay + Nuclide ZAI : 370960 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 95.93433 + Atomic weight ratio (AWR) : 95.11020 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.199 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.17700E+01 MeV frac = 8.66000E-01 Product nuclide = 380960 : beta- + 2 RTYP = 15 Q = 5.86100E+00 MeV frac = 1.34000E-01 Product nuclide = 380950 : beta- + neutron emission + + Nuclide 720 / 1657 : 370961 -- rubidium 96m (Rb-96m) + + Pointers : 612543 -1000000 + Primary type : Decay + Nuclide ZAI : 370961 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 95.93433 + Atomic weight ratio (AWR) : 95.11020 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.17140E+01 MeV frac = 5.00000E-01 Product nuclide = 380960 : beta- + 2 RTYP = 3 Q = 0.00000E+00 MeV frac = 5.00000E-01 Product nuclide = 370960 : IT + + Nuclide 721 / 1657 : 370970 -- rubidium 97 (Rb-97) + + Pointers : 612800 -1000000 + Primary type : Decay + Nuclide ZAI : 370970 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 96.93734 + Atomic weight ratio (AWR) : 96.10460 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.17 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.05200E+01 MeV frac = 7.49000E-01 Product nuclide = 380970 : beta- + 2 RTYP = 15 Q = 6.53700E+00 MeV frac = 2.51000E-01 Product nuclide = 380960 : beta- + neutron emission + + Nuclide 722 / 1657 : 370980 -- rubidium 98 (Rb-98) + + Pointers : 614952 -1000000 + Primary type : Decay + Nuclide ZAI : 370980 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 97.94177 + Atomic weight ratio (AWR) : 97.10040 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.114 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 1 Q = 1.24260E+01 MeV frac = 8.61490E-01 Product nuclide = 380980 : beta- + 2 RTYP = 15 Q = 6.49670E+00 MeV frac = 1.38000E-01 Product nuclide = 380970 : beta- + neutron emission + 3 RTYP = 155 Q = 2.57640E+00 MeV frac = 5.10000E-04 Product nuclide = 380960 : beta- + neutron emission + neutron emission + + Nuclide 723 / 1657 : 370981 -- rubidium 98m (Rb-98m) + + Pointers : 615282 -1000000 + Primary type : Decay + Nuclide ZAI : 370981 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 97.94177 + Atomic weight ratio (AWR) : 97.10040 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 96 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.28160E+01 MeV frac = 1.00000E+00 Product nuclide = 380980 : beta- + + Nuclide 724 / 1657 : 370990 -- rubidium 99 (Rb-99) + + Pointers : 615466 -1000000 + Primary type : Decay + Nuclide ZAI : 370990 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 98.94539 + Atomic weight ratio (AWR) : 98.09540 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 50.3 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.13100E+01 MeV frac = 8.41000E-01 Product nuclide = 380990 : beta- + 2 RTYP = 15 Q = 7.69470E+00 MeV frac = 1.59000E-01 Product nuclide = 380980 : beta- + neutron emission + + Nuclide 725 / 1657 : 371000 -- rubidium 100 (Rb-100) + + Pointers : 615723 -1000000 + Primary type : Decay + Nuclide ZAI : 371000 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 99.94982 + Atomic weight ratio (AWR) : 99.09120 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 51 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 1 Q = 1.35200E+01 MeV frac = 9.42500E-01 Product nuclide = 381000 : beta- + 2 RTYP = 15 Q = 7.41870E+00 MeV frac = 5.60000E-02 Product nuclide = 380990 : beta- + neutron emission + 3 RTYP = 155 Q = 3.80340E+00 MeV frac = 1.50000E-03 Product nuclide = 380980 : beta- + neutron emission + neutron emission + + Nuclide 726 / 1657 : 371010 -- rubidium 101 (Rb-101) + + Pointers : 616053 -1000000 + Primary type : Decay + Nuclide ZAI : 371010 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 100.95324 + Atomic weight ratio (AWR) : 100.08600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 32 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.18100E+01 MeV frac = 1.00000E+00 Product nuclide = 381010 : beta- + + Nuclide 727 / 1657 : 380840 -- strontium 84 (Sr-84) + + Pointers : 616830 -1000000 + Primary type : Decay + Nuclide ZAI : 380840 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 83.91346 + Atomic weight ratio (AWR) : 83.19260 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 728 / 1657 : 380850 -- strontium 85 (Sr-85) + + Pointers : 616936 -1000000 + Primary type : Decay + Nuclide ZAI : 380850 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 84.91295 + Atomic weight ratio (AWR) : 84.18350 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.60E+06 seconds (64.8 days) + Specific ingestion toxicity : 5.60E-10 Sv/Bq + Specific inhalation toxicity : 8.10E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 1.06500E+00 MeV frac = 1.00000E+00 Product nuclide = 37085.82c : EC/beta+ + + Nuclide 729 / 1657 : 380851 -- strontium 85m (Sr-85m) + + Pointers : 617727 -1000000 + Primary type : Decay + Nuclide ZAI : 380851 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 84.91295 + Atomic weight ratio (AWR) : 84.18350 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.06E+03 seconds (1.13 hours) + Specific ingestion toxicity : 6.10E-12 Sv/Bq + Specific inhalation toxicity : 4.30E-12 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 1.30400E+00 MeV frac = 1.34000E-01 Product nuclide = 37085.82c : EC/beta+ + 2 RTYP = 3 Q = 2.38660E-01 MeV frac = 8.66000E-01 Product nuclide = 380850 : IT + + Nuclide 730 / 1657 : 380871 -- strontium 87m (Sr-87m) + + Pointers : 623251 -1000000 + Primary type : Decay + Nuclide ZAI : 380871 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 86.90889 + Atomic weight ratio (AWR) : 86.16230 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.01E+04 seconds (2.82 hours) + Specific ingestion toxicity : 3.00E-11 Sv/Bq + Specific inhalation toxicity : 2.10E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 1.05900E-01 MeV frac = 3.00000E-03 Product nuclide = 37087.82c : EC/beta+ + 2 RTYP = 3 Q = 3.88533E-01 MeV frac = 9.97000E-01 Product nuclide = 38087.82c : IT + + Nuclide 731 / 1657 : 380910 -- strontium 91 (Sr-91) + + Pointers : 630832 -1000000 + Primary type : Decay + Nuclide ZAI : 380910 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 90.91017 + Atomic weight ratio (AWR) : 90.12920 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.47E+04 seconds (9.65 hours) + Specific ingestion toxicity : 6.50E-10 Sv/Bq + Specific inhalation toxicity : 4.10E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 2.69900E+00 MeV frac = 4.11637E-01 Product nuclide = 39091.82c : beta- + 2 RTYP = 1 Q = 2.14342E+00 MeV frac = 5.88363E-01 Product nuclide = 390911 : beta- + + Nuclide 732 / 1657 : 380920 -- strontium 92 (Sr-92) + + Pointers : 632466 -1000000 + Primary type : Decay + Nuclide ZAI : 380920 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 91.91106 + Atomic weight ratio (AWR) : 91.12150 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.76E+03 seconds (2.71 hours) + Specific ingestion toxicity : 4.30E-10 Sv/Bq + Specific inhalation toxicity : 2.30E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.94000E+00 MeV frac = 1.00000E+00 Product nuclide = 390920 : beta- + + Nuclide 733 / 1657 : 380930 -- strontium 93 (Sr-93) + + Pointers : 633145 -1000000 + Primary type : Decay + Nuclide ZAI : 380930 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 92.91398 + Atomic weight ratio (AWR) : 92.11580 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.45E+02 seconds (7.42 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 4.13700E+00 MeV frac = 7.49759E-01 Product nuclide = 390930 : beta- + 2 RTYP = 1 Q = 3.37828E+00 MeV frac = 2.50241E-01 Product nuclide = 390931 : beta- + + Nuclide 734 / 1657 : 380940 -- strontium 94 (Sr-94) + + Pointers : 636011 -1000000 + Primary type : Decay + Nuclide ZAI : 380940 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 93.91538 + Atomic weight ratio (AWR) : 93.10860 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.53E+01 seconds (1.25 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.51000E+00 MeV frac = 1.00000E+00 Product nuclide = 390940 : beta- + + Nuclide 735 / 1657 : 380950 -- strontium 95 (Sr-95) + + Pointers : 637264 -1000000 + Primary type : Decay + Nuclide ZAI : 380950 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 94.91931 + Atomic weight ratio (AWR) : 94.10390 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 23.9 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.09000E+00 MeV frac = 1.00000E+00 Product nuclide = 390950 : beta- + + Nuclide 736 / 1657 : 380960 -- strontium 96 (Sr-96) + + Pointers : 639287 -1000000 + Primary type : Decay + Nuclide ZAI : 380960 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 95.92172 + Atomic weight ratio (AWR) : 95.09770 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.07 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.41500E+00 MeV frac = 1.00000E+00 Product nuclide = 390960 : beta- + + Nuclide 737 / 1657 : 380970 -- strontium 97 (Sr-97) + + Pointers : 640232 -1000000 + Primary type : Decay + Nuclide ZAI : 380970 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 96.92615 + Atomic weight ratio (AWR) : 96.09350 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.429 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 4 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 4 decay reactions: + + 1 RTYP = 1 Q = 7.47000E+00 MeV frac = 8.50774E-01 Product nuclide = 390970 : beta- + 2 RTYP = 1 Q = 6.80249E+00 MeV frac = 1.48726E-01 Product nuclide = 390971 : beta- + 3 RTYP = 15 Q = 1.48770E+00 MeV frac = 2.50000E-04 Product nuclide = 390960 : beta- + neutron emission + 4 RTYP = 15 Q = 3.47698E-01 MeV frac = 2.50000E-04 Product nuclide = 390961 : beta- + neutron emission + + Nuclide 738 / 1657 : 380980 -- strontium 98 (Sr-98) + + Pointers : 640635 -1000000 + Primary type : Decay + Nuclide ZAI : 380980 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 97.92846 + Atomic weight ratio (AWR) : 97.08720 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.653 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.82300E+00 MeV frac = 1.00000E+00 Product nuclide = 390980 : beta- + + Nuclide 739 / 1657 : 380990 -- strontium 99 (Sr-99) + + Pointers : 642406 -1000000 + Primary type : Decay + Nuclide ZAI : 380990 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 98.93319 + Atomic weight ratio (AWR) : 98.08330 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.27 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.53000E+00 MeV frac = 1.00000E+00 Product nuclide = 390990 : beta- + + Nuclide 740 / 1657 : 381000 -- strontium 100 (Sr-100) + + Pointers : 644555 -1000000 + Primary type : Decay + Nuclide ZAI : 381000 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 99.93540 + Atomic weight ratio (AWR) : 99.07690 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.202 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 7.07000E+00 MeV frac = 9.92200E-01 Product nuclide = 391000 : beta- + 2 RTYP = 15 Q = 1.90970E+00 MeV frac = 7.80000E-03 Product nuclide = 390990 : beta- + neutron emission + + Nuclide 741 / 1657 : 381010 -- strontium 101 (Sr-101) + + Pointers : 644812 -1000000 + Primary type : Decay + Nuclide ZAI : 381010 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 100.94013 + Atomic weight ratio (AWR) : 100.07300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.118 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 1 Q = 9.50000E+00 MeV frac = 9.76300E-01 Product nuclide = 391010 : beta- + 2 RTYP = 15 Q = 3.80870E+00 MeV frac = 1.18500E-02 Product nuclide = 391000 : beta- + neutron emission + 3 RTYP = 15 Q = 3.60870E+00 MeV frac = 1.18500E-02 Product nuclide = 391001 : beta- + neutron emission + + Nuclide 742 / 1657 : 381020 -- strontium 102 (Sr-102) + + Pointers : 645142 -1000000 + Primary type : Decay + Nuclide ZAI : 381020 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 101.94274 + Atomic weight ratio (AWR) : 101.06700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 69 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 1 Q = 8.81000E+00 MeV frac = 4.72500E-01 Product nuclide = 391020 : beta- + 2 RTYP = 1 Q = 8.61000E+00 MeV frac = 4.72500E-01 Product nuclide = 391021 : beta- + 3 RTYP = 15 Q = 3.75870E+00 MeV frac = 5.50000E-02 Product nuclide = 391010 : beta- + neutron emission + + Nuclide 743 / 1657 : 381030 -- strontium 103 (Sr-103) + + Pointers : 645472 -1000000 + Primary type : Decay + Nuclide ZAI : 381030 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 102.94939 + Atomic weight ratio (AWR) : 102.06500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 50 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.13900E+01 MeV frac = 1.00000E+00 Product nuclide = 391030 : beta- + + Nuclide 744 / 1657 : 381040 -- strontium 104 (Sr-104) + + Pointers : 645656 -1000000 + Primary type : Decay + Nuclide ZAI : 381040 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 103.95200 + Atomic weight ratio (AWR) : 103.05900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 30 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.05100E+01 MeV frac = 1.00000E+00 Product nuclide = 391040 : beta- + + Nuclide 745 / 1657 : 390880 -- yttrium 88 (Y-88) + + Pointers : 645840 -1000000 + Primary type : Decay + Nuclide ZAI : 390880 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 87.90949 + Atomic weight ratio (AWR) : 87.15430 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.21E+06 seconds (107 days) + Specific ingestion toxicity : 1.30E-09 Sv/Bq + Specific inhalation toxicity : 4.40E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 3.62260E+00 MeV frac = 1.00000E+00 Product nuclide = 38088.82c : EC/beta+ + + Nuclide 746 / 1657 : 390881 -- yttrium 88m (Y-88m) + + Pointers : 646645 -1000000 + Primary type : Decay + Nuclide ZAI : 390881 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 87.90949 + Atomic weight ratio (AWR) : 87.15430 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 13.9 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 6.74550E-01 MeV frac = 1.00000E+00 Product nuclide = 390880 : IT + + Nuclide 747 / 1657 : 390891 -- yttrium 89m (Y-89m) + + Pointers : 656449 -1000000 + Primary type : Decay + Nuclide ZAI : 390891 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 88.90585 + Atomic weight ratio (AWR) : 88.14210 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 15.7 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 9.08960E-01 MeV frac = 1.00000E+00 Product nuclide = 39089.82c : IT + + Nuclide 748 / 1657 : 390901 -- yttrium 90m (Y-90m) + + Pointers : 659049 -1000000 + Primary type : Decay + Nuclide ZAI : 390901 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 89.90715 + Atomic weight ratio (AWR) : 89.13480 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.15E+04 seconds (3.19 hours) + Specific ingestion toxicity : 1.70E-10 Sv/Bq + Specific inhalation toxicity : 1.00E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 6.82040E-01 MeV frac = 9.99979E-01 Product nuclide = 39090.82c : IT + + Nuclide 749 / 1657 : 390911 -- yttrium 91m (Y-91m) + + Pointers : 661765 -1000000 + Primary type : Decay + Nuclide ZAI : 390911 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 90.90734 + Atomic weight ratio (AWR) : 90.12640 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.98E+03 seconds (49.7 minutes) + Specific ingestion toxicity : 1.10E-11 Sv/Bq + Specific inhalation toxicity : 1.10E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 5.55570E-01 MeV frac = 1.00000E+00 Product nuclide = 39091.82c : IT + + Nuclide 750 / 1657 : 390920 -- yttrium 92 (Y-92) + + Pointers : 662136 -1000000 + Primary type : Decay + Nuclide ZAI : 390920 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 91.90895 + Atomic weight ratio (AWR) : 91.11940 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.27E+04 seconds (3.54 hours) + Specific ingestion toxicity : 4.90E-10 Sv/Bq + Specific inhalation toxicity : 1.80E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.63900E+00 MeV frac = 1.00000E+00 Product nuclide = 40092.82c : beta- + + Nuclide 751 / 1657 : 390930 -- yttrium 93 (Y-93) + + Pointers : 662941 -1000000 + Primary type : Decay + Nuclide ZAI : 390930 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 92.90954 + Atomic weight ratio (AWR) : 92.11140 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.66E+04 seconds (10.2 hours) + Specific ingestion toxicity : 1.20E-09 Sv/Bq + Specific inhalation toxicity : 4.20E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.89500E+00 MeV frac = 1.00000E+00 Product nuclide = 40093.82c : beta- + + Nuclide 752 / 1657 : 390931 -- yttrium 93m (Y-93m) + + Pointers : 663872 -1000000 + Primary type : Decay + Nuclide ZAI : 390931 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 92.90954 + Atomic weight ratio (AWR) : 92.11140 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.82 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 7.58739E-01 MeV frac = 1.00000E+00 Product nuclide = 390930 : IT + + Nuclide 753 / 1657 : 390940 -- yttrium 94 (Y-94) + + Pointers : 664313 -1000000 + Primary type : Decay + Nuclide ZAI : 390940 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 93.91155 + Atomic weight ratio (AWR) : 93.10480 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.12E+03 seconds (18.7 minutes) + Specific ingestion toxicity : 8.10E-11 Sv/Bq + Specific inhalation toxicity : 2.80E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.91800E+00 MeV frac = 1.00000E+00 Product nuclide = 40094.82c : beta- + + Nuclide 754 / 1657 : 390950 -- yttrium 95 (Y-95) + + Pointers : 665720 -1000000 + Primary type : Decay + Nuclide ZAI : 390950 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 94.91285 + Atomic weight ratio (AWR) : 94.09750 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.18E+02 seconds (10.3 minutes) + Specific ingestion toxicity : 4.60E-11 Sv/Bq + Specific inhalation toxicity : 1.60E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.45000E+00 MeV frac = 1.00000E+00 Product nuclide = 40095.82c : beta- + + Nuclide 755 / 1657 : 390960 -- yttrium 96 (Y-96) + + Pointers : 666973 -1000000 + Primary type : Decay + Nuclide ZAI : 390960 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 95.91587 + Atomic weight ratio (AWR) : 95.09190 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.34 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.09600E+00 MeV frac = 1.00000E+00 Product nuclide = 40096.82c : beta- + + Nuclide 756 / 1657 : 390961 -- yttrium 96m (Y-96m) + + Pointers : 669360 -1000000 + Primary type : Decay + Nuclide ZAI : 390961 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 95.91587 + Atomic weight ratio (AWR) : 95.09190 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.62 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.70000E+00 MeV frac = 1.00000E+00 Product nuclide = 40096.82c : beta- + + Nuclide 757 / 1657 : 390970 -- yttrium 97 (Y-97) + + Pointers : 672335 -1000000 + Primary type : Decay + Nuclide ZAI : 390970 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 96.91818 + Atomic weight ratio (AWR) : 96.08560 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.75 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 6.68900E+00 MeV frac = 9.99450E-01 Product nuclide = 400970 : beta- + 2 RTYP = 15 Q = 1.11400E+00 MeV frac = 5.50000E-04 Product nuclide = 40096.82c : beta- + neutron emission + + Nuclide 758 / 1657 : 390971 -- yttrium 97m (Y-97m) + + Pointers : 673661 -1000000 + Primary type : Decay + Nuclide ZAI : 390971 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 96.91818 + Atomic weight ratio (AWR) : 96.08560 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.17 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 1 Q = 7.35700E+00 MeV frac = 9.92500E-01 Product nuclide = 400970 : beta- + 2 RTYP = 3 Q = 6.67500E-01 MeV frac = 7.00000E-03 Product nuclide = 390970 : IT + 3 RTYP = 15 Q = 1.78200E+00 MeV frac = 5.00000E-04 Product nuclide = 40096.82c : beta- + neutron emission + + Nuclide 759 / 1657 : 390972 -- yttrium 97m (Y-97m) + + Pointers : 3506583 -1000000 + Primary type : Decay + Nuclide ZAI : 390972 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 96.91818 + Atomic weight ratio (AWR) : 96.08560 + Temperature : 900.0 Kelvin + XS temperature : -1.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.142 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is not present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.02120E+01 MeV frac = 1.60000E-02 Product nuclide = 400970 : beta- + 2 RTYP = 3 Q = 2.85580E+00 MeV frac = 9.84000E-01 Product nuclide = 390971 : IT + + Nuclide 760 / 1657 : 390980 -- yttrium 98 (Y-98) + + Pointers : 676194 -1000000 + Primary type : Decay + Nuclide ZAI : 390980 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 97.92220 + Atomic weight ratio (AWR) : 97.08100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.59 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.82400E+00 MeV frac = 9.97300E-01 Product nuclide = 400980 : beta- + 2 RTYP = 15 Q = 2.42600E+00 MeV frac = 2.70000E-03 Product nuclide = 400970 : beta- + neutron emission + + Nuclide 761 / 1657 : 390981 -- yttrium 98m (Y-98m) + + Pointers : 678700 -1000000 + Primary type : Decay + Nuclide ZAI : 390981 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 97.92220 + Atomic weight ratio (AWR) : 97.08100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 9.80000E+00 MeV frac = 9.65600E-01 Product nuclide = 400980 : beta- + 2 RTYP = 15 Q = 3.42600E+00 MeV frac = 3.44000E-02 Product nuclide = 400970 : beta- + neutron emission + + Nuclide 762 / 1657 : 390990 -- yttrium 99 (Y-99) + + Pointers : 681408 -1000000 + Primary type : Decay + Nuclide ZAI : 390990 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 98.92461 + Atomic weight ratio (AWR) : 98.07480 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.48 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 7.56700E+00 MeV frac = 9.83000E-01 Product nuclide = 400990 : beta- + 2 RTYP = 15 Q = 3.09000E+00 MeV frac = 1.70000E-02 Product nuclide = 400980 : beta- + neutron emission + + Nuclide 763 / 1657 : 391000 -- yttrium 100 (Y-100) + + Pointers : 687906 -1000000 + Primary type : Decay + Nuclide ZAI : 391000 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 99.92773 + Atomic weight ratio (AWR) : 99.06930 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.735 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 9.31001E+00 MeV frac = 9.90800E-01 Product nuclide = 401000 : beta- + 2 RTYP = 15 Q = 2.40670E+00 MeV frac = 9.20000E-03 Product nuclide = 400990 : beta- + neutron emission + + Nuclide 764 / 1657 : 391001 -- yttrium 100m (Y-100m) + + Pointers : 688163 -1000000 + Primary type : Decay + Nuclide ZAI : 391001 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 99.92773 + Atomic weight ratio (AWR) : 99.06930 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.94 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.51001E+00 MeV frac = 1.00000E+00 Product nuclide = 401000 : beta- + + Nuclide 765 / 1657 : 391010 -- yttrium 101 (Y-101) + + Pointers : 688347 -1000000 + Primary type : Decay + Nuclide ZAI : 391010 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 100.93004 + Atomic weight ratio (AWR) : 100.06300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.45 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.54500E+00 MeV frac = 1.00000E+00 Product nuclide = 401010 : beta- + + Nuclide 766 / 1657 : 391020 -- yttrium 102 (Y-102) + + Pointers : 690356 -1000000 + Primary type : Decay + Nuclide ZAI : 391020 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 101.93366 + Atomic weight ratio (AWR) : 101.05800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 9.85000E+00 MeV frac = 9.51000E-01 Product nuclide = 401020 : beta- + 2 RTYP = 15 Q = 3.49870E+00 MeV frac = 4.90000E-02 Product nuclide = 401010 : beta- + neutron emission + + Nuclide 767 / 1657 : 391021 -- yttrium 102m (Y-102m) + + Pointers : 690613 -1000000 + Primary type : Decay + Nuclide ZAI : 391021 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 101.93366 + Atomic weight ratio (AWR) : 101.05800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.36 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.00500E+01 MeV frac = 9.51000E-01 Product nuclide = 401020 : beta- + 2 RTYP = 15 Q = 3.69870E+00 MeV frac = 4.90000E-02 Product nuclide = 401010 : beta- + neutron emission + + Nuclide 768 / 1657 : 391030 -- yttrium 103 (Y-103) + + Pointers : 690870 -1000000 + Primary type : Decay + Nuclide ZAI : 391030 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 102.93628 + Atomic weight ratio (AWR) : 102.05200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.224 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 9.43000E+00 MeV frac = 9.20000E-01 Product nuclide = 401030 : beta- + 2 RTYP = 15 Q = 4.72870E+00 MeV frac = 8.00000E-02 Product nuclide = 401020 : beta- + neutron emission + + Nuclide 769 / 1657 : 391040 -- yttrium 104 (Y-104) + + Pointers : 691127 -1000000 + Primary type : Decay + Nuclide ZAI : 391040 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 103.94091 + Atomic weight ratio (AWR) : 103.04800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.13 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.27370E+01 MeV frac = 9.12230E-01 Product nuclide = 401040 : beta- + 2 RTYP = 15 Q = 5.50800E+00 MeV frac = 8.77690E-02 Product nuclide = 401030 : beta- + neutron emission + + Nuclide 770 / 1657 : 391050 -- yttrium 105 (Y-105) + + Pointers : 700614 -1000000 + Primary type : Decay + Nuclide ZAI : 391050 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 104.94352 + Atomic weight ratio (AWR) : 104.04200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.15 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.08350E+01 MeV frac = 8.02470E-01 Product nuclide = 401050 : beta- + 2 RTYP = 15 Q = 6.83900E+00 MeV frac = 1.97530E-01 Product nuclide = 401040 : beta- + neutron emission + + Nuclide 771 / 1657 : 391060 -- yttrium 106 (Y-106) + + Pointers : 709357 -1000000 + Primary type : Decay + Nuclide ZAI : 391060 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 105.95017 + Atomic weight ratio (AWR) : 105.04000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 50 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.29300E+01 MeV frac = 1.00000E+00 Product nuclide = 401060 : beta- + + Nuclide 772 / 1657 : 391070 -- yttrium 107 (Y-107) + + Pointers : 709541 -1000000 + Primary type : Decay + Nuclide ZAI : 391070 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 106.95379 + Atomic weight ratio (AWR) : 106.03500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 30 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.24700E+01 MeV frac = 1.00000E+00 Product nuclide = 401070 : beta- + + Nuclide 773 / 1657 : 400880 -- zirconium 88 (Zr-88) + + Pointers : 709725 -1000000 + Primary type : Decay + Nuclide ZAI : 400880 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 87.91020 + Atomic weight ratio (AWR) : 87.15500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.21E+06 seconds (83.4 days) + Specific ingestion toxicity : 4.50E-10 Sv/Bq + Specific inhalation toxicity : 3.60E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 6.68000E-01 MeV frac = 1.00000E+00 Product nuclide = 390880 : EC/beta+ + + Nuclide 774 / 1657 : 400890 -- zirconium 89 (Zr-89) + + Pointers : 710124 -1000000 + Primary type : Decay + Nuclide ZAI : 400890 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 88.90887 + Atomic weight ratio (AWR) : 88.14510 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.82E+05 seconds (3.27 days) + Specific ingestion toxicity : 7.90E-10 Sv/Bq + Specific inhalation toxicity : 5.50E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 2.83280E+00 MeV frac = 1.22965E-03 Product nuclide = 39089.82c : EC/beta+ + 2 RTYP = 2 Q = 1.92383E+00 MeV frac = 9.98770E-01 Product nuclide = 390891 : EC/beta+ + + Nuclide 775 / 1657 : 400901 -- zirconium 90m (Zr-90m) + + Pointers : 713363 -1000000 + Primary type : Decay + Nuclide ZAI : 400901 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 89.90473 + Atomic weight ratio (AWR) : 89.13240 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.808 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 2.31900E+00 MeV frac = 1.00000E+00 Product nuclide = 40090.82c : IT + + Nuclide 776 / 1657 : 400970 -- zirconium 97 (Zr-97) + + Pointers : 732830 -1000000 + Primary type : Decay + Nuclide ZAI : 400970 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 96.91092 + Atomic weight ratio (AWR) : 96.07840 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.03E+04 seconds (16.7 hours) + Specific ingestion toxicity : 2.10E-09 Sv/Bq + Specific inhalation toxicity : 8.90E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 2.65830E+00 MeV frac = 4.95212E-02 Product nuclide = 410970 : beta- + 2 RTYP = 1 Q = 1.91495E+00 MeV frac = 9.50479E-01 Product nuclide = 410971 : beta- + + Nuclide 777 / 1657 : 400980 -- zirconium 98 (Zr-98) + + Pointers : 733848 -1000000 + Primary type : Decay + Nuclide ZAI : 400980 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 97.91272 + Atomic weight ratio (AWR) : 97.07160 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 30.7 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.25000E+00 MeV frac = 1.00000E+00 Product nuclide = 410980 : beta- + + Nuclide 778 / 1657 : 400990 -- zirconium 99 (Zr-99) + + Pointers : 734065 -1000000 + Primary type : Decay + Nuclide ZAI : 400990 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 98.91655 + Atomic weight ratio (AWR) : 98.06680 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 4.19300E+00 MeV frac = 3.68000E-01 Product nuclide = 410991 : beta- + 2 RTYP = 1 Q = 4.55800E+00 MeV frac = 6.32000E-01 Product nuclide = 410990 : beta- + + Nuclide 779 / 1657 : 401000 -- zirconium 100 (Zr-100) + + Pointers : 735307 -1000000 + Primary type : Decay + Nuclide ZAI : 401000 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 99.91775 + Atomic weight ratio (AWR) : 99.05940 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.1 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.42600E+00 MeV frac = 1.00000E+00 Product nuclide = 411000 : beta- + + Nuclide 780 / 1657 : 401010 -- zirconium 101 (Zr-101) + + Pointers : 735748 -1000000 + Primary type : Decay + Nuclide ZAI : 401010 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 100.92096 + Atomic weight ratio (AWR) : 100.05400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.48500E+00 MeV frac = 1.00000E+00 Product nuclide = 411010 : beta- + + Nuclide 781 / 1657 : 401020 -- zirconium 102 (Zr-102) + + Pointers : 737911 -1000000 + Primary type : Decay + Nuclide ZAI : 401020 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 101.92257 + Atomic weight ratio (AWR) : 101.04700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.9 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.62600E+00 MeV frac = 1.00000E+00 Product nuclide = 411020 : beta- + + Nuclide 782 / 1657 : 401030 -- zirconium 103 (Zr-103) + + Pointers : 738702 -1000000 + Primary type : Decay + Nuclide ZAI : 401030 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 102.92619 + Atomic weight ratio (AWR) : 102.04200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.95001E+00 MeV frac = 1.00000E+00 Product nuclide = 411030 : beta- + + Nuclide 783 / 1657 : 401040 -- zirconium 104 (Zr-104) + + Pointers : 738886 -1000000 + Primary type : Decay + Nuclide ZAI : 401040 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 103.92880 + Atomic weight ratio (AWR) : 103.03600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.88000E+00 MeV frac = 1.00000E+00 Product nuclide = 411040 : beta- + + Nuclide 784 / 1657 : 401050 -- zirconium 105 (Zr-105) + + Pointers : 739070 -1000000 + Primary type : Decay + Nuclide ZAI : 401050 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 104.93243 + Atomic weight ratio (AWR) : 104.03100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.6 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.30060E+00 MeV frac = 9.86000E-01 Product nuclide = 411050 : beta- + 2 RTYP = 15 Q = 1.79400E+00 MeV frac = 1.40000E-02 Product nuclide = 411040 : beta- + neutron emission + + Nuclide 785 / 1657 : 401060 -- zirconium 106 (Zr-106) + + Pointers : 744783 -1000000 + Primary type : Decay + Nuclide ZAI : 401060 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 105.93504 + Atomic weight ratio (AWR) : 105.02500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.9 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 6.39860E+00 MeV frac = 9.84760E-01 Product nuclide = 411060 : beta- + 2 RTYP = 15 Q = 2.56300E+00 MeV frac = 1.52420E-02 Product nuclide = 411050 : beta- + neutron emission + + Nuclide 786 / 1657 : 401070 -- zirconium 107 (Zr-107) + + Pointers : 749581 -1000000 + Primary type : Decay + Nuclide ZAI : 401070 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 106.94068 + Atomic weight ratio (AWR) : 106.02200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.24 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 9.24790E+00 MeV frac = 9.62870E-01 Product nuclide = 411070 : beta- + 2 RTYP = 15 Q = 3.96900E+00 MeV frac = 3.71270E-02 Product nuclide = 411060 : beta- + neutron emission + + Nuclide 787 / 1657 : 401080 -- zirconium 108 (Zr-108) + + Pointers : 756509 -1000000 + Primary type : Decay + Nuclide ZAI : 401080 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 107.94430 + Atomic weight ratio (AWR) : 107.01700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 80 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 411080 : beta- + + Nuclide 788 / 1657 : 401090 -- zirconium 109 (Zr-109) + + Pointers : 756693 -1000000 + Primary type : Decay + Nuclide ZAI : 401090 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 108.94893 + Atomic weight ratio (AWR) : 108.01300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 60 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.08200E+01 MeV frac = 1.00000E+00 Product nuclide = 411090 : beta- + + Nuclide 789 / 1657 : 410900 -- niobium 90 (Nb-90) + + Pointers : 756877 -1000000 + Primary type : Decay + Nuclide ZAI : 410900 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 89.91129 + Atomic weight ratio (AWR) : 89.13890 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.25E+04 seconds (14.6 hours) + Specific ingestion toxicity : 1.20E-09 Sv/Bq + Specific inhalation toxicity : 6.60E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 3.79200E+00 MeV frac = 9.81000E-01 Product nuclide = 400901 : EC/beta+ + 2 RTYP = 2 Q = 6.11100E+00 MeV frac = 1.90000E-02 Product nuclide = 40090.82c : EC/beta+ + + Nuclide 790 / 1657 : 410910 -- niobium 91 (Nb-91) + + Pointers : 758357 -1000000 + Primary type : Decay + Nuclide ZAI : 410910 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 90.90704 + Atomic weight ratio (AWR) : 90.12610 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.15E+10 seconds (680 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 1.25460E+00 MeV frac = 1.00000E+00 Product nuclide = 40091.82c : EC/beta+ + + Nuclide 791 / 1657 : 410911 -- niobium 91m (Nb-91m) + + Pointers : 758714 -1000000 + Primary type : Decay + Nuclide ZAI : 410911 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 90.90704 + Atomic weight ratio (AWR) : 90.12610 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.26E+06 seconds (60.9 days) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 1.04490E-01 MeV frac = 9.76000E-01 Product nuclide = 410910 : IT + 2 RTYP = 2 Q = 1.35910E+00 MeV frac = 2.40000E-02 Product nuclide = 40091.82c : EC/beta+ + + Nuclide 792 / 1657 : 410920 -- niobium 92 (Nb-92) + + Pointers : 759326 -1000000 + Primary type : Decay + Nuclide ZAI : 410920 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 91.90723 + Atomic weight ratio (AWR) : 91.11770 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.10E+15 seconds (35 million years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 2.00590E+00 MeV frac = 1.00000E+00 Product nuclide = 40092.82c : EC/beta+ + + Nuclide 793 / 1657 : 410931 -- niobium 93m (Nb-93m) + + Pointers : 763707 -1000000 + Primary type : Decay + Nuclide ZAI : 410931 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 92.90642 + Atomic weight ratio (AWR) : 92.10830 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.09E+08 seconds (16.1 years) + Specific ingestion toxicity : 1.20E-10 Sv/Bq + Specific inhalation toxicity : 1.80E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 3.08200E-02 MeV frac = 1.00000E+00 Product nuclide = 41093.82c : IT + + Nuclide 794 / 1657 : 410941 -- niobium 94m (Nb-94m) + + Pointers : 768974 -1000000 + Primary type : Decay + Nuclide ZAI : 410941 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 93.90731 + Atomic weight ratio (AWR) : 93.10060 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.76E+02 seconds (6.26 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 2.08630E+00 MeV frac = 5.00000E-03 Product nuclide = 42094.82c : beta- + 2 RTYP = 3 Q = 4.09500E-02 MeV frac = 9.95000E-01 Product nuclide = 41094.82c : IT + + Nuclide 795 / 1657 : 410951 -- niobium 95m (Nb-95m) + + Pointers : 773761 -1000000 + Primary type : Decay + Nuclide ZAI : 410951 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 94.90680 + Atomic weight ratio (AWR) : 94.09150 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.12E+05 seconds (3.61 days) + Specific ingestion toxicity : 5.60E-10 Sv/Bq + Specific inhalation toxicity : 8.80E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 2.35690E-01 MeV frac = 9.75000E-01 Product nuclide = 41095.82c : IT + 2 RTYP = 1 Q = 1.16129E+00 MeV frac = 2.50000E-02 Product nuclide = 42095.82c : beta- + + Nuclide 796 / 1657 : 410960 -- niobium 96 (Nb-96) + + Pointers : 774415 -1000000 + Primary type : Decay + Nuclide ZAI : 410960 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 95.90810 + Atomic weight ratio (AWR) : 95.08420 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.41E+04 seconds (23.3 hours) + Specific ingestion toxicity : 1.10E-09 Sv/Bq + Specific inhalation toxicity : 6.60E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.18700E+00 MeV frac = 1.00000E+00 Product nuclide = 42096.82c : beta- + + Nuclide 797 / 1657 : 410970 -- niobium 97 (Nb-97) + + Pointers : 776676 -1000000 + Primary type : Decay + Nuclide ZAI : 410970 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 96.90809 + Atomic weight ratio (AWR) : 96.07560 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.33E+03 seconds (1.2 hours) + Specific ingestion toxicity : 6.80E-11 Sv/Bq + Specific inhalation toxicity : 4.50E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.93480E+00 MeV frac = 1.00000E+00 Product nuclide = 42097.82c : beta- + + Nuclide 798 / 1657 : 410971 -- niobium 97m (Nb-97m) + + Pointers : 777271 -1000000 + Primary type : Decay + Nuclide ZAI : 410971 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 96.90809 + Atomic weight ratio (AWR) : 96.07560 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 52.7 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 7.43400E-01 MeV frac = 1.00000E+00 Product nuclide = 410970 : IT + + Nuclide 799 / 1657 : 410980 -- niobium 98 (Nb-98) + + Pointers : 777614 -1000000 + Primary type : Decay + Nuclide ZAI : 410980 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 97.91030 + Atomic weight ratio (AWR) : 97.06920 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.86 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.58600E+00 MeV frac = 1.00000E+00 Product nuclide = 42098.82c : beta- + + Nuclide 800 / 1657 : 410981 -- niobium 98m (Nb-98m) + + Pointers : 778195 -1000000 + Primary type : Decay + Nuclide ZAI : 410981 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 97.91030 + Atomic weight ratio (AWR) : 97.06920 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.08E+03 seconds (51.3 minutes) + Specific ingestion toxicity : 1.10E-10 Sv/Bq + Specific inhalation toxicity : 5.80E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.67000E+00 MeV frac = 1.00000E+00 Product nuclide = 42098.82c : beta- + + Nuclide 801 / 1657 : 410990 -- niobium 99 (Nb-99) + + Pointers : 782626 -1000000 + Primary type : Decay + Nuclide ZAI : 410990 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 98.91160 + Atomic weight ratio (AWR) : 98.06190 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 15 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.63900E+00 MeV frac = 1.00000E+00 Product nuclide = 42099.82c : beta- + + Nuclide 802 / 1657 : 410991 -- niobium 99m (Nb-99m) + + Pointers : 785993 -1000000 + Primary type : Decay + Nuclide ZAI : 410991 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 98.91160 + Atomic weight ratio (AWR) : 98.06190 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.56E+02 seconds (2.6 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 4.00420E+00 MeV frac = 9.80000E-01 Product nuclide = 42099.82c : beta- + 2 RTYP = 3 Q = 3.65290E-01 MeV frac = 2.00000E-02 Product nuclide = 410990 : IT + + Nuclide 803 / 1657 : 411000 -- niobium 100 (Nb-100) + + Pointers : 788719 -1000000 + Primary type : Decay + Nuclide ZAI : 411000 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 99.91422 + Atomic weight ratio (AWR) : 99.05590 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.38400E+00 MeV frac = 1.00000E+00 Product nuclide = 42100.82c : beta- + + Nuclide 804 / 1657 : 411001 -- niobium 100m (Nb-100m) + + Pointers : 790476 -1000000 + Primary type : Decay + Nuclide ZAI : 411001 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 99.91422 + Atomic weight ratio (AWR) : 99.05590 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.9 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.72500E+00 MeV frac = 1.00000E+00 Product nuclide = 42100.82c : beta- + + Nuclide 805 / 1657 : 411010 -- niobium 101 (Nb-101) + + Pointers : 792149 -1000000 + Primary type : Decay + Nuclide ZAI : 411010 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 100.91491 + Atomic weight ratio (AWR) : 100.04800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.1 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.56900E+00 MeV frac = 1.00000E+00 Product nuclide = 421010 : beta- + + Nuclide 806 / 1657 : 411020 -- niobium 102 (Nb-102) + + Pointers : 793556 -1000000 + Primary type : Decay + Nuclide ZAI : 411020 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 101.91853 + Atomic weight ratio (AWR) : 101.04300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.20700E+00 MeV frac = 1.00000E+00 Product nuclide = 421020 : beta- + + Nuclide 807 / 1657 : 411021 -- niobium 102m (Nb-102m) + + Pointers : 793740 -1000000 + Primary type : Decay + Nuclide ZAI : 411021 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 101.91853 + Atomic weight ratio (AWR) : 101.04300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.34000E+00 MeV frac = 1.00000E+00 Product nuclide = 421020 : beta- + + Nuclide 808 / 1657 : 411030 -- niobium 103 (Nb-103) + + Pointers : 794531 -1000000 + Primary type : Decay + Nuclide ZAI : 411030 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 102.91913 + Atomic weight ratio (AWR) : 102.03500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.53000E+00 MeV frac = 1.00000E+00 Product nuclide = 421030 : beta- + + Nuclide 809 / 1657 : 411040 -- niobium 104 (Nb-104) + + Pointers : 794715 -1000000 + Primary type : Decay + Nuclide ZAI : 411040 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 103.92275 + Atomic weight ratio (AWR) : 103.03000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.9 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.11000E+00 MeV frac = 9.99400E-01 Product nuclide = 421040 : beta- + 2 RTYP = 15 Q = 5.58705E-01 MeV frac = 6.00000E-04 Product nuclide = 421030 : beta- + neutron emission + + Nuclide 810 / 1657 : 411041 -- niobium 104m (Nb-104m) + + Pointers : 794972 -1000000 + Primary type : Decay + Nuclide ZAI : 411041 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 103.92275 + Atomic weight ratio (AWR) : 103.03000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.94 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.33000E+00 MeV frac = 9.99500E-01 Product nuclide = 421040 : beta- + 2 RTYP = 15 Q = 7.78705E-01 MeV frac = 5.00000E-04 Product nuclide = 421030 : beta- + neutron emission + + Nuclide 811 / 1657 : 411050 -- niobium 105 (Nb-105) + + Pointers : 795229 -1000000 + Primary type : Decay + Nuclide ZAI : 411050 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 104.92436 + Atomic weight ratio (AWR) : 104.02300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.95 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 6.49000E+00 MeV frac = 9.83000E-01 Product nuclide = 421050 : beta- + 2 RTYP = 15 Q = 1.40870E+00 MeV frac = 1.70000E-02 Product nuclide = 421040 : beta- + neutron emission + + Nuclide 812 / 1657 : 411060 -- niobium 106 (Nb-106) + + Pointers : 795486 -1000000 + Primary type : Decay + Nuclide ZAI : 411060 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 105.92798 + Atomic weight ratio (AWR) : 105.01800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.92 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 9.15500E+00 MeV frac = 9.55000E-01 Product nuclide = 421060 : beta- + 2 RTYP = 15 Q = 2.16870E+00 MeV frac = 4.50000E-02 Product nuclide = 421050 : beta- + neutron emission + + Nuclide 813 / 1657 : 411070 -- niobium 107 (Nb-107) + + Pointers : 795743 -1000000 + Primary type : Decay + Nuclide ZAI : 411070 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 106.93059 + Atomic weight ratio (AWR) : 106.01200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.02000E+00 MeV frac = 9.40000E-01 Product nuclide = 421070 : beta- + 2 RTYP = 15 Q = 3.26370E+00 MeV frac = 6.00000E-02 Product nuclide = 421060 : beta- + neutron emission + + Nuclide 814 / 1657 : 411080 -- niobium 108 (Nb-108) + + Pointers : 796000 -1000000 + Primary type : Decay + Nuclide ZAI : 411080 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 107.93522 + Atomic weight ratio (AWR) : 107.00800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.193 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.06000E+01 MeV frac = 9.38000E-01 Product nuclide = 421080 : beta- + 2 RTYP = 15 Q = 4.16870E+00 MeV frac = 6.20000E-02 Product nuclide = 421070 : beta- + neutron emission + + Nuclide 815 / 1657 : 411090 -- niobium 109 (Nb-109) + + Pointers : 796257 -1000000 + Primary type : Decay + Nuclide ZAI : 411090 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 108.93783 + Atomic weight ratio (AWR) : 108.00200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.19 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.77730E+00 MeV frac = 8.73470E-01 Product nuclide = 421090 : beta- + 2 RTYP = 15 Q = 5.30900E+00 MeV frac = 1.26530E-01 Product nuclide = 421080 : beta- + neutron emission + + Nuclide 816 / 1657 : 411100 -- niobium 110 (Nb-110) + + Pointers : 803305 -1000000 + Primary type : Decay + Nuclide ZAI : 411100 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 109.94246 + Atomic weight ratio (AWR) : 108.99800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.17 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.18400E+01 MeV frac = 6.00000E-01 Product nuclide = 421100 : beta- + 2 RTYP = 15 Q = 5.55870E+00 MeV frac = 4.00000E-01 Product nuclide = 421090 : beta- + neutron emission + + Nuclide 817 / 1657 : 411110 -- niobium 111 (Nb-111) + + Pointers : 803562 -1000000 + Primary type : Decay + Nuclide ZAI : 411110 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 110.94609 + Atomic weight ratio (AWR) : 109.99300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 80 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.04700E+01 MeV frac = 1.00000E+00 Product nuclide = 421110 : beta- + + Nuclide 818 / 1657 : 411120 -- niobium 112 (Nb-112) + + Pointers : 803746 -1000000 + Primary type : Decay + Nuclide ZAI : 411120 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 111.95072 + Atomic weight ratio (AWR) : 110.98900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 60 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.30300E+01 MeV frac = 1.00000E+00 Product nuclide = 421120 : beta- + + Nuclide 819 / 1657 : 420910 -- molybdenum 91 (Mo-91) + + Pointers : 803930 -1000000 + Primary type : Decay + Nuclide ZAI : 420910 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 90.91178 + Atomic weight ratio (AWR) : 90.13080 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.29E+02 seconds (15.5 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 4.43000E+00 MeV frac = 9.99658E-01 Product nuclide = 410910 : EC/beta+ + 2 RTYP = 2 Q = 4.32539E+00 MeV frac = 3.42163E-04 Product nuclide = 410911 : EC/beta+ + + Nuclide 820 / 1657 : 420930 -- molybdenum 93 (Mo-93) + + Pointers : 808279 -1000000 + Primary type : Decay + Nuclide ZAI : 420930 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 92.90682 + Atomic weight ratio (AWR) : 92.10870 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.50E+10 seconds (3,014 years) + Specific ingestion toxicity : 3.10E-09 Sv/Bq + Specific inhalation toxicity : 2.30E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 4.06000E-01 MeV frac = 1.50000E-01 Product nuclide = 41093.82c : EC/beta+ + 2 RTYP = 2 Q = 3.75000E-01 MeV frac = 8.50000E-01 Product nuclide = 410931 : EC/beta+ + + Nuclide 821 / 1657 : 420931 -- molybdenum 93m (Mo-93m) + + Pointers : 808695 -1000000 + Primary type : Decay + Nuclide ZAI : 420931 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 92.90682 + Atomic weight ratio (AWR) : 92.10870 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.47E+04 seconds (6.85 hours) + Specific ingestion toxicity : 1.10E-10 Sv/Bq + Specific inhalation toxicity : 1.70E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 2.83100E+00 MeV frac = 1.20000E-03 Product nuclide = 41093.82c : EC/beta+ + 2 RTYP = 3 Q = 2.42493E+00 MeV frac = 9.98800E-01 Product nuclide = 420930 : IT + + Nuclide 822 / 1657 : 421010 -- molybdenum 101 (Mo-101) + + Pointers : 831594 -1000000 + Primary type : Decay + Nuclide ZAI : 421010 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 100.90987 + Atomic weight ratio (AWR) : 100.04300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.77E+02 seconds (14.6 minutes) + Specific ingestion toxicity : 4.10E-11 Sv/Bq + Specific inhalation toxicity : 2.60E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.82400E+00 MeV frac = 1.00000E+00 Product nuclide = 431010 : beta- + + Nuclide 823 / 1657 : 421020 -- molybdenum 102 (Mo-102) + + Pointers : 834905 -1000000 + Primary type : Decay + Nuclide ZAI : 421020 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 101.91046 + Atomic weight ratio (AWR) : 101.03500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.78E+02 seconds (11.3 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.00800E+00 MeV frac = 1.00000E+00 Product nuclide = 431020 : beta- + + Nuclide 824 / 1657 : 421030 -- molybdenum 103 (Mo-103) + + Pointers : 835276 -1000000 + Primary type : Decay + Nuclide ZAI : 421030 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 102.91308 + Atomic weight ratio (AWR) : 102.02900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.79E+01 seconds (1.13 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.75000E+00 MeV frac = 1.00000E+00 Product nuclide = 431030 : beta- + + Nuclide 825 / 1657 : 421040 -- molybdenum 104 (Mo-104) + + Pointers : 837677 -1000000 + Primary type : Decay + Nuclide ZAI : 421040 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 103.91367 + Atomic weight ratio (AWR) : 103.02100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 60 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.16000E+00 MeV frac = 1.00000E+00 Product nuclide = 431040 : beta- + + Nuclide 826 / 1657 : 421050 -- molybdenum 105 (Mo-105) + + Pointers : 837861 -1000000 + Primary type : Decay + Nuclide ZAI : 421050 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 104.91730 + Atomic weight ratio (AWR) : 104.01600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 35.6 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.95000E+00 MeV frac = 1.00000E+00 Product nuclide = 431050 : beta- + + Nuclide 827 / 1657 : 421060 -- molybdenum 106 (Mo-106) + + Pointers : 841144 -1000000 + Primary type : Decay + Nuclide ZAI : 421060 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 105.91789 + Atomic weight ratio (AWR) : 105.00800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.73 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.52000E+00 MeV frac = 1.00000E+00 Product nuclide = 431060 : beta- + + Nuclide 828 / 1657 : 421070 -- molybdenum 107 (Mo-107) + + Pointers : 841328 -1000000 + Primary type : Decay + Nuclide ZAI : 421070 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 106.92151 + Atomic weight ratio (AWR) : 106.00300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.16000E+00 MeV frac = 1.00000E+00 Product nuclide = 431070 : beta- + + Nuclide 829 / 1657 : 421080 -- molybdenum 108 (Mo-108) + + Pointers : 841512 -1000000 + Primary type : Decay + Nuclide ZAI : 421080 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 107.92312 + Atomic weight ratio (AWR) : 106.99600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.09 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.65000E+00 MeV frac = 1.00000E+00 Product nuclide = 431080 : beta- + + Nuclide 830 / 1657 : 421090 -- molybdenum 109 (Mo-109) + + Pointers : 841696 -1000000 + Primary type : Decay + Nuclide ZAI : 421090 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 108.92775 + Atomic weight ratio (AWR) : 107.99200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 6.71570E+00 MeV frac = 9.94700E-01 Product nuclide = 431090 : beta- + 2 RTYP = 15 Q = 6.20000E-01 MeV frac = 5.30000E-03 Product nuclide = 431080 : beta- + neutron emission + + Nuclide 831 / 1657 : 421100 -- molybdenum 110 (Mo-110) + + Pointers : 846101 -1000000 + Primary type : Decay + Nuclide ZAI : 421100 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 109.92935 + Atomic weight ratio (AWR) : 108.98500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 431100 : beta- + + Nuclide 832 / 1657 : 421110 -- molybdenum 111 (Mo-111) + + Pointers : 846285 -1000000 + Primary type : Decay + Nuclide ZAI : 421110 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 110.93499 + Atomic weight ratio (AWR) : 109.98200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.03170E+00 MeV frac = 9.89700E-01 Product nuclide = 431110 : beta- + 2 RTYP = 15 Q = 2.22900E+00 MeV frac = 1.03030E-02 Product nuclide = 431100 : beta- + neutron emission + + Nuclide 833 / 1657 : 421120 -- molybdenum 112 (Mo-112) + + Pointers : 851965 -1000000 + Primary type : Decay + Nuclide ZAI : 421120 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 111.93760 + Atomic weight ratio (AWR) : 110.97600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 6.03210E+00 MeV frac = 9.79210E-01 Product nuclide = 431120 : beta- + 2 RTYP = 15 Q = 2.73900E+00 MeV frac = 2.07880E-02 Product nuclide = 431110 : beta- + neutron emission + + Nuclide 834 / 1657 : 421130 -- molybdenum 113 (Mo-113) + + Pointers : 856598 -1000000 + Primary type : Decay + Nuclide ZAI : 421130 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 112.94223 + Atomic weight ratio (AWR) : 111.97200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 100 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.58000E+00 MeV frac = 1.00000E+00 Product nuclide = 431130 : beta- + + Nuclide 835 / 1657 : 421140 -- molybdenum 114 (Mo-114) + + Pointers : 856782 -1000000 + Primary type : Decay + Nuclide ZAI : 421140 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 113.94485 + Atomic weight ratio (AWR) : 112.96600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 80 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.42000E+00 MeV frac = 1.00000E+00 Product nuclide = 431140 : beta- + + Nuclide 836 / 1657 : 421150 -- molybdenum 115 (Mo-115) + + Pointers : 856966 -1000000 + Primary type : Decay + Nuclide ZAI : 421150 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 114.95049 + Atomic weight ratio (AWR) : 113.96300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 60 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.08000E+01 MeV frac = 1.00000E+00 Product nuclide = 431150 : beta- + + Nuclide 837 / 1657 : 430970 -- technetium 97 (Tc-97) + + Pointers : 857150 -1000000 + Primary type : Decay + Nuclide ZAI : 430970 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 96.90638 + Atomic weight ratio (AWR) : 96.07390 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.20E+13 seconds (2.6 million years) + Specific ingestion toxicity : 6.80E-11 Sv/Bq + Specific inhalation toxicity : 1.80E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 3.20000E-01 MeV frac = 1.00000E+00 Product nuclide = 42097.82c : EC/beta+ + + Nuclide 838 / 1657 : 430980 -- technetium 98 (Tc-98) + + Pointers : 857493 -1000000 + Primary type : Decay + Nuclide ZAI : 430980 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 97.90728 + Atomic weight ratio (AWR) : 97.06620 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.36E+14 seconds (4.3 million years) + Specific ingestion toxicity : 2.00E-09 Sv/Bq + Specific inhalation toxicity : 4.50E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.79700E+00 MeV frac = 1.00000E+00 Product nuclide = 440980 : beta- + + Nuclide 839 / 1657 : 430991 -- technetium 99m (Tc-99m) + + Pointers : 866172 -1000000 + Primary type : Decay + Nuclide ZAI : 430991 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 98.90626 + Atomic weight ratio (AWR) : 98.05660 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.16E+04 seconds (6.01 hours) + Specific ingestion toxicity : 2.20E-11 Sv/Bq + Specific inhalation toxicity : 2.00E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 1.42684E-01 MeV frac = 9.99963E-01 Product nuclide = 43099.82c : IT + 2 RTYP = 1 Q = 4.35883E-01 MeV frac = 3.70000E-05 Product nuclide = 440990 : beta- + + Nuclide 840 / 1657 : 431000 -- technetium 100 (Tc-100) + + Pointers : 867064 -1000000 + Primary type : Decay + Nuclide ZAI : 431000 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 99.90766 + Atomic weight ratio (AWR) : 99.04940 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 15.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 1.68000E-01 MeV frac = 1.80000E-05 Product nuclide = 42100.82c : EC/beta+ + 2 RTYP = 1 Q = 3.20280E+00 MeV frac = 9.99982E-01 Product nuclide = 44100.82c : beta- + + Nuclide 841 / 1657 : 431010 -- technetium 101 (Tc-101) + + Pointers : 868264 -1000000 + Primary type : Decay + Nuclide ZAI : 431010 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 100.90684 + Atomic weight ratio (AWR) : 100.04000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.52E+02 seconds (14.2 minutes) + Specific ingestion toxicity : 1.90E-11 Sv/Bq + Specific inhalation toxicity : 1.20E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.61300E+00 MeV frac = 1.00000E+00 Product nuclide = 44101.82c : beta- + + Nuclide 842 / 1657 : 431020 -- technetium 102 (Tc-102) + + Pointers : 869517 -1000000 + Primary type : Decay + Nuclide ZAI : 431020 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 101.90946 + Atomic weight ratio (AWR) : 101.03400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.28 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.53200E+00 MeV frac = 1.00000E+00 Product nuclide = 44102.82c : beta- + + Nuclide 843 / 1657 : 431021 -- technetium 102m (Tc-102m) + + Pointers : 870042 -1000000 + Primary type : Decay + Nuclide ZAI : 431021 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 101.90946 + Atomic weight ratio (AWR) : 101.03400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.61E+02 seconds (4.35 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.55200E+00 MeV frac = 1.00000E+00 Product nuclide = 44102.82c : beta- + + Nuclide 844 / 1657 : 431030 -- technetium 103 (Tc-103) + + Pointers : 870903 -1000000 + Primary type : Decay + Nuclide ZAI : 431030 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 102.90904 + Atomic weight ratio (AWR) : 102.02500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 54.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.66200E+00 MeV frac = 1.00000E+00 Product nuclide = 44103.82c : beta- + + Nuclide 845 / 1657 : 431040 -- technetium 104 (Tc-104) + + Pointers : 872254 -1000000 + Primary type : Decay + Nuclide ZAI : 431040 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 103.91166 + Atomic weight ratio (AWR) : 103.01900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.10E+03 seconds (18.3 minutes) + Specific ingestion toxicity : 8.00E-11 Sv/Bq + Specific inhalation toxicity : 2.90E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 44104.82c : beta- + + Nuclide 846 / 1657 : 431050 -- technetium 105 (Tc-105) + + Pointers : 874697 -1000000 + Primary type : Decay + Nuclide ZAI : 431050 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 104.91124 + Atomic weight ratio (AWR) : 104.01000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.56E+02 seconds (7.6 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.64000E+00 MeV frac = 1.00000E+00 Product nuclide = 44105.82c : beta- + + Nuclide 847 / 1657 : 431060 -- technetium 106 (Tc-106) + + Pointers : 876566 -1000000 + Primary type : Decay + Nuclide ZAI : 431060 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 105.91386 + Atomic weight ratio (AWR) : 105.00400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 35.6 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.54700E+00 MeV frac = 1.00000E+00 Product nuclide = 44106.82c : beta- + + Nuclide 848 / 1657 : 431070 -- technetium 107 (Tc-107) + + Pointers : 877861 -1000000 + Primary type : Decay + Nuclide ZAI : 431070 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 106.91546 + Atomic weight ratio (AWR) : 105.99700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 21.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.82000E+00 MeV frac = 1.00000E+00 Product nuclide = 441070 : beta- + + Nuclide 849 / 1657 : 431080 -- technetium 108 (Tc-108) + + Pointers : 881018 -1000000 + Primary type : Decay + Nuclide ZAI : 431080 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 107.91807 + Atomic weight ratio (AWR) : 106.99100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.17 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.72000E+00 MeV frac = 1.00000E+00 Product nuclide = 441080 : beta- + + Nuclide 850 / 1657 : 431090 -- technetium 109 (Tc-109) + + Pointers : 881202 -1000000 + Primary type : Decay + Nuclide ZAI : 431090 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 108.91968 + Atomic weight ratio (AWR) : 107.98400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.86 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 6.31001E+00 MeV frac = 9.99200E-01 Product nuclide = 441090 : beta- + 2 RTYP = 15 Q = 1.05871E+00 MeV frac = 8.00000E-04 Product nuclide = 441080 : beta- + neutron emission + + Nuclide 851 / 1657 : 431100 -- technetium 110 (Tc-110) + + Pointers : 881459 -1000000 + Primary type : Decay + Nuclide ZAI : 431100 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 109.92431 + Atomic weight ratio (AWR) : 108.98000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.92 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 9.02000E+00 MeV frac = 9.99600E-01 Product nuclide = 441100 : beta- + 2 RTYP = 15 Q = 1.81870E+00 MeV frac = 4.00000E-04 Product nuclide = 441090 : beta- + neutron emission + + Nuclide 852 / 1657 : 431110 -- technetium 111 (Tc-111) + + Pointers : 881716 -1000000 + Primary type : Decay + Nuclide ZAI : 431110 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 110.92591 + Atomic weight ratio (AWR) : 109.97300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.29 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.45000E+00 MeV frac = 1.00000E+00 Product nuclide = 441110 : beta- + + Nuclide 853 / 1657 : 431120 -- technetium 112 (Tc-112) + + Pointers : 882591 -1000000 + Primary type : Decay + Nuclide ZAI : 431120 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 111.92953 + Atomic weight ratio (AWR) : 110.96800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.29 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 9.48000E+00 MeV frac = 9.85000E-01 Product nuclide = 441120 : beta- + 2 RTYP = 15 Q = 2.59871E+00 MeV frac = 1.50000E-02 Product nuclide = 441110 : beta- + neutron emission + + Nuclide 854 / 1657 : 431130 -- technetium 113 (Tc-113) + + Pointers : 882848 -1000000 + Primary type : Decay + Nuclide ZAI : 431130 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 112.93215 + Atomic weight ratio (AWR) : 111.96200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.13 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 7.55570E+00 MeV frac = 9.28140E-01 Product nuclide = 441130 : beta- + 2 RTYP = 15 Q = 4.09900E+00 MeV frac = 7.18640E-02 Product nuclide = 441120 : beta- + neutron emission + + Nuclide 855 / 1657 : 431140 -- technetium 114 (Tc-114) + + Pointers : 888801 -1000000 + Primary type : Decay + Nuclide ZAI : 431140 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 113.93678 + Atomic weight ratio (AWR) : 112.95800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.06210E+01 MeV frac = 9.34640E-01 Product nuclide = 441140 : beta- + 2 RTYP = 15 Q = 4.80900E+00 MeV frac = 6.53580E-02 Product nuclide = 441130 : beta- + neutron emission + + Nuclide 856 / 1657 : 431150 -- technetium 115 (Tc-115) + + Pointers : 896809 -1000000 + Primary type : Decay + Nuclide ZAI : 431150 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 114.93939 + Atomic weight ratio (AWR) : 113.95200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.27 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.88590E+00 MeV frac = 8.56630E-01 Product nuclide = 441150 : beta- + 2 RTYP = 15 Q = 5.92900E+00 MeV frac = 1.43370E-01 Product nuclide = 441140 : beta- + neutron emission + + Nuclide 857 / 1657 : 431160 -- technetium 116 (Tc-116) + + Pointers : 904109 -1000000 + Primary type : Decay + Nuclide ZAI : 431160 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 115.94402 + Atomic weight ratio (AWR) : 114.94800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.12 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.18720E+01 MeV frac = 8.77770E-01 Product nuclide = 441160 : beta- + 2 RTYP = 15 Q = 6.65900E+00 MeV frac = 1.22230E-01 Product nuclide = 441150 : beta- + neutron emission + + Nuclide 858 / 1657 : 431170 -- technetium 117 (Tc-117) + + Pointers : 913422 -1000000 + Primary type : Decay + Nuclide ZAI : 431170 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 116.94663 + Atomic weight ratio (AWR) : 115.94200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 40 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.01600E+01 MeV frac = 1.00000E+00 Product nuclide = 441170 : beta- + + Nuclide 859 / 1657 : 431180 -- technetium 118 (Tc-118) + + Pointers : 913606 -1000000 + Primary type : Decay + Nuclide ZAI : 431180 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 117.95126 + Atomic weight ratio (AWR) : 116.93800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 30 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.27200E+01 MeV frac = 1.00000E+00 Product nuclide = 441180 : beta- + + Nuclide 860 / 1657 : 440980 -- ruthenium 98 (Ru-98) + + Pointers : 913790 -1000000 + Primary type : Decay + Nuclide ZAI : 440980 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 97.90526 + Atomic weight ratio (AWR) : 97.06420 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 861 / 1657 : 440990 -- ruthenium 99 (Ru-99) + + Pointers : 913896 -1000000 + Primary type : Decay + Nuclide ZAI : 440990 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 98.90595 + Atomic weight ratio (AWR) : 98.05630 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 862 / 1657 : 441031 -- ruthenium 103m (Ru-103m) + + Pointers : 926429 -1000000 + Primary type : Decay + Nuclide ZAI : 441031 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 102.90602 + Atomic weight ratio (AWR) : 102.02200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.69 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 2.38000E-01 MeV frac = 1.00000E+00 Product nuclide = 44103.82c : IT + + Nuclide 863 / 1657 : 441070 -- ruthenium 107 (Ru-107) + + Pointers : 935619 -1000000 + Primary type : Decay + Nuclide ZAI : 441070 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 106.90941 + Atomic weight ratio (AWR) : 105.99100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.25E+02 seconds (3.75 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.94000E+00 MeV frac = 1.00000E+00 Product nuclide = 451070 : beta- + + Nuclide 864 / 1657 : 441080 -- ruthenium 108 (Ru-108) + + Pointers : 939392 -1000000 + Primary type : Decay + Nuclide ZAI : 441080 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 107.91000 + Atomic weight ratio (AWR) : 106.98300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.73E+02 seconds (4.55 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.35000E+00 MeV frac = 1.00000E+00 Product nuclide = 451080 : beta- + + Nuclide 865 / 1657 : 441090 -- ruthenium 109 (Ru-109) + + Pointers : 939576 -1000000 + Primary type : Decay + Nuclide ZAI : 441090 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 108.91363 + Atomic weight ratio (AWR) : 107.97800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 34.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.16000E+00 MeV frac = 1.00000E+00 Product nuclide = 451090 : beta- + + Nuclide 866 / 1657 : 441100 -- ruthenium 110 (Ru-110) + + Pointers : 945519 -1000000 + Primary type : Decay + Nuclide ZAI : 441100 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 109.91422 + Atomic weight ratio (AWR) : 108.97000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 12 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.77400E+00 MeV frac = 1.00000E+00 Product nuclide = 451100 : beta- + + Nuclide 867 / 1657 : 441110 -- ruthenium 111 (Ru-111) + + Pointers : 946114 -1000000 + Primary type : Decay + Nuclide ZAI : 441110 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 110.91784 + Atomic weight ratio (AWR) : 109.96500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.12 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.68700E+00 MeV frac = 1.00000E+00 Product nuclide = 451110 : beta- + + Nuclide 868 / 1657 : 441120 -- ruthenium 112 (Ru-112) + + Pointers : 946298 -1000000 + Primary type : Decay + Nuclide ZAI : 441120 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 111.91945 + Atomic weight ratio (AWR) : 110.95800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.75 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.26000E+00 MeV frac = 1.00000E+00 Product nuclide = 451120 : beta- + + Nuclide 869 / 1657 : 441130 -- ruthenium 113 (Ru-113) + + Pointers : 946482 -1000000 + Primary type : Decay + Nuclide ZAI : 441130 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 112.92206 + Atomic weight ratio (AWR) : 111.95200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.8 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.63000E+00 MeV frac = 1.00000E+00 Product nuclide = 451130 : beta- + + Nuclide 870 / 1657 : 441131 -- ruthenium 113m (Ru-113m) + + Pointers : 947343 -1000000 + Primary type : Decay + Nuclide ZAI : 441131 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 112.92206 + Atomic weight ratio (AWR) : 111.95200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.51 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 1.30000E-01 MeV frac = 5.00000E-01 Product nuclide = 441130 : IT + 2 RTYP = 1 Q = 6.61000E+00 MeV frac = 5.00000E-01 Product nuclide = 451130 : beta- + + Nuclide 871 / 1657 : 441140 -- ruthenium 114 (Ru-114) + + Pointers : 947600 -1000000 + Primary type : Decay + Nuclide ZAI : 441140 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 113.92467 + Atomic weight ratio (AWR) : 112.94600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.53 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.10000E+00 MeV frac = 1.00000E+00 Product nuclide = 451140 : beta- + + Nuclide 872 / 1657 : 441150 -- ruthenium 115 (Ru-115) + + Pointers : 947784 -1000000 + Primary type : Decay + Nuclide ZAI : 441150 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 114.92830 + Atomic weight ratio (AWR) : 113.94100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.7 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 7.26180E+00 MeV frac = 9.97720E-01 Product nuclide = 451150 : beta- + 2 RTYP = 15 Q = 1.41900E+00 MeV frac = 2.27600E-03 Product nuclide = 451140 : beta- + neutron emission + + Nuclide 873 / 1657 : 441160 -- ruthenium 116 (Ru-116) + + Pointers : 952759 -1000000 + Primary type : Decay + Nuclide ZAI : 441160 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 115.93091 + Atomic weight ratio (AWR) : 114.93500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.7 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 5.52690E+00 MeV frac = 9.89190E-01 Product nuclide = 451160 : beta- + 2 RTYP = 15 Q = 2.15900E+00 MeV frac = 1.08110E-02 Product nuclide = 451150 : beta- + neutron emission + + Nuclide 874 / 1657 : 441170 -- ruthenium 117 (Ru-117) + + Pointers : 956912 -1000000 + Primary type : Decay + Nuclide ZAI : 441170 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 116.93554 + Atomic weight ratio (AWR) : 115.93100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.34 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.51310E+00 MeV frac = 9.79490E-01 Product nuclide = 451170 : beta- + 2 RTYP = 15 Q = 3.19900E+00 MeV frac = 2.05090E-02 Product nuclide = 451160 : beta- + neutron emission + + Nuclide 875 / 1657 : 441180 -- ruthenium 118 (Ru-118) + + Pointers : 963171 -1000000 + Primary type : Decay + Nuclide ZAI : 441180 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 117.93714 + Atomic weight ratio (AWR) : 116.92400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.7 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 6.54810E+00 MeV frac = 9.58910E-01 Product nuclide = 451180 : beta- + 2 RTYP = 15 Q = 3.68900E+00 MeV frac = 4.10920E-02 Product nuclide = 451170 : beta- + neutron emission + + Nuclide 876 / 1657 : 441190 -- ruthenium 119 (Ru-119) + + Pointers : 968395 -1000000 + Primary type : Decay + Nuclide ZAI : 441190 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 118.94177 + Atomic weight ratio (AWR) : 117.92000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.19 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 9.30710E+00 MeV frac = 9.56420E-01 Product nuclide = 451190 : beta- + 2 RTYP = 15 Q = 4.45900E+00 MeV frac = 4.35800E-02 Product nuclide = 451180 : beta- + neutron emission + + Nuclide 877 / 1657 : 441200 -- ruthenium 120 (Ru-120) + + Pointers : 975506 -1000000 + Primary type : Decay + Nuclide ZAI : 441200 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 119.94539 + Atomic weight ratio (AWR) : 118.91500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 80 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.29000E+00 MeV frac = 1.00000E+00 Product nuclide = 451200 : beta- + + Nuclide 878 / 1657 : 451010 -- rhodium 101 (Rh-101) + + Pointers : 975690 -1000000 + Primary type : Decay + Nuclide ZAI : 451010 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 100.90583 + Atomic weight ratio (AWR) : 100.03900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.01E+08 seconds (3.2 years) + Specific ingestion toxicity : 5.50E-10 Sv/Bq + Specific inhalation toxicity : 5.40E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 5.42000E-01 MeV frac = 1.00000E+00 Product nuclide = 44101.82c : EC/beta+ + + Nuclide 879 / 1657 : 451020 -- rhodium 102 (Rh-102) + + Pointers : 976481 -1000000 + Primary type : Decay + Nuclide ZAI : 451020 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 101.90643 + Atomic weight ratio (AWR) : 101.03100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.16E+07 seconds (2.9 years) + Specific ingestion toxicity : 1.20E-09 Sv/Bq + Specific inhalation toxicity : 7.10E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 2.32300E+00 MeV frac = 1.00000E+00 Product nuclide = 44102.82c : EC/beta+ + + Nuclide 880 / 1657 : 451031 -- rhodium 103m (Rh-103m) + + Pointers : 989716 -1000000 + Primary type : Decay + Nuclide ZAI : 451031 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 102.90602 + Atomic weight ratio (AWR) : 102.02200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.37E+03 seconds (56.1 minutes) + Specific ingestion toxicity : 3.80E-12 Sv/Bq + Specific inhalation toxicity : 2.70E-12 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 3.97560E-02 MeV frac = 1.00000E+00 Product nuclide = 45103.82c : IT + + Nuclide 881 / 1657 : 451040 -- rhodium 104 (Rh-104) + + Pointers : 990115 -1000000 + Primary type : Decay + Nuclide ZAI : 451040 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 103.90661 + Atomic weight ratio (AWR) : 103.01400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 42.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 2.44800E+00 MeV frac = 9.95500E-01 Product nuclide = 461040 : beta- + 2 RTYP = 2 Q = 1.14600E+00 MeV frac = 4.50000E-03 Product nuclide = 44104.82c : EC/beta+ + + Nuclide 882 / 1657 : 451041 -- rhodium 104m (Rh-104m) + + Pointers : 991343 -1000000 + Primary type : Decay + Nuclide ZAI : 451041 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 103.90661 + Atomic weight ratio (AWR) : 103.01400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.60E+02 seconds (4.34 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 2.57700E+00 MeV frac = 1.30000E-03 Product nuclide = 461040 : beta- + 2 RTYP = 3 Q = 1.28956E-01 MeV frac = 9.98700E-01 Product nuclide = 451040 : IT + + Nuclide 883 / 1657 : 451051 -- rhodium 105m (Rh-105m) + + Pointers : 995653 -1000000 + Primary type : Decay + Nuclide ZAI : 451051 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 104.90519 + Atomic weight ratio (AWR) : 104.00400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 40 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.29570E-01 MeV frac = 1.00000E+00 Product nuclide = 45105.82c : IT + + Nuclide 884 / 1657 : 451060 -- rhodium 106 (Rh-106) + + Pointers : 996010 -1000000 + Primary type : Decay + Nuclide ZAI : 451060 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 105.90680 + Atomic weight ratio (AWR) : 104.99700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 30.1 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.54600E+00 MeV frac = 1.00000E+00 Product nuclide = 46106.82c : beta- + + Nuclide 885 / 1657 : 451061 -- rhodium 106m (Rh-106m) + + Pointers : 999839 -1000000 + Primary type : Decay + Nuclide ZAI : 451061 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 105.90780 + Atomic weight ratio (AWR) : 104.99800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.92E+03 seconds (2.2 hours) + Specific ingestion toxicity : 1.60E-10 Sv/Bq + Specific inhalation toxicity : 1.10E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.67800E+00 MeV frac = 1.00000E+00 Product nuclide = 46106.82c : beta- + + Nuclide 886 / 1657 : 451070 -- rhodium 107 (Rh-107) + + Pointers : 1001946 -1000000 + Primary type : Decay + Nuclide ZAI : 451070 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 106.90638 + Atomic weight ratio (AWR) : 105.98800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.30E+03 seconds (21.7 minutes) + Specific ingestion toxicity : 2.40E-11 Sv/Bq + Specific inhalation toxicity : 1.70E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.50400E+00 MeV frac = 1.00000E+00 Product nuclide = 46107.82c : beta- + + Nuclide 887 / 1657 : 451080 -- rhodium 108 (Rh-108) + + Pointers : 1002877 -1000000 + Primary type : Decay + Nuclide ZAI : 451080 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 107.90900 + Atomic weight ratio (AWR) : 106.98200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 16.8 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.51000E+00 MeV frac = 1.00000E+00 Product nuclide = 46108.82c : beta- + + Nuclide 888 / 1657 : 451081 -- rhodium 108m (Rh-108m) + + Pointers : 1003206 -1000000 + Primary type : Decay + Nuclide ZAI : 451081 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 107.90900 + Atomic weight ratio (AWR) : 106.98200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.60E+02 seconds (6 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.50400E+00 MeV frac = 1.00000E+00 Product nuclide = 46108.82c : beta- + + Nuclide 889 / 1657 : 451090 -- rhodium 109 (Rh-109) + + Pointers : 1003390 -1000000 + Primary type : Decay + Nuclide ZAI : 451090 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 108.90858 + Atomic weight ratio (AWR) : 107.97300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.00E+01 seconds (1.33 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 2.59600E+00 MeV frac = 5.00000E-01 Product nuclide = 461090 : beta- + 2 RTYP = 1 Q = 2.40701E+00 MeV frac = 5.00000E-01 Product nuclide = 461091 : beta- + + Nuclide 890 / 1657 : 451100 -- rhodium 110 (Rh-110) + + Pointers : 1003647 -1000000 + Primary type : Decay + Nuclide ZAI : 451100 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 109.91120 + Atomic weight ratio (AWR) : 108.96700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 28.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.40000E+00 MeV frac = 1.00000E+00 Product nuclide = 46110.82c : beta- + + Nuclide 891 / 1657 : 451101 -- rhodium 110m (Rh-110m) + + Pointers : 1004998 -1000000 + Primary type : Decay + Nuclide ZAI : 451101 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 109.91120 + Atomic weight ratio (AWR) : 108.96700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 46110.82c : beta- + + Nuclide 892 / 1657 : 451110 -- rhodium 111 (Rh-111) + + Pointers : 1005873 -1000000 + Primary type : Decay + Nuclide ZAI : 451110 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 110.91179 + Atomic weight ratio (AWR) : 109.95900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 12 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.64700E+00 MeV frac = 1.00000E+00 Product nuclide = 461110 : beta- + + Nuclide 893 / 1657 : 451120 -- rhodium 112 (Rh-112) + + Pointers : 1008302 -1000000 + Primary type : Decay + Nuclide ZAI : 451120 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 111.91440 + Atomic weight ratio (AWR) : 110.95300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.1 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 461120 : beta- + + Nuclide 894 / 1657 : 451121 -- rhodium 112m (Rh-112m) + + Pointers : 1008687 -1000000 + Primary type : Decay + Nuclide ZAI : 451121 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 111.91440 + Atomic weight ratio (AWR) : 110.95300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.8 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.96000E+00 MeV frac = 1.00000E+00 Product nuclide = 461120 : beta- + + Nuclide 895 / 1657 : 451130 -- rhodium 113 (Rh-113) + + Pointers : 1009394 -1000000 + Primary type : Decay + Nuclide ZAI : 451130 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 112.91601 + Atomic weight ratio (AWR) : 111.94600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.8 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.01000E+00 MeV frac = 1.00000E+00 Product nuclide = 461130 : beta- + + Nuclide 896 / 1657 : 451140 -- rhodium 114 (Rh-114) + + Pointers : 1009578 -1000000 + Primary type : Decay + Nuclide ZAI : 451140 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 113.91862 + Atomic weight ratio (AWR) : 112.94000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.85 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.90000E+00 MeV frac = 1.00000E+00 Product nuclide = 461140 : beta- + + Nuclide 897 / 1657 : 451141 -- rhodium 114m (Rh-114m) + + Pointers : 1010089 -1000000 + Primary type : Decay + Nuclide ZAI : 451141 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 113.91862 + Atomic weight ratio (AWR) : 112.94000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.85 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.06700E+00 MeV frac = 1.00000E+00 Product nuclide = 461140 : beta- + + Nuclide 898 / 1657 : 451150 -- rhodium 115 (Rh-115) + + Pointers : 1010273 -1000000 + Primary type : Decay + Nuclide ZAI : 451150 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 114.92023 + Atomic weight ratio (AWR) : 113.93300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.99 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 6.19000E+00 MeV frac = 8.54800E-01 Product nuclide = 461150 : beta- + 2 RTYP = 1 Q = 6.10082E+00 MeV frac = 1.45200E-01 Product nuclide = 461151 : beta- + + Nuclide 899 / 1657 : 451160 -- rhodium 116 (Rh-116) + + Pointers : 1010530 -1000000 + Primary type : Decay + Nuclide ZAI : 451160 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 115.92385 + Atomic weight ratio (AWR) : 114.92800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.68 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 461160 : beta- + + Nuclide 900 / 1657 : 451161 -- rhodium 116m (Rh-116m) + + Pointers : 1011083 -1000000 + Primary type : Decay + Nuclide ZAI : 451161 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 115.92385 + Atomic weight ratio (AWR) : 114.92800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.57 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.37000E+00 MeV frac = 1.00000E+00 Product nuclide = 461160 : beta- + + Nuclide 901 / 1657 : 451170 -- rhodium 117 (Rh-117) + + Pointers : 1012224 -1000000 + Primary type : Decay + Nuclide ZAI : 451170 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 116.92646 + Atomic weight ratio (AWR) : 115.92200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.44 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.58000E+00 MeV frac = 1.00000E+00 Product nuclide = 461170 : beta- + + Nuclide 902 / 1657 : 451180 -- rhodium 118 (Rh-118) + + Pointers : 1012408 -1000000 + Primary type : Decay + Nuclide ZAI : 451180 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 117.93008 + Atomic weight ratio (AWR) : 116.91700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.32 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 9.98510E+00 MeV frac = 9.70830E-01 Product nuclide = 461180 : beta- + 2 RTYP = 15 Q = 3.41900E+00 MeV frac = 2.91670E-02 Product nuclide = 461170 : beta- + neutron emission + + Nuclide 903 / 1657 : 451190 -- rhodium 119 (Rh-119) + + Pointers : 1019615 -1000000 + Primary type : Decay + Nuclide ZAI : 451190 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 118.93169 + Atomic weight ratio (AWR) : 117.91000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.38000E+00 MeV frac = 1.00000E+00 Product nuclide = 461190 : beta- + + Nuclide 904 / 1657 : 451200 -- rhodium 120 (Rh-120) + + Pointers : 1019799 -1000000 + Primary type : Decay + Nuclide ZAI : 451200 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 119.93632 + Atomic weight ratio (AWR) : 118.90600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.17 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.07790E+01 MeV frac = 9.40720E-01 Product nuclide = 461200 : beta- + 2 RTYP = 15 Q = 4.84900E+00 MeV frac = 5.92820E-02 Product nuclide = 461190 : beta- + neutron emission + + Nuclide 905 / 1657 : 451210 -- rhodium 121 (Rh-121) + + Pointers : 1027912 -1000000 + Primary type : Decay + Nuclide ZAI : 451210 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 120.93792 + Atomic weight ratio (AWR) : 119.89900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.25 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.80710E+00 MeV frac = 8.64320E-01 Product nuclide = 461210 : beta- + 2 RTYP = 15 Q = 6.00900E+00 MeV frac = 1.35680E-01 Product nuclide = 461200 : beta- + neutron emission + + Nuclide 906 / 1657 : 451220 -- rhodium 122 (Rh-122) + + Pointers : 1035188 -1000000 + Primary type : Decay + Nuclide ZAI : 451220 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 121.94356 + Atomic weight ratio (AWR) : 120.89600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 50 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.17900E+01 MeV frac = 1.00000E+00 Product nuclide = 461220 : beta- + + Nuclide 907 / 1657 : 461030 -- palladium 103 (Pd-103) + + Pointers : 1035372 -1000000 + Primary type : Decay + Nuclide ZAI : 461030 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 102.90602 + Atomic weight ratio (AWR) : 102.02200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.47E+06 seconds (17 days) + Specific ingestion toxicity : 1.90E-10 Sv/Bq + Specific inhalation toxicity : 4.50E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 5.72200E-01 MeV frac = 2.60000E-04 Product nuclide = 45103.82c : EC/beta+ + 2 RTYP = 2 Q = 5.32400E-01 MeV frac = 9.99740E-01 Product nuclide = 451031 : EC/beta+ + + Nuclide 908 / 1657 : 461040 -- palladium 104 (Pd-104) + + Pointers : 1036236 -1000000 + Primary type : Decay + Nuclide ZAI : 461040 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 103.90359 + Atomic weight ratio (AWR) : 103.01100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 909 / 1657 : 461071 -- palladium 107m (Pd-107m) + + Pointers : 1053371 -1000000 + Primary type : Decay + Nuclide ZAI : 461071 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 106.90537 + Atomic weight ratio (AWR) : 105.98700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 21.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 2.14900E-01 MeV frac = 1.00000E+00 Product nuclide = 46107.82c : IT + + Nuclide 910 / 1657 : 461090 -- palladium 109 (Pd-109) + + Pointers : 1059858 -1000000 + Primary type : Decay + Nuclide ZAI : 461090 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 108.90556 + Atomic weight ratio (AWR) : 107.97000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.89E+04 seconds (13.6 hours) + Specific ingestion toxicity : 5.50E-10 Sv/Bq + Specific inhalation toxicity : 3.70E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.11610E+00 MeV frac = 4.86934E-04 Product nuclide = 47109.82c : beta- + 2 RTYP = 1 Q = 1.02807E+00 MeV frac = 9.99513E-01 Product nuclide = 471091 : beta- + + Nuclide 911 / 1657 : 461091 -- palladium 109m (Pd-109m) + + Pointers : 1062584 -1000000 + Primary type : Decay + Nuclide ZAI : 461091 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 108.90556 + Atomic weight ratio (AWR) : 107.97000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.81E+02 seconds (4.69 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.88900E-01 MeV frac = 1.00000E+00 Product nuclide = 461090 : IT + + Nuclide 912 / 1657 : 461110 -- palladium 111 (Pd-111) + + Pointers : 1065640 -1000000 + Primary type : Decay + Nuclide ZAI : 461110 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 110.90776 + Atomic weight ratio (AWR) : 109.95500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.40E+03 seconds (23.4 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 2.18800E+00 MeV frac = 7.04165E-03 Product nuclide = 47111.82c : beta- + 2 RTYP = 1 Q = 2.12815E+00 MeV frac = 9.92958E-01 Product nuclide = 471111 : beta- + + Nuclide 913 / 1657 : 461111 -- palladium 111m (Pd-111m) + + Pointers : 1067610 -1000000 + Primary type : Decay + Nuclide ZAI : 461111 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 110.90776 + Atomic weight ratio (AWR) : 109.95500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.98E+04 seconds (5.5 hours) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 3 Q = 1.72180E-01 MeV frac = 7.30000E-01 Product nuclide = 461110 : IT + 2 RTYP = 1 Q = 2.38918E+00 MeV frac = 7.81380E-02 Product nuclide = 47111.82c : beta- + 3 RTYP = 1 Q = 2.32936E+00 MeV frac = 1.91862E-01 Product nuclide = 471111 : beta- + + Nuclide 914 / 1657 : 461120 -- palladium 112 (Pd-112) + + Pointers : 1067940 -1000000 + Primary type : Decay + Nuclide ZAI : 461120 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 111.90734 + Atomic weight ratio (AWR) : 110.94600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.31E+04 seconds (20.3 hours) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.88000E-01 MeV frac = 1.00000E+00 Product nuclide = 471120 : beta- + + Nuclide 915 / 1657 : 461130 -- palladium 113 (Pd-113) + + Pointers : 1068269 -1000000 + Primary type : Decay + Nuclide ZAI : 461130 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 112.91097 + Atomic weight ratio (AWR) : 111.94100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.10E+01 seconds (1.52 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 3.29700E+00 MeV frac = 9.50000E-01 Product nuclide = 471131 : beta- + 2 RTYP = 1 Q = 3.34000E+00 MeV frac = 5.00000E-02 Product nuclide = 471130 : beta- + + Nuclide 916 / 1657 : 461131 -- palladium 113m (Pd-113m) + + Pointers : 1070561 -1000000 + Primary type : Decay + Nuclide ZAI : 461131 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 112.91097 + Atomic weight ratio (AWR) : 111.94100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 8.11000E-02 MeV frac = 1.00000E+00 Product nuclide = 461130 : IT + + Nuclide 917 / 1657 : 461140 -- palladium 114 (Pd-114) + + Pointers : 1070960 -1000000 + Primary type : Decay + Nuclide ZAI : 461140 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 113.91055 + Atomic weight ratio (AWR) : 112.93200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.45E+02 seconds (2.42 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.44000E+00 MeV frac = 1.00000E+00 Product nuclide = 471140 : beta- + + Nuclide 918 / 1657 : 461150 -- palladium 115 (Pd-115) + + Pointers : 1071639 -1000000 + Primary type : Decay + Nuclide ZAI : 461150 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 114.91417 + Atomic weight ratio (AWR) : 113.92700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 25 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 4.59000E+00 MeV frac = 7.30000E-01 Product nuclide = 471150 : beta- + 2 RTYP = 1 Q = 4.54884E+00 MeV frac = 2.70000E-01 Product nuclide = 471151 : beta- + + Nuclide 919 / 1657 : 461151 -- palladium 115m (Pd-115m) + + Pointers : 1071896 -1000000 + Primary type : Decay + Nuclide ZAI : 461151 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 114.91417 + Atomic weight ratio (AWR) : 113.92700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 50 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 4.63802E+00 MeV frac = 9.20000E-01 Product nuclide = 471151 : beta- + 2 RTYP = 3 Q = 8.91800E-02 MeV frac = 8.00000E-02 Product nuclide = 461150 : IT + + Nuclide 920 / 1657 : 461160 -- palladium 116 (Pd-116) + + Pointers : 1072153 -1000000 + Primary type : Decay + Nuclide ZAI : 461160 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 115.91376 + Atomic weight ratio (AWR) : 114.91800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 11.8 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.61000E+00 MeV frac = 1.00000E+00 Product nuclide = 471160 : beta- + + Nuclide 921 / 1657 : 461170 -- palladium 117 (Pd-117) + + Pointers : 1072748 -1000000 + Primary type : Decay + Nuclide ZAI : 461170 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 116.91738 + Atomic weight ratio (AWR) : 115.91300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 5.74000E+00 MeV frac = 5.00000E-01 Product nuclide = 471170 : beta- + 2 RTYP = 1 Q = 5.71140E+00 MeV frac = 5.00000E-01 Product nuclide = 471171 : beta- + + Nuclide 922 / 1657 : 461171 -- palladium 117m (Pd-117m) + + Pointers : 1073005 -1000000 + Primary type : Decay + Nuclide ZAI : 461171 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 116.91738 + Atomic weight ratio (AWR) : 115.91300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 19.1 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 2.03200E-01 MeV frac = 1.00000E+00 Product nuclide = 461170 : IT + + Nuclide 923 / 1657 : 461180 -- palladium 118 (Pd-118) + + Pointers : 1073614 -1000000 + Primary type : Decay + Nuclide ZAI : 461180 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 117.91899 + Atomic weight ratio (AWR) : 116.90600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.9 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 4.10000E+00 MeV frac = 8.57042E-01 Product nuclide = 471180 : beta- + 2 RTYP = 1 Q = 3.97237E+00 MeV frac = 1.42958E-01 Product nuclide = 471181 : beta- + + Nuclide 924 / 1657 : 461190 -- palladium 119 (Pd-119) + + Pointers : 1075304 -1000000 + Primary type : Decay + Nuclide ZAI : 461190 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 118.92362 + Atomic weight ratio (AWR) : 117.90200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.92 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 6.94000E+00 MeV frac = 5.00000E-01 Product nuclide = 471190 : beta- + 2 RTYP = 1 Q = 6.92000E+00 MeV frac = 5.00000E-01 Product nuclide = 471191 : beta- + + Nuclide 925 / 1657 : 461200 -- palladium 120 (Pd-120) + + Pointers : 1075561 -1000000 + Primary type : Decay + Nuclide ZAI : 461200 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 119.92421 + Atomic weight ratio (AWR) : 118.89400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 5.50000E+00 MeV frac = 5.00000E-01 Product nuclide = 471200 : beta- + 2 RTYP = 1 Q = 5.29700E+00 MeV frac = 5.00000E-01 Product nuclide = 471201 : beta- + + Nuclide 926 / 1657 : 461210 -- palladium 121 (Pd-121) + + Pointers : 1075818 -1000000 + Primary type : Decay + Nuclide ZAI : 461210 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 120.92783 + Atomic weight ratio (AWR) : 119.88900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.6 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 7.57010E+00 MeV frac = 9.97280E-01 Product nuclide = 471210 : beta- + 2 RTYP = 15 Q = 1.53600E+00 MeV frac = 2.72200E-03 Product nuclide = 471200 : beta- + neutron emission + + Nuclide 927 / 1657 : 461220 -- palladium 122 (Pd-122) + + Pointers : 1081015 -1000000 + Primary type : Decay + Nuclide ZAI : 461220 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 121.93045 + Atomic weight ratio (AWR) : 120.88300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.54000E+00 MeV frac = 1.00000E+00 Product nuclide = 471220 : beta- + + Nuclide 928 / 1657 : 461230 -- palladium 123 (Pd-123) + + Pointers : 1081199 -1000000 + Primary type : Decay + Nuclide ZAI : 461230 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 122.93508 + Atomic weight ratio (AWR) : 121.87900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.35000E+00 MeV frac = 1.00000E+00 Product nuclide = 471230 : beta- + + Nuclide 929 / 1657 : 461240 -- palladium 124 (Pd-124) + + Pointers : 1081383 -1000000 + Primary type : Decay + Nuclide ZAI : 461240 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 123.93668 + Atomic weight ratio (AWR) : 122.87200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 100 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.67000E+00 MeV frac = 1.00000E+00 Product nuclide = 471240 : beta- + + Nuclide 930 / 1657 : 471070 -- silver 107 (Ag-107) + + Pointers : 1081567 -1000000 + Primary type : Decay + Nuclide ZAI : 471070 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 106.90537 + Atomic weight ratio (AWR) : 105.98700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 931 / 1657 : 471080 -- silver 108 (Ag-108) + + Pointers : 1081673 -1000000 + Primary type : Decay + Nuclide ZAI : 471080 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 107.90597 + Atomic weight ratio (AWR) : 106.97900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.43E+02 seconds (2.38 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 1.92200E+00 MeV frac = 2.47000E-02 Product nuclide = 46108.82c : EC/beta+ + 2 RTYP = 1 Q = 1.64900E+00 MeV frac = 9.75300E-01 Product nuclide = 481080 : beta- + + Nuclide 932 / 1657 : 471081 -- silver 108m (Ag-108m) + + Pointers : 1082509 -1000000 + Primary type : Decay + Nuclide ZAI : 471081 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 107.90597 + Atomic weight ratio (AWR) : 106.97900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.38E+10 seconds (438 years) + Specific ingestion toxicity : 2.30E-09 Sv/Bq + Specific inhalation toxicity : 3.70E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 1.09440E-01 MeV frac = 9.10000E-02 Product nuclide = 471080 : IT + 2 RTYP = 2 Q = 2.03144E+00 MeV frac = 9.09000E-01 Product nuclide = 46108.82c : EC/beta+ + + Nuclide 933 / 1657 : 471091 -- silver 109m (Ag-109m) + + Pointers : 1086221 -1000000 + Primary type : Decay + Nuclide ZAI : 471091 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 108.90455 + Atomic weight ratio (AWR) : 107.96900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 39.7 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 8.80340E-02 MeV frac = 1.00000E+00 Product nuclide = 47109.82c : IT + + Nuclide 934 / 1657 : 471100 -- silver 110 (Ag-110) + + Pointers : 1086620 -1000000 + Primary type : Decay + Nuclide ZAI : 471100 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 109.90615 + Atomic weight ratio (AWR) : 108.96200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 24.6 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 8.92000E-01 MeV frac = 3.00000E-03 Product nuclide = 46110.82c : EC/beta+ + 2 RTYP = 1 Q = 2.89220E+00 MeV frac = 9.97000E-01 Product nuclide = 48110.82c : beta- + + Nuclide 935 / 1657 : 471111 -- silver 111m (Ag-111m) + + Pointers : 1097406 -1000000 + Primary type : Decay + Nuclide ZAI : 471111 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 110.90574 + Atomic weight ratio (AWR) : 109.95300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.48E+01 seconds (1.08 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.09660E+00 MeV frac = 5.00000E-03 Product nuclide = 48111.82c : beta- + 2 RTYP = 3 Q = 5.98200E-02 MeV frac = 9.95000E-01 Product nuclide = 47111.82c : IT + + Nuclide 936 / 1657 : 471120 -- silver 112 (Ag-112) + + Pointers : 1098620 -1000000 + Primary type : Decay + Nuclide ZAI : 471120 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 111.90734 + Atomic weight ratio (AWR) : 110.94600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.13E+04 seconds (3.13 hours) + Specific ingestion toxicity : 4.30E-10 Sv/Bq + Specific inhalation toxicity : 1.70E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.95651E+00 MeV frac = 1.00000E+00 Product nuclide = 48112.82c : beta- + + Nuclide 937 / 1657 : 471130 -- silver 113 (Ag-113) + + Pointers : 1098804 -1000000 + Primary type : Decay + Nuclide ZAI : 471130 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 112.90693 + Atomic weight ratio (AWR) : 111.93700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.93E+04 seconds (5.37 hours) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 2.01600E+00 MeV frac = 9.82635E-01 Product nuclide = 48113.82c : beta- + 2 RTYP = 1 Q = 1.75242E+00 MeV frac = 1.73647E-02 Product nuclide = 481131 : beta- + + Nuclide 938 / 1657 : 471131 -- silver 113m (Ag-113m) + + Pointers : 1100144 -1000000 + Primary type : Decay + Nuclide ZAI : 471131 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 112.90693 + Atomic weight ratio (AWR) : 111.93700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.87E+01 seconds (1.14 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 4.36000E-02 MeV frac = 6.40000E-01 Product nuclide = 471130 : IT + 2 RTYP = 1 Q = 2.05920E+00 MeV frac = 3.60000E-01 Product nuclide = 48113.82c : beta- + + Nuclide 939 / 1657 : 471140 -- silver 114 (Ag-114) + + Pointers : 1101260 -1000000 + Primary type : Decay + Nuclide ZAI : 471140 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 113.90853 + Atomic weight ratio (AWR) : 112.93000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.6 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.08700E+00 MeV frac = 1.00000E+00 Product nuclide = 48114.82c : beta- + + Nuclide 940 / 1657 : 471141 -- silver 114m (Ag-114m) + + Pointers : 1102387 -1000000 + Primary type : Decay + Nuclide ZAI : 471141 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 113.90853 + Atomic weight ratio (AWR) : 112.93000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.5 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.99000E-01 MeV frac = 1.00000E+00 Product nuclide = 471140 : IT + + Nuclide 941 / 1657 : 471150 -- silver 115 (Ag-115) + + Pointers : 1102954 -1000000 + Primary type : Decay + Nuclide ZAI : 471150 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 114.90913 + Atomic weight ratio (AWR) : 113.92200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.20E+03 seconds (20 minutes) + Specific ingestion toxicity : 6.00E-11 Sv/Bq + Specific inhalation toxicity : 2.90E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 3.10000E+00 MeV frac = 9.41622E-01 Product nuclide = 481150 : beta- + 2 RTYP = 1 Q = 2.91899E+00 MeV frac = 5.83779E-02 Product nuclide = 48515.82c : beta- + + Nuclide 942 / 1657 : 471151 -- silver 115m (Ag-115m) + + Pointers : 1105778 -1000000 + Primary type : Decay + Nuclide ZAI : 471151 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 114.90913 + Atomic weight ratio (AWR) : 113.92200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 18.6 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 1 Q = 3.14400E+00 MeV frac = 7.67000E-01 Product nuclide = 481150 : beta- + 2 RTYP = 1 Q = 2.96300E+00 MeV frac = 2.30000E-02 Product nuclide = 48515.82c : beta- + 3 RTYP = 3 Q = 4.11000E-02 MeV frac = 2.10000E-01 Product nuclide = 471150 : IT + + Nuclide 943 / 1657 : 471160 -- silver 116 (Ag-116) + + Pointers : 1107723 -1000000 + Primary type : Decay + Nuclide ZAI : 471160 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 115.91174 + Atomic weight ratio (AWR) : 114.91600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.37E+02 seconds (3.95 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.17600E+00 MeV frac = 1.00000E+00 Product nuclide = 48116.82c : beta- + + Nuclide 944 / 1657 : 471161 -- silver 116m (Ag-116m) + + Pointers : 1111930 -1000000 + Primary type : Decay + Nuclide ZAI : 471161 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 115.91174 + Atomic weight ratio (AWR) : 114.91600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.6 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 6.24190E+00 MeV frac = 9.40000E-01 Product nuclide = 48116.82c : beta- + 2 RTYP = 3 Q = 8.19000E-02 MeV frac = 6.00000E-02 Product nuclide = 471160 : IT + + Nuclide 945 / 1657 : 471170 -- silver 117 (Ag-117) + + Pointers : 1112668 -1000000 + Primary type : Decay + Nuclide ZAI : 471170 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 116.91133 + Atomic weight ratio (AWR) : 115.90700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.36E+01 seconds (1.23 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 4.15500E+00 MeV frac = 8.30700E-01 Product nuclide = 481170 : beta- + 2 RTYP = 1 Q = 4.01860E+00 MeV frac = 1.69300E-01 Product nuclide = 481171 : beta- + + Nuclide 946 / 1657 : 471171 -- silver 117m (Ag-117m) + + Pointers : 1112925 -1000000 + Primary type : Decay + Nuclide ZAI : 471171 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 116.91133 + Atomic weight ratio (AWR) : 115.90700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.34 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 1 Q = 4.18360E+00 MeV frac = 7.07162E-01 Product nuclide = 481170 : beta- + 2 RTYP = 1 Q = 4.04720E+00 MeV frac = 2.32838E-01 Product nuclide = 481171 : beta- + 3 RTYP = 3 Q = 2.86000E-02 MeV frac = 6.00000E-02 Product nuclide = 471170 : IT + + Nuclide 947 / 1657 : 471180 -- silver 118 (Ag-118) + + Pointers : 1113255 -1000000 + Primary type : Decay + Nuclide ZAI : 471180 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 117.91495 + Atomic weight ratio (AWR) : 116.90200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.76 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.13900E+00 MeV frac = 1.00000E+00 Product nuclide = 481180 : beta- + + Nuclide 948 / 1657 : 471181 -- silver 118m (Ag-118m) + + Pointers : 1113439 -1000000 + Primary type : Decay + Nuclide ZAI : 471181 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 117.91495 + Atomic weight ratio (AWR) : 116.90200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 7.26649E+00 MeV frac = 5.90000E-01 Product nuclide = 481180 : beta- + 2 RTYP = 3 Q = 1.27490E-01 MeV frac = 4.10000E-01 Product nuclide = 471180 : IT + + Nuclide 949 / 1657 : 471190 -- silver 119 (Ag-119) + + Pointers : 1113696 -1000000 + Primary type : Decay + Nuclide ZAI : 471190 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 118.91555 + Atomic weight ratio (AWR) : 117.89400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 5.35000E+00 MeV frac = 5.00000E-01 Product nuclide = 481190 : beta- + 2 RTYP = 1 Q = 5.20346E+00 MeV frac = 5.00000E-01 Product nuclide = 481191 : beta- + + Nuclide 950 / 1657 : 471191 -- silver 119m (Ag-119m) + + Pointers : 1113953 -1000000 + Primary type : Decay + Nuclide ZAI : 471191 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 118.91555 + Atomic weight ratio (AWR) : 117.89400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.1 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.37000E+00 MeV frac = 1.00000E+00 Product nuclide = 481190 : beta- + + Nuclide 951 / 1657 : 471200 -- silver 120 (Ag-120) + + Pointers : 1114137 -1000000 + Primary type : Decay + Nuclide ZAI : 471200 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 119.91917 + Atomic weight ratio (AWR) : 118.88900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.23 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 1 Q = 8.32401E+00 MeV frac = 9.99970E-01 Product nuclide = 481200 : beta- + 2 RTYP = 15 Q = 1.88702E-01 MeV frac = 1.50000E-05 Product nuclide = 481190 : beta- + neutron emission + 3 RTYP = 15 Q = 4.21621E-02 MeV frac = 1.50000E-05 Product nuclide = 481191 : beta- + neutron emission + + Nuclide 952 / 1657 : 471201 -- silver 120m (Ag-120m) + + Pointers : 1114467 -1000000 + Primary type : Decay + Nuclide ZAI : 471201 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 119.91917 + Atomic weight ratio (AWR) : 118.88900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.371 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.52701E+00 MeV frac = 6.30000E-01 Product nuclide = 481200 : beta- + 2 RTYP = 3 Q = 2.03000E-01 MeV frac = 3.70000E-01 Product nuclide = 471200 : IT + + Nuclide 953 / 1657 : 471210 -- silver 121 (Ag-121) + + Pointers : 1114724 -1000000 + Primary type : Decay + Nuclide ZAI : 471210 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 120.91976 + Atomic weight ratio (AWR) : 119.88100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.78 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 6.67000E+00 MeV frac = 8.96067E-01 Product nuclide = 481210 : beta- + 2 RTYP = 1 Q = 6.45510E+00 MeV frac = 1.03933E-01 Product nuclide = 481211 : beta- + + Nuclide 954 / 1657 : 471220 -- silver 122 (Ag-122) + + Pointers : 1117464 -1000000 + Primary type : Decay + Nuclide ZAI : 471220 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 121.92339 + Atomic weight ratio (AWR) : 120.87600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.529 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.50000E+00 MeV frac = 9.98000E-01 Product nuclide = 481220 : beta- + + Nuclide 955 / 1657 : 471221 -- silver 122m (Ag-122m) + + Pointers : 1117807 -1000000 + Primary type : Decay + Nuclide ZAI : 471221 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 121.92339 + Atomic weight ratio (AWR) : 120.87600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.58000E+00 MeV frac = 1.00000E+00 Product nuclide = 481220 : beta- + + Nuclide 956 / 1657 : 471230 -- silver 123 (Ag-123) + + Pointers : 1117991 -1000000 + Primary type : Decay + Nuclide ZAI : 471230 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 122.92499 + Atomic weight ratio (AWR) : 121.86900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 7.36000E+00 MeV frac = 8.18164E-01 Product nuclide = 481230 : beta- + 2 RTYP = 1 Q = 7.04348E+00 MeV frac = 1.81836E-01 Product nuclide = 481231 : beta- + + Nuclide 957 / 1657 : 471240 -- silver 124 (Ag-124) + + Pointers : 1119429 -1000000 + Primary type : Decay + Nuclide ZAI : 471240 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 123.92861 + Atomic weight ratio (AWR) : 122.86400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.172 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 1 Q = 1.02400E+01 MeV frac = 9.99000E-01 Product nuclide = 481240 : beta- + 2 RTYP = 15 Q = 2.76870E+00 MeV frac = 5.00000E-04 Product nuclide = 481230 : beta- + neutron emission + 3 RTYP = 15 Q = 2.45218E+00 MeV frac = 5.00000E-04 Product nuclide = 481231 : beta- + neutron emission + + Nuclide 958 / 1657 : 471241 -- silver 124m (Ag-124m) + + Pointers : 1119759 -1000000 + Primary type : Decay + Nuclide ZAI : 471241 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 123.92861 + Atomic weight ratio (AWR) : 122.86400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.02400E+01 MeV frac = 5.00000E-01 Product nuclide = 481240 : beta- + 2 RTYP = 3 Q = 0.00000E+00 MeV frac = 5.00000E-01 Product nuclide = 471240 : IT + + Nuclide 959 / 1657 : 471250 -- silver 125 (Ag-125) + + Pointers : 1120016 -1000000 + Primary type : Decay + Nuclide ZAI : 471250 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 124.93022 + Atomic weight ratio (AWR) : 123.85700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.166 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.56000E+00 MeV frac = 5.00000E-01 Product nuclide = 481250 : beta- + 2 RTYP = 1 Q = 8.51000E+00 MeV frac = 5.00000E-01 Product nuclide = 481251 : beta- + + Nuclide 960 / 1657 : 471260 -- silver 126 (Ag-126) + + Pointers : 1120273 -1000000 + Primary type : Decay + Nuclide ZAI : 471260 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 125.93485 + Atomic weight ratio (AWR) : 124.85300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.107 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.13200E+01 MeV frac = 1.00000E+00 Product nuclide = 481260 : beta- + + Nuclide 961 / 1657 : 471270 -- silver 127 (Ag-127) + + Pointers : 1120457 -1000000 + Primary type : Decay + Nuclide ZAI : 471270 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 126.93645 + Atomic weight ratio (AWR) : 125.84600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 79 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.62000E+00 MeV frac = 1.00000E+00 Product nuclide = 481270 : beta- + + Nuclide 962 / 1657 : 471280 -- silver 128 (Ag-128) + + Pointers : 1120641 -1000000 + Primary type : Decay + Nuclide ZAI : 471280 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 127.94108 + Atomic weight ratio (AWR) : 126.84200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 58 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.24900E+01 MeV frac = 1.00000E+00 Product nuclide = 481280 : beta- + + Nuclide 963 / 1657 : 471290 -- silver 129 (Ag-129) + + Pointers : 1120825 -1000000 + Primary type : Decay + Nuclide ZAI : 471290 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 128.94369 + Atomic weight ratio (AWR) : 127.83600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 44 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.07500E+01 MeV frac = 5.00000E-01 Product nuclide = 481290 : beta- + 2 RTYP = 1 Q = 1.07500E+01 MeV frac = 5.00000E-01 Product nuclide = 481291 : beta- + + Nuclide 964 / 1657 : 471300 -- silver 130 (Ag-130) + + Pointers : 1121082 -1000000 + Primary type : Decay + Nuclide ZAI : 471300 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 129.95034 + Atomic weight ratio (AWR) : 128.83400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 50 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.54100E+01 MeV frac = 1.00000E+00 Product nuclide = 481300 : beta- + + Nuclide 965 / 1657 : 481080 -- cadmium 108 (Cd-108) + + Pointers : 1121266 -1000000 + Primary type : Decay + Nuclide ZAI : 481080 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 107.90395 + Atomic weight ratio (AWR) : 106.97700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.29E+25 seconds (4.1E+17 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 22 Q = 2.71996E-01 MeV frac = 1.00000E+00 Product nuclide = 46108.82c : EC/beta+ + EC/beta+ + + Nuclide 966 / 1657 : 481090 -- cadmium 109 (Cd-109) + + Pointers : 1121450 -1000000 + Primary type : Decay + Nuclide ZAI : 481090 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 108.90455 + Atomic weight ratio (AWR) : 107.96900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.99E+07 seconds (1.27 years) + Specific ingestion toxicity : 2.00E-09 Sv/Bq + Specific inhalation toxicity : 8.10E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 1.27466E-01 MeV frac = 1.00000E+00 Product nuclide = 471091 : EC/beta+ + + Nuclide 967 / 1657 : 481111 -- cadmium 111m (Cd-111m) + + Pointers : 1128270 -1000000 + Primary type : Decay + Nuclide ZAI : 481111 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 110.90372 + Atomic weight ratio (AWR) : 109.95100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.91E+03 seconds (48.5 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 3.96220E-01 MeV frac = 1.00000E+00 Product nuclide = 48111.82c : IT + + Nuclide 968 / 1657 : 481131 -- cadmium 113m (Cd-113m) + + Pointers : 1134971 -1000000 + Primary type : Decay + Nuclide ZAI : 481131 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 112.90390 + Atomic weight ratio (AWR) : 111.93400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.45E+08 seconds (14.1 years) + Specific ingestion toxicity : 2.30E-08 Sv/Bq + Specific inhalation toxicity : 1.10E-07 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 2.63700E-01 MeV frac = 1.40000E-03 Product nuclide = 48113.82c : IT + 2 RTYP = 1 Q = 5.85700E-01 MeV frac = 9.98600E-01 Product nuclide = 49113.82c : beta- + + Nuclide 969 / 1657 : 481150 -- cadmium 115 (Cd-115) + + Pointers : 1138625 -1000000 + Primary type : Decay + Nuclide ZAI : 481150 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 114.90510 + Atomic weight ratio (AWR) : 113.91800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.92E+05 seconds (2.23 days) + Specific ingestion toxicity : 1.40E-09 Sv/Bq + Specific inhalation toxicity : 1.10E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.44870E+00 MeV frac = 6.99783E-07 Product nuclide = 49115.82c : beta- + 2 RTYP = 1 Q = 1.11244E+00 MeV frac = 9.99999E-01 Product nuclide = 491151 : beta- + + Nuclide 970 / 1657 : 481170 -- cadmium 117 (Cd-117) + + Pointers : 1145661 -1000000 + Primary type : Decay + Nuclide ZAI : 481170 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 116.90730 + Atomic weight ratio (AWR) : 115.90300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.96E+03 seconds (2.49 hours) + Specific ingestion toxicity : 2.80E-10 Sv/Bq + Specific inhalation toxicity : 1.70E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 2.52200E+00 MeV frac = 8.34229E-02 Product nuclide = 491170 : beta- + 2 RTYP = 1 Q = 2.20670E+00 MeV frac = 9.16577E-01 Product nuclide = 491171 : beta- + + Nuclide 971 / 1657 : 481171 -- cadmium 117m (Cd-117m) + + Pointers : 1148247 -1000000 + Primary type : Decay + Nuclide ZAI : 481171 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 116.90730 + Atomic weight ratio (AWR) : 115.90300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.21E+04 seconds (3.36 hours) + Specific ingestion toxicity : 2.80E-10 Sv/Bq + Specific inhalation toxicity : 2.10E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 2.66140E+00 MeV frac = 9.84760E-01 Product nuclide = 491170 : beta- + 2 RTYP = 1 Q = 2.34609E+00 MeV frac = 1.52398E-02 Product nuclide = 491171 : beta- + + Nuclide 972 / 1657 : 481180 -- cadmium 118 (Cd-118) + + Pointers : 1149713 -1000000 + Primary type : Decay + Nuclide ZAI : 481180 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 117.90688 + Atomic weight ratio (AWR) : 116.89400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.02E+03 seconds (50.3 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.20000E-01 MeV frac = 1.00000E+00 Product nuclide = 491180 : beta- + + Nuclide 973 / 1657 : 481190 -- cadmium 119 (Cd-119) + + Pointers : 1149930 -1000000 + Primary type : Decay + Nuclide ZAI : 481190 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 118.90950 + Atomic weight ratio (AWR) : 117.88800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.61E+02 seconds (2.69 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 3.73000E+00 MeV frac = 9.72332E-02 Product nuclide = 491190 : beta- + 2 RTYP = 1 Q = 3.41893E+00 MeV frac = 9.02767E-01 Product nuclide = 491191 : beta- + + Nuclide 974 / 1657 : 481191 -- cadmium 119m (Cd-119m) + + Pointers : 1151648 -1000000 + Primary type : Decay + Nuclide ZAI : 481191 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 118.90950 + Atomic weight ratio (AWR) : 117.88800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.32E+02 seconds (2.2 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 3.87654E+00 MeV frac = 9.98121E-01 Product nuclide = 491190 : beta- + 2 RTYP = 1 Q = 3.56573E+00 MeV frac = 1.87880E-03 Product nuclide = 491191 : beta- + + Nuclide 975 / 1657 : 481200 -- cadmium 120 (Cd-120) + + Pointers : 1153464 -1000000 + Primary type : Decay + Nuclide ZAI : 481200 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 119.91009 + Atomic weight ratio (AWR) : 118.88000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 50.8 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.76000E+00 MeV frac = 1.00000E+00 Product nuclide = 491200 : beta- + + Nuclide 976 / 1657 : 481210 -- cadmium 121 (Cd-121) + + Pointers : 1153681 -1000000 + Primary type : Decay + Nuclide ZAI : 481210 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 120.91270 + Atomic weight ratio (AWR) : 119.87400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 13.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 4.78000E+00 MeV frac = 3.25652E-01 Product nuclide = 491210 : beta- + 2 RTYP = 1 Q = 4.46631E+00 MeV frac = 6.74348E-01 Product nuclide = 491211 : beta- + + Nuclide 977 / 1657 : 481211 -- cadmium 121m (Cd-121m) + + Pointers : 1155609 -1000000 + Primary type : Decay + Nuclide ZAI : 481211 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 120.91270 + Atomic weight ratio (AWR) : 119.87400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.99489E+00 MeV frac = 1.00000E+00 Product nuclide = 491210 : beta- + + Nuclide 978 / 1657 : 481220 -- cadmium 122 (Cd-122) + + Pointers : 1157338 -1000000 + Primary type : Decay + Nuclide ZAI : 481220 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 121.91330 + Atomic weight ratio (AWR) : 120.86600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.24 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.85000E+00 MeV frac = 1.00000E+00 Product nuclide = 491220 : beta- + + Nuclide 979 / 1657 : 481230 -- cadmium 123 (Cd-123) + + Pointers : 1157555 -1000000 + Primary type : Decay + Nuclide ZAI : 481230 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 122.91692 + Atomic weight ratio (AWR) : 121.86100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.1 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 6.10000E+00 MeV frac = 3.09747E-01 Product nuclide = 491230 : beta- + 2 RTYP = 1 Q = 5.77279E+00 MeV frac = 6.90253E-01 Product nuclide = 491231 : beta- + + Nuclide 980 / 1657 : 481231 -- cadmium 123m (Cd-123m) + + Pointers : 1158867 -1000000 + Primary type : Decay + Nuclide ZAI : 481231 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 122.91692 + Atomic weight ratio (AWR) : 121.86100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.82 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 6.43153E+00 MeV frac = 9.83421E-01 Product nuclide = 491230 : beta- + 2 RTYP = 1 Q = 6.10430E+00 MeV frac = 1.65791E-02 Product nuclide = 491231 : beta- + + Nuclide 981 / 1657 : 481240 -- cadmium 124 (Cd-124) + + Pointers : 1160879 -1000000 + Primary type : Decay + Nuclide ZAI : 481240 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 123.91752 + Atomic weight ratio (AWR) : 122.85300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.25 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.17000E+00 MeV frac = 1.00000E+00 Product nuclide = 491240 : beta- + + Nuclide 982 / 1657 : 481250 -- cadmium 125 (Cd-125) + + Pointers : 1161063 -1000000 + Primary type : Decay + Nuclide ZAI : 481250 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 124.92114 + Atomic weight ratio (AWR) : 123.84800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.68 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 7.12000E+00 MeV frac = 4.58570E-01 Product nuclide = 491250 : beta- + 2 RTYP = 1 Q = 6.75988E+00 MeV frac = 5.41430E-01 Product nuclide = 491251 : beta- + + Nuclide 983 / 1657 : 481251 -- cadmium 125m (Cd-125m) + + Pointers : 1161829 -1000000 + Primary type : Decay + Nuclide ZAI : 481251 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 124.92114 + Atomic weight ratio (AWR) : 123.84800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.48 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.30400E+00 MeV frac = 1.00000E+00 Product nuclide = 491250 : beta- + + Nuclide 984 / 1657 : 481260 -- cadmium 126 (Cd-126) + + Pointers : 1163040 -1000000 + Primary type : Decay + Nuclide ZAI : 481260 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 125.92274 + Atomic weight ratio (AWR) : 124.84100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.515 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.48000E+00 MeV frac = 1.00000E+00 Product nuclide = 491260 : beta- + + Nuclide 985 / 1657 : 481270 -- cadmium 127 (Cd-127) + + Pointers : 1163224 -1000000 + Primary type : Decay + Nuclide ZAI : 481270 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 126.92636 + Atomic weight ratio (AWR) : 125.83600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.37 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.01000E+00 MeV frac = 1.00000E+00 Product nuclide = 491271 : beta- + + Nuclide 986 / 1657 : 481280 -- cadmium 128 (Cd-128) + + Pointers : 1163408 -1000000 + Primary type : Decay + Nuclide ZAI : 481280 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 127.92797 + Atomic weight ratio (AWR) : 126.82900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.28 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.82213E+00 MeV frac = 1.00000E+00 Product nuclide = 491281 : beta- + + Nuclide 987 / 1657 : 481290 -- cadmium 129 (Cd-129) + + Pointers : 1163592 -1000000 + Primary type : Decay + Nuclide ZAI : 481290 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 128.93260 + Atomic weight ratio (AWR) : 127.82500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.242 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.36000E+00 MeV frac = 1.00000E+00 Product nuclide = 491291 : beta- + + Nuclide 988 / 1657 : 481291 -- cadmium 129m (Cd-129m) + + Pointers : 1163776 -1000000 + Primary type : Decay + Nuclide ZAI : 481291 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 128.93260 + Atomic weight ratio (AWR) : 127.82500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.104 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.74000E+00 MeV frac = 1.00000E+00 Product nuclide = 491290 : beta- + + Nuclide 989 / 1657 : 481300 -- cadmium 130 (Cd-130) + + Pointers : 1163960 -1000000 + Primary type : Decay + Nuclide ZAI : 481300 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 129.93420 + Atomic weight ratio (AWR) : 128.81800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.162 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 1 Q = 8.32000E+00 MeV frac = 9.65000E-01 Product nuclide = 491300 : beta- + 2 RTYP = 15 Q = 3.29870E+00 MeV frac = 1.75000E-02 Product nuclide = 491290 : beta- + neutron emission + 3 RTYP = 15 Q = 2.91870E+00 MeV frac = 1.75000E-02 Product nuclide = 491291 : beta- + neutron emission + + Nuclide 990 / 1657 : 481310 -- cadmium 131 (Cd-131) + + Pointers : 1164290 -1000000 + Primary type : Decay + Nuclide ZAI : 481310 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 130.94085 + Atomic weight ratio (AWR) : 129.81600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 68 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.28670E+01 MeV frac = 9.65000E-01 Product nuclide = 491310 : beta- + 2 RTYP = 15 Q = 6.54870E+00 MeV frac = 3.50000E-02 Product nuclide = 491300 : beta- + neutron emission + + Nuclide 991 / 1657 : 481320 -- cadmium 132 (Cd-132) + + Pointers : 1164547 -1000000 + Primary type : Decay + Nuclide ZAI : 481320 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 131.94548 + Atomic weight ratio (AWR) : 130.81200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 97 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.17000E+01 MeV frac = 4.00000E-01 Product nuclide = 491320 : beta- + 2 RTYP = 15 Q = 8.99570E+00 MeV frac = 6.00000E-01 Product nuclide = 491311 : beta- + neutron emission + + Nuclide 992 / 1657 : 491110 -- indium 111 (In-111) + + Pointers : 1164804 -1000000 + Primary type : Decay + Nuclide ZAI : 491110 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 110.90473 + Atomic weight ratio (AWR) : 109.95200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.42E+05 seconds (2.8 days) + Specific ingestion toxicity : 2.90E-10 Sv/Bq + Specific inhalation toxicity : 2.30E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 8.61800E-01 MeV frac = 9.99950E-01 Product nuclide = 48111.82c : EC/beta+ + 2 RTYP = 2 Q = 4.65640E-01 MeV frac = 5.00171E-05 Product nuclide = 481111 : EC/beta+ + + Nuclide 993 / 1657 : 491120 -- indium 112 (In-112) + + Pointers : 1165290 -1000000 + Primary type : Decay + Nuclide ZAI : 491120 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 111.90533 + Atomic weight ratio (AWR) : 110.94400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.82E+02 seconds (14.7 minutes) + Specific ingestion toxicity : 1.00E-11 Sv/Bq + Specific inhalation toxicity : 7.40E-12 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 6.64000E-01 MeV frac = 4.40000E-01 Product nuclide = 501120 : beta- + 2 RTYP = 2 Q = 2.58900E+00 MeV frac = 5.60000E-01 Product nuclide = 48112.82c : EC/beta+ + + Nuclide 994 / 1657 : 491131 -- indium 113m (In-113m) + + Pointers : 1170481 -1000000 + Primary type : Decay + Nuclide ZAI : 491131 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 112.90390 + Atomic weight ratio (AWR) : 111.93400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.97E+03 seconds (1.66 hours) + Specific ingestion toxicity : 2.80E-11 Sv/Bq + Specific inhalation toxicity : 2.00E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 3.91699E-01 MeV frac = 1.00000E+00 Product nuclide = 49113.82c : IT + + Nuclide 995 / 1657 : 491140 -- indium 114 (In-114) + + Pointers : 1170838 -1000000 + Primary type : Decay + Nuclide ZAI : 491140 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 113.90450 + Atomic weight ratio (AWR) : 112.92600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.19E+01 seconds (1.2 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.98630E+00 MeV frac = 9.95000E-01 Product nuclide = 501140 : beta- + 2 RTYP = 2 Q = 1.44400E+00 MeV frac = 5.00000E-03 Product nuclide = 48114.82c : EC/beta+ + + Nuclide 996 / 1657 : 491141 -- indium 114m (In-114m) + + Pointers : 1171338 -1000000 + Primary type : Decay + Nuclide ZAI : 491141 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 113.90450 + Atomic weight ratio (AWR) : 112.92600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.32E+06 seconds (50 days) + Specific ingestion toxicity : 4.10E-09 Sv/Bq + Specific inhalation toxicity : 9.30E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 1.63400E+00 MeV frac = 3.50000E-02 Product nuclide = 48114.82c : EC/beta+ + 2 RTYP = 3 Q = 1.90340E-01 MeV frac = 9.65000E-01 Product nuclide = 491140 : IT + + Nuclide 997 / 1657 : 491142 -- indium 114m (In-114m) + + Pointers : 3508889 -1000000 + Primary type : Decay + Nuclide ZAI : 491142 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 113.90450 + Atomic weight ratio (AWR) : 112.92600 + Temperature : 900.0 Kelvin + XS temperature : -1.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 43 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is not present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 3.11600E-01 MeV frac = 1.00000E+00 Product nuclide = 491141 : IT + + Nuclide 998 / 1657 : 491151 -- indium 115m (In-115m) + + Pointers : 1175143 -1000000 + Primary type : Decay + Nuclide ZAI : 491151 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 114.90409 + Atomic weight ratio (AWR) : 113.91700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.61E+04 seconds (4.49 hours) + Specific ingestion toxicity : 8.60E-11 Sv/Bq + Specific inhalation toxicity : 5.90E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.23733E-01 MeV frac = 5.00000E-02 Product nuclide = 50115.82c : beta- + 2 RTYP = 3 Q = 3.36244E-01 MeV frac = 9.50000E-01 Product nuclide = 49115.82c : IT + + Nuclide 999 / 1657 : 491160 -- indium 116 (In-116) + + Pointers : 1175755 -1000000 + Primary type : Decay + Nuclide ZAI : 491160 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 115.90569 + Atomic weight ratio (AWR) : 114.91000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 14.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.27600E+00 MeV frac = 1.00000E+00 Product nuclide = 50116.82c : beta- + + Nuclide 1000 / 1657 : 491161 -- indium 116m (In-116m) + + Pointers : 1176616 -1000000 + Primary type : Decay + Nuclide ZAI : 491161 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 115.90569 + Atomic weight ratio (AWR) : 114.91000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.28E+03 seconds (54.6 minutes) + Specific ingestion toxicity : 6.40E-11 Sv/Bq + Specific inhalation toxicity : 4.50E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.40300E+00 MeV frac = 1.00000E+00 Product nuclide = 50116.82c : beta- + + Nuclide 1001 / 1657 : 491162 -- indium 116m (In-116m) + + Pointers : 3509288 -1000000 + Primary type : Decay + Nuclide ZAI : 491162 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 115.90569 + Atomic weight ratio (AWR) : 114.91000 + Temperature : 900.0 Kelvin + XS temperature : -1.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.17 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is not present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.62390E-01 MeV frac = 1.00000E+00 Product nuclide = 491161 : IT + + Nuclide 1002 / 1657 : 491170 -- indium 117 (In-117) + + Pointers : 1179171 -1000000 + Primary type : Decay + Nuclide ZAI : 491170 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 116.90427 + Atomic weight ratio (AWR) : 115.90000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.59E+03 seconds (43.2 minutes) + Specific ingestion toxicity : 3.10E-11 Sv/Bq + Specific inhalation toxicity : 2.90E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.45500E+00 MeV frac = 9.96590E-01 Product nuclide = 50117.82c : beta- + 2 RTYP = 1 Q = 1.14040E+00 MeV frac = 3.40992E-03 Product nuclide = 501171 : beta- + + Nuclide 1003 / 1657 : 491171 -- indium 117m (In-117m) + + Pointers : 1179671 -1000000 + Primary type : Decay + Nuclide ZAI : 491171 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 116.90427 + Atomic weight ratio (AWR) : 115.90000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.97E+03 seconds (1.94 hours) + Specific ingestion toxicity : 1.20E-10 Sv/Bq + Specific inhalation toxicity : 7.20E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 3.15302E-01 MeV frac = 4.71000E-01 Product nuclide = 491170 : IT + 2 RTYP = 1 Q = 1.77030E+00 MeV frac = 5.29000E-01 Product nuclide = 50117.82c : beta- + + Nuclide 1004 / 1657 : 491180 -- indium 118 (In-118) + + Pointers : 1180381 -1000000 + Primary type : Decay + Nuclide ZAI : 491180 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 117.90587 + Atomic weight ratio (AWR) : 116.89300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.42300E+00 MeV frac = 1.00000E+00 Product nuclide = 50118.82c : beta- + + Nuclide 1005 / 1657 : 491181 -- indium 118m (In-118m) + + Pointers : 1180948 -1000000 + Primary type : Decay + Nuclide ZAI : 491181 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 117.90587 + Atomic weight ratio (AWR) : 116.89300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.67E+02 seconds (4.45 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.52300E+00 MeV frac = 1.00000E+00 Product nuclide = 50118.82c : beta- + + Nuclide 1006 / 1657 : 491182 -- indium 118m (In-118m) + + Pointers : 3509687 -1000000 + Primary type : Decay + Nuclide ZAI : 491182 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 117.90587 + Atomic weight ratio (AWR) : 116.89300 + Temperature : 900.0 Kelvin + XS temperature : -1.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is not present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 1.40000E-01 MeV frac = 9.86000E-01 Product nuclide = 491181 : IT + 2 RTYP = 1 Q = 4.66610E+00 MeV frac = 1.40000E-02 Product nuclide = 50118.82c : beta- + + Nuclide 1007 / 1657 : 491190 -- indium 119 (In-119) + + Pointers : 1182467 -1000000 + Primary type : Decay + Nuclide ZAI : 491190 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 118.90546 + Atomic weight ratio (AWR) : 117.88400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.44E+02 seconds (2.4 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 2.36440E+00 MeV frac = 9.66000E-02 Product nuclide = 50119.82c : beta- + 2 RTYP = 1 Q = 2.27487E+00 MeV frac = 9.03400E-01 Product nuclide = 501191 : beta- + + Nuclide 1008 / 1657 : 491191 -- indium 119m (In-119m) + + Pointers : 1182724 -1000000 + Primary type : Decay + Nuclide ZAI : 491191 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 118.90546 + Atomic weight ratio (AWR) : 117.88400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.08E+03 seconds (18 minutes) + Specific ingestion toxicity : 4.70E-11 Sv/Bq + Specific inhalation toxicity : 1.70E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 2.67577E+00 MeV frac = 9.44000E-01 Product nuclide = 50119.82c : beta- + 2 RTYP = 3 Q = 3.11370E-01 MeV frac = 5.60000E-02 Product nuclide = 491190 : IT + + Nuclide 1009 / 1657 : 491200 -- indium 120 (In-120) + + Pointers : 1182981 -1000000 + Primary type : Decay + Nuclide ZAI : 491200 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 119.90807 + Atomic weight ratio (AWR) : 118.87800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.08 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.37000E+00 MeV frac = 1.00000E+00 Product nuclide = 50120.82c : beta- + + Nuclide 1010 / 1657 : 491201 -- indium 120m (In-120m) + + Pointers : 1183380 -1000000 + Primary type : Decay + Nuclide ZAI : 491201 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 119.90807 + Atomic weight ratio (AWR) : 118.87800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 46.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.44000E+00 MeV frac = 1.00000E+00 Product nuclide = 50120.82c : beta- + + Nuclide 1011 / 1657 : 491202 -- indium 120m (In-120m) + + Pointers : 3509944 -1000000 + Primary type : Decay + Nuclide ZAI : 491202 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 119.90807 + Atomic weight ratio (AWR) : 118.87800 + Temperature : 900.0 Kelvin + XS temperature : -1.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 47.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is not present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.66510E+00 MeV frac = 1.00000E+00 Product nuclide = 50120.82c : beta- + + Nuclide 1012 / 1657 : 491210 -- indium 121 (In-121) + + Pointers : 1184829 -1000000 + Primary type : Decay + Nuclide ZAI : 491210 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 120.90766 + Atomic weight ratio (AWR) : 119.86900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 23.1 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 3.36300E+00 MeV frac = 8.86480E-01 Product nuclide = 501210 : beta- + 2 RTYP = 1 Q = 3.35670E+00 MeV frac = 1.13520E-01 Product nuclide = 501211 : beta- + + Nuclide 1013 / 1657 : 491211 -- indium 121m (In-121m) + + Pointers : 1185609 -1000000 + Primary type : Decay + Nuclide ZAI : 491211 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 120.90766 + Atomic weight ratio (AWR) : 119.86900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.33E+02 seconds (3.88 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 3.13600E-01 MeV frac = 1.20000E-02 Product nuclide = 491210 : IT + 2 RTYP = 1 Q = 3.67660E+00 MeV frac = 9.88000E-01 Product nuclide = 501210 : beta- + + Nuclide 1014 / 1657 : 491220 -- indium 122 (In-122) + + Pointers : 1186459 -1000000 + Primary type : Decay + Nuclide ZAI : 491220 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 121.91027 + Atomic weight ratio (AWR) : 120.86300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.37000E+00 MeV frac = 1.00000E+00 Product nuclide = 50122.82c : beta- + + Nuclide 1015 / 1657 : 491221 -- indium 122m (In-122m) + + Pointers : 1187236 -1000000 + Primary type : Decay + Nuclide ZAI : 491221 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 121.91027 + Atomic weight ratio (AWR) : 120.86300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 10.8 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.57000E+00 MeV frac = 1.00000E+00 Product nuclide = 50122.82c : beta- + + Nuclide 1016 / 1657 : 491222 -- indium 122m (In-122m) + + Pointers : 3510128 -1000000 + Primary type : Decay + Nuclide ZAI : 491222 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 121.91027 + Atomic weight ratio (AWR) : 120.86300 + Temperature : 900.0 Kelvin + XS temperature : -1.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 10.8 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is not present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.66000E+00 MeV frac = 1.00000E+00 Product nuclide = 50122.82c : beta- + + Nuclide 1017 / 1657 : 491230 -- indium 123 (In-123) + + Pointers : 1188139 -1000000 + Primary type : Decay + Nuclide ZAI : 491230 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 122.91087 + Atomic weight ratio (AWR) : 121.85500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.17 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 4.39400E+00 MeV frac = 3.23587E-02 Product nuclide = 50123.82c : beta- + 2 RTYP = 1 Q = 4.36940E+00 MeV frac = 9.67641E-01 Product nuclide = 501231 : beta- + + Nuclide 1018 / 1657 : 491231 -- indium 123m (In-123m) + + Pointers : 1189045 -1000000 + Primary type : Decay + Nuclide ZAI : 491231 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 122.91087 + Atomic weight ratio (AWR) : 121.85500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 47.8 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 4.72721E+00 MeV frac = 0.00000E+00 Product nuclide = 50123.82c : beta- + 2 RTYP = 1 Q = 4.70261E+00 MeV frac = 1.00000E+00 Product nuclide = 501231 : beta- + + Nuclide 1019 / 1657 : 491240 -- indium 124 (In-124) + + Pointers : 1189713 -1000000 + Primary type : Decay + Nuclide ZAI : 491240 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 123.91348 + Atomic weight ratio (AWR) : 122.84900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.12 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.36000E+00 MeV frac = 1.00000E+00 Product nuclide = 50124.82c : beta- + + Nuclide 1020 / 1657 : 491241 -- indium 124m (In-124m) + + Pointers : 1191498 -1000000 + Primary type : Decay + Nuclide ZAI : 491241 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 123.91348 + Atomic weight ratio (AWR) : 122.84900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.7 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.41000E+00 MeV frac = 1.00000E+00 Product nuclide = 50124.82c : beta- + + Nuclide 1021 / 1657 : 491250 -- indium 125 (In-125) + + Pointers : 1192541 -1000000 + Primary type : Decay + Nuclide ZAI : 491250 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 124.91408 + Atomic weight ratio (AWR) : 123.84100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.36 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 5.41800E+00 MeV frac = 1.86908E-01 Product nuclide = 50125.82c : beta- + 2 RTYP = 1 Q = 5.39050E+00 MeV frac = 8.13092E-01 Product nuclide = 501251 : beta- + + Nuclide 1022 / 1657 : 491251 -- indium 125m (In-125m) + + Pointers : 1193265 -1000000 + Primary type : Decay + Nuclide ZAI : 491251 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 124.91408 + Atomic weight ratio (AWR) : 123.84100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 12.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.75112E+00 MeV frac = 1.00000E+00 Product nuclide = 501251 : beta- + + Nuclide 1023 / 1657 : 491260 -- indium 126 (In-126) + + Pointers : 1193449 -1000000 + Primary type : Decay + Nuclide ZAI : 491260 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 125.91669 + Atomic weight ratio (AWR) : 124.83500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.53 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.20700E+00 MeV frac = 1.00000E+00 Product nuclide = 50126.82c : beta- + + Nuclide 1024 / 1657 : 491261 -- indium 126m (In-126m) + + Pointers : 1194758 -1000000 + Primary type : Decay + Nuclide ZAI : 491261 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 125.91669 + Atomic weight ratio (AWR) : 124.83500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.64 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.31000E+00 MeV frac = 1.00000E+00 Product nuclide = 50126.82c : beta- + + Nuclide 1025 / 1657 : 491270 -- indium 127 (In-127) + + Pointers : 1194942 -1000000 + Primary type : Decay + Nuclide ZAI : 491270 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 126.91729 + Atomic weight ratio (AWR) : 125.82700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.09 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 6.51000E+00 MeV frac = 1.72768E-01 Product nuclide = 501270 : beta- + 2 RTYP = 1 Q = 6.50493E+00 MeV frac = 8.27232E-01 Product nuclide = 501271 : beta- + + Nuclide 1026 / 1657 : 491271 -- indium 127m (In-127m) + + Pointers : 1197136 -1000000 + Primary type : Decay + Nuclide ZAI : 491271 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 126.91729 + Atomic weight ratio (AWR) : 125.82700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.67 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 6.96430E+00 MeV frac = 9.93100E-01 Product nuclide = 501271 : beta- + 2 RTYP = 15 Q = 1.41870E+00 MeV frac = 6.90000E-03 Product nuclide = 50126.82c : beta- + neutron emission + + Nuclide 1027 / 1657 : 491280 -- indium 128 (In-128) + + Pointers : 1197393 -1000000 + Primary type : Decay + Nuclide ZAI : 491280 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 127.91990 + Atomic weight ratio (AWR) : 126.82100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.84 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.97600E+00 MeV frac = 1.00000E+00 Product nuclide = 501280 : beta- + + Nuclide 1028 / 1657 : 491281 -- indium 128m (In-128m) + + Pointers : 1198506 -1000000 + Primary type : Decay + Nuclide ZAI : 491281 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 127.91990 + Atomic weight ratio (AWR) : 126.82100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 10 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 2.47870E-01 MeV frac = 1.00000E+00 Product nuclide = 491280 : IT + + Nuclide 1029 / 1657 : 491282 -- indium 128m (In-128m) + + Pointers : 3511031 -1000000 + Primary type : Decay + Nuclide ZAI : 491282 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 127.91990 + Atomic weight ratio (AWR) : 126.82100 + Temperature : 900.0 Kelvin + XS temperature : -1.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.72 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is not present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.20351E+00 MeV frac = 1.00000E+00 Product nuclide = 501281 : beta- + + Nuclide 1030 / 1657 : 491290 -- indium 129 (In-129) + + Pointers : 1198690 -1000000 + Primary type : Decay + Nuclide ZAI : 491290 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 128.92150 + Atomic weight ratio (AWR) : 127.81400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.61 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 7.66000E+00 MeV frac = 8.93541E-01 Product nuclide = 501290 : beta- + 2 RTYP = 1 Q = 7.62480E+00 MeV frac = 1.06459E-01 Product nuclide = 501291 : beta- + + Nuclide 1031 / 1657 : 491291 -- indium 129m (In-129m) + + Pointers : 1199498 -1000000 + Primary type : Decay + Nuclide ZAI : 491291 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 128.92150 + Atomic weight ratio (AWR) : 127.81400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.23 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.04000E+00 MeV frac = 9.97000E-01 Product nuclide = 501290 : beta- + + Nuclide 1032 / 1657 : 491300 -- indium 130 (In-130) + + Pointers : 1199981 -1000000 + Primary type : Decay + Nuclide ZAI : 491300 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 129.92513 + Atomic weight ratio (AWR) : 128.80900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.29 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.02490E+01 MeV frac = 7.10609E-01 Product nuclide = 501300 : beta- + 2 RTYP = 1 Q = 8.30216E+00 MeV frac = 2.89391E-01 Product nuclide = 501301 : beta- + + Nuclide 1033 / 1657 : 491301 -- indium 130m (In-130m) + + Pointers : 1200789 -1000000 + Primary type : Decay + Nuclide ZAI : 491301 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 129.92513 + Atomic weight ratio (AWR) : 128.80900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.54 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.35212E+00 MeV frac = 1.00000E+00 Product nuclide = 501301 : beta- + + Nuclide 1034 / 1657 : 491302 -- indium 130m (In-130m) + + Pointers : 3511215 -1000000 + Primary type : Decay + Nuclide ZAI : 491302 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 129.92513 + Atomic weight ratio (AWR) : 128.80900 + Temperature : 900.0 Kelvin + XS temperature : -1.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.54 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is not present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.06490E+01 MeV frac = 1.00000E+00 Product nuclide = 501300 : beta- + + Nuclide 1035 / 1657 : 491310 -- indium 131 (In-131) + + Pointers : 1201244 -1000000 + Primary type : Decay + Nuclide ZAI : 491310 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 130.92673 + Atomic weight ratio (AWR) : 129.80200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.28 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 9.18400E+00 MeV frac = 9.46928E-01 Product nuclide = 501310 : beta- + 2 RTYP = 1 Q = 8.94220E+00 MeV frac = 5.30721E-02 Product nuclide = 501311 : beta- + + Nuclide 1036 / 1657 : 491311 -- indium 131m (In-131m) + + Pointers : 1201800 -1000000 + Primary type : Decay + Nuclide ZAI : 491311 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 130.92673 + Atomic weight ratio (AWR) : 129.80200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.35 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 4 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 4 decay reactions: + + 1 RTYP = 1 Q = 9.52700E+00 MeV frac = 9.79820E-01 Product nuclide = 501310 : beta- + 2 RTYP = 15 Q = 4.28071E+00 MeV frac = 1.00000E-02 Product nuclide = 501300 : beta- + neutron emission + 3 RTYP = 15 Q = 2.33383E+00 MeV frac = 1.00000E-02 Product nuclide = 501301 : beta- + neutron emission + 4 RTYP = 3 Q = 3.50000E-01 MeV frac = 1.80000E-04 Product nuclide = 491310 : IT + + Nuclide 1037 / 1657 : 491312 -- indium 131m (In-131m) + + Pointers : 3512216 -1000000 + Primary type : Decay + Nuclide ZAI : 491312 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 130.92673 + Atomic weight ratio (AWR) : 129.80200 + Temperature : 900.0 Kelvin + XS temperature : -1.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.32 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is not present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 4 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 4 decay reactions: + + 1 RTYP = 1 Q = 1.31970E+01 MeV frac = 9.89720E-01 Product nuclide = 501311 : beta- + 2 RTYP = 15 Q = 8.03071E+00 MeV frac = 1.40000E-04 Product nuclide = 501300 : beta- + neutron emission + 3 RTYP = 15 Q = 6.08383E+00 MeV frac = 1.40000E-04 Product nuclide = 501301 : beta- + neutron emission + 4 RTYP = 3 Q = 4.10000E+00 MeV frac = 1.00000E-02 Product nuclide = 491310 : IT + + Nuclide 1038 / 1657 : 491320 -- indium 132 (In-132) + + Pointers : 1202203 -1000000 + Primary type : Decay + Nuclide ZAI : 491320 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 131.93338 + Atomic weight ratio (AWR) : 130.80000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.207 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.41400E+01 MeV frac = 1.00000E+00 Product nuclide = 501320 : beta- + + Nuclide 1039 / 1657 : 491330 -- indium 133 (In-133) + + Pointers : 1204002 -1000000 + Primary type : Decay + Nuclide ZAI : 491330 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 132.93801 + Atomic weight ratio (AWR) : 131.79600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.165 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.30200E+01 MeV frac = 1.50000E-01 Product nuclide = 501330 : beta- + 2 RTYP = 15 Q = 1.05527E+01 MeV frac = 8.50000E-01 Product nuclide = 501320 : beta- + neutron emission + + Nuclide 1040 / 1657 : 491331 -- indium 133m (In-133m) + + Pointers : 1204259 -1000000 + Primary type : Decay + Nuclide ZAI : 491331 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 132.93801 + Atomic weight ratio (AWR) : 131.79600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.18 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 3.30000E-01 MeV frac = 1.00000E+00 Product nuclide = 491330 : IT + + Nuclide 1041 / 1657 : 491340 -- indium 134 (In-134) + + Pointers : 1204443 -1000000 + Primary type : Decay + Nuclide ZAI : 491340 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 133.94466 + Atomic weight ratio (AWR) : 132.79400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.14 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 1 Q = 1.47800E+01 MeV frac = 3.10000E-01 Product nuclide = 501340 : beta- + 2 RTYP = 15 Q = 1.08587E+01 MeV frac = 6.50000E-01 Product nuclide = 501330 : beta- + neutron emission + 3 RTYP = 155 Q = 8.39140E+00 MeV frac = 4.00000E-02 Product nuclide = 501320 : beta- + neutron emission + neutron emission + + Nuclide 1042 / 1657 : 491350 -- indium 135 (In-135) + + Pointers : 1204773 -1000000 + Primary type : Decay + Nuclide ZAI : 491350 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 134.94929 + Atomic weight ratio (AWR) : 133.79000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 92 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.36000E+01 MeV frac = 1.00000E+00 Product nuclide = 501350 : beta- + + Nuclide 1043 / 1657 : 501120 -- tin 112 (Sn-112) + + Pointers : 1204957 -1000000 + Primary type : Decay + Nuclide ZAI : 501120 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 111.90533 + Atomic weight ratio (AWR) : 110.94400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1044 / 1657 : 501130 -- tin 113 (Sn-113) + + Pointers : 1205063 -1000000 + Primary type : Decay + Nuclide ZAI : 501130 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 112.90491 + Atomic weight ratio (AWR) : 111.93500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.94E+06 seconds (115 days) + Specific ingestion toxicity : 7.30E-10 Sv/Bq + Specific inhalation toxicity : 2.70E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 1.03600E+00 MeV frac = 4.00005E-08 Product nuclide = 49113.82c : EC/beta+ + 2 RTYP = 2 Q = 6.44301E-01 MeV frac = 1.00000E+00 Product nuclide = 491131 : EC/beta+ + + Nuclide 1045 / 1657 : 501140 -- tin 114 (Sn-114) + + Pointers : 1205549 -1000000 + Primary type : Decay + Nuclide ZAI : 501140 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 113.90248 + Atomic weight ratio (AWR) : 112.92400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1046 / 1657 : 501171 -- tin 117m (Sn-117m) + + Pointers : 1214402 -1000000 + Primary type : Decay + Nuclide ZAI : 501171 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 116.90326 + Atomic weight ratio (AWR) : 115.89900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.21E+06 seconds (14 days) + Specific ingestion toxicity : 7.10E-10 Sv/Bq + Specific inhalation toxicity : 2.40E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 3.14580E-01 MeV frac = 1.00000E+00 Product nuclide = 50117.82c : IT + + Nuclide 1047 / 1657 : 501191 -- tin 119m (Sn-119m) + + Pointers : 1220702 -1000000 + Primary type : Decay + Nuclide ZAI : 501191 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 118.90344 + Atomic weight ratio (AWR) : 117.88200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.53E+07 seconds (293 days) + Specific ingestion toxicity : 3.40E-10 Sv/Bq + Specific inhalation toxicity : 2.20E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 8.95300E-02 MeV frac = 1.00000E+00 Product nuclide = 50119.82c : IT + + Nuclide 1048 / 1657 : 501210 -- tin 121 (Sn-121) + + Pointers : 1224193 -1000000 + Primary type : Decay + Nuclide ZAI : 501210 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 120.90463 + Atomic weight ratio (AWR) : 119.86600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.73E+04 seconds (1.13 days) + Specific ingestion toxicity : 2.30E-10 Sv/Bq + Specific inhalation toxicity : 2.30E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.90600E-01 MeV frac = 1.00000E+00 Product nuclide = 51121.82c : beta- + + Nuclide 1049 / 1657 : 501211 -- tin 121m (Sn-121m) + + Pointers : 1224410 -1000000 + Primary type : Decay + Nuclide ZAI : 501211 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 120.90463 + Atomic weight ratio (AWR) : 119.86600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.39E+09 seconds (43.9 years) + Specific ingestion toxicity : 3.80E-10 Sv/Bq + Specific inhalation toxicity : 4.50E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 3.97300E-01 MeV frac = 2.24000E-01 Product nuclide = 51121.82c : beta- + 2 RTYP = 3 Q = 6.30000E-03 MeV frac = 7.76000E-01 Product nuclide = 501210 : IT + + Nuclide 1050 / 1657 : 501231 -- tin 123m (Sn-123m) + + Pointers : 1230363 -1000000 + Primary type : Decay + Nuclide ZAI : 501231 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 122.90583 + Atomic weight ratio (AWR) : 121.85000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.40E+03 seconds (40.1 minutes) + Specific ingestion toxicity : 3.80E-11 Sv/Bq + Specific inhalation toxicity : 2.70E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.42820E+00 MeV frac = 1.00000E+00 Product nuclide = 51123.82c : beta- + + Nuclide 1051 / 1657 : 501251 -- tin 125m (Sn-125m) + + Pointers : 1238011 -1000000 + Primary type : Decay + Nuclide ZAI : 501251 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 124.90803 + Atomic weight ratio (AWR) : 123.83500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.71E+02 seconds (9.52 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.38450E+00 MeV frac = 1.00000E+00 Product nuclide = 51125.82c : beta- + + Nuclide 1052 / 1657 : 501270 -- tin 127 (Sn-127) + + Pointers : 1242108 -1000000 + Primary type : Decay + Nuclide ZAI : 501270 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 126.91023 + Atomic weight ratio (AWR) : 125.82000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.56E+03 seconds (2.1 hours) + Specific ingestion toxicity : 2.00E-10 Sv/Bq + Specific inhalation toxicity : 1.30E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.20100E+00 MeV frac = 1.00000E+00 Product nuclide = 511270 : beta- + + Nuclide 1053 / 1657 : 501271 -- tin 127m (Sn-127m) + + Pointers : 1242292 -1000000 + Primary type : Decay + Nuclide ZAI : 501271 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 126.91023 + Atomic weight ratio (AWR) : 125.82000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.48E+02 seconds (4.13 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.20570E+00 MeV frac = 1.00000E+00 Product nuclide = 511270 : beta- + + Nuclide 1054 / 1657 : 501280 -- tin 128 (Sn-128) + + Pointers : 1242476 -1000000 + Primary type : Decay + Nuclide ZAI : 501280 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 127.91082 + Atomic weight ratio (AWR) : 126.81200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.54E+03 seconds (59.1 minutes) + Specific ingestion toxicity : 1.50E-10 Sv/Bq + Specific inhalation toxicity : 9.20E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.27400E+00 MeV frac = 1.00000E+00 Product nuclide = 511280 : beta- + + Nuclide 1055 / 1657 : 501281 -- tin 128m (Sn-128m) + + Pointers : 1243197 -1000000 + Primary type : Decay + Nuclide ZAI : 501281 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 127.91082 + Atomic weight ratio (AWR) : 126.81200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 2.09150E+00 MeV frac = 1.00000E+00 Product nuclide = 501280 : IT + + Nuclide 1056 / 1657 : 501290 -- tin 129 (Sn-129) + + Pointers : 1243596 -1000000 + Primary type : Decay + Nuclide ZAI : 501290 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 128.91343 + Atomic weight ratio (AWR) : 127.80600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.34E+02 seconds (2.23 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.03000E+00 MeV frac = 1.00000E+00 Product nuclide = 511290 : beta- + + Nuclide 1057 / 1657 : 501291 -- tin 129m (Sn-129m) + + Pointers : 1246697 -1000000 + Primary type : Decay + Nuclide ZAI : 501291 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 128.91343 + Atomic weight ratio (AWR) : 127.80600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.32E+02 seconds (7.2 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 2.21400E+00 MeV frac = 3.10000E-01 Product nuclide = 511291 : beta- + 2 RTYP = 1 Q = 4.06500E+00 MeV frac = 6.90000E-01 Product nuclide = 511290 : beta- + + Nuclide 1058 / 1657 : 501300 -- tin 130 (Sn-130) + + Pointers : 1250571 -1000000 + Primary type : Decay + Nuclide ZAI : 501300 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 129.91403 + Atomic weight ratio (AWR) : 128.79800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.24E+02 seconds (3.73 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.14800E+00 MeV frac = 1.00000E+00 Product nuclide = 511301 : beta- + + Nuclide 1059 / 1657 : 501301 -- tin 130m (Sn-130m) + + Pointers : 1252048 -1000000 + Primary type : Decay + Nuclide ZAI : 501301 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 129.91403 + Atomic weight ratio (AWR) : 128.79800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.02E+02 seconds (1.7 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 4.09500E+00 MeV frac = 1.60000E-01 Product nuclide = 511301 : beta- + 2 RTYP = 1 Q = 4.10000E+00 MeV frac = 8.40000E-01 Product nuclide = 511300 : beta- + + Nuclide 1060 / 1657 : 501310 -- tin 131 (Sn-131) + + Pointers : 1255110 -1000000 + Primary type : Decay + Nuclide ZAI : 501310 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 130.91664 + Atomic weight ratio (AWR) : 129.79200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 56 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.67400E+00 MeV frac = 1.00000E+00 Product nuclide = 511310 : beta- + + Nuclide 1061 / 1657 : 501311 -- tin 131m (Sn-131m) + + Pointers : 1255294 -1000000 + Primary type : Decay + Nuclide ZAI : 501311 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 130.91664 + Atomic weight ratio (AWR) : 129.79200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 58.4 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 4.75400E+00 MeV frac = 9.99996E-01 Product nuclide = 511310 : beta- + 2 RTYP = 3 Q = 8.00000E-02 MeV frac = 3.99998E-06 Product nuclide = 501310 : IT + + Nuclide 1062 / 1657 : 501320 -- tin 132 (Sn-132) + + Pointers : 1255551 -1000000 + Primary type : Decay + Nuclide ZAI : 501320 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 131.91825 + Atomic weight ratio (AWR) : 130.78500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 39.7 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.11900E+00 MeV frac = 1.00000E+00 Product nuclide = 511320 : beta- + + Nuclide 1063 / 1657 : 501330 -- tin 133 (Sn-133) + + Pointers : 1256636 -1000000 + Primary type : Decay + Nuclide ZAI : 501330 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 132.92389 + Atomic weight ratio (AWR) : 131.78200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.46 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.09500E+00 MeV frac = 1.00000E+00 Product nuclide = 511330 : beta- + + Nuclide 1064 / 1657 : 501340 -- tin 134 (Sn-134) + + Pointers : 1259639 -1000000 + Primary type : Decay + Nuclide ZAI : 501340 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 133.92852 + Atomic weight ratio (AWR) : 132.77800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.05 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 7.37000E+00 MeV frac = 8.30000E-01 Product nuclide = 511340 : beta- + 2 RTYP = 15 Q = 4.07170E+00 MeV frac = 1.70000E-01 Product nuclide = 511330 : beta- + neutron emission + + Nuclide 1065 / 1657 : 501350 -- tin 135 (Sn-135) + + Pointers : 1259896 -1000000 + Primary type : Decay + Nuclide ZAI : 501350 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 134.93516 + Atomic weight ratio (AWR) : 133.77600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.53 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 1 Q = 8.91000E+00 MeV frac = 7.90000E-01 Product nuclide = 511350 : beta- + 2 RTYP = 15 Q = 5.29870E+00 MeV frac = 1.05000E-01 Product nuclide = 511340 : beta- + neutron emission + 3 RTYP = 15 Q = 5.21870E+00 MeV frac = 1.05000E-01 Product nuclide = 511341 : beta- + neutron emission + + Nuclide 1066 / 1657 : 501360 -- tin 136 (Sn-136) + + Pointers : 1260226 -1000000 + Primary type : Decay + Nuclide ZAI : 501360 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 135.93979 + Atomic weight ratio (AWR) : 134.77200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.25 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.38000E+00 MeV frac = 7.00000E-01 Product nuclide = 511360 : beta- + 2 RTYP = 15 Q = 5.13870E+00 MeV frac = 3.00000E-01 Product nuclide = 511350 : beta- + neutron emission + + Nuclide 1067 / 1657 : 501370 -- tin 137 (Sn-137) + + Pointers : 1260483 -1000000 + Primary type : Decay + Nuclide ZAI : 501370 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 136.94644 + Atomic weight ratio (AWR) : 135.77000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.19 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 9.95000E+00 MeV frac = 4.20000E-01 Product nuclide = 511370 : beta- + 2 RTYP = 15 Q = 6.49870E+00 MeV frac = 5.80000E-01 Product nuclide = 511360 : beta- + neutron emission + + Nuclide 1068 / 1657 : 511180 -- antimony 118 (Sb-118) + + Pointers : 1260740 -1000000 + Primary type : Decay + Nuclide ZAI : 511180 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 117.90587 + Atomic weight ratio (AWR) : 116.89300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.16E+02 seconds (3.6 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 3.65660E+00 MeV frac = 1.00000E+00 Product nuclide = 50118.82c : EC/beta+ + + Nuclide 1069 / 1657 : 511181 -- antimony 118m (Sb-118m) + + Pointers : 1261321 -1000000 + Primary type : Decay + Nuclide ZAI : 511181 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 117.90587 + Atomic weight ratio (AWR) : 116.89300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.80E+04 seconds (5 hours) + Specific ingestion toxicity : 2.10E-10 Sv/Bq + Specific inhalation toxicity : 1.20E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 3.90660E+00 MeV frac = 1.00000E+00 Product nuclide = 50118.82c : EC/beta+ + + Nuclide 1070 / 1657 : 511190 -- antimony 119 (Sb-119) + + Pointers : 1261916 -1000000 + Primary type : Decay + Nuclide ZAI : 511190 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 118.90445 + Atomic weight ratio (AWR) : 117.88300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.38E+05 seconds (1.6 days) + Specific ingestion toxicity : 8.00E-11 Sv/Bq + Specific inhalation toxicity : 3.60E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 5.93000E-01 MeV frac = 1.00000E+00 Product nuclide = 50119.82c : EC/beta+ + + Nuclide 1071 / 1657 : 511191 -- antimony 119m (Sb-119m) + + Pointers : 1262301 -1000000 + Primary type : Decay + Nuclide ZAI : 511191 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 118.90445 + Atomic weight ratio (AWR) : 117.88300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.85 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 2.85200E+00 MeV frac = 1.00000E+00 Product nuclide = 511190 : IT + + Nuclide 1072 / 1657 : 511200 -- antimony 120 (Sb-120) + + Pointers : 1262485 -1000000 + Primary type : Decay + Nuclide ZAI : 511200 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 119.90505 + Atomic weight ratio (AWR) : 118.87500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.54E+02 seconds (15.9 minutes) + Specific ingestion toxicity : 1.40E-11 Sv/Bq + Specific inhalation toxicity : 7.30E-12 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 2.68100E+00 MeV frac = 1.00000E+00 Product nuclide = 50120.82c : EC/beta+ + + Nuclide 1073 / 1657 : 511201 -- antimony 120m (Sb-120m) + + Pointers : 1263010 -1000000 + Primary type : Decay + Nuclide ZAI : 511201 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 119.90505 + Atomic weight ratio (AWR) : 118.87500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.98E+05 seconds (5.76 days) + Specific ingestion toxicity : 1.20E-09 Sv/Bq + Specific inhalation toxicity : 1.10E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 2.88000E+00 MeV frac = 1.00000E+00 Product nuclide = 50120.82c : EC/beta+ + + Nuclide 1074 / 1657 : 511220 -- antimony 122 (Sb-122) + + Pointers : 1266422 -1000000 + Primary type : Decay + Nuclide ZAI : 511220 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 121.90523 + Atomic weight ratio (AWR) : 120.85800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.33E+05 seconds (2.7 days) + Specific ingestion toxicity : 1.70E-09 Sv/Bq + Specific inhalation toxicity : 1.10E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.98300E+00 MeV frac = 9.76300E-01 Product nuclide = 52122.82c : beta- + 2 RTYP = 2 Q = 1.62000E+00 MeV frac = 2.37000E-02 Product nuclide = 50122.82c : EC/beta+ + + Nuclide 1075 / 1657 : 511221 -- antimony 122m (Sb-122m) + + Pointers : 1267048 -1000000 + Primary type : Decay + Nuclide ZAI : 511221 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 121.90523 + Atomic weight ratio (AWR) : 120.85800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.51E+02 seconds (4.19 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.63560E-01 MeV frac = 1.00000E+00 Product nuclide = 511220 : IT + + Nuclide 1076 / 1657 : 511241 -- antimony 124m (Sb-124m) + + Pointers : 1275509 -1000000 + Primary type : Decay + Nuclide ZAI : 511241 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 123.90642 + Atomic weight ratio (AWR) : 122.84200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.30E+01 seconds (1.55 minutes) + Specific ingestion toxicity : 8.00E-12 Sv/Bq + Specific inhalation toxicity : 5.90E-12 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 2.91600E+00 MeV frac = 2.50000E-01 Product nuclide = 52124.82c : beta- + 2 RTYP = 3 Q = 1.08600E-02 MeV frac = 7.50000E-01 Product nuclide = 51124.82c : IT + + Nuclide 1077 / 1657 : 511242 -- antimony 124m (Sb-124m) + + Pointers : 3512619 -1000000 + Primary type : Decay + Nuclide ZAI : 511242 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 123.90642 + Atomic weight ratio (AWR) : 122.84200 + Temperature : 900.0 Kelvin + XS temperature : -1.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.21E+03 seconds (20.2 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is not present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 2.59800E-02 MeV frac = 1.00000E+00 Product nuclide = 511241 : IT + + Nuclide 1078 / 1657 : 511261 -- antimony 126m (Sb-126m) + + Pointers : 1285134 -1000000 + Primary type : Decay + Nuclide ZAI : 511261 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 125.90761 + Atomic weight ratio (AWR) : 124.82600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.15E+03 seconds (19.1 minutes) + Specific ingestion toxicity : 3.60E-11 Sv/Bq + Specific inhalation toxicity : 2.00E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 1.77000E-02 MeV frac = 1.40000E-01 Product nuclide = 51126.82c : IT + 2 RTYP = 1 Q = 3.69000E+00 MeV frac = 8.60000E-01 Product nuclide = 52126.82c : beta- + + Nuclide 1079 / 1657 : 511262 -- antimony 126m (Sb-126m) + + Pointers : 3503389 -1000000 + Primary type : Decay + Nuclide ZAI : 511262 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 125.90761 + Atomic weight ratio (AWR) : 124.82600 + Temperature : 900.0 Kelvin + XS temperature : -1.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 11 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is not present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 2.27000E-02 MeV frac = 1.00000E+00 Product nuclide = 511261 : IT + + Nuclide 1080 / 1657 : 511270 -- antimony 127 (Sb-127) + + Pointers : 1286152 -1000000 + Primary type : Decay + Nuclide ZAI : 511270 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 126.90720 + Atomic weight ratio (AWR) : 125.81700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.33E+05 seconds (3.85 days) + Specific ingestion toxicity : 1.70E-09 Sv/Bq + Specific inhalation toxicity : 1.90E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.58200E+00 MeV frac = 8.31773E-01 Product nuclide = 521270 : beta- + 2 RTYP = 1 Q = 1.49379E+00 MeV frac = 1.68227E-01 Product nuclide = 52527.82c : beta- + + Nuclide 1081 / 1657 : 511280 -- antimony 128 (Sb-128) + + Pointers : 1289172 -1000000 + Primary type : Decay + Nuclide ZAI : 511280 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 127.90880 + Atomic weight ratio (AWR) : 126.81000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.24E+04 seconds (9.01 hours) + Specific ingestion toxicity : 7.60E-10 Sv/Bq + Specific inhalation toxicity : 4.20E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.38400E+00 MeV frac = 1.00000E+00 Product nuclide = 52128.82c : beta- + + Nuclide 1082 / 1657 : 511281 -- antimony 128m (Sb-128m) + + Pointers : 1290509 -1000000 + Primary type : Decay + Nuclide ZAI : 511281 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 127.90880 + Atomic weight ratio (AWR) : 126.81000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.24E+02 seconds (10.4 minutes) + Specific ingestion toxicity : 3.30E-11 Sv/Bq + Specific inhalation toxicity : 1.50E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 1.00000E-02 MeV frac = 3.60000E-02 Product nuclide = 511280 : IT + 2 RTYP = 1 Q = 4.39400E+00 MeV frac = 9.64000E-01 Product nuclide = 52128.82c : beta- + + Nuclide 1083 / 1657 : 511290 -- antimony 129 (Sb-129) + + Pointers : 1291051 -1000000 + Primary type : Decay + Nuclide ZAI : 511290 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 128.90940 + Atomic weight ratio (AWR) : 127.80200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.57E+04 seconds (4.36 hours) + Specific ingestion toxicity : 4.20E-10 Sv/Bq + Specific inhalation toxicity : 2.50E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 2.37700E+00 MeV frac = 8.34000E-01 Product nuclide = 521290 : beta- + 2 RTYP = 1 Q = 2.27200E+00 MeV frac = 1.66000E-01 Product nuclide = 52529.82c : beta- + + Nuclide 1084 / 1657 : 511291 -- antimony 129m (Sb-129m) + + Pointers : 1293497 -1000000 + Primary type : Decay + Nuclide ZAI : 511291 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 128.90940 + Atomic weight ratio (AWR) : 127.80200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.06E+03 seconds (17.7 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 1 Q = 4.22800E+00 MeV frac = 2.00000E-02 Product nuclide = 521290 : beta- + 2 RTYP = 1 Q = 4.12300E+00 MeV frac = 8.30000E-01 Product nuclide = 52529.82c : beta- + 3 RTYP = 3 Q = 1.85130E+00 MeV frac = 1.50000E-01 Product nuclide = 511290 : IT + + Nuclide 1085 / 1657 : 511300 -- antimony 130 (Sb-130) + + Pointers : 1295246 -1000000 + Primary type : Decay + Nuclide ZAI : 511300 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 129.91201 + Atomic weight ratio (AWR) : 128.79600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.37E+03 seconds (39.5 minutes) + Specific ingestion toxicity : 9.10E-11 Sv/Bq + Specific inhalation toxicity : 5.30E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.95900E+00 MeV frac = 1.00000E+00 Product nuclide = 52130.82c : beta- + + Nuclide 1086 / 1657 : 511301 -- antimony 130m (Sb-130m) + + Pointers : 1296709 -1000000 + Primary type : Decay + Nuclide ZAI : 511301 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 129.91201 + Atomic weight ratio (AWR) : 128.79600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.78E+02 seconds (6.3 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.06420E+00 MeV frac = 1.00000E+00 Product nuclide = 52130.82c : beta- + + Nuclide 1087 / 1657 : 511310 -- antimony 131 (Sb-131) + + Pointers : 1296893 -1000000 + Primary type : Decay + Nuclide ZAI : 511310 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 130.91160 + Atomic weight ratio (AWR) : 129.78700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.38E+03 seconds (23 minutes) + Specific ingestion toxicity : 1.00E-10 Sv/Bq + Specific inhalation toxicity : 4.40E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 3.19000E+00 MeV frac = 9.19939E-01 Product nuclide = 521310 : beta- + 2 RTYP = 1 Q = 3.00775E+00 MeV frac = 8.00613E-02 Product nuclide = 521311 : beta- + + Nuclide 1088 / 1657 : 511320 -- antimony 132 (Sb-132) + + Pointers : 1298681 -1000000 + Primary type : Decay + Nuclide ZAI : 511320 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 131.91421 + Atomic weight ratio (AWR) : 130.78100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.67E+02 seconds (2.79 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.49000E+00 MeV frac = 1.00000E+00 Product nuclide = 52132.82c : beta- + + Nuclide 1089 / 1657 : 511321 -- antimony 132m (Sb-132m) + + Pointers : 1299724 -1000000 + Primary type : Decay + Nuclide ZAI : 511321 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 131.91421 + Atomic weight ratio (AWR) : 130.78100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.46E+02 seconds (4.1 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.69000E+00 MeV frac = 1.00000E+00 Product nuclide = 52132.82c : beta- + + Nuclide 1090 / 1657 : 511330 -- antimony 133 (Sb-133) + + Pointers : 1300459 -1000000 + Primary type : Decay + Nuclide ZAI : 511330 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 132.91481 + Atomic weight ratio (AWR) : 131.77300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.50E+02 seconds (2.5 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 4.00300E+00 MeV frac = 8.27113E-01 Product nuclide = 521330 : beta- + 2 RTYP = 1 Q = 3.66874E+00 MeV frac = 1.72887E-01 Product nuclide = 521331 : beta- + + Nuclide 1091 / 1657 : 511340 -- antimony 134 (Sb-134) + + Pointers : 1301463 -1000000 + Primary type : Decay + Nuclide ZAI : 511340 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 133.92045 + Atomic weight ratio (AWR) : 132.77000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.78 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.39400E+00 MeV frac = 1.00000E+00 Product nuclide = 521340 : beta- + + Nuclide 1092 / 1657 : 511341 -- antimony 134m (Sb-134m) + + Pointers : 1302002 -1000000 + Primary type : Decay + Nuclide ZAI : 511341 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 133.92045 + Atomic weight ratio (AWR) : 132.77000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 10.1 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 1 Q = 8.46900E+00 MeV frac = 9.99090E-01 Product nuclide = 521340 : beta- + 2 RTYP = 15 Q = 7.83702E-01 MeV frac = 4.55000E-04 Product nuclide = 521330 : beta- + neutron emission + 3 RTYP = 15 Q = 4.49442E-01 MeV frac = 4.55000E-04 Product nuclide = 521331 : beta- + neutron emission + + Nuclide 1093 / 1657 : 511350 -- antimony 135 (Sb-135) + + Pointers : 1302332 -1000000 + Primary type : Decay + Nuclide ZAI : 511350 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 134.92508 + Atomic weight ratio (AWR) : 133.76600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.74 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.12000E+00 MeV frac = 8.43000E-01 Product nuclide = 521350 : beta- + 2 RTYP = 15 Q = 4.62000E+00 MeV frac = 1.57000E-01 Product nuclide = 521340 : beta- + neutron emission + + Nuclide 1094 / 1657 : 511360 -- antimony 136 (Sb-136) + + Pointers : 1304484 -1000000 + Primary type : Decay + Nuclide ZAI : 511360 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 135.93072 + Atomic weight ratio (AWR) : 134.76300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.923 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 1 Q = 9.55000E+00 MeV frac = 8.34200E-01 Product nuclide = 521360 : beta- + 2 RTYP = 15 Q = 4.87870E+00 MeV frac = 1.63000E-01 Product nuclide = 521350 : beta- + neutron emission + 3 RTYP = 155 Q = 1.53640E+00 MeV frac = 2.80000E-03 Product nuclide = 521340 : beta- + neutron emission + neutron emission + + Nuclide 1095 / 1657 : 511370 -- antimony 137 (Sb-137) + + Pointers : 1304814 -1000000 + Primary type : Decay + Nuclide ZAI : 511370 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 136.93535 + Atomic weight ratio (AWR) : 135.75900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.45 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 9.30000E+00 MeV frac = 5.10000E-01 Product nuclide = 521370 : beta- + 2 RTYP = 15 Q = 6.09870E+00 MeV frac = 4.90000E-01 Product nuclide = 521360 : beta- + neutron emission + + Nuclide 1096 / 1657 : 511380 -- antimony 138 (Sb-138) + + Pointers : 1305071 -1000000 + Primary type : Decay + Nuclide ZAI : 511380 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 137.94099 + Atomic weight ratio (AWR) : 136.75600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.07800E+01 MeV frac = 1.00000E+00 Product nuclide = 521380 : beta- + + Nuclide 1097 / 1657 : 511390 -- antimony 139 (Sb-139) + + Pointers : 1305255 -1000000 + Primary type : Decay + Nuclide ZAI : 511390 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 138.94562 + Atomic weight ratio (AWR) : 137.75200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.04800E+01 MeV frac = 1.00000E+00 Product nuclide = 521390 : beta- + + Nuclide 1098 / 1657 : 521210 -- tellurium 121 (Te-121) + + Pointers : 1307248 -1000000 + Primary type : Decay + Nuclide ZAI : 521210 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 120.90463 + Atomic weight ratio (AWR) : 119.86600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.66E+06 seconds (19.2 days) + Specific ingestion toxicity : 4.30E-10 Sv/Bq + Specific inhalation toxicity : 4.10E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 1.03600E+00 MeV frac = 1.00000E+00 Product nuclide = 51121.82c : EC/beta+ + + Nuclide 1099 / 1657 : 521211 -- tellurium 121m (Te-121m) + + Pointers : 1307871 -1000000 + Primary type : Decay + Nuclide ZAI : 521211 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 120.90463 + Atomic weight ratio (AWR) : 119.86600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.33E+07 seconds (154 days) + Specific ingestion toxicity : 2.30E-09 Sv/Bq + Specific inhalation toxicity : 5.70E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 1.33000E+00 MeV frac = 1.13000E-01 Product nuclide = 51121.82c : EC/beta+ + 2 RTYP = 3 Q = 2.93991E-01 MeV frac = 8.87000E-01 Product nuclide = 521210 : IT + + Nuclide 1100 / 1657 : 521231 -- tellurium 123m (Te-123m) + + Pointers : 1313691 -1000000 + Primary type : Decay + Nuclide ZAI : 521231 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 122.90381 + Atomic weight ratio (AWR) : 121.84800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.03E+07 seconds (119 days) + Specific ingestion toxicity : 1.40E-09 Sv/Bq + Specific inhalation toxicity : 5.10E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 2.47430E-01 MeV frac = 1.00000E+00 Product nuclide = 52123.82c : IT + + Nuclide 1101 / 1657 : 521251 -- tellurium 125m (Te-125m) + + Pointers : 1318969 -1000000 + Primary type : Decay + Nuclide ZAI : 521251 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 124.90399 + Atomic weight ratio (AWR) : 123.83100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.96E+06 seconds (57.4 days) + Specific ingestion toxicity : 8.70E-10 Sv/Bq + Specific inhalation toxicity : 4.20E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.44766E-01 MeV frac = 1.00000E+00 Product nuclide = 52125.82c : IT + + Nuclide 1102 / 1657 : 521270 -- tellurium 127 (Te-127) + + Pointers : 1322140 -1000000 + Primary type : Decay + Nuclide ZAI : 521270 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 126.90518 + Atomic weight ratio (AWR) : 125.81500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.37E+04 seconds (9.35 hours) + Specific ingestion toxicity : 1.70E-10 Sv/Bq + Specific inhalation toxicity : 1.40E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.02000E-01 MeV frac = 1.00000E+00 Product nuclide = 53127.82c : beta- + + Nuclide 1103 / 1657 : 521290 -- tellurium 129 (Te-129) + + Pointers : 1326979 -1000000 + Primary type : Decay + Nuclide ZAI : 521290 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 128.90637 + Atomic weight ratio (AWR) : 127.79900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.18E+03 seconds (1.16 hours) + Specific ingestion toxicity : 6.30E-11 Sv/Bq + Specific inhalation toxicity : 3.90E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.49790E+00 MeV frac = 1.00000E+00 Product nuclide = 53129.82c : beta- + + Nuclide 1104 / 1657 : 521310 -- tellurium 131 (Te-131) + + Pointers : 1334798 -1000000 + Primary type : Decay + Nuclide ZAI : 521310 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 130.90857 + Atomic weight ratio (AWR) : 129.78400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.50E+03 seconds (25 minutes) + Specific ingestion toxicity : 8.70E-11 Sv/Bq + Specific inhalation toxicity : 2.80E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.24900E+00 MeV frac = 1.00000E+00 Product nuclide = 53131.82c : beta- + + Nuclide 1105 / 1657 : 521311 -- tellurium 131m (Te-131m) + + Pointers : 1336079 -1000000 + Primary type : Decay + Nuclide ZAI : 521311 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 130.90857 + Atomic weight ratio (AWR) : 129.78400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.08E+05 seconds (1.25 days) + Specific ingestion toxicity : 1.90E-09 Sv/Bq + Specific inhalation toxicity : 9.40E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 1.82320E-01 MeV frac = 2.10000E-01 Product nuclide = 521310 : IT + 2 RTYP = 1 Q = 2.43132E+00 MeV frac = 7.90000E-01 Product nuclide = 53131.82c : beta- + + Nuclide 1106 / 1657 : 521330 -- tellurium 133 (Te-133) + + Pointers : 1341214 -1000000 + Primary type : Decay + Nuclide ZAI : 521330 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 132.91077 + Atomic weight ratio (AWR) : 131.76900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.47E+02 seconds (12.4 minutes) + Specific ingestion toxicity : 7.20E-11 Sv/Bq + Specific inhalation toxicity : 2.00E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.92000E+00 MeV frac = 1.00000E+00 Product nuclide = 531330 : beta- + + Nuclide 1107 / 1657 : 521331 -- tellurium 133m (Te-133m) + + Pointers : 1344595 -1000000 + Primary type : Decay + Nuclide ZAI : 521331 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 132.91077 + Atomic weight ratio (AWR) : 131.76900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.32E+03 seconds (55.4 minutes) + Specific ingestion toxicity : 2.80E-10 Sv/Bq + Specific inhalation toxicity : 8.70E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 3.25426E+00 MeV frac = 8.25000E-01 Product nuclide = 531330 : beta- + 2 RTYP = 3 Q = 3.34270E-01 MeV frac = 1.75000E-01 Product nuclide = 521330 : IT + + Nuclide 1108 / 1657 : 521340 -- tellurium 134 (Te-134) + + Pointers : 1349029 -1000000 + Primary type : Decay + Nuclide ZAI : 521340 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 133.91137 + Atomic weight ratio (AWR) : 132.76100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.51E+03 seconds (41.8 minutes) + Specific ingestion toxicity : 1.10E-10 Sv/Bq + Specific inhalation toxicity : 6.80E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.55000E+00 MeV frac = 1.00000E+00 Product nuclide = 531340 : beta- + + Nuclide 1109 / 1657 : 521350 -- tellurium 135 (Te-135) + + Pointers : 1349848 -1000000 + Primary type : Decay + Nuclide ZAI : 521350 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 134.91600 + Atomic weight ratio (AWR) : 133.75700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 19 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.88800E+00 MeV frac = 1.00000E+00 Product nuclide = 53135.82c : beta- + + Nuclide 1110 / 1657 : 521360 -- tellurium 136 (Te-136) + + Pointers : 1350891 -1000000 + Primary type : Decay + Nuclide ZAI : 521360 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 135.91962 + Atomic weight ratio (AWR) : 134.75200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 17.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.07000E+00 MeV frac = 1.00000E+00 Product nuclide = 531360 : beta- + + Nuclide 1111 / 1657 : 521370 -- tellurium 137 (Te-137) + + Pointers : 1351752 -1000000 + Primary type : Decay + Nuclide ZAI : 521370 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 136.92526 + Atomic weight ratio (AWR) : 135.74900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.49 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 1 Q = 6.94300E+00 MeV frac = 9.70100E-01 Product nuclide = 531370 : beta- + 2 RTYP = 15 Q = 1.86870E+00 MeV frac = 1.49500E-02 Product nuclide = 531360 : beta- + neutron emission + 3 RTYP = 15 Q = 1.21870E+00 MeV frac = 1.49500E-02 Product nuclide = 531361 : beta- + neutron emission + + Nuclide 1112 / 1657 : 521380 -- tellurium 138 (Te-138) + + Pointers : 1352082 -1000000 + Primary type : Decay + Nuclide ZAI : 521380 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 137.92888 + Atomic weight ratio (AWR) : 136.74400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.4 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 6.40000E+00 MeV frac = 9.37000E-01 Product nuclide = 531380 : beta- + 2 RTYP = 15 Q = 2.50171E+00 MeV frac = 6.30000E-02 Product nuclide = 531370 : beta- + neutron emission + + Nuclide 1113 / 1657 : 521390 -- tellurium 139 (Te-139) + + Pointers : 1352339 -1000000 + Primary type : Decay + Nuclide ZAI : 521390 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 138.93452 + Atomic weight ratio (AWR) : 137.74100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.04000E+00 MeV frac = 1.00000E+00 Product nuclide = 531390 : beta- + + Nuclide 1114 / 1657 : 521400 -- tellurium 140 (Te-140) + + Pointers : 1352523 -1000000 + Primary type : Decay + Nuclide ZAI : 521400 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 139.93915 + Atomic weight ratio (AWR) : 138.73700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.31000E+00 MeV frac = 1.00000E+00 Product nuclide = 531400 : beta- + + Nuclide 1115 / 1657 : 521410 -- tellurium 141 (Te-141) + + Pointers : 1352707 -1000000 + Primary type : Decay + Nuclide ZAI : 521410 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 140.94479 + Atomic weight ratio (AWR) : 139.73400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 100 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.96000E+00 MeV frac = 1.00000E+00 Product nuclide = 531410 : beta- + + Nuclide 1116 / 1657 : 521420 -- tellurium 142 (Te-142) + + Pointers : 1352891 -1000000 + Primary type : Decay + Nuclide ZAI : 521420 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 141.94942 + Atomic weight ratio (AWR) : 140.73000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 50 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.29000E+00 MeV frac = 1.00000E+00 Product nuclide = 531420 : beta- + + Nuclide 1117 / 1657 : 531250 -- iodine 125 (I-125) + + Pointers : 1353075 -1000000 + Primary type : Decay + Nuclide ZAI : 531250 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 124.90500 + Atomic weight ratio (AWR) : 123.83200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.13E+06 seconds (59.4 days) + Specific ingestion toxicity : 1.50E-08 Sv/Bq + Specific inhalation toxicity : 5.10E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 1.85770E-01 MeV frac = 1.00000E+00 Product nuclide = 52125.82c : EC/beta+ + + Nuclide 1118 / 1657 : 531260 -- iodine 126 (I-126) + + Pointers : 1353446 -1000000 + Primary type : Decay + Nuclide ZAI : 531260 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 125.90560 + Atomic weight ratio (AWR) : 124.82400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.12E+06 seconds (13 days) + Specific ingestion toxicity : 2.90E-08 Sv/Bq + Specific inhalation toxicity : 9.80E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.25100E+00 MeV frac = 4.37000E-01 Product nuclide = 541260 : beta- + 2 RTYP = 2 Q = 2.15600E+00 MeV frac = 5.63000E-01 Product nuclide = 52126.82c : EC/beta+ + + Nuclide 1119 / 1657 : 531280 -- iodine 128 (I-128) + + Pointers : 1366258 -1000000 + Primary type : Decay + Nuclide ZAI : 531280 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 127.90578 + Atomic weight ratio (AWR) : 126.80700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.50E+03 seconds (25 minutes) + Specific ingestion toxicity : 4.60E-11 Sv/Bq + Specific inhalation toxicity : 2.00E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 1.25200E+00 MeV frac = 6.90000E-02 Product nuclide = 52128.82c : EC/beta+ + 2 RTYP = 1 Q = 2.11900E+00 MeV frac = 9.31000E-01 Product nuclide = 54128.82c : beta- + + Nuclide 1120 / 1657 : 531301 -- iodine 130m (I-130m) + + Pointers : 1381383 -1000000 + Primary type : Decay + Nuclide ZAI : 531301 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 129.90697 + Atomic weight ratio (AWR) : 128.79100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.30E+02 seconds (8.84 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 3.99525E-02 MeV frac = 8.40000E-01 Product nuclide = 53130.82c : IT + 2 RTYP = 1 Q = 2.98965E+00 MeV frac = 1.60000E-01 Product nuclide = 54130.82c : beta- + + Nuclide 1121 / 1657 : 531320 -- iodine 132 (I-132) + + Pointers : 1386488 -1000000 + Primary type : Decay + Nuclide ZAI : 531320 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 131.90816 + Atomic weight ratio (AWR) : 130.77500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.26E+03 seconds (2.29 hours) + Specific ingestion toxicity : 2.90E-10 Sv/Bq + Specific inhalation toxicity : 1.10E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.58100E+00 MeV frac = 1.00000E+00 Product nuclide = 54132.82c : beta- + + Nuclide 1122 / 1657 : 531321 -- iodine 132m (I-132m) + + Pointers : 1390737 -1000000 + Primary type : Decay + Nuclide ZAI : 531321 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 131.90816 + Atomic weight ratio (AWR) : 130.77500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.98E+03 seconds (1.38 hours) + Specific ingestion toxicity : 2.20E-10 Sv/Bq + Specific inhalation toxicity : 8.50E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 1.20000E-01 MeV frac = 8.60000E-01 Product nuclide = 531320 : IT + 2 RTYP = 1 Q = 3.69700E+00 MeV frac = 1.40000E-01 Product nuclide = 54132.82c : beta- + + Nuclide 1123 / 1657 : 531330 -- iodine 133 (I-133) + + Pointers : 1391783 -1000000 + Primary type : Decay + Nuclide ZAI : 531330 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 132.90775 + Atomic weight ratio (AWR) : 131.76600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.51E+04 seconds (20.9 hours) + Specific ingestion toxicity : 4.30E-09 Sv/Bq + Specific inhalation toxicity : 1.50E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.75700E+00 MeV frac = 9.71189E-01 Product nuclide = 54133.82c : beta- + 2 RTYP = 1 Q = 1.52378E+00 MeV frac = 2.88108E-02 Product nuclide = 541331 : beta- + + Nuclide 1124 / 1657 : 531331 -- iodine 133m (I-133m) + + Pointers : 1393809 -1000000 + Primary type : Decay + Nuclide ZAI : 531331 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 132.90775 + Atomic weight ratio (AWR) : 131.76600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.63415E+00 MeV frac = 1.00000E+00 Product nuclide = 531330 : IT + + Nuclide 1125 / 1657 : 531340 -- iodine 134 (I-134) + + Pointers : 1394320 -1000000 + Primary type : Decay + Nuclide ZAI : 531340 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 133.90935 + Atomic weight ratio (AWR) : 132.75900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.15E+03 seconds (52.5 minutes) + Specific ingestion toxicity : 1.10E-10 Sv/Bq + Specific inhalation toxicity : 5.50E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.17500E+00 MeV frac = 1.00000E+00 Product nuclide = 54134.82c : beta- + + Nuclide 1126 / 1657 : 531341 -- iodine 134m (I-134m) + + Pointers : 1396357 -1000000 + Primary type : Decay + Nuclide ZAI : 531341 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 133.91036 + Atomic weight ratio (AWR) : 132.76000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.16E+02 seconds (3.6 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 3.16500E-01 MeV frac = 9.77000E-01 Product nuclide = 531340 : IT + 2 RTYP = 1 Q = 2.52020E+00 MeV frac = 2.30000E-02 Product nuclide = 541341 : beta- + + Nuclide 1127 / 1657 : 531360 -- iodine 136 (I-136) + + Pointers : 1401716 -1000000 + Primary type : Decay + Nuclide ZAI : 531360 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 135.91458 + Atomic weight ratio (AWR) : 134.74700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.35E+01 seconds (1.39 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.85700E+00 MeV frac = 1.00000E+00 Product nuclide = 54136.82c : beta- + + Nuclide 1128 / 1657 : 531361 -- iodine 136m (I-136m) + + Pointers : 1406371 -1000000 + Primary type : Decay + Nuclide ZAI : 531361 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 135.91458 + Atomic weight ratio (AWR) : 134.74700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 47 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 54136.82c : beta- + + Nuclide 1129 / 1657 : 531370 -- iodine 137 (I-137) + + Pointers : 1408408 -1000000 + Primary type : Decay + Nuclide ZAI : 531370 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 136.91820 + Atomic weight ratio (AWR) : 135.74200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 24.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 5.87700E+00 MeV frac = 9.35000E-01 Product nuclide = 541370 : beta- + 2 RTYP = 15 Q = 1.86000E+00 MeV frac = 6.50000E-02 Product nuclide = 54136.82c : beta- + neutron emission + + Nuclide 1130 / 1657 : 531380 -- iodine 138 (I-138) + + Pointers : 1417056 -1000000 + Primary type : Decay + Nuclide ZAI : 531380 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 137.92283 + Atomic weight ratio (AWR) : 136.73800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.46 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 7.82000E+00 MeV frac = 9.47000E-01 Product nuclide = 541380 : beta- + 2 RTYP = 15 Q = 2.00000E+00 MeV frac = 5.30000E-02 Product nuclide = 541370 : beta- + neutron emission + + Nuclide 1131 / 1657 : 531390 -- iodine 139 (I-139) + + Pointers : 1420272 -1000000 + Primary type : Decay + Nuclide ZAI : 531390 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 138.92645 + Atomic weight ratio (AWR) : 137.73300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 6.80700E+00 MeV frac = 9.02000E-01 Product nuclide = 541390 : beta- + 2 RTYP = 15 Q = 3.18000E+00 MeV frac = 9.80000E-02 Product nuclide = 541380 : beta- + neutron emission + + Nuclide 1132 / 1657 : 531400 -- iodine 140 (I-140) + + Pointers : 1424524 -1000000 + Primary type : Decay + Nuclide ZAI : 531400 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 139.93108 + Atomic weight ratio (AWR) : 138.72900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.86 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.72000E+00 MeV frac = 9.07000E-01 Product nuclide = 541400 : beta- + 2 RTYP = 15 Q = 3.30270E+00 MeV frac = 9.30000E-02 Product nuclide = 541390 : beta- + neutron emission + + Nuclide 1133 / 1657 : 531410 -- iodine 141 (I-141) + + Pointers : 1424781 -1000000 + Primary type : Decay + Nuclide ZAI : 531410 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 140.93470 + Atomic weight ratio (AWR) : 139.72400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.43 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 7.81000E+00 MeV frac = 7.90000E-01 Product nuclide = 541410 : beta- + 2 RTYP = 15 Q = 4.39870E+00 MeV frac = 2.10000E-01 Product nuclide = 541400 : beta- + neutron emission + + Nuclide 1134 / 1657 : 531420 -- iodine 142 (I-142) + + Pointers : 1425038 -1000000 + Primary type : Decay + Nuclide ZAI : 531420 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 141.94034 + Atomic weight ratio (AWR) : 140.72100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 9.76000E+00 MeV frac = 7.50000E-01 Product nuclide = 541420 : beta- + 2 RTYP = 15 Q = 4.53870E+00 MeV frac = 2.50000E-01 Product nuclide = 541410 : beta- + neutron emission + + Nuclide 1135 / 1657 : 531430 -- iodine 143 (I-143) + + Pointers : 1425295 -1000000 + Primary type : Decay + Nuclide ZAI : 531430 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 142.94497 + Atomic weight ratio (AWR) : 141.71700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 100 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.81000E+00 MeV frac = 6.00000E-01 Product nuclide = 541430 : beta- + 2 RTYP = 15 Q = 5.76870E+00 MeV frac = 4.00000E-01 Product nuclide = 541420 : beta- + neutron emission + + Nuclide 1136 / 1657 : 531440 -- iodine 144 (I-144) + + Pointers : 1425552 -1000000 + Primary type : Decay + Nuclide ZAI : 531440 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 143.94960 + Atomic weight ratio (AWR) : 142.71300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 50 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.07000E+01 MeV frac = 6.00000E-01 Product nuclide = 541440 : beta- + 2 RTYP = 15 Q = 5.79870E+00 MeV frac = 4.00000E-01 Product nuclide = 541430 : beta- + neutron emission + + Nuclide 1137 / 1657 : 541260 -- xenon 126 (Xe-126) + + Pointers : 1425809 -1000000 + Primary type : Decay + Nuclide ZAI : 541260 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 125.90459 + Atomic weight ratio (AWR) : 124.82300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1138 / 1657 : 541270 -- xenon 127 (Xe-127) + + Pointers : 1425915 -1000000 + Primary type : Decay + Nuclide ZAI : 541270 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 126.90518 + Atomic weight ratio (AWR) : 125.81500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.14E+06 seconds (36.4 days) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 6.62300E-01 MeV frac = 1.00000E+00 Product nuclide = 53127.82c : EC/beta+ + + Nuclide 1139 / 1657 : 541291 -- xenon 129m (Xe-129m) + + Pointers : 1433520 -1000000 + Primary type : Decay + Nuclide ZAI : 541291 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 128.90436 + Atomic weight ratio (AWR) : 127.79700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.67E+05 seconds (8.88 days) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 2.36140E-01 MeV frac = 1.00000E+00 Product nuclide = 54129.82c : IT + + Nuclide 1140 / 1657 : 541311 -- xenon 131m (Xe-131m) + + Pointers : 1438276 -1000000 + Primary type : Decay + Nuclide ZAI : 541311 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 130.90555 + Atomic weight ratio (AWR) : 129.78100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.03E+06 seconds (12 days) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.63930E-01 MeV frac = 1.00000E+00 Product nuclide = 54131.82c : IT + + Nuclide 1141 / 1657 : 541321 -- xenon 132m (Xe-132m) + + Pointers : 1441770 -1000000 + Primary type : Decay + Nuclide ZAI : 541321 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 131.90413 + Atomic weight ratio (AWR) : 130.77100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.39 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 2.75216E+00 MeV frac = 1.00000E+00 Product nuclide = 54132.82c : IT + + Nuclide 1142 / 1657 : 541331 -- xenon 133m (Xe-133m) + + Pointers : 1446011 -1000000 + Primary type : Decay + Nuclide ZAI : 541331 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 132.90573 + Atomic weight ratio (AWR) : 131.76400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.90E+05 seconds (2.2 days) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 2.33219E-01 MeV frac = 1.00000E+00 Product nuclide = 54133.82c : IT + + Nuclide 1143 / 1657 : 541341 -- xenon 134m (Xe-134m) + + Pointers : 1449724 -1000000 + Primary type : Decay + Nuclide ZAI : 541341 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 133.90532 + Atomic weight ratio (AWR) : 132.75500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.29 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.96550E+00 MeV frac = 1.00000E+00 Product nuclide = 54134.82c : IT + + Nuclide 1144 / 1657 : 541351 -- xenon 135m (Xe-135m) + + Pointers : 1451394 -1000000 + Primary type : Decay + Nuclide ZAI : 541351 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 134.90692 + Atomic weight ratio (AWR) : 133.74800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.18E+02 seconds (15.3 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 5.26571E-01 MeV frac = 9.99960E-01 Product nuclide = 54135.82c : IT + 2 RTYP = 1 Q = 1.69197E+00 MeV frac = 4.00000E-05 Product nuclide = 55135.82c : beta- + + Nuclide 1145 / 1657 : 541370 -- xenon 137 (Xe-137) + + Pointers : 1454981 -1000000 + Primary type : Decay + Nuclide ZAI : 541370 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 136.91114 + Atomic weight ratio (AWR) : 135.73500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.29E+02 seconds (3.82 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.17300E+00 MeV frac = 1.00000E+00 Product nuclide = 55137.82c : beta- + + Nuclide 1146 / 1657 : 541380 -- xenon 138 (Xe-138) + + Pointers : 1456962 -1000000 + Primary type : Decay + Nuclide ZAI : 541380 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 137.91375 + Atomic weight ratio (AWR) : 136.72900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.45E+02 seconds (14.1 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.77000E+00 MeV frac = 1.00000E+00 Product nuclide = 551380 : beta- + + Nuclide 1147 / 1657 : 541390 -- xenon 139 (Xe-139) + + Pointers : 1459223 -1000000 + Primary type : Decay + Nuclide ZAI : 541390 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 138.91838 + Atomic weight ratio (AWR) : 137.72500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 39.7 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.05700E+00 MeV frac = 1.00000E+00 Product nuclide = 551390 : beta- + + Nuclide 1148 / 1657 : 541400 -- xenon 140 (Xe-140) + + Pointers : 1466398 -1000000 + Primary type : Decay + Nuclide ZAI : 541400 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 139.92200 + Atomic weight ratio (AWR) : 138.72000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 13.6 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.06100E+00 MeV frac = 1.00000E+00 Product nuclide = 551400 : beta- + + Nuclide 1149 / 1657 : 541410 -- xenon 141 (Xe-141) + + Pointers : 1466582 -1000000 + Primary type : Decay + Nuclide ZAI : 541410 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 140.92663 + Atomic weight ratio (AWR) : 139.71600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.73 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 6.14700E+00 MeV frac = 9.99560E-01 Product nuclide = 551410 : beta- + 2 RTYP = 15 Q = 6.49701E-01 MeV frac = 4.40000E-04 Product nuclide = 551400 : beta- + neutron emission + + Nuclide 1150 / 1657 : 541420 -- xenon 142 (Xe-142) + + Pointers : 1466839 -1000000 + Primary type : Decay + Nuclide ZAI : 541420 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 141.92925 + Atomic weight ratio (AWR) : 140.71000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.22 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 5.03500E+00 MeV frac = 9.96400E-01 Product nuclide = 551420 : beta- + 2 RTYP = 15 Q = 9.25702E-01 MeV frac = 3.60000E-03 Product nuclide = 551410 : beta- + neutron emission + + Nuclide 1151 / 1657 : 541430 -- xenon 143 (Xe-143) + + Pointers : 1467096 -1000000 + Primary type : Decay + Nuclide ZAI : 541430 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 142.93489 + Atomic weight ratio (AWR) : 141.70700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.511 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 7.22100E+00 MeV frac = 9.90000E-01 Product nuclide = 551430 : beta- + 2 RTYP = 15 Q = 1.99370E+00 MeV frac = 1.00000E-02 Product nuclide = 551420 : beta- + neutron emission + + Nuclide 1152 / 1657 : 541440 -- xenon 144 (Xe-144) + + Pointers : 1467353 -1000000 + Primary type : Decay + Nuclide ZAI : 541440 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 143.93851 + Atomic weight ratio (AWR) : 142.70200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.388 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 5.99000E+00 MeV frac = 9.70000E-01 Product nuclide = 551440 : beta- + 2 RTYP = 15 Q = 2.31970E+00 MeV frac = 3.00000E-02 Product nuclide = 551430 : beta- + neutron emission + + Nuclide 1153 / 1657 : 541450 -- xenon 145 (Xe-145) + + Pointers : 1467610 -1000000 + Primary type : Decay + Nuclide ZAI : 541450 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 144.94415 + Atomic weight ratio (AWR) : 143.69900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.188 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 1 Q = 7.95700E+00 MeV frac = 9.50000E-01 Product nuclide = 551450 : beta- + 2 RTYP = 15 Q = 3.09870E+00 MeV frac = 2.50000E-02 Product nuclide = 551440 : beta- + neutron emission + 3 RTYP = 15 Q = 2.79870E+00 MeV frac = 2.50000E-02 Product nuclide = 551441 : beta- + neutron emission + + Nuclide 1154 / 1657 : 541460 -- xenon 146 (Xe-146) + + Pointers : 1467940 -1000000 + Primary type : Decay + Nuclide ZAI : 541460 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 145.94777 + Atomic weight ratio (AWR) : 144.69400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.146 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 6.95000E+00 MeV frac = 9.31000E-01 Product nuclide = 551460 : beta- + 2 RTYP = 15 Q = 3.31570E+00 MeV frac = 6.90000E-02 Product nuclide = 551450 : beta- + neutron emission + + Nuclide 1155 / 1657 : 541470 -- xenon 147 (Xe-147) + + Pointers : 1468197 -1000000 + Primary type : Decay + Nuclide ZAI : 541470 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 146.95341 + Atomic weight ratio (AWR) : 145.69100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.13 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.76000E+00 MeV frac = 9.60000E-01 Product nuclide = 551470 : beta- + 2 RTYP = 15 Q = 4.28870E+00 MeV frac = 4.00000E-02 Product nuclide = 551460 : beta- + neutron emission + + Nuclide 1156 / 1657 : 551310 -- cesium 131 (Cs-131) + + Pointers : 1468454 -1000000 + Primary type : Decay + Nuclide ZAI : 551310 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 130.90555 + Atomic weight ratio (AWR) : 129.78100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.37E+05 seconds (9.69 days) + Specific ingestion toxicity : 5.80E-11 Sv/Bq + Specific inhalation toxicity : 4.70E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 3.55000E-01 MeV frac = 1.00000E+00 Product nuclide = 54131.82c : EC/beta+ + + Nuclide 1157 / 1657 : 551320 -- cesium 132 (Cs-132) + + Pointers : 1468797 -1000000 + Primary type : Decay + Nuclide ZAI : 551320 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 131.90614 + Atomic weight ratio (AWR) : 130.77300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.64E+05 seconds (6.53 days) + Specific ingestion toxicity : 5.00E-10 Sv/Bq + Specific inhalation toxicity : 3.00E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.27900E+00 MeV frac = 1.80000E-02 Product nuclide = 561320 : beta- + 2 RTYP = 2 Q = 2.13000E+00 MeV frac = 9.82000E-01 Product nuclide = 54132.82c : EC/beta+ + + Nuclide 1158 / 1657 : 551341 -- cesium 134m (Cs-134m) + + Pointers : 1474914 -1000000 + Primary type : Decay + Nuclide ZAI : 551341 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 133.90633 + Atomic weight ratio (AWR) : 132.75600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.05E+04 seconds (2.91 hours) + Specific ingestion toxicity : 2.00E-11 Sv/Bq + Specific inhalation toxicity : 6.00E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.38747E-01 MeV frac = 1.00000E+00 Product nuclide = 55134.82c : IT + + Nuclide 1159 / 1657 : 551351 -- cesium 135m (Cs-135m) + + Pointers : 1477983 -1000000 + Primary type : Decay + Nuclide ZAI : 551351 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 134.90591 + Atomic weight ratio (AWR) : 133.74700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.18E+03 seconds (53 minutes) + Specific ingestion toxicity : 1.90E-11 Sv/Bq + Specific inhalation toxicity : 1.60E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.63330E+00 MeV frac = 1.00000E+00 Product nuclide = 55135.82c : IT + + Nuclide 1160 / 1657 : 551361 -- cesium 136m (Cs-136m) + + Pointers : 1481591 -1000000 + Primary type : Decay + Nuclide ZAI : 551361 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 135.90752 + Atomic weight ratio (AWR) : 134.74000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 19 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 3.10000E+00 MeV frac = 5.00000E-01 Product nuclide = 56136.82c : beta- + 2 RTYP = 3 Q = 6.00000E-01 MeV frac = 5.00000E-01 Product nuclide = 55136.82c : IT + + Nuclide 1161 / 1657 : 551380 -- cesium 138 (Cs-138) + + Pointers : 1484894 -1000000 + Primary type : Decay + Nuclide ZAI : 551380 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 137.91073 + Atomic weight ratio (AWR) : 136.72600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.00E+03 seconds (33.4 minutes) + Specific ingestion toxicity : 9.20E-11 Sv/Bq + Specific inhalation toxicity : 4.30E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.37400E+00 MeV frac = 1.00000E+00 Product nuclide = 56138.82c : beta- + + Nuclide 1162 / 1657 : 551381 -- cesium 138m (Cs-138m) + + Pointers : 1487337 -1000000 + Primary type : Decay + Nuclide ZAI : 551381 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 137.91073 + Atomic weight ratio (AWR) : 136.72600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.75E+02 seconds (2.91 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 7.99000E-02 MeV frac = 8.10000E-01 Product nuclide = 551380 : IT + 2 RTYP = 1 Q = 5.45450E+00 MeV frac = 1.90000E-01 Product nuclide = 56138.82c : beta- + + Nuclide 1163 / 1657 : 551390 -- cesium 139 (Cs-139) + + Pointers : 1487594 -1000000 + Primary type : Decay + Nuclide ZAI : 551390 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 138.91334 + Atomic weight ratio (AWR) : 137.72000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.56E+02 seconds (9.27 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.21300E+00 MeV frac = 1.00000E+00 Product nuclide = 561390 : beta- + + Nuclide 1164 / 1657 : 551400 -- cesium 140 (Cs-140) + + Pointers : 1491171 -1000000 + Primary type : Decay + Nuclide ZAI : 551400 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 139.91696 + Atomic weight ratio (AWR) : 138.71500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.40E+01 seconds (1.07 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.22000E+00 MeV frac = 1.00000E+00 Product nuclide = 56140.82c : beta- + + Nuclide 1165 / 1657 : 551410 -- cesium 141 (Cs-141) + + Pointers : 1502490 -1000000 + Primary type : Decay + Nuclide ZAI : 551410 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 140.91957 + Atomic weight ratio (AWR) : 139.70900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 24.8 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.25600E+00 MeV frac = 1.00000E+00 Product nuclide = 561410 : beta- + + Nuclide 1166 / 1657 : 551420 -- cesium 142 (Cs-142) + + Pointers : 1506529 -1000000 + Primary type : Decay + Nuclide ZAI : 551420 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 141.92420 + Atomic weight ratio (AWR) : 140.70500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.68 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.30800E+00 MeV frac = 1.00000E+00 Product nuclide = 561420 : beta- + + Nuclide 1167 / 1657 : 551430 -- cesium 143 (Cs-143) + + Pointers : 1507754 -1000000 + Primary type : Decay + Nuclide ZAI : 551430 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 142.92783 + Atomic weight ratio (AWR) : 141.70000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.79 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 6.26500E+00 MeV frac = 9.83600E-01 Product nuclide = 561430 : beta- + 2 RTYP = 15 Q = 2.08070E+00 MeV frac = 1.64000E-02 Product nuclide = 561420 : beta- + neutron emission + + Nuclide 1168 / 1657 : 551440 -- cesium 144 (Cs-144) + + Pointers : 1508011 -1000000 + Primary type : Decay + Nuclide ZAI : 551440 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 143.93246 + Atomic weight ratio (AWR) : 142.69600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.994 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.49900E+00 MeV frac = 9.68000E-01 Product nuclide = 561440 : beta- + 2 RTYP = 15 Q = 2.59470E+00 MeV frac = 3.20000E-02 Product nuclide = 561430 : beta- + neutron emission + + Nuclide 1169 / 1657 : 551441 -- cesium 144m (Cs-144m) + + Pointers : 1508268 -1000000 + Primary type : Decay + Nuclide ZAI : 551441 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 143.93246 + Atomic weight ratio (AWR) : 142.69600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.79900E+00 MeV frac = 5.00000E-01 Product nuclide = 561440 : beta- + 2 RTYP = 3 Q = 3.00000E-01 MeV frac = 5.00000E-01 Product nuclide = 551440 : IT + + Nuclide 1170 / 1657 : 551450 -- cesium 145 (Cs-145) + + Pointers : 1508525 -1000000 + Primary type : Decay + Nuclide ZAI : 551450 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 144.93507 + Atomic weight ratio (AWR) : 143.69000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.594 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 7.93000E+00 MeV frac = 8.57000E-01 Product nuclide = 561450 : beta- + 2 RTYP = 15 Q = 3.52400E+00 MeV frac = 1.43000E-01 Product nuclide = 561440 : beta- + neutron emission + + Nuclide 1171 / 1657 : 551460 -- cesium 146 (Cs-146) + + Pointers : 1511181 -1000000 + Primary type : Decay + Nuclide ZAI : 551460 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 145.94071 + Atomic weight ratio (AWR) : 144.68700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.323 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 9.38000E+00 MeV frac = 8.58000E-01 Product nuclide = 561460 : beta- + 2 RTYP = 15 Q = 3.71870E+00 MeV frac = 1.42000E-01 Product nuclide = 561450 : beta- + neutron emission + + Nuclide 1172 / 1657 : 551470 -- cesium 147 (Cs-147) + + Pointers : 1511438 -1000000 + Primary type : Decay + Nuclide ZAI : 551470 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 146.94433 + Atomic weight ratio (AWR) : 145.68200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.225 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.58000E+00 MeV frac = 7.15000E-01 Product nuclide = 561470 : beta- + 2 RTYP = 15 Q = 4.90870E+00 MeV frac = 2.85000E-01 Product nuclide = 561460 : beta- + neutron emission + + Nuclide 1173 / 1657 : 551480 -- cesium 148 (Cs-148) + + Pointers : 1511695 -1000000 + Primary type : Decay + Nuclide ZAI : 551480 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 147.94896 + Atomic weight ratio (AWR) : 146.67800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.146 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.07100E+01 MeV frac = 7.49000E-01 Product nuclide = 561480 : beta- + 2 RTYP = 15 Q = 5.22870E+00 MeV frac = 2.51000E-01 Product nuclide = 561470 : beta- + neutron emission + + Nuclide 1174 / 1657 : 551490 -- cesium 149 (Cs-149) + + Pointers : 1511952 -1000000 + Primary type : Decay + Nuclide ZAI : 551490 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 148.95258 + Atomic weight ratio (AWR) : 147.67300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.15 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.64000E+00 MeV frac = 1.00000E+00 Product nuclide = 561490 : beta- + + Nuclide 1175 / 1657 : 551500 -- cesium 150 (Cs-150) + + Pointers : 1512136 -1000000 + Primary type : Decay + Nuclide ZAI : 551500 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 149.95822 + Atomic weight ratio (AWR) : 148.67000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 100 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.16400E+01 MeV frac = 1.00000E+00 Product nuclide = 561500 : beta- + + Nuclide 1176 / 1657 : 561320 -- barium 132 (Ba-132) + + Pointers : 1512320 -1000000 + Primary type : Decay + Nuclide ZAI : 561320 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 131.90514 + Atomic weight ratio (AWR) : 130.77200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1177 / 1657 : 561330 -- barium 133 (Ba-133) + + Pointers : 1512426 -1000000 + Primary type : Decay + Nuclide ZAI : 561330 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 132.90573 + Atomic weight ratio (AWR) : 131.76400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.33E+08 seconds (10.5 years) + Specific ingestion toxicity : 1.50E-09 Sv/Bq + Specific inhalation toxicity : 1.00E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 5.17300E-01 MeV frac = 1.00000E+00 Product nuclide = 55133.82c : EC/beta+ + + Nuclide 1178 / 1657 : 561331 -- barium 133m (Ba-133m) + + Pointers : 1513357 -1000000 + Primary type : Decay + Nuclide ZAI : 561331 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 132.90573 + Atomic weight ratio (AWR) : 131.76400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.38E+05 seconds (1.59 days) + Specific ingestion toxicity : 5.40E-10 Sv/Bq + Specific inhalation toxicity : 4.60E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 8.09000E-01 MeV frac = 1.01000E-04 Product nuclide = 55133.82c : EC/beta+ + 2 RTYP = 3 Q = 2.88250E-01 MeV frac = 9.99899E-01 Product nuclide = 561330 : IT + + Nuclide 1179 / 1657 : 561351 -- barium 135m (Ba-135m) + + Pointers : 1519698 -1000000 + Primary type : Decay + Nuclide ZAI : 561351 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 134.90591 + Atomic weight ratio (AWR) : 133.74700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.03E+05 seconds (1.2 days) + Specific ingestion toxicity : 4.30E-10 Sv/Bq + Specific inhalation toxicity : 3.60E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 2.68218E-01 MeV frac = 1.00000E+00 Product nuclide = 56135.82c : IT + + Nuclide 1180 / 1657 : 561361 -- barium 136m (Ba-136m) + + Pointers : 1522681 -1000000 + Primary type : Decay + Nuclide ZAI : 561361 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 135.90449 + Atomic weight ratio (AWR) : 134.73700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.308 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 2.03047E+00 MeV frac = 1.00000E+00 Product nuclide = 56136.82c : IT + + Nuclide 1181 / 1657 : 561371 -- barium 137m (Ba-137m) + + Pointers : 1525782 -1000000 + Primary type : Decay + Nuclide ZAI : 561371 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 136.90610 + Atomic weight ratio (AWR) : 135.73000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.53E+02 seconds (2.55 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 6.61659E-01 MeV frac = 1.00000E+00 Product nuclide = 56137.82c : IT + + Nuclide 1182 / 1657 : 561390 -- barium 139 (Ba-139) + + Pointers : 1529302 -1000000 + Primary type : Decay + Nuclide ZAI : 561390 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 138.90930 + Atomic weight ratio (AWR) : 137.71600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.98E+03 seconds (1.38 hours) + Specific ingestion toxicity : 1.20E-10 Sv/Bq + Specific inhalation toxicity : 5.90E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.31680E+00 MeV frac = 1.00000E+00 Product nuclide = 57139.82c : beta- + + Nuclide 1183 / 1657 : 561410 -- barium 141 (Ba-141) + + Pointers : 1533196 -1000000 + Primary type : Decay + Nuclide ZAI : 561410 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 140.91453 + Atomic weight ratio (AWR) : 139.70400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.10E+03 seconds (18.3 minutes) + Specific ingestion toxicity : 7.00E-11 Sv/Bq + Specific inhalation toxicity : 3.40E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.23000E+00 MeV frac = 1.00000E+00 Product nuclide = 571410 : beta- + + Nuclide 1184 / 1657 : 561420 -- barium 142 (Ba-142) + + Pointers : 1535723 -1000000 + Primary type : Decay + Nuclide ZAI : 561420 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 141.91613 + Atomic weight ratio (AWR) : 140.69700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.36E+02 seconds (10.6 minutes) + Specific ingestion toxicity : 3.50E-11 Sv/Bq + Specific inhalation toxicity : 2.20E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.21100E+00 MeV frac = 1.00000E+00 Product nuclide = 571420 : beta- + + Nuclide 1185 / 1657 : 561430 -- barium 143 (Ba-143) + + Pointers : 1538152 -1000000 + Primary type : Decay + Nuclide ZAI : 561430 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 142.92077 + Atomic weight ratio (AWR) : 141.69300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 14.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.25100E+00 MeV frac = 1.00000E+00 Product nuclide = 571430 : beta- + + Nuclide 1186 / 1657 : 561440 -- barium 144 (Ba-144) + + Pointers : 1538336 -1000000 + Primary type : Decay + Nuclide ZAI : 561440 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 143.92338 + Atomic weight ratio (AWR) : 142.68700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 11.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.12100E+00 MeV frac = 1.00000E+00 Product nuclide = 571440 : beta- + + Nuclide 1187 / 1657 : 561450 -- barium 145 (Ba-145) + + Pointers : 1538520 -1000000 + Primary type : Decay + Nuclide ZAI : 561450 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 144.92801 + Atomic weight ratio (AWR) : 143.68300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.31 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.58000E+00 MeV frac = 1.00000E+00 Product nuclide = 571450 : beta- + + Nuclide 1188 / 1657 : 561460 -- barium 146 (Ba-146) + + Pointers : 1538704 -1000000 + Primary type : Decay + Nuclide ZAI : 561460 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 145.93062 + Atomic weight ratio (AWR) : 144.67700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.22 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.12000E+00 MeV frac = 1.00000E+00 Product nuclide = 571460 : beta- + + Nuclide 1189 / 1657 : 561470 -- barium 147 (Ba-147) + + Pointers : 1538888 -1000000 + Primary type : Decay + Nuclide ZAI : 561470 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 146.93525 + Atomic weight ratio (AWR) : 145.67300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.894 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.25000E+00 MeV frac = 1.00000E+00 Product nuclide = 571470 : beta- + + Nuclide 1190 / 1657 : 561480 -- barium 148 (Ba-148) + + Pointers : 1541205 -1000000 + Primary type : Decay + Nuclide ZAI : 561480 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 147.93786 + Atomic weight ratio (AWR) : 146.66700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.612 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 5.12000E+00 MeV frac = 9.96000E-01 Product nuclide = 571480 : beta- + 2 RTYP = 15 Q = 7.68704E-01 MeV frac = 4.00000E-03 Product nuclide = 571470 : beta- + neutron emission + + Nuclide 1191 / 1657 : 561490 -- barium 149 (Ba-149) + + Pointers : 1541462 -1000000 + Primary type : Decay + Nuclide ZAI : 561490 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 148.94250 + Atomic weight ratio (AWR) : 147.66300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.344 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 7.31000E+00 MeV frac = 9.95700E-01 Product nuclide = 571490 : beta- + 2 RTYP = 15 Q = 1.56870E+00 MeV frac = 4.30000E-03 Product nuclide = 571480 : beta- + neutron emission + + Nuclide 1192 / 1657 : 561500 -- barium 150 (Ba-150) + + Pointers : 1541719 -1000000 + Primary type : Decay + Nuclide ZAI : 561500 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 149.94612 + Atomic weight ratio (AWR) : 148.65800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.44000E+00 MeV frac = 1.00000E+00 Product nuclide = 571500 : beta- + + Nuclide 1193 / 1657 : 561510 -- barium 151 (Ba-151) + + Pointers : 1541903 -1000000 + Primary type : Decay + Nuclide ZAI : 561510 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 150.95075 + Atomic weight ratio (AWR) : 149.65400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.47000E+00 MeV frac = 1.00000E+00 Product nuclide = 571510 : beta- + + Nuclide 1194 / 1657 : 561520 -- barium 152 (Ba-152) + + Pointers : 1542087 -1000000 + Primary type : Decay + Nuclide ZAI : 561520 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 151.95437 + Atomic weight ratio (AWR) : 150.64900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 100 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.47000E+00 MeV frac = 1.00000E+00 Product nuclide = 571520 : beta- + + Nuclide 1195 / 1657 : 561530 -- barium 153 (Ba-153) + + Pointers : 1542271 -1000000 + Primary type : Decay + Nuclide ZAI : 561530 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 152.96001 + Atomic weight ratio (AWR) : 151.64600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 80 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.31000E+00 MeV frac = 1.00000E+00 Product nuclide = 571530 : beta- + + Nuclide 1196 / 1657 : 571360 -- lanthanum 136 (La-136) + + Pointers : 1542455 -1000000 + Primary type : Decay + Nuclide ZAI : 571360 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 135.90752 + Atomic weight ratio (AWR) : 134.74000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.92E+02 seconds (9.87 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 2.87000E+00 MeV frac = 1.00000E+00 Product nuclide = 56136.82c : EC/beta+ + + Nuclide 1197 / 1657 : 571361 -- lanthanum 136m (La-136m) + + Pointers : 1543064 -1000000 + Primary type : Decay + Nuclide ZAI : 571361 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 135.90752 + Atomic weight ratio (AWR) : 134.74000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.114 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 2.55000E-01 MeV frac = 1.00000E+00 Product nuclide = 571360 : IT + + Nuclide 1198 / 1657 : 571370 -- lanthanum 137 (La-137) + + Pointers : 1543248 -1000000 + Primary type : Decay + Nuclide ZAI : 571370 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 136.90610 + Atomic weight ratio (AWR) : 135.73000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.89E+12 seconds (60,041 years) + Specific ingestion toxicity : 8.10E-11 Sv/Bq + Specific inhalation toxicity : 8.70E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 5.97000E-01 MeV frac = 1.00000E+00 Product nuclide = 56137.82c : EC/beta+ + + Nuclide 1199 / 1657 : 571410 -- lanthanum 141 (La-141) + + Pointers : 1555355 -1000000 + Primary type : Decay + Nuclide ZAI : 571410 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 140.91050 + Atomic weight ratio (AWR) : 139.70000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.41E+04 seconds (3.92 hours) + Specific ingestion toxicity : 3.60E-10 Sv/Bq + Specific inhalation toxicity : 1.50E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.44600E+00 MeV frac = 1.00000E+00 Product nuclide = 58141.82c : beta- + + Nuclide 1200 / 1657 : 571420 -- lanthanum 142 (La-142) + + Pointers : 1556174 -1000000 + Primary type : Decay + Nuclide ZAI : 571420 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 141.91412 + Atomic weight ratio (AWR) : 140.69500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.47E+03 seconds (1.52 hours) + Specific ingestion toxicity : 1.80E-10 Sv/Bq + Specific inhalation toxicity : 8.90E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.50400E+00 MeV frac = 1.00000E+00 Product nuclide = 58142.82c : beta- + + Nuclide 1201 / 1657 : 571430 -- lanthanum 143 (La-143) + + Pointers : 1560241 -1000000 + Primary type : Decay + Nuclide ZAI : 571430 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 142.91572 + Atomic weight ratio (AWR) : 141.68800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.48E+02 seconds (14.1 minutes) + Specific ingestion toxicity : 5.60E-11 Sv/Bq + Specific inhalation toxicity : 2.10E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.29000E+00 MeV frac = 1.00000E+00 Product nuclide = 58143.82c : beta- + + Nuclide 1202 / 1657 : 571440 -- lanthanum 144 (La-144) + + Pointers : 1561816 -1000000 + Primary type : Decay + Nuclide ZAI : 571440 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 143.91934 + Atomic weight ratio (AWR) : 142.68300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 40.8 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.54100E+00 MeV frac = 1.00000E+00 Product nuclide = 58144.82c : beta- + + Nuclide 1203 / 1657 : 571450 -- lanthanum 145 (La-145) + + Pointers : 1565393 -1000000 + Primary type : Decay + Nuclide ZAI : 571450 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 144.92196 + Atomic weight ratio (AWR) : 143.67700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 24.8 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.12000E+00 MeV frac = 1.00000E+00 Product nuclide = 581450 : beta- + + Nuclide 1204 / 1657 : 571460 -- lanthanum 146 (La-146) + + Pointers : 1567374 -1000000 + Primary type : Decay + Nuclide ZAI : 571460 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 145.92558 + Atomic weight ratio (AWR) : 144.67200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.27 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.53000E+00 MeV frac = 1.00000E+00 Product nuclide = 581460 : beta- + + Nuclide 1205 / 1657 : 571461 -- lanthanum 146m (La-146m) + + Pointers : 1570993 -1000000 + Primary type : Decay + Nuclide ZAI : 571461 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 145.92558 + Atomic weight ratio (AWR) : 144.67200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 10 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.69000E+00 MeV frac = 1.00000E+00 Product nuclide = 581460 : beta- + + Nuclide 1206 / 1657 : 571470 -- lanthanum 147 (La-147) + + Pointers : 1571177 -1000000 + Primary type : Decay + Nuclide ZAI : 571470 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 146.92819 + Atomic weight ratio (AWR) : 145.66600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.06 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.18000E+00 MeV frac = 1.00000E+00 Product nuclide = 581470 : beta- + + Nuclide 1207 / 1657 : 571480 -- lanthanum 148 (La-148) + + Pointers : 1573200 -1000000 + Primary type : Decay + Nuclide ZAI : 571480 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 147.93181 + Atomic weight ratio (AWR) : 146.66100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.26 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.26000E+00 MeV frac = 1.00000E+00 Product nuclide = 581480 : beta- + + Nuclide 1208 / 1657 : 571490 -- lanthanum 149 (La-149) + + Pointers : 1574761 -1000000 + Primary type : Decay + Nuclide ZAI : 571490 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 148.93443 + Atomic weight ratio (AWR) : 147.65500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.05 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 5.90000E+00 MeV frac = 9.86000E-01 Product nuclide = 581490 : beta- + 2 RTYP = 15 Q = 1.51970E+00 MeV frac = 1.40000E-02 Product nuclide = 581480 : beta- + neutron emission + + Nuclide 1209 / 1657 : 571500 -- lanthanum 150 (La-150) + + Pointers : 1575018 -1000000 + Primary type : Decay + Nuclide ZAI : 571500 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 149.93906 + Atomic weight ratio (AWR) : 148.65100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.51 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 7.78000E+00 MeV frac = 9.73000E-01 Product nuclide = 581500 : beta- + 2 RTYP = 15 Q = 1.58870E+00 MeV frac = 2.70000E-02 Product nuclide = 581490 : beta- + neutron emission + + Nuclide 1210 / 1657 : 571510 -- lanthanum 151 (La-151) + + Pointers : 1575275 -1000000 + Primary type : Decay + Nuclide ZAI : 571510 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 150.94167 + Atomic weight ratio (AWR) : 149.64500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.21000E+00 MeV frac = 1.00000E+00 Product nuclide = 581510 : beta- + + Nuclide 1211 / 1657 : 571520 -- lanthanum 152 (La-152) + + Pointers : 1575459 -1000000 + Primary type : Decay + Nuclide ZAI : 571520 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 151.94428 + Atomic weight ratio (AWR) : 150.63900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.28 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.82000E+00 MeV frac = 9.39610E-01 Product nuclide = 581520 : beta- + 2 RTYP = 15 Q = 3.98900E+00 MeV frac = 6.03930E-02 Product nuclide = 581510 : beta- + neutron emission + + Nuclide 1212 / 1657 : 571530 -- lanthanum 153 (La-153) + + Pointers : 1582138 -1000000 + Primary type : Decay + Nuclide ZAI : 571530 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 152.94992 + Atomic weight ratio (AWR) : 151.63600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.15 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.42000E+00 MeV frac = 1.00000E+00 Product nuclide = 581530 : beta- + + Nuclide 1213 / 1657 : 571540 -- lanthanum 154 (La-154) + + Pointers : 1582322 -1000000 + Primary type : Decay + Nuclide ZAI : 571540 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 153.95455 + Atomic weight ratio (AWR) : 152.63200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 100 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.03200E+01 MeV frac = 1.00000E+00 Product nuclide = 581540 : beta- + + Nuclide 1214 / 1657 : 571550 -- lanthanum 155 (La-155) + + Pointers : 1582506 -1000000 + Primary type : Decay + Nuclide ZAI : 571550 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 154.95817 + Atomic weight ratio (AWR) : 153.62700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 60 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 581550 : beta- + + Nuclide 1215 / 1657 : 581380 -- cerium 138 (Ce-138) + + Pointers : 1582690 -1000000 + Primary type : Decay + Nuclide ZAI : 581380 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 137.90568 + Atomic weight ratio (AWR) : 136.72100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1216 / 1657 : 581381 -- cerium 138m (Ce-138m) + + Pointers : 1582796 -1000000 + Primary type : Decay + Nuclide ZAI : 581381 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 137.90568 + Atomic weight ratio (AWR) : 136.72100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.65 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 2.12917E+00 MeV frac = 1.00000E+00 Product nuclide = 581380 : IT + + Nuclide 1217 / 1657 : 581390 -- cerium 139 (Ce-139) + + Pointers : 1582980 -1000000 + Primary type : Decay + Nuclide ZAI : 581390 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 138.90628 + Atomic weight ratio (AWR) : 137.71300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.19E+07 seconds (138 days) + Specific ingestion toxicity : 2.60E-10 Sv/Bq + Specific inhalation toxicity : 1.90E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 2.77000E-01 MeV frac = 1.00000E+00 Product nuclide = 57139.82c : EC/beta+ + + Nuclide 1218 / 1657 : 581391 -- cerium 139m (Ce-139m) + + Pointers : 1583379 -1000000 + Primary type : Decay + Nuclide ZAI : 581391 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 138.90628 + Atomic weight ratio (AWR) : 137.71300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 56.1 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 7.54240E-01 MeV frac = 1.00000E+00 Product nuclide = 581390 : IT + + Nuclide 1219 / 1657 : 581450 -- cerium 145 (Ce-145) + + Pointers : 1599324 -1000000 + Primary type : Decay + Nuclide ZAI : 581450 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 144.91691 + Atomic weight ratio (AWR) : 143.67200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.77E+02 seconds (2.95 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.53500E+00 MeV frac = 1.00000E+00 Product nuclide = 591450 : beta- + + Nuclide 1220 / 1657 : 581460 -- cerium 146 (Ce-146) + + Pointers : 1603307 -1000000 + Primary type : Decay + Nuclide ZAI : 581460 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 145.91852 + Atomic weight ratio (AWR) : 144.66500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.11E+02 seconds (13.5 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.03001E+00 MeV frac = 1.00000E+00 Product nuclide = 591460 : beta- + + Nuclide 1221 / 1657 : 581470 -- cerium 147 (Ce-147) + + Pointers : 1603491 -1000000 + Primary type : Decay + Nuclide ZAI : 581470 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 146.92214 + Atomic weight ratio (AWR) : 145.66000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 57 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.29000E+00 MeV frac = 1.00000E+00 Product nuclide = 591470 : beta- + + Nuclide 1222 / 1657 : 581480 -- cerium 148 (Ce-148) + + Pointers : 1606830 -1000000 + Primary type : Decay + Nuclide ZAI : 581480 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 147.92475 + Atomic weight ratio (AWR) : 146.65400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 56 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.14000E+00 MeV frac = 1.00000E+00 Product nuclide = 591480 : beta- + + Nuclide 1223 / 1657 : 581490 -- cerium 149 (Ce-149) + + Pointers : 1607014 -1000000 + Primary type : Decay + Nuclide ZAI : 581490 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 148.92837 + Atomic weight ratio (AWR) : 147.64900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.36000E+00 MeV frac = 1.00000E+00 Product nuclide = 591490 : beta- + + Nuclide 1224 / 1657 : 581500 -- cerium 150 (Ce-150) + + Pointers : 1608575 -1000000 + Primary type : Decay + Nuclide ZAI : 581500 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 149.92998 + Atomic weight ratio (AWR) : 148.64200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.48400E+00 MeV frac = 1.00000E+00 Product nuclide = 591500 : beta- + + Nuclide 1225 / 1657 : 581510 -- cerium 151 (Ce-151) + + Pointers : 1608759 -1000000 + Primary type : Decay + Nuclide ZAI : 581510 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 150.93360 + Atomic weight ratio (AWR) : 149.63700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.02 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.27100E+00 MeV frac = 1.00000E+00 Product nuclide = 591510 : beta- + + Nuclide 1226 / 1657 : 581520 -- cerium 152 (Ce-152) + + Pointers : 1608943 -1000000 + Primary type : Decay + Nuclide ZAI : 581520 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 151.93621 + Atomic weight ratio (AWR) : 150.63100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.1 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.70000E+00 MeV frac = 1.00000E+00 Product nuclide = 591520 : beta- + + Nuclide 1227 / 1657 : 581530 -- cerium 153 (Ce-153) + + Pointers : 1609127 -1000000 + Primary type : Decay + Nuclide ZAI : 581530 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 152.93883 + Atomic weight ratio (AWR) : 151.62500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 5.83900E+00 MeV frac = 9.93780E-01 Product nuclide = 591530 : beta- + 2 RTYP = 15 Q = 1.63600E+00 MeV frac = 6.21900E-03 Product nuclide = 591520 : beta- + neutron emission + + Nuclide 1228 / 1657 : 581540 -- cerium 154 (Ce-154) + + Pointers : 1613310 -1000000 + Primary type : Decay + Nuclide ZAI : 581540 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 153.94043 + Atomic weight ratio (AWR) : 152.61800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 5.02000E+00 MeV frac = 9.93630E-01 Product nuclide = 591540 : beta- + 2 RTYP = 15 Q = 1.65900E+00 MeV frac = 6.37300E-03 Product nuclide = 591530 : beta- + neutron emission + + Nuclide 1229 / 1657 : 581550 -- cerium 155 (Ce-155) + + Pointers : 1617010 -1000000 + Primary type : Decay + Nuclide ZAI : 581550 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 154.94809 + Atomic weight ratio (AWR) : 153.61700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.38000E+00 MeV frac = 1.00000E+00 Product nuclide = 591550 : beta- + + Nuclide 1230 / 1657 : 581560 -- cerium 156 (Ce-156) + + Pointers : 1617194 -1000000 + Primary type : Decay + Nuclide ZAI : 581560 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 155.95171 + Atomic weight ratio (AWR) : 154.61200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.15 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.51000E+00 MeV frac = 1.00000E+00 Product nuclide = 591560 : beta- + + Nuclide 1231 / 1657 : 581570 -- cerium 157 (Ce-157) + + Pointers : 1617378 -1000000 + Primary type : Decay + Nuclide ZAI : 581570 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 156.95634 + Atomic weight ratio (AWR) : 155.60800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 50 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.30000E+00 MeV frac = 1.00000E+00 Product nuclide = 591570 : beta- + + Nuclide 1232 / 1657 : 591390 -- praseodymium 139 (Pr-139) + + Pointers : 1617562 -1000000 + Primary type : Decay + Nuclide ZAI : 591390 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 138.90930 + Atomic weight ratio (AWR) : 137.71600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.59E+04 seconds (4.41 hours) + Specific ingestion toxicity : 3.10E-11 Sv/Bq + Specific inhalation toxicity : 2.00E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 2.12900E+00 MeV frac = 9.99836E-01 Product nuclide = 581390 : EC/beta+ + 2 RTYP = 2 Q = 1.37476E+00 MeV frac = 1.63980E-04 Product nuclide = 581391 : EC/beta+ + + Nuclide 1233 / 1657 : 591400 -- praseodymium 140 (Pr-140) + + Pointers : 1618496 -1000000 + Primary type : Decay + Nuclide ZAI : 591400 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 139.90889 + Atomic weight ratio (AWR) : 138.70700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.03E+02 seconds (3.39 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 3.38800E+00 MeV frac = 1.00000E+00 Product nuclide = 58140.82c : EC/beta+ + + Nuclide 1234 / 1657 : 591421 -- praseodymium 142m (Pr-142m) + + Pointers : 1626194 -1000000 + Primary type : Decay + Nuclide ZAI : 591421 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 141.91008 + Atomic weight ratio (AWR) : 140.69100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.76E+02 seconds (14.6 minutes) + Specific ingestion toxicity : 1.70E-11 Sv/Bq + Specific inhalation toxicity : 7.00E-12 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 3.69400E-03 MeV frac = 1.00000E+00 Product nuclide = 59142.82c : IT + + Nuclide 1235 / 1657 : 591440 -- praseodymium 144 (Pr-144) + + Pointers : 1629691 -1000000 + Primary type : Decay + Nuclide ZAI : 591440 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 143.91329 + Atomic weight ratio (AWR) : 142.67700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.04E+03 seconds (17.3 minutes) + Specific ingestion toxicity : 5.00E-11 Sv/Bq + Specific inhalation toxicity : 1.80E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.99740E+00 MeV frac = 1.00000E+00 Product nuclide = 60144.82c : beta- + + Nuclide 1236 / 1657 : 591441 -- praseodymium 144m (Pr-144m) + + Pointers : 1631266 -1000000 + Primary type : Decay + Nuclide ZAI : 591441 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 143.91329 + Atomic weight ratio (AWR) : 142.67700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.32E+02 seconds (7.2 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 5.90300E-02 MeV frac = 9.99400E-01 Product nuclide = 591440 : IT + 2 RTYP = 1 Q = 3.05643E+00 MeV frac = 6.00000E-04 Product nuclide = 60144.82c : beta- + + Nuclide 1237 / 1657 : 591450 -- praseodymium 145 (Pr-145) + + Pointers : 1632130 -1000000 + Primary type : Decay + Nuclide ZAI : 591450 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 144.91490 + Atomic weight ratio (AWR) : 143.67000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.15E+04 seconds (5.98 hours) + Specific ingestion toxicity : 3.90E-10 Sv/Bq + Specific inhalation toxicity : 1.70E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.80510E+00 MeV frac = 1.00000E+00 Product nuclide = 60145.82c : beta- + + Nuclide 1238 / 1657 : 591460 -- praseodymium 146 (Pr-146) + + Pointers : 1632314 -1000000 + Primary type : Decay + Nuclide ZAI : 591460 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 145.91751 + Atomic weight ratio (AWR) : 144.66400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.45E+03 seconds (24.1 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.16900E+00 MeV frac = 1.00000E+00 Product nuclide = 60146.82c : beta- + + Nuclide 1239 / 1657 : 591470 -- praseodymium 147 (Pr-147) + + Pointers : 1634323 -1000000 + Primary type : Decay + Nuclide ZAI : 591470 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 146.91911 + Atomic weight ratio (AWR) : 145.65700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.04E+02 seconds (13.4 minutes) + Specific ingestion toxicity : 3.30E-11 Sv/Bq + Specific inhalation toxicity : 1.80E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.69690E+00 MeV frac = 1.00000E+00 Product nuclide = 60147.82c : beta- + + Nuclide 1240 / 1657 : 591480 -- praseodymium 148 (Pr-148) + + Pointers : 1634507 -1000000 + Primary type : Decay + Nuclide ZAI : 591480 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 147.92173 + Atomic weight ratio (AWR) : 146.65100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.37E+02 seconds (2.29 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.93000E+00 MeV frac = 1.00000E+00 Product nuclide = 60148.82c : beta- + + Nuclide 1241 / 1657 : 591481 -- praseodymium 148m (Pr-148m) + + Pointers : 1635942 -1000000 + Primary type : Decay + Nuclide ZAI : 591481 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 147.92173 + Atomic weight ratio (AWR) : 146.65100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.21E+02 seconds (2.02 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.05000E+00 MeV frac = 1.00000E+00 Product nuclide = 60148.82c : beta- + + Nuclide 1242 / 1657 : 591490 -- praseodymium 149 (Pr-149) + + Pointers : 1636327 -1000000 + Primary type : Decay + Nuclide ZAI : 591490 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 148.92333 + Atomic weight ratio (AWR) : 147.64400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.36E+02 seconds (2.26 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.39700E+00 MeV frac = 1.00000E+00 Product nuclide = 601490 : beta- + + Nuclide 1243 / 1657 : 591500 -- praseodymium 150 (Pr-150) + + Pointers : 1639064 -1000000 + Primary type : Decay + Nuclide ZAI : 591500 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 149.92695 + Atomic weight ratio (AWR) : 148.63900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.1 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.69000E+00 MeV frac = 1.00000E+00 Product nuclide = 60150.82c : beta- + + Nuclide 1244 / 1657 : 591510 -- praseodymium 151 (Pr-151) + + Pointers : 1641311 -1000000 + Primary type : Decay + Nuclide ZAI : 591510 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 150.92856 + Atomic weight ratio (AWR) : 149.63200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 18.9 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.18200E+00 MeV frac = 1.00000E+00 Product nuclide = 601510 : beta- + + Nuclide 1245 / 1657 : 591520 -- praseodymium 152 (Pr-152) + + Pointers : 1641495 -1000000 + Primary type : Decay + Nuclide ZAI : 591520 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 151.93117 + Atomic weight ratio (AWR) : 150.62600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.63 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.44000E+00 MeV frac = 1.00000E+00 Product nuclide = 601520 : beta- + + Nuclide 1246 / 1657 : 591530 -- praseodymium 153 (Pr-153) + + Pointers : 1644078 -1000000 + Primary type : Decay + Nuclide ZAI : 591530 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 152.93378 + Atomic weight ratio (AWR) : 151.62000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.28 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.71901E+00 MeV frac = 1.00000E+00 Product nuclide = 601530 : beta- + + Nuclide 1247 / 1657 : 591540 -- praseodymium 154 (Pr-154) + + Pointers : 1644262 -1000000 + Primary type : Decay + Nuclide ZAI : 591540 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 153.93740 + Atomic weight ratio (AWR) : 152.61500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.49000E+00 MeV frac = 1.00000E+00 Product nuclide = 601540 : beta- + + Nuclide 1248 / 1657 : 591550 -- praseodymium 155 (Pr-155) + + Pointers : 1644446 -1000000 + Primary type : Decay + Nuclide ZAI : 591550 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 154.94002 + Atomic weight ratio (AWR) : 153.60900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.69000E+00 MeV frac = 1.00000E+00 Product nuclide = 601550 : beta- + + Nuclide 1249 / 1657 : 591560 -- praseodymium 156 (Pr-156) + + Pointers : 1644630 -1000000 + Primary type : Decay + Nuclide ZAI : 591560 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 155.94263 + Atomic weight ratio (AWR) : 154.60300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.70600E+00 MeV frac = 9.72830E-01 Product nuclide = 601560 : beta- + 2 RTYP = 15 Q = 2.80900E+00 MeV frac = 2.71700E-02 Product nuclide = 601550 : beta- + neutron emission + + Nuclide 1250 / 1657 : 591570 -- praseodymium 157 (Pr-157) + + Pointers : 1650886 -1000000 + Primary type : Decay + Nuclide ZAI : 591570 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 156.94524 + Atomic weight ratio (AWR) : 155.59700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.14700E+00 MeV frac = 9.36130E-01 Product nuclide = 601570 : beta- + 2 RTYP = 15 Q = 3.60900E+00 MeV frac = 6.38740E-02 Product nuclide = 601560 : beta- + neutron emission + + Nuclide 1251 / 1657 : 591580 -- praseodymium 158 (Pr-158) + + Pointers : 1657046 -1000000 + Primary type : Decay + Nuclide ZAI : 591580 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 157.95189 + Atomic weight ratio (AWR) : 156.59500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.67000E+00 MeV frac = 1.00000E+00 Product nuclide = 601580 : beta- + + Nuclide 1252 / 1657 : 591590 -- praseodymium 159 (Pr-159) + + Pointers : 1657230 -1000000 + Primary type : Decay + Nuclide ZAI : 591590 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 158.95551 + Atomic weight ratio (AWR) : 157.59000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 100 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.77000E+00 MeV frac = 1.00000E+00 Product nuclide = 601590 : beta- + + Nuclide 1253 / 1657 : 601420 -- neodymium 142 (Nd-142) + + Pointers : 1657414 -1000000 + Primary type : Decay + Nuclide ZAI : 601420 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 141.90807 + Atomic weight ratio (AWR) : 140.68900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1254 / 1657 : 601430 -- neodymium 143 (Nd-143) + + Pointers : 1657520 -1000000 + Primary type : Decay + Nuclide ZAI : 601430 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 142.90967 + Atomic weight ratio (AWR) : 141.68200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1255 / 1657 : 601490 -- neodymium 149 (Nd-149) + + Pointers : 1680327 -1000000 + Primary type : Decay + Nuclide ZAI : 601490 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 148.92030 + Atomic weight ratio (AWR) : 147.64100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.22E+03 seconds (1.73 hours) + Specific ingestion toxicity : 1.20E-10 Sv/Bq + Specific inhalation toxicity : 8.90E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.69100E+00 MeV frac = 1.00000E+00 Product nuclide = 61149.82c : beta- + + Nuclide 1256 / 1657 : 601510 -- neodymium 151 (Nd-151) + + Pointers : 1690163 -1000000 + Primary type : Decay + Nuclide ZAI : 601510 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 150.92351 + Atomic weight ratio (AWR) : 149.62700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.46E+02 seconds (12.4 minutes) + Specific ingestion toxicity : 3.00E-11 Sv/Bq + Specific inhalation toxicity : 1.70E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.44200E+00 MeV frac = 1.00000E+00 Product nuclide = 61151.82c : beta- + + Nuclide 1257 / 1657 : 601520 -- neodymium 152 (Nd-152) + + Pointers : 1700656 -1000000 + Primary type : Decay + Nuclide ZAI : 601520 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 151.92512 + Atomic weight ratio (AWR) : 150.62000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.84E+02 seconds (11.4 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.10400E+00 MeV frac = 1.00000E+00 Product nuclide = 611520 : beta- + + Nuclide 1258 / 1657 : 601530 -- neodymium 153 (Nd-153) + + Pointers : 1700840 -1000000 + Primary type : Decay + Nuclide ZAI : 601530 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 152.92773 + Atomic weight ratio (AWR) : 151.61400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 31.6 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.33600E+00 MeV frac = 1.00000E+00 Product nuclide = 611530 : beta- + + Nuclide 1259 / 1657 : 601540 -- neodymium 154 (Nd-154) + + Pointers : 1701024 -1000000 + Primary type : Decay + Nuclide ZAI : 601540 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 153.92933 + Atomic weight ratio (AWR) : 152.60700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 25.9 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.81000E+00 MeV frac = 1.00000E+00 Product nuclide = 611540 : beta- + + Nuclide 1260 / 1657 : 601550 -- neodymium 155 (Nd-155) + + Pointers : 1701208 -1000000 + Primary type : Decay + Nuclide ZAI : 601550 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 154.93296 + Atomic weight ratio (AWR) : 153.60200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.9 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 611550 : beta- + + Nuclide 1261 / 1657 : 601560 -- neodymium 156 (Nd-156) + + Pointers : 1701392 -1000000 + Primary type : Decay + Nuclide ZAI : 601560 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 155.93456 + Atomic weight ratio (AWR) : 154.59500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.49 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.69000E+00 MeV frac = 1.00000E+00 Product nuclide = 611560 : beta- + + Nuclide 1262 / 1657 : 601570 -- neodymium 157 (Nd-157) + + Pointers : 1701576 -1000000 + Primary type : Decay + Nuclide ZAI : 601570 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 156.93717 + Atomic weight ratio (AWR) : 155.58900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.57000E+00 MeV frac = 1.00000E+00 Product nuclide = 611570 : beta- + + Nuclide 1263 / 1657 : 601580 -- neodymium 158 (Nd-158) + + Pointers : 1705004 -1000000 + Primary type : Decay + Nuclide ZAI : 601580 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 157.93979 + Atomic weight ratio (AWR) : 156.58300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.7 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 5.01100E+00 MeV frac = 9.99950E-01 Product nuclide = 611580 : beta- + 2 RTYP = 15 Q = 3.39000E-01 MeV frac = 5.30000E-05 Product nuclide = 611570 : beta- + neutron emission + + Nuclide 1264 / 1657 : 601590 -- neodymium 159 (Nd-159) + + Pointers : 1708305 -1000000 + Primary type : Decay + Nuclide ZAI : 601590 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 158.94442 + Atomic weight ratio (AWR) : 157.57900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 7.16600E+00 MeV frac = 9.97640E-01 Product nuclide = 611590 : beta- + 2 RTYP = 15 Q = 1.24900E+00 MeV frac = 2.36100E-03 Product nuclide = 611580 : beta- + neutron emission + + Nuclide 1265 / 1657 : 601600 -- neodymium 160 (Nd-160) + + Pointers : 1713169 -1000000 + Primary type : Decay + Nuclide ZAI : 601600 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 159.94703 + Atomic weight ratio (AWR) : 158.57300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 6.36500E+00 MeV frac = 9.90530E-01 Product nuclide = 611600 : beta- + 2 RTYP = 15 Q = 1.84900E+00 MeV frac = 9.46900E-03 Product nuclide = 611590 : beta- + neutron emission + + Nuclide 1266 / 1657 : 601610 -- neodymium 161 (Nd-161) + + Pointers : 1717733 -1000000 + Primary type : Decay + Nuclide ZAI : 601610 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 160.95368 + Atomic weight ratio (AWR) : 159.57100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.47000E+00 MeV frac = 1.00000E+00 Product nuclide = 611610 : beta- + + Nuclide 1267 / 1657 : 611450 -- promethium 145 (Pm-145) + + Pointers : 1717917 -1000000 + Primary type : Decay + Nuclide ZAI : 611450 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 144.91288 + Atomic weight ratio (AWR) : 143.66800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.59E+08 seconds (17.7 years) + Specific ingestion toxicity : 1.10E-10 Sv/Bq + Specific inhalation toxicity : 3.60E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 1.61400E-01 MeV frac = 1.00000E+00 Product nuclide = 60145.82c : EC/beta+ + 2 RTYP = 4 Q = 2.32200E+00 MeV frac = 2.80000E-09 Product nuclide = 59141.82c : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 2.32200E+00 MeV frac = 2.80000E-09 Product nuclide = 2004.82c : alpha + + Nuclide 1268 / 1657 : 611460 -- promethium 146 (Pm-146) + + Pointers : 1718546 -1000000 + Primary type : Decay + Nuclide ZAI : 611460 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 145.91448 + Atomic weight ratio (AWR) : 144.66100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.75E+08 seconds (5.53 years) + Specific ingestion toxicity : 9.00E-10 Sv/Bq + Specific inhalation toxicity : 2.10E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.54200E+00 MeV frac = 3.40000E-01 Product nuclide = 621460 : beta- + 2 RTYP = 2 Q = 1.48200E+00 MeV frac = 6.60000E-01 Product nuclide = 60146.82c : EC/beta+ + + Nuclide 1269 / 1657 : 611500 -- promethium 150 (Pm-150) + + Pointers : 1735699 -1000000 + Primary type : Decay + Nuclide ZAI : 611500 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 149.92090 + Atomic weight ratio (AWR) : 148.63300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.71E+03 seconds (2.7 hours) + Specific ingestion toxicity : 2.60E-10 Sv/Bq + Specific inhalation toxicity : 1.30E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.45400E+00 MeV frac = 1.00000E+00 Product nuclide = 62150.82c : beta- + + Nuclide 1270 / 1657 : 611520 -- promethium 152 (Pm-152) + + Pointers : 1752755 -1000000 + Primary type : Decay + Nuclide ZAI : 611520 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 151.92310 + Atomic weight ratio (AWR) : 150.61800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.47E+02 seconds (4.12 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 62152.82c : beta- + + Nuclide 1271 / 1657 : 611521 -- promethium 152m (Pm-152m) + + Pointers : 1755394 -1000000 + Primary type : Decay + Nuclide ZAI : 611521 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 151.92310 + Atomic weight ratio (AWR) : 150.61800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.51E+02 seconds (7.52 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.65000E+00 MeV frac = 1.00000E+00 Product nuclide = 62152.82c : beta- + + Nuclide 1272 / 1657 : 611522 -- promethium 152m (Pm-152m) + + Pointers : 3512934 -1000000 + Primary type : Decay + Nuclide ZAI : 611522 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 151.92310 + Atomic weight ratio (AWR) : 150.61800 + Temperature : 900.0 Kelvin + XS temperature : -1.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.64E+02 seconds (14.4 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is not present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.82500E+00 MeV frac = 1.00000E+00 Product nuclide = 62152.82c : beta- + + Nuclide 1273 / 1657 : 611530 -- promethium 153 (Pm-153) + + Pointers : 1757151 -1000000 + Primary type : Decay + Nuclide ZAI : 611530 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 152.92370 + Atomic weight ratio (AWR) : 151.61000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.15E+02 seconds (5.25 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.88100E+00 MeV frac = 1.00000E+00 Product nuclide = 62153.82c : beta- + + Nuclide 1274 / 1657 : 611540 -- promethium 154 (Pm-154) + + Pointers : 1759230 -1000000 + Primary type : Decay + Nuclide ZAI : 611540 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 153.92631 + Atomic weight ratio (AWR) : 152.60400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.04E+02 seconds (1.73 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.96160E+00 MeV frac = 1.00000E+00 Product nuclide = 62154.82c : beta- + + Nuclide 1275 / 1657 : 611541 -- promethium 154m (Pm-154m) + + Pointers : 1759414 -1000000 + Primary type : Decay + Nuclide ZAI : 611541 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 153.92631 + Atomic weight ratio (AWR) : 152.60400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.61E+02 seconds (2.68 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.01160E+00 MeV frac = 1.00000E+00 Product nuclide = 62154.82c : beta- + + Nuclide 1276 / 1657 : 611550 -- promethium 155 (Pm-155) + + Pointers : 1759598 -1000000 + Primary type : Decay + Nuclide ZAI : 611550 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 154.92791 + Atomic weight ratio (AWR) : 153.59700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 41.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.22000E+00 MeV frac = 1.00000E+00 Product nuclide = 621550 : beta- + + Nuclide 1277 / 1657 : 611560 -- promethium 156 (Pm-156) + + Pointers : 1760739 -1000000 + Primary type : Decay + Nuclide ZAI : 611560 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 155.93153 + Atomic weight ratio (AWR) : 154.59200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 26.7 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.15000E+00 MeV frac = 1.00000E+00 Product nuclide = 621560 : beta- + + Nuclide 1278 / 1657 : 611570 -- promethium 157 (Pm-157) + + Pointers : 1760923 -1000000 + Primary type : Decay + Nuclide ZAI : 611570 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 156.93314 + Atomic weight ratio (AWR) : 155.58500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 10.6 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.36000E+00 MeV frac = 1.00000E+00 Product nuclide = 621570 : beta- + + Nuclide 1279 / 1657 : 611580 -- promethium 158 (Pm-158) + + Pointers : 1761107 -1000000 + Primary type : Decay + Nuclide ZAI : 611580 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 157.93676 + Atomic weight ratio (AWR) : 156.58000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.8 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.12000E+00 MeV frac = 1.00000E+00 Product nuclide = 621580 : beta- + + Nuclide 1280 / 1657 : 611590 -- promethium 159 (Pm-159) + + Pointers : 1761291 -1000000 + Primary type : Decay + Nuclide ZAI : 611590 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 158.93836 + Atomic weight ratio (AWR) : 157.57300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 5.66400E+00 MeV frac = 9.99820E-01 Product nuclide = 621590 : beta- + 2 RTYP = 15 Q = 4.19000E-01 MeV frac = 1.85000E-04 Product nuclide = 621580 : beta- + neutron emission + + Nuclide 1281 / 1657 : 611600 -- promethium 160 (Pm-160) + + Pointers : 1765006 -1000000 + Primary type : Decay + Nuclide ZAI : 611600 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 159.94199 + Atomic weight ratio (AWR) : 158.56800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 7.81900E+00 MeV frac = 9.97320E-01 Product nuclide = 621600 : beta- + 2 RTYP = 15 Q = 1.14900E+00 MeV frac = 2.67600E-03 Product nuclide = 621590 : beta- + neutron emission + + Nuclide 1282 / 1657 : 611610 -- promethium 161 (Pm-161) + + Pointers : 1770230 -1000000 + Primary type : Decay + Nuclide ZAI : 611610 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 160.94561 + Atomic weight ratio (AWR) : 159.56300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.7 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.55000E+00 MeV frac = 1.00000E+00 Product nuclide = 621610 : beta- + + Nuclide 1283 / 1657 : 611620 -- promethium 162 (Pm-162) + + Pointers : 1770414 -1000000 + Primary type : Decay + Nuclide ZAI : 611620 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 161.95024 + Atomic weight ratio (AWR) : 160.55900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.44000E+00 MeV frac = 1.00000E+00 Product nuclide = 621620 : beta- + + Nuclide 1284 / 1657 : 611630 -- promethium 163 (Pm-163) + + Pointers : 1770598 -1000000 + Primary type : Decay + Nuclide ZAI : 611630 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 162.95386 + Atomic weight ratio (AWR) : 161.55400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.75000E+00 MeV frac = 1.00000E+00 Product nuclide = 621630 : beta- + + Nuclide 1285 / 1657 : 621460 -- samarium 146 (Sm-146) + + Pointers : 1770782 -1000000 + Primary type : Decay + Nuclide ZAI : 621460 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 145.91347 + Atomic weight ratio (AWR) : 144.66000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.16E+15 seconds (100 million years) + Specific ingestion toxicity : 5.40E-08 Sv/Bq + Specific inhalation toxicity : 1.10E-05 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 4 Q = 2.57000E+00 MeV frac = 1.00000E+00 Product nuclide = 601420 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 2.57000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 1286 / 1657 : 621531 -- samarium 153m (Sm-153m) + + Pointers : 1800130 -1000000 + Primary type : Decay + Nuclide ZAI : 621531 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 152.92168 + Atomic weight ratio (AWR) : 151.60800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 10.6 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 9.83700E-02 MeV frac = 1.00000E+00 Product nuclide = 62153.82c : IT + + Nuclide 1287 / 1657 : 621550 -- samarium 155 (Sm-155) + + Pointers : 1805024 -1000000 + Primary type : Decay + Nuclide ZAI : 621550 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 154.92489 + Atomic weight ratio (AWR) : 153.59400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.34E+03 seconds (22.3 minutes) + Specific ingestion toxicity : 2.90E-11 Sv/Bq + Specific inhalation toxicity : 1.70E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.62720E+00 MeV frac = 1.00000E+00 Product nuclide = 63155.82c : beta- + + Nuclide 1288 / 1657 : 621560 -- samarium 156 (Sm-156) + + Pointers : 1806935 -1000000 + Primary type : Decay + Nuclide ZAI : 621560 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 155.92548 + Atomic weight ratio (AWR) : 154.58600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.38E+04 seconds (9.4 hours) + Specific ingestion toxicity : 2.50E-10 Sv/Bq + Specific inhalation toxicity : 2.20E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.22000E-01 MeV frac = 1.00000E+00 Product nuclide = 63156.82c : beta- + + Nuclide 1289 / 1657 : 621570 -- samarium 157 (Sm-157) + + Pointers : 1807922 -1000000 + Primary type : Decay + Nuclide ZAI : 621570 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 156.92810 + Atomic weight ratio (AWR) : 155.58000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.82E+02 seconds (8.03 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.73700E+00 MeV frac = 1.00000E+00 Product nuclide = 63157.82c : beta- + + Nuclide 1290 / 1657 : 621580 -- samarium 158 (Sm-158) + + Pointers : 1808106 -1000000 + Primary type : Decay + Nuclide ZAI : 621580 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 157.92970 + Atomic weight ratio (AWR) : 156.57300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.18E+02 seconds (5.3 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 631580 : beta- + + Nuclide 1291 / 1657 : 621590 -- samarium 159 (Sm-159) + + Pointers : 1808290 -1000000 + Primary type : Decay + Nuclide ZAI : 621590 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 158.93332 + Atomic weight ratio (AWR) : 157.56800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 11.4 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.80500E+00 MeV frac = 1.00000E+00 Product nuclide = 631590 : beta- + + Nuclide 1292 / 1657 : 621600 -- samarium 160 (Sm-160) + + Pointers : 1809809 -1000000 + Primary type : Decay + Nuclide ZAI : 621600 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 159.93493 + Atomic weight ratio (AWR) : 158.56100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.6 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.95000E+00 MeV frac = 1.00000E+00 Product nuclide = 631600 : beta- + + Nuclide 1293 / 1657 : 621610 -- samarium 161 (Sm-161) + + Pointers : 1809993 -1000000 + Primary type : Decay + Nuclide ZAI : 621610 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 160.93855 + Atomic weight ratio (AWR) : 159.55600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.8 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.80000E+00 MeV frac = 1.00000E+00 Product nuclide = 631610 : beta- + + Nuclide 1294 / 1657 : 621620 -- samarium 162 (Sm-162) + + Pointers : 1810177 -1000000 + Primary type : Decay + Nuclide ZAI : 621620 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 161.94116 + Atomic weight ratio (AWR) : 160.55000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.4 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.90000E+00 MeV frac = 1.00000E+00 Product nuclide = 631620 : beta- + + Nuclide 1295 / 1657 : 621630 -- samarium 163 (Sm-163) + + Pointers : 1810361 -1000000 + Primary type : Decay + Nuclide ZAI : 621630 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 162.94579 + Atomic weight ratio (AWR) : 161.54600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.73000E+00 MeV frac = 1.00000E+00 Product nuclide = 631630 : beta- + + Nuclide 1296 / 1657 : 621640 -- samarium 164 (Sm-164) + + Pointers : 1810545 -1000000 + Primary type : Decay + Nuclide ZAI : 621640 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 163.94840 + Atomic weight ratio (AWR) : 162.54000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.92000E+00 MeV frac = 1.00000E+00 Product nuclide = 631640 : beta- + + Nuclide 1297 / 1657 : 621650 -- samarium 165 (Sm-165) + + Pointers : 1810729 -1000000 + Primary type : Decay + Nuclide ZAI : 621650 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 164.95303 + Atomic weight ratio (AWR) : 163.53600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.76000E+00 MeV frac = 1.00000E+00 Product nuclide = 631650 : beta- + + Nuclide 1298 / 1657 : 631490 -- europium 149 (Eu-149) + + Pointers : 1810913 -1000000 + Primary type : Decay + Nuclide ZAI : 631490 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 148.91829 + Atomic weight ratio (AWR) : 147.63900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.04E+06 seconds (93.1 days) + Specific ingestion toxicity : 1.00E-10 Sv/Bq + Specific inhalation toxicity : 2.90E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 6.95000E-01 MeV frac = 1.00000E+00 Product nuclide = 62149.82c : EC/beta+ + + Nuclide 1299 / 1657 : 631500 -- europium 150 (Eu-150) + + Pointers : 1812670 -1000000 + Primary type : Decay + Nuclide ZAI : 631500 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 149.91989 + Atomic weight ratio (AWR) : 148.63200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.15E+09 seconds (36.4 years) + Specific ingestion toxicity : 1.30E-09 Sv/Bq + Specific inhalation toxicity : 5.30E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 2.29500E+00 MeV frac = 1.00000E+00 Product nuclide = 62150.82c : EC/beta+ + + Nuclide 1300 / 1657 : 631521 -- europium 152m (Eu-152m) + + Pointers : 1833374 -1000000 + Primary type : Decay + Nuclide ZAI : 631521 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 151.92209 + Atomic weight ratio (AWR) : 150.61700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.34E+04 seconds (9.27 hours) + Specific ingestion toxicity : 5.00E-10 Sv/Bq + Specific inhalation toxicity : 2.20E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.86770E+00 MeV frac = 7.20000E-01 Product nuclide = 64152.82c : beta- + 2 RTYP = 2 Q = 1.92170E+00 MeV frac = 2.80000E-01 Product nuclide = 62152.82c : EC/beta+ + + Nuclide 1301 / 1657 : 631522 -- europium 152m (Eu-152m) + + Pointers : 3516175 -1000000 + Primary type : Decay + Nuclide ZAI : 631522 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 151.92209 + Atomic weight ratio (AWR) : 150.61700 + Temperature : 900.0 Kelvin + XS temperature : -1.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.76E+03 seconds (1.6 hours) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is not present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.47800E-01 MeV frac = 1.00000E+00 Product nuclide = 63152.82c : IT + + Nuclide 1302 / 1657 : 631541 -- europium 154m (Eu-154m) + + Pointers : 1844134 -1000000 + Primary type : Decay + Nuclide ZAI : 631541 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 153.92328 + Atomic weight ratio (AWR) : 152.60100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.78E+03 seconds (46.4 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.57000E-01 MeV frac = 1.00000E+00 Product nuclide = 63154.82c : IT + + Nuclide 1303 / 1657 : 631580 -- europium 158 (Eu-158) + + Pointers : 1864140 -1000000 + Primary type : Decay + Nuclide ZAI : 631580 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 157.92768 + Atomic weight ratio (AWR) : 156.57100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.75E+03 seconds (45.9 minutes) + Specific ingestion toxicity : 9.40E-11 Sv/Bq + Specific inhalation toxicity : 4.70E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.48500E+00 MeV frac = 1.00000E+00 Product nuclide = 64158.82c : beta- + + Nuclide 1304 / 1657 : 631590 -- europium 159 (Eu-159) + + Pointers : 1867409 -1000000 + Primary type : Decay + Nuclide ZAI : 631590 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 158.92929 + Atomic weight ratio (AWR) : 157.56400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.09E+03 seconds (18.1 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.51500E+00 MeV frac = 1.00000E+00 Product nuclide = 641590 : beta- + + Nuclide 1305 / 1657 : 631600 -- europium 160 (Eu-160) + + Pointers : 1869376 -1000000 + Primary type : Decay + Nuclide ZAI : 631600 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 159.93190 + Atomic weight ratio (AWR) : 158.55800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 38 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.57861E+00 MeV frac = 1.00000E+00 Product nuclide = 64160.82c : beta- + + Nuclide 1306 / 1657 : 631610 -- europium 161 (Eu-161) + + Pointers : 1869560 -1000000 + Primary type : Decay + Nuclide ZAI : 631610 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 160.93350 + Atomic weight ratio (AWR) : 159.55100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 26 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.73270E+00 MeV frac = 1.00000E+00 Product nuclide = 641610 : beta- + + Nuclide 1307 / 1657 : 631620 -- europium 162 (Eu-162) + + Pointers : 1869744 -1000000 + Primary type : Decay + Nuclide ZAI : 631620 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 161.93713 + Atomic weight ratio (AWR) : 160.54600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 10.6 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.63700E+00 MeV frac = 1.00000E+00 Product nuclide = 641620 : beta- + + Nuclide 1308 / 1657 : 631630 -- europium 163 (Eu-163) + + Pointers : 1869928 -1000000 + Primary type : Decay + Nuclide ZAI : 631630 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 162.93873 + Atomic weight ratio (AWR) : 161.53900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.86000E+00 MeV frac = 1.00000E+00 Product nuclide = 641630 : beta- + + Nuclide 1309 / 1657 : 631640 -- europium 164 (Eu-164) + + Pointers : 1870112 -1000000 + Primary type : Decay + Nuclide ZAI : 631640 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 163.94336 + Atomic weight ratio (AWR) : 162.53500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.65000E+00 MeV frac = 1.00000E+00 Product nuclide = 641640 : beta- + + Nuclide 1310 / 1657 : 631650 -- europium 165 (Eu-165) + + Pointers : 1870296 -1000000 + Primary type : Decay + Nuclide ZAI : 631650 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 164.94597 + Atomic weight ratio (AWR) : 163.52900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.91000E+00 MeV frac = 1.00000E+00 Product nuclide = 641650 : beta- + + Nuclide 1311 / 1657 : 631660 -- europium 166 (Eu-166) + + Pointers : 1870480 -1000000 + Primary type : Decay + Nuclide ZAI : 631660 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 165.94960 + Atomic weight ratio (AWR) : 164.52400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.4 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.80000E+00 MeV frac = 1.00000E+00 Product nuclide = 641660 : beta- + + Nuclide 1312 / 1657 : 631670 -- europium 167 (Eu-167) + + Pointers : 1870664 -1000000 + Primary type : Decay + Nuclide ZAI : 631670 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 166.95322 + Atomic weight ratio (AWR) : 165.51900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.11000E+00 MeV frac = 1.00000E+00 Product nuclide = 641670 : beta- + + Nuclide 1313 / 1657 : 641500 -- gadolinium 150 (Gd-150) + + Pointers : 1870848 -1000000 + Primary type : Decay + Nuclide ZAI : 641500 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 149.91888 + Atomic weight ratio (AWR) : 148.63100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.74E+13 seconds (1.82 million years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 4 Q = 2.79700E+00 MeV frac = 1.00000E+00 Product nuclide = 621460 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 2.79700E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 1314 / 1657 : 641510 -- gadolinium 151 (Gd-151) + + Pointers : 1871138 -1000000 + Primary type : Decay + Nuclide ZAI : 641510 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 150.92049 + Atomic weight ratio (AWR) : 149.62400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.07E+07 seconds (124 days) + Specific ingestion toxicity : 2.00E-10 Sv/Bq + Specific inhalation toxicity : 8.60E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 4.65000E-01 MeV frac = 1.00000E+00 Product nuclide = 63151.82c : EC/beta+ + 2 RTYP = 4 Q = 2.67000E+00 MeV frac = 1.00000E-08 Product nuclide = 62147.82c : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 2.67000E+00 MeV frac = 1.00000E-08 Product nuclide = 2004.82c : alpha + + Nuclide 1315 / 1657 : 641530 -- gadolinium 153 (Gd-153) + + Pointers : 1877750 -1000000 + Primary type : Decay + Nuclide ZAI : 641530 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 152.92168 + Atomic weight ratio (AWR) : 151.60800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.08E+07 seconds (240 days) + Specific ingestion toxicity : 2.70E-10 Sv/Bq + Specific inhalation toxicity : 2.10E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 4.83900E-01 MeV frac = 1.00000E+00 Product nuclide = 63153.82c : EC/beta+ + + Nuclide 1316 / 1657 : 641551 -- gadolinium 155m (Gd-155m) + + Pointers : 1885607 -1000000 + Primary type : Decay + Nuclide ZAI : 641551 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 154.92287 + Atomic weight ratio (AWR) : 153.59200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 32 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.21050E-01 MeV frac = 1.00000E+00 Product nuclide = 64155.82c : IT + + Nuclide 1317 / 1657 : 641590 -- gadolinium 159 (Gd-159) + + Pointers : 1894884 -1000000 + Primary type : Decay + Nuclide ZAI : 641590 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 158.92626 + Atomic weight ratio (AWR) : 157.56100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.65E+04 seconds (18.5 hours) + Specific ingestion toxicity : 4.90E-10 Sv/Bq + Specific inhalation toxicity : 2.70E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.70500E-01 MeV frac = 1.00000E+00 Product nuclide = 65159.82c : beta- + + Nuclide 1318 / 1657 : 641610 -- gadolinium 161 (Gd-161) + + Pointers : 1898364 -1000000 + Primary type : Decay + Nuclide ZAI : 641610 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 160.92947 + Atomic weight ratio (AWR) : 159.54700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.20E+02 seconds (3.66 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.95550E+00 MeV frac = 1.00000E+00 Product nuclide = 651610 : beta- + + Nuclide 1319 / 1657 : 641620 -- gadolinium 162 (Gd-162) + + Pointers : 1901493 -1000000 + Primary type : Decay + Nuclide ZAI : 641620 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 161.93107 + Atomic weight ratio (AWR) : 160.54000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.04E+02 seconds (8.4 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.39000E+00 MeV frac = 1.00000E+00 Product nuclide = 651620 : beta- + + Nuclide 1320 / 1657 : 641630 -- gadolinium 163 (Gd-163) + + Pointers : 1902032 -1000000 + Primary type : Decay + Nuclide ZAI : 641630 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 162.93369 + Atomic weight ratio (AWR) : 161.53400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.80E+01 seconds (1.13 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.11000E+00 MeV frac = 1.00000E+00 Product nuclide = 651630 : beta- + + Nuclide 1321 / 1657 : 641640 -- gadolinium 164 (Gd-164) + + Pointers : 1903271 -1000000 + Primary type : Decay + Nuclide ZAI : 641640 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 163.93630 + Atomic weight ratio (AWR) : 162.52800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 45 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.33000E+00 MeV frac = 1.00000E+00 Product nuclide = 651640 : beta- + + Nuclide 1322 / 1657 : 641650 -- gadolinium 165 (Gd-165) + + Pointers : 1903455 -1000000 + Primary type : Decay + Nuclide ZAI : 641650 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 164.93891 + Atomic weight ratio (AWR) : 163.52200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 10.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.19000E+00 MeV frac = 1.00000E+00 Product nuclide = 651650 : beta- + + Nuclide 1323 / 1657 : 641660 -- gadolinium 166 (Gd-166) + + Pointers : 1903639 -1000000 + Primary type : Decay + Nuclide ZAI : 641660 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 165.94153 + Atomic weight ratio (AWR) : 164.51600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.8 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.36000E+00 MeV frac = 1.00000E+00 Product nuclide = 651660 : beta- + + Nuclide 1324 / 1657 : 641670 -- gadolinium 167 (Gd-167) + + Pointers : 1903823 -1000000 + Primary type : Decay + Nuclide ZAI : 641670 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 166.94515 + Atomic weight ratio (AWR) : 165.51100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.14000E+00 MeV frac = 1.00000E+00 Product nuclide = 651670 : beta- + + Nuclide 1325 / 1657 : 641680 -- gadolinium 168 (Gd-168) + + Pointers : 1904007 -1000000 + Primary type : Decay + Nuclide ZAI : 641680 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 167.94877 + Atomic weight ratio (AWR) : 166.50600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.40000E+00 MeV frac = 1.00000E+00 Product nuclide = 651680 : beta- + + Nuclide 1326 / 1657 : 641690 -- gadolinium 169 (Gd-169) + + Pointers : 1904191 -1000000 + Primary type : Decay + Nuclide ZAI : 641690 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 168.95239 + Atomic weight ratio (AWR) : 167.50100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.20000E+00 MeV frac = 1.00000E+00 Product nuclide = 651690 : beta- + + Nuclide 1327 / 1657 : 651560 -- terbium 156 (Tb-156) + + Pointers : 1904375 -1000000 + Primary type : Decay + Nuclide ZAI : 651560 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 155.92447 + Atomic weight ratio (AWR) : 154.58500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.47E+05 seconds (5.17 days) + Specific ingestion toxicity : 1.20E-09 Sv/Bq + Specific inhalation toxicity : 1.20E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 2.44400E+00 MeV frac = 1.00000E+00 Product nuclide = 64156.82c : EC/beta+ + + Nuclide 1328 / 1657 : 651561 -- terbium 156m (Tb-156m) + + Pointers : 1909044 -1000000 + Primary type : Decay + Nuclide ZAI : 651561 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 155.92447 + Atomic weight ratio (AWR) : 154.58500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.78E+04 seconds (1.02 days) + Specific ingestion toxicity : 1.70E-10 Sv/Bq + Specific inhalation toxicity : 2.10E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 6.00000E-02 MeV frac = 1.00000E+00 Product nuclide = 651560 : IT + + Nuclide 1329 / 1657 : 651562 -- terbium 156m (Tb-156m) + + Pointers : 3521071 -1000000 + Primary type : Decay + Nuclide ZAI : 651562 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 155.92447 + Atomic weight ratio (AWR) : 154.58500 + Temperature : 900.0 Kelvin + XS temperature : -1.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.84E+04 seconds (5.1 hours) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is not present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 2.53200E+00 MeV frac = 1.90000E-03 Product nuclide = 64156.82c : EC/beta+ + 2 RTYP = 3 Q = 8.84000E-02 MeV frac = 9.98100E-01 Product nuclide = 651560 : IT + + Nuclide 1330 / 1657 : 651570 -- terbium 157 (Tb-157) + + Pointers : 1909401 -1000000 + Primary type : Decay + Nuclide ZAI : 651570 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 156.92406 + Atomic weight ratio (AWR) : 155.57600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.12E+09 seconds (99.1 years) + Specific ingestion toxicity : 3.40E-11 Sv/Bq + Specific inhalation toxicity : 1.20E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 6.29000E-02 MeV frac = 1.00000E+00 Product nuclide = 64157.82c : EC/beta+ + + Nuclide 1331 / 1657 : 651580 -- terbium 158 (Tb-158) + + Pointers : 1909800 -1000000 + Primary type : Decay + Nuclide ZAI : 651580 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 157.92567 + Atomic weight ratio (AWR) : 156.56900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.68E+09 seconds (180 years) + Specific ingestion toxicity : 1.10E-09 Sv/Bq + Specific inhalation toxicity : 4.60E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 9.34900E-01 MeV frac = 1.68000E-01 Product nuclide = 661580 : beta- + 2 RTYP = 2 Q = 1.21960E+00 MeV frac = 8.32000E-01 Product nuclide = 64158.82c : EC/beta+ + + Nuclide 1332 / 1657 : 651581 -- terbium 158m (Tb-158m) + + Pointers : 1911168 -1000000 + Primary type : Decay + Nuclide ZAI : 651581 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 157.92567 + Atomic weight ratio (AWR) : 156.56900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 10.8 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.10300E-01 MeV frac = 1.00000E+00 Product nuclide = 651580 : IT + + Nuclide 1333 / 1657 : 651610 -- terbium 161 (Tb-161) + + Pointers : 1918189 -1000000 + Primary type : Decay + Nuclide ZAI : 651610 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 160.92745 + Atomic weight ratio (AWR) : 159.54500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.95E+05 seconds (6.89 days) + Specific ingestion toxicity : 7.20E-10 Sv/Bq + Specific inhalation toxicity : 1.30E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.93100E-01 MeV frac = 1.00000E+00 Product nuclide = 66161.82c : beta- + + Nuclide 1334 / 1657 : 651620 -- terbium 162 (Tb-162) + + Pointers : 1920660 -1000000 + Primary type : Decay + Nuclide ZAI : 651620 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 161.92906 + Atomic weight ratio (AWR) : 160.53800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.56E+02 seconds (7.6 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.51000E+00 MeV frac = 1.00000E+00 Product nuclide = 66162.82c : beta- + + Nuclide 1335 / 1657 : 651630 -- terbium 163 (Tb-163) + + Pointers : 1923131 -1000000 + Primary type : Decay + Nuclide ZAI : 651630 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 162.93066 + Atomic weight ratio (AWR) : 161.53100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.17E+03 seconds (19.5 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.78500E+00 MeV frac = 1.00000E+00 Product nuclide = 66163.82c : beta- + + Nuclide 1336 / 1657 : 651640 -- terbium 164 (Tb-164) + + Pointers : 1927842 -1000000 + Primary type : Decay + Nuclide ZAI : 651640 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 163.93327 + Atomic weight ratio (AWR) : 162.52500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.80E+02 seconds (3 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.89330E+00 MeV frac = 1.00000E+00 Product nuclide = 66164.82c : beta- + + Nuclide 1337 / 1657 : 651650 -- terbium 165 (Tb-165) + + Pointers : 1928026 -1000000 + Primary type : Decay + Nuclide ZAI : 651650 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 164.93488 + Atomic weight ratio (AWR) : 163.51800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.27E+02 seconds (2.11 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.96000E+00 MeV frac = 1.00000E+00 Product nuclide = 661650 : beta- + + Nuclide 1338 / 1657 : 651660 -- terbium 166 (Tb-166) + + Pointers : 1928565 -1000000 + Primary type : Decay + Nuclide ZAI : 651660 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 165.93850 + Atomic weight ratio (AWR) : 164.51300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 25.6 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.83010E+00 MeV frac = 1.00000E+00 Product nuclide = 661660 : beta- + + Nuclide 1339 / 1657 : 651670 -- terbium 167 (Tb-167) + + Pointers : 1928749 -1000000 + Primary type : Decay + Nuclide ZAI : 651670 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 166.94010 + Atomic weight ratio (AWR) : 165.50600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 19 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.10000E+00 MeV frac = 1.00000E+00 Product nuclide = 661670 : beta- + + Nuclide 1340 / 1657 : 651680 -- terbium 168 (Tb-168) + + Pointers : 1928933 -1000000 + Primary type : Decay + Nuclide ZAI : 651680 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 167.94373 + Atomic weight ratio (AWR) : 166.50100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.06000E+00 MeV frac = 1.00000E+00 Product nuclide = 661680 : beta- + + Nuclide 1341 / 1657 : 651690 -- terbium 169 (Tb-169) + + Pointers : 1929117 -1000000 + Primary type : Decay + Nuclide ZAI : 651690 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 168.94634 + Atomic weight ratio (AWR) : 167.49500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 661690 : beta- + + Nuclide 1342 / 1657 : 651700 -- terbium 170 (Tb-170) + + Pointers : 1929301 -1000000 + Primary type : Decay + Nuclide ZAI : 651700 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 169.94996 + Atomic weight ratio (AWR) : 168.49000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.32000E+00 MeV frac = 1.00000E+00 Product nuclide = 661700 : beta- + + Nuclide 1343 / 1657 : 651710 -- terbium 171 (Tb-171) + + Pointers : 1929485 -1000000 + Primary type : Decay + Nuclide ZAI : 651710 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 170.95358 + Atomic weight ratio (AWR) : 169.48500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.61000E+00 MeV frac = 1.00000E+00 Product nuclide = 661710 : beta- + + Nuclide 1344 / 1657 : 661580 -- dysprosium 158 (Dy-158) + + Pointers : 1929669 -1000000 + Primary type : Decay + Nuclide ZAI : 661580 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 157.92466 + Atomic weight ratio (AWR) : 156.56800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1345 / 1657 : 661590 -- dysprosium 159 (Dy-159) + + Pointers : 1929775 -1000000 + Primary type : Decay + Nuclide ZAI : 661590 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 158.92626 + Atomic weight ratio (AWR) : 157.56100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.25E+07 seconds (144 days) + Specific ingestion toxicity : 1.00E-10 Sv/Bq + Specific inhalation toxicity : 3.70E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 3.65600E-01 MeV frac = 1.00000E+00 Product nuclide = 65159.82c : EC/beta+ + + Nuclide 1346 / 1657 : 661650 -- dysprosium 165 (Dy-165) + + Pointers : 1950468 -1000000 + Primary type : Decay + Nuclide ZAI : 661650 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 164.93185 + Atomic weight ratio (AWR) : 163.51500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.40E+03 seconds (2.33 hours) + Specific ingestion toxicity : 1.10E-10 Sv/Bq + Specific inhalation toxicity : 6.00E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.28660E+00 MeV frac = 1.00000E+00 Product nuclide = 67165.82c : beta- + + Nuclide 1347 / 1657 : 661651 -- dysprosium 165m (Dy-165m) + + Pointers : 1952715 -1000000 + Primary type : Decay + Nuclide ZAI : 661651 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 164.93185 + Atomic weight ratio (AWR) : 163.51500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.54E+01 seconds (1.26 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 1.08160E-01 MeV frac = 9.77600E-01 Product nuclide = 661650 : IT + 2 RTYP = 1 Q = 1.39486E+00 MeV frac = 2.24000E-02 Product nuclide = 67165.82c : beta- + + Nuclide 1348 / 1657 : 661660 -- dysprosium 166 (Dy-166) + + Pointers : 1952972 -1000000 + Primary type : Decay + Nuclide ZAI : 661660 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 165.93245 + Atomic weight ratio (AWR) : 164.50700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.94E+05 seconds (3.4 days) + Specific ingestion toxicity : 1.60E-09 Sv/Bq + Specific inhalation toxicity : 1.90E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.86800E-01 MeV frac = 1.00000E+00 Product nuclide = 671660 : beta- + + Nuclide 1349 / 1657 : 661670 -- dysprosium 167 (Dy-167) + + Pointers : 1953735 -1000000 + Primary type : Decay + Nuclide ZAI : 661670 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 166.93607 + Atomic weight ratio (AWR) : 165.50200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.72E+02 seconds (6.2 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.35000E+00 MeV frac = 1.00000E+00 Product nuclide = 671670 : beta- + + Nuclide 1350 / 1657 : 661680 -- dysprosium 168 (Dy-168) + + Pointers : 1955086 -1000000 + Primary type : Decay + Nuclide ZAI : 661680 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 167.93667 + Atomic weight ratio (AWR) : 166.49400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.22E+02 seconds (8.7 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.51000E+00 MeV frac = 1.00000E+00 Product nuclide = 671680 : beta- + + Nuclide 1351 / 1657 : 661690 -- dysprosium 169 (Dy-169) + + Pointers : 1955270 -1000000 + Primary type : Decay + Nuclide ZAI : 661690 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 168.94029 + Atomic weight ratio (AWR) : 167.48900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 39 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.20300E+00 MeV frac = 1.00000E+00 Product nuclide = 671690 : beta- + + Nuclide 1352 / 1657 : 661700 -- dysprosium 170 (Dy-170) + + Pointers : 1955454 -1000000 + Primary type : Decay + Nuclide ZAI : 661700 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 169.94290 + Atomic weight ratio (AWR) : 168.48300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 30 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.48000E+00 MeV frac = 1.00000E+00 Product nuclide = 671701 : beta- + + Nuclide 1353 / 1657 : 661710 -- dysprosium 171 (Dy-171) + + Pointers : 1955638 -1000000 + Primary type : Decay + Nuclide ZAI : 661710 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 170.94652 + Atomic weight ratio (AWR) : 169.47800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.41000E+00 MeV frac = 1.00000E+00 Product nuclide = 671710 : beta- + + Nuclide 1354 / 1657 : 661720 -- dysprosium 172 (Dy-172) + + Pointers : 1955822 -1000000 + Primary type : Decay + Nuclide ZAI : 661720 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 171.94913 + Atomic weight ratio (AWR) : 170.47200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.67000E+00 MeV frac = 1.00000E+00 Product nuclide = 671720 : beta- + + Nuclide 1355 / 1657 : 661730 -- dysprosium 173 (Dy-173) + + Pointers : 1956006 -1000000 + Primary type : Decay + Nuclide ZAI : 661730 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 172.95276 + Atomic weight ratio (AWR) : 171.46700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.32000E+00 MeV frac = 1.00000E+00 Product nuclide = 671730 : beta- + + Nuclide 1356 / 1657 : 671610 -- holmium 161 (Ho-161) + + Pointers : 1956190 -1000000 + Primary type : Decay + Nuclide ZAI : 671610 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 160.92745 + Atomic weight ratio (AWR) : 159.54500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.93E+03 seconds (2.48 hours) + Specific ingestion toxicity : 1.30E-11 Sv/Bq + Specific inhalation toxicity : 6.00E-12 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 8.56500E-01 MeV frac = 1.00000E+00 Product nuclide = 66161.82c : EC/beta+ + + Nuclide 1357 / 1657 : 671611 -- holmium 161m (Ho-161m) + + Pointers : 1959319 -1000000 + Primary type : Decay + Nuclide ZAI : 671611 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 160.92745 + Atomic weight ratio (AWR) : 159.54500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.77 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 2.11140E-01 MeV frac = 1.00000E+00 Product nuclide = 671610 : IT + + Nuclide 1358 / 1657 : 671620 -- holmium 162 (Ho-162) + + Pointers : 1959718 -1000000 + Primary type : Decay + Nuclide ZAI : 671620 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 161.92906 + Atomic weight ratio (AWR) : 160.53800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.00E+02 seconds (15 minutes) + Specific ingestion toxicity : 3.30E-12 Sv/Bq + Specific inhalation toxicity : 2.80E-12 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 2.14000E+00 MeV frac = 1.00000E+00 Product nuclide = 66162.82c : EC/beta+ + + Nuclide 1359 / 1657 : 671621 -- holmium 162m (Ho-162m) + + Pointers : 1960845 -1000000 + Primary type : Decay + Nuclide ZAI : 671621 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 161.92906 + Atomic weight ratio (AWR) : 160.53800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.02E+03 seconds (1.12 hours) + Specific ingestion toxicity : 2.60E-11 Sv/Bq + Specific inhalation toxicity : 2.10E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 2.24600E+00 MeV frac = 4.50000E-01 Product nuclide = 66162.82c : EC/beta+ + 2 RTYP = 3 Q = 1.05870E-01 MeV frac = 5.50000E-01 Product nuclide = 671620 : IT + + Nuclide 1360 / 1657 : 671630 -- holmium 163 (Ho-163) + + Pointers : 1964061 -1000000 + Primary type : Decay + Nuclide ZAI : 671630 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 162.92864 + Atomic weight ratio (AWR) : 161.52900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.44E+11 seconds (4,573 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 2.65000E-03 MeV frac = 1.00000E+00 Product nuclide = 66163.82c : EC/beta+ + + Nuclide 1361 / 1657 : 671631 -- holmium 163m (Ho-163m) + + Pointers : 1964245 -1000000 + Primary type : Decay + Nuclide ZAI : 671631 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 162.92864 + Atomic weight ratio (AWR) : 161.52900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.1 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 2.97880E-01 MeV frac = 1.00000E+00 Product nuclide = 671630 : IT + + Nuclide 1362 / 1657 : 671640 -- holmium 164 (Ho-164) + + Pointers : 1964644 -1000000 + Primary type : Decay + Nuclide ZAI : 671640 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 163.93025 + Atomic weight ratio (AWR) : 162.52200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.72E+03 seconds (28.6 minutes) + Specific ingestion toxicity : 9.50E-12 Sv/Bq + Specific inhalation toxicity : 8.40E-12 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 9.63000E-01 MeV frac = 5.17000E-01 Product nuclide = 68164.82c : beta- + 2 RTYP = 2 Q = 9.87000E-01 MeV frac = 4.83000E-01 Product nuclide = 66164.82c : EC/beta+ + + Nuclide 1363 / 1657 : 671641 -- holmium 164m (Ho-164m) + + Pointers : 1965438 -1000000 + Primary type : Decay + Nuclide ZAI : 671641 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 163.93025 + Atomic weight ratio (AWR) : 162.52200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.26E+03 seconds (37.6 minutes) + Specific ingestion toxicity : 1.60E-11 Sv/Bq + Specific inhalation toxicity : 1.20E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.40000E-01 MeV frac = 1.00000E+00 Product nuclide = 671640 : IT + + Nuclide 1364 / 1657 : 671660 -- holmium 166 (Ho-166) + + Pointers : 1967713 -1000000 + Primary type : Decay + Nuclide ZAI : 671660 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 165.93245 + Atomic weight ratio (AWR) : 164.50700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.65E+04 seconds (1.12 days) + Specific ingestion toxicity : 1.40E-09 Sv/Bq + Specific inhalation toxicity : 6.50E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.85450E+00 MeV frac = 1.00000E+00 Product nuclide = 68166.82c : beta- + + Nuclide 1365 / 1657 : 671661 -- holmium 166m (Ho-166m) + + Pointers : 1968882 -1000000 + Primary type : Decay + Nuclide ZAI : 671661 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 165.93245 + Atomic weight ratio (AWR) : 164.50700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.58E+10 seconds (1,134 years) + Specific ingestion toxicity : 2.00E-09 Sv/Bq + Specific inhalation toxicity : 1.20E-07 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.86048E+00 MeV frac = 1.00000E+00 Product nuclide = 68166.82c : beta- + + Nuclide 1366 / 1657 : 671670 -- holmium 167 (Ho-167) + + Pointers : 1973089 -1000000 + Primary type : Decay + Nuclide ZAI : 671670 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 166.93304 + Atomic weight ratio (AWR) : 165.49900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.12E+04 seconds (3.1 hours) + Specific ingestion toxicity : 8.30E-11 Sv/Bq + Specific inhalation toxicity : 7.10E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.00700E+00 MeV frac = 8.80508E-01 Product nuclide = 68167.82c : beta- + 2 RTYP = 1 Q = 7.99180E-01 MeV frac = 1.19492E-01 Product nuclide = 681671 : beta- + + Nuclide 1367 / 1657 : 671680 -- holmium 168 (Ho-168) + + Pointers : 1975017 -1000000 + Primary type : Decay + Nuclide ZAI : 671680 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 167.93566 + Atomic weight ratio (AWR) : 166.49300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.79E+02 seconds (2.99 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.91000E+00 MeV frac = 1.00000E+00 Product nuclide = 68168.82c : beta- + + Nuclide 1368 / 1657 : 671681 -- holmium 168m (Ho-168m) + + Pointers : 1977572 -1000000 + Primary type : Decay + Nuclide ZAI : 671681 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 167.93566 + Atomic weight ratio (AWR) : 166.49300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.32E+02 seconds (2.2 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 5.90000E-02 MeV frac = 9.95000E-01 Product nuclide = 671680 : IT + 2 RTYP = 1 Q = 2.98570E+00 MeV frac = 5.00000E-03 Product nuclide = 68168.82c : beta- + + Nuclide 1369 / 1657 : 671690 -- holmium 169 (Ho-169) + + Pointers : 1977829 -1000000 + Primary type : Decay + Nuclide ZAI : 671690 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 168.93726 + Atomic weight ratio (AWR) : 167.48600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.82E+02 seconds (4.7 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.12570E+00 MeV frac = 1.00000E+00 Product nuclide = 681690 : beta- + + Nuclide 1370 / 1657 : 671700 -- holmium 170 (Ho-170) + + Pointers : 1978013 -1000000 + Primary type : Decay + Nuclide ZAI : 671700 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 169.93987 + Atomic weight ratio (AWR) : 168.48000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.67E+02 seconds (2.78 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.87000E+00 MeV frac = 1.00000E+00 Product nuclide = 68170.82c : beta- + + Nuclide 1371 / 1657 : 671701 -- holmium 170m (Ho-170m) + + Pointers : 1980316 -1000000 + Primary type : Decay + Nuclide ZAI : 671701 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 169.93987 + Atomic weight ratio (AWR) : 168.48000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 43 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.99000E+00 MeV frac = 1.00000E+00 Product nuclide = 68170.82c : beta- + + Nuclide 1372 / 1657 : 671710 -- holmium 171 (Ho-171) + + Pointers : 1981695 -1000000 + Primary type : Decay + Nuclide ZAI : 671710 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 170.94148 + Atomic weight ratio (AWR) : 169.47300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 53 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.20490E+00 MeV frac = 1.00000E+00 Product nuclide = 681710 : beta- + + Nuclide 1373 / 1657 : 671720 -- holmium 172 (Ho-172) + + Pointers : 1981879 -1000000 + Primary type : Decay + Nuclide ZAI : 671720 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 171.94510 + Atomic weight ratio (AWR) : 170.46800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 25 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.08900E+00 MeV frac = 1.00000E+00 Product nuclide = 681720 : beta- + + Nuclide 1374 / 1657 : 671730 -- holmium 173 (Ho-173) + + Pointers : 1982063 -1000000 + Primary type : Decay + Nuclide ZAI : 671730 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 172.94771 + Atomic weight ratio (AWR) : 171.46200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 10 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.55000E+00 MeV frac = 1.00000E+00 Product nuclide = 681730 : beta- + + Nuclide 1375 / 1657 : 671740 -- holmium 174 (Ho-174) + + Pointers : 1982247 -1000000 + Primary type : Decay + Nuclide ZAI : 671740 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 173.95133 + Atomic weight ratio (AWR) : 172.45700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.45000E+00 MeV frac = 1.00000E+00 Product nuclide = 681740 : beta- + + Nuclide 1376 / 1657 : 671750 -- holmium 175 (Ho-175) + + Pointers : 1982431 -1000000 + Primary type : Decay + Nuclide ZAI : 671750 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 174.95395 + Atomic weight ratio (AWR) : 173.45100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.85000E+00 MeV frac = 1.00000E+00 Product nuclide = 681750 : beta- + + Nuclide 1377 / 1657 : 681620 -- erbium 162 (Er-162) + + Pointers : 1982615 -1000000 + Primary type : Decay + Nuclide ZAI : 681620 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 161.92906 + Atomic weight ratio (AWR) : 160.53800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.42E+21 seconds (1.4E+14 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 4 Q = 1.64410E+00 MeV frac = 5.00000E-01 Product nuclide = 661580 : alpha + 2 RTYP = 22 Q = 1.84380E+00 MeV frac = 5.00000E-01 Product nuclide = 66162.82c : EC/beta+ + EC/beta+ + + 1 additional decay branch: + + 1 RTYP = 4 Q = 1.64410E+00 MeV frac = 5.00000E-01 Product nuclide = 2004.82c : alpha + + Nuclide 1378 / 1657 : 681630 -- erbium 163 (Er-163) + + Pointers : 1982945 -1000000 + Primary type : Decay + Nuclide ZAI : 681630 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 162.92965 + Atomic weight ratio (AWR) : 161.53000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.50E+03 seconds (1.25 hours) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 1.21000E+00 MeV frac = 9.99847E-01 Product nuclide = 671630 : EC/beta+ + 2 RTYP = 2 Q = 9.12190E-01 MeV frac = 1.52868E-04 Product nuclide = 671631 : EC/beta+ + + Nuclide 1379 / 1657 : 681650 -- erbium 165 (Er-165) + + Pointers : 1987299 -1000000 + Primary type : Decay + Nuclide ZAI : 681650 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 164.93084 + Atomic weight ratio (AWR) : 163.51400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.73E+04 seconds (10.4 hours) + Specific ingestion toxicity : 1.90E-11 Sv/Bq + Specific inhalation toxicity : 7.90E-12 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 3.76300E-01 MeV frac = 1.00000E+00 Product nuclide = 67165.82c : EC/beta+ + + Nuclide 1380 / 1657 : 681671 -- erbium 167m (Er-167m) + + Pointers : 1994995 -1000000 + Primary type : Decay + Nuclide ZAI : 681671 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 166.93203 + Atomic weight ratio (AWR) : 165.49800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.27 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 2.07801E-01 MeV frac = 1.00000E+00 Product nuclide = 68167.82c : IT + + Nuclide 1381 / 1657 : 681690 -- erbium 169 (Er-169) + + Pointers : 1999447 -1000000 + Primary type : Decay + Nuclide ZAI : 681690 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 168.93423 + Atomic weight ratio (AWR) : 167.48300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.10E+05 seconds (9.38 days) + Specific ingestion toxicity : 3.70E-10 Sv/Bq + Specific inhalation toxicity : 1.00E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.53000E-01 MeV frac = 1.00000E+00 Product nuclide = 691690 : beta- + + Nuclide 1382 / 1657 : 681710 -- erbium 171 (Er-171) + + Pointers : 2002930 -1000000 + Primary type : Decay + Nuclide ZAI : 681710 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 170.93845 + Atomic weight ratio (AWR) : 169.47000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.71E+04 seconds (7.52 hours) + Specific ingestion toxicity : 3.60E-10 Sv/Bq + Specific inhalation toxicity : 2.20E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.49070E+00 MeV frac = 1.00000E+00 Product nuclide = 691710 : beta- + + Nuclide 1383 / 1657 : 681720 -- erbium 172 (Er-172) + + Pointers : 2005667 -1000000 + Primary type : Decay + Nuclide ZAI : 681720 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 171.93905 + Atomic weight ratio (AWR) : 170.46200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.77E+05 seconds (2.05 days) + Specific ingestion toxicity : 1.00E-09 Sv/Bq + Specific inhalation toxicity : 1.10E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.91000E-01 MeV frac = 1.00000E+00 Product nuclide = 691720 : beta- + + Nuclide 1384 / 1657 : 681730 -- erbium 173 (Er-173) + + Pointers : 2008530 -1000000 + Primary type : Decay + Nuclide ZAI : 681730 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 172.94267 + Atomic weight ratio (AWR) : 171.45700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.40E+01 seconds (1.4 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 691730 : beta- + + Nuclide 1385 / 1657 : 681740 -- erbium 174 (Er-174) + + Pointers : 2009349 -1000000 + Primary type : Decay + Nuclide ZAI : 681740 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 173.94427 + Atomic weight ratio (AWR) : 172.45000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.92E+02 seconds (3.2 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.92000E+00 MeV frac = 1.00000E+00 Product nuclide = 691740 : beta- + + Nuclide 1386 / 1657 : 681750 -- erbium 175 (Er-175) + + Pointers : 2009533 -1000000 + Primary type : Decay + Nuclide ZAI : 681750 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 174.94790 + Atomic weight ratio (AWR) : 173.44500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.20E+01 seconds (1.2 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.67000E+00 MeV frac = 1.00000E+00 Product nuclide = 691750 : beta- + + Nuclide 1387 / 1657 : 681760 -- erbium 176 (Er-176) + + Pointers : 2009717 -1000000 + Primary type : Decay + Nuclide ZAI : 681760 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 175.95051 + Atomic weight ratio (AWR) : 174.43900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 20 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.87000E+00 MeV frac = 1.00000E+00 Product nuclide = 691760 : beta- + + Nuclide 1388 / 1657 : 681770 -- erbium 177 (Er-177) + + Pointers : 2009901 -1000000 + Primary type : Decay + Nuclide ZAI : 681770 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 176.95413 + Atomic weight ratio (AWR) : 175.43400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.67000E+00 MeV frac = 1.00000E+00 Product nuclide = 691770 : beta- + + Nuclide 1389 / 1657 : 691660 -- thulium 166 (Tm-166) + + Pointers : 2010085 -1000000 + Primary type : Decay + Nuclide ZAI : 691660 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 165.93346 + Atomic weight ratio (AWR) : 164.50800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.77E+04 seconds (7.7 hours) + Specific ingestion toxicity : 2.80E-10 Sv/Bq + Specific inhalation toxicity : 1.70E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 3.03800E+00 MeV frac = 1.00000E+00 Product nuclide = 68166.82c : EC/beta+ + + Nuclide 1390 / 1657 : 691670 -- thulium 167 (Tm-167) + + Pointers : 2020774 -1000000 + Primary type : Decay + Nuclide ZAI : 691670 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 166.93304 + Atomic weight ratio (AWR) : 165.49900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.99E+05 seconds (9.25 days) + Specific ingestion toxicity : 5.60E-10 Sv/Bq + Specific inhalation toxicity : 1.10E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 5.40600E-01 MeV frac = 9.82500E-01 Product nuclide = 681671 : EC/beta+ + 2 RTYP = 2 Q = 7.48400E-01 MeV frac = 1.75000E-02 Product nuclide = 68167.82c : EC/beta+ + + Nuclide 1391 / 1657 : 691680 -- thulium 168 (Tm-168) + + Pointers : 2021666 -1000000 + Primary type : Decay + Nuclide ZAI : 691680 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 167.93465 + Atomic weight ratio (AWR) : 166.49200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.78E+06 seconds (90 days) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 2.57000E-01 MeV frac = 1.00000E-04 Product nuclide = 701680 : beta- + 2 RTYP = 2 Q = 1.67900E+00 MeV frac = 9.99900E-01 Product nuclide = 68168.82c : EC/beta+ + + Nuclide 1392 / 1657 : 691690 -- thulium 169 (Tm-169) + + Pointers : 2025596 -1000000 + Primary type : Decay + Nuclide ZAI : 691690 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 168.93423 + Atomic weight ratio (AWR) : 167.48300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1393 / 1657 : 691700 -- thulium 170 (Tm-170) + + Pointers : 2025702 -1000000 + Primary type : Decay + Nuclide ZAI : 691700 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 169.93584 + Atomic weight ratio (AWR) : 168.47600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.11E+07 seconds (129 days) + Specific ingestion toxicity : 1.30E-09 Sv/Bq + Specific inhalation toxicity : 7.00E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 3.14400E-01 MeV frac = 1.31000E-03 Product nuclide = 68170.82c : EC/beta+ + 2 RTYP = 1 Q = 9.68000E-01 MeV frac = 9.98690E-01 Product nuclide = 701700 : beta- + + Nuclide 1394 / 1657 : 691710 -- thulium 171 (Tm-171) + + Pointers : 2026328 -1000000 + Primary type : Decay + Nuclide ZAI : 691710 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 170.93643 + Atomic weight ratio (AWR) : 169.46800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.05E+07 seconds (1.92 years) + Specific ingestion toxicity : 1.10E-10 Sv/Bq + Specific inhalation toxicity : 1.40E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.65000E-02 MeV frac = 1.00000E+00 Product nuclide = 701710 : beta- + + Nuclide 1395 / 1657 : 691720 -- thulium 172 (Tm-172) + + Pointers : 2026755 -1000000 + Primary type : Decay + Nuclide ZAI : 691720 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 171.93804 + Atomic weight ratio (AWR) : 170.46100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.29E+05 seconds (2.65 days) + Specific ingestion toxicity : 1.70E-09 Sv/Bq + Specific inhalation toxicity : 1.10E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.88000E+00 MeV frac = 1.00000E+00 Product nuclide = 701720 : beta- + + Nuclide 1396 / 1657 : 691730 -- thulium 173 (Tm-173) + + Pointers : 2028946 -1000000 + Primary type : Decay + Nuclide ZAI : 691730 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 172.93964 + Atomic weight ratio (AWR) : 171.45400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.97E+04 seconds (8.24 hours) + Specific ingestion toxicity : 3.10E-10 Sv/Bq + Specific inhalation toxicity : 1.80E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.29800E+00 MeV frac = 1.00000E+00 Product nuclide = 701730 : beta- + + Nuclide 1397 / 1657 : 691740 -- thulium 174 (Tm-174) + + Pointers : 2029499 -1000000 + Primary type : Decay + Nuclide ZAI : 691740 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 173.94226 + Atomic weight ratio (AWR) : 172.44800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.24E+02 seconds (5.4 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.08000E+00 MeV frac = 1.00000E+00 Product nuclide = 701740 : beta- + + Nuclide 1398 / 1657 : 691750 -- thulium 175 (Tm-175) + + Pointers : 2032264 -1000000 + Primary type : Decay + Nuclide ZAI : 691750 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 174.94386 + Atomic weight ratio (AWR) : 173.44100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.12E+02 seconds (15.2 minutes) + Specific ingestion toxicity : 2.70E-11 Sv/Bq + Specific inhalation toxicity : 1.80E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 2.38060E+00 MeV frac = 2.30000E-01 Product nuclide = 701750 : beta- + 2 RTYP = 1 Q = 1.86574E+00 MeV frac = 7.70000E-01 Product nuclide = 701751 : beta- + + Nuclide 1399 / 1657 : 691760 -- thulium 176 (Tm-176) + + Pointers : 2032521 -1000000 + Primary type : Decay + Nuclide ZAI : 691760 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 175.94748 + Atomic weight ratio (AWR) : 174.43600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.11E+02 seconds (1.85 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 4.12410E+00 MeV frac = 5.00000E-01 Product nuclide = 701760 : beta- + 2 RTYP = 1 Q = 3.07410E+00 MeV frac = 5.00000E-01 Product nuclide = 701761 : beta- + + Nuclide 1400 / 1657 : 691770 -- thulium 177 (Tm-177) + + Pointers : 2032778 -1000000 + Primary type : Decay + Nuclide ZAI : 691770 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 176.94909 + Atomic weight ratio (AWR) : 175.42900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.00E+01 seconds (1.5 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.18770E+00 MeV frac = 1.00000E+00 Product nuclide = 701771 : beta- + + Nuclide 1401 / 1657 : 691780 -- thulium 178 (Tm-178) + + Pointers : 2032962 -1000000 + Primary type : Decay + Nuclide ZAI : 691780 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 177.95271 + Atomic weight ratio (AWR) : 176.42400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 30 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.57800E+00 MeV frac = 1.00000E+00 Product nuclide = 701780 : beta- + + Nuclide 1402 / 1657 : 691790 -- thulium 179 (Tm-179) + + Pointers : 2033146 -1000000 + Primary type : Decay + Nuclide ZAI : 691790 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 178.95532 + Atomic weight ratio (AWR) : 177.41800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 20 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.82000E+00 MeV frac = 1.00000E+00 Product nuclide = 701790 : beta- + + Nuclide 1403 / 1657 : 701680 -- ytterbium 168 (Yb-168) + + Pointers : 2033330 -1000000 + Primary type : Decay + Nuclide ZAI : 701680 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 167.93364 + Atomic weight ratio (AWR) : 166.49100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.10E+21 seconds (1.3E+14 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 4 Q = 1.95010E+00 MeV frac = 5.00000E-01 Product nuclide = 68164.82c : alpha + 2 RTYP = 22 Q = 1.42170E+00 MeV frac = 5.00000E-01 Product nuclide = 68168.82c : EC/beta+ + EC/beta+ + + 1 additional decay branch: + + 1 RTYP = 4 Q = 1.95010E+00 MeV frac = 5.00000E-01 Product nuclide = 2004.82c : alpha + + Nuclide 1404 / 1657 : 701690 -- ytterbium 169 (Yb-169) + + Pointers : 2033660 -1000000 + Primary type : Decay + Nuclide ZAI : 701690 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 168.93524 + Atomic weight ratio (AWR) : 167.48400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.77E+06 seconds (32 days) + Specific ingestion toxicity : 7.10E-10 Sv/Bq + Specific inhalation toxicity : 3.00E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 9.09000E-01 MeV frac = 1.00000E+00 Product nuclide = 691690 : EC/beta+ + + Nuclide 1405 / 1657 : 701700 -- ytterbium 170 (Yb-170) + + Pointers : 2035697 -1000000 + Primary type : Decay + Nuclide ZAI : 701700 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 169.93483 + Atomic weight ratio (AWR) : 168.47500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1406 / 1657 : 701710 -- ytterbium 171 (Yb-171) + + Pointers : 2035803 -1000000 + Primary type : Decay + Nuclide ZAI : 701710 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 170.93643 + Atomic weight ratio (AWR) : 169.46800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1407 / 1657 : 701711 -- ytterbium 171m (Yb-171m) + + Pointers : 2035909 -1000000 + Primary type : Decay + Nuclide ZAI : 701711 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 170.93643 + Atomic weight ratio (AWR) : 169.46800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.25 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 9.52820E-02 MeV frac = 1.00000E+00 Product nuclide = 701710 : IT + + Nuclide 1408 / 1657 : 701720 -- ytterbium 172 (Yb-172) + + Pointers : 2036093 -1000000 + Primary type : Decay + Nuclide ZAI : 701720 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 171.93602 + Atomic weight ratio (AWR) : 170.45900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1409 / 1657 : 701730 -- ytterbium 173 (Yb-173) + + Pointers : 2036199 -1000000 + Primary type : Decay + Nuclide ZAI : 701730 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 172.93863 + Atomic weight ratio (AWR) : 171.45300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1410 / 1657 : 701740 -- ytterbium 174 (Yb-174) + + Pointers : 2036305 -1000000 + Primary type : Decay + Nuclide ZAI : 701740 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 173.93923 + Atomic weight ratio (AWR) : 172.44500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1411 / 1657 : 701750 -- ytterbium 175 (Yb-175) + + Pointers : 2036411 -1000000 + Primary type : Decay + Nuclide ZAI : 701750 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 174.94083 + Atomic weight ratio (AWR) : 173.43800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.62E+05 seconds (4.18 days) + Specific ingestion toxicity : 4.40E-10 Sv/Bq + Specific inhalation toxicity : 7.30E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.68800E-01 MeV frac = 1.00000E+00 Product nuclide = 71175.82c : beta- + + Nuclide 1412 / 1657 : 701751 -- ytterbium 175m (Yb-175m) + + Pointers : 2037132 -1000000 + Primary type : Decay + Nuclide ZAI : 701751 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 174.94083 + Atomic weight ratio (AWR) : 173.43800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 68.2 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 5.14865E-01 MeV frac = 1.00000E+00 Product nuclide = 701750 : IT + + Nuclide 1413 / 1657 : 701760 -- ytterbium 176 (Yb-176) + + Pointers : 2037316 -1000000 + Primary type : Decay + Nuclide ZAI : 701760 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 175.94244 + Atomic weight ratio (AWR) : 174.43100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1414 / 1657 : 701761 -- ytterbium 176m (Yb-176m) + + Pointers : 2037422 -1000000 + Primary type : Decay + Nuclide ZAI : 701761 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 175.94244 + Atomic weight ratio (AWR) : 174.43100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 11.4 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.04980E+00 MeV frac = 1.00000E+00 Product nuclide = 701760 : IT + + Nuclide 1415 / 1657 : 701770 -- ytterbium 177 (Yb-177) + + Pointers : 2038045 -1000000 + Primary type : Decay + Nuclide ZAI : 701770 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 176.94505 + Atomic weight ratio (AWR) : 175.42500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.88E+03 seconds (1.91 hours) + Specific ingestion toxicity : 8.80E-11 Sv/Bq + Specific inhalation toxicity : 6.90E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.39920E+00 MeV frac = 1.00000E+00 Product nuclide = 711770 : beta- + + Nuclide 1416 / 1657 : 701771 -- ytterbium 177m (Yb-177m) + + Pointers : 2040544 -1000000 + Primary type : Decay + Nuclide ZAI : 701771 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 176.94505 + Atomic weight ratio (AWR) : 175.42500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.41 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 3.31500E-01 MeV frac = 1.00000E+00 Product nuclide = 701770 : IT + + Nuclide 1417 / 1657 : 701780 -- ytterbium 178 (Yb-178) + + Pointers : 2040985 -1000000 + Primary type : Decay + Nuclide ZAI : 701780 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 177.94666 + Atomic weight ratio (AWR) : 176.41800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.44E+03 seconds (1.23 hours) + Specific ingestion toxicity : 1.20E-10 Sv/Bq + Specific inhalation toxicity : 7.50E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.45001E-01 MeV frac = 1.00000E+00 Product nuclide = 711780 : beta- + + Nuclide 1418 / 1657 : 701790 -- ytterbium 179 (Yb-179) + + Pointers : 2041169 -1000000 + Primary type : Decay + Nuclide ZAI : 701790 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 178.95028 + Atomic weight ratio (AWR) : 177.41300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.80E+02 seconds (8 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.05160E+00 MeV frac = 1.00000E+00 Product nuclide = 711791 : beta- + + Nuclide 1419 / 1657 : 701800 -- ytterbium 180 (Yb-180) + + Pointers : 2041353 -1000000 + Primary type : Decay + Nuclide ZAI : 701800 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 179.95188 + Atomic weight ratio (AWR) : 178.40600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.44E+02 seconds (2.4 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.27610E+00 MeV frac = 1.00000E+00 Product nuclide = 711801 : beta- + + Nuclide 1420 / 1657 : 701810 -- ytterbium 181 (Yb-181) + + Pointers : 2041537 -1000000 + Primary type : Decay + Nuclide ZAI : 701810 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 180.95651 + Atomic weight ratio (AWR) : 179.40200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 60 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.89000E+00 MeV frac = 1.00000E+00 Product nuclide = 711810 : beta- + + Nuclide 1421 / 1657 : 711720 -- lutetium 172 (Lu-172) + + Pointers : 2041721 -1000000 + Primary type : Decay + Nuclide ZAI : 711720 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 171.93905 + Atomic weight ratio (AWR) : 170.46200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.79E+05 seconds (6.7 days) + Specific ingestion toxicity : 1.30E-09 Sv/Bq + Specific inhalation toxicity : 1.60E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 2.52090E+00 MeV frac = 1.00000E+00 Product nuclide = 701720 : EC/beta+ + + Nuclide 1422 / 1657 : 711730 -- lutetium 173 (Lu-173) + + Pointers : 2052270 -1000000 + Primary type : Decay + Nuclide ZAI : 711730 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 172.93863 + Atomic weight ratio (AWR) : 171.45300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.22E+07 seconds (1.34 years) + Specific ingestion toxicity : 2.60E-10 Sv/Bq + Specific inhalation toxicity : 2.40E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 6.72300E-01 MeV frac = 1.00000E+00 Product nuclide = 701730 : EC/beta+ + + Nuclide 1423 / 1657 : 711740 -- lutetium 174 (Lu-174) + + Pointers : 2053663 -1000000 + Primary type : Decay + Nuclide ZAI : 711740 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 173.94024 + Atomic weight ratio (AWR) : 172.44600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.12E+08 seconds (3.56 years) + Specific ingestion toxicity : 2.70E-10 Sv/Bq + Specific inhalation toxicity : 4.20E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 1.37600E+00 MeV frac = 1.00000E+00 Product nuclide = 701740 : EC/beta+ + + Nuclide 1424 / 1657 : 711741 -- lutetium 174m (Lu-174m) + + Pointers : 2054300 -1000000 + Primary type : Decay + Nuclide ZAI : 711741 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 173.94024 + Atomic weight ratio (AWR) : 172.44600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.23E+07 seconds (142 days) + Specific ingestion toxicity : 5.30E-10 Sv/Bq + Specific inhalation toxicity : 4.20E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 1.54700E+00 MeV frac = 5.80000E-03 Product nuclide = 701740 : EC/beta+ + 2 RTYP = 3 Q = 1.70830E-01 MeV frac = 9.94200E-01 Product nuclide = 711740 : IT + + Nuclide 1425 / 1657 : 711761 -- lutetium 176m (Lu-176m) + + Pointers : 2059456 -1000000 + Primary type : Decay + Nuclide ZAI : 711761 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 175.94244 + Atomic weight ratio (AWR) : 174.43100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.31E+04 seconds (3.63 hours) + Specific ingestion toxicity : 1.70E-10 Sv/Bq + Specific inhalation toxicity : 1.20E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 2.33200E-01 MeV frac = 9.50000E-04 Product nuclide = 701760 : EC/beta+ + 2 RTYP = 1 Q = 1.31980E+00 MeV frac = 9.99050E-01 Product nuclide = 72176.82c : beta- + + Nuclide 1426 / 1657 : 711770 -- lutetium 177 (Lu-177) + + Pointers : 2060250 -1000000 + Primary type : Decay + Nuclide ZAI : 711770 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 176.94404 + Atomic weight ratio (AWR) : 175.42400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.74E+05 seconds (6.65 days) + Specific ingestion toxicity : 5.30E-10 Sv/Bq + Specific inhalation toxicity : 1.20E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.98300E-01 MeV frac = 1.00000E+00 Product nuclide = 72177.82c : beta- + + Nuclide 1427 / 1657 : 711771 -- lutetium 177m (Lu-177m) + + Pointers : 2060943 -1000000 + Primary type : Decay + Nuclide ZAI : 711771 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 176.94404 + Atomic weight ratio (AWR) : 175.42400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.38E+07 seconds (160 days) + Specific ingestion toxicity : 1.70E-09 Sv/Bq + Specific inhalation toxicity : 1.60E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.52500E-01 MeV frac = 7.74000E-01 Product nuclide = 721771 : beta- + 2 RTYP = 3 Q = 9.70175E-01 MeV frac = 2.26000E-01 Product nuclide = 711770 : IT + + Nuclide 1428 / 1657 : 711772 -- lutetium 177m (Lu-177m) + + Pointers : 3516756 -1000000 + Primary type : Decay + Nuclide ZAI : 711772 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 176.94404 + Atomic weight ratio (AWR) : 175.42400 + Temperature : 900.0 Kelvin + XS temperature : -1.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.20E+02 seconds (7 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is not present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.66058E+00 MeV frac = 5.00000E-01 Product nuclide = 721772 : beta- + 2 RTYP = 3 Q = 2.92983E+00 MeV frac = 5.00000E-01 Product nuclide = 711771 : IT + + Nuclide 1429 / 1657 : 711780 -- lutetium 178 (Lu-178) + + Pointers : 2061933 -1000000 + Primary type : Decay + Nuclide ZAI : 711780 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 177.94565 + Atomic weight ratio (AWR) : 176.41700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.70E+03 seconds (28.4 minutes) + Specific ingestion toxicity : 4.70E-11 Sv/Bq + Specific inhalation toxicity : 2.60E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.10130E+00 MeV frac = 1.00000E+00 Product nuclide = 72178.82c : beta- + + Nuclide 1430 / 1657 : 711781 -- lutetium 178m (Lu-178m) + + Pointers : 2062850 -1000000 + Primary type : Decay + Nuclide ZAI : 711781 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 177.94565 + Atomic weight ratio (AWR) : 176.41700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.39E+03 seconds (23.1 minutes) + Specific ingestion toxicity : 3.80E-11 Sv/Bq + Specific inhalation toxicity : 3.30E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.07758E+00 MeV frac = 1.00000E+00 Product nuclide = 721781 : beta- + + Nuclide 1431 / 1657 : 711790 -- lutetium 179 (Lu-179) + + Pointers : 2063034 -1000000 + Primary type : Decay + Nuclide ZAI : 711790 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 178.94725 + Atomic weight ratio (AWR) : 177.41000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.65E+04 seconds (4.59 hours) + Specific ingestion toxicity : 2.10E-10 Sv/Bq + Specific inhalation toxicity : 1.20E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.40800E+00 MeV frac = 1.00000E+00 Product nuclide = 72179.82c : beta- + + Nuclide 1432 / 1657 : 711791 -- lutetium 179m (Lu-179m) + + Pointers : 2064777 -1000000 + Primary type : Decay + Nuclide ZAI : 711791 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 178.94725 + Atomic weight ratio (AWR) : 177.41000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.1 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 5.92400E-01 MeV frac = 1.00000E+00 Product nuclide = 711790 : IT + + Nuclide 1433 / 1657 : 711800 -- lutetium 180 (Lu-180) + + Pointers : 2064961 -1000000 + Primary type : Decay + Nuclide ZAI : 711800 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 179.94986 + Atomic weight ratio (AWR) : 178.40400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.42E+02 seconds (5.7 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.10000E+00 MeV frac = 1.00000E+00 Product nuclide = 72180.82c : beta- + + Nuclide 1434 / 1657 : 711801 -- lutetium 180m (Lu-180m) + + Pointers : 2066410 -1000000 + Primary type : Decay + Nuclide ZAI : 711801 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 179.94986 + Atomic weight ratio (AWR) : 178.40400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 3.11230E+00 MeV frac = 5.00000E-01 Product nuclide = 72180.82c : beta- + 2 RTYP = 3 Q = 1.39000E-02 MeV frac = 5.00000E-01 Product nuclide = 711800 : IT + + Nuclide 1435 / 1657 : 711802 -- lutetium 180m (Lu-180m) + + Pointers : 3517832 -1000000 + Primary type : Decay + Nuclide ZAI : 711802 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 179.94986 + Atomic weight ratio (AWR) : 178.40400 + Temperature : 900.0 Kelvin + XS temperature : -1.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is not present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 2.58090E+00 MeV frac = 5.00000E-01 Product nuclide = 721801 : beta- + 2 RTYP = 3 Q = 6.24000E-01 MeV frac = 5.00000E-01 Product nuclide = 711800 : IT + + Nuclide 1436 / 1657 : 711810 -- lutetium 181 (Lu-181) + + Pointers : 2066667 -1000000 + Primary type : Decay + Nuclide ZAI : 711810 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 180.95248 + Atomic weight ratio (AWR) : 179.39800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.10E+02 seconds (3.5 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.67190E+00 MeV frac = 1.00000E+00 Product nuclide = 721810 : beta- + + Nuclide 1437 / 1657 : 711820 -- lutetium 182 (Lu-182) + + Pointers : 2066851 -1000000 + Primary type : Decay + Nuclide ZAI : 711820 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 181.95509 + Atomic weight ratio (AWR) : 180.39200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.20E+02 seconds (2 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.17900E+00 MeV frac = 1.00000E+00 Product nuclide = 721820 : beta- + + Nuclide 1438 / 1657 : 711830 -- lutetium 183 (Lu-183) + + Pointers : 2067035 -1000000 + Primary type : Decay + Nuclide ZAI : 711830 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 182.95770 + Atomic weight ratio (AWR) : 181.38600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 58 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.40000E+00 MeV frac = 1.00000E+00 Product nuclide = 721830 : beta- + + Nuclide 1439 / 1657 : 711840 -- lutetium 184 (Lu-184) + + Pointers : 2068092 -1000000 + Primary type : Decay + Nuclide ZAI : 711840 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 183.96133 + Atomic weight ratio (AWR) : 182.38100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 20 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 5.09000E+00 MeV frac = 5.00000E-01 Product nuclide = 721840 : beta- + 2 RTYP = 1 Q = 3.81760E+00 MeV frac = 5.00000E-01 Product nuclide = 721841 : beta- + + Nuclide 1440 / 1657 : 721740 -- hafnium 174 (Hf-174) + + Pointers : 2068349 -1000000 + Primary type : Decay + Nuclide ZAI : 721740 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 173.94024 + Atomic weight ratio (AWR) : 172.44600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.31E+22 seconds (2E+15 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 4 Q = 2.50400E+00 MeV frac = 1.00000E+00 Product nuclide = 701700 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 2.50400E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 1441 / 1657 : 721750 -- hafnium 175 (Hf-175) + + Pointers : 2068639 -1000000 + Primary type : Decay + Nuclide ZAI : 721750 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 174.94184 + Atomic weight ratio (AWR) : 173.43900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.05E+06 seconds (70 days) + Specific ingestion toxicity : 4.10E-10 Sv/Bq + Specific inhalation toxicity : 1.20E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 6.19000E-01 MeV frac = 1.00000E+00 Product nuclide = 71175.82c : EC/beta+ + + Nuclide 1442 / 1657 : 721771 -- hafnium 177m (Hf-177m) + + Pointers : 2074397 -1000000 + Primary type : Decay + Nuclide ZAI : 721771 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 176.94303 + Atomic weight ratio (AWR) : 175.42300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.08 seconds + Specific ingestion toxicity : 8.10E-11 Sv/Bq + Specific inhalation toxicity : 9.00E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.31545E+00 MeV frac = 1.00000E+00 Product nuclide = 72177.82c : IT + + Nuclide 1443 / 1657 : 721772 -- hafnium 177m (Hf-177m) + + Pointers : 3517013 -1000000 + Primary type : Decay + Nuclide ZAI : 721772 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 176.94303 + Atomic weight ratio (AWR) : 175.42300 + Temperature : 900.0 Kelvin + XS temperature : -1.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.08E+03 seconds (51.4 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is not present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.42455E+00 MeV frac = 1.00000E+00 Product nuclide = 721771 : IT + + Nuclide 1444 / 1657 : 721781 -- hafnium 178m (Hf-178m) + + Pointers : 2079489 -1000000 + Primary type : Decay + Nuclide ZAI : 721781 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 177.94363 + Atomic weight ratio (AWR) : 176.41500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4 seconds + Specific ingestion toxicity : 4.70E-09 Sv/Bq + Specific inhalation toxicity : 2.60E-07 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.14742E+00 MeV frac = 1.00000E+00 Product nuclide = 72178.82c : IT + + Nuclide 1445 / 1657 : 721782 -- hafnium 178m (Hf-178m) + + Pointers : 3518089 -1000000 + Primary type : Decay + Nuclide ZAI : 721782 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 177.94363 + Atomic weight ratio (AWR) : 176.41500 + Temperature : 900.0 Kelvin + XS temperature : -1.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.78E+08 seconds (31 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is not present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.29863E+00 MeV frac = 1.00000E+00 Product nuclide = 721781 : IT + + Nuclide 1446 / 1657 : 721791 -- hafnium 179m (Hf-179m) + + Pointers : 2082140 -1000000 + Primary type : Decay + Nuclide ZAI : 721791 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 178.94624 + Atomic weight ratio (AWR) : 177.40900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 18.7 seconds + Specific ingestion toxicity : 1.20E-09 Sv/Bq + Specific inhalation toxicity : 3.80E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 3.75037E-01 MeV frac = 1.00000E+00 Product nuclide = 72179.82c : IT + + Nuclide 1447 / 1657 : 721792 -- hafnium 179m (Hf-179m) + + Pointers : 3503704 -1000000 + Primary type : Decay + Nuclide ZAI : 721792 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 178.94624 + Atomic weight ratio (AWR) : 177.40900 + Temperature : 900.0 Kelvin + XS temperature : -1.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.17E+06 seconds (25.1 days) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is not present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.10580E+00 MeV frac = 1.00000E+00 Product nuclide = 72179.82c : IT + + Nuclide 1448 / 1657 : 721801 -- hafnium 180m (Hf-180m) + + Pointers : 2084514 -1000000 + Primary type : Decay + Nuclide ZAI : 721801 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 179.94684 + Atomic weight ratio (AWR) : 178.40100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.98E+04 seconds (5.5 hours) + Specific ingestion toxicity : 1.70E-10 Sv/Bq + Specific inhalation toxicity : 1.30E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 2.12000E-01 MeV frac = 3.10000E-03 Product nuclide = 731801 : beta- + 2 RTYP = 3 Q = 1.14148E+00 MeV frac = 9.96900E-01 Product nuclide = 72180.82c : IT + + Nuclide 1449 / 1657 : 721810 -- hafnium 181 (Hf-181) + + Pointers : 2085462 -1000000 + Primary type : Decay + Nuclide ZAI : 721810 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 180.94945 + Atomic weight ratio (AWR) : 179.39500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.66E+06 seconds (42.4 days) + Specific ingestion toxicity : 1.10E-09 Sv/Bq + Specific inhalation toxicity : 5.00E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.02830E+00 MeV frac = 1.00000E+00 Product nuclide = 73181.82c : beta- + + Nuclide 1450 / 1657 : 721820 -- hafnium 182 (Hf-182) + + Pointers : 2086337 -1000000 + Primary type : Decay + Nuclide ZAI : 721820 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 181.95005 + Atomic weight ratio (AWR) : 180.38700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.81E+14 seconds (8.91 million years) + Specific ingestion toxicity : 3.00E-09 Sv/Bq + Specific inhalation toxicity : 3.10E-07 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.75000E-01 MeV frac = 1.00000E+00 Product nuclide = 73182.82c : beta- + + Nuclide 1451 / 1657 : 721821 -- hafnium 182m (Hf-182m) + + Pointers : 2087002 -1000000 + Primary type : Decay + Nuclide ZAI : 721821 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 181.95106 + Atomic weight ratio (AWR) : 180.38800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.69E+03 seconds (1.02 hours) + Specific ingestion toxicity : 4.20E-11 Sv/Bq + Specific inhalation toxicity : 4.60E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.02761E+00 MeV frac = 5.80000E-01 Product nuclide = 731821 : beta- + 2 RTYP = 3 Q = 1.17288E+00 MeV frac = 4.20000E-01 Product nuclide = 721820 : IT + + Nuclide 1452 / 1657 : 721830 -- hafnium 183 (Hf-183) + + Pointers : 2087259 -1000000 + Primary type : Decay + Nuclide ZAI : 721830 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 182.95367 + Atomic weight ratio (AWR) : 181.38200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.84E+03 seconds (1.07 hours) + Specific ingestion toxicity : 7.30E-11 Sv/Bq + Specific inhalation toxicity : 5.70E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.00610E+00 MeV frac = 1.00000E+00 Product nuclide = 731830 : beta- + + Nuclide 1453 / 1657 : 721840 -- hafnium 184 (Hf-184) + + Pointers : 2087443 -1000000 + Primary type : Decay + Nuclide ZAI : 721840 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 183.95527 + Atomic weight ratio (AWR) : 182.37500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.48E+04 seconds (4.12 hours) + Specific ingestion toxicity : 5.20E-10 Sv/Bq + Specific inhalation toxicity : 3.30E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.34100E+00 MeV frac = 1.00000E+00 Product nuclide = 731840 : beta- + + Nuclide 1454 / 1657 : 721841 -- hafnium 184m (Hf-184m) + + Pointers : 2087627 -1000000 + Primary type : Decay + Nuclide ZAI : 721841 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 183.95527 + Atomic weight ratio (AWR) : 182.37500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 48 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.61340E+00 MeV frac = 1.00000E+00 Product nuclide = 731840 : beta- + + Nuclide 1455 / 1657 : 721850 -- hafnium 185 (Hf-185) + + Pointers : 2087811 -1000000 + Primary type : Decay + Nuclide ZAI : 721850 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 184.95889 + Atomic weight ratio (AWR) : 183.37000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.10E+02 seconds (3.5 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.03600E+00 MeV frac = 1.00000E+00 Product nuclide = 731850 : beta- + + Nuclide 1456 / 1657 : 721860 -- hafnium 186 (Hf-186) + + Pointers : 2087995 -1000000 + Primary type : Decay + Nuclide ZAI : 721860 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 185.96050 + Atomic weight ratio (AWR) : 184.36300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.56E+02 seconds (2.6 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.18000E+00 MeV frac = 1.00000E+00 Product nuclide = 731860 : beta- + + Nuclide 1457 / 1657 : 721870 -- hafnium 187 (Hf-187) + + Pointers : 2088179 -1000000 + Primary type : Decay + Nuclide ZAI : 721870 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 186.96412 + Atomic weight ratio (AWR) : 185.35800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 30 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.79000E+00 MeV frac = 1.00000E+00 Product nuclide = 731870 : beta- + + Nuclide 1458 / 1657 : 721880 -- hafnium 188 (Hf-188) + + Pointers : 2088363 -1000000 + Primary type : Decay + Nuclide ZAI : 721880 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 187.96673 + Atomic weight ratio (AWR) : 186.35200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 20 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.93000E+00 MeV frac = 1.00000E+00 Product nuclide = 731880 : beta- + + Nuclide 1459 / 1657 : 731780 -- tantalum 178 (Ta-178) + + Pointers : 2088547 -1000000 + Primary type : Decay + Nuclide ZAI : 731780 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 177.94565 + Atomic weight ratio (AWR) : 176.41700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.59E+02 seconds (9.31 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 1.91000E+00 MeV frac = 1.00000E+00 Product nuclide = 72178.82c : EC/beta+ + + Nuclide 1460 / 1657 : 731781 -- tantalum 178m (Ta-178m) + + Pointers : 2089996 -1000000 + Primary type : Decay + Nuclide ZAI : 731781 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 177.94565 + Atomic weight ratio (AWR) : 176.41700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.50E+03 seconds (2.36 hours) + Specific ingestion toxicity : 7.20E-11 Sv/Bq + Specific inhalation toxicity : 6.80E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 7.89875E-01 MeV frac = 1.00000E+00 Product nuclide = 721781 : EC/beta+ + + Nuclide 1461 / 1657 : 731790 -- tantalum 179 (Ta-179) + + Pointers : 2090180 -1000000 + Primary type : Decay + Nuclide ZAI : 731790 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 178.94624 + Atomic weight ratio (AWR) : 177.40900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.08E+07 seconds (1.61 years) + Specific ingestion toxicity : 6.50E-11 Sv/Bq + Specific inhalation toxicity : 5.60E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 1.10000E-01 MeV frac = 1.00000E+00 Product nuclide = 72179.82c : EC/beta+ + + Nuclide 1462 / 1657 : 731791 -- tantalum 179m (Ta-179m) + + Pointers : 2090523 -1000000 + Primary type : Decay + Nuclide ZAI : 731791 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 178.94624 + Atomic weight ratio (AWR) : 177.40900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.31730E+00 MeV frac = 1.00000E+00 Product nuclide = 731790 : IT + + Nuclide 1463 / 1657 : 731792 -- tantalum 179m (Ta-179m) + + Pointers : 3521683 -1000000 + Primary type : Decay + Nuclide ZAI : 731792 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 178.94624 + Atomic weight ratio (AWR) : 177.40900 + Temperature : 900.0 Kelvin + XS temperature : -1.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 54.1 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is not present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.32200E+00 MeV frac = 1.00000E+00 Product nuclide = 731791 : IT + + Nuclide 1464 / 1657 : 731800 -- tantalum 180 (Ta-180) + + Pointers : 2090707 -1000000 + Primary type : Decay + Nuclide ZAI : 731800 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 179.94785 + Atomic weight ratio (AWR) : 178.40200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.91E+04 seconds (8.08 hours) + Specific ingestion toxicity : 5.40E-11 Sv/Bq + Specific inhalation toxicity : 4.20E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 7.08000E-01 MeV frac = 1.81000E-01 Product nuclide = 741800 : beta- + 2 RTYP = 2 Q = 8.53000E-01 MeV frac = 8.19000E-01 Product nuclide = 72180.82c : EC/beta+ + + Nuclide 1465 / 1657 : 731801 -- tantalum 180m (Ta-180m) + + Pointers : 2091389 -1000000 + Primary type : Decay + Nuclide ZAI : 731801 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 179.94785 + Atomic weight ratio (AWR) : 178.40200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.68E+22 seconds (1.8E+15 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 7.83000E-01 MeV frac = 2.00000E-01 Product nuclide = 741800 : beta- + 2 RTYP = 2 Q = 9.28000E-01 MeV frac = 8.00000E-01 Product nuclide = 72180.82c : EC/beta+ + + Nuclide 1466 / 1657 : 731821 -- tantalum 182m (Ta-182m) + + Pointers : 2098658 -1000000 + Primary type : Decay + Nuclide ZAI : 731821 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 181.95005 + Atomic weight ratio (AWR) : 180.38700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.283 seconds + Specific ingestion toxicity : 1.20E-11 Sv/Bq + Specific inhalation toxicity : 2.10E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.62630E-02 MeV frac = 1.00000E+00 Product nuclide = 73182.82c : IT + + Nuclide 1467 / 1657 : 731822 -- tantalum 182m (Ta-182m) + + Pointers : 3519034 -1000000 + Primary type : Decay + Nuclide ZAI : 731822 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 181.95005 + Atomic weight ratio (AWR) : 180.38700 + Temperature : 900.0 Kelvin + XS temperature : -1.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.50E+02 seconds (15.8 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is not present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 5.03310E-01 MeV frac = 1.00000E+00 Product nuclide = 731821 : IT + + Nuclide 1468 / 1657 : 731830 -- tantalum 183 (Ta-183) + + Pointers : 2098973 -1000000 + Primary type : Decay + Nuclide ZAI : 731830 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 182.95165 + Atomic weight ratio (AWR) : 181.38000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.40E+05 seconds (5.09 days) + Specific ingestion toxicity : 1.30E-09 Sv/Bq + Specific inhalation toxicity : 2.10E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.07010E+00 MeV frac = 9.66000E-01 Product nuclide = 74183.82c : beta- + 2 RTYP = 1 Q = 7.60600E-01 MeV frac = 3.40000E-02 Product nuclide = 741831 : beta- + + Nuclide 1469 / 1657 : 731840 -- tantalum 184 (Ta-184) + + Pointers : 2101139 -1000000 + Primary type : Decay + Nuclide ZAI : 731840 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 183.95426 + Atomic weight ratio (AWR) : 182.37400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.13E+04 seconds (8.7 hours) + Specific ingestion toxicity : 6.80E-10 Sv/Bq + Specific inhalation toxicity : 4.30E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.86630E+00 MeV frac = 1.00000E+00 Product nuclide = 74184.82c : beta- + + Nuclide 1470 / 1657 : 731850 -- tantalum 185 (Ta-185) + + Pointers : 2101323 -1000000 + Primary type : Decay + Nuclide ZAI : 731850 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 184.95587 + Atomic weight ratio (AWR) : 183.36700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.96E+03 seconds (49.4 minutes) + Specific ingestion toxicity : 6.80E-11 Sv/Bq + Specific inhalation toxicity : 4.80E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.99400E+00 MeV frac = 1.00000E+00 Product nuclide = 741850 : beta- + + Nuclide 1471 / 1657 : 731851 -- tantalum 185m (Ta-185m) + + Pointers : 2102870 -1000000 + Primary type : Decay + Nuclide ZAI : 731851 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 184.95587 + Atomic weight ratio (AWR) : 183.36700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.30800E+00 MeV frac = 1.00000E+00 Product nuclide = 731850 : IT + + Nuclide 1472 / 1657 : 731860 -- tantalum 186 (Ta-186) + + Pointers : 2103054 -1000000 + Primary type : Decay + Nuclide ZAI : 731860 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 185.95848 + Atomic weight ratio (AWR) : 184.36100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.30E+02 seconds (10.5 minutes) + Specific ingestion toxicity : 3.30E-11 Sv/Bq + Specific inhalation toxicity : 1.80E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.89950E+00 MeV frac = 1.00000E+00 Product nuclide = 74186.82c : beta- + + Nuclide 1473 / 1657 : 731870 -- tantalum 187 (Ta-187) + + Pointers : 2103238 -1000000 + Primary type : Decay + Nuclide ZAI : 731870 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 186.96009 + Atomic weight ratio (AWR) : 185.35400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.20E+02 seconds (2 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.13480E+00 MeV frac = 1.00000E+00 Product nuclide = 741870 : beta- + + Nuclide 1474 / 1657 : 731880 -- tantalum 188 (Ta-188) + + Pointers : 2103422 -1000000 + Primary type : Decay + Nuclide ZAI : 731880 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 187.96371 + Atomic weight ratio (AWR) : 186.34900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 20 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.85700E+00 MeV frac = 1.00000E+00 Product nuclide = 741880 : beta- + + Nuclide 1475 / 1657 : 731890 -- tantalum 189 (Ta-189) + + Pointers : 2103606 -1000000 + Primary type : Decay + Nuclide ZAI : 731890 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 188.96632 + Atomic weight ratio (AWR) : 187.34300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.65000E+00 MeV frac = 1.00000E+00 Product nuclide = 741890 : beta- + + Nuclide 1476 / 1657 : 731900 -- tantalum 190 (Ta-190) + + Pointers : 2103790 -1000000 + Primary type : Decay + Nuclide ZAI : 731900 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 189.96893 + Atomic weight ratio (AWR) : 188.33700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.64000E+00 MeV frac = 1.00000E+00 Product nuclide = 741900 : beta- + + Nuclide 1477 / 1657 : 741800 -- tungsten 180 (W-180) + + Pointers : 2103974 -1000000 + Primary type : Decay + Nuclide ZAI : 741800 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 179.94684 + Atomic weight ratio (AWR) : 178.40100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1478 / 1657 : 741810 -- tungsten 181 (W-181) + + Pointers : 2104080 -1000000 + Primary type : Decay + Nuclide ZAI : 741810 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 180.94844 + Atomic weight ratio (AWR) : 179.39400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.05E+07 seconds (121 days) + Specific ingestion toxicity : 7.60E-11 Sv/Bq + Specific inhalation toxicity : 2.70E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 1.86000E-01 MeV frac = 1.00000E+00 Product nuclide = 73181.82c : EC/beta+ + + Nuclide 1479 / 1657 : 741831 -- tungsten 183m (W-183m) + + Pointers : 2110425 -1000000 + Primary type : Decay + Nuclide ZAI : 741831 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 182.95064 + Atomic weight ratio (AWR) : 181.37900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.25 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 3.09500E-01 MeV frac = 1.00000E+00 Product nuclide = 74183.82c : IT + + Nuclide 1480 / 1657 : 741850 -- tungsten 185 (W-185) + + Pointers : 2113615 -1000000 + Primary type : Decay + Nuclide ZAI : 741850 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 184.95385 + Atomic weight ratio (AWR) : 183.36500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.49E+06 seconds (75.1 days) + Specific ingestion toxicity : 4.40E-10 Sv/Bq + Specific inhalation toxicity : 1.20E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.32800E-01 MeV frac = 1.00000E+00 Product nuclide = 75185.82c : beta- + + Nuclide 1481 / 1657 : 741851 -- tungsten 185m (W-185m) + + Pointers : 2114042 -1000000 + Primary type : Decay + Nuclide ZAI : 741851 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 184.95385 + Atomic weight ratio (AWR) : 183.36500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.00E+02 seconds (1.67 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.97430E-01 MeV frac = 1.00000E+00 Product nuclide = 741850 : IT + + Nuclide 1482 / 1657 : 741861 -- tungsten 186m (W-186m) + + Pointers : 2117737 -1000000 + Primary type : Decay + Nuclide ZAI : 741861 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 185.95445 + Atomic weight ratio (AWR) : 184.35700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 3.54280E+00 MeV frac = 1.00000E+00 Product nuclide = 74186.82c : IT + + Nuclide 1483 / 1657 : 741870 -- tungsten 187 (W-187) + + Pointers : 2117921 -1000000 + Primary type : Decay + Nuclide ZAI : 741870 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 186.95706 + Atomic weight ratio (AWR) : 185.35100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.59E+04 seconds (23.8 hours) + Specific ingestion toxicity : 6.30E-10 Sv/Bq + Specific inhalation toxicity : 1.90E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.31250E+00 MeV frac = 1.00000E+00 Product nuclide = 75187.82c : beta- + + Nuclide 1484 / 1657 : 741880 -- tungsten 188 (W-188) + + Pointers : 2120784 -1000000 + Primary type : Decay + Nuclide ZAI : 741880 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 187.95866 + Atomic weight ratio (AWR) : 186.34400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.03E+06 seconds (69.8 days) + Specific ingestion toxicity : 2.10E-09 Sv/Bq + Specific inhalation toxicity : 5.70E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.49000E-01 MeV frac = 1.00000E+00 Product nuclide = 751880 : beta- + + Nuclide 1485 / 1657 : 741890 -- tungsten 189 (W-189) + + Pointers : 2121505 -1000000 + Primary type : Decay + Nuclide ZAI : 741890 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 188.96229 + Atomic weight ratio (AWR) : 187.33900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.42E+02 seconds (10.7 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.49800E+00 MeV frac = 1.00000E+00 Product nuclide = 751890 : beta- + + Nuclide 1486 / 1657 : 741900 -- tungsten 190 (W-190) + + Pointers : 2121689 -1000000 + Primary type : Decay + Nuclide ZAI : 741900 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 189.96288 + Atomic weight ratio (AWR) : 188.33100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.80E+03 seconds (30 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.27000E+00 MeV frac = 1.00000E+00 Product nuclide = 751900 : beta- + + Nuclide 1487 / 1657 : 741901 -- tungsten 190m (W-190m) + + Pointers : 2122144 -1000000 + Primary type : Decay + Nuclide ZAI : 741901 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 189.96288 + Atomic weight ratio (AWR) : 188.33100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.1 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 2.38100E+00 MeV frac = 1.00000E+00 Product nuclide = 741900 : IT + + Nuclide 1488 / 1657 : 741910 -- tungsten 191 (W-191) + + Pointers : 2122328 -1000000 + Primary type : Decay + Nuclide ZAI : 741910 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 190.96650 + Atomic weight ratio (AWR) : 189.32600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 20 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.23900E+00 MeV frac = 1.00000E+00 Product nuclide = 751910 : beta- + + Nuclide 1489 / 1657 : 741920 -- tungsten 192 (W-192) + + Pointers : 2122512 -1000000 + Primary type : Decay + Nuclide ZAI : 741920 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 191.96811 + Atomic weight ratio (AWR) : 190.31900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 10 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.06000E+00 MeV frac = 1.00000E+00 Product nuclide = 751920 : beta- + + Nuclide 1490 / 1657 : 751830 -- rhenium 183 (Re-183) + + Pointers : 2122696 -1000000 + Primary type : Decay + Nuclide ZAI : 751830 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 182.95064 + Atomic weight ratio (AWR) : 181.37900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.05E+06 seconds (70 days) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 5.56000E-01 MeV frac = 1.00000E+00 Product nuclide = 74183.82c : EC/beta+ + + Nuclide 1491 / 1657 : 751840 -- rhenium 184 (Re-184) + + Pointers : 2124565 -1000000 + Primary type : Decay + Nuclide ZAI : 751840 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 183.95225 + Atomic weight ratio (AWR) : 182.37200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.06E+06 seconds (35.4 days) + Specific ingestion toxicity : 1.00E-09 Sv/Bq + Specific inhalation toxicity : 1.90E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 1.48000E+00 MeV frac = 1.00000E+00 Product nuclide = 74184.82c : EC/beta+ + + Nuclide 1492 / 1657 : 751841 -- rhenium 184m (Re-184m) + + Pointers : 2126560 -1000000 + Primary type : Decay + Nuclide ZAI : 751841 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 183.95225 + Atomic weight ratio (AWR) : 182.37200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.45E+07 seconds (168 days) + Specific ingestion toxicity : 1.50E-09 Sv/Bq + Specific inhalation toxicity : 6.50E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 1.66800E+00 MeV frac = 2.52000E-01 Product nuclide = 74184.82c : EC/beta+ + 2 RTYP = 3 Q = 1.88010E-01 MeV frac = 7.48000E-01 Product nuclide = 751840 : IT + + Nuclide 1493 / 1657 : 751860 -- rhenium 186 (Re-186) + + Pointers : 2130461 -1000000 + Primary type : Decay + Nuclide ZAI : 751860 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 185.95546 + Atomic weight ratio (AWR) : 184.35800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.24E+05 seconds (3.75 days) + Specific ingestion toxicity : 1.50E-09 Sv/Bq + Specific inhalation toxicity : 1.10E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.06930E+00 MeV frac = 9.31300E-01 Product nuclide = 761860 : beta- + 2 RTYP = 2 Q = 5.79000E-01 MeV frac = 6.87000E-02 Product nuclide = 74186.82c : EC/beta+ + + Nuclide 1494 / 1657 : 751861 -- rhenium 186m (Re-186m) + + Pointers : 2131521 -1000000 + Primary type : Decay + Nuclide ZAI : 751861 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 185.95546 + Atomic weight ratio (AWR) : 184.35800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.00E+12 seconds (190,126 years) + Specific ingestion toxicity : 2.20E-09 Sv/Bq + Specific inhalation toxicity : 1.20E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.49000E-01 MeV frac = 1.00000E+00 Product nuclide = 751860 : IT + + Nuclide 1495 / 1657 : 751880 -- rhenium 188 (Re-188) + + Pointers : 2134034 -1000000 + Primary type : Decay + Nuclide ZAI : 751880 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 187.95766 + Atomic weight ratio (AWR) : 186.34300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.12E+04 seconds (17 hours) + Specific ingestion toxicity : 1.40E-09 Sv/Bq + Specific inhalation toxicity : 5.40E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.12040E+00 MeV frac = 1.00000E+00 Product nuclide = 761880 : beta- + + Nuclide 1496 / 1657 : 751881 -- rhenium 188m (Re-188m) + + Pointers : 2136001 -1000000 + Primary type : Decay + Nuclide ZAI : 751881 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 187.95766 + Atomic weight ratio (AWR) : 186.34300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.12E+03 seconds (18.6 minutes) + Specific ingestion toxicity : 3.00E-11 Sv/Bq + Specific inhalation toxicity : 1.30E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.72069E-01 MeV frac = 1.00000E+00 Product nuclide = 751880 : IT + + Nuclide 1497 / 1657 : 751890 -- rhenium 189 (Re-189) + + Pointers : 2136185 -1000000 + Primary type : Decay + Nuclide ZAI : 751890 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 188.95926 + Atomic weight ratio (AWR) : 187.33600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.75E+04 seconds (1.01 days) + Specific ingestion toxicity : 7.80E-10 Sv/Bq + Specific inhalation toxicity : 4.30E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.00900E+00 MeV frac = 8.97169E-01 Product nuclide = 761890 : beta- + 2 RTYP = 1 Q = 9.78188E-01 MeV frac = 1.02831E-01 Product nuclide = 761891 : beta- + + Nuclide 1498 / 1657 : 751900 -- rhenium 190 (Re-190) + + Pointers : 2140703 -1000000 + Primary type : Decay + Nuclide ZAI : 751900 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 189.96187 + Atomic weight ratio (AWR) : 188.33000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.86E+02 seconds (3.1 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.14000E+00 MeV frac = 1.00000E+00 Product nuclide = 761900 : beta- + + Nuclide 1499 / 1657 : 751901 -- rhenium 190m (Re-190m) + + Pointers : 2142222 -1000000 + Primary type : Decay + Nuclide ZAI : 751901 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 189.96187 + Atomic weight ratio (AWR) : 188.33000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.15E+04 seconds (3.2 hours) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.64090E+00 MeV frac = 5.44000E-01 Product nuclide = 761901 : beta- + 2 RTYP = 3 Q = 2.10000E-01 MeV frac = 4.56000E-01 Product nuclide = 751900 : IT + + Nuclide 1500 / 1657 : 751910 -- rhenium 191 (Re-191) + + Pointers : 2142479 -1000000 + Primary type : Decay + Nuclide ZAI : 751910 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 190.96348 + Atomic weight ratio (AWR) : 189.32300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.82E+02 seconds (9.7 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.97000E+00 MeV frac = 1.00000E+00 Product nuclide = 761910 : beta- + + Nuclide 1501 / 1657 : 751920 -- rhenium 192 (Re-192) + + Pointers : 2142696 -1000000 + Primary type : Decay + Nuclide ZAI : 751920 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 191.96609 + Atomic weight ratio (AWR) : 190.31700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.17400E+00 MeV frac = 1.00000E+00 Product nuclide = 761920 : beta- + + Nuclide 1502 / 1657 : 751930 -- rhenium 193 (Re-193) + + Pointers : 2143375 -1000000 + Primary type : Decay + Nuclide ZAI : 751930 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 192.96769 + Atomic weight ratio (AWR) : 191.31000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 30 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.09260E+00 MeV frac = 1.00000E+00 Product nuclide = 761930 : beta- + + Nuclide 1503 / 1657 : 751940 -- rhenium 194 (Re-194) + + Pointers : 2143559 -1000000 + Primary type : Decay + Nuclide ZAI : 751940 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 193.97031 + Atomic weight ratio (AWR) : 192.30400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.88270E+00 MeV frac = 1.00000E+00 Product nuclide = 761940 : beta- + + Nuclide 1504 / 1657 : 761860 -- osmium 186 (Os-186) + + Pointers : 2143743 -1000000 + Primary type : Decay + Nuclide ZAI : 761860 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 185.95344 + Atomic weight ratio (AWR) : 184.35600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.31E+22 seconds (2E+15 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 4 Q = 2.82310E+00 MeV frac = 1.00000E+00 Product nuclide = 74182.82c : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 2.82310E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 1505 / 1657 : 761870 -- osmium 187 (Os-187) + + Pointers : 2144000 -1000000 + Primary type : Decay + Nuclide ZAI : 761870 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 186.95605 + Atomic weight ratio (AWR) : 185.35000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1506 / 1657 : 761880 -- osmium 188 (Os-188) + + Pointers : 2144106 -1000000 + Primary type : Decay + Nuclide ZAI : 761880 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 187.95564 + Atomic weight ratio (AWR) : 186.34100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1507 / 1657 : 761890 -- osmium 189 (Os-189) + + Pointers : 2144212 -1000000 + Primary type : Decay + Nuclide ZAI : 761890 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 188.95825 + Atomic weight ratio (AWR) : 187.33500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1508 / 1657 : 761891 -- osmium 189m (Os-189m) + + Pointers : 2144318 -1000000 + Primary type : Decay + Nuclide ZAI : 761891 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 188.95825 + Atomic weight ratio (AWR) : 187.33500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.09E+04 seconds (5.81 hours) + Specific ingestion toxicity : 1.80E-11 Sv/Bq + Specific inhalation toxicity : 5.30E-12 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 3.08120E-02 MeV frac = 1.00000E+00 Product nuclide = 761890 : IT + + Nuclide 1509 / 1657 : 761900 -- osmium 190 (Os-190) + + Pointers : 2144633 -1000000 + Primary type : Decay + Nuclide ZAI : 761900 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 189.95885 + Atomic weight ratio (AWR) : 188.32700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1510 / 1657 : 761901 -- osmium 190m (Os-190m) + + Pointers : 2144739 -1000000 + Primary type : Decay + Nuclide ZAI : 761901 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 189.95885 + Atomic weight ratio (AWR) : 188.32700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.94E+02 seconds (9.9 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.70540E+00 MeV frac = 1.00000E+00 Product nuclide = 761900 : IT + + Nuclide 1511 / 1657 : 761910 -- osmium 191 (Os-191) + + Pointers : 2145348 -1000000 + Primary type : Decay + Nuclide ZAI : 761910 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 190.96146 + Atomic weight ratio (AWR) : 189.32100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.32E+06 seconds (15.3 days) + Specific ingestion toxicity : 5.70E-10 Sv/Bq + Specific inhalation toxicity : 1.90E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.41500E-01 MeV frac = 1.00000E+00 Product nuclide = 771911 : beta- + + Nuclide 1512 / 1657 : 761911 -- osmium 191m (Os-191m) + + Pointers : 2145565 -1000000 + Primary type : Decay + Nuclide ZAI : 761911 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 190.96146 + Atomic weight ratio (AWR) : 189.32100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.72E+04 seconds (13.1 hours) + Specific ingestion toxicity : 9.60E-11 Sv/Bq + Specific inhalation toxicity : 1.60E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 7.43820E-02 MeV frac = 1.00000E+00 Product nuclide = 761910 : IT + + Nuclide 1513 / 1657 : 761920 -- osmium 192 (Os-192) + + Pointers : 2145964 -1000000 + Primary type : Decay + Nuclide ZAI : 761920 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 191.96105 + Atomic weight ratio (AWR) : 190.31200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1514 / 1657 : 761921 -- osmium 192m (Os-192m) + + Pointers : 2146070 -1000000 + Primary type : Decay + Nuclide ZAI : 761921 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 191.96105 + Atomic weight ratio (AWR) : 190.31200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.9 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 2.01540E+00 MeV frac = 8.70000E-01 Product nuclide = 761920 : IT + 2 RTYP = 1 Q = 7.99962E-01 MeV frac = 1.30000E-01 Product nuclide = 771921 : beta- + + Nuclide 1515 / 1657 : 761930 -- osmium 193 (Os-193) + + Pointers : 2146327 -1000000 + Primary type : Decay + Nuclide ZAI : 761930 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 192.96366 + Atomic weight ratio (AWR) : 191.30600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.08E+05 seconds (1.25 days) + Specific ingestion toxicity : 8.10E-10 Sv/Bq + Specific inhalation toxicity : 5.20E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.14120E+00 MeV frac = 9.97348E-01 Product nuclide = 77193.82c : beta- + 2 RTYP = 1 Q = 1.06096E+00 MeV frac = 2.65208E-03 Product nuclide = 771931 : beta- + + Nuclide 1516 / 1657 : 761940 -- osmium 194 (Os-194) + + Pointers : 2148493 -1000000 + Primary type : Decay + Nuclide ZAI : 761940 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 193.96526 + Atomic weight ratio (AWR) : 192.29900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.89E+08 seconds (6 years) + Specific ingestion toxicity : 2.40E-09 Sv/Bq + Specific inhalation toxicity : 8.50E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.66000E-02 MeV frac = 1.00000E+00 Product nuclide = 771940 : beta- + + Nuclide 1517 / 1657 : 761950 -- osmium 195 (Os-195) + + Pointers : 2148976 -1000000 + Primary type : Decay + Nuclide ZAI : 761950 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 194.96788 + Atomic weight ratio (AWR) : 193.29300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.90E+02 seconds (6.5 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 771950 : beta- + + Nuclide 1518 / 1657 : 761960 -- osmium 196 (Os-196) + + Pointers : 2150215 -1000000 + Primary type : Decay + Nuclide ZAI : 761960 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 195.96948 + Atomic weight ratio (AWR) : 194.28600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.09E+03 seconds (34.9 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.15800E+00 MeV frac = 1.00000E+00 Product nuclide = 771960 : beta- + + Nuclide 1519 / 1657 : 771890 -- iridium 189 (Ir-189) + + Pointers : 2151188 -1000000 + Primary type : Decay + Nuclide ZAI : 771890 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 188.95825 + Atomic weight ratio (AWR) : 187.33500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.14E+06 seconds (13.2 days) + Specific ingestion toxicity : 2.40E-10 Sv/Bq + Specific inhalation toxicity : 6.00E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 5.01000E-01 MeV frac = 7.50000E-02 Product nuclide = 761891 : EC/beta+ + 2 RTYP = 2 Q = 5.32000E-01 MeV frac = 9.25000E-01 Product nuclide = 761890 : EC/beta+ + + Nuclide 1520 / 1657 : 771891 -- iridium 189m (Ir-189m) + + Pointers : 2152906 -1000000 + Primary type : Decay + Nuclide ZAI : 771891 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 188.95825 + Atomic weight ratio (AWR) : 187.33500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 13.3 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 3.72170E-01 MeV frac = 1.00000E+00 Product nuclide = 771890 : IT + + Nuclide 1521 / 1657 : 771900 -- iridium 190 (Ir-190) + + Pointers : 2153090 -1000000 + Primary type : Decay + Nuclide ZAI : 771900 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 189.96086 + Atomic weight ratio (AWR) : 188.32900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.04E+06 seconds (12 days) + Specific ingestion toxicity : 1.20E-09 Sv/Bq + Specific inhalation toxicity : 2.40E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 2.08000E+00 MeV frac = 1.00000E+00 Product nuclide = 761900 : EC/beta+ + + Nuclide 1522 / 1657 : 771901 -- iridium 190m (Ir-190m) + + Pointers : 2156135 -1000000 + Primary type : Decay + Nuclide ZAI : 771901 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 189.96086 + Atomic weight ratio (AWR) : 188.32900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.03E+03 seconds (1.12 hours) + Specific ingestion toxicity : 1.20E-10 Sv/Bq + Specific inhalation toxicity : 8.30E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 2.61000E-02 MeV frac = 1.00000E+00 Product nuclide = 771900 : IT + + Nuclide 1523 / 1657 : 771902 -- iridium 190m (Ir-190m) + + Pointers : 3521867 -1000000 + Primary type : Decay + Nuclide ZAI : 771902 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 189.96086 + Atomic weight ratio (AWR) : 188.32900 + Temperature : 900.0 Kelvin + XS temperature : -1.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.11E+04 seconds (3.09 hours) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is not present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 3.76400E-01 MeV frac = 8.60000E-02 Product nuclide = 771900 : IT + 2 RTYP = 2 Q = 7.51000E-01 MeV frac = 9.14000E-01 Product nuclide = 761901 : EC/beta+ + + Nuclide 1524 / 1657 : 771911 -- iridium 191m (Ir-191m) + + Pointers : 2157802 -1000000 + Primary type : Decay + Nuclide ZAI : 771911 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 190.96045 + Atomic weight ratio (AWR) : 189.32000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.9 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.71240E-01 MeV frac = 1.00000E+00 Product nuclide = 77191.82c : IT + + Nuclide 1525 / 1657 : 771912 -- iridium 191m (Ir-191m) + + Pointers : 3522703 -1000000 + Primary type : Decay + Nuclide ZAI : 771912 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 190.96045 + Atomic weight ratio (AWR) : 189.32000 + Temperature : 900.0 Kelvin + XS temperature : -1.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is not present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.91400E+00 MeV frac = 1.00000E+00 Product nuclide = 771911 : IT + + Nuclide 1526 / 1657 : 771920 -- iridium 192 (Ir-192) + + Pointers : 2158341 -1000000 + Primary type : Decay + Nuclide ZAI : 771920 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 191.96306 + Atomic weight ratio (AWR) : 190.31400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.38E+06 seconds (73.8 days) + Specific ingestion toxicity : 1.40E-09 Sv/Bq + Specific inhalation toxicity : 6.60E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.45970E+00 MeV frac = 9.52000E-01 Product nuclide = 781920 : beta- + 2 RTYP = 2 Q = 1.04620E+00 MeV frac = 4.80000E-02 Product nuclide = 761920 : EC/beta+ + + Nuclide 1527 / 1657 : 771921 -- iridium 192m (Ir-192m) + + Pointers : 2160479 -1000000 + Primary type : Decay + Nuclide ZAI : 771921 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 191.96306 + Atomic weight ratio (AWR) : 190.31400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.64E+01 seconds (1.44 minutes) + Specific ingestion toxicity : 3.10E-10 Sv/Bq + Specific inhalation toxicity : 3.90E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.51640E+00 MeV frac = 1.75000E-04 Product nuclide = 781920 : beta- + 2 RTYP = 3 Q = 5.67200E-02 MeV frac = 9.99825E-01 Product nuclide = 771920 : IT + + Nuclide 1528 / 1657 : 771922 -- iridium 192m (Ir-192m) + + Pointers : 3519657 -1000000 + Primary type : Decay + Nuclide ZAI : 771922 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 191.96306 + Atomic weight ratio (AWR) : 190.31400 + Temperature : 900.0 Kelvin + XS temperature : -1.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.61E+09 seconds (241 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is not present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.68140E-01 MeV frac = 1.00000E+00 Product nuclide = 771920 : IT + + Nuclide 1529 / 1657 : 771931 -- iridium 193m (Ir-193m) + + Pointers : 2162555 -1000000 + Primary type : Decay + Nuclide ZAI : 771931 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 192.96265 + Atomic weight ratio (AWR) : 191.30500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.10E+05 seconds (10.5 days) + Specific ingestion toxicity : 2.70E-10 Sv/Bq + Specific inhalation toxicity : 1.30E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 8.02400E-02 MeV frac = 1.00000E+00 Product nuclide = 77193.82c : IT + + Nuclide 1530 / 1657 : 771940 -- iridium 194 (Ir-194) + + Pointers : 2162954 -1000000 + Primary type : Decay + Nuclide ZAI : 771940 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 193.96526 + Atomic weight ratio (AWR) : 192.29900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.95E+04 seconds (19.3 hours) + Specific ingestion toxicity : 1.30E-09 Sv/Bq + Specific inhalation toxicity : 5.60E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.24680E+00 MeV frac = 1.00000E+00 Product nuclide = 781940 : beta- + + Nuclide 1531 / 1657 : 771941 -- iridium 194m (Ir-194m) + + Pointers : 2165579 -1000000 + Primary type : Decay + Nuclide ZAI : 771941 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 193.96526 + Atomic weight ratio (AWR) : 192.29900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 31.8 milliseconds + Specific ingestion toxicity : 2.10E-09 Sv/Bq + Specific inhalation toxicity : 1.30E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.47072E-01 MeV frac = 1.00000E+00 Product nuclide = 771940 : IT + + Nuclide 1532 / 1657 : 771942 -- iridium 194m (Ir-194m) + + Pointers : 3520084 -1000000 + Primary type : Decay + Nuclide ZAI : 771942 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 193.96526 + Atomic weight ratio (AWR) : 192.29900 + Temperature : 900.0 Kelvin + XS temperature : -1.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.48E+07 seconds (171 days) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is not present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.50600E+00 MeV frac = 1.00000E+00 Product nuclide = 781940 : beta- + + Nuclide 1533 / 1657 : 771950 -- iridium 195 (Ir-195) + + Pointers : 2166384 -1000000 + Primary type : Decay + Nuclide ZAI : 771950 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 194.96586 + Atomic weight ratio (AWR) : 193.29100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.00E+03 seconds (2.5 hours) + Specific ingestion toxicity : 1.00E-10 Sv/Bq + Specific inhalation toxicity : 7.10E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.10700E+00 MeV frac = 1.00000E+00 Product nuclide = 781950 : beta- + + Nuclide 1534 / 1657 : 771951 -- iridium 195m (Ir-195m) + + Pointers : 2167007 -1000000 + Primary type : Decay + Nuclide ZAI : 771951 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 194.96586 + Atomic weight ratio (AWR) : 193.29100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.37E+04 seconds (3.8 hours) + Specific ingestion toxicity : 2.10E-10 Sv/Bq + Specific inhalation toxicity : 1.70E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 1 Q = 1.23000E+00 MeV frac = 6.46000E-01 Product nuclide = 781950 : beta- + 2 RTYP = 1 Q = 9.70700E-01 MeV frac = 3.04000E-01 Product nuclide = 781951 : beta- + 3 RTYP = 3 Q = 1.23000E-01 MeV frac = 5.00000E-02 Product nuclide = 771950 : IT + + Nuclide 1535 / 1657 : 771960 -- iridium 196 (Ir-196) + + Pointers : 2167337 -1000000 + Primary type : Decay + Nuclide ZAI : 771960 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 195.96847 + Atomic weight ratio (AWR) : 194.28500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 52 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.20900E+00 MeV frac = 1.00000E+00 Product nuclide = 781960 : beta- + + Nuclide 1536 / 1657 : 771961 -- iridium 196m (Ir-196m) + + Pointers : 2168296 -1000000 + Primary type : Decay + Nuclide ZAI : 771961 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 195.96847 + Atomic weight ratio (AWR) : 194.28500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.04E+03 seconds (1.4 hours) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 3.41740E+00 MeV frac = 9.97000E-01 Product nuclide = 781960 : beta- + 2 RTYP = 3 Q = 2.10000E-01 MeV frac = 3.00000E-03 Product nuclide = 771960 : IT + + Nuclide 1537 / 1657 : 771970 -- iridium 197 (Ir-197) + + Pointers : 2168553 -1000000 + Primary type : Decay + Nuclide ZAI : 771970 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 196.97008 + Atomic weight ratio (AWR) : 195.27800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.48E+02 seconds (5.8 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.15500E+00 MeV frac = 1.00000E+00 Product nuclide = 781970 : beta- + + Nuclide 1538 / 1657 : 771971 -- iridium 197m (Ir-197m) + + Pointers : 2171010 -1000000 + Primary type : Decay + Nuclide ZAI : 771971 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 196.97008 + Atomic weight ratio (AWR) : 195.27800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.34E+02 seconds (8.9 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.87000E+00 MeV frac = 9.97500E-01 Product nuclide = 781971 : beta- + 2 RTYP = 3 Q = 1.15000E-01 MeV frac = 2.50000E-03 Product nuclide = 771970 : IT + + Nuclide 1539 / 1657 : 781920 -- platinum 192 (Pt-192) + + Pointers : 2171496 -1000000 + Primary type : Decay + Nuclide ZAI : 781920 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 191.96105 + Atomic weight ratio (AWR) : 190.31200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1540 / 1657 : 781930 -- platinum 193 (Pt-193) + + Pointers : 2171602 -1000000 + Primary type : Decay + Nuclide ZAI : 781930 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 192.96265 + Atomic weight ratio (AWR) : 191.30500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.58E+09 seconds (50 years) + Specific ingestion toxicity : 3.10E-11 Sv/Bq + Specific inhalation toxicity : 2.10E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 5.66000E-02 MeV frac = 1.00000E+00 Product nuclide = 77193.82c : EC/beta+ + + Nuclide 1541 / 1657 : 781931 -- platinum 193m (Pt-193m) + + Pointers : 2171945 -1000000 + Primary type : Decay + Nuclide ZAI : 781931 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 192.96265 + Atomic weight ratio (AWR) : 191.30500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.75E+05 seconds (4.34 days) + Specific ingestion toxicity : 4.50E-10 Sv/Bq + Specific inhalation toxicity : 1.20E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.49780E-01 MeV frac = 1.00000E+00 Product nuclide = 781930 : IT + + Nuclide 1542 / 1657 : 781940 -- platinum 194 (Pt-194) + + Pointers : 2172386 -1000000 + Primary type : Decay + Nuclide ZAI : 781940 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 193.96224 + Atomic weight ratio (AWR) : 192.29600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1543 / 1657 : 781950 -- platinum 195 (Pt-195) + + Pointers : 2172492 -1000000 + Primary type : Decay + Nuclide ZAI : 781950 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 194.96485 + Atomic weight ratio (AWR) : 193.29000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1544 / 1657 : 781951 -- platinum 195m (Pt-195m) + + Pointers : 2172598 -1000000 + Primary type : Decay + Nuclide ZAI : 781951 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 194.96485 + Atomic weight ratio (AWR) : 193.29000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.54E+05 seconds (4.1 days) + Specific ingestion toxicity : 6.30E-10 Sv/Bq + Specific inhalation toxicity : 1.80E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 2.59300E-01 MeV frac = 1.00000E+00 Product nuclide = 781950 : IT + + Nuclide 1545 / 1657 : 781960 -- platinum 196 (Pt-196) + + Pointers : 2173403 -1000000 + Primary type : Decay + Nuclide ZAI : 781960 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 195.96545 + Atomic weight ratio (AWR) : 194.28200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1546 / 1657 : 781970 -- platinum 197 (Pt-197) + + Pointers : 2173509 -1000000 + Primary type : Decay + Nuclide ZAI : 781970 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 196.96705 + Atomic weight ratio (AWR) : 195.27500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.16E+04 seconds (19.9 hours) + Specific ingestion toxicity : 4.00E-10 Sv/Bq + Specific inhalation toxicity : 8.50E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.18900E-01 MeV frac = 1.00000E+00 Product nuclide = 79197.82c : beta- + + Nuclide 1547 / 1657 : 781971 -- platinum 197m (Pt-197m) + + Pointers : 2174048 -1000000 + Primary type : Decay + Nuclide ZAI : 781971 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 196.96705 + Atomic weight ratio (AWR) : 195.27500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.72E+03 seconds (1.59 hours) + Specific ingestion toxicity : 8.40E-11 Sv/Bq + Specific inhalation toxicity : 2.40E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 7.09300E-01 MeV frac = 3.30000E-02 Product nuclide = 791971 : beta- + 2 RTYP = 3 Q = 3.99590E-01 MeV frac = 9.67000E-01 Product nuclide = 781970 : IT + + Nuclide 1548 / 1657 : 781980 -- platinum 198 (Pt-198) + + Pointers : 2174576 -1000000 + Primary type : Decay + Nuclide ZAI : 781980 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 197.96765 + Atomic weight ratio (AWR) : 196.26700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1549 / 1657 : 781990 -- platinum 199 (Pt-199) + + Pointers : 2174682 -1000000 + Primary type : Decay + Nuclide ZAI : 781990 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 198.97026 + Atomic weight ratio (AWR) : 197.26100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.85E+03 seconds (30.8 minutes) + Specific ingestion toxicity : 3.90E-11 Sv/Bq + Specific inhalation toxicity : 1.20E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.70300E+00 MeV frac = 1.00000E+00 Product nuclide = 791990 : beta- + + Nuclide 1550 / 1657 : 781991 -- platinum 199m (Pt-199m) + + Pointers : 2177293 -1000000 + Primary type : Decay + Nuclide ZAI : 781991 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 198.97026 + Atomic weight ratio (AWR) : 197.26100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 13.6 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 4.24000E-01 MeV frac = 1.00000E+00 Product nuclide = 781990 : IT + + Nuclide 1551 / 1657 : 791950 -- gold 195 (Au-195) + + Pointers : 2177706 -1000000 + Primary type : Decay + Nuclide ZAI : 791950 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 194.95476 + Atomic weight ratio (AWR) : 193.28000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.61E+07 seconds (186 days) + Specific ingestion toxicity : 2.50E-10 Sv/Bq + Specific inhalation toxicity : 1.70E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 2.26800E-01 MeV frac = 1.00000E+00 Product nuclide = 781950 : EC/beta+ + + Nuclide 1552 / 1657 : 791960 -- gold 196 (Au-196) + + Pointers : 2178315 -1000000 + Primary type : Decay + Nuclide ZAI : 791960 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 195.96646 + Atomic weight ratio (AWR) : 194.28300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.33E+05 seconds (6.17 days) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 6.87000E-01 MeV frac = 7.00000E-02 Product nuclide = 801960 : beta- + 2 RTYP = 2 Q = 1.50700E+00 MeV frac = 9.30000E-01 Product nuclide = 781960 : EC/beta+ + + Nuclide 1553 / 1657 : 791961 -- gold 196m (Au-196m) + + Pointers : 2179837 -1000000 + Primary type : Decay + Nuclide ZAI : 791961 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 195.96646 + Atomic weight ratio (AWR) : 194.28300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.1 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 8.46600E-02 MeV frac = 1.00000E+00 Product nuclide = 791960 : IT + + Nuclide 1554 / 1657 : 791971 -- gold 197m (Au-197m) + + Pointers : 2182195 -1000000 + Primary type : Decay + Nuclide ZAI : 791971 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 196.96705 + Atomic weight ratio (AWR) : 195.27500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.74 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 4.09150E-01 MeV frac = 1.00000E+00 Product nuclide = 79197.82c : IT + + Nuclide 1555 / 1657 : 791980 -- gold 198 (Au-198) + + Pointers : 2182804 -1000000 + Primary type : Decay + Nuclide ZAI : 791980 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 197.96866 + Atomic weight ratio (AWR) : 196.26800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.33E+05 seconds (2.69 days) + Specific ingestion toxicity : 1.00E-09 Sv/Bq + Specific inhalation toxicity : 8.60E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.37280E+00 MeV frac = 1.00000E+00 Product nuclide = 80198.82c : beta- + + Nuclide 1556 / 1657 : 791981 -- gold 198m (Au-198m) + + Pointers : 2183357 -1000000 + Primary type : Decay + Nuclide ZAI : 791981 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 197.96866 + Atomic weight ratio (AWR) : 196.26800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.99E+05 seconds (2.3 days) + Specific ingestion toxicity : 1.30E-09 Sv/Bq + Specific inhalation toxicity : 2.00E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 8.12000E-01 MeV frac = 1.00000E+00 Product nuclide = 791980 : IT + + Nuclide 1557 / 1657 : 791990 -- gold 199 (Au-199) + + Pointers : 2183994 -1000000 + Primary type : Decay + Nuclide ZAI : 791990 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 198.96925 + Atomic weight ratio (AWR) : 197.26000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.71E+05 seconds (3.14 days) + Specific ingestion toxicity : 4.40E-10 Sv/Bq + Specific inhalation toxicity : 7.90E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.52300E-01 MeV frac = 1.00000E+00 Product nuclide = 80199.82c : beta- + + Nuclide 1558 / 1657 : 792000 -- gold 200 (Au-200) + + Pointers : 2184533 -1000000 + Primary type : Decay + Nuclide ZAI : 792000 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 199.97086 + Atomic weight ratio (AWR) : 198.25300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.90E+03 seconds (48.4 minutes) + Specific ingestion toxicity : 6.80E-11 Sv/Bq + Specific inhalation toxicity : 3.50E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.24000E+00 MeV frac = 1.00000E+00 Product nuclide = 80200.82c : beta- + + Nuclide 1559 / 1657 : 792001 -- gold 200m (Au-200m) + + Pointers : 2190966 -1000000 + Primary type : Decay + Nuclide ZAI : 792001 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 199.97086 + Atomic weight ratio (AWR) : 198.25300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.73E+04 seconds (18.7 hours) + Specific ingestion toxicity : 1.10E-09 Sv/Bq + Specific inhalation toxicity : 7.20E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 3.19410E+00 MeV frac = 8.20000E-01 Product nuclide = 80200.82c : beta- + 2 RTYP = 3 Q = 9.60000E-01 MeV frac = 1.80000E-01 Product nuclide = 792000 : IT + + Nuclide 1560 / 1657 : 801960 -- mercury 196 (Hg-196) + + Pointers : 2191223 -1000000 + Primary type : Decay + Nuclide ZAI : 801960 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 195.96545 + Atomic weight ratio (AWR) : 194.28200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.89E+25 seconds (2.5E+18 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 22 Q = 8.20704E-01 MeV frac = 1.00000E+00 Product nuclide = 781960 : EC/beta+ + EC/beta+ + + Nuclide 1561 / 1657 : 801970 -- mercury 197 (Hg-197) + + Pointers : 2191407 -1000000 + Primary type : Decay + Nuclide ZAI : 801970 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 196.96705 + Atomic weight ratio (AWR) : 195.27500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.33E+05 seconds (2.69 days) + Specific ingestion toxicity : 2.30E-10 Sv/Bq + Specific inhalation toxicity : 3.00E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 6.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 79197.82c : EC/beta+ + + Nuclide 1562 / 1657 : 801991 -- mercury 199m (Hg-199m) + + Pointers : 2197474 -1000000 + Primary type : Decay + Nuclide ZAI : 801991 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 198.96824 + Atomic weight ratio (AWR) : 197.25900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.53E+03 seconds (42.1 minutes) + Specific ingestion toxicity : 3.10E-11 Sv/Bq + Specific inhalation toxicity : 3.20E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 5.32500E-01 MeV frac = 1.00000E+00 Product nuclide = 80199.82c : IT + + Nuclide 1563 / 1657 : 802010 -- mercury 201 (Hg-201) + + Pointers : 2202094 -1000000 + Primary type : Decay + Nuclide ZAI : 802010 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 200.97044 + Atomic weight ratio (AWR) : 199.24400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1564 / 1657 : 802060 -- mercury 206 (Hg-206) + + Pointers : 2202200 -1000000 + Primary type : Decay + Nuclide ZAI : 802060 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 205.97746 + Atomic weight ratio (AWR) : 204.20800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.99E+02 seconds (8.32 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.30800E+00 MeV frac = 1.00000E+00 Product nuclide = 812060 : beta- + + Nuclide 1565 / 1657 : 812050 -- thallium 205 (Tl-205) + + Pointers : 2202893 -1000000 + Primary type : Decay + Nuclide ZAI : 812050 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 204.97484 + Atomic weight ratio (AWR) : 203.21400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1566 / 1657 : 812060 -- thallium 206 (Tl-206) + + Pointers : 2202999 -1000000 + Primary type : Decay + Nuclide ZAI : 812060 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 205.97645 + Atomic weight ratio (AWR) : 204.20700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.52E+02 seconds (4.2 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.53240E+00 MeV frac = 1.00000E+00 Product nuclide = 822060 : beta- + + Nuclide 1567 / 1657 : 812070 -- thallium 207 (Tl-207) + + Pointers : 2203482 -1000000 + Primary type : Decay + Nuclide ZAI : 812070 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 206.97704 + Atomic weight ratio (AWR) : 205.19900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.86E+02 seconds (4.77 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.41800E+00 MeV frac = 1.00000E+00 Product nuclide = 822070 : beta- + + Nuclide 1568 / 1657 : 812080 -- thallium 208 (Tl-208) + + Pointers : 2204035 -1000000 + Primary type : Decay + Nuclide ZAI : 812080 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 207.98167 + Atomic weight ratio (AWR) : 206.19500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.83E+02 seconds (3.06 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.99900E+00 MeV frac = 1.00000E+00 Product nuclide = 822080 : beta- + + Nuclide 1569 / 1657 : 812090 -- thallium 209 (Tl-209) + + Pointers : 2206436 -1000000 + Primary type : Decay + Nuclide ZAI : 812090 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 208.98529 + Atomic weight ratio (AWR) : 207.19000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.30E+02 seconds (2.16 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.97600E+00 MeV frac = 1.00000E+00 Product nuclide = 822090 : beta- + + Nuclide 1570 / 1657 : 812100 -- thallium 210 (Tl-210) + + Pointers : 2207745 -1000000 + Primary type : Decay + Nuclide ZAI : 812100 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 209.98992 + Atomic weight ratio (AWR) : 208.18600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.80E+01 seconds (1.3 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.48200E+00 MeV frac = 1.00000E+00 Product nuclide = 822100 : beta- + + Nuclide 1571 / 1657 : 822060 -- lead 206 (Pb-206) + + Pointers : 2208564 -1000000 + Primary type : Decay + Nuclide ZAI : 822060 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 205.97443 + Atomic weight ratio (AWR) : 204.20500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1572 / 1657 : 822070 -- lead 207 (Pb-207) + + Pointers : 2208670 -1000000 + Primary type : Decay + Nuclide ZAI : 822070 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 206.97603 + Atomic weight ratio (AWR) : 205.19800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1573 / 1657 : 822080 -- lead 208 (Pb-208) + + Pointers : 2208776 -1000000 + Primary type : Decay + Nuclide ZAI : 822080 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 207.97663 + Atomic weight ratio (AWR) : 206.19000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1574 / 1657 : 822090 -- lead 209 (Pb-209) + + Pointers : 2208882 -1000000 + Primary type : Decay + Nuclide ZAI : 822090 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 208.98126 + Atomic weight ratio (AWR) : 207.18600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.18E+04 seconds (3.28 hours) + Specific ingestion toxicity : 5.70E-11 Sv/Bq + Specific inhalation toxicity : 6.10E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.44000E-01 MeV frac = 1.00000E+00 Product nuclide = 832090 : beta- + + Nuclide 1575 / 1657 : 822100 -- lead 210 (Pb-210) + + Pointers : 2209099 -1000000 + Primary type : Decay + Nuclide ZAI : 822100 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 209.98387 + Atomic weight ratio (AWR) : 208.18000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.02E+08 seconds (22.2 years) + Specific ingestion toxicity : 6.90E-07 Sv/Bq + Specific inhalation toxicity : 5.60E-06 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 4 Q = 3.79200E+00 MeV frac = 1.90000E-08 Product nuclide = 802060 : alpha + 2 RTYP = 1 Q = 6.35000E-02 MeV frac = 1.00000E+00 Product nuclide = 832100 : beta- + + 1 additional decay branch: + + 1 RTYP = 4 Q = 3.79200E+00 MeV frac = 1.90000E-08 Product nuclide = 2004.82c : alpha + + Nuclide 1576 / 1657 : 822110 -- lead 211 (Pb-211) + + Pointers : 2209602 -1000000 + Primary type : Decay + Nuclide ZAI : 822110 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 210.98850 + Atomic weight ratio (AWR) : 209.17600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.17E+03 seconds (36.1 minutes) + Specific ingestion toxicity : 1.80E-10 Sv/Bq + Specific inhalation toxicity : 1.20E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.36700E+00 MeV frac = 1.00000E+00 Product nuclide = 832110 : beta- + + Nuclide 1577 / 1657 : 822120 -- lead 212 (Pb-212) + + Pointers : 2210897 -1000000 + Primary type : Decay + Nuclide ZAI : 822120 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 211.99212 + Atomic weight ratio (AWR) : 210.17100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.83E+04 seconds (10.6 hours) + Specific ingestion toxicity : 6.00E-09 Sv/Bq + Specific inhalation toxicity : 1.90E-07 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.69900E-01 MeV frac = 1.00000E+00 Product nuclide = 832120 : beta- + + Nuclide 1578 / 1657 : 822140 -- lead 214 (Pb-214) + + Pointers : 2211660 -1000000 + Primary type : Decay + Nuclide ZAI : 822140 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 213.99937 + Atomic weight ratio (AWR) : 212.16100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.61E+03 seconds (26.9 minutes) + Specific ingestion toxicity : 1.40E-10 Sv/Bq + Specific inhalation toxicity : 1.50E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.01900E+00 MeV frac = 1.00000E+00 Product nuclide = 832140 : beta- + + Nuclide 1579 / 1657 : 832090 -- bismuth 209 (Bi-209) + + Pointers : 2213095 -1000000 + Primary type : Decay + Nuclide ZAI : 832090 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 208.98025 + Atomic weight ratio (AWR) : 207.18500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.00E+26 seconds (1.9E+19 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 4 Q = 3.13720E+00 MeV frac = 1.00000E+00 Product nuclide = 812050 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 3.13720E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 1580 / 1657 : 832100 -- bismuth 210 (Bi-210) + + Pointers : 2213352 -1000000 + Primary type : Decay + Nuclide ZAI : 832100 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 209.98387 + Atomic weight ratio (AWR) : 208.18000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.33E+05 seconds (5.01 days) + Specific ingestion toxicity : 1.30E-09 Sv/Bq + Specific inhalation toxicity : 9.30E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 4 Q = 5.03650E+00 MeV frac = 1.40000E-06 Product nuclide = 812060 : alpha + 2 RTYP = 1 Q = 1.16120E+00 MeV frac = 9.99999E-01 Product nuclide = 842100 : beta- + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.03650E+00 MeV frac = 1.40000E-06 Product nuclide = 2004.82c : alpha + + Nuclide 1581 / 1657 : 832110 -- bismuth 211 (Bi-211) + + Pointers : 2213995 -1000000 + Primary type : Decay + Nuclide ZAI : 832110 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 210.98749 + Atomic weight ratio (AWR) : 209.17500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.29E+02 seconds (2.15 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 4 Q = 6.75033E+00 MeV frac = 9.97240E-01 Product nuclide = 812070 : alpha + 2 RTYP = 1 Q = 5.74000E-01 MeV frac = 2.76000E-03 Product nuclide = 842110 : beta- + + 1 additional decay branch: + + 1 RTYP = 4 Q = 6.75033E+00 MeV frac = 9.97240E-01 Product nuclide = 2004.82c : alpha + + Nuclide 1582 / 1657 : 832120 -- bismuth 212 (Bi-212) + + Pointers : 2214568 -1000000 + Primary type : Decay + Nuclide ZAI : 832120 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 211.99112 + Atomic weight ratio (AWR) : 210.17000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.63E+03 seconds (1.01 hours) + Specific ingestion toxicity : 2.60E-10 Sv/Bq + Specific inhalation toxicity : 3.10E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 4 Q = 6.20726E+00 MeV frac = 3.59300E-01 Product nuclide = 812080 : alpha + 2 RTYP = 1 Q = 2.25210E+00 MeV frac = 6.40700E-01 Product nuclide = 842120 : beta- + + 1 additional decay branch: + + 1 RTYP = 4 Q = 6.20726E+00 MeV frac = 3.59300E-01 Product nuclide = 2004.82c : alpha + + Nuclide 1583 / 1657 : 832130 -- bismuth 213 (Bi-213) + + Pointers : 2216793 -1000000 + Primary type : Decay + Nuclide ZAI : 832130 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 212.99474 + Atomic weight ratio (AWR) : 211.16500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.74E+03 seconds (45.6 minutes) + Specific ingestion toxicity : 2.00E-10 Sv/Bq + Specific inhalation toxicity : 3.00E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 4 Q = 5.98300E+00 MeV frac = 2.09000E-02 Product nuclide = 812090 : alpha + 2 RTYP = 1 Q = 1.42300E+00 MeV frac = 9.79100E-01 Product nuclide = 842130 : beta- + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.98300E+00 MeV frac = 2.09000E-02 Product nuclide = 2004.82c : alpha + + Nuclide 1584 / 1657 : 832140 -- bismuth 214 (Bi-214) + + Pointers : 2217996 -1000000 + Primary type : Decay + Nuclide ZAI : 832140 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 213.99836 + Atomic weight ratio (AWR) : 212.16000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.19E+03 seconds (19.8 minutes) + Specific ingestion toxicity : 1.10E-10 Sv/Bq + Specific inhalation toxicity : 1.40E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 4 Q = 5.62100E+00 MeV frac = 2.10000E-04 Product nuclide = 812100 : alpha + 2 RTYP = 1 Q = 3.27000E+00 MeV frac = 9.99790E-01 Product nuclide = 842140 : beta- + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.62100E+00 MeV frac = 2.10000E-04 Product nuclide = 2004.82c : alpha + + Nuclide 1585 / 1657 : 832150 -- bismuth 215 (Bi-215) + + Pointers : 2226605 -1000000 + Primary type : Decay + Nuclide ZAI : 832150 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 215.00198 + Atomic weight ratio (AWR) : 213.15500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.56E+02 seconds (7.6 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.18900E+00 MeV frac = 1.00000E+00 Product nuclide = 842150 : beta- + + Nuclide 1586 / 1657 : 842100 -- polonium 210 (Po-210) + + Pointers : 2227704 -1000000 + Primary type : Decay + Nuclide ZAI : 842100 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 209.98286 + Atomic weight ratio (AWR) : 208.17900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.20E+07 seconds (138 days) + Specific ingestion toxicity : 1.20E-06 Sv/Bq + Specific inhalation toxicity : 4.30E-06 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 4 Q = 5.40745E+00 MeV frac = 1.00000E+00 Product nuclide = 822060 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.40745E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 1587 / 1657 : 842110 -- polonium 211 (Po-211) + + Pointers : 2228190 -1000000 + Primary type : Decay + Nuclide ZAI : 842110 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 210.98649 + Atomic weight ratio (AWR) : 209.17400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.516 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 4 Q = 7.59450E+00 MeV frac = 1.00000E+00 Product nuclide = 822070 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 7.59450E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 1588 / 1657 : 842120 -- polonium 212 (Po-212) + + Pointers : 2228830 -1000000 + Primary type : Decay + Nuclide ZAI : 842120 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 211.98910 + Atomic weight ratio (AWR) : 210.16800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.3 microseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 4 Q = 8.95412E+00 MeV frac = 1.00000E+00 Product nuclide = 822080 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 8.95412E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 1589 / 1657 : 842130 -- polonium 213 (Po-213) + + Pointers : 2229120 -1000000 + Primary type : Decay + Nuclide ZAI : 842130 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 212.99272 + Atomic weight ratio (AWR) : 211.16300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.7 microseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 4 Q = 8.53610E+00 MeV frac = 1.00000E+00 Product nuclide = 822090 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 8.53610E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 1590 / 1657 : 842140 -- polonium 214 (Po-214) + + Pointers : 2229606 -1000000 + Primary type : Decay + Nuclide ZAI : 842140 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 213.99533 + Atomic weight ratio (AWR) : 212.15700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.162 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 4 Q = 7.83346E+00 MeV frac = 1.00000E+00 Product nuclide = 822100 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 7.83346E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 1591 / 1657 : 842150 -- polonium 215 (Po-215) + + Pointers : 2230176 -1000000 + Primary type : Decay + Nuclide ZAI : 842150 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 214.99896 + Atomic weight ratio (AWR) : 213.15200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.78 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 4 Q = 7.52630E+00 MeV frac = 9.99998E-01 Product nuclide = 822110 : alpha + 2 RTYP = 1 Q = 7.15000E-01 MeV frac = 2.30000E-06 Product nuclide = 852150 : beta- + + 1 additional decay branch: + + 1 RTYP = 4 Q = 7.52630E+00 MeV frac = 9.99998E-01 Product nuclide = 2004.82c : alpha + + Nuclide 1592 / 1657 : 842160 -- polonium 216 (Po-216) + + Pointers : 2230819 -1000000 + Primary type : Decay + Nuclide ZAI : 842160 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 216.00157 + Atomic weight ratio (AWR) : 214.14600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.148 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 4 Q = 6.90630E+00 MeV frac = 1.00000E+00 Product nuclide = 822120 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 6.90630E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 1593 / 1657 : 842180 -- polonium 218 (Po-218) + + Pointers : 2231305 -1000000 + Primary type : Decay + Nuclide ZAI : 842180 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 218.00881 + Atomic weight ratio (AWR) : 216.13600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.84E+02 seconds (3.07 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 4 Q = 6.11468E+00 MeV frac = 9.99780E-01 Product nuclide = 822140 : alpha + 2 RTYP = 1 Q = 2.60000E-01 MeV frac = 2.20000E-04 Product nuclide = 852180 : beta- + + 1 additional decay branch: + + 1 RTYP = 4 Q = 6.11468E+00 MeV frac = 9.99780E-01 Product nuclide = 2004.82c : alpha + + Nuclide 1594 / 1657 : 852150 -- astatine 215 (At-215) + + Pointers : 2231738 -1000000 + Primary type : Decay + Nuclide ZAI : 852150 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 214.99896 + Atomic weight ratio (AWR) : 213.15200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 100 microseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 4 Q = 8.17800E+00 MeV frac = 1.00000E+00 Product nuclide = 832110 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 8.17800E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 1595 / 1657 : 852170 -- astatine 217 (At-217) + + Pointers : 2232224 -1000000 + Primary type : Decay + Nuclide ZAI : 852170 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 217.00519 + Atomic weight ratio (AWR) : 215.14100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 32.3 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 4 Q = 7.20130E+00 MeV frac = 9.99933E-01 Product nuclide = 832130 : alpha + 2 RTYP = 1 Q = 7.37000E-01 MeV frac = 6.70000E-05 Product nuclide = 862170 : beta- + + 1 additional decay branch: + + 1 RTYP = 4 Q = 7.20130E+00 MeV frac = 9.99933E-01 Product nuclide = 2004.82c : alpha + + Nuclide 1596 / 1657 : 852180 -- astatine 218 (At-218) + + Pointers : 2232881 -1000000 + Primary type : Decay + Nuclide ZAI : 852180 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 218.00881 + Atomic weight ratio (AWR) : 216.13600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.4 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 4 Q = 6.87400E+00 MeV frac = 9.99000E-01 Product nuclide = 832140 : alpha + 2 RTYP = 1 Q = 2.88100E+00 MeV frac = 1.00000E-03 Product nuclide = 862180 : beta- + + 1 additional decay branch: + + 1 RTYP = 4 Q = 6.87400E+00 MeV frac = 9.99000E-01 Product nuclide = 2004.82c : alpha + + Nuclide 1597 / 1657 : 852190 -- astatine 219 (At-219) + + Pointers : 2233300 -1000000 + Primary type : Decay + Nuclide ZAI : 852190 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 219.01142 + Atomic weight ratio (AWR) : 217.13000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 56 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 4 Q = 6.32400E+00 MeV frac = 9.70000E-01 Product nuclide = 832150 : alpha + 2 RTYP = 1 Q = 1.56600E+00 MeV frac = 3.00000E-02 Product nuclide = 862190 : beta- + + 1 additional decay branch: + + 1 RTYP = 4 Q = 6.32400E+00 MeV frac = 9.70000E-01 Product nuclide = 2004.82c : alpha + + Nuclide 1598 / 1657 : 862160 -- radon 216 (Rn-216) + + Pointers : 2233691 -1000000 + Primary type : Decay + Nuclide ZAI : 862160 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 216.00056 + Atomic weight ratio (AWR) : 214.14500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 45 microseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 4 Q = 8.20050E+00 MeV frac = 1.00000E+00 Product nuclide = 842120 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 8.20050E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 1599 / 1657 : 862170 -- radon 217 (Rn-217) + + Pointers : 2233948 -1000000 + Primary type : Decay + Nuclide ZAI : 862170 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 217.00418 + Atomic weight ratio (AWR) : 215.14000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.54 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 4 Q = 7.88700E+00 MeV frac = 1.00000E+00 Product nuclide = 842130 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 7.88700E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 1600 / 1657 : 862180 -- radon 218 (Rn-218) + + Pointers : 2234238 -1000000 + Primary type : Decay + Nuclide ZAI : 862180 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 218.00579 + Atomic weight ratio (AWR) : 216.13300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 36 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 4 Q = 7.26250E+00 MeV frac = 1.00000E+00 Product nuclide = 842140 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 7.26250E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 1601 / 1657 : 862190 -- radon 219 (Rn-219) + + Pointers : 2234724 -1000000 + Primary type : Decay + Nuclide ZAI : 862190 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 219.00941 + Atomic weight ratio (AWR) : 217.12800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.98 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 4 Q = 6.94610E+00 MeV frac = 1.00000E+00 Product nuclide = 842150 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 6.94610E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 1602 / 1657 : 862200 -- radon 220 (Rn-220) + + Pointers : 2236162 -1000000 + Primary type : Decay + Nuclide ZAI : 862200 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 220.01101 + Atomic weight ratio (AWR) : 218.12100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 55.8 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 4 Q = 6.40467E+00 MeV frac = 1.00000E+00 Product nuclide = 842160 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 6.40467E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 1603 / 1657 : 862220 -- radon 222 (Rn-222) + + Pointers : 2236648 -1000000 + Primary type : Decay + Nuclide ZAI : 862220 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 222.01725 + Atomic weight ratio (AWR) : 220.11000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.30E+05 seconds (3.82 days) + Specific ingestion toxicity : 8.20E-08 Sv/Bq + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 4 Q = 5.59030E+00 MeV frac = 1.00000E+00 Product nuclide = 842180 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.59030E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 1604 / 1657 : 872210 -- francium 221 (Fr-221) + + Pointers : 2237148 -1000000 + Primary type : Decay + Nuclide ZAI : 872210 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 221.01463 + Atomic weight ratio (AWR) : 219.11600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.87E+02 seconds (4.79 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 4 Q = 6.45780E+00 MeV frac = 9.99952E-01 Product nuclide = 852170 : alpha + 2 RTYP = 1 Q = 3.14000E-01 MeV frac = 4.80000E-05 Product nuclide = 882210 : beta- + + 1 additional decay branch: + + 1 RTYP = 4 Q = 6.45780E+00 MeV frac = 9.99952E-01 Product nuclide = 2004.82c : alpha + + Nuclide 1605 / 1657 : 872220 -- francium 222 (Fr-222) + + Pointers : 2238911 -1000000 + Primary type : Decay + Nuclide ZAI : 872220 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 222.01725 + Atomic weight ratio (AWR) : 220.11000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.52E+02 seconds (14.2 minutes) + Specific ingestion toxicity : 7.20E-10 Sv/Bq + Specific inhalation toxicity : 1.40E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.03200E+00 MeV frac = 1.00000E+00 Product nuclide = 882220 : beta- + + Nuclide 1606 / 1657 : 872230 -- francium 223 (Fr-223) + + Pointers : 2240948 -1000000 + Primary type : Decay + Nuclide ZAI : 872230 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 223.01986 + Atomic weight ratio (AWR) : 221.10400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.32E+03 seconds (22 minutes) + Specific ingestion toxicity : 2.40E-09 Sv/Bq + Specific inhalation toxicity : 8.90E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 4 Q = 5.56200E+00 MeV frac = 2.00000E-04 Product nuclide = 852190 : alpha + 2 RTYP = 1 Q = 1.14920E+00 MeV frac = 9.99800E-01 Product nuclide = 882230 : beta- + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.56200E+00 MeV frac = 2.00000E-04 Product nuclide = 2004.82c : alpha + + Nuclide 1607 / 1657 : 872240 -- francium 224 (Fr-224) + + Pointers : 2246001 -1000000 + Primary type : Decay + Nuclide ZAI : 872240 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 224.02348 + Atomic weight ratio (AWR) : 222.09900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.00E+02 seconds (3.33 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.83000E+00 MeV frac = 1.00000E+00 Product nuclide = 882240 : beta- + + Nuclide 1608 / 1657 : 882200 -- radium 220 (Ra-220) + + Pointers : 2249298 -1000000 + Primary type : Decay + Nuclide ZAI : 882200 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 220.01101 + Atomic weight ratio (AWR) : 218.12100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 18 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 4 Q = 7.59200E+00 MeV frac = 1.00000E+00 Product nuclide = 862160 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 7.59200E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 1609 / 1657 : 882210 -- radium 221 (Ra-221) + + Pointers : 2249630 -1000000 + Primary type : Decay + Nuclide ZAI : 882210 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 221.01362 + Atomic weight ratio (AWR) : 219.11500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 28 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 4 Q = 6.88010E+00 MeV frac = 1.00000E+00 Product nuclide = 862170 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 6.88010E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 1610 / 1657 : 882220 -- radium 222 (Ra-222) + + Pointers : 2249887 -1000000 + Primary type : Decay + Nuclide ZAI : 882220 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 222.01523 + Atomic weight ratio (AWR) : 220.10800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 36.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 4 Q = 6.67900E+00 MeV frac = 1.00000E+00 Product nuclide = 862180 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 6.67900E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 1611 / 1657 : 882230 -- radium 223 (Ra-223) + + Pointers : 2250625 -1000000 + Primary type : Decay + Nuclide ZAI : 882230 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 223.01885 + Atomic weight ratio (AWR) : 221.10300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.88E+05 seconds (11.4 days) + Specific ingestion toxicity : 1.00E-07 Sv/Bq + Specific inhalation toxicity : 8.70E-06 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 4 Q = 5.97899E+00 MeV frac = 1.00000E+00 Product nuclide = 862190 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.97899E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 1612 / 1657 : 882240 -- radium 224 (Ra-224) + + Pointers : 2253841 -1000000 + Primary type : Decay + Nuclide ZAI : 882240 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 224.02045 + Atomic weight ratio (AWR) : 222.09600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.14E+05 seconds (3.63 days) + Specific ingestion toxicity : 6.50E-08 Sv/Bq + Specific inhalation toxicity : 3.40E-06 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 4 Q = 5.78885E+00 MeV frac = 1.00000E+00 Product nuclide = 862200 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.78885E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 1613 / 1657 : 882250 -- radium 225 (Ra-225) + + Pointers : 2254649 -1000000 + Primary type : Decay + Nuclide ZAI : 882250 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 225.02408 + Atomic weight ratio (AWR) : 223.09100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.28E+06 seconds (14.8 days) + Specific ingestion toxicity : 9.90E-08 Sv/Bq + Specific inhalation toxicity : 7.70E-06 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.56000E-01 MeV frac = 1.00000E+00 Product nuclide = 892250 : beta- + + Nuclide 1614 / 1657 : 882260 -- radium 226 (Ra-226) + + Pointers : 2255006 -1000000 + Primary type : Decay + Nuclide ZAI : 882260 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 226.02568 + Atomic weight ratio (AWR) : 224.08400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.05E+10 seconds (1,601 years) + Specific ingestion toxicity : 2.80E-07 Sv/Bq + Specific inhalation toxicity : 9.50E-06 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 4 Q = 4.87062E+00 MeV frac = 1.00000E+00 Product nuclide = 862220 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 4.87062E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 1615 / 1657 : 882280 -- radium 228 (Ra-228) + + Pointers : 2255814 -1000000 + Primary type : Decay + Nuclide ZAI : 882280 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 228.03091 + Atomic weight ratio (AWR) : 226.07200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.81E+08 seconds (5.75 years) + Specific ingestion toxicity : 6.90E-07 Sv/Bq + Specific inhalation toxicity : 1.60E-05 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.58000E-02 MeV frac = 1.00000E+00 Product nuclide = 892280 : beta- + + Nuclide 1616 / 1657 : 892250 -- actinium 225 (Ac-225) + + Pointers : 2256339 -1000000 + Primary type : Decay + Nuclide ZAI : 892250 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 225.02307 + Atomic weight ratio (AWR) : 223.09000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.64E+05 seconds (10 days) + Specific ingestion toxicity : 2.40E-08 Sv/Bq + Specific inhalation toxicity : 8.50E-06 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 4 Q = 5.93510E+00 MeV frac = 1.00000E+00 Product nuclide = 872210 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.93510E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 1617 / 1657 : 892260 -- actinium 226 (Ac-226) + + Pointers : 2263713 -1000000 + Primary type : Decay + Nuclide ZAI : 892260 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 226.02568 + Atomic weight ratio (AWR) : 224.08400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.06E+05 seconds (1.22 days) + Specific ingestion toxicity : 1.00E-08 Sv/Bq + Specific inhalation toxicity : 1.30E-06 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 1 Q = 1.11300E+00 MeV frac = 8.29950E-01 Product nuclide = 902260 : beta- + 2 RTYP = 2 Q = 6.40902E-01 MeV frac = 1.69990E-01 Product nuclide = 882260 : EC/beta+ + 3 RTYP = 4 Q = 5.53610E+00 MeV frac = 5.99964E-05 Product nuclide = 872220 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.53610E+00 MeV frac = 5.99964E-05 Product nuclide = 2004.82c : alpha + + Nuclide 1618 / 1657 : 892270 -- actinium 227 (Ac-227) + + Pointers : 2264116 -1000000 + Primary type : Decay + Nuclide ZAI : 892270 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 227.02728 + Atomic weight ratio (AWR) : 225.07700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.87E+08 seconds (21.8 years) + Specific ingestion toxicity : 1.10E-06 Sv/Bq + Specific inhalation toxicity : 5.50E-04 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 4 Q = 5.04219E+00 MeV frac = 1.38000E-02 Product nuclide = 872230 : alpha + 2 RTYP = 1 Q = 4.48000E-02 MeV frac = 9.86200E-01 Product nuclide = 90227.82c : beta- + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.04219E+00 MeV frac = 1.38000E-02 Product nuclide = 2004.82c : alpha + + Nuclide 1619 / 1657 : 892280 -- actinium 228 (Ac-228) + + Pointers : 2267993 -1000000 + Primary type : Decay + Nuclide ZAI : 892280 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 228.03091 + Atomic weight ratio (AWR) : 226.07200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.21E+04 seconds (6.15 hours) + Specific ingestion toxicity : 4.30E-10 Sv/Bq + Specific inhalation toxicity : 2.50E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 4 Q = 4.81000E+00 MeV frac = 5.50000E-08 Product nuclide = 872240 : alpha + 2 RTYP = 1 Q = 2.12380E+00 MeV frac = 1.00000E+00 Product nuclide = 90228.82c : beta- + + 1 additional decay branch: + + 1 RTYP = 4 Q = 4.81000E+00 MeV frac = 5.50000E-08 Product nuclide = 2004.82c : alpha + + Nuclide 1620 / 1657 : 902240 -- thorium 224 (Th-224) + + Pointers : 2282370 -1000000 + Primary type : Decay + Nuclide ZAI : 902240 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 224.02146 + Atomic weight ratio (AWR) : 222.09700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.05 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 4 Q = 7.29800E+00 MeV frac = 1.00000E+00 Product nuclide = 882200 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 7.29800E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 1621 / 1657 : 902250 -- thorium 225 (Th-225) + + Pointers : 2283094 -1000000 + Primary type : Decay + Nuclide ZAI : 902250 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 225.02408 + Atomic weight ratio (AWR) : 223.09100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.23E+02 seconds (8.72 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 4 Q = 6.92110E+00 MeV frac = 9.00000E-01 Product nuclide = 882210 : alpha + 2 RTYP = 2 Q = 6.72001E-01 MeV frac = 1.00000E-01 Product nuclide = 892250 : EC/beta+ + + 1 additional decay branch: + + 1 RTYP = 4 Q = 6.92110E+00 MeV frac = 9.00000E-01 Product nuclide = 2004.82c : alpha + + Nuclide 1622 / 1657 : 902260 -- thorium 226 (Th-226) + + Pointers : 2283424 -1000000 + Primary type : Decay + Nuclide ZAI : 902260 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 226.02467 + Atomic weight ratio (AWR) : 224.08300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.83E+03 seconds (30.6 minutes) + Specific ingestion toxicity : 3.50E-10 Sv/Bq + Specific inhalation toxicity : 6.10E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 4 Q = 6.45090E+00 MeV frac = 1.00000E+00 Product nuclide = 882220 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 6.45090E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 1623 / 1657 : 902310 -- thorium 231 (Th-231) + + Pointers : 2412221 -1000000 + Primary type : Decay + Nuclide ZAI : 902310 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 231.03673 + Atomic weight ratio (AWR) : 229.05200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.19E+04 seconds (1.06 days) + Specific ingestion toxicity : 3.40E-10 Sv/Bq + Specific inhalation toxicity : 3.30E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.91600E-01 MeV frac = 1.00000E+00 Product nuclide = 91231.82c : beta- + + Nuclide 1624 / 1657 : 902320 -- thorium 232 (Th-232) + + Pointers : 2415574 -1000000 + Primary type : Decay + Nuclide ZAI : 902320 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 232.03833 + Atomic weight ratio (AWR) : 230.04500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.43E+17 seconds (14.1 billion years) + Specific ingestion toxicity : 2.30E-07 Sv/Bq + Specific inhalation toxicity : 1.10E-04 Sv/Bq + Spontaneous fission nubar : 1.50000 + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 4 Q = 4.08100E+00 MeV frac = 1.00000E+00 Product nuclide = 882280 : alpha + 2 RTYP = 6 Q = 1.69400E+02 MeV frac = 1.40000E-11 SF without yield : spontaneous fission + + 1 additional decay branch: + + 1 RTYP = 4 Q = 4.08100E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 1625 / 1657 : 902340 -- thorium 234 (Th-234) + + Pointers : 2416432 -1000000 + Primary type : Decay + Nuclide ZAI : 902340 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 234.04356 + Atomic weight ratio (AWR) : 232.03300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.08E+06 seconds (24.1 days) + Specific ingestion toxicity : 3.40E-09 Sv/Bq + Specific inhalation toxicity : 7.70E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.88000E-01 MeV frac = 1.00000E+00 Product nuclide = 912341 : beta- + + Nuclide 1626 / 1657 : 912290 -- protactinium 229 (Pa-229) + + Pointers : 2417307 -1000000 + Primary type : Decay + Nuclide ZAI : 912290 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 229.03251 + Atomic weight ratio (AWR) : 227.06500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.30E+05 seconds (1.5 days) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 4 Q = 5.83500E+00 MeV frac = 4.80000E-03 Product nuclide = 892250 : alpha + 2 RTYP = 2 Q = 3.11000E-01 MeV frac = 9.95200E-01 Product nuclide = 90229.82c : EC/beta+ + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.83500E+00 MeV frac = 4.80000E-03 Product nuclide = 2004.82c : alpha + + Nuclide 1627 / 1657 : 912300 -- protactinium 230 (Pa-230) + + Pointers : 2420106 -1000000 + Primary type : Decay + Nuclide ZAI : 912300 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 230.03412 + Atomic weight ratio (AWR) : 228.05800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.50E+06 seconds (17.4 days) + Specific ingestion toxicity : 9.20E-10 Sv/Bq + Specific inhalation toxicity : 7.60E-07 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 2 Q = 1.31100E+00 MeV frac = 9.15971E-01 Product nuclide = 90230.82c : EC/beta+ + 2 RTYP = 1 Q = 5.60001E-01 MeV frac = 8.39973E-02 Product nuclide = 922300 : beta- + 3 RTYP = 4 Q = 5.44010E+00 MeV frac = 3.19990E-05 Product nuclide = 892260 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.44010E+00 MeV frac = 3.19990E-05 Product nuclide = 2004.82c : alpha + + Nuclide 1628 / 1657 : 912340 -- protactinium 234 (Pa-234) + + Pointers : 2502799 -1000000 + Primary type : Decay + Nuclide ZAI : 912340 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 234.04356 + Atomic weight ratio (AWR) : 232.03300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.41E+04 seconds (6.7 hours) + Specific ingestion toxicity : 5.10E-10 Sv/Bq + Specific inhalation toxicity : 4.00E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.19500E+00 MeV frac = 1.00000E+00 Product nuclide = 92234.82c : beta- + + Nuclide 1629 / 1657 : 912341 -- protactinium 234m (Pa-234m) + + Pointers : 2520600 -1000000 + Primary type : Decay + Nuclide ZAI : 912341 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 234.04356 + Atomic weight ratio (AWR) : 232.03300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.95E+01 seconds (1.16 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 8.40000E-02 MeV frac = 1.50000E-03 Product nuclide = 912340 : IT + 2 RTYP = 1 Q = 2.27910E+00 MeV frac = 9.98500E-01 Product nuclide = 92234.82c : beta- + + Nuclide 1630 / 1657 : 922300 -- uranium 230 (U-230) + + Pointers : 2526812 -1000000 + Primary type : Decay + Nuclide ZAI : 922300 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 230.03412 + Atomic weight ratio (AWR) : 228.05800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.80E+06 seconds (20.8 days) + Specific ingestion toxicity : 5.60E-08 Sv/Bq + Specific inhalation toxicity : 1.60E-05 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 4 Q = 5.99270E+00 MeV frac = 1.00000E+00 Product nuclide = 902260 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.99270E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 1631 / 1657 : 922310 -- uranium 231 (U-231) + + Pointers : 2527718 -1000000 + Primary type : Decay + Nuclide ZAI : 922310 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 231.03673 + Atomic weight ratio (AWR) : 229.05200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.63E+05 seconds (4.2 days) + Specific ingestion toxicity : 2.80E-10 Sv/Bq + Specific inhalation toxicity : 5.20E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 3.81302E-01 MeV frac = 9.99960E-01 Product nuclide = 91231.82c : EC/beta+ + 2 RTYP = 4 Q = 5.57590E+00 MeV frac = 4.00000E-05 Product nuclide = 90227.82c : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.57590E+00 MeV frac = 4.00000E-05 Product nuclide = 2004.82c : alpha + + Nuclide 1632 / 1657 : 922351 -- uranium 235m (U-235m) + + Pointers : 2639217 -1000000 + Primary type : Decay + Nuclide ZAI : 922351 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 235.04415 + Atomic weight ratio (AWR) : 233.02500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.56E+03 seconds (26 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 7.68000E-05 MeV frac = 1.00000E+00 Product nuclide = 92235.82c : IT + + Nuclide 1633 / 1657 : 922390 -- uranium 239 (U-239) + + Pointers : 2700878 -1000000 + Primary type : Decay + Nuclide ZAI : 922390 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 239.05461 + Atomic weight ratio (AWR) : 237.00100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.41E+03 seconds (23.5 minutes) + Specific ingestion toxicity : 2.70E-11 Sv/Bq + Specific inhalation toxicity : 2.40E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.26150E+00 MeV frac = 1.00000E+00 Product nuclide = 93239.82c : beta- + + Nuclide 1634 / 1657 : 922400 -- uranium 240 (U-240) + + Pointers : 2705071 -1000000 + Primary type : Decay + Nuclide ZAI : 922400 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 240.05621 + Atomic weight ratio (AWR) : 237.99400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.08E+04 seconds (14.1 hours) + Specific ingestion toxicity : 1.10E-09 Sv/Bq + Specific inhalation toxicity : 5.80E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.90000E-01 MeV frac = 1.00000E+00 Product nuclide = 932400 : beta- + + Nuclide 1635 / 1657 : 932330 -- neptunium 233 (Np-233) + + Pointers : 2705456 -1000000 + Primary type : Decay + Nuclide ZAI : 932330 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 233.04095 + Atomic weight ratio (AWR) : 231.03900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.17E+03 seconds (36.2 minutes) + Specific ingestion toxicity : 2.20E-12 Sv/Bq + Specific inhalation toxicity : 1.70E-12 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 1.03000E+00 MeV frac = 1.00000E+00 Product nuclide = 92233.82c : EC/beta+ + + Nuclide 1636 / 1657 : 932340 -- neptunium 234 (Np-234) + + Pointers : 2706051 -1000000 + Primary type : Decay + Nuclide ZAI : 932340 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 234.04255 + Atomic weight ratio (AWR) : 232.03200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.80E+05 seconds (4.4 days) + Specific ingestion toxicity : 8.10E-10 Sv/Bq + Specific inhalation toxicity : 5.50E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 1.81000E+00 MeV frac = 1.00000E+00 Product nuclide = 92234.82c : EC/beta+ + + Nuclide 1637 / 1657 : 932361 -- neptunium 236m (Np-236m) + + Pointers : 2755876 -1000000 + Primary type : Decay + Nuclide ZAI : 932361 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 236.04677 + Atomic weight ratio (AWR) : 234.01900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.10E+04 seconds (22.5 hours) + Specific ingestion toxicity : 1.90E-10 Sv/Bq + Specific inhalation toxicity : 9.00E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 9.90000E-01 MeV frac = 5.30000E-01 Product nuclide = 92236.82c : EC/beta+ + 2 RTYP = 1 Q = 5.40000E-01 MeV frac = 4.70000E-01 Product nuclide = 94236.82c : beta- + + Nuclide 1638 / 1657 : 932400 -- neptunium 240 (Np-240) + + Pointers : 2819051 -1000000 + Primary type : Decay + Nuclide ZAI : 932400 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 240.05621 + Atomic weight ratio (AWR) : 237.99400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.90E+03 seconds (1.08 hours) + Specific ingestion toxicity : 8.20E-11 Sv/Bq + Specific inhalation toxicity : 9.00E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.19900E+00 MeV frac = 1.00000E+00 Product nuclide = 94240.82c : beta- + + Nuclide 1639 / 1657 : 932401 -- neptunium 240m (Np-240m) + + Pointers : 2820304 -1000000 + Primary type : Decay + Nuclide ZAI : 932401 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 240.05621 + Atomic weight ratio (AWR) : 237.99400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.44E+02 seconds (7.4 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 2.21900E+00 MeV frac = 9.98900E-01 Product nuclide = 94240.82c : beta- + 2 RTYP = 3 Q = 2.00000E-02 MeV frac = 1.10000E-03 Product nuclide = 932400 : IT + + Nuclide 1640 / 1657 : 942340 -- plutonium 234 (Pu-234) + + Pointers : 2823002 -1000000 + Primary type : Decay + Nuclide ZAI : 942340 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 234.04356 + Atomic weight ratio (AWR) : 232.03300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.17E+04 seconds (8.8 hours) + Specific ingestion toxicity : 1.60E-10 Sv/Bq + Specific inhalation toxicity : 2.40E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 3.94001E-01 MeV frac = 9.40000E-01 Product nuclide = 932340 : EC/beta+ + 2 RTYP = 4 Q = 6.31010E+00 MeV frac = 6.00000E-02 Product nuclide = 922300 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 6.31010E+00 MeV frac = 6.00000E-02 Product nuclide = 2004.82c : alpha + + Nuclide 1641 / 1657 : 942350 -- plutonium 235 (Pu-235) + + Pointers : 2823332 -1000000 + Primary type : Decay + Nuclide ZAI : 942350 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 235.04516 + Atomic weight ratio (AWR) : 233.02600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.52E+03 seconds (25.3 minutes) + Specific ingestion toxicity : 2.10E-12 Sv/Bq + Specific inhalation toxicity : 1.50E-12 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 1.13930E+00 MeV frac = 9.99972E-01 Product nuclide = 93235.82c : EC/beta+ + 2 RTYP = 4 Q = 5.95210E+00 MeV frac = 2.80000E-05 Product nuclide = 922310 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.95210E+00 MeV frac = 2.80000E-05 Product nuclide = 2004.82c : alpha + + Nuclide 1642 / 1657 : 942371 -- plutonium 237m (Pu-237m) + + Pointers : 2872143 -1000000 + Primary type : Decay + Nuclide ZAI : 942371 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 237.04837 + Atomic weight ratio (AWR) : 235.01200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.18 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.45544E-01 MeV frac = 1.00000E+00 Product nuclide = 94237.82c : IT + + Nuclide 1643 / 1657 : 942450 -- plutonium 245 (Pu-245) + + Pointers : 3025843 -1000000 + Primary type : Decay + Nuclide ZAI : 942450 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 245.06827 + Atomic weight ratio (AWR) : 242.96300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.78E+04 seconds (10.5 hours) + Specific ingestion toxicity : 7.20E-10 Sv/Bq + Specific inhalation toxicity : 4.30E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.28400E+00 MeV frac = 1.00000E+00 Product nuclide = 952450 : beta- + + Nuclide 1644 / 1657 : 942460 -- plutonium 246 (Pu-246) + + Pointers : 3028958 -1000000 + Primary type : Decay + Nuclide ZAI : 942460 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 246.06987 + Atomic weight ratio (AWR) : 243.95600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.37E+05 seconds (10.8 days) + Specific ingestion toxicity : 3.30E-09 Sv/Bq + Specific inhalation toxicity : 8.00E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.96000E-01 MeV frac = 1.00000E+00 Product nuclide = 952461 : beta- + + Nuclide 1645 / 1657 : 952380 -- americium 238 (Am-238) + + Pointers : 3029931 -1000000 + Primary type : Decay + Nuclide ZAI : 952380 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 238.05199 + Atomic weight ratio (AWR) : 236.00700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.88E+03 seconds (1.63 hours) + Specific ingestion toxicity : 3.20E-11 Sv/Bq + Specific inhalation toxicity : 1.90E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 4 Q = 6.04000E+00 MeV frac = 1.00000E-06 Product nuclide = 932340 : alpha + 2 RTYP = 2 Q = 2.25800E+00 MeV frac = 1.00000E+00 Product nuclide = 94238.82c : EC/beta+ + + 1 additional decay branch: + + 1 RTYP = 4 Q = 6.04000E+00 MeV frac = 1.00000E-06 Product nuclide = 2004.82c : alpha + + Nuclide 1646 / 1657 : 952390 -- americium 239 (Am-239) + + Pointers : 3032268 -1000000 + Primary type : Decay + Nuclide ZAI : 952390 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 239.05259 + Atomic weight ratio (AWR) : 236.99900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.28E+04 seconds (11.9 hours) + Specific ingestion toxicity : 2.40E-10 Sv/Bq + Specific inhalation toxicity : 2.40E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 8.02101E-01 MeV frac = 9.99900E-01 Product nuclide = 94239.82c : EC/beta+ + 2 RTYP = 4 Q = 5.92240E+00 MeV frac = 1.00000E-04 Product nuclide = 93235.82c : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.92240E+00 MeV frac = 1.00000E-04 Product nuclide = 2004.82c : alpha + + Nuclide 1647 / 1657 : 952400 -- americium 240 (Am-240) + + Pointers : 3032598 -1000000 + Primary type : Decay + Nuclide ZAI : 952400 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 240.05520 + Atomic weight ratio (AWR) : 237.99300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.83E+05 seconds (2.12 days) + Specific ingestion toxicity : 5.80E-10 Sv/Bq + Specific inhalation toxicity : 4.30E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 1.37600E+00 MeV frac = 1.00000E+00 Product nuclide = 94240.82c : EC/beta+ + 2 RTYP = 4 Q = 5.70000E+00 MeV frac = 1.90000E-06 Product nuclide = 93236.82c : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.70000E+00 MeV frac = 1.90000E-06 Product nuclide = 2004.82c : alpha + + Nuclide 1648 / 1657 : 952450 -- americium 245 (Am-245) + + Pointers : 3183310 -1000000 + Primary type : Decay + Nuclide ZAI : 952450 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 245.06625 + Atomic weight ratio (AWR) : 242.96100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.38E+03 seconds (2.05 hours) + Specific ingestion toxicity : 6.20E-11 Sv/Bq + Specific inhalation toxicity : 5.60E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.96000E-01 MeV frac = 1.00000E+00 Product nuclide = 96245.82c : beta- + + Nuclide 1649 / 1657 : 952461 -- americium 246m (Am-246m) + + Pointers : 3184017 -1000000 + Primary type : Decay + Nuclide ZAI : 952461 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 246.06987 + Atomic weight ratio (AWR) : 243.95600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.50E+03 seconds (25 minutes) + Specific ingestion toxicity : 3.40E-11 Sv/Bq + Specific inhalation toxicity : 2.30E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.38100E+00 MeV frac = 1.00000E+00 Product nuclide = 96246.82c : beta- + + Nuclide 1650 / 1657 : 962380 -- curium 238 (Cm-238) + + Pointers : 3189904 -1000000 + Primary type : Decay + Nuclide ZAI : 962380 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 238.05300 + Atomic weight ratio (AWR) : 236.00800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.64E+03 seconds (2.4 hours) + Specific ingestion toxicity : 8.00E-11 Sv/Bq + Specific inhalation toxicity : 4.90E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 9.80000E-01 MeV frac = 9.00000E-01 Product nuclide = 952380 : EC/beta+ + 2 RTYP = 4 Q = 6.62510E+00 MeV frac = 1.00000E-01 Product nuclide = 942340 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 6.62510E+00 MeV frac = 1.00000E-01 Product nuclide = 2004.82c : alpha + + Nuclide 1651 / 1657 : 962390 -- curium 239 (Cm-239) + + Pointers : 3190234 -1000000 + Primary type : Decay + Nuclide ZAI : 962390 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 239.05461 + Atomic weight ratio (AWR) : 237.00100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.04E+04 seconds (2.9 hours) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 1.79800E+00 MeV frac = 9.99000E-01 Product nuclide = 952390 : EC/beta+ + 2 RTYP = 4 Q = 6.58110E+00 MeV frac = 1.00000E-03 Product nuclide = 942350 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 6.58110E+00 MeV frac = 1.00000E-03 Product nuclide = 2004.82c : alpha + + Nuclide 1652 / 1657 : 962441 -- curium 244m (Cm-244m) + + Pointers : 3314003 -1000000 + Primary type : Decay + Nuclide ZAI : 962441 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 244.06263 + Atomic weight ratio (AWR) : 241.96600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 34 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.04019E+00 MeV frac = 1.00000E+00 Product nuclide = 96244.82c : IT + + Nuclide 1653 / 1657 : 962510 -- curium 251 (Cm-251) + + Pointers : 3489899 -1000000 + Primary type : Decay + Nuclide ZAI : 962510 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 251.08193 + Atomic weight ratio (AWR) : 248.92500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.01E+03 seconds (16.8 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.42000E+00 MeV frac = 1.00000E+00 Product nuclide = 972510 : beta- + + Nuclide 1654 / 1657 : 972490 -- berkelium 249 (Bk-249) + + Pointers : 3491152 -1000000 + Primary type : Decay + Nuclide ZAI : 972490 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 249.07468 + Atomic weight ratio (AWR) : 246.93500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.76E+07 seconds (320 days) + Specific ingestion toxicity : 9.70E-10 Sv/Bq + Specific inhalation toxicity : 1.60E-07 Sv/Bq + Spontaneous fission nubar : 3.40000 + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 1 Q = 1.25000E-01 MeV frac = 9.99986E-01 Product nuclide = 982490 : beta- + 2 RTYP = 4 Q = 5.52600E+00 MeV frac = 1.45000E-05 Product nuclide = 952450 : alpha + 3 RTYP = 6 Q = 1.92700E+02 MeV frac = 4.69000E-10 SF without yield : spontaneous fission + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.52600E+00 MeV frac = 1.45000E-05 Product nuclide = 2004.82c : alpha + + Nuclide 1655 / 1657 : 972510 -- berkelium 251 (Bk-251) + + Pointers : 3492293 -1000000 + Primary type : Decay + Nuclide ZAI : 972510 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 251.08092 + Atomic weight ratio (AWR) : 248.92400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.34E+03 seconds (55.6 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.09300E+00 MeV frac = 1.00000E+00 Product nuclide = 982510 : beta- + + Nuclide 1656 / 1657 : 982490 -- californium 249 (Cf-249) + + Pointers : 3492477 -1000000 + Primary type : Decay + Nuclide ZAI : 982490 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 249.07468 + Atomic weight ratio (AWR) : 246.93500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.11E+10 seconds (351 years) + Specific ingestion toxicity : 3.50E-07 Sv/Bq + Specific inhalation toxicity : 7.00E-05 Sv/Bq + Spontaneous fission nubar : 3.40000 + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 4 Q = 6.29560E+00 MeV frac = 1.00000E+00 Product nuclide = 96245.82c : alpha + 2 RTYP = 6 Q = 1.96000E+02 MeV frac = 5.20000E-09 SF without yield : spontaneous fission + + 1 additional decay branch: + + 1 RTYP = 4 Q = 6.29560E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 1657 / 1657 : 982510 -- californium 251 (Cf-251) + + Pointers : 3495099 -1000000 + Primary type : Decay + Nuclide ZAI : 982510 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 251.07991 + Atomic weight ratio (AWR) : 248.92300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.83E+10 seconds (899 years) + Specific ingestion toxicity : 3.60E-07 Sv/Bq + Specific inhalation toxicity : 7.10E-05 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 4 Q = 6.17240E+00 MeV frac = 1.00000E+00 Product nuclide = 96247.82c : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 6.17240E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + --- Table 3: Fission yield data: + + Nuclide 90227.82c -- thorium 227 (Th-227) is using NFY data from U-233 + + Nuclide 90228.82c -- thorium 228 (Th-228) is using NFY data from U-233 + + Nuclide 90229.82c -- thorium 229 (Th-229) is using NFY data from U-233 + + Nuclide 90230.82c -- thorium 230 (Th-230) is using NFY data from U-233 + + Nuclide 91231.82c -- protactinium 231 (Pa-231) is using NFY data from U-233 + + Nuclide 91232.82c -- protactinium 232 (Pa-232) is using NFY data from U-233 + + Nuclide 91233.82c -- protactinium 233 (Pa-233) is using NFY data from Th-232 + + Nuclide 92232.82c -- uranium 232 (U-232) is using NFY data from U-233 + + Nuclide 92233.82c -- uranium 233 (U-233) + + Neutron-induced fission: + + Interpolation region : 1 / 3 + Interpolation energy : 2.53000E-08 MeV + Number of products : 901 / 966 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 3.33770E-05 3.33770E-05 1001.82c + 2 10020 H-2 8.46600E-06 8.46600E-06 1002.82c + 3 10030 H-3 1.14000E-04 1.14000E-04 1003.82c + 4 20040 He-4 2.11000E-03 2.11110E-03 2004.82c + 5 20060 He-6 2.15300E-05 2.15300E-05 20060 + 6 20080 He-8 3.71700E-07 3.71700E-07 20080 + 7 30070 Li-7 7.64000E-07 8.08600E-07 3007.82c + 8 30080 Li-8 3.71700E-07 6.98800E-07 30080 + 9 30090 Li-9 7.43400E-07 7.43400E-07 30090 + 10 40090 Be-9 7.43400E-07 1.11880E-06 4009.82c + 11 40100 Be-10 8.88000E-06 8.88000E-06 40100 + 12 240590 Cr-59 2.37470E-12 2.37470E-12 240590 + 13 240600 Cr-60 6.31200E-12 6.31200E-12 240600 + 14 240610 Cr-61 5.49010E-12 5.49010E-12 240610 + 15 240620 Cr-62 6.35880E-12 6.35880E-12 240620 + 16 240630 Cr-63 2.06430E-12 2.06430E-12 240630 + 17 250590 Mn-59 1.01890E-12 3.39360E-12 250590 + 18 250600 Mn-60 4.06800E-13 7.13430E-12 250600 + 19 250601 Mn-60m 3.61300E-12 3.61300E-12 250601 + 20 250610 Mn-61 2.15490E-11 2.70390E-11 250610 + 21 250620 Mn-62 3.32050E-11 3.63840E-11 250620 + 22 250621 Mn-62m 5.96110E-12 9.14050E-12 250621 + 23 250630 Mn-63 8.89450E-11 9.10090E-11 250630 + 24 250640 Mn-64 5.47820E-11 5.47820E-11 250640 + 25 250650 Mn-65 5.28980E-11 5.28980E-11 250650 + 26 250660 Mn-66 1.41450E-11 1.41450E-11 250660 + 27 250670 Mn-67 3.90080E-12 3.90080E-12 250670 + 28 260610 Fe-61 3.49680E-12 3.05360E-11 260610 + 29 260620 Fe-62 3.97980E-11 8.53230E-11 260620 + 30 260630 Fe-63 1.33460E-10 2.24470E-10 260630 + 31 260640 Fe-64 5.16790E-10 5.71570E-10 260640 + 32 260650 Fe-65 8.10580E-10 8.63480E-10 260650 + 33 260660 Fe-66 1.57020E-09 1.58440E-09 260660 + 34 260670 Fe-67 8.07700E-10 8.11600E-10 260670 + 35 260680 Fe-68 5.15770E-10 5.15770E-10 260680 + 36 260690 Fe-69 1.12320E-10 1.12320E-10 260690 + 37 260700 Fe-70 2.40810E-11 2.40810E-11 260700 + 38 260710 Fe-71 1.55530E-12 1.55530E-12 260710 + 39 270630 Co-63 1.70320E-11 2.41500E-10 270630 + 40 270640 Co-64 1.02950E-10 6.74520E-10 270640 + 41 270650 Co-65 9.92920E-10 1.85640E-09 270650 + 42 270660 Co-66 2.86100E-09 4.44540E-09 270660 + 43 270670 Co-67 9.52140E-09 1.03330E-08 270670 + 44 270680 Co-68 5.44100E-09 8.10280E-09 270680 + 45 270681 Co-68m 4.80000E-09 5.32360E-09 270681 + 46 270690 Co-69 1.66830E-08 1.67880E-08 270690 + 47 270700 Co-70 3.41640E-09 3.41640E-09 270700 + 48 270701 Co-70m 3.41640E-09 3.44050E-09 270701 + 49 270710 Co-71 3.60750E-09 3.60910E-09 270710 + 50 270720 Co-72 2.00740E-10 2.00740E-10 270720 + 51 270730 Co-73 1.09180E-10 1.09180E-10 270730 + 52 270740 Co-74 4.49020E-12 4.49020E-12 270740 + 53 280640 Ni-64 2.73380E-12 6.77260E-10 28064.82c + 54 280650 Ni-65 4.60790E-11 1.90250E-09 280650 + 55 280660 Ni-66 8.90390E-10 5.33570E-09 280660 + 56 280670 Ni-67 4.49660E-09 1.48300E-08 280670 + 57 280680 Ni-68 2.95430E-08 4.04750E-08 280680 + 58 280690 Ni-69 3.64730E-08 5.30930E-08 280690 + 59 280691 Ni-69m 3.64730E-08 3.64730E-08 280691 + 60 280700 Ni-70 2.00010E-07 2.06870E-07 280700 + 61 280710 Ni-71 1.84240E-07 1.87850E-07 280710 + 62 280720 Ni-72 7.88920E-08 7.90930E-08 280720 + 63 280730 Ni-73 8.36330E-08 8.37420E-08 280730 + 64 280740 Ni-74 2.94680E-08 2.94730E-08 280740 + 65 280750 Ni-75 3.25740E-09 3.25740E-09 280750 + 66 280760 Ni-76 3.59450E-10 3.59450E-10 280760 + 67 280770 Ni-77 1.03520E-11 1.03520E-11 280770 + 68 290660 Cu-66 4.15910E-12 5.33990E-09 290660 + 69 290670 Cu-67 1.57350E-10 1.49870E-08 290670 + 70 290680 Cu-68 5.21920E-10 4.20240E-08 290680 + 71 290681 Cu-68m 1.22250E-09 1.22250E-09 290681 + 72 290690 Cu-69 2.79100E-08 1.17480E-07 290690 + 73 290700 Cu-70 8.66860E-09 6.23430E-08 290700 + 74 290701 Cu-70m 9.65730E-08 1.07350E-07 290701 + 75 290702 Cu-70m 8.66860E-09 2.15540E-07 290702 + 76 290710 Cu-71 6.44800E-07 8.32650E-07 290710 + 77 290720 Cu-72 4.30310E-07 5.09400E-07 290720 + 78 290730 Cu-73 2.69210E-06 2.77580E-06 290730 + 79 290740 Cu-74 2.01080E-06 2.04030E-06 290740 + 80 290750 Cu-75 1.31000E-06 1.31320E-06 290750 + 81 290760 Cu-76 1.91340E-07 1.91520E-07 290760 + 82 290761 Cu-76m 1.91340E-07 1.91520E-07 290761 + 83 290770 Cu-77 1.35850E-07 1.35860E-07 290770 + 84 290780 Cu-78 7.00660E-09 7.00660E-09 290780 + 85 290790 Cu-79 5.32180E-10 5.32180E-10 290790 + 86 300680 Zn-68 1.14110E-11 4.22310E-08 300680 + 87 300690 Zn-69 6.40300E-11 1.17820E-07 300690 + 88 300691 Zn-69m 2.76920E-10 2.76920E-10 300691 + 89 300700 Zn-70 1.00970E-08 3.30870E-07 300700 + 90 300710 Zn-71 1.74670E-08 8.50120E-07 300710 + 91 300711 Zn-71m 7.55430E-08 7.55430E-08 300711 + 92 300720 Zn-72 9.28880E-07 1.43830E-06 300720 + 93 300730 Zn-73 5.32520E-07 6.09830E-06 300730 + 94 300731 Zn-73m 7.27970E-07 2.78990E-06 300731 + 95 300732 Zn-73m 4.12390E-06 4.12390E-06 300732 + 96 300740 Zn-74 1.71190E-05 1.92050E-05 300740 + 97 300750 Zn-75 3.27430E-05 3.40160E-05 300750 + 98 300760 Zn-76 4.60910E-05 4.64680E-05 300760 + 99 300770 Zn-77 3.61860E-05 3.90880E-05 300770 + 100 300771 Zn-77m 5.53180E-06 5.53180E-06 300771 + 101 300780 Zn-78 2.94690E-05 2.94760E-05 300780 + 102 300790 Zn-79 6.32060E-06 6.32080E-06 300790 + 103 300800 Zn-80 2.38020E-06 2.38020E-06 300800 + 104 300810 Zn-81 9.51700E-09 9.51700E-09 300810 + 105 300820 Zn-82 4.48790E-10 4.48790E-10 300820 + 106 310700 Ga-70 1.13060E-11 1.13060E-11 310700 + 107 310710 Ga-71 8.25550E-10 9.26480E-07 310710 + 108 310720 Ga-72 5.66270E-09 1.44460E-06 310720 + 109 310721 Ga-72m 6.37590E-10 4.85620E-08 310721 + 110 310730 Ga-73 4.79750E-07 8.64000E-06 310730 + 111 310740 Ga-74 1.22280E-06 1.65440E-05 310740 + 112 310741 Ga-74m 1.22280E-06 2.04280E-05 310741 + 113 310750 Ga-75 1.31020E-05 4.71180E-05 310750 + 114 310760 Ga-76 4.96810E-05 9.61490E-05 310760 + 115 310770 Ga-77 1.69750E-04 2.11600E-04 310770 + 116 310780 Ga-78 1.11690E-04 1.41250E-04 310780 + 117 310790 Ga-79 1.69260E-04 1.75500E-04 310790 + 118 310800 Ga-80 7.25010E-05 7.48820E-05 310800 + 119 310810 Ga-81 3.21550E-05 3.21640E-05 310810 + 120 310820 Ga-82 3.83420E-06 3.83460E-06 310820 + 121 310830 Ga-83 1.91330E-07 1.91330E-07 310830 + 122 310840 Ga-84 5.59290E-09 5.59290E-09 310840 + 123 320720 Ge-72 9.66930E-12 1.44460E-06 32072.82c + 124 320730 Ge-73 1.16900E-09 8.64140E-06 32073.82c + 125 320731 Ge-73m 2.70300E-10 8.51340E-06 320731 + 126 320740 Ge-74 6.96290E-08 2.17200E-05 32074.82c + 127 320750 Ge-75 6.94930E-07 5.23570E-05 320750 + 128 320751 Ge-75m 4.54590E-06 6.43060E-06 320751 + 129 320760 Ge-76 2.48490E-05 1.21000E-04 32076.82c + 130 320770 Ge-77 1.43810E-04 1.88190E-04 320770 + 131 320771 Ge-77m 2.19840E-05 2.33590E-04 320771 + 132 320780 Ge-78 4.55250E-04 5.96650E-04 320780 + 133 320790 Ge-79 1.25770E-04 3.33760E-04 320790 + 134 320791 Ge-79m 8.22690E-04 8.22960E-04 320791 + 135 320800 Ge-80 1.66210E-03 1.74080E-03 320800 + 136 320810 Ge-81 1.11820E-03 1.13630E-03 320810 + 137 320811 Ge-81m 2.58560E-04 2.72340E-04 320811 + 138 320820 Ge-82 9.73420E-04 9.76510E-04 320820 + 139 320830 Ge-83 2.33530E-04 2.33650E-04 320830 + 140 320840 Ge-84 5.02130E-05 5.02150E-05 320840 + 141 320850 Ge-85 9.45350E-06 9.45350E-06 320850 + 142 320860 Ge-86 1.09620E-06 1.09620E-06 320860 + 143 320870 Ge-87 2.09770E-09 2.09770E-09 320870 + 144 330740 As-74 1.79610E-11 1.79610E-11 330740 + 145 330750 As-75 5.27640E-10 5.23610E-05 33075.82c + 146 330751 As-75m 1.72630E-09 3.65540E-09 330751 + 147 330760 As-76 6.81610E-08 6.81610E-08 330760 + 148 330770 As-77 4.31960E-06 3.81710E-04 330770 + 149 330780 As-78 2.58130E-05 6.22470E-04 330780 + 150 330790 As-79 1.20300E-04 1.24410E-03 330790 + 151 330800 As-80 6.51380E-04 2.39220E-03 330800 + 152 330810 As-81 1.59110E-03 2.99700E-03 330810 + 153 330820 As-82 5.31600E-04 1.50810E-03 330820 + 154 330821 As-82m 1.60420E-03 1.60420E-03 330821 + 155 330830 As-83 2.52180E-03 2.76090E-03 330830 + 156 330840 As-84 6.65400E-04 6.88460E-04 330840 + 157 330841 As-84m 6.65400E-04 6.88460E-04 330841 + 158 330850 As-85 8.04600E-04 8.12730E-04 330850 + 159 330860 As-86 1.75050E-04 1.76150E-04 330860 + 160 330870 As-87 6.37110E-05 6.37130E-05 330870 + 161 330880 As-88 6.55810E-06 6.55810E-06 330880 + 162 330890 As-89 1.14750E-06 1.14750E-06 330890 + 163 340760 Se-76 2.33410E-11 6.81840E-08 34076.82c + 164 340770 Se-77 3.08850E-10 3.81720E-04 34077.82c + 165 340771 Se-77m 2.02030E-09 2.02030E-09 340771 + 166 340780 Se-78 1.36100E-07 6.22600E-04 34078.82c + 167 340790 Se-79 5.48610E-06 1.24970E-03 34079.82c + 168 340791 Se-79m 8.38670E-07 1.21550E-03 340791 + 169 340800 Se-80 1.14010E-04 2.50620E-03 34080.82c + 170 340810 Se-81 9.74860E-05 3.73190E-03 340810 + 171 340811 Se-81m 6.37700E-04 7.45290E-04 340811 + 172 340820 Se-82 2.72300E-03 5.83530E-03 34082.82c + 173 340830 Se-83 6.09840E-03 7.09330E-03 340830 + 174 340831 Se-83m 1.41010E-03 3.17800E-03 340831 + 175 340840 Se-84 1.36590E-02 1.52130E-02 340840 + 176 340850 Se-85 1.24580E-02 1.31500E-02 340850 + 177 340860 Se-86 9.46630E-03 9.59410E-03 340860 + 178 340870 Se-87 4.20600E-03 4.25990E-03 340870 + 179 340880 Se-88 1.60130E-03 1.60790E-03 340880 + 180 340890 Se-89 2.94150E-04 2.95300E-04 340890 + 181 340900 Se-90 6.53360E-05 6.53360E-05 340900 + 182 340910 Se-91 2.40160E-07 2.40160E-07 340910 + 183 340920 Se-92 7.54730E-09 7.54730E-09 340920 + 184 350780 Br-78 1.42690E-11 1.42690E-11 350780 + 185 350790 Br-79 3.16250E-10 6.82020E-07 35079.82c + 186 350791 Br-79m 1.03460E-09 1.03460E-09 350791 + 187 350800 Br-80 1.60340E-08 6.44200E-08 350800 + 188 350801 Br-80m 4.83860E-08 4.83860E-08 350801 + 189 350810 Br-81 5.36730E-06 3.73760E-03 35081.82c + 190 350820 Br-82 2.15450E-05 3.05230E-05 350820 + 191 350821 Br-82m 9.19860E-06 9.19860E-06 350821 + 192 350830 Br-83 3.14280E-04 1.05860E-02 350830 + 193 350840 Br-84 8.56700E-04 1.60700E-02 350840 + 194 350841 Br-84m 8.56700E-04 8.56700E-04 350841 + 195 350850 Br-85 7.77110E-03 2.09210E-02 350850 + 196 350860 Br-86 1.37340E-02 2.33280E-02 350860 + 197 350870 Br-87 1.73830E-02 2.16590E-02 350870 + 198 350880 Br-88 1.19080E-02 1.35230E-02 350880 + 199 350890 Br-89 7.90110E-03 8.17340E-03 350890 + 200 350900 Br-90 2.42940E-03 2.49480E-03 350900 + 201 350910 Br-91 8.12440E-04 8.12630E-04 350910 + 202 350920 Br-92 5.59100E-05 5.59180E-05 350920 + 203 350930 Br-93 1.21710E-05 1.21710E-05 350930 + 204 350940 Br-94 3.72700E-08 3.72700E-08 350940 + 205 360810 Kr-81 3.55040E-10 4.09320E-10 360810 + 206 360811 Kr-81m 5.42760E-11 5.42760E-11 360811 + 207 360820 Kr-82 9.58820E-07 3.17030E-05 36082.82c + 208 360830 Kr-83 8.97720E-06 1.05970E-02 36083.82c + 209 360831 Kr-83m 2.07570E-06 1.05780E-02 360831 + 210 360840 Kr-84 1.23330E-04 1.70490E-02 36084.82c + 211 360850 Kr-85 7.77430E-04 5.31980E-03 36085.82c + 212 360851 Kr-85m 1.79760E-04 2.10670E-02 360851 + 213 360860 Kr-86 7.32210E-03 3.11940E-02 36086.82c + 214 360870 Kr-87 1.78830E-02 3.99040E-02 360870 + 215 360880 Kr-88 3.90420E-02 5.28110E-02 360880 + 216 360890 Kr-89 4.54190E-02 5.30540E-02 360890 + 217 360900 Kr-90 4.12010E-02 4.32450E-02 360900 + 218 360910 Kr-91 2.15840E-02 2.22530E-02 360910 + 219 360920 Kr-92 9.03970E-03 9.08540E-03 360920 + 220 360930 Kr-93 2.26920E-03 2.27310E-03 360930 + 221 360940 Kr-94 4.92480E-04 4.92490E-04 360940 + 222 360950 Kr-95 4.66500E-05 4.66500E-05 360950 + 223 360960 Kr-96 2.62500E-06 2.62500E-06 360960 + 224 360970 Kr-97 4.47990E-09 4.47990E-09 360970 + 225 370840 Rb-84 3.59690E-09 1.00670E-08 370840 + 226 370841 Rb-84m 6.47010E-09 6.47010E-09 370841 + 227 370850 Rb-85 6.88250E-07 2.18790E-02 37085.82c + 228 370860 Rb-86 8.62240E-06 2.41320E-05 37086.82c + 229 370861 Rb-86m 1.55100E-05 1.55100E-05 370861 + 230 370870 Rb-87 4.09780E-04 4.03140E-02 37087.82c + 231 370880 Rb-88 1.81710E-03 5.46290E-02 370880 + 232 370890 Rb-89 8.87530E-03 6.19290E-02 370890 + 233 370900 Rb-90 1.90910E-03 4.00850E-02 370900 + 234 370901 Rb-90m 1.69560E-02 2.26120E-02 370901 + 235 370910 Rb-91 3.14860E-02 5.37390E-02 370910 + 236 370920 Rb-92 2.61580E-02 3.52430E-02 370920 + 237 370930 Rb-93 2.12780E-02 2.35570E-02 370930 + 238 370940 Rb-94 8.58550E-03 9.07390E-03 370940 + 239 370950 Rb-95 3.80190E-03 3.84730E-03 370950 + 240 370960 Rb-96 3.05590E-04 4.60290E-04 370960 + 241 370961 Rb-96m 3.05590E-04 3.06860E-04 370961 + 242 370970 Rb-97 1.24760E-04 1.24760E-04 370970 + 243 370980 Rb-98 2.21430E-06 2.21430E-06 370980 + 244 370981 Rb-98m 2.21430E-06 2.21430E-06 370981 + 245 370990 Rb-99 4.10450E-08 4.10450E-08 370990 + 246 380860 Sr-86 3.59850E-09 2.41340E-05 38086.82c + 247 380870 Sr-87 1.76520E-06 2.17220E-06 38087.82c + 248 380871 Sr-87m 4.08170E-07 4.08170E-07 380871 + 249 380880 Sr-88 9.08890E-05 5.47190E-02 38088.82c + 250 380890 Sr-89 5.28290E-04 6.24570E-02 38089.82c + 251 380900 Sr-90 4.24830E-03 6.63580E-02 38090.82c + 252 380910 Sr-91 1.18310E-02 6.55700E-02 380910 + 253 380920 Sr-92 3.00450E-02 6.56180E-02 380920 + 254 380930 Sr-93 4.27800E-02 6.69230E-02 380930 + 255 380940 Sr-94 5.08480E-02 5.93360E-02 380940 + 256 380950 Sr-95 3.42940E-02 3.78720E-02 380950 + 257 380960 Sr-96 1.90200E-02 1.96030E-02 380960 + 258 380970 Sr-97 6.98230E-03 7.07610E-03 380970 + 259 380980 Sr-98 2.03820E-03 2.04230E-03 380980 + 260 380990 Sr-99 3.16680E-04 3.16720E-04 380990 + 261 381000 Sr-100 5.22920E-05 5.22920E-05 381000 + 262 381010 Sr-101 4.78010E-06 4.78010E-06 381010 + 263 381020 Sr-102 3.78560E-09 3.78560E-09 381020 + 264 390890 Y-89 2.15540E-07 6.24580E-02 39089.82c + 265 390891 Y-89m 9.32160E-07 6.95250E-06 390891 + 266 390900 Y-90 3.44550E-06 6.63660E-02 39090.82c + 267 390901 Y-90m 4.88910E-06 4.88910E-06 390901 + 268 390910 Y-91 2.35650E-05 6.56950E-02 39091.82c + 269 390911 Y-91m 1.01920E-04 3.86800E-02 390911 + 270 390920 Y-92 5.18730E-04 6.61370E-02 390920 + 271 390930 Y-93 4.44770E-04 7.02780E-02 390930 + 272 390931 Y-93m 2.90940E-03 1.96560E-02 390931 + 273 390940 Y-94 8.15890E-03 6.74950E-02 390940 + 274 390950 Y-95 2.31700E-02 6.10420E-02 390950 + 275 390960 Y-96 8.95640E-03 2.85620E-02 390960 + 276 390961 Y-96m 1.61110E-02 1.61120E-02 390961 + 277 390970 Y-97 4.70550E-03 1.08690E-02 390970 + 278 390971 Y-97m 1.60380E-02 2.05380E-02 390971 + 279 390972 Y-97m 4.30960E-03 4.30960E-03 390972 + 280 390980 Y-98 2.41890E-03 4.46120E-03 390980 + 281 390981 Y-98m 1.01730E-02 1.01730E-02 390981 + 282 390990 Y-99 7.68130E-03 7.99840E-03 390990 + 283 391000 Y-100 1.18420E-03 1.23610E-03 391000 + 284 391001 Y-100m 1.18420E-03 1.18430E-03 391001 + 285 391010 Y-101 6.30520E-04 6.35190E-04 391010 + 286 391020 Y-102 3.48600E-05 3.48620E-05 391020 + 287 391021 Y-102m 3.48600E-05 3.48620E-05 391021 + 288 391030 Y-103 1.23480E-05 1.23480E-05 391030 + 289 391040 Y-104 7.81110E-09 7.81110E-09 391040 + 290 391050 Y-105 1.67050E-10 1.67050E-10 391050 + 291 400910 Zr-91 2.27770E-06 6.56970E-02 40091.82c + 292 400920 Zr-92 1.59940E-05 6.61530E-02 40092.82c + 293 400930 Zr-93 1.16950E-04 7.03940E-02 40093.82c + 294 400940 Zr-94 8.68540E-04 6.83640E-02 40094.82c + 295 400950 Zr-95 3.34790E-03 6.43900E-02 40095.82c + 296 400960 Zr-96 1.28580E-02 5.75480E-02 40096.82c + 297 400970 Zr-97 2.26440E-02 5.51160E-02 400970 + 298 400980 Zr-98 3.42060E-02 4.86140E-02 400980 + 299 400990 Zr-99 3.09470E-02 3.88210E-02 400990 + 300 401000 Zr-100 2.68670E-02 2.92760E-02 401000 + 301 401010 Zr-101 1.09370E-02 1.15760E-02 401010 + 302 401020 Zr-102 4.52010E-03 4.58740E-03 401020 + 303 401030 Zr-103 7.75780E-04 7.87140E-04 401030 + 304 401040 Zr-104 1.23960E-04 1.23970E-04 401040 + 305 401050 Zr-105 8.42170E-06 8.42180E-06 401050 + 306 401060 Zr-106 2.09970E-06 2.09970E-06 401060 + 307 401070 Zr-107 1.58670E-10 1.58670E-10 401070 + 308 410940 Nb-94 1.71100E-08 2.91080E-08 41094.82c + 309 410941 Nb-94m 1.20580E-08 1.20580E-08 410941 + 310 410950 Nb-95 1.18490E-05 6.43660E-02 41095.82c + 311 410951 Nb-95m 2.73980E-06 6.98380E-04 410951 + 312 410960 Nb-96 9.19990E-05 9.19990E-05 410960 + 313 410970 Nb-97 5.16600E-04 5.57520E-02 410970 + 314 410971 Nb-97m 1.19450E-04 5.25060E-02 410971 + 315 410980 Nb-98 4.55740E-04 4.90700E-02 410980 + 316 410981 Nb-98m 1.37530E-03 1.37530E-03 410981 + 317 410990 Nb-99 5.40400E-03 3.02490E-02 410990 + 318 410991 Nb-99m 1.24950E-03 1.55360E-02 410991 + 319 411000 Nb-100 2.19010E-03 3.14660E-02 411000 + 320 411001 Nb-100m 9.21090E-03 9.21090E-03 411001 + 321 411010 Nb-101 1.57050E-02 2.72810E-02 411010 + 322 411020 Nb-102 5.91350E-03 1.05010E-02 411020 + 323 411021 Nb-102m 5.91350E-03 5.91350E-03 411021 + 324 411030 Nb-103 7.26650E-03 8.05360E-03 411030 + 325 411040 Nb-104 1.18240E-03 1.30650E-03 411040 + 326 411041 Nb-104m 1.18240E-03 1.18240E-03 411041 + 327 411050 Nb-105 6.92340E-04 7.00680E-04 411050 + 328 411060 Nb-106 1.26070E-04 1.28140E-04 411060 + 329 411070 Nb-107 4.92440E-06 4.92460E-06 411070 + 330 411080 Nb-108 2.48800E-08 2.48800E-08 411080 + 331 411090 Nb-109 5.71530E-10 5.71530E-10 411090 + 332 411100 Nb-110 9.23390E-12 9.23390E-12 411100 + 333 420960 Mo-96 4.56320E-09 9.20040E-05 42096.82c + 334 420970 Mo-97 7.65300E-06 5.57590E-02 42097.82c + 335 420980 Mo-98 9.58900E-05 5.05410E-02 42098.82c + 336 420990 Mo-99 4.55900E-04 4.59300E-02 42099.82c + 337 421000 Mo-100 2.13100E-03 4.28080E-02 42100.82c + 338 421010 Mo-101 4.11830E-03 3.13990E-02 421010 + 339 421020 Mo-102 7.93180E-03 2.43460E-02 421020 + 340 421030 Mo-103 7.25570E-03 1.53110E-02 421030 + 341 421040 Mo-104 6.48060E-03 8.98000E-03 421040 + 342 421050 Mo-105 2.94850E-03 3.64300E-03 421050 + 343 421060 Mo-106 1.30380E-03 1.42650E-03 421060 + 344 421070 Mo-107 2.69900E-04 2.74530E-04 421070 + 345 421080 Mo-108 9.07910E-05 9.08140E-05 421080 + 346 421090 Mo-109 6.30800E-06 6.30850E-06 421090 + 347 421100 Mo-110 1.04390E-07 1.04400E-07 421100 + 348 421110 Mo-111 1.87210E-09 1.87210E-09 421110 + 349 421120 Mo-112 3.37090E-11 3.37090E-11 421120 + 350 430990 Tc-99 1.99600E-06 4.59310E-02 43099.82c + 351 430991 Tc-99m 4.61520E-07 4.04470E-02 430991 + 352 431000 Tc-100 2.85530E-06 2.85530E-06 431000 + 353 431010 Tc-101 3.82470E-05 3.14370E-02 431010 + 354 431020 Tc-102 1.03680E-04 2.44500E-02 431020 + 355 431021 Tc-102m 1.03680E-04 1.03680E-04 431021 + 356 431030 Tc-103 5.80220E-04 1.58910E-02 431030 + 357 431040 Tc-104 8.50800E-04 9.83080E-03 431040 + 358 431050 Tc-105 1.30890E-03 4.95190E-03 431050 + 359 431060 Tc-106 9.00930E-04 2.32740E-03 431060 + 360 431070 Tc-107 6.15480E-04 8.90010E-04 431070 + 361 431080 Tc-108 3.51320E-04 4.42170E-04 431080 + 362 431090 Tc-109 1.19720E-04 1.26000E-04 431090 + 363 431100 Tc-110 3.82930E-05 3.83970E-05 431100 + 364 431110 Tc-111 9.34840E-06 9.35030E-06 431110 + 365 431120 Tc-112 3.22610E-06 3.22610E-06 431120 + 366 431130 Tc-113 8.38990E-09 8.38990E-09 431130 + 367 431140 Tc-114 2.01420E-10 2.01420E-10 431140 + 368 431150 Tc-115 6.43180E-12 6.43180E-12 431150 + 369 431180 Tc-118 1.98770E-11 1.98770E-11 431180 + 370 441010 Ru-101 1.67510E-09 3.14370E-02 44101.82c + 371 441020 Ru-102 3.17100E-06 2.45570E-02 44102.82c + 372 441030 Ru-103 2.95970E-06 1.59010E-02 44103.82c + 373 441031 Ru-103m 7.14520E-06 7.14520E-06 441031 + 374 441040 Ru-104 5.22110E-05 9.88300E-03 44104.82c + 375 441050 Ru-105 1.11410E-04 5.06330E-03 44105.82c + 376 441060 Ru-106 2.19230E-04 2.54660E-03 44106.82c + 377 441070 Ru-107 2.69280E-04 1.15930E-03 441070 + 378 441080 Ru-108 3.52900E-04 7.95170E-04 441080 + 379 441090 Ru-109 2.55680E-04 3.81590E-04 441090 + 380 441100 Ru-110 2.58460E-04 2.96840E-04 441100 + 381 441110 Ru-111 1.37030E-04 1.46430E-04 441110 + 382 441120 Ru-112 5.05180E-05 5.36960E-05 441120 + 383 441130 Ru-113 9.86900E-06 1.48110E-05 441130 + 384 441131 Ru-113m 9.86900E-06 9.86900E-06 441131 + 385 441140 Ru-114 5.98270E-06 5.98290E-06 441140 + 386 441150 Ru-115 4.14320E-08 4.14380E-08 441150 + 387 441160 Ru-116 2.16370E-09 2.16370E-09 441160 + 388 441170 Ru-117 3.28550E-11 3.28550E-11 441170 + 389 441180 Ru-118 1.51610E-07 1.51630E-07 441180 + 390 441190 Ru-119 6.06470E-09 6.06470E-09 441190 + 391 441200 Ru-120 2.94220E-10 2.94220E-10 441200 + 392 451040 Rh-104 6.86190E-10 2.75420E-09 451040 + 393 451041 Rh-104m 2.07070E-09 2.07070E-09 451041 + 394 451050 Rh-105 6.95540E-08 5.06340E-03 45105.82c + 395 451051 Rh-105m 1.06330E-08 1.43740E-03 451051 + 396 451060 Rh-106 1.87440E-07 2.54680E-03 451060 + 397 451061 Rh-106m 4.39030E-07 4.39030E-07 451061 + 398 451070 Rh-107 9.85130E-06 1.16910E-03 451070 + 399 451080 Rh-108 2.95290E-06 7.98120E-04 451080 + 400 451081 Rh-108m 8.91110E-06 8.91110E-06 451081 + 401 451090 Rh-109 4.10330E-05 4.22620E-04 451090 + 402 451100 Rh-110 9.33900E-05 3.90230E-04 451100 + 403 451101 Rh-110m 2.49300E-06 2.49300E-06 451101 + 404 451110 Rh-111 9.04420E-05 2.36870E-04 451110 + 405 451120 Rh-112 3.06540E-05 8.43500E-05 451120 + 406 451121 Rh-112m 3.06540E-05 3.06540E-05 451121 + 407 451130 Rh-113 7.68800E-05 9.66260E-05 451130 + 408 451140 Rh-114 2.79080E-05 3.38910E-05 451140 + 409 451141 Rh-114m 2.79080E-05 2.79080E-05 451141 + 410 451150 Rh-115 3.27360E-05 3.27770E-05 451150 + 411 451160 Rh-116 1.23640E-06 1.23850E-06 451160 + 412 451161 Rh-116m 2.89590E-06 2.89590E-06 451161 + 413 451170 Rh-117 1.05840E-06 1.06470E-06 451170 + 414 451180 Rh-118 1.24480E-05 1.25940E-05 451180 + 415 451190 Rh-119 4.00500E-06 4.01080E-06 451190 + 416 451200 Rh-120 3.88940E-07 3.89230E-07 451200 + 417 451210 Rh-121 3.91070E-08 3.91070E-08 451210 + 418 451220 Rh-122 1.19690E-09 1.19690E-09 451220 + 419 461060 Pd-106 9.90450E-11 2.54730E-03 46106.82c + 420 461070 Pd-107 8.26570E-10 1.16910E-03 46107.82c + 421 461071 Pd-107m 1.55340E-09 1.55340E-09 461071 + 422 461080 Pd-108 6.99460E-08 8.07100E-04 46108.82c + 423 461090 Pd-109 1.09560E-06 4.25780E-04 461090 + 424 461091 Pd-109m 2.05910E-06 2.13370E-04 461091 + 425 461100 Pd-110 9.58090E-06 4.02310E-04 46110.82c + 426 461110 Pd-111 4.87230E-06 2.48170E-04 461110 + 427 461111 Pd-111m 9.15670E-06 1.01040E-05 461111 + 428 461120 Pd-112 3.01250E-05 1.45130E-04 461120 + 429 461130 Pd-113 1.88840E-05 1.61100E-04 461130 + 430 461131 Pd-113m 4.55870E-05 4.55870E-05 461131 + 431 461140 Pd-114 1.06760E-04 1.68560E-04 461140 + 432 461150 Pd-115 4.99040E-05 8.58050E-05 461150 + 433 461151 Pd-115m 9.37860E-05 9.85460E-05 461151 + 434 461160 Pd-116 1.23920E-04 1.28050E-04 461160 + 435 461170 Pd-117 1.69010E-05 5.00970E-05 461170 + 436 461171 Pd-117m 3.17640E-05 3.17640E-05 461171 + 437 461180 Pd-118 2.98880E-05 4.21140E-05 461180 + 438 461190 Pd-119 6.93130E-06 1.09650E-05 461190 + 439 461200 Pd-120 2.67890E-06 3.05040E-06 461200 + 440 461210 Pd-121 8.86040E-06 8.89420E-06 461210 + 441 461220 Pd-122 2.22430E-06 2.22550E-06 461220 + 442 461230 Pd-123 1.52690E-07 1.52690E-07 461230 + 443 461240 Pd-124 1.82240E-08 1.82240E-08 461240 + 444 471090 Ag-109 1.84830E-11 4.25780E-04 47109.82c + 445 471091 Ag-109m 1.20910E-10 4.25570E-04 471091 + 446 471100 Ag-110 1.11340E-09 1.14890E-09 471100 + 447 471101 Ag-110m 2.60780E-09 2.60780E-09 47510.82c + 448 471110 Ag-111 1.00500E-08 2.49730E-04 47111.82c + 449 471111 Ag-111m 6.57420E-08 2.48430E-04 471111 + 450 471120 Ag-112 4.03450E-07 1.45530E-04 471120 + 451 471130 Ag-113 1.37810E-07 1.06280E-04 471130 + 452 471131 Ag-113m 9.01490E-07 1.55160E-04 471131 + 453 471140 Ag-114 1.34120E-06 1.75540E-04 471140 + 454 471141 Ag-114m 5.64050E-06 5.64050E-06 471141 + 455 471150 Ag-115 2.52200E-06 9.25290E-05 471150 + 456 471151 Ag-115m 1.64980E-05 1.30330E-04 471151 + 457 471160 Ag-116 1.08230E-05 1.40400E-04 471160 + 458 471161 Ag-116m 2.53500E-05 2.53500E-05 471161 + 459 471170 Ag-117 1.10900E-05 4.19940E-05 471170 + 460 471171 Ag-117m 7.25460E-05 9.75940E-05 471171 + 461 471180 Ag-118 1.22790E-05 7.20150E-05 471180 + 462 471181 Ag-118m 5.16430E-05 5.76630E-05 471181 + 463 471190 Ag-119 1.07200E-05 1.62030E-05 471190 + 464 471191 Ag-119m 7.01250E-05 7.56080E-05 471191 + 465 471200 Ag-120 1.49460E-05 2.49070E-05 471200 + 466 471201 Ag-120m 2.12080E-05 2.27330E-05 471201 + 467 471210 Ag-121 2.68910E-05 3.57610E-05 471210 + 468 471220 Ag-122 5.35990E-06 7.58540E-06 471220 + 469 471221 Ag-122m 4.82810E-06 4.82810E-06 471221 + 470 471230 Ag-123 7.68840E-06 7.84110E-06 471230 + 471 471240 Ag-124 1.46630E-06 2.14500E-06 471240 + 472 471241 Ag-124m 1.32090E-06 1.32090E-06 471241 + 473 471250 Ag-125 3.68330E-06 3.68330E-06 471250 + 474 471260 Ag-126 3.71530E-07 3.71530E-07 471260 + 475 471270 Ag-127 3.98910E-08 3.98910E-08 471270 + 476 471280 Ag-128 1.36480E-09 1.36480E-09 471280 + 477 481110 Cd-111 1.59360E-12 2.50980E-04 48111.82c + 478 481111 Cd-111m 5.21390E-12 5.21390E-12 481111 + 479 481120 Cd-112 3.48330E-10 1.45530E-04 48112.82c + 480 481130 Cd-113 1.96790E-09 1.60300E-04 48113.82c + 481 481131 Cd-113m 6.43840E-09 1.84380E-06 481131 + 482 481140 Cd-114 2.27750E-07 1.75770E-04 48114.82c + 483 481150 Cd-115 2.47300E-07 1.87400E-04 481150 + 484 481151 Cd-115m 8.09100E-07 9.13840E-06 48515.82c + 485 481160 Cd-116 6.19980E-06 1.70430E-04 48116.82c + 486 481170 Cd-117 4.21330E-06 1.08110E-04 481170 + 487 481171 Cd-117m 1.37850E-05 4.36180E-05 481171 + 488 481180 Cd-118 4.95190E-05 1.55560E-04 481180 + 489 481190 Cd-119 1.89610E-05 1.02670E-04 481190 + 490 481191 Cd-119m 4.57730E-05 5.38750E-05 481191 + 491 481200 Cd-120 1.19250E-04 1.58480E-04 481200 + 492 481210 Cd-121 3.50220E-05 6.70470E-05 481210 + 493 481211 Cd-121m 8.45480E-05 8.82850E-05 481211 + 494 481220 Cd-122 1.06930E-04 1.19340E-04 481220 + 495 481230 Cd-123 2.11570E-05 2.75740E-05 481230 + 496 481231 Cd-123m 5.10770E-05 5.25040E-05 481231 + 497 481240 Cd-124 1.21090E-04 1.23890E-04 481240 + 498 481250 Cd-125 7.12600E-05 7.31010E-05 481250 + 499 481251 Cd-125m 1.72030E-04 1.73870E-04 481251 + 500 481260 Cd-126 1.48370E-04 1.48740E-04 481260 + 501 481270 Cd-127 4.83860E-05 4.84260E-05 481270 + 502 481280 Cd-128 1.73780E-05 1.73790E-05 481280 + 503 481290 Cd-129 1.30470E-06 1.30470E-06 481290 + 504 481291 Cd-129m 3.14970E-06 3.14970E-06 481291 + 505 481300 Cd-130 4.17740E-08 4.17740E-08 481300 + 506 481310 Cd-131 9.91230E-10 9.91230E-10 481310 + 507 491140 In-114 8.02150E-12 3.13780E-11 491140 + 508 491141 In-114m 1.22950E-11 2.42030E-11 491141 + 509 491142 In-114m 1.19080E-11 1.19080E-11 491142 + 510 491150 In-115 1.77090E-09 1.87180E-04 49115.82c + 511 491151 In-115m 4.09480E-10 1.87410E-04 491151 + 512 491160 In-116 7.76740E-09 7.76740E-09 491160 + 513 491161 In-116m 1.19060E-08 2.34360E-08 491161 + 514 491162 In-116m 1.15310E-08 1.15310E-08 491162 + 515 491170 In-117 4.33040E-07 9.94480E-05 491170 + 516 491171 In-117m 1.00130E-07 9.98420E-05 491171 + 517 491180 In-118 2.56620E-07 1.55810E-04 491180 + 518 491181 In-118m 3.93330E-07 7.68950E-07 491181 + 519 491182 In-118m 3.80960E-07 3.80960E-07 491182 + 520 491190 In-119 2.81530E-06 7.17880E-05 491190 + 521 491191 In-119m 6.50970E-07 9.34570E-05 491191 + 522 491200 In-120 6.25240E-06 1.64730E-04 491200 + 523 491201 In-120m 6.25240E-06 6.25240E-06 491201 + 524 491202 In-120m 6.25240E-06 6.25240E-06 491202 + 525 491210 In-121 2.55010E-05 1.36970E-04 491210 + 526 491211 In-121m 5.89640E-06 5.03620E-05 491211 + 527 491220 In-122 2.31790E-05 1.42520E-04 491220 + 528 491221 In-122m 1.64450E-05 1.64450E-05 491221 + 529 491222 In-122m 1.64450E-05 1.64450E-05 491222 + 530 491230 In-123 7.62220E-05 1.36630E-04 491230 + 531 491231 In-123m 1.76240E-05 3.72980E-05 491231 + 532 491240 In-124 6.30690E-05 1.86960E-04 491240 + 533 491241 In-124m 5.68110E-05 5.68110E-05 491241 + 534 491250 In-125 4.50700E-04 6.59560E-04 491250 + 535 491251 In-125m 1.04210E-04 1.42320E-04 491251 + 536 491260 In-126 4.46730E-04 5.95470E-04 491260 + 537 491261 In-126m 4.02410E-04 4.02410E-04 491261 + 538 491270 In-127 8.04170E-04 8.04170E-04 491270 + 539 491271 In-127m 1.85940E-04 2.34370E-04 491271 + 540 491280 In-128 2.94530E-04 4.31800E-04 491280 + 541 491281 In-128m 1.19890E-04 1.37270E-04 491281 + 542 491282 In-128m 3.73300E-04 3.73300E-04 491282 + 543 491290 In-129 3.93020E-04 3.96170E-04 491290 + 544 491291 In-129m 9.08760E-05 9.21820E-05 491291 + 545 491300 In-130 2.78250E-05 2.78650E-05 491300 + 546 491301 In-130m 3.10780E-05 3.10780E-05 491301 + 547 491302 In-130m 5.28770E-05 5.28770E-05 491302 + 548 491310 In-131 6.32670E-06 6.39210E-06 491310 + 549 491311 In-131m 6.32670E-06 6.32670E-06 491311 + 550 491312 In-131m 6.32670E-06 6.32670E-06 491312 + 551 491320 In-132 3.02450E-07 3.02450E-07 491320 + 552 491330 In-133 9.93080E-09 1.22270E-08 491330 + 553 491331 In-133m 2.29620E-09 2.29620E-09 491331 + 554 501160 Sn-116 6.59670E-12 3.12110E-08 50116.82c + 555 501170 Sn-117 4.90350E-11 1.52260E-04 50117.82c + 556 501171 Sn-117m 1.60420E-10 3.38990E-07 501171 + 557 501200 Sn-120 6.84270E-11 1.77240E-04 50120.82c + 558 501210 Sn-121 5.68200E-10 1.83250E-04 501210 + 559 501211 Sn-121m 1.37170E-09 1.55180E-05 501211 + 560 501220 Sn-122 2.20890E-05 1.97500E-04 50122.82c + 561 501230 Sn-123 2.28490E-05 3.32660E-05 50123.82c + 562 501231 Sn-123m 9.46480E-06 1.72970E-04 501231 + 563 501240 Sn-124 8.09290E-05 3.24700E-04 50124.82c + 564 501250 Sn-125 2.51510E-04 3.62920E-04 50125.82c + 565 501251 Sn-125m 1.04180E-04 7.94650E-04 501251 + 566 501260 Sn-126 1.33550E-03 2.33500E-03 50126.82c + 567 501270 Sn-127 2.24110E-03 2.55450E-03 501270 + 568 501271 Sn-127m 9.28320E-04 1.65180E-03 501271 + 569 501280 Sn-128 2.25080E-03 8.32780E-03 501280 + 570 501281 Sn-128m 5.27190E-03 5.64520E-03 501281 + 571 501290 Sn-129 2.80430E-03 3.25060E-03 501290 + 572 501291 Sn-129m 6.77000E-03 6.81220E-03 501291 + 573 501300 Sn-130 2.52980E-03 2.60250E-03 501300 + 574 501301 Sn-130m 5.92540E-03 5.96460E-03 501301 + 575 501310 Sn-131 1.08870E-03 1.10090E-03 501310 + 576 501311 Sn-131m 2.62820E-03 2.63480E-03 501311 + 577 501320 Sn-132 1.26560E-03 1.26590E-03 501320 + 578 501330 Sn-133 8.36820E-05 8.36840E-05 501330 + 579 501340 Sn-134 1.04630E-05 1.04630E-05 501340 + 580 501350 Sn-135 6.48130E-08 6.48130E-08 501350 + 581 501360 Sn-136 2.92890E-09 2.92890E-09 501360 + 582 511220 Sb-122 2.10110E-12 4.48280E-12 511220 + 583 511221 Sb-122m 2.38170E-12 2.38170E-12 511221 + 584 511230 Sb-123 4.51970E-10 2.06240E-04 51123.82c + 585 511240 Sb-124 4.97970E-07 1.16980E-06 51124.82c + 586 511241 Sb-124m 3.80760E-07 8.95730E-07 511241 + 587 511242 Sb-124m 5.14970E-07 5.14970E-07 511242 + 588 511250 Sb-125 1.43590E-05 1.17190E-03 51125.82c + 589 511260 Sb-126 2.42110E-05 2.99940E-05 51126.82c + 590 511261 Sb-126m 1.79010E-05 4.13120E-05 511261 + 591 511262 Sb-126m 2.34110E-05 2.34110E-05 511262 + 592 511270 Sb-127 3.38020E-04 4.54430E-03 511270 + 593 511280 Sb-128 6.01840E-04 8.96660E-03 511280 + 594 511281 Sb-128m 1.02700E-03 1.02700E-03 511281 + 595 511290 Sb-129 3.86300E-03 1.13850E-02 511290 + 596 511291 Sb-129m 2.36070E-03 5.76670E-03 511291 + 597 511300 Sb-130 5.77200E-03 1.13570E-02 511300 + 598 511301 Sb-130m 5.77200E-03 8.75430E-03 511301 + 599 511310 Sb-131 1.71430E-02 2.08790E-02 511310 + 600 511320 Sb-132 7.28840E-03 8.55430E-03 511320 + 601 511321 Sb-132m 5.37160E-03 5.37160E-03 511321 + 602 511330 Sb-133 7.57460E-03 7.66010E-03 511330 + 603 511340 Sb-134 3.71310E-04 3.80000E-04 511340 + 604 511341 Sb-134m 8.69690E-04 8.69700E-04 511341 + 605 511350 Sb-135 1.67750E-04 1.67800E-04 511350 + 606 511360 Sb-136 1.12130E-05 1.12150E-05 511360 + 607 511370 Sb-137 1.60750E-06 1.60750E-06 511370 + 608 511380 Sb-138 8.34470E-09 8.34470E-09 511380 + 609 521250 Te-125 7.41890E-11 1.17190E-03 52125.82c + 610 521251 Te-125m 2.42720E-10 2.62240E-04 521251 + 611 521260 Te-126 1.77160E-06 6.72950E-05 52126.82c + 612 521270 Te-127 4.61050E-06 4.54180E-03 521270 + 613 521271 Te-127m 1.11300E-05 7.60010E-04 52527.82c + 614 521280 Te-128 1.06540E-04 1.00630E-02 52128.82c + 615 521290 Te-129 2.60520E-04 1.44730E-02 521290 + 616 521291 Te-129m 6.28930E-04 7.30510E-03 52529.82c + 617 521300 Te-130 4.75900E-03 2.48700E-02 52130.82c + 618 521310 Te-131 4.32120E-03 2.60700E-02 521310 + 619 521311 Te-131m 1.04320E-02 1.21030E-02 521311 + 620 521320 Te-132 3.22030E-02 4.61290E-02 52132.82c + 621 521330 Te-133 1.28380E-02 2.48300E-02 521330 + 622 521331 Te-133m 3.09930E-02 3.23180E-02 521331 + 623 521340 Te-134 3.64200E-02 3.76950E-02 521340 + 624 521350 Te-135 1.04830E-02 1.06260E-02 521350 + 625 521360 Te-136 3.94400E-03 3.95410E-03 521360 + 626 521370 Te-137 7.11370E-04 7.12190E-04 521370 + 627 521380 Te-138 1.14680E-04 1.14690E-04 521380 + 628 521390 Te-139 7.67670E-06 7.67670E-06 521390 + 629 521400 Te-140 1.15430E-06 1.15430E-06 521400 + 630 521410 Te-141 1.70380E-09 1.70380E-09 521410 + 631 531270 I-127 1.48290E-10 4.56010E-03 53127.82c + 632 531280 I-128 1.15900E-06 1.15900E-06 531280 + 633 531290 I-129 2.22750E-06 1.71780E-02 53129.82c + 634 531300 I-130 1.82680E-05 2.48190E-05 53130.82c + 635 531301 I-130m 7.79920E-06 7.79920E-06 531301 + 636 531310 I-131 3.13170E-04 3.59450E-02 53131.82c + 637 531320 I-132 1.16900E-03 4.80390E-02 531320 + 638 531321 I-132m 8.61540E-04 8.61540E-04 531321 + 639 531330 I-133 5.21000E-03 5.98860E-02 531330 + 640 531331 I-133m 3.18380E-03 3.18380E-03 531331 + 641 531340 I-134 1.30360E-02 6.01170E-02 531340 + 642 531341 I-134m 9.60740E-03 9.60740E-03 531341 + 643 531350 I-135 3.35840E-02 4.42100E-02 53135.82c + 644 531360 I-136 7.44620E-03 1.14110E-02 531360 + 645 531361 I-136m 1.74410E-02 1.74520E-02 531361 + 646 531370 I-137 1.16540E-02 1.23520E-02 531370 + 647 531380 I-138 3.47620E-03 3.58370E-03 531380 + 648 531390 I-139 1.50360E-03 1.51130E-03 531390 + 649 531400 I-140 2.62340E-04 2.63490E-04 531400 + 650 531410 I-141 3.67190E-05 3.67210E-05 531410 + 651 531420 I-142 4.28700E-07 4.28700E-07 531420 + 652 531430 I-143 1.21240E-08 1.21240E-08 531430 + 653 541300 Xe-130 8.74330E-09 2.60760E-05 54130.82c + 654 541310 Xe-131 3.08890E-07 3.59460E-02 54131.82c + 655 541311 Xe-131m 7.45710E-07 3.91180E-04 541311 + 656 541320 Xe-132 2.31750E-05 4.82090E-02 54132.82c + 657 541321 Xe-132m 2.62710E-05 2.62710E-05 541321 + 658 541330 Xe-133 1.19090E-04 6.02920E-02 54133.82c + 659 541331 Xe-133m 2.87510E-04 1.99210E-03 541331 + 660 541340 Xe-134 7.92730E-04 6.29880E-02 54134.82c + 661 541341 Xe-134m 1.85680E-03 2.07770E-03 541341 + 662 541350 Xe-135 3.03390E-03 5.44810E-02 54135.82c + 663 541351 Xe-135m 7.32410E-03 1.46230E-02 541351 + 664 541360 Xe-136 4.98250E-02 7.94900E-02 54136.82c + 665 541370 Xe-137 4.62640E-02 5.80030E-02 541370 + 666 541380 Xe-138 4.37080E-02 4.72500E-02 541380 + 667 541390 Xe-139 2.56710E-02 2.70590E-02 541390 + 668 541400 Xe-140 1.66130E-02 1.68600E-02 541400 + 669 541410 Xe-141 5.92880E-03 5.95790E-03 541410 + 670 541420 Xe-142 1.42410E-03 1.42440E-03 541420 + 671 541430 Xe-143 1.66560E-04 1.66570E-04 541430 + 672 541440 Xe-144 1.55740E-05 1.55740E-05 541440 + 673 541450 Xe-145 4.29780E-08 4.29780E-08 541450 + 674 541460 Xe-146 9.77500E-10 9.77500E-10 541460 + 675 551320 Cs-132 1.11610E-09 1.11610E-09 551320 + 676 551330 Cs-133 1.32460E-07 6.02920E-02 55133.82c + 677 551340 Cs-134 1.81700E-06 3.15620E-06 55134.82c + 678 551341 Cs-134m 1.33920E-06 1.33920E-06 551341 + 679 551350 Cs-135 3.09870E-05 5.46180E-02 55135.82c + 680 551351 Cs-135m 1.89350E-05 1.89350E-05 551351 + 681 551360 Cs-136 3.95920E-04 5.11940E-04 55136.82c + 682 551361 Cs-136m 2.32030E-04 2.32030E-04 551361 + 683 551370 Cs-137 4.60350E-03 6.26070E-02 55137.82c + 684 551380 Cs-138 4.88230E-03 5.77440E-02 551380 + 685 551381 Cs-138m 6.92770E-03 6.92770E-03 551381 + 686 551390 Cs-139 2.48830E-02 5.19420E-02 551390 + 687 551400 Cs-140 2.74570E-02 4.43190E-02 551400 + 688 551410 Cs-141 2.82850E-02 3.42450E-02 551410 + 689 551420 Cs-142 1.57210E-02 1.71420E-02 551420 + 690 551430 Cs-143 6.66460E-03 6.83000E-03 551430 + 691 551440 Cs-144 8.27100E-04 1.25580E-03 551440 + 692 551441 Cs-144m 8.27100E-04 8.27100E-04 551441 + 693 551450 Cs-145 2.54400E-04 2.54440E-04 551450 + 694 551460 Cs-146 2.64830E-05 2.64840E-05 551460 + 695 551470 Cs-147 9.01520E-07 9.01520E-07 551470 + 696 551480 Cs-148 1.85510E-09 1.85510E-09 551480 + 697 561350 Ba-135 3.88300E-09 1.32570E-08 56135.82c + 698 561351 Ba-135m 9.37400E-09 9.37400E-09 561351 + 699 561360 Ba-136 5.59260E-07 6.29820E-04 56136.82c + 700 561361 Ba-136m 1.30990E-06 1.30990E-06 561361 + 701 561370 Ba-137 1.90810E-05 6.26720E-02 56137.82c + 702 561371 Ba-137m 4.60650E-05 5.91460E-02 561371 + 703 561380 Ba-138 1.25820E-03 6.03180E-02 56138.82c + 704 561390 Ba-139 4.93030E-03 5.68720E-02 561390 + 705 561400 Ba-140 2.04810E-02 6.48000E-02 56140.82c + 706 561410 Ba-141 2.76150E-02 6.18600E-02 561410 + 707 561420 Ba-142 4.89210E-02 6.61750E-02 561420 + 708 561430 Ba-143 4.24730E-02 4.92310E-02 561430 + 709 561440 Ba-144 2.62540E-02 2.79190E-02 561440 + 710 561450 Ba-145 9.93550E-03 1.01570E-02 561450 + 711 561460 Ba-146 2.75000E-03 2.77300E-03 561460 + 712 561470 Ba-147 6.18090E-04 6.18740E-04 561470 + 713 561480 Ba-148 8.83900E-05 8.83910E-05 561480 + 714 561490 Ba-149 3.25650E-06 3.25650E-06 561490 + 715 561500 Ba-150 8.67540E-09 8.67540E-09 561500 + 716 561510 Ba-151 9.25070E-11 9.25070E-11 561510 + 717 571370 La-137 1.99460E-09 1.99460E-09 571370 + 718 571380 La-138 9.04040E-08 9.04040E-08 57138.82c + 719 571390 La-139 2.59230E-05 5.68980E-02 57139.82c + 720 571400 La-140 1.53840E-04 6.49540E-02 57140.82c + 721 571410 La-141 1.05000E-03 6.29100E-02 571410 + 722 571420 La-142 2.45210E-03 6.86270E-02 571420 + 723 571430 La-143 9.95470E-03 5.91860E-02 571430 + 724 571440 La-144 1.59620E-02 4.38810E-02 571440 + 725 571450 La-145 1.73360E-02 2.74930E-02 571450 + 726 571460 La-146 3.44800E-03 6.22100E-03 571460 + 727 571461 La-146m 6.20230E-03 6.20230E-03 571461 + 728 571470 La-147 5.16500E-03 5.78410E-03 571470 + 729 571480 La-148 1.81460E-03 1.90270E-03 571480 + 730 571490 La-149 4.38560E-04 4.41800E-04 571490 + 731 571500 La-150 5.59500E-05 5.59590E-05 571500 + 732 571510 La-151 9.96300E-06 9.96310E-06 571510 + 733 571520 La-152 1.78710E-06 1.78710E-06 571520 + 734 571530 La-153 2.72420E-10 2.72420E-10 571530 + 735 581400 Ce-140 1.15430E-06 6.49550E-02 58140.82c + 736 581410 Ce-141 1.54140E-05 6.29260E-02 58141.82c + 737 581420 Ce-142 1.76070E-04 6.88030E-02 58142.82c + 738 581430 Ce-143 5.66530E-04 5.97520E-02 58143.82c + 739 581440 Ce-144 3.25050E-03 4.71320E-02 58144.82c + 740 581450 Ce-145 6.87990E-03 3.43730E-02 581450 + 741 581460 Ce-146 1.30270E-02 2.54500E-02 581460 + 742 581470 Ce-147 1.20740E-02 1.78580E-02 581470 + 743 581480 Ce-148 9.65960E-03 1.15680E-02 581480 + 744 581490 Ce-149 4.68290E-03 5.12000E-03 581490 + 745 581500 Ce-150 1.85560E-03 1.91000E-03 581500 + 746 581510 Ce-151 5.56920E-04 5.66990E-04 581510 + 747 581520 Ce-152 8.35040E-05 8.51830E-05 581520 + 748 581530 Ce-153 9.03060E-06 9.03090E-06 581530 + 749 581540 Ce-154 2.73550E-08 2.73550E-08 581540 + 750 581550 Ce-155 2.96470E-10 2.96470E-10 581550 + 751 581560 Ce-156 4.42760E-12 4.42760E-12 581560 + 752 591420 Pr-142 4.66450E-10 1.55900E-09 59142.82c + 753 591421 Pr-142m 1.09250E-09 1.09250E-09 591421 + 754 591430 Pr-143 1.29320E-07 5.97530E-02 59143.82c + 755 591440 Pr-144 6.06580E-07 4.71380E-02 591440 + 756 591441 Pr-144m 5.38730E-06 6.55780E-04 591441 + 757 591450 Pr-145 5.32860E-05 3.44260E-02 591450 + 758 591460 Pr-146 1.85250E-04 2.56350E-02 591460 + 759 591470 Pr-147 7.00570E-04 1.85590E-02 591470 + 760 591480 Pr-148 2.78560E-04 1.18470E-02 591480 + 761 591481 Pr-148m 1.17150E-03 1.17150E-03 591481 + 762 591490 Pr-149 2.42520E-03 7.54520E-03 591490 + 763 591500 Pr-150 2.21810E-03 4.12810E-03 591500 + 764 591510 Pr-151 1.61810E-03 2.18510E-03 591510 + 765 591520 Pr-152 6.56310E-04 7.41550E-04 591520 + 766 591530 Pr-153 2.36630E-04 2.45600E-04 591530 + 767 591540 Pr-154 3.03830E-05 3.04100E-05 591540 + 768 591550 Pr-155 1.98200E-06 1.98230E-06 591550 + 769 591560 Pr-156 1.00360E-06 1.00360E-06 591560 + 770 591570 Pr-157 6.16230E-10 6.16230E-10 591570 + 771 591580 Pr-158 6.36380E-12 6.36380E-12 591580 + 772 601450 Nd-145 1.10530E-06 3.44280E-02 60145.82c + 773 601460 Nd-146 1.96340E-06 2.56380E-02 60146.82c + 774 601470 Nd-147 1.62500E-05 1.85750E-02 60147.82c + 775 601480 Nd-148 1.09890E-04 1.31280E-02 60148.82c + 776 601490 Nd-149 2.91910E-04 7.83710E-03 601490 + 777 601500 Nd-150 8.23960E-04 4.95210E-03 60150.82c + 778 601510 Nd-151 1.22140E-03 3.40650E-03 601510 + 779 601520 Nd-152 1.22070E-03 1.96230E-03 601520 + 780 601530 Nd-153 1.00880E-03 1.25440E-03 601530 + 781 601540 Nd-154 3.14080E-04 3.44490E-04 601540 + 782 601550 Nd-155 1.03980E-04 1.05990E-04 601550 + 783 601560 Nd-156 2.40790E-05 2.50550E-05 601560 + 784 601570 Nd-157 5.51070E-07 5.51650E-07 601570 + 785 601580 Nd-158 5.09200E-08 5.09260E-08 601580 + 786 601590 Nd-159 3.80970E-10 3.80970E-10 601590 + 787 601600 Nd-160 4.51760E-12 4.51760E-12 601600 + 788 611470 Pm-147 6.01750E-10 1.85750E-02 61147.82c + 789 611480 Pm-148 5.92060E-09 6.61390E-09 61148.82c + 790 611481 Pm-148m 1.38670E-08 1.38670E-08 61548.82c + 791 611490 Pm-149 8.14270E-07 7.83790E-03 61149.82c + 792 611500 Pm-150 2.55250E-06 2.55250E-06 611500 + 793 611510 Pm-151 2.72180E-05 3.43370E-03 61151.82c + 794 611520 Pm-152 8.93550E-06 1.97120E-03 611520 + 795 611521 Pm-152m 1.78430E-05 1.78430E-05 611521 + 796 611522 Pm-152m 1.97360E-05 1.97360E-05 611522 + 797 611530 Pm-153 1.22180E-04 1.37660E-03 611530 + 798 611540 Pm-154 5.28500E-05 3.97340E-04 611540 + 799 611541 Pm-154m 5.28500E-05 5.28500E-05 611541 + 800 611550 Pm-155 1.16000E-04 2.21990E-04 611550 + 801 611560 Pm-156 4.91730E-05 7.42280E-05 611560 + 802 611570 Pm-157 2.74820E-05 2.80340E-05 611570 + 803 611580 Pm-158 1.20530E-05 1.21040E-05 611580 + 804 611590 Pm-159 2.45330E-07 2.45710E-07 611590 + 805 611600 Pm-160 5.82670E-09 5.83120E-09 611600 + 806 611610 Pm-161 2.74690E-10 2.74690E-10 611610 + 807 611620 Pm-162 2.53920E-12 2.53920E-12 611620 + 808 621500 Sm-150 1.73510E-09 2.55420E-06 62150.82c + 809 621510 Sm-151 9.06490E-07 3.43460E-03 62151.82c + 810 621520 Sm-152 7.05230E-07 2.00950E-03 62152.82c + 811 621530 Sm-153 3.30920E-06 1.38790E-03 62153.82c + 812 621531 Sm-153m 7.98880E-06 7.98880E-06 621531 + 813 621540 Sm-154 1.84060E-05 4.68600E-04 62154.82c + 814 621550 Sm-155 2.08180E-05 2.42810E-04 621550 + 815 621560 Sm-156 4.01630E-05 1.14390E-04 621560 + 816 621570 Sm-157 3.92760E-05 6.73100E-05 621570 + 817 621580 Sm-158 3.01390E-05 4.22430E-05 621580 + 818 621590 Sm-159 4.62130E-06 4.86700E-06 621590 + 819 621600 Sm-160 2.53780E-06 2.54360E-06 621600 + 820 621610 Sm-161 6.07210E-08 6.09960E-08 621610 + 821 621620 Sm-162 4.60760E-09 4.61010E-09 621620 + 822 621630 Sm-163 1.18910E-10 1.18910E-10 621630 + 823 621640 Sm-164 3.00530E-12 3.00530E-12 621640 + 824 631520 Eu-152 1.95150E-11 4.12800E-11 63152.82c + 825 631521 Eu-152m 4.64790E-12 4.64790E-12 631521 + 826 631522 Eu-152m 2.17650E-11 2.17650E-11 631522 + 827 631530 Eu-153 2.86040E-09 1.38790E-03 63153.82c + 828 631540 Eu-154 1.13320E-08 2.15390E-08 63154.82c + 829 631541 Eu-154m 1.02070E-08 1.02070E-08 631541 + 830 631550 Eu-155 2.83930E-07 2.43090E-04 63155.82c + 831 631560 Eu-156 9.55340E-07 1.15350E-04 63156.82c + 832 631570 Eu-157 4.69740E-06 7.20070E-05 63157.82c + 833 631580 Eu-158 2.00920E-06 4.42520E-05 631580 + 834 631590 Eu-159 4.62160E-06 9.48860E-06 631590 + 835 631600 Eu-160 1.29370E-06 3.83730E-06 631600 + 836 631610 Eu-161 7.58090E-07 8.19090E-07 631610 + 837 631620 Eu-162 9.84610E-08 1.03070E-07 631620 + 838 631630 Eu-163 1.93270E-08 1.94460E-08 631630 + 839 631640 Eu-164 9.48530E-10 9.51540E-10 631640 + 840 631650 Eu-165 5.82890E-11 5.82890E-11 631650 + 841 631660 Eu-166 1.06910E-12 1.06910E-12 631660 + 842 641550 Gd-155 1.73670E-11 2.43090E-04 64155.82c + 843 641551 Gd-155m 4.19270E-11 4.19270E-11 641551 + 844 641560 Gd-156 1.68690E-09 1.15350E-04 64156.82c + 845 641570 Gd-157 1.63900E-08 7.20230E-05 64157.82c + 846 641580 Gd-158 2.00930E-06 4.62610E-05 64158.82c + 847 641590 Gd-159 2.36600E-07 9.72520E-06 641590 + 848 641600 Gd-160 4.20820E-07 4.25810E-06 64160.82c + 849 641610 Gd-161 3.77520E-07 1.19660E-06 641610 + 850 641620 Gd-162 3.02780E-07 4.05850E-07 641620 + 851 641630 Gd-163 9.13700E-08 1.10820E-07 641630 + 852 641640 Gd-164 3.05390E-08 3.14900E-08 641640 + 853 641650 Gd-165 3.33440E-09 3.39270E-09 641650 + 854 641660 Gd-166 4.79180E-10 4.80250E-10 641660 + 855 641670 Gd-167 1.91010E-11 1.91010E-11 641670 + 856 651570 Tb-157 2.18520E-12 2.18520E-12 651570 + 857 651580 Tb-158 6.00590E-11 6.67800E-11 651580 + 858 651581 Tb-158m 6.76230E-12 6.76230E-12 651581 + 859 651590 Tb-159 6.01180E-10 9.72580E-06 65159.82c + 860 651600 Tb-160 2.06870E-09 2.06870E-09 65160.82c + 861 651610 Tb-161 1.40410E-08 1.21070E-06 651610 + 862 651620 Tb-162 1.91530E-08 4.25000E-07 651620 + 863 651630 Tb-163 3.77180E-08 1.48530E-07 651630 + 864 651640 Tb-164 1.89300E-08 5.04200E-08 651640 + 865 651650 Tb-165 1.28690E-08 1.62620E-08 651650 + 866 651660 Tb-166 2.93320E-09 3.41350E-09 651660 + 867 651670 Tb-167 8.27780E-10 8.46880E-10 651670 + 868 651680 Tb-168 6.28230E-11 6.28230E-11 651680 + 869 651690 Tb-169 7.38580E-12 7.38580E-12 651690 + 870 661610 Dy-161 1.21500E-11 1.21070E-06 66161.82c + 871 661620 Dy-162 1.35520E-10 4.25140E-07 66162.82c + 872 661630 Dy-163 5.03160E-10 1.49040E-07 66163.82c + 873 661640 Dy-164 1.84570E-09 5.22670E-08 66164.82c + 874 661650 Dy-165 1.78040E-09 1.83080E-08 661650 + 875 661651 Dy-165m 2.72170E-10 2.72170E-10 661651 + 876 661660 Dy-166 2.96360E-09 6.37710E-09 661660 + 877 661670 Dy-167 1.24840E-09 2.09530E-09 661670 + 878 661680 Dy-168 6.02530E-10 6.65350E-10 661680 + 879 661690 Dy-169 1.16580E-10 1.23970E-10 661690 + 880 661700 Dy-170 2.76940E-11 2.76940E-11 661700 + 881 661710 Dy-171 1.72530E-12 1.72530E-12 661710 + 882 671640 Ho-164 6.87710E-13 2.29850E-12 671640 + 883 671641 Ho-164m 1.61080E-12 1.61080E-12 671641 + 884 671650 Ho-165 2.04620E-11 1.83350E-08 67165.82c + 885 671660 Ho-166 1.61680E-11 6.39320E-09 671660 + 886 671661 Ho-166m 3.78700E-11 3.78700E-11 671661 + 887 671670 Ho-167 1.60190E-10 2.25550E-09 671670 + 888 671680 Ho-168 5.04220E-11 7.86960E-10 671680 + 889 671681 Ho-168m 7.15480E-11 7.15480E-11 671681 + 890 671690 Ho-169 1.46620E-10 2.70590E-10 671690 + 891 671700 Ho-170 3.67320E-11 3.67320E-11 671700 + 892 671701 Ho-170m 1.56820E-11 4.33760E-11 671701 + 893 671710 Ho-171 2.14230E-11 2.31480E-11 671710 + 894 671720 Ho-172 2.78660E-12 2.78660E-12 671720 + 895 681680 Er-168 3.29970E-12 7.90620E-10 68168.82c + 896 681690 Er-169 7.00880E-12 2.77600E-10 681690 + 897 681700 Er-170 1.69600E-11 9.70680E-11 68170.82c + 898 681710 Er-171 1.06150E-11 3.37630E-11 681710 + 899 681720 Er-172 8.52600E-12 1.13130E-11 681720 + 900 681730 Er-173 2.57900E-12 2.57900E-12 681730 + 901 691730 Tm-173 1.05920E-12 3.63820E-12 691730 + + Neutron-induced fission: + + Interpolation region : 2 / 3 + Interpolation energy : 4.00000E-01 MeV + Number of products : 986 / 1051 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 3.33770E-05 3.33770E-05 1001.82c + 2 10020 H-2 1.02000E-05 1.02000E-05 1002.82c + 3 10030 H-3 1.14000E-04 1.14000E-04 1003.82c + 4 20040 He-4 2.11000E-03 2.11000E-03 2004.82c + 5 190500 K-50 1.12580E-11 1.12580E-11 190500 + 6 190510 K-51 2.53560E-12 2.53560E-12 190510 + 7 200500 Ca-50 4.53140E-10 4.62330E-10 200500 + 8 200510 Ca-51 1.87210E-10 1.88550E-10 200510 + 9 200520 Ca-52 9.94480E-11 9.94480E-11 200520 + 10 200530 Ca-53 1.58120E-11 1.58120E-11 200530 + 11 200540 Ca-54 2.51390E-12 2.51390E-12 200540 + 12 210500 Sc-50 2.60110E-10 8.10890E-10 210500 + 13 210501 Sc-50m 9.54270E-11 5.57750E-10 210501 + 14 210510 Sc-51 8.80700E-10 1.07120E-09 210510 + 15 210520 Sc-52 7.66380E-10 8.68580E-10 210520 + 16 210530 Sc-53 8.34800E-10 8.45870E-10 210530 + 17 210540 Sc-54 2.50880E-10 2.53390E-10 210540 + 18 210550 Sc-55 1.11020E-10 1.11020E-10 210550 + 19 210560 Sc-56 1.43950E-11 1.43950E-11 210560 + 20 210570 Sc-57 1.85280E-12 1.85280E-12 210570 + 21 220500 Ti-50 4.30700E-11 8.60930E-10 22050.82c + 22 220510 Ti-51 1.75490E-10 1.24670E-09 220510 + 23 220520 Ti-52 9.17710E-10 1.78630E-09 220520 + 24 220530 Ti-53 1.52440E-09 2.37030E-09 220530 + 25 220540 Ti-54 2.81120E-09 3.06460E-09 220540 + 26 220550 Ti-55 2.11090E-09 2.22190E-09 220550 + 27 220560 Ti-56 1.93960E-09 1.95460E-09 220560 + 28 220570 Ti-57 4.84350E-10 4.85590E-10 220570 + 29 220580 Ti-58 1.42360E-10 1.42360E-10 220580 + 30 220590 Ti-59 1.49890E-11 1.49890E-11 220590 + 31 220600 Ti-60 1.53260E-12 1.53260E-12 220600 + 32 230510 V-51 2.20530E-12 1.24890E-09 230510 + 33 230520 V-52 2.12360E-11 1.80750E-09 230520 + 34 230530 V-53 2.34200E-10 2.60450E-09 230530 + 35 230540 V-54 6.87990E-10 3.75260E-09 230540 + 36 230550 V-55 3.06090E-09 5.28280E-09 230550 + 37 230560 V-56 4.33800E-09 6.29410E-09 230560 + 38 230570 V-57 6.85480E-09 7.33890E-09 230570 + 39 230580 V-58 3.54320E-09 3.68560E-09 230580 + 40 230590 V-59 2.72560E-09 2.74060E-09 230590 + 41 230600 V-60 5.53130E-10 5.54660E-10 230600 + 42 230610 V-61 1.34300E-10 1.34300E-10 230610 + 43 230620 V-62 1.01900E-11 1.01900E-11 230620 + 44 240530 Cr-53 1.02100E-12 2.60550E-09 24053.82c + 45 240540 Cr-54 2.21410E-11 3.77470E-09 24054.82c + 46 240550 Cr-55 1.75470E-10 5.45830E-09 240550 + 47 240560 Cr-56 1.59330E-09 7.91670E-09 240560 + 48 240570 Cr-57 3.91060E-09 1.41690E-08 240570 + 49 240580 Cr-58 1.19500E-08 1.26870E-08 240580 + 50 240590 Cr-59 1.44950E-08 1.72360E-08 240590 + 51 240600 Cr-60 1.92730E-08 1.98360E-08 240600 + 52 240610 Cr-61 8.51520E-09 8.64140E-09 240610 + 53 240620 Cr-62 4.84890E-09 4.85910E-09 240620 + 54 240630 Cr-63 8.08250E-10 8.08250E-10 240630 + 55 240640 Cr-64 1.36710E-10 1.36710E-10 240640 + 56 240650 Cr-65 8.45900E-12 8.45900E-12 240650 + 57 250560 Mn-56 9.41680E-12 7.92610E-09 250560 + 58 250570 Mn-57 1.65710E-10 1.43340E-08 250570 + 59 250580 Mn-58 7.92660E-10 1.34800E-08 250580 + 60 250581 Mn-58m 7.79170E-11 7.79170E-11 250581 + 61 250590 Mn-59 6.54860E-09 2.37840E-08 250590 + 62 250600 Mn-60 1.19180E-09 2.24220E-08 250600 + 63 250601 Mn-60m 1.21240E-08 1.21240E-08 250601 + 64 250610 Mn-61 3.51290E-08 4.37700E-08 250610 + 65 250620 Mn-62 2.80990E-08 3.05290E-08 250620 + 66 250621 Mn-62m 4.40050E-09 6.83000E-09 250621 + 67 250630 Mn-63 3.67920E-08 3.76000E-08 250630 + 68 250640 Mn-64 1.16820E-08 1.18190E-08 250640 + 69 250650 Mn-65 5.54710E-09 5.55560E-09 250650 + 70 250660 Mn-66 7.61750E-10 7.61750E-10 250660 + 71 250670 Mn-67 1.04640E-10 1.04640E-10 250670 + 72 250680 Mn-68 4.24850E-12 4.24850E-12 250680 + 73 260580 Fe-58 6.91200E-12 1.35650E-08 26058.82c + 74 260590 Fe-59 9.92840E-11 2.38840E-08 260590 + 75 260600 Fe-60 1.40080E-09 3.45520E-08 260600 + 76 260610 Fe-61 6.13040E-09 4.99010E-08 260610 + 77 260620 Fe-62 3.42600E-08 7.16190E-08 260620 + 78 260630 Fe-63 5.90890E-08 9.66890E-08 260630 + 79 260640 Fe-64 1.14380E-07 1.26200E-07 260640 + 80 260650 Fe-65 9.13420E-08 9.68980E-08 260650 + 81 260660 Fe-66 8.81780E-08 8.89400E-08 260660 + 82 260670 Fe-67 2.33640E-08 2.34690E-08 260670 + 83 260680 Fe-68 7.41730E-09 7.42150E-09 260680 + 84 260690 Fe-69 4.33910E-10 4.33910E-10 260690 + 85 260700 Fe-70 1.29350E-10 1.29350E-10 260700 + 86 260710 Fe-71 1.03410E-12 1.03410E-12 260710 + 87 270600 Co-60 1.45130E-12 1.98240E-12 270600 + 88 270610 Co-61 6.60820E-11 4.99670E-08 270610 + 89 270620 Co-62 1.83920E-10 7.18080E-08 270620 + 90 270621 Co-62m 5.01310E-10 5.01310E-10 270621 + 91 270630 Co-63 7.91620E-09 1.04610E-07 270630 + 92 270640 Co-64 2.45910E-08 1.50790E-07 270640 + 93 270650 Co-65 1.16640E-07 2.13540E-07 270650 + 94 270660 Co-66 1.73010E-07 2.61950E-07 270660 + 95 270670 Co-67 2.87750E-07 3.11220E-07 270670 + 96 270680 Co-68 9.11810E-08 1.28940E-07 270680 + 97 270681 Co-68m 6.80590E-08 7.55110E-08 270681 + 98 270690 Co-69 6.75810E-08 6.79840E-08 270690 + 99 270700 Co-70 1.98840E-08 1.98840E-08 270700 + 100 270701 Co-70m 1.98840E-08 2.00130E-08 270701 + 101 270710 Co-71 2.51230E-09 2.51330E-09 270710 + 102 270720 Co-72 3.52860E-10 3.52860E-10 270720 + 103 270730 Co-73 5.27660E-11 5.27660E-11 270730 + 104 270740 Co-74 5.64890E-12 5.64890E-12 270740 + 105 280620 Ni-62 1.27360E-12 7.23060E-08 28062.82c + 106 280630 Ni-63 2.95100E-11 1.04630E-07 280630 + 107 280640 Ni-64 6.81120E-10 1.51470E-07 28064.82c + 108 280650 Ni-65 5.80350E-09 2.19340E-07 280650 + 109 280660 Ni-66 5.56280E-08 3.17580E-07 280660 + 110 280670 Ni-67 1.44490E-07 4.55710E-07 280670 + 111 280680 Ni-68 4.72430E-07 6.39800E-07 280680 + 112 280690 Ni-69 1.57090E-07 2.24390E-07 280690 + 113 280691 Ni-69m 1.57090E-07 1.57090E-07 280691 + 114 280700 Ni-70 1.97650E-06 2.01640E-06 280700 + 115 280710 Ni-71 1.36910E-07 1.39420E-07 280710 + 116 280720 Ni-72 1.43420E-07 1.43770E-07 280720 + 117 280730 Ni-73 4.32080E-08 4.32610E-08 280730 + 118 280740 Ni-74 3.67250E-08 3.67310E-08 280740 + 119 280750 Ni-75 4.45300E-09 4.45300E-09 280750 + 120 280760 Ni-76 3.67780E-10 3.67780E-10 280760 + 121 280770 Ni-77 1.12950E-11 1.12950E-11 280770 + 122 290650 Cu-65 1.49430E-11 2.19360E-07 29065.82c + 123 290660 Cu-66 2.81920E-10 3.17860E-07 290660 + 124 290670 Cu-67 5.28950E-09 4.61000E-07 290670 + 125 290680 Cu-68 8.05170E-09 6.66290E-07 290680 + 126 290681 Cu-68m 2.19470E-08 2.19470E-08 290681 + 127 290690 Cu-69 5.21360E-07 9.02830E-07 290690 + 128 290700 Cu-70 4.94580E-08 4.16920E-07 290700 + 129 290701 Cu-70m 6.31620E-07 7.34920E-07 290701 + 130 290702 Cu-70m 4.94580E-08 2.06580E-06 290702 + 131 290710 Cu-71 6.88960E-07 8.28380E-07 290710 + 132 290720 Cu-72 8.36910E-07 9.80680E-07 290720 + 133 290730 Cu-73 8.95790E-07 9.39050E-07 290730 + 134 290740 Cu-74 2.68880E-06 2.72560E-06 290740 + 135 290750 Cu-75 6.41940E-06 6.42380E-06 290750 + 136 290760 Cu-76 2.09660E-07 2.09840E-07 290760 + 137 290761 Cu-76m 2.09660E-07 2.09840E-07 290761 + 138 290770 Cu-77 1.33660E-07 1.33670E-07 290770 + 139 290780 Cu-78 7.12380E-09 7.12380E-09 290780 + 140 290790 Cu-79 5.19120E-10 5.19120E-10 290790 + 141 300670 Zn-67 4.59790E-12 4.61000E-07 300670 + 142 300680 Zn-68 2.03600E-10 6.70000E-07 300680 + 143 300690 Zn-69 2.72500E-10 9.04460E-07 300690 + 144 300691 Zn-69m 1.35340E-09 1.35340E-09 300691 + 145 300700 Zn-70 6.66700E-08 2.81360E-06 300700 + 146 300710 Zn-71 1.26850E-08 8.41070E-07 300710 + 147 300711 Zn-71m 6.30030E-08 6.30030E-08 300711 + 148 300720 Zn-72 1.80880E-06 2.78950E-06 300720 + 149 300730 Zn-73 2.35660E-07 2.56350E-06 300730 + 150 300731 Zn-73m 3.25940E-07 1.38880E-06 300731 + 151 300732 Zn-73m 2.12580E-06 2.12580E-06 300732 + 152 300740 Zn-74 2.48990E-05 2.78490E-05 300740 + 153 300750 Zn-75 4.62510E-05 5.24560E-05 300750 + 154 300760 Zn-76 7.50520E-05 7.54650E-05 300760 + 155 300770 Zn-77 4.01400E-05 4.29450E-05 300770 + 156 300771 Zn-77m 5.34440E-06 5.34440E-06 300771 + 157 300780 Zn-78 2.97130E-05 2.97200E-05 300780 + 158 300790 Zn-79 4.32190E-06 4.32210E-06 300790 + 159 300800 Zn-80 8.97490E-07 8.97490E-07 300800 + 160 300810 Zn-81 6.78380E-09 6.78380E-09 300810 + 161 300820 Zn-82 3.86160E-10 3.86160E-10 300820 + 162 310700 Ga-70 8.04910E-11 8.04910E-11 310700 + 163 310710 Ga-71 6.99330E-10 9.04770E-07 310710 + 164 310720 Ga-72 1.22090E-08 2.80290E-06 310720 + 165 310721 Ga-72m 1.20010E-09 9.41470E-08 310721 + 166 310730 Ga-73 8.95630E-07 4.52210E-06 310730 + 167 310740 Ga-74 1.08240E-06 2.27810E-05 310740 + 168 310741 Ga-74m 1.08240E-06 2.89320E-05 310741 + 169 310750 Ga-75 2.56500E-05 7.81060E-05 310750 + 170 310760 Ga-76 5.06120E-05 1.26080E-04 310760 + 171 310770 Ga-77 2.03990E-04 2.49610E-04 310770 + 172 310780 Ga-78 1.56330E-04 1.86110E-04 310780 + 173 310790 Ga-79 2.08400E-04 2.12670E-04 310790 + 174 310800 Ga-80 6.46150E-05 6.55130E-05 310800 + 175 310810 Ga-81 3.16500E-05 3.16560E-05 310810 + 176 310820 Ga-82 2.36290E-06 2.36330E-06 310820 + 177 310830 Ga-83 1.67440E-07 1.67440E-07 310830 + 178 310840 Ga-84 5.18410E-09 5.18410E-09 310840 + 179 320720 Ge-72 2.11970E-11 2.80290E-06 32072.82c + 180 320730 Ge-73 7.42200E-10 4.52290E-06 32073.82c + 181 320731 Ge-73m 1.49440E-10 4.45580E-06 320731 + 182 320740 Ge-74 1.03480E-07 3.01180E-05 32074.82c + 183 320750 Ge-75 1.50620E-07 7.93870E-05 320750 + 184 320751 Ge-75m 1.13130E-06 4.25550E-06 320751 + 185 320760 Ge-76 1.61930E-05 1.42270E-04 32076.82c + 186 320770 Ge-77 1.42930E-04 1.93970E-04 320770 + 187 320771 Ge-77m 1.90300E-05 2.68640E-04 320771 + 188 320780 Ge-78 4.43210E-04 6.29510E-04 320780 + 189 320790 Ge-79 1.10170E-04 3.55430E-04 320790 + 190 320791 Ge-79m 8.27420E-04 8.27740E-04 320791 + 191 320800 Ge-80 1.32510E-03 1.39440E-03 320800 + 192 320810 Ge-81 9.01320E-04 9.18250E-04 320810 + 193 320811 Ge-81m 1.81480E-04 1.94890E-04 320811 + 194 320820 Ge-82 8.09230E-04 8.11150E-04 320820 + 195 320830 Ge-83 2.33410E-04 2.33520E-04 320830 + 196 320840 Ge-84 5.47020E-05 5.47040E-05 320840 + 197 320850 Ge-85 2.01300E-06 2.01300E-06 320850 + 198 320860 Ge-86 1.11280E-07 1.11280E-07 320860 + 199 320870 Ge-87 2.16670E-09 2.16670E-09 320870 + 200 330740 As-74 2.82450E-11 2.82450E-11 330740 + 201 330750 As-75 7.90350E-10 7.93920E-05 33075.82c + 202 330751 As-75m 2.99310E-09 4.26970E-09 330751 + 203 330760 As-76 8.77760E-08 8.77760E-08 330760 + 204 330770 As-77 1.27680E-06 4.12840E-04 330770 + 205 330780 As-78 1.96710E-05 6.49180E-04 330780 + 206 330790 As-79 1.35490E-04 1.28560E-03 330790 + 207 330800 As-80 5.58980E-04 1.95340E-03 330800 + 208 330810 As-81 1.25390E-03 2.36510E-03 330810 + 209 330820 As-82 4.48790E-04 1.25990E-03 330820 + 210 330821 As-82m 1.56370E-03 1.56370E-03 330821 + 211 330830 As-83 2.57950E-03 2.81890E-03 330830 + 212 330840 As-84 6.91150E-04 7.15690E-04 330840 + 213 330841 As-84m 6.91150E-04 7.15690E-04 330841 + 214 330850 As-85 8.26760E-04 8.28490E-04 330850 + 215 330860 As-86 1.74610E-04 1.74720E-04 330860 + 216 330870 As-87 5.86980E-05 5.87000E-05 330870 + 217 330880 As-88 1.04300E-06 1.04300E-06 330880 + 218 330890 As-89 3.61710E-08 3.61710E-08 330890 + 219 340760 Se-76 3.24510E-11 8.78090E-08 34076.82c + 220 340770 Se-77 3.31790E-10 4.12850E-04 34077.82c + 221 340771 Se-77m 2.49190E-09 2.49190E-09 340771 + 222 340780 Se-78 1.64030E-07 6.49340E-04 34078.82c + 223 340790 Se-79 1.04310E-05 1.29670E-03 34079.82c + 224 340791 Se-79m 1.38890E-06 1.25650E-03 340791 + 225 340800 Se-80 8.17260E-05 2.03510E-03 34080.82c + 226 340810 Se-81 6.03290E-05 2.87830E-03 340810 + 227 340811 Se-81m 4.53110E-04 5.38010E-04 340811 + 228 340820 Se-82 2.23700E-03 5.06060E-03 34082.82c + 229 340830 Se-83 5.62100E-03 6.63680E-03 340830 + 230 340831 Se-83m 1.13170E-03 2.93690E-03 340831 + 231 340840 Se-84 1.30680E-02 1.46800E-02 340840 + 232 340850 Se-85 1.20190E-02 1.27230E-02 340850 + 233 340860 Se-86 8.77610E-03 8.90220E-03 340860 + 234 340870 Se-87 4.27350E-03 4.32320E-03 340870 + 235 340880 Se-88 1.62760E-03 1.62860E-03 340880 + 236 340890 Se-89 2.92020E-04 2.92060E-04 340890 + 237 340900 Se-90 5.57280E-05 5.57280E-05 340900 + 238 340910 Se-91 2.19910E-07 2.19910E-07 340910 + 239 340920 Se-92 7.37980E-09 7.37980E-09 340920 + 240 350780 Br-78 1.61170E-11 1.61170E-11 350780 + 241 350790 Br-79 3.64780E-10 7.05380E-07 35079.82c + 242 350791 Br-79m 1.38140E-09 1.38140E-09 350791 + 243 350800 Br-80 1.35380E-08 6.07090E-08 350800 + 244 350801 Br-80m 4.71710E-08 4.71710E-08 350801 + 245 350810 Br-81 8.33700E-07 2.87940E-03 35081.82c + 246 350820 Br-82 2.64420E-05 3.59100E-05 350820 + 247 350821 Br-82m 9.70080E-06 9.70080E-06 350821 + 248 350830 Br-83 3.44930E-04 9.91860E-03 350830 + 249 350840 Br-84 8.53050E-04 1.55330E-02 350840 + 250 350841 Br-84m 8.53050E-04 8.53050E-04 350841 + 251 350850 Br-85 7.31230E-03 2.00350E-02 350850 + 252 350860 Br-86 1.23540E-02 2.12560E-02 350860 + 253 350870 Br-87 1.78080E-02 2.21470E-02 350870 + 254 350880 Br-88 1.16200E-02 1.32550E-02 350880 + 255 350890 Br-89 8.14730E-03 8.41660E-03 350890 + 256 350900 Br-90 2.45140E-03 2.50720E-03 350900 + 257 350910 Br-91 8.02320E-04 8.02490E-04 350910 + 258 350920 Br-92 6.30770E-05 6.30840E-05 350920 + 259 350930 Br-93 1.32690E-05 1.32690E-05 350930 + 260 350940 Br-94 3.53370E-08 3.53370E-08 350940 + 261 360810 Kr-81 3.56350E-10 4.03790E-10 360810 + 262 360811 Kr-81m 4.74450E-11 4.74450E-11 360811 + 263 360820 Kr-82 1.56790E-06 3.77110E-05 36082.82c + 264 360830 Kr-83 7.78310E-06 9.92790E-03 36083.82c + 265 360831 Kr-83m 1.56710E-06 9.91130E-03 360831 + 266 360840 Kr-84 1.15710E-04 1.65010E-02 36084.82c + 267 360850 Kr-85 8.35400E-04 5.18450E-03 36085.82c + 268 360851 Kr-85m 1.68200E-04 2.01710E-02 360851 + 269 360860 Kr-86 6.41830E-03 2.82300E-02 36086.82c + 270 360870 Kr-87 1.83130E-02 4.07930E-02 360870 + 271 360880 Kr-88 3.63730E-02 4.99270E-02 360880 + 272 360890 Kr-89 4.49160E-02 5.27630E-02 360890 + 273 360900 Kr-90 3.91270E-02 4.11780E-02 360900 + 274 360910 Kr-91 1.97940E-02 2.04570E-02 360910 + 275 360920 Kr-92 8.83290E-03 8.88410E-03 360920 + 276 360930 Kr-93 2.18330E-03 2.18760E-03 360930 + 277 360940 Kr-94 5.22800E-04 5.22810E-04 360940 + 278 360950 Kr-95 4.26290E-05 4.26290E-05 360950 + 279 360960 Kr-96 6.14850E-06 6.14850E-06 360960 + 280 360970 Kr-97 4.48400E-09 4.48400E-09 360970 + 281 370840 Rb-84 3.46620E-09 1.07380E-08 370840 + 282 370841 Rb-84m 7.27180E-09 7.27180E-09 370841 + 283 370850 Rb-85 2.01350E-06 2.10410E-02 37085.82c + 284 370860 Rb-86 8.27660E-06 2.56400E-05 37086.82c + 285 370861 Rb-86m 1.73630E-05 1.73630E-05 370861 + 286 370870 Rb-87 3.67170E-04 4.11600E-02 37087.82c + 287 370880 Rb-88 1.71330E-03 5.16400E-02 370880 + 288 370890 Rb-89 8.97150E-03 6.17340E-02 370890 + 289 370900 Rb-90 1.72620E-03 3.81150E-02 370900 + 290 370901 Rb-90m 1.75610E-02 2.29470E-02 370901 + 291 370910 Rb-91 3.14850E-02 5.19420E-02 370910 + 292 370920 Rb-92 2.68620E-02 3.57460E-02 370920 + 293 370930 Rb-93 2.22880E-02 2.44810E-02 370930 + 294 370940 Rb-94 8.87920E-03 9.39740E-03 370940 + 295 370950 Rb-95 3.68260E-03 3.72420E-03 370950 + 296 370960 Rb-96 2.91850E-04 4.42220E-04 370960 + 297 370961 Rb-96m 2.91850E-04 2.94820E-04 370961 + 298 370970 Rb-97 1.29190E-04 1.29190E-04 370970 + 299 370980 Rb-98 5.79400E-06 5.79400E-06 370980 + 300 370981 Rb-98m 5.79400E-06 5.79400E-06 370981 + 301 370990 Rb-99 8.97220E-07 8.97220E-07 370990 + 302 380860 Sr-86 4.28000E-09 2.56430E-05 38086.82c + 303 380870 Sr-87 1.88760E-06 2.26650E-06 38087.82c + 304 380871 Sr-87m 3.80050E-07 3.80050E-07 380871 + 305 380880 Sr-88 7.93490E-05 5.17200E-02 38088.82c + 306 380890 Sr-89 5.32850E-04 6.22670E-02 38089.82c + 307 380900 Sr-90 4.13530E-03 6.46000E-02 38090.82c + 308 380910 Sr-91 1.09550E-02 6.28970E-02 380910 + 309 380920 Sr-92 2.87940E-02 6.48830E-02 380920 + 310 380930 Sr-93 4.21570E-02 6.72450E-02 380930 + 311 380940 Sr-94 4.99550E-02 5.87240E-02 380940 + 312 380950 Sr-95 3.44760E-02 3.79390E-02 380950 + 313 380960 Sr-96 2.01170E-02 2.06800E-02 380960 + 314 380970 Sr-97 7.11430E-03 7.21190E-03 380970 + 315 380980 Sr-98 2.20660E-03 2.21750E-03 380980 + 316 380990 Sr-99 3.34320E-04 3.35070E-04 380990 + 317 381000 Sr-100 5.42740E-05 5.42740E-05 381000 + 318 381010 Sr-101 6.29370E-06 6.29370E-06 381010 + 319 381020 Sr-102 3.86570E-09 3.86570E-09 381020 + 320 390890 Y-89 7.74630E-09 6.22670E-02 39089.82c + 321 390891 Y-89m 3.84730E-08 6.04040E-06 390891 + 322 390900 Y-90 2.17580E-06 6.46060E-02 39090.82c + 323 390901 Y-90m 3.63880E-06 3.63880E-06 390901 + 324 390910 Y-91 1.83960E-05 6.30070E-02 39091.82c + 325 390911 Y-91m 9.13640E-05 3.70970E-02 390911 + 326 390920 Y-92 5.62760E-04 6.54460E-02 390920 + 327 390930 Y-93 3.96600E-04 7.06200E-02 390930 + 328 390931 Y-93m 2.97870E-03 1.98060E-02 390931 + 329 390940 Y-94 8.12170E-03 6.68450E-02 390940 + 330 390950 Y-95 2.21760E-02 6.01150E-02 390950 + 331 390960 Y-96 8.12160E-03 2.88030E-02 390960 + 332 390961 Y-96m 1.70380E-02 1.70400E-02 390961 + 333 390970 Y-97 4.38780E-03 1.06760E-02 390970 + 334 390971 Y-97m 1.62190E-02 2.17500E-02 390971 + 335 390972 Y-97m 5.57370E-03 5.57370E-03 390972 + 336 390980 Y-98 2.46240E-03 4.67990E-03 390980 + 337 390981 Y-98m 1.19380E-02 1.19380E-02 390981 + 338 390990 Y-99 8.82770E-03 9.16320E-03 390990 + 339 391000 Y-100 1.30130E-03 1.35520E-03 391000 + 340 391001 Y-100m 1.30130E-03 1.30130E-03 391001 + 341 391010 Y-101 6.98150E-04 7.04290E-04 391010 + 342 391020 Y-102 3.57450E-05 3.57470E-05 391020 + 343 391021 Y-102m 3.57450E-05 3.57470E-05 391021 + 344 391030 Y-103 1.07900E-05 1.07900E-05 391030 + 345 391040 Y-104 9.59140E-09 9.59140E-09 391040 + 346 391050 Y-105 2.11820E-10 2.11820E-10 391050 + 347 400910 Zr-91 3.28950E-06 6.30100E-02 40091.82c + 348 400920 Zr-92 1.48010E-05 6.54600E-02 40092.82c + 349 400930 Zr-93 1.19620E-04 7.07400E-02 40093.82c + 350 400940 Zr-94 8.29350E-04 6.76750E-02 40094.82c + 351 400950 Zr-95 3.19420E-03 6.33090E-02 40095.82c + 352 400960 Zr-96 1.19390E-02 5.78000E-02 40096.82c + 353 400970 Zr-97 2.09150E-02 5.47090E-02 400970 + 354 400980 Zr-98 3.36730E-02 5.00230E-02 400980 + 355 400990 Zr-99 3.21440E-02 4.11640E-02 400990 + 356 401000 Zr-100 2.76540E-02 3.02980E-02 401000 + 357 401010 Zr-101 1.16990E-02 1.24070E-02 401010 + 358 401020 Zr-102 4.39880E-03 4.46770E-03 401020 + 359 401030 Zr-103 7.99200E-04 8.09130E-04 401030 + 360 401040 Zr-104 1.84590E-04 1.84600E-04 401040 + 361 401050 Zr-105 1.34240E-05 1.34240E-05 401050 + 362 401060 Zr-106 2.68140E-08 2.68140E-08 401060 + 363 401070 Zr-107 1.93340E-10 1.93340E-10 401070 + 364 410940 Nb-94 5.91940E-07 9.44120E-07 41094.82c + 365 410941 Nb-94m 3.53950E-07 3.53950E-07 410941 + 366 410950 Nb-95 1.18350E-05 6.32850E-02 41095.82c + 367 410951 Nb-95m 2.38290E-06 6.86350E-04 410951 + 368 410960 Nb-96 9.14310E-05 9.14310E-05 410960 + 369 410970 Nb-97 5.33670E-04 5.53500E-02 410970 + 370 410971 Nb-97m 1.07450E-04 5.21070E-02 410971 + 371 410980 Nb-98 4.48140E-04 5.04710E-02 410980 + 372 410981 Nb-98m 1.56150E-03 1.56150E-03 410981 + 373 410990 Nb-99 6.08680E-03 3.24300E-02 410990 + 374 410991 Nb-99m 1.22560E-03 1.63740E-02 410991 + 375 411000 Nb-100 2.05590E-03 3.23540E-02 411000 + 376 411001 Nb-100m 9.96710E-03 9.96710E-03 411001 + 377 411010 Nb-101 1.69810E-02 2.93880E-02 411010 + 378 411020 Nb-102 5.85850E-03 1.03260E-02 411020 + 379 411021 Nb-102m 5.85850E-03 5.85850E-03 411021 + 380 411030 Nb-103 6.75400E-03 7.56310E-03 411030 + 381 411040 Nb-104 1.37590E-03 1.56060E-03 411040 + 382 411041 Nb-104m 1.37590E-03 1.37590E-03 411041 + 383 411050 Nb-105 8.83980E-04 8.97220E-04 411050 + 384 411060 Nb-106 1.09340E-04 1.09370E-04 411060 + 385 411070 Nb-107 7.61600E-06 7.61620E-06 411070 + 386 411080 Nb-108 5.30530E-06 5.30530E-06 411080 + 387 411090 Nb-109 7.44810E-10 7.44810E-10 411090 + 388 411100 Nb-110 1.42190E-11 1.42190E-11 411100 + 389 420960 Mo-96 4.49130E-09 9.14360E-05 42096.82c + 390 420970 Mo-97 1.01450E-05 5.53600E-02 42097.82c + 391 420980 Mo-98 7.80770E-05 5.21110E-02 42098.82c + 392 420990 Mo-99 4.61410E-04 4.89380E-02 42099.82c + 393 421000 Mo-100 2.25210E-03 4.45730E-02 42100.82c + 394 421010 Mo-101 4.76230E-03 3.41500E-02 421010 + 395 421020 Mo-102 8.82270E-03 2.50070E-02 421020 + 396 421030 Mo-103 7.53590E-03 1.51010E-02 421030 + 397 421040 Mo-104 7.83290E-03 1.07830E-02 421040 + 398 421050 Mo-105 3.68000E-03 4.56690E-03 421050 + 399 421060 Mo-106 1.44810E-03 1.55300E-03 421060 + 400 421070 Mo-107 3.25730E-04 3.33220E-04 421070 + 401 421080 Mo-108 8.43550E-05 8.93310E-05 421080 + 402 421090 Mo-109 2.82980E-06 2.83050E-06 421090 + 403 421100 Mo-110 6.00660E-06 6.00660E-06 421100 + 404 421110 Mo-111 4.30070E-09 4.30070E-09 421110 + 405 421120 Mo-112 1.82000E-10 1.82000E-10 421120 + 406 430990 Tc-99 1.97040E-08 4.89360E-02 43099.82c + 407 430991 Tc-99m 3.96730E-09 4.30950E-02 430991 + 408 431000 Tc-100 6.03520E-06 6.03520E-06 431000 + 409 431010 Tc-101 6.51320E-05 3.42150E-02 431010 + 410 431020 Tc-102 1.07780E-04 2.51150E-02 431020 + 411 431021 Tc-102m 1.07780E-04 1.07780E-04 431021 + 412 431030 Tc-103 5.74110E-04 1.56750E-02 431030 + 413 431040 Tc-104 1.15960E-03 1.19430E-02 431040 + 414 431050 Tc-105 1.68560E-03 6.25250E-03 431050 + 415 431060 Tc-106 1.09660E-03 2.64960E-03 431060 + 416 431070 Tc-107 7.69740E-04 1.10300E-03 431070 + 417 431080 Tc-108 2.76360E-04 3.65710E-04 431080 + 418 431090 Tc-109 1.53620E-04 1.56430E-04 431090 + 419 431100 Tc-110 6.27330E-05 6.87400E-05 431100 + 420 431110 Tc-111 2.84680E-05 2.84720E-05 431110 + 421 431120 Tc-112 4.71000E-07 4.71180E-07 431120 + 422 431130 Tc-113 3.36110E-08 3.36110E-08 431130 + 423 431140 Tc-114 7.39730E-10 7.39730E-10 431140 + 424 431150 Tc-115 1.89590E-11 1.89590E-11 431150 + 425 431180 Tc-118 5.18600E-11 5.18600E-11 431180 + 426 441010 Ru-101 1.04920E-06 3.42160E-02 44101.82c + 427 441020 Ru-102 3.20490E-06 2.52260E-02 44102.82c + 428 441030 Ru-103 5.13330E-06 1.56940E-02 44103.82c + 429 441031 Ru-103m 1.43630E-05 1.43630E-05 441031 + 430 441040 Ru-104 7.82590E-05 1.20210E-02 44104.82c + 431 441050 Ru-105 1.51160E-04 6.40370E-03 44105.82c + 432 441060 Ru-106 2.62450E-04 2.91200E-03 44106.82c + 433 441070 Ru-107 3.01560E-04 1.40450E-03 441070 + 434 441080 Ru-108 3.39920E-04 7.05750E-04 441080 + 435 441090 Ru-109 3.30430E-04 4.86770E-04 441090 + 436 441100 Ru-110 4.08020E-04 4.76730E-04 441100 + 437 441110 Ru-111 2.88740E-04 3.17220E-04 441110 + 438 441120 Ru-112 2.57410E-04 2.57880E-04 441120 + 439 441130 Ru-113 3.33620E-05 5.00740E-05 441130 + 440 441131 Ru-113m 3.33620E-05 3.33620E-05 441131 + 441 441140 Ru-114 1.55490E-05 1.55500E-05 441140 + 442 441150 Ru-115 6.20430E-06 6.20430E-06 441150 + 443 441160 Ru-116 2.98910E-06 2.98910E-06 441160 + 444 441170 Ru-117 1.47530E-10 1.47530E-10 441170 + 445 441180 Ru-118 4.66380E-07 4.66430E-07 441180 + 446 441190 Ru-119 2.18170E-08 2.18170E-08 441190 + 447 441200 Ru-120 9.88150E-10 9.88150E-10 441200 + 448 451040 Rh-104 7.54900E-10 3.38180E-09 451040 + 449 451041 Rh-104m 2.63030E-09 2.63030E-09 451041 + 450 451050 Rh-105 8.71100E-08 6.40370E-03 45105.82c + 451 451051 Rh-105m 1.15980E-08 1.81790E-03 451051 + 452 451060 Rh-106 1.17740E-06 2.91320E-03 451060 + 453 451061 Rh-106m 3.20950E-06 3.20950E-06 451061 + 454 451070 Rh-107 2.53970E-06 1.40710E-03 451070 + 455 451080 Rh-108 2.95880E-06 7.08710E-04 451080 + 456 451081 Rh-108m 1.03090E-05 1.03090E-05 451081 + 457 451090 Rh-109 4.80500E-05 5.34820E-04 451090 + 458 451100 Rh-110 1.28470E-04 6.05210E-04 451100 + 459 451101 Rh-110m 3.02450E-06 3.02450E-06 451101 + 460 451110 Rh-111 1.98510E-04 5.15730E-04 451110 + 461 451120 Rh-112 1.49000E-04 4.06880E-04 451120 + 462 451121 Rh-112m 1.49000E-04 1.49000E-04 451121 + 463 451130 Rh-113 3.33660E-04 4.00410E-04 451130 + 464 451140 Rh-114 8.94300E-05 1.04990E-04 451140 + 465 451141 Rh-114m 8.94300E-05 8.94300E-05 451141 + 466 451150 Rh-115 1.12720E-04 1.18940E-04 451150 + 467 451160 Rh-116 8.86180E-06 1.18190E-05 451160 + 468 451161 Rh-116m 2.41550E-05 2.41550E-05 451161 + 469 451170 Rh-117 1.84470E-05 1.84660E-05 451170 + 470 451180 Rh-118 4.41140E-05 4.45620E-05 451180 + 471 451190 Rh-119 1.60220E-05 1.60430E-05 451190 + 472 451200 Rh-120 1.53010E-06 1.53110E-06 451200 + 473 451210 Rh-121 1.03150E-07 1.03150E-07 451210 + 474 451220 Rh-122 3.88740E-09 3.88740E-09 451220 + 475 461060 Pd-106 1.13620E-10 2.91640E-03 46106.82c + 476 461070 Pd-107 8.70560E-10 1.40710E-03 46107.82c + 477 461071 Pd-107m 1.91340E-09 1.91340E-09 461071 + 478 461080 Pd-108 5.91590E-08 7.19080E-04 46108.82c + 479 461090 Pd-109 1.67630E-07 5.35350E-04 461090 + 480 461091 Pd-109m 3.68440E-07 2.67780E-04 461091 + 481 461100 Pd-110 9.00650E-06 6.17240E-04 46110.82c + 482 461110 Pd-111 9.88190E-06 5.40910E-04 461110 + 483 461111 Pd-111m 2.17200E-05 2.37830E-05 461111 + 484 461120 Pd-112 1.21950E-04 6.77830E-04 461120 + 485 461130 Pd-113 5.65170E-05 6.15070E-04 461130 + 486 461131 Pd-113m 1.58130E-04 1.58130E-04 461131 + 487 461140 Pd-114 3.89300E-04 5.83720E-04 461140 + 488 461150 Pd-115 1.21750E-04 2.46210E-04 461150 + 489 461151 Pd-115m 2.67610E-04 2.84880E-04 461151 + 490 461160 Pd-116 3.39130E-04 3.75100E-04 461160 + 491 461170 Pd-117 6.70870E-05 2.34310E-04 461170 + 492 461171 Pd-117m 1.47450E-04 1.47450E-04 461171 + 493 461180 Pd-118 1.26370E-04 1.69630E-04 461180 + 494 461190 Pd-119 5.71770E-05 7.33110E-05 461190 + 495 461200 Pd-120 1.73900E-05 1.88440E-05 461200 + 496 461210 Pd-121 2.64760E-05 2.65650E-05 461210 + 497 461220 Pd-122 7.91790E-06 7.92180E-06 461220 + 498 461230 Pd-123 5.06380E-07 5.06380E-07 461230 + 499 461240 Pd-124 5.20600E-08 5.20600E-08 461240 + 500 471090 Ag-109 1.83170E-11 5.35350E-04 47109.82c + 501 471091 Ag-109m 1.37570E-10 5.35090E-04 471091 + 502 471100 Ag-110 1.46170E-09 1.51580E-09 471100 + 503 471101 Ag-110m 3.98420E-09 3.98420E-09 47510.82c + 504 471110 Ag-111 1.83630E-08 5.44780E-04 47111.82c + 505 471111 Ag-111m 1.37920E-07 5.41800E-04 471111 + 506 471120 Ag-112 3.08430E-06 6.80910E-04 471120 + 507 471130 Ag-113 3.70520E-07 4.05190E-04 471130 + 508 471131 Ag-113m 2.78290E-06 5.91760E-04 471131 + 509 471140 Ag-114 2.11850E-06 5.96110E-04 471140 + 510 471141 Ag-114m 1.02700E-05 1.02700E-05 471141 + 511 471150 Ag-115 8.66740E-06 2.71070E-04 471150 + 512 471151 Ag-115m 6.50980E-05 3.93660E-04 471151 + 513 471160 Ag-116 5.92090E-05 4.44000E-04 471160 + 514 471161 Ag-116m 1.61390E-04 1.61390E-04 471161 + 515 471170 Ag-117 3.70550E-05 1.77930E-04 471170 + 516 471171 Ag-117m 2.78310E-04 3.95460E-04 471171 + 517 471180 Ag-118 3.89540E-05 2.71710E-04 471180 + 518 471181 Ag-118m 1.88850E-04 2.13100E-04 471181 + 519 471190 Ag-119 3.31620E-05 6.98170E-05 471190 + 520 471191 Ag-119m 2.49070E-04 2.85720E-04 471191 + 521 471200 Ag-120 7.22360E-05 1.29910E-04 471200 + 522 471201 Ag-120m 1.20800E-04 1.30230E-04 471201 + 523 471210 Ag-121 8.35460E-05 1.10040E-04 471210 + 524 471220 Ag-122 2.00150E-05 2.79360E-05 471220 + 525 471221 Ag-122m 2.15780E-05 2.15780E-05 471221 + 526 471230 Ag-123 2.48210E-05 2.53270E-05 471230 + 527 471240 Ag-124 1.99600E-06 3.12400E-06 471240 + 528 471241 Ag-124m 2.15190E-06 2.15190E-06 471241 + 529 471250 Ag-125 2.41720E-06 2.41720E-06 471250 + 530 471260 Ag-126 4.12280E-07 4.12280E-07 471260 + 531 471270 Ag-127 3.65450E-08 3.65450E-08 471270 + 532 471280 Ag-128 1.56570E-09 1.56570E-09 471280 + 533 481110 Cd-111 3.10860E-12 5.47490E-04 48111.82c + 534 481111 Cd-111m 1.17720E-11 1.17720E-11 481111 + 535 481120 Cd-112 1.50800E-09 6.80910E-04 48112.82c + 536 481130 Cd-113 6.33780E-09 6.11230E-04 48113.82c + 537 481131 Cd-113m 2.40010E-08 7.02920E-06 481131 + 538 481140 Cd-114 3.09990E-06 5.99210E-04 48114.82c + 539 481150 Cd-115 1.07640E-06 5.58470E-04 481150 + 540 481151 Cd-115m 4.07630E-06 2.87510E-05 48515.82c + 541 481160 Cd-116 2.37930E-05 6.19500E-04 48116.82c + 542 481170 Cd-117 1.08080E-05 4.38270E-04 481170 + 543 481171 Cd-117m 4.09290E-05 1.63130E-04 481171 + 544 481180 Cd-118 1.96600E-04 5.94030E-04 481180 + 545 481190 Cd-119 9.05700E-05 4.11200E-04 481190 + 546 481191 Cd-119m 2.53410E-04 2.88320E-04 481191 + 547 481200 Cd-120 5.59500E-04 7.71450E-04 481200 + 548 481210 Cd-121 8.58570E-05 1.84400E-04 481210 + 549 481211 Cd-121m 2.40220E-04 2.51720E-04 481211 + 550 481220 Cd-122 4.51270E-04 5.00790E-04 481220 + 551 481230 Cd-123 7.30180E-05 9.37420E-05 481230 + 552 481231 Cd-123m 2.04300E-04 2.08910E-04 481231 + 553 481240 Cd-124 4.20990E-04 4.25190E-04 481240 + 554 481250 Cd-125 6.71680E-05 6.83760E-05 481250 + 555 481251 Cd-125m 1.87930E-04 1.89140E-04 481251 + 556 481260 Cd-126 1.76140E-04 1.76550E-04 481260 + 557 481270 Cd-127 7.27200E-05 7.27570E-05 481270 + 558 481280 Cd-128 2.43460E-05 2.43480E-05 481280 + 559 481290 Cd-129 2.04270E-06 2.04270E-06 481290 + 560 481291 Cd-129m 5.71520E-06 5.71520E-06 481291 + 561 481300 Cd-130 3.13240E-08 3.13240E-08 481300 + 562 481310 Cd-131 1.05600E-09 1.05600E-09 481310 + 563 491140 In-114 2.49000E-11 1.08620E-10 491140 + 564 491141 In-114m 4.02090E-11 8.67600E-11 491141 + 565 491142 In-114m 4.65510E-11 4.65510E-11 491142 + 566 491150 In-115 4.95520E-09 5.59300E-04 49115.82c + 567 491151 In-115m 9.97710E-10 5.58470E-04 491151 + 568 491160 In-116 2.38360E-08 2.38360E-08 491160 + 569 491161 In-116m 3.84910E-08 8.30530E-08 491161 + 570 491162 In-116m 4.45620E-08 4.45620E-08 491162 + 571 491170 In-117 1.65390E-06 3.89430E-04 491170 + 572 491171 In-117m 3.33000E-07 4.04460E-04 491171 + 573 491180 In-118 1.21070E-06 5.95240E-04 491180 + 574 491181 In-118m 1.95510E-06 4.18690E-06 491181 + 575 491182 In-118m 2.26350E-06 2.26350E-06 491182 + 576 491190 In-119 3.04810E-05 3.79320E-04 491190 + 577 491191 In-119m 6.13720E-06 3.77990E-04 491191 + 578 491200 In-120 1.74610E-05 7.88910E-04 491200 + 579 491201 In-120m 1.74610E-05 1.74610E-05 491201 + 580 491202 In-120m 1.74610E-05 1.74610E-05 491202 + 581 491210 In-121 1.28010E-04 4.43610E-04 491210 + 582 491211 In-121m 2.57730E-05 1.48070E-04 491211 + 583 491220 In-122 1.14060E-04 6.14850E-04 491220 + 584 491221 In-122m 9.53750E-05 9.53750E-05 491221 + 585 491222 In-122m 9.53750E-05 9.53750E-05 491222 + 586 491230 In-123 3.51900E-04 5.87290E-04 491230 + 587 491231 In-123m 7.08530E-05 1.38110E-04 491231 + 588 491240 In-124 2.19270E-04 6.44460E-04 491240 + 589 491241 In-124m 2.36410E-04 2.36410E-04 491241 + 590 491250 In-125 5.97820E-04 8.19690E-04 491250 + 591 491251 In-125m 1.20370E-04 1.56020E-04 491251 + 592 491260 In-126 5.58100E-04 7.34650E-04 491260 + 593 491261 In-126m 6.01700E-04 6.01700E-04 491261 + 594 491270 In-127 9.77490E-04 9.77490E-04 491270 + 595 491271 In-127m 1.96810E-04 2.69570E-04 491271 + 596 491280 In-128 3.47600E-04 5.08050E-04 491280 + 597 491281 In-128m 1.36100E-04 1.60450E-04 491281 + 598 491282 In-128m 5.21500E-04 5.21500E-04 491282 + 599 491290 In-129 3.91370E-04 3.97080E-04 491290 + 600 491291 In-129m 7.88000E-05 8.08440E-05 491291 + 601 491300 In-130 2.53800E-05 2.54100E-05 491300 + 602 491301 In-130m 3.69540E-05 3.69540E-05 491301 + 603 491302 In-130m 5.14760E-05 5.14760E-05 491302 + 604 491310 In-131 6.26770E-06 6.33250E-06 491310 + 605 491311 In-131m 6.26770E-06 6.26770E-06 491311 + 606 491312 In-131m 6.26770E-06 6.26770E-06 491312 + 607 491320 In-132 2.36030E-07 2.36030E-07 491320 + 608 491330 In-133 7.86730E-09 9.45130E-09 491330 + 609 491331 In-133m 1.58400E-09 1.58400E-09 491331 + 610 501160 Sn-116 2.36770E-11 1.06910E-07 50116.82c + 611 501170 Sn-117 1.60950E-10 6.03390E-04 50117.82c + 612 501171 Sn-117m 6.09490E-10 1.32740E-06 501171 + 613 501200 Sn-120 4.14380E-10 8.23840E-04 50120.82c + 614 501210 Sn-121 6.28870E-06 5.98590E-04 501210 + 615 501211 Sn-121m 1.75950E-05 6.78490E-05 501211 + 616 501220 Sn-122 2.08240E-05 8.26420E-04 50122.82c + 617 501230 Sn-123 7.70440E-05 1.21820E-04 50123.82c + 618 501231 Sn-123m 2.75360E-05 7.08160E-04 501231 + 619 501240 Sn-124 3.05870E-04 1.18670E-03 50124.82c + 620 501250 Sn-125 3.65920E-04 5.04380E-04 50125.82c + 621 501251 Sn-125m 1.30780E-04 9.68030E-04 501251 + 622 501260 Sn-126 1.87020E-03 3.20840E-03 50126.82c + 623 501270 Sn-127 2.78560E-03 3.16660E-03 501270 + 624 501271 Sn-127m 9.95590E-04 1.85980E-03 501271 + 625 501280 Sn-128 2.71810E-03 1.11560E-02 501280 + 626 501281 Sn-128m 7.40890E-03 7.93040E-03 501281 + 627 501290 Sn-129 2.35050E-03 2.78630E-03 501290 + 628 501291 Sn-129m 6.57650E-03 6.61880E-03 501291 + 629 501300 Sn-130 1.89340E-03 1.96300E-03 501300 + 630 501301 Sn-130m 5.16100E-03 5.20540E-03 501301 + 631 501310 Sn-131 9.19390E-04 9.31540E-04 501310 + 632 501311 Sn-131m 2.57240E-03 2.57890E-03 501311 + 633 501320 Sn-132 1.02750E-03 1.02770E-03 501320 + 634 501330 Sn-133 6.27310E-05 6.27320E-05 501330 + 635 501340 Sn-134 9.27440E-06 9.27440E-06 501340 + 636 501350 Sn-135 5.96050E-08 5.96050E-08 501350 + 637 501360 Sn-136 2.52490E-09 2.52490E-09 501360 + 638 511220 Sb-122 1.63690E-11 3.83000E-11 511220 + 639 511221 Sb-122m 2.19310E-11 2.19310E-11 511221 + 640 511230 Sb-123 4.14030E-06 8.34120E-04 51123.82c + 641 511240 Sb-124 2.67980E-06 6.89690E-06 51124.82c + 642 511241 Sb-124m 2.16180E-06 5.62280E-06 511241 + 643 511242 Sb-124m 3.46100E-06 3.46100E-06 511242 + 644 511250 Sb-125 2.66260E-05 1.49900E-03 51125.82c + 645 511260 Sb-126 3.89810E-05 4.66150E-05 51126.82c + 646 511261 Sb-126m 2.43480E-05 5.45300E-05 511261 + 647 511262 Sb-126m 3.01820E-05 3.01820E-05 511262 + 648 511270 Sb-127 3.88750E-04 5.41510E-03 511270 + 649 511280 Sb-128 9.69670E-04 1.21750E-02 511280 + 650 511281 Sb-128m 1.35620E-03 1.35620E-03 511281 + 651 511290 Sb-129 4.21040E-03 1.12700E-02 511290 + 652 511291 Sb-129m 3.11590E-03 6.42520E-03 511291 + 653 511300 Sb-130 6.00900E-03 1.05750E-02 511300 + 654 511301 Sb-130m 6.00900E-03 8.61170E-03 511301 + 655 511310 Sb-131 1.86650E-02 2.21760E-02 511310 + 656 511320 Sb-132 6.46190E-03 7.48960E-03 511320 + 657 511321 Sb-132m 5.72110E-03 5.72110E-03 511321 + 658 511330 Sb-133 6.95220E-03 7.01650E-03 511330 + 659 511340 Sb-134 3.04630E-04 3.12340E-04 511340 + 660 511341 Sb-134m 8.30370E-04 8.30370E-04 511341 + 661 511350 Sb-135 1.59360E-04 1.59410E-04 511350 + 662 511360 Sb-136 1.54410E-05 1.54430E-05 511360 + 663 511370 Sb-137 1.72040E-06 1.72040E-06 511370 + 664 511380 Sb-138 7.64570E-09 7.64570E-09 511380 + 665 521250 Te-125 1.10180E-10 1.49900E-03 52125.82c + 666 521251 Te-125m 4.17240E-10 3.35430E-04 521251 + 667 521260 Te-126 5.95660E-06 9.94670E-05 52126.82c + 668 521270 Te-127 4.36050E-06 5.41000E-03 521270 + 669 521271 Te-127m 1.22000E-05 9.04590E-04 52527.82c + 670 521280 Te-128 1.85970E-04 1.36680E-02 52128.82c + 671 521290 Te-129 2.81200E-04 1.48430E-02 521290 + 672 521291 Te-129m 7.86800E-04 7.99050E-03 52529.82c + 673 521300 Te-130 4.84060E-03 2.40270E-02 52130.82c + 674 521310 Te-131 4.25940E-03 2.75350E-02 521310 + 675 521311 Te-131m 1.19180E-02 1.36930E-02 521311 + 676 521320 Te-132 3.19200E-02 4.51310E-02 52132.82c + 677 521330 Te-133 1.08330E-02 2.21530E-02 521330 + 678 521331 Te-133m 3.03100E-02 3.15240E-02 521331 + 679 521340 Te-134 3.65880E-02 3.77550E-02 521340 + 680 521350 Te-135 1.16010E-02 1.17380E-02 521350 + 681 521360 Te-136 3.28650E-03 3.30020E-03 521360 + 682 521370 Te-137 6.38770E-04 6.39650E-04 521370 + 683 521380 Te-138 9.95010E-05 9.95090E-05 521380 + 684 521390 Te-139 9.81260E-06 9.81260E-06 521390 + 685 521400 Te-140 1.11490E-06 1.11490E-06 521400 + 686 521410 Te-141 1.77640E-09 1.77640E-09 521410 + 687 531270 I-127 3.48050E-10 5.43170E-03 53127.82c + 688 531280 I-128 2.66170E-08 2.66170E-08 531280 + 689 531290 I-129 2.22010E-06 1.78010E-02 53129.82c + 690 531300 I-130 2.71170E-05 3.54730E-05 53130.82c + 691 531301 I-130m 9.94820E-06 9.94820E-06 531301 + 692 531310 I-131 3.81810E-04 3.87340E-02 53131.82c + 693 531320 I-132 1.10320E-03 4.70740E-02 531320 + 694 531321 I-132m 9.76770E-04 9.76770E-04 531321 + 695 531330 I-133 4.91280E-03 5.67090E-02 531330 + 696 531331 I-133m 3.63570E-03 3.63570E-03 531331 + 697 531340 I-134 1.18150E-02 5.97900E-02 531340 + 698 531341 I-134m 1.04610E-02 1.04610E-02 531341 + 699 531350 I-135 3.87370E-02 5.04750E-02 53135.82c + 700 531360 I-136 5.99180E-03 9.30160E-03 531360 + 701 531361 I-136m 1.63320E-02 1.63420E-02 531361 + 702 531370 I-137 1.24780E-02 1.31050E-02 531370 + 703 531380 I-138 3.59990E-03 3.69310E-03 531380 + 704 531390 I-139 1.56920E-03 1.57900E-03 531390 + 705 531400 I-140 2.22550E-04 2.23670E-04 531400 + 706 531410 I-141 4.45700E-05 4.45720E-05 531410 + 707 531420 I-142 1.10780E-06 1.10780E-06 531420 + 708 531430 I-143 8.96840E-09 8.96840E-09 531430 + 709 541300 Xe-130 1.10560E-08 3.70760E-05 54130.82c + 710 541310 Xe-131 1.74840E-06 3.87410E-02 54131.82c + 711 541311 Xe-131m 4.89200E-06 4.25620E-04 541311 + 712 541320 Xe-132 1.92590E-05 4.72560E-02 54132.82c + 713 541321 Xe-132m 2.58020E-05 2.58020E-05 541321 + 714 541330 Xe-133 1.03830E-04 5.71030E-02 54133.82c + 715 541331 Xe-133m 2.90500E-04 1.90460E-03 541331 + 716 541340 Xe-134 7.39630E-04 6.27870E-02 54134.82c + 717 541341 Xe-134m 2.01610E-03 2.25670E-03 541341 + 718 541350 Xe-135 3.16880E-03 6.24070E-02 54135.82c + 719 541351 Xe-135m 8.86620E-03 1.71990E-02 541351 + 720 541360 Xe-136 4.18360E-02 6.83310E-02 54136.82c + 721 541370 Xe-137 4.69110E-02 5.93600E-02 541370 + 722 541380 Xe-138 4.68610E-02 5.05130E-02 541380 + 723 541390 Xe-139 2.77030E-02 2.91480E-02 541390 + 724 541400 Xe-140 1.54170E-02 1.56290E-02 541400 + 725 541410 Xe-141 5.61760E-03 5.65310E-03 541410 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Cs-142 1.40670E-02 1.52340E-02 551420 + 746 551430 Cs-143 5.83150E-03 5.97770E-03 551430 + 747 551440 Cs-144 7.32650E-04 1.11920E-03 551440 + 748 551441 Cs-144m 7.32650E-04 7.32650E-04 551441 + 749 551450 Cs-145 2.45060E-04 2.45090E-04 551450 + 750 551460 Cs-146 1.77340E-05 1.77350E-05 551460 + 751 551470 Cs-147 2.55760E-06 2.55760E-06 551470 + 752 551480 Cs-148 1.44190E-09 1.44190E-09 551480 + 753 561350 Ba-135 5.38080E-09 2.04360E-08 56135.82c + 754 561351 Ba-135m 1.50550E-08 1.50550E-08 561351 + 755 561360 Ba-136 1.96380E-06 5.42020E-04 56136.82c + 756 561361 Ba-136m 5.35280E-06 5.35280E-06 561361 + 757 561370 Ba-137 2.58430E-05 6.48480E-02 56137.82c + 758 561371 Ba-137m 7.23080E-05 6.11960E-02 561371 + 759 561380 Ba-138 1.48890E-03 6.55170E-02 56138.82c + 760 561390 Ba-139 6.20370E-03 6.39310E-02 561390 + 761 561400 Ba-140 2.04030E-02 6.18900E-02 56140.82c + 762 561410 Ba-141 2.92380E-02 6.35970E-02 561410 + 763 561420 Ba-142 4.61800E-02 6.15120E-02 561420 + 764 561430 Ba-143 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581510 + 803 581520 Ce-152 7.59820E-05 7.59920E-05 581520 + 804 581530 Ce-153 3.81740E-06 3.81760E-06 581530 + 805 581540 Ce-154 2.10780E-08 2.10780E-08 581540 + 806 581550 Ce-155 1.79010E-10 1.79010E-10 581550 + 807 581560 Ce-156 6.14790E-12 6.14790E-12 581560 + 808 591420 Pr-142 3.92000E-10 1.46050E-09 59142.82c + 809 591421 Pr-142m 1.06850E-09 1.06850E-09 591421 + 810 591430 Pr-143 1.13260E-06 5.36410E-02 59143.82c + 811 591440 Pr-144 1.03840E-07 4.51090E-02 591440 + 812 591441 Pr-144m 1.05640E-06 6.23520E-04 591441 + 813 591450 Pr-145 5.72030E-05 3.25260E-02 591450 + 814 591460 Pr-146 1.96330E-04 2.43650E-02 591460 + 815 591470 Pr-147 7.61840E-04 1.75140E-02 591470 + 816 591480 Pr-148 2.34530E-04 1.09490E-02 591480 + 817 591481 Pr-148m 1.13700E-03 1.13700E-03 591481 + 818 591490 Pr-149 2.27870E-03 7.00240E-03 591490 + 819 591500 Pr-150 2.04040E-03 3.80660E-03 591500 + 820 591510 Pr-151 1.48270E-03 1.94870E-03 591510 + 821 591520 Pr-152 6.11300E-04 6.87320E-04 591520 + 822 591530 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4.49600E-07 611590 + 861 611600 Pm-160 2.23990E-09 2.24150E-09 611600 + 862 611610 Pm-161 1.03920E-09 1.03920E-09 611610 + 863 611620 Pm-162 4.11180E-11 4.11180E-11 611620 + 864 621500 Sm-150 1.99980E-09 5.39030E-06 62150.82c + 865 621510 Sm-151 8.38240E-07 3.15420E-03 62151.82c + 866 621520 Sm-152 7.20920E-07 1.95490E-03 62152.82c + 867 621530 Sm-153 1.19380E-06 1.10900E-03 62153.82c + 868 621531 Sm-153m 3.34000E-06 3.34000E-06 621531 + 869 621540 Sm-154 1.57120E-05 4.63210E-04 62154.82c + 870 621550 Sm-155 1.69130E-05 1.66040E-04 621550 + 871 621560 Sm-156 5.72250E-05 1.57860E-04 621560 + 872 621570 Sm-157 6.66380E-05 1.06600E-04 621570 + 873 621580 Sm-158 1.73910E-05 2.47670E-05 621580 + 874 621590 Sm-159 1.64140E-05 1.68630E-05 621590 + 875 621600 Sm-160 1.02920E-06 1.03140E-06 621600 + 876 621610 Sm-161 2.40940E-07 2.41980E-07 621610 + 877 621620 Sm-162 7.55750E-08 7.56160E-08 621620 + 878 621630 Sm-163 7.66270E-10 7.66270E-10 621630 + 879 621640 Sm-164 2.30400E-11 2.30400E-11 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651610 Tb-161 6.02070E-08 4.95750E-06 651610 + 919 651620 Tb-162 3.49420E-07 7.21730E-06 651620 + 920 651630 Tb-163 2.61210E-07 1.92860E-06 651630 + 921 651640 Tb-164 1.60900E-07 4.16970E-07 651640 + 922 651650 Tb-165 1.35490E-07 1.70780E-07 651650 + 923 651660 Tb-166 3.94180E-08 4.55950E-08 651660 + 924 651670 Tb-167 1.37940E-08 1.41090E-08 651670 + 925 651680 Tb-168 1.34770E-09 1.36390E-09 651680 + 926 651690 Tb-169 1.95200E-10 1.95200E-10 651690 + 927 651700 Tb-170 8.07560E-12 8.07560E-12 651700 + 928 661610 Dy-161 5.43970E-11 4.95750E-06 66161.82c + 929 661620 Dy-162 2.49540E-09 7.21980E-06 66162.82c + 930 661630 Dy-163 3.62330E-09 1.93220E-06 66163.82c + 931 661640 Dy-164 1.57520E-08 4.32730E-07 66164.82c + 932 661650 Dy-165 1.97250E-08 1.93080E-07 661650 + 933 661651 Dy-165m 2.62620E-09 2.62620E-09 661651 + 934 661660 Dy-166 3.97990E-08 8.53940E-08 661660 + 935 661670 Dy-167 2.14460E-08 3.55550E-08 661670 + 936 661680 Dy-168 1.29000E-08 1.42640E-08 661680 + 937 661690 Dy-169 3.17590E-09 3.37110E-09 661690 + 938 661700 Dy-170 9.34970E-10 9.43050E-10 661700 + 939 661710 Dy-171 7.48190E-11 7.48190E-11 661710 + 940 661720 Dy-172 7.07640E-12 7.07640E-12 661720 + 941 671630 Ho-163 2.00570E-12 2.27270E-12 671630 + 942 671640 Ho-164 5.52180E-12 2.05730E-11 671640 + 943 671641 Ho-164m 1.50510E-11 1.50510E-11 671641 + 944 671650 Ho-165 2.25770E-10 1.93360E-07 67165.82c + 945 671660 Ho-166 2.03350E-10 8.55970E-08 671660 + 946 671661 Ho-166m 5.54280E-10 5.54280E-10 671661 + 947 671670 Ho-167 2.77480E-09 3.83290E-08 671670 + 948 671680 Ho-168 1.01540E-09 1.69690E-08 671680 + 949 671681 Ho-168m 1.69810E-09 1.69810E-09 671681 + 950 671690 Ho-169 4.01260E-09 7.38370E-09 671690 + 951 671700 Ho-170 1.34230E-09 1.34230E-09 671700 + 952 671701 Ho-170m 4.92430E-10 1.43550E-09 671701 + 953 671710 Ho-171 9.32390E-10 1.00720E-09 671710 + 954 671720 Ho-172 1.55780E-10 1.62860E-10 671720 + 955 671730 Ho-173 3.78850E-11 3.78850E-11 671730 + 956 671740 Ho-174 2.40390E-12 2.40390E-12 671740 + 957 681660 Er-166 1.33230E-12 8.55990E-08 68166.82c + 958 681670 Er-167 8.77220E-12 3.83390E-08 68167.82c + 959 681671 Er-167m 1.16800E-12 4.58120E-09 681671 + 960 681680 Er-168 7.32780E-11 1.70510E-08 68168.82c + 961 681690 Er-169 1.97280E-10 7.58100E-09 681690 + 962 681700 Er-170 5.90010E-10 3.36780E-09 68170.82c + 963 681710 Er-171 4.73340E-10 1.48060E-09 681710 + 964 681720 Er-172 4.72350E-10 6.35210E-10 681720 + 965 681730 Er-173 1.82240E-10 2.20130E-10 681730 + 966 681740 Er-174 7.61860E-11 7.85900E-11 681740 + 967 681750 Er-175 1.07030E-11 1.07030E-11 681750 + 968 681760 Er-176 1.91600E-12 1.91600E-12 681760 + 969 691700 Tm-170 2.99040E-12 2.99040E-12 691700 + 970 691710 Tm-171 1.75470E-11 1.49810E-09 691710 + 971 691720 Tm-172 3.07060E-11 6.65910E-10 691720 + 972 691730 Tm-173 7.47460E-11 2.94870E-10 691730 + 973 691740 Tm-174 4.84000E-11 1.26990E-10 691740 + 974 691750 Tm-175 4.09500E-11 5.16530E-11 691750 + 975 691760 Tm-176 1.19950E-11 1.39110E-11 691760 + 976 691770 Tm-177 4.21800E-12 4.21800E-12 691770 + 977 701730 Yb-173 1.01310E-12 2.95880E-10 701730 + 978 701740 Yb-174 4.63580E-12 1.31630E-10 701740 + 979 701750 Yb-175 5.84050E-12 5.82710E-11 701750 + 980 701751 Yb-175m 7.77630E-13 4.05500E-11 701751 + 981 701760 Yb-176 3.83360E-12 2.42870E-11 701760 + 982 701761 Yb-176m 8.04240E-12 1.49980E-11 701761 + 983 701770 Yb-177 5.35250E-12 1.06480E-11 701770 + 984 701771 Yb-177m 1.07770E-12 5.29570E-12 701771 + 985 701780 Yb-178 3.89570E-12 3.89570E-12 701780 + 986 711790 Lu-179 1.05800E-12 1.19890E-12 711790 + + Neutron-induced fission: + + Interpolation region : 3 / 3 + Interpolation energy : 1.40000E+01 MeV + Number of products : 1162 / 1197 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 3.09570E-05 3.09570E-05 1001.82c + 2 10020 H-2 9.46060E-06 9.46060E-06 1002.82c + 3 10030 H-3 2.48000E-04 2.48000E-04 1003.82c + 4 20040 He-4 1.95700E-03 1.95700E-03 2004.82c + 5 190500 K-50 7.08760E-11 7.08760E-11 190500 + 6 190510 K-51 9.33630E-12 9.33630E-12 190510 + 7 200500 Ca-50 6.62280E-09 6.67750E-09 200500 + 8 200510 Ca-51 2.06010E-09 2.06510E-09 200510 + 9 200520 Ca-52 6.28110E-10 6.28110E-10 200520 + 10 200530 Ca-53 7.78500E-11 7.78500E-11 200530 + 11 200540 Ca-54 8.05200E-12 8.05200E-12 200540 + 12 210500 Sc-50 1.04880E-08 1.93750E-08 210500 + 13 210501 Sc-50m 2.32240E-09 9.00000E-09 210501 + 14 210510 Sc-51 2.03770E-08 2.24550E-08 210510 + 15 210520 Sc-52 1.32040E-08 1.38430E-08 210520 + 16 210530 Sc-53 9.69710E-09 9.75160E-09 210530 + 17 210540 Sc-54 2.42540E-09 2.43350E-09 210540 + 18 210550 Sc-55 6.16440E-10 6.16440E-10 210550 + 19 210560 Sc-56 5.81910E-11 5.81910E-11 210560 + 20 210570 Sc-57 4.73180E-12 4.73180E-12 210570 + 21 220500 Ti-50 3.22940E-09 2.27170E-08 22050.82c + 22 220510 Ti-51 9.90310E-09 3.23580E-08 220510 + 23 220520 Ti-52 3.10870E-08 4.49300E-08 220520 + 24 220530 Ti-53 4.36340E-08 5.33860E-08 220530 + 25 220540 Ti-54 5.76890E-08 6.01230E-08 220540 + 26 220550 Ti-55 3.22670E-08 3.28830E-08 220550 + 27 220560 Ti-56 1.85670E-08 1.86270E-08 220560 + 28 220570 Ti-57 3.72440E-09 3.72760E-09 220570 + 29 220580 Ti-58 6.63990E-10 6.63990E-10 220580 + 30 220590 Ti-59 5.08340E-11 5.08340E-11 220590 + 31 220600 Ti-60 2.97210E-12 2.97210E-12 220600 + 32 230500 V-50 1.50240E-11 1.50240E-11 230500 + 33 230510 V-51 2.75970E-10 3.26340E-08 230510 + 34 230520 V-52 1.86500E-09 4.67950E-08 230520 + 35 230530 V-53 1.35430E-08 6.69290E-08 230530 + 36 230540 V-54 3.38110E-08 9.39330E-08 230540 + 37 230550 V-55 9.19640E-08 1.24850E-07 230550 + 38 230560 V-56 1.03830E-07 1.22470E-07 230560 + 39 230570 V-57 1.14060E-07 1.17780E-07 230570 + 40 230580 V-58 4.62250E-08 4.68890E-08 230580 + 41 230590 V-59 2.21000E-08 2.21510E-08 230590 + 42 230600 V-60 3.24670E-09 3.24970E-09 230600 + 43 230610 V-61 8.42080E-10 8.42080E-10 230610 + 44 230620 V-62 4.49280E-11 4.49280E-11 230620 + 45 240520 Cr-52 9.25720E-12 4.68040E-08 24052.82c + 46 240530 Cr-53 1.60200E-10 6.70890E-08 24053.82c + 47 240540 Cr-54 2.32330E-09 9.62590E-08 24054.82c + 48 240550 Cr-55 1.31280E-08 1.37970E-07 240550 + 49 240560 Cr-56 7.44230E-08 1.97360E-07 240560 + 50 240570 Cr-57 1.52840E-07 3.07660E-07 240570 + 51 240580 Cr-58 3.05850E-07 3.15230E-07 240580 + 52 240590 Cr-59 2.96310E-07 3.18460E-07 240590 + 53 240600 Cr-60 2.46950E-07 2.50250E-07 240600 + 54 240610 Cr-61 1.49870E-07 1.50660E-07 240610 + 55 240620 Cr-62 5.09690E-08 5.10140E-08 240620 + 56 240630 Cr-63 1.28800E-09 1.28800E-09 240630 + 57 240640 Cr-64 3.37670E-10 3.37670E-10 240640 + 58 240650 Cr-65 6.10100E-12 6.10100E-12 240650 + 59 250540 Mn-54 2.46790E-12 2.46790E-12 250540 + 60 250550 Mn-55 8.84220E-11 1.38060E-07 25055.82c + 61 250560 Mn-56 1.16360E-09 1.98530E-07 250560 + 62 250570 Mn-57 1.34200E-08 3.21080E-07 250570 + 63 250580 Mn-58 5.07510E-08 3.65980E-07 250580 + 64 250581 Mn-58m 3.13620E-09 3.13620E-09 250581 + 65 250590 Mn-59 2.56350E-07 5.74810E-07 250590 + 66 250600 Mn-60 2.22220E-08 3.13830E-07 250600 + 67 250601 Mn-60m 3.59600E-07 3.59600E-07 250601 + 68 250610 Mn-61 1.40290E-06 1.55360E-06 250610 + 69 250620 Mn-62 7.98900E-07 8.24410E-07 250620 + 70 250621 Mn-62m 7.85300E-08 1.04040E-07 250621 + 71 250630 Mn-63 1.29990E-07 1.31280E-07 250630 + 72 250640 Mn-64 8.17650E-08 8.21030E-08 250640 + 73 250650 Mn-65 9.61600E-09 9.62210E-09 250650 + 74 250660 Mn-66 2.79510E-09 2.79510E-09 250660 + 75 250670 Mn-67 4.50890E-10 4.50890E-10 250670 + 76 250680 Mn-68 1.51910E-11 1.51910E-11 250680 + 77 260560 Fe-56 1.28620E-12 1.98530E-07 26056.82c + 78 260570 Fe-57 3.71190E-11 3.21110E-07 26057.82c + 79 260580 Fe-58 9.24700E-10 3.70040E-07 26058.82c + 80 260590 Fe-59 9.90970E-09 5.84720E-07 260590 + 81 260600 Fe-60 3.81820E-07 1.01390E-06 260600 + 82 260610 Fe-61 4.67640E-07 2.02120E-06 260610 + 83 260620 Fe-62 2.26260E-06 3.19100E-06 260620 + 84 260630 Fe-63 7.56590E-07 8.87870E-07 260630 + 85 260640 Fe-64 1.44830E-06 1.53040E-06 260640 + 86 260650 Fe-65 4.10060E-07 4.19680E-07 260650 + 87 260660 Fe-66 7.19850E-07 7.22650E-07 260660 + 88 260670 Fe-67 2.84670E-07 2.85120E-07 260670 + 89 260680 Fe-68 6.26890E-08 6.27040E-08 260680 + 90 260690 Fe-69 4.82270E-09 4.82270E-09 260690 + 91 260700 Fe-70 3.30040E-10 3.30040E-10 260700 + 92 260710 Fe-71 9.63840E-12 9.63840E-12 260710 + 93 270590 Co-59 1.51870E-11 5.84740E-07 27059.82c + 94 270600 Co-60 2.57990E-10 3.14980E-10 270600 + 95 270601 Co-60m 5.71310E-11 5.71310E-11 270601 + 96 270610 Co-61 1.13900E-08 2.03260E-06 270610 + 97 270620 Co-62 6.83660E-08 3.26250E-06 270620 + 98 270621 Co-62m 3.08720E-07 3.08720E-07 270621 + 99 270630 Co-63 1.26480E-07 1.01440E-06 270630 + 100 270640 Co-64 9.65500E-07 2.49590E-06 270640 + 101 270650 Co-65 1.49890E-06 1.91860E-06 270650 + 102 270660 Co-66 4.07950E-06 4.80220E-06 270660 + 103 270670 Co-67 6.13210E-06 6.41720E-06 270670 + 104 270680 Co-68 1.11310E-06 1.38570E-06 270680 + 105 270681 Co-68m 4.82070E-07 5.45110E-07 270681 + 106 270690 Co-69 1.60590E-06 1.61040E-06 270690 + 107 270700 Co-70 1.43810E-07 1.43810E-07 270700 + 108 270701 Co-70m 1.43810E-07 1.44140E-07 270701 + 109 270710 Co-71 5.81400E-08 5.81500E-08 270710 + 110 270720 Co-72 3.85130E-09 3.85130E-09 270720 + 111 270730 Co-73 2.56810E-10 2.56810E-10 270730 + 112 270740 Co-74 9.09100E-12 9.09100E-12 270740 + 113 280610 Ni-61 7.02390E-12 2.03260E-06 28061.82c + 114 280620 Ni-62 3.43450E-10 3.56850E-06 28062.82c + 115 280630 Ni-63 1.21390E-09 1.01560E-06 280630 + 116 280640 Ni-64 4.45000E-08 2.54040E-06 28064.82c + 117 280650 Ni-65 1.16100E-07 2.03470E-06 280650 + 118 280660 Ni-66 2.26640E-06 7.06860E-06 280660 + 119 280670 Ni-67 9.19770E-06 1.56150E-05 280670 + 120 280680 Ni-68 1.91420E-05 2.08160E-05 280680 + 121 280690 Ni-69 8.03000E-06 9.62430E-06 280690 + 122 280691 Ni-69m 8.03000E-06 8.03000E-06 280691 + 123 280700 Ni-70 1.76050E-05 1.78930E-05 280700 + 124 280710 Ni-71 9.89060E-06 9.94880E-06 280710 + 125 280720 Ni-72 4.73430E-06 4.73810E-06 280720 + 126 280730 Ni-73 5.90940E-07 5.91200E-07 280730 + 127 280740 Ni-74 8.33090E-08 8.33180E-08 280740 + 128 280750 Ni-75 4.18940E-09 4.18940E-09 280750 + 129 280760 Ni-76 2.00460E-10 2.00460E-10 280760 + 130 290640 Cu-64 3.78980E-11 3.78980E-11 290640 + 131 290650 Cu-65 6.31450E-10 2.03530E-06 29065.82c + 132 290660 Cu-66 2.55830E-08 7.09410E-06 290660 + 133 290670 Cu-67 7.66500E-07 1.63810E-05 290670 + 134 290680 Cu-68 5.78370E-07 2.35890E-05 290680 + 135 290681 Cu-68m 2.61170E-06 2.61170E-06 290681 + 136 290690 Cu-69 1.52550E-05 3.29090E-05 290690 + 137 290700 Cu-70 9.67810E-07 1.12740E-05 290700 + 138 290701 Cu-70m 1.96690E-05 2.06130E-05 290701 + 139 290702 Cu-70m 9.67810E-07 1.88610E-05 290702 + 140 290710 Cu-71 4.86260E-05 5.85750E-05 290710 + 141 290720 Cu-72 4.81390E-05 5.28770E-05 290720 + 142 290730 Cu-73 6.16850E-05 6.22760E-05 290730 + 143 290740 Cu-74 2.04960E-05 2.05790E-05 290740 + 144 290750 Cu-75 7.66800E-06 7.67210E-06 290750 + 145 290760 Cu-76 8.84950E-07 8.85050E-07 290760 + 146 290761 Cu-76m 8.84950E-07 8.85050E-07 290761 + 147 290770 Cu-77 6.67800E-08 6.67800E-08 290770 + 148 290780 Cu-78 2.73440E-09 2.73440E-09 290780 + 149 290790 Cu-79 9.86220E-11 9.86220E-11 290790 + 150 300660 Zn-66 2.26210E-11 7.09410E-06 300660 + 151 300670 Zn-67 1.29650E-09 1.63830E-05 300670 + 152 300680 Zn-68 3.99880E-08 2.40460E-05 300680 + 153 300690 Zn-69 1.79220E-07 3.45150E-05 300690 + 154 300691 Zn-69m 1.42670E-06 1.42670E-06 300691 + 155 300700 Zn-70 8.80080E-06 4.82990E-05 300700 + 156 300710 Zn-71 2.66690E-06 6.12420E-05 300710 + 157 300711 Zn-71m 2.12300E-05 2.12300E-05 300711 + 158 300720 Zn-72 7.88830E-05 1.31760E-04 300720 + 159 300730 Zn-73 8.55540E-06 1.47030E-04 300730 + 160 300731 Zn-73m 1.21710E-05 7.62030E-05 300731 + 161 300732 Zn-73m 1.28060E-04 1.28060E-04 300732 + 162 300740 Zn-74 2.58820E-04 2.79670E-04 300740 + 163 300750 Zn-75 2.34510E-04 2.41940E-04 300750 + 164 300760 Zn-76 1.91380E-04 1.93120E-04 300760 + 165 300770 Zn-77 8.44090E-05 8.79920E-05 300770 + 166 300771 Zn-77m 7.03180E-06 7.03180E-06 300771 + 167 300780 Zn-78 3.12420E-05 3.12450E-05 300780 + 168 300790 Zn-79 7.99610E-06 7.99610E-06 300790 + 169 300800 Zn-80 5.79150E-08 5.79150E-08 300800 + 170 300810 Zn-81 1.52900E-09 1.52900E-09 300810 + 171 310680 Ga-68 7.59530E-12 7.59530E-12 310680 + 172 310690 Ga-69 5.27440E-10 3.45160E-05 310690 + 173 310700 Ga-70 1.27780E-08 1.27780E-08 310700 + 174 310710 Ga-71 1.64820E-06 8.41200E-05 310710 + 175 310720 Ga-72 2.97220E-06 1.34920E-04 310720 + 176 310721 Ga-72m 1.83670E-07 4.57400E-06 310721 + 177 310730 Ga-73 2.63060E-05 2.37370E-04 310730 + 178 310740 Ga-74 4.01180E-05 2.79960E-04 310740 + 179 310741 Ga-74m 4.01180E-05 3.19790E-04 310741 + 180 310750 Ga-75 2.87780E-04 5.29720E-04 310750 + 181 310760 Ga-76 4.51420E-04 6.44540E-04 310760 + 182 310770 Ga-77 6.04040E-04 6.95550E-04 310770 + 183 310780 Ga-78 4.31340E-04 4.62690E-04 310780 + 184 310790 Ga-79 3.07340E-04 3.15230E-04 310790 + 185 310800 Ga-80 1.06610E-04 1.06670E-04 310800 + 186 310810 Ga-81 2.85210E-05 2.85220E-05 310810 + 187 310820 Ga-82 1.89590E-06 1.89590E-06 310820 + 188 310830 Ga-83 2.69230E-08 2.69230E-08 310830 + 189 310840 Ga-84 4.61510E-10 4.61510E-10 310840 + 190 320700 Ge-70 1.74620E-12 1.27270E-08 32070.82c + 191 320710 Ge-71 1.98980E-11 1.78300E-10 320710 + 192 320711 Ge-71m 1.58400E-10 1.58400E-10 320711 + 193 320720 Ge-72 1.07970E-08 1.34930E-04 32072.82c + 194 320730 Ge-73 2.26630E-07 2.37630E-04 32073.82c + 195 320731 Ge-73m 2.84690E-08 2.33920E-04 320731 + 196 320740 Ge-74 1.28070E-05 3.72710E-04 32074.82c + 197 320750 Ge-75 4.38720E-06 5.86750E-04 320750 + 198 320751 Ge-75m 5.26640E-05 7.38530E-05 320751 + 199 320760 Ge-76 2.73030E-04 9.17570E-04 32076.82c + 200 320770 Ge-77 6.47680E-04 7.90080E-04 320770 + 201 320771 Ge-77m 5.39550E-05 7.49500E-04 320771 + 202 320780 Ge-78 1.74030E-03 2.20330E-03 320780 + 203 320790 Ge-79 1.60520E-04 5.52090E-04 320790 + 204 320791 Ge-79m 1.92690E-03 1.92730E-03 320791 + 205 320800 Ge-80 2.59020E-03 2.70030E-03 320800 + 206 320810 Ge-81 1.30490E-03 1.32010E-03 320810 + 207 320811 Ge-81m 1.63920E-04 1.75980E-04 320811 + 208 320820 Ge-82 7.90030E-04 7.91530E-04 320820 + 209 320830 Ge-83 1.35360E-04 1.35380E-04 320830 + 210 320840 Ge-84 1.99660E-05 1.99660E-05 320840 + 211 320850 Ge-85 2.67170E-07 2.67170E-07 320850 + 212 320860 Ge-86 1.09810E-08 1.09810E-08 320860 + 213 330730 As-73 6.60350E-11 6.60350E-11 330730 + 214 330740 As-74 3.42730E-09 3.42730E-09 330740 + 215 330750 As-75 2.20620E-08 5.86930E-04 33075.82c + 216 330751 As-75m 1.36320E-07 1.58470E-07 330751 + 217 330760 As-76 8.84860E-07 8.84860E-07 330760 + 218 330770 As-77 3.15740E-05 1.42870E-03 330770 + 219 330780 As-78 1.83180E-04 2.38650E-03 330780 + 220 330790 As-79 7.50400E-04 3.15280E-03 330790 + 221 330800 As-80 1.79330E-03 4.49360E-03 330800 + 222 330810 As-81 3.49400E-03 4.98830E-03 330810 + 223 330820 As-82 6.26440E-04 1.41800E-03 330820 + 224 330821 As-82m 3.54430E-03 3.54430E-03 330821 + 225 330830 As-83 3.74000E-03 3.87750E-03 330830 + 226 330840 As-84 6.58150E-04 6.67070E-04 330840 + 227 330841 As-84m 6.58150E-04 6.67070E-04 330841 + 228 330850 As-85 4.68440E-04 4.68670E-04 330850 + 229 330860 As-86 8.86800E-05 8.86910E-05 330860 + 230 330870 As-87 1.63590E-05 1.63590E-05 330870 + 231 330880 As-88 8.81510E-08 8.81510E-08 330880 + 232 330890 As-89 3.03990E-09 3.03990E-09 330890 + 233 340750 Se-75 1.68250E-11 1.68250E-11 340750 + 234 340760 Se-76 1.83750E-09 8.86700E-07 34076.82c + 235 340770 Se-77 1.35080E-07 1.43050E-03 34077.82c + 236 340771 Se-77m 1.62150E-06 1.62150E-06 340771 + 237 340780 Se-78 3.67300E-06 2.39010E-03 34078.82c + 238 340790 Se-79 5.71780E-05 3.21300E-03 34079.82c + 239 340791 Se-79m 4.76330E-06 3.08280E-03 340791 + 240 340800 Se-80 4.20090E-04 4.91380E-03 34080.82c + 241 340810 Se-81 1.23530E-04 6.59390E-03 340810 + 242 340811 Se-81m 1.48290E-03 1.66190E-03 340811 + 243 340820 Se-82 4.92760E-03 9.88980E-03 34082.82c + 244 340830 Se-83 7.52170E-03 8.91860E-03 340830 + 245 340831 Se-83m 9.44870E-04 3.42740E-03 340831 + 246 340840 Se-84 1.33710E-02 1.48060E-02 340840 + 247 340850 Se-85 8.99800E-03 9.39280E-03 340850 + 248 340860 Se-86 6.16880E-03 6.23070E-03 340860 + 249 340870 Se-87 2.09600E-03 2.10980E-03 340870 + 250 340880 Se-88 5.92800E-04 5.92890E-04 340880 + 251 340890 Se-89 9.09940E-05 9.09970E-05 340890 + 252 340900 Se-90 8.70570E-06 8.70570E-06 340900 + 253 340910 Se-91 2.09330E-08 2.09330E-08 340910 + 254 350780 Br-78 4.07250E-10 4.07250E-10 350780 + 255 350790 Br-79 3.94270E-09 1.75470E-06 35079.82c + 256 350791 Br-79m 2.43610E-08 2.43610E-08 350791 + 257 350800 Br-80 2.75170E-07 1.83200E-06 350800 + 258 350801 Br-80m 1.55680E-06 1.55680E-06 350801 + 259 350810 Br-81 2.66200E-05 6.62130E-03 35081.82c + 260 350820 Br-82 1.48500E-04 1.80590E-04 350820 + 261 350821 Br-82m 3.28840E-05 3.28840E-05 350821 + 262 350830 Br-83 1.08480E-03 1.34310E-02 350830 + 263 350840 Br-84 1.80650E-03 1.66130E-02 350840 + 264 350841 Br-84m 1.80650E-03 1.80650E-03 350841 + 265 350850 Br-85 1.01900E-02 1.95830E-02 350850 + 266 350860 Br-86 1.22100E-02 1.84410E-02 350860 + 267 350870 Br-87 1.64540E-02 1.85700E-02 350870 + 268 350880 Br-88 8.42790E-03 9.02200E-03 350880 + 269 350890 Br-89 4.72290E-03 4.80680E-03 350890 + 270 350900 Br-90 1.04870E-03 1.05740E-03 350900 + 271 350910 Br-91 3.06670E-04 3.06690E-04 350910 + 272 350920 Br-92 2.31120E-05 2.31120E-05 350920 + 273 350930 Br-93 1.00780E-06 1.00780E-06 350930 + 274 350940 Br-94 2.75870E-09 2.75870E-09 350940 + 275 360800 Kr-80 1.76570E-10 1.68010E-06 36080.82c + 276 360810 Kr-81 7.23370E-09 7.83630E-09 360810 + 277 360811 Kr-81m 6.02610E-10 6.02610E-10 360811 + 278 360820 Kr-82 1.89570E-06 1.83280E-04 36082.82c + 279 360830 Kr-83 2.83330E-05 1.34630E-02 36083.82c + 280 360831 Kr-83m 3.55920E-06 1.34220E-02 360831 + 281 360840 Kr-84 3.70860E-04 1.87910E-02 36084.82c + 282 360850 Kr-85 1.69010E-03 5.95130E-03 36085.82c + 283 360851 Kr-85m 2.12310E-04 1.97630E-02 360851 + 284 360860 Kr-86 8.71700E-03 2.76240E-02 36086.82c + 285 360870 Kr-87 1.87060E-02 3.74140E-02 360870 + 286 360880 Kr-88 3.01020E-02 3.91970E-02 360880 + 287 360890 Kr-89 3.05540E-02 3.49430E-02 360890 + 288 360900 Kr-90 2.35520E-02 2.44110E-02 360900 + 289 360910 Kr-91 9.50470E-03 9.75770E-03 360910 + 290 360920 Kr-92 3.43610E-03 3.45230E-03 360920 + 291 360930 Kr-93 7.27180E-04 7.27500E-04 360930 + 292 360940 Kr-94 1.57360E-04 1.57360E-04 360940 + 293 360950 Kr-95 1.36540E-05 1.36540E-05 360950 + 294 360960 Kr-96 8.80990E-07 8.80990E-07 360960 + 295 370830 Rb-83 3.82270E-10 2.13680E-09 370830 + 296 370831 Rb-83m 1.75450E-09 1.75450E-09 370831 + 297 370840 Rb-84 2.11040E-07 9.49330E-07 370840 + 298 370841 Rb-84m 7.38290E-07 7.38290E-07 370841 + 299 370850 Rb-85 1.57160E-05 2.15010E-02 37085.82c + 300 370860 Rb-86 2.43600E-05 1.09580E-04 37086.82c + 301 370861 Rb-86m 8.52200E-05 8.52200E-05 370861 + 302 370870 Rb-87 1.14940E-03 3.85640E-02 37087.82c + 303 370880 Rb-88 3.48560E-03 4.26830E-02 370880 + 304 370890 Rb-89 1.29720E-02 4.79150E-02 370890 + 305 370900 Rb-90 1.11450E-03 2.28840E-02 370900 + 306 370901 Rb-90m 1.80340E-02 2.12270E-02 370901 + 307 370910 Rb-91 2.77060E-02 3.74640E-02 370910 + 308 370920 Rb-92 1.99720E-02 2.34240E-02 370920 + 309 370930 Rb-93 1.59410E-02 1.66700E-02 370930 + 310 370940 Rb-94 5.33240E-03 5.48840E-03 370940 + 311 370950 Rb-95 1.76180E-03 1.77510E-03 370950 + 312 370960 Rb-96 1.43790E-04 2.16320E-04 370960 + 313 370961 Rb-96m 1.43790E-04 1.44210E-04 370961 + 314 370970 Rb-97 4.82240E-05 4.82240E-05 370970 + 315 370980 Rb-98 4.27650E-07 4.27650E-07 370980 + 316 370981 Rb-98m 4.27650E-07 4.27650E-07 370981 + 317 370990 Rb-99 8.67960E-07 8.67960E-07 370990 + 318 380850 Sr-85 5.53230E-10 6.13420E-10 380850 + 319 380851 Sr-85m 6.94970E-11 6.94970E-11 380851 + 320 380860 Sr-86 1.00520E-06 1.10580E-04 38086.82c + 321 380870 Sr-87 8.30170E-06 9.34140E-06 38087.82c + 322 380871 Sr-87m 1.04290E-06 1.04290E-06 380871 + 323 380880 Sr-88 2.32910E-04 4.29160E-02 38088.82c + 324 380890 Sr-89 1.08770E-03 4.90030E-02 38089.82c + 325 380900 Sr-90 5.36770E-03 4.89270E-02 38090.82c + 326 380910 Sr-91 1.14390E-02 4.89030E-02 380910 + 327 380920 Sr-92 2.26820E-02 4.63400E-02 380920 + 328 380930 Sr-93 3.12390E-02 4.82300E-02 380930 + 329 380940 Sr-94 3.65040E-02 4.15910E-02 380940 + 330 380950 Sr-95 2.04030E-02 2.20540E-02 380950 + 331 380960 Sr-96 1.09580E-02 1.12290E-02 380960 + 332 380970 Sr-97 3.14710E-03 3.18330E-03 380970 + 333 380980 Sr-98 8.19540E-04 8.20470E-04 380980 + 334 380990 Sr-99 9.88650E-05 9.95950E-05 380990 + 335 381000 Sr-100 1.29220E-05 1.29220E-05 381000 + 336 381010 Sr-101 2.54500E-08 2.54500E-08 381010 + 337 390880 Y-88 1.60160E-09 4.14820E-09 390880 + 338 390881 Y-88m 2.54660E-09 2.54660E-09 390881 + 339 390890 Y-89 6.59310E-07 4.90090E-02 39089.82c + 340 390891 Y-89m 5.24850E-06 9.97190E-06 390891 + 341 390900 Y-90 6.20450E-06 4.89510E-02 39090.82c + 342 390901 Y-90m 1.77330E-05 1.77330E-05 390901 + 343 390910 Y-91 3.75960E-05 4.92400E-02 39091.82c + 344 390911 Y-91m 2.99280E-04 2.90710E-02 390911 + 345 390920 Y-92 1.21860E-03 4.75580E-02 390920 + 346 390930 Y-93 4.56920E-04 5.41720E-02 390930 + 347 390931 Y-93m 5.48480E-03 1.75540E-02 390931 + 348 390940 Y-94 1.19900E-02 5.35810E-02 390940 + 349 390950 Y-95 2.29290E-02 4.49830E-02 390950 + 350 390960 Y-96 4.88860E-03 1.61190E-02 390960 + 351 390961 Y-96m 1.71020E-02 1.71030E-02 390961 + 352 390970 Y-97 2.30330E-03 5.13250E-03 390970 + 353 390971 Y-97m 1.06660E-02 1.72750E-02 390971 + 354 390972 Y-97m 7.66950E-03 7.66950E-03 390972 + 355 390980 Y-98 1.17880E-03 1.99930E-03 390980 + 356 390981 Y-98m 9.24420E-03 9.24420E-03 390981 + 357 390990 Y-99 5.06960E-03 5.16930E-03 390990 + 358 391000 Y-100 6.55500E-04 6.68320E-04 391000 + 359 391001 Y-100m 6.55500E-04 6.55500E-04 391001 + 360 391010 Y-101 3.51110E-04 3.51130E-04 391010 + 361 391020 Y-102 2.28050E-05 2.28050E-05 391020 + 362 391021 Y-102m 2.28050E-05 2.28050E-05 391021 + 363 391030 Y-103 7.32470E-06 7.32470E-06 391030 + 364 391040 Y-104 2.07770E-09 2.07770E-09 391040 + 365 400910 Zr-91 1.02270E-06 4.92410E-02 40091.82c + 366 400920 Zr-92 3.91200E-05 4.75970E-02 40092.82c + 367 400930 Zr-93 2.63450E-04 5.44350E-02 40093.82c + 368 400940 Zr-94 1.55610E-03 5.51370E-02 40094.82c + 369 400950 Zr-95 4.66170E-03 4.96450E-02 40095.82c + 370 400960 Zr-96 1.40560E-02 4.72920E-02 40096.82c + 371 400970 Zr-97 2.10010E-02 4.51310E-02 400970 + 372 400980 Zr-98 2.92370E-02 4.02450E-02 400980 + 373 400990 Zr-99 2.11090E-02 2.61970E-02 400990 + 374 401000 Zr-100 1.57670E-02 1.70850E-02 401000 + 375 401010 Zr-101 6.52370E-03 6.87710E-03 401010 + 376 401020 Zr-102 2.72250E-03 2.76650E-03 401020 + 377 401030 Zr-103 5.29670E-04 5.36410E-04 401030 + 378 401040 Zr-104 1.09770E-04 1.09770E-04 401040 + 379 401050 Zr-105 1.00180E-05 1.00180E-05 401050 + 380 401060 Zr-106 2.15850E-06 2.15850E-06 401060 + 381 401070 Zr-107 3.89970E-10 3.89970E-10 401070 + 382 410930 Nb-93 4.55590E-09 5.12820E-09 41093.82c + 383 410931 Nb-93m 5.72310E-10 5.72310E-10 410931 + 384 410940 Nb-94 5.03290E-06 6.78510E-06 41094.82c + 385 410941 Nb-94m 1.76100E-06 1.76100E-06 410941 + 386 410950 Nb-95 5.25970E-05 4.96740E-02 41095.82c + 387 410951 Nb-95m 6.60720E-06 5.42950E-04 410951 + 388 410960 Nb-96 2.73090E-04 2.73090E-04 410960 + 389 410970 Nb-97 1.44280E-03 4.67550E-02 410970 + 390 410971 Nb-97m 1.81240E-04 4.30780E-02 410971 + 391 410980 Nb-98 6.16020E-04 4.08610E-02 410980 + 392 410981 Nb-98m 3.48530E-03 3.48530E-03 410981 + 393 410990 Nb-99 9.60450E-03 2.63780E-02 410990 + 394 410991 Nb-99m 1.20650E-03 1.08470E-02 410991 + 395 411000 Nb-100 1.66130E-03 1.87460E-02 411000 + 396 411001 Nb-100m 1.30280E-02 1.30280E-02 411001 + 397 411010 Nb-101 1.97380E-02 2.66150E-02 411010 + 398 411020 Nb-102 6.80700E-03 9.57350E-03 411020 + 399 411021 Nb-102m 6.80700E-03 6.80700E-03 411021 + 400 411030 Nb-103 9.78240E-03 1.03190E-02 411030 + 401 411040 Nb-104 1.69860E-03 1.80850E-03 411040 + 402 411041 Nb-104m 1.69860E-03 1.69860E-03 411041 + 403 411050 Nb-105 1.36350E-03 1.37340E-03 411050 + 404 411060 Nb-106 2.28730E-04 2.30860E-04 411060 + 405 411070 Nb-107 6.46840E-05 6.46840E-05 411070 + 406 411080 Nb-108 6.01410E-06 6.01410E-06 411080 + 407 411090 Nb-109 2.18450E-09 2.18450E-09 411090 + 408 420950 Mo-95 9.10190E-07 4.97050E-02 42095.82c + 409 420960 Mo-96 2.64300E-06 2.75730E-04 42096.82c + 410 420970 Mo-97 3.24440E-05 4.67880E-02 42097.82c + 411 420980 Mo-98 2.08110E-04 4.45540E-02 42098.82c + 412 420990 Mo-99 8.99630E-04 3.79070E-02 42099.82c + 413 421000 Mo-100 3.22590E-03 3.50000E-02 42100.82c + 414 421010 Mo-101 6.45130E-03 3.30660E-02 421010 + 415 421020 Mo-102 1.23330E-02 2.87130E-02 421020 + 416 421030 Mo-103 1.30780E-02 2.33990E-02 421030 + 417 421040 Mo-104 1.28620E-02 1.63900E-02 421040 + 418 421050 Mo-105 7.35670E-03 8.71710E-03 421050 + 419 421060 Mo-106 3.99310E-03 4.21750E-03 421060 + 420 421070 Mo-107 1.38990E-03 1.45110E-03 421070 + 421 421080 Mo-108 5.63410E-04 5.69050E-04 421080 + 422 421090 Mo-109 1.16040E-04 1.16040E-04 421090 + 423 421100 Mo-110 2.53010E-05 2.53010E-05 421100 + 424 421110 Mo-111 1.15120E-06 1.15120E-06 421110 + 425 421120 Mo-112 5.62960E-10 5.62960E-10 421120 + 426 430980 Tc-98 2.15710E-09 2.15710E-09 430980 + 427 430990 Tc-99 6.93990E-06 3.79140E-02 43099.82c + 428 430991 Tc-99m 8.71790E-07 3.33820E-02 430991 + 429 431000 Tc-100 2.86220E-05 2.86220E-05 431000 + 430 431010 Tc-101 2.67810E-04 3.33340E-02 431010 + 431 431020 Tc-102 4.38320E-04 2.91520E-02 431020 + 432 431021 Tc-102m 4.38320E-04 4.38320E-04 431021 + 433 431030 Tc-103 2.77460E-03 2.61730E-02 431030 + 434 431040 Tc-104 4.41460E-03 2.08050E-02 431040 + 435 431050 Tc-105 7.73530E-03 1.64520E-02 431050 + 436 431060 Tc-106 6.53100E-03 1.07480E-02 431060 + 437 431070 Tc-107 7.80160E-03 9.25270E-03 431070 + 438 431080 Tc-108 4.72440E-03 5.29410E-03 431080 + 439 431090 Tc-109 2.89110E-03 3.00650E-03 431090 + 440 431100 Tc-110 1.09120E-03 1.11650E-03 431100 + 441 431110 Tc-111 3.67390E-04 3.68530E-04 431110 + 442 431120 Tc-112 9.87360E-05 9.87370E-05 431120 + 443 431130 Tc-113 1.13900E-05 1.13900E-05 431130 + 444 431140 Tc-114 8.40490E-07 8.40490E-07 431140 + 445 441010 Ru-101 1.13110E-08 3.33340E-02 44101.82c + 446 441020 Ru-102 2.06500E-05 2.96110E-02 44102.82c + 447 441030 Ru-103 1.83610E-05 2.62760E-02 44103.82c + 448 441031 Ru-103m 8.42690E-05 8.42690E-05 441031 + 449 441040 Ru-104 3.67900E-04 2.11730E-02 44104.82c + 450 441050 Ru-105 9.23190E-04 1.73760E-02 44105.82c + 451 441060 Ru-106 2.25790E-03 1.30060E-02 44106.82c + 452 441070 Ru-107 3.99720E-03 1.32500E-02 441070 + 453 441080 Ru-108 6.78030E-03 1.20770E-02 441080 + 454 441090 Ru-109 6.55750E-03 9.56210E-03 441090 + 455 441100 Ru-110 6.88540E-03 8.00150E-03 441100 + 456 441110 Ru-111 3.90880E-03 4.27880E-03 441110 + 457 441120 Ru-112 2.70640E-03 2.80450E-03 441120 + 458 441130 Ru-113 2.10320E-04 3.26110E-04 441130 + 459 441131 Ru-113m 2.10320E-04 2.10320E-04 441131 + 460 441140 Ru-114 1.42860E-04 1.43650E-04 441140 + 461 441150 Ru-115 3.00000E-05 3.00000E-05 441150 + 462 441160 Ru-116 2.39240E-06 2.39240E-06 441160 + 463 441170 Ru-117 3.81710E-10 3.81710E-10 441170 + 464 441180 Ru-118 9.73560E-08 9.73560E-08 441180 + 465 441190 Ru-119 1.69940E-09 1.69940E-09 441190 + 466 451030 Rh-103 6.27340E-11 2.62760E-02 45103.82c + 467 451031 Rh-103m 7.53060E-10 2.59610E-02 451031 + 468 451040 Rh-104 1.81290E-07 1.20570E-06 451040 + 469 451041 Rh-104m 1.02570E-06 1.02570E-06 451041 + 470 451050 Rh-105 1.73400E-05 1.73940E-02 45105.82c + 471 451051 Rh-105m 1.44460E-06 4.93400E-03 451051 + 472 451060 Rh-106 1.07610E-05 1.30170E-02 451060 + 473 451061 Rh-106m 4.85960E-05 4.85960E-05 451061 + 474 451070 Rh-107 3.25690E-04 1.35760E-02 451070 + 475 451080 Rh-108 1.25760E-04 1.22020E-02 451080 + 476 451081 Rh-108m 7.11550E-04 7.11550E-04 451081 + 477 451090 Rh-109 2.17500E-03 1.17370E-02 451090 + 478 451100 Rh-110 3.85660E-03 1.18580E-02 451100 + 479 451101 Rh-110m 5.79350E-05 5.79350E-05 451101 + 480 451110 Rh-111 6.94080E-03 1.12200E-02 451110 + 481 451120 Rh-112 4.27360E-03 7.07810E-03 451120 + 482 451121 Rh-112m 4.27360E-03 4.27360E-03 451121 + 483 451130 Rh-113 5.54170E-03 5.97300E-03 451130 + 484 451140 Rh-114 1.22980E-03 1.37360E-03 451140 + 485 451141 Rh-114m 1.22980E-03 1.22980E-03 451141 + 486 451150 Rh-115 1.67280E-03 1.70280E-03 451150 + 487 451160 Rh-116 7.92080E-05 8.15750E-05 451160 + 488 451161 Rh-116m 3.57680E-04 3.57680E-04 451161 + 489 451170 Rh-117 1.21410E-04 1.21410E-04 451170 + 490 451180 Rh-118 1.45600E-05 1.46530E-05 451180 + 491 451190 Rh-119 8.71740E-06 8.71900E-06 451190 + 492 451200 Rh-120 3.71250E-07 3.71250E-07 451200 + 493 451210 Rh-121 1.37040E-08 1.37040E-08 451210 + 494 451220 Rh-122 2.81860E-10 2.81860E-10 451220 + 495 461060 Pd-106 1.07920E-06 1.30670E-02 46106.82c + 496 461070 Pd-107 7.66920E-07 1.35790E-02 46107.82c + 497 461071 Pd-107m 2.82690E-06 2.82690E-06 461071 + 498 461080 Pd-108 2.64410E-05 1.29410E-02 46108.82c + 499 461090 Pd-109 2.49150E-05 1.18540E-02 461090 + 500 461091 Pd-109m 9.18350E-05 5.96040E-03 461091 + 501 461100 Pd-110 4.48940E-04 1.23650E-02 46110.82c + 502 461110 Pd-111 2.64400E-04 1.21830E-02 461110 + 503 461111 Pd-111m 9.74600E-04 1.01950E-03 461111 + 504 461120 Pd-112 4.12750E-03 1.54790E-02 461120 + 505 461130 Pd-113 6.86060E-04 9.80790E-03 461130 + 506 461131 Pd-113m 3.14880E-03 3.14880E-03 461131 + 507 461140 Pd-114 6.00020E-03 8.60360E-03 461140 + 508 461150 Pd-115 1.40650E-03 3.29650E-03 461150 + 509 461151 Pd-115m 5.18420E-03 5.43150E-03 461151 + 510 461160 Pd-116 5.46660E-03 5.90590E-03 461160 + 511 461170 Pd-117 4.58680E-04 2.27120E-03 461170 + 512 461171 Pd-117m 1.69070E-03 1.69070E-03 461171 + 513 461180 Pd-118 1.04770E-03 1.06190E-03 461180 + 514 461190 Pd-119 2.39000E-04 2.47740E-04 461190 + 515 461200 Pd-120 7.05110E-05 7.08620E-05 461200 + 516 461210 Pd-121 1.00960E-05 1.01080E-05 461210 + 517 461220 Pd-122 2.68220E-06 2.68250E-06 461220 + 518 461230 Pd-123 9.49330E-08 9.49330E-08 461230 + 519 461240 Pd-124 2.96980E-09 2.96980E-09 461240 + 520 471080 Ag-108 5.69750E-11 7.93590E-11 471080 + 521 471081 Ag-108m 2.57290E-10 2.57290E-10 471081 + 522 471090 Ag-109 1.45590E-09 1.18540E-02 47109.82c + 523 471091 Ag-109m 1.74760E-08 1.18480E-02 471091 + 524 471100 Ag-110 2.08510E-07 2.21320E-07 471100 + 525 471101 Ag-110m 9.41590E-07 9.41590E-07 47510.82c + 526 471110 Ag-111 3.35660E-06 1.24410E-02 47111.82c + 527 471111 Ag-111m 4.02920E-05 1.23330E-02 471111 + 528 471120 Ag-112 1.56550E-04 1.56360E-02 471120 + 529 471130 Ag-113 3.77530E-05 6.75460E-03 471130 + 530 471131 Ag-113m 4.53180E-04 9.84490E-03 471131 + 531 471140 Ag-114 1.41520E-04 9.85490E-03 471140 + 532 471141 Ag-114m 1.10980E-03 1.10980E-03 471141 + 533 471150 Ag-115 3.29530E-04 4.80290E-03 471150 + 534 471151 Ag-115m 3.95570E-03 9.84270E-03 471151 + 535 471160 Ag-116 1.05620E-03 7.24820E-03 471160 + 536 471161 Ag-116m 4.76950E-03 4.76950E-03 471161 + 537 471170 Ag-117 6.10450E-04 2.25390E-03 471170 + 538 471171 Ag-117m 7.32780E-03 8.46350E-03 471171 + 539 471180 Ag-118 6.57550E-04 3.74400E-03 471180 + 540 471181 Ag-118m 5.15630E-03 5.30820E-03 471181 + 541 471190 Ag-119 3.30820E-04 4.54690E-04 471190 + 542 471191 Ag-119m 3.97110E-03 4.09490E-03 471191 + 543 471200 Ag-120 4.69850E-04 1.01530E-03 471200 + 544 471201 Ag-120m 1.34290E-03 1.37830E-03 471201 + 545 471210 Ag-121 8.54180E-04 8.64260E-04 471210 + 546 471220 Ag-122 6.58970E-05 6.85800E-05 471220 + 547 471221 Ag-122m 1.26220E-04 1.26220E-04 471221 + 548 471230 Ag-123 9.82480E-05 9.83430E-05 471230 + 549 471240 Ag-124 2.37780E-06 4.65810E-06 471240 + 550 471241 Ag-124m 4.55460E-06 4.55460E-06 471241 + 551 471250 Ag-125 3.38530E-06 3.38530E-06 471250 + 552 471260 Ag-126 2.15150E-08 2.15150E-08 471260 + 553 471270 Ag-127 6.67290E-10 6.67290E-10 471270 + 554 481110 Cd-111 2.96930E-10 1.25020E-02 48111.82c + 555 481111 Cd-111m 1.83470E-09 1.83470E-09 481111 + 556 481120 Cd-112 1.54250E-07 1.56360E-02 48112.82c + 557 481130 Cd-113 1.95080E-06 1.01840E-02 48113.82c + 558 481131 Cd-113m 1.20530E-05 1.28830E-04 481131 + 559 481140 Cd-114 6.20050E-05 9.91690E-03 48114.82c + 560 481150 Cd-115 4.86780E-05 1.21240E-02 481150 + 561 481151 Cd-115m 3.00770E-04 8.03910E-04 48515.82c + 562 481160 Cd-116 1.38360E-03 1.31150E-02 48116.82c + 563 481170 Cd-117 3.96990E-04 8.25430E-03 481170 + 564 481171 Cd-117m 2.45290E-03 4.80510E-03 481171 + 565 481180 Cd-118 5.49100E-03 1.23670E-02 481180 + 566 481190 Cd-119 1.04320E-03 5.36560E-03 481190 + 567 481191 Cd-119m 4.78820E-03 5.01550E-03 481191 + 568 481200 Cd-120 7.30050E-03 9.18410E-03 481200 + 569 481210 Cd-121 8.83910E-04 1.65790E-03 481210 + 570 481211 Cd-121m 4.05690E-03 4.14720E-03 481211 + 571 481220 Cd-122 3.69020E-03 3.88500E-03 481220 + 572 481230 Cd-123 2.97030E-04 3.77490E-04 481230 + 573 481231 Cd-123m 1.36330E-03 1.38120E-03 481231 + 574 481240 Cd-124 1.02610E-03 1.03300E-03 481240 + 575 481250 Cd-125 6.14490E-05 6.31410E-05 481250 + 576 481251 Cd-125m 2.82030E-04 2.83720E-04 481251 + 577 481260 Cd-126 1.22560E-04 1.22580E-04 481260 + 578 481270 Cd-127 3.07440E-05 3.07450E-05 481270 + 579 481280 Cd-128 7.60380E-06 7.60380E-06 481280 + 580 481290 Cd-129 1.34430E-09 1.34430E-09 481290 + 581 481291 Cd-129m 6.17000E-09 6.17000E-09 481291 + 582 491130 In-113 2.79890E-10 1.28650E-04 49113.82c + 583 491131 In-113m 3.51600E-11 3.51600E-11 491131 + 584 491140 In-114 1.42520E-09 9.20650E-09 491140 + 585 491141 In-114m 2.64360E-09 8.06350E-09 491141 + 586 491142 In-114m 5.41990E-09 5.41990E-09 491142 + 587 491150 In-115 2.04840E-06 1.23240E-02 49115.82c + 588 491151 In-115m 2.57320E-07 1.21240E-02 491151 + 589 491160 In-116 3.77210E-06 3.77210E-06 491160 + 590 491161 In-116m 6.99680E-06 2.13420E-05 491161 + 591 491162 In-116m 1.43450E-05 1.43450E-05 491162 + 592 491170 In-117 1.17170E-04 9.14320E-03 491170 + 593 491171 In-117m 1.47190E-05 7.65240E-03 491171 + 594 491180 In-118 7.06770E-05 1.24380E-02 491180 + 595 491181 In-118m 1.31090E-04 3.96110E-04 491181 + 596 491182 In-118m 2.68780E-04 2.68780E-04 491182 + 597 491190 In-119 1.24500E-03 7.05190E-03 491190 + 598 491191 In-119m 1.56400E-04 5.01120E-03 491191 + 599 491200 In-120 9.01680E-04 1.00860E-02 491200 + 600 491201 In-120m 9.01680E-04 9.01680E-04 491201 + 601 491202 In-120m 9.01680E-04 9.01680E-04 491202 + 602 491210 In-121 4.86220E-03 9.58830E-03 491210 + 603 491211 In-121m 6.10790E-04 1.71030E-03 491211 + 604 491220 In-122 1.47770E-03 5.36270E-03 491220 + 605 491221 In-122m 2.11160E-03 2.11160E-03 491221 + 606 491222 In-122m 2.11160E-03 2.11160E-03 491222 + 607 491230 In-123 6.68360E-03 8.16480E-03 491230 + 608 491231 In-123m 8.39590E-04 1.11700E-03 491231 + 609 491240 In-124 1.82800E-03 2.86100E-03 491240 + 610 491241 In-124m 3.50130E-03 3.50130E-03 491241 + 611 491250 In-125 4.52880E-03 4.84270E-03 491250 + 612 491251 In-125m 5.68900E-04 6.01820E-04 491251 + 613 491260 In-126 9.74910E-04 1.09750E-03 491260 + 614 491261 In-126m 1.86740E-03 1.86740E-03 491261 + 615 491270 In-127 1.76230E-03 1.76230E-03 491270 + 616 491271 In-127m 2.21380E-04 2.52130E-04 491271 + 617 491280 In-128 1.65740E-04 2.31880E-04 491280 + 618 491281 In-128m 5.85370E-05 6.61410E-05 491281 + 619 491282 In-128m 4.29710E-04 4.29710E-04 491282 + 620 491290 In-129 2.14160E-04 2.14160E-04 491290 + 621 491291 In-129m 2.69020E-05 2.69040E-05 491291 + 622 491300 In-130 5.51770E-06 5.51770E-06 491300 + 623 491301 In-130m 1.78830E-05 1.78830E-05 491301 + 624 491302 In-130m 1.33350E-05 1.33350E-05 491302 + 625 491310 In-131 1.54950E-06 1.56520E-06 491310 + 626 491311 In-131m 1.54950E-06 1.54950E-06 491311 + 627 491312 In-131m 1.54950E-06 1.54950E-06 491312 + 628 491320 In-132 9.86210E-10 9.86210E-10 491320 + 629 501160 Sn-116 2.39630E-09 2.51160E-05 50116.82c + 630 501170 Sn-117 1.70170E-07 1.31930E-02 50117.82c + 631 501171 Sn-117m 1.05140E-06 3.22030E-05 501171 + 632 501180 Sn-118 3.63810E-06 1.28410E-02 50118.82c + 633 501190 Sn-119 4.32920E-06 1.18130E-02 50119.82c + 634 501191 Sn-119m 2.67490E-05 6.39750E-03 501191 + 635 501200 Sn-120 2.48550E-04 1.21400E-02 50120.82c + 636 501210 Sn-121 1.15160E-04 1.15600E-02 501210 + 637 501211 Sn-121m 5.28530E-04 1.61470E-03 501211 + 638 501220 Sn-122 1.90930E-03 1.14960E-02 50122.82c + 639 501230 Sn-123 2.72490E-03 3.34740E-03 50123.82c + 640 501231 Sn-123m 5.93700E-04 9.25300E-03 501231 + 641 501240 Sn-124 6.64290E-03 1.30050E-02 50124.82c + 642 501250 Sn-125 6.29420E-03 7.11230E-03 50125.82c + 643 501251 Sn-125m 1.37140E-03 5.99790E-03 501251 + 644 501260 Sn-126 1.18420E-02 1.48090E-02 50126.82c + 645 501270 Sn-127 8.29390E-03 8.98080E-03 501270 + 646 501271 Sn-127m 1.80710E-03 3.13290E-03 501271 + 647 501280 Sn-128 1.93460E-03 1.13330E-02 501280 + 648 501281 Sn-128m 8.73640E-03 9.16610E-03 501281 + 649 501290 Sn-129 9.86130E-04 1.20450E-03 501290 + 650 501291 Sn-129m 4.52610E-03 4.54890E-03 501291 + 651 501300 Sn-130 5.42650E-04 5.59920E-04 501300 + 652 501301 Sn-130m 2.45040E-03 2.46990E-03 501301 + 653 501310 Sn-131 1.48400E-04 1.51400E-04 501310 + 654 501311 Sn-131m 6.81090E-04 6.82710E-04 501311 + 655 501320 Sn-132 1.19580E-04 1.19580E-04 501320 + 656 501330 Sn-133 4.92600E-06 4.92600E-06 501330 + 657 501340 Sn-134 1.58300E-06 1.58300E-06 501340 + 658 511200 Sb-120 6.40350E-07 6.40350E-07 511200 + 659 511201 Sb-120m 1.83010E-06 1.83010E-06 511201 + 660 511210 Sb-121 1.76650E-05 1.19390E-02 51121.82c + 661 511220 Sb-122 1.42450E-05 4.71390E-05 511220 + 662 511221 Sb-122m 3.28940E-05 3.28940E-05 511221 + 663 511230 Sb-123 2.41520E-04 1.28420E-02 51123.82c + 664 511240 Sb-124 1.36400E-04 4.94280E-04 51124.82c + 665 511241 Sb-124m 1.26700E-04 4.77170E-04 511241 + 666 511242 Sb-124m 3.50470E-04 3.50470E-04 511242 + 667 511250 Sb-125 2.01420E-03 1.51240E-02 51125.82c + 668 511260 Sb-126 2.03760E-03 2.25170E-03 51126.82c + 669 511261 Sb-126m 7.36630E-04 1.52960E-03 511261 + 670 511262 Sb-126m 7.92990E-04 7.92990E-04 511262 + 671 511270 Sb-127 8.36220E-03 2.04760E-02 511270 + 672 511280 Sb-128 6.32260E-03 1.78260E-02 511280 + 673 511281 Sb-128m 4.74640E-03 4.74640E-03 511281 + 674 511290 Sb-129 7.71570E-03 1.31070E-02 511290 + 675 511291 Sb-129m 1.04770E-02 1.27520E-02 511291 + 676 511300 Sb-130 7.27900E-03 9.07390E-03 511300 + 677 511301 Sb-130m 7.27900E-03 8.51400E-03 511301 + 678 511310 Sb-131 1.47620E-02 1.55960E-02 511310 + 679 511320 Sb-132 1.70590E-03 1.82550E-03 511320 + 680 511321 Sb-132m 2.71240E-03 2.71240E-03 511321 + 681 511330 Sb-133 1.68950E-03 1.69470E-03 511330 + 682 511340 Sb-134 3.25110E-05 3.38250E-05 511340 + 683 511341 Sb-134m 1.46810E-04 1.46810E-04 511341 + 684 511350 Sb-135 2.18620E-05 2.18620E-05 511350 + 685 511360 Sb-136 1.61790E-06 1.61790E-06 511360 + 686 511370 Sb-137 1.52920E-09 1.52920E-09 511370 + 687 521220 Te-122 1.17830E-06 4.70920E-05 52122.82c + 688 521230 Te-123 6.59560E-07 4.73480E-06 52123.82c + 689 521231 Te-123m 4.07520E-06 4.07520E-06 521231 + 690 521240 Te-124 2.42680E-05 6.37840E-04 52124.82c + 691 521250 Te-125 1.39970E-05 1.52250E-02 52125.82c + 692 521251 Te-125m 8.64830E-05 3.47080E-03 521251 + 693 521260 Te-126 4.23730E-04 3.99290E-03 52126.82c + 694 521270 Te-127 1.84960E-04 2.14080E-02 521270 + 695 521271 Te-127m 8.48930E-04 4.22330E-03 52527.82c + 696 521280 Te-128 3.70590E-03 2.61140E-02 52128.82c + 697 521290 Te-129 1.42520E-03 2.47710E-02 521290 + 698 521291 Te-129m 6.54140E-03 1.93010E-02 52529.82c + 699 521300 Te-130 1.85290E-02 3.61170E-02 52130.82c + 700 521310 Te-131 4.84000E-03 2.41150E-02 521310 + 701 521311 Te-131m 2.22140E-02 2.34630E-02 521311 + 702 521320 Te-132 2.61410E-02 3.06790E-02 52132.82c + 703 521330 Te-133 3.31210E-03 7.42550E-03 521330 + 704 521331 Te-133m 1.52020E-02 1.54950E-02 521331 + 705 521340 Te-134 1.11840E-02 1.13680E-02 521340 + 706 521350 Te-135 2.22190E-03 2.24060E-03 521350 + 707 521360 Te-136 5.88200E-04 5.89550E-04 521360 + 708 521370 Te-137 7.91280E-05 7.91290E-05 521370 + 709 521380 Te-138 1.53440E-05 1.53440E-05 521380 + 710 521390 Te-139 1.98870E-08 1.98870E-08 521390 + 711 531260 I-126 3.43880E-06 3.43880E-06 531260 + 712 531270 I-127 2.19700E-05 2.15320E-02 53127.82c + 713 531280 I-128 8.91670E-05 8.91670E-05 531280 + 714 531290 I-129 4.74230E-04 3.23870E-02 53129.82c + 715 531300 I-130 1.06260E-03 1.26030E-03 53130.82c + 716 531301 I-130m 2.35310E-04 2.35310E-04 531301 + 717 531310 I-131 5.45100E-03 4.81010E-02 53131.82c + 718 531320 I-132 3.24760E-03 3.83670E-02 531320 + 719 531321 I-132m 5.16380E-03 5.16380E-03 531321 + 720 531330 I-133 9.18560E-03 4.18680E-02 531330 + 721 531331 I-133m 1.24730E-02 1.24730E-02 531331 + 722 531340 I-134 9.39960E-03 3.53690E-02 531340 + 723 531341 I-134m 1.49450E-02 1.49450E-02 531341 + 724 531350 I-135 2.55400E-02 2.77810E-02 53135.82c + 725 531360 I-136 1.72370E-03 2.31450E-03 531360 + 726 531361 I-136m 7.78390E-03 7.78510E-03 531361 + 727 531370 I-137 4.18600E-03 4.26370E-03 531370 + 728 531380 I-138 8.82280E-04 8.96660E-04 531380 + 729 531390 I-139 3.77130E-04 3.77150E-04 531390 + 730 531400 I-140 3.45960E-05 3.45960E-05 531400 + 731 531410 I-141 2.41260E-06 2.41260E-06 531410 + 732 531420 I-142 1.96310E-09 1.96310E-09 531420 + 733 541280 Xe-128 2.17270E-06 8.51870E-05 54128.82c + 734 541290 Xe-129 1.62840E-06 1.16900E-05 54129.82c + 735 541291 Xe-129m 1.00620E-05 1.00620E-05 541291 + 736 541300 Xe-130 5.25120E-05 1.35040E-03 54130.82c + 737 541310 Xe-131 4.14300E-05 4.83330E-02 54131.82c + 738 541311 Xe-131m 1.90150E-04 7.12620E-04 541311 + 739 541320 Xe-132 2.63540E-04 3.99660E-02 54132.82c + 740 541321 Xe-132m 6.08530E-04 6.08530E-04 541321 + 741 541330 Xe-133 5.78450E-04 4.51010E-02 54133.82c + 742 541331 Xe-133m 2.65490E-03 3.84670E-03 541331 + 743 541340 Xe-134 2.06660E-03 4.71120E-02 54134.82c + 744 541341 Xe-134m 9.33240E-03 9.67610E-03 541341 + 745 541350 Xe-135 3.96410E-03 4.98020E-02 54135.82c + 746 541351 Xe-135m 1.81940E-02 2.27800E-02 541351 + 747 541360 Xe-136 4.05590E-02 5.09360E-02 54136.82c + 748 541370 Xe-137 2.79490E-02 3.19830E-02 541370 + 749 541380 Xe-138 2.32560E-02 2.41420E-02 541380 + 750 541390 Xe-139 9.62940E-03 9.97280E-03 541390 + 751 541400 Xe-140 3.70820E-03 3.74010E-03 541400 + 752 541410 Xe-141 7.77870E-04 7.79780E-04 541410 + 753 541420 Xe-142 1.52350E-04 1.52350E-04 541420 + 754 541430 Xe-143 8.34890E-06 8.34890E-06 541430 + 755 541440 Xe-144 9.73310E-07 9.73310E-07 541440 + 756 551310 Cs-131 7.50750E-09 7.50750E-09 551310 + 757 551320 Cs-132 3.98820E-06 3.98820E-06 551320 + 758 551330 Cs-133 4.76130E-05 4.51500E-02 55133.82c + 759 551340 Cs-134 9.09770E-05 2.35630E-04 55134.82c + 760 551341 Cs-134m 1.44650E-04 1.44650E-04 551341 + 761 551350 Cs-135 6.78010E-04 5.15370E-02 55135.82c + 762 551351 Cs-135m 9.20690E-04 9.20690E-04 551351 + 763 551360 Cs-136 2.14550E-03 3.57450E-03 55136.82c + 764 551361 Cs-136m 2.85800E-03 2.85800E-03 551361 + 765 551370 Cs-137 1.60150E-02 4.79980E-02 55137.82c + 766 551380 Cs-138 5.74210E-03 4.31770E-02 551380 + 767 551381 Cs-138m 1.64110E-02 1.64110E-02 551381 + 768 551390 Cs-139 2.88850E-02 3.88580E-02 551390 + 769 551400 Cs-140 1.52230E-02 1.89630E-02 551400 + 770 551410 Cs-141 1.29960E-02 1.37760E-02 551410 + 771 551420 Cs-142 4.15390E-03 4.30580E-03 551420 + 772 551430 Cs-143 1.36090E-03 1.36920E-03 551430 + 773 551440 Cs-144 1.12390E-04 1.69540E-04 551440 + 774 551441 Cs-144m 1.12390E-04 1.12390E-04 551441 + 775 551450 Cs-145 3.19180E-05 3.19180E-05 551450 + 776 551460 Cs-146 8.94360E-07 8.94360E-07 551460 + 777 551470 Cs-147 7.45580E-10 7.45580E-10 551470 + 778 561330 Ba-133 1.14370E-07 8.20960E-07 561330 + 779 561331 Ba-133m 7.06660E-07 7.06660E-07 561331 + 780 561340 Ba-134 6.33170E-06 2.41960E-04 56134.82c + 781 561350 Ba-135 5.72770E-06 3.20160E-05 56135.82c + 782 561351 Ba-135m 2.62880E-05 2.62880E-05 561351 + 783 561360 Ba-136 5.19820E-05 5.29020E-03 56136.82c + 784 561361 Ba-136m 2.34740E-04 2.34740E-04 561361 + 785 561370 Ba-137 2.88660E-04 4.96120E-02 56137.82c + 786 561371 Ba-137m 1.32480E-03 4.66350E-02 561371 + 787 561380 Ba-138 8.87310E-03 5.51680E-02 56138.82c + 788 561390 Ba-139 1.72310E-02 5.60890E-02 561390 + 789 561400 Ba-140 2.49040E-02 4.38670E-02 56140.82c + 790 561410 Ba-141 2.43040E-02 3.80800E-02 561410 + 791 561420 Ba-142 2.69880E-02 3.13160E-02 561420 + 792 561430 Ba-143 1.38770E-02 1.52290E-02 561430 + 793 561440 Ba-144 7.31270E-03 7.53760E-03 561440 + 794 561450 Ba-145 1.78250E-03 1.81000E-03 561450 + 795 561460 Ba-146 4.80000E-04 4.80770E-04 561460 + 796 561470 Ba-147 7.18180E-05 7.18190E-05 561470 + 797 561480 Ba-148 1.34710E-05 1.34710E-05 561480 + 798 561490 Ba-149 9.79990E-07 9.79990E-07 561490 + 799 571360 La-136 2.68980E-09 5.37960E-09 571360 + 800 571361 La-136m 2.68980E-09 2.68980E-09 571361 + 801 571370 La-137 8.79520E-06 8.79520E-06 571370 + 802 571380 La-138 1.04130E-04 1.04130E-04 57138.82c + 803 571390 La-139 8.65380E-04 5.69670E-02 57139.82c + 804 571400 La-140 1.74460E-03 4.56120E-02 57140.82c + 805 571410 La-141 5.65730E-03 4.37370E-02 571410 + 806 571420 La-142 7.26260E-03 3.85790E-02 571420 + 807 571430 La-143 1.34440E-02 2.86730E-02 571430 + 808 571440 La-144 1.22070E-02 1.97450E-02 571440 + 809 571450 La-145 1.01400E-02 1.19500E-02 571450 + 810 571460 La-146 9.27790E-04 1.40860E-03 571460 + 811 571461 La-146m 3.24580E-03 3.24580E-03 571461 + 812 571470 La-147 2.04870E-03 2.12060E-03 571470 + 813 571480 La-148 5.11990E-04 5.25410E-04 571480 + 814 571490 La-149 1.05290E-04 1.06270E-04 571490 + 815 571500 La-150 1.83320E-05 1.83320E-05 571500 + 816 571510 La-151 1.99130E-08 1.99130E-08 571510 + 817 571520 La-152 1.94910E-10 1.94910E-10 571520 + 818 581380 Ce-138 3.97410E-07 2.19200E-06 581380 + 819 581381 Ce-138m 1.79460E-06 1.79460E-06 581381 + 820 581390 Ce-139 2.37060E-06 1.32510E-05 581390 + 821 581391 Ce-139m 1.08800E-05 1.08800E-05 581391 + 822 581400 Ce-140 9.03630E-05 4.57020E-02 58140.82c + 823 581410 Ce-141 3.33920E-04 4.40710E-02 58141.82c + 824 581420 Ce-142 1.35950E-03 3.99380E-02 58142.82c + 825 581430 Ce-143 2.48900E-03 3.11620E-02 58143.82c + 826 581440 Ce-144 6.29760E-03 2.60420E-02 58144.82c + 827 581450 Ce-145 8.39900E-03 2.03490E-02 581450 + 828 581460 Ce-146 1.06840E-02 1.53380E-02 581460 + 829 581470 Ce-147 7.66560E-03 9.78620E-03 581470 + 830 581480 Ce-148 5.97500E-03 6.50190E-03 581480 + 831 581490 Ce-149 2.38000E-03 2.48530E-03 581490 + 832 581500 Ce-150 9.22900E-04 9.40740E-04 581500 + 833 581510 Ce-151 1.68300E-04 1.68320E-04 581510 + 834 581520 Ce-152 3.18600E-05 3.18600E-05 581520 + 835 581530 Ce-153 2.36780E-06 2.36780E-06 581530 + 836 581540 Ce-154 8.61190E-10 8.61190E-10 581540 + 837 591410 Pr-141 1.20620E-06 4.40720E-02 59141.82c + 838 591420 Pr-142 1.00710E-06 5.55470E-06 59142.82c + 839 591421 Pr-142m 4.54760E-06 4.54760E-06 591421 + 840 591430 Pr-143 3.96050E-05 3.12020E-02 59143.82c + 841 591440 Pr-144 7.61490E-06 2.61730E-02 591440 + 842 591441 Pr-144m 1.23230E-04 4.82590E-04 591441 + 843 591450 Pr-145 4.88070E-04 2.08370E-02 591450 + 844 591460 Pr-146 1.09510E-03 1.64340E-02 591460 + 845 591470 Pr-147 2.27930E-03 1.20650E-02 591470 + 846 591480 Pr-148 3.38080E-04 6.84000E-03 591480 + 847 591481 Pr-148m 2.65110E-03 2.65110E-03 591481 + 848 591490 Pr-149 3.93870E-03 6.42400E-03 591490 + 849 591500 Pr-150 2.82840E-03 3.76910E-03 591500 + 850 591510 Pr-151 1.67550E-03 1.84380E-03 591510 + 851 591520 Pr-152 4.41670E-04 4.73550E-04 591520 + 852 591530 Pr-153 1.19120E-04 1.21470E-04 591530 + 853 591540 Pr-154 2.01250E-05 2.01260E-05 591540 + 854 591550 Pr-155 1.59820E-06 1.59820E-06 591550 + 855 591560 Pr-156 1.97650E-09 1.97650E-09 591560 + 856 591570 Pr-157 3.43570E-11 3.43570E-11 591570 + 857 601440 Nd-144 9.73220E-07 2.61740E-02 60144.82c + 858 601450 Nd-145 1.31280E-05 2.08500E-02 60145.82c + 859 601460 Nd-146 6.58110E-05 1.64990E-02 60146.82c + 860 601470 Nd-147 2.38840E-04 1.23040E-02 60147.82c + 861 601480 Nd-148 6.58440E-04 1.01500E-02 60148.82c + 862 601490 Nd-149 1.31390E-03 7.73790E-03 601490 + 863 601500 Nd-150 2.30000E-03 6.06910E-03 60150.82c + 864 601510 Nd-151 2.11880E-03 3.96260E-03 601510 + 865 601520 Nd-152 1.70600E-03 2.17950E-03 601520 + 866 601530 Nd-153 7.31510E-04 8.52980E-04 601530 + 867 601540 Nd-154 3.25980E-04 3.46110E-04 601540 + 868 601550 Nd-155 8.31640E-05 8.47620E-05 601550 + 869 601560 Nd-156 2.42180E-05 2.42200E-05 601560 + 870 601570 Nd-157 1.72980E-07 1.73010E-07 601570 + 871 601580 Nd-158 6.30510E-09 6.30510E-09 601580 + 872 601590 Nd-159 1.00410E-10 1.00410E-10 601590 + 873 601600 Nd-160 2.84890E-12 2.84890E-12 601600 + 874 611460 Pm-146 7.96490E-10 7.96490E-10 611460 + 875 611470 Pm-147 1.70860E-06 1.23060E-02 61147.82c + 876 611480 Pm-148 3.25490E-07 3.98980E-07 61148.82c + 877 611481 Pm-148m 1.46980E-06 1.46980E-06 61548.82c + 878 611490 Pm-149 3.51950E-05 7.77310E-03 61149.82c + 879 611500 Pm-150 1.09320E-04 1.09320E-04 611500 + 880 611510 Pm-151 3.18550E-04 4.28120E-03 61151.82c + 881 611520 Pm-152 4.67860E-05 2.22630E-03 611520 + 882 611521 Pm-152m 1.12930E-04 1.12930E-04 611521 + 883 611522 Pm-152m 2.53950E-04 2.53950E-04 611522 + 884 611530 Pm-153 4.59010E-04 1.31200E-03 611530 + 885 611540 Pm-154 1.96520E-04 5.42630E-04 611540 + 886 611541 Pm-154m 1.96520E-04 1.96520E-04 611541 + 887 611550 Pm-155 2.96590E-04 3.81350E-04 611550 + 888 611560 Pm-156 1.52280E-04 1.76500E-04 611560 + 889 611570 Pm-157 6.02850E-05 6.04580E-05 611570 + 890 611580 Pm-158 1.27940E-05 1.28000E-05 611580 + 891 611590 Pm-159 2.75740E-07 2.75840E-07 611590 + 892 611600 Pm-160 1.11210E-08 1.11240E-08 611600 + 893 611610 Pm-161 3.31610E-10 3.31610E-10 611610 + 894 611620 Pm-162 3.65420E-12 3.65420E-12 611620 + 895 621490 Sm-149 9.79880E-07 7.77410E-03 62149.82c + 896 621500 Sm-150 5.38450E-06 1.14700E-04 62150.82c + 897 621510 Sm-151 1.04380E-05 4.29160E-03 62151.82c + 898 621520 Sm-152 4.38710E-05 2.63770E-03 62152.82c + 899 621530 Sm-153 1.59300E-05 1.40100E-03 62153.82c + 900 621531 Sm-153m 7.31160E-05 7.31160E-05 621531 + 901 621540 Sm-154 1.68990E-04 9.08140E-04 62154.82c + 902 621550 Sm-155 1.96330E-04 5.77680E-04 621550 + 903 621560 Sm-156 2.33310E-04 4.09810E-04 621560 + 904 621570 Sm-157 1.63550E-04 2.24010E-04 621570 + 905 621580 Sm-158 8.44480E-05 9.72480E-05 621580 + 906 621590 Sm-159 4.02730E-05 4.05490E-05 621590 + 907 621600 Sm-160 1.62770E-05 1.62880E-05 621600 + 908 621610 Sm-161 3.68740E-07 3.69070E-07 621610 + 909 621620 Sm-162 2.79930E-08 2.79970E-08 621620 + 910 621630 Sm-163 7.05070E-10 7.05070E-10 621630 + 911 621640 Sm-164 3.11230E-11 3.11230E-11 621640 + 912 631510 Eu-151 2.69100E-10 4.29160E-03 63151.82c + 913 631520 Eu-152 2.66050E-07 8.80010E-07 63152.82c + 914 631521 Eu-152m 5.43870E-08 5.43870E-08 631521 + 915 631522 Eu-152m 6.13960E-07 6.13960E-07 631522 + 916 631530 Eu-153 1.20730E-07 1.40120E-03 63153.82c + 917 631540 Eu-154 7.95420E-07 2.31900E-06 63154.82c + 918 631541 Eu-154m 1.52360E-06 1.52360E-06 631541 + 919 631550 Eu-155 1.35810E-05 5.91260E-04 63155.82c + 920 631560 Eu-156 2.50700E-05 4.34880E-04 63156.82c + 921 631570 Eu-157 4.99090E-05 2.73920E-04 63157.82c + 922 631580 Eu-158 4.77460E-05 1.44990E-04 631580 + 923 631590 Eu-159 5.39870E-05 9.45360E-05 631590 + 924 631600 Eu-160 3.76370E-05 5.39250E-05 631600 + 925 631610 Eu-161 1.59190E-05 1.62880E-05 631610 + 926 631620 Eu-162 9.57810E-06 9.60610E-06 631620 + 927 631630 Eu-163 1.19440E-06 1.19510E-06 631630 + 928 631640 Eu-164 4.83630E-08 4.83940E-08 631640 + 929 631650 Eu-165 2.29450E-09 2.29450E-09 631650 + 930 631660 Eu-166 1.57750E-11 1.57750E-11 631660 + 931 641540 Gd-154 4.30590E-10 2.31900E-06 64154.82c + 932 641550 Gd-155 1.50990E-09 5.91270E-04 64155.82c + 933 641551 Gd-155m 6.93010E-09 6.93010E-09 641551 + 934 641560 Gd-156 2.59390E-06 4.37470E-04 64156.82c + 935 641570 Gd-157 3.44330E-06 2.77360E-04 64157.82c + 936 641580 Gd-158 9.37990E-06 1.54380E-04 64158.82c + 937 641590 Gd-159 1.18950E-05 1.06430E-04 641590 + 938 641600 Gd-160 2.33910E-05 7.73160E-05 64160.82c + 939 641610 Gd-161 2.57130E-05 4.20010E-05 641610 + 940 641620 Gd-162 1.55630E-05 2.51690E-05 641620 + 941 641630 Gd-163 1.31380E-05 1.43330E-05 641630 + 942 641640 Gd-164 5.99230E-06 6.04070E-06 641640 + 943 641650 Gd-165 1.17860E-06 1.18090E-06 641650 + 944 641660 Gd-166 2.58730E-08 2.58890E-08 641660 + 945 641670 Gd-167 2.83680E-09 2.83680E-09 641670 + 946 641680 Gd-168 1.69170E-10 1.69170E-10 641680 + 947 641690 Gd-169 1.04820E-12 1.04820E-12 641690 + 948 651560 Tb-156 2.60690E-12 1.06830E-11 651560 + 949 651561 Tb-156m 7.45530E-12 7.45530E-12 651561 + 950 651570 Tb-157 6.52770E-10 6.52770E-10 651570 + 951 651580 Tb-158 8.12200E-09 8.62080E-09 651580 + 952 651581 Tb-158m 5.01910E-10 5.01910E-10 651581 + 953 651590 Tb-159 1.28760E-07 1.06560E-04 65159.82c + 954 651600 Tb-160 1.01720E-06 1.01720E-06 65160.82c + 955 651610 Tb-161 4.89780E-06 4.68990E-05 651610 + 956 651620 Tb-162 3.59150E-06 2.87610E-05 651620 + 957 651630 Tb-163 2.38870E-06 1.67220E-05 651630 + 958 651640 Tb-164 1.19840E-05 1.80250E-05 651640 + 959 651650 Tb-165 7.07130E-06 8.25220E-06 651650 + 960 651660 Tb-166 1.12940E-06 1.15530E-06 651660 + 961 651670 Tb-167 4.07870E-07 4.10710E-07 651670 + 962 651680 Tb-168 5.93760E-08 5.95450E-08 651680 + 963 651690 Tb-169 2.40520E-09 2.40630E-09 651690 + 964 651700 Tb-170 8.56320E-11 8.56320E-11 651700 + 965 651710 Tb-171 1.44370E-12 1.44370E-12 651710 + 966 661590 Dy-159 3.04280E-11 3.04280E-11 661590 + 967 661600 Dy-160 1.14810E-09 1.01830E-06 66160.82c + 968 661610 Dy-161 1.23860E-08 4.69110E-05 66161.82c + 969 661620 Dy-162 1.19720E-06 2.99580E-05 66162.82c + 970 661630 Dy-163 1.19440E-06 1.79160E-05 66163.82c + 971 661640 Dy-164 2.39670E-06 2.04290E-05 66164.82c + 972 661650 Dy-165 2.17580E-06 1.06050E-05 661650 + 973 661651 Dy-165m 1.81260E-07 1.81260E-07 661651 + 974 661660 Dy-166 1.12940E-06 2.28470E-06 661660 + 975 661670 Dy-167 3.26580E-06 3.67650E-06 661670 + 976 661680 Dy-168 1.66500E-06 1.72460E-06 661680 + 977 661690 Dy-169 1.46060E-07 1.48470E-07 661690 + 978 661700 Dy-170 3.20450E-08 3.21310E-08 661700 + 979 661710 Dy-171 1.34640E-09 1.34780E-09 661710 + 980 661720 Dy-172 1.21820E-10 1.21820E-10 661720 + 981 661730 Dy-173 4.71760E-12 4.71760E-12 661730 + 982 671610 Ho-161 1.33090E-12 1.44180E-12 671610 + 983 671620 Ho-162 7.94980E-12 3.02070E-11 671620 + 984 671621 Ho-162m 3.58990E-11 3.58990E-11 671621 + 985 671630 Ho-163 9.63900E-10 1.04420E-09 671630 + 986 671631 Ho-163m 8.02990E-11 8.02990E-11 671631 + 987 671640 Ho-164 3.00610E-09 1.65810E-08 671640 + 988 671641 Ho-164m 1.35750E-08 1.35750E-08 671641 + 989 671650 Ho-165 1.11570E-07 1.07210E-05 67165.82c + 990 671660 Ho-166 2.02040E-08 2.30490E-06 671660 + 991 671661 Ho-166m 9.12360E-08 9.12360E-08 671661 + 992 671670 Ho-167 7.27920E-07 4.40440E-06 671670 + 993 671680 Ho-168 2.87710E-07 2.83040E-06 671680 + 994 671681 Ho-168m 8.22290E-07 8.22290E-07 671681 + 995 671690 Ho-169 4.59990E-07 6.08460E-07 671690 + 996 671700 Ho-170 1.68640E-07 1.68640E-07 671700 + 997 671701 Ho-170m 3.73460E-08 6.94770E-08 671701 + 998 671710 Ho-171 1.31240E-07 1.32590E-07 671710 + 999 671720 Ho-172 1.00030E-08 1.01250E-08 671720 + 1000 671730 Ho-173 2.44510E-09 2.44980E-09 671730 + 1001 671740 Ho-174 1.38300E-10 1.38300E-10 671740 + 1002 671750 Ho-175 5.82180E-12 5.82180E-12 671750 + 1003 681640 Er-164 5.92830E-12 8.57830E-09 68164.82c + 1004 681650 Er-165 9.88110E-11 9.88110E-11 681650 + 1005 681660 Er-166 6.37730E-10 2.30550E-06 68166.82c + 1006 681670 Er-167 9.15170E-09 4.41440E-06 68167.82c + 1007 681671 Er-167m 7.62390E-10 5.27060E-07 681671 + 1008 681680 Er-168 8.44300E-08 2.91910E-06 68168.82c + 1009 681690 Er-169 2.29990E-07 8.38450E-07 681690 + 1010 681700 Er-170 1.68150E-07 4.06270E-07 68170.82c + 1011 681710 Er-171 7.35140E-08 2.06100E-07 681710 + 1012 681720 Er-172 7.63110E-08 8.64360E-08 681720 + 1013 681730 Er-173 3.83090E-08 4.07590E-08 681730 + 1014 681740 Er-174 1.24620E-08 1.26000E-08 681740 + 1015 681750 Er-175 1.24240E-09 1.24820E-09 681750 + 1016 681760 Er-176 1.85390E-10 1.85390E-10 681760 + 1017 681770 Er-177 1.11750E-11 1.11750E-11 681770 + 1018 691670 Tm-167 4.85710E-12 4.85710E-12 691670 + 1019 691680 Tm-168 1.04550E-10 1.04550E-10 691680 + 1020 691690 Tm-169 6.05370E-10 8.39050E-07 691690 + 1021 691700 Tm-170 3.05510E-09 3.05510E-09 691700 + 1022 691710 Tm-171 7.46420E-09 2.13570E-07 691710 + 1023 691720 Tm-172 9.39700E-08 1.80410E-07 691720 + 1024 691730 Tm-173 3.81110E-08 7.88700E-08 691730 + 1025 691740 Tm-174 2.33630E-08 3.59630E-08 691740 + 1026 691750 Tm-175 1.19350E-08 1.31830E-08 691750 + 1027 691760 Tm-176 3.79350E-09 3.97890E-09 691760 + 1028 691770 Tm-177 1.35900E-09 1.37020E-09 691770 + 1029 691780 Tm-178 1.65380E-10 1.65380E-10 691780 + 1030 691790 Tm-179 2.04420E-11 2.04420E-11 691790 + 1031 701700 Yb-170 3.99560E-12 3.05510E-09 701700 + 1032 701710 Yb-171 1.87240E-12 2.13590E-07 701710 + 1033 701711 Yb-171m 2.24770E-11 2.24770E-11 701711 + 1034 701720 Yb-172 3.12540E-10 1.80720E-07 701720 + 1035 701730 Yb-173 1.72640E-09 8.05990E-08 701730 + 1036 701740 Yb-174 5.70170E-09 4.16910E-08 701740 + 1037 701750 Yb-175 5.21070E-09 1.88280E-08 701750 + 1038 701751 Yb-175m 4.34090E-10 1.05850E-08 701751 + 1039 701760 Yb-176 1.93950E-09 1.18260E-08 701760 + 1040 701761 Yb-176m 6.78520E-09 8.77460E-09 701761 + 1041 701770 Yb-177 5.32190E-09 7.36060E-09 701770 + 1042 701771 Yb-177m 6.68530E-10 2.03870E-09 701771 + 1043 701780 Yb-178 3.86370E-09 4.02910E-09 701780 + 1044 701790 Yb-179 1.05430E-09 1.07470E-09 701790 + 1045 701800 Yb-180 2.94880E-10 2.94880E-10 701800 + 1046 701810 Yb-181 2.86310E-11 2.86310E-11 701810 + 1047 711730 Lu-173 3.15590E-12 3.15590E-12 711730 + 1048 711740 Lu-174 4.63280E-12 2.54320E-11 711740 + 1049 711741 Lu-174m 2.09200E-11 2.09200E-11 711741 + 1050 711750 Lu-175 1.52430E-10 1.89800E-08 71175.82c + 1051 711760 Lu-176 3.96770E-10 1.27420E-09 71176.82c + 1052 711761 Lu-176m 1.13410E-10 1.13410E-10 711761 + 1053 711770 Lu-177 9.25660E-10 8.47460E-09 711770 + 1054 711771 Lu-177m 7.71170E-10 8.33660E-10 711771 + 1055 711772 Lu-177m 1.24980E-10 1.24980E-10 711772 + 1056 711780 Lu-178 6.73390E-10 4.70250E-09 711780 + 1057 711781 Lu-178m 1.55490E-09 1.55490E-09 711781 + 1058 711790 Lu-179 2.73870E-09 4.04160E-09 711790 + 1059 711791 Lu-179m 2.28150E-10 1.30290E-09 711791 + 1060 711800 Lu-180 3.15230E-10 1.12160E-09 711800 + 1061 711801 Lu-180m 3.15230E-10 6.10110E-10 711801 + 1062 711802 Lu-180m 1.00270E-09 1.00270E-09 711802 + 1063 711810 Lu-181 8.71620E-10 9.00250E-10 711810 + 1064 711820 Lu-182 1.71180E-10 1.71180E-10 711820 + 1065 711830 Lu-183 3.95300E-11 3.95300E-11 711830 + 1066 711840 Lu-184 3.19390E-12 3.19390E-12 711840 + 1067 721760 Hf-176 2.46060E-12 1.15770E-10 72176.82c + 1068 721770 Hf-177 1.06940E-11 9.20340E-09 72177.82c + 1069 721771 Hf-177m 8.71140E-12 7.18090E-10 721771 + 1070 721772 Hf-177m 1.64380E-12 6.41320E-11 721772 + 1071 721780 Hf-178 3.34230E-11 6.40770E-09 72178.82c + 1072 721781 Hf-178m 8.86160E-11 1.67180E-09 721781 + 1073 721782 Hf-178m 2.83110E-11 2.83110E-11 721782 + 1074 721790 Hf-179 1.99120E-10 4.46240E-09 72179.82c + 1075 721791 Hf-179m 4.66440E-11 4.66440E-11 721791 + 1076 721792 Hf-179m 1.72200E-10 1.72200E-10 721792 + 1077 721800 Hf-180 2.57930E-10 3.08840E-09 72180.82c + 1078 721801 Hf-180m 9.02370E-10 1.40370E-09 721801 + 1079 721810 Hf-181 1.16180E-09 2.06200E-09 721810 + 1080 721820 Hf-182 2.51380E-10 7.91920E-10 721820 + 1081 721821 Hf-182m 8.79420E-10 8.79420E-10 721821 + 1082 721830 Hf-183 5.31200E-10 5.70730E-10 721830 + 1083 721840 Hf-184 5.43660E-11 5.59630E-11 721840 + 1084 721841 Hf-184m 1.90190E-10 1.91790E-10 721841 + 1085 721850 Hf-185 3.98220E-11 3.98220E-11 721850 + 1086 721860 Hf-186 6.41300E-12 6.41300E-12 721860 + 1087 731790 Ta-179 1.52670E-12 2.77230E-12 731790 + 1088 731791 Ta-179m 1.05540E-12 1.24560E-12 731791 + 1089 731800 Ta-180 5.42570E-12 5.42570E-12 731800 + 1090 731801 Ta-180m 1.25280E-11 1.68800E-11 731801 + 1091 731810 Ta-181 1.01430E-10 2.16350E-09 73181.82c + 1092 731820 Ta-182 4.42110E-11 7.08940E-10 73182.82c + 1093 731821 Ta-182m 5.78540E-11 6.64730E-10 731821 + 1094 731822 Ta-182m 9.68150E-11 6.06880E-10 731822 + 1095 731830 Ta-183 4.60500E-10 1.03120E-09 731830 + 1096 731840 Ta-184 3.98500E-10 6.46250E-10 731840 + 1097 731850 Ta-185 1.54170E-10 3.69660E-10 731850 + 1098 731851 Ta-185m 1.75670E-10 1.75670E-10 731851 + 1099 731860 Ta-186 1.12040E-10 1.18450E-10 731860 + 1100 731870 Ta-187 4.22000E-11 4.22000E-11 731870 + 1101 731880 Ta-188 5.41690E-12 5.41690E-12 731880 + 1102 741820 W-182 3.40660E-12 7.12350E-10 74182.82c + 1103 741830 W-183 2.48570E-12 1.04910E-09 74183.82c + 1104 741831 W-183m 1.53580E-11 5.04200E-11 741831 + 1105 741840 W-184 8.40020E-11 7.30260E-10 74184.82c + 1106 741850 W-185 2.42800E-11 5.05380E-10 741850 + 1107 741851 W-185m 1.11440E-10 1.11440E-10 741851 + 1108 741860 W-186 1.23920E-10 3.43120E-10 74186.82c + 1109 741861 W-186m 1.00540E-10 1.00540E-10 741861 + 1110 741870 W-187 1.61140E-10 2.03340E-10 741870 + 1111 741880 W-188 1.08600E-10 1.14020E-10 741880 + 1112 741890 W-189 3.17360E-11 3.17360E-11 741890 + 1113 741900 W-190 2.86890E-12 9.49340E-12 741900 + 1114 741901 W-190m 6.62450E-12 6.62450E-12 741901 + 1115 751850 Re-185 3.11970E-12 5.08500E-10 75185.82c + 1116 751860 Re-186 2.92350E-12 2.92350E-12 751860 + 1117 751861 Re-186m 8.35550E-12 8.35550E-12 751861 + 1118 751870 Re-187 4.24990E-11 2.45840E-10 75187.82c + 1119 751880 Re-188 9.89440E-12 1.68590E-10 751880 + 1120 751881 Re-188m 4.46810E-11 4.46810E-11 751881 + 1121 751890 Re-189 7.76530E-11 1.09390E-10 751890 + 1122 751900 Re-190 1.00840E-11 3.56640E-11 751900 + 1123 751901 Re-190m 3.52780E-11 3.52780E-11 751901 + 1124 751910 Re-191 2.53580E-11 2.53580E-11 751910 + 1125 751920 Re-192 5.29490E-12 5.29490E-12 751920 + 1126 751930 Re-193 1.30510E-12 1.30510E-12 751930 + 1127 761880 Os-188 3.14790E-12 1.71740E-10 761880 + 1128 761890 Os-189 1.31540E-12 1.18830E-10 761890 + 1129 761891 Os-189m 8.12770E-12 1.93760E-11 761891 + 1130 761900 Os-190 8.47070E-12 8.28850E-11 761900 + 1131 761901 Os-190m 1.95590E-11 3.87510E-11 761901 + 1132 761910 Os-191 2.53470E-11 5.48070E-11 761910 + 1133 761911 Os-191m 4.10220E-12 4.10220E-12 761911 + 1134 761920 Os-192 9.16030E-12 3.32110E-11 761920 + 1135 761921 Os-192m 2.11520E-11 2.11520E-11 761921 + 1136 761930 Os-193 1.50600E-11 1.63650E-11 761930 + 1137 761940 Os-194 7.27650E-12 7.27650E-12 761940 + 1138 761950 Os-195 1.26670E-12 1.26670E-12 761950 + 1139 771910 Ir-191 3.94970E-13 5.70150E-11 77191.82c + 1140 771911 Ir-191m 1.06570E-12 2.76820E-11 771911 + 1141 771920 Ir-192 1.54030E-12 7.37030E-12 771920 + 1142 771921 Ir-192m 1.54030E-12 1.54030E-12 771921 + 1143 771922 Ir-192m 1.54030E-12 4.29000E-12 771922 + 1144 771930 Ir-193 2.03500E-12 2.77400E-11 77193.82c + 1145 771931 Ir-193m 9.34000E-12 9.39690E-12 771931 + 1146 771940 Ir-194 3.43700E-12 1.41510E-11 771940 + 1147 771941 Ir-194m 3.43700E-12 3.43700E-12 771941 + 1148 771942 Ir-194m 3.43700E-12 3.43700E-12 771942 + 1149 771950 Ir-195 1.62020E-12 3.25870E-12 771950 + 1150 771951 Ir-195m 7.43620E-12 7.43620E-12 771951 + 1151 771960 Ir-196 1.64370E-12 1.64860E-12 771960 + 1152 771961 Ir-196m 1.64370E-12 1.64370E-12 771961 + 1153 771971 Ir-197m 1.06760E-12 1.06760E-12 771971 + 1154 781940 Pt-194 1.87540E-12 1.94630E-11 781940 + 1155 781950 Pt-195 5.79670E-13 1.35630E-11 781950 + 1156 781951 Pt-195m 2.66050E-12 4.92110E-12 781951 + 1157 781960 Pt-196 5.73850E-12 9.02590E-12 781960 + 1158 781970 Pt-197 7.70130E-13 5.45320E-12 781970 + 1159 781971 Pt-197m 3.53470E-12 4.59960E-12 781971 + 1160 781980 Pt-198 3.03350E-12 3.03350E-12 781980 + 1161 791980 Au-198 6.24640E-13 1.32790E-12 791980 + 1162 791990 Au-199 2.01920E-12 2.01920E-12 791990 + + Nuclide 92234.82c -- uranium 234 (U-234) + + Neutron-induced fission: + + Interpolation region : 1 / 1 + Interpolation energy : 4.00000E-01 MeV + Number of products : 845 / 929 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 3.65250E-05 3.65250E-05 1001.82c + 2 10020 H-2 1.11620E-05 1.11620E-05 1002.82c + 3 10030 H-3 1.59250E-04 1.59250E-04 1003.82c + 4 20040 He-4 2.30900E-03 2.30900E-03 2004.82c + 5 240590 Cr-59 1.45230E-12 1.45230E-12 240590 + 6 240600 Cr-60 3.98610E-12 3.98610E-12 240600 + 7 240610 Cr-61 2.78460E-12 2.78460E-12 240610 + 8 240620 Cr-62 3.62560E-12 3.62560E-12 240620 + 9 250600 Mn-60 1.70920E-13 4.35700E-12 250600 + 10 250601 Mn-60m 1.73880E-12 1.73880E-12 250601 + 11 250610 Mn-61 1.15600E-11 1.43450E-11 250610 + 12 250620 Mn-62 1.58810E-11 1.76940E-11 250620 + 13 250621 Mn-62m 2.48700E-12 4.29980E-12 250621 + 14 250630 Mn-63 4.51720E-11 4.51720E-11 250630 + 15 250640 Mn-64 2.13400E-11 2.13400E-11 250640 + 16 250650 Mn-65 2.32230E-11 2.32230E-11 250650 + 17 250660 Mn-66 4.78780E-12 4.78780E-12 250660 + 18 250670 Mn-67 1.28380E-12 1.28380E-12 250670 + 19 260610 Fe-61 1.23080E-12 1.55750E-11 260610 + 20 260620 Fe-62 1.75210E-11 3.95150E-11 260620 + 21 260630 Fe-63 4.94100E-11 9.45820E-11 260630 + 22 260640 Fe-64 2.06180E-10 2.27520E-10 260640 + 23 260650 Fe-65 2.84330E-10 3.07550E-10 260650 + 24 260660 Fe-66 6.09530E-10 6.14320E-10 260660 + 25 260670 Fe-67 2.43630E-10 2.44910E-10 260670 + 26 260680 Fe-68 1.71270E-10 1.71270E-10 260680 + 27 260690 Fe-69 2.99130E-11 2.99130E-11 260690 + 28 260700 Fe-70 6.02310E-12 6.02310E-12 260700 + 29 270630 Co-63 5.33620E-12 9.99180E-11 270630 + 30 270640 Co-64 2.76940E-11 2.55210E-10 270640 + 31 270650 Co-65 3.33710E-10 6.41260E-10 270650 + 32 270660 Co-66 8.23070E-10 1.43740E-09 270660 + 33 270670 Co-67 2.99360E-09 3.23850E-09 270670 + 34 270680 Co-68 1.58970E-09 2.26970E-09 270680 + 35 270681 Co-68m 1.18660E-09 1.36000E-09 270681 + 36 270690 Co-69 5.22670E-09 5.25450E-09 270690 + 37 270700 Co-70 8.05300E-10 8.05300E-10 270700 + 38 270701 Co-70m 8.05300E-10 8.11320E-10 270701 + 39 270710 Co-71 9.32630E-10 9.32630E-10 270710 + 40 270720 Co-72 1.22300E-10 1.22300E-10 270720 + 41 270730 Co-73 1.23160E-11 1.23160E-11 270730 + 42 280650 Ni-65 8.80510E-12 6.50070E-10 280650 + 43 280660 Ni-66 2.12920E-10 1.65030E-09 280660 + 44 280670 Ni-67 9.29810E-10 4.16830E-09 280670 + 45 280680 Ni-68 7.43690E-09 1.04390E-08 280680 + 46 280690 Ni-69 8.18850E-09 1.33910E-08 280690 + 47 280691 Ni-69m 8.18850E-09 8.18850E-09 280691 + 48 280700 Ni-70 4.76330E-08 4.92500E-08 280700 + 49 280710 Ni-71 3.78600E-08 3.87930E-08 280710 + 50 280720 Ni-72 5.52450E-08 5.53670E-08 280720 + 51 280730 Ni-73 8.71120E-09 8.72350E-09 280730 + 52 280740 Ni-74 7.30310E-09 7.30310E-09 280740 + 53 280750 Ni-75 2.62960E-10 2.62960E-10 280750 + 54 280760 Ni-76 8.51840E-11 8.51840E-11 280760 + 55 280770 Ni-77 2.30480E-12 2.30480E-12 280770 + 56 290670 Cu-67 2.35940E-11 4.19190E-09 290670 + 57 290680 Cu-68 6.93900E-11 1.06670E-08 290680 + 58 290681 Cu-68m 1.89140E-10 1.89140E-10 290681 + 59 290690 Cu-69 5.36370E-09 2.69430E-08 290690 + 60 290700 Cu-70 1.23410E-09 1.03770E-08 290700 + 61 290701 Cu-70m 1.57610E-08 1.82850E-08 290701 + 62 290702 Cu-70m 1.23410E-09 5.04840E-08 290702 + 63 290710 Cu-71 1.24990E-07 1.63780E-07 290710 + 64 290720 Cu-72 2.19330E-07 2.74700E-07 290720 + 65 290730 Cu-73 6.70000E-07 6.78720E-07 290730 + 66 290740 Cu-74 4.05610E-07 4.12920E-07 290740 + 67 290750 Cu-75 1.67010E-07 1.67270E-07 290750 + 68 290760 Cu-76 4.29880E-08 4.30310E-08 290760 + 69 290761 Cu-76m 4.29880E-08 4.30310E-08 290761 + 70 290770 Cu-77 2.64090E-08 2.64110E-08 290770 + 71 290780 Cu-78 2.45070E-09 2.45070E-09 290780 + 72 290790 Cu-79 2.58780E-10 2.58780E-10 290790 + 73 300690 Zn-69 5.30440E-12 2.69740E-08 300690 + 74 300691 Zn-69m 2.63450E-11 2.63450E-11 300691 + 75 300700 Zn-70 1.15750E-09 6.86360E-08 300700 + 76 300710 Zn-71 1.75140E-09 1.65530E-07 300710 + 77 300711 Zn-71m 8.69860E-09 8.69860E-09 300711 + 78 300720 Zn-72 1.66580E-07 4.41280E-07 300720 + 79 300730 Zn-73 2.60230E-08 8.58110E-07 300730 + 80 300731 Zn-73m 3.59930E-08 1.53360E-07 300731 + 81 300732 Zn-73m 2.34740E-07 2.34740E-07 300732 + 82 300740 Zn-74 3.25890E-06 3.67770E-06 300740 + 83 300750 Zn-75 3.32060E-06 3.48330E-06 300750 + 84 300760 Zn-76 1.09770E-05 1.10620E-05 300760 + 85 300770 Zn-77 2.64980E-06 2.85260E-06 300770 + 86 300771 Zn-77m 3.52810E-07 3.52810E-07 300771 + 87 300780 Zn-78 1.41300E-05 1.41330E-05 300780 + 88 300790 Zn-79 1.01030E-06 1.01040E-06 300790 + 89 300800 Zn-80 1.01980E-06 1.01980E-06 300800 + 90 300810 Zn-81 6.48270E-09 6.48270E-09 300810 + 91 300820 Zn-82 4.52890E-10 4.52890E-10 300820 + 92 310710 Ga-71 5.68050E-11 1.74290E-07 310710 + 93 310720 Ga-72 1.22730E-09 4.42630E-07 310720 + 94 310721 Ga-72m 1.20650E-10 1.48240E-08 310721 + 95 310730 Ga-73 2.49220E-08 1.00040E-06 310730 + 96 310740 Ga-74 1.64590E-07 3.04630E-06 310740 + 97 310741 Ga-74m 1.64590E-07 3.84230E-06 310741 + 98 310750 Ga-75 1.48980E-06 4.97310E-06 310750 + 99 310760 Ga-76 6.98580E-06 1.80480E-05 310760 + 100 310770 Ga-77 2.00160E-05 2.30450E-05 310770 + 101 310780 Ga-78 3.33060E-05 4.74520E-05 310780 + 102 310790 Ga-79 5.35170E-05 5.45140E-05 310790 + 103 310800 Ga-80 2.85430E-05 2.95630E-05 310800 + 104 310810 Ga-81 1.83500E-05 1.83560E-05 310810 + 105 310820 Ga-82 5.12910E-06 5.12950E-06 310820 + 106 310830 Ga-83 2.63120E-07 2.63120E-07 310830 + 107 310840 Ga-84 8.17130E-09 8.17130E-09 310840 + 108 320720 Ge-72 1.02460E-12 4.42630E-07 32072.82c + 109 320730 Ge-73 2.53070E-11 1.00040E-06 32073.82c + 110 320731 Ge-73m 5.09550E-12 9.85720E-07 320731 + 111 320740 Ge-74 4.63580E-09 4.01150E-06 32074.82c + 112 320750 Ge-75 3.55770E-09 5.00330E-06 320750 + 113 320751 Ge-75m 2.67200E-08 2.25650E-07 320751 + 114 320760 Ge-76 1.99590E-06 2.00430E-05 32076.82c + 115 320770 Ge-77 2.03190E-05 2.52110E-05 320770 + 116 320771 Ge-77m 2.70530E-06 2.57500E-05 320771 + 117 320780 Ge-78 1.07060E-04 1.54560E-04 320780 + 118 320790 Ge-79 3.87110E-05 1.04730E-04 320790 + 119 320791 Ge-79m 2.90750E-04 2.90830E-04 320791 + 120 320800 Ge-80 6.98190E-04 7.29940E-04 320800 + 121 320810 Ge-81 7.31720E-04 7.42360E-04 320810 + 122 320811 Ge-81m 1.47330E-04 1.55510E-04 320811 + 123 320820 Ge-82 9.22630E-04 9.26760E-04 320820 + 124 320830 Ge-83 3.52750E-04 3.52920E-04 320830 + 125 320840 Ge-84 1.20890E-04 1.20890E-04 320840 + 126 320850 Ge-85 2.71910E-05 2.71910E-05 320850 + 127 320860 Ge-86 2.13440E-06 2.13440E-06 320860 + 128 320870 Ge-87 3.32720E-09 3.32720E-09 320870 + 129 330750 As-75 6.91690E-12 5.00340E-06 33075.82c + 130 330751 As-75m 2.61940E-11 9.38880E-11 330751 + 131 330760 As-76 3.14010E-09 3.14010E-09 330760 + 132 330770 As-77 1.74630E-07 4.62440E-05 330770 + 133 330780 As-78 3.02870E-06 1.57590E-04 330780 + 134 330790 As-79 1.92010E-05 4.03130E-04 330790 + 135 330800 As-80 2.16570E-04 9.46510E-04 330800 + 136 330810 As-81 6.15570E-04 1.51190E-03 330810 + 137 330820 As-82 3.32340E-04 1.25910E-03 330820 + 138 330821 As-82m 1.15800E-03 1.15800E-03 330821 + 139 330830 As-83 2.43260E-03 2.79860E-03 330830 + 140 330840 As-84 8.38850E-04 8.94670E-04 330840 + 141 330841 As-84m 8.38850E-04 8.94670E-04 330841 + 142 330850 As-85 9.85540E-04 1.00890E-03 330850 + 143 330860 As-86 2.73010E-04 2.75140E-04 330860 + 144 330870 As-87 9.08790E-05 9.08820E-05 330870 + 145 330880 As-88 5.96710E-06 5.96710E-06 330880 + 146 330890 As-89 7.39110E-08 7.39110E-08 330890 + 147 330900 As-90 1.35300E-09 1.35300E-09 330900 + 148 340770 Se-77 4.87460E-12 4.62440E-05 34077.82c + 149 340771 Se-77m 3.66110E-11 3.66110E-11 340771 + 150 340780 Se-78 8.58140E-09 1.57600E-04 34078.82c + 151 340790 Se-79 1.78330E-06 4.04930E-04 34079.82c + 152 340791 Se-79m 2.37430E-07 3.93820E-04 340791 + 153 340800 Se-80 3.26520E-05 9.79240E-04 34080.82c + 154 340810 Se-81 2.74160E-05 1.74510E-03 340810 + 155 340811 Se-81m 2.05910E-04 2.60190E-04 340811 + 156 340820 Se-82 1.22170E-03 3.63880E-03 34082.82c + 157 340830 Se-83 3.70270E-03 4.71140E-03 340830 + 158 340831 Se-83m 7.45520E-04 2.53790E-03 340831 + 159 340840 Se-84 1.13340E-02 1.33430E-02 340840 + 160 340850 Se-85 1.27490E-02 1.36270E-02 340850 + 161 340860 Se-86 1.16910E-02 1.18890E-02 340860 + 162 340870 Se-87 5.99240E-03 6.06930E-03 340870 + 163 340880 Se-88 2.65210E-03 2.65810E-03 340880 + 164 340890 Se-89 5.64130E-04 5.64200E-04 340890 + 165 340900 Se-90 1.38470E-04 1.38470E-04 340900 + 166 340910 Se-91 8.44450E-06 8.44450E-06 340910 + 167 340920 Se-92 1.62980E-08 1.62980E-08 340920 + 168 350790 Br-79 1.20130E-11 2.20590E-07 35079.82c + 169 350791 Br-79m 4.54920E-11 4.54920E-11 350791 + 170 350800 Br-80 2.27420E-07 1.01980E-06 350800 + 171 350801 Br-80m 7.92390E-07 7.92390E-07 350801 + 172 350810 Br-81 1.01980E-06 1.74620E-03 35081.82c + 173 350820 Br-82 4.50410E-06 6.11680E-06 350820 + 174 350821 Br-82m 1.65240E-06 1.65240E-06 350821 + 175 350830 Br-83 1.37760E-04 7.38700E-03 350830 + 176 350840 Br-84 4.85210E-04 1.38280E-02 350840 + 177 350841 Br-84m 4.85210E-04 4.85210E-04 350841 + 178 350850 Br-85 4.51360E-03 1.81400E-02 350850 + 179 350860 Br-86 1.00900E-02 2.19790E-02 350860 + 180 350870 Br-87 1.51130E-02 2.12090E-02 350870 + 181 350880 Br-88 1.22720E-02 1.49480E-02 350880 + 182 350890 Br-89 8.78250E-03 9.30270E-03 350890 + 183 350900 Br-90 3.39460E-03 3.53480E-03 350900 + 184 350910 Br-91 1.33410E-03 1.34080E-03 350910 + 185 350920 Br-92 1.48520E-04 1.48540E-04 350920 + 186 350930 Br-93 3.12890E-05 3.12890E-05 350930 + 187 350940 Br-94 8.96090E-08 8.96090E-08 350940 + 188 350950 Br-95 2.59230E-09 2.59230E-09 350950 + 189 360820 Kr-82 3.77410E-09 6.16030E-06 36082.82c + 190 360830 Kr-83 4.26940E-06 7.39220E-03 36083.82c + 191 360831 Kr-83m 8.59620E-07 7.38130E-03 360831 + 192 360840 Kr-84 5.69760E-05 1.43700E-02 36084.82c + 193 360850 Kr-85 4.09090E-04 4.33190E-03 36085.82c + 194 360851 Kr-85m 8.23690E-05 1.81930E-02 360851 + 195 360860 Kr-86 4.11700E-03 2.66290E-02 36086.82c + 196 360870 Kr-87 1.21440E-02 3.38220E-02 360870 + 197 360880 Kr-88 3.12750E-02 4.65330E-02 360880 + 198 360890 Kr-89 4.02860E-02 4.91470E-02 360890 + 199 360900 Kr-90 4.12790E-02 4.42120E-02 360900 + 200 360910 Kr-91 2.43230E-02 2.54450E-02 360910 + 201 360920 Kr-92 1.24260E-02 1.25470E-02 360920 + 202 360930 Kr-93 3.70480E-03 3.71490E-03 360930 + 203 360940 Kr-94 1.08590E-03 1.08590E-03 360940 + 204 360950 Kr-95 1.38090E-04 1.38090E-04 360950 + 205 360960 Kr-96 1.95770E-05 1.95770E-05 360960 + 206 360970 Kr-97 1.61440E-08 1.61440E-08 360970 + 207 370840 Rb-84 2.93080E-10 9.07920E-10 370840 + 208 370841 Rb-84m 6.14840E-10 6.14840E-10 370841 + 209 370850 Rb-85 1.04640E-06 1.86330E-02 37085.82c + 210 370860 Rb-86 3.10130E-06 9.60740E-06 37086.82c + 211 370861 Rb-86m 6.50610E-06 6.50610E-06 370861 + 212 370870 Rb-87 1.78650E-04 3.40000E-02 37087.82c + 213 370880 Rb-88 8.63000E-04 4.73960E-02 370880 + 214 370890 Rb-89 4.97030E-03 5.41170E-02 370890 + 215 370900 Rb-90 1.18250E-03 4.00750E-02 370900 + 216 370901 Rb-90m 1.20300E-02 1.78120E-02 370901 + 217 370910 Rb-91 2.73790E-02 5.28240E-02 370910 + 218 370920 Rb-92 2.69700E-02 3.95170E-02 370920 + 219 370930 Rb-93 2.14160E-02 2.51430E-02 370930 + 220 370940 Rb-94 1.09820E-02 1.20600E-02 370940 + 221 370950 Rb-95 5.89040E-03 6.02530E-03 370950 + 222 370960 Rb-96 6.90300E-04 1.04960E-03 370960 + 223 370961 Rb-96m 6.90300E-04 6.99730E-04 370961 + 224 370970 Rb-97 3.09550E-04 3.09560E-04 370970 + 225 370980 Rb-98 1.02490E-05 1.02490E-05 370980 + 226 370981 Rb-98m 1.02490E-05 1.02490E-05 370981 + 227 370990 Rb-99 3.86550E-06 3.86550E-06 370990 + 228 371000 Rb-100 1.05590E-09 1.05590E-09 371000 + 229 380870 Sr-87 2.58480E-06 3.10360E-06 38087.82c + 230 380871 Sr-87m 5.20430E-07 5.20430E-07 380871 + 231 380880 Sr-88 4.48150E-05 4.74410E-02 38088.82c + 232 380890 Sr-89 2.13990E-04 5.43310E-02 38089.82c + 233 380900 Sr-90 2.37620E-03 5.98010E-02 38090.82c + 234 380910 Sr-91 7.56720E-03 6.03910E-02 380910 + 235 380920 Sr-92 2.67450E-02 6.66140E-02 380920 + 236 380930 Sr-93 4.17570E-02 6.77660E-02 380930 + 237 380940 Sr-94 5.85340E-02 6.98940E-02 380940 + 238 380950 Sr-95 4.36860E-02 4.93340E-02 380950 + 239 380960 Sr-96 2.88230E-02 3.01590E-02 380960 + 240 380970 Sr-97 1.17610E-02 1.19940E-02 380970 + 241 380980 Sr-98 4.70780E-03 4.72750E-03 380980 + 242 380990 Sr-99 8.97600E-04 9.00850E-04 380990 + 243 381000 Sr-100 1.63230E-04 1.63230E-04 381000 + 244 381010 Sr-101 8.65400E-06 8.65400E-06 381010 + 245 381020 Sr-102 1.33590E-08 1.33590E-08 381020 + 246 390890 Y-89 6.35240E-10 5.43310E-02 39089.82c + 247 390891 Y-89m 3.15500E-09 5.24020E-06 390891 + 248 390900 Y-90 3.96910E-07 5.98020E-02 39090.82c + 249 390901 Y-90m 6.63790E-07 6.63790E-07 390901 + 250 390910 Y-91 7.26260E-06 6.04340E-02 39091.82c + 251 390911 Y-91m 3.60700E-05 3.55670E-02 390911 + 252 390920 Y-92 2.50630E-04 6.68640E-02 390920 + 253 390930 Y-93 2.13970E-04 6.95870E-02 390930 + 254 390931 Y-93m 1.60700E-03 1.85650E-02 390931 + 255 390940 Y-94 5.43760E-03 7.53320E-02 390940 + 256 390950 Y-95 1.91050E-02 6.84390E-02 390950 + 257 390960 Y-96 8.76850E-03 3.89310E-02 390960 + 258 390961 Y-96m 1.83950E-02 1.83990E-02 390961 + 259 390970 Y-97 5.30070E-03 1.56930E-02 390970 + 260 390971 Y-97m 1.95930E-02 2.67630E-02 390971 + 261 390972 Y-97m 6.73340E-03 6.73340E-03 390972 + 262 390980 Y-98 3.29620E-03 8.02370E-03 390980 + 263 390981 Y-98m 1.59800E-02 1.59800E-02 390981 + 264 390990 Y-99 1.24360E-02 1.33380E-02 390990 + 265 391000 Y-100 2.08080E-03 2.24280E-03 391000 + 266 391001 Y-100m 2.08080E-03 2.08080E-03 391001 + 267 391010 Y-101 1.26030E-03 1.26870E-03 391010 + 268 391020 Y-102 7.03950E-05 7.04010E-05 391020 + 269 391021 Y-102m 7.03950E-05 7.04010E-05 391021 + 270 391030 Y-103 1.48080E-05 1.48080E-05 391030 + 271 391040 Y-104 1.70400E-08 1.70400E-08 391040 + 272 391050 Y-105 1.80800E-10 1.80800E-10 391050 + 273 400920 Zr-92 3.04210E-06 6.68670E-02 40092.82c + 274 400930 Zr-93 5.19400E-05 6.96390E-02 40093.82c + 275 400940 Zr-94 4.41700E-04 7.57730E-02 40094.82c + 276 400950 Zr-95 2.05840E-03 7.04970E-02 40095.82c + 277 400960 Zr-96 1.03400E-02 6.76910E-02 40096.82c + 278 400970 Zr-97 2.08610E-02 6.50260E-02 400970 + 279 400980 Zr-98 4.25350E-02 6.61940E-02 400980 + 280 400990 Zr-99 3.84680E-02 5.16000E-02 400990 + 281 401000 Zr-100 3.20960E-02 3.63990E-02 401000 + 282 401010 Zr-101 1.41820E-02 1.54580E-02 401010 + 283 401020 Zr-102 6.01980E-03 6.15490E-03 401020 + 284 401030 Zr-103 1.23920E-03 1.25280E-03 401030 + 285 401040 Zr-104 2.11690E-04 2.11710E-04 401040 + 286 401050 Zr-105 1.01540E-05 1.01540E-05 401050 + 287 401060 Zr-106 3.05870E-08 3.05870E-08 401060 + 288 401070 Zr-107 1.27820E-10 1.27820E-10 401070 + 289 410940 Nb-94 6.03060E-07 9.61870E-07 41094.82c + 290 410941 Nb-94m 3.60610E-07 3.60610E-07 410941 + 291 410950 Nb-95 5.98000E-06 7.04620E-02 41095.82c + 292 410951 Nb-95m 1.20410E-06 7.62820E-04 410951 + 293 410960 Nb-96 4.85040E-05 4.85040E-05 410960 + 294 410970 Nb-97 3.23720E-04 6.54150E-02 410970 + 295 410971 Nb-97m 6.51800E-05 6.18710E-02 410971 + 296 410980 Nb-98 3.17890E-04 6.65120E-02 410980 + 297 410981 Nb-98m 1.10760E-03 1.10760E-03 410981 + 298 410990 Nb-99 4.54540E-03 3.75550E-02 410990 + 299 410991 Nb-99m 9.15200E-04 1.99040E-02 410991 + 300 411000 Nb-100 1.64300E-03 3.80420E-02 411000 + 301 411001 Nb-100m 7.96500E-03 7.96500E-03 411001 + 302 411010 Nb-101 1.49020E-02 3.03600E-02 411010 + 303 411020 Nb-102 5.11550E-03 1.12700E-02 411020 + 304 411021 Nb-102m 5.11550E-03 5.11550E-03 411021 + 305 411030 Nb-103 6.39170E-03 7.64450E-03 411030 + 306 411040 Nb-104 9.74550E-04 1.18640E-03 411040 + 307 411041 Nb-104m 9.74550E-04 9.74550E-04 411041 + 308 411050 Nb-105 5.21320E-04 5.31330E-04 411050 + 309 411060 Nb-106 5.26260E-05 5.26560E-05 411060 + 310 411070 Nb-107 6.86280E-06 6.86290E-06 411070 + 311 411080 Nb-108 1.97910E-06 1.97910E-06 411080 + 312 411090 Nb-109 5.84260E-10 5.84260E-10 411090 + 313 411100 Nb-110 5.72540E-12 5.72540E-12 411100 + 314 420960 Mo-96 1.03090E-06 4.95350E-05 42096.82c + 315 420970 Mo-97 5.84670E-06 6.54210E-02 42097.82c + 316 420980 Mo-98 5.51070E-05 6.76740E-02 42098.82c + 317 420990 Mo-99 2.95250E-04 5.73560E-02 42099.82c + 318 421000 Mo-100 1.50020E-03 4.75070E-02 42100.82c + 319 421010 Mo-101 3.27030E-03 3.36300E-02 421010 + 320 421020 Mo-102 6.51350E-03 2.28990E-02 421020 + 321 421030 Mo-103 5.65630E-03 1.33020E-02 421030 + 322 421040 Mo-104 4.25770E-03 6.42650E-03 421040 + 323 421050 Mo-105 1.63510E-03 2.15980E-03 421050 + 324 421060 Mo-106 5.70850E-04 6.21550E-04 421060 + 325 421070 Mo-107 8.52510E-05 9.18250E-05 421070 + 326 421080 Mo-108 2.57210E-05 2.75780E-05 421080 + 327 421090 Mo-109 2.97770E-06 2.97820E-06 421090 + 328 421100 Mo-110 1.97850E-06 1.97850E-06 421100 + 329 421110 Mo-111 2.55270E-09 2.55270E-09 421110 + 330 421120 Mo-112 9.39430E-11 9.39430E-11 421120 + 331 430990 Tc-99 1.67990E-09 5.73540E-02 43099.82c + 332 430991 Tc-99m 3.38230E-10 5.05070E-02 430991 + 333 431000 Tc-100 2.96060E-06 2.96060E-06 431000 + 334 431010 Tc-101 2.40630E-05 3.36540E-02 431010 + 335 431020 Tc-102 3.32390E-05 2.29330E-02 431020 + 336 431021 Tc-102m 3.32390E-05 3.32390E-05 431021 + 337 431030 Tc-103 2.43960E-04 1.35460E-02 431030 + 338 431040 Tc-104 2.90210E-04 6.71670E-03 431040 + 339 431050 Tc-105 3.62940E-04 2.52270E-03 431050 + 340 431060 Tc-106 2.29080E-04 8.50630E-04 431060 + 341 431070 Tc-107 1.31460E-04 2.23280E-04 431070 + 342 431080 Tc-108 4.74980E-05 7.50910E-05 431080 + 343 431090 Tc-109 3.07640E-05 3.37260E-05 431090 + 344 431100 Tc-110 9.89180E-06 1.18700E-05 431100 + 345 431110 Tc-111 9.90290E-06 9.90540E-06 431110 + 346 431120 Tc-112 4.94080E-06 4.94090E-06 431120 + 347 431130 Tc-113 2.02080E-08 2.02080E-08 431130 + 348 431140 Tc-114 4.54140E-10 4.54140E-10 431140 + 349 431150 Tc-115 2.43010E-11 2.43010E-11 431150 + 350 431180 Tc-118 3.38000E-11 3.38000E-11 431180 + 351 441020 Ru-102 9.48010E-07 2.29670E-02 44102.82c + 352 441030 Ru-103 7.31390E-07 1.35490E-02 44103.82c + 353 441031 Ru-103m 2.04640E-06 2.04640E-06 441031 + 354 441040 Ru-104 1.96070E-05 6.73630E-03 44104.82c + 355 441050 Ru-105 1.94000E-05 2.54210E-03 44105.82c + 356 441060 Ru-106 3.29480E-05 8.83580E-04 44106.82c + 357 441070 Ru-107 1.86360E-05 2.41920E-04 441070 + 358 441080 Ru-108 4.45530E-05 1.19670E-04 441080 + 359 441090 Ru-109 5.85780E-05 9.22820E-05 441090 + 360 441100 Ru-110 7.02440E-05 8.21100E-05 441100 + 361 441110 Ru-111 5.24870E-05 6.24670E-05 441110 + 362 441120 Ru-112 4.34750E-05 4.83430E-05 441120 + 363 441130 Ru-113 8.80350E-06 1.32240E-05 441130 + 364 441131 Ru-113m 8.80350E-06 8.80350E-06 441131 + 365 441140 Ru-114 1.08520E-05 1.08520E-05 441140 + 366 441150 Ru-115 9.92440E-07 9.92460E-07 441150 + 367 441160 Ru-116 6.85900E-09 6.85900E-09 441160 + 368 441170 Ru-117 1.04570E-10 1.04570E-10 441170 + 369 441180 Ru-118 2.53630E-07 2.53660E-07 441180 + 370 441190 Ru-119 8.64700E-09 8.64700E-09 441190 + 371 441200 Ru-120 5.49740E-10 5.49740E-10 441200 + 372 451050 Rh-105 2.47320E-09 2.54210E-03 45105.82c + 373 451051 Rh-105m 3.29290E-10 7.21650E-04 451051 + 374 451060 Rh-106 5.86270E-09 8.83580E-04 451060 + 375 451061 Rh-106m 1.59800E-08 1.59800E-08 451061 + 376 451070 Rh-107 9.80590E-07 2.42900E-04 451070 + 377 451080 Rh-108 4.41380E-07 1.20110E-04 451080 + 378 451081 Rh-108m 1.53790E-06 1.53790E-06 451081 + 379 451090 Rh-109 3.97070E-06 9.62530E-05 451090 + 380 451100 Rh-110 6.76640E-06 8.88760E-05 451100 + 381 451101 Rh-110m 1.59290E-07 1.59290E-07 451101 + 382 451110 Rh-111 2.37760E-05 8.62420E-05 451110 + 383 451120 Rh-112 8.89550E-06 5.72390E-05 451120 + 384 451121 Rh-112m 8.89550E-06 8.89550E-06 451121 + 385 451130 Rh-113 5.67480E-05 7.43740E-05 451130 + 386 451140 Rh-114 1.43060E-05 2.51610E-05 451140 + 387 451141 Rh-114m 1.43060E-05 1.43060E-05 451141 + 388 451150 Rh-115 3.76990E-05 3.86890E-05 451150 + 389 451160 Rh-116 2.62250E-06 2.62930E-06 451160 + 390 451161 Rh-116m 7.14840E-06 7.14840E-06 451161 + 391 451170 Rh-117 1.00910E-06 1.01960E-06 451170 + 392 451180 Rh-118 1.00690E-06 1.25050E-06 451180 + 393 451190 Rh-119 4.80060E-06 4.80890E-06 451190 + 394 451200 Rh-120 4.90870E-07 4.91420E-07 451200 + 395 451210 Rh-121 4.81060E-08 4.81060E-08 451210 + 396 451220 Rh-122 1.65560E-09 1.65560E-09 451220 + 397 461070 Pd-107 5.70960E-12 2.42900E-04 46107.82c + 398 461071 Pd-107m 1.25490E-11 1.25490E-11 461071 + 399 461080 Pd-108 8.57450E-10 1.21650E-04 46108.82c + 400 461090 Pd-109 3.64200E-09 9.62650E-05 461090 + 401 461091 Pd-109m 8.00500E-09 4.81340E-05 461091 + 402 461100 Pd-110 2.81420E-07 8.93170E-05 46110.82c + 403 461110 Pd-111 6.19460E-07 8.77630E-05 461110 + 404 461111 Pd-111m 1.36150E-06 1.70650E-06 461111 + 405 461120 Pd-112 6.91870E-06 7.30530E-05 461120 + 406 461130 Pd-113 3.34940E-06 8.70950E-05 461130 + 407 461131 Pd-113m 9.37160E-06 9.37160E-06 461131 + 408 461140 Pd-114 4.63920E-05 8.58590E-05 461140 + 409 461150 Pd-115 2.51410E-05 6.30830E-05 461150 + 410 461151 Pd-115m 5.52590E-05 6.08770E-05 461151 + 411 461160 Pd-116 7.52390E-05 8.50170E-05 461160 + 412 461170 Pd-117 1.38800E-05 4.54440E-05 461170 + 413 461171 Pd-117m 3.05080E-05 3.05080E-05 461171 + 414 461180 Pd-118 2.01340E-05 2.13480E-05 461180 + 415 461190 Pd-119 4.76270E-06 9.60070E-06 461190 + 416 461200 Pd-120 2.01620E-06 2.48500E-06 461200 + 417 461210 Pd-121 6.19640E-06 6.23800E-06 461210 + 418 461220 Pd-122 2.52050E-06 2.52220E-06 461220 + 419 461230 Pd-123 1.38070E-07 1.38070E-07 461230 + 420 461240 Pd-124 1.39140E-08 1.39140E-08 461240 + 421 471100 Ag-110 1.07570E-11 1.11550E-11 471100 + 422 471101 Ag-110m 2.93200E-11 2.93200E-11 47510.82c + 423 471110 Ag-111 3.04340E-10 8.77890E-05 47111.82c + 424 471111 Ag-111m 2.28580E-09 8.74750E-05 471111 + 425 471120 Ag-112 2.82450E-08 7.30810E-05 471120 + 426 471130 Ag-113 7.95390E-08 5.75330E-05 471130 + 427 471131 Ag-113m 5.97390E-07 8.39970E-05 471131 + 428 471140 Ag-114 1.68740E-07 8.68450E-05 471140 + 429 471141 Ag-114m 8.18040E-07 8.18040E-07 471141 + 430 471150 Ag-115 2.09950E-06 6.68000E-05 471150 + 431 471151 Ag-115m 1.57680E-05 8.88070E-05 471151 + 432 471160 Ag-116 4.45950E-06 9.02060E-05 471160 + 433 471161 Ag-116m 1.21560E-05 1.21560E-05 471161 + 434 471170 Ag-117 4.26920E-06 3.02790E-05 471170 + 435 471171 Ag-117m 3.20650E-05 5.47870E-05 471171 + 436 471180 Ag-118 7.40410E-06 4.16690E-05 471180 + 437 471181 Ag-118m 3.58950E-05 3.89470E-05 471181 + 438 471190 Ag-119 4.47670E-06 9.27710E-06 471190 + 439 471191 Ag-119m 3.36230E-05 3.84240E-05 471191 + 440 471200 Ag-120 6.78910E-06 1.27090E-05 471200 + 441 471201 Ag-120m 1.13540E-05 1.25960E-05 471201 + 442 471210 Ag-121 1.10530E-05 1.72740E-05 471210 + 443 471220 Ag-122 2.36020E-06 4.88230E-06 471220 + 444 471221 Ag-122m 2.54460E-06 2.54460E-06 471221 + 445 471230 Ag-123 1.00430E-06 1.14240E-06 471230 + 446 471240 Ag-124 1.25650E-06 1.94770E-06 471240 + 447 471241 Ag-124m 1.35460E-06 1.35460E-06 471241 + 448 471250 Ag-125 1.00770E-06 1.00770E-06 471250 + 449 471260 Ag-126 1.30190E-07 1.30190E-07 471260 + 450 471270 Ag-127 3.55560E-08 3.55560E-08 471270 + 451 471280 Ag-128 2.15320E-09 2.15320E-09 471280 + 452 481120 Cd-112 6.06060E-12 7.30810E-05 48112.82c + 453 481130 Cd-113 5.41780E-11 8.67780E-05 48113.82c + 454 481131 Cd-113m 2.05170E-10 9.94880E-07 481131 + 455 481140 Cd-114 1.28490E-08 8.68580E-05 48114.82c + 456 481150 Cd-115 4.27350E-08 1.31110E-04 481150 + 457 481151 Cd-115m 1.61830E-07 6.05360E-06 48515.82c + 458 481160 Cd-116 1.95450E-06 1.03590E-04 48116.82c + 459 481170 Cd-117 1.89750E-06 6.57930E-05 481170 + 460 481171 Cd-117m 7.18570E-06 2.50680E-05 481171 + 461 481180 Cd-118 2.31650E-05 8.78120E-05 481180 + 462 481190 Cd-119 1.02870E-05 5.33490E-05 481190 + 463 481191 Cd-119m 2.87820E-05 3.34210E-05 481191 + 464 481200 Cd-120 7.25980E-05 9.32430E-05 481200 + 465 481210 Cd-121 1.11580E-05 2.66270E-05 481210 + 466 481211 Cd-121m 3.12180E-05 3.30230E-05 481211 + 467 481220 Cd-122 5.39490E-05 6.13760E-05 481220 + 468 481230 Cd-123 8.72470E-06 9.66030E-06 481230 + 469 481231 Cd-123m 2.44110E-05 2.46200E-05 481231 + 470 481240 Cd-124 1.54830E-05 1.81060E-05 481240 + 471 481250 Cd-125 3.71390E-06 4.21770E-06 481250 + 472 481251 Cd-125m 1.03910E-05 1.08950E-05 481251 + 473 481260 Cd-126 3.25010E-05 3.26310E-05 481260 + 474 481270 Cd-127 2.90370E-05 2.90730E-05 481270 + 475 481280 Cd-128 2.68400E-05 2.68420E-05 481280 + 476 481290 Cd-129 1.67100E-06 1.67100E-06 481290 + 477 481291 Cd-129m 4.67520E-06 4.67520E-06 481291 + 478 481300 Cd-130 1.36270E-07 1.36270E-07 481300 + 479 481310 Cd-131 2.59200E-09 2.59200E-09 481310 + 480 491150 In-115 5.66370E-11 1.30610E-04 49115.82c + 481 491151 In-115m 1.14040E-11 1.31110E-04 491151 + 482 491160 In-116 2.93110E-10 2.93110E-10 491160 + 483 491161 In-116m 4.73320E-10 1.02130E-09 491161 + 484 491162 In-116m 5.47970E-10 5.47970E-10 491162 + 485 491170 In-117 3.66540E-08 5.88040E-05 491170 + 486 491171 In-117m 7.38010E-09 6.06840E-05 491171 + 487 491180 In-118 1.67500E-12 8.78120E-05 491180 + 488 491181 In-118m 2.70470E-12 5.79220E-12 491181 + 489 491182 In-118m 3.13130E-12 3.13130E-12 491182 + 490 491190 In-119 4.86410E-10 4.12360E-05 491190 + 491 491191 In-119m 9.79350E-11 4.82350E-05 491191 + 492 491200 In-120 6.72030E-07 9.39150E-05 491200 + 493 491201 In-120m 6.72030E-07 6.72030E-07 491201 + 494 491202 In-120m 6.72030E-07 6.72030E-07 491202 + 495 491210 In-121 1.22710E-05 5.45040E-05 491210 + 496 491211 In-121m 2.47080E-06 2.01300E-05 491211 + 497 491220 In-122 8.44490E-06 6.98210E-05 491220 + 498 491221 In-122m 7.06150E-06 7.06150E-06 491221 + 499 491222 In-122m 7.06150E-06 7.06150E-06 491222 + 500 491230 In-123 2.25760E-05 4.98870E-05 491230 + 501 491231 In-123m 4.54550E-06 1.15140E-05 491231 + 502 491240 In-124 1.35070E-05 3.16130E-05 491240 + 503 491241 In-124m 1.45620E-05 1.45620E-05 491241 + 504 491250 In-125 3.69040E-05 4.98180E-05 491250 + 505 491251 In-125m 7.43060E-06 9.62950E-06 491251 + 506 491260 In-126 4.34990E-05 7.61310E-05 491260 + 507 491261 In-126m 4.68980E-05 4.68980E-05 491261 + 508 491270 In-127 2.32700E-04 2.32700E-04 491270 + 509 491271 In-127m 4.68530E-05 7.59250E-05 491271 + 510 491280 In-128 1.44300E-04 2.27640E-04 491280 + 511 491281 In-128m 5.65010E-05 8.33430E-05 491281 + 512 491282 In-128m 2.16490E-04 2.16490E-04 491282 + 513 491290 In-129 3.49320E-04 3.54000E-04 491290 + 514 491291 In-129m 7.03350E-05 7.20080E-05 491291 + 515 491300 In-130 4.72070E-05 4.73390E-05 491300 + 516 491301 In-130m 6.87360E-05 6.87360E-05 491301 + 517 491302 In-130m 9.57470E-05 9.57470E-05 491302 + 518 491310 In-131 2.18640E-05 2.20890E-05 491310 + 519 491311 In-131m 2.18640E-05 2.18640E-05 491311 + 520 491312 In-131m 2.18640E-05 2.18640E-05 491312 + 521 491320 In-132 2.07890E-06 2.07890E-06 491320 + 522 491330 In-133 5.23000E-08 6.28300E-08 491330 + 523 491331 In-133m 1.05300E-08 1.05300E-08 491331 + 524 501170 Sn-117 4.74850E-13 9.09050E-05 50117.82c + 525 501171 Sn-117m 1.79820E-12 2.00350E-07 501171 + 526 501210 Sn-121 1.21290E-11 7.30090E-05 501210 + 527 501211 Sn-121m 3.39370E-11 6.17440E-06 501211 + 528 501220 Sn-122 3.92440E-06 8.78680E-05 50122.82c + 529 501230 Sn-123 5.92000E-06 9.72350E-06 50123.82c + 530 501231 Sn-123m 2.11580E-06 5.97140E-05 501231 + 531 501240 Sn-124 2.42040E-05 7.03790E-05 50124.82c + 532 501250 Sn-125 3.26780E-05 4.10930E-05 50125.82c + 533 501251 Sn-125m 1.16790E-05 6.27120E-05 501251 + 534 501260 Sn-126 1.37300E-04 2.60850E-04 50126.82c + 535 501270 Sn-127 4.20390E-04 5.11090E-04 501270 + 536 501271 Sn-127m 1.50250E-04 3.67650E-04 501271 + 537 501280 Sn-128 7.82090E-04 3.35800E-03 501280 + 538 501281 Sn-128m 2.13180E-03 2.34830E-03 501281 + 539 501290 Sn-129 1.29820E-03 1.68660E-03 501290 + 540 501291 Sn-129m 3.63220E-03 3.66990E-03 501291 + 541 501300 Sn-130 2.12780E-03 2.25740E-03 501300 + 542 501301 Sn-130m 5.79990E-03 5.88260E-03 501301 + 543 501310 Sn-131 1.33560E-03 1.37790E-03 501310 + 544 501311 Sn-131m 3.73690E-03 3.75970E-03 501311 + 545 501320 Sn-132 2.55970E-03 2.56180E-03 501320 + 546 501330 Sn-133 2.57910E-04 2.57920E-04 501330 + 547 501340 Sn-134 4.86600E-05 4.86600E-05 501340 + 548 501350 Sn-135 1.02430E-06 1.02430E-06 501350 + 549 501360 Sn-136 1.54770E-08 1.54770E-08 501360 + 550 511230 Sb-123 7.37790E-12 6.94370E-05 51123.82c + 551 511240 Sb-124 7.78210E-11 2.00280E-10 51124.82c + 552 511241 Sb-124m 6.27770E-11 1.63280E-10 511241 + 553 511242 Sb-124m 1.00510E-10 1.00510E-10 511242 + 554 511250 Sb-125 2.01560E-06 1.05820E-04 51125.82c + 555 511260 Sb-126 1.69470E-06 2.02660E-06 51126.82c + 556 511261 Sb-126m 1.05850E-06 2.37060E-06 511261 + 557 511262 Sb-126m 1.31220E-06 1.31220E-06 511262 + 558 511270 Sb-127 4.88030E-05 9.27540E-04 511270 + 559 511280 Sb-128 8.89000E-05 3.45140E-03 511280 + 560 511281 Sb-128m 1.24340E-04 1.24340E-04 511281 + 561 511290 Sb-129 1.39510E-03 5.34670E-03 511290 + 562 511291 Sb-129m 1.03240E-03 2.86730E-03 511291 + 563 511300 Sb-130 2.90220E-03 8.10090E-03 511300 + 564 511301 Sb-130m 2.90220E-03 5.84350E-03 511301 + 565 511310 Sb-131 1.45610E-02 1.96990E-02 511310 + 566 511320 Sb-132 7.15350E-03 9.71530E-03 511320 + 567 511321 Sb-132m 6.33350E-03 6.33350E-03 511321 + 568 511330 Sb-133 1.07210E-02 1.09870E-02 511330 + 569 511340 Sb-134 7.94060E-04 8.34560E-04 511340 + 570 511341 Sb-134m 2.16440E-03 2.16450E-03 511341 + 571 511350 Sb-135 6.80420E-04 6.81230E-04 511350 + 572 511360 Sb-136 8.13680E-05 8.13790E-05 511360 + 573 511370 Sb-137 6.86240E-06 6.86240E-06 511370 + 574 511380 Sb-138 6.99650E-08 6.99650E-08 511380 + 575 511390 Sb-139 2.15040E-09 2.15040E-09 511390 + 576 521260 Te-126 2.40840E-10 4.06560E-06 52126.82c + 577 521270 Te-127 2.73200E-07 9.24890E-04 521270 + 578 521271 Te-127m 7.64400E-07 1.53620E-04 52527.82c + 579 521280 Te-128 1.93430E-05 3.59060E-03 52128.82c + 580 521290 Te-129 3.35020E-05 6.66750E-03 521290 + 581 521291 Te-129m 9.37380E-05 3.36120E-03 52529.82c + 582 521300 Te-130 1.84410E-03 1.57890E-02 52130.82c + 583 521310 Te-131 1.62020E-03 2.10250E-02 521310 + 584 521311 Te-131m 4.53310E-03 6.11020E-03 521311 + 585 521320 Te-132 2.73180E-02 4.33670E-02 52132.82c + 586 521330 Te-133 1.00450E-02 2.43840E-02 521330 + 587 521331 Te-133m 2.81040E-02 3.00050E-02 521331 + 588 521340 Te-134 6.10850E-02 6.41890E-02 521340 + 589 521350 Te-135 2.07360E-02 2.13230E-02 521350 + 590 521360 Te-136 1.05160E-02 1.05870E-02 521360 + 591 521370 Te-137 2.02380E-03 2.02730E-03 521370 + 592 521380 Te-138 5.05480E-04 5.05550E-04 521380 + 593 521390 Te-139 3.17060E-05 3.17080E-05 521390 + 594 521400 Te-140 7.21200E-06 7.21200E-06 521400 + 595 521410 Te-141 8.48010E-09 8.48010E-09 521410 + 596 531280 I-128 1.53800E-10 1.53800E-10 531280 + 597 531290 I-129 3.86530E-08 7.91120E-03 53129.82c + 598 531300 I-130 5.38730E-06 7.04750E-06 53130.82c + 599 531301 I-130m 1.97640E-06 1.97640E-06 531301 + 600 531310 I-131 9.71590E-05 2.59490E-02 53131.82c + 601 531320 I-132 2.52990E-04 4.38120E-02 531320 + 602 531321 I-132m 2.23990E-04 2.23990E-04 531321 + 603 531330 I-133 2.43510E-03 5.33750E-02 531330 + 604 531331 I-133m 1.80210E-03 1.80210E-03 531331 + 605 531340 I-134 6.63320E-03 7.65600E-02 531340 + 606 531341 I-134m 5.87280E-03 5.87280E-03 531341 + 607 531350 I-135 4.30360E-02 6.43600E-02 53135.82c + 608 531360 I-136 7.71840E-03 1.83360E-02 531360 + 609 531361 I-136m 2.10390E-02 2.10690E-02 531361 + 610 531370 I-137 2.19870E-02 2.39850E-02 531370 + 611 531380 I-138 6.56740E-03 7.04110E-03 531380 + 612 531390 I-139 4.11870E-03 4.15040E-03 531390 + 613 531400 I-140 8.05880E-04 8.13090E-04 531400 + 614 531410 I-141 1.32070E-04 1.32080E-04 531410 + 615 531420 I-142 1.17860E-05 1.17860E-05 531420 + 616 531430 I-143 9.43710E-08 9.43710E-08 531430 + 617 531440 I-144 1.19230E-09 1.19230E-09 531440 + 618 541310 Xe-131 3.07110E-09 2.59490E-02 54131.82c + 619 541311 Xe-131m 8.59290E-09 2.81870E-04 541311 + 620 541320 Xe-132 4.44370E-06 4.38540E-02 54132.82c + 621 541321 Xe-132m 5.95330E-06 5.95330E-06 541321 + 622 541330 Xe-133 2.24590E-05 5.34610E-02 54133.82c + 623 541331 Xe-133m 6.28380E-05 1.58210E-03 541331 + 624 541340 Xe-134 3.16100E-04 7.78730E-02 54134.82c + 625 541341 Xe-134m 8.61600E-04 9.96680E-04 541341 + 626 541350 Xe-135 1.41150E-03 6.96330E-02 54135.82c + 627 541351 Xe-135m 3.94940E-03 1.45740E-02 541351 + 628 541360 Xe-136 3.77020E-02 7.86660E-02 54136.82c + 629 541370 Xe-137 4.91940E-02 7.19940E-02 541370 + 630 541380 Xe-138 6.24000E-02 6.94750E-02 541380 + 631 541390 Xe-139 3.14720E-02 3.52910E-02 541390 + 632 541400 Xe-140 2.70540E-02 2.78190E-02 541400 + 633 541410 Xe-141 8.60290E-03 8.71020E-03 541410 + 634 541420 Xe-142 3.58590E-03 3.59480E-03 541420 + 635 541430 Xe-143 5.30400E-04 5.30460E-04 541430 + 636 541440 Xe-144 1.06200E-04 1.06200E-04 541440 + 637 541450 Xe-145 5.81890E-06 5.81890E-06 541450 + 638 541460 Xe-146 9.16600E-09 9.16600E-09 541460 + 639 551330 Cs-133 3.69600E-09 5.34610E-02 55133.82c + 640 551340 Cs-134 1.04180E-07 1.96410E-07 55134.82c + 641 551341 Cs-134m 9.22340E-08 9.22340E-08 551341 + 642 551350 Cs-135 6.47690E-06 6.97320E-02 55135.82c + 643 551351 Cs-135m 4.79310E-06 4.79310E-06 551351 + 644 551360 Cs-136 9.18090E-05 1.24630E-04 55136.82c + 645 551361 Cs-136m 6.56410E-05 6.56410E-05 551361 + 646 551370 Cs-137 2.22990E-03 7.42240E-02 55137.82c + 647 551380 Cs-138 2.82230E-03 7.61200E-02 551380 + 648 551381 Cs-138m 4.71990E-03 4.71990E-03 551381 + 649 551390 Cs-139 2.08370E-02 5.61280E-02 551390 + 650 551400 Cs-140 2.15790E-02 4.94020E-02 551400 + 651 551410 Cs-141 3.10640E-02 3.97830E-02 551410 + 652 551420 Cs-142 1.52270E-02 1.88140E-02 551420 + 653 551430 Cs-143 1.07090E-02 1.12370E-02 551430 + 654 551440 Cs-144 1.66660E-03 2.60310E-03 551440 + 655 551441 Cs-144m 1.66660E-03 1.66680E-03 551441 + 656 551450 Cs-145 7.84250E-04 7.89780E-04 551450 + 657 551460 Cs-146 1.01600E-04 1.01610E-04 551460 + 658 551470 Cs-147 1.14610E-05 1.14610E-05 551470 + 659 551480 Cs-148 2.45350E-08 2.45350E-08 551480 + 660 551490 Cs-149 3.66420E-10 3.66420E-10 551490 + 661 561360 Ba-136 1.16310E-08 1.57490E-04 56136.82c + 662 561361 Ba-136m 3.17030E-08 3.17030E-08 561361 + 663 561370 Ba-137 5.94140E-06 7.42460E-02 56137.82c + 664 561371 Ba-137m 1.66240E-05 7.00830E-02 561371 + 665 561380 Ba-138 4.26630E-04 7.74430E-02 56138.82c + 666 561390 Ba-139 2.29430E-03 5.84230E-02 561390 + 667 561400 Ba-140 9.54960E-03 5.89520E-02 56140.82c + 668 561410 Ba-141 1.64350E-02 5.62180E-02 561410 + 669 561420 Ba-142 4.10370E-02 6.00350E-02 561420 + 670 561430 Ba-143 3.76840E-02 4.88200E-02 561430 + 671 561440 Ba-144 4.00810E-02 4.35470E-02 561440 + 672 561450 Ba-145 1.41110E-02 1.48020E-02 561450 + 673 561460 Ba-146 7.56480E-03 7.65520E-03 561460 + 674 561470 Ba-147 1.66260E-03 1.67080E-03 561470 + 675 561480 Ba-148 4.31260E-04 4.31280E-04 561480 + 676 561490 Ba-149 4.93760E-05 4.93760E-05 561490 + 677 561500 Ba-150 9.45720E-07 9.45720E-07 561500 + 678 561510 Ba-151 8.78790E-10 8.78790E-10 561510 + 679 571380 La-138 3.33170E-09 3.33170E-09 57138.82c + 680 571390 La-139 2.04710E-06 5.84250E-02 57139.82c + 681 571400 La-140 2.06210E-05 5.89720E-02 57140.82c + 682 571410 La-141 2.60590E-04 5.64790E-02 571410 + 683 571420 La-142 7.80290E-04 6.08160E-02 571420 + 684 571430 La-143 4.14970E-03 5.29700E-02 571430 + 685 571440 La-144 8.78640E-03 5.23330E-02 571440 + 686 571450 La-145 1.67840E-02 3.15860E-02 571450 + 687 571460 La-146 3.51980E-03 1.11750E-02 571460 + 688 571461 La-146m 7.38420E-03 7.38420E-03 571461 + 689 571470 La-147 1.01640E-02 1.18360E-02 571470 + 690 571480 La-148 3.43770E-03 3.86750E-03 571480 + 691 571490 La-149 1.26040E-03 1.30960E-03 571490 + 692 571500 La-150 2.14730E-04 2.15680E-04 571500 + 693 571510 La-151 2.91250E-05 2.91260E-05 571510 + 694 571520 La-152 1.94050E-06 1.94050E-06 571520 + 695 571530 La-153 2.64730E-09 2.64730E-09 571530 + 696 571540 La-154 1.08910E-11 1.08910E-11 571540 + 697 581410 Ce-141 1.96270E-06 5.64810E-02 58141.82c + 698 581420 Ce-142 2.81450E-05 6.08440E-02 58142.82c + 699 581430 Ce-143 1.81790E-04 5.31520E-02 58143.82c + 700 581440 Ce-144 1.06530E-03 5.33990E-02 58144.82c + 701 581450 Ce-145 3.21260E-03 3.47990E-02 581450 + 702 581460 Ce-146 8.97740E-03 2.75370E-02 581460 + 703 581470 Ce-147 1.06940E-02 2.25300E-02 581470 + 704 581480 Ce-148 1.40940E-02 1.79800E-02 581480 + 705 581490 Ce-149 7.11160E-03 8.40870E-03 581490 + 706 581500 Ce-150 4.38690E-03 4.59680E-03 581500 + 707 581510 Ce-151 9.94180E-04 1.02340E-03 581510 + 708 581520 Ce-152 2.82080E-04 2.83900E-04 581520 + 709 581530 Ce-153 3.51710E-05 3.51740E-05 581530 + 710 581540 Ce-154 1.96550E-06 1.96550E-06 581540 + 711 581550 Ce-155 2.10060E-09 2.10060E-09 581550 + 712 581560 Ce-156 3.10600E-11 3.10600E-11 581560 + 713 591430 Pr-143 1.85040E-09 5.31520E-02 59143.82c + 714 591440 Pr-144 8.98850E-08 5.33990E-02 591440 + 715 591441 Pr-144m 9.14410E-07 7.37790E-04 591441 + 716 591450 Pr-145 1.26150E-05 3.48120E-02 591450 + 717 591460 Pr-146 4.67040E-05 2.75830E-02 591460 + 718 591470 Pr-147 2.69020E-04 2.28000E-02 591470 + 719 591480 Pr-148 1.04550E-04 1.80840E-02 591480 + 720 591481 Pr-148m 5.06870E-04 5.06870E-04 591481 + 721 591490 Pr-149 1.77270E-03 1.01810E-02 591490 + 722 591500 Pr-150 1.68880E-03 6.28550E-03 591500 + 723 591510 Pr-151 1.82880E-03 2.85220E-03 591510 + 724 591520 Pr-152 7.33260E-04 1.01740E-03 591520 + 725 591530 Pr-153 3.16970E-04 3.51940E-04 591530 + 726 591540 Pr-154 6.97230E-05 7.16760E-05 591540 + 727 591550 Pr-155 1.18570E-05 1.18590E-05 591550 + 728 591560 Pr-156 7.10300E-08 7.10610E-08 591560 + 729 591570 Pr-157 2.30770E-09 2.30770E-09 591570 + 730 591580 Pr-158 1.57980E-11 1.57980E-11 591580 + 731 601460 Nd-146 9.52000E-07 2.75840E-02 60146.82c + 732 601470 Nd-147 2.86670E-06 2.28020E-02 60147.82c + 733 601480 Nd-148 3.56070E-05 1.86270E-02 60148.82c + 734 601490 Nd-149 1.24940E-04 1.03060E-02 601490 + 735 601500 Nd-150 4.44740E-04 6.73030E-03 60150.82c + 736 601510 Nd-151 6.53590E-04 3.50580E-03 601510 + 737 601520 Nd-152 9.50180E-04 1.96760E-03 601520 + 738 601530 Nd-153 5.88090E-04 9.40030E-04 601530 + 739 601540 Nd-154 3.94200E-04 4.65880E-04 601540 + 740 601550 Nd-155 9.87960E-05 1.10660E-04 601550 + 741 601560 Nd-156 2.27990E-05 2.28680E-05 601560 + 742 601570 Nd-157 5.90540E-06 5.90760E-06 601570 + 743 601580 Nd-158 6.22970E-08 6.23130E-08 601580 + 744 601590 Nd-159 2.19560E-10 2.19560E-10 601590 + 745 601600 Nd-160 5.46210E-11 5.46210E-11 601600 + 746 611480 Pm-148 1.04520E-10 1.18770E-10 61148.82c + 747 611481 Pm-148m 2.84910E-10 2.84910E-10 61548.82c + 748 611490 Pm-149 2.27180E-08 1.03060E-02 61149.82c + 749 611500 Pm-150 3.11150E-07 3.11150E-07 611500 + 750 611510 Pm-151 4.85820E-06 3.51070E-03 61151.82c + 751 611520 Pm-152 1.32760E-06 1.96890E-03 611520 + 752 611521 Pm-152m 2.79110E-06 2.79110E-06 611521 + 753 611522 Pm-152m 3.64590E-06 3.64590E-06 611522 + 754 611530 Pm-153 2.93430E-05 9.69370E-04 611530 + 755 611540 Pm-154 1.96650E-05 4.85540E-04 611540 + 756 611541 Pm-154m 1.96650E-05 1.96650E-05 611541 + 757 611550 Pm-155 4.25110E-05 1.53170E-04 611550 + 758 611560 Pm-156 2.67710E-05 4.96390E-05 611560 + 759 611570 Pm-157 9.84270E-06 1.57500E-05 611570 + 760 611580 Pm-158 9.90600E-07 1.05290E-06 611580 + 761 611590 Pm-159 6.64350E-08 6.66550E-08 611590 + 762 611600 Pm-160 2.61270E-08 2.61810E-08 611600 + 763 611610 Pm-161 9.37900E-10 9.37900E-10 611610 + 764 611620 Pm-162 1.37750E-11 1.37750E-11 611620 + 765 621510 Sm-151 7.03030E-10 3.51070E-03 62151.82c + 766 621520 Sm-152 2.93320E-08 1.97540E-03 62152.82c + 767 621530 Sm-153 5.90580E-08 9.69590E-04 62153.82c + 768 621531 Sm-153m 1.65240E-07 1.65240E-07 621531 + 769 621540 Sm-154 2.94860E-06 5.08160E-04 62154.82c + 770 621550 Sm-155 7.90750E-06 1.61080E-04 621550 + 771 621560 Sm-156 1.28920E-05 6.25310E-05 621560 + 772 621570 Sm-157 5.90610E-06 2.16560E-05 621570 + 773 621580 Sm-158 5.94390E-06 6.99680E-06 621580 + 774 621590 Sm-159 3.32660E-07 3.99370E-07 621590 + 775 621600 Sm-160 2.10900E-06 2.13510E-06 621600 + 776 621610 Sm-161 6.66780E-08 6.76160E-08 621610 + 777 621620 Sm-162 1.13200E-08 1.13340E-08 621620 + 778 621630 Sm-163 3.81660E-10 3.81660E-10 621630 + 779 621640 Sm-164 1.60190E-11 1.60190E-11 621640 + 780 631530 Eu-153 3.43800E-11 9.69590E-04 63153.82c + 781 631540 Eu-154 2.67280E-10 5.55450E-10 63154.82c + 782 631541 Eu-154m 2.88170E-10 2.88170E-10 631541 + 783 631550 Eu-155 1.03130E-08 1.61090E-04 63155.82c + 784 631560 Eu-156 4.68860E-08 6.25780E-05 63156.82c + 785 631570 Eu-157 2.89760E-07 2.19460E-05 63157.82c + 786 631580 Eu-158 9.90620E-07 7.98740E-06 631580 + 787 631590 Eu-159 5.98760E-07 9.98130E-07 631590 + 788 631600 Eu-160 7.78600E-07 2.91370E-06 631600 + 789 631610 Eu-161 3.54090E-07 4.21710E-07 631610 + 790 631620 Eu-162 7.54760E-08 8.68100E-08 631620 + 791 631630 Eu-163 2.62600E-08 2.66420E-08 631630 + 792 631640 Eu-164 1.64030E-09 1.65630E-09 631640 + 793 631650 Eu-165 2.26920E-10 2.26920E-10 631650 + 794 631660 Eu-166 6.23450E-12 6.23450E-12 631660 + 795 641560 Gd-156 1.55300E-11 6.25780E-05 64156.82c + 796 641570 Gd-157 1.61510E-10 2.19460E-05 64157.82c + 797 641580 Gd-158 2.60160E-09 7.99000E-06 64158.82c + 798 641590 Gd-159 1.74030E-09 9.99870E-07 641590 + 799 641600 Gd-160 8.31310E-08 2.99680E-06 64160.82c + 800 641610 Gd-161 4.85780E-08 4.70280E-07 641610 + 801 641620 Gd-162 9.25440E-08 1.79350E-07 641620 + 802 641630 Gd-163 3.73090E-08 6.39510E-08 641630 + 803 641640 Gd-164 2.11060E-08 2.27620E-08 641640 + 804 641650 Gd-165 3.82420E-09 4.05110E-09 641650 + 805 641660 Gd-166 1.12880E-09 1.13500E-09 641660 + 806 641670 Gd-167 5.88130E-11 5.88130E-11 641670 + 807 641680 Gd-168 5.04870E-12 5.04870E-12 641680 + 808 651600 Tb-160 6.86680E-11 6.86680E-11 65160.82c + 809 651610 Tb-161 4.70700E-10 4.70750E-07 651610 + 810 651620 Tb-162 1.31430E-09 1.80670E-07 651620 + 811 651630 Tb-163 5.36530E-09 6.93160E-08 651630 + 812 651640 Tb-164 3.74530E-09 2.65080E-08 651640 + 813 651650 Tb-165 5.94110E-09 9.99220E-09 651650 + 814 651660 Tb-166 2.05490E-09 3.18990E-09 651660 + 815 651670 Tb-167 1.00540E-09 1.06420E-09 651670 + 816 651680 Tb-168 1.18010E-10 1.23060E-10 651680 + 817 651690 Tb-169 2.97640E-11 2.97640E-11 651690 + 818 651700 Tb-170 1.22630E-12 1.22630E-12 651700 + 819 661620 Dy-162 1.85740E-12 1.80670E-07 66162.82c + 820 661630 Dy-163 1.21160E-11 6.93280E-08 66163.82c + 821 661640 Dy-164 9.65340E-11 2.66040E-08 66164.82c + 822 661650 Dy-165 1.90750E-10 1.02080E-08 661650 + 823 661651 Dy-165m 2.53980E-11 2.53980E-11 661651 + 824 661660 Dy-166 7.25070E-10 3.91500E-09 661660 + 825 661670 Dy-167 4.23380E-10 1.48760E-09 661670 + 826 661680 Dy-168 4.32410E-10 5.55470E-10 661680 + 827 661690 Dy-169 1.31030E-10 1.60790E-10 661690 + 828 661700 Dy-170 5.28630E-11 5.40890E-11 661700 + 829 661710 Dy-171 5.19300E-12 5.19300E-12 661710 + 830 671660 Ho-166 6.38550E-13 3.91560E-09 671660 + 831 671661 Ho-166m 1.74060E-12 1.74060E-12 671661 + 832 671670 Ho-167 1.53550E-11 1.50300E-09 671670 + 833 671680 Ho-168 7.94730E-12 5.76640E-10 671680 + 834 671681 Ho-168m 1.32910E-11 1.32910E-11 671681 + 835 671690 Ho-169 5.99100E-11 2.20700E-10 671690 + 836 671700 Ho-170 2.06410E-11 2.06410E-11 671700 + 837 671701 Ho-170m 7.57240E-12 6.16620E-11 671701 + 838 671710 Ho-171 2.43480E-11 2.95410E-11 671710 + 839 671720 Ho-172 5.50610E-12 5.50610E-12 671720 + 840 671730 Ho-173 1.97180E-12 1.97180E-12 671730 + 841 681700 Er-170 2.62710E-12 8.49290E-11 68170.82c + 842 681710 Er-171 2.94080E-12 3.24820E-11 681710 + 843 681720 Er-172 5.98110E-12 1.14870E-11 681720 + 844 681730 Er-173 2.48090E-12 4.45270E-12 681730 + 845 681740 Er-174 1.47360E-12 1.47360E-12 681740 + + Nuclide 92235.82c -- uranium 235 (U-235) + + Neutron-induced fission: + + Interpolation region : 1 / 3 + Interpolation energy : 2.53000E-08 MeV + Number of products : 873 / 983 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 1.71100E-05 1.71100E-05 1001.82c + 2 10020 H-2 8.40000E-06 8.40000E-06 1002.82c + 3 10030 H-3 1.08000E-04 1.08000E-04 1003.82c + 4 20040 He-4 1.70000E-03 1.70210E-03 2004.82c + 5 20060 He-6 2.66800E-05 2.66800E-05 20060 + 6 30080 Li-8 7.29200E-07 7.29200E-07 30080 + 7 30090 Li-9 4.07100E-07 4.07100E-07 30090 + 8 40080 Be-8 7.29200E-07 1.34180E-06 40080 + 9 40090 Be-9 4.07100E-07 6.12680E-07 4009.82c + 10 40100 Be-10 5.20100E-06 5.20100E-06 40100 + 11 40120 Be-12 1.26100E-07 1.26100E-07 40120 + 12 50090 B-9 4.07100E-07 4.07100E-07 50090 + 13 50100 B-10 5.20100E-06 5.20100E-06 5010.82c + 14 50120 B-12 1.26100E-07 2.52200E-07 50120 + 15 60140 C-14 1.57800E-06 1.57800E-06 60140 + 16 60150 C-15 2.52800E-07 2.52800E-07 60150 + 17 100210 Ne-21 2.14600E-06 2.14600E-06 100210 + 18 220560 Ti-56 1.01040E-12 1.01040E-12 220560 + 19 230560 V-56 1.31210E-12 2.32250E-12 230560 + 20 230570 V-57 4.17090E-12 4.17090E-12 230570 + 21 230580 V-58 3.49080E-12 3.49080E-12 230580 + 22 230590 V-59 5.78070E-12 5.78070E-12 230590 + 23 230600 V-60 1.48530E-12 1.48530E-12 230600 + 24 240570 Cr-57 1.02360E-12 7.97050E-12 240570 + 25 240580 Cr-58 7.88200E-12 8.58020E-12 240580 + 26 240590 Cr-59 1.47600E-11 2.05410E-11 240590 + 27 240600 Cr-60 3.79930E-11 3.94780E-11 240600 + 28 240610 Cr-61 2.53250E-11 2.53250E-11 240610 + 29 240620 Cr-62 3.39050E-11 3.39050E-11 240620 + 30 240630 Cr-63 7.36830E-12 7.36830E-12 240630 + 31 240640 Cr-64 2.48330E-12 2.48330E-12 240640 + 32 250590 Mn-59 4.62960E-12 2.51700E-11 250590 + 33 250600 Mn-60 1.37700E-12 4.22620E-11 250600 + 34 250601 Mn-60m 1.22300E-11 1.22300E-11 250601 + 35 250610 Mn-61 8.32000E-11 1.08520E-10 250610 + 36 250620 Mn-62 1.09690E-10 1.26640E-10 250620 + 37 250621 Mn-62m 1.96920E-11 3.66440E-11 250621 + 38 250630 Mn-63 2.93570E-10 3.00940E-10 250630 + 39 250640 Mn-64 1.37240E-10 1.39720E-10 250640 + 40 250650 Mn-65 1.48780E-10 1.48780E-10 250650 + 41 250660 Mn-66 2.73720E-11 2.73720E-11 250660 + 42 250670 Mn-67 7.11780E-12 7.11780E-12 250670 + 43 260610 Fe-61 5.26970E-12 1.13800E-10 260610 + 44 260620 Fe-62 8.02440E-11 2.43530E-10 260620 + 45 260630 Fe-63 2.03800E-10 5.04740E-10 260630 + 46 260640 Fe-64 8.83860E-10 1.02360E-09 260640 + 47 260650 Fe-65 1.15340E-09 1.30220E-09 260650 + 48 260660 Fe-66 2.31060E-09 2.33800E-09 260660 + 49 260670 Fe-67 8.62940E-10 8.70060E-10 260670 + 50 260680 Fe-68 6.60880E-10 6.60880E-10 260680 + 51 260690 Fe-69 1.03850E-10 1.03850E-10 260690 + 52 260700 Fe-70 1.99300E-11 1.99300E-11 260700 + 53 270630 Co-63 1.56330E-11 5.20370E-10 270630 + 54 270640 Co-64 8.46230E-11 1.10820E-09 270640 + 55 270650 Co-65 1.04630E-09 2.34850E-09 270650 + 56 270660 Co-66 2.33090E-09 4.66890E-09 270660 + 57 270670 Co-67 8.27360E-09 9.14370E-09 270670 + 58 270680 Co-68 4.22080E-09 6.41660E-09 270680 + 59 270681 Co-68m 3.72350E-09 4.39160E-09 270681 + 60 270690 Co-69 1.41440E-08 1.42410E-08 270690 + 61 270700 Co-70 2.00900E-09 2.00900E-09 270700 + 62 270701 Co-70m 2.00900E-09 2.02890E-09 270701 + 63 270710 Co-71 2.37290E-09 2.37290E-09 270710 + 64 270720 Co-72 3.02930E-10 3.02930E-10 270720 + 65 270730 Co-73 4.63620E-11 4.63620E-11 270730 + 66 270740 Co-74 2.40200E-12 2.40200E-12 270740 + 67 280650 Ni-65 1.52990E-11 2.36380E-09 280650 + 68 280660 Ni-66 3.69460E-10 5.03830E-09 280660 + 69 280670 Ni-67 1.57200E-09 1.07160E-08 280670 + 70 280680 Ni-68 1.39780E-08 2.27330E-08 280680 + 71 280690 Ni-69 1.39500E-08 2.80480E-08 280690 + 72 280691 Ni-69m 1.39500E-08 1.39500E-08 280691 + 73 280700 Ni-70 7.79170E-08 8.19550E-08 280700 + 74 280710 Ni-71 6.01760E-08 6.25490E-08 280710 + 75 280720 Ni-72 9.02260E-08 9.05290E-08 280720 + 76 280730 Ni-73 2.09680E-08 2.10140E-08 280730 + 77 280740 Ni-74 1.41310E-08 1.41330E-08 280740 + 78 280750 Ni-75 1.00690E-09 1.00690E-09 280750 + 79 280760 Ni-76 5.14040E-10 5.14040E-10 280760 + 80 280770 Ni-77 1.21280E-11 1.21280E-11 280770 + 81 290670 Cu-67 2.63490E-11 1.07420E-08 290670 + 82 290680 Cu-68 9.68360E-11 2.30200E-08 290680 + 83 290681 Cu-68m 2.26810E-10 2.26810E-10 290681 + 84 290690 Cu-69 6.71390E-09 4.87110E-08 290690 + 85 290700 Cu-70 1.65190E-09 1.29440E-08 290700 + 86 290701 Cu-70m 1.84030E-08 2.25830E-08 290701 + 87 290702 Cu-70m 1.65190E-09 8.36070E-08 290702 + 88 290710 Cu-71 1.53720E-07 2.16270E-07 290710 + 89 290720 Cu-72 2.63930E-07 3.54460E-07 290720 + 90 290730 Cu-73 6.27620E-07 6.48630E-07 290730 + 91 290740 Cu-74 6.40030E-07 6.54180E-07 290740 + 92 290750 Cu-75 4.97490E-07 4.98480E-07 290750 + 93 290760 Cu-76 1.96910E-07 1.97170E-07 290760 + 94 290761 Cu-76m 1.96910E-07 1.97170E-07 290761 + 95 290770 Cu-77 1.12840E-07 1.12850E-07 290770 + 96 290780 Cu-78 8.73600E-09 8.73600E-09 290780 + 97 290790 Cu-79 1.06310E-09 1.06310E-09 290790 + 98 290800 Cu-80 3.39210E-11 3.39210E-11 290800 + 99 300690 Zn-69 3.83770E-12 4.87320E-08 300690 + 100 300691 Zn-69m 1.65970E-11 1.65970E-11 300691 + 101 300700 Zn-70 7.85580E-10 1.04450E-07 300700 + 102 300710 Zn-71 1.38760E-09 2.17660E-07 300710 + 103 300711 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1.47490E-04 6.13990E-02 42099.82c + 340 421000 Mo-100 9.66880E-04 6.25490E-02 42100.82c + 341 421010 Mo-101 2.80510E-03 5.17820E-02 421010 + 342 421020 Mo-102 7.04180E-03 4.28530E-02 421020 + 343 421030 Mo-103 9.16260E-03 3.08170E-02 421030 + 344 421040 Mo-104 1.05210E-02 1.82460E-02 421040 + 345 421050 Mo-105 6.21270E-03 8.60100E-03 421050 + 346 421060 Mo-106 3.07740E-03 3.39700E-03 421060 + 347 421070 Mo-107 6.58610E-04 7.05950E-04 421070 + 348 421080 Mo-108 1.56480E-04 1.61220E-04 421080 + 349 421090 Mo-109 3.48130E-05 3.62020E-05 421090 + 350 421100 Mo-110 3.61460E-06 3.61460E-06 421100 + 351 421110 Mo-111 1.64380E-08 1.64380E-08 421110 + 352 421120 Mo-112 5.18850E-10 5.18850E-10 421120 + 353 421130 Mo-113 7.52280E-12 7.52280E-12 421130 + 354 431000 Tc-100 1.07410E-08 1.07410E-08 431000 + 355 431010 Tc-101 1.07590E-05 5.17930E-02 431010 + 356 431020 Tc-102 4.18080E-05 4.28950E-02 431020 + 357 431021 Tc-102m 4.18080E-05 4.18080E-05 431021 + 358 431030 Tc-103 2.97550E-04 3.11140E-02 431030 + 359 431040 Tc-104 5.62140E-04 1.88080E-02 431040 + 360 431050 Tc-105 8.45760E-04 9.44680E-03 431050 + 361 431060 Tc-106 6.44680E-04 4.04170E-03 431060 + 362 431070 Tc-107 6.13280E-04 1.31920E-03 431070 + 363 431080 Tc-108 3.19460E-04 4.80870E-04 431080 + 364 431090 Tc-109 1.54520E-04 1.90530E-04 431090 + 365 431100 Tc-110 9.08310E-05 9.44460E-05 431100 + 366 431110 Tc-111 3.67140E-05 3.67300E-05 431110 + 367 431120 Tc-112 4.35940E-06 4.35990E-06 431120 + 368 431130 Tc-113 1.48820E-06 1.48820E-06 431130 + 369 431140 Tc-114 1.05880E-06 1.05880E-06 431140 + 370 431150 Tc-115 8.42590E-11 8.42590E-11 431150 + 371 441020 Ru-102 2.30620E-06 4.29390E-02 44102.82c + 372 441030 Ru-103 1.03720E-06 3.11180E-02 44103.82c + 373 441031 Ru-103m 2.50410E-06 2.50410E-06 441031 + 374 441040 Ru-104 2.37220E-05 1.88320E-02 44104.82c + 375 441050 Ru-105 4.13410E-05 9.48810E-03 44105.82c + 376 441060 Ru-106 5.40910E-05 4.09580E-03 44106.82c + 377 441070 Ru-107 6.79620E-05 1.38720E-03 441070 + 378 441080 Ru-108 8.36350E-05 5.64650E-04 441080 + 379 441090 Ru-109 8.94480E-05 2.79860E-04 441090 + 380 441100 Ru-110 1.40280E-04 2.34690E-04 441100 + 381 441110 Ru-111 1.11450E-04 1.48250E-04 441110 + 382 441120 Ru-112 7.15240E-05 7.59250E-05 441120 + 383 441130 Ru-113 2.03290E-05 3.19440E-05 441130 + 384 441131 Ru-113m 2.03290E-05 2.03290E-05 441131 + 385 441140 Ru-114 1.92080E-05 2.01980E-05 441140 + 386 441150 Ru-115 3.79540E-06 3.79550E-06 441150 + 387 441160 Ru-116 2.70030E-06 2.70030E-06 441160 + 388 441170 Ru-117 5.00590E-10 5.00590E-10 441170 + 389 441180 Ru-118 1.78750E-11 1.78750E-11 441180 + 390 441190 Ru-119 6.64460E-08 6.64460E-08 441190 + 391 441200 Ru-120 5.36150E-09 5.36150E-09 441200 + 392 451050 Rh-105 1.35750E-09 9.48810E-03 45105.82c + 393 451051 Rh-105m 2.07520E-10 2.69350E-03 451051 + 394 451060 Rh-106 5.25330E-09 4.09580E-03 451060 + 395 451061 Rh-106m 1.23050E-08 1.23050E-08 451061 + 396 451070 Rh-107 3.14810E-07 1.38750E-03 451070 + 397 451080 Rh-108 8.88500E-07 5.65540E-04 451080 + 398 451081 Rh-108m 2.68120E-06 2.68120E-06 451081 + 399 451090 Rh-109 4.71060E-06 2.84570E-04 451090 + 400 451100 Rh-110 1.20300E-05 2.46720E-04 451100 + 401 451101 Rh-110m 3.21130E-07 3.21130E-07 451101 + 402 451110 Rh-111 4.13650E-05 1.89610E-04 451110 + 403 451120 Rh-112 1.64630E-05 9.23880E-05 451120 + 404 451121 Rh-112m 1.64630E-05 1.64630E-05 451121 + 405 451130 Rh-113 8.83520E-05 1.30460E-04 451130 + 406 451140 Rh-114 2.44160E-05 4.46220E-05 451140 + 407 451141 Rh-114m 2.44160E-05 2.44160E-05 451141 + 408 451150 Rh-115 5.07870E-05 5.46030E-05 451150 + 409 451160 Rh-116 5.28240E-06 7.95350E-06 451160 + 410 451161 Rh-116m 1.23730E-05 1.23730E-05 451161 + 411 451170 Rh-117 7.60840E-06 7.60890E-06 451170 + 412 451180 Rh-118 3.97750E-06 3.98040E-06 451180 + 413 451190 Rh-119 2.00220E-05 2.00860E-05 451190 + 414 451200 Rh-120 2.48180E-06 2.48720E-06 451200 + 415 451210 Rh-121 3.82360E-07 3.82360E-07 451210 + 416 451220 Rh-122 1.80850E-08 1.80850E-08 451220 + 417 461080 Pd-108 6.47570E-10 5.68230E-04 46108.82c + 418 461090 Pd-109 2.72160E-09 2.84580E-04 461090 + 419 461091 Pd-109m 5.11490E-09 1.42290E-04 461091 + 420 461100 Pd-110 2.54160E-07 2.47290E-04 46110.82c + 421 461110 Pd-111 2.45700E-06 1.95230E-04 461110 + 422 461111 Pd-111m 4.61770E-06 5.37610E-06 461111 + 423 461120 Pd-112 8.54250E-06 1.17390E-04 461120 + 424 461130 Pd-113 7.69300E-06 1.56730E-04 461130 + 425 461131 Pd-113m 1.85720E-05 1.85720E-05 461131 + 426 461140 Pd-114 5.78560E-05 1.26890E-04 461140 + 427 461150 Pd-115 1.88160E-05 6.89540E-05 461150 + 428 461151 Pd-115m 3.53620E-05 4.32900E-05 461151 + 429 461160 Pd-116 1.19790E-04 1.40120E-04 461160 + 430 461170 Pd-117 2.32720E-05 7.47340E-05 461170 + 431 461171 Pd-117m 4.37370E-05 4.37370E-05 461171 + 432 461180 Pd-118 7.26310E-05 7.64950E-05 461180 + 433 461190 Pd-119 2.53810E-05 4.56140E-05 461190 + 434 461200 Pd-120 1.37120E-05 1.61040E-05 461200 + 435 461210 Pd-121 1.32190E-06 1.65240E-06 461210 + 436 461220 Pd-122 1.28190E-05 1.28370E-05 461220 + 437 461230 Pd-123 9.06310E-07 9.06310E-07 461230 + 438 461240 Pd-124 2.25040E-07 2.25040E-07 461240 + 439 471100 Ag-110 5.12110E-12 5.28420E-12 471100 + 440 471101 Ag-110m 1.19950E-11 1.19950E-11 47510.82c + 441 471110 Ag-111 1.64620E-10 1.95710E-04 47111.82c + 442 471111 Ag-111m 1.07690E-09 1.94890E-04 471111 + 443 471120 Ag-112 1.26220E-08 1.17410E-04 471120 + 444 471130 Ag-113 1.96060E-07 1.03720E-04 471130 + 445 471131 Ag-113m 1.28250E-06 1.51360E-04 471131 + 446 471140 Ag-114 2.02470E-07 1.27950E-04 471140 + 447 471141 Ag-114m 8.51530E-07 8.51530E-07 471141 + 448 471150 Ag-115 5.00500E-07 6.37980E-05 471150 + 449 471151 Ag-115m 3.27400E-06 6.17190E-05 471151 + 450 471160 Ag-116 4.79620E-06 1.45590E-04 471160 + 451 471161 Ag-116m 1.12340E-05 1.12340E-05 471161 + 452 471170 Ag-117 6.68650E-06 4.89200E-05 471170 + 453 471171 Ag-117m 4.37390E-05 8.11070E-05 471171 + 454 471180 Ag-118 9.58620E-06 9.61590E-05 471180 + 455 471181 Ag-118m 4.03160E-05 5.12510E-05 471181 + 456 471190 Ag-119 1.04430E-05 3.32500E-05 471190 + 457 471191 Ag-119m 6.83140E-05 9.11210E-05 471191 + 458 471200 Ag-120 2.22150E-05 4.49140E-05 471200 + 459 471201 Ag-120m 3.15230E-05 3.95740E-05 471201 + 460 471210 Ag-121 2.95910E-05 3.12390E-05 471210 + 461 471220 Ag-122 7.27180E-06 2.01090E-05 471220 + 462 471221 Ag-122m 6.55020E-06 6.55020E-06 471221 + 463 471230 Ag-123 2.57000E-06 3.47630E-06 471230 + 464 471240 Ag-124 3.57290E-06 5.40710E-06 471240 + 465 471241 Ag-124m 3.21830E-06 3.21830E-06 471241 + 466 471250 Ag-125 3.48300E-06 3.48300E-06 471250 + 467 471260 Ag-126 1.36730E-06 1.36730E-06 471260 + 468 471270 Ag-127 9.35480E-07 9.35480E-07 471270 + 469 471280 Ag-128 1.58900E-08 1.58900E-08 471280 + 470 471290 Ag-129 9.91810E-10 9.91810E-10 471290 + 471 481130 Cd-113 1.76110E-11 1.56410E-04 48113.82c + 472 481131 Cd-113m 5.76170E-11 1.79320E-06 481131 + 473 481140 Cd-114 4.18260E-09 1.27950E-04 48114.82c + 474 481150 Cd-115 1.13480E-08 1.07470E-04 481150 + 475 481151 Cd-115m 3.71280E-08 5.13290E-06 48515.82c + 476 481160 Cd-116 2.68620E-06 1.58830E-04 48116.82c + 477 481170 Cd-117 6.63560E-07 9.86570E-05 481170 + 478 481171 Cd-117m 2.17090E-06 2.93380E-05 481171 + 479 481180 Cd-118 2.22220E-05 1.48620E-04 481180 + 480 481190 Cd-119 9.78080E-06 1.17530E-04 481190 + 481 481191 Cd-119m 2.36120E-05 4.02380E-05 481191 + 482 481200 Cd-120 7.78530E-05 1.47700E-04 481200 + 483 481210 Cd-121 2.43160E-05 5.22910E-05 481210 + 484 481211 Cd-121m 5.87030E-05 6.19670E-05 481211 + 485 481220 Cd-122 1.22640E-04 1.49300E-04 481220 + 486 481230 Cd-123 2.04400E-05 2.32870E-05 481230 + 487 481231 Cd-123m 4.93450E-05 4.99800E-05 481231 + 488 481240 Cd-124 1.27820E-04 1.34830E-04 481240 + 489 481250 Cd-125 3.47350E-05 3.64770E-05 481250 + 490 481251 Cd-125m 8.38550E-05 8.55970E-05 481251 + 491 481260 Cd-126 1.88760E-04 1.90130E-04 481260 + 492 481270 Cd-127 1.47720E-04 1.48660E-04 481270 + 493 481280 Cd-128 8.75240E-05 8.75400E-05 481280 + 494 481290 Cd-129 8.49530E-06 8.49580E-06 481290 + 495 481291 Cd-129m 2.05090E-05 2.05090E-05 481291 + 496 481300 Cd-130 1.11330E-05 1.11330E-05 481300 + 497 481310 Cd-131 2.11000E-08 2.11000E-08 481310 + 498 491150 In-115 6.84350E-12 1.07230E-04 49115.82c + 499 491151 In-115m 1.58240E-12 1.07470E-04 491151 + 500 491160 In-116 9.69440E-11 9.69440E-11 491160 + 501 491161 In-116m 1.48590E-10 2.92510E-10 491161 + 502 491162 In-116m 1.43920E-10 1.43920E-10 491162 + 503 491170 In-117 1.35430E-08 7.99460E-05 491170 + 504 491171 In-117m 3.13140E-09 9.08610E-05 491171 + 505 491180 In-118 4.87990E-08 1.48670E-04 491180 + 506 491181 In-118m 7.47970E-08 1.46230E-07 491181 + 507 491182 In-118m 7.24440E-08 7.24440E-08 491182 + 508 491190 In-119 7.15080E-11 5.75220E-05 491190 + 509 491191 In-119m 1.65340E-11 1.06190E-04 491191 + 510 491200 In-120 1.78470E-06 1.49480E-04 491200 + 511 491201 In-120m 1.78470E-06 1.78470E-06 491201 + 512 491202 In-120m 1.78470E-06 1.78470E-06 491202 + 513 491210 In-121 1.03400E-05 9.03630E-05 491210 + 514 491211 In-121m 2.39090E-06 3.70700E-05 491211 + 515 491220 In-122 1.29600E-05 1.62260E-04 491220 + 516 491221 In-122m 9.19500E-06 9.19500E-06 491221 + 517 491222 In-122m 9.19500E-06 9.19500E-06 491222 + 518 491230 In-123 4.73270E-05 1.03910E-04 491230 + 519 491231 In-123m 1.09430E-05 2.76270E-05 491231 + 520 491240 In-124 3.94130E-05 1.74240E-04 491240 + 521 491241 In-124m 3.55030E-05 3.55030E-05 491241 + 522 491250 In-125 1.05530E-04 2.08590E-04 491250 + 523 491251 In-125m 2.44010E-05 4.34180E-05 491251 + 524 491260 In-126 1.12880E-04 3.03000E-04 491260 + 525 491261 In-126m 1.01680E-04 1.01680E-04 491261 + 526 491270 In-127 4.33250E-04 4.33250E-04 491270 + 527 491271 In-127m 1.00180E-04 2.48830E-04 491271 + 528 491280 In-128 2.96820E-04 5.05180E-04 491280 + 529 491281 In-128m 1.20820E-04 2.08360E-04 491281 + 530 491282 In-128m 3.76200E-04 3.76200E-04 491282 + 531 491290 In-129 8.12190E-04 8.32900E-04 491290 + 532 491291 In-129m 1.87800E-04 1.96490E-04 491291 + 533 491300 In-130 1.48660E-04 1.59400E-04 491300 + 534 491301 In-130m 1.66040E-04 1.66040E-04 491301 + 535 491302 In-130m 2.82500E-04 2.82500E-04 491302 + 536 491310 In-131 6.77270E-05 6.84360E-05 491310 + 537 491311 In-131m 6.77270E-05 6.77270E-05 491311 + 538 491312 In-131m 6.77270E-05 6.77270E-05 491312 + 539 491320 In-132 1.06030E-05 1.06030E-05 491320 + 540 491330 In-133 4.66630E-07 5.74530E-07 491330 + 541 491331 In-133m 1.07900E-07 1.07900E-07 491331 + 542 491340 In-134 6.95940E-09 6.95940E-09 491340 + 543 501180 Sn-118 7.74560E-11 1.48820E-04 50118.82c + 544 501210 Sn-121 1.74380E-12 1.24700E-04 501210 + 545 501211 Sn-121m 4.20970E-12 1.02370E-05 501211 + 546 501220 Sn-122 3.38120E-06 1.84030E-04 50122.82c + 547 501230 Sn-123 4.47710E-06 1.23990E-05 50123.82c + 548 501231 Sn-123m 1.85460E-06 1.25470E-04 501231 + 549 501240 Sn-124 3.96920E-05 2.49440E-04 50124.82c + 550 501250 Sn-125 3.35940E-05 6.88280E-05 50125.82c + 551 501251 Sn-125m 1.39150E-05 2.30680E-04 501251 + 552 501260 Sn-126 1.70550E-04 5.76940E-04 50126.82c + 553 501270 Sn-127 3.74830E-04 5.43700E-04 501270 + 554 501271 Sn-127m 1.55260E-04 6.66760E-04 501271 + 555 501280 Sn-128 6.76400E-04 3.14210E-03 501280 + 556 501281 Sn-128m 1.58430E-03 1.96050E-03 501281 + 557 501290 Sn-129 1.68520E-03 2.62600E-03 501290 + 558 501291 Sn-129m 4.06830E-03 4.15700E-03 501291 + 559 501300 Sn-130 3.64580E-03 4.04220E-03 501300 + 560 501301 Sn-130m 8.53920E-03 8.75210E-03 501301 + 561 501310 Sn-131 3.33090E-03 3.46210E-03 501310 + 562 501311 Sn-131m 8.04110E-03 8.11180E-03 501311 + 563 501320 Sn-132 7.36720E-03 7.37830E-03 501320 + 564 501330 Sn-133 9.58620E-04 9.58710E-04 501330 + 565 501340 Sn-134 1.08880E-04 1.08880E-04 501340 + 566 501350 Sn-135 9.90980E-06 9.90980E-06 501350 + 567 501360 Sn-136 8.92730E-07 8.92730E-07 501360 + 568 511240 Sb-124 2.68920E-11 6.31710E-11 51124.82c + 569 511241 Sb-124m 2.05620E-11 4.83720E-11 511241 + 570 511242 Sb-124m 2.78100E-11 2.78100E-11 511242 + 571 511250 Sb-125 3.44320E-06 3.02950E-04 51125.82c + 572 511260 Sb-126 3.00310E-06 3.72050E-06 51126.82c + 573 511261 Sb-126m 2.22040E-06 5.12430E-06 511261 + 574 511262 Sb-126m 2.90390E-06 2.90390E-06 511262 + 575 511270 Sb-127 2.87000E-05 1.23920E-03 511270 + 576 511280 Sb-128 7.03340E-05 3.21670E-03 511280 + 577 511281 Sb-128m 1.20020E-04 1.20020E-04 511281 + 578 511290 Sb-129 7.88660E-04 5.87720E-03 511290 + 579 511291 Sb-129m 4.81940E-04 2.56040E-03 511291 + 580 511300 Sb-130 2.53300E-03 1.09510E-02 511300 + 581 511301 Sb-130m 2.53300E-03 6.90900E-03 511301 + 582 511310 Sb-131 1.32970E-02 2.48710E-02 511310 + 583 511320 Sb-132 1.17900E-02 1.91690E-02 511320 + 584 511321 Sb-132m 8.68970E-03 8.68970E-03 511321 + 585 511330 Sb-133 2.41420E-02 2.51190E-02 511330 + 586 511340 Sb-134 1.91940E-03 2.01080E-03 511340 + 587 511341 Sb-134m 4.49570E-03 4.49670E-03 511341 + 588 511350 Sb-135 1.40460E-03 1.41270E-03 511350 + 589 511360 Sb-136 2.14620E-04 2.15250E-04 511360 + 590 511370 Sb-137 2.25880E-05 2.25880E-05 511370 + 591 511380 Sb-138 3.93920E-07 3.93920E-07 511380 + 592 511390 Sb-139 1.21320E-08 1.21320E-08 511390 + 593 521260 Te-126 2.43920E-11 8.12740E-06 52126.82c + 594 521270 Te-127 5.46410E-07 1.23610E-03 521270 + 595 521271 Te-127m 1.31910E-06 2.05530E-04 52527.82c + 596 521280 Te-128 5.41960E-06 3.33780E-03 52128.82c + 597 521290 Te-129 2.45650E-05 6.96810E-03 521290 + 598 521291 Te-129m 5.93040E-05 3.16000E-03 52529.82c + 599 521300 Te-130 8.03010E-04 1.86630E-02 52130.82c + 600 521310 Te-131 1.26240E-03 2.52000E-02 521310 + 601 521311 Te-131m 3.04750E-03 5.03870E-03 521311 + 602 521320 Te-132 1.50420E-02 4.29000E-02 52132.82c + 603 521330 Te-133 1.15360E-02 3.79490E-02 521330 + 604 521331 Te-133m 2.78500E-02 3.21950E-02 521331 + 605 521340 Te-134 6.30010E-02 6.97270E-02 521340 + 606 521350 Te-135 3.47770E-02 3.60030E-02 521350 + 607 521360 Te-136 1.66520E-02 1.68430E-02 521360 + 608 521370 Te-137 4.84400E-03 4.85550E-03 521370 + 609 521380 Te-138 1.12800E-03 1.12840E-03 521380 + 610 521390 Te-139 1.69770E-04 1.69780E-04 521390 + 611 521400 Te-140 2.47710E-05 2.47710E-05 521400 + 612 521410 Te-141 6.06940E-08 6.06940E-08 521410 + 613 521420 Te-142 2.31770E-09 2.31770E-09 521420 + 614 531290 I-129 3.63660E-09 8.13740E-03 53129.82c + 615 531300 I-130 1.51160E-06 2.05360E-06 53130.82c + 616 531301 I-130m 6.45340E-07 6.45340E-07 531301 + 617 531310 I-131 2.96040E-05 2.92100E-02 53131.82c + 618 531320 I-132 1.63490E-04 4.31670E-02 531320 + 619 531321 I-132m 1.20500E-04 1.20500E-04 531321 + 620 531330 I-133 1.23020E-03 6.64910E-02 531330 + 621 531331 I-133m 7.51740E-04 7.51740E-04 531331 + 622 531340 I-134 4.41730E-03 7.73250E-02 531340 + 623 531341 I-134m 3.25570E-03 3.25570E-03 531341 + 624 531350 I-135 2.46350E-02 6.06380E-02 53135.82c + 625 531360 I-136 9.09030E-03 2.60060E-02 531360 + 626 531361 I-136m 2.12920E-02 2.13640E-02 531361 + 627 531370 I-137 2.70260E-02 3.18070E-02 531370 + 628 531380 I-138 1.24190E-02 1.34760E-02 531380 + 629 531390 I-139 7.38460E-03 7.55440E-03 531390 + 630 531400 I-140 1.93130E-03 1.95610E-03 531400 + 631 531410 I-141 4.68430E-04 4.68490E-04 531410 + 632 531420 I-142 4.67730E-05 4.67750E-05 531420 + 633 531430 I-143 4.31870E-06 4.31870E-06 531430 + 634 531440 I-144 7.40820E-09 7.40820E-09 531440 + 635 541310 Xe-131 2.06000E-10 2.92100E-02 54131.82c + 636 541311 Xe-131m 4.97310E-10 3.17280E-04 541311 + 637 541320 Xe-132 1.65400E-06 4.31880E-02 54132.82c + 638 541321 Xe-132m 1.87480E-06 1.87480E-06 541321 + 639 541330 Xe-133 1.24490E-05 6.65340E-02 54133.82c + 640 541331 Xe-133m 3.00530E-05 1.92260E-03 541331 + 641 541340 Xe-134 1.04710E-04 7.77500E-02 54134.82c + 642 541341 Xe-134m 2.45270E-04 3.20150E-04 541341 + 643 541350 Xe-135 7.31220E-04 6.30640E-02 54135.82c + 644 541351 Xe-135m 1.76530E-03 1.17760E-02 541351 + 645 541360 Xe-136 1.60280E-02 6.54650E-02 54136.82c + 646 541370 Xe-137 2.96320E-02 6.00860E-02 541370 + 647 541380 Xe-138 4.98260E-02 6.33280E-02 541380 + 648 541390 Xe-139 4.34330E-02 5.04290E-02 541390 + 649 541400 Xe-140 3.83430E-02 4.02160E-02 541400 + 650 541410 Xe-141 1.94660E-02 1.98480E-02 541410 + 651 541420 Xe-142 6.84910E-03 6.88590E-03 541420 + 652 541430 Xe-143 1.82220E-03 1.82480E-03 541430 + 653 541440 Xe-144 3.15460E-04 3.15460E-04 541440 + 654 541450 Xe-145 3.17270E-05 3.17270E-05 541450 + 655 541460 Xe-146 5.55350E-06 5.55350E-06 541460 + 656 541470 Xe-147 5.38480E-10 5.38480E-10 541470 + 657 551340 Cs-134 1.00160E-08 1.73980E-08 55134.82c + 658 551341 Cs-134m 7.38200E-09 7.38200E-09 551341 + 659 551350 Cs-135 5.59030E-07 6.31350E-02 55135.82c + 660 551351 Cs-135m 3.41620E-07 3.41620E-07 551351 + 661 551360 Cs-136 2.25160E-05 2.91130E-05 55136.82c + 662 551361 Cs-136m 1.31950E-05 1.31950E-05 551361 + 663 551370 Cs-137 8.10950E-04 6.08970E-02 55137.82c + 664 551380 Cs-138 1.39000E-03 6.63160E-02 551380 + 665 551381 Cs-138m 1.97230E-03 1.97230E-03 551381 + 666 551390 Cs-139 1.19490E-02 6.23780E-02 551390 + 667 551400 Cs-140 1.81940E-02 5.84180E-02 551400 + 668 551410 Cs-141 2.90800E-02 4.89440E-02 551410 + 669 551420 Cs-142 2.33290E-02 3.02080E-02 551420 + 670 551430 Cs-143 1.56820E-02 1.74980E-02 551430 + 671 551440 Cs-144 3.43280E-03 5.45630E-03 551440 + 672 551441 Cs-144m 3.43280E-03 3.43350E-03 551441 + 673 551450 Cs-145 1.96810E-03 1.99860E-03 551450 + 674 551460 Cs-146 3.23460E-04 3.28630E-04 551460 + 675 551470 Cs-147 6.65080E-05 6.65090E-05 551470 + 676 551480 Cs-148 2.72070E-06 2.72070E-06 551480 + 677 551490 Cs-149 2.80620E-09 2.80620E-09 551490 + 678 561360 Ba-136 2.67100E-07 3.66040E-05 56136.82c + 679 561361 Ba-136m 6.25610E-07 6.25610E-07 561361 + 680 561370 Ba-137 2.03540E-06 6.09040E-02 56137.82c + 681 561371 Ba-137m 4.91380E-06 5.74920E-02 561371 + 682 561380 Ba-138 1.39440E-04 6.68300E-02 56138.82c + 683 561390 Ba-139 8.53770E-04 6.32320E-02 561390 + 684 561400 Ba-140 5.02540E-03 6.34440E-02 56140.82c + 685 561410 Ba-141 9.59550E-03 5.85390E-02 561410 + 686 561420 Ba-142 2.76210E-02 5.81160E-02 561420 + 687 561430 Ba-143 3.99330E-02 5.73190E-02 561430 + 688 561440 Ba-144 4.14180E-02 4.87020E-02 561440 + 689 561450 Ba-145 2.35530E-02 2.53130E-02 561450 + 690 561460 Ba-146 1.07710E-02 1.10720E-02 561460 + 691 561470 Ba-147 3.88810E-03 3.93630E-03 561470 + 692 561480 Ba-148 8.75120E-04 8.77160E-04 561480 + 693 561490 Ba-149 1.22130E-04 1.22130E-04 561490 + 694 561500 Ba-150 1.05240E-05 1.05240E-05 561500 + 695 561510 Ba-151 6.67960E-09 6.67960E-09 561510 + 696 561520 Ba-152 1.01530E-10 1.01530E-10 561520 + 697 571390 La-139 1.94120E-08 6.32320E-02 57139.82c + 698 571400 La-140 6.46280E-06 6.34500E-02 57140.82c + 699 571410 La-141 1.06780E-04 5.86460E-02 571410 + 700 571420 La-142 3.16290E-04 5.84330E-02 571420 + 701 571430 La-143 2.15620E-03 5.94750E-02 571430 + 702 571440 La-144 5.66650E-03 5.43690E-02 571440 + 703 571450 La-145 1.27090E-02 3.80210E-02 571450 + 704 571460 La-146 4.64060E-03 1.57130E-02 571460 + 705 571461 La-146m 8.34740E-03 8.34740E-03 571461 + 706 571470 La-147 9.46310E-03 1.34030E-02 571470 + 707 571480 La-148 4.70010E-03 5.57430E-03 571480 + 708 571490 La-149 1.86280E-03 1.98440E-03 571490 + 709 571500 La-150 4.87830E-04 4.98350E-04 571500 + 710 571510 La-151 8.65670E-05 8.65740E-05 571510 + 711 571520 La-152 1.13090E-05 1.13090E-05 571520 + 712 571530 La-153 2.20260E-08 2.20260E-08 571530 + 713 571540 La-154 1.30040E-10 1.30040E-10 571540 + 714 581410 Ce-141 1.41150E-09 5.86460E-02 58141.82c + 715 581420 Ce-142 1.09560E-05 5.84440E-02 58142.82c + 716 581430 Ce-143 4.76340E-05 5.95220E-02 58143.82c + 717 581440 Ce-144 4.11930E-04 5.47810E-02 58144.82c + 718 581450 Ce-145 1.53660E-03 3.95580E-02 581450 + 719 581460 Ce-146 5.88910E-03 2.99490E-02 581460 + 720 581470 Ce-147 8.94430E-03 2.23470E-02 581470 + 721 581480 Ce-148 1.09360E-02 1.65380E-02 581480 + 722 581490 Ce-149 7.29820E-03 9.26830E-03 581490 + 723 581500 Ce-150 4.24740E-03 4.73230E-03 581500 + 724 581510 Ce-151 1.78780E-03 1.87510E-03 581510 + 725 581520 Ce-152 5.17680E-04 5.28310E-04 581520 + 726 581530 Ce-153 7.89880E-05 7.90100E-05 581530 + 727 581540 Ce-154 8.37770E-06 8.37780E-06 581540 + 728 581550 Ce-155 1.70060E-08 1.70060E-08 581550 + 729 581560 Ce-156 3.78400E-10 3.78400E-10 581560 + 730 581570 Ce-157 1.56570E-12 1.56570E-12 581570 + 731 591440 Pr-144 7.49710E-10 5.47800E-02 591440 + 732 591441 Pr-144m 6.65850E-09 7.55950E-04 591441 + 733 591450 Pr-145 2.18980E-06 3.95600E-02 591450 + 734 591460 Pr-146 2.00660E-05 2.99690E-02 591460 + 735 591470 Pr-147 1.16710E-04 2.24640E-02 591470 + 736 591480 Pr-148 7.19110E-05 1.66100E-02 591480 + 737 591481 Pr-148m 3.02430E-04 3.02430E-04 591481 + 738 591490 Pr-149 9.61350E-04 1.02300E-02 591490 + 739 591500 Pr-150 1.57350E-03 6.30580E-03 591500 + 740 591510 Pr-151 1.84110E-03 3.71620E-03 591510 + 741 591520 Pr-152 1.06050E-03 1.58930E-03 591520 + 742 591530 Pr-153 4.75120E-04 5.53690E-04 591530 + 743 591540 Pr-154 1.13040E-04 1.21360E-04 591540 + 744 591550 Pr-155 2.61920E-05 2.62090E-05 591550 + 745 591560 Pr-156 2.91610E-06 2.91650E-06 591560 + 746 591570 Pr-157 3.15160E-08 3.15180E-08 591570 + 747 591580 Pr-158 2.15330E-10 2.15330E-10 591580 + 748 591590 Pr-159 3.75590E-12 3.75590E-12 591590 + 749 601460 Nd-146 1.26120E-09 2.99690E-02 60146.82c + 750 601470 Nd-147 9.95240E-07 2.24650E-02 60147.82c + 751 601480 Nd-148 1.46330E-05 1.69270E-02 60148.82c + 752 601490 Nd-149 4.59200E-05 1.02760E-02 601490 + 753 601500 Nd-150 2.31860E-04 6.53770E-03 60150.82c + 754 601510 Nd-151 5.72770E-04 4.28890E-03 601510 + 755 601520 Nd-152 9.43460E-04 2.53280E-03 601520 + 756 601530 Nd-153 8.93360E-04 1.44710E-03 601530 + 757 601540 Nd-154 5.80620E-04 7.01980E-04 601540 + 758 601550 Nd-155 2.42970E-04 2.69260E-04 601550 + 759 601560 Nd-156 8.89850E-05 9.18240E-05 601560 + 760 601570 Nd-157 2.27740E-05 2.28030E-05 601570 + 761 601580 Nd-158 2.99570E-06 2.99590E-06 601580 + 762 601590 Nd-159 1.17210E-08 1.17250E-08 601590 + 763 601600 Nd-160 4.98160E-10 4.98160E-10 601600 + 764 611490 Pm-149 2.00440E-09 1.02760E-02 61149.82c + 765 611500 Pm-150 9.55140E-07 9.55140E-07 611500 + 766 611510 Pm-151 1.07770E-06 4.29000E-03 61151.82c + 767 611520 Pm-152 1.72550E-06 2.53450E-03 611520 + 768 611521 Pm-152m 3.44570E-06 3.44570E-06 611521 + 769 611522 Pm-152m 3.81130E-06 3.81130E-06 611522 + 770 611530 Pm-153 2.03490E-05 1.46740E-03 611530 + 771 611540 Pm-154 1.46980E-05 7.16680E-04 611540 + 772 611541 Pm-154m 1.46980E-05 1.46980E-05 611541 + 773 611550 Pm-155 3.35610E-05 3.02820E-04 611550 + 774 611560 Pm-156 3.49140E-05 1.26740E-04 611560 + 775 611570 Pm-157 2.73810E-05 5.01850E-05 611570 + 776 611580 Pm-158 5.91940E-06 8.91520E-06 611580 + 777 611590 Pm-159 3.04560E-06 3.05730E-06 611590 + 778 611600 Pm-160 1.32870E-07 1.33360E-07 611600 + 779 611610 Pm-161 3.20810E-09 3.20810E-09 611610 + 780 611620 Pm-162 2.03710E-10 2.03710E-10 611620 + 781 611630 Pm-163 5.55700E-12 5.55700E-12 611630 + 782 621510 Sm-151 1.09500E-10 4.29000E-03 62151.82c + 783 621520 Sm-152 3.85810E-09 2.54170E-03 62152.82c + 784 621530 Sm-153 1.40050E-08 1.46740E-03 62153.82c + 785 621531 Sm-153m 3.38100E-08 3.38100E-08 621531 + 786 621540 Sm-154 9.29100E-07 7.32310E-04 62154.82c + 787 621550 Sm-155 8.59820E-06 3.11420E-04 621550 + 788 621560 Sm-156 7.56700E-06 1.34310E-04 621560 + 789 621570 Sm-157 1.57390E-05 6.59240E-05 621570 + 790 621580 Sm-158 1.02930E-05 1.92090E-05 621580 + 791 621590 Sm-159 6.08100E-06 9.13810E-06 621590 + 792 621600 Sm-160 3.49530E-06 3.62830E-06 621600 + 793 621610 Sm-161 4.41010E-07 4.44220E-07 621610 + 794 621620 Sm-162 8.27410E-08 8.29450E-08 621620 + 795 621630 Sm-163 3.52700E-09 3.53260E-09 621630 + 796 621640 Sm-164 2.27180E-10 2.27180E-10 621640 + 797 621650 Sm-165 3.75840E-12 3.75840E-12 621650 + 798 631540 Eu-154 3.04050E-11 5.77940E-11 63154.82c + 799 631541 Eu-154m 2.73890E-11 2.73890E-11 631541 + 800 631550 Eu-155 2.47980E-09 3.11420E-04 63155.82c + 801 631560 Eu-156 1.93130E-08 1.34320E-04 63156.82c + 802 631570 Eu-157 2.60930E-07 6.61850E-05 63157.82c + 803 631580 Eu-158 3.85920E-07 1.95950E-05 631580 + 804 631590 Eu-159 1.49480E-06 1.06330E-05 631590 + 805 631600 Eu-160 6.98530E-07 4.32680E-06 631600 + 806 631610 Eu-161 3.47010E-07 7.91230E-07 631610 + 807 631620 Eu-162 3.15130E-07 3.98070E-07 631620 + 808 631630 Eu-163 1.42570E-07 1.46100E-07 631630 + 809 631640 Eu-164 1.29740E-08 1.32010E-08 631640 + 810 631650 Eu-165 2.68830E-09 2.69210E-09 631650 + 811 631660 Eu-166 9.40870E-11 9.40870E-11 631660 + 812 631670 Eu-167 4.52260E-12 4.52260E-12 631670 + 813 641570 Gd-157 5.01010E-11 6.61850E-05 64157.82c + 814 641580 Gd-158 9.82130E-10 1.95960E-05 64158.82c + 815 641590 Gd-159 5.88260E-09 1.06390E-05 641590 + 816 641600 Gd-160 5.35490E-08 4.38040E-06 64160.82c + 817 641610 Gd-161 2.15950E-08 8.12820E-07 641610 + 818 641620 Gd-162 1.95060E-07 5.93130E-07 641620 + 819 641630 Gd-163 1.00220E-07 2.46320E-07 641630 + 820 641640 Gd-164 8.59140E-08 9.91150E-08 641640 + 821 641650 Gd-165 2.18170E-08 2.45090E-08 641650 + 822 641660 Gd-166 8.48470E-09 8.57880E-09 641660 + 823 641670 Gd-167 5.98430E-10 6.02950E-10 641670 + 824 641680 Gd-168 8.44570E-11 8.44570E-11 641680 + 825 641690 Gd-169 2.46670E-12 2.46670E-12 641690 + 826 651590 Tb-159 1.36580E-12 1.06390E-05 65159.82c + 827 651600 Tb-160 1.85170E-11 1.85170E-11 65160.82c + 828 651610 Tb-161 9.74600E-11 8.12920E-07 651610 + 829 651620 Tb-162 1.32320E-09 5.94460E-07 651620 + 830 651630 Tb-163 7.79750E-09 2.54120E-07 651630 + 831 651640 Tb-164 8.46280E-09 1.07580E-07 651640 + 832 651650 Tb-165 2.06250E-08 4.51340E-08 651650 + 833 651660 Tb-166 9.05210E-09 1.76310E-08 651660 + 834 651670 Tb-167 6.18120E-09 6.78420E-09 651670 + 835 651680 Tb-168 1.11830E-09 1.20280E-09 651680 + 836 651690 Tb-169 3.78910E-10 3.81380E-10 651690 + 837 651700 Tb-170 2.00000E-11 2.00000E-11 651700 + 838 651710 Tb-171 2.09800E-12 2.09800E-12 651710 + 839 661630 Dy-163 6.44560E-12 2.54130E-07 66163.82c + 840 661640 Dy-164 8.94110E-11 1.07670E-07 66164.82c + 841 661650 Dy-165 2.74660E-10 4.54500E-08 661650 + 842 661651 Dy-165m 4.19880E-11 4.19880E-11 661651 + 843 661660 Dy-166 1.52530E-09 1.91560E-08 661660 + 844 661670 Dy-167 1.26190E-09 8.04610E-09 661670 + 845 661680 Dy-168 2.14010E-09 3.34290E-09 661680 + 846 661690 Dy-169 8.27160E-10 1.20850E-09 661690 + 847 661700 Dy-170 4.39280E-10 4.59280E-10 661700 + 848 661710 Dy-171 6.18530E-11 6.39510E-11 661710 + 849 661720 Dy-172 1.69400E-11 1.69400E-11 661720 + 850 671660 Ho-166 6.70390E-13 1.91570E-08 671660 + 851 671661 Ho-166m 1.57020E-12 1.57020E-12 671661 + 852 671670 Ho-167 2.30330E-11 8.06910E-09 671670 + 853 671680 Ho-168 2.25610E-11 3.39730E-09 671680 + 854 671681 Ho-168m 3.20140E-11 3.20140E-11 671681 + 855 671690 Ho-169 2.21090E-10 1.42960E-09 671690 + 856 671700 Ho-170 9.60940E-11 9.60940E-11 671700 + 857 671701 Ho-170m 4.10260E-11 5.00310E-10 671701 + 858 671710 Ho-171 1.79560E-10 2.43510E-10 671710 + 859 671720 Ho-172 5.75790E-11 7.45190E-11 671720 + 860 671730 Ho-173 2.63670E-11 2.63670E-11 671730 + 861 671740 Ho-174 2.52810E-12 2.52810E-12 671740 + 862 681700 Er-170 5.67470E-12 6.02080E-10 68170.82c + 863 681710 Er-171 9.93770E-12 2.53450E-10 681710 + 864 681720 Er-172 3.19520E-11 1.06470E-10 681720 + 865 681730 Er-173 1.66660E-11 4.30330E-11 681730 + 866 681740 Er-174 1.49990E-11 1.75270E-11 681740 + 867 681750 Er-175 3.98050E-12 3.98050E-12 681750 + 868 681760 Er-176 1.58450E-12 1.58450E-12 681760 + 869 691730 Tm-173 1.14800E-12 4.41810E-11 691730 + 870 691740 Tm-174 1.31940E-12 1.88470E-11 691740 + 871 691750 Tm-175 3.38110E-12 7.36160E-12 691750 + 872 691760 Tm-176 1.51860E-12 3.10310E-12 691760 + 873 691770 Tm-177 1.08900E-12 1.08900E-12 691770 + + Neutron-induced fission: + + Interpolation region : 2 / 3 + Interpolation energy : 4.00000E-01 MeV + Number of products : 867 / 971 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 2.68910E-05 2.68910E-05 1001.82c + 2 10020 H-2 8.21820E-06 8.21820E-06 1002.82c + 3 10030 H-3 1.08000E-04 1.08000E-04 1003.82c + 4 20040 He-4 1.70000E-03 1.70000E-03 2004.82c + 5 230570 V-57 2.30530E-12 2.30530E-12 230570 + 6 230580 V-58 2.14100E-12 2.14100E-12 230580 + 7 230590 V-59 3.87110E-12 3.87110E-12 230590 + 8 230600 V-60 1.11060E-12 1.11060E-12 230600 + 9 240580 Cr-58 4.69150E-12 5.11970E-12 240580 + 10 240590 Cr-59 9.63840E-12 1.35090E-11 240590 + 11 240600 Cr-60 2.71110E-11 2.82220E-11 240600 + 12 240610 Cr-61 2.01280E-11 2.01280E-11 240610 + 13 240620 Cr-62 2.95040E-11 2.95040E-11 240620 + 14 240630 Cr-63 7.15320E-12 7.15320E-12 240630 + 15 240640 Cr-64 2.68370E-12 2.68370E-12 240640 + 16 250590 Mn-59 2.94860E-12 1.64580E-11 250590 + 17 250600 Mn-60 8.53290E-13 3.00730E-11 250600 + 18 250601 Mn-60m 8.68070E-12 8.68070E-12 250601 + 19 250610 Mn-61 6.37820E-11 8.39100E-11 250610 + 20 250620 Mn-62 9.42500E-11 1.09000E-10 250620 + 21 250621 Mn-62m 1.47600E-11 2.95120E-11 250621 + 22 250630 Mn-63 2.69840E-10 2.76990E-10 250630 + 23 250640 Mn-64 1.40430E-10 1.43110E-10 250640 + 24 250650 Mn-65 1.67280E-10 1.67280E-10 250650 + 25 250660 Mn-66 3.42920E-11 3.42920E-11 250660 + 26 250670 Mn-67 9.95080E-12 9.95080E-12 250670 + 27 260610 Fe-61 4.02780E-12 8.79380E-11 260610 + 28 260620 Fe-62 6.62310E-11 2.04740E-10 260620 + 29 260630 Fe-63 1.84720E-10 4.61710E-10 260630 + 30 260640 Fe-64 8.75400E-10 1.01850E-09 260640 + 31 260650 Fe-65 1.25870E-09 1.42600E-09 260650 + 32 260660 Fe-66 2.74580E-09 2.78010E-09 260660 + 33 260670 Fe-67 1.14430E-09 1.15430E-09 260670 + 34 260680 Fe-68 9.65480E-10 9.65480E-10 260680 + 35 260690 Fe-69 1.69120E-10 1.69120E-10 260690 + 36 260700 Fe-70 3.61780E-11 3.61780E-11 260700 + 37 260710 Fe-71 1.89240E-12 1.89240E-12 260710 + 38 270630 Co-63 1.39710E-11 4.75680E-10 270630 + 39 270640 Co-64 8.30790E-11 1.10160E-09 270640 + 40 270650 Co-65 1.11230E-09 2.53830E-09 270650 + 41 270660 Co-66 2.71520E-09 5.49530E-09 270660 + 42 270670 Co-67 1.05460E-08 1.17000E-08 270670 + 43 270680 Co-68 6.40000E-09 9.27710E-09 270680 + 44 270681 Co-68m 4.77700E-09 5.75440E-09 270681 + 45 270690 Co-69 2.16720E-08 2.18290E-08 270690 + 46 270700 Co-70 3.43080E-09 3.43080E-09 270700 + 47 270701 Co-70m 3.43080E-09 3.46700E-09 270701 + 48 270710 Co-71 4.49420E-09 4.49610E-09 270710 + 49 270720 Co-72 6.44460E-10 6.44460E-10 270720 + 50 270730 Co-73 1.16110E-10 1.16110E-10 270730 + 51 270740 Co-74 2.67100E-12 2.67100E-12 270740 + 52 270750 Co-75 1.04530E-12 1.04530E-12 270750 + 53 280650 Ni-65 1.64160E-11 2.55470E-09 280650 + 54 280660 Ni-66 4.25930E-10 5.92120E-09 280660 + 55 280670 Ni-67 1.99470E-09 1.36950E-08 280670 + 56 280680 Ni-68 1.92420E-08 3.16150E-08 280680 + 57 280690 Ni-69 2.10260E-08 4.26370E-08 280690 + 58 280691 Ni-69m 2.10260E-08 2.10260E-08 280691 + 59 280700 Ni-70 1.28240E-07 1.35140E-07 280700 + 60 280710 Ni-71 1.09980E-07 1.14480E-07 280710 + 61 280720 Ni-72 1.80920E-07 1.81560E-07 280720 + 62 280730 Ni-73 4.94780E-08 4.95940E-08 280730 + 63 280740 Ni-74 1.45340E-08 1.45370E-08 280740 + 64 280750 Ni-75 5.38950E-09 5.39050E-09 280750 + 65 280760 Ni-76 4.13930E-10 4.13930E-10 280760 + 66 280770 Ni-77 1.14020E-11 1.14020E-11 280770 + 67 290670 Cu-67 3.34170E-11 1.37280E-08 290670 + 68 290680 Cu-68 1.19900E-10 3.20090E-08 290680 + 69 290681 Cu-68m 3.26820E-10 3.26820E-10 290681 + 70 290690 Cu-69 9.95610E-09 7.36190E-08 290690 + 71 290700 Cu-70 2.39430E-09 2.11210E-08 290700 + 72 290701 Cu-70m 3.05770E-08 3.74540E-08 290701 + 73 290702 Cu-70m 2.39430E-09 1.37530E-07 290702 + 74 290710 Cu-71 2.73270E-07 3.87750E-07 290710 + 75 290720 Cu-72 5.17130E-07 6.98690E-07 290720 + 76 290730 Cu-73 1.41650E-06 1.46610E-06 290730 + 77 290740 Cu-74 5.67130E-07 5.81750E-07 290740 + 78 290750 Cu-75 2.48930E-06 2.49460E-06 290750 + 79 290760 Cu-76 1.48270E-07 1.48480E-07 290760 + 80 290761 Cu-76m 1.48270E-07 1.48480E-07 290761 + 81 290770 Cu-77 1.12770E-07 1.12780E-07 290770 + 82 290780 Cu-78 1.05440E-08 1.05440E-08 290780 + 83 290790 Cu-79 1.31140E-09 1.31140E-09 290790 + 84 290800 Cu-80 2.35080E-11 2.35080E-11 290800 + 85 300690 Zn-69 5.20210E-12 7.36500E-08 300690 + 86 300691 Zn-69m 2.58370E-11 2.58370E-11 300691 + 87 300700 Zn-70 1.28300E-09 1.71790E-07 300700 + 88 300710 Zn-71 2.21500E-09 3.89960E-07 300710 + 89 300711 Zn-71m 1.10010E-08 1.10010E-08 300711 + 90 300720 Zn-72 2.44910E-07 9.43600E-07 300720 + 91 300730 Zn-73 6.68040E-08 1.92660E-06 300730 + 92 300731 Zn-73m 9.23980E-08 3.93700E-07 300731 + 93 300732 Zn-73m 6.02600E-07 6.02600E-07 300732 + 94 300740 Zn-74 3.09600E-06 3.76510E-06 300740 + 95 300750 Zn-75 2.64060E-05 2.88180E-05 300750 + 96 300760 Zn-76 2.56370E-05 2.59290E-05 300760 + 97 300770 Zn-77 1.92130E-05 2.06050E-05 300770 + 98 300771 Zn-77m 2.55810E-06 2.55810E-06 300771 + 99 300780 Zn-78 3.45930E-05 3.46040E-05 300780 + 100 300790 Zn-79 7.96360E-06 7.96420E-06 300790 + 101 300800 Zn-80 7.04370E-06 7.04370E-06 300800 + 102 300810 Zn-81 1.77240E-08 1.77240E-08 300810 + 103 300820 Zn-82 1.13300E-09 1.13300E-09 300820 + 104 310710 Ga-71 4.49420E-11 4.01010E-07 310710 + 105 310720 Ga-72 1.13580E-09 9.44850E-07 310720 + 106 310721 Ga-72m 1.11640E-10 3.15530E-08 310721 + 107 310730 Ga-73 4.36480E-08 2.27150E-06 310730 + 108 310740 Ga-74 1.01120E-07 3.00080E-06 310740 + 109 310741 Ga-74m 1.01120E-07 3.86620E-06 310741 + 110 310750 Ga-75 1.65010E-06 3.04680E-05 310750 + 111 310760 Ga-76 7.99460E-06 3.39240E-05 310760 + 112 310770 Ga-77 3.86320E-05 6.05160E-05 310770 + 113 310780 Ga-78 7.03030E-05 1.05010E-04 310780 + 114 310790 Ga-79 1.63500E-04 1.71360E-04 310790 + 115 310800 Ga-80 7.26590E-05 7.97040E-05 310800 + 116 310810 Ga-81 4.42590E-05 4.42750E-05 310810 + 117 310820 Ga-82 5.65720E-06 5.65830E-06 310820 + 118 310830 Ga-83 6.00900E-07 6.00900E-07 310830 + 119 310840 Ga-84 1.91760E-08 1.91760E-08 310840 + 120 310850 Ga-85 4.98120E-10 4.98120E-10 310850 + 121 320730 Ge-73 2.22580E-11 2.27160E-06 32073.82c + 122 320731 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340771 + 162 340780 Se-78 3.38960E-09 2.35130E-04 34078.82c + 163 340790 Se-79 1.39210E-06 5.55720E-04 34079.82c + 164 340791 Se-79m 1.85360E-07 5.41500E-04 340791 + 165 340800 Se-80 1.80600E-05 9.85720E-04 34080.82c + 166 340810 Se-81 1.38520E-05 1.59120E-03 340810 + 167 340811 Se-81m 1.04040E-04 1.56930E-04 340811 + 168 340820 Se-82 7.20540E-04 2.78600E-03 34082.82c + 169 340830 Se-83 2.61410E-03 3.55640E-03 340830 + 170 340831 Se-83m 5.26350E-04 2.20050E-03 340831 + 171 340840 Se-84 8.32930E-03 1.02490E-02 340840 + 172 340850 Se-85 9.62420E-03 1.05780E-02 340850 + 173 340860 Se-86 1.03040E-02 1.05760E-02 340860 + 174 340870 Se-87 5.91810E-03 6.02180E-03 340870 + 175 340880 Se-88 2.94550E-03 2.95970E-03 340880 + 176 340890 Se-89 8.29680E-04 8.31700E-04 340890 + 177 340900 Se-90 1.98510E-04 1.98510E-04 340900 + 178 340910 Se-91 1.35060E-05 1.35060E-05 340910 + 179 340920 Se-92 4.00140E-06 4.00140E-06 340920 + 180 350790 Br-79 4.64340E-12 3.03260E-07 35079.82c + 181 350791 Br-79m 1.75850E-11 1.75850E-11 350791 + 182 350800 Br-80 2.41130E-10 1.08130E-09 350800 + 183 350801 Br-80m 8.40170E-10 8.40170E-10 350801 + 184 350810 Br-81 1.01900E-07 1.59140E-03 35081.82c + 185 350820 Br-82 4.89240E-06 6.64420E-06 350820 + 186 350821 Br-82m 1.79490E-06 1.79490E-06 350821 + 187 350830 Br-83 6.90100E-05 5.82590E-03 350830 + 188 350840 Br-84 2.07510E-04 1.04570E-02 350840 + 189 350841 Br-84m 2.07510E-04 2.07510E-04 350841 + 190 350850 Br-85 2.49760E-03 1.30750E-02 350850 + 191 350860 Br-86 7.01010E-03 1.75860E-02 350860 + 192 350870 Br-87 1.27620E-02 1.88130E-02 350870 + 193 350880 Br-88 1.14750E-02 1.44700E-02 350880 + 194 350890 Br-89 9.14950E-03 9.91630E-03 350890 + 195 350900 Br-90 4.24150E-03 4.44280E-03 350900 + 196 350910 Br-91 1.91500E-03 1.92570E-03 350910 + 197 350920 Br-92 2.98470E-04 3.02470E-04 350920 + 198 350930 Br-93 6.31800E-05 6.31800E-05 350930 + 199 350940 Br-94 1.72750E-06 1.72750E-06 350940 + 200 350950 Br-95 9.60780E-09 9.60780E-09 350950 + 201 360820 Kr-82 5.66480E-10 6.68790E-06 36082.82c + 202 360830 Kr-83 1.90730E-06 5.82820E-03 36083.82c + 203 360831 Kr-83m 3.84020E-07 5.82110E-03 360831 + 204 360840 Kr-84 1.62890E-05 1.06810E-02 36084.82c + 205 360850 Kr-85 1.69800E-04 2.99200E-03 36085.82c + 206 360851 Kr-85m 3.41890E-05 1.30880E-02 360851 + 207 360860 Kr-86 2.08740E-03 2.01460E-02 36086.82c + 208 360870 Kr-87 7.03730E-03 2.63480E-02 360870 + 209 360880 Kr-88 2.16680E-02 3.65670E-02 360880 + 210 360890 Kr-89 3.26820E-02 4.22930E-02 360890 + 211 360900 Kr-90 3.95850E-02 4.33200E-02 360900 + 212 360910 Kr-91 2.86250E-02 3.02660E-02 360910 + 213 360920 Kr-92 1.71920E-02 1.74370E-02 360920 + 214 360930 Kr-93 5.72940E-03 5.75080E-03 360930 + 215 360940 Kr-94 1.75680E-03 1.75730E-03 360940 + 216 360950 Kr-95 2.85060E-04 2.85070E-04 360950 + 217 360960 Kr-96 3.87950E-05 3.87950E-05 360960 + 218 360970 Kr-97 2.69230E-06 2.69230E-06 360970 + 219 360980 Kr-98 8.79630E-07 8.79630E-07 360980 + 220 370850 Rb-85 1.49440E-08 1.32790E-02 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280 391030 Y-103 7.75810E-05 7.75820E-05 391030 + 281 391040 Y-104 9.47620E-06 9.47620E-06 391040 + 282 391050 Y-105 4.34710E-09 4.34710E-09 391050 + 283 400920 Zr-92 2.00110E-06 5.90040E-02 40092.82c + 284 400930 Zr-93 2.73840E-05 6.05620E-02 40093.82c + 285 400940 Zr-94 2.20240E-04 6.24640E-02 40094.82c + 286 400950 Zr-95 9.73090E-04 6.45890E-02 40095.82c + 287 400960 Zr-96 5.06040E-03 6.31760E-02 40096.82c + 288 400970 Zr-97 1.20680E-02 6.03010E-02 400970 + 289 400980 Zr-98 2.91490E-02 6.02920E-02 400980 + 290 400990 Zr-99 3.54810E-02 5.51520E-02 400990 + 291 401000 Zr-100 4.64300E-02 5.48820E-02 401000 + 292 401010 Zr-101 2.88830E-02 3.20000E-02 401010 + 293 401020 Zr-102 1.65530E-02 1.70800E-02 401020 + 294 401030 Zr-103 4.49600E-03 4.56820E-03 401030 + 295 401040 Zr-104 1.11560E-03 1.12430E-03 401040 + 296 401050 Zr-105 1.14330E-04 1.14330E-04 401050 + 297 401060 Zr-106 8.69720E-06 8.69720E-06 401060 + 298 401070 Zr-107 3.60850E-09 3.60850E-09 401070 + 299 401080 Zr-108 3.59330E-11 3.59330E-11 401080 + 300 410950 Nb-95 2.29390E-06 6.45530E-02 41095.82c + 301 410951 Nb-95m 4.61870E-07 6.98250E-04 410951 + 302 410960 Nb-96 1.80480E-05 1.80480E-05 410960 + 303 410970 Nb-97 1.47870E-04 6.04790E-02 410970 + 304 410971 Nb-97m 2.97720E-05 5.73450E-02 410971 + 305 410980 Nb-98 1.70650E-04 6.04630E-02 410980 + 306 410981 Nb-98m 5.94590E-04 5.94590E-04 410981 + 307 410990 Nb-99 3.04020E-03 3.83140E-02 410990 + 308 410991 Nb-99m 6.12130E-04 2.09080E-02 410991 + 309 411000 Nb-100 1.43780E-03 5.63200E-02 411000 + 310 411001 Nb-100m 6.97020E-03 6.97020E-03 411001 + 311 411010 Nb-101 1.74600E-02 4.94600E-02 411010 + 312 411020 Nb-102 9.39950E-03 2.64800E-02 411020 + 313 411021 Nb-102m 9.39950E-03 9.39950E-03 411021 + 314 411030 Nb-103 1.70990E-02 2.16670E-02 411030 + 315 411040 Nb-104 3.59620E-03 4.72200E-03 411040 + 316 411041 Nb-104m 3.59620E-03 3.59620E-03 411041 + 317 411050 Nb-105 3.16540E-03 3.27830E-03 411050 + 318 411060 Nb-106 4.37380E-04 4.45950E-04 411060 + 319 411070 Nb-107 9.00330E-05 9.00360E-05 411070 + 320 411080 Nb-108 2.99290E-06 2.99290E-06 411080 + 321 411090 Nb-109 9.23150E-09 9.23150E-09 411090 + 322 411100 Nb-110 9.82570E-11 9.82570E-11 411100 + 323 420970 Mo-97 2.69230E-06 6.04810E-02 42097.82c + 324 420980 Mo-98 2.28660E-05 6.10800E-02 42098.82c + 325 420990 Mo-99 1.52490E-04 5.89570E-02 42099.82c + 326 421000 Mo-100 1.04060E-03 6.43310E-02 42100.82c + 327 421010 Mo-101 2.96600E-03 5.24260E-02 421010 + 328 421020 Mo-102 8.50730E-03 4.43870E-02 421020 + 329 421030 Mo-103 1.07270E-02 3.23990E-02 421030 + 330 421040 Mo-104 1.21760E-02 2.05450E-02 421040 + 331 421050 Mo-105 7.86450E-03 1.11070E-02 421050 + 332 421060 Mo-106 3.08340E-03 3.51470E-03 421060 + 333 421070 Mo-107 7.95120E-04 8.79940E-04 421070 + 334 421080 Mo-108 2.60230E-04 2.63040E-04 421080 + 335 421090 Mo-109 3.67700E-05 3.67780E-05 421090 + 336 421100 Mo-110 6.09900E-06 6.09910E-06 421100 + 337 421110 Mo-111 2.84260E-08 2.84260E-08 421110 + 338 421120 Mo-112 1.23540E-09 1.23540E-09 421120 + 339 421130 Mo-113 1.63480E-11 1.63480E-11 421130 + 340 431000 Tc-100 4.10120E-06 4.10120E-06 431000 + 341 431010 Tc-101 1.52360E-05 5.24410E-02 431010 + 342 431020 Tc-102 4.34220E-05 4.44300E-02 431020 + 343 431021 Tc-102m 4.34220E-05 4.34220E-05 431021 + 344 431030 Tc-103 4.04040E-04 3.28030E-02 431030 + 345 431040 Tc-104 8.30520E-04 2.13760E-02 431040 + 346 431050 Tc-105 1.60960E-03 1.27170E-02 431050 + 347 431060 Tc-106 9.88030E-04 4.50270E-03 431060 + 348 431070 Tc-107 8.78370E-04 1.75830E-03 431070 + 349 431080 Tc-108 4.38130E-04 7.01360E-04 431080 + 350 431090 Tc-109 2.06790E-04 2.43370E-04 431090 + 351 431100 Tc-110 8.29200E-05 8.90190E-05 431100 + 352 431110 Tc-111 5.84230E-05 5.84510E-05 431110 + 353 431120 Tc-112 1.29780E-05 1.29790E-05 431120 + 354 431130 Tc-113 2.50320E-06 2.50320E-06 431130 + 355 431140 Tc-114 4.45600E-09 4.45600E-09 431140 + 356 431150 Tc-115 2.09810E-10 2.09810E-10 431150 + 357 441020 Ru-102 2.38120E-06 4.44760E-02 44102.82c + 358 441030 Ru-103 1.59660E-06 3.28090E-02 44103.82c + 359 441031 Ru-103m 4.46720E-06 4.46720E-06 441031 + 360 441040 Ru-104 2.73320E-05 2.14030E-02 44104.82c + 361 441050 Ru-105 9.40670E-05 1.28110E-02 44105.82c + 362 441060 Ru-106 1.56980E-04 4.65970E-03 44106.82c + 363 441070 Ru-107 1.63400E-04 1.92170E-03 441070 + 364 441080 Ru-108 1.88820E-04 8.90380E-04 441080 + 365 441090 Ru-109 1.73920E-04 4.17130E-04 441090 + 366 441100 Ru-110 2.31900E-04 3.20880E-04 441100 + 367 441110 Ru-111 1.93500E-04 2.52150E-04 441110 + 368 441120 Ru-112 1.61570E-04 1.74530E-04 441120 + 369 441130 Ru-113 4.19130E-05 6.51920E-05 441130 + 370 441131 Ru-113m 4.19130E-05 4.19130E-05 441131 + 371 441140 Ru-114 4.75600E-05 4.75640E-05 441140 + 372 441150 Ru-115 1.19980E-05 1.19980E-05 441150 + 373 441160 Ru-116 1.99210E-06 1.99210E-06 441160 + 374 441170 Ru-117 1.55910E-09 1.55910E-09 441170 + 375 441180 Ru-118 4.76070E-11 4.76070E-11 441180 + 376 441190 Ru-119 1.33150E-07 1.33150E-07 441190 + 377 441200 Ru-120 1.13790E-08 1.13790E-08 441200 + 378 451050 Rh-105 2.55750E-09 1.28110E-02 45105.82c + 379 451051 Rh-105m 3.40510E-10 3.63670E-03 451051 + 380 451060 Rh-106 7.61750E-09 4.65970E-03 451060 + 381 451061 Rh-106m 2.07630E-08 2.07630E-08 451061 + 382 451070 Rh-107 1.23360E-06 1.92290E-03 451070 + 383 451080 Rh-108 3.33670E-07 8.90710E-04 451080 + 384 451081 Rh-108m 1.16260E-06 1.16260E-06 451081 + 385 451090 Rh-109 1.05100E-05 4.27640E-04 451090 + 386 451100 Rh-110 2.17940E-05 3.42680E-04 451100 + 387 451101 Rh-110m 5.13060E-07 5.13060E-07 451101 + 388 451110 Rh-111 7.74090E-05 3.29550E-04 451110 + 389 451120 Rh-112 3.86370E-05 2.13170E-04 451120 + 390 451121 Rh-112m 3.86370E-05 3.86370E-05 451121 + 391 451130 Rh-113 1.82590E-04 2.68740E-04 451130 + 392 451140 Rh-114 5.66950E-05 1.04290E-04 451140 + 393 451141 Rh-114m 5.66950E-05 5.66950E-05 451141 + 394 451150 Rh-115 9.49550E-05 1.06950E-04 451150 + 395 451160 Rh-116 1.02250E-05 1.21960E-05 451160 + 396 451161 Rh-116m 2.78720E-05 2.78720E-05 451161 + 397 451170 Rh-117 3.31040E-05 3.31050E-05 451170 + 398 451180 Rh-118 1.00910E-05 1.00970E-05 451180 + 399 451190 Rh-119 4.07990E-05 4.09260E-05 451190 + 400 451200 Rh-120 5.37150E-06 5.38290E-06 451200 + 401 451210 Rh-121 8.53040E-07 8.53040E-07 451210 + 402 451220 Rh-122 2.61310E-08 2.61310E-08 451220 + 403 461070 Pd-107 1.44660E-11 1.92290E-03 46107.82c + 404 461071 Pd-107m 3.17960E-11 3.17960E-11 461071 + 405 461080 Pd-108 1.22180E-09 8.91880E-04 46108.82c + 406 461090 Pd-109 4.06700E-09 4.27660E-04 461090 + 407 461091 Pd-109m 8.93900E-09 2.13830E-04 461091 + 408 461100 Pd-110 3.58800E-07 3.43550E-04 46110.82c + 409 461110 Pd-111 2.03130E-06 3.34490E-04 461110 + 410 461111 Pd-111m 4.46480E-06 5.78300E-06 461111 + 411 461120 Pd-112 1.47750E-05 2.66580E-04 461120 + 412 461130 Pd-113 1.94920E-05 3.42770E-04 461130 + 413 461131 Pd-113m 5.45360E-05 5.45360E-05 461131 + 414 461140 Pd-114 7.83890E-05 2.39370E-04 461140 + 415 461150 Pd-115 4.54600E-05 1.46110E-04 461150 + 416 461151 Pd-115m 9.99200E-05 1.15450E-04 461151 + 417 461160 Pd-116 2.67210E-04 3.07280E-04 461160 + 418 461170 Pd-117 7.02700E-05 2.58120E-04 461170 + 419 461171 Pd-117m 1.54450E-04 1.54450E-04 461171 + 420 461180 Pd-118 1.81610E-04 1.91410E-04 461180 + 421 461190 Pd-119 3.96270E-05 8.08730E-05 461190 + 422 461200 Pd-120 2.36500E-05 2.88290E-05 461200 + 423 461210 Pd-121 9.32300E-06 1.00600E-05 461210 + 424 461220 Pd-122 1.85870E-05 1.86130E-05 461220 + 425 461230 Pd-123 1.72910E-06 1.72910E-06 461230 + 426 461240 Pd-124 3.40720E-07 3.40720E-07 461240 + 427 471100 Ag-110 8.11450E-12 8.41530E-12 471100 + 428 471101 Ag-110m 2.21190E-11 2.21190E-11 47510.82c + 429 471110 Ag-111 2.72060E-10 3.34390E-04 47111.82c + 430 471111 Ag-111m 2.04330E-09 3.33250E-04 471111 + 431 471120 Ag-112 3.11380E-08 2.66610E-04 471120 + 432 471130 Ag-113 1.25320E-07 2.25330E-04 471130 + 433 471131 Ag-113m 9.41270E-07 3.29170E-04 471131 + 434 471140 Ag-114 5.92570E-07 2.42840E-04 471140 + 435 471141 Ag-114m 2.87270E-06 2.87270E-06 471141 + 436 471150 Ag-115 1.59990E-06 1.41380E-04 471150 + 437 471151 Ag-115m 1.20160E-05 1.57680E-04 471151 + 438 471160 Ag-116 1.27120E-05 3.22070E-04 471160 + 439 471161 Ag-116m 3.46490E-05 3.46490E-05 471161 + 440 471170 Ag-117 1.26750E-05 1.55190E-04 471170 + 441 471171 Ag-117m 9.51950E-05 2.24260E-04 471171 + 442 471180 Ag-118 2.31070E-05 2.44300E-04 471180 + 443 471181 Ag-118m 1.12020E-04 1.39390E-04 471181 + 444 471190 Ag-119 1.92610E-05 5.96970E-05 471190 + 445 471191 Ag-119m 1.44660E-04 1.85100E-04 471191 + 446 471200 Ag-120 5.59650E-05 1.10370E-04 471200 + 447 471201 Ag-120m 9.35950E-05 1.08010E-04 471201 + 448 471210 Ag-121 7.73630E-05 8.73960E-05 471210 + 449 471220 Ag-122 1.03510E-05 2.89640E-05 471220 + 450 471221 Ag-122m 1.11590E-05 1.11590E-05 471221 + 451 471230 Ag-123 1.93310E-05 2.10600E-05 471230 + 452 471240 Ag-124 3.56090E-06 5.82120E-06 471240 + 453 471241 Ag-124m 3.83920E-06 3.83920E-06 471241 + 454 471250 Ag-125 7.69160E-06 7.69160E-06 471250 + 455 471260 Ag-126 1.91120E-06 1.91120E-06 471260 + 456 471270 Ag-127 6.03020E-07 6.03020E-07 471270 + 457 471280 Ag-128 2.04050E-08 2.04050E-08 471280 + 458 471290 Ag-129 1.29410E-09 1.29410E-09 471290 + 459 481130 Cd-113 3.92730E-11 3.39940E-04 48113.82c + 460 481131 Cd-113m 1.48730E-10 3.89590E-06 481131 + 461 481140 Cd-114 8.76150E-09 2.42840E-04 48114.82c + 462 481150 Cd-115 3.56510E-07 2.54530E-04 481150 + 463 481151 Cd-115m 1.35010E-06 1.31230E-05 48515.82c + 464 481160 Cd-116 3.37310E-06 3.58010E-04 48116.82c + 465 481170 Cd-117 3.69000E-06 2.91190E-04 481170 + 466 481171 Cd-117m 1.39740E-05 9.24630E-05 481171 + 467 481180 Cd-118 6.96060E-05 3.96150E-04 481180 + 468 481190 Cd-119 2.33090E-05 2.38250E-04 481190 + 469 481191 Cd-119m 6.52170E-05 9.50670E-05 481191 + 470 481200 Cd-120 1.57320E-04 3.35730E-04 481200 + 471 481210 Cd-121 4.83180E-05 1.26580E-04 481210 + 472 481211 Cd-121m 1.35190E-04 1.44320E-04 481211 + 473 481220 Cd-122 1.92860E-04 2.32980E-04 481220 + 474 481230 Cd-123 3.39710E-05 5.12050E-05 481230 + 475 481231 Cd-123m 9.50490E-05 9.88810E-05 481231 + 476 481240 Cd-124 1.51070E-04 1.58810E-04 481240 + 477 481250 Cd-125 6.22490E-05 6.60950E-05 481250 + 478 481251 Cd-125m 1.74170E-04 1.78020E-04 481251 + 479 481260 Cd-126 2.46330E-04 2.48240E-04 481260 + 480 481270 Cd-127 2.21250E-04 2.21850E-04 481270 + 481 481280 Cd-128 8.89760E-05 8.89960E-05 481280 + 482 481290 Cd-129 6.52720E-06 6.52780E-06 481290 + 483 481291 Cd-129m 1.82630E-05 1.82630E-05 481291 + 484 481300 Cd-130 3.35240E-06 3.35240E-06 481300 + 485 481310 Cd-131 2.35320E-08 2.35320E-08 481310 + 486 491150 In-115 1.66320E-11 2.54920E-04 49115.82c + 487 491151 In-115m 3.34880E-12 2.54530E-04 491151 + 488 491160 In-116 2.21960E-10 2.21960E-10 491160 + 489 491161 In-116m 3.58430E-10 7.73390E-10 491161 + 490 491162 In-116m 4.14970E-10 4.14970E-10 491162 + 491 491170 In-117 4.55860E-08 2.41790E-04 491170 + 492 491171 In-117m 9.17860E-09 2.68270E-04 491171 + 493 491180 In-118 1.25410E-07 3.96270E-04 491180 + 494 491181 In-118m 2.02520E-07 4.33700E-07 491181 + 495 491182 In-118m 2.34470E-07 2.34470E-07 491182 + 496 491190 In-119 5.46660E-06 1.35610E-04 491190 + 497 491191 In-119m 1.10070E-06 2.16400E-04 491191 + 498 491200 In-120 5.48840E-06 3.41220E-04 491200 + 499 491201 In-120m 5.48840E-06 5.48840E-06 491201 + 500 491202 In-120m 5.48840E-06 5.48840E-06 491202 + 501 491210 In-121 2.51860E-05 2.13210E-04 491210 + 502 491211 In-121m 5.07110E-06 8.90210E-05 491211 + 503 491220 In-122 1.52890E-05 2.48270E-04 491220 + 504 491221 In-122m 1.27840E-05 1.27840E-05 491221 + 505 491222 In-122m 1.27840E-05 1.27840E-05 491222 + 506 491230 In-123 8.87500E-05 2.02290E-04 491230 + 507 491231 In-123m 1.78690E-05 5.44200E-05 491231 + 508 491240 In-124 6.80220E-05 2.26830E-04 491240 + 509 491241 In-124m 7.33380E-05 7.33380E-05 491241 + 510 491250 In-125 2.54650E-04 4.64300E-04 491250 + 511 491251 In-125m 5.12720E-05 8.57320E-05 491251 + 512 491260 In-126 2.11980E-04 4.60220E-04 491260 + 513 491261 In-126m 2.28540E-04 2.28540E-04 491261 + 514 491270 In-127 1.08580E-03 1.08580E-03 491270 + 515 491271 In-127m 2.18620E-04 4.40470E-04 491271 + 516 491280 In-128 3.83180E-04 6.22210E-04 491280 + 517 491281 In-128m 1.50040E-04 2.39030E-04 491281 + 518 491282 In-128m 5.74880E-04 5.74880E-04 491282 + 519 491290 In-129 1.01650E-03 1.03480E-03 491290 + 520 491291 In-129m 2.04670E-04 2.11260E-04 491291 + 521 491300 In-130 1.43310E-04 1.46540E-04 491300 + 522 491301 In-130m 2.08660E-04 2.08660E-04 491301 + 523 491302 In-130m 2.90660E-04 2.90660E-04 491302 + 524 491310 In-131 7.99020E-05 8.07380E-05 491310 + 525 491311 In-131m 7.99020E-05 7.99020E-05 491311 + 526 491312 In-131m 7.99020E-05 7.99020E-05 491312 + 527 491320 In-132 1.08720E-05 1.08720E-05 491320 + 528 491330 In-133 1.92300E-06 2.31020E-06 491330 + 529 491331 In-133m 3.87190E-07 3.87190E-07 491331 + 530 491340 In-134 6.83220E-09 6.83220E-09 491340 + 531 501180 Sn-118 2.38030E-10 3.96710E-04 50118.82c + 532 501210 Sn-121 3.79310E-12 2.95750E-04 501210 + 533 501211 Sn-121m 1.06130E-11 2.41530E-05 501211 + 534 501220 Sn-122 2.14500E-06 2.75990E-04 50122.82c + 535 501230 Sn-123 1.60020E-05 3.14240E-05 50123.82c + 536 501231 Sn-123m 5.71910E-06 2.47000E-04 501231 + 537 501240 Sn-124 9.15570E-05 3.91720E-04 50124.82c + 538 501250 Sn-125 9.67430E-05 1.75170E-04 50125.82c + 539 501251 Sn-125m 3.45770E-05 5.06180E-04 501251 + 540 501260 Sn-126 3.07940E-04 9.99740E-04 50126.82c + 541 501270 Sn-127 1.08900E-03 1.51220E-03 501270 + 542 501271 Sn-127m 3.89210E-04 1.48920E-03 501271 + 543 501280 Sn-128 9.94130E-04 4.90100E-03 501280 + 544 501281 Sn-128m 2.70980E-03 3.28470E-03 501281 + 545 501290 Sn-129 2.22180E-03 3.35790E-03 501290 + 546 501291 Sn-129m 6.21660E-03 6.32670E-03 501291 + 547 501300 Sn-130 3.64840E-03 4.04400E-03 501300 + 548 501301 Sn-130m 9.94460E-03 1.01970E-02 501301 + 549 501310 Sn-131 3.15620E-03 3.31100E-03 501310 + 550 501311 Sn-131m 8.83080E-03 8.91420E-03 501311 + 551 501320 Sn-132 6.81810E-03 6.83090E-03 501320 + 552 501330 Sn-133 9.40480E-04 9.40830E-04 501330 + 553 501340 Sn-134 1.12860E-04 1.12860E-04 501340 + 554 501350 Sn-135 1.35680E-05 1.35680E-05 501350 + 555 501360 Sn-136 8.41580E-07 8.41580E-07 501360 + 556 501370 Sn-137 1.43190E-09 1.43190E-09 501370 + 557 511240 Sb-124 7.95640E-07 2.04770E-06 51124.82c + 558 511241 Sb-124m 6.41830E-07 1.66940E-06 511241 + 559 511242 Sb-124m 1.02760E-06 1.02760E-06 511242 + 560 511250 Sb-125 7.68720E-06 6.89040E-04 51125.82c + 561 511260 Sb-126 4.45540E-06 5.32800E-06 51126.82c + 562 511261 Sb-126m 2.78290E-06 6.23270E-06 511261 + 563 511262 Sb-126m 3.44980E-06 3.44980E-06 511262 + 564 511270 Sb-127 5.46290E-05 3.05600E-03 511270 + 565 511280 Sb-128 1.02290E-04 5.00840E-03 511280 + 566 511281 Sb-128m 1.43060E-04 1.43060E-04 511281 + 567 511290 Sb-129 1.05140E-03 8.16380E-03 511290 + 568 511291 Sb-129m 7.78090E-04 3.94140E-03 511291 + 569 511300 Sb-130 3.20000E-03 1.23420E-02 511300 + 570 511301 Sb-130m 3.20000E-03 8.29820E-03 511301 + 571 511310 Sb-131 1.65610E-02 2.87860E-02 511310 + 572 511320 Sb-132 1.18650E-02 1.86960E-02 511320 + 573 511321 Sb-132m 1.05040E-02 1.05040E-02 511321 + 574 511330 Sb-133 2.22080E-02 2.31680E-02 511330 + 575 511340 Sb-134 1.59550E-03 1.69060E-03 511340 + 576 511341 Sb-134m 4.34910E-03 4.35050E-03 511341 + 577 511350 Sb-135 1.38400E-03 1.39500E-03 511350 + 578 511360 Sb-136 2.23960E-04 2.24550E-04 511360 + 579 511370 Sb-137 2.77630E-05 2.77640E-05 511370 + 580 511380 Sb-138 3.79580E-07 3.79580E-07 511380 + 581 511390 Sb-139 1.19390E-08 1.19390E-08 511390 + 582 521260 Te-126 8.05300E-11 1.06880E-05 52126.82c + 583 521270 Te-127 2.18760E-09 3.04400E-03 521270 + 584 521271 Te-127m 6.12070E-09 5.03630E-04 52527.82c + 585 521280 Te-128 8.98390E-06 5.15530E-03 52128.82c + 586 521290 Te-129 3.40550E-05 9.89630E-03 521290 + 587 521291 Te-129m 9.52850E-05 4.72180E-03 52529.82c + 588 521300 Te-130 9.40230E-04 2.15810E-02 52130.82c + 589 521310 Te-131 1.35480E-03 2.91160E-02 521310 + 590 521311 Te-131m 3.79080E-03 6.09540E-03 521311 + 591 521320 Te-132 1.78930E-02 4.70930E-02 52132.82c + 592 521330 Te-133 1.08500E-02 3.60290E-02 521330 + 593 521331 Te-133m 3.03580E-02 3.43650E-02 521331 + 594 521340 Te-134 6.20020E-02 6.82590E-02 521340 + 595 521350 Te-135 3.28690E-02 3.40820E-02 521350 + 596 521360 Te-136 1.48990E-02 1.51000E-02 521360 + 597 521370 Te-137 4.33730E-03 4.35150E-03 521370 + 598 521380 Te-138 9.90910E-04 9.91290E-04 521380 + 599 521390 Te-139 1.35220E-04 1.35230E-04 521390 + 600 521400 Te-140 2.16700E-05 2.16700E-05 521400 + 601 521410 Te-141 2.18650E-06 2.18650E-06 521410 + 602 521420 Te-142 2.27900E-09 2.27900E-09 521420 + 603 531290 I-129 6.47000E-09 1.16430E-02 53129.82c + 604 531300 I-130 3.27120E-06 4.27930E-06 53130.82c + 605 531301 I-130m 1.20010E-06 1.20010E-06 531301 + 606 531310 I-131 3.18460E-05 3.39640E-02 53131.82c + 607 531320 I-132 1.82500E-04 4.74140E-02 531320 + 608 531321 I-132m 1.61590E-04 1.61590E-04 531321 + 609 531330 I-133 1.22010E-03 6.65030E-02 531330 + 610 531331 I-133m 9.02910E-04 9.02910E-04 531331 + 611 531340 I-134 4.33320E-03 7.63400E-02 531340 + 612 531341 I-134m 3.83640E-03 3.83640E-03 531341 + 613 531350 I-135 2.65250E-02 6.06070E-02 53135.82c + 614 531360 I-136 7.95320E-03 2.31180E-02 531360 + 615 531361 I-136m 2.16790E-02 2.17440E-02 531361 + 616 531370 I-137 2.60700E-02 3.03540E-02 531370 + 617 531380 I-138 1.18560E-02 1.27850E-02 531380 + 618 531390 I-139 7.35820E-03 7.49340E-03 531390 + 619 531400 I-140 1.89560E-03 1.91730E-03 531400 + 620 531410 I-141 4.49280E-04 4.51470E-04 531410 + 621 531420 I-142 4.41200E-05 4.41220E-05 531420 + 622 531430 I-143 5.23470E-06 5.23470E-06 531430 + 623 531440 I-144 6.98660E-09 6.98660E-09 531440 + 624 541310 Xe-131 4.27310E-10 3.39640E-02 54131.82c + 625 541311 Xe-131m 1.19560E-09 3.68910E-04 541311 + 626 541320 Xe-132 1.03250E-06 4.74390E-02 54132.82c + 627 541321 Xe-132m 1.38330E-06 1.38330E-06 541321 + 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Cs-134m 9.62490E-09 9.62490E-09 551341 + 648 551350 Cs-135 5.19750E-07 6.31640E-02 55135.82c + 649 551351 Cs-135m 3.84640E-07 3.84640E-07 551351 + 650 551360 Cs-136 2.50270E-05 3.39730E-05 55136.82c + 651 551361 Cs-136m 1.78930E-05 1.78930E-05 551361 + 652 551370 Cs-137 8.32950E-04 5.85720E-02 55137.82c + 653 551380 Cs-138 1.29270E-03 6.40200E-02 551380 + 654 551381 Cs-138m 2.16180E-03 2.16180E-03 551381 + 655 551390 Cs-139 1.20250E-02 6.18520E-02 551390 + 656 551400 Cs-140 1.68930E-02 5.56740E-02 551400 + 657 551410 Cs-141 2.90800E-02 4.89370E-02 551410 + 658 551420 Cs-142 2.25270E-02 2.91370E-02 551420 + 659 551430 Cs-143 1.45100E-02 1.60860E-02 551430 + 660 551440 Cs-144 3.18730E-03 5.05710E-03 551440 + 661 551441 Cs-144m 3.18730E-03 3.18800E-03 551441 + 662 551450 Cs-145 1.93930E-03 1.96410E-03 551450 + 663 551460 Cs-146 3.22430E-04 3.28550E-04 551460 + 664 551470 Cs-147 6.25570E-05 6.25570E-05 551470 + 665 551480 Cs-148 1.38520E-07 1.38520E-07 551480 + 666 551490 Cs-149 3.22710E-09 3.22710E-09 551490 + 667 561360 Ba-136 6.49070E-10 4.29220E-05 56136.82c + 668 561361 Ba-136m 1.76920E-09 1.76920E-09 561361 + 669 561370 Ba-137 8.86060E-07 5.85760E-02 56137.82c + 670 561371 Ba-137m 2.47910E-06 5.52950E-02 561371 + 671 561380 Ba-138 1.40180E-04 6.45710E-02 56138.82c + 672 561390 Ba-139 9.49980E-04 6.28020E-02 561390 + 673 561400 Ba-140 4.91200E-03 6.05860E-02 56140.82c + 674 561410 Ba-141 1.00590E-02 5.89960E-02 561410 + 675 561420 Ba-142 2.77160E-02 5.71160E-02 561420 + 676 561430 Ba-143 3.73250E-02 5.33090E-02 561430 + 677 561440 Ba-144 3.89210E-02 4.56910E-02 561440 + 678 561450 Ba-145 2.19760E-02 2.37060E-02 561450 + 679 561460 Ba-146 1.03830E-02 1.06830E-02 561460 + 680 561470 Ba-147 3.55340E-03 3.59820E-03 561470 + 681 561480 Ba-148 8.66140E-04 8.66240E-04 561480 + 682 561490 Ba-149 9.97720E-05 9.97750E-05 561490 + 683 561500 Ba-150 8.30910E-06 8.30910E-06 561500 + 684 561510 Ba-151 6.95140E-09 6.95140E-09 561510 + 685 561520 Ba-152 1.23470E-10 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5.51100E-05 1.66850E-02 591480 + 725 591481 Pr-148m 2.67170E-04 2.67170E-04 591481 + 726 591490 Pr-149 9.83210E-04 1.07240E-02 591490 + 727 591500 Pr-150 1.48560E-03 6.64510E-03 591500 + 728 591510 Pr-151 1.82040E-03 3.92350E-03 591510 + 729 591520 Pr-152 1.50490E-03 2.14330E-03 591520 + 730 591530 Pr-153 5.60710E-04 6.57640E-04 591530 + 731 591540 Pr-154 2.25720E-04 2.40430E-04 591540 + 732 591550 Pr-155 2.04030E-05 2.04180E-05 591550 + 733 591560 Pr-156 1.12060E-05 1.12070E-05 591560 + 734 591570 Pr-157 9.90880E-09 9.90880E-09 591570 + 735 591580 Pr-158 2.34990E-10 2.34990E-10 591580 + 736 591590 Pr-159 1.21090E-11 1.21090E-11 591590 + 737 601460 Nd-146 1.19880E-09 2.88750E-02 60146.82c + 738 601470 Nd-147 2.71550E-08 2.18340E-02 60147.82c + 739 601480 Nd-148 9.96600E-06 1.69620E-02 60148.82c + 740 601490 Nd-149 4.45900E-05 1.07690E-02 601490 + 741 601500 Nd-150 2.02040E-04 6.84720E-03 60150.82c + 742 601510 Nd-151 4.56310E-04 4.37990E-03 601510 + 743 601520 Nd-152 9.69200E-04 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1.67500E-06 1.68770E-06 621610 + 783 621620 Sm-162 1.94560E-07 1.95070E-07 621620 + 784 621630 Sm-163 8.87480E-09 8.88960E-09 621630 + 785 621640 Sm-164 6.05190E-10 6.05190E-10 621640 + 786 621650 Sm-165 1.07220E-11 1.07220E-11 621650 + 787 631540 Eu-154 5.56890E-11 1.15730E-10 63154.82c + 788 631541 Eu-154m 6.00410E-11 6.00410E-11 631541 + 789 631550 Eu-155 2.20810E-09 2.78930E-04 63155.82c + 790 631560 Eu-156 2.83630E-08 1.81480E-04 63156.82c + 791 631570 Eu-157 8.00970E-08 1.91900E-05 63157.82c + 792 631580 Eu-158 3.92900E-07 1.95890E-05 631580 + 793 631590 Eu-159 4.42640E-06 3.15490E-05 631590 + 794 631600 Eu-160 1.13960E-06 5.47250E-06 631600 + 795 631610 Eu-161 1.30680E-06 2.99450E-06 631610 + 796 631620 Eu-162 7.28120E-07 9.23190E-07 631620 + 797 631630 Eu-163 3.44220E-07 3.53110E-07 631630 + 798 631640 Eu-164 3.31060E-08 3.37110E-08 631640 + 799 631650 Eu-165 7.15470E-09 7.16540E-09 631650 + 800 631660 Eu-166 2.65250E-10 2.65250E-10 631660 + 801 631670 Eu-167 1.35250E-11 1.35250E-11 631670 + 802 641570 Gd-157 1.64820E-11 1.91900E-05 64157.82c + 803 641580 Gd-158 1.04190E-09 1.95890E-05 64158.82c + 804 641590 Gd-159 1.81070E-08 3.15670E-05 641590 + 805 641600 Gd-160 5.42470E-08 5.52680E-06 64160.82c + 806 641610 Gd-161 8.25250E-08 3.07700E-06 641610 + 807 641620 Gd-162 4.47860E-07 1.37100E-06 641620 + 808 641630 Gd-163 2.41390E-07 5.94500E-07 641630 + 809 641640 Gd-164 2.14260E-07 2.47970E-07 641640 + 810 641650 Gd-165 5.68030E-08 6.39680E-08 641650 + 811 641660 Gd-166 2.28210E-08 2.30860E-08 641660 + 812 641670 Gd-167 1.70330E-09 1.71680E-09 641670 + 813 641680 Gd-168 2.51750E-10 2.51750E-10 641680 + 814 641690 Gd-169 7.80470E-12 7.80470E-12 641690 + 815 651590 Tb-159 4.03620E-12 3.15670E-05 65159.82c + 816 651600 Tb-160 1.96750E-11 1.96750E-11 65160.82c + 817 651610 Tb-161 3.81680E-10 3.07740E-06 651610 + 818 651620 Tb-162 3.10890E-09 1.37420E-06 651620 + 819 651630 Tb-163 1.87670E-08 6.13270E-07 651630 + 820 651640 Tb-164 2.11320E-08 2.69100E-07 651640 + 821 651650 Tb-165 5.27020E-08 1.16670E-07 651650 + 822 651660 Tb-166 2.39880E-08 4.70740E-08 651660 + 823 651670 Tb-167 1.69600E-08 1.86770E-08 651670 + 824 651680 Tb-168 3.21190E-09 3.46370E-09 651680 + 825 651690 Tb-169 1.12550E-09 1.13330E-09 651690 + 826 651700 Tb-170 6.29400E-11 6.29400E-11 651700 + 827 651710 Tb-171 6.97520E-12 6.97520E-12 651710 + 828 661620 Dy-162 1.64440E-12 1.37420E-06 66162.82c + 829 661630 Dy-163 1.62210E-11 6.13280E-07 66163.82c + 830 661640 Dy-164 2.27400E-10 2.69330E-07 66164.82c + 831 661650 Dy-165 7.26860E-10 1.17490E-07 661650 + 832 661651 Dy-165m 9.67780E-11 9.67780E-11 661651 + 833 661660 Dy-166 4.02280E-09 5.10970E-08 661660 + 834 661670 Dy-167 3.45750E-09 2.21340E-08 661670 + 835 661680 Dy-168 6.01830E-09 9.48200E-09 661680 + 836 661690 Dy-169 2.41300E-09 3.54630E-09 661690 + 837 661700 Dy-170 1.32640E-09 1.38930E-09 661700 + 838 661710 Dy-171 1.96970E-10 2.03950E-10 661710 + 839 661720 Dy-172 5.60600E-11 5.60600E-11 661720 + 840 661730 Dy-173 2.59090E-12 2.59090E-12 661730 + 841 671660 Ho-166 1.63070E-12 5.10990E-08 671660 + 842 671661 Ho-166m 4.44500E-12 4.44500E-12 671661 + 843 671670 Ho-167 6.32890E-11 2.21980E-08 671670 + 844 671680 Ho-168 5.76230E-11 9.63550E-09 671680 + 845 671681 Ho-168m 9.63670E-11 9.63670E-11 671681 + 846 671690 Ho-169 6.33510E-10 4.17980E-09 671690 + 847 671700 Ho-170 2.98750E-10 2.98750E-10 671700 + 848 671701 Ho-170m 1.09600E-10 1.49890E-09 671701 + 849 671710 Ho-171 5.52870E-10 7.56820E-10 671710 + 850 671720 Ho-172 1.84560E-10 2.40620E-10 671720 + 851 671730 Ho-173 8.75410E-11 9.01320E-11 671730 + 852 671740 Ho-174 8.88740E-12 8.88740E-12 671740 + 853 671750 Ho-175 2.03100E-12 2.03100E-12 671750 + 854 681690 Er-169 2.22950E-12 4.18200E-09 681690 + 855 681700 Er-170 1.68630E-11 1.81450E-09 68170.82c + 856 681710 Er-171 3.05860E-11 7.87400E-10 681710 + 857 681720 Er-172 1.00340E-10 3.40960E-10 681720 + 858 681730 Er-173 5.44500E-11 1.44580E-10 681730 + 859 681740 Er-174 5.08140E-11 5.97010E-11 681740 + 860 681750 Er-175 1.41190E-11 1.61500E-11 681750 + 861 681760 Er-176 5.81930E-12 5.81930E-12 681760 + 862 691730 Tm-173 3.68960E-12 1.48270E-10 691730 + 863 691740 Tm-174 4.41070E-12 6.41120E-11 691740 + 864 691750 Tm-175 1.16080E-11 2.77580E-11 691750 + 865 691760 Tm-176 5.41970E-12 1.12390E-11 691760 + 866 691770 Tm-177 4.04920E-12 4.04920E-12 691770 + 867 701780 Yb-178 1.35910E-12 1.35910E-12 701780 + + Neutron-induced fission: + + Interpolation region : 3 / 3 + Interpolation energy : 1.40000E+01 MeV + Number of products : 1112 / 1173 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 2.63690E-05 2.63690E-05 1001.82c + 2 10020 H-2 8.05870E-06 8.05870E-06 1002.82c + 3 10030 H-3 1.74200E-04 1.74200E-04 1003.82c + 4 20040 He-4 1.66700E-03 1.66700E-03 2004.82c + 5 190500 K-50 1.90050E-11 1.90050E-11 190500 + 6 190510 K-51 4.31580E-12 4.31580E-12 190510 + 7 200500 Ca-50 9.08480E-10 9.24000E-10 200500 + 8 200510 Ca-51 3.74840E-10 3.77130E-10 200510 + 9 200520 Ca-52 2.00070E-10 2.00070E-10 200520 + 10 200530 Ca-53 3.51760E-11 3.51760E-11 200530 + 11 200540 Ca-54 6.14320E-12 6.14320E-12 200540 + 12 210500 Sc-50 8.39740E-10 1.93580E-09 210500 + 13 210501 Sc-50m 1.85960E-10 1.11000E-09 210501 + 14 210510 Sc-51 2.38080E-09 2.76190E-09 210510 + 15 210520 Sc-52 2.08490E-09 2.29150E-09 210520 + 16 210530 Sc-53 2.33760E-09 2.36220E-09 210530 + 17 210540 Sc-54 7.59750E-10 7.65890E-10 210540 + 18 210550 Sc-55 3.35970E-10 3.35970E-10 210550 + 19 210560 Sc-56 4.84650E-11 4.84650E-11 210560 + 20 210570 Sc-57 6.97430E-12 6.97430E-12 210570 + 21 220500 Ti-50 1.70720E-10 2.12040E-09 22050.82c + 22 220510 Ti-51 6.30740E-10 3.39270E-09 220510 + 23 220520 Ti-52 3.05540E-09 5.34690E-09 220520 + 24 220530 Ti-53 5.20530E-09 7.56750E-09 220530 + 25 220540 Ti-54 9.73550E-09 1.05010E-08 220540 + 26 220550 Ti-55 7.27750E-09 7.61350E-09 220550 + 27 220560 Ti-56 6.88090E-09 6.93170E-09 220560 + 28 220570 Ti-57 1.88180E-09 1.88650E-09 220570 + 29 220580 Ti-58 5.98140E-10 5.98140E-10 220580 + 30 220590 Ti-59 7.11010E-11 7.11010E-11 220590 + 31 220600 Ti-60 2.53170E-11 2.53170E-11 220600 + 32 220610 Ti-61 2.29120E-12 2.29120E-12 220610 + 33 230510 V-51 1.32070E-11 3.40590E-09 230510 + 34 230520 V-52 1.12910E-10 5.45980E-09 230520 + 35 230530 V-53 1.15320E-09 8.72070E-09 230530 + 36 230540 V-54 3.35270E-09 1.38540E-08 230540 + 37 230550 V-55 1.37700E-08 2.13840E-08 230550 + 38 230560 V-56 2.00560E-08 2.69930E-08 230560 + 39 230570 V-57 3.24340E-08 3.43150E-08 230570 + 40 230580 V-58 1.79510E-08 1.85490E-08 230580 + 41 230590 V-59 1.43380E-08 1.44090E-08 230590 + 42 230600 V-60 9.87810E-09 9.90340E-09 230600 + 43 230610 V-61 6.54710E-09 6.54940E-09 230610 + 44 230620 V-62 5.03250E-10 5.03250E-10 230620 + 45 230630 V-63 7.57830E-12 7.57830E-12 230630 + 46 240530 Cr-53 7.70600E-12 8.72840E-09 24053.82c + 47 240540 Cr-54 1.48610E-10 1.40030E-08 24054.82c + 48 240550 Cr-55 1.04640E-09 2.24300E-08 240550 + 49 240560 Cr-56 8.87920E-09 3.60100E-08 240560 + 50 240570 Cr-57 2.19370E-08 7.09540E-08 240570 + 51 240580 Cr-58 6.68770E-08 7.05870E-08 240580 + 52 240590 Cr-59 8.40260E-08 9.84350E-08 240590 + 53 240600 Cr-60 7.09580E-07 7.19880E-07 240600 + 54 240610 Cr-61 4.18520E-07 4.24680E-07 240610 + 55 240620 Cr-62 2.20930E-07 2.21440E-07 240620 + 56 240630 Cr-63 6.52760E-09 6.53250E-09 240630 + 57 240640 Cr-64 1.47190E-09 1.47190E-09 240640 + 58 240650 Cr-65 2.47990E-11 2.47990E-11 240650 + 59 240660 Cr-66 5.76520E-12 5.76520E-12 240660 + 60 250550 Mn-55 5.25510E-12 2.24350E-08 25055.82c + 61 250560 Mn-56 8.38420E-11 3.60940E-08 250560 + 62 250570 Mn-57 1.33850E-09 7.22920E-08 250570 + 63 250580 Mn-58 6.39340E-09 7.69800E-08 250580 + 64 250581 Mn-58m 3.95090E-10 3.95090E-10 250581 + 65 250590 Mn-59 4.84610E-08 1.46900E-07 250590 + 66 250600 Mn-60 1.79150E-08 7.71130E-07 250600 + 67 250601 Mn-60m 2.89910E-07 2.89910E-07 250601 + 68 250610 Mn-61 1.84370E-06 2.26840E-06 250610 + 69 250620 Mn-62 9.06950E-07 1.01770E-06 250620 + 70 250621 Mn-62m 8.91510E-08 1.99870E-07 250621 + 71 250630 Mn-63 3.21740E-07 3.28270E-07 250630 + 72 250640 Mn-64 1.33290E-07 1.34760E-07 250640 + 73 250650 Mn-65 1.57120E-08 1.57370E-08 250650 + 74 250660 Mn-66 7.24260E-09 7.24840E-09 250660 + 75 250670 Mn-67 1.50580E-09 1.50580E-09 250670 + 76 250680 Mn-68 3.34870E-11 3.34870E-11 250680 + 77 250690 Mn-69 4.86950E-12 4.86950E-12 250690 + 78 260570 Fe-57 2.08630E-12 7.22940E-08 26057.82c + 79 260580 Fe-58 7.40590E-11 7.74490E-08 26058.82c + 80 260590 Fe-59 9.71830E-10 1.47870E-07 260590 + 81 260600 Fe-60 3.87650E-08 1.06650E-06 260600 + 82 260610 Fe-61 9.21850E-07 3.19020E-06 260610 + 83 260620 Fe-62 2.98830E-06 4.20580E-06 260620 + 84 260630 Fe-63 5.52250E-07 8.80520E-07 260630 + 85 260640 Fe-64 8.26100E-07 9.60860E-07 260640 + 86 260650 Fe-65 6.56230E-07 6.71970E-07 260650 + 87 260660 Fe-66 1.06290E-06 1.07020E-06 260660 + 88 260670 Fe-67 2.96140E-07 2.97650E-07 260670 + 89 260680 Fe-68 4.68290E-08 4.68640E-08 260680 + 90 260690 Fe-69 1.43030E-08 1.43070E-08 260690 + 91 260700 Fe-70 1.37510E-09 1.37510E-09 260700 + 92 260710 Fe-71 4.84860E-11 4.84860E-11 260710 + 93 260720 Fe-72 4.17800E-12 4.17800E-12 260720 + 94 270590 Co-59 1.11040E-12 1.47870E-07 27059.82c + 95 270600 Co-60 7.14030E-11 8.71760E-11 270600 + 96 270601 Co-60m 1.58120E-11 1.58120E-11 270601 + 97 270610 Co-61 6.40260E-09 3.19660E-06 270610 + 98 270620 Co-62 9.88230E-09 4.21620E-06 270620 + 99 270621 Co-62m 4.46260E-08 4.46260E-08 270621 + 100 270630 Co-63 9.32300E-08 9.73750E-07 270630 + 101 270640 Co-64 3.45230E-07 1.30610E-06 270640 + 102 270650 Co-65 3.72730E-07 1.04470E-06 270650 + 103 270660 Co-66 1.06290E-06 2.13300E-06 270660 + 104 270670 Co-67 6.12020E-07 9.09670E-07 270670 + 105 270680 Co-68 9.40630E-07 1.16820E-06 270680 + 106 270681 Co-68m 4.07370E-07 4.55230E-07 270681 + 107 270690 Co-69 1.41570E-06 1.42900E-06 270690 + 108 270700 Co-70 1.94850E-07 1.94850E-07 270700 + 109 270701 Co-70m 1.94850E-07 1.96220E-07 270701 + 110 270710 Co-71 9.84070E-08 9.84560E-08 270710 + 111 270720 Co-72 1.41220E-08 1.41260E-08 270720 + 112 270730 Co-73 1.96210E-09 1.96210E-09 270730 + 113 270740 Co-74 6.76160E-11 6.76160E-11 270740 + 114 280610 Ni-61 2.21730E-12 3.19660E-06 28061.82c + 115 280620 Ni-62 1.37900E-10 4.26050E-06 28062.82c + 116 280630 Ni-63 4.56760E-10 9.74210E-07 280630 + 117 280640 Ni-64 8.26100E-07 2.13220E-06 28064.82c + 118 280650 Ni-65 2.13870E-08 1.06610E-06 280650 + 119 280660 Ni-66 1.06290E-06 3.19590E-06 280660 + 120 280670 Ni-67 5.50820E-06 6.41790E-06 280670 + 121 280680 Ni-68 2.02200E-06 3.43220E-06 280680 + 122 280690 Ni-69 6.72450E-06 8.13920E-06 280690 + 123 280691 Ni-69m 6.72450E-06 6.72450E-06 280691 + 124 280700 Ni-70 1.09020E-05 1.12930E-05 280700 + 125 280710 Ni-71 6.93040E-06 7.02890E-06 280710 + 126 280720 Ni-72 6.47070E-06 6.48480E-06 280720 + 127 280730 Ni-73 3.19680E-06 3.19880E-06 280730 + 128 280740 Ni-74 1.04030E-06 1.04040E-06 280740 + 129 280750 Ni-75 2.04040E-08 2.04040E-08 280750 + 130 280760 Ni-76 1.70790E-09 1.70790E-09 280760 + 131 280770 Ni-77 5.43530E-11 5.43530E-11 280770 + 132 290640 Cu-64 5.80660E-12 5.80660E-12 290640 + 133 290650 Cu-65 7.82940E-11 1.06620E-06 29065.82c + 134 290660 Cu-66 4.00420E-09 3.20000E-06 290660 + 135 290670 Cu-67 9.20580E-08 6.50990E-06 290670 + 136 290680 Cu-68 1.22190E-07 4.01790E-06 290680 + 137 290681 Cu-68m 5.51800E-07 5.51800E-07 290681 + 138 290690 Cu-69 1.41570E-06 1.62790E-05 290690 + 139 290700 Cu-70 2.93050E-07 3.56060E-06 290700 + 140 290701 Cu-70m 5.95580E-06 6.53520E-06 290701 + 141 290702 Cu-70m 2.93050E-07 1.15860E-05 290702 + 142 290710 Cu-71 1.00110E-05 1.70400E-05 290710 + 143 290720 Cu-72 2.75000E-05 3.39850E-05 290720 + 144 290730 Cu-73 4.36890E-05 4.68880E-05 290730 + 145 290740 Cu-74 2.08070E-05 2.18480E-05 290740 + 146 290750 Cu-75 1.22630E-05 1.22830E-05 290750 + 147 290760 Cu-76 2.51930E-06 2.52010E-06 290760 + 148 290761 Cu-76m 2.51930E-06 2.52010E-06 290761 + 149 290770 Cu-77 3.24320E-07 3.24370E-07 290770 + 150 290780 Cu-78 2.20590E-08 2.20590E-08 290780 + 151 290790 Cu-79 1.52330E-09 1.52330E-09 290790 + 152 300660 Zn-66 2.23550E-12 3.20000E-06 300660 + 153 300670 Zn-67 1.04020E-10 6.51000E-06 300670 + 154 300680 Zn-68 1.85130E-09 4.10800E-06 300680 + 155 300690 Zn-69 6.96860E-09 1.63420E-05 300690 + 156 300691 Zn-69m 5.54740E-08 5.54740E-08 300691 + 157 300700 Zn-70 7.26820E-07 1.85620E-05 300700 + 158 300710 Zn-71 7.73430E-07 1.78130E-05 300710 + 159 300711 Zn-71m 6.15700E-06 6.15700E-06 300711 + 160 300720 Zn-72 2.02200E-05 5.42050E-05 300720 + 161 300730 Zn-73 3.55370E-06 8.20940E-05 300730 + 162 300731 Zn-73m 5.05560E-06 3.16530E-05 300731 + 163 300732 Zn-73m 5.31950E-05 5.31950E-05 300732 + 164 300740 Zn-74 1.41480E-04 1.63760E-04 300740 + 165 300750 Zn-75 1.67590E-04 1.79520E-04 300750 + 166 300760 Zn-76 1.56200E-04 1.61170E-04 300760 + 167 300770 Zn-77 7.36270E-05 7.70190E-05 300770 + 168 300771 Zn-77m 6.13360E-06 6.13360E-06 300771 + 169 300780 Zn-78 6.72790E-05 6.73020E-05 300780 + 170 300790 Zn-79 1.32790E-05 1.32800E-05 300790 + 171 300800 Zn-80 1.95170E-06 1.95170E-06 300800 + 172 300810 Zn-81 1.93050E-08 1.93050E-08 300810 + 173 300820 Zn-82 1.00290E-09 1.00290E-09 300820 + 174 310690 Ga-69 5.14010E-11 1.63420E-05 310690 + 175 310700 Ga-70 1.09520E-09 1.09520E-09 310700 + 176 310710 Ga-71 3.07540E-08 2.40010E-05 310710 + 177 310720 Ga-72 2.28520E-06 5.66310E-05 310720 + 178 310721 Ga-72m 1.41220E-07 1.94740E-06 310721 + 179 310730 Ga-73 6.39350E-06 1.15090E-04 310730 + 180 310740 Ga-74 1.09240E-05 1.41930E-04 310740 + 181 310741 Ga-74m 1.09240E-05 1.74680E-04 310741 + 182 310750 Ga-75 6.94900E-05 2.49010E-04 310750 + 183 310760 Ga-76 1.74330E-04 3.35490E-04 310760 + 184 310770 Ga-77 3.80470E-04 4.60560E-04 310770 + 185 310780 Ga-78 3.45710E-04 4.13180E-04 310780 + 186 310790 Ga-79 3.65060E-04 3.78170E-04 310790 + 187 310800 Ga-80 1.34180E-04 1.36130E-04 310800 + 188 310810 Ga-81 5.57590E-05 5.57770E-05 310810 + 189 310820 Ga-82 6.29030E-06 6.29130E-06 310820 + 190 310830 Ga-83 3.67330E-07 3.67330E-07 310830 + 191 310840 Ga-84 1.21810E-08 1.21810E-08 310840 + 192 310850 Ga-85 5.79500E-10 5.79500E-10 310850 + 193 320710 Ge-71 8.54350E-13 7.65550E-12 320710 + 194 320711 Ge-71m 6.80110E-12 6.80110E-12 320711 + 195 320720 Ge-72 8.94100E-10 5.66320E-05 32072.82c + 196 320730 Ge-73 2.43180E-08 1.15110E-04 32073.82c + 197 320731 Ge-73m 3.05480E-09 1.13400E-04 320731 + 198 320740 Ge-74 2.08070E-06 1.87690E-04 32074.82c + 199 320750 Ge-75 7.07260E-07 2.58200E-04 320750 + 200 320751 Ge-75m 8.48980E-06 1.84500E-05 320751 + 201 320760 Ge-76 6.34830E-05 3.98980E-04 32076.82c + 202 320770 Ge-77 1.96340E-04 2.86960E-04 320770 + 203 320771 Ge-77m 1.63570E-05 4.76910E-04 320771 + 204 320780 Ge-78 7.56570E-04 1.17010E-03 320780 + 205 320790 Ge-79 1.01010E-04 5.26790E-04 320790 + 206 320791 Ge-79m 1.21250E-03 1.21310E-03 320791 + 207 320800 Ge-80 1.97740E-03 2.12020E-03 320800 + 208 320810 Ge-81 1.51040E-03 1.53910E-03 320810 + 209 320811 Ge-81m 1.89730E-04 2.13590E-04 320811 + 210 320820 Ge-82 1.32260E-03 1.32770E-03 320820 + 211 320830 Ge-83 3.06810E-04 3.07050E-04 320830 + 212 320840 Ge-84 7.77750E-05 7.77790E-05 320840 + 213 320850 Ge-85 1.63170E-05 1.63180E-05 320850 + 214 320860 Ge-86 2.10750E-07 2.10750E-07 320860 + 215 320870 Ge-87 4.46920E-09 4.46920E-09 320870 + 216 330730 As-73 3.82470E-12 3.82470E-12 330730 + 217 330740 As-74 2.79470E-10 2.79470E-10 330740 + 218 330750 As-75 2.07420E-09 2.58220E-04 33075.82c + 219 330751 As-75m 1.28160E-08 1.83510E-08 330751 + 220 330760 As-76 2.74630E-07 2.74630E-07 330760 + 221 330770 As-77 5.11040E-06 6.78370E-04 330770 + 222 330780 As-78 3.80230E-05 1.20810E-03 330780 + 223 330790 As-79 2.23560E-04 1.91490E-03 330790 + 224 330800 As-80 6.89280E-04 2.80940E-03 330800 + 225 330810 As-81 1.73760E-03 3.48820E-03 330810 + 226 330820 As-82 4.04610E-04 1.73230E-03 330820 + 227 330821 As-82m 2.28920E-03 2.28920E-03 330821 + 228 330830 As-83 2.94580E-03 3.26120E-03 330830 + 229 330840 As-84 7.19150E-04 7.54980E-04 330840 + 230 330841 As-84m 7.19150E-04 7.54980E-04 330841 + 231 330850 As-85 9.25250E-04 9.39280E-04 330850 + 232 330860 As-86 2.27990E-04 2.28200E-04 330860 + 233 330870 As-87 6.13240E-05 6.13290E-05 330870 + 234 330880 As-88 4.67550E-06 4.67550E-06 330880 + 235 330890 As-89 7.58720E-08 7.58720E-08 330890 + 236 330900 As-90 1.05170E-09 1.05170E-09 330900 + 237 340760 Se-76 1.17790E-10 2.74750E-07 34076.82c + 238 340770 Se-77 3.98470E-10 6.78370E-04 34077.82c + 239 340771 Se-77m 4.78320E-09 4.78320E-09 340771 + 240 340780 Se-78 2.81830E-07 1.20840E-03 34078.82c + 241 340790 Se-79 9.42760E-06 1.92410E-03 34079.82c + 242 340791 Se-79m 7.85380E-07 1.87030E-03 340791 + 243 340800 Se-80 8.88840E-05 2.89830E-03 34080.82c + 244 340810 Se-81 4.02690E-05 4.01150E-03 340810 + 245 340811 Se-81m 4.83390E-04 6.08610E-04 340811 + 246 340820 Se-82 2.51930E-03 6.54080E-03 34082.82c + 247 340830 Se-83 5.73810E-03 6.91320E-03 340830 + 248 340831 Se-83m 7.20810E-04 2.80910E-03 340831 + 249 340840 Se-84 1.12590E-02 1.29740E-02 340840 + 250 340850 Se-85 8.81740E-03 9.62530E-03 340850 + 251 340860 Se-86 6.27560E-03 6.43790E-03 340860 + 252 340870 Se-87 2.74380E-03 2.79570E-03 340870 + 253 340880 Se-88 1.31340E-03 1.31810E-03 340880 + 254 340890 Se-89 2.78290E-04 2.78370E-04 340890 + 255 340900 Se-90 4.62920E-05 4.62930E-05 340900 + 256 340910 Se-91 4.94430E-06 4.94430E-06 340910 + 257 340920 Se-92 9.65890E-07 9.65890E-07 340920 + 258 350780 Br-78 2.90250E-11 2.90250E-11 350780 + 259 350790 Br-79 3.53680E-10 1.04990E-06 35079.82c + 260 350791 Br-79m 2.18530E-09 2.18530E-09 350791 + 261 350800 Br-80 1.21970E-08 8.12040E-08 350800 + 262 350801 Br-80m 6.90070E-08 6.90070E-08 350801 + 263 350810 Br-81 4.04510E-06 4.01590E-03 35081.82c + 264 350820 Br-82 3.44510E-05 4.18970E-05 350820 + 265 350821 Br-82m 7.62910E-06 7.62910E-06 350821 + 266 350830 Br-83 3.12850E-04 1.00350E-02 350830 + 267 350840 Br-84 6.87000E-04 1.36610E-02 350840 + 268 350841 Br-84m 6.87000E-04 6.87000E-04 350841 + 269 350850 Br-85 6.73010E-03 1.63550E-02 350850 + 270 350860 Br-86 1.03870E-02 1.68250E-02 350860 + 271 350870 Br-87 1.29560E-02 1.57650E-02 350870 + 272 350880 Br-88 9.42290E-03 1.07500E-02 350880 + 273 350890 Br-89 6.84090E-03 7.09760E-03 350890 + 274 350900 Br-90 2.42840E-03 2.47570E-03 350900 + 275 350910 Br-91 8.93770E-04 8.97680E-04 350910 + 276 350920 Br-92 1.18610E-04 1.19580E-04 350920 + 277 350930 Br-93 2.23130E-05 2.23130E-05 350930 + 278 350940 Br-94 9.14320E-07 9.14320E-07 350940 + 279 350950 Br-95 3.35020E-09 3.35020E-09 350950 + 280 360810 Kr-81 5.03380E-10 5.45310E-10 360810 + 281 360811 Kr-81m 4.19340E-11 4.19340E-11 360811 + 282 360820 Kr-82 4.73890E-08 4.21270E-05 36082.82c + 283 360830 Kr-83 8.11300E-06 1.00440E-02 36083.82c + 284 360831 Kr-83m 1.01910E-06 1.00270E-02 360831 + 285 360840 Kr-84 8.46810E-05 1.44320E-02 36084.82c + 286 360850 Kr-85 5.07120E-04 4.04170E-03 36085.82c + 287 360851 Kr-85m 6.37050E-05 1.63930E-02 360851 + 288 360860 Kr-86 4.10100E-03 2.13220E-02 36086.82c + 289 360870 Kr-87 8.88570E-03 2.49750E-02 360870 + 290 360880 Kr-88 2.34200E-02 3.44500E-02 360880 + 291 360890 Kr-89 2.81260E-02 3.48320E-02 360890 + 292 360900 Kr-90 2.84840E-02 3.05300E-02 360900 + 293 360910 Kr-91 1.66030E-02 1.73610E-02 360910 + 294 360920 Kr-92 8.62470E-03 8.71990E-03 360920 + 295 360930 Kr-93 2.21420E-03 2.22200E-03 360930 + 296 360940 Kr-94 5.67720E-04 5.67990E-04 360940 + 297 360950 Kr-95 6.81050E-05 6.81080E-05 360950 + 298 360960 Kr-96 7.55590E-06 7.55590E-06 360960 + 299 360970 Kr-97 2.47890E-08 2.47890E-08 360970 + 300 370840 Rb-84 1.82950E-09 8.23010E-09 370840 + 301 370841 Rb-84m 6.40060E-09 6.40060E-09 370841 + 302 370850 Rb-85 1.01990E-06 1.69270E-02 37085.82c + 303 370860 Rb-86 4.33970E-06 1.95220E-05 37086.82c + 304 370861 Rb-86m 1.51820E-05 1.51820E-05 370861 + 305 370870 Rb-87 2.10720E-04 2.51860E-02 37087.82c + 306 370880 Rb-88 1.05020E-03 3.55000E-02 370880 + 307 370890 Rb-89 5.25190E-03 4.00840E-02 370890 + 308 370900 Rb-90 6.59520E-04 2.75780E-02 370900 + 309 370901 Rb-90m 1.06720E-02 1.46660E-02 370901 + 310 370910 Rb-91 2.27420E-02 4.01030E-02 370910 + 311 370920 Rb-92 2.39010E-02 3.26210E-02 370920 + 312 370930 Rb-93 2.18360E-02 2.40640E-02 370930 + 313 370940 Rb-94 1.00460E-02 1.06100E-02 370940 + 314 370950 Rb-95 4.57730E-03 4.64370E-03 370950 + 315 370960 Rb-96 4.96460E-04 7.50140E-04 370960 + 316 370961 Rb-96m 4.96460E-04 5.00090E-04 370961 + 317 370970 Rb-97 2.38620E-04 2.38640E-04 370970 + 318 370980 Rb-98 1.13540E-05 1.13540E-05 370980 + 319 370981 Rb-98m 1.13540E-05 1.13540E-05 370981 + 320 370990 Rb-99 4.78230E-06 4.78230E-06 370990 + 321 371000 Rb-100 3.33690E-09 3.33690E-09 371000 + 322 380860 Sr-86 1.95090E-06 2.14720E-05 38086.82c + 323 380870 Sr-87 2.38940E-06 2.68870E-06 38087.82c + 324 380871 Sr-87m 3.00160E-07 3.00160E-07 380871 + 325 380880 Sr-88 5.14810E-05 3.55520E-02 38088.82c + 326 380890 Sr-89 2.96100E-04 4.03800E-02 38089.82c + 327 380900 Sr-90 1.92720E-03 4.37890E-02 38090.82c + 328 380910 Sr-91 5.64990E-03 4.57530E-02 380910 + 329 380920 Sr-92 1.66870E-02 4.96450E-02 380920 + 330 380930 Sr-93 2.45900E-02 4.93890E-02 380930 + 331 380940 Sr-94 3.89240E-02 4.88610E-02 380940 + 332 380950 Sr-95 3.01870E-02 3.45320E-02 380950 + 333 380960 Sr-96 2.18750E-02 2.28350E-02 380960 + 334 380970 Sr-97 8.84580E-03 9.02610E-03 380970 + 335 380980 Sr-98 3.22930E-03 3.25120E-03 380980 + 336 380990 Sr-99 5.76670E-04 5.80690E-04 380990 + 337 381000 Sr-100 1.20270E-04 1.20270E-04 381000 + 338 381010 Sr-101 9.36860E-06 9.36860E-06 381010 + 339 381020 Sr-102 1.09540E-06 1.09540E-06 381020 + 340 381030 Sr-103 8.49810E-10 8.49810E-10 381030 + 341 390890 Y-89 2.33580E-09 4.03800E-02 39089.82c + 342 390891 Y-89m 1.85940E-08 3.91080E-06 390891 + 343 390900 Y-90 1.53590E-06 4.37950E-02 39090.82c + 344 390901 Y-90m 4.38980E-06 4.38980E-06 390901 + 345 390910 Y-91 5.95820E-06 4.58060E-02 39091.82c + 346 390911 Y-91m 4.74310E-05 2.69660E-02 390911 + 347 390920 Y-92 3.64890E-04 5.00100E-02 390920 + 348 390930 Y-93 1.70900E-04 5.16110E-02 390930 + 349 390931 Y-93m 2.05140E-03 1.44100E-02 390931 + 350 390940 Y-94 5.66300E-03 5.45240E-02 390940 + 351 390950 Y-95 1.43510E-02 4.88830E-02 390950 + 352 390960 Y-96 4.31770E-03 2.71550E-02 390960 + 353 390961 Y-96m 1.51050E-02 1.51070E-02 390961 + 354 390970 Y-97 3.13200E-03 1.09810E-02 390970 + 355 390971 Y-97m 1.45040E-02 2.41900E-02 390971 + 356 390972 Y-97m 1.04290E-02 1.04290E-02 390972 + 357 390980 Y-98 2.29400E-03 5.54520E-03 390980 + 358 390981 Y-98m 1.79890E-02 1.79890E-02 390981 + 359 390990 Y-99 1.36250E-02 1.42070E-02 390990 + 360 391000 Y-100 2.15930E-03 2.27880E-03 391000 + 361 391001 Y-100m 2.15930E-03 2.15950E-03 391001 + 362 391010 Y-101 1.52280E-03 1.53200E-03 391010 + 363 391020 Y-102 1.06320E-04 1.06830E-04 391020 + 364 391021 Y-102m 1.06320E-04 1.06830E-04 391021 + 365 391030 Y-103 4.72500E-05 4.72510E-05 391030 + 366 391040 Y-104 1.09560E-06 1.09560E-06 391040 + 367 391050 Y-105 2.74240E-09 2.74240E-09 391050 + 368 400910 Zr-91 9.89130E-07 4.58070E-02 40091.82c + 369 400920 Zr-92 6.76100E-06 5.00160E-02 40092.82c + 370 400930 Zr-93 4.64730E-05 5.16580E-02 40093.82c + 371 400940 Zr-94 4.75980E-04 5.50000E-02 40094.82c + 372 400950 Zr-95 1.73670E-03 5.06200E-02 40095.82c + 373 400960 Zr-96 6.65780E-03 4.89390E-02 40096.82c + 374 400970 Zr-97 1.35760E-02 5.12770E-02 400970 + 375 400980 Zr-98 2.75430E-02 5.06850E-02 400980 + 376 400990 Zr-99 2.94060E-02 4.33920E-02 400990 + 377 401000 Zr-100 2.90010E-02 3.34180E-02 401000 + 378 401010 Zr-101 1.54430E-02 1.69860E-02 401010 + 379 401020 Zr-102 7.65890E-03 7.86590E-03 401020 + 380 401030 Zr-103 2.04300E-03 2.08660E-03 401030 + 381 401040 Zr-104 5.15230E-04 5.16230E-04 401040 + 382 401050 Zr-105 7.56580E-05 7.56600E-05 401050 + 383 401060 Zr-106 7.46130E-06 7.46130E-06 401060 + 384 401070 Zr-107 3.03310E-06 3.03310E-06 401070 + 385 401080 Zr-108 5.05730E-10 5.05730E-10 401080 + 386 410940 Nb-94 1.35460E-06 1.82620E-06 41094.82c + 387 410941 Nb-94m 4.73970E-07 4.73970E-07 410941 + 388 410950 Nb-95 1.30130E-05 5.06040E-02 41095.82c + 389 410951 Nb-95m 1.63470E-06 5.48500E-04 410951 + 390 410960 Nb-96 5.53780E-05 5.53780E-05 410960 + 391 410970 Nb-97 4.53090E-04 5.17870E-02 410970 + 392 410971 Nb-97m 5.69170E-05 4.87950E-02 410971 + 393 410980 Nb-98 2.76340E-04 5.09610E-02 410980 + 394 410981 Nb-98m 1.56350E-03 1.56350E-03 410981 + 395 410990 Nb-99 5.83610E-03 3.35940E-02 410990 + 396 410991 Nb-99m 7.33120E-04 1.67010E-02 410991 + 397 411000 Nb-100 1.23170E-03 3.46500E-02 411000 + 398 411001 Nb-100m 9.65830E-03 9.65830E-03 411001 + 399 411010 Nb-101 1.92820E-02 3.62680E-02 411010 + 400 411020 Nb-102 8.28200E-03 1.61480E-02 411020 + 401 411021 Nb-102m 8.28200E-03 8.28200E-03 411021 + 402 411030 Nb-103 1.43010E-02 1.63880E-02 411030 + 403 411040 Nb-104 3.05660E-03 3.57390E-03 411040 + 404 411041 Nb-104m 3.05660E-03 3.05660E-03 411041 + 405 411050 Nb-105 2.72000E-03 2.79470E-03 411050 + 406 411060 Nb-106 9.30200E-04 9.37660E-04 411060 + 407 411070 Nb-107 2.72450E-04 2.75370E-04 411070 + 408 411080 Nb-108 5.39880E-05 5.39880E-05 411080 + 409 411090 Nb-109 1.39740E-05 1.39740E-05 411090 + 410 411100 Nb-110 1.54230E-06 1.54230E-06 411100 + 411 420960 Mo-96 1.79440E-09 5.53800E-05 42096.82c + 412 420970 Mo-97 4.35920E-06 5.17910E-02 42097.82c + 413 420980 Mo-98 5.26850E-05 5.25770E-02 42098.82c + 414 420990 Mo-99 3.39410E-04 5.03010E-02 42099.82c + 415 421000 Mo-100 1.68830E-03 4.59970E-02 42100.82c + 416 421010 Mo-101 4.38940E-03 4.06570E-02 421010 + 417 421020 Mo-102 1.07150E-02 3.51450E-02 421020 + 418 421030 Mo-103 1.34920E-02 2.98830E-02 421030 + 419 421040 Mo-104 1.42190E-02 2.08930E-02 421040 + 420 421050 Mo-105 8.36900E-03 1.11580E-02 421050 + 421 421060 Mo-106 7.93880E-03 8.85080E-03 421060 + 422 421070 Mo-107 3.46390E-03 3.72610E-03 421070 + 423 421080 Mo-108 1.64890E-03 1.70130E-03 421080 + 424 421090 Mo-109 4.41150E-04 4.53970E-04 421090 + 425 421100 Mo-110 1.49060E-04 1.49980E-04 421100 + 426 421110 Mo-111 2.51920E-05 2.51920E-05 421110 + 427 421120 Mo-112 4.45400E-06 4.45400E-06 421120 + 428 421130 Mo-113 2.90020E-10 2.90020E-10 421130 + 429 430990 Tc-99 8.98970E-09 5.02990E-02 43099.82c + 430 430991 Tc-99m 1.12930E-09 4.42950E-02 430991 + 431 431000 Tc-100 7.68940E-06 7.68940E-06 431000 + 432 431010 Tc-101 6.15230E-05 4.07180E-02 431010 + 433 431020 Tc-102 1.55790E-04 3.53010E-02 431020 + 434 431021 Tc-102m 1.55790E-04 1.55790E-04 431021 + 435 431030 Tc-103 1.30070E-03 3.11840E-02 431030 + 436 431040 Tc-104 2.47770E-03 2.33710E-02 431040 + 437 431050 Tc-105 4.90680E-03 1.60650E-02 431050 + 438 431060 Tc-106 7.75660E-03 1.66070E-02 431060 + 439 431070 Tc-107 8.99990E-03 1.27260E-02 431070 + 440 431080 Tc-108 6.57370E-03 8.27740E-03 431080 + 441 431090 Tc-109 5.26370E-03 5.71530E-03 431090 + 442 431100 Tc-110 2.46340E-03 2.61360E-03 431100 + 443 431110 Tc-111 1.17100E-03 1.19600E-03 431110 + 444 431120 Tc-112 1.67610E-04 1.71970E-04 431120 + 445 431130 Tc-113 7.81520E-05 7.81520E-05 431130 + 446 431140 Tc-114 3.52960E-06 3.52960E-06 431140 + 447 431150 Tc-115 4.18030E-09 4.18030E-09 431150 + 448 441010 Ru-101 1.10980E-09 4.07180E-02 44101.82c + 449 441020 Ru-102 3.28660E-06 3.54600E-02 44102.82c + 450 441030 Ru-103 4.65320E-06 3.12100E-02 44103.82c + 451 441031 Ru-103m 2.13570E-05 2.13570E-05 441031 + 452 441040 Ru-104 1.19870E-04 2.34910E-02 44104.82c + 453 441050 Ru-105 3.24490E-04 1.63900E-02 44105.82c + 454 441060 Ru-106 1.39220E-03 1.80000E-02 44106.82c + 455 441070 Ru-107 2.59380E-03 1.53200E-02 441070 + 456 441080 Ru-108 5.25360E-03 1.35360E-02 441080 + 457 441090 Ru-109 6.23930E-03 1.19510E-02 441090 + 458 441100 Ru-110 7.93240E-03 1.05450E-02 441100 + 459 441110 Ru-111 5.71200E-03 6.91060E-03 441110 + 460 441120 Ru-112 2.61320E-03 2.78820E-03 441120 + 461 441130 Ru-113 7.31900E-04 1.17060E-03 441130 + 462 441131 Ru-113m 7.31900E-04 7.31900E-04 441131 + 463 441140 Ru-114 5.72950E-04 5.76250E-04 441140 + 464 441150 Ru-115 8.60680E-05 8.60720E-05 441150 + 465 441160 Ru-116 3.12630E-05 3.12630E-05 441160 + 466 441170 Ru-117 1.38250E-06 1.38250E-06 441170 + 467 441180 Ru-118 8.25940E-10 8.25940E-10 441180 + 468 441190 Ru-119 1.14470E-07 1.14470E-07 441190 + 469 441200 Ru-120 4.34390E-09 4.34390E-09 441200 + 470 451040 Rh-104 3.40440E-10 2.26410E-09 451040 + 471 451041 Rh-104m 1.92620E-09 1.92620E-09 451041 + 472 451050 Rh-105 2.91280E-06 1.63930E-02 45105.82c + 473 451051 Rh-105m 2.42660E-07 4.65290E-03 451051 + 474 451060 Rh-106 3.78920E-06 1.80030E-02 451060 + 475 451061 Rh-106m 1.71110E-05 1.71110E-05 451061 + 476 451070 Rh-107 1.03190E-04 1.54230E-02 451070 + 477 451080 Rh-108 4.29380E-05 1.35790E-02 451080 + 478 451081 Rh-108m 2.42930E-04 2.42930E-04 451081 + 479 451090 Rh-109 1.04110E-03 1.29920E-02 451090 + 480 451100 Rh-110 2.21210E-03 1.27570E-02 451100 + 481 451101 Rh-110m 3.32300E-05 3.32300E-05 451101 + 482 451110 Rh-111 4.65500E-03 1.15660E-02 451110 + 483 451120 Rh-112 1.80570E-03 4.59390E-03 451120 + 484 451121 Rh-112m 1.80570E-03 1.80570E-03 451121 + 485 451130 Rh-113 7.21840E-03 8.75500E-03 451130 + 486 451140 Rh-114 2.47750E-03 3.05400E-03 451140 + 487 451141 Rh-114m 2.47750E-03 2.47750E-03 451141 + 488 451150 Rh-115 3.19690E-03 3.28310E-03 451150 + 489 451160 Rh-116 1.84110E-04 2.15060E-04 451160 + 490 451161 Rh-116m 8.31390E-04 8.31390E-04 451161 + 491 451170 Rh-117 4.25630E-04 4.26980E-04 451170 + 492 451180 Rh-118 7.12620E-05 7.12680E-05 451180 + 493 451190 Rh-119 2.92880E-05 2.93980E-05 451190 + 494 451200 Rh-120 4.56950E-06 4.57380E-06 451200 + 495 451210 Rh-121 8.06440E-07 8.06440E-07 451210 + 496 451220 Rh-122 2.16670E-08 2.16670E-08 451220 + 497 461070 Pd-107 3.23620E-07 1.54250E-02 46107.82c + 498 461071 Pd-107m 1.19290E-06 1.19290E-06 461071 + 499 461080 Pd-108 1.08090E-05 1.38320E-02 46108.82c + 500 461090 Pd-109 3.64250E-06 1.30090E-02 461090 + 501 461091 Pd-109m 1.34260E-05 6.50950E-03 461091 + 502 461100 Pd-110 1.57200E-04 1.29480E-02 46110.82c + 503 461110 Pd-111 9.15190E-05 1.18910E-02 461110 + 504 461111 Pd-111m 3.37340E-04 3.83600E-04 461111 + 505 461120 Pd-112 8.97710E-04 7.29720E-03 461120 + 506 461130 Pd-113 4.25780E-04 1.11350E-02 461130 + 507 461131 Pd-113m 1.95420E-03 1.95420E-03 461131 + 508 461140 Pd-114 4.36000E-03 9.89140E-03 461140 + 509 461150 Pd-115 1.05710E-03 4.21330E-03 461150 + 510 461151 Pd-115m 3.89630E-03 4.37300E-03 461151 + 511 461160 Pd-116 6.74800E-03 7.79440E-03 461160 + 512 461170 Pd-117 8.67790E-04 4.49560E-03 461170 + 513 461171 Pd-117m 3.19870E-03 3.19870E-03 461171 + 514 461180 Pd-118 2.50290E-03 2.57210E-03 461180 + 515 461190 Pd-119 8.09460E-04 8.39130E-04 461190 + 516 461200 Pd-120 3.16900E-04 3.21310E-04 461200 + 517 461210 Pd-121 5.27450E-05 5.34420E-05 461210 + 518 461220 Pd-122 9.49060E-06 9.51230E-06 461220 + 519 461230 Pd-123 3.43310E-06 3.43310E-06 461230 + 520 461240 Pd-124 2.46000E-07 2.46000E-07 461240 + 521 471090 Ag-109 6.60460E-11 1.30090E-02 47109.82c + 522 471091 Ag-109m 7.92800E-10 1.30030E-02 471091 + 523 471100 Ag-110 5.89210E-09 6.25390E-09 471100 + 524 471101 Ag-110m 2.66070E-08 2.66070E-08 47510.82c + 525 471110 Ag-111 3.41860E-07 1.19400E-02 47111.82c + 526 471111 Ag-111m 4.10360E-06 1.18850E-02 471111 + 527 471120 Ag-112 8.00930E-06 7.30520E-03 471120 + 528 471130 Ag-113 1.08430E-05 7.39060E-03 471130 + 529 471131 Ag-113m 1.30160E-04 1.07930E-02 471131 + 530 471140 Ag-114 4.95300E-05 1.03290E-02 471140 + 531 471141 Ag-114m 3.88400E-04 3.88400E-04 471141 + 532 471150 Ag-115 1.08140E-04 4.54020E-03 471150 + 533 471151 Ag-115m 1.29810E-03 6.45890E-03 471151 + 534 471160 Ag-116 5.09940E-04 8.44260E-03 471160 + 535 471161 Ag-116m 2.30280E-03 2.30280E-03 471161 + 536 471170 Ag-117 4.13950E-04 3.09470E-03 471170 + 537 471171 Ag-117m 4.96910E-03 7.21680E-03 471171 + 538 471180 Ag-118 6.26850E-04 4.99740E-03 471180 + 539 471181 Ag-118m 4.91560E-03 5.28330E-03 471181 + 540 471190 Ag-119 4.59530E-04 8.79100E-04 471190 + 541 471191 Ag-119m 5.51620E-03 5.93570E-03 471191 + 542 471200 Ag-120 9.06990E-04 2.08630E-03 471200 + 543 471201 Ag-120m 2.59220E-03 2.75290E-03 471201 + 544 471210 Ag-121 2.35390E-03 2.40720E-03 471210 + 545 471220 Ag-122 2.78180E-04 2.87700E-04 471220 + 546 471221 Ag-122m 5.32850E-04 5.32850E-04 471221 + 547 471230 Ag-123 3.69030E-04 3.72460E-04 471230 + 548 471240 Ag-124 3.20530E-05 6.29960E-05 471240 + 549 471241 Ag-124m 6.13950E-05 6.13950E-05 471241 + 550 471250 Ag-125 3.90480E-05 3.90480E-05 471250 + 551 471260 Ag-126 6.16500E-06 6.16500E-06 471260 + 552 471270 Ag-127 7.68550E-08 7.68550E-08 471270 + 553 471280 Ag-128 1.03500E-09 1.03500E-09 471280 + 554 481120 Cd-112 3.71500E-09 7.30520E-03 48112.82c + 555 481130 Cd-113 1.90670E-08 1.11480E-02 48113.82c + 556 481131 Cd-113m 1.17810E-07 1.27890E-04 481131 + 557 481140 Cd-114 1.40950E-05 1.03440E-02 48114.82c + 558 481150 Cd-115 9.82570E-06 9.24240E-03 481150 + 559 481151 Cd-115m 6.07100E-05 4.70880E-04 48515.82c + 560 481160 Cd-116 3.78670E-04 1.09860E-02 48116.82c + 561 481170 Cd-117 1.37260E-04 7.81150E-03 481170 + 562 481171 Cd-117m 8.48120E-04 3.05240E-03 481171 + 563 481180 Cd-118 2.70790E-03 1.08220E-02 481180 + 564 481190 Cd-119 7.20560E-04 7.09590E-03 481190 + 565 481191 Cd-119m 3.30710E-03 3.74670E-03 481191 + 566 481200 Cd-120 6.57900E-03 1.04000E-02 481200 + 567 481210 Cd-121 1.04340E-03 3.19910E-03 481210 + 568 481211 Cd-121m 4.78910E-03 5.04060E-03 481211 + 569 481220 Cd-122 5.89640E-03 6.71690E-03 481220 + 570 481230 Cd-123 6.10140E-04 9.14910E-04 481230 + 571 481231 Cd-123m 2.80040E-03 2.86810E-03 481231 + 572 481240 Cd-124 2.51190E-03 2.60550E-03 481240 + 573 481250 Cd-125 2.05770E-04 2.25300E-04 481250 + 574 481251 Cd-125m 9.44430E-04 9.63950E-04 481251 + 575 481260 Cd-126 5.92890E-04 5.99060E-04 481260 + 576 481270 Cd-127 1.57760E-04 1.57840E-04 481270 + 577 481280 Cd-128 4.23390E-05 4.23400E-05 481280 + 578 481290 Cd-129 1.19240E-06 1.19240E-06 481290 + 579 481291 Cd-129m 5.47300E-06 5.47300E-06 481291 + 580 481300 Cd-130 8.82100E-07 8.82100E-07 481300 + 581 491140 In-114 3.76150E-11 2.42980E-10 491140 + 582 491141 In-114m 6.97700E-11 2.12820E-10 491141 + 583 491142 In-114m 1.43050E-10 1.43050E-10 491142 + 584 491150 In-115 1.97110E-08 9.25110E-03 49115.82c + 585 491151 In-115m 2.47610E-09 9.24240E-03 491151 + 586 491160 In-116 5.85480E-07 5.85480E-07 491160 + 587 491161 In-116m 1.08600E-06 3.31250E-06 491161 + 588 491162 In-116m 2.22650E-06 2.22650E-06 491162 + 589 491170 In-117 1.84130E-05 7.07190E-03 491170 + 590 491171 In-117m 2.31300E-06 7.20750E-03 491171 + 591 491180 In-118 1.31610E-05 1.08350E-02 491180 + 592 491181 In-118m 2.44110E-05 7.37600E-05 491181 + 593 491182 In-118m 5.00490E-05 5.00490E-05 491182 + 594 491190 In-119 4.18600E-04 5.20920E-03 491190 + 595 491191 In-119m 5.25840E-05 6.46670E-03 491191 + 596 491200 In-120 3.72500E-04 1.07720E-02 491200 + 597 491201 In-120m 3.72500E-04 3.72500E-04 491201 + 598 491202 In-120m 3.72500E-04 3.72500E-04 491202 + 599 491210 In-121 2.57840E-03 8.72580E-03 491210 + 600 491211 In-121m 3.23900E-04 2.44560E-03 491211 + 601 491220 In-122 1.05240E-03 7.76930E-03 491220 + 602 491221 In-122m 1.50380E-03 1.50380E-03 491221 + 603 491222 In-122m 1.50380E-03 1.50380E-03 491222 + 604 491230 In-123 6.17900E-03 9.29550E-03 491230 + 605 491231 In-123m 7.76200E-04 1.44270E-03 491231 + 606 491240 In-124 2.09420E-03 4.69970E-03 491240 + 607 491241 In-124m 4.01130E-03 4.01130E-03 491241 + 608 491250 In-125 6.67120E-03 7.74300E-03 491250 + 609 491251 In-125m 8.38030E-04 9.55490E-04 491251 + 610 491260 In-126 1.75980E-03 2.35890E-03 491260 + 611 491261 In-126m 3.37080E-03 3.37080E-03 491261 + 612 491270 In-127 4.03630E-03 4.03630E-03 491270 + 613 491271 In-127m 5.07030E-04 6.64870E-04 491271 + 614 491280 In-128 4.46310E-04 6.46290E-04 491280 + 615 491281 In-128m 1.57640E-04 1.99980E-04 491281 + 616 491282 In-128m 1.15720E-03 1.15720E-03 491282 + 617 491290 In-129 5.81710E-04 5.87190E-04 491290 + 618 491291 In-129m 7.30730E-05 7.42810E-05 491291 + 619 491300 In-130 2.83430E-05 2.91940E-05 491300 + 620 491301 In-130m 9.18590E-05 9.18590E-05 491301 + 621 491302 In-130m 6.84980E-05 6.84980E-05 491302 + 622 491310 In-131 1.02260E-05 1.03300E-05 491310 + 623 491311 In-131m 1.02260E-05 1.02260E-05 491311 + 624 491312 In-131m 1.02260E-05 1.02260E-05 491312 + 625 491320 In-132 8.88760E-07 8.88760E-07 491320 + 626 491330 In-133 4.95950E-09 5.58250E-09 491330 + 627 491331 In-133m 6.23010E-10 6.23010E-10 491331 + 628 501170 Sn-117 3.77380E-10 1.08850E-02 50117.82c + 629 501171 Sn-117m 2.33170E-09 2.40970E-05 501171 + 630 501180 Sn-118 1.41450E-06 1.09110E-02 50118.82c + 631 501190 Sn-119 1.21980E-06 1.13220E-02 50119.82c + 632 501191 Sn-119m 7.53670E-06 4.71350E-03 501191 + 633 501200 Sn-120 5.18210E-05 1.15690E-02 50120.82c + 634 501210 Sn-121 3.09030E-05 1.10620E-02 501210 + 635 501211 Sn-121m 1.41840E-04 1.13030E-03 501211 + 636 501220 Sn-122 7.67350E-04 1.15440E-02 50122.82c + 637 501230 Sn-123 1.29180E-03 2.00050E-03 50123.82c + 638 501231 Sn-123m 2.81460E-04 1.03110E-02 501231 + 639 501240 Sn-124 4.35720E-03 1.30680E-02 50124.82c + 640 501250 Sn-125 4.88600E-03 6.19390E-03 50125.82c + 641 501251 Sn-125m 1.06450E-03 8.45510E-03 501251 + 642 501260 Sn-126 1.12480E-02 1.69820E-02 50126.82c + 643 501270 Sn-127 1.00340E-02 1.16070E-02 501270 + 644 501271 Sn-127m 2.18620E-03 5.30950E-03 501271 + 645 501280 Sn-128 2.30180E-03 1.45000E-02 501280 + 646 501281 Sn-128m 1.03940E-02 1.15510E-02 501281 + 647 501290 Sn-129 1.22460E-03 1.82370E-03 501290 + 648 501291 Sn-129m 5.62040E-03 5.68290E-03 501291 + 649 501300 Sn-130 1.22330E-03 1.31260E-03 501300 + 650 501301 Sn-130m 5.52400E-03 5.62440E-03 501301 + 651 501310 Sn-131 5.81250E-04 6.01060E-04 501310 + 652 501311 Sn-131m 2.66770E-03 2.67840E-03 501311 + 653 501320 Sn-132 9.68970E-04 9.69860E-04 501320 + 654 501330 Sn-133 7.57720E-05 7.57730E-05 501330 + 655 501340 Sn-134 6.17330E-06 6.17330E-06 501340 + 656 501350 Sn-135 4.08940E-08 4.08940E-08 501350 + 657 501360 Sn-136 1.95700E-09 1.95700E-09 501360 + 658 511210 Sb-121 3.18580E-06 1.13180E-02 51121.82c + 659 511220 Sb-122 1.43340E-06 4.74310E-06 511220 + 660 511221 Sb-122m 3.30970E-06 3.30970E-06 511221 + 661 511230 Sb-123 6.58340E-05 1.23770E-02 51123.82c + 662 511240 Sb-124 4.66720E-05 1.69130E-04 51124.82c + 663 511241 Sb-124m 4.33550E-05 1.63280E-04 511241 + 664 511242 Sb-124m 1.19920E-04 1.19920E-04 511242 + 665 511250 Sb-125 7.98120E-04 1.54470E-02 51125.82c + 666 511260 Sb-126 9.38430E-04 1.03710E-03 51126.82c + 667 511261 Sb-126m 3.39260E-04 7.04470E-04 511261 + 668 511262 Sb-126m 3.65220E-04 3.65220E-04 511262 + 669 511270 Sb-127 4.75560E-03 2.16720E-02 511270 + 670 511280 Sb-128 3.41650E-03 1.80080E-02 511280 + 671 511281 Sb-128m 2.56470E-03 2.56470E-03 511281 + 672 511290 Sb-129 4.12930E-03 1.00620E-02 511290 + 673 511291 Sb-129m 5.60740E-03 8.44880E-03 511291 + 674 511300 Sb-130 6.90250E-03 1.10270E-02 511300 + 675 511301 Sb-130m 6.90250E-03 9.71470E-03 511301 + 676 511310 Sb-131 2.15880E-02 2.48680E-02 511310 + 677 511320 Sb-132 4.77490E-03 5.74480E-03 511320 + 678 511321 Sb-132m 7.59210E-03 7.59210E-03 511321 + 679 511330 Sb-133 7.71650E-03 7.79330E-03 511330 + 680 511340 Sb-134 2.19050E-04 2.24170E-04 511340 + 681 511341 Sb-134m 9.89150E-04 9.89160E-04 511341 + 682 511350 Sb-135 2.25870E-04 2.25900E-04 511350 + 683 511360 Sb-136 2.31630E-05 2.31640E-05 511360 + 684 511370 Sb-137 9.59920E-07 9.59920E-07 511370 + 685 511380 Sb-138 6.22650E-09 6.22650E-09 511380 + 686 521240 Te-124 4.91020E-10 2.09950E-04 52124.82c + 687 521250 Te-125 3.48420E-06 1.54720E-02 52125.82c + 688 521251 Te-125m 2.15280E-05 3.47810E-03 521251 + 689 521260 Te-126 1.25060E-04 1.76800E-03 52126.82c + 690 521270 Te-127 5.28860E-05 2.18760E-02 521270 + 691 521271 Te-127m 2.42730E-04 3.81420E-03 52527.82c + 692 521280 Te-128 9.86400E-04 2.14680E-02 52128.82c + 693 521290 Te-129 3.30000E-04 1.53150E-02 521290 + 694 521291 Te-129m 1.51460E-03 1.01970E-02 52529.82c + 695 521300 Te-130 6.78770E-03 2.75300E-02 52130.82c + 696 521310 Te-131 2.73020E-03 2.86560E-02 521310 + 697 521311 Te-131m 1.25310E-02 1.45220E-02 521311 + 698 521320 Te-132 2.81700E-02 4.15070E-02 52132.82c + 699 521330 Te-133 6.38570E-03 1.81970E-02 521330 + 700 521331 Te-133m 2.93080E-02 3.06560E-02 521331 + 701 521340 Te-134 3.20890E-02 3.33370E-02 521340 + 702 521350 Te-135 9.10520E-03 9.29940E-03 521350 + 703 521360 Te-136 3.05470E-03 3.07450E-03 521360 + 704 521370 Te-137 6.34060E-04 6.34550E-04 521370 + 705 521380 Te-138 1.16040E-04 1.16050E-04 521380 + 706 521390 Te-139 8.72420E-06 8.72420E-06 521390 + 707 521400 Te-140 6.57340E-08 6.57340E-08 521400 + 708 521410 Te-141 1.20830E-09 1.20830E-09 521410 + 709 531270 I-127 4.40010E-06 2.19720E-02 53127.82c + 710 531280 I-128 1.19570E-05 1.19570E-05 531280 + 711 531290 I-129 5.70360E-05 1.91450E-02 53129.82c + 712 531300 I-130 1.91990E-04 2.27710E-04 53130.82c + 713 531301 I-130m 4.25170E-05 4.25170E-05 531301 + 714 531310 I-131 1.22200E-03 4.13500E-02 53131.82c + 715 531320 I-132 1.22500E-03 4.44070E-02 531320 + 716 531321 I-132m 1.94770E-03 1.94770E-03 531321 + 717 531330 I-133 5.05400E-03 5.54050E-02 531330 + 718 531331 I-133m 6.86300E-03 6.86300E-03 531331 + 719 531340 I-134 7.86990E-03 5.34320E-02 531340 + 720 531341 I-134m 1.25130E-02 1.25130E-02 531341 + 721 531350 I-135 3.42250E-02 4.35240E-02 53135.82c + 722 531360 I-136 3.50220E-03 6.58610E-03 531360 + 723 531361 I-136m 1.58150E-02 1.58240E-02 531361 + 724 531370 I-137 1.39380E-02 1.45610E-02 531370 + 725 531380 I-138 3.40990E-03 3.51860E-03 531380 + 726 531390 I-139 1.91340E-03 1.92210E-03 531390 + 727 531400 I-140 3.03120E-04 3.03190E-04 531400 + 728 531410 I-141 4.39950E-05 4.39960E-05 531410 + 729 531420 I-142 6.55330E-06 6.55330E-06 531420 + 730 531430 I-143 9.96600E-09 9.96600E-09 531430 + 731 541290 Xe-129 2.06370E-07 1.48150E-06 54129.82c + 732 541291 Xe-129m 1.27510E-06 1.27510E-06 541291 + 733 541300 Xe-130 7.93870E-06 2.42450E-04 54130.82c + 734 541310 Xe-131 6.77310E-06 4.13880E-02 54131.82c + 735 541311 Xe-131m 3.10870E-05 4.80230E-04 541311 + 736 541320 Xe-132 6.19240E-05 4.48850E-02 54132.82c + 737 541321 Xe-132m 1.42990E-04 1.42990E-04 541321 + 738 541330 Xe-133 1.59660E-04 5.62980E-02 54133.82c + 739 541331 Xe-133m 7.32820E-04 2.30990E-03 541331 + 740 541340 Xe-134 7.36400E-04 5.77820E-02 54134.82c + 741 541341 Xe-134m 3.32540E-03 3.61320E-03 541341 + 742 541350 Xe-135 2.00030E-03 5.46070E-02 54135.82c + 743 541351 Xe-135m 9.18070E-03 1.63660E-02 541351 + 744 541360 Xe-136 2.82850E-02 5.16420E-02 54136.82c + 745 541370 Xe-137 3.55650E-02 4.93660E-02 541370 + 746 541380 Xe-138 3.44600E-02 3.79810E-02 541380 + 747 541390 Xe-139 2.06160E-02 2.23780E-02 541390 + 748 541400 Xe-140 1.24990E-02 1.27830E-02 541400 + 749 541410 Xe-141 3.75470E-03 3.79110E-03 541410 + 750 541420 Xe-142 1.19980E-03 1.20470E-03 541420 + 751 541430 Xe-143 1.81900E-04 1.81910E-04 541430 + 752 541440 Xe-144 2.31730E-05 2.31730E-05 541440 + 753 541450 Xe-145 2.11930E-06 2.11930E-06 541450 + 754 541460 Xe-146 7.57990E-10 7.57990E-10 541460 + 755 551320 Cs-132 6.47890E-09 6.47890E-09 551320 + 756 551330 Cs-133 9.71900E-06 5.63070E-02 55133.82c + 757 551340 Cs-134 1.66770E-05 4.31930E-05 55134.82c + 758 551341 Cs-134m 2.65160E-05 2.65160E-05 551341 + 759 551350 Cs-135 1.48260E-04 5.50550E-02 55135.82c + 760 551351 Cs-135m 2.01320E-04 2.01320E-04 551351 + 761 551360 Cs-136 5.92300E-04 9.86800E-04 55136.82c + 762 551361 Cs-136m 7.89000E-04 7.89000E-04 551361 + 763 551370 Cs-137 7.64740E-03 5.70130E-02 55137.82c + 764 551380 Cs-138 3.10990E-03 4.82900E-02 551380 + 765 551381 Cs-138m 8.88810E-03 8.88810E-03 551381 + 766 551390 Cs-139 2.18560E-02 4.42340E-02 551390 + 767 551400 Cs-140 1.84490E-02 3.12340E-02 551400 + 768 551410 Cs-141 2.14700E-02 2.52640E-02 551410 + 769 551420 Cs-142 1.13460E-02 1.25480E-02 551420 + 770 551430 Cs-143 5.96390E-03 6.14470E-03 551430 + 771 551440 Cs-144 6.85800E-04 1.05130E-03 551440 + 772 551441 Cs-144m 6.85800E-04 6.85850E-04 551441 + 773 551450 Cs-145 2.93120E-04 2.95130E-04 551450 + 774 551460 Cs-146 4.19910E-05 4.19920E-05 551460 + 775 551470 Cs-147 3.84350E-06 3.84350E-06 551470 + 776 551480 Cs-148 8.82650E-07 8.82650E-07 551480 + 777 561340 Ba-134 2.09900E-09 4.31950E-05 56134.82c + 778 561350 Ba-135 5.93300E-07 3.31640E-06 56135.82c + 779 561351 Ba-135m 2.72310E-06 2.72310E-06 561351 + 780 561360 Ba-136 6.71640E-06 1.41840E-03 56136.82c + 781 561361 Ba-136m 3.03300E-05 3.03300E-05 561361 + 782 561370 Ba-137 5.31980E-05 5.73110E-02 56137.82c + 783 561371 Ba-137m 2.44160E-04 5.40640E-02 561371 + 784 561380 Ba-138 2.14540E-03 5.21240E-02 56138.82c + 785 561390 Ba-139 5.79770E-03 5.00320E-02 561390 + 786 561400 Ba-140 1.36950E-02 4.49290E-02 56140.82c + 787 561410 Ba-141 1.77250E-02 4.29890E-02 561410 + 788 561420 Ba-142 3.04630E-02 4.31120E-02 561420 + 789 561430 Ba-143 2.55110E-02 3.15880E-02 561430 + 790 561440 Ba-144 1.63300E-02 1.77330E-02 561440 + 791 561450 Ba-145 6.58800E-03 6.84690E-03 561450 + 792 561460 Ba-146 2.56060E-03 2.59770E-03 561460 + 793 561470 Ba-147 5.46580E-04 5.49550E-04 561470 + 794 561480 Ba-148 5.23650E-05 5.30260E-05 561480 + 795 561490 Ba-149 1.25740E-05 1.25740E-05 561490 + 796 561500 Ba-150 1.57130E-06 1.57130E-06 561500 + 797 561510 Ba-151 2.24070E-10 2.24070E-10 561510 + 798 571370 La-137 2.87990E-06 2.87990E-06 571370 + 799 571380 La-138 1.29830E-05 1.29830E-05 57138.82c + 800 571390 La-139 1.02610E-04 5.01360E-02 57139.82c + 801 571400 La-140 3.54170E-04 4.52830E-02 57140.82c + 802 571410 La-141 1.51810E-03 4.45070E-02 571410 + 803 571420 La-142 2.78780E-03 4.59000E-02 571420 + 804 571430 La-143 8.98160E-03 4.05700E-02 571430 + 805 571440 La-144 1.10740E-02 2.88070E-02 571440 + 806 571450 La-145 1.32840E-02 2.01310E-02 571450 + 807 571460 La-146 1.59610E-03 4.19390E-03 571460 + 808 571461 La-146m 5.58400E-03 5.58400E-03 571461 + 809 571470 La-147 4.81380E-03 5.36360E-03 571470 + 810 571480 La-148 8.86990E-04 9.39860E-04 571480 + 811 571490 La-149 4.23690E-04 4.36210E-04 571490 + 812 571500 La-150 9.53130E-05 9.68840E-05 571500 + 813 571510 La-151 1.30400E-05 1.30400E-05 571510 + 814 571520 La-152 3.31330E-06 3.31330E-06 571520 + 815 571530 La-153 1.08260E-09 1.08260E-09 571530 + 816 581390 Ce-139 3.90180E-07 2.18100E-06 581390 + 817 581391 Ce-139m 1.79080E-06 1.79080E-06 581391 + 818 581400 Ce-140 9.22940E-06 4.52920E-02 58140.82c + 819 581410 Ce-141 3.22370E-05 4.45390E-02 58141.82c + 820 581420 Ce-142 2.27680E-04 4.61280E-02 58142.82c + 821 581430 Ce-143 6.88330E-04 4.12580E-02 58143.82c + 822 581440 Ce-144 2.76790E-03 3.15750E-02 58144.82c + 823 581450 Ce-145 5.42050E-03 2.55510E-02 581450 + 824 581460 Ce-146 1.08060E-02 2.05840E-02 581460 + 825 581470 Ce-147 1.02570E-02 1.56210E-02 581470 + 826 581480 Ce-148 4.18630E-03 5.13230E-03 581480 + 827 581490 Ce-149 3.11380E-03 3.54650E-03 581490 + 828 581500 Ce-150 1.97480E-03 2.06910E-03 581500 + 829 581510 Ce-151 6.48380E-04 6.61620E-04 581510 + 830 581520 Ce-152 1.85150E-04 1.88260E-04 581520 + 831 581530 Ce-153 1.86020E-05 1.86030E-05 581530 + 832 581540 Ce-154 2.37430E-06 2.37430E-06 581540 + 833 581550 Ce-155 2.26660E-09 2.26660E-09 581550 + 834 581560 Ce-156 3.84740E-11 3.84740E-11 581560 + 835 591420 Pr-142 6.12430E-10 3.37800E-09 59142.82c + 836 591421 Pr-142m 2.76560E-09 2.76560E-09 591421 + 837 591430 Pr-143 4.72730E-06 4.12630E-02 59143.82c + 838 591440 Pr-144 9.21190E-07 3.15900E-02 591440 + 839 591441 Pr-144m 1.49070E-05 4.50620E-04 591441 + 840 591450 Pr-145 9.51430E-05 2.56460E-02 591450 + 841 591460 Pr-146 3.11520E-04 2.08950E-02 591460 + 842 591470 Pr-147 1.02790E-03 1.66490E-02 591470 + 843 591480 Pr-148 9.04570E-05 5.22270E-03 591480 + 844 591481 Pr-148m 7.09340E-04 7.09340E-04 591481 + 845 591490 Pr-149 2.04780E-03 5.59430E-03 591490 + 846 591500 Pr-150 2.40290E-03 4.47200E-03 591500 + 847 591510 Pr-151 2.32020E-03 2.98180E-03 591510 + 848 591520 Pr-152 1.23560E-03 1.42400E-03 591520 + 849 591530 Pr-153 5.62210E-04 5.80710E-04 591530 + 850 591540 Pr-154 1.32910E-04 1.35270E-04 591540 + 851 591550 Pr-155 3.15250E-05 3.15270E-05 591550 + 852 591560 Pr-156 3.12280E-06 3.12280E-06 591560 + 853 591570 Pr-157 7.75390E-09 7.75390E-09 591570 + 854 591580 Pr-158 9.73280E-11 9.73280E-11 591580 + 855 601440 Nd-144 1.05350E-06 3.15920E-02 60144.82c + 856 601450 Nd-145 1.05970E-06 2.56480E-02 60145.82c + 857 601460 Nd-146 7.00870E-06 2.09020E-02 60146.82c + 858 601470 Nd-147 3.17150E-05 1.66800E-02 60147.82c + 859 601480 Nd-148 7.84740E-05 6.01050E-03 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Sm-153m 2.19480E-05 2.19480E-05 621531 + 899 621540 Sm-154 8.06840E-05 1.52500E-03 62154.82c + 900 621550 Sm-155 1.02190E-04 8.21730E-04 621550 + 901 621560 Sm-156 1.59210E-04 5.16050E-04 621560 + 902 621570 Sm-157 1.62920E-04 3.32580E-04 621570 + 903 621580 Sm-158 1.45850E-04 1.80520E-04 621580 + 904 621590 Sm-159 6.54630E-05 8.60810E-05 621590 + 905 621600 Sm-160 4.73920E-05 4.78550E-05 621600 + 906 621610 Sm-161 1.43200E-05 1.43470E-05 621610 + 907 621620 Sm-162 6.42160E-07 6.42830E-07 621620 + 908 621630 Sm-163 4.53450E-08 4.53680E-08 621630 + 909 621640 Sm-164 6.98920E-10 6.98920E-10 621640 + 910 621650 Sm-165 3.70150E-11 3.70150E-11 621650 + 911 631520 Eu-152 2.40740E-11 7.96280E-11 63152.82c + 912 631521 Eu-152m 4.92130E-12 4.92130E-12 631521 + 913 631522 Eu-152m 5.55550E-11 5.55550E-11 631522 + 914 631530 Eu-153 5.18090E-09 2.30580E-03 63153.82c + 915 631540 Eu-154 2.39050E-08 6.96940E-08 63154.82c + 916 631541 Eu-154m 4.57890E-08 4.57890E-08 631541 + 917 631550 Eu-155 1.12340E-06 8.22860E-04 63155.82c + 918 631560 Eu-156 5.20330E-06 5.21250E-04 63156.82c + 919 631570 Eu-157 2.47180E-05 3.57300E-04 63157.82c + 920 631580 Eu-158 2.86920E-05 2.09220E-04 631580 + 921 631590 Eu-159 3.51560E-05 1.21240E-04 631590 + 922 631600 Eu-160 4.46840E-05 9.25380E-05 631600 + 923 631610 Eu-161 2.29120E-05 3.72590E-05 631610 + 924 631620 Eu-162 5.33120E-06 5.97400E-06 631620 + 925 631630 Eu-163 6.22120E-06 6.26660E-06 631630 + 926 631640 Eu-164 1.38560E-07 1.39260E-07 631640 + 927 631650 Eu-165 5.28140E-08 5.28510E-08 631650 + 928 631660 Eu-166 9.26870E-10 9.26870E-10 631660 + 929 631670 Eu-167 5.15900E-11 5.15900E-11 631670 + 930 641550 Gd-155 3.54310E-11 8.22860E-04 64155.82c + 931 641551 Gd-155m 1.62620E-10 1.62620E-10 641551 + 932 641560 Gd-156 6.30970E-09 5.21260E-04 64156.82c + 933 641570 Gd-157 6.91510E-08 3.57370E-04 64157.82c + 934 641580 Gd-158 3.58660E-06 2.12800E-04 64158.82c + 935 641590 Gd-159 6.06140E-06 1.27300E-04 641590 + 936 641600 Gd-160 1.35410E-05 1.06080E-04 64160.82c + 937 641610 Gd-161 1.28880E-05 5.01470E-05 641610 + 938 641620 Gd-162 2.53230E-05 3.12970E-05 641620 + 939 641630 Gd-163 1.49310E-05 2.11980E-05 641630 + 940 641640 Gd-164 4.11510E-06 4.25440E-06 641640 + 941 641650 Gd-165 4.12210E-06 4.17490E-06 641650 + 942 641660 Gd-166 1.23570E-06 1.23660E-06 641660 + 943 641670 Gd-167 2.30110E-08 2.30630E-08 641670 + 944 641680 Gd-168 2.01010E-09 2.01010E-09 641680 + 945 641690 Gd-169 8.50740E-11 8.50740E-11 641690 + 946 651570 Tb-157 1.18740E-11 1.18740E-11 651570 + 947 651580 Tb-158 2.36390E-10 2.50910E-10 651580 + 948 651581 Tb-158m 1.46080E-11 1.46080E-11 651581 + 949 651590 Tb-159 6.07060E-09 1.27310E-04 65159.82c + 950 651600 Tb-160 6.31420E-08 6.31420E-08 65160.82c + 951 651610 Tb-161 4.23330E-07 5.05710E-05 651610 + 952 651620 Tb-162 1.33280E-06 3.26300E-05 651620 + 953 651630 Tb-163 4.97690E-06 2.61750E-05 651630 + 954 651640 Tb-164 1.36510E-06 5.61950E-06 651640 + 955 651650 Tb-165 2.06100E-06 6.23590E-06 651650 + 956 651660 Tb-166 9.40580E-07 2.17720E-06 651660 + 957 651670 Tb-167 6.70830E-07 6.93890E-07 651670 + 958 651680 Tb-168 9.78160E-08 9.98260E-08 651680 + 959 651690 Tb-169 2.85940E-08 2.86790E-08 651690 + 960 651700 Tb-170 7.78410E-09 7.78410E-09 651700 + 961 651710 Tb-171 1.89970E-10 1.89970E-10 651710 + 962 661600 Dy-160 2.33810E-11 6.31650E-08 66160.82c + 963 661610 Dy-161 3.24150E-10 5.05710E-05 66161.82c + 964 661620 Dy-162 6.62360E-09 3.26360E-05 66162.82c + 965 661630 Dy-163 5.33310E-08 2.62280E-05 66163.82c + 966 661640 Dy-164 9.38030E-08 5.71330E-06 66164.82c + 967 661650 Dy-165 9.51350E-07 7.26480E-06 661650 + 968 661651 Dy-165m 7.92530E-08 7.92530E-08 661651 + 969 661660 Dy-166 6.17860E-07 2.79510E-06 661660 + 970 661670 Dy-167 6.70830E-07 1.36470E-06 661670 + 971 661680 Dy-168 5.54810E-07 6.54640E-07 661680 + 972 661690 Dy-169 5.34320E-07 5.63000E-07 661690 + 973 661700 Dy-170 4.06310E-07 4.14090E-07 661700 + 974 661710 Dy-171 2.03570E-08 2.05470E-08 661710 + 975 661720 Dy-172 4.85070E-09 4.85070E-09 661720 + 976 661730 Dy-173 1.55190E-09 1.55190E-09 661730 + 977 671630 Ho-163 2.80550E-11 3.03920E-11 671630 + 978 671631 Ho-163m 2.33710E-12 2.33710E-12 671631 + 979 671640 Ho-164 1.94500E-11 1.07280E-10 671640 + 980 671641 Ho-164m 8.78300E-11 8.78300E-11 671641 + 981 671650 Ho-165 4.71520E-09 7.27130E-06 67165.82c + 982 671660 Ho-166 1.70560E-09 2.79680E-06 671660 + 983 671661 Ho-166m 7.70220E-09 7.70220E-09 671661 + 984 671670 Ho-167 6.03210E-08 1.42500E-06 671670 + 985 671680 Ho-168 2.24580E-08 7.40960E-07 671680 + 986 671681 Ho-168m 6.41860E-08 6.41860E-08 671681 + 987 671690 Ho-169 2.30820E-07 7.93820E-07 671690 + 988 671700 Ho-170 6.65300E-07 6.65300E-07 671700 + 989 671701 Ho-170m 1.47330E-07 5.61420E-07 671701 + 990 671710 Ho-171 1.55340E-07 1.75890E-07 671710 + 991 671720 Ho-172 6.18670E-08 6.67180E-08 671720 + 992 671730 Ho-173 1.28610E-07 1.30160E-07 671730 + 993 671740 Ho-174 2.66790E-08 2.66790E-08 671740 + 994 671750 Ho-175 4.37330E-09 4.37330E-09 671750 + 995 681660 Er-166 1.21740E-11 2.79680E-06 68166.82c + 996 681670 Er-167 1.43380E-10 1.42520E-06 68167.82c + 997 681671 Er-167m 1.19450E-11 1.70290E-07 681671 + 998 681680 Er-168 1.54880E-09 7.42830E-07 68168.82c + 999 681690 Er-169 7.47200E-09 8.01290E-07 681690 + 1000 681700 Er-170 1.20260E-07 1.34700E-06 68170.82c + 1001 681710 Er-171 4.91610E-08 2.25050E-07 681710 + 1002 681720 Er-172 1.08640E-07 1.75360E-07 681720 + 1003 681730 Er-173 5.88810E-07 7.18970E-07 681730 + 1004 681740 Er-174 6.00180E-07 6.26860E-07 681740 + 1005 681750 Er-175 1.19210E-07 1.23580E-07 681750 + 1006 681760 Er-176 3.97530E-09 3.97530E-09 681760 + 1007 681770 Er-177 3.82920E-10 3.82920E-10 681770 + 1008 691690 Tm-169 1.44720E-11 8.01310E-07 691690 + 1009 691700 Tm-170 4.55060E-10 4.55060E-10 691700 + 1010 691710 Tm-171 1.26280E-09 2.26310E-07 691710 + 1011 691720 Tm-172 4.90820E-09 1.80270E-07 691720 + 1012 691730 Tm-173 9.35660E-08 8.12540E-07 691730 + 1013 691740 Tm-174 1.76520E-07 8.03380E-07 691740 + 1014 691750 Tm-175 2.76000E-07 3.99580E-07 691750 + 1015 691760 Tm-176 1.43960E-08 1.83710E-08 691760 + 1016 691770 Tm-177 8.36900E-09 8.75190E-09 691770 + 1017 691780 Tm-178 1.60160E-09 1.60160E-09 691780 + 1018 691790 Tm-179 4.43880E-10 4.43880E-10 691790 + 1019 701720 Yb-172 2.14170E-11 1.80290E-07 701720 + 1020 701730 Yb-173 7.83260E-10 8.13320E-07 701730 + 1021 701740 Yb-174 9.77460E-09 8.13160E-07 701740 + 1022 701750 Yb-175 3.81780E-07 8.13160E-07 701750 + 1023 701751 Yb-175m 3.18040E-08 3.39480E-07 701751 + 1024 701760 Yb-176 1.75230E-09 2.47220E-08 701760 + 1025 701761 Yb-176m 6.13010E-09 1.53160E-08 701761 + 1026 701770 Yb-177 6.22830E-09 1.57630E-08 701770 + 1027 701771 Yb-177m 7.82390E-10 9.53430E-09 701771 + 1028 701780 Yb-178 7.47160E-09 9.07320E-09 701780 + 1029 701790 Yb-179 3.32020E-09 3.76410E-09 701790 + 1030 701800 Yb-180 1.67320E-09 1.67320E-09 701800 + 1031 701810 Yb-181 2.67380E-10 2.67380E-10 701810 + 1032 711740 Lu-174 1.59780E-12 8.77140E-12 711740 + 1033 711741 Lu-174m 7.21540E-12 7.21540E-12 711741 + 1034 711750 Lu-175 1.67380E-10 8.13330E-07 71175.82c + 1035 711760 Lu-176 7.39100E-11 1.60550E-09 71176.82c + 1036 711761 Lu-176m 2.11270E-11 2.11270E-11 711761 + 1037 711770 Lu-177 2.76080E-10 1.60950E-08 711770 + 1038 711771 Lu-177m 2.30000E-10 2.48640E-10 711771 + 1039 711772 Lu-177m 3.72740E-11 3.72740E-11 711772 + 1040 711780 Lu-178 2.89190E-10 9.36240E-09 711780 + 1041 711781 Lu-178m 6.67750E-10 6.67750E-10 711781 + 1042 711790 Lu-179 2.22290E-09 6.17220E-09 711790 + 1043 711791 Lu-179m 1.85180E-10 3.94930E-09 711791 + 1044 711800 Lu-180 3.56450E-10 1.93820E-09 711800 + 1045 711801 Lu-180m 3.56450E-10 2.02960E-09 711801 + 1046 711802 Lu-180m 1.13380E-09 1.13380E-09 711802 + 1047 711810 Lu-181 1.67030E-09 1.93770E-09 711810 + 1048 711820 Lu-182 5.66820E-10 5.66820E-10 711820 + 1049 711830 Lu-183 2.44570E-10 2.44570E-10 711830 + 1050 711840 Lu-184 3.04510E-11 3.04510E-11 711840 + 1051 721770 Hf-177 5.61650E-13 1.63070E-08 72177.82c + 1052 721771 Hf-177m 4.57530E-13 2.11630E-10 721771 + 1053 721772 Hf-177m 8.63320E-14 1.87240E-11 721772 + 1054 721780 Hf-178 3.02860E-12 1.00440E-08 72178.82c + 1055 721781 Hf-178m 8.03000E-12 6.78350E-10 721781 + 1056 721782 Hf-178m 2.56540E-12 2.56540E-12 721782 + 1057 721790 Hf-179 2.98960E-11 6.23490E-09 72179.82c + 1058 721791 Hf-179m 7.00340E-12 7.00340E-12 721791 + 1059 721792 Hf-179m 2.58550E-11 2.58550E-11 721792 + 1060 721800 Hf-180 6.66920E-11 3.81740E-09 72180.82c + 1061 721801 Hf-180m 2.33320E-10 8.00220E-10 721801 + 1062 721810 Hf-181 4.35390E-10 2.37310E-09 721810 + 1063 721820 Hf-182 1.82960E-10 1.01860E-09 721820 + 1064 721821 Hf-182m 6.40070E-10 6.40070E-10 721821 + 1065 721830 Hf-183 5.43140E-10 7.87710E-10 721830 + 1066 721840 Hf-184 8.71150E-11 1.02340E-10 721840 + 1067 721841 Hf-184m 3.04760E-10 3.19990E-10 721841 + 1068 721850 Hf-185 1.12320E-10 1.12320E-10 721850 + 1069 721860 Hf-186 4.05160E-11 4.05160E-11 721860 + 1070 721870 Hf-187 4.20510E-12 4.20510E-12 721870 + 1071 731810 Ta-181 8.94790E-12 2.38200E-09 73181.82c + 1072 731820 Ta-182 6.69150E-12 4.01340E-10 73182.82c + 1073 731821 Ta-182m 8.75640E-12 3.94650E-10 731821 + 1074 731822 Ta-182m 1.46530E-11 3.85890E-10 731822 + 1075 731830 Ta-183 1.20000E-10 9.07710E-10 731830 + 1076 731840 Ta-184 1.35500E-10 5.57830E-10 731840 + 1077 731850 Ta-185 1.00400E-10 3.27130E-10 731850 + 1078 731851 Ta-185m 1.14410E-10 1.14410E-10 731851 + 1079 731860 Ta-186 1.20240E-10 1.60760E-10 731860 + 1080 731870 Ta-187 7.44150E-11 7.86200E-11 731870 + 1081 731880 Ta-188 1.56210E-11 1.56210E-11 731880 + 1082 731890 Ta-189 4.71150E-12 4.71150E-12 731890 + 1083 741840 W-184 6.03440E-12 5.63860E-10 74184.82c + 1084 741850 W-185 2.95420E-12 3.43640E-10 741850 + 1085 741851 W-185m 1.35590E-11 1.35590E-11 741851 + 1086 741860 W-186 2.99150E-11 2.14940E-10 74186.82c + 1087 741861 W-186m 2.42690E-11 2.42690E-11 741861 + 1088 741870 W-187 5.15480E-11 1.30170E-10 741870 + 1089 741880 W-188 6.00260E-11 7.56470E-11 741880 + 1090 741890 W-189 2.87290E-11 3.34410E-11 741890 + 1091 741900 W-190 4.63000E-12 1.53210E-11 741900 + 1092 741901 W-190m 1.06910E-11 1.06910E-11 741901 + 1093 741910 W-191 2.68960E-12 2.68960E-12 741910 + 1094 751870 Re-187 3.23060E-12 1.33400E-10 75187.82c + 1095 751880 Re-188 1.14090E-12 8.19400E-11 751880 + 1096 751881 Re-188m 5.15210E-12 5.15210E-12 751881 + 1097 751890 Re-189 1.72020E-11 5.06430E-11 751890 + 1098 751900 Re-190 3.10640E-12 2.33830E-11 751900 + 1099 751901 Re-190m 1.08680E-11 1.08680E-11 751901 + 1100 751910 Re-191 1.37820E-11 1.64720E-11 751910 + 1101 751920 Re-192 5.12210E-12 5.12210E-12 751920 + 1102 751930 Re-193 2.34550E-12 2.34550E-12 751930 + 1103 761900 Os-190 5.57890E-13 3.11410E-11 761900 + 1104 761901 Os-190m 1.28820E-12 7.20020E-12 761901 + 1105 761910 Os-191 2.54280E-12 1.94260E-11 761910 + 1106 761920 Os-192 1.85840E-12 1.07410E-11 761920 + 1107 761921 Os-192m 4.29130E-12 4.29130E-12 761921 + 1108 761930 Os-193 4.29370E-12 6.63920E-12 761930 + 1109 761940 Os-194 3.31630E-12 3.31630E-12 761940 + 1110 761950 Os-195 1.04300E-12 1.04300E-12 761950 + 1111 771950 Ir-195 2.94970E-13 1.40570E-12 771950 + 1112 771951 Ir-195m 1.35380E-12 1.35380E-12 771951 + + Nuclide 92236.82c -- uranium 236 (U-236) + + Neutron-induced fission: + + Interpolation region : 1 / 2 + Interpolation energy : 2.53000E-08 MeV + Number of products : 811 / 920 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 3.33770E-05 3.33770E-05 1001.82c + 2 10020 H-2 8.46600E-06 8.46600E-06 1002.82c + 3 10030 H-3 1.14000E-04 1.14000E-04 1003.82c + 4 20040 He-4 2.11000E-03 2.11000E-03 2004.82c + 5 230590 V-59 1.09560E-12 1.09560E-12 230590 + 6 230600 V-60 7.13840E-11 7.13840E-11 230600 + 7 230610 V-61 5.46880E-11 5.46880E-11 230610 + 8 230620 V-62 7.73020E-12 7.73020E-12 230620 + 9 240590 Cr-59 2.47900E-12 3.57460E-12 240590 + 10 240600 Cr-60 1.42070E-09 1.49540E-09 240600 + 11 240610 Cr-61 2.16440E-09 2.21580E-09 240610 + 12 240620 Cr-62 3.44920E-09 3.45690E-09 240620 + 13 240630 Cr-63 1.07330E-09 1.07330E-09 240630 + 14 240640 Cr-64 3.89480E-10 3.89480E-10 240640 + 15 240650 Cr-65 3.78060E-11 3.78060E-11 240650 + 16 240660 Cr-66 2.83730E-12 2.83730E-12 240660 + 17 250600 Mn-60 3.12220E-11 1.55850E-09 250600 + 18 250601 Mn-60m 2.77300E-10 2.77300E-10 250601 + 19 250610 Mn-61 3.80420E-09 6.02000E-09 250610 + 20 250620 Mn-62 8.49500E-09 1.02230E-08 250620 + 21 250621 Mn-62m 1.52500E-09 3.25350E-09 250621 + 22 250630 Mn-63 2.90250E-08 3.00980E-08 250630 + 23 250640 Mn-64 2.21730E-08 2.25630E-08 250640 + 24 250650 Mn-65 2.53000E-08 2.53380E-08 250650 + 25 250660 Mn-66 4.72890E-09 4.73170E-09 250660 + 26 250670 Mn-67 9.06890E-10 9.06890E-10 250670 + 27 250680 Mn-68 3.92170E-11 3.92170E-11 250680 + 28 250690 Mn-69 1.57590E-12 1.57590E-12 250690 + 29 260600 Fe-60 5.20510E-12 1.80910E-09 260600 + 30 260610 Fe-61 1.35530E-10 6.15550E-09 260610 + 31 260620 Fe-62 3.33400E-09 1.68110E-08 260620 + 32 260630 Fe-63 1.59940E-08 4.60920E-08 260630 + 33 260640 Fe-64 9.88320E-08 1.21390E-07 260640 + 34 260650 Fe-65 1.94680E-07 2.20020E-07 260650 + 35 260660 Fe-66 3.59700E-07 3.64430E-07 260660 + 36 260670 Fe-67 1.52820E-07 1.53730E-07 260670 + 37 260680 Fe-68 8.04000E-08 8.04400E-08 260680 + 38 260690 Fe-69 8.47930E-09 8.48050E-09 260690 + 39 260700 Fe-70 7.85820E-10 7.85820E-10 260700 + 40 260710 Fe-71 2.11690E-11 2.11690E-11 260710 + 41 270620 Co-62 2.14470E-12 1.68130E-08 270620 + 42 270621 Co-62m 5.02350E-12 5.02350E-12 270621 + 43 270630 Co-63 3.88660E-10 4.64810E-08 270630 + 44 270640 Co-64 4.79170E-09 1.26190E-07 270640 + 45 270650 Co-65 8.32620E-08 3.03280E-07 270650 + 46 270660 Co-66 2.47990E-07 6.12420E-07 270660 + 47 270670 Co-67 8.70600E-07 1.02430E-06 270670 + 48 270680 Co-68 4.43890E-07 6.80200E-07 270680 + 49 270681 Co-68m 3.91590E-07 4.72620E-07 270681 + 50 270690 Co-69 9.23080E-07 9.30970E-07 270690 + 51 270700 Co-70 9.89700E-08 9.89700E-08 270700 + 52 270701 Co-70m 9.89700E-08 9.97560E-08 270701 + 53 270710 Co-71 6.65870E-08 6.66080E-08 270710 + 54 270720 Co-72 4.72800E-09 4.72800E-09 270720 + 55 270730 Co-73 3.79090E-10 3.79090E-10 270730 + 56 270740 Co-74 1.09330E-11 1.09330E-11 270740 + 57 280640 Ni-64 1.30000E-11 1.26200E-07 28064.82c + 58 280650 Ni-65 5.32580E-10 3.03810E-07 280650 + 59 280660 Ni-66 1.70730E-08 6.29500E-07 280660 + 60 280670 Ni-67 1.12620E-07 1.13690E-06 280670 + 61 280680 Ni-68 9.09260E-07 1.83510E-06 280680 + 62 280690 Ni-69 8.05150E-07 1.72680E-06 280690 + 63 280691 Ni-69m 8.05150E-07 8.05150E-07 280691 + 64 280700 Ni-70 2.97010E-06 3.16880E-06 280700 + 65 280710 Ni-71 1.93490E-06 2.00150E-06 280710 + 66 280720 Ni-72 1.51680E-06 1.52150E-06 280720 + 67 280730 Ni-73 2.91650E-07 2.92030E-07 280730 + 68 280740 Ni-74 1.07090E-07 1.07100E-07 280740 + 69 280750 Ni-75 1.19910E-08 1.19910E-08 280750 + 70 280760 Ni-76 1.07370E-09 1.07370E-09 280760 + 71 280770 Ni-77 4.08570E-11 4.08570E-11 280770 + 72 290660 Cu-66 5.65350E-12 6.29500E-07 290660 + 73 290670 Cu-67 4.60120E-10 1.13740E-06 290670 + 74 290680 Cu-68 2.51870E-09 1.84260E-06 290680 + 75 290681 Cu-68m 5.89940E-09 5.89940E-09 290681 + 76 290690 Cu-69 1.51790E-07 2.68370E-06 290690 + 77 290700 Cu-70 3.77660E-08 3.28300E-07 290700 + 78 290701 Cu-70m 4.20740E-07 5.81070E-07 290701 + 79 290702 Cu-70m 3.77660E-08 3.20660E-06 290702 + 80 290710 Cu-71 2.63610E-06 4.63760E-06 290710 + 81 290720 Cu-72 3.36800E-06 4.88950E-06 290720 + 82 290730 Cu-73 5.87430E-06 6.16630E-06 290730 + 83 290740 Cu-74 4.43030E-06 4.53760E-06 290740 + 84 290750 Cu-75 5.72970E-06 5.74150E-06 290750 + 85 290760 Cu-76 6.34200E-07 6.34740E-07 290760 + 86 290761 Cu-76m 6.34200E-07 6.34740E-07 290761 + 87 290770 Cu-77 5.75530E-07 5.75570E-07 290770 + 88 290780 Cu-78 2.67850E-08 2.67850E-08 290780 + 89 290790 Cu-79 1.72950E-09 1.72950E-09 290790 + 90 300680 Zn-68 3.42170E-12 1.84350E-06 300680 + 91 300690 Zn-69 2.90620E-11 2.68390E-06 300690 + 92 300691 Zn-69m 1.25690E-10 1.25690E-10 300691 + 93 300700 Zn-70 6.05600E-09 3.67110E-06 300700 + 94 300710 Zn-71 1.30570E-08 4.65070E-06 300710 + 95 300711 Zn-71m 5.64710E-08 5.64710E-08 300711 + 96 300720 Zn-72 8.52090E-07 5.74160E-06 300720 + 97 300730 Zn-73 2.47800E-07 7.71240E-06 300730 + 98 300731 Zn-73m 3.38760E-07 1.29830E-06 300731 + 99 300732 Zn-73m 1.91900E-06 1.91900E-06 300732 + 100 300740 Zn-74 1.81520E-05 2.28910E-05 300740 + 101 300750 Zn-75 2.61580E-05 3.17180E-05 300750 + 102 300760 Zn-76 1.07010E-04 1.08260E-04 300760 + 103 300770 Zn-77 4.16670E-05 4.54280E-05 300770 + 104 300771 Zn-77m 6.36970E-06 6.36970E-06 300771 + 105 300780 Zn-78 1.08930E-04 1.08960E-04 300780 + 106 300790 Zn-79 4.40330E-05 4.40340E-05 300790 + 107 300800 Zn-80 2.63300E-05 2.63300E-05 300800 + 108 300810 Zn-81 3.70480E-08 3.70480E-08 300810 + 109 300820 Zn-82 1.44300E-09 1.44300E-09 300820 + 110 310710 Ga-71 4.34290E-11 4.70720E-06 310710 + 111 310720 Ga-72 1.17960E-09 5.74290E-06 310720 + 112 310721 Ga-72m 1.32810E-10 1.91450E-07 310721 + 113 310730 Ga-73 4.44660E-08 8.71640E-06 310730 + 114 310740 Ga-74 2.76960E-07 1.76530E-05 310740 + 115 310741 Ga-74m 2.76960E-07 2.31680E-05 310741 + 116 310750 Ga-75 2.61580E-05 5.78760E-05 310750 + 117 310760 Ga-76 3.79600E-05 1.46220E-04 310760 + 118 310770 Ga-77 1.92150E-04 2.40760E-04 310770 + 119 310780 Ga-78 3.26800E-04 4.36330E-04 310780 + 120 310790 Ga-79 3.08230E-04 3.51690E-04 310790 + 121 310800 Ga-80 2.36970E-04 2.63300E-04 310800 + 122 310810 Ga-81 1.48330E-04 1.48360E-04 310810 + 123 310820 Ga-82 2.45940E-05 2.45950E-05 310820 + 124 310830 Ga-83 9.97380E-07 9.97380E-07 310830 + 125 310840 Ga-84 2.36940E-08 2.36940E-08 310840 + 126 310850 Ga-85 7.39760E-10 7.39760E-10 310850 + 127 320730 Ge-73 5.44950E-12 8.71640E-06 32073.82c + 128 320731 Ge-73m 1.26000E-12 8.58840E-06 320731 + 129 320740 Ge-74 1.06820E-09 2.34460E-05 32074.82c + 130 320750 Ge-75 6.70320E-09 5.79250E-05 320750 + 131 320751 Ge-75m 4.38490E-08 2.35890E-06 320751 + 132 320760 Ge-76 1.92980E-06 1.48150E-04 32076.82c + 133 320770 Ge-77 1.25000E-04 1.74380E-04 320770 + 134 320771 Ge-77m 1.91090E-05 2.59870E-04 320771 + 135 320780 Ge-78 1.90630E-04 6.27270E-04 320780 + 136 320790 Ge-79 1.14830E-04 4.95750E-04 320790 + 137 320791 Ge-79m 7.51150E-04 7.51680E-04 320791 + 138 320800 Ge-80 1.97470E-03 2.25570E-03 320800 + 139 320810 Ge-81 2.16250E-03 2.23980E-03 320810 + 140 320811 Ge-81m 5.00020E-04 5.64320E-04 320811 + 141 320820 Ge-82 2.83330E-03 2.85300E-03 320820 + 142 320830 Ge-83 1.65640E-03 1.65700E-03 320830 + 143 320840 Ge-84 4.98030E-04 4.98040E-04 320840 + 144 320850 Ge-85 1.23600E-04 1.23600E-04 320850 + 145 320860 Ge-86 1.35770E-05 1.35770E-05 320860 + 146 320870 Ge-87 9.63460E-09 9.63460E-09 320870 + 147 330750 As-75 1.22790E-12 5.79260E-05 33075.82c + 148 330751 As-75m 4.01710E-12 7.11680E-10 330751 + 149 330760 As-76 4.51160E-10 4.51160E-10 330760 + 150 330770 As-77 8.73960E-08 3.84960E-04 330770 + 151 330780 As-78 1.71790E-06 6.28990E-04 330780 + 152 330790 As-79 4.40330E-05 1.26140E-03 330790 + 153 330800 As-80 2.76460E-04 2.53210E-03 330800 + 154 330810 As-81 8.15800E-04 3.61420E-03 330810 + 155 330820 As-82 5.24010E-04 3.37700E-03 330820 + 156 330821 As-82m 1.58130E-03 1.58130E-03 330821 + 157 330830 As-83 4.57800E-03 6.28880E-03 330830 + 158 330840 As-84 1.74160E-03 1.97240E-03 330840 + 159 330841 As-84m 1.74160E-03 1.97240E-03 330841 + 160 330850 As-85 2.36190E-03 2.46820E-03 330850 + 161 330860 As-86 8.30140E-04 8.43720E-04 330860 + 162 330870 As-87 3.83660E-04 3.83670E-04 330870 + 163 330880 As-88 4.67210E-05 4.67210E-05 330880 + 164 330890 As-89 4.67820E-06 4.67820E-06 330890 + 165 330900 As-90 1.52950E-09 1.52950E-09 330900 + 166 340780 Se-78 4.98780E-10 6.28990E-04 34078.82c + 167 340790 Se-79 3.00880E-08 1.26070E-03 34079.82c + 168 340791 Se-79m 4.59960E-09 1.23150E-03 340791 + 169 340800 Se-80 2.63300E-05 2.55840E-03 34080.82c + 170 340810 Se-81 1.86850E-05 3.75500E-03 340810 + 171 340811 Se-81m 1.22230E-04 2.51970E-04 340811 + 172 340820 Se-82 1.07720E-03 6.03550E-03 34082.82c + 173 340830 Se-83 3.83830E-03 6.10500E-03 340830 + 174 340831 Se-83m 8.87510E-04 4.91510E-03 340831 + 175 340840 Se-84 1.26550E-02 1.71370E-02 340840 + 176 340850 Se-85 1.67510E-02 1.89550E-02 340850 + 177 340860 Se-86 2.07040E-02 2.13280E-02 340860 + 178 340870 Se-87 1.56290E-02 1.59540E-02 340870 + 179 340880 Se-88 8.67040E-03 8.71710E-03 340880 + 180 340890 Se-89 2.54500E-03 2.54970E-03 340890 + 181 340900 Se-90 5.54590E-04 5.54590E-04 340900 + 182 340910 Se-91 6.12050E-05 6.12050E-05 340910 + 183 340920 Se-92 7.54490E-06 7.54490E-06 340920 + 184 350800 Br-80 2.82150E-11 1.13360E-10 350800 + 185 350801 Br-80m 8.51450E-11 8.51450E-11 350801 + 186 350810 Br-81 1.59900E-08 3.75520E-03 35081.82c + 187 350820 Br-82 4.63660E-07 6.56860E-07 350820 + 188 350821 Br-82m 1.97950E-07 1.97950E-07 350821 + 189 350830 Br-83 5.65180E-05 1.10770E-02 350830 + 190 350840 Br-84 2.41600E-04 1.73790E-02 350840 + 191 350841 Br-84m 2.41600E-04 2.41600E-04 350841 + 192 350850 Br-85 2.73710E-03 2.16920E-02 350850 + 193 350860 Br-86 7.37780E-03 2.87060E-02 350860 + 194 350870 Br-87 1.73490E-02 3.33890E-02 350870 + 195 350880 Br-88 2.11130E-02 2.99430E-02 350880 + 196 350890 Br-89 1.88340E-02 2.11850E-02 350890 + 197 350900 Br-90 8.40740E-03 8.97480E-03 350900 + 198 350910 Br-91 3.73460E-03 3.78300E-03 350910 + 199 350920 Br-92 6.10070E-04 6.17610E-04 350920 + 200 350930 Br-93 1.82660E-04 1.82660E-04 350930 + 201 350940 Br-94 8.50090E-06 8.50090E-06 350940 + 202 350950 Br-95 4.35390E-09 4.35390E-09 350950 + 203 360830 Kr-83 3.53100E-06 1.10810E-02 36083.82c + 204 360831 Kr-83m 8.16460E-07 1.10680E-02 360831 + 205 360840 Kr-84 1.18580E-05 1.76320E-02 36084.82c + 206 360850 Kr-85 1.31410E-04 4.80770E-03 36085.82c + 207 360851 Kr-85m 3.03860E-05 2.16870E-02 360851 + 208 360860 Kr-86 1.96290E-03 3.15070E-02 36086.82c + 209 360870 Kr-87 6.86410E-03 4.14210E-02 360870 + 210 360880 Kr-88 2.47780E-02 5.57020E-02 360880 + 211 360890 Kr-89 4.11640E-02 6.15700E-02 360890 + 212 360900 Kr-90 5.26870E-02 6.02110E-02 360900 + 213 360910 Kr-91 4.25680E-02 4.57990E-02 360910 + 214 360920 Kr-92 2.93200E-02 2.98570E-02 360920 + 215 360930 Kr-93 1.19370E-02 1.20010E-02 360930 + 216 360940 Kr-94 3.81870E-03 3.82120E-03 360940 + 217 360950 Kr-95 6.54080E-04 6.54080E-04 360950 + 218 360960 Kr-96 1.16520E-04 1.16520E-04 360960 + 219 360970 Kr-97 4.92830E-06 4.92830E-06 360970 + 220 370850 Rb-85 7.39760E-10 2.18540E-02 37085.82c + 221 370860 Rb-86 2.09270E-08 5.85690E-08 37086.82c + 222 370861 Rb-86m 3.76420E-08 3.76420E-08 370861 + 223 370870 Rb-87 5.48090E-05 4.14760E-02 37087.82c + 224 370880 Rb-88 3.28780E-04 5.60300E-02 370880 + 225 370890 Rb-89 2.47640E-03 6.40460E-02 370890 + 226 370900 Rb-90 6.30940E-04 5.33170E-02 370900 + 227 370901 Rb-90m 5.60370E-03 1.34790E-02 370901 + 228 370910 Rb-91 1.71970E-02 6.29960E-02 370910 + 229 370920 Rb-92 2.45120E-02 5.43690E-02 370920 + 230 370930 Rb-93 3.27690E-02 4.48130E-02 370930 + 231 370940 Rb-94 1.91460E-02 2.29440E-02 370940 + 232 370950 Rb-95 1.16410E-02 1.22810E-02 370950 + 233 370960 Rb-96 1.58610E-03 2.46360E-03 370960 + 234 370961 Rb-96m 1.58610E-03 1.64240E-03 370961 + 235 370970 Rb-97 1.05060E-03 1.05520E-03 370970 + 236 370980 Rb-98 5.71800E-05 5.71800E-05 370980 + 237 370981 Rb-98m 5.71800E-05 5.71800E-05 370981 + 238 370990 Rb-99 1.74520E-05 1.74520E-05 370990 + 239 371000 Rb-100 1.30620E-06 1.30620E-06 371000 + 240 380880 Sr-88 1.21130E-05 5.60430E-02 38088.82c + 241 380890 Sr-89 9.51210E-05 6.41410E-02 38089.82c + 242 380900 Sr-90 6.81390E-04 6.71270E-02 38090.82c + 243 380910 Sr-91 2.80040E-03 6.57960E-02 380910 + 244 380920 Sr-92 1.18350E-02 6.68320E-02 380920 + 245 380930 Sr-93 2.48520E-02 7.13550E-02 380930 + 246 380940 Sr-94 4.46510E-02 6.63330E-02 380940 + 247 380950 Sr-95 4.50400E-02 5.65950E-02 380950 + 248 380960 Sr-96 3.99790E-02 4.31990E-02 380960 + 249 380970 Sr-97 2.29770E-02 2.37750E-02 380970 + 250 380980 Sr-98 1.06850E-02 1.07940E-02 380980 + 251 380990 Sr-99 2.63940E-03 2.65420E-03 380990 + 252 381000 Sr-100 6.50480E-04 6.51710E-04 381000 + 253 381010 Sr-101 6.08320E-05 6.08320E-05 381010 + 254 381020 Sr-102 7.75060E-06 7.75060E-06 381020 + 255 390900 Y-90 6.32300E-10 6.71270E-02 39090.82c + 256 390901 Y-90m 8.97210E-10 8.97210E-10 390901 + 257 390910 Y-91 8.67490E-07 6.58010E-02 39091.82c + 258 390911 Y-91m 3.75170E-06 3.87150E-02 390911 + 259 390920 Y-92 6.03600E-05 6.68920E-02 390920 + 260 390930 Y-93 8.26790E-05 7.19780E-02 390930 + 261 390931 Y-93m 5.40840E-04 1.83970E-02 390931 + 262 390940 Y-94 1.78710E-03 6.81210E-02 390940 + 263 390950 Y-95 7.28020E-03 6.38750E-02 390950 + 264 390960 Y-96 4.28550E-03 4.74900E-02 390960 + 265 390961 Y-96m 7.70850E-03 7.71450E-03 390961 + 266 390970 Y-97 4.48770E-03 2.48700E-02 390970 + 267 390971 Y-97m 1.52960E-02 2.21200E-02 390971 + 268 390972 Y-97m 4.11010E-03 4.11010E-03 390972 + 269 390980 Y-98 3.96400E-03 1.47580E-02 390980 + 270 390981 Y-98m 1.66710E-02 1.66710E-02 390981 + 271 390990 Y-99 1.74100E-02 2.00690E-02 390990 + 272 391000 Y-100 3.63370E-03 4.28110E-03 391000 + 273 391001 Y-100m 3.63370E-03 3.63450E-03 391001 + 274 391010 Y-101 2.99310E-03 3.05290E-03 391010 + 275 391020 Y-102 2.69010E-04 2.72670E-04 391020 + 276 391021 Y-102m 2.69010E-04 2.72670E-04 391021 + 277 391030 Y-103 1.04880E-04 1.04880E-04 391030 + 278 391040 Y-104 6.70530E-06 6.70530E-06 391040 + 279 391050 Y-105 8.49590E-10 8.49590E-10 391050 + 280 400920 Zr-92 1.07790E-06 6.68930E-02 40092.82c + 281 400930 Zr-93 1.46580E-05 7.19930E-02 40093.82c + 282 400940 Zr-94 8.50090E-05 6.82060E-02 40094.82c + 283 400950 Zr-95 5.24360E-04 6.43990E-02 40095.82c + 284 400960 Zr-96 2.74290E-03 5.79650E-02 40096.82c + 285 400970 Zr-97 7.76600E-03 5.60190E-02 400970 + 286 400980 Zr-98 2.01680E-02 5.13250E-02 400980 + 287 400990 Zr-99 2.54850E-02 4.52520E-02 400990 + 288 401000 Zr-100 3.16820E-02 3.95580E-02 401000 + 289 401010 Zr-101 1.97180E-02 2.27980E-02 401010 + 290 401020 Zr-102 1.20900E-02 1.26170E-02 401020 + 291 401030 Zr-103 3.59930E-03 3.69640E-03 401030 + 292 401040 Zr-104 9.99090E-04 1.00520E-03 401040 + 293 401050 Zr-105 1.34510E-04 1.34510E-04 401050 + 294 401060 Zr-106 1.76000E-05 1.76000E-05 401060 + 295 401070 Zr-107 1.55630E-09 1.55630E-09 401070 + 296 401080 Zr-108 3.21480E-11 3.21480E-11 401080 + 297 410950 Nb-95 7.26790E-07 6.43610E-02 41095.82c + 298 410951 Nb-95m 1.68050E-07 6.95900E-04 410951 + 299 410960 Nb-96 4.78840E-06 4.78840E-06 410960 + 300 410970 Nb-97 6.13760E-05 5.60940E-02 410970 + 301 410971 Nb-97m 1.41920E-05 5.32590E-02 410971 + 302 410980 Nb-98 8.93000E-05 5.14140E-02 410980 + 303 410981 Nb-98m 2.69480E-04 2.69480E-04 410981 + 304 410990 Nb-99 1.34490E-03 3.02840E-02 410990 + 305 410991 Nb-99m 3.10980E-04 1.69640E-02 410991 + 306 411000 Nb-100 7.06060E-04 4.02640E-02 411000 + 307 411001 Nb-100m 2.96940E-03 2.96940E-03 411001 + 308 411010 Nb-101 8.01340E-03 3.08110E-02 411010 + 309 411020 Nb-102 4.37010E-03 1.69870E-02 411020 + 310 411021 Nb-102m 4.37010E-03 4.37010E-03 411021 + 311 411030 Nb-103 8.13600E-03 1.18320E-02 411030 + 312 411040 Nb-104 1.91650E-03 2.92360E-03 411040 + 313 411041 Nb-104m 1.91650E-03 1.91650E-03 411041 + 314 411050 Nb-105 1.67610E-03 1.80900E-03 411050 + 315 411060 Nb-106 3.69610E-04 3.86940E-04 411060 + 316 411070 Nb-107 1.01400E-04 1.01400E-04 411070 + 317 411080 Nb-108 2.63290E-05 2.63290E-05 411080 + 318 411090 Nb-109 1.51300E-05 1.51300E-05 411090 + 319 411100 Nb-110 6.00190E-11 6.00190E-11 411100 + 320 420970 Mo-97 8.21380E-07 5.60950E-02 42097.82c + 321 420980 Mo-98 8.96970E-06 5.16930E-02 42098.82c + 322 420990 Mo-99 6.21320E-05 4.69700E-02 42099.82c + 323 421000 Mo-100 3.55940E-04 4.35900E-02 42100.82c + 324 421010 Mo-101 1.06930E-03 3.18800E-02 421010 + 325 421020 Mo-102 3.24340E-03 2.46010E-02 421020 + 326 421030 Mo-103 4.14930E-03 1.59840E-02 421030 + 327 421040 Mo-104 4.90420E-03 9.77230E-03 421040 + 328 421050 Mo-105 2.96170E-03 4.75740E-03 421050 + 329 421060 Mo-106 1.82430E-03 2.19990E-03 421060 + 330 421070 Mo-107 6.92660E-04 7.89610E-04 421070 + 331 421080 Mo-108 3.86150E-04 4.12760E-04 421080 + 332 421090 Mo-109 6.80840E-05 8.13000E-05 421090 + 333 421100 Mo-110 2.26090E-05 2.26090E-05 421100 + 334 421110 Mo-111 2.13130E-08 2.13130E-08 421110 + 335 421120 Mo-112 4.38180E-10 4.38180E-10 421120 + 336 421130 Mo-113 4.43910E-12 4.43910E-12 421130 + 337 431010 Tc-101 6.27120E-06 3.18870E-02 431010 + 338 431020 Tc-102 1.38860E-05 2.46150E-02 431020 + 339 431021 Tc-102m 1.38860E-05 1.38860E-05 431021 + 340 431030 Tc-103 7.69530E-05 1.60610E-02 431030 + 341 431040 Tc-104 1.54220E-04 9.92650E-03 431040 + 342 431050 Tc-105 3.00320E-04 5.05770E-03 431050 + 343 431060 Tc-106 3.15930E-04 2.51580E-03 431060 + 344 431070 Tc-107 3.41330E-04 1.13090E-03 431070 + 345 431080 Tc-108 3.02770E-04 7.15960E-04 431080 + 346 431090 Tc-109 1.89120E-04 2.69990E-04 431090 + 347 431100 Tc-110 1.46960E-04 1.69570E-04 431100 + 348 431110 Tc-111 3.68770E-05 3.68980E-05 431110 + 349 431120 Tc-112 8.73470E-07 8.73900E-07 431120 + 350 431130 Tc-113 1.03950E-07 1.03950E-07 431130 + 351 431140 Tc-114 2.68930E-09 2.68930E-09 431140 + 352 431150 Tc-115 7.23180E-11 7.23180E-11 431150 + 353 441020 Ru-102 6.45880E-07 2.46290E-02 44102.82c + 354 441030 Ru-103 1.81770E-07 1.60620E-02 44103.82c + 355 441031 Ru-103m 4.38820E-07 4.38820E-07 441031 + 356 441040 Ru-104 3.65750E-06 9.93020E-03 44104.82c + 357 441050 Ru-105 1.19860E-05 5.06970E-03 44105.82c + 358 441060 Ru-106 3.25610E-05 2.54840E-03 44106.82c + 359 441070 Ru-107 3.42760E-05 1.16520E-03 441070 + 360 441080 Ru-108 9.21490E-05 8.08330E-04 441080 + 361 441090 Ru-109 1.51300E-04 4.21140E-04 441090 + 362 441100 Ru-110 2.14780E-04 3.84280E-04 441100 + 363 441110 Ru-111 1.77010E-04 2.13920E-04 441110 + 364 441120 Ru-112 1.14320E-04 1.15190E-04 441120 + 365 441130 Ru-113 4.83500E-05 7.26220E-05 441130 + 366 441131 Ru-113m 4.83500E-05 4.83500E-05 441131 + 367 441140 Ru-114 3.95270E-05 3.95300E-05 441140 + 368 441150 Ru-115 1.84430E-05 1.84430E-05 441150 + 369 441160 Ru-116 1.45410E-05 1.45410E-05 441160 + 370 441170 Ru-117 4.60390E-10 4.60390E-10 441170 + 371 441180 Ru-118 6.24700E-12 6.24700E-12 441180 + 372 441190 Ru-119 1.62010E-07 1.62010E-07 441190 + 373 441200 Ru-120 1.36710E-08 1.36710E-08 441200 + 374 451060 Rh-106 2.73380E-10 2.54840E-03 451060 + 375 451061 Rh-106m 6.40340E-10 6.40340E-10 451061 + 376 451070 Rh-107 1.42820E-06 1.16660E-03 451070 + 377 451080 Rh-108 1.05790E-07 8.08430E-04 451080 + 378 451081 Rh-108m 3.19230E-07 3.19230E-07 451081 + 379 451090 Rh-109 4.59830E-06 4.25740E-04 451090 + 380 451100 Rh-110 1.92910E-05 4.03570E-04 451100 + 381 451101 Rh-110m 5.14960E-07 5.14960E-07 451101 + 382 451110 Rh-111 3.68770E-05 2.50800E-04 451110 + 383 451120 Rh-112 1.33370E-05 1.28520E-04 451120 + 384 451121 Rh-112m 1.33370E-05 1.33370E-05 451121 + 385 451130 Rh-113 4.39550E-05 1.40750E-04 451130 + 386 451140 Rh-114 4.79950E-05 8.75670E-05 451140 + 387 451141 Rh-114m 4.79950E-05 4.79950E-05 451141 + 388 451150 Rh-115 5.53290E-05 7.38870E-05 451150 + 389 451160 Rh-116 8.70070E-06 2.30850E-05 451160 + 390 451161 Rh-116m 2.03790E-05 2.03790E-05 451161 + 391 451170 Rh-117 2.82710E-05 2.82710E-05 451170 + 392 451180 Rh-118 8.77580E-08 9.48240E-08 451180 + 393 451190 Rh-119 3.02340E-05 3.03890E-05 451190 + 394 451200 Rh-120 6.10960E-06 6.12330E-06 451200 + 395 451210 Rh-121 1.20220E-06 1.20220E-06 451210 + 396 451220 Rh-122 4.58410E-08 4.58410E-08 451220 + 397 461080 Pd-108 3.21480E-11 8.08750E-04 46108.82c + 398 461090 Pd-109 4.10580E-10 4.25740E-04 461090 + 399 461091 Pd-109m 7.71620E-10 2.12870E-04 461091 + 400 461100 Pd-110 6.39070E-08 4.04150E-04 46110.82c + 401 461110 Pd-111 1.93260E-07 2.50990E-04 461110 + 402 461111 Pd-111m 3.63210E-07 1.36640E-06 461111 + 403 461120 Pd-112 3.81070E-06 1.45670E-04 461120 + 404 461130 Pd-113 7.72440E-06 1.67130E-04 461130 + 405 461131 Pd-113m 1.86480E-05 1.86480E-05 461131 + 406 461140 Pd-114 5.08180E-05 1.86380E-04 461140 + 407 461150 Pd-115 3.84320E-05 1.08230E-04 461150 + 408 461151 Pd-115m 7.22280E-05 8.29560E-05 461151 + 409 461160 Pd-116 1.21170E-04 1.64630E-04 461160 + 410 461170 Pd-117 3.43650E-05 1.27220E-04 461170 + 411 461171 Pd-117m 6.45840E-05 6.45840E-05 461171 + 412 461180 Pd-118 9.61620E-05 9.62540E-05 461180 + 413 461190 Pd-119 2.68290E-05 5.75810E-05 461190 + 414 461200 Pd-120 1.14110E-05 1.73340E-05 461200 + 415 461210 Pd-121 6.87400E-06 7.91310E-06 461210 + 416 461220 Pd-122 2.60830E-05 2.61290E-05 461220 + 417 461230 Pd-123 3.57830E-06 3.57830E-06 461230 + 418 461240 Pd-124 6.49160E-07 6.49160E-07 461240 + 419 471110 Ag-111 1.11120E-11 2.50110E-04 47111.82c + 420 471111 Ag-111m 7.26900E-11 2.49480E-04 471111 + 421 471120 Ag-112 1.93490E-09 1.45680E-04 471120 + 422 471130 Ag-113 1.29540E-08 1.09580E-04 471130 + 423 471131 Ag-113m 8.47400E-08 1.60120E-04 471131 + 424 471140 Ag-114 2.05760E-07 1.87450E-04 471140 + 425 471141 Ag-114m 8.65340E-07 8.65340E-07 471141 + 426 471150 Ag-115 1.63030E-06 1.05040E-04 471150 + 427 471151 Ag-115m 1.06650E-05 1.16210E-04 471151 + 428 471160 Ag-116 2.90040E-06 1.67940E-04 471160 + 429 471161 Ag-116m 6.79330E-06 6.79330E-06 471161 + 430 471170 Ag-117 2.81150E-06 7.13430E-05 471170 + 431 471171 Ag-117m 1.83910E-05 8.20030E-05 471171 + 432 471180 Ag-118 5.83330E-06 1.04030E-04 471180 + 433 471181 Ag-118m 2.45330E-05 3.82930E-05 471181 + 434 471190 Ag-119 9.48690E-06 3.82770E-05 471190 + 435 471191 Ag-119m 6.20580E-05 9.08490E-05 471191 + 436 471200 Ag-120 2.12280E-05 4.42690E-05 471200 + 437 471201 Ag-120m 3.01220E-05 3.87890E-05 471201 + 438 471210 Ag-121 6.87400E-05 7.66310E-05 471210 + 439 471220 Ag-122 1.50220E-05 4.11510E-05 471220 + 440 471221 Ag-122m 1.35320E-05 1.35320E-05 471221 + 441 471230 Ag-123 1.86280E-05 2.22060E-05 471230 + 442 471240 Ag-124 2.49410E-05 3.68240E-05 471240 + 443 471241 Ag-124m 2.24670E-05 2.24670E-05 471241 + 444 471250 Ag-125 6.80660E-05 6.80660E-05 471250 + 445 471260 Ag-126 4.64150E-05 4.64150E-05 471260 + 446 471270 Ag-127 2.36420E-06 2.36420E-06 471270 + 447 471280 Ag-128 1.13460E-07 1.13460E-07 471280 + 448 471290 Ag-129 4.63500E-09 4.63500E-09 471290 + 449 481130 Cd-113 1.03920E-12 1.65330E-04 48113.82c + 450 481131 Cd-113m 3.39990E-12 1.89450E-06 481131 + 451 481140 Cd-114 5.19330E-10 1.87450E-04 48114.82c + 452 481150 Cd-115 3.64990E-09 1.88120E-04 481150 + 453 481151 Cd-115m 1.19410E-08 8.73740E-06 48515.82c + 454 481160 Cd-116 4.43570E-07 1.74770E-04 48116.82c + 455 481170 Cd-117 8.27260E-07 1.18080E-04 481170 + 456 481171 Cd-117m 2.70650E-06 3.38780E-05 481171 + 457 481180 Cd-118 3.03660E-05 1.56990E-04 481180 + 458 481190 Cd-119 9.16780E-06 1.19160E-04 481190 + 459 481191 Cd-119m 2.21320E-05 4.12720E-05 481191 + 460 481200 Cd-120 1.08410E-04 1.77110E-04 481200 + 461 481210 Cd-121 3.22160E-05 1.00840E-04 481210 + 462 481211 Cd-121m 7.77740E-05 8.57810E-05 481211 + 463 481220 Cd-122 1.42770E-04 1.97450E-04 481220 + 464 481230 Cd-123 4.18320E-05 6.00190E-05 481230 + 465 481231 Cd-123m 1.00990E-04 1.05040E-04 481231 + 466 481240 Cd-124 1.47260E-04 1.95280E-04 481240 + 467 481250 Cd-125 9.07900E-05 1.24820E-04 481250 + 468 481251 Cd-125m 2.19180E-04 2.53210E-04 481251 + 469 481260 Cd-126 5.10570E-04 5.56980E-04 481260 + 470 481270 Cd-127 7.11760E-04 7.14120E-04 481270 + 471 481280 Cd-128 4.53140E-04 4.53250E-04 481280 + 472 481290 Cd-129 5.02760E-05 5.02790E-05 481290 + 473 481291 Cd-129m 1.21370E-04 1.21380E-04 481291 + 474 481300 Cd-130 2.54080E-05 2.54080E-05 481300 + 475 481310 Cd-131 7.84440E-08 7.84440E-08 481310 + 476 481320 Cd-132 1.92200E-09 1.92200E-09 481320 + 477 491160 In-116 6.78180E-12 6.78180E-12 491160 + 478 491161 In-116m 1.03950E-11 2.04620E-11 491161 + 479 491162 In-116m 1.00680E-11 1.00680E-11 491162 + 480 491170 In-117 1.69930E-09 9.44440E-05 491170 + 481 491171 In-117m 3.92910E-10 1.08730E-04 491171 + 482 491180 In-118 1.12310E-08 1.57000E-04 491180 + 483 491181 In-118m 1.72140E-08 3.36530E-08 491181 + 484 491182 In-118m 1.66720E-08 1.66720E-08 491182 + 485 491200 In-120 2.41800E-11 1.77110E-04 491200 + 486 491201 In-120m 2.41800E-11 2.41800E-11 491201 + 487 491202 In-120m 2.41800E-11 2.41800E-11 491202 + 488 491210 In-121 5.04280E-09 1.20550E-04 491210 + 489 491211 In-121m 1.16600E-09 6.68790E-05 491211 + 490 491220 In-122 4.24150E-08 1.97500E-04 491220 + 491 491221 In-122m 3.00930E-08 3.00930E-08 491221 + 492 491222 In-122m 3.00930E-08 3.00930E-08 491222 + 493 491230 In-123 3.53030E-05 1.57660E-04 491230 + 494 491231 In-123m 8.16290E-06 5.08730E-05 491231 + 495 491240 In-124 4.30400E-05 2.38320E-04 491240 + 496 491241 In-124m 3.87700E-05 3.87700E-05 491241 + 497 491250 In-125 3.23700E-04 6.36660E-04 491250 + 498 491251 In-125m 7.48480E-05 1.39930E-04 491251 + 499 491260 In-126 5.12800E-04 1.06980E-03 491260 + 500 491261 In-126m 4.61930E-04 4.61930E-04 491261 + 501 491270 In-127 1.54930E-03 1.54930E-03 491270 + 502 491271 In-127m 3.58230E-04 1.07230E-03 491271 + 503 491280 In-128 9.16650E-04 1.74300E-03 491280 + 504 491281 In-128m 3.73130E-04 8.26390E-04 491281 + 505 491282 In-128m 1.16180E-03 1.16180E-03 491282 + 506 491290 In-129 2.35520E-03 2.47700E-03 491290 + 507 491291 In-129m 5.44580E-04 5.95310E-04 491291 + 508 491300 In-130 3.16200E-04 3.40720E-04 491300 + 509 491301 In-130m 3.53170E-04 3.53170E-04 491301 + 510 491302 In-130m 6.00900E-04 6.00900E-04 491302 + 511 491310 In-131 2.04890E-04 2.07050E-04 491310 + 512 491311 In-131m 2.04890E-04 2.04890E-04 491311 + 513 491312 In-131m 2.04890E-04 2.04890E-04 491312 + 514 491320 In-132 6.60520E-05 6.60530E-05 491320 + 515 491330 In-133 6.71950E-06 8.27320E-06 491330 + 516 491331 In-133m 1.55370E-06 1.55370E-06 491331 + 517 491340 In-134 1.68360E-08 1.68360E-08 491340 + 518 501180 Sn-118 6.24700E-12 1.57030E-04 50118.82c + 519 501220 Sn-122 1.36420E-11 1.97560E-04 50122.82c + 520 501230 Sn-123 4.89040E-10 1.20200E-05 50123.82c + 521 501231 Sn-123m 2.02570E-10 1.96510E-04 501231 + 522 501240 Sn-124 4.90850E-05 3.26180E-04 50124.82c + 523 501250 Sn-125 2.81810E-04 3.89360E-04 50125.82c + 524 501251 Sn-125m 1.16730E-04 7.85780E-04 501251 + 525 501260 Sn-126 8.81890E-04 2.42100E-03 50126.82c + 526 501270 Sn-127 1.28840E-03 1.89230E-03 501270 + 527 501271 Sn-127m 5.33690E-04 2.54400E-03 501271 + 528 501280 Sn-128 2.09280E-03 9.89960E-03 501280 + 529 501281 Sn-128m 4.90190E-03 6.06370E-03 501281 + 530 501290 Sn-129 3.64510E-03 6.45400E-03 501290 + 531 501291 Sn-129m 8.79990E-03 9.06360E-03 501291 + 532 501300 Sn-130 5.82000E-03 6.66510E-03 501300 + 533 501301 Sn-130m 1.36320E-02 1.40860E-02 501301 + 534 501310 Sn-131 5.21510E-03 5.61200E-03 501310 + 535 501311 Sn-131m 1.25900E-02 1.28040E-02 501311 + 536 501320 Sn-132 1.42770E-02 1.43500E-02 501320 + 537 501330 Sn-133 2.34140E-03 2.34260E-03 501330 + 538 501340 Sn-134 3.60370E-04 3.60380E-04 501340 + 539 501350 Sn-135 3.79140E-05 3.79140E-05 501350 + 540 501360 Sn-136 7.90330E-06 7.90330E-06 501360 + 541 501370 Sn-137 1.67010E-09 1.67010E-09 501370 + 542 511250 Sb-125 4.80950E-10 1.17510E-03 51125.82c + 543 511260 Sb-126 1.71500E-05 2.12470E-05 51126.82c + 544 511261 Sb-126m 1.26810E-05 2.92650E-05 511261 + 545 511262 Sb-126m 1.65840E-05 1.65840E-05 511262 + 546 511270 Sb-127 1.70820E-04 4.60710E-03 511270 + 547 511280 Sb-128 8.58640E-05 9.99070E-03 511280 + 548 511281 Sb-128m 1.46520E-04 1.46520E-04 511281 + 549 511290 Sb-129 1.09590E-03 1.28620E-02 511290 + 550 511291 Sb-129m 6.69690E-04 5.20140E-03 511291 + 551 511300 Sb-130 1.90000E-03 1.56080E-02 511300 + 552 511301 Sb-130m 1.90000E-03 8.94300E-03 511301 + 553 511310 Sb-131 1.53270E-02 3.37430E-02 511310 + 554 511320 Sb-132 1.19500E-02 2.63010E-02 511320 + 555 511321 Sb-132m 8.80760E-03 8.80760E-03 511321 + 556 511330 Sb-133 2.98180E-02 3.22220E-02 511330 + 557 511340 Sb-134 2.32920E-03 2.63230E-03 511340 + 558 511341 Sb-134m 5.45560E-03 5.45960E-03 511341 + 559 511350 Sb-135 2.98270E-03 3.01500E-03 511350 + 560 511360 Sb-136 7.00430E-04 7.05960E-04 511360 + 561 511370 Sb-137 9.41040E-05 9.41050E-05 511370 + 562 511380 Sb-138 7.69910E-06 7.69910E-06 511380 + 563 511390 Sb-139 1.80900E-06 1.80900E-06 511390 + 564 521270 Te-127 3.59040E-11 4.58890E-03 521270 + 565 521271 Te-127m 8.66760E-11 7.59240E-04 52527.82c + 566 521280 Te-128 3.71140E-08 1.01320E-02 52128.82c + 567 521290 Te-129 1.61600E-05 1.49360E-02 521290 + 568 521291 Te-129m 3.90130E-05 6.49120E-03 52529.82c + 569 521300 Te-130 5.98500E-04 2.51500E-02 52130.82c + 570 521310 Te-131 6.56740E-04 3.25980E-02 521310 + 571 521311 Te-131m 1.58550E-03 4.28690E-03 521311 + 572 521320 Te-132 1.31140E-02 4.82220E-02 52132.82c + 573 521330 Te-133 7.99820E-03 3.90060E-02 521330 + 574 521331 Te-133m 1.93090E-02 2.48820E-02 521331 + 575 521340 Te-134 5.23220E-02 6.08840E-02 521340 + 576 521350 Te-135 3.44540E-02 3.71110E-02 521350 + 577 521360 Te-136 3.48330E-02 3.54680E-02 521360 + 578 521370 Te-137 8.92280E-03 8.97080E-03 521370 + 579 521380 Te-138 3.35250E-03 3.36020E-03 521380 + 580 521390 Te-139 3.61790E-04 3.63600E-04 521390 + 581 521400 Te-140 1.07170E-04 1.07170E-04 521400 + 582 521410 Te-141 3.16420E-06 3.16420E-06 521410 + 583 521420 Te-142 5.36790E-09 5.36790E-09 521420 + 584 531300 I-130 3.53810E-09 4.80690E-09 53130.82c + 585 531301 I-130m 1.51050E-09 1.51050E-09 531301 + 586 531310 I-131 6.25160E-06 3.59910E-02 53131.82c + 587 531320 I-132 3.33880E-05 4.82770E-02 531320 + 588 531321 I-132m 2.46070E-05 2.46070E-05 531321 + 589 531330 I-133 5.16960E-04 6.03670E-02 531330 + 590 531331 I-133m 3.15910E-04 3.15910E-04 531331 + 591 531340 I-134 1.34030E-03 6.31900E-02 531340 + 592 531341 I-134m 9.87850E-04 9.87850E-04 531341 + 593 531350 I-135 1.59380E-02 5.30490E-02 53135.82c + 594 531360 I-136 7.93690E-03 4.35390E-02 531360 + 595 531361 I-136m 1.85900E-02 1.87240E-02 531361 + 596 531370 I-137 3.41260E-02 4.30400E-02 531370 + 597 531380 I-138 1.36560E-02 1.68040E-02 531380 + 598 531390 I-139 1.36050E-02 1.39690E-02 531390 + 599 531400 I-140 3.43630E-03 3.54350E-03 531400 + 600 531410 I-141 1.43440E-03 1.43760E-03 531410 + 601 531420 I-142 2.01140E-04 2.01150E-04 531420 + 602 531430 I-143 2.75140E-05 2.75140E-05 531430 + 603 531440 I-144 1.48190E-06 1.48190E-06 531440 + 604 541320 Xe-132 9.00840E-10 4.82800E-02 54132.82c + 605 541321 Xe-132m 1.02120E-09 1.02120E-09 541321 + 606 541330 Xe-133 3.23100E-06 6.03780E-02 54133.82c + 607 541331 Xe-133m 7.80000E-06 1.72610E-03 541331 + 608 541340 Xe-134 2.87020E-05 6.33080E-02 54134.82c + 609 541341 Xe-134m 6.72270E-05 8.99480E-05 541341 + 610 541350 Xe-135 2.00380E-04 5.36770E-02 54135.82c + 611 541351 Xe-135m 4.83740E-04 9.24140E-03 541351 + 612 541360 Xe-136 9.23250E-03 7.42930E-02 54136.82c + 613 541370 Xe-137 1.94540E-02 6.05870E-02 541370 + 614 541380 Xe-138 4.09590E-02 5.82420E-02 541380 + 615 541390 Xe-139 3.73230E-02 5.02520E-02 541390 + 616 541400 Xe-140 5.05720E-02 5.40880E-02 541400 + 617 541410 Xe-141 2.89130E-02 3.00990E-02 541410 + 618 541420 Xe-142 2.09930E-02 2.11550E-02 541420 + 619 541430 Xe-143 4.05970E-03 4.07680E-03 541430 + 620 541440 Xe-144 8.74360E-04 8.75250E-04 541440 + 621 541450 Xe-145 9.71860E-05 9.71860E-05 541450 + 622 541460 Xe-146 1.27930E-05 1.27930E-05 541460 + 623 541470 Xe-147 1.45470E-09 1.45470E-09 541470 + 624 551350 Cs-135 1.02320E-06 5.37340E-02 55135.82c + 625 551351 Cs-135m 6.25240E-07 6.25240E-07 551351 + 626 551360 Cs-136 6.22890E-06 8.05410E-06 55136.82c + 627 551361 Cs-136m 3.65040E-06 3.65040E-06 551361 + 628 551370 Cs-137 2.43780E-04 6.08310E-02 55137.82c + 629 551380 Cs-138 5.20220E-04 5.93600E-02 551380 + 630 551381 Cs-138m 7.38180E-04 7.38180E-04 551381 + 631 551390 Cs-139 5.29190E-03 5.55440E-02 551390 + 632 551400 Cs-140 8.57490E-03 6.26760E-02 551400 + 633 551410 Cs-141 2.76700E-02 5.78320E-02 551410 + 634 551420 Cs-142 2.68920E-02 4.80110E-02 551420 + 635 551430 Cs-143 2.69720E-02 3.10340E-02 551430 + 636 551440 Cs-144 4.19630E-03 7.14720E-03 551440 + 637 551441 Cs-144m 4.19630E-03 4.19880E-03 551441 + 638 551450 Cs-145 3.99170E-03 4.08490E-03 551450 + 639 551460 Cs-146 6.56500E-04 6.68410E-04 551460 + 640 551470 Cs-147 1.18170E-04 1.18170E-04 551470 + 641 551480 Cs-148 1.26820E-05 1.26820E-05 551480 + 642 551490 Cs-149 5.43810E-07 5.43810E-07 551490 + 643 561370 Ba-137 2.62510E-07 6.08320E-02 56137.82c + 644 561371 Ba-137m 6.33730E-07 5.74250E-02 561371 + 645 561380 Ba-138 3.16530E-05 5.95320E-02 56138.82c + 646 561390 Ba-139 2.80380E-04 5.58240E-02 561390 + 647 561400 Ba-140 1.50740E-03 6.41830E-02 56140.82c + 648 561410 Ba-141 4.74500E-03 6.25770E-02 561410 + 649 561420 Ba-142 1.92410E-02 6.77610E-02 561420 + 650 561430 Ba-143 2.77010E-02 5.84550E-02 561430 + 651 561440 Ba-144 3.56020E-02 4.52040E-02 561440 + 652 561450 Ba-145 2.34650E-02 2.70610E-02 561450 + 653 561460 Ba-146 1.71310E-02 1.77380E-02 561460 + 654 561470 Ba-147 5.21440E-03 5.30210E-03 561470 + 655 561480 Ba-148 1.97410E-03 1.98360E-03 561480 + 656 561490 Ba-149 2.37100E-04 2.37640E-04 561490 + 657 561500 Ba-150 2.57330E-05 2.57330E-05 561500 + 658 561510 Ba-151 2.62710E-08 2.62710E-08 561510 + 659 561520 Ba-152 3.18650E-10 3.18650E-10 561520 + 660 571400 La-140 7.16060E-09 6.41830E-02 57140.82c + 661 571410 La-141 2.42590E-05 6.26010E-02 571410 + 662 571420 La-142 8.39930E-05 6.78450E-02 571420 + 663 571430 La-143 7.22540E-04 5.91780E-02 571430 + 664 571440 La-144 1.92500E-03 4.71290E-02 571440 + 665 571450 La-145 6.26090E-03 3.33220E-02 571450 + 666 571460 La-146 2.17140E-03 1.99100E-02 571460 + 667 571461 La-146m 3.90580E-03 3.90580E-03 571461 + 668 571470 La-147 9.59760E-03 1.49080E-02 571470 + 669 571480 La-148 4.81580E-03 6.79250E-03 571480 + 670 571490 La-149 2.69820E-03 2.93480E-03 571490 + 671 571500 La-150 5.56600E-04 5.82330E-04 571500 + 672 571510 La-151 1.95820E-04 1.95850E-04 571510 + 673 571520 La-152 2.45940E-05 2.45940E-05 571520 + 674 571530 La-153 1.10670E-06 1.10670E-06 571530 + 675 571540 La-154 4.69720E-10 4.69720E-10 571540 + 676 581430 Ce-143 5.09520E-06 5.91830E-02 58143.82c + 677 581440 Ce-144 1.09660E-04 4.72390E-02 58144.82c + 678 581450 Ce-145 4.78110E-04 3.38000E-02 581450 + 679 581460 Ce-146 1.64770E-03 2.54630E-02 581460 + 680 581470 Ce-147 3.28790E-03 1.81950E-02 581470 + 681 581480 Ce-148 6.20090E-03 1.30340E-02 581480 + 682 581490 Ce-149 4.55020E-03 7.45970E-03 581490 + 683 581500 Ce-150 3.93150E-03 4.49810E-03 581500 + 684 581510 Ce-151 2.04630E-03 2.24360E-03 581510 + 685 581520 Ce-152 9.38520E-04 9.61630E-04 581520 + 686 581530 Ce-153 2.02530E-04 2.03640E-04 581530 + 687 581540 Ce-154 2.04870E-05 2.04870E-05 581540 + 688 581550 Ce-155 1.77810E-06 1.77810E-06 581550 + 689 581560 Ce-156 1.80830E-09 1.80830E-09 581560 + 690 581570 Ce-157 1.14320E-11 1.14320E-11 581570 + 691 591450 Pr-145 3.43820E-09 3.38000E-02 591450 + 692 591460 Pr-146 4.04000E-06 2.54670E-02 591460 + 693 591470 Pr-147 2.67070E-05 1.82220E-02 591470 + 694 591480 Pr-148 1.43860E-05 1.30490E-02 591480 + 695 591481 Pr-148m 6.05000E-05 6.05000E-05 591481 + 696 591490 Pr-149 2.64290E-04 7.72400E-03 591490 + 697 591500 Pr-150 3.93140E-04 4.89120E-03 591500 + 698 591510 Pr-151 1.00850E-03 3.25210E-03 591510 + 699 591520 Pr-152 6.88620E-04 1.65150E-03 591520 + 700 591530 Pr-153 6.45220E-04 8.47720E-04 591530 + 701 591540 Pr-154 1.40950E-04 1.61310E-04 591540 + 702 591550 Pr-155 4.80110E-05 4.97890E-05 591550 + 703 591560 Pr-156 4.55360E-06 4.55540E-06 591560 + 704 591570 Pr-157 1.46650E-07 1.46660E-07 591570 + 705 591580 Pr-158 2.74220E-09 2.74220E-09 591580 + 706 591590 Pr-159 1.31930E-11 1.31930E-11 591590 + 707 601480 Nd-148 6.03920E-07 1.31100E-02 60148.82c + 708 601490 Nd-149 8.70110E-06 7.73260E-03 601490 + 709 601500 Nd-150 4.19350E-05 4.93320E-03 60150.82c + 710 601510 Nd-151 1.46110E-04 3.39820E-03 601510 + 711 601520 Nd-152 3.47480E-04 1.99900E-03 601520 + 712 601530 Nd-153 4.60400E-04 1.30810E-03 601530 + 713 601540 Nd-154 2.98290E-04 4.59600E-04 601540 + 714 601550 Nd-155 1.45810E-04 1.95720E-04 601550 + 715 601560 Nd-156 8.65180E-05 9.09590E-05 601560 + 716 601570 Nd-157 2.95190E-05 2.96560E-05 601570 + 717 601580 Nd-158 3.14720E-06 3.14990E-06 601580 + 718 601590 Nd-159 4.05990E-08 4.06120E-08 601590 + 719 601600 Nd-160 3.15770E-09 3.15770E-09 601600 + 720 601610 Nd-161 1.72890E-11 1.72890E-11 601610 + 721 611500 Pm-150 2.20800E-10 2.20800E-10 611500 + 722 611510 Pm-151 1.85030E-08 3.39830E-03 61151.82c + 723 611520 Pm-152 3.04810E-07 1.99930E-03 611520 + 724 611521 Pm-152m 6.08660E-07 6.08660E-07 611521 + 725 611522 Pm-152m 6.73240E-07 6.73240E-07 611522 + 726 611530 Pm-153 7.74700E-06 1.31590E-03 611530 + 727 611540 Pm-154 4.09730E-06 4.63690E-04 611540 + 728 611541 Pm-154m 4.09730E-06 4.09730E-06 611541 + 729 611550 Pm-155 2.22270E-05 2.17950E-04 611550 + 730 611560 Pm-156 2.04910E-05 1.11450E-04 611560 + 731 611570 Pm-157 3.79530E-05 6.76100E-05 611570 + 732 611580 Pm-158 2.83240E-05 3.14740E-05 611580 + 733 611590 Pm-159 6.26630E-06 6.30680E-06 611590 + 734 611600 Pm-160 9.85280E-07 9.88410E-07 611600 + 735 611610 Pm-161 3.25770E-08 3.25940E-08 611610 + 736 611620 Pm-162 1.81330E-09 1.81330E-09 611620 + 737 611630 Pm-163 9.42520E-11 9.42520E-11 611630 + 738 621530 Sm-153 1.74280E-10 1.31590E-03 62153.82c + 739 621531 Sm-153m 4.20750E-10 4.20750E-10 621531 + 740 621540 Sm-154 1.76060E-08 4.67810E-04 62154.82c + 741 621550 Sm-155 3.55620E-06 2.21510E-04 621550 + 742 621560 Sm-156 3.41510E-06 1.14870E-04 621560 + 743 621570 Sm-157 4.21700E-06 7.18260E-05 621570 + 744 621580 Sm-158 1.25890E-05 4.40640E-05 621580 + 745 621590 Sm-159 3.22100E-06 9.52930E-06 621590 + 746 621600 Sm-160 3.94120E-06 4.92700E-06 621600 + 747 621610 Sm-161 6.04250E-07 6.36840E-07 621610 + 748 621620 Sm-162 3.61350E-07 3.63160E-07 621620 + 749 621630 Sm-163 4.43440E-08 4.44380E-08 621630 + 750 621640 Sm-164 6.94330E-09 6.94330E-09 621640 + 751 621650 Sm-165 2.83560E-10 2.83560E-10 621650 + 752 631550 Eu-155 7.39830E-12 2.21510E-04 63155.82c + 753 631560 Eu-156 3.05210E-10 1.14870E-04 63156.82c + 754 631570 Eu-157 1.12770E-08 7.18380E-05 63157.82c + 755 631580 Eu-158 9.12130E-08 4.41550E-05 631580 + 756 631590 Eu-159 1.94390E-07 9.72370E-06 631590 + 757 631600 Eu-160 5.32880E-07 5.45980E-06 631600 + 758 631610 Eu-161 5.64320E-07 1.20120E-06 631610 + 759 631620 Eu-162 5.45570E-07 9.08730E-07 631620 + 760 631630 Eu-163 5.89430E-07 6.33870E-07 631630 + 761 631640 Eu-164 1.83770E-07 1.90710E-07 631640 + 762 631650 Eu-165 8.48920E-08 8.51760E-08 631650 + 763 631660 Eu-166 7.25320E-09 7.25320E-09 631660 + 764 631670 Eu-167 8.52740E-10 8.52740E-10 631670 + 765 641580 Gd-158 2.10510E-11 4.41550E-05 64158.82c + 766 641590 Gd-159 1.17570E-10 9.72380E-06 641590 + 767 641600 Gd-160 3.96800E-09 5.46380E-06 64160.82c + 768 641610 Gd-161 9.43970E-09 1.21060E-06 641610 + 769 641620 Gd-162 9.15850E-08 1.00030E-06 641620 + 770 641630 Gd-163 1.73020E-07 8.06890E-07 641630 + 771 641640 Gd-164 4.39310E-07 6.30020E-07 641640 + 772 641650 Gd-165 3.36370E-07 4.21550E-07 641650 + 773 641660 Gd-166 2.68090E-07 2.75340E-07 641660 + 774 641670 Gd-167 6.65840E-08 6.74370E-08 641670 + 775 641680 Gd-168 2.21690E-08 2.21690E-08 641680 + 776 641690 Gd-169 1.41680E-09 1.41680E-09 641690 + 777 651610 Tb-161 3.50770E-12 1.21060E-06 651610 + 778 651620 Tb-162 8.61290E-11 1.00040E-06 651620 + 779 651630 Tb-163 1.93580E-09 8.08820E-07 651630 + 780 651640 Tb-164 1.04890E-08 6.40510E-07 651640 + 781 651650 Tb-165 7.57520E-08 4.97300E-07 651650 + 782 651660 Tb-166 1.00750E-07 3.76090E-07 651660 + 783 651670 Tb-167 2.03350E-07 2.70790E-07 651670 + 784 651680 Tb-168 1.17270E-07 1.39440E-07 651680 + 785 651690 Tb-169 7.43770E-08 7.57940E-08 651690 + 786 651700 Tb-170 1.07720E-08 1.07720E-08 651700 + 787 651710 Tb-171 2.48730E-09 2.48730E-09 651710 + 788 661640 Dy-164 1.24080E-11 6.40520E-07 66164.82c + 789 661650 Dy-165 1.90950E-10 4.97520E-07 661650 + 790 661651 Dy-165m 2.91910E-11 2.91910E-11 661651 + 791 661660 Dy-166 3.34000E-09 3.79430E-07 661660 + 792 661670 Dy-167 1.35730E-08 2.84360E-07 661670 + 793 661680 Dy-168 6.95910E-08 2.09030E-07 661680 + 794 661690 Dy-169 7.15610E-08 1.47360E-07 661690 + 795 661700 Dy-170 8.60220E-08 9.67940E-08 661700 + 796 661710 Dy-171 3.64050E-08 3.88920E-08 661710 + 797 661720 Dy-172 1.39700E-08 1.39700E-08 661720 + 798 671670 Ho-167 2.50170E-11 2.84380E-07 671670 + 799 671680 Ho-168 1.26040E-10 2.09330E-07 671680 + 800 671681 Ho-168m 1.78850E-10 1.78850E-10 671681 + 801 671690 Ho-169 3.40190E-09 1.50760E-07 671690 + 802 671700 Ho-170 5.42420E-09 5.42420E-09 671700 + 803 671701 Ho-170m 2.31580E-09 9.91100E-08 671701 + 804 671710 Ho-171 2.77240E-08 6.66160E-08 671710 + 805 671720 Ho-172 1.71410E-08 3.11110E-08 671720 + 806 671730 Ho-173 3.15000E-12 3.15000E-12 671730 + 807 681690 Er-169 1.55920E-12 1.50760E-07 681690 + 808 681700 Er-170 4.41990E-11 1.04580E-07 68170.82c + 809 681710 Er-171 3.61340E-10 6.69780E-08 681710 + 810 681720 Er-172 2.28930E-09 3.34000E-08 681720 + 811 691720 Tm-172 1.64080E-12 3.34020E-08 691720 + + Neutron-induced fission: + + Interpolation region : 2 / 2 + Interpolation energy : 4.00000E-01 MeV + Number of products : 801 / 933 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 3.00310E-05 3.00310E-05 1001.82c + 2 10020 H-2 9.17770E-06 9.17770E-06 1002.82c + 3 10030 H-3 1.30940E-04 1.30940E-04 1003.82c + 4 20040 He-4 1.89850E-03 1.89850E-03 2004.82c + 5 220550 Ti-55 1.36370E-12 1.36370E-12 220550 + 6 220560 Ti-56 2.25450E-12 2.25450E-12 220560 + 7 230560 V-56 2.24750E-12 4.50200E-12 230560 + 8 230570 V-57 7.35950E-12 7.35950E-12 230570 + 9 230580 V-58 7.41320E-12 7.41320E-12 230580 + 10 230590 V-59 1.02930E-11 1.02930E-11 230590 + 11 230600 V-60 2.85480E-12 2.85480E-12 230600 + 12 230610 V-61 1.24100E-12 1.24100E-12 230610 + 13 240570 Cr-57 1.42120E-12 1.46820E-11 240570 + 14 240580 Cr-58 1.16080E-11 1.30910E-11 240580 + 15 240590 Cr-59 2.59090E-11 3.62020E-11 240590 + 16 240600 Cr-60 6.27810E-11 6.57100E-11 240600 + 17 240610 Cr-61 5.42880E-11 5.54540E-11 240610 + 18 240620 Cr-62 6.20490E-11 6.20490E-11 240620 + 19 240630 Cr-63 1.38570E-11 1.38570E-11 240630 + 20 240640 Cr-64 3.61460E-12 3.61460E-12 240640 + 21 250590 Mn-59 3.69940E-12 3.99010E-11 250590 + 22 250600 Mn-60 1.36700E-12 6.86770E-11 250600 + 23 250601 Mn-60m 1.39070E-11 1.39070E-11 250601 + 24 250610 Mn-61 1.05200E-10 1.60650E-10 250610 + 25 250620 Mn-62 1.71930E-10 2.02960E-10 250620 + 26 250621 Mn-62m 2.69260E-11 5.79500E-11 250621 + 27 250630 Mn-63 4.10220E-10 4.24080E-10 250630 + 28 250640 Mn-64 2.24760E-10 2.28370E-10 250640 + 29 250650 Mn-65 2.09360E-10 2.09360E-10 250650 + 30 250660 Mn-66 3.79380E-11 3.79380E-11 250660 + 31 250670 Mn-67 7.90550E-12 7.90550E-12 250670 + 32 260610 Fe-61 4.32000E-12 1.64970E-10 260610 + 33 260620 Fe-62 7.41560E-11 3.35070E-10 260620 + 34 260630 Fe-63 2.50400E-10 6.74480E-10 260630 + 35 260640 Fe-64 1.09620E-09 1.32460E-09 260640 + 36 260650 Fe-65 1.76520E-09 1.97460E-09 260650 + 37 260660 Fe-66 3.13140E-09 3.16930E-09 260660 + 38 260670 Fe-67 1.43850E-09 1.44640E-09 260670 + 39 260680 Fe-68 9.15070E-10 9.15070E-10 260680 + 40 260690 Fe-69 1.32510E-10 1.32510E-10 260690 + 41 260700 Fe-70 1.80400E-11 1.80400E-11 260700 + 42 270630 Co-63 7.02240E-12 6.81500E-10 270630 + 43 270640 Co-64 6.01260E-11 1.38470E-09 270640 + 44 270650 Co-65 8.33090E-10 2.80760E-09 270650 + 45 270660 Co-66 2.36450E-09 5.53380E-09 270660 + 46 270670 Co-67 8.88790E-09 1.03340E-08 270670 + 47 270680 Co-68 5.90870E-09 8.57600E-09 270680 + 48 270681 Co-68m 4.41030E-09 5.33470E-09 270681 + 49 270690 Co-69 1.54630E-08 1.55860E-08 270690 + 50 270700 Co-70 2.41810E-09 2.41810E-09 270700 + 51 270701 Co-70m 2.41810E-09 2.43610E-09 270701 + 52 270710 Co-71 2.49260E-09 2.49260E-09 270710 + 53 270720 Co-72 2.92030E-10 2.92030E-10 270720 + 54 270730 Co-73 3.10950E-11 3.10950E-11 270730 + 55 280650 Ni-65 6.22330E-12 2.81390E-09 280650 + 56 280660 Ni-66 1.84650E-10 5.71850E-09 280660 + 57 280670 Ni-67 1.28090E-09 1.16150E-08 280670 + 58 280680 Ni-68 1.22500E-08 2.36490E-08 280680 + 59 280690 Ni-69 1.46560E-08 3.00860E-08 280690 + 60 280691 Ni-69m 1.46560E-08 1.46560E-08 280691 + 61 280700 Ni-70 7.81420E-08 8.29960E-08 280700 + 62 280710 Ni-71 7.78890E-08 8.03820E-08 280710 + 63 280720 Ni-72 9.92740E-08 9.95660E-08 280720 + 64 280730 Ni-73 2.51240E-08 2.51550E-08 280730 + 65 280740 Ni-74 6.24440E-09 6.24440E-09 280740 + 66 280750 Ni-75 1.16220E-09 1.16220E-09 280750 + 67 280760 Ni-76 2.42430E-11 2.42430E-11 280760 + 68 290670 Cu-67 6.10980E-12 1.16210E-08 290670 + 69 290680 Cu-68 3.48710E-11 2.37640E-08 290680 + 70 290681 Cu-68m 9.50500E-11 9.50500E-11 290681 + 71 290690 Cu-69 3.07700E-09 4.78180E-08 290690 + 72 290700 Cu-70 9.69600E-10 9.26010E-09 290700 + 73 290701 Cu-70m 1.23830E-08 1.65810E-08 290701 + 74 290702 Cu-70m 9.69600E-10 8.39660E-08 290702 + 75 290710 Cu-71 1.14420E-07 1.94800E-07 290710 + 76 290720 Cu-72 2.37300E-07 3.36870E-07 290720 + 77 290730 Cu-73 5.39420E-07 5.64580E-07 290730 + 78 290740 Cu-74 2.74380E-07 2.80640E-07 290740 + 79 290750 Cu-75 5.79890E-07 5.81030E-07 290750 + 80 290760 Cu-76 1.48110E-08 1.48230E-08 290760 + 81 290761 Cu-76m 1.48110E-08 1.48230E-08 290761 + 82 290770 Cu-77 1.62690E-08 1.62690E-08 290770 + 83 290780 Cu-78 1.34530E-09 1.34530E-09 290780 + 84 290790 Cu-79 1.67400E-10 1.67400E-10 290790 + 85 300690 Zn-69 6.20170E-13 4.78220E-08 300690 + 86 300691 Zn-69m 3.08010E-12 3.08010E-12 300691 + 87 300700 Zn-70 2.00600E-10 9.75190E-08 300700 + 88 300710 Zn-71 5.69770E-10 1.95370E-07 300710 + 89 300711 Zn-71m 2.82980E-09 2.82980E-09 300711 + 90 300720 Zn-72 6.58620E-08 4.02730E-07 300720 + 91 300730 Zn-73 2.18780E-08 7.15390E-07 300730 + 92 300731 Zn-73m 3.02610E-08 1.28940E-07 300731 + 93 300732 Zn-73m 1.97360E-07 1.97360E-07 300732 + 94 300740 Zn-74 1.18160E-06 1.48260E-06 300740 + 95 300750 Zn-75 5.70380E-06 6.26490E-06 300750 + 96 300760 Zn-76 1.75140E-06 1.78060E-06 300760 + 97 300770 Zn-77 1.32810E-06 1.43280E-06 300770 + 98 300771 Zn-77m 1.76830E-07 1.76830E-07 300771 + 99 300780 Zn-78 1.36590E-05 1.36600E-05 300780 + 100 300790 Zn-79 3.15280E-06 3.15290E-06 300790 + 101 300800 Zn-80 1.55130E-07 1.55130E-07 300800 + 102 300810 Zn-81 1.66770E-06 1.66770E-06 300810 + 103 300820 Zn-82 4.05480E-10 4.05480E-10 300820 + 104 310710 Ga-71 2.49790E-12 1.98200E-07 310710 + 105 310720 Ga-72 1.06920E-10 4.02850E-07 310720 + 106 310721 Ga-72m 1.05100E-11 1.34300E-08 310721 + 107 310730 Ga-73 4.98650E-09 8.19060E-07 310730 + 108 310740 Ga-74 2.02930E-08 1.14740E-06 310740 + 109 310741 Ga-74m 2.02930E-08 1.50290E-06 310741 + 110 310750 Ga-75 1.27870E-06 7.54360E-06 310750 + 111 310760 Ga-76 1.82200E-06 3.60260E-06 310760 + 112 310770 Ga-77 4.51450E-06 6.03570E-06 310770 + 113 310780 Ga-78 6.07110E-06 1.97730E-05 310780 + 114 310790 Ga-79 2.99480E-05 3.30600E-05 310790 + 115 310800 Ga-80 2.50670E-05 2.53470E-05 310800 + 116 310810 Ga-81 3.83540E-05 3.98970E-05 310810 + 117 310820 Ga-82 3.32300E-06 3.32340E-06 310820 + 118 310830 Ga-83 3.62940E-07 3.62940E-07 310830 + 119 310840 Ga-84 1.27910E-08 1.27910E-08 310840 + 120 310850 Ga-85 5.26490E-10 5.26490E-10 310850 + 121 320740 Ge-74 9.06660E-11 1.52320E-06 32074.82c + 122 320750 Ge-75 7.89750E-10 7.55030E-06 320750 + 123 320751 Ge-75m 5.93160E-09 3.07680E-07 320751 + 124 320760 Ge-76 9.10990E-07 4.51360E-06 32076.82c + 125 320770 Ge-77 5.31210E-06 6.59330E-06 320770 + 126 320771 Ge-77m 7.07280E-07 6.74300E-06 320771 + 127 320780 Ge-78 1.51790E-05 3.49810E-05 320780 + 128 320790 Ge-79 1.14850E-05 4.79190E-05 320790 + 129 320791 Ge-79m 8.62630E-05 8.63120E-05 320791 + 130 320800 Ge-80 2.82540E-04 3.12640E-04 320800 + 131 320810 Ge-81 4.59950E-04 4.79960E-04 320810 + 132 320811 Ge-81m 9.26090E-05 1.09550E-04 320811 + 133 320820 Ge-82 1.00950E-03 1.01220E-03 320820 + 134 320830 Ge-83 5.68300E-04 5.68540E-04 320830 + 135 320840 Ge-84 2.89930E-04 2.89930E-04 320840 + 136 320850 Ge-85 7.05370E-05 7.05380E-05 320850 + 137 320860 Ge-86 1.79160E-05 1.79160E-05 320860 + 138 320870 Ge-87 5.79250E-09 5.79250E-09 320870 + 139 330760 As-76 1.54380E-11 1.54380E-11 330760 + 140 330770 As-77 3.40320E-09 1.20580E-05 330770 + 141 330780 As-78 1.12150E-07 3.50930E-05 330780 + 142 330790 As-79 4.72930E-06 1.35510E-04 330790 + 143 330800 As-80 4.68060E-05 3.59440E-04 330800 + 144 330810 As-81 1.60260E-04 7.48680E-04 330810 + 145 330820 As-82 1.58400E-04 1.17070E-03 330820 + 146 330821 As-82m 5.51920E-04 5.51920E-04 330821 + 147 330830 As-83 2.00000E-03 2.59980E-03 330830 + 148 330840 As-84 1.23770E-03 1.37200E-03 330840 + 149 330841 As-84m 1.23770E-03 1.37200E-03 330841 + 150 330850 As-85 1.78690E-03 1.84760E-03 330850 + 151 330860 As-86 5.98710E-04 6.16630E-04 330860 + 152 330870 As-87 2.37680E-04 2.37690E-04 330870 + 153 330880 As-88 2.79100E-05 2.79100E-05 330880 + 154 330890 As-89 1.60610E-06 1.60610E-06 330890 + 155 330900 As-90 1.05390E-09 1.05390E-09 330900 + 156 340780 Se-78 3.74950E-11 3.50930E-05 34078.82c + 157 340790 Se-79 4.18730E-09 1.35440E-04 34079.82c + 158 340791 Se-79m 5.57510E-10 1.32300E-04 340791 + 159 340800 Se-80 6.68200E-06 3.66120E-04 34080.82c + 160 340810 Se-81 2.93400E-06 7.73620E-04 340810 + 161 340811 Se-81m 2.20360E-05 4.89130E-05 340811 + 162 340820 Se-82 3.25110E-04 2.04770E-03 34082.82c + 163 340830 Se-83 1.41750E-03 2.35540E-03 340830 + 164 340831 Se-83m 2.85410E-04 1.95120E-03 340831 + 165 340840 Se-84 6.11700E-03 9.26350E-03 340840 + 166 340850 Se-85 1.03180E-02 1.19630E-02 340850 + 167 340860 Se-86 1.23980E-02 1.28480E-02 340860 + 168 340870 Se-87 8.17190E-03 8.37300E-03 340870 + 169 340880 Se-88 4.16830E-03 4.19620E-03 340880 + 170 340890 Se-89 1.16520E-03 1.16680E-03 340890 + 171 340900 Se-90 4.05280E-04 4.05280E-04 340900 + 172 340910 Se-91 4.75590E-05 4.75590E-05 340910 + 173 340920 Se-92 1.11330E-05 1.11330E-05 340920 + 174 350800 Br-80 3.59480E-12 1.61200E-11 350800 + 175 350801 Br-80m 1.25250E-11 1.25250E-11 350801 + 176 350810 Br-81 4.27930E-09 7.73650E-04 35081.82c + 177 350820 Br-82 1.21540E-06 1.65060E-06 350820 + 178 350821 Br-82m 4.45890E-07 4.45890E-07 350821 + 179 350830 Br-83 2.83240E-05 4.33490E-03 350830 + 180 350840 Br-84 1.46890E-04 9.41040E-03 350840 + 181 350841 Br-84m 1.46890E-04 1.46890E-04 350841 + 182 350850 Br-85 2.15250E-03 1.41150E-02 350850 + 183 350860 Br-86 5.41760E-03 1.82650E-02 350860 + 184 350870 Br-87 1.08020E-02 1.92170E-02 350870 + 185 350880 Br-88 1.09220E-02 1.51680E-02 350880 + 186 350890 Br-89 8.60130E-03 9.67710E-03 350890 + 187 350900 Br-90 5.18550E-03 5.60080E-03 350900 + 188 350910 Br-91 3.04420E-03 3.08180E-03 350910 + 189 350920 Br-92 6.07420E-04 6.18550E-04 350920 + 190 350930 Br-93 1.31140E-04 1.31140E-04 350930 + 191 350940 Br-94 1.03270E-05 1.03270E-05 350940 + 192 350950 Br-95 4.27500E-09 4.27500E-09 350950 + 193 360830 Kr-83 1.62670E-09 4.33490E-03 36083.82c + 194 360831 Kr-83m 3.27520E-10 4.33110E-03 360831 + 195 360840 Kr-84 1.54920E-05 9.57280E-03 36084.82c + 196 360850 Kr-85 9.53100E-05 3.13810E-03 36085.82c + 197 360851 Kr-85m 1.91900E-05 1.41110E-02 360851 + 198 360860 Kr-86 1.36030E-03 2.01080E-02 36086.82c + 199 360870 Kr-87 4.33820E-03 2.40890E-02 360870 + 200 360880 Kr-88 1.58430E-02 3.13590E-02 360880 + 201 360890 Kr-89 2.33070E-02 3.29970E-02 360890 + 202 360900 Kr-90 3.71340E-02 4.19730E-02 360900 + 203 360910 Kr-91 3.21640E-02 3.48340E-02 360910 + 204 360920 Kr-92 2.12530E-02 2.17560E-02 360920 + 205 360930 Kr-93 7.60840E-03 7.65760E-03 360930 + 206 360940 Kr-94 2.96130E-03 2.96440E-03 360940 + 207 360950 Kr-95 6.16420E-04 6.16420E-04 360950 + 208 360960 Kr-96 1.26210E-04 1.26210E-04 360960 + 209 360970 Kr-97 3.27350E-06 3.27350E-06 360970 + 210 370850 Rb-85 5.26490E-10 1.42300E-02 37085.82c + 211 370860 Rb-86 4.44240E-07 1.37620E-06 37086.82c + 212 370861 Rb-86m 9.31960E-07 9.31960E-07 370861 + 213 370870 Rb-87 4.41050E-05 2.41330E-02 37087.82c + 214 370880 Rb-88 1.67800E-04 3.15270E-02 370880 + 215 370890 Rb-89 1.25230E-03 3.42500E-02 370890 + 216 370900 Rb-90 4.17800E-04 3.71540E-02 370900 + 217 370901 Rb-90m 4.25040E-03 9.74050E-03 370901 + 218 370910 Rb-91 1.67110E-02 5.15450E-02 370910 + 219 370920 Rb-92 2.46330E-02 4.63890E-02 370920 + 220 370930 Rb-93 2.30980E-02 3.07880E-02 370930 + 221 370940 Rb-94 1.39530E-02 1.69020E-02 370940 + 222 370950 Rb-95 1.02500E-02 1.08530E-02 370950 + 223 370960 Rb-96 1.62160E-03 2.52370E-03 370960 + 224 370961 Rb-96m 1.62160E-03 1.68250E-03 370961 + 225 370970 Rb-97 1.03650E-03 1.03950E-03 370970 + 226 370980 Rb-98 6.69650E-05 6.69650E-05 370980 + 227 370981 Rb-98m 6.69650E-05 6.69650E-05 370981 + 228 370990 Rb-99 2.15310E-05 2.15310E-05 370990 + 229 371000 Rb-100 9.40170E-07 9.40170E-07 371000 + 230 380880 Sr-88 9.60510E-06 3.15360E-02 38088.82c + 231 380890 Sr-89 4.58380E-05 3.42960E-02 38089.82c + 232 380900 Sr-90 5.41130E-04 4.71830E-02 38090.82c + 233 380910 Sr-91 2.48870E-03 5.40340E-02 380910 + 234 380920 Sr-92 1.21700E-02 5.89900E-02 380920 + 235 380930 Sr-93 2.23890E-02 5.44540E-02 380930 + 236 380940 Sr-94 4.39840E-02 6.01120E-02 380940 + 237 380950 Sr-95 4.60740E-02 5.63320E-02 380950 + 238 380960 Sr-96 3.85450E-02 4.18330E-02 380960 + 239 380970 Sr-97 1.96210E-02 2.04090E-02 380970 + 240 380980 Sr-98 1.01800E-02 1.03080E-02 380980 + 241 380990 Sr-99 2.95070E-03 2.96890E-03 380990 + 242 381000 Sr-100 8.68000E-04 8.68890E-04 381000 + 243 381010 Sr-101 1.01390E-04 1.01390E-04 381010 + 244 381020 Sr-102 1.55290E-05 1.55290E-05 381020 + 245 390900 Y-90 3.94370E-10 4.71830E-02 39090.82c + 246 390901 Y-90m 6.59530E-10 6.59530E-10 390901 + 247 390910 Y-91 1.69910E-06 5.40440E-02 39091.82c + 248 390911 Y-91m 8.43890E-06 3.17990E-02 390911 + 249 390920 Y-92 5.88010E-05 5.90490E-02 390920 + 250 390930 Y-93 4.94520E-05 5.48740E-02 390930 + 251 390931 Y-93m 3.71420E-04 1.39980E-02 390931 + 252 390940 Y-94 1.56050E-03 6.16730E-02 390940 + 253 390950 Y-95 7.81570E-03 6.41480E-02 390950 + 254 390960 Y-96 4.74710E-03 4.65850E-02 390960 + 255 390961 Y-96m 9.95890E-03 9.96400E-03 390961 + 256 390970 Y-97 4.40600E-03 2.19360E-02 390970 + 257 390971 Y-97m 1.62860E-02 2.37990E-02 390971 + 258 390972 Y-97m 5.59690E-03 5.59690E-03 390972 + 259 390980 Y-98 3.87690E-03 1.41850E-02 390980 + 260 390981 Y-98m 1.87950E-02 1.87950E-02 390981 + 261 390990 Y-99 1.90520E-02 2.20280E-02 390990 + 262 391000 Y-100 4.82180E-03 5.68510E-03 391000 + 263 391001 Y-100m 4.82180E-03 4.82300E-03 391001 + 264 391010 Y-101 4.89100E-03 4.99080E-03 391010 + 265 391020 Y-102 5.80700E-04 5.88040E-04 391020 + 266 391021 Y-102m 5.80700E-04 5.88040E-04 391021 + 267 391030 Y-103 2.31290E-04 2.31290E-04 391030 + 268 391040 Y-104 2.80060E-05 2.80060E-05 391040 + 269 391050 Y-105 3.31870E-09 3.31870E-09 391050 + 270 400930 Zr-93 7.69750E-06 5.48820E-02 40093.82c + 271 400940 Zr-94 9.39940E-05 6.17670E-02 40094.82c + 272 400950 Zr-95 5.00960E-04 6.46490E-02 40095.82c + 273 400960 Zr-96 3.17210E-03 5.97400E-02 40096.82c + 274 400970 Zr-97 8.58570E-03 5.59390E-02 400970 + 275 400980 Zr-98 2.57460E-02 5.84160E-02 400980 + 276 400990 Zr-99 3.37620E-02 5.54680E-02 400990 + 277 401000 Zr-100 4.72400E-02 5.76960E-02 401000 + 278 401010 Zr-101 3.32680E-02 3.83170E-02 401010 + 279 401020 Zr-102 2.33680E-02 2.45050E-02 401020 + 280 401030 Zr-103 8.04690E-03 8.26210E-03 401030 + 281 401040 Zr-104 3.04920E-03 3.07470E-03 401040 + 282 401050 Zr-105 4.08890E-04 4.08890E-04 401050 + 283 401060 Zr-106 6.24740E-05 6.24740E-05 401060 + 284 401070 Zr-107 6.14540E-06 6.14540E-06 401070 + 285 401080 Zr-108 1.04340E-10 1.04340E-10 401080 + 286 410950 Nb-95 7.34980E-07 6.46110E-02 41095.82c + 287 410951 Nb-95m 1.47980E-07 6.98580E-04 410951 + 288 410960 Nb-96 6.84360E-06 6.84360E-06 410960 + 289 410970 Nb-97 6.47920E-05 5.60170E-02 410970 + 290 410971 Nb-97m 1.30460E-05 5.31820E-02 410971 + 291 410980 Nb-98 8.80400E-05 5.85040E-02 410980 + 292 410981 Nb-98m 3.06760E-04 3.06760E-04 410981 + 293 410990 Nb-99 1.78500E-03 3.72560E-02 410990 + 294 410991 Nb-99m 3.59400E-04 2.07710E-02 410991 + 295 411000 Nb-100 9.69060E-04 5.86650E-02 411000 + 296 411001 Nb-100m 4.69790E-03 4.69790E-03 411001 + 297 411010 Nb-101 1.48650E-02 5.31810E-02 411010 + 298 411020 Nb-102 9.35250E-03 3.38570E-02 411020 + 299 411021 Nb-102m 9.35250E-03 9.35250E-03 411021 + 300 411030 Nb-103 1.94470E-02 2.77090E-02 411030 + 301 411040 Nb-104 5.97600E-03 9.05650E-03 411040 + 302 411041 Nb-104m 5.97600E-03 5.97600E-03 411041 + 303 411050 Nb-105 6.50730E-03 6.91140E-03 411050 + 304 411060 Nb-106 1.43080E-03 1.49260E-03 411060 + 305 411070 Nb-107 5.70520E-04 5.76440E-04 411070 + 306 411080 Nb-108 8.35080E-05 8.35080E-05 411080 + 307 411090 Nb-109 1.50310E-08 1.50310E-08 411090 + 308 411100 Nb-110 1.05880E-10 1.05880E-10 411100 + 309 420980 Mo-98 9.06690E-06 5.88200E-02 42098.82c + 310 420990 Mo-99 7.21540E-05 5.76840E-02 42099.82c + 311 421000 Mo-100 5.76980E-04 6.39400E-02 42100.82c + 312 421010 Mo-101 1.92310E-03 5.51050E-02 421010 + 313 421020 Mo-102 6.98970E-03 5.02000E-02 421020 + 314 421030 Mo-103 1.05340E-02 3.82520E-02 421030 + 315 421040 Mo-104 1.62750E-02 3.14160E-02 421040 + 316 421050 Mo-105 1.11360E-02 1.79970E-02 421050 + 317 421060 Mo-106 6.46450E-03 7.92450E-03 421060 + 318 421070 Mo-107 3.28820E-03 3.83520E-03 421070 + 319 421080 Mo-108 1.23320E-03 1.31150E-03 421080 + 320 421090 Mo-109 1.97410E-04 1.97420E-04 421090 + 321 421100 Mo-110 3.19900E-05 3.19900E-05 421100 + 322 421110 Mo-111 3.30790E-05 3.30790E-05 421110 + 323 421120 Mo-112 3.45250E-09 3.45250E-09 421120 + 324 421130 Mo-113 1.44010E-11 1.44010E-11 421130 + 325 431010 Tc-101 9.73170E-06 5.51140E-02 431010 + 326 431020 Tc-102 2.20700E-05 5.02220E-02 431020 + 327 431021 Tc-102m 2.20700E-05 2.20700E-05 431021 + 328 431030 Tc-103 2.14990E-04 3.84670E-02 431030 + 329 431040 Tc-104 5.15100E-04 3.19320E-02 431040 + 330 431050 Tc-105 1.29880E-03 1.92960E-02 431050 + 331 431060 Tc-106 1.24890E-03 9.17340E-03 431060 + 332 431070 Tc-107 2.04390E-03 5.87910E-03 431070 + 333 431080 Tc-108 1.02150E-03 2.33410E-03 431080 + 334 431090 Tc-109 4.49780E-04 6.46160E-04 431090 + 335 431100 Tc-110 1.12140E-04 1.44470E-04 431100 + 336 431110 Tc-111 6.62970E-05 9.90350E-05 431110 + 337 431120 Tc-112 4.58640E-05 4.58670E-05 431120 + 338 431130 Tc-113 2.16410E-05 2.16410E-05 431130 + 339 431140 Tc-114 1.52670E-08 1.52670E-08 431140 + 340 431150 Tc-115 4.35150E-10 4.35150E-10 431150 + 341 441020 Ru-102 1.29460E-06 5.02450E-02 44102.82c + 342 441030 Ru-103 7.54140E-07 3.84690E-02 44103.82c + 343 441031 Ru-103m 2.11010E-06 2.11010E-06 441031 + 344 441040 Ru-104 1.68300E-05 3.19480E-02 44104.82c + 345 441050 Ru-105 4.04620E-05 1.93360E-02 44105.82c + 346 441060 Ru-106 1.25960E-04 9.29930E-03 44106.82c + 347 441070 Ru-107 2.60710E-04 6.13980E-03 441070 + 348 441080 Ru-108 2.71960E-04 2.60660E-03 441080 + 349 441090 Ru-109 2.62180E-04 9.07880E-04 441090 + 350 441100 Ru-110 4.17110E-04 5.61520E-04 441100 + 351 441110 Ru-111 4.48370E-04 5.48090E-04 441110 + 352 441120 Ru-112 6.87720E-04 7.34450E-04 441120 + 353 441130 Ru-113 1.62220E-04 2.63420E-04 441130 + 354 441131 Ru-113m 1.62220E-04 1.62220E-04 441131 + 355 441140 Ru-114 7.66600E-05 7.66740E-05 441140 + 356 441150 Ru-115 1.06380E-04 1.06380E-04 441150 + 357 441160 Ru-116 3.14700E-05 3.14700E-05 441160 + 358 441170 Ru-117 3.33780E-09 3.33780E-09 441170 + 359 441180 Ru-118 5.81010E-11 5.81010E-11 441180 + 360 441190 Ru-119 1.19880E-06 1.19880E-06 441190 + 361 441200 Ru-120 6.95560E-08 6.95560E-08 441200 + 362 451060 Rh-106 9.80840E-10 9.29930E-03 451060 + 363 451061 Rh-106m 2.67360E-09 2.67360E-09 451061 + 364 451070 Rh-107 1.91850E-07 6.14000E-03 451070 + 365 451080 Rh-108 3.17190E-07 2.60690E-03 451080 + 366 451081 Rh-108m 1.10520E-06 1.10520E-06 451081 + 367 451090 Rh-109 9.92750E-06 9.17810E-04 451090 + 368 451100 Rh-110 3.13110E-05 5.92830E-04 451100 + 369 451101 Rh-110m 7.37100E-07 7.37100E-07 451101 + 370 451110 Rh-111 4.97510E-05 5.97840E-04 451110 + 371 451120 Rh-112 1.14750E-04 8.49210E-04 451120 + 372 451121 Rh-112m 1.14750E-04 1.14750E-04 451121 + 373 451130 Rh-113 1.29910E-04 4.74450E-04 451130 + 374 451140 Rh-114 2.29930E-04 3.06850E-04 451140 + 375 451141 Rh-114m 2.29930E-04 2.29930E-04 451141 + 376 451150 Rh-115 3.72330E-04 4.78810E-04 451150 + 377 451160 Rh-116 5.06630E-05 8.17930E-05 451160 + 378 451161 Rh-116m 1.38100E-04 1.38100E-04 451161 + 379 451170 Rh-117 1.18910E-04 1.18910E-04 451170 + 380 451180 Rh-118 4.59700E-07 5.12000E-07 451180 + 381 451190 Rh-119 2.67470E-05 2.78940E-05 451190 + 382 451200 Rh-120 2.83870E-05 2.84570E-05 451200 + 383 451210 Rh-121 5.75950E-06 5.75950E-06 451210 + 384 451220 Rh-122 2.42510E-07 2.42510E-07 451220 + 385 461080 Pd-108 1.04340E-10 2.60800E-03 46108.82c + 386 461090 Pd-109 8.38880E-10 9.17810E-04 461090 + 387 461091 Pd-109m 1.84380E-09 4.58900E-04 461091 + 388 461100 Pd-110 1.01250E-07 5.93670E-04 46110.82c + 389 461110 Pd-111 4.17240E-07 5.98290E-04 461110 + 390 461111 Pd-111m 9.17060E-07 3.30840E-06 461111 + 391 461120 Pd-112 2.29390E-05 9.86890E-04 461120 + 392 461130 Pd-113 1.71040E-05 5.39410E-04 461130 + 393 461131 Pd-113m 4.78570E-05 4.78570E-05 461131 + 394 461140 Pd-114 3.83820E-04 9.20600E-04 461140 + 395 461150 Pd-115 1.33280E-04 5.71570E-04 461150 + 396 461151 Pd-115m 2.92950E-04 3.62470E-04 461151 + 397 461160 Pd-116 7.55760E-04 9.75650E-04 461160 + 398 461170 Pd-117 1.48740E-04 5.94600E-04 461170 + 399 461171 Pd-117m 3.26930E-04 3.26930E-04 461171 + 400 461180 Pd-118 4.46930E-04 4.47430E-04 461180 + 401 461190 Pd-119 2.93880E-04 3.23460E-04 461190 + 402 461200 Pd-120 7.76640E-05 1.05220E-04 461200 + 403 461210 Pd-121 2.92720E-05 3.42500E-05 461210 + 404 461220 Pd-122 1.97160E-05 1.99580E-05 461220 + 405 461230 Pd-123 1.82490E-05 1.82490E-05 461230 + 406 461240 Pd-124 2.37240E-06 2.37240E-06 461240 + 407 471110 Ag-111 2.57390E-11 5.96210E-04 47111.82c + 408 471111 Ag-111m 1.93320E-10 5.94710E-04 471111 + 409 471120 Ag-112 1.35430E-08 9.86910E-04 471120 + 410 471130 Ag-113 3.72450E-08 3.53680E-04 471130 + 411 471131 Ag-113m 2.79740E-07 5.16800E-04 471131 + 412 471140 Ag-114 8.94720E-07 9.25830E-04 471140 + 413 471141 Ag-114m 4.33760E-06 4.33760E-06 471141 + 414 471150 Ag-115 3.12740E-06 5.27740E-04 471150 + 415 471151 Ag-115m 2.34890E-05 5.11280E-04 471151 + 416 471160 Ag-116 1.69010E-05 9.95320E-04 471160 + 417 471161 Ag-116m 4.60670E-05 4.60670E-05 471161 + 418 471170 Ag-117 3.14840E-05 3.60810E-04 471170 + 419 471171 Ag-117m 2.36470E-04 5.33760E-04 471171 + 420 471180 Ag-118 4.43660E-05 5.42240E-04 471180 + 421 471181 Ag-118m 2.15080E-04 2.79050E-04 471181 + 422 471190 Ag-119 5.03430E-05 2.12070E-04 471190 + 423 471191 Ag-119m 3.78110E-04 5.39840E-04 471191 + 424 471200 Ag-120 7.75080E-05 1.97630E-04 471200 + 425 471201 Ag-120m 1.29620E-04 1.82230E-04 471201 + 426 471210 Ag-121 3.21660E-04 3.55820E-04 471210 + 427 471220 Ag-122 2.84470E-05 4.84050E-05 471220 + 428 471221 Ag-122m 3.06690E-05 3.06690E-05 471221 + 429 471230 Ag-123 5.96910E-05 7.79400E-05 471230 + 430 471240 Ag-124 1.55410E-05 2.62910E-05 471240 + 431 471241 Ag-124m 1.67550E-05 1.67550E-05 471241 + 432 471250 Ag-125 6.17920E-05 6.17920E-05 471250 + 433 471260 Ag-126 1.59330E-05 1.59330E-05 471260 + 434 471270 Ag-127 2.03310E-06 2.03310E-06 471270 + 435 471280 Ag-128 6.98010E-08 6.98010E-08 471280 + 436 471290 Ag-129 2.79890E-09 2.79890E-09 471290 + 437 481130 Cd-113 3.00840E-12 5.33620E-04 48113.82c + 438 481131 Cd-113m 1.13930E-11 6.11470E-06 481131 + 439 481140 Cd-114 2.59920E-09 9.25830E-04 48114.82c + 440 481150 Cd-115 1.54260E-08 8.89500E-04 481150 + 441 481151 Cd-115m 5.84200E-08 4.22280E-05 48515.82c + 442 481160 Cd-116 2.59270E-06 1.04120E-03 48116.82c + 443 481170 Cd-117 1.24340E-05 6.89620E-04 481170 + 444 481171 Cd-117m 4.70870E-05 2.32450E-04 481171 + 445 481180 Cd-118 2.35650E-05 7.30440E-04 481180 + 446 481190 Cd-119 2.82070E-05 6.74080E-04 481190 + 447 481191 Cd-119m 7.89230E-05 1.84960E-04 481191 + 448 481200 Cd-120 4.41300E-04 7.53730E-04 481200 + 449 481210 Cd-121 1.08070E-04 4.26700E-04 481210 + 450 481211 Cd-121m 3.02360E-04 3.39540E-04 481211 + 451 481220 Cd-122 6.68820E-04 7.47900E-04 481220 + 452 481230 Cd-123 1.88200E-04 2.51980E-04 481230 + 453 481231 Cd-123m 5.26560E-04 5.40750E-04 481231 + 454 481240 Cd-124 4.80850E-04 5.15490E-04 481240 + 455 481250 Cd-125 7.01190E-05 1.01010E-04 481250 + 456 481251 Cd-125m 1.96190E-04 2.27090E-04 481251 + 457 481260 Cd-126 1.04000E-03 1.05590E-03 481260 + 458 481270 Cd-127 5.17590E-04 5.19620E-04 481270 + 459 481280 Cd-128 2.25900E-04 2.25970E-04 481280 + 460 481290 Cd-129 2.10510E-05 2.10520E-05 481290 + 461 481291 Cd-129m 5.88980E-05 5.89000E-05 481291 + 462 481300 Cd-130 2.64810E-05 2.64810E-05 481300 + 463 481310 Cd-131 7.65120E-08 7.65120E-08 481310 + 464 481320 Cd-132 1.68880E-09 1.68880E-09 481320 + 465 491160 In-116 3.62020E-11 3.62020E-11 491160 + 466 491161 In-116m 5.84590E-11 1.26140E-10 491161 + 467 491162 In-116m 6.76800E-11 6.76800E-11 491162 + 468 491170 In-117 1.04770E-08 5.85890E-04 491170 + 469 491171 In-117m 2.10960E-09 6.35520E-04 491171 + 470 491180 In-118 4.57680E-08 7.30490E-04 491180 + 471 491181 In-118m 7.39070E-08 1.58270E-07 491181 + 472 491182 In-118m 8.55650E-08 8.55650E-08 491182 + 473 491200 In-120 8.63880E-06 7.62370E-04 491200 + 474 491201 In-120m 8.63880E-06 8.63880E-06 491201 + 475 491202 In-120m 8.63880E-06 8.63880E-06 491202 + 476 491210 In-121 4.87760E-05 5.35550E-04 491210 + 477 491211 In-121m 9.82090E-06 2.92810E-04 491211 + 478 491220 In-122 1.47750E-05 7.62670E-04 491220 + 479 491221 In-122m 1.23540E-05 1.23540E-05 491221 + 480 491222 In-122m 1.23540E-05 1.23540E-05 491222 + 481 491230 In-123 1.49280E-04 7.61480E-04 491230 + 482 491231 In-123m 3.00570E-05 2.10580E-04 491231 + 483 491240 In-124 1.39610E-04 6.55100E-04 491240 + 484 491241 In-124m 1.50520E-04 1.50520E-04 491241 + 485 491250 In-125 3.87290E-04 6.62730E-04 491250 + 486 491251 In-125m 7.79790E-05 1.30650E-04 491251 + 487 491260 In-126 4.65600E-04 1.52150E-03 491260 + 488 491261 In-126m 5.01990E-04 5.01990E-04 491261 + 489 491270 In-127 1.38650E-03 1.38650E-03 491270 + 490 491271 In-127m 2.79160E-04 7.98780E-04 491271 + 491 491280 In-128 4.36740E-04 8.33730E-04 491280 + 492 491281 In-128m 1.71010E-04 3.96980E-04 491281 + 493 491282 In-128m 6.55240E-04 6.55240E-04 491282 + 494 491290 In-129 1.13170E-03 1.19110E-03 491290 + 495 491291 In-129m 2.27870E-04 2.49380E-04 491291 + 496 491300 In-130 2.08300E-04 2.33860E-04 491300 + 497 491301 In-130m 3.03300E-04 3.03300E-04 491301 + 498 491302 In-130m 4.22480E-04 4.22480E-04 491302 + 499 491310 In-131 1.55770E-04 1.57430E-04 491310 + 500 491311 In-131m 1.55770E-04 1.55770E-04 491311 + 501 491312 In-131m 1.55770E-04 1.55770E-04 491312 + 502 491320 In-132 4.99610E-05 4.99620E-05 491320 + 503 491330 In-133 3.79640E-06 4.56080E-06 491330 + 504 491331 In-133m 7.64390E-07 7.64390E-07 491331 + 505 491340 In-134 2.26690E-08 2.26690E-08 491340 + 506 501180 Sn-118 2.90500E-11 7.30650E-04 50118.82c + 507 501220 Sn-122 1.98230E-05 8.07200E-04 50122.82c + 508 501230 Sn-123 2.20740E-05 8.01310E-05 50123.82c + 509 501231 Sn-123m 7.88930E-06 9.21900E-04 501231 + 510 501240 Sn-124 1.30800E-04 9.36420E-04 50124.82c + 511 501250 Sn-125 1.75750E-04 2.87690E-04 50125.82c + 512 501251 Sn-125m 6.28130E-05 7.44240E-04 501251 + 513 501260 Sn-126 8.58010E-04 2.88700E-03 50126.82c + 514 501270 Sn-127 1.04230E-03 1.58270E-03 501270 + 515 501271 Sn-127m 3.72520E-04 2.01180E-03 501271 + 516 501280 Sn-128 1.13100E-03 5.70270E-03 501280 + 517 501281 Sn-128m 3.08270E-03 3.73800E-03 501281 + 518 501290 Sn-129 1.89870E-03 3.21250E-03 501290 + 519 501291 Sn-129m 5.31240E-03 5.43920E-03 501291 + 520 501300 Sn-130 4.11110E-03 4.70130E-03 501300 + 521 501301 Sn-130m 1.12060E-02 1.15790E-02 501301 + 522 501310 Sn-131 3.90840E-03 4.21020E-03 501310 + 523 501311 Sn-131m 1.09360E-02 1.10980E-02 501311 + 524 501320 Sn-132 1.14100E-02 1.14640E-02 501320 + 525 501330 Sn-133 2.57710E-03 2.57780E-03 501330 + 526 501340 Sn-134 4.58160E-04 4.58170E-04 501340 + 527 501350 Sn-135 4.10370E-05 4.10370E-05 501350 + 528 501360 Sn-136 1.56110E-06 1.56110E-06 501360 + 529 501370 Sn-137 3.28660E-09 3.28660E-09 501370 + 530 511250 Sb-125 4.54050E-10 1.03190E-03 51125.82c + 531 511260 Sb-126 2.06580E-08 2.47040E-08 51126.82c + 532 511261 Sb-126m 1.29030E-08 2.88980E-08 511261 + 533 511262 Sb-126m 1.59950E-08 1.59950E-08 511262 + 534 511270 Sb-127 3.08320E-05 3.62530E-03 511270 + 535 511280 Sb-128 4.79020E-05 5.75300E-03 511280 + 536 511281 Sb-128m 6.69980E-05 6.69980E-05 511281 + 537 511290 Sb-129 6.25220E-04 7.03460E-03 511290 + 538 511291 Sb-129m 4.62680E-04 3.18220E-03 511291 + 539 511300 Sb-130 1.58200E-03 1.20730E-02 511300 + 540 511301 Sb-130m 1.58200E-03 7.37130E-03 511301 + 541 511310 Sb-131 1.45270E-02 2.98350E-02 511310 + 542 511320 Sb-132 9.83570E-03 2.13000E-02 511320 + 543 511321 Sb-132m 8.70830E-03 8.70830E-03 511321 + 544 511330 Sb-133 3.08850E-02 3.35410E-02 511330 + 545 511340 Sb-134 2.45730E-03 2.84180E-03 511340 + 546 511341 Sb-134m 6.69790E-03 6.70220E-03 511341 + 547 511350 Sb-135 3.66590E-03 3.69880E-03 511350 + 548 511360 Sb-136 5.61070E-04 5.62160E-04 511360 + 549 511370 Sb-137 1.09250E-04 1.09250E-04 511370 + 550 511380 Sb-138 7.67710E-06 7.67710E-06 511380 + 551 511390 Sb-139 3.68620E-08 3.68620E-08 511390 + 552 521270 Te-127 2.57230E-11 3.61100E-03 521270 + 553 521271 Te-127m 7.19710E-11 5.97440E-04 52527.82c + 554 521280 Te-128 9.96280E-06 5.82750E-03 52128.82c + 555 521290 Te-129 2.19050E-06 8.33620E-03 521290 + 556 521291 Te-129m 6.12880E-06 3.81510E-03 52529.82c + 557 521300 Te-130 3.65650E-04 1.98100E-02 52130.82c + 558 521310 Te-131 5.18460E-04 2.87710E-02 521310 + 559 521311 Te-131m 1.45060E-03 3.83930E-03 521311 + 560 521320 Te-132 1.24080E-02 4.24160E-02 52132.82c + 561 521330 Te-133 8.99850E-03 4.21650E-02 521330 + 562 521331 Te-133m 2.51770E-02 3.09790E-02 521331 + 563 521340 Te-134 6.65640E-02 7.66840E-02 521340 + 564 521350 Te-135 3.80320E-02 4.12420E-02 521350 + 565 521360 Te-136 2.25160E-02 2.30380E-02 521360 + 566 521370 Te-137 7.90600E-03 7.96170E-03 521370 + 567 521380 Te-138 2.88490E-03 2.89260E-03 521380 + 568 521390 Te-139 3.74810E-04 3.74850E-04 521390 + 569 521400 Te-140 1.00800E-04 1.00800E-04 521400 + 570 521410 Te-141 2.83430E-06 2.83430E-06 521410 + 571 521420 Te-142 4.28330E-09 4.28330E-09 521420 + 572 531300 I-130 3.13240E-09 4.09770E-09 53130.82c + 573 531301 I-130m 1.14920E-09 1.14920E-09 531301 + 574 531310 I-131 1.19190E-05 3.18160E-02 53131.82c + 575 531320 I-132 3.45270E-05 4.24770E-02 531320 + 576 531321 I-132m 3.05700E-05 3.05700E-05 531321 + 577 531330 I-133 5.98780E-04 6.87650E-02 531330 + 578 531331 I-133m 4.43120E-04 4.43120E-04 531331 + 579 531340 I-134 1.57980E-03 7.96310E-02 531340 + 580 531341 I-134m 1.39870E-03 1.39870E-03 531341 + 581 531350 I-135 2.17520E-02 6.29940E-02 53135.82c + 582 531360 I-136 6.15090E-03 2.93080E-02 531360 + 583 531361 I-136m 1.67660E-02 1.68850E-02 531361 + 584 531370 I-137 3.09810E-02 3.88870E-02 531370 + 585 531380 I-138 1.08800E-02 1.35900E-02 531380 + 586 531390 I-139 1.32900E-02 1.36650E-02 531390 + 587 531400 I-140 3.26110E-03 3.36190E-03 531400 + 588 531410 I-141 1.18140E-03 1.18420E-03 531410 + 589 531420 I-142 1.56830E-04 1.56830E-04 531420 + 590 531430 I-143 2.18850E-05 2.18850E-05 531430 + 591 531440 I-144 1.51490E-06 1.51490E-06 531440 + 592 541320 Xe-132 7.21790E-10 4.24810E-02 54132.82c + 593 541321 Xe-132m 9.67010E-10 9.67010E-10 541321 + 594 541330 Xe-133 4.00560E-06 6.87800E-02 54133.82c + 595 541331 Xe-133m 1.12070E-05 1.96850E-03 541331 + 596 541340 Xe-134 3.30130E-05 7.97860E-02 54134.82c + 597 541341 Xe-134m 8.99870E-05 1.22160E-04 541341 + 598 541350 Xe-135 2.19630E-04 6.37620E-02 54135.82c + 599 541351 Xe-135m 6.14530E-04 1.10140E-02 541351 + 600 541360 Xe-136 8.29010E-03 5.70110E-02 54136.82c + 601 541370 Xe-137 2.22400E-02 5.93190E-02 541370 + 602 541380 Xe-138 4.24480E-02 5.66570E-02 541380 + 603 541390 Xe-139 4.48050E-02 5.74430E-02 541390 + 604 541400 Xe-140 4.38480E-02 4.71460E-02 541400 + 605 541410 Xe-141 2.04940E-02 2.14690E-02 541410 + 606 541420 Xe-142 1.29770E-02 1.31030E-02 541420 + 607 541430 Xe-143 2.93020E-03 2.94390E-03 541430 + 608 541440 Xe-144 8.34050E-04 8.34960E-04 541440 + 609 541450 Xe-145 1.24860E-04 1.24860E-04 541450 + 610 541460 Xe-146 1.95830E-05 1.95830E-05 541460 + 611 541470 Xe-147 1.70340E-09 1.70340E-09 541470 + 612 551350 Cs-135 5.75500E-07 6.38290E-02 55135.82c + 613 551351 Cs-135m 4.25890E-07 4.25890E-07 551351 + 614 551360 Cs-136 3.18660E-06 4.32580E-06 55136.82c + 615 551361 Cs-136m 2.27840E-06 2.27840E-06 551361 + 616 551370 Cs-137 2.46330E-04 5.95660E-02 55137.82c + 617 551380 Cs-138 4.77630E-04 5.77820E-02 551380 + 618 551381 Cs-138m 7.98770E-04 7.98770E-04 551381 + 619 551390 Cs-139 6.73520E-03 6.41780E-02 551390 + 620 551400 Cs-140 9.25410E-03 5.64100E-02 551400 + 621 551410 Cs-141 2.80200E-02 4.95270E-02 551410 + 622 551420 Cs-142 2.17960E-02 3.48820E-02 551420 + 623 551430 Cs-143 1.87900E-02 2.17290E-02 551430 + 624 551440 Cs-144 3.76800E-03 6.46670E-03 551440 + 625 551441 Cs-144m 3.76800E-03 3.77120E-03 551441 + 626 551450 Cs-145 4.40480E-03 4.52480E-03 551450 + 627 551460 Cs-146 9.73420E-04 9.91650E-04 551460 + 628 551470 Cs-147 1.44630E-04 1.44630E-04 551470 + 629 551480 Cs-148 2.85130E-05 2.85130E-05 551480 + 630 551490 Cs-149 3.42660E-06 3.42660E-06 551490 + 631 561370 Ba-137 4.60990E-07 5.95680E-02 56137.82c + 632 561371 Ba-137m 1.28980E-06 5.62310E-02 561371 + 633 561380 Ba-138 2.45960E-05 5.79580E-02 56138.82c + 634 561390 Ba-139 3.42370E-04 6.45210E-02 561390 + 635 561400 Ba-140 1.60090E-03 5.80100E-02 56140.82c + 636 561410 Ba-141 4.70350E-03 5.42300E-02 561410 + 637 561420 Ba-142 1.86860E-02 5.39240E-02 561420 + 638 561430 Ba-143 2.48700E-02 4.64500E-02 561430 + 639 561440 Ba-144 3.82510E-02 4.70430E-02 561440 + 640 561450 Ba-145 2.72890E-02 3.13080E-02 561450 + 641 561460 Ba-146 2.23240E-02 2.32160E-02 561460 + 642 561470 Ba-147 5.51500E-03 5.62560E-03 561470 + 643 561480 Ba-148 2.72990E-03 2.75130E-03 561480 + 644 561490 Ba-149 4.45840E-04 4.49270E-04 561490 + 645 561500 Ba-150 5.91410E-05 5.91410E-05 561500 + 646 561510 Ba-151 2.91760E-06 2.91760E-06 561510 + 647 561520 Ba-152 8.02920E-10 8.02920E-10 561520 + 648 571400 La-140 2.52500E-06 5.80130E-02 57140.82c + 649 571410 La-141 2.17470E-05 5.42520E-02 571410 + 650 571420 La-142 1.01930E-04 5.40260E-02 571420 + 651 571430 La-143 6.56840E-04 4.71070E-02 571430 + 652 571440 La-144 1.95340E-03 4.89970E-02 571440 + 653 571450 La-145 8.53200E-03 3.98390E-02 571450 + 654 571460 La-146 3.24870E-03 2.64650E-02 571460 + 655 571461 La-146m 6.81530E-03 6.81530E-03 571461 + 656 571470 La-147 1.14940E-02 1.71310E-02 571470 + 657 571480 La-148 7.36360E-03 1.01060E-02 571480 + 658 571490 La-149 5.36670E-03 5.81400E-03 571490 + 659 571500 La-150 1.19780E-03 1.25690E-03 571500 + 660 571510 La-151 3.79980E-04 3.82900E-04 571510 + 661 571520 La-152 5.68890E-05 5.68900E-05 571520 + 662 571530 La-153 6.00650E-06 6.00650E-06 571530 + 663 571540 La-154 1.26870E-09 1.26870E-09 571540 + 664 581420 Ce-142 3.59810E-06 5.40300E-02 58142.82c + 665 581430 Ce-143 8.92480E-06 4.71160E-02 58143.82c + 666 581440 Ce-144 1.03420E-04 4.91000E-02 58144.82c + 667 581450 Ce-145 6.20250E-04 4.04600E-02 581450 + 668 581460 Ce-146 2.63950E-03 3.59200E-02 581460 + 669 581470 Ce-147 4.13420E-03 2.12650E-02 581470 + 670 581480 Ce-148 1.06550E-02 2.08420E-02 581480 + 671 581490 Ce-149 1.01180E-02 1.58850E-02 581490 + 672 581500 Ce-150 8.85990E-03 1.00830E-02 581500 + 673 581510 Ce-151 4.57050E-03 4.95680E-03 581510 + 674 581520 Ce-152 2.72960E-03 2.78310E-03 581520 + 675 581530 Ce-153 3.51720E-04 3.57730E-04 581530 + 676 581540 Ce-154 5.93720E-05 5.93730E-05 581540 + 677 581550 Ce-155 7.47130E-06 7.47130E-06 581550 + 678 581560 Ce-156 4.36760E-09 4.36760E-09 581560 + 679 581570 Ce-157 1.63460E-11 1.63460E-11 581570 + 680 591450 Pr-145 9.78260E-07 4.04610E-02 591450 + 681 591460 Pr-146 6.18510E-06 3.59260E-02 591460 + 682 591470 Pr-147 2.52000E-05 2.12900E-02 591470 + 683 591480 Pr-148 2.10060E-05 2.08630E-02 591480 + 684 591481 Pr-148m 1.01830E-04 1.01830E-04 591481 + 685 591490 Pr-149 5.35870E-04 1.64200E-02 591490 + 686 591500 Pr-150 7.88390E-04 1.08710E-02 591500 + 687 591510 Pr-151 1.64360E-03 6.60040E-03 591510 + 688 591520 Pr-152 1.60060E-03 4.38590E-03 591520 + 689 591530 Pr-153 1.15350E-03 1.50940E-03 591530 + 690 591540 Pr-154 4.14580E-04 4.73580E-04 591540 + 691 591550 Pr-155 1.09350E-04 1.16820E-04 591550 + 692 591560 Pr-156 3.61860E-05 3.61900E-05 591560 + 693 591570 Pr-157 2.26930E-07 2.26950E-07 591570 + 694 591580 Pr-158 2.77960E-09 2.77960E-09 591580 + 695 591590 Pr-159 2.12630E-11 2.12630E-11 591590 + 696 601480 Nd-148 9.83930E-07 2.09660E-02 60148.82c + 697 601490 Nd-149 2.16670E-05 1.64420E-02 601490 + 698 601500 Nd-150 7.70680E-05 1.09480E-02 60150.82c + 699 601510 Nd-151 3.18330E-04 6.91880E-03 601510 + 700 601520 Nd-152 7.84020E-04 5.16990E-03 601520 + 701 601530 Nd-153 7.59300E-04 2.26870E-03 601530 + 702 601540 Nd-154 8.84670E-04 1.35820E-03 601540 + 703 601550 Nd-155 3.75490E-04 4.93300E-04 601550 + 704 601560 Nd-156 2.13840E-04 2.49060E-04 601560 + 705 601570 Nd-157 5.54610E-05 5.56740E-05 601570 + 706 601580 Nd-158 1.50580E-05 1.50610E-05 601580 + 707 601590 Nd-159 6.78490E-08 6.78700E-08 601590 + 708 601600 Nd-160 6.42540E-09 6.42540E-09 601600 + 709 601610 Nd-161 5.07030E-11 5.07030E-11 601610 + 710 611500 Pm-150 6.88610E-10 6.88610E-10 611500 + 711 611510 Pm-151 4.51660E-08 6.91880E-03 61151.82c + 712 611520 Pm-152 6.92930E-07 5.17060E-03 611520 + 713 611521 Pm-152m 1.45680E-06 1.45680E-06 611521 + 714 611522 Pm-152m 1.90290E-06 1.90290E-06 611522 + 715 611530 Pm-153 6.00220E-06 2.27470E-03 611530 + 716 611540 Pm-154 1.01920E-05 1.36840E-03 611540 + 717 611541 Pm-154m 1.01920E-05 1.01920E-05 611541 + 718 611550 Pm-155 6.22230E-05 5.55520E-04 611550 + 719 611560 Pm-156 4.27850E-05 2.91850E-04 611560 + 720 611570 Pm-157 5.15160E-05 1.07190E-04 611570 + 721 611580 Pm-158 1.00390E-05 2.50990E-05 611580 + 722 611590 Pm-159 5.79220E-06 5.86000E-06 611590 + 723 611600 Pm-160 1.03320E-06 1.03960E-06 611600 + 724 611610 Pm-161 9.96750E-08 9.97260E-08 611610 + 725 611620 Pm-162 1.43660E-08 1.43660E-08 611620 + 726 611630 Pm-163 5.44750E-11 5.44750E-11 611630 + 727 621530 Sm-153 3.72460E-10 2.27470E-03 62153.82c + 728 621531 Sm-153m 1.04210E-09 1.04210E-09 621531 + 729 621540 Sm-154 2.26470E-06 1.38090E-03 62154.82c + 730 621550 Sm-155 4.54200E-07 5.55970E-04 621550 + 731 621560 Sm-156 1.64550E-05 3.08300E-04 621560 + 732 621570 Sm-157 1.58520E-05 1.23040E-04 621570 + 733 621580 Sm-158 2.51010E-05 5.02010E-05 621580 + 734 621590 Sm-159 5.79240E-06 1.16540E-05 621590 + 735 621600 Sm-160 1.13660E-05 1.24030E-05 621600 + 736 621610 Sm-161 1.98280E-06 2.08250E-06 621610 + 737 621620 Sm-162 9.61730E-06 9.63170E-06 621620 + 738 621630 Sm-163 2.72400E-08 2.72940E-08 621630 + 739 621640 Sm-164 1.87170E-09 1.87170E-09 621640 + 740 621650 Sm-165 3.50790E-11 3.50790E-11 621650 + 741 631550 Eu-155 3.70280E-11 5.55970E-04 63155.82c + 742 631560 Eu-156 1.09110E-09 3.08300E-04 63156.82c + 743 631570 Eu-157 2.42020E-08 1.23070E-04 63157.82c + 744 631580 Eu-158 1.23740E-07 5.03250E-05 631580 + 745 631590 Eu-159 4.06710E-07 1.20610E-05 631590 + 746 631600 Eu-160 1.33550E-06 1.37380E-05 631600 + 747 631610 Eu-161 1.99430E-06 4.07680E-06 631610 + 748 631620 Eu-162 4.96340E-06 1.45950E-05 631620 + 749 631630 Eu-163 3.89100E-07 4.16390E-07 631630 + 750 631640 Eu-164 5.34550E-08 5.53270E-08 631640 + 751 631650 Eu-165 1.12330E-08 1.12680E-08 631650 + 752 631660 Eu-166 4.47990E-10 4.47990E-10 631660 + 753 631670 Eu-167 2.43350E-11 2.43350E-11 631670 + 754 641580 Gd-158 3.39450E-11 5.03250E-05 64158.82c + 755 641590 Gd-159 2.86740E-10 1.20610E-05 641590 + 756 641600 Gd-160 1.13600E-08 1.37500E-05 64160.82c + 757 641610 Gd-161 3.76520E-08 4.11450E-06 641610 + 758 641620 Gd-162 9.20380E-07 1.55150E-05 641620 + 759 641630 Gd-163 1.25070E-07 5.41460E-07 641630 + 760 641640 Gd-164 1.38380E-07 1.93710E-07 641640 + 761 641650 Gd-165 4.84170E-08 5.96850E-08 641650 + 762 641660 Gd-166 1.79510E-08 1.83990E-08 641660 + 763 641670 Gd-167 2.06640E-09 2.09070E-09 641670 + 764 641680 Gd-168 3.24430E-10 3.24430E-10 641680 + 765 641690 Gd-169 1.02280E-11 1.02280E-11 641690 + 766 651610 Tb-161 1.65490E-11 4.11450E-06 651610 + 767 651620 Tb-162 1.00950E-09 1.55160E-05 651620 + 768 651630 Tb-163 1.59800E-09 5.43060E-07 651630 + 769 651640 Tb-164 3.72430E-09 1.97430E-07 651640 + 770 651650 Tb-165 1.20340E-08 7.17190E-08 651650 + 771 651660 Tb-166 7.39890E-09 2.57980E-08 651660 + 772 651670 Tb-167 6.86870E-09 8.95940E-09 651670 + 773 651680 Tb-168 1.87990E-09 2.20430E-09 651680 + 774 651690 Tb-169 5.86010E-10 5.96240E-10 651690 + 775 651700 Tb-170 4.26350E-11 4.26350E-11 651700 + 776 651710 Tb-171 5.32630E-12 5.32630E-12 651710 + 777 661640 Dy-164 5.20270E-12 1.97440E-07 66164.82c + 778 661650 Dy-165 3.60720E-11 7.17600E-08 661650 + 779 661651 Dy-165m 4.80280E-12 4.80280E-12 661651 + 780 661660 Dy-166 2.80350E-10 2.60780E-08 661660 + 781 661670 Dy-167 5.16900E-10 9.47630E-09 661670 + 782 661680 Dy-168 1.23330E-09 3.43760E-09 661680 + 783 661690 Dy-169 6.21620E-10 1.21790E-09 661690 + 784 661700 Dy-170 3.73760E-10 4.16390E-10 661700 + 785 661710 Dy-171 8.62020E-11 9.15280E-11 661710 + 786 661720 Dy-172 2.33460E-11 2.33460E-11 661720 + 787 661730 Dy-173 1.37110E-12 1.37110E-12 661730 + 788 671670 Ho-167 1.12680E-12 9.47750E-09 671670 + 789 671680 Ho-168 2.36150E-12 3.44390E-09 671680 + 790 671681 Ho-168m 3.94930E-12 3.94930E-12 671681 + 791 671690 Ho-169 3.37130E-11 1.25160E-09 671690 + 792 671700 Ho-170 2.76940E-11 2.76940E-11 671700 + 793 671701 Ho-170m 1.01600E-11 4.26550E-10 671701 + 794 671710 Ho-171 7.26520E-11 1.64180E-10 671710 + 795 671720 Ho-172 3.17440E-11 5.50900E-11 671720 + 796 671730 Ho-173 1.60940E-11 1.74650E-11 671730 + 797 671740 Ho-174 2.43310E-12 2.43310E-12 671740 + 798 681710 Er-171 1.10650E-12 1.65290E-10 681710 + 799 681720 Er-172 4.83510E-12 5.99250E-11 681720 + 800 681730 Er-173 4.31670E-12 2.17820E-11 681730 + 801 681740 Er-174 5.27850E-12 7.71160E-12 681740 + + Nuclide 92237.82c -- uranium 237 (U-237) is using NFY data from Np-238 + + Nuclide 92238.82c -- uranium 238 (U-238) + + Neutron-induced fission: + + Interpolation region : 1 / 2 + Interpolation energy : 4.00000E-01 MeV + Number of products : 771 / 935 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 2.35370E-05 2.35370E-05 1001.82c + 2 10020 H-2 7.19320E-06 7.19320E-06 1002.82c + 3 10030 H-3 1.02620E-04 1.02620E-04 1003.82c + 4 20040 He-4 1.48800E-03 1.48800E-03 2004.82c + 5 240600 Cr-60 8.12710E-12 8.12710E-12 240600 + 6 240610 Cr-61 8.55480E-12 8.55480E-12 240610 + 7 240620 Cr-62 9.66660E-12 9.66660E-12 240620 + 8 240630 Cr-63 2.71880E-12 2.71880E-12 240630 + 9 250600 Mn-60 2.14070E-13 8.59160E-12 250600 + 10 250601 Mn-60m 2.17770E-12 2.17770E-12 250601 + 11 250610 Mn-61 1.63150E-11 2.48700E-11 250610 + 12 250620 Mn-62 3.19300E-11 3.67640E-11 250620 + 13 250621 Mn-62m 5.00050E-12 9.83380E-12 250621 + 14 250630 Mn-63 7.95210E-11 8.22400E-11 250630 + 15 250640 Mn-64 5.38390E-11 5.38390E-11 250640 + 16 250650 Mn-65 5.14680E-11 5.14680E-11 250650 + 17 250660 Mn-66 1.24280E-11 1.24280E-11 250660 + 18 250670 Mn-67 2.93300E-12 2.93300E-12 250670 + 19 260620 Fe-62 1.51280E-11 6.17260E-11 260620 + 20 260630 Fe-63 6.35300E-11 1.45770E-10 260630 + 21 260640 Fe-64 2.80650E-10 3.34490E-10 260640 + 22 260650 Fe-65 5.59630E-10 6.11100E-10 260650 + 23 260660 Fe-66 1.08760E-09 1.10000E-09 260660 + 24 260670 Fe-67 6.83380E-10 6.86310E-10 260670 + 25 260680 Fe-68 4.61420E-10 4.61420E-10 260680 + 26 260690 Fe-69 8.76880E-11 8.76880E-11 260690 + 27 260700 Fe-70 1.38970E-11 1.38970E-11 260700 + 28 270630 Co-63 1.55770E-12 1.47330E-10 270630 + 29 270640 Co-64 1.61020E-11 3.50590E-10 270640 + 30 270650 Co-65 2.24840E-10 8.35940E-10 270650 + 31 270660 Co-66 8.37010E-10 1.93700E-09 270660 + 32 270670 Co-67 3.50700E-09 4.19330E-09 270670 + 33 270680 Co-68 2.96480E-09 4.30510E-09 270680 + 34 270681 Co-68m 2.21300E-09 2.68050E-09 270681 + 35 270690 Co-69 8.30810E-09 8.38970E-09 270690 + 36 270700 Co-70 1.81620E-09 1.81620E-09 270700 + 37 270701 Co-70m 1.81620E-09 1.83010E-09 270701 + 38 270710 Co-71 2.19450E-09 2.19450E-09 270710 + 39 270720 Co-72 3.59520E-10 3.59520E-10 270720 + 40 270730 Co-73 4.71980E-11 4.71980E-11 270730 + 41 270740 Co-74 1.75320E-12 1.75320E-12 270740 + 42 280650 Ni-65 1.91340E-12 8.37850E-10 280650 + 43 280660 Ni-66 6.11150E-11 1.99820E-09 280660 + 44 280670 Ni-67 5.69870E-10 4.76320E-09 280670 + 45 280680 Ni-68 5.67200E-09 1.14010E-08 280680 + 46 280690 Ni-69 8.69200E-09 1.69980E-08 280690 + 47 280691 Ni-69m 8.69200E-09 8.69200E-09 280691 + 48 280700 Ni-70 5.24530E-08 5.60990E-08 280700 + 49 280710 Ni-71 7.28510E-08 7.50450E-08 280710 + 50 280720 Ni-72 1.05280E-07 1.05640E-07 280720 + 51 280730 Ni-73 3.93000E-08 3.93470E-08 280730 + 52 280740 Ni-74 1.47860E-08 1.47880E-08 280740 + 53 280750 Ni-75 1.92610E-09 1.92610E-09 280750 + 54 280760 Ni-76 1.97710E-10 1.97710E-10 280760 + 55 280770 Ni-77 7.11990E-12 7.11990E-12 280770 + 56 290670 Cu-67 1.95710E-12 4.76510E-09 290670 + 57 290680 Cu-68 1.41050E-11 1.14480E-08 290680 + 58 290681 Cu-68m 3.84470E-11 3.84470E-11 290681 + 59 290690 Cu-69 1.31900E-09 2.70090E-08 290690 + 60 290700 Cu-70 5.71190E-10 5.63530E-09 290700 + 61 290701 Cu-70m 7.29470E-09 1.01280E-08 290701 + 62 290702 Cu-70m 5.71190E-10 5.66700E-08 290702 + 63 290710 Cu-71 7.69260E-08 1.51970E-07 290710 + 64 290720 Cu-72 2.15070E-07 3.20710E-07 290720 + 65 290730 Cu-73 5.78690E-07 6.18040E-07 290730 + 66 290740 Cu-74 5.25890E-07 5.40710E-07 290740 + 67 290750 Cu-75 6.28220E-07 6.30120E-07 290750 + 68 290760 Cu-76 9.41600E-08 9.42590E-08 290760 + 69 290761 Cu-76m 9.41600E-08 9.42590E-08 290761 + 70 290770 Cu-77 7.04050E-08 7.04120E-08 290770 + 71 290780 Cu-78 4.45170E-09 4.45170E-09 290780 + 72 290790 Cu-79 4.76300E-10 4.76300E-10 290790 + 73 290800 Cu-80 5.92200E-12 5.92200E-12 290800 + 74 300690 Zn-69 2.46320E-13 2.70100E-08 300690 + 75 300691 Zn-69m 1.22340E-12 1.22340E-12 300691 + 76 300700 Zn-70 9.07110E-11 6.46270E-08 300700 + 77 300710 Zn-71 3.59690E-10 1.52330E-07 300710 + 78 300711 Zn-71m 1.78640E-09 1.78640E-09 300711 + 79 300720 Zn-72 4.67610E-08 3.67470E-07 300720 + 80 300730 Zn-73 2.24000E-08 7.72450E-07 300730 + 81 300731 Zn-73m 3.09820E-08 1.32010E-07 300731 + 82 300732 Zn-73m 2.02060E-07 2.02060E-07 300732 + 83 300740 Zn-74 1.50520E-06 2.06800E-06 300740 + 84 300750 Zn-75 3.57350E-06 4.18440E-06 300750 + 85 300760 Zn-76 8.10720E-06 8.29290E-06 300760 + 86 300770 Zn-77 1.07920E-05 1.15810E-05 300770 + 87 300771 Zn-77m 1.43690E-06 1.43690E-06 300771 + 88 300780 Zn-78 1.12170E-05 1.12220E-05 300780 + 89 300790 Zn-79 1.46420E-06 1.46440E-06 300790 + 90 300800 Zn-80 4.54180E-06 4.54180E-06 300800 + 91 300810 Zn-81 1.86450E-08 1.86450E-08 300810 + 92 300820 Zn-82 1.41340E-09 1.41340E-09 300820 + 93 310720 Ga-72 5.37560E-11 3.67530E-07 310720 + 94 310721 Ga-72m 5.28410E-12 1.22500E-08 310721 + 95 310730 Ga-73 3.01750E-09 8.76500E-07 310730 + 96 310740 Ga-74 2.20780E-08 1.58960E-06 310740 + 97 310741 Ga-74m 2.20780E-08 2.09000E-06 310741 + 98 310750 Ga-75 7.77140E-07 4.96150E-06 310750 + 99 310760 Ga-76 3.45980E-06 1.17530E-05 310760 + 100 310770 Ga-77 1.22300E-05 2.45290E-05 310770 + 101 310780 Ga-78 2.80460E-05 3.92870E-05 310780 + 102 310790 Ga-79 6.44000E-05 6.58450E-05 310790 + 103 310800 Ga-80 2.72480E-05 3.17910E-05 310800 + 104 310810 Ga-81 3.19140E-05 3.19310E-05 310810 + 105 310820 Ga-82 3.09260E-05 3.09270E-05 310820 + 106 310830 Ga-83 5.74290E-06 5.74290E-06 310830 + 107 310840 Ga-84 2.40950E-08 2.40950E-08 310840 + 108 310850 Ga-85 1.02240E-09 1.02240E-09 310850 + 109 320740 Ge-74 6.08820E-11 2.11220E-06 32074.82c + 110 320750 Ge-75 3.63470E-10 4.96460E-06 320750 + 111 320751 Ge-75m 2.72990E-09 2.01190E-07 320751 + 112 320760 Ge-76 1.24350E-07 1.18770E-05 32076.82c + 113 320770 Ge-77 5.39670E-06 1.01940E-05 320770 + 114 320771 Ge-77m 7.18550E-07 2.52480E-05 320771 + 115 320780 Ge-78 1.12190E-05 5.05640E-05 320780 + 116 320790 Ge-79 9.90210E-06 7.85690E-05 320790 + 117 320791 Ge-79m 7.43710E-05 7.44700E-05 320791 + 118 320800 Ge-80 2.13520E-04 2.49110E-04 320800 + 119 320810 Ge-81 4.21780E-04 4.40940E-04 320810 + 120 320811 Ge-81m 8.49230E-05 1.01490E-04 320811 + 121 320820 Ge-82 1.10900E-03 1.13550E-03 320820 + 122 320830 Ge-83 6.91590E-04 6.95230E-04 320830 + 123 320840 Ge-84 3.27260E-04 3.27270E-04 320840 + 124 320850 Ge-85 1.67770E-04 1.67770E-04 320850 + 125 320860 Ge-86 5.64210E-05 5.64210E-05 320860 + 126 320870 Ge-87 2.87810E-06 2.87810E-06 320870 + 127 320880 Ge-88 8.46140E-10 8.46140E-10 320880 + 128 330760 As-76 1.91190E-11 1.91190E-11 330760 + 129 330770 As-77 2.84360E-09 3.06480E-05 330770 + 130 330780 As-78 6.99600E-08 5.06340E-05 330780 + 131 330790 As-79 2.95130E-06 1.53010E-04 330790 + 132 330800 As-80 1.81730E-05 2.67280E-04 330800 + 133 330810 As-81 5.98930E-05 6.01310E-04 330810 + 134 330820 As-82 8.23030E-05 1.21780E-03 330820 + 135 330821 As-82m 2.86770E-04 2.86770E-04 330821 + 136 330830 As-83 1.11190E-03 1.84250E-03 330830 + 137 330840 As-84 6.76000E-04 8.33710E-04 330840 + 138 330841 As-84m 6.76000E-04 8.33710E-04 330841 + 139 330850 As-85 1.66600E-03 1.81030E-03 330850 + 140 330860 As-86 7.79430E-04 8.35850E-04 330860 + 141 330870 As-87 4.15470E-04 4.18350E-04 330870 + 142 330880 As-88 7.95090E-05 7.95100E-05 330880 + 143 330890 As-89 2.34020E-05 2.34020E-05 330890 + 144 330900 As-90 1.53830E-06 1.53830E-06 330900 + 145 340780 Se-78 1.19680E-11 5.06340E-05 34078.82c + 146 340790 Se-79 1.30220E-09 1.52930E-04 34079.82c + 147 340791 Se-79m 1.73380E-10 1.49390E-04 340791 + 148 340800 Se-80 1.08330E-07 2.67390E-04 34080.82c + 149 340810 Se-81 4.68860E-07 6.05290E-04 340810 + 150 340811 Se-81m 3.52140E-06 2.51080E-05 340811 + 151 340820 Se-82 1.16650E-04 1.62120E-03 34082.82c + 152 340830 Se-83 4.87360E-04 1.15180E-03 340830 + 153 340831 Se-83m 9.81280E-05 1.27850E-03 340831 + 154 340840 Se-84 2.35340E-03 4.41670E-03 340840 + 155 340850 Se-85 5.79250E-03 7.48040E-03 340850 + 156 340860 Se-86 8.69370E-03 9.31820E-03 340860 + 157 340870 Se-87 8.32310E-03 8.67700E-03 340870 + 158 340880 Se-88 5.37180E-03 5.45130E-03 340880 + 159 340890 Se-89 2.62300E-03 2.64640E-03 340890 + 160 340900 Se-90 7.98450E-04 7.99990E-04 340900 + 161 340910 Se-91 1.89930E-04 1.89930E-04 340910 + 162 340920 Se-92 2.95340E-05 2.95340E-05 340920 + 163 340930 Se-93 3.04490E-09 3.04490E-09 340930 + 164 350810 Br-81 5.51590E-10 6.05300E-04 35081.82c + 165 350820 Br-82 3.64980E-08 4.95670E-08 350820 + 166 350821 Br-82m 1.33900E-08 1.33900E-08 350821 + 167 350830 Br-83 2.35160E-06 2.43270E-03 350830 + 168 350840 Br-84 1.39470E-05 4.43070E-03 350840 + 169 350841 Br-84m 1.39470E-05 1.39470E-05 350841 + 170 350850 Br-85 5.16820E-04 7.99720E-03 350850 + 171 350860 Br-86 1.69930E-03 1.10170E-02 350860 + 172 350870 Br-87 6.01330E-03 1.47440E-02 350870 + 173 350880 Br-88 8.64780E-03 1.42520E-02 350880 + 174 350890 Br-89 1.00620E-02 1.25020E-02 350890 + 175 350900 Br-90 5.34930E-03 6.18920E-03 350900 + 176 350910 Br-91 4.30330E-03 4.45330E-03 350910 + 177 350920 Br-92 1.37560E-03 1.40510E-03 350920 + 178 350930 Br-93 5.09050E-04 5.09050E-04 350930 + 179 350940 Br-94 4.87000E-05 4.87000E-05 350940 + 180 350950 Br-95 8.67130E-06 8.67130E-06 350950 + 181 360830 Kr-83 1.15780E-10 2.43270E-03 36083.82c + 182 360831 Kr-83m 2.33120E-11 2.43050E-03 360831 + 183 360840 Kr-84 2.25560E-08 4.44460E-03 36084.82c + 184 360850 Kr-85 1.20640E-05 1.73420E-03 36085.82c + 185 360851 Kr-85m 2.42900E-06 7.98660E-03 360851 + 186 360860 Kr-86 2.71620E-04 1.16590E-02 36086.82c + 187 360870 Kr-87 1.25330E-03 1.65820E-02 360870 + 188 360880 Kr-88 7.14670E-03 2.22060E-02 360880 + 189 360890 Kr-89 1.74750E-02 2.97370E-02 360890 + 190 360900 Kr-90 2.50860E-02 3.06430E-02 360900 + 191 360910 Kr-91 3.04730E-02 3.45010E-02 360910 + 192 360920 Kr-92 2.44700E-02 2.57560E-02 360920 + 193 360930 Kr-93 1.28210E-02 1.30180E-02 360930 + 194 360940 Kr-94 5.61690E-03 5.63150E-03 360940 + 195 360950 Kr-95 1.62520E-03 1.63390E-03 360950 + 196 360960 Kr-96 4.81460E-04 4.81460E-04 360960 + 197 360970 Kr-97 4.32950E-05 4.32950E-05 360970 + 198 360980 Kr-98 6.78840E-06 6.78840E-06 360980 + 199 370860 Rb-86 9.62750E-10 2.98250E-09 37086.82c + 200 370861 Rb-86m 2.01980E-09 2.01980E-09 370861 + 201 370870 Rb-87 4.31850E-06 1.65870E-02 37087.82c + 202 370880 Rb-88 4.22120E-05 2.22480E-02 370880 + 203 370890 Rb-89 4.43850E-04 3.01810E-02 370890 + 204 370900 Rb-90 1.14850E-04 2.68850E-02 370900 + 205 370901 Rb-90m 1.16840E-03 5.17660E-03 370901 + 206 370910 Rb-91 6.99940E-03 4.15000E-02 370910 + 207 370920 Rb-92 1.38980E-02 3.96540E-02 370920 + 208 370930 Rb-93 2.63030E-02 3.93840E-02 370930 + 209 370940 Rb-94 1.58850E-02 2.15010E-02 370940 + 210 370950 Rb-95 1.21920E-02 1.37970E-02 370950 + 211 370960 Rb-96 3.08740E-03 4.98100E-03 370960 + 212 370961 Rb-96m 3.08740E-03 3.32070E-03 370961 + 213 370970 Rb-97 2.91700E-03 2.95790E-03 370970 + 214 370980 Rb-98 3.00760E-04 3.00760E-04 370980 + 215 370981 Rb-98m 3.00760E-04 3.07070E-04 370981 + 216 370990 Rb-99 1.55970E-04 1.55970E-04 370990 + 217 371000 Rb-100 6.02600E-06 6.02600E-06 371000 + 218 371010 Rb-101 9.79920E-07 9.79920E-07 371010 + 219 380880 Sr-88 8.46140E-10 2.22480E-02 38088.82c + 220 380890 Sr-89 1.11580E-05 3.01920E-02 38089.82c + 221 380900 Sr-90 9.81710E-05 3.20250E-02 38090.82c + 222 380910 Sr-91 6.01180E-04 4.21010E-02 380910 + 223 380920 Sr-92 3.79670E-03 4.40020E-02 380920 + 224 380930 Sr-93 1.19850E-02 5.29890E-02 380930 + 225 380940 Sr-94 2.94800E-02 4.99960E-02 380940 + 226 380950 Sr-95 3.65990E-02 4.98770E-02 380950 + 227 380960 Sr-96 4.64570E-02 5.31730E-02 380960 + 228 380970 Sr-97 3.17100E-02 3.39670E-02 380970 + 229 380980 Sr-98 2.05330E-02 2.11240E-02 380980 + 230 380990 Sr-99 8.40010E-03 8.53160E-03 380990 + 231 381000 Sr-100 2.93140E-03 2.93710E-03 381000 + 232 381010 Sr-101 5.97490E-04 5.98470E-04 381010 + 233 381020 Sr-102 1.10780E-04 1.10780E-04 381020 + 234 381030 Sr-103 4.18260E-06 4.18260E-06 381030 + 235 390910 Y-91 8.68050E-10 4.21010E-02 39091.82c + 236 390911 Y-91m 4.31120E-09 2.47710E-02 390911 + 237 390920 Y-92 3.48110E-06 4.40060E-02 390920 + 238 390930 Y-93 1.12760E-05 5.30850E-02 390930 + 239 390931 Y-93m 8.46870E-05 1.33450E-02 390931 + 240 390940 Y-94 4.72500E-04 5.04680E-02 390940 + 241 390950 Y-95 2.52030E-03 5.23970E-02 390950 + 242 390960 Y-96 2.15690E-03 5.53390E-02 390960 + 243 390961 Y-96m 4.52490E-03 4.53340E-03 390961 + 244 390970 Y-97 3.22190E-03 3.22620E-02 390970 + 245 390971 Y-97m 1.19090E-02 2.02350E-02 390971 + 246 390972 Y-97m 4.09280E-03 4.09280E-03 390972 + 247 390980 Y-98 3.99680E-03 2.51210E-02 390980 + 248 390981 Y-98m 1.93760E-02 1.93760E-02 390981 + 249 390990 Y-99 2.82710E-02 3.68250E-02 390990 + 250 391000 Y-100 8.15600E-03 1.10770E-02 391000 + 251 391001 Y-100m 8.15600E-03 8.16310E-03 391001 + 252 391010 Y-101 1.09550E-02 1.15450E-02 391010 + 253 391020 Y-102 1.87710E-03 1.92950E-03 391020 + 254 391021 Y-102m 1.87710E-03 1.92950E-03 391021 + 255 391030 Y-103 1.32990E-03 1.33410E-03 391030 + 256 391040 Y-104 1.46480E-04 1.46480E-04 391040 + 257 391050 Y-105 2.71750E-05 2.71750E-05 391050 + 258 391060 Y-106 1.66910E-09 1.66910E-09 391060 + 259 400930 Zr-93 1.89540E-06 5.30870E-02 40093.82c + 260 400940 Zr-94 1.40650E-05 5.04820E-02 40094.82c + 261 400950 Zr-95 1.09410E-04 5.25060E-02 40095.82c + 262 400960 Zr-96 8.62620E-04 6.07510E-02 40096.82c + 263 400970 Zr-97 3.37210E-03 5.72640E-02 400970 + 264 400980 Zr-98 1.34520E-02 5.78410E-02 400980 + 265 400990 Zr-99 2.50530E-02 6.13540E-02 400990 + 266 401000 Zr-100 4.37030E-02 6.28410E-02 401000 + 267 401010 Zr-101 4.23990E-02 5.41340E-02 401010 + 268 401020 Zr-102 3.93830E-02 4.31600E-02 401020 + 269 401030 Zr-103 2.12740E-02 2.25140E-02 401030 + 270 401040 Zr-104 8.99870E-03 9.13770E-03 401040 + 271 401050 Zr-105 2.40280E-03 2.42460E-03 401050 + 272 401060 Zr-106 5.89850E-04 5.89850E-04 401060 + 273 401070 Zr-107 3.45680E-05 3.45680E-05 401070 + 274 401080 Zr-108 2.65650E-06 2.65650E-06 401080 + 275 401090 Zr-109 4.70900E-11 4.70900E-11 401090 + 276 410960 Nb-96 1.31630E-09 1.31630E-09 410960 + 277 410970 Nb-97 1.66650E-05 5.72840E-02 410970 + 278 410971 Nb-97m 3.35530E-06 5.44320E-02 410971 + 279 410980 Nb-98 2.23600E-05 5.78630E-02 410980 + 280 410981 Nb-98m 7.79100E-05 7.79100E-05 410981 + 281 410990 Nb-99 6.49370E-04 3.98790E-02 410990 + 282 410991 Nb-99m 1.30750E-04 2.27090E-02 410991 + 283 411000 Nb-100 4.14660E-04 6.32560E-02 411000 + 284 411001 Nb-100m 2.01020E-03 2.01020E-03 411001 + 285 411010 Nb-101 9.27810E-03 6.34120E-02 411010 + 286 411020 Nb-102 8.00700E-03 5.11670E-02 411020 + 287 411021 Nb-102m 8.00700E-03 8.00700E-03 411021 + 288 411030 Nb-103 2.83640E-02 5.08780E-02 411030 + 289 411040 Nb-104 9.21850E-03 1.83900E-02 411040 + 290 411041 Nb-104m 9.21850E-03 9.21850E-03 411041 + 291 411050 Nb-105 1.49420E-02 1.73420E-02 411050 + 292 411060 Nb-106 5.76360E-03 6.34570E-03 411060 + 293 411070 Nb-107 2.90200E-03 2.93530E-03 411070 + 294 411080 Nb-108 2.49220E-04 2.51880E-04 411080 + 295 411090 Nb-109 5.12440E-05 5.12440E-05 411090 + 296 411100 Nb-110 2.54510E-05 2.54510E-05 411100 + 297 411110 Nb-111 1.76690E-10 1.76690E-10 411110 + 298 411120 Nb-112 1.13810E-05 1.13810E-05 411120 + 299 420990 Mo-99 1.26010E-05 6.21470E-02 42099.82c + 300 421000 Mo-100 1.49260E-04 6.54160E-02 42100.82c + 301 421010 Mo-101 7.78090E-04 6.41900E-02 421010 + 302 421020 Mo-102 3.71420E-03 6.28880E-02 421020 + 303 421030 Mo-103 9.33710E-03 6.02310E-02 421030 + 304 421040 Mo-104 1.81750E-02 4.60630E-02 421040 + 305 421050 Mo-105 1.87450E-02 3.60770E-02 421050 + 306 421060 Mo-106 1.71360E-02 2.33720E-02 421060 + 307 421070 Mo-107 1.12640E-02 1.40390E-02 421070 + 308 421080 Mo-108 2.81760E-03 3.06030E-03 421080 + 309 421090 Mo-109 6.15800E-04 6.70740E-04 421090 + 310 421100 Mo-110 1.97310E-04 2.12580E-04 421100 + 311 421110 Mo-111 4.51450E-05 4.51450E-05 421110 + 312 421120 Mo-112 1.13820E-05 2.27630E-05 421120 + 313 421130 Mo-113 6.12740E-06 6.12740E-06 421130 + 314 421140 Mo-114 2.58080E-11 2.58080E-11 421140 + 315 431020 Tc-102 6.16500E-06 6.28940E-02 431020 + 316 431021 Tc-102m 6.16500E-06 6.16500E-06 431021 + 317 431030 Tc-103 9.90170E-05 6.03300E-02 431030 + 318 431040 Tc-104 3.01780E-04 4.63650E-02 431040 + 319 431050 Tc-105 1.14850E-03 3.72260E-02 431050 + 320 431060 Tc-106 1.56020E-03 2.49320E-02 431060 + 321 431070 Tc-107 3.06460E-03 1.71030E-02 431070 + 322 431080 Tc-108 1.19250E-03 4.25640E-03 431080 + 323 431090 Tc-109 7.54330E-04 1.42150E-03 431090 + 324 431100 Tc-110 3.87370E-04 6.00420E-04 431100 + 325 431110 Tc-111 2.36640E-04 2.81790E-04 431110 + 326 431120 Tc-112 5.68850E-05 7.91750E-05 431120 + 327 431130 Tc-113 4.28710E-05 4.89980E-05 431130 + 328 431140 Tc-114 2.04040E-05 2.04040E-05 431140 + 329 431150 Tc-115 1.36250E-08 1.36250E-08 431150 + 330 431160 Tc-116 2.57950E-10 2.57950E-10 431160 + 331 441030 Ru-103 3.67120E-07 6.03310E-02 44103.82c + 332 441031 Ru-103m 1.02720E-06 1.02720E-06 441031 + 333 441040 Ru-104 1.78340E-05 4.63820E-02 44104.82c + 334 441050 Ru-105 4.24900E-05 3.72680E-02 44105.82c + 335 441060 Ru-106 1.30910E-04 2.50630E-02 44106.82c + 336 441070 Ru-107 2.00840E-04 1.73040E-02 441070 + 337 441080 Ru-108 2.82360E-04 4.53990E-03 441080 + 338 441090 Ru-109 1.95660E-04 1.61630E-03 441090 + 339 441100 Ru-110 2.93300E-04 8.93480E-04 441100 + 340 441110 Ru-111 2.59760E-04 5.42740E-04 441110 + 341 441120 Ru-112 3.18750E-04 4.00260E-04 441120 + 342 441130 Ru-113 9.49500E-05 1.89240E-04 441130 + 343 441131 Ru-113m 9.49500E-05 9.49500E-05 441131 + 344 441140 Ru-114 1.42760E-04 1.61830E-04 441140 + 345 441150 Ru-115 3.16830E-05 3.16950E-05 441150 + 346 441160 Ru-116 2.41480E-05 2.41480E-05 441160 + 347 441170 Ru-117 1.10520E-05 1.10520E-05 441170 + 348 441180 Ru-118 3.95550E-09 3.95550E-09 441180 + 349 441190 Ru-119 3.99250E-11 3.99250E-11 441190 + 350 441200 Ru-120 1.05050E-07 1.05050E-07 441200 + 351 451060 Rh-106 5.23940E-07 2.50640E-02 451060 + 352 451061 Rh-106m 1.42820E-06 1.42820E-06 451061 + 353 451070 Rh-107 7.38460E-09 1.73040E-02 451070 + 354 451080 Rh-108 1.66170E-08 4.53990E-03 451080 + 355 451081 Rh-108m 5.79010E-08 5.79010E-08 451081 + 356 451090 Rh-109 9.58540E-07 1.61720E-03 451090 + 357 451100 Rh-110 1.24380E-05 9.05910E-04 451100 + 358 451101 Rh-110m 2.92810E-07 2.92810E-07 451101 + 359 451110 Rh-111 1.01700E-04 6.44440E-04 451110 + 360 451120 Rh-112 2.84730E-05 4.28730E-04 451120 + 361 451121 Rh-112m 2.84730E-05 2.84730E-05 451121 + 362 451130 Rh-113 6.74400E-05 3.04150E-04 451130 + 363 451140 Rh-114 6.63800E-05 2.28290E-04 451140 + 364 451141 Rh-114m 6.63800E-05 6.63800E-05 451141 + 365 451150 Rh-115 1.74220E-04 2.06100E-04 451150 + 366 451160 Rh-116 5.18120E-05 7.59260E-05 451160 + 367 451161 Rh-116m 1.41230E-04 1.41230E-04 451161 + 368 451170 Rh-117 1.21460E-04 1.32280E-04 451170 + 369 451180 Rh-118 1.76370E-05 1.76410E-05 451180 + 370 451190 Rh-119 9.14320E-06 9.14320E-06 451190 + 371 451200 Rh-120 1.37160E-05 1.38210E-05 451200 + 372 451210 Rh-121 3.94670E-06 3.94670E-06 451210 + 373 451220 Rh-122 2.69100E-07 2.69100E-07 451220 + 374 461090 Pd-109 1.47250E-11 1.61720E-03 461090 + 375 461091 Pd-109m 3.23650E-11 8.08620E-04 461091 + 376 461100 Pd-110 2.49840E-09 9.06210E-04 46110.82c + 377 461110 Pd-111 1.62330E-08 6.43790E-04 461110 + 378 461111 Pd-111m 3.56800E-08 2.61340E-06 461111 + 379 461120 Pd-112 1.02790E-06 4.58230E-04 461120 + 380 461130 Pd-113 3.22750E-06 3.16410E-04 461130 + 381 461131 Pd-113m 9.03050E-06 9.03050E-06 461131 + 382 461140 Pd-114 3.06320E-05 3.25300E-04 461140 + 383 461150 Pd-115 5.45660E-05 2.42730E-04 461150 + 384 461151 Pd-115m 1.19930E-04 1.49860E-04 461151 + 385 461160 Pd-116 2.41920E-04 4.59070E-04 461160 + 386 461170 Pd-117 9.68620E-05 4.42560E-04 461170 + 387 461171 Pd-117m 2.12900E-04 2.12900E-04 461171 + 388 461180 Pd-118 2.38010E-04 2.55140E-04 461180 + 389 461190 Pd-119 1.27950E-04 1.37910E-04 461190 + 390 461200 Pd-120 8.22690E-05 9.58060E-05 461200 + 391 461210 Pd-121 2.74620E-05 3.08730E-05 461210 + 392 461220 Pd-122 5.39740E-06 5.66650E-06 461220 + 393 461230 Pd-123 7.61100E-06 7.61100E-06 461230 + 394 461240 Pd-124 2.56300E-06 2.56300E-06 461240 + 395 471120 Ag-112 5.11730E-11 4.58230E-04 471120 + 396 471130 Ag-113 3.50710E-10 2.07340E-04 471130 + 397 471131 Ag-113m 2.63410E-09 3.02990E-04 471131 + 398 471140 Ag-114 1.19680E-08 3.25370E-04 471140 + 399 471141 Ag-114m 5.80190E-08 5.80190E-08 471141 + 400 471150 Ag-115 2.08430E-07 2.20450E-04 471150 + 401 471151 Ag-115m 1.56550E-06 2.04970E-04 471151 + 402 471160 Ag-116 3.56700E-06 4.63220E-04 471160 + 403 471161 Ag-116m 9.72300E-06 9.72300E-06 471161 + 404 471170 Ag-117 3.89830E-06 2.40210E-04 471170 + 405 471171 Ag-117m 2.92790E-05 2.50560E-04 471171 + 406 471180 Ag-118 1.50970E-05 2.78720E-04 471180 + 407 471181 Ag-118m 7.31870E-05 1.09660E-04 471181 + 408 471190 Ag-119 1.50490E-05 8.40060E-05 471190 + 409 471191 Ag-119m 1.13030E-04 1.81990E-04 471191 + 410 471200 Ag-120 3.59420E-05 1.23890E-04 471200 + 411 471201 Ag-120m 6.01080E-05 1.08010E-04 471201 + 412 471210 Ag-121 6.86640E-05 9.94530E-05 471210 + 413 471220 Ag-122 2.59650E-05 3.16320E-05 471220 + 414 471221 Ag-122m 2.79940E-05 2.79940E-05 471221 + 415 471230 Ag-123 4.82750E-05 5.58860E-05 471230 + 416 471240 Ag-124 1.23470E-05 2.15660E-05 471240 + 417 471241 Ag-124m 1.33120E-05 1.33120E-05 471241 + 418 471250 Ag-125 1.27200E-05 1.27200E-05 471250 + 419 471260 Ag-126 1.83880E-05 1.83880E-05 471260 + 420 471270 Ag-127 9.94390E-06 9.94390E-06 471270 + 421 471280 Ag-128 5.88800E-06 5.88800E-06 471280 + 422 471290 Ag-129 2.35660E-08 2.35660E-08 471290 + 423 471300 Ag-130 7.94240E-10 7.94240E-10 471300 + 424 481150 Cd-115 6.01340E-11 3.64960E-04 481150 + 425 481151 Cd-115m 2.27730E-10 1.74170E-05 48515.82c + 426 481160 Cd-116 2.24170E-08 4.72390E-04 48116.82c + 427 481170 Cd-117 8.60230E-08 3.76820E-04 481170 + 428 481171 Cd-117m 3.25770E-07 9.93330E-05 481171 + 429 481180 Cd-118 5.05810E-06 3.48480E-04 481180 + 430 481190 Cd-119 2.40790E-06 2.26400E-04 481190 + 431 481191 Cd-119m 6.73730E-06 4.87420E-05 481191 + 432 481200 Cd-120 4.80380E-05 2.39970E-04 481200 + 433 481210 Cd-121 2.53310E-05 1.14390E-04 481210 + 434 481211 Cd-121m 7.08750E-05 8.12660E-05 481211 + 435 481220 Cd-122 1.13370E-04 1.73000E-04 481220 + 436 481230 Cd-123 1.83690E-05 6.41040E-05 481230 + 437 481231 Cd-123m 5.13960E-05 6.15690E-05 481231 + 438 481240 Cd-124 1.73220E-04 2.01420E-04 481240 + 439 481250 Cd-125 1.84180E-05 2.47780E-05 481250 + 440 481251 Cd-125m 5.15340E-05 5.78940E-05 481251 + 441 481260 Cd-126 4.76660E-04 4.95050E-04 481260 + 442 481270 Cd-127 4.76200E-04 4.86140E-04 481270 + 443 481280 Cd-128 6.22370E-04 6.28260E-04 481280 + 444 481290 Cd-129 1.02460E-04 1.02470E-04 481290 + 445 481291 Cd-129m 2.86670E-04 2.86680E-04 481291 + 446 481300 Cd-130 1.91340E-04 1.91340E-04 481300 + 447 481310 Cd-131 2.04830E-05 2.04830E-05 481310 + 448 481320 Cd-132 4.87970E-06 4.87970E-06 481320 + 449 491170 In-117 2.41450E-11 2.92670E-04 491170 + 450 491171 In-117m 4.86160E-12 3.46840E-04 491171 + 451 491180 In-118 2.13830E-10 3.48480E-04 491180 + 452 491181 In-118m 3.45300E-10 7.39470E-10 491181 + 453 491182 In-118m 3.99770E-10 3.99770E-10 491182 + 454 491190 In-119 3.14460E-08 8.21280E-05 491190 + 455 491191 In-119m 6.33140E-09 2.04500E-04 491191 + 456 491200 In-120 1.79870E-12 2.39970E-04 491200 + 457 491201 In-120m 1.79870E-12 1.79870E-12 491201 + 458 491202 In-120m 1.79870E-12 1.79870E-12 491202 + 459 491210 In-121 3.81160E-06 1.24530E-04 491210 + 460 491211 In-121m 7.67440E-07 7.66330E-05 491211 + 461 491220 In-122 1.01020E-05 1.83100E-04 491220 + 462 491221 In-122m 8.44710E-06 8.44710E-06 491221 + 463 491222 In-122m 8.44710E-06 8.44710E-06 491222 + 464 491230 In-123 1.34020E-05 9.40750E-05 491230 + 465 491231 In-123m 2.69840E-06 4.76980E-05 491231 + 466 491240 In-124 2.16200E-05 2.23040E-04 491240 + 467 491241 In-124m 2.33090E-05 2.33090E-05 491241 + 468 491250 In-125 7.94640E-05 1.49220E-04 491250 + 469 491251 In-125m 1.60000E-05 2.89180E-05 491251 + 470 491260 In-126 1.20490E-04 6.15540E-04 491260 + 471 491261 In-126m 1.29910E-04 1.29910E-04 491261 + 472 491270 In-127 5.47860E-04 5.47860E-04 491270 + 473 491271 In-127m 1.10310E-04 5.96450E-04 491271 + 474 491280 In-128 3.69900E-04 1.14300E-03 491280 + 475 491281 In-128m 1.44840E-04 7.73100E-04 491281 + 476 491282 In-128m 5.54960E-04 5.54960E-04 491282 + 477 491290 In-129 1.81550E-03 2.10550E-03 491290 + 478 491291 In-129m 3.65540E-04 4.71350E-04 491291 + 479 491300 In-130 5.91800E-04 7.77160E-04 491300 + 480 491301 In-130m 8.61690E-04 8.61690E-04 491301 + 481 491302 In-130m 1.20030E-03 1.20030E-03 491302 + 482 491310 In-131 8.60450E-04 8.88970E-04 491310 + 483 491311 In-131m 8.60450E-04 8.63370E-04 491311 + 484 491312 In-131m 8.60450E-04 8.60450E-04 491312 + 485 491320 In-132 4.64010E-04 4.65960E-04 491320 + 486 491330 In-133 8.00860E-05 9.62110E-05 491330 + 487 491331 In-133m 1.61250E-05 1.61250E-05 491331 + 488 491340 In-134 6.10810E-06 6.10810E-06 491340 + 489 491350 In-135 5.91280E-09 5.91280E-09 491350 + 490 501230 Sn-123 2.58870E-11 7.17250E-06 50123.82c + 491 501231 Sn-123m 9.25210E-12 1.34600E-04 501231 + 492 501240 Sn-124 6.41640E-06 2.52770E-04 50124.82c + 493 501250 Sn-125 2.34320E-05 4.86380E-05 50125.82c + 494 501251 Sn-125m 8.37480E-06 1.61300E-04 501251 + 495 501260 Sn-126 1.81890E-04 9.31450E-04 50126.82c + 496 501270 Sn-127 2.19750E-04 4.33290E-04 501270 + 497 501271 Sn-127m 7.85400E-05 1.00520E-03 501271 + 498 501280 Sn-128 3.36310E-04 2.95100E-03 501280 + 499 501281 Sn-128m 9.16700E-04 1.47170E-03 501281 + 500 501290 Sn-129 9.13680E-04 3.26640E-03 501290 + 501 501291 Sn-129m 2.55640E-03 2.78060E-03 501291 + 502 501300 Sn-130 3.67410E-03 5.43540E-03 501300 + 503 501301 Sn-130m 1.00150E-02 1.11100E-02 501301 + 504 501310 Sn-131 6.00640E-03 7.69420E-03 501310 + 505 501311 Sn-131m 1.68060E-02 1.77040E-02 501311 + 506 501320 Sn-132 2.85690E-02 2.91170E-02 501320 + 507 501330 Sn-133 9.55230E-03 9.57070E-03 501330 + 508 501340 Sn-134 2.70830E-03 2.71020E-03 501340 + 509 501350 Sn-135 3.68490E-04 3.68500E-04 501350 + 510 501360 Sn-136 5.71170E-05 5.71170E-05 501360 + 511 501370 Sn-137 7.44530E-06 7.44530E-06 501370 + 512 511250 Sb-125 6.40530E-12 2.09940E-04 51125.82c + 513 511260 Sb-126 4.60090E-10 5.50200E-10 51126.82c + 514 511261 Sb-126m 2.87380E-10 6.43620E-10 511261 + 515 511262 Sb-126m 3.56240E-10 3.56240E-10 511262 + 516 511270 Sb-127 1.98920E-05 1.45840E-03 511270 + 517 511280 Sb-128 2.94690E-05 2.98190E-03 511280 + 518 511281 Sb-128m 4.12160E-05 4.12160E-05 511281 + 519 511290 Sb-129 1.34230E-04 5.01440E-03 511290 + 520 511291 Sb-129m 9.93370E-05 1.48960E-03 511291 + 521 511300 Sb-130 4.99750E-04 1.14900E-02 511300 + 522 511301 Sb-130m 4.99750E-04 6.05490E-03 511301 + 523 511310 Sb-131 7.58540E-03 3.29840E-02 511310 + 524 511320 Sb-132 8.08810E-03 3.72050E-02 511320 + 525 511321 Sb-132m 7.16090E-03 7.16090E-03 511321 + 526 511330 Sb-133 4.29590E-02 5.29900E-02 511330 + 527 511340 Sb-134 4.54350E-03 6.83160E-03 511340 + 528 511341 Sb-134m 1.23840E-02 1.24230E-02 511341 + 529 511350 Sb-135 1.12570E-02 1.15650E-02 511350 + 530 511360 Sb-136 3.00260E-03 3.04690E-03 511360 + 531 511370 Sb-137 9.53300E-04 9.56430E-04 511370 + 532 511380 Sb-138 8.06050E-05 8.06050E-05 511380 + 533 511390 Sb-139 2.45810E-05 2.45810E-05 511390 + 534 521280 Te-128 4.77430E-10 3.02160E-03 52128.82c + 535 521290 Te-129 1.41000E-08 5.51510E-03 521290 + 536 521291 Te-129m 3.94510E-08 2.06880E-03 52529.82c + 537 521300 Te-130 3.43690E-05 1.75800E-02 52130.82c + 538 521310 Te-131 1.04660E-04 3.10640E-02 521310 + 539 521311 Te-131m 2.92820E-04 2.93360E-03 521311 + 540 521320 Te-132 3.44930E-03 4.78150E-02 52132.82c + 541 521330 Te-133 3.83180E-03 5.11470E-02 521330 + 542 521331 Te-133m 1.07210E-02 1.98880E-02 521331 + 543 521340 Te-134 4.67930E-02 6.78610E-02 521340 + 544 521350 Te-135 4.73330E-02 5.75790E-02 521350 + 545 521360 Te-136 4.97100E-02 5.27200E-02 521360 + 546 521370 Te-137 2.25230E-02 2.30110E-02 521370 + 547 521380 Te-138 1.36430E-02 1.37240E-02 521380 + 548 521390 Te-139 2.21300E-03 2.23760E-03 521390 + 549 521400 Te-140 8.82020E-04 8.82020E-04 521400 + 550 521410 Te-141 9.99280E-05 9.99280E-05 521410 + 551 521420 Te-142 2.04500E-05 2.04500E-05 521420 + 552 531310 I-131 2.91690E-08 3.33810E-02 53131.82c + 553 531320 I-132 1.72550E-06 4.78180E-02 531320 + 554 531321 I-132m 1.52770E-06 1.52770E-06 531321 + 555 531330 I-133 6.68030E-05 6.76710E-02 531330 + 556 531331 I-133m 4.94370E-05 4.94370E-05 531331 + 557 531340 I-134 2.93470E-04 6.84080E-02 531340 + 558 531341 I-134m 2.59830E-04 2.59830E-04 531341 + 559 531350 I-135 6.54890E-03 6.41280E-02 53135.82c + 560 531360 I-136 3.77770E-03 5.68420E-02 531360 + 561 531361 I-136m 1.02970E-02 1.06410E-02 531361 + 562 531370 I-137 3.11330E-02 5.43200E-02 531370 + 563 531380 I-138 2.02050E-02 3.30640E-02 531380 + 564 531390 I-139 2.47030E-02 2.69410E-02 531390 + 565 531400 I-140 8.63360E-03 9.51560E-03 531400 + 566 531410 I-141 5.99570E-03 6.09560E-03 531410 + 567 531420 I-142 9.32440E-04 9.52890E-04 531420 + 568 531430 I-143 2.42890E-04 2.42890E-04 531430 + 569 531440 I-144 2.46190E-05 2.46190E-05 531440 + 570 541330 Xe-133 1.03080E-09 6.76710E-02 54133.82c + 571 541331 Xe-133m 2.88410E-09 1.92620E-03 541331 + 572 541340 Xe-134 1.63960E-06 6.84200E-02 54134.82c + 573 541341 Xe-134m 4.46920E-06 1.04450E-05 541341 + 574 541350 Xe-135 2.63620E-05 6.41640E-02 54135.82c + 575 541351 Xe-135m 7.37580E-05 1.06600E-02 541351 + 576 541360 Xe-136 1.75290E-03 7.27670E-02 54136.82c + 577 541370 Xe-137 7.47830E-03 6.00200E-02 541370 + 578 541380 Xe-138 2.60160E-02 5.99680E-02 541380 + 579 541390 Xe-139 3.13700E-02 5.65550E-02 541390 + 580 541400 Xe-140 4.76470E-02 5.75580E-02 541400 + 581 541410 Xe-141 3.74520E-02 4.25060E-02 541410 + 582 541420 Xe-142 2.70020E-02 2.78140E-02 541420 + 583 541430 Xe-143 9.21820E-03 9.37380E-03 541430 + 584 541440 Xe-144 4.25230E-03 4.26710E-03 541440 + 585 541450 Xe-145 7.90810E-04 7.90810E-04 541450 + 586 541460 Xe-146 2.10400E-04 2.10400E-04 541460 + 587 541470 Xe-147 1.87320E-05 1.87320E-05 541470 + 588 551360 Cs-136 5.12730E-07 6.96030E-07 55136.82c + 589 551361 Cs-136m 3.66590E-07 3.66590E-07 551361 + 590 551370 Cs-137 2.51450E-05 6.00450E-02 55137.82c + 591 551380 Cs-138 9.17950E-05 6.01840E-02 551380 + 592 551381 Cs-138m 1.53520E-04 1.53520E-04 551381 + 593 551390 Cs-139 1.19340E-03 5.77490E-02 551390 + 594 551400 Cs-140 2.68970E-03 6.02660E-02 551400 + 595 551410 Cs-141 1.43960E-02 5.69830E-02 551410 + 596 551420 Cs-142 1.57030E-02 4.35100E-02 551420 + 597 551430 Cs-143 2.55520E-02 3.49600E-02 551430 + 598 551440 Cs-144 6.28600E-03 1.35980E-02 551440 + 599 551441 Cs-144m 6.28600E-03 6.30580E-03 551441 + 600 551450 Cs-145 9.73280E-03 1.04990E-02 551450 + 601 551460 Cs-146 3.10430E-03 3.30090E-03 551460 + 602 551470 Cs-147 1.41170E-03 1.42970E-03 551470 + 603 551480 Cs-148 2.54860E-04 2.54860E-04 551480 + 604 551490 Cs-149 2.61090E-05 2.61090E-05 551490 + 605 551500 Cs-150 7.35000E-09 7.35000E-09 551500 + 606 561380 Ba-138 1.96790E-06 6.02150E-02 56138.82c + 607 561390 Ba-139 2.55590E-05 5.77740E-02 561390 + 608 561400 Ba-140 1.90610E-04 6.04570E-02 56140.82c + 609 561410 Ba-141 9.52790E-04 5.79360E-02 561410 + 610 561420 Ba-142 4.29580E-03 4.83800E-02 561420 + 611 561430 Ba-143 1.18200E-02 4.66420E-02 561430 + 612 561440 Ba-144 2.87090E-02 4.65260E-02 561440 + 613 561450 Ba-145 2.70690E-02 3.65350E-02 561450 + 614 561460 Ba-146 2.84930E-02 3.17330E-02 561460 + 615 561470 Ba-147 1.36470E-02 1.47330E-02 561470 + 616 561480 Ba-148 8.81530E-03 9.00620E-03 561480 + 617 561490 Ba-149 2.07660E-03 2.10270E-03 561490 + 618 561500 Ba-150 6.07030E-04 6.07040E-04 561500 + 619 561510 Ba-151 7.10640E-05 7.10640E-05 561510 + 620 561520 Ba-152 1.02530E-05 1.02530E-05 561520 + 621 561530 Ba-153 4.22380E-10 4.22380E-10 561530 + 622 571410 La-141 1.00060E-06 5.79370E-02 571410 + 623 571420 La-142 4.72170E-06 4.83840E-02 571420 + 624 571430 La-143 7.36210E-05 4.67160E-02 571430 + 625 571440 La-144 3.77750E-04 4.69040E-02 571440 + 626 571450 La-145 1.93130E-03 3.84660E-02 571450 + 627 571460 La-146 1.18240E-03 3.29150E-02 571460 + 628 571461 La-146m 2.48060E-03 2.48060E-03 571461 + 629 571470 La-147 1.04450E-02 2.52140E-02 571470 + 630 571480 La-148 9.02040E-03 1.80000E-02 571480 + 631 571490 La-149 8.10130E-03 1.01950E-02 571490 + 632 571500 La-150 3.03880E-03 3.64580E-03 571500 + 633 571510 La-151 1.52130E-03 1.59240E-03 571510 + 634 571520 La-152 3.15010E-04 3.25260E-04 571520 + 635 571530 La-153 6.16280E-05 6.16280E-05 571530 + 636 571540 La-154 8.60310E-06 8.60310E-06 571540 + 637 571550 La-155 2.22370E-09 2.22370E-09 571550 + 638 581430 Ce-143 8.33940E-07 4.67160E-02 58143.82c + 639 581440 Ce-144 1.27080E-05 4.69160E-02 58144.82c + 640 581450 Ce-145 5.43050E-05 3.85210E-02 581450 + 641 581460 Ce-146 3.69570E-04 3.57650E-02 581460 + 642 581470 Ce-147 1.42150E-03 2.66360E-02 581470 + 643 581480 Ce-148 4.81740E-03 2.29600E-02 581480 + 644 581490 Ce-149 6.67500E-03 1.68260E-02 581490 + 645 581500 Ce-150 9.39800E-03 1.29450E-02 581500 + 646 581510 Ce-151 5.72770E-03 7.33970E-03 581510 + 647 581520 Ce-152 4.15940E-03 4.46500E-03 581520 + 648 581530 Ce-153 1.55170E-03 1.61330E-03 581530 + 649 581540 Ce-154 5.87060E-04 5.95660E-04 581540 + 650 581550 Ce-155 1.06220E-04 1.06220E-04 581550 + 651 581560 Ce-156 3.82620E-07 3.82620E-07 581560 + 652 581570 Ce-157 3.48420E-09 3.48420E-09 581570 + 653 591460 Pr-146 3.29540E-09 3.57650E-02 591460 + 654 591470 Pr-147 3.74950E-06 2.66390E-02 591470 + 655 591480 Pr-148 2.93330E-06 2.29630E-02 591480 + 656 591481 Pr-148m 1.42210E-05 1.42210E-05 591481 + 657 591490 Pr-149 1.00440E-04 1.69260E-02 591490 + 658 591500 Pr-150 2.35600E-04 1.31810E-02 591500 + 659 591510 Pr-151 7.56050E-04 8.09580E-03 591510 + 660 591520 Pr-152 9.68830E-04 5.44390E-03 591520 + 661 591530 Pr-153 1.61520E-03 3.22230E-03 591530 + 662 591540 Pr-154 9.61230E-04 1.55310E-03 591540 + 663 591550 Pr-155 5.28820E-04 6.35040E-04 591550 + 664 591560 Pr-156 1.06270E-04 1.06650E-04 591560 + 665 591570 Pr-157 2.02700E-05 2.02740E-05 591570 + 666 591580 Pr-158 1.99250E-07 1.99250E-07 591580 + 667 591590 Pr-159 7.89360E-09 7.89360E-09 591590 + 668 601480 Nd-148 1.00880E-06 2.29780E-02 60148.82c + 669 601490 Nd-149 2.09170E-06 1.69280E-02 601490 + 670 601500 Nd-150 1.06880E-05 1.31920E-02 60150.82c + 671 601510 Nd-151 5.05820E-05 8.14630E-03 601510 + 672 601520 Nd-152 2.03420E-04 5.64730E-03 601520 + 673 601530 Nd-153 3.97550E-04 3.61980E-03 601530 + 674 601540 Nd-154 8.57930E-04 2.41100E-03 601540 + 675 601550 Nd-155 8.02580E-04 1.44050E-03 601550 + 676 601560 Nd-156 4.95180E-04 6.00230E-04 601560 + 677 601570 Nd-157 1.82440E-04 2.01420E-04 601570 + 678 601580 Nd-158 8.65730E-05 8.67720E-05 601580 + 679 601590 Nd-159 1.56630E-05 1.56710E-05 601590 + 680 601600 Nd-160 4.23750E-07 4.23750E-07 601600 + 681 601610 Nd-161 8.25810E-09 8.25810E-09 601610 + 682 611510 Pm-151 4.81300E-10 8.14630E-03 61151.82c + 683 611520 Pm-152 2.84420E-09 5.64730E-03 611520 + 684 611521 Pm-152m 5.97960E-09 5.97960E-09 611521 + 685 611522 Pm-152m 7.81090E-09 7.81090E-09 611522 + 686 611530 Pm-153 2.28590E-06 3.62210E-03 611530 + 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3.89980E-06 4.01780E-06 621620 + 707 621630 Sm-163 7.08020E-07 7.16460E-07 621630 + 708 621640 Sm-164 1.36030E-07 1.36030E-07 621640 + 709 621650 Sm-165 6.44070E-09 6.44070E-09 621650 + 710 631560 Eu-156 1.48050E-11 6.57530E-04 63156.82c + 711 631570 Eu-157 5.27060E-10 2.43900E-04 63157.82c + 712 631580 Eu-158 7.73920E-09 1.15690E-04 631580 + 713 631590 Eu-159 1.30750E-07 8.38820E-05 631590 + 714 631600 Eu-160 5.13950E-07 3.43480E-05 631600 + 715 631610 Eu-161 1.43170E-06 1.19510E-05 631610 + 716 631620 Eu-162 1.32640E-06 5.34420E-06 631620 + 717 631630 Eu-163 1.59190E-06 2.30840E-06 631630 + 718 631640 Eu-164 6.33780E-07 7.69810E-07 631640 + 719 631650 Eu-165 2.39650E-07 2.46090E-07 631650 + 720 631660 Eu-166 2.72380E-08 2.72380E-08 631660 + 721 631670 Eu-167 4.34230E-09 4.34230E-09 631670 + 722 641590 Gd-159 1.18550E-11 8.38820E-05 641590 + 723 641600 Gd-160 4.94470E-10 3.43480E-05 64160.82c + 724 641610 Gd-161 4.13190E-09 1.19550E-05 641610 + 725 641620 Gd-162 3.60760E-08 5.38030E-06 641620 + 726 641630 Gd-163 1.07190E-07 2.41560E-06 641630 + 727 641640 Gd-164 3.14070E-07 1.08390E-06 641640 + 728 641650 Gd-165 2.34100E-07 4.80190E-07 641650 + 729 641660 Gd-166 1.78440E-07 2.05680E-07 641660 + 730 641670 Gd-167 6.19510E-08 6.62930E-08 641670 + 731 641680 Gd-168 2.10120E-08 2.10120E-08 641680 + 732 641690 Gd-169 2.10680E-09 2.10680E-09 641690 + 733 651620 Tb-162 4.06190E-12 5.38030E-06 651620 + 734 651630 Tb-163 1.27450E-10 2.41570E-06 651630 + 735 651640 Tb-164 1.08890E-09 1.08500E-06 651640 + 736 651650 Tb-165 7.32020E-09 4.87510E-07 651650 + 737 651660 Tb-166 1.30570E-08 2.18740E-07 651660 + 738 651670 Tb-167 3.17710E-08 9.80640E-08 651670 + 739 651680 Tb-168 2.09740E-08 4.19860E-08 651680 + 740 651690 Tb-169 1.45660E-08 1.66730E-08 651690 + 741 651700 Tb-170 3.49120E-09 3.49120E-09 651700 + 742 651710 Tb-171 9.52370E-10 9.52370E-10 651710 + 743 661650 Dy-165 2.56720E-12 4.87510E-07 661650 + 744 661660 Dy-166 5.34010E-11 2.18790E-07 661660 + 745 661670 Dy-167 3.65970E-10 9.84300E-08 661670 + 746 661680 Dy-168 2.07180E-09 4.40580E-08 661680 + 747 661690 Dy-169 3.18190E-09 1.98550E-08 661690 + 748 661700 Dy-170 5.15270E-09 8.64390E-09 661700 + 749 661710 Dy-171 2.75560E-09 3.70800E-09 661710 + 750 661720 Dy-172 1.41020E-09 1.41020E-09 661720 + 751 661730 Dy-173 3.12900E-10 3.12900E-10 661730 + 752 671680 Ho-168 3.82280E-13 4.40590E-08 671680 + 753 671690 Ho-169 1.57200E-11 1.98700E-08 671690 + 754 671700 Ho-170 5.03180E-11 5.03180E-11 671700 + 755 671701 Ho-170m 1.84600E-11 8.66240E-09 671701 + 756 671710 Ho-171 2.98480E-10 4.00640E-09 671710 + 757 671720 Ho-172 3.20700E-10 1.73090E-09 671720 + 758 671730 Ho-173 4.71370E-10 7.84270E-10 671730 + 759 671740 Ho-174 2.19750E-10 2.19750E-10 671740 + 760 671750 Ho-175 9.55770E-11 9.55770E-11 671750 + 761 681720 Er-172 5.29790E-12 1.73620E-09 681720 + 762 681730 Er-173 2.00520E-11 8.04320E-10 681730 + 763 681740 Er-174 7.16530E-11 2.91400E-10 681740 + 764 681750 Er-175 6.27510E-11 1.58330E-10 681750 + 765 681760 Er-176 5.74110E-11 5.74110E-11 681760 + 766 681770 Er-177 2.27300E-11 2.27300E-11 681770 + 767 691750 Tm-175 1.21030E-12 1.59540E-10 691750 + 768 691760 Tm-176 2.70230E-12 6.01130E-11 691760 + 769 691770 Tm-177 7.76730E-12 3.04970E-11 691770 + 770 691780 Tm-178 5.76860E-12 5.76860E-12 691780 + 771 691790 Tm-179 4.88740E-12 4.88740E-12 691790 + + Neutron-induced fission: + + Interpolation region : 2 / 2 + Interpolation energy : 1.40000E+01 MeV + Number of products : 1037 / 1146 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 1.30120E-05 1.30120E-05 1001.82c + 2 10020 H-2 3.97660E-06 3.97660E-06 1002.82c + 3 10030 H-3 6.49900E-05 6.49900E-05 1003.82c + 4 20040 He-4 8.22600E-04 8.22600E-04 2004.82c + 5 190500 K-50 2.14670E-12 2.14670E-12 190500 + 6 190510 K-51 1.16000E-12 1.16000E-12 190510 + 7 200500 Ca-50 2.64520E-11 2.85210E-11 200500 + 8 200510 Ca-51 2.22670E-11 2.28820E-11 200510 + 9 200520 Ca-52 2.47380E-11 2.47380E-11 200520 + 10 200530 Ca-53 7.94820E-12 7.94820E-12 200530 + 11 200540 Ca-54 3.12010E-12 3.12010E-12 200540 + 12 210500 Sc-50 7.45480E-12 3.72500E-11 210500 + 13 210501 Sc-50m 1.65090E-12 3.01720E-11 210501 + 14 210510 Sc-51 4.17690E-11 6.51460E-11 210510 + 15 210520 Sc-52 6.66250E-11 9.32530E-11 210520 + 16 210530 Sc-53 1.24310E-10 1.29870E-10 210530 + 17 210540 Sc-54 7.80060E-11 8.11260E-11 210540 + 18 210550 Sc-55 7.46210E-11 7.46210E-11 210550 + 19 210560 Sc-56 2.03680E-11 2.03680E-11 210560 + 20 210570 Sc-57 6.74230E-12 6.74230E-12 210570 + 21 220510 Ti-51 3.44690E-12 6.85930E-11 220510 + 22 220520 Ti-52 3.15240E-11 1.24780E-10 220520 + 23 220530 Ti-53 8.38550E-11 2.13730E-10 220530 + 24 220540 Ti-54 2.87310E-10 3.68440E-10 220540 + 25 220550 Ti-55 4.01630E-10 4.76250E-10 220550 + 26 220560 Ti-56 6.53020E-10 6.75610E-10 220560 + 27 220570 Ti-57 3.54170E-10 3.58690E-10 220570 + 28 220580 Ti-58 2.62700E-10 2.62700E-10 220580 + 29 220590 Ti-59 6.13440E-11 6.13440E-11 220590 + 30 220600 Ti-60 1.54110E-11 1.54110E-11 220600 + 31 220610 Ti-61 1.44070E-12 1.44070E-12 220610 + 32 230530 V-53 5.68360E-12 2.19410E-10 230530 + 33 230540 V-54 2.99180E-11 3.98350E-10 230540 + 34 230550 V-55 2.34730E-10 7.10980E-10 230550 + 35 230560 V-56 5.39830E-10 1.21650E-09 230560 + 36 230570 V-57 1.61370E-09 1.97130E-09 230570 + 37 230580 V-58 1.78820E-09 2.05090E-09 230580 + 38 230590 V-59 2.55250E-09 2.61380E-09 230590 + 39 230600 V-60 1.07480E-09 1.09020E-09 230600 + 40 230610 V-61 6.78700E-10 6.80140E-10 230610 + 41 230620 V-62 1.34070E-10 1.34070E-10 230620 + 42 230630 V-63 1.87520E-10 1.87520E-10 230630 + 43 230640 V-64 6.18240E-12 6.18240E-12 230640 + 44 230650 V-65 1.01110E-12 1.01110E-12 230650 + 45 240550 Cr-55 5.30610E-12 7.16290E-10 240550 + 46 240560 Cr-56 7.48270E-11 1.29920E-09 240560 + 47 240570 Cr-57 3.35160E-10 3.93930E-09 240570 + 48 240580 Cr-58 2.05030E-09 2.46050E-09 240580 + 49 240590 Cr-59 4.13760E-09 6.75140E-09 240590 + 50 240600 Cr-60 9.75610E-09 1.08870E-08 240600 + 51 240610 Cr-61 9.43480E-09 1.00740E-08 240610 + 52 240620 Cr-62 1.16830E-08 1.18830E-08 240620 + 53 240630 Cr-63 2.79580E-08 2.80800E-08 240630 + 54 240640 Cr-64 6.32640E-09 6.33260E-09 240640 + 55 240650 Cr-65 1.90160E-09 1.90260E-09 240650 + 56 240660 Cr-66 6.56390E-11 6.56390E-11 240660 + 57 240670 Cr-67 2.92630E-12 2.92630E-12 240670 + 58 250570 Mn-57 5.99180E-12 3.94530E-09 250570 + 59 250580 Mn-58 5.67260E-11 2.51720E-09 250580 + 60 250581 Mn-58m 3.50540E-12 3.50540E-12 250581 + 61 250590 Mn-59 7.26300E-10 7.47770E-09 250590 + 62 250600 Mn-60 1.46020E-10 1.13050E-08 250600 + 63 250601 Mn-60m 2.36290E-09 2.36290E-09 250601 + 64 250610 Mn-61 1.32580E-08 2.33320E-08 250610 + 65 250620 Mn-62 2.12820E-08 2.72230E-08 250620 + 66 250621 Mn-62m 2.09200E-09 8.03330E-09 250621 + 67 250630 Mn-63 3.19810E-07 3.47890E-07 250630 + 68 250640 Mn-64 1.13730E-07 1.20060E-07 250640 + 69 250650 Mn-65 2.19390E-07 2.21290E-07 250650 + 70 250660 Mn-66 1.31930E-08 1.32590E-08 250660 + 71 250670 Mn-67 4.08680E-09 4.08970E-09 250670 + 72 250680 Mn-68 8.97410E-10 8.97410E-10 250680 + 73 250690 Mn-69 6.66670E-11 6.66670E-11 250690 + 74 260590 Fe-59 4.18490E-12 7.48190E-09 260590 + 75 260600 Fe-60 9.43480E-11 1.34900E-08 260600 + 76 260610 Fe-61 7.99460E-10 2.41320E-08 260610 + 77 260620 Fe-62 8.20990E-09 4.34670E-08 260620 + 78 260630 Fe-63 5.05320E-07 8.53210E-07 260630 + 79 260640 Fe-64 3.13080E-07 4.33140E-07 260640 + 80 260650 Fe-65 8.71800E-07 1.09310E-06 260650 + 81 260660 Fe-66 3.07060E-07 3.20320E-07 260660 + 82 260670 Fe-67 1.53360E-07 1.57450E-07 260670 + 83 260680 Fe-68 2.20770E-07 2.21680E-07 260680 + 84 260690 Fe-69 2.90290E-08 2.90800E-08 260690 + 85 260700 Fe-70 1.69820E-08 1.69820E-08 260700 + 86 260710 Fe-71 1.53920E-09 1.53920E-09 260710 + 87 260720 Fe-72 2.71460E-10 2.71460E-10 260720 + 88 270610 Co-61 3.53700E-12 2.41350E-08 270610 + 89 270620 Co-62 1.14310E-11 4.34790E-08 270620 + 90 270621 Co-62m 5.16210E-11 5.16210E-11 270621 + 91 270630 Co-63 7.92410E-09 8.61130E-07 270630 + 92 270640 Co-64 4.27530E-07 8.60670E-07 270640 + 93 270650 Co-65 1.51930E-06 2.61240E-06 270650 + 94 270660 Co-66 5.15350E-07 8.35670E-07 270660 + 95 270670 Co-67 5.20000E-07 6.77450E-07 270670 + 96 270680 Co-68 1.08780E-06 1.43520E-06 270680 + 97 270681 Co-68m 4.71100E-07 6.94820E-07 270681 + 98 270690 Co-69 8.70570E-07 8.97610E-07 270690 + 99 270700 Co-70 5.79300E-07 5.79300E-07 270700 + 100 270701 Co-70m 5.79300E-07 5.96280E-07 270701 + 101 270710 Co-71 5.09360E-07 5.10900E-07 270710 + 102 270720 Co-72 1.60930E-07 1.61200E-07 270720 + 103 270730 Co-73 4.20630E-08 4.20630E-08 270730 + 104 270740 Co-74 3.63010E-09 3.63010E-09 270740 + 105 270750 Co-75 4.23320E-10 4.23320E-10 270750 + 106 280630 Ni-63 1.10200E-11 8.61140E-07 280630 + 107 280640 Ni-64 2.28230E-10 8.60900E-07 28064.82c + 108 280650 Ni-65 6.16020E-09 2.61860E-06 280650 + 109 280660 Ni-66 1.92190E-08 8.54890E-07 280660 + 110 280670 Ni-67 7.30830E-07 1.40830E-06 280670 + 111 280680 Ni-68 7.79420E-07 2.57100E-06 280680 + 112 280690 Ni-69 7.04450E-07 1.59310E-06 280690 + 113 280691 Ni-69m 7.04450E-07 7.04450E-07 280691 + 114 280700 Ni-70 3.47560E-06 4.65120E-06 280700 + 115 280710 Ni-71 7.55920E-06 8.07010E-06 280710 + 116 280720 Ni-72 1.57810E-05 1.59420E-05 280720 + 117 280730 Ni-73 1.00980E-05 1.01400E-05 280730 + 118 280740 Ni-74 6.83180E-06 6.83540E-06 280740 + 119 280750 Ni-75 5.46260E-07 5.46680E-07 280750 + 120 280760 Ni-76 8.48090E-08 8.48090E-08 280760 + 121 280770 Ni-77 3.30970E-09 3.30970E-09 280770 + 122 280780 Ni-78 1.88480E-10 1.88480E-10 280780 + 123 290650 Cu-65 6.47100E-12 2.61860E-06 29065.82c + 124 290660 Cu-66 3.62950E-11 8.54920E-07 290660 + 125 290670 Cu-67 1.01700E-09 1.40930E-06 290670 + 126 290680 Cu-68 3.63510E-09 2.58840E-06 290680 + 127 290681 Cu-68m 1.64150E-08 1.64150E-08 290681 + 128 290690 Cu-69 7.04430E-07 3.00200E-06 290690 + 129 290700 Cu-70 1.03800E-07 1.27740E-06 290700 + 130 290701 Cu-70m 2.10950E-06 2.34730E-06 290701 + 131 290702 Cu-70m 1.03800E-07 4.75500E-06 290702 + 132 290710 Cu-71 3.77870E-06 1.18490E-05 290710 + 133 290720 Cu-72 1.14690E-05 2.74110E-05 290720 + 134 290730 Cu-73 2.82650E-05 3.84050E-05 290730 + 135 290740 Cu-74 2.50560E-05 3.19000E-05 290740 + 136 290750 Cu-75 6.12860E-05 6.18240E-05 290750 + 137 290760 Cu-76 1.01280E-05 1.01710E-05 290760 + 138 290761 Cu-76m 1.01280E-05 1.01710E-05 290761 + 139 290770 Cu-77 4.78180E-06 4.78510E-06 290770 + 140 290780 Cu-78 3.28710E-07 3.28900E-07 290780 + 141 290790 Cu-79 6.98230E-08 6.98230E-08 290790 + 142 290800 Cu-80 4.09760E-09 4.09760E-09 290800 + 143 300680 Zn-68 4.58330E-11 2.59110E-06 300680 + 144 300690 Zn-69 6.17780E-11 3.00250E-06 300690 + 145 300691 Zn-69m 4.91790E-10 4.91790E-10 300691 + 146 300700 Zn-70 2.91110E-08 6.99740E-06 300700 + 147 300710 Zn-71 2.65520E-08 1.18750E-05 300710 + 148 300711 Zn-71m 2.11370E-07 2.11370E-07 300711 + 149 300720 Zn-72 2.86740E-06 3.02790E-05 300720 + 150 300730 Zn-73 9.27820E-07 4.75970E-05 300730 + 151 300731 Zn-73m 1.31990E-06 8.26400E-06 300731 + 152 300732 Zn-73m 1.38880E-05 1.38880E-05 300732 + 153 300740 Zn-74 7.05390E-05 1.04600E-04 300740 + 154 300750 Zn-75 1.47370E-04 2.07340E-04 300750 + 155 300760 Zn-76 1.93680E-04 2.13720E-04 300760 + 156 300770 Zn-77 1.15290E-04 1.24880E-04 300770 + 157 300771 Zn-77m 9.60480E-06 9.60480E-06 300771 + 158 300780 Zn-78 9.94200E-05 9.97870E-05 300780 + 159 300790 Zn-79 4.76330E-05 4.76640E-05 300790 + 160 300800 Zn-80 2.44690E-05 2.44730E-05 300800 + 161 300810 Zn-81 3.41970E-06 3.41970E-06 300810 + 162 300820 Zn-82 1.11420E-07 1.11420E-07 300820 + 163 300830 Zn-83 3.87170E-09 3.87170E-09 300830 + 164 310700 Ga-70 1.28740E-11 1.28740E-11 310700 + 165 310710 Ga-71 7.39030E-10 1.20880E-05 310710 + 166 310720 Ga-72 1.99550E-08 3.03000E-05 310720 + 167 310721 Ga-72m 1.23310E-09 1.01010E-06 310721 + 168 310730 Ga-73 4.96860E-07 5.50380E-05 310730 + 169 310740 Ga-74 1.13750E-06 8.04430E-05 310740 + 170 310741 Ga-74m 1.13750E-06 1.05740E-04 310741 + 171 310750 Ga-75 1.89830E-05 2.26320E-04 310750 + 172 310760 Ga-76 8.10540E-05 2.94770E-04 310760 + 173 310770 Ga-77 1.52860E-04 2.82540E-04 310770 + 174 310780 Ga-78 1.91210E-04 2.91620E-04 310780 + 175 310790 Ga-79 3.94620E-04 4.41660E-04 310790 + 176 310800 Ga-80 3.87050E-04 4.11780E-04 310800 + 177 310810 Ga-81 3.32660E-04 3.35820E-04 310810 + 178 310820 Ga-82 8.19290E-05 8.20400E-05 310820 + 179 310830 Ga-83 2.24620E-05 2.24660E-05 310830 + 180 310840 Ga-84 9.65880E-07 9.65880E-07 310840 + 181 310850 Ga-85 5.11730E-08 5.11730E-08 310850 + 182 310860 Ga-86 1.67560E-09 1.67560E-09 310860 + 183 320720 Ge-72 1.12640E-11 3.03000E-05 32072.82c + 184 320730 Ge-73 4.29040E-10 5.50380E-05 32073.82c + 185 320731 Ge-73m 5.38950E-11 5.42300E-05 320731 + 186 320740 Ge-74 2.61680E-08 1.06900E-04 32074.82c + 187 320750 Ge-75 3.80990E-08 2.26810E-04 320750 + 188 320751 Ge-75m 4.57340E-07 9.51010E-06 320751 + 189 320760 Ge-76 8.39240E-06 3.03160E-04 32076.82c + 190 320770 Ge-77 3.90400E-05 9.33410E-05 320770 + 191 320771 Ge-77m 3.25230E-06 2.85800E-04 320771 + 192 320780 Ge-78 1.26580E-04 4.18590E-04 320780 + 193 320790 Ge-79 3.50890E-05 4.92570E-04 320790 + 194 320791 Ge-79m 4.21200E-04 4.21860E-04 320791 + 195 320800 Ge-80 1.28550E-03 1.73720E-03 320800 + 196 320810 Ge-81 1.87600E-03 2.04490E-03 320810 + 197 320811 Ge-81m 2.35670E-04 3.84020E-04 320811 + 198 320820 Ge-82 2.48690E-03 2.55980E-03 320820 + 199 320830 Ge-83 1.27270E-03 1.28750E-03 320830 + 200 320840 Ge-84 5.53300E-04 5.53590E-04 320840 + 201 320850 Ge-85 8.08230E-05 8.08740E-05 320850 + 202 320860 Ge-86 2.25740E-05 2.25760E-05 320860 + 203 320870 Ge-87 2.38850E-06 2.38850E-06 320870 + 204 320880 Ge-88 2.42750E-08 2.42750E-08 320880 + 205 320890 Ge-89 7.28230E-10 7.28230E-10 320890 + 206 330740 As-74 2.48640E-12 2.48640E-12 330740 + 207 330750 As-75 5.05440E-11 2.26810E-04 33075.82c + 208 330751 As-75m 3.12300E-10 3.16530E-09 330751 + 209 330760 As-76 9.16720E-09 9.16720E-09 330760 + 210 330770 As-77 2.24540E-07 3.25060E-04 330770 + 211 330780 As-78 9.76290E-07 4.19570E-04 330780 + 212 330790 As-79 3.00620E-05 9.27620E-04 330790 + 213 330800 As-80 1.19930E-04 1.85720E-03 330800 + 214 330810 As-81 6.91490E-04 3.11650E-03 330810 + 215 330820 As-82 2.79930E-04 2.83970E-03 330820 + 216 330821 As-82m 1.58380E-03 1.58380E-03 330821 + 217 330830 As-83 3.89970E-03 5.24700E-03 330830 + 218 330840 As-84 1.84610E-03 2.09870E-03 330840 + 219 330841 As-84m 1.84610E-03 2.09870E-03 330841 + 220 330850 As-85 2.08910E-03 2.15860E-03 330850 + 221 330860 As-86 1.15520E-03 1.17780E-03 330860 + 222 330870 As-87 4.37570E-04 4.39960E-04 330870 + 223 330880 As-88 6.98150E-05 6.98390E-05 330880 + 224 330890 As-89 8.75090E-06 8.75160E-06 330890 + 225 330900 As-90 1.78430E-07 1.78430E-07 330900 + 226 330910 As-91 8.46020E-09 8.46020E-09 330910 + 227 340770 Se-77 3.99780E-12 3.25060E-04 34077.82c + 228 340771 Se-77m 4.79890E-11 4.79890E-11 340771 + 229 340780 Se-78 3.26710E-09 4.19570E-04 34078.82c + 230 340790 Se-79 1.16010E-06 9.28370E-04 34079.82c + 231 340791 Se-79m 9.66400E-08 9.05750E-04 340791 + 232 340800 Se-80 4.52200E-06 1.86170E-03 34080.82c + 233 340810 Se-81 6.83230E-06 3.20530E-03 340810 + 234 340811 Se-81m 8.20150E-05 1.93890E-04 340811 + 235 340820 Se-82 4.44770E-04 4.86830E-03 34082.82c + 236 340830 Se-83 1.72140E-03 3.61320E-03 340830 + 237 340831 Se-83m 2.16240E-04 3.57730E-03 340831 + 238 340840 Se-84 7.92280E-03 1.25890E-02 340840 + 239 340850 Se-85 7.09890E-03 9.17130E-03 340850 + 240 340860 Se-86 1.15190E-02 1.23760E-02 340860 + 241 340870 Se-87 6.71160E-03 7.08380E-03 340870 + 242 340880 Se-88 3.69070E-03 3.76050E-03 340880 + 243 340890 Se-89 1.52700E-03 1.53580E-03 340890 + 244 340900 Se-90 4.09830E-04 4.10010E-04 340900 + 245 340910 Se-91 6.72700E-05 6.72780E-05 340910 + 246 340920 Se-92 1.03140E-05 1.03140E-05 340920 + 247 340930 Se-93 6.30360E-08 6.30360E-08 340930 + 248 340940 Se-94 1.84590E-09 1.84590E-09 340940 + 249 350790 Br-79 4.36930E-12 5.07250E-07 35079.82c + 250 350791 Br-79m 2.69970E-11 2.69970E-11 350791 + 251 350800 Br-80 1.96130E-10 1.30580E-09 350800 + 252 350801 Br-80m 1.10970E-09 1.10970E-09 350801 + 253 350810 Br-81 9.21850E-08 3.20550E-03 35081.82c + 254 350820 Br-82 2.68660E-06 3.26730E-06 350820 + 255 350821 Br-82m 5.94950E-07 5.94950E-07 350821 + 256 350830 Br-83 3.61860E-05 7.22670E-03 350830 + 257 350840 Br-84 1.29370E-04 1.27190E-02 350840 + 258 350841 Br-84m 1.29370E-04 1.29370E-04 350841 + 259 350850 Br-85 1.19510E-03 1.03660E-02 350850 + 260 350860 Br-86 3.99140E-03 1.63670E-02 350860 + 261 350870 Br-87 9.27110E-03 1.63920E-02 350870 + 262 350880 Br-88 9.68260E-03 1.35260E-02 350880 + 263 350890 Br-89 1.21430E-02 1.35590E-02 350890 + 264 350900 Br-90 6.73160E-03 7.15570E-03 350900 + 265 350910 Br-91 4.02360E-03 4.07670E-03 350910 + 266 350920 Br-92 9.70800E-04 9.81110E-04 350920 + 267 350930 Br-93 2.54570E-04 2.54630E-04 350930 + 268 350940 Br-94 2.74120E-05 2.74140E-05 350940 + 269 350950 Br-95 7.18810E-06 7.18810E-06 350950 + 270 350960 Br-96 1.40950E-08 1.40950E-08 350960 + 271 360820 Kr-82 5.56110E-10 3.28220E-06 36082.82c + 272 360830 Kr-83 2.23580E-08 7.22670E-03 36083.82c + 273 360831 Kr-83m 2.80850E-09 7.22030E-03 360831 + 274 360840 Kr-84 9.14040E-06 1.28570E-02 36084.82c + 275 360850 Kr-85 4.39160E-05 2.27680E-03 36085.82c + 276 360851 Kr-85m 5.51670E-06 1.03550E-02 360851 + 277 360860 Kr-86 6.01870E-04 1.73810E-02 36086.82c + 278 360870 Kr-87 1.83180E-03 1.87190E-02 360870 + 279 360880 Kr-88 6.50250E-03 2.10340E-02 360880 + 280 360890 Kr-89 1.33290E-02 2.67360E-02 360890 + 281 360900 Kr-90 2.24480E-02 2.86590E-02 360900 + 282 360910 Kr-91 2.32620E-02 2.68480E-02 360910 + 283 360920 Kr-92 1.95320E-02 2.03620E-02 360920 + 284 360930 Kr-93 9.37560E-03 9.47630E-03 360930 + 285 360940 Kr-94 4.09620E-03 4.10440E-03 360940 + 286 360950 Kr-95 7.57020E-04 7.64210E-04 360950 + 287 360960 Kr-96 1.46680E-04 1.46690E-04 360960 + 288 360970 Kr-97 1.54060E-05 1.54060E-05 360970 + 289 360980 Kr-98 1.81450E-06 1.81450E-06 360980 + 290 360990 Kr-99 3.11760E-09 3.11760E-09 360990 + 291 370850 Rb-85 5.87790E-09 1.04160E-02 37085.82c + 292 370860 Rb-86 4.94460E-08 2.22430E-07 37086.82c + 293 370861 Rb-86m 1.72980E-07 1.72980E-07 370861 + 294 370870 Rb-87 2.15040E-05 1.87400E-02 37087.82c + 295 370880 Rb-88 1.04690E-04 2.11390E-02 370880 + 296 370890 Rb-89 7.89040E-04 2.75260E-02 370890 + 297 370900 Rb-90 1.47060E-04 2.52170E-02 370900 + 298 370901 Rb-90m 2.37970E-03 6.12830E-03 370901 + 299 370910 Rb-91 8.82610E-03 3.56740E-02 370910 + 300 370920 Rb-92 1.36790E-02 3.40410E-02 370920 + 301 370930 Rb-93 2.44730E-02 3.39950E-02 370930 + 302 370940 Rb-94 2.16080E-02 2.56890E-02 370940 + 303 370950 Rb-95 1.58000E-02 1.65480E-02 370950 + 304 370960 Rb-96 2.95630E-03 4.54110E-03 370960 + 305 370961 Rb-96m 2.95630E-03 3.02740E-03 370961 + 306 370970 Rb-97 2.43850E-03 2.45300E-03 370970 + 307 370980 Rb-98 2.17140E-04 2.17140E-04 370980 + 308 370981 Rb-98m 2.17140E-04 2.18830E-04 370981 + 309 370990 Rb-99 9.36430E-05 9.36460E-05 370990 + 310 371000 Rb-100 5.02530E-06 5.02530E-06 371000 + 311 371010 Rb-101 1.03940E-06 1.03940E-06 371010 + 312 380870 Sr-87 8.61960E-10 9.69910E-10 38087.82c + 313 380871 Sr-87m 1.08280E-10 1.08280E-10 380871 + 314 380880 Sr-88 2.96250E-06 2.11410E-02 38088.82c + 315 380890 Sr-89 1.09430E-05 2.75360E-02 38089.82c + 316 380900 Sr-90 1.47460E-04 3.13330E-02 38090.82c + 317 380910 Sr-91 9.00130E-04 3.65740E-02 380910 + 318 380920 Sr-92 3.82210E-03 3.83380E-02 380920 + 319 380930 Sr-93 9.07000E-03 4.51840E-02 380930 + 320 380940 Sr-94 2.14520E-02 4.59690E-02 380940 + 321 380950 Sr-95 2.62160E-02 4.19490E-02 380950 + 322 380960 Sr-96 3.59590E-02 4.20210E-02 380960 + 323 380970 Sr-97 2.64800E-02 2.83470E-02 380970 + 324 380980 Sr-98 1.68990E-02 1.73200E-02 380980 + 325 380990 Sr-99 5.05260E-03 5.13160E-03 380990 + 326 381000 Sr-100 1.55510E-03 1.55980E-03 381000 + 327 381010 Sr-101 2.29190E-04 2.30230E-04 381010 + 328 381020 Sr-102 3.28380E-05 3.28380E-05 381020 + 329 381030 Sr-103 2.02930E-06 2.02930E-06 381030 + 330 381040 Sr-104 5.45260E-09 5.45260E-09 381040 + 331 390900 Y-90 1.95150E-09 3.13330E-02 39090.82c + 332 390901 Y-90m 5.57750E-09 5.57750E-09 390901 + 333 390910 Y-91 2.31410E-07 3.65760E-02 39091.82c + 334 390911 Y-91m 1.84220E-06 2.15210E-02 390911 + 335 390920 Y-92 2.34310E-05 3.83620E-02 390920 + 336 390930 Y-93 1.94140E-05 4.54360E-02 390930 + 337 390931 Y-93m 2.33050E-04 1.15400E-02 390931 + 338 390940 Y-94 1.04760E-03 4.70170E-02 390940 + 339 390950 Y-95 4.23420E-03 4.61830E-02 390950 + 340 390960 Y-96 1.84060E-03 4.38690E-02 390960 + 341 390961 Y-96m 6.43930E-03 6.44640E-03 390961 + 342 390970 Y-97 2.11480E-03 2.63690E-02 390970 + 343 390971 Y-97m 9.79340E-03 1.96430E-02 390971 + 344 390972 Y-97m 7.04180E-03 7.04180E-03 390972 + 345 390980 Y-98 2.73690E-03 2.00570E-02 390980 + 346 390981 Y-98m 2.14620E-02 2.14620E-02 390981 + 347 390990 Y-99 3.30170E-02 3.81610E-02 390990 + 348 391000 Y-100 1.01210E-02 1.16710E-02 391000 + 349 391001 Y-100m 1.01210E-02 1.01240E-02 391001 + 350 391010 Y-101 1.11690E-02 1.13960E-02 391010 + 351 391020 Y-102 1.07380E-03 1.08930E-03 391020 + 352 391021 Y-102m 1.07380E-03 1.08930E-03 391021 + 353 391030 Y-103 7.52380E-04 7.54410E-04 391030 + 354 391040 Y-104 9.00700E-05 9.00760E-05 391040 + 355 391050 Y-105 1.39140E-05 1.39140E-05 391050 + 356 391060 Y-106 2.06680E-08 2.06680E-08 391060 + 357 391070 Y-107 5.85200E-10 5.85200E-10 391070 + 358 400920 Zr-92 1.39060E-09 3.83620E-02 40092.82c + 359 400930 Zr-93 5.95520E-06 4.54420E-02 40093.82c + 360 400940 Zr-94 3.71430E-05 4.70540E-02 40094.82c + 361 400950 Zr-95 2.05340E-04 4.63890E-02 40095.82c + 362 400960 Zr-96 1.19450E-03 5.15250E-02 40096.82c + 363 400970 Zr-97 3.79670E-03 5.18560E-02 400970 + 364 400980 Zr-98 1.08190E-02 5.21940E-02 400980 + 365 400990 Zr-99 1.84430E-02 5.60620E-02 400990 + 366 401000 Zr-100 3.39340E-02 5.56220E-02 401000 + 367 401010 Zr-101 3.38090E-02 4.53110E-02 401010 + 368 401020 Zr-102 2.24110E-02 2.45430E-02 401020 + 369 401030 Zr-103 1.20630E-02 1.27650E-02 401030 + 370 401040 Zr-104 4.54470E-03 4.62960E-03 401040 + 371 401050 Zr-105 9.92320E-04 1.00350E-03 401050 + 372 401060 Zr-106 2.21350E-04 2.21370E-04 401060 + 373 401070 Zr-107 3.02910E-05 3.02920E-05 401070 + 374 401080 Zr-108 5.13870E-06 5.13870E-06 401080 + 375 401090 Zr-109 2.52110E-09 2.52110E-09 401090 + 376 410950 Nb-95 1.59620E-06 4.63620E-02 41095.82c + 377 410951 Nb-95m 2.00510E-07 5.01360E-04 410951 + 378 410960 Nb-96 1.72000E-06 1.72000E-06 410960 + 379 410970 Nb-97 4.98040E-05 5.19130E-02 410970 + 380 410971 Nb-97m 6.25630E-06 4.92950E-02 410971 + 381 410980 Nb-98 4.28480E-05 5.22370E-02 410980 + 382 410981 Nb-98m 2.42420E-04 2.42420E-04 410981 + 383 410990 Nb-99 1.44320E-03 3.72910E-02 410990 + 384 410991 Nb-99m 1.81290E-04 2.08120E-02 410991 + 385 411000 Nb-100 4.98630E-04 5.61200E-02 411000 + 386 411001 Nb-100m 3.91020E-03 3.91020E-03 411001 + 387 411010 Nb-101 1.17990E-02 5.71100E-02 411010 + 388 411020 Nb-102 6.22550E-03 3.07690E-02 411020 + 389 411021 Nb-102m 6.22550E-03 6.22550E-03 411021 + 390 411030 Nb-103 2.46370E-02 3.74020E-02 411030 + 391 411040 Nb-104 8.75450E-03 1.33980E-02 411040 + 392 411041 Nb-104m 8.75450E-03 8.75450E-03 411041 + 393 411050 Nb-105 1.36730E-02 1.46660E-02 411050 + 394 411060 Nb-106 5.15460E-03 5.37370E-03 411060 + 395 411070 Nb-107 1.99210E-03 2.02130E-03 411070 + 396 411080 Nb-108 5.71720E-04 5.76860E-04 411080 + 397 411090 Nb-109 1.92260E-04 1.92260E-04 411090 + 398 411100 Nb-110 3.69790E-05 3.69790E-05 411100 + 399 411110 Nb-111 5.79570E-06 5.79570E-06 411110 + 400 411120 Nb-112 1.29760E-05 1.29760E-05 411120 + 401 420970 Mo-97 1.36830E-09 5.19130E-02 42097.82c + 402 420980 Mo-98 6.34880E-06 5.24860E-02 42098.82c + 403 420990 Mo-99 2.59680E-05 5.77130E-02 42099.82c + 404 421000 Mo-100 2.80240E-04 6.03110E-02 42100.82c + 405 421010 Mo-101 1.03750E-03 5.81480E-02 421010 + 406 421020 Mo-102 2.90450E-03 3.98990E-02 421020 + 407 421030 Mo-103 7.19540E-03 4.46100E-02 421030 + 408 421040 Mo-104 1.27090E-02 3.50990E-02 421040 + 409 421050 Mo-105 1.34790E-02 2.81370E-02 421050 + 410 421060 Mo-106 1.44180E-02 1.96710E-02 421060 + 411 421070 Mo-107 7.14860E-03 9.08440E-03 421070 + 412 421080 Mo-108 5.20160E-03 5.76700E-03 421080 + 413 421090 Mo-109 2.14470E-03 2.32740E-03 421090 + 414 421100 Mo-110 9.24880E-04 9.47070E-04 421100 + 415 421110 Mo-111 2.16940E-04 2.22740E-04 421110 + 416 421120 Mo-112 9.43210E-05 1.07300E-04 421120 + 417 421130 Mo-113 1.12970E-05 1.12970E-05 421130 + 418 421140 Mo-114 1.04560E-05 1.04560E-05 421140 + 419 421150 Mo-115 1.13760E-06 1.13760E-06 421150 + 420 431000 Tc-100 4.45020E-09 4.45020E-09 431000 + 421 431010 Tc-101 6.23590E-06 5.81540E-02 431010 + 422 431020 Tc-102 1.52540E-05 3.99140E-02 431020 + 423 431021 Tc-102m 1.52540E-05 1.52540E-05 431021 + 424 431030 Tc-103 2.71590E-04 4.48810E-02 431030 + 425 431040 Tc-104 8.30010E-04 3.59290E-02 431040 + 426 431050 Tc-105 2.98340E-03 3.11210E-02 431050 + 427 431060 Tc-106 4.89730E-03 2.45690E-02 431060 + 428 431070 Tc-107 7.28780E-03 1.63720E-02 431070 + 429 431080 Tc-108 7.24980E-03 1.30290E-02 431080 + 430 431090 Tc-109 7.23810E-03 9.55320E-03 431090 + 431 431100 Tc-110 4.31900E-03 5.26840E-03 431100 + 432 431110 Tc-111 2.91760E-03 3.14030E-03 431110 + 433 431120 Tc-112 1.28780E-03 1.39290E-03 431120 + 434 431130 Tc-113 5.79630E-04 5.90930E-04 431130 + 435 431140 Tc-114 1.11880E-04 1.22340E-04 431140 + 436 431150 Tc-115 2.84930E-05 2.96310E-05 431150 + 437 431160 Tc-116 9.62450E-07 9.62450E-07 431160 + 438 431170 Tc-117 4.63830E-10 4.63830E-10 431170 + 439 441030 Ru-103 3.68930E-09 4.48810E-02 44103.82c + 440 441031 Ru-103m 1.69330E-08 1.69330E-08 441031 + 441 441040 Ru-104 1.51460E-05 3.59440E-02 44104.82c + 442 441050 Ru-105 1.02910E-04 3.12240E-02 44105.82c + 443 441060 Ru-106 3.76800E-04 2.49450E-02 44106.82c + 444 441070 Ru-107 7.72700E-04 1.71450E-02 441070 + 445 441080 Ru-108 2.33060E-03 1.53670E-02 441080 + 446 441090 Ru-109 3.52740E-03 1.30750E-02 441090 + 447 441100 Ru-110 5.81310E-03 1.10790E-02 441100 + 448 441110 Ru-111 5.14710E-03 8.30830E-03 441110 + 449 441120 Ru-112 6.25670E-03 7.67110E-03 441120 + 450 441130 Ru-113 1.81700E-03 3.28200E-03 441130 + 451 441131 Ru-113m 1.81700E-03 1.81700E-03 441131 + 452 441140 Ru-114 2.31190E-03 2.43050E-03 441140 + 453 441150 Ru-115 7.02730E-04 7.28230E-04 441150 + 454 441160 Ru-116 2.07930E-04 2.08770E-04 441160 + 455 441170 Ru-117 2.67540E-05 2.67540E-05 441170 + 456 441180 Ru-118 1.74290E-05 1.74290E-05 441180 + 457 441190 Ru-119 5.55190E-09 5.55190E-09 441190 + 458 441200 Ru-120 3.44560E-07 3.44560E-07 441200 + 459 451050 Rh-105 1.97330E-09 3.12240E-02 45105.82c + 460 451051 Rh-105m 1.64390E-10 8.86370E-03 451051 + 461 451060 Rh-106 1.80970E-07 2.49450E-02 451060 + 462 451061 Rh-106m 8.17230E-07 8.17230E-07 451061 + 463 451070 Rh-107 9.79870E-06 1.71550E-02 451070 + 464 451080 Rh-108 9.11370E-06 1.53760E-02 451080 + 465 451081 Rh-108m 5.15630E-05 5.15630E-05 451081 + 466 451090 Rh-109 2.36920E-04 1.33120E-02 451090 + 467 451100 Rh-110 5.05840E-04 1.15850E-02 451100 + 468 451101 Rh-110m 7.59890E-06 7.59890E-06 451101 + 469 451110 Rh-111 1.41050E-03 9.71880E-03 451110 + 470 451120 Rh-112 1.20510E-03 8.87620E-03 451120 + 471 451121 Rh-112m 1.20510E-03 1.20510E-03 451121 + 472 451130 Rh-113 4.37350E-03 8.56410E-03 451130 + 473 451140 Rh-114 2.39560E-03 4.82770E-03 451140 + 474 451141 Rh-114m 2.39560E-03 2.39560E-03 451141 + 475 451150 Rh-115 6.21170E-03 6.94050E-03 451150 + 476 451160 Rh-116 6.03710E-04 8.10780E-04 451160 + 477 451161 Rh-116m 2.72620E-03 2.72620E-03 451161 + 478 451170 Rh-117 1.80740E-03 1.83430E-03 451170 + 479 451180 Rh-118 7.09770E-04 7.26480E-04 451180 + 480 451190 Rh-119 2.54340E-04 2.54350E-04 451190 + 481 451200 Rh-120 3.91580E-05 3.95030E-05 451200 + 482 451210 Rh-121 1.76020E-05 1.76020E-05 451210 + 483 451220 Rh-122 1.30630E-06 1.30630E-06 451220 + 484 461080 Pd-108 5.88730E-09 1.54280E-02 46108.82c + 485 461090 Pd-109 4.92830E-07 1.33140E-02 461090 + 486 461091 Pd-109m 1.81660E-06 6.65780E-03 461091 + 487 461100 Pd-110 2.18920E-05 1.16150E-02 46110.82c + 488 461110 Pd-111 1.34400E-05 9.75790E-03 461110 + 489 461111 Pd-111m 4.95420E-05 8.84170E-05 461111 + 490 461120 Pd-112 2.27070E-04 1.03080E-02 461120 + 491 461130 Pd-113 1.00590E-04 9.12630E-03 461130 + 492 461131 Pd-113m 4.61660E-04 4.61660E-04 461131 + 493 461140 Pd-114 1.28500E-03 8.50830E-03 461140 + 494 461150 Pd-115 3.88280E-04 6.51620E-03 461150 + 495 461151 Pd-115m 1.43120E-03 2.43900E-03 461151 + 496 461160 Pd-116 2.88290E-03 6.41990E-03 461160 + 497 461170 Pd-117 8.61600E-04 5.89300E-03 461170 + 498 461171 Pd-117m 3.17590E-03 3.17590E-03 461171 + 499 461180 Pd-118 6.62990E-03 7.33520E-03 461180 + 500 461190 Pd-119 3.28030E-03 3.53700E-03 461190 + 501 461200 Pd-120 1.91450E-03 1.95410E-03 461200 + 502 461210 Pd-121 5.32120E-04 5.47330E-04 461210 + 503 461220 Pd-122 2.32350E-04 2.33660E-04 461220 + 504 461230 Pd-123 5.11360E-05 5.11360E-05 461230 + 505 461240 Pd-124 1.62280E-05 1.62280E-05 461240 + 506 471100 Ag-110 4.90090E-11 5.20190E-11 471100 + 507 471101 Ag-110m 2.21310E-10 2.21310E-10 47510.82c + 508 471110 Ag-111 1.19060E-09 9.73320E-03 47111.82c + 509 471111 Ag-111m 1.42910E-08 9.70610E-03 471111 + 510 471120 Ag-112 2.59380E-06 1.03110E-02 471120 + 511 471130 Ag-113 8.65430E-07 5.98770E-03 471130 + 512 471131 Ag-113m 1.03890E-05 8.74950E-03 471131 + 513 471140 Ag-114 4.65680E-06 8.54950E-03 471140 + 514 471141 Ag-114m 3.65170E-05 3.65170E-05 471141 + 515 471150 Ag-115 1.86850E-05 5.66330E-03 471150 + 516 471151 Ag-115m 2.24300E-04 4.22750E-03 471151 + 517 471160 Ag-116 8.41700E-05 6.52680E-03 471160 + 518 471161 Ag-116m 3.80090E-04 3.80090E-04 471161 + 519 471170 Ag-117 7.51790E-05 3.25260E-03 471170 + 520 471171 Ag-117m 9.02440E-04 3.84890E-03 471171 + 521 471180 Ag-118 3.42960E-04 8.16210E-03 471180 + 522 471181 Ag-118m 2.68940E-03 3.73810E-03 471181 + 523 471190 Ag-119 3.94600E-04 2.16310E-03 471190 + 524 471191 Ag-119m 4.73670E-03 6.50520E-03 471191 + 525 471200 Ag-120 1.27130E-03 3.95570E-03 471200 + 526 471201 Ag-120m 3.63340E-03 4.61040E-03 471201 + 527 471210 Ag-121 5.31740E-03 5.86320E-03 471210 + 528 471220 Ag-122 1.01740E-03 1.25110E-03 471220 + 529 471221 Ag-122m 1.94880E-03 1.94880E-03 471221 + 530 471230 Ag-123 2.00580E-03 2.05690E-03 471230 + 531 471240 Ag-124 2.32770E-04 4.71930E-04 471240 + 532 471241 Ag-124m 4.45870E-04 4.45870E-04 471241 + 533 471250 Ag-125 2.85230E-04 2.85230E-04 471250 + 534 471260 Ag-126 9.43390E-05 9.43390E-05 471260 + 535 471270 Ag-127 1.69040E-05 1.69040E-05 471270 + 536 471280 Ag-128 5.32550E-06 5.32550E-06 471280 + 537 471290 Ag-129 7.21880E-09 7.21880E-09 471290 + 538 481130 Cd-113 1.97180E-10 9.03420E-03 48113.82c + 539 481131 Cd-113m 1.21830E-09 1.03520E-04 481131 + 540 481140 Cd-114 6.54990E-08 8.54960E-03 48114.82c + 541 481150 Cd-115 3.16660E-07 8.57980E-03 481150 + 542 481151 Cd-115m 1.95650E-06 4.25520E-04 48515.82c + 543 481160 Cd-116 1.43450E-05 6.89850E-03 48116.82c + 544 481170 Cd-117 1.49080E-05 5.43870E-03 481170 + 545 481171 Cd-117m 9.21120E-05 1.53900E-03 481171 + 546 481180 Cd-118 6.88870E-04 1.10570E-02 481180 + 547 481190 Cd-119 2.48920E-04 7.83570E-03 481190 + 548 481191 Cd-119m 1.14250E-03 2.22410E-03 481191 + 549 481200 Cd-120 3.09060E-03 9.95070E-03 481200 + 550 481210 Cd-121 7.08340E-04 5.95900E-03 481210 + 551 481211 Cd-121m 3.25110E-03 3.86370E-03 481211 + 552 481220 Cd-122 5.82280E-03 9.02270E-03 481220 + 553 481230 Cd-123 8.81120E-04 2.56430E-03 481230 + 554 481231 Cd-123m 4.04410E-03 4.41830E-03 481231 + 555 481240 Cd-124 5.19980E-03 5.89420E-03 481240 + 556 481250 Cd-125 5.06540E-04 6.49150E-04 481250 + 557 481251 Cd-125m 2.32490E-03 2.46750E-03 481251 + 558 481260 Cd-126 1.96280E-03 2.05710E-03 481260 + 559 481270 Cd-127 8.00020E-04 8.16920E-04 481270 + 560 481280 Cd-128 3.36630E-04 3.41960E-04 481280 + 561 481290 Cd-129 1.71180E-05 1.71210E-05 481290 + 562 481291 Cd-129m 7.85660E-05 7.85700E-05 481291 + 563 481300 Cd-130 1.46560E-05 1.46560E-05 481300 + 564 481310 Cd-131 8.62130E-07 8.62130E-07 481310 + 565 481320 Cd-132 5.35440E-09 5.35440E-09 481320 + 566 491150 In-115 2.46020E-10 8.57630E-03 49115.82c + 567 491151 In-115m 3.09040E-11 8.57980E-03 491151 + 568 491160 In-116 7.76560E-10 7.76560E-10 491160 + 569 491161 In-116m 1.44040E-09 4.39360E-09 491161 + 570 491162 In-116m 2.95320E-09 2.95320E-09 491162 + 571 491170 In-117 1.75730E-07 4.32880E-03 491170 + 572 491171 In-117m 2.20760E-08 5.00760E-03 491171 + 573 491180 In-118 1.18570E-06 1.10580E-02 491180 + 574 491181 In-118m 2.19920E-06 6.64500E-06 491181 + 575 491182 In-118m 4.50890E-06 4.50890E-06 491182 + 576 491190 In-119 5.28310E-05 3.43060E-03 491190 + 577 491191 In-119m 6.63660E-06 7.08550E-03 491191 + 578 491200 In-120 5.72080E-05 1.00080E-02 491200 + 579 491201 In-120m 5.72080E-05 5.72080E-05 491201 + 580 491202 In-120m 5.72080E-05 5.72080E-05 491202 + 581 491210 In-121 6.91240E-04 6.61040E-03 491210 + 582 491211 In-121m 8.68330E-05 4.03880E-03 491211 + 583 491220 In-122 4.21100E-04 9.44380E-03 491220 + 584 491221 In-122m 6.01750E-04 6.01750E-04 491221 + 585 491222 In-122m 6.01750E-04 6.01750E-04 491222 + 586 491230 In-123 3.22050E-03 8.37920E-03 491230 + 587 491231 In-123m 4.04560E-04 2.22850E-03 491231 + 588 491240 In-124 1.67010E-03 7.56430E-03 491240 + 589 491241 In-124m 3.19890E-03 3.19890E-03 491241 + 590 491250 In-125 6.62310E-03 9.40130E-03 491250 + 591 491251 In-125m 8.31990E-04 1.17040E-03 491251 + 592 491260 In-126 2.15990E-03 4.21700E-03 491260 + 593 491261 In-126m 4.13710E-03 4.13710E-03 491261 + 594 491270 In-127 5.70660E-03 5.70660E-03 491270 + 595 491271 In-127m 7.16860E-04 1.53380E-03 491271 + 596 491280 In-128 1.02210E-03 1.72510E-03 491280 + 597 491281 In-128m 3.61010E-04 7.02960E-04 491281 + 598 491282 In-128m 2.65010E-03 2.65010E-03 491282 + 599 491290 In-129 2.39350E-03 2.47230E-03 491290 + 600 491291 In-129m 3.00670E-04 3.18050E-04 491291 + 601 491300 In-130 2.07730E-04 2.21900E-04 491300 + 602 491301 In-130m 6.73240E-04 6.73240E-04 491301 + 603 491302 In-130m 5.02030E-04 5.02030E-04 491302 + 604 491310 In-131 1.83590E-04 1.86290E-04 491310 + 605 491311 In-131m 1.83590E-04 1.83590E-04 491311 + 606 491312 In-131m 1.83590E-04 1.83590E-04 491312 + 607 491320 In-132 6.12860E-05 6.12880E-05 491320 + 608 491330 In-133 4.94630E-06 5.56770E-06 491330 + 609 491331 In-133m 6.21360E-07 6.21360E-07 491331 + 610 491340 In-134 3.50750E-08 3.50750E-08 491340 + 611 491350 In-135 1.84050E-09 1.84050E-09 491350 + 612 501180 Sn-118 1.63940E-09 1.10640E-02 50118.82c + 613 501190 Sn-119 2.30460E-07 1.01210E-02 50119.82c + 614 501191 Sn-119m 1.42390E-06 3.10060E-03 501191 + 615 501200 Sn-120 6.73750E-06 1.01290E-02 50120.82c + 616 501210 Sn-121 4.07340E-06 1.04520E-02 501210 + 617 501211 Sn-121m 1.86960E-05 7.67540E-04 501211 + 618 501220 Sn-122 1.38040E-04 1.07850E-02 50122.82c + 619 501230 Sn-123 2.70280E-04 9.09130E-04 50123.82c + 620 501231 Sn-123m 5.88880E-05 1.00280E-02 501231 + 621 501240 Sn-124 1.11310E-03 1.18760E-02 50124.82c + 622 501250 Sn-125 1.77620E-03 3.36430E-03 50125.82c + 623 501251 Sn-125m 3.87000E-04 9.37070E-03 501251 + 624 501260 Sn-126 4.94410E-03 1.33090E-02 50126.82c + 625 501270 Sn-127 5.18000E-03 7.40430E-03 501270 + 626 501271 Sn-127m 1.12860E-03 6.13410E-03 501271 + 627 501280 Sn-128 1.90750E-03 1.48960E-02 501280 + 628 501281 Sn-128m 8.61350E-03 1.12640E-02 501281 + 629 501290 Sn-129 1.69480E-03 4.22210E-03 501290 + 630 501291 Sn-129m 7.77840E-03 8.04160E-03 501291 + 631 501300 Sn-130 2.57750E-03 3.23910E-03 501300 + 632 501301 Sn-130m 1.16400E-02 1.23790E-02 501301 + 633 501310 Sn-131 1.90850E-03 2.26480E-03 501310 + 634 501311 Sn-131m 8.75950E-03 8.95110E-03 501311 + 635 501320 Sn-132 6.56300E-03 6.62900E-03 501320 + 636 501330 Sn-133 1.07190E-03 1.07280E-03 501330 + 637 501340 Sn-134 2.40680E-04 2.40690E-04 501340 + 638 501350 Sn-135 2.21380E-05 2.21400E-05 501350 + 639 501360 Sn-136 4.75180E-06 4.75180E-06 501360 + 640 501370 Sn-137 7.50620E-09 7.50620E-09 501370 + 641 511220 Sb-122 5.12020E-07 1.69430E-06 511220 + 642 511221 Sb-122m 1.18230E-06 1.18230E-06 511221 + 643 511230 Sb-123 7.91870E-06 1.09450E-02 51123.82c + 644 511240 Sb-124 4.90910E-06 1.77890E-05 51124.82c + 645 511241 Sb-124m 4.56010E-06 1.71740E-05 511241 + 646 511242 Sb-124m 1.26140E-05 1.26140E-05 511242 + 647 511250 Sb-125 9.01830E-05 1.28250E-02 51125.82c + 648 511260 Sb-126 1.52190E-04 1.68190E-04 51126.82c + 649 511261 Sb-126m 5.50200E-05 1.14250E-04 511261 + 650 511262 Sb-126m 5.92300E-05 5.92300E-05 511262 + 651 511270 Sb-127 8.87010E-04 1.44260E-02 511270 + 652 511280 Sb-128 9.74920E-04 1.58970E-02 511280 + 653 511281 Sb-128m 7.31880E-04 7.31880E-04 511281 + 654 511290 Sb-129 1.89660E-03 1.11290E-02 511290 + 655 511291 Sb-129m 2.57540E-03 6.59620E-03 511291 + 656 511300 Sb-130 4.11210E-03 1.35410E-02 511300 + 657 511301 Sb-130m 4.11210E-03 1.03010E-02 511301 + 658 511310 Sb-131 1.98490E-02 3.10650E-02 511310 + 659 511320 Sb-132 9.09540E-03 1.57240E-02 511320 + 660 511321 Sb-132m 1.44620E-02 1.44620E-02 511321 + 661 511330 Sb-133 2.49360E-02 2.60500E-02 511330 + 662 511340 Sb-134 1.28460E-03 1.48670E-03 511340 + 663 511341 Sb-134m 5.80100E-03 5.80330E-03 511341 + 664 511350 Sb-135 2.55800E-03 2.57690E-03 511350 + 665 511360 Sb-136 6.09490E-04 6.12820E-04 511360 + 666 511370 Sb-137 1.27630E-04 1.27630E-04 511370 + 667 511380 Sb-138 9.30300E-06 9.30300E-06 511380 + 668 511390 Sb-139 3.23900E-06 3.23900E-06 511390 + 669 521240 Te-124 1.47130E-06 2.35540E-05 52124.82c + 670 521250 Te-125 1.76630E-07 1.28260E-02 52125.82c + 671 521251 Te-125m 1.09140E-06 2.87090E-03 521251 + 672 521260 Te-126 6.58740E-06 2.73030E-04 52126.82c + 673 521270 Te-127 3.66120E-06 1.43890E-02 521270 + 674 521271 Te-127m 1.68040E-05 2.39400E-03 52527.82c + 675 521280 Te-128 1.14720E-04 1.67180E-02 52128.82c + 676 521290 Te-129 5.99830E-05 1.42600E-02 521290 + 677 521291 Te-129m 2.75310E-04 7.59750E-03 52529.82c + 678 521300 Te-130 1.72670E-03 2.55690E-02 52130.82c + 679 521310 Te-131 9.31530E-04 3.09290E-02 521310 + 680 521311 Te-131m 4.27550E-03 6.76260E-03 521311 + 681 521320 Te-132 1.60470E-02 4.62330E-02 52132.82c + 682 521330 Te-133 4.76550E-03 3.09300E-02 521330 + 683 521331 Te-133m 2.18720E-02 2.63790E-02 521331 + 684 521340 Te-134 4.40610E-02 5.17520E-02 521340 + 685 521350 Te-135 2.37610E-02 2.60330E-02 521350 + 686 521360 Te-136 1.77530E-02 1.83270E-02 521360 + 687 521370 Te-137 4.94860E-03 5.01370E-03 521370 + 688 521380 Te-138 1.63030E-03 1.63960E-03 521380 + 689 521390 Te-139 1.91000E-04 1.94240E-04 521390 + 690 521400 Te-140 6.30360E-05 6.30360E-05 521400 + 691 521410 Te-141 5.35950E-06 5.35950E-06 521410 + 692 521420 Te-142 1.05330E-06 1.05330E-06 521420 + 693 531280 I-128 7.60850E-07 7.60850E-07 531280 + 694 531290 I-129 2.51460E-06 1.70730E-02 53129.82c + 695 531300 I-130 1.62040E-05 1.92180E-05 53130.82c + 696 531301 I-130m 3.58830E-06 3.58830E-06 531301 + 697 531310 I-131 2.14360E-04 3.64860E-02 53131.82c + 698 531320 I-132 3.52450E-04 4.70670E-02 531320 + 699 531321 I-132m 5.60400E-04 5.60400E-04 531321 + 700 531330 I-133 2.02200E-03 5.74610E-02 531330 + 701 531331 I-133m 2.74570E-03 2.74570E-03 531331 + 702 531340 I-134 4.13740E-03 6.23170E-02 531340 + 703 531341 I-134m 6.57850E-03 6.57850E-03 531341 + 704 531350 I-135 2.44150E-02 5.04480E-02 53135.82c + 705 531360 I-136 4.83530E-03 2.32370E-02 531360 + 706 531361 I-136m 2.18350E-02 2.19100E-02 531361 + 707 531370 I-137 2.97600E-02 3.47270E-02 531370 + 708 531380 I-138 1.15350E-02 1.30710E-02 531380 + 709 531390 I-139 1.15090E-02 1.17030E-02 531390 + 710 531400 I-140 2.62980E-03 2.69280E-03 531400 + 711 531410 I-141 1.08180E-03 1.08720E-03 531410 + 712 531420 I-142 1.57580E-04 1.58630E-04 531420 + 713 531430 I-143 2.70470E-05 2.70470E-05 531430 + 714 531440 I-144 1.10020E-06 1.10020E-06 531440 + 715 541300 Xe-130 7.33430E-07 2.05250E-05 54130.82c + 716 541310 Xe-131 1.54240E-07 3.64870E-02 54131.82c + 717 541311 Xe-131m 7.07900E-07 3.97020E-04 541311 + 718 541320 Xe-132 6.53450E-06 4.71680E-02 54132.82c + 719 541321 Xe-132m 1.50880E-05 1.50880E-05 541321 + 720 541330 Xe-133 3.31720E-05 5.76460E-02 54133.82c + 721 541331 Xe-133m 1.52250E-04 1.78780E-03 541331 + 722 541340 Xe-134 2.16630E-04 6.36630E-02 54134.82c + 723 541341 Xe-134m 9.78270E-04 1.12960E-03 541341 + 724 541350 Xe-135 7.53760E-04 5.45910E-02 54135.82c + 725 541351 Xe-135m 3.45950E-03 1.17880E-02 541351 + 726 541360 Xe-136 1.37230E-02 6.11270E-02 54136.82c + 727 541370 Xe-137 1.87260E-02 5.18890E-02 541370 + 728 541380 Xe-138 2.83650E-02 4.18900E-02 541380 + 729 541390 Xe-139 2.68010E-02 3.76080E-02 541390 + 730 541400 Xe-140 2.85920E-02 3.12630E-02 541400 + 731 541410 Xe-141 1.50530E-02 1.59520E-02 541410 + 732 541420 Xe-142 8.34310E-03 8.47290E-03 541420 + 733 541430 Xe-143 1.94870E-03 1.96540E-03 541430 + 734 541440 Xe-144 5.59020E-04 5.59680E-04 541440 + 735 541450 Xe-145 7.89780E-05 7.89780E-05 541450 + 736 541460 Xe-146 2.27680E-05 2.27680E-05 541460 + 737 541470 Xe-147 2.46910E-06 2.46910E-06 541470 + 738 551330 Cs-133 5.74820E-09 5.76460E-02 55133.82c + 739 551340 Cs-134 1.35800E-06 3.51730E-06 55134.82c + 740 551341 Cs-134m 2.15930E-06 2.15930E-06 551341 + 741 551350 Cs-135 1.76590E-05 5.47030E-02 55135.82c + 742 551351 Cs-135m 2.39790E-05 2.39790E-05 551351 + 743 551360 Cs-136 1.65490E-04 2.75720E-04 55136.82c + 744 551361 Cs-136m 2.20450E-04 2.20450E-04 551361 + 745 551370 Cs-137 2.47070E-03 5.43590E-02 55137.82c + 746 551380 Cs-138 1.22120E-03 4.59390E-02 551380 + 747 551381 Cs-138m 3.49010E-03 3.49010E-03 551381 + 748 551390 Cs-139 1.03330E-02 4.79410E-02 551390 + 749 551400 Cs-140 1.14110E-02 4.26810E-02 551400 + 750 551410 Cs-141 2.14720E-02 3.74470E-02 551410 + 751 551420 Cs-142 1.80520E-02 2.65140E-02 551420 + 752 551430 Cs-143 1.64000E-02 1.83630E-02 551430 + 753 551440 Cs-144 3.44120E-03 5.70770E-03 551440 + 754 551441 Cs-144m 3.44120E-03 3.44320E-03 551441 + 755 551450 Cs-145 3.38830E-03 3.46490E-03 551450 + 756 551460 Cs-146 9.07580E-04 9.28880E-04 551460 + 757 551470 Cs-147 2.31960E-04 2.34330E-04 551470 + 758 551480 Cs-148 1.76640E-05 1.76640E-05 551480 + 759 551490 Cs-149 3.75250E-06 3.75250E-06 551490 + 760 551500 Cs-150 1.15620E-09 1.15620E-09 551500 + 761 561360 Ba-136 8.61230E-07 3.90700E-04 56136.82c + 762 561361 Ba-136m 3.88910E-06 3.88910E-06 561361 + 763 561370 Ba-137 6.46870E-06 5.43950E-02 56137.82c + 764 561371 Ba-137m 2.96890E-05 5.13450E-02 561371 + 765 561380 Ba-138 3.79490E-04 4.69810E-02 56138.82c + 766 561390 Ba-139 1.34080E-03 4.92820E-02 561390 + 767 561400 Ba-140 3.75680E-03 4.64370E-02 56140.82c + 768 561410 Ba-141 6.47290E-03 4.39200E-02 561410 + 769 561420 Ba-142 1.46350E-02 4.14500E-02 561420 + 770 561430 Ba-143 1.80080E-02 3.62520E-02 561430 + 771 561440 Ba-144 2.34230E-02 3.11650E-02 561440 + 772 561450 Ba-145 1.58730E-02 1.89740E-02 561450 + 773 561460 Ba-146 1.17600E-02 1.26240E-02 561460 + 774 561470 Ba-147 4.34600E-03 4.51800E-03 561470 + 775 561480 Ba-148 1.49760E-03 1.51080E-03 561480 + 776 561490 Ba-149 3.30250E-04 3.34000E-04 561490 + 777 561500 Ba-150 8.78810E-05 8.78820E-05 561500 + 778 561510 Ba-151 7.35220E-06 7.35220E-06 561510 + 779 561520 Ba-152 8.33020E-09 8.33020E-09 561520 + 780 561530 Ba-153 1.05690E-10 1.05690E-10 561530 + 781 571380 La-138 2.78990E-06 2.78990E-06 57138.82c + 782 571390 La-139 1.18730E-05 4.92930E-02 57139.82c + 783 571400 La-140 4.32190E-05 4.64810E-02 57140.82c + 784 571410 La-141 2.52430E-04 4.41720E-02 571410 + 785 571420 La-142 6.08210E-04 4.20580E-02 571420 + 786 571430 La-143 2.43100E-03 3.86830E-02 571430 + 787 571440 La-144 4.53790E-03 3.57030E-02 571440 + 788 571450 La-145 9.45170E-03 2.84260E-02 571450 + 789 571460 La-146 2.13760E-03 1.47610E-02 571460 + 790 571461 La-146m 7.47810E-03 7.47810E-03 571461 + 791 571470 La-147 1.06270E-02 1.51510E-02 571470 + 792 571480 La-148 5.06400E-03 6.57020E-03 571480 + 793 571490 La-149 3.97320E-03 4.30580E-03 571490 + 794 571500 La-150 1.42080E-03 1.50870E-03 571500 + 795 571510 La-151 4.54410E-04 4.61760E-04 571510 + 796 571520 La-152 9.36750E-05 9.36830E-05 571520 + 797 571530 La-153 7.12400E-06 7.12410E-06 571530 + 798 571540 La-154 1.53950E-06 1.53950E-06 571540 + 799 571550 La-155 4.56570E-10 4.56570E-10 571550 + 800 581410 Ce-141 2.14350E-06 4.41740E-02 58141.82c + 801 581420 Ce-142 2.63460E-05 4.20850E-02 58142.82c + 802 581430 Ce-143 8.66660E-05 3.87700E-02 58143.82c + 803 581440 Ce-144 4.43850E-04 3.61470E-02 58144.82c + 804 581450 Ce-145 1.36030E-03 2.97860E-02 581450 + 805 581460 Ce-146 3.92920E-03 2.61690E-02 581460 + 806 581470 Ce-147 6.08890E-03 2.12400E-02 581470 + 807 581480 Ce-148 7.64940E-03 1.42800E-02 581480 + 808 581490 Ce-149 8.14670E-03 1.24330E-02 581490 + 809 581500 Ce-150 7.67420E-03 9.14210E-03 581500 + 810 581510 Ce-151 3.56750E-03 4.03490E-03 581510 + 811 581520 Ce-152 1.88340E-03 1.97140E-03 581520 + 812 581530 Ce-153 4.28390E-04 4.35510E-04 581530 + 813 581540 Ce-154 1.35200E-04 1.36740E-04 581540 + 814 581550 Ce-155 1.21130E-05 1.21140E-05 581550 + 815 581560 Ce-156 6.80990E-08 6.80990E-08 581560 + 816 581570 Ce-157 1.09700E-09 1.09700E-09 581570 + 817 591430 Pr-143 1.31290E-09 3.87700E-02 59143.82c + 818 591440 Pr-144 1.62380E-09 3.61470E-02 591440 + 819 591441 Pr-144m 2.62760E-08 4.98830E-04 591441 + 820 591450 Pr-145 5.97860E-06 2.97920E-02 591450 + 821 591460 Pr-146 4.30910E-05 2.62120E-02 591460 + 822 591470 Pr-147 2.28640E-04 2.14690E-02 591470 + 823 591480 Pr-148 5.41760E-05 1.43340E-02 591480 + 824 591481 Pr-148m 4.24830E-04 4.24830E-04 591481 + 825 591490 Pr-149 1.51800E-03 1.39510E-02 591490 + 826 591500 Pr-150 2.46790E-03 1.16100E-02 591500 + 827 591510 Pr-151 3.49480E-03 7.52970E-03 591510 + 828 591520 Pr-152 2.73520E-03 4.70930E-03 591520 + 829 591530 Pr-153 1.83450E-03 2.26820E-03 591530 + 830 591540 Pr-154 8.30550E-04 9.66420E-04 591540 + 831 591550 Pr-155 3.27510E-04 3.39620E-04 591550 + 832 591560 Pr-156 7.85680E-05 7.86360E-05 591560 + 833 591570 Pr-157 1.50510E-05 1.50520E-05 591570 + 834 591580 Pr-158 8.92130E-08 8.92130E-08 591580 + 835 591590 Pr-159 3.91790E-09 3.91790E-09 591590 + 836 601460 Nd-146 1.26470E-06 2.62130E-02 60146.82c + 837 601470 Nd-147 3.70450E-06 2.14720E-02 60147.82c + 838 601480 Nd-148 2.16150E-05 1.47810E-02 60148.82c + 839 601490 Nd-149 8.66460E-05 1.40380E-02 601490 + 840 601500 Nd-150 3.69540E-04 1.19800E-02 60150.82c + 841 601510 Nd-151 7.93930E-04 8.32370E-03 601510 + 842 601520 Nd-152 1.64520E-03 6.35450E-03 601520 + 843 601530 Nd-153 1.61750E-03 3.88570E-03 601530 + 844 601540 Nd-154 1.86030E-03 2.82670E-03 601540 + 845 601550 Nd-155 1.08310E-03 1.42490E-03 601550 + 846 601560 Nd-156 6.60640E-04 7.38100E-04 601560 + 847 601570 Nd-157 2.14640E-04 2.28730E-04 601570 + 848 601580 Nd-158 7.90250E-05 7.91140E-05 601580 + 849 601590 Nd-159 1.26080E-05 1.26120E-05 601590 + 850 601600 Nd-160 1.74410E-07 1.74410E-07 601600 + 851 601610 Nd-161 5.89350E-09 5.89350E-09 601610 + 852 611490 Pm-149 7.96110E-09 1.40380E-02 61149.82c + 853 611500 Pm-150 1.44390E-06 1.44390E-06 611500 + 854 611510 Pm-151 1.02760E-05 8.33390E-03 61151.82c + 855 611520 Pm-152 4.15810E-06 6.35870E-03 611520 + 856 611521 Pm-152m 1.00370E-05 1.00370E-05 611521 + 857 611522 Pm-152m 2.25700E-05 2.25700E-05 611522 + 858 611530 Pm-153 1.31520E-04 4.01720E-03 611530 + 859 611540 Pm-154 1.02100E-04 2.92880E-03 611540 + 860 611541 Pm-154m 1.02100E-04 1.02100E-04 611541 + 861 611550 Pm-155 3.10320E-04 1.73520E-03 611550 + 862 611560 Pm-156 3.23020E-04 1.06110E-03 611560 + 863 611570 Pm-157 2.95190E-04 5.23920E-04 611570 + 864 611580 Pm-158 2.06200E-04 2.85340E-04 611580 + 865 611590 Pm-159 1.14330E-04 1.26910E-04 611590 + 866 611600 Pm-160 2.70420E-05 2.72150E-05 611600 + 867 611610 Pm-161 4.79760E-06 4.80350E-06 611610 + 868 611620 Pm-162 1.49960E-06 1.49960E-06 611620 + 869 611630 Pm-163 1.47270E-08 1.47270E-08 611630 + 870 621510 Sm-151 4.45320E-10 8.33390E-03 62151.82c + 871 621520 Sm-152 1.78500E-08 6.39130E-03 62152.82c + 872 621530 Sm-153 5.09020E-07 4.02000E-03 62153.82c + 873 621531 Sm-153m 2.33630E-06 2.33630E-06 621531 + 874 621540 Sm-154 1.97770E-05 3.05070E-03 62154.82c + 875 621550 Sm-155 2.53280E-05 1.76050E-03 621550 + 876 621560 Sm-156 8.50640E-05 1.14620E-03 621560 + 877 621570 Sm-157 1.09840E-04 6.33770E-04 621570 + 878 621580 Sm-158 1.43110E-04 4.28470E-04 621580 + 879 621590 Sm-159 1.07250E-04 2.34210E-04 621590 + 880 621600 Sm-160 7.54270E-05 1.02570E-04 621600 + 881 621610 Sm-161 4.62660E-05 5.10700E-05 621610 + 882 621620 Sm-162 1.34930E-05 1.49930E-05 621620 + 883 621630 Sm-163 9.76920E-06 9.78390E-06 621630 + 884 621640 Sm-164 1.75920E-06 1.75920E-06 621640 + 885 621650 Sm-165 2.36220E-08 2.36220E-08 621650 + 886 631540 Eu-154 2.18370E-10 6.36650E-10 63154.82c + 887 631541 Eu-154m 4.18280E-10 4.18280E-10 631541 + 888 631550 Eu-155 1.71220E-08 1.76050E-03 63155.82c + 889 631560 Eu-156 1.59610E-07 1.14630E-03 63156.82c + 890 631570 Eu-157 2.72080E-06 6.36490E-04 63157.82c + 891 631580 Eu-158 8.03560E-06 4.36510E-04 631580 + 892 631590 Eu-159 2.21440E-05 2.56360E-04 631590 + 893 631600 Eu-160 1.32390E-05 1.15810E-04 631600 + 894 631610 Eu-161 2.70860E-05 7.81550E-05 631610 + 895 631620 Eu-162 1.94700E-05 3.44630E-05 631620 + 896 631630 Eu-163 1.46450E-05 2.44290E-05 631630 + 897 631640 Eu-164 1.40760E-05 1.58350E-05 631640 + 898 631650 Eu-165 5.76350E-06 5.78710E-06 631650 + 899 631660 Eu-166 1.33260E-07 1.33260E-07 631660 + 900 631670 Eu-167 5.58280E-08 5.58280E-08 631670 + 901 641560 Gd-156 4.17020E-11 1.14630E-03 64156.82c + 902 641570 Gd-157 6.91940E-10 6.36490E-04 64157.82c + 903 641580 Gd-158 1.80060E-08 4.36530E-04 64158.82c + 904 641590 Gd-159 1.39210E-06 2.57750E-04 641590 + 905 641600 Gd-160 5.52450E-06 1.21330E-04 64160.82c + 906 641610 Gd-161 3.19040E-06 8.13460E-05 641610 + 907 641620 Gd-162 1.49640E-05 4.94270E-05 641620 + 908 641630 Gd-163 8.13190E-06 3.25610E-05 641630 + 909 641640 Gd-164 7.03420E-06 2.28690E-05 641640 + 910 641650 Gd-165 5.76170E-06 1.15490E-05 641650 + 911 641660 Gd-166 4.48250E-06 4.61580E-06 641660 + 912 641670 Gd-167 4.87320E-06 4.92900E-06 641670 + 913 641680 Gd-168 1.16370E-07 1.16370E-07 641680 + 914 641690 Gd-169 2.19140E-08 2.19140E-08 641690 + 915 651590 Tb-159 4.28670E-11 2.57750E-04 65159.82c + 916 651600 Tb-160 4.91560E-10 4.91560E-10 65160.82c + 917 651610 Tb-161 1.00660E-08 8.13560E-05 651610 + 918 651620 Tb-162 5.83400E-08 4.94850E-05 651620 + 919 651630 Tb-163 4.43550E-07 3.30040E-05 651630 + 920 651640 Tb-164 1.75870E-06 2.46280E-05 651640 + 921 651650 Tb-165 3.84030E-06 1.53890E-05 651650 + 922 651660 Tb-166 1.57310E-06 6.18890E-06 651660 + 923 651670 Tb-167 3.24810E-06 8.17710E-06 651670 + 924 651680 Tb-168 1.07030E-06 1.18670E-06 651680 + 925 651690 Tb-169 5.78220E-07 6.00130E-07 651690 + 926 651700 Tb-170 9.64450E-08 9.64450E-08 651700 + 927 651710 Tb-171 2.51710E-08 2.51710E-08 651710 + 928 661620 Dy-162 4.06860E-11 4.94850E-05 66162.82c + 929 661630 Dy-163 5.61190E-10 3.30050E-05 66163.82c + 930 661640 Dy-164 1.06150E-08 2.46390E-05 66164.82c + 931 661650 Dy-165 4.76900E-08 1.54410E-05 661650 + 932 661651 Dy-165m 3.97290E-09 3.97290E-09 661651 + 933 661660 Dy-166 1.43040E-07 6.33190E-06 661660 + 934 661670 Dy-167 7.88100E-07 8.96520E-06 661670 + 935 661680 Dy-168 3.98680E-07 1.58530E-06 661680 + 936 661690 Dy-169 6.25580E-07 1.22570E-06 661690 + 937 661700 Dy-170 5.72080E-07 6.68520E-07 661700 + 938 661710 Dy-171 2.21900E-07 2.47070E-07 661710 + 939 661720 Dy-172 1.05310E-07 1.05310E-07 661720 + 940 661730 Dy-173 1.53680E-08 1.53680E-08 661730 + 941 671640 Ho-164 2.12030E-13 1.16950E-12 671640 + 942 671650 Ho-165 4.85710E-11 1.54410E-05 67165.82c + 943 671660 Ho-166 4.35680E-11 6.33190E-06 671660 + 944 671661 Ho-166m 1.96740E-10 1.96740E-10 671661 + 945 671670 Ho-167 8.87750E-09 8.97410E-06 671670 + 946 671680 Ho-168 1.93800E-09 1.59280E-06 671680 + 947 671681 Ho-168m 5.53870E-09 5.53870E-09 671681 + 948 671690 Ho-169 7.12830E-08 1.29700E-06 671690 + 949 671700 Ho-170 7.92990E-08 7.92990E-08 671700 + 950 671701 Ho-170m 1.75610E-08 6.86090E-07 671701 + 951 671710 Ho-171 2.05950E-07 4.53020E-07 671710 + 952 671720 Ho-172 1.37340E-07 2.42650E-07 671720 + 953 671730 Ho-173 1.11580E-07 1.26950E-07 671730 + 954 671740 Ho-174 3.32900E-08 3.32900E-08 671740 + 955 671750 Ho-175 1.38720E-08 1.38720E-08 671750 + 956 681670 Er-167 2.40110E-12 8.97410E-06 68167.82c + 957 681671 Er-167m 2.00020E-13 1.07230E-06 681671 + 958 681680 Er-168 1.49330E-11 1.59280E-06 68168.82c + 959 681690 Er-169 2.52550E-10 1.29720E-06 681690 + 960 681700 Er-170 2.26360E-09 7.67650E-07 68170.82c + 961 681710 Er-171 7.84160E-09 4.60860E-07 681710 + 962 681720 Er-172 3.10010E-08 2.73650E-07 681720 + 963 681730 Er-173 3.66360E-08 1.63580E-07 681730 + 964 681740 Er-174 5.93510E-08 9.26410E-08 681740 + 965 681750 Er-175 3.49900E-08 4.88620E-08 681750 + 966 681760 Er-176 2.35810E-08 2.35810E-08 681760 + 967 681770 Er-177 6.18280E-09 6.18280E-09 681770 + 968 691710 Tm-171 2.08420E-11 4.60880E-07 691710 + 969 691720 Tm-172 1.44160E-10 2.73790E-07 691720 + 970 691730 Tm-173 1.10310E-09 1.64690E-07 691730 + 971 691740 Tm-174 2.84440E-09 9.54850E-08 691740 + 972 691750 Tm-175 9.70320E-09 5.85650E-08 691750 + 973 691760 Tm-176 9.34860E-09 3.29300E-08 691760 + 974 691770 Tm-177 1.32710E-08 1.94540E-08 691770 + 975 691780 Tm-178 6.69700E-09 6.69700E-09 691780 + 976 691790 Tm-179 3.99180E-09 3.99180E-09 691790 + 977 701740 Yb-174 1.59800E-11 9.55010E-08 701740 + 978 701750 Yb-175 8.66960E-11 5.86590E-08 701750 + 979 701751 Yb-175m 7.22230E-12 4.51020E-08 701751 + 980 701760 Yb-176 1.27570E-10 3.18120E-08 701760 + 981 701761 Yb-176m 4.46280E-10 1.69110E-08 701761 + 982 701770 Yb-177 1.12410E-09 2.07190E-08 701770 + 983 701771 Yb-177m 1.41210E-10 1.95950E-08 701771 + 984 701780 Yb-178 3.61240E-09 1.03090E-08 701780 + 985 701790 Yb-179 3.04150E-09 7.03330E-09 701790 + 986 701800 Yb-180 3.26900E-09 3.26900E-09 701800 + 987 701810 Yb-181 1.45630E-09 1.45630E-09 701810 + 988 711770 Lu-177 4.75400E-12 2.07250E-08 711770 + 989 711771 Lu-177m 3.96060E-12 4.28150E-12 711771 + 990 711780 Lu-178 1.36640E-11 1.03230E-08 711780 + 991 711781 Lu-178m 3.15520E-11 3.15520E-11 711781 + 992 711790 Lu-179 2.17850E-10 7.26930E-09 711790 + 993 711791 Lu-179m 1.81480E-11 7.05150E-09 711791 + 994 711800 Lu-180 7.41930E-11 1.86380E-09 711800 + 995 711801 Lu-180m 7.41930E-11 3.34320E-09 711801 + 996 711802 Lu-180m 2.36000E-10 2.36000E-10 711802 + 997 711810 Lu-181 9.50540E-10 2.40680E-09 711810 + 998 711820 Lu-182 7.01340E-10 7.01340E-10 711820 + 999 711830 Lu-183 6.64110E-10 6.64110E-10 711830 + 1000 711840 Lu-184 2.34400E-10 2.34400E-10 711840 + 1001 721800 Hf-180 1.31930E-12 3.65890E-09 72180.82c + 1002 721801 Hf-180m 4.61560E-12 1.22610E-10 721801 + 1003 721810 Hf-181 2.43500E-11 2.43120E-09 721810 + 1004 721820 Hf-182 2.41710E-11 7.61030E-10 721820 + 1005 721821 Hf-182m 8.45590E-11 8.45590E-11 721821 + 1006 721830 Hf-183 1.52430E-10 8.16540E-10 721830 + 1007 721840 Hf-184 6.54300E-11 1.82630E-10 721840 + 1008 721841 Hf-184m 2.28900E-10 3.46100E-10 721841 + 1009 721850 Hf-185 1.91990E-10 1.91990E-10 721850 + 1010 721860 Hf-186 1.45910E-10 1.45910E-10 721860 + 1011 721870 Hf-187 4.53520E-11 4.53520E-11 721870 + 1012 721880 Hf-188 1.82900E-11 1.82900E-11 721880 + 1013 731830 Ta-183 3.05360E-12 8.19590E-10 731830 + 1014 731840 Ta-184 9.57130E-12 5.38300E-10 731840 + 1015 731850 Ta-185 1.72310E-11 2.28860E-10 731850 + 1016 731851 Ta-185m 1.96340E-11 1.96340E-11 731851 + 1017 731860 Ta-186 4.06260E-11 1.86540E-10 731860 + 1018 731870 Ta-187 6.84990E-11 1.13850E-10 731870 + 1019 731880 Ta-188 3.91530E-11 5.74430E-11 731880 + 1020 731890 Ta-189 2.62850E-11 2.62850E-11 731890 + 1021 731900 Ta-190 6.16300E-12 6.16300E-12 731900 + 1022 741860 W-186 9.23110E-13 1.88210E-10 74186.82c + 1023 741870 W-187 4.46970E-12 1.18320E-10 741870 + 1024 741880 W-188 1.47260E-11 7.21690E-11 741880 + 1025 741890 W-189 1.41000E-11 4.03850E-11 741890 + 1026 741900 W-190 5.41060E-12 2.40670E-11 741900 + 1027 741901 W-190m 1.24930E-11 1.24930E-11 741901 + 1028 741910 W-191 9.04790E-12 9.04790E-12 741910 + 1029 741920 W-192 5.25560E-12 5.25560E-12 741920 + 1030 751900 Re-190 3.23000E-13 2.49050E-11 751900 + 1031 751901 Re-190m 1.13000E-12 1.13000E-12 751901 + 1032 751910 Re-191 4.14040E-12 1.31880E-11 751910 + 1033 751920 Re-192 3.39230E-12 8.64790E-12 751920 + 1034 751930 Re-193 3.79010E-12 3.79010E-12 751930 + 1035 751940 Re-194 1.56850E-12 1.56850E-12 751940 + 1036 761940 Os-194 1.38560E-12 2.95410E-12 761940 + 1037 761950 Os-195 1.00010E-12 1.00010E-12 761950 + + Nuclide 93235.82c -- neptunium 235 (Np-235) is using NFY data from Th-232 + + Nuclide 93236.82c -- neptunium 236 (Np-236) is using NFY data from U-235 + + Nuclide 93237.82c -- neptunium 237 (Np-237) + + Neutron-induced fission: + + Interpolation region : 1 / 2 + Interpolation energy : 2.53000E-08 MeV + Number of products : 891 / 976 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 3.25860E-05 3.25860E-05 1001.82c + 2 10020 H-2 9.95850E-06 9.95850E-06 1002.82c + 3 10030 H-3 1.25000E-04 1.25000E-04 1003.82c + 4 20040 He-4 2.06000E-03 2.06000E-03 2004.82c + 5 230560 V-56 1.99070E-12 1.99070E-12 230560 + 6 230570 V-57 4.37760E-12 4.37760E-12 230570 + 7 230580 V-58 4.06940E-12 4.06940E-12 230580 + 8 230590 V-59 3.90360E-12 3.90360E-12 230590 + 9 230600 V-60 1.29800E-12 1.29800E-12 230600 + 10 240570 Cr-57 2.24330E-12 9.85890E-12 240570 + 11 240580 Cr-58 1.02530E-11 1.10670E-11 240580 + 12 240590 Cr-59 2.15620E-11 2.54660E-11 240590 + 13 240600 Cr-60 3.98390E-11 4.11370E-11 240600 + 14 240610 Cr-61 3.10710E-11 3.10710E-11 240610 + 15 240620 Cr-62 2.31390E-11 2.31390E-11 240620 + 16 240630 Cr-63 6.05160E-12 6.05160E-12 240630 + 17 240640 Cr-64 1.27300E-12 1.27300E-12 240640 + 18 250590 Mn-59 6.82640E-12 3.22920E-11 250590 + 19 250600 Mn-60 2.72950E-12 4.66540E-11 250600 + 20 250601 Mn-60m 2.42410E-11 2.42410E-11 250601 + 21 250610 Mn-61 1.04210E-10 1.35280E-10 250610 + 22 250620 Mn-62 1.49330E-10 1.60900E-10 250620 + 23 250621 Mn-62m 2.68080E-11 3.83780E-11 250621 + 24 250630 Mn-63 2.67300E-10 2.73350E-10 250630 + 25 250640 Mn-64 1.53270E-10 1.54540E-10 250640 + 26 250650 Mn-65 9.23480E-11 9.23480E-11 250650 + 27 250660 Mn-66 1.99490E-11 1.99490E-11 250660 + 28 250670 Mn-67 3.30310E-12 3.30310E-12 250670 + 29 260600 Fe-60 1.49460E-12 6.96030E-11 260600 + 30 260610 Fe-61 1.39340E-11 1.49220E-10 260610 + 31 260620 Fe-62 1.20890E-10 3.20170E-10 260620 + 32 260630 Fe-63 3.88080E-10 6.61430E-10 260630 + 33 260640 Fe-64 1.12630E-09 1.28080E-09 260640 + 34 260650 Fe-65 1.60450E-09 1.69680E-09 260650 + 35 260660 Fe-66 2.09690E-09 2.11690E-09 260660 + 36 260670 Fe-67 9.77190E-10 9.80490E-10 260670 + 37 260680 Fe-68 4.15810E-10 4.15810E-10 260680 + 38 260690 Fe-69 7.00600E-11 7.00600E-11 260690 + 39 260700 Fe-70 8.93190E-12 8.93190E-12 260700 + 40 270620 Co-62 4.80160E-13 3.20660E-10 270620 + 41 270621 Co-62m 1.12460E-12 1.12460E-12 270621 + 42 270630 Co-63 3.04940E-11 6.91930E-10 270630 + 43 270640 Co-64 2.04660E-10 1.48550E-09 270640 + 44 270650 Co-65 1.45670E-09 3.15360E-09 270650 + 45 270660 Co-66 4.04270E-09 6.15950E-09 270660 + 46 270670 Co-67 9.85060E-09 1.08310E-08 270670 + 47 270680 Co-68 5.49840E-09 8.13410E-09 270680 + 48 270681 Co-68m 4.85060E-09 5.27130E-09 270681 + 49 270690 Co-69 1.09570E-08 1.10220E-08 270690 + 50 270700 Co-70 2.02080E-09 2.02080E-09 270700 + 51 270701 Co-70m 2.02080E-09 2.02970E-09 270701 + 52 270710 Co-71 1.38930E-09 1.38930E-09 270710 + 53 270720 Co-72 2.15740E-10 2.15740E-10 270720 + 54 270730 Co-73 1.23760E-11 1.23760E-11 270730 + 55 280640 Ni-64 2.39510E-12 1.48790E-09 28064.82c + 56 280650 Ni-65 4.55960E-11 3.19910E-09 280650 + 57 280660 Ni-66 7.17620E-10 6.87720E-09 280660 + 58 280670 Ni-67 3.89220E-09 1.47230E-08 280670 + 59 280680 Ni-68 2.01390E-08 3.10190E-08 280680 + 60 280690 Ni-69 2.30560E-08 3.39680E-08 280690 + 61 280691 Ni-69m 2.30560E-08 2.30560E-08 280691 + 62 280700 Ni-70 9.25420E-08 9.65920E-08 280700 + 63 280710 Ni-71 8.19390E-08 8.33280E-08 280710 + 64 280720 Ni-72 8.46870E-07 8.47090E-07 280720 + 65 280730 Ni-73 1.40170E-08 1.40290E-08 280730 + 66 280740 Ni-74 6.23070E-09 6.23070E-09 280740 + 67 280750 Ni-75 7.97520E-11 7.97520E-11 280750 + 68 280760 Ni-76 4.95340E-11 4.95340E-11 280760 + 69 290660 Cu-66 1.91740E-12 6.87910E-09 290660 + 70 290670 Cu-67 6.74910E-11 1.47910E-08 290670 + 71 290680 Cu-68 2.68720E-10 3.18160E-08 290680 + 72 290681 Cu-68m 6.29400E-10 6.29400E-10 290681 + 73 290690 Cu-69 1.11720E-08 6.81970E-08 290690 + 74 290700 Cu-70 3.68660E-09 2.67290E-08 290700 + 75 290701 Cu-70m 4.10710E-08 4.60850E-08 290701 + 76 290702 Cu-70m 3.68660E-09 1.00280E-07 290702 + 77 290710 Cu-71 2.11320E-07 2.94650E-07 290710 + 78 290720 Cu-72 4.75140E-07 1.32220E-06 290720 + 79 290730 Cu-73 1.01810E-06 1.03210E-06 290730 + 80 290740 Cu-74 5.44760E-07 5.50990E-07 290740 + 81 290750 Cu-75 4.66030E-08 4.66820E-08 290750 + 82 290760 Cu-76 4.37590E-08 4.37840E-08 290760 + 83 290761 Cu-76m 4.37590E-08 4.37840E-08 290761 + 84 290770 Cu-77 7.47750E-09 7.47750E-09 290770 + 85 290780 Cu-78 9.43560E-10 9.43560E-10 290780 + 86 290790 Cu-79 5.93740E-11 5.93740E-11 290790 + 87 300680 Zn-68 2.03350E-12 3.19190E-08 300680 + 88 300690 Zn-69 1.37290E-11 6.82700E-08 300690 + 89 300691 Zn-69m 5.93740E-11 5.93740E-11 300691 + 90 300700 Zn-70 1.98930E-09 1.47030E-07 300700 + 91 300710 Zn-71 4.01740E-09 2.98670E-07 300710 + 92 300711 Zn-71m 1.73750E-08 1.73750E-08 300711 + 93 300720 Zn-72 2.51150E-07 1.57340E-06 300720 + 94 300730 Zn-73 5.07840E-08 1.34900E-06 300730 + 95 300731 Zn-73m 6.94240E-08 2.66070E-07 300731 + 96 300732 Zn-73m 3.93280E-07 3.93280E-07 300732 + 97 300740 Zn-74 3.74110E-06 4.29370E-06 300740 + 98 300750 Zn-75 1.09450E-06 1.14090E-06 300750 + 99 300760 Zn-76 4.69210E-06 4.77830E-06 300760 + 100 300770 Zn-77 2.71920E-06 2.93450E-06 300770 + 101 300771 Zn-77m 4.15690E-07 4.15690E-07 300771 + 102 300780 Zn-78 7.75270E-06 7.75370E-06 300780 + 103 300790 Zn-79 4.62720E-06 4.62720E-06 300790 + 104 300800 Zn-80 4.44450E-08 4.44450E-08 300800 + 105 300810 Zn-81 2.18920E-09 2.18920E-09 300810 + 106 300820 Zn-82 1.03540E-10 1.03540E-10 300820 + 107 310710 Ga-71 7.40370E-11 3.16110E-07 310710 + 108 310720 Ga-72 2.19660E-09 1.57580E-06 310720 + 109 310721 Ga-72m 2.47320E-10 5.26730E-08 310721 + 110 310730 Ga-73 3.01850E-08 1.57580E-06 310730 + 111 310740 Ga-74 2.12090E-07 3.59140E-06 310740 + 112 310741 Ga-74m 2.12090E-07 4.50580E-06 310741 + 113 310750 Ga-75 4.24910E-07 1.56580E-06 310750 + 114 310760 Ga-76 9.38450E-06 1.41630E-05 310760 + 115 310770 Ga-77 7.83700E-06 1.09790E-05 310770 + 116 310780 Ga-78 1.08540E-05 1.86680E-05 310780 + 117 310790 Ga-79 2.62180E-05 3.07850E-05 310790 + 118 310800 Ga-80 1.65630E-05 1.66080E-05 310800 + 119 310810 Ga-81 7.60550E-06 7.60750E-06 310810 + 120 310820 Ga-82 3.00230E-06 3.00240E-06 310820 + 121 310830 Ga-83 8.04970E-08 8.04970E-08 310830 + 122 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9.44490E-06 320850 + 142 320860 Ge-86 8.63610E-08 8.63610E-08 320860 + 143 320870 Ge-87 1.58350E-09 1.58350E-09 320870 + 144 330750 As-75 1.48540E-12 1.57560E-06 33075.82c + 145 330751 As-75m 4.85990E-12 2.62080E-11 330751 + 146 330760 As-76 2.58470E-09 2.58470E-09 330760 + 147 330770 As-77 4.69640E-08 1.72960E-05 330770 + 148 330780 As-78 1.55070E-06 6.52190E-05 330780 + 149 330790 As-79 1.23400E-05 1.46450E-04 330790 + 150 330800 As-80 6.62760E-05 3.41200E-04 330800 + 151 330810 As-81 2.54040E-04 5.95440E-04 330810 + 152 330820 As-82 1.61830E-04 5.31880E-04 330820 + 153 330821 As-82m 4.88360E-04 4.88360E-04 330821 + 154 330830 As-83 1.19450E-03 1.34780E-03 330830 + 155 330840 As-84 4.48800E-04 4.61960E-04 330840 + 156 330841 As-84m 4.48800E-04 4.61960E-04 330841 + 157 330850 As-85 7.30700E-04 7.38820E-04 330850 + 158 330860 As-86 1.82340E-04 1.82430E-04 330860 + 159 330870 As-87 5.65910E-05 5.65930E-05 330870 + 160 330880 As-88 5.72980E-06 5.72980E-06 330880 + 161 330890 As-89 2.78060E-08 2.78060E-08 330890 + 162 340770 Se-77 1.43330E-12 1.72960E-05 34077.82c + 163 340771 Se-77m 9.37570E-12 9.37570E-12 340771 + 164 340780 Se-78 2.06720E-09 6.52210E-05 34078.82c + 165 340790 Se-79 7.31160E-08 1.46450E-04 34079.82c + 166 340791 Se-79m 1.11770E-08 1.42990E-04 340791 + 167 340800 Se-80 7.53110E-06 3.48730E-04 34080.82c + 168 340810 Se-81 1.03080E-05 6.73130E-04 340810 + 169 340811 Se-81m 6.74300E-05 8.88050E-05 340811 + 170 340820 Se-82 4.43670E-04 1.46390E-03 34082.82c + 171 340830 Se-83 1.37400E-03 1.85990E-03 340830 + 172 340831 Se-83m 3.17700E-04 1.18100E-03 340831 + 173 340840 Se-84 4.79940E-03 5.88460E-03 340840 + 174 340850 Se-85 6.54410E-03 7.18060E-03 340850 + 175 340860 Se-86 6.16820E-03 6.29910E-03 340860 + 176 340870 Se-87 3.43540E-03 3.48330E-03 340870 + 177 340880 Se-88 1.36300E-03 1.36870E-03 340880 + 178 340890 Se-89 3.17830E-04 3.17860E-04 340890 + 179 340900 Se-90 7.00180E-05 7.00180E-05 340900 + 180 340910 Se-91 5.22120E-06 5.22120E-06 340910 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2.83610E-05 350930 + 201 350940 Br-94 6.54780E-08 6.54780E-08 350940 + 202 350950 Br-95 1.84220E-09 1.84220E-09 350950 + 203 360820 Kr-82 7.24780E-10 6.00710E-06 36082.82c + 204 360830 Kr-83 4.39040E-08 3.08920E-03 36083.82c + 205 360831 Kr-83m 1.01520E-08 3.08650E-03 360831 + 206 360840 Kr-84 1.26190E-05 6.28970E-03 36084.82c + 207 360850 Kr-85 1.63350E-04 2.30940E-03 36085.82c + 208 360851 Kr-85m 3.77700E-05 9.95300E-03 360851 + 209 360860 Kr-86 2.00800E-03 1.43140E-02 36086.82c + 210 360870 Kr-87 5.67070E-03 1.88160E-02 360870 + 211 360880 Kr-88 1.34600E-02 2.22250E-02 360880 + 212 360890 Kr-89 2.03940E-02 2.61890E-02 360890 + 213 360900 Kr-90 2.37150E-02 2.58280E-02 360900 + 214 360910 Kr-91 1.61080E-02 1.69580E-02 360910 + 215 360920 Kr-92 9.25320E-03 9.37060E-03 360920 + 216 360930 Kr-93 3.16980E-03 3.17890E-03 360930 + 217 360940 Kr-94 9.06970E-04 9.06990E-04 360940 + 218 360950 Kr-95 1.44570E-04 1.44570E-04 360950 + 219 360960 Kr-96 1.34600E-05 1.34600E-05 360960 + 220 360970 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4.21790E-03 391000 + 280 391001 Y-100m 3.94670E-03 3.94700E-03 391001 + 281 391010 Y-101 3.05660E-03 3.08120E-03 391010 + 282 391020 Y-102 2.50590E-04 2.50610E-04 391020 + 283 391021 Y-102m 2.50590E-04 2.50610E-04 391021 + 284 391030 Y-103 9.36430E-05 9.36430E-05 391030 + 285 391040 Y-104 4.65020E-06 4.65020E-06 391040 + 286 391050 Y-105 1.63420E-09 1.63420E-09 391050 + 287 400920 Zr-92 3.30530E-06 4.27550E-02 40092.82c + 288 400930 Zr-93 3.72360E-05 5.17650E-02 40093.82c + 289 400940 Zr-94 2.83550E-04 5.40350E-02 40094.82c + 290 400950 Zr-95 1.28550E-03 5.93640E-02 40095.82c + 291 400960 Zr-96 6.25380E-03 6.04720E-02 40096.82c + 292 400970 Zr-97 1.32130E-02 5.97320E-02 400970 + 293 400980 Zr-98 3.27340E-02 6.55020E-02 400980 + 294 400990 Zr-99 3.89720E-02 5.98120E-02 400990 + 295 401000 Zr-100 4.85660E-02 5.66920E-02 401000 + 296 401010 Zr-101 3.06770E-02 3.37830E-02 401010 + 297 401020 Zr-102 1.73570E-02 1.78410E-02 401020 + 298 401030 Zr-103 4.80360E-03 4.89020E-03 401030 + 299 401040 Zr-104 9.72100E-04 9.76340E-04 401040 + 300 401050 Zr-105 1.38430E-04 1.38430E-04 401050 + 301 401060 Zr-106 1.23470E-05 1.23470E-05 401060 + 302 401070 Zr-107 4.24080E-09 4.24080E-09 401070 + 303 410950 Nb-95 2.16340E-06 5.93310E-02 41095.82c + 304 410951 Nb-95m 5.00220E-07 6.41840E-04 410951 + 305 410960 Nb-96 3.94760E-05 3.94760E-05 410960 + 306 410970 Nb-97 2.86590E-04 6.00840E-02 410970 + 307 410971 Nb-97m 6.62650E-05 5.68400E-02 410971 + 308 410980 Nb-98 4.00830E-04 6.59030E-02 410980 + 309 410981 Nb-98m 1.20960E-03 1.20960E-03 410981 + 310 410990 Nb-99 5.46280E-03 4.37300E-02 410990 + 311 410991 Nb-99m 1.26310E-03 2.32740E-02 410991 + 312 411000 Nb-100 2.71480E-03 5.94070E-02 411000 + 313 411001 Nb-100m 1.14170E-02 1.14170E-02 411001 + 314 411010 Nb-101 2.94500E-02 6.32330E-02 411010 + 315 411020 Nb-102 1.51680E-02 3.30090E-02 411020 + 316 411021 Nb-102m 1.51680E-02 1.51680E-02 411021 + 317 411030 Nb-103 2.88570E-02 3.37470E-02 411030 + 318 411040 Nb-104 5.62300E-03 6.60130E-03 411040 + 319 411041 Nb-104m 5.62300E-03 5.62300E-03 411041 + 320 411050 Nb-105 4.80150E-03 4.93820E-03 411050 + 321 411060 Nb-106 1.00940E-03 1.02160E-03 411060 + 322 411070 Nb-107 1.82570E-04 1.82570E-04 411070 + 323 411080 Nb-108 8.40220E-06 8.40220E-06 411080 + 324 411090 Nb-109 5.84030E-09 5.84030E-09 411090 + 325 411100 Nb-110 3.07600E-11 3.07600E-11 411100 + 326 420970 Mo-97 4.33290E-06 6.00890E-02 42097.82c + 327 420980 Mo-98 3.63580E-05 6.71490E-02 42098.82c + 328 420990 Mo-99 2.74400E-04 6.68130E-02 42099.82c + 329 421000 Mo-100 1.86180E-03 7.26860E-02 42100.82c + 330 421010 Mo-101 5.63510E-03 6.88680E-02 421010 + 331 421020 Mo-102 1.63500E-02 6.45260E-02 421020 + 332 421030 Mo-103 2.32210E-02 5.69750E-02 421030 + 333 421040 Mo-104 2.34360E-02 3.57370E-02 421040 + 334 421050 Mo-105 1.44070E-02 1.93070E-02 421050 + 335 421060 Mo-106 7.95490E-03 8.94140E-03 421060 + 336 421070 Mo-107 2.03170E-03 2.20380E-03 421070 + 337 421080 Mo-108 5.30680E-04 5.38560E-04 421080 + 338 421090 Mo-109 5.94700E-05 5.94750E-05 421090 + 339 421100 Mo-110 2.35490E-06 2.35490E-06 421100 + 340 421110 Mo-111 2.33700E-06 2.33700E-06 421110 + 341 421120 Mo-112 1.73680E-10 1.73680E-10 421120 + 342 431000 Tc-100 5.22230E-06 5.22230E-06 431000 + 343 431010 Tc-101 5.38060E-05 6.89220E-02 431010 + 344 431020 Tc-102 1.67470E-04 6.46940E-02 431020 + 345 431021 Tc-102m 1.67470E-04 1.67470E-04 431021 + 346 431030 Tc-103 1.63540E-03 5.86100E-02 431030 + 347 431040 Tc-104 3.04140E-03 3.87790E-02 431040 + 348 431050 Tc-105 6.28820E-03 2.55950E-02 431050 + 349 431060 Tc-106 5.62030E-03 1.45620E-02 431060 + 350 431070 Tc-107 4.44550E-03 6.64930E-03 431070 + 351 431080 Tc-108 1.64820E-03 2.18710E-03 431080 + 352 431090 Tc-109 5.88810E-04 6.47970E-04 431090 + 353 431100 Tc-110 1.29690E-04 1.32070E-04 431100 + 354 431110 Tc-111 3.62380E-05 3.85510E-05 431110 + 355 431120 Tc-112 1.04610E-05 1.04610E-05 431120 + 356 431130 Tc-113 1.15050E-06 1.15050E-06 431130 + 357 431140 Tc-114 1.14700E-06 1.14700E-06 431140 + 358 431150 Tc-115 2.02820E-11 2.02820E-11 431150 + 359 441020 Ru-102 4.99970E-06 6.48660E-02 44102.82c + 360 441030 Ru-103 8.74040E-06 5.86400E-02 44103.82c + 361 441031 Ru-103m 2.11010E-05 2.11010E-05 441031 + 362 441040 Ru-104 1.25470E-04 3.89040E-02 44104.82c + 363 441050 Ru-105 3.87140E-04 2.59820E-02 44105.82c + 364 441060 Ru-106 8.59550E-04 1.54210E-02 44106.82c + 365 441070 Ru-107 8.28950E-04 7.47830E-03 441070 + 366 441080 Ru-108 8.85890E-04 3.07350E-03 441080 + 367 441090 Ru-109 4.08960E-04 1.05650E-03 441090 + 368 441100 Ru-110 2.29310E-04 3.61330E-04 441100 + 369 441110 Ru-111 1.10950E-04 1.49660E-04 441110 + 370 441120 Ru-112 7.43580E-05 8.47450E-05 441120 + 371 441130 Ru-113 1.03540E-05 1.66730E-05 441130 + 372 441131 Ru-113m 1.03540E-05 1.03540E-05 441131 + 373 441140 Ru-114 9.17560E-06 1.02480E-05 441140 + 374 441150 Ru-115 2.28310E-06 2.28310E-06 441150 + 375 441160 Ru-116 1.10670E-08 1.10670E-08 441160 + 376 441170 Ru-117 2.75400E-10 2.75400E-10 441170 + 377 441180 Ru-118 6.41160E-12 6.41160E-12 441180 + 378 441200 Ru-120 4.59110E-10 4.59110E-10 441200 + 379 451050 Rh-105 9.92220E-09 2.59830E-02 45105.82c + 380 451051 Rh-105m 1.51680E-09 7.37580E-03 451051 + 381 451060 Rh-106 1.84710E-06 1.54230E-02 451060 + 382 451061 Rh-106m 4.32640E-06 4.32640E-06 451061 + 383 451070 Rh-107 1.34060E-05 7.49170E-03 451070 + 384 451080 Rh-108 8.36430E-06 3.08190E-03 451080 + 385 451081 Rh-108m 2.52410E-05 2.52410E-05 451081 + 386 451090 Rh-109 5.11440E-05 1.10760E-03 451090 + 387 451100 Rh-110 4.01390E-05 4.01470E-04 451100 + 388 451101 Rh-110m 1.07150E-06 1.07150E-06 451101 + 389 451110 Rh-111 7.12820E-05 2.20940E-04 451110 + 390 451120 Rh-112 3.13810E-05 1.16130E-04 451120 + 391 451121 Rh-112m 3.13810E-05 3.13810E-05 451121 + 392 451130 Rh-113 9.20370E-05 1.13890E-04 451130 + 393 451140 Rh-114 3.38320E-05 4.40850E-05 451140 + 394 451141 Rh-114m 3.38320E-05 3.38320E-05 451141 + 395 451150 Rh-115 3.99500E-05 4.22280E-05 451150 + 396 451160 Rh-116 6.96870E-06 6.97960E-06 451160 + 397 451161 Rh-116m 1.63220E-05 1.63220E-05 451161 + 398 451170 Rh-117 1.18850E-05 1.18850E-05 451170 + 399 451180 Rh-118 6.07310E-06 6.07310E-06 451180 + 400 451190 Rh-119 1.23980E-06 1.23980E-06 451190 + 401 451200 Rh-120 7.71810E-07 7.72270E-07 451200 + 402 451210 Rh-121 6.04950E-08 6.04950E-08 451210 + 403 451220 Rh-122 2.34520E-09 2.34520E-09 451220 + 404 461070 Pd-107 7.36420E-11 7.49170E-03 46107.82c + 405 461071 Pd-107m 1.38400E-10 1.38400E-10 461071 + 406 461080 Pd-108 9.04860E-09 3.10710E-03 46108.82c + 407 461090 Pd-109 4.13180E-07 1.10880E-03 461090 + 408 461091 Pd-109m 7.76520E-07 5.54580E-04 461091 + 409 461100 Pd-110 3.53250E-06 4.06070E-04 46110.82c + 410 461110 Pd-111 8.11640E-07 2.22630E-04 461110 + 411 461111 Pd-111m 1.52540E-06 2.40910E-06 461111 + 412 461120 Pd-112 1.16230E-05 1.59130E-04 461120 + 413 461130 Pd-113 8.42560E-06 1.42650E-04 461130 + 414 461131 Pd-113m 2.03400E-05 2.03400E-05 461131 + 415 461140 Pd-114 7.80130E-05 1.55930E-04 461140 + 416 461150 Pd-115 2.73590E-05 6.80600E-05 461150 + 417 461151 Pd-115m 5.14180E-05 5.75490E-05 461151 + 418 461160 Pd-116 1.10630E-04 1.33930E-04 461160 + 419 461170 Pd-117 2.80640E-05 9.28690E-05 461170 + 420 461171 Pd-117m 5.27430E-05 5.27430E-05 461171 + 421 461180 Pd-118 4.25060E-05 4.84020E-05 461180 + 422 461190 Pd-119 1.48770E-05 1.61630E-05 461190 + 423 461200 Pd-120 6.29030E-06 7.02500E-06 461200 + 424 461210 Pd-121 1.28530E-06 1.33760E-06 461210 + 425 461220 Pd-122 3.34060E-06 3.34290E-06 461220 + 426 461230 Pd-123 2.85450E-07 2.85450E-07 461230 + 427 461240 Pd-124 2.32550E-08 2.32550E-08 461240 + 428 471100 Ag-110 2.76100E-11 2.84890E-11 471100 + 429 471101 Ag-110m 6.46690E-11 6.46690E-11 47510.82c + 430 471110 Ag-111 3.93870E-10 2.22170E-04 47111.82c + 431 471111 Ag-111m 2.57650E-09 2.21520E-04 471111 + 432 471120 Ag-112 4.37440E-08 1.59170E-04 471120 + 433 471130 Ag-113 8.96060E-08 9.39410E-05 471130 + 434 471131 Ag-113m 5.86150E-07 1.37190E-04 471131 + 435 471140 Ag-114 4.40700E-07 1.58220E-04 471140 + 436 471141 Ag-114m 1.85340E-06 1.85340E-06 471141 + 437 471150 Ag-115 1.21110E-06 6.75360E-05 471150 + 438 471151 Ag-115m 7.92210E-06 7.92440E-05 471151 + 439 471160 Ag-116 1.28960E-05 1.48640E-04 471160 + 440 471161 Ag-116m 3.02040E-05 3.02040E-05 471161 + 441 471170 Ag-117 1.37150E-05 6.83180E-05 471170 + 442 471171 Ag-117m 8.97150E-05 1.36150E-04 471171 + 443 471180 Ag-118 2.10020E-05 1.01540E-04 471180 + 444 471181 Ag-118m 8.83280E-05 9.52470E-05 471181 + 445 471190 Ag-119 1.29870E-05 2.10680E-05 471190 + 446 471191 Ag-119m 8.49510E-05 9.30330E-05 471191 + 447 471200 Ag-120 2.23610E-05 3.89170E-05 471200 + 448 471201 Ag-120m 3.17300E-05 3.52420E-05 471201 + 449 471210 Ag-121 3.98390E-05 4.11730E-05 471210 + 450 471220 Ag-122 5.39570E-06 8.73860E-06 471220 + 451 471221 Ag-122m 4.86030E-06 4.86030E-06 471221 + 452 471230 Ag-123 1.33100E-06 1.61640E-06 471230 + 453 471240 Ag-124 4.27900E-06 6.22950E-06 471240 + 454 471241 Ag-124m 3.85440E-06 3.85440E-06 471241 + 455 471250 Ag-125 1.38030E-06 1.38030E-06 471250 + 456 471260 Ag-126 2.52990E-07 2.52990E-07 471260 + 457 471270 Ag-127 4.08450E-08 4.08450E-08 471270 + 458 471280 Ag-128 2.16180E-09 2.16180E-09 471280 + 459 481120 Cd-112 5.60270E-12 1.59170E-04 48112.82c + 460 481130 Cd-113 5.13900E-11 1.41710E-04 48113.82c + 461 481131 Cd-113m 1.68130E-10 1.62430E-06 481131 + 462 481140 Cd-114 1.08280E-08 1.58240E-04 48114.82c + 463 481150 Cd-115 3.28770E-08 1.24460E-04 481150 + 464 481151 Cd-115m 1.07560E-07 5.82180E-06 48515.82c + 465 481160 Cd-116 4.65890E-06 1.81690E-04 48116.82c + 466 481170 Cd-117 2.22610E-06 1.55260E-04 481170 + 467 481171 Cd-117m 7.28320E-06 5.05500E-05 481171 + 468 481180 Cd-118 2.30830E-05 1.80810E-04 481180 + 469 481190 Cd-119 1.27120E-05 1.16280E-04 481190 + 470 481191 Cd-119m 3.06900E-05 4.12240E-05 481191 + 471 481200 Cd-120 8.93440E-05 1.50460E-04 481200 + 472 481210 Cd-121 1.69420E-05 5.38130E-05 481210 + 473 481211 Cd-121m 4.09000E-05 4.52020E-05 481211 + 474 481220 Cd-122 9.35870E-05 1.07190E-04 481220 + 475 481230 Cd-123 1.59830E-05 1.73080E-05 481230 + 476 481231 Cd-123m 3.85840E-05 3.88810E-05 481231 + 477 481240 Cd-124 4.20230E-05 5.01730E-05 481240 + 478 481250 Cd-125 1.05120E-05 1.12020E-05 481250 + 479 481251 Cd-125m 2.53770E-05 2.60670E-05 481251 + 480 481260 Cd-126 4.77140E-05 4.79670E-05 481260 + 481 481270 Cd-127 4.98450E-05 4.98860E-05 481270 + 482 481280 Cd-128 3.12550E-05 3.12570E-05 481280 + 483 481290 Cd-129 3.82610E-07 3.82610E-07 481290 + 484 481291 Cd-129m 9.23680E-07 9.23680E-07 481291 + 485 481300 Cd-130 1.32580E-06 1.32580E-06 481300 + 486 481310 Cd-131 2.01000E-09 2.01000E-09 481310 + 487 491150 In-115 1.97670E-11 1.24060E-04 49115.82c + 488 491151 In-115m 4.57070E-12 1.24460E-04 491151 + 489 491160 In-116 3.28750E-10 3.28750E-10 491160 + 490 491161 In-116m 5.03880E-10 9.91920E-10 491161 + 491 491162 In-116m 4.88040E-10 4.88040E-10 491162 + 492 491170 In-117 4.08740E-08 1.30180E-04 491170 + 493 491171 In-117m 9.45100E-09 1.43060E-04 491171 + 494 491180 In-118 3.02340E-07 1.81120E-04 491180 + 495 491181 In-118m 4.63410E-07 9.05960E-07 491181 + 496 491182 In-118m 4.48830E-07 4.48830E-07 491182 + 497 491190 In-119 1.00700E-06 5.93420E-05 491190 + 498 491191 In-119m 2.32850E-07 1.05300E-04 491191 + 499 491200 In-120 1.25800E-06 1.51720E-04 491200 + 500 491201 In-120m 1.25800E-06 1.25800E-06 491201 + 501 491202 In-120m 1.25800E-06 1.25800E-06 491202 + 502 491210 In-121 2.40150E-05 8.78360E-05 491210 + 503 491211 In-121m 5.55290E-06 4.12420E-05 491211 + 504 491220 In-122 1.85540E-05 1.25740E-04 491220 + 505 491221 In-122m 1.31640E-05 1.31640E-05 491221 + 506 491222 In-122m 1.31640E-05 1.31640E-05 491222 + 507 491230 In-123 7.13690E-05 1.15140E-04 491230 + 508 491231 In-123m 1.65020E-05 2.89240E-05 491231 + 509 491240 In-124 5.20860E-05 1.02260E-04 491240 + 510 491241 In-124m 4.69190E-05 4.69190E-05 491241 + 511 491250 In-125 1.06580E-04 1.38010E-04 491250 + 512 491251 In-125m 2.46430E-05 3.04840E-05 491251 + 513 491260 In-126 1.47180E-04 1.95140E-04 491260 + 514 491261 In-126m 1.32570E-04 1.32570E-04 491261 + 515 491270 In-127 6.50240E-04 6.50240E-04 491270 + 516 491271 In-127m 1.50350E-04 2.00240E-04 491271 + 517 491280 In-128 4.06540E-04 6.03290E-04 491280 + 518 491281 In-128m 1.65490E-04 1.96740E-04 491281 + 519 491282 In-128m 5.15270E-04 5.15270E-04 491282 + 520 491290 In-129 9.30130E-04 9.31080E-04 491290 + 521 491291 In-129m 2.15070E-04 2.15470E-04 491291 + 522 491300 In-130 1.41990E-04 1.43270E-04 491300 + 523 491301 In-130m 1.58590E-04 1.58590E-04 491301 + 524 491302 In-130m 2.69830E-04 2.69830E-04 491302 + 525 491310 In-131 6.72500E-05 6.79370E-05 491310 + 526 491311 In-131m 6.72500E-05 6.72500E-05 491311 + 527 491312 In-131m 6.72500E-05 6.72500E-05 491312 + 528 491320 In-132 1.46760E-05 1.46760E-05 491320 + 529 491330 In-133 1.03980E-06 1.28020E-06 491330 + 530 491331 In-133m 2.40420E-07 2.40420E-07 491331 + 531 501170 Sn-117 1.37170E-12 2.05860E-04 50117.82c + 532 501171 Sn-117m 4.48780E-12 4.43540E-07 501171 + 533 501180 Sn-118 2.24400E-10 1.82030E-04 50118.82c + 534 501190 Sn-119 1.43130E-09 1.58750E-04 50119.82c + 535 501191 Sn-119m 4.68280E-09 5.36140E-05 501191 + 536 501210 Sn-121 3.76460E-07 1.27440E-04 501210 + 537 501211 Sn-121m 9.08840E-07 1.08590E-05 501211 + 538 501220 Sn-122 3.84620E-06 1.55910E-04 50122.82c + 539 501230 Sn-123 8.46890E-06 1.72470E-05 50123.82c + 540 501231 Sn-123m 3.50810E-06 1.38790E-04 501231 + 541 501240 Sn-124 3.11690E-05 1.80350E-04 50124.82c + 542 501250 Sn-125 5.26650E-05 7.59770E-05 50125.82c + 543 501251 Sn-125m 2.18150E-05 1.66990E-04 501251 + 544 501260 Sn-126 2.12890E-04 5.41990E-04 50126.82c + 545 501270 Sn-127 5.25400E-04 7.78840E-04 501270 + 546 501271 Sn-127m 2.17630E-04 8.13280E-04 501271 + 547 501280 Sn-128 9.38920E-04 4.25670E-03 501280 + 548 501281 Sn-128m 2.19920E-03 2.71450E-03 501281 + 549 501290 Sn-129 1.43910E-03 2.48660E-03 501290 + 550 501291 Sn-129m 3.47430E-03 3.57340E-03 501291 + 551 501300 Sn-130 2.29580E-03 2.66810E-03 501300 + 552 501301 Sn-130m 5.37720E-03 5.57800E-03 501301 + 553 501310 Sn-131 1.41080E-03 1.54110E-03 501310 + 554 501311 Sn-131m 3.40600E-03 3.47610E-03 501311 + 555 501320 Sn-132 1.95260E-03 1.96840E-03 501320 + 556 501330 Sn-133 2.40000E-04 2.40190E-04 501330 + 557 501340 Sn-134 2.75860E-05 2.75860E-05 501340 + 558 501350 Sn-135 4.11940E-07 4.11940E-07 501350 + 559 501360 Sn-136 7.68210E-09 7.68210E-09 501360 + 560 511230 Sb-123 9.70780E-12 1.56040E-04 51123.82c + 561 511240 Sb-124 4.84360E-07 1.13780E-06 51124.82c + 562 511241 Sb-124m 3.70350E-07 8.71240E-07 511241 + 563 511242 Sb-124m 5.00890E-07 5.00890E-07 511242 + 564 511250 Sb-125 8.28170E-06 2.51250E-04 51125.82c + 565 511260 Sb-126 3.62960E-06 4.49660E-06 51126.82c + 566 511261 Sb-126m 2.68360E-06 6.19330E-06 511261 + 567 511262 Sb-126m 3.50970E-06 3.50970E-06 511262 + 568 511270 Sb-127 9.54240E-05 1.68750E-03 511270 + 569 511280 Sb-128 1.64580E-04 4.43130E-03 511280 + 570 511281 Sb-128m 2.80840E-04 2.80840E-04 511281 + 571 511290 Sb-129 2.25260E-03 7.00030E-03 511290 + 572 511291 Sb-129m 1.37650E-03 3.16320E-03 511291 + 573 511300 Sb-130 4.74280E-03 1.02000E-02 511300 + 574 511301 Sb-130m 4.74280E-03 7.53180E-03 511301 + 575 511310 Sb-131 2.59780E-02 3.09950E-02 511310 + 576 511320 Sb-132 1.31260E-02 1.50940E-02 511320 + 577 511321 Sb-132m 9.67400E-03 9.67400E-03 511321 + 578 511330 Sb-133 2.56810E-02 2.59260E-02 511330 + 579 511340 Sb-134 1.72000E-03 1.74300E-03 511340 + 580 511341 Sb-134m 4.02880E-03 4.02880E-03 511341 + 581 511350 Sb-135 1.66960E-03 1.66990E-03 511350 + 582 511360 Sb-136 2.25540E-04 2.25550E-04 511360 + 583 511370 Sb-137 2.87000E-05 2.87000E-05 511370 + 584 511380 Sb-138 4.77710E-08 4.77710E-08 511380 + 585 521260 Te-126 2.90350E-10 9.82320E-06 52126.82c + 586 521270 Te-127 1.25120E-06 1.68510E-03 521270 + 587 521271 Te-127m 3.02070E-06 2.81120E-04 52527.82c + 588 521280 Te-128 2.17430E-05 4.72390E-03 52128.82c + 589 521290 Te-129 3.13990E-05 8.36680E-03 521290 + 590 521291 Te-129m 7.58010E-05 3.86330E-03 52529.82c + 591 521300 Te-130 1.32380E-03 1.90550E-02 52130.82c + 592 521310 Te-131 1.38000E-03 3.11140E-02 521310 + 593 521311 Te-131m 3.33160E-03 5.81310E-03 521311 + 594 521320 Te-132 1.74670E-02 4.22350E-02 52132.82c + 595 521330 Te-133 9.61180E-03 3.59030E-02 521330 + 596 521331 Te-133m 2.32040E-02 2.76880E-02 521331 + 597 521340 Te-134 4.46230E-02 5.06540E-02 521340 + 598 521350 Te-135 1.75500E-02 1.89950E-02 521350 + 599 521360 Te-136 8.41950E-03 8.62170E-03 521360 + 600 521370 Te-137 1.36490E-03 1.37950E-03 521370 + 601 521380 Te-138 3.19600E-04 3.19650E-04 521380 + 602 521390 Te-139 2.08640E-05 2.08640E-05 521390 + 603 521400 Te-140 3.09530E-06 3.09530E-06 521400 + 604 521410 Te-141 6.69840E-09 6.69840E-09 521410 + 605 531280 I-128 1.35870E-06 1.35870E-06 531280 + 606 531290 I-129 2.92190E-08 9.79630E-03 53129.82c + 607 531300 I-130 7.43340E-06 1.00990E-05 53130.82c + 608 531301 I-130m 3.17360E-06 3.17360E-06 531301 + 609 531310 I-131 1.48140E-04 3.58550E-02 53131.82c + 610 531320 I-132 4.22860E-04 4.29260E-02 531320 + 611 531321 I-132m 3.11650E-04 3.11650E-04 531321 + 612 531330 I-133 3.93520E-03 6.50860E-02 531330 + 613 531331 I-133m 2.40480E-03 2.40480E-03 531331 + 614 531340 I-134 8.50420E-03 6.52820E-02 531340 + 615 531341 I-134m 6.26780E-03 6.26780E-03 531341 + 616 531350 I-135 5.48940E-02 7.38880E-02 53135.82c + 617 531360 I-136 1.45160E-02 2.31580E-02 531360 + 618 531361 I-136m 3.39990E-02 3.40200E-02 531361 + 619 531370 I-137 4.42870E-02 4.56450E-02 531370 + 620 531380 I-138 1.36340E-02 1.39330E-02 531380 + 621 531390 I-139 9.52430E-03 9.54520E-03 531390 + 622 531400 I-140 1.98180E-03 1.98490E-03 531400 + 623 531410 I-141 4.21100E-04 4.21110E-04 531410 + 624 531420 I-142 3.99440E-05 3.99440E-05 531420 + 625 531430 I-143 4.61940E-06 4.61940E-06 531430 + 626 531440 I-144 1.08720E-09 1.08720E-09 531440 + 627 541310 Xe-131 3.90850E-07 3.58560E-02 54131.82c + 628 541311 Xe-131m 9.43550E-07 3.90400E-04 541311 + 629 541320 Xe-132 2.11650E-06 4.29740E-02 54132.82c + 630 541321 Xe-132m 2.39910E-06 2.39910E-06 541321 + 631 541330 Xe-133 1.19960E-05 6.51270E-02 54133.82c + 632 541331 Xe-133m 2.89600E-05 1.88150E-03 541331 + 633 541340 Xe-134 1.43630E-04 6.59060E-02 54134.82c + 634 541341 Xe-134m 3.36410E-04 4.80570E-04 541341 + 635 541350 Xe-135 8.12390E-04 7.65770E-02 54135.82c + 636 541351 Xe-135m 1.96120E-03 1.41590E-02 541351 + 637 541360 Xe-136 1.60330E-02 7.61780E-02 54136.82c + 638 541370 Xe-137 2.37150E-02 6.71320E-02 541370 + 639 541380 Xe-138 3.61830E-02 5.03130E-02 541380 + 640 541390 Xe-139 2.25570E-02 3.13510E-02 541390 + 641 541400 Xe-140 2.24990E-02 2.43880E-02 541400 + 642 541410 Xe-141 5.81870E-03 6.16140E-03 541410 + 643 541420 Xe-142 2.24990E-03 2.28170E-03 541420 + 644 541430 Xe-143 3.22420E-04 3.25190E-04 541430 + 645 541440 Xe-144 5.00500E-05 5.00510E-05 541440 + 646 541450 Xe-145 7.95260E-06 7.95260E-06 541450 + 647 541460 Xe-146 5.80660E-09 5.80660E-09 541460 + 648 551330 Cs-133 2.01520E-09 6.51270E-02 55133.82c + 649 551340 Cs-134 5.88420E-07 1.02210E-06 55134.82c + 650 551341 Cs-134m 4.33680E-07 4.33680E-07 551341 + 651 551350 Cs-135 1.90640E-05 7.66930E-02 55135.82c + 652 551351 Cs-135m 1.16490E-05 1.16490E-05 551351 + 653 551360 Cs-136 1.61480E-04 2.08800E-04 55136.82c + 654 551361 Cs-136m 9.46360E-05 9.46360E-05 551361 + 655 551370 Cs-137 3.20170E-03 7.03340E-02 55137.82c + 656 551380 Cs-138 4.23400E-03 5.94140E-02 551380 + 657 551381 Cs-138m 6.00800E-03 6.00800E-03 551381 + 658 551390 Cs-139 2.43470E-02 5.56980E-02 551390 + 659 551400 Cs-140 3.01490E-02 5.45390E-02 551400 + 660 551410 Cs-141 4.44290E-02 5.05960E-02 551410 + 661 551420 Cs-142 2.68330E-02 2.91100E-02 551420 + 662 551430 Cs-143 2.12440E-02 2.15670E-02 551430 + 663 551440 Cs-144 3.32620E-03 5.03810E-03 551440 + 664 551441 Cs-144m 3.32620E-03 3.32640E-03 551441 + 665 551450 Cs-145 2.10020E-03 2.10780E-03 551450 + 666 551460 Cs-146 3.11580E-04 3.11590E-04 551460 + 667 551470 Cs-147 5.82250E-05 5.82250E-05 551470 + 668 551480 Cs-148 5.37080E-06 5.37080E-06 551480 + 669 551490 Cs-149 5.36520E-10 5.36520E-10 551490 + 670 561360 Ba-136 6.12910E-09 2.56140E-04 56136.82c + 671 561361 Ba-136m 1.43560E-08 1.43560E-08 561361 + 672 561370 Ba-137 2.71150E-06 7.03430E-02 56137.82c + 673 561371 Ba-137m 6.54600E-06 6.64010E-02 561371 + 674 561380 Ba-138 1.96270E-04 6.07520E-02 56138.82c + 675 561390 Ba-139 9.65310E-04 5.66640E-02 561390 + 676 561400 Ba-140 4.05170E-03 5.85910E-02 56140.82c + 677 561410 Ba-141 6.82970E-03 5.74260E-02 561410 + 678 561420 Ba-142 1.72770E-02 4.67400E-02 561420 + 679 561430 Ba-143 2.06840E-02 4.20590E-02 561430 + 680 561440 Ba-144 2.25390E-02 2.93810E-02 561440 + 681 561450 Ba-145 9.12270E-03 1.09730E-02 561450 + 682 561460 Ba-146 5.23320E-03 5.51710E-03 561460 + 683 561470 Ba-147 1.14340E-03 1.18640E-03 561470 + 684 561480 Ba-148 3.44070E-04 3.48090E-04 561480 + 685 561490 Ba-149 3.24140E-05 3.24140E-05 561490 + 686 561500 Ba-150 1.65420E-07 1.65420E-07 561500 + 687 561510 Ba-151 1.88730E-09 1.88730E-09 561510 + 688 571380 La-138 1.54100E-09 1.54100E-09 57138.82c + 689 571390 La-139 6.63780E-06 5.66700E-02 57139.82c + 690 571400 La-140 7.02010E-05 5.86610E-02 57140.82c + 691 571410 La-141 4.03400E-04 5.78290E-02 571410 + 692 571420 La-142 1.25960E-03 4.80000E-02 571420 + 693 571430 La-143 6.42080E-03 4.84800E-02 571430 + 694 571440 La-144 1.30300E-02 4.24100E-02 571440 + 695 571450 La-145 2.40170E-02 3.49900E-02 571450 + 696 571460 La-146 6.44930E-03 1.19660E-02 571460 + 697 571461 La-146m 1.16010E-02 1.16010E-02 571461 + 698 571470 La-147 1.78690E-02 1.90570E-02 571470 + 699 571480 La-148 8.28880E-03 8.63560E-03 571480 + 700 571490 La-149 4.50660E-03 4.53890E-03 571490 + 701 571500 La-150 9.49600E-04 9.49760E-04 571500 + 702 571510 La-151 1.65590E-04 1.65590E-04 571510 + 703 571520 La-152 2.17520E-05 2.17520E-05 571520 + 704 571530 La-153 5.99230E-09 5.99230E-09 571530 + 705 571540 La-154 2.94080E-11 2.94080E-11 571540 + 706 581410 Ce-141 1.00480E-08 5.78290E-02 58141.82c + 707 581420 Ce-142 7.48920E-06 4.80080E-02 58142.82c + 708 581430 Ce-143 4.43850E-05 4.85240E-02 58143.82c + 709 581440 Ce-144 3.05680E-04 4.27160E-02 58144.82c + 710 581450 Ce-145 1.23170E-03 3.62220E-02 581450 + 711 581460 Ce-146 3.65960E-03 2.72270E-02 581460 + 712 581470 Ce-147 5.59950E-03 2.46560E-02 581470 + 713 581480 Ce-148 9.95150E-03 1.86510E-02 581480 + 714 581490 Ce-149 7.17700E-03 1.16780E-02 581490 + 715 581500 Ce-150 5.01130E-03 5.93540E-03 581500 + 716 581510 Ce-151 1.28520E-03 1.45210E-03 581510 + 717 581520 Ce-152 4.44650E-04 4.65090E-04 581520 + 718 581530 Ce-153 3.48950E-05 3.49010E-05 581530 + 719 581540 Ce-154 1.31640E-06 1.31640E-06 581540 + 720 581550 Ce-155 9.09960E-09 9.09960E-09 581550 + 721 581560 Ce-156 1.05080E-10 1.05080E-10 581560 + 722 591430 Pr-143 1.54140E-09 4.85240E-02 59143.82c + 723 591440 Pr-144 9.21030E-08 4.27170E-02 591440 + 724 591441 Pr-144m 8.18010E-07 5.90280E-04 591441 + 725 591450 Pr-145 1.23770E-05 3.62340E-02 591450 + 726 591460 Pr-146 1.18910E-04 2.73460E-02 591460 + 727 591470 Pr-147 5.73290E-04 2.52300E-02 591470 + 728 591480 Pr-148 3.47760E-04 1.89980E-02 591480 + 729 591481 Pr-148m 1.46250E-03 1.46250E-03 591481 + 730 591490 Pr-149 5.37790E-03 1.70560E-02 591490 + 731 591500 Pr-150 5.67580E-03 1.16110E-02 591500 + 732 591510 Pr-151 6.27360E-03 7.72570E-03 591510 + 733 591520 Pr-152 3.02940E-03 3.49470E-03 591520 + 734 591530 Pr-153 1.65520E-03 1.68990E-03 591530 + 735 591540 Pr-154 3.03810E-04 3.05120E-04 591540 + 736 591550 Pr-155 8.43390E-05 8.43480E-05 591550 + 737 591560 Pr-156 7.98320E-06 7.98330E-06 591560 + 738 591570 Pr-157 1.39990E-08 1.39990E-08 591570 + 739 591580 Pr-158 9.39720E-11 9.39720E-11 591580 + 740 601460 Nd-146 4.83880E-09 2.73460E-02 60146.82c + 741 601470 Nd-147 8.82840E-07 2.52300E-02 60147.82c + 742 601480 Nd-148 9.67270E-06 2.04710E-02 60148.82c + 743 601490 Nd-149 7.15680E-05 1.71270E-02 601490 + 744 601500 Nd-150 2.76790E-04 1.18880E-02 60150.82c + 745 601510 Nd-151 6.00860E-04 8.32660E-03 601510 + 746 601520 Nd-152 1.07130E-03 4.56600E-03 601520 + 747 601530 Nd-153 8.48270E-04 2.53820E-03 601530 + 748 601540 Nd-154 6.32560E-04 9.37680E-04 601540 + 749 601550 Nd-155 2.09940E-04 2.94500E-04 601550 + 750 601560 Nd-156 6.91860E-05 7.69530E-05 601560 + 751 601570 Nd-157 1.04190E-05 1.04320E-05 601570 + 752 601580 Nd-158 2.97930E-07 2.98020E-07 601580 + 753 601590 Nd-159 7.41460E-09 7.41460E-09 601590 + 754 601600 Nd-160 2.54880E-10 2.54880E-10 601600 + 755 601610 Nd-161 2.75560E-12 2.75560E-12 601610 + 756 611490 Pm-149 1.71690E-08 1.71280E-02 61149.82c + 757 611500 Pm-150 2.62510E-06 2.62510E-06 611500 + 758 611510 Pm-151 1.04850E-05 8.33710E-03 61151.82c + 759 611520 Pm-152 1.30870E-05 4.57910E-03 611520 + 760 611521 Pm-152m 2.61320E-05 2.61320E-05 611521 + 761 611522 Pm-152m 2.89050E-05 2.89050E-05 611522 + 762 611530 Pm-153 1.96210E-04 2.73440E-03 611530 + 763 611540 Pm-154 1.14120E-04 1.05180E-03 611540 + 764 611541 Pm-154m 1.14120E-04 1.14120E-04 611541 + 765 611550 Pm-155 3.24000E-04 6.18500E-04 611550 + 766 611560 Pm-156 1.71710E-04 2.48660E-04 611560 + 767 611570 Pm-157 1.18520E-04 1.28950E-04 611570 + 768 611580 Pm-158 2.68480E-05 2.71460E-05 611580 + 769 611590 Pm-159 8.93070E-06 8.93810E-06 611590 + 770 611600 Pm-160 3.73740E-06 3.73770E-06 611600 + 771 611610 Pm-161 1.44520E-08 1.44550E-08 611610 + 772 611620 Pm-162 7.82000E-11 7.82000E-11 611620 + 773 611630 Pm-163 5.91670E-12 5.91670E-12 611630 + 774 621510 Sm-151 7.07730E-10 8.33710E-03 62151.82c + 775 621520 Sm-152 3.17440E-08 4.63420E-03 62152.82c + 776 621530 Sm-153 1.32820E-07 2.73480E-03 62153.82c + 777 621531 Sm-153m 3.20660E-07 3.20660E-07 621531 + 778 621540 Sm-154 3.83630E-06 1.16980E-03 62154.82c + 779 621550 Sm-155 1.32050E-05 6.31710E-04 621550 + 780 621560 Sm-156 1.99640E-05 2.68630E-04 621560 + 781 621570 Sm-157 1.43280E-05 1.43280E-04 621570 + 782 621580 Sm-158 1.02280E-05 3.73760E-05 621580 + 783 621590 Sm-159 5.10350E-06 1.40500E-05 621590 + 784 621600 Sm-160 2.49160E-06 6.21920E-06 621600 + 785 621610 Sm-161 3.45360E-06 3.46810E-06 621610 + 786 621620 Sm-162 4.80930E-08 4.81710E-08 621620 + 787 621630 Sm-163 1.10840E-08 1.10900E-08 621630 + 788 621640 Sm-164 4.02010E-10 4.02010E-10 621640 + 789 621650 Sm-165 7.11500E-12 7.11500E-12 621650 + 790 631540 Eu-154 3.71310E-10 7.05780E-10 63154.82c + 791 631541 Eu-154m 3.34470E-10 3.34470E-10 631541 + 792 631550 Eu-155 2.00440E-08 6.31730E-04 63155.82c + 793 631560 Eu-156 2.66160E-06 2.71290E-04 63156.82c + 794 631570 Eu-157 2.60490E-06 1.45890E-04 63157.82c + 795 631580 Eu-158 3.83570E-06 4.12110E-05 631580 + 796 631590 Eu-159 2.55170E-06 1.66020E-05 631590 + 797 631600 Eu-160 4.98330E-06 1.12030E-05 631600 + 798 631610 Eu-161 3.45360E-06 6.92170E-06 631610 + 799 631620 Eu-162 4.15240E-07 4.63410E-07 631620 + 800 631630 Eu-163 8.04360E-07 8.15450E-07 631630 + 801 631640 Eu-164 5.71820E-08 5.75840E-08 631640 + 802 631650 Eu-165 6.97770E-09 6.98480E-09 631650 + 803 631660 Eu-166 3.05090E-10 3.05090E-10 631660 + 804 631670 Eu-167 9.99870E-12 9.99870E-12 631670 + 805 641560 Gd-156 2.86600E-11 2.71290E-04 64156.82c + 806 641570 Gd-157 6.23530E-10 1.45890E-04 64157.82c + 807 641580 Gd-158 6.73330E-09 4.12180E-05 64158.82c + 808 641590 Gd-159 3.72280E-08 1.66390E-05 641590 + 809 641600 Gd-160 2.86790E-07 1.14890E-05 64160.82c + 810 641610 Gd-161 7.39720E-07 7.66140E-06 641610 + 811 641620 Gd-162 8.07660E-07 1.27110E-06 641620 + 812 641630 Gd-163 9.31850E-07 1.74730E-06 641630 + 813 641640 Gd-164 4.83870E-07 5.41450E-07 641640 + 814 641650 Gd-165 1.42690E-07 1.49670E-07 641650 + 815 641660 Gd-166 3.85980E-08 3.89030E-08 641660 + 816 641670 Gd-167 3.63510E-09 3.64510E-09 641670 + 817 641680 Gd-168 3.05440E-10 3.05440E-10 641680 + 818 641690 Gd-169 1.02590E-11 1.02590E-11 641690 + 819 651590 Tb-159 9.30530E-12 1.66390E-05 65159.82c + 820 651600 Tb-160 2.27530E-10 2.27530E-10 65160.82c + 821 651610 Tb-161 4.04470E-09 7.66540E-06 651610 + 822 651620 Tb-162 4.86400E-09 1.27590E-06 651620 + 823 651630 Tb-163 8.04370E-07 2.55170E-06 651630 + 824 651640 Tb-164 1.00920E-07 6.42370E-07 651640 + 825 651650 Tb-165 1.49360E-07 2.99030E-07 651650 + 826 651660 Tb-166 8.69530E-08 1.25860E-07 651660 + 827 651670 Tb-167 4.37480E-08 4.73930E-08 651670 + 828 651680 Tb-168 9.30180E-09 9.60720E-09 651680 + 829 651690 Tb-169 2.00950E-09 2.01980E-09 651690 + 830 651700 Tb-170 1.49480E-10 1.49480E-10 651700 + 831 651710 Tb-171 9.94680E-12 9.94680E-12 651710 + 832 661620 Dy-162 3.29680E-12 1.27590E-06 66162.82c + 833 661630 Dy-163 1.72550E-10 2.55180E-06 66163.82c + 834 661640 Dy-164 1.39130E-09 6.43760E-07 66164.82c + 835 661650 Dy-165 4.78390E-09 3.04530E-07 661650 + 836 661651 Dy-165m 7.31310E-10 7.31310E-10 661651 + 837 661660 Dy-166 1.81770E-08 1.44030E-07 661660 + 838 661670 Dy-167 2.03540E-08 6.77470E-08 661670 + 839 661680 Dy-168 2.14870E-08 3.10940E-08 661680 + 840 661690 Dy-169 1.02290E-08 1.22490E-08 661690 + 841 661700 Dy-170 4.24690E-09 4.39640E-09 661700 + 842 661710 Dy-171 7.47300E-10 7.57250E-10 661710 + 843 661720 Dy-172 1.24420E-10 1.24420E-10 661720 + 844 661730 Dy-173 7.18260E-12 7.18260E-12 661730 + 845 671650 Ho-165 5.99820E-12 3.04560E-07 67165.82c + 846 671660 Ho-166 1.76090E-11 1.44050E-07 671660 + 847 671661 Ho-166m 4.12440E-11 4.12440E-11 671661 + 848 671670 Ho-167 4.28520E-10 6.81760E-08 671670 + 849 671680 Ho-168 4.79830E-10 3.22520E-08 671680 + 850 671681 Ho-168m 6.80870E-10 6.80870E-10 671681 + 851 671690 Ho-169 2.99070E-09 1.52390E-08 671690 + 852 671700 Ho-170 1.88370E-09 1.88370E-09 671700 + 853 671701 Ho-170m 8.04250E-10 5.20060E-09 671701 + 854 671710 Ho-171 2.36200E-09 3.11920E-09 671710 + 855 671720 Ho-172 8.98030E-10 1.02240E-09 671720 + 856 671730 Ho-173 3.03000E-10 3.10180E-10 671730 + 857 671740 Ho-174 3.85070E-11 3.85070E-11 671740 + 858 671750 Ho-175 5.10380E-12 5.10380E-12 671750 + 859 681680 Er-168 3.27540E-12 3.22580E-08 68168.82c + 860 681690 Er-169 2.44680E-11 1.52640E-08 681690 + 861 681700 Er-170 1.37770E-10 7.22210E-09 68170.82c + 862 681710 Er-171 2.96770E-10 3.41600E-09 681710 + 863 681720 Er-172 5.86940E-10 1.60940E-09 681720 + 864 681730 Er-173 4.23070E-10 7.33250E-10 681730 + 865 681740 Er-174 2.74310E-10 3.12820E-10 681740 + 866 681750 Er-175 8.66900E-11 9.17940E-11 681750 + 867 681760 Er-176 2.49190E-11 2.49190E-11 681760 + 868 681770 Er-177 2.53720E-12 2.53720E-12 681770 + 869 691710 Tm-171 1.32240E-12 3.41730E-09 691710 + 870 691720 Tm-172 7.35150E-12 1.61670E-09 691720 + 871 691730 Tm-173 3.18250E-11 7.65080E-10 691730 + 872 691740 Tm-174 4.83400E-11 3.61160E-10 691740 + 873 691750 Tm-175 7.71480E-11 1.68940E-10 691750 + 874 691760 Tm-176 4.75330E-11 7.24520E-11 691760 + 875 691770 Tm-177 2.55490E-11 2.80860E-11 691770 + 876 691780 Tm-178 5.87120E-12 5.87120E-12 691780 + 877 691790 Tm-179 1.34990E-12 1.34990E-12 691790 + 878 701750 Yb-175 2.04650E-12 1.71300E-10 701750 + 879 701751 Yb-175m 3.12840E-13 1.30400E-10 701751 + 880 701760 Yb-176 2.98070E-12 7.66360E-11 701760 + 881 701761 Yb-176m 5.36170E-12 4.15880E-11 701761 + 882 701770 Yb-177 8.19100E-12 3.81710E-11 701770 + 883 701771 Yb-177m 1.89400E-12 2.99800E-11 701771 + 884 701780 Yb-178 1.15240E-11 1.73950E-11 701780 + 885 701790 Yb-179 5.78980E-12 7.13970E-12 701790 + 886 701800 Yb-180 2.53420E-12 2.53420E-12 701800 + 887 711790 Lu-179 1.23990E-12 8.56910E-12 711790 + 888 711791 Lu-179m 1.89540E-13 7.32920E-12 711791 + 889 711800 Lu-180 3.92610E-13 2.14530E-12 711800 + 890 711801 Lu-180m 3.92610E-13 2.92680E-12 711801 + 891 711810 Lu-181 1.29440E-12 1.29440E-12 711810 + + Neutron-induced fission: + + Interpolation region : 2 / 2 + Interpolation energy : 4.00000E-01 MeV + Number of products : 896 / 979 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 3.25860E-05 3.25860E-05 1001.82c + 2 10020 H-2 9.95850E-06 9.95850E-06 1002.82c + 3 10030 H-3 1.25000E-04 1.25000E-04 1003.82c + 4 20040 He-4 2.06000E-03 2.06000E-03 2004.82c + 5 230560 V-56 1.53460E-12 1.53460E-12 230560 + 6 230570 V-57 3.71370E-12 3.71370E-12 230570 + 7 230580 V-58 3.82800E-12 3.82800E-12 230580 + 8 230590 V-59 4.01450E-12 4.01450E-12 230590 + 9 230600 V-60 1.44150E-12 1.44150E-12 230600 + 10 240570 Cr-57 1.59220E-12 8.35350E-12 240570 + 11 240580 Cr-58 8.17940E-12 8.94500E-12 240580 + 12 240590 Cr-59 1.86390E-11 2.26540E-11 240590 + 13 240600 Cr-60 3.72570E-11 3.86980E-11 240600 + 14 240610 Cr-61 3.18100E-11 3.18100E-11 240610 + 15 240620 Cr-62 2.61610E-11 2.61610E-11 240620 + 16 240630 Cr-63 7.37670E-12 7.37670E-12 240630 + 17 240640 Cr-64 1.69810E-12 1.69810E-12 240640 + 18 250590 Mn-59 5.12120E-12 2.77750E-11 250590 + 19 250600 Mn-60 1.96900E-12 4.29710E-11 250600 + 20 250601 Mn-60m 2.00310E-11 2.00310E-11 250601 + 21 250610 Mn-61 9.39410E-11 1.25750E-10 250610 + 22 250620 Mn-62 1.50060E-10 1.63140E-10 250620 + 23 250621 Mn-62m 2.35000E-11 3.65810E-11 250621 + 24 250630 Mn-63 2.84880E-10 2.92260E-10 250630 + 25 250640 Mn-64 1.77450E-10 1.79150E-10 250640 + 26 250650 Mn-65 1.16600E-10 1.16600E-10 250650 + 27 250660 Mn-66 2.69630E-11 2.69630E-11 250660 + 28 250670 Mn-67 4.83880E-12 4.83880E-12 250670 + 29 260600 Fe-60 1.01220E-12 6.17110E-11 260600 + 30 260610 Fe-61 1.05620E-11 1.36310E-10 260610 + 31 260620 Fe-62 1.02450E-10 3.02170E-10 260620 + 32 260630 Fe-63 3.55980E-10 6.48240E-10 260630 + 33 260640 Fe-64 1.12970E-09 1.30890E-09 260640 + 34 260650 Fe-65 1.73760E-09 1.85420E-09 260650 + 35 260660 Fe-66 2.44330E-09 2.47030E-09 260660 + 36 260670 Fe-67 1.22810E-09 1.23290E-09 260670 + 37 260680 Fe-68 5.72970E-10 5.72970E-10 260680 + 38 260690 Fe-69 1.02920E-10 1.02920E-10 260690 + 39 260700 Fe-70 1.39950E-11 1.39950E-11 260700 + 40 270620 Co-62 3.09810E-13 3.02490E-10 270620 + 41 270630 Co-63 2.43570E-11 6.72590E-10 270630 + 42 270640 Co-64 1.80690E-10 1.48950E-09 270640 + 43 270650 Co-65 1.41470E-09 3.26890E-09 270650 + 44 270660 Co-66 4.21220E-09 6.68250E-09 270660 + 45 270670 Co-67 1.11280E-08 1.23610E-08 270670 + 46 270680 Co-68 7.27550E-09 1.02810E-08 270680 + 47 270681 Co-68m 5.43050E-09 6.01070E-09 270681 + 48 270690 Co-69 1.44490E-08 1.45450E-08 270690 + 49 270700 Co-70 2.83240E-09 2.83240E-09 270700 + 50 270701 Co-70m 2.83240E-09 2.84640E-09 270701 + 51 270710 Co-71 2.10150E-09 2.10150E-09 270710 + 52 270720 Co-72 4.61110E-10 4.61110E-10 270720 + 53 270730 Co-73 2.52240E-11 2.52240E-11 270730 + 54 270740 Co-74 1.06700E-12 1.06700E-12 270740 + 55 280640 Ni-64 1.76640E-12 1.49130E-09 28064.82c + 56 280650 Ni-65 3.73800E-11 3.30630E-09 280650 + 57 280660 Ni-66 6.46960E-10 7.32940E-09 280660 + 58 280670 Ni-67 3.83490E-09 1.61960E-08 280670 + 59 280680 Ni-68 2.18910E-08 3.53230E-08 280680 + 60 280690 Ni-69 2.67700E-08 4.11690E-08 280690 + 61 280691 Ni-69m 2.67700E-08 2.67700E-08 280691 + 62 280700 Ni-70 1.14820E-07 1.20500E-07 280700 + 63 280710 Ni-71 1.08950E-07 1.11050E-07 280710 + 64 280720 Ni-72 1.56790E-07 1.57250E-07 280720 + 65 280730 Ni-73 2.53230E-08 2.53480E-08 280730 + 66 280740 Ni-74 7.60480E-09 7.60590E-09 280740 + 67 280750 Ni-75 4.08800E-10 4.08800E-10 280750 + 68 280760 Ni-76 5.99570E-11 5.99570E-11 280760 + 69 280770 Ni-77 1.49300E-12 1.49300E-12 280770 + 70 290660 Cu-66 1.48050E-12 7.33090E-09 290660 + 71 290670 Cu-67 5.82370E-11 1.62540E-08 290670 + 72 290680 Cu-68 2.31820E-10 3.60850E-08 290680 + 73 290681 Cu-68m 6.31890E-10 6.31890E-10 290681 + 74 290690 Cu-69 1.17420E-08 7.96800E-08 290690 + 75 290700 Cu-70 3.70140E-09 3.04420E-08 290700 + 76 290701 Cu-70m 4.72700E-08 5.34800E-08 290701 + 77 290702 Cu-70m 3.70140E-09 1.24200E-07 290702 + 78 290710 Cu-71 2.58570E-07 3.69620E-07 290710 + 79 290720 Cu-72 8.23840E-07 9.81090E-07 290720 + 80 290730 Cu-73 7.60740E-07 7.86090E-07 290730 + 81 290740 Cu-74 6.08790E-07 6.16400E-07 290740 + 82 290750 Cu-75 2.21230E-07 2.21630E-07 290750 + 83 290760 Cu-76 4.87770E-08 4.88070E-08 290760 + 84 290761 Cu-76m 4.87770E-08 4.88070E-08 290761 + 85 290770 Cu-77 1.36690E-08 1.36700E-08 290770 + 86 290780 Cu-78 1.79460E-09 1.79460E-09 290780 + 87 290790 Cu-79 1.24970E-10 1.24970E-10 290790 + 88 300680 Zn-68 1.65270E-12 3.61880E-08 300680 + 89 300690 Zn-69 1.09600E-11 7.97460E-08 300690 + 90 300691 Zn-69m 5.44310E-11 5.44310E-11 300691 + 91 300700 Zn-70 1.95410E-09 1.77130E-07 300700 + 92 300710 Zn-71 3.85410E-09 3.73480E-07 300710 + 93 300711 Zn-71m 1.91420E-08 1.91420E-08 300711 + 94 300720 Zn-72 1.43830E-06 2.41940E-06 300720 + 95 300730 Zn-73 1.39930E-07 1.75070E-06 300730 + 96 300731 Zn-73m 1.93550E-07 8.24690E-07 300731 + 97 300732 Zn-73m 1.26230E-06 1.26230E-06 300732 + 98 300740 Zn-74 3.82430E-06 4.44850E-06 300740 + 99 300750 Zn-75 2.29480E-06 2.51010E-06 300750 + 100 300760 Zn-76 1.35180E-05 1.36140E-05 300760 + 101 300770 Zn-77 2.11930E-06 2.27410E-06 300770 + 102 300771 Zn-77m 2.82180E-07 2.82180E-07 300771 + 103 300780 Zn-78 1.16010E-05 1.16030E-05 300780 + 104 300790 Zn-79 4.68870E-06 4.68880E-06 300790 + 105 300800 Zn-80 7.25040E-08 7.25040E-08 300800 + 106 300810 Zn-81 4.14920E-09 4.14920E-09 300810 + 107 300820 Zn-82 1.35820E-10 1.35820E-10 300820 + 108 310710 Ga-71 7.04490E-11 3.92690E-07 310710 + 109 310720 Ga-72 3.08520E-09 2.42280E-06 310720 + 110 310721 Ga-72m 3.03270E-10 8.09190E-08 310721 + 111 310730 Ga-73 4.10820E-08 2.42290E-06 310730 + 112 310740 Ga-74 1.97430E-07 3.68190E-06 310740 + 113 310741 Ga-74m 1.97430E-07 4.64590E-06 310741 + 114 310750 Ga-75 2.29480E-06 4.80490E-06 310750 + 115 310760 Ga-76 4.50610E-06 1.81200E-05 310760 + 116 310770 Ga-77 1.68100E-05 1.92250E-05 310770 + 117 310780 Ga-78 3.01640E-05 4.18280E-05 310780 + 118 310790 Ga-79 2.81310E-05 3.27590E-05 310790 + 119 310800 Ga-80 3.15690E-05 3.16420E-05 310800 + 120 310810 Ga-81 2.01690E-05 2.01730E-05 310810 + 121 310820 Ga-82 4.10930E-06 4.10940E-06 310820 + 122 310830 Ga-83 1.48470E-07 1.48470E-07 310830 + 123 310840 Ga-84 4.78370E-09 4.78370E-09 310840 + 124 320720 Ge-72 1.20870E-12 2.42280E-06 32072.82c + 125 320730 Ge-73 3.70460E-11 2.42300E-06 32073.82c + 126 320731 Ge-73m 7.45900E-12 2.38740E-06 320731 + 127 320740 Ge-74 2.95120E-09 4.84630E-06 32074.82c + 128 320750 Ge-75 4.09240E-09 4.83970E-06 320750 + 129 320751 Ge-75m 3.07370E-08 2.22930E-07 320751 + 130 320760 Ge-76 1.14790E-06 1.92680E-05 32076.82c + 131 320770 Ge-77 6.35800E-06 1.01720E-05 320770 + 132 320771 Ge-77m 8.46530E-07 2.00720E-05 320771 + 133 320780 Ge-78 6.03320E-05 1.02190E-04 320780 + 134 320790 Ge-79 2.34150E-05 6.31320E-05 320790 + 135 320791 Ge-79m 1.75870E-04 1.75910E-04 320791 + 136 320800 Ge-80 3.67780E-04 4.01820E-04 320800 + 137 320810 Ge-81 4.66670E-04 4.77520E-04 320810 + 138 320811 Ge-81m 9.39620E-05 1.02790E-04 320811 + 139 320820 Ge-82 5.61000E-04 5.64290E-04 320820 + 140 320830 Ge-83 2.48630E-04 2.48730E-04 320830 + 141 320840 Ge-84 7.35780E-05 7.35790E-05 320840 + 142 320850 Ge-85 9.42680E-06 9.42680E-06 320850 + 143 320860 Ge-86 1.36470E-06 1.36470E-06 320860 + 144 320870 Ge-87 1.42980E-09 1.42980E-09 320870 + 145 330750 As-75 4.21850E-12 4.83980E-06 33075.82c + 146 330751 As-75m 1.59750E-11 8.28560E-11 330751 + 147 330760 As-76 1.99590E-09 1.99590E-09 330760 + 148 330770 As-77 6.13520E-08 2.64910E-05 330770 + 149 330780 As-78 1.78100E-06 1.03970E-04 330780 + 150 330790 As-79 1.64110E-05 2.48420E-04 330790 + 151 330800 As-80 8.12020E-05 4.83020E-04 330800 + 152 330810 As-81 3.93790E-04 9.73070E-04 330810 + 153 330820 As-82 1.86330E-04 7.50620E-04 330820 + 154 330821 As-82m 6.49220E-04 6.49220E-04 330821 + 155 330830 As-83 2.07220E-03 2.32890E-03 330830 + 156 330840 As-84 6.55800E-04 6.89280E-04 330840 + 157 330841 As-84m 6.55800E-04 6.89280E-04 330841 + 158 330850 As-85 7.15720E-04 7.23830E-04 330850 + 159 330860 As-86 1.82590E-04 1.83950E-04 330860 + 160 330870 As-87 4.24070E-05 4.24080E-05 330870 + 161 330880 As-88 1.85090E-06 1.85090E-06 330880 + 162 330890 As-89 1.99760E-08 1.99760E-08 330890 + 163 340770 Se-77 1.40340E-12 2.64910E-05 34077.82c + 164 340771 Se-77m 1.05410E-11 1.05410E-11 340771 + 165 340780 Se-78 2.57760E-09 1.03970E-04 34078.82c + 166 340790 Se-79 1.05440E-07 2.48400E-04 34079.82c + 167 340791 Se-79m 1.40390E-08 2.42550E-04 340791 + 168 340800 Se-80 1.12650E-05 4.94290E-04 34080.82c + 169 340810 Se-81 1.46090E-05 1.09730E-03 340810 + 170 340811 Se-81m 1.09720E-04 1.44650E-04 340811 + 171 340820 Se-82 5.40600E-04 1.94040E-03 34082.82c + 172 340830 Se-83 2.06570E-03 2.90500E-03 340830 + 173 340831 Se-83m 4.15920E-04 1.90740E-03 340831 + 174 340840 Se-84 5.76790E-03 7.30380E-03 340840 + 175 340850 Se-85 5.99400E-03 6.61930E-03 340850 + 176 340860 Se-86 5.17580E-03 5.30560E-03 340860 + 177 340870 Se-87 2.66210E-03 2.69800E-03 340870 + 178 340880 Se-88 1.11780E-03 1.11970E-03 340880 + 179 340890 Se-89 2.06620E-04 2.06640E-04 340890 + 180 340900 Se-90 6.30270E-05 6.30270E-05 340900 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1.50200E-04 350920 + 201 350930 Br-93 3.38920E-05 3.38920E-05 350930 + 202 350940 Br-94 6.00030E-08 6.00030E-08 350940 + 203 350950 Br-95 1.79000E-09 1.79000E-09 350950 + 204 360820 Kr-82 7.47040E-10 4.11000E-06 36082.82c + 205 360830 Kr-83 6.12400E-08 4.90140E-03 36083.82c + 206 360831 Kr-83m 1.23300E-08 4.89700E-03 360831 + 207 360840 Kr-84 1.73860E-05 7.87710E-03 36084.82c + 208 360850 Kr-85 1.88260E-04 2.18110E-03 36085.82c + 209 360851 Kr-85m 3.79040E-05 9.24220E-03 360851 + 210 360860 Kr-86 1.93380E-03 1.33730E-02 36086.82c + 211 360870 Kr-87 5.78610E-03 1.73370E-02 360870 + 212 360880 Kr-88 1.44250E-02 2.16900E-02 360880 + 213 360890 Kr-89 1.45580E-02 1.82480E-02 360890 + 214 360900 Kr-90 2.28590E-02 2.47700E-02 360900 + 215 360910 Kr-91 1.55120E-02 1.63710E-02 360910 + 216 360920 Kr-92 8.80660E-03 8.93010E-03 360920 + 217 360930 Kr-93 3.11150E-03 3.12240E-03 360930 + 218 360940 Kr-94 8.21260E-04 8.21280E-04 360940 + 219 360950 Kr-95 1.23950E-04 1.23950E-04 360950 + 220 360960 Kr-96 2.44940E-05 2.44940E-05 360960 + 221 360970 Kr-97 1.23680E-08 1.23680E-08 360970 + 222 370840 Rb-84 6.71390E-11 2.07990E-10 370840 + 223 370841 Rb-84m 1.40850E-10 1.40850E-10 370841 + 224 370850 Rb-85 2.24590E-08 9.44550E-03 37085.82c + 225 370860 Rb-86 1.32190E-06 4.09500E-06 37086.82c + 226 370861 Rb-86m 2.77310E-06 2.77310E-06 370861 + 227 370870 Rb-87 1.10130E-04 1.74470E-02 37087.82c + 228 370880 Rb-88 4.30200E-04 2.21200E-02 370880 + 229 370890 Rb-89 1.96780E-03 2.02160E-02 370890 + 230 370900 Rb-90 6.62620E-04 2.24520E-02 370900 + 231 370901 Rb-90m 6.74100E-03 9.98090E-03 370901 + 232 370910 Rb-91 1.83770E-02 3.47480E-02 370910 + 233 370920 Rb-92 2.08620E-02 2.97920E-02 370920 + 234 370930 Rb-93 2.07610E-02 2.38930E-02 370930 + 235 370940 Rb-94 9.91370E-03 1.07290E-02 370940 + 236 370950 Rb-95 5.88380E-03 6.00510E-03 370950 + 237 370960 Rb-96 7.59750E-04 1.15730E-03 370960 + 238 370961 Rb-96m 7.59750E-04 7.71540E-04 370961 + 239 370970 Rb-97 4.11510E-04 4.11520E-04 370970 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1.54070E-05 381010 + 260 381020 Sr-102 2.27470E-08 2.27470E-08 381020 + 261 390890 Y-89 1.01450E-10 2.02900E-02 39089.82c + 262 390891 Y-89m 5.03840E-10 1.95630E-06 390891 + 263 390900 Y-90 1.56110E-08 3.31610E-02 39090.82c + 264 390901 Y-90m 2.61080E-08 2.61080E-08 390901 + 265 390910 Y-91 5.04780E-06 3.86330E-02 39091.82c + 266 390911 Y-91m 2.50700E-05 2.27370E-02 390911 + 267 390920 Y-92 1.87490E-04 4.48670E-02 390920 + 268 390930 Y-93 1.62630E-04 5.23430E-02 390930 + 269 390931 Y-93m 1.22150E-03 1.39730E-02 390931 + 270 390940 Y-94 3.70860E-03 5.08000E-02 390940 + 271 390950 Y-95 1.43830E-02 5.54530E-02 390950 + 272 390960 Y-96 6.91370E-03 3.49940E-02 390960 + 273 390961 Y-96m 1.45040E-02 1.45080E-02 390961 + 274 390970 Y-97 5.71530E-03 1.71860E-02 390970 + 275 390971 Y-97m 2.11260E-02 2.89030E-02 390971 + 276 390972 Y-97m 7.26010E-03 7.26010E-03 390972 + 277 390980 Y-98 3.99680E-03 8.79890E-03 390980 + 278 390981 Y-98m 1.93760E-02 1.93760E-02 390981 + 279 390990 Y-99 2.15620E-02 2.27670E-02 390990 + 280 391000 Y-100 3.43670E-03 3.69490E-03 391000 + 281 391001 Y-100m 3.43670E-03 3.43690E-03 391001 + 282 391010 Y-101 2.66030E-03 2.67530E-03 391010 + 283 391020 Y-102 2.43020E-04 2.43030E-04 391020 + 284 391021 Y-102m 2.43020E-04 2.43030E-04 391021 + 285 391030 Y-103 8.00310E-05 8.00310E-05 391030 + 286 391040 Y-104 4.82070E-06 4.82070E-06 391040 + 287 391050 Y-105 1.84560E-09 1.84560E-09 391050 + 288 400920 Zr-92 8.74260E-07 4.48680E-02 40092.82c + 289 400930 Zr-93 2.59150E-05 5.23690E-02 40093.82c + 290 400940 Zr-94 2.48120E-04 5.10480E-02 40094.82c + 291 400950 Zr-95 1.26180E-03 5.67150E-02 40095.82c + 292 400960 Zr-96 6.21340E-03 5.57390E-02 40096.82c + 293 400970 Zr-97 1.50570E-02 6.30640E-02 400970 + 294 400980 Zr-98 3.21740E-02 6.00460E-02 400980 + 295 400990 Zr-99 4.61650E-02 6.85800E-02 400990 + 296 401000 Zr-100 4.30270E-02 5.01250E-02 401000 + 297 401010 Zr-101 2.48230E-02 2.75220E-02 401010 + 298 401020 Zr-102 1.42640E-02 1.47330E-02 401020 + 299 401030 Zr-103 4.07800E-03 4.15210E-03 401030 + 300 401040 Zr-104 1.16310E-03 1.16750E-03 401040 + 301 401050 Zr-105 1.18520E-04 1.18520E-04 401050 + 302 401060 Zr-106 1.48120E-05 1.48120E-05 401060 + 303 401070 Zr-107 6.36570E-09 6.36570E-09 401070 + 304 410950 Nb-95 2.87340E-06 5.66840E-02 41095.82c + 305 410951 Nb-95m 5.78540E-07 6.13290E-04 410951 + 306 410960 Nb-96 3.63470E-05 3.63470E-05 410960 + 307 410970 Nb-97 3.12910E-04 6.34400E-02 410970 + 308 410971 Nb-97m 6.30020E-05 6.00040E-02 410971 + 309 410980 Nb-98 3.06940E-04 6.03530E-02 410980 + 310 410981 Nb-98m 1.06950E-03 1.06950E-03 410981 + 311 410990 Nb-99 6.94180E-03 5.08170E-02 410990 + 312 410991 Nb-99m 1.39770E-03 2.66350E-02 410991 + 313 411000 Nb-100 2.44910E-03 5.25740E-02 411000 + 314 411001 Nb-100m 1.18730E-02 1.18730E-02 411001 + 315 411010 Nb-101 2.97530E-02 5.72750E-02 411010 + 316 411020 Nb-102 1.47640E-02 2.94970E-02 411020 + 317 411021 Nb-102m 1.47640E-02 1.47640E-02 411021 + 318 411030 Nb-103 2.72840E-02 3.14360E-02 411030 + 319 411040 Nb-104 6.12300E-03 7.29220E-03 411040 + 320 411041 Nb-104m 6.12300E-03 6.12300E-03 411041 + 321 411050 Nb-105 5.44810E-03 5.56520E-03 411050 + 322 411060 Nb-106 1.43410E-03 1.44870E-03 411060 + 323 411070 Nb-107 2.69600E-04 2.69610E-04 411070 + 324 411080 Nb-108 1.64510E-05 1.64510E-05 411080 + 325 411090 Nb-109 2.65250E-06 2.65250E-06 411090 + 326 411100 Nb-110 8.42890E-11 8.42890E-11 411100 + 327 420970 Mo-97 2.78500E-06 6.34420E-02 42097.82c + 328 420980 Mo-98 4.23480E-05 6.14650E-02 42098.82c + 329 420990 Mo-99 3.19360E-04 7.72380E-02 42099.82c + 330 421000 Mo-100 1.72780E-03 6.61750E-02 42100.82c + 331 421010 Mo-101 5.13070E-03 6.24060E-02 421010 + 332 421020 Mo-102 1.48710E-02 5.91330E-02 421020 + 333 421030 Mo-103 2.08060E-02 5.22490E-02 421030 + 334 421040 Mo-104 2.56790E-02 3.91810E-02 421040 + 335 421050 Mo-105 1.70410E-02 2.25770E-02 421050 + 336 421060 Mo-106 1.21220E-02 1.35220E-02 421060 + 337 421070 Mo-107 4.11030E-03 4.36470E-03 421070 + 338 421080 Mo-108 1.01710E-03 1.03290E-03 421080 + 339 421090 Mo-109 1.30230E-04 1.32550E-04 421090 + 340 421100 Mo-110 2.09100E-05 2.09100E-05 421100 + 341 421110 Mo-111 4.45990E-06 4.45990E-06 421110 + 342 421120 Mo-112 5.15070E-10 5.15070E-10 421120 + 343 431000 Tc-100 8.64960E-06 8.64960E-06 431000 + 344 431010 Tc-101 6.36780E-05 6.24690E-02 431010 + 345 431020 Tc-102 1.62750E-04 5.92950E-02 431020 + 346 431021 Tc-102m 1.62750E-04 1.62750E-04 431021 + 347 431030 Tc-103 1.49910E-03 5.37490E-02 431030 + 348 431040 Tc-104 3.13850E-03 4.23200E-02 431040 + 349 431050 Tc-105 6.73020E-03 2.93070E-02 431050 + 350 431060 Tc-106 7.61000E-03 2.11320E-02 431060 + 351 431070 Tc-107 8.17370E-03 1.25380E-02 431070 + 352 431080 Tc-108 3.77570E-03 4.80930E-03 431080 + 353 431090 Tc-109 1.69970E-03 1.83150E-03 431090 + 354 431100 Tc-110 5.09470E-04 5.30430E-04 431100 + 355 431110 Tc-111 1.34150E-04 1.38560E-04 431110 + 356 431120 Tc-112 1.99950E-05 1.99950E-05 431120 + 357 431130 Tc-113 4.90160E-06 4.90160E-06 431130 + 358 431140 Tc-114 1.95310E-09 1.95310E-09 431140 + 359 431150 Tc-115 4.12360E-11 4.12360E-11 431150 + 360 441020 Ru-102 3.31360E-06 5.94620E-02 44102.82c + 361 441030 Ru-103 7.85950E-06 5.37780E-02 44103.82c + 362 441031 Ru-103m 2.19900E-05 2.19900E-05 441031 + 363 441040 Ru-104 1.77440E-04 4.24970E-02 44104.82c + 364 441050 Ru-105 3.68570E-04 2.96760E-02 44105.82c + 365 441060 Ru-106 1.20090E-03 2.23330E-02 44106.82c + 366 441070 Ru-107 1.60890E-03 1.41470E-02 441070 + 367 441080 Ru-108 1.79290E-03 6.60360E-03 441080 + 368 441090 Ru-109 1.16270E-03 2.99300E-03 441090 + 369 441100 Ru-110 9.63900E-04 1.49410E-03 441100 + 370 441110 Ru-111 4.85050E-04 6.23910E-04 441110 + 371 441120 Ru-112 2.89630E-04 3.09680E-04 441120 + 372 441130 Ru-113 4.16500E-05 6.70240E-05 441130 + 373 441131 Ru-113m 4.16500E-05 4.16500E-05 441131 + 374 441140 Ru-114 3.24650E-05 3.24670E-05 441140 + 375 441150 Ru-115 6.07400E-06 6.07400E-06 441150 + 376 441160 Ru-116 2.15900E-08 2.15900E-08 441160 + 377 441170 Ru-117 4.01180E-10 4.01180E-10 441170 + 378 441200 Ru-120 1.25580E-09 1.25580E-09 441200 + 379 451050 Rh-105 1.13730E-06 2.96770E-02 45105.82c + 380 451051 Rh-105m 1.51420E-07 8.42440E-03 451051 + 381 451060 Rh-106 2.20830E-06 2.23350E-02 451060 + 382 451061 Rh-106m 6.01920E-06 6.01920E-06 451061 + 383 451070 Rh-107 4.10660E-05 1.41880E-02 451070 + 384 451080 Rh-108 1.83150E-05 6.62190E-03 451080 + 385 451081 Rh-108m 6.38170E-05 6.38170E-05 451081 + 386 451090 Rh-109 1.66750E-04 3.15970E-03 451090 + 387 451100 Rh-110 1.52990E-04 1.64710E-03 451100 + 388 451101 Rh-110m 3.60160E-06 3.60160E-06 451101 + 389 451110 Rh-111 2.89650E-04 9.13560E-04 451110 + 390 451120 Rh-112 1.32400E-04 4.42080E-04 451120 + 391 451121 Rh-112m 1.32400E-04 1.32400E-04 451121 + 392 451130 Rh-113 2.59730E-04 3.47580E-04 451130 + 393 451140 Rh-114 1.00090E-04 1.32580E-04 451140 + 394 451141 Rh-114m 1.00090E-04 1.00090E-04 451141 + 395 451150 Rh-115 1.30570E-04 1.36630E-04 451150 + 396 451160 Rh-116 1.41380E-05 1.41590E-05 451160 + 397 451161 Rh-116m 3.85370E-05 3.85370E-05 451161 + 398 451170 Rh-117 3.23430E-05 3.23430E-05 451170 + 399 451180 Rh-118 6.74640E-06 6.74640E-06 451180 + 400 451190 Rh-119 4.35170E-09 4.35170E-09 451190 + 401 451200 Rh-120 2.28270E-06 2.28400E-06 451200 + 402 451210 Rh-121 2.06830E-07 2.06830E-07 451210 + 403 451220 Rh-122 7.49650E-09 7.49650E-09 451220 + 404 461070 Pd-107 2.48820E-10 1.41880E-02 46107.82c + 405 461071 Pd-107m 5.46890E-10 5.46890E-10 461071 + 406 461080 Pd-108 2.28200E-08 6.68580E-03 46108.82c + 407 461090 Pd-109 9.02080E-08 3.16000E-03 461090 + 408 461091 Pd-109m 1.98270E-07 1.58010E-03 461091 + 409 461100 Pd-110 6.96630E-06 1.65770E-03 46110.82c + 410 461110 Pd-111 4.18330E-06 9.23470E-04 461110 + 411 461111 Pd-111m 9.19470E-06 1.28490E-05 461111 + 412 461120 Pd-112 6.49610E-05 6.39450E-04 461120 + 413 461130 Pd-113 2.64590E-05 4.48070E-04 461130 + 414 461131 Pd-113m 7.40310E-05 7.40310E-05 461131 + 415 461140 Pd-114 1.54250E-04 3.86920E-04 461140 + 416 461150 Pd-115 6.93320E-05 1.99900E-04 461150 + 417 461151 Pd-115m 1.52390E-04 1.72230E-04 461151 + 418 461160 Pd-116 2.97450E-04 3.50150E-04 461160 + 419 461170 Pd-117 5.56200E-05 2.10410E-04 461170 + 420 461171 Pd-117m 1.22250E-04 1.22250E-04 461171 + 421 461180 Pd-118 1.31520E-04 1.38070E-04 461180 + 422 461190 Pd-119 8.40770E-05 8.42170E-05 461190 + 423 461200 Pd-120 1.80460E-05 2.02230E-05 461200 + 424 461210 Pd-121 3.68870E-06 3.86750E-06 461210 + 425 461220 Pd-122 3.73520E-06 3.74270E-06 461220 + 426 461230 Pd-123 8.12260E-07 8.12260E-07 461230 + 427 461240 Pd-124 5.70050E-08 5.70050E-08 461240 + 428 471100 Ag-110 1.24430E-10 1.29040E-10 471100 + 429 471101 Ag-110m 3.39160E-10 3.39160E-10 47510.82c + 430 471110 Ag-111 1.77440E-09 9.22360E-04 47111.82c + 431 471111 Ag-111m 1.33270E-08 9.19450E-04 471111 + 432 471120 Ag-112 2.10040E-07 6.39660E-04 471120 + 433 471130 Ag-113 5.75890E-07 2.96950E-04 471130 + 434 471131 Ag-113m 4.32530E-06 4.33390E-04 471131 + 435 471140 Ag-114 2.77620E-06 4.03160E-04 471140 + 436 471141 Ag-114m 1.34590E-05 1.34590E-05 471141 + 437 471150 Ag-115 9.27970E-06 2.14450E-04 471150 + 438 471151 Ag-115m 6.96960E-05 2.82120E-04 471151 + 439 471160 Ag-116 2.99480E-05 3.84990E-04 471160 + 440 471161 Ag-116m 8.16320E-05 8.16320E-05 471161 + 441 471170 Ag-117 2.28080E-05 1.44600E-04 471170 + 442 471171 Ag-117m 1.71300E-04 2.76510E-04 471171 + 443 471180 Ag-118 5.07630E-05 2.78090E-04 471180 + 444 471181 Ag-118m 2.46100E-04 2.65840E-04 471181 + 445 471190 Ag-119 3.45810E-05 7.66900E-05 471190 + 446 471191 Ag-119m 2.59730E-04 3.01840E-04 471191 + 447 471200 Ag-120 7.15660E-05 1.29710E-04 471200 + 448 471201 Ag-120m 1.19680E-04 1.29800E-04 471201 + 449 471210 Ag-121 1.51200E-04 1.55060E-04 471210 + 450 471220 Ag-122 1.61760E-05 1.99180E-05 471220 + 451 471221 Ag-122m 1.74400E-05 1.74400E-05 471221 + 452 471230 Ag-123 1.87560E-05 1.95680E-05 471230 + 453 471240 Ag-124 9.59460E-06 1.48240E-05 471240 + 454 471241 Ag-124m 1.03440E-05 1.03440E-05 471241 + 455 471250 Ag-125 6.17850E-06 6.17850E-06 471250 + 456 471260 Ag-126 6.29440E-07 6.29440E-07 471260 + 457 471270 Ag-127 9.53900E-08 9.53900E-08 471270 + 458 471280 Ag-128 3.03440E-09 3.03440E-09 471280 + 459 481120 Cd-112 2.23940E-11 6.39660E-04 48112.82c + 460 481130 Cd-113 1.84660E-10 4.47840E-04 48113.82c + 461 481131 Cd-113m 6.99320E-10 5.13470E-06 481131 + 462 481140 Cd-114 3.40350E-08 4.03190E-04 48114.82c + 463 481150 Cd-115 1.17960E-07 4.18600E-04 481150 + 464 481151 Cd-115m 4.46720E-07 1.92930E-05 48515.82c + 465 481160 Cd-116 9.29670E-06 4.71020E-04 48116.82c + 466 481170 Cd-117 5.40610E-06 3.21060E-04 481170 + 467 481171 Cd-117m 2.04730E-05 1.09340E-04 481171 + 468 481180 Cd-118 8.09720E-05 5.15900E-04 481180 + 469 481190 Cd-119 3.59880E-05 3.76170E-04 481190 + 470 481191 Cd-119m 1.00690E-04 1.39040E-04 481191 + 471 481200 Cd-120 2.56310E-04 4.67790E-04 481200 + 472 481210 Cd-121 6.50770E-05 2.03930E-04 481210 + 473 481211 Cd-121m 1.82080E-04 1.98280E-04 481211 + 474 481220 Cd-122 3.02540E-04 3.39900E-04 481220 + 475 481230 Cd-123 3.95080E-05 5.55260E-05 481230 + 476 481231 Cd-123m 1.10540E-04 1.14110E-04 481231 + 477 481240 Cd-124 1.47850E-04 1.67830E-04 481240 + 478 481250 Cd-125 4.09540E-05 4.40430E-05 481250 + 479 481251 Cd-125m 1.14590E-04 1.17680E-04 481251 + 480 481260 Cd-126 1.49680E-04 1.50310E-04 481260 + 481 481270 Cd-127 1.15340E-04 1.15430E-04 481270 + 482 481280 Cd-128 4.69890E-05 4.69920E-05 481280 + 483 481290 Cd-129 2.61230E-06 2.61230E-06 481290 + 484 481291 Cd-129m 7.30920E-06 7.30920E-06 481291 + 485 481300 Cd-130 2.68490E-06 2.68490E-06 481300 + 486 481310 Cd-131 2.16150E-09 2.16150E-09 481310 + 487 491150 In-115 9.15310E-11 4.16960E-04 49115.82c + 488 491151 In-115m 1.84290E-11 4.18600E-04 491151 + 489 491160 In-116 9.96410E-10 9.96410E-10 491160 + 490 491161 In-116m 1.60900E-09 3.47180E-09 491161 + 491 491162 In-116m 1.86280E-09 1.86280E-09 491162 + 492 491170 In-117 1.11340E-07 2.73990E-04 491170 + 493 491171 In-117m 2.24180E-08 2.95920E-04 491171 + 494 491180 In-118 4.15740E-07 5.16320E-04 491180 + 495 491181 In-118m 6.71330E-07 1.43770E-06 491181 + 496 491182 In-118m 7.77230E-07 7.77230E-07 491182 + 497 491190 In-119 2.91660E-06 1.97290E-04 491190 + 498 491191 In-119m 5.87250E-07 3.40490E-04 491191 + 499 491200 In-120 1.08280E-05 4.78620E-04 491200 + 500 491201 In-120m 1.08280E-05 1.08280E-05 491201 + 501 491202 In-120m 1.08280E-05 1.08280E-05 491202 + 502 491210 In-121 7.98500E-05 3.48630E-04 491210 + 503 491211 In-121m 1.60770E-05 1.51330E-04 491211 + 504 491220 In-122 7.97010E-05 4.19600E-04 491220 + 505 491221 In-122m 6.66450E-05 6.66450E-05 491221 + 506 491222 In-122m 6.66450E-05 6.66450E-05 491222 + 507 491230 In-123 2.46840E-04 3.76750E-04 491230 + 508 491231 In-123m 4.97000E-05 8.94190E-05 491231 + 509 491240 In-124 1.14620E-04 2.82450E-04 491240 + 510 491241 In-124m 1.23580E-04 1.23580E-04 491241 + 511 491250 In-125 4.42060E-04 5.80820E-04 491250 + 512 491251 In-125m 8.90070E-05 1.11970E-04 491251 + 513 491260 In-126 3.67920E-04 5.18230E-04 491260 + 514 491261 In-126m 3.96670E-04 3.96670E-04 491261 + 515 491270 In-127 1.76690E-03 1.76690E-03 491270 + 516 491271 In-127m 3.55770E-04 4.71200E-04 491271 + 517 491280 In-128 6.20780E-04 9.10840E-04 491280 + 518 491281 In-128m 2.43070E-04 2.90060E-04 491281 + 519 491282 In-128m 9.31350E-04 9.31350E-04 491282 + 520 491290 In-129 1.57120E-03 1.57850E-03 491290 + 521 491291 In-129m 3.16340E-04 3.19000E-04 491291 + 522 491300 In-130 1.37810E-04 1.40400E-04 491300 + 523 491301 In-130m 2.00660E-04 2.00660E-04 491301 + 524 491302 In-130m 2.79510E-04 2.79510E-04 491302 + 525 491310 In-131 7.26930E-05 7.34350E-05 491310 + 526 491311 In-131m 7.26930E-05 7.26930E-05 491311 + 527 491312 In-131m 7.26930E-05 7.26930E-05 491312 + 528 491320 In-132 1.57270E-05 1.57270E-05 491320 + 529 491330 In-133 3.71740E-08 4.46590E-08 491330 + 530 491331 In-133m 7.48490E-09 7.48490E-09 491331 + 531 501170 Sn-117 2.53960E-12 4.30530E-04 50117.82c + 532 501171 Sn-117m 9.61740E-12 9.33530E-07 501171 + 533 501180 Sn-118 8.67440E-10 5.17770E-04 50118.82c + 534 501190 Sn-119 5.47070E-09 5.18740E-04 50119.82c + 535 501191 Sn-119m 2.07170E-08 1.78250E-04 501191 + 536 501210 Sn-121 8.15180E-11 4.89300E-04 501210 + 537 501211 Sn-121m 2.28080E-10 3.94950E-05 501211 + 538 501220 Sn-122 1.12030E-05 5.64090E-04 50122.82c + 539 501230 Sn-123 2.20940E-05 5.08180E-05 50123.82c + 540 501231 Sn-123m 7.89640E-06 4.45340E-04 501231 + 541 501240 Sn-124 1.18670E-04 5.24700E-04 50124.82c + 542 501250 Sn-125 1.46690E-04 2.44800E-04 50125.82c + 543 501251 Sn-125m 5.24280E-05 6.47110E-04 501251 + 544 501260 Sn-126 5.59550E-04 1.47770E-03 50126.82c + 545 501270 Sn-127 1.46170E-03 2.15040E-03 501270 + 546 501271 Sn-127m 5.22410E-04 2.06860E-03 501271 + 547 501280 Sn-128 1.39850E-03 7.05270E-03 501280 + 548 501281 Sn-128m 3.81200E-03 4.74340E-03 501281 + 549 501290 Sn-129 2.26220E-03 3.99180E-03 501290 + 550 501291 Sn-129m 6.32970E-03 6.49770E-03 501291 + 551 501300 Sn-130 2.38970E-03 2.76970E-03 501300 + 552 501301 Sn-130m 6.51380E-03 6.75580E-03 501301 + 553 501310 Sn-131 1.44600E-03 1.58680E-03 501310 + 554 501311 Sn-131m 4.04590E-03 4.12170E-03 501311 + 555 501320 Sn-132 2.31520E-03 2.33100E-03 501320 + 556 501330 Sn-133 2.43130E-04 2.43140E-04 501330 + 557 501340 Sn-134 3.40080E-05 3.40080E-05 501340 + 558 501350 Sn-135 3.49700E-07 3.49700E-07 501350 + 559 501360 Sn-136 7.22000E-09 7.22000E-09 501360 + 560 511230 Sb-123 3.11260E-11 4.96160E-04 51123.82c + 561 511240 Sb-124 1.16320E-06 2.99360E-06 51124.82c + 562 511241 Sb-124m 9.38330E-07 2.44060E-06 511241 + 563 511242 Sb-124m 1.50230E-06 1.50230E-06 511242 + 564 511250 Sb-125 3.32800E-05 9.25190E-04 51125.82c + 565 511260 Sb-126 1.76240E-05 2.10760E-05 51126.82c + 566 511261 Sb-126m 1.10080E-05 2.46540E-05 511261 + 567 511262 Sb-126m 1.36460E-05 1.36460E-05 511262 + 568 511270 Sb-127 2.41220E-04 4.46020E-03 511270 + 569 511280 Sb-128 3.37220E-04 7.40690E-03 511280 + 570 511281 Sb-128m 4.71650E-04 4.71650E-04 511281 + 571 511290 Sb-129 3.35060E-03 1.14510E-02 511290 + 572 511291 Sb-129m 2.47960E-03 5.72840E-03 511291 + 573 511300 Sb-130 4.90200E-03 1.10500E-02 511300 + 574 511301 Sb-130m 4.90200E-03 8.27990E-03 511301 + 575 511310 Sb-131 2.65410E-02 3.22500E-02 511310 + 576 511320 Sb-132 1.33380E-02 1.56690E-02 511320 + 577 511321 Sb-132m 1.18090E-02 1.18090E-02 511321 + 578 511330 Sb-133 2.63650E-02 2.66140E-02 511330 + 579 511340 Sb-134 1.72890E-03 1.75710E-03 511340 + 580 511341 Sb-134m 4.71240E-03 4.71250E-03 511341 + 581 511350 Sb-135 1.51460E-03 1.51490E-03 511350 + 582 511360 Sb-136 2.30120E-04 2.30120E-04 511360 + 583 511370 Sb-137 2.33490E-05 2.33490E-05 511370 + 584 511380 Sb-138 4.48920E-08 4.48920E-08 511380 + 585 521260 Te-126 9.01660E-10 4.22790E-05 52126.82c + 586 521270 Te-127 1.55530E-06 4.44840E-03 521270 + 587 521271 Te-127m 4.35180E-06 7.39370E-04 52527.82c + 588 521280 Te-128 2.34690E-05 7.88500E-03 52128.82c + 589 521290 Te-129 5.89320E-05 1.40200E-02 521290 + 590 521291 Te-129m 1.64890E-04 6.82020E-03 52529.82c + 591 521300 Te-130 1.54350E-03 2.08730E-02 52130.82c + 592 521310 Te-131 1.36700E-03 3.23800E-02 521310 + 593 521311 Te-131m 3.82490E-03 6.40680E-03 521311 + 594 521320 Te-132 1.87190E-02 4.61970E-02 52132.82c + 595 521330 Te-133 8.73730E-03 3.58360E-02 521330 + 596 521331 Te-133m 2.44470E-02 2.90500E-02 521331 + 597 521340 Te-134 4.72780E-02 5.39820E-02 521340 + 598 521350 Te-135 1.53800E-02 1.66950E-02 521350 + 599 521360 Te-136 7.31270E-03 7.51610E-03 521360 + 600 521370 Te-137 1.18890E-03 1.20080E-03 521370 + 601 521380 Te-138 3.57510E-04 3.57560E-04 521380 + 602 521390 Te-139 2.17540E-05 2.17540E-05 521390 + 603 521400 Te-140 6.06880E-06 6.06880E-06 521400 + 604 521410 Te-141 5.55160E-09 5.55160E-09 521410 + 605 531280 I-128 4.04590E-10 4.04590E-10 531280 + 606 531290 I-129 5.49270E-08 1.65430E-02 53129.82c + 607 531300 I-130 7.85670E-06 1.02780E-05 53130.82c + 608 531301 I-130m 2.88240E-06 2.88240E-06 531301 + 609 531310 I-131 1.62350E-04 3.76040E-02 53131.82c + 610 531320 I-132 4.47420E-04 4.69850E-02 531320 + 611 531321 I-132m 3.96130E-04 3.96130E-04 531321 + 612 531330 I-133 4.12180E-03 6.69740E-02 531330 + 613 531331 I-133m 3.05030E-03 3.05030E-03 531331 + 614 531340 I-134 1.01460E-02 7.29030E-02 531340 + 615 531341 I-134m 8.98250E-03 8.98250E-03 531341 + 616 531350 I-135 5.66220E-02 7.33170E-02 53135.82c + 617 531360 I-136 1.20210E-02 1.95550E-02 531360 + 618 531361 I-136m 3.27660E-02 3.27840E-02 531361 + 619 531370 I-137 3.60070E-02 3.71940E-02 531370 + 620 531380 I-138 1.31410E-02 1.34760E-02 531380 + 621 531390 I-139 8.50010E-03 8.52180E-03 531390 + 622 531400 I-140 1.87940E-03 1.88550E-03 531400 + 623 531410 I-141 3.41720E-04 3.41730E-04 531410 + 624 531420 I-142 3.68860E-05 3.68860E-05 531420 + 625 531430 I-143 3.69460E-06 3.69460E-06 531430 + 626 531440 I-144 1.07280E-09 1.07280E-09 531440 + 627 541310 Xe-131 3.41470E-09 3.76040E-02 54131.82c + 628 541311 Xe-131m 9.55430E-09 4.08460E-04 541311 + 629 541320 Xe-132 3.10090E-06 4.70480E-02 54132.82c + 630 541321 Xe-132m 4.15430E-06 4.15430E-06 541321 + 631 541330 Xe-133 1.24480E-05 6.70220E-02 54133.82c + 632 541331 Xe-133m 3.48270E-05 1.94120E-03 541331 + 633 541340 Xe-134 1.47340E-04 7.36590E-02 54134.82c + 634 541341 Xe-134m 4.01610E-04 6.08210E-04 541341 + 635 541350 Xe-135 7.18840E-04 7.59620E-02 54135.82c + 636 541351 Xe-135m 2.01130E-03 1.41150E-02 541351 + 637 541360 Xe-136 1.66350E-02 7.13920E-02 54136.82c + 638 541370 Xe-137 2.36540E-02 5.91450E-02 541370 + 639 541380 Xe-138 3.77450E-02 5.13420E-02 541380 + 640 541390 Xe-139 2.14060E-02 2.92680E-02 541390 + 641 541400 Xe-140 2.01430E-02 2.19250E-02 541400 + 642 541410 Xe-141 4.67450E-03 4.95370E-03 541410 + 643 541420 Xe-142 2.28630E-03 2.31540E-03 541420 + 644 541430 Xe-143 3.19690E-04 3.21910E-04 541430 + 645 541440 Xe-144 4.85910E-05 4.85920E-05 541440 + 646 541450 Xe-145 5.54410E-06 5.54410E-06 541450 + 647 541460 Xe-146 6.10230E-09 6.10230E-09 541460 + 648 551330 Cs-133 2.12660E-09 6.70220E-02 55133.82c + 649 551340 Cs-134 6.21950E-07 1.17260E-06 55134.82c + 650 551341 Cs-134m 5.50650E-07 5.50650E-07 551341 + 651 551350 Cs-135 1.45990E-05 7.60720E-02 55135.82c + 652 551351 Cs-135m 1.08040E-05 1.08040E-05 551351 + 653 551360 Cs-136 1.55330E-04 2.10860E-04 55136.82c + 654 551361 Cs-136m 1.11060E-04 1.11060E-04 551361 + 655 551370 Cs-137 2.98400E-03 6.21290E-02 55137.82c + 656 551380 Cs-138 4.25800E-03 6.13680E-02 551380 + 657 551381 Cs-138m 7.12100E-03 7.12100E-03 551381 + 658 551390 Cs-139 2.63300E-02 5.55980E-02 551390 + 659 551400 Cs-140 3.15870E-02 5.35140E-02 551400 + 660 551410 Cs-141 3.70890E-02 4.20490E-02 551410 + 661 551420 Cs-142 2.65890E-02 2.88990E-02 551420 + 662 551430 Cs-143 1.94470E-02 1.97670E-02 551430 + 663 551440 Cs-144 3.06310E-03 4.64200E-03 551440 + 664 551441 Cs-144m 3.06310E-03 3.06320E-03 551441 + 665 551450 Cs-145 1.71260E-03 1.71790E-03 551450 + 666 551460 Cs-146 3.21490E-04 3.21500E-04 551460 + 667 551470 Cs-147 4.74540E-05 4.74540E-05 551470 + 668 551480 Cs-148 6.86680E-06 6.86680E-06 551480 + 669 551490 Cs-149 4.06900E-10 4.06900E-10 551490 + 670 561360 Ba-136 2.45390E-07 2.67300E-04 56136.82c + 671 561361 Ba-136m 6.68860E-07 6.68860E-07 561361 + 672 561370 Ba-137 4.39180E-07 6.21310E-02 56137.82c + 673 561371 Ba-137m 1.22880E-06 5.86510E-02 561371 + 674 561380 Ba-138 2.12620E-04 6.29340E-02 56138.82c + 675 561390 Ba-139 9.75610E-04 5.65740E-02 561390 + 676 561400 Ba-140 4.07940E-03 5.75930E-02 56140.82c + 677 561410 Ba-141 5.96180E-03 4.80110E-02 561410 + 678 561420 Ba-142 1.93640E-02 4.85870E-02 561420 + 679 561430 Ba-143 2.10770E-02 4.06690E-02 561430 + 680 561440 Ba-144 2.15000E-02 2.77710E-02 561440 + 681 561450 Ba-145 7.86100E-03 9.37890E-03 561450 + 682 561460 Ba-146 5.27720E-03 5.56660E-03 561460 + 683 561470 Ba-147 1.03770E-03 1.07340E-03 561470 + 684 561480 Ba-148 3.08750E-04 3.13890E-04 561480 + 685 561490 Ba-149 3.19480E-05 3.19480E-05 561490 + 686 561500 Ba-150 1.28860E-07 1.28860E-07 561500 + 687 561510 Ba-151 1.53410E-09 1.53410E-09 561510 + 688 571380 La-138 1.60330E-09 1.60330E-09 57138.82c + 689 571390 La-139 6.62280E-06 5.65800E-02 57139.82c + 690 571400 La-140 8.10600E-05 5.76740E-02 57140.82c + 691 571410 La-141 3.82030E-04 4.83930E-02 571410 + 692 571420 La-142 1.31640E-03 4.99040E-02 571420 + 693 571430 La-143 6.70200E-03 4.73710E-02 571430 + 694 571440 La-144 1.35960E-02 4.13670E-02 571440 + 695 571450 La-145 2.17960E-02 3.11750E-02 571450 + 696 571460 La-146 5.99440E-03 1.15610E-02 571460 + 697 571461 La-146m 1.25760E-02 1.25760E-02 571461 + 698 571470 La-147 1.52740E-02 1.63490E-02 571470 + 699 571480 La-148 6.52760E-03 6.84040E-03 571480 + 700 571490 La-149 3.08150E-03 3.11330E-03 571490 + 701 571500 La-150 7.16840E-04 7.16970E-04 571500 + 702 571510 La-151 1.35020E-04 1.35020E-04 571510 + 703 571520 La-152 1.86980E-05 1.86980E-05 571520 + 704 571530 La-153 7.81610E-09 7.81610E-09 571530 + 705 571540 La-154 4.76230E-11 4.76230E-11 571540 + 706 581410 Ce-141 9.71530E-09 4.83930E-02 58141.82c + 707 581420 Ce-142 9.66730E-06 4.99140E-02 58142.82c + 708 581430 Ce-143 4.62790E-05 4.74170E-02 58143.82c + 709 581440 Ce-144 3.76530E-04 4.17430E-02 58144.82c + 710 581450 Ce-145 1.11230E-03 3.22870E-02 581450 + 711 581460 Ce-146 4.14370E-03 2.82800E-02 581460 + 712 581470 Ce-147 5.52520E-03 2.18740E-02 581470 + 713 581480 Ce-148 9.15310E-03 1.60370E-02 581480 + 714 581490 Ce-149 5.17870E-03 8.26780E-03 581490 + 715 581500 Ce-150 3.72760E-03 4.42520E-03 581500 + 716 581510 Ce-151 9.66740E-04 1.10290E-03 581510 + 717 581520 Ce-152 3.59630E-04 3.77200E-04 581520 + 718 581530 Ce-153 9.10730E-05 9.10810E-05 581530 + 719 581540 Ce-154 9.63720E-06 9.63720E-06 581540 + 720 581550 Ce-155 2.04030E-08 2.04030E-08 581550 + 721 581560 Ce-156 3.21910E-10 3.21910E-10 581560 + 722 591430 Pr-143 1.53850E-09 4.74170E-02 59143.82c + 723 591440 Pr-144 8.05880E-08 4.17440E-02 591440 + 724 591441 Pr-144m 8.19830E-07 5.76850E-04 591441 + 725 591450 Pr-145 1.66620E-05 3.23040E-02 591450 + 726 591460 Pr-146 1.10200E-04 2.83900E-02 591460 + 727 591470 Pr-147 5.60000E-04 2.24340E-02 591470 + 728 591480 Pr-148 2.85380E-04 1.63220E-02 591480 + 729 591481 Pr-148m 1.38350E-03 1.38350E-03 591481 + 730 591490 Pr-149 4.57960E-03 1.28470E-02 591490 + 731 591500 Pr-150 5.29380E-03 9.71900E-03 591500 + 732 591510 Pr-151 5.60240E-03 6.70530E-03 591510 + 733 591520 Pr-152 3.25410E-03 3.63190E-03 591520 + 734 591530 Pr-153 2.31520E-03 2.40580E-03 591530 + 735 591540 Pr-154 5.40330E-04 5.49910E-04 591540 + 736 591550 Pr-155 1.57360E-04 1.57380E-04 591550 + 737 591560 Pr-156 5.12430E-05 5.12430E-05 591560 + 738 591570 Pr-157 4.38890E-08 4.38890E-08 591570 + 739 591580 Pr-158 3.66500E-10 3.66500E-10 591580 + 740 591590 Pr-159 2.40780E-12 2.40780E-12 591590 + 741 601460 Nd-146 5.08510E-09 2.83900E-02 60146.82c + 742 601470 Nd-147 1.72690E-07 2.24340E-02 60147.82c + 743 601480 Nd-148 1.17750E-05 1.77180E-02 60148.82c + 744 601490 Nd-149 4.09700E-05 1.28880E-02 601490 + 745 601500 Nd-150 2.45340E-04 9.96440E-03 60150.82c + 746 601510 Nd-151 4.75350E-04 7.18060E-03 601510 + 747 601520 Nd-152 9.18340E-04 4.55020E-03 601520 + 748 601530 Nd-153 1.06270E-03 3.46850E-03 601530 + 749 601540 Nd-154 8.87280E-04 1.43720E-03 601540 + 750 601550 Nd-155 4.66990E-04 6.25760E-04 601550 + 751 601560 Nd-156 1.57340E-04 2.07190E-04 601560 + 752 601570 Nd-157 4.65640E-05 4.66050E-05 601570 + 753 601580 Nd-158 1.17010E-06 1.17050E-06 601580 + 754 601590 Nd-159 3.37280E-08 3.37300E-08 601590 + 755 601600 Nd-160 5.55200E-10 5.55200E-10 601600 + 756 601610 Nd-161 3.86950E-12 3.86950E-12 601610 + 757 611490 Pm-149 1.30210E-08 1.28880E-02 61149.82c + 758 611500 Pm-150 3.31680E-06 3.31680E-06 611500 + 759 611510 Pm-151 1.65100E-05 7.19720E-03 61151.82c + 760 611520 Pm-152 1.23050E-05 4.56250E-03 611520 + 761 611521 Pm-152m 2.58690E-05 2.58690E-05 611521 + 762 611522 Pm-152m 3.37910E-05 3.37910E-05 611522 + 763 611530 Pm-153 3.00880E-04 3.76940E-03 611530 + 764 611540 Pm-154 2.15100E-04 1.65230E-03 611540 + 765 611541 Pm-154m 2.15100E-04 2.15100E-04 611541 + 766 611550 Pm-155 8.08520E-04 1.43430E-03 611550 + 767 611560 Pm-156 6.32710E-04 8.39900E-04 611560 + 768 611570 Pm-157 3.44590E-04 3.91190E-04 611570 + 769 611580 Pm-158 1.22850E-04 1.24020E-04 611580 + 770 611590 Pm-159 1.70240E-05 1.70580E-05 611590 + 771 611600 Pm-160 4.12910E-06 4.12970E-06 611600 + 772 611610 Pm-161 2.06500E-08 2.06540E-08 611610 + 773 611620 Pm-162 5.64410E-10 5.64410E-10 611620 + 774 611630 Pm-163 9.57410E-12 9.57410E-12 611630 + 775 621510 Sm-151 1.10170E-06 7.19820E-03 62151.82c + 776 621520 Sm-152 3.01450E-08 4.62220E-03 62152.82c + 777 621530 Sm-153 1.59630E-07 3.77000E-03 62153.82c + 778 621531 Sm-153m 4.46630E-07 4.46630E-07 621531 + 779 621540 Sm-154 3.85500E-06 1.87120E-03 62154.82c + 780 621550 Sm-155 2.77600E-05 1.46200E-03 621550 + 781 621560 Sm-156 7.66010E-05 9.16500E-04 621560 + 782 621570 Sm-157 5.58860E-05 4.47080E-04 621570 + 783 621580 Sm-158 3.07150E-05 1.54740E-04 621580 + 784 621590 Sm-159 3.40490E-05 5.11150E-05 621590 + 785 621600 Sm-160 1.65170E-05 2.06360E-05 621600 + 786 621610 Sm-161 1.86660E-06 1.88730E-06 621610 + 787 621620 Sm-162 3.45200E-07 3.45760E-07 621620 + 788 621630 Sm-163 1.77570E-08 1.77670E-08 621630 + 789 621640 Sm-164 1.43780E-09 1.43780E-09 621640 + 790 621650 Sm-165 2.09010E-11 2.09010E-11 621650 + 791 631540 Eu-154 5.49960E-10 1.14290E-09 63154.82c + 792 631541 Eu-154m 5.92940E-10 5.92940E-10 631541 + 793 631550 Eu-155 4.63500E-08 1.46210E-03 63155.82c + 794 631560 Eu-156 5.27100E-07 9.17030E-04 63156.82c + 795 631570 Eu-157 1.39710E-05 4.61050E-04 63157.82c + 796 631580 Eu-158 8.77590E-06 1.63520E-04 631580 + 797 631590 Eu-159 2.55380E-05 7.66530E-05 631590 + 798 631600 Eu-160 4.12920E-06 2.47650E-05 631600 + 799 631610 Eu-161 9.78050E-06 1.16680E-05 631610 + 800 631620 Eu-162 5.79620E-06 6.14200E-06 631620 + 801 631630 Eu-163 2.58150E-06 2.59930E-06 631630 + 802 631640 Eu-164 2.13120E-06 2.13260E-06 631640 + 803 631650 Eu-165 2.08430E-08 2.08640E-08 631650 + 804 631660 Eu-166 9.03810E-10 9.03810E-10 631660 + 805 631670 Eu-167 2.95760E-11 2.95760E-11 631670 + 806 641560 Gd-156 9.65760E-11 9.17030E-04 64156.82c + 807 641570 Gd-157 1.91510E-09 4.61050E-04 64157.82c + 808 641580 Gd-158 2.60870E-08 1.63540E-04 64158.82c + 809 641590 Gd-159 1.67950E-07 7.68200E-05 641590 + 810 641600 Gd-160 6.23350E-07 2.53880E-05 64160.82c + 811 641610 Gd-161 1.03040E-06 1.26980E-05 641610 + 812 641620 Gd-162 2.27250E-06 8.41450E-06 641620 + 813 641630 Gd-163 1.48040E-06 4.07970E-06 641630 + 814 641640 Gd-164 1.71860E-06 3.85120E-06 641640 + 815 641650 Gd-165 4.16730E-07 4.37590E-07 641650 + 816 641660 Gd-166 1.12660E-07 1.13560E-07 641660 + 817 641670 Gd-167 1.05330E-08 1.05630E-08 641670 + 818 641680 Gd-168 8.90800E-10 8.90800E-10 641680 + 819 641690 Gd-169 2.97750E-11 2.97750E-11 641690 + 820 651590 Tb-159 4.33410E-11 7.68200E-05 65159.82c + 821 651600 Tb-160 4.90150E-10 4.90150E-10 65160.82c + 822 651610 Tb-161 5.63340E-09 1.27040E-05 651610 + 823 651620 Tb-162 3.44020E-08 8.44890E-06 651620 + 824 651630 Tb-163 1.34020E-07 4.21370E-06 651630 + 825 651640 Tb-164 3.58000E-07 4.20920E-06 651640 + 826 651650 Tb-165 4.39090E-07 8.76680E-07 651650 + 827 651660 Tb-166 2.53830E-07 3.67390E-07 651660 + 828 651670 Tb-167 1.27660E-07 1.38220E-07 651670 + 829 651680 Tb-168 2.71440E-08 2.80350E-08 651680 + 830 651690 Tb-169 5.88070E-09 5.91050E-09 651690 + 831 651700 Tb-170 4.34370E-10 4.34370E-10 651700 + 832 651710 Tb-171 2.89070E-11 2.89070E-11 651710 + 833 661620 Dy-162 2.25290E-11 8.44890E-06 66162.82c + 834 661630 Dy-163 2.64810E-10 4.21390E-06 66163.82c + 835 661640 Dy-164 4.79220E-09 4.21400E-06 66164.82c + 836 661650 Dy-165 1.38300E-08 8.92310E-07 661650 + 837 661651 Dy-165m 1.84130E-09 1.84130E-09 661651 + 838 661660 Dy-166 5.17510E-08 4.19150E-07 661660 + 839 661670 Dy-167 5.76230E-08 1.95850E-07 661670 + 840 661680 Dy-168 6.12870E-08 8.93220E-08 661680 + 841 661690 Dy-169 2.90600E-08 3.49710E-08 661690 + 842 661700 Dy-170 1.20620E-08 1.24960E-08 661700 + 843 661710 Dy-171 2.10880E-09 2.13770E-09 661710 + 844 661720 Dy-172 3.53780E-10 3.53780E-10 661720 + 845 661730 Dy-173 2.03810E-11 2.03810E-11 661730 + 846 671650 Ho-165 1.68800E-11 8.92370E-07 67165.82c + 847 671660 Ho-166 4.42940E-11 4.19190E-07 671660 + 848 671661 Ho-166m 1.20740E-10 1.20740E-10 671661 + 849 671670 Ho-167 1.20620E-09 1.97050E-07 671670 + 850 671680 Ho-168 1.22660E-09 9.25890E-08 671680 + 851 671681 Ho-168m 2.05140E-09 2.05140E-09 671681 + 852 671690 Ho-169 8.48830E-09 4.34590E-08 671690 + 853 671700 Ho-170 5.54880E-09 5.54880E-09 671700 + 854 671701 Ho-170m 2.03570E-09 1.45320E-08 671701 + 855 671710 Ho-171 6.66840E-09 8.80610E-09 671710 + 856 671720 Ho-172 2.53630E-09 2.89010E-09 671720 + 857 671730 Ho-173 8.59640E-10 8.80020E-10 671730 + 858 671740 Ho-174 1.09240E-10 1.09240E-10 671740 + 859 671750 Ho-175 1.45420E-11 1.45420E-11 671750 + 860 681680 Er-168 8.88650E-12 9.26090E-08 68168.82c + 861 681690 Er-169 6.64370E-11 4.35250E-08 681690 + 862 681700 Er-170 3.75490E-10 2.04560E-08 68170.82c + 863 681710 Er-171 8.05980E-10 9.61210E-09 681710 + 864 681720 Er-172 1.60870E-09 4.49880E-09 681720 + 865 681730 Er-173 1.15780E-09 2.03780E-09 681730 + 866 681740 Er-174 7.55580E-10 8.64820E-10 681740 + 867 681750 Er-175 2.38030E-10 2.52570E-10 681750 + 868 681760 Er-176 6.86670E-11 6.86670E-11 681760 + 869 681770 Er-177 6.98060E-12 6.98060E-12 681770 + 870 691710 Tm-171 3.53320E-12 9.61560E-09 691710 + 871 691720 Tm-172 1.97430E-11 4.51850E-09 691720 + 872 691730 Tm-173 8.61940E-11 2.12400E-09 691730 + 873 691740 Tm-174 1.31230E-10 9.96050E-10 691740 + 874 691750 Tm-175 2.10550E-10 4.63120E-10 691750 + 875 691760 Tm-176 1.29320E-10 1.97990E-10 691760 + 876 691770 Tm-177 6.98230E-11 7.68040E-11 691770 + 877 691780 Tm-178 1.61450E-11 1.61450E-11 691780 + 878 691790 Tm-179 3.74110E-12 3.74110E-12 691790 + 879 701740 Yb-174 1.41500E-12 9.97460E-10 701740 + 880 701750 Yb-175 5.41030E-12 4.69250E-10 701750 + 881 701751 Yb-175m 7.20360E-13 3.57320E-10 701751 + 882 701760 Yb-176 7.04700E-12 2.08440E-10 701760 + 883 701761 Yb-176m 1.47840E-11 1.13780E-10 701761 + 884 701770 Yb-177 2.19700E-11 1.03200E-10 701770 + 885 701771 Yb-177m 4.42360E-12 8.12270E-11 701771 + 886 701780 Yb-178 3.05840E-11 4.67290E-11 701780 + 887 701790 Yb-179 1.53720E-11 1.91130E-11 701790 + 888 701800 Yb-180 6.75630E-12 6.75630E-12 701800 + 889 701810 Yb-181 1.28820E-12 1.28820E-12 701810 + 890 711780 Lu-178 5.74250E-13 4.73030E-11 711780 + 891 711790 Lu-179 3.30110E-12 2.28540E-11 711790 + 892 711791 Lu-179m 4.39520E-13 1.95530E-11 711791 + 893 711800 Lu-180 9.45760E-13 5.63410E-12 711800 + 894 711801 Lu-180m 9.45760E-13 7.70210E-12 711801 + 895 711802 Lu-180m 1.67470E-12 1.67470E-12 711802 + 896 711810 Lu-181 3.40740E-12 4.69560E-12 711810 + + Nuclide 93238.82c -- neptunium 238 (Np-238) + + Neutron-induced fission: + + Interpolation region : 1 / 2 + Interpolation energy : 2.53000E-08 MeV + Number of products : 964 / 1066 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 2.94220E-05 2.94220E-05 1001.82c + 2 10020 H-2 8.99170E-06 8.99170E-06 1002.82c + 3 10030 H-3 1.25000E-04 1.25000E-04 1003.82c + 4 20040 He-4 1.86000E-03 1.86000E-03 2004.82c + 5 200500 Ca-50 3.06960E-12 3.06960E-12 200500 + 6 200510 Ca-51 2.70200E-12 2.70200E-12 200510 + 7 200520 Ca-52 2.64890E-12 2.64890E-12 200520 + 8 210500 Sc-50 7.73470E-13 4.13080E-12 210500 + 9 210501 Sc-50m 3.30230E-13 3.39980E-12 210501 + 10 210510 Sc-51 5.17200E-12 7.92700E-12 210510 + 11 210520 Sc-52 9.34910E-12 1.19450E-11 210520 + 12 210530 Sc-53 1.64440E-11 1.64440E-11 210530 + 13 210540 Sc-54 1.07430E-11 1.07430E-11 210540 + 14 210550 Sc-55 8.46500E-12 8.46500E-12 210550 + 15 210560 Sc-56 2.07490E-12 2.07490E-12 210560 + 16 220520 Ti-52 3.50420E-12 1.54490E-11 220520 + 17 220530 Ti-53 1.12420E-11 2.76860E-11 220530 + 18 220540 Ti-54 3.92370E-11 4.99800E-11 220540 + 19 220550 Ti-55 5.86870E-11 6.71520E-11 220550 + 20 220560 Ti-56 8.74760E-11 8.95510E-11 220560 + 21 220570 Ti-57 4.54320E-11 4.54320E-11 220570 + 22 220580 Ti-58 2.69510E-11 2.69510E-11 220580 + 23 220590 Ti-59 5.31530E-12 5.31530E-12 220590 + 24 230540 V-54 4.07980E-12 5.40600E-11 230540 + 25 230550 V-55 3.38280E-11 1.00980E-10 230550 + 26 230560 V-56 9.08710E-11 1.80560E-10 230560 + 27 230570 V-57 2.56420E-10 3.01720E-10 230570 + 28 230580 V-58 2.99350E-10 3.26300E-10 230580 + 29 230590 V-59 3.73270E-10 3.78580E-10 230590 + 30 230600 V-60 1.48550E-10 1.48550E-10 230600 + 31 230610 V-61 6.83050E-11 6.83050E-11 230610 + 32 230620 V-62 1.07980E-11 1.07980E-11 230620 + 33 230630 V-63 1.45810E-12 1.45810E-12 230630 + 34 240560 Cr-56 9.45840E-12 1.91220E-10 240560 + 35 240570 Cr-57 5.20390E-11 6.13590E-10 240570 + 36 240580 Cr-58 3.28310E-10 3.93570E-10 240580 + 37 240590 Cr-59 7.39080E-10 1.11770E-09 240590 + 38 240600 Cr-60 1.64310E-09 1.79570E-09 240600 + 39 240610 Cr-61 1.54650E-09 1.61070E-09 240610 + 40 240620 Cr-62 1.60260E-09 1.61390E-09 240620 + 41 240630 Cr-63 5.11000E-10 5.11950E-10 240630 + 42 240640 Cr-64 1.67910E-10 1.67910E-10 240640 + 43 240650 Cr-65 2.07850E-11 2.07850E-11 240650 + 44 240660 Cr-66 2.22480E-12 2.22480E-12 240660 + 45 250580 Mn-58 8.13330E-12 4.01700E-10 250580 + 46 250590 Mn-59 1.22680E-10 1.24030E-09 250590 + 47 250600 Mn-60 5.19770E-11 1.90080E-09 250600 + 48 250601 Mn-60m 4.61630E-10 4.61630E-10 250601 + 49 250610 Mn-61 2.57700E-09 4.18770E-09 250610 + 50 250620 Mn-62 4.14990E-09 4.95690E-09 250620 + 51 250621 Mn-62m 7.45000E-10 1.55200E-09 250621 + 52 250630 Mn-63 9.03320E-09 9.54520E-09 250630 + 53 250640 Mn-64 6.31810E-09 6.48600E-09 250640 + 54 250650 Mn-65 5.29380E-09 5.31460E-09 250650 + 55 250660 Mn-66 1.36940E-09 1.37160E-09 250660 + 56 250670 Mn-67 3.45150E-10 3.45150E-10 250670 + 57 250680 Mn-68 3.16730E-11 3.16730E-11 250680 + 58 250690 Mn-69 2.69260E-12 2.69260E-12 250690 + 59 260600 Fe-60 1.35200E-11 2.32290E-09 260600 + 60 260610 Fe-61 1.44480E-10 4.33220E-09 260610 + 61 260620 Fe-62 1.58930E-09 8.09810E-09 260620 + 62 260630 Fe-63 5.37750E-09 1.49230E-08 260630 + 63 260640 Fe-64 2.00480E-08 2.65340E-08 260640 + 64 260650 Fe-65 3.16190E-08 3.69340E-08 260650 + 65 260660 Fe-66 4.92280E-08 5.06000E-08 260660 + 66 260670 Fe-67 2.73950E-08 2.77400E-08 260670 + 67 260680 Fe-68 1.74910E-08 1.75230E-08 260680 + 68 260690 Fe-69 3.65160E-09 3.65370E-09 260690 + 69 260700 Fe-70 1.06990E-09 1.06990E-09 260700 + 70 260710 Fe-71 3.40170E-11 3.40170E-11 260710 + 71 260720 Fe-72 3.17680E-12 3.17680E-12 260720 + 72 270620 Co-62 3.17270E-12 8.10140E-09 270620 + 73 270621 Co-62m 7.43130E-12 7.43130E-12 270621 + 74 270630 Co-63 2.35320E-10 1.51580E-08 270630 + 75 270640 Co-64 1.79690E-09 2.83310E-08 270640 + 76 270650 Co-65 1.58390E-08 5.27730E-08 270650 + 77 270660 Co-66 4.45260E-08 9.51260E-08 270660 + 78 270670 Co-67 1.33870E-07 1.61610E-07 270670 + 79 270680 Co-68 8.84930E-08 1.36420E-07 270680 + 80 270681 Co-68m 7.80670E-08 9.58460E-08 270681 + 81 270690 Co-69 2.17670E-07 2.21070E-07 270690 + 82 270700 Co-70 7.27400E-08 7.27400E-08 270700 + 83 270701 Co-70m 7.27400E-08 7.38100E-08 270701 + 84 270710 Co-71 3.29520E-08 3.29860E-08 270710 + 85 270720 Co-72 7.82620E-09 7.82940E-09 270720 + 86 270730 Co-73 1.14830E-09 1.14830E-09 270730 + 87 270740 Co-74 1.33640E-11 1.33640E-11 270740 + 88 280640 Ni-64 1.10190E-11 2.83420E-08 28064.82c + 89 280650 Ni-65 2.23400E-10 5.29960E-08 280650 + 90 280660 Ni-66 3.97290E-09 9.90990E-08 280660 + 91 280670 Ni-67 2.35200E-08 1.85130E-07 280670 + 92 280680 Ni-68 1.59050E-07 3.45600E-07 280680 + 93 280690 Ni-69 1.87280E-07 4.06140E-07 280690 + 94 280691 Ni-69m 1.87280E-07 1.87280E-07 280691 + 95 280700 Ni-70 1.80110E-06 1.94760E-06 280700 + 96 280710 Ni-71 6.36510E-07 6.69500E-07 280710 + 97 280720 Ni-72 9.82070E-07 9.89900E-07 280720 + 98 280730 Ni-73 3.38000E-07 3.39150E-07 280730 + 99 280740 Ni-74 2.86100E-08 2.86230E-08 280740 + 100 280750 Ni-75 4.64270E-09 4.64270E-09 280750 + 101 280760 Ni-76 9.46310E-10 9.46310E-10 280760 + 102 280770 Ni-77 4.64220E-11 4.64220E-11 280770 + 103 290660 Cu-66 5.98100E-12 9.91040E-08 290660 + 104 290670 Cu-67 2.47970E-10 1.85380E-07 290670 + 105 290680 Cu-68 1.11830E-09 3.48920E-07 290680 + 106 290681 Cu-68m 2.61920E-09 2.61920E-09 290681 + 107 290690 Cu-69 5.35580E-08 6.46970E-07 290690 + 108 290700 Cu-70 2.86680E-08 2.37760E-07 290700 + 109 290701 Cu-70m 3.19380E-07 4.18190E-07 290701 + 110 290702 Cu-70m 2.86680E-08 1.97630E-06 290702 + 111 290710 Cu-71 1.61720E-06 2.28670E-06 290710 + 112 290720 Cu-72 2.59820E-06 3.58810E-06 290720 + 113 290730 Cu-73 5.12610E-06 5.46520E-06 290730 + 114 290740 Cu-74 9.14350E-07 9.43050E-07 290740 + 115 290750 Cu-75 2.59590E-06 2.60050E-06 290750 + 116 290760 Cu-76 6.65550E-07 6.66020E-07 290760 + 117 290761 Cu-76m 6.65550E-07 6.66020E-07 290761 + 118 290770 Cu-77 1.75860E-07 1.75910E-07 290770 + 119 290780 Cu-78 1.48980E-08 1.48980E-08 290780 + 120 290790 Cu-79 1.70310E-09 1.70310E-09 290790 + 121 290800 Cu-80 5.94550E-11 5.94550E-11 290800 + 122 300680 Zn-68 5.02960E-12 3.49340E-07 300680 + 123 300690 Zn-69 3.29140E-11 6.47150E-07 300690 + 124 300691 Zn-69m 1.42350E-10 1.42350E-10 300691 + 125 300700 Zn-70 8.41170E-09 2.33280E-06 300700 + 126 300710 Zn-71 8.33100E-09 2.29500E-06 300710 + 127 300711 Zn-71m 3.60300E-08 3.60300E-08 300711 + 128 300720 Zn-72 7.29930E-07 4.31800E-06 300720 + 129 300730 Zn-73 2.62670E-07 7.10410E-06 300730 + 130 300731 Zn-73m 3.59080E-07 1.37610E-06 300731 + 131 300732 Zn-73m 2.03410E-06 2.03410E-06 300732 + 132 300740 Zn-74 3.47290E-06 4.50700E-06 300740 + 133 300750 Zn-75 6.05570E-06 8.58510E-06 300750 + 134 300760 Zn-76 1.59790E-05 1.72910E-05 300760 + 135 300770 Zn-77 1.59350E-05 1.73290E-05 300770 + 136 300771 Zn-77m 2.43600E-06 2.43600E-06 300771 + 137 300780 Zn-78 2.14090E-05 2.14250E-05 300780 + 138 300790 Zn-79 8.09380E-06 8.09460E-06 300790 + 139 300800 Zn-80 5.74270E-06 5.74280E-06 300800 + 140 300810 Zn-81 3.07550E-08 3.07550E-08 300810 + 141 300820 Zn-82 1.75230E-09 1.75230E-09 300820 + 142 300830 Zn-83 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3.66600E-04 421090 + 379 421100 Mo-110 7.85440E-05 7.85450E-05 421100 + 380 421110 Mo-111 1.55350E-05 1.55350E-05 421110 + 381 421120 Mo-112 1.57320E-09 1.57320E-09 421120 + 382 421130 Mo-113 1.12690E-11 1.12690E-11 421130 + 383 431000 Tc-100 9.54630E-07 9.54630E-07 431000 + 384 431010 Tc-101 1.88660E-05 6.94080E-02 431010 + 385 431020 Tc-102 1.02560E-04 6.91710E-02 431020 + 386 431021 Tc-102m 1.02560E-04 1.02560E-04 431021 + 387 431030 Tc-103 1.13390E-03 6.71340E-02 431030 + 388 431040 Tc-104 3.06880E-03 5.71110E-02 431040 + 389 431050 Tc-105 7.38040E-03 4.14320E-02 431050 + 390 431060 Tc-106 8.56850E-03 2.73540E-02 431060 + 391 431070 Tc-107 8.74600E-03 1.44670E-02 431070 + 392 431080 Tc-108 5.99520E-03 8.27670E-03 431080 + 393 431090 Tc-109 2.87300E-03 3.23760E-03 431090 + 394 431100 Tc-110 8.32930E-04 9.11640E-04 431100 + 395 431110 Tc-111 3.40890E-04 3.56260E-04 431110 + 396 431120 Tc-112 3.72650E-05 3.72660E-05 431120 + 397 431130 Tc-113 8.62060E-06 8.62060E-06 431130 + 398 431140 Tc-114 2.31230E-06 2.31230E-06 431140 + 399 431150 Tc-115 7.46800E-11 7.46800E-11 431150 + 400 441010 Ru-101 1.04810E-06 6.94090E-02 44101.82c + 401 441020 Ru-102 4.87020E-09 6.92740E-02 44102.82c + 402 441030 Ru-103 6.48330E-06 6.71560E-02 44103.82c + 403 441031 Ru-103m 1.56520E-05 1.56520E-05 441031 + 404 441040 Ru-104 9.78350E-05 5.72090E-02 44104.82c + 405 441050 Ru-105 4.15900E-04 4.18480E-02 44105.82c + 406 441060 Ru-106 1.19520E-03 2.85490E-02 44106.82c + 407 441070 Ru-107 1.53620E-03 1.60030E-02 441070 + 408 441080 Ru-108 2.67830E-03 1.09580E-02 441080 + 409 441090 Ru-109 1.77020E-03 5.00560E-03 441090 + 410 441100 Ru-110 1.31090E-03 2.22220E-03 441100 + 411 441110 Ru-111 5.79130E-04 9.35950E-04 441110 + 412 441120 Ru-112 1.51730E-04 1.89060E-04 441120 + 413 441130 Ru-113 1.44520E-05 2.98310E-05 441130 + 414 441131 Ru-113m 1.44520E-05 1.44520E-05 441131 + 415 441140 Ru-114 1.52940E-05 1.74550E-05 441140 + 416 441150 Ru-115 3.46640E-06 3.46650E-06 441150 + 417 441160 Ru-116 1.46490E-08 1.46490E-08 441160 + 418 441170 Ru-117 5.24270E-10 5.24270E-10 441170 + 419 441180 Ru-118 1.00790E-11 1.00790E-11 441180 + 420 441200 Ru-120 5.67480E-09 5.67480E-09 441200 + 421 451050 Rh-105 1.33620E-08 4.18480E-02 45105.82c + 422 451051 Rh-105m 2.04270E-09 1.18800E-02 451051 + 423 451060 Rh-106 1.71170E-06 2.85510E-02 451060 + 424 451061 Rh-106m 4.00930E-06 4.00930E-06 451061 + 425 451070 Rh-107 2.57180E-05 1.60290E-02 451070 + 426 451080 Rh-108 2.00490E-05 1.09780E-02 451080 + 427 451081 Rh-108m 6.05000E-05 6.05000E-05 451081 + 428 451090 Rh-109 1.43980E-04 5.14960E-03 451090 + 429 451100 Rh-110 1.38210E-04 2.36040E-03 451100 + 430 451101 Rh-110m 3.68940E-06 3.68940E-06 451101 + 431 451110 Rh-111 1.97090E-04 1.13300E-03 451110 + 432 451120 Rh-112 6.94650E-05 2.58520E-04 451120 + 433 451121 Rh-112m 6.94650E-05 6.94650E-05 451121 + 434 451130 Rh-113 8.28710E-05 1.19930E-04 451130 + 435 451140 Rh-114 3.40880E-05 5.15510E-05 451140 + 436 451141 Rh-114m 3.40880E-05 3.40880E-05 451141 + 437 451150 Rh-115 4.48250E-05 4.82840E-05 451150 + 438 451160 Rh-116 8.27710E-06 8.29160E-06 451160 + 439 451161 Rh-116m 1.93870E-05 1.93870E-05 451161 + 440 451170 Rh-117 7.24670E-06 7.24720E-06 451170 + 441 451180 Rh-118 3.38150E-06 3.38150E-06 451180 + 442 451190 Rh-119 1.49640E-06 1.49640E-06 451190 + 443 451200 Rh-120 1.48150E-06 1.48720E-06 451200 + 444 451210 Rh-121 2.70720E-07 2.70720E-07 451210 + 445 451220 Rh-122 1.66740E-08 1.66740E-08 451220 + 446 461060 Pd-106 1.14850E-06 2.85560E-02 46106.82c + 447 461070 Pd-107 1.47920E-10 1.60290E-02 46107.82c + 448 461071 Pd-107m 2.77990E-10 2.77990E-10 461071 + 449 461080 Pd-108 2.56210E-06 1.10410E-02 46108.82c + 450 461090 Pd-109 9.95330E-08 5.14990E-03 461090 + 451 461091 Pd-109m 1.87060E-07 2.57500E-03 461091 + 452 461100 Pd-110 5.07880E-06 2.36910E-03 46110.82c + 453 461110 Pd-111 2.38270E-06 1.13750E-03 461110 + 454 461111 Pd-111m 4.47800E-06 9.01020E-06 461111 + 455 461120 Pd-112 9.41340E-06 3.37400E-04 461120 + 456 461130 Pd-113 5.32020E-06 1.38090E-04 461130 + 457 461131 Pd-113m 1.28440E-05 1.28440E-05 461131 + 458 461140 Pd-114 3.08280E-05 1.16470E-04 461140 + 459 461150 Pd-115 1.58970E-05 6.01200E-05 461150 + 460 461151 Pd-115m 2.98750E-05 3.68860E-05 461151 + 461 461160 Pd-116 4.94240E-05 7.71030E-05 461160 + 462 461170 Pd-117 2.10020E-05 6.78170E-05 461170 + 463 461171 Pd-117m 3.94690E-05 3.94690E-05 461171 + 464 461180 Pd-118 2.48370E-05 2.81200E-05 461180 + 465 461190 Pd-119 1.94760E-05 2.10610E-05 461190 + 466 461200 Pd-120 1.03810E-05 1.18170E-05 461200 + 467 461210 Pd-121 1.48230E-06 1.71630E-06 461210 + 468 461220 Pd-122 1.51390E-06 1.53060E-06 461220 + 469 461230 Pd-123 9.46360E-07 9.46360E-07 461230 + 470 461240 Pd-124 1.93230E-07 1.93230E-07 461240 + 471 471100 Ag-110 1.49480E-10 1.54240E-10 471100 + 472 471101 Ag-110m 3.50130E-10 3.50130E-10 47510.82c + 473 471110 Ag-111 1.85490E-09 1.13430E-03 47111.82c + 474 471111 Ag-111m 1.21340E-08 1.13120E-03 471111 + 475 471120 Ag-112 7.96700E-08 3.37480E-04 471120 + 476 471130 Ag-113 7.82780E-08 9.08940E-05 471130 + 477 471131 Ag-113m 5.12050E-07 1.32750E-04 471131 + 478 471140 Ag-114 2.21300E-07 1.17620E-04 471140 + 479 471141 Ag-114m 9.30700E-07 9.30700E-07 471141 + 480 471150 Ag-115 1.06500E-06 5.69510E-05 471150 + 481 471151 Ag-115m 6.96680E-06 5.71350E-05 471151 + 482 471160 Ag-116 4.12330E-06 8.18050E-05 471160 + 483 471161 Ag-116m 9.65770E-06 9.65770E-06 471161 + 484 471170 Ag-117 6.06650E-06 4.43900E-05 471170 + 485 471171 Ag-117m 3.96840E-05 7.35920E-05 471171 + 486 471180 Ag-118 9.94810E-06 5.28500E-05 471180 + 487 471181 Ag-118m 4.18380E-05 4.58580E-05 471181 + 488 471190 Ag-119 8.93470E-06 1.94650E-05 471190 + 489 471191 Ag-119m 5.84460E-05 6.89770E-05 471191 + 490 471200 Ag-120 2.02720E-05 3.90150E-05 471200 + 491 471201 Ag-120m 2.87660E-05 3.46740E-05 471201 + 492 471210 Ag-121 2.82450E-05 2.99570E-05 471210 + 493 471220 Ag-122 8.79690E-06 1.03280E-05 471220 + 494 471221 Ag-122m 7.92410E-06 7.92410E-06 471221 + 495 471230 Ag-123 1.23520E-05 1.32980E-05 471230 + 496 471240 Ag-124 5.74240E-06 8.52190E-06 471240 + 497 471241 Ag-124m 5.17260E-06 5.17260E-06 471241 + 498 471250 Ag-125 4.93970E-06 4.93970E-06 471250 + 499 471260 Ag-126 3.34510E-06 3.34510E-06 471260 + 500 471270 Ag-127 3.15050E-06 3.15050E-06 471270 + 501 471280 Ag-128 4.62280E-08 4.62280E-08 471280 + 502 471290 Ag-129 2.27760E-09 2.27760E-09 471290 + 503 481120 Cd-112 1.19180E-11 3.37480E-04 48112.82c + 504 481130 Cd-113 4.83650E-11 1.37110E-04 48113.82c + 505 481131 Cd-113m 1.58230E-10 1.57160E-06 481131 + 506 481140 Cd-114 7.62620E-09 1.17630E-04 48114.82c + 507 481150 Cd-115 2.17570E-08 9.75130E-05 481150 + 508 481151 Cd-115m 7.11820E-08 4.66700E-06 48515.82c + 509 481160 Cd-116 1.13430E-06 9.20180E-05 48116.82c + 510 481170 Cd-117 1.41130E-06 9.03280E-05 481170 + 511 481171 Cd-117m 4.61720E-06 2.92680E-05 481171 + 512 481180 Cd-118 1.57430E-05 9.56490E-05 481180 + 513 481190 Cd-119 5.69190E-06 8.44020E-05 481190 + 514 481191 Cd-119m 1.37410E-05 2.34740E-05 481191 + 515 481200 Cd-120 8.15230E-05 1.42380E-04 481200 + 516 481210 Cd-121 1.69810E-05 4.38080E-05 481210 + 517 481211 Cd-121m 4.09950E-05 4.41260E-05 481211 + 518 481220 Cd-122 7.06630E-05 8.89150E-05 481220 + 519 481230 Cd-123 1.39270E-05 2.48110E-05 481230 + 520 481231 Cd-123m 3.36210E-05 3.60440E-05 481231 + 521 481240 Cd-124 1.13300E-04 1.24400E-04 481240 + 522 481250 Cd-125 6.05220E-05 6.29920E-05 481250 + 523 481251 Cd-125m 1.46110E-04 1.48580E-04 481251 + 524 481260 Cd-126 3.78720E-04 3.82070E-04 481260 + 525 481270 Cd-127 2.84340E-04 2.87490E-04 481270 + 526 481280 Cd-128 1.11230E-04 1.11280E-04 481280 + 527 481290 Cd-129 1.02790E-05 1.02800E-05 481290 + 528 481291 Cd-129m 2.48150E-05 2.48160E-05 481291 + 529 481300 Cd-130 1.11880E-06 1.11880E-06 481300 + 530 481310 Cd-131 3.62250E-08 3.62250E-08 481310 + 531 481320 Cd-132 1.66990E-09 1.66990E-09 481320 + 532 491150 In-115 1.92990E-11 9.73050E-05 49115.82c + 533 491151 In-115m 4.46250E-12 9.75140E-05 491151 + 534 491160 In-116 1.75750E-10 1.75750E-10 491160 + 535 491161 In-116m 2.69370E-10 5.30270E-10 491161 + 536 491162 In-116m 2.60900E-10 2.60900E-10 491162 + 537 491170 In-117 2.49470E-08 7.55970E-05 491170 + 538 491171 In-117m 5.76850E-09 8.32300E-05 491171 + 539 491180 In-118 6.61730E-08 9.57150E-05 491180 + 540 491181 In-118m 1.01430E-07 1.98290E-07 491181 + 541 491182 In-118m 9.82350E-08 9.82350E-08 491182 + 542 491190 In-119 1.21330E-06 3.71270E-05 491190 + 543 491191 In-119m 2.80550E-07 7.65280E-05 491191 + 544 491200 In-120 1.96340E-06 1.44340E-04 491200 + 545 491201 In-120m 1.96340E-06 1.96340E-06 491201 + 546 491202 In-120m 1.96340E-06 1.96340E-06 491202 + 547 491210 In-121 5.97770E-06 6.52230E-05 491210 + 548 491211 In-121m 1.38220E-06 3.04360E-05 491211 + 549 491220 In-122 1.16450E-05 1.00560E-04 491220 + 550 491221 In-122m 8.26200E-06 8.26200E-06 491221 + 551 491222 In-122m 8.26200E-06 8.26200E-06 491222 + 552 491230 In-123 4.91590E-05 9.24480E-05 491230 + 553 491231 In-123m 1.13670E-05 2.89330E-05 491231 + 554 491240 In-124 3.39800E-05 1.58380E-04 491240 + 555 491241 In-124m 3.06080E-05 3.06080E-05 491241 + 556 491250 In-125 2.10960E-04 3.89690E-04 491250 + 557 491251 In-125m 4.87790E-05 8.16210E-05 491251 + 558 491260 In-126 3.55540E-04 7.37610E-04 491260 + 559 491261 In-126m 3.20270E-04 3.20270E-04 491261 + 560 491270 In-127 1.54590E-03 1.54590E-03 491270 + 561 491271 In-127m 3.57460E-04 6.44950E-04 491271 + 562 491280 In-128 8.86250E-04 1.35830E-03 491280 + 563 491281 In-128m 3.60760E-04 4.72040E-04 491281 + 564 491282 In-128m 1.12330E-03 1.12330E-03 491282 + 565 491290 In-129 2.01520E-03 2.04010E-03 491290 + 566 491291 In-129m 4.65970E-04 4.76270E-04 491291 + 567 491300 In-130 3.42860E-04 3.43940E-04 491300 + 568 491301 In-130m 3.82940E-04 3.82940E-04 491301 + 569 491302 In-130m 6.51560E-04 6.51560E-04 491302 + 570 491310 In-131 1.68440E-04 1.70190E-04 491310 + 571 491311 In-131m 1.68440E-04 1.68440E-04 491311 + 572 491312 In-131m 1.68440E-04 1.68440E-04 491312 + 573 491320 In-132 5.76090E-05 5.76100E-05 491320 + 574 491330 In-133 5.52690E-06 6.80480E-06 491330 + 575 491331 In-133m 1.27790E-06 1.27790E-06 491331 + 576 491340 In-134 1.18390E-08 1.18390E-08 491340 + 577 501170 Sn-117 7.48350E-13 1.19630E-04 50117.82c + 578 501171 Sn-117m 2.44840E-12 2.57570E-07 501171 + 579 501180 Sn-118 1.47810E-10 9.59150E-05 50118.82c + 580 501190 Sn-119 1.02760E-09 1.09370E-04 50119.82c + 581 501191 Sn-119m 3.36210E-09 3.35440E-05 501191 + 582 501210 Sn-121 3.71690E-12 9.36380E-05 501210 + 583 501211 Sn-121m 8.97310E-12 7.38870E-06 501211 + 584 501220 Sn-122 9.85230E-10 1.17080E-04 50122.82c + 585 501230 Sn-123 2.88210E-06 9.93050E-06 50123.82c + 586 501231 Sn-123m 1.19390E-06 1.15530E-04 501231 + 587 501240 Sn-124 3.35870E-05 2.22580E-04 50124.82c + 588 501250 Sn-125 3.99930E-05 1.05820E-04 50125.82c + 589 501251 Sn-125m 1.65660E-05 4.22050E-04 501251 + 590 501260 Sn-126 3.35070E-04 1.39740E-03 50126.82c + 591 501270 Sn-127 8.62450E-04 1.46500E-03 501270 + 592 501271 Sn-127m 3.57250E-04 1.94110E-03 501271 + 593 501280 Sn-128 1.30450E-03 6.84170E-03 501280 + 594 501281 Sn-128m 3.05560E-03 4.17880E-03 501281 + 595 501290 Sn-129 2.35540E-03 4.65470E-03 501290 + 596 501291 Sn-129m 5.68630E-03 5.90350E-03 501291 + 597 501300 Sn-130 3.43690E-03 4.33460E-03 501300 + 598 501301 Sn-130m 8.05010E-03 8.53430E-03 501301 + 599 501310 Sn-131 2.41790E-03 2.74410E-03 501310 + 600 501311 Sn-131m 5.83710E-03 6.01290E-03 501311 + 601 501320 Sn-132 4.67340E-03 4.73680E-03 501320 + 602 501330 Sn-133 6.45050E-04 6.46080E-04 501330 + 603 501340 Sn-134 9.44500E-05 9.44540E-05 501340 + 604 501350 Sn-135 7.19950E-06 7.19950E-06 501350 + 605 501360 Sn-136 1.30430E-07 1.30430E-07 501360 + 606 501370 Sn-137 1.92280E-09 1.92280E-09 501370 + 607 511230 Sb-123 4.15770E-12 1.25460E-04 51123.82c + 608 511240 Sb-124 6.97520E-11 1.63850E-10 51124.82c + 609 511241 Sb-124m 5.33340E-11 1.25470E-10 511241 + 610 511242 Sb-124m 7.21340E-11 7.21340E-11 511242 + 611 511250 Sb-125 1.64140E-06 5.29510E-04 51125.82c + 612 511260 Sb-126 3.69430E-06 4.57690E-06 51126.82c + 613 511261 Sb-126m 2.73150E-06 6.30390E-06 511261 + 614 511262 Sb-126m 3.57240E-06 3.57240E-06 511262 + 615 511270 Sb-127 8.91810E-05 3.49530E-03 511270 + 616 511280 Sb-128 1.63070E-04 7.01480E-03 511280 + 617 511281 Sb-128m 2.78260E-04 2.78260E-04 511281 + 618 511290 Sb-129 1.78510E-03 9.99790E-03 511290 + 619 511291 Sb-129m 1.09090E-03 4.04250E-03 511291 + 620 511300 Sb-130 4.53230E-03 1.31340E-02 511300 + 621 511301 Sb-130m 4.53230E-03 8.79940E-03 511301 + 622 511310 Sb-131 2.27130E-02 3.14700E-02 511310 + 623 511320 Sb-132 1.79060E-02 2.26430E-02 511320 + 624 511321 Sb-132m 1.31970E-02 1.31970E-02 511321 + 625 511330 Sb-133 3.35730E-02 3.42350E-02 511330 + 626 511340 Sb-134 3.76480E-03 3.84400E-03 511340 + 627 511341 Sb-134m 8.81820E-03 8.81890E-03 511341 + 628 511350 Sb-135 3.18430E-03 3.19000E-03 511350 + 629 511360 Sb-136 7.08730E-04 7.08820E-04 511360 + 630 511370 Sb-137 7.18780E-05 7.18790E-05 511370 + 631 511380 Sb-138 5.14630E-06 5.14630E-06 511380 + 632 511390 Sb-139 1.13820E-08 1.13820E-08 511390 + 633 521260 Te-126 2.05650E-10 9.99840E-06 52126.82c + 634 521270 Te-127 6.24080E-09 3.48150E-03 521270 + 635 521271 Te-127m 1.50660E-08 5.76030E-04 52527.82c + 636 521280 Te-128 8.09870E-06 7.29110E-03 52128.82c + 637 521290 Te-129 2.25840E-05 1.16350E-02 521290 + 638 521291 Te-129m 5.45220E-05 5.06950E-03 52529.82c + 639 521300 Te-130 6.55350E-04 2.25890E-02 52130.82c + 640 521310 Te-131 8.58750E-04 3.07740E-02 521310 + 641 521311 Te-131m 2.07320E-03 4.59270E-03 521311 + 642 521320 Te-132 1.19760E-02 4.78160E-02 52132.82c + 643 521330 Te-133 8.43520E-03 4.13560E-02 521330 + 644 521331 Te-133m 2.03640E-02 2.62870E-02 521331 + 645 521340 Te-134 5.39770E-02 6.71350E-02 521340 + 646 521350 Te-135 2.49120E-02 2.77170E-02 521350 + 647 521360 Te-136 1.48520E-02 1.54780E-02 521360 + 648 521370 Te-137 3.44540E-03 3.48210E-03 521370 + 649 521380 Te-138 7.46580E-04 7.51730E-04 521380 + 650 521390 Te-139 6.70540E-05 6.70650E-05 521390 + 651 521400 Te-140 8.54370E-06 8.54370E-06 521400 + 652 521410 Te-141 2.05800E-06 2.05800E-06 521410 + 653 521420 Te-142 2.02260E-09 2.02260E-09 521420 + 654 531290 I-129 1.24330E-06 1.35120E-02 53129.82c + 655 531300 I-130 4.27310E-06 5.80550E-06 53130.82c + 656 531301 I-130m 1.82430E-06 1.82430E-06 531301 + 657 531310 I-131 3.53930E-05 3.44370E-02 53131.82c + 658 531320 I-132 2.14300E-04 4.81660E-02 531320 + 659 531321 I-132m 1.57950E-04 1.57950E-04 531321 + 660 531330 I-133 1.66960E-03 6.57320E-02 531330 + 661 531331 I-133m 1.02030E-03 1.02030E-03 531331 + 662 531340 I-134 7.01090E-03 7.91940E-02 531340 + 663 531341 I-134m 5.16710E-03 5.16710E-03 531341 + 664 531350 I-135 3.50520E-02 6.27690E-02 53135.82c + 665 531360 I-136 1.60490E-02 3.15790E-02 531360 + 666 531361 I-136m 3.75890E-02 3.76420E-02 531361 + 667 531370 I-137 4.94880E-02 5.29130E-02 531370 + 668 531380 I-138 2.37790E-02 2.44830E-02 531380 + 669 531390 I-139 1.24660E-02 1.25330E-02 531390 + 670 531400 I-140 3.60950E-03 3.61800E-03 531400 + 671 531410 I-141 1.10640E-03 1.10850E-03 531410 + 672 531420 I-142 1.24610E-04 1.24610E-04 531420 + 673 531430 I-143 1.63820E-05 1.63820E-05 531430 + 674 531440 I-144 3.49310E-06 3.49310E-06 531440 + 675 541310 Xe-131 1.06100E-09 3.44370E-02 54131.82c + 676 541311 Xe-131m 2.56130E-09 3.74060E-04 541311 + 677 541320 Xe-132 1.42450E-07 4.81880E-02 54132.82c + 678 541321 Xe-132m 1.61470E-07 1.61470E-07 541321 + 679 541330 Xe-133 4.98280E-06 6.57490E-02 54133.82c + 680 541331 Xe-133m 1.20290E-05 1.88300E-03 541331 + 681 541340 Xe-134 5.89330E-05 7.95100E-02 54134.82c + 682 541341 Xe-134m 1.38040E-04 2.56880E-04 541341 + 683 541350 Xe-135 3.57690E-04 6.39230E-02 54135.82c + 684 541351 Xe-135m 8.63510E-04 1.12260E-02 541351 + 685 541360 Xe-136 1.12720E-02 8.39320E-02 54136.82c + 686 541370 Xe-137 1.85360E-02 6.93080E-02 541370 + 687 541380 Xe-138 3.42210E-02 5.86350E-02 541380 + 688 541390 Xe-139 2.20980E-02 3.37390E-02 541390 + 689 541400 Xe-140 2.15130E-02 2.50270E-02 541400 + 690 541410 Xe-141 1.22580E-02 1.31650E-02 541410 + 691 541420 Xe-142 4.53420E-03 4.63420E-03 541420 + 692 541430 Xe-143 7.16170E-04 7.27400E-04 541430 + 693 541440 Xe-144 1.42390E-04 1.44490E-04 541440 + 694 541450 Xe-145 1.77380E-05 1.77380E-05 541450 + 695 541460 Xe-146 6.88150E-08 6.88150E-08 541460 + 696 541470 Xe-147 6.72900E-10 6.72900E-10 541470 + 697 551340 Cs-134 2.95360E-08 5.13050E-08 55134.82c + 698 551341 Cs-134m 2.17690E-08 2.17690E-08 551341 + 699 551350 Cs-135 5.02690E-06 6.39980E-02 55135.82c + 700 551351 Cs-135m 3.07190E-06 3.07190E-06 551351 + 701 551360 Cs-136 6.20000E-05 8.01680E-05 55136.82c + 702 551361 Cs-136m 3.63350E-05 3.63350E-05 551361 + 703 551370 Cs-137 1.59780E-03 7.09050E-02 55137.82c + 704 551380 Cs-138 2.45820E-03 6.39190E-02 551380 + 705 551381 Cs-138m 3.48820E-03 3.48820E-03 551381 + 706 551390 Cs-139 1.37860E-02 4.75250E-02 551390 + 707 551400 Cs-140 1.93180E-02 4.43510E-02 551400 + 708 551410 Cs-141 4.26560E-02 5.58320E-02 551410 + 709 551420 Cs-142 3.79740E-02 4.25990E-02 551420 + 710 551430 Cs-143 2.11850E-02 2.19090E-02 551430 + 711 551440 Cs-144 5.35500E-03 8.17330E-03 551440 + 712 551441 Cs-144m 5.35500E-03 5.35540E-03 551441 + 713 551450 Cs-145 3.77370E-03 3.79060E-03 551450 + 714 551460 Cs-146 8.60330E-04 8.60390E-04 551460 + 715 551470 Cs-147 1.87130E-04 1.87130E-04 551470 + 716 551480 Cs-148 9.86090E-06 9.86090E-06 551480 + 717 551490 Cs-149 4.01210E-09 4.01210E-09 551490 + 718 561360 Ba-136 2.54510E-09 9.83430E-05 56136.82c + 719 561361 Ba-136m 5.96110E-09 5.96110E-09 561361 + 720 561370 Ba-137 8.30720E-07 7.09080E-02 56137.82c + 721 561371 Ba-137m 2.00550E-06 6.69360E-02 561371 + 722 561380 Ba-138 6.48290E-05 6.46460E-02 56138.82c + 723 561390 Ba-139 3.43820E-04 4.78690E-02 561390 + 724 561400 Ba-140 1.75560E-03 4.61070E-02 56140.82c + 725 561410 Ba-141 4.31670E-03 6.01480E-02 561410 + 726 561420 Ba-142 1.39880E-02 5.69460E-02 561420 + 727 561430 Ba-143 1.46910E-02 3.65030E-02 561430 + 728 561440 Ba-144 2.08760E-02 3.20080E-02 561440 + 729 561450 Ba-145 1.33110E-02 1.66820E-02 561450 + 730 561460 Ba-146 8.18160E-03 8.97310E-03 561460 + 731 561470 Ba-147 2.48400E-03 2.62030E-03 561470 + 732 561480 Ba-148 5.70830E-04 5.78220E-04 561480 + 733 561490 Ba-149 7.83660E-05 7.83700E-05 561490 + 734 561500 Ba-150 7.62360E-06 7.62360E-06 561500 + 735 561510 Ba-151 1.55370E-08 1.55370E-08 561510 + 736 561520 Ba-152 1.94320E-10 1.94320E-10 561520 + 737 571390 La-139 2.48170E-06 4.78720E-02 57139.82c + 738 571400 La-140 1.62310E-05 4.61230E-02 57140.82c + 739 571410 La-141 1.93430E-04 6.03420E-02 571410 + 740 571420 La-142 5.71270E-04 5.75170E-02 571420 + 741 571430 La-143 2.59510E-03 3.90980E-02 571430 + 742 571440 La-144 6.93640E-03 3.89440E-02 571440 + 743 571450 La-145 1.60860E-02 3.27680E-02 571450 + 744 571460 La-146 6.86980E-03 1.58430E-02 571460 + 745 571461 La-146m 1.23570E-02 1.23570E-02 571461 + 746 571470 La-147 1.75490E-02 2.01720E-02 571470 + 747 571480 La-148 9.54780E-03 1.01240E-02 571480 + 748 571490 La-149 4.64850E-03 4.72650E-03 571490 + 749 571500 La-150 1.47110E-03 1.47870E-03 571500 + 750 571510 La-151 3.39610E-04 3.39630E-04 571510 + 751 571520 La-152 4.78980E-05 4.78980E-05 571520 + 752 571530 La-153 6.69550E-06 6.69550E-06 571530 + 753 571540 La-154 5.13240E-10 5.13240E-10 571540 + 754 581410 Ce-141 1.02900E-06 6.03430E-02 58141.82c + 755 581420 Ce-142 2.00840E-06 5.75190E-02 58142.82c + 756 581430 Ce-143 2.02870E-05 3.91180E-02 58143.82c + 757 581440 Ce-144 1.18970E-04 3.90630E-02 58144.82c + 758 581450 Ce-145 5.23500E-04 3.32910E-02 581450 + 759 581460 Ce-146 2.41760E-03 3.06180E-02 581460 + 760 581470 Ce-147 3.64530E-03 2.38170E-02 581470 + 761 581480 Ce-148 6.41940E-03 1.66100E-02 581480 + 762 581490 Ce-149 5.41990E-03 1.01200E-02 581490 + 763 581500 Ce-150 4.17190E-03 5.61070E-03 581500 + 764 581510 Ce-151 1.93260E-03 2.27510E-03 581510 + 765 581520 Ce-152 6.52850E-04 6.97860E-04 581520 + 766 581530 Ce-153 1.22800E-04 1.29500E-04 581530 + 767 581540 Ce-154 1.84200E-05 1.84210E-05 581540 + 768 581550 Ce-155 2.63250E-06 2.63250E-06 581550 + 769 581560 Ce-156 1.74220E-09 1.74220E-09 581560 + 770 581570 Ce-157 9.94520E-12 9.94520E-12 581570 + 771 591440 Pr-144 8.83830E-08 3.90630E-02 591440 + 772 591441 Pr-144m 7.84970E-07 5.39830E-04 591441 + 773 591450 Pr-145 8.40960E-06 3.33000E-02 591450 + 774 591460 Pr-146 4.91040E-05 3.06670E-02 591460 + 775 591470 Pr-147 3.06530E-04 2.41230E-02 591470 + 776 591480 Pr-148 1.49500E-04 1.67590E-02 591480 + 777 591481 Pr-148m 6.28730E-04 6.28730E-04 591481 + 778 591490 Pr-149 2.64440E-03 1.27650E-02 591490 + 779 591500 Pr-150 4.38120E-03 9.99190E-03 591500 + 780 591510 Pr-151 5.16320E-03 7.43830E-03 591510 + 781 591520 Pr-152 3.42050E-03 4.11920E-03 591520 + 782 591530 Pr-153 1.93880E-03 2.06760E-03 591530 + 783 591540 Pr-154 6.93500E-04 7.11800E-04 591540 + 784 591550 Pr-155 2.05950E-04 2.08580E-04 591550 + 785 591560 Pr-156 3.53630E-05 3.53650E-05 591560 + 786 591570 Pr-157 5.22900E-06 5.22900E-06 591570 + 787 591580 Pr-158 2.68220E-09 2.68220E-09 591580 + 788 591590 Pr-159 3.74900E-11 3.74900E-11 591590 + 789 601460 Nd-146 2.18460E-09 3.06670E-02 60146.82c + 790 601470 Nd-147 7.94080E-08 2.41230E-02 60147.82c + 791 601480 Nd-148 3.59510E-06 1.73910E-02 60148.82c + 792 601490 Nd-149 2.05950E-05 1.27850E-02 601490 + 793 601500 Nd-150 1.28560E-04 1.01200E-02 60150.82c + 794 601510 Nd-151 3.77510E-04 7.81580E-03 601510 + 795 601520 Nd-152 9.25730E-04 5.04490E-03 601520 + 796 601530 Nd-153 1.01810E-03 3.08570E-03 601530 + 797 601540 Nd-154 8.47950E-04 1.55970E-03 601540 + 798 601550 Nd-155 4.66000E-04 6.75540E-04 601550 + 799 601560 Nd-156 1.82900E-04 2.17640E-04 601560 + 800 601570 Nd-157 5.51970E-05 6.00920E-05 601570 + 801 601580 Nd-158 6.50880E-06 6.51150E-06 601580 + 802 601590 Nd-159 1.19480E-07 1.19520E-07 601590 + 803 601600 Nd-160 3.04040E-09 3.04040E-09 601600 + 804 601610 Nd-161 4.27670E-11 4.27670E-11 601610 + 805 611490 Pm-149 7.13270E-09 1.27850E-02 61149.82c + 806 611500 Pm-150 2.18040E-06 2.18040E-06 611500 + 807 611510 Pm-151 1.61360E-05 7.83200E-03 61151.82c + 808 611520 Pm-152 7.34740E-06 5.05220E-03 611520 + 809 611521 Pm-152m 1.46720E-05 1.46720E-05 611521 + 810 611522 Pm-152m 1.62290E-05 1.62290E-05 611522 + 811 611530 Pm-153 1.55600E-04 3.24130E-03 611530 + 812 611540 Pm-154 1.36030E-04 1.69580E-03 611540 + 813 611541 Pm-154m 1.36030E-04 1.36030E-04 611541 + 814 611550 Pm-155 4.55210E-04 1.13080E-03 611550 + 815 611560 Pm-156 3.55300E-04 5.72940E-04 611560 + 816 611570 Pm-157 2.63220E-04 3.23310E-04 611570 + 817 611580 Pm-158 1.20070E-04 1.26580E-04 611580 + 818 611590 Pm-159 2.94450E-05 2.95640E-05 611590 + 819 611600 Pm-160 6.28930E-06 6.29230E-06 611600 + 820 611610 Pm-161 9.79990E-08 9.80420E-08 611610 + 821 611620 Pm-162 4.92000E-09 4.92000E-09 611620 + 822 611630 Pm-163 1.72640E-11 1.72640E-11 611630 + 823 621510 Sm-151 4.25680E-10 7.83200E-03 62151.82c + 824 621520 Sm-152 1.98210E-08 5.08320E-03 62152.82c + 825 621530 Sm-153 3.92600E-07 3.24270E-03 62153.82c + 826 621531 Sm-153m 9.47800E-07 9.47800E-07 621531 + 827 621540 Sm-154 5.28070E-06 1.83710E-03 62154.82c + 828 621550 Sm-155 1.44760E-05 1.14520E-03 621550 + 829 621560 Sm-156 1.44970E-05 5.87430E-04 621560 + 830 621570 Sm-157 4.30530E-05 3.66370E-04 621570 + 831 621580 Sm-158 6.09620E-05 1.87550E-04 621580 + 832 621590 Sm-159 4.21430E-05 7.17190E-05 621590 + 833 621600 Sm-160 1.25730E-05 1.88490E-05 621600 + 834 621610 Sm-161 3.80340E-06 3.90140E-06 621610 + 835 621620 Sm-162 1.40820E-06 1.41310E-06 621620 + 836 621630 Sm-163 1.20030E-08 1.20200E-08 621630 + 837 621640 Sm-164 1.32010E-09 1.32010E-09 621640 + 838 621650 Sm-165 1.75450E-10 1.75450E-10 621650 + 839 631540 Eu-154 3.43650E-10 6.53210E-10 63154.82c + 840 631541 Eu-154m 3.09560E-10 3.09560E-10 631541 + 841 631550 Eu-155 2.14170E-08 1.14530E-03 63155.82c + 842 631560 Eu-156 3.95600E-06 5.91390E-04 63156.82c + 843 631570 Eu-157 5.23040E-06 3.71600E-04 63157.82c + 844 631580 Eu-158 7.79780E-06 1.95350E-04 631580 + 845 631590 Eu-159 1.53120E-05 8.70310E-05 631590 + 846 631600 Eu-160 1.00500E-05 2.88990E-05 631600 + 847 631610 Eu-161 8.87180E-06 1.27730E-05 631610 + 848 631620 Eu-162 1.26310E-05 1.40440E-05 631620 + 849 631630 Eu-163 8.36260E-07 8.48280E-07 631630 + 850 631640 Eu-164 6.62900E-07 6.64220E-07 631640 + 851 631650 Eu-165 8.88470E-08 8.90220E-08 631650 + 852 631660 Eu-166 4.26600E-09 4.26600E-09 631660 + 853 631670 Eu-167 2.75710E-10 2.75710E-10 631670 + 854 641560 Gd-156 4.14800E-11 5.91390E-04 64156.82c + 855 641570 Gd-157 8.75180E-10 3.71600E-04 64157.82c + 856 641580 Gd-158 1.89300E-08 1.95370E-04 64158.82c + 857 641590 Gd-159 1.11900E-07 8.71420E-05 641590 + 858 641600 Gd-160 4.78590E-07 2.93770E-05 64160.82c + 859 641610 Gd-161 3.80120E-06 1.65740E-05 641610 + 860 641620 Gd-162 1.14820E-06 1.51920E-05 641620 + 861 641630 Gd-163 3.98190E-07 1.24650E-06 641630 + 862 641640 Gd-164 5.28830E-07 1.19300E-06 641640 + 863 641650 Gd-165 9.65860E-07 1.05490E-06 641650 + 864 641660 Gd-166 2.92420E-07 2.96690E-07 641660 + 865 641670 Gd-167 4.34390E-08 4.37150E-08 641670 + 866 641680 Gd-168 5.80070E-09 5.80070E-09 641680 + 867 641690 Gd-169 2.71220E-10 2.71220E-10 641690 + 868 651590 Tb-159 3.46070E-11 8.71430E-05 65159.82c + 869 651600 Tb-160 3.64510E-10 3.64510E-10 65160.82c + 870 651610 Tb-161 6.41530E-09 1.65810E-05 651610 + 871 651620 Tb-162 5.39480E-08 1.52460E-05 651620 + 872 651630 Tb-163 3.21300E-08 1.27860E-06 651630 + 873 651640 Tb-164 8.44070E-08 1.27750E-06 651640 + 874 651650 Tb-165 8.41450E-07 1.89630E-06 651650 + 875 651660 Tb-166 8.61300E-07 1.15800E-06 651660 + 876 651670 Tb-167 3.82440E-07 4.26160E-07 651670 + 877 651680 Tb-168 1.04280E-07 1.10080E-07 651680 + 878 651690 Tb-169 3.19330E-08 3.22040E-08 651690 + 879 651700 Tb-170 3.00610E-09 3.00610E-09 651700 + 880 651710 Tb-171 3.05770E-10 3.05770E-10 651710 + 881 661620 Dy-162 3.67440E-11 1.52460E-05 66162.82c + 882 661630 Dy-163 5.46900E-11 1.27870E-06 66163.82c + 883 661640 Dy-164 1.01200E-09 1.27850E-06 66164.82c + 884 661650 Dy-165 1.96000E-08 1.91890E-06 661650 + 885 661651 Dy-165m 2.99620E-09 2.99620E-09 661651 + 886 661660 Dy-166 7.57040E-08 1.23370E-06 661660 + 887 661670 Dy-167 1.19570E-07 5.45720E-07 661670 + 888 661680 Dy-168 1.74960E-07 2.85040E-07 661680 + 889 661690 Dy-169 9.83190E-08 1.30520E-07 661690 + 890 661700 Dy-170 5.34860E-08 5.64920E-08 661700 + 891 661710 Dy-171 1.15700E-08 1.18760E-08 661710 + 892 661720 Dy-172 2.82950E-09 2.82950E-09 661720 + 893 661730 Dy-173 2.12870E-10 2.12870E-10 661730 + 894 671650 Ho-165 2.78940E-11 1.91900E-06 67165.82c + 895 671660 Ho-166 6.83730E-11 1.23380E-06 671660 + 896 671661 Ho-166m 1.60150E-10 1.60150E-10 671661 + 897 671670 Ho-167 2.47410E-09 5.48200E-07 671670 + 898 671680 Ho-168 3.23050E-09 2.92830E-07 671680 + 899 671681 Ho-168m 4.58400E-09 4.58400E-09 671681 + 900 671690 Ho-169 2.57550E-08 1.56280E-07 671690 + 901 671700 Ho-170 1.81700E-08 1.81700E-08 671700 + 902 671701 Ho-170m 7.75740E-09 6.42490E-08 671701 + 903 671710 Ho-171 3.00150E-08 4.18910E-08 671710 + 904 671720 Ho-172 1.38190E-08 1.66480E-08 671720 + 905 671730 Ho-173 6.25300E-09 6.46590E-09 671730 + 906 671740 Ho-174 9.97850E-10 9.97850E-10 671740 + 907 671750 Ho-175 1.92110E-10 1.92110E-10 671750 + 908 681680 Er-168 2.16190E-11 2.92880E-07 68168.82c + 909 681690 Er-169 1.70140E-10 1.56450E-07 681690 + 910 681700 Er-170 1.13700E-09 8.35560E-08 68170.82c + 911 681710 Er-171 2.72970E-09 4.46200E-08 681710 + 912 681720 Er-172 7.09910E-09 2.37480E-08 681720 + 913 681730 Er-173 5.83820E-09 1.23040E-08 681730 + 914 681740 Er-174 5.04480E-09 6.04270E-09 681740 + 915 681750 Er-175 1.89320E-09 2.08530E-09 681750 + 916 681760 Er-176 7.25100E-10 7.25100E-10 681760 + 917 681770 Er-177 9.12970E-11 9.12970E-11 681770 + 918 691710 Tm-171 1.34020E-11 4.46340E-08 691710 + 919 691720 Tm-172 8.10400E-11 2.38290E-08 691720 + 920 691730 Tm-173 4.26520E-10 1.27310E-08 691730 + 921 691740 Tm-174 7.33750E-10 6.77640E-09 691740 + 922 691750 Tm-175 1.50910E-09 3.59440E-09 691750 + 923 691760 Tm-176 1.04620E-09 1.77130E-09 691760 + 924 691770 Tm-177 7.31160E-10 8.22460E-10 691770 + 925 691780 Tm-178 2.08020E-10 2.08020E-10 691780 + 926 691790 Tm-179 6.57550E-11 6.57550E-11 691790 + 927 701740 Yb-174 7.89300E-12 6.78430E-09 701740 + 928 701750 Yb-175 3.17140E-11 3.63100E-09 701750 + 929 701751 Yb-175m 4.84810E-12 2.77250E-09 701751 + 930 701760 Yb-176 5.57000E-11 1.82860E-09 701760 + 931 701761 Yb-176m 1.00190E-10 9.85840E-10 701761 + 932 701770 Yb-177 1.69600E-10 1.03130E-09 701770 + 933 701771 Yb-177m 3.92160E-11 8.61670E-10 701771 + 934 701780 Yb-178 3.19410E-10 5.27430E-10 701780 + 935 701790 Yb-179 1.84720E-10 2.50480E-10 701790 + 936 701800 Yb-180 1.03590E-10 1.03590E-10 701800 + 937 701810 Yb-181 2.34200E-11 2.34200E-11 701810 + 938 711770 Lu-177 2.76870E-12 1.03430E-09 711770 + 939 711771 Lu-177m 1.08240E-12 1.09990E-12 711771 + 940 711780 Lu-178 6.05230E-12 5.33480E-10 711780 + 941 711781 Lu-178m 6.86070E-12 6.86070E-12 711781 + 942 711790 Lu-179 3.82410E-11 2.94560E-10 711790 + 943 711791 Lu-179m 5.84590E-12 2.56320E-10 711791 + 944 711800 Lu-180 1.32250E-11 8.13780E-11 711800 + 945 711801 Lu-180m 1.32250E-11 1.16810E-10 711801 + 946 711802 Lu-180m 1.94910E-11 1.94910E-11 711802 + 947 711810 Lu-181 5.55510E-11 7.89710E-11 711810 + 948 711820 Lu-182 2.64730E-11 2.64730E-11 711820 + 949 711830 Lu-183 1.23340E-11 1.23340E-11 711830 + 950 711840 Lu-184 2.05460E-12 2.05460E-12 711840 + 951 721800 Hf-180 6.49320E-13 1.51320E-10 72180.82c + 952 721801 Hf-180m 1.16800E-12 1.09140E-11 721801 + 953 721810 Hf-181 4.58770E-12 8.35590E-11 721810 + 954 721820 Hf-182 4.43800E-12 3.42640E-11 721820 + 955 721821 Hf-182m 7.98300E-12 7.98300E-12 721821 + 956 721830 Hf-183 1.05380E-11 2.28720E-11 721830 + 957 721840 Hf-184 3.38690E-12 4.41420E-12 721840 + 958 721841 Hf-184m 6.09230E-12 7.11960E-12 721841 + 959 721850 Hf-185 3.69110E-12 3.69110E-12 721850 + 960 721860 Hf-186 1.45500E-12 1.45500E-12 721860 + 961 731840 Ta-184 1.25590E-12 1.27900E-11 731840 + 962 731850 Ta-185 1.81330E-12 6.38260E-12 731850 + 963 731860 Ta-186 1.91980E-12 3.37480E-12 731860 + 964 731870 Ta-187 1.39330E-12 1.39330E-12 731870 + + Neutron-induced fission: + + Interpolation region : 2 / 2 + Interpolation energy : 4.00000E-01 MeV + Number of products : 931 / 1025 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 2.94220E-05 2.94220E-05 1001.82c + 2 10020 H-2 8.99170E-06 8.99170E-06 1002.82c + 3 10030 H-3 1.25000E-04 1.25000E-04 1003.82c + 4 20040 He-4 1.86000E-03 1.86000E-03 2004.82c + 5 220540 Ti-54 1.91080E-12 1.91080E-12 220540 + 6 220550 Ti-55 3.26700E-12 3.26700E-12 220550 + 7 220560 Ti-56 4.88480E-12 4.88480E-12 220560 + 8 220570 Ti-57 3.02250E-12 3.02250E-12 220570 + 9 220580 Ti-58 1.67940E-12 1.67940E-12 220580 + 10 230550 V-55 1.71360E-12 4.98060E-12 230550 + 11 230560 V-56 5.46590E-12 1.03600E-11 230560 + 12 230570 V-57 1.56420E-11 1.86550E-11 230570 + 13 230580 V-58 2.03950E-11 2.20740E-11 230580 + 14 230590 V-59 2.45770E-11 2.45770E-11 230590 + 15 230600 V-60 1.15590E-11 1.15590E-11 230600 + 16 230610 V-61 5.25190E-12 5.25190E-12 230610 + 17 240570 Cr-57 4.03340E-12 4.02740E-11 240570 + 18 240580 Cr-58 2.40490E-11 2.84640E-11 240580 + 19 240590 Cr-59 6.20520E-11 8.66290E-11 240590 + 20 240600 Cr-60 1.38980E-10 1.50850E-10 240600 + 21 240610 Cr-61 1.54140E-10 1.59080E-10 240610 + 22 240620 Cr-62 1.54670E-10 1.54670E-10 240620 + 23 240630 Cr-63 5.79590E-11 5.79590E-11 240630 + 24 240640 Cr-64 1.82520E-11 1.82520E-11 240640 + 25 240650 Cr-65 2.55580E-12 2.55580E-12 240650 + 26 250590 Mn-59 9.29130E-12 9.59200E-11 250590 + 27 250600 Mn-60 4.14050E-12 1.59840E-10 250600 + 28 250601 Mn-60m 4.21220E-11 4.21220E-11 250601 + 29 250610 Mn-61 2.31830E-10 3.90910E-10 250610 + 30 250620 Mn-62 4.37990E-10 5.15320E-10 250620 + 31 250621 Mn-62m 6.85910E-11 1.45930E-10 250621 + 32 250630 Mn-63 9.37250E-10 9.95210E-10 250630 + 33 250640 Mn-64 7.49080E-10 7.67330E-10 250640 + 34 250650 Mn-65 6.05870E-10 6.08430E-10 250650 + 35 250660 Mn-66 1.86000E-10 1.86000E-10 250660 + 36 250670 Mn-67 4.72990E-11 4.72990E-11 250670 + 37 250680 Mn-68 4.81650E-12 4.81650E-12 250680 + 38 260600 Fe-60 1.29830E-12 1.98410E-10 260600 + 39 260610 Fe-61 1.63690E-11 4.07280E-10 260610 + 40 260620 Fe-62 1.75100E-10 8.36350E-10 260620 + 41 260630 Fe-63 7.02020E-10 1.69720E-09 260630 + 42 260640 Fe-64 2.53900E-09 3.30630E-09 260640 + 43 260650 Fe-65 4.59790E-09 5.20630E-09 260650 + 44 260660 Fe-66 7.24940E-09 7.43540E-09 260660 + 45 260670 Fe-67 4.85060E-09 4.89790E-09 260670 + 46 260680 Fe-68 2.93070E-09 2.93550E-09 260680 + 47 260690 Fe-69 6.98800E-10 6.98800E-10 260690 + 48 260700 Fe-70 1.29270E-10 1.29270E-10 260700 + 49 260710 Fe-71 1.05170E-11 1.05170E-11 260710 + 50 270620 Co-62 3.30750E-13 8.36690E-10 270620 + 51 270630 Co-63 2.74440E-11 1.72470E-09 270630 + 52 270640 Co-64 2.40110E-10 3.54640E-09 270640 + 53 270650 Co-65 2.05550E-09 7.26180E-09 270650 + 54 270660 Co-66 6.92500E-09 1.43600E-08 270660 + 55 270670 Co-67 2.12850E-08 2.61830E-08 270670 + 56 270680 Co-68 1.70810E-08 2.49470E-08 270680 + 57 270681 Co-68m 1.27490E-08 1.57340E-08 270681 + 58 270690 Co-69 3.79890E-08 3.86390E-08 270690 + 59 270700 Co-70 9.54800E-09 9.54800E-09 270700 + 60 270701 Co-70m 9.54800E-09 9.67730E-09 270701 + 61 270710 Co-71 9.43530E-09 9.44580E-09 270710 + 62 270720 Co-72 1.83120E-09 1.83120E-09 270720 + 63 270730 Co-73 3.80180E-10 3.80180E-10 270730 + 64 270740 Co-74 8.94320E-12 8.94320E-12 270740 + 65 280640 Ni-64 1.54890E-12 3.54800E-09 28064.82c + 66 280650 Ni-65 3.61080E-11 7.29790E-09 280650 + 67 280660 Ni-66 6.51540E-10 1.50120E-08 280660 + 68 280670 Ni-67 4.65820E-09 3.08410E-08 280670 + 69 280680 Ni-68 3.00360E-08 6.32370E-08 280680 + 70 280690 Ni-69 4.08460E-08 7.90980E-08 280690 + 71 280691 Ni-69m 4.08460E-08 4.08460E-08 280691 + 72 280700 Ni-70 1.93670E-07 2.12900E-07 280700 + 73 280710 Ni-71 2.30820E-07 2.40270E-07 280710 + 74 280720 Ni-72 2.48190E-07 2.50020E-07 280720 + 75 280730 Ni-73 1.43900E-07 1.44280E-07 280730 + 76 280740 Ni-74 2.10030E-08 2.10120E-08 280740 + 77 280750 Ni-75 7.80320E-09 7.80320E-09 280750 + 78 280760 Ni-76 6.67310E-10 6.67310E-10 280760 + 79 280770 Ni-77 2.65800E-11 2.65800E-11 280770 + 80 290660 Cu-66 1.01930E-12 1.50130E-08 290660 + 81 290670 Cu-67 4.33210E-11 3.08840E-08 290670 + 82 290680 Cu-68 1.97770E-10 6.38870E-08 290680 + 83 290681 Cu-68m 5.39090E-10 5.39090E-10 290681 + 84 290690 Cu-69 1.03230E-08 1.30270E-07 290690 + 85 290700 Cu-70 3.71860E-09 3.28790E-08 290700 + 86 290701 Cu-70m 4.74900E-08 5.83210E-08 290701 + 87 290702 Cu-70m 3.71860E-09 2.16610E-07 290702 + 88 290710 Cu-71 2.96420E-07 5.36690E-07 290710 + 89 290720 Cu-72 6.89660E-07 9.39680E-07 290720 + 90 290730 Cu-73 2.69790E-06 2.84220E-06 290730 + 91 290740 Cu-74 7.01740E-07 7.22880E-07 290740 + 92 290750 Cu-75 2.88390E-06 2.89160E-06 290750 + 93 290760 Cu-76 3.70530E-07 3.70860E-07 290760 + 94 290761 Cu-76m 3.70530E-07 3.70860E-07 290761 + 95 290770 Cu-77 9.09550E-08 9.09820E-08 290770 + 96 290780 Cu-78 1.21840E-08 1.21840E-08 290780 + 97 290790 Cu-79 8.77970E-10 8.77970E-10 290790 + 98 290800 Cu-80 2.44600E-11 2.44600E-11 290800 + 99 300680 Zn-68 1.02740E-12 6.39750E-08 300680 + 100 300690 Zn-69 6.95300E-12 1.30310E-07 300690 + 101 300691 Zn-69m 3.45330E-11 3.45330E-11 300691 + 102 300700 Zn-70 1.27780E-09 2.69100E-07 300700 + 103 300710 Zn-71 2.94140E-09 5.39630E-07 300710 + 104 300711 Zn-71m 1.46090E-08 1.46090E-08 300711 + 105 300720 Zn-72 2.02190E-07 1.14190E-06 300720 + 106 300730 Zn-73 5.91520E-08 3.24990E-06 300730 + 107 300731 Zn-73m 8.18140E-08 3.48610E-07 300731 + 108 300732 Zn-73m 5.33580E-07 5.33580E-07 300732 + 109 300740 Zn-74 1.40340E-06 2.22750E-06 300740 + 110 300750 Zn-75 9.37270E-06 1.21740E-05 300750 + 111 300760 Zn-76 1.70440E-05 1.77750E-05 300760 + 112 300770 Zn-77 1.11150E-05 1.19460E-05 300770 + 113 300771 Zn-77m 1.47990E-06 1.47990E-06 300771 + 114 300780 Zn-78 2.02760E-05 2.02890E-05 300780 + 115 300790 Zn-79 4.52840E-06 4.52880E-06 300790 + 116 300800 Zn-80 2.48670E-06 2.48670E-06 300800 + 117 300810 Zn-81 8.05190E-07 8.05190E-07 300810 + 118 300820 Zn-82 9.26050E-10 9.26050E-10 300820 + 119 310710 Ga-71 3.61330E-11 5.54270E-07 310710 + 120 310720 Ga-72 1.06860E-09 1.14310E-06 310720 + 121 310721 Ga-72m 1.05040E-10 3.81530E-08 310721 + 122 310730 Ga-73 4.06610E-08 3.55740E-06 310730 + 123 310740 Ga-74 3.50870E-07 2.28460E-06 310740 + 124 310741 Ga-74m 3.50870E-07 2.57840E-06 310741 + 125 310750 Ga-75 2.88390E-06 1.50580E-05 310750 + 126 310760 Ga-76 4.44620E-06 2.22210E-05 310760 + 127 310770 Ga-77 2.00030E-05 3.26890E-05 310770 + 128 310780 Ga-78 3.58730E-05 5.62210E-05 310780 + 129 310790 Ga-79 5.50960E-05 5.95660E-05 310790 + 130 310800 Ga-80 2.81830E-05 3.07300E-05 310800 + 131 310810 Ga-81 2.09350E-05 2.16800E-05 310810 + 132 310820 Ga-82 3.97980E-06 3.98070E-06 310820 + 133 310830 Ga-83 1.67610E-06 1.67610E-06 310830 + 134 310840 Ga-84 1.89370E-08 1.89370E-08 310840 + 135 310850 Ga-85 6.29590E-10 6.29590E-10 310850 + 136 320730 Ge-73 2.93470E-11 3.55740E-06 32073.82c + 137 320731 Ge-73m 5.90890E-12 3.50520E-06 320731 + 138 320740 Ge-74 8.72230E-10 2.93010E-06 32074.82c + 139 320750 Ge-75 6.34020E-09 1.51120E-05 320750 + 140 320751 Ge-75m 4.76190E-08 6.49940E-07 320751 + 141 320760 Ge-76 7.41060E-07 2.29620E-05 32076.82c + 142 320770 Ge-77 7.84570E-06 1.42550E-05 320770 + 143 320771 Ge-77m 1.04460E-06 3.37340E-05 320771 + 144 320780 Ge-78 4.83480E-05 1.04620E-04 320780 + 145 320790 Ge-79 1.31240E-05 7.64930E-05 320790 + 146 320791 Ge-79m 9.85660E-05 9.86560E-05 320791 + 147 320800 Ge-80 2.53640E-04 2.86950E-04 320800 + 148 320810 Ge-81 2.44660E-04 2.55760E-04 320810 + 149 320811 Ge-81m 4.92610E-05 5.86980E-05 320811 + 150 320820 Ge-82 3.47910E-04 3.51660E-04 320820 + 151 320830 Ge-83 1.60100E-04 1.61170E-04 320830 + 152 320840 Ge-84 6.53360E-05 6.53420E-05 320840 + 153 320850 Ge-85 8.40840E-06 8.40900E-06 320850 + 154 320860 Ge-86 6.65610E-06 6.65610E-06 320860 + 155 320870 Ge-87 1.17050E-08 1.17050E-08 320870 + 156 320880 Ge-88 6.29070E-10 6.29070E-10 320880 + 157 330750 As-75 4.91980E-12 1.51120E-05 33075.82c + 158 330751 As-75m 1.86310E-11 2.13610E-10 330751 + 159 330760 As-76 9.95080E-10 9.95080E-10 330760 + 160 330770 As-77 4.07920E-08 4.16200E-05 330770 + 161 330780 As-78 7.79830E-07 1.05400E-04 330780 + 162 330790 As-79 5.28290E-06 1.76490E-04 330790 + 163 330800 As-80 3.31550E-05 3.20100E-04 330800 + 164 330810 As-81 1.48950E-04 4.62820E-04 330810 + 165 330820 As-82 9.06940E-05 4.42360E-04 330820 + 166 330821 As-82m 3.16010E-04 3.16010E-04 330821 + 167 330830 As-83 7.88020E-04 9.56250E-04 330830 + 168 330840 As-84 3.53800E-04 3.83530E-04 330840 + 169 330841 As-84m 3.53800E-04 3.83530E-04 330841 + 170 330850 As-85 5.62350E-04 5.69580E-04 330850 + 171 330860 As-86 1.95100E-04 2.01760E-04 330860 + 172 330870 As-87 6.94520E-05 6.94640E-05 330870 + 173 330880 As-88 1.05010E-05 1.05020E-05 330880 + 174 330890 As-89 3.13030E-06 3.13030E-06 330890 + 175 330900 As-90 4.09600E-09 4.09600E-09 330900 + 176 340770 Se-77 8.51750E-13 4.16200E-05 34077.82c + 177 340771 Se-77m 6.39710E-12 6.39710E-12 340771 + 178 340780 Se-78 1.03910E-09 1.05400E-04 34078.82c + 179 340790 Se-79 3.27090E-08 1.76430E-04 34079.82c + 180 340791 Se-79m 4.35500E-09 1.72310E-04 340791 + 181 340800 Se-80 4.97320E-06 3.25080E-04 34080.82c + 182 340810 Se-81 3.12200E-06 4.89370E-04 340810 + 183 340811 Se-81m 2.34480E-05 4.00620E-05 340811 + 184 340820 Se-82 1.83030E-04 9.41390E-04 34082.82c + 185 340830 Se-83 6.15120E-04 9.59900E-04 340830 + 186 340831 Se-83m 1.23850E-04 7.36390E-04 340831 + 187 340840 Se-84 2.62840E-03 3.51970E-03 340840 + 188 340850 Se-85 3.62970E-03 4.14050E-03 340850 + 189 340860 Se-86 4.73430E-03 4.88020E-03 340860 + 190 340870 Se-87 3.22000E-03 3.27880E-03 340870 + 191 340880 Se-88 1.82000E-03 1.83050E-03 340880 + 192 340890 Se-89 4.98510E-04 5.01640E-04 340890 + 193 340900 Se-90 1.06690E-04 1.06690E-04 340900 + 194 340910 Se-91 1.39070E-05 1.39070E-05 340910 + 195 340920 Se-92 2.21200E-06 2.21200E-06 340920 + 196 340930 Se-93 1.44450E-09 1.44450E-09 340930 + 197 350790 Br-79 1.12520E-12 9.64990E-08 35079.82c + 198 350791 Br-79m 4.26110E-12 4.26110E-12 350791 + 199 350800 Br-80 7.09090E-11 3.17980E-10 350800 + 200 350801 Br-80m 2.47070E-10 2.47070E-10 350801 + 201 350810 Br-81 2.04630E-08 4.89410E-04 35081.82c + 202 350820 Br-82 4.66130E-07 6.33040E-07 350820 + 203 350821 Br-82m 1.71010E-07 1.71010E-07 350821 + 204 350830 Br-83 1.34060E-05 1.70970E-03 350830 + 205 350840 Br-84 8.10350E-05 3.60070E-03 350840 + 206 350841 Br-84m 8.10350E-05 8.10350E-05 350841 + 207 350850 Br-85 9.16500E-04 5.05700E-03 350850 + 208 350860 Br-86 2.37770E-03 7.25790E-03 350860 + 209 350870 Br-87 5.24700E-03 8.54390E-03 350870 + 210 350880 Br-88 6.97710E-03 8.82860E-03 350880 + 211 350890 Br-89 6.45110E-03 6.91360E-03 350890 + 212 350900 Br-90 2.76180E-03 2.87140E-03 350900 + 213 350910 Br-91 1.52320E-03 1.53420E-03 350910 + 214 350920 Br-92 3.06020E-04 3.08230E-04 350920 + 215 350930 Br-93 7.14500E-05 7.14510E-05 350930 + 216 350940 Br-94 4.06390E-06 4.06390E-06 350940 + 217 350950 Br-95 1.42470E-08 1.42470E-08 350950 + 218 360820 Kr-82 1.65360E-10 6.37300E-07 36082.82c + 219 360830 Kr-83 9.03570E-09 1.70970E-03 36083.82c + 220 360831 Kr-83m 1.81930E-09 1.70820E-03 360831 + 221 360840 Kr-84 5.76410E-06 3.68750E-03 36084.82c + 222 360850 Kr-85 5.36350E-05 1.14460E-03 36085.82c + 223 360851 Kr-85m 1.07990E-05 5.05960E-03 360851 + 224 360860 Kr-86 6.37260E-04 8.10960E-03 36086.82c + 225 360870 Kr-87 2.24910E-03 1.11700E-02 360870 + 226 360880 Kr-88 8.82110E-03 1.80330E-02 360880 + 227 360890 Kr-89 1.51710E-02 2.18160E-02 360890 + 228 360900 Kr-90 1.96910E-02 2.21630E-02 360900 + 229 360910 Kr-91 1.80870E-02 1.94160E-02 360910 + 230 360920 Kr-92 1.45210E-02 1.47760E-02 360920 + 231 360930 Kr-93 5.04210E-03 5.06780E-03 360930 + 232 360940 Kr-94 1.73330E-03 1.73450E-03 360940 + 233 360950 Kr-95 2.33260E-04 2.33270E-04 360950 + 234 360960 Kr-96 4.89060E-05 4.89060E-05 360960 + 235 360970 Kr-97 1.18130E-07 1.18130E-07 360970 + 236 360980 Kr-98 2.60320E-09 2.60320E-09 360980 + 237 370850 Rb-85 4.72190E-09 5.12150E-03 37085.82c + 238 370860 Rb-86 6.13870E-07 1.90170E-06 37086.82c + 239 370861 Rb-86m 1.28780E-06 1.28780E-06 370861 + 240 370870 Rb-87 3.12860E-05 1.12010E-02 37087.82c + 241 370880 Rb-88 2.05870E-04 1.82390E-02 370880 + 242 370890 Rb-89 1.57080E-03 2.33870E-02 370890 + 243 370900 Rb-90 3.56530E-04 1.97900E-02 370900 + 244 370901 Rb-90m 3.62710E-03 6.52600E-03 370901 + 245 370910 Rb-91 1.23630E-02 3.17790E-02 370910 + 246 370920 Rb-92 2.03660E-02 3.51420E-02 370920 + 247 370930 Rb-93 2.35060E-02 2.85930E-02 370930 + 248 370940 Rb-94 1.47360E-02 1.64580E-02 370940 + 249 370950 Rb-95 8.81750E-03 9.04590E-03 370950 + 250 370960 Rb-96 1.42590E-03 2.17420E-03 370960 + 251 370961 Rb-96m 1.42590E-03 1.44940E-03 370961 + 252 370970 Rb-97 8.21980E-04 8.22090E-04 370970 + 253 370980 Rb-98 5.89600E-05 5.89600E-05 370980 + 254 370981 Rb-98m 5.89600E-05 5.89620E-05 370981 + 255 370990 Rb-99 1.47470E-05 1.47470E-05 370990 + 256 371000 Rb-100 1.65380E-08 1.65380E-08 371000 + 257 380870 Sr-87 7.89940E-10 9.48510E-10 38087.82c + 258 380871 Sr-87m 1.59050E-10 1.59050E-10 380871 + 259 380880 Sr-88 8.40070E-06 1.82470E-02 38088.82c + 260 380890 Sr-89 4.48760E-05 2.34320E-02 38089.82c + 261 380900 Sr-90 4.45410E-04 2.65920E-02 38090.82c + 262 380910 Sr-91 2.11650E-03 3.38960E-02 380910 + 263 380920 Sr-92 1.03240E-02 4.58660E-02 380920 + 264 380930 Sr-93 2.01410E-02 4.99960E-02 380930 + 265 380940 Sr-94 3.94060E-02 5.49800E-02 380940 + 266 380950 Sr-95 3.79840E-02 4.65430E-02 380950 + 267 380960 Sr-96 3.73430E-02 4.01570E-02 380960 + 268 380970 Sr-97 1.88130E-02 1.94370E-02 380970 + 269 380980 Sr-98 9.54930E-03 9.66140E-03 380980 + 270 380990 Sr-99 2.03130E-03 2.04370E-03 380990 + 271 381000 Sr-100 4.40400E-04 4.40420E-04 381000 + 272 381010 Sr-101 5.74610E-05 5.74610E-05 381010 + 273 381020 Sr-102 7.42650E-06 7.42650E-06 381020 + 274 381030 Sr-103 1.56150E-09 1.56150E-09 381030 + 275 390900 Y-90 5.87530E-09 2.65920E-02 39090.82c + 276 390901 Y-90m 9.82570E-09 9.82570E-09 390901 + 277 390910 Y-91 1.83120E-06 3.39070E-02 39091.82c + 278 390911 Y-91m 9.09480E-06 1.99520E-02 390911 + 279 390920 Y-92 9.62540E-05 4.59620E-02 390920 + 280 390930 Y-93 9.99270E-05 5.08470E-02 390930 + 281 390931 Y-93m 7.50510E-04 1.32620E-02 390931 + 282 390940 Y-94 2.77570E-03 5.77550E-02 390940 + 283 390950 Y-95 1.06670E-02 5.72100E-02 390950 + 284 390960 Y-96 6.64060E-03 4.68020E-02 390960 + 285 390961 Y-96m 1.39310E-02 1.39360E-02 390961 + 286 390970 Y-97 5.65920E-03 2.24020E-02 390970 + 287 390971 Y-97m 2.09180E-02 2.95600E-02 390971 + 288 390972 Y-97m 7.18880E-03 7.18880E-03 390972 + 289 390980 Y-98 5.42930E-03 1.50910E-02 390980 + 290 390981 Y-98m 2.63210E-02 2.63210E-02 390981 + 291 390990 Y-99 2.35830E-02 2.56300E-02 390990 + 292 391000 Y-100 4.87850E-03 5.31620E-03 391000 + 293 391001 Y-100m 4.87850E-03 4.87920E-03 391001 + 294 391010 Y-101 4.73480E-03 4.79130E-03 391010 + 295 391020 Y-102 4.81170E-04 4.84680E-04 391020 + 296 391021 Y-102m 4.81170E-04 4.84680E-04 391021 + 297 391030 Y-103 1.84200E-04 1.84200E-04 391030 + 298 391040 Y-104 1.29610E-05 1.29610E-05 391040 + 299 391050 Y-105 1.44480E-08 1.44480E-08 391050 + 300 400920 Zr-92 1.10600E-06 4.59630E-02 40092.82c + 301 400930 Zr-93 1.49350E-05 5.08610E-02 40093.82c + 302 400940 Zr-94 1.27050E-04 5.78820E-02 40094.82c + 303 400950 Zr-95 7.48280E-04 5.79590E-02 40095.82c + 304 400960 Zr-96 4.43640E-03 6.51990E-02 40096.82c + 305 400970 Zr-97 1.09540E-02 6.50700E-02 400970 + 306 400980 Zr-98 3.17990E-02 7.27000E-02 400980 + 307 400990 Zr-99 3.70270E-02 6.22700E-02 400990 + 308 401000 Zr-100 4.22310E-02 5.23780E-02 401000 + 309 401010 Zr-101 3.13270E-02 3.61660E-02 401010 + 310 401020 Zr-102 2.05850E-02 2.15220E-02 401020 + 311 401030 Zr-103 6.39640E-03 6.56700E-03 401030 + 312 401040 Zr-104 1.93460E-03 1.94640E-03 401040 + 313 401050 Zr-105 2.92910E-04 2.92920E-04 401050 + 314 401060 Zr-106 4.75620E-05 4.75620E-05 401060 + 315 401070 Zr-107 5.89770E-06 5.89770E-06 401070 + 316 401080 Zr-108 5.00820E-10 5.00820E-10 401080 + 317 410950 Nb-95 3.28040E-06 5.79270E-02 41095.82c + 318 410951 Nb-95m 6.60500E-07 6.26820E-04 410951 + 319 410960 Nb-96 2.23350E-05 2.23350E-05 410960 + 320 410970 Nb-97 1.72300E-04 6.52770E-02 410970 + 321 410971 Nb-97m 3.46910E-05 6.18820E-02 410971 + 322 410980 Nb-98 2.35290E-04 7.29350E-02 410980 + 323 410981 Nb-98m 8.19810E-04 8.19810E-04 410981 + 324 410990 Nb-99 3.83340E-03 4.36620E-02 410990 + 325 410991 Nb-99m 7.71850E-04 2.36870E-02 410991 + 326 411000 Nb-100 1.73190E-03 5.41090E-02 411000 + 327 411001 Nb-100m 8.39610E-03 8.39610E-03 411001 + 328 411010 Nb-101 2.83130E-02 6.44790E-02 411010 + 329 411020 Nb-102 1.55300E-02 3.70520E-02 411020 + 330 411021 Nb-102m 1.55300E-02 1.55300E-02 411021 + 331 411030 Nb-103 2.95270E-02 3.60940E-02 411030 + 332 411040 Nb-104 7.79750E-03 9.74800E-03 411040 + 333 411041 Nb-104m 7.79750E-03 7.79750E-03 411041 + 334 411050 Nb-105 8.33570E-03 8.62520E-03 411050 + 335 411060 Nb-106 2.17370E-03 2.22080E-03 411060 + 336 411070 Nb-107 4.83010E-04 4.88690E-04 411070 + 337 411080 Nb-108 6.24140E-05 6.24140E-05 411080 + 338 411090 Nb-109 6.80610E-06 6.80610E-06 411090 + 339 411100 Nb-110 6.28910E-10 6.28910E-10 411100 + 340 420970 Mo-97 2.04640E-06 6.52790E-02 42097.82c + 341 420980 Mo-98 3.49650E-05 7.37900E-02 42098.82c + 342 420990 Mo-99 1.56560E-04 6.70320E-02 42099.82c + 343 421000 Mo-100 9.52730E-04 6.34580E-02 42100.82c + 344 421010 Mo-101 3.55990E-03 6.80390E-02 421010 + 345 421020 Mo-102 1.18760E-02 6.44580E-02 421020 + 346 421030 Mo-103 1.73360E-02 5.34400E-02 421030 + 347 421040 Mo-104 2.54010E-02 4.30830E-02 421040 + 348 421050 Mo-105 2.03200E-02 2.88990E-02 421050 + 349 421060 Mo-106 1.47430E-02 1.68930E-02 421060 + 350 421070 Mo-107 4.80640E-03 5.26960E-03 421070 + 351 421080 Mo-108 1.49230E-03 1.55170E-03 421080 + 352 421090 Mo-109 2.45510E-04 2.51450E-04 421090 + 353 421100 Mo-110 4.41300E-05 4.41300E-05 421100 + 354 421110 Mo-111 1.49210E-05 1.49210E-05 421110 + 355 421120 Mo-112 4.23020E-06 4.23020E-06 421120 + 356 421130 Mo-113 1.04360E-11 1.04360E-11 421130 + 357 431000 Tc-100 9.06060E-07 9.06060E-07 431000 + 358 431010 Tc-101 3.76130E-05 6.80760E-02 431010 + 359 431020 Tc-102 1.01690E-04 6.45590E-02 431020 + 360 431021 Tc-102m 1.01690E-04 1.01690E-04 431021 + 361 431030 Tc-103 8.63310E-04 5.43030E-02 431030 + 362 431040 Tc-104 2.23920E-03 4.53230E-02 431040 + 363 431050 Tc-105 5.49090E-03 3.43900E-02 431050 + 364 431060 Tc-106 6.60170E-03 2.34950E-02 431060 + 365 431070 Tc-107 6.96980E-03 1.22390E-02 431070 + 366 431080 Tc-108 3.75470E-03 5.30770E-03 431080 + 367 431090 Tc-109 1.83470E-03 2.08480E-03 431090 + 368 431100 Tc-110 5.07290E-04 5.51570E-04 431100 + 369 431110 Tc-111 1.39210E-04 1.54060E-04 431110 + 370 431120 Tc-112 2.81990E-05 3.23410E-05 431120 + 371 431130 Tc-113 4.91890E-06 4.91890E-06 431130 + 372 431140 Tc-114 1.84090E-09 1.84090E-09 431140 + 373 431150 Tc-115 6.09900E-11 6.09900E-11 431150 + 374 441020 Ru-102 6.36550E-06 6.46670E-02 44102.82c + 375 441030 Ru-103 2.05540E-06 5.43110E-02 44103.82c + 376 441031 Ru-103m 5.75090E-06 5.75090E-06 441031 + 377 441040 Ru-104 9.24740E-05 4.54150E-02 44104.82c + 378 441050 Ru-105 2.87750E-04 3.46770E-02 44105.82c + 379 441060 Ru-106 9.33990E-04 2.44290E-02 44106.82c + 380 441070 Ru-107 1.41170E-03 1.36510E-02 441070 + 381 441080 Ru-108 1.70540E-03 7.01480E-03 441080 + 382 441090 Ru-109 1.16000E-03 3.24340E-03 441090 + 383 441100 Ru-110 6.91060E-04 1.24240E-03 441100 + 384 441110 Ru-111 2.52090E-04 4.06640E-04 441110 + 385 441120 Ru-112 9.30550E-05 1.25270E-04 441120 + 386 441130 Ru-113 1.40540E-05 2.56460E-05 441130 + 387 441131 Ru-113m 1.40540E-05 1.40540E-05 441131 + 388 441140 Ru-114 1.19210E-05 1.19230E-05 441140 + 389 441150 Ru-115 3.50090E-06 3.50090E-06 441150 + 390 441160 Ru-116 6.92020E-07 6.92020E-07 441160 + 391 441170 Ru-117 4.17760E-10 4.17760E-10 441170 + 392 441180 Ru-118 1.10260E-11 1.10260E-11 441180 + 393 441200 Ru-120 5.30720E-09 5.30720E-09 441200 + 394 451050 Rh-105 1.67620E-06 3.46790E-02 45105.82c + 395 451051 Rh-105m 2.23180E-07 9.84430E-03 451051 + 396 451060 Rh-106 3.50450E-06 2.44320E-02 451060 + 397 451061 Rh-106m 9.55250E-06 9.55250E-06 451061 + 398 451070 Rh-107 3.28510E-05 1.36840E-02 451070 + 399 451080 Rh-108 1.69720E-05 7.03180E-03 451080 + 400 451081 Rh-108m 5.91350E-05 5.91350E-05 451081 + 401 451090 Rh-109 1.31520E-04 3.37490E-03 451090 + 402 451100 Rh-110 1.28470E-04 1.37090E-03 451100 + 403 451101 Rh-110m 3.02430E-06 3.02430E-06 451101 + 404 451110 Rh-111 1.35620E-04 5.42260E-04 451110 + 405 451120 Rh-112 3.63030E-05 1.61570E-04 451120 + 406 451121 Rh-112m 3.63030E-05 3.63030E-05 451121 + 407 451130 Rh-113 7.51870E-05 1.07860E-04 451130 + 408 451140 Rh-114 2.17380E-05 3.36690E-05 451140 + 409 451141 Rh-114m 2.17380E-05 2.17380E-05 451141 + 410 451150 Rh-115 3.43090E-05 3.78090E-05 451150 + 411 451160 Rh-116 2.97200E-06 3.65650E-06 451160 + 412 451161 Rh-116m 8.10100E-06 8.10100E-06 451161 + 413 451170 Rh-117 7.70920E-06 7.70960E-06 451170 + 414 451180 Rh-118 1.38900E-06 1.38900E-06 451180 + 415 451190 Rh-119 7.17650E-07 7.17650E-07 451190 + 416 451200 Rh-120 2.03980E-06 2.04510E-06 451200 + 417 451210 Rh-121 2.57060E-07 2.57060E-07 451210 + 418 451220 Rh-122 1.80500E-08 1.80500E-08 451220 + 419 461070 Pd-107 1.25870E-10 1.36840E-02 46107.82c + 420 461071 Pd-107m 2.76660E-10 2.76660E-10 461071 + 421 461080 Pd-108 1.52750E-08 7.09090E-03 46108.82c + 422 461090 Pd-109 9.45790E-07 3.37790E-03 461090 + 423 461091 Pd-109m 2.07880E-06 1.68950E-03 461091 + 424 461100 Pd-110 7.22640E-06 1.38110E-03 46110.82c + 425 461110 Pd-111 3.10920E-06 5.49770E-04 461110 + 426 461111 Pd-111m 6.83380E-06 9.00290E-06 461111 + 427 461120 Pd-112 1.40990E-05 2.11970E-04 461120 + 428 461130 Pd-113 2.77520E-06 1.18400E-04 461130 + 429 461131 Pd-113m 7.76480E-06 7.76480E-06 461131 + 430 461140 Pd-114 2.38410E-05 7.92490E-05 461140 + 431 461150 Pd-115 1.16040E-05 4.64030E-05 461150 + 432 461151 Pd-115m 2.55050E-05 3.09950E-05 461151 + 433 461160 Pd-116 5.74380E-05 6.91950E-05 461160 + 434 461170 Pd-117 1.29300E-05 4.91000E-05 461170 + 435 461171 Pd-117m 2.84200E-05 2.84200E-05 461171 + 436 461180 Pd-118 2.70870E-05 2.84350E-05 461180 + 437 461190 Pd-119 9.32950E-06 1.01680E-05 461190 + 438 461200 Pd-120 7.01560E-06 8.97430E-06 461200 + 439 461210 Pd-121 1.43410E-06 1.65630E-06 461210 + 440 461220 Pd-122 6.47870E-06 6.49680E-06 461220 + 441 461230 Pd-123 9.49200E-07 9.49200E-07 461230 + 442 461240 Pd-124 2.00110E-07 2.00110E-07 461240 + 443 471100 Ag-110 6.56450E-11 6.80790E-11 471100 + 444 471101 Ag-110m 1.78930E-10 1.78930E-10 47510.82c + 445 471110 Ag-111 6.52640E-10 5.49470E-04 47111.82c + 446 471111 Ag-111m 4.90180E-09 5.47630E-04 471111 + 447 471120 Ag-112 4.42990E-08 2.12010E-04 471120 + 448 471130 Ag-113 8.25670E-08 7.80640E-05 471130 + 449 471131 Ag-113m 6.20130E-07 1.14000E-04 471131 + 450 471140 Ag-114 3.59730E-07 8.13520E-05 471140 + 451 471141 Ag-114m 1.74400E-06 1.74400E-06 471141 + 452 471150 Ag-115 9.87210E-07 4.50380E-05 471150 + 453 471151 Ag-115m 7.41460E-06 4.84590E-05 471151 + 454 471160 Ag-116 3.34350E-06 7.30860E-05 471160 + 455 471161 Ag-116m 9.11350E-06 9.11350E-06 471161 + 456 471170 Ag-117 3.62320E-06 3.12790E-05 471170 + 457 471171 Ag-117m 2.72130E-05 5.17630E-05 471171 + 458 471180 Ag-118 6.76940E-06 4.62620E-05 471180 + 459 471181 Ag-118m 3.28180E-05 3.68830E-05 471181 + 460 471190 Ag-119 6.07130E-06 1.11560E-05 471190 + 461 471191 Ag-119m 4.56000E-05 5.06840E-05 471191 + 462 471200 Ag-120 1.20760E-05 2.57010E-05 471200 + 463 471201 Ag-120m 2.01960E-05 2.46830E-05 471201 + 464 471210 Ag-121 2.29450E-05 2.45970E-05 471210 + 465 471220 Ag-122 4.50860E-06 1.10050E-05 471220 + 466 471221 Ag-122m 4.86090E-06 4.86090E-06 471221 + 467 471230 Ag-123 1.21460E-05 1.30950E-05 471230 + 468 471240 Ag-124 4.54030E-06 7.18790E-06 471240 + 469 471241 Ag-124m 4.89500E-06 4.89500E-06 471241 + 470 471250 Ag-125 1.17140E-05 1.17140E-05 471250 + 471 471260 Ag-126 4.49510E-06 4.49510E-06 471260 + 472 471270 Ag-127 3.13060E-06 3.13060E-06 471270 + 473 471280 Ag-128 4.43830E-08 4.43830E-08 471280 + 474 471290 Ag-129 2.22060E-09 2.22060E-09 471290 + 475 481120 Cd-112 7.45320E-12 2.12010E-04 48112.82c + 476 481130 Cd-113 3.34300E-11 1.17760E-04 48113.82c + 477 481131 Cd-113m 1.26600E-10 1.34980E-06 481131 + 478 481140 Cd-114 4.53430E-09 8.13570E-05 48114.82c + 479 481150 Cd-115 1.53460E-08 7.96260E-05 481150 + 480 481151 Cd-115m 5.81160E-08 3.76790E-06 48515.82c + 481 481160 Cd-116 9.34540E-07 8.25870E-05 48116.82c + 482 481170 Cd-117 1.46400E-07 6.27350E-05 481170 + 483 481171 Cd-117m 5.54420E-07 1.79020E-05 481171 + 484 481180 Cd-118 1.04170E-05 7.84390E-05 481180 + 485 481190 Cd-119 2.64540E-06 5.89070E-05 481190 + 486 481191 Cd-119m 7.40160E-06 1.29800E-05 481191 + 487 481200 Cd-120 3.57790E-05 7.70290E-05 481200 + 488 481210 Cd-121 9.06200E-06 3.10890E-05 481210 + 489 481211 Cd-121m 2.53550E-05 2.79250E-05 481211 + 490 481220 Cd-122 4.88550E-05 6.47210E-05 481220 + 491 481230 Cd-123 9.59410E-06 2.03120E-05 481230 + 492 481231 Cd-123m 2.68440E-05 2.92290E-05 481231 + 493 481240 Cd-124 6.67740E-05 7.64020E-05 481240 + 494 481250 Cd-125 2.54480E-05 3.13050E-05 481250 + 495 481251 Cd-125m 7.12010E-05 7.70580E-05 481251 + 496 481260 Cd-126 1.75350E-04 1.79850E-04 481260 + 497 481270 Cd-127 1.44040E-04 1.47170E-04 481270 + 498 481280 Cd-128 8.38190E-05 8.38630E-05 481280 + 499 481290 Cd-129 8.12490E-06 8.12600E-06 481290 + 500 481291 Cd-129m 2.27330E-05 2.27340E-05 481291 + 501 481300 Cd-130 3.73880E-06 3.73880E-06 481300 + 502 481310 Cd-131 3.76710E-08 3.76710E-08 481310 + 503 481320 Cd-132 1.68070E-09 1.68070E-09 481320 + 504 491150 In-115 1.26920E-11 7.94120E-05 49115.82c + 505 491151 In-115m 2.55560E-12 7.96260E-05 491151 + 506 491160 In-116 1.18800E-10 1.18800E-10 491160 + 507 491161 In-116m 1.91840E-10 4.13940E-10 491161 + 508 491162 In-116m 2.22100E-10 2.22100E-10 491162 + 509 491170 In-117 1.37500E-08 5.00950E-05 491170 + 510 491171 In-117m 2.76860E-09 5.77670E-05 491171 + 511 491180 In-118 4.34070E-08 7.84830E-05 491180 + 512 491181 In-118m 7.00940E-08 1.50110E-07 491181 + 513 491182 In-118m 8.11500E-08 8.11500E-08 491182 + 514 491190 In-119 1.48130E-06 2.31560E-05 491190 + 515 491191 In-119m 2.98240E-07 5.35070E-05 491191 + 516 491200 In-120 1.16910E-06 7.81980E-05 491200 + 517 491201 In-120m 1.16910E-06 1.16910E-06 491201 + 518 491202 In-120m 1.16910E-06 1.16910E-06 491202 + 519 491210 In-121 5.37160E-06 4.40280E-05 491210 + 520 491211 In-121m 1.08160E-06 2.17000E-05 491211 + 521 491220 In-122 7.51320E-06 7.22340E-05 491220 + 522 491221 In-122m 6.28240E-06 6.28240E-06 491221 + 523 491222 In-122m 6.28240E-06 6.28240E-06 491222 + 524 491230 In-123 2.43840E-05 5.95470E-05 491230 + 525 491231 In-123m 4.90950E-06 1.92860E-05 491231 + 526 491240 In-124 3.03830E-05 1.06790E-04 491240 + 527 491241 In-124m 3.27580E-05 3.27580E-05 491241 + 528 491250 In-125 1.07870E-04 1.99910E-04 491250 + 529 491251 In-125m 2.17190E-05 3.80400E-05 491251 + 530 491260 In-126 1.97950E-04 3.77790E-04 491260 + 531 491261 In-126m 2.13410E-04 2.13410E-04 491261 + 532 491270 In-127 9.82150E-04 9.82150E-04 491270 + 533 491271 In-127m 1.97750E-04 3.44920E-04 491271 + 534 491280 In-128 5.56250E-04 8.57920E-04 491280 + 535 491281 In-128m 2.17800E-04 3.01670E-04 491281 + 536 491282 In-128m 8.34540E-04 8.34540E-04 491282 + 537 491290 In-129 1.44950E-03 1.47230E-03 491290 + 538 491291 In-129m 2.91860E-04 3.00050E-04 491291 + 539 491300 In-130 2.04350E-04 2.07960E-04 491300 + 540 491301 In-130m 2.97550E-04 2.97550E-04 491301 + 541 491302 In-130m 4.14470E-04 4.14470E-04 491302 + 542 491310 In-131 1.00560E-04 1.01620E-04 491310 + 543 491311 In-131m 1.00560E-04 1.00560E-04 491311 + 544 491312 In-131m 1.00560E-04 1.00560E-04 491312 + 545 491320 In-132 4.14470E-05 4.14480E-05 491320 + 546 491330 In-133 2.29650E-06 2.75890E-06 491330 + 547 491331 In-133m 4.62390E-07 4.62390E-07 491331 + 548 491340 In-134 2.47240E-08 2.47240E-08 491340 + 549 501170 Sn-117 4.90290E-13 8.06530E-05 50117.82c + 550 501171 Sn-117m 1.85670E-12 1.70680E-07 501171 + 551 501180 Sn-118 9.64790E-11 7.86340E-05 50118.82c + 552 501190 Sn-119 5.51830E-10 7.36690E-05 50119.82c + 553 501191 Sn-119m 2.08980E-09 2.09210E-05 501191 + 554 501210 Sn-121 1.00060E-12 6.43500E-05 501210 + 555 501211 Sn-121m 2.79960E-12 4.98760E-06 501211 + 556 501220 Sn-122 3.35540E-10 8.48000E-05 50122.82c + 557 501230 Sn-123 3.68450E-06 8.22440E-06 50123.82c + 558 501231 Sn-123m 1.31680E-06 7.56100E-05 501231 + 559 501240 Sn-124 1.37900E-05 1.53330E-04 50124.82c + 560 501250 Sn-125 2.15730E-05 5.53420E-05 50125.82c + 561 501251 Sn-125m 7.71020E-06 2.11890E-04 501251 + 562 501260 Sn-126 1.66300E-04 7.59880E-04 50126.82c + 563 501270 Sn-127 5.63330E-04 9.46140E-04 501270 + 564 501271 Sn-127m 2.01330E-04 1.14320E-03 501271 + 565 501280 Sn-128 7.70090E-04 4.56170E-03 501280 + 566 501281 Sn-128m 2.09910E-03 2.93360E-03 501281 + 567 501290 Sn-129 1.45230E-03 3.06800E-03 501290 + 568 501291 Sn-129m 4.06330E-03 4.22010E-03 501291 + 569 501300 Sn-130 2.14180E-03 2.70510E-03 501300 + 570 501301 Sn-130m 5.83810E-03 6.19680E-03 501301 + 571 501310 Sn-131 1.64990E-03 1.84470E-03 501310 + 572 501311 Sn-131m 4.61650E-03 4.72140E-03 501311 + 573 501320 Sn-132 5.14870E-03 5.19250E-03 501320 + 574 501330 Sn-133 8.24690E-04 8.25120E-04 501330 + 575 501340 Sn-134 1.46710E-04 1.46720E-04 501340 + 576 501350 Sn-135 1.86740E-06 1.86740E-06 501350 + 577 501360 Sn-136 5.93690E-08 5.93690E-08 501360 + 578 501370 Sn-137 2.61260E-09 2.61260E-09 501370 + 579 511240 Sb-124 2.12500E-11 5.46910E-11 51124.82c + 580 511241 Sb-124m 1.71420E-11 4.45870E-11 511241 + 581 511242 Sb-124m 2.74450E-11 2.74450E-11 511242 + 582 511250 Sb-125 2.92820E-06 2.70160E-04 51125.82c + 583 511260 Sb-126 4.99570E-06 5.97410E-06 51126.82c + 584 511261 Sb-126m 3.12040E-06 6.98850E-06 511261 + 585 511262 Sb-126m 3.86810E-06 3.86810E-06 511262 + 586 511270 Sb-127 6.48700E-05 2.15420E-03 511270 + 587 511280 Sb-128 1.16870E-04 4.68440E-03 511280 + 588 511281 Sb-128m 1.63470E-04 1.63470E-04 511281 + 589 511290 Sb-129 1.06350E-03 6.67600E-03 511290 + 590 511291 Sb-129m 7.87020E-04 2.89700E-03 511291 + 591 511300 Sb-130 2.58810E-03 8.39150E-03 511300 + 592 511301 Sb-130m 2.58810E-03 5.68650E-03 511301 + 593 511310 Sb-131 1.28990E-02 1.94650E-02 511310 + 594 511320 Sb-132 1.44960E-02 1.96890E-02 511320 + 595 511321 Sb-132m 1.28350E-02 1.28350E-02 511321 + 596 511330 Sb-133 3.49040E-02 3.57540E-02 511330 + 597 511340 Sb-134 4.64140E-03 4.76340E-03 511340 + 598 511341 Sb-134m 1.26520E-02 1.26520E-02 511341 + 599 511350 Sb-135 8.11790E-04 8.13280E-04 511350 + 600 511360 Sb-136 2.37710E-04 2.37750E-04 511360 + 601 511370 Sb-137 1.17450E-04 1.17450E-04 511370 + 602 511380 Sb-138 7.12400E-06 7.12400E-06 511380 + 603 511390 Sb-139 1.49830E-08 1.49830E-08 511390 + 604 521260 Te-126 5.40500E-11 1.19840E-05 52126.82c + 605 521270 Te-127 2.06060E-07 2.14650E-03 521270 + 606 521271 Te-127m 5.76550E-07 3.55580E-04 52527.82c + 607 521280 Te-128 3.91560E-06 4.84590E-03 52128.82c + 608 521290 Te-129 1.06180E-05 7.86810E-03 521290 + 609 521291 Te-129m 2.97070E-05 3.54240E-03 52529.82c + 610 521300 Te-130 4.11170E-04 1.44890E-02 52130.82c + 611 521310 Te-131 5.17670E-04 1.90560E-02 521310 + 612 521311 Te-131m 1.44840E-03 3.00680E-03 521311 + 613 521320 Te-132 1.21500E-02 4.46730E-02 52132.82c + 614 521330 Te-133 9.72310E-03 4.51450E-02 521330 + 615 521331 Te-133m 2.72050E-02 3.33920E-02 521331 + 616 521340 Te-134 7.33400E-02 9.08720E-02 521340 + 617 521350 Te-135 9.29900E-05 8.17340E-04 521350 + 618 521360 Te-136 1.84630E-03 2.10220E-03 521360 + 619 521370 Te-137 3.83700E-03 3.89690E-03 521370 + 620 521380 Te-138 8.63290E-04 8.70410E-04 521380 + 621 521390 Te-139 8.48030E-05 8.48180E-05 521390 + 622 521400 Te-140 1.01960E-05 1.01960E-05 521400 + 623 521410 Te-141 3.33750E-06 3.33750E-06 521410 + 624 521420 Te-142 2.14650E-09 2.14650E-09 521420 + 625 531290 I-129 7.91090E-07 9.17960E-03 53129.82c + 626 531300 I-130 2.18820E-06 2.86250E-06 53130.82c + 627 531301 I-130m 8.02780E-07 8.02780E-07 531301 + 628 531310 I-131 3.50140E-05 2.14660E-02 53131.82c + 629 531320 I-132 2.07220E-04 4.50390E-02 531320 + 630 531321 I-132m 1.83470E-04 1.83470E-04 531321 + 631 531330 I-133 2.03150E-03 7.62290E-02 531330 + 632 531331 I-133m 1.50340E-03 1.50340E-03 531331 + 633 531340 I-134 1.27620E-02 1.14670E-01 531340 + 634 531341 I-134m 1.13000E-02 1.13000E-02 531341 + 635 531350 I-135 2.79680E-02 2.87850E-02 53135.82c + 636 531360 I-136 7.70520E-03 9.86570E-03 531360 + 637 531361 I-136m 2.10030E-02 2.10610E-02 531361 + 638 531370 I-137 5.93540E-02 6.31890E-02 531370 + 639 531380 I-138 2.47970E-02 2.56130E-02 531380 + 640 531390 I-139 1.38310E-02 1.39160E-02 531390 + 641 531400 I-140 3.93660E-03 3.94680E-03 531400 + 642 531410 I-141 1.16470E-03 1.16800E-03 531410 + 643 531420 I-142 1.20170E-04 1.20170E-04 531420 + 644 531430 I-143 2.07680E-05 2.07680E-05 531430 + 645 531440 I-144 1.87300E-06 1.87300E-06 531440 + 646 541310 Xe-131 3.42030E-10 2.14660E-02 54131.82c + 647 541311 Xe-131m 9.56970E-10 2.33160E-04 541311 + 648 541320 Xe-132 4.91680E-07 4.50650E-02 54132.82c + 649 541321 Xe-132m 6.58720E-07 6.58720E-07 541321 + 650 541330 Xe-133 6.17670E-06 7.62520E-02 54133.82c + 651 541331 Xe-133m 1.72820E-05 2.18700E-03 541331 + 652 541340 Xe-134 8.76140E-05 1.15260E-01 54134.82c + 653 541341 Xe-134m 2.38820E-04 4.98710E-04 541341 + 654 541350 Xe-135 1.19060E-04 2.92070E-02 54135.82c + 655 541351 Xe-135m 3.33110E-04 5.08520E-03 541351 + 656 541360 Xe-136 4.96710E-03 4.00010E-02 54136.82c + 657 541370 Xe-137 2.59220E-02 8.63610E-02 541370 + 658 541380 Xe-138 4.12820E-02 6.69010E-02 541380 + 659 541390 Xe-139 2.65800E-02 3.94990E-02 541390 + 660 541400 Xe-140 2.25350E-02 2.63600E-02 541400 + 661 541410 Xe-141 1.19960E-02 1.29490E-02 541410 + 662 541420 Xe-142 4.62910E-03 4.72750E-03 541420 + 663 541430 Xe-143 8.57490E-04 8.70700E-04 541430 + 664 541440 Xe-144 1.34550E-04 1.35670E-04 541440 + 665 541450 Xe-145 1.54380E-05 1.54380E-05 541450 + 666 541460 Xe-146 6.79340E-08 6.79340E-08 541460 + 667 541470 Xe-147 7.92450E-10 7.92450E-10 541470 + 668 551340 Cs-134 2.78670E-08 5.25400E-08 55134.82c + 669 551341 Cs-134m 2.46730E-08 2.46730E-08 551341 + 670 551350 Cs-135 1.07310E-06 2.92390E-02 55135.82c + 671 551351 Cs-135m 7.94120E-07 7.94120E-07 551351 + 672 551360 Cs-136 2.39960E-05 3.25750E-05 55136.82c + 673 551361 Cs-136m 1.71570E-05 1.71570E-05 551361 + 674 551370 Cs-137 2.00150E-03 8.83630E-02 55137.82c + 675 551380 Cs-138 2.66970E-03 7.31870E-02 551380 + 676 551381 Cs-138m 4.46480E-03 4.46480E-03 551381 + 677 551390 Cs-139 2.02100E-02 5.97090E-02 551390 + 678 551400 Cs-140 2.62530E-02 5.26190E-02 551400 + 679 551410 Cs-141 4.86500E-02 6.16100E-02 551410 + 680 551420 Cs-142 3.82530E-02 4.29720E-02 551420 + 681 551430 Cs-143 2.12600E-02 2.21260E-02 551430 + 682 551440 Cs-144 5.07000E-03 7.73720E-03 551440 + 683 551441 Cs-144m 5.07000E-03 5.07040E-03 551441 + 684 551450 Cs-145 3.71740E-03 3.73210E-03 551450 + 685 551460 Cs-146 8.51080E-04 8.51140E-04 551460 + 686 551470 Cs-147 1.85840E-04 1.85840E-04 551470 + 687 551480 Cs-148 1.13050E-05 1.13050E-05 551480 + 688 551490 Cs-149 3.39380E-09 3.39380E-09 551490 + 689 561360 Ba-136 5.40150E-10 4.11550E-05 56136.82c + 690 561361 Ba-136m 1.47230E-09 1.47230E-09 561361 + 691 561370 Ba-137 3.13190E-07 8.83640E-02 56137.82c + 692 561371 Ba-137m 8.76310E-07 8.34150E-02 561371 + 693 561380 Ba-138 9.15380E-05 7.41270E-02 56138.82c + 694 561390 Ba-139 4.21990E-04 6.01310E-02 561390 + 695 561400 Ba-140 2.04850E-03 5.46670E-02 56140.82c + 696 561410 Ba-141 4.69260E-03 6.63030E-02 561410 + 697 561420 Ba-142 1.61520E-02 5.94870E-02 561420 + 698 561430 Ba-143 1.85670E-02 4.05780E-02 561430 + 699 561440 Ba-144 2.26450E-02 3.32030E-02 561440 + 700 561450 Ba-145 1.34570E-02 1.67760E-02 561450 + 701 561460 Ba-146 7.85620E-03 8.63940E-03 561460 + 702 561470 Ba-147 2.82350E-03 2.95920E-03 561470 + 703 561480 Ba-148 5.45930E-04 5.54400E-04 561480 + 704 561490 Ba-149 7.78370E-05 7.78400E-05 561490 + 705 561500 Ba-150 9.28170E-06 9.28170E-06 561500 + 706 561510 Ba-151 1.33530E-08 1.33530E-08 561510 + 707 561520 Ba-152 1.58910E-10 1.58910E-10 561520 + 708 571390 La-139 2.09830E-06 6.01330E-02 57139.82c + 709 571400 La-140 2.65300E-05 5.46940E-02 57140.82c + 710 571410 La-141 1.91820E-04 6.64940E-02 571410 + 711 571420 La-142 6.05380E-04 6.00930E-02 571420 + 712 571430 La-143 3.11350E-03 4.36910E-02 571430 + 713 571440 La-144 7.88980E-03 4.10930E-02 571440 + 714 571450 La-145 1.79640E-02 3.47400E-02 571450 + 715 571460 La-146 6.49670E-03 1.51360E-02 571460 + 716 571461 La-146m 1.36290E-02 1.36290E-02 571461 + 717 571470 La-147 1.98000E-02 2.27610E-02 571470 + 718 571480 La-148 1.00900E-02 1.06420E-02 571480 + 719 571490 La-149 4.69100E-03 4.76850E-03 571490 + 720 571500 La-150 1.39640E-03 1.40570E-03 571500 + 721 571510 La-151 3.66640E-04 3.66650E-04 571510 + 722 571520 La-152 3.61580E-05 3.61580E-05 571520 + 723 571530 La-153 5.78000E-06 5.78000E-06 571530 + 724 571540 La-154 4.16690E-10 4.16690E-10 571540 + 725 581410 Ce-141 3.83390E-09 6.64940E-02 58141.82c + 726 581420 Ce-142 4.37500E-06 6.00970E-02 58142.82c + 727 581430 Ce-143 1.89770E-05 4.37100E-02 58143.82c + 728 581440 Ce-144 1.38040E-04 4.12310E-02 58144.82c + 729 581450 Ce-145 5.24150E-04 3.52640E-02 581450 + 730 581460 Ce-146 2.46930E-03 3.12350E-02 581460 + 731 581470 Ce-147 4.02460E-03 2.67860E-02 581470 + 732 581480 Ce-148 6.50220E-03 1.72120E-02 581480 + 733 581490 Ce-149 5.82750E-03 1.05670E-02 581490 + 734 581500 Ce-150 4.58360E-03 5.95130E-03 581500 + 735 581510 Ce-151 2.01290E-03 2.38170E-03 581510 + 736 581520 Ce-152 5.86830E-04 6.20800E-04 581520 + 737 581530 Ce-153 9.79060E-05 1.03690E-04 581530 + 738 581540 Ce-154 1.86220E-05 1.86220E-05 581540 + 739 581550 Ce-155 2.97860E-06 2.97860E-06 581550 + 740 581560 Ce-156 1.36140E-09 1.36140E-09 581560 + 741 581570 Ce-157 1.09550E-11 1.09550E-11 581570 + 742 591440 Pr-144 1.47550E-09 4.12310E-02 591440 + 743 591441 Pr-144m 1.50110E-08 5.68980E-04 591441 + 744 591450 Pr-145 1.06140E-05 3.52750E-02 591450 + 745 591460 Pr-146 4.33710E-05 3.12780E-02 591460 + 746 591470 Pr-147 2.75470E-04 2.70610E-02 591470 + 747 591480 Pr-148 1.21920E-04 1.73330E-02 591480 + 748 591481 Pr-148m 5.91080E-04 5.91080E-04 591481 + 749 591490 Pr-149 1.98860E-03 1.25560E-02 591490 + 750 591500 Pr-150 3.13470E-03 9.08600E-03 591500 + 751 591510 Pr-151 4.44060E-03 6.82230E-03 591510 + 752 591520 Pr-152 3.13410E-03 3.75550E-03 591520 + 753 591530 Pr-153 1.50690E-03 1.61010E-03 591530 + 754 591540 Pr-154 7.43880E-04 7.62380E-04 591540 + 755 591550 Pr-155 1.91680E-04 1.94660E-04 591550 + 756 591560 Pr-156 2.41610E-05 2.41620E-05 591560 + 757 591570 Pr-157 2.24580E-06 2.24580E-06 591570 + 758 591580 Pr-158 2.51020E-09 2.51020E-09 591580 + 759 591590 Pr-159 2.89160E-11 2.89160E-11 591590 + 760 601460 Nd-146 2.19140E-09 3.12780E-02 60146.82c + 761 601470 Nd-147 1.03510E-06 2.70620E-02 60147.82c + 762 601480 Nd-148 4.34840E-06 1.79290E-02 60148.82c + 763 601490 Nd-149 2.53520E-05 1.25810E-02 601490 + 764 601500 Nd-150 1.23050E-04 9.20910E-03 60150.82c + 765 601510 Nd-151 2.98320E-04 7.12070E-03 601510 + 766 601520 Nd-152 6.90620E-04 4.44620E-03 601520 + 767 601530 Nd-153 6.14310E-04 2.22440E-03 601530 + 768 601540 Nd-154 7.79050E-04 1.54140E-03 601540 + 769 601550 Nd-155 4.02110E-04 5.97420E-04 601550 + 770 601560 Nd-156 1.65850E-04 1.89500E-04 601560 + 771 601570 Nd-157 4.60430E-05 4.81450E-05 601570 + 772 601580 Nd-158 1.12370E-05 1.12390E-05 601580 + 773 601590 Nd-159 1.26670E-07 1.26700E-07 601590 + 774 601600 Nd-160 4.54990E-09 4.54990E-09 601600 + 775 601610 Nd-161 6.86550E-11 6.86550E-11 601610 + 776 611490 Pm-149 5.65640E-09 1.25810E-02 61149.82c + 777 611500 Pm-150 1.85630E-06 1.85630E-06 611500 + 778 611510 Pm-151 1.28050E-05 7.13350E-03 61151.82c + 779 611520 Pm-152 5.85060E-06 4.45200E-03 611520 + 780 611521 Pm-152m 1.23000E-05 1.23000E-05 611521 + 781 611522 Pm-152m 1.60670E-05 1.60670E-05 611522 + 782 611530 Pm-153 1.14660E-04 2.33900E-03 611530 + 783 611540 Pm-154 1.43600E-04 1.68500E-03 611540 + 784 611541 Pm-154m 1.43600E-04 1.43600E-04 611541 + 785 611550 Pm-155 3.83950E-04 9.81380E-04 611550 + 786 611560 Pm-156 3.77700E-04 5.67200E-04 611560 + 787 611570 Pm-157 2.70620E-04 3.18770E-04 611570 + 788 611580 Pm-158 1.35970E-04 1.47210E-04 611580 + 789 611590 Pm-159 4.26110E-05 4.27370E-05 611590 + 790 611600 Pm-160 9.90990E-06 9.91440E-06 611600 + 791 611610 Pm-161 1.56480E-07 1.56550E-07 611610 + 792 611620 Pm-162 4.69290E-09 4.69290E-09 611620 + 793 611630 Pm-163 6.28610E-11 6.28610E-11 611630 + 794 621510 Sm-151 4.23890E-10 7.13350E-03 62151.82c + 795 621520 Sm-152 1.70040E-08 4.48040E-03 62152.82c + 796 621530 Sm-153 2.17360E-07 2.33990E-03 62153.82c + 797 621531 Sm-153m 6.08160E-07 6.08160E-07 621531 + 798 621540 Sm-154 2.06770E-06 1.83070E-03 62154.82c + 799 621550 Sm-155 1.58820E-05 9.97260E-04 621550 + 800 621560 Sm-156 2.74520E-05 5.94650E-04 621560 + 801 621570 Sm-157 5.16480E-05 3.70410E-04 621570 + 802 621580 Sm-158 7.75260E-05 2.24740E-04 621580 + 803 621590 Sm-159 3.66900E-05 7.94460E-05 621590 + 804 621600 Sm-160 2.72520E-05 3.71400E-05 621600 + 805 621610 Sm-161 9.85440E-06 1.00110E-05 621610 + 806 621620 Sm-162 3.82090E-06 3.82560E-06 621620 + 807 621630 Sm-163 6.21210E-08 6.21840E-08 621630 + 808 621640 Sm-164 6.66910E-09 6.66910E-09 621640 + 809 621650 Sm-165 1.31660E-10 1.31660E-10 621650 + 810 631540 Eu-154 3.34180E-10 6.94480E-10 63154.82c + 811 631541 Eu-154m 3.60300E-10 3.60300E-10 631541 + 812 631550 Eu-155 9.92720E-07 9.98250E-04 63155.82c + 813 631560 Eu-156 1.09810E-06 5.95750E-04 63156.82c + 814 631570 Eu-157 5.61430E-06 3.76030E-04 63157.82c + 815 631580 Eu-158 1.79780E-05 2.42720E-04 631580 + 816 631590 Eu-159 2.60380E-05 1.05480E-04 631590 + 817 631600 Eu-160 1.85800E-05 5.57200E-05 631600 + 818 631610 Eu-161 2.46350E-05 3.46460E-05 631610 + 819 631620 Eu-162 1.14630E-05 1.52890E-05 631620 + 820 631630 Eu-163 2.47120E-06 2.53340E-06 631630 + 821 631640 Eu-164 1.13260E-06 1.13930E-06 631640 + 822 631650 Eu-165 6.83810E-08 6.85130E-08 631650 + 823 631660 Eu-166 3.81060E-09 3.81060E-09 631660 + 824 631670 Eu-167 1.59690E-10 1.59690E-10 631670 + 825 641560 Gd-156 4.18890E-11 5.95750E-04 64156.82c + 826 641570 Gd-157 1.15020E-09 3.76030E-04 64157.82c + 827 641580 Gd-158 2.80560E-08 2.42750E-04 64158.82c + 828 641590 Gd-159 1.74190E-07 1.05660E-04 641590 + 829 641600 Gd-160 2.47740E-06 5.81970E-05 64160.82c + 830 641610 Gd-161 1.23180E-06 3.58780E-05 641610 + 831 641620 Gd-162 2.54720E-06 1.78360E-05 641620 + 832 641630 Gd-163 2.47120E-06 5.00460E-06 641630 + 833 641640 Gd-164 3.39790E-06 4.53720E-06 641640 + 834 641650 Gd-165 1.02960E-06 1.09810E-06 641650 + 835 641660 Gd-166 3.14010E-07 3.17820E-07 641660 + 836 641670 Gd-167 3.66350E-08 3.67950E-08 641670 + 837 641680 Gd-168 3.68340E-09 3.68340E-09 641680 + 838 641690 Gd-169 1.55080E-10 1.55080E-10 641690 + 839 651590 Tb-159 4.81920E-11 1.05660E-04 65159.82c + 840 651600 Tb-160 9.24490E-10 9.24490E-10 65160.82c + 841 651610 Tb-161 1.59060E-08 3.58940E-05 651610 + 842 651620 Tb-162 8.48110E-08 1.79210E-05 651620 + 843 651630 Tb-163 2.05520E-07 5.21010E-06 651630 + 844 651640 Tb-164 6.52350E-07 5.18950E-06 651640 + 845 651650 Tb-165 8.62130E-07 1.96020E-06 651650 + 846 651660 Tb-166 5.70690E-07 8.88510E-07 651660 + 847 651670 Tb-167 3.21160E-07 3.57950E-07 651670 + 848 651680 Tb-168 7.99620E-08 8.36450E-08 651680 + 849 651690 Tb-169 1.91610E-08 1.93160E-08 651690 + 850 651700 Tb-170 1.72900E-09 1.72900E-09 651700 + 851 651710 Tb-171 1.38060E-10 1.38060E-10 651710 + 852 661610 Dy-161 2.08050E-12 3.58940E-05 66161.82c + 853 661620 Dy-162 6.45090E-11 1.79210E-05 66162.82c + 854 661630 Dy-163 4.65320E-10 5.21060E-06 66163.82c + 855 661640 Dy-164 8.90650E-09 5.19840E-06 66164.82c + 856 661650 Dy-165 2.77100E-08 1.99160E-06 661650 + 857 661651 Dy-165m 3.68940E-09 3.68940E-09 661651 + 858 661660 Dy-166 1.07940E-07 9.96450E-07 661660 + 859 661670 Dy-167 1.37400E-07 4.95350E-07 661670 + 860 661680 Dy-168 1.56890E-07 2.40530E-07 661680 + 861 661690 Dy-169 8.30550E-08 1.02370E-07 661690 + 862 661700 Dy-170 3.76020E-08 3.93310E-08 661700 + 863 661710 Dy-171 7.75950E-09 7.89760E-09 661710 + 864 661720 Dy-172 1.43690E-09 1.43690E-09 661720 + 865 661730 Dy-173 9.93090E-11 9.93090E-11 661730 + 866 671640 Ho-164 4.30490E-13 1.60390E-12 671640 + 867 671641 Ho-164m 1.17340E-12 1.17340E-12 671641 + 868 671650 Ho-165 3.74260E-11 1.99170E-06 67165.82c + 869 671660 Ho-166 1.00970E-10 9.96550E-07 671660 + 870 671661 Ho-166m 2.75210E-10 2.75210E-10 671661 + 871 671670 Ho-167 2.80260E-09 4.98160E-07 671670 + 872 671680 Ho-168 3.06870E-09 2.48710E-07 671680 + 873 671681 Ho-168m 5.13200E-09 5.13200E-09 671681 + 874 671690 Ho-169 2.16010E-08 1.23970E-07 671690 + 875 671700 Ho-170 1.57320E-08 1.57320E-08 671700 + 876 671701 Ho-170m 5.77140E-09 4.51020E-08 671701 + 877 671710 Ho-171 2.03820E-08 2.82800E-08 671710 + 878 671720 Ho-172 8.59810E-09 1.00350E-08 671720 + 879 671730 Ho-173 3.11320E-09 3.21250E-09 671730 + 880 671740 Ho-174 4.57210E-10 4.57210E-10 671740 + 881 671750 Ho-175 6.71350E-11 6.71350E-11 671750 + 882 681670 Er-167 1.28440E-12 4.98160E-07 68167.82c + 883 681671 Er-167m 1.71010E-13 5.95260E-08 681671 + 884 681680 Er-168 2.67920E-11 2.48760E-07 68168.82c + 885 681690 Er-169 2.01130E-10 1.24170E-07 681690 + 886 681700 Er-170 1.13100E-09 6.19650E-08 68170.82c + 887 681710 Er-171 2.63140E-09 3.09110E-08 681710 + 888 681720 Er-172 5.31670E-09 1.53520E-08 681720 + 889 681730 Er-173 4.17130E-09 7.38380E-09 681730 + 890 681740 Er-174 2.86370E-09 3.32090E-09 681740 + 891 681750 Er-175 9.96360E-10 1.06350E-09 681750 + 892 681760 Er-176 3.04430E-10 3.04430E-10 681760 + 893 681770 Er-177 3.56850E-11 3.56850E-11 681770 + 894 691710 Tm-171 1.32350E-11 3.09240E-08 691710 + 895 691720 Tm-172 7.39720E-11 1.54260E-08 691720 + 896 691730 Tm-173 3.14940E-10 7.69870E-09 691730 + 897 691740 Tm-174 5.08530E-10 3.82940E-09 691740 + 898 691750 Tm-175 8.23570E-10 1.88710E-09 691750 + 899 691760 Tm-176 5.46050E-10 8.50480E-10 691760 + 900 691770 Tm-177 3.08490E-10 3.44180E-10 691770 + 901 691780 Tm-178 7.72170E-11 7.72170E-11 691780 + 902 691790 Tm-179 1.85880E-11 1.85880E-11 691790 + 903 701740 Yb-174 6.83410E-12 3.83630E-09 701740 + 904 701750 Yb-175 2.60800E-11 1.91660E-09 701750 + 905 701751 Yb-175m 3.47250E-12 1.45650E-09 701751 + 906 701760 Yb-176 3.28770E-11 9.02910E-10 701760 + 907 701761 Yb-176m 6.89730E-11 4.94210E-10 701761 + 908 701770 Yb-177 1.08440E-10 4.74450E-10 701770 + 909 701771 Yb-177m 2.18330E-11 3.66010E-10 701771 + 910 701780 Yb-178 1.49550E-10 2.26770E-10 701780 + 911 701790 Yb-179 7.94860E-11 9.80740E-11 701790 + 912 701800 Yb-180 3.61340E-11 3.61340E-11 701800 + 913 701810 Yb-181 7.50310E-12 7.50310E-12 701810 + 914 711770 Lu-177 1.74470E-12 4.76380E-10 711770 + 915 711780 Lu-178 3.29340E-12 2.30060E-10 711780 + 916 711781 Lu-178m 4.41230E-12 4.41230E-12 711781 + 917 711790 Lu-179 1.80000E-11 1.18470E-10 711790 + 918 711791 Lu-179m 2.39650E-12 1.00470E-10 711791 + 919 711800 Lu-180 5.40930E-12 3.09700E-11 711800 + 920 711801 Lu-180m 5.40930E-12 4.15430E-11 711801 + 921 711802 Lu-180m 9.57840E-12 9.57840E-12 711802 + 922 711810 Lu-181 1.94500E-11 2.69530E-11 711810 + 923 711820 Lu-182 8.25090E-12 8.25090E-12 711820 + 924 711830 Lu-183 3.00090E-12 3.00090E-12 711830 + 925 721800 Hf-180 3.41170E-13 5.75710E-11 72180.82c + 926 721801 Hf-180m 7.15730E-13 5.50490E-12 721801 + 927 721810 Hf-181 2.47650E-12 2.94300E-11 721810 + 928 721820 Hf-182 1.62550E-12 1.13090E-11 721820 + 929 721821 Hf-182m 3.41010E-12 3.41010E-12 721821 + 930 721830 Hf-183 3.96920E-12 6.97010E-12 721830 + 931 721841 Hf-184m 1.85500E-12 1.85500E-12 721841 + + Nuclide 93239.82c -- neptunium 239 (Np-239) is using NFY data from U-238 + + Nuclide 94236.82c -- plutonium 236 (Pu-236) is using NFY data from Th-232 + + Nuclide 94237.82c -- plutonium 237 (Pu-237) is using NFY data from U-235 + + Nuclide 94238.82c -- plutonium 238 (Pu-238) + + Neutron-induced fission: + + Interpolation region : 1 / 2 + Interpolation energy : 2.53000E-08 MeV + Number of products : 1019 / 1084 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 3.82810E-05 3.82810E-05 1001.82c + 2 10020 H-2 1.16990E-05 1.16990E-05 1002.82c + 3 10030 H-3 1.44000E-04 1.44000E-04 1003.82c + 4 20040 He-4 2.42000E-03 2.42000E-03 2004.82c + 5 210510 Sc-51 1.37880E-12 1.37880E-12 210510 + 6 210520 Sc-52 2.45790E-12 2.45790E-12 210520 + 7 210530 Sc-53 3.83610E-12 3.83610E-12 210530 + 8 210540 Sc-54 2.36900E-12 2.36900E-12 210540 + 9 210550 Sc-55 1.64510E-12 1.64510E-12 210550 + 10 220520 Ti-52 1.29280E-12 3.75070E-12 220520 + 11 220530 Ti-53 4.11080E-12 7.94690E-12 220530 + 12 220540 Ti-54 1.17410E-11 1.41100E-11 220540 + 13 220550 Ti-55 1.74450E-11 1.90900E-11 220550 + 14 220560 Ti-56 2.32510E-11 2.32510E-11 220560 + 15 220570 Ti-57 1.22590E-11 1.22590E-11 220570 + 16 220580 Ti-58 5.59750E-12 5.59750E-12 220580 + 17 220590 Ti-59 1.05520E-12 1.05520E-12 220590 + 18 230540 V-54 1.31570E-12 1.54260E-11 230540 + 19 230550 V-55 9.22630E-12 2.83160E-11 230550 + 20 230560 V-56 2.48630E-11 4.81510E-11 230560 + 21 230570 V-57 6.19280E-11 7.41500E-11 230570 + 22 230580 V-58 6.28730E-11 6.84710E-11 230580 + 23 230590 V-59 6.46270E-11 6.56820E-11 230590 + 24 230600 V-60 2.47990E-11 2.47990E-11 230600 + 25 230610 V-61 9.73060E-12 9.73060E-12 230610 + 26 230620 V-62 1.39500E-12 1.39500E-12 230620 + 27 240560 Cr-56 4.31780E-12 5.27650E-11 240560 + 28 240570 Cr-57 2.29830E-11 1.51610E-10 240570 + 29 240580 Cr-58 1.07870E-10 1.21560E-10 240580 + 30 240590 Cr-59 2.26010E-10 2.91690E-10 240590 + 31 240600 Cr-60 4.23210E-10 4.48590E-10 240600 + 32 240610 Cr-61 3.84610E-10 3.93760E-10 240610 + 33 240620 Cr-62 3.11580E-10 3.12970E-10 240620 + 34 240630 Cr-63 9.14620E-11 9.14620E-11 240630 + 35 240640 Cr-64 2.22480E-11 2.22480E-11 240640 + 36 240650 Cr-65 2.51810E-12 2.51810E-12 240650 + 37 250580 Mn-58 3.47160E-12 1.25040E-10 250580 + 38 250590 Mn-59 4.06690E-11 3.32360E-10 250590 + 39 250600 Mn-60 1.59640E-11 4.80860E-10 250600 + 40 250601 Mn-60m 1.41790E-10 1.41790E-10 250601 + 41 250610 Mn-61 6.58720E-10 1.05250E-09 250610 + 42 250620 Mn-62 9.43260E-10 1.09980E-09 250620 + 43 250621 Mn-62m 1.69340E-10 3.25830E-10 250621 + 44 250630 Mn-63 1.65710E-09 1.74860E-09 250630 + 45 250640 Mn-64 9.70950E-10 9.93200E-10 250640 + 46 250650 Mn-65 6.40580E-10 6.43100E-10 250650 + 47 250660 Mn-66 1.54760E-10 1.54760E-10 250660 + 48 250670 Mn-67 3.06770E-11 3.06770E-11 250670 + 49 250680 Mn-68 2.18870E-12 2.18870E-12 250680 + 50 260600 Fe-60 8.45620E-12 6.14800E-10 260600 + 51 260610 Fe-61 8.09960E-11 1.13350E-09 260610 + 52 260620 Fe-62 6.61940E-10 2.08750E-09 260620 + 53 260630 Fe-63 2.00290E-09 3.75150E-09 260630 + 54 260640 Fe-64 5.44520E-09 6.43840E-09 260640 + 55 260650 Fe-65 7.74420E-09 8.38730E-09 260650 + 56 260660 Fe-66 9.88790E-09 1.00430E-08 260660 + 57 260670 Fe-67 4.89090E-09 4.92160E-09 260670 + 58 260680 Fe-68 2.08740E-09 2.08960E-09 260680 + 59 260690 Fe-69 3.74790E-10 3.74790E-10 260690 + 60 260700 Fe-70 8.19030E-11 8.19030E-11 260700 + 61 260710 Fe-71 2.40080E-12 2.40080E-12 260710 + 62 270620 Co-62 2.11620E-12 2.08970E-09 270620 + 63 270621 Co-62m 4.95660E-12 4.95660E-12 270621 + 64 270630 Co-63 1.15620E-10 3.86710E-09 270630 + 65 270640 Co-64 6.92300E-10 7.13070E-09 270640 + 66 270650 Co-65 4.62240E-09 1.30100E-08 270650 + 67 270660 Co-66 1.19370E-08 2.19800E-08 270660 + 68 270670 Co-67 2.80600E-08 3.29820E-08 270670 + 69 270680 Co-68 1.42660E-08 2.16160E-08 270680 + 70 270681 Co-68m 1.25850E-08 1.47010E-08 270681 + 71 270690 Co-69 2.64910E-08 2.68400E-08 270690 + 72 270700 Co-70 7.44650E-09 7.44650E-09 270700 + 73 270701 Co-70m 7.44650E-09 7.52840E-09 270701 + 74 270710 Co-71 2.66390E-09 2.66630E-09 270710 + 75 270720 Co-72 4.78970E-10 4.78970E-10 270720 + 76 270730 Co-73 5.06840E-11 5.06840E-11 270730 + 77 280640 Ni-64 1.07330E-11 7.14140E-09 28064.82c + 78 280650 Ni-65 1.76140E-10 1.31860E-08 280650 + 79 280660 Ni-66 2.36100E-09 2.43410E-08 280660 + 80 280670 Ni-67 1.17760E-08 4.47580E-08 280670 + 81 280680 Ni-68 5.19590E-08 8.11940E-08 280680 + 82 280690 Ni-69 5.24300E-08 7.90010E-08 280690 + 83 280691 Ni-69m 5.24300E-08 5.24300E-08 280691 + 84 280700 Ni-70 4.07380E-07 4.22350E-07 280700 + 85 280710 Ni-71 1.21100E-07 1.23770E-07 280710 + 86 280720 Ni-72 1.23870E-07 1.24350E-07 280720 + 87 280730 Ni-73 3.45840E-08 3.46350E-08 280730 + 88 280740 Ni-74 2.61120E-09 2.61120E-09 280740 + 89 280750 Ni-75 6.16270E-10 6.16270E-10 280750 + 90 280760 Ni-76 4.41720E-11 4.41720E-11 280760 + 91 280770 Ni-77 1.89230E-12 1.89230E-12 280770 + 92 290660 Cu-66 7.09640E-12 2.43480E-08 290660 + 93 290670 Cu-67 2.03610E-10 4.49610E-08 290670 + 94 290680 Cu-68 6.36550E-10 8.30830E-08 290680 + 95 290681 Cu-68m 1.49090E-09 1.49090E-09 290681 + 96 290690 Cu-69 2.14010E-08 1.52830E-07 290690 + 97 290700 Cu-70 9.27890E-09 7.17560E-08 290700 + 98 290701 Cu-70m 1.03370E-07 1.24950E-07 290701 + 99 290702 Cu-70m 9.27890E-09 4.31630E-07 290702 + 100 290710 Cu-71 3.95030E-07 5.18800E-07 290710 + 101 290720 Cu-72 5.02590E-07 6.26940E-07 290720 + 102 290730 Cu-73 7.17890E-07 7.52530E-07 290730 + 103 290740 Cu-74 4.88990E-07 4.91610E-07 290740 + 104 290750 Cu-75 5.53800E-07 5.54410E-07 290750 + 105 290760 Cu-76 1.76030E-08 1.76260E-08 290760 + 106 290761 Cu-76m 1.76030E-08 1.76260E-08 290761 + 107 290770 Cu-77 1.01440E-08 1.01460E-08 290770 + 108 290780 Cu-78 6.12900E-10 6.12900E-10 290780 + 109 290790 Cu-79 4.97090E-11 4.97090E-11 290790 + 110 300680 Zn-68 9.05920E-12 8.33310E-08 300680 + 111 300690 Zn-69 4.44410E-11 1.53070E-07 300690 + 112 300691 Zn-69m 1.92200E-10 1.92200E-10 300691 + 113 300700 Zn-70 7.50390E-09 5.51790E-07 300700 + 114 300710 Zn-71 6.15670E-09 5.24950E-07 300710 + 115 300711 Zn-71m 2.66260E-08 2.66260E-08 300711 + 116 300720 Zn-72 3.38020E-07 9.64960E-07 300720 + 117 300730 Zn-73 9.67940E-08 1.35640E-06 300730 + 118 300731 Zn-73m 1.32320E-07 5.07120E-07 300731 + 119 300732 Zn-73m 7.49590E-07 7.49590E-07 300732 + 120 300740 Zn-74 4.88990E-07 1.00000E-06 300740 + 121 300750 Zn-75 2.21520E-06 2.75070E-06 300750 + 122 300760 Zn-76 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6.27500E-02 42098.82c + 359 420990 Mo-99 9.50540E-04 5.91190E-02 42099.82c + 360 421000 Mo-100 5.37820E-03 6.48840E-02 42100.82c + 361 421010 Mo-101 1.33600E-02 6.51750E-02 421010 + 362 421020 Mo-102 3.60380E-02 7.18440E-02 421020 + 363 421030 Mo-103 4.43990E-02 6.85690E-02 421030 + 364 421040 Mo-104 4.33430E-02 5.30090E-02 421040 + 365 421050 Mo-105 2.53110E-02 2.92720E-02 421050 + 366 421060 Mo-106 1.31310E-02 1.38770E-02 421060 + 367 421070 Mo-107 3.79650E-03 3.91160E-03 421070 + 368 421080 Mo-108 1.01600E-03 1.02510E-03 421080 + 369 421090 Mo-109 1.48270E-04 1.50290E-04 421090 + 370 421100 Mo-110 1.05680E-05 1.05680E-05 421100 + 371 421110 Mo-111 1.96660E-09 1.96660E-09 421110 + 372 421120 Mo-112 2.33480E-11 2.33480E-11 421120 + 373 430980 Tc-98 1.42560E-09 1.42560E-09 430980 + 374 430990 Tc-99 2.13240E-06 5.91190E-02 43099.82c + 375 430991 Tc-99m 4.93070E-07 5.20610E-02 430991 + 376 431000 Tc-100 3.23160E-05 3.23160E-05 431000 + 377 431010 Tc-101 2.28940E-04 6.54040E-02 431010 + 378 431020 Tc-102 5.78550E-04 7.24230E-02 431020 + 379 431021 Tc-102m 5.78550E-04 5.78550E-04 431021 + 380 431030 Tc-103 5.44640E-03 7.40150E-02 431030 + 381 431040 Tc-104 1.00100E-02 6.30190E-02 431040 + 382 431050 Tc-105 2.14070E-02 5.06790E-02 431050 + 383 431060 Tc-106 1.93750E-02 3.32520E-02 431060 + 384 431070 Tc-107 1.60680E-02 1.99800E-02 431070 + 385 431080 Tc-108 7.18130E-03 8.20720E-03 431080 + 386 431090 Tc-109 3.71060E-03 3.86010E-03 431090 + 387 431100 Tc-110 4.45020E-04 4.55590E-04 431100 + 388 431110 Tc-111 1.17190E-04 1.17190E-04 431110 + 389 431120 Tc-112 2.32020E-05 2.32020E-05 431120 + 390 431130 Tc-113 4.24400E-06 4.24400E-06 431130 + 391 431140 Tc-114 2.19590E-11 2.19590E-11 431140 + 392 441010 Ru-101 2.96210E-06 6.54070E-02 44101.82c + 393 441020 Ru-102 2.31080E-05 7.30240E-02 44102.82c + 394 441030 Ru-103 4.87800E-05 7.41810E-02 44103.82c + 395 441031 Ru-103m 1.17760E-04 1.17760E-04 441031 + 396 441040 Ru-104 9.46140E-04 6.39650E-02 44104.82c + 397 441050 Ru-105 2.90940E-03 5.35880E-02 44105.82c + 398 441060 Ru-106 6.54730E-03 3.98000E-02 44106.82c + 399 441070 Ru-107 8.32340E-03 2.83030E-02 441070 + 400 441080 Ru-108 9.33930E-03 1.75500E-02 441080 + 401 441090 Ru-109 7.20450E-03 1.10620E-02 441090 + 402 441100 Ru-110 2.40120E-03 2.85660E-03 441100 + 403 441110 Ru-111 6.83610E-04 8.01150E-04 441110 + 404 441120 Ru-112 1.69750E-04 1.92910E-04 441120 + 405 441130 Ru-113 6.37000E-06 1.34940E-05 441130 + 406 441131 Ru-113m 6.37000E-06 6.37000E-06 441131 + 407 441140 Ru-114 1.20890E-05 1.20890E-05 441140 + 408 441150 Ru-115 6.25540E-09 6.25540E-09 441150 + 409 441160 Ru-116 1.55490E-10 1.55490E-10 441160 + 410 441200 Ru-120 8.85000E-11 8.85000E-11 441200 + 411 451030 Rh-103 2.74310E-10 7.41810E-02 45103.82c + 412 451031 Rh-103m 1.79440E-09 7.32930E-02 451031 + 413 451040 Rh-104 1.23890E-06 4.97270E-06 451040 + 414 451041 Rh-104m 3.73870E-06 3.73870E-06 451041 + 415 451050 Rh-105 2.08390E-05 5.36120E-02 45105.82c + 416 451051 Rh-105m 3.18570E-06 1.52160E-02 451051 + 417 451060 Rh-106 3.23260E-05 3.98320E-02 451060 + 418 451061 Rh-106m 7.57140E-05 7.57140E-05 451061 + 419 451070 Rh-107 4.04130E-04 2.87070E-02 451070 + 420 451080 Rh-108 1.72890E-04 1.77220E-02 451080 + 421 451081 Rh-108m 5.21710E-04 5.21710E-04 451081 + 422 451090 Rh-109 1.54040E-03 1.26020E-02 451090 + 423 451100 Rh-110 7.65040E-04 3.62160E-03 451100 + 424 451101 Rh-110m 2.04220E-05 2.04220E-05 451101 + 425 451110 Rh-111 7.12530E-04 1.51370E-03 451110 + 426 451120 Rh-112 1.58160E-04 3.51070E-04 451120 + 427 451121 Rh-112m 1.58160E-04 1.58160E-04 451121 + 428 451130 Rh-113 1.63470E-04 1.80150E-04 451130 + 429 451140 Rh-114 3.72620E-05 4.93510E-05 451140 + 430 451141 Rh-114m 3.72620E-05 3.72620E-05 451141 + 431 451150 Rh-115 3.74430E-05 3.74490E-05 451150 + 432 451160 Rh-116 1.16920E-06 1.16930E-06 451160 + 433 451161 Rh-116m 2.73850E-06 2.73850E-06 451161 + 434 451170 Rh-117 1.97020E-06 1.97020E-06 451170 + 435 451180 Rh-118 5.11030E-10 5.11030E-10 451180 + 436 451190 Rh-119 1.19290E-11 1.19290E-11 451190 + 437 451200 Rh-120 1.58780E-07 1.58870E-07 451200 + 438 451210 Rh-121 1.24720E-08 1.24720E-08 451210 + 439 451220 Rh-122 3.52670E-10 3.52670E-10 451220 + 440 461060 Pd-106 1.66790E-08 3.99080E-02 46106.82c + 441 461070 Pd-107 2.09340E-06 2.87130E-02 46107.82c + 442 461071 Pd-107m 3.93430E-06 3.93430E-06 461071 + 443 461080 Pd-108 2.96700E-05 1.82740E-02 46108.82c + 444 461090 Pd-109 2.24130E-05 1.26670E-02 461090 + 445 461091 Pd-109m 4.21210E-05 6.34320E-03 461091 + 446 461100 Pd-110 8.92950E-05 3.73140E-03 46110.82c + 447 461110 Pd-111 3.39640E-05 1.59260E-03 461110 + 448 461111 Pd-111m 6.38310E-05 6.98850E-05 461111 + 449 461120 Pd-112 9.80140E-05 6.07240E-04 461120 + 450 461130 Pd-113 3.41140E-05 2.96620E-04 461130 + 451 461131 Pd-113m 8.23560E-05 8.23560E-05 461131 + 452 461140 Pd-114 8.84730E-05 1.75090E-04 461140 + 453 461150 Pd-115 3.10450E-05 6.81600E-05 461150 + 454 461151 Pd-115m 5.83450E-05 6.37830E-05 461151 + 455 461160 Pd-116 6.64630E-05 7.03710E-05 461160 + 456 461170 Pd-117 1.09530E-05 3.35080E-05 461170 + 457 461171 Pd-117m 2.05850E-05 2.05850E-05 461171 + 458 461180 Pd-118 1.32280E-05 1.32290E-05 461180 + 459 461190 Pd-119 4.27170E-06 4.28110E-06 461190 + 460 461200 Pd-120 2.51400E-05 2.52910E-05 461200 + 461 461210 Pd-121 5.04500E-06 5.05580E-06 461210 + 462 461220 Pd-122 8.61100E-07 8.61450E-07 461220 + 463 461230 Pd-123 9.51090E-08 9.51090E-08 461230 + 464 461240 Pd-124 9.00170E-09 9.00170E-09 461240 + 465 471080 Ag-108 2.43890E-10 2.93590E-10 471080 + 466 471081 Ag-108m 5.71260E-10 5.71260E-10 471081 + 467 471090 Ag-109 3.98180E-09 1.26670E-02 47109.82c + 468 471091 Ag-109m 2.60470E-08 1.26600E-02 471091 + 469 471100 Ag-110 6.59800E-08 6.80810E-08 471100 + 470 471101 Ag-110m 1.54540E-07 1.54540E-07 47510.82c + 471 471110 Ag-111 7.12340E-07 1.60880E-03 47111.82c + 472 471111 Ag-111m 4.65980E-06 1.59950E-03 471111 + 473 471120 Ag-112 1.93060E-06 6.09170E-04 471120 + 474 471130 Ag-113 5.62500E-07 1.97280E-04 471130 + 475 471131 Ag-113m 3.67960E-06 2.87720E-04 471131 + 476 471140 Ag-114 2.70550E-06 1.89170E-04 471140 + 477 471141 Ag-114m 1.13780E-05 1.13780E-05 471141 + 478 471150 Ag-115 6.33390E-06 8.09790E-05 471150 + 479 471151 Ag-115m 4.14330E-05 1.18520E-04 471151 + 480 471160 Ag-116 1.57730E-05 8.83600E-05 471160 + 481 471161 Ag-116m 3.69430E-05 3.69430E-05 471161 + 482 471170 Ag-117 7.83630E-06 2.86710E-05 471170 + 483 471171 Ag-117m 5.12610E-05 6.80150E-05 471171 + 484 471180 Ag-118 1.30680E-05 4.77140E-05 471180 + 485 471181 Ag-118m 5.49590E-05 5.68500E-05 471181 + 486 471190 Ag-119 5.66600E-06 7.80660E-06 471190 + 487 471191 Ag-119m 3.70640E-05 3.92050E-05 471191 + 488 471200 Ag-120 1.21440E-05 3.58580E-05 471200 + 489 471201 Ag-120m 1.72320E-05 2.98770E-05 471201 + 490 471210 Ag-121 1.77780E-05 2.28200E-05 471210 + 491 471220 Ag-122 1.05120E-06 1.91260E-06 471220 + 492 471221 Ag-122m 9.46850E-07 9.46850E-07 471221 + 493 471230 Ag-123 7.73460E-06 7.82970E-06 471230 + 494 471240 Ag-124 2.11910E-06 3.08250E-06 471240 + 495 471241 Ag-124m 1.90880E-06 1.90880E-06 471241 + 496 471250 Ag-125 4.00800E-06 4.00800E-06 471250 + 497 471260 Ag-126 2.26360E-06 2.26360E-06 471260 + 498 471270 Ag-127 2.20270E-08 2.20270E-08 471270 + 499 471280 Ag-128 6.80580E-10 6.80580E-10 471280 + 500 481110 Cd-111 1.65270E-10 1.61680E-03 48111.82c + 501 481111 Cd-111m 5.40710E-10 5.40710E-10 481111 + 502 481120 Cd-112 1.30980E-08 6.09190E-04 48112.82c + 503 481130 Cd-113 2.78910E-08 2.97480E-04 48113.82c + 504 481131 Cd-113m 9.12490E-08 3.50210E-06 481131 + 505 481140 Cd-114 1.17310E-06 1.90340E-04 48114.82c + 506 481150 Cd-115 4.86550E-07 1.67700E-04 481150 + 507 481151 Cd-115m 1.59190E-06 8.98400E-06 48515.82c + 508 481160 Cd-116 3.90670E-06 1.26990E-04 48116.82c + 509 481170 Cd-117 5.07080E-06 7.69860E-05 481170 + 510 481171 Cd-117m 1.65900E-05 3.72810E-05 481171 + 511 481180 Cd-118 3.58730E-05 1.17130E-04 481180 + 512 481190 Cd-119 1.56330E-05 5.87420E-05 481190 + 513 481191 Cd-119m 3.77410E-05 4.16450E-05 481191 + 514 481200 Cd-120 7.70650E-05 1.31750E-04 481200 + 515 481210 Cd-121 1.67760E-05 3.72120E-05 481210 + 516 481211 Cd-121m 4.05010E-05 4.28850E-05 481211 + 517 481220 Cd-122 6.39800E-05 6.68390E-05 481220 + 518 481230 Cd-123 1.81400E-05 2.45470E-05 481230 + 519 481231 Cd-123m 4.37910E-05 4.52170E-05 481231 + 520 481240 Cd-124 1.16520E-04 1.20550E-04 481240 + 521 481250 Cd-125 3.29570E-05 3.49610E-05 481250 + 522 481251 Cd-125m 7.95630E-05 8.15670E-05 481251 + 523 481260 Cd-126 1.24940E-04 1.27200E-04 481260 + 524 481270 Cd-127 7.11430E-05 7.11650E-05 481270 + 525 481280 Cd-128 2.55040E-05 2.55050E-05 481280 + 526 481290 Cd-129 8.87600E-07 8.87600E-07 481290 + 527 481291 Cd-129m 2.14280E-06 2.14280E-06 481291 + 528 481300 Cd-130 2.63620E-08 2.63620E-08 481300 + 529 491130 In-113 1.39450E-11 3.49720E-06 49113.82c + 530 491131 In-113m 3.22430E-12 3.22430E-12 491131 + 531 491140 In-114 1.14780E-10 4.48970E-10 491140 + 532 491141 In-114m 1.75920E-10 3.46320E-10 491141 + 533 491142 In-114m 1.70390E-10 1.70390E-10 491142 + 534 491150 In-115 1.27550E-08 1.68320E-04 49115.82c + 535 491151 In-115m 2.94920E-09 1.67710E-04 491151 + 536 491160 In-116 3.82460E-08 3.82460E-08 491160 + 537 491161 In-116m 5.86210E-08 1.15400E-07 491161 + 538 491162 In-116m 5.67770E-08 5.67770E-08 491162 + 539 491170 In-117 1.30890E-06 7.80950E-05 491170 + 540 491171 In-117m 3.02640E-07 7.14220E-05 491171 + 541 491180 In-118 4.70150E-07 1.17600E-04 491180 + 542 491181 In-118m 7.20620E-07 1.40880E-06 491181 + 543 491182 In-118m 6.97950E-07 6.97950E-07 491182 + 544 491190 In-119 1.73440E-06 5.19970E-05 491190 + 545 491191 In-119m 4.01050E-07 5.35220E-05 491191 + 546 491200 In-120 6.72700E-06 1.38470E-04 491200 + 547 491201 In-120m 6.72700E-06 6.72700E-06 491201 + 548 491202 In-120m 6.72700E-06 6.72700E-06 491202 + 549 491210 In-121 4.64810E-05 1.02320E-04 491210 + 550 491211 In-121m 1.07480E-05 3.54270E-05 491211 + 551 491220 In-122 2.14710E-05 8.83100E-05 491220 + 552 491221 In-122m 1.52330E-05 1.52330E-05 491221 + 553 491222 In-122m 1.52330E-05 1.52330E-05 491222 + 554 491230 In-123 8.79610E-05 1.40230E-04 491230 + 555 491231 In-123m 2.03390E-05 3.78340E-05 491231 + 556 491240 In-124 7.57480E-05 1.96300E-04 491240 + 557 491241 In-124m 6.82320E-05 6.82320E-05 491241 + 558 491250 In-125 5.01970E-04 6.00270E-04 491250 + 559 491251 In-125m 1.16070E-04 1.34290E-04 491251 + 560 491260 In-126 6.08700E-04 7.35900E-04 491260 + 561 491261 In-126m 5.48300E-04 5.48300E-04 491261 + 562 491270 In-127 1.31950E-03 1.31950E-03 491270 + 563 491271 In-127m 3.05100E-04 3.76260E-04 491271 + 564 491280 In-128 4.20230E-04 6.16790E-04 491280 + 565 491281 In-128m 1.71060E-04 1.96560E-04 491281 + 566 491282 In-128m 5.32620E-04 5.32620E-04 491282 + 567 491290 In-129 4.29870E-04 4.32020E-04 491290 + 568 491291 In-129m 9.93970E-05 1.00290E-04 491291 + 569 491300 In-130 3.47610E-05 3.47870E-05 491300 + 570 491301 In-130m 3.88260E-05 3.88260E-05 491301 + 571 491302 In-130m 6.60590E-05 6.60590E-05 491302 + 572 491310 In-131 7.38760E-06 7.46280E-06 491310 + 573 491311 In-131m 7.38760E-06 7.38760E-06 491311 + 574 491312 In-131m 7.38760E-06 7.38760E-06 491312 + 575 491320 In-132 2.04730E-07 2.04730E-07 491320 + 576 491330 In-133 3.54580E-09 4.36570E-09 491330 + 577 491331 In-133m 8.19880E-10 8.19880E-10 491331 + 578 501160 Sn-116 8.26070E-11 1.53730E-07 50116.82c + 579 501170 Sn-117 5.61910E-10 1.15880E-04 50117.82c + 580 501171 Sn-117m 1.83840E-09 2.67920E-07 501171 + 581 501180 Sn-118 6.73050E-08 1.19090E-04 50118.82c + 582 501190 Sn-119 4.99870E-07 1.04660E-04 50119.82c + 583 501191 Sn-119m 1.63540E-06 4.86100E-05 501191 + 584 501200 Sn-120 1.83530E-06 1.53760E-04 50120.82c + 585 501210 Sn-121 1.28870E-09 1.34730E-04 501210 + 586 501211 Sn-121m 3.11110E-09 1.15950E-05 501211 + 587 501220 Sn-122 1.19800E-05 1.30760E-04 50122.82c + 588 501230 Sn-123 2.32030E-05 3.38940E-05 50123.82c + 589 501231 Sn-123m 9.61120E-06 1.76980E-04 501231 + 590 501240 Sn-124 8.64050E-05 3.50940E-04 50124.82c + 591 501250 Sn-125 2.43980E-04 3.45380E-04 50125.82c + 592 501251 Sn-125m 1.01060E-04 7.34230E-04 501251 + 593 501260 Sn-126 1.98720E-03 3.27400E-03 50126.82c + 594 501270 Sn-127 2.85520E-03 3.36950E-03 501270 + 595 501271 Sn-127m 1.18270E-03 2.36160E-03 501271 + 596 501280 Sn-128 2.98610E-03 1.11300E-02 501280 + 597 501281 Sn-128m 6.99410E-03 7.52670E-03 501281 + 598 501290 Sn-129 2.45190E-03 2.93830E-03 501290 + 599 501291 Sn-129m 5.91910E-03 5.96510E-03 501291 + 600 501300 Sn-130 2.76330E-03 2.85420E-03 501300 + 601 501301 Sn-130m 6.47230E-03 6.52130E-03 501301 + 602 501310 Sn-131 1.00020E-03 1.01450E-03 501310 + 603 501311 Sn-131m 2.41450E-03 2.42220E-03 501311 + 604 501320 Sn-132 1.17800E-03 1.17820E-03 501320 + 605 501330 Sn-133 4.99140E-05 4.99150E-05 501330 + 606 501340 Sn-134 7.15780E-06 7.15780E-06 501340 + 607 501350 Sn-135 4.16210E-08 4.16210E-08 501350 + 608 511180 Sb-118 2.28390E-12 2.28390E-12 511180 + 609 511181 Sb-118m 3.24070E-12 3.24070E-12 511181 + 610 511190 Sb-119 2.89640E-10 3.81710E-10 511190 + 611 511191 Sb-119m 9.20680E-11 9.20680E-11 511191 + 612 511220 Sb-122 5.65110E-12 1.20570E-11 511220 + 613 511221 Sb-122m 6.40590E-12 6.40590E-12 511221 + 614 511230 Sb-123 3.86560E-06 2.14740E-04 51123.82c + 615 511240 Sb-124 2.11150E-06 4.96000E-06 51124.82c + 616 511241 Sb-124m 1.61450E-06 3.79800E-06 511241 + 617 511242 Sb-124m 2.18360E-06 2.18360E-06 511242 + 618 511250 Sb-125 2.60280E-05 1.10560E-03 51125.82c + 619 511260 Sb-126 4.76030E-05 5.89750E-05 51126.82c + 620 511261 Sb-126m 3.51960E-05 8.12270E-05 511261 + 621 511262 Sb-126m 4.60310E-05 4.60310E-05 511262 + 622 511270 Sb-127 7.12580E-04 6.44370E-03 511270 + 623 511280 Sb-128 1.07950E-03 1.22750E-02 511280 + 624 511281 Sb-128m 1.84190E-03 1.84190E-03 511281 + 625 511290 Sb-129 6.58310E-03 1.35550E-02 511290 + 626 511291 Sb-129m 4.02290E-03 7.00540E-03 511291 + 627 511300 Sb-130 9.32900E-03 1.54440E-02 511300 + 628 511301 Sb-130m 9.32900E-03 1.25900E-02 511301 + 629 511310 Sb-131 2.50280E-02 2.84650E-02 511310 + 630 511320 Sb-132 9.76270E-03 1.09410E-02 511320 + 631 511321 Sb-132m 7.19530E-03 7.19530E-03 511321 + 632 511330 Sb-133 8.60500E-03 8.65610E-03 511330 + 633 511340 Sb-134 4.02510E-04 4.08460E-04 511340 + 634 511341 Sb-134m 9.42790E-04 9.42790E-04 511341 + 635 511350 Sb-135 1.99030E-04 1.99060E-04 511350 + 636 511360 Sb-136 1.06970E-05 1.06970E-05 511360 + 637 511370 Sb-137 7.86780E-07 7.86780E-07 511370 + 638 511380 Sb-138 2.75780E-09 2.75780E-09 511380 + 639 521240 Te-124 1.34960E-11 5.90950E-06 52124.82c + 640 521250 Te-125 2.49710E-10 1.10560E-03 52125.82c + 641 521251 Te-125m 8.16990E-10 2.47410E-04 521251 + 642 521260 Te-126 9.05330E-06 1.37880E-04 52126.82c + 643 521270 Te-127 7.98560E-06 6.44500E-03 521270 + 644 521271 Te-127m 1.92780E-05 1.08120E-03 52527.82c + 645 521280 Te-128 2.74870E-04 1.43260E-02 52128.82c + 646 521290 Te-129 3.90880E-04 1.75110E-02 521290 + 647 521291 Te-129m 9.43630E-04 9.00820E-03 52529.82c + 648 521300 Te-130 9.90610E-03 3.79400E-02 52130.82c + 649 521310 Te-131 6.08620E-03 3.58360E-02 521310 + 650 521311 Te-131m 1.46930E-02 1.69720E-02 521311 + 651 521320 Te-132 5.50060E-02 7.31420E-02 52132.82c + 652 521330 Te-133 1.38430E-02 2.71130E-02 521330 + 653 521331 Te-133m 3.34180E-02 3.49150E-02 521331 + 654 521340 Te-134 3.90740E-02 4.04560E-02 521340 + 655 521350 Te-135 9.75310E-03 9.92260E-03 521350 + 656 521360 Te-136 3.18300E-03 3.19230E-03 521360 + 657 521370 Te-137 3.94420E-04 3.94820E-04 521370 + 658 521380 Te-138 7.82660E-05 7.82690E-05 521380 + 659 521390 Te-139 1.96160E-06 1.96160E-06 521390 + 660 521400 Te-140 3.47800E-08 3.47800E-08 521400 + 661 531270 I-127 7.53050E-10 6.47090E-03 53127.82c + 662 531280 I-128 6.63560E-08 6.63560E-08 531280 + 663 531290 I-129 9.09060E-06 2.08530E-02 53129.82c + 664 531300 I-130 6.90810E-05 9.38550E-05 53130.82c + 665 531301 I-130m 2.94930E-05 2.94930E-05 531301 + 666 531310 I-131 9.76340E-04 5.02200E-02 53131.82c + 667 531320 I-132 2.33800E-03 7.69620E-02 531320 + 668 531321 I-132m 1.72320E-03 1.72320E-03 531321 + 669 531330 I-133 1.10940E-02 7.37910E-02 531330 + 670 531331 I-133m 6.77920E-03 6.77920E-03 531331 + 671 531340 I-134 1.81230E-02 7.16280E-02 531340 + 672 531341 I-134m 1.33570E-02 1.33570E-02 531341 + 673 531350 I-135 4.80930E-02 5.80160E-02 53135.82c + 674 531360 I-136 6.34060E-03 9.53890E-03 531360 + 675 531361 I-136m 1.48510E-02 1.48570E-02 531361 + 676 531370 I-137 1.11580E-02 1.15460E-02 531370 + 677 531380 I-138 2.67960E-03 2.75290E-03 531380 + 678 531390 I-139 1.36560E-03 1.36760E-03 531390 + 679 531400 I-140 1.61510E-04 1.61540E-04 531400 + 680 531410 I-141 2.96990E-05 2.96990E-05 531410 + 681 531420 I-142 1.69550E-06 1.69550E-06 531420 + 682 531430 I-143 2.12340E-09 2.12340E-09 531430 + 683 541290 Xe-129 1.54070E-10 6.58140E-10 54129.82c + 684 541291 Xe-129m 5.04070E-10 5.04070E-10 541291 + 685 541300 Xe-130 4.54030E-08 9.86190E-05 54130.82c + 686 541310 Xe-131 3.24330E-06 5.02310E-02 54131.82c + 687 541311 Xe-131m 7.82970E-06 5.53310E-04 541311 + 688 541320 Xe-132 5.08070E-05 7.73120E-02 54132.82c + 689 541321 Xe-132m 5.75930E-05 5.75930E-05 541321 + 690 541330 Xe-133 1.93010E-04 7.44500E-02 54133.82c + 691 541331 Xe-133m 4.65960E-04 2.56630E-03 541331 + 692 541340 Xe-134 1.39320E-03 7.65920E-02 54134.82c + 693 541341 Xe-134m 3.26330E-03 3.57060E-03 541341 + 694 541350 Xe-135 4.60730E-03 7.36220E-02 54135.82c + 695 541351 Xe-135m 1.11230E-02 2.07000E-02 541351 + 696 541360 Xe-136 5.15680E-02 7.67150E-02 54136.82c + 697 541370 Xe-137 4.05670E-02 5.15080E-02 541370 + 698 541380 Xe-138 3.71620E-02 3.99030E-02 541380 + 699 541390 Xe-139 1.78980E-02 1.91470E-02 541390 + 700 541400 Xe-140 1.10480E-02 1.12010E-02 541400 + 701 541410 Xe-141 2.94690E-03 2.97080E-03 541410 + 702 541420 Xe-142 7.62910E-04 7.64180E-04 541420 + 703 541430 Xe-143 5.95860E-05 5.95870E-05 541430 + 704 541440 Xe-144 1.02580E-05 1.02580E-05 541440 + 705 541450 Xe-145 1.40870E-08 1.40870E-08 541450 + 706 551320 Cs-132 7.05980E-09 7.05980E-09 551320 + 707 551330 Cs-133 1.38710E-06 7.44510E-02 55133.82c + 708 551340 Cs-134 4.80860E-06 8.35260E-06 55134.82c + 709 551341 Cs-134m 3.54400E-06 3.54400E-06 551341 + 710 551350 Cs-135 9.75120E-05 7.39030E-02 55135.82c + 711 551351 Cs-135m 5.95880E-05 5.95880E-05 551351 + 712 551360 Cs-136 6.15430E-04 7.95770E-04 55136.82c + 713 551361 Cs-136m 3.60670E-04 3.60670E-04 551361 + 714 551370 Cs-137 6.98660E-03 5.84950E-02 55137.82c + 715 551380 Cs-138 6.59290E-03 5.40740E-02 551380 + 716 551381 Cs-138m 9.35510E-03 9.35510E-03 551381 + 717 551390 Cs-139 2.90100E-02 4.81570E-02 551390 + 718 551400 Cs-140 2.07460E-02 3.19480E-02 551400 + 719 551410 Cs-141 2.26150E-02 2.55870E-02 551410 + 720 551420 Cs-142 8.90580E-03 9.66780E-03 551420 + 721 551430 Cs-143 3.95890E-03 4.01820E-03 551430 + 722 551440 Cs-144 3.80760E-04 5.81100E-04 551440 + 723 551441 Cs-144m 3.80760E-04 3.80760E-04 551441 + 724 551450 Cs-145 1.53160E-04 1.53170E-04 551450 + 725 551460 Cs-146 1.07530E-05 1.07530E-05 551460 + 726 551470 Cs-147 1.21990E-06 1.21990E-06 551470 + 727 551480 Cs-148 5.67120E-10 5.67120E-10 551480 + 728 561340 Ba-134 3.09270E-09 8.35570E-06 56134.82c + 729 561350 Ba-135 2.09950E-08 7.16800E-08 56135.82c + 730 561351 Ba-135m 5.06850E-08 5.06850E-08 561351 + 731 561360 Ba-136 2.66830E-06 9.85020E-04 56136.82c + 732 561361 Ba-136m 6.24970E-06 6.24970E-06 561361 + 733 561370 Ba-137 4.20460E-05 5.86390E-02 56137.82c + 734 561371 Ba-137m 1.01500E-04 5.53210E-02 561371 + 735 561380 Ba-138 1.85080E-03 5.77020E-02 56138.82c + 736 561390 Ba-139 7.06180E-03 5.52180E-02 561390 + 737 561400 Ba-140 1.86210E-02 5.05690E-02 56140.82c + 738 561410 Ba-141 2.45220E-02 5.01090E-02 561410 + 739 561420 Ba-142 3.59770E-02 4.57110E-02 561420 + 740 561430 Ba-143 2.30750E-02 2.70460E-02 561430 + 741 561440 Ba-144 1.55660E-02 1.63410E-02 561440 + 742 561450 Ba-145 5.15040E-03 5.28320E-03 561450 + 743 561460 Ba-146 1.90740E-03 1.91700E-03 561460 + 744 561470 Ba-147 3.02050E-04 3.02920E-04 561470 + 745 561480 Ba-148 5.81670E-05 5.81670E-05 561480 + 746 561490 Ba-149 3.97200E-06 3.97200E-06 561490 + 747 561500 Ba-150 3.70330E-09 3.70330E-09 561500 + 748 571370 La-137 6.63510E-09 6.63510E-09 571370 + 749 571380 La-138 2.70260E-07 2.70260E-07 57138.82c + 750 571390 La-139 4.81170E-05 5.52670E-02 57139.82c + 751 571400 La-140 2.45320E-04 5.08140E-02 57140.82c + 752 571410 La-141 1.38700E-03 5.14960E-02 571410 + 753 571420 La-142 2.82270E-03 4.85330E-02 571420 + 754 571430 La-143 8.72860E-03 3.57750E-02 571430 + 755 571440 La-144 1.12760E-02 2.76170E-02 571440 + 756 571450 La-145 1.42210E-02 1.95040E-02 571450 + 757 571460 La-146 2.45190E-03 4.36890E-03 571460 + 758 571461 La-146m 4.41040E-03 4.41040E-03 571461 + 759 571470 La-147 4.52480E-03 4.82800E-03 571470 + 760 571480 La-148 1.29020E-03 1.34810E-03 571480 + 761 571490 La-149 3.15270E-04 3.19230E-04 571490 + 762 571500 La-150 6.03010E-05 6.03050E-05 571500 + 763 571510 La-151 7.71800E-06 7.71800E-06 571510 + 764 571520 La-152 7.96580E-09 7.96580E-09 571520 + 765 571530 La-153 9.38940E-11 9.38940E-11 571530 + 766 581390 Ce-139 5.06540E-10 1.72940E-09 581390 + 767 581391 Ce-139m 1.22290E-09 1.22290E-09 581391 + 768 581400 Ce-140 3.72540E-06 5.08180E-02 58140.82c + 769 581410 Ce-141 3.64630E-05 5.15330E-02 58141.82c + 770 581420 Ce-142 1.74490E-04 4.87080E-02 58142.82c + 771 581430 Ce-143 6.21010E-04 3.63950E-02 58143.82c + 772 581440 Ce-144 2.53700E-03 3.01540E-02 58144.82c + 773 581450 Ce-145 5.73800E-03 2.52420E-02 581450 + 774 581460 Ce-146 9.84130E-03 1.86210E-02 581460 + 775 581470 Ce-147 8.69120E-03 1.35190E-02 581470 + 776 581480 Ce-148 9.90870E-03 1.12610E-02 581480 + 777 581490 Ce-149 4.22190E-03 4.53830E-03 581490 + 778 581500 Ce-150 2.56940E-03 2.62810E-03 581500 + 779 581510 Ce-151 4.98800E-04 5.06520E-04 581510 + 780 581520 Ce-152 1.14710E-04 1.14720E-04 581520 + 781 581530 Ce-153 8.61250E-06 8.61260E-06 581530 + 782 581540 Ce-154 2.14050E-08 2.14050E-08 581540 + 783 581550 Ce-155 2.58830E-10 2.58830E-10 581550 + 784 591420 Pr-142 1.33010E-09 4.44550E-09 59142.82c + 785 591421 Pr-142m 3.11540E-09 3.11540E-09 591421 + 786 591430 Pr-143 8.06060E-07 3.63960E-02 59143.82c + 787 591440 Pr-144 1.48340E-07 3.01550E-02 591440 + 788 591441 Pr-144m 1.31750E-06 4.17420E-04 591441 + 789 591450 Pr-145 5.91430E-05 2.53010E-02 591450 + 790 591460 Pr-146 2.63790E-04 1.88840E-02 591460 + 791 591470 Pr-147 7.46450E-04 1.42660E-02 591470 + 792 591480 Pr-148 2.93660E-04 1.15550E-02 591480 + 793 591481 Pr-148m 1.23500E-03 1.23500E-03 591481 + 794 591490 Pr-149 2.43360E-03 6.97190E-03 591490 + 795 591500 Pr-150 2.53020E-03 5.15830E-03 591500 + 796 591510 Pr-151 2.48130E-03 2.98780E-03 591510 + 797 591520 Pr-152 8.97340E-04 1.01210E-03 591520 + 798 591530 Pr-153 3.10540E-04 3.19100E-04 591530 + 799 591540 Pr-154 3.96930E-05 3.97140E-05 591540 + 800 591550 Pr-155 7.45980E-06 7.46010E-06 591550 + 801 591560 Pr-156 2.16350E-08 2.16350E-08 591560 + 802 591570 Pr-157 5.24640E-10 5.24640E-10 591570 + 803 591580 Pr-158 3.47080E-12 3.47080E-12 591580 + 804 601440 Nd-144 1.19430E-09 3.01550E-02 60144.82c + 805 601450 Nd-145 7.49400E-07 2.53020E-02 60145.82c + 806 601460 Nd-146 6.71280E-06 1.88910E-02 60146.82c + 807 601470 Nd-147 2.66790E-05 1.42920E-02 60147.82c + 808 601480 Nd-148 1.49810E-04 1.29400E-02 60148.82c + 809 601490 Nd-149 3.34200E-04 7.30610E-03 601490 + 810 601500 Nd-150 8.17120E-04 5.97540E-03 60150.82c + 811 601510 Nd-151 1.15340E-03 4.14120E-03 601510 + 812 601520 Nd-152 1.69540E-03 2.70750E-03 601520 + 813 601530 Nd-153 1.04170E-03 1.36080E-03 601530 + 814 601540 Nd-154 5.26180E-04 5.65890E-04 601540 + 815 601550 Nd-155 1.57520E-04 1.64980E-04 601550 + 816 601560 Nd-156 4.19350E-05 4.19560E-05 601560 + 817 601570 Nd-157 4.48920E-06 4.48970E-06 601570 + 818 601580 Nd-158 4.01560E-08 4.01600E-08 601580 + 819 601590 Nd-159 9.10010E-10 9.10010E-10 601590 + 820 601600 Nd-160 1.66550E-11 1.66550E-11 601600 + 821 611470 Pm-147 1.59540E-09 1.42920E-02 61147.82c + 822 611480 Pm-148 1.67130E-08 1.86700E-08 61148.82c + 823 611481 Pm-148m 3.91460E-08 3.91460E-08 61548.82c + 824 611490 Pm-149 5.67290E-07 7.30660E-03 61149.82c + 825 611500 Pm-150 9.21530E-06 9.21530E-06 611500 + 826 611510 Pm-151 4.72550E-05 4.18850E-03 61151.82c + 827 611520 Pm-152 2.01050E-05 2.72760E-03 611520 + 828 611521 Pm-152m 4.01480E-05 4.01480E-05 611521 + 829 611522 Pm-152m 4.44070E-05 4.44070E-05 611522 + 830 611530 Pm-153 2.28670E-04 1.58950E-03 611530 + 831 611540 Pm-154 1.14380E-04 6.80280E-04 611540 + 832 611541 Pm-154m 1.14380E-04 1.14380E-04 611541 + 833 611550 Pm-155 2.29760E-04 3.94740E-04 611550 + 834 611560 Pm-156 1.18400E-04 1.60360E-04 611560 + 835 611570 Pm-157 5.61490E-05 6.06390E-05 611570 + 836 611580 Pm-158 1.05760E-05 1.06160E-05 611580 + 837 611590 Pm-159 2.38460E-06 2.38550E-06 611590 + 838 611600 Pm-160 3.12150E-08 3.12310E-08 611600 + 839 611610 Pm-161 8.46850E-10 8.46850E-10 611610 + 840 611620 Pm-162 8.41870E-12 8.41870E-12 611620 + 841 621490 Sm-149 2.12530E-10 7.30660E-03 62149.82c + 842 621500 Sm-150 6.75330E-09 9.22200E-06 62150.82c + 843 621510 Sm-151 1.39220E-07 4.18860E-03 62151.82c + 844 621520 Sm-152 5.09960E-06 2.81730E-03 62152.82c + 845 621530 Sm-153 7.32660E-06 1.61450E-03 62153.82c + 846 621531 Sm-153m 1.76870E-05 1.76870E-05 621531 + 847 621540 Sm-154 5.30930E-05 8.47760E-04 62154.82c + 848 621550 Sm-155 9.28360E-05 4.87580E-04 621550 + 849 621560 Sm-156 1.22470E-04 2.82830E-04 621560 + 850 621570 Sm-157 9.41840E-05 1.54820E-04 621570 + 851 621580 Sm-158 5.13590E-05 6.19760E-05 621580 + 852 621590 Sm-159 2.54380E-05 2.78230E-05 621590 + 853 621600 Sm-160 1.23900E-05 1.24210E-05 621600 + 854 621610 Sm-161 8.30230E-07 8.31080E-07 621610 + 855 621620 Sm-162 2.06620E-08 2.06700E-08 621620 + 856 621630 Sm-163 1.03590E-09 1.03590E-09 621630 + 857 621640 Sm-164 1.43340E-11 1.43340E-11 621640 + 858 631520 Eu-152 1.17730E-10 2.49030E-10 63152.82c + 859 631521 Eu-152m 2.80390E-11 2.80390E-11 631521 + 860 631522 Eu-152m 1.31300E-10 1.31300E-10 631522 + 861 631530 Eu-153 9.24850E-09 1.61450E-03 63153.82c + 862 631540 Eu-154 3.50200E-07 6.65660E-07 63154.82c + 863 631541 Eu-154m 3.15460E-07 3.15460E-07 631541 + 864 631550 Eu-155 7.44660E-07 4.88320E-04 63155.82c + 865 631560 Eu-156 2.93900E-06 2.85760E-04 63156.82c + 866 631570 Eu-157 5.23580E-06 1.60060E-04 63157.82c + 867 631580 Eu-158 1.13260E-05 7.33020E-05 631580 + 868 631590 Eu-159 1.50990E-05 4.29220E-05 631590 + 869 631600 Eu-160 5.78100E-06 1.82020E-05 631600 + 870 631610 Eu-161 5.81170E-06 6.64280E-06 631610 + 871 631620 Eu-162 7.88540E-07 8.09210E-07 631620 + 872 631630 Eu-163 1.78730E-07 1.79770E-07 631630 + 873 631640 Eu-164 6.46170E-09 6.47600E-09 631640 + 874 631650 Eu-165 1.75790E-09 1.75790E-09 631650 + 875 631660 Eu-166 5.32020E-11 5.32020E-11 631660 + 876 631670 Eu-167 1.08150E-12 1.08150E-12 631670 + 877 641540 Gd-154 3.25300E-11 6.65560E-07 64154.82c + 878 641550 Gd-155 1.38250E-10 4.88320E-04 64155.82c + 879 641551 Gd-155m 3.33740E-10 3.33740E-10 641551 + 880 641560 Gd-156 1.18460E-08 2.85780E-04 64156.82c + 881 641570 Gd-157 1.06090E-07 1.60170E-04 64157.82c + 882 641580 Gd-158 1.51040E-06 7.48120E-05 64158.82c + 883 641590 Gd-159 1.58950E-06 4.45120E-05 641590 + 884 641600 Gd-160 7.43180E-06 2.56340E-05 64160.82c + 885 641610 Gd-161 2.49050E-06 9.13330E-06 641610 + 886 641620 Gd-162 2.36560E-06 3.17480E-06 641620 + 887 641630 Gd-163 7.90840E-07 9.70610E-07 641630 + 888 641640 Gd-164 5.71880E-07 5.78360E-07 641640 + 889 641650 Gd-165 1.86030E-07 1.87790E-07 641650 + 890 641660 Gd-166 3.27060E-08 3.27590E-08 641660 + 891 641670 Gd-167 1.77350E-09 1.77460E-09 641670 + 892 641680 Gd-168 8.88530E-11 8.88530E-11 641680 + 893 641690 Gd-169 2.00480E-12 2.00480E-12 641690 + 894 651570 Tb-157 1.82480E-11 1.82480E-11 651570 + 895 651580 Tb-158 3.08840E-10 3.43400E-10 651580 + 896 651581 Tb-158m 3.47730E-11 3.47730E-11 651581 + 897 651590 Tb-159 6.53730E-09 4.45180E-05 65159.82c + 898 651600 Tb-160 4.54100E-08 4.54100E-08 65160.82c + 899 651610 Tb-161 1.69860E-07 9.30310E-06 651610 + 900 651620 Tb-162 2.39500E-07 3.41430E-06 651620 + 901 651630 Tb-163 1.58160E-06 2.55220E-06 651630 + 902 651640 Tb-164 2.46270E-07 8.24630E-07 651640 + 903 651650 Tb-165 7.47710E-07 9.35500E-07 651650 + 904 651660 Tb-166 3.52960E-07 3.85720E-07 651660 + 905 651670 Tb-167 8.16220E-08 8.33970E-08 651670 + 906 651680 Tb-168 1.01800E-08 1.02690E-08 651680 + 907 651690 Tb-169 1.36470E-09 1.36670E-09 651690 + 908 651700 Tb-170 6.77790E-11 6.77790E-11 651700 + 909 651710 Tb-171 2.63140E-12 2.63140E-12 651710 + 910 661590 Dy-159 1.38720E-12 1.38720E-12 661590 + 911 661600 Dy-160 3.03700E-11 4.54400E-08 66160.82c + 912 661610 Dy-161 3.09100E-10 9.30340E-06 66161.82c + 913 661620 Dy-162 2.57110E-09 3.41690E-06 66162.82c + 914 661630 Dy-163 1.76880E-08 2.56990E-06 66163.82c + 915 661640 Dy-164 3.41500E-08 8.58810E-07 66164.82c + 916 661650 Dy-165 1.92320E-07 1.15660E-06 661650 + 917 661651 Dy-165m 2.94000E-08 2.94000E-08 661651 + 918 661660 Dy-166 3.52960E-07 7.38680E-07 661660 + 919 661670 Dy-167 2.22910E-07 3.06310E-07 661670 + 920 661680 Dy-168 1.32020E-07 1.42290E-07 661680 + 921 661690 Dy-169 3.97310E-08 4.10980E-08 661690 + 922 661700 Dy-170 1.08220E-08 1.08900E-08 661700 + 923 661710 Dy-171 1.07390E-09 1.07650E-09 661710 + 924 661720 Dy-172 9.04680E-11 9.04680E-11 661720 + 925 661730 Dy-173 3.54180E-12 3.54180E-12 661730 + 926 671630 Ho-163 1.16120E-11 1.33870E-11 671630 + 927 671631 Ho-163m 1.77510E-12 1.77510E-12 671631 + 928 671640 Ho-164 2.05130E-11 6.85580E-11 671640 + 929 671641 Ho-164m 4.80450E-11 4.80450E-11 671641 + 930 671650 Ho-165 2.56600E-09 1.15980E-06 67165.82c + 931 671660 Ho-166 3.20380E-09 7.41880E-07 671660 + 932 671661 Ho-166m 7.50420E-09 7.50420E-09 671661 + 933 671670 Ho-167 3.10650E-08 3.37370E-07 671670 + 934 671680 Ho-168 1.57510E-08 1.80280E-07 671680 + 935 671681 Ho-168m 2.23500E-08 2.23500E-08 671681 + 936 671690 Ho-169 5.20940E-08 9.31920E-08 671690 + 937 671700 Ho-170 2.02360E-08 2.02360E-08 671700 + 938 671701 Ho-170m 8.63970E-09 1.95290E-08 671701 + 939 671710 Ho-171 1.40790E-08 1.51550E-08 671710 + 940 671720 Ho-172 2.76430E-09 2.85480E-09 671720 + 941 671730 Ho-173 6.12240E-10 6.15780E-10 671730 + 942 671740 Ho-174 5.01680E-11 5.01680E-11 671740 + 943 671750 Ho-175 3.61070E-12 3.61070E-12 671750 + 944 681650 Er-165 1.13660E-12 1.13660E-12 681650 + 945 681660 Er-166 2.93900E-11 7.41910E-07 68166.82c + 946 681670 Er-167 1.92070E-10 3.37590E-07 68167.82c + 947 681671 Er-167m 2.93620E-11 4.03430E-08 681671 + 948 681680 Er-168 1.52240E-09 1.81910E-07 68168.82c + 949 681690 Er-169 4.79600E-09 9.79880E-08 681690 + 950 681700 Er-170 1.29180E-08 5.26840E-08 68170.82c + 951 681710 Er-171 1.27390E-08 2.78940E-08 681710 + 952 681720 Er-172 1.13890E-08 1.42440E-08 681720 + 953 681730 Er-173 5.27150E-09 5.88730E-09 681730 + 954 681740 Er-174 2.20350E-09 2.25370E-09 681740 + 955 681750 Er-175 3.82800E-10 3.86410E-10 681750 + 956 681760 Er-176 5.87250E-11 5.87250E-11 681760 + 957 681770 Er-177 3.63000E-12 3.63000E-12 681770 + 958 691690 Tm-169 1.45260E-11 9.80020E-08 691690 + 959 691700 Tm-170 9.92650E-11 9.92650E-11 691700 + 960 691710 Tm-171 5.31260E-10 2.84260E-08 691710 + 961 691720 Tm-172 1.05370E-09 1.52970E-08 691720 + 962 691730 Tm-173 2.29500E-09 8.18230E-09 691730 + 963 691740 Tm-174 1.91810E-09 4.17180E-09 691740 + 964 691750 Tm-175 1.54090E-09 1.92730E-09 691750 + 965 691760 Tm-176 5.11170E-10 5.69900E-10 691760 + 966 691770 Tm-177 1.67350E-10 1.70980E-10 691770 + 967 691780 Tm-178 2.08440E-11 2.08440E-11 691780 + 968 691790 Tm-179 2.79090E-12 2.79090E-12 691790 + 969 701720 Yb-172 1.13320E-11 1.53090E-08 701720 + 970 701730 Yb-173 6.08830E-11 8.24320E-09 701730 + 971 701740 Yb-174 2.66420E-10 4.43820E-09 701740 + 972 701750 Yb-175 3.96960E-10 2.38500E-09 701750 + 973 701751 Yb-175m 6.06830E-11 1.54470E-09 701751 + 974 701760 Yb-176 2.49300E-10 1.19430E-09 701760 + 975 701761 Yb-176m 4.48430E-10 7.33380E-10 701761 + 976 701770 Yb-177 3.71760E-10 6.28700E-10 701770 + 977 701771 Yb-177m 8.59600E-11 2.56940E-10 701771 + 978 701780 Yb-178 2.70770E-10 2.91610E-10 701780 + 979 701790 Yb-179 8.13950E-11 8.41860E-11 701790 + 980 701800 Yb-180 2.21510E-11 2.21510E-11 701800 + 981 701810 Yb-181 2.19610E-12 2.19610E-12 701810 + 982 711750 Lu-175 5.30570E-12 2.39030E-09 71175.82c + 983 711760 Lu-176 1.24160E-11 8.57540E-11 71176.82c + 984 711761 Lu-176m 6.90270E-12 6.90270E-12 711761 + 985 711770 Lu-177 4.55170E-11 6.78300E-10 711770 + 986 711771 Lu-177m 1.77940E-11 1.80810E-11 711771 + 987 711780 Lu-178 3.66790E-11 3.28290E-10 711780 + 988 711781 Lu-178m 4.15790E-11 4.15790E-11 711781 + 989 711790 Lu-179 9.27080E-11 1.91070E-10 711790 + 990 711791 Lu-179m 1.41720E-11 9.83580E-11 711791 + 991 711800 Lu-180 1.70420E-11 4.91970E-11 711800 + 992 711801 Lu-180m 1.70420E-11 3.91930E-11 711801 + 993 711802 Lu-180m 2.51160E-11 2.51160E-11 711802 + 994 711810 Lu-181 2.88390E-11 3.10350E-11 711810 + 995 711820 Lu-182 5.65790E-12 5.65790E-12 711820 + 996 711830 Lu-183 1.25240E-12 1.25240E-12 711830 + 997 721780 Hf-178 1.11920E-12 3.73000E-10 72178.82c + 998 721781 Hf-178m 1.84660E-12 4.35920E-11 721781 + 999 721790 Hf-179 5.92970E-12 2.00920E-10 72179.82c + 1000 721791 Hf-179m 1.85100E-12 1.85100E-12 721791 + 1001 721792 Hf-179m 2.07580E-12 2.07580E-12 721792 + 1002 721800 Hf-180 9.47630E-12 1.07780E-10 72180.82c + 1003 721801 Hf-180m 1.70460E-11 2.96040E-11 721801 + 1004 721810 Hf-181 2.61330E-11 5.71680E-11 721810 + 1005 721820 Hf-182 8.34150E-12 2.03010E-11 721820 + 1006 721821 Hf-182m 1.50040E-11 1.50040E-11 721821 + 1007 721830 Hf-183 1.08010E-11 1.20530E-11 721830 + 1008 721840 Hf-184 1.61240E-12 1.61240E-12 721840 + 1009 721841 Hf-184m 2.90020E-12 2.90020E-12 721841 + 1010 731810 Ta-181 1.09170E-12 5.82600E-11 73181.82c + 1011 731820 Ta-182 7.72980E-13 1.08660E-11 73182.82c + 1012 731821 Ta-182m 7.88990E-13 1.00930E-11 731821 + 1013 731822 Ta-182m 6.01430E-13 9.30400E-12 731822 + 1014 731830 Ta-183 4.70930E-12 1.67630E-11 731830 + 1015 731840 Ta-184 3.93380E-12 8.44640E-12 731840 + 1016 731850 Ta-185 2.12740E-12 3.15780E-12 731850 + 1017 731851 Ta-185m 1.03040E-12 1.03040E-12 731851 + 1018 731860 Ta-186 1.04680E-12 1.04680E-12 731860 + 1019 741860 W-186 1.08200E-12 2.47780E-12 74186.82c + + Neutron-induced fission: + + Interpolation region : 2 / 2 + Interpolation energy : 4.00000E-01 MeV + Number of products : 985 / 1051 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 3.82810E-05 3.82810E-05 1001.82c + 2 10020 H-2 1.16990E-05 1.16990E-05 1002.82c + 3 10030 H-3 1.44000E-04 1.44000E-04 1003.82c + 4 20040 He-4 2.42000E-03 2.42000E-03 2004.82c + 5 210530 Sc-53 1.52800E-12 1.52800E-12 210530 + 6 210540 Sc-54 1.00410E-12 1.00410E-12 210540 + 7 220530 Ti-53 1.63540E-12 3.16340E-12 220530 + 8 220540 Ti-54 5.00110E-12 6.00520E-12 220540 + 9 220550 Ti-55 7.90490E-12 7.90490E-12 220550 + 10 220560 Ti-56 1.12670E-11 1.12670E-11 220560 + 11 220570 Ti-57 6.30210E-12 6.30210E-12 220570 + 12 220580 Ti-58 3.08300E-12 3.08300E-12 220580 + 13 230550 V-55 4.26700E-12 1.21720E-11 230550 + 14 230560 V-56 1.22190E-11 2.35050E-11 230560 + 15 230570 V-57 3.24920E-11 3.87750E-11 230570 + 16 230580 V-58 3.51430E-11 3.82260E-11 230580 + 17 230590 V-59 3.87490E-11 3.87490E-11 230590 + 18 230600 V-60 1.58100E-11 1.58100E-11 230600 + 19 230610 V-61 6.62330E-12 6.62330E-12 230610 + 20 230620 V-62 1.01050E-12 1.01050E-12 230620 + 21 240560 Cr-56 2.13150E-12 2.57910E-11 240560 + 22 240570 Cr-57 1.20300E-11 8.12310E-11 240570 + 23 240580 Cr-58 6.04950E-11 6.81400E-11 240580 + 24 240590 Cr-59 1.35130E-10 1.73880E-10 240590 + 25 240600 Cr-60 2.70820E-10 2.87030E-10 240600 + 26 240610 Cr-61 2.61240E-10 2.67470E-10 240610 + 27 240620 Cr-62 2.26690E-10 2.27700E-10 240620 + 28 240630 Cr-63 7.08720E-11 7.08720E-11 240630 + 29 240640 Cr-64 1.84750E-11 1.84750E-11 240640 + 30 240650 Cr-65 2.22560E-12 2.22560E-12 240650 + 31 250580 Mn-58 2.00010E-12 7.01400E-11 250580 + 32 250590 Mn-59 2.47920E-11 1.98670E-10 250590 + 33 250600 Mn-60 9.14960E-12 3.06880E-10 250600 + 34 250601 Mn-60m 9.30800E-11 9.30800E-11 250601 + 35 250610 Mn-61 4.55840E-10 7.23310E-10 250610 + 36 250620 Mn-62 7.08810E-10 8.22660E-10 250620 + 37 250621 Mn-62m 1.11000E-10 2.24850E-10 250621 + 38 250630 Mn-63 1.30880E-09 1.37970E-09 250630 + 39 250640 Mn-64 8.17000E-10 8.35470E-10 250640 + 40 250650 Mn-65 5.77320E-10 5.79550E-10 250650 + 41 250660 Mn-66 1.48370E-10 1.48370E-10 250660 + 42 250670 Mn-67 3.14450E-11 3.14450E-11 250670 + 43 250680 Mn-68 2.39410E-12 2.39410E-12 250680 + 44 260600 Fe-60 5.49960E-12 3.94760E-10 260600 + 45 260610 Fe-61 5.58620E-11 7.79170E-10 260610 + 46 260620 Fe-62 4.88800E-10 1.53630E-09 260620 + 47 260630 Fe-63 1.57510E-09 2.95480E-09 260630 + 48 260640 Fe-64 4.59010E-09 5.42560E-09 260640 + 49 260650 Fe-65 6.95060E-09 7.53020E-09 260650 + 50 260660 Fe-66 9.50090E-09 9.64930E-09 260660 + 51 260670 Fe-67 4.99460E-09 5.02610E-09 260670 + 52 260680 Fe-68 2.28780E-09 2.29020E-09 260680 + 53 260690 Fe-69 4.38240E-10 4.38240E-10 260690 + 54 260700 Fe-70 6.69090E-11 6.69090E-11 260700 + 55 260710 Fe-71 3.53600E-12 3.53600E-12 260710 + 56 270620 Co-62 1.41980E-12 1.53780E-09 270620 + 57 270621 Co-62m 3.87020E-12 3.87020E-12 270621 + 58 270630 Co-63 9.26080E-11 3.04740E-09 270630 + 59 270640 Co-64 5.90370E-10 6.01590E-09 270640 + 60 270650 Co-65 4.22090E-09 1.17510E-08 270650 + 61 270660 Co-66 1.15960E-08 2.12450E-08 270660 + 62 270670 Co-67 2.91510E-08 3.41770E-08 270670 + 63 270680 Co-68 1.70410E-08 2.45620E-08 270680 + 64 270681 Co-68m 1.27200E-08 1.50410E-08 270681 + 65 270690 Co-69 3.15220E-08 3.19300E-08 270690 + 66 270700 Co-70 6.15200E-09 6.15200E-09 270700 + 67 270701 Co-70m 6.15200E-09 6.21890E-09 270701 + 68 270710 Co-71 3.99400E-09 3.99750E-09 270710 + 69 270720 Co-72 9.41660E-10 9.41660E-10 270720 + 70 270730 Co-73 1.93520E-11 1.93520E-11 270730 + 71 280640 Ni-64 9.17260E-12 6.02510E-09 28064.82c + 72 280650 Ni-65 1.60120E-10 1.19110E-08 280650 + 73 280660 Ni-66 2.29590E-09 2.35410E-08 280660 + 74 280670 Ni-67 1.21650E-08 4.63420E-08 280670 + 75 280680 Ni-68 5.76050E-08 9.00060E-08 280680 + 76 280690 Ni-69 6.20200E-08 9.36300E-08 280690 + 77 280691 Ni-69m 6.20200E-08 6.20200E-08 280691 + 78 280700 Ni-70 2.39590E-07 2.51960E-07 280700 + 79 280710 Ni-71 5.94190E-07 5.98190E-07 280710 + 80 280720 Ni-72 6.67930E-07 6.68870E-07 280720 + 81 280730 Ni-73 1.31310E-08 1.31500E-08 280730 + 82 280740 Ni-74 2.09620E-09 2.09620E-09 280740 + 83 280750 Ni-75 1.76930E-09 1.76930E-09 280750 + 84 280760 Ni-76 1.35330E-10 1.35330E-10 280760 + 85 280770 Ni-77 3.88190E-12 3.88190E-12 280770 + 86 290660 Cu-66 6.98000E-12 2.35480E-08 290660 + 87 290670 Cu-67 2.13970E-10 4.65560E-08 290670 + 88 290680 Cu-68 6.39680E-10 9.21100E-08 290680 + 89 290681 Cu-68m 1.74360E-09 1.74360E-09 290681 + 90 290690 Cu-69 2.57250E-08 1.81370E-07 290690 + 91 290700 Cu-70 6.88710E-09 5.73360E-08 290700 + 92 290701 Cu-70m 8.79560E-08 1.00900E-07 290701 + 93 290702 Cu-70m 6.88710E-09 2.58850E-07 290702 + 94 290710 Cu-71 3.54610E-07 9.52800E-07 290710 + 95 290720 Cu-72 9.97930E-07 1.66680E-06 290720 + 96 290730 Cu-73 2.76860E-07 2.90010E-07 290730 + 97 290740 Cu-74 1.06620E-07 1.08740E-07 290740 + 98 290750 Cu-75 1.98600E-06 1.98770E-06 290750 + 99 290760 Cu-76 5.42300E-08 5.42980E-08 290760 + 100 290761 Cu-76m 5.42300E-08 5.42980E-08 290761 + 101 290770 Cu-77 2.09030E-08 2.09070E-08 290770 + 102 290780 Cu-78 2.13800E-09 2.13800E-09 290780 + 103 290790 Cu-79 1.00190E-10 1.00190E-10 290790 + 104 300680 Zn-68 1.01580E-11 9.24000E-08 300680 + 105 300690 Zn-69 4.73970E-11 1.81660E-07 300690 + 106 300691 Zn-69m 2.35400E-10 2.35400E-10 300691 + 107 300700 Zn-70 6.25970E-09 3.59950E-07 300700 + 108 300710 Zn-71 8.26250E-09 9.61060E-07 300710 + 109 300711 Zn-71m 4.10360E-08 4.10360E-08 300711 + 110 300720 Zn-72 1.33580E-06 3.00260E-06 300720 + 111 300730 Zn-73 6.02480E-08 7.05320E-07 300730 + 112 300731 Zn-73m 8.33310E-08 3.55070E-07 300731 + 113 300732 Zn-73m 5.43470E-07 5.43470E-07 300732 + 114 300740 Zn-74 7.93350E-07 9.71670E-07 300740 + 115 300750 Zn-75 5.95810E-06 7.87790E-06 300750 + 116 300760 Zn-76 1.31770E-05 1.32840E-05 300760 + 117 300770 Zn-77 1.79720E-06 1.93780E-06 300770 + 118 300771 Zn-77m 2.39290E-07 2.39290E-07 300771 + 119 300780 Zn-78 3.15220E-06 3.15440E-06 300780 + 120 300790 Zn-79 2.99150E-07 2.99200E-07 300790 + 121 300800 Zn-80 5.24980E-08 5.24980E-08 300800 + 122 300810 Zn-81 2.08390E-09 2.08390E-09 300810 + 123 300820 Zn-82 1.24470E-10 1.24470E-10 300820 + 124 310700 Ga-70 5.11320E-12 5.11320E-12 310700 + 125 310710 Ga-71 2.44290E-10 1.00230E-06 310710 + 126 310720 Ga-72 7.58380E-09 3.01090E-06 310720 + 127 310721 Ga-72m 7.45470E-10 1.00790E-07 310721 + 128 310730 Ga-73 2.50880E-08 1.00220E-06 310730 + 129 310740 Ga-74 4.91350E-08 8.14730E-07 310740 + 130 310741 Ga-74m 4.91350E-08 1.02080E-06 310741 + 131 310750 Ga-75 4.96490E-06 1.28430E-05 310750 + 132 310760 Ga-76 7.09480E-06 2.03790E-05 310760 + 133 310770 Ga-77 1.83300E-05 2.03870E-05 310770 + 134 310780 Ga-78 1.99660E-05 2.31240E-05 310780 + 135 310790 Ga-79 2.90890E-05 2.93840E-05 310790 + 136 310800 Ga-80 8.57100E-06 8.62370E-06 310800 + 137 310810 Ga-81 6.32440E-06 6.32630E-06 310810 + 138 310820 Ga-82 3.81630E-07 3.81750E-07 310820 + 139 310830 Ga-83 3.81560E-08 3.81560E-08 310830 + 140 310840 Ga-84 1.49170E-09 1.49170E-09 310840 + 141 320720 Ge-72 9.40780E-12 3.01090E-06 32072.82c + 142 320730 Ge-73 6.31330E-11 1.00220E-06 32073.82c + 143 320731 Ge-73m 1.27120E-11 9.87450E-07 320731 + 144 320740 Ge-74 1.75810E-09 1.07170E-06 32074.82c + 145 320750 Ge-75 2.52910E-08 1.30580E-05 320750 + 146 320751 Ge-75m 1.89950E-07 7.03660E-07 320751 + 147 320760 Ge-76 2.02710E-06 2.24060E-05 32076.82c + 148 320770 Ge-77 1.88700E-05 2.32210E-05 320770 + 149 320771 Ge-77m 2.51240E-06 2.29000E-05 320771 + 150 320780 Ge-78 8.19550E-05 1.05110E-04 320780 + 151 320790 Ge-79 1.29370E-05 4.61390E-05 320790 + 152 320791 Ge-79m 9.71630E-05 9.72070E-05 320791 + 153 320800 Ge-80 2.39170E-04 2.48550E-04 320800 + 154 320810 Ge-81 1.28650E-04 1.31920E-04 320810 + 155 320811 Ge-81m 2.59030E-05 2.85730E-05 320811 + 156 320820 Ge-82 1.54940E-04 1.55260E-04 320820 + 157 320830 Ge-83 4.49510E-05 4.49760E-05 320830 + 158 320840 Ge-84 1.25170E-05 1.25170E-05 320840 + 159 320850 Ge-85 4.71000E-07 4.71000E-07 320850 + 160 320860 Ge-86 2.98230E-08 2.98230E-08 320860 + 161 320870 Ge-87 6.66020E-10 6.66020E-10 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7.64680E-03 7.75280E-03 401020 + 320 401030 Zr-103 1.78390E-03 1.80280E-03 401030 + 321 401040 Zr-104 3.85810E-04 3.85820E-04 401040 + 322 401050 Zr-105 3.02790E-05 3.02790E-05 401050 + 323 401060 Zr-106 3.87290E-06 3.87290E-06 401060 + 324 401070 Zr-107 5.64680E-10 5.64680E-10 401070 + 325 410930 Nb-93 1.12370E-09 1.34990E-09 41093.82c + 326 410931 Nb-93m 2.26240E-10 2.26240E-10 410931 + 327 410940 Nb-94 3.77030E-08 6.01350E-08 41094.82c + 328 410941 Nb-94m 2.25450E-08 2.25450E-08 410941 + 329 410950 Nb-95 2.15330E-05 5.60800E-02 41095.82c + 330 410951 Nb-95m 4.33560E-06 6.10280E-04 410951 + 331 410960 Nb-96 1.60200E-04 1.60200E-04 410960 + 332 410970 Nb-97 9.60420E-04 6.34170E-02 410970 + 333 410971 Nb-97m 1.93380E-04 5.93740E-02 410971 + 334 410980 Nb-98 8.56810E-04 6.75830E-02 410980 + 335 410981 Nb-98m 2.98540E-03 2.98540E-03 410981 + 336 410990 Nb-99 1.16570E-02 4.55930E-02 410990 + 337 410991 Nb-99m 2.34710E-03 2.18530E-02 410991 + 338 411000 Nb-100 4.06070E-03 4.35910E-02 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421030 Mo-103 3.15410E-02 5.20850E-02 421030 + 359 421040 Mo-104 3.27170E-02 4.06840E-02 421040 + 360 421050 Mo-105 1.70670E-02 1.98280E-02 421050 + 361 421060 Mo-106 8.93540E-03 9.42650E-03 421060 + 362 421070 Mo-107 2.41970E-03 2.48860E-03 421070 + 363 421080 Mo-108 5.97140E-04 6.01560E-04 421080 + 364 421090 Mo-109 6.90050E-05 6.90060E-05 421090 + 365 421100 Mo-110 7.30110E-06 7.30110E-06 421100 + 366 421110 Mo-111 1.22780E-09 1.22780E-09 421110 + 367 421120 Mo-112 1.45870E-11 1.45870E-11 421120 + 368 430980 Tc-98 1.59730E-09 1.59730E-09 430980 + 369 430990 Tc-99 2.50450E-06 6.80850E-02 43099.82c + 370 430991 Tc-99m 5.04280E-07 5.99550E-02 430991 + 371 431000 Tc-100 2.97060E-05 2.97060E-05 431000 + 372 431010 Tc-101 2.37610E-04 6.57700E-02 431010 + 373 431020 Tc-102 5.31600E-04 6.31620E-02 431020 + 374 431021 Tc-102m 5.31600E-04 5.31600E-04 431021 + 375 431030 Tc-103 4.08560E-03 5.61710E-02 431030 + 376 431040 Tc-104 8.02640E-03 4.87100E-02 431040 + 377 431050 Tc-105 1.44340E-02 3.42620E-02 431050 + 378 431060 Tc-106 1.26040E-02 2.20310E-02 431060 + 379 431070 Tc-107 1.00960E-02 1.25850E-02 431070 + 380 431080 Tc-108 4.14350E-03 4.74540E-03 431080 + 381 431090 Tc-109 1.51150E-03 1.58010E-03 431090 + 382 431100 Tc-110 2.89140E-04 2.96440E-04 431100 + 383 431110 Tc-111 7.71160E-05 7.71170E-05 431110 + 384 431120 Tc-112 4.74220E-06 4.74220E-06 431120 + 385 431130 Tc-113 1.09370E-09 1.09370E-09 431130 + 386 431140 Tc-114 1.17280E-11 1.17280E-11 431140 + 387 441010 Ru-101 9.90650E-07 6.57710E-02 44101.82c + 388 441020 Ru-102 1.94590E-05 6.37130E-02 44102.82c + 389 441030 Ru-103 3.50640E-05 5.63040E-02 44103.82c + 390 441031 Ru-103m 9.81060E-05 9.81060E-05 441031 + 391 441040 Ru-104 7.53950E-04 4.94640E-02 44104.82c + 392 441050 Ru-105 1.99990E-03 3.62620E-02 44105.82c + 393 441060 Ru-106 4.69240E-03 2.67230E-02 44106.82c + 394 441070 Ru-107 5.42680E-03 1.80110E-02 441070 + 395 441080 Ru-108 5.77510E-03 1.05220E-02 441080 + 396 441090 Ru-109 2.96580E-03 4.54480E-03 441090 + 397 441100 Ru-110 1.46620E-03 1.76250E-03 441100 + 398 441110 Ru-111 4.08750E-04 4.85940E-04 441110 + 399 441120 Ru-112 1.22070E-04 1.26740E-04 441120 + 400 441130 Ru-113 6.65250E-06 9.97980E-06 441130 + 401 441131 Ru-113m 6.65250E-06 6.65250E-06 441131 + 402 441140 Ru-114 2.88070E-06 2.88070E-06 441140 + 403 441150 Ru-115 9.42680E-07 9.42680E-07 441150 + 404 441160 Ru-116 1.15000E-10 1.15000E-10 441160 + 405 441170 Ru-117 2.48170E-12 2.48170E-12 441170 + 406 441200 Ru-120 6.37420E-11 6.37420E-11 441200 + 407 451030 Rh-103 1.88830E-10 5.63040E-02 45103.82c + 408 451031 Rh-103m 1.41830E-09 5.56300E-02 451031 + 409 451040 Rh-104 2.19480E-07 9.83230E-07 451040 + 410 451041 Rh-104m 7.64740E-07 7.64740E-07 451041 + 411 451050 Rh-105 1.63710E-05 3.62810E-02 45105.82c + 412 451051 Rh-105m 2.17970E-06 1.02960E-02 451051 + 413 451060 Rh-106 2.04520E-05 2.67430E-02 451060 + 414 451061 Rh-106m 5.57470E-05 5.57470E-05 451061 + 415 451070 Rh-107 2.65210E-04 1.82770E-02 451070 + 416 451080 Rh-108 9.96320E-05 1.06210E-02 451080 + 417 451081 Rh-108m 3.47150E-04 3.47150E-04 451081 + 418 451090 Rh-109 6.55410E-04 5.20020E-03 451090 + 419 451100 Rh-110 5.84020E-04 2.34650E-03 451100 + 420 451101 Rh-110m 1.37490E-05 1.37490E-05 451101 + 421 451110 Rh-111 4.34070E-04 9.20010E-04 451110 + 422 451120 Rh-112 8.92800E-05 2.16020E-04 451120 + 423 451121 Rh-112m 8.92800E-05 8.92800E-05 451121 + 424 451130 Rh-113 9.01920E-05 1.03500E-04 451130 + 425 451140 Rh-114 1.63230E-05 1.92060E-05 451140 + 426 451141 Rh-114m 1.63230E-05 1.63230E-05 451141 + 427 451150 Rh-115 1.41410E-05 1.50810E-05 451150 + 428 451160 Rh-116 7.82010E-07 7.82120E-07 451160 + 429 451161 Rh-116m 2.13160E-06 2.13160E-06 451161 + 430 451170 Rh-117 1.18690E-08 1.18710E-08 451170 + 431 451180 Rh-118 3.29730E-10 3.29730E-10 451180 + 432 451190 Rh-119 9.46880E-12 9.46880E-12 451190 + 433 451200 Rh-120 1.13300E-07 1.13360E-07 451200 + 434 451210 Rh-121 7.28730E-09 7.28730E-09 451210 + 435 451220 Rh-122 2.56790E-10 2.56790E-10 451220 + 436 461060 Pd-106 1.13300E-08 2.67990E-02 46106.82c + 437 461070 Pd-107 9.01700E-07 1.82800E-02 46107.82c + 438 461071 Pd-107m 1.98190E-06 1.98190E-06 461071 + 439 461080 Pd-108 1.13080E-05 1.09800E-02 46108.82c + 440 461090 Pd-109 1.20600E-05 5.23880E-03 461090 + 441 461091 Pd-109m 2.65060E-05 2.62660E-03 461091 + 442 461100 Pd-110 6.54530E-05 2.42570E-03 46110.82c + 443 461110 Pd-111 2.13680E-05 9.74670E-04 461110 + 444 461111 Pd-111m 4.69650E-05 5.06450E-05 461111 + 445 461120 Pd-112 7.47510E-05 3.80050E-04 461120 + 446 461130 Pd-113 1.47420E-05 1.59490E-04 461130 + 447 461131 Pd-113m 4.12490E-05 4.12490E-05 461131 + 448 461140 Pd-114 6.33460E-05 9.88750E-05 461140 + 449 461150 Pd-115 1.65070E-05 3.24770E-05 461150 + 450 461151 Pd-115m 3.62820E-05 3.84720E-05 461151 + 451 461160 Pd-116 5.82800E-05 6.11940E-05 461160 + 452 461170 Pd-117 4.52540E-06 1.44840E-05 461170 + 453 461171 Pd-117m 9.94660E-06 9.94660E-06 461171 + 454 461180 Pd-118 7.32820E-06 7.32850E-06 461180 + 455 461190 Pd-119 1.01990E-06 1.02660E-06 461190 + 456 461200 Pd-120 2.04400E-06 2.15160E-06 461200 + 457 461210 Pd-121 1.02120E-06 1.02750E-06 461210 + 458 461220 Pd-122 6.11380E-07 6.11640E-07 461220 + 459 461230 Pd-123 5.56060E-08 5.56060E-08 461230 + 460 461240 Pd-124 6.68680E-09 6.68680E-09 461240 + 461 471080 Ag-108 1.34640E-10 1.66570E-10 471080 + 462 471081 Ag-108m 3.67010E-10 3.67010E-10 471081 + 463 471090 Ag-109 1.43880E-09 5.23880E-03 47109.82c + 464 471091 Ag-109m 1.08060E-08 5.23620E-03 471091 + 465 471100 Ag-110 2.44940E-07 2.54020E-07 471100 + 466 471101 Ag-110m 6.67640E-07 6.67640E-07 47510.82c + 467 471110 Ag-111 2.20570E-07 9.85320E-04 47111.82c + 468 471111 Ag-111m 1.65660E-06 9.79180E-04 471111 + 469 471120 Ag-112 1.89640E-06 3.81950E-04 471120 + 470 471130 Ag-113 6.69360E-07 1.08400E-04 471130 + 471 471131 Ag-113m 5.02730E-06 1.57750E-04 471131 + 472 471140 Ag-114 3.28340E-07 1.00790E-04 471140 + 473 471141 Ag-114m 1.59180E-06 1.59180E-06 471141 + 474 471150 Ag-115 2.43640E-06 3.92610E-05 471150 + 475 471151 Ag-115m 1.82990E-05 6.24610E-05 471151 + 476 471160 Ag-116 7.03690E-06 6.93810E-05 471160 + 477 471161 Ag-116m 1.91810E-05 1.91810E-05 471161 + 478 471170 Ag-117 6.12090E-06 1.65560E-05 471170 + 479 471171 Ag-117m 4.59720E-05 5.32140E-05 471171 + 480 471180 Ag-118 6.73570E-06 2.68340E-05 471180 + 481 471181 Ag-118m 3.26540E-05 3.37020E-05 471181 + 482 471190 Ag-119 4.91400E-06 5.42730E-06 471190 + 483 471191 Ag-119m 3.69070E-05 3.74200E-05 471191 + 484 471200 Ag-120 7.26700E-06 1.32400E-05 471200 + 485 471201 Ag-120m 1.21530E-05 1.32290E-05 471201 + 486 471210 Ag-121 2.04220E-06 3.06690E-06 471210 + 487 471220 Ag-122 4.90630E-07 1.10230E-06 471220 + 488 471221 Ag-122m 5.28970E-07 5.28970E-07 471221 + 489 471230 Ag-123 5.12650E-06 5.18210E-06 471230 + 490 471240 Ag-124 1.96790E-06 3.03540E-06 471240 + 491 471241 Ag-124m 2.12160E-06 2.12160E-06 471241 + 492 471250 Ag-125 1.07400E-06 1.07400E-06 471250 + 493 471260 Ag-126 1.09880E-06 1.09880E-06 471260 + 494 471270 Ag-127 1.39590E-08 1.39590E-08 471270 + 495 471280 Ag-128 4.14500E-10 4.14500E-10 471280 + 496 481110 Cd-111 8.33550E-11 9.90220E-04 48111.82c + 497 481111 Cd-111m 3.15670E-10 3.15670E-10 481111 + 498 481120 Cd-112 7.95000E-09 3.81960E-04 48112.82c + 499 481130 Cd-113 1.32560E-08 1.63330E-04 48113.82c + 500 481131 Cd-113m 5.01980E-08 1.92420E-06 481131 + 501 481140 Cd-114 6.11420E-07 1.01410E-04 48114.82c + 502 481150 Cd-115 6.69060E-07 8.55760E-05 481150 + 503 481151 Cd-115m 2.53370E-06 6.23270E-06 48515.82c + 504 481160 Cd-116 3.88450E-06 9.12960E-05 48116.82c + 505 481170 Cd-117 2.82100E-06 5.42050E-05 481170 + 506 481171 Cd-117m 1.06830E-05 2.58760E-05 481171 + 507 481180 Cd-118 2.74750E-05 7.41930E-05 481180 + 508 481190 Cd-119 1.02030E-05 5.03370E-05 481190 + 509 481191 Cd-119m 2.85470E-05 3.12610E-05 481191 + 510 481200 Cd-120 5.72260E-05 7.88000E-05 481200 + 511 481210 Cd-121 1.10250E-05 1.37710E-05 481210 + 512 481211 Cd-121m 3.08460E-05 3.11670E-05 481211 + 513 481220 Cd-122 4.89570E-05 5.05880E-05 481220 + 514 481230 Cd-123 1.13430E-05 1.55850E-05 481230 + 515 481231 Cd-123m 3.17380E-05 3.26820E-05 481231 + 516 481240 Cd-124 6.96170E-05 7.37100E-05 481240 + 517 481250 Cd-125 2.41660E-05 2.47030E-05 481250 + 518 481251 Cd-125m 6.76140E-05 6.81510E-05 481251 + 519 481260 Cd-126 7.71330E-05 7.82320E-05 481260 + 520 481270 Cd-127 4.00950E-05 4.01090E-05 481270 + 521 481280 Cd-128 1.25890E-05 1.25890E-05 481280 + 522 481290 Cd-129 5.44580E-07 5.44580E-07 481290 + 523 481291 Cd-129m 1.52370E-06 1.52370E-06 481291 + 524 481300 Cd-130 1.55460E-08 1.55460E-08 481300 + 525 491130 In-113 7.88220E-12 1.92160E-06 49113.82c + 526 491131 In-113m 1.58700E-12 1.58700E-12 491131 + 527 491140 In-114 5.28290E-11 2.30460E-10 491140 + 528 491141 In-114m 8.53080E-11 1.84070E-10 491141 + 529 491142 In-114m 9.87640E-11 9.87640E-11 491142 + 530 491150 In-115 6.41060E-09 8.75370E-05 49115.82c + 531 491151 In-115m 1.29070E-09 8.55780E-05 491151 + 532 491160 In-116 2.41240E-08 2.41240E-08 491160 + 533 491161 In-116m 3.89560E-08 8.40560E-08 491161 + 534 491162 In-116m 4.51000E-08 4.51000E-08 491162 + 535 491170 In-117 9.27790E-07 5.46100E-05 491170 + 536 491171 In-117m 1.86810E-07 5.02560E-05 491171 + 537 491180 In-118 1.03160E-06 7.52250E-05 491180 + 538 491181 In-118m 1.66590E-06 3.56750E-06 491181 + 539 491182 In-118m 1.92860E-06 1.92860E-06 491182 + 540 491190 In-119 8.48970E-07 3.94940E-05 491190 + 541 491191 In-119m 1.70930E-07 4.56820E-05 491191 + 542 491200 In-120 3.06550E-06 8.18650E-05 491200 + 543 491201 In-120m 3.06550E-06 3.06550E-06 491201 + 544 491202 In-120m 3.06550E-06 3.06550E-06 491202 + 545 491210 In-121 2.29460E-05 5.89160E-05 491210 + 546 491211 In-121m 4.62010E-06 1.37530E-05 491211 + 547 491220 In-122 1.25900E-05 6.31790E-05 491220 + 548 491221 In-122m 1.05280E-05 1.05280E-05 491221 + 549 491222 In-122m 1.05280E-05 1.05280E-05 491222 + 550 491230 In-123 4.69480E-05 8.40580E-05 491230 + 551 491231 In-123m 9.45280E-06 2.06090E-05 491231 + 552 491240 In-124 5.17290E-05 1.25440E-04 491240 + 553 491241 In-124m 5.57710E-05 5.57710E-05 491241 + 554 491250 In-125 3.11240E-04 3.91220E-04 491250 + 555 491251 In-125m 6.26670E-05 7.55460E-05 491251 + 556 491260 In-126 2.98490E-04 3.76720E-04 491260 + 557 491261 In-126m 3.21810E-04 3.21810E-04 491261 + 558 491270 In-127 8.57540E-04 8.57540E-04 491270 + 559 491271 In-127m 1.72660E-04 2.12770E-04 491271 + 560 491280 In-128 2.15030E-04 3.11810E-04 491280 + 561 491281 In-128m 8.41940E-05 9.67840E-05 491281 + 562 491282 In-128m 3.22600E-04 3.22600E-04 491282 + 563 491290 In-129 2.89710E-04 2.91230E-04 491290 + 564 491291 In-129m 5.83320E-05 5.88760E-05 491291 + 565 491300 In-130 2.50450E-05 2.50600E-05 491300 + 566 491301 In-130m 3.64670E-05 3.64670E-05 491301 + 567 491302 In-130m 5.07980E-05 5.07980E-05 491302 + 568 491310 In-131 5.77840E-06 5.83720E-06 491310 + 569 491311 In-131m 5.77840E-06 5.77840E-06 491311 + 570 491312 In-131m 5.77840E-06 5.77840E-06 491312 + 571 491320 In-132 1.24540E-07 1.24540E-07 491320 + 572 491330 In-133 2.67230E-09 3.21040E-09 491330 + 573 491331 In-133m 5.38060E-10 5.38060E-10 491331 + 574 501160 Sn-116 5.92390E-11 1.08240E-07 50116.82c + 575 501170 Sn-117 3.38000E-10 8.11970E-05 50117.82c + 576 501171 Sn-117m 1.28000E-09 1.87340E-07 501171 + 577 501180 Sn-118 4.07180E-08 7.88600E-05 50118.82c + 578 501190 Sn-119 9.57120E-08 8.30760E-05 50119.82c + 579 501191 Sn-119m 3.62460E-07 3.60410E-05 501191 + 580 501200 Sn-120 9.72870E-11 8.79960E-05 50120.82c + 581 501210 Sn-121 2.68860E-07 7.18620E-05 501210 + 582 501211 Sn-121m 7.52240E-07 7.42650E-06 501211 + 583 501220 Sn-122 6.11530E-06 9.03500E-05 50122.82c + 584 501230 Sn-123 1.20740E-05 1.84830E-05 50123.82c + 585 501231 Sn-123m 4.31520E-06 1.02570E-04 501231 + 586 501240 Sn-124 7.03150E-05 2.51530E-04 50124.82c + 587 501250 Sn-125 1.55380E-04 2.21470E-04 50125.82c + 588 501251 Sn-125m 5.55350E-05 4.56210E-04 501251 + 589 501260 Sn-126 1.09350E-03 1.79350E-03 50126.82c + 590 501270 Sn-127 1.81950E-03 2.15370E-03 501270 + 591 501271 Sn-127m 6.50300E-04 1.38490E-03 501271 + 592 501280 Sn-128 1.63730E-03 6.73450E-03 501280 + 593 501281 Sn-128m 4.46280E-03 4.78540E-03 501281 + 594 501290 Sn-129 1.51380E-03 1.83300E-03 501290 + 595 501291 Sn-129m 4.23550E-03 4.26650E-03 501291 + 596 501300 Sn-130 1.39180E-03 1.46040E-03 501300 + 597 501301 Sn-130m 3.79360E-03 3.83740E-03 501301 + 598 501310 Sn-131 5.59170E-04 5.70370E-04 501310 + 599 501311 Sn-131m 1.56450E-03 1.57060E-03 501311 + 600 501320 Sn-132 7.06700E-04 7.06830E-04 501320 + 601 501330 Sn-133 4.05640E-05 4.05650E-05 501330 + 602 501340 Sn-134 7.32070E-06 7.32070E-06 501340 + 603 501350 Sn-135 3.95970E-08 3.95970E-08 501350 + 604 511180 Sb-118 1.29200E-12 1.29200E-12 511180 + 605 511181 Sb-118m 2.16060E-12 2.16060E-12 511181 + 606 511190 Sb-119 2.07750E-10 2.91170E-10 511190 + 607 511191 Sb-119m 8.34200E-11 8.34200E-11 511191 + 608 511220 Sb-122 3.56910E-12 8.35080E-12 511220 + 609 511221 Sb-122m 4.78170E-12 4.78170E-12 511221 + 610 511230 Sb-123 1.02510E-06 1.22080E-04 51123.82c + 611 511240 Sb-124 6.59900E-07 1.69840E-06 51124.82c + 612 511241 Sb-124m 5.32340E-07 1.38460E-06 511241 + 613 511242 Sb-124m 8.52270E-07 8.52270E-07 511242 + 614 511250 Sb-125 1.05240E-05 6.88210E-04 51125.82c + 615 511260 Sb-126 2.79230E-05 3.33910E-05 51126.82c + 616 511261 Sb-126m 1.74410E-05 3.90610E-05 511261 + 617 511262 Sb-126m 2.16200E-05 2.16200E-05 511262 + 618 511270 Sb-127 4.81390E-04 4.02000E-03 511270 + 619 511280 Sb-128 7.52760E-04 7.52520E-03 511280 + 620 511281 Sb-128m 1.05280E-03 1.05280E-03 511281 + 621 511290 Sb-129 4.36660E-03 9.13750E-03 511290 + 622 511291 Sb-129m 3.23140E-03 5.36460E-03 511291 + 623 511300 Sb-130 5.69200E-03 9.07110E-03 511300 + 624 511301 Sb-130m 5.69200E-03 7.61070E-03 511301 + 625 511310 Sb-131 1.67860E-02 1.89270E-02 511310 + 626 511320 Sb-132 5.57880E-03 6.28560E-03 511320 + 627 511321 Sb-132m 4.93930E-03 4.93930E-03 511321 + 628 511330 Sb-133 6.58230E-03 6.62410E-03 511330 + 629 511340 Sb-134 3.07910E-04 3.13990E-04 511340 + 630 511341 Sb-134m 8.39290E-04 8.39300E-04 511341 + 631 511350 Sb-135 1.98200E-04 1.98230E-04 511350 + 632 511360 Sb-136 2.44210E-05 2.44210E-05 511360 + 633 511370 Sb-137 9.95690E-07 9.95690E-07 511370 + 634 511380 Sb-138 3.33800E-09 3.33800E-09 511380 + 635 521250 Te-125 4.39780E-07 6.90310E-04 52125.82c + 636 521251 Te-125m 1.66540E-06 1.55660E-04 521251 + 637 521260 Te-126 7.41360E-08 6.70580E-05 52126.82c + 638 521270 Te-127 3.41790E-06 4.01690E-03 521270 + 639 521271 Te-127m 9.56310E-06 6.72040E-04 52527.82c + 640 521280 Te-128 1.45970E-04 8.68610E-03 52128.82c + 641 521290 Te-129 2.47930E-04 1.21740E-02 521290 + 642 521291 Te-129m 6.93710E-04 6.66320E-03 52529.82c + 643 521300 Te-130 5.90500E-03 2.25870E-02 52130.82c + 644 521310 Te-131 3.56690E-03 2.33930E-02 521310 + 645 521311 Te-131m 9.98010E-03 1.14950E-02 521311 + 646 521320 Te-132 3.36330E-02 4.48580E-02 52132.82c + 647 521330 Te-133 9.60360E-03 1.99860E-02 521330 + 648 521331 Te-133m 2.68700E-02 2.80160E-02 521331 + 649 521340 Te-134 3.67920E-02 3.79760E-02 521340 + 650 521350 Te-135 1.02420E-02 1.04130E-02 521350 + 651 521360 Te-136 3.55930E-03 3.58020E-03 521360 + 652 521370 Te-137 4.69320E-04 4.69830E-04 521370 + 653 521380 Te-138 8.79940E-05 8.79970E-05 521380 + 654 521390 Te-139 3.98540E-06 3.98540E-06 521390 + 655 521400 Te-140 3.41870E-08 3.41870E-08 521400 + 656 531270 I-127 4.69180E-10 4.03300E-03 53127.82c + 657 531280 I-128 3.95850E-08 3.95850E-08 531280 + 658 531290 I-129 2.06820E-06 1.46410E-02 53129.82c + 659 531300 I-130 3.75170E-05 4.90790E-05 53130.82c + 660 531301 I-130m 1.37640E-05 1.37640E-05 531301 + 661 531310 I-131 5.73170E-04 3.30470E-02 53131.82c + 662 531320 I-132 1.24780E-03 4.70560E-02 531320 + 663 531321 I-132m 1.10470E-03 1.10470E-03 531321 + 664 531330 I-133 7.05670E-03 5.53780E-02 531330 + 665 531331 I-133m 5.22230E-03 5.22230E-03 531331 + 666 531340 I-134 1.39700E-02 6.40300E-02 531340 + 667 531341 I-134m 1.23690E-02 1.23690E-02 531341 + 668 531350 I-135 4.88190E-02 5.92320E-02 53135.82c + 669 531360 I-136 6.46870E-03 1.00560E-02 531360 + 670 531361 I-136m 1.76320E-02 1.76390E-02 531361 + 671 531370 I-137 1.41390E-02 1.46000E-02 531370 + 672 531380 I-138 3.23540E-03 3.31780E-03 531380 + 673 531390 I-139 1.37130E-03 1.37530E-03 531390 + 674 531400 I-140 1.58470E-04 1.58500E-04 531400 + 675 531410 I-141 3.54920E-05 3.54920E-05 531410 + 676 531420 I-142 9.66560E-07 9.66560E-07 531420 + 677 531430 I-143 2.61560E-09 2.61560E-09 531430 + 678 541300 Xe-130 2.59100E-08 5.13070E-05 54130.82c + 679 541310 Xe-131 1.61000E-06 3.30530E-02 54131.82c + 680 541311 Xe-131m 4.50480E-06 3.63460E-04 541311 + 681 541320 Xe-132 3.68580E-05 4.72970E-02 54132.82c + 682 541321 Xe-132m 4.93800E-05 4.93800E-05 541321 + 683 541330 Xe-133 1.33860E-04 5.58860E-02 54133.82c + 684 541331 Xe-133m 3.74530E-04 1.95080E-03 541331 + 685 541340 Xe-134 1.06280E-03 6.82740E-02 54134.82c + 686 541341 Xe-134m 2.89690E-03 3.18140E-03 541341 + 687 541350 Xe-135 4.06270E-03 7.45350E-02 54135.82c + 688 541351 Xe-135m 1.13670E-02 2.11460E-02 541351 + 689 541360 Xe-136 5.47880E-02 8.34320E-02 54136.82c + 690 541370 Xe-137 5.01820E-02 6.40090E-02 541370 + 691 541380 Xe-138 4.39350E-02 4.72120E-02 541380 + 692 541390 Xe-139 1.78120E-02 1.90670E-02 541390 + 693 541400 Xe-140 1.15000E-02 1.16510E-02 541400 + 694 541410 Xe-141 2.84580E-03 2.87410E-03 541410 + 695 541420 Xe-142 8.99440E-04 9.00170E-04 541420 + 696 541430 Xe-143 9.00020E-05 9.00040E-05 541430 + 697 541440 Xe-144 1.08420E-05 1.08420E-05 541440 + 698 541450 Xe-145 1.63410E-08 1.63410E-08 541450 + 699 551320 Cs-132 4.29440E-09 4.29440E-09 551320 + 700 551330 Cs-133 1.01490E-06 5.58870E-02 55133.82c + 701 551340 Cs-134 4.43890E-06 8.36900E-06 55134.82c + 702 551341 Cs-134m 3.93010E-06 3.93010E-06 551341 + 703 551350 Cs-135 8.69980E-05 7.48140E-02 55135.82c + 704 551351 Cs-135m 6.43820E-05 6.43820E-05 551351 + 705 551360 Cs-136 6.15170E-04 8.35080E-04 55136.82c + 706 551361 Cs-136m 4.39830E-04 4.39830E-04 551361 + 707 551370 Cs-137 8.98480E-03 7.29940E-02 55137.82c + 708 551380 Cs-138 7.26320E-03 6.43140E-02 551380 + 709 551381 Cs-138m 1.21470E-02 1.21470E-02 551381 + 710 551390 Cs-139 2.91640E-02 4.82310E-02 551390 + 711 551400 Cs-140 2.16590E-02 3.33120E-02 551400 + 712 551410 Cs-141 2.34140E-02 2.62900E-02 551410 + 713 551420 Cs-142 9.99440E-03 1.08920E-02 551420 + 714 551430 Cs-143 4.92080E-03 5.01020E-03 551430 + 715 551440 Cs-144 5.52100E-04 8.38670E-04 551440 + 716 551441 Cs-144m 5.52100E-04 5.52100E-04 551441 + 717 551450 Cs-145 1.99150E-04 1.99170E-04 551450 + 718 551460 Cs-146 1.45550E-05 1.45550E-05 551460 + 719 551470 Cs-147 2.91920E-06 2.91920E-06 551470 + 720 551480 Cs-148 8.94050E-10 8.94050E-10 551480 + 721 561340 Ba-134 2.68340E-09 8.37170E-06 56134.82c + 722 561350 Ba-135 1.90120E-08 7.22080E-08 56135.82c + 723 561351 Ba-135m 5.31960E-08 5.31960E-08 561351 + 724 561360 Ba-136 2.09870E-06 1.06280E-03 56136.82c + 725 561361 Ba-136m 5.72060E-06 5.72060E-06 561361 + 726 561370 Ba-137 3.91530E-05 7.31430E-02 56137.82c + 727 561371 Ba-137m 1.09550E-04 6.90150E-02 561371 + 728 561380 Ba-138 2.36210E-03 6.89840E-02 56138.82c + 729 561390 Ba-139 7.12150E-03 5.53530E-02 561390 + 730 561400 Ba-140 1.94560E-02 5.27680E-02 56140.82c + 731 561410 Ba-141 2.46810E-02 5.09710E-02 561410 + 732 561420 Ba-142 4.12150E-02 5.21890E-02 561420 + 733 561430 Ba-143 2.87480E-02 3.37030E-02 561430 + 734 561440 Ba-144 2.13090E-02 2.24250E-02 561440 + 735 561450 Ba-145 6.75630E-03 6.92900E-03 561450 + 736 561460 Ba-146 2.74740E-03 2.76070E-03 561460 + 737 561470 Ba-147 4.93520E-04 4.95610E-04 561470 + 738 561480 Ba-148 1.09520E-04 1.09520E-04 561480 + 739 561490 Ba-149 4.93790E-06 4.93790E-06 561490 + 740 561500 Ba-150 5.27050E-09 5.27050E-09 561500 + 741 571370 La-137 8.41470E-09 8.41470E-09 571370 + 742 571380 La-138 2.07300E-06 2.07300E-06 57138.82c + 743 571390 La-139 4.78690E-05 5.54010E-02 57139.82c + 744 571400 La-140 2.67810E-04 5.30350E-02 57140.82c + 745 571410 La-141 1.40950E-03 5.23810E-02 571410 + 746 571420 La-142 3.10860E-03 5.52980E-02 571420 + 747 571430 La-143 1.05330E-02 4.42360E-02 571430 + 748 571440 La-144 1.50420E-02 3.74670E-02 571440 + 749 571450 La-145 1.81900E-02 2.51190E-02 571450 + 750 571460 La-146 3.14800E-03 5.90870E-03 571460 + 751 571461 La-146m 6.60420E-03 6.60420E-03 571461 + 752 571470 La-147 6.83540E-03 7.33140E-03 571470 + 753 571480 La-148 2.02500E-03 2.13410E-03 571480 + 754 571490 La-149 5.72740E-04 5.77660E-04 571490 + 755 571500 La-150 7.49210E-05 7.49260E-05 571500 + 756 571510 La-151 1.97850E-06 1.97850E-06 571510 + 757 571520 La-152 9.74960E-07 9.74960E-07 571520 + 758 571530 La-153 1.30970E-10 1.30970E-10 571530 + 759 581390 Ce-139 4.54220E-10 1.72510E-09 581390 + 760 581391 Ce-139m 1.27090E-09 1.27090E-09 581391 + 761 581400 Ce-140 2.94180E-06 5.30380E-02 58140.82c + 762 581410 Ce-141 3.06020E-05 5.24110E-02 58141.82c + 763 581420 Ce-142 1.93060E-04 5.54910E-02 58142.82c + 764 581430 Ce-143 7.71970E-04 4.50080E-02 58143.82c + 765 581440 Ce-144 3.32810E-03 4.07950E-02 58144.82c + 766 581450 Ce-145 7.70290E-03 3.28220E-02 581450 + 767 581460 Ce-146 1.44730E-02 2.69860E-02 581460 + 768 581470 Ce-147 1.40880E-02 2.14190E-02 581470 + 769 581480 Ce-148 1.39650E-02 1.61070E-02 581480 + 770 581490 Ce-149 6.14240E-03 6.71400E-03 581490 + 771 581500 Ce-150 3.05740E-03 3.13030E-03 581500 + 772 581510 Ce-151 6.09150E-04 6.11190E-04 581510 + 773 581520 Ce-152 1.46810E-04 1.47730E-04 581520 + 774 581530 Ce-153 1.12740E-05 1.12740E-05 581530 + 775 581540 Ce-154 3.16110E-08 3.16110E-08 581540 + 776 581550 Ce-155 3.52080E-10 3.52080E-10 581550 + 777 591420 Pr-142 2.59440E-07 9.66610E-07 59142.82c + 778 591421 Pr-142m 7.07170E-07 7.07170E-07 591421 + 779 591430 Pr-143 3.96240E-06 4.50120E-02 59143.82c + 780 591440 Pr-144 9.70810E-07 4.08060E-02 591440 + 781 591441 Pr-144m 9.87620E-06 5.72830E-04 591441 + 782 591450 Pr-145 9.07330E-05 3.29130E-02 591450 + 783 591460 Pr-146 3.42880E-04 2.73290E-02 591460 + 784 591470 Pr-147 1.34840E-03 2.27680E-02 591470 + 785 591480 Pr-148 4.54710E-04 1.65620E-02 591480 + 786 591481 Pr-148m 2.20440E-03 2.20440E-03 591481 + 787 591490 Pr-149 4.67850E-03 1.13920E-02 591490 + 788 591500 Pr-150 3.75590E-03 6.88620E-03 591500 + 789 591510 Pr-151 3.16790E-03 3.77910E-03 591510 + 790 591520 Pr-152 1.07260E-03 1.22040E-03 591520 + 791 591530 Pr-153 3.68580E-04 3.79780E-04 591530 + 792 591540 Pr-154 7.03260E-05 7.03570E-05 591540 + 793 591550 Pr-155 1.03120E-05 1.03120E-05 591550 + 794 591560 Pr-156 3.30140E-08 3.30140E-08 591560 + 795 591570 Pr-157 7.93920E-10 7.93920E-10 591570 + 796 591580 Pr-158 5.12400E-12 5.12400E-12 591580 + 797 601440 Nd-144 1.60150E-09 4.08060E-02 60144.82c + 798 601450 Nd-145 3.37020E-08 3.29130E-02 60145.82c + 799 601460 Nd-146 5.82510E-06 2.73350E-02 60146.82c + 800 601470 Nd-147 4.77610E-05 2.28160E-02 60147.82c + 801 601480 Nd-148 2.65620E-04 1.90320E-02 60148.82c + 802 601490 Nd-149 7.68060E-04 1.21610E-02 601490 + 803 601500 Nd-150 1.68960E-03 8.57580E-03 60150.82c + 804 601510 Nd-151 2.34920E-03 6.12830E-03 601510 + 805 601520 Nd-152 2.72730E-03 3.94770E-03 601520 + 806 601530 Nd-153 1.57860E-03 1.95840E-03 601530 + 807 601540 Nd-154 9.17470E-04 9.87830E-04 601540 + 808 601550 Nd-155 2.21950E-04 2.32260E-04 601550 + 809 601560 Nd-156 6.84070E-05 6.84390E-05 601560 + 810 601570 Nd-157 7.42820E-06 7.42890E-06 601570 + 811 601580 Nd-158 5.39240E-08 5.39290E-08 601580 + 812 601590 Nd-159 1.31220E-09 1.31220E-09 601590 + 813 601600 Nd-160 1.88870E-11 1.88870E-11 601600 + 814 611470 Pm-147 3.25010E-09 2.28160E-02 61147.82c + 815 611480 Pm-148 2.51960E-08 2.86300E-08 61148.82c + 816 611481 Pm-148m 6.86790E-08 6.86790E-08 61548.82c + 817 611490 Pm-149 9.87600E-07 1.21620E-02 61149.82c + 818 611500 Pm-150 2.06860E-05 2.06860E-05 611500 + 819 611510 Pm-151 8.61910E-05 6.21450E-03 61151.82c + 820 611520 Pm-152 2.88990E-05 3.97660E-03 611520 + 821 611521 Pm-152m 6.07550E-05 6.07550E-05 611521 + 822 611522 Pm-152m 7.93620E-05 7.93620E-05 611522 + 823 611530 Pm-153 3.48570E-04 2.30690E-03 611530 + 824 611540 Pm-154 1.71940E-04 1.15980E-03 611540 + 825 611541 Pm-154m 1.71940E-04 1.71940E-04 611541 + 826 611550 Pm-155 3.46750E-04 5.79010E-04 611550 + 827 611560 Pm-156 1.94470E-04 2.62910E-04 611560 + 828 611570 Pm-157 1.04830E-04 1.12260E-04 611570 + 829 611580 Pm-158 1.28480E-05 1.29020E-05 611580 + 830 611590 Pm-159 7.60530E-06 7.60660E-06 611590 + 831 611600 Pm-160 3.69550E-08 3.69740E-08 611600 + 832 611610 Pm-161 1.05130E-09 1.05130E-09 611610 + 833 611620 Pm-162 1.91250E-11 1.91250E-11 611620 + 834 621490 Sm-149 3.80420E-10 1.21620E-02 62149.82c + 835 621500 Sm-150 1.12000E-08 2.06970E-05 62150.82c + 836 621510 Sm-151 1.97810E-06 6.21650E-03 62151.82c + 837 621520 Sm-152 3.89800E-06 4.12060E-03 62152.82c + 838 621530 Sm-153 7.15040E-06 2.33410E-03 62153.82c + 839 621531 Sm-153m 2.00070E-05 2.00070E-05 621531 + 840 621540 Sm-154 7.31590E-05 1.40490E-03 62154.82c + 841 621550 Sm-155 1.26530E-04 7.05540E-04 621550 + 842 621560 Sm-156 2.05160E-04 4.68070E-04 621560 + 843 621570 Sm-157 1.38060E-04 2.50320E-04 621570 + 844 621580 Sm-158 7.89150E-05 9.18180E-05 621580 + 845 621590 Sm-159 4.18310E-05 4.94360E-05 621590 + 846 621600 Sm-160 1.55240E-05 1.55610E-05 621600 + 847 621610 Sm-161 9.68790E-07 9.69840E-07 621610 + 848 621620 Sm-162 4.94270E-08 4.94460E-08 621620 + 849 621630 Sm-163 8.96350E-10 8.96350E-10 621630 + 850 621640 Sm-164 1.13110E-11 1.13110E-11 621640 + 851 631520 Eu-152 1.84610E-10 4.29130E-10 63152.82c + 852 631521 Eu-152m 4.21820E-11 4.21820E-11 631521 + 853 631522 Eu-152m 2.44520E-10 2.44520E-10 631522 + 854 631530 Eu-153 1.41440E-08 2.33410E-03 63153.82c + 855 631540 Eu-154 8.60000E-08 1.78720E-07 63154.82c + 856 631541 Eu-154m 9.27200E-08 9.27200E-08 631541 + 857 631550 Eu-155 2.80940E-06 7.08350E-04 63155.82c + 858 631560 Eu-156 7.43040E-06 4.75500E-04 63156.82c + 859 631570 Eu-157 1.66910E-05 2.67010E-04 63157.82c + 860 631580 Eu-158 1.55970E-05 1.07420E-04 631580 + 861 631590 Eu-159 2.09110E-05 7.03470E-05 631590 + 862 631600 Eu-160 1.55220E-05 3.10830E-05 631600 + 863 631610 Eu-161 3.87520E-06 4.84500E-06 631610 + 864 631620 Eu-162 1.59010E-06 1.63960E-06 631620 + 865 631630 Eu-163 1.53250E-06 1.53340E-06 631630 + 866 631640 Eu-164 5.41840E-09 5.42970E-09 631640 + 867 631650 Eu-165 7.55000E-10 7.55000E-10 631650 + 868 631660 Eu-166 2.56960E-11 2.56960E-11 631660 + 869 641540 Gd-154 5.26850E-11 1.78740E-07 64154.82c + 870 641550 Gd-155 2.02790E-10 7.08350E-04 64155.82c + 871 641551 Gd-155m 5.67380E-10 5.67380E-10 641551 + 872 641560 Gd-156 2.16490E-08 4.75520E-04 64156.82c + 873 641570 Gd-157 1.85490E-06 2.68870E-04 64157.82c + 874 641580 Gd-158 2.75260E-06 1.10170E-04 64158.82c + 875 641590 Gd-159 1.90120E-06 7.22480E-05 641590 + 876 641600 Gd-160 1.94030E-06 3.30230E-05 64160.82c + 877 641610 Gd-161 7.75010E-06 1.25950E-05 641610 + 878 641620 Gd-162 6.57560E-06 8.21520E-06 641620 + 879 641630 Gd-163 7.66240E-07 2.29960E-06 641630 + 880 641640 Gd-164 2.48550E-07 2.53980E-07 641640 + 881 641650 Gd-165 8.34410E-08 8.41960E-08 641650 + 882 641660 Gd-166 1.66630E-08 1.66890E-08 641660 + 883 641670 Gd-167 9.06330E-10 9.06330E-10 641670 + 884 641680 Gd-168 3.99400E-11 3.99400E-11 641680 + 885 651570 Tb-157 3.85390E-11 3.85390E-11 651570 + 886 651580 Tb-158 5.15530E-10 5.65900E-10 651580 + 887 651581 Tb-158m 5.06760E-11 5.06760E-11 651581 + 888 651590 Tb-159 1.17620E-08 7.22600E-05 65159.82c + 889 651600 Tb-160 6.36760E-08 6.36760E-08 65160.82c + 890 651610 Tb-161 2.51670E-07 1.28470E-05 651610 + 891 651620 Tb-162 1.64390E-06 9.85910E-06 651620 + 892 651630 Tb-163 6.72220E-07 2.97190E-06 651630 + 893 651640 Tb-164 2.26760E-07 4.80740E-07 651640 + 894 651650 Tb-165 3.55380E-07 4.39580E-07 651650 + 895 651660 Tb-166 1.53220E-07 1.69910E-07 651660 + 896 651670 Tb-167 4.46250E-08 4.55310E-08 651670 + 897 651680 Tb-168 4.88710E-09 4.92700E-09 651680 + 898 651690 Tb-169 5.73600E-10 5.73600E-10 651690 + 899 651700 Tb-170 2.48050E-11 2.48050E-11 651700 + 900 661590 Dy-159 2.23930E-12 2.23930E-12 661590 + 901 661600 Dy-160 4.53290E-11 6.37210E-08 66160.82c + 902 661610 Dy-161 4.75060E-10 1.28470E-05 66161.82c + 903 661620 Dy-162 7.37400E-09 9.86640E-06 66162.82c + 904 661630 Dy-163 1.84790E-08 2.99030E-06 66163.82c + 905 661640 Dy-164 5.17130E-07 9.97900E-07 66164.82c + 906 661650 Dy-165 4.91500E-07 9.95050E-07 661650 + 907 661651 Dy-165m 6.54400E-08 6.54400E-08 661651 + 908 661660 Dy-166 2.17600E-07 3.87510E-07 661660 + 909 661670 Dy-167 1.26520E-07 1.72050E-07 661670 + 910 661680 Dy-168 6.64910E-08 7.14180E-08 661680 + 911 661690 Dy-169 1.75010E-08 1.80750E-08 661690 + 912 661700 Dy-170 4.19680E-09 4.22160E-09 661700 + 913 661710 Dy-171 3.63760E-10 3.63760E-10 661710 + 914 661720 Dy-172 2.68620E-11 2.68620E-11 661720 + 915 671630 Ho-163 1.31960E-11 1.49530E-11 671630 + 916 671631 Ho-163m 1.75700E-12 1.75700E-12 671631 + 917 671640 Ho-164 1.87320E-11 6.97900E-11 671640 + 918 671641 Ho-164m 5.10580E-11 5.10580E-11 671641 + 919 671650 Ho-165 1.34640E-09 9.97860E-07 67165.82c + 920 671660 Ho-166 1.70880E-09 3.89220E-07 671660 + 921 671661 Ho-166m 4.65780E-09 4.65780E-09 671661 + 922 671670 Ho-167 1.87490E-08 1.90800E-07 671670 + 923 671680 Ho-168 7.58170E-09 9.16160E-08 671680 + 924 671681 Ho-168m 1.26790E-08 1.26790E-08 671681 + 925 671690 Ho-169 2.44070E-08 4.24820E-08 671690 + 926 671700 Ho-170 8.69140E-09 8.69140E-09 671700 + 927 671701 Ho-170m 3.18860E-09 7.41020E-09 671701 + 928 671710 Ho-171 5.11690E-09 5.48070E-09 671710 + 929 671720 Ho-172 8.79960E-10 9.06820E-10 671720 + 930 671730 Ho-173 1.71840E-10 1.71840E-10 671730 + 931 671740 Ho-174 1.23020E-11 1.23020E-11 671740 + 932 681660 Er-166 1.84080E-11 3.89240E-07 68166.82c + 933 681670 Er-167 1.23520E-10 1.90940E-07 68167.82c + 934 681671 Er-167m 1.64450E-11 2.28160E-08 681671 + 935 681680 Er-168 8.52360E-10 9.25310E-08 68168.82c + 936 681690 Er-169 2.34750E-09 4.48290E-08 681690 + 937 681700 Er-170 5.57740E-09 2.16790E-08 68170.82c + 938 681710 Er-171 4.82860E-09 1.03090E-08 681710 + 939 681720 Er-172 3.81360E-09 4.72040E-09 681720 + 940 681730 Er-173 1.55420E-09 1.72600E-09 681730 + 941 681740 Er-174 5.74340E-10 5.86640E-10 681740 + 942 681750 Er-175 8.65310E-11 8.65310E-11 681750 + 943 681760 Er-176 1.15910E-11 1.15910E-11 681760 + 944 691690 Tm-169 7.64780E-12 4.48370E-08 691690 + 945 691700 Tm-170 4.57890E-11 4.57890E-11 691700 + 946 691710 Tm-171 2.16140E-10 1.05250E-08 691710 + 947 691720 Tm-172 3.75650E-10 5.09610E-09 691720 + 948 691730 Tm-173 7.23910E-10 2.44990E-09 691730 + 949 691740 Tm-174 5.32160E-10 1.11880E-09 691740 + 950 691750 Tm-175 3.74510E-10 4.61040E-10 691750 + 951 691760 Tm-176 1.08420E-10 1.20010E-10 691760 + 952 691770 Tm-177 3.14000E-11 3.14000E-11 691770 + 953 691780 Tm-178 3.41790E-12 3.41790E-12 691780 + 954 701720 Yb-172 4.29330E-12 5.10040E-09 701720 + 955 701730 Yb-173 2.02590E-11 2.47020E-09 701730 + 956 701740 Yb-174 7.82900E-11 1.19710E-09 701740 + 957 701750 Yb-175 1.03110E-10 5.77880E-10 701750 + 958 701751 Yb-175m 1.37290E-11 3.68730E-10 701751 + 959 701760 Yb-176 5.04790E-11 2.59800E-10 701760 + 960 701761 Yb-176m 1.05900E-10 1.65910E-10 701761 + 961 701770 Yb-177 7.52720E-11 1.21830E-10 701770 + 962 701771 Yb-177m 1.51560E-11 4.65560E-11 701771 + 963 701780 Yb-178 4.72790E-11 5.06970E-11 701780 + 964 701790 Yb-179 1.23550E-11 1.23550E-11 701790 + 965 701800 Yb-180 2.94140E-12 2.94140E-12 701800 + 966 711750 Lu-175 1.46830E-12 5.79350E-10 71175.82c + 967 711760 Lu-176 3.15270E-12 1.97430E-11 71176.82c + 968 711761 Lu-176m 1.50280E-12 1.50280E-12 711761 + 969 711770 Lu-177 9.08250E-12 1.31910E-10 711770 + 970 711771 Lu-177m 4.32470E-12 4.43230E-12 711771 + 971 711780 Lu-178 6.25370E-12 5.69510E-11 711780 + 972 711781 Lu-178m 8.37830E-12 8.37830E-12 711781 + 973 711790 Lu-179 1.54430E-11 2.98540E-11 711790 + 974 711791 Lu-179m 2.05610E-12 1.44110E-11 711791 + 975 711800 Lu-180 2.24400E-12 6.82350E-12 711800 + 976 711801 Lu-180m 2.24400E-12 5.18540E-12 711801 + 977 711802 Lu-180m 3.97360E-12 3.97360E-12 711802 + 978 711810 Lu-181 3.62200E-12 3.62200E-12 711810 + 979 721790 Hf-179 9.91420E-13 3.15660E-11 72179.82c + 980 721800 Hf-180 1.30290E-12 1.54240E-11 72180.82c + 981 721801 Hf-180m 2.73320E-12 4.72000E-12 721801 + 982 721810 Hf-181 3.47090E-12 7.09290E-12 721810 + 983 721820 Hf-182 8.79080E-13 1.65360E-12 721820 + 984 721821 Hf-182m 1.84420E-12 1.84420E-12 721821 + 985 721830 Hf-183 1.10400E-12 1.10400E-12 721830 + + Nuclide 94239.82c -- plutonium 239 (Pu-239) + + Neutron-induced fission: + + Interpolation region : 1 / 2 + Interpolation energy : 2.53000E-08 MeV + Number of products : 1006 / 1093 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 4.08000E-05 4.08000E-05 1001.82c + 2 10020 H-2 1.34700E-05 1.34700E-05 1002.82c + 3 10030 H-3 1.42000E-04 1.42000E-04 1003.82c + 4 20040 He-4 2.19000E-03 2.19190E-03 2004.82c + 5 20060 He-6 4.09800E-05 4.09800E-05 20060 + 6 20080 He-8 6.87000E-07 6.87000E-07 20080 + 7 30070 Li-7 1.40000E-06 1.50500E-06 3007.82c + 8 30090 Li-9 1.14000E-06 1.14000E-06 30090 + 9 40090 Be-9 1.14000E-06 1.71570E-06 4009.82c + 10 40100 Be-10 1.05000E-05 1.05000E-05 40100 + 11 40110 Be-11 7.52000E-07 7.52000E-07 40110 + 12 40120 Be-12 4.73000E-07 4.73000E-07 40120 + 13 60080 C-8 6.87000E-07 6.87000E-07 60080 + 14 60140 C-14 3.01000E-06 3.01000E-06 60140 + 15 200500 Ca-50 1.11660E-12 1.11660E-12 200500 + 16 210510 Sc-51 2.19030E-12 2.19030E-12 210510 + 17 210520 Sc-52 3.17810E-12 3.17810E-12 210520 + 18 210530 Sc-53 5.01670E-12 5.01670E-12 210530 + 19 210540 Sc-54 2.51670E-12 2.51670E-12 210540 + 20 210550 Sc-55 1.76640E-12 1.76640E-12 210550 + 21 220520 Ti-52 2.26000E-12 5.43810E-12 220520 + 22 220530 Ti-53 5.82660E-12 1.08430E-11 220530 + 23 220540 Ti-54 1.64430E-11 1.89600E-11 220540 + 24 220550 Ti-55 2.02790E-11 2.20450E-11 220550 + 25 220560 Ti-56 2.74280E-11 2.74280E-11 220560 + 26 220570 Ti-57 1.14080E-11 1.14080E-11 220570 + 27 220580 Ti-58 5.44550E-12 5.44550E-12 220580 + 28 230540 V-54 2.57230E-12 2.15320E-11 230540 + 29 230550 V-55 1.78330E-11 3.98780E-11 230550 + 30 230560 V-56 3.94060E-11 6.68680E-11 230560 + 31 230570 V-57 9.44950E-11 1.05870E-10 230570 + 32 230580 V-58 8.21920E-11 8.76370E-11 230580 + 33 230590 V-59 9.20970E-11 9.20970E-11 230590 + 34 230600 V-60 2.96130E-11 2.96130E-11 230600 + 35 230610 V-61 1.16130E-11 1.16130E-11 230610 + 36 230620 V-62 1.48340E-12 1.48340E-12 230620 + 37 240560 Cr-56 8.69760E-12 7.59890E-11 240560 + 38 240570 Cr-57 3.54330E-11 2.10990E-10 240570 + 39 240580 Cr-58 1.70950E-10 1.88480E-10 240580 + 40 240590 Cr-59 3.17080E-10 4.09180E-10 240590 + 41 240600 Cr-60 6.07100E-10 6.37410E-10 240600 + 42 240610 Cr-61 4.50090E-10 4.61010E-10 240610 + 43 240620 Cr-62 3.94730E-10 3.96210E-10 240620 + 44 240630 Cr-63 1.02780E-10 1.02780E-10 240630 + 45 240640 Cr-64 2.70370E-11 2.70370E-11 240640 + 46 240650 Cr-65 2.76570E-12 2.76570E-12 240650 + 47 250580 Mn-58 7.20500E-12 1.95680E-10 250580 + 48 250590 Mn-59 8.87440E-11 4.97920E-10 250590 + 49 250600 Mn-60 2.84990E-11 6.95020E-10 250600 + 50 250601 Mn-60m 2.53110E-10 2.53110E-10 250601 + 51 250610 Mn-61 1.15760E-09 1.61860E-09 250610 + 52 250620 Mn-62 1.45940E-09 1.65750E-09 250620 + 53 250621 Mn-62m 2.62000E-10 4.60100E-10 250621 + 54 250630 Mn-63 2.76750E-09 2.87030E-09 250630 + 55 250640 Mn-64 1.42490E-09 1.45190E-09 250640 + 56 250650 Mn-65 1.02800E-09 1.03080E-09 250650 + 57 250660 Mn-66 2.21130E-10 2.21130E-10 250660 + 58 250670 Mn-67 4.68170E-11 4.68170E-11 250670 + 59 250680 Mn-68 3.19720E-12 3.19720E-12 250680 + 60 260600 Fe-60 1.79130E-11 9.36930E-10 260600 + 61 260610 Fe-61 1.34510E-10 1.75310E-09 260610 + 62 260620 Fe-62 1.15550E-09 3.27310E-09 260620 + 63 260630 Fe-63 3.03640E-09 5.90670E-09 260630 + 64 260640 Fe-64 8.77710E-09 1.02290E-08 260640 + 65 260650 Fe-65 1.10850E-08 1.21160E-08 260650 + 66 260660 Fe-66 1.52750E-08 1.54960E-08 260660 + 67 260670 Fe-67 6.53040E-09 6.57720E-09 260670 + 68 260680 Fe-68 3.21790E-09 3.22110E-09 260680 + 69 260690 Fe-69 5.53660E-10 5.53660E-10 260690 + 70 260700 Fe-70 8.74900E-11 8.74900E-11 260700 + 71 260710 Fe-71 5.52170E-12 5.52170E-12 260710 + 72 270620 Co-62 4.49070E-12 3.27770E-09 270620 + 73 270621 Co-62m 1.05180E-11 1.05180E-11 270621 + 74 270630 Co-63 2.54230E-10 6.16090E-09 270630 + 75 270640 Co-64 1.29440E-09 1.15230E-08 270640 + 76 270650 Co-65 9.20850E-09 2.13240E-08 270650 + 77 270660 Co-66 2.07170E-08 3.62130E-08 270660 + 78 270670 Co-67 5.09090E-08 5.74860E-08 270670 + 79 270680 Co-68 2.41910E-08 3.64910E-08 270680 + 80 270681 Co-68m 2.13400E-08 2.46000E-08 270681 + 81 270690 Co-69 5.19650E-08 5.24800E-08 270690 + 82 270700 Co-70 8.51700E-09 8.51700E-09 270700 + 83 270701 Co-70m 8.51700E-09 8.60450E-09 270701 + 84 270710 Co-71 7.91750E-09 7.92300E-09 270710 + 85 270720 Co-72 5.02810E-10 5.02810E-10 270720 + 86 270730 Co-73 1.25550E-10 1.25550E-10 270730 + 87 270740 Co-74 9.46820E-12 9.46820E-12 270740 + 88 280640 Ni-64 2.19760E-11 1.15450E-08 28064.82c + 89 280650 Ni-65 3.07740E-10 2.16320E-08 280650 + 90 280660 Ni-66 4.30230E-09 4.05150E-08 280660 + 91 280670 Ni-67 1.80190E-08 7.55050E-08 280670 + 92 280680 Ni-68 8.94630E-08 1.38780E-07 280680 + 93 280690 Ni-69 8.43400E-08 1.36290E-07 280690 + 94 280691 Ni-69m 8.43400E-08 8.43400E-08 280691 + 95 280700 Ni-70 3.28030E-07 3.45150E-07 280700 + 96 280710 Ni-71 5.23600E-07 5.31520E-07 280710 + 97 280720 Ni-72 1.24820E-07 1.25320E-07 280720 + 98 280730 Ni-73 6.61530E-08 6.62790E-08 280730 + 99 280740 Ni-74 3.69090E-08 3.69190E-08 280740 + 100 280750 Ni-75 1.76330E-09 1.76330E-09 280750 + 101 280760 Ni-76 2.14930E-10 2.14930E-10 280760 + 102 280770 Ni-77 1.05280E-11 1.05280E-11 280770 + 103 290660 Cu-66 1.44340E-11 4.05300E-08 290660 + 104 290670 Cu-67 4.17090E-10 7.59220E-08 290670 + 105 290680 Cu-68 1.17860E-09 1.42280E-07 290680 + 106 290681 Cu-68m 2.76070E-09 2.76070E-09 290681 + 107 290690 Cu-69 4.44990E-08 2.65130E-07 290690 + 108 290700 Cu-70 1.09390E-08 8.07720E-08 290700 + 109 290701 Cu-70m 1.21860E-07 1.39670E-07 290701 + 110 290702 Cu-70m 1.09390E-08 3.56090E-07 290702 + 111 290710 Cu-71 5.23620E-07 1.05510E-06 290710 + 112 290720 Cu-72 5.04380E-07 6.29700E-07 290720 + 113 290730 Cu-73 1.80600E-06 1.87230E-06 290730 + 114 290740 Cu-74 1.32080E-06 1.35780E-06 290740 + 115 290750 Cu-75 7.43640E-07 7.45380E-07 290750 + 116 290760 Cu-76 7.79900E-07 7.80010E-07 290760 + 117 290761 Cu-76m 7.79900E-07 7.80010E-07 290761 + 118 290770 Cu-77 5.50250E-08 5.50350E-08 290770 + 119 290780 Cu-78 7.96850E-09 7.96850E-09 290780 + 120 290790 Cu-79 1.50930E-10 1.50930E-10 290790 + 121 290800 Cu-80 2.52970E-11 2.52970E-11 290800 + 122 300680 Zn-68 1.67980E-11 1.42730E-07 300680 + 123 300690 Zn-69 7.44140E-11 2.65530E-07 300690 + 124 300691 Zn-69m 3.21830E-10 3.21830E-10 300691 + 125 300700 Zn-70 8.56840E-09 4.97460E-07 300700 + 126 300710 Zn-71 1.43140E-08 1.06950E-06 300710 + 127 300711 Zn-71m 6.19050E-08 6.19050E-08 300711 + 128 300720 Zn-72 5.04390E-07 1.13410E-06 300720 + 129 300730 Zn-73 1.78630E-07 2.98680E-06 300730 + 130 300731 Zn-73m 2.44200E-07 9.35880E-07 300731 + 131 300732 Zn-73m 1.38340E-06 1.38340E-06 300732 + 132 300740 Zn-74 9.90720E-06 1.12910E-05 300740 + 133 300750 Zn-75 7.43610E-06 8.17880E-06 300750 + 134 300760 Zn-76 1.48150E-05 1.63520E-05 300760 + 135 300770 Zn-77 1.05560E-05 1.14180E-05 300770 + 136 300771 Zn-77m 1.61370E-06 1.61370E-06 300771 + 137 300780 Zn-78 1.89110E-05 1.89190E-05 300780 + 138 300790 Zn-79 5.32050E-07 5.32120E-07 300790 + 139 300800 Zn-80 2.61590E-06 2.61590E-06 300800 + 140 300810 Zn-81 9.61600E-09 9.61600E-09 300810 + 141 300820 Zn-82 3.83040E-10 3.83040E-10 300820 + 142 310700 Ga-70 7.05310E-12 7.05310E-12 310700 + 143 310710 Ga-71 4.54950E-10 1.13180E-06 310710 + 144 310720 Ga-72 3.54470E-09 1.13800E-06 310720 + 145 310721 Ga-72m 3.99110E-10 3.81880E-08 310721 + 146 310730 Ga-73 1.36080E-07 3.81460E-06 310730 + 147 310740 Ga-74 6.60500E-07 9.62420E-06 310740 + 148 310741 Ga-74m 6.60500E-07 1.19520E-05 310741 + 149 310750 Ga-75 3.71890E-06 1.18980E-05 310750 + 150 310760 Ga-76 8.58230E-06 2.49340E-05 310760 + 151 310770 Ga-77 4.02680E-05 5.24930E-05 310770 + 152 310780 Ga-78 7.55700E-05 9.44960E-05 310780 + 153 310790 Ga-79 2.90500E-05 2.95750E-05 310790 + 154 310800 Ga-80 5.73170E-05 5.99340E-05 310800 + 155 310810 Ga-81 2.15450E-05 2.15540E-05 310810 + 156 310820 Ga-82 1.82480E-06 1.82520E-06 310820 + 157 310830 Ga-83 1.16240E-07 1.16240E-07 310830 + 158 310840 Ga-84 4.11130E-09 4.11130E-09 310840 + 159 310850 Ga-85 1.85500E-10 1.85500E-10 310850 + 160 320720 Ge-72 4.02790E-12 1.13800E-06 32072.82c + 161 320730 Ge-73 2.46850E-10 3.81490E-06 32073.82c + 162 320731 Ge-73m 5.70780E-11 3.75860E-06 320731 + 163 320740 Ge-74 2.32590E-08 1.26350E-05 32074.82c + 164 320750 Ge-75 2.01610E-08 1.20500E-05 320750 + 165 320751 Ge-75m 1.31880E-07 6.07790E-07 320751 + 166 320760 Ge-76 2.34050E-06 2.72740E-05 32076.82c + 167 320770 Ge-77 2.03300E-05 3.08940E-05 320770 + 168 320771 Ge-77m 3.10790E-06 5.56010E-05 320771 + 169 320780 Ge-78 1.83470E-04 2.77990E-04 320780 + 170 320790 Ge-79 1.24440E-05 4.52070E-05 320790 + 171 320791 Ge-79m 8.14030E-05 8.14470E-05 320791 + 172 320800 Ge-80 7.81620E-04 8.44120E-04 320800 + 173 320810 Ge-81 4.99980E-04 5.11450E-04 320810 + 174 320811 Ge-81m 1.15610E-04 1.24760E-04 320811 + 175 320820 Ge-82 4.16170E-04 4.17650E-04 320820 + 176 320830 Ge-83 1.02460E-04 1.02540E-04 320830 + 177 320840 Ge-84 3.50770E-05 3.50780E-05 320840 + 178 320850 Ge-85 5.16420E-06 5.16440E-06 320850 + 179 320860 Ge-86 7.29700E-08 7.29700E-08 320860 + 180 320870 Ge-87 1.60290E-09 1.60290E-09 320870 + 181 330740 As-74 4.43830E-12 4.43830E-12 330740 + 182 330750 As-75 5.20640E-11 1.20500E-05 33075.82c + 183 330751 As-75m 1.70340E-10 3.52670E-10 330751 + 184 330760 As-76 8.12920E-09 8.12920E-09 330760 + 185 330770 As-77 3.80030E-07 7.63110E-05 330770 + 186 330780 As-78 6.31740E-06 2.84310E-04 330780 + 187 330790 As-79 1.09090E-05 1.34310E-04 330790 + 188 330800 As-80 1.80740E-04 1.02490E-03 330800 + 189 330810 As-81 6.86730E-04 1.32170E-03 330810 + 190 330820 As-82 2.04150E-04 6.21800E-04 330820 + 191 330821 As-82m 6.16070E-04 6.16070E-04 330821 + 192 330830 As-83 8.66180E-04 9.72510E-04 330830 + 193 330840 As-84 2.43500E-04 2.59510E-04 330840 + 194 330841 As-84m 2.43500E-04 2.59510E-04 330841 + 195 330850 As-85 2.90170E-04 2.94610E-04 330850 + 196 330860 As-86 5.52050E-05 5.52780E-05 330860 + 197 330870 As-87 1.37820E-05 1.37840E-05 330870 + 198 330880 As-88 4.09920E-07 4.09920E-07 330880 + 199 330890 As-89 2.29920E-08 2.29920E-08 330890 + 200 330900 As-90 5.04360E-10 5.04360E-10 330900 + 201 340760 Se-76 2.05680E-12 8.13130E-09 34076.82c + 202 340770 Se-77 2.70830E-11 7.63110E-05 34077.82c + 203 340771 Se-77m 1.77170E-10 1.77170E-10 340771 + 204 340780 Se-78 2.10590E-06 2.86420E-04 34078.82c + 205 340790 Se-79 1.49710E-07 1.34400E-04 34079.82c + 206 340791 Se-79m 2.28850E-08 1.31150E-04 340791 + 207 340800 Se-80 3.44530E-05 1.05930E-03 34080.82c + 208 340810 Se-81 2.30490E-05 1.49540E-03 340810 + 209 340811 Se-81m 1.50770E-04 1.98220E-04 340811 + 210 340820 Se-82 7.96190E-04 2.03410E-03 34082.82c + 211 340830 Se-83 1.52840E-03 1.87890E-03 340830 + 212 340831 Se-83m 3.53400E-04 9.76170E-04 340831 + 213 340840 Se-84 3.89160E-03 4.47470E-03 340840 + 214 340850 Se-85 3.44470E-03 3.69270E-03 340850 + 215 340860 Se-86 2.69650E-03 2.73570E-03 340860 + 216 340870 Se-87 1.27110E-03 1.28280E-03 340870 + 217 340880 Se-88 4.98820E-04 4.99230E-04 340880 + 218 340890 Se-89 1.15790E-04 1.15810E-04 340890 + 219 340900 Se-90 2.50770E-05 2.50770E-05 340900 + 220 340910 Se-91 1.83020E-06 1.83020E-06 340910 + 221 340920 Se-92 6.78420E-09 6.78420E-09 340920 + 222 350790 Br-79 1.41330E-11 7.35030E-08 35079.82c + 223 350791 Br-79m 4.62380E-11 4.62380E-11 350791 + 224 350800 Br-80 3.36860E-09 1.35340E-08 350800 + 225 350801 Br-80m 1.01650E-08 1.01650E-08 350801 + 226 350810 Br-81 5.71460E-07 1.49610E-03 35081.82c + 227 350820 Br-82 5.12830E-06 7.26520E-06 350820 + 228 350821 Br-82m 2.18950E-06 2.18950E-06 350821 + 229 350830 Br-83 8.63920E-05 2.94140E-03 350830 + 230 350840 Br-84 2.00020E-04 4.67470E-03 350840 + 231 350841 Br-84m 2.00020E-04 2.00020E-04 350841 + 232 350850 Br-85 1.89480E-03 5.58750E-03 350850 + 233 350860 Br-86 3.38880E-03 6.12450E-03 350860 + 234 350870 Br-87 4.72390E-03 6.01160E-03 350870 + 235 350880 Br-88 3.22470E-03 3.72800E-03 350880 + 236 350890 Br-89 2.57390E-03 2.68070E-03 350890 + 237 350900 Br-90 1.10920E-03 1.13470E-03 350900 + 238 350910 Br-91 3.79630E-04 3.81080E-04 350910 + 239 350920 Br-92 6.34810E-05 6.34880E-05 350920 + 240 350930 Br-93 1.15820E-05 1.15820E-05 350930 + 241 350940 Br-94 9.01970E-07 9.01970E-07 350940 + 242 350950 Br-95 1.55980E-09 1.55980E-09 350950 + 243 360810 Kr-81 7.31660E-11 8.43510E-11 360810 + 244 360811 Kr-81m 1.11850E-11 1.11850E-11 360811 + 245 360820 Kr-82 6.74140E-09 7.32450E-06 36082.82c + 246 360830 Kr-83 2.42040E-06 2.94440E-03 36083.82c + 247 360831 Kr-83m 5.59640E-07 2.93940E-03 360831 + 248 360840 Kr-84 2.33990E-05 4.89820E-03 36084.82c + 249 360850 Kr-85 1.36020E-04 1.34560E-03 36085.82c + 250 360851 Kr-85m 3.14510E-05 5.60990E-03 360851 + 251 360860 Kr-86 1.46840E-03 7.74370E-03 36086.82c + 252 360870 Kr-87 3.74080E-03 9.85130E-03 360870 + 253 360880 Kr-88 9.17410E-03 1.30300E-02 360880 + 254 360890 Kr-89 1.22140E-02 1.47960E-02 360890 + 255 360900 Kr-90 1.31540E-02 1.40860E-02 360900 + 256 360910 Kr-91 8.00170E-03 8.32760E-03 360910 + 257 360920 Kr-92 4.56880E-03 4.61910E-03 360920 + 258 360930 Kr-93 1.57020E-03 1.57450E-03 360930 + 259 360940 Kr-94 4.41830E-04 4.42100E-04 360940 + 260 360950 Kr-95 5.52250E-05 5.52270E-05 360950 + 261 360960 Kr-96 6.62050E-06 6.62050E-06 360960 + 262 360970 Kr-97 9.21180E-07 9.21180E-07 360970 + 263 370840 Rb-84 4.89640E-10 1.37040E-09 370840 + 264 370841 Rb-84m 8.80760E-10 8.80760E-10 370841 + 265 370850 Rb-85 9.08940E-08 5.75510E-03 37085.82c + 266 370860 Rb-86 2.13610E-06 5.97850E-06 37086.82c + 267 370861 Rb-86m 3.84240E-06 3.84240E-06 370861 + 268 370870 Rb-87 9.54350E-05 9.94670E-03 37087.82c + 269 370880 Rb-88 3.59700E-04 1.33900E-02 370880 + 270 370890 Rb-89 2.21120E-03 1.70070E-02 370890 + 271 370900 Rb-90 5.71450E-04 1.29950E-02 370900 + 272 370901 Rb-90m 5.07520E-03 6.91770E-03 370901 + 273 370910 Rb-91 1.24020E-02 2.07300E-02 370910 + 274 370920 Rb-92 1.33380E-02 1.79570E-02 370920 + 275 370930 Rb-93 1.31150E-02 1.46940E-02 370930 + 276 370940 Rb-94 6.65050E-03 7.08930E-03 370940 + 277 370950 Rb-95 3.49830E-03 3.55220E-03 370950 + 278 370960 Rb-96 3.77570E-04 5.71180E-04 370960 + 279 370961 Rb-96m 3.77570E-04 3.80780E-04 370961 + 280 370970 Rb-97 1.86590E-04 1.87450E-04 370970 + 281 370980 Rb-98 8.87700E-06 8.87700E-06 370980 + 282 370981 Rb-98m 8.87700E-06 8.87700E-06 370981 + 283 370990 Rb-99 3.78600E-06 3.78600E-06 370990 + 284 371000 Rb-100 1.52100E-09 1.52100E-09 371000 + 285 380860 Sr-86 5.83780E-10 5.97880E-06 38086.82c + 286 380870 Sr-87 8.65640E-07 1.06520E-06 38087.82c + 287 380871 Sr-87m 2.00160E-07 2.00160E-07 380871 + 288 380880 Sr-88 1.83160E-05 1.34080E-02 38088.82c + 289 380890 Sr-89 1.14360E-04 1.71210E-02 38089.82c + 290 380900 Sr-90 1.03530E-03 2.07680E-02 38090.82c + 291 380910 Sr-91 3.54940E-03 2.42790E-02 380910 + 292 380920 Sr-92 1.26030E-02 3.07660E-02 380920 + 293 380930 Sr-93 2.24780E-02 3.76830E-02 380930 + 294 380940 Sr-94 3.29970E-02 3.96760E-02 380940 + 295 380950 Sr-95 2.86990E-02 3.20220E-02 380950 + 296 380960 Sr-96 2.04100E-02 2.11420E-02 380960 + 297 380970 Sr-97 8.44700E-03 8.58860E-03 380970 + 298 380980 Sr-98 2.96700E-03 2.98410E-03 380980 + 299 380990 Sr-99 6.62550E-04 6.65730E-04 380990 + 300 381000 Sr-100 1.31590E-04 1.31590E-04 381000 + 301 381010 Sr-101 8.73090E-06 8.73090E-06 381010 + 302 381020 Sr-102 2.03980E-08 2.03980E-08 381020 + 303 390890 Y-89 1.73830E-07 1.71220E-02 39089.82c + 304 390891 Y-89m 7.51780E-07 2.40210E-06 390891 + 305 390900 Y-90 7.70370E-07 2.07700E-02 39090.82c + 306 390901 Y-90m 1.09310E-06 1.09310E-06 390901 + 307 390910 Y-91 5.50440E-06 2.43080E-02 39091.82c + 308 390911 Y-91m 2.38060E-05 1.43080E-02 390911 + 309 390920 Y-92 1.90000E-04 3.09560E-02 390920 + 310 390930 Y-93 2.16240E-04 3.93140E-02 390930 + 311 390931 Y-93m 1.41460E-03 1.08440E-02 390931 + 312 390940 Y-94 4.55440E-03 4.42300E-02 390940 + 313 390950 Y-95 1.50670E-02 4.70890E-02 390950 + 314 390960 Y-96 7.55220E-03 2.86960E-02 390960 + 315 390961 Y-96m 1.35850E-02 1.35870E-02 390961 + 316 390970 Y-97 5.42700E-03 1.29000E-02 390970 + 317 390971 Y-97m 1.84980E-02 2.37510E-02 390971 + 318 390972 Y-97m 4.97050E-03 4.97050E-03 390972 + 319 390980 Y-98 3.66260E-03 6.64670E-03 390980 + 320 390981 Y-98m 1.54030E-02 1.54030E-02 390981 + 321 390990 Y-99 1.43360E-02 1.50030E-02 390990 + 322 391000 Y-100 2.44190E-03 2.57250E-03 391000 + 323 391001 Y-100m 2.44190E-03 2.44200E-03 391001 + 324 391010 Y-101 1.63210E-03 1.64060E-03 391010 + 325 391020 Y-102 1.40650E-04 1.40660E-04 391020 + 326 391021 Y-102m 1.40650E-04 1.40660E-04 391021 + 327 391030 Y-103 4.66660E-05 4.66660E-05 391030 + 328 391040 Y-104 6.80470E-06 6.80470E-06 391040 + 329 391050 Y-105 1.85100E-09 1.85100E-09 391050 + 330 400910 Zr-91 6.75080E-10 2.43080E-02 40091.82c + 331 400920 Zr-92 6.19870E-06 3.09620E-02 40092.82c + 332 400930 Zr-93 3.86470E-05 3.93520E-02 40093.82c + 333 400940 Zr-94 3.74530E-04 4.46050E-02 40094.82c + 334 400950 Zr-95 1.71610E-03 4.88050E-02 40095.82c + 335 400960 Zr-96 7.62080E-03 4.99230E-02 40096.82c + 336 400970 Zr-97 1.52670E-02 5.32750E-02 400970 + 337 400980 Zr-98 3.04780E-02 5.22350E-02 400980 + 338 400990 Zr-99 3.78150E-02 5.25860E-02 400990 + 339 401000 Zr-100 4.21740E-02 4.71650E-02 401000 + 340 401010 Zr-101 2.46610E-02 2.63150E-02 401010 + 341 401020 Zr-102 1.40400E-02 1.43110E-02 401020 + 342 401030 Zr-103 3.70980E-03 3.75330E-03 401030 + 343 401040 Zr-104 1.09290E-03 1.09910E-03 401040 + 344 401050 Zr-105 1.17750E-04 1.17750E-04 401050 + 345 401060 Zr-106 1.67430E-05 1.67430E-05 401060 + 346 401070 Zr-107 7.72830E-09 7.72830E-09 401070 + 347 410940 Nb-94 6.05080E-09 1.02940E-08 41094.82c + 348 410941 Nb-94m 4.26420E-09 4.26420E-09 410941 + 349 410950 Nb-95 3.94150E-06 4.87810E-02 41095.82c + 350 410951 Nb-95m 9.11380E-07 5.28180E-04 410951 + 351 410960 Nb-96 5.86350E-05 5.86350E-05 410960 + 352 410970 Nb-97 4.31850E-04 5.38070E-02 410970 + 353 410971 Nb-97m 9.98550E-05 5.07370E-02 410971 + 354 410980 Nb-98 4.68680E-04 5.27040E-02 410980 + 355 410981 Nb-98m 1.41430E-03 1.41430E-03 410981 + 356 410990 Nb-99 6.75500E-03 4.04080E-02 410990 + 357 410991 Nb-99m 1.56190E-03 2.09140E-02 410991 + 358 411000 Nb-100 2.89050E-03 5.00550E-02 411000 + 359 411001 Nb-100m 1.21570E-02 1.21570E-02 411001 + 360 411010 Nb-101 2.94560E-02 5.57710E-02 411010 + 361 411020 Nb-102 1.51210E-02 2.94320E-02 411020 + 362 411021 Nb-102m 1.51210E-02 1.51210E-02 411021 + 363 411030 Nb-103 3.01340E-02 3.38870E-02 411030 + 364 411040 Nb-104 7.47750E-03 8.57830E-03 411040 + 365 411041 Nb-104m 7.47750E-03 7.47750E-03 411041 + 366 411050 Nb-105 7.14010E-03 7.25650E-03 411050 + 367 411060 Nb-106 1.44820E-03 1.46470E-03 411060 + 368 411070 Nb-107 2.97940E-04 2.97950E-04 411070 + 369 411080 Nb-108 2.15430E-05 2.15430E-05 411080 + 370 411090 Nb-109 3.01210E-06 3.01210E-06 411090 + 371 411100 Nb-110 1.49450E-10 1.49450E-10 411100 + 372 420960 Mo-96 1.89200E-06 6.05270E-05 42096.82c + 373 420970 Mo-97 7.36900E-06 5.38140E-02 42097.82c + 374 420980 Mo-98 7.10100E-05 5.41890E-02 42098.82c + 375 420990 Mo-99 5.06680E-04 6.14100E-02 42099.82c + 376 421000 Mo-100 2.77160E-03 6.49830E-02 42100.82c + 377 421010 Mo-101 7.55410E-03 6.33260E-02 421010 + 378 421020 Mo-102 2.17810E-02 6.63330E-02 421020 + 379 421030 Mo-103 3.17310E-02 6.56270E-02 421030 + 380 421040 Mo-104 4.29160E-02 5.90860E-02 421040 + 381 421050 Mo-105 2.95270E-02 3.67260E-02 421050 + 382 421060 Mo-106 1.83450E-02 1.97620E-02 421060 + 383 421070 Mo-107 5.75130E-03 6.03270E-03 421070 + 384 421080 Mo-108 1.74230E-03 1.76290E-03 421080 + 385 421090 Mo-109 2.87940E-04 2.90570E-04 421090 + 386 421100 Mo-110 3.78270E-05 3.78270E-05 421100 + 387 421110 Mo-111 2.09410E-06 2.09410E-06 421110 + 388 421120 Mo-112 4.68440E-10 4.68440E-10 421120 + 389 430990 Tc-99 1.44550E-08 6.14080E-02 43099.82c + 390 430991 Tc-99m 3.34250E-09 5.40780E-02 430991 + 391 431000 Tc-100 1.79860E-05 1.79860E-05 431000 + 392 431010 Tc-101 9.90080E-05 6.34240E-02 431010 + 393 431020 Tc-102 2.95780E-04 6.66290E-02 431020 + 394 431021 Tc-102m 2.95780E-04 2.95780E-04 431021 + 395 431030 Tc-103 3.02450E-03 6.86520E-02 431030 + 396 431040 Tc-104 7.33420E-03 6.64200E-02 431040 + 397 431050 Tc-105 1.77920E-02 5.45180E-02 431050 + 398 431060 Tc-106 1.83650E-02 3.81270E-02 431060 + 399 431070 Tc-107 1.67220E-02 2.27550E-02 431070 + 400 431080 Tc-108 8.15770E-03 9.92210E-03 431080 + 401 431090 Tc-109 3.88810E-03 4.17710E-03 431090 + 402 431100 Tc-110 1.18030E-03 1.21820E-03 431100 + 403 431110 Tc-111 2.64060E-04 2.66130E-04 431110 + 404 431120 Tc-112 3.83570E-05 3.83570E-05 431120 + 405 431130 Tc-113 2.45180E-05 2.45180E-05 431130 + 406 431140 Tc-114 6.02360E-06 6.02360E-06 431140 + 407 431150 Tc-115 2.40640E-06 2.40640E-06 431150 + 408 441010 Ru-101 2.91040E-06 6.34270E-02 44101.82c + 409 441020 Ru-102 9.25940E-06 6.69340E-02 44102.82c + 410 441030 Ru-103 1.68650E-05 6.87090E-02 44103.82c + 411 441031 Ru-103m 4.07150E-05 4.07150E-05 441031 + 412 441040 Ru-104 5.37070E-04 6.69580E-02 44104.82c + 413 441050 Ru-105 1.83120E-03 5.63490E-02 44105.82c + 414 441060 Ru-106 5.27730E-03 4.34040E-02 44106.82c + 415 441070 Ru-107 7.03210E-03 2.97870E-02 441070 + 416 441080 Ru-108 8.94350E-03 1.88690E-02 441080 + 417 441090 Ru-109 5.65670E-03 9.83100E-03 441090 + 418 441100 Ru-110 3.50750E-03 4.72520E-03 441100 + 419 441110 Ru-111 1.23370E-03 1.50040E-03 441110 + 420 441120 Ru-112 4.36080E-04 4.75620E-04 441120 + 421 441130 Ru-113 6.96150E-05 1.27570E-04 441130 + 422 441131 Ru-113m 6.96150E-05 6.96150E-05 441131 + 423 441140 Ru-114 4.80450E-05 5.40200E-05 441140 + 424 441150 Ru-115 4.81230E-06 6.87370E-06 441150 + 425 441160 Ru-116 3.04480E-06 3.04480E-06 441160 + 426 441170 Ru-117 1.39680E-10 1.39680E-10 441170 + 427 451040 Rh-104 2.82330E-07 1.13320E-06 451040 + 428 451041 Rh-104m 8.51970E-07 8.51970E-07 451041 + 429 451050 Rh-105 9.49280E-06 5.63600E-02 45105.82c + 430 451051 Rh-105m 1.45120E-06 1.59980E-02 451051 + 431 451060 Rh-106 2.16870E-05 4.34260E-02 451060 + 432 451061 Rh-106m 5.07970E-05 5.07970E-05 451061 + 433 451070 Rh-107 2.84720E-04 3.00720E-02 451070 + 434 451080 Rh-108 1.51330E-04 1.90200E-02 451080 + 435 451081 Rh-108m 4.56650E-04 4.56650E-04 451081 + 436 451090 Rh-109 1.19060E-03 1.10220E-02 451090 + 437 451100 Rh-110 1.26790E-03 5.99300E-03 451100 + 438 451101 Rh-110m 3.38440E-05 3.38440E-05 451101 + 439 451110 Rh-111 1.21850E-03 2.71890E-03 451110 + 440 451120 Rh-112 2.99090E-04 7.74720E-04 451120 + 441 451121 Rh-112m 2.99090E-04 2.99090E-04 451121 + 442 451130 Rh-113 4.60770E-04 6.23150E-04 451130 + 443 451140 Rh-114 1.03710E-04 1.57750E-04 451140 + 444 451141 Rh-114m 1.03710E-04 1.03710E-04 451141 + 445 451150 Rh-115 9.19980E-05 9.88890E-05 451150 + 446 451160 Rh-116 1.09620E-05 1.39740E-05 451160 + 447 451161 Rh-116m 2.56750E-05 2.56750E-05 451161 + 448 451170 Rh-117 1.44240E-05 1.44240E-05 451170 + 449 451180 Rh-118 2.47700E-08 2.47700E-08 451180 + 450 451190 Rh-119 1.16970E-09 1.16970E-09 451190 + 451 451200 Rh-120 9.71440E-12 9.71440E-12 451200 + 452 451210 Rh-121 1.67420E-07 1.67420E-07 451210 + 453 451220 Rh-122 9.30670E-09 9.30670E-09 451220 + 454 461060 Pd-106 1.69170E-09 4.34760E-02 46106.82c + 455 461070 Pd-107 1.13650E-06 3.00750E-02 46107.82c + 456 461071 Pd-107m 2.13590E-06 2.13590E-06 461071 + 457 461080 Pd-108 2.15710E-05 1.94980E-02 46108.82c + 458 461090 Pd-109 1.25700E-05 1.10580E-02 461090 + 459 461091 Pd-109m 2.36220E-05 5.53440E-03 461091 + 460 461100 Pd-110 1.12830E-04 6.13970E-03 46110.82c + 461 461110 Pd-111 3.55980E-05 2.80040E-03 461110 + 462 461111 Pd-111m 6.69020E-05 7.77770E-05 461111 + 463 461120 Pd-112 1.78380E-04 1.25220E-03 461120 + 464 461130 Pd-113 5.19080E-05 8.00370E-04 461130 + 465 461131 Pd-113m 1.25310E-04 1.25310E-04 461131 + 466 461140 Pd-114 2.55000E-04 5.16460E-04 461140 + 467 461150 Pd-115 7.47770E-05 1.71700E-04 461150 + 468 461151 Pd-115m 1.40530E-04 1.54890E-04 461151 + 469 461160 Pd-116 2.60320E-04 2.99970E-04 461160 + 470 461170 Pd-117 5.22960E-05 1.65000E-04 461170 + 471 461171 Pd-117m 9.82840E-05 9.82840E-05 461171 + 472 461180 Pd-118 9.32340E-05 9.32580E-05 461180 + 473 461190 Pd-119 2.78320E-05 2.78330E-05 461190 + 474 461200 Pd-120 1.43160E-05 1.43390E-05 461200 + 475 461210 Pd-121 2.88820E-05 2.90270E-05 461210 + 476 461220 Pd-122 1.17290E-05 1.17380E-05 461220 + 477 461230 Pd-123 5.82500E-07 5.82500E-07 461230 + 478 461240 Pd-124 1.42170E-07 1.42170E-07 461240 + 479 471090 Ag-109 3.40950E-10 1.10580E-02 47109.82c + 480 471091 Ag-109m 2.23030E-09 1.10520E-02 471091 + 481 471100 Ag-110 3.14880E-07 3.24910E-07 471100 + 482 471101 Ag-110m 7.37520E-07 7.37520E-07 47510.82c + 483 471110 Ag-111 5.55500E-07 2.81160E-03 47111.82c + 484 471111 Ag-111m 3.63380E-06 2.79920E-03 471111 + 485 471120 Ag-112 3.02900E-06 1.25520E-03 471120 + 486 471130 Ag-113 1.52110E-06 5.32350E-04 471130 + 487 471131 Ag-113m 9.94990E-06 7.76360E-04 471131 + 488 471140 Ag-114 4.63210E-06 5.40570E-04 471140 + 489 471141 Ag-114m 1.94810E-05 1.94810E-05 471141 + 490 471150 Ag-115 6.38730E-06 1.80160E-04 471150 + 491 471151 Ag-115m 4.17830E-05 2.30640E-04 471151 + 492 471160 Ag-116 4.11040E-05 3.46850E-04 471160 + 493 471161 Ag-116m 9.62760E-05 9.62760E-05 471161 + 494 471170 Ag-117 3.39970E-05 1.34790E-04 471170 + 495 471171 Ag-117m 2.22390E-04 3.04900E-04 471171 + 496 471180 Ag-118 4.74540E-05 2.14670E-04 471180 + 497 471181 Ag-118m 1.99580E-04 2.12910E-04 471181 + 498 471190 Ag-119 2.99280E-05 4.38440E-05 471190 + 499 471191 Ag-119m 1.95770E-04 2.09690E-04 471191 + 500 471200 Ag-120 3.39960E-05 6.17450E-05 471200 + 501 471201 Ag-120m 4.82390E-05 5.54080E-05 471201 + 502 471210 Ag-121 9.17310E-05 1.20680E-04 471210 + 503 471220 Ag-122 3.07380E-05 4.24770E-05 471220 + 504 471221 Ag-122m 2.76890E-05 2.76890E-05 471221 + 505 471230 Ag-123 3.13870E-05 3.19690E-05 471230 + 506 471240 Ag-124 5.48670E-06 8.10000E-06 471240 + 507 471241 Ag-124m 4.94230E-06 4.94230E-06 471241 + 508 471250 Ag-125 5.67150E-06 5.67150E-06 471250 + 509 471260 Ag-126 9.21550E-07 9.21550E-07 471260 + 510 471270 Ag-127 1.01250E-07 1.01250E-07 471270 + 511 471280 Ag-128 3.33360E-09 3.33360E-09 471280 + 512 481110 Cd-111 1.83340E-11 2.82560E-03 48111.82c + 513 481111 Cd-111m 5.99840E-11 5.99840E-11 481111 + 514 481120 Cd-112 2.34220E-09 1.25520E-03 48112.82c + 515 481130 Cd-113 8.31240E-09 8.02660E-04 48113.82c + 516 481131 Cd-113m 2.71960E-08 9.23090E-06 481131 + 517 481140 Cd-114 5.88640E-07 5.41160E-04 48114.82c + 518 481150 Cd-115 5.63530E-07 3.47250E-04 481150 + 519 481151 Cd-115m 1.84370E-06 1.75300E-05 48515.82c + 520 481160 Cd-116 2.13450E-05 4.58690E-04 48116.82c + 521 481170 Cd-117 8.44980E-06 3.36030E-04 481170 + 522 481171 Cd-117m 2.76450E-05 1.21460E-04 481171 + 523 481180 Cd-118 1.16610E-04 4.56900E-04 481180 + 524 481190 Cd-119 6.36500E-05 2.95260E-04 481190 + 525 481191 Cd-119m 1.53660E-04 1.75580E-04 481191 + 526 481200 Cd-120 2.80990E-04 3.77640E-04 481200 + 527 481210 Cd-121 6.87670E-05 1.76840E-04 481210 + 528 481211 Cd-121m 1.66010E-04 1.78620E-04 481211 + 529 481220 Cd-122 3.72580E-04 4.42740E-04 481220 + 530 481230 Cd-123 5.33810E-05 7.95410E-05 481230 + 531 481231 Cd-123m 1.28870E-04 1.34690E-04 481231 + 532 481240 Cd-124 5.30580E-04 5.41140E-04 481240 + 533 481250 Cd-125 5.44320E-05 5.72680E-05 481250 + 534 481251 Cd-125m 1.31410E-04 1.34240E-04 481251 + 535 481260 Cd-126 1.83550E-04 1.84470E-04 481260 + 536 481270 Cd-127 8.40020E-05 8.41030E-05 481270 + 537 481280 Cd-128 3.08820E-05 3.08850E-05 481280 + 538 481290 Cd-129 2.79800E-06 2.79800E-06 481290 + 539 481291 Cd-129m 6.75480E-06 6.75480E-06 481291 + 540 481300 Cd-130 1.07970E-07 1.07970E-07 481300 + 541 481310 Cd-131 2.05790E-09 2.05790E-09 481310 + 542 491140 In-114 2.22010E-11 8.68430E-11 491140 + 543 491141 In-114m 3.40290E-11 6.69870E-11 491141 + 544 491142 In-114m 3.29580E-11 3.29580E-11 491142 + 545 491150 In-115 2.73900E-09 3.47420E-04 49115.82c + 546 491151 In-115m 6.33320E-10 3.47250E-04 491151 + 547 491160 In-116 1.88830E-08 1.88830E-08 491160 + 548 491161 In-116m 2.89430E-08 5.69750E-08 491161 + 549 491162 In-116m 2.80320E-08 2.80320E-08 491162 + 550 491170 In-117 1.15620E-06 2.94890E-04 491170 + 551 491171 In-117m 2.67330E-07 3.10070E-04 491171 + 552 491180 In-118 9.31810E-07 4.57830E-04 491180 + 553 491181 In-118m 1.42820E-06 2.79220E-06 491181 + 554 491182 In-118m 1.38330E-06 1.38330E-06 491182 + 555 491190 In-119 8.48500E-06 2.27450E-04 491190 + 556 491191 In-119m 1.96190E-06 2.68900E-04 491191 + 557 491200 In-120 1.19080E-05 3.89550E-04 491200 + 558 491201 In-120m 1.19080E-05 1.19080E-05 491201 + 559 491202 In-120m 1.19080E-05 1.19080E-05 491202 + 560 491210 In-121 6.62350E-05 3.06010E-04 491210 + 561 491211 In-121m 1.53150E-05 1.32590E-04 491211 + 562 491220 In-122 8.58590E-05 5.28600E-04 491220 + 563 491221 In-122m 6.09160E-05 6.09160E-05 491221 + 564 491222 In-122m 6.09160E-05 6.09160E-05 491222 + 565 491230 In-123 1.46830E-04 3.04510E-04 491230 + 566 491231 In-123m 3.39500E-05 9.04980E-05 491231 + 567 491240 In-124 2.74300E-04 8.15440E-04 491240 + 568 491241 In-124m 2.47080E-04 2.47080E-04 491241 + 569 491250 In-125 4.97960E-04 6.59610E-04 491250 + 570 491251 In-125m 1.15140E-04 1.45000E-04 491251 + 571 491260 In-126 6.05540E-04 7.90010E-04 491260 + 572 491261 In-126m 5.45460E-04 5.45460E-04 491261 + 573 491270 In-127 1.16060E-03 1.16060E-03 491270 + 574 491271 In-127m 2.68370E-04 3.52470E-04 491271 + 575 491280 In-128 3.28960E-04 4.93750E-04 491280 + 576 491281 In-128m 1.33910E-04 1.64790E-04 491281 + 577 491282 In-128m 4.16940E-04 4.16940E-04 491282 + 578 491290 In-129 5.39370E-04 5.46120E-04 491290 + 579 491291 In-129m 1.24710E-04 1.27510E-04 491291 + 580 491300 In-130 6.52870E-05 6.53910E-05 491300 + 581 491301 In-130m 7.29190E-05 7.29190E-05 491301 + 582 491302 In-130m 1.24070E-04 1.24070E-04 491302 + 583 491310 In-131 1.81200E-05 1.83070E-05 491310 + 584 491311 In-131m 1.81200E-05 1.81200E-05 491311 + 585 491312 In-131m 1.81200E-05 1.81200E-05 491312 + 586 491320 In-132 1.09550E-06 1.09550E-06 491320 + 587 491330 In-133 2.77650E-08 3.41850E-08 491330 + 588 491331 In-133m 6.41990E-09 6.41990E-09 491331 + 589 501160 Sn-116 1.73230E-11 7.58760E-08 50116.82c + 590 501170 Sn-117 1.33770E-10 4.58910E-04 50117.82c + 591 501171 Sn-117m 4.37640E-10 1.00520E-06 501171 + 592 501180 Sn-118 2.53470E-08 4.60670E-04 50118.82c + 593 501190 Sn-119 8.43880E-08 4.81650E-04 50119.82c + 594 501191 Sn-119m 2.76090E-07 2.05760E-04 501191 + 595 501200 Sn-120 4.45530E-06 4.17820E-04 50120.82c + 596 501210 Sn-121 1.85850E-06 4.34580E-04 501210 + 597 501211 Sn-121m 4.48660E-06 3.91520E-05 501211 + 598 501220 Sn-122 4.10490E-05 6.91480E-04 50122.82c + 599 501230 Sn-123 2.24900E-05 4.57060E-05 50123.82c + 600 501231 Sn-123m 9.31600E-06 3.81110E-04 501231 + 601 501240 Sn-124 1.97540E-04 1.26010E-03 50124.82c + 602 501250 Sn-125 1.95040E-04 3.06460E-04 50125.82c + 603 501251 Sn-125m 8.07910E-05 7.73980E-04 501251 + 604 501260 Sn-126 1.58040E-03 2.91830E-03 50126.82c + 605 501270 Sn-127 2.41010E-03 2.86250E-03 501270 + 606 501271 Sn-127m 9.98320E-04 2.05660E-03 501271 + 607 501280 Sn-128 2.07550E-03 7.84770E-03 501280 + 608 501281 Sn-128m 4.86140E-03 5.27840E-03 501281 + 609 501290 Sn-129 2.33170E-03 2.94730E-03 501290 + 610 501291 Sn-129m 5.62890E-03 5.68710E-03 501291 + 611 501300 Sn-130 2.47910E-03 2.64990E-03 501300 + 612 501301 Sn-130m 5.80680E-03 5.89880E-03 501301 + 613 501310 Sn-131 1.22980E-03 1.26490E-03 501310 + 614 501311 Sn-131m 2.96890E-03 2.98780E-03 501311 + 615 501320 Sn-132 1.63610E-03 1.63720E-03 501320 + 616 501330 Sn-133 1.43190E-04 1.43190E-04 501330 + 617 501340 Sn-134 1.21350E-05 1.21350E-05 501340 + 618 501350 Sn-135 2.24550E-07 2.24550E-07 501350 + 619 501360 Sn-136 5.14750E-09 5.14750E-09 501360 + 620 511190 Sb-119 7.00720E-11 9.23460E-11 511190 + 621 511191 Sb-119m 2.22740E-11 2.22740E-11 511191 + 622 511200 Sb-120 1.05620E-09 1.05620E-09 511200 + 623 511201 Sb-120m 1.49870E-09 1.49870E-09 511201 + 624 511220 Sb-122 7.49500E-12 1.59910E-11 511220 + 625 511221 Sb-122m 8.49600E-12 8.49600E-12 511221 + 626 511230 Sb-123 2.09500E-06 4.28910E-04 51123.82c + 627 511240 Sb-124 2.48610E-06 5.84010E-06 51124.82c + 628 511241 Sb-124m 1.90090E-06 4.47200E-06 511241 + 629 511242 Sb-124m 2.57100E-06 2.57100E-06 511242 + 630 511250 Sb-125 2.41670E-05 1.10460E-03 51125.82c + 631 511260 Sb-126 2.77630E-05 3.43950E-05 51126.82c + 632 511261 Sb-126m 2.05270E-05 4.73730E-05 511261 + 633 511262 Sb-126m 2.68460E-05 2.68460E-05 511262 + 634 511270 Sb-127 4.57000E-04 5.37610E-03 511270 + 635 511280 Sb-128 5.21290E-04 8.40100E-03 511280 + 636 511281 Sb-128m 8.89510E-04 8.89510E-04 511281 + 637 511290 Sb-129 4.62580E-03 1.12670E-02 511290 + 638 511291 Sb-129m 2.82670E-03 5.67020E-03 511291 + 639 511300 Sb-130 7.22300E-03 1.28220E-02 511300 + 640 511301 Sb-130m 7.22300E-03 1.01720E-02 511301 + 641 511310 Sb-131 2.18640E-02 2.61170E-02 511310 + 642 511320 Sb-132 9.56930E-03 1.12060E-02 511320 + 643 511321 Sb-132m 7.05270E-03 7.05270E-03 511321 + 644 511330 Sb-133 1.21390E-02 1.22840E-02 511330 + 645 511340 Sb-134 7.17870E-04 7.27970E-04 511340 + 646 511341 Sb-134m 1.68140E-03 1.68140E-03 511341 + 647 511350 Sb-135 5.47320E-04 5.47500E-04 511350 + 648 511360 Sb-136 5.64480E-05 5.64520E-05 511360 + 649 511370 Sb-137 4.62720E-06 4.62720E-06 511370 + 650 511380 Sb-138 2.41810E-08 2.41810E-08 511380 + 651 521250 Te-125 3.31980E-07 1.10600E-03 52125.82c + 652 521251 Te-125m 1.08610E-06 2.48260E-04 521251 + 653 521260 Te-126 1.52470E-06 7.66610E-05 52126.82c + 654 521270 Te-127 1.78350E-06 5.36080E-03 521270 + 655 521271 Te-127m 4.30550E-06 8.90250E-04 52527.82c + 656 521280 Te-128 8.82410E-05 9.34670E-03 52128.82c + 657 521290 Te-129 1.66740E-04 1.40740E-02 521290 + 658 521291 Te-129m 4.02520E-04 6.97910E-03 52529.82c + 659 521300 Te-130 4.20800E-03 2.72030E-02 52130.82c + 660 521310 Te-131 3.31940E-03 2.94670E-02 521310 + 661 521311 Te-131m 8.01360E-03 1.01050E-02 521311 + 662 521320 Te-132 3.15440E-02 4.98030E-02 52132.82c + 663 521330 Te-133 1.38670E-02 3.02590E-02 521330 + 664 521331 Te-133m 3.34770E-02 3.56020E-02 521331 + 665 521340 Te-134 4.39300E-02 4.64240E-02 521340 + 666 521350 Te-135 1.70330E-02 1.75040E-02 521350 + 667 521360 Te-136 5.64680E-03 5.69620E-03 521360 + 668 521370 Te-137 1.11790E-03 1.12030E-03 521370 + 669 521380 Te-138 1.94780E-04 1.94800E-04 521380 + 670 521390 Te-139 1.59460E-05 1.59460E-05 521390 + 671 521400 Te-140 2.33490E-07 2.33490E-07 521400 + 672 521410 Te-141 2.93180E-09 2.93180E-09 521410 + 673 531270 I-127 1.67910E-10 5.38220E-03 53127.82c + 674 531280 I-128 6.45870E-09 6.45870E-09 531280 + 675 531290 I-129 4.24790E-06 1.66600E-02 53129.82c + 676 531300 I-130 2.24260E-05 3.04680E-05 53130.82c + 677 531301 I-130m 9.57440E-06 9.57440E-06 531301 + 678 531310 I-131 3.22120E-04 3.77720E-02 53131.82c + 679 531320 I-132 8.62690E-04 5.12130E-02 531320 + 680 531321 I-132m 6.35810E-04 6.35810E-04 531321 + 681 531330 I-133 5.31530E-03 6.81930E-02 531330 + 682 531331 I-133m 3.24810E-03 3.24810E-03 531331 + 683 531340 I-134 1.10810E-02 6.54840E-02 531340 + 684 531341 I-134m 8.16690E-03 8.16690E-03 531341 + 685 531350 I-135 4.80370E-02 6.55410E-02 53135.82c + 686 531360 I-136 9.33830E-03 1.50510E-02 531360 + 687 531361 I-136m 2.18730E-02 2.18890E-02 531361 + 688 531370 I-137 2.13330E-02 2.24320E-02 531370 + 689 531380 I-138 5.79460E-03 5.97710E-03 531380 + 690 531390 I-139 2.93140E-03 2.94740E-03 531390 + 691 531400 I-140 4.76530E-04 4.76760E-04 531400 + 692 531410 I-141 7.99140E-05 7.99170E-05 531410 + 693 531420 I-142 4.70810E-06 4.70810E-06 531420 + 694 531430 I-143 1.00710E-06 1.00710E-06 531430 + 695 541300 Xe-130 4.03630E-09 3.20040E-05 54130.82c + 696 541310 Xe-131 5.78620E-08 3.77720E-02 54131.82c + 697 541311 Xe-131m 1.39690E-07 4.10410E-04 541311 + 698 541320 Xe-132 1.43810E-05 5.13320E-02 54132.82c + 699 541321 Xe-132m 1.63010E-05 1.63010E-05 541321 + 700 541330 Xe-133 7.23700E-05 6.84400E-02 54133.82c + 701 541331 Xe-133m 1.74710E-04 2.11580E-03 541331 + 702 541340 Xe-134 5.28570E-04 6.74390E-02 54134.82c + 703 541341 Xe-134m 1.23800E-03 1.42590E-03 541341 + 704 541350 Xe-135 2.54210E-03 7.41180E-02 54135.82c + 705 541351 Xe-135m 6.13690E-03 1.69570E-02 541351 + 706 541360 Xe-136 3.07600E-02 6.91590E-02 54136.82c + 707 541370 Xe-137 3.97650E-02 6.10560E-02 541370 + 708 541380 Xe-138 4.33990E-02 4.93480E-02 541380 + 709 541390 Xe-139 2.83570E-02 3.10600E-02 541390 + 710 541400 Xe-140 1.83130E-02 1.87620E-02 541400 + 711 541410 Xe-141 5.93520E-03 5.99950E-03 541410 + 712 541420 Xe-142 1.58550E-03 1.58940E-03 541420 + 713 541430 Xe-143 2.53740E-04 2.54340E-04 541430 + 714 541440 Xe-144 2.96930E-05 2.96930E-05 541440 + 715 541450 Xe-145 7.65450E-06 7.65450E-06 541450 + 716 541460 Xe-146 1.89420E-09 1.89420E-09 541460 + 717 551330 Cs-133 6.40970E-08 6.84400E-02 55133.82c + 718 551340 Cs-134 3.22520E-06 5.60230E-06 55134.82c + 719 551341 Cs-134m 2.37710E-06 2.37710E-06 551341 + 720 551350 Cs-135 3.86310E-05 7.42820E-02 55135.82c + 721 551351 Cs-135m 2.36070E-05 2.36070E-05 551351 + 722 551360 Cs-136 3.06400E-04 3.96180E-04 55136.82c + 723 551361 Cs-136m 1.79560E-04 1.79560E-04 551361 + 724 551370 Cs-137 4.74000E-03 6.57960E-02 55137.82c + 725 551380 Cs-138 4.29320E-03 5.85760E-02 551380 + 726 551381 Cs-138m 6.09180E-03 6.09180E-03 551381 + 727 551390 Cs-139 2.29940E-02 5.40540E-02 551390 + 728 551400 Cs-140 2.17580E-02 4.05230E-02 551400 + 729 551410 Cs-141 2.75110E-02 3.35140E-02 551410 + 730 551420 Cs-142 1.40060E-02 1.55920E-02 551420 + 731 551430 Cs-143 7.35960E-03 7.61230E-03 551430 + 732 551440 Cs-144 9.93300E-04 1.51900E-03 551440 + 733 551441 Cs-144m 9.93300E-04 9.93490E-04 551441 + 734 551450 Cs-145 4.27360E-04 4.34630E-04 551450 + 735 551460 Cs-146 3.89100E-05 3.89120E-05 551460 + 736 551470 Cs-147 1.77560E-06 1.77560E-06 551470 + 737 551480 Cs-148 7.59650E-09 7.59650E-09 551480 + 738 561350 Ba-135 2.37020E-09 8.09200E-09 56135.82c + 739 561351 Ba-135m 5.72190E-09 5.72190E-09 561351 + 740 561360 Ba-136 7.79770E-07 4.88570E-04 56136.82c + 741 561361 Ba-136m 1.82640E-06 1.82640E-06 561361 + 742 561370 Ba-137 2.14120E-05 6.58690E-02 56137.82c + 743 561371 Ba-137m 5.16920E-05 6.21630E-02 561371 + 744 561380 Ba-138 9.42050E-04 6.06750E-02 56138.82c + 745 561390 Ba-139 3.91340E-03 5.79670E-02 561390 + 746 561400 Ba-140 1.23570E-02 5.28800E-02 56140.82c + 747 561410 Ba-141 1.77140E-02 5.12280E-02 561410 + 748 561420 Ba-142 3.22990E-02 4.80160E-02 561420 + 749 561430 Ba-143 2.95770E-02 3.71130E-02 561430 + 750 561440 Ba-144 2.26850E-02 2.47140E-02 561440 + 751 561450 Ba-145 9.48400E-03 9.86200E-03 561450 + 752 561460 Ba-146 3.86750E-03 3.90140E-03 561460 + 753 561470 Ba-147 9.78250E-04 9.79520E-04 561470 + 754 561480 Ba-148 1.83260E-04 1.83270E-04 561480 + 755 561490 Ba-149 4.38550E-05 4.38550E-05 561490 + 756 561500 Ba-150 9.75300E-07 9.75300E-07 561500 + 757 561510 Ba-151 6.60820E-10 6.60820E-10 561510 + 758 571370 La-137 9.25470E-07 9.25470E-07 571370 + 759 571380 La-138 8.97140E-07 8.97140E-07 57138.82c + 760 571390 La-139 1.27580E-05 5.79800E-02 57139.82c + 761 571400 La-140 1.09260E-04 5.29890E-02 57140.82c + 762 571410 La-141 7.07330E-04 5.19350E-02 571410 + 763 571420 La-142 1.57200E-03 4.95880E-02 571420 + 764 571430 La-143 7.05760E-03 4.41710E-02 571430 + 765 571440 La-144 1.10460E-02 3.57600E-02 571440 + 766 571450 La-145 1.61600E-02 2.60220E-02 571450 + 767 571460 La-146 3.67630E-03 7.57770E-03 571460 + 768 571461 La-146m 6.61270E-03 6.61270E-03 571461 + 769 571470 La-147 7.18220E-03 8.16240E-03 571470 + 770 571480 La-148 2.84440E-03 3.02710E-03 571480 + 771 571490 La-149 1.07400E-03 1.11770E-03 571490 + 772 571500 La-150 1.93160E-04 1.94140E-04 571500 + 773 571510 La-151 3.33640E-05 3.33650E-05 571510 + 774 571520 La-152 1.10030E-06 1.10030E-06 571520 + 775 571530 La-153 1.68820E-06 1.68820E-06 571530 + 776 581400 Ce-140 2.09880E-06 5.29910E-02 58140.82c + 777 581410 Ce-141 2.13020E-06 5.19370E-02 58141.82c + 778 581420 Ce-142 7.07830E-05 4.96590E-02 58142.82c + 779 581430 Ce-143 3.31490E-04 4.45020E-02 58143.82c + 780 581440 Ce-144 1.86240E-03 3.76230E-02 58144.82c + 781 581450 Ce-145 4.42090E-03 3.04430E-02 581450 + 782 581460 Ce-146 1.09080E-02 2.50980E-02 581460 + 783 581470 Ce-147 1.17730E-02 1.99350E-02 581470 + 784 581480 Ce-148 1.21330E-02 1.51760E-02 581480 + 785 581490 Ce-149 7.24660E-03 8.35390E-03 581490 + 786 581500 Ce-150 4.02200E-03 4.21090E-03 581500 + 787 581510 Ce-151 1.33860E-03 1.37200E-03 581510 + 788 581520 Ce-152 3.79340E-04 3.80370E-04 581520 + 789 581530 Ce-153 9.56570E-05 9.73450E-05 581530 + 790 581540 Ce-154 3.88350E-06 3.88350E-06 581540 + 791 581550 Ce-155 6.91190E-09 6.91190E-09 581550 + 792 581560 Ce-156 1.25370E-10 1.25370E-10 581560 + 793 591430 Pr-143 1.00710E-06 4.45030E-02 59143.82c + 794 591440 Pr-144 1.93910E-07 3.76240E-02 591440 + 795 591441 Pr-144m 1.72220E-06 5.20890E-04 591441 + 796 591450 Pr-145 2.87570E-05 3.04720E-02 591450 + 797 591460 Pr-146 1.88350E-04 2.52870E-02 591460 + 798 591470 Pr-147 7.60500E-04 2.06960E-02 591470 + 799 591480 Pr-148 3.02230E-04 1.54780E-02 591480 + 800 591481 Pr-148m 1.27110E-03 1.27110E-03 591481 + 801 591490 Pr-149 3.83060E-03 1.21840E-02 591490 + 802 591500 Pr-150 4.10610E-03 8.31700E-03 591500 + 803 591510 Pr-151 3.87370E-03 5.24570E-03 591510 + 804 591520 Pr-152 1.89870E-03 2.27970E-03 591520 + 805 591530 Pr-153 1.28970E-03 1.38650E-03 591530 + 806 591540 Pr-154 2.62820E-04 2.66680E-04 591540 + 807 591550 Pr-155 4.71950E-05 4.72020E-05 591550 + 808 591560 Pr-156 2.59280E-06 2.59290E-06 591560 + 809 591570 Pr-157 1.89960E-08 1.89960E-08 591570 + 810 591580 Pr-158 3.23450E-10 3.23450E-10 591580 + 811 601450 Nd-145 3.44290E-09 3.04720E-02 60145.82c + 812 601460 Nd-146 1.85490E-06 2.52890E-02 60146.82c + 813 601470 Nd-147 1.77990E-05 2.07140E-02 60147.82c + 814 601480 Nd-148 1.01380E-04 1.68500E-02 60148.82c + 815 601490 Nd-149 3.99420E-04 1.25840E-02 601490 + 816 601500 Nd-150 1.43650E-03 9.75350E-03 60150.82c + 817 601510 Nd-151 2.56100E-03 7.80670E-03 601510 + 818 601520 Nd-152 3.72310E-03 6.00280E-03 601520 + 819 601530 Nd-153 3.78340E-03 5.16990E-03 601530 + 820 601540 Nd-154 1.77730E-03 2.04400E-03 601540 + 821 601550 Nd-155 7.29880E-04 7.77150E-04 601550 + 822 601560 Nd-156 2.12480E-04 2.15000E-04 601560 + 823 601570 Nd-157 7.94950E-05 7.95130E-05 601570 + 824 601580 Nd-158 1.03470E-05 1.03470E-05 601580 + 825 601590 Nd-159 2.24770E-08 2.24770E-08 601590 + 826 601600 Nd-160 6.64280E-10 6.64280E-10 601600 + 827 601610 Nd-161 4.05640E-12 4.05640E-12 601610 + 828 611480 Pm-148 3.11020E-09 3.47440E-09 61148.82c + 829 611481 Pm-148m 7.28480E-09 7.28480E-09 61548.82c + 830 611490 Pm-149 2.74840E-06 1.25870E-02 61149.82c + 831 611500 Pm-150 4.88450E-06 4.88450E-06 611500 + 832 611510 Pm-151 4.26360E-05 7.84940E-03 61151.82c + 833 611520 Pm-152 2.81790E-05 6.03100E-03 611520 + 834 611521 Pm-152m 5.62700E-05 5.62700E-05 611521 + 835 611522 Pm-152m 6.22410E-05 6.22410E-05 611522 + 836 611530 Pm-153 6.59090E-04 5.82900E-03 611530 + 837 611540 Pm-154 3.47800E-04 2.39180E-03 611540 + 838 611541 Pm-154m 3.47800E-04 3.47800E-04 611541 + 839 611550 Pm-155 8.87920E-04 1.66510E-03 611550 + 840 611560 Pm-156 4.84630E-04 6.99630E-04 611560 + 841 611570 Pm-157 3.11870E-04 3.91380E-04 611570 + 842 611580 Pm-158 1.52600E-04 1.62950E-04 611580 + 843 611590 Pm-159 2.66900E-05 2.67120E-05 611590 + 844 611600 Pm-160 2.69280E-06 2.69350E-06 611600 + 845 611610 Pm-161 2.51990E-08 2.52030E-08 611610 + 846 611620 Pm-162 4.94990E-10 4.94990E-10 611620 + 847 611630 Pm-163 1.00320E-11 1.00320E-11 611630 + 848 621500 Sm-150 1.14400E-09 4.88560E-06 62150.82c + 849 621510 Sm-151 3.61250E-08 7.84940E-03 62151.82c + 850 621520 Sm-152 4.40940E-06 6.15390E-03 62152.82c + 851 621530 Sm-153 1.95000E-05 5.89550E-03 62153.82c + 852 621531 Sm-153m 4.70750E-05 4.70750E-05 621531 + 853 621540 Sm-154 1.11980E-04 2.85160E-03 62154.82c + 854 621550 Sm-155 2.36030E-04 1.90110E-03 621550 + 855 621560 Sm-156 4.15610E-04 1.11520E-03 621560 + 856 621570 Sm-157 3.78440E-04 7.69820E-04 621570 + 857 621580 Sm-158 4.66340E-04 6.29290E-04 621580 + 858 621590 Sm-159 1.19840E-04 1.46560E-04 621590 + 859 621600 Sm-160 5.11310E-05 5.38170E-05 621600 + 860 621610 Sm-161 1.10260E-05 1.10510E-05 621610 + 861 621620 Sm-162 9.99340E-07 9.99840E-07 621620 + 862 621630 Sm-163 2.50500E-08 2.50600E-08 621630 + 863 621640 Sm-164 1.66170E-09 1.66170E-09 621640 + 864 621650 Sm-165 1.00920E-11 1.00920E-11 621650 + 865 631530 Eu-153 4.80260E-09 5.89550E-03 63153.82c + 866 631540 Eu-154 3.33740E-08 6.34370E-08 63154.82c + 867 631541 Eu-154m 3.00630E-08 3.00630E-08 631541 + 868 631550 Eu-155 2.80040E-06 1.90390E-03 63155.82c + 869 631560 Eu-156 3.89480E-06 1.11910E-03 63156.82c + 870 631570 Eu-157 2.56490E-05 7.95470E-04 63157.82c + 871 631580 Eu-158 5.81120E-05 6.87400E-04 631580 + 872 631590 Eu-159 6.18260E-05 2.08380E-04 631590 + 873 631600 Eu-160 6.06310E-05 1.14450E-04 631600 + 874 631610 Eu-161 2.20610E-05 3.31120E-05 631610 + 875 631620 Eu-162 9.99170E-06 1.09910E-05 631620 + 876 631630 Eu-163 1.98990E-06 2.01500E-06 631630 + 877 631640 Eu-164 9.50370E-07 9.52030E-07 631640 + 878 631650 Eu-165 1.62230E-08 1.62330E-08 631650 + 879 631660 Eu-166 4.85880E-10 4.85880E-10 631660 + 880 631670 Eu-167 1.54090E-11 1.54090E-11 631670 + 881 641550 Gd-155 4.67170E-11 1.90390E-03 64155.82c + 882 641551 Gd-155m 1.12780E-10 1.12780E-10 641551 + 883 641560 Gd-156 6.60250E-09 1.11910E-03 64156.82c + 884 641570 Gd-157 1.50480E-06 7.96980E-04 64157.82c + 885 641580 Gd-158 1.69380E-06 6.89100E-04 64158.82c + 886 641590 Gd-159 8.15120E-06 2.16530E-04 641590 + 887 641600 Gd-160 1.61690E-05 1.30620E-04 64160.82c + 888 641610 Gd-161 1.56380E-05 4.87500E-05 641610 + 889 641620 Gd-162 1.29940E-05 2.39850E-05 641620 + 890 641630 Gd-163 1.19410E-05 1.39560E-05 641630 + 891 641640 Gd-164 7.60290E-06 8.55490E-06 641640 + 892 641650 Gd-165 8.59690E-07 8.75920E-07 641650 + 893 641660 Gd-166 6.18850E-07 6.19340E-07 641660 + 894 641670 Gd-167 9.21020E-09 9.22560E-09 641670 + 895 641680 Gd-168 8.82020E-10 8.82020E-10 641680 + 896 641690 Gd-169 2.23190E-11 2.23190E-11 641690 + 897 651580 Tb-158 3.48870E-10 3.87910E-10 651580 + 898 651581 Tb-158m 3.92810E-11 3.92810E-11 651581 + 899 651590 Tb-159 5.99930E-09 2.16540E-04 65159.82c + 900 651600 Tb-160 5.44380E-08 5.44380E-08 65160.82c + 901 651610 Tb-161 3.21480E-07 4.90720E-05 651610 + 902 651620 Tb-162 2.99860E-06 2.69840E-05 651620 + 903 651630 Tb-163 9.95090E-07 1.49510E-05 651630 + 904 651640 Tb-164 2.85150E-06 1.14060E-05 651640 + 905 651650 Tb-165 1.71950E-06 2.59540E-06 651650 + 906 651660 Tb-166 6.17700E-07 1.23700E-06 651660 + 907 651670 Tb-167 5.97300E-07 6.06530E-07 651670 + 908 651680 Tb-168 4.91440E-08 5.00260E-08 651680 + 909 651690 Tb-169 8.82410E-09 8.84640E-09 651690 + 910 651700 Tb-170 4.73620E-10 4.73620E-10 651700 + 911 651710 Tb-171 2.47690E-11 2.47690E-11 651710 + 912 661600 Dy-160 1.47620E-11 5.44530E-08 66160.82c + 913 661610 Dy-161 2.05520E-10 4.90720E-05 66161.82c + 914 661620 Dy-162 4.19990E-09 2.69880E-05 66162.82c + 915 661630 Dy-163 2.64380E-08 1.49780E-05 66163.82c + 916 661640 Dy-164 2.43790E-07 1.16500E-05 66164.82c + 917 661650 Dy-165 1.83540E-07 2.80640E-06 661650 + 918 661651 Dy-165m 2.80580E-08 2.80580E-08 661651 + 919 661660 Dy-166 6.18890E-07 1.85590E-06 661660 + 920 661670 Dy-167 2.98350E-07 9.04880E-07 661670 + 921 661680 Dy-168 3.17620E-07 3.67650E-07 661680 + 922 661690 Dy-169 1.00500E-07 1.09350E-07 661690 + 923 661700 Dy-170 3.48070E-08 3.52810E-08 661700 + 924 661710 Dy-171 3.70120E-09 3.72600E-09 661710 + 925 661720 Dy-172 4.50210E-10 4.50210E-10 661720 + 926 661730 Dy-173 1.92630E-11 1.92630E-11 661730 + 927 671630 Ho-163 9.53010E-12 1.09870E-11 671630 + 928 671631 Ho-163m 1.45690E-12 1.45690E-12 671631 + 929 671640 Ho-164 6.72630E-11 2.24810E-10 671640 + 930 671641 Ho-164m 1.57550E-10 1.57550E-10 671641 + 931 671650 Ho-165 1.41630E-09 2.80840E-06 67165.82c + 932 671660 Ho-166 1.75790E-09 1.85770E-06 671660 + 933 671661 Ho-166m 4.11730E-09 4.11730E-09 671661 + 934 671670 Ho-167 2.61990E-08 9.31080E-07 671670 + 935 671680 Ho-168 2.03200E-08 4.16650E-07 671680 + 936 671681 Ho-168m 2.88330E-08 2.88330E-08 671681 + 937 671690 Ho-169 8.77490E-08 1.97100E-07 671690 + 938 671700 Ho-170 3.49070E-08 3.49070E-08 671700 + 939 671701 Ho-170m 1.49030E-08 5.01840E-08 671701 + 940 671710 Ho-171 3.06380E-08 3.43640E-08 671710 + 941 671720 Ho-172 6.81600E-09 7.26620E-09 671720 + 942 671730 Ho-173 1.94930E-09 1.96860E-09 671730 + 943 671740 Ho-174 1.59550E-10 1.59550E-10 671740 + 944 671750 Ho-175 1.58490E-11 1.58490E-11 671750 + 945 681660 Er-166 6.80740E-12 1.85770E-06 68166.82c + 946 681670 Er-167 5.74830E-11 9.31140E-07 68167.82c + 947 681671 Er-167m 8.78740E-12 1.11260E-07 681671 + 948 681680 Er-168 8.82350E-10 4.17680E-07 68168.82c + 949 681690 Er-169 3.10340E-09 2.00200E-07 681690 + 950 681700 Er-170 1.09480E-08 9.60390E-08 68170.82c + 951 681710 Er-171 1.14810E-08 4.58450E-08 681710 + 952 681720 Er-172 1.42150E-08 2.14810E-08 681720 + 953 681730 Er-173 6.75280E-09 8.72140E-09 681730 + 954 681740 Er-174 3.30450E-09 3.46400E-09 681740 + 955 681750 Er-175 6.23350E-10 6.39200E-10 681750 + 956 681760 Er-176 1.38690E-10 1.38690E-10 681760 + 957 681770 Er-177 9.14850E-12 9.14850E-12 681770 + 958 691690 Tm-169 5.19080E-12 2.00200E-07 691690 + 959 691700 Tm-170 3.91920E-11 3.91920E-11 691700 + 960 691710 Tm-171 2.83890E-10 4.61290E-08 691710 + 961 691720 Tm-172 6.68580E-10 2.21500E-08 691720 + 962 691730 Tm-173 1.90170E-09 1.06230E-08 691730 + 963 691740 Tm-174 1.54720E-09 5.01120E-09 691740 + 964 691750 Tm-175 1.62380E-09 2.26300E-09 691750 + 965 691760 Tm-176 6.15140E-10 7.53830E-10 691760 + 966 691770 Tm-177 2.51770E-10 2.60920E-10 691770 + 967 691780 Tm-178 3.28300E-11 3.28300E-11 691780 + 968 691790 Tm-179 5.97720E-12 5.97720E-12 691790 + 969 701720 Yb-172 3.07030E-12 2.21530E-08 701720 + 970 701730 Yb-173 1.82630E-11 1.06410E-08 701730 + 971 701740 Yb-174 9.94600E-11 5.11070E-09 701740 + 972 701750 Yb-175 1.65880E-10 2.45420E-09 701750 + 973 701751 Yb-175m 2.53580E-11 1.76790E-09 701751 + 974 701760 Yb-176 1.49930E-10 1.10880E-09 701760 + 975 701761 Yb-176m 2.69680E-10 6.46600E-10 701761 + 976 701770 Yb-177 2.28700E-10 5.42500E-10 701770 + 977 701771 Yb-177m 5.28810E-11 3.13800E-10 701771 + 978 701780 Yb-178 2.06980E-10 2.39810E-10 701780 + 979 701790 Yb-179 6.63070E-11 7.22840E-11 701790 + 980 701800 Yb-180 2.31710E-11 2.31710E-11 701800 + 981 701810 Yb-181 2.49450E-12 2.49450E-12 701810 + 982 711750 Lu-175 1.24300E-12 2.45550E-09 71175.82c + 983 711760 Lu-176 3.56870E-12 6.82290E-11 71176.82c + 984 711761 Lu-176m 1.98400E-12 1.98400E-12 711761 + 985 711770 Lu-177 1.71550E-11 5.61190E-10 711770 + 986 711771 Lu-177m 6.70660E-12 6.81490E-12 711771 + 987 711780 Lu-178 1.46440E-11 2.54450E-10 711780 + 988 711781 Lu-178m 1.65990E-11 1.65990E-11 711781 + 989 711790 Lu-179 4.90270E-11 1.28810E-10 711790 + 990 711791 Lu-179m 7.49480E-12 7.97790E-11 711791 + 991 711800 Lu-180 9.31760E-12 3.24280E-11 711800 + 992 711801 Lu-180m 9.31760E-12 3.24890E-11 711801 + 993 711802 Lu-180m 1.37320E-11 1.37320E-11 711802 + 994 711810 Lu-181 2.01280E-11 2.26230E-11 711810 + 995 711820 Lu-182 4.53340E-12 4.53340E-12 711820 + 996 711830 Lu-183 1.30750E-12 1.30750E-12 711830 + 997 721790 Hf-179 1.17030E-12 1.30750E-10 72179.82c + 998 721800 Hf-180 2.47750E-12 6.24370E-11 72180.82c + 999 721801 Hf-180m 4.45650E-12 1.13220E-11 721801 + 1000 721810 Hf-181 7.36160E-12 2.99840E-11 721810 + 1001 721820 Hf-182 3.29820E-12 1.03230E-11 721820 + 1002 721821 Hf-182m 5.93280E-12 5.93280E-12 721821 + 1003 721830 Hf-183 4.41840E-12 5.72590E-12 721830 + 1004 721841 Hf-184m 1.40030E-12 1.40030E-12 721841 + 1005 731830 Ta-183 1.21370E-12 6.93960E-12 731830 + 1006 731850 Ta-185 7.12770E-13 1.05800E-12 731850 + + Neutron-induced fission: + + Interpolation region : 2 / 2 + Interpolation energy : 4.00000E-01 MeV + Number of products : 1078 / 1142 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 3.46420E-05 3.46420E-05 1001.82c + 2 10020 H-2 1.05870E-05 1.05870E-05 1002.82c + 3 10030 H-3 1.42000E-04 1.42000E-04 1003.82c + 4 20040 He-4 2.19000E-03 2.19000E-03 2004.82c + 5 190500 K-50 1.69840E-12 1.69840E-12 190500 + 6 200500 Ca-50 3.51900E-11 3.63960E-11 200500 + 7 200510 Ca-51 2.36500E-11 2.36500E-11 200510 + 8 200520 Ca-52 1.85890E-11 1.85890E-11 200520 + 9 200530 Ca-53 4.43900E-12 4.43900E-12 200530 + 10 200540 Ca-54 1.05560E-12 1.05560E-12 200540 + 11 210500 Sc-50 1.25930E-11 5.30960E-11 210500 + 12 210501 Sc-50m 4.62000E-12 4.10160E-11 210501 + 13 210510 Sc-51 6.29390E-11 8.69610E-11 210510 + 14 210520 Sc-52 8.50900E-11 1.04640E-10 210520 + 15 210530 Sc-53 1.23190E-10 1.26300E-10 210530 + 16 210540 Sc-54 5.80840E-11 5.91400E-11 210540 + 17 210550 Sc-55 3.74090E-11 3.74090E-11 210550 + 18 210560 Sc-56 7.37130E-12 7.37130E-12 210560 + 19 210570 Sc-57 1.40420E-12 1.40420E-12 210570 + 20 220500 Ti-50 1.13300E-12 5.47420E-11 22050.82c + 21 220510 Ti-51 7.63650E-12 9.45970E-11 220510 + 22 220520 Ti-52 5.83530E-11 1.62990E-10 220520 + 23 220530 Ti-53 1.39810E-10 2.66110E-10 220530 + 24 220540 Ti-54 3.63410E-10 4.22550E-10 220540 + 25 220550 Ti-55 4.15660E-10 4.53070E-10 220550 + 26 220560 Ti-56 5.14970E-10 5.22810E-10 220560 + 27 220570 Ti-57 2.00580E-10 2.01520E-10 220570 + 28 220580 Ti-58 8.87190E-11 8.87190E-11 220580 + 29 220590 Ti-59 1.39700E-11 1.39700E-11 220590 + 30 220600 Ti-60 2.00470E-12 2.00470E-12 220600 + 31 230530 V-53 1.23220E-11 2.78430E-10 230530 + 32 230540 V-54 5.69500E-11 4.79500E-10 230540 + 33 230550 V-55 3.59330E-10 8.12400E-10 230550 + 34 230560 V-56 7.36590E-10 1.26000E-09 230560 + 35 230570 V-57 1.61990E-09 1.82080E-09 230570 + 36 230580 V-58 1.31910E-09 1.40780E-09 230580 + 37 230590 V-59 1.35180E-09 1.36580E-09 230590 + 38 230600 V-60 4.07320E-10 4.09320E-10 230600 + 39 230610 V-61 1.47160E-10 1.47160E-10 230610 + 40 230620 V-62 1.76620E-11 1.76620E-11 230620 + 41 230630 V-63 2.00470E-12 2.00470E-12 230630 + 42 240540 Cr-54 1.01170E-12 4.80510E-10 24054.82c + 43 240550 Cr-55 1.26720E-11 8.25070E-10 240550 + 44 240560 Cr-56 1.57680E-10 1.42500E-09 240560 + 45 240570 Cr-57 5.97090E-10 3.53690E-09 240570 + 46 240580 Cr-58 2.64600E-09 2.92760E-09 240580 + 47 240590 Cr-59 4.54280E-09 5.90860E-09 240590 + 48 240600 Cr-60 7.97830E-09 8.39650E-09 240600 + 49 240610 Cr-61 5.50390E-09 5.64220E-09 240610 + 50 240620 Cr-62 4.43390E-09 4.45230E-09 240620 + 51 240630 Cr-63 1.08040E-09 1.08170E-09 240630 + 52 240640 Cr-64 2.63870E-10 2.63870E-10 240640 + 53 240650 Cr-65 2.52700E-11 2.52700E-11 240650 + 54 240660 Cr-66 2.32060E-12 2.32060E-12 240660 + 55 250570 Mn-57 1.47090E-11 3.55160E-09 250570 + 56 250580 Mn-58 1.13860E-10 3.04140E-09 250580 + 57 250581 Mn-58m 1.11920E-11 1.11920E-11 250581 + 58 250590 Mn-59 1.25700E-09 7.16560E-09 250590 + 59 250600 Mn-60 3.31880E-10 9.11660E-09 250600 + 60 250601 Mn-60m 3.37620E-09 3.37620E-09 250601 + 61 250610 Mn-61 1.39090E-08 1.95510E-08 250610 + 62 250620 Mn-62 1.66190E-08 1.88460E-08 250620 + 63 250621 Mn-62m 2.60270E-09 4.82880E-09 250621 + 64 250630 Mn-63 2.82940E-08 2.93760E-08 250630 + 65 250640 Mn-64 1.36590E-08 1.39230E-08 250640 + 66 250650 Mn-65 9.01750E-09 9.04280E-09 250650 + 67 250660 Mn-66 1.81370E-09 1.81600E-09 250660 + 68 250670 Mn-67 3.55270E-10 3.55270E-10 250670 + 69 250680 Mn-68 2.29430E-11 2.29430E-11 250680 + 70 250690 Mn-69 2.46470E-12 2.46470E-12 250690 + 71 260590 Fe-59 1.19450E-11 7.17750E-09 260590 + 72 260600 Fe-60 2.30300E-10 1.23350E-08 260600 + 73 260610 Fe-61 1.59800E-09 2.11490E-08 260610 + 74 260620 Fe-62 1.25170E-08 3.61910E-08 260620 + 75 260630 Fe-63 3.05130E-08 5.98890E-08 260630 + 76 260640 Fe-64 8.10570E-08 9.49800E-08 260640 + 77 260650 Fe-65 9.47250E-08 1.03770E-07 260650 + 78 260660 Fe-66 1.19380E-07 1.21200E-07 260660 + 79 260670 Fe-67 4.76850E-08 4.80400E-08 260670 + 80 260680 Fe-68 2.17220E-08 2.17460E-08 260680 + 81 260690 Fe-69 5.12470E-09 5.12660E-09 260690 + 82 260700 Fe-70 2.02300E-10 2.02300E-10 260700 + 83 260710 Fe-71 3.71660E-11 3.71660E-11 260710 + 84 260720 Fe-72 1.04240E-12 1.04240E-12 260720 + 85 270610 Co-61 1.02680E-11 2.11600E-08 270610 + 86 270620 Co-62 4.43020E-11 3.62370E-08 270620 + 87 270621 Co-62m 1.20760E-10 1.20760E-10 270621 + 88 270630 Co-63 2.54180E-09 6.24300E-08 270630 + 89 270640 Co-64 1.20470E-08 1.07030E-07 270640 + 90 270650 Co-65 7.78080E-08 1.81580E-07 270650 + 91 270660 Co-66 1.62160E-07 2.83360E-07 270660 + 92 270670 Co-67 3.64750E-07 4.12790E-07 270670 + 93 270680 Co-68 1.74540E-07 2.50730E-07 270680 + 94 270681 Co-68m 1.30280E-07 1.52380E-07 270681 + 95 270690 Co-69 1.20240E-06 1.20720E-06 270690 + 96 270700 Co-70 1.92900E-08 1.92900E-08 270700 + 97 270701 Co-70m 1.92900E-08 1.94930E-08 270701 + 98 270710 Co-71 5.10510E-08 5.10880E-08 270710 + 99 270720 Co-72 2.95370E-09 2.95470E-09 270720 + 100 270730 Co-73 4.94560E-10 4.94560E-10 270730 + 101 270740 Co-74 1.87850E-11 1.87850E-11 270740 + 102 280630 Ni-63 6.12790E-12 6.24370E-08 280630 + 103 280640 Ni-64 2.01290E-10 1.07230E-07 28064.82c + 104 280650 Ni-65 2.58890E-09 1.84170E-07 280650 + 105 280660 Ni-66 3.28670E-08 3.16220E-07 280660 + 106 280670 Ni-67 1.27650E-07 5.40440E-07 280670 + 107 280680 Ni-68 5.80960E-07 9.19960E-07 280680 + 108 280690 Ni-69 6.01200E-07 1.79630E-06 280690 + 109 280691 Ni-69m 6.01200E-07 6.01200E-07 280691 + 110 280700 Ni-70 1.02890E-06 1.06770E-06 280700 + 111 280710 Ni-71 1.30120E-06 1.35230E-06 280710 + 112 280720 Ni-72 1.39600E-06 1.39890E-06 280720 + 113 280730 Ni-73 2.49980E-07 2.50480E-07 280730 + 114 280740 Ni-74 6.84690E-08 6.84880E-08 280740 + 115 280750 Ni-75 3.55960E-09 3.55960E-09 280750 + 116 280760 Ni-76 6.81390E-10 6.81390E-10 280760 + 117 280770 Ni-77 2.00290E-11 2.00290E-11 280770 + 118 290650 Cu-65 4.12110E-12 1.84170E-07 29065.82c + 119 290660 Cu-66 1.12900E-10 3.16340E-07 290660 + 120 290670 Cu-67 2.96200E-09 5.43400E-07 290670 + 121 290680 Cu-68 6.96500E-09 9.42870E-07 290680 + 122 290681 Cu-68m 1.89850E-08 1.89850E-08 290681 + 123 290690 Cu-69 3.90230E-07 2.78770E-06 290690 + 124 290700 Cu-70 2.13610E-08 1.84990E-07 290700 + 125 290701 Cu-70m 2.72800E-07 3.27250E-07 290701 + 126 290702 Cu-70m 2.13610E-08 1.08900E-06 290702 + 127 290710 Cu-71 5.20490E-06 6.55720E-06 290710 + 128 290720 Cu-72 1.39590E-06 2.79490E-06 290720 + 129 290730 Cu-73 3.98660E-06 4.23710E-06 290730 + 130 290740 Cu-74 1.41030E-06 1.47880E-06 290740 + 131 290750 Cu-75 1.19250E-06 1.19600E-06 290750 + 132 290760 Cu-76 7.14650E-07 7.14990E-07 290760 + 133 290761 Cu-76m 7.14650E-07 7.14990E-07 290761 + 134 290770 Cu-77 1.09500E-07 1.09520E-07 290770 + 135 290780 Cu-78 7.45930E-09 7.45930E-09 290780 + 136 290790 Cu-79 4.87080E-10 4.87080E-10 290790 + 137 290800 Cu-80 1.80450E-11 1.80450E-11 290800 + 138 300670 Zn-67 1.73720E-12 5.43400E-07 300670 + 139 300680 Zn-68 1.09850E-10 9.46020E-07 300680 + 140 300690 Zn-69 5.84540E-10 2.79120E-06 300690 + 141 300691 Zn-69m 2.90320E-09 2.90320E-09 300691 + 142 300700 Zn-70 1.84870E-08 1.40170E-06 300700 + 143 300710 Zn-71 7.87130E-08 6.63590E-06 300710 + 144 300711 Zn-71m 3.90940E-07 3.90940E-07 300711 + 145 300720 Zn-72 2.79180E-06 5.58670E-06 300720 + 146 300730 Zn-73 8.15750E-07 9.86040E-06 300730 + 147 300731 Zn-73m 1.12830E-06 4.80750E-06 300731 + 148 300732 Zn-73m 7.35850E-06 7.35850E-06 300732 + 149 300740 Zn-74 1.97430E-05 2.12640E-05 300740 + 150 300750 Zn-75 1.07090E-05 1.18850E-05 300750 + 151 300760 Zn-76 4.86040E-05 5.00130E-05 300760 + 152 300770 Zn-77 2.12530E-05 2.27780E-05 300770 + 153 300771 Zn-77m 2.82970E-06 2.82970E-06 300771 + 154 300780 Zn-78 2.76560E-05 2.76640E-05 300780 + 155 300790 Zn-79 4.28800E-06 4.28820E-06 300790 + 156 300800 Zn-80 1.71090E-07 1.71110E-07 300800 + 157 300810 Zn-81 6.85860E-09 6.85860E-09 300810 + 158 300820 Zn-82 3.75490E-10 3.75490E-10 300820 + 159 310690 Ga-69 1.30940E-12 2.79120E-06 310690 + 160 310700 Ga-70 1.57110E-11 1.57110E-11 310700 + 161 310710 Ga-71 2.83470E-09 7.02970E-06 310710 + 162 310720 Ga-72 2.00040E-08 5.60860E-06 310720 + 163 310721 Ga-72m 1.96630E-09 1.88120E-07 310721 + 164 310730 Ga-73 4.98460E-07 1.40380E-05 310730 + 165 310740 Ga-74 7.05100E-07 1.71820E-05 310740 + 166 310741 Ga-74m 7.05100E-07 2.19690E-05 310741 + 167 310750 Ga-75 1.07080E-05 2.25930E-05 310750 + 168 310760 Ga-76 2.42940E-05 7.43060E-05 310760 + 169 310770 Ga-77 5.80750E-05 8.22670E-05 310770 + 170 310780 Ga-78 6.98650E-05 9.75850E-05 310780 + 171 310790 Ga-79 7.72290E-05 8.14620E-05 310790 + 172 310800 Ga-80 3.83890E-05 3.85610E-05 310800 + 173 310810 Ga-81 2.26290E-05 2.26350E-05 310810 + 174 310820 Ga-82 1.38410E-06 1.38450E-06 310820 + 175 310830 Ga-83 1.40970E-06 1.40970E-06 310830 + 176 310840 Ga-84 4.98420E-09 4.98420E-09 310840 + 177 310850 Ga-85 2.00560E-10 2.00560E-10 310850 + 178 320720 Ge-72 2.25170E-11 5.60870E-06 32072.82c + 179 320730 Ge-73 9.38610E-10 1.40390E-05 32073.82c + 180 320731 Ge-73m 1.88990E-10 1.38320E-05 320731 + 181 320740 Ge-74 4.15730E-08 2.27150E-05 32074.82c + 182 320750 Ge-75 1.57280E-07 2.39310E-05 320750 + 183 320751 Ge-75m 1.18130E-06 2.08500E-06 320751 + 184 320760 Ge-76 7.14560E-06 8.14520E-05 32076.82c + 185 320770 Ge-77 5.49710E-05 7.19920E-05 320770 + 186 320771 Ge-77m 7.31910E-06 8.95870E-05 320771 + 187 320780 Ge-78 1.45420E-04 2.43080E-04 320780 + 188 320790 Ge-79 3.44160E-05 1.26030E-04 320790 + 189 320791 Ge-79m 2.58480E-04 2.58610E-04 320791 + 190 320800 Ge-80 5.60080E-04 6.01330E-04 320800 + 191 320810 Ge-81 3.46440E-04 3.57910E-04 320810 + 192 320811 Ge-81m 6.97530E-05 7.93110E-05 320811 + 193 320820 Ge-82 4.15230E-04 4.16840E-04 320820 + 194 320830 Ge-83 1.10420E-04 1.11310E-04 320830 + 195 320840 Ge-84 4.06630E-05 4.06640E-05 320840 + 196 320850 Ge-85 1.34930E-06 1.34950E-06 320850 + 197 320860 Ge-86 7.89420E-08 7.89420E-08 320860 + 198 320870 Ge-87 1.66430E-09 1.66430E-09 320870 + 199 330740 As-74 8.58760E-12 8.58760E-12 330740 + 200 330750 As-75 9.04410E-11 2.39320E-05 33075.82c + 201 330751 As-75m 3.42500E-10 9.68000E-10 330751 + 202 330760 As-76 2.47080E-08 2.47080E-08 330760 + 203 330770 As-77 7.26540E-07 1.45280E-04 330770 + 204 330780 As-78 7.27470E-06 2.50350E-04 330780 + 205 330790 As-79 2.57210E-05 4.00010E-04 330790 + 206 330800 As-80 1.45990E-04 7.47320E-04 330800 + 207 330810 As-81 4.50050E-04 8.86480E-04 330810 + 208 330820 As-82 1.59100E-04 5.75940E-04 330820 + 209 330821 As-82m 5.54360E-04 5.54360E-04 330821 + 210 330830 As-83 1.18370E-03 1.29940E-03 330830 + 211 330840 As-84 3.40450E-04 3.58690E-04 330840 + 212 330841 As-84m 3.40450E-04 3.58690E-04 330841 + 213 330850 As-85 3.44100E-04 3.45260E-04 330850 + 214 330860 As-86 6.70970E-05 6.71760E-05 330860 + 215 330870 As-87 2.06210E-05 2.06230E-05 330870 + 216 330880 As-88 1.93160E-06 1.93160E-06 330880 + 217 330890 As-89 2.45030E-08 2.45030E-08 330890 + 218 330900 As-90 5.13130E-10 5.13130E-10 330900 + 219 340760 Se-76 6.08390E-12 2.47140E-08 34076.82c + 220 340770 Se-77 4.70690E-11 1.45280E-04 34077.82c + 221 340771 Se-77m 3.53520E-10 3.53520E-10 340771 + 222 340780 Se-78 2.66220E-08 2.50380E-04 34078.82c + 223 340790 Se-79 4.55790E-07 4.00310E-04 34079.82c + 224 340791 Se-79m 6.06860E-08 3.90600E-04 340791 + 225 340800 Se-80 1.47480E-05 7.62070E-04 34080.82c + 226 340810 Se-81 1.53490E-05 1.01700E-03 340810 + 227 340811 Se-81m 1.15280E-04 1.47100E-04 340811 + 228 340820 Se-82 5.37940E-04 1.66820E-03 34082.82c + 229 340830 Se-83 1.47340E-03 1.94170E-03 340830 + 230 340831 Se-83m 2.96670E-04 1.12880E-03 340831 + 231 340840 Se-84 3.82870E-03 4.62100E-03 340840 + 232 340850 Se-85 3.72780E-03 4.01930E-03 340850 + 233 340860 Se-86 3.15930E-03 3.20750E-03 340860 + 234 340870 Se-87 1.44270E-03 1.46010E-03 340870 + 235 340880 Se-88 5.93110E-04 5.95040E-04 340880 + 236 340890 Se-89 1.18140E-04 1.18170E-04 340890 + 237 340900 Se-90 2.25300E-05 2.25310E-05 340900 + 238 340910 Se-91 9.66640E-07 9.66640E-07 340910 + 239 340920 Se-92 7.80460E-09 7.80460E-09 340920 + 240 350790 Br-79 3.74890E-11 2.18910E-07 35079.82c + 241 350791 Br-79m 1.41970E-10 1.41970E-10 350791 + 242 350800 Br-80 2.21330E-09 9.92520E-09 350800 + 243 350801 Br-80m 7.71190E-09 7.71190E-09 350801 + 244 350810 Br-81 3.89430E-07 1.01750E-03 35081.82c + 245 350820 Br-82 6.07540E-06 8.25080E-06 350820 + 246 350821 Br-82m 2.22890E-06 2.22890E-06 350821 + 247 350830 Br-83 9.17510E-05 3.16230E-03 350830 + 248 350840 Br-84 2.00760E-04 4.82180E-03 350840 + 249 350841 Br-84m 2.00760E-04 2.00760E-04 350841 + 250 350850 Br-85 1.84830E-03 5.86760E-03 350850 + 251 350860 Br-86 3.28070E-03 6.48820E-03 350860 + 252 350870 Br-87 4.77210E-03 6.23810E-03 350870 + 253 350880 Br-88 3.59860E-03 4.19700E-03 350880 + 254 350890 Br-89 2.69650E-03 2.80550E-03 350890 + 255 350900 Br-90 1.10790E-03 1.13060E-03 350900 + 256 350910 Br-91 4.47510E-04 4.48270E-04 350910 + 257 350920 Br-92 6.47340E-05 6.47420E-05 350920 + 258 350930 Br-93 1.62400E-05 1.62400E-05 350930 + 259 350940 Br-94 4.92340E-08 4.92340E-08 350940 + 260 350950 Br-95 1.50200E-09 1.50200E-09 350950 + 261 360810 Kr-81 4.98150E-11 5.64480E-11 360810 + 262 360811 Kr-81m 6.63260E-12 6.63260E-12 360811 + 263 360820 Kr-82 5.69500E-09 8.31000E-06 36082.82c + 264 360830 Kr-83 1.17340E-06 3.16370E-03 36083.82c + 265 360831 Kr-83m 2.36270E-07 3.15970E-03 360831 + 266 360840 Kr-84 2.10160E-05 5.04360E-03 36084.82c + 267 360850 Kr-85 1.48480E-04 1.41800E-03 36085.82c + 268 360851 Kr-85m 2.98970E-05 5.88790E-03 360851 + 269 360860 Kr-86 1.36520E-03 8.01000E-03 36086.82c + 270 360870 Kr-87 3.72440E-03 1.00870E-02 360870 + 271 360880 Kr-88 9.30110E-03 1.36120E-02 360880 + 272 360890 Kr-89 1.21860E-02 1.48740E-02 360890 + 273 360900 Kr-90 1.30480E-02 1.39900E-02 360900 + 274 360910 Kr-91 8.41740E-03 8.79750E-03 360910 + 275 360920 Kr-92 4.60050E-03 4.65490E-03 360920 + 276 360930 Kr-93 1.50470E-03 1.50990E-03 360930 + 277 360940 Kr-94 4.07350E-04 4.07360E-04 360940 + 278 360950 Kr-95 5.78350E-05 5.78370E-05 360950 + 279 360960 Kr-96 9.48000E-06 9.48000E-06 360960 + 280 360970 Kr-97 8.60020E-07 8.60020E-07 360970 + 281 370840 Rb-84 5.10150E-10 1.58040E-09 370840 + 282 370841 Rb-84m 1.07020E-09 1.07020E-09 370841 + 283 370850 Rb-85 1.01880E-07 6.04600E-03 37085.82c + 284 370860 Rb-86 6.88180E-07 2.13190E-06 37086.82c + 285 370861 Rb-86m 1.44370E-06 1.44370E-06 370861 + 286 370870 Rb-87 1.06900E-04 1.01940E-02 37087.82c + 287 370880 Rb-88 4.35730E-04 1.40480E-02 370880 + 288 370890 Rb-89 2.20220E-03 1.70760E-02 370890 + 289 370900 Rb-90 5.20220E-04 1.28660E-02 370900 + 290 370901 Rb-90m 5.29230E-03 7.12220E-03 370901 + 291 370910 Rb-91 1.32480E-02 2.20450E-02 370910 + 292 370920 Rb-92 1.32330E-02 1.78880E-02 370920 + 293 370930 Rb-93 1.28010E-02 1.43160E-02 370930 + 294 370940 Rb-94 6.37310E-03 6.77760E-03 370940 + 295 370950 Rb-95 3.45510E-03 3.51160E-03 370950 + 296 370960 Rb-96 4.20150E-04 6.37110E-04 370960 + 297 370961 Rb-96m 4.20150E-04 4.24740E-04 370961 + 298 370970 Rb-97 1.70620E-04 1.71420E-04 370970 + 299 370980 Rb-98 9.47000E-06 9.47000E-06 370980 + 300 370981 Rb-98m 9.47000E-06 9.47000E-06 370981 + 301 370990 Rb-99 9.21630E-07 9.21630E-07 370990 + 302 371000 Rb-100 1.61290E-09 1.61290E-09 371000 + 303 380860 Sr-86 5.98040E-10 2.13240E-06 38086.82c + 304 380870 Sr-87 9.03240E-07 1.08460E-06 38087.82c + 305 380871 Sr-87m 1.81860E-07 1.81860E-07 380871 + 306 380880 Sr-88 2.41760E-05 1.40720E-02 38088.82c + 307 380890 Sr-89 9.90420E-05 1.71750E-02 38089.82c + 308 380900 Sr-90 1.01250E-03 2.08150E-02 38090.82c + 309 380910 Sr-91 3.57630E-03 2.56220E-02 380910 + 310 380920 Sr-92 1.24250E-02 3.05130E-02 380920 + 311 380930 Sr-93 2.27650E-02 3.75650E-02 380930 + 312 380940 Sr-94 3.21460E-02 3.85410E-02 380940 + 313 380950 Sr-95 2.68040E-02 3.00990E-02 380950 + 314 380960 Sr-96 1.97360E-02 2.05430E-02 380960 + 315 380970 Sr-97 7.65420E-03 7.78390E-03 380970 + 316 380980 Sr-98 3.06370E-03 3.08150E-03 380980 + 317 380990 Sr-99 5.91100E-04 5.91870E-04 380990 + 318 381000 Sr-100 1.26360E-04 1.26360E-04 381000 + 319 381010 Sr-101 1.27960E-05 1.27960E-05 381010 + 320 381020 Sr-102 2.05440E-08 2.05440E-08 381020 + 321 390890 Y-89 1.09520E-09 1.71750E-02 39089.82c + 322 390891 Y-89m 5.43910E-09 1.66100E-06 390891 + 323 390900 Y-90 9.02500E-08 2.08150E-02 39090.82c + 324 390901 Y-90m 1.50930E-07 1.50930E-07 390901 + 325 390910 Y-91 8.43620E-06 2.56720E-02 39091.82c + 326 390911 Y-91m 4.18990E-05 1.51160E-02 390911 + 327 390920 Y-92 2.13330E-04 3.07270E-02 390920 + 328 390930 Y-93 1.83060E-04 3.91230E-02 390930 + 329 390931 Y-93m 1.37490E-03 1.07750E-02 390931 + 330 390940 Y-94 4.39440E-03 4.29360E-02 390940 + 331 390950 Y-95 1.50970E-02 4.51960E-02 390950 + 332 390960 Y-96 6.91630E-03 2.74610E-02 390960 + 333 390961 Y-96m 1.45100E-02 1.45120E-02 390961 + 334 390970 Y-97 4.50940E-03 1.12890E-02 390970 + 335 390971 Y-97m 1.66680E-02 2.24090E-02 390971 + 336 390972 Y-97m 5.72830E-03 5.72830E-03 390972 + 337 390980 Y-98 3.35140E-03 6.43290E-03 390980 + 338 390981 Y-98m 1.62480E-02 1.62480E-02 390981 + 339 390990 Y-99 1.35590E-02 1.41520E-02 390990 + 340 391000 Y-100 2.57870E-03 2.70430E-03 391000 + 341 391001 Y-100m 2.57870E-03 2.57890E-03 391001 + 342 391010 Y-101 1.84960E-03 1.86210E-03 391010 + 343 391020 Y-102 1.38710E-04 1.38720E-04 391020 + 344 391021 Y-102m 1.38710E-04 1.38720E-04 391021 + 345 391030 Y-103 4.97700E-05 4.97700E-05 391030 + 346 391040 Y-104 4.21310E-06 4.21310E-06 391040 + 347 391050 Y-105 1.67210E-09 1.67210E-09 391050 + 348 400910 Zr-91 7.15270E-10 2.56720E-02 40091.82c + 349 400920 Zr-92 2.63430E-06 3.07290E-02 40092.82c + 350 400930 Zr-93 4.87930E-05 3.91710E-02 40093.82c + 351 400940 Zr-94 3.49750E-04 4.32850E-02 40094.82c + 352 400950 Zr-95 1.71320E-03 4.69090E-02 40095.82c + 353 400960 Zr-96 7.55010E-03 4.95410E-02 40096.82c + 354 400970 Zr-97 1.41920E-02 4.94360E-02 400970 + 355 400980 Zr-98 3.27060E-02 5.50510E-02 400980 + 356 400990 Zr-99 3.57540E-02 4.96900E-02 400990 + 357 401000 Zr-100 4.14990E-02 4.67570E-02 401000 + 358 401010 Zr-101 2.44940E-02 2.63700E-02 401010 + 359 401020 Zr-102 1.31440E-02 1.34120E-02 401020 + 360 401030 Zr-103 3.63160E-03 3.67780E-03 401030 + 361 401040 Zr-104 9.27930E-04 9.31770E-04 401040 + 362 401050 Zr-105 1.18740E-04 1.18740E-04 401050 + 363 401060 Zr-106 1.15150E-05 1.15150E-05 401060 + 364 401070 Zr-107 7.35960E-09 7.35960E-09 401070 + 365 410940 Nb-94 6.91630E-09 1.10310E-08 41094.82c + 366 410941 Nb-94m 4.13570E-09 4.13570E-09 410941 + 367 410950 Nb-95 7.90950E-06 4.68900E-02 41095.82c + 368 410951 Nb-95m 1.59250E-06 5.08380E-04 410951 + 369 410960 Nb-96 6.07010E-05 6.07010E-05 410960 + 370 410970 Nb-97 4.11150E-04 4.99300E-02 410970 + 371 410971 Nb-97m 8.27830E-05 4.70710E-02 410971 + 372 410980 Nb-98 4.55540E-04 5.55060E-02 410980 + 373 410981 Nb-98m 1.58730E-03 1.58730E-03 410981 + 374 410990 Nb-99 6.85660E-03 3.86540E-02 410990 + 375 410991 Nb-99m 1.38050E-03 1.96660E-02 410991 + 376 411000 Nb-100 2.93930E-03 4.96970E-02 411000 + 377 411001 Nb-100m 1.42500E-02 1.42500E-02 411001 + 378 411010 Nb-101 3.38100E-02 6.01800E-02 411010 + 379 411020 Nb-102 1.54000E-02 2.88120E-02 411020 + 380 411021 Nb-102m 1.54000E-02 1.54000E-02 411021 + 381 411030 Nb-103 2.75060E-02 3.11840E-02 411030 + 382 411040 Nb-104 6.81450E-03 7.74790E-03 411040 + 383 411041 Nb-104m 6.81450E-03 6.81450E-03 411041 + 384 411050 Nb-105 6.44710E-03 6.56440E-03 411050 + 385 411060 Nb-106 1.36030E-03 1.37160E-03 411060 + 386 411070 Nb-107 2.98330E-04 2.98340E-04 411070 + 387 411080 Nb-108 2.20740E-05 2.20740E-05 411080 + 388 411090 Nb-109 2.24190E-06 2.24190E-06 411090 + 389 411100 Nb-110 1.34840E-10 1.34840E-10 411100 + 390 420960 Mo-96 1.84890E-09 6.07030E-05 42096.82c + 391 420970 Mo-97 2.58010E-06 4.99330E-02 42097.82c + 392 420980 Mo-98 7.40150E-05 5.71680E-02 42098.82c + 393 420990 Mo-99 4.38880E-04 5.83660E-02 42099.82c + 394 421000 Mo-100 2.83670E-03 6.67830E-02 42100.82c + 395 421010 Mo-101 8.53160E-03 6.87110E-02 421010 + 396 421020 Mo-102 2.36140E-02 6.78270E-02 421020 + 397 421030 Mo-103 3.16090E-02 6.28010E-02 421030 + 398 421040 Mo-104 4.24340E-02 5.71000E-02 421040 + 399 421050 Mo-105 2.85580E-02 3.50720E-02 421050 + 400 421060 Mo-106 1.78140E-02 1.91420E-02 421060 + 401 421070 Mo-107 5.85010E-03 6.13190E-03 421070 + 402 421080 Mo-108 1.89900E-03 1.92000E-03 421080 + 403 421090 Mo-109 3.37170E-04 3.39130E-04 421090 + 404 421100 Mo-110 3.58410E-05 3.58410E-05 421100 + 405 421110 Mo-111 6.82100E-06 6.82100E-06 421110 + 406 421120 Mo-112 2.02650E-06 2.02650E-06 421120 + 407 421130 Mo-113 2.30890E-06 2.30890E-06 421130 + 408 430990 Tc-99 7.67180E-07 5.83650E-02 43099.82c + 409 430991 Tc-99m 1.54470E-07 5.13970E-02 430991 + 410 431000 Tc-100 9.95640E-06 9.95640E-06 431000 + 411 431010 Tc-101 1.35580E-04 6.88470E-02 431010 + 412 431020 Tc-102 3.30310E-04 6.81570E-02 431020 + 413 431021 Tc-102m 3.30310E-04 3.30310E-04 431021 + 414 431030 Tc-103 2.84690E-03 6.56480E-02 431030 + 415 431040 Tc-104 6.83490E-03 6.39350E-02 431040 + 416 431050 Tc-105 1.60320E-02 5.11040E-02 431050 + 417 431060 Tc-106 1.70510E-02 3.61930E-02 431060 + 418 431070 Tc-107 1.85300E-02 2.46620E-02 431070 + 419 431080 Tc-108 1.03310E-02 1.22530E-02 431080 + 420 431090 Tc-109 5.67210E-03 6.00940E-03 431090 + 421 431100 Tc-110 1.15180E-03 1.18770E-03 431100 + 422 431110 Tc-111 3.81180E-04 3.87970E-04 431110 + 423 431120 Tc-112 6.22370E-05 6.42210E-05 431120 + 424 431130 Tc-113 4.64750E-05 4.87840E-05 431130 + 425 431140 Tc-114 5.87110E-06 5.87110E-06 431140 + 426 431150 Tc-115 3.54830E-06 3.54830E-06 431150 + 427 441000 Ru-100 9.95560E-07 1.09520E-05 44100.82c + 428 441010 Ru-101 1.92940E-09 6.88470E-02 44101.82c + 429 441020 Ru-102 7.33060E-06 6.84950E-02 44102.82c + 430 441030 Ru-103 1.61050E-05 6.57090E-02 44103.82c + 431 441031 Ru-103m 4.50610E-05 4.50610E-05 441031 + 432 441040 Ru-104 4.51530E-04 6.43860E-02 44104.82c + 433 441050 Ru-105 1.52480E-03 5.26290E-02 44105.82c + 434 441060 Ru-106 4.18240E-03 4.03750E-02 44106.82c + 435 441070 Ru-107 5.94270E-03 3.06050E-02 441070 + 436 441080 Ru-108 8.44090E-03 2.06990E-02 441080 + 437 441090 Ru-109 7.59790E-03 1.36030E-02 441090 + 438 441100 Ru-110 4.36350E-03 5.55070E-03 441100 + 439 441110 Ru-111 2.17260E-03 2.56150E-03 441110 + 440 441120 Ru-112 5.35810E-04 6.02570E-04 441120 + 441 441130 Ru-113 1.26420E-04 2.35280E-04 441130 + 442 441131 Ru-113m 1.26420E-04 1.26420E-04 441131 + 443 441140 Ru-114 1.19470E-04 1.25470E-04 441140 + 444 441150 Ru-115 2.49280E-05 2.79680E-05 441150 + 445 441160 Ru-116 1.25880E-05 1.25880E-05 441160 + 446 441170 Ru-117 1.23050E-10 1.23050E-10 441170 + 447 451040 Rh-104 2.34840E-07 1.05200E-06 451040 + 448 451041 Rh-104m 8.18260E-07 8.18260E-07 451041 + 449 451050 Rh-105 8.72400E-06 5.26390E-02 45105.82c + 450 451051 Rh-105m 1.16160E-06 1.49410E-02 451051 + 451 451060 Rh-106 1.85780E-05 4.03940E-02 451060 + 452 451061 Rh-106m 5.06400E-05 5.06400E-05 451061 + 453 451070 Rh-107 2.30420E-04 3.08350E-02 451070 + 454 451080 Rh-108 1.07300E-04 2.08060E-02 451080 + 455 451081 Rh-108m 3.73880E-04 3.73880E-04 451081 + 456 451090 Rh-109 9.43270E-04 1.45460E-02 451090 + 457 451100 Rh-110 6.79070E-04 6.22980E-03 451100 + 458 451101 Rh-110m 1.59860E-05 1.59860E-05 451101 + 459 451110 Rh-111 1.30610E-03 3.86760E-03 451110 + 460 451120 Rh-112 3.09260E-04 9.11840E-04 451120 + 461 451121 Rh-112m 3.09260E-04 3.09260E-04 451121 + 462 451130 Rh-113 6.90090E-04 9.88580E-04 451130 + 463 451140 Rh-114 1.56100E-04 2.81620E-04 451140 + 464 451141 Rh-114m 1.56100E-04 1.56100E-04 451141 + 465 451150 Rh-115 2.23480E-04 2.51520E-04 451150 + 466 451160 Rh-116 1.51770E-05 2.76290E-05 451160 + 467 451161 Rh-116m 4.13690E-05 4.13690E-05 451161 + 468 451170 Rh-117 1.17980E-05 1.17980E-05 451170 + 469 451180 Rh-118 2.16100E-08 2.16100E-08 451180 + 470 451190 Rh-119 1.23220E-09 1.23220E-09 451190 + 471 451200 Rh-120 1.01950E-11 1.01950E-11 451200 + 472 451210 Rh-121 1.30550E-07 1.30550E-07 451210 + 473 451220 Rh-122 5.12240E-09 5.12240E-09 451220 + 474 461060 Pd-106 1.48540E-09 4.04440E-02 46106.82c + 475 461070 Pd-107 6.33120E-07 3.08370E-02 46107.82c + 476 461071 Pd-107m 1.39160E-06 1.39160E-06 461071 + 477 461080 Pd-108 1.10030E-05 2.11910E-02 46108.82c + 478 461090 Pd-109 1.73020E-05 1.46020E-02 461090 + 479 461091 Pd-109m 3.80300E-05 7.31120E-03 461091 + 480 461100 Pd-110 8.77320E-05 6.33350E-03 46110.82c + 481 461110 Pd-111 5.96690E-05 4.01890E-03 461110 + 482 461111 Pd-111m 1.31150E-04 1.46620E-04 461111 + 483 461120 Pd-112 2.01350E-04 1.42250E-03 461120 + 484 461130 Pd-113 7.13990E-05 1.25980E-03 461130 + 485 461131 Pd-113m 1.99770E-04 1.99770E-04 461131 + 486 461140 Pd-114 4.66400E-04 9.04120E-04 461140 + 487 461150 Pd-115 1.21600E-04 3.60910E-04 461150 + 488 461151 Pd-115m 2.67280E-04 3.03800E-04 461151 + 489 461160 Pd-116 3.26470E-04 3.95470E-04 461160 + 490 461170 Pd-117 4.87590E-05 1.67730E-04 461170 + 491 461171 Pd-117m 1.07170E-04 1.07170E-04 461171 + 492 461180 Pd-118 7.88070E-05 7.88280E-05 461180 + 493 461190 Pd-119 3.37560E-05 3.37570E-05 461190 + 494 461200 Pd-120 1.63840E-05 1.64020E-05 461200 + 495 461210 Pd-121 2.34120E-05 2.35250E-05 461210 + 496 461220 Pd-122 6.57040E-06 6.57550E-06 461220 + 497 461230 Pd-123 5.50770E-07 5.50770E-07 461230 + 498 461240 Pd-124 7.35520E-08 7.35520E-08 461240 + 499 471090 Ag-109 4.01940E-10 1.46020E-02 47109.82c + 500 471091 Ag-109m 3.01890E-09 1.45940E-02 471091 + 501 471100 Ag-110 1.23770E-08 1.28360E-08 471100 + 502 471101 Ag-110m 3.37380E-08 3.37380E-08 47510.82c + 503 471110 Ag-111 1.60180E-07 4.03970E-03 47111.82c + 504 471111 Ag-111m 1.20300E-06 4.01990E-03 471111 + 505 471120 Ag-112 5.06300E-06 1.42750E-03 471120 + 506 471130 Ag-113 3.51970E-06 8.45920E-04 471130 + 507 471131 Ag-113m 2.64350E-05 1.23270E-03 471131 + 508 471140 Ag-114 1.00090E-05 9.62650E-04 471140 + 509 471141 Ag-114m 4.85230E-05 4.85230E-05 471141 + 510 471150 Ag-115 1.41360E-05 3.79050E-04 471150 + 511 471151 Ag-115m 1.06170E-04 4.83110E-04 471151 + 512 471160 Ag-116 5.71800E-05 4.62000E-04 471160 + 513 471161 Ag-116m 1.55860E-04 1.55860E-04 471161 + 514 471170 Ag-117 2.21530E-05 1.21030E-04 471170 + 515 471171 Ag-117m 1.66390E-04 2.50250E-04 471171 + 516 471180 Ag-118 3.34730E-05 1.72190E-04 471180 + 517 471181 Ag-118m 1.62280E-04 1.73550E-04 471181 + 518 471190 Ag-119 2.92170E-05 4.60960E-05 471190 + 519 471191 Ag-119m 2.19440E-04 2.36320E-04 471191 + 520 471200 Ag-120 2.86200E-05 5.76280E-05 471200 + 521 471201 Ag-120m 4.78630E-05 5.60640E-05 471201 + 522 471210 Ag-121 6.59060E-05 8.93670E-05 471210 + 523 471220 Ag-122 2.23420E-05 2.89180E-05 471220 + 524 471221 Ag-122m 2.40880E-05 2.40880E-05 471221 + 525 471230 Ag-123 3.36530E-05 3.42040E-05 471230 + 526 471240 Ag-124 8.35600E-06 1.29340E-05 471240 + 527 471241 Ag-124m 9.00900E-06 9.00900E-06 471241 + 528 471250 Ag-125 2.67600E-06 2.67600E-06 471250 + 529 471260 Ag-126 1.90060E-06 1.90060E-06 471260 + 530 471270 Ag-127 9.91550E-08 9.91550E-08 471270 + 531 471280 Ag-128 3.39580E-09 3.39580E-09 471280 + 532 481110 Cd-111 2.32670E-11 4.05980E-03 48111.82c + 533 481111 Cd-111m 8.81130E-11 8.81130E-11 481111 + 534 481120 Cd-112 2.93540E-09 1.42750E-03 48112.82c + 535 481130 Cd-113 1.29640E-08 1.27510E-03 48113.82c + 536 481131 Cd-113m 4.90930E-08 1.46740E-05 481131 + 537 481140 Cd-114 1.10730E-06 9.63760E-04 48114.82c + 538 481150 Cd-115 1.39510E-06 7.29150E-04 481150 + 539 481151 Cd-115m 5.28310E-06 3.82370E-05 48515.82c + 540 481160 Cd-116 1.56950E-05 6.24200E-04 48116.82c + 541 481170 Cd-117 9.84690E-06 2.87360E-04 481170 + 542 481171 Cd-117m 3.72900E-05 1.16050E-04 481171 + 543 481180 Cd-118 1.25270E-04 3.99850E-04 481180 + 544 481190 Cd-119 5.40790E-05 3.13450E-04 481190 + 545 481191 Cd-119m 1.51310E-04 1.74360E-04 481191 + 546 481200 Cd-120 2.83970E-04 3.76920E-04 481200 + 547 481210 Cd-121 5.39080E-05 1.33940E-04 481210 + 548 481211 Cd-121m 1.50830E-04 1.60170E-04 481211 + 549 481220 Cd-122 2.26100E-04 2.79110E-04 481220 + 550 481230 Cd-123 3.79840E-05 6.59740E-05 481230 + 551 481231 Cd-123m 1.06280E-04 1.12500E-04 481231 + 552 481240 Cd-124 3.02690E-04 3.20120E-04 481240 + 553 481250 Cd-125 6.13250E-05 6.26630E-05 481250 + 554 481251 Cd-125m 1.71590E-04 1.72920E-04 481251 + 555 481260 Cd-126 1.37320E-04 1.39220E-04 481260 + 556 481270 Cd-127 9.88520E-05 9.89510E-05 481270 + 557 481280 Cd-128 2.82460E-05 2.82490E-05 481280 + 558 481290 Cd-129 6.76810E-07 6.76810E-07 481290 + 559 481291 Cd-129m 1.89370E-06 1.89370E-06 481291 + 560 481300 Cd-130 1.09130E-07 1.09130E-07 481300 + 561 481310 Cd-131 2.32790E-09 2.32790E-09 481310 + 562 491140 In-114 4.10700E-11 1.79160E-10 491140 + 563 491141 In-114m 6.63200E-11 1.43100E-10 491141 + 564 491142 In-114m 7.67800E-11 7.67800E-11 491142 + 565 491150 In-115 6.40250E-09 7.30940E-04 49115.82c + 566 491151 In-115m 1.28910E-09 7.29160E-04 491151 + 567 491160 In-116 2.48940E-08 2.48940E-08 491160 + 568 491161 In-116m 4.01980E-08 8.67370E-08 491161 + 569 491162 In-116m 4.65380E-08 4.65380E-08 491162 + 570 491170 In-117 1.10230E-06 2.64370E-04 491170 + 571 491171 In-117m 2.21940E-07 2.65330E-04 491171 + 572 491180 In-118 4.74280E-07 4.00320E-04 491180 + 573 491181 In-118m 7.65860E-07 1.64010E-06 491181 + 574 491182 In-118m 8.86660E-07 8.86660E-07 491182 + 575 491190 In-119 1.53200E-05 2.35810E-04 491190 + 576 491191 In-119m 3.08450E-06 2.86440E-04 491191 + 577 491200 In-120 1.72830E-05 3.94200E-04 491200 + 578 491201 In-120m 1.72830E-05 1.72830E-05 491201 + 579 491202 In-120m 1.72830E-05 1.72830E-05 491202 + 580 491210 In-121 6.26360E-05 2.69130E-04 491210 + 581 491211 In-121m 1.26120E-05 1.01440E-04 491211 + 582 491220 In-122 4.41970E-05 3.23300E-04 491220 + 583 491221 In-122m 3.69570E-05 3.69570E-05 491221 + 584 491222 In-122m 3.69570E-05 3.69570E-05 491222 + 585 491230 In-123 1.80870E-04 3.12440E-04 491230 + 586 491231 In-123m 3.64180E-05 8.33300E-05 491231 + 587 491240 In-124 1.38600E-04 4.58710E-04 491240 + 588 491241 In-124m 1.49430E-04 1.49430E-04 491241 + 589 491250 In-125 6.45580E-04 8.48500E-04 491250 + 590 491251 In-125m 1.29990E-04 1.62660E-04 491251 + 591 491260 In-126 4.66470E-04 6.05700E-04 491260 + 592 491261 In-126m 5.02920E-04 5.02920E-04 491261 + 593 491270 In-127 1.66700E-03 1.66700E-03 491270 + 594 491271 In-127m 3.35650E-04 4.34600E-04 491271 + 595 491280 In-128 4.48850E-04 6.52850E-04 491280 + 596 491281 In-128m 1.75750E-04 2.04000E-04 491281 + 597 491282 In-128m 6.73400E-04 6.73400E-04 491282 + 598 491290 In-129 6.08110E-04 6.10010E-04 491290 + 599 491291 In-129m 1.22440E-04 1.23120E-04 491291 + 600 491300 In-130 7.20960E-05 7.22010E-05 491300 + 601 491301 In-130m 1.04980E-04 1.04980E-04 491301 + 602 491302 In-130m 1.46230E-04 1.46230E-04 491302 + 603 491310 In-131 1.83180E-05 1.85070E-05 491310 + 604 491311 In-131m 1.83180E-05 1.83180E-05 491311 + 605 491312 In-131m 1.83180E-05 1.83180E-05 491312 + 606 491320 In-132 2.28610E-06 2.28610E-06 491320 + 607 491330 In-133 2.65160E-08 3.18550E-08 491330 + 608 491331 In-133m 5.33890E-09 5.33890E-09 491331 + 609 501160 Sn-116 2.33310E-11 1.11650E-07 50116.82c + 610 501170 Sn-117 1.16840E-10 4.04730E-04 50117.82c + 611 501171 Sn-117m 4.42460E-10 9.01180E-07 501171 + 612 501180 Sn-118 2.38810E-08 4.02000E-04 50118.82c + 613 501190 Sn-119 8.45420E-08 5.06620E-04 50119.82c + 614 501191 Sn-119m 3.20160E-07 2.13360E-04 501191 + 615 501200 Sn-120 4.81510E-06 4.33580E-04 50120.82c + 616 501210 Sn-121 1.85660E-06 3.68410E-04 501210 + 617 501211 Sn-121m 5.19460E-06 3.56830E-05 501211 + 618 501220 Sn-122 2.31250E-05 4.20340E-04 50122.82c + 619 501230 Sn-123 3.82720E-05 6.20920E-05 50123.82c + 620 501231 Sn-123m 1.36780E-05 3.85620E-04 501231 + 621 501240 Sn-124 1.33440E-04 7.41580E-04 50124.82c + 622 501250 Sn-125 2.75360E-04 4.18690E-04 50125.82c + 623 501251 Sn-125m 9.84140E-05 9.66240E-04 501251 + 624 501260 Sn-126 1.01800E-03 2.12960E-03 50126.82c + 625 501270 Sn-127 2.24440E-03 2.89410E-03 501270 + 626 501271 Sn-127m 8.02140E-04 2.25100E-03 501271 + 627 501280 Sn-128 1.79670E-03 8.02050E-03 501280 + 628 501281 Sn-128m 4.89750E-03 5.57090E-03 501281 + 629 501290 Sn-129 1.71040E-03 2.37860E-03 501290 + 630 501291 Sn-129m 4.78550E-03 4.85050E-03 501291 + 631 501300 Sn-130 2.92560E-03 3.12330E-03 501300 + 632 501301 Sn-130m 7.97440E-03 8.10050E-03 501301 + 633 501310 Sn-131 1.33560E-03 1.37110E-03 501310 + 634 501311 Sn-131m 3.73710E-03 3.75620E-03 501311 + 635 501320 Sn-132 1.68950E-03 1.69180E-03 501320 + 636 501330 Sn-133 1.68770E-04 1.68770E-04 501330 + 637 501340 Sn-134 1.07740E-05 1.07740E-05 501340 + 638 501350 Sn-135 1.90420E-07 1.90420E-07 501350 + 639 501360 Sn-136 5.20160E-09 5.20160E-09 501360 + 640 511190 Sb-119 8.09750E-11 1.13490E-10 511190 + 641 511191 Sb-119m 3.25150E-11 3.25150E-11 511191 + 642 511200 Sb-120 1.11020E-09 1.11020E-09 511200 + 643 511201 Sb-120m 1.85670E-09 1.85670E-09 511201 + 644 511220 Sb-122 4.20200E-12 9.83160E-12 511220 + 645 511221 Sb-122m 5.62960E-12 5.62960E-12 511221 + 646 511230 Sb-123 1.86740E-06 4.49580E-04 51123.82c + 647 511240 Sb-124 1.12000E-06 2.88250E-06 51124.82c + 648 511241 Sb-124m 9.03480E-07 2.35000E-06 511241 + 649 511242 Sb-124m 1.44650E-06 1.44650E-06 511242 + 650 511250 Sb-125 2.00180E-05 1.40490E-03 51125.82c + 651 511260 Sb-126 3.30830E-05 3.95620E-05 51126.82c + 652 511261 Sb-126m 2.06640E-05 4.62790E-05 511261 + 653 511262 Sb-126m 2.56150E-05 2.56150E-05 511262 + 654 511270 Sb-127 4.95410E-04 5.64060E-03 511270 + 655 511280 Sb-128 6.39360E-04 8.69210E-03 511280 + 656 511281 Sb-128m 8.94240E-04 8.94240E-04 511281 + 657 511290 Sb-129 3.08850E-03 8.59900E-03 511290 + 658 511291 Sb-129m 2.28570E-03 4.71080E-03 511291 + 659 511300 Sb-130 7.50100E-03 1.46750E-02 511300 + 660 511301 Sb-130m 7.50100E-03 1.15510E-02 511301 + 661 511310 Sb-131 2.30210E-02 2.81480E-02 511310 + 662 511320 Sb-132 9.47980E-03 1.11720E-02 511320 + 663 511321 Sb-132m 8.39320E-03 8.39320E-03 511321 + 664 511330 Sb-133 1.29970E-02 1.31680E-02 511330 + 665 511340 Sb-134 7.55920E-04 7.64880E-04 511340 + 666 511341 Sb-134m 2.06050E-03 2.06050E-03 511341 + 667 511350 Sb-135 4.75740E-04 4.75890E-04 511350 + 668 511360 Sb-136 5.77350E-05 5.77390E-05 511360 + 669 511370 Sb-137 5.30260E-06 5.30260E-06 511370 + 670 511380 Sb-138 1.90270E-08 1.90270E-08 511380 + 671 521250 Te-125 2.79420E-07 1.40630E-03 52125.82c + 672 521251 Te-125m 1.05820E-06 3.15440E-04 521251 + 673 521260 Te-126 1.90000E-06 8.12620E-05 52126.82c + 674 521270 Te-127 4.45950E-06 5.63490E-03 521270 + 675 521271 Te-127m 1.24780E-05 9.42010E-04 52527.82c + 676 521280 Te-128 1.09350E-04 9.66350E-03 52128.82c + 677 521290 Te-129 1.40910E-04 1.10180E-02 521290 + 678 521291 Te-129m 3.94270E-04 5.73170E-03 52529.82c + 679 521300 Te-130 4.91030E-03 3.11360E-02 52130.82c + 680 521310 Te-131 3.26120E-03 3.15450E-02 521310 + 681 521311 Te-131m 9.12480E-03 1.13780E-02 521311 + 682 521320 Te-132 3.11480E-02 5.07130E-02 52132.82c + 683 521330 Te-133 1.24260E-02 2.98020E-02 521330 + 684 521331 Te-133m 3.47690E-02 3.70460E-02 521331 + 685 521340 Te-134 4.61080E-02 4.90060E-02 521340 + 686 521350 Te-135 1.52510E-02 1.56620E-02 521350 + 687 521360 Te-136 5.24730E-03 5.29810E-03 521360 + 688 521370 Te-137 9.82390E-04 9.85090E-04 521370 + 689 521380 Te-138 1.44230E-04 1.44250E-04 521380 + 690 521390 Te-139 1.10980E-05 1.10980E-05 521390 + 691 521400 Te-140 1.90090E-07 1.90090E-07 521400 + 692 521410 Te-141 2.79990E-09 2.79990E-09 521410 + 693 531270 I-127 1.87440E-10 5.65750E-03 53127.82c + 694 531280 I-128 9.70230E-09 9.70230E-09 531280 + 695 531290 I-129 4.28250E-06 1.31430E-02 53129.82c + 696 531300 I-130 2.55330E-05 3.34010E-05 53130.82c + 697 531301 I-130m 9.36720E-06 9.36720E-06 531301 + 698 531310 I-131 3.92020E-04 4.09260E-02 53131.82c + 699 531320 I-132 9.56470E-04 5.23980E-02 531320 + 700 531321 I-132m 8.46830E-04 8.46830E-04 531321 + 701 531330 I-133 5.72090E-03 7.03190E-02 531330 + 702 531331 I-133m 4.23370E-03 4.23370E-03 531331 + 703 531340 I-134 1.27050E-02 7.27020E-02 531340 + 704 531341 I-134m 1.12490E-02 1.12490E-02 531341 + 705 531350 I-135 4.95360E-02 6.51980E-02 53135.82c + 706 531360 I-136 7.84800E-03 1.31610E-02 531360 + 707 531361 I-136m 2.13920E-02 2.14070E-02 531361 + 708 531370 I-137 1.87030E-02 1.96680E-02 531370 + 709 531380 I-138 5.08990E-03 5.22510E-03 531380 + 710 531390 I-139 2.67080E-03 2.68190E-03 531390 + 711 531400 I-140 4.36140E-04 4.36330E-04 531400 + 712 531410 I-141 8.00960E-05 8.00990E-05 531410 + 713 531420 I-142 6.63020E-06 6.63020E-06 531420 + 714 531430 I-143 1.97880E-06 1.97880E-06 531430 + 715 541300 Xe-130 7.11710E-09 3.49070E-05 54130.82c + 716 541310 Xe-131 7.53910E-08 4.09270E-02 54131.82c + 717 541311 Xe-131m 2.10940E-07 4.44750E-04 541311 + 718 541320 Xe-132 1.66090E-05 5.25550E-02 54132.82c + 719 541321 Xe-132m 2.22510E-05 2.22510E-05 541321 + 720 541330 Xe-133 7.88740E-05 7.06190E-02 54133.82c + 721 541331 Xe-133m 2.20690E-04 2.22220E-03 541331 + 722 541340 Xe-134 6.06610E-04 7.52200E-02 54134.82c + 723 541341 Xe-134m 1.65350E-03 1.91220E-03 541341 + 724 541350 Xe-135 2.60760E-03 7.49930E-02 54135.82c + 725 541351 Xe-135m 7.29600E-03 1.80590E-02 541351 + 726 541360 Xe-136 3.53690E-02 7.12150E-02 54136.82c + 727 541370 Xe-137 3.93430E-02 5.80090E-02 541370 + 728 541380 Xe-138 4.04040E-02 4.56150E-02 541380 + 729 541390 Xe-139 2.47610E-02 2.72210E-02 541390 + 730 541400 Xe-140 1.68330E-02 1.72460E-02 541400 + 731 541410 Xe-141 5.26800E-03 5.33290E-03 541410 + 732 541420 Xe-142 1.39990E-03 1.40570E-03 541420 + 733 541430 Xe-143 2.25320E-04 2.26510E-04 541430 + 734 541440 Xe-144 3.57470E-05 3.57470E-05 541440 + 735 541450 Xe-145 8.14840E-08 8.14840E-08 541450 + 736 541460 Xe-146 1.85310E-09 1.85310E-09 541460 + 737 551320 Cs-132 1.25350E-09 1.25350E-09 551320 + 738 551330 Cs-133 8.87370E-08 7.06190E-02 55133.82c + 739 551340 Cs-134 2.28560E-06 4.30920E-06 55134.82c + 740 551341 Cs-134m 2.02360E-06 2.02360E-06 551341 + 741 551350 Cs-135 4.53520E-05 7.51800E-02 55135.82c + 742 551351 Cs-135m 3.35620E-05 3.35620E-05 551351 + 743 551360 Cs-136 3.51220E-04 4.76770E-04 55136.82c + 744 551361 Cs-136m 2.51110E-04 2.51110E-04 551361 + 745 551370 Cs-137 5.08900E-03 6.30980E-02 55137.82c + 746 551380 Cs-138 4.06310E-03 5.51820E-02 551380 + 747 551381 Cs-138m 6.79490E-03 6.79490E-03 551381 + 748 551390 Cs-139 2.29280E-02 5.01490E-02 551390 + 749 551400 Cs-140 2.23450E-02 3.95930E-02 551400 + 750 551410 Cs-141 2.58730E-02 3.12090E-02 551410 + 751 551420 Cs-142 1.33740E-02 1.47770E-02 551420 + 752 551430 Cs-143 6.74960E-03 6.97490E-03 551430 + 753 551440 Cs-144 8.85650E-04 1.36320E-03 551440 + 754 551441 Cs-144m 8.85650E-04 8.85650E-04 551441 + 755 551450 Cs-145 4.09240E-04 4.09320E-04 551450 + 756 551460 Cs-146 5.16110E-05 5.16130E-05 551460 + 757 551470 Cs-147 7.41200E-06 7.41200E-06 551470 + 758 551480 Cs-148 6.05600E-09 6.05600E-09 551480 + 759 561350 Ba-135 2.69540E-09 1.02370E-08 56135.82c + 760 561351 Ba-135m 7.54160E-09 7.54160E-09 561351 + 761 561360 Ba-136 1.19260E-06 6.06770E-04 56136.82c + 762 561361 Ba-136m 3.25070E-06 3.25070E-06 561361 + 763 561370 Ba-137 2.11850E-05 6.31790E-02 56137.82c + 764 561371 Ba-137m 5.92730E-05 5.96240E-02 561371 + 765 561380 Ba-138 1.05000E-03 5.75230E-02 56138.82c + 766 561390 Ba-139 3.99890E-03 5.41480E-02 561390 + 767 561400 Ba-140 1.33230E-02 5.29160E-02 56140.82c + 768 561410 Ba-141 1.76640E-02 4.88730E-02 561410 + 769 561420 Ba-142 3.28290E-02 4.77200E-02 561420 + 770 561430 Ba-143 2.77710E-02 3.46750E-02 561430 + 771 561440 Ba-144 2.01840E-02 2.20050E-02 561440 + 772 561450 Ba-145 8.70660E-03 9.06470E-03 561450 + 773 561460 Ba-146 3.40600E-03 3.45240E-03 561460 + 774 561470 Ba-147 8.19270E-04 8.24570E-04 561470 + 775 561480 Ba-148 1.76280E-04 1.76290E-04 561480 + 776 561490 Ba-149 2.03650E-05 2.03650E-05 561490 + 777 561500 Ba-150 4.00760E-06 4.00760E-06 561500 + 778 561510 Ba-151 4.45430E-10 4.45430E-10 561510 + 779 571370 La-137 2.03640E-09 2.03640E-09 571370 + 780 571380 La-138 5.30030E-08 5.30030E-08 57138.82c + 781 571390 La-139 2.01870E-05 5.41680E-02 57139.82c + 782 571400 La-140 1.50840E-04 5.30670E-02 57140.82c + 783 571410 La-141 7.63220E-04 4.96360E-02 571410 + 784 571420 La-142 1.84210E-03 4.95620E-02 571420 + 785 571430 La-143 7.53140E-03 4.22070E-02 571430 + 786 571440 La-144 1.11300E-02 3.31350E-02 571440 + 787 571450 La-145 1.63260E-02 2.53910E-02 571450 + 788 571460 La-146 3.28740E-03 6.73980E-03 571460 + 789 571461 La-146m 6.89660E-03 6.89660E-03 571461 + 790 571470 La-147 6.66940E-03 7.49470E-03 571470 + 791 571480 La-148 2.79200E-03 2.96770E-03 571480 + 792 571490 La-149 1.04900E-03 1.06930E-03 571490 + 793 571500 La-150 2.03630E-04 2.07640E-04 571500 + 794 571510 La-151 3.96860E-05 3.96860E-05 571510 + 795 571520 La-152 8.40780E-08 8.40780E-08 571520 + 796 571530 La-153 2.49180E-09 2.49180E-09 571530 + 797 581400 Ce-140 1.06710E-06 5.30680E-02 58140.82c + 798 581410 Ce-141 7.19150E-06 4.96430E-02 58141.82c + 799 581420 Ce-142 1.02700E-04 4.96650E-02 58142.82c + 800 581430 Ce-143 3.61390E-04 4.25680E-02 58143.82c + 801 581440 Ce-144 1.85950E-03 3.49940E-02 58144.82c + 802 581450 Ce-145 4.72790E-03 3.01190E-02 581450 + 803 581460 Ce-146 1.12810E-02 2.49170E-02 581460 + 804 581470 Ce-147 1.10550E-02 1.85500E-02 581470 + 805 581480 Ce-148 1.21690E-02 1.51520E-02 581480 + 806 581490 Ce-149 7.32790E-03 8.38780E-03 581490 + 807 581500 Ce-150 4.18380E-03 4.38580E-03 581500 + 808 581510 Ce-151 1.32200E-03 1.36170E-03 581510 + 809 581520 Ce-152 3.59250E-04 3.59330E-04 581520 + 810 581530 Ce-153 5.83930E-05 5.83960E-05 581530 + 811 581540 Ce-154 7.80260E-06 7.80260E-06 581540 + 812 581550 Ce-155 5.53650E-09 5.53650E-09 581550 + 813 581560 Ce-156 9.62560E-11 9.62560E-11 581560 + 814 591420 Pr-142 3.14380E-10 1.17130E-09 59142.82c + 815 591421 Pr-142m 8.56920E-10 8.56920E-10 591421 + 816 591430 Pr-143 5.31220E-08 4.25680E-02 59143.82c + 817 591440 Pr-144 9.03140E-07 3.50040E-02 591440 + 818 591441 Pr-144m 9.18790E-06 4.92090E-04 591441 + 819 591450 Pr-145 5.01250E-05 3.01690E-02 591450 + 820 591460 Pr-146 1.85310E-04 2.51030E-02 591460 + 821 591470 Pr-147 7.78580E-04 1.93280E-02 591470 + 822 591480 Pr-148 2.90770E-04 1.54420E-02 591480 + 823 591481 Pr-148m 1.40960E-03 1.40960E-03 591481 + 824 591490 Pr-149 3.99870E-03 1.23860E-02 591490 + 825 591500 Pr-150 4.18690E-03 8.57270E-03 591500 + 826 591510 Pr-151 4.00480E-03 5.36650E-03 591510 + 827 591520 Pr-152 2.02040E-03 2.38010E-03 591520 + 828 591530 Pr-153 1.10250E-03 1.16060E-03 591530 + 829 591540 Pr-154 2.39600E-04 2.47350E-04 591540 + 830 591550 Pr-155 5.04330E-05 5.04390E-05 591550 + 831 591560 Pr-156 6.74170E-06 6.74180E-06 591560 + 832 591570 Pr-157 1.95870E-08 1.95870E-08 591570 + 833 591580 Pr-158 2.13450E-10 2.13450E-10 591580 + 834 601450 Nd-145 4.24390E-09 3.01690E-02 60145.82c + 835 601460 Nd-146 1.84610E-06 2.51050E-02 60146.82c + 836 601470 Nd-147 1.56710E-05 1.93440E-02 60147.82c + 837 601480 Nd-148 1.31270E-04 1.69830E-02 60148.82c + 838 601490 Nd-149 4.63890E-04 1.28500E-02 601490 + 839 601500 Nd-150 1.52210E-03 1.00950E-02 60150.82c + 840 601510 Nd-151 2.63320E-03 7.99970E-03 601510 + 841 601520 Nd-152 3.78320E-03 6.16330E-03 601520 + 842 601530 Nd-153 3.54980E-03 4.71040E-03 601530 + 843 601540 Nd-154 2.00190E-03 2.24920E-03 601540 + 844 601550 Nd-155 8.72670E-04 9.23290E-04 601550 + 845 601560 Nd-156 2.79760E-04 2.86320E-04 601560 + 846 601570 Nd-157 8.94710E-05 8.94890E-05 601570 + 847 601580 Nd-158 1.07220E-06 1.07240E-06 601580 + 848 601590 Nd-159 1.28640E-06 1.28640E-06 601590 + 849 601600 Nd-160 4.74060E-10 4.74060E-10 601600 + 850 601610 Nd-161 3.86390E-12 3.86390E-12 601610 + 851 611470 Pm-147 6.13840E-10 1.93440E-02 61147.82c + 852 611480 Pm-148 4.00940E-09 4.55580E-09 61148.82c + 853 611481 Pm-148m 1.09290E-08 1.09290E-08 61548.82c + 854 611490 Pm-149 1.85300E-06 1.28520E-02 61149.82c + 855 611500 Pm-150 7.01480E-06 7.01480E-06 611500 + 856 611510 Pm-151 5.79910E-05 8.05770E-03 61151.82c + 857 611520 Pm-152 2.71750E-05 6.19050E-03 611520 + 858 611521 Pm-152m 5.71320E-05 5.71320E-05 611521 + 859 611522 Pm-152m 7.46290E-05 7.46290E-05 611522 + 860 611530 Pm-153 5.66910E-04 5.27730E-03 611530 + 861 611540 Pm-154 2.83230E-04 2.53250E-03 611540 + 862 611541 Pm-154m 2.83230E-04 2.83230E-04 611541 + 863 611550 Pm-155 8.35230E-04 1.75850E-03 611550 + 864 611560 Pm-156 5.53030E-04 8.39350E-04 611560 + 865 611570 Pm-157 3.99080E-04 4.88570E-04 611570 + 866 611580 Pm-158 1.28440E-04 1.29510E-04 611580 + 867 611590 Pm-159 2.57340E-05 2.70170E-05 611590 + 868 611600 Pm-160 4.29790E-06 4.29840E-06 611600 + 869 611610 Pm-161 8.70880E-07 8.70880E-07 611610 + 870 611620 Pm-162 4.31320E-10 4.31320E-10 611620 + 871 611630 Pm-163 7.93790E-12 7.93790E-12 611630 + 872 621500 Sm-150 1.92360E-09 7.01670E-06 62150.82c + 873 621510 Sm-151 1.07510E-06 8.05880E-03 62151.82c + 874 621520 Sm-152 1.08660E-05 6.33310E-03 62152.82c + 875 621530 Sm-153 9.53170E-06 5.31350E-03 62153.82c + 876 621531 Sm-153m 2.66690E-05 2.66690E-05 621531 + 877 621540 Sm-154 8.99500E-05 2.90570E-03 62154.82c + 878 621550 Sm-155 2.37940E-04 1.99650E-03 621550 + 879 621560 Sm-156 4.40200E-04 1.27950E-03 621560 + 880 621570 Sm-157 5.31910E-04 1.02050E-03 621570 + 881 621580 Sm-158 4.20460E-04 5.49980E-04 621580 + 882 621590 Sm-159 1.64720E-04 1.91740E-04 621590 + 883 621600 Sm-160 6.01870E-05 6.44740E-05 621600 + 884 621610 Sm-161 1.91630E-05 2.00340E-05 621610 + 885 621620 Sm-162 5.82440E-06 5.82480E-06 621620 + 886 621630 Sm-163 2.22410E-08 2.22490E-08 621630 + 887 621640 Sm-164 1.02880E-09 1.02880E-09 621640 + 888 621650 Sm-165 1.48090E-11 1.48090E-11 621650 + 889 631520 Eu-152 5.76780E-11 1.34070E-10 63152.82c + 890 631521 Eu-152m 1.31790E-11 1.31790E-11 631521 + 891 631522 Eu-152m 7.63930E-11 7.63930E-11 631522 + 892 631530 Eu-153 6.14660E-09 5.31350E-03 63153.82c + 893 631540 Eu-154 4.04840E-08 8.41320E-08 63154.82c + 894 631541 Eu-154m 4.36480E-08 4.36480E-08 631541 + 895 631550 Eu-155 5.04400E-06 2.00150E-03 63155.82c + 896 631560 Eu-156 6.74020E-06 1.28630E-03 63156.82c + 897 631570 Eu-157 3.20400E-05 1.05250E-03 63157.82c + 898 631580 Eu-158 4.17510E-05 5.91730E-04 631580 + 899 631590 Eu-159 8.35590E-05 2.75300E-04 631590 + 900 631600 Eu-160 4.61910E-05 1.10660E-04 631600 + 901 631610 Eu-161 2.61260E-05 4.61600E-05 631610 + 902 631620 Eu-162 9.15230E-06 1.49770E-05 631620 + 903 631630 Eu-163 6.46550E-06 6.48770E-06 631630 + 904 631640 Eu-164 2.54390E-07 2.55420E-07 631640 + 905 631650 Eu-165 2.66250E-08 2.66400E-08 631650 + 906 631660 Eu-166 5.80650E-10 5.80650E-10 631660 + 907 631670 Eu-167 9.37350E-11 9.37350E-11 631670 + 908 641550 Gd-155 7.28870E-11 2.00150E-03 64155.82c + 909 641551 Gd-155m 2.03930E-10 2.03930E-10 641551 + 910 641560 Gd-156 1.09250E-08 1.28630E-03 64156.82c + 911 641570 Gd-157 1.68490E-07 1.05270E-03 64157.82c + 912 641580 Gd-158 7.45770E-06 5.99190E-04 64158.82c + 913 641590 Gd-159 1.92880E-05 2.94590E-04 641590 + 914 641600 Gd-160 1.50390E-05 1.25700E-04 64160.82c + 915 641610 Gd-161 2.17680E-05 6.79280E-05 641610 + 916 641620 Gd-162 1.58070E-05 3.07840E-05 641620 + 917 641630 Gd-163 1.00570E-05 1.65450E-05 641630 + 918 641640 Gd-164 5.91320E-06 6.16860E-06 641640 + 919 641650 Gd-165 3.45670E-06 3.48330E-06 641650 + 920 641660 Gd-166 6.28420E-07 6.29000E-07 641660 + 921 641670 Gd-167 6.26130E-08 6.27070E-08 641670 + 922 641680 Gd-168 8.16590E-10 8.16590E-10 641680 + 923 641690 Gd-169 6.17090E-11 6.17090E-11 641690 + 924 651570 Tb-157 3.37700E-11 3.37700E-11 651570 + 925 651580 Tb-158 4.66430E-10 5.12000E-10 651580 + 926 651581 Tb-158m 4.58490E-11 4.58490E-11 651581 + 927 651590 Tb-159 1.15000E-08 2.94600E-04 65159.82c + 928 651600 Tb-160 6.98780E-08 6.98780E-08 65160.82c + 929 651610 Tb-161 1.74170E-06 6.96700E-05 651610 + 930 651620 Tb-162 1.20330E-06 3.19870E-05 651620 + 931 651630 Tb-163 3.31110E-06 1.98560E-05 651630 + 932 651640 Tb-164 2.53410E-06 8.70270E-06 651640 + 933 651650 Tb-165 8.64160E-07 4.34750E-06 651650 + 934 651660 Tb-166 1.25690E-06 1.88590E-06 651660 + 935 651670 Tb-167 2.44700E-06 2.50970E-06 651670 + 936 651680 Tb-168 5.21030E-08 5.29200E-08 651680 + 937 651690 Tb-169 2.74920E-08 2.75540E-08 651690 + 938 651700 Tb-170 1.71040E-09 1.71040E-09 651700 + 939 651710 Tb-171 1.00790E-10 1.00790E-10 651710 + 940 661600 Dy-160 2.34690E-11 6.99010E-08 66160.82c + 941 661610 Dy-161 4.30820E-10 6.96700E-05 66161.82c + 942 661620 Dy-162 6.53680E-09 3.19940E-05 66162.82c + 943 661630 Dy-163 3.78190E-08 1.98940E-05 66163.82c + 944 661640 Dy-164 8.44710E-07 9.54760E-06 66164.82c + 945 661650 Dy-165 7.62610E-07 5.20940E-06 661650 + 946 661651 Dy-165m 1.01540E-07 1.01540E-07 661651 + 947 661660 Dy-166 7.12630E-07 2.59850E-06 661660 + 948 661670 Dy-167 2.44690E-06 4.95660E-06 661670 + 949 661680 Dy-168 3.70560E-07 4.23480E-07 661680 + 950 661690 Dy-169 3.51660E-07 3.79210E-07 661690 + 951 661700 Dy-170 1.39400E-07 1.41110E-07 661700 + 952 661710 Dy-171 1.69980E-08 1.70990E-08 661710 + 953 661720 Dy-172 2.31530E-09 2.31530E-09 661720 + 954 661730 Dy-173 1.14240E-10 1.14240E-10 661730 + 955 671630 Ho-163 1.63460E-11 1.85220E-11 671630 + 956 671631 Ho-163m 2.17630E-12 2.17630E-12 671631 + 957 671640 Ho-164 7.12470E-11 2.65450E-10 671640 + 958 671641 Ho-164m 1.94200E-10 1.94200E-10 671641 + 959 671650 Ho-165 3.83410E-09 5.21550E-06 67165.82c + 960 671660 Ho-166 3.06220E-09 2.60160E-06 671660 + 961 671661 Ho-166m 8.34680E-09 8.34680E-09 671661 + 962 671670 Ho-167 2.55720E-07 5.21230E-06 671670 + 963 671680 Ho-168 1.66680E-07 8.67530E-07 671680 + 964 671681 Ho-168m 2.78760E-07 2.78760E-07 671681 + 965 671690 Ho-169 3.45330E-07 7.24540E-07 671690 + 966 671700 Ho-170 1.66710E-07 1.66710E-07 671700 + 967 671701 Ho-170m 6.11600E-08 2.02270E-07 671701 + 968 671710 Ho-171 1.58730E-07 1.75830E-07 671710 + 969 671720 Ho-172 4.03670E-08 4.26820E-08 671720 + 970 671730 Ho-173 1.31360E-08 1.32500E-08 671730 + 971 671740 Ho-174 1.24870E-09 1.24870E-09 671740 + 972 671750 Ho-175 1.37610E-10 1.37610E-10 671750 + 973 681660 Er-166 1.54870E-11 2.60160E-06 68166.82c + 974 681670 Er-167 6.71990E-10 5.21310E-06 68167.82c + 975 681671 Er-167m 8.94720E-11 6.22920E-07 681671 + 976 681680 Er-168 1.35820E-09 8.70280E-07 68168.82c + 977 681690 Er-169 1.40700E-08 7.38610E-07 681690 + 978 681700 Er-170 5.61130E-08 4.25090E-07 68170.82c + 979 681710 Er-171 6.71140E-08 2.42940E-07 681710 + 980 681720 Er-172 9.31370E-08 1.35820E-07 681720 + 981 681730 Er-173 5.12600E-08 6.45100E-08 681730 + 982 681740 Er-174 2.88010E-08 3.00500E-08 681740 + 983 681750 Er-175 6.15010E-09 6.28770E-09 681750 + 984 681760 Er-176 1.53340E-09 1.53340E-09 681760 + 985 681770 Er-177 1.16960E-10 1.16960E-10 681770 + 986 691690 Tm-169 2.80640E-11 7.38640E-07 691690 + 987 691700 Tm-170 2.40900E-10 2.40900E-10 691700 + 988 691710 Tm-171 1.93690E-09 2.44880E-07 691710 + 989 691720 Tm-172 5.13290E-09 1.40950E-07 691720 + 990 691730 Tm-173 1.64610E-08 8.09710E-08 691730 + 991 691740 Tm-174 1.55220E-08 4.55720E-08 691740 + 992 691750 Tm-175 1.81360E-08 2.44240E-08 691750 + 993 691760 Tm-176 7.85550E-09 9.38890E-09 691760 + 994 691770 Tm-177 3.67600E-09 3.79300E-09 691770 + 995 691780 Tm-178 5.50360E-10 5.50360E-10 691780 + 996 691790 Tm-179 1.11630E-10 1.11630E-10 691790 + 997 701710 Yb-171 1.68910E-13 2.44880E-07 701710 + 998 701711 Yb-171m 1.26860E-12 1.26860E-12 701711 + 999 701720 Yb-172 2.75420E-11 1.40980E-07 701720 + 1000 701730 Yb-173 1.85790E-10 8.11570E-08 701730 + 1001 701740 Yb-174 1.14030E-09 4.67130E-08 701740 + 1002 701750 Yb-175 2.16240E-09 2.68740E-08 701750 + 1003 701751 Yb-175m 2.87910E-10 1.90940E-08 701751 + 1004 701760 Yb-176 1.93410E-09 1.45060E-08 701760 + 1005 701761 Yb-176m 4.05760E-09 8.75210E-09 701761 + 1006 701770 Yb-177 3.87440E-09 8.44750E-09 701770 + 1007 701771 Yb-177m 7.80090E-10 4.57310E-09 701771 + 1008 701780 Yb-178 3.87400E-09 4.42440E-09 701780 + 1009 701790 Yb-179 1.41230E-09 1.52390E-09 701790 + 1010 701800 Yb-180 5.61580E-10 5.61580E-10 701800 + 1011 701810 Yb-181 6.87880E-11 6.87880E-11 701810 + 1012 711740 Lu-174 3.34370E-13 1.24050E-12 711740 + 1013 711750 Lu-175 1.89580E-11 2.68930E-08 71175.82c + 1014 711760 Lu-176 6.42120E-11 9.39420E-10 71176.82c + 1015 711761 Lu-176m 3.06080E-11 3.06080E-11 711761 + 1016 711770 Lu-177 3.08420E-10 8.78990E-09 711770 + 1017 711771 Lu-177m 1.46860E-10 1.50510E-10 711771 + 1018 711772 Lu-177m 7.30810E-12 7.30810E-12 711772 + 1019 711780 Lu-178 2.91760E-10 4.71610E-09 711780 + 1020 711781 Lu-178m 3.90880E-10 3.90880E-10 711781 + 1021 711790 Lu-179 1.21180E-09 2.89710E-09 711790 + 1022 711791 Lu-179m 1.61350E-10 1.68530E-09 711791 + 1023 711800 Lu-180 2.41000E-10 8.55670E-10 711800 + 1024 711801 Lu-180m 2.41000E-10 8.02580E-10 711801 + 1025 711802 Lu-180m 4.26750E-10 4.26750E-10 711802 + 1026 711810 Lu-181 6.35530E-10 7.04320E-10 711810 + 1027 711820 Lu-182 1.62420E-10 1.62420E-10 711820 + 1028 711830 Lu-183 5.30390E-11 5.30390E-11 711830 + 1029 711840 Lu-184 5.06090E-12 5.06090E-12 711840 + 1030 721770 Hf-177 9.07120E-13 8.91140E-09 72177.82c + 1031 721771 Hf-177m 4.27980E-13 1.20600E-10 721771 + 1032 721772 Hf-177m 2.53030E-14 3.67940E-12 721772 + 1033 721780 Hf-178 4.48300E-12 5.12090E-09 72178.82c + 1034 721781 Hf-178m 8.36060E-12 4.00290E-10 721781 + 1035 721782 Hf-178m 1.04580E-12 1.04580E-12 721782 + 1036 721790 Hf-179 3.20450E-11 2.95250E-09 72179.82c + 1037 721791 Hf-179m 9.27260E-12 9.27260E-12 721791 + 1038 721792 Hf-179m 1.40090E-11 1.40090E-11 721792 + 1039 721800 Hf-180 7.14810E-11 1.69060E-09 72180.82c + 1040 721801 Hf-180m 1.49960E-10 3.63340E-10 721801 + 1041 721810 Hf-181 2.66040E-10 9.70360E-10 721810 + 1042 721820 Hf-182 1.19760E-10 3.87710E-10 721820 + 1043 721821 Hf-182m 2.51250E-10 2.51250E-10 721821 + 1044 721830 Hf-183 2.04850E-10 2.57890E-10 721830 + 1045 721840 Hf-184 3.72640E-11 3.97940E-11 721840 + 1046 721841 Hf-184m 7.81760E-11 8.07060E-11 721841 + 1047 721850 Hf-185 2.47800E-11 2.47800E-11 721850 + 1048 721860 Hf-186 6.20810E-12 6.20810E-12 721860 + 1049 731810 Ta-181 7.58910E-12 9.77950E-10 73181.82c + 1050 731820 Ta-182 6.52860E-12 1.65950E-10 73182.82c + 1051 731821 Ta-182m 7.13130E-12 1.59420E-10 731821 + 1052 731822 Ta-182m 6.56710E-12 1.52290E-10 731822 + 1053 731830 Ta-183 6.51160E-11 3.23010E-10 731830 + 1054 731840 Ta-184 6.16040E-11 1.82100E-10 731840 + 1055 731850 Ta-185 4.53040E-11 9.71160E-11 731850 + 1056 731851 Ta-185m 2.70320E-11 2.70320E-11 731851 + 1057 731860 Ta-186 3.14690E-11 3.76770E-11 731860 + 1058 731870 Ta-187 1.47730E-11 1.47730E-11 731870 + 1059 731880 Ta-188 2.22180E-12 2.22180E-12 731880 + 1060 741840 W-184 4.47470E-12 1.86580E-10 74184.82c + 1061 741850 W-185 2.54620E-12 1.06790E-10 741850 + 1062 741851 W-185m 7.12410E-12 7.12410E-12 741851 + 1063 741860 W-186 1.69150E-11 6.14410E-11 74186.82c + 1064 741861 W-186m 6.84880E-12 6.84880E-12 741861 + 1065 741870 W-187 1.85200E-11 3.32930E-11 741870 + 1066 741880 W-188 1.54780E-11 1.77000E-11 741880 + 1067 741890 W-189 5.66680E-12 5.66680E-12 741890 + 1068 741900 W-190 9.66390E-13 2.26110E-12 741900 + 1069 741901 W-190m 1.29470E-12 1.29470E-12 741901 + 1070 751870 Re-187 1.82040E-12 3.51130E-11 75187.82c + 1071 751880 Re-188 7.24570E-13 2.03990E-11 751880 + 1072 751881 Re-188m 1.97500E-12 1.97500E-12 751881 + 1073 751890 Re-189 5.45540E-12 1.11220E-11 751890 + 1074 751900 Re-190 1.16930E-12 4.54900E-12 751900 + 1075 751901 Re-190m 2.45300E-12 2.45300E-12 751901 + 1076 751910 Re-191 2.54390E-12 2.54390E-12 751910 + 1077 761910 Os-191 8.33980E-13 3.59810E-12 761910 + 1078 761920 Os-192 6.31570E-13 1.37300E-12 761920 + + Nuclide 94240.82c -- plutonium 240 (Pu-240) + + Neutron-induced fission: + + Interpolation region : 1 / 1 + Interpolation energy : 4.00000E-01 MeV + Number of products : 950 / 1036 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 4.39890E-05 4.39890E-05 1001.82c + 2 10020 H-2 1.34430E-05 1.34430E-05 1002.82c + 3 10030 H-3 1.91790E-04 1.91790E-04 1003.82c + 4 20040 He-4 2.78090E-03 2.78090E-03 2004.82c + 5 220560 Ti-56 1.56370E-12 1.56370E-12 220560 + 6 230560 V-56 1.91200E-12 3.47570E-12 230560 + 7 230570 V-57 6.11000E-12 6.11000E-12 230570 + 8 230580 V-58 5.81490E-12 5.81490E-12 230580 + 9 230590 V-59 9.08550E-12 9.08550E-12 230590 + 10 230600 V-60 2.88940E-12 2.88940E-12 230600 + 11 230610 V-61 1.50510E-12 1.50510E-12 230610 + 12 240570 Cr-57 1.72850E-12 1.24660E-11 240570 + 13 240580 Cr-58 1.21090E-11 1.32720E-11 240580 + 14 240590 Cr-59 2.52140E-11 3.43000E-11 240590 + 15 240600 Cr-60 6.34130E-11 6.63930E-11 240600 + 16 240610 Cr-61 5.09950E-11 5.24100E-11 240610 + 17 240620 Cr-62 6.34870E-11 6.34870E-11 240620 + 18 240630 Cr-63 1.68880E-11 1.68880E-11 240630 + 19 240640 Cr-64 5.74220E-12 5.74220E-12 240640 + 20 250590 Mn-59 6.78000E-12 4.10790E-11 250590 + 21 250600 Mn-60 2.05750E-12 7.08570E-11 250600 + 22 250601 Mn-60m 2.09310E-11 2.09310E-11 250601 + 23 250610 Mn-61 1.35580E-10 1.87990E-10 250610 + 24 250620 Mn-62 1.99220E-10 2.30960E-10 250620 + 25 250621 Mn-62m 3.11990E-11 6.29420E-11 250621 + 26 250630 Mn-63 5.03830E-10 5.20720E-10 250630 + 27 250640 Mn-64 2.74550E-10 2.80290E-10 250640 + 28 250650 Mn-65 2.83620E-10 2.83620E-10 250650 + 29 250660 Mn-66 6.28540E-11 6.28540E-11 250660 + 30 250670 Mn-67 1.72190E-11 1.72190E-11 250670 + 31 250680 Mn-68 1.24490E-12 1.24490E-12 250680 + 32 260600 Fe-60 1.19850E-12 9.05800E-11 260600 + 33 260610 Fe-61 1.07130E-11 1.98700E-10 260610 + 34 260620 Fe-62 1.41610E-10 4.35520E-10 260620 + 35 260630 Fe-63 4.09690E-10 9.30410E-10 260630 + 36 260640 Fe-64 1.65370E-09 1.93400E-09 260640 + 37 260650 Fe-65 2.41040E-09 2.69400E-09 260650 + 38 260660 Fe-66 4.56840E-09 4.63120E-09 260660 + 39 260670 Fe-67 2.07470E-09 2.09190E-09 260670 + 40 260680 Fe-68 1.46840E-09 1.46960E-09 260680 + 41 260690 Fe-69 2.71320E-10 2.71320E-10 260690 + 42 260700 Fe-70 5.38080E-11 5.38080E-11 260700 + 43 260710 Fe-71 3.10830E-12 3.10830E-12 260710 + 44 270620 Co-62 3.08850E-13 4.35830E-10 270620 + 45 270630 Co-63 2.94020E-11 9.59810E-10 270630 + 46 270640 Co-64 1.72900E-10 2.10690E-09 270640 + 47 270650 Co-65 1.90100E-09 4.59500E-09 270650 + 48 270660 Co-66 4.73940E-09 9.37060E-09 270660 + 49 270670 Co-67 1.63040E-08 1.83960E-08 270670 + 50 270680 Co-68 9.68500E-09 1.40440E-08 270680 + 51 270681 Co-68m 7.22900E-09 8.71770E-09 270681 + 52 270690 Co-69 2.77600E-08 2.80120E-08 270690 + 53 270700 Co-70 4.69960E-09 4.69960E-09 270700 + 54 270701 Co-70m 4.69960E-09 4.75340E-09 270701 + 55 270710 Co-71 5.41380E-09 5.41690E-09 270710 + 56 270720 Co-72 7.86830E-10 7.86830E-10 270720 + 57 270730 Co-73 1.22240E-10 1.22240E-10 270730 + 58 270740 Co-74 2.60400E-12 2.60400E-12 270740 + 59 280640 Ni-64 2.10500E-12 2.10900E-09 28064.82c + 60 280650 Ni-65 3.81750E-11 4.63320E-09 280650 + 61 280660 Ni-66 8.08980E-10 1.01800E-08 280660 + 62 280670 Ni-67 3.90490E-09 2.23010E-08 280670 + 63 280680 Ni-68 2.99340E-08 4.86170E-08 280680 + 64 280690 Ni-69 3.25710E-08 6.03030E-08 280690 + 65 280691 Ni-69m 3.25710E-08 3.25710E-08 280691 + 66 280700 Ni-70 1.72480E-07 1.81930E-07 280700 + 67 280710 Ni-71 1.51520E-07 1.56940E-07 280710 + 68 280720 Ni-72 2.02440E-07 2.03230E-07 280720 + 69 280730 Ni-73 5.50310E-08 5.51530E-08 280730 + 70 280740 Ni-74 1.18990E-08 1.19020E-08 280740 + 71 280750 Ni-75 1.88270E-09 1.88270E-09 280750 + 72 280760 Ni-76 4.23380E-10 4.23380E-10 280760 + 73 280770 Ni-77 8.99650E-12 8.99650E-12 280770 + 74 290660 Cu-66 1.47900E-12 1.01810E-08 290660 + 75 290670 Cu-67 6.79250E-11 2.23690E-08 290670 + 76 290680 Cu-68 2.22730E-10 4.93500E-08 290680 + 77 290681 Cu-68m 6.07120E-10 6.07120E-10 290681 + 78 290690 Cu-69 1.47530E-08 1.07630E-07 290690 + 79 290700 Cu-70 3.59430E-09 3.11840E-08 290700 + 80 290701 Cu-70m 4.59020E-08 5.51790E-08 290701 + 81 290702 Cu-70m 3.59430E-09 1.85530E-07 290702 + 82 290710 Cu-71 3.41920E-07 4.98860E-07 290710 + 83 290720 Cu-72 6.18310E-07 8.21540E-07 290720 + 84 290730 Cu-73 2.38340E-06 2.43860E-06 290730 + 85 290740 Cu-74 4.67650E-07 4.79580E-07 290740 + 86 290750 Cu-75 7.00970E-07 7.02820E-07 290750 + 87 290760 Cu-76 1.40940E-07 1.41150E-07 290760 + 88 290761 Cu-76m 1.40940E-07 1.41150E-07 290761 + 89 290770 Cu-77 5.97120E-08 5.97210E-08 290770 + 90 290780 Cu-78 5.07550E-09 5.07550E-09 290780 + 91 290790 Cu-79 4.59160E-10 4.59160E-10 290790 + 92 290800 Cu-80 1.37610E-11 1.37610E-11 290800 + 93 300680 Zn-68 2.20500E-12 4.94490E-08 300680 + 94 300690 Zn-69 1.15340E-11 1.07700E-07 300690 + 95 300691 Zn-69m 5.72850E-11 5.72850E-11 300691 + 96 300700 Zn-70 2.28800E-09 2.37310E-07 300700 + 97 300710 Zn-71 3.78960E-09 5.02650E-07 300710 + 98 300711 Zn-71m 1.88210E-08 1.88210E-08 300711 + 99 300720 Zn-72 3.21530E-07 1.14310E-06 300720 + 100 300730 Zn-73 8.27210E-08 3.00880E-06 300730 + 101 300731 Zn-73m 1.14410E-07 4.87510E-07 300731 + 102 300732 Zn-73m 7.46190E-07 7.46190E-07 300732 + 103 300740 Zn-74 2.70320E-06 3.20740E-06 300740 + 104 300750 Zn-75 3.10690E-06 3.78940E-06 300750 + 105 300760 Zn-76 2.19860E-05 2.22640E-05 300760 + 106 300770 Zn-77 8.78920E-06 9.43400E-06 300770 + 107 300771 Zn-77m 1.17020E-06 1.17020E-06 300771 + 108 300780 Zn-78 1.00440E-05 1.00490E-05 300780 + 109 300790 Zn-79 3.39130E-06 3.39150E-06 300790 + 110 300800 Zn-80 2.35180E-07 2.35190E-07 300800 + 111 300810 Zn-81 8.66400E-09 8.66400E-09 300810 + 112 300820 Zn-82 5.32590E-10 5.32590E-10 300820 + 113 310710 Ga-71 8.81120E-11 5.21560E-07 310710 + 114 310720 Ga-72 1.95530E-09 1.14520E-06 310720 + 115 310721 Ga-72m 1.92200E-10 3.82800E-08 310721 + 116 310730 Ga-73 5.62690E-08 3.43810E-06 310730 + 117 310740 Ga-74 1.04850E-07 2.58900E-06 310740 + 118 310741 Ga-74m 1.04850E-07 3.31220E-06 310741 + 119 310750 Ga-75 6.21450E-06 1.00040E-05 310750 + 120 310760 Ga-76 1.25690E-05 3.48330E-05 310760 + 121 310770 Ga-77 3.32070E-05 4.32260E-05 310770 + 122 310780 Ga-78 3.68260E-05 4.69190E-05 310780 + 123 310790 Ga-79 4.74410E-05 5.07880E-05 310790 + 124 310800 Ga-80 2.84630E-05 2.86990E-05 310800 + 125 310810 Ga-81 2.41900E-05 2.41980E-05 310810 + 126 310820 Ga-82 3.64930E-06 3.64980E-06 310820 + 127 310830 Ga-83 1.82740E-07 1.82740E-07 310830 + 128 310840 Ga-84 6.59190E-09 6.59190E-09 310840 + 129 310850 Ga-85 1.54130E-10 1.54130E-10 310850 + 130 320720 Ge-72 1.20960E-12 1.14520E-06 32072.82c + 131 320730 Ge-73 4.75080E-11 3.43820E-06 32073.82c + 132 320731 Ge-73m 9.56540E-12 3.38770E-06 320731 + 133 320740 Ge-74 2.08820E-09 3.41920E-06 32074.82c + 134 320750 Ge-75 6.50520E-09 1.00590E-05 320750 + 135 320751 Ge-75m 4.88580E-08 4.49010E-07 320751 + 136 320760 Ge-76 2.12940E-06 3.69620E-05 32076.82c + 137 320770 Ge-77 5.86170E-06 1.42230E-05 320770 + 138 320771 Ge-77m 7.80450E-07 4.40070E-05 320771 + 139 320780 Ge-78 7.37410E-05 1.20710E-04 320780 + 140 320790 Ge-79 1.99400E-05 7.66000E-05 320790 + 141 320791 Ge-79m 1.49760E-04 1.49840E-04 320791 + 142 320800 Ge-80 5.08250E-04 5.39830E-04 320800 + 143 320810 Ge-81 3.70850E-04 3.83350E-04 320810 + 144 320811 Ge-81m 7.46690E-05 8.51180E-05 320811 + 145 320820 Ge-82 4.71000E-04 4.73940E-04 320820 + 146 320830 Ge-83 1.67980E-04 1.68100E-04 320830 + 147 320840 Ge-84 4.76580E-05 4.76600E-05 320840 + 148 320850 Ge-85 3.93000E-06 3.93010E-06 320850 + 149 320860 Ge-86 7.23930E-06 7.23930E-06 320860 + 150 320870 Ge-87 2.62830E-09 2.62830E-09 320870 + 151 330750 As-75 9.58430E-12 1.00590E-05 33075.82c + 152 330751 As-75m 3.62960E-11 1.71000E-10 330751 + 153 330760 As-76 3.17190E-09 3.17190E-09 330760 + 154 330770 As-77 1.12770E-07 4.99810E-05 330770 + 155 330780 As-78 1.61520E-06 1.22320E-04 330780 + 156 330790 As-79 1.35720E-05 2.34010E-04 330790 + 157 330800 As-80 7.73770E-05 6.17210E-04 330800 + 158 330810 As-81 2.91960E-04 7.59580E-04 330810 + 159 330820 As-82 1.44140E-04 6.18080E-04 330820 + 160 330821 As-82m 5.02210E-04 5.02210E-04 330821 + 161 330830 As-83 1.05590E-03 1.22920E-03 330830 + 162 330840 As-84 3.38240E-04 3.59770E-04 330840 + 163 330841 As-84m 3.38240E-04 3.59770E-04 330841 + 164 330850 As-85 3.65790E-04 3.69170E-04 330850 + 165 330860 As-86 8.89120E-05 9.61510E-05 330860 + 166 330870 As-87 2.65420E-05 2.65450E-05 330870 + 167 330880 As-88 1.05750E-06 1.05750E-06 330880 + 168 330890 As-89 5.12670E-08 5.12670E-08 330890 + 169 330900 As-90 8.30290E-10 8.30290E-10 330900 + 170 340770 Se-77 2.86920E-12 4.99810E-05 34077.82c + 171 340771 Se-77m 2.15500E-11 2.15500E-11 340771 + 172 340780 Se-78 3.48490E-09 1.22320E-04 34078.82c + 173 340790 Se-79 8.50520E-08 2.33980E-04 34079.82c + 174 340791 Se-79m 1.13240E-08 2.28480E-04 340791 + 175 340800 Se-80 4.78240E-06 6.21990E-04 34080.82c + 176 340810 Se-81 9.71690E-06 8.42220E-04 340810 + 177 340811 Se-81m 7.29800E-05 1.00250E-04 340811 + 178 340820 Se-82 3.71190E-04 1.49150E-03 34082.82c + 179 340830 Se-83 8.25540E-04 1.26850E-03 340830 + 180 340831 Se-83m 1.66220E-04 9.53380E-04 340831 + 181 340840 Se-84 2.93460E-03 3.73430E-03 340840 + 182 340850 Se-85 2.90530E-03 3.22500E-03 340850 + 183 340860 Se-86 2.94260E-03 3.01110E-03 340860 + 184 340870 Se-87 1.59860E-03 1.62110E-03 340870 + 185 340880 Se-88 6.17230E-04 6.18290E-04 340880 + 186 340890 Se-89 1.72820E-04 1.72870E-04 340890 + 187 340900 Se-90 4.85510E-05 4.85520E-05 340900 + 188 340910 Se-91 6.28270E-06 6.28270E-06 340910 + 189 340920 Se-92 1.68960E-08 1.68960E-08 340920 + 190 350790 Br-79 3.36560E-12 1.27970E-07 35079.82c + 191 350791 Br-79m 1.27450E-11 1.27450E-11 350791 + 192 350800 Br-80 3.37550E-10 1.51370E-09 350800 + 193 350801 Br-80m 1.17610E-09 1.17610E-09 350801 + 194 350810 Br-81 9.53140E-08 8.42370E-04 35081.82c + 195 350820 Br-82 2.67020E-06 3.62630E-06 350820 + 196 350821 Br-82m 9.79610E-07 9.79610E-07 350821 + 197 350830 Br-83 2.69750E-05 2.24890E-03 350830 + 198 350840 Br-84 8.53800E-05 3.81970E-03 350840 + 199 350841 Br-84m 8.53800E-05 8.53800E-05 350841 + 200 350850 Br-85 9.74860E-04 4.19980E-03 350850 + 201 350860 Br-86 2.34750E-03 5.35860E-03 350860 + 202 350870 Br-87 4.25310E-03 5.88030E-03 350870 + 203 350880 Br-88 2.75650E-03 3.38220E-03 350880 + 204 350890 Br-89 2.79270E-03 2.95210E-03 350890 + 205 350900 Br-90 1.25050E-03 1.30040E-03 350900 + 206 350910 Br-91 6.02780E-04 6.07740E-04 350910 + 207 350920 Br-92 9.46660E-05 9.46830E-05 350920 + 208 350930 Br-93 2.44290E-05 2.44290E-05 350930 + 209 350940 Br-94 1.05630E-07 1.05630E-07 350940 + 210 350950 Br-95 3.12720E-09 3.12720E-09 350950 + 211 360820 Kr-82 8.28480E-10 3.65060E-06 36082.82c + 212 360830 Kr-83 2.75420E-08 2.24890E-03 36083.82c + 213 360831 Kr-83m 5.54540E-09 2.24690E-03 360831 + 214 360840 Kr-84 2.11990E-05 3.92630E-03 36084.82c + 215 360850 Kr-85 5.26680E-05 9.59070E-04 36085.82c + 216 360851 Kr-85m 1.06040E-05 4.20360E-03 360851 + 217 360860 Kr-86 8.34210E-04 6.34040E-03 36086.82c + 218 360870 Kr-87 2.63840E-03 8.59770E-03 360870 + 219 360880 Kr-88 6.18850E-03 9.76030E-03 360880 + 220 360890 Kr-89 1.14500E-02 1.43060E-02 360890 + 221 360900 Kr-90 1.25840E-02 1.36860E-02 360900 + 222 360910 Kr-91 8.95040E-03 9.46790E-03 360910 + 223 360920 Kr-92 5.29330E-03 5.37330E-03 360920 + 224 360930 Kr-93 2.27850E-03 2.28640E-03 360930 + 225 360940 Kr-94 7.18210E-04 7.18240E-04 360940 + 226 360950 Kr-95 1.36910E-04 1.36910E-04 360950 + 227 360960 Kr-96 1.56450E-05 1.56450E-05 360960 + 228 360970 Kr-97 2.94840E-08 2.94840E-08 360970 + 229 370840 Rb-84 2.87550E-11 8.90810E-11 370840 + 230 370841 Rb-84m 6.03260E-11 6.03260E-11 370841 + 231 370850 Rb-85 1.29470E-08 4.26310E-03 37085.82c + 232 370860 Rb-86 1.22720E-07 3.80180E-07 37086.82c + 233 370861 Rb-86m 2.57460E-07 2.57460E-07 370861 + 234 370870 Rb-87 3.32820E-05 8.63100E-03 37087.82c + 235 370880 Rb-88 1.66940E-04 9.92720E-03 370880 + 236 370890 Rb-89 1.50760E-03 1.58130E-02 370890 + 237 370900 Rb-90 3.29920E-04 1.23600E-02 370900 + 238 370901 Rb-90m 3.35640E-03 5.14650E-03 370901 + 239 370910 Rb-91 1.04550E-02 1.99230E-02 370910 + 240 370920 Rb-92 1.19130E-02 1.72860E-02 370920 + 241 370930 Rb-93 1.28200E-02 1.51140E-02 370930 + 242 370940 Rb-94 6.47750E-03 7.19170E-03 370940 + 243 370950 Rb-95 4.39240E-03 4.52600E-03 370950 + 244 370960 Rb-96 6.99000E-04 1.05980E-03 370960 + 245 370961 Rb-96m 6.99000E-04 7.06530E-04 370961 + 246 370970 Rb-97 3.85740E-04 3.85770E-04 370970 + 247 370980 Rb-98 1.94950E-05 1.94950E-05 370980 + 248 370981 Rb-98m 1.94950E-05 1.94950E-05 370981 + 249 370990 Rb-99 5.94120E-06 5.94120E-06 370990 + 250 371000 Rb-100 4.79260E-09 4.79260E-09 371000 + 251 380870 Sr-87 1.82310E-09 2.18910E-09 38087.82c + 252 380871 Sr-87m 3.67080E-10 3.67080E-10 380871 + 253 380880 Sr-88 6.34930E-06 9.93360E-03 38088.82c + 254 380890 Sr-89 4.87940E-05 1.58620E-02 38089.82c + 255 380900 Sr-90 5.39250E-04 1.79120E-02 38090.82c + 256 380910 Sr-91 2.25400E-03 2.21770E-02 380910 + 257 380920 Sr-92 9.59530E-03 2.70930E-02 380920 + 258 380930 Sr-93 2.08820E-02 3.65110E-02 380930 + 259 380940 Sr-94 2.99060E-02 3.67610E-02 380940 + 260 380950 Sr-95 2.80590E-02 3.23380E-02 380950 + 261 380960 Sr-96 2.15210E-02 2.28890E-02 380960 + 262 380970 Sr-97 1.01060E-02 1.03980E-02 380970 + 263 380980 Sr-98 4.44560E-03 4.48280E-03 380980 + 264 380990 Sr-99 1.25670E-03 1.26170E-03 380990 + 265 381000 Sr-100 2.80150E-04 2.80150E-04 381000 + 266 381010 Sr-101 3.36690E-05 3.36690E-05 381010 + 267 381020 Sr-102 4.00770E-06 4.00770E-06 381020 + 268 390890 Y-89 8.85800E-11 1.58620E-02 39089.82c + 269 390891 Y-89m 4.39940E-10 1.52940E-06 390891 + 270 390900 Y-90 3.89020E-07 1.79130E-02 39090.82c + 271 390901 Y-90m 6.50580E-07 6.50580E-07 390901 + 272 390910 Y-91 2.63720E-06 2.21930E-02 39091.82c + 273 390911 Y-91m 1.30980E-05 1.30610E-02 390911 + 274 390920 Y-92 9.59170E-05 2.71890E-02 390920 + 275 390930 Y-93 1.03730E-04 3.73940E-02 390930 + 276 390931 Y-93m 7.79070E-04 9.91560E-03 390931 + 277 390940 Y-94 2.56240E-03 3.93230E-02 390940 + 278 390950 Y-95 1.15110E-02 4.38490E-02 390950 + 279 390960 Y-96 6.23420E-03 2.91260E-02 390960 + 280 390961 Y-96m 1.30790E-02 1.30810E-02 390961 + 281 390970 Y-97 4.64590E-03 1.36560E-02 390970 + 282 390971 Y-97m 1.71730E-02 2.34400E-02 390971 + 283 390972 Y-97m 5.90160E-03 5.90160E-03 390972 + 284 390980 Y-98 2.97080E-03 7.45360E-03 390980 + 285 390981 Y-98m 1.44020E-02 1.44020E-02 390981 + 286 390990 Y-99 1.47000E-02 1.59640E-02 390990 + 287 391000 Y-100 3.35270E-03 3.63110E-03 391000 + 288 391001 Y-100m 3.35270E-03 3.35310E-03 391001 + 289 391010 Y-101 2.83980E-03 2.87290E-03 391010 + 290 391020 Y-102 2.85440E-04 2.87330E-04 391020 + 291 391021 Y-102m 2.85440E-04 2.87330E-04 391021 + 292 391030 Y-103 1.09610E-04 1.09610E-04 391030 + 293 391040 Y-104 8.51390E-06 8.51390E-06 391040 + 294 391050 Y-105 7.61950E-09 7.61950E-09 391050 + 295 400920 Zr-92 1.89130E-06 2.71910E-02 40092.82c + 296 400930 Zr-93 1.63410E-05 3.74100E-02 40093.82c + 297 400940 Zr-94 1.71180E-04 3.94940E-02 40094.82c + 298 400950 Zr-95 9.58090E-04 4.48070E-02 40095.82c + 299 400960 Zr-96 5.70230E-03 4.79280E-02 40096.82c + 300 400970 Zr-97 1.39210E-02 5.25300E-02 400970 + 301 400980 Zr-98 3.29170E-02 5.45290E-02 400980 + 302 400990 Zr-99 4.23540E-02 5.80800E-02 400990 + 303 401000 Zr-100 4.53290E-02 5.22800E-02 401000 + 304 401010 Zr-101 2.42480E-02 2.71490E-02 401010 + 305 401020 Zr-102 1.41670E-02 1.47220E-02 401020 + 306 401030 Zr-103 5.48560E-03 5.58720E-03 401030 + 307 401040 Zr-104 1.84680E-03 1.85460E-03 401040 + 308 401050 Zr-105 2.92870E-04 2.92880E-04 401050 + 309 401060 Zr-106 5.12970E-05 5.12970E-05 401060 + 310 401070 Zr-107 3.93730E-06 3.93730E-06 401070 + 311 401080 Zr-108 9.64460E-10 9.64460E-10 401080 + 312 410940 Nb-94 5.20500E-10 8.30180E-10 41094.82c + 313 410941 Nb-94m 3.11240E-10 3.11240E-10 410941 + 314 410950 Nb-95 7.87250E-07 4.47810E-02 41095.82c + 315 410951 Nb-95m 1.58510E-07 4.84230E-04 410951 + 316 410960 Nb-96 2.84100E-05 2.84100E-05 410960 + 317 410970 Nb-97 2.22930E-04 5.27980E-02 410970 + 318 410971 Nb-97m 4.48870E-05 4.99740E-02 410971 + 319 410980 Nb-98 2.43160E-04 5.47720E-02 410980 + 320 410981 Nb-98m 8.47240E-04 8.47240E-04 410981 + 321 410990 Nb-99 5.11070E-03 4.22650E-02 410990 + 322 410991 Nb-99m 1.02900E-03 2.24020E-02 410991 + 323 411000 Nb-100 2.47560E-03 5.47550E-02 411000 + 324 411001 Nb-100m 1.20010E-02 1.20010E-02 411001 + 325 411010 Nb-101 3.26320E-02 5.97810E-02 411010 + 326 411020 Nb-102 1.51780E-02 2.99010E-02 411020 + 327 411021 Nb-102m 1.51780E-02 1.51780E-02 411021 + 328 411030 Nb-103 2.58830E-02 3.14700E-02 411030 + 329 411040 Nb-104 6.52250E-03 8.38120E-03 411040 + 330 411041 Nb-104m 6.52250E-03 6.52250E-03 411041 + 331 411050 Nb-105 7.95950E-03 8.24910E-03 411050 + 332 411060 Nb-106 2.87170E-03 2.92240E-03 411060 + 333 411070 Nb-107 7.07180E-04 7.10970E-04 411070 + 334 411080 Nb-108 8.18170E-05 8.18180E-05 411080 + 335 411090 Nb-109 1.18870E-05 1.18870E-05 411090 + 336 411100 Nb-110 1.18090E-09 1.18090E-09 411100 + 337 420960 Mo-96 9.78820E-07 2.93890E-05 42096.82c + 338 420970 Mo-97 3.79740E-06 5.28020E-02 42097.82c + 339 420980 Mo-98 3.99860E-05 5.56590E-02 42098.82c + 340 420990 Mo-99 2.30490E-04 6.44500E-02 42099.82c + 341 421000 Mo-100 1.80700E-03 6.85640E-02 42100.82c + 342 421010 Mo-101 6.19790E-03 6.59790E-02 421010 + 343 421020 Mo-102 2.16230E-02 6.67020E-02 421020 + 344 421030 Mo-103 3.44990E-02 6.59770E-02 421030 + 345 421040 Mo-104 4.70340E-02 6.20700E-02 421040 + 346 421050 Mo-105 2.98040E-02 3.80440E-02 421050 + 347 421060 Mo-106 2.15620E-02 2.43960E-02 421060 + 348 421070 Mo-107 7.36620E-03 8.03960E-03 421070 + 349 421080 Mo-108 3.15770E-03 3.23600E-03 421080 + 350 421090 Mo-109 7.49260E-04 7.59640E-04 421090 + 351 421100 Mo-110 1.13500E-04 1.13500E-04 421100 + 352 421110 Mo-111 1.93070E-05 1.93070E-05 421110 + 353 421120 Mo-112 8.51190E-06 8.51190E-06 421120 + 354 421130 Mo-113 4.01430E-11 4.01430E-11 421130 + 355 430990 Tc-99 1.80810E-09 6.44480E-02 43099.82c + 356 430991 Tc-99m 3.64060E-10 5.67550E-02 430991 + 357 431000 Tc-100 4.12560E-06 4.12560E-06 431000 + 358 431010 Tc-101 6.24790E-05 6.60410E-02 431010 + 359 431020 Tc-102 1.42370E-04 6.68450E-02 431020 + 360 431021 Tc-102m 1.42370E-04 1.42370E-04 431021 + 361 431030 Tc-103 1.80830E-03 6.77860E-02 431030 + 362 431040 Tc-104 4.70730E-03 6.67770E-02 431040 + 363 431050 Tc-105 1.41450E-02 5.21890E-02 431050 + 364 431060 Tc-106 2.07110E-02 4.51070E-02 431060 + 365 431070 Tc-107 1.93910E-02 2.74310E-02 431070 + 366 431080 Tc-108 9.28450E-03 1.25240E-02 431080 + 367 431090 Tc-109 6.07530E-03 6.83090E-03 431090 + 368 431100 Tc-110 1.94840E-03 2.06210E-03 431100 + 369 431110 Tc-111 7.63320E-04 7.82610E-04 431110 + 370 431120 Tc-112 1.57290E-04 1.65630E-04 431120 + 371 431130 Tc-113 7.82600E-05 7.82600E-05 431130 + 372 431140 Tc-114 6.02250E-05 6.02250E-05 431140 + 373 431150 Tc-115 9.39930E-06 9.39930E-06 431150 + 374 441010 Ru-101 1.02160E-06 6.60430E-02 44101.82c + 375 441020 Ru-102 1.07320E-08 6.69870E-02 44102.82c + 376 441030 Ru-103 9.16260E-06 6.78210E-02 44103.82c + 377 441031 Ru-103m 2.56360E-05 2.56360E-05 441031 + 378 441040 Ru-104 2.54880E-04 6.70320E-02 44104.82c + 379 441050 Ru-105 9.62430E-04 5.31520E-02 44105.82c + 380 441060 Ru-106 4.62010E-03 4.97270E-02 44106.82c + 381 441070 Ru-107 7.04420E-03 3.44750E-02 441070 + 382 441080 Ru-108 1.13440E-02 2.38740E-02 441080 + 383 441090 Ru-109 9.07810E-03 1.59040E-02 441090 + 384 441100 Ru-110 5.54420E-03 7.60550E-03 441100 + 385 441110 Ru-111 2.59530E-03 3.38040E-03 441110 + 386 441120 Ru-112 1.10850E-03 1.27730E-03 441120 + 387 441130 Ru-113 2.15550E-04 3.99890E-04 441130 + 388 441131 Ru-113m 2.15550E-04 2.15550E-04 441131 + 389 441140 Ru-114 2.76410E-04 3.34050E-04 441140 + 390 441150 Ru-115 7.48900E-05 8.29420E-05 441150 + 391 441160 Ru-116 2.78010E-08 2.78010E-08 441160 + 392 441170 Ru-117 7.99420E-06 7.99420E-06 441170 + 393 441180 Ru-118 1.01390E-11 1.01390E-11 441180 + 394 451040 Rh-104 2.11070E-07 9.45540E-07 451040 + 395 451041 Rh-104m 7.35430E-07 7.35430E-07 451041 + 396 451050 Rh-105 7.79300E-06 5.31610E-02 45105.82c + 397 451051 Rh-105m 1.03760E-06 1.50900E-02 451051 + 398 451060 Rh-106 7.23070E-06 4.97340E-02 451060 + 399 451061 Rh-106m 1.97090E-05 1.97090E-05 451061 + 400 451070 Rh-107 1.59780E-04 3.46350E-02 451070 + 401 451080 Rh-108 8.51970E-05 2.39590E-02 451080 + 402 451081 Rh-108m 2.96850E-04 2.96850E-04 451081 + 403 451090 Rh-109 1.09460E-03 1.69990E-02 451090 + 404 451100 Rh-110 1.05890E-03 8.66430E-03 451100 + 405 451101 Rh-110m 2.49270E-05 2.49270E-05 451101 + 406 451110 Rh-111 1.41840E-03 4.79880E-03 451110 + 407 451120 Rh-112 4.21960E-04 1.69920E-03 451120 + 408 451121 Rh-112m 4.21960E-04 4.21960E-04 451121 + 409 451130 Rh-113 8.18540E-04 1.32620E-03 451130 + 410 451140 Rh-114 2.19230E-04 5.53460E-04 451140 + 411 451141 Rh-114m 2.19230E-04 2.19230E-04 451141 + 412 451150 Rh-115 2.53760E-04 3.36510E-04 451150 + 413 451160 Rh-116 1.80770E-05 1.82680E-05 451160 + 414 451161 Rh-116m 4.92740E-05 4.92740E-05 451161 + 415 451170 Rh-117 1.62580E-06 9.45600E-06 451170 + 416 451180 Rh-118 6.19950E-08 6.20050E-08 451180 + 417 451190 Rh-119 6.67810E-06 6.67810E-06 451190 + 418 451200 Rh-120 5.70010E-11 5.70010E-11 451200 + 419 451210 Rh-121 1.51850E-07 1.51850E-07 451210 + 420 451220 Rh-122 8.30000E-09 8.30000E-09 451220 + 421 461070 Pd-107 3.07920E-07 3.46360E-02 46107.82c + 422 461071 Pd-107m 6.76800E-07 6.76800E-07 461071 + 423 461080 Pd-108 7.57710E-06 2.42640E-02 46108.82c + 424 461090 Pd-109 7.46010E-06 1.70230E-02 461090 + 425 461091 Pd-109m 1.63970E-05 8.51590E-03 461091 + 426 461100 Pd-110 6.87640E-05 8.75800E-03 46110.82c + 427 461110 Pd-111 3.77590E-05 4.89190E-03 461110 + 428 461111 Pd-111m 8.29910E-05 1.02190E-04 461111 + 429 461120 Pd-112 1.85250E-04 2.30640E-03 461120 + 430 461130 Pd-113 5.88240E-05 1.54960E-03 461130 + 431 461131 Pd-113m 1.64590E-04 1.64590E-04 461131 + 432 461140 Pd-114 3.01760E-04 1.07450E-03 461140 + 433 461150 Pd-115 8.58270E-05 3.92480E-04 461150 + 434 461151 Pd-115m 1.88640E-04 2.37500E-04 461151 + 435 461160 Pd-116 2.19320E-04 2.86860E-04 461160 + 436 461170 Pd-117 4.49410E-05 1.53180E-04 461170 + 437 461171 Pd-117m 9.87790E-05 9.87790E-05 461171 + 438 461180 Pd-118 9.47950E-05 9.48550E-05 461180 + 439 461190 Pd-119 1.33560E-05 2.00340E-05 461190 + 440 461200 Pd-120 6.25020E-06 6.27090E-06 461200 + 441 461210 Pd-121 1.36110E-05 1.37420E-05 461210 + 442 461220 Pd-122 7.25870E-06 7.26700E-06 461220 + 443 461230 Pd-123 5.66000E-07 5.66000E-07 461230 + 444 461240 Pd-124 1.58950E-07 1.58950E-07 461240 + 445 471100 Ag-110 1.10930E-09 1.15040E-09 471100 + 446 471101 Ag-110m 3.02370E-09 3.02370E-09 47510.82c + 447 471110 Ag-111 1.62690E-08 4.89530E-03 47111.82c + 448 471111 Ag-111m 1.22190E-07 4.87720E-03 471111 + 449 471120 Ag-112 9.05390E-07 2.30730E-03 471120 + 450 471130 Ag-113 1.19570E-06 1.02240E-03 471130 + 451 471131 Ag-113m 8.98030E-06 1.49280E-03 471131 + 452 471140 Ag-114 4.72220E-06 1.10210E-03 471140 + 453 471141 Ag-114m 2.28930E-05 2.28930E-05 471141 + 454 471150 Ag-115 3.32130E-06 3.63210E-04 471150 + 455 471151 Ag-115m 2.49450E-05 3.49420E-04 471151 + 456 471160 Ag-116 1.13310E-05 3.00050E-04 471160 + 457 471161 Ag-116m 3.08870E-05 3.08870E-05 471161 + 458 471170 Ag-117 1.69500E-05 1.05770E-04 471170 + 459 471171 Ag-117m 1.27310E-04 2.03900E-04 471171 + 460 471180 Ag-118 2.00040E-05 1.46620E-04 471180 + 461 471181 Ag-118m 9.69760E-05 1.10540E-04 471181 + 462 471190 Ag-119 1.72490E-05 2.72660E-05 471190 + 463 471191 Ag-119m 1.29550E-04 1.39570E-04 471191 + 464 471200 Ag-120 3.50450E-05 6.10630E-05 471200 + 465 471201 Ag-120m 5.86080E-05 6.17440E-05 471201 + 466 471210 Ag-121 1.92540E-05 3.29590E-05 471210 + 467 471220 Ag-122 2.21330E-06 9.48030E-06 471220 + 468 471221 Ag-122m 2.38630E-06 2.38630E-06 471221 + 469 471230 Ag-123 1.61930E-05 1.67590E-05 471230 + 470 471240 Ag-124 4.98520E-06 7.83160E-06 471240 + 471 471241 Ag-124m 5.37480E-06 5.37480E-06 471241 + 472 471250 Ag-125 8.09310E-06 8.09310E-06 471250 + 473 471260 Ag-126 2.26700E-06 2.26700E-06 471260 + 474 471270 Ag-127 4.03100E-07 4.03100E-07 471270 + 475 471280 Ag-128 1.59230E-08 1.59230E-08 471280 + 476 471290 Ag-129 5.81070E-10 5.81070E-10 471290 + 477 481120 Cd-112 1.83380E-10 2.30730E-03 48112.82c + 478 481130 Cd-113 1.03150E-09 1.54210E-03 48113.82c + 479 481131 Cd-113m 3.90620E-09 1.76790E-05 481131 + 480 481140 Cd-114 1.58590E-07 1.10220E-03 48114.82c + 481 481150 Cd-115 2.05570E-07 6.10490E-04 481150 + 482 481151 Cd-115m 7.78470E-07 2.97440E-05 48515.82c + 483 481160 Cd-116 7.22580E-06 3.36310E-04 48116.82c + 484 481170 Cd-117 6.69380E-06 2.38750E-04 481170 + 485 481171 Cd-117m 2.53490E-05 9.07320E-05 481171 + 486 481180 Cd-118 4.39010E-05 2.55740E-04 481180 + 487 481190 Cd-119 2.46640E-05 1.77870E-04 481190 + 488 481191 Cd-119m 6.90080E-05 8.26420E-05 481191 + 489 481200 Cd-120 1.25200E-04 2.25160E-04 481200 + 490 481210 Cd-121 1.90280E-05 4.85430E-05 481210 + 491 481211 Cd-121m 5.32380E-05 5.66820E-05 481211 + 492 481220 Cd-122 8.73240E-05 9.91910E-05 481220 + 493 481230 Cd-123 2.13170E-05 3.50330E-05 481230 + 494 481231 Cd-123m 5.96440E-05 6.26950E-05 481231 + 495 481240 Cd-124 1.75460E-04 1.85970E-04 481240 + 496 481250 Cd-125 6.41980E-05 6.82440E-05 481250 + 497 481251 Cd-125m 1.79620E-04 1.83670E-04 481251 + 498 481260 Cd-126 3.21280E-04 3.23550E-04 481260 + 499 481270 Cd-127 1.85120E-04 1.85520E-04 481270 + 500 481280 Cd-128 8.92450E-05 8.92610E-05 481280 + 501 481290 Cd-129 5.77710E-06 5.77740E-06 481290 + 502 481291 Cd-129m 1.61640E-05 1.61640E-05 481291 + 503 481300 Cd-130 4.97860E-06 4.97860E-06 481300 + 504 481310 Cd-131 1.14720E-08 1.14720E-08 481310 + 505 491150 In-115 2.93320E-10 6.09710E-04 49115.82c + 506 491151 In-115m 5.90590E-11 6.10490E-04 491151 + 507 491160 In-116 1.04830E-09 1.04830E-09 491160 + 508 491161 In-116m 1.69280E-09 3.65270E-09 491161 + 509 491162 In-116m 1.95990E-09 1.95990E-09 491162 + 510 491170 In-117 1.34280E-07 2.13150E-04 491170 + 511 491171 In-117m 2.70370E-08 2.20200E-04 491171 + 512 491180 In-118 2.29760E-07 2.55970E-04 491180 + 513 491181 In-118m 3.71010E-07 7.94530E-07 491181 + 514 491182 In-118m 4.29530E-07 4.29530E-07 491182 + 515 491190 In-119 9.64090E-06 1.18510E-04 491190 + 516 491191 In-119m 1.94110E-06 1.62690E-04 491191 + 517 491200 In-120 2.08420E-06 2.27240E-04 491200 + 518 491201 In-120m 2.08420E-06 2.08420E-06 491201 + 519 491202 In-120m 2.08420E-06 2.08420E-06 491202 + 520 491210 In-121 1.20310E-05 8.54770E-05 491210 + 521 491211 In-121m 2.42230E-06 3.46160E-05 491211 + 522 491220 In-122 2.23980E-05 1.21590E-04 491220 + 523 491221 In-122m 1.87290E-05 1.87290E-05 491221 + 524 491222 In-122m 1.87290E-05 1.87290E-05 491222 + 525 491230 In-123 3.71170E-05 1.09900E-04 491230 + 526 491231 In-123m 7.47330E-06 3.24200E-05 491231 + 527 491240 In-124 4.48930E-05 2.30860E-04 491240 + 528 491241 In-124m 4.84010E-05 4.84010E-05 491241 + 529 491250 In-125 3.79000E-04 5.95330E-04 491250 + 530 491251 In-125m 7.63100E-05 1.11890E-04 491251 + 531 491260 In-126 4.50990E-04 7.74540E-04 491260 + 532 491261 In-126m 4.86240E-04 4.86240E-04 491261 + 533 491270 In-127 1.45800E-03 1.45800E-03 491270 + 534 491271 In-127m 2.93570E-04 4.79090E-04 491271 + 535 491280 In-128 5.06870E-04 7.94600E-04 491280 + 536 491281 In-128m 1.98470E-04 2.87730E-04 491281 + 537 491282 In-128m 7.60460E-04 7.60460E-04 491282 + 538 491290 In-129 1.28520E-03 1.30150E-03 491290 + 539 491291 In-129m 2.58770E-04 2.64640E-04 491291 + 540 491300 In-130 1.87910E-04 1.92710E-04 491300 + 541 491301 In-130m 2.73610E-04 2.73610E-04 491301 + 542 491302 In-130m 3.81130E-04 3.81130E-04 491302 + 543 491310 In-131 5.33010E-05 5.38550E-05 491310 + 544 491311 In-131m 5.33010E-05 5.33010E-05 491311 + 545 491312 In-131m 5.33010E-05 5.33010E-05 491312 + 546 491320 In-132 1.62180E-05 1.62180E-05 491320 + 547 491330 In-133 1.87940E-07 2.25780E-07 491330 + 548 491331 In-133m 3.78410E-08 3.78410E-08 491331 + 549 491340 In-134 3.30800E-09 3.30800E-09 491340 + 550 501170 Sn-117 3.53650E-12 3.29640E-04 50117.82c + 551 501171 Sn-117m 1.33930E-11 7.26250E-07 501171 + 552 501180 Sn-118 9.63180E-10 2.56770E-04 50118.82c + 553 501190 Sn-119 4.07560E-09 2.72110E-04 50119.82c + 554 501191 Sn-119m 1.54340E-08 1.07070E-04 501191 + 555 501200 Sn-120 4.55610E-07 2.31870E-04 50120.82c + 556 501210 Sn-121 1.00760E-11 1.17510E-04 501210 + 557 501211 Sn-121m 2.81930E-11 9.68320E-06 501211 + 558 501220 Sn-122 9.20710E-06 1.68250E-04 50122.82c + 559 501230 Sn-123 2.98490E-06 1.13640E-05 50123.82c + 560 501231 Sn-123m 1.06680E-06 1.35010E-04 501231 + 561 501240 Sn-124 7.28760E-05 3.52140E-04 50124.82c + 562 501250 Sn-125 8.81020E-05 1.88670E-04 50125.82c + 563 501251 Sn-125m 3.14880E-05 6.38150E-04 501251 + 564 501260 Sn-126 8.66610E-04 2.13070E-03 50126.82c + 565 501270 Sn-127 1.65540E-03 2.22370E-03 501270 + 566 501271 Sn-127m 5.91630E-04 1.95710E-03 501271 + 567 501280 Sn-128 1.73540E-03 8.02080E-03 501280 + 568 501281 Sn-128m 4.73030E-03 5.49080E-03 501281 + 569 501290 Sn-129 2.66880E-03 4.09650E-03 501290 + 570 501291 Sn-129m 7.46720E-03 7.60570E-03 501291 + 571 501300 Sn-130 3.82850E-03 4.34710E-03 501300 + 572 501301 Sn-130m 1.04360E-02 1.07660E-02 501301 + 573 501310 Sn-131 1.46950E-03 1.57270E-03 501310 + 574 501311 Sn-131m 4.11160E-03 4.16720E-03 501311 + 575 501320 Sn-132 3.03760E-03 3.05400E-03 501320 + 576 501330 Sn-133 4.91700E-04 4.91740E-04 501330 + 577 501340 Sn-134 7.97480E-05 7.97490E-05 501340 + 578 501350 Sn-135 1.98970E-06 1.98970E-06 501350 + 579 501360 Sn-136 4.08570E-08 4.08570E-08 501360 + 580 511200 Sb-120 2.32690E-11 2.32690E-11 511200 + 581 511201 Sb-120m 3.89140E-11 3.89140E-11 511201 + 582 511230 Sb-123 1.00380E-11 1.46370E-04 51123.82c + 583 511240 Sb-124 1.11570E-06 2.87150E-06 51124.82c + 584 511241 Sb-124m 9.00050E-07 2.34100E-06 511241 + 585 511242 Sb-124m 1.44100E-06 1.44100E-06 511242 + 586 511250 Sb-125 2.43500E-05 8.51160E-04 51125.82c + 587 511260 Sb-126 1.21180E-05 1.44910E-05 51126.82c + 588 511261 Sb-126m 7.56900E-06 1.69520E-05 511261 + 589 511262 Sb-126m 9.38280E-06 9.38280E-06 511262 + 590 511270 Sb-127 2.01360E-04 4.38220E-03 511270 + 591 511280 Sb-128 2.64280E-04 8.29830E-03 511280 + 592 511281 Sb-128m 3.69630E-04 3.69630E-04 511281 + 593 511290 Sb-129 2.82250E-03 1.16060E-02 511290 + 594 511291 Sb-129m 2.08880E-03 5.89160E-03 511291 + 595 511300 Sb-130 7.03100E-03 1.67610E-02 511300 + 596 511301 Sb-130m 7.03100E-03 1.24140E-02 511301 + 597 511310 Sb-131 2.34740E-02 2.92140E-02 511310 + 598 511320 Sb-132 8.85930E-03 1.19130E-02 511320 + 599 511321 Sb-132m 7.84370E-03 7.84370E-03 511321 + 600 511330 Sb-133 1.32910E-02 1.37960E-02 511330 + 601 511340 Sb-134 1.21500E-03 1.28140E-03 511340 + 602 511341 Sb-134m 3.31180E-03 3.31200E-03 511341 + 603 511350 Sb-135 1.43110E-03 1.43270E-03 511350 + 604 511360 Sb-136 1.70710E-04 1.70740E-04 511360 + 605 511370 Sb-137 2.65820E-05 2.65820E-05 511370 + 606 511380 Sb-138 9.02320E-07 9.02320E-07 511380 + 607 511390 Sb-139 4.07190E-09 4.07190E-09 511390 + 608 521260 Te-126 2.41710E-06 3.14870E-05 52126.82c + 609 521270 Te-127 2.99080E-06 4.37600E-03 521270 + 610 521271 Te-127m 8.36820E-06 7.30530E-04 52527.82c + 611 521280 Te-128 2.59000E-05 8.68060E-03 52128.82c + 612 521290 Te-129 5.60570E-05 1.42460E-02 521290 + 613 521291 Te-129m 1.56840E-04 6.97340E-03 52529.82c + 614 521300 Te-130 2.34380E-03 3.15180E-02 52130.82c + 615 521310 Te-131 1.66760E-03 3.00140E-02 521310 + 616 521311 Te-131m 4.66580E-03 7.00470E-03 521311 + 617 521320 Te-132 2.63230E-02 4.60800E-02 52132.82c + 618 521330 Te-133 1.36780E-02 3.22050E-02 521330 + 619 521331 Te-133m 3.82700E-02 4.06570E-02 521331 + 620 521340 Te-134 5.42920E-02 5.91080E-02 521340 + 621 521350 Te-135 1.97160E-02 2.09520E-02 521350 + 622 521360 Te-136 9.79030E-03 9.94580E-03 521360 + 623 521370 Te-137 2.46230E-03 2.47590E-03 521370 + 624 521380 Te-138 6.90720E-04 6.91620E-04 521380 + 625 521390 Te-139 5.27310E-05 5.27350E-05 521390 + 626 521400 Te-140 1.15120E-05 1.15120E-05 521400 + 627 521410 Te-141 2.29440E-08 2.29440E-08 521410 + 628 531280 I-128 1.89560E-10 1.89560E-10 531280 + 629 531290 I-129 1.46510E-06 1.68280E-02 53129.82c + 630 531300 I-130 2.42930E-06 3.17790E-06 53130.82c + 631 531301 I-130m 8.91220E-07 8.91220E-07 531301 + 632 531310 I-131 9.58200E-05 3.56430E-02 53131.82c + 633 531320 I-132 2.42540E-04 4.65070E-02 531320 + 634 531321 I-132m 2.14740E-04 2.14740E-04 531321 + 635 531330 I-133 2.44630E-03 7.00040E-02 531330 + 636 531331 I-133m 1.81040E-03 1.81040E-03 531331 + 637 531340 I-134 6.55730E-03 7.13370E-02 531340 + 638 531341 I-134m 5.80570E-03 5.80570E-03 531341 + 639 531350 I-135 4.99710E-02 7.09230E-02 53135.82c + 640 531360 I-136 8.18350E-03 1.81660E-02 531360 + 641 531361 I-136m 2.23060E-02 2.23430E-02 531361 + 642 531370 I-137 2.21350E-02 2.45800E-02 531370 + 643 531380 I-138 8.15000E-03 8.79800E-03 531380 + 644 531390 I-139 6.08050E-03 6.13320E-03 531390 + 645 531400 I-140 1.25270E-03 1.26420E-03 531400 + 646 531410 I-141 2.73140E-04 2.73160E-04 531410 + 647 531420 I-142 2.33200E-05 2.33200E-05 531420 + 648 531430 I-143 2.14060E-07 2.14060E-07 531430 + 649 531440 I-144 2.77380E-09 2.77380E-09 531440 + 650 541310 Xe-131 2.32360E-09 3.56430E-02 54131.82c + 651 541311 Xe-131m 6.50130E-09 3.87160E-04 541311 + 652 541320 Xe-132 1.30250E-06 4.65400E-02 54132.82c + 653 541321 Xe-132m 1.74500E-06 1.74500E-06 541321 + 654 541330 Xe-133 2.00730E-05 7.00800E-02 54133.82c + 655 541331 Xe-133m 5.61640E-05 2.04870E-03 541331 + 656 541340 Xe-134 1.58190E-04 7.20600E-02 54134.82c + 657 541341 Xe-134m 4.31180E-04 5.64710E-04 541341 + 658 541350 Xe-135 1.12980E-03 7.51240E-02 54135.82c + 659 541351 Xe-135m 3.16120E-03 1.48700E-02 541351 + 660 541360 Xe-136 2.51700E-02 6.72780E-02 54136.82c + 661 541370 Xe-137 3.96410E-02 6.30900E-02 541370 + 662 541380 Xe-138 4.82170E-02 5.71500E-02 541380 + 663 541390 Xe-139 3.15350E-02 3.71850E-02 541390 + 664 541400 Xe-140 2.50780E-02 2.62820E-02 541400 + 665 541410 Xe-141 8.25340E-03 8.47500E-03 541410 + 666 541420 Xe-142 3.78730E-03 3.80490E-03 541420 + 667 541430 Xe-143 6.83800E-04 6.83930E-04 541430 + 668 541440 Xe-144 1.27330E-04 1.27330E-04 541440 + 669 541450 Xe-145 1.34650E-05 1.34650E-05 541450 + 670 541460 Xe-146 2.39810E-08 2.39810E-08 541460 + 671 551330 Cs-133 2.25790E-09 7.00800E-02 55133.82c + 672 551340 Cs-134 5.06010E-07 9.54010E-07 55134.82c + 673 551341 Cs-134m 4.48000E-07 4.48000E-07 551341 + 674 551350 Cs-135 6.86480E-06 7.52260E-02 55135.82c + 675 551351 Cs-135m 5.08020E-06 5.08020E-06 551351 + 676 551360 Cs-136 6.68870E-05 9.07990E-05 55136.82c + 677 551361 Cs-136m 4.78230E-05 4.78230E-05 551361 + 678 551370 Cs-137 1.80700E-03 6.48970E-02 55137.82c + 679 551380 Cs-138 2.29170E-03 6.25460E-02 551380 + 680 551381 Cs-138m 3.83260E-03 3.83260E-03 551381 + 681 551390 Cs-139 1.86120E-02 5.57970E-02 551390 + 682 551400 Cs-140 2.11780E-02 4.74640E-02 551400 + 683 551410 Cs-141 2.64680E-02 3.49530E-02 551410 + 684 551420 Cs-142 1.44060E-02 1.82040E-02 551420 + 685 551430 Cs-143 1.05300E-02 1.12110E-02 551430 + 686 551440 Cs-144 1.81080E-03 2.84030E-03 551440 + 687 551441 Cs-144m 1.81080E-03 1.81120E-03 551441 + 688 551450 Cs-145 1.28780E-03 1.30060E-03 551450 + 689 551460 Cs-146 2.13330E-04 2.13350E-04 551460 + 690 551470 Cs-147 3.04230E-05 3.04230E-05 551470 + 691 551480 Cs-148 1.70230E-06 1.70230E-06 551480 + 692 551490 Cs-149 1.38940E-09 1.38940E-09 551490 + 693 561360 Ba-136 2.27340E-07 1.15560E-04 56136.82c + 694 561361 Ba-136m 6.19680E-07 6.19680E-07 561361 + 695 561370 Ba-137 2.26150E-06 6.49060E-02 56137.82c + 696 561371 Ba-137m 6.32740E-06 6.12690E-02 561371 + 697 561380 Ba-138 3.22930E-04 6.35970E-02 56138.82c + 698 561390 Ba-139 1.53130E-03 5.73280E-02 561390 + 699 561400 Ba-140 6.66380E-03 5.41280E-02 56140.82c + 700 561410 Ba-141 1.12010E-02 4.61540E-02 561410 + 701 561420 Ba-142 2.83180E-02 4.67060E-02 561420 + 702 561430 Ba-143 3.03900E-02 4.15080E-02 561430 + 703 561440 Ba-144 2.79050E-02 3.17460E-02 561440 + 704 561450 Ba-145 1.25670E-02 1.37120E-02 561450 + 705 561460 Ba-146 7.30770E-03 7.49940E-03 561460 + 706 561470 Ba-147 2.00850E-03 2.03070E-03 561470 + 707 561480 Ba-148 6.20620E-04 6.21900E-04 561480 + 708 561490 Ba-149 7.71640E-05 7.71650E-05 561490 + 709 561500 Ba-150 1.63020E-05 1.63020E-05 561500 + 710 561510 Ba-151 6.08780E-09 6.08780E-09 561510 + 711 571380 La-138 1.38360E-09 1.38360E-09 57138.82c + 712 571390 La-139 1.05650E-06 5.73290E-02 57139.82c + 713 571400 La-140 3.56510E-05 5.41630E-02 57140.82c + 714 571410 La-141 1.79130E-04 4.63330E-02 571410 + 715 571420 La-142 6.17910E-04 4.73240E-02 571420 + 716 571430 La-143 3.03000E-03 4.45380E-02 571430 + 717 571440 La-144 7.09170E-03 3.88380E-02 571440 + 718 571450 La-145 1.49270E-02 2.86390E-02 571450 + 719 571460 La-146 3.61570E-03 1.11150E-02 571460 + 720 571461 La-146m 7.58530E-03 7.58530E-03 571461 + 721 571470 La-147 9.48170E-03 1.15150E-02 571470 + 722 571480 La-148 3.88580E-03 4.50550E-03 571480 + 723 571490 La-149 2.19780E-03 2.27460E-03 571490 + 724 571500 La-150 5.14690E-04 5.30990E-04 571500 + 725 571510 La-151 1.10120E-04 1.10130E-04 571510 + 726 571520 La-152 7.32790E-06 7.32790E-06 571520 + 727 571530 La-153 3.42970E-08 3.42970E-08 571530 + 728 571540 La-154 2.63320E-10 2.63320E-10 571540 + 729 581410 Ce-141 8.97500E-07 4.63340E-02 58141.82c + 730 581420 Ce-142 1.73150E-05 4.73410E-02 58142.82c + 731 581430 Ce-143 9.80680E-05 4.46360E-02 58143.82c + 732 581440 Ce-144 5.68510E-04 3.94060E-02 58144.82c + 733 581450 Ce-145 2.28930E-03 3.09280E-02 581450 + 734 581460 Ce-146 6.81230E-03 2.55130E-02 581460 + 735 581470 Ce-147 9.74710E-03 2.12620E-02 581470 + 736 581480 Ce-148 1.27110E-02 1.72480E-02 581480 + 737 581490 Ce-149 8.77620E-03 1.10330E-02 581490 + 738 581500 Ce-150 6.59780E-03 7.11450E-03 581500 + 739 581510 Ce-151 2.31830E-03 2.42890E-03 581510 + 740 581520 Ce-152 9.97820E-04 1.00470E-03 581520 + 741 581530 Ce-153 2.03760E-04 2.03790E-04 581530 + 742 581540 Ce-154 3.08720E-05 3.08720E-05 581540 + 743 581550 Ce-155 2.55270E-06 2.55270E-06 581550 + 744 581560 Ce-156 2.21150E-09 2.21150E-09 581560 + 745 581570 Ce-157 3.35550E-11 3.35550E-11 581570 + 746 591430 Pr-143 1.50750E-09 4.46360E-02 59143.82c + 747 591440 Pr-144 7.94740E-08 3.94070E-02 591440 + 748 591441 Pr-144m 8.08510E-07 5.44590E-04 591441 + 749 591450 Pr-145 6.74110E-06 3.09350E-02 591450 + 750 591460 Pr-146 3.64690E-05 2.55490E-02 591460 + 751 591470 Pr-147 2.32060E-04 2.14940E-02 591470 + 752 591480 Pr-148 1.18510E-04 1.73670E-02 591480 + 753 591481 Pr-148m 5.74540E-04 5.74540E-04 591481 + 754 591490 Pr-149 2.09850E-03 1.31320E-02 591490 + 755 591500 Pr-150 3.02520E-03 1.01400E-02 591500 + 756 591510 Pr-151 4.43410E-03 6.86300E-03 591510 + 757 591520 Pr-152 2.49270E-03 3.49870E-03 591520 + 758 591530 Pr-153 1.66220E-03 1.86490E-03 591530 + 759 591540 Pr-154 4.23150E-04 4.53830E-04 591540 + 760 591550 Pr-155 1.72260E-04 1.74810E-04 591550 + 761 591560 Pr-156 1.75360E-05 1.75380E-05 591560 + 762 591570 Pr-157 3.79100E-06 3.79100E-06 591570 + 763 591580 Pr-158 3.00510E-09 3.00510E-09 591580 + 764 591590 Pr-159 5.48110E-11 5.48110E-11 591590 + 765 601460 Nd-146 9.56640E-07 2.55500E-02 60146.82c + 766 601470 Nd-147 3.58760E-06 2.14980E-02 60147.82c + 767 601480 Nd-148 2.90750E-05 1.79710E-02 60148.82c + 768 601490 Nd-149 1.18050E-04 1.32500E-02 601490 + 769 601500 Nd-150 5.56230E-04 1.06960E-02 60150.82c + 770 601510 Nd-151 1.48240E-03 8.34540E-03 601510 + 771 601520 Nd-152 2.83610E-03 6.33480E-03 601520 + 772 601530 Nd-153 3.08680E-03 4.95170E-03 601530 + 773 601540 Nd-154 2.20850E-03 2.66230E-03 601540 + 774 601550 Nd-155 1.39300E-03 1.56830E-03 601550 + 775 601560 Nd-156 7.09320E-04 7.26620E-04 601560 + 776 601570 Nd-157 2.07010E-04 2.10560E-04 601570 + 777 601580 Nd-158 4.51500E-05 4.51530E-05 601580 + 778 601590 Nd-159 2.30240E-07 2.30300E-07 601590 + 779 601600 Nd-160 1.10990E-08 1.10990E-08 601600 + 780 601610 Nd-161 1.23720E-10 1.23720E-10 601610 + 781 611480 Pm-148 1.03140E-10 1.17190E-10 61148.82c + 782 611481 Pm-148m 2.81120E-10 2.81120E-10 61548.82c + 783 611490 Pm-149 1.71370E-08 1.32500E-02 61149.82c + 784 611500 Pm-150 3.38190E-07 3.38190E-07 611500 + 785 611510 Pm-151 1.22050E-05 8.35760E-03 61151.82c + 786 611520 Pm-152 8.26920E-06 6.34300E-03 611520 + 787 611521 Pm-152m 1.73850E-05 1.73850E-05 611521 + 788 611522 Pm-152m 2.27090E-05 2.27090E-05 611522 + 789 611530 Pm-153 1.97830E-04 5.14960E-03 611530 + 790 611540 Pm-154 1.67100E-04 2.82940E-03 611540 + 791 611541 Pm-154m 1.67100E-04 1.67100E-04 611541 + 792 611550 Pm-155 6.96380E-04 2.26470E-03 611550 + 793 611560 Pm-156 6.56320E-04 1.38290E-03 611560 + 794 611570 Pm-157 5.83580E-04 7.94140E-04 611570 + 795 611580 Pm-158 1.67740E-04 2.12890E-04 611580 + 796 611590 Pm-159 5.45210E-05 5.47510E-05 611590 + 797 611600 Pm-160 2.57070E-05 2.57180E-05 611600 + 798 611610 Pm-161 4.36850E-07 4.36970E-07 611610 + 799 611620 Pm-162 1.87270E-08 1.87270E-08 611620 + 800 611630 Pm-163 3.20850E-10 3.20850E-10 611630 + 801 621510 Sm-151 8.69670E-10 8.35760E-03 62151.82c + 802 621520 Sm-152 2.93380E-06 6.38610E-03 62152.82c + 803 621530 Sm-153 2.28380E-06 5.15820E-03 62153.82c + 804 621531 Sm-153m 6.38990E-06 6.38990E-06 621531 + 805 621540 Sm-154 2.60710E-05 3.02260E-03 62154.82c + 806 621550 Sm-155 1.17190E-04 2.38190E-03 621550 + 807 621560 Sm-156 3.03230E-04 1.68620E-03 621560 + 808 621570 Sm-157 4.90010E-04 1.28410E-03 621570 + 809 621580 Sm-158 3.43600E-04 5.56500E-04 621580 + 810 621590 Sm-159 2.30590E-04 2.85400E-04 621590 + 811 621600 Sm-160 1.11420E-04 1.37070E-04 621600 + 812 621610 Sm-161 5.67270E-05 5.71640E-05 621610 + 813 621620 Sm-162 1.27690E-05 1.27880E-05 621620 + 814 621630 Sm-163 2.95990E-07 2.96310E-07 621630 + 815 621640 Sm-164 1.68930E-08 1.68930E-08 621640 + 816 621650 Sm-165 6.54160E-10 6.54160E-10 621650 + 817 631540 Eu-154 9.82030E-10 2.04080E-09 63154.82c + 818 631541 Eu-154m 1.05880E-09 1.05880E-09 631541 + 819 631550 Eu-155 2.55340E-06 2.38440E-03 63155.82c + 820 631560 Eu-156 5.84940E-06 1.69200E-03 63156.82c + 821 631570 Eu-157 1.13780E-05 1.29550E-03 63157.82c + 822 631580 Eu-158 1.40680E-05 5.70570E-04 631580 + 823 631590 Eu-159 3.33930E-05 3.18790E-04 631590 + 824 631600 Eu-160 4.72310E-05 1.84300E-04 631600 + 825 631610 Eu-161 5.04950E-05 1.07660E-04 631610 + 826 631620 Eu-162 7.02340E-05 8.30220E-05 631620 + 827 631630 Eu-163 2.01130E-05 2.04090E-05 631630 + 828 631640 Eu-164 6.70920E-06 6.72610E-06 631640 + 829 631650 Eu-165 5.00620E-07 5.01270E-07 631650 + 830 631660 Eu-166 1.57830E-08 1.57830E-08 631660 + 831 631670 Eu-167 1.05670E-09 1.05670E-09 631670 + 832 641560 Gd-156 2.68050E-10 1.69200E-03 64156.82c + 833 641570 Gd-157 6.20780E-09 1.29550E-03 64157.82c + 834 641580 Gd-158 1.17180E-07 5.70690E-04 64158.82c + 835 641590 Gd-159 6.61530E-07 3.19450E-04 641590 + 836 641600 Gd-160 1.28760E-05 1.97180E-04 64160.82c + 837 641610 Gd-161 1.26240E-05 1.20280E-04 641610 + 838 641620 Gd-162 3.19610E-05 1.14980E-04 641620 + 839 641630 Gd-163 1.34150E-05 3.38240E-05 641630 + 840 641640 Gd-164 6.71030E-06 1.34360E-05 641640 + 841 641650 Gd-165 1.53440E-05 1.58450E-05 641650 + 842 641660 Gd-166 1.87290E-06 1.88870E-06 641660 + 843 641670 Gd-167 2.14320E-07 2.15380E-07 641670 + 844 641680 Gd-168 2.81200E-08 2.81200E-08 641680 + 845 641690 Gd-169 1.05100E-09 1.05100E-09 641690 + 846 651590 Tb-159 2.85010E-10 3.19450E-04 65159.82c + 847 651600 Tb-160 4.31370E-09 4.31370E-09 65160.82c + 848 651610 Tb-161 8.49510E-08 1.20370E-04 651610 + 849 651620 Tb-162 6.26130E-07 1.15610E-04 651620 + 850 651630 Tb-163 1.88370E-06 3.57080E-05 651630 + 851 651640 Tb-164 1.91930E-06 1.53560E-05 651640 + 852 651650 Tb-165 7.94750E-06 2.37930E-05 651650 + 853 651660 Tb-166 5.95500E-06 7.84370E-06 651660 + 854 651670 Tb-167 2.64030E-06 2.85570E-06 651670 + 855 651680 Tb-168 5.27590E-07 5.55710E-07 651680 + 856 651690 Tb-169 1.81410E-07 1.82460E-07 651690 + 857 651700 Tb-170 1.19110E-08 1.19110E-08 651700 + 858 651710 Tb-171 1.18790E-09 1.18790E-09 651710 + 859 661610 Dy-161 9.27890E-12 1.20370E-04 66161.82c + 860 661620 Dy-162 7.11070E-10 1.15610E-04 66162.82c + 861 661630 Dy-163 3.88570E-09 3.57120E-05 66163.82c + 862 661640 Dy-164 3.81680E-08 1.53940E-05 66164.82c + 863 661650 Dy-165 2.25590E-07 2.40480E-05 661650 + 864 661651 Dy-165m 3.00360E-08 3.00360E-08 661651 + 865 661660 Dy-166 7.88130E-07 8.63180E-06 661660 + 866 661670 Dy-167 9.68630E-07 3.82430E-06 661670 + 867 661680 Dy-168 1.42780E-06 1.98350E-06 661680 + 868 661690 Dy-169 6.65230E-07 8.47690E-07 661690 + 869 661700 Dy-170 3.54410E-07 3.66320E-07 661700 + 870 661710 Dy-171 5.60340E-08 5.72220E-08 661710 + 871 661720 Dy-172 1.39040E-08 1.39040E-08 661720 + 872 661730 Dy-173 7.60240E-10 7.60240E-10 661730 + 873 671640 Ho-164 1.69450E-12 6.31340E-12 671640 + 874 671641 Ho-164m 4.61890E-12 4.61890E-12 671641 + 875 671650 Ho-165 4.40550E-10 2.40490E-05 67165.82c + 876 671660 Ho-166 6.47730E-10 8.63250E-06 671660 + 877 671661 Ho-166m 1.76560E-09 1.76560E-09 671661 + 878 671670 Ho-167 2.77680E-08 3.85210E-06 671670 + 879 671680 Ho-168 2.38360E-08 2.04700E-06 671680 + 880 671681 Ho-168m 3.98630E-08 3.98630E-08 671681 + 881 671690 Ho-169 2.36410E-07 1.08410E-06 671690 + 882 671700 Ho-170 1.23560E-07 1.23560E-07 671700 + 883 671701 Ho-170m 4.53300E-08 4.11650E-07 671701 + 884 671710 Ho-171 1.97660E-07 2.54880E-07 671710 + 885 671720 Ho-172 6.84930E-08 8.23970E-08 671720 + 886 671730 Ho-173 3.16610E-08 3.24210E-08 671730 + 887 671740 Ho-174 3.41050E-09 3.41050E-09 671740 + 888 671750 Ho-175 6.89900E-10 6.89900E-10 671750 + 889 681670 Er-167 1.10530E-11 3.85210E-06 68167.82c + 890 681671 Er-167m 1.47170E-12 4.60290E-07 681671 + 891 681680 Er-168 2.90130E-10 2.04750E-06 68168.82c + 892 681690 Er-169 1.86730E-09 1.08600E-06 681690 + 893 681700 Er-170 1.20700E-08 5.47280E-07 68170.82c + 894 681710 Er-171 2.11020E-08 2.75980E-07 681710 + 895 681720 Er-172 5.62170E-08 1.38610E-07 681720 + 896 681730 Er-173 3.44110E-08 6.68320E-08 681730 + 897 681740 Er-174 2.79260E-08 3.13360E-08 681740 + 898 681750 Er-175 8.19200E-09 8.88190E-09 681750 + 899 681760 Er-176 3.26240E-09 3.26240E-09 681760 + 900 681770 Er-177 2.89640E-10 2.89640E-10 681770 + 901 691700 Tm-170 8.23120E-12 8.23120E-12 691700 + 902 691710 Tm-171 1.42820E-10 2.76130E-07 691710 + 903 691720 Tm-172 6.41120E-10 1.39260E-07 691720 + 904 691730 Tm-173 3.41720E-09 7.02490E-08 691730 + 905 691740 Tm-174 3.97860E-09 3.53150E-08 691740 + 906 691750 Tm-175 8.73940E-09 1.76210E-08 691750 + 907 691760 Tm-176 4.61770E-09 7.88010E-09 691760 + 908 691770 Tm-177 3.18030E-09 3.46990E-09 691770 + 909 691780 Tm-178 6.38610E-10 6.38610E-10 691780 + 910 691790 Tm-179 2.16580E-10 2.16580E-10 691790 + 911 701730 Yb-173 6.16480E-12 7.02560E-08 701730 + 912 701740 Yb-174 6.95510E-11 3.53850E-08 701740 + 913 701750 Yb-175 2.19670E-10 1.78700E-08 701750 + 914 701751 Yb-175m 2.92480E-11 1.35980E-08 701751 + 915 701760 Yb-176 3.54890E-10 8.51100E-09 701760 + 916 701761 Yb-176m 7.44510E-10 4.68460E-09 701761 + 917 701770 Yb-177 8.72190E-10 4.51770E-09 701770 + 918 701771 Yb-177m 1.75610E-10 3.64560E-09 701771 + 919 701780 Yb-178 1.55370E-09 2.19230E-09 701780 + 920 701790 Yb-179 7.10640E-10 9.27220E-10 701790 + 921 701800 Yb-180 3.90460E-10 3.90460E-10 701800 + 922 701810 Yb-181 6.54590E-11 6.54590E-11 701810 + 923 711760 Lu-176 1.99780E-12 4.70450E-10 71176.82c + 924 711770 Lu-177 1.76620E-11 4.53740E-09 711770 + 925 711771 Lu-177m 8.40990E-12 8.61920E-12 711771 + 926 711780 Lu-178 2.63320E-11 2.21860E-09 711780 + 927 711781 Lu-178m 3.52770E-11 3.52770E-11 711781 + 928 711790 Lu-179 1.99600E-10 1.15340E-09 711790 + 929 711791 Lu-179m 2.65760E-11 9.53800E-10 711791 + 930 711800 Lu-180 4.43710E-11 3.01070E-10 711800 + 931 711801 Lu-180m 4.43710E-11 4.34830E-10 711801 + 932 711802 Lu-180m 7.85690E-11 7.85690E-11 711802 + 933 711810 Lu-181 2.07240E-10 2.72700E-10 711810 + 934 711820 Lu-182 7.51980E-11 7.51980E-11 711820 + 935 711830 Lu-183 3.57840E-11 3.57840E-11 711830 + 936 711840 Lu-184 4.05970E-12 4.05970E-12 711840 + 937 721790 Hf-179 9.09290E-13 1.15500E-09 72179.82c + 938 721800 Hf-180 3.41550E-12 5.68210E-10 72180.82c + 939 721801 Hf-180m 7.16540E-12 4.64500E-11 721801 + 940 721810 Hf-181 1.97390E-11 2.92440E-10 721810 + 941 721820 Hf-182 1.78900E-11 1.08850E-10 721820 + 942 721821 Hf-182m 3.75300E-11 3.75300E-11 721821 + 943 721830 Hf-183 3.49690E-11 7.07530E-11 721830 + 944 721840 Hf-184 9.60400E-12 1.16340E-11 721840 + 945 721841 Hf-184m 2.01480E-11 2.21780E-11 721841 + 946 721850 Hf-185 9.15630E-12 9.15630E-12 721850 + 947 731830 Ta-183 3.08510E-12 7.38380E-11 731830 + 948 731840 Ta-184 3.79480E-12 3.76070E-11 731840 + 949 731850 Ta-185 5.50050E-12 1.79390E-11 731850 + 950 731851 Ta-185m 3.28200E-12 3.28200E-12 731851 + + Nuclide 94241.82c -- plutonium 241 (Pu-241) + + Neutron-induced fission: + + Interpolation region : 1 / 2 + Interpolation energy : 2.53000E-08 MeV + Number of products : 958 / 1071 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 2.94220E-05 2.94220E-05 1001.82c + 2 10020 H-2 8.99170E-06 8.99170E-06 1002.82c + 3 10030 H-3 1.41000E-04 1.41000E-04 1003.82c + 4 20040 He-4 1.86000E-03 1.86000E-03 2004.82c + 5 210530 Sc-53 1.98420E-12 1.98420E-12 210530 + 6 210540 Sc-54 1.16690E-12 1.16690E-12 210540 + 7 210550 Sc-55 1.26230E-12 1.26230E-12 210550 + 8 220540 Ti-54 4.05280E-12 5.21970E-12 220540 + 9 220550 Ti-55 5.80820E-12 7.07050E-12 220550 + 10 220560 Ti-56 1.04980E-11 1.04980E-11 220560 + 11 220570 Ti-57 4.97030E-12 4.97030E-12 220570 + 12 220580 Ti-58 3.96060E-12 3.96060E-12 220580 + 13 230550 V-55 2.89680E-12 9.96730E-12 230550 + 14 230560 V-56 6.71810E-12 1.72310E-11 230560 + 15 230570 V-57 2.44570E-11 2.94120E-11 230570 + 16 230580 V-58 2.67220E-11 3.06830E-11 230580 + 17 230590 V-59 4.20210E-11 4.20210E-11 230590 + 18 230600 V-60 1.41450E-11 1.41450E-11 230600 + 19 230610 V-61 8.89800E-12 8.89800E-12 230610 + 20 230620 V-62 1.28840E-12 1.28840E-12 230620 + 21 240570 Cr-57 3.33410E-12 5.71750E-11 240570 + 22 240580 Cr-58 2.84500E-11 3.45870E-11 240580 + 23 240590 Cr-59 5.71050E-11 9.91260E-11 240590 + 24 240600 Cr-60 1.51370E-10 1.66050E-10 240600 + 25 240610 Cr-61 1.35850E-10 1.44210E-10 240610 + 26 240620 Cr-62 1.81750E-10 1.83040E-10 240620 + 27 240630 Cr-63 4.97940E-11 4.97940E-11 240630 + 28 240640 Cr-64 2.07050E-11 2.07050E-11 240640 + 29 240650 Cr-65 2.42620E-12 2.42620E-12 240650 + 30 250590 Mn-59 8.21140E-12 1.07340E-10 250590 + 31 250600 Mn-60 2.98760E-12 1.72090E-10 250600 + 32 250601 Mn-60m 2.65340E-11 2.65340E-11 250601 + 33 250610 Mn-61 2.02770E-10 3.46980E-10 250610 + 34 250620 Mn-62 2.96360E-10 3.87890E-10 250620 + 35 250621 Mn-62m 5.32050E-11 1.44720E-10 250621 + 36 250630 Mn-63 7.80040E-10 8.29830E-10 250630 + 37 250640 Mn-64 4.82100E-10 5.02810E-10 250640 + 38 250650 Mn-65 5.40590E-10 5.43020E-10 250650 + 39 250660 Mn-66 1.18150E-10 1.18150E-10 250660 + 40 250670 Mn-67 3.80490E-11 3.80490E-11 250670 + 41 250680 Mn-68 3.22810E-12 3.22810E-12 250680 + 42 260610 Fe-61 7.63210E-12 3.54620E-10 260610 + 43 260620 Fe-62 1.10880E-10 6.43490E-10 260620 + 44 260630 Fe-63 3.25030E-10 1.15490E-09 260630 + 45 260640 Fe-64 1.52760E-09 2.03040E-09 260640 + 46 260650 Fe-65 2.25840E-09 2.80140E-09 260650 + 47 260660 Fe-66 4.18160E-09 4.29980E-09 260660 + 48 260670 Fe-67 2.08160E-09 2.11960E-09 260670 + 49 260680 Fe-68 1.74200E-09 1.74520E-09 260680 + 50 260690 Fe-69 3.17860E-10 3.17860E-10 260690 + 51 260700 Fe-70 6.97070E-11 6.97070E-11 260700 + 52 260710 Fe-71 4.56690E-12 4.56690E-12 260710 + 53 270630 Co-63 1.23210E-11 1.16720E-09 270630 + 54 270640 Co-64 8.56260E-11 2.11600E-09 270640 + 55 270650 Co-65 1.02610E-09 3.82750E-09 270650 + 56 270660 Co-66 2.44330E-09 6.74300E-09 270660 + 57 270670 Co-67 9.32620E-09 1.14460E-08 270670 + 58 270680 Co-68 5.65040E-09 9.02640E-09 270680 + 59 270681 Co-68m 4.98460E-09 6.75210E-09 270681 + 60 270690 Co-69 1.71290E-08 1.74250E-08 270690 + 61 270700 Co-70 3.00820E-09 3.00820E-09 270700 + 62 270701 Co-70m 3.00820E-09 3.07800E-09 270701 + 63 270710 Co-71 3.98810E-09 3.99270E-09 270710 + 64 270720 Co-72 5.98580E-10 5.98580E-10 270720 + 65 270730 Co-73 9.13900E-11 9.13900E-11 270730 + 66 270740 Co-74 3.24360E-12 3.24360E-12 270740 + 67 280650 Ni-65 9.73820E-12 3.83730E-09 280650 + 68 280660 Ni-66 2.13210E-10 6.95630E-09 280660 + 69 280670 Ni-67 1.15500E-09 1.26010E-08 280670 + 70 280680 Ni-68 1.03330E-08 2.29100E-08 280680 + 71 280690 Ni-69 1.06200E-08 2.78700E-08 280690 + 72 280691 Ni-69m 1.06200E-08 1.06200E-08 280691 + 73 280700 Ni-70 5.84680E-08 6.45540E-08 280700 + 74 280710 Ni-71 5.49160E-08 5.89090E-08 280710 + 75 280720 Ni-72 7.56790E-08 7.62780E-08 280720 + 76 280730 Ni-73 9.39510E-08 9.40420E-08 280730 + 77 280740 Ni-74 7.00600E-09 7.00920E-09 280740 + 78 280750 Ni-75 1.08300E-09 1.08300E-09 280750 + 79 280760 Ni-76 1.57730E-10 1.57730E-10 280760 + 80 280770 Ni-77 5.43730E-12 5.43730E-12 280770 + 81 280780 Ni-78 1.22020E-12 1.22020E-12 280780 + 82 290670 Cu-67 1.06060E-11 1.26120E-08 290670 + 83 290680 Cu-68 4.55260E-11 2.30450E-08 290680 + 84 290681 Cu-68m 1.06630E-10 1.06630E-10 290681 + 85 290690 Cu-69 2.76490E-09 4.12550E-08 290690 + 86 290700 Cu-70 7.90370E-10 6.82660E-09 290700 + 87 290701 Cu-70m 8.80530E-09 1.20720E-08 290701 + 88 290702 Cu-70m 7.90370E-10 6.53450E-08 290702 + 89 290710 Cu-71 7.48450E-08 1.33750E-07 290710 + 90 290720 Cu-72 1.32570E-07 2.08850E-07 290720 + 91 290730 Cu-73 2.81850E-07 3.75890E-07 290730 + 92 290740 Cu-74 1.46660E-07 1.53690E-07 290740 + 93 290750 Cu-75 4.81180E-07 4.82250E-07 290750 + 94 290760 Cu-76 2.66330E-08 2.67110E-08 290760 + 95 290761 Cu-76m 2.66330E-08 2.67110E-08 290761 + 96 290770 Cu-77 1.93330E-08 1.93380E-08 290770 + 97 290780 Cu-78 5.45230E-09 5.45350E-09 290780 + 98 290790 Cu-79 1.15240E-09 1.15240E-09 290790 + 99 290800 Cu-80 3.71290E-11 3.71290E-11 290800 + 100 300690 Zn-69 1.15320E-12 4.12610E-08 300690 + 101 300691 Zn-69m 4.98750E-12 4.98750E-12 300691 + 102 300700 Zn-70 2.27780E-10 7.51680E-08 300700 + 103 300710 Zn-71 4.77200E-10 1.34230E-07 300710 + 104 300711 Zn-71m 2.06380E-09 2.06380E-09 300711 + 105 300720 Zn-72 3.81880E-08 2.47040E-07 300720 + 106 300730 Zn-73 1.01760E-08 4.39380E-07 300730 + 107 300731 Zn-73m 1.39110E-08 5.33130E-08 300731 + 108 300732 Zn-73m 7.88030E-08 7.88030E-08 300732 + 109 300740 Zn-74 5.48930E-07 7.19500E-07 300740 + 110 300750 Zn-75 4.81180E-07 9.47350E-07 300750 + 111 300760 Zn-76 2.25480E-06 2.30740E-06 300760 + 112 300770 Zn-77 1.45770E-06 1.58840E-06 300770 + 113 300771 Zn-77m 2.22830E-07 2.22830E-07 300771 + 114 300780 Zn-78 6.69330E-06 6.69940E-06 300780 + 115 300790 Zn-79 2.01690E-06 2.01740E-06 300790 + 116 300800 Zn-80 3.56510E-07 3.56550E-07 300800 + 117 300810 Zn-81 2.43770E-08 2.43770E-08 300810 + 118 300820 Zn-82 2.12470E-09 2.12470E-09 300820 + 119 300830 Zn-83 4.98350E-11 4.98350E-11 300830 + 120 310710 Ga-71 5.30480E-12 1.36300E-07 310710 + 121 310720 Ga-72 1.22070E-10 2.47170E-07 310720 + 122 310721 Ga-72m 1.37450E-11 8.24510E-09 310721 + 123 310730 Ga-73 3.50620E-09 4.82290E-07 310730 + 124 310740 Ga-74 1.07560E-08 5.58440E-07 310740 + 125 310741 Ga-74m 1.07560E-08 7.30250E-07 310741 + 126 310750 Ga-75 4.81180E-07 1.42850E-06 310750 + 127 310760 Ga-76 2.37350E-07 2.54480E-06 310760 + 128 310770 Ga-77 2.28060E-06 3.98040E-06 310770 + 129 310780 Ga-78 9.84270E-06 1.65680E-05 310780 + 130 310790 Ga-79 4.03440E-05 4.23350E-05 310790 + 131 310800 Ga-80 2.82470E-05 2.86050E-05 310800 + 132 310810 Ga-81 2.94890E-05 2.95120E-05 310810 + 133 310820 Ga-82 1.16710E-05 1.16730E-05 310820 + 134 310830 Ga-83 6.11600E-07 6.11650E-07 310830 + 135 310840 Ga-84 2.78480E-08 2.78480E-08 310840 + 136 310850 Ga-85 1.05070E-09 1.05070E-09 310850 + 137 320730 Ge-73 1.40260E-12 4.82290E-07 32073.82c + 138 320731 Ge-73m 3.24310E-13 4.75210E-07 320731 + 139 320740 Ge-74 1.10150E-10 7.41120E-07 32074.82c + 140 320750 Ge-75 3.82020E-10 1.43140E-06 320750 + 141 320751 Ge-75m 2.49900E-09 5.96400E-08 320751 + 142 320760 Ge-76 1.18670E-07 2.66340E-06 32076.82c + 143 320770 Ge-77 7.28800E-07 1.50620E-06 320770 + 144 320771 Ge-77m 1.11410E-07 4.09180E-06 320771 + 145 320780 Ge-78 1.41720E-05 3.07780E-05 320780 + 146 320790 Ge-79 8.11110E-06 5.24700E-05 320790 + 147 320791 Ge-79m 5.30590E-05 5.31220E-05 320791 + 148 320800 Ge-80 2.08790E-04 2.40910E-04 320800 + 149 320810 Ge-81 2.79890E-04 2.95650E-04 320810 + 150 320811 Ge-81m 6.47180E-05 7.82300E-05 320811 + 151 320820 Ge-82 4.70890E-04 4.80300E-04 320820 + 152 320830 Ge-83 2.76120E-04 2.76530E-04 320830 + 153 320840 Ge-84 1.16560E-04 1.16570E-04 320840 + 154 320850 Ge-85 5.61050E-06 5.61150E-06 320850 + 155 320860 Ge-86 2.83010E-06 2.83010E-06 320860 + 156 320870 Ge-87 1.11540E-08 1.11540E-08 320870 + 157 320880 Ge-88 4.08590E-10 4.08590E-10 320880 + 158 330750 As-75 3.10790E-13 1.43140E-06 33075.82c + 159 330751 As-75m 1.01680E-12 1.89090E-11 330751 + 160 330760 As-76 5.76320E-11 5.76320E-11 330760 + 161 330770 As-77 1.20030E-07 4.94070E-06 330770 + 162 330780 As-78 3.93700E-07 3.11720E-05 330780 + 163 330790 As-79 4.03360E-06 1.07500E-04 330790 + 164 330800 As-80 3.22710E-05 2.73180E-04 330800 + 165 330810 As-81 1.54030E-04 5.27130E-04 330810 + 166 330820 As-82 1.07400E-04 5.87700E-04 330820 + 167 330821 As-82m 3.24090E-04 3.24090E-04 330821 + 168 330830 As-83 9.54580E-04 1.24370E-03 330830 + 169 330840 As-84 4.27460E-04 4.79840E-04 330840 + 170 330841 As-84m 4.27460E-04 4.79840E-04 330841 + 171 330850 As-85 4.77550E-04 4.82380E-04 330850 + 172 330860 As-86 1.81140E-04 1.83970E-04 330860 + 173 330870 As-87 5.83970E-05 5.84080E-05 330870 + 174 330880 As-88 1.18160E-05 1.18160E-05 330880 + 175 330890 As-89 1.75790E-07 1.75790E-07 330890 + 176 330900 As-90 3.13230E-09 3.13230E-09 330900 + 177 340780 Se-78 1.92790E-10 3.11720E-05 34078.82c + 178 340790 Se-79 5.83140E-07 1.08120E-04 34079.82c + 179 340791 Se-79m 8.91440E-08 1.05040E-04 340791 + 180 340800 Se-80 4.03430E-06 2.77210E-04 34080.82c + 181 340810 Se-81 3.37560E-06 5.52560E-04 340810 + 182 340811 Se-81m 2.20810E-05 4.10040E-05 340811 + 183 340820 Se-82 1.48230E-04 1.06000E-03 34082.82c + 184 340830 Se-83 6.02360E-04 1.05080E-03 340830 + 185 340831 Se-83m 1.39280E-04 9.35920E-04 340831 + 186 340840 Se-84 2.48670E-03 3.55120E-03 340840 + 187 340850 Se-85 2.88000E-03 3.31700E-03 340850 + 188 340860 Se-86 4.44370E-03 4.57590E-03 340860 + 189 340870 Se-87 3.25210E-03 3.30150E-03 340870 + 190 340880 Se-88 1.59920E-03 1.61100E-03 340880 + 191 340890 Se-89 3.93020E-04 3.93200E-04 340890 + 192 340900 Se-90 9.37320E-05 9.37350E-05 340900 + 193 340910 Se-91 1.81510E-06 1.81510E-06 340910 + 194 340920 Se-92 1.90320E-06 1.90320E-06 340920 + 195 340930 Se-93 7.13640E-10 7.13640E-10 340930 + 196 350800 Br-80 3.38850E-11 1.36140E-10 350800 + 197 350801 Br-80m 1.02250E-10 1.02250E-10 350801 + 198 350810 Br-81 1.66800E-08 5.52600E-04 35081.82c + 199 350820 Br-82 3.09330E-07 4.38230E-07 350820 + 200 350821 Br-82m 1.32070E-07 1.32070E-07 350821 + 201 350830 Br-83 1.37320E-05 2.00040E-03 350830 + 202 350840 Br-84 5.95850E-05 3.61070E-03 350840 + 203 350841 Br-84m 5.95850E-05 5.95850E-05 350841 + 204 350850 Br-85 5.11810E-04 3.82880E-03 350850 + 205 350860 Br-86 1.13860E-03 5.71450E-03 350860 + 206 350870 Br-87 2.81740E-03 6.13490E-03 350870 + 207 350880 Br-88 4.01530E-03 5.64100E-03 350880 + 208 350890 Br-89 3.77510E-03 4.13760E-03 350890 + 209 350900 Br-90 1.80770E-03 1.90180E-03 350900 + 210 350910 Br-91 8.42250E-04 8.43680E-04 350910 + 211 350920 Br-92 1.84790E-04 1.86690E-04 350920 + 212 350930 Br-93 4.41480E-05 4.41490E-05 350930 + 213 350940 Br-94 3.51020E-06 3.51020E-06 350940 + 214 350950 Br-95 1.52020E-08 1.52020E-08 350950 + 215 360820 Kr-82 1.24980E-10 4.41520E-07 36082.82c + 216 360830 Kr-83 5.54530E-09 2.00040E-03 36083.82c + 217 360831 Kr-83m 1.28220E-09 1.99860E-03 360831 + 218 360840 Kr-84 3.81030E-06 3.67410E-03 36084.82c + 219 360850 Kr-85 2.37610E-05 8.49190E-04 36085.82c + 220 360851 Kr-85m 5.49410E-06 3.82800E-03 360851 + 221 360860 Kr-86 3.54780E-04 6.22330E-03 36086.82c + 222 360870 Kr-87 1.13520E-03 7.49400E-03 360870 + 223 360880 Kr-88 3.94590E-03 9.79240E-03 360880 + 224 360890 Kr-89 6.89600E-03 1.09180E-02 360890 + 225 360900 Kr-90 1.08540E-02 1.24570E-02 360900 + 226 360910 Kr-91 9.55020E-03 1.02870E-02 360910 + 227 360920 Kr-92 7.99650E-03 8.15140E-03 360920 + 228 360930 Kr-93 3.52420E-03 3.54080E-03 360930 + 229 360940 Kr-94 1.16930E-03 1.17030E-03 360940 + 230 360950 Kr-95 1.97790E-04 1.97810E-04 360950 + 231 360960 Kr-96 4.01090E-05 4.01090E-05 360960 + 232 360970 Kr-97 3.86770E-06 3.86770E-06 360970 + 233 360980 Kr-98 2.01400E-09 2.01400E-09 360980 + 234 370850 Rb-85 2.49540E-09 3.85800E-03 37085.82c + 235 370860 Rb-86 3.30590E-08 9.25260E-08 37086.82c + 236 370861 Rb-86m 5.94660E-08 5.94660E-08 370861 + 237 370870 Rb-87 2.02360E-05 7.51430E-03 37087.82c + 238 370880 Rb-88 1.21250E-04 9.91360E-03 370880 + 239 370890 Rb-89 7.08990E-04 1.16270E-02 370890 + 240 370900 Rb-90 1.92710E-04 1.11070E-02 370900 + 241 370901 Rb-90m 1.71160E-03 3.34090E-03 370901 + 242 370910 Rb-91 5.47030E-03 1.57570E-02 370910 + 243 370920 Rb-92 9.23980E-03 1.73910E-02 370920 + 244 370930 Rb-93 1.37100E-02 1.72640E-02 370930 + 245 370940 Rb-94 8.63890E-03 9.80190E-03 370940 + 246 370950 Rb-95 6.26540E-03 6.45900E-03 370950 + 247 370960 Rb-96 1.02030E-03 1.55950E-03 370960 + 248 370961 Rb-96m 1.02030E-03 1.03970E-03 370961 + 249 370970 Rb-97 6.99760E-04 7.03370E-04 370970 + 250 370980 Rb-98 4.64130E-05 4.64130E-05 370980 + 251 370981 Rb-98m 4.64130E-05 4.64140E-05 370981 + 252 370990 Rb-99 2.32700E-05 2.32700E-05 370990 + 253 371000 Rb-100 1.90980E-08 1.90980E-08 371000 + 254 380870 Sr-87 3.01980E-10 3.71590E-10 38087.82c + 255 380871 Sr-87m 6.98240E-11 6.98240E-11 380871 + 256 380880 Sr-88 2.62020E-06 9.91630E-03 38088.82c + 257 380890 Sr-89 1.93510E-05 1.16460E-02 38089.82c + 258 380900 Sr-90 2.15650E-04 1.45770E-02 38090.82c + 259 380910 Sr-91 9.05590E-04 1.66630E-02 380910 + 260 380920 Sr-92 4.55830E-03 2.21910E-02 380920 + 261 380930 Sr-93 1.05810E-02 2.85930E-02 380930 + 262 380940 Sr-94 2.13660E-02 3.07330E-02 380940 + 263 380950 Sr-95 2.57900E-02 3.19030E-02 380950 + 264 380960 Sr-96 2.60480E-02 2.80950E-02 380960 + 265 380970 Sr-97 1.51510E-02 1.56840E-02 380970 + 266 380980 Sr-98 7.77360E-03 7.86370E-03 380980 + 267 380990 Sr-99 2.10800E-03 2.12760E-03 380990 + 268 381000 Sr-100 5.94810E-04 5.94830E-04 381000 + 269 381010 Sr-101 5.29470E-05 5.29470E-05 381010 + 270 381020 Sr-102 6.95050E-06 6.95050E-06 381020 + 271 381030 Sr-103 3.52420E-09 3.52420E-09 381030 + 272 390900 Y-90 4.04180E-07 1.45780E-02 39090.82c + 273 390901 Y-90m 5.73530E-07 5.73530E-07 390901 + 274 390910 Y-91 1.19240E-06 1.66690E-02 39091.82c + 275 390911 Y-91m 5.15720E-06 9.80880E-03 390911 + 276 390920 Y-92 3.99450E-05 2.22310E-02 390920 + 277 390930 Y-93 5.66680E-05 2.90200E-02 390930 + 278 390931 Y-93m 3.70690E-04 7.52580E-03 390931 + 279 390940 Y-94 1.37950E-03 3.21130E-02 390940 + 280 390950 Y-95 6.34110E-03 3.82440E-02 390950 + 281 390960 Y-96 4.17080E-03 3.22700E-02 390960 + 282 390961 Y-96m 7.50220E-03 7.50620E-03 390961 + 283 390970 Y-97 4.34790E-03 1.78340E-02 390970 + 284 390971 Y-97m 1.48200E-02 2.03380E-02 390971 + 285 390972 Y-97m 3.98210E-03 3.98210E-03 390972 + 286 390980 Y-98 4.08370E-03 1.19470E-02 390980 + 287 390981 Y-98m 1.71740E-02 1.71740E-02 390981 + 288 390990 Y-99 2.04590E-02 2.25910E-02 390990 + 289 391000 Y-100 5.22750E-03 5.81830E-03 391000 + 290 391001 Y-100m 5.22750E-03 5.22810E-03 391001 + 291 391010 Y-101 4.26140E-03 4.31350E-03 391010 + 292 391020 Y-102 5.09200E-04 5.12480E-04 391020 + 293 391021 Y-102m 5.09200E-04 5.12480E-04 391021 + 294 391030 Y-103 2.93390E-04 2.93390E-04 391030 + 295 391040 Y-104 3.49240E-05 3.49240E-05 391040 + 296 391050 Y-105 2.80240E-06 2.80240E-06 391050 + 297 400920 Zr-92 9.51190E-07 2.22320E-02 40092.82c + 298 400930 Zr-93 7.01180E-06 2.90280E-02 40093.82c + 299 400940 Zr-94 9.21190E-05 3.22050E-02 40094.82c + 300 400950 Zr-95 4.65310E-04 3.87090E-02 40095.82c + 301 400960 Zr-96 2.66120E-03 4.24530E-02 40096.82c + 302 400970 Zr-97 7.44010E-03 4.68730E-02 400970 + 303 400980 Zr-98 2.14960E-02 5.03790E-02 400980 + 304 400990 Zr-99 3.15540E-02 5.38150E-02 400990 + 305 401000 Zr-100 4.81930E-02 5.91860E-02 401000 + 306 401010 Zr-101 3.02340E-02 3.45980E-02 401010 + 307 401020 Zr-102 2.33680E-02 2.43660E-02 401020 + 308 401030 Zr-103 9.87010E-03 1.01430E-02 401030 + 309 401040 Zr-104 3.69690E-03 3.72930E-03 401040 + 310 401050 Zr-105 6.56740E-04 6.58990E-04 401050 + 311 401060 Zr-106 1.16280E-04 1.16280E-04 401060 + 312 401070 Zr-107 1.28870E-05 1.28870E-05 401070 + 313 401080 Zr-108 3.21860E-09 3.21860E-09 401080 + 314 410950 Nb-95 7.71510E-07 3.86860E-02 41095.82c + 315 410951 Nb-95m 1.78390E-07 4.18370E-04 410951 + 316 410960 Nb-96 1.11910E-05 1.11910E-05 410960 + 317 410970 Nb-97 8.87570E-05 4.69820E-02 410970 + 318 410971 Nb-97m 2.05230E-05 4.45720E-02 410971 + 319 410980 Nb-98 1.49750E-04 5.05280E-02 410980 + 320 410981 Nb-98m 4.51890E-04 4.51890E-04 410981 + 321 410990 Nb-99 2.76680E-03 3.71860E-02 410990 + 322 410991 Nb-99m 6.39740E-04 2.04430E-02 410991 + 323 411000 Nb-100 1.80280E-03 6.09890E-02 411000 + 324 411001 Nb-100m 7.58170E-03 7.58170E-03 411001 + 325 411010 Nb-101 2.06560E-02 5.52540E-02 411010 + 326 411020 Nb-102 1.35470E-02 3.79130E-02 411020 + 327 411021 Nb-102m 1.35470E-02 1.35470E-02 411021 + 328 411030 Nb-103 3.55610E-02 4.57040E-02 411030 + 329 411040 Nb-104 1.09370E-02 1.46760E-02 411040 + 330 411041 Nb-104m 1.09370E-02 1.09370E-02 411041 + 331 411050 Nb-105 1.41260E-02 1.47780E-02 411050 + 332 411060 Nb-106 5.72390E-03 5.83890E-03 411060 + 333 411070 Nb-107 2.04290E-03 2.05530E-03 411070 + 334 411080 Nb-108 3.56170E-04 3.56170E-04 411080 + 335 411090 Nb-109 4.57390E-05 4.57390E-05 411090 + 336 411100 Nb-110 2.94600E-06 2.94600E-06 411100 + 337 420970 Mo-97 2.34200E-09 4.69820E-02 42097.82c + 338 420980 Mo-98 1.43540E-05 5.09950E-02 42098.82c + 339 420990 Mo-99 1.21500E-04 5.73430E-02 42099.82c + 340 421000 Mo-100 9.48780E-04 6.95190E-02 42100.82c + 341 421010 Mo-101 3.07470E-03 5.83280E-02 421010 + 342 421020 Mo-102 1.18540E-02 6.33140E-02 421020 + 343 421030 Mo-103 2.28570E-02 6.85750E-02 421030 + 344 421040 Mo-104 4.04450E-02 6.62950E-02 421040 + 345 421050 Mo-105 3.47640E-02 4.95530E-02 421050 + 346 421060 Mo-106 3.64070E-02 4.21060E-02 421060 + 347 421070 Mo-107 1.80630E-02 2.00170E-02 421070 + 348 421080 Mo-108 8.97360E-03 9.31350E-03 421080 + 349 421090 Mo-109 2.25720E-03 2.29830E-03 421090 + 350 421100 Mo-110 4.54790E-04 4.56560E-04 421100 + 351 421110 Mo-111 3.31630E-05 3.31630E-05 421110 + 352 421120 Mo-112 5.07850E-06 5.07850E-06 421120 + 353 421130 Mo-113 1.00280E-06 1.00280E-06 421130 + 354 431000 Tc-100 3.28560E-06 3.28560E-06 431000 + 355 431010 Tc-101 1.70220E-05 5.83450E-02 431010 + 356 431020 Tc-102 8.20500E-05 6.33960E-02 431020 + 357 431021 Tc-102m 8.20500E-05 8.20500E-05 431021 + 358 431030 Tc-103 1.03170E-03 6.96070E-02 431030 + 359 431040 Tc-104 2.99610E-03 6.92920E-02 431040 + 360 431050 Tc-105 9.15320E-03 5.87060E-02 431050 + 361 431060 Tc-106 1.59850E-02 5.80910E-02 431060 + 362 431070 Tc-107 2.42410E-02 4.42580E-02 431070 + 363 431080 Tc-108 1.89190E-02 2.82450E-02 431080 + 364 431090 Tc-109 1.26800E-02 1.49660E-02 431090 + 365 431100 Tc-110 5.00930E-03 5.46620E-03 431100 + 366 431110 Tc-111 1.45490E-03 1.48780E-03 431110 + 367 431120 Tc-112 1.90060E-04 1.95030E-04 431120 + 368 431130 Tc-113 1.40780E-04 1.41780E-04 431130 + 369 431140 Tc-114 1.70290E-04 1.70290E-04 431140 + 370 431150 Tc-115 1.30030E-04 1.30030E-04 431150 + 371 431160 Tc-116 2.78120E-05 2.78120E-05 431160 + 372 441020 Ru-102 1.98600E-06 6.34800E-02 44102.82c + 373 441030 Ru-103 3.05110E-06 6.96170E-02 44103.82c + 374 441031 Ru-103m 7.36590E-06 7.36590E-06 441031 + 375 441040 Ru-104 1.12820E-04 6.94040E-02 44104.82c + 376 441050 Ru-105 5.36900E-04 5.92430E-02 44105.82c + 377 441060 Ru-106 2.58260E-03 6.06740E-02 44106.82c + 378 441070 Ru-107 5.41220E-03 4.96700E-02 441070 + 379 441080 Ru-108 1.13930E-02 3.96500E-02 441080 + 380 441090 Ru-109 1.10040E-02 2.59600E-02 441090 + 381 441100 Ru-110 9.09990E-03 1.45640E-02 441100 + 382 441110 Ru-111 3.47720E-03 4.96790E-03 441110 + 383 441120 Ru-112 1.03260E-03 1.23490E-03 441120 + 384 441130 Ru-113 3.48200E-04 6.65020E-04 441130 + 385 441131 Ru-113m 3.48200E-04 3.48200E-04 441131 + 386 441140 Ru-114 9.10660E-04 1.08850E-03 441140 + 387 441150 Ru-115 3.31690E-04 4.46480E-04 441150 + 388 441160 Ru-116 1.92570E-04 2.16980E-04 441160 + 389 441170 Ru-117 7.70510E-05 7.70510E-05 441170 + 390 441180 Ru-118 5.73240E-05 5.73240E-05 441180 + 391 451050 Rh-105 8.10380E-07 5.92440E-02 45105.82c + 392 451051 Rh-105m 1.23880E-07 1.68180E-02 451051 + 393 451060 Rh-106 3.19990E-06 6.06770E-02 451060 + 394 451061 Rh-106m 7.49510E-06 7.49510E-06 451061 + 395 451070 Rh-107 1.05740E-04 4.97760E-02 451070 + 396 451080 Rh-108 9.09330E-05 3.97410E-02 451080 + 397 451081 Rh-108m 2.74410E-04 2.74410E-04 451081 + 398 451090 Rh-109 1.15020E-03 2.71110E-02 451090 + 399 451100 Rh-110 1.49360E-03 1.60570E-02 451100 + 400 451101 Rh-110m 3.98710E-05 3.98710E-05 451101 + 401 451110 Rh-111 1.54830E-03 6.51630E-03 451110 + 402 451120 Rh-112 3.14220E-04 1.54910E-03 451120 + 403 451121 Rh-112m 3.14220E-04 3.14220E-04 451121 + 404 451130 Rh-113 8.86990E-04 1.72610E-03 451130 + 405 451140 Rh-114 5.75550E-04 1.66500E-03 451140 + 406 451141 Rh-114m 5.75550E-04 5.75550E-04 451141 + 407 451150 Rh-115 6.58750E-04 1.10660E-03 451150 + 408 451160 Rh-116 4.74170E-05 2.63630E-04 451160 + 409 451161 Rh-116m 1.11060E-04 1.11060E-04 451161 + 410 451170 Rh-117 7.76730E-05 1.55500E-04 451170 + 411 451180 Rh-118 1.43980E-05 6.93660E-05 451180 + 412 451190 Rh-119 2.69640E-08 2.69640E-08 451190 + 413 451200 Rh-120 2.25410E-10 2.25410E-10 451200 + 414 451220 Rh-122 1.61890E-07 1.61890E-07 451220 + 415 461070 Pd-107 7.46280E-07 4.97780E-02 46107.82c + 416 461071 Pd-107m 1.40250E-06 1.40250E-06 461071 + 417 461080 Pd-108 9.97980E-06 4.00250E-02 46108.82c + 418 461090 Pd-109 7.97160E-06 2.71340E-02 461090 + 419 461091 Pd-109m 1.49810E-05 1.35700E-02 461091 + 420 461100 Pd-110 6.32090E-05 1.61610E-02 46110.82c + 421 461110 Pd-111 3.48480E-05 6.59190E-03 461110 + 422 461111 Pd-111m 6.54920E-05 9.15570E-05 461111 + 423 461120 Pd-112 1.02870E-04 1.96620E-03 461120 + 424 461130 Pd-113 5.96840E-05 1.92990E-03 461130 + 425 461131 Pd-113m 1.44090E-04 1.44090E-04 461131 + 426 461140 Pd-114 6.05790E-04 2.84640E-03 461140 + 427 461150 Pd-115 1.91430E-04 1.17900E-03 461150 + 428 461151 Pd-115m 3.59760E-04 5.20430E-04 461151 + 429 461160 Pd-116 5.25110E-04 8.99810E-04 461160 + 430 461170 Pd-117 1.43030E-04 5.69350E-04 461170 + 431 461171 Pd-117m 2.68800E-04 2.68800E-04 461171 + 432 461180 Pd-118 2.59800E-04 3.27140E-04 461180 + 433 461190 Pd-119 1.22230E-04 1.22260E-04 461190 + 434 461200 Pd-120 2.64990E-05 2.64990E-05 461200 + 435 461210 Pd-121 1.69240E-05 1.69240E-05 461210 + 436 461220 Pd-122 3.53610E-05 3.55230E-05 461220 + 437 461230 Pd-123 1.09100E-05 1.09100E-05 461230 + 438 461240 Pd-124 2.14610E-06 2.14610E-06 461240 + 439 471100 Ag-110 9.14410E-10 9.43540E-10 471100 + 440 471101 Ag-110m 2.14180E-09 2.14180E-09 47510.82c + 441 471110 Ag-111 9.78300E-08 6.58450E-03 47111.82c + 442 471111 Ag-111m 6.39950E-07 6.56370E-03 471111 + 443 471120 Ag-112 2.54060E-06 1.96880E-03 471120 + 444 471130 Ag-113 1.19740E-06 1.27080E-03 471130 + 445 471131 Ag-113m 7.83250E-06 1.85580E-03 471131 + 446 471140 Ag-114 3.75820E-06 2.86590E-03 471140 + 447 471141 Ag-114m 1.58060E-05 1.58060E-05 471141 + 448 471150 Ag-115 1.19150E-05 1.05630E-03 471150 + 449 471151 Ag-115m 7.79410E-05 8.75060E-04 471151 + 450 471160 Ag-116 4.17740E-05 9.47450E-04 471160 + 451 471161 Ag-116m 9.78460E-05 9.78460E-05 471161 + 452 471170 Ag-117 3.09020E-05 3.44790E-04 471170 + 453 471171 Ag-117m 2.02150E-04 4.86820E-04 471171 + 454 471180 Ag-118 4.15320E-05 4.12700E-04 471180 + 455 471181 Ag-118m 1.74670E-04 2.21440E-04 471181 + 456 471190 Ag-119 5.78770E-05 1.19010E-04 471190 + 457 471191 Ag-119m 3.78600E-04 4.39730E-04 471191 + 458 471200 Ag-120 6.57880E-05 1.18530E-04 471200 + 459 471201 Ag-120m 9.33520E-05 1.06600E-04 471201 + 460 471210 Ag-121 3.72480E-04 3.89360E-04 471210 + 461 471220 Ag-122 1.02230E-04 1.37760E-04 471220 + 462 471221 Ag-122m 9.20880E-05 9.20880E-05 471221 + 463 471230 Ag-123 1.34570E-04 1.45480E-04 471230 + 464 471240 Ag-124 4.21630E-05 6.32980E-05 471240 + 465 471241 Ag-124m 3.79790E-05 3.79790E-05 471241 + 466 471250 Ag-125 4.86700E-05 4.86700E-05 471250 + 467 471260 Ag-126 2.77830E-05 2.77830E-05 471260 + 468 471270 Ag-127 4.94190E-06 4.94190E-06 471270 + 469 471280 Ag-128 5.65150E-08 5.65150E-08 471280 + 470 471290 Ag-129 3.29550E-09 3.29550E-09 471290 + 471 481120 Cd-112 7.78760E-11 1.96880E-03 48112.82c + 472 481130 Cd-113 2.34780E-07 1.91720E-03 48113.82c + 473 481131 Cd-113m 7.68120E-07 2.27390E-05 481131 + 474 481140 Cd-114 2.09700E-07 2.86610E-03 48114.82c + 475 481150 Cd-115 3.61800E-07 1.66700E-03 481150 + 476 481151 Cd-115m 1.18370E-06 8.21770E-05 48515.82c + 477 481160 Cd-116 1.85830E-05 1.05800E-03 48116.82c + 478 481170 Cd-117 2.59450E-06 6.33270E-04 481170 + 479 481171 Cd-117m 8.48850E-06 1.80210E-04 481171 + 480 481180 Cd-118 1.00780E-04 6.44120E-04 481180 + 481 481190 Cd-119 8.17190E-05 5.80950E-04 481190 + 482 481191 Cd-119m 1.97280E-04 2.56790E-04 481191 + 483 481200 Cd-120 2.29120E-04 4.14800E-04 481200 + 484 481210 Cd-121 1.13730E-04 4.62410E-04 481210 + 485 481211 Cd-121m 2.74560E-04 3.15240E-04 481211 + 486 481220 Cd-122 4.92180E-04 7.22020E-04 481220 + 487 481230 Cd-123 1.51300E-04 2.70360E-04 481230 + 488 481231 Cd-123m 3.65250E-04 3.91740E-04 481231 + 489 481240 Cd-124 1.01660E-03 1.09880E-03 481240 + 490 481250 Cd-125 2.38520E-04 2.62850E-04 481250 + 491 481251 Cd-125m 5.75810E-04 6.00150E-04 481251 + 492 481260 Cd-126 6.68190E-04 6.95970E-04 481260 + 493 481270 Cd-127 3.08940E-04 3.13880E-04 481270 + 494 481280 Cd-128 1.20760E-04 1.20820E-04 481280 + 495 481290 Cd-129 1.20790E-05 1.20810E-05 481290 + 496 481291 Cd-129m 2.91610E-05 2.91630E-05 481291 + 497 481300 Cd-130 1.49850E-05 1.49850E-05 481300 + 498 481310 Cd-131 5.72590E-08 5.72590E-08 481310 + 499 481320 Cd-132 1.77870E-09 1.77870E-09 481320 + 500 491150 In-115 3.52550E-10 1.66580E-03 49115.82c + 501 491151 In-115m 8.15180E-11 1.66700E-03 491151 + 502 491160 In-116 1.93350E-09 1.93350E-09 491160 + 503 491161 In-116m 2.96360E-09 5.83410E-09 491161 + 504 491162 In-116m 2.87040E-09 2.87040E-09 491162 + 505 491170 In-117 1.91250E-07 5.05240E-04 491170 + 506 491171 In-117m 4.42210E-08 5.83140E-04 491171 + 507 491180 In-118 4.25670E-07 6.44550E-04 491180 + 508 491181 In-118m 6.52440E-07 1.27550E-06 491181 + 509 491182 In-118m 6.31920E-07 6.31920E-07 491182 + 510 491190 In-119 2.25070E-05 3.64910E-04 491190 + 511 491191 In-119m 5.20410E-06 5.30240E-04 491191 + 512 491200 In-120 1.35660E-05 4.28370E-04 491200 + 513 491201 In-120m 1.35660E-05 1.35660E-05 491201 + 514 491202 In-120m 1.35660E-05 1.35660E-05 491202 + 515 491210 In-121 5.49230E-05 5.29740E-04 491210 + 516 491211 In-121m 1.27000E-05 3.19370E-04 491211 + 517 491220 In-122 8.00960E-05 8.02120E-04 491220 + 518 491221 In-122m 5.68270E-05 5.68270E-05 491221 + 519 491222 In-122m 5.68270E-05 5.68270E-05 491222 + 520 491230 In-123 3.37990E-04 8.08690E-04 491230 + 521 491231 In-123m 7.81510E-05 2.69540E-04 491231 + 522 491240 In-124 2.03810E-04 1.30260E-03 491240 + 523 491241 In-124m 1.83580E-04 1.83580E-04 491241 + 524 491250 In-125 7.05220E-04 1.43120E-03 491250 + 525 491251 In-125m 1.63060E-04 3.00110E-04 491251 + 526 491260 In-126 6.54680E-04 1.35060E-03 491260 + 527 491261 In-126m 5.89720E-04 5.89720E-04 491261 + 528 491270 In-127 1.41640E-03 1.41640E-03 491270 + 529 491271 In-127m 3.27500E-04 6.41390E-04 491271 + 530 491280 In-128 4.36270E-04 7.34670E-04 491280 + 531 491281 In-128m 1.77590E-04 2.98400E-04 491281 + 532 491282 In-128m 5.52950E-04 5.52950E-04 491282 + 533 491290 In-129 8.71900E-04 9.01320E-04 491290 + 534 491291 In-129m 2.01600E-04 2.13950E-04 491291 + 535 491300 In-130 1.93280E-04 2.07750E-04 491300 + 536 491301 In-130m 2.15880E-04 2.15880E-04 491301 + 537 491302 In-130m 3.67310E-04 3.67310E-04 491302 + 538 491310 In-131 1.22230E-04 1.23530E-04 491310 + 539 491311 In-131m 1.22230E-04 1.22230E-04 491311 + 540 491312 In-131m 1.22230E-04 1.22230E-04 491312 + 541 491320 In-132 4.22880E-05 4.22890E-05 491320 + 542 491330 In-133 6.39890E-06 7.87850E-06 491330 + 543 491331 In-133m 1.47960E-06 1.47960E-06 491331 + 544 491340 In-134 2.38200E-08 2.38200E-08 491340 + 545 501170 Sn-117 4.75570E-12 8.13720E-04 50117.82c + 546 501171 Sn-117m 1.55590E-11 1.72140E-06 501171 + 547 501180 Sn-118 1.21980E-09 6.45830E-04 50118.82c + 548 501190 Sn-119 8.10990E-09 8.65490E-04 50119.82c + 549 501191 Sn-119m 2.65330E-08 3.29680E-04 501191 + 550 501200 Sn-120 5.13840E-07 4.56010E-04 50120.82c + 551 501210 Sn-121 4.96850E-06 8.46100E-04 501210 + 552 501211 Sn-121m 1.19950E-05 7.20050E-05 501211 + 553 501220 Sn-122 7.14260E-05 9.87200E-04 50122.82c + 554 501230 Sn-123 1.09460E-04 1.71120E-04 50123.82c + 555 501231 Sn-123m 4.53410E-05 1.06190E-03 501231 + 556 501240 Sn-124 1.43320E-04 1.62950E-03 50124.82c + 557 501250 Sn-125 3.33490E-04 5.75250E-04 50125.82c + 558 501251 Sn-125m 1.38140E-04 1.62770E-03 501251 + 559 501260 Sn-126 1.15220E-03 3.09700E-03 50126.82c + 560 501270 Sn-127 1.63790E-03 2.18990E-03 501270 + 561 501271 Sn-127m 6.78440E-04 2.17970E-03 501271 + 562 501280 Sn-128 1.62360E-03 6.71420E-03 501280 + 563 501281 Sn-128m 3.80300E-03 4.35590E-03 501281 + 564 501290 Sn-129 2.46270E-03 3.48210E-03 501290 + 565 501291 Sn-129m 5.94530E-03 6.04120E-03 501291 + 566 501300 Sn-130 3.53180E-03 4.04790E-03 501300 + 567 501301 Sn-130m 8.27220E-03 8.54950E-03 501301 + 568 501310 Sn-131 2.72360E-03 2.96040E-03 501310 + 569 501311 Sn-131m 6.57520E-03 6.70270E-03 501311 + 570 501320 Sn-132 6.27070E-03 6.31970E-03 501320 + 571 501330 Sn-133 1.15590E-03 1.15710E-03 501330 + 572 501340 Sn-134 2.21630E-04 2.21640E-04 501340 + 573 501350 Sn-135 1.38580E-05 1.38580E-05 501350 + 574 501360 Sn-136 2.93030E-06 2.93030E-06 501360 + 575 501370 Sn-137 3.28870E-09 3.28870E-09 501370 + 576 511200 Sb-120 2.32950E-11 2.32950E-11 511200 + 577 511201 Sb-120m 3.30560E-11 3.30560E-11 511201 + 578 511210 Sb-121 8.57750E-09 8.62240E-04 51121.82c + 579 511230 Sb-123 3.38800E-05 1.26690E-03 51123.82c + 580 511240 Sb-124 7.18670E-06 1.68820E-05 51124.82c + 581 511241 Sb-124m 5.49510E-06 1.29270E-05 511241 + 582 511242 Sb-124m 7.43210E-06 7.43210E-06 511242 + 583 511250 Sb-125 5.46110E-05 2.25750E-03 51125.82c + 584 511260 Sb-126 2.91190E-05 3.60750E-05 51126.82c + 585 511261 Sb-126m 2.15300E-05 4.96880E-05 511261 + 586 511262 Sb-126m 2.81580E-05 2.81580E-05 511262 + 587 511270 Sb-127 1.75610E-04 4.54530E-03 511270 + 588 511280 Sb-128 1.41220E-04 6.86410E-03 511280 + 589 511281 Sb-128m 2.40970E-04 2.40970E-04 511281 + 590 511290 Sb-129 1.26770E-03 8.33960E-03 511290 + 591 511291 Sb-129m 7.74640E-04 3.79520E-03 511291 + 592 511300 Sb-130 3.08180E-03 1.14040E-02 511300 + 593 511301 Sb-130m 3.08180E-03 7.35650E-03 511301 + 594 511310 Sb-131 1.84090E-02 2.80720E-02 511310 + 595 511320 Sb-132 1.40820E-02 2.04020E-02 511320 + 596 511321 Sb-132m 1.03790E-02 1.03790E-02 511321 + 597 511330 Sb-133 2.74370E-02 2.86320E-02 511330 + 598 511340 Sb-134 2.82600E-03 3.01140E-03 511340 + 599 511341 Sb-134m 6.61910E-03 6.62060E-03 511341 + 600 511350 Sb-135 2.86240E-03 2.87420E-03 511350 + 601 511360 Sb-136 6.49720E-04 6.51770E-04 511360 + 602 511370 Sb-137 9.49860E-05 9.49870E-05 511370 + 603 511380 Sb-138 2.80560E-06 2.80560E-06 511380 + 604 511390 Sb-139 3.62180E-08 3.62180E-08 511390 + 605 521260 Te-126 2.51270E-10 7.88070E-05 52126.82c + 606 521270 Te-127 4.25730E-09 4.52730E-03 521270 + 607 521271 Te-127m 1.02780E-08 7.49050E-04 52527.82c + 608 521280 Te-128 1.17650E-05 7.10820E-03 52128.82c + 609 521290 Te-129 1.97310E-05 9.93760E-03 521290 + 610 521291 Te-129m 4.76340E-05 4.58200E-03 52529.82c + 611 521300 Te-130 6.24410E-04 1.93850E-02 52130.82c + 612 521310 Te-131 8.68770E-04 2.76060E-02 521310 + 613 521311 Te-131m 2.09730E-03 4.34480E-03 521311 + 614 521320 Te-132 1.51840E-02 4.59650E-02 52132.82c + 615 521330 Te-133 1.13560E-02 4.07060E-02 521330 + 616 521331 Te-133m 2.74160E-02 3.23690E-02 521331 + 617 521340 Te-134 6.35590E-02 7.36380E-02 521340 + 618 521350 Te-135 3.17240E-02 3.42530E-02 521350 + 619 521360 Te-136 2.01390E-02 2.07290E-02 521360 + 620 521370 Te-137 5.49030E-03 5.53870E-03 521370 + 621 521380 Te-138 1.50570E-03 1.50850E-03 521380 + 622 521390 Te-139 1.86980E-04 1.87020E-04 521390 + 623 521400 Te-140 4.12520E-05 4.12520E-05 521400 + 624 521410 Te-141 1.92130E-06 1.92130E-06 521410 + 625 521420 Te-142 5.23840E-09 5.23840E-09 521420 + 626 531290 I-129 8.48810E-07 1.16340E-02 53129.82c + 627 531300 I-130 2.47660E-06 3.36480E-06 53130.82c + 628 531301 I-130m 1.05740E-06 1.05740E-06 531301 + 629 531310 I-131 2.48260E-05 3.10630E-02 53131.82c + 630 531320 I-132 1.39680E-04 4.61930E-02 531320 + 631 531321 I-132m 1.02940E-04 1.02940E-04 531321 + 632 531330 I-133 1.30730E-03 6.95160E-02 531330 + 633 531331 I-133m 7.98840E-04 7.98840E-04 531331 + 634 531340 I-134 4.62710E-03 8.15970E-02 531340 + 635 531341 I-134m 3.41020E-03 3.41020E-03 531341 + 636 531350 I-135 3.13700E-02 6.56230E-02 53135.82c + 637 531360 I-136 1.11830E-02 3.19950E-02 531360 + 638 531361 I-136m 2.61930E-02 2.62760E-02 531361 + 639 531370 I-137 3.39270E-02 3.93950E-02 531370 + 640 531380 I-138 1.43160E-02 1.57300E-02 531380 + 641 531390 I-139 9.95250E-03 1.01390E-02 531390 + 642 531400 I-140 2.86910E-03 2.91030E-03 531400 + 643 531410 I-141 6.66760E-04 6.68680E-04 531410 + 644 531420 I-142 9.37360E-05 9.37410E-05 531420 + 645 531430 I-143 1.06550E-05 1.06550E-05 531430 + 646 531440 I-144 8.97560E-07 8.97560E-07 531440 + 647 541310 Xe-131 4.41340E-10 3.10630E-02 54131.82c + 648 541311 Xe-131m 1.06550E-09 3.37400E-04 541311 + 649 541320 Xe-132 4.86750E-07 4.62080E-02 54132.82c + 650 541321 Xe-132m 5.51750E-07 5.51750E-07 541321 + 651 541330 Xe-133 5.61230E-06 6.95350E-02 54133.82c + 652 541331 Xe-133m 1.35490E-05 1.99220E-03 541331 + 653 541340 Xe-134 8.32130E-05 8.19530E-02 54134.82c + 654 541341 Xe-134m 1.94910E-04 2.73340E-04 541341 + 655 541350 Xe-135 5.47780E-04 6.74200E-02 54135.82c + 656 541351 Xe-135m 1.32240E-03 1.21560E-02 541351 + 657 541360 Xe-136 1.51630E-02 7.59950E-02 54136.82c + 658 541370 Xe-137 2.54750E-02 6.31430E-02 541370 + 659 541380 Xe-138 4.24560E-02 5.83460E-02 541380 + 660 541390 Xe-139 3.36440E-02 4.30610E-02 541390 + 661 541400 Xe-140 3.68750E-02 3.96550E-02 541400 + 662 541410 Xe-141 1.54800E-02 1.60320E-02 541410 + 663 541420 Xe-142 6.62090E-03 6.69550E-03 541420 + 664 541430 Xe-143 1.62630E-03 1.63310E-03 541430 + 665 541440 Xe-144 2.99850E-04 3.00390E-04 541440 + 666 541450 Xe-145 4.87240E-05 4.87240E-05 541450 + 667 541460 Xe-146 6.64020E-06 6.64020E-06 541460 + 668 541470 Xe-147 2.24740E-09 2.24740E-09 541470 + 669 551340 Cs-134 1.16030E-08 2.01550E-08 55134.82c + 670 551341 Cs-134m 8.55180E-09 8.55180E-09 551341 + 671 551350 Cs-135 4.01540E-06 6.75000E-02 55135.82c + 672 551351 Cs-135m 2.45370E-06 2.45370E-06 551351 + 673 551360 Cs-136 3.69600E-05 4.77900E-05 55136.82c + 674 551361 Cs-136m 2.16600E-05 2.16600E-05 551361 + 675 551370 Cs-137 9.00740E-04 6.40440E-02 55137.82c + 676 551380 Cs-138 1.36520E-03 6.12800E-02 551380 + 677 551381 Cs-138m 1.93710E-03 1.93710E-03 551381 + 678 551390 Cs-139 9.79560E-03 5.28560E-02 551390 + 679 551400 Cs-140 1.47800E-02 5.44420E-02 551400 + 680 551410 Cs-141 2.53040E-02 4.13530E-02 551410 + 681 551420 Cs-142 2.06880E-02 2.73760E-02 551420 + 682 551430 Cs-143 1.64490E-02 1.80750E-02 551430 + 683 551440 Cs-144 3.27380E-03 5.20390E-03 551440 + 684 551441 Cs-144m 3.27380E-03 3.27500E-03 551441 + 685 551450 Cs-145 2.39260E-03 2.43930E-03 551450 + 686 551460 Cs-146 4.74750E-04 4.80930E-04 551460 + 687 551470 Cs-147 9.01140E-05 9.01160E-05 551470 + 688 551480 Cs-148 1.13160E-05 1.13160E-05 551480 + 689 551490 Cs-149 2.89110E-06 2.89110E-06 551490 + 690 551500 Cs-150 2.44110E-10 2.44110E-10 551500 + 691 561360 Ba-136 8.57420E-10 5.86230E-05 56136.82c + 692 561361 Ba-136m 2.00830E-09 2.00830E-09 561361 + 693 561370 Ba-137 1.59140E-06 6.40490E-02 56137.82c + 694 561371 Ba-137m 3.84190E-06 6.04610E-02 561371 + 695 561380 Ba-138 1.15970E-04 6.17640E-02 56138.82c + 696 561390 Ba-139 6.06870E-04 5.34630E-02 561390 + 697 561400 Ba-140 3.21360E-03 5.76560E-02 56140.82c + 698 561410 Ba-141 5.71340E-03 4.70660E-02 561410 + 699 561420 Ba-142 1.68560E-02 4.45280E-02 561420 + 700 561430 Ba-143 2.31750E-02 4.11200E-02 561430 + 701 561440 Ba-144 2.89490E-02 3.59730E-02 561440 + 702 561450 Ba-145 1.91060E-02 2.12650E-02 561450 + 703 561460 Ba-146 1.16880E-02 1.21260E-02 561460 + 704 561470 Ba-147 4.30660E-03 4.37390E-03 561470 + 705 561480 Ba-148 1.18550E-03 1.19400E-03 561480 + 706 561490 Ba-149 2.20130E-04 2.23020E-04 561490 + 707 561500 Ba-150 2.95630E-05 2.95630E-05 561500 + 708 561510 Ba-151 3.03510E-06 3.03510E-06 561510 + 709 561520 Ba-152 1.68490E-09 1.68490E-09 561520 + 710 571390 La-139 1.52500E-08 5.34630E-02 57139.82c + 711 571400 La-140 1.08590E-05 5.76670E-02 57140.82c + 712 571410 La-141 8.74070E-05 4.71540E-02 571410 + 713 571420 La-142 2.70020E-04 4.47980E-02 571420 + 714 571430 La-143 1.62030E-03 4.27400E-02 571430 + 715 571440 La-144 3.71160E-03 3.96840E-02 571440 + 716 571450 La-145 9.40830E-03 3.06730E-02 571450 + 717 571460 La-146 3.56490E-03 1.56910E-02 571460 + 718 571461 La-146m 6.41250E-03 6.41250E-03 571461 + 719 571470 La-147 1.21160E-02 1.64950E-02 571470 + 720 571480 La-148 6.70500E-03 7.89520E-03 571480 + 721 571490 La-149 3.76070E-03 3.98280E-03 571490 + 722 571500 La-150 9.69130E-04 9.98690E-04 571500 + 723 571510 La-151 2.64260E-04 2.67300E-04 571510 + 724 571520 La-152 3.03370E-05 3.03390E-05 571520 + 725 571530 La-153 4.61420E-06 4.61420E-06 571530 + 726 571540 La-154 4.86160E-09 4.86160E-09 571540 + 727 571550 La-155 1.09530E-10 1.09530E-10 571550 + 728 581410 Ce-141 1.18370E-09 4.71540E-02 58141.82c + 729 581420 Ce-142 9.28220E-06 4.48070E-02 58142.82c + 730 581430 Ce-143 2.71180E-05 4.27670E-02 58143.82c + 731 581440 Ce-144 2.58140E-04 3.99420E-02 58144.82c + 732 581450 Ce-145 9.70670E-04 3.16440E-02 581450 + 733 581460 Ce-146 3.42840E-03 2.55320E-02 581460 + 734 581470 Ce-147 5.82150E-03 2.23160E-02 581470 + 735 581480 Ce-148 1.00250E-02 1.79760E-02 581480 + 736 581490 Ce-149 9.99090E-03 1.39450E-02 581490 + 737 581500 Ce-150 8.21480E-03 9.18650E-03 581500 + 738 581510 Ce-151 4.43970E-03 4.70880E-03 581510 + 739 581520 Ce-152 2.01890E-03 2.04740E-03 581520 + 740 581530 Ce-153 3.80580E-04 3.85190E-04 581530 + 741 581540 Ce-154 9.61350E-05 9.61400E-05 581540 + 742 581550 Ce-155 1.60700E-05 1.60700E-05 581550 + 743 581560 Ce-156 3.87360E-06 3.87360E-06 581560 + 744 581570 Ce-157 4.72990E-10 4.72990E-10 581570 + 745 591440 Pr-144 4.55650E-10 3.99420E-02 591440 + 746 591441 Pr-144m 4.04680E-09 5.51190E-04 591441 + 747 591450 Pr-145 9.55290E-07 3.16450E-02 591450 + 748 591460 Pr-146 1.70640E-05 2.55490E-02 591460 + 749 591470 Pr-147 1.45270E-04 2.24610E-02 591470 + 750 591480 Pr-148 7.96100E-05 1.80550E-02 591480 + 751 591481 Pr-148m 3.34810E-04 3.34810E-04 591481 + 752 591490 Pr-149 1.29570E-03 1.52410E-02 591490 + 753 591500 Pr-150 1.96850E-03 1.11550E-02 591500 + 754 591510 Pr-151 3.58580E-03 8.29460E-03 591510 + 755 591520 Pr-152 3.73580E-03 5.78560E-03 591520 + 756 591530 Pr-153 2.56910E-03 2.95250E-03 591530 + 757 591540 Pr-154 1.02690E-03 1.12240E-03 591540 + 758 591550 Pr-155 3.80920E-04 3.96990E-04 591550 + 759 591560 Pr-156 9.41580E-05 9.80320E-05 591560 + 760 591570 Pr-157 3.92350E-05 3.92360E-05 591570 + 761 591580 Pr-158 8.69260E-08 8.69260E-08 591580 + 762 591590 Pr-159 3.17760E-09 3.17760E-09 591590 + 763 601460 Nd-146 9.99530E-10 2.55490E-02 60146.82c + 764 601470 Nd-147 1.85410E-08 2.24610E-02 60147.82c + 765 601480 Nd-148 1.73370E-05 1.84080E-02 60148.82c + 766 601490 Nd-149 7.38200E-05 1.53140E-02 601490 + 767 601500 Nd-150 2.86050E-04 1.14410E-02 60150.82c + 768 601510 Nd-151 7.05770E-04 9.00040E-03 601510 + 769 601520 Nd-152 1.44500E-03 7.23060E-03 601520 + 770 601530 Nd-153 1.69180E-03 4.64430E-03 601530 + 771 601540 Nd-154 2.40080E-03 3.52320E-03 601540 + 772 601550 Nd-155 1.75740E-03 2.15710E-03 601550 + 773 601560 Nd-156 1.16190E-03 1.25980E-03 601560 + 774 601570 Nd-157 5.12920E-04 5.49650E-04 601570 + 775 601580 Nd-158 1.33780E-04 1.33870E-04 601580 + 776 601590 Nd-159 2.78910E-05 2.78940E-05 601590 + 777 601600 Nd-160 1.11930E-05 1.11930E-05 601600 + 778 601610 Nd-161 9.08710E-09 9.08710E-09 601610 + 779 611490 Pm-149 9.63430E-07 1.53150E-02 61149.82c + 780 611500 Pm-150 1.73710E-06 1.73710E-06 611500 + 781 611510 Pm-151 8.07720E-06 9.00850E-03 61151.82c + 782 611520 Pm-152 8.07930E-06 7.23870E-03 611520 + 783 611521 Pm-152m 1.61330E-05 1.61330E-05 611521 + 784 611522 Pm-152m 1.78450E-05 1.78450E-05 611522 + 785 611530 Pm-153 1.35830E-04 4.78010E-03 611530 + 786 611540 Pm-154 1.57350E-04 3.68060E-03 611540 + 787 611541 Pm-154m 1.57350E-04 1.57350E-04 611541 + 788 611550 Pm-155 6.57710E-04 2.81480E-03 611550 + 789 611560 Pm-156 8.88090E-04 2.14790E-03 611560 + 790 611570 Pm-157 9.21090E-04 1.47080E-03 611570 + 791 611580 Pm-158 6.62380E-04 7.96310E-04 611580 + 792 611590 Pm-159 2.83350E-04 3.11280E-04 611590 + 793 611600 Pm-160 1.40060E-04 1.51150E-04 611600 + 794 611610 Pm-161 4.51510E-05 4.51600E-05 611610 + 795 611620 Pm-162 5.64580E-07 5.64580E-07 611620 + 796 611630 Pm-163 1.88380E-08 1.88380E-08 611630 + 797 621520 Sm-152 2.41890E-06 7.27510E-03 62152.82c + 798 621530 Sm-153 1.01240E-06 4.78360E-03 62153.82c + 799 621531 Sm-153m 2.44400E-06 2.44400E-06 621531 + 800 621540 Sm-154 3.41560E-05 3.87210E-03 62154.82c + 801 621550 Sm-155 1.29540E-04 2.94430E-03 621550 + 802 621560 Sm-156 3.26920E-04 2.47480E-03 621560 + 803 621570 Sm-157 5.96420E-04 2.06720E-03 621570 + 804 621580 Sm-158 8.37020E-04 1.63340E-03 621580 + 805 621590 Sm-159 7.79750E-04 1.09140E-03 621590 + 806 621600 Sm-160 5.87800E-04 7.38540E-04 621600 + 807 621610 Sm-161 3.42090E-04 3.87250E-04 621610 + 808 621620 Sm-162 1.30500E-04 1.31070E-04 621620 + 809 621630 Sm-163 1.94840E-05 1.95030E-05 621630 + 810 621640 Sm-164 6.40960E-07 6.40960E-07 621640 + 811 621650 Sm-165 3.13840E-08 3.13840E-08 621650 + 812 631540 Eu-154 1.47550E-10 2.80470E-10 63154.82c + 813 631541 Eu-154m 1.32920E-10 1.32920E-10 631541 + 814 631550 Eu-155 1.41290E-08 2.94430E-03 63155.82c + 815 631560 Eu-156 1.93320E-06 2.47670E-03 63156.82c + 816 631570 Eu-157 1.38190E-05 2.08100E-03 63157.82c + 817 631580 Eu-158 3.60660E-05 1.66950E-03 631580 + 818 631590 Eu-159 1.31250E-04 1.22260E-03 631590 + 819 631600 Eu-160 1.89970E-04 9.28510E-04 631600 + 820 631610 Eu-161 2.70460E-04 6.57710E-04 631610 + 821 631620 Eu-162 2.22410E-04 3.53480E-04 631620 + 822 631630 Eu-163 6.49460E-05 8.44490E-05 631630 + 823 631640 Eu-164 6.76960E-06 7.41060E-06 631640 + 824 631650 Eu-165 1.50330E-05 1.50640E-05 631650 + 825 631660 Eu-166 3.79300E-07 3.79300E-07 631660 + 826 631670 Eu-167 3.99000E-08 3.99000E-08 631670 + 827 641570 Gd-157 8.40870E-10 2.08100E-03 64157.82c + 828 641580 Gd-158 4.20140E-08 1.66950E-03 64158.82c + 829 641590 Gd-159 7.96390E-06 1.23060E-03 641590 + 830 641600 Gd-160 3.91430E-05 9.67660E-04 64160.82c + 831 641610 Gd-161 4.51040E-05 7.02810E-04 641610 + 832 641620 Gd-162 1.37900E-04 4.91370E-04 641620 + 833 641630 Gd-163 8.43620E-05 1.68810E-04 641630 + 834 641640 Gd-164 6.76940E-05 7.51050E-05 641640 + 835 641650 Gd-165 3.75810E-05 5.26450E-05 641650 + 836 641660 Gd-166 7.27830E-06 7.65760E-06 641660 + 837 641670 Gd-167 2.67610E-06 2.71600E-06 641670 + 838 641680 Gd-168 6.25090E-07 6.25090E-07 641680 + 839 641690 Gd-169 3.28490E-08 3.28490E-08 641690 + 840 651590 Tb-159 8.70580E-11 1.23060E-03 65159.82c + 841 651600 Tb-160 2.03810E-09 2.03810E-09 65160.82c + 842 651610 Tb-161 6.99450E-08 7.02880E-04 651610 + 843 651620 Tb-162 5.30330E-07 4.91900E-04 651620 + 844 651630 Tb-163 6.49200E-06 1.75300E-04 651630 + 845 651640 Tb-164 1.35370E-05 8.86420E-05 651640 + 846 651650 Tb-165 7.51510E-06 6.01610E-05 651650 + 847 651660 Tb-166 2.18340E-05 2.94920E-05 651660 + 848 651670 Tb-167 1.42670E-05 1.69830E-05 651670 + 849 651680 Tb-168 4.53930E-06 5.16440E-06 651680 + 850 651690 Tb-169 2.10300E-06 2.13590E-06 651690 + 851 651700 Tb-170 2.06710E-07 2.06710E-07 651700 + 852 651710 Tb-171 3.80710E-08 3.80710E-08 651710 + 853 661620 Dy-162 2.11810E-10 4.91900E-04 66162.82c + 854 661630 Dy-163 2.08210E-09 1.75310E-04 66163.82c + 855 661640 Dy-164 3.78540E-08 8.86790E-05 66164.82c + 856 661650 Dy-165 1.95510E-05 8.26340E-05 661650 + 857 661651 Dy-165m 2.98880E-06 2.98880E-06 661651 + 858 661660 Dy-166 1.23050E-06 3.07220E-05 661660 + 859 661670 Dy-167 2.11010E-06 1.90930E-05 661670 + 860 661680 Dy-168 5.16730E-06 1.03320E-05 661680 + 861 661690 Dy-169 3.02320E-06 5.15910E-06 661690 + 862 661700 Dy-170 2.32010E-06 2.52680E-06 661700 + 863 661710 Dy-171 6.04110E-07 6.42180E-07 661710 + 864 661720 Dy-172 2.37670E-07 2.37670E-07 661720 + 865 661730 Dy-173 1.92470E-08 1.92470E-08 661730 + 866 671640 Ho-164 5.96100E-13 1.99230E-12 671640 + 867 671641 Ho-164m 1.39620E-12 1.39620E-12 671641 + 868 671650 Ho-165 1.95920E-10 8.27010E-05 67165.82c + 869 671660 Ho-166 4.19270E-10 3.07230E-05 671660 + 870 671661 Ho-166m 9.82030E-10 9.82030E-10 671661 + 871 671670 Ho-167 2.38330E-08 1.91170E-05 671670 + 872 671680 Ho-168 3.78050E-08 1.04230E-05 671680 + 873 671681 Ho-168m 5.36430E-08 5.36430E-08 671681 + 874 671690 Ho-169 4.61900E-07 5.62090E-06 671690 + 875 671700 Ho-170 3.31950E-07 3.31950E-07 671700 + 876 671701 Ho-170m 1.41720E-07 2.66850E-06 671701 + 877 671710 Ho-171 9.32690E-07 1.57490E-06 671710 + 878 671720 Ho-172 4.68060E-07 7.05730E-07 671720 + 879 671730 Ho-173 3.05510E-07 3.24760E-07 671730 + 880 671740 Ho-174 5.56340E-08 5.56340E-08 671740 + 881 671750 Ho-175 1.85680E-08 1.85680E-08 671750 + 882 681670 Er-167 3.09380E-12 1.91170E-05 68167.82c + 883 681671 Er-167m 4.72940E-13 2.28430E-06 681671 + 884 681680 Er-168 1.42900E-10 1.04230E-05 68168.82c + 885 681690 Er-169 1.23280E-09 5.62220E-06 681690 + 886 681700 Er-170 1.22290E-08 3.01270E-06 68170.82c + 887 681710 Er-171 3.64720E-08 1.61130E-06 681710 + 888 681720 Er-172 1.52100E-07 8.57830E-07 681720 + 889 681730 Er-173 1.28840E-07 4.53600E-07 681730 + 890 681740 Er-174 1.76470E-07 2.32100E-07 681740 + 891 681750 Er-175 7.67570E-08 9.53250E-08 681750 + 892 681760 Er-176 4.20580E-08 4.20580E-08 681760 + 893 681770 Er-177 6.28850E-09 6.28850E-09 681770 + 894 691700 Tm-170 2.90040E-12 2.90040E-12 691700 + 895 691710 Tm-171 8.92680E-11 1.61140E-06 691710 + 896 691720 Tm-172 6.22390E-10 8.58450E-07 691720 + 897 691730 Tm-173 4.95330E-09 4.58550E-07 691730 + 898 691740 Tm-174 9.90290E-09 2.42010E-07 691740 + 899 691750 Tm-175 3.45230E-08 1.29850E-07 691750 + 900 691760 Tm-176 2.40680E-08 6.61260E-08 691760 + 901 691770 Tm-177 2.72690E-08 3.35580E-08 691770 + 902 691780 Tm-178 9.30930E-09 9.30930E-09 691780 + 903 691790 Tm-179 4.48560E-09 4.48560E-09 691790 + 904 701730 Yb-173 2.78980E-12 4.58550E-07 701730 + 905 701740 Yb-174 5.69100E-11 2.42060E-07 701740 + 906 701750 Yb-175 2.80840E-10 1.30170E-07 701750 + 907 701751 Yb-175m 4.29320E-11 1.00030E-07 701751 + 908 701760 Yb-176 7.32890E-10 6.47390E-08 701760 + 909 701761 Yb-176m 1.31830E-09 3.43810E-08 701761 + 910 701770 Yb-177 2.65220E-09 3.68230E-08 701770 + 911 701771 Yb-177m 6.13240E-10 3.41710E-08 701771 + 912 701780 Yb-178 8.66450E-09 1.79740E-08 701780 + 913 701790 Yb-179 5.27020E-09 9.75580E-09 701790 + 914 701800 Yb-180 4.36290E-09 4.36290E-09 701800 + 915 701810 Yb-181 1.24970E-09 1.24970E-09 701810 + 916 711760 Lu-176 1.16340E-12 3.43930E-09 71176.82c + 917 711770 Lu-177 2.05400E-11 3.68450E-08 711770 + 918 711771 Lu-177m 8.02970E-12 8.15950E-12 711771 + 919 711780 Lu-178 5.68810E-11 1.80310E-08 711780 + 920 711781 Lu-178m 6.44790E-11 6.44790E-11 711781 + 921 711790 Lu-179 5.61040E-10 1.04030E-08 711790 + 922 711791 Lu-179m 8.57670E-11 9.84160E-09 711791 + 923 711800 Lu-180 2.08780E-10 2.64850E-09 711800 + 924 711801 Lu-180m 2.08780E-10 4.57170E-09 711801 + 925 711802 Lu-180m 3.07690E-10 3.07690E-10 711802 + 926 711810 Lu-181 1.57950E-09 2.82920E-09 711810 + 927 711820 Lu-182 8.37980E-10 8.37980E-10 711820 + 928 711830 Lu-183 5.89280E-10 5.89280E-10 711830 + 929 711840 Lu-184 1.19550E-10 1.19550E-10 711840 + 930 721790 Hf-179 8.07950E-13 1.04040E-08 72179.82c + 931 721800 Hf-180 5.25660E-12 5.10230E-09 72180.82c + 932 721801 Hf-180m 9.45540E-12 1.63300E-10 721801 + 933 721810 Hf-181 4.92090E-11 2.87840E-09 721810 + 934 721820 Hf-182 7.86770E-11 9.76100E-10 721820 + 935 721821 Hf-182m 1.41520E-10 1.41520E-10 721821 + 936 721830 Hf-183 2.03080E-10 7.92360E-10 721830 + 937 721840 Hf-184 1.10780E-10 1.70560E-10 721840 + 938 721841 Hf-184m 1.99280E-10 2.59050E-10 721841 + 939 721850 Hf-185 1.43670E-10 1.43670E-10 721850 + 940 721860 Hf-186 8.31250E-11 8.31250E-11 721860 + 941 721870 Hf-187 1.38800E-11 1.38800E-11 721870 + 942 721880 Hf-188 3.90050E-12 3.90050E-12 721880 + 943 731830 Ta-183 6.17100E-12 7.98530E-10 731830 + 944 731840 Ta-184 1.39580E-11 4.43570E-10 731840 + 945 731850 Ta-185 3.54050E-11 1.96220E-10 731850 + 946 731851 Ta-185m 1.71480E-11 1.71480E-11 731851 + 947 731860 Ta-186 3.89380E-11 1.22060E-10 731860 + 948 731870 Ta-187 4.90520E-11 6.29320E-11 731870 + 949 731880 Ta-188 1.82850E-11 2.21850E-11 731880 + 950 731890 Ta-189 9.28000E-12 9.28000E-12 731890 + 951 731900 Ta-190 1.09600E-12 1.09600E-12 731900 + 952 741860 W-186 1.99640E-12 1.24700E-10 74186.82c + 953 741870 W-187 4.74370E-12 6.76760E-11 741870 + 954 741880 W-188 1.38980E-11 3.60830E-11 741880 + 955 741890 W-189 8.91820E-12 1.81980E-11 741890 + 956 741900 W-190 3.78050E-12 9.16200E-12 741900 + 957 741901 W-190m 4.28550E-12 4.28550E-12 741901 + 958 751900 Re-190 3.89170E-13 9.87040E-12 751900 + + Neutron-induced fission: + + Interpolation region : 2 / 2 + Interpolation energy : 4.00000E-01 MeV + Number of products : 927 / 1035 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 2.94220E-05 2.94220E-05 1001.82c + 2 10020 H-2 8.99170E-06 8.99170E-06 1002.82c + 3 10030 H-3 1.41000E-04 1.41000E-04 1003.82c + 4 20040 He-4 1.86000E-03 1.86000E-03 2004.82c + 5 220550 Ti-55 1.24200E-12 1.24200E-12 220550 + 6 220560 Ti-56 2.92520E-12 2.92520E-12 220560 + 7 220570 Ti-57 1.90080E-12 1.90080E-12 220570 + 8 220580 Ti-58 2.05100E-12 2.05100E-12 220580 + 9 230560 V-56 1.61160E-12 4.54250E-12 230560 + 10 230570 V-57 7.91890E-12 9.81400E-12 230570 + 11 230580 V-58 1.16430E-11 1.36940E-11 230580 + 12 230590 V-59 2.37440E-11 2.37440E-11 230590 + 13 230600 V-60 1.08190E-11 1.08190E-11 230600 + 14 230610 V-61 9.21840E-12 9.21840E-12 230610 + 15 230620 V-62 1.78310E-12 1.78310E-12 230620 + 16 240580 Cr-58 1.06420E-11 1.33810E-11 240580 + 17 240590 Cr-59 2.78470E-11 5.15910E-11 240590 + 18 240600 Cr-60 9.79280E-11 1.09300E-10 240600 + 19 240610 Cr-61 1.18170E-10 1.26840E-10 240610 + 20 240620 Cr-62 2.05930E-10 2.07710E-10 240620 + 21 240630 Cr-63 7.57720E-11 7.57720E-11 240630 + 22 240640 Cr-64 4.29090E-11 4.29090E-11 240640 + 23 240650 Cr-65 6.73170E-12 6.73170E-12 240650 + 24 240660 Cr-66 1.14860E-12 1.14860E-12 240660 + 25 250590 Mn-59 3.46120E-12 5.50520E-11 250590 + 26 250600 Mn-60 1.49740E-12 1.12550E-10 250600 + 27 250601 Mn-60m 1.52340E-11 1.52340E-11 250601 + 28 250610 Mn-61 1.53250E-10 2.80090E-10 250610 + 29 250620 Mn-62 2.97970E-10 4.01820E-10 250620 + 30 250621 Mn-62m 4.66630E-11 1.50520E-10 250621 + 31 250630 Mn-63 1.01000E-09 1.08580E-09 250630 + 32 250640 Mn-64 8.43860E-10 8.86770E-10 250640 + 33 250650 Mn-65 1.23690E-09 1.24360E-09 250650 + 34 250660 Mn-66 3.57450E-10 3.58600E-10 250660 + 35 250670 Mn-67 1.55950E-10 1.55950E-10 250670 + 36 250680 Mn-68 1.79520E-11 1.79520E-11 250680 + 37 250690 Mn-69 2.48620E-12 2.48620E-12 250690 + 38 260610 Fe-61 5.04800E-12 2.85130E-10 260610 + 39 260620 Fe-62 9.52680E-11 6.47610E-10 260620 + 40 260630 Fe-63 3.70990E-10 1.45680E-09 260630 + 41 260640 Fe-64 2.32930E-09 3.21610E-09 260640 + 42 260650 Fe-65 4.49390E-09 5.73750E-09 260650 + 43 260660 Fe-66 1.07480E-08 1.11070E-08 260660 + 44 260670 Fe-67 7.20070E-09 7.35670E-09 260670 + 45 260680 Fe-68 7.99330E-09 8.01180E-09 260680 + 46 260690 Fe-69 1.91810E-09 1.92000E-09 260690 + 47 260700 Fe-70 5.63160E-10 5.63160E-10 260700 + 48 260710 Fe-71 5.09360E-11 5.09360E-11 260710 + 49 260720 Fe-72 2.41370E-12 2.41370E-12 260720 + 50 270630 Co-63 1.23560E-11 1.46910E-09 270630 + 51 270640 Co-64 1.16060E-10 3.33210E-09 270640 + 52 270650 Co-65 1.80580E-09 7.54330E-09 270650 + 53 270660 Co-66 5.60330E-09 1.67100E-08 270660 + 54 270670 Co-67 2.83490E-08 3.57060E-08 270670 + 55 270680 Co-68 2.44640E-08 3.76680E-08 270680 + 56 270681 Co-68m 1.82610E-08 2.64070E-08 270681 + 57 270690 Co-69 8.84000E-08 9.01860E-08 270690 + 58 270700 Co-70 2.06690E-08 2.06690E-08 270700 + 59 270701 Co-70m 2.06690E-08 2.12320E-08 270701 + 60 270710 Co-71 3.70400E-08 3.70910E-08 270710 + 61 270720 Co-72 3.10930E-09 3.11170E-09 270720 + 62 270730 Co-73 1.42610E-09 1.42610E-09 270730 + 63 270740 Co-74 9.95170E-11 9.95170E-11 270740 + 64 270750 Co-75 9.24940E-12 9.24940E-12 270750 + 65 280650 Ni-65 1.52850E-11 7.55860E-09 280650 + 66 280660 Ni-66 4.32820E-10 1.71430E-08 280660 + 67 280670 Ni-67 3.14450E-09 3.88500E-08 280670 + 68 280680 Ni-68 3.69330E-08 8.87060E-08 280680 + 69 280690 Ni-69 4.90380E-08 1.38320E-07 280690 + 70 280691 Ni-69m 4.90380E-08 4.90380E-08 280691 + 71 280700 Ni-70 3.53060E-07 3.94960E-07 280700 + 72 280710 Ni-71 4.46180E-07 4.83270E-07 280710 + 73 280720 Ni-72 3.36140E-07 3.39250E-07 280720 + 74 280730 Ni-73 2.53500E-07 2.54930E-07 280730 + 75 280740 Ni-74 1.79340E-07 1.79440E-07 280740 + 76 280750 Ni-75 2.81170E-08 2.81260E-08 280750 + 77 280760 Ni-76 4.11320E-09 4.11320E-09 280760 + 78 280770 Ni-77 1.01170E-10 1.01170E-10 280770 + 79 280780 Ni-78 4.38140E-12 4.38140E-12 280780 + 80 290670 Cu-67 2.59210E-11 3.88760E-08 290670 + 81 290680 Cu-68 1.32070E-10 8.91410E-08 290680 + 82 290681 Cu-68m 3.59990E-10 3.59990E-10 290681 + 83 290690 Cu-69 1.14710E-08 1.98830E-07 290690 + 84 290700 Cu-70 3.85740E-09 3.84600E-08 290700 + 85 290701 Cu-70m 4.92630E-08 6.92040E-08 290701 + 86 290702 Cu-70m 3.85740E-09 3.98820E-07 290702 + 87 290710 Cu-71 1.04220E-06 1.52550E-06 290710 + 88 290720 Cu-72 1.06410E-06 1.40340E-06 290720 + 89 290730 Cu-73 2.88380E-06 3.13870E-06 290730 + 90 290740 Cu-74 7.24530E-06 7.42520E-06 290740 + 91 290750 Cu-75 2.90890E-06 2.93660E-06 290750 + 92 290760 Cu-76 1.38920E-06 1.39120E-06 290760 + 93 290761 Cu-76m 1.38920E-06 1.39120E-06 290761 + 94 290770 Cu-77 1.46230E-06 1.46240E-06 290770 + 95 290780 Cu-78 2.54890E-08 2.54930E-08 290780 + 96 290790 Cu-79 3.34580E-09 3.34580E-09 290790 + 97 290800 Cu-80 8.51940E-11 8.51940E-11 290800 + 98 300690 Zn-69 3.90120E-12 1.98850E-07 300690 + 99 300691 Zn-69m 1.93760E-11 1.93760E-11 300691 + 100 300700 Zn-70 1.12880E-09 4.53070E-07 300700 + 101 300710 Zn-71 2.83850E-09 1.52830E-06 300710 + 102 300711 Zn-71m 1.40970E-08 1.40970E-08 300711 + 103 300720 Zn-72 1.38570E-07 1.54190E-06 300720 + 104 300730 Zn-73 1.26460E-07 4.01040E-06 300730 + 105 300731 Zn-73m 1.74900E-07 7.45250E-07 300731 + 106 300732 Zn-73m 1.14070E-06 1.14070E-06 300732 + 107 300740 Zn-74 4.34740E-06 1.18750E-05 300740 + 108 300750 Zn-75 2.47270E-05 2.76020E-05 300750 + 109 300760 Zn-76 3.61170E-05 3.88580E-05 300760 + 110 300770 Zn-77 1.67750E-05 1.93550E-05 300770 + 111 300771 Zn-77m 2.23360E-06 2.23360E-06 300771 + 112 300780 Zn-78 1.93600E-05 1.93870E-05 300780 + 113 300790 Zn-79 6.45640E-06 6.45790E-06 300790 + 114 300800 Zn-80 7.08370E-06 7.08380E-06 300800 + 115 300810 Zn-81 1.26900E-06 1.26900E-06 300810 + 116 300820 Zn-82 2.62490E-09 2.62490E-09 300820 + 117 300830 Zn-83 4.91920E-11 4.91920E-11 300830 + 118 310710 Ga-71 3.25850E-11 1.54240E-06 310710 + 119 310720 Ga-72 4.15330E-10 1.54240E-06 310720 + 120 310721 Ga-72m 4.08260E-11 5.14180E-08 310721 + 121 310730 Ga-73 3.44990E-08 4.61530E-06 310730 + 122 310740 Ga-74 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320771 Ge-77m 1.54650E-06 5.12660E-05 320771 + 143 320780 Ge-78 5.25700E-05 1.08070E-04 320780 + 144 320790 Ge-79 1.74560E-05 9.73180E-05 320790 + 145 320791 Ge-79m 1.31100E-04 1.31220E-04 320791 + 146 320800 Ge-80 3.47080E-04 3.89470E-04 320800 + 147 320810 Ge-81 3.50410E-04 3.69580E-04 320810 + 148 320811 Ge-81m 7.05530E-05 8.69730E-05 320811 + 149 320820 Ge-82 4.30380E-04 4.36260E-04 320820 + 150 320830 Ge-83 2.77160E-04 2.79130E-04 320830 + 151 320840 Ge-84 7.39830E-05 7.39930E-05 320840 + 152 320850 Ge-85 1.70850E-05 1.70860E-05 320850 + 153 320860 Ge-86 9.96060E-06 9.96060E-06 320860 + 154 320870 Ge-87 1.45070E-08 1.45070E-08 320870 + 155 320880 Ge-88 3.51470E-10 3.51470E-10 320880 + 156 330750 As-75 4.50850E-12 2.91070E-05 33075.82c + 157 330751 As-75m 1.70730E-11 3.78930E-10 330751 + 158 330760 As-76 9.25640E-10 9.25640E-10 330760 + 159 330770 As-77 3.91830E-08 6.29210E-05 330770 + 160 330780 As-78 4.14950E-06 1.12210E-04 330780 + 161 330790 As-79 6.45740E-06 2.29740E-04 330790 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390950 Y-95 6.34850E-03 3.76890E-02 390950 + 281 390960 Y-96 4.06790E-03 3.20140E-02 390960 + 282 390961 Y-96m 8.53410E-03 8.53770E-03 390961 + 283 390970 Y-97 3.92620E-03 1.65510E-02 390970 + 284 390971 Y-97m 1.45120E-02 2.06840E-02 390971 + 285 390972 Y-97m 4.98740E-03 4.98740E-03 390972 + 286 390980 Y-98 3.58250E-03 1.06090E-02 390980 + 287 390981 Y-98m 1.73680E-02 1.73680E-02 390981 + 288 390990 Y-99 2.01180E-02 2.20900E-02 390990 + 289 391000 Y-100 4.75680E-03 5.24140E-03 391000 + 290 391001 Y-100m 4.75680E-03 4.75770E-03 391001 + 291 391010 Y-101 4.49520E-03 4.56670E-03 391010 + 292 391020 Y-102 5.17900E-04 5.22750E-04 391020 + 293 391021 Y-102m 5.17900E-04 5.22750E-04 391021 + 294 391030 Y-103 2.84110E-04 2.84110E-04 391030 + 295 391040 Y-104 2.52390E-05 2.52390E-05 391040 + 296 391050 Y-105 4.00380E-06 4.00380E-06 391050 + 297 400920 Zr-92 1.82830E-09 2.34660E-02 40092.82c + 298 400930 Zr-93 2.01740E-06 3.00920E-02 40093.82c + 299 400940 Zr-94 6.64010E-05 3.30750E-02 40094.82c + 300 400950 Zr-95 4.68760E-04 3.81580E-02 40095.82c + 301 400960 Zr-96 2.65480E-03 4.32230E-02 40096.82c + 302 400970 Zr-97 7.26580E-03 4.59630E-02 400970 + 303 400980 Zr-98 2.01940E-02 4.79200E-02 400980 + 304 400990 Zr-99 2.99250E-02 5.16880E-02 400990 + 305 401000 Zr-100 4.24750E-02 5.24260E-02 401000 + 306 401010 Zr-101 3.33280E-02 3.79460E-02 401010 + 307 401020 Zr-102 2.57600E-02 2.67770E-02 401020 + 308 401030 Zr-103 9.77590E-03 1.00390E-02 401030 + 309 401040 Zr-104 3.71820E-03 3.74200E-03 401040 + 310 401050 Zr-105 6.52050E-04 6.55260E-04 401050 + 311 401060 Zr-106 1.52430E-04 1.52430E-04 401060 + 312 401070 Zr-107 7.06940E-06 7.06940E-06 401070 + 313 401080 Zr-108 3.02690E-09 3.02690E-09 401080 + 314 410950 Nb-95 1.54490E-08 3.81350E-02 41095.82c + 315 410951 Nb-95m 3.11070E-09 4.12240E-04 410951 + 316 410960 Nb-96 9.56910E-06 9.56910E-06 410960 + 317 410970 Nb-97 9.00570E-05 4.60710E-02 410970 + 318 410971 Nb-97m 1.81330E-05 4.37050E-02 410971 + 319 410980 Nb-98 1.25470E-04 4.80450E-02 410980 + 320 410981 Nb-98m 4.37170E-04 4.37170E-04 410981 + 321 410990 Nb-99 2.72140E-03 3.57790E-02 410990 + 322 410991 Nb-99m 5.47940E-04 1.95690E-02 410991 + 323 411000 Nb-100 1.34990E-03 5.37760E-02 411000 + 324 411001 Nb-100m 6.54450E-03 6.54450E-03 411001 + 325 411010 Nb-101 2.14200E-02 5.93660E-02 411010 + 326 411020 Nb-102 1.36890E-02 4.04660E-02 411020 + 327 411021 Nb-102m 1.36890E-02 1.36890E-02 411021 + 328 411030 Nb-103 3.52130E-02 4.52530E-02 411030 + 329 411040 Nb-104 1.17590E-02 1.55100E-02 411040 + 330 411041 Nb-104m 1.17590E-02 1.17590E-02 411041 + 331 411050 Nb-105 1.53850E-02 1.60330E-02 411050 + 332 411060 Nb-106 5.61220E-03 5.76260E-03 411060 + 333 411070 Nb-107 1.91440E-03 1.92120E-03 411070 + 334 411080 Nb-108 3.24090E-04 3.24090E-04 411080 + 335 411090 Nb-109 4.41780E-05 4.41780E-05 411090 + 336 411100 Nb-110 3.21150E-06 3.21150E-06 411100 + 337 420970 Mo-97 2.27290E-09 4.60710E-02 42097.82c + 338 420980 Mo-98 1.55130E-05 4.84980E-02 42098.82c + 339 420990 Mo-99 1.11150E-04 5.50680E-02 42099.82c + 340 421000 Mo-100 7.98590E-04 6.11190E-02 42100.82c + 341 421010 Mo-101 3.19320E-03 6.25590E-02 421010 + 342 421020 Mo-102 1.16960E-02 6.58510E-02 421020 + 343 421030 Mo-103 2.11110E-02 6.63790E-02 421030 + 344 421040 Mo-104 3.96390E-02 6.71660E-02 421040 + 345 421050 Mo-105 3.63460E-02 5.23660E-02 421050 + 346 421060 Mo-106 3.57020E-02 4.13210E-02 421060 + 347 421070 Mo-107 1.67190E-02 1.85450E-02 421070 + 348 421080 Mo-108 8.61670E-03 8.92630E-03 421080 + 349 421090 Mo-109 2.21220E-03 2.25210E-03 421090 + 350 421100 Mo-110 5.30250E-04 5.32180E-04 421100 + 351 421110 Mo-111 4.60500E-05 4.60500E-05 421110 + 352 421120 Mo-112 1.71370E-05 1.71370E-05 421120 + 353 421130 Mo-113 2.31900E-06 2.31900E-06 421130 + 354 431000 Tc-100 2.91210E-06 2.91210E-06 431000 + 355 431010 Tc-101 2.92580E-05 6.25880E-02 431010 + 356 431020 Tc-102 7.85850E-05 6.59300E-02 431020 + 357 431021 Tc-102m 7.85850E-05 7.85850E-05 431021 + 358 431030 Tc-103 9.59820E-04 6.73380E-02 431030 + 359 431040 Tc-104 3.03860E-03 7.02040E-02 431040 + 360 431050 Tc-105 9.66510E-03 6.20310E-02 431050 + 361 431060 Tc-106 1.58600E-02 5.71810E-02 431060 + 362 431070 Tc-107 2.33700E-02 4.19150E-02 431070 + 363 431080 Tc-108 1.82870E-02 2.72250E-02 431080 + 364 431090 Tc-109 1.33970E-02 1.56370E-02 431090 + 365 431100 Tc-110 5.83310E-03 6.36570E-03 431100 + 366 431110 Tc-111 2.19030E-03 2.23620E-03 431110 + 367 431120 Tc-112 5.20840E-04 5.37620E-04 431120 + 368 431130 Tc-113 1.54390E-04 1.56710E-04 431130 + 369 431140 Tc-114 4.83070E-05 4.83070E-05 431140 + 370 431150 Tc-115 2.58090E-05 2.58090E-05 431150 + 371 431160 Tc-116 5.15340E-06 5.15340E-06 431160 + 372 441020 Ru-102 1.02630E-06 6.60090E-02 44102.82c + 373 441030 Ru-103 3.46030E-06 6.73520E-02 44103.82c + 374 441031 Ru-103m 9.68170E-06 9.68170E-06 441031 + 375 441040 Ru-104 1.16300E-04 7.03200E-02 44104.82c + 376 441050 Ru-105 5.65320E-04 6.25970E-02 44105.82c + 377 441060 Ru-106 2.41740E-03 5.95980E-02 44106.82c + 378 441070 Ru-107 4.84720E-03 4.67620E-02 441070 + 379 441080 Ru-108 1.08010E-02 3.80390E-02 441080 + 380 441090 Ru-109 1.13360E-02 2.69630E-02 441090 + 381 441100 Ru-110 1.11590E-02 1.75220E-02 441100 + 382 441110 Ru-111 5.88650E-03 8.13080E-03 441110 + 383 441120 Ru-112 2.83140E-03 3.37220E-03 441120 + 384 441130 Ru-113 4.71430E-04 8.55760E-04 441130 + 385 441131 Ru-113m 4.71430E-04 4.71430E-04 441131 + 386 441140 Ru-114 3.17150E-04 3.66000E-04 441140 + 387 441150 Ru-115 9.40950E-05 1.16830E-04 441150 + 388 441160 Ru-116 3.10640E-05 3.55870E-05 441160 + 389 441170 Ru-117 6.78970E-06 6.78970E-06 441170 + 390 441180 Ru-118 2.67870E-06 2.67870E-06 441180 + 391 451050 Rh-105 8.83380E-07 6.25980E-02 45105.82c + 392 451051 Rh-105m 1.17620E-07 1.77700E-02 451051 + 393 451060 Rh-106 3.43610E-06 5.96010E-02 451060 + 394 451061 Rh-106m 9.36590E-06 9.36590E-06 451061 + 395 451070 Rh-107 9.62930E-05 4.68580E-02 451070 + 396 451080 Rh-108 7.80570E-05 3.81170E-02 451080 + 397 451081 Rh-108m 2.71970E-04 2.71970E-04 451081 + 398 451090 Rh-109 1.07260E-03 2.80360E-02 451090 + 399 451100 Rh-110 1.65500E-03 1.91770E-02 451100 + 400 451101 Rh-110m 3.89620E-05 3.89620E-05 451101 + 401 451110 Rh-111 2.34950E-03 1.04800E-02 451110 + 402 451120 Rh-112 8.02550E-04 4.17480E-03 451120 + 403 451121 Rh-112m 8.02550E-04 8.02550E-04 451121 + 404 451130 Rh-113 1.10720E-03 2.19870E-03 451130 + 405 451140 Rh-114 2.06010E-04 5.72280E-04 451140 + 406 451141 Rh-114m 2.06010E-04 2.06010E-04 451141 + 407 451150 Rh-115 1.22050E-04 2.39000E-04 451150 + 408 451160 Rh-116 9.74510E-06 4.50870E-05 451160 + 409 451161 Rh-116m 2.65630E-05 2.65630E-05 451161 + 410 451170 Rh-117 1.36040E-05 2.03650E-05 451170 + 411 451180 Rh-118 4.01990E-06 6.58850E-06 451180 + 412 451190 Rh-119 2.87000E-09 2.87000E-09 451190 + 413 451200 Rh-120 6.04500E-11 6.04500E-11 451200 + 414 451220 Rh-122 1.86800E-08 1.86800E-08 451220 + 415 461070 Pd-107 3.15730E-07 4.68590E-02 46107.82c + 416 461071 Pd-107m 6.93970E-07 6.93970E-07 461071 + 417 461080 Pd-108 7.25660E-06 3.83960E-02 46108.82c + 418 461090 Pd-109 7.19080E-06 2.80590E-02 461090 + 419 461091 Pd-109m 1.58050E-05 1.40340E-02 461091 + 420 461100 Pd-110 1.00540E-04 1.93170E-02 46110.82c + 421 461110 Pd-111 4.54350E-05 1.05870E-02 461110 + 422 461111 Pd-111m 9.98650E-05 1.41790E-04 461111 + 423 461120 Pd-112 2.28700E-04 5.20600E-03 461120 + 424 461130 Pd-113 5.42740E-05 2.40480E-03 461130 + 425 461131 Pd-113m 1.51860E-04 1.51860E-04 461131 + 426 461140 Pd-114 1.83090E-04 9.61380E-04 461140 + 427 461150 Pd-115 3.77460E-05 2.51460E-04 461150 + 428 461151 Pd-115m 8.29640E-05 1.17670E-04 461151 + 429 461160 Pd-116 1.10650E-04 1.82300E-04 461160 + 430 461170 Pd-117 1.47970E-05 6.78760E-05 461170 + 431 461171 Pd-117m 3.25220E-05 3.25220E-05 461171 + 432 461180 Pd-118 4.54620E-05 5.18580E-05 461180 + 433 461190 Pd-119 1.52060E-05 1.52090E-05 461190 + 434 461200 Pd-120 5.00340E-06 5.00350E-06 461200 + 435 461210 Pd-121 3.42820E-06 3.42820E-06 461210 + 436 461220 Pd-122 8.72980E-06 8.74850E-06 461220 + 437 461230 Pd-123 1.54980E-06 1.54980E-06 461230 + 438 461240 Pd-124 5.59290E-07 5.59290E-07 461240 + 439 471100 Ag-110 1.28220E-09 1.32970E-09 471100 + 440 471101 Ag-110m 3.49490E-09 3.49490E-09 47510.82c + 441 471110 Ag-111 1.28890E-07 1.05740E-02 47111.82c + 442 471111 Ag-111m 9.68010E-07 1.05410E-02 471111 + 443 471120 Ag-112 5.34660E-06 5.21140E-03 471120 + 444 471130 Ag-113 1.08710E-06 1.58210E-03 471130 + 445 471131 Ag-113m 8.16440E-06 2.31090E-03 471131 + 446 471140 Ag-114 2.40380E-06 9.75430E-04 471140 + 447 471141 Ag-114m 1.16530E-05 1.16530E-05 471141 + 448 471150 Ag-115 1.72370E-06 2.25000E-04 471150 + 449 471151 Ag-115m 1.29460E-05 1.89090E-04 471151 + 450 471160 Ag-116 3.79490E-06 1.86720E-04 471160 + 451 471161 Ag-116m 1.03440E-05 1.03440E-05 471161 + 452 471170 Ag-117 3.65810E-06 4.12810E-05 471170 + 453 471171 Ag-117m 2.74750E-05 6.14130E-05 471171 + 454 471180 Ag-118 1.09760E-05 8.02760E-05 471180 + 455 471181 Ag-118m 5.32090E-05 6.06230E-05 471181 + 456 471190 Ag-119 7.96160E-06 1.55660E-05 471190 + 457 471191 Ag-119m 5.97960E-05 6.74010E-05 471191 + 458 471200 Ag-120 1.81020E-05 3.27400E-05 471200 + 459 471201 Ag-120m 3.02730E-05 3.27750E-05 471201 + 460 471210 Ag-121 3.60180E-05 3.94370E-05 471210 + 461 471220 Ag-122 7.31130E-06 1.60600E-05 471220 + 462 471221 Ag-122m 7.88260E-06 7.88260E-06 471221 + 463 471230 Ag-123 2.42120E-05 2.57620E-05 471230 + 464 471240 Ag-124 1.07590E-05 1.71180E-05 471240 + 465 471241 Ag-124m 1.16000E-05 1.16000E-05 471241 + 466 471250 Ag-125 1.80960E-05 1.80960E-05 471250 + 467 471260 Ag-126 5.01760E-06 5.01760E-06 471260 + 468 471270 Ag-127 3.14850E-06 3.14850E-06 471270 + 469 471280 Ag-128 5.54540E-08 5.54540E-08 471280 + 470 471290 Ag-129 6.55920E-09 6.55920E-09 471290 + 471 481120 Cd-112 1.98040E-10 5.21140E-03 48112.82c + 472 481130 Cd-113 8.83310E-10 2.38670E-03 48113.82c + 473 481131 Cd-113m 3.34510E-09 2.73560E-05 481131 + 474 481140 Cd-114 8.67810E-08 9.75520E-04 48114.82c + 475 481150 Cd-115 8.20230E-08 3.57150E-04 481150 + 476 481151 Cd-115m 3.10620E-07 1.76250E-05 48515.82c + 477 481160 Cd-116 3.24630E-06 1.99690E-04 48116.82c + 478 481170 Cd-117 5.66430E-07 7.82870E-05 481170 + 479 481171 Cd-117m 2.14510E-06 2.34330E-05 481171 + 480 481180 Cd-118 1.73970E-05 1.33440E-04 481180 + 481 481190 Cd-119 4.36870E-06 7.95530E-05 481190 + 482 481191 Cd-119m 1.22230E-05 2.00070E-05 481191 + 483 481200 Cd-120 7.00890E-05 1.23480E-04 481200 + 484 481210 Cd-121 1.58170E-05 5.11340E-05 481210 + 485 481211 Cd-121m 4.42560E-05 4.83760E-05 481211 + 486 481220 Cd-122 7.60980E-05 1.00040E-04 481220 + 487 481230 Cd-123 2.33520E-05 4.44380E-05 481230 + 488 481231 Cd-123m 6.53370E-05 7.00300E-05 481231 + 489 481240 Cd-124 2.16660E-04 2.39560E-04 481240 + 490 481250 Cd-125 8.57700E-05 9.48180E-05 481250 + 491 481251 Cd-125m 2.39980E-04 2.49030E-04 481251 + 492 481260 Cd-126 3.40270E-04 3.45290E-04 481260 + 493 481270 Cd-127 2.18170E-04 2.21320E-04 481270 + 494 481280 Cd-128 1.10030E-04 1.10090E-04 481280 + 495 481290 Cd-129 2.21520E-05 2.21550E-05 481290 + 496 481291 Cd-129m 6.19800E-05 6.19830E-05 481291 + 497 481300 Cd-130 1.40750E-05 1.40750E-05 481300 + 498 481310 Cd-131 5.92460E-08 5.92460E-08 481310 + 499 481320 Cd-132 1.76680E-09 1.76680E-09 481320 + 500 491150 In-115 1.11050E-10 3.56920E-04 49115.82c + 501 491151 In-115m 2.23590E-11 3.57150E-04 491151 + 502 491160 In-116 4.18640E-10 4.18640E-10 491160 + 503 491161 In-116m 6.76020E-10 1.45870E-09 491161 + 504 491162 In-116m 7.82650E-10 7.82650E-10 491162 + 505 491170 In-117 3.02730E-08 6.36120E-05 491170 + 506 491171 In-117m 6.09530E-09 7.21070E-05 491171 + 507 491180 In-118 9.30780E-08 1.33530E-04 491180 + 508 491181 In-118m 1.50300E-07 3.21880E-07 491181 + 509 491182 In-118m 1.74010E-07 1.74010E-07 491182 + 510 491190 In-119 1.15020E-06 3.28840E-05 491190 + 511 491191 In-119m 2.31590E-07 7.20950E-05 491191 + 512 491200 In-120 1.11090E-06 1.24590E-04 491200 + 513 491201 In-120m 1.11090E-06 1.11090E-06 491201 + 514 491202 In-120m 1.11090E-06 1.11090E-06 491202 + 515 491210 In-121 7.12080E-06 7.31430E-05 491210 + 516 491211 In-121m 1.43380E-06 3.53460E-05 491211 + 517 491220 In-122 3.78200E-06 1.03820E-04 491220 + 518 491221 In-122m 3.16250E-06 3.16250E-06 491221 + 519 491222 In-122m 3.16250E-06 3.16250E-06 491222 + 520 491230 In-123 3.70850E-05 1.20030E-04 491230 + 521 491231 In-123m 7.46690E-06 3.89950E-05 491231 + 522 491240 In-124 4.63640E-05 2.85930E-04 491240 + 523 491241 In-124m 4.99860E-05 4.99860E-05 491241 + 524 491250 In-125 3.46050E-04 6.40460E-04 491250 + 525 491251 In-125m 6.96750E-05 1.19110E-04 491251 + 526 491260 In-126 3.29920E-04 6.75200E-04 491260 + 527 491261 In-126m 3.55690E-04 3.55690E-04 491261 + 528 491270 In-127 1.20620E-03 1.20620E-03 491270 + 529 491271 In-127m 2.42850E-04 4.64170E-04 491271 + 530 491280 In-128 5.17520E-04 8.30250E-04 491280 + 531 491281 In-128m 2.02640E-04 3.12730E-04 491281 + 532 491282 In-128m 7.76440E-04 7.76440E-04 491282 + 533 491290 In-129 2.36790E-03 2.43020E-03 491290 + 534 491291 In-129m 4.76770E-04 4.99170E-04 491291 + 535 491300 In-130 3.07090E-04 3.20680E-04 491300 + 536 491301 In-130m 4.47140E-04 4.47140E-04 491301 + 537 491302 In-130m 6.22860E-04 6.22860E-04 491302 + 538 491310 In-131 1.32650E-04 1.34060E-04 491310 + 539 491311 In-131m 1.32650E-04 1.32650E-04 491311 + 540 491312 In-131m 1.32650E-04 1.32650E-04 491312 + 541 491320 In-132 4.17960E-05 4.17970E-05 491320 + 542 491330 In-133 2.69250E-06 3.23460E-06 491330 + 543 491331 In-133m 5.42120E-07 5.42120E-07 491331 + 544 491340 In-134 2.24030E-08 2.24030E-08 491340 + 545 501170 Sn-117 5.34090E-13 1.01760E-04 50117.82c + 546 501171 Sn-117m 2.02260E-12 2.16730E-07 501171 + 547 501180 Sn-118 3.40210E-10 1.33860E-04 50118.82c + 548 501190 Sn-119 1.12730E-09 1.00950E-04 50119.82c + 549 501191 Sn-119m 4.26920E-09 2.97120E-05 501191 + 550 501200 Sn-120 1.92380E-07 1.27000E-04 50120.82c + 551 501210 Sn-121 4.51140E-07 1.07640E-04 501210 + 552 501211 Sn-121m 1.26230E-06 9.54820E-06 501211 + 553 501220 Sn-122 3.37360E-06 1.13520E-04 50122.82c + 554 501230 Sn-123 8.88610E-06 1.80370E-05 50123.82c + 555 501231 Sn-123m 3.17590E-06 1.53050E-04 501231 + 556 501240 Sn-124 7.05390E-05 4.06450E-04 50124.82c + 557 501250 Sn-125 1.14340E-04 2.22520E-04 50125.82c + 558 501251 Sn-125m 4.08640E-05 6.92240E-04 501251 + 559 501260 Sn-126 5.34130E-04 1.56820E-03 50126.82c + 560 501270 Sn-127 9.92190E-04 1.46230E-03 501270 + 561 501271 Sn-127m 3.54610E-04 1.55160E-03 501271 + 562 501280 Sn-128 1.08360E-03 5.64410E-03 501280 + 563 501281 Sn-128m 2.95380E-03 3.73020E-03 501281 + 564 501290 Sn-129 3.15040E-03 5.82120E-03 501290 + 565 501291 Sn-129m 8.81460E-03 9.07330E-03 501291 + 566 501300 Sn-130 4.39370E-03 5.24580E-03 501300 + 567 501301 Sn-130m 1.19760E-02 1.25180E-02 501301 + 568 501310 Sn-131 2.50520E-03 2.76210E-03 501310 + 569 501311 Sn-131m 7.00930E-03 7.14770E-03 501311 + 570 501320 Sn-132 6.07440E-03 6.11890E-03 501320 + 571 501330 Sn-133 1.10300E-03 1.10350E-03 501330 + 572 501340 Sn-134 1.61610E-04 1.61620E-04 501340 + 573 501350 Sn-135 1.37750E-05 1.37750E-05 501350 + 574 501360 Sn-136 5.48940E-06 5.48940E-06 501360 + 575 501370 Sn-137 3.24650E-09 3.24650E-09 501370 + 576 511200 Sb-120 9.69440E-12 9.69440E-12 511200 + 577 511201 Sb-120m 1.62130E-11 1.62130E-11 511201 + 578 511210 Sb-121 1.48430E-09 1.09780E-04 51121.82c + 579 511230 Sb-123 3.45070E-06 1.74530E-04 51123.82c + 580 511240 Sb-124 3.27220E-06 8.42160E-06 51124.82c + 581 511241 Sb-124m 2.63970E-06 6.86580E-06 511241 + 582 511242 Sb-124m 4.22610E-06 4.22610E-06 511242 + 583 511250 Sb-125 1.08200E-05 9.25590E-04 51125.82c + 584 511260 Sb-126 1.40930E-05 1.68530E-05 51126.82c + 585 511261 Sb-126m 8.80260E-06 1.97140E-05 511261 + 586 511262 Sb-126m 1.09120E-05 1.09120E-05 511262 + 587 511270 Sb-127 1.33240E-04 3.14720E-03 511270 + 588 511280 Sb-128 1.41230E-04 5.79240E-03 511280 + 589 511281 Sb-128m 1.97520E-04 1.97520E-04 511281 + 590 511290 Sb-129 2.02660E-03 1.32900E-02 511290 + 591 511291 Sb-129m 1.49980E-03 6.03640E-03 511291 + 592 511300 Sb-130 4.34060E-03 1.58450E-02 511300 + 593 511301 Sb-130m 4.34060E-03 1.05990E-02 511301 + 594 511310 Sb-131 1.83800E-02 2.82900E-02 511310 + 595 511320 Sb-132 1.27270E-02 1.88460E-02 511320 + 596 511321 Sb-132m 1.12690E-02 1.12690E-02 511321 + 597 511330 Sb-133 2.62970E-02 2.74280E-02 511330 + 598 511340 Sb-134 2.29000E-03 2.42560E-03 511340 + 599 511341 Sb-134m 6.24200E-03 6.24350E-03 511341 + 600 511350 Sb-135 2.95780E-03 2.97030E-03 511350 + 601 511360 Sb-136 5.69860E-04 5.73700E-04 511360 + 602 511370 Sb-137 6.82690E-05 6.82700E-05 511370 + 603 511380 Sb-138 4.83720E-06 4.83720E-06 511380 + 604 511390 Sb-139 3.68920E-08 3.68920E-08 511390 + 605 521260 Te-126 3.75940E-06 3.75670E-05 52126.82c + 606 521270 Te-127 8.28450E-07 3.13780E-03 521270 + 607 521271 Te-127m 2.31790E-06 5.20950E-04 52527.82c + 608 521280 Te-128 1.19420E-05 5.99480E-03 52128.82c + 609 521290 Te-129 3.75650E-05 1.58550E-02 521290 + 610 521291 Te-129m 1.05110E-04 7.32140E-03 52529.82c + 611 521300 Te-130 1.06180E-03 2.75060E-02 52130.82c + 612 521310 Te-131 7.94900E-04 2.77620E-02 521310 + 613 521311 Te-131m 2.22410E-03 4.48900E-03 521311 + 614 521320 Te-132 1.52890E-02 4.54040E-02 52132.82c + 615 521330 Te-133 9.72390E-03 3.80040E-02 521330 + 616 521331 Te-133m 2.72070E-02 3.19520E-02 521331 + 617 521340 Te-134 5.98790E-02 6.90100E-02 521340 + 618 521350 Te-135 3.44300E-02 3.70270E-02 521350 + 619 521360 Te-136 1.90580E-02 1.95700E-02 521360 + 620 521370 Te-137 5.29980E-03 5.33460E-03 521370 + 621 521380 Te-138 1.40420E-03 1.40900E-03 521380 + 622 521390 Te-139 1.95410E-04 1.95450E-04 521390 + 623 521400 Te-140 2.82280E-05 2.82280E-05 521400 + 624 521410 Te-141 9.62020E-07 9.62020E-07 521410 + 625 521420 Te-142 3.58830E-09 3.58830E-09 521420 + 626 531290 I-129 1.24630E-08 1.85630E-02 53129.82c + 627 531300 I-130 1.86800E-06 2.44360E-06 53130.82c + 628 531301 I-130m 6.85310E-07 6.85310E-07 531301 + 629 531310 I-131 3.09810E-05 3.13400E-02 53131.82c + 630 531320 I-132 1.24190E-04 4.56230E-02 531320 + 631 531321 I-132m 1.09950E-04 1.09950E-04 531321 + 632 531330 I-133 1.22630E-03 6.64990E-02 531330 + 633 531331 I-133m 9.07500E-04 9.07500E-04 531331 + 634 531340 I-134 4.25560E-03 7.69470E-02 531340 + 635 531341 I-134m 3.76780E-03 3.76780E-03 531341 + 636 531350 I-135 3.31080E-02 7.01360E-02 53135.82c + 637 531360 I-136 9.35240E-03 2.90020E-02 531360 + 638 531361 I-136m 2.54930E-02 2.55720E-02 531361 + 639 531370 I-137 3.45050E-02 3.97690E-02 531370 + 640 531380 I-138 1.50290E-02 1.63490E-02 531380 + 641 531390 I-139 1.15480E-02 1.17430E-02 531390 + 642 531400 I-140 2.48070E-03 2.50890E-03 531400 + 643 531410 I-141 6.45100E-04 6.46060E-04 531410 + 644 531420 I-142 6.49940E-05 6.49980E-05 531420 + 645 531430 I-143 5.21350E-06 5.21350E-06 531430 + 646 531440 I-144 2.10250E-08 2.10250E-08 531440 + 647 541310 Xe-131 4.10510E-10 3.13400E-02 54131.82c + 648 541311 Xe-131m 1.14860E-09 3.40410E-04 541311 + 649 541320 Xe-132 1.74520E-06 4.56420E-02 54132.82c + 650 541321 Xe-132m 2.33800E-06 2.33800E-06 541321 + 651 541330 Xe-133 7.38270E-06 6.65270E-02 54133.82c + 652 541331 Xe-133m 2.06560E-05 1.91350E-03 541331 + 653 541340 Xe-134 8.54400E-05 7.73520E-02 54134.82c + 654 541341 Xe-134m 2.32890E-04 3.19550E-04 541341 + 655 541350 Xe-135 5.60250E-04 7.21840E-02 54135.82c + 656 541351 Xe-135m 1.56760E-03 1.31460E-02 541351 + 657 541360 Xe-136 1.42740E-02 7.14330E-02 54136.82c + 658 541370 Xe-137 2.41230E-02 6.21730E-02 541370 + 659 541380 Xe-138 4.21890E-02 5.88230E-02 541380 + 660 541390 Xe-139 3.71910E-02 4.80170E-02 541390 + 661 541400 Xe-140 3.29840E-02 3.53950E-02 541400 + 662 541410 Xe-141 1.47890E-02 1.53160E-02 541410 + 663 541420 Xe-142 6.44160E-03 6.49240E-03 541420 + 664 541430 Xe-143 1.61070E-03 1.61380E-03 541430 + 665 541440 Xe-144 3.14100E-04 3.14110E-04 541440 + 666 541450 Xe-145 4.54060E-05 4.54060E-05 541450 + 667 541460 Xe-146 6.23240E-06 6.23240E-06 541460 + 668 541470 Xe-147 1.67900E-09 1.67900E-09 541470 + 669 551340 Cs-134 1.27960E-08 2.41260E-08 55134.82c + 670 551341 Cs-134m 1.13300E-08 1.13300E-08 551341 + 671 551350 Cs-135 3.39360E-06 7.22690E-02 55135.82c + 672 551351 Cs-135m 2.51140E-06 2.51140E-06 551351 + 673 551360 Cs-136 4.00120E-05 5.43150E-05 55136.82c + 674 551361 Cs-136m 2.86070E-05 2.86070E-05 551361 + 675 551370 Cs-137 9.92490E-04 6.31660E-02 55137.82c + 676 551380 Cs-138 1.35590E-03 6.20150E-02 551380 + 677 551381 Cs-138m 2.26760E-03 2.26760E-03 551381 + 678 551390 Cs-139 1.16100E-02 5.96270E-02 551390 + 679 551400 Cs-140 1.41540E-02 4.95560E-02 551400 + 680 551410 Cs-141 2.46320E-02 3.99640E-02 551410 + 681 551420 Cs-142 2.00270E-02 2.65120E-02 551420 + 682 551430 Cs-143 1.60960E-02 1.77030E-02 551430 + 683 551440 Cs-144 3.25210E-03 5.18450E-03 551440 + 684 551441 Cs-144m 3.25210E-03 3.25320E-03 551441 + 685 551450 Cs-145 2.33500E-03 2.37860E-03 551450 + 686 551460 Cs-146 5.15370E-04 5.21170E-04 551460 + 687 551470 Cs-147 9.56390E-05 9.56410E-05 551470 + 688 551480 Cs-148 8.79700E-06 8.79700E-06 551480 + 689 551490 Cs-149 8.99250E-07 8.99250E-07 551490 + 690 561360 Ba-136 2.45580E-07 6.95340E-05 56136.82c + 691 561361 Ba-136m 6.69410E-07 6.69410E-07 561361 + 692 561370 Ba-137 1.18310E-06 6.31700E-02 56137.82c + 693 561371 Ba-137m 3.31040E-06 5.96320E-02 561371 + 694 561380 Ba-138 1.29690E-04 6.25760E-02 56138.82c + 695 561390 Ba-139 7.67870E-04 6.03950E-02 561390 + 696 561400 Ba-140 3.14430E-03 5.27000E-02 56140.82c + 697 561410 Ba-141 6.08030E-03 4.60450E-02 561410 + 698 561420 Ba-142 1.88990E-02 4.57010E-02 561420 + 699 561430 Ba-143 2.56670E-02 4.32460E-02 561430 + 700 561440 Ba-144 2.95230E-02 3.65080E-02 561440 + 701 561450 Ba-145 1.73350E-02 1.94470E-02 561450 + 702 561460 Ba-146 1.05290E-02 1.10030E-02 561460 + 703 561470 Ba-147 3.74570E-03 3.81630E-03 561470 + 704 561480 Ba-148 1.13560E-03 1.14220E-03 561480 + 705 561490 Ba-149 1.89090E-04 1.89990E-04 561490 + 706 561500 Ba-150 2.61230E-05 2.61230E-05 561500 + 707 561510 Ba-151 6.38530E-06 6.38530E-06 561510 + 708 561520 Ba-152 1.09940E-09 1.09940E-09 561520 + 709 571390 La-139 1.12330E-06 6.03960E-02 57139.82c + 710 571400 La-140 1.31090E-05 5.27130E-02 57140.82c + 711 571410 La-141 8.47790E-05 4.61290E-02 571410 + 712 571420 La-142 3.07100E-04 4.60090E-02 571420 + 713 571430 La-143 1.97020E-03 4.52160E-02 571430 + 714 571440 La-144 4.47190E-03 4.09800E-02 571440 + 715 571450 La-145 1.14310E-02 3.08780E-02 571450 + 716 571460 La-146 3.69730E-03 1.47010E-02 571460 + 717 571461 La-146m 7.75670E-03 7.75670E-03 571461 + 718 571470 La-147 1.09710E-02 1.47920E-02 571470 + 719 571480 La-148 5.73130E-03 6.86970E-03 571480 + 720 571490 La-149 3.10290E-03 3.29210E-03 571490 + 721 571500 La-150 1.01650E-03 1.04260E-03 571500 + 722 571510 La-151 2.50070E-04 2.56450E-04 571510 + 723 571520 La-152 2.85080E-05 2.85090E-05 571520 + 724 571530 La-153 5.02940E-06 5.02940E-06 571530 + 725 571540 La-154 3.11740E-09 3.11740E-09 571540 + 726 571550 La-155 9.59340E-11 9.59340E-11 571550 + 727 581410 Ce-141 1.17280E-09 4.61290E-02 58141.82c + 728 581420 Ce-142 7.76320E-06 4.60160E-02 58142.82c + 729 581430 Ce-143 3.86470E-05 4.52550E-02 58143.82c + 730 581440 Ce-144 3.02540E-04 4.12830E-02 58144.82c + 731 581450 Ce-145 1.16810E-03 3.20460E-02 581450 + 732 581460 Ce-146 4.43680E-03 2.68940E-02 581460 + 733 581470 Ce-147 7.00420E-03 2.17960E-02 581470 + 734 581480 Ce-148 1.17880E-02 1.87040E-02 581480 + 735 581490 Ce-149 9.28350E-03 1.25580E-02 581490 + 736 581500 Ce-150 7.56300E-03 8.57750E-03 581500 + 737 581510 Ce-151 3.40950E-03 3.66770E-03 581510 + 738 581520 Ce-152 1.47060E-03 1.49740E-03 581520 + 739 581530 Ce-153 4.00310E-04 4.05340E-04 581530 + 740 581540 Ce-154 7.69520E-05 7.69550E-05 581540 + 741 581550 Ce-155 7.87070E-06 7.87080E-06 581550 + 742 581560 Ce-156 1.31550E-06 1.31550E-06 581560 + 743 581570 Ce-157 1.82810E-10 1.82810E-10 581570 + 744 591440 Pr-144 6.84250E-10 4.12820E-02 591440 + 745 591441 Pr-144m 6.96100E-09 5.69690E-04 591441 + 746 591450 Pr-145 7.07040E-06 3.20540E-02 591450 + 747 591460 Pr-146 1.97710E-05 2.69140E-02 591460 + 748 591470 Pr-147 1.43080E-04 2.19390E-02 591470 + 749 591480 Pr-148 7.69180E-05 1.87810E-02 591480 + 750 591481 Pr-148m 3.72890E-04 3.72890E-04 591481 + 751 591490 Pr-149 1.67260E-03 1.42300E-02 591490 + 752 591500 Pr-150 2.82240E-03 1.14000E-02 591500 + 753 591510 Pr-151 4.16480E-03 7.83250E-03 591510 + 754 591520 Pr-152 2.80670E-03 4.30660E-03 591520 + 755 591530 Pr-153 2.07330E-03 2.47660E-03 591530 + 756 591540 Pr-154 6.95010E-04 7.71470E-04 591540 + 757 591550 Pr-155 2.61790E-04 2.69660E-04 591550 + 758 591560 Pr-156 4.58310E-05 4.71460E-05 591560 + 759 591570 Pr-157 1.21160E-05 1.21160E-05 591570 + 760 591580 Pr-158 2.88190E-08 2.88190E-08 591580 + 761 591590 Pr-159 7.84460E-10 7.84460E-10 591590 + 762 601460 Nd-146 1.03900E-06 2.69150E-02 60146.82c + 763 601470 Nd-147 4.65740E-06 2.19440E-02 60147.82c + 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1.97780E-05 1.97780E-05 611522 + 784 611530 Pm-153 1.71690E-04 5.75480E-03 611530 + 785 611540 Pm-154 1.70940E-04 3.47120E-03 611540 + 786 611541 Pm-154m 1.70940E-04 1.70940E-04 611541 + 787 611550 Pm-155 7.09380E-04 2.59720E-03 611550 + 788 611560 Pm-156 6.33400E-04 1.47390E-03 611560 + 789 611570 Pm-157 5.73060E-04 8.44150E-04 611570 + 790 611580 Pm-158 2.57610E-04 3.21750E-04 611580 + 791 611590 Pm-159 8.61830E-05 9.60270E-05 611590 + 792 611600 Pm-160 2.57810E-05 2.81020E-05 611600 + 793 611610 Pm-161 3.55540E-06 3.55640E-06 611610 + 794 611620 Pm-162 5.32770E-08 5.32770E-08 611620 + 795 611630 Pm-163 2.96700E-09 2.96700E-09 611630 + 796 621510 Sm-151 2.34390E-10 9.00190E-03 62151.82c + 797 621520 Sm-152 1.10020E-06 7.04120E-03 62152.82c + 798 621530 Sm-153 2.32100E-06 5.76360E-03 62153.82c + 799 621531 Sm-153m 6.49420E-06 6.49420E-06 621531 + 800 621540 Sm-154 3.27650E-05 3.67490E-03 62154.82c + 801 621550 Sm-155 1.08300E-04 2.70550E-03 621550 + 802 621560 Sm-156 2.40170E-04 1.71410E-03 621560 + 803 621570 Sm-157 3.64780E-04 1.20890E-03 621570 + 804 621580 Sm-158 4.39180E-04 7.60940E-04 621580 + 805 621590 Sm-159 3.14200E-04 4.10280E-04 621590 + 806 621600 Sm-160 1.85180E-04 2.13210E-04 621600 + 807 621610 Sm-161 5.92500E-05 6.28060E-05 621610 + 808 621620 Sm-162 1.91280E-05 1.91810E-05 621620 + 809 621630 Sm-163 1.07010E-06 1.07310E-06 621630 + 810 621640 Sm-164 1.86640E-07 1.86640E-07 621640 + 811 621650 Sm-165 1.65000E-09 1.65000E-09 621650 + 812 631540 Eu-154 1.97380E-10 4.10180E-10 63154.82c + 813 631541 Eu-154m 2.12800E-10 2.12800E-10 631541 + 814 631550 Eu-155 1.31320E-06 2.70680E-03 63155.82c + 815 631560 Eu-156 3.94780E-06 1.71800E-03 63156.82c + 816 631570 Eu-157 4.04460E-06 1.21300E-03 63157.82c + 817 631580 Eu-158 1.89300E-05 7.79870E-04 631580 + 818 631590 Eu-159 3.94140E-05 4.49700E-04 631590 + 819 631600 Eu-160 4.45440E-05 2.57750E-04 631600 + 820 631610 Eu-161 3.79290E-05 1.00740E-04 631610 + 821 631620 Eu-162 2.81320E-05 4.73130E-05 631620 + 822 631630 Eu-163 1.62810E-05 1.73540E-05 631630 + 823 631640 Eu-164 6.58800E-06 6.77460E-06 631640 + 824 631650 Eu-165 1.06780E-06 1.06940E-06 631650 + 825 631660 Eu-166 8.32800E-08 8.32800E-08 631660 + 826 631670 Eu-167 2.60350E-09 2.60350E-09 631670 + 827 641570 Gd-157 1.34810E-06 1.21430E-03 64157.82c + 828 641580 Gd-158 3.23340E-08 7.79910E-04 64158.82c + 829 641590 Gd-159 3.69430E-06 4.53390E-04 641590 + 830 641600 Gd-160 8.20450E-06 2.65960E-04 64160.82c + 831 641610 Gd-161 1.06670E-05 1.11400E-04 641610 + 832 641620 Gd-162 1.68800E-05 6.41930E-05 641620 + 833 641630 Gd-163 2.27960E-05 4.01500E-05 641630 + 834 641640 Gd-164 2.52550E-05 3.20300E-05 641640 + 835 641650 Gd-165 2.13560E-06 3.20500E-06 641650 + 836 641660 Gd-166 4.26350E-06 4.34680E-06 641660 + 837 641670 Gd-167 2.11340E-07 2.13940E-07 641670 + 838 641680 Gd-168 3.02650E-08 3.02650E-08 641680 + 839 641690 Gd-169 2.12830E-09 2.12830E-09 641690 + 840 651590 Tb-159 4.80300E-11 4.53390E-04 65159.82c + 841 651600 Tb-160 1.01500E-09 1.01500E-09 65160.82c + 842 651610 Tb-161 1.81560E-08 1.11420E-04 651610 + 843 651620 Tb-162 1.03870E-07 6.42970E-05 651620 + 844 651630 Tb-163 2.17100E-06 4.23210E-05 651630 + 845 651640 Tb-164 3.29410E-06 3.53240E-05 651640 + 846 651650 Tb-165 3.20350E-06 6.40850E-06 651650 + 847 651660 Tb-166 3.19770E-06 7.54450E-06 651660 + 848 651670 Tb-167 1.68320E-06 1.89710E-06 651670 + 849 651680 Tb-168 6.64560E-07 6.94820E-07 651680 + 850 651690 Tb-169 1.65850E-07 1.67980E-07 651690 + 851 651700 Tb-170 1.28350E-08 1.28350E-08 651700 + 852 651710 Tb-171 1.78870E-09 1.78870E-09 651710 + 853 661620 Dy-162 5.76950E-11 6.42970E-05 66162.82c + 854 661630 Dy-163 8.74210E-10 4.23220E-05 66163.82c + 855 661640 Dy-164 2.43190E-08 3.53480E-05 66164.82c + 856 661650 Dy-165 2.98940E-08 6.44230E-06 661650 + 857 661651 Dy-165m 3.98020E-09 3.98020E-09 661651 + 858 661660 Dy-166 1.06590E-06 8.61040E-06 661660 + 859 661670 Dy-167 2.44470E-07 2.14160E-06 661670 + 860 661680 Dy-168 3.66410E-07 1.06120E-06 661680 + 861 661690 Dy-169 2.89060E-07 4.57040E-07 661690 + 862 661700 Dy-170 1.74490E-07 1.87320E-07 661700 + 863 661710 Dy-171 3.50210E-08 3.68100E-08 661710 + 864 661720 Dy-172 1.09000E-08 1.09000E-08 661720 + 865 661730 Dy-173 6.98950E-10 6.98950E-10 661730 + 866 671640 Ho-164 6.42520E-13 2.39390E-12 671640 + 867 671641 Ho-164m 1.75140E-12 1.75140E-12 671641 + 868 671650 Ho-165 2.96510E-11 6.44240E-06 67165.82c + 869 671660 Ho-166 1.94030E-10 8.61060E-06 671660 + 870 671661 Ho-166m 5.28880E-10 5.28880E-10 671661 + 871 671670 Ho-167 3.56990E-09 2.14520E-06 671670 + 872 671680 Ho-168 3.10720E-09 1.06950E-06 671680 + 873 671681 Ho-168m 5.19630E-09 5.19630E-09 671681 + 874 671690 Ho-169 5.49920E-08 5.12030E-07 671690 + 875 671700 Ho-170 3.22310E-08 3.22310E-08 671700 + 876 671701 Ho-170m 1.18240E-08 1.99150E-07 671701 + 877 671710 Ho-171 6.58800E-08 1.02690E-07 671710 + 878 671720 Ho-172 2.64990E-08 3.73990E-08 671720 + 879 671730 Ho-173 1.37170E-08 1.44160E-08 671730 + 880 671740 Ho-174 1.91610E-09 1.91610E-09 671740 + 881 671750 Ho-175 4.98470E-10 4.98470E-10 671750 + 882 681680 Er-168 1.73620E-11 1.06960E-06 68168.82c + 883 681690 Er-169 1.95000E-10 5.12220E-07 681690 + 884 681700 Er-170 1.47230E-09 2.32850E-07 68170.82c + 885 681710 Er-171 3.29730E-09 1.05990E-07 681710 + 886 681720 Er-172 1.07190E-08 4.81180E-08 681720 + 887 681730 Er-173 7.17520E-09 2.15910E-08 681730 + 888 681740 Er-174 7.46640E-09 9.38250E-09 681740 + 889 681750 Er-175 2.57540E-09 3.07390E-09 681750 + 890 681760 Er-176 1.13600E-09 1.13600E-09 681760 + 891 681770 Er-177 1.29300E-10 1.29300E-10 681770 + 892 691710 Tm-171 1.09090E-11 1.06000E-07 691710 + 893 691720 Tm-172 5.88360E-11 4.81770E-08 691720 + 894 691730 Tm-173 3.59750E-10 2.19510E-08 691730 + 895 691740 Tm-174 5.39740E-10 9.92220E-09 691740 + 896 691750 Tm-175 1.45370E-09 4.52760E-09 691750 + 897 691760 Tm-176 8.16790E-10 1.95280E-09 691760 + 898 691770 Tm-177 7.01460E-10 8.30760E-10 691770 + 899 691780 Tm-178 1.84230E-10 1.84230E-10 691780 + 900 691790 Tm-179 7.11400E-11 7.11400E-11 691790 + 901 701740 Yb-174 4.20470E-12 9.92640E-09 701740 + 902 701750 Yb-175 1.61510E-11 4.54590E-09 701750 + 903 701751 Yb-175m 2.15040E-12 3.48840E-09 701751 + 904 701760 Yb-176 2.92750E-11 1.93970E-09 701760 + 905 701761 Yb-176m 6.14160E-11 1.03780E-09 701761 + 906 701770 Yb-177 8.99660E-11 9.38840E-10 701770 + 907 701771 Yb-177m 1.81140E-11 8.48870E-10 701771 + 908 701780 Yb-178 2.15670E-10 3.99900E-10 701780 + 909 701790 Yb-179 1.05850E-10 1.76990E-10 701790 + 910 701800 Yb-180 6.78490E-11 6.78490E-11 701800 + 911 701810 Yb-181 1.47640E-11 1.47640E-11 701810 + 912 711770 Lu-177 8.70570E-13 9.39810E-10 711770 + 913 711780 Lu-178 1.74540E-12 4.01650E-10 711780 + 914 711781 Lu-178m 2.33840E-12 2.33840E-12 711781 + 915 711790 Lu-179 1.50210E-11 1.94010E-10 711790 + 916 711791 Lu-179m 2.00000E-12 1.78990E-10 711791 + 917 711800 Lu-180 3.87620E-12 4.31710E-11 711800 + 918 711801 Lu-180m 3.87620E-12 7.17250E-11 711801 + 919 711802 Lu-180m 6.86370E-12 6.86370E-12 711802 + 920 711810 Lu-181 2.37610E-11 3.85250E-11 711810 + 921 711820 Lu-182 1.00450E-11 1.00450E-11 711820 + 922 711830 Lu-183 5.48520E-12 5.48520E-12 711830 + 923 721820 Hf-182 1.11410E-12 1.21410E-11 721820 + 924 721821 Hf-182m 2.33740E-12 2.33740E-12 721821 + 925 721830 Hf-183 2.45380E-12 7.93900E-12 721830 + 926 721841 Hf-184m 1.87850E-12 1.87850E-12 721841 + 927 721850 Hf-185 1.01110E-12 1.01110E-12 721850 + + Nuclide 94242.82c -- plutonium 242 (Pu-242) + + Neutron-induced fission: + + Interpolation region : 1 / 1 + Interpolation energy : 4.00000E-01 MeV + Number of products : 938 / 1075 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 3.74950E-05 3.74950E-05 1001.82c + 2 10020 H-2 1.14590E-05 1.14590E-05 1002.82c + 3 10030 H-3 1.63480E-04 1.63480E-04 1003.82c + 4 20040 He-4 2.37030E-03 2.37030E-03 2004.82c + 5 200520 Ca-52 1.54770E-12 1.54770E-12 200520 + 6 210520 Sc-52 3.33880E-12 4.85550E-12 210520 + 7 210530 Sc-53 7.50750E-12 7.50750E-12 210530 + 8 210540 Sc-54 4.53840E-12 4.53840E-12 210540 + 9 210550 Sc-55 5.18120E-12 5.18120E-12 210550 + 10 210560 Sc-56 1.08590E-12 1.08590E-12 210560 + 11 220520 Ti-52 1.08830E-12 5.94390E-12 220520 + 12 220530 Ti-53 3.12500E-12 1.06330E-11 220530 + 13 220540 Ti-54 1.52090E-11 1.97470E-11 220540 + 14 220550 Ti-55 2.24030E-11 2.75840E-11 220550 + 15 220560 Ti-56 4.26180E-11 4.37040E-11 220560 + 16 220570 Ti-57 2.03260E-11 2.03260E-11 220570 + 17 220580 Ti-58 1.75600E-11 1.75600E-11 220580 + 18 220590 Ti-59 3.09930E-12 3.09930E-12 220590 + 19 230550 V-55 1.10350E-11 3.86190E-11 230550 + 20 230560 V-56 2.62540E-11 7.00190E-11 230560 + 21 230570 V-57 1.01820E-10 1.22080E-10 230570 + 22 230580 V-58 1.17500E-10 1.35060E-10 230580 + 23 230590 V-59 1.96250E-10 1.99350E-10 230590 + 24 230600 V-60 6.78140E-11 6.78140E-11 230600 + 25 230610 V-61 4.56510E-11 4.56510E-11 230610 + 26 230620 V-62 6.69610E-12 6.69610E-12 230620 + 27 230630 V-63 1.14230E-12 1.14230E-12 230630 + 28 240560 Cr-56 2.20280E-12 7.27100E-11 240560 + 29 240570 Cr-57 1.18650E-11 2.41510E-10 240570 + 30 240580 Cr-58 1.13850E-10 1.40860E-10 240580 + 31 240590 Cr-59 2.36130E-10 4.35480E-10 240590 + 32 240600 Cr-60 6.79010E-10 7.49560E-10 240600 + 33 240610 Cr-61 6.35600E-10 6.78510E-10 240610 + 34 240620 Cr-62 9.18090E-10 9.25190E-10 240620 + 35 240630 Cr-63 2.55740E-10 2.56480E-10 240630 + 36 240640 Cr-64 1.17650E-10 1.17650E-10 240640 + 37 240650 Cr-65 1.40930E-11 1.40930E-11 240650 + 38 240660 Cr-66 1.87270E-12 1.87270E-12 240660 + 39 250580 Mn-58 1.45100E-12 1.42310E-10 250580 + 40 250590 Mn-59 3.12420E-11 4.66720E-10 250590 + 41 250600 Mn-60 1.07280E-11 7.72840E-10 250600 + 42 250601 Mn-60m 1.09140E-10 1.09140E-10 250601 + 43 250610 Mn-61 9.11990E-10 1.59050E-09 250610 + 44 250620 Mn-62 1.42510E-09 1.88770E-09 250620 + 45 250621 Mn-62m 2.23180E-10 6.85770E-10 250621 + 46 250630 Mn-63 3.95000E-09 4.20650E-09 250630 + 47 250640 Mn-64 2.63490E-09 2.75250E-09 250640 + 48 250650 Mn-65 3.22190E-09 3.23600E-09 250650 + 49 250660 Mn-66 7.17780E-10 7.19650E-10 250660 + 50 250670 Mn-67 2.50390E-10 2.50390E-10 250670 + 51 250680 Mn-68 2.25040E-11 2.25040E-11 250680 + 52 250690 Mn-69 2.45720E-12 2.45720E-12 250690 + 53 260600 Fe-60 2.33620E-12 8.71770E-10 260600 + 54 260610 Fe-61 2.71480E-11 1.61770E-09 260610 + 55 260620 Fe-62 4.44800E-10 3.01830E-09 260620 + 56 260630 Fe-63 1.37420E-09 5.58070E-09 260630 + 57 260640 Fe-64 7.37980E-09 1.01320E-08 260640 + 58 260650 Fe-65 1.15320E-08 1.47680E-08 260650 + 59 260660 Fe-66 2.29930E-08 2.37130E-08 260660 + 60 260670 Fe-67 1.21080E-08 1.23580E-08 260670 + 61 260680 Fe-68 1.14650E-08 1.14880E-08 260680 + 62 260690 Fe-69 2.14400E-09 2.14590E-09 260690 + 63 260700 Fe-70 5.15900E-10 5.15900E-10 260700 + 64 260710 Fe-71 3.54780E-11 3.54780E-11 260710 + 65 260720 Fe-72 3.16350E-12 3.16350E-12 260720 + 66 270620 Co-62 3.71280E-13 3.01870E-09 270620 + 67 270621 Co-62m 1.01200E-12 1.01200E-12 270621 + 68 270630 Co-63 4.40760E-11 5.62480E-09 270630 + 69 270640 Co-64 3.47560E-10 1.04800E-08 270640 + 70 270650 Co-65 4.72750E-09 1.94960E-08 270650 + 71 270660 Co-66 1.18550E-08 3.55680E-08 270660 + 72 270670 Co-67 5.05130E-08 6.28710E-08 270670 + 73 270680 Co-68 3.61300E-08 5.54330E-08 270680 + 74 270681 Co-68m 2.69680E-08 3.86060E-08 270681 + 75 270690 Co-69 1.10120E-07 1.12120E-07 270690 + 76 270700 Co-70 2.07480E-08 2.07480E-08 270700 + 77 270701 Co-70m 2.07480E-08 2.12640E-08 270701 + 78 270710 Co-71 3.08690E-08 3.09040E-08 270710 + 79 270720 Co-72 4.81490E-09 4.81810E-09 270720 + 80 270730 Co-73 7.04020E-10 7.04020E-10 270730 + 81 270740 Co-74 1.82840E-11 1.82840E-11 270740 + 82 270750 Co-75 1.56740E-12 1.56740E-12 270750 + 83 280640 Ni-64 1.44930E-12 1.04810E-08 28064.82c + 84 280650 Ni-65 3.24690E-11 1.95280E-08 280650 + 85 280660 Ni-66 8.11130E-10 3.63790E-08 280660 + 86 280670 Ni-67 4.86790E-09 6.77390E-08 280670 + 87 280680 Ni-68 5.10780E-08 1.26930E-07 280680 + 88 280690 Ni-69 5.53900E-08 1.66380E-07 280690 + 89 280691 Ni-69m 5.53900E-08 5.53900E-08 280691 + 90 280700 Ni-70 3.44260E-07 3.86270E-07 280700 + 91 280710 Ni-71 3.51180E-07 3.82080E-07 280710 + 92 280720 Ni-72 5.32440E-07 5.37260E-07 280720 + 93 280730 Ni-73 1.25920E-07 1.26620E-07 280730 + 94 280740 Ni-74 3.61900E-08 3.62080E-08 280740 + 95 280750 Ni-75 5.55720E-09 5.55880E-09 280750 + 96 280760 Ni-76 1.38340E-09 1.38340E-09 280760 + 97 280770 Ni-77 5.47570E-11 5.47570E-11 280770 + 98 280780 Ni-78 2.92380E-12 2.92380E-12 280780 + 99 290670 Cu-67 3.44860E-11 6.77740E-08 290670 + 100 290680 Cu-68 1.55370E-10 1.27450E-07 290680 + 101 290681 Cu-68m 4.23500E-10 4.23500E-10 290681 + 102 290690 Cu-69 1.20310E-08 2.33810E-07 290690 + 103 290700 Cu-70 3.42180E-09 3.50140E-08 290700 + 104 290701 Cu-70m 4.37000E-08 6.31850E-08 290701 + 105 290702 Cu-70m 3.42180E-09 3.89700E-07 290702 + 106 290710 Cu-71 4.21710E-07 8.03790E-07 290710 + 107 290720 Cu-72 7.96700E-07 1.33400E-06 290720 + 108 290730 Cu-73 1.60140E-06 1.72800E-06 290730 + 109 290740 Cu-74 2.14490E-06 2.18120E-06 290740 + 110 290750 Cu-75 1.01960E-06 1.02510E-06 290750 + 111 290760 Cu-76 2.10940E-07 2.11640E-07 290760 + 112 290761 Cu-76m 2.10940E-07 2.11640E-07 290761 + 113 290770 Cu-77 1.87810E-07 1.87860E-07 290770 + 114 290780 Cu-78 2.02940E-08 2.02970E-08 290780 + 115 290790 Cu-79 2.66370E-09 2.66370E-09 290790 + 116 290800 Cu-80 6.87190E-11 6.87190E-11 290800 + 117 300690 Zn-69 2.94890E-12 2.33820E-07 300690 + 118 300691 Zn-69m 1.46460E-11 1.46460E-11 300691 + 119 300700 Zn-70 7.92560E-10 4.37610E-07 300700 + 120 300710 Zn-71 1.71390E-09 8.05510E-07 300710 + 121 300711 Zn-71m 8.51210E-09 8.51210E-09 300711 + 122 300720 Zn-72 1.77620E-07 1.51160E-06 300720 + 123 300730 Zn-73 1.79290E-07 2.96400E-06 300730 + 124 300731 Zn-73m 2.47990E-07 1.05670E-06 300731 + 125 300732 Zn-73m 1.61730E-06 1.61730E-06 300732 + 126 300740 Zn-74 1.54160E-06 3.75870E-06 300740 + 127 300750 Zn-75 5.38760E-06 6.38310E-06 300750 + 128 300760 Zn-76 1.54450E-05 1.58620E-05 300760 + 129 300770 Zn-77 1.27370E-05 1.37730E-05 300770 + 130 300771 Zn-77m 1.69590E-06 1.69590E-06 300771 + 131 300780 Zn-78 2.72380E-05 2.72600E-05 300780 + 132 300790 Zn-79 2.86780E-06 2.86900E-06 300790 + 133 300800 Zn-80 9.76670E-06 9.76680E-06 300800 + 134 300810 Zn-81 2.95960E-08 2.95960E-08 300810 + 135 300820 Zn-82 1.09110E-09 1.09110E-09 300820 + 136 300830 Zn-83 8.44730E-11 8.44730E-11 300830 + 137 310710 Ga-71 1.49700E-11 8.14030E-07 310710 + 138 310720 Ga-72 4.02530E-10 1.51200E-06 310720 + 139 310721 Ga-72m 3.95680E-11 5.04060E-08 310721 + 140 310730 Ga-73 1.20700E-08 3.78470E-06 310730 + 141 310740 Ga-74 2.97650E-08 2.87110E-06 310740 + 142 310741 Ga-74m 2.97650E-08 3.78840E-06 310741 + 143 310750 Ga-75 1.03110E-06 7.41420E-06 310750 + 144 310760 Ga-76 4.77090E-06 2.06330E-05 310760 + 145 310770 Ga-77 1.44450E-05 2.90660E-05 310770 + 146 310780 Ga-78 2.38740E-05 5.11710E-05 310780 + 147 310790 Ga-79 6.57740E-05 6.86060E-05 310790 + 148 310800 Ga-80 1.95350E-05 2.93040E-05 310800 + 149 310810 Ga-81 4.56580E-05 4.56850E-05 310810 + 150 310820 Ga-82 4.07950E-06 4.08060E-06 310820 + 151 310830 Ga-83 9.31740E-07 9.31820E-07 310830 + 152 310840 Ga-84 4.59720E-08 4.59720E-08 310840 + 153 310850 Ga-85 1.26380E-09 1.26380E-09 310850 + 154 320730 Ge-73 2.95080E-12 3.78470E-06 32073.82c + 155 320731 Ge-73m 5.94120E-13 3.72910E-06 320731 + 156 320740 Ge-74 1.97860E-10 3.81840E-06 32074.82c + 157 320750 Ge-75 6.68890E-10 7.41980E-06 320750 + 158 320751 Ge-75m 5.02380E-09 3.01590E-07 320751 + 159 320760 Ge-76 2.65570E-07 2.08980E-05 32076.82c + 160 320770 Ge-77 3.18670E-06 8.78980E-06 320770 + 161 320771 Ge-77m 4.24290E-07 2.94900E-05 320771 + 162 320780 Ge-78 2.39100E-05 7.51420E-05 320780 + 163 320790 Ge-79 9.13080E-06 8.03200E-05 320790 + 164 320791 Ge-79m 6.85780E-05 6.86810E-05 320791 + 165 320800 Ge-80 2.30590E-04 2.65330E-04 320800 + 166 320810 Ge-81 2.04940E-04 2.27230E-04 320810 + 167 320811 Ge-81m 4.12630E-05 6.06910E-05 320811 + 168 320820 Ge-82 1.71120E-04 1.74680E-04 320820 + 169 320830 Ge-83 2.97040E-04 2.97660E-04 320830 + 170 320840 Ge-84 2.11420E-04 2.11430E-04 320840 + 171 320850 Ge-85 1.21040E-05 1.21050E-05 320850 + 172 320860 Ge-86 2.54820E-06 2.54820E-06 320860 + 173 320870 Ge-87 1.82720E-08 1.82720E-08 320870 + 174 320880 Ge-88 5.94360E-10 5.94360E-10 320880 + 175 330750 As-75 3.27430E-13 7.41990E-06 33075.82c + 176 330751 As-75m 1.24000E-12 9.17180E-11 330751 + 177 330760 As-76 1.36260E-10 1.36260E-10 330760 + 178 330770 As-77 1.14970E-08 3.26880E-05 330770 + 179 330780 As-78 2.31930E-07 7.53740E-05 330780 + 180 330790 As-79 2.87000E-06 1.49120E-04 330790 + 181 330800 As-80 1.47130E-05 2.80040E-04 330800 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1.72250E-02 370920 + 261 370930 Rb-93 1.32030E-02 1.69060E-02 370930 + 262 370940 Rb-94 6.83220E-03 8.24450E-03 370940 + 263 370950 Rb-95 5.35520E-03 5.72920E-03 370950 + 264 370960 Rb-96 1.39250E-03 2.15470E-03 370960 + 265 370961 Rb-96m 1.39250E-03 1.43650E-03 370961 + 266 370970 Rb-97 1.18700E-03 1.19250E-03 370970 + 267 370980 Rb-98 8.23300E-05 8.23300E-05 370980 + 268 370981 Rb-98m 8.23300E-05 8.31800E-05 370981 + 269 370990 Rb-99 3.40290E-05 3.40290E-05 370990 + 270 371000 Rb-100 2.76700E-06 2.76700E-06 371000 + 271 371010 Rb-101 2.25270E-09 2.25270E-09 371010 + 272 380880 Sr-88 8.61800E-09 8.08630E-03 38088.82c + 273 380890 Sr-89 7.92340E-06 9.66170E-03 38089.82c + 274 380900 Sr-90 1.12690E-04 1.54570E-02 38090.82c + 275 380910 Sr-91 6.44780E-04 1.73230E-02 380910 + 276 380920 Sr-92 3.88250E-03 2.13440E-02 380920 + 277 380930 Sr-93 1.07010E-02 2.82030E-02 380930 + 278 380940 Sr-94 2.19040E-02 2.98090E-02 380940 + 279 380950 Sr-95 2.50770E-02 3.06020E-02 380950 + 280 380960 Sr-96 2.74540E-02 3.03380E-02 380960 + 281 380970 Sr-97 1.47690E-02 1.56730E-02 380970 + 282 380980 Sr-98 8.15350E-03 8.31300E-03 380980 + 283 380990 Sr-99 3.35550E-03 3.38430E-03 380990 + 284 381000 Sr-100 9.41690E-04 9.44300E-04 381000 + 285 381010 Sr-101 1.72980E-04 1.72980E-04 381010 + 286 381020 Sr-102 3.00070E-05 3.00070E-05 381020 + 287 381030 Sr-103 1.96370E-06 1.96370E-06 381030 + 288 390900 Y-90 3.85350E-10 1.54570E-02 39090.82c + 289 390901 Y-90m 6.44450E-10 6.44450E-10 390901 + 290 390910 Y-91 1.85920E-08 1.73240E-02 39091.82c + 291 390911 Y-91m 9.23380E-08 1.01920E-02 390911 + 292 390920 Y-92 2.04740E-05 2.13640E-02 390920 + 293 390930 Y-93 2.49020E-05 2.84150E-02 390930 + 294 390931 Y-93m 1.87030E-04 7.24460E-03 390931 + 295 390940 Y-94 7.18600E-04 3.05270E-02 390940 + 296 390950 Y-95 4.24890E-03 3.48510E-02 390950 + 297 390960 Y-96 3.41260E-03 3.37540E-02 390960 + 298 390961 Y-96m 7.15940E-03 7.16330E-03 390961 + 299 390970 Y-97 3.79500E-03 1.72710E-02 390970 + 300 390971 Y-97m 1.40270E-02 2.02150E-02 390971 + 301 390972 Y-97m 4.82070E-03 4.82070E-03 390972 + 302 390980 Y-98 3.47320E-03 1.17860E-02 390980 + 303 390981 Y-98m 1.68380E-02 1.68380E-02 390981 + 304 390990 Y-99 2.01160E-02 2.35080E-02 390990 + 305 391000 Y-100 4.91310E-03 5.85200E-03 391000 + 306 391001 Y-100m 4.91310E-03 4.91510E-03 391001 + 307 391010 Y-101 6.15300E-03 6.32350E-03 391010 + 308 391020 Y-102 9.07900E-04 9.22080E-04 391020 + 309 391021 Y-102m 9.07900E-04 9.22080E-04 391021 + 310 391030 Y-103 4.84310E-04 4.86270E-04 391030 + 311 391040 Y-104 5.17340E-05 5.17340E-05 391040 + 312 391050 Y-105 1.02620E-05 1.02620E-05 391050 + 313 391060 Y-106 1.26530E-09 1.26530E-09 391060 + 314 400930 Zr-93 1.18310E-06 2.84160E-02 40093.82c + 315 400940 Zr-94 2.69340E-05 3.05540E-02 40094.82c + 316 400950 Zr-95 2.16560E-04 3.50680E-02 40095.82c + 317 400960 Zr-96 1.72800E-03 4.26620E-02 40096.82c + 318 400970 Zr-97 5.43900E-03 4.43430E-02 400970 + 319 400980 Zr-98 1.86410E-02 4.70540E-02 400980 + 320 400990 Zr-99 3.11280E-02 5.42900E-02 400990 + 321 401000 Zr-100 4.33850E-02 5.40980E-02 401000 + 322 401010 Zr-101 3.43680E-02 4.07820E-02 401010 + 323 401020 Zr-102 2.68770E-02 2.86700E-02 401020 + 324 401030 Zr-103 1.18660E-02 1.23180E-02 401030 + 325 401040 Zr-104 5.33570E-03 5.38490E-03 401040 + 326 401050 Zr-105 1.32640E-03 1.33460E-03 401050 + 327 401060 Zr-106 2.92110E-04 2.92110E-04 401060 + 328 401070 Zr-107 4.12690E-05 4.12690E-05 401070 + 329 401080 Zr-108 1.40360E-08 1.40360E-08 401080 + 330 410950 Nb-95 7.56640E-07 3.50470E-02 41095.82c + 331 410951 Nb-95m 1.52350E-07 3.79010E-04 410951 + 332 410960 Nb-96 3.01820E-06 3.01820E-06 410960 + 333 410970 Nb-97 3.48490E-05 4.43850E-02 410970 + 334 410971 Nb-97m 7.01670E-06 4.21540E-02 410971 + 335 410980 Nb-98 6.01010E-05 4.71140E-02 410980 + 336 410981 Nb-98m 2.09410E-04 2.09410E-04 410981 + 337 410990 Nb-99 1.71620E-03 3.64340E-02 410990 + 338 410991 Nb-99m 3.45540E-04 2.03240E-02 410991 + 339 411000 Nb-100 9.12850E-04 5.50110E-02 411000 + 340 411001 Nb-100m 4.42550E-03 4.42550E-03 411001 + 341 411010 Nb-101 1.83480E-02 5.91300E-02 411010 + 342 411020 Nb-102 1.33610E-02 4.20300E-02 411020 + 343 411021 Nb-102m 1.33610E-02 1.33610E-02 411021 + 344 411030 Nb-103 3.34810E-02 4.57990E-02 411030 + 345 411040 Nb-104 1.05700E-02 1.59730E-02 411040 + 346 411041 Nb-104m 1.05700E-02 1.05700E-02 411041 + 347 411050 Nb-105 1.55340E-02 1.68540E-02 411050 + 348 411060 Nb-106 6.78760E-03 7.07680E-03 411060 + 349 411070 Nb-107 3.25760E-03 3.29730E-03 411070 + 350 411080 Nb-108 7.82270E-04 7.82280E-04 411080 + 351 411090 Nb-109 1.57070E-04 1.57070E-04 411090 + 352 411100 Nb-110 1.00990E-05 1.00990E-05 411100 + 353 411110 Nb-111 6.49420E-10 6.49420E-10 411110 + 354 420970 Mo-97 9.72380E-07 4.43850E-02 42097.82c + 355 420980 Mo-98 9.13700E-07 4.73240E-02 42098.82c + 356 420990 Mo-99 5.62380E-05 5.64080E-02 42099.82c + 357 421000 Mo-100 4.09260E-04 5.98460E-02 42100.82c + 358 421010 Mo-101 1.98560E-03 6.11160E-02 421010 + 359 421020 Mo-102 9.14650E-03 6.45370E-02 421020 + 360 421030 Mo-103 1.86260E-02 6.44400E-02 421030 + 361 421040 Mo-104 3.79130E-02 6.47270E-02 421040 + 362 421050 Mo-105 3.65410E-02 5.34270E-02 421050 + 363 421060 Mo-106 3.50490E-02 4.20050E-02 421060 + 364 421070 Mo-107 2.02190E-02 2.33670E-02 421070 + 365 421080 Mo-108 1.19700E-02 1.27240E-02 421080 + 366 421090 Mo-109 4.72410E-03 4.86530E-03 421090 + 367 421100 Mo-110 1.38520E-03 1.39130E-03 421100 + 368 421110 Mo-111 2.20220E-04 2.20220E-04 421110 + 369 421120 Mo-112 3.64890E-05 3.64890E-05 421120 + 370 421130 Mo-113 1.66740E-05 1.66740E-05 421130 + 371 421140 Mo-114 8.90370E-06 8.90370E-06 421140 + 372 431000 Tc-100 2.62620E-09 2.62620E-09 431000 + 373 431010 Tc-101 8.28610E-06 6.11240E-02 431010 + 374 431020 Tc-102 3.54660E-05 6.45730E-02 431020 + 375 431021 Tc-102m 3.54660E-05 3.54660E-05 431021 + 376 431030 Tc-103 4.99670E-04 6.49390E-02 431030 + 377 431040 Tc-104 1.72390E-03 6.64510E-02 431040 + 378 431050 Tc-105 6.29090E-03 5.97180E-02 431050 + 379 431060 Tc-106 1.09020E-02 5.29070E-02 431060 + 380 431070 Tc-107 2.30170E-02 4.63840E-02 431070 + 381 431080 Tc-108 2.12460E-02 3.39950E-02 431080 + 382 431090 Tc-109 1.82110E-02 2.30510E-02 431090 + 383 431100 Tc-110 9.11960E-03 1.05130E-02 431100 + 384 431110 Tc-111 4.68060E-03 4.89930E-03 431110 + 385 431120 Tc-112 1.42020E-03 1.45590E-03 431120 + 386 431130 Tc-113 5.23850E-04 5.40520E-04 431130 + 387 431140 Tc-114 1.58980E-04 1.67880E-04 431140 + 388 431150 Tc-115 4.78540E-05 4.78540E-05 431150 + 389 431160 Tc-116 1.67640E-05 1.67640E-05 431160 + 390 431170 Tc-117 6.76600E-06 6.76600E-06 431170 + 391 441020 Ru-102 1.07290E-06 6.46090E-02 44102.82c + 392 441030 Ru-103 7.75730E-07 6.49420E-02 44103.82c + 393 441031 Ru-103m 2.17050E-06 2.17050E-06 441031 + 394 441040 Ru-104 6.17920E-05 6.65130E-02 44104.82c + 395 441050 Ru-105 2.44940E-04 5.99630E-02 44105.82c + 396 441060 Ru-106 1.26070E-03 5.41680E-02 44106.82c + 397 441070 Ru-107 3.63200E-03 5.00160E-02 441070 + 398 441080 Ru-108 9.70750E-03 4.37210E-02 441080 + 399 441090 Ru-109 1.29010E-02 3.59370E-02 441090 + 400 441100 Ru-110 1.46870E-02 2.51960E-02 441100 + 401 441110 Ru-111 9.30110E-03 1.42220E-02 441110 + 402 441120 Ru-112 5.75270E-03 7.22560E-03 441120 + 403 441130 Ru-113 1.13510E-03 2.21520E-03 441130 + 404 441131 Ru-113m 1.13510E-03 1.13510E-03 441131 + 405 441140 Ru-114 1.04020E-03 1.20400E-03 441140 + 406 441150 Ru-115 3.14220E-04 3.57260E-04 441150 + 407 441160 Ru-116 8.55910E-05 1.00310E-04 441160 + 408 441170 Ru-117 2.47760E-05 3.15420E-05 441170 + 409 441180 Ru-118 4.78480E-06 4.78480E-06 441180 + 410 451050 Rh-105 1.51020E-06 5.99650E-02 45105.82c + 411 451051 Rh-105m 2.01080E-07 1.70220E-02 451051 + 412 451060 Rh-106 1.10040E-06 5.41690E-02 451060 + 413 451061 Rh-106m 2.99930E-06 2.99930E-06 451061 + 414 451070 Rh-107 4.24100E-05 5.00580E-02 451070 + 415 451080 Rh-108 4.26910E-05 4.37640E-02 451080 + 416 451081 Rh-108m 1.48750E-04 1.48750E-04 451081 + 417 451090 Rh-109 6.40640E-04 3.65780E-02 451090 + 418 451100 Rh-110 1.38910E-03 2.65850E-02 451100 + 419 451101 Rh-110m 3.27010E-05 3.27010E-05 451101 + 420 451110 Rh-111 2.58440E-03 1.68070E-02 451110 + 421 451120 Rh-112 1.11020E-03 8.33580E-03 451120 + 422 451121 Rh-112m 1.11020E-03 1.11020E-03 451121 + 423 451130 Rh-113 1.86310E-03 4.64580E-03 451130 + 424 451140 Rh-114 3.50130E-04 1.55490E-03 451140 + 425 451141 Rh-114m 3.50130E-04 3.50130E-04 451141 + 426 451150 Rh-115 2.53400E-04 6.10930E-04 451150 + 427 451160 Rh-116 1.80350E-05 1.17900E-04 451160 + 428 451161 Rh-116m 4.91580E-05 4.91580E-05 451161 + 429 451170 Rh-117 2.48180E-05 5.59100E-05 451170 + 430 451180 Rh-118 2.39340E-06 6.98160E-06 451180 + 431 451190 Rh-119 3.77530E-09 3.77530E-09 451190 + 432 451200 Rh-120 5.79270E-11 5.79270E-11 451200 + 433 451210 Rh-121 2.40210E-12 2.40210E-12 451210 + 434 451220 Rh-122 2.40870E-08 2.40870E-08 451220 + 435 461080 Pd-108 1.89400E-06 4.39150E-02 46108.82c + 436 461090 Pd-109 3.98820E-06 3.65910E-02 461090 + 437 461091 Pd-109m 8.76580E-06 1.82980E-02 461091 + 438 461100 Pd-110 5.44040E-05 2.66720E-02 46110.82c + 439 461110 Pd-111 4.31710E-05 1.69010E-02 461110 + 440 461111 Pd-111m 9.48890E-05 1.62120E-04 461111 + 441 461120 Pd-112 2.25960E-04 9.67190E-03 461120 + 442 461130 Pd-113 6.93740E-05 4.90930E-03 461130 + 443 461131 Pd-113m 1.94110E-04 1.94110E-04 461131 + 444 461140 Pd-114 2.44050E-04 2.14910E-03 461140 + 445 461150 Pd-115 3.26990E-05 5.67770E-04 461150 + 446 461151 Pd-115m 7.18710E-05 1.60580E-04 461151 + 447 461160 Pd-116 6.74220E-05 2.34480E-04 461160 + 448 461170 Pd-117 1.13070E-05 9.22740E-05 461170 + 449 461171 Pd-117m 2.48530E-05 2.48530E-05 461171 + 450 461180 Pd-118 1.19700E-05 1.87480E-05 461180 + 451 461190 Pd-119 1.56180E-05 1.56220E-05 461190 + 452 461200 Pd-120 2.54130E-06 2.54130E-06 461200 + 453 461210 Pd-121 2.20130E-06 2.20130E-06 461210 + 454 461220 Pd-122 5.53640E-06 5.56050E-06 461220 + 455 461230 Pd-123 2.12960E-06 2.12960E-06 461230 + 456 461240 Pd-124 8.95490E-07 8.95490E-07 461240 + 457 471100 Ag-110 1.67460E-10 1.73660E-10 471100 + 458 471101 Ag-110m 4.56450E-10 4.56450E-10 47510.82c + 459 471110 Ag-111 3.96810E-09 1.68610E-02 47111.82c + 460 471111 Ag-111m 2.98030E-08 1.68130E-02 471111 + 461 471120 Ag-112 4.22570E-07 9.67230E-03 471120 + 462 471130 Ag-113 5.88820E-07 3.22040E-03 471130 + 463 471131 Ag-113m 4.42240E-06 4.70550E-03 471131 + 464 471140 Ag-114 9.14780E-07 2.15440E-03 471140 + 465 471141 Ag-114m 4.43480E-06 4.43480E-06 471141 + 466 471150 Ag-115 4.51380E-07 4.78850E-04 471150 + 467 471151 Ag-115m 3.39010E-06 3.04420E-04 471151 + 468 471160 Ag-116 2.81900E-06 2.37760E-04 471160 + 469 471161 Ag-116m 7.68400E-06 7.68400E-06 471161 + 470 471170 Ag-117 1.32730E-06 5.08310E-05 471170 + 471 471171 Ag-117m 9.96870E-06 5.61060E-05 471171 + 472 471180 Ag-118 4.09370E-07 1.83900E-05 471180 + 473 471181 Ag-118m 1.98460E-06 4.66480E-06 471181 + 474 471190 Ag-119 1.37730E-06 9.18820E-06 471190 + 475 471191 Ag-119m 1.03450E-05 1.81560E-05 471191 + 476 471200 Ag-120 3.80370E-06 7.90420E-06 471200 + 477 471201 Ag-120m 6.36130E-06 7.63190E-06 471201 + 478 471210 Ag-121 6.60350E-06 8.79880E-06 471210 + 479 471220 Ag-122 1.18070E-06 6.74120E-06 471220 + 480 471221 Ag-122m 1.27290E-06 1.27290E-06 471221 + 481 471230 Ag-123 1.49280E-05 1.70580E-05 471230 + 482 471240 Ag-124 4.65290E-06 8.05670E-06 471240 + 483 471241 Ag-124m 5.01650E-06 5.01650E-06 471241 + 484 471250 Ag-125 1.33880E-05 1.33880E-05 471250 + 485 471260 Ag-126 1.68970E-05 1.68970E-05 471260 + 486 471270 Ag-127 5.68480E-06 5.68480E-06 471270 + 487 471280 Ag-128 3.24670E-07 3.24670E-07 471280 + 488 471290 Ag-129 4.14030E-08 4.14030E-08 471290 + 489 471300 Ag-130 5.50880E-10 5.50880E-10 471300 + 490 481130 Cd-113 1.53130E-10 4.85870E-03 48113.82c + 491 481131 Cd-113m 5.79920E-10 5.56770E-05 481131 + 492 481140 Cd-114 2.46270E-08 2.15450E-03 48114.82c + 493 481150 Cd-115 2.83330E-08 6.84780E-04 481150 + 494 481151 Cd-115m 1.07300E-07 3.47020E-05 48515.82c + 495 481160 Cd-116 1.07960E-06 2.46070E-04 48116.82c + 496 481170 Cd-117 4.71590E-07 8.23730E-05 481170 + 497 481171 Cd-117m 1.78590E-06 2.34550E-05 481171 + 498 481180 Cd-118 2.39430E-06 2.35360E-05 481180 + 499 481190 Cd-119 2.12030E-06 2.48700E-05 481190 + 500 481191 Cd-119m 5.93240E-06 1.05270E-05 481191 + 501 481200 Cd-120 7.62690E-06 2.03390E-05 481200 + 502 481210 Cd-121 6.37740E-06 1.42570E-05 481210 + 503 481211 Cd-121m 1.78440E-05 1.87630E-05 481211 + 504 481220 Cd-122 2.45470E-05 3.25610E-05 481220 + 505 481230 Cd-123 9.43880E-06 2.33990E-05 481230 + 506 481231 Cd-123m 2.64090E-05 2.95150E-05 481231 + 507 481240 Cd-124 7.71800E-05 8.77370E-05 481240 + 508 481250 Cd-125 5.85030E-05 6.51970E-05 481250 + 509 481251 Cd-125m 1.63690E-04 1.70380E-04 481251 + 510 481260 Cd-126 5.05810E-04 5.22710E-04 481260 + 511 481270 Cd-127 3.88420E-04 3.94110E-04 481270 + 512 481280 Cd-128 2.11370E-04 2.11690E-04 481280 + 513 481290 Cd-129 4.10480E-05 4.10690E-05 481290 + 514 481291 Cd-129m 1.14850E-04 1.14870E-04 481291 + 515 481300 Cd-130 4.86920E-05 4.86930E-05 481300 + 516 481310 Cd-131 1.04640E-06 1.04640E-06 481310 + 517 481320 Cd-132 2.24440E-08 2.24440E-08 481320 + 518 491150 In-115 2.19660E-11 6.85240E-04 49115.82c + 519 491151 In-115m 4.42280E-12 6.84780E-04 491151 + 520 491160 In-116 4.90760E-11 4.90760E-11 491160 + 521 491161 In-116m 7.92470E-11 1.70990E-10 491161 + 522 491162 In-116m 9.17470E-11 9.17470E-11 491162 + 523 491170 In-117 4.53350E-09 6.57110E-05 491170 + 524 491171 In-117m 9.12800E-10 7.58460E-05 491171 + 525 491180 In-118 3.45050E-09 2.35400E-05 491180 + 526 491181 In-118m 5.57180E-09 1.19320E-08 491181 + 527 491182 In-118m 6.45070E-09 6.45070E-09 491182 + 528 491190 In-119 2.62420E-07 1.44450E-05 491190 + 529 491191 In-119m 5.28380E-08 2.25280E-05 491191 + 530 491200 In-120 3.09920E-07 2.06490E-05 491200 + 531 491201 In-120m 3.09920E-07 3.09920E-07 491201 + 532 491202 In-120m 3.09920E-07 3.09920E-07 491202 + 533 491210 In-121 7.38680E-06 3.10830E-05 491210 + 534 491211 In-121m 1.48730E-06 1.09430E-05 491211 + 535 491220 In-122 9.18360E-07 3.34790E-05 491220 + 536 491221 In-122m 7.67920E-07 7.67920E-07 491221 + 537 491222 In-122m 7.67920E-07 7.67920E-07 491222 + 538 491230 In-123 2.24120E-05 5.88150E-05 491230 + 539 491231 In-123m 4.51260E-06 2.10240E-05 491231 + 540 491240 In-124 1.24210E-05 1.00160E-04 491240 + 541 491241 In-124m 1.33910E-05 1.33910E-05 491241 + 542 491250 In-125 1.31180E-04 3.32770E-04 491250 + 543 491251 In-125m 2.64120E-05 6.04030E-05 491251 + 544 491260 In-126 2.73970E-04 7.96680E-04 491260 + 545 491261 In-126m 2.95380E-04 2.95380E-04 491261 + 546 491270 In-127 1.28940E-03 1.28940E-03 491270 + 547 491271 In-127m 2.59610E-04 6.53720E-04 491271 + 548 491280 In-128 5.63380E-04 9.95670E-04 491280 + 549 491281 In-128m 2.20590E-04 4.32290E-04 491281 + 550 491282 In-128m 8.45230E-04 8.45230E-04 491282 + 551 491290 In-129 2.46270E-03 2.57850E-03 491290 + 552 491291 In-129m 4.95860E-04 5.37780E-04 491291 + 553 491300 In-130 4.18150E-04 4.65170E-04 491300 + 554 491301 In-130m 6.08850E-04 6.08850E-04 491301 + 555 491302 In-130m 8.48110E-04 8.48110E-04 491302 + 556 491310 In-131 2.84210E-04 2.88120E-04 491310 + 557 491311 In-131m 2.84210E-04 2.84230E-04 491311 + 558 491312 In-131m 2.84210E-04 2.84210E-04 491312 + 559 491320 In-132 1.38140E-04 1.38150E-04 491320 + 560 491330 In-133 1.78600E-05 2.14560E-05 491330 + 561 491331 In-133m 3.59600E-06 3.59600E-06 491331 + 562 491340 In-134 1.73140E-07 1.73140E-07 491340 + 563 491350 In-135 5.05780E-09 5.05780E-09 491350 + 564 501180 Sn-118 3.73120E-12 2.35520E-05 50118.82c + 565 501190 Sn-119 3.05600E-11 3.57120E-05 50119.82c + 566 501191 Sn-119m 1.15730E-10 1.30500E-05 501191 + 567 501200 Sn-120 4.80650E-09 2.12740E-05 50120.82c + 568 501210 Sn-121 1.97080E-08 4.11680E-05 501210 + 569 501211 Sn-121m 5.51410E-08 3.57630E-06 501211 + 570 501220 Sn-122 1.26220E-11 3.50150E-05 50122.82c + 571 501230 Sn-123 2.20220E-06 6.68640E-06 50123.82c + 572 501231 Sn-123m 7.87080E-07 7.61420E-05 501231 + 573 501240 Sn-124 5.18170E-05 1.65370E-04 50124.82c + 574 501250 Sn-125 9.71930E-05 1.53400E-04 50125.82c + 575 501251 Sn-125m 3.47370E-05 3.71700E-04 501251 + 576 501260 Sn-126 5.91240E-04 1.68780E-03 50126.82c + 577 501270 Sn-127 9.76860E-04 1.47940E-03 501270 + 578 501271 Sn-127m 3.49140E-04 1.78520E-03 501271 + 579 501280 Sn-128 9.75850E-04 5.47670E-03 501280 + 580 501281 Sn-128m 2.65990E-03 3.50520E-03 501281 + 581 501290 Sn-129 2.61030E-03 5.45220E-03 501290 + 582 501291 Sn-129m 7.30340E-03 7.57790E-03 501291 + 583 501300 Sn-130 4.83040E-03 6.01190E-03 501300 + 584 501301 Sn-130m 1.31670E-02 1.39130E-02 501301 + 585 501310 Sn-131 3.54430E-03 4.09560E-03 501310 + 586 501311 Sn-131m 9.91670E-03 1.02130E-02 501311 + 587 501320 Sn-132 1.08680E-02 1.10240E-02 501320 + 588 501330 Sn-133 2.67770E-03 2.68100E-03 501330 + 589 501340 Sn-134 5.59280E-04 5.59330E-04 501340 + 590 501350 Sn-135 6.45910E-05 6.45960E-05 501350 + 591 501360 Sn-136 1.18890E-05 1.18890E-05 501360 + 592 501370 Sn-137 3.03870E-08 3.03870E-08 501370 + 593 511210 Sb-121 3.48300E-11 4.19690E-05 51121.82c + 594 511240 Sb-124 1.21040E-12 3.11520E-12 51124.82c + 595 511241 Sb-124m 9.76420E-13 2.53970E-12 511241 + 596 511242 Sb-124m 1.56330E-12 1.56330E-12 511242 + 597 511250 Sb-125 2.35080E-05 5.48610E-04 51125.82c + 598 511260 Sb-126 1.84080E-05 2.20130E-05 51126.82c + 599 511261 Sb-126m 1.14980E-05 2.57510E-05 511261 + 600 511262 Sb-126m 1.42530E-05 1.42530E-05 511262 + 601 511270 Sb-127 1.48870E-04 3.41350E-03 511270 + 602 511280 Sb-128 9.04880E-05 5.57170E-03 511280 + 603 511281 Sb-128m 1.26560E-04 1.26560E-04 511281 + 604 511290 Sb-129 1.04120E-03 1.09660E-02 511290 + 605 511291 Sb-129m 7.70520E-04 4.55940E-03 511291 + 606 511300 Sb-130 2.25270E-03 1.52210E-02 511300 + 607 511301 Sb-130m 2.25270E-03 9.20910E-03 511301 + 608 511310 Sb-131 1.48940E-02 2.92030E-02 511310 + 609 511320 Sb-132 1.27730E-02 2.37970E-02 511320 + 610 511321 Sb-132m 1.13090E-02 1.13090E-02 511321 + 611 511330 Sb-133 3.35190E-02 3.62950E-02 511330 + 612 511340 Sb-134 2.96660E-03 3.43760E-03 511340 + 613 511341 Sb-134m 8.08640E-03 8.09320E-03 511341 + 614 511350 Sb-135 5.89680E-03 5.95140E-03 511350 + 615 511360 Sb-136 1.44470E-03 1.45300E-03 511360 + 616 511370 Sb-137 2.74300E-04 2.74310E-04 511370 + 617 511380 Sb-138 2.60110E-05 2.60110E-05 511380 + 618 511390 Sb-139 4.03280E-06 4.03280E-06 511390 + 619 521270 Te-127 1.91260E-06 3.40710E-03 521270 + 620 521271 Te-127m 5.35140E-06 5.67870E-04 52527.82c + 621 521280 Te-128 1.14140E-05 5.70520E-03 52128.82c + 622 521290 Te-129 1.10390E-05 1.27980E-02 521290 + 623 521291 Te-129m 3.08880E-05 5.63560E-03 52529.82c + 624 521300 Te-130 3.16710E-04 2.47470E-02 52130.82c + 625 521310 Te-131 3.32230E-04 2.78830E-02 521310 + 626 521311 Te-131m 9.29570E-04 3.26760E-03 521311 + 627 521320 Te-132 9.20790E-03 4.43140E-02 52132.82c + 628 521330 Te-133 8.09730E-03 4.31850E-02 521330 + 629 521331 Te-133m 2.26560E-02 2.89340E-02 521331 + 630 521340 Te-134 5.75420E-02 7.00040E-02 521340 + 631 521350 Te-135 3.86920E-02 4.39460E-02 521350 + 632 521360 Te-136 2.69080E-02 2.82540E-02 521360 + 633 521370 Te-137 9.08500E-03 9.22490E-03 521370 + 634 521380 Te-138 3.83220E-03 3.85820E-03 521380 + 635 521390 Te-139 4.92150E-04 4.96180E-04 521390 + 636 521400 Te-140 1.48330E-04 1.48330E-04 521400 + 637 521410 Te-141 9.29850E-06 9.29850E-06 521410 + 638 521420 Te-142 1.90630E-06 1.90630E-06 521420 + 639 531290 I-129 5.24070E-10 1.48840E-02 53129.82c + 640 531300 I-130 9.92930E-07 1.29890E-06 53130.82c + 641 531301 I-130m 3.64270E-07 3.64270E-07 531301 + 642 531310 I-131 1.15160E-05 3.04760E-02 53131.82c + 643 531320 I-132 3.07830E-05 4.43680E-02 531320 + 644 531321 I-132m 2.72540E-05 2.72540E-05 531321 + 645 531330 I-133 4.27130E-04 6.77990E-02 531330 + 646 531331 I-133m 3.16090E-04 3.16090E-04 531331 + 647 531340 I-134 1.62810E-03 7.30400E-02 531340 + 648 531341 I-134m 1.44150E-03 1.44150E-03 531341 + 649 531350 I-135 2.30760E-02 6.70220E-02 53135.82c + 650 531360 I-136 8.71250E-03 3.71050E-02 531360 + 651 531361 I-136m 2.37480E-02 2.38860E-02 531361 + 652 531370 I-137 3.52270E-02 4.44190E-02 531370 + 653 531380 I-138 1.66940E-02 2.03090E-02 531380 + 654 531390 I-139 1.54520E-02 1.59480E-02 531390 + 655 531400 I-140 4.74320E-03 4.89150E-03 531400 + 656 531410 I-141 2.11580E-03 2.12510E-03 531410 + 657 531420 I-142 2.32250E-04 2.34160E-04 531420 + 658 531430 I-143 4.74330E-05 4.74330E-05 531430 + 659 531440 I-144 1.76280E-06 1.76280E-06 531440 + 660 541310 Xe-131 2.75570E-07 3.04770E-02 54131.82c + 661 541311 Xe-131m 7.71030E-07 3.31800E-04 541311 + 662 541320 Xe-132 3.68940E-09 4.43720E-02 54132.82c + 663 541321 Xe-132m 4.94290E-09 4.94290E-09 541321 + 664 541330 Xe-133 5.95770E-07 6.78010E-02 54133.82c + 665 541331 Xe-133m 1.66690E-06 1.93150E-03 541331 + 666 541340 Xe-134 1.83120E-05 7.31420E-02 54134.82c + 667 541341 Xe-134m 4.99160E-05 8.30700E-05 541341 + 668 541350 Xe-135 1.80490E-04 6.76380E-02 54135.82c + 669 541351 Xe-135m 5.05010E-04 1.15690E-02 541351 + 670 541360 Xe-136 7.35070E-03 7.12290E-02 54136.82c + 671 541370 Xe-137 1.74830E-02 6.00910E-02 541370 + 672 541380 Xe-138 3.93420E-02 6.01380E-02 541380 + 673 541390 Xe-139 3.72200E-02 5.20600E-02 541390 + 674 541400 Xe-140 3.97440E-02 4.46270E-02 541400 + 675 541410 Xe-141 2.26510E-02 2.43880E-02 541410 + 676 541420 Xe-142 1.17170E-02 1.19120E-02 541420 + 677 541430 Xe-143 3.26790E-03 3.29710E-03 541430 + 678 541440 Xe-144 9.74990E-04 9.76050E-04 541440 + 679 541450 Xe-145 1.42580E-04 1.42580E-04 541450 + 680 541460 Xe-146 2.30420E-05 2.30420E-05 541460 + 681 541470 Xe-147 2.36550E-08 2.36550E-08 541470 + 682 551350 Cs-135 1.06270E-06 6.77090E-02 55135.82c + 683 551351 Cs-135m 7.86420E-07 7.86420E-07 551351 + 684 551360 Cs-136 9.07240E-06 1.23160E-05 55136.82c + 685 551361 Cs-136m 6.48650E-06 6.48650E-06 551361 + 686 551370 Cs-137 2.76210E-04 6.03670E-02 55137.82c + 687 551380 Cs-138 4.95070E-04 6.13030E-02 551380 + 688 551381 Cs-138m 8.27930E-04 8.27930E-04 551381 + 689 551390 Cs-139 5.64370E-03 5.77040E-02 551390 + 690 551400 Cs-140 9.64030E-03 5.42780E-02 551400 + 691 551410 Cs-141 2.74250E-02 5.18460E-02 551410 + 692 551420 Cs-142 2.04430E-02 3.23450E-02 551420 + 693 551430 Cs-143 1.82100E-02 2.15030E-02 551430 + 694 551440 Cs-144 3.95930E-03 6.89100E-03 551440 + 695 551441 Cs-144m 3.95930E-03 3.96280E-03 551441 + 696 551450 Cs-145 4.72840E-03 4.86540E-03 551450 + 697 551460 Cs-146 1.21440E-03 1.23580E-03 551460 + 698 551470 Cs-147 3.11730E-04 3.11750E-04 551470 + 699 551480 Cs-148 2.61520E-05 2.61520E-05 551480 + 700 551490 Cs-149 4.83620E-06 4.83620E-06 551490 + 701 551500 Cs-150 2.30010E-09 2.30010E-09 551500 + 702 561370 Ba-137 4.48950E-07 6.03690E-02 56137.82c + 703 561371 Ba-137m 1.25620E-06 5.69880E-02 561371 + 704 561380 Ba-138 2.88590E-05 6.14900E-02 56138.82c + 705 561390 Ba-139 1.98030E-04 5.79020E-02 561390 + 706 561400 Ba-140 1.20540E-03 5.54830E-02 56140.82c + 707 561410 Ba-141 3.84970E-03 5.56950E-02 561410 + 708 561420 Ba-142 1.27090E-02 4.54060E-02 561420 + 709 561430 Ba-143 2.26420E-02 4.40130E-02 561430 + 710 561440 Ba-144 3.06690E-02 4.00170E-02 561440 + 711 561450 Ba-145 2.09020E-02 2.52470E-02 561450 + 712 561460 Ba-146 1.58530E-02 1.70020E-02 561460 + 713 561470 Ba-147 5.75930E-03 5.98880E-03 561470 + 714 561480 Ba-148 2.71220E-03 2.73180E-03 561480 + 715 561490 Ba-149 5.18300E-04 5.23140E-04 561490 + 716 561500 Ba-150 1.47170E-04 1.47170E-04 561500 + 717 561510 Ba-151 1.10440E-05 1.10440E-05 561510 + 718 561520 Ba-152 1.80900E-08 1.80900E-08 561520 + 719 561530 Ba-153 1.59030E-10 1.59030E-10 561530 + 720 571400 La-140 2.95720E-06 5.54860E-02 57140.82c + 721 571410 La-141 1.16330E-05 5.57070E-02 571410 + 722 571420 La-142 8.61880E-05 4.54920E-02 571420 + 723 571430 La-143 5.92050E-04 4.46050E-02 571430 + 724 571440 La-144 2.01940E-03 4.20360E-02 571440 + 725 571450 La-145 7.03370E-03 3.22810E-02 571450 + 726 571460 La-146 3.04320E-03 2.00450E-02 571460 + 727 571461 La-146m 6.38430E-03 6.38430E-03 571461 + 728 571470 La-147 1.27650E-02 1.87650E-02 571470 + 729 571480 La-148 7.03240E-03 9.75550E-03 571480 + 730 571490 La-149 4.83390E-03 5.35480E-03 571490 + 731 571500 La-150 1.91560E-03 2.06280E-03 571500 + 732 571510 La-151 7.61030E-04 7.72070E-04 571510 + 733 571520 La-152 1.40410E-04 1.40430E-04 571520 + 734 571530 La-153 2.53590E-05 2.53590E-05 571530 + 735 571540 La-154 3.98870E-08 3.98870E-08 571540 + 736 571550 La-155 1.33210E-09 1.33210E-09 571550 + 737 581420 Ce-142 9.53290E-07 4.54930E-02 58142.82c + 738 581430 Ce-143 5.82010E-06 4.46110E-02 58143.82c + 739 581440 Ce-144 6.29730E-05 4.20990E-02 58144.82c + 740 581450 Ce-145 3.71280E-04 3.26520E-02 581450 + 741 581460 Ce-146 1.89270E-03 2.83220E-02 581460 + 742 581470 Ce-147 4.33910E-03 2.31040E-02 581470 + 743 581480 Ce-148 9.77640E-03 1.96070E-02 581480 + 744 581490 Ce-149 9.55740E-03 1.48930E-02 581490 + 745 581500 Ce-150 1.06690E-02 1.26760E-02 581500 + 746 581510 Ce-151 5.20160E-03 5.98220E-03 581510 + 747 581520 Ce-152 2.93400E-03 3.06600E-03 581520 + 748 581530 Ce-153 8.65000E-04 8.90360E-04 581530 + 749 581540 Ce-154 2.41830E-04 2.41870E-04 581540 + 750 581550 Ce-155 3.93040E-05 3.93050E-05 581550 + 751 581560 Ce-156 6.85130E-06 6.85130E-06 581560 + 752 581570 Ce-157 2.26770E-09 2.26770E-09 581570 + 753 591450 Pr-145 1.88310E-08 3.26520E-02 591450 + 754 591460 Pr-146 3.14610E-06 2.83260E-02 591460 + 755 591470 Pr-147 3.09990E-05 2.31350E-02 591470 + 756 591480 Pr-148 2.87110E-05 1.96360E-02 591480 + 757 591481 Pr-148m 1.39190E-04 1.39190E-04 591481 + 758 591490 Pr-149 5.77130E-04 1.54700E-02 591490 + 759 591500 Pr-150 1.48060E-03 1.41570E-02 591500 + 760 591510 Pr-151 3.39060E-03 9.37270E-03 591510 + 761 591520 Pr-152 3.02450E-03 6.09600E-03 591520 + 762 591530 Pr-153 2.98960E-03 3.87600E-03 591530 + 763 591540 Pr-154 9.84600E-04 1.22490E-03 591540 + 764 591550 Pr-155 7.31060E-04 7.70360E-04 591550 + 765 591560 Pr-156 1.03900E-04 1.10750E-04 591560 + 766 591570 Pr-157 2.57550E-05 2.57570E-05 591570 + 767 591580 Pr-158 2.35450E-06 2.35450E-06 591580 + 768 591590 Pr-159 1.18720E-08 1.18720E-08 591590 + 769 601470 Nd-147 1.15390E-09 2.31350E-02 60147.82c + 770 601480 Nd-148 9.70770E-07 1.97760E-02 60148.82c + 771 601490 Nd-149 2.23690E-05 1.54920E-02 601490 + 772 601500 Nd-150 1.34690E-04 1.42910E-02 60150.82c + 773 601510 Nd-151 4.81100E-04 9.85390E-03 601510 + 774 601520 Nd-152 1.53270E-03 7.62870E-03 601520 + 775 601530 Nd-153 2.51320E-03 6.38920E-03 601530 + 776 601540 Nd-154 2.88730E-03 4.11220E-03 601540 + 777 601550 Nd-155 2.37920E-03 3.15260E-03 601550 + 778 601560 Nd-156 1.36150E-03 1.47090E-03 601560 + 779 601570 Nd-157 3.82890E-04 4.07000E-04 601570 + 780 601580 Nd-158 1.53390E-04 1.55740E-04 601580 + 781 601590 Nd-159 1.95680E-05 1.95800E-05 601590 + 782 601600 Nd-160 2.12770E-06 2.12770E-06 601600 + 783 601610 Nd-161 1.01440E-08 1.01440E-08 601610 + 784 611500 Pm-150 2.40000E-06 2.40000E-06 611500 + 785 611510 Pm-151 1.38250E-06 9.85520E-03 61151.82c + 786 611520 Pm-152 2.01370E-06 7.63070E-03 611520 + 787 611521 Pm-152m 4.23350E-06 4.23350E-06 611521 + 788 611522 Pm-152m 5.53000E-06 5.53000E-06 611522 + 789 611530 Pm-153 8.12800E-05 6.47040E-03 611530 + 790 611540 Pm-154 6.89850E-05 4.18120E-03 611540 + 791 611541 Pm-154m 6.89850E-05 6.89850E-05 611541 + 792 611550 Pm-155 4.61700E-04 3.61430E-03 611550 + 793 611560 Pm-156 5.84600E-04 2.05550E-03 611560 + 794 611570 Pm-157 5.13330E-04 9.20340E-04 611570 + 795 611580 Pm-158 3.21140E-04 4.76920E-04 611580 + 796 611590 Pm-159 1.95460E-04 2.15010E-04 611590 + 797 611600 Pm-160 4.46290E-05 4.67370E-05 611600 + 798 611610 Pm-161 1.43530E-05 1.43630E-05 611610 + 799 611620 Pm-162 2.02580E-06 2.02580E-06 611620 + 800 611630 Pm-163 1.95860E-08 1.95860E-08 611630 + 801 621520 Sm-152 3.11890E-10 7.64050E-03 62152.82c + 802 621530 Sm-153 5.15200E-07 6.47240E-03 62153.82c + 803 621531 Sm-153m 1.44150E-06 1.44150E-06 621531 + 804 621540 Sm-154 8.84670E-06 4.25910E-03 62154.82c + 805 621550 Sm-155 5.46130E-05 3.66890E-03 621550 + 806 621560 Sm-156 1.46140E-04 2.20160E-03 621560 + 807 621570 Sm-157 1.90180E-04 1.11050E-03 621570 + 808 621580 Sm-158 2.80820E-04 7.57780E-04 621580 + 809 621590 Sm-159 3.13240E-04 5.28340E-04 621590 + 810 621600 Sm-160 1.74640E-04 2.21250E-04 621600 + 811 621610 Sm-161 5.12560E-05 6.56190E-05 621610 + 812 621620 Sm-162 4.65480E-05 4.85740E-05 621620 + 813 621630 Sm-163 5.65530E-06 5.67490E-06 621630 + 814 621640 Sm-164 2.33800E-07 2.33800E-07 621640 + 815 621650 Sm-165 2.41410E-09 2.41410E-09 621650 + 816 631550 Eu-155 9.32480E-10 3.66890E-03 63155.82c + 817 631560 Eu-156 1.68340E-08 2.20160E-03 63156.82c + 818 631570 Eu-157 7.05490E-06 1.11760E-03 63157.82c + 819 631580 Eu-158 1.17860E-05 7.69570E-04 631580 + 820 631590 Eu-159 2.40060E-05 5.52340E-04 631590 + 821 631600 Eu-160 2.34340E-05 2.44690E-04 631600 + 822 631610 Eu-161 3.90210E-05 1.04640E-04 631610 + 823 631620 Eu-162 2.43230E-05 7.28970E-05 631620 + 824 631630 Eu-163 1.50840E-05 2.07590E-05 631630 + 825 631640 Eu-164 1.77950E-06 2.01330E-06 631640 + 826 631650 Eu-165 3.21900E-07 3.24310E-07 631650 + 827 631660 Eu-166 5.59450E-08 5.59450E-08 631660 + 828 631670 Eu-167 3.37510E-08 3.37510E-08 631670 + 829 641570 Gd-157 2.73220E-11 1.11760E-03 64157.82c + 830 641580 Gd-158 1.31660E-09 7.69570E-04 64158.82c + 831 641590 Gd-159 2.08230E-08 5.52370E-04 641590 + 832 641600 Gd-160 2.12870E-06 2.46810E-04 64160.82c + 833 641610 Gd-161 1.23210E-05 1.16960E-04 641610 + 834 641620 Gd-162 1.41940E-05 8.70910E-05 641620 + 835 641630 Gd-163 9.43220E-06 3.01910E-05 641630 + 836 641640 Gd-164 7.11890E-06 9.13220E-06 641640 + 837 641650 Gd-165 1.31160E-06 1.63590E-06 641650 + 838 641660 Gd-166 1.39300E-06 1.44890E-06 641660 + 839 641670 Gd-167 1.73300E-06 1.76680E-06 641670 + 840 641680 Gd-168 1.83920E-07 1.83920E-07 641680 + 841 641690 Gd-169 1.21910E-08 1.21910E-08 641690 + 842 651600 Tb-160 2.81350E-11 2.81350E-11 65160.82c + 843 651610 Tb-161 1.00800E-09 1.16960E-04 651610 + 844 651620 Tb-162 1.27320E-08 8.71040E-05 651620 + 845 651630 Tb-163 1.05680E-07 3.02970E-05 651630 + 846 651640 Tb-164 1.65120E-07 9.29730E-06 651640 + 847 651650 Tb-165 1.88670E-07 1.82460E-06 651650 + 848 651660 Tb-166 3.61550E-07 1.81050E-06 651660 + 849 651670 Tb-167 1.73320E-06 3.49990E-06 651670 + 850 651680 Tb-168 6.24230E-07 8.08150E-07 651680 + 851 651690 Tb-169 3.71200E-07 3.83390E-07 651690 + 852 651700 Tb-170 5.38220E-08 5.38220E-08 651700 + 853 651710 Tb-171 1.54720E-08 1.54720E-08 651710 + 854 661630 Dy-163 2.21070E-11 3.02970E-05 66163.82c + 855 661640 Dy-164 3.94600E-10 9.29770E-06 66164.82c + 856 661650 Dy-165 6.65910E-10 1.82530E-06 661650 + 857 661651 Dy-165m 8.86620E-11 8.86620E-11 661651 + 858 661660 Dy-166 1.47690E-08 1.82530E-06 661660 + 859 661670 Dy-167 1.50960E-07 3.65090E-06 661670 + 860 661680 Dy-168 3.19390E-07 1.12750E-06 661680 + 861 661690 Dy-169 2.37390E-07 6.20780E-07 661690 + 862 661700 Dy-170 2.78060E-07 3.31880E-07 661700 + 863 661710 Dy-171 1.05590E-07 1.21060E-07 661710 + 864 661720 Dy-172 5.48480E-08 5.48480E-08 661720 + 865 661730 Dy-173 6.34000E-09 6.34000E-09 661730 + 866 671660 Ho-166 1.44010E-12 1.82530E-06 671660 + 867 671661 Ho-166m 3.92530E-12 3.92530E-12 671661 + 868 671670 Ho-167 6.09960E-10 3.65150E-06 671670 + 869 671680 Ho-168 7.88510E-10 1.12960E-06 671680 + 870 671681 Ho-168m 1.31870E-09 1.31870E-09 671681 + 871 671690 Ho-169 1.54530E-08 6.36230E-07 671690 + 872 671700 Ho-170 1.84700E-08 1.84700E-08 671700 + 873 671701 Ho-170m 6.77600E-09 3.38660E-07 671701 + 874 671710 Ho-171 7.99000E-08 2.00960E-07 671710 + 875 671720 Ho-172 5.13770E-08 1.06220E-07 671720 + 876 671730 Ho-173 4.89520E-08 5.52920E-08 671730 + 877 671740 Ho-174 1.39970E-08 1.39970E-08 671740 + 878 671750 Ho-175 6.38240E-09 6.38240E-09 671750 + 879 681690 Er-169 1.26430E-11 6.36250E-07 681690 + 880 681700 Er-170 2.25170E-10 3.57350E-07 68170.82c + 881 681710 Er-171 1.13040E-09 2.02090E-07 681710 + 882 681720 Er-172 6.90080E-09 1.13130E-07 681720 + 883 681730 Er-173 8.81340E-09 6.41050E-08 681730 + 884 681740 Er-174 2.04890E-08 3.44860E-08 681740 + 885 681750 Er-175 1.16150E-08 1.79970E-08 681750 + 886 681760 Er-176 8.61210E-09 8.61210E-09 681760 + 887 681770 Er-177 1.98010E-09 1.98010E-09 681770 + 888 691720 Tm-172 9.56680E-12 1.13140E-07 691720 + 889 691730 Tm-173 1.30020E-10 6.42350E-08 691730 + 890 691740 Tm-174 4.63550E-10 3.49500E-08 691740 + 891 691750 Tm-175 2.39570E-09 2.03930E-08 691750 + 892 691760 Tm-176 2.29860E-09 1.09110E-08 691760 + 893 691770 Tm-177 4.24380E-09 6.22390E-09 691770 + 894 691780 Tm-178 2.06110E-09 2.06110E-09 691780 + 895 691790 Tm-179 1.30780E-09 1.30780E-09 691790 + 896 701750 Yb-175 6.48500E-12 2.04000E-08 701750 + 897 701751 Yb-175m 8.63440E-13 1.57040E-08 701751 + 898 701760 Yb-176 2.35450E-11 1.04330E-08 701760 + 899 701761 Yb-176m 4.93950E-11 5.50470E-09 701761 + 900 701770 Yb-177 1.65550E-10 6.42280E-09 701770 + 901 701771 Yb-177m 3.33320E-11 6.25720E-09 701771 + 902 701780 Yb-178 8.45770E-10 2.90690E-09 701780 + 903 701790 Yb-179 6.76010E-10 1.98380E-09 701790 + 904 701800 Yb-180 8.86020E-10 8.86020E-10 701800 + 905 701810 Yb-181 3.66230E-10 3.66230E-10 701810 + 906 711780 Lu-178 1.83880E-12 2.90870E-09 711780 + 907 711781 Lu-178m 2.46340E-12 2.46340E-12 711781 + 908 711790 Lu-179 3.03840E-11 2.01820E-09 711790 + 909 711791 Lu-179m 4.04540E-12 1.98790E-09 711791 + 910 711800 Lu-180 1.69750E-11 4.83500E-10 711800 + 911 711801 Lu-180m 1.69750E-11 9.03000E-10 711801 + 912 711802 Lu-180m 3.00580E-11 3.00580E-11 711802 + 913 711810 Lu-181 2.23370E-10 5.89600E-10 711810 + 914 711820 Lu-182 1.51700E-10 1.51700E-10 711820 + 915 711830 Lu-183 1.60370E-10 1.60370E-10 711830 + 916 711840 Lu-184 5.09950E-11 5.09950E-11 711840 + 917 721810 Hf-181 2.45140E-12 5.92050E-10 721810 + 918 721820 Hf-182 5.18550E-12 1.61450E-10 721820 + 919 721821 Hf-182m 1.08790E-11 1.08790E-11 721821 + 920 721830 Hf-183 2.31280E-11 1.83500E-10 721830 + 921 721840 Hf-184 1.94740E-11 4.49710E-11 721840 + 922 721841 Hf-184m 4.08540E-11 6.63520E-11 721841 + 923 721850 Hf-185 3.60410E-11 3.60410E-11 721850 + 924 721860 Hf-186 2.89680E-11 2.89680E-11 721860 + 925 721870 Hf-187 7.45740E-12 7.45740E-12 721870 + 926 721880 Hf-188 3.08350E-12 3.08350E-12 721880 + 927 731840 Ta-184 1.06630E-12 1.12390E-10 731840 + 928 731850 Ta-185 3.69880E-12 4.19470E-11 731850 + 929 731851 Ta-185m 2.20700E-12 2.20700E-12 731851 + 930 731860 Ta-186 6.22620E-12 3.51940E-11 731860 + 931 731870 Ta-187 1.29160E-11 2.03730E-11 731870 + 932 731880 Ta-188 6.69880E-12 9.78230E-12 731880 + 933 731890 Ta-189 4.55470E-12 4.55470E-12 731890 + 934 741880 W-188 2.19910E-12 1.19810E-11 741880 + 935 741890 W-189 1.90210E-12 6.45680E-12 741890 + 936 741900 W-190 1.19520E-12 2.79640E-12 741900 + 937 741901 W-190m 1.60120E-12 1.60120E-12 741901 + 938 741910 W-191 1.24810E-12 1.24810E-12 741910 + + Nuclide 94243.82c -- plutonium 243 (Pu-243) is using NFY data from Cm-245 + + Nuclide 94244.82c -- plutonium 244 (Pu-244) is using NFY data from U-233 + + Nuclide 95241.82c -- americium 241 (Am-241) + + Neutron-induced fission: + + Interpolation region : 1 / 2 + Interpolation energy : 2.53000E-08 MeV + Number of products : 1144 / 1195 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 3.74900E-05 3.74900E-05 1001.82c + 2 10020 H-2 1.14570E-05 1.14570E-05 1002.82c + 3 10030 H-3 1.65000E-04 1.65000E-04 1003.82c + 4 20040 He-4 2.37000E-03 2.37000E-03 2004.82c + 5 190500 K-50 1.97480E-12 1.97480E-12 190500 + 6 200500 Ca-50 1.82610E-11 1.96630E-11 200500 + 7 200510 Ca-51 2.35600E-11 2.35600E-11 200510 + 8 200520 Ca-52 1.43210E-11 1.43210E-11 200520 + 9 200530 Ca-53 6.77460E-12 6.77460E-12 200530 + 10 200540 Ca-54 1.50470E-12 1.50470E-12 200540 + 11 210500 Sc-50 5.28600E-12 2.69320E-11 210500 + 12 210501 Sc-50m 2.25680E-12 2.19200E-11 210501 + 13 210510 Sc-51 2.06560E-11 4.45020E-11 210510 + 14 210520 Sc-52 4.93930E-11 6.54600E-11 210520 + 15 210530 Sc-53 5.30360E-11 5.77780E-11 210530 + 16 210540 Sc-54 5.19070E-11 5.34120E-11 210540 + 17 210550 Sc-55 2.29640E-11 2.29640E-11 210550 + 18 210560 Sc-56 9.76730E-12 9.76730E-12 210560 + 19 210570 Sc-57 1.73830E-12 1.73830E-12 210570 + 20 220510 Ti-51 3.64550E-12 4.81480E-11 220510 + 21 220520 Ti-52 1.94600E-11 8.49200E-11 220520 + 22 220530 Ti-53 8.14720E-11 1.39250E-10 220530 + 23 220540 Ti-54 1.69810E-10 2.23220E-10 220540 + 24 220550 Ti-55 3.02580E-10 3.25540E-10 220550 + 25 220560 Ti-56 3.01860E-10 3.12200E-10 220560 + 26 220570 Ti-57 2.44190E-10 2.45350E-10 220570 + 27 220580 Ti-58 8.39090E-11 8.39090E-11 220580 + 28 220590 Ti-59 2.24750E-11 2.24750E-11 220590 + 29 220600 Ti-60 3.18550E-12 3.18550E-12 220600 + 30 230530 V-53 2.88010E-12 1.42130E-10 230530 + 31 230540 V-54 2.51390E-11 2.48360E-10 230540 + 32 230550 V-55 9.73970E-11 4.22940E-10 230550 + 33 230560 V-56 3.75960E-10 6.88900E-10 230560 + 34 230570 V-57 6.57400E-10 9.02020E-10 230570 + 35 230580 V-58 9.37530E-10 1.02140E-09 230580 + 36 230590 V-59 6.08700E-10 6.31180E-10 230590 + 37 230600 V-60 4.03210E-10 4.06400E-10 230600 + 38 230610 V-61 1.16970E-10 1.16970E-10 230610 + 39 230620 V-62 2.69500E-11 2.69500E-11 230620 + 40 230630 V-63 2.52070E-12 2.52070E-12 230630 + 41 240550 Cr-55 5.67850E-12 4.28620E-10 240550 + 42 240560 Cr-56 5.18860E-11 7.44390E-10 240560 + 43 240570 Cr-57 3.68290E-10 2.08380E-09 240570 + 44 240580 Cr-58 1.12190E-09 1.32620E-09 240580 + 45 240590 Cr-59 2.83080E-09 3.46200E-09 240590 + 46 240600 Cr-60 4.15290E-09 4.56630E-09 240600 + 47 240610 Cr-61 5.16750E-09 5.27750E-09 240610 + 48 240620 Cr-62 2.97640E-09 3.00420E-09 240620 + 49 240630 Cr-63 1.33220E-09 1.33380E-09 240630 + 50 240640 Cr-64 2.84160E-10 2.84160E-10 240640 + 51 240650 Cr-65 4.71650E-11 4.71650E-11 240650 + 52 240660 Cr-66 3.90370E-12 3.90370E-12 240660 + 53 250570 Mn-57 4.18160E-12 2.08800E-09 250570 + 54 250580 Mn-58 5.08990E-11 1.37710E-09 250580 + 55 250581 Mn-58m 5.73100E-12 5.73100E-12 250581 + 56 250590 Mn-59 3.27220E-10 3.78920E-09 250590 + 57 250600 Mn-60 1.92200E-10 4.95480E-09 250600 + 58 250601 Mn-60m 1.70700E-09 1.70700E-09 250601 + 59 250610 Mn-61 5.01460E-09 1.02920E-08 250610 + 60 250620 Mn-62 9.66920E-09 1.11710E-08 250620 + 61 250621 Mn-62m 1.73580E-09 3.23800E-09 250621 + 62 250630 Mn-63 1.16540E-08 1.29880E-08 250630 + 63 250640 Mn-64 1.10190E-08 1.13030E-08 250640 + 64 250650 Mn-65 4.69900E-09 4.74620E-09 250650 + 65 250660 Mn-66 1.89860E-09 1.90250E-09 250660 + 66 250670 Mn-67 3.19490E-10 3.19490E-10 250670 + 67 250680 Mn-68 3.98020E-11 3.98020E-11 250680 + 68 250690 Mn-69 2.05340E-12 2.05340E-12 250690 + 69 260590 Fe-59 5.96900E-12 3.79520E-09 260590 + 70 260600 Fe-60 8.68450E-11 6.55240E-09 260600 + 71 260610 Fe-61 9.86590E-10 1.12790E-08 260610 + 72 260620 Fe-62 4.98230E-09 1.93910E-08 260620 + 73 260630 Fe-63 1.98070E-08 3.27950E-08 260630 + 74 260640 Fe-64 3.99570E-08 5.12600E-08 260640 + 75 260650 Fe-65 6.89860E-08 7.37320E-08 260650 + 76 260660 Fe-66 6.57780E-08 6.76800E-08 260660 + 77 260670 Fe-67 5.05850E-08 5.09040E-08 260670 + 78 260680 Fe-68 1.65780E-08 1.66180E-08 260680 + 79 260690 Fe-69 4.24000E-09 4.24160E-09 260690 + 80 260700 Fe-70 6.35550E-10 6.35550E-10 260700 + 81 260710 Fe-71 9.17670E-11 9.17670E-11 260710 + 82 270610 Co-61 3.42390E-12 1.12820E-08 270610 + 83 270620 Co-62 2.42360E-11 1.94160E-08 270620 + 84 270621 Co-62m 5.67670E-11 5.67670E-11 270621 + 85 270630 Co-63 7.82910E-10 3.35780E-08 270630 + 86 270640 Co-64 6.57430E-09 5.78350E-08 270640 + 87 270650 Co-65 2.45820E-08 9.83140E-08 270650 + 88 270660 Co-66 9.06820E-08 1.58360E-07 270660 + 89 270670 Co-67 1.51320E-07 2.02220E-07 270670 + 90 270680 Co-68 1.10010E-07 1.66990E-07 270680 + 91 270681 Co-68m 9.70440E-08 1.13960E-07 270681 + 92 270690 Co-69 1.29120E-07 1.33070E-07 270690 + 93 270700 Co-70 4.54390E-08 4.54390E-08 270700 + 94 270701 Co-70m 4.54390E-08 4.60740E-08 270701 + 95 270710 Co-71 3.52010E-08 3.52930E-08 270710 + 96 270720 Co-72 1.43310E-09 1.43310E-09 270720 + 97 270730 Co-73 7.84470E-11 7.84470E-11 270730 + 98 270740 Co-74 3.12010E-11 3.12010E-11 270740 + 99 280630 Ni-63 4.27790E-12 3.35820E-08 280630 + 100 280640 Ni-64 9.42960E-11 5.79290E-08 28064.82c + 101 280650 Ni-65 1.60720E-09 9.99210E-08 280650 + 102 280660 Ni-66 1.39480E-08 1.72310E-07 280660 + 103 280670 Ni-67 9.39880E-08 2.96210E-07 280670 + 104 280680 Ni-68 2.74110E-07 4.99410E-07 280680 + 105 280690 Ni-69 3.32870E-07 4.64600E-07 280690 + 106 280691 Ni-69m 3.32870E-07 3.32870E-07 280691 + 107 280700 Ni-70 1.64890E-06 1.74040E-06 280700 + 108 280710 Ni-71 2.07150E-06 2.10680E-06 280710 + 109 280720 Ni-72 1.78420E-07 1.79850E-07 280720 + 110 280730 Ni-73 4.69290E-08 4.70070E-08 280730 + 111 280740 Ni-74 5.09860E-08 5.10170E-08 280740 + 112 280750 Ni-75 7.85070E-09 7.85070E-09 280750 + 113 280760 Ni-76 7.71990E-10 7.71990E-10 280760 + 114 280770 Ni-77 3.59990E-11 3.59990E-11 280770 + 115 290650 Cu-65 1.64230E-12 9.99230E-08 29065.82c + 116 290660 Cu-66 6.94620E-11 1.72380E-07 290660 + 117 290670 Cu-67 1.19990E-09 2.97410E-07 290670 + 118 290680 Cu-68 4.62740E-09 5.13140E-07 290680 + 119 290681 Cu-68m 1.08390E-08 1.08390E-08 290681 + 120 290690 Cu-69 8.55090E-08 8.82980E-07 290690 + 121 290700 Cu-70 4.01860E-08 3.08550E-07 290700 + 122 290701 Cu-70m 4.47700E-07 5.36730E-07 290701 + 123 290702 Cu-70m 4.01860E-08 1.78060E-06 290702 + 124 290710 Cu-71 2.07150E-06 4.17830E-06 290710 + 125 290720 Cu-72 7.59850E-07 9.39700E-07 290720 + 126 290730 Cu-73 1.34640E-06 1.39340E-06 290730 + 127 290740 Cu-74 2.06090E-06 2.11200E-06 290740 + 128 290750 Cu-75 8.83700E-07 8.91430E-07 290750 + 129 290760 Cu-76 2.12710E-07 2.13100E-07 290760 + 130 290761 Cu-76m 2.12710E-07 2.13100E-07 290761 + 131 290770 Cu-77 5.36480E-08 5.36840E-08 290770 + 132 290780 Cu-78 7.91580E-09 7.91580E-09 290780 + 133 290790 Cu-79 4.72610E-10 4.72610E-10 290790 + 134 290800 Cu-80 3.14980E-11 3.14980E-11 290800 + 135 300670 Zn-67 1.90430E-12 2.97410E-07 300670 + 136 300680 Zn-68 6.65510E-11 5.14940E-07 300680 + 137 300690 Zn-69 3.30170E-10 8.84740E-07 300690 + 138 300691 Zn-69m 1.42790E-09 1.42790E-09 300691 + 139 300700 Zn-70 2.70680E-08 2.29550E-06 300700 + 140 300710 Zn-71 7.71220E-08 4.25540E-06 300710 + 141 300711 Zn-71m 3.33540E-07 3.33540E-07 300711 + 142 300720 Zn-72 1.34870E-06 2.28840E-06 300720 + 143 300730 Zn-73 8.53620E-08 1.92600E-06 300730 + 144 300731 Zn-73m 1.16690E-07 4.47220E-07 300731 + 145 300732 Zn-73m 6.61060E-07 6.61060E-07 300732 + 146 300740 Zn-74 1.03050E-05 1.24480E-05 300740 + 147 300750 Zn-75 1.55630E-05 1.64300E-05 300750 + 148 300760 Zn-76 2.37020E-05 2.41220E-05 300760 + 149 300770 Zn-77 2.12580E-06 2.34200E-06 300770 + 150 300771 Zn-77m 3.24980E-07 3.24980E-07 300771 + 151 300780 Zn-78 1.06110E-05 1.06190E-05 300780 + 152 300790 Zn-79 2.55900E-06 2.55920E-06 300790 + 153 300800 Zn-80 1.75140E-07 1.75170E-07 300800 + 154 300810 Zn-81 1.26530E-08 1.26530E-08 300810 + 155 300820 Zn-82 4.56530E-10 4.56530E-10 300820 + 156 310700 Ga-70 3.97670E-11 3.97670E-11 310700 + 157 310710 Ga-71 1.60950E-09 4.59060E-06 310710 + 158 310720 Ga-72 6.04400E-09 2.29510E-06 310720 + 159 310721 Ga-72m 6.80520E-10 7.69310E-08 310721 + 160 310730 Ga-73 3.81230E-08 2.29460E-06 310730 + 161 310740 Ga-74 8.17100E-07 1.07660E-05 310740 + 162 310741 Ga-74m 8.17100E-07 1.32650E-05 310741 + 163 310750 Ga-75 4.44660E-06 2.08760E-05 310750 + 164 310760 Ga-76 1.42210E-05 3.83430E-05 310760 + 165 310770 Ga-77 3.92130E-05 4.17180E-05 310770 + 166 310780 Ga-78 3.18320E-05 4.24840E-05 310780 + 167 310790 Ga-79 4.35040E-05 4.60300E-05 310790 + 168 310800 Ga-80 3.40800E-05 3.42560E-05 310800 + 169 310810 Ga-81 1.23090E-05 1.23210E-05 310810 + 170 310820 Ga-82 1.03550E-06 1.03600E-06 310820 + 171 310830 Ga-83 8.06310E-08 8.06310E-08 310830 + 172 310840 Ga-84 5.13840E-09 5.13840E-09 310840 + 173 310850 Ga-85 8.38380E-11 8.38380E-11 310850 + 174 320720 Ge-72 8.38870E-12 2.29510E-06 32072.82c + 175 320730 Ge-73 1.91350E-10 2.29490E-06 32073.82c + 176 320731 Ge-73m 4.42460E-11 2.26100E-06 320731 + 177 320740 Ge-74 2.64120E-08 1.41090E-05 32074.82c + 178 320750 Ge-75 5.54200E-08 2.12940E-05 320750 + 179 320751 Ge-75m 3.62530E-07 1.19760E-06 320751 + 180 320760 Ge-76 9.48080E-06 4.78240E-05 32076.82c + 181 320770 Ge-77 2.12580E-05 2.98020E-05 320770 + 182 320771 Ge-77m 3.24980E-06 4.49670E-05 320771 + 183 320780 Ge-78 9.01900E-05 1.32710E-04 320780 + 184 320790 Ge-79 2.40930E-05 7.63200E-05 320790 + 185 320791 Ge-79m 1.57610E-04 1.57680E-04 320791 + 186 320800 Ge-80 4.05850E-04 4.41570E-04 320800 + 187 320810 Ge-81 2.23290E-04 2.29700E-04 320810 + 188 320811 Ge-81m 5.16300E-05 5.68630E-05 320811 + 189 320820 Ge-82 2.07210E-04 2.08060E-04 320820 + 190 320830 Ge-83 4.95210E-05 4.95750E-05 320830 + 191 320840 Ge-84 1.44230E-05 1.44250E-05 320840 + 192 320850 Ge-85 1.10040E-06 1.10050E-06 320850 + 193 320860 Ge-86 5.16350E-08 5.16350E-08 320860 + 194 320870 Ge-87 1.97270E-09 1.97270E-09 320870 + 195 330740 As-74 1.11670E-11 1.11670E-11 330740 + 196 330750 As-75 1.13280E-10 2.12950E-05 33075.82c + 197 330751 As-75m 3.70610E-10 7.29890E-10 330751 + 198 330760 As-76 2.43110E-08 2.43110E-08 330760 + 199 330770 As-77 3.14550E-07 6.65400E-05 330770 + 200 330780 As-78 2.65260E-06 1.35370E-04 330780 + 201 330790 As-79 3.07070E-05 2.58400E-04 330790 + 202 330800 As-80 1.36340E-04 5.77910E-04 330800 + 203 330810 As-81 3.64940E-04 6.50930E-04 330810 + 204 330820 As-82 1.58160E-04 3.66220E-04 330820 + 205 330821 As-82m 4.77290E-04 4.77290E-04 330821 + 206 330830 As-83 6.83090E-04 7.34220E-04 330830 + 207 330840 As-84 1.51460E-04 1.57970E-04 330840 + 208 330841 As-84m 1.51460E-04 1.57970E-04 330841 + 209 330850 As-85 1.70290E-04 1.71240E-04 330850 + 210 330860 As-86 4.16760E-05 4.17280E-05 330860 + 211 330870 As-87 6.29940E-06 6.30140E-06 330870 + 212 330880 As-88 3.20620E-07 3.20620E-07 330880 + 213 330890 As-89 1.39350E-08 1.39350E-08 330890 + 214 330900 As-90 3.67360E-10 3.67360E-10 330900 + 215 340760 Se-76 7.92610E-12 2.43190E-08 34076.82c + 216 340770 Se-77 7.50100E-11 6.65410E-05 34077.82c + 217 340771 Se-77m 4.90680E-10 4.90680E-10 340771 + 218 340780 Se-78 2.34300E-08 1.35390E-04 34078.82c + 219 340790 Se-79 6.23760E-07 2.58970E-04 34079.82c + 220 340791 Se-79m 9.53540E-08 2.52370E-04 340791 + 221 340800 Se-80 1.70200E-05 5.94930E-04 34080.82c + 222 340810 Se-81 1.77860E-05 7.84990E-04 340810 + 223 340811 Se-81m 1.16340E-04 1.39710E-04 340811 + 224 340820 Se-82 3.98470E-04 1.24200E-03 34082.82c + 225 340830 Se-83 8.46230E-04 1.11080E-03 340830 + 226 340831 Se-83m 1.95670E-04 6.65790E-04 340831 + 227 340840 Se-84 2.20680E-03 2.56000E-03 340840 + 228 340850 Se-85 2.10960E-03 2.25690E-03 340850 + 229 340860 Se-86 1.56890E-03 1.59780E-03 340860 + 230 340870 Se-87 6.37620E-04 6.42950E-04 340870 + 231 340880 Se-88 1.83840E-04 1.84160E-04 340880 + 232 340890 Se-89 3.96850E-05 3.96990E-05 340890 + 233 340900 Se-90 1.44090E-05 1.44090E-05 340900 + 234 340910 Se-91 2.08990E-07 2.08990E-07 340910 + 235 340920 Se-92 5.63660E-09 5.63660E-09 340920 + 236 350780 Br-78 3.59320E-12 3.59320E-12 350780 + 237 350790 Br-79 5.53180E-11 1.41560E-07 35079.82c + 238 350791 Br-79m 1.80980E-10 1.80980E-10 350791 + 239 350800 Br-80 4.82540E-09 1.93870E-08 350800 + 240 350801 Br-80m 1.45620E-08 1.45620E-08 350801 + 241 350810 Br-81 3.92870E-07 7.85460E-04 35081.82c + 242 350820 Br-82 2.03170E-06 2.87830E-06 350820 + 243 350821 Br-82m 8.67410E-07 8.67410E-07 350821 + 244 350830 Br-83 5.14180E-05 1.82800E-03 350830 + 245 350840 Br-84 1.51130E-04 2.71110E-03 350840 + 246 350841 Br-84m 1.51130E-04 1.51130E-04 350841 + 247 350850 Br-85 1.21310E-03 3.47000E-03 350850 + 248 350860 Br-86 1.88610E-03 3.48390E-03 350860 + 249 350870 Br-87 2.84250E-03 3.48730E-03 350870 + 250 350880 Br-88 2.02610E-03 2.21150E-03 350880 + 251 350890 Br-89 1.55360E-03 1.59020E-03 350890 + 252 350900 Br-90 5.28940E-04 5.43390E-04 350900 + 253 350910 Br-91 2.27460E-04 2.27620E-04 350910 + 254 350920 Br-92 1.99700E-05 1.99760E-05 350920 + 255 350930 Br-93 1.86820E-06 1.86820E-06 350930 + 256 350940 Br-94 4.43990E-08 4.43990E-08 350940 + 257 350950 Br-95 9.27900E-10 9.27900E-10 350950 + 258 360810 Kr-81 1.85120E-10 2.13420E-10 360810 + 259 360811 Kr-81m 2.83000E-11 2.83000E-11 360811 + 260 360820 Kr-82 1.07490E-08 2.90990E-06 36082.82c + 261 360830 Kr-83 1.90630E-06 1.83030E-03 36083.82c + 262 360831 Kr-83m 4.40780E-07 1.82680E-03 360831 + 263 360840 Kr-84 1.23280E-05 2.87460E-03 36084.82c + 264 360850 Kr-85 1.40720E-04 8.94710E-04 36085.82c + 265 360851 Kr-85m 3.25380E-05 3.49690E-03 360851 + 266 360860 Kr-86 8.79710E-04 4.45120E-03 36086.82c + 267 360870 Kr-87 2.06290E-03 5.61080E-03 360870 + 268 360880 Kr-88 4.65790E-03 6.94550E-03 360880 + 269 360890 Kr-89 6.94010E-03 8.43980E-03 360890 + 270 360900 Kr-90 7.83880E-03 8.29400E-03 360900 + 271 360910 Kr-91 5.22460E-03 5.41330E-03 360910 + 272 360920 Kr-92 2.46500E-03 2.47960E-03 360920 + 273 360930 Kr-93 7.29910E-04 7.30540E-04 360930 + 274 360940 Kr-94 1.97090E-04 1.97100E-04 360940 + 275 360950 Kr-95 2.66110E-05 2.66120E-05 360950 + 276 360960 Kr-96 9.72250E-07 9.72250E-07 360960 + 277 360970 Kr-97 1.15270E-08 1.15270E-08 360970 + 278 370830 Rb-83 1.24170E-11 4.23920E-11 370830 + 279 370831 Rb-83m 2.99750E-11 2.99750E-11 370831 + 280 370840 Rb-84 1.31530E-09 3.68130E-09 370840 + 281 370841 Rb-84m 2.36600E-09 2.36600E-09 370841 + 282 370850 Rb-85 1.20060E-07 3.64340E-03 37085.82c + 283 370860 Rb-86 1.05630E-06 2.95630E-06 37086.82c + 284 370861 Rb-86m 1.90000E-06 1.90000E-06 370861 + 285 370870 Rb-87 6.53720E-05 5.67620E-03 37087.82c + 286 370880 Rb-88 3.18460E-04 7.26390E-03 370880 + 287 370890 Rb-89 1.81100E-03 1.02510E-02 370890 + 288 370900 Rb-90 4.29580E-04 7.76620E-03 370900 + 289 370901 Rb-90m 3.81530E-03 4.90020E-03 370901 + 290 370910 Rb-91 8.87150E-03 1.42850E-02 370910 + 291 370920 Rb-92 8.44970E-03 1.09290E-02 370920 + 292 370930 Rb-93 7.91230E-03 8.64500E-03 370930 + 293 370940 Rb-94 4.17690E-03 4.37260E-03 370940 + 294 370950 Rb-95 2.24710E-03 2.27300E-03 370950 + 295 370960 Rb-96 2.32620E-04 3.49630E-04 370960 + 296 370961 Rb-96m 2.32620E-04 2.33080E-04 370961 + 297 370970 Rb-97 1.15750E-04 1.15760E-04 370970 + 298 370980 Rb-98 2.96380E-06 2.96380E-06 370980 + 299 370981 Rb-98m 2.96380E-06 2.96380E-06 370981 + 300 370990 Rb-99 5.94290E-08 5.94290E-08 370990 + 301 371000 Rb-100 1.79470E-09 1.79470E-09 371000 + 302 380860 Sr-86 1.17020E-09 2.95730E-06 38086.82c + 303 380870 Sr-87 5.43000E-08 6.68170E-08 38087.82c + 304 380871 Sr-87m 1.25550E-08 1.25550E-08 380871 + 305 380880 Sr-88 1.40000E-05 7.27790E-03 38088.82c + 306 380890 Sr-89 1.05030E-04 1.03560E-02 38089.82c + 307 380900 Sr-90 9.44820E-04 1.34840E-02 38090.82c + 308 380910 Sr-91 3.30480E-03 1.75900E-02 380910 + 309 380920 Sr-92 1.00180E-02 2.10680E-02 380920 + 310 380930 Sr-93 1.64770E-02 2.54430E-02 380930 + 311 380940 Sr-94 2.42670E-02 2.83930E-02 380940 + 312 380950 Sr-95 1.81220E-02 2.02460E-02 380950 + 313 380960 Sr-96 1.13900E-02 1.18380E-02 380960 + 314 380970 Sr-97 5.10710E-03 5.19420E-03 380970 + 315 380980 Sr-98 1.87620E-03 1.88170E-03 380980 + 316 380990 Sr-99 3.83460E-04 3.83510E-04 380990 + 317 381000 Sr-100 6.37820E-05 6.37840E-05 381000 + 318 381010 Sr-101 5.17590E-06 5.17590E-06 381010 + 319 381020 Sr-102 1.12870E-08 1.12870E-08 381020 + 320 390880 Y-88 1.12610E-10 1.95610E-10 390880 + 321 390881 Y-88m 8.29970E-11 8.29970E-11 390881 + 322 390890 Y-89 2.66300E-09 1.03560E-02 39089.82c + 323 390891 Y-89m 1.15170E-08 1.00970E-06 390891 + 324 390900 Y-90 2.12580E-06 1.34890E-02 39090.82c + 325 390901 Y-90m 3.01650E-06 3.01650E-06 390901 + 326 390910 Y-91 7.55200E-06 1.76300E-02 39091.82c + 327 390911 Y-91m 3.26610E-05 1.03820E-02 390911 + 328 390920 Y-92 2.66900E-04 2.13350E-02 390920 + 329 390930 Y-93 2.30530E-04 2.71810E-02 390930 + 330 390931 Y-93m 1.50800E-03 7.87480E-03 390931 + 331 390940 Y-94 5.43150E-03 3.38250E-02 390940 + 332 390950 Y-95 1.70850E-02 3.73310E-02 390950 + 333 390960 Y-96 7.42040E-03 1.92600E-02 390960 + 334 390961 Y-96m 1.33480E-02 1.33490E-02 390961 + 335 390970 Y-97 4.46870E-03 9.02270E-03 390970 + 336 390971 Y-97m 1.52310E-02 1.92780E-02 390971 + 337 390972 Y-97m 4.09270E-03 4.09270E-03 390972 + 338 390980 Y-98 2.74590E-03 4.62760E-03 390980 + 339 390981 Y-98m 1.15480E-02 1.15480E-02 390981 + 340 390990 Y-99 1.02310E-02 1.06150E-02 390990 + 341 391000 Y-100 1.75420E-03 1.81760E-03 391000 + 342 391001 Y-100m 1.75420E-03 1.75430E-03 391001 + 343 391010 Y-101 1.09840E-03 1.10340E-03 391010 + 344 391020 Y-102 9.19700E-05 9.19750E-05 391020 + 345 391021 Y-102m 9.19700E-05 9.19750E-05 391021 + 346 391030 Y-103 2.40710E-05 2.40710E-05 391030 + 347 391040 Y-104 6.40590E-08 6.40590E-08 391040 + 348 391050 Y-105 1.52710E-09 1.52710E-09 391050 + 349 400910 Zr-91 6.94310E-09 1.76300E-02 40091.82c + 350 400920 Zr-92 7.26090E-06 2.13430E-02 40092.82c + 351 400930 Zr-93 5.33430E-05 2.72340E-02 40093.82c + 352 400940 Zr-94 4.73170E-04 3.42980E-02 40094.82c + 353 400950 Zr-95 2.31210E-03 3.96430E-02 40095.82c + 354 400960 Zr-96 9.97380E-03 4.25980E-02 40096.82c + 355 400970 Zr-97 2.01950E-02 4.95740E-02 400970 + 356 400980 Zr-98 4.03710E-02 5.63170E-02 400980 + 357 400990 Zr-99 4.10200E-02 5.14710E-02 400990 + 358 401000 Zr-100 3.47750E-02 3.83300E-02 401000 + 359 401010 Zr-101 1.65830E-02 1.76950E-02 401010 + 360 401020 Zr-102 8.31660E-03 8.49350E-03 401020 + 361 401030 Zr-103 2.45720E-03 2.47930E-03 401030 + 362 401040 Zr-104 6.29200E-04 6.29260E-04 401040 + 363 401050 Zr-105 6.84600E-05 6.84610E-05 401050 + 364 401060 Zr-106 3.22830E-07 3.22830E-07 401060 + 365 401070 Zr-107 6.75320E-09 6.75320E-09 401070 + 366 410930 Nb-93 4.93570E-10 6.07690E-10 41093.82c + 367 410931 Nb-93m 1.14120E-10 1.14120E-10 410931 + 368 410940 Nb-94 3.68960E-08 6.27680E-08 41094.82c + 369 410941 Nb-94m 2.60020E-08 2.60020E-08 410941 + 370 410950 Nb-95 6.65690E-06 3.96280E-02 41095.82c + 371 410951 Nb-95m 1.53920E-06 4.29830E-04 410951 + 372 410960 Nb-96 1.04310E-04 1.04310E-04 410960 + 373 410970 Nb-97 7.15290E-04 5.04540E-02 410970 + 374 410971 Nb-97m 1.65390E-04 4.72840E-02 410971 + 375 410980 Nb-98 7.87870E-04 5.71050E-02 410980 + 376 410981 Nb-98m 2.37750E-03 2.37750E-03 410981 + 377 410990 Nb-99 1.08900E-02 4.38490E-02 410990 + 378 410991 Nb-99m 2.51800E-03 2.14590E-02 410991 + 379 411000 Nb-100 4.46650E-03 4.27970E-02 411000 + 380 411001 Nb-100m 1.87840E-02 1.87840E-02 411001 + 381 411010 Nb-101 3.70120E-02 5.47070E-02 411010 + 382 411020 Nb-102 1.46320E-02 2.31260E-02 411020 + 383 411021 Nb-102m 1.46320E-02 1.46320E-02 411021 + 384 411030 Nb-103 2.54540E-02 2.79330E-02 411030 + 385 411040 Nb-104 6.14650E-03 6.77670E-03 411040 + 386 411041 Nb-104m 6.14650E-03 6.14650E-03 411041 + 387 411050 Nb-105 5.83700E-03 5.90450E-03 411050 + 388 411060 Nb-106 1.14940E-03 1.14970E-03 411060 + 389 411070 Nb-107 2.81430E-04 2.81440E-04 411070 + 390 411080 Nb-108 2.79770E-05 2.79770E-05 411080 + 391 411090 Nb-109 1.29690E-08 1.29690E-08 411090 + 392 411100 Nb-110 4.24890E-10 4.24890E-10 411100 + 393 420960 Mo-96 1.72480E-08 1.04330E-04 42096.82c + 394 420970 Mo-97 1.59060E-05 5.04700E-02 42097.82c + 395 420980 Mo-98 1.21850E-04 5.96050E-02 42098.82c + 396 420990 Mo-99 8.44700E-04 6.57240E-02 42099.82c + 397 421000 Mo-100 4.40630E-03 6.59870E-02 42100.82c + 398 421010 Mo-101 1.11830E-02 6.58910E-02 421010 + 399 421020 Mo-102 2.95250E-02 6.72820E-02 421020 + 400 421030 Mo-103 3.78960E-02 6.58370E-02 421030 + 401 421040 Mo-104 4.39470E-02 5.69640E-02 421040 + 402 421050 Mo-105 2.66580E-02 3.25140E-02 421050 + 403 421060 Mo-106 1.50400E-02 1.61550E-02 421060 + 404 421070 Mo-107 5.54360E-03 5.80990E-03 421070 + 405 421080 Mo-108 1.71440E-03 1.74060E-03 421080 + 406 421090 Mo-109 2.66110E-04 2.66120E-04 421090 + 407 421100 Mo-110 3.77210E-05 3.77210E-05 421100 + 408 421110 Mo-111 3.00050E-06 3.00050E-06 421110 + 409 421120 Mo-112 7.44870E-10 7.44870E-10 421120 + 410 430980 Tc-98 3.00760E-09 3.00760E-09 430980 + 411 430990 Tc-99 2.70060E-06 6.57250E-02 43099.82c + 412 430991 Tc-99m 6.24440E-07 5.78770E-02 430991 + 413 431000 Tc-100 2.75670E-05 2.75670E-05 431000 + 414 431010 Tc-101 2.47780E-04 6.61380E-02 431010 + 415 431020 Tc-102 5.53100E-04 6.78360E-02 431020 + 416 431021 Tc-102m 5.53100E-04 5.53100E-04 431021 + 417 431030 Tc-103 5.45750E-03 7.12940E-02 431030 + 418 431040 Tc-104 1.28140E-02 6.97780E-02 431040 + 419 431050 Tc-105 2.94630E-02 6.19770E-02 431050 + 420 431060 Tc-106 2.56960E-02 4.18510E-02 431060 + 421 431070 Tc-107 2.28650E-02 2.86750E-02 431070 + 422 431080 Tc-108 1.11900E-02 1.29320E-02 431080 + 423 431090 Tc-109 5.59350E-03 5.85820E-03 431090 + 424 431100 Tc-110 2.04700E-03 2.08470E-03 431100 + 425 431110 Tc-111 5.65650E-04 5.68620E-04 431110 + 426 431120 Tc-112 5.83390E-05 5.83400E-05 431120 + 427 431130 Tc-113 9.78020E-06 9.78020E-06 431130 + 428 431140 Tc-114 7.06870E-10 7.06870E-10 431140 + 429 441010 Ru-101 4.14230E-06 6.61420E-02 44101.82c + 430 441020 Ru-102 2.00980E-05 6.84090E-02 44102.82c + 431 441030 Ru-103 3.78840E-05 7.14230E-02 44103.82c + 432 441031 Ru-103m 9.14560E-05 9.14560E-05 441031 + 433 441040 Ru-104 1.02010E-03 7.07980E-02 44104.82c + 434 441050 Ru-105 3.18460E-03 6.51610E-02 44105.82c + 435 441060 Ru-106 9.01640E-03 5.08670E-02 44106.82c + 436 441070 Ru-107 1.27170E-02 4.13920E-02 441070 + 437 441080 Ru-108 1.62100E-02 2.91470E-02 441080 + 438 441090 Ru-109 1.02660E-02 1.61200E-02 441090 + 439 441100 Ru-110 8.04640E-03 1.01300E-02 441100 + 440 441110 Ru-111 3.54530E-03 4.11480E-03 441110 + 441 441120 Ru-112 1.25650E-03 1.31470E-03 441120 + 442 441130 Ru-113 1.39650E-04 2.18550E-04 441130 + 443 441131 Ru-113m 1.39650E-04 1.39650E-04 441131 + 444 441140 Ru-114 6.52140E-05 6.52150E-05 441140 + 445 441150 Ru-115 1.03950E-05 1.03950E-05 441150 + 446 441160 Ru-116 1.03160E-06 1.03160E-06 441160 + 447 441170 Ru-117 1.10700E-06 1.10700E-06 441170 + 448 451030 Rh-103 4.36860E-10 7.14230E-02 45103.82c + 449 451031 Rh-103m 2.85770E-09 7.05680E-02 451031 + 450 451040 Rh-104 1.04740E-06 4.20390E-06 451040 + 451 451041 Rh-104m 3.16060E-06 3.16060E-06 451041 + 452 451050 Rh-105 3.02720E-05 6.51960E-02 45105.82c + 453 451051 Rh-105m 4.62770E-06 1.85030E-02 451051 + 454 451060 Rh-106 4.53890E-05 5.09130E-02 451060 + 455 451061 Rh-106m 1.06310E-04 1.06310E-04 451061 + 456 451070 Rh-107 7.82580E-04 4.21740E-02 451070 + 457 451080 Rh-108 4.29350E-04 2.95760E-02 451080 + 458 451081 Rh-108m 1.29560E-03 1.29560E-03 451081 + 459 451090 Rh-109 3.44430E-03 1.95650E-02 451090 + 460 451100 Rh-110 4.63480E-03 1.47650E-02 451100 + 461 451101 Rh-110m 1.23720E-04 1.23720E-04 451101 + 462 451110 Rh-111 5.57220E-03 9.68700E-03 451110 + 463 451120 Rh-112 1.50720E-03 2.82190E-03 451120 + 464 451121 Rh-112m 1.50720E-03 1.50720E-03 451121 + 465 451130 Rh-113 1.50190E-03 1.79030E-03 451130 + 466 451140 Rh-114 2.33850E-04 2.99090E-04 451140 + 467 451141 Rh-114m 2.33850E-04 2.33850E-04 451141 + 468 451150 Rh-115 1.51250E-04 1.61630E-04 451150 + 469 451160 Rh-116 1.04730E-05 1.15160E-05 451160 + 470 451161 Rh-116m 2.45300E-05 2.45300E-05 451161 + 471 451170 Rh-117 8.85210E-06 9.93640E-06 451170 + 472 451180 Rh-118 1.15050E-06 1.15050E-06 451180 + 473 451190 Rh-119 1.02920E-10 1.02920E-10 451190 + 474 451220 Rh-122 2.42970E-09 2.42970E-09 451220 + 475 461060 Pd-106 2.98270E-08 5.10190E-02 46106.82c + 476 461070 Pd-107 3.40690E-06 4.21840E-02 46107.82c + 477 461071 Pd-107m 6.40270E-06 6.40270E-06 461071 + 478 461080 Pd-108 4.42440E-05 3.09160E-02 46108.82c + 479 461090 Pd-109 5.29080E-05 1.97170E-02 461090 + 480 461091 Pd-109m 9.94320E-05 9.88180E-03 461091 + 481 461100 Pd-110 5.57700E-04 1.54470E-02 46110.82c + 482 461110 Pd-111 2.94550E-04 1.03750E-02 461110 + 483 461111 Pd-111m 5.53550E-04 5.92300E-04 461111 + 484 461120 Pd-112 1.15190E-03 5.48110E-03 461120 + 485 461130 Pd-113 2.23170E-04 2.55220E-03 461130 + 486 461131 Pd-113m 5.38770E-04 5.38770E-04 461131 + 487 461140 Pd-114 5.29680E-04 1.06260E-03 461140 + 488 461150 Pd-115 7.06930E-05 2.21360E-04 461150 + 489 461151 Pd-115m 1.32860E-04 1.56330E-04 461151 + 490 461160 Pd-116 1.27040E-04 1.63090E-04 461160 + 491 461170 Pd-117 1.73050E-05 5.97970E-05 461170 + 492 461171 Pd-117m 3.25220E-05 3.25220E-05 461171 + 493 461180 Pd-118 2.64640E-05 2.75810E-05 461180 + 494 461190 Pd-119 1.09390E-05 1.09390E-05 461190 + 495 461200 Pd-120 1.99130E-08 1.99130E-08 461200 + 496 461210 Pd-121 7.74840E-10 7.74840E-10 461210 + 497 461220 Pd-122 2.34920E-06 2.35160E-06 461220 + 498 461230 Pd-123 3.32710E-07 3.32710E-07 461230 + 499 461240 Pd-124 3.28260E-08 3.28260E-08 461240 + 500 471080 Ag-108 7.45940E-10 8.97940E-10 471080 + 501 471081 Ag-108m 1.74720E-09 1.74720E-09 471081 + 502 471090 Ag-109 9.69480E-08 1.97180E-02 47109.82c + 503 471091 Ag-109m 6.34180E-07 1.97080E-02 471091 + 504 471100 Ag-110 1.31470E-06 1.35660E-06 471100 + 505 471101 Ag-110m 3.07940E-06 3.07940E-06 47510.82c + 506 471110 Ag-111 3.05590E-06 1.05060E-02 47111.82c + 507 471111 Ag-111m 1.99900E-05 1.04360E-02 471111 + 508 471120 Ag-112 5.25830E-05 5.53370E-03 471120 + 509 471130 Ag-113 1.05530E-05 1.72710E-03 471130 + 510 471131 Ag-113m 6.90330E-05 2.51300E-03 471131 + 511 471140 Ag-114 1.82550E-05 1.15770E-03 471140 + 512 471141 Ag-114m 7.67720E-05 7.67720E-05 471141 + 513 471150 Ag-115 1.10620E-05 2.30610E-04 471150 + 514 471151 Ag-115m 7.23650E-05 2.75950E-04 471151 + 515 471160 Ag-116 3.05870E-05 1.97970E-04 471160 + 516 471161 Ag-116m 7.16430E-05 7.16430E-05 471161 + 517 471170 Ag-117 1.82110E-05 5.70510E-05 471170 + 518 471171 Ag-117m 1.19130E-04 1.49030E-04 471171 + 519 471180 Ag-118 2.14400E-05 8.36640E-05 471180 + 520 471181 Ag-118m 9.01700E-05 9.41130E-05 471181 + 521 471190 Ag-119 1.40210E-05 1.94910E-05 471190 + 522 471191 Ag-119m 9.17190E-05 9.71880E-05 471191 + 523 471200 Ag-120 1.83470E-05 2.79930E-05 471200 + 524 471201 Ag-120m 2.60340E-05 2.60440E-05 471201 + 525 471210 Ag-121 2.30620E-05 2.30630E-05 471210 + 526 471220 Ag-122 6.64830E-06 9.00000E-06 471220 + 527 471221 Ag-122m 5.98870E-06 5.98870E-06 471221 + 528 471230 Ag-123 7.69100E-06 8.02370E-06 471230 + 529 471240 Ag-124 2.12960E-06 3.12160E-06 471240 + 530 471241 Ag-124m 1.91830E-06 1.91830E-06 471241 + 531 471250 Ag-125 2.33700E-06 2.33700E-06 471250 + 532 471260 Ag-126 4.38990E-07 4.38990E-07 471260 + 533 471270 Ag-127 5.55690E-08 5.55690E-08 471270 + 534 471280 Ag-128 2.75630E-09 2.75630E-09 471280 + 535 481110 Cd-111 2.34190E-07 1.05590E-02 48111.82c + 536 481111 Cd-111m 7.66210E-07 7.66210E-07 481111 + 537 481120 Cd-112 1.26070E-07 5.53380E-03 48112.82c + 538 481130 Cd-113 2.29130E-07 2.60220E-03 48113.82c + 539 481131 Cd-113m 7.49630E-07 3.06100E-05 481131 + 540 481140 Cd-114 1.00800E-06 1.15870E-03 48114.82c + 541 481150 Cd-115 6.64380E-07 4.29640E-04 481150 + 542 481151 Cd-115m 2.17360E-06 2.18090E-05 48515.82c + 543 481160 Cd-116 1.34130E-05 2.78730E-04 48116.82c + 544 481170 Cd-117 4.92450E-06 1.57700E-04 481170 + 545 481171 Cd-117m 1.61110E-05 6.04700E-05 481171 + 546 481180 Cd-118 6.44320E-05 2.03620E-04 481180 + 547 481190 Cd-119 2.95450E-05 1.36480E-04 481190 + 548 481191 Cd-119m 7.13250E-05 8.10710E-05 481191 + 549 481200 Cd-120 1.40900E-04 1.85300E-04 481200 + 550 481210 Cd-121 2.98610E-05 5.05140E-05 481210 + 551 481211 Cd-121m 7.20890E-05 7.44990E-05 481211 + 552 481220 Cd-122 9.47280E-05 1.09720E-04 481220 + 553 481230 Cd-123 1.91320E-05 2.56990E-05 481230 + 554 481231 Cd-123m 4.61880E-05 4.76480E-05 481231 + 555 481240 Cd-124 1.27780E-04 1.31860E-04 481240 + 556 481250 Cd-125 3.26090E-05 3.37770E-05 481250 + 557 481251 Cd-125m 7.87210E-05 7.98900E-05 481251 + 558 481260 Cd-126 8.86830E-05 8.91220E-05 481260 + 559 481270 Cd-127 5.80690E-05 5.81250E-05 481270 + 560 481280 Cd-128 1.34200E-05 1.34230E-05 481280 + 561 481290 Cd-129 2.67520E-07 2.67520E-07 481290 + 562 481291 Cd-129m 6.45830E-07 6.45830E-07 481291 + 563 481300 Cd-130 4.43480E-08 4.43480E-08 481300 + 564 481310 Cd-131 1.31960E-09 1.31960E-09 481310 + 565 491130 In-113 1.47450E-10 3.05670E-05 49113.82c + 566 491131 In-113m 3.40930E-11 3.40930E-11 491131 + 567 491140 In-114 1.04040E-09 4.06950E-09 491140 + 568 491141 In-114m 1.59460E-09 3.13900E-09 491141 + 569 491142 In-114m 1.54440E-09 1.54440E-09 491142 + 570 491150 In-115 2.88570E-08 4.30000E-04 49115.82c + 571 491151 In-115m 6.67240E-09 4.29650E-04 491151 + 572 491160 In-116 9.43980E-08 9.43980E-08 491160 + 573 491161 In-116m 1.44690E-07 2.84820E-07 491161 + 574 491162 In-116m 1.40140E-07 1.40140E-07 491162 + 575 491170 In-117 1.83080E-06 1.43260E-04 491170 + 576 491171 In-117m 4.23320E-07 1.45870E-04 491171 + 577 491180 In-118 2.86380E-07 2.03910E-04 491180 + 578 491181 In-118m 4.38950E-07 8.58150E-07 491181 + 579 491182 In-118m 4.25150E-07 4.25150E-07 491182 + 580 491190 In-119 1.48070E-05 1.16070E-04 491190 + 581 491191 In-119m 3.42380E-06 1.26810E-04 491191 + 582 491200 In-120 5.91710E-06 1.91220E-04 491200 + 583 491201 In-120m 5.91710E-06 5.91710E-06 491201 + 584 491202 In-120m 5.91710E-06 5.91710E-06 491202 + 585 491210 In-121 4.23880E-05 1.34420E-04 491210 + 586 491211 In-121m 9.80110E-06 4.33020E-05 491211 + 587 491220 In-122 4.75040E-05 1.57220E-04 491220 + 588 491221 In-122m 3.37030E-05 3.37030E-05 491221 + 589 491222 In-122m 3.37030E-05 3.37030E-05 491222 + 590 491230 In-123 1.35040E-04 1.90060E-04 491230 + 591 491231 In-123m 3.12240E-05 4.95430E-05 491231 + 592 491240 In-124 1.26300E-04 2.58150E-04 491240 + 593 491241 In-124m 1.13760E-04 1.13760E-04 491241 + 594 491250 In-125 4.69480E-04 5.65530E-04 491250 + 595 491251 In-125m 1.08550E-04 1.26160E-04 491251 + 596 491260 In-126 3.74080E-04 4.63200E-04 491260 + 597 491261 In-126m 3.36960E-04 3.36960E-04 491261 + 598 491270 In-127 1.30400E-03 1.30400E-03 491270 + 599 491271 In-127m 3.01510E-04 3.59640E-04 491271 + 600 491280 In-128 3.36480E-04 4.86870E-04 491280 + 601 491281 In-128m 1.36970E-04 1.50390E-04 491281 + 602 491282 In-128m 4.26470E-04 4.26470E-04 491282 + 603 491290 In-129 3.72810E-04 3.73460E-04 491290 + 604 491291 In-129m 8.62020E-05 8.64700E-05 491291 + 605 491300 In-130 3.12620E-05 3.13050E-05 491300 + 606 491301 In-130m 3.49170E-05 3.49170E-05 491301 + 607 491302 In-130m 5.94090E-05 5.94090E-05 491302 + 608 491310 In-131 8.82340E-06 8.91450E-06 491310 + 609 491311 In-131m 8.82340E-06 8.82340E-06 491311 + 610 491312 In-131m 8.82340E-06 8.82340E-06 491312 + 611 491320 In-132 3.64690E-06 3.64690E-06 491320 + 612 491330 In-133 1.17090E-08 1.44160E-08 491330 + 613 491331 In-133m 2.70730E-09 2.70730E-09 491331 + 614 501160 Sn-116 2.23560E-10 3.79450E-07 50116.82c + 615 501170 Sn-117 1.56730E-09 2.20430E-04 50117.82c + 616 501171 Sn-117m 5.12780E-09 4.93240E-07 501171 + 617 501180 Sn-118 1.03730E-07 2.04880E-04 50118.82c + 618 501190 Sn-119 2.84550E-07 2.37000E-04 50119.82c + 619 501191 Sn-119m 9.30950E-07 1.05790E-04 501191 + 620 501200 Sn-120 2.21960E-06 2.05290E-04 50120.82c + 621 501210 Sn-121 7.11190E-07 1.75830E-04 501210 + 622 501211 Sn-121m 1.71690E-06 1.69440E-05 501211 + 623 501220 Sn-122 1.89830E-05 2.43640E-04 50122.82c + 624 501230 Sn-123 3.18270E-05 4.63180E-05 50123.82c + 625 501231 Sn-123m 1.31840E-05 2.38300E-04 501231 + 626 501240 Sn-124 1.48330E-04 5.20250E-04 50124.82c + 627 501250 Sn-125 2.14780E-04 3.10300E-04 50125.82c + 628 501251 Sn-125m 8.89650E-05 6.85130E-04 501251 + 629 501260 Sn-126 1.18830E-03 1.99090E-03 50126.82c + 630 501270 Sn-127 2.75630E-03 3.26460E-03 501270 + 631 501271 Sn-127m 1.14170E-03 2.29460E-03 501271 + 632 501280 Sn-128 1.76130E-03 6.79990E-03 501280 + 633 501281 Sn-128m 4.12530E-03 4.55180E-03 501281 + 634 501290 Sn-129 1.18300E-03 1.60320E-03 501290 + 635 501291 Sn-129m 2.85580E-03 2.89560E-03 501291 + 636 501300 Sn-130 1.05890E-03 1.14060E-03 501300 + 637 501301 Sn-130m 2.48010E-03 2.52420E-03 501301 + 638 501310 Sn-131 5.58530E-04 5.75620E-04 501310 + 639 501311 Sn-131m 1.34840E-03 1.35760E-03 501311 + 640 501320 Sn-132 6.02570E-04 6.06230E-04 501320 + 641 501330 Sn-133 6.45880E-05 6.45900E-05 501330 + 642 501340 Sn-134 6.55670E-06 6.55670E-06 501340 + 643 501350 Sn-135 2.09170E-07 2.09170E-07 501350 + 644 501360 Sn-136 2.43560E-09 2.43560E-09 501360 + 645 511180 Sb-118 8.99520E-12 8.99520E-12 511180 + 646 511181 Sb-118m 1.27640E-11 1.27640E-11 511181 + 647 511190 Sb-119 6.61780E-10 8.72140E-10 511190 + 648 511191 Sb-119m 2.10360E-10 2.10360E-10 511191 + 649 511200 Sb-120 8.94760E-09 8.94760E-09 511200 + 650 511201 Sb-120m 1.26960E-08 1.26960E-08 511201 + 651 511210 Sb-121 2.36510E-07 1.79870E-04 51121.82c + 652 511220 Sb-122 5.92440E-07 1.26400E-06 511220 + 653 511221 Sb-122m 6.71560E-07 6.71560E-07 511221 + 654 511230 Sb-123 1.28210E-06 2.85900E-04 51123.82c + 655 511240 Sb-124 3.37860E-06 7.93660E-06 51124.82c + 656 511241 Sb-124m 2.58340E-06 6.07730E-06 511241 + 657 511242 Sb-124m 3.49400E-06 3.49400E-06 511242 + 658 511250 Sb-125 2.96490E-05 1.02510E-03 51125.82c + 659 511260 Sb-126 3.67830E-05 4.55700E-05 51126.82c + 660 511261 Sb-126m 2.71960E-05 6.27640E-05 511261 + 661 511262 Sb-126m 3.55680E-05 3.55680E-05 511262 + 662 511270 Sb-127 8.88850E-04 6.44810E-03 511270 + 663 511280 Sb-128 8.95520E-04 7.75050E-03 511280 + 664 511281 Sb-128m 1.52810E-03 1.52810E-03 511281 + 665 511290 Sb-129 4.93080E-03 8.65090E-03 511290 + 666 511291 Sb-129m 3.01320E-03 4.46090E-03 511291 + 667 511300 Sb-130 6.13650E-03 8.53920E-03 511300 + 668 511301 Sb-130m 6.13650E-03 7.39860E-03 511301 + 669 511310 Sb-131 1.95420E-02 2.14750E-02 511310 + 670 511320 Sb-132 6.85310E-03 7.45940E-03 511320 + 671 511321 Sb-132m 5.05090E-03 5.05090E-03 511321 + 672 511330 Sb-133 8.50410E-03 8.56980E-03 511330 + 673 511340 Sb-134 5.15010E-04 5.20480E-04 511340 + 674 511341 Sb-134m 1.20630E-03 1.20630E-03 511341 + 675 511350 Sb-135 3.88210E-04 3.88380E-04 511350 + 676 511360 Sb-136 3.57610E-05 3.57630E-05 511360 + 677 511370 Sb-137 7.15740E-06 7.15740E-06 511370 + 678 511380 Sb-138 2.08770E-08 2.08770E-08 511380 + 679 521200 Te-120 6.86440E-12 6.86440E-12 52120.82c + 680 521210 Te-121 4.73910E-11 1.84920E-10 521210 + 681 521211 Te-121m 1.55050E-10 1.55050E-10 521211 + 682 521240 Te-124 1.77340E-11 9.45590E-06 52124.82c + 683 521250 Te-125 4.49190E-10 1.02510E-03 52125.82c + 684 521251 Te-125m 1.46960E-09 2.29380E-04 521251 + 685 521260 Te-126 5.45700E-06 1.05000E-04 52126.82c + 686 521270 Te-127 6.93260E-06 6.44590E-03 521270 + 687 521271 Te-127m 1.67360E-05 1.07930E-03 52527.82c + 688 521280 Te-128 1.82710E-04 9.40620E-03 52128.82c + 689 521290 Te-129 1.91130E-04 1.10230E-02 521290 + 690 521291 Te-129m 4.61410E-04 5.60000E-03 52529.82c + 691 521300 Te-130 4.15510E-03 2.00930E-02 52130.82c + 692 521310 Te-131 3.47440E-03 2.53530E-02 521310 + 693 521311 Te-131m 8.38760E-03 1.01070E-02 521311 + 694 521320 Te-132 2.84730E-02 4.09830E-02 52132.82c + 695 521330 Te-133 9.65540E-03 2.10830E-02 521330 + 696 521331 Te-133m 2.33100E-02 2.47920E-02 521331 + 697 521340 Te-134 2.61120E-02 2.78990E-02 521340 + 698 521350 Te-135 9.14460E-03 9.47780E-03 521350 + 699 521360 Te-136 2.99530E-03 3.02860E-03 521360 + 700 521370 Te-137 4.89860E-04 4.93510E-04 521370 + 701 521380 Te-138 7.88390E-05 7.88600E-05 521380 + 702 521390 Te-139 4.95260E-06 4.95260E-06 521390 + 703 521400 Te-140 1.37230E-07 1.37230E-07 521400 + 704 521410 Te-141 1.96670E-09 1.96670E-09 521410 + 705 531270 I-127 1.02640E-09 6.47180E-03 53127.82c + 706 531280 I-128 6.89070E-08 6.89070E-08 531280 + 707 531290 I-129 6.05560E-06 1.31010E-02 53129.82c + 708 531300 I-130 4.61150E-05 6.26540E-05 53130.82c + 709 531301 I-130m 1.96890E-05 1.96890E-05 531301 + 710 531310 I-131 6.62910E-04 3.40000E-02 53131.82c + 711 531320 I-132 1.48210E-03 4.34050E-02 531320 + 712 531321 I-132m 1.09240E-03 1.09240E-03 531321 + 713 531330 I-133 1.00240E-02 5.76860E-02 531330 + 714 531331 I-133m 6.12570E-03 6.12570E-03 531331 + 715 531340 I-134 1.84030E-02 5.95540E-02 531340 + 716 531341 I-134m 1.35640E-02 1.35640E-02 531341 + 717 531350 I-135 6.14960E-02 7.09740E-02 53135.82c + 718 531360 I-136 9.73030E-03 1.27660E-02 531360 + 719 531361 I-136m 2.27910E-02 2.27980E-02 531361 + 720 531370 I-137 2.16730E-02 2.21570E-02 531370 + 721 531380 I-138 6.22530E-03 6.29920E-03 531380 + 722 531390 I-139 3.28030E-03 3.28520E-03 531390 + 723 531400 I-140 5.05180E-04 5.05320E-04 531400 + 724 531410 I-141 6.87200E-05 6.87220E-05 531410 + 725 531420 I-142 5.16750E-06 5.16750E-06 531420 + 726 531430 I-143 9.67010E-09 9.67010E-09 531430 + 727 541290 Xe-129 1.15020E-10 4.91350E-10 54129.82c + 728 541291 Xe-129m 3.76320E-10 3.76320E-10 541291 + 729 541300 Xe-130 3.13040E-08 6.58350E-05 54130.82c + 730 541310 Xe-131 8.64440E-07 3.40030E-02 54131.82c + 731 541311 Xe-131m 2.08690E-06 3.71390E-04 541311 + 732 541320 Xe-132 1.66900E-05 4.35930E-02 54132.82c + 733 541321 Xe-132m 1.89190E-05 1.89190E-05 541321 + 734 541330 Xe-133 9.95360E-05 5.80260E-02 54133.82c + 735 541331 Xe-133m 2.40290E-04 1.88230E-03 541331 + 736 541340 Xe-134 7.04680E-04 6.22210E-02 54134.82c + 737 541341 Xe-134m 1.65050E-03 1.96250E-03 541341 + 738 541350 Xe-135 2.91500E-03 8.08140E-02 54135.82c + 739 541351 Xe-135m 7.03730E-03 1.87540E-02 541351 + 740 541360 Xe-136 3.64710E-02 7.34760E-02 54136.82c + 741 541370 Xe-137 3.85220E-02 5.95720E-02 541370 + 742 541380 Xe-138 3.48910E-02 4.11780E-02 541380 + 743 541390 Xe-139 1.68490E-02 1.98590E-02 541390 + 744 541400 Xe-140 9.90660E-03 1.03790E-02 541400 + 745 541410 Xe-141 2.06000E-03 2.11560E-03 541410 + 746 541420 Xe-142 6.87010E-04 6.90890E-04 541420 + 747 541430 Xe-143 5.35850E-05 5.35910E-05 541430 + 748 541440 Xe-144 9.33220E-06 9.33220E-06 541440 + 749 541450 Xe-145 8.58590E-08 8.58590E-08 541450 + 750 541460 Xe-146 7.97720E-10 7.97720E-10 541460 + 751 551320 Cs-132 7.81210E-09 7.81210E-09 551320 + 752 551330 Cs-133 3.59100E-07 5.80260E-02 55133.82c + 753 551340 Cs-134 7.01490E-06 1.21850E-05 55134.82c + 754 551341 Cs-134m 5.17010E-06 5.17010E-06 551341 + 755 551350 Cs-135 1.32880E-04 8.11400E-02 55135.82c + 756 551351 Cs-135m 8.12010E-05 8.12010E-05 551351 + 757 551360 Cs-136 9.40450E-04 1.21600E-03 55136.82c + 758 551361 Cs-136m 5.51150E-04 5.51150E-04 551361 + 759 551370 Cs-137 1.24970E-02 7.20690E-02 55137.82c + 760 551380 Cs-138 1.16050E-02 6.61220E-02 551380 + 761 551381 Cs-138m 1.64670E-02 1.64670E-02 551381 + 762 551390 Cs-139 4.76520E-02 6.75110E-02 551390 + 763 551400 Cs-140 3.39050E-02 4.42850E-02 551400 + 764 551410 Cs-141 2.92100E-02 3.13270E-02 551410 + 765 551420 Cs-142 1.50320E-02 1.57210E-02 551420 + 766 551430 Cs-143 6.91540E-03 6.96870E-03 551430 + 767 551440 Cs-144 8.51050E-04 1.28560E-03 551440 + 768 551441 Cs-144m 8.51050E-04 8.51050E-04 551441 + 769 551450 Cs-145 4.64150E-04 4.64230E-04 551450 + 770 551460 Cs-146 5.88400E-05 5.88410E-05 551460 + 771 551470 Cs-147 1.01900E-05 1.01900E-05 551470 + 772 551480 Cs-148 4.77510E-09 4.77510E-09 551480 + 773 561340 Ba-134 2.09360E-09 1.21870E-05 56134.82c + 774 561350 Ba-135 4.32470E-08 1.47650E-07 56135.82c + 775 561351 Ba-135m 1.04400E-07 1.04400E-07 561351 + 776 561360 Ba-136 1.92300E-06 1.49800E-03 56136.82c + 777 561361 Ba-136m 4.50420E-06 4.50420E-06 561361 + 778 561370 Ba-137 3.06170E-05 7.21740E-02 56137.82c + 779 561371 Ba-137m 7.39130E-05 6.81070E-02 561371 + 780 561380 Ba-138 1.46170E-03 7.07120E-02 56138.82c + 781 561390 Ba-139 4.96150E-03 7.24730E-02 561390 + 782 561400 Ba-140 1.37600E-02 5.80450E-02 56140.82c + 783 561410 Ba-141 1.47860E-02 4.61130E-02 561410 + 784 561420 Ba-142 2.80930E-02 4.39280E-02 561420 + 785 561430 Ba-143 1.70620E-02 2.39580E-02 561430 + 786 561440 Ba-144 1.17870E-02 1.35230E-02 561440 + 787 561450 Ba-145 4.29470E-03 4.70090E-03 561450 + 788 561460 Ba-146 1.80210E-03 1.85550E-03 561460 + 789 561470 Ba-147 2.85950E-04 2.93240E-04 561470 + 790 561480 Ba-148 5.65520E-05 5.65560E-05 561480 + 791 561490 Ba-149 8.89390E-06 8.89390E-06 561490 + 792 561500 Ba-150 2.29990E-08 2.29990E-08 561500 + 793 561510 Ba-151 6.09240E-10 6.09240E-10 561510 + 794 571370 La-137 1.18300E-08 1.18300E-08 571370 + 795 571380 La-138 6.76990E-06 6.76990E-06 57138.82c + 796 571390 La-139 1.04360E-04 7.25770E-02 57139.82c + 797 571400 La-140 5.05190E-04 5.85500E-02 57140.82c + 798 571410 La-141 1.95620E-03 4.80690E-02 571410 + 799 571420 La-142 5.04830E-03 4.89760E-02 571420 + 800 571430 La-143 1.41660E-02 3.81240E-02 571430 + 801 571440 La-144 1.89010E-02 3.24240E-02 571440 + 802 571450 La-145 2.36170E-02 2.83180E-02 571450 + 803 571460 La-146 4.73780E-03 6.59330E-03 571460 + 804 571461 La-146m 8.52220E-03 8.52220E-03 571461 + 805 571470 La-147 9.76490E-03 1.00580E-02 571470 + 806 571480 La-148 3.37220E-03 3.42860E-03 571480 + 807 571490 La-149 1.14320E-03 1.15210E-03 571490 + 808 571500 La-150 2.03000E-04 2.03020E-04 571500 + 809 571510 La-151 2.65740E-05 2.65750E-05 571510 + 810 571520 La-152 2.54980E-06 2.54980E-06 571520 + 811 571530 La-153 1.42810E-09 1.42810E-09 571530 + 812 581390 Ce-139 8.09580E-10 2.76400E-09 581390 + 813 581391 Ce-139m 1.95440E-09 1.95440E-09 581391 + 814 581400 Ce-140 2.30790E-06 5.85530E-02 58140.82c + 815 581410 Ce-141 1.02300E-05 4.80800E-02 58141.82c + 816 581420 Ce-142 1.05820E-04 4.90820E-02 58142.82c + 817 581430 Ce-143 3.10450E-04 3.84340E-02 58143.82c + 818 581440 Ce-144 1.48050E-03 3.39050E-02 58144.82c + 819 581450 Ce-145 3.90600E-03 3.22240E-02 581450 + 820 581460 Ce-146 7.93610E-03 2.30520E-02 581460 + 821 581470 Ce-147 8.28290E-03 1.83410E-02 581470 + 822 581480 Ce-148 9.03800E-03 1.24830E-02 581480 + 823 581490 Ce-149 4.47750E-03 5.61890E-03 581490 + 824 581500 Ce-150 2.46670E-03 2.66420E-03 581500 + 825 581510 Ce-151 4.83980E-04 5.10710E-04 581510 + 826 581520 Ce-152 1.59770E-04 1.62170E-04 581520 + 827 581530 Ce-153 2.68440E-05 2.68450E-05 581530 + 828 581540 Ce-154 2.27900E-07 2.27900E-07 581540 + 829 581550 Ce-155 7.84010E-09 7.84010E-09 581550 + 830 581560 Ce-156 1.54930E-10 1.54930E-10 581560 + 831 591420 Pr-142 2.74840E-09 9.18600E-09 59142.82c + 832 591421 Pr-142m 6.43750E-09 6.43750E-09 591421 + 833 591430 Pr-143 4.47140E-06 3.84390E-02 59143.82c + 834 591440 Pr-144 1.89040E-06 3.39230E-02 591440 + 835 591441 Pr-144m 1.67900E-05 4.84660E-04 591441 + 836 591450 Pr-145 1.19060E-04 3.23430E-02 591450 + 837 591460 Pr-146 5.72620E-04 2.36240E-02 591460 + 838 591470 Pr-147 1.97820E-03 2.03200E-02 591470 + 839 591480 Pr-148 7.50750E-04 1.32330E-02 591480 + 840 591481 Pr-148m 3.15740E-03 3.15740E-03 591481 + 841 591490 Pr-149 6.85900E-03 1.24780E-02 591490 + 842 591500 Pr-150 6.43170E-03 9.09590E-03 591500 + 843 591510 Pr-151 5.87050E-03 6.38120E-03 591510 + 844 591520 Pr-152 3.30160E-03 3.46390E-03 591520 + 845 591530 Pr-153 1.74750E-03 1.77420E-03 591530 + 846 591540 Pr-154 3.17300E-04 3.17530E-04 591540 + 847 591550 Pr-155 6.98570E-05 6.98650E-05 591550 + 848 591560 Pr-156 1.30620E-05 1.30620E-05 591560 + 849 591570 Pr-157 1.39430E-08 1.39430E-08 591570 + 850 591580 Pr-158 1.91110E-10 1.91110E-10 591580 + 851 601440 Nd-144 1.11930E-09 3.39240E-02 60144.82c + 852 601450 Nd-145 5.84830E-08 3.23430E-02 60145.82c + 853 601460 Nd-146 1.78630E-06 2.36260E-02 60146.82c + 854 601470 Nd-147 1.61350E-05 2.03360E-02 60147.82c + 855 601480 Nd-148 1.10350E-04 1.65010E-02 60148.82c + 856 601490 Nd-149 3.67980E-04 1.28460E-02 601490 + 857 601500 Nd-150 1.01390E-03 1.01100E-02 60150.82c + 858 601510 Nd-151 1.52170E-03 7.90290E-03 601510 + 859 601520 Nd-152 2.66750E-03 6.13140E-03 601520 + 860 601530 Nd-153 2.53570E-03 4.30990E-03 601530 + 861 601540 Nd-154 1.59320E-03 1.91070E-03 601540 + 862 601550 Nd-155 5.87110E-04 6.57330E-04 601550 + 863 601560 Nd-156 2.01270E-04 2.13980E-04 601560 + 864 601570 Nd-157 3.60150E-05 3.60280E-05 601570 + 865 601580 Nd-158 3.87630E-06 3.87650E-06 601580 + 866 601590 Nd-159 5.22860E-08 5.22860E-08 601590 + 867 601600 Nd-160 6.46330E-10 6.46330E-10 601600 + 868 601610 Nd-161 1.67900E-11 1.67900E-11 601610 + 869 611470 Pm-147 3.30800E-09 2.03360E-02 61147.82c + 870 611480 Pm-148 2.64820E-07 2.95830E-07 61148.82c + 871 611481 Pm-148m 6.20260E-07 6.20260E-07 61548.82c + 872 611490 Pm-149 8.00280E-06 1.28540E-02 61149.82c + 873 611500 Pm-150 3.54270E-05 3.54270E-05 611500 + 874 611510 Pm-151 1.47630E-04 8.05050E-03 61151.82c + 875 611520 Pm-152 1.02660E-04 6.23410E-03 611520 + 876 611521 Pm-152m 2.05000E-04 2.05000E-04 611521 + 877 611522 Pm-152m 2.26750E-04 2.26750E-04 611522 + 878 611530 Pm-153 1.36370E-03 5.67360E-03 611530 + 879 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Sm-156 5.11150E-04 2.31330E-03 621560 + 899 621570 Sm-157 5.22890E-04 1.41000E-03 621570 + 900 621580 Sm-158 2.99630E-04 4.84150E-04 621580 + 901 621590 Sm-159 2.53590E-04 3.26060E-04 621590 + 902 621600 Sm-160 4.21060E-05 4.91230E-05 621600 + 903 621610 Sm-161 2.77770E-05 2.78170E-05 621610 + 904 621620 Sm-162 7.94030E-07 7.94860E-07 621620 + 905 621630 Sm-163 6.21610E-08 6.21740E-08 621630 + 906 621640 Sm-164 2.49680E-09 2.49680E-09 621640 + 907 621650 Sm-165 3.37280E-11 3.37280E-11 621650 + 908 631520 Eu-152 5.20590E-10 1.10120E-09 63152.82c + 909 631521 Eu-152m 1.23990E-10 1.23990E-10 631521 + 910 631522 Eu-152m 5.80620E-10 5.80620E-10 631522 + 911 631530 Eu-153 3.49230E-08 5.69860E-03 63153.82c + 912 631540 Eu-154 1.65670E-06 3.14910E-06 63154.82c + 913 631541 Eu-154m 1.49240E-06 1.49240E-06 631541 + 914 631550 Eu-155 1.31170E-05 2.90700E-03 63155.82c + 915 631560 Eu-156 5.44120E-05 2.36770E-03 63156.82c + 916 631570 Eu-157 1.74140E-04 1.58410E-03 63157.82c + 917 631580 Eu-158 1.52300E-04 6.36450E-04 631580 + 918 631590 Eu-159 3.52990E-04 6.79050E-04 631590 + 919 631600 Eu-160 1.86920E-04 2.36040E-04 631600 + 920 631610 Eu-161 1.41970E-04 1.69790E-04 631610 + 921 631620 Eu-162 4.81480E-05 4.89430E-05 631620 + 922 631630 Eu-163 1.15480E-05 1.16100E-05 631630 + 923 631640 Eu-164 5.57590E-06 5.57840E-06 631640 + 924 631650 Eu-165 2.88710E-08 2.89050E-08 631650 + 925 631660 Eu-166 3.60970E-09 3.60970E-09 631660 + 926 631670 Eu-167 3.05030E-11 3.05030E-11 631670 + 927 641540 Gd-154 1.20140E-10 3.14860E-06 64154.82c + 928 641550 Gd-155 1.54180E-09 2.90700E-03 64155.82c + 929 641551 Gd-155m 3.72210E-09 3.72210E-09 641551 + 930 641560 Gd-156 1.04500E-07 2.36780E-03 64156.82c + 931 641570 Gd-157 2.56190E-06 1.58670E-03 64157.82c + 932 641580 Gd-158 1.15970E-05 6.49660E-04 64158.82c + 933 641590 Gd-159 2.50880E-05 7.04130E-04 641590 + 934 641600 Gd-160 3.74260E-05 2.73470E-04 64160.82c + 935 641610 Gd-161 4.32070E-05 2.12990E-04 641610 + 936 641620 Gd-162 2.67480E-05 7.56910E-05 641620 + 937 641630 Gd-163 2.02090E-05 3.18190E-05 641630 + 938 641640 Gd-164 1.11510E-05 1.67290E-05 641640 + 939 641650 Gd-165 4.95990E-06 4.98880E-06 641650 + 940 641660 Gd-166 9.56180E-07 9.59790E-07 641660 + 941 641670 Gd-167 3.91510E-08 3.91810E-08 641670 + 942 641680 Gd-168 8.56090E-09 8.56090E-09 641680 + 943 641690 Gd-169 1.40860E-10 1.40860E-10 641690 + 944 651570 Tb-157 2.50910E-10 2.50910E-10 651570 + 945 651580 Tb-158 1.73910E-06 1.93370E-06 651580 + 946 651581 Tb-158m 1.95810E-07 1.95810E-07 651581 + 947 651590 Tb-159 9.58690E-08 7.04230E-04 65159.82c + 948 651600 Tb-160 2.33990E-06 2.33990E-06 65160.82c + 949 651610 Tb-161 3.08620E-06 2.16080E-04 651610 + 950 651620 Tb-162 5.34970E-06 8.10410E-05 651620 + 951 651630 Tb-163 2.02090E-05 5.20280E-05 651630 + 952 651640 Tb-164 2.23030E-05 3.90320E-05 651640 + 953 651650 Tb-165 7.43980E-06 1.24290E-05 651650 + 954 651660 Tb-166 1.38030E-05 1.47630E-05 651660 + 955 651670 Tb-167 1.69780E-06 1.73700E-06 651670 + 956 651680 Tb-168 7.64620E-07 7.73180E-07 651680 + 957 651690 Tb-169 3.28710E-08 3.30120E-08 651690 + 958 651700 Tb-170 5.20000E-09 5.20000E-09 651700 + 959 651710 Tb-171 2.09840E-10 2.09840E-10 651710 + 960 661590 Dy-159 2.74470E-11 2.74470E-11 661590 + 961 661600 Dy-160 4.24750E-10 2.34030E-06 66160.82c + 962 661610 Dy-161 1.12740E-08 2.16090E-04 66161.82c + 963 661620 Dy-162 6.15900E-08 8.11020E-05 66162.82c + 964 661630 Dy-163 4.72460E-07 5.25010E-05 66163.82c + 965 661640 Dy-164 1.88200E-06 4.09170E-05 66164.82c + 966 661650 Dy-165 2.28770E-06 1.50580E-05 661650 + 967 661651 Dy-165m 3.49720E-07 3.49720E-07 661651 + 968 661660 Dy-166 2.76070E-06 1.75230E-05 661660 + 969 661670 Dy-167 2.68680E-06 4.42380E-06 661670 + 970 661680 Dy-168 5.52550E-06 6.29870E-06 661680 + 971 661690 Dy-169 1.03560E-06 1.06860E-06 661690 + 972 661700 Dy-170 3.97990E-07 4.03190E-07 661700 + 973 661710 Dy-171 7.49240E-08 7.51340E-08 661710 + 974 661720 Dy-172 6.47500E-09 6.47500E-09 661720 + 975 661730 Dy-173 4.40190E-10 4.40190E-10 661730 + 976 671620 Ho-162 4.46380E-12 1.09460E-11 671620 + 977 671621 Ho-162m 1.04550E-11 1.04550E-11 671621 + 978 671630 Ho-163 2.74050E-10 3.15950E-10 671630 + 979 671631 Ho-163m 4.18950E-11 4.18950E-11 671631 + 980 671640 Ho-164 1.83460E-09 6.13160E-09 671640 + 981 671641 Ho-164m 4.29700E-09 4.29700E-09 671641 + 982 671650 Ho-165 2.21040E-08 1.50880E-05 67165.82c + 983 671660 Ho-166 8.12360E-08 1.76050E-05 671660 + 984 671661 Ho-166m 1.90270E-07 1.90270E-07 671661 + 985 671670 Ho-167 1.69780E-06 6.12160E-06 671670 + 986 671680 Ho-168 1.14210E-06 9.05330E-06 671680 + 987 671681 Ho-168m 1.62060E-06 1.62060E-06 671681 + 988 671690 Ho-169 1.88710E-06 2.95570E-06 671690 + 989 671700 Ho-170 7.73820E-07 7.73820E-07 671700 + 990 671701 Ho-170m 3.30380E-07 7.33570E-07 671701 + 991 671710 Ho-171 4.61010E-07 5.36140E-07 671710 + 992 671720 Ho-172 1.71220E-07 1.77700E-07 671720 + 993 671730 Ho-173 2.90660E-08 2.95060E-08 671730 + 994 671740 Ho-174 4.92690E-09 4.92690E-09 671740 + 995 671750 Ho-175 3.57380E-10 3.57380E-10 671750 + 996 681640 Er-164 1.30520E-12 3.17130E-09 68164.82c + 997 681650 Er-165 2.21640E-11 2.21640E-11 681650 + 998 681660 Er-166 7.41100E-10 1.76050E-05 68166.82c + 999 681670 Er-167 2.61780E-09 6.12460E-06 68167.82c + 1000 681671 Er-167m 4.00190E-10 7.31880E-07 681671 + 1001 681680 Er-168 6.46660E-08 9.12610E-06 68168.82c + 1002 681690 Er-169 1.05510E-07 3.06120E-06 681690 + 1003 681700 Er-170 3.50190E-07 1.85760E-06 68170.82c + 1004 681710 Er-171 5.67590E-07 1.10370E-06 681710 + 1005 681720 Er-172 4.43010E-07 6.20700E-07 681720 + 1006 681730 Er-173 2.96360E-07 3.25870E-07 681730 + 1007 681740 Er-174 1.14780E-07 1.19710E-07 681740 + 1008 681750 Er-175 3.68730E-08 3.72300E-08 681750 + 1009 681760 Er-176 5.09560E-09 5.09560E-09 681760 + 1010 681770 Er-177 5.53290E-10 5.53290E-10 681770 + 1011 691680 Tm-168 5.83360E-11 5.83360E-11 691680 + 1012 691690 Tm-169 2.54140E-10 3.06150E-06 691690 + 1013 691700 Tm-170 3.95650E-09 3.95650E-09 691700 + 1014 691710 Tm-171 1.56850E-08 1.11940E-06 691710 + 1015 691720 Tm-172 5.13820E-08 6.72090E-07 691720 + 1016 691730 Tm-173 7.47140E-08 4.00580E-07 691730 + 1017 691740 Tm-174 1.11020E-07 2.30730E-07 691740 + 1018 691750 Tm-175 7.56530E-08 1.12880E-07 691750 + 1019 691760 Tm-176 4.22720E-08 4.73680E-08 691760 + 1020 691770 Tm-177 1.08180E-08 1.13710E-08 691770 + 1021 691780 Tm-178 2.80710E-09 2.80710E-09 691780 + 1022 691790 Tm-179 3.24820E-10 3.24820E-10 691790 + 1023 701700 Yb-170 2.94730E-12 3.95430E-09 701700 + 1024 701710 Yb-171 7.65010E-12 1.11950E-06 701710 + 1025 701711 Yb-171m 5.00430E-11 5.00430E-11 701711 + 1026 701720 Yb-172 4.96030E-10 6.72580E-07 701720 + 1027 701730 Yb-173 3.30430E-09 4.03890E-07 701730 + 1028 701740 Yb-174 1.16590E-08 2.42420E-07 701740 + 1029 701750 Yb-175 2.80620E-08 1.45230E-07 701750 + 1030 701751 Yb-175m 4.28990E-09 9.12100E-08 701751 + 1031 701760 Yb-176 1.37520E-08 8.10150E-08 701760 + 1032 701761 Yb-176m 2.47370E-08 4.84210E-08 701761 + 1033 701770 Yb-177 3.06520E-08 4.91110E-08 701770 + 1034 701771 Yb-177m 7.08760E-09 1.84590E-08 701771 + 1035 701780 Yb-178 2.11650E-08 2.39720E-08 701780 + 1036 701790 Yb-179 1.02020E-08 1.05270E-08 701790 + 1037 701800 Yb-180 2.42600E-09 2.42600E-09 701800 + 1038 701810 Yb-181 4.56360E-10 4.56360E-10 701810 + 1039 711730 Lu-173 2.20540E-12 2.20540E-12 711730 + 1040 711740 Lu-174 1.13280E-11 3.77080E-11 711740 + 1041 711741 Lu-174m 2.65340E-11 2.65340E-11 711741 + 1042 711750 Lu-175 2.70240E-10 1.45510E-07 71175.82c + 1043 711760 Lu-176 9.21570E-10 5.76360E-09 71176.82c + 1044 711761 Lu-176m 5.12330E-10 5.12330E-10 711761 + 1045 711770 Lu-177 2.30600E-09 5.16240E-08 711770 + 1046 711771 Lu-177m 9.01480E-10 9.16040E-10 711771 + 1047 711772 Lu-177m 2.91320E-11 2.91320E-11 711772 + 1048 711780 Lu-178 3.37210E-09 2.73440E-08 711780 + 1049 711781 Lu-178m 3.82240E-09 3.82240E-09 711781 + 1050 711790 Lu-179 6.32960E-09 1.78240E-08 711790 + 1051 711791 Lu-179m 9.67610E-10 1.14940E-08 711791 + 1052 711800 Lu-180 1.93220E-09 5.53510E-09 711800 + 1053 711801 Lu-180m 1.93220E-09 4.35820E-09 711801 + 1054 711802 Lu-180m 2.84770E-09 2.84770E-09 711802 + 1055 711810 Lu-181 2.79950E-09 3.25590E-09 711810 + 1056 711820 Lu-182 1.03930E-09 1.03930E-09 711820 + 1057 711830 Lu-183 1.76460E-10 1.76460E-10 711830 + 1058 711840 Lu-184 2.99350E-11 2.99350E-11 711840 + 1059 721760 Hf-176 3.89800E-12 5.15740E-10 72176.82c + 1060 721770 Hf-177 3.00070E-11 5.23900E-08 72177.82c + 1061 721771 Hf-177m 1.16590E-11 7.35690E-10 721771 + 1062 721772 Hf-177m 4.50690E-13 1.50170E-11 721772 + 1063 721780 Hf-178 8.40580E-11 3.14020E-08 72178.82c + 1064 721781 Hf-178m 1.38690E-10 3.97360E-09 721781 + 1065 721782 Hf-178m 1.25160E-11 1.25160E-11 721782 + 1066 721790 Hf-179 6.21570E-10 1.88600E-08 72179.82c + 1067 721791 Hf-179m 1.94030E-10 1.94030E-10 721791 + 1068 721792 Hf-179m 2.17590E-10 2.17590E-10 721792 + 1069 721800 Hf-180 7.58300E-10 1.12610E-08 72180.82c + 1070 721801 Hf-180m 1.36400E-09 2.78780E-09 721801 + 1071 721810 Hf-181 3.43690E-09 6.69280E-09 721810 + 1072 721820 Hf-182 9.58060E-10 2.72120E-09 721820 + 1073 721821 Hf-182m 1.72330E-09 1.72330E-09 721821 + 1074 721830 Hf-183 1.79380E-09 1.97030E-09 721830 + 1075 721840 Hf-184 2.48390E-10 2.63360E-10 721840 + 1076 721841 Hf-184m 4.46800E-10 4.61770E-10 721841 + 1077 721850 Hf-185 2.23540E-10 2.23540E-10 721850 + 1078 721860 Hf-186 3.09320E-11 3.09320E-11 721860 + 1079 721870 Hf-187 3.36260E-12 3.36260E-12 721870 + 1080 731790 Ta-179 1.88210E-12 2.48020E-12 731790 + 1081 731800 Ta-180 1.12010E-11 1.12010E-11 731800 + 1082 731801 Ta-180m 1.26970E-11 2.13390E-11 731801 + 1083 731810 Ta-181 9.46730E-11 6.78740E-09 73181.82c + 1084 731820 Ta-182 1.10790E-10 1.30960E-09 73182.82c + 1085 731821 Ta-182m 1.13080E-10 1.19880E-09 731821 + 1086 731822 Ta-182m 8.62000E-11 1.08570E-09 731822 + 1087 731830 Ta-183 4.50950E-10 2.42120E-09 731830 + 1088 731840 Ta-184 6.70530E-10 1.39570E-09 731840 + 1089 731850 Ta-185 3.08090E-10 6.80850E-10 731850 + 1090 731851 Ta-185m 1.49220E-10 1.49220E-10 731851 + 1091 731860 Ta-186 2.55810E-10 2.86740E-10 731860 + 1092 731870 Ta-187 6.55360E-11 6.88990E-11 731870 + 1093 731880 Ta-188 1.70230E-11 1.70230E-11 731880 + 1094 731890 Ta-189 1.97160E-12 1.97160E-12 731890 + 1095 741820 W-182 2.98320E-12 1.31260E-09 74182.82c + 1096 741830 W-183 4.65370E-12 2.44110E-09 74183.82c + 1097 741831 W-183m 1.52250E-11 9.75460E-11 741831 + 1098 741840 W-184 7.02040E-11 1.46590E-09 74184.82c + 1099 741850 W-185 5.71130E-11 8.75840E-10 741850 + 1100 741851 W-185m 1.37880E-10 1.37880E-10 741851 + 1101 741860 W-186 1.75610E-10 5.19250E-10 74186.82c + 1102 741861 W-186m 5.66480E-11 5.66480E-11 741861 + 1103 741870 W-187 2.27980E-10 2.96880E-10 741870 + 1104 741880 W-188 1.27970E-10 1.44990E-10 741880 + 1105 741890 W-189 6.17280E-11 6.37000E-11 741890 + 1106 741900 W-190 6.89080E-12 1.47020E-11 741900 + 1107 741901 W-190m 7.81120E-12 7.81120E-12 741901 + 1108 741910 W-191 2.76970E-12 2.76970E-12 741910 + 1109 751850 Re-185 1.62340E-12 8.77460E-10 75185.82c + 1110 751860 Re-186 3.56580E-12 3.56580E-12 751860 + 1111 751861 Re-186m 5.05970E-12 5.05970E-12 751861 + 1112 751870 Re-187 1.94950E-11 3.16370E-10 75187.82c + 1113 751880 Re-188 1.29780E-11 1.88370E-10 751880 + 1114 751881 Re-188m 3.03980E-11 3.03980E-11 751881 + 1115 751890 Re-189 4.40310E-11 1.07730E-10 751890 + 1116 751900 Re-190 1.44900E-11 4.10760E-11 751900 + 1117 751901 Re-190m 2.60630E-11 2.60630E-11 751901 + 1118 751910 Re-191 1.69380E-11 1.97080E-11 751910 + 1119 751920 Re-192 6.29450E-12 6.29450E-12 751920 + 1120 751930 Re-193 1.06980E-12 1.06980E-12 751930 + 1121 761880 Os-188 1.41380E-12 1.89780E-10 761880 + 1122 761890 Os-189 1.45500E-12 1.13950E-10 761890 + 1123 761891 Os-189m 4.76020E-12 1.58380E-11 761891 + 1124 761900 Os-190 5.99330E-12 6.80420E-11 761900 + 1125 761901 Os-190m 6.79370E-12 2.09720E-11 761901 + 1126 761910 Os-191 1.58820E-11 4.04450E-11 761910 + 1127 761911 Os-191m 4.85450E-12 4.85450E-12 761911 + 1128 761920 Os-192 7.59010E-12 2.15130E-11 761920 + 1129 761921 Os-192m 8.60390E-12 8.60390E-12 761921 + 1130 761930 Os-193 1.08430E-11 1.19130E-11 761930 + 1131 761940 Os-194 4.20730E-12 4.20730E-12 761940 + 1132 761950 Os-195 1.35460E-12 1.35460E-12 761950 + 1133 771920 Ir-192 6.22270E-13 2.98520E-12 771920 + 1134 771922 Ir-192m 6.22270E-13 1.74080E-12 771922 + 1135 771930 Ir-193 7.96160E-13 1.46310E-11 77193.82c + 1136 771931 Ir-193m 1.92200E-12 1.96340E-12 771931 + 1137 771940 Ir-194 1.34870E-12 6.90480E-12 771940 + 1138 771941 Ir-194m 1.34870E-12 1.34870E-12 771941 + 1139 771942 Ir-194m 1.34870E-12 1.34870E-12 771942 + 1140 771950 Ir-195 8.09340E-13 2.26160E-12 771950 + 1141 771951 Ir-195m 1.95390E-12 1.95390E-12 771951 + 1142 781950 Pt-195 3.44070E-13 5.29250E-12 781950 + 1143 781951 Pt-195m 8.30630E-13 1.42460E-12 781951 + 1144 781960 Pt-196 1.40120E-12 2.94880E-12 781960 + + Neutron-induced fission: + + Interpolation region : 2 / 2 + Interpolation energy : 4.00000E-01 MeV + Number of products : 1155 / 1203 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 3.74900E-05 3.74900E-05 1001.82c + 2 10020 H-2 1.14570E-05 1.14570E-05 1002.82c + 3 10030 H-3 1.65000E-04 1.65000E-04 1003.82c + 4 20040 He-4 2.37000E-03 2.37000E-03 2004.82c + 5 190500 K-50 1.01300E-12 1.01300E-12 190500 + 6 200500 Ca-50 8.49820E-12 9.21740E-12 200500 + 7 200510 Ca-51 1.16620E-11 1.16620E-11 200510 + 8 200520 Ca-52 7.80820E-12 7.80820E-12 200520 + 9 200530 Ca-53 3.97850E-12 3.97850E-12 200530 + 10 210500 Sc-50 2.31440E-12 1.22550E-11 210500 + 11 210501 Sc-50m 8.49080E-13 1.00660E-11 210501 + 12 210510 Sc-51 9.47580E-12 2.12940E-11 210510 + 13 210520 Sc-52 2.43930E-11 3.32390E-11 210520 + 14 210530 Sc-53 2.88530E-11 3.16380E-11 210530 + 15 210540 Sc-54 2.97820E-11 2.97820E-11 210540 + 16 210550 Sc-55 1.43290E-11 1.43290E-11 210550 + 17 210560 Sc-56 6.47030E-12 6.47030E-12 210560 + 18 210570 Sc-57 1.25750E-12 1.25750E-12 210570 + 19 220510 Ti-51 1.47270E-12 2.27670E-11 220510 + 20 220520 Ti-52 8.74600E-12 4.19850E-11 220520 + 21 220530 Ti-53 3.96440E-11 7.12820E-11 220530 + 22 220540 Ti-54 8.94320E-11 1.19210E-10 220540 + 23 220550 Ti-55 1.69220E-10 1.83550E-10 220550 + 24 220560 Ti-56 1.83350E-10 1.90230E-10 220560 + 25 220570 Ti-57 1.58260E-10 1.59100E-10 220570 + 26 220580 Ti-58 5.92100E-11 5.92100E-11 220580 + 27 220590 Ti-59 1.68820E-11 1.68820E-11 220590 + 28 220600 Ti-60 2.56450E-12 2.56450E-12 220600 + 29 230530 V-53 1.28500E-12 7.25670E-11 230530 + 30 230540 V-54 1.19730E-11 1.31190E-10 230540 + 31 230550 V-55 5.08260E-11 2.34370E-10 230550 + 32 230560 V-56 2.08970E-10 3.99680E-10 230560 + 33 230570 V-57 3.99540E-10 5.58170E-10 230570 + 34 230580 V-58 6.05660E-10 6.64870E-10 230580 + 35 230590 V-59 4.28580E-10 4.45460E-10 230590 + 36 230600 V-60 2.97580E-10 3.00140E-10 230600 + 37 230610 V-61 9.33340E-11 9.33340E-11 230610 + 38 230620 V-62 2.28560E-11 2.28560E-11 230620 + 39 230630 V-63 2.32370E-12 2.32370E-12 230630 + 40 240550 Cr-55 2.61580E-12 2.36990E-10 240550 + 41 240560 Cr-56 2.63210E-11 4.28240E-10 240560 + 42 240570 Cr-57 2.01240E-10 1.28910E-09 240570 + 43 240580 Cr-58 6.71040E-10 8.04010E-10 240580 + 44 240590 Cr-59 1.80660E-09 2.25210E-09 240590 + 45 240600 Cr-60 2.84490E-09 3.15060E-09 240600 + 46 240610 Cr-61 3.73780E-09 3.82550E-09 240610 + 47 240620 Cr-62 2.34520E-09 2.36890E-09 240620 + 48 240630 Cr-63 1.11720E-09 1.11870E-09 240630 + 49 240640 Cr-64 2.54970E-10 2.54970E-10 240640 + 50 240650 Cr-65 4.44890E-11 4.44890E-11 240650 + 51 240660 Cr-66 3.95200E-12 3.95200E-12 240660 + 52 250570 Mn-57 2.10140E-12 1.29120E-09 250570 + 53 250580 Mn-58 2.79650E-11 8.31980E-10 250580 + 54 250581 Mn-58m 2.74890E-12 2.74890E-12 250581 + 55 250590 Mn-59 1.95650E-10 2.44770E-09 250590 + 56 250600 Mn-60 1.07310E-10 3.38350E-09 250600 + 57 250601 Mn-60m 1.09170E-09 1.09170E-09 250601 + 58 250610 Mn-61 3.43570E-09 7.26120E-09 250610 + 59 250620 Mn-62 7.19620E-09 8.38060E-09 250620 + 60 250621 Mn-62m 1.12690E-09 2.31140E-09 250621 + 61 250630 Mn-63 9.26930E-09 1.03880E-08 250630 + 62 250640 Mn-64 9.16500E-09 9.42000E-09 250640 + 63 250650 Mn-65 4.21510E-09 4.25960E-09 250650 + 64 250660 Mn-66 1.79030E-09 1.79430E-09 250660 + 65 250670 Mn-67 3.25330E-10 3.25330E-10 250670 + 66 250680 Mn-68 1.44190E-10 1.44190E-10 250680 + 67 250690 Mn-69 5.66460E-12 5.66460E-12 250690 + 68 260590 Fe-59 3.16210E-12 2.45090E-09 260590 + 69 260600 Fe-60 5.01830E-11 4.39980E-09 260600 + 70 260610 Fe-61 6.09860E-10 7.87110E-09 260610 + 71 260620 Fe-62 3.38570E-09 1.40780E-08 260620 + 72 260630 Fe-63 1.44030E-08 2.47910E-08 260630 + 73 260640 Fe-64 3.11850E-08 4.06050E-08 260640 + 74 260650 Fe-65 5.67490E-08 6.10090E-08 260650 + 75 260660 Fe-66 5.82730E-08 6.00670E-08 260660 + 76 260670 Fe-67 4.73390E-08 4.76640E-08 260670 + 77 260680 Fe-68 5.66670E-08 5.68130E-08 260680 + 78 260690 Fe-69 1.08140E-08 1.08180E-08 260690 + 79 260700 Fe-70 6.49330E-10 6.49330E-10 260700 + 80 260710 Fe-71 3.14220E-11 3.14220E-11 260710 + 81 270610 Co-61 1.95540E-12 7.87300E-09 270610 + 82 270620 Co-62 1.34440E-11 1.40920E-08 270620 + 83 270621 Co-62m 3.66450E-11 3.66450E-11 270621 + 84 270630 Co-63 5.35150E-10 2.53260E-08 270630 + 85 270640 Co-64 4.75030E-09 4.53550E-08 270640 + 86 270650 Co-65 1.92930E-08 8.03020E-08 270650 + 87 270660 Co-66 7.51410E-08 1.35210E-07 270660 + 88 270670 Co-67 1.35820E-07 1.83480E-07 270670 + 89 270680 Co-68 3.79880E-07 5.50440E-07 270680 + 90 270681 Co-68m 2.83550E-07 3.41120E-07 270681 + 91 270690 Co-69 3.16500E-07 3.26560E-07 270690 + 92 270700 Co-70 4.36870E-08 4.36870E-08 270700 + 93 270701 Co-70m 4.36870E-08 4.43360E-08 270701 + 94 270710 Co-71 1.16580E-08 1.16890E-08 270710 + 95 270720 Co-72 1.61970E-09 1.61970E-09 270720 + 96 270730 Co-73 1.09710E-10 1.09710E-10 270730 + 97 270740 Co-74 4.31530E-11 4.31530E-11 270740 + 98 270750 Co-75 1.16950E-12 1.16950E-12 270750 + 99 280630 Ni-63 2.60440E-12 2.53290E-08 280630 + 100 280640 Ni-64 6.26370E-11 4.54180E-08 28064.82c + 101 280650 Ni-65 1.14200E-09 8.14440E-08 280650 + 102 280660 Ni-66 1.08050E-08 1.46010E-07 280660 + 103 280670 Ni-67 7.75880E-08 2.61070E-07 280670 + 104 280680 Ni-68 1.58500E-06 2.30930E-06 280680 + 105 280690 Ni-69 9.15700E-07 1.23900E-06 280690 + 106 280691 Ni-69m 9.15700E-07 9.15700E-07 280691 + 107 280700 Ni-70 9.52690E-07 1.04070E-06 280700 + 108 280710 Ni-71 5.36510E-07 5.48200E-07 280710 + 109 280720 Ni-72 1.92240E-07 1.93860E-07 280720 + 110 280730 Ni-73 6.12970E-08 6.14070E-08 280730 + 111 280740 Ni-74 6.75000E-08 6.75430E-08 280740 + 112 280750 Ni-75 1.09040E-08 1.09050E-08 280750 + 113 280760 Ni-76 1.06610E-09 1.06610E-09 280760 + 114 280770 Ni-77 5.32590E-11 5.32590E-11 280770 + 115 290650 Cu-65 1.08350E-12 8.14450E-08 29065.82c + 116 290660 Cu-66 4.92100E-11 1.46060E-07 290660 + 117 290670 Cu-67 9.34870E-10 2.62010E-07 290670 + 118 290680 Cu-68 1.17000E-08 2.34780E-06 290680 + 119 290681 Cu-68m 3.18920E-08 3.18920E-08 290681 + 120 290690 Cu-69 1.86250E-07 2.34100E-06 290690 + 121 290700 Cu-70 3.07630E-08 2.53990E-07 290700 + 122 290701 Cu-70m 3.92870E-07 4.46450E-07 290701 + 123 290702 Cu-70m 3.07630E-08 1.07150E-06 290702 + 124 290710 Cu-71 5.58020E-07 1.10620E-06 290710 + 125 290720 Cu-72 7.75570E-07 9.69430E-07 290720 + 126 290730 Cu-73 5.82380E-07 6.43790E-07 290730 + 127 290740 Cu-74 2.79850E-06 2.86620E-06 290740 + 128 290750 Cu-75 1.19840E-06 1.20910E-06 290750 + 129 290760 Cu-76 2.81200E-07 2.81730E-07 290760 + 130 290761 Cu-76m 2.81200E-07 2.81730E-07 290761 + 131 290770 Cu-77 8.21790E-08 8.22320E-08 290770 + 132 290780 Cu-78 1.24470E-08 1.24470E-08 290780 + 133 290790 Cu-79 6.81950E-10 6.81950E-10 290790 + 134 290800 Cu-80 3.41460E-11 3.41460E-11 290800 + 135 300670 Zn-67 1.32710E-12 2.62010E-07 300670 + 136 300680 Zn-68 1.73440E-10 2.35300E-06 300680 + 137 300690 Zn-69 5.83850E-10 2.34440E-06 300690 + 138 300691 Zn-69m 2.89980E-09 2.89980E-09 300691 + 139 300700 Zn-70 2.18660E-08 1.51700E-06 300700 + 140 300710 Zn-71 2.07670E-07 1.31390E-06 300710 + 141 300711 Zn-71m 1.03140E-06 1.03140E-06 300711 + 142 300720 Zn-72 1.36970E-06 2.33910E-06 300720 + 143 300730 Zn-73 1.44570E-07 1.64040E-06 300730 + 144 300731 Zn-73m 1.99960E-07 8.52030E-07 300731 + 145 300732 Zn-73m 1.30410E-06 1.30410E-06 300732 + 146 300740 Zn-74 1.49350E-05 1.78430E-05 300740 + 147 300750 Zn-75 1.61230E-05 1.72980E-05 300750 + 148 300760 Zn-76 2.43390E-05 2.48940E-05 300760 + 149 300770 Zn-77 1.10090E-05 1.18240E-05 300770 + 150 300771 Zn-77m 1.46580E-06 1.46580E-06 300771 + 151 300780 Zn-78 1.91660E-05 1.91790E-05 300780 + 152 300790 Zn-79 1.52890E-06 1.52920E-06 300790 + 153 300800 Zn-80 2.05400E-07 2.05430E-07 300800 + 154 300810 Zn-81 1.61340E-08 1.61340E-08 300810 + 155 300820 Zn-82 5.76090E-10 5.76090E-10 300820 + 156 310700 Ga-70 2.95510E-11 2.95510E-11 310700 + 157 310710 Ga-71 4.20390E-10 2.34570E-06 310710 + 158 310720 Ga-72 5.55780E-09 2.34520E-06 310720 + 159 310721 Ga-72m 5.46320E-10 7.84870E-08 310721 + 160 310730 Ga-73 4.35430E-08 2.33600E-06 310730 + 161 310740 Ga-74 9.34750E-07 1.50190E-05 310740 + 162 310741 Ga-74m 9.34750E-07 1.87780E-05 310741 + 163 310750 Ga-75 6.90790E-06 2.42060E-05 310750 + 164 310760 Ga-76 2.18910E-05 4.67850E-05 310760 + 165 310770 Ga-77 4.49050E-05 5.74620E-05 310770 + 166 310780 Ga-78 4.92830E-05 6.84820E-05 310780 + 167 310790 Ga-79 6.61330E-05 6.76420E-05 310790 + 168 310800 Ga-80 3.44200E-05 3.46270E-05 310800 + 169 310810 Ga-81 1.09620E-05 1.09770E-05 310810 + 170 310820 Ga-82 1.26520E-06 1.26580E-06 310820 + 171 310830 Ga-83 1.09750E-07 1.09750E-07 310830 + 172 310840 Ga-84 7.34410E-09 7.34410E-09 310840 + 173 310850 Ga-85 1.08350E-10 1.08350E-10 310850 + 174 320720 Ge-72 7.11370E-12 2.34520E-06 32072.82c + 175 320730 Ge-73 2.05020E-10 2.33620E-06 32073.82c + 176 320731 Ge-73m 4.12800E-11 2.30170E-06 320731 + 177 320740 Ge-74 2.85150E-08 1.97420E-05 32074.82c + 178 320750 Ge-75 2.70550E-07 2.65080E-05 320750 + 179 320751 Ge-75m 2.03200E-06 3.00030E-06 320751 + 180 320760 Ge-76 1.21580E-05 5.89430E-05 32076.82c + 181 320770 Ge-77 3.07910E-05 4.24880E-05 320770 + 182 320771 Ge-77m 4.09970E-06 6.15620E-05 320771 + 183 320780 Ge-78 1.14800E-04 1.83340E-04 320780 + 184 320790 Ge-79 2.65070E-05 1.01950E-04 320790 + 185 320791 Ge-79m 1.99080E-04 1.99180E-04 320791 + 186 320800 Ge-80 4.39020E-04 4.74950E-04 320800 + 187 320810 Ge-81 2.95700E-04 3.01590E-04 320810 + 188 320811 Ge-81m 5.95380E-05 6.42370E-05 320811 + 189 320820 Ge-82 2.96620E-04 2.97660E-04 320820 + 190 320830 Ge-83 7.01810E-05 7.02550E-05 320830 + 191 320840 Ge-84 1.65800E-05 1.65820E-05 320840 + 192 320850 Ge-85 1.46060E-06 1.46070E-06 320850 + 193 320860 Ge-86 8.24640E-08 8.24640E-08 320860 + 194 320870 Ge-87 3.68070E-09 3.68070E-09 320870 + 195 330740 As-74 1.10850E-11 1.10850E-11 330740 + 196 330750 As-75 1.11280E-10 2.65090E-05 33075.82c + 197 330751 As-75m 4.21400E-10 1.32150E-09 330751 + 198 330760 As-76 2.66020E-08 2.66020E-08 330760 + 199 330770 As-77 4.06130E-07 9.27590E-05 330770 + 200 330780 As-78 1.09410E-05 1.94280E-04 330780 + 201 330790 As-79 4.39870E-05 3.37160E-04 330790 + 202 330800 As-80 1.52960E-04 6.27910E-04 330800 + 203 330810 As-81 4.13530E-04 7.78710E-04 330810 + 204 330820 As-82 1.35330E-04 4.32990E-04 330820 + 205 330821 As-82m 4.71550E-04 4.71550E-04 330821 + 206 330830 As-83 9.32700E-04 1.00480E-03 330830 + 207 330840 As-84 2.22750E-04 2.30250E-04 330840 + 208 330841 As-84m 2.22750E-04 2.30250E-04 330841 + 209 330850 As-85 2.29920E-04 2.31180E-04 330850 + 210 330860 As-86 4.51070E-05 4.51890E-05 330860 + 211 330870 As-87 1.17440E-05 1.17480E-05 330870 + 212 330880 As-88 3.55090E-07 3.55090E-07 330880 + 213 330890 As-89 2.49190E-08 2.49190E-08 330890 + 214 330900 As-90 6.29200E-10 6.29200E-10 330900 + 215 340760 Se-76 9.78060E-12 2.66120E-08 34076.82c + 216 340770 Se-77 7.92680E-11 9.27600E-05 34077.82c + 217 340771 Se-77m 5.95350E-10 5.95350E-10 340771 + 218 340780 Se-78 2.99930E-08 1.94310E-04 34078.82c + 219 340790 Se-79 7.47350E-07 3.37820E-04 34079.82c + 220 340791 Se-79m 9.95060E-08 3.29270E-04 340791 + 221 340800 Se-80 1.87170E-05 6.46630E-04 34080.82c + 222 340810 Se-81 1.82850E-05 9.34240E-04 340810 + 223 340811 Se-81m 1.37340E-04 1.65290E-04 340811 + 224 340820 Se-82 5.19860E-04 1.42440E-03 34082.82c + 225 340830 Se-83 1.03090E-03 1.39300E-03 340830 + 226 340831 Se-83m 2.07570E-04 8.50930E-04 340831 + 227 340840 Se-84 2.85130E-03 3.36200E-03 340840 + 228 340850 Se-85 2.68530E-03 2.88050E-03 340850 + 229 340860 Se-86 2.49260E-03 2.52470E-03 340860 + 230 340870 Se-87 1.13880E-03 1.14870E-03 340870 + 231 340880 Se-88 2.36480E-04 2.36830E-04 340880 + 232 340890 Se-89 6.47690E-05 6.47940E-05 340890 + 233 340900 Se-90 1.20560E-05 1.20570E-05 340900 + 234 340910 Se-91 2.76440E-07 2.76440E-07 340910 + 235 340920 Se-92 7.19150E-09 7.19150E-09 340920 + 236 350780 Br-78 5.14950E-12 5.14950E-12 350780 + 237 350790 Br-79 5.66600E-11 1.84660E-07 35079.82c + 238 350791 Br-79m 2.14570E-10 2.14570E-10 350791 + 239 350800 Br-80 4.17660E-09 1.87290E-08 350800 + 240 350801 Br-80m 1.45520E-08 1.45520E-08 350801 + 241 350810 Br-81 2.73760E-06 9.37070E-04 35081.82c + 242 350820 Br-82 3.96820E-06 5.38910E-06 350820 + 243 350821 Br-82m 1.45580E-06 1.45580E-06 350821 + 244 350830 Br-83 6.39490E-05 2.30780E-03 350830 + 245 350840 Br-84 1.78840E-04 3.54090E-03 350840 + 246 350841 Br-84m 1.78840E-04 1.78840E-04 350841 + 247 350850 Br-85 1.53450E-03 4.41500E-03 350850 + 248 350860 Br-86 2.72020E-03 5.24490E-03 350860 + 249 350870 Br-87 4.50530E-03 5.65640E-03 350870 + 250 350880 Br-88 2.04130E-03 2.28080E-03 350880 + 251 350890 Br-89 2.58260E-03 2.64230E-03 350890 + 252 350900 Br-90 8.57110E-04 8.69230E-04 350900 + 253 350910 Br-91 2.66130E-04 2.66350E-04 350910 + 254 350920 Br-92 2.76560E-05 2.76630E-05 350920 + 255 350930 Br-93 3.28670E-06 3.28670E-06 350930 + 256 350940 Br-94 4.92880E-08 4.92880E-08 350940 + 257 350950 Br-95 9.82170E-10 9.82170E-10 350950 + 258 360810 Kr-81 1.90270E-10 2.15600E-10 360810 + 259 360811 Kr-81m 2.53330E-11 2.53330E-11 360811 + 260 360820 Kr-82 1.11380E-08 5.43510E-06 36082.82c + 261 360830 Kr-83 4.45680E-06 2.31320E-03 36083.82c + 262 360831 Kr-83m 8.97350E-07 2.30670E-03 360831 + 263 360840 Kr-84 2.35830E-05 3.74330E-03 36084.82c + 264 360850 Kr-85 1.52470E-04 1.10950E-03 36085.82c + 265 360851 Kr-85m 3.06990E-05 4.43860E-03 360851 + 266 360860 Kr-86 1.35570E-03 6.74260E-03 36086.82c + 267 360870 Kr-87 3.62840E-03 9.29560E-03 360870 + 268 360880 Kr-88 4.98820E-03 7.48880E-03 360880 + 269 360890 Kr-89 1.14850E-02 1.39690E-02 360890 + 270 360900 Kr-90 1.16090E-02 1.23180E-02 360900 + 271 360910 Kr-91 5.70510E-03 5.92730E-03 360910 + 272 360920 Kr-92 2.83400E-03 2.85470E-03 360920 + 273 360930 Kr-93 8.53060E-04 8.54150E-04 360930 + 274 360940 Kr-94 2.42850E-04 2.42870E-04 360940 + 275 360950 Kr-95 3.37070E-05 3.37080E-05 360950 + 276 360960 Kr-96 7.24790E-06 7.24790E-06 360960 + 277 360970 Kr-97 1.09960E-08 1.09960E-08 360970 + 278 370830 Rb-83 1.42910E-11 5.42780E-11 370830 + 279 370831 Rb-83m 3.99870E-11 3.99870E-11 370831 + 280 370840 Rb-84 1.41590E-09 4.38620E-09 370840 + 281 370841 Rb-84m 2.97030E-09 2.97030E-09 370841 + 282 370850 Rb-85 1.42910E-07 4.59830E-03 37085.82c + 283 370860 Rb-86 1.96110E-06 6.07540E-06 37086.82c + 284 370861 Rb-86m 4.11430E-06 4.11430E-06 370861 + 285 370870 Rb-87 1.37170E-04 9.43280E-03 37087.82c + 286 370880 Rb-88 3.80440E-04 7.86920E-03 370880 + 287 370890 Rb-89 3.48140E-03 1.74500E-02 370890 + 288 370900 Rb-90 7.32690E-04 1.16750E-02 370900 + 289 370901 Rb-90m 7.45380E-03 9.06500E-03 370901 + 290 370910 Rb-91 1.27880E-02 1.87150E-02 370910 + 291 370920 Rb-92 1.07330E-02 1.35880E-02 370920 + 292 370930 Rb-93 8.55820E-03 9.41500E-03 370930 + 293 370940 Rb-94 4.63620E-03 4.87730E-03 370940 + 294 370950 Rb-95 2.28110E-03 2.31410E-03 370950 + 295 370960 Rb-96 2.68070E-04 4.07350E-04 370960 + 296 370961 Rb-96m 2.68070E-04 2.71560E-04 370961 + 297 370970 Rb-97 1.21320E-04 1.21330E-04 370970 + 298 370980 Rb-98 5.01050E-06 5.01050E-06 370980 + 299 370981 Rb-98m 5.01050E-06 5.01050E-06 370981 + 300 370990 Rb-99 1.83720E-06 1.83720E-06 370990 + 301 371000 Rb-100 1.54730E-09 1.54730E-09 371000 + 302 380860 Sr-86 1.56010E-09 6.07660E-06 38086.82c + 303 380870 Sr-87 8.67030E-08 1.04110E-07 38087.82c + 304 380871 Sr-87m 1.74570E-08 1.74570E-08 380871 + 305 380880 Sr-88 1.44520E-05 7.88370E-03 38088.82c + 306 380890 Sr-89 2.07190E-04 1.76570E-02 38089.82c + 307 380900 Sr-90 1.63250E-03 2.21370E-02 38090.82c + 308 380910 Sr-91 4.76120E-03 2.34770E-02 380910 + 309 380920 Sr-92 1.38020E-02 2.75220E-02 380920 + 310 380930 Sr-93 2.05410E-02 3.03170E-02 380930 + 311 380940 Sr-94 2.83200E-02 3.29040E-02 380940 + 312 380950 Sr-95 1.87500E-02 2.09200E-02 380950 + 313 380960 Sr-96 1.19440E-02 1.24630E-02 380960 + 314 380970 Sr-97 4.81700E-03 4.90860E-03 380970 + 315 380980 Sr-98 1.68410E-03 1.69370E-03 380980 + 316 380990 Sr-99 2.83110E-04 2.84650E-04 380990 + 317 381000 Sr-100 6.00500E-05 6.00510E-05 381000 + 318 381010 Sr-101 6.55190E-06 6.55190E-06 381010 + 319 381020 Sr-102 1.04340E-08 1.04340E-08 381020 + 320 390880 Y-88 1.11460E-10 2.10150E-10 390880 + 321 390881 Y-88m 9.86860E-11 9.86860E-11 390881 + 322 390890 Y-89 3.88850E-09 1.76570E-02 39089.82c + 323 390891 Y-89m 1.93120E-08 1.72130E-06 390891 + 324 390900 Y-90 6.44450E-07 2.21380E-02 39090.82c + 325 390901 Y-90m 1.07770E-06 1.07770E-06 390901 + 326 390910 Y-91 1.29640E-05 2.35540E-02 39091.82c + 327 390911 Y-91m 6.43850E-05 1.38770E-02 390911 + 328 390920 Y-92 3.17430E-04 2.78390E-02 390920 + 329 390930 Y-93 2.56660E-04 3.25010E-02 390930 + 330 390931 Y-93m 1.92760E-03 9.51420E-03 390931 + 331 390940 Y-94 6.06610E-03 3.89700E-02 390940 + 332 390950 Y-95 1.83510E-02 3.92710E-02 390950 + 333 390960 Y-96 6.92540E-03 1.93900E-02 390960 + 334 390961 Y-96m 1.45290E-02 1.45300E-02 390961 + 335 390970 Y-97 3.70210E-03 8.00540E-03 390970 + 336 390971 Y-97m 1.36840E-02 1.81760E-02 390971 + 337 390972 Y-97m 4.70280E-03 4.70280E-03 390972 + 338 390980 Y-98 2.17150E-03 3.86530E-03 390980 + 339 390981 Y-98m 1.05280E-02 1.05280E-02 390981 + 340 390990 Y-99 8.42890E-03 8.71400E-03 390990 + 341 391000 Y-100 1.52410E-03 1.58380E-03 391000 + 342 391001 Y-100m 1.52410E-03 1.52420E-03 391001 + 343 391010 Y-101 1.03800E-03 1.04440E-03 391010 + 344 391020 Y-102 7.95050E-05 7.95100E-05 391020 + 345 391021 Y-102m 7.95050E-05 7.95100E-05 391021 + 346 391030 Y-103 2.85140E-05 2.85140E-05 391030 + 347 391040 Y-104 5.02410E-08 5.02410E-08 391040 + 348 391050 Y-105 1.25410E-09 1.25410E-09 391050 + 349 400910 Zr-91 1.37590E-06 2.35550E-02 40091.82c + 350 400920 Zr-92 5.77030E-06 2.78450E-02 40092.82c + 351 400930 Zr-93 7.03580E-05 3.25720E-02 40093.82c + 352 400940 Zr-94 5.56520E-04 3.95260E-02 40094.82c + 353 400950 Zr-95 2.36120E-03 4.16320E-02 40095.82c + 354 400960 Zr-96 1.03320E-02 4.42660E-02 40096.82c + 355 400970 Zr-97 2.01250E-02 4.74780E-02 400970 + 356 400980 Zr-98 3.73530E-02 5.15210E-02 400980 + 357 400990 Zr-99 3.32700E-02 4.18500E-02 400990 + 358 401000 Zr-100 3.02250E-02 3.33180E-02 401000 + 359 401010 Zr-101 1.49360E-02 1.59880E-02 401010 + 360 401020 Zr-102 7.75760E-03 7.91110E-03 401020 + 361 401030 Zr-103 2.14700E-03 2.17320E-03 401030 + 362 401040 Zr-104 5.37980E-04 5.38030E-04 401040 + 363 401050 Zr-105 6.86500E-05 6.86510E-05 401050 + 364 401060 Zr-106 8.00000E-06 8.00000E-06 401060 + 365 401070 Zr-107 6.59420E-09 6.59420E-09 401070 + 366 410930 Nb-93 5.98870E-10 7.19450E-10 41093.82c + 367 410931 Nb-93m 1.20580E-10 1.20580E-10 410931 + 368 410940 Nb-94 6.90380E-07 1.10110E-06 41094.82c + 369 410941 Nb-94m 4.12820E-07 4.12820E-07 410941 + 370 410950 Nb-95 1.36100E-05 4.16230E-02 41095.82c + 371 410951 Nb-95m 2.74030E-06 4.52510E-04 410951 + 372 410960 Nb-96 1.21610E-04 1.21610E-04 410960 + 373 410970 Nb-97 7.04290E-04 4.83240E-02 410970 + 374 410971 Nb-97m 1.41810E-04 4.52690E-02 410971 + 375 410980 Nb-98 6.47500E-04 5.21690E-02 410980 + 376 410981 Nb-98m 2.25610E-03 2.25610E-03 410981 + 377 410990 Nb-99 9.21380E-03 3.60080E-02 410990 + 378 410991 Nb-99m 1.85520E-03 1.72560E-02 410991 + 379 411000 Nb-100 3.46340E-03 3.67820E-02 411000 + 380 411001 Nb-100m 1.67910E-02 1.67910E-02 411001 + 381 411010 Nb-101 3.36310E-02 4.96190E-02 411010 + 382 411020 Nb-102 1.38790E-02 2.17900E-02 411020 + 383 411021 Nb-102m 1.38790E-02 1.38790E-02 411021 + 384 411030 Nb-103 2.37320E-02 2.59050E-02 411030 + 385 411040 Nb-104 5.58450E-03 6.12350E-03 411040 + 386 411041 Nb-104m 5.58450E-03 5.58450E-03 411041 + 387 411050 Nb-105 4.84610E-03 4.91390E-03 411050 + 388 411060 Nb-106 1.12960E-03 1.13750E-03 411060 + 389 411070 Nb-107 2.54160E-04 2.54170E-04 411070 + 390 411080 Nb-108 2.36810E-05 2.36810E-05 411080 + 391 411090 Nb-109 6.43490E-06 6.43490E-06 411090 + 392 420960 Mo-96 1.03590E-06 1.22650E-04 42096.82c + 393 420970 Mo-97 9.76140E-06 4.83340E-02 42097.82c + 394 420980 Mo-98 1.38970E-04 5.45640E-02 42098.82c + 395 420990 Mo-99 6.76980E-04 5.35960E-02 42099.82c + 396 421000 Mo-100 3.78470E-03 5.73570E-02 42100.82c + 397 421010 Mo-101 9.93550E-03 5.95550E-02 421010 + 398 421020 Mo-102 2.62680E-02 6.19370E-02 421020 + 399 421030 Mo-103 3.41930E-02 6.01050E-02 421030 + 400 421040 Mo-104 3.94310E-02 5.12160E-02 421040 + 401 421050 Mo-105 2.36450E-02 2.85270E-02 421050 + 402 421060 Mo-106 1.53470E-02 1.64490E-02 421060 + 403 421070 Mo-107 5.60310E-03 5.84350E-03 421070 + 404 421080 Mo-108 1.89450E-03 1.91750E-03 421080 + 405 421090 Mo-109 3.20400E-04 3.26020E-04 421090 + 406 421100 Mo-110 4.84700E-05 4.84700E-05 421100 + 407 421110 Mo-111 3.51460E-06 3.51460E-06 421110 + 408 421120 Mo-112 7.32070E-10 7.32070E-10 421120 + 409 430980 Tc-98 2.73900E-09 2.73900E-09 430980 + 410 430990 Tc-99 2.29430E-06 5.35970E-02 43099.82c + 411 430991 Tc-99m 4.61960E-07 4.71970E-02 430991 + 412 431000 Tc-100 1.52860E-05 1.52860E-05 431000 + 413 431010 Tc-101 2.02050E-04 5.97570E-02 431010 + 414 431020 Tc-102 5.45100E-04 6.24820E-02 431020 + 415 431021 Tc-102m 5.45100E-04 5.45100E-04 431021 + 416 431030 Tc-103 4.98810E-03 6.50930E-02 431030 + 417 431040 Tc-104 1.04620E-02 6.16780E-02 431040 + 418 431050 Tc-105 2.27450E-02 5.12720E-02 431050 + 419 431060 Tc-106 2.41680E-02 4.06160E-02 431060 + 420 431070 Tc-107 2.48640E-02 3.07070E-02 431070 + 421 431080 Tc-108 1.35620E-02 1.54810E-02 431080 + 422 431090 Tc-109 6.79730E-03 7.12160E-03 431090 + 423 431100 Tc-110 2.22650E-03 2.27500E-03 431100 + 424 431110 Tc-111 5.16980E-04 5.20460E-04 431110 + 425 431120 Tc-112 1.07640E-04 1.07640E-04 431120 + 426 431130 Tc-113 1.82660E-05 1.82660E-05 431130 + 427 431140 Tc-114 2.08920E-06 2.08920E-06 431140 + 428 441010 Ru-101 2.80880E-06 5.97600E-02 44101.82c + 429 441020 Ru-102 1.97300E-05 6.30470E-02 44102.82c + 430 441030 Ru-103 3.71730E-05 6.52340E-02 44103.82c + 431 441031 Ru-103m 1.04010E-04 1.04010E-04 441031 + 432 441040 Ru-104 7.80150E-04 6.24580E-02 44104.82c + 433 441050 Ru-105 2.47250E-03 5.37440E-02 44105.82c + 434 441060 Ru-106 7.63740E-03 4.82540E-02 44106.82c + 435 441070 Ru-107 1.18000E-02 4.25070E-02 441070 + 436 441080 Ru-108 1.70810E-02 3.25680E-02 441080 + 437 441090 Ru-109 1.25810E-02 1.96980E-02 441090 + 438 441100 Ru-110 9.81940E-03 1.20940E-02 441100 + 439 441110 Ru-111 3.79460E-03 4.31670E-03 441110 + 440 441120 Ru-112 1.83350E-03 1.94080E-03 441120 + 441 441130 Ru-113 2.09740E-04 3.31700E-04 441130 + 442 441131 Ru-113m 2.09740E-04 2.09740E-04 441131 + 443 441140 Ru-114 1.62710E-04 1.64660E-04 441140 + 444 441150 Ru-115 2.70470E-05 2.70470E-05 441150 + 445 441160 Ru-116 1.34510E-05 1.34510E-05 441160 + 446 441170 Ru-117 1.34600E-06 1.34600E-06 441170 + 447 451030 Rh-103 3.55670E-10 6.52340E-02 45103.82c + 448 451031 Rh-103m 2.67130E-09 6.44530E-02 451031 + 449 451040 Rh-104 1.21290E-06 5.43340E-06 451040 + 450 451041 Rh-104m 4.22600E-06 4.22600E-06 451041 + 451 451050 Rh-105 2.48810E-05 5.37720E-02 45105.82c + 452 451051 Rh-105m 3.31280E-06 1.52600E-02 451051 + 453 451060 Rh-106 3.55170E-05 4.82890E-02 451060 + 454 451061 Rh-106m 9.68130E-05 9.68130E-05 451061 + 455 451070 Rh-107 7.14460E-04 4.32220E-02 451070 + 456 451080 Rh-108 3.87240E-04 3.29550E-02 451080 + 457 451081 Rh-108m 1.34930E-03 1.34930E-03 451081 + 458 451090 Rh-109 3.28060E-03 2.29780E-02 451090 + 459 451100 Rh-110 4.06690E-03 1.61600E-02 451100 + 460 451101 Rh-110m 9.57400E-05 9.57400E-05 451101 + 461 451110 Rh-111 4.82240E-03 9.13910E-03 451110 + 462 451120 Rh-112 2.03040E-03 3.97120E-03 451120 + 463 451121 Rh-112m 2.03040E-03 2.03040E-03 451121 + 464 451130 Rh-113 3.01330E-03 3.44990E-03 451130 + 465 451140 Rh-114 5.55200E-04 7.19920E-04 451140 + 466 451141 Rh-114m 5.55200E-04 5.55200E-04 451141 + 467 451150 Rh-115 4.92000E-04 5.19130E-04 451150 + 468 451160 Rh-116 1.83090E-05 3.16420E-05 451160 + 469 451161 Rh-116m 4.99050E-05 4.99050E-05 451161 + 470 451170 Rh-117 1.49710E-05 1.62890E-05 451170 + 471 451180 Rh-118 4.58500E-09 4.58500E-09 451180 + 472 451190 Rh-119 1.06040E-10 1.06040E-10 451190 + 473 451220 Rh-122 5.24520E-09 5.24520E-09 451220 + 474 461060 Pd-106 8.89000E-07 4.83870E-02 46106.82c + 475 461070 Pd-107 2.74120E-06 4.32310E-02 46107.82c + 476 461071 Pd-107m 6.02500E-06 6.02500E-06 461071 + 477 461080 Pd-108 5.23040E-05 3.43570E-02 46108.82c + 478 461090 Pd-109 5.10580E-05 2.31420E-02 461090 + 479 461091 Pd-109m 1.12220E-04 1.16010E-02 461091 + 480 461100 Pd-110 5.02260E-04 1.67580E-02 46110.82c + 481 461110 Pd-111 2.12660E-04 9.68310E-03 461110 + 482 461111 Pd-111m 4.67410E-04 5.03970E-04 461111 + 483 461120 Pd-112 1.32510E-03 7.32660E-03 461120 + 484 461130 Pd-113 3.62060E-04 4.82500E-03 461130 + 485 461131 Pd-113m 1.01300E-03 1.01300E-03 461131 + 486 461140 Pd-114 1.33200E-03 2.60710E-03 461140 + 487 461150 Pd-115 2.31310E-04 7.21770E-04 461150 + 488 461151 Pd-115m 5.08420E-04 5.83790E-04 461151 + 489 461160 Pd-116 3.15470E-04 3.97020E-04 461160 + 490 461170 Pd-117 2.28860E-05 8.94790E-05 461170 + 491 461171 Pd-117m 5.03030E-05 5.03030E-05 461171 + 492 461180 Pd-118 3.32690E-05 3.32730E-05 461180 + 493 461190 Pd-119 9.38080E-06 9.38090E-06 461190 + 494 461200 Pd-120 7.00190E-06 7.00190E-06 461200 + 495 461210 Pd-121 1.56560E-09 1.56560E-09 461210 + 496 461220 Pd-122 5.17090E-06 5.17620E-06 461220 + 497 461230 Pd-123 8.47000E-07 8.47000E-07 461230 + 498 461240 Pd-124 6.25390E-08 6.25390E-08 461240 + 499 471080 Ag-108 7.16220E-10 8.86070E-10 471080 + 500 471081 Ag-108m 1.95230E-09 1.95230E-09 471081 + 501 471090 Ag-109 3.77710E-07 2.31450E-02 47109.82c + 502 471091 Ag-109m 2.83690E-06 2.31330E-02 471091 + 503 471100 Ag-110 9.12480E-07 9.46310E-07 471100 + 504 471101 Ag-110m 2.48720E-06 2.48720E-06 47510.82c + 505 471110 Ag-111 3.07230E-06 9.79660E-03 47111.82c + 506 471111 Ag-111m 2.30750E-05 9.73460E-03 471111 + 507 471120 Ag-112 7.28870E-05 7.39950E-03 471120 + 508 471130 Ag-113 1.86570E-05 3.27000E-03 471130 + 509 471131 Ag-113m 1.40120E-04 4.76040E-03 471131 + 510 471140 Ag-114 3.06710E-05 2.78650E-03 471140 + 511 471141 Ag-114m 1.48690E-04 1.48690E-04 471141 + 512 471150 Ag-115 3.61690E-05 7.73820E-04 471150 + 513 471151 Ag-115m 2.71650E-04 1.00360E-03 471151 + 514 471160 Ag-116 5.65680E-05 4.62840E-04 471160 + 515 471161 Ag-116m 1.54190E-04 1.54190E-04 471161 + 516 471170 Ag-117 2.05660E-05 7.72580E-05 471170 + 517 471171 Ag-117m 1.54460E-04 1.99200E-04 471171 + 518 471180 Ag-118 2.95570E-05 1.18770E-04 471180 + 519 471181 Ag-118m 1.43290E-04 1.48050E-04 471181 + 520 471190 Ag-119 1.62340E-05 2.09240E-05 471190 + 521 471191 Ag-119m 1.21930E-04 1.26620E-04 471191 + 522 471200 Ag-120 8.29150E-05 1.39020E-04 471200 + 523 471201 Ag-120m 1.38670E-04 1.42170E-04 471201 + 524 471210 Ag-121 3.44620E-05 3.44640E-05 471210 + 525 471220 Ag-122 9.83190E-06 1.50080E-05 471220 + 526 471221 Ag-122m 1.06000E-05 1.06000E-05 471221 + 527 471230 Ag-123 2.94650E-05 3.03120E-05 471230 + 528 471240 Ag-124 6.32870E-06 9.80290E-06 471240 + 529 471241 Ag-124m 6.82330E-06 6.82330E-06 471241 + 530 471250 Ag-125 2.05620E-06 2.05620E-06 471250 + 531 471260 Ag-126 7.19250E-07 7.19250E-07 471260 + 532 471270 Ag-127 4.23330E-08 4.23330E-08 471270 + 533 471280 Ag-128 1.62220E-09 1.62220E-09 471280 + 534 481110 Cd-111 1.72420E-09 9.84530E-03 48111.82c + 535 481111 Cd-111m 6.52940E-09 6.52940E-09 481111 + 536 481120 Cd-112 1.81550E-07 7.39970E-03 48112.82c + 537 481130 Cd-113 3.46440E-07 4.92760E-03 48113.82c + 538 481131 Cd-113m 1.31200E-06 5.78470E-05 481131 + 539 481140 Cd-114 1.24810E-05 2.79900E-03 48114.82c + 540 481150 Cd-115 3.92480E-06 1.50290E-03 481150 + 541 481151 Cd-115m 1.48630E-05 8.25360E-05 48515.82c + 542 481160 Cd-116 3.40250E-05 6.41800E-04 48116.82c + 543 481170 Cd-117 8.03600E-06 2.13080E-04 481170 + 544 481171 Cd-117m 3.04320E-05 8.98940E-05 481171 + 545 481180 Cd-118 1.02390E-04 3.08510E-04 481180 + 546 481190 Cd-119 3.34630E-05 1.70540E-04 481190 + 547 481191 Cd-119m 9.36270E-05 1.04090E-04 481191 + 548 481200 Cd-120 4.46710E-04 6.75290E-04 481200 + 549 481210 Cd-121 7.35340E-05 1.04400E-04 481210 + 550 481211 Cd-121m 2.05750E-04 2.09350E-04 481211 + 551 481220 Cd-122 2.52610E-04 2.78220E-04 481220 + 552 481230 Cd-123 5.07910E-05 7.55960E-05 481230 + 553 481231 Cd-123m 1.42110E-04 1.47630E-04 481231 + 554 481240 Cd-124 2.40900E-04 2.54110E-04 481240 + 555 481250 Cd-125 6.70570E-05 6.80850E-05 481250 + 556 481251 Cd-125m 1.87620E-04 1.88650E-04 481251 + 557 481260 Cd-126 1.40580E-04 1.41300E-04 481260 + 558 481270 Cd-127 4.20050E-05 4.20470E-05 481270 + 559 481280 Cd-128 8.25270E-06 8.25430E-06 481280 + 560 481290 Cd-129 2.37500E-07 2.37500E-07 481290 + 561 481291 Cd-129m 6.64520E-07 6.64520E-07 481291 + 562 481300 Cd-130 4.81720E-08 4.81720E-08 481300 + 563 481310 Cd-131 1.65910E-09 1.65910E-09 481310 + 564 491130 In-113 3.72150E-10 5.77660E-05 49113.82c + 565 491131 In-113m 7.49310E-11 7.49310E-11 491131 + 566 491140 In-114 2.47750E-09 1.08080E-08 491140 + 567 491141 In-114m 4.00070E-09 8.63250E-09 491141 + 568 491142 In-114m 4.63180E-09 4.63180E-09 491142 + 569 491150 In-115 1.15410E-07 1.51050E-03 49115.82c + 570 491151 In-115m 2.32380E-08 1.50300E-03 491151 + 571 491160 In-116 2.12890E-07 2.12890E-07 491160 + 572 491161 In-116m 3.43780E-07 7.41790E-07 491161 + 573 491162 In-116m 3.98010E-07 3.98010E-07 491162 + 574 491170 In-117 2.88760E-06 2.02110E-04 491170 + 575 491171 In-117m 5.81400E-07 1.97230E-04 491171 + 576 491180 In-118 6.00740E-07 3.09110E-04 491180 + 577 491181 In-118m 9.70070E-07 2.07740E-06 491181 + 578 491182 In-118m 1.12310E-06 1.12310E-06 491182 + 579 491190 In-119 1.09390E-05 1.40140E-04 491190 + 580 491191 In-119m 2.20260E-06 1.56390E-04 491191 + 581 491200 In-120 3.12080E-05 7.06500E-04 491200 + 582 491201 In-120m 3.12080E-05 3.12080E-05 491201 + 583 491202 In-120m 3.12080E-05 3.12080E-05 491202 + 584 491210 In-121 9.97050E-05 3.45280E-04 491210 + 585 491211 In-121m 2.00750E-05 8.93110E-05 491211 + 586 491220 In-122 8.04080E-05 3.58630E-04 491220 + 587 491221 In-122m 6.72360E-05 6.72360E-05 491221 + 588 491222 In-122m 6.72360E-05 6.72360E-05 491222 + 589 491230 In-123 3.52440E-04 5.21680E-04 491230 + 590 491231 In-123m 7.09620E-05 1.24940E-04 491231 + 591 491240 In-124 2.46290E-04 5.00400E-04 491240 + 592 491241 In-124m 2.65540E-04 2.65540E-04 491241 + 593 491250 In-125 9.77240E-04 1.19850E-03 491250 + 594 491251 In-125m 1.96760E-04 2.32260E-04 491251 + 595 491260 In-126 6.35950E-04 7.77250E-04 491260 + 596 491261 In-126m 6.85650E-04 6.85650E-04 491261 + 597 491270 In-127 1.22840E-03 1.22840E-03 491270 + 598 491271 In-127m 2.47330E-04 2.89370E-04 491271 + 599 491280 In-128 2.09800E-04 3.00200E-04 491280 + 600 491281 In-128m 8.21480E-05 9.04030E-05 491281 + 601 491282 In-128m 3.14760E-04 3.14760E-04 491282 + 602 491290 In-129 3.93780E-04 3.94440E-04 491290 + 603 491291 In-129m 7.92850E-05 7.95230E-05 491291 + 604 491300 In-130 3.53340E-05 3.53810E-05 491300 + 605 491301 In-130m 5.14490E-05 5.14490E-05 491301 + 606 491302 In-130m 7.16670E-05 7.16670E-05 491302 + 607 491310 In-131 9.79570E-06 9.89700E-06 491310 + 608 491311 In-131m 9.79570E-06 9.79570E-06 491311 + 609 491312 In-131m 9.79570E-06 9.79570E-06 491312 + 610 491320 In-132 9.36780E-07 9.36780E-07 491320 + 611 491330 In-133 1.00850E-08 1.21160E-08 491330 + 612 491331 In-133m 2.03060E-09 2.03060E-09 491331 + 613 501150 Sn-115 6.02860E-11 7.51480E-05 50115.82c + 614 501160 Sn-116 5.99600E-10 9.55280E-07 50116.82c + 615 501170 Sn-117 2.22460E-09 3.06460E-04 50117.82c + 616 501171 Sn-117m 8.42440E-09 6.97050E-07 501171 + 617 501180 Sn-118 1.78380E-07 3.11390E-04 50118.82c + 618 501190 Sn-119 4.35080E-07 2.89860E-04 50119.82c + 619 501191 Sn-119m 1.64760E-06 1.28250E-04 501191 + 620 501200 Sn-120 3.19970E-05 8.01000E-04 50120.82c + 621 501210 Sn-121 5.55040E-06 4.42360E-04 501210 + 622 501211 Sn-121m 1.55300E-05 5.46450E-05 501211 + 623 501220 Sn-122 5.06520E-05 5.43750E-04 50122.82c + 624 501230 Sn-123 6.96800E-05 1.09450E-04 50123.82c + 625 501231 Sn-123m 2.49040E-05 6.31750E-04 501231 + 626 501240 Sn-124 2.50790E-04 1.01670E-03 50124.82c + 627 501250 Sn-125 4.47240E-04 6.49690E-04 50125.82c + 628 501251 Sn-125m 1.59850E-04 1.38810E-03 501251 + 629 501260 Sn-126 1.83070E-03 3.29560E-03 50126.82c + 630 501270 Sn-127 2.09220E-03 2.57100E-03 501270 + 631 501271 Sn-127m 7.47770E-04 1.78470E-03 501271 + 632 501280 Sn-128 1.06390E-03 4.57880E-03 501280 + 633 501281 Sn-128m 2.89990E-03 3.21470E-03 501281 + 634 501290 Sn-129 1.34270E-03 1.77480E-03 501290 + 635 501291 Sn-129m 3.75690E-03 3.79890E-03 501291 + 636 501300 Sn-130 1.49700E-03 1.59390E-03 501300 + 637 501301 Sn-130m 4.08050E-03 4.14230E-03 501301 + 638 501310 Sn-131 6.94110E-04 7.13090E-04 501310 + 639 501311 Sn-131m 1.94210E-03 1.95230E-03 501311 + 640 501320 Sn-132 5.80740E-04 5.81690E-04 501320 + 641 501330 Sn-133 5.04230E-05 5.04250E-05 501330 + 642 501340 Sn-134 4.52340E-06 4.52340E-06 501340 + 643 501350 Sn-135 1.54980E-07 1.54980E-07 501350 + 644 501360 Sn-136 2.23250E-09 2.23250E-09 501360 + 645 511180 Sb-118 1.24320E-11 1.24320E-11 511180 + 646 511181 Sb-118m 2.07920E-11 2.07920E-11 511181 + 647 511190 Sb-119 8.84240E-10 1.23930E-09 511190 + 648 511191 Sb-119m 3.55060E-10 3.55060E-10 511191 + 649 511200 Sb-120 3.45800E-08 3.45800E-08 511200 + 650 511201 Sb-120m 5.78300E-08 5.78300E-08 511201 + 651 511210 Sb-121 6.77160E-07 4.55280E-04 51121.82c + 652 511220 Sb-122 4.26430E-11 9.97720E-11 511220 + 653 511221 Sb-122m 5.71290E-11 5.71290E-11 511221 + 654 511230 Sb-123 4.88640E-06 7.46090E-04 51123.82c + 655 511240 Sb-124 7.04280E-06 1.81260E-05 51124.82c + 656 511241 Sb-124m 5.68140E-06 1.47770E-05 511241 + 657 511242 Sb-124m 9.09590E-06 9.09590E-06 511242 + 658 511250 Sb-125 8.17580E-05 2.11960E-03 51125.82c + 659 511260 Sb-126 8.67690E-05 1.03760E-04 51126.82c + 660 511261 Sb-126m 5.41970E-05 1.21380E-04 511261 + 661 511262 Sb-126m 6.71840E-05 6.71840E-05 511262 + 662 511270 Sb-127 7.26120E-04 5.08190E-03 511270 + 663 511280 Sb-128 5.84080E-04 5.19220E-03 511280 + 664 511281 Sb-128m 8.16920E-04 8.16920E-04 511281 + 665 511290 Sb-129 3.97780E-03 8.37840E-03 511290 + 666 511291 Sb-129m 2.94370E-03 4.84310E-03 511291 + 667 511300 Sb-130 6.01050E-03 9.67550E-03 511300 + 668 511301 Sb-130m 6.01050E-03 8.08160E-03 511301 + 669 511310 Sb-131 2.36920E-02 2.63570E-02 511310 + 670 511320 Sb-132 6.59870E-03 7.18040E-03 511320 + 671 511321 Sb-132m 5.84230E-03 5.84230E-03 511321 + 672 511330 Sb-133 9.07110E-03 9.12230E-03 511330 + 673 511340 Sb-134 4.41970E-04 4.45740E-04 511340 + 674 511341 Sb-134m 1.20470E-03 1.20470E-03 511341 + 675 511350 Sb-135 2.95990E-04 2.96110E-04 511350 + 676 511360 Sb-136 5.06970E-05 5.06990E-05 511360 + 677 511370 Sb-137 1.78260E-06 1.78260E-06 511370 + 678 511380 Sb-138 1.61510E-08 1.61510E-08 511380 + 679 521200 Te-120 2.56660E-11 2.56660E-11 52120.82c + 680 521210 Te-121 1.23550E-10 5.38570E-10 521210 + 681 521211 Te-121m 4.67890E-10 4.67890E-10 521211 + 682 521240 Te-124 3.50150E-11 2.18200E-05 52124.82c + 683 521250 Te-125 4.29290E-07 2.12160E-03 52125.82c + 684 521251 Te-125m 1.62570E-06 4.75920E-04 521251 + 685 521260 Te-126 4.80590E-06 2.12960E-04 52126.82c + 686 521270 Te-127 8.56730E-06 5.09370E-03 521270 + 687 521271 Te-127m 2.39710E-05 8.61440E-04 52527.82c + 688 521280 Te-128 1.15810E-04 6.09560E-03 52128.82c + 689 521290 Te-129 2.00380E-04 1.10470E-02 521290 + 690 521291 Te-129m 5.60640E-04 5.97120E-03 52529.82c + 691 521300 Te-130 4.57760E-03 2.23350E-02 52130.82c + 692 521310 Te-131 3.67830E-03 3.05300E-02 521310 + 693 521311 Te-131m 1.02920E-02 1.24020E-02 521311 + 694 521320 Te-132 2.76860E-02 4.07090E-02 52132.82c + 695 521330 Te-133 8.36000E-03 2.02750E-02 521330 + 696 521331 Te-133m 2.33910E-02 2.49690E-02 521331 + 697 521340 Te-134 2.24880E-02 2.41840E-02 521340 + 698 521350 Te-135 7.24790E-03 7.50580E-03 521350 + 699 521360 Te-136 2.64660E-03 2.68980E-03 521360 + 700 521370 Te-137 3.97640E-04 3.98550E-04 521370 + 701 521380 Te-138 8.53010E-05 8.53170E-05 521380 + 702 521390 Te-139 3.46010E-06 3.46010E-06 521390 + 703 521400 Te-140 9.60220E-08 9.60220E-08 521400 + 704 521410 Te-141 1.92070E-09 1.92070E-09 521410 + 705 531270 I-127 9.53960E-10 5.11440E-03 53127.82c + 706 531280 I-128 4.62320E-08 4.62320E-08 531280 + 707 531290 I-129 1.05350E-05 1.32670E-02 53129.82c + 708 531300 I-130 5.78290E-05 7.56510E-05 53130.82c + 709 531301 I-130m 2.12160E-05 2.12160E-05 531301 + 710 531310 I-131 9.47450E-04 4.12750E-02 53131.82c + 711 531320 I-132 1.55400E-03 4.34460E-02 531320 + 712 531321 I-132m 1.37590E-03 1.37590E-03 531321 + 713 531330 I-133 9.44630E-03 5.73110E-02 531330 + 714 531331 I-133m 6.99070E-03 6.99070E-03 531331 + 715 531340 I-134 1.75420E-02 5.69010E-02 531340 + 716 531341 I-134m 1.55320E-02 1.55320E-02 531341 + 717 531350 I-135 5.16820E-02 5.91880E-02 53135.82c + 718 531360 I-136 7.80350E-03 1.04990E-02 531360 + 719 531361 I-136m 2.12710E-02 2.12770E-02 531361 + 720 531370 I-137 1.82210E-02 1.86130E-02 531370 + 721 531380 I-138 5.54870E-03 5.62860E-03 531380 + 722 531390 I-139 2.84110E-03 2.84460E-03 531390 + 723 531400 I-140 3.90200E-04 3.90300E-04 531400 + 724 531410 I-141 6.04570E-05 6.04590E-05 531410 + 725 531420 I-142 5.23490E-06 5.23490E-06 531420 + 726 531430 I-143 7.99610E-09 7.99610E-09 531430 + 727 541290 Xe-129 1.08890E-10 5.21260E-10 54129.82c + 728 541291 Xe-129m 4.12370E-10 4.12370E-10 541291 + 729 541300 Xe-130 9.87030E-07 8.00320E-05 54130.82c + 730 541310 Xe-131 1.93170E-06 4.12820E-02 54131.82c + 731 541311 Xe-131m 5.40480E-06 4.53730E-04 541311 + 732 541320 Xe-132 2.28600E-05 4.36920E-02 54132.82c + 733 541321 Xe-132m 3.06260E-05 3.06260E-05 541321 + 734 541330 Xe-133 9.48010E-05 5.76710E-02 54133.82c + 735 541331 Xe-133m 2.65250E-04 1.89660E-03 541331 + 736 541340 Xe-134 6.68850E-04 5.97500E-02 54134.82c + 737 541341 Xe-134m 1.82310E-03 2.18040E-03 541341 + 738 541350 Xe-135 2.46890E-03 6.84640E-02 54135.82c + 739 541351 Xe-135m 6.90770E-03 1.66790E-02 541351 + 740 541360 Xe-136 3.38630E-02 6.68490E-02 54136.82c + 741 541370 Xe-137 3.30820E-02 5.07840E-02 541370 + 742 541380 Xe-138 3.26290E-02 3.82380E-02 541380 + 743 541390 Xe-139 1.52360E-02 1.78380E-02 541390 + 744 541400 Xe-140 8.11710E-03 8.48380E-03 541400 + 745 541410 Xe-141 1.93060E-03 1.97970E-03 541410 + 746 541420 Xe-142 5.49040E-04 5.52970E-04 541420 + 747 541430 Xe-143 6.07150E-05 6.07200E-05 541430 + 748 541440 Xe-144 2.62330E-06 2.62330E-06 541440 + 749 541450 Xe-145 8.74540E-08 8.74540E-08 541450 + 750 541460 Xe-146 1.25050E-09 1.25050E-09 541460 + 751 551320 Cs-132 9.28630E-09 9.28630E-09 551320 + 752 551330 Cs-133 1.05000E-06 5.76730E-02 55133.82c + 753 551340 Cs-134 9.60180E-06 1.81030E-05 55134.82c + 754 551341 Cs-134m 8.50120E-06 8.50120E-06 551341 + 755 551350 Cs-135 1.06880E-04 6.87500E-02 55135.82c + 756 551351 Cs-135m 7.90930E-05 7.90930E-05 551351 + 757 551360 Cs-136 8.64910E-04 1.17410E-03 55136.82c + 758 551361 Cs-136m 6.18390E-04 6.18390E-04 551361 + 759 551370 Cs-137 1.14970E-02 6.22810E-02 55137.82c + 760 551380 Cs-138 1.00790E-02 6.19710E-02 551380 + 761 551381 Cs-138m 1.68560E-02 1.68560E-02 551381 + 762 551390 Cs-139 4.33590E-02 6.11970E-02 551390 + 763 551400 Cs-140 2.78860E-02 3.63710E-02 551400 + 764 551410 Cs-141 2.76080E-02 2.95890E-02 551410 + 765 551420 Cs-142 1.20170E-02 1.25690E-02 551420 + 766 551430 Cs-143 6.54710E-03 6.60730E-03 551430 + 767 551440 Cs-144 7.89400E-04 1.18670E-03 551440 + 768 551441 Cs-144m 7.89400E-04 7.89400E-04 551441 + 769 551450 Cs-145 5.48540E-04 5.48620E-04 551450 + 770 551460 Cs-146 8.65570E-05 8.65580E-05 551460 + 771 551470 Cs-147 2.80920E-06 2.80920E-06 551470 + 772 551480 Cs-148 5.11730E-09 5.11730E-09 551480 + 773 561340 Ba-134 2.02670E-09 1.81050E-05 56134.82c + 774 561350 Ba-135 3.53640E-08 1.34310E-07 56135.82c + 775 561351 Ba-135m 9.89460E-08 9.89460E-08 561351 + 776 561360 Ba-136 2.01030E-06 1.49080E-03 56136.82c + 777 561361 Ba-136m 5.47970E-06 5.47970E-06 561361 + 778 561370 Ba-137 2.61110E-05 6.23800E-02 56137.82c + 779 561371 Ba-137m 7.30580E-05 5.88660E-02 561371 + 780 561380 Ba-138 1.57930E-03 6.67530E-02 56138.82c + 781 561390 Ba-139 5.11200E-03 6.63090E-02 561390 + 782 561400 Ba-140 1.24820E-02 4.88530E-02 56140.82c + 783 561410 Ba-141 1.52190E-02 4.48080E-02 561410 + 784 561420 Ba-142 2.41560E-02 3.68330E-02 561420 + 785 561430 Ba-143 1.69980E-02 2.35350E-02 561430 + 786 561440 Ba-144 1.16500E-02 1.32720E-02 561440 + 787 561450 Ba-145 5.48890E-03 5.97140E-03 561450 + 788 561460 Ba-146 2.74170E-03 2.81680E-03 561460 + 789 561470 Ba-147 3.20300E-04 3.22310E-04 561470 + 790 561480 Ba-148 8.19010E-05 8.19050E-05 561480 + 791 561490 Ba-149 6.42740E-06 6.42740E-06 561490 + 792 561500 Ba-150 2.76320E-08 2.76320E-08 561500 + 793 561510 Ba-151 3.63310E-10 3.63310E-10 561510 + 794 571370 La-137 8.91350E-07 8.91350E-07 571370 + 795 571380 La-138 5.40800E-06 5.40800E-06 57138.82c + 796 571390 La-139 1.11120E-04 6.64210E-02 57139.82c + 797 571400 La-140 4.57160E-04 4.93100E-02 57140.82c + 798 571410 La-141 2.10980E-03 4.69180E-02 571410 + 799 571420 La-142 4.28440E-03 4.11170E-02 571420 + 800 571430 La-143 1.48430E-02 3.83780E-02 571430 + 801 571440 La-144 1.93590E-02 3.26310E-02 571440 + 802 571450 La-145 2.96680E-02 3.56390E-02 571450 + 803 571460 La-146 6.43210E-03 9.24890E-03 571460 + 804 571461 La-146m 1.34940E-02 1.34940E-02 571461 + 805 571470 La-147 9.65960E-03 9.98220E-03 571470 + 806 571480 La-148 4.73490E-03 4.81650E-03 571480 + 807 571490 La-149 1.32180E-03 1.32820E-03 571490 + 808 571500 La-150 3.12360E-04 3.12390E-04 571500 + 809 571510 La-151 2.44800E-05 2.44800E-05 571510 + 810 571520 La-152 5.69200E-06 5.69200E-06 571520 + 811 571530 La-153 1.15470E-09 1.15470E-09 571530 + 812 581390 Ce-139 3.03720E-07 1.15350E-06 581390 + 813 581391 Ce-139m 8.49780E-07 8.49780E-07 581391 + 814 581400 Ce-140 2.98240E-06 4.93130E-02 58140.82c + 815 581410 Ce-141 1.70330E-05 4.69350E-02 58141.82c + 816 581420 Ce-142 9.54840E-05 4.12130E-02 58142.82c + 817 581430 Ce-143 3.37470E-04 3.87150E-02 58143.82c + 818 581440 Ce-144 1.72250E-03 3.43530E-02 58144.82c + 819 581450 Ce-145 5.32490E-03 4.09640E-02 581450 + 820 581460 Ce-146 1.28750E-02 3.56180E-02 581460 + 821 581470 Ce-147 9.37130E-03 1.93530E-02 581470 + 822 581480 Ce-148 1.28460E-02 1.76810E-02 581480 + 823 581490 Ce-149 4.84590E-03 6.16390E-03 581490 + 824 581500 Ce-150 3.49970E-03 3.80360E-03 581500 + 825 581510 Ce-151 6.33670E-04 6.58490E-04 581510 + 826 581520 Ce-152 2.62620E-04 2.67970E-04 581520 + 827 581530 Ce-153 1.67990E-05 1.68000E-05 581530 + 828 581540 Ce-154 4.48970E-06 4.48970E-06 581540 + 829 581550 Ce-155 7.78230E-09 7.78230E-09 581550 + 830 581560 Ce-156 8.43560E-11 8.43560E-11 581560 + 831 591420 Pr-142 2.63510E-09 9.81800E-09 59142.82c + 832 591421 Pr-142m 7.18280E-09 7.18280E-09 591421 + 833 591430 Pr-143 3.68640E-06 3.87190E-02 59143.82c + 834 591440 Pr-144 1.80220E-06 3.43730E-02 591440 + 835 591441 Pr-144m 1.83340E-05 4.92390E-04 591441 + 836 591450 Pr-145 2.28030E-04 4.11920E-02 591450 + 837 591460 Pr-146 1.06170E-03 3.66790E-02 591460 + 838 591470 Pr-147 2.33660E-03 2.16900E-02 591470 + 839 591480 Pr-148 1.06400E-03 1.87450E-02 591480 + 840 591481 Pr-148m 5.15830E-03 5.15830E-03 591481 + 841 591490 Pr-149 9.09910E-03 1.52630E-02 591490 + 842 591500 Pr-150 1.01670E-02 1.39710E-02 591500 + 843 591510 Pr-151 6.64450E-03 7.30300E-03 591510 + 844 591520 Pr-152 4.87100E-03 5.13910E-03 591520 + 845 591530 Pr-153 1.70260E-03 1.71930E-03 591530 + 846 591540 Pr-154 4.86250E-04 4.90710E-04 591540 + 847 591550 Pr-155 9.50260E-05 9.50340E-05 591550 + 848 591560 Pr-156 1.69050E-05 1.69050E-05 591560 + 849 591570 Pr-157 1.04800E-08 1.04800E-08 591570 + 850 591580 Pr-158 1.76190E-10 1.76190E-10 591580 + 851 601440 Nd-144 1.13720E-09 3.43740E-02 60144.82c + 852 601450 Nd-145 8.90410E-08 4.11920E-02 60145.82c + 853 601460 Nd-146 2.79710E-06 3.66820E-02 60146.82c + 854 601470 Nd-147 2.24940E-05 2.17130E-02 60147.82c + 855 601480 Nd-148 1.83100E-04 2.40870E-02 60148.82c + 856 601490 Nd-149 5.00050E-04 1.57630E-02 601490 + 857 601500 Nd-150 1.78230E-03 1.57530E-02 60150.82c + 858 601510 Nd-151 1.99100E-03 9.29400E-03 601510 + 859 601520 Nd-152 4.43180E-03 9.57090E-03 601520 + 860 601530 Nd-153 2.81060E-03 4.52990E-03 601530 + 861 601540 Nd-154 2.30170E-03 2.79240E-03 601540 + 862 601550 Nd-155 7.07120E-04 8.02610E-04 601550 + 863 601560 Nd-156 2.03600E-04 2.20050E-04 601560 + 864 601570 Nd-157 3.07250E-05 3.07350E-05 601570 + 865 601580 Nd-158 6.78340E-07 6.78520E-07 601580 + 866 601590 Nd-159 4.35480E-08 4.35480E-08 601590 + 867 601600 Nd-160 7.31930E-10 7.31930E-10 601600 + 868 601610 Nd-161 1.43040E-11 1.43040E-11 601610 + 869 611470 Pm-147 4.65610E-09 2.17130E-02 61147.82c + 870 611480 Pm-148 5.61410E-08 6.37930E-08 61148.82c + 871 611481 Pm-148m 1.53030E-07 1.53030E-07 61548.82c + 872 611490 Pm-149 1.28570E-05 1.57760E-02 61149.82c + 873 611500 Pm-150 6.37710E-05 6.37710E-05 611500 + 874 611510 Pm-151 2.47100E-04 9.54110E-03 61151.82c + 875 611520 Pm-152 1.51190E-04 9.72210E-03 611520 + 876 611521 Pm-152m 3.17860E-04 3.17860E-04 611521 + 877 611522 Pm-152m 4.15210E-04 4.15210E-04 611522 + 878 611530 Pm-153 1.71520E-03 6.24510E-03 611530 + 879 611540 Pm-154 1.29660E-03 4.08900E-03 611540 + 880 611541 Pm-154m 1.29660E-03 1.29660E-03 611541 + 881 611550 Pm-155 2.89330E-03 3.69590E-03 611550 + 882 611560 Pm-156 1.74540E-03 1.96550E-03 611560 + 883 611570 Pm-157 9.40600E-04 9.71340E-04 611570 + 884 611580 Pm-158 2.04060E-04 2.04740E-04 611580 + 885 611590 Pm-159 1.05690E-04 1.05730E-04 611590 + 886 611600 Pm-160 5.65530E-06 5.65600E-06 611600 + 887 611610 Pm-161 4.04450E-06 4.04450E-06 611610 + 888 611620 Pm-162 9.37550E-10 9.37550E-10 611620 + 889 611630 Pm-163 2.00630E-11 2.00630E-11 611630 + 890 621490 Sm-149 5.88510E-10 1.57760E-02 62149.82c + 891 621500 Sm-150 3.07590E-08 6.38020E-05 62150.82c + 892 621510 Sm-151 6.00840E-07 9.54170E-03 62151.82c + 893 621520 Sm-152 9.47510E-06 1.04650E-02 62152.82c + 894 621530 Sm-153 1.35640E-05 6.29660E-03 62153.82c + 895 621531 Sm-153m 3.79510E-05 3.79510E-05 621531 + 896 621540 Sm-154 1.80390E-04 5.56590E-03 62154.82c + 897 621550 Sm-155 3.73040E-04 4.06890E-03 621550 + 898 621560 Sm-156 5.69710E-04 2.53520E-03 621560 + 899 621570 Sm-157 4.57040E-04 1.42840E-03 621570 + 900 621580 Sm-158 3.60480E-04 5.65240E-04 621580 + 901 621590 Sm-159 2.86810E-04 3.92540E-04 621590 + 902 621600 Sm-160 9.63280E-05 1.01970E-04 621600 + 903 621610 Sm-161 2.02170E-05 2.42620E-05 621610 + 904 621620 Sm-162 7.04570E-06 7.04660E-06 621620 + 905 621630 Sm-163 1.13330E-07 1.13350E-07 621630 + 906 621640 Sm-164 2.24730E-09 2.24730E-09 621640 + 907 621650 Sm-165 5.64020E-11 5.64020E-11 621650 + 908 631520 Eu-152 9.71100E-10 2.25730E-09 63152.82c + 909 631521 Eu-152m 2.21890E-10 2.21890E-10 631521 + 910 631522 Eu-152m 1.28620E-09 1.28620E-09 631522 + 911 631530 Eu-153 1.67980E-06 6.29830E-03 63153.82c + 912 631540 Eu-154 3.23650E-06 6.72590E-06 63154.82c + 913 631541 Eu-154m 3.48940E-06 3.48940E-06 631541 + 914 631550 Eu-155 1.88490E-05 4.08780E-03 63155.82c + 915 631560 Eu-156 7.13610E-05 2.60650E-03 63156.82c + 916 631570 Eu-157 1.87820E-04 1.61620E-03 63157.82c + 917 631580 Eu-158 2.52640E-04 8.17880E-04 631580 + 918 631590 Eu-159 3.65720E-04 7.58260E-04 631590 + 919 631600 Eu-160 2.89840E-04 3.91810E-04 631600 + 920 631610 Eu-161 2.62900E-04 2.87160E-04 631610 + 921 631620 Eu-162 5.28850E-05 5.99320E-05 631620 + 922 631630 Eu-163 3.79950E-05 3.81080E-05 631630 + 923 631640 Eu-164 8.12810E-07 8.15060E-07 631640 + 924 631650 Eu-165 5.62600E-08 5.63160E-08 631650 + 925 631660 Eu-166 8.58430E-10 8.58430E-10 631660 + 926 631670 Eu-167 2.73860E-11 2.73860E-11 631670 + 927 641540 Gd-154 1.85040E-10 6.72470E-06 64154.82c + 928 641550 Gd-155 2.45080E-09 4.08780E-03 64155.82c + 929 641551 Gd-155m 6.85710E-09 6.85710E-09 641551 + 930 641560 Gd-156 1.44070E-07 2.60670E-03 64156.82c + 931 641570 Gd-157 2.35050E-06 1.61860E-03 64157.82c + 932 641580 Gd-158 6.38270E-06 8.24270E-04 64158.82c + 933 641590 Gd-159 3.00330E-05 7.88290E-04 641590 + 934 641600 Gd-160 4.78240E-05 4.39630E-04 64160.82c + 935 641610 Gd-161 7.25900E-05 3.59750E-04 641610 + 936 641620 Gd-162 5.27730E-05 1.12700E-04 641620 + 937 641630 Gd-163 5.86250E-05 9.67330E-05 641630 + 938 641640 Gd-164 2.07940E-05 2.16090E-05 641640 + 939 641650 Gd-165 6.52260E-06 6.57890E-06 641650 + 940 641660 Gd-166 2.68680E-06 2.68770E-06 641660 + 941 641670 Gd-167 4.01800E-08 4.02070E-08 641670 + 942 641680 Gd-168 7.01120E-09 7.01120E-09 641680 + 943 641690 Gd-169 2.96490E-10 2.96490E-10 641690 + 944 651570 Tb-157 3.62630E-10 3.62630E-10 651570 + 945 651580 Tb-158 7.01820E-09 7.70390E-09 651580 + 946 651581 Tb-158m 6.89870E-10 6.89870E-10 651581 + 947 651590 Tb-159 1.37680E-07 7.88430E-04 65159.82c + 948 651600 Tb-160 5.63950E-06 5.63950E-06 65160.82c + 949 651610 Tb-161 1.21130E-05 3.71860E-04 651610 + 950 651620 Tb-162 1.40740E-05 1.26780E-04 651620 + 951 651630 Tb-163 2.75590E-05 1.24290E-04 651630 + 952 651640 Tb-164 2.77020E-05 4.93110E-05 651640 + 953 651650 Tb-165 3.05400E-05 3.71190E-05 651650 + 954 651660 Tb-166 2.68650E-06 5.37420E-06 651660 + 955 651670 Tb-167 2.20540E-06 2.24560E-06 651670 + 956 651680 Tb-168 7.21270E-07 7.28280E-07 651680 + 957 651690 Tb-169 8.24110E-08 8.27080E-08 651690 + 958 651700 Tb-170 5.88940E-09 5.88940E-09 651700 + 959 651710 Tb-171 2.88300E-10 2.88300E-10 651710 + 960 661590 Dy-159 3.04960E-11 3.04960E-11 661590 + 961 661600 Dy-160 9.41060E-10 5.64040E-06 66160.82c + 962 661610 Dy-161 2.52170E-08 3.71890E-04 66161.82c + 963 661620 Dy-162 1.23220E-07 1.26900E-04 66162.82c + 964 661630 Dy-163 1.35730E-06 1.25650E-04 66163.82c + 965 661640 Dy-164 2.72830E-06 5.20440E-05 66164.82c + 966 661650 Dy-165 6.33130E-06 4.42740E-05 661650 + 967 661651 Dy-165m 8.42980E-07 8.42980E-07 661651 + 968 661660 Dy-166 2.52310E-06 7.89730E-06 661660 + 969 661670 Dy-167 3.53610E-06 5.78170E-06 661670 + 970 661680 Dy-168 6.19750E-06 6.92580E-06 661680 + 971 661690 Dy-169 2.91500E-06 2.99770E-06 661690 + 972 661700 Dy-170 5.24240E-07 5.30130E-07 661700 + 973 661710 Dy-171 1.18180E-07 1.18470E-07 661710 + 974 661720 Dy-172 9.88360E-09 9.88360E-09 661720 + 975 661730 Dy-173 6.37120E-10 6.37120E-10 661730 + 976 671620 Ho-162 9.01900E-12 2.42610E-11 671620 + 977 671621 Ho-162m 2.45840E-11 2.45840E-11 671621 + 978 671630 Ho-163 9.18150E-10 1.04040E-09 671630 + 979 671631 Ho-163m 1.22250E-10 1.22250E-10 671631 + 980 671640 Ho-164 2.67310E-09 9.95940E-09 671640 + 981 671641 Ho-164m 7.28630E-09 7.28630E-09 671641 + 982 671650 Ho-165 6.90490E-08 4.43620E-05 67165.82c + 983 671660 Ho-166 2.83560E-08 7.92560E-06 671660 + 984 671661 Ho-166m 7.72940E-08 7.72940E-08 671661 + 985 671670 Ho-167 2.20510E-06 7.98680E-06 671670 + 986 671680 Ho-168 8.83110E-07 9.27840E-06 671680 + 987 671681 Ho-168m 1.47690E-06 1.47690E-06 671681 + 988 671690 Ho-169 2.39810E-06 5.39580E-06 671690 + 989 671700 Ho-170 2.08650E-06 2.08650E-06 671700 + 990 671701 Ho-170m 7.65450E-07 1.29560E-06 671701 + 991 671710 Ho-171 8.49730E-07 9.68200E-07 671710 + 992 671720 Ho-172 3.01970E-07 3.11850E-07 671720 + 993 671730 Ho-173 5.03470E-08 5.09840E-08 671730 + 994 671740 Ho-174 7.96610E-09 7.96610E-09 671740 + 995 671750 Ho-175 5.49090E-10 5.49090E-10 671750 + 996 681640 Er-164 1.62490E-12 5.15060E-09 68164.82c + 997 681650 Er-165 7.75530E-11 7.75530E-11 681650 + 998 681660 Er-166 3.27650E-10 7.92590E-06 68166.82c + 999 681670 Er-167 4.46080E-09 7.99190E-06 68167.82c + 1000 681671 Er-167m 5.93930E-10 9.54950E-07 681671 + 1001 681680 Er-168 8.80960E-08 9.37400E-06 68168.82c + 1002 681690 Er-169 3.77770E-07 5.77360E-06 681690 + 1003 681700 Er-170 5.90000E-07 3.97200E-06 68170.82c + 1004 681710 Er-171 1.15840E-06 2.12660E-06 681710 + 1005 681720 Er-172 8.90390E-07 1.20220E-06 681720 + 1006 681730 Er-173 5.77090E-07 6.28070E-07 681730 + 1007 681740 Er-174 2.16270E-07 2.24240E-07 681740 + 1008 681750 Er-175 6.52810E-08 6.58300E-08 681750 + 1009 681760 Er-176 8.62620E-09 8.62620E-09 681760 + 1010 681770 Er-177 8.76480E-10 8.76480E-10 681770 + 1011 691670 Tm-167 1.01810E-12 1.01810E-12 691670 + 1012 691680 Tm-168 9.03150E-11 9.03150E-11 691680 + 1013 691690 Tm-169 1.05950E-09 5.77460E-06 691690 + 1014 691700 Tm-170 7.58270E-09 7.58270E-09 691700 + 1015 691710 Tm-171 3.72220E-08 2.16380E-06 691710 + 1016 691720 Tm-172 1.16970E-07 1.31920E-06 691720 + 1017 691730 Tm-173 1.68480E-07 7.96550E-07 691730 + 1018 691740 Tm-174 2.37220E-07 4.61460E-07 691740 + 1019 691750 Tm-175 1.56760E-07 2.22590E-07 691750 + 1020 691760 Tm-176 8.27740E-08 9.14000E-08 691760 + 1021 691770 Tm-177 2.05590E-08 2.14360E-08 691770 + 1022 691780 Tm-178 5.03570E-09 5.03570E-09 691780 + 1023 691790 Tm-179 5.63230E-10 5.63230E-10 691790 + 1024 701700 Yb-170 6.49780E-12 7.57930E-09 701700 + 1025 701710 Yb-171 1.81220E-11 2.16400E-06 701710 + 1026 701711 Yb-171m 1.36110E-10 1.36110E-10 701711 + 1027 701720 Yb-172 1.30410E-09 1.32050E-06 701720 + 1028 701730 Yb-173 8.39650E-09 8.04960E-07 701730 + 1029 701740 Yb-174 2.86680E-08 4.90230E-07 701740 + 1030 701750 Yb-175 6.63050E-08 2.97720E-07 701750 + 1031 701751 Yb-175m 8.82810E-09 1.80220E-07 701751 + 1032 701760 Yb-176 2.79210E-08 1.67470E-07 701760 + 1033 701761 Yb-176m 5.85750E-08 1.04270E-07 701761 + 1034 701770 Yb-177 6.72820E-08 1.02260E-07 701770 + 1035 701771 Yb-177m 1.35470E-08 3.49820E-08 701771 + 1036 701780 Yb-178 4.42730E-08 4.93090E-08 701780 + 1037 701790 Yb-179 2.04120E-08 2.09750E-08 701790 + 1038 701800 Yb-180 4.60440E-09 4.60440E-09 701800 + 1039 701810 Yb-181 7.98540E-10 7.98540E-10 701810 + 1040 711730 Lu-173 6.61330E-12 6.61330E-12 711730 + 1041 711740 Lu-174 2.88310E-11 1.06960E-10 711740 + 1042 711741 Lu-174m 7.85880E-11 7.85880E-11 711741 + 1043 711750 Lu-175 7.41480E-10 2.98470E-07 71175.82c + 1044 711760 Lu-176 2.51230E-09 1.29400E-08 71176.82c + 1045 711761 Lu-176m 1.19760E-09 1.19760E-09 711761 + 1046 711770 Lu-177 5.43040E-09 1.08290E-07 711770 + 1047 711771 Lu-177m 2.58570E-09 2.65010E-09 711771 + 1048 711772 Lu-177m 1.28670E-10 1.28670E-10 711772 + 1049 711780 Lu-178 7.36540E-09 5.66740E-08 711780 + 1050 711781 Lu-178m 9.86760E-09 9.86760E-09 711781 + 1051 711790 Lu-179 1.51460E-08 3.81370E-08 711790 + 1052 711791 Lu-179m 2.01650E-09 2.29920E-08 711791 + 1053 711800 Lu-180 3.91040E-09 1.16300E-08 711800 + 1054 711801 Lu-180m 3.91040E-09 8.51480E-09 711801 + 1055 711802 Lu-180m 6.92420E-09 6.92420E-09 711802 + 1056 711810 Lu-181 5.87920E-09 6.67770E-09 711810 + 1057 711820 Lu-182 2.06700E-09 2.06700E-09 711820 + 1058 711830 Lu-183 3.41220E-10 3.41220E-10 711830 + 1059 711840 Lu-184 5.33680E-11 5.33680E-11 711840 + 1060 721760 Hf-176 1.18160E-11 1.20820E-09 72176.82c + 1061 721770 Hf-177 8.08830E-11 1.10530E-07 72177.82c + 1062 721771 Hf-177m 3.81610E-11 2.15590E-09 721771 + 1063 721772 Hf-177m 2.25620E-12 6.65940E-11 721772 + 1064 721780 Hf-178 2.12840E-10 6.72010E-08 72178.82c + 1065 721781 Hf-178m 3.96930E-10 1.03140E-08 721781 + 1066 721782 Hf-178m 4.96490E-11 4.96490E-11 721782 + 1067 721790 Hf-179 1.60290E-09 4.09130E-08 72179.82c + 1068 721791 Hf-179m 4.63830E-10 4.63830E-10 721791 + 1069 721792 Hf-179m 7.00730E-10 7.00730E-10 721792 + 1070 721800 Hf-180 1.74910E-09 2.47710E-08 72180.82c + 1071 721801 Hf-180m 3.66940E-09 7.13150E-09 721801 + 1072 721810 Hf-181 8.19040E-09 1.48680E-08 721810 + 1073 721820 Hf-182 2.01120E-09 5.85030E-09 721820 + 1074 721821 Hf-182m 4.21930E-09 4.21930E-09 721821 + 1075 721830 Hf-183 4.00220E-09 4.34340E-09 721830 + 1076 721840 Hf-184 4.79160E-10 5.05850E-10 721840 + 1077 721841 Hf-184m 1.00520E-09 1.03190E-09 721841 + 1078 721850 Hf-185 4.43060E-10 4.43060E-10 721850 + 1079 721860 Hf-186 5.79010E-11 5.79010E-11 721860 + 1080 721870 Hf-187 5.82010E-12 5.82010E-12 721870 + 1081 731790 Ta-179 5.68440E-12 7.96690E-12 731790 + 1082 731791 Ta-179m 2.15660E-12 2.28250E-12 731791 + 1083 731800 Ta-180 3.05250E-11 3.05250E-11 731800 + 1084 731801 Ta-180m 4.08950E-11 6.30020E-11 731801 + 1085 731810 Ta-181 2.69600E-10 1.51390E-08 73181.82c + 1086 731820 Ta-182 2.70310E-10 3.28470E-09 73182.82c + 1087 731821 Ta-182m 2.95270E-10 3.01440E-09 731821 + 1088 731822 Ta-182m 2.71900E-10 2.71910E-09 731822 + 1089 731830 Ta-183 1.19430E-09 5.53770E-09 731830 + 1090 731840 Ta-184 1.66380E-09 3.20160E-09 731840 + 1091 731850 Ta-185 6.81410E-10 1.53110E-09 731850 + 1092 731851 Ta-185m 4.06590E-10 4.06590E-10 731851 + 1093 731860 Ta-186 5.68870E-10 6.26770E-10 731860 + 1094 731870 Ta-187 1.39960E-10 1.45780E-10 731870 + 1095 731880 Ta-188 3.40010E-11 3.40010E-11 731880 + 1096 731890 Ta-189 3.76890E-12 3.76890E-12 731890 + 1097 741810 W-181 1.14750E-12 1.14750E-12 741810 + 1098 741820 W-182 9.58000E-12 3.29420E-09 74182.82c + 1099 741830 W-183 1.27450E-11 5.59870E-09 74183.82c + 1100 741831 W-183m 4.82660E-11 2.36550E-10 741831 + 1101 741840 W-184 2.05840E-10 3.40740E-09 74184.82c + 1102 741850 W-185 1.40390E-10 2.06420E-09 741850 + 1103 741851 W-185m 3.92790E-10 3.92790E-10 741851 + 1104 741860 W-186 4.32390E-10 1.23490E-09 74186.82c + 1105 741861 W-186m 1.75070E-10 1.75070E-10 741861 + 1106 741870 W-187 5.62520E-10 7.08300E-10 741870 + 1107 741880 W-188 3.05880E-10 3.39880E-10 741880 + 1108 741890 W-189 1.39950E-10 1.43720E-10 741890 + 1109 741900 W-190 1.33400E-11 3.12120E-11 741900 + 1110 741901 W-190m 1.78720E-11 1.78720E-11 741901 + 1111 741910 W-191 5.35000E-12 5.35000E-12 741910 + 1112 751850 Re-185 5.39630E-12 2.06960E-09 75185.82c + 1113 751860 Re-186 9.98700E-12 9.98700E-12 751860 + 1114 751861 Re-186m 1.67020E-11 1.67020E-11 751861 + 1115 751870 Re-187 5.79840E-11 7.66280E-10 75187.82c + 1116 751880 Re-188 3.26640E-11 4.61580E-10 751880 + 1117 751881 Re-188m 8.90360E-11 8.90360E-11 751881 + 1118 751890 Re-189 1.20250E-10 2.63970E-10 751890 + 1119 751900 Re-190 3.29970E-11 9.57740E-11 751900 + 1120 751901 Re-190m 6.92230E-11 6.92230E-11 751901 + 1121 751910 Re-191 4.03300E-11 4.56800E-11 751910 + 1122 751920 Re-192 1.40720E-11 1.40720E-11 751920 + 1123 751930 Re-193 2.30470E-12 2.30470E-12 751930 + 1124 761880 Os-188 4.77260E-12 4.66350E-10 761880 + 1125 761890 Os-189 4.14690E-12 2.83820E-10 761890 + 1126 761891 Os-189m 1.57040E-11 4.28480E-11 761891 + 1127 761900 Os-190 1.64160E-11 1.71840E-10 761900 + 1128 761901 Os-190m 2.19920E-11 5.96500E-11 761901 + 1129 761910 Os-191 4.54190E-11 1.03090E-10 761910 + 1130 761911 Os-191m 1.19940E-11 1.19940E-11 761911 + 1131 761920 Os-192 1.85300E-11 5.46420E-11 761920 + 1132 761921 Os-192m 2.48260E-11 2.48260E-11 761921 + 1133 761930 Os-193 2.76590E-11 2.99640E-11 761930 + 1134 761940 Os-194 1.01640E-11 1.01640E-11 761940 + 1135 761950 Os-195 3.00220E-12 3.00220E-12 761950 + 1136 771910 Ir-191 5.09720E-13 1.05030E-10 77191.82c + 1137 771911 Ir-191m 1.06490E-12 5.00860E-11 771911 + 1138 771920 Ir-192 1.98690E-12 9.18780E-12 771920 + 1139 771921 Ir-192m 1.98690E-12 1.98690E-12 771921 + 1140 771922 Ir-192m 1.98690E-12 5.21430E-12 771922 + 1141 771930 Ir-193 2.22120E-12 3.84000E-11 77193.82c + 1142 771931 Ir-193m 6.21480E-12 6.31890E-12 771931 + 1143 771940 Ir-194 3.88060E-12 1.79250E-11 771940 + 1144 771941 Ir-194m 3.88060E-12 3.88060E-12 771941 + 1145 771942 Ir-194m 3.88060E-12 3.88060E-12 771942 + 1146 771950 Ir-195 1.98520E-12 5.26510E-12 771950 + 1147 771951 Ir-195m 5.55440E-12 5.55440E-12 771951 + 1148 771960 Ir-196 1.95280E-12 1.95870E-12 771960 + 1149 771961 Ir-196m 1.95280E-12 1.95280E-12 771961 + 1150 781940 Pt-194 1.47450E-12 2.32800E-11 781940 + 1151 781950 Pt-195 9.94750E-13 1.43200E-11 781950 + 1152 781951 Pt-195m 2.78320E-12 4.47180E-12 781951 + 1153 781960 Pt-196 4.26190E-12 8.16750E-12 781960 + 1154 781970 Pt-197 1.03010E-12 3.81710E-12 781970 + 1155 781971 Pt-197m 2.88210E-12 2.88210E-12 781971 + + Nuclide 95242.82c -- americium 242 (Am-242) is using NFY data from Am-242m + + Nuclide 95642.82c -- americium 242m (Am-242m) + + Neutron-induced fission: + + Interpolation region : 1 / 2 + Interpolation energy : 2.53000E-08 MeV + Number of products : 1064 / 1134 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 3.32190E-05 3.32190E-05 1001.82c + 2 10020 H-2 1.01520E-05 1.01520E-05 1002.82c + 3 10030 H-3 1.60000E-04 1.60000E-04 1003.82c + 4 20040 He-4 2.10000E-03 2.10000E-03 2004.82c + 5 200500 Ca-50 4.33200E-12 4.33200E-12 200500 + 6 200510 Ca-51 4.67750E-12 4.67750E-12 200510 + 7 200520 Ca-52 3.48070E-12 3.48070E-12 200520 + 8 200530 Ca-53 1.30580E-12 1.30580E-12 200530 + 9 210500 Sc-50 1.27220E-12 6.08650E-12 210500 + 10 210501 Sc-50m 5.43170E-13 4.87520E-12 210501 + 11 210510 Sc-51 6.63760E-12 1.13850E-11 210510 + 12 210520 Sc-52 1.34420E-11 1.72450E-11 210520 + 13 210530 Sc-53 1.86630E-11 1.95770E-11 210530 + 14 210540 Sc-54 1.44260E-11 1.44260E-11 210540 + 15 210550 Sc-55 8.49790E-12 8.49790E-12 210550 + 16 210560 Sc-56 2.66640E-12 2.66640E-12 210560 + 17 220520 Ti-52 5.80860E-12 2.30530E-11 220520 + 18 220530 Ti-53 2.15670E-11 4.11440E-11 220530 + 19 220540 Ti-54 5.67980E-11 7.12240E-11 220540 + 20 220550 Ti-55 9.36960E-11 1.02190E-10 220550 + 21 220560 Ti-56 1.12910E-10 1.15580E-10 220560 + 22 220570 Ti-57 7.33290E-11 7.33290E-11 220570 + 23 220580 Ti-58 3.13920E-11 3.13920E-11 220580 + 24 220590 Ti-59 7.12310E-12 7.12310E-12 220590 + 25 220600 Ti-60 1.07120E-12 1.07120E-12 220600 + 26 230530 V-53 1.00020E-12 4.21440E-11 230530 + 27 230540 V-54 7.67040E-12 7.88940E-11 230540 + 28 230550 V-55 4.40460E-11 1.46240E-10 230550 + 29 230560 V-56 1.40890E-10 2.56690E-10 230560 + 30 230570 V-57 3.17590E-10 3.90700E-10 230570 + 31 230580 V-58 3.94220E-10 4.25610E-10 230580 + 32 230590 V-59 3.56250E-10 3.63370E-10 230590 + 33 230600 V-60 1.78150E-10 1.79220E-10 230600 + 34 230610 V-61 6.42940E-11 6.42940E-11 230610 + 35 230620 V-62 1.16950E-11 1.16950E-11 230620 + 36 230630 V-63 1.29580E-12 1.29580E-12 230630 + 37 240550 Cr-55 1.54300E-12 1.47780E-10 240550 + 38 240560 Cr-56 1.90400E-11 2.77290E-10 240560 + 39 240570 Cr-57 1.20660E-10 8.50290E-10 240570 + 40 240580 Cr-58 5.11070E-10 5.96190E-10 240580 + 41 240590 Cr-59 1.23320E-09 1.59660E-09 240590 + 42 240600 Cr-60 2.20230E-09 2.38540E-09 240600 + 43 240610 Cr-61 2.39180E-09 2.45220E-09 240610 + 44 240620 Cr-62 1.79140E-09 1.80360E-09 240620 + 45 240630 Cr-63 6.76570E-10 6.77410E-10 240630 + 46 240640 Cr-64 1.68530E-10 1.68530E-10 240640 + 47 240650 Cr-65 2.35390E-11 2.35390E-11 240650 + 48 240660 Cr-66 2.13710E-12 2.13710E-12 240660 + 49 250570 Mn-57 1.56770E-12 8.51850E-10 250570 + 50 250580 Mn-58 1.87170E-11 6.14910E-10 250580 + 51 250581 Mn-58m 2.10740E-12 2.10740E-12 250581 + 52 250590 Mn-59 1.86760E-10 1.78330E-09 250590 + 53 250600 Mn-60 9.21250E-11 2.57160E-09 250600 + 54 250601 Mn-60m 8.18200E-10 8.18200E-10 250601 + 55 250610 Mn-61 3.34790E-09 5.80010E-09 250610 + 56 250620 Mn-62 5.78220E-09 6.68390E-09 250620 + 57 250621 Mn-62m 1.03800E-09 1.93980E-09 250621 + 58 250630 Mn-63 9.52330E-09 1.02010E-08 250630 + 59 250640 Mn-64 7.40280E-09 7.57130E-09 250640 + 60 250650 Mn-65 4.38450E-09 4.40800E-09 250650 + 61 250660 Mn-66 1.38420E-09 1.38630E-09 250660 + 62 250670 Mn-67 2.80450E-10 2.80450E-10 250670 + 63 250680 Mn-68 2.78010E-11 2.78010E-11 250680 + 64 250690 Mn-69 1.92710E-12 1.92710E-12 250690 + 65 260590 Fe-59 1.77260E-12 1.78510E-09 260590 + 66 260600 Fe-60 3.57410E-11 3.33150E-09 260600 + 67 260610 Fe-61 3.97630E-10 6.19780E-09 260610 + 68 260620 Fe-62 2.90630E-09 1.15300E-08 260620 + 69 260630 Fe-63 1.08570E-08 2.10580E-08 260630 + 70 260640 Fe-64 2.87420E-08 3.63130E-08 260640 + 71 260650 Fe-65 4.76360E-08 5.20440E-08 260650 + 72 260660 Fe-66 5.77020E-08 5.90880E-08 260660 + 73 260670 Fe-67 3.77240E-08 3.80050E-08 260670 + 74 260680 Fe-68 1.62580E-08 1.62860E-08 260680 + 75 260690 Fe-69 3.98050E-09 3.98200E-09 260690 + 76 260700 Fe-70 4.65670E-10 4.65670E-10 260700 + 77 260710 Fe-71 1.79640E-11 1.79640E-11 260710 + 78 260720 Fe-72 1.78410E-12 1.78410E-12 260720 + 79 270610 Co-61 1.35930E-12 6.19910E-09 270610 + 80 270620 Co-62 9.92240E-12 1.15400E-08 270620 + 81 270621 Co-62m 2.32410E-11 2.32410E-11 270621 + 82 270630 Co-63 4.95850E-10 2.15540E-08 270630 + 83 270640 Co-64 3.82620E-09 4.01400E-08 270640 + 84 270650 Co-65 2.20890E-08 7.41330E-08 270650 + 85 270660 Co-66 7.10230E-08 1.30110E-07 270660 + 86 270670 Co-67 1.61060E-07 1.99060E-07 270670 + 87 270680 Co-68 1.06830E-07 1.62240E-07 270680 + 88 270681 Co-68m 9.42460E-08 1.10810E-07 270681 + 89 270690 Co-69 1.95890E-07 1.99590E-07 270690 + 90 270700 Co-70 3.80770E-08 3.80770E-08 270700 + 91 270701 Co-70m 3.80770E-08 3.85430E-08 270701 + 92 270710 Co-71 1.30380E-08 1.30560E-08 270710 + 93 270720 Co-72 4.71980E-09 4.72160E-09 270720 + 94 270730 Co-73 5.35670E-10 5.35670E-10 270730 + 95 270740 Co-74 4.46220E-11 4.46220E-11 270740 + 96 280630 Ni-63 1.20780E-12 2.15550E-08 280630 + 97 280640 Ni-64 4.06820E-11 4.01800E-08 28064.82c + 98 280650 Ni-65 7.61760E-10 7.48950E-08 280650 + 99 280660 Ni-66 9.45730E-09 1.39570E-07 280660 + 100 280670 Ni-67 6.03440E-08 2.59410E-07 280670 + 101 280680 Ni-68 2.57150E-07 4.76790E-07 280680 + 102 280690 Ni-69 3.34380E-07 5.31980E-07 280690 + 103 280691 Ni-69m 3.34380E-07 3.34380E-07 280691 + 104 280700 Ni-70 1.34000E-06 1.41660E-06 280700 + 105 280710 Ni-71 4.77460E-07 4.90520E-07 280710 + 106 280720 Ni-72 7.11150E-07 7.15870E-07 280720 + 107 280730 Ni-73 2.74990E-07 2.75530E-07 280730 + 108 280740 Ni-74 1.02850E-07 1.02890E-07 280740 + 109 280750 Ni-75 9.98500E-09 9.98500E-09 280750 + 110 280760 Ni-76 7.70760E-10 7.70760E-10 280760 + 111 280770 Ni-77 5.12740E-11 5.12740E-11 280770 + 112 290660 Cu-66 2.83830E-11 1.39600E-07 290660 + 113 290670 Cu-67 7.71440E-10 2.60180E-07 290670 + 114 290680 Cu-68 3.08740E-09 4.85950E-07 290680 + 115 290681 Cu-68m 7.23160E-09 7.23160E-09 290681 + 116 290690 Cu-69 9.40250E-07 1.80660E-06 290690 + 117 290700 Cu-70 2.87850E-08 2.25260E-07 290700 + 118 290701 Cu-70m 3.20680E-07 3.92950E-07 290701 + 119 290702 Cu-70m 2.87850E-08 1.44540E-06 290702 + 120 290710 Cu-71 1.24200E-06 1.73250E-06 290710 + 121 290720 Cu-72 1.56510E-06 2.28100E-06 290720 + 122 290730 Cu-73 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4.34850E-02 41095.82c + 359 410951 Nb-95m 1.21630E-06 4.71220E-04 410951 + 360 410960 Nb-96 6.97790E-05 6.97790E-05 410960 + 361 410970 Nb-97 4.07160E-04 5.00020E-02 410970 + 362 410971 Nb-97m 9.41440E-05 4.71440E-02 410971 + 363 410980 Nb-98 4.76420E-04 5.78270E-02 410980 + 364 410981 Nb-98m 1.43770E-03 1.43770E-03 410981 + 365 410990 Nb-99 6.25060E-03 3.59890E-02 410990 + 366 410991 Nb-99m 1.44530E-03 1.85460E-02 410991 + 367 411000 Nb-100 2.87050E-03 4.15360E-02 411000 + 368 411001 Nb-100m 1.20720E-02 1.20720E-02 411001 + 369 411010 Nb-101 2.99530E-02 5.07970E-02 411010 + 370 411020 Nb-102 1.40790E-02 2.55610E-02 411020 + 371 411021 Nb-102m 1.40790E-02 1.40790E-02 411021 + 372 411030 Nb-103 2.47570E-02 2.78990E-02 411030 + 373 411040 Nb-104 6.30150E-03 7.22510E-03 411040 + 374 411041 Nb-104m 6.30150E-03 6.30150E-03 411041 + 375 411050 Nb-105 6.85160E-03 6.98020E-03 411050 + 376 411060 Nb-106 2.18050E-03 2.20430E-03 411060 + 377 411070 Nb-107 5.29330E-04 5.31490E-04 411070 + 378 411080 Nb-108 7.46460E-05 7.46460E-05 411080 + 379 411090 Nb-109 1.07890E-05 1.07890E-05 411090 + 380 411100 Nb-110 1.16810E-09 1.16810E-09 411100 + 381 420960 Mo-96 1.74080E-09 6.97810E-05 42096.82c + 382 420970 Mo-97 2.32390E-06 5.00050E-02 42097.82c + 383 420980 Mo-98 6.07270E-05 5.93250E-02 42098.82c + 384 420990 Mo-99 3.75860E-04 5.45400E-02 42099.82c + 385 421000 Mo-100 2.17200E-03 5.57800E-02 42100.82c + 386 421010 Mo-101 6.53360E-03 5.73310E-02 421010 + 387 421020 Mo-102 1.93590E-02 5.89990E-02 421020 + 388 421030 Mo-103 2.59720E-02 5.38790E-02 421030 + 389 421040 Mo-104 3.54060E-02 4.90440E-02 421040 + 390 421050 Mo-105 2.60640E-02 3.30250E-02 421050 + 391 421060 Mo-106 2.17530E-02 2.38900E-02 421060 + 392 421070 Mo-107 8.20660E-03 8.71080E-03 421070 + 393 421080 Mo-108 3.47470E-03 3.54610E-03 421080 + 394 421090 Mo-109 7.58980E-04 7.68400E-04 421090 + 395 421100 Mo-110 1.34980E-04 1.34980E-04 421100 + 396 421110 Mo-111 7.36610E-06 7.36610E-06 421110 + 397 421120 Mo-112 7.14860E-07 7.14860E-07 421120 + 398 430990 Tc-99 8.45820E-07 5.45390E-02 43099.82c + 399 430991 Tc-99m 1.95580E-07 4.80280E-02 430991 + 400 431000 Tc-100 9.03170E-06 9.03170E-06 431000 + 401 431010 Tc-101 1.13410E-04 5.74440E-02 431010 + 402 431020 Tc-102 2.76280E-04 5.92750E-02 431020 + 403 431021 Tc-102m 2.76280E-04 2.76280E-04 431021 + 404 431030 Tc-103 2.49190E-03 5.63700E-02 431030 + 405 431040 Tc-104 6.09490E-03 5.51390E-02 431040 + 406 431050 Tc-105 1.57810E-02 4.88060E-02 431050 + 407 431060 Tc-106 2.18980E-02 4.57880E-02 431060 + 408 431070 Tc-107 2.40100E-02 3.27210E-02 431070 + 409 431080 Tc-108 1.60510E-02 1.96010E-02 431080 + 410 431090 Tc-109 1.06430E-02 1.14070E-02 431090 + 411 431100 Tc-110 4.27730E-03 4.41240E-03 431100 + 412 431110 Tc-111 1.26930E-03 1.27660E-03 431110 + 413 431120 Tc-112 2.00020E-04 2.00720E-04 431120 + 414 431130 Tc-113 2.43160E-05 2.43160E-05 431130 + 415 431140 Tc-114 1.33330E-06 1.33330E-06 431140 + 416 431150 Tc-115 4.42570E-11 4.42570E-11 431150 + 417 441010 Ru-101 1.85900E-09 5.74440E-02 44101.82c + 418 441020 Ru-102 6.84490E-06 5.95580E-02 44102.82c + 419 441030 Ru-103 1.75190E-05 5.64300E-02 44103.82c + 420 441031 Ru-103m 4.22920E-05 4.22920E-05 441031 + 421 441040 Ru-104 3.59380E-04 5.54980E-02 44104.82c + 422 441050 Ru-105 1.34090E-03 5.01470E-02 44105.82c + 423 441060 Ru-106 5.17620E-03 5.09640E-02 44106.82c + 424 441070 Ru-107 8.08950E-03 4.08100E-02 441070 + 425 441080 Ru-108 1.50080E-02 3.46180E-02 441080 + 426 441090 Ru-109 1.41670E-02 2.55670E-02 441090 + 427 441100 Ru-110 1.29820E-02 1.73930E-02 441100 + 428 441110 Ru-111 5.85810E-03 7.13770E-03 441110 + 429 441120 Ru-112 2.48380E-03 2.68330E-03 441120 + 430 441130 Ru-113 2.77730E-04 4.39250E-04 441130 + 431 441131 Ru-113m 2.77730E-04 2.77730E-04 441131 + 432 441140 Ru-114 1.82180E-04 1.83430E-04 441140 + 433 441150 Ru-115 3.91020E-05 3.91020E-05 441150 + 434 441160 Ru-116 1.82370E-05 1.82370E-05 441160 + 435 441170 Ru-117 4.41620E-06 4.41620E-06 441170 + 436 441180 Ru-118 3.29940E-06 3.29940E-06 441180 + 437 451040 Rh-104 7.97850E-07 3.20240E-06 451040 + 438 451041 Rh-104m 2.40770E-06 2.40770E-06 451041 + 439 451050 Rh-105 5.51520E-06 5.01530E-02 45105.82c + 440 451051 Rh-105m 8.43110E-07 1.42360E-02 451051 + 441 451060 Rh-106 2.08810E-05 5.09850E-02 451060 + 442 451061 Rh-106m 4.89080E-05 4.89080E-05 451061 + 443 451070 Rh-107 3.75920E-04 4.11860E-02 451070 + 444 451080 Rh-108 2.87480E-04 3.49060E-02 451080 + 445 451081 Rh-108m 8.67520E-04 8.67520E-04 451081 + 446 451090 Rh-109 3.06530E-03 2.86320E-02 451090 + 447 451100 Rh-110 4.48710E-03 2.18800E-02 451100 + 448 451101 Rh-110m 1.19780E-04 1.19780E-04 451101 + 449 451110 Rh-111 5.85200E-03 1.29900E-02 451110 + 450 451120 Rh-112 2.02150E-03 4.70480E-03 451120 + 451 451121 Rh-112m 2.02150E-03 2.02150E-03 451121 + 452 451130 Rh-113 2.50350E-03 3.08160E-03 451130 + 453 451140 Rh-114 4.48120E-04 6.31630E-04 451140 + 454 451141 Rh-114m 4.48120E-04 4.48120E-04 451141 + 455 451150 Rh-115 2.99400E-04 3.38610E-04 451150 + 456 451160 Rh-116 2.38480E-05 4.19780E-05 451160 + 457 451161 Rh-116m 5.58580E-05 5.58580E-05 451161 + 458 451170 Rh-117 2.83570E-05 3.28180E-05 451170 + 459 451180 Rh-118 4.61910E-06 7.78290E-06 451180 + 460 451190 Rh-119 3.16660E-10 3.16660E-10 451190 + 461 451200 Rh-120 4.97130E-12 4.97130E-12 451200 + 462 451220 Rh-122 3.44110E-09 3.44110E-09 451220 + 463 461060 Pd-106 1.78460E-09 5.10340E-02 46106.82c + 464 461070 Pd-107 7.78510E-07 4.11890E-02 46107.82c + 465 461071 Pd-107m 1.46310E-06 1.46310E-06 461071 + 466 461080 Pd-108 2.61870E-05 3.57990E-02 46108.82c + 467 461090 Pd-109 4.25160E-05 2.87550E-02 461090 + 468 461091 Pd-109m 7.99040E-05 1.43960E-02 461091 + 469 461100 Pd-110 4.24790E-04 2.24240E-02 46110.82c + 470 461110 Pd-111 2.26260E-04 1.35120E-02 461110 + 471 461111 Pd-111m 4.25210E-04 4.77170E-04 461111 + 472 461120 Pd-112 1.24240E-03 7.96870E-03 461120 + 473 461130 Pd-113 3.05520E-04 4.12470E-03 461130 + 474 461131 Pd-113m 7.37580E-04 7.37580E-04 461131 + 475 461140 Pd-114 8.20820E-04 1.90060E-03 461140 + 476 461150 Pd-115 1.22240E-04 4.34000E-04 461150 + 477 461151 Pd-115m 2.29730E-04 2.78900E-04 461151 + 478 461160 Pd-116 1.90400E-04 2.88240E-04 461160 + 479 461170 Pd-117 2.62930E-05 1.08750E-04 461170 + 480 461171 Pd-117m 4.94150E-05 4.94150E-05 461171 + 481 461180 Pd-118 2.04550E-05 2.80110E-05 461180 + 482 461190 Pd-119 6.73520E-06 6.73550E-06 461190 + 483 461200 Pd-120 1.28890E-06 1.28890E-06 461200 + 484 461210 Pd-121 6.86900E-07 6.86900E-07 461210 + 485 461220 Pd-122 7.13040E-07 7.16480E-07 461220 + 486 461230 Pd-123 4.57070E-07 4.57070E-07 461230 + 487 461240 Pd-124 6.31110E-08 6.31110E-08 461240 + 488 471090 Ag-109 1.02210E-07 2.87550E-02 47109.82c + 489 471091 Ag-109m 6.68630E-07 2.87410E-02 471091 + 490 471100 Ag-110 7.01710E-07 7.24070E-07 471100 + 491 471101 Ag-110m 1.64360E-06 1.64360E-06 47510.82c + 492 471110 Ag-111 1.95520E-06 1.35880E-02 47111.82c + 493 471111 Ag-111m 1.27900E-05 1.35220E-02 471111 + 494 471120 Ag-112 3.36510E-05 8.00230E-03 471120 + 495 471130 Ag-113 1.15170E-05 2.76250E-03 471130 + 496 471131 Ag-113m 7.53400E-05 4.02510E-03 471131 + 497 471140 Ag-114 1.95400E-05 2.00230E-03 471140 + 498 471141 Ag-114m 8.21800E-05 8.21800E-05 471141 + 499 471150 Ag-115 1.49590E-05 4.30810E-04 471150 + 500 471151 Ag-115m 9.78510E-05 4.71610E-04 471151 + 501 471160 Ag-116 2.68120E-05 3.18820E-04 471160 + 502 471161 Ag-116m 6.28010E-05 6.28010E-05 471161 + 503 471170 Ag-117 1.21520E-05 7.45610E-05 471170 + 504 471171 Ag-117m 7.94920E-05 1.33870E-04 471171 + 505 471180 Ag-118 1.42050E-05 6.43470E-05 471180 + 506 471181 Ag-118m 5.97410E-05 6.37450E-05 471181 + 507 471190 Ag-119 9.01720E-06 1.23850E-05 471190 + 508 471191 Ag-119m 5.89860E-05 6.23540E-05 471191 + 509 471200 Ag-120 1.14500E-05 1.83460E-05 471200 + 510 471201 Ag-120m 1.62470E-05 1.68910E-05 471201 + 511 471210 Ag-121 2.74570E-05 2.81420E-05 471210 + 512 471220 Ag-122 3.37560E-06 4.09200E-06 471220 + 513 471221 Ag-122m 3.04060E-06 3.04060E-06 471221 + 514 471230 Ag-123 1.25450E-05 1.30020E-05 471230 + 515 471240 Ag-124 4.44390E-06 6.50840E-06 471240 + 516 471241 Ag-124m 4.00290E-06 4.00290E-06 471241 + 517 471250 Ag-125 4.67580E-06 4.67580E-06 471250 + 518 471260 Ag-126 1.54210E-06 1.54210E-06 471260 + 519 471270 Ag-127 1.07960E-07 1.07960E-07 471270 + 520 471280 Ag-128 5.90060E-09 5.90060E-09 471280 + 521 471290 Ag-129 3.12490E-10 3.12490E-10 471290 + 522 481110 Cd-111 1.04380E-10 1.36560E-02 48111.82c + 523 481111 Cd-111m 3.41480E-10 3.41480E-10 481111 + 524 481120 Cd-112 1.42990E-06 8.00370E-03 48112.82c + 525 481130 Cd-113 1.58250E-07 4.16400E-03 48113.82c + 526 481131 Cd-113m 5.17750E-07 4.82790E-05 481131 + 527 481140 Cd-114 2.00020E-06 2.00430E-03 48114.82c + 528 481150 Cd-115 1.50380E-06 7.69220E-04 481150 + 529 481151 Cd-115m 4.92000E-06 4.05920E-05 48515.82c + 530 481160 Cd-116 8.81770E-06 3.86670E-04 48116.82c + 531 481170 Cd-117 4.13940E-06 1.60740E-04 481170 + 532 481171 Cd-117m 1.35430E-05 5.73360E-05 481171 + 533 481180 Cd-118 2.64200E-05 1.28380E-04 481180 + 534 481190 Cd-119 1.28320E-05 8.13790E-05 481190 + 535 481191 Cd-119m 3.09790E-05 3.71720E-05 481191 + 536 481200 Cd-120 5.73710E-05 8.63580E-05 481200 + 537 481210 Cd-121 1.83070E-05 4.35080E-05 481210 + 538 481211 Cd-121m 4.41940E-05 4.71350E-05 481211 + 539 481220 Cd-122 6.41270E-05 7.12600E-05 481220 + 540 481230 Cd-123 1.72800E-05 2.79210E-05 481230 + 541 481231 Cd-123m 4.17170E-05 4.40840E-05 481231 + 542 481240 Cd-124 1.28630E-04 1.37130E-04 481240 + 543 481250 Cd-125 4.22480E-05 4.45860E-05 481250 + 544 481251 Cd-125m 1.01990E-04 1.04330E-04 481251 + 545 481260 Cd-126 1.30850E-04 1.32390E-04 481260 + 546 481270 Cd-127 5.18830E-05 5.19910E-05 481270 + 547 481280 Cd-128 3.29440E-05 3.29500E-05 481280 + 548 481290 Cd-129 1.78780E-06 1.78800E-06 481290 + 549 481291 Cd-129m 4.31610E-06 4.31620E-06 481291 + 550 481300 Cd-130 1.31640E-07 1.31640E-07 481300 + 551 481310 Cd-131 5.19740E-09 5.19740E-09 481310 + 552 491140 In-114 7.69800E-11 3.01120E-10 491140 + 553 491141 In-114m 1.17990E-10 2.32270E-10 491141 + 554 491142 In-114m 1.14280E-10 1.14280E-10 491142 + 555 491150 In-115 4.74490E-09 7.71360E-04 49115.82c + 556 491151 In-115m 1.09710E-09 7.69230E-04 491151 + 557 491160 In-116 1.60650E-08 1.60650E-08 491160 + 558 491161 In-116m 2.46240E-08 4.84740E-08 491161 + 559 491162 In-116m 2.38500E-08 2.38500E-08 491162 + 560 491170 In-117 5.12600E-07 1.40260E-04 491170 + 561 491171 In-117m 1.18530E-07 1.48300E-04 491171 + 562 491180 In-118 3.28600E-07 1.28710E-04 491180 + 563 491181 In-118m 5.03660E-07 9.84640E-07 491181 + 564 491182 In-118m 4.87810E-07 4.87810E-07 491182 + 565 491190 In-119 3.83050E-06 5.30010E-05 491190 + 566 491191 In-119m 8.85700E-07 7.44340E-05 491191 + 567 491200 In-120 3.43770E-06 8.97960E-05 491200 + 568 491201 In-120m 3.43770E-06 3.43770E-06 491201 + 569 491202 In-120m 3.43770E-06 3.43770E-06 491202 + 570 491210 In-121 2.34470E-05 8.56460E-05 491210 + 571 491211 In-121m 5.42140E-06 3.42760E-05 491211 + 572 491220 In-122 2.18260E-05 9.30860E-05 491220 + 573 491221 In-122m 1.54850E-05 1.54850E-05 491221 + 574 491222 In-122m 1.54850E-05 1.54850E-05 491222 + 575 491230 In-123 7.79800E-05 1.30180E-04 491230 + 576 491231 In-123m 1.80310E-05 3.78420E-05 491231 + 577 491240 In-124 8.32290E-05 2.20360E-04 491240 + 578 491241 In-124m 7.49710E-05 7.49710E-05 491241 + 579 491250 In-125 3.74210E-04 4.99870E-04 491250 + 580 491251 In-125m 8.65250E-05 1.09770E-04 491251 + 581 491260 In-126 3.88700E-04 5.21100E-04 491260 + 582 491261 In-126m 3.50140E-04 3.50140E-04 491261 + 583 491270 In-127 1.04840E-03 1.04840E-03 491270 + 584 491271 In-127m 2.42410E-04 2.94400E-04 491271 + 585 491280 In-128 4.14810E-04 6.16600E-04 491280 + 586 491281 In-128m 1.68850E-04 2.01800E-04 491281 + 587 491282 In-128m 5.25740E-04 5.25740E-04 491282 + 588 491290 In-129 6.45020E-04 6.49340E-04 491290 + 589 491291 In-129m 1.49140E-04 1.50930E-04 491291 + 590 491300 In-130 7.64650E-05 7.65920E-05 491300 + 591 491301 In-130m 8.54040E-05 8.54040E-05 491301 + 592 491302 In-130m 1.45310E-04 1.45310E-04 491302 + 593 491310 In-131 2.90190E-05 2.93190E-05 491310 + 594 491311 In-131m 2.90190E-05 2.90190E-05 491311 + 595 491312 In-131m 2.90190E-05 2.90190E-05 491312 + 596 491320 In-132 4.26700E-06 4.26700E-06 491320 + 597 491330 In-133 3.77750E-08 4.65090E-08 491330 + 598 491331 In-133m 8.73440E-09 8.73440E-09 491331 + 599 491340 In-134 1.49210E-09 1.49210E-09 491340 + 600 501160 Sn-116 1.33520E-11 6.45530E-08 50116.82c + 601 501170 Sn-117 6.97800E-11 2.18710E-04 50117.82c + 602 501171 Sn-117m 2.28300E-10 4.78100E-07 501171 + 603 501180 Sn-118 6.24340E-09 1.29700E-04 50118.82c + 604 501190 Sn-119 2.42970E-08 1.23370E-04 50119.82c + 605 501191 Sn-119m 7.94930E-08 4.79610E-05 501191 + 606 501200 Sn-120 9.26650E-07 9.75990E-05 50120.82c + 607 501210 Sn-121 1.00630E-06 1.20230E-04 501210 + 608 501211 Sn-121m 2.42920E-06 1.21320E-05 501211 + 609 501220 Sn-122 7.13400E-06 1.31190E-04 50122.82c + 610 501230 Sn-123 1.41130E-05 2.40380E-05 50123.82c + 611 501231 Sn-123m 5.84600E-06 1.63940E-04 501231 + 612 501240 Sn-124 6.32090E-05 3.58540E-04 50124.82c + 613 501250 Sn-125 1.22280E-04 2.06720E-04 50125.82c + 614 501251 Sn-125m 5.06510E-05 5.75860E-04 501251 + 615 501260 Sn-126 7.71900E-04 1.64520E-03 50126.82c + 616 501270 Sn-127 1.37180E-03 1.78050E-03 501270 + 617 501271 Sn-127m 5.68260E-04 1.50040E-03 501271 + 618 501280 Sn-128 1.51500E-03 6.20600E-03 501280 + 619 501281 Sn-128m 3.54860E-03 4.07430E-03 501281 + 620 501290 Sn-129 1.53160E-03 2.26280E-03 501290 + 621 501291 Sn-129m 3.69740E-03 3.76660E-03 501291 + 622 501300 Sn-130 1.57700E-03 1.77710E-03 501300 + 623 501301 Sn-130m 3.69380E-03 3.80170E-03 501301 + 624 501310 Sn-131 9.65960E-04 1.02220E-03 501310 + 625 501311 Sn-131m 2.33200E-03 2.36220E-03 501311 + 626 501320 Sn-132 9.98370E-04 1.00270E-03 501320 + 627 501330 Sn-133 1.34970E-04 1.34980E-04 501330 + 628 501340 Sn-134 1.44990E-05 1.45000E-05 501340 + 629 501350 Sn-135 4.35470E-07 4.35470E-07 501350 + 630 501360 Sn-136 1.16460E-08 1.16460E-08 501360 + 631 511190 Sb-119 1.53370E-11 2.02120E-11 511190 + 632 511191 Sb-119m 4.87510E-12 4.87510E-12 511191 + 633 511200 Sb-120 2.65110E-10 2.65110E-10 511200 + 634 511201 Sb-120m 3.76190E-10 3.76190E-10 511201 + 635 511210 Sb-121 2.14270E-08 1.22970E-04 51121.82c + 636 511230 Sb-123 4.43180E-06 1.92410E-04 51123.82c + 637 511240 Sb-124 2.74650E-06 6.45180E-06 51124.82c + 638 511241 Sb-124m 2.10010E-06 4.94040E-06 511241 + 639 511242 Sb-124m 2.84030E-06 2.84030E-06 511242 + 640 511250 Sb-125 2.65570E-05 8.09130E-04 51125.82c + 641 511260 Sb-126 2.46120E-05 3.04910E-05 51126.82c + 642 511261 Sb-126m 1.81970E-05 4.19960E-05 511261 + 643 511262 Sb-126m 2.37990E-05 2.37990E-05 511262 + 644 511270 Sb-127 3.30280E-04 3.61110E-03 511270 + 645 511280 Sb-128 3.88090E-04 6.61790E-03 511280 + 646 511281 Sb-128m 6.62210E-04 6.62210E-04 511281 + 647 511290 Sb-129 3.31880E-03 8.05150E-03 511290 + 648 511291 Sb-129m 2.02810E-03 3.91130E-03 511291 + 649 511300 Sb-130 5.41950E-03 9.09740E-03 511300 + 650 511301 Sb-130m 5.41950E-03 7.32040E-03 511301 + 651 511310 Sb-131 2.17400E-02 2.51240E-02 511310 + 652 511320 Sb-132 7.11680E-03 8.11950E-03 511320 + 653 511321 Sb-132m 5.24520E-03 5.24520E-03 511321 + 654 511330 Sb-133 1.06650E-02 1.08020E-02 511330 + 655 511340 Sb-134 9.20550E-04 9.32630E-04 511340 + 656 511341 Sb-134m 2.15610E-03 2.15620E-03 511341 + 657 511350 Sb-135 6.83190E-04 6.83540E-04 511350 + 658 511360 Sb-136 1.21890E-04 1.21900E-04 511360 + 659 511370 Sb-137 1.43810E-05 1.43810E-05 511370 + 660 511380 Sb-138 6.20580E-08 6.20580E-08 511380 + 661 511390 Sb-139 1.33970E-09 1.33970E-09 511390 + 662 521210 Te-121 9.35580E-13 3.65060E-12 521210 + 663 521211 Te-121m 3.06090E-12 3.06090E-12 521211 + 664 521250 Te-125 1.85050E-11 8.09130E-04 52125.82c + 665 521251 Te-125m 6.05440E-11 1.81060E-04 521251 + 666 521260 Te-126 2.31400E-06 6.89220E-05 52126.82c + 667 521270 Te-127 1.59460E-06 3.60220E-03 521270 + 668 521271 Te-127m 3.84950E-06 5.98950E-04 52527.82c + 669 521280 Te-128 4.89290E-05 7.30520E-03 52128.82c + 670 521290 Te-129 8.06440E-05 9.88380E-03 521290 + 671 521291 Te-129m 1.94690E-04 4.77760E-03 52529.82c + 672 521300 Te-130 2.06790E-03 1.84860E-02 52130.82c + 673 521310 Te-131 2.09700E-03 2.66950E-02 521310 + 674 521311 Te-131m 5.06250E-03 7.07400E-03 521311 + 675 521320 Te-132 1.87700E-02 3.21350E-02 52132.82c + 676 521330 Te-133 8.98820E-03 2.20480E-02 521330 + 677 521331 Te-133m 2.16990E-02 2.35670E-02 521331 + 678 521340 Te-134 2.88520E-02 3.20460E-02 521340 + 679 521350 Te-135 9.16160E-03 9.75770E-03 521350 + 680 521360 Te-136 5.08340E-03 5.19210E-03 521360 + 681 521370 Te-137 1.03390E-03 1.04120E-03 521370 + 682 521380 Te-138 2.50280E-04 2.50340E-04 521380 + 683 521390 Te-139 1.62810E-05 1.62820E-05 521390 + 684 521400 Te-140 2.15550E-06 2.15550E-06 521400 + 685 521410 Te-141 1.19080E-08 1.19080E-08 521410 + 686 531280 I-128 3.31910E-09 3.31910E-09 531280 + 687 531290 I-129 1.52740E-06 1.16530E-02 53129.82c + 688 531300 I-130 1.87010E-05 2.54080E-05 53130.82c + 689 531301 I-130m 7.98420E-06 7.98420E-06 531301 + 690 531310 I-131 2.47740E-04 3.25320E-02 53131.82c + 691 531320 I-132 5.37780E-04 3.30130E-02 531320 + 692 531321 I-132m 3.96360E-04 3.96360E-04 531321 + 693 531330 I-133 4.54600E-03 4.88150E-02 531330 + 694 531331 I-133m 2.77800E-03 2.77800E-03 531331 + 695 531340 I-134 1.29650E-02 5.43480E-02 531340 + 696 531341 I-134m 9.55570E-03 9.55570E-03 531341 + 697 531350 I-135 4.99620E-02 5.97200E-02 53135.82c + 698 531360 I-136 1.03160E-02 1.55240E-02 531360 + 699 531361 I-136m 2.41630E-02 2.41780E-02 531361 + 700 531370 I-137 2.01950E-02 2.12210E-02 531370 + 701 531380 I-138 9.19880E-03 9.43340E-03 531380 + 702 531390 I-139 4.06640E-03 4.08270E-03 531390 + 703 531400 I-140 1.06480E-03 1.06700E-03 531400 + 704 531410 I-141 2.40320E-04 2.40330E-04 531410 + 705 531420 I-142 1.98070E-05 1.98070E-05 531420 + 706 531430 I-143 5.15850E-08 5.15850E-08 531430 + 707 531440 I-144 1.13000E-09 1.13000E-09 531440 + 708 541300 Xe-130 1.25370E-09 2.66860E-05 54130.82c + 709 541310 Xe-131 3.50130E-08 3.25320E-02 54131.82c + 710 541311 Xe-131m 8.45270E-08 3.53440E-04 541311 + 711 541320 Xe-132 3.33740E-06 3.30760E-02 54132.82c + 712 541321 Xe-132m 3.78310E-06 3.78310E-06 541321 + 713 541330 Xe-133 3.09920E-05 4.89210E-02 54133.82c + 714 541331 Xe-133m 7.48180E-05 1.46430E-03 541331 + 715 541340 Xe-134 2.88600E-04 5.55320E-02 54134.82c + 716 541341 Xe-134m 6.75970E-04 8.95750E-04 541341 + 717 541350 Xe-135 1.33710E-03 6.42060E-02 54135.82c + 718 541351 Xe-135m 3.22800E-03 1.30870E-02 541351 + 719 541360 Xe-136 2.70130E-02 6.80950E-02 54136.82c + 720 541370 Xe-137 3.09000E-02 5.12420E-02 541370 + 721 541380 Xe-138 3.48360E-02 4.41700E-02 541380 + 722 541390 Xe-139 1.40910E-02 1.78730E-02 541390 + 723 541400 Xe-140 1.10900E-02 1.21080E-02 541400 + 724 541410 Xe-141 4.92120E-03 5.11600E-03 541410 + 725 541420 Xe-142 1.49130E-03 1.50620E-03 541420 + 726 541430 Xe-143 2.21770E-04 2.21800E-04 541430 + 727 541440 Xe-144 3.86080E-05 3.86090E-05 541440 + 728 541450 Xe-145 3.56290E-06 3.56290E-06 541450 + 729 541460 Xe-146 7.44100E-09 7.44100E-09 541460 + 730 551330 Cs-133 1.70060E-06 4.89230E-02 55133.82c + 731 551340 Cs-134 1.47470E-06 2.56150E-06 55134.82c + 732 551341 Cs-134m 1.08680E-06 1.08680E-06 551341 + 733 551350 Cs-135 3.90020E-05 6.43480E-02 55135.82c + 734 551351 Cs-135m 2.38330E-05 2.38330E-05 551351 + 735 551360 Cs-136 3.42570E-04 4.42950E-04 55136.82c + 736 551361 Cs-136m 2.00760E-04 2.00760E-04 551361 + 737 551370 Cs-137 5.29400E-03 5.65360E-02 55137.82c + 738 551380 Cs-138 7.05880E-03 5.93410E-02 551380 + 739 551381 Cs-138m 1.00160E-02 1.00160E-02 551381 + 740 551390 Cs-139 3.16490E-02 4.95220E-02 551390 + 741 551400 Cs-140 3.25230E-02 4.46330E-02 551400 + 742 551410 Cs-141 3.91040E-02 4.42230E-02 551410 + 743 551420 Cs-142 1.89120E-02 2.04150E-02 551420 + 744 551430 Cs-143 1.05870E-02 1.08080E-02 551430 + 745 551440 Cs-144 2.13390E-03 3.23850E-03 551440 + 746 551441 Cs-144m 2.13390E-03 2.13400E-03 551441 + 747 551450 Cs-145 1.20940E-03 1.21280E-03 551450 + 748 551460 Cs-146 2.02190E-04 2.02200E-04 551460 + 749 551470 Cs-147 4.40530E-05 4.40530E-05 551470 + 750 551480 Cs-148 5.30900E-06 5.30900E-06 551480 + 751 551490 Cs-149 6.00120E-10 6.00120E-10 551490 + 752 561350 Ba-135 1.12880E-09 3.85390E-09 56135.82c + 753 561351 Ba-135m 2.72510E-09 2.72510E-09 561351 + 754 561360 Ba-136 5.35210E-07 5.45120E-04 56136.82c + 755 561361 Ba-136m 1.25360E-06 1.25360E-06 561361 + 756 561370 Ba-137 8.19740E-06 5.65640E-02 56137.82c + 757 561371 Ba-137m 1.97900E-05 5.33890E-02 561371 + 758 561380 Ba-138 4.73640E-04 6.17180E-02 56138.82c + 759 561390 Ba-139 1.69680E-03 5.12190E-02 561390 + 760 561400 Ba-140 7.48640E-03 5.21200E-02 56140.82c + 761 561410 Ba-141 1.28320E-02 5.70550E-02 561410 + 762 561420 Ba-142 2.76120E-02 4.82040E-02 561420 + 763 561430 Ba-143 2.30940E-02 3.38280E-02 561430 + 764 561440 Ba-144 1.83550E-02 2.27300E-02 561440 + 765 561450 Ba-145 8.36430E-03 9.43240E-03 561450 + 766 561460 Ba-146 4.19000E-03 4.37600E-03 561460 + 767 561470 Ba-147 1.15150E-03 1.18430E-03 561470 + 768 561480 Ba-148 2.58010E-04 2.61990E-04 561480 + 769 561490 Ba-149 2.38270E-05 2.38280E-05 561490 + 770 561500 Ba-150 5.41710E-06 5.41710E-06 561500 + 771 561510 Ba-151 3.59480E-09 3.59480E-09 561510 + 772 571380 La-138 2.10960E-06 2.10960E-06 57138.82c + 773 571390 La-139 2.35770E-05 5.12420E-02 57139.82c + 774 571400 La-140 1.65350E-04 5.22850E-02 57140.82c + 775 571410 La-141 1.09690E-03 5.81520E-02 571410 + 776 571420 La-142 2.54270E-03 5.07470E-02 571420 + 777 571430 La-143 1.11090E-02 4.49370E-02 571430 + 778 571440 La-144 2.02770E-02 4.30070E-02 571440 + 779 571450 La-145 3.09900E-02 4.04220E-02 571450 + 780 571460 La-146 7.79060E-03 1.21670E-02 571460 + 781 571461 La-146m 1.40130E-02 1.40130E-02 571461 + 782 571470 La-147 1.73950E-02 1.85800E-02 571470 + 783 571480 La-148 7.78750E-03 8.04850E-03 571480 + 784 571490 La-149 3.27280E-03 3.29650E-03 571490 + 785 571500 La-150 7.73080E-04 7.78500E-04 571500 + 786 571510 La-151 1.22090E-04 1.22090E-04 571510 + 787 571520 La-152 1.04350E-05 1.04350E-05 571520 + 788 571530 La-153 1.12070E-08 1.12070E-08 571530 + 789 571540 La-154 1.50340E-10 1.50340E-10 571540 + 790 581400 Ce-140 3.58530E-09 5.22850E-02 58140.82c + 791 581410 Ce-141 5.92990E-06 5.81580E-02 58141.82c + 792 581420 Ce-142 3.53130E-05 5.07820E-02 58142.82c + 793 581430 Ce-143 1.41360E-04 4.50790E-02 58143.82c + 794 581440 Ce-144 9.71870E-04 4.39790E-02 58144.82c + 795 581450 Ce-145 2.88490E-03 4.33070E-02 581450 + 796 581460 Ce-146 8.76760E-03 3.49480E-02 581460 + 797 581470 Ce-147 1.15130E-02 3.00930E-02 581470 + 798 581480 Ce-148 1.45600E-02 2.26550E-02 581480 + 799 581490 Ce-149 8.52650E-03 1.17980E-02 581490 + 800 581500 Ce-150 5.28160E-03 6.03910E-03 581500 + 801 581510 Ce-151 1.85340E-03 1.97610E-03 581510 + 802 581520 Ce-152 4.90170E-04 4.99980E-04 581520 + 803 581530 Ce-153 9.33380E-05 9.33490E-05 581530 + 804 581540 Ce-154 1.03920E-05 1.03920E-05 581540 + 805 581550 Ce-155 4.54000E-08 4.54000E-08 581550 + 806 581560 Ce-156 7.58800E-10 7.58800E-10 581560 + 807 591430 Pr-143 1.12310E-06 4.50800E-02 59143.82c + 808 591440 Pr-144 1.42440E-06 4.39930E-02 591440 + 809 591441 Pr-144m 1.26510E-05 6.19540E-04 591441 + 810 591450 Pr-145 8.59600E-05 4.33930E-02 591450 + 811 591460 Pr-146 3.81260E-04 3.53290E-02 591460 + 812 591470 Pr-147 1.84380E-03 3.19370E-02 591470 + 813 591480 Pr-148 8.01670E-04 2.34560E-02 591480 + 814 591481 Pr-148m 3.37150E-03 3.37150E-03 591481 + 815 591490 Pr-149 1.00720E-02 2.18700E-02 591490 + 816 591500 Pr-150 1.05230E-02 1.65620E-02 591500 + 817 591510 Pr-151 1.09220E-02 1.28980E-02 591510 + 818 591520 Pr-152 6.20280E-03 6.70340E-03 591520 + 819 591530 Pr-153 3.01690E-03 3.10970E-03 591530 + 820 591540 Pr-154 8.99540E-04 9.09870E-04 591540 + 821 591550 Pr-155 2.14310E-04 2.14360E-04 591550 + 822 591560 Pr-156 3.71880E-05 3.71890E-05 591560 + 823 591570 Pr-157 7.48820E-06 7.48820E-06 591570 + 824 591580 Pr-158 1.87150E-09 1.87150E-09 591580 + 825 591590 Pr-159 2.20830E-11 2.20830E-11 591590 + 826 601450 Nd-145 2.70160E-09 4.33930E-02 60145.82c + 827 601460 Nd-146 1.12860E-07 3.53290E-02 60146.82c + 828 601470 Nd-147 9.36660E-06 3.19470E-02 60147.82c + 829 601480 Nd-148 1.28520E-04 2.69560E-02 60148.82c + 830 601490 Nd-149 3.58010E-04 2.22280E-02 601490 + 831 601500 Nd-150 1.29480E-03 1.78570E-02 60150.82c + 832 601510 Nd-151 2.44400E-03 1.53420E-02 601510 + 833 601520 Nd-152 4.20270E-03 1.09060E-02 601520 + 834 601530 Nd-153 3.57980E-03 6.68950E-03 601530 + 835 601540 Nd-154 2.64070E-03 3.55060E-03 601540 + 836 601550 Nd-155 1.15540E-03 1.37080E-03 601550 + 837 601560 Nd-156 4.28590E-04 4.65250E-04 601560 + 838 601570 Nd-157 9.41940E-05 1.01200E-04 601570 + 839 601580 Nd-158 1.46020E-05 1.46040E-05 601580 + 840 601590 Nd-159 4.21550E-06 4.21550E-06 601590 + 841 601600 Nd-160 6.48700E-09 6.48700E-09 601600 + 842 601610 Nd-161 9.64660E-11 9.64660E-11 601610 + 843 611480 Pm-148 3.97250E-07 4.43770E-07 61148.82c + 844 611481 Pm-148m 9.30450E-07 9.30450E-07 61548.82c + 845 611490 Pm-149 3.97650E-06 2.22320E-02 61149.82c + 846 611500 Pm-150 4.48300E-05 4.48300E-05 611500 + 847 611510 Pm-151 2.24950E-04 1.55670E-02 61151.82c + 848 611520 Pm-152 1.28010E-04 1.10340E-02 611520 + 849 611521 Pm-152m 2.55630E-04 2.55630E-04 611521 + 850 611522 Pm-152m 2.82750E-04 2.82750E-04 611522 + 851 611530 Pm-153 1.60580E-03 8.29530E-03 611530 + 852 611540 Pm-154 1.09560E-03 4.64620E-03 611540 + 853 611541 Pm-154m 1.09560E-03 1.09560E-03 611541 + 854 611550 Pm-155 2.96540E-03 4.33620E-03 611550 + 855 611560 Pm-156 2.03200E-03 2.49720E-03 611560 + 856 611570 Pm-157 1.29820E-03 1.39940E-03 611570 + 857 611580 Pm-158 4.70220E-04 4.84830E-04 611580 + 858 611590 Pm-159 1.54040E-04 1.58250E-04 611590 + 859 611600 Pm-160 3.59090E-05 3.59150E-05 611600 + 860 611610 Pm-161 7.13280E-06 7.13290E-06 611610 + 861 611620 Pm-162 1.10430E-08 1.10430E-08 611620 + 862 611630 Pm-163 1.63080E-10 1.63080E-10 611630 + 863 621500 Sm-150 1.22680E-09 4.48310E-05 62150.82c + 864 621510 Sm-151 4.31370E-08 1.55670E-02 62151.82c + 865 621520 Sm-152 4.47540E-06 1.15770E-02 62152.82c + 866 621530 Sm-153 6.97720E-06 8.31920E-03 62153.82c + 867 621531 Sm-153m 1.68440E-05 1.68440E-05 621531 + 868 621540 Sm-154 1.28250E-04 5.87000E-03 62154.82c + 869 621550 Sm-155 2.51090E-04 4.58730E-03 621550 + 870 621560 Sm-156 5.94710E-04 3.09200E-03 621560 + 871 621570 Sm-157 5.99940E-04 1.99930E-03 621570 + 872 621580 Sm-158 6.26400E-04 1.11130E-03 621580 + 873 621590 Sm-159 2.82100E-04 4.40410E-04 621590 + 874 621600 Sm-160 1.56440E-04 1.92260E-04 621600 + 875 621610 Sm-161 4.41990E-05 5.13320E-05 621610 + 876 621620 Sm-162 1.50650E-05 1.50760E-05 621620 + 877 621630 Sm-163 3.74740E-07 3.74900E-07 621630 + 878 621640 Sm-164 1.68630E-08 1.68630E-08 621640 + 879 621650 Sm-165 4.75150E-10 4.75150E-10 621650 + 880 631530 Eu-153 2.74450E-09 8.31920E-03 63153.82c + 881 631540 Eu-154 1.56330E-06 2.97140E-06 63154.82c + 882 631541 Eu-154m 1.40820E-06 1.40820E-06 631541 + 883 631550 Eu-155 2.14740E-05 4.60870E-03 63155.82c + 884 631560 Eu-156 4.50680E-05 3.13700E-03 63156.82c + 885 631570 Eu-157 1.45880E-04 2.14520E-03 63157.82c + 886 631580 Eu-158 2.53990E-04 1.36520E-03 631580 + 887 631590 Eu-159 3.57250E-04 7.97660E-04 631590 + 888 631600 Eu-160 3.39980E-04 5.32240E-04 631600 + 889 631610 Eu-161 2.66820E-04 3.18150E-04 631610 + 890 631620 Eu-162 1.21810E-04 1.36890E-04 631620 + 891 631630 Eu-163 5.36570E-05 5.40320E-05 631630 + 892 631640 Eu-164 1.31590E-05 1.31760E-05 631640 + 893 631650 Eu-165 1.33210E-06 1.33260E-06 631650 + 894 631660 Eu-166 1.68490E-08 1.68490E-08 631660 + 895 631670 Eu-167 3.83590E-10 3.83590E-10 631670 + 896 641550 Gd-155 8.71990E-11 4.60870E-03 64155.82c + 897 641551 Gd-155m 2.10510E-10 2.10510E-10 641551 + 898 641560 Gd-156 8.45540E-09 3.13700E-03 64156.82c + 899 641570 Gd-157 1.60900E-07 2.14540E-03 64157.82c + 900 641580 Gd-158 7.30650E-06 1.37260E-03 64158.82c + 901 641590 Gd-159 1.12470E-05 8.08910E-04 641590 + 902 641600 Gd-160 3.45360E-05 5.66780E-04 64160.82c + 903 641610 Gd-161 4.56980E-05 3.63850E-04 641610 + 904 641620 Gd-162 9.05150E-05 2.27400E-04 641620 + 905 641630 Gd-163 3.62520E-05 9.02840E-05 641630 + 906 641640 Gd-164 3.02730E-05 4.34490E-05 641640 + 907 641650 Gd-165 1.19870E-05 1.33200E-05 641650 + 908 641660 Gd-166 1.31660E-06 1.33340E-06 641660 + 909 641670 Gd-167 2.14030E-07 2.14410E-07 641670 + 910 641680 Gd-168 2.80290E-08 2.80290E-08 641680 + 911 641690 Gd-169 2.15360E-10 2.15360E-10 641690 + 912 651580 Tb-158 3.49110E-10 3.88180E-10 651580 + 913 651581 Tb-158m 3.93080E-11 3.93080E-11 651581 + 914 651590 Tb-159 9.67240E-09 8.08920E-04 65159.82c + 915 651600 Tb-160 4.31430E-06 4.31430E-06 65160.82c + 916 651610 Tb-161 7.13640E-06 3.70990E-04 651610 + 917 651620 Tb-162 1.50780E-05 2.42480E-04 651620 + 918 651630 Tb-163 1.47720E-05 1.05060E-04 651630 + 919 651640 Tb-164 1.58000E-05 5.92490E-05 651640 + 920 651650 Tb-165 2.66470E-05 3.99670E-05 651650 + 921 651660 Tb-166 1.71160E-05 1.84490E-05 651660 + 922 651670 Tb-167 6.17270E-06 6.38710E-06 651670 + 923 651680 Tb-168 2.33680E-06 2.36480E-06 651680 + 924 651690 Tb-169 4.24600E-08 4.26750E-08 651690 + 925 651700 Tb-170 7.33640E-09 7.33640E-09 651700 + 926 651710 Tb-171 6.72850E-10 6.72850E-10 651710 + 927 661600 Dy-160 1.97180E-11 4.31430E-06 66160.82c + 928 661610 Dy-161 8.68200E-10 3.70990E-04 66161.82c + 929 661620 Dy-162 1.80270E-08 2.42500E-04 66162.82c + 930 661630 Dy-163 1.25350E-07 1.05180E-04 66163.82c + 931 661640 Dy-164 7.45340E-07 5.99950E-05 66164.82c + 932 661650 Dy-165 1.15560E-06 4.12950E-05 661650 + 933 661651 Dy-165m 1.76650E-07 1.76650E-07 661651 + 934 661660 Dy-166 1.31670E-06 1.97660E-05 661660 + 935 661670 Dy-167 1.23460E-06 7.62170E-06 661670 + 936 661680 Dy-168 4.67390E-06 7.03870E-06 661680 + 937 661690 Dy-169 4.84930E-07 5.27600E-07 661690 + 938 661700 Dy-170 8.14050E-07 8.21390E-07 661700 + 939 661710 Dy-171 7.01940E-07 7.02610E-07 661710 + 940 661720 Dy-172 1.42310E-08 1.42310E-08 661720 + 941 661730 Dy-173 9.32550E-10 9.32550E-10 661730 + 942 671630 Ho-163 2.48170E-11 2.86110E-11 671630 + 943 671631 Ho-163m 3.79380E-12 3.79380E-12 671631 + 944 671640 Ho-164 1.85460E-10 6.19870E-10 671640 + 945 671641 Ho-164m 4.34410E-10 4.34410E-10 671641 + 946 671650 Ho-165 1.04440E-08 4.13090E-05 67165.82c + 947 671660 Ho-166 1.83740E-08 1.97850E-05 671660 + 948 671661 Ho-166m 4.30350E-08 4.30350E-08 671661 + 949 671670 Ho-167 1.86110E-07 7.80780E-06 671670 + 950 671680 Ho-168 3.09090E-07 7.78420E-06 671680 + 951 671681 Ho-168m 4.38580E-07 4.38580E-07 671681 + 952 671690 Ho-169 7.55900E-07 1.28350E-06 671690 + 953 671700 Ho-170 2.89300E-07 2.89300E-07 671700 + 954 671701 Ho-170m 1.23510E-07 9.44900E-07 671701 + 955 671710 Ho-171 4.22400E-07 1.12500E-06 671710 + 956 671720 Ho-172 1.83250E-07 1.97480E-07 671720 + 957 671730 Ho-173 4.77050E-08 4.86380E-08 671730 + 958 671740 Ho-174 6.88940E-09 6.88940E-09 671740 + 959 671750 Ho-175 7.19180E-10 7.19180E-10 671750 + 960 681650 Er-165 1.34220E-12 1.34220E-12 681650 + 961 681660 Er-166 4.50250E-11 1.97850E-05 68166.82c + 962 681670 Er-167 4.20170E-10 7.80830E-06 68167.82c + 963 681671 Er-167m 6.42310E-11 9.33040E-07 681671 + 964 681680 Er-168 8.44020E-09 7.79480E-06 68168.82c + 965 681690 Er-169 8.56700E-09 1.29210E-06 681690 + 966 681700 Er-170 5.75800E-08 1.29180E-06 68170.82c + 967 681710 Er-171 1.64780E-07 1.28980E-06 681710 + 968 681720 Er-172 2.42960E-07 4.40440E-07 681720 + 969 681730 Er-173 1.68400E-07 2.17040E-07 681730 + 970 681740 Er-174 8.66320E-08 9.35210E-08 681740 + 971 681750 Er-175 2.71370E-08 2.78560E-08 681750 + 972 681760 Er-176 5.87690E-09 5.87690E-09 681760 + 973 681770 Er-177 6.43770E-10 6.43770E-10 681770 + 974 691680 Tm-168 1.62240E-12 1.62240E-12 691680 + 975 691690 Tm-169 7.80800E-12 1.29210E-06 691690 + 976 691700 Tm-170 1.82170E-10 1.82170E-10 691700 + 977 691710 Tm-171 2.20730E-09 1.29200E-06 691710 + 978 691720 Tm-172 1.01520E-08 4.50590E-07 691720 + 979 691730 Tm-173 2.60220E-08 2.43060E-07 691730 + 980 691740 Tm-174 3.63840E-08 1.29900E-07 691740 + 981 691750 Tm-175 3.84640E-08 6.63200E-08 691750 + 982 691760 Tm-176 2.25880E-08 2.84650E-08 691760 + 983 691770 Tm-177 9.12020E-09 9.76400E-09 691770 + 984 691780 Tm-178 2.05580E-09 2.05580E-09 691780 + 985 691790 Tm-179 3.54090E-10 3.54090E-10 691790 + 986 701710 Yb-171 1.84540E-13 1.29200E-06 701710 + 987 701711 Yb-171m 1.20720E-12 1.20720E-12 701711 + 988 701720 Yb-172 2.89710E-11 4.50620E-07 701720 + 989 701730 Yb-173 2.52750E-10 2.43310E-07 701730 + 990 701740 Yb-174 1.45460E-09 1.31360E-07 701740 + 991 701750 Yb-175 4.01630E-09 7.09500E-08 701750 + 992 701751 Yb-175m 6.13980E-10 5.16800E-08 701751 + 993 701760 Yb-176 3.47140E-09 3.61330E-08 701760 + 994 701761 Yb-176m 6.24430E-09 2.04770E-08 701761 + 995 701770 Yb-177 8.49320E-09 2.02210E-08 701770 + 996 701771 Yb-177m 1.96380E-09 1.17280E-08 701771 + 997 701780 Yb-178 8.00160E-09 1.00570E-08 701780 + 998 701790 Yb-179 3.84310E-09 4.19720E-09 701790 + 999 701800 Yb-180 1.35250E-09 1.35250E-09 701800 + 1000 701810 Yb-181 2.57780E-10 2.57780E-10 701810 + 1001 711740 Lu-174 3.40760E-13 1.13430E-12 711740 + 1002 711750 Lu-175 1.60730E-11 7.09670E-08 71175.82c + 1003 711760 Lu-176 7.20210E-11 2.11970E-09 71176.82c + 1004 711761 Lu-176m 4.00390E-11 4.00390E-11 711761 + 1005 711770 Lu-177 3.42440E-10 2.05940E-08 711770 + 1006 711771 Lu-177m 1.33870E-10 1.36040E-10 711771 + 1007 711772 Lu-177m 4.32620E-12 4.32620E-12 711772 + 1008 711780 Lu-178 5.00520E-10 1.05580E-08 711780 + 1009 711781 Lu-178m 5.67380E-10 5.67380E-10 711781 + 1010 711790 Lu-179 1.54420E-09 5.97750E-09 711790 + 1011 711791 Lu-179m 2.36070E-10 4.43330E-09 711791 + 1012 711800 Lu-180 4.77190E-10 1.74370E-09 711800 + 1013 711801 Lu-180m 4.77190E-10 1.82970E-09 711801 + 1014 711802 Lu-180m 7.03280E-10 7.03280E-10 711802 + 1015 711810 Lu-181 1.09180E-09 1.34960E-09 711810 + 1016 711820 Lu-182 3.97160E-10 3.97160E-10 711820 + 1017 711830 Lu-183 1.05300E-10 1.05300E-10 711830 + 1018 711840 Lu-184 1.54970E-11 1.54970E-11 711840 + 1019 721770 Hf-177 8.40130E-13 2.07030E-08 72177.82c + 1020 721771 Hf-177m 3.26430E-13 1.07790E-10 721771 + 1021 721772 Hf-177m 1.26180E-14 2.17570E-12 721772 + 1022 721780 Hf-178 4.06860E-12 1.11370E-08 72178.82c + 1023 721781 Hf-178m 6.71260E-12 5.74690E-10 721781 + 1024 721790 Hf-179 3.68970E-11 6.03880E-09 72179.82c + 1025 721791 Hf-179m 1.15180E-11 1.15180E-11 721791 + 1026 721792 Hf-179m 1.29160E-11 1.29160E-11 721792 + 1027 721800 Hf-180 7.84920E-11 3.22830E-09 72180.82c + 1028 721801 Hf-180m 1.41190E-10 4.92830E-10 721801 + 1029 721810 Hf-181 4.05850E-10 1.75540E-09 721810 + 1030 721820 Hf-182 1.79500E-10 7.12260E-10 721820 + 1031 721821 Hf-182m 3.22870E-10 3.22870E-10 721821 + 1032 721830 Hf-183 3.54240E-10 4.59540E-10 721830 + 1033 721840 Hf-184 6.61720E-11 7.39210E-11 721840 + 1034 721841 Hf-184m 1.19030E-10 1.26780E-10 721841 + 1035 721850 Hf-185 5.91920E-11 5.91920E-11 721850 + 1036 721860 Hf-186 1.31130E-11 1.31130E-11 721860 + 1037 721870 Hf-187 1.46970E-12 1.46970E-12 721870 + 1038 731810 Ta-181 5.14160E-12 1.76060E-09 73181.82c + 1039 731820 Ta-182 7.11460E-12 2.07180E-10 73182.82c + 1040 731821 Ta-182m 7.26190E-12 2.00060E-10 731821 + 1041 731822 Ta-182m 5.53550E-12 1.92800E-10 731822 + 1042 731830 Ta-183 5.20860E-11 5.11630E-10 731830 + 1043 731840 Ta-184 7.41810E-11 2.74880E-10 731840 + 1044 731850 Ta-185 5.39090E-11 1.39210E-10 731850 + 1045 731851 Ta-185m 2.61100E-11 2.61100E-11 731851 + 1046 731860 Ta-186 4.79750E-11 6.10880E-11 731860 + 1047 731870 Ta-187 1.97560E-11 2.12260E-11 731870 + 1048 731880 Ta-188 4.53990E-12 4.53990E-12 731880 + 1049 741840 W-184 2.80870E-12 2.77690E-10 74184.82c + 1050 741850 W-185 2.68070E-12 1.48360E-10 741850 + 1051 741851 W-185m 6.47160E-12 6.47160E-12 741851 + 1052 741860 W-186 1.48660E-11 8.07490E-11 74186.82c + 1053 741861 W-186m 4.79530E-12 4.79530E-12 741861 + 1054 741870 W-187 2.16100E-11 4.28360E-11 741870 + 1055 741880 W-188 1.68410E-11 2.13810E-11 741880 + 1056 741890 W-189 8.22220E-12 8.22220E-12 741890 + 1057 741900 W-190 1.38100E-12 2.94640E-12 741900 + 1058 741901 W-190m 1.56540E-12 1.56540E-12 741901 + 1059 751880 Re-188 6.39900E-13 2.35200E-11 751880 + 1060 751881 Re-188m 1.49880E-12 1.49880E-12 751881 + 1061 751890 Re-189 3.63260E-12 1.18550E-11 751890 + 1062 751900 Re-190 1.23060E-12 5.18640E-12 751900 + 1063 751901 Re-190m 2.21360E-12 2.21360E-12 751901 + 1064 751910 Re-191 2.31740E-12 2.31740E-12 751910 + + Neutron-induced fission: + + Interpolation region : 2 / 2 + Interpolation energy : 4.00000E-01 MeV + Number of products : 1061 / 1137 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 3.32190E-05 3.32190E-05 1001.82c + 2 10020 H-2 1.01520E-05 1.01520E-05 1002.82c + 3 10030 H-3 1.60000E-04 1.60000E-04 1003.82c + 4 20040 He-4 2.10000E-03 2.10000E-03 2004.82c + 5 190500 K-50 2.76810E-12 2.76810E-12 190500 + 6 190510 K-51 1.02270E-12 1.02270E-12 190510 + 7 200500 Ca-50 2.92420E-11 3.16880E-11 200500 + 8 200510 Ca-51 2.79210E-11 2.84630E-11 200510 + 9 200520 Ca-52 2.30600E-11 2.30600E-11 200520 + 10 200530 Ca-53 7.22090E-12 7.22090E-12 200530 + 11 200540 Ca-54 1.81720E-12 1.81720E-12 200540 + 12 210500 Sc-50 6.77520E-12 4.05220E-11 210500 + 13 210501 Sc-50m 2.48560E-12 3.41740E-11 210501 + 14 210510 Sc-51 3.99240E-11 6.88480E-11 210510 + 15 210520 Sc-52 7.59090E-11 1.00670E-10 210520 + 16 210530 Sc-53 1.17280E-10 1.22330E-10 210530 + 17 210540 Sc-54 7.98070E-11 8.16240E-11 210540 + 18 210550 Sc-55 5.12330E-11 5.12330E-11 210550 + 19 210560 Sc-56 1.26510E-11 1.26510E-11 210560 + 20 210570 Sc-57 2.43240E-12 2.43240E-12 210570 + 21 220510 Ti-51 2.50790E-12 7.13560E-11 220510 + 22 220520 Ti-52 2.34960E-11 1.24170E-10 220520 + 23 220530 Ti-53 8.35060E-11 2.05840E-10 220530 + 24 220540 Ti-54 2.56640E-10 3.38260E-10 220540 + 25 220550 Ti-55 3.91500E-10 4.42730E-10 220550 + 26 220560 Ti-56 4.99240E-10 5.12690E-10 220560 + 27 220570 Ti-57 2.70590E-10 2.72220E-10 220570 + 28 220580 Ti-58 1.26370E-10 1.26370E-10 220580 + 29 220590 Ti-59 2.34870E-11 2.34870E-11 220590 + 30 220600 Ti-60 3.21320E-12 3.21320E-12 220600 + 31 230530 V-53 3.12270E-12 2.08960E-10 230530 + 32 230540 V-54 2.47680E-11 3.63030E-10 230540 + 33 230550 V-55 1.78700E-10 6.21430E-10 230550 + 34 230560 V-56 5.15570E-10 1.02910E-09 230560 + 35 230570 V-57 1.28460E-09 1.55600E-09 230570 + 36 230580 V-58 1.48580E-09 1.61220E-09 230580 + 37 230590 V-59 1.49200E-09 1.51550E-09 230590 + 38 230600 V-60 5.96640E-10 5.99850E-10 230600 + 39 230610 V-61 2.15820E-10 2.15820E-10 230610 + 40 230620 V-62 3.11190E-11 3.11190E-11 230620 + 41 230630 V-63 2.29660E-12 2.29660E-12 230630 + 42 240550 Cr-55 3.01360E-12 6.24450E-10 240550 + 43 240560 Cr-56 4.67730E-11 1.08210E-09 240560 + 44 240570 Cr-57 2.87380E-10 3.12690E-09 240570 + 45 240580 Cr-58 1.52440E-09 1.84680E-09 240580 + 46 240590 Cr-59 3.46620E-09 4.98170E-09 240590 + 47 240600 Cr-60 6.57990E-09 7.19270E-09 240600 + 48 240610 Cr-61 6.17050E-09 6.37340E-09 240610 + 49 240620 Cr-62 5.01040E-09 5.04230E-09 240620 + 50 240630 Cr-63 1.11420E-09 1.11570E-09 240630 + 51 240640 Cr-64 3.79630E-10 3.79630E-10 240640 + 52 240650 Cr-65 4.10430E-11 4.10430E-11 240650 + 53 240660 Cr-66 3.22770E-12 3.22770E-12 240660 + 54 250570 Mn-57 2.77260E-12 3.12970E-09 250570 + 55 250580 Mn-58 3.76010E-11 1.88440E-09 250580 + 56 250581 Mn-58m 3.69610E-12 3.69610E-12 250581 + 57 250590 Mn-59 4.82730E-10 5.46440E-09 250590 + 58 250600 Mn-60 1.94190E-10 7.61410E-09 250600 + 59 250601 Mn-60m 1.97550E-09 1.97550E-09 250601 + 60 250610 Mn-61 9.18180E-09 1.55550E-08 250610 + 61 250620 Mn-62 1.48650E-08 1.73860E-08 250620 + 62 250621 Mn-62m 2.32790E-09 4.84910E-09 250621 + 63 250630 Mn-63 1.89220E-08 2.00380E-08 250630 + 64 250640 Mn-64 1.74840E-08 1.78640E-08 250640 + 65 250650 Mn-65 1.10370E-08 1.10780E-08 250650 + 66 250660 Mn-66 2.68220E-09 2.68540E-09 250660 + 67 250670 Mn-67 5.05110E-10 5.05110E-10 250670 + 68 250680 Mn-68 2.92930E-11 2.92930E-11 250680 + 69 250690 Mn-69 2.25490E-12 2.25490E-12 250690 + 70 260590 Fe-59 2.02790E-12 5.46640E-09 260590 + 71 260600 Fe-60 5.29210E-11 9.41530E-09 260600 + 72 260610 Fe-61 6.02960E-10 1.61580E-08 260610 + 73 260620 Fe-62 5.54670E-09 2.77820E-08 260620 + 74 260630 Fe-63 3.44860E-08 5.45240E-08 260630 + 75 260640 Fe-64 5.85460E-08 7.64100E-08 260640 + 76 260650 Fe-65 8.80470E-08 9.91250E-08 260650 + 77 260660 Fe-66 1.10840E-07 1.13530E-07 260660 + 78 260670 Fe-67 5.90000E-08 5.95050E-08 260670 + 79 260680 Fe-68 2.05910E-08 2.06210E-08 260680 + 80 260690 Fe-69 4.95870E-09 4.96040E-09 260690 + 81 260700 Fe-70 2.47670E-10 2.47670E-10 260700 + 82 260710 Fe-71 5.04200E-11 5.04200E-11 260710 + 83 260720 Fe-72 1.21290E-12 1.21290E-12 260720 + 84 270610 Co-61 1.40680E-12 1.61590E-08 270610 + 85 270620 Co-62 1.04180E-11 2.77930E-08 270620 + 86 270621 Co-62m 2.83990E-11 2.83990E-11 270621 + 87 270630 Co-63 5.48930E-10 5.50730E-08 270630 + 88 270640 Co-64 5.89750E-09 8.23070E-08 270640 + 89 270650 Co-65 4.18440E-08 1.40970E-07 270650 + 90 270660 Co-66 1.19120E-07 2.32650E-07 270660 + 91 270670 Co-67 2.91980E-07 3.51490E-07 270670 + 92 270680 Co-68 1.44960E-07 2.09540E-07 270680 + 93 270681 Co-68m 1.08200E-07 1.29170E-07 270681 + 94 270690 Co-69 3.30360E-07 3.34970E-07 270690 + 95 270700 Co-70 2.41700E-08 2.41700E-08 270700 + 96 270701 Co-70m 2.41700E-08 2.44180E-08 270701 + 97 270710 Co-71 6.07660E-08 6.08160E-08 270710 + 98 270720 Co-72 4.94010E-09 4.94130E-09 270720 + 99 270730 Co-73 5.18920E-10 5.18920E-10 270730 + 100 270740 Co-74 2.53270E-11 2.53270E-11 270740 + 101 270750 Co-75 1.21520E-12 1.21520E-12 270750 + 102 280640 Ni-64 3.58760E-11 8.23430E-08 28064.82c + 103 280650 Ni-65 7.39890E-10 1.41710E-07 280650 + 104 280660 Ni-66 1.12970E-08 2.43940E-07 280660 + 105 280670 Ni-67 6.80850E-08 4.19570E-07 280670 + 106 280680 Ni-68 5.52920E-07 8.30400E-07 280680 + 107 280690 Ni-69 3.99590E-07 7.31210E-07 280690 + 108 280691 Ni-69m 3.99590E-07 3.99590E-07 280691 + 109 280700 Ni-70 7.63600E-07 8.12190E-07 280700 + 110 280710 Ni-71 9.73330E-07 1.03420E-06 280710 + 111 280720 Ni-72 2.02100E-06 2.02590E-06 280720 + 112 280730 Ni-73 2.64910E-07 2.65430E-07 280730 + 113 280740 Ni-74 8.11260E-08 8.11510E-08 280740 + 114 280750 Ni-75 1.02400E-08 1.02410E-08 280750 + 115 280760 Ni-76 6.81640E-10 6.81640E-10 280760 + 116 280770 Ni-77 2.09450E-11 2.09450E-11 280770 + 117 290660 Cu-66 1.91360E-11 2.43960E-07 290660 + 118 290670 Cu-67 6.89510E-10 4.20260E-07 290670 + 119 290680 Cu-68 2.05740E-09 8.37170E-07 290680 + 120 290681 Cu-68m 5.60810E-09 5.60810E-09 290681 + 121 290690 Cu-69 1.16160E-07 1.24700E-06 290690 + 122 290700 Cu-70 1.29360E-08 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41095.82c + 359 410951 Nb-95m 5.14770E-07 3.71270E-04 410951 + 360 410960 Nb-96 4.74710E-05 4.74710E-05 410960 + 361 410970 Nb-97 3.19090E-04 4.34000E-02 410970 + 362 410971 Nb-97m 6.42480E-05 4.09510E-02 410971 + 363 410980 Nb-98 3.63670E-04 4.84260E-02 410980 + 364 410981 Nb-98m 1.26710E-03 1.26710E-03 410981 + 365 410990 Nb-99 5.97210E-03 3.43950E-02 410990 + 366 410991 Nb-99m 1.20250E-03 1.75480E-02 410991 + 367 411000 Nb-100 2.56210E-03 4.15420E-02 411000 + 368 411001 Nb-100m 1.24210E-02 1.24210E-02 411001 + 369 411010 Nb-101 2.99160E-02 5.07270E-02 411010 + 370 411020 Nb-102 1.44920E-02 2.60370E-02 411020 + 371 411021 Nb-102m 1.44920E-02 1.44920E-02 411021 + 372 411030 Nb-103 2.78800E-02 3.16560E-02 411030 + 373 411040 Nb-104 7.68250E-03 8.81520E-03 411040 + 374 411041 Nb-104m 7.68250E-03 7.68250E-03 411041 + 375 411050 Nb-105 8.40550E-03 8.57670E-03 411050 + 376 411060 Nb-106 2.36270E-03 2.39110E-03 411060 + 377 411070 Nb-107 6.70190E-04 6.70200E-04 411070 + 378 411080 Nb-108 9.09830E-05 9.09830E-05 411080 + 379 411090 Nb-109 1.17270E-05 1.17270E-05 411090 + 380 420970 Mo-97 5.05810E-06 4.34050E-02 42097.82c + 381 420980 Mo-98 4.88790E-05 4.97420E-02 42098.82c + 382 420990 Mo-99 3.80030E-04 5.19720E-02 42099.82c + 383 421000 Mo-100 2.18410E-03 5.61470E-02 42100.82c + 384 421010 Mo-101 6.43900E-03 5.71660E-02 421010 + 385 421020 Mo-102 1.97590E-02 6.02880E-02 421020 + 386 421030 Mo-103 2.99260E-02 6.15910E-02 421030 + 387 421040 Mo-104 4.34400E-02 6.00740E-02 421040 + 388 421050 Mo-105 3.22300E-02 4.07680E-02 421050 + 389 421060 Mo-106 2.50480E-02 2.73720E-02 421060 + 390 421070 Mo-107 1.07460E-02 1.13820E-02 421070 + 391 421080 Mo-108 4.59210E-03 4.67890E-03 421080 + 392 421090 Mo-109 9.46840E-04 9.57080E-04 421090 + 393 421100 Mo-110 1.95350E-04 1.95350E-04 421100 + 394 421110 Mo-111 9.72560E-06 9.72560E-06 421110 + 395 421120 Mo-112 1.55170E-09 1.55170E-09 421120 + 396 430990 Tc-99 3.99760E-09 5.19710E-02 43099.82c + 397 430991 Tc-99m 8.04900E-10 4.57670E-02 430991 + 398 431000 Tc-100 7.20280E-06 7.20280E-06 431000 + 399 431010 Tc-101 9.16680E-05 5.72580E-02 431010 + 400 431020 Tc-102 2.74710E-04 6.05620E-02 431020 + 401 431021 Tc-102m 2.74710E-04 2.74710E-04 431021 + 402 431030 Tc-103 3.05010E-03 6.46410E-02 431030 + 403 431040 Tc-104 7.56290E-03 6.76370E-02 431040 + 404 431050 Tc-105 1.97400E-02 6.05080E-02 431050 + 405 431060 Tc-106 2.55130E-02 5.28850E-02 431060 + 406 431070 Tc-107 3.18380E-02 4.32200E-02 431070 + 407 431080 Tc-108 2.12640E-02 2.59480E-02 431080 + 408 431090 Tc-109 1.36830E-02 1.46350E-02 431090 + 409 431100 Tc-110 5.43650E-03 5.63200E-03 431100 + 410 431110 Tc-111 1.65390E-03 1.66350E-03 431110 + 411 431120 Tc-112 2.80110E-04 2.80110E-04 431120 + 412 431130 Tc-113 3.83430E-05 3.83430E-05 431130 + 413 431140 Tc-114 8.78940E-06 8.78940E-06 431140 + 414 431150 Tc-115 9.68510E-07 9.68510E-07 431150 + 415 441020 Ru-102 9.98680E-06 6.08470E-02 44102.82c + 416 441030 Ru-103 1.52750E-05 6.46990E-02 44103.82c + 417 441031 Ru-103m 4.27380E-05 4.27380E-05 441031 + 418 441040 Ru-104 4.44160E-04 6.80820E-02 44104.82c + 419 441050 Ru-105 1.70110E-03 6.22100E-02 44105.82c + 420 441060 Ru-106 5.84060E-03 5.87250E-02 44106.82c + 421 441070 Ru-107 1.07890E-02 5.40090E-02 441070 + 422 441080 Ru-108 1.96430E-02 4.56030E-02 441080 + 423 441090 Ru-109 1.82440E-02 3.28700E-02 441090 + 424 441100 Ru-110 1.62280E-02 2.18580E-02 441100 + 425 441110 Ru-111 7.82140E-03 9.48910E-03 441110 + 426 441120 Ru-112 3.61670E-03 3.89540E-03 441120 + 427 441130 Ru-113 4.41550E-04 6.98480E-04 441130 + 428 441131 Ru-113m 4.41550E-04 4.41550E-04 441131 + 429 441140 Ru-114 2.76360E-04 2.84710E-04 441140 + 430 441150 Ru-115 7.74590E-05 7.82890E-05 441150 + 431 441160 Ru-116 2.70840E-05 2.70840E-05 441160 + 432 441170 Ru-117 7.89090E-06 7.89090E-06 441170 + 433 441180 Ru-118 6.38610E-07 6.38610E-07 441180 + 434 451030 Rh-103 1.17440E-07 6.47000E-02 45103.82c + 435 451031 Rh-103m 8.82060E-07 6.39250E-02 451031 + 436 451040 Rh-104 1.16840E-09 5.23420E-09 451040 + 437 451041 Rh-104m 4.07110E-09 4.07110E-09 451041 + 438 451050 Rh-105 7.92680E-06 6.22190E-02 45105.82c + 439 451051 Rh-105m 1.05540E-06 1.76610E-02 451051 + 440 451060 Rh-106 2.00800E-05 5.87450E-02 451060 + 441 451061 Rh-106m 5.47330E-05 5.47330E-05 451061 + 442 451070 Rh-107 4.63260E-04 5.44720E-02 451070 + 443 451080 Rh-108 3.46210E-04 4.59490E-02 451080 + 444 451081 Rh-108m 1.20630E-03 1.20630E-03 451081 + 445 451090 Rh-109 4.12160E-03 3.69910E-02 451090 + 446 451100 Rh-110 5.76980E-03 2.76270E-02 451100 + 447 451101 Rh-110m 1.35830E-04 1.35830E-04 451101 + 448 451110 Rh-111 7.84000E-03 1.73290E-02 451110 + 449 451120 Rh-112 2.79900E-03 6.69440E-03 451120 + 450 451121 Rh-112m 2.79900E-03 2.79900E-03 451121 + 451 451130 Rh-113 3.76050E-03 4.67970E-03 451130 + 452 451140 Rh-114 7.42800E-04 1.02770E-03 451140 + 453 451141 Rh-114m 7.42800E-04 7.42800E-04 451141 + 454 451150 Rh-115 6.20090E-04 6.98490E-04 451150 + 455 451160 Rh-116 3.88750E-05 6.58280E-05 451160 + 456 451161 Rh-116m 1.05970E-04 1.05970E-04 451161 + 457 451170 Rh-117 3.00220E-05 3.77770E-05 451170 + 458 451180 Rh-118 7.11970E-06 7.73210E-06 451180 + 459 451190 Rh-119 4.74880E-06 4.74880E-06 451190 + 460 451220 Rh-122 3.42800E-09 3.42800E-09 451220 + 461 461060 Pd-106 9.96350E-07 5.88010E-02 46106.82c + 462 461070 Pd-107 1.53440E-06 5.44770E-02 46107.82c + 463 461071 Pd-107m 3.37260E-06 3.37260E-06 461071 + 464 461080 Pd-108 4.21750E-05 4.71970E-02 46108.82c + 465 461090 Pd-109 4.08140E-05 3.71220E-02 461090 + 466 461091 Pd-109m 8.97060E-05 1.85850E-02 461091 + 467 461100 Pd-110 5.66920E-04 2.83300E-02 46110.82c + 468 461110 Pd-111 3.03580E-04 1.81010E-02 461110 + 469 461111 Pd-111m 6.67250E-04 7.36570E-04 461111 + 470 461120 Pd-112 1.67000E-03 1.11630E-02 461120 + 471 461130 Pd-113 4.11850E-04 6.24390E-03 461130 + 472 461131 Pd-113m 1.15230E-03 1.15230E-03 461131 + 473 461140 Pd-114 1.35700E-03 3.12750E-03 461140 + 474 461150 Pd-115 1.87960E-04 8.26200E-04 461150 + 475 461151 Pd-115m 4.13130E-04 5.14550E-04 461151 + 476 461160 Pd-116 3.03260E-04 4.75050E-04 461160 + 477 461170 Pd-117 3.37250E-05 1.45850E-04 461170 + 478 461171 Pd-117m 7.41250E-05 7.41250E-05 461171 + 479 461180 Pd-118 4.21890E-05 4.96950E-05 461180 + 480 461190 Pd-119 4.74980E-06 9.49860E-06 461190 + 481 461200 Pd-120 8.94240E-06 8.94240E-06 461200 + 482 461210 Pd-121 4.84200E-06 4.84200E-06 461210 + 483 461220 Pd-122 4.65060E-06 4.65400E-06 461220 + 484 461230 Pd-123 4.62190E-07 4.62190E-07 461230 + 485 461240 Pd-124 5.34590E-08 5.34590E-08 461240 + 486 471090 Ag-109 4.05910E-10 3.71220E-02 47109.82c + 487 471091 Ag-109m 3.04870E-09 3.71040E-02 471091 + 488 471100 Ag-110 1.05160E-06 1.09060E-06 471100 + 489 471101 Ag-110m 2.86650E-06 2.86650E-06 47510.82c + 490 471110 Ag-111 3.32440E-06 1.82380E-02 47111.82c + 491 471111 Ag-111m 2.49690E-05 1.81400E-02 471111 + 492 471120 Ag-112 6.41010E-05 1.12280E-02 471120 + 493 471130 Ag-113 1.68710E-05 4.18940E-03 471130 + 494 471131 Ag-113m 1.26710E-04 6.10580E-03 471131 + 495 471140 Ag-114 2.95380E-05 3.30020E-03 471140 + 496 471141 Ag-114m 1.43200E-04 1.43200E-04 471141 + 497 471150 Ag-115 2.71620E-05 8.19380E-04 471150 + 498 471151 Ag-115m 2.04010E-04 9.00470E-04 471151 + 499 471160 Ag-116 3.92130E-05 5.20680E-04 471160 + 500 471161 Ag-116m 1.06890E-04 1.06890E-04 471161 + 501 471170 Ag-117 2.07420E-05 1.07390E-04 471170 + 502 471171 Ag-117m 1.55790E-04 2.28710E-04 471171 + 503 471180 Ag-118 1.69430E-05 9.61240E-05 471180 + 504 471181 Ag-118m 8.21390E-05 8.92430E-05 471181 + 505 471190 Ag-119 1.33570E-05 1.81070E-05 471190 + 506 471191 Ag-119m 1.00320E-04 1.05070E-04 471191 + 507 471200 Ag-120 4.55360E-05 7.98520E-05 471200 + 508 471201 Ag-120m 7.61540E-05 8.06250E-05 471201 + 509 471210 Ag-121 5.52320E-05 6.00610E-05 471210 + 510 471220 Ag-122 1.22030E-05 1.68570E-05 471220 + 511 471221 Ag-122m 1.31570E-05 1.31570E-05 471221 + 512 471230 Ag-123 1.68670E-05 1.73290E-05 471230 + 513 471240 Ag-124 8.06060E-06 1.24590E-05 471240 + 514 471241 Ag-124m 8.69040E-06 8.69040E-06 471241 + 515 471250 Ag-125 9.55560E-06 9.55560E-06 471250 + 516 471260 Ag-126 3.06730E-06 3.06730E-06 471260 + 517 471270 Ag-127 7.83390E-08 7.83390E-08 471270 + 518 471280 Ag-128 2.67170E-09 2.67170E-09 471280 + 519 481120 Cd-112 9.31040E-09 1.12280E-02 48112.82c + 520 481130 Cd-113 6.09360E-07 6.31580E-03 48113.82c + 521 481131 Cd-113m 2.30760E-06 7.47390E-05 481131 + 522 481140 Cd-114 6.64960E-06 3.30690E-03 48114.82c + 523 481150 Cd-115 2.12910E-06 1.46500E-03 481150 + 524 481151 Cd-115m 8.06290E-06 7.59890E-05 48515.82c + 525 481160 Cd-116 1.86850E-05 6.39840E-04 48116.82c + 526 481170 Cd-117 4.67330E-06 2.55620E-04 481170 + 527 481171 Cd-117m 1.76980E-05 8.91320E-05 481171 + 528 481180 Cd-118 2.87170E-05 1.77500E-04 481180 + 529 481190 Cd-119 9.08310E-06 1.23210E-04 481190 + 530 481191 Cd-119m 2.54140E-05 3.44680E-05 481191 + 531 481200 Cd-120 1.96060E-04 3.26700E-04 481200 + 532 481210 Cd-121 3.03270E-05 8.41120E-05 481210 + 533 481211 Cd-121m 8.48530E-05 9.11290E-05 481211 + 534 481220 Cd-122 1.35720E-04 1.65730E-04 481220 + 535 481230 Cd-123 3.10220E-05 4.52060E-05 481230 + 536 481231 Cd-123m 8.67980E-05 8.99550E-05 481231 + 537 481240 Cd-124 2.20870E-04 2.37660E-04 481240 + 538 481250 Cd-125 5.51560E-05 5.99340E-05 481250 + 539 481251 Cd-125m 1.54320E-04 1.59100E-04 481251 + 540 481260 Cd-126 1.67410E-04 1.70480E-04 481260 + 541 481270 Cd-127 8.80790E-05 8.81570E-05 481270 + 542 481280 Cd-128 4.19520E-05 4.19550E-05 481280 + 543 481290 Cd-129 2.93500E-06 2.93500E-06 481290 + 544 481291 Cd-129m 8.21200E-06 8.21200E-06 481291 + 545 481300 Cd-130 6.77530E-08 6.77530E-08 481300 + 546 481310 Cd-131 1.02140E-09 1.02140E-09 481310 + 547 491140 In-114 5.69360E-11 2.48380E-10 491140 + 548 491141 In-114m 9.19410E-11 1.98380E-10 491141 + 549 491142 In-114m 1.06440E-10 1.06440E-10 491142 + 550 491150 In-115 6.75560E-09 1.46770E-03 49115.82c + 551 491151 In-115m 1.36020E-09 1.46500E-03 491151 + 552 491160 In-116 2.06850E-07 2.06850E-07 491160 + 553 491161 In-116m 3.34030E-07 7.20740E-07 491161 + 554 491162 In-116m 3.86710E-07 3.86710E-07 491162 + 555 491170 In-117 7.06100E-07 2.20890E-04 491170 + 556 491171 In-117m 1.42170E-07 2.35760E-04 491171 + 557 491180 In-118 7.14670E-07 1.78210E-04 491180 + 558 491181 In-118m 1.15400E-06 2.47140E-06 491181 + 559 491182 In-118m 1.33610E-06 1.33610E-06 491182 + 560 491190 In-119 5.88220E-06 5.85530E-05 491190 + 561 491191 In-119m 1.18430E-06 1.12490E-04 491191 + 562 491200 In-120 8.24780E-06 3.34950E-04 491200 + 563 491201 In-120m 8.24780E-06 8.24780E-06 491201 + 564 491202 In-120m 8.24780E-06 8.24780E-06 491202 + 565 491210 In-121 4.93700E-05 1.69620E-04 491210 + 566 491211 In-121m 9.94040E-06 6.57240E-05 491211 + 567 491220 In-122 3.44410E-05 2.00180E-04 491220 + 568 491221 In-122m 2.87990E-05 2.87990E-05 491221 + 569 491222 In-122m 2.87990E-05 2.87990E-05 491222 + 570 491230 In-123 1.33920E-04 2.36780E-04 491230 + 571 491231 In-123m 2.69650E-05 5.92670E-05 491231 + 572 491240 In-124 1.11940E-04 3.49600E-04 491240 + 573 491241 In-124m 1.20680E-04 1.20680E-04 491241 + 574 491250 In-125 5.70140E-04 7.57930E-04 491250 + 575 491251 In-125m 1.14800E-04 1.46040E-04 491251 + 576 491260 In-126 5.16620E-04 6.87090E-04 491260 + 577 491261 In-126m 5.56980E-04 5.56980E-04 491261 + 578 491270 In-127 1.57220E-03 1.57220E-03 491270 + 579 491271 In-127m 3.16550E-04 4.04700E-04 491271 + 580 491280 In-128 5.40900E-04 7.94650E-04 491280 + 581 491281 In-128m 2.11790E-04 2.53750E-04 491281 + 582 491282 In-128m 8.11510E-04 8.11510E-04 491282 + 583 491290 In-129 9.21050E-04 9.29260E-04 491290 + 584 491291 In-129m 1.85450E-04 1.88390E-04 491291 + 585 491300 In-130 8.59930E-05 8.60590E-05 491300 + 586 491301 In-130m 1.25210E-04 1.25210E-04 491301 + 587 491302 In-130m 1.74420E-04 1.74420E-04 491302 + 588 491310 In-131 3.14340E-05 3.17550E-05 491310 + 589 491311 In-131m 3.14340E-05 3.14340E-05 491311 + 590 491312 In-131m 3.14340E-05 3.14340E-05 491312 + 591 491320 In-132 6.09900E-06 6.09900E-06 491320 + 592 491330 In-133 1.78310E-08 2.14210E-08 491330 + 593 491331 In-133m 3.59020E-09 3.59020E-09 491331 + 594 501170 Sn-117 5.19620E-11 3.45600E-04 50117.82c + 595 501171 Sn-117m 1.96780E-10 7.52780E-07 501171 + 596 501180 Sn-118 6.07490E-09 1.80700E-04 50118.82c + 597 501190 Sn-119 2.10400E-08 1.64840E-04 50119.82c + 598 501191 Sn-119m 7.96800E-08 5.29760E-05 501191 + 599 501200 Sn-120 3.43270E-06 3.54880E-04 50120.82c + 600 501210 Sn-121 3.32180E-06 2.40780E-04 501210 + 601 501211 Sn-121m 9.29420E-06 2.85090E-05 501211 + 602 501220 Sn-122 2.14790E-05 2.79310E-04 50122.82c + 603 501230 Sn-123 2.97870E-05 4.78400E-05 50123.82c + 604 501231 Sn-123m 1.06460E-05 2.88650E-04 501231 + 605 501240 Sn-124 1.14890E-04 5.85170E-04 50124.82c + 606 501250 Sn-125 2.20910E-04 3.48940E-04 50125.82c + 607 501251 Sn-125m 7.89560E-05 8.54900E-04 501251 + 608 501260 Sn-126 1.17070E-03 2.41760E-03 50126.82c + 609 501270 Sn-127 1.94280E-03 2.55560E-03 501270 + 610 501271 Sn-127m 6.94380E-04 2.05570E-03 501271 + 611 501280 Sn-128 1.71590E-03 7.99920E-03 501280 + 612 501281 Sn-128m 4.67710E-03 5.48860E-03 501281 + 613 501290 Sn-129 1.93930E-03 2.95810E-03 501290 + 614 501291 Sn-129m 5.42610E-03 5.52500E-03 501291 + 615 501300 Sn-130 2.08240E-03 2.31820E-03 501300 + 616 501301 Sn-130m 5.67610E-03 5.82650E-03 501301 + 617 501310 Sn-131 1.04640E-03 1.10730E-03 501310 + 618 501311 Sn-131m 2.92780E-03 2.96060E-03 501311 + 619 501320 Sn-132 1.67900E-03 1.68510E-03 501320 + 620 501330 Sn-133 1.36830E-04 1.36830E-04 501330 + 621 501340 Sn-134 1.03080E-05 1.03080E-05 501340 + 622 501350 Sn-135 9.89350E-07 9.89350E-07 501350 + 623 501360 Sn-136 5.20000E-09 5.20000E-09 501360 + 624 511190 Sb-119 1.00520E-11 1.40880E-11 511190 + 625 511191 Sb-119m 4.03620E-12 4.03620E-12 511191 + 626 511200 Sb-120 6.52190E-10 6.52190E-10 511200 + 627 511201 Sb-120m 1.09070E-09 1.09070E-09 511201 + 628 511210 Sb-121 4.00660E-08 2.47210E-04 51121.82c + 629 511220 Sb-122 9.70880E-07 2.27160E-06 511220 + 630 511221 Sb-122m 1.30070E-06 1.30070E-06 511221 + 631 511230 Sb-123 1.05310E-10 3.36480E-04 51123.82c + 632 511240 Sb-124 3.07880E-06 7.92380E-06 51124.82c + 633 511241 Sb-124m 2.48360E-06 6.45990E-06 511241 + 634 511242 Sb-124m 3.97630E-06 3.97630E-06 511242 + 635 511250 Sb-125 4.21330E-05 1.24600E-03 51125.82c + 636 511260 Sb-126 3.92630E-05 4.69520E-05 51126.82c + 637 511261 Sb-126m 2.45240E-05 5.49250E-05 511261 + 638 511262 Sb-126m 3.04010E-05 3.04010E-05 511262 + 639 511270 Sb-127 4.83940E-04 5.09520E-03 511270 + 640 511280 Sb-128 5.79280E-04 8.60760E-03 511280 + 641 511281 Sb-128m 8.10220E-04 8.10220E-04 511281 + 642 511290 Sb-129 3.89420E-03 1.04620E-02 511290 + 643 511291 Sb-129m 2.88190E-03 5.64430E-03 511291 + 644 511300 Sb-130 6.44500E-03 1.16760E-02 511300 + 645 511301 Sb-130m 6.44500E-03 9.35820E-03 511301 + 646 511310 Sb-131 2.34020E-02 2.74700E-02 511310 + 647 511320 Sb-132 1.08570E-02 1.25420E-02 511320 + 648 511321 Sb-132m 9.61270E-03 9.61270E-03 511321 + 649 511330 Sb-133 1.50760E-02 1.52150E-02 511330 + 650 511340 Sb-134 1.05760E-03 1.06620E-03 511340 + 651 511341 Sb-134m 2.88270E-03 2.88280E-03 511341 + 652 511350 Sb-135 9.36930E-04 9.37710E-04 511350 + 653 511360 Sb-136 1.29020E-04 1.29020E-04 511360 + 654 511370 Sb-137 2.74430E-05 2.74430E-05 511370 + 655 511380 Sb-138 2.03500E-08 2.03500E-08 511380 + 656 521250 Te-125 7.59370E-12 1.24600E-03 52125.82c + 657 521251 Te-125m 2.87570E-11 2.78810E-04 521251 + 658 521260 Te-126 2.02190E-06 9.62090E-05 52126.82c + 659 521270 Te-127 1.85930E-06 5.08200E-03 521270 + 660 521271 Te-127m 5.20220E-06 8.44870E-04 52527.82c + 661 521280 Te-128 6.42430E-05 9.45290E-03 52128.82c + 662 521290 Te-129 1.03000E-04 1.31680E-02 521290 + 663 521291 Te-129m 2.88200E-04 6.70960E-03 52529.82c + 664 521300 Te-130 2.57440E-03 2.36090E-02 52130.82c + 665 521310 Te-131 2.03220E-03 2.89590E-02 521310 + 666 521311 Te-131m 5.68600E-03 7.88530E-03 521311 + 667 521320 Te-132 2.34420E-02 4.55970E-02 52132.82c + 668 521330 Te-133 9.12280E-03 2.66360E-02 521330 + 669 521331 Te-133m 2.55250E-02 2.81570E-02 521331 + 670 521340 Te-134 3.98940E-02 4.39880E-02 521340 + 671 521350 Te-135 1.42800E-02 1.50920E-02 521350 + 672 521360 Te-136 6.23920E-03 6.36030E-03 521360 + 673 521370 Te-137 1.21520E-03 1.22920E-03 521370 + 674 521380 Te-138 2.27360E-04 2.27380E-04 521380 + 675 521390 Te-139 1.36440E-05 1.36440E-05 521390 + 676 521400 Te-140 1.96980E-06 1.96980E-06 521400 + 677 521410 Te-141 2.97260E-09 2.97260E-09 521410 + 678 531280 I-128 2.18590E-09 2.18590E-09 531280 + 679 531290 I-129 8.11700E-06 1.56580E-02 53129.82c + 680 531300 I-130 1.70670E-05 2.23260E-05 53130.82c + 681 531301 I-130m 6.26120E-06 6.26120E-06 531301 + 682 531310 I-131 2.97800E-04 3.54860E-02 53131.82c + 683 531320 I-132 7.49300E-04 4.69170E-02 531320 + 684 531321 I-132m 6.63400E-04 6.63400E-04 531321 + 685 531330 I-133 4.59830E-03 5.78660E-02 531330 + 686 531331 I-133m 3.40290E-03 3.40290E-03 531331 + 687 531340 I-134 1.27300E-02 6.77290E-02 531340 + 688 531341 I-134m 1.12700E-02 1.12700E-02 531341 + 689 531350 I-135 5.61870E-02 7.12780E-02 53135.82c + 690 531360 I-136 1.11530E-02 1.75310E-02 531360 + 691 531361 I-136m 3.04000E-02 3.04190E-02 531361 + 692 531370 I-137 2.92640E-02 3.04710E-02 531370 + 693 531380 I-138 9.31880E-03 9.53190E-03 531380 + 694 531390 I-139 4.70630E-03 4.71990E-03 531390 + 695 531400 I-140 9.52650E-04 9.54620E-04 531400 + 696 531410 I-141 2.10870E-04 2.10870E-04 531410 + 697 531420 I-142 1.48890E-05 1.48890E-05 531420 + 698 531430 I-143 1.72390E-08 1.72390E-08 531430 + 699 541300 Xe-130 8.06590E-10 2.33290E-05 54130.82c + 700 541310 Xe-131 1.74810E-08 3.54860E-02 54131.82c + 701 541311 Xe-131m 4.89110E-08 3.85490E-04 541311 + 702 541320 Xe-132 6.95380E-06 4.70260E-02 54132.82c + 703 541321 Xe-132m 9.31620E-06 9.31620E-06 541321 + 704 541330 Xe-133 2.94420E-05 5.79780E-02 54133.82c + 705 541331 Xe-133m 8.23780E-05 1.72950E-03 541331 + 706 541340 Xe-134 3.05060E-04 6.91250E-02 54134.82c + 707 541341 Xe-134m 8.31540E-04 1.09080E-03 541341 + 708 541350 Xe-135 1.47690E-03 7.67920E-02 54135.82c + 709 541351 Xe-135m 4.13220E-03 1.58990E-02 541351 + 710 541360 Xe-136 2.69080E-02 7.68390E-02 54136.82c + 711 541370 Xe-137 3.34900E-02 6.24850E-02 541370 + 712 541380 Xe-138 3.51140E-02 4.46030E-02 541380 + 713 541390 Xe-139 1.77650E-02 2.21110E-02 541390 + 714 541400 Xe-140 1.21050E-02 1.30150E-02 541400 + 715 541410 Xe-141 4.28130E-03 4.45160E-03 541410 + 716 541420 Xe-142 1.17230E-03 1.18350E-03 541420 + 717 541430 Xe-143 1.71920E-04 1.71930E-04 541430 + 718 541440 Xe-144 2.65340E-05 2.65340E-05 541440 + 719 541450 Xe-145 9.73070E-07 9.73070E-07 541450 + 720 541460 Xe-146 1.89930E-09 1.89930E-09 541460 + 721 551330 Cs-133 1.42810E-08 5.79780E-02 55133.82c + 722 551340 Cs-134 1.64050E-06 3.09300E-06 55134.82c + 723 551341 Cs-134m 1.45250E-06 1.45250E-06 551341 + 724 551350 Cs-135 3.87000E-05 7.69550E-02 55135.82c + 725 551351 Cs-135m 2.86400E-05 2.86400E-05 551351 + 726 551360 Cs-136 3.81840E-04 5.18350E-04 55136.82c + 727 551361 Cs-136m 2.73010E-04 2.73010E-04 551361 + 728 551370 Cs-137 6.33120E-03 6.88170E-02 55137.82c + 729 551380 Cs-138 5.48500E-03 5.75180E-02 551380 + 730 551381 Cs-138m 9.17300E-03 9.17300E-03 551381 + 731 551390 Cs-139 2.88090E-02 5.09200E-02 551390 + 732 551400 Cs-140 2.77730E-02 4.07900E-02 551400 + 733 551410 Cs-141 3.53800E-02 3.98340E-02 551410 + 734 551420 Cs-142 2.02240E-02 2.14050E-02 551420 + 735 551430 Cs-143 1.09870E-02 1.11580E-02 551430 + 736 551440 Cs-144 1.87830E-03 2.84320E-03 551440 + 737 551441 Cs-144m 1.87830E-03 1.87830E-03 551441 + 738 551450 Cs-145 9.80660E-04 9.81590E-04 551450 + 739 551460 Cs-146 1.75440E-04 1.75440E-04 551460 + 740 551470 Cs-147 3.09580E-05 3.09580E-05 551470 + 741 551480 Cs-148 8.48560E-09 8.48560E-09 551480 + 742 561350 Ba-135 5.72310E-10 2.17360E-09 56135.82c + 743 561351 Ba-135m 1.60130E-09 1.60130E-09 561351 + 744 561360 Ba-136 2.70950E-07 6.55860E-04 56136.82c + 745 561361 Ba-136m 7.38550E-07 7.38550E-07 561361 + 746 561370 Ba-137 1.01790E-05 6.88550E-02 56137.82c + 747 561371 Ba-137m 2.84810E-05 6.49910E-02 561371 + 748 561380 Ba-138 4.91380E-04 5.97530E-02 56138.82c + 749 561390 Ba-139 1.85610E-03 5.27760E-02 561390 + 750 561400 Ba-140 6.31620E-03 4.71060E-02 56140.82c + 751 561410 Ba-141 1.00130E-02 4.98470E-02 561410 + 752 561420 Ba-142 2.19640E-02 4.35520E-02 561420 + 753 561430 Ba-143 1.97000E-02 3.07660E-02 561430 + 754 561440 Ba-144 1.70280E-02 2.08600E-02 561440 + 755 561450 Ba-145 7.24370E-03 8.10980E-03 561450 + 756 561460 Ba-146 3.37340E-03 3.53270E-03 561460 + 757 561470 Ba-147 8.69550E-04 8.91690E-04 561470 + 758 561480 Ba-148 1.81350E-04 1.81360E-04 561480 + 759 561490 Ba-149 1.85950E-05 1.85950E-05 561490 + 760 561500 Ba-150 1.96660E-06 1.96660E-06 561500 + 761 561510 Ba-151 6.32080E-10 6.32080E-10 561510 + 762 571380 La-138 1.25230E-08 1.25230E-08 57138.82c + 763 571390 La-139 3.21890E-05 5.28090E-02 57139.82c + 764 571400 La-140 1.47120E-04 4.72530E-02 57140.82c + 765 571410 La-141 9.14550E-04 5.07620E-02 571410 + 766 571420 La-142 2.27410E-03 4.58260E-02 571420 + 767 571430 La-143 8.80380E-03 3.95700E-02 571430 + 768 571440 La-144 1.49700E-02 3.58300E-02 571440 + 769 571450 La-145 2.29230E-02 3.10330E-02 571450 + 770 571460 La-146 5.58830E-03 9.12110E-03 571460 + 771 571461 La-146m 1.17240E-02 1.17240E-02 571461 + 772 571470 La-147 1.43980E-02 1.52900E-02 571470 + 773 571480 La-148 6.56050E-03 6.74120E-03 571480 + 774 571490 La-149 2.42620E-03 2.44470E-03 571490 + 775 571500 La-150 5.30550E-04 5.32520E-04 571500 + 776 571510 La-151 9.92050E-05 9.92060E-05 571510 + 777 571520 La-152 8.94740E-06 8.94740E-06 571520 + 778 571530 La-153 3.03140E-09 3.03140E-09 571530 + 779 581390 Ce-139 2.56670E-07 9.74820E-07 581390 + 780 581391 Ce-139m 7.18150E-07 7.18150E-07 581391 + 781 581400 Ce-140 1.61270E-09 4.72530E-02 58140.82c + 782 581410 Ce-141 4.00910E-06 5.07650E-02 58141.82c + 783 581420 Ce-142 2.78150E-05 4.58540E-02 58142.82c + 784 581430 Ce-143 1.39200E-04 3.97090E-02 58143.82c + 785 581440 Ce-144 8.23310E-04 3.66530E-02 58144.82c + 786 581450 Ce-145 2.31720E-03 3.33500E-02 581450 + 787 581460 Ce-146 6.42170E-03 2.72660E-02 581460 + 788 581470 Ce-147 8.29870E-03 2.35890E-02 581470 + 789 581480 Ce-148 1.04620E-02 1.72370E-02 581480 + 790 581490 Ce-149 6.66770E-03 9.09260E-03 581490 + 791 581500 Ce-150 4.04680E-03 4.56490E-03 581500 + 792 581510 Ce-151 1.27210E-03 1.37180E-03 581510 + 793 581520 Ce-152 3.87510E-04 3.95920E-04 581520 + 794 581530 Ce-153 4.86190E-05 4.86220E-05 581530 + 795 581540 Ce-154 2.98150E-06 2.98150E-06 581540 + 796 581550 Ce-155 1.14170E-08 1.14170E-08 581550 + 797 581560 Ce-156 1.54310E-10 1.54310E-10 581560 + 798 591430 Pr-143 9.84890E-07 3.97100E-02 59143.82c + 799 591440 Pr-144 8.80170E-07 3.66630E-02 591440 + 800 591441 Pr-144m 8.95410E-06 5.14750E-04 591441 + 801 591450 Pr-145 6.62600E-05 3.34160E-02 591450 + 802 591460 Pr-146 2.98730E-04 2.75650E-02 591460 + 803 591470 Pr-147 1.42450E-03 2.50140E-02 591470 + 804 591480 Pr-148 5.33720E-04 1.77710E-02 591480 + 805 591481 Pr-148m 2.58750E-03 2.58750E-03 591481 + 806 591490 Pr-149 6.99850E-03 1.60910E-02 591490 + 807 591500 Pr-150 7.66230E-03 1.22270E-02 591500 + 808 591510 Pr-151 7.66410E-03 9.03590E-03 591510 + 809 591520 Pr-152 4.39610E-03 4.79230E-03 591520 + 810 591530 Pr-153 2.11850E-03 2.16680E-03 591530 + 811 591540 Pr-154 6.19670E-04 6.22630E-04 591540 + 812 591550 Pr-155 1.48880E-04 1.48890E-04 591550 + 813 591560 Pr-156 2.09810E-05 2.09810E-05 591560 + 814 591570 Pr-157 2.95950E-06 2.95950E-06 591570 + 815 591580 Pr-158 4.71270E-10 4.71270E-10 591580 + 816 601450 Nd-145 9.52010E-10 3.34160E-02 60145.82c + 817 601460 Nd-146 3.97650E-06 2.75690E-02 60146.82c + 818 601470 Nd-147 1.09950E-05 2.50250E-02 60147.82c + 819 601480 Nd-148 7.62370E-05 2.04350E-02 60148.82c + 820 601490 Nd-149 2.51850E-04 1.63430E-02 601490 + 821 601500 Nd-150 9.78730E-04 1.32060E-02 60150.82c + 822 601510 Nd-151 1.70750E-03 1.07430E-02 601510 + 823 601520 Nd-152 2.86160E-03 7.65390E-03 601520 + 824 601530 Nd-153 2.46220E-03 4.62900E-03 601530 + 825 601540 Nd-154 1.90570E-03 2.52830E-03 601540 + 826 601550 Nd-155 8.38480E-04 9.87940E-04 601550 + 827 601560 Nd-156 3.01350E-04 3.21950E-04 601560 + 828 601570 Nd-157 7.78670E-05 8.06380E-05 601570 + 829 601580 Nd-158 9.74100E-06 9.74150E-06 601580 + 830 601590 Nd-159 9.55140E-07 9.55140E-07 601590 + 831 601600 Nd-160 1.88230E-09 1.88230E-09 601600 + 832 601610 Nd-161 1.61300E-11 1.61300E-11 601610 + 833 611480 Pm-148 2.65280E-07 3.01430E-07 61148.82c + 834 611481 Pm-148m 7.23080E-07 7.23080E-07 61548.82c + 835 611490 Pm-149 3.91680E-06 1.63470E-02 61149.82c + 836 611500 Pm-150 2.95270E-05 2.95270E-05 611500 + 837 611510 Pm-151 1.68690E-04 1.09120E-02 61151.82c + 838 611520 Pm-152 7.18710E-05 7.72580E-03 611520 + 839 611521 Pm-152m 1.51100E-04 1.51100E-04 611521 + 840 611522 Pm-152m 1.97370E-04 1.97370E-04 611522 + 841 611530 Pm-153 1.12510E-03 5.75410E-03 611530 + 842 611540 Pm-154 7.78150E-04 3.30650E-03 611540 + 843 611541 Pm-154m 7.78150E-04 7.78150E-04 611541 + 844 611550 Pm-155 2.00790E-03 2.99580E-03 611550 + 845 611560 Pm-156 1.43310E-03 1.75500E-03 611560 + 846 611570 Pm-157 9.46410E-04 1.02710E-03 611570 + 847 611580 Pm-158 3.50620E-04 3.60360E-04 611580 + 848 611590 Pm-159 1.01930E-04 1.02880E-04 611590 + 849 611600 Pm-160 2.41000E-05 2.41020E-05 611600 + 850 611610 Pm-161 5.50340E-06 5.50340E-06 611610 + 851 611620 Pm-162 3.14760E-09 3.14760E-09 611620 + 852 611630 Pm-163 5.55180E-11 5.55180E-11 611630 + 853 621500 Sm-150 4.52590E-10 2.95280E-05 62150.82c + 854 621510 Sm-151 1.48540E-08 1.09120E-02 62151.82c + 855 621520 Sm-152 9.94960E-06 8.08420E-03 62152.82c + 856 621530 Sm-153 5.76020E-06 5.77600E-03 62153.82c + 857 621531 Sm-153m 1.61170E-05 1.61170E-05 621531 + 858 621540 Sm-154 9.88750E-05 4.18350E-03 62154.82c + 859 621550 Sm-155 2.15070E-04 3.21090E-03 621550 + 860 621560 Sm-156 4.57270E-04 2.21230E-03 621560 + 861 621570 Sm-157 4.79040E-04 1.50610E-03 621570 + 862 621580 Sm-158 4.84100E-04 8.44480E-04 621580 + 863 621590 Sm-159 3.08780E-04 4.11710E-04 621590 + 864 621600 Sm-160 1.19870E-04 1.43910E-04 621600 + 865 621610 Sm-161 4.16530E-05 4.71560E-05 621610 + 866 621620 Sm-162 7.12860E-06 7.13170E-06 621620 + 867 621630 Sm-163 1.83780E-07 1.83840E-07 621630 + 868 621640 Sm-164 9.20190E-09 9.20190E-09 621640 + 869 621650 Sm-165 1.46850E-10 1.46850E-10 621650 + 870 631530 Eu-153 1.06990E-09 5.77600E-03 63153.82c + 871 631540 Eu-154 1.53810E-08 3.19630E-08 63154.82c + 872 631541 Eu-154m 1.65820E-08 1.65820E-08 631541 + 873 631550 Eu-155 1.09340E-05 3.22190E-03 63155.82c + 874 631560 Eu-156 3.67350E-05 2.24910E-03 63156.82c + 875 631570 Eu-157 1.12960E-04 1.61900E-03 63157.82c + 876 631580 Eu-158 1.74460E-04 1.01890E-03 631580 + 877 631590 Eu-159 2.58770E-04 6.70480E-04 631590 + 878 631600 Eu-160 2.41190E-04 3.85100E-04 631600 + 879 631610 Eu-161 1.83640E-04 2.30800E-04 631610 + 880 631620 Eu-162 8.21910E-05 8.93230E-05 631620 + 881 631630 Eu-163 3.90990E-05 3.92830E-05 631630 + 882 631640 Eu-164 1.09280E-05 1.09370E-05 631640 + 883 631650 Eu-165 2.57570E-07 2.57720E-07 631650 + 884 631660 Eu-166 5.15190E-09 5.15190E-09 631660 + 885 631670 Eu-167 3.00290E-10 3.00290E-10 631670 + 886 641550 Gd-155 2.44390E-11 3.22190E-03 64155.82c + 887 641551 Gd-155m 6.83800E-11 6.83800E-11 641551 + 888 641560 Gd-156 3.39480E-09 2.24910E-03 64156.82c + 889 641570 Gd-157 7.37000E-08 1.61910E-03 64157.82c + 890 641580 Gd-158 9.73800E-07 1.01990E-03 64158.82c + 891 641590 Gd-159 1.42710E-05 6.84750E-04 641590 + 892 641600 Gd-160 2.75430E-05 4.12640E-04 64160.82c + 893 641610 Gd-161 4.45620E-05 2.75360E-04 641610 + 894 641620 Gd-162 5.04150E-05 1.39740E-04 641620 + 895 641630 Gd-163 3.26820E-05 7.19650E-05 641630 + 896 641640 Gd-164 2.91080E-05 4.00450E-05 641640 + 897 641650 Gd-165 1.27910E-05 1.30490E-05 641650 + 898 641660 Gd-166 7.38400E-07 7.43550E-07 641660 + 899 641670 Gd-167 2.18180E-07 2.18480E-07 641670 + 900 641680 Gd-168 1.74340E-08 1.74340E-08 641680 + 901 641690 Gd-169 7.25650E-10 7.25650E-10 641690 + 902 651580 Tb-158 1.43030E-10 1.57000E-10 651580 + 903 651581 Tb-158m 1.40600E-11 1.40600E-11 651581 + 904 651590 Tb-159 5.76640E-09 6.84750E-04 65159.82c + 905 651600 Tb-160 9.23500E-07 9.23500E-07 65160.82c + 906 651610 Tb-161 3.66070E-06 2.79020E-04 651610 + 907 651620 Tb-162 9.75320E-06 1.49490E-04 651620 + 908 651630 Tb-163 1.85030E-05 9.04680E-05 651630 + 909 651640 Tb-164 2.17530E-05 6.17980E-05 651640 + 910 651650 Tb-165 1.91450E-05 3.21940E-05 651650 + 911 651660 Tb-166 9.60000E-06 1.03440E-05 651660 + 912 651670 Tb-167 9.33870E-06 9.55720E-06 651670 + 913 651680 Tb-168 3.91320E-06 3.93060E-06 651680 + 914 651690 Tb-169 2.83970E-07 2.84700E-07 651690 + 915 651700 Tb-170 4.37160E-09 4.37160E-09 651700 + 916 651710 Tb-171 4.70080E-10 4.70080E-10 651710 + 917 661600 Dy-160 1.42600E-11 9.23510E-07 66160.82c + 918 661610 Dy-161 3.22620E-10 2.79020E-04 66161.82c + 919 661620 Dy-162 7.60150E-09 1.49500E-04 66162.82c + 920 661630 Dy-163 7.76050E-08 9.05450E-05 66163.82c + 921 661640 Dy-164 9.08610E-07 6.27070E-05 66164.82c + 922 661650 Dy-165 2.41410E-06 3.49220E-05 661650 + 923 661651 Dy-165m 3.21420E-07 3.21420E-07 661651 + 924 661660 Dy-166 2.69450E-06 1.30380E-05 661660 + 925 661670 Dy-167 9.33500E-07 1.04910E-05 661670 + 926 661680 Dy-168 1.95580E-06 5.88640E-06 661680 + 927 661690 Dy-169 3.68110E-06 3.96580E-06 661690 + 928 661700 Dy-170 2.53570E-07 2.57940E-07 661700 + 929 661710 Dy-171 7.76620E-08 7.81320E-08 661710 + 930 661720 Dy-172 1.50970E-08 1.50970E-08 661720 + 931 661730 Dy-173 8.18920E-10 8.18920E-10 661730 + 932 671630 Ho-163 1.22490E-11 1.38800E-11 671630 + 933 671631 Ho-163m 1.63090E-12 1.63090E-12 671631 + 934 671640 Ho-164 1.11130E-10 4.14050E-10 671640 + 935 671641 Ho-164m 3.02920E-10 3.02920E-10 671641 + 936 671650 Ho-165 9.12050E-07 3.58410E-05 67165.82c + 937 671660 Ho-166 7.50120E-09 1.30460E-05 671660 + 938 671661 Ho-166m 2.04470E-08 2.04470E-08 671661 + 939 671670 Ho-167 9.33380E-07 1.14240E-05 671670 + 940 671680 Ho-168 3.65910E-07 6.86120E-06 671680 + 941 671681 Ho-168m 6.11940E-07 6.11940E-07 671681 + 942 671690 Ho-169 1.84000E-06 5.80580E-06 671690 + 943 671700 Ho-170 5.02230E-07 5.02230E-07 671700 + 944 671701 Ho-170m 1.84250E-07 4.42190E-07 671701 + 945 671710 Ho-171 7.50080E-07 8.28210E-07 671710 + 946 671720 Ho-172 2.52690E-07 2.67790E-07 671720 + 947 671730 Ho-173 7.49620E-08 7.57810E-08 671730 + 948 671740 Ho-174 8.74690E-09 8.74690E-09 671740 + 949 671750 Ho-175 8.99720E-10 8.99720E-10 671750 + 950 681650 Er-165 1.02690E-12 1.02690E-12 681650 + 951 681660 Er-166 1.31180E-11 1.30460E-05 68166.82c + 952 681670 Er-167 3.96070E-10 1.14250E-05 68167.82c + 953 681671 Er-167m 5.27340E-11 1.36510E-06 681671 + 954 681680 Er-168 6.62770E-09 6.87090E-06 68168.82c + 955 681690 Er-169 5.06760E-08 5.85650E-06 681690 + 956 681700 Er-170 4.76070E-08 9.92030E-07 68170.82c + 957 681710 Er-171 1.61170E-07 9.89380E-07 681710 + 958 681720 Er-172 3.54200E-07 6.21990E-07 681720 + 959 681730 Er-173 2.37660E-07 3.13440E-07 681730 + 960 681740 Er-174 1.33110E-07 1.41860E-07 681740 + 961 681750 Er-175 3.59510E-08 3.68510E-08 681750 + 962 681760 Er-176 8.51300E-09 8.51300E-09 681760 + 963 681770 Er-177 5.91930E-10 5.91930E-10 681770 + 964 691690 Tm-169 4.02660E-11 5.85650E-06 691690 + 965 691700 Tm-170 1.16290E-10 1.16290E-10 691700 + 966 691710 Tm-171 2.29530E-09 9.91680E-07 691710 + 967 691720 Tm-172 1.37170E-08 6.35700E-07 691720 + 968 691730 Tm-173 4.57570E-08 3.59200E-07 691730 + 969 691740 Tm-174 5.91240E-08 2.00980E-07 691740 + 970 691750 Tm-175 7.13340E-08 1.08180E-07 691750 + 971 691760 Tm-176 3.91540E-08 4.76670E-08 691760 + 972 691770 Tm-177 2.81410E-08 2.87330E-08 691770 + 973 691780 Tm-178 3.44760E-09 3.44760E-09 691780 + 974 691790 Tm-179 6.42120E-10 6.42120E-10 691790 + 975 701720 Yb-172 2.79390E-11 6.35730E-07 701720 + 976 701730 Yb-173 2.80250E-10 3.59480E-07 701730 + 977 701740 Yb-174 2.04340E-09 2.03030E-07 701740 + 978 701750 Yb-175 5.67380E-09 1.14610E-07 701750 + 979 701751 Yb-175m 7.55430E-10 8.40580E-08 701751 + 980 701760 Yb-176 5.43370E-09 6.09770E-08 701760 + 981 701761 Yb-176m 1.13990E-08 3.52330E-08 701761 + 982 701770 Yb-177 1.10010E-08 4.19490E-08 701770 + 983 701771 Yb-177m 2.21500E-09 3.09480E-08 701771 + 984 701780 Yb-178 1.50740E-08 1.85220E-08 701780 + 985 701790 Yb-179 6.74410E-09 7.38620E-09 701790 + 986 701800 Yb-180 2.55960E-09 2.55960E-09 701800 + 987 701810 Yb-181 3.99620E-10 3.99620E-10 701810 + 988 711740 Lu-174 2.99020E-13 1.10940E-12 711740 + 989 711750 Lu-175 2.15470E-11 1.14630E-07 71175.82c + 990 711760 Lu-176 1.11770E-10 3.63510E-09 71176.82c + 991 711761 Lu-176m 5.32750E-11 5.32750E-11 711761 + 992 711770 Lu-177 4.69560E-10 4.24700E-08 711770 + 993 711771 Lu-177m 2.23580E-10 2.29150E-10 711771 + 994 711772 Lu-177m 1.11260E-11 1.11260E-11 711772 + 995 711780 Lu-178 8.56980E-10 1.93790E-08 711780 + 996 711781 Lu-178m 1.14810E-09 1.14810E-09 711781 + 997 711790 Lu-179 3.64810E-09 1.15200E-08 711790 + 998 711791 Lu-179m 4.85720E-10 7.87190E-09 711791 + 999 711800 Lu-180 9.31510E-10 3.50180E-09 711800 + 1000 711801 Lu-180m 9.31510E-10 3.49110E-09 711801 + 1001 711802 Lu-180m 1.64950E-09 1.64950E-09 711802 + 1002 711810 Lu-181 2.53300E-09 2.93260E-09 711810 + 1003 711820 Lu-182 8.51270E-10 8.51270E-10 711820 + 1004 711830 Lu-183 2.56300E-10 2.56300E-10 711830 + 1005 711840 Lu-184 3.04560E-11 3.04560E-11 711840 + 1006 721780 Hf-178 5.44110E-12 2.05440E-08 72178.82c + 1007 721781 Hf-178m 1.01470E-11 1.15950E-09 721781 + 1008 721782 Hf-178m 1.26930E-12 1.26930E-12 721782 + 1009 721790 Hf-179 5.70150E-11 1.16190E-08 72179.82c + 1010 721791 Hf-179m 1.64980E-11 1.64980E-11 721791 + 1011 721792 Hf-179m 2.49240E-11 2.49240E-11 721792 + 1012 721800 Hf-180 1.40720E-10 6.50490E-09 72180.82c + 1013 721801 Hf-180m 2.95210E-10 1.12000E-09 721801 + 1014 721810 Hf-181 7.52790E-10 3.68540E-09 721810 + 1015 721820 Hf-182 3.67770E-10 1.54310E-09 721820 + 1016 721821 Hf-182m 7.71530E-10 7.71530E-10 721821 + 1017 721830 Hf-183 7.74680E-10 1.03100E-09 721830 + 1018 721840 Hf-184 1.42170E-10 1.57400E-10 721840 + 1019 721841 Hf-184m 2.98260E-10 3.13490E-10 721841 + 1020 721850 Hf-185 1.21470E-10 1.21470E-10 721850 + 1021 721860 Hf-186 2.93620E-11 2.93620E-11 721860 + 1022 721870 Hf-187 2.70290E-12 2.70290E-12 721870 + 1023 731801 Ta-180m 5.75180E-13 4.04700E-12 731801 + 1024 731810 Ta-181 1.01380E-11 3.69560E-09 73181.82c + 1025 731820 Ta-182 1.35120E-11 4.89350E-10 73182.82c + 1026 731821 Ta-182m 1.47590E-11 4.75840E-10 731821 + 1027 731822 Ta-182m 1.35910E-11 4.61080E-10 731822 + 1028 731830 Ta-183 1.42010E-10 1.17300E-09 731830 + 1029 731840 Ta-184 1.86720E-10 6.57610E-10 731840 + 1030 731850 Ta-185 1.44060E-10 3.51490E-10 731850 + 1031 731851 Ta-185m 8.59590E-11 8.59590E-11 731851 + 1032 731860 Ta-186 1.28560E-10 1.57920E-10 731860 + 1033 731870 Ta-187 5.90330E-11 6.17360E-11 731870 + 1034 731880 Ta-188 1.17560E-11 1.17560E-11 731880 + 1035 731890 Ta-189 2.23650E-12 2.23650E-12 731890 + 1036 741840 W-184 6.11140E-12 6.63720E-10 74184.82c + 1037 741850 W-185 5.18750E-12 3.71190E-10 741850 + 1038 741851 W-185m 1.45140E-11 1.45140E-11 741851 + 1039 741860 W-186 3.75080E-11 2.10620E-10 74186.82c + 1040 741861 W-186m 1.51860E-11 1.51860E-11 741861 + 1041 741870 W-187 5.46530E-11 1.16390E-10 741870 + 1042 741880 W-188 4.90090E-11 6.07650E-11 741880 + 1043 741890 W-189 2.23220E-11 2.45590E-11 741890 + 1044 741900 W-190 3.68060E-12 8.61160E-12 741900 + 1045 741901 W-190m 4.93100E-12 4.93100E-12 741901 + 1046 741910 W-191 1.37530E-12 1.37530E-12 741910 + 1047 751870 Re-187 2.76250E-12 1.19150E-10 75187.82c + 1048 751880 Re-188 1.66570E-12 6.69710E-11 751880 + 1049 751881 Re-188m 4.54030E-12 4.54030E-12 751881 + 1050 751890 Re-189 1.30570E-11 3.76160E-11 751890 + 1051 751900 Re-190 3.64050E-12 1.57350E-11 751900 + 1052 751901 Re-190m 7.63750E-12 7.63750E-12 751901 + 1053 751910 Re-191 8.29890E-12 9.67420E-12 751910 + 1054 751920 Re-192 2.84920E-12 2.84920E-12 751920 + 1055 761900 Os-190 5.68530E-13 2.12200E-11 761900 + 1056 761901 Os-190m 7.61670E-13 4.91650E-12 761901 + 1057 761910 Os-191 1.86030E-12 1.20260E-11 761910 + 1058 761920 Os-192 1.55590E-12 6.23160E-12 761920 + 1059 761921 Os-192m 2.08450E-12 2.08450E-12 761921 + 1060 761930 Os-193 2.51480E-12 2.51480E-12 761930 + 1061 761940 Os-194 1.45330E-12 1.45330E-12 761940 + + Nuclide 95243.82c -- americium 243 (Am-243) + + Neutron-induced fission: + + Interpolation region : 1 / 2 + Interpolation energy : 2.53000E-08 MeV + Number of products : 1018 / 1121 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 2.87890E-05 2.87890E-05 1001.82c + 2 10020 H-2 8.79830E-06 8.79830E-06 1002.82c + 3 10030 H-3 1.57000E-04 1.57000E-04 1003.82c + 4 20040 He-4 1.82000E-03 1.82000E-03 2004.82c + 5 200500 Ca-50 1.04220E-12 1.04220E-12 200500 + 6 200510 Ca-51 1.29310E-12 1.29310E-12 200510 + 7 200520 Ca-52 1.37270E-12 1.37270E-12 200520 + 8 210510 Sc-51 1.16010E-12 2.48060E-12 210510 + 9 210520 Sc-52 2.72300E-12 4.06820E-12 210520 + 10 210530 Sc-53 5.27670E-12 5.27670E-12 210530 + 11 210540 Sc-54 4.56770E-12 4.56770E-12 210540 + 12 210550 Sc-55 3.78860E-12 3.78860E-12 210550 + 13 210560 Sc-56 1.25120E-12 1.25120E-12 210560 + 14 220530 Ti-53 2.84340E-12 8.12010E-12 220530 + 15 220540 Ti-54 1.07210E-11 1.52890E-11 220540 + 16 220550 Ti-55 2.00600E-11 2.38490E-11 220550 + 17 220560 Ti-56 3.17470E-11 3.29980E-11 220560 + 18 220570 Ti-57 2.34130E-11 2.34130E-11 220570 + 19 220580 Ti-58 1.46830E-11 1.46830E-11 220580 + 20 220590 Ti-59 3.65370E-12 3.65370E-12 220590 + 21 230550 V-55 5.81620E-12 2.96650E-11 230550 + 22 230560 V-56 2.04360E-11 5.35040E-11 230560 + 23 230570 V-57 6.60190E-11 8.93620E-11 230570 + 24 230580 V-58 9.64100E-11 1.11090E-10 230580 + 25 230590 V-59 1.19830E-10 1.23480E-10 230590 + 26 230600 V-60 6.23960E-11 6.23960E-11 230600 + 27 230610 V-61 3.17230E-11 3.17230E-11 230610 + 28 230620 V-62 6.42420E-12 6.42420E-12 230620 + 29 240560 Cr-56 1.42220E-12 5.52840E-11 240560 + 30 240570 Cr-57 1.12340E-11 1.89110E-10 240570 + 31 240580 Cr-58 7.38390E-11 9.60580E-11 240580 + 32 240590 Cr-59 2.01810E-10 3.25290E-10 240590 + 33 240600 Cr-60 4.69750E-10 5.34050E-10 240600 + 34 240610 Cr-61 5.78200E-10 6.08020E-10 240610 + 35 240620 Cr-62 6.09010E-10 6.15430E-10 240620 + 36 240630 Cr-63 2.53580E-10 2.53580E-10 240630 + 37 240640 Cr-64 8.61980E-11 8.61980E-11 240640 + 38 240650 Cr-65 1.31520E-11 1.31520E-11 240650 + 39 240660 Cr-66 1.49210E-12 1.49210E-12 240660 + 40 250580 Mn-58 1.16500E-12 9.72230E-11 250580 + 41 250590 Mn-59 1.78730E-11 3.43170E-10 250590 + 42 250600 Mn-60 9.89170E-12 5.54040E-10 250600 + 43 250601 Mn-60m 8.78520E-11 8.78520E-11 250601 + 44 250610 Mn-61 5.28950E-10 1.13700E-09 250610 + 45 250620 Mn-62 1.04470E-09 1.35250E-09 250620 + 46 250621 Mn-62m 1.87560E-10 4.95270E-10 250621 + 47 250630 Mn-63 2.36830E-09 2.62190E-09 250630 + 48 250640 Mn-64 2.03160E-09 2.11780E-09 250640 + 49 250650 Mn-65 1.67270E-09 1.68580E-09 250650 + 50 250660 Mn-66 5.48140E-10 5.49630E-10 250660 + 51 250670 Mn-67 1.52400E-10 1.52400E-10 250670 + 52 250680 Mn-68 1.69870E-11 1.69870E-11 250680 + 53 250690 Mn-69 1.41990E-12 1.41990E-12 250690 + 54 260600 Fe-60 1.84520E-12 6.33640E-10 260600 + 55 260610 Fe-61 2.64440E-11 1.16340E-09 260610 + 56 260620 Fe-62 2.98180E-10 2.14590E-09 260620 + 57 260630 Fe-63 1.30150E-09 3.92340E-09 260630 + 58 260640 Fe-64 4.86260E-09 6.98040E-09 260640 + 59 260650 Fe-65 9.03960E-09 1.07260E-08 260650 + 60 260660 Fe-66 1.42160E-08 1.47660E-08 260660 + 61 260670 Fe-67 1.03850E-08 1.05370E-08 260670 + 62 260680 Fe-68 6.44900E-09 6.46630E-09 260680 + 63 260690 Fe-69 1.59200E-09 1.59310E-09 260690 + 64 260700 Fe-70 3.01880E-10 3.01880E-10 260700 + 65 260710 Fe-71 2.66010E-11 2.66010E-11 260710 + 66 260720 Fe-72 1.45200E-12 1.45200E-12 260720 + 67 270620 Co-62 4.10260E-13 2.14630E-09 270620 + 68 270630 Co-63 3.25220E-11 3.95590E-09 270630 + 69 270640 Co-64 3.09280E-10 7.28970E-09 270640 + 70 270650 Co-65 2.67400E-09 1.34000E-08 270650 + 71 270660 Co-66 9.33040E-09 2.40960E-08 270660 + 72 270670 Co-67 2.98710E-08 4.04080E-08 270670 + 73 270680 Co-68 2.29780E-08 3.64020E-08 270680 + 74 270681 Co-68m 2.02710E-08 2.68490E-08 270681 + 75 270690 Co-69 5.34060E-08 5.48880E-08 270690 + 76 270700 Co-70 1.38020E-08 1.38020E-08 270700 + 77 270701 Co-70m 1.38020E-08 1.41040E-08 270701 + 78 270710 Co-71 1.39210E-08 1.39480E-08 270710 + 79 270720 Co-72 2.27320E-09 2.27470E-09 270720 + 80 270730 Co-73 4.11940E-10 4.11940E-10 270730 + 81 270740 Co-74 2.87600E-11 2.87600E-11 270740 + 82 280640 Ni-64 1.48380E-12 7.29120E-09 28064.82c + 83 280650 Ni-65 3.62840E-11 1.34360E-08 280650 + 84 280660 Ni-66 6.63770E-10 2.47600E-08 280660 + 85 280670 Ni-67 5.18870E-09 4.55970E-08 280670 + 86 280680 Ni-68 3.37800E-08 8.41560E-08 280680 + 87 280690 Ni-69 4.58570E-08 1.00200E-07 280690 + 88 280691 Ni-69m 4.58570E-08 4.58570E-08 280691 + 89 280700 Ni-70 2.12120E-07 2.40030E-07 280700 + 90 280710 Ni-71 2.59350E-07 2.73300E-07 280710 + 91 280720 Ni-72 2.20560E-07 2.22830E-07 280720 + 92 280730 Ni-73 1.12480E-07 1.12890E-07 280730 + 93 280740 Ni-74 4.58940E-08 4.59230E-08 280740 + 94 280750 Ni-75 3.37350E-09 3.37350E-09 280750 + 95 280760 Ni-76 7.42800E-10 7.42800E-10 280760 + 96 280770 Ni-77 2.45270E-11 2.45270E-11 280770 + 97 280780 Ni-78 1.33430E-12 1.33430E-12 280780 + 98 290670 Cu-67 3.39840E-11 4.56310E-08 290670 + 99 290680 Cu-68 1.81500E-10 8.46940E-08 290680 + 100 290681 Cu-68m 4.25120E-10 4.25120E-10 290681 + 101 290690 Cu-69 8.29790E-09 1.54350E-07 290690 + 102 290700 Cu-70 3.42680E-09 2.86010E-08 290700 + 103 290701 Cu-70m 3.81760E-08 5.03490E-08 290701 + 104 290702 Cu-70m 3.42680E-09 2.43450E-07 290702 + 105 290710 Cu-71 2.41900E-07 5.15200E-07 290710 + 106 290720 Cu-72 8.27550E-07 1.05040E-06 290720 + 107 290730 Cu-73 1.07300E-06 1.18590E-06 290730 + 108 290740 Cu-74 9.56730E-07 1.00270E-06 290740 + 109 290750 Cu-75 4.39370E-07 4.42690E-07 290750 + 110 290760 Cu-76 1.39810E-07 1.40180E-07 290760 + 111 290761 Cu-76m 1.39810E-07 1.40180E-07 290761 + 112 290770 Cu-77 5.52010E-08 5.52260E-08 290770 + 113 290780 Cu-78 6.97910E-09 6.98040E-09 290780 + 114 290790 Cu-79 7.29680E-10 7.29680E-10 290790 + 115 290800 Cu-80 1.84130E-11 1.84130E-11 290800 + 116 300690 Zn-69 5.37730E-12 1.54380E-07 300690 + 117 300691 Zn-69m 2.32560E-11 2.32560E-11 300691 + 118 300700 Zn-70 8.70060E-10 2.85930E-07 300700 + 119 300710 Zn-71 2.32180E-09 5.17520E-07 300710 + 120 300711 Zn-71m 1.00410E-08 1.00410E-08 300711 + 121 300720 Zn-72 1.12460E-07 1.16280E-06 300720 + 122 300730 Zn-73 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4.29830E-03 411060 + 359 411070 Nb-107 1.45280E-03 1.45470E-03 411070 + 360 411080 Nb-108 2.61430E-04 2.61430E-04 411080 + 361 411090 Nb-109 4.01520E-05 4.01520E-05 411090 + 362 411100 Nb-110 9.73920E-07 9.73920E-07 411100 + 363 420970 Mo-97 7.41820E-09 4.15020E-02 42097.82c + 364 420980 Mo-98 2.22060E-05 4.87520E-02 42098.82c + 365 420990 Mo-99 2.01550E-04 5.13670E-02 42099.82c + 366 421000 Mo-100 1.29980E-03 5.66550E-02 42100.82c + 367 421010 Mo-101 4.39960E-03 5.72350E-02 421010 + 368 421020 Mo-102 1.51250E-02 5.98770E-02 421020 + 369 421030 Mo-103 2.63720E-02 6.32920E-02 421030 + 370 421040 Mo-104 4.36980E-02 6.47960E-02 421040 + 371 421050 Mo-105 3.66490E-02 4.91960E-02 421050 + 372 421060 Mo-106 3.28010E-02 3.69930E-02 421060 + 373 421070 Mo-107 1.61000E-02 1.74840E-02 421070 + 374 421080 Mo-108 8.03360E-03 8.28390E-03 421080 + 375 421090 Mo-109 2.15340E-03 2.18890E-03 421090 + 376 421100 Mo-110 4.81730E-04 4.82310E-04 421100 + 377 421110 Mo-111 6.02110E-05 6.02110E-05 421110 + 378 421120 Mo-112 2.91340E-06 2.91340E-06 421120 + 379 421130 Mo-113 2.29400E-10 2.29400E-10 421130 + 380 430990 Tc-99 8.19830E-07 5.13670E-02 43099.82c + 381 430991 Tc-99m 1.89560E-07 4.52340E-02 430991 + 382 431000 Tc-100 4.10440E-06 4.10440E-06 431000 + 383 431010 Tc-101 4.90950E-05 5.72850E-02 431010 + 384 431020 Tc-102 1.41170E-04 6.00180E-02 431020 + 385 431021 Tc-102m 1.41170E-04 1.41170E-04 431021 + 386 431030 Tc-103 1.83150E-03 6.51240E-02 431030 + 387 431040 Tc-104 5.16880E-03 6.99650E-02 431040 + 388 431050 Tc-105 1.64410E-02 6.56380E-02 431050 + 389 431060 Tc-106 2.43840E-02 6.13770E-02 431060 + 390 431070 Tc-107 3.51080E-02 5.25920E-02 431070 + 391 431080 Tc-108 2.64200E-02 3.47160E-02 431080 + 392 431090 Tc-109 1.98260E-02 2.20030E-02 431090 + 393 431100 Tc-110 8.81470E-03 9.29760E-03 431100 + 394 431110 Tc-111 3.53890E-03 3.59850E-03 431110 + 395 431120 Tc-112 6.73400E-04 6.76250E-04 431120 + 396 431130 Tc-113 1.04160E-04 1.04160E-04 431130 + 397 431140 Tc-114 1.05090E-05 1.05090E-05 431140 + 398 431150 Tc-115 7.19070E-07 7.19070E-07 431150 + 399 441020 Ru-102 3.03510E-06 6.01630E-02 44102.82c + 400 441030 Ru-103 1.03080E-05 6.51590E-02 44103.82c + 401 441031 Ru-103m 2.48860E-05 2.48860E-05 441031 + 402 441040 Ru-104 2.59890E-04 7.02250E-02 44104.82c + 403 441050 Ru-105 1.12570E-03 6.67630E-02 44105.82c + 404 441060 Ru-106 4.48810E-03 6.58650E-02 44106.82c + 405 441070 Ru-107 9.09720E-03 6.16890E-02 441070 + 406 441080 Ru-108 1.86820E-02 5.34150E-02 441080 + 407 441090 Ru-109 2.01550E-02 4.21440E-02 441090 + 408 441100 Ru-110 2.01710E-02 2.94650E-02 441100 + 409 441110 Ru-111 1.12000E-02 1.48090E-02 441110 + 410 441120 Ru-112 5.91710E-03 6.59070E-03 441120 + 411 441130 Ru-113 8.20150E-04 1.32760E-03 441130 + 412 441131 Ru-113m 8.20150E-04 8.20150E-04 441131 + 413 441140 Ru-114 4.62860E-04 4.72780E-04 441140 + 414 441150 Ru-115 8.58060E-05 8.64220E-05 441150 + 415 441160 Ru-116 3.61780E-05 3.61780E-05 441160 + 416 441170 Ru-117 1.25090E-05 1.25090E-05 441170 + 417 441180 Ru-118 4.25110E-06 4.25110E-06 441180 + 418 451040 Rh-104 4.24050E-10 1.70200E-09 451040 + 419 451041 Rh-104m 1.27970E-09 1.27970E-09 451041 + 420 451050 Rh-105 2.60590E-06 6.67660E-02 45105.82c + 421 451051 Rh-105m 3.98370E-07 1.89530E-02 451051 + 422 451060 Rh-106 1.27020E-05 6.58780E-02 451060 + 423 451061 Rh-106m 2.97510E-05 2.97510E-05 451061 + 424 451070 Rh-107 2.99550E-04 6.19880E-02 451070 + 425 451080 Rh-108 2.31030E-04 5.36460E-02 451080 + 426 451081 Rh-108m 6.97170E-04 6.97170E-04 451081 + 427 451090 Rh-109 3.09100E-03 4.52350E-02 451090 + 428 451100 Rh-110 5.03410E-03 3.44990E-02 451100 + 429 451101 Rh-110m 1.34380E-04 1.34380E-04 451101 + 430 451110 Rh-111 8.15470E-03 2.29630E-02 451110 + 431 451120 Rh-112 3.23690E-03 9.82760E-03 451120 + 432 451121 Rh-112m 3.23690E-03 3.23690E-03 451121 + 433 451130 Rh-113 4.70760E-03 6.44530E-03 451130 + 434 451140 Rh-114 9.10800E-04 1.38380E-03 451140 + 435 451141 Rh-114m 9.10800E-04 9.10800E-04 451141 + 436 451150 Rh-115 6.29000E-04 7.15620E-04 451150 + 437 451160 Rh-116 4.56550E-05 8.16980E-05 451160 + 438 451161 Rh-116m 1.06940E-04 1.06940E-04 451161 + 439 451170 Rh-117 5.97460E-05 7.21730E-05 451170 + 440 451180 Rh-118 1.11240E-05 1.52000E-05 451180 + 441 451190 Rh-119 4.39470E-06 4.39470E-06 451190 + 442 451200 Rh-120 3.53160E-12 3.53160E-12 451200 + 443 461070 Pd-107 1.70720E-06 6.19930E-02 46107.82c + 444 461071 Pd-107m 3.20840E-06 3.20840E-06 461071 + 445 461080 Pd-108 2.44410E-05 5.43680E-02 46108.82c + 446 461090 Pd-109 2.77480E-05 4.53150E-02 461090 + 447 461091 Pd-109m 5.21480E-05 2.26700E-02 461091 + 448 461100 Pd-110 3.21450E-04 3.49550E-02 46110.82c + 449 461110 Pd-111 2.44080E-04 2.35180E-02 461110 + 450 461111 Pd-111m 4.58720E-04 5.50570E-04 461111 + 451 461120 Pd-112 1.50060E-03 1.45650E-02 461120 + 452 461130 Pd-113 3.80680E-04 7.74500E-03 461130 + 453 461131 Pd-113m 9.19020E-04 9.19020E-04 461131 + 454 461140 Pd-114 1.20030E-03 3.49490E-03 461140 + 455 461150 Pd-115 1.56590E-04 8.00150E-04 461150 + 456 461151 Pd-115m 2.94290E-04 3.98200E-04 461151 + 457 461160 Pd-116 2.16390E-04 4.05020E-04 461160 + 458 461170 Pd-117 2.45760E-05 1.43380E-04 461170 + 459 461171 Pd-117m 4.61880E-05 4.61880E-05 461171 + 460 461180 Pd-118 2.60750E-05 4.08320E-05 461180 + 461 461190 Pd-119 2.92210E-06 7.31680E-06 461190 + 462 461200 Pd-120 1.50430E-06 1.50430E-06 461200 + 463 461210 Pd-121 1.33800E-09 1.33800E-09 461210 + 464 461220 Pd-122 8.96580E-11 8.96580E-11 461220 + 465 461230 Pd-123 5.02540E-07 5.02540E-07 461230 + 466 461240 Pd-124 1.24270E-07 1.24270E-07 461240 + 467 471090 Ag-109 1.79410E-10 4.53150E-02 47109.82c + 468 471091 Ag-109m 1.17360E-09 4.52930E-02 471091 + 469 471100 Ag-110 2.91010E-07 3.00280E-07 471100 + 470 471101 Ag-110m 6.81630E-07 6.81630E-07 47510.82c + 471 471110 Ag-111 1.14630E-06 2.35570E-02 47111.82c + 472 471111 Ag-111m 7.49820E-06 2.34650E-02 471111 + 473 471120 Ag-112 3.23920E-05 1.45970E-02 471120 + 474 471130 Ag-113 8.40110E-06 5.11860E-03 471130 + 475 471131 Ag-113m 5.49560E-05 7.47130E-03 471131 + 476 471140 Ag-114 1.34950E-05 3.56510E-03 471140 + 477 471141 Ag-114m 5.67530E-05 5.67530E-05 471141 + 478 471150 Ag-115 9.04070E-06 7.27870E-04 471150 + 479 471151 Ag-115m 5.91390E-05 6.41520E-04 471151 + 480 471160 Ag-116 1.44080E-05 4.21460E-04 471160 + 481 471161 Ag-116m 3.37460E-05 3.37460E-05 471161 + 482 471170 Ag-117 6.32790E-06 8.48030E-05 471170 + 483 471171 Ag-117m 4.13940E-05 1.13080E-04 471171 + 484 471180 Ag-118 6.61920E-06 5.54210E-05 471180 + 485 471181 Ag-118m 2.78380E-05 3.36750E-05 471181 + 486 471190 Ag-119 3.42840E-06 7.08680E-06 471190 + 487 471191 Ag-119m 2.24270E-05 2.60850E-05 471191 + 488 471200 Ag-120 3.71920E-06 6.70230E-06 471200 + 489 471201 Ag-120m 5.27740E-06 6.02960E-06 471201 + 490 471210 Ag-121 1.32190E-05 1.32200E-05 471210 + 491 471220 Ag-122 1.82330E-06 1.82340E-06 471220 + 492 471221 Ag-122m 1.64240E-06 1.64240E-06 471221 + 493 471230 Ag-123 7.81780E-06 8.32030E-06 471230 + 494 471240 Ag-124 3.98480E-06 5.90380E-06 471240 + 495 471241 Ag-124m 3.58950E-06 3.58950E-06 471241 + 496 471250 Ag-125 1.03220E-05 1.03220E-05 471250 + 497 471260 Ag-126 5.45550E-06 5.45550E-06 471260 + 498 471270 Ag-127 4.25120E-07 4.25120E-07 471270 + 499 471280 Ag-128 2.83390E-08 2.83390E-08 471280 + 500 471290 Ag-129 1.30400E-09 1.30400E-09 471290 + 501 481120 Cd-112 3.69040E-09 1.45970E-02 48112.82c + 502 481130 Cd-113 2.15800E-07 7.72020E-03 48113.82c + 503 481131 Cd-113m 7.06020E-07 8.92020E-05 481131 + 504 481140 Cd-114 2.61490E-06 3.56770E-03 48114.82c + 505 481150 Cd-115 1.16310E-06 1.17910E-03 481150 + 506 481151 Cd-115m 3.80530E-06 6.05020E-05 48515.82c + 507 481160 Cd-116 6.44990E-06 4.59630E-04 48116.82c + 508 481170 Cd-117 7.72200E-07 1.51190E-04 481170 + 509 481171 Cd-117m 2.52640E-06 4.32140E-05 481171 + 510 481180 Cd-118 6.72880E-06 8.20180E-05 481180 + 511 481190 Cd-119 1.27240E-06 3.09010E-05 481190 + 512 481191 Cd-119m 3.07190E-06 6.61530E-06 481191 + 513 481200 Cd-120 1.72020E-05 2.77030E-05 481200 + 514 481210 Cd-121 5.16060E-06 1.70000E-05 481210 + 515 481211 Cd-121m 1.24580E-05 1.38400E-05 481211 + 516 481220 Cd-122 5.02610E-05 5.37270E-05 481220 + 517 481230 Cd-123 8.25830E-06 1.50690E-05 481230 + 518 481231 Cd-123m 1.99370E-05 2.14530E-05 481231 + 519 481240 Cd-124 7.53200E-05 8.30130E-05 481240 + 520 481250 Cd-125 4.12580E-05 4.64190E-05 481250 + 521 481251 Cd-125m 9.96020E-05 1.04760E-04 481251 + 522 481260 Cd-126 1.70210E-04 1.75670E-04 481260 + 523 481270 Cd-127 1.08400E-04 1.08830E-04 481270 + 524 481280 Cd-128 7.46980E-05 7.47260E-05 481280 + 525 481290 Cd-129 4.11610E-06 4.11680E-06 481290 + 526 481291 Cd-129m 9.93690E-06 9.93750E-06 481291 + 527 481300 Cd-130 5.04650E-06 5.04650E-06 481300 + 528 481310 Cd-131 2.88480E-08 2.88480E-08 481310 + 529 491140 In-114 2.10170E-11 8.22110E-11 491140 + 530 491141 In-114m 3.22140E-11 6.34140E-11 491141 + 531 491142 In-114m 3.12000E-11 3.12000E-11 491142 + 532 491150 In-115 1.35570E-09 1.18070E-03 49115.82c + 533 491151 In-115m 3.13480E-10 1.17910E-03 491151 + 534 491160 In-116 4.59220E-09 4.59220E-09 491160 + 535 491161 In-116m 7.03870E-09 1.38560E-08 491161 + 536 491162 In-116m 6.81730E-09 6.81730E-09 491162 + 537 491170 In-117 1.46530E-07 1.20920E-04 491170 + 538 491171 In-117m 3.38810E-08 1.39240E-04 491171 + 539 491180 In-118 2.10270E-07 8.22280E-05 491180 + 540 491181 In-118m 3.22290E-07 6.30080E-07 491181 + 541 491182 In-118m 3.12160E-07 3.12160E-07 491182 + 542 491190 In-119 5.88190E-07 1.17640E-05 491190 + 543 491191 In-119m 1.36000E-07 2.80470E-05 491191 + 544 491200 In-120 2.49300E-07 2.79520E-05 491200 + 545 491201 In-120m 2.49300E-07 2.49300E-07 491201 + 546 491202 In-120m 2.49300E-07 2.49300E-07 491202 + 547 491210 In-121 3.55440E-06 2.32650E-05 491210 + 548 491211 In-121m 8.21870E-07 1.20960E-05 491211 + 549 491220 In-122 6.59540E-06 6.03220E-05 491220 + 550 491221 In-122m 4.67930E-06 4.67930E-06 491221 + 551 491222 In-122m 4.67930E-06 4.67930E-06 491222 + 552 491230 In-123 2.30860E-05 4.89440E-05 491230 + 553 491231 In-123m 5.33800E-06 1.60010E-05 491231 + 554 491240 In-124 2.40020E-05 1.07020E-04 491240 + 555 491241 In-124m 2.16210E-05 2.16210E-05 491241 + 556 491250 In-125 1.97950E-04 3.24930E-04 491250 + 557 491251 In-125m 4.57710E-05 6.99720E-05 491251 + 558 491260 In-126 3.00980E-04 4.76650E-04 491260 + 559 491261 In-126m 2.71120E-04 2.71120E-04 491261 + 560 491270 In-127 1.01750E-03 1.01750E-03 491270 + 561 491271 In-127m 2.35280E-04 3.44100E-04 491271 + 562 491280 In-128 5.18040E-04 8.03640E-04 491280 + 563 491281 In-128m 2.10870E-04 2.85600E-04 491281 + 564 491282 In-128m 6.56590E-04 6.56590E-04 491282 + 565 491290 In-129 1.13580E-03 1.14580E-03 491290 + 566 491291 In-129m 2.62620E-04 2.66820E-04 491291 + 567 491300 In-130 1.73640E-04 1.78510E-04 491300 + 568 491301 In-130m 1.93940E-04 1.93940E-04 491301 + 569 491302 In-130m 3.29980E-04 3.29980E-04 491302 + 570 491310 In-131 7.68790E-05 7.76890E-05 491310 + 571 491311 In-131m 7.68790E-05 7.68790E-05 491311 + 572 491312 In-131m 7.68790E-05 7.68790E-05 491312 + 573 491320 In-132 2.25010E-05 2.25010E-05 491320 + 574 491330 In-133 2.48680E-06 3.06180E-06 491330 + 575 491331 In-133m 5.75010E-07 5.75010E-07 491331 + 576 491340 In-134 7.47320E-09 7.47320E-09 491340 + 577 501170 Sn-117 9.55200E-12 1.94580E-04 50117.82c + 578 501171 Sn-117m 3.12510E-11 4.12020E-07 501171 + 579 501180 Sn-118 9.33680E-10 8.28640E-05 50118.82c + 580 501190 Sn-119 2.15420E-09 3.82500E-05 50119.82c + 581 501191 Sn-119m 7.04790E-09 1.06340E-05 501191 + 582 501200 Sn-120 1.14990E-07 2.85660E-05 50120.82c + 583 501210 Sn-121 2.82480E-07 3.54370E-05 501210 + 584 501211 Sn-121m 6.81930E-07 3.31750E-06 501211 + 585 501220 Sn-122 2.30400E-06 7.19860E-05 50122.82c + 586 501230 Sn-123 3.91880E-06 7.65040E-06 50123.82c + 587 501231 Sn-123m 1.62330E-06 6.28370E-05 501231 + 588 501240 Sn-124 4.20660E-05 1.70700E-04 50124.82c + 589 501250 Sn-125 6.22780E-05 1.17160E-04 50125.82c + 590 501251 Sn-125m 2.57970E-05 3.65810E-04 501251 + 591 501260 Sn-126 4.72270E-04 1.22240E-03 50126.82c + 592 501270 Sn-127 8.82040E-04 1.27860E-03 501270 + 593 501271 Sn-127m 3.65360E-04 1.32800E-03 501271 + 594 501280 Sn-128 1.21970E-03 5.53660E-03 501280 + 595 501281 Sn-128m 2.85670E-03 3.51330E-03 501281 + 596 501290 Sn-129 1.86310E-03 3.15390E-03 501290 + 597 501291 Sn-129m 4.49780E-03 4.61980E-03 501291 + 598 501300 Sn-130 2.77400E-03 3.23160E-03 501300 + 599 501301 Sn-130m 6.49740E-03 6.74380E-03 501301 + 600 501310 Sn-131 1.79070E-03 1.93960E-03 501310 + 601 501311 Sn-131m 4.32290E-03 4.40310E-03 501311 + 602 501320 Sn-132 3.31710E-03 3.34220E-03 501320 + 603 501330 Sn-133 4.55140E-04 4.55600E-04 501330 + 604 501340 Sn-134 8.81510E-05 8.81530E-05 501340 + 605 501350 Sn-135 5.91440E-06 5.91440E-06 501350 + 606 501360 Sn-136 9.06180E-08 9.06180E-08 501360 + 607 501370 Sn-137 2.33290E-09 2.33290E-09 501370 + 608 511190 Sb-119 8.59040E-13 1.13210E-12 511190 + 609 511200 Sb-120 1.46000E-11 1.46000E-11 511200 + 610 511201 Sb-120m 2.07160E-11 2.07160E-11 511201 + 611 511210 Sb-121 1.77320E-09 3.61820E-05 51121.82c + 612 511220 Sb-122 2.70320E-08 5.76750E-08 511220 + 613 511221 Sb-122m 3.06430E-08 3.06430E-08 511221 + 614 511230 Sb-123 1.11100E-06 7.15980E-05 51123.82c + 615 511240 Sb-124 8.97820E-07 2.10910E-06 51124.82c + 616 511241 Sb-124m 6.86500E-07 1.61500E-06 511241 + 617 511242 Sb-124m 9.28480E-07 9.28480E-07 511242 + 618 511250 Sb-125 1.27850E-05 4.95760E-04 51125.82c + 619 511260 Sb-126 2.10100E-05 2.60290E-05 51126.82c + 620 511261 Sb-126m 1.55340E-05 3.58500E-05 511261 + 621 511262 Sb-126m 2.03160E-05 2.03160E-05 511262 + 622 511270 Sb-127 1.58700E-04 2.76540E-03 511270 + 623 511280 Sb-128 2.07950E-04 5.75730E-03 511280 + 624 511281 Sb-128m 3.54830E-04 3.54830E-04 511281 + 625 511290 Sb-129 2.08920E-03 8.09080E-03 511290 + 626 511291 Sb-129m 1.27670E-03 3.58650E-03 511291 + 627 511300 Sb-130 4.31040E-03 1.09140E-02 511300 + 628 511301 Sb-130m 4.31040E-03 7.68220E-03 511301 + 629 511310 Sb-131 2.22180E-02 2.85610E-02 511310 + 630 511320 Sb-132 1.39730E-02 1.73150E-02 511320 + 631 511321 Sb-132m 1.02980E-02 1.02980E-02 511321 + 632 511330 Sb-133 2.36110E-02 2.40820E-02 511330 + 633 511340 Sb-134 2.25150E-03 2.32530E-03 511340 + 634 511341 Sb-134m 5.27370E-03 5.27430E-03 511341 + 635 511350 Sb-135 2.46470E-03 2.46940E-03 511350 + 636 511360 Sb-136 4.41000E-04 4.41060E-04 511360 + 637 511370 Sb-137 6.36670E-05 6.36680E-05 511370 + 638 511380 Sb-138 3.41130E-07 3.41130E-07 511380 + 639 511390 Sb-139 8.05280E-09 8.05280E-09 511390 + 640 521220 Te-122 1.79320E-11 5.61930E-08 52122.82c + 641 521260 Te-126 1.35870E-06 5.82190E-05 52126.82c + 642 521270 Te-127 6.54920E-07 2.75660E-03 521270 + 643 521271 Te-127m 1.58110E-06 4.57300E-04 52527.82c + 644 521280 Te-128 1.56850E-05 6.11520E-03 52128.82c + 645 521290 Te-129 2.95100E-05 9.61540E-03 521290 + 646 521291 Te-129m 7.12400E-05 4.39110E-03 52529.82c + 647 521300 Te-130 1.05530E-03 1.96510E-02 52130.82c + 648 521310 Te-131 1.15270E-03 2.84910E-02 521310 + 649 521311 Te-131m 2.78260E-03 5.06930E-03 521311 + 650 521320 Te-132 1.72740E-02 4.48870E-02 52132.82c + 651 521330 Te-133 9.67300E-03 3.44090E-02 521330 + 652 521331 Te-133m 2.33520E-02 2.75180E-02 521331 + 653 521340 Te-134 5.05590E-02 5.85430E-02 521340 + 654 521350 Te-135 2.12220E-02 2.33760E-02 521350 + 655 521360 Te-136 1.19400E-02 1.23390E-02 521360 + 656 521370 Te-137 2.86090E-03 2.89340E-03 521370 + 657 521380 Te-138 6.18910E-04 6.19250E-04 521380 + 658 521390 Te-139 2.95980E-05 2.96060E-05 521390 + 659 521400 Te-140 1.87580E-05 1.87580E-05 521400 + 660 521410 Te-141 5.86470E-08 5.86470E-08 521410 + 661 521420 Te-142 1.71880E-09 1.71880E-09 521420 + 662 531280 I-128 1.04540E-06 1.04540E-06 531280 + 663 531290 I-129 2.02110E-08 1.12400E-02 53129.82c + 664 531300 I-130 3.51410E-06 4.77440E-06 53130.82c + 665 531301 I-130m 1.50030E-06 1.50030E-06 531301 + 666 531310 I-131 7.52390E-05 3.25710E-02 53131.82c + 667 531320 I-132 3.09650E-04 4.53930E-02 531320 + 668 531321 I-132m 2.28220E-04 2.28220E-04 531321 + 669 531330 I-133 2.55560E-03 6.12290E-02 531330 + 670 531331 I-133m 1.56170E-03 1.56170E-03 531331 + 671 531340 I-134 9.02060E-03 7.40590E-02 531340 + 672 531341 I-134m 6.64840E-03 6.64840E-03 531341 + 673 531350 I-135 5.33290E-02 7.67050E-02 53135.82c + 674 531360 I-136 1.38930E-02 2.62750E-02 531360 + 675 531361 I-136m 3.25410E-02 3.25840E-02 531361 + 676 531370 I-137 4.00810E-02 4.29270E-02 531370 + 677 531380 I-138 1.44800E-02 1.50600E-02 531380 + 678 531390 I-139 9.72000E-03 9.74960E-03 531390 + 679 531400 I-140 2.24320E-03 2.26200E-03 531400 + 680 531410 I-141 6.08330E-04 6.08390E-04 531410 + 681 531420 I-142 8.41680E-05 8.41700E-05 531420 + 682 531430 I-143 1.38960E-05 1.38960E-05 531430 + 683 531440 I-144 9.84350E-07 9.84350E-07 531440 + 684 541310 Xe-131 2.25310E-09 3.25710E-02 54131.82c + 685 541311 Xe-131m 5.43930E-09 3.53790E-04 541311 + 686 541320 Xe-132 1.44060E-06 4.54280E-02 54132.82c + 687 541321 Xe-132m 1.63300E-06 1.63300E-06 541321 + 688 541330 Xe-133 1.34650E-05 6.12750E-02 54133.82c + 689 541331 Xe-133m 3.25050E-05 1.77530E-03 541331 + 690 541340 Xe-134 1.28720E-04 7.46420E-02 54134.82c + 691 541341 Xe-134m 3.01500E-04 4.54410E-04 541341 + 692 541350 Xe-135 8.16490E-04 7.94040E-02 54135.82c + 693 541351 Xe-135m 1.97110E-03 1.46340E-02 541351 + 694 541360 Xe-136 1.77180E-02 7.93680E-02 54136.82c + 695 541370 Xe-137 2.93610E-02 7.02960E-02 541370 + 696 541380 Xe-138 3.72840E-02 5.25010E-02 541380 + 697 541390 Xe-139 2.32450E-02 3.22500E-02 541390 + 698 541400 Xe-140 1.90040E-02 2.11830E-02 541400 + 699 541410 Xe-141 7.08040E-03 7.58210E-03 541410 + 700 541420 Xe-142 3.27080E-03 3.33950E-03 541420 + 701 541430 Xe-143 5.42840E-04 5.51570E-04 541430 + 702 541440 Xe-144 9.92410E-05 9.98320E-05 541440 + 703 541450 Xe-145 6.72880E-06 6.72880E-06 541450 + 704 541460 Xe-146 4.03900E-08 4.03900E-08 541460 + 705 541470 Xe-147 8.09810E-10 8.09810E-10 541470 + 706 551330 Cs-133 1.81030E-09 6.12750E-02 55133.82c + 707 551340 Cs-134 5.91010E-07 1.02660E-06 55134.82c + 708 551341 Cs-134m 4.35590E-07 4.35590E-07 551341 + 709 551350 Cs-135 6.12050E-06 7.95020E-02 55135.82c + 710 551351 Cs-135m 3.74020E-06 3.74020E-06 551351 + 711 551360 Cs-136 1.64230E-04 2.12360E-04 55136.82c + 712 551361 Cs-136m 9.62470E-05 9.62470E-05 551361 + 713 551370 Cs-137 2.87270E-03 7.31680E-02 55137.82c + 714 551380 Cs-138 3.59270E-03 6.02240E-02 551380 + 715 551381 Cs-138m 5.09800E-03 5.09800E-03 551381 + 716 551390 Cs-139 2.12120E-02 5.34620E-02 551390 + 717 551400 Cs-140 2.53180E-02 4.65050E-02 551400 + 718 551410 Cs-141 3.86470E-02 4.62380E-02 551410 + 719 551420 Cs-142 2.60600E-02 2.93930E-02 551420 + 720 551430 Cs-143 1.92440E-02 1.97930E-02 551430 + 721 551440 Cs-144 3.46930E-03 5.30100E-03 551440 + 722 551441 Cs-144m 3.46930E-03 3.46950E-03 551441 + 723 551450 Cs-145 2.59120E-03 2.59760E-03 551450 + 724 551460 Cs-146 4.53570E-04 4.53610E-04 551460 + 725 551470 Cs-147 1.03760E-04 1.03760E-04 551470 + 726 551480 Cs-148 1.37370E-05 1.37370E-05 551480 + 727 551490 Cs-149 2.72250E-09 2.72250E-09 551490 + 728 561360 Ba-136 5.75150E-09 2.60500E-04 56136.82c + 729 561361 Ba-136m 1.34710E-08 1.34710E-08 561361 + 730 561370 Ba-137 3.91460E-06 7.31820E-02 56137.82c + 731 561371 Ba-137m 9.45040E-06 6.90800E-02 561371 + 732 561380 Ba-138 1.55590E-04 6.13480E-02 56138.82c + 733 561390 Ba-139 7.38460E-04 5.42000E-02 561390 + 734 561400 Ba-140 3.19140E-03 4.96960E-02 56140.82c + 735 561410 Ba-141 6.41200E-03 5.26500E-02 561410 + 736 561420 Ba-142 1.71030E-02 4.68210E-02 561420 + 737 561430 Ba-143 2.03770E-02 4.00150E-02 561430 + 738 561440 Ba-144 2.13770E-02 2.86150E-02 561440 + 739 561450 Ba-145 1.04060E-02 1.26970E-02 561450 + 740 561460 Ba-146 6.36000E-03 6.77880E-03 561460 + 741 561470 Ba-147 1.76960E-03 1.84720E-03 561470 + 742 561480 Ba-148 5.22830E-04 5.33120E-04 561480 + 743 561490 Ba-149 6.56720E-05 6.56750E-05 561490 + 744 561500 Ba-150 9.85610E-06 9.85610E-06 561500 + 745 561510 Ba-151 1.26280E-08 1.26280E-08 561510 + 746 561520 Ba-152 2.27660E-10 2.27660E-10 561520 + 747 571380 La-138 1.52290E-09 1.52290E-09 57138.82c + 748 571390 La-139 7.89780E-06 5.42080E-02 57139.82c + 749 571400 La-140 3.36030E-05 4.97300E-02 57140.82c + 750 571410 La-141 3.33580E-04 5.29830E-02 571410 + 751 571420 La-142 1.02690E-03 4.78480E-02 571420 + 752 571430 La-143 4.70380E-03 4.47190E-02 571430 + 753 571440 La-144 1.01560E-02 3.87710E-02 571440 + 754 571450 La-145 1.91050E-02 3.18020E-02 571450 + 755 571460 La-146 6.19410E-03 1.29730E-02 571460 + 756 571461 La-146m 1.11420E-02 1.11420E-02 571461 + 757 571470 La-147 1.83060E-02 2.01550E-02 571470 + 758 571480 La-148 8.56630E-03 9.09760E-03 571480 + 759 571490 La-149 4.59290E-03 4.65830E-03 571490 + 760 571500 La-150 1.07610E-03 1.08600E-03 571500 + 761 571510 La-151 2.43970E-04 2.43980E-04 571510 + 762 571520 La-152 2.37960E-05 2.37960E-05 571520 + 763 571530 La-153 9.92260E-07 9.92260E-07 571530 + 764 571540 La-154 4.89740E-10 4.89740E-10 571540 + 765 581410 Ce-141 1.10950E-08 5.29830E-02 58141.82c + 766 581420 Ce-142 4.95910E-06 4.78520E-02 58142.82c + 767 581430 Ce-143 3.37820E-05 4.47530E-02 58143.82c + 768 581440 Ce-144 3.20820E-04 3.90910E-02 58144.82c + 769 581450 Ce-145 1.03070E-03 3.28320E-02 581450 + 770 581460 Ce-146 3.40370E-03 2.75190E-02 581460 + 771 581470 Ce-147 5.73580E-03 2.58910E-02 581470 + 772 581480 Ce-148 8.89540E-03 1.80580E-02 581480 + 773 581490 Ce-149 6.81650E-03 1.14390E-02 581490 + 774 581500 Ce-150 5.27120E-03 6.32780E-03 581500 + 775 581510 Ce-151 1.75000E-03 1.99540E-03 581510 + 776 581520 Ce-152 7.52070E-04 7.74430E-04 581520 + 777 581530 Ce-153 9.41110E-05 9.51030E-05 581530 + 778 581540 Ce-154 8.94280E-06 8.94330E-06 581540 + 779 581550 Ce-155 1.04150E-07 1.04150E-07 581550 + 780 581560 Ce-156 2.42530E-09 2.42530E-09 581560 + 781 581570 Ce-157 2.66210E-11 2.66210E-11 581570 + 782 591430 Pr-143 1.34830E-09 4.47530E-02 59143.82c + 783 591440 Pr-144 1.99250E-07 3.90930E-02 591440 + 784 591441 Pr-144m 1.76970E-06 5.41210E-04 591441 + 785 591450 Pr-145 1.82760E-05 3.28500E-02 591450 + 786 591460 Pr-146 1.03200E-04 2.76220E-02 591460 + 787 591470 Pr-147 5.20990E-04 2.64120E-02 591470 + 788 591480 Pr-148 2.76340E-04 1.83350E-02 591480 + 789 591481 Pr-148m 1.16220E-03 1.16220E-03 591481 + 790 591490 Pr-149 3.80540E-03 1.52440E-02 591490 + 791 591500 Pr-150 5.06040E-03 1.13880E-02 591500 + 792 591510 Pr-151 6.28860E-03 8.28400E-03 591510 + 793 591520 Pr-152 3.97830E-03 4.75330E-03 591520 + 794 591530 Pr-153 2.47460E-03 2.56920E-03 591530 + 795 591540 Pr-154 7.80900E-04 7.89790E-04 591540 + 796 591550 Pr-155 2.79250E-04 2.79350E-04 591550 + 797 591560 Pr-156 3.42930E-05 3.42950E-05 591560 + 798 591570 Pr-157 5.71480E-06 5.71480E-06 591570 + 799 591580 Pr-158 4.31060E-09 4.31060E-09 591580 + 800 591590 Pr-159 7.99070E-11 7.99070E-11 591590 + 801 601460 Nd-146 5.91060E-09 2.76220E-02 60146.82c + 802 601470 Nd-147 1.98050E-06 2.64140E-02 60147.82c + 803 601480 Nd-148 1.17820E-05 1.95090E-02 60148.82c + 804 601490 Nd-149 8.65670E-05 1.53310E-02 601490 + 805 601500 Nd-150 3.63680E-04 1.17520E-02 60150.82c + 806 601510 Nd-151 8.15360E-04 9.09940E-03 601510 + 807 601520 Nd-152 1.42980E-03 6.18310E-03 601520 + 808 601530 Nd-153 1.50010E-03 4.06930E-03 601530 + 809 601540 Nd-154 1.39100E-03 2.18080E-03 601540 + 810 601550 Nd-155 6.66230E-04 9.46520E-04 601550 + 811 601560 Nd-156 3.41860E-04 3.75590E-04 601560 + 812 601570 Nd-157 9.06250E-05 9.59750E-05 601570 + 813 601580 Nd-158 1.50480E-05 1.50520E-05 601580 + 814 601590 Nd-159 1.89130E-06 1.89140E-06 601590 + 815 601600 Nd-160 2.77730E-06 2.77730E-06 601600 + 816 601610 Nd-161 2.21860E-10 2.21860E-10 601610 + 817 611480 Pm-148 1.45190E-10 1.62200E-10 61148.82c + 818 611481 Pm-148m 3.40080E-10 3.40080E-10 61548.82c + 819 611490 Pm-149 1.96290E-06 1.53330E-02 61149.82c + 820 611500 Pm-150 5.91610E-06 5.91610E-06 611500 + 821 611510 Pm-151 2.76960E-05 9.12710E-03 61151.82c + 822 611520 Pm-152 2.88630E-05 6.21200E-03 611520 + 823 611521 Pm-152m 5.76360E-05 5.76360E-05 611521 + 824 611522 Pm-152m 6.37510E-05 6.37510E-05 611522 + 825 611530 Pm-153 4.00400E-04 4.46970E-03 611530 + 826 611540 Pm-154 3.10120E-04 2.49090E-03 611540 + 827 611541 Pm-154m 3.10120E-04 3.10120E-04 611541 + 828 611550 Pm-155 1.03920E-03 1.98570E-03 611550 + 829 611560 Pm-156 8.04860E-04 1.18040E-03 611560 + 830 611570 Pm-157 6.08190E-04 7.04170E-04 611570 + 831 611580 Pm-158 2.66390E-04 2.81450E-04 611580 + 832 611590 Pm-159 1.17570E-04 1.19480E-04 611590 + 833 611600 Pm-160 2.41480E-05 2.68990E-05 611600 + 834 611610 Pm-161 4.67650E-06 4.67670E-06 611610 + 835 611620 Pm-162 1.62870E-08 1.62870E-08 611620 + 836 611630 Pm-163 5.94020E-10 5.94020E-10 611630 + 837 621510 Sm-151 1.37250E-09 9.12710E-03 62151.82c + 838 621520 Sm-152 1.98380E-06 6.33540E-03 62152.82c + 839 621530 Sm-153 1.74300E-06 4.47560E-03 62153.82c + 840 621531 Sm-153m 4.20790E-06 4.20790E-06 621531 + 841 621540 Sm-154 2.28150E-05 2.82380E-03 62154.82c + 842 621550 Sm-155 5.61940E-05 2.04190E-03 621550 + 843 621560 Sm-156 1.50970E-04 1.33140E-03 621560 + 844 621570 Sm-157 1.61750E-04 8.65920E-04 621570 + 845 621580 Sm-158 1.89160E-04 4.70630E-04 621580 + 846 621590 Sm-159 1.36910E-04 2.56440E-04 621590 + 847 621600 Sm-160 7.33380E-05 1.00170E-04 621600 + 848 621610 Sm-161 3.18550E-05 3.65320E-05 621610 + 849 621620 Sm-162 1.12460E-05 1.12620E-05 621620 + 850 621630 Sm-163 3.74160E-06 3.74220E-06 621630 + 851 621640 Sm-164 2.54740E-08 2.54740E-08 621640 + 852 621650 Sm-165 8.65520E-10 8.65520E-10 621650 + 853 631530 Eu-153 1.32340E-10 4.47560E-03 63153.82c + 854 631540 Eu-154 1.32510E-09 2.51870E-09 63154.82c + 855 631541 Eu-154m 1.19360E-09 1.19360E-09 631541 + 856 631550 Eu-155 2.97050E-06 2.04490E-03 63155.82c + 857 631560 Eu-156 3.91760E-06 1.33530E-03 63156.82c + 858 631570 Eu-157 2.27650E-05 8.88680E-04 63157.82c + 859 631580 Eu-158 5.40620E-05 5.24690E-04 631580 + 860 631590 Eu-159 8.24130E-05 3.38860E-04 631590 + 861 631600 Eu-160 9.83780E-05 1.98540E-04 631600 + 862 631610 Eu-161 8.29930E-05 1.19530E-04 631610 + 863 631620 Eu-162 4.77500E-05 5.90120E-05 631620 + 864 631630 Eu-163 2.52730E-05 2.90150E-05 631630 + 865 631640 Eu-164 5.83840E-06 5.86390E-06 631640 + 866 631650 Eu-165 9.43740E-07 9.44610E-07 631650 + 867 631660 Eu-166 1.58980E-08 1.58980E-08 631660 + 868 631670 Eu-167 1.20170E-09 1.20170E-09 631670 + 869 641560 Gd-156 2.37770E-10 1.33530E-03 64156.82c + 870 641570 Gd-157 5.88310E-09 8.88690E-04 64157.82c + 871 641580 Gd-158 9.39510E-07 5.25630E-04 64158.82c + 872 641590 Gd-159 9.45310E-07 3.39800E-04 641590 + 873 641600 Gd-160 4.62330E-06 2.03170E-04 64160.82c + 874 641610 Gd-161 8.40090E-06 1.27930E-04 641610 + 875 641620 Gd-162 1.49540E-05 7.39660E-05 641620 + 876 641630 Gd-163 2.24080E-05 5.14230E-05 641630 + 877 641640 Gd-164 7.78030E-06 1.36440E-05 641640 + 878 641650 Gd-165 2.83140E-06 3.77600E-06 641650 + 879 641660 Gd-166 1.97730E-06 1.99320E-06 641660 + 880 641670 Gd-167 2.95650E-07 2.96850E-07 641670 + 881 641680 Gd-168 3.75680E-08 3.75680E-08 641680 + 882 641690 Gd-169 1.57520E-09 1.57520E-09 641690 + 883 651580 Tb-158 1.16700E-11 1.29760E-11 651580 + 884 651581 Tb-158m 1.31400E-12 1.31400E-12 651581 + 885 651590 Tb-159 3.29620E-10 3.39800E-04 65159.82c + 886 651600 Tb-160 5.87800E-09 5.87800E-09 65160.82c + 887 651610 Tb-161 9.34270E-07 1.28860E-04 651610 + 888 651620 Tb-162 4.79600E-07 7.44460E-05 651620 + 889 651630 Tb-163 3.73710E-06 5.51600E-05 651630 + 890 651640 Tb-164 5.83170E-06 1.94760E-05 651640 + 891 651650 Tb-165 1.03760E-05 1.41520E-05 651650 + 892 651660 Tb-166 1.97690E-06 3.97010E-06 651660 + 893 651670 Tb-167 2.57510E-06 2.87200E-06 651670 + 894 651680 Tb-168 1.32280E-06 1.36040E-06 651680 + 895 651690 Tb-169 1.81570E-07 1.83140E-07 651690 + 896 651700 Tb-170 1.88890E-08 1.88890E-08 651700 + 897 651710 Tb-171 1.70240E-09 1.70240E-09 651710 + 898 661610 Dy-161 1.55690E-11 1.28860E-04 66161.82c + 899 661620 Dy-162 5.29540E-10 7.44460E-05 66162.82c + 900 661630 Dy-163 8.91300E-09 5.51690E-05 66163.82c + 901 661640 Dy-164 5.62500E-08 1.95320E-05 66164.82c + 902 661650 Dy-165 2.57280E-07 1.44480E-05 661650 + 903 661651 Dy-165m 3.93310E-08 3.93310E-08 661651 + 904 661660 Dy-166 9.88380E-07 4.95850E-06 661660 + 905 661670 Dy-167 1.32600E-06 4.19800E-06 661670 + 906 661680 Dy-168 1.32260E-06 2.68300E-06 661680 + 907 661690 Dy-169 9.01460E-07 1.08460E-06 661690 + 908 661700 Dy-170 4.43390E-07 4.62280E-07 661700 + 909 661710 Dy-171 1.03350E-07 1.05050E-07 661710 + 910 661720 Dy-172 2.06690E-08 2.06690E-08 661720 + 911 661730 Dy-173 1.64100E-09 1.64100E-09 661730 + 912 671640 Ho-164 4.18610E-12 1.39910E-11 671640 + 913 671641 Ho-164m 9.80490E-12 9.80490E-12 671641 + 914 671650 Ho-165 4.42330E-10 1.44490E-05 67165.82c + 915 671660 Ho-166 7.88540E-10 4.95930E-06 671660 + 916 671661 Ho-166m 1.84700E-09 1.84700E-09 671661 + 917 671670 Ho-167 3.07370E-08 4.22870E-06 671670 + 918 671680 Ho-168 4.39860E-08 2.78910E-06 671680 + 919 671681 Ho-168m 6.24140E-08 6.24140E-08 671681 + 920 671690 Ho-169 2.45360E-07 1.33000E-06 671690 + 921 671700 Ho-170 1.86600E-07 1.86600E-07 671700 + 922 671701 Ho-170m 7.96650E-08 5.41940E-07 671701 + 923 671710 Ho-171 2.69180E-07 3.74230E-07 671710 + 924 671720 Ho-172 1.23660E-07 1.44330E-07 671720 + 925 671730 Ho-173 4.82730E-08 4.99140E-08 671730 + 926 671740 Ho-174 7.99100E-09 7.99100E-09 671740 + 927 671750 Ho-175 1.30810E-09 1.30810E-09 671750 + 928 681670 Er-167 2.00990E-11 4.22870E-06 68167.82c + 929 681671 Er-167m 3.07260E-12 5.05300E-07 681671 + 930 681680 Er-168 4.66310E-10 2.78980E-06 68168.82c + 931 681690 Er-169 3.02190E-09 1.33300E-06 681690 + 932 681700 Er-170 1.71250E-08 7.45660E-07 68170.82c + 933 681710 Er-171 4.21770E-08 4.16410E-07 681710 + 934 681720 Er-172 8.68420E-08 2.31170E-07 681720 + 935 681730 Er-173 7.39690E-08 1.23880E-07 681730 + 936 681740 Er-174 5.40410E-08 6.20320E-08 681740 + 937 681750 Er-175 2.10670E-08 2.23750E-08 681750 + 938 681760 Er-176 7.06640E-09 7.06640E-09 681760 + 939 681770 Er-177 9.54500E-10 9.54500E-10 681770 + 940 691690 Tm-169 1.01530E-12 1.33300E-06 691690 + 941 691700 Tm-170 1.74310E-11 1.74310E-11 691700 + 942 691710 Tm-171 2.45180E-10 4.16650E-07 691710 + 943 691720 Tm-172 1.37880E-09 2.32550E-07 691720 + 944 691730 Tm-173 5.90810E-09 1.29790E-07 691730 + 945 691740 Tm-174 1.01190E-08 7.21510E-08 691740 + 946 691750 Tm-175 1.72580E-08 3.96330E-08 691750 + 947 691760 Tm-176 1.26680E-08 1.97340E-08 691760 + 948 691770 Tm-177 7.77010E-09 8.72460E-09 691770 + 949 691780 Tm-178 2.15330E-09 2.15330E-09 691780 + 950 691790 Tm-179 5.69760E-10 5.69760E-10 691790 + 951 701720 Yb-172 1.39950E-12 2.32550E-07 701720 + 952 701730 Yb-173 1.76890E-11 1.29810E-07 701730 + 953 701740 Yb-174 1.68920E-10 7.23200E-08 701740 + 954 701750 Yb-175 6.60140E-10 4.03940E-08 701750 + 955 701751 Yb-175m 1.00920E-10 3.06180E-08 701751 + 956 701760 Yb-176 9.65390E-10 2.12760E-08 701760 + 957 701761 Yb-176m 1.73650E-09 1.16040E-08 701761 + 958 701770 Yb-177 3.05110E-09 1.24810E-08 701770 + 959 701771 Yb-177m 7.05490E-10 9.43010E-09 701771 + 960 701780 Yb-178 4.50070E-09 6.65400E-09 701780 + 961 701790 Yb-179 2.64970E-09 3.21950E-09 701790 + 962 701800 Yb-180 1.32610E-09 1.32610E-09 701800 + 963 701810 Yb-181 3.18080E-10 3.18080E-10 701810 + 964 711750 Lu-175 1.04750E-12 4.03950E-08 71175.82c + 965 711760 Lu-176 6.90200E-12 1.16730E-09 71176.82c + 966 711761 Lu-176m 3.83700E-12 3.83700E-12 711761 + 967 711770 Lu-177 5.76460E-11 1.25440E-08 711770 + 968 711771 Lu-177m 2.25360E-11 2.29000E-11 711771 + 969 711780 Lu-178 1.15660E-10 6.76970E-09 711780 + 970 711781 Lu-178m 1.31110E-10 1.31110E-10 711781 + 971 711790 Lu-179 5.86430E-10 3.89550E-09 711790 + 972 711791 Lu-179m 8.96480E-11 3.30910E-09 711791 + 973 711800 Lu-180 2.15380E-10 1.14480E-09 711800 + 974 711801 Lu-180m 2.15380E-10 1.54150E-09 711801 + 975 711802 Lu-180m 3.17420E-10 3.17420E-10 711802 + 976 711810 Lu-181 7.77390E-10 1.09550E-09 711810 + 977 711820 Lu-182 3.66780E-10 3.66780E-10 711820 + 978 711830 Lu-183 1.46350E-10 1.46350E-10 711830 + 979 711840 Lu-184 2.48690E-11 2.48690E-11 711840 + 980 721790 Hf-179 4.64600E-12 3.90330E-09 72179.82c + 981 721791 Hf-179m 1.45030E-12 1.45030E-12 721791 + 982 721792 Hf-179m 1.62640E-12 1.62640E-12 721792 + 983 721800 Hf-180 1.60100E-11 2.11850E-09 72180.82c + 984 721801 Hf-180m 2.87980E-11 1.87510E-10 721801 + 985 721810 Hf-181 1.13950E-10 1.20940E-09 721810 + 986 721820 Hf-182 8.63950E-11 5.18440E-10 721820 + 987 721821 Hf-182m 1.55400E-10 1.55400E-10 721821 + 988 721830 Hf-183 2.10630E-10 3.56980E-10 721830 + 989 721840 Hf-184 5.62930E-11 6.87270E-11 721840 + 990 721841 Hf-184m 1.01260E-10 1.13690E-10 721841 + 991 721850 Hf-185 6.29480E-11 6.29480E-11 721850 + 992 721860 Hf-186 2.16260E-11 2.16260E-11 721860 + 993 721870 Hf-187 3.01280E-12 3.01280E-12 721870 + 994 731820 Ta-182 1.27450E-12 9.37020E-11 73182.82c + 995 731821 Ta-182m 1.30090E-12 9.24270E-11 731821 + 996 731822 Ta-182m 9.91650E-13 9.11260E-11 731822 + 997 731830 Ta-183 1.57020E-11 3.72680E-10 731830 + 998 731840 Ta-184 2.76520E-11 2.10070E-10 731840 + 999 731850 Ta-185 3.26330E-11 1.11390E-10 731850 + 1000 731851 Ta-185m 1.58060E-11 1.58060E-11 731851 + 1001 731860 Ta-186 3.63800E-11 5.80060E-11 731860 + 1002 731870 Ta-187 2.29280E-11 2.59410E-11 731870 + 1003 731880 Ta-188 6.54220E-12 6.54220E-12 731880 + 1004 731890 Ta-189 1.77150E-12 1.77150E-12 731890 + 1005 741850 W-185 5.82610E-13 1.13380E-10 741850 + 1006 741851 W-185m 1.40650E-12 1.40650E-12 741851 + 1007 741860 W-186 5.48810E-12 6.52640E-11 74186.82c + 1008 741861 W-186m 1.77030E-12 1.77030E-12 741861 + 1009 741870 W-187 1.04050E-11 3.63460E-11 741870 + 1010 741880 W-188 1.28430E-11 1.93850E-11 741880 + 1011 741890 W-189 7.71840E-12 9.48990E-12 741890 + 1012 741900 W-190 1.84800E-12 3.94280E-12 741900 + 1013 741901 W-190m 2.09480E-12 2.09480E-12 741901 + 1014 751890 Re-189 1.84570E-12 1.13360E-11 751890 + 1015 751900 Re-190 7.46540E-13 5.30170E-12 751900 + 1016 751901 Re-190m 1.34290E-12 1.34290E-12 751901 + 1017 751910 Re-191 2.23570E-12 2.23570E-12 751910 + 1018 751920 Re-192 1.08430E-12 1.08430E-12 751920 + + Neutron-induced fission: + + Interpolation region : 2 / 2 + Interpolation energy : 4.00000E-01 MeV + Number of products : 994 / 1091 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 2.87890E-05 2.87890E-05 1001.82c + 2 10020 H-2 8.79830E-06 8.79830E-06 1002.82c + 3 10030 H-3 1.57000E-04 1.57000E-04 1003.82c + 4 20040 He-4 1.82000E-03 1.82000E-03 2004.82c + 5 200500 Ca-50 4.85930E-12 4.85930E-12 200500 + 6 200510 Ca-51 5.85750E-12 5.85750E-12 200510 + 7 200520 Ca-52 6.01030E-12 6.01030E-12 200520 + 8 200530 Ca-53 2.46120E-12 2.46120E-12 200530 + 9 210510 Sc-51 4.89060E-12 1.08680E-11 210510 + 10 210520 Sc-52 1.11490E-11 1.77780E-11 210520 + 11 210530 Sc-53 2.09610E-11 2.26840E-11 210530 + 12 210540 Sc-54 1.76770E-11 1.76770E-11 210540 + 13 210550 Sc-55 1.41120E-11 1.41120E-11 210550 + 14 210560 Sc-56 4.49940E-12 4.49940E-12 210560 + 15 210570 Sc-57 1.22560E-12 1.22560E-12 210570 + 16 220520 Ti-52 2.43720E-12 2.02150E-11 220520 + 17 220530 Ti-53 1.05250E-11 3.32090E-11 220530 + 18 220540 Ti-54 3.86750E-11 5.63520E-11 220540 + 19 220550 Ti-55 6.98890E-11 8.40010E-11 220550 + 20 220560 Ti-56 1.06350E-10 1.11250E-10 220560 + 21 220570 Ti-57 7.62530E-11 7.70740E-11 220570 + 22 220580 Ti-58 4.63090E-11 4.63090E-11 220580 + 23 220590 Ti-59 1.11100E-11 1.11100E-11 220590 + 24 220600 Ti-60 2.04460E-12 2.04460E-12 220600 + 25 230540 V-54 2.23590E-12 5.85880E-11 230540 + 26 230550 V-55 1.89080E-11 1.02910E-10 230550 + 27 230560 V-56 6.44240E-11 1.75910E-10 230560 + 28 230570 V-57 2.02060E-10 2.78900E-10 230570 + 29 230580 V-58 2.86550E-10 3.32860E-10 230580 + 30 230590 V-59 3.42210E-10 3.53320E-10 230590 + 31 230600 V-60 1.72160E-10 1.74200E-10 230600 + 32 230610 V-61 8.42550E-11 8.42550E-11 230610 + 33 230620 V-62 1.64350E-11 1.64350E-11 230620 + 34 230630 V-63 2.34070E-12 2.34070E-12 230630 + 35 240560 Cr-56 4.13480E-12 1.81160E-10 240560 + 36 240570 Cr-57 3.20820E-11 5.76160E-10 240570 + 37 240580 Cr-58 2.05500E-10 2.72070E-10 240580 + 38 240590 Cr-59 5.43220E-10 8.96540E-10 240590 + 39 240600 Cr-60 1.21860E-09 1.39790E-09 240600 + 40 240610 Cr-61 1.44800E-09 1.52720E-09 240610 + 41 240620 Cr-62 1.46510E-09 1.48230E-09 240620 + 42 240630 Cr-63 5.89550E-10 5.91070E-10 240630 + 43 240640 Cr-64 1.93120E-10 1.93120E-10 240640 + 44 240650 Cr-65 2.82390E-11 2.82390E-11 240650 + 45 240660 Cr-66 3.05600E-12 3.05600E-12 240660 + 46 250580 Mn-58 3.05090E-12 2.75120E-10 250580 + 47 250590 Mn-59 4.49260E-11 9.41470E-10 250590 + 48 250600 Mn-60 2.14200E-11 1.44430E-09 250600 + 49 250601 Mn-60m 2.17910E-10 2.17910E-10 250601 + 50 250610 Mn-61 1.25250E-09 2.77970E-09 250610 + 51 250620 Mn-62 2.43610E-09 3.17730E-09 250620 + 52 250621 Mn-62m 3.81500E-10 1.12270E-09 250621 + 53 250630 Mn-63 5.21710E-09 5.80820E-09 250630 + 54 250640 Mn-64 4.32760E-09 4.52070E-09 250640 + 55 250650 Mn-65 3.40880E-09 3.43700E-09 250650 + 56 250660 Mn-66 1.07160E-09 1.07470E-09 250660 + 57 250670 Mn-67 2.86210E-10 2.86210E-10 250670 + 58 250680 Mn-68 3.06770E-11 3.06770E-11 250680 + 59 250690 Mn-69 2.44110E-12 2.44110E-12 250690 + 60 260600 Fe-60 4.17050E-12 1.64140E-09 260600 + 61 260610 Fe-61 5.84650E-11 2.83820E-09 260610 + 62 260620 Fe-62 6.39570E-10 4.93950E-09 260620 + 63 260630 Fe-63 2.71490E-09 8.52310E-09 260630 + 64 260640 Fe-64 9.81000E-09 1.43310E-08 260640 + 65 260650 Fe-65 1.75200E-08 2.09570E-08 260650 + 66 260660 Fe-66 2.63560E-08 2.74310E-08 260660 + 67 260670 Fe-67 1.85740E-08 1.88600E-08 260670 + 68 260680 Fe-68 1.10810E-08 1.11120E-08 260680 + 69 260690 Fe-69 2.61940E-09 2.62130E-09 260690 + 70 260700 Fe-70 4.74320E-10 4.74320E-10 260700 + 71 260710 Fe-71 3.74300E-11 3.74300E-11 260710 + 72 260720 Fe-72 1.15510E-12 1.15510E-12 260720 + 73 270620 Co-62 7.34420E-13 4.94030E-09 270620 + 74 270621 Co-62m 2.00190E-12 2.00190E-12 270621 + 75 270630 Co-63 6.34060E-11 8.58650E-09 270630 + 76 270640 Co-64 5.89660E-10 1.49200E-08 270640 + 77 270650 Co-65 4.91650E-09 2.58740E-08 270650 + 78 270660 Co-66 1.65410E-08 4.39720E-08 270660 + 79 270670 Co-67 5.10280E-08 6.98880E-08 270670 + 80 270680 Co-68 4.07970E-08 6.16700E-08 270680 + 81 270681 Co-68m 3.04510E-08 4.17470E-08 270681 + 82 270690 Co-69 8.40580E-08 8.64960E-08 270690 + 83 270700 Co-70 2.08500E-08 2.08500E-08 270700 + 84 270701 Co-70m 2.08500E-08 2.13240E-08 270701 + 85 270710 Co-71 1.88240E-08 1.88610E-08 270710 + 86 270720 Co-72 1.77170E-09 1.77290E-09 270720 + 87 270730 Co-73 3.58710E-10 3.58710E-10 270730 + 88 270740 Co-74 2.36320E-11 2.36320E-11 270740 + 89 270750 Co-75 1.62220E-12 1.62220E-12 270750 + 90 280640 Ni-64 2.61840E-12 1.49230E-08 28064.82c + 91 280650 Ni-65 6.23770E-11 2.59360E-08 280650 + 92 280660 Ni-66 1.10520E-09 4.50770E-08 280660 + 93 280670 Ni-67 8.41280E-09 7.83010E-08 280670 + 94 280680 Ni-68 5.29530E-08 1.36360E-07 280680 + 95 280690 Ni-69 6.91300E-08 1.54760E-07 280690 + 96 280691 Ni-69m 6.91300E-08 6.91300E-08 280691 + 97 280700 Ni-70 3.06340E-07 3.48510E-07 280700 + 98 280710 Ni-71 6.71500E-07 6.90360E-07 280710 + 99 280720 Ni-72 5.98450E-07 6.00220E-07 280720 + 100 280730 Ni-73 9.44120E-08 9.47710E-08 280730 + 101 280740 Ni-74 3.64100E-08 3.64340E-08 280740 + 102 280750 Ni-75 7.92770E-09 7.92930E-09 280750 + 103 280760 Ni-76 1.07250E-09 1.07250E-09 280760 + 104 280770 Ni-77 4.89290E-11 4.89290E-11 280770 + 105 280780 Ni-78 1.11400E-12 1.11400E-12 280780 + 106 290660 Cu-66 1.17590E-12 4.50780E-08 290660 + 107 290670 Cu-67 5.16090E-11 7.83530E-08 290670 + 108 290680 Cu-68 2.41550E-10 1.37160E-07 290680 + 109 290681 Cu-68m 6.58430E-10 6.58430E-10 290681 + 110 290690 Cu-69 1.18880E-08 2.35780E-07 290690 + 111 290700 Cu-70 4.22460E-09 4.00190E-08 290700 + 112 290701 Cu-70m 5.39520E-08 7.15890E-08 290701 + 113 290702 Cu-70m 4.22460E-09 3.52740E-07 290702 + 114 290710 Cu-71 3.01660E-07 9.92020E-07 290710 + 115 290720 Cu-72 3.28490E-07 9.28710E-07 290720 + 116 290730 Cu-73 7.23400E-07 8.18170E-07 290730 + 117 290740 Cu-74 1.91000E-06 1.94660E-06 290740 + 118 290750 Cu-75 9.99240E-07 1.00700E-06 290750 + 119 290760 Cu-76 1.96680E-07 1.97220E-07 290760 + 120 290761 Cu-76m 1.96680E-07 1.97220E-07 290761 + 121 290770 Cu-77 1.07420E-07 1.07470E-07 290770 + 122 290780 Cu-78 6.23000E-09 6.23110E-09 290780 + 123 290790 Cu-79 1.00910E-09 1.00910E-09 290790 + 124 290800 Cu-80 2.83250E-11 2.83250E-11 290800 + 125 300690 Zn-69 6.44740E-12 2.35820E-07 300690 + 126 300691 Zn-69m 3.20220E-11 3.20220E-11 300691 + 127 300700 Zn-70 1.13460E-09 4.12050E-07 300700 + 128 300710 Zn-71 2.45670E-09 9.94480E-07 300710 + 129 300711 Zn-71m 1.22010E-08 1.22010E-08 300711 + 130 300720 Zn-72 7.74200E-08 1.00610E-06 300720 + 131 300730 Zn-73 4.10630E-08 1.10120E-06 300730 + 132 300731 Zn-73m 5.67950E-08 2.42000E-07 300731 + 133 300732 Zn-73m 3.70410E-07 3.70410E-07 300732 + 134 300740 Zn-74 9.54870E-07 2.93670E-06 300740 + 135 300750 Zn-75 7.87460E-06 8.85230E-06 300750 + 136 300760 Zn-76 1.00610E-05 1.04500E-05 300760 + 137 300770 Zn-77 7.24600E-06 7.83590E-06 300770 + 138 300771 Zn-77m 9.64770E-07 9.64770E-07 300771 + 139 300780 Zn-78 2.07840E-06 2.08520E-06 300780 + 140 300790 Zn-79 3.21330E-06 3.21370E-06 300790 + 141 300800 Zn-80 1.86290E-07 1.86320E-07 300800 + 142 300810 Zn-81 1.35870E-08 1.35870E-08 300810 + 143 300820 Zn-82 6.59950E-10 6.59950E-10 300820 + 144 300830 Zn-83 1.99220E-11 1.99220E-11 300830 + 145 310710 Ga-71 2.23710E-11 1.00670E-06 310710 + 146 310720 Ga-72 3.15000E-10 1.00650E-06 310720 + 147 310721 Ga-72m 3.09630E-11 3.35560E-08 310721 + 148 310730 Ga-73 7.23300E-07 2.00970E-06 310730 + 149 310740 Ga-74 6.23850E-08 2.31170E-06 310740 + 150 310741 Ga-74m 6.23850E-08 2.99910E-06 310741 + 151 310750 Ga-75 1.55100E-06 1.04030E-05 310750 + 152 310760 Ga-76 4.02170E-06 1.44710E-05 310760 + 153 310770 Ga-77 1.33320E-05 2.16500E-05 310770 + 154 310780 Ga-78 6.23550E-06 8.36250E-06 310780 + 155 310790 Ga-79 3.11080E-05 3.42800E-05 310790 + 156 310800 Ga-80 1.23670E-05 1.25540E-05 310800 + 157 310810 Ga-81 1.03420E-05 1.03550E-05 310810 + 158 310820 Ga-82 2.21130E-06 2.21200E-06 310820 + 159 310830 Ga-83 2.16180E-06 2.16180E-06 310830 + 160 310840 Ga-84 8.25150E-09 8.25150E-09 310840 + 161 310850 Ga-85 2.53940E-10 2.53940E-10 310850 + 162 320730 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431060 Tc-106 2.34180E-02 6.09240E-02 431060 + 399 431070 Tc-107 3.49960E-02 5.27770E-02 431070 + 400 431080 Tc-108 2.72820E-02 3.58070E-02 431080 + 401 431090 Tc-109 2.06450E-02 2.27890E-02 431090 + 402 431100 Tc-110 9.28010E-03 9.81540E-03 431100 + 403 431110 Tc-111 3.70800E-03 3.76470E-03 431110 + 404 431120 Tc-112 6.67440E-04 6.72220E-04 431120 + 405 431130 Tc-113 9.93010E-05 9.93010E-05 431130 + 406 431140 Tc-114 1.46810E-05 1.46810E-05 431140 + 407 431150 Tc-115 1.67670E-06 1.67670E-06 431150 + 408 441020 Ru-102 3.02190E-06 5.97670E-02 44102.82c + 409 441030 Ru-103 6.07040E-06 6.45880E-02 44103.82c + 410 441031 Ru-103m 1.69850E-05 1.69850E-05 441031 + 411 441040 Ru-104 2.35120E-04 6.95050E-02 44104.82c + 412 441050 Ru-105 1.08130E-03 6.63810E-02 44105.82c + 413 441060 Ru-106 4.29690E-03 6.52210E-02 44106.82c + 414 441070 Ru-107 8.80070E-03 6.15780E-02 441070 + 415 441080 Ru-108 1.83020E-02 5.41280E-02 441080 + 416 441090 Ru-109 2.00510E-02 4.28260E-02 441090 + 417 441100 Ru-110 2.07070E-02 3.05190E-02 441100 + 418 441110 Ru-111 1.17850E-02 1.55600E-02 441110 + 419 441120 Ru-112 6.21200E-03 6.88130E-03 441120 + 420 441130 Ru-113 8.16750E-04 1.31820E-03 441130 + 421 441131 Ru-113m 8.16750E-04 8.16750E-04 441131 + 422 441140 Ru-114 4.75550E-04 4.89510E-04 441140 + 423 441150 Ru-115 1.07830E-04 1.09270E-04 441150 + 424 441160 Ru-116 3.41190E-05 3.41190E-05 441160 + 425 441170 Ru-117 1.18480E-05 1.18480E-05 441170 + 426 441180 Ru-118 2.58980E-06 2.58980E-06 441180 + 427 441190 Ru-119 7.07860E-07 7.07860E-07 441190 + 428 451040 Rh-104 3.79480E-10 1.70000E-09 451040 + 429 451041 Rh-104m 1.32220E-09 1.32220E-09 451041 + 430 451050 Rh-105 6.18210E-06 6.63880E-02 45105.82c + 431 451051 Rh-105m 8.23110E-07 1.88450E-02 451051 + 432 451060 Rh-106 1.34940E-05 6.52350E-02 451060 + 433 451061 Rh-106m 3.67820E-05 3.67820E-05 451061 + 434 451070 Rh-107 3.01390E-04 6.18790E-02 451070 + 435 451080 Rh-108 2.07060E-04 5.43350E-02 451080 + 436 451081 Rh-108m 7.21460E-04 7.21460E-04 451081 + 437 451090 Rh-109 3.21720E-03 4.60430E-02 451090 + 438 451100 Rh-110 4.95760E-03 3.54760E-02 451100 + 439 451101 Rh-110m 1.16710E-04 1.16710E-04 451101 + 440 451110 Rh-111 8.20210E-03 2.37620E-02 451110 + 441 451120 Rh-112 3.34100E-03 1.02220E-02 451120 + 442 451121 Rh-112m 3.34100E-03 3.34100E-03 451121 + 443 451130 Rh-113 4.89930E-03 6.62590E-03 451130 + 444 451140 Rh-114 1.01930E-03 1.50910E-03 451140 + 445 451141 Rh-114m 1.01930E-03 1.01930E-03 451141 + 446 451150 Rh-115 8.02960E-04 9.12350E-04 451150 + 447 451160 Rh-116 5.65980E-05 9.05910E-05 451160 + 448 451161 Rh-116m 1.54270E-04 1.54270E-04 451161 + 449 451170 Rh-117 7.22480E-05 8.39590E-05 451170 + 450 451180 Rh-118 2.10410E-05 2.35550E-05 451180 + 451 451190 Rh-119 2.12970E-06 2.80670E-06 451190 + 452 451200 Rh-120 3.72230E-12 3.72230E-12 451200 + 453 461070 Pd-107 9.26840E-07 6.18820E-02 46107.82c + 454 461071 Pd-107m 2.03720E-06 2.03720E-06 461071 + 455 461080 Pd-108 2.17310E-05 5.50780E-02 46108.82c + 456 461090 Pd-109 2.51380E-05 4.61230E-02 461090 + 457 461091 Pd-109m 5.52520E-05 2.30770E-02 461091 + 458 461100 Pd-110 3.70570E-04 3.59630E-02 46110.82c + 459 461110 Pd-111 2.26460E-04 2.43260E-02 461110 + 460 461111 Pd-111m 4.97760E-04 5.92800E-04 461111 + 461 461120 Pd-112 1.49680E-03 1.50600E-02 461120 + 462 461130 Pd-113 3.63010E-04 8.00460E-03 461130 + 463 461131 Pd-113m 1.01570E-03 1.01570E-03 461131 + 464 461140 Pd-114 1.19000E-03 3.71840E-03 461140 + 465 461150 Pd-115 1.70990E-04 9.91530E-04 461150 + 466 461151 Pd-115m 3.75820E-04 5.08290E-04 461151 + 467 461160 Pd-116 2.63380E-04 5.08240E-04 461160 + 468 461170 Pd-117 2.42080E-05 1.62060E-04 461170 + 469 461171 Pd-117m 5.32070E-05 5.32070E-05 461171 + 470 461180 Pd-118 2.37570E-05 4.66250E-05 461180 + 471 461190 Pd-119 1.23170E-05 1.51240E-05 461190 + 472 461200 Pd-120 4.10810E-06 4.10810E-06 461200 + 473 461210 Pd-121 1.78640E-09 1.78640E-09 461210 + 474 461220 Pd-122 6.79220E-11 6.79220E-11 461220 + 475 461230 Pd-123 5.43670E-07 5.43670E-07 461230 + 476 461240 Pd-124 1.48230E-07 1.48230E-07 461240 + 477 471090 Ag-109 1.61010E-10 4.61230E-02 47109.82c + 478 471091 Ag-109m 1.20930E-09 4.61010E-02 471091 + 479 471100 Ag-110 5.28720E-07 5.48320E-07 471100 + 480 471101 Ag-110m 1.44120E-06 1.44120E-06 47510.82c + 481 471110 Ag-111 9.16550E-07 2.43720E-02 47111.82c + 482 471111 Ag-111m 6.88390E-06 2.42750E-02 471111 + 483 471120 Ag-112 3.33250E-05 1.50930E-02 471120 + 484 471130 Ag-113 8.40540E-06 5.29400E-03 471130 + 485 471131 Ag-113m 6.31300E-05 7.72820E-03 471131 + 486 471140 Ag-114 1.48040E-05 3.80490E-03 471140 + 487 471141 Ag-114m 7.17710E-05 7.17710E-05 471141 + 488 471150 Ag-115 1.00990E-05 9.04260E-04 471150 + 489 471151 Ag-115m 7.58480E-05 8.11190E-04 471151 + 490 471160 Ag-116 1.65470E-05 5.27500E-04 471160 + 491 471161 Ag-116m 4.51040E-05 4.51040E-05 471161 + 492 471170 Ag-117 6.61900E-06 9.54940E-05 471170 + 493 471171 Ag-117m 4.97130E-05 1.30740E-04 471171 + 494 471180 Ag-118 4.72010E-06 5.67950E-05 471180 + 495 471181 Ag-118m 2.28830E-05 2.95480E-05 471181 + 496 471190 Ag-119 3.27840E-06 1.08400E-05 471190 + 497 471191 Ag-119m 2.46230E-05 3.21850E-05 471191 + 498 471200 Ag-120 6.10130E-06 1.26910E-05 471200 + 499 471201 Ag-120m 1.02040E-05 1.22580E-05 471201 + 500 471210 Ag-121 8.94700E-06 8.94880E-06 471210 + 501 471220 Ag-122 4.27670E-06 4.27670E-06 471220 + 502 471221 Ag-122m 4.61080E-06 4.61080E-06 471221 + 503 471230 Ag-123 2.22250E-06 2.76620E-06 471230 + 504 471240 Ag-124 5.82110E-06 9.10730E-06 471240 + 505 471241 Ag-124m 6.27590E-06 6.27590E-06 471241 + 506 471250 Ag-125 1.21470E-05 1.21470E-05 471250 + 507 471260 Ag-126 2.38750E-06 2.38750E-06 471260 + 508 471270 Ag-127 1.12440E-06 1.12440E-06 471270 + 509 471280 Ag-128 2.75100E-08 2.75100E-08 471280 + 510 471290 Ag-129 1.04080E-09 1.04080E-09 471290 + 511 481120 Cd-112 3.77450E-09 1.50930E-02 48112.82c + 512 481130 Cd-113 3.82980E-07 7.98510E-03 48113.82c + 513 481131 Cd-113m 1.45030E-06 9.29780E-05 481131 + 514 481140 Cd-114 1.72070E-06 3.80670E-03 48114.82c + 515 481150 Cd-115 1.04000E-06 1.47540E-03 481150 + 516 481151 Cd-115m 3.93840E-06 7.47020E-05 48515.82c + 517 481160 Cd-116 7.70730E-06 5.77600E-04 48116.82c + 518 481170 Cd-117 1.68530E-06 1.73470E-04 481170 + 519 481171 Cd-117m 6.38230E-06 5.29920E-05 481171 + 520 481180 Cd-118 8.52810E-06 8.27560E-05 481180 + 521 481190 Cd-119 2.58910E-06 4.01940E-05 481190 + 522 481191 Cd-119m 7.24400E-06 1.26640E-05 481191 + 523 481200 Cd-120 1.30150E-05 3.34280E-05 481200 + 524 481210 Cd-121 8.58570E-06 1.65990E-05 481210 + 525 481211 Cd-121m 2.40220E-05 2.49570E-05 481211 + 526 481220 Cd-122 4.08470E-05 4.97350E-05 481220 + 527 481230 Cd-123 8.64600E-06 1.09140E-05 481230 + 528 481231 Cd-123m 2.41910E-05 2.46990E-05 481231 + 529 481240 Cd-124 9.30190E-05 1.05250E-04 481240 + 530 481250 Cd-125 3.71020E-05 4.31750E-05 481250 + 531 481251 Cd-125m 1.03810E-04 1.09880E-04 481251 + 532 481260 Cd-126 1.91140E-04 1.93530E-04 481260 + 533 481270 Cd-127 1.40010E-04 1.41130E-04 481270 + 534 481280 Cd-128 6.51260E-05 6.51530E-05 481280 + 535 481290 Cd-129 5.41820E-06 5.41870E-06 481290 + 536 481291 Cd-129m 1.51600E-05 1.51600E-05 481291 + 537 481300 Cd-130 3.01220E-06 3.01220E-06 481300 + 538 481310 Cd-131 2.54960E-08 2.54960E-08 481310 + 539 491140 In-114 1.97170E-11 8.60130E-11 491140 + 540 491141 In-114m 3.18390E-11 6.87000E-11 491141 + 541 491142 In-114m 3.68610E-11 3.68610E-11 491142 + 542 491150 In-115 1.88260E-09 1.47630E-03 49115.82c + 543 491151 In-115m 3.79060E-10 1.47540E-03 491151 + 544 491160 In-116 5.55540E-09 5.55540E-09 491160 + 545 491161 In-116m 8.97080E-09 1.93570E-08 491161 + 546 491162 In-116m 1.03860E-08 1.03860E-08 491162 + 547 491170 In-117 1.86970E-07 1.42140E-04 491170 + 548 491171 In-117m 3.76460E-08 1.59820E-04 491171 + 549 491180 In-118 1.91570E-07 8.29480E-05 491180 + 550 491181 In-118m 3.09350E-07 6.62480E-07 491181 + 551 491182 In-118m 3.58150E-07 3.58150E-07 491182 + 552 491190 In-119 2.80810E-06 2.14180E-05 491190 + 553 491191 In-119m 5.65400E-07 3.68790E-05 491191 + 554 491200 In-120 1.34460E-06 3.47720E-05 491200 + 555 491201 In-120m 1.34460E-06 1.34460E-06 491201 + 556 491202 In-120m 1.34460E-06 1.34460E-06 491202 + 557 491210 In-121 1.01040E-05 4.08090E-05 491210 + 558 491211 In-121m 2.03450E-06 1.30430E-05 491211 + 559 491220 In-122 4.23180E-06 5.39660E-05 491220 + 560 491221 In-122m 3.53860E-06 3.53860E-06 491221 + 561 491222 In-122m 3.53860E-06 3.53860E-06 491222 + 562 491230 In-123 3.16770E-05 5.94550E-05 491230 + 563 491231 In-123m 6.37800E-06 1.42130E-05 491231 + 564 491240 In-124 3.40330E-05 1.39290E-04 491240 + 565 491241 In-124m 3.66920E-05 3.66920E-05 491241 + 566 491250 In-125 2.27350E-04 3.57900E-04 491250 + 567 491251 In-125m 4.57770E-05 6.82860E-05 491251 + 568 491260 In-126 2.79030E-04 4.72560E-04 491260 + 569 491261 In-126m 3.00830E-04 3.00830E-04 491261 + 570 491270 In-127 1.12890E-03 1.12890E-03 491270 + 571 491271 In-127m 2.27300E-04 3.68430E-04 491271 + 572 491280 In-128 4.79140E-04 7.31900E-04 491280 + 573 491281 In-128m 1.87610E-04 2.52760E-04 491281 + 574 491282 In-128m 7.18850E-04 7.18850E-04 491282 + 575 491290 In-129 1.20640E-03 1.22160E-03 491290 + 576 491291 In-129m 2.42900E-04 2.48370E-04 491291 + 577 491300 In-130 1.66050E-04 1.68960E-04 491300 + 578 491301 In-130m 2.41780E-04 2.41780E-04 491301 + 579 491302 In-130m 3.36790E-04 3.36790E-04 491302 + 580 491310 In-131 7.96820E-05 8.05180E-05 491310 + 581 491311 In-131m 7.96820E-05 7.96820E-05 491311 + 582 491312 In-131m 7.96820E-05 7.96820E-05 491312 + 583 491320 In-132 2.22210E-05 2.22210E-05 491320 + 584 491330 In-133 2.53130E-06 3.04090E-06 491330 + 585 491331 In-133m 5.09650E-07 5.09650E-07 491331 + 586 491340 In-134 7.42650E-09 7.42650E-09 491340 + 587 501170 Sn-117 9.91650E-12 2.26690E-04 50117.82c + 588 501171 Sn-117m 3.75530E-11 4.84330E-07 501171 + 589 501180 Sn-118 1.02590E-09 8.36160E-05 50118.82c + 590 501190 Sn-119 2.87470E-09 5.62450E-05 50119.82c + 591 501191 Sn-119m 1.08860E-08 1.93590E-05 501191 + 592 501200 Sn-120 1.62130E-07 3.76240E-05 50120.82c + 593 501210 Sn-121 4.09750E-07 5.39600E-05 501210 + 594 501211 Sn-121m 1.14650E-06 5.76950E-06 501211 + 595 501220 Sn-122 2.52930E-06 6.35740E-05 50122.82c + 596 501230 Sn-123 3.26240E-06 7.79530E-06 50123.82c + 597 501231 Sn-123m 1.16600E-06 7.03000E-05 501231 + 598 501240 Sn-124 4.01010E-05 2.16080E-04 50124.82c + 599 501250 Sn-125 7.10300E-05 1.31490E-04 50125.82c + 600 501251 Sn-125m 2.53860E-05 3.91120E-04 501251 + 601 501260 Sn-126 4.91510E-04 1.26740E-03 50126.82c + 602 501270 Sn-127 9.92560E-04 1.43260E-03 501270 + 603 501271 Sn-127m 3.54740E-04 1.40950E-03 501271 + 604 501280 Sn-128 1.20750E-03 5.94950E-03 501280 + 605 501281 Sn-128m 3.29120E-03 4.01010E-03 501281 + 606 501290 Sn-129 1.73700E-03 3.07710E-03 501290 + 607 501291 Sn-129m 4.86010E-03 4.99010E-03 501291 + 608 501300 Sn-130 2.53130E-03 2.98900E-03 501300 + 609 501301 Sn-130m 6.89980E-03 7.19130E-03 501301 + 610 501310 Sn-131 1.65040E-03 1.80470E-03 501310 + 611 501311 Sn-131m 4.61780E-03 4.70090E-03 501311 + 612 501320 Sn-132 3.27870E-03 3.30350E-03 501320 + 613 501330 Sn-133 3.82830E-04 3.83290E-04 501330 + 614 501340 Sn-134 6.40570E-05 6.40590E-05 501340 + 615 501350 Sn-135 4.96140E-06 4.96140E-06 501350 + 616 501360 Sn-136 7.59560E-08 7.59560E-08 501360 + 617 511190 Sb-119 1.11330E-12 1.56030E-12 511190 + 618 511200 Sb-120 1.95000E-11 1.95000E-11 511200 + 619 511201 Sb-120m 3.26120E-11 3.26120E-11 511201 + 620 511210 Sb-121 2.97530E-09 5.52550E-05 51121.82c + 621 511220 Sb-122 2.38270E-08 5.57480E-08 511220 + 622 511221 Sb-122m 3.19210E-08 3.19210E-08 511221 + 623 511230 Sb-123 2.21660E-06 8.03120E-05 51123.82c + 624 511240 Sb-124 7.74620E-07 1.99360E-06 51124.82c + 625 511241 Sb-124m 6.24880E-07 1.62530E-06 511241 + 626 511242 Sb-124m 1.00040E-06 1.00040E-06 511242 + 627 511250 Sb-125 2.03580E-05 5.42960E-04 51125.82c + 628 511260 Sb-126 1.82900E-05 2.18720E-05 51126.82c + 629 511261 Sb-126m 1.14240E-05 2.55860E-05 511261 + 630 511262 Sb-126m 1.41620E-05 1.41620E-05 511262 + 631 511270 Sb-127 2.07970E-04 3.05010E-03 511270 + 632 511280 Sb-128 2.46020E-04 6.20790E-03 511280 + 633 511281 Sb-128m 3.44090E-04 3.44090E-04 511281 + 634 511290 Sb-129 2.10000E-03 8.27940E-03 511290 + 635 511291 Sb-129m 1.55410E-03 4.04910E-03 511291 + 636 511300 Sb-130 4.33930E-03 1.09240E-02 511300 + 637 511301 Sb-130m 4.33930E-03 7.93490E-03 511301 + 638 511310 Sb-131 2.22530E-02 2.87590E-02 511310 + 639 511320 Sb-132 1.30070E-02 1.63100E-02 511320 + 640 511321 Sb-132m 1.15150E-02 1.15150E-02 511321 + 641 511330 Sb-133 2.38610E-02 2.42550E-02 511330 + 642 511340 Sb-134 1.94560E-03 1.99930E-03 511340 + 643 511341 Sb-134m 5.30330E-03 5.30380E-03 511341 + 644 511350 Sb-135 2.23010E-03 2.23400E-03 511350 + 645 511360 Sb-136 3.95380E-04 3.95430E-04 511360 + 646 511370 Sb-137 4.77690E-05 4.77690E-05 511370 + 647 511380 Sb-138 4.00200E-06 4.00200E-06 511380 + 648 511390 Sb-139 6.42540E-09 6.42540E-09 511390 + 649 521220 Te-122 1.81130E-11 5.43170E-08 52122.82c + 650 521260 Te-126 4.89620E-10 4.38770E-05 52126.82c + 651 521270 Te-127 1.18260E-06 3.04240E-03 521270 + 652 521271 Te-127m 3.30890E-06 5.05940E-04 52527.82c + 653 521280 Te-128 1.56330E-05 6.55520E-03 52128.82c + 654 521290 Te-129 3.27310E-05 1.00600E-02 521290 + 655 521291 Te-129m 9.15790E-05 4.82670E-03 52529.82c + 656 521300 Te-130 1.10660E-03 1.99650E-02 52130.82c + 657 521310 Te-131 1.08560E-03 2.86630E-02 521310 + 658 521311 Te-131m 3.03750E-03 5.33990E-03 521311 + 659 521320 Te-132 1.72170E-02 4.50420E-02 52132.82c + 660 521330 Te-133 8.56570E-03 3.35580E-02 521330 + 661 521331 Te-133m 2.39660E-02 2.81620E-02 521331 + 662 521340 Te-134 5.07570E-02 5.84070E-02 521340 + 663 521350 Te-135 2.19910E-02 2.39390E-02 521350 + 664 521360 Te-136 1.16490E-02 1.20020E-02 521360 + 665 521370 Te-137 2.84570E-03 2.87010E-03 521370 + 666 521380 Te-138 6.96590E-04 7.00590E-04 521380 + 667 521390 Te-139 4.45790E-05 4.45850E-05 521390 + 668 521400 Te-140 1.19160E-05 1.19160E-05 521400 + 669 521410 Te-141 4.77310E-08 4.77310E-08 521410 + 670 531280 I-128 1.66720E-10 1.66720E-10 531280 + 671 531290 I-129 2.32450E-08 1.18460E-02 53129.82c + 672 531300 I-130 7.31600E-06 9.57060E-06 53130.82c + 673 531301 I-130m 2.68400E-06 2.68400E-06 531301 + 674 531310 I-131 8.34260E-05 3.29650E-02 53131.82c + 675 531320 I-132 2.91790E-04 4.55560E-02 531320 + 676 531321 I-132m 2.58340E-04 2.58340E-04 531321 + 677 531330 I-133 2.47640E-03 6.11010E-02 531330 + 678 531331 I-133m 1.83260E-03 1.83260E-03 531331 + 679 531340 I-134 8.17980E-03 7.36630E-02 531340 + 680 531341 I-134m 7.24220E-03 7.24220E-03 531341 + 681 531350 I-135 5.14170E-02 7.53560E-02 53135.82c + 682 531360 I-136 1.23680E-02 2.44130E-02 531360 + 683 531361 I-136m 3.37120E-02 3.37550E-02 531361 + 684 531370 I-137 3.99720E-02 4.28000E-02 531370 + 685 531380 I-138 1.45970E-02 1.52530E-02 531380 + 686 531390 I-139 9.63430E-03 9.67890E-03 531390 + 687 531400 I-140 2.08720E-03 2.09910E-03 531400 + 688 531410 I-141 5.92320E-04 5.92370E-04 531410 + 689 531420 I-142 5.56610E-05 5.56610E-05 531420 + 690 531430 I-143 4.98070E-06 4.98070E-06 531430 + 691 531440 I-144 1.97880E-06 1.97880E-06 531440 + 692 541310 Xe-131 2.64460E-07 3.29660E-02 54131.82c + 693 541311 Xe-131m 7.39940E-07 3.58810E-04 541311 + 694 541320 Xe-132 3.02550E-06 4.56000E-02 54132.82c + 695 541321 Xe-132m 4.05340E-06 4.05340E-06 541321 + 696 541330 Xe-133 1.01470E-05 6.11390E-02 54133.82c + 697 541331 Xe-133m 2.83910E-05 1.76760E-03 541331 + 698 541340 Xe-134 1.29350E-04 7.43110E-02 54134.82c + 699 541341 Xe-134m 3.52580E-04 5.19150E-04 541341 + 700 541350 Xe-135 7.77050E-04 7.82190E-02 54135.82c + 701 541351 Xe-135m 2.17420E-03 1.46140E-02 541351 + 702 541360 Xe-136 1.75380E-02 7.84880E-02 54136.82c + 703 541370 Xe-137 2.83990E-02 6.92260E-02 541370 + 704 541380 Xe-138 3.69920E-02 5.23860E-02 541380 + 705 541390 Xe-139 2.34060E-02 3.23320E-02 541390 + 706 541400 Xe-140 1.95580E-02 2.15860E-02 541400 + 707 541410 Xe-141 7.25100E-03 7.73290E-03 541410 + 708 541420 Xe-142 3.23820E-03 3.28190E-03 541420 + 709 541430 Xe-143 5.12710E-04 5.16490E-04 541430 + 710 541440 Xe-144 1.12650E-04 1.13840E-04 541440 + 711 541450 Xe-145 8.79210E-06 8.79210E-06 541450 + 712 541460 Xe-146 3.14110E-08 3.14110E-08 541460 + 713 541470 Xe-147 8.06070E-10 8.06070E-10 541470 + 714 551330 Cs-133 1.80340E-09 6.11390E-02 55133.82c + 715 551340 Cs-134 5.39680E-07 1.01750E-06 55134.82c + 716 551341 Cs-134m 4.77820E-07 4.77820E-07 551341 + 717 551350 Cs-135 7.41540E-06 7.83200E-02 55135.82c + 718 551351 Cs-135m 5.48760E-06 5.48760E-06 551351 + 719 551360 Cs-136 1.43180E-04 1.94370E-04 55136.82c + 720 551361 Cs-136m 1.02370E-04 1.02370E-04 551361 + 721 551370 Cs-137 2.86050E-03 7.20860E-02 55137.82c + 722 551380 Cs-138 3.23030E-03 5.99920E-02 551380 + 723 551381 Cs-138m 5.40230E-03 5.40230E-03 551381 + 724 551390 Cs-139 2.08350E-02 5.31670E-02 551390 + 725 551400 Cs-140 2.48120E-02 4.64020E-02 551400 + 726 551410 Cs-141 3.83170E-02 4.60580E-02 551410 + 727 551420 Cs-142 2.62170E-02 2.94920E-02 551420 + 728 551430 Cs-143 1.90180E-02 1.95330E-02 551430 + 729 551440 Cs-144 3.32670E-03 5.10080E-03 551440 + 730 551441 Cs-144m 3.32670E-03 3.32690E-03 551441 + 731 551450 Cs-145 2.46420E-03 2.47260E-03 551450 + 732 551460 Cs-146 4.65750E-04 4.65780E-04 551460 + 733 551470 Cs-147 1.01650E-04 1.01650E-04 551470 + 734 551480 Cs-148 8.94100E-06 8.94100E-06 551480 + 735 551490 Cs-149 2.29790E-09 2.29790E-09 551490 + 736 561360 Ba-136 5.82480E-09 2.45570E-04 56136.82c + 737 561361 Ba-136m 1.58770E-08 1.58770E-08 561361 + 738 561370 Ba-137 1.87420E-06 7.20930E-02 56137.82c + 739 561371 Ba-137m 5.24400E-06 6.80540E-02 561371 + 740 561380 Ba-138 1.99530E-04 6.12180E-02 56138.82c + 741 561390 Ba-139 8.36850E-04 5.40030E-02 561390 + 742 561400 Ba-140 3.49350E-03 4.98950E-02 56140.82c + 743 561410 Ba-141 6.51720E-03 5.25750E-02 561410 + 744 561420 Ba-142 1.67660E-02 4.65790E-02 561420 + 745 561430 Ba-143 1.99070E-02 3.92830E-02 561430 + 746 561440 Ba-144 2.14940E-02 2.84490E-02 561440 + 747 561450 Ba-145 1.05810E-02 1.27660E-02 561450 + 748 561460 Ba-146 6.43830E-03 6.86690E-03 561460 + 749 561470 Ba-147 1.75080E-03 1.82570E-03 561470 + 750 561480 Ba-148 5.50420E-04 5.57120E-04 561480 + 751 561490 Ba-149 5.12780E-05 5.12800E-05 561490 + 752 561500 Ba-150 8.89660E-06 8.89660E-06 561500 + 753 561510 Ba-151 9.88310E-09 9.88310E-09 561510 + 754 561520 Ba-152 2.35160E-10 2.35160E-10 561520 + 755 571380 La-138 1.52100E-09 1.52100E-09 57138.82c + 756 571390 La-139 8.92100E-06 5.40120E-02 57139.82c + 757 571400 La-140 4.86960E-05 4.99440E-02 57140.82c + 758 571410 La-141 3.38140E-04 5.29140E-02 571410 + 759 571420 La-142 9.60290E-04 4.75390E-02 571420 + 760 571430 La-143 4.72860E-03 4.40110E-02 571430 + 761 571440 La-144 1.01720E-02 3.86210E-02 571440 + 762 571450 La-145 1.88030E-02 3.15690E-02 571450 + 763 571460 La-146 5.50540E-03 1.23720E-02 571460 + 764 571461 La-146m 1.15500E-02 1.15500E-02 571461 + 765 571470 La-147 1.82180E-02 2.00460E-02 571470 + 766 571480 La-148 8.79080E-03 9.34590E-03 571480 + 767 571490 La-149 4.54850E-03 4.59960E-03 571490 + 768 571500 La-150 1.10090E-03 1.10980E-03 571500 + 769 571510 La-151 2.74390E-04 2.74400E-04 571510 + 770 571520 La-152 3.08190E-05 3.08190E-05 571520 + 771 571530 La-153 2.00030E-06 2.00030E-06 571530 + 772 571540 La-154 4.00430E-10 4.00430E-10 571540 + 773 581410 Ce-141 9.87880E-07 5.29150E-02 58141.82c + 774 581420 Ce-142 1.29320E-05 4.75520E-02 58142.82c + 775 581430 Ce-143 5.18420E-05 4.40630E-02 58143.82c + 776 581440 Ce-144 3.16790E-04 3.89370E-02 58144.82c + 777 581450 Ce-145 1.11940E-03 3.26890E-02 581450 + 778 581460 Ce-146 3.48600E-03 2.74080E-02 581460 + 779 581470 Ce-147 5.84690E-03 2.58930E-02 581470 + 780 581480 Ce-148 8.96460E-03 1.83750E-02 581480 + 781 581490 Ce-149 7.01980E-03 1.15850E-02 581490 + 782 581500 Ce-150 5.35470E-03 6.43450E-03 581500 + 783 581510 Ce-151 1.76860E-03 2.04490E-03 581510 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8.50020E-04 8.77900E-04 591540 + 804 591550 Pr-155 2.85620E-04 2.85710E-04 591550 + 805 591560 Pr-156 4.04790E-05 4.04810E-05 591560 + 806 591570 Pr-157 1.05370E-05 1.05370E-05 591570 + 807 591580 Pr-158 3.46650E-09 3.46650E-09 591580 + 808 591590 Pr-159 5.71120E-11 5.71120E-11 591590 + 809 601460 Nd-146 6.87090E-09 2.74980E-02 60146.82c + 810 601470 Nd-147 1.99570E-06 2.64160E-02 60147.82c + 811 601480 Nd-148 1.49080E-05 2.00190E-02 60148.82c + 812 601490 Nd-149 9.68640E-05 1.55450E-02 601490 + 813 601500 Nd-150 3.69640E-04 1.20570E-02 60150.82c + 814 601510 Nd-151 7.96040E-04 9.34800E-03 601510 + 815 601520 Nd-152 1.62830E-03 6.43050E-03 601520 + 816 601530 Nd-153 1.62930E-03 4.37490E-03 601530 + 817 601540 Nd-154 1.54620E-03 2.42410E-03 601540 + 818 601550 Nd-155 7.25330E-04 1.01210E-03 601550 + 819 601560 Nd-156 3.44130E-04 3.84180E-04 601560 + 820 601570 Nd-157 8.53050E-05 9.51690E-05 601570 + 821 601580 Nd-158 1.92880E-05 1.92910E-05 601580 + 822 601590 Nd-159 9.28570E-07 9.28630E-07 601590 + 823 601600 Nd-160 1.02050E-08 1.02050E-08 601600 + 824 601610 Nd-161 1.67410E-10 1.67410E-10 601610 + 825 611480 Pm-148 1.33720E-10 1.51950E-10 61148.82c + 826 611481 Pm-148m 3.64510E-10 3.64510E-10 61548.82c + 827 611490 Pm-149 9.86810E-07 1.55460E-02 61149.82c + 828 611500 Pm-150 7.91160E-06 7.91160E-06 611500 + 829 611510 Pm-151 3.95410E-05 9.38750E-03 61151.82c + 830 611520 Pm-152 2.16860E-05 6.45210E-03 611520 + 831 611521 Pm-152m 4.55920E-05 4.55920E-05 611521 + 832 611522 Pm-152m 5.95550E-05 5.95550E-05 611522 + 833 611530 Pm-153 4.52500E-04 4.82740E-03 611530 + 834 611540 Pm-154 3.83580E-04 2.80770E-03 611540 + 835 611541 Pm-154m 3.83580E-04 3.83580E-04 611541 + 836 611550 Pm-155 1.12430E-03 2.13640E-03 611550 + 837 611560 Pm-156 9.53370E-04 1.33760E-03 611560 + 838 611570 Pm-157 6.74280E-04 7.69450E-04 611570 + 839 611580 Pm-158 2.77090E-04 2.96380E-04 611580 + 840 611590 Pm-159 1.23310E-04 1.24240E-04 611590 + 841 611600 Pm-160 1.76000E-05 1.76100E-05 611600 + 842 611610 Pm-161 1.02980E-05 1.02980E-05 611610 + 843 611620 Pm-162 1.47480E-08 1.47480E-08 611620 + 844 611630 Pm-163 4.20870E-10 4.20870E-10 611630 + 845 621510 Sm-151 1.97650E-09 9.38750E-03 62151.82c + 846 621520 Sm-152 9.94630E-07 6.55830E-03 62152.82c + 847 621530 Sm-153 5.26630E-07 4.82940E-03 62153.82c + 848 621531 Sm-153m 1.47350E-06 1.47350E-06 621531 + 849 621540 Sm-154 3.00060E-05 3.22130E-03 62154.82c + 850 621550 Sm-155 8.17160E-05 2.21810E-03 621550 + 851 621560 Sm-156 1.64600E-04 1.50220E-03 621560 + 852 621570 Sm-157 1.99890E-04 9.69340E-04 621570 + 853 621580 Sm-158 2.06320E-04 5.02730E-04 621580 + 854 621590 Sm-159 1.59600E-04 2.83860E-04 621590 + 855 621600 Sm-160 8.19800E-05 9.95430E-05 621600 + 856 621610 Sm-161 2.57520E-05 3.60500E-05 621610 + 857 621620 Sm-162 9.00360E-06 9.01830E-06 621620 + 858 621630 Sm-163 3.81790E-06 3.81830E-06 621630 + 859 621640 Sm-164 2.36700E-08 2.36700E-08 621640 + 860 621650 Sm-165 1.29410E-09 1.29410E-09 621650 + 861 631530 Eu-153 1.42970E-10 4.82940E-03 63153.82c + 862 631540 Eu-154 1.81130E-09 3.76420E-09 63154.82c + 863 631541 Eu-154m 1.95290E-09 1.95290E-09 631541 + 864 631550 Eu-155 1.03440E-07 2.21830E-03 63155.82c + 865 631560 Eu-156 7.89140E-06 1.51000E-03 63156.82c + 866 631570 Eu-157 3.23710E-05 1.00170E-03 63157.82c + 867 631580 Eu-158 6.62460E-05 5.68970E-04 631580 + 868 631590 Eu-159 1.00870E-04 3.84730E-04 631590 + 869 631600 Eu-160 9.58340E-05 1.95380E-04 631600 + 870 631610 Eu-161 8.87760E-05 1.24830E-04 631610 + 871 631620 Eu-162 6.38880E-05 7.29060E-05 631620 + 872 631630 Eu-163 3.53350E-05 3.91530E-05 631630 + 873 631640 Eu-164 7.74130E-06 7.76500E-06 631640 + 874 631650 Eu-165 1.15740E-05 1.15750E-05 631650 + 875 631660 Eu-166 2.37990E-08 2.37990E-08 631660 + 876 631670 Eu-167 8.32490E-10 8.32490E-10 631670 + 877 641560 Gd-156 3.21000E-10 1.51000E-03 64156.82c + 878 641570 Gd-157 9.57680E-07 1.00270E-03 64157.82c + 879 641580 Gd-158 9.17450E-07 5.69890E-04 64158.82c + 880 641590 Gd-159 3.71080E-06 3.88440E-04 641590 + 881 641600 Gd-160 7.88090E-06 2.03260E-04 64160.82c + 882 641610 Gd-161 1.36650E-05 1.38490E-04 641610 + 883 641620 Gd-162 1.34690E-05 8.63750E-05 641620 + 884 641630 Gd-163 1.14370E-05 5.05900E-05 641630 + 885 641640 Gd-164 1.06350E-05 1.84000E-05 641640 + 886 641650 Gd-165 4.81600E-06 1.63910E-05 641650 + 887 641660 Gd-166 1.68830E-06 1.71210E-06 641660 + 888 641670 Gd-167 9.83990E-07 9.84820E-07 641670 + 889 641680 Gd-168 3.39620E-08 3.39620E-08 641680 + 890 641690 Gd-169 4.99890E-10 4.99890E-10 641690 + 891 651580 Tb-158 1.28310E-11 1.40840E-11 651580 + 892 651581 Tb-158m 1.26120E-12 1.26120E-12 651581 + 893 651590 Tb-159 5.02580E-10 3.88440E-04 65159.82c + 894 651600 Tb-160 8.76770E-07 8.76770E-07 65160.82c + 895 651610 Tb-161 1.17610E-07 1.38610E-04 651610 + 896 651620 Tb-162 8.99080E-07 8.72740E-05 651620 + 897 651630 Tb-163 3.81310E-06 5.44030E-05 651630 + 898 651640 Tb-164 4.83200E-06 2.32320E-05 651640 + 899 651650 Tb-165 1.15450E-05 2.79360E-05 651650 + 900 651660 Tb-166 7.59570E-06 9.30780E-06 651660 + 901 651670 Tb-167 9.83890E-07 1.96870E-06 651670 + 902 651680 Tb-168 9.82880E-07 1.01680E-06 651680 + 903 651690 Tb-169 6.65900E-08 6.70900E-08 651690 + 904 651700 Tb-170 1.02080E-08 1.02080E-08 651700 + 905 651710 Tb-171 6.85670E-10 6.85670E-10 651710 + 906 661610 Dy-161 2.51110E-11 1.38610E-04 66161.82c + 907 661620 Dy-162 8.32570E-10 8.72750E-05 66162.82c + 908 661630 Dy-163 1.12870E-08 5.44150E-05 66163.82c + 909 661640 Dy-164 8.26010E-08 2.33150E-05 66164.82c + 910 661650 Dy-165 8.49820E-07 2.88970E-05 661650 + 911 661651 Dy-165m 1.13150E-07 1.13150E-07 661651 + 912 661660 Dy-166 1.30130E-06 1.06090E-05 661660 + 913 661670 Dy-167 1.96740E-06 3.93610E-06 661670 + 914 661680 Dy-168 9.82780E-07 1.99960E-06 661680 + 915 661690 Dy-169 3.72610E-07 4.39700E-07 661690 + 916 661700 Dy-170 2.72520E-07 2.82730E-07 661700 + 917 661710 Dy-171 4.81000E-08 4.87860E-08 661710 + 918 661720 Dy-172 7.22590E-09 7.22590E-09 661720 + 919 661730 Dy-173 4.35130E-10 4.35130E-10 661730 + 920 671630 Ho-163 1.41230E-12 1.60030E-12 671630 + 921 671640 Ho-164 6.34550E-12 2.36420E-11 671640 + 922 671641 Ho-164m 1.72970E-11 1.72970E-11 671641 + 923 671650 Ho-165 1.20250E-09 2.89000E-05 67165.82c + 924 671660 Ho-166 1.69770E-09 1.06110E-05 671660 + 925 671661 Ho-166m 4.62770E-09 4.62770E-09 671661 + 926 671670 Ho-167 3.47870E-08 3.97090E-06 671670 + 927 671680 Ho-168 3.67720E-07 2.97920E-06 671680 + 928 671681 Ho-168m 6.14960E-07 6.14960E-07 671681 + 929 671690 Ho-169 5.52480E-07 9.92180E-07 671690 + 930 671700 Ho-170 1.34600E-07 1.34600E-07 671700 + 931 671701 Ho-170m 4.93800E-08 3.32110E-07 671701 + 932 671710 Ho-171 1.41280E-07 1.90070E-07 671710 + 933 671720 Ho-172 4.94630E-08 5.66890E-08 671720 + 934 671730 Ho-173 1.47950E-08 1.52300E-08 671730 + 935 671740 Ho-174 1.86500E-09 1.86500E-09 671740 + 936 671750 Ho-175 2.29250E-10 2.29250E-10 671750 + 937 681660 Er-166 1.65930E-12 1.06110E-05 68166.82c + 938 681670 Er-167 2.62030E-11 3.97090E-06 68167.82c + 939 681671 Er-167m 3.48880E-12 4.74490E-07 681671 + 940 681680 Er-168 6.86090E-10 2.98300E-06 68168.82c + 941 681690 Er-169 1.58800E-09 9.93770E-07 681690 + 942 681700 Er-170 1.33520E-08 4.80060E-07 68170.82c + 943 681710 Er-171 2.49620E-08 2.15030E-07 681710 + 944 681720 Er-172 3.89590E-08 9.56480E-08 681720 + 945 681730 Er-173 2.55850E-08 4.08150E-08 681730 + 946 681740 Er-174 1.43220E-08 1.61870E-08 681740 + 947 681750 Er-175 4.26120E-09 4.49050E-09 681750 + 948 681760 Er-176 1.08690E-09 1.08690E-09 681760 + 949 681770 Er-177 1.10390E-10 1.10390E-10 681770 + 950 691700 Tm-170 1.55750E-11 1.55750E-11 691700 + 951 691710 Tm-171 1.65900E-10 2.15190E-07 691710 + 952 691720 Tm-172 7.08210E-10 9.63560E-08 691720 + 953 691730 Tm-173 2.32340E-09 4.31380E-08 691730 + 954 691740 Tm-174 3.04680E-09 1.92340E-08 691740 + 955 691750 Tm-175 3.95250E-09 8.44300E-09 691750 + 956 691760 Tm-176 2.22740E-09 3.31430E-09 691760 + 957 691770 Tm-177 1.03630E-09 1.14670E-09 691770 + 958 691780 Tm-178 2.17070E-10 2.17070E-10 691780 + 959 691790 Tm-179 4.36220E-11 4.36220E-11 691790 + 960 701730 Yb-173 8.00110E-12 4.31470E-08 701730 + 961 701740 Yb-174 5.82720E-11 1.92920E-08 701740 + 962 701750 Yb-175 1.76240E-10 8.64260E-09 701750 + 963 701751 Yb-175m 2.34650E-11 6.52450E-09 701751 + 964 701760 Yb-176 1.74320E-10 3.65200E-09 701760 + 965 701761 Yb-176m 3.65710E-10 2.02290E-09 701761 + 966 701770 Yb-177 4.74240E-10 1.71640E-09 701770 + 967 701771 Yb-177m 9.54870E-11 1.24220E-09 701771 + 968 701780 Yb-178 5.15690E-10 7.32760E-10 701780 + 969 701790 Yb-179 2.33590E-10 2.77210E-10 701790 + 970 701800 Yb-180 8.95910E-11 8.95910E-11 701800 + 971 701810 Yb-181 1.61180E-11 1.61180E-11 701810 + 972 711760 Lu-176 1.68870E-12 2.03980E-10 71176.82c + 973 711770 Lu-177 9.45520E-12 1.72690E-09 711770 + 974 711771 Lu-177m 4.50220E-12 4.61420E-12 711771 + 975 711780 Lu-178 1.39440E-11 7.46700E-10 711780 + 976 711781 Lu-178m 1.86820E-11 1.86820E-11 711781 + 977 711790 Lu-179 6.02160E-11 3.45450E-10 711790 + 978 711791 Lu-179m 8.01750E-12 2.85230E-10 711791 + 979 711800 Lu-180 1.53850E-11 8.14940E-11 711800 + 980 711801 Lu-180m 1.53850E-11 1.04980E-10 711801 + 981 711802 Lu-180m 2.72420E-11 2.72420E-11 711802 + 982 711810 Lu-181 4.53600E-11 6.14780E-11 711810 + 983 711820 Lu-182 1.61710E-11 1.61710E-11 711820 + 984 711830 Lu-183 4.90770E-12 4.90770E-12 711830 + 985 721800 Hf-180 1.29640E-12 1.51570E-10 72180.82c + 986 721801 Hf-180m 2.71970E-12 1.63410E-11 721801 + 987 721810 Hf-181 7.66770E-12 6.91460E-11 721810 + 988 721820 Hf-182 3.94200E-12 2.35860E-11 721820 + 989 721821 Hf-182m 8.27000E-12 8.27000E-12 721821 + 990 721830 Hf-183 8.13830E-12 1.30460E-11 721830 + 991 721840 Hf-184 1.49340E-12 1.49340E-12 721840 + 992 721841 Hf-184m 3.13310E-12 3.13310E-12 721841 + 993 721850 Hf-185 1.40010E-12 1.40010E-12 721850 + 994 731850 Ta-185 7.80120E-13 2.64570E-12 731850 + + Nuclide 95244.82c -- americium 244 (Am-244) is using NFY data from Cm-245 + + Nuclide 95644.82c -- americium 244m (Am-244m) is using NFY data from Cm-245 + + Nuclide 96240.82c -- curium 240 (Cm-240) is using NFY data from U-236 + + Nuclide 96241.82c -- curium 241 (Cm-241) is using NFY data from Np-238 + + Nuclide 96242.82c -- curium 242 (Cm-242) is using NFY data from U-238 + + Spontaneous fission: + + Decay constant : 4.92390E-08 + SF decay fraction : 6.10000E-08 + Number of products : 1012 / 1052 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 5.59970E-05 5.59970E-05 1001.82c + 2 10020 H-2 1.71130E-05 1.71130E-05 1002.82c + 3 10030 H-3 1.92000E-04 1.92000E-04 1003.82c + 4 20040 He-4 3.54000E-03 3.54000E-03 2004.82c + 5 220530 Ti-53 1.72840E-12 1.72840E-12 220530 + 6 220540 Ti-54 3.16410E-12 3.16410E-12 220540 + 7 220550 Ti-55 2.36520E-12 2.36520E-12 220550 + 8 220560 Ti-56 1.81700E-12 1.81700E-12 220560 + 9 230540 V-54 1.31960E-12 4.48370E-12 230540 + 10 230550 V-55 5.55400E-12 7.91920E-12 230550 + 11 230560 V-56 8.58430E-12 1.04010E-11 230560 + 12 230570 V-57 1.26230E-11 1.26230E-11 230570 + 13 230580 V-58 6.16290E-12 6.16290E-12 230580 + 14 230590 V-59 3.73480E-12 3.73480E-12 230590 + 15 240560 Cr-56 5.00320E-12 1.54550E-11 240560 + 16 240570 Cr-57 1.41760E-11 3.16790E-11 240570 + 17 240580 Cr-58 3.95930E-11 4.08260E-11 240580 + 18 240590 Cr-59 5.04710E-11 5.42060E-11 240590 + 19 240600 Cr-60 6.27260E-11 6.27260E-11 240600 + 20 240610 Cr-61 2.45560E-11 2.45560E-11 240610 + 21 240620 Cr-62 9.55010E-12 9.55010E-12 240620 + 22 240630 Cr-63 1.31140E-12 1.31140E-12 240630 + 23 250580 Mn-58 4.56990E-12 4.53950E-11 250580 + 24 250590 Mn-59 3.73900E-11 9.15960E-11 250590 + 25 250600 Mn-60 9.03290E-12 8.09850E-11 250600 + 26 250601 Mn-60m 8.02250E-11 8.02250E-11 250601 + 27 250610 Mn-61 2.06650E-10 2.31210E-10 250610 + 28 250620 Mn-62 1.50690E-10 1.55460E-10 250620 + 29 250621 Mn-62m 2.70520E-11 3.18270E-11 250621 + 30 250630 Mn-63 1.73720E-10 1.75030E-10 250630 + 31 250640 Mn-64 5.02280E-11 5.02280E-11 250640 + 32 250650 Mn-65 1.55520E-11 1.55520E-11 250650 + 33 250660 Mn-66 1.55440E-12 1.55440E-12 250660 + 34 260600 Fe-60 1.54810E-11 1.67470E-10 260600 + 35 260610 Fe-61 7.30080E-11 3.04210E-10 260610 + 36 260620 Fe-62 3.54520E-10 5.41810E-10 260620 + 37 260630 Fe-63 6.77040E-10 8.52070E-10 260630 + 38 260640 Fe-64 1.21100E-09 1.26120E-09 260640 + 39 260650 Fe-65 8.71650E-10 8.87200E-10 260650 + 40 260660 Fe-66 6.45450E-10 6.47000E-10 260660 + 41 260670 Fe-67 1.42330E-10 1.42330E-10 260670 + 42 260680 Fe-68 2.76020E-11 2.76020E-11 260680 + 43 260690 Fe-69 2.10820E-12 2.10820E-12 260690 + 44 270610 Co-61 1.13990E-12 3.05350E-10 270610 + 45 270620 Co-62 3.88360E-12 5.45780E-10 270620 + 46 270621 Co-62m 9.09640E-12 9.09640E-12 270621 + 47 270630 Co-63 1.54710E-10 1.00680E-09 270630 + 48 270640 Co-64 5.43410E-10 1.80460E-09 270640 + 49 270650 Co-65 2.20430E-09 3.09150E-09 270650 + 50 270660 Co-66 3.29970E-09 3.94670E-09 270660 + 51 270670 Co-67 4.73310E-09 4.87540E-09 270670 + 52 270680 Co-68 1.18680E-09 1.72420E-09 270680 + 53 270681 Co-68m 1.04700E-09 1.07470E-09 270681 + 54 270690 Co-69 1.30640E-09 1.30840E-09 270690 + 55 270700 Co-70 1.15750E-10 1.15750E-10 270700 + 56 270701 Co-70m 1.15750E-10 1.15750E-10 270701 + 57 270710 Co-71 3.44800E-11 3.44800E-11 270710 + 58 270720 Co-72 1.63270E-12 1.63270E-12 270720 + 59 280630 Ni-63 1.01840E-12 1.00780E-09 280630 + 60 280640 Ni-64 2.56590E-11 1.83030E-09 28064.82c + 61 280650 Ni-65 2.32300E-10 3.32380E-09 280650 + 62 280660 Ni-66 2.07200E-09 6.01870E-09 280660 + 63 280670 Ni-67 5.71840E-09 1.05940E-08 280670 + 64 280680 Ni-68 1.54880E-08 1.77630E-08 280680 + 65 280690 Ni-69 9.58150E-09 1.08770E-08 280690 + 66 280691 Ni-69m 9.58150E-09 9.58150E-09 280691 + 67 280700 Ni-70 2.32170E-08 2.34480E-08 280700 + 68 280710 Ni-71 8.75500E-09 8.78950E-09 280710 + 69 280720 Ni-72 3.26230E-09 3.26390E-09 280720 + 70 280730 Ni-73 4.34260E-10 4.34260E-10 280730 + 71 280740 Ni-74 4.66570E-11 4.66570E-11 280740 + 72 280750 Ni-75 1.72920E-12 1.72920E-12 280750 + 73 290660 Cu-66 1.97430E-11 6.03850E-09 290660 + 74 290670 Cu-67 3.73630E-10 1.09680E-08 290670 + 75 290680 Cu-68 6.42500E-10 1.96690E-08 290680 + 76 290681 Cu-68m 1.50490E-09 1.50490E-09 290681 + 77 290690 Cu-69 1.52740E-08 3.57320E-08 290690 + 78 290700 Cu-70 2.70780E-09 1.84450E-08 290700 + 79 290701 Cu-70m 3.01660E-08 3.14740E-08 290701 + 80 290702 Cu-70m 2.70780E-09 2.61560E-08 290702 + 81 290710 Cu-71 7.97410E-08 8.85300E-08 290710 + 82 290720 Cu-72 6.61090E-08 6.93730E-08 290720 + 83 290730 Cu-73 6.29640E-08 6.33980E-08 290730 + 84 290740 Cu-74 1.76980E-08 1.77450E-08 290740 + 85 290750 Cu-75 5.24960E-09 5.25130E-09 290750 + 86 290760 Cu-76 2.52010E-10 2.52010E-10 290760 + 87 290761 Cu-76m 2.52010E-10 2.52010E-10 290761 + 88 290770 Cu-77 4.01890E-11 4.01890E-11 290770 + 89 290780 Cu-78 1.00430E-12 1.00430E-12 290780 + 90 300680 Zn-68 2.53270E-11 1.99350E-08 300680 + 91 300690 Zn-69 8.25480E-11 3.61720E-08 300690 + 92 300691 Zn-69m 3.57000E-10 3.57000E-10 300691 + 93 300700 Zn-70 6.68180E-09 6.57120E-08 300700 + 94 300710 Zn-71 5.69940E-09 9.42300E-08 300710 + 95 300711 Zn-71m 2.46490E-08 2.46490E-08 300711 + 96 300720 Zn-72 1.41870E-07 2.11240E-07 300720 + 97 300730 Zn-73 2.61950E-08 2.26830E-07 300730 + 98 300731 Zn-73m 3.58090E-08 1.37240E-07 300731 + 99 300732 Zn-73m 2.02860E-07 2.02860E-07 300732 + 100 300740 Zn-74 4.63240E-07 4.81170E-07 300740 + 101 300750 Zn-75 3.21290E-07 3.26360E-07 300750 + 102 300760 Zn-76 2.29530E-07 2.30030E-07 300760 + 103 300770 Zn-77 4.26940E-08 4.59980E-08 300770 + 104 300771 Zn-77m 6.52670E-09 6.52670E-09 300771 + 105 300780 Zn-78 9.22850E-09 9.22950E-09 300780 + 106 300790 Zn-79 6.87760E-10 6.87760E-10 300790 + 107 300800 Zn-80 4.67790E-11 4.67790E-11 300800 + 108 310700 Ga-70 1.53430E-11 1.53430E-11 310700 + 109 310710 Ga-71 5.17470E-10 1.19400E-07 310710 + 110 310720 Ga-72 5.06950E-09 2.16880E-07 310720 + 111 310721 Ga-72m 5.70800E-10 7.60950E-09 310721 + 112 310730 Ga-73 6.53360E-08 3.93590E-07 310730 + 113 310740 Ga-74 1.11820E-07 5.56570E-07 310740 + 114 310741 Ga-74m 1.11820E-07 5.92990E-07 310741 + 115 310750 Ga-75 8.75140E-07 1.20150E-06 310750 + 116 310760 Ga-76 1.27020E-06 1.50020E-06 310760 + 117 310770 Ga-77 1.78270E-06 1.83200E-06 310770 + 118 310780 Ga-78 8.17510E-07 8.26750E-07 310780 + 119 310790 Ga-79 4.68400E-07 4.69080E-07 310790 + 120 310800 Ga-80 8.82230E-08 8.82700E-08 310800 + 121 310810 Ga-81 7.77120E-09 7.77120E-09 310810 + 122 310820 Ga-82 4.64710E-10 4.64710E-10 310820 + 123 310830 Ga-83 2.69720E-11 2.69720E-11 310830 + 124 320720 Ge-72 1.55610E-11 2.16900E-07 32072.82c + 125 320730 Ge-73 3.82380E-10 3.94070E-07 32073.82c + 126 320731 Ge-73m 8.84140E-11 3.87900E-07 320731 + 127 320740 Ge-74 1.15010E-08 7.16320E-07 32074.82c + 128 320750 Ge-75 1.32390E-08 1.30130E-06 320750 + 129 320751 Ge-75m 8.66010E-08 1.34660E-07 320751 + 130 320760 Ge-76 8.59150E-07 2.35940E-06 32076.82c + 131 320770 Ge-77 2.00990E-06 2.41640E-06 320770 + 132 320771 Ge-77m 3.07260E-07 2.13920E-06 320771 + 133 320780 Ge-78 6.11910E-06 6.94630E-06 320780 + 134 320790 Ge-79 1.44920E-06 2.29640E-06 320790 + 135 320791 Ge-79m 9.47980E-06 9.48050E-06 320791 + 136 320800 Ge-80 2.28360E-05 2.29250E-05 320800 + 137 320810 Ge-81 1.75800E-06 1.76580E-06 320810 + 138 320811 Ge-81m 4.06490E-07 4.09770E-07 320811 + 139 320820 Ge-82 1.02210E-06 1.02250E-06 320820 + 140 320830 Ge-83 1.59600E-07 1.59620E-07 320830 + 141 320840 Ge-84 1.68060E-08 1.68060E-08 320840 + 142 320850 Ge-85 5.34410E-10 5.34410E-10 320850 + 143 330740 As-74 6.02040E-12 6.02040E-12 330740 + 144 330750 As-75 9.62530E-11 1.30180E-06 33075.82c + 145 330751 As-75m 3.14910E-10 3.55310E-10 330751 + 146 330760 As-76 8.93950E-09 8.93950E-09 330760 + 147 330770 As-77 1.64380E-07 4.31350E-06 330770 + 148 330780 As-78 9.15760E-07 7.86200E-06 330780 + 149 330790 As-79 3.64280E-06 1.50400E-05 330790 + 150 330800 As-80 3.80550E-06 2.67310E-05 330800 + 151 330810 As-81 2.49140E-05 2.70850E-05 330810 + 152 330820 As-82 5.48500E-06 6.50750E-06 330820 + 153 330821 As-82m 1.65520E-05 1.65520E-05 330821 + 154 330830 As-83 1.93320E-05 1.94930E-05 330830 + 155 330840 As-84 3.91970E-06 3.92720E-06 330840 + 156 330841 As-84m 3.91970E-06 3.92720E-06 330841 + 157 330850 As-85 1.77370E-06 1.77420E-06 330850 + 158 330860 As-86 1.89230E-07 1.89230E-07 330860 + 159 330870 As-87 1.45780E-08 1.45780E-08 330870 + 160 330880 As-88 3.30210E-10 3.30210E-10 330880 + 161 340760 Se-76 5.47260E-12 8.94500E-09 34076.82c + 162 340770 Se-77 3.68010E-11 4.31380E-06 34077.82c + 163 340771 Se-77m 2.40730E-10 2.40730E-10 340771 + 164 340780 Se-78 1.18200E-08 7.87380E-06 34078.82c + 165 340790 Se-79 1.73900E-07 1.52330E-05 34079.82c + 166 340791 Se-79m 2.65850E-08 1.47110E-05 340791 + 167 340800 Se-80 3.80530E-06 3.05370E-05 34080.82c + 168 340810 Se-81 9.43750E-07 3.41990E-05 340810 + 169 340811 Se-81m 6.17360E-06 7.14590E-06 340811 + 170 340820 Se-82 5.13990E-05 7.44590E-05 34082.82c + 171 340830 Se-83 1.09880E-04 1.16910E-04 340830 + 172 340831 Se-83m 2.54080E-05 3.78890E-05 340831 + 173 340840 Se-84 2.00050E-04 2.08280E-04 340840 + 174 340850 Se-85 1.67070E-04 1.68520E-04 340850 + 175 340860 Se-86 1.25330E-04 1.25460E-04 340860 + 176 340870 Se-87 4.81130E-05 4.81250E-05 340870 + 177 340880 Se-88 9.22950E-06 9.22980E-06 340880 + 178 340890 Se-89 1.86090E-07 1.86090E-07 340890 + 179 340900 Se-90 8.13220E-09 8.13220E-09 340900 + 180 350780 Br-78 1.33900E-12 1.33900E-12 350780 + 181 350790 Br-79 4.42240E-11 8.42700E-09 35079.82c + 182 350791 Br-79m 1.44690E-10 1.44690E-10 350791 + 183 350800 Br-80 2.03220E-09 8.16470E-09 350800 + 184 350801 Br-80m 6.13250E-09 6.13250E-09 350801 + 185 350810 Br-81 1.62870E-07 3.43660E-05 35081.82c + 186 350820 Br-82 1.57550E-06 2.23200E-06 350820 + 187 350821 Br-82m 6.72630E-07 6.72630E-07 350821 + 188 350830 Br-83 1.93220E-05 1.74120E-04 350830 + 189 350840 Br-84 4.11220E-05 2.49410E-04 350840 + 190 350841 Br-84m 4.11220E-05 4.11220E-05 350841 + 191 350850 Br-85 2.61940E-04 4.30460E-04 350850 + 192 350860 Br-86 4.59570E-04 5.85030E-04 350860 + 193 350870 Br-87 5.62380E-04 6.10600E-04 350870 + 194 350880 Br-88 3.80610E-04 3.89760E-04 350880 + 195 350890 Br-89 2.03390E-04 2.03560E-04 350890 + 196 350900 Br-90 4.73780E-05 4.73860E-05 350900 + 197 350910 Br-91 1.83050E-06 1.83050E-06 350910 + 198 350920 Br-92 6.02220E-08 6.02220E-08 350920 + 199 350930 Br-93 2.25980E-09 2.25980E-09 350930 + 200 360800 Kr-80 1.14100E-12 7.48820E-09 36080.82c + 201 360810 Kr-81 5.33100E-11 6.14600E-11 360810 + 202 360811 Kr-81m 8.14960E-12 8.14960E-12 360811 + 203 360820 Kr-82 6.81200E-09 2.25490E-06 36082.82c + 204 360830 Kr-83 1.96180E-07 1.74360E-04 36083.82c + 205 360831 Kr-83m 4.53610E-08 1.74010E-04 360831 + 206 360840 Kr-84 1.17550E-05 3.02290E-04 36084.82c + 207 360850 Kr-85 6.12120E-05 1.56910E-04 36085.82c + 208 360851 Kr-85m 1.41540E-05 4.43910E-04 360851 + 209 360860 Kr-86 5.31670E-04 1.13200E-03 36086.82c + 210 360870 Kr-87 1.26180E-03 1.88320E-03 360870 + 211 360880 Kr-88 2.58470E-03 2.97710E-03 360880 + 212 360890 Kr-89 3.06250E-03 3.24900E-03 360890 + 213 360900 Kr-90 2.43010E-03 2.46620E-03 360900 + 214 360910 Kr-91 1.14730E-03 1.14880E-03 360910 + 215 360920 Kr-92 3.85330E-04 3.85370E-04 360920 + 216 360930 Kr-93 1.00640E-04 1.00640E-04 360930 + 217 360940 Kr-94 1.91650E-05 1.91650E-05 360940 + 218 360950 Kr-95 2.52060E-08 2.52060E-08 360950 + 219 370830 Rb-83 1.42200E-11 4.85480E-11 370830 + 220 370831 Rb-83m 3.43280E-11 3.43280E-11 370831 + 221 370840 Rb-84 1.19340E-09 3.34000E-09 370840 + 222 370841 Rb-84m 2.14660E-09 2.14660E-09 370841 + 223 370850 Rb-85 1.93970E-07 5.06020E-04 37085.82c + 224 370860 Rb-86 1.48930E-06 4.16820E-06 37086.82c + 225 370861 Rb-86m 2.67890E-06 2.67890E-06 370861 + 226 370870 Rb-87 9.99620E-05 1.98310E-03 37087.82c + 227 370880 Rb-88 5.05820E-04 3.48290E-03 370880 + 228 370890 Rb-89 1.42260E-03 4.67160E-03 370890 + 229 370900 Rb-90 2.84120E-04 2.50170E-03 370900 + 230 370901 Rb-90m 2.52340E-03 2.84600E-03 370901 + 231 370910 Rb-91 4.17750E-03 5.32630E-03 370910 + 232 370920 Rb-92 3.14610E-03 3.53150E-03 370920 + 233 370930 Rb-93 2.80840E-03 2.90920E-03 370930 + 234 370940 Rb-94 1.06170E-03 1.08070E-03 370940 + 235 370950 Rb-95 3.54200E-04 3.54220E-04 370950 + 236 370960 Rb-96 1.58140E-05 2.37200E-05 370960 + 237 370961 Rb-96m 1.58140E-05 1.58140E-05 370961 + 238 370970 Rb-97 2.59590E-07 2.59590E-07 370970 + 239 370980 Rb-98 1.97580E-09 1.97580E-09 370980 + 240 370981 Rb-98m 1.97580E-09 1.97580E-09 370981 + 241 380850 Sr-85 1.17310E-11 1.40800E-11 380850 + 242 380851 Sr-85m 2.71260E-12 2.71260E-12 380851 + 243 380860 Sr-86 3.19460E-09 4.17120E-06 38086.82c + 244 380870 Sr-87 3.54800E-06 4.36590E-06 38087.82c + 245 380871 Sr-87m 8.20390E-07 8.20390E-07 380871 + 246 380880 Sr-88 3.68380E-05 3.51970E-03 38088.82c + 247 380890 Sr-89 2.42280E-04 4.91390E-03 38089.82c + 248 380900 Sr-90 1.48900E-03 6.76270E-03 38090.82c + 249 380910 Sr-91 3.51420E-03 8.84050E-03 380910 + 250 380920 Sr-92 7.60180E-03 1.11740E-02 380920 + 251 380930 Sr-93 1.21060E-02 1.50840E-02 380930 + 252 380940 Sr-94 1.46260E-02 1.56280E-02 380940 + 253 380950 Sr-95 9.77040E-03 1.00970E-02 380950 + 254 380960 Sr-96 5.12310E-03 5.15160E-03 380960 + 255 380970 Sr-97 1.62810E-03 1.62830E-03 380970 + 256 380980 Sr-98 4.32540E-04 4.32540E-04 380980 + 257 380990 Sr-99 3.64420E-05 3.64420E-05 380990 + 258 381000 Sr-100 5.76020E-08 5.76020E-08 381000 + 259 390880 Y-88 5.22780E-10 9.08070E-10 390880 + 260 390881 Y-88m 3.85290E-10 3.85290E-10 390881 + 261 390890 Y-89 1.47360E-08 4.91400E-03 39089.82c + 262 390891 Y-89m 6.37290E-08 5.37380E-07 390891 + 263 390900 Y-90 1.95450E-06 6.76740E-03 39090.82c + 264 390901 Y-90m 2.77340E-06 2.77340E-06 390901 + 265 390910 Y-91 2.97360E-05 8.99880E-03 39091.82c + 266 390911 Y-91m 1.28600E-04 5.32990E-03 390911 + 267 390920 Y-92 5.52990E-04 1.17270E-02 390920 + 268 390930 Y-93 3.79000E-04 1.79420E-02 390930 + 269 390931 Y-93m 2.47920E-03 6.25380E-03 390931 + 270 390940 Y-94 6.98200E-03 2.26100E-02 390940 + 271 390950 Y-95 1.50370E-02 2.51340E-02 390950 + 272 390960 Y-96 5.76220E-03 1.09140E-02 390960 + 273 390961 Y-96m 1.03650E-02 1.03650E-02 390961 + 274 390970 Y-97 2.64950E-03 4.11330E-03 390970 + 275 390971 Y-97m 9.03050E-03 1.12140E-02 390971 + 276 390972 Y-97m 2.42660E-03 2.42660E-03 390972 + 277 390980 Y-98 1.29460E-03 1.72710E-03 390980 + 278 390981 Y-98m 5.44460E-03 5.44460E-03 390981 + 279 390990 Y-99 2.92320E-03 2.95960E-03 390990 + 280 391000 Y-100 3.58700E-04 3.58750E-04 391000 + 281 391001 Y-100m 3.58700E-04 3.58700E-04 391001 + 282 391010 Y-101 1.61530E-04 1.61530E-04 391010 + 283 391020 Y-102 1.52720E-07 1.52720E-07 391020 + 284 391021 Y-102m 1.52720E-07 1.52720E-07 391021 + 285 391030 Y-103 7.48490E-09 7.48490E-09 391030 + 286 400900 Zr-90 4.88170E-11 6.76740E-03 40090.82c + 287 400901 Zr-90m 2.05300E-10 2.55230E-10 400901 + 288 400910 Zr-91 2.21940E-08 8.99880E-03 40091.82c + 289 400920 Zr-92 2.24420E-05 1.17490E-02 40092.82c + 290 400930 Zr-93 2.38460E-04 1.81800E-02 40093.82c + 291 400940 Zr-94 1.70080E-03 2.43110E-02 40094.82c + 292 400950 Zr-95 4.92530E-03 3.00600E-02 40095.82c + 293 400960 Zr-96 1.64090E-02 3.76970E-02 40096.82c + 294 400970 Zr-97 2.50220E-02 4.09390E-02 400970 + 295 400980 Zr-98 3.92780E-02 4.63080E-02 400980 + 296 400990 Zr-99 2.77740E-02 3.06870E-02 400990 + 297 401000 Zr-100 2.09120E-02 2.16260E-02 401000 + 298 401010 Zr-101 7.87670E-03 8.03820E-03 401010 + 299 401020 Zr-102 3.11350E-03 3.11380E-03 401020 + 300 401030 Zr-103 6.61540E-04 6.61550E-04 401030 + 301 401040 Zr-104 1.11360E-04 1.11360E-04 401040 + 302 401050 Zr-105 5.52380E-08 5.52380E-08 401050 + 303 410930 Nb-93 5.50650E-09 6.77970E-09 41093.82c + 304 410931 Nb-93m 1.27320E-09 1.27320E-09 410931 + 305 410940 Nb-94 1.95430E-07 3.32470E-07 41094.82c + 306 410941 Nb-94m 1.37730E-07 1.37730E-07 410941 + 307 410950 Nb-95 9.91290E-05 3.01620E-02 41095.82c + 308 410951 Nb-95m 2.29210E-05 3.47670E-04 410951 + 309 410960 Nb-96 5.83370E-04 5.83370E-04 410960 + 310 410970 Nb-97 2.39670E-03 4.38900E-02 410970 + 311 410971 Nb-97m 5.54180E-04 3.94660E-02 410971 + 312 410980 Nb-98 1.95390E-03 4.82620E-02 410980 + 313 410981 Nb-98m 5.89610E-03 5.89610E-03 410981 + 314 410990 Nb-99 1.52010E-02 3.48910E-02 410990 + 315 410991 Nb-99m 3.51490E-03 1.48070E-02 410991 + 316 411000 Nb-100 5.06430E-03 2.66900E-02 411000 + 317 411001 Nb-100m 2.12990E-02 2.12990E-02 411001 + 318 411010 Nb-101 3.35380E-02 4.15760E-02 411010 + 319 411020 Nb-102 1.10550E-02 1.41690E-02 411020 + 320 411021 Nb-102m 1.10550E-02 1.10550E-02 411021 + 321 411030 Nb-103 1.52860E-02 1.59470E-02 411030 + 322 411040 Nb-104 2.64090E-03 2.75230E-03 411040 + 323 411041 Nb-104m 2.64090E-03 2.64090E-03 411041 + 324 411050 Nb-105 1.69100E-03 1.69100E-03 411050 + 325 411060 Nb-106 1.69480E-04 1.69480E-04 411060 + 326 411070 Nb-107 2.56930E-07 2.56930E-07 411070 + 327 411080 Nb-108 2.00270E-09 2.00270E-09 411080 + 328 420950 Mo-95 8.69180E-10 3.01820E-02 42095.82c + 329 420960 Mo-96 1.58020E-05 5.99170E-04 42096.82c + 330 420970 Mo-97 1.10800E-04 4.40010E-02 42097.82c + 331 420980 Mo-98 1.03210E-03 5.51900E-02 42098.82c + 332 420990 Mo-99 3.49540E-03 5.28980E-02 42099.82c + 333 421000 Mo-100 1.32930E-02 6.12820E-02 42100.82c + 334 421010 Mo-101 2.49490E-02 6.65250E-02 421010 + 335 421020 Mo-102 4.58160E-02 7.10410E-02 421020 + 336 421030 Mo-103 4.86650E-02 6.46160E-02 421030 + 337 421040 Mo-104 4.94870E-02 5.49060E-02 421040 + 338 421050 Mo-105 2.85740E-02 3.02440E-02 421050 + 339 421060 Mo-106 1.13180E-02 1.14800E-02 421060 + 340 421070 Mo-107 2.64480E-03 2.64500E-03 421070 + 341 421080 Mo-108 5.08600E-04 5.08600E-04 421080 + 342 421090 Mo-109 6.77350E-05 6.77350E-05 421090 + 343 421100 Mo-110 1.53230E-08 1.53230E-08 421100 + 344 430980 Tc-98 1.84410E-08 1.84410E-08 430980 + 345 430990 Tc-99 1.47900E-05 5.29150E-02 43099.82c + 346 430991 Tc-99m 3.41980E-06 4.65850E-02 430991 + 347 431000 Tc-100 1.83740E-04 1.83740E-04 431000 + 348 431010 Tc-101 1.36260E-03 6.78880E-02 431010 + 349 431020 Tc-102 2.22860E-03 7.32690E-02 431020 + 350 431021 Tc-102m 2.22860E-03 2.22860E-03 431021 + 351 431030 Tc-103 1.47570E-02 7.93720E-02 431030 + 352 431040 Tc-104 2.43060E-02 7.92120E-02 431040 + 353 431050 Tc-105 4.32140E-02 7.34580E-02 431050 + 354 431060 Tc-106 3.20440E-02 4.35240E-02 431060 + 355 431070 Tc-107 2.46160E-02 2.72610E-02 431070 + 356 431080 Tc-108 9.80950E-03 1.03180E-02 431080 + 357 431090 Tc-109 2.98570E-03 3.05310E-03 431090 + 358 431100 Tc-110 7.03020E-04 7.03030E-04 431100 + 359 431110 Tc-111 1.20650E-04 1.20650E-04 431110 + 360 431120 Tc-112 2.67010E-08 2.67010E-08 431120 + 361 431130 Tc-113 1.55110E-10 1.55110E-10 431130 + 362 441000 Ru-100 4.60820E-09 1.83740E-04 44100.82c + 363 441010 Ru-101 1.07580E-05 6.78990E-02 44101.82c + 364 441020 Ru-102 3.16680E-04 7.58150E-02 44102.82c + 365 441030 Ru-103 3.04150E-04 8.04110E-02 44103.82c + 366 441031 Ru-103m 7.34250E-04 7.34250E-04 441031 + 367 441040 Ru-104 5.29230E-03 8.45040E-02 44104.82c + 368 441050 Ru-105 1.30460E-02 8.65040E-02 44105.82c + 369 441060 Ru-106 2.32160E-02 6.67400E-02 44106.82c + 370 441070 Ru-107 2.52550E-02 5.25160E-02 441070 + 371 441080 Ru-108 2.72210E-02 3.75420E-02 441080 + 372 441090 Ru-109 1.51760E-02 1.82270E-02 441090 + 373 441100 Ru-110 1.00240E-02 1.07270E-02 441100 + 374 441110 Ru-111 3.73700E-03 3.85760E-03 441110 + 375 441120 Ru-112 7.16540E-04 7.16570E-04 441120 + 376 441130 Ru-113 5.22200E-05 7.83300E-05 441130 + 377 441131 Ru-113m 5.22200E-05 5.22200E-05 441131 + 378 441140 Ru-114 3.71590E-08 3.71590E-08 441140 + 379 441150 Ru-115 7.89050E-11 7.89050E-11 441150 + 380 451030 Rh-103 5.29340E-09 8.04110E-02 45103.82c + 381 451031 Rh-103m 3.46270E-08 7.94480E-02 451031 + 382 451040 Rh-104 3.07840E-06 1.23560E-05 451040 + 383 451041 Rh-104m 9.28960E-06 9.28960E-06 451041 + 384 451050 Rh-105 2.15900E-04 8.67530E-02 45105.82c + 385 451051 Rh-105m 3.30040E-05 2.45900E-02 451051 + 386 451060 Rh-106 2.78900E-04 6.70190E-02 451060 + 387 451061 Rh-106m 6.53250E-04 6.53250E-04 451061 + 388 451070 Rh-107 2.66770E-03 5.51840E-02 451070 + 389 451080 Rh-108 1.22770E-03 3.87700E-02 451080 + 390 451081 Rh-108m 3.70480E-03 3.70480E-03 451081 + 391 451090 Rh-109 7.60710E-03 2.58340E-02 451090 + 392 451100 Rh-110 8.29830E-03 1.90250E-02 451100 + 393 451101 Rh-110m 2.21520E-04 2.21520E-04 451101 + 394 451110 Rh-111 8.04850E-03 1.19060E-02 451110 + 395 451120 Rh-112 2.51080E-03 3.22740E-03 451120 + 396 451121 Rh-112m 2.51080E-03 2.51080E-03 451121 + 397 451130 Rh-113 1.03810E-03 1.14250E-03 451130 + 398 451140 Rh-114 1.55700E-04 1.55740E-04 451140 + 399 451141 Rh-114m 1.55700E-04 1.55700E-04 451141 + 400 451150 Rh-115 3.58250E-07 3.58330E-07 451150 + 401 451160 Rh-116 2.66320E-09 2.66320E-09 451160 + 402 451161 Rh-116m 6.23800E-09 6.23800E-09 451161 + 403 451170 Rh-117 7.15980E-11 7.15980E-11 451170 + 404 451180 Rh-118 2.36790E-12 2.36790E-12 451180 + 405 461050 Pd-105 5.02170E-09 8.67530E-02 46105.82c + 406 461060 Pd-106 3.62640E-05 6.77080E-02 46106.82c + 407 461070 Pd-107 2.43130E-05 5.52540E-02 46107.82c + 408 461071 Pd-107m 4.56920E-05 4.56920E-05 461071 + 409 461080 Pd-108 2.63400E-04 4.27380E-02 46108.82c + 410 461090 Pd-109 2.40900E-04 2.65280E-02 461090 + 411 461091 Pd-109m 4.52740E-04 1.33700E-02 461091 + 412 461100 Pd-110 1.65050E-03 2.08970E-02 46110.82c + 413 461110 Pd-111 6.55490E-04 1.34480E-02 461110 + 414 461111 Pd-111m 1.23190E-03 1.27950E-03 461111 + 415 461120 Pd-112 2.67010E-03 8.40830E-03 461120 + 416 461130 Pd-113 3.51740E-04 2.34340E-03 461130 + 417 461131 Pd-113m 8.49160E-04 8.49160E-04 461131 + 418 461140 Pd-114 7.93180E-04 1.10460E-03 461140 + 419 461150 Pd-115 3.75530E-05 4.35100E-05 461150 + 420 461151 Pd-115m 7.05770E-05 7.06280E-05 461151 + 421 461160 Pd-116 3.76820E-05 3.76910E-05 461160 + 422 461170 Pd-117 4.45130E-08 1.28240E-07 461170 + 423 461171 Pd-117m 8.36570E-08 8.36570E-08 461171 + 424 461180 Pd-118 3.26450E-08 3.26470E-08 461180 + 425 461190 Pd-119 1.06110E-09 1.06110E-09 461190 + 426 461200 Pd-120 3.33930E-11 3.33930E-11 461200 + 427 461220 Pd-122 1.40380E-08 1.40380E-08 461220 + 428 461230 Pd-123 1.90840E-10 1.90840E-10 461230 + 429 461240 Pd-124 2.27590E-11 2.27590E-11 461240 + 430 471080 Ag-108 5.39280E-09 6.49170E-09 471080 + 431 471081 Ag-108m 1.26310E-08 1.26310E-08 471081 + 432 471090 Ag-109 4.48290E-06 2.65610E-02 47109.82c + 433 471091 Ag-109m 2.93250E-05 2.65440E-02 471091 + 434 471100 Ag-110 4.66540E-06 4.81400E-06 471100 + 435 471101 Ag-110m 1.09280E-05 1.09280E-05 47510.82c + 436 471110 Ag-111 1.58910E-05 1.38450E-02 47111.82c + 437 471111 Ag-111m 1.03950E-04 1.37030E-02 471111 + 438 471120 Ag-112 1.04670E-04 8.51290E-03 471120 + 439 471130 Ag-113 2.06260E-05 1.64260E-03 471130 + 440 471131 Ag-113m 1.34920E-04 2.37890E-03 471131 + 441 471140 Ag-114 2.95410E-05 1.25840E-03 471140 + 442 471141 Ag-114m 1.24240E-04 1.24240E-04 471141 + 443 471150 Ag-115 3.58100E-06 5.63750E-05 471150 + 444 471151 Ag-115m 2.34250E-05 1.00150E-04 471151 + 445 471160 Ag-116 1.69030E-05 5.69700E-05 471160 + 446 471161 Ag-116m 3.95920E-05 3.95920E-05 471161 + 447 471170 Ag-117 8.68970E-07 1.27800E-06 471170 + 448 471171 Ag-117m 5.68430E-06 5.74840E-06 471171 + 449 471180 Ag-118 7.99640E-07 2.20830E-06 471180 + 450 471181 Ag-118m 3.36300E-06 3.36760E-06 471181 + 451 471190 Ag-119 1.39750E-07 1.40280E-07 471190 + 452 471191 Ag-119m 9.14150E-07 9.14680E-07 471191 + 453 471200 Ag-120 3.83120E-08 5.84500E-08 471200 + 454 471201 Ag-120m 5.43640E-08 5.43800E-08 471201 + 455 471210 Ag-121 4.39080E-09 4.39080E-09 471210 + 456 471220 Ag-122 1.08950E-06 1.10350E-06 471220 + 457 471221 Ag-122m 9.81400E-07 9.81400E-07 471221 + 458 471230 Ag-123 2.23340E-07 2.23530E-07 471230 + 459 471240 Ag-124 4.08440E-08 5.92630E-08 471240 + 460 471241 Ag-124m 3.67920E-08 3.67920E-08 471241 + 461 471250 Ag-125 2.37730E-08 2.37730E-08 471250 + 462 471260 Ag-126 1.45280E-09 1.45280E-09 471260 + 463 471270 Ag-127 1.05390E-10 1.05390E-10 471270 + 464 481100 Cd-110 1.53230E-09 1.55800E-05 48110.82c + 465 481110 Cd-111 1.24780E-08 1.39130E-02 48111.82c + 466 481111 Cd-111m 4.08240E-08 4.08240E-08 481111 + 467 481120 Cd-112 1.41590E-06 8.51440E-03 48112.82c + 468 481130 Cd-113 1.31490E-06 2.47200E-03 48113.82c + 469 481131 Cd-113m 4.30190E-06 3.27000E-05 481131 + 470 481140 Cd-114 3.49110E-05 1.29330E-03 48114.82c + 471 481150 Cd-115 6.31980E-06 1.36260E-04 481150 + 472 481151 Cd-115m 2.06760E-05 2.62280E-05 48515.82c + 473 481160 Cd-116 4.06920E-05 1.34880E-04 48116.82c + 474 481170 Cd-117 4.54130E-06 9.66800E-06 481170 + 475 481171 Cd-117m 1.48580E-05 1.64120E-05 481171 + 476 481180 Cd-118 2.49820E-05 2.91770E-05 481180 + 477 481190 Cd-119 6.86380E-06 7.84860E-06 481190 + 478 481191 Cd-119m 1.65700E-05 1.66400E-05 481191 + 479 481200 Cd-120 1.44870E-05 1.45800E-05 481200 + 480 481210 Cd-121 5.19340E-07 5.23270E-07 481210 + 481 481211 Cd-121m 1.25380E-06 1.25420E-06 481211 + 482 481220 Cd-122 2.39270E-05 2.60120E-05 481220 + 483 481230 Cd-123 1.68420E-06 1.86710E-06 481230 + 484 481231 Cd-123m 4.06580E-06 4.10650E-06 481231 + 485 481240 Cd-124 1.43720E-05 1.44500E-05 481240 + 486 481250 Cd-125 3.40090E-06 3.41280E-06 481250 + 487 481251 Cd-125m 8.21010E-06 8.22200E-06 481251 + 488 481260 Cd-126 5.73440E-06 5.73590E-06 481260 + 489 481270 Cd-127 1.01680E-06 1.01690E-06 481270 + 490 481280 Cd-128 8.46280E-08 8.46280E-08 481280 + 491 481290 Cd-129 7.44610E-10 7.44610E-10 481290 + 492 481291 Cd-129m 1.79760E-09 1.79760E-09 481291 + 493 491130 In-113 1.25980E-09 3.26560E-05 49113.82c + 494 491131 In-113m 2.91300E-10 2.91300E-10 491131 + 495 491140 In-114 6.66600E-09 2.60750E-08 491140 + 496 491141 In-114m 1.02170E-08 2.01130E-08 491141 + 497 491142 In-114m 9.89600E-09 9.89600E-09 491142 + 498 491150 In-115 8.65800E-08 1.55780E-04 49115.82c + 499 491151 In-115m 2.00190E-08 1.36280E-04 491151 + 500 491160 In-116 1.49430E-07 1.49430E-07 491160 + 501 491161 In-116m 2.29030E-07 4.50860E-07 491161 + 502 491162 In-116m 2.21830E-07 2.21830E-07 491162 + 503 491170 In-117 9.11130E-07 2.22720E-05 491170 + 504 491171 In-117m 2.10670E-07 9.32080E-06 491171 + 505 491180 In-118 6.21600E-06 3.53930E-05 491180 + 506 491181 In-118m 9.52760E-06 1.86260E-05 491181 + 507 491182 In-118m 9.22790E-06 9.22790E-06 491182 + 508 491190 In-119 2.18490E-05 3.98980E-05 491190 + 509 491191 In-119m 5.05200E-06 1.21730E-05 491191 + 510 491200 In-120 1.07590E-05 2.53380E-05 491200 + 511 491201 In-120m 1.07590E-05 1.07590E-05 491201 + 512 491202 In-120m 1.07590E-05 1.07590E-05 491202 + 513 491210 In-121 3.18220E-05 3.33450E-05 491210 + 514 491211 In-121m 7.35800E-06 7.70500E-06 491211 + 515 491220 In-122 5.91000E-06 3.19220E-05 491220 + 516 491221 In-122m 4.19300E-06 4.19300E-06 491221 + 517 491222 In-122m 4.19300E-06 4.19300E-06 491222 + 518 491230 In-123 6.08780E-06 1.07230E-05 491230 + 519 491231 In-123m 1.40760E-06 2.74650E-06 491231 + 520 491240 In-124 1.18340E-05 2.62840E-05 491240 + 521 491241 In-124m 1.06600E-05 1.06600E-05 491241 + 522 491250 In-125 6.47530E-05 7.46080E-05 491250 + 523 491251 In-125m 1.49720E-05 1.67520E-05 491251 + 524 491260 In-126 8.79640E-05 9.37000E-05 491260 + 525 491261 In-126m 7.92360E-05 7.92360E-05 491261 + 526 491270 In-127 1.88020E-04 1.88020E-04 491270 + 527 491271 In-127m 4.34760E-05 4.44930E-05 491271 + 528 491280 In-128 2.58010E-05 3.63890E-05 491280 + 529 491281 In-128m 1.05030E-05 1.05870E-05 491281 + 530 491282 In-128m 3.27020E-05 3.27020E-05 491282 + 531 491290 In-129 7.91110E-05 7.91130E-05 491290 + 532 491291 In-129m 1.82920E-05 1.82930E-05 491291 + 533 491300 In-130 7.91580E-06 7.91580E-06 491300 + 534 491301 In-130m 8.84120E-06 8.84120E-06 491301 + 535 491302 In-130m 1.50430E-05 1.50430E-05 491302 + 536 491310 In-131 1.88050E-08 1.89960E-08 491310 + 537 491311 In-131m 1.88050E-08 1.88050E-08 491311 + 538 491312 In-131m 1.88050E-08 1.88050E-08 491312 + 539 491320 In-132 1.29790E-09 1.29790E-09 491320 + 540 501150 Sn-115 1.39240E-11 6.81430E-06 50115.82c + 541 501160 Sn-116 5.43410E-10 6.00820E-07 50116.82c + 542 501170 Sn-117 6.44220E-10 2.72050E-05 50117.82c + 543 501171 Sn-117m 2.10770E-09 7.79890E-08 501171 + 544 501180 Sn-118 1.58820E-07 5.43080E-05 50118.82c + 545 501190 Sn-119 2.76450E-07 5.25720E-05 50119.82c + 546 501191 Sn-119m 9.04450E-07 3.69490E-05 501191 + 547 501200 Sn-120 8.96810E-06 5.58560E-05 50120.82c + 548 501210 Sn-121 3.88830E-06 5.12840E-05 501210 + 549 501211 Sn-121m 9.38670E-06 1.31640E-05 501211 + 550 501220 Sn-122 1.42930E-05 5.46010E-05 50122.82c + 551 501230 Sn-123 9.75440E-06 1.05720E-05 50123.82c + 552 501231 Sn-123m 4.04060E-06 1.66920E-05 501231 + 553 501240 Sn-124 4.49660E-05 8.19100E-05 50124.82c + 554 501250 Sn-125 1.50140E-04 1.62740E-04 50125.82c + 555 501251 Sn-125m 6.21910E-05 1.40950E-04 501251 + 556 501260 Sn-126 6.95610E-04 8.68850E-04 50126.82c + 557 501270 Sn-127 1.53420E-03 1.60750E-03 501270 + 558 501271 Sn-127m 6.35500E-04 7.94430E-04 501271 + 559 501280 Sn-128 8.52780E-04 2.91930E-03 501280 + 560 501281 Sn-128m 1.99740E-03 2.03010E-03 501281 + 561 501290 Sn-129 6.32840E-04 7.21850E-04 501290 + 562 501291 Sn-129m 1.52780E-03 1.53620E-03 501291 + 563 501300 Sn-130 5.06190E-04 5.26860E-04 501300 + 564 501301 Sn-130m 1.18560E-03 1.19670E-03 501301 + 565 501310 Sn-131 1.55290E-04 1.55320E-04 501310 + 566 501311 Sn-131m 3.74880E-04 3.74900E-04 501311 + 567 501320 Sn-132 1.11010E-04 1.11010E-04 501320 + 568 501330 Sn-133 4.24810E-07 4.24810E-07 501330 + 569 501340 Sn-134 1.21130E-08 1.21130E-08 501340 + 570 511180 Sb-118 1.12570E-11 1.12570E-11 511180 + 571 511181 Sb-118m 1.59740E-11 1.59740E-11 511181 + 572 511190 Sb-119 1.23260E-09 1.62440E-09 511190 + 573 511191 Sb-119m 3.91810E-10 3.91810E-10 511191 + 574 511200 Sb-120 1.34700E-08 1.34700E-08 511200 + 575 511201 Sb-120m 1.91130E-08 1.91130E-08 511201 + 576 511210 Sb-121 3.50030E-07 5.45830E-05 51121.82c + 577 511220 Sb-122 1.07990E-11 2.30400E-11 511220 + 578 511221 Sb-122m 1.22410E-11 1.22410E-11 511221 + 579 511230 Sb-123 6.15710E-10 2.72650E-05 51123.82c + 580 511240 Sb-124 1.82830E-08 4.29480E-08 51124.82c + 581 511241 Sb-124m 1.39800E-08 3.28870E-08 511241 + 582 511242 Sb-124m 1.89070E-08 1.89070E-08 511242 + 583 511250 Sb-125 2.65260E-05 3.30220E-04 51125.82c + 584 511260 Sb-126 4.09440E-05 5.07260E-05 51126.82c + 585 511261 Sb-126m 3.02730E-05 6.98660E-05 511261 + 586 511262 Sb-126m 3.95920E-05 3.95920E-05 511262 + 587 511270 Sb-127 8.75240E-04 3.27710E-03 511270 + 588 511280 Sb-128 1.01980E-03 4.00180E-03 511280 + 589 511281 Sb-128m 1.74020E-03 1.74020E-03 511281 + 590 511290 Sb-129 4.50170E-03 6.51950E-03 511290 + 591 511291 Sb-129m 2.75090E-03 3.51900E-03 511291 + 592 511300 Sb-130 4.83980E-03 5.96500E-03 511300 + 593 511301 Sb-130m 4.83980E-03 5.43810E-03 511301 + 594 511310 Sb-131 1.14040E-02 1.19340E-02 511310 + 595 511320 Sb-132 3.04700E-03 3.15800E-03 511320 + 596 511321 Sb-132m 2.24570E-03 2.24570E-03 511321 + 597 511330 Sb-133 1.63340E-03 1.63380E-03 511330 + 598 511340 Sb-134 8.40000E-05 8.40100E-05 511340 + 599 511341 Sb-134m 1.96750E-04 1.96750E-04 511341 + 600 511350 Sb-135 2.46520E-05 2.46520E-05 511350 + 601 511360 Sb-136 8.92090E-08 8.92090E-08 511360 + 602 521200 Te-120 6.67850E-12 6.67850E-12 52120.82c + 603 521210 Te-121 4.54370E-11 1.77290E-10 521210 + 604 521211 Te-121m 1.48650E-10 1.48650E-10 521211 + 605 521240 Te-124 1.26430E-11 5.11830E-08 52124.82c + 606 521250 Te-125 5.89530E-10 3.30220E-04 52125.82c + 607 521251 Te-125m 1.92880E-09 7.38930E-05 521251 + 608 521260 Te-126 3.01080E-07 1.11110E-04 52126.82c + 609 521270 Te-127 4.20370E-05 3.40530E-03 521270 + 610 521271 Te-127m 1.01480E-04 6.41540E-04 52527.82c + 611 521280 Te-128 4.78840E-04 6.15820E-03 52128.82c + 612 521290 Te-129 8.51810E-04 1.01770E-02 521290 + 613 521291 Te-129m 2.05640E-03 6.05940E-03 52529.82c + 614 521300 Te-130 1.19860E-02 2.33890E-02 52130.82c + 615 521310 Te-131 7.06680E-03 2.18290E-02 521310 + 616 521311 Te-131m 1.70600E-02 1.80160E-02 521311 + 617 521320 Te-132 3.73790E-02 4.27830E-02 52132.82c + 618 521330 Te-133 7.41450E-03 1.19480E-02 521330 + 619 521331 Te-133m 1.78990E-02 1.81820E-02 521331 + 620 521340 Te-134 1.74520E-02 1.77360E-02 521340 + 621 521350 Te-135 4.52470E-03 4.54550E-03 521350 + 622 521360 Te-136 7.24080E-04 7.24150E-04 521360 + 623 521370 Te-137 1.15790E-04 1.15790E-04 521370 + 624 521380 Te-138 5.86070E-07 5.86070E-07 521380 + 625 521390 Te-139 5.22010E-09 5.22010E-09 521390 + 626 531260 I-126 2.30590E-11 2.30590E-11 531260 + 627 531270 I-127 4.84820E-09 3.42070E-03 53127.82c + 628 531280 I-128 2.71090E-07 2.71090E-07 531280 + 629 531290 I-129 3.23460E-05 1.24510E-02 53129.82c + 630 531300 I-130 3.33790E-04 4.53500E-04 53130.82c + 631 531301 I-130m 1.42510E-04 1.42510E-04 531301 + 632 531310 I-131 2.96230E-03 3.90240E-02 53131.82c + 633 531320 I-132 6.16000E-03 5.28470E-02 531320 + 634 531321 I-132m 4.54000E-03 4.54000E-03 531321 + 635 531330 I-133 1.45620E-02 5.04080E-02 531330 + 636 531331 I-133m 8.89840E-03 8.89840E-03 531331 + 637 531340 I-134 2.05530E-02 5.30890E-02 531340 + 638 531341 I-134m 1.51480E-02 1.51480E-02 531341 + 639 531350 I-135 5.55770E-02 6.01230E-02 53135.82c + 640 531360 I-136 6.34990E-03 7.07580E-03 531360 + 641 531361 I-136m 1.48730E-02 1.48750E-02 531361 + 642 531370 I-137 7.40560E-03 7.51800E-03 531370 + 643 531380 I-138 8.27460E-04 8.28010E-04 531380 + 644 531390 I-139 1.94350E-04 1.94360E-04 531390 + 645 531400 I-140 1.83630E-05 1.83630E-05 531400 + 646 531410 I-141 3.47140E-08 3.47140E-08 531410 + 647 541290 Xe-129 5.95130E-10 2.54220E-09 54129.82c + 648 541291 Xe-129m 1.94710E-09 1.94710E-09 541291 + 649 541300 Xe-130 1.58810E-05 4.92180E-04 54130.82c + 650 541310 Xe-131 1.74720E-05 3.90830E-02 54131.82c + 651 541311 Xe-131m 4.21790E-05 4.66050E-04 541311 + 652 541320 Xe-132 2.98160E-04 5.41190E-02 54132.82c + 653 541321 Xe-132m 3.37980E-04 3.37980E-04 541321 + 654 541330 Xe-133 8.38660E-04 5.32710E-02 54133.82c + 655 541331 Xe-133m 2.02460E-03 3.45940E-03 541331 + 656 541340 Xe-134 3.46770E-03 6.50280E-02 54134.82c + 657 541341 Xe-134m 8.12230E-03 8.47070E-03 541341 + 658 541350 Xe-135 1.10440E-02 9.76090E-02 54135.82c + 659 541351 Xe-135m 2.66620E-02 3.65870E-02 541351 + 660 541360 Xe-136 8.16970E-02 1.04140E-01 54136.82c + 661 541370 Xe-137 5.21880E-02 5.92610E-02 541370 + 662 541380 Xe-138 3.09130E-02 3.17160E-02 541380 + 663 541390 Xe-139 8.96300E-03 9.14000E-03 541390 + 664 541400 Xe-140 2.71660E-03 2.73330E-03 541400 + 665 541410 Xe-141 5.68590E-04 5.68620E-04 541410 + 666 541420 Xe-142 5.86620E-05 5.86620E-05 541420 + 667 541430 Xe-143 1.65000E-07 1.65000E-07 541430 + 668 541440 Xe-144 3.44650E-09 3.44650E-09 541440 + 669 551310 Cs-131 1.22650E-09 1.22650E-09 551310 + 670 551320 Cs-132 8.04740E-08 8.04740E-08 551320 + 671 551330 Cs-133 1.08890E-05 5.32820E-02 55133.82c + 672 551340 Cs-134 6.83760E-05 1.18770E-04 55134.82c + 673 551341 Cs-134m 5.03940E-05 5.03940E-05 551341 + 674 551350 Cs-135 7.18210E-04 9.89860E-02 55135.82c + 675 551351 Cs-135m 4.38890E-04 4.38890E-04 551351 + 676 551360 Cs-136 4.05020E-03 5.23700E-03 55136.82c + 677 551361 Cs-136m 2.37360E-03 2.37360E-03 551361 + 678 551370 Cs-137 2.69280E-02 8.61890E-02 55137.82c + 679 551380 Cs-138 1.38340E-02 6.14500E-02 551380 + 680 551381 Cs-138m 1.96290E-02 1.96290E-02 551381 + 681 551390 Cs-139 3.31370E-02 4.22770E-02 551390 + 682 551400 Cs-140 1.74350E-02 2.01680E-02 551400 + 683 551410 Cs-141 1.13640E-02 1.19330E-02 551410 + 684 551420 Cs-142 3.52010E-03 3.57850E-03 551420 + 685 551430 Cs-143 9.28420E-04 9.28580E-04 551430 + 686 551440 Cs-144 8.19150E-05 1.22880E-04 551440 + 687 551441 Cs-144m 8.19150E-05 8.19150E-05 551441 + 688 551450 Cs-145 1.32360E-05 1.32360E-05 551450 + 689 551460 Cs-146 8.77010E-09 8.77010E-09 551460 + 690 561340 Ba-134 2.18040E-08 1.18790E-04 56134.82c + 691 561350 Ba-135 3.96120E-07 1.35240E-06 56135.82c + 692 561351 Ba-135m 9.56280E-07 9.56280E-07 561351 + 693 561360 Ba-136 4.40750E-05 6.57110E-03 56136.82c + 694 561361 Ba-136m 1.03230E-04 1.03230E-04 561361 + 695 561370 Ba-137 4.46150E-04 8.77120E-02 56137.82c + 696 561371 Ba-137m 1.07700E-03 8.24390E-02 561371 + 697 561380 Ba-138 9.93660E-03 7.51160E-02 56138.82c + 698 561390 Ba-139 1.81430E-02 6.04200E-02 561390 + 699 561400 Ba-140 3.21340E-02 5.23030E-02 56140.82c + 700 561410 Ba-141 2.73290E-02 3.92620E-02 561410 + 701 561420 Ba-142 3.30830E-02 3.66770E-02 561420 + 702 561430 Ba-143 1.69470E-02 1.78640E-02 561430 + 703 561440 Ba-144 6.88240E-03 7.04420E-03 561440 + 704 561450 Ba-145 1.58300E-03 1.59430E-03 561450 + 705 561460 Ba-146 3.13250E-04 3.13260E-04 561460 + 706 561470 Ba-147 2.21060E-05 2.21060E-05 561470 + 707 561480 Ba-148 4.18100E-08 4.18100E-08 561480 + 708 561490 Ba-149 3.75490E-10 3.75490E-10 561490 + 709 571360 La-136 1.31180E-09 2.62370E-09 571360 + 710 571361 La-136m 1.31180E-09 1.31180E-09 571361 + 711 571370 La-137 2.29190E-07 2.29190E-07 571370 + 712 571380 La-138 2.20300E-05 2.20300E-05 57138.82c + 713 571390 La-139 4.58940E-04 6.08790E-02 57139.82c + 714 571400 La-140 1.76720E-03 5.40700E-02 57140.82c + 715 571410 La-141 5.37740E-03 4.46390E-02 571410 + 716 571420 La-142 7.69120E-03 4.43680E-02 571420 + 717 571430 La-143 1.65010E-02 3.43650E-02 571430 + 718 571440 La-144 1.55880E-02 2.26320E-02 571440 + 719 571450 La-145 1.22910E-02 1.38850E-02 571450 + 720 571460 La-146 1.70040E-03 2.01370E-03 571460 + 721 571461 La-146m 3.05870E-03 3.05870E-03 571461 + 722 571470 La-147 1.57170E-03 1.59380E-03 571470 + 723 571480 La-148 2.82970E-04 2.83010E-04 571480 + 724 571490 La-149 5.28190E-05 5.28190E-05 571490 + 725 571500 La-150 7.35380E-06 7.35380E-06 571500 + 726 571510 La-151 1.57820E-09 1.57820E-09 571510 + 727 581390 Ce-139 6.62570E-09 2.26210E-08 581390 + 728 581391 Ce-139m 1.59950E-08 1.59950E-08 581391 + 729 581400 Ce-140 7.33680E-05 5.41430E-02 58140.82c + 730 581410 Ce-141 2.82560E-04 4.49220E-02 58141.82c + 731 581420 Ce-142 1.39250E-03 4.57610E-02 58142.82c + 732 581430 Ce-143 2.77120E-03 3.71370E-02 58143.82c + 733 581440 Ce-144 8.08660E-03 3.07190E-02 58144.82c + 734 581450 Ce-145 1.04870E-02 2.43720E-02 581450 + 735 581460 Ce-146 1.39440E-02 1.90160E-02 581460 + 736 581470 Ce-147 1.03880E-02 1.19820E-02 581470 + 737 581480 Ce-148 6.46520E-03 6.74900E-03 581480 + 738 581490 Ce-149 2.23460E-03 2.28690E-03 581490 + 739 581500 Ce-150 3.69130E-04 3.76290E-04 581500 + 740 581510 Ce-151 1.00800E-04 1.00800E-04 581510 + 741 581520 Ce-152 1.66270E-05 1.66270E-05 581520 + 742 581530 Ce-153 5.71300E-09 5.71300E-09 581530 + 743 581540 Ce-154 5.66460E-11 5.66460E-11 581540 + 744 591410 Pr-141 2.77710E-09 4.49220E-02 59141.82c + 745 591420 Pr-142 3.55750E-08 1.18900E-07 59142.82c + 746 591421 Pr-142m 8.33250E-08 8.33250E-08 591421 + 747 591430 Pr-143 1.59030E-05 3.71520E-02 59143.82c + 748 591440 Pr-144 8.60100E-06 3.08030E-02 591440 + 749 591441 Pr-144m 7.63890E-05 5.00290E-04 591441 + 750 591450 Pr-145 6.24510E-04 2.49970E-02 591450 + 751 591460 Pr-146 1.33860E-03 2.03550E-02 591460 + 752 591470 Pr-147 2.78980E-03 1.47720E-02 591470 + 753 591480 Pr-148 5.91230E-04 7.34020E-03 591480 + 754 591481 Pr-148m 2.48650E-03 2.48650E-03 591481 + 755 591490 Pr-149 4.06330E-03 6.35020E-03 591490 + 756 591500 Pr-150 2.65380E-03 3.03010E-03 591500 + 757 591510 Pr-151 1.24740E-03 1.34820E-03 591510 + 758 591520 Pr-152 3.93800E-04 4.10430E-04 591520 + 759 591530 Pr-153 1.15100E-04 1.15110E-04 591530 + 760 591540 Pr-154 1.50670E-05 1.50670E-05 591540 + 761 591550 Pr-155 1.38240E-08 1.38240E-08 591550 + 762 591560 Pr-156 1.20560E-10 1.20560E-10 591560 + 763 601440 Nd-144 1.95300E-08 3.08040E-02 60144.82c + 764 601450 Nd-145 6.60870E-06 2.50040E-02 60145.82c + 765 601460 Nd-146 5.77890E-05 2.04130E-02 60146.82c + 766 601470 Nd-147 2.14710E-04 1.49860E-02 60147.82c + 767 601480 Nd-148 6.57230E-04 1.04840E-02 60148.82c + 768 601490 Nd-149 6.96990E-04 7.04720E-03 601490 + 769 601500 Nd-150 1.13230E-03 4.16240E-03 60150.82c + 770 601510 Nd-151 2.01370E-03 3.36190E-03 601510 + 771 601520 Nd-152 2.10990E-03 2.52030E-03 601520 + 772 601530 Nd-153 1.21470E-03 1.32980E-03 601530 + 773 601540 Nd-154 4.16710E-04 4.31780E-04 601540 + 774 601550 Nd-155 9.90680E-05 9.90820E-05 601550 + 775 601560 Nd-156 3.45190E-05 3.45190E-05 601560 + 776 601570 Nd-157 2.47410E-08 2.47410E-08 601570 + 777 601580 Nd-158 2.19390E-10 2.19390E-10 601580 + 778 601590 Nd-159 3.08600E-12 3.08600E-12 601590 + 779 611460 Pm-146 9.74460E-10 9.74460E-10 611460 + 780 611470 Pm-147 6.64590E-08 1.49860E-02 61147.82c + 781 611480 Pm-148 3.34620E-07 3.73810E-07 61148.82c + 782 611481 Pm-148m 7.83770E-07 7.83770E-07 61548.82c + 783 611490 Pm-149 1.84920E-05 7.06570E-03 61149.82c + 784 611500 Pm-150 8.90900E-05 8.90900E-05 611500 + 785 611510 Pm-151 2.24310E-04 3.58620E-03 61151.82c + 786 611520 Pm-152 8.78450E-05 2.60820E-03 611520 + 787 611521 Pm-152m 1.75420E-04 1.75420E-04 611521 + 788 611522 Pm-152m 1.94030E-04 1.94030E-04 611522 + 789 611530 Pm-153 8.32040E-04 2.16180E-03 611530 + 790 611540 Pm-154 3.71650E-04 8.03430E-04 611540 + 791 611541 Pm-154m 3.71650E-04 3.71650E-04 611541 + 792 611550 Pm-155 4.37580E-04 5.36660E-04 611550 + 793 611560 Pm-156 1.46790E-04 1.81310E-04 611560 + 794 611570 Pm-157 1.73660E-05 1.73910E-05 611570 + 795 611580 Pm-158 3.43790E-07 3.44010E-07 611580 + 796 611590 Pm-159 3.59870E-08 3.59900E-08 611590 + 797 611600 Pm-160 3.14240E-10 3.14240E-10 611600 + 798 611610 Pm-161 4.48260E-12 4.48260E-12 611610 + 799 621490 Sm-149 4.50590E-09 7.06570E-03 62149.82c + 800 621500 Sm-150 1.81300E-07 8.92710E-05 62150.82c + 801 621510 Sm-151 1.33400E-05 3.59950E-03 62151.82c + 802 621520 Sm-152 4.94720E-05 3.02710E-03 62152.82c + 803 621530 Sm-153 2.91570E-05 2.26140E-03 62153.82c + 804 621531 Sm-153m 7.03890E-05 7.03890E-05 621531 + 805 621540 Sm-154 3.35830E-04 1.51090E-03 62154.82c + 806 621550 Sm-155 3.44570E-04 8.81230E-04 621550 + 807 621560 Sm-156 3.01250E-04 4.82560E-04 621560 + 808 621570 Sm-157 2.95230E-04 3.12620E-04 621570 + 809 621580 Sm-158 3.60370E-05 3.63810E-05 621580 + 810 621590 Sm-159 1.79650E-05 1.80010E-05 621590 + 811 621600 Sm-160 5.95600E-07 5.95910E-07 621600 + 812 621610 Sm-161 2.40550E-08 2.40600E-08 621610 + 813 621620 Sm-162 1.46490E-09 1.46490E-09 621620 + 814 621630 Sm-163 1.27170E-11 1.27170E-11 621630 + 815 631510 Eu-151 3.64200E-10 3.59950E-03 63151.82c + 816 631520 Eu-152 6.23920E-09 1.31980E-08 63152.82c + 817 631521 Eu-152m 1.48600E-09 1.48600E-09 631521 + 818 631522 Eu-152m 6.95880E-09 6.95880E-09 631522 + 819 631530 Eu-153 4.45290E-07 2.26180E-03 63153.82c + 820 631540 Eu-154 1.99050E-06 3.78350E-06 63154.82c + 821 631541 Eu-154m 1.79300E-06 1.79300E-06 631541 + 822 631550 Eu-155 8.23620E-06 8.89470E-04 63155.82c + 823 631560 Eu-156 2.58520E-05 5.08410E-04 63156.82c + 824 631570 Eu-157 3.47050E-05 3.47330E-04 63157.82c + 825 631580 Eu-158 4.50210E-05 8.14020E-05 631580 + 826 631590 Eu-159 6.28610E-05 8.08620E-05 631590 + 827 631600 Eu-160 1.74490E-05 1.80450E-05 631600 + 828 631610 Eu-161 3.35770E-06 3.38180E-06 631610 + 829 631620 Eu-162 5.41500E-07 5.42970E-07 631620 + 830 631630 Eu-163 3.85200E-08 3.85330E-08 631630 + 831 631640 Eu-164 1.12680E-09 1.12680E-09 631640 + 832 631650 Eu-165 2.69820E-11 2.69820E-11 631650 + 833 641540 Gd-154 1.86930E-09 3.78460E-06 64154.82c + 834 641550 Gd-155 1.03740E-08 8.89500E-04 64155.82c + 835 641551 Gd-155m 2.50440E-08 2.50440E-08 641551 + 836 641560 Gd-156 5.93170E-07 5.09000E-04 64156.82c + 837 641570 Gd-157 3.68010E-06 3.51010E-04 64157.82c + 838 641580 Gd-158 9.00460E-06 9.04210E-05 64158.82c + 839 641590 Gd-159 2.69290E-05 1.07790E-04 641590 + 840 641600 Gd-160 1.74450E-05 3.54900E-05 64160.82c + 841 641610 Gd-161 2.06480E-05 2.40300E-05 641610 + 842 641620 Gd-162 1.34760E-05 1.40190E-05 641620 + 843 641630 Gd-163 2.33150E-06 2.37000E-06 641630 + 844 641640 Gd-164 5.14100E-07 5.15230E-07 641640 + 845 641650 Gd-165 3.35630E-08 3.35900E-08 641650 + 846 641660 Gd-166 1.88680E-09 1.88680E-09 641660 + 847 641670 Gd-167 4.11610E-11 4.11610E-11 641670 + 848 651560 Tb-156 2.21530E-11 6.02690E-11 651560 + 849 651561 Tb-156m 3.20270E-11 3.20270E-11 651561 + 850 651562 Tb-156m 6.10040E-12 6.10040E-12 651562 + 851 651570 Tb-157 2.86440E-09 2.86440E-09 651570 + 852 651580 Tb-158 1.53570E-08 1.70750E-08 651580 + 853 651581 Tb-158m 1.72910E-09 1.72910E-09 651581 + 854 651590 Tb-159 4.25440E-07 1.08220E-04 65159.82c + 855 651600 Tb-160 8.98270E-07 8.98270E-07 65160.82c + 856 651610 Tb-161 3.26700E-06 2.72970E-05 651610 + 857 651620 Tb-162 6.55780E-06 2.05770E-05 651620 + 858 651630 Tb-163 6.29140E-06 8.66140E-06 651630 + 859 651640 Tb-164 2.84980E-06 3.36500E-06 651640 + 860 651650 Tb-165 1.23310E-06 1.26670E-06 651650 + 861 651660 Tb-166 1.71990E-07 1.73880E-07 651660 + 862 651670 Tb-167 2.92790E-08 2.93200E-08 651670 + 863 651680 Tb-168 1.50430E-09 1.50430E-09 651680 + 864 651690 Tb-169 6.32630E-11 6.32630E-11 651690 + 865 661580 Dy-158 3.37520E-12 2.84830E-09 661580 + 866 661590 Dy-159 1.35780E-10 1.35780E-10 661590 + 867 661600 Dy-160 2.34990E-09 9.00620E-07 66160.82c + 868 661610 Dy-161 2.26640E-08 2.73190E-05 66161.82c + 869 661620 Dy-162 6.73630E-06 2.73130E-05 66162.82c + 870 661630 Dy-163 7.10630E-07 9.37210E-06 66163.82c + 871 661640 Dy-164 1.93050E-06 5.30520E-06 66164.82c + 872 661650 Dy-165 1.40750E-06 2.88460E-06 661650 + 873 661651 Dy-165m 2.15170E-07 2.15170E-07 661651 + 874 661660 Dy-166 1.31890E-06 1.49280E-06 661660 + 875 661670 Dy-167 4.84580E-07 5.13900E-07 661670 + 876 661680 Dy-168 1.73890E-07 1.75390E-07 661680 + 877 661690 Dy-169 1.88980E-08 1.89610E-08 661690 + 878 661700 Dy-170 1.98490E-09 1.98490E-09 661700 + 879 661710 Dy-171 7.52020E-11 7.52020E-11 661710 + 880 661720 Dy-172 2.27560E-12 2.27560E-12 661720 + 881 671610 Ho-161 3.33270E-12 3.84220E-12 671610 + 882 671620 Ho-162 5.03050E-11 1.23360E-10 671620 + 883 671621 Ho-162m 1.17830E-10 1.17830E-10 671621 + 884 671630 Ho-163 2.50910E-09 2.89270E-09 671630 + 885 671631 Ho-163m 3.83570E-10 3.83570E-10 671631 + 886 671640 Ho-164 6.02080E-09 2.01230E-08 671640 + 887 671641 Ho-164m 1.41020E-08 1.41020E-08 671641 + 888 671650 Ho-165 1.16710E-07 3.00630E-06 67165.82c + 889 671660 Ho-166 6.04950E-08 1.55330E-06 671660 + 890 671661 Ho-166m 1.41690E-07 1.41690E-07 671661 + 891 671670 Ho-167 4.29830E-07 9.43730E-07 671670 + 892 671680 Ho-168 1.24210E-07 4.74970E-07 671680 + 893 671681 Ho-168m 1.76250E-07 1.76250E-07 671681 + 894 671690 Ho-169 1.97960E-07 2.16920E-07 671690 + 895 671700 Ho-170 3.31840E-08 3.31840E-08 671700 + 896 671701 Ho-170m 1.41680E-08 1.61530E-08 671701 + 897 671710 Ho-171 1.31330E-08 1.32080E-08 671710 + 898 671720 Ho-172 1.06210E-09 1.06440E-09 671720 + 899 671730 Ho-173 8.66390E-11 8.66390E-11 671730 + 900 671740 Ho-174 2.26490E-12 2.26490E-12 671740 + 901 681640 Er-164 1.24900E-11 1.04160E-08 68164.82c + 902 681650 Er-165 2.00200E-10 2.00200E-10 681650 + 903 681660 Er-166 2.68520E-09 1.55600E-06 68166.82c + 904 681670 Er-167 1.21510E-08 9.57750E-07 68167.82c + 905 681671 Er-167m 1.85750E-09 1.14640E-07 681671 + 906 681680 Er-168 6.40710E-08 5.40100E-07 68168.82c + 907 681690 Er-169 8.58230E-08 3.02740E-07 681690 + 908 681700 Er-170 1.16820E-07 1.66160E-07 68170.82c + 909 681710 Er-171 6.46830E-08 7.78910E-08 681710 + 910 681720 Er-172 3.33540E-08 3.44180E-08 681720 + 911 681730 Er-173 6.52550E-09 6.61210E-09 681730 + 912 681740 Er-174 1.29920E-09 1.30150E-09 681740 + 913 681750 Er-175 7.83560E-11 7.83560E-11 681750 + 914 681760 Er-176 4.00100E-12 4.00100E-12 681760 + 915 691670 Tm-167 1.37860E-11 1.37860E-11 691670 + 916 691680 Tm-168 1.70660E-10 1.70660E-10 691680 + 917 691690 Tm-169 1.70730E-09 3.04450E-07 691690 + 918 691700 Tm-170 5.42820E-09 5.42820E-09 691700 + 919 691710 Tm-171 1.86510E-08 9.65420E-08 691710 + 920 691720 Tm-172 1.89080E-08 5.33260E-08 691720 + 921 691730 Tm-173 2.11780E-08 2.77900E-08 691730 + 922 691740 Tm-174 8.77520E-09 1.00770E-08 691740 + 923 691750 Tm-175 3.56080E-09 3.63920E-09 691750 + 924 691760 Tm-176 4.56630E-10 4.60630E-10 691760 + 925 691770 Tm-177 7.06860E-11 7.06860E-11 691770 + 926 691780 Tm-178 3.34160E-12 3.34160E-12 691780 + 927 701700 Yb-170 1.78980E-11 5.43900E-09 701700 + 928 701710 Yb-171 2.14340E-11 9.67040E-08 701710 + 929 701711 Yb-171m 1.40210E-10 1.40210E-10 701711 + 930 701720 Yb-172 1.17160E-09 5.44980E-08 701720 + 931 701730 Yb-173 2.90570E-09 3.07110E-08 701730 + 932 701740 Yb-174 7.13730E-09 1.73060E-08 701740 + 933 701750 Yb-175 4.87230E-09 9.25630E-09 701750 + 934 701751 Yb-175m 7.44830E-10 3.54700E-09 701751 + 935 701760 Yb-176 1.51420E-09 4.40350E-09 701760 + 936 701761 Yb-176m 2.72380E-09 2.95410E-09 701761 + 937 701770 Yb-177 1.16740E-09 1.50800E-09 701770 + 938 701771 Yb-177m 2.69920E-10 3.40610E-10 701771 + 939 701780 Yb-178 4.81140E-10 4.84480E-10 701780 + 940 701790 Yb-179 4.77480E-11 4.77480E-11 701790 + 941 701800 Yb-180 4.50750E-12 4.50750E-12 701800 + 942 711730 Lu-173 1.48450E-11 1.48450E-11 711730 + 943 711740 Lu-174 2.76300E-11 9.19720E-11 711740 + 944 711741 Lu-174m 6.47170E-11 6.47170E-11 711741 + 945 711750 Lu-175 4.94190E-10 9.75150E-09 71175.82c + 946 711760 Lu-176 5.03560E-10 7.98960E-10 71176.82c + 947 711761 Lu-176m 2.79950E-10 2.79950E-10 711761 + 948 711770 Lu-177 1.08790E-09 2.69360E-09 711770 + 949 711771 Lu-177m 4.25300E-10 4.32170E-10 711771 + 950 711772 Lu-177m 1.37440E-11 1.37440E-11 711772 + 951 711780 Lu-178 4.68980E-10 9.53460E-10 711780 + 952 711781 Lu-178m 5.31620E-10 5.31620E-10 711781 + 953 711790 Lu-179 5.29220E-10 6.57870E-10 711790 + 954 711791 Lu-179m 8.09020E-11 1.28650E-10 711791 + 955 711800 Lu-180 3.83310E-11 8.79960E-11 711800 + 956 711801 Lu-180m 3.83310E-11 4.28380E-11 711801 + 957 711802 Lu-180m 5.64910E-11 5.64910E-11 711802 + 958 711810 Lu-181 3.44310E-11 3.44310E-11 711810 + 959 711820 Lu-182 2.59270E-12 2.59270E-12 711820 + 960 721750 Hf-175 1.06810E-12 1.06810E-12 721750 + 961 721760 Hf-176 1.29880E-11 2.92670E-10 72176.82c + 962 721770 Hf-177 4.36770E-11 3.09620E-09 72177.82c + 963 721771 Hf-177m 1.69710E-11 3.59000E-10 721771 + 964 721772 Hf-177m 6.56020E-13 7.52800E-12 721772 + 965 721780 Hf-178 9.24940E-11 1.74390E-09 72178.82c + 966 721781 Hf-178m 1.52600E-10 6.98000E-10 721781 + 967 721782 Hf-178m 1.37720E-11 1.37720E-11 721782 + 968 721790 Hf-179 1.90940E-10 9.83090E-10 72179.82c + 969 721791 Hf-179m 5.96060E-11 5.96060E-11 721791 + 970 721792 Hf-179m 6.68420E-11 6.68420E-11 721792 + 971 721800 Hf-180 1.40750E-10 5.39290E-10 72180.82c + 972 721801 Hf-180m 2.53170E-10 2.81420E-10 721801 + 973 721810 Hf-181 2.05450E-10 2.39880E-10 721810 + 974 721820 Hf-182 3.57800E-11 6.54040E-11 721820 + 975 721821 Hf-182m 6.43600E-11 6.43600E-11 721821 + 976 721830 Hf-183 1.77830E-11 1.77830E-11 721830 + 977 721840 Hf-184 1.14530E-12 1.14530E-12 721840 + 978 721841 Hf-184m 2.06020E-12 2.06020E-12 721841 + 979 731790 Ta-179 5.94060E-12 7.82810E-12 731790 + 980 731791 Ta-179m 1.81710E-12 1.88750E-12 731791 + 981 731800 Ta-180 1.04820E-11 1.04820E-11 731800 + 982 731801 Ta-180m 1.18830E-11 1.27550E-11 731801 + 983 731810 Ta-181 7.13820E-11 3.11260E-10 73181.82c + 984 731820 Ta-182 2.42950E-11 1.05330E-10 73182.82c + 985 731821 Ta-182m 2.47990E-11 8.10300E-11 731821 + 986 731822 Ta-182m 1.89030E-11 5.62320E-11 731822 + 987 731830 Ta-183 6.95200E-11 8.73030E-11 731830 + 988 731840 Ta-184 2.64400E-11 2.96460E-11 731840 + 989 731850 Ta-185 6.80910E-12 1.01070E-11 731850 + 990 731851 Ta-185m 3.29790E-12 3.29790E-12 731851 + 991 731860 Ta-186 1.19680E-12 1.19680E-12 731860 + 992 741820 W-182 5.18420E-12 1.10510E-10 74182.82c + 993 741830 W-183 2.70640E-12 9.88640E-11 74183.82c + 994 741831 W-183m 8.85460E-12 1.18230E-11 741831 + 995 741840 W-184 2.57930E-11 5.54380E-11 74184.82c + 996 741850 W-185 5.60290E-12 2.92360E-11 741850 + 997 741851 W-185m 1.35260E-11 1.35260E-11 741851 + 998 741860 W-186 1.01850E-11 1.47520E-11 74186.82c + 999 741861 W-186m 3.28530E-12 3.28530E-12 741861 + 1000 741870 W-187 4.20720E-12 4.20720E-12 741870 + 1001 741880 W-188 1.30920E-12 1.30920E-12 741880 + 1002 751850 Re-185 2.05390E-12 3.12900E-11 75185.82c + 1003 751860 Re-186 1.23950E-12 1.23950E-12 751860 + 1004 751861 Re-186m 1.75890E-12 1.75890E-12 751861 + 1005 751870 Re-187 5.35410E-12 9.56130E-12 75187.82c + 1006 751880 Re-188 9.82090E-13 4.59160E-12 751880 + 1007 751881 Re-188m 2.30030E-12 2.30030E-12 751881 + 1008 751890 Re-189 1.85910E-12 1.85910E-12 751890 + 1009 761880 Os-188 1.02830E-12 5.61990E-12 761880 + 1010 761890 Os-189 2.71440E-13 3.01860E-12 761890 + 1011 761891 Os-189m 8.88060E-13 1.07920E-12 761891 + 1012 761900 Os-190 6.16760E-13 1.31590E-12 761900 + + Nuclide 96243.82c -- curium 243 (Cm-243) + + Neutron-induced fission: + + Interpolation region : 1 / 2 + Interpolation energy : 2.53000E-08 MeV + Number of products : 1173 / 1216 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 4.08110E-05 4.08110E-05 1001.82c + 2 10020 H-2 1.24720E-05 1.24720E-05 1002.82c + 3 10030 H-3 1.96000E-04 1.96000E-04 1003.82c + 4 20040 He-4 2.58000E-03 2.58000E-03 2004.82c + 5 190500 K-50 1.28440E-11 1.28440E-11 190500 + 6 190510 K-51 4.17280E-12 4.17280E-12 190510 + 7 200500 Ca-50 1.83230E-10 1.94310E-10 200500 + 8 200510 Ca-51 1.50100E-10 1.52310E-10 200510 + 9 200520 Ca-52 1.05570E-10 1.05570E-10 200520 + 10 200530 Ca-53 2.76230E-11 2.76230E-11 200530 + 11 200540 Ca-54 5.71610E-12 5.71610E-12 200540 + 12 210500 Sc-50 4.66360E-11 2.58180E-10 210500 + 13 210501 Sc-50m 1.99110E-11 2.14220E-10 210501 + 14 210510 Sc-51 2.45990E-10 4.00410E-10 210510 + 15 210520 Sc-52 3.89740E-10 5.01490E-10 210520 + 16 210530 Sc-53 5.09380E-10 5.28720E-10 210530 + 17 210540 Sc-54 2.77730E-10 2.83450E-10 210540 + 18 210550 Sc-55 1.52510E-10 1.52510E-10 210550 + 19 210560 Sc-56 3.19750E-11 3.19750E-11 210560 + 20 210570 Sc-57 5.16200E-12 5.16200E-12 210570 + 21 220500 Ti-50 2.51720E-12 2.63370E-10 22050.82c + 22 220510 Ti-51 2.36330E-11 4.24050E-10 220510 + 23 220520 Ti-52 1.80340E-10 6.81830E-10 220520 + 24 220530 Ti-53 5.20420E-10 1.04910E-09 220530 + 25 220540 Ti-54 1.29030E-09 1.57380E-09 220540 + 26 220550 Ti-55 1.65440E-09 1.80690E-09 220550 + 27 220560 Ti-56 1.81290E-09 1.84660E-09 220560 + 28 220570 Ti-57 8.02170E-10 8.05630E-10 220570 + 29 220580 Ti-58 2.95600E-10 2.95600E-10 220580 + 30 220590 Ti-59 4.52900E-11 4.52900E-11 220590 + 31 220600 Ti-60 5.19190E-12 5.19190E-12 220600 + 32 230520 V-52 1.66350E-12 6.83490E-10 230520 + 33 230530 V-53 2.60900E-11 1.07520E-09 230530 + 34 230540 V-54 1.57000E-10 1.73080E-09 230540 + 35 230550 V-55 9.35150E-10 2.74210E-09 230550 + 36 230560 V-56 2.24420E-09 4.09320E-09 230560 + 37 230570 V-57 4.62790E-09 5.43110E-09 230570 + 38 230580 V-58 4.15870E-09 4.45430E-09 230580 + 39 230590 V-59 3.47820E-09 3.52350E-09 230590 + 40 230600 V-60 1.13000E-09 1.13520E-09 230600 + 41 230610 V-61 3.36150E-10 3.36150E-10 230610 + 42 230620 V-62 3.85370E-11 3.85370E-11 230620 + 43 230630 V-63 3.21610E-12 3.21610E-12 230630 + 44 240540 Cr-54 1.66410E-12 1.73240E-09 24054.82c + 45 240550 Cr-55 2.70620E-11 2.76910E-09 240550 + 46 240560 Cr-56 3.37860E-10 4.45280E-09 240560 + 47 240570 Cr-57 1.61990E-09 1.05930E-08 240570 + 48 240580 Cr-58 6.60910E-09 7.50000E-09 240580 + 49 240590 Cr-59 1.22270E-08 1.57500E-08 240590 + 50 240600 Cr-60 1.92160E-08 2.03710E-08 240600 + 51 240610 Cr-61 1.45850E-08 1.49010E-08 240610 + 52 240620 Cr-62 9.48790E-09 9.52760E-09 240620 + 53 240630 Cr-63 2.30710E-09 2.30920E-09 240630 + 54 240640 Cr-64 4.39780E-10 4.39780E-10 240640 + 55 240650 Cr-65 4.98440E-11 4.98440E-11 240650 + 56 240660 Cr-66 2.69030E-12 2.69030E-12 240660 + 57 250570 Mn-57 2.36110E-11 1.06160E-08 250570 + 58 250580 Mn-58 2.27120E-10 7.72710E-09 250580 + 59 250581 Mn-58m 2.55720E-11 2.55720E-11 250581 + 60 250590 Mn-59 2.32410E-09 1.80750E-08 250590 + 61 250600 Mn-60 8.30170E-10 2.20490E-08 250600 + 62 250601 Mn-60m 7.37310E-09 7.37310E-09 250601 + 63 250610 Mn-61 2.81050E-08 4.30060E-08 250610 + 64 250620 Mn-62 3.52090E-08 3.99730E-08 250620 + 65 250621 Mn-62m 6.32090E-09 1.10850E-08 250621 + 66 250630 Mn-63 5.10430E-08 5.33520E-08 250630 + 67 250640 Mn-64 2.59170E-08 2.63570E-08 250640 + 68 250650 Mn-65 1.72240E-08 1.72740E-08 250650 + 69 250660 Mn-66 2.78080E-09 2.78350E-09 250660 + 70 250670 Mn-67 2.20800E-10 2.20800E-10 250670 + 71 250680 Mn-68 1.00020E-11 1.00020E-11 250680 + 72 260590 Fe-59 1.89310E-11 1.80930E-08 260590 + 73 260600 Fe-60 3.74080E-10 2.89490E-08 260600 + 74 260610 Fe-61 3.21630E-09 4.62220E-08 260610 + 75 260620 Fe-62 2.26530E-08 7.37110E-08 260620 + 76 260630 Fe-63 6.12360E-08 1.14590E-07 260630 + 77 260640 Fe-64 1.42090E-07 1.68450E-07 260640 + 78 260650 Fe-65 2.22900E-07 2.40170E-07 260650 + 79 260660 Fe-66 1.90320E-07 1.93100E-07 260660 + 80 260670 Fe-67 4.18090E-08 4.20300E-08 260670 + 81 260680 Fe-68 1.14140E-08 1.14240E-08 260680 + 82 260690 Fe-69 3.51240E-09 3.51240E-09 260690 + 83 260700 Fe-70 1.81360E-10 1.81360E-10 260700 + 84 260710 Fe-71 3.71020E-12 3.71020E-12 260710 + 85 270610 Co-61 1.28280E-11 4.62350E-08 270610 + 86 270620 Co-62 7.57330E-11 7.37880E-08 270620 + 87 270621 Co-62m 1.77390E-10 1.77390E-10 270621 + 88 270630 Co-63 3.67780E-09 1.18270E-07 270630 + 89 270640 Co-64 2.04700E-08 1.88920E-07 270640 + 90 270650 Co-65 1.48060E-07 3.88230E-07 270650 + 91 270660 Co-66 5.37890E-07 7.30990E-07 270660 + 92 270670 Co-67 2.86210E-07 3.28240E-07 270670 + 93 270680 Co-68 1.02440E-07 1.53460E-07 270680 + 94 270681 Co-68m 9.03700E-08 1.02040E-07 270681 + 95 270690 Co-69 3.27380E-07 3.30650E-07 270690 + 96 270700 Co-70 2.41420E-08 2.41420E-08 270700 + 97 270701 Co-70m 2.41420E-08 2.43240E-08 270701 + 98 270710 Co-71 6.05510E-09 6.05880E-09 270710 + 99 270720 Co-72 1.04240E-09 1.04240E-09 270720 + 100 270730 Co-73 1.63790E-10 1.63790E-10 270730 + 101 270740 Co-74 8.70930E-12 8.70930E-12 270740 + 102 280630 Ni-63 8.00270E-12 1.18270E-07 280630 + 103 280640 Ni-64 2.63970E-10 1.89180E-07 28064.82c + 104 280650 Ni-65 3.92510E-07 7.80740E-07 280650 + 105 280660 Ni-66 4.96540E-08 7.80650E-07 280660 + 106 280670 Ni-67 4.50320E-07 7.78560E-07 280670 + 107 280680 Ni-68 5.59830E-07 7.67620E-07 280680 + 108 280690 Ni-69 6.79550E-07 1.00690E-06 280690 + 109 280691 Ni-69m 6.79550E-07 6.79550E-07 280691 + 110 280700 Ni-70 7.42640E-07 7.91110E-07 280700 + 111 280710 Ni-71 3.17390E-07 3.23450E-07 280710 + 112 280720 Ni-72 7.78220E-07 7.79260E-07 280720 + 113 280730 Ni-73 1.44210E-07 1.44370E-07 280730 + 114 280740 Ni-74 4.82820E-08 4.82910E-08 280740 + 115 280750 Ni-75 2.29110E-09 2.29110E-09 280750 + 116 280760 Ni-76 1.79180E-10 1.79180E-10 280760 + 117 280770 Ni-77 2.99440E-12 2.99440E-12 280770 + 118 290650 Cu-65 5.39360E-12 7.80750E-07 29065.82c + 119 290660 Cu-66 1.52440E-10 7.80800E-07 290660 + 120 290670 Cu-67 2.08280E-09 7.80640E-07 290670 + 121 290680 Cu-68 4.92690E-09 7.82240E-07 290680 + 122 290681 Cu-68m 1.15400E-08 1.15400E-08 290681 + 123 290690 Cu-69 3.05650E-07 1.99210E-06 290690 + 124 290700 Cu-70 5.65140E-08 3.92510E-07 290700 + 125 290701 Cu-70m 6.29600E-07 6.71980E-07 290701 + 126 290702 Cu-70m 5.65140E-08 8.47620E-07 290702 + 127 290710 Cu-71 1.14620E-06 1.46960E-06 290710 + 128 290720 Cu-72 7.78210E-07 1.55750E-06 290720 + 129 290730 Cu-73 3.75110E-06 3.89550E-06 290730 + 130 290740 Cu-74 8.54320E-07 9.02650E-07 290740 + 131 290750 Cu-75 1.65330E-06 1.65550E-06 290750 + 132 290760 Cu-76 1.13040E-07 1.13130E-07 290760 + 133 290761 Cu-76m 1.13040E-07 1.13130E-07 290761 + 134 290770 Cu-77 3.24070E-08 3.24100E-08 290770 + 135 290780 Cu-78 2.19500E-09 2.19500E-09 290780 + 136 290790 Cu-79 7.40100E-11 7.40100E-11 290790 + 137 300670 Zn-67 1.17150E-12 7.80640E-07 300670 + 138 300680 Zn-68 5.69120E-11 7.84140E-07 300680 + 139 300690 Zn-69 5.68530E-10 1.99510E-06 300690 + 140 300691 Zn-69m 2.45880E-09 2.45880E-09 300691 + 141 300700 Zn-70 2.69870E-08 1.56070E-06 300700 + 142 300710 Zn-71 1.83930E-08 1.48800E-06 300710 + 143 300711 Zn-71m 7.95480E-08 7.95480E-08 300711 + 144 300720 Zn-72 1.55630E-06 3.11380E-06 300720 + 145 300730 Zn-73 5.93490E-07 7.59830E-06 300730 + 146 300731 Zn-73m 8.11320E-07 3.10940E-06 300731 + 147 300732 Zn-73m 4.59610E-06 4.59610E-06 300732 + 148 300740 Zn-74 2.47750E-05 2.57360E-05 300740 + 149 300750 Zn-75 9.92030E-06 1.15210E-05 300750 + 150 300760 Zn-76 2.12380E-05 2.14610E-05 300760 + 151 300770 Zn-77 9.36960E-06 1.01180E-05 300770 + 152 300771 Zn-77m 1.43230E-06 1.43230E-06 300771 + 153 300780 Zn-78 3.59470E-06 3.59690E-06 300780 + 154 300790 Zn-79 3.09110E-07 3.09140E-07 300790 + 155 300800 Zn-80 3.39080E-08 3.39080E-08 300800 + 156 300810 Zn-81 1.20210E-09 1.20210E-09 300810 + 157 300820 Zn-82 3.42840E-11 3.42840E-11 300820 + 158 310700 Ga-70 2.17300E-11 2.17300E-11 310700 + 159 310710 Ga-71 4.76740E-10 1.56810E-06 310710 + 160 310720 Ga-72 1.26930E-08 3.12790E-06 310720 + 161 310721 Ga-72m 1.42910E-09 1.05180E-07 310721 + 162 310730 Ga-73 3.88060E-07 1.02840E-05 310730 + 163 310740 Ga-74 8.54250E-07 2.07970E-05 310740 + 164 310741 Ga-74m 8.54250E-07 2.65900E-05 310741 + 165 310750 Ga-75 1.57020E-05 2.72230E-05 310750 + 166 310760 Ga-76 2.97170E-05 5.11780E-05 310760 + 167 310770 Ga-77 4.95100E-05 6.03440E-05 310770 + 168 310780 Ga-78 4.22680E-05 4.58690E-05 310780 + 169 310790 Ga-79 3.91650E-05 3.94700E-05 310790 + 170 310800 Ga-80 9.79260E-06 9.82660E-06 310800 + 171 310810 Ga-81 6.68920E-06 6.69030E-06 310810 + 172 310820 Ga-82 2.10270E-07 2.10300E-07 310820 + 173 310830 Ga-83 1.48180E-08 1.48180E-08 310830 + 174 310840 Ga-84 4.17120E-10 4.17120E-10 310840 + 175 320720 Ge-72 1.26350E-11 3.12790E-06 32072.82c + 176 320730 Ge-73 8.39570E-10 1.02860E-05 32073.82c + 177 320731 Ge-73m 1.94130E-10 1.01340E-05 320731 + 178 320740 Ge-74 5.97510E-08 2.75040E-05 32074.82c + 179 320750 Ge-75 1.09600E-07 2.80490E-05 320750 + 180 320751 Ge-75m 7.16960E-07 1.80590E-06 320751 + 181 320760 Ge-76 9.33850E-06 6.05160E-05 32076.82c + 182 320770 Ge-77 3.27640E-05 4.51810E-05 320770 + 183 320771 Ge-77m 5.00870E-06 6.53530E-05 320771 + 184 320780 Ge-78 1.41030E-04 1.86930E-04 320780 + 185 320790 Ge-79 2.23340E-05 6.75560E-05 320790 + 186 320791 Ge-79m 1.46100E-04 1.46150E-04 320791 + 187 320800 Ge-80 2.88710E-04 2.99330E-04 320800 + 188 320810 Ge-81 1.49340E-04 1.52850E-04 320810 + 189 320811 Ge-81m 3.45310E-05 3.73350E-05 320811 + 190 320820 Ge-82 1.38080E-04 1.38250E-04 320820 + 191 320830 Ge-83 2.18300E-05 2.18400E-05 320830 + 192 320840 Ge-84 8.80860E-06 8.80870E-06 320840 + 193 320850 Ge-85 1.29760E-07 1.29760E-07 320850 + 194 320860 Ge-86 6.02530E-09 6.02530E-09 320860 + 195 320870 Ge-87 1.46370E-10 1.46370E-10 320870 + 196 330740 As-74 1.20590E-11 1.20590E-11 330740 + 197 330750 As-75 1.47010E-10 2.80500E-05 33075.82c + 198 330751 As-75m 4.80960E-10 1.02270E-09 330751 + 199 330760 As-76 2.55610E-08 2.55610E-08 330760 + 200 330770 As-77 8.99860E-07 9.90170E-05 330770 + 201 330780 As-78 1.16780E-05 1.98610E-04 330780 + 202 330790 As-79 4.09180E-05 2.48780E-04 330790 + 203 330800 As-80 1.19140E-04 4.18470E-04 330800 + 204 330810 As-81 3.49500E-04 5.39310E-04 330810 + 205 330820 As-82 1.06460E-04 2.44710E-04 330820 + 206 330821 As-82m 3.21250E-04 3.21250E-04 330821 + 207 330830 As-83 5.18960E-04 5.41750E-04 330830 + 208 330840 As-84 1.13130E-04 1.17070E-04 330840 + 209 330841 As-84m 1.13130E-04 1.17070E-04 330841 + 210 330850 As-85 8.90480E-05 8.91600E-05 330850 + 211 330860 As-86 2.69210E-05 2.69270E-05 330860 + 212 330870 As-87 7.27310E-06 7.27330E-06 330870 + 213 330880 As-88 4.51440E-08 4.51440E-08 330880 + 214 330890 As-89 1.19700E-09 1.19700E-09 330890 + 215 340760 Se-76 6.55500E-12 2.55680E-08 34076.82c + 216 340770 Se-77 5.75720E-11 9.90180E-05 34077.82c + 217 340771 Se-77m 3.76610E-10 3.76610E-10 340771 + 218 340780 Se-78 1.79640E-06 2.00410E-04 34078.82c + 219 340790 Se-79 3.15480E-06 2.52280E-04 34079.82c + 220 340791 Se-79m 4.82280E-07 2.43370E-04 340791 + 221 340800 Se-80 1.86140E-05 4.37090E-04 34080.82c + 222 340810 Se-81 1.35850E-05 6.41700E-04 340810 + 223 340811 Se-81m 8.88650E-05 1.08230E-04 340811 + 224 340820 Se-82 3.71450E-04 9.37410E-04 34082.82c + 225 340830 Se-83 6.67430E-04 8.62630E-04 340830 + 226 340831 Se-83m 1.54330E-04 5.01210E-04 340831 + 227 340840 Se-84 1.83240E-03 2.08580E-03 340840 + 228 340850 Se-85 1.31490E-03 1.39330E-03 340850 + 229 340860 Se-86 1.06590E-03 1.08510E-03 340860 + 230 340870 Se-87 4.13890E-04 4.20040E-04 340870 + 231 340880 Se-88 1.61740E-04 1.61790E-04 340880 + 232 340890 Se-89 2.15270E-05 2.15280E-05 340890 + 233 340900 Se-90 3.29100E-06 3.29100E-06 340900 + 234 340910 Se-91 1.29850E-08 1.29850E-08 340910 + 235 340920 Se-92 6.32800E-10 6.32800E-10 340920 + 236 350790 Br-79 4.15810E-11 1.36470E-07 35079.82c + 237 350791 Br-79m 1.36040E-10 1.36040E-10 350791 + 238 350800 Br-80 2.56670E-09 1.03120E-08 350800 + 239 350801 Br-80m 7.74530E-09 7.74530E-09 350801 + 240 350810 Br-81 9.55070E-07 6.42710E-04 35081.82c + 241 350820 Br-82 4.39100E-06 6.22070E-06 350820 + 242 350821 Br-82m 1.87470E-06 1.87470E-06 350821 + 243 350830 Br-83 5.86780E-05 1.42250E-03 350830 + 244 350840 Br-84 1.47720E-04 2.23350E-03 350840 + 245 350841 Br-84m 1.47720E-04 1.47720E-04 350841 + 246 350850 Br-85 9.65080E-04 2.35840E-03 350850 + 247 350860 Br-86 1.56190E-03 2.64700E-03 350860 + 248 350870 Br-87 2.31620E-03 2.73780E-03 350870 + 249 350880 Br-88 1.61590E-03 1.77780E-03 350880 + 250 350890 Br-89 1.04380E-03 1.06360E-03 350890 + 251 350900 Br-90 2.88100E-04 2.91390E-04 350900 + 252 350910 Br-91 9.93190E-05 9.93290E-05 350910 + 253 350920 Br-92 1.54760E-05 1.54770E-05 350920 + 254 350930 Br-93 1.19950E-07 1.19950E-07 350930 + 255 350940 Br-94 2.61600E-09 2.61600E-09 350940 + 256 360810 Kr-81 6.72720E-11 7.75560E-11 360810 + 257 360811 Kr-81m 1.02840E-11 1.02840E-11 360811 + 258 360820 Kr-82 6.44550E-09 6.27210E-06 36082.82c + 259 360830 Kr-83 1.47250E-06 1.42430E-03 36083.82c + 260 360831 Kr-83m 3.40480E-07 1.42160E-03 360831 + 261 360840 Kr-84 1.95330E-05 2.40080E-03 36084.82c + 262 360850 Kr-85 9.94780E-05 6.12110E-04 36085.82c + 263 360851 Kr-85m 2.30020E-05 2.37760E-03 360851 + 264 360860 Kr-86 8.03530E-04 3.51920E-03 36086.82c + 265 360870 Kr-87 2.00090E-03 4.78910E-03 360870 + 266 360880 Kr-88 4.58070E-03 6.38930E-03 360880 + 267 360890 Kr-89 5.59940E-03 6.58480E-03 360890 + 268 360900 Kr-90 5.68200E-03 5.92160E-03 360900 + 269 360910 Kr-91 3.20910E-03 3.29370E-03 360910 + 270 360920 Kr-92 1.71950E-03 1.72990E-03 360920 + 271 360930 Kr-93 3.83790E-04 3.83830E-04 360930 + 272 360940 Kr-94 9.19790E-05 9.19800E-05 360940 + 273 360950 Kr-95 1.64860E-05 1.64860E-05 360950 + 274 360960 Kr-96 3.29940E-08 3.29940E-08 360960 + 275 370840 Rb-84 6.81300E-10 1.90680E-09 370840 + 276 370841 Rb-84m 1.22550E-09 1.22550E-09 370841 + 277 370850 Rb-85 1.76760E-06 2.48270E-03 37085.82c + 278 370860 Rb-86 1.23370E-06 3.45270E-06 37086.82c + 279 370861 Rb-86m 2.21900E-06 2.21900E-06 370861 + 280 370870 Rb-87 9.95360E-05 4.88870E-03 37087.82c + 281 370880 Rb-88 3.87490E-04 6.77680E-03 370880 + 282 370890 Rb-89 1.43200E-03 8.01680E-03 370890 + 283 370900 Rb-90 3.17920E-04 5.55850E-03 370900 + 284 370901 Rb-90m 2.82360E-03 3.59810E-03 370901 + 285 370910 Rb-91 6.13620E-03 9.42990E-03 370910 + 286 370920 Rb-92 7.43290E-03 9.16280E-03 370920 + 287 370930 Rb-93 6.07020E-03 6.45510E-03 370930 + 288 370940 Rb-94 2.94290E-03 3.03430E-03 370940 + 289 370950 Rb-95 1.29640E-03 1.31240E-03 370950 + 290 370960 Rb-96 1.21670E-04 1.82530E-04 370960 + 291 370961 Rb-96m 1.21670E-04 1.21690E-04 370961 + 292 370970 Rb-97 4.96090E-05 4.96090E-05 370970 + 293 370980 Rb-98 1.55290E-06 1.55290E-06 370980 + 294 370981 Rb-98m 1.55290E-06 1.55290E-06 370981 + 295 370990 Rb-99 4.85800E-09 4.85800E-09 370990 + 296 380860 Sr-86 6.27640E-10 3.45320E-06 38086.82c + 297 380870 Sr-87 7.37260E-07 9.07220E-07 38087.82c + 298 380871 Sr-87m 1.70470E-07 1.70470E-07 380871 + 299 380880 Sr-88 2.36410E-05 6.80050E-03 38088.82c + 300 380890 Sr-89 1.25020E-04 8.14180E-03 38089.82c + 301 380900 Sr-90 8.61300E-04 9.92440E-03 38090.82c + 302 380910 Sr-91 2.36150E-03 1.17910E-02 380910 + 303 380920 Sr-92 7.62850E-03 1.68820E-02 380920 + 304 380930 Sr-93 1.08560E-02 1.75270E-02 380930 + 305 380940 Sr-94 1.77080E-02 2.05490E-02 380940 + 306 380950 Sr-95 1.36490E-02 1.48730E-02 380950 + 307 380960 Sr-96 9.01630E-03 9.24770E-03 380960 + 308 380970 Sr-97 3.19810E-03 3.23550E-03 380970 + 309 380980 Sr-98 1.12690E-03 1.12980E-03 380980 + 310 380990 Sr-99 1.93130E-04 1.93130E-04 380990 + 311 381000 Sr-100 2.96330E-05 2.96330E-05 381000 + 312 381010 Sr-101 4.26770E-08 4.26770E-08 381010 + 313 390880 Y-88 9.59000E-11 1.66580E-10 390880 + 314 390881 Y-88m 7.06800E-11 7.06800E-11 390881 + 315 390890 Y-89 1.61620E-07 8.14260E-03 39089.82c + 316 390891 Y-89m 6.98970E-07 1.48380E-06 390891 + 317 390900 Y-90 6.80130E-07 9.92600E-03 39090.82c + 318 390901 Y-90m 9.65070E-07 9.65070E-07 390901 + 319 390910 Y-91 1.19000E-05 1.18550E-02 39091.82c + 320 390911 Y-91m 5.14640E-05 6.98900E-03 390911 + 321 390920 Y-92 3.07450E-04 1.71890E-02 390920 + 322 390930 Y-93 2.10330E-04 1.91130E-02 390930 + 323 390931 Y-93m 1.37590E-03 5.76190E-03 390931 + 324 390940 Y-94 4.72850E-03 2.52770E-02 390940 + 325 390950 Y-95 1.21860E-02 2.70590E-02 390950 + 326 390960 Y-96 5.51600E-03 1.47640E-02 390960 + 327 390961 Y-96m 9.92200E-03 9.92280E-03 390961 + 328 390970 Y-97 3.35350E-03 6.20680E-03 390970 + 329 390971 Y-97m 1.14300E-02 1.43690E-02 390971 + 330 390972 Y-97m 3.07140E-03 3.07140E-03 390972 + 331 390980 Y-98 2.23370E-03 3.36350E-03 390980 + 332 390981 Y-98m 9.39430E-03 9.39430E-03 390981 + 333 390990 Y-99 7.49850E-03 7.69190E-03 390990 + 334 391000 Y-100 1.19840E-03 1.22780E-03 391000 + 335 391001 Y-100m 1.19840E-03 1.19840E-03 391001 + 336 391010 Y-101 6.42360E-04 6.42400E-04 391010 + 337 391020 Y-102 4.55690E-05 4.55690E-05 391020 + 338 391021 Y-102m 4.55690E-05 4.55690E-05 391021 + 339 391030 Y-103 1.21350E-05 1.21350E-05 391030 + 340 391040 Y-104 3.51700E-09 3.51700E-09 391040 + 341 400910 Zr-91 2.16410E-09 1.18550E-02 40091.82c + 342 400920 Zr-92 1.00060E-05 1.71990E-02 40092.82c + 343 400930 Zr-93 6.55520E-05 1.91790E-02 40093.82c + 344 400940 Zr-94 5.63850E-04 2.58410E-02 40094.82c + 345 400950 Zr-95 2.24450E-03 2.93030E-02 40095.82c + 346 400960 Zr-96 8.66460E-03 3.33630E-02 40096.82c + 347 400970 Zr-97 1.64400E-02 3.78500E-02 400970 + 348 400980 Zr-98 3.24240E-02 4.49800E-02 400980 + 349 400990 Zr-99 3.22310E-02 3.98030E-02 400990 + 350 401000 Zr-100 2.86160E-02 3.10310E-02 401000 + 351 401010 Zr-101 1.41710E-02 1.48180E-02 401010 + 352 401020 Zr-102 6.11580E-03 6.20340E-03 401020 + 353 401030 Zr-103 1.27910E-03 1.29030E-03 401030 + 354 401040 Zr-104 3.42530E-04 3.42530E-04 401040 + 355 401050 Zr-105 3.61830E-05 3.61830E-05 401050 + 356 401060 Zr-106 3.09080E-08 3.09080E-08 401060 + 357 410930 Nb-93 4.63930E-10 5.71200E-10 41093.82c + 358 410931 Nb-93m 1.07270E-10 1.07270E-10 410931 + 359 410940 Nb-94 2.23970E-06 3.81020E-06 41094.82c + 360 410941 Nb-94m 1.57840E-06 1.57840E-06 410941 + 361 410950 Nb-95 2.12540E-05 2.93120E-02 41095.82c + 362 410951 Nb-95m 4.91430E-06 3.21490E-04 410951 + 363 410960 Nb-96 1.49390E-04 1.49390E-04 410960 + 364 410970 Nb-97 8.52400E-04 3.88990E-02 410970 + 365 410971 Nb-97m 1.97100E-04 3.61730E-02 410971 + 366 410980 Nb-98 9.02210E-04 4.58820E-02 410980 + 367 410981 Nb-98m 2.72260E-03 2.72260E-03 410981 + 368 410990 Nb-99 1.12380E-02 3.67380E-02 410990 + 369 410991 Nb-99m 2.59840E-03 1.72460E-02 410991 + 370 411000 Nb-100 4.48070E-03 3.55120E-02 411000 + 371 411001 Nb-100m 1.88440E-02 1.88440E-02 411001 + 372 411010 Nb-101 3.74840E-02 5.23020E-02 411010 + 373 411020 Nb-102 1.35280E-02 1.97310E-02 411020 + 374 411021 Nb-102m 1.35280E-02 1.35280E-02 411021 + 375 411030 Nb-103 1.91930E-02 2.04830E-02 411030 + 376 411040 Nb-104 4.54730E-03 4.89030E-03 411040 + 377 411041 Nb-104m 4.54730E-03 4.54730E-03 411041 + 378 411050 Nb-105 3.56030E-03 3.59600E-03 411050 + 379 411060 Nb-106 6.41900E-04 6.41930E-04 411060 + 380 411070 Nb-107 1.48570E-04 1.48570E-04 411070 + 381 411080 Nb-108 1.47610E-05 1.47610E-05 411080 + 382 411090 Nb-109 3.39590E-06 3.39590E-06 411090 + 383 420960 Mo-96 1.93790E-06 1.51330E-04 42096.82c + 384 420970 Mo-97 1.65240E-05 3.89160E-02 42097.82c + 385 420980 Mo-98 1.94940E-04 4.88000E-02 42098.82c + 386 420990 Mo-99 1.19090E-03 5.48300E-02 42099.82c + 387 421000 Mo-100 5.85530E-03 6.02110E-02 42100.82c + 388 421010 Mo-101 1.47840E-02 6.70860E-02 421010 + 389 421020 Mo-102 3.25740E-02 6.58330E-02 421020 + 390 421030 Mo-103 3.45370E-02 5.50250E-02 421030 + 391 421040 Mo-104 4.42130E-02 5.37070E-02 421040 + 392 421050 Mo-105 2.52310E-02 2.87950E-02 421050 + 393 421060 Mo-106 1.41470E-02 1.47690E-02 421060 + 394 421070 Mo-107 5.16320E-03 5.30380E-03 421070 + 395 421080 Mo-108 1.08210E-03 1.09640E-03 421080 + 396 421090 Mo-109 2.19770E-04 2.22740E-04 421090 + 397 421100 Mo-110 3.72980E-05 3.72980E-05 421100 + 398 421110 Mo-111 5.12180E-06 5.12180E-06 421110 + 399 430980 Tc-98 1.18950E-09 1.18950E-09 430980 + 400 430990 Tc-99 5.54280E-06 5.48350E-02 43099.82c + 401 430991 Tc-99m 1.28160E-06 4.82850E-02 430991 + 402 431000 Tc-100 4.38830E-05 4.38830E-05 431000 + 403 431010 Tc-101 4.69700E-04 6.75560E-02 431010 + 404 431020 Tc-102 8.68700E-04 6.67020E-02 431020 + 405 431021 Tc-102m 8.68700E-04 8.68700E-04 431021 + 406 431030 Tc-103 6.77290E-03 6.17980E-02 431030 + 407 431040 Tc-104 1.57260E-02 6.94330E-02 431040 + 408 431050 Tc-105 2.97450E-02 5.85400E-02 431050 + 409 431060 Tc-106 2.63800E-02 4.11490E-02 431060 + 410 431070 Tc-107 2.98620E-02 3.51660E-02 431070 + 411 431080 Tc-108 1.01900E-02 1.12880E-02 431080 + 412 431090 Tc-109 7.62500E-03 7.84660E-03 431090 + 413 431100 Tc-110 2.74050E-03 2.77790E-03 431100 + 414 431110 Tc-111 6.88080E-04 6.93150E-04 431110 + 415 431120 Tc-112 8.25840E-05 8.25840E-05 431120 + 416 431130 Tc-113 1.07780E-05 1.07780E-05 431130 + 417 431140 Tc-114 9.23420E-07 9.23420E-07 431140 + 418 441010 Ru-101 6.09560E-06 6.75620E-02 44101.82c + 419 441020 Ru-102 3.71790E-05 6.76080E-02 44102.82c + 420 441030 Ru-103 7.47800E-05 6.20540E-02 44103.82c + 421 441031 Ru-103m 1.80530E-04 1.80530E-04 441031 + 422 441040 Ru-104 1.67740E-03 7.11100E-02 44104.82c + 423 441050 Ru-105 4.80000E-03 6.33400E-02 44105.82c + 424 441060 Ru-106 1.20370E-02 5.31860E-02 44106.82c + 425 441070 Ru-107 1.94240E-02 5.45900E-02 441070 + 426 441080 Ru-108 1.81190E-02 2.94130E-02 441080 + 427 441090 Ru-109 2.17210E-02 2.95620E-02 441090 + 428 441100 Ru-110 2.02580E-02 2.30350E-02 441100 + 429 441110 Ru-111 8.57130E-03 9.26570E-03 441110 + 430 441120 Ru-112 2.93040E-03 3.01250E-03 441120 + 431 441130 Ru-113 3.03390E-04 4.65150E-04 441130 + 432 441131 Ru-113m 3.03390E-04 3.03390E-04 441131 + 433 441140 Ru-114 9.66420E-05 9.75050E-05 441140 + 434 441150 Ru-115 7.06450E-06 7.06450E-06 441150 + 435 441160 Ru-116 2.97820E-06 2.97820E-06 441160 + 436 451030 Rh-103 4.83090E-10 6.20540E-02 45103.82c + 437 451031 Rh-103m 3.16010E-09 6.13100E-02 451031 + 438 451040 Rh-104 1.65450E-06 6.64090E-06 451040 + 439 451041 Rh-104m 4.99290E-06 4.99290E-06 451041 + 440 451050 Rh-105 6.90160E-05 6.34190E-02 45105.82c + 441 451051 Rh-105m 1.05510E-05 1.79910E-02 451051 + 442 451060 Rh-106 1.03800E-04 5.32900E-02 451060 + 443 451061 Rh-106m 2.43120E-04 2.43120E-04 451061 + 444 451070 Rh-107 1.67600E-03 5.62660E-02 451070 + 445 451080 Rh-108 6.32480E-04 3.00450E-02 451080 + 446 451081 Rh-108m 1.90860E-03 1.90860E-03 451081 + 447 451090 Rh-109 7.19900E-03 3.67610E-02 451090 + 448 451100 Rh-110 1.06200E-02 3.36540E-02 451100 + 449 451101 Rh-110m 2.83480E-04 2.83480E-04 451101 + 450 451110 Rh-111 1.50550E-02 2.43210E-02 451110 + 451 451120 Rh-112 4.71740E-03 7.72990E-03 451120 + 452 451121 Rh-112m 4.71740E-03 4.71740E-03 451121 + 453 451130 Rh-113 6.22810E-03 6.84490E-03 451130 + 454 451140 Rh-114 8.54750E-04 9.52270E-04 451140 + 455 451141 Rh-114m 8.54750E-04 8.54750E-04 451141 + 456 451150 Rh-115 5.43900E-04 5.50980E-04 451150 + 457 451160 Rh-116 3.38130E-05 3.67590E-05 451160 + 458 451161 Rh-116m 7.91970E-05 7.91970E-05 451161 + 459 451170 Rh-117 2.93310E-05 2.93310E-05 451170 + 460 451180 Rh-118 5.01400E-06 5.01400E-06 451180 + 461 451190 Rh-119 3.99970E-06 3.99970E-06 451190 + 462 461050 Pd-105 1.03410E-06 6.34200E-02 46105.82c + 463 461060 Pd-106 3.65730E-06 5.35370E-02 46106.82c + 464 461070 Pd-107 8.31120E-06 5.62900E-02 46107.82c + 465 461071 Pd-107m 1.56200E-05 1.56200E-05 461071 + 466 461080 Pd-108 1.43530E-04 3.20980E-02 46108.82c + 467 461090 Pd-109 2.31360E-04 3.74280E-02 461090 + 468 461091 Pd-109m 4.34820E-04 1.88150E-02 461091 + 469 461100 Pd-110 2.02690E-03 3.59650E-02 46110.82c + 470 461110 Pd-111 1.14340E-03 2.70060E-02 461110 + 471 461111 Pd-111m 2.14880E-03 2.24610E-03 461111 + 472 461120 Pd-112 4.42740E-03 1.68750E-02 461120 + 473 461130 Pd-113 1.27800E-03 1.12080E-02 461130 + 474 461131 Pd-113m 3.08540E-03 3.08540E-03 461131 + 475 461140 Pd-114 3.71100E-03 5.51800E-03 461140 + 476 461150 Pd-115 6.08570E-04 1.17750E-03 461150 + 477 461151 Pd-115m 1.14370E-03 1.22370E-03 461151 + 478 461160 Pd-116 7.86870E-04 9.02830E-04 461160 + 479 461170 Pd-117 6.46920E-05 2.15750E-04 461170 + 480 461171 Pd-117m 1.21580E-04 1.21580E-04 461171 + 481 461180 Pd-118 7.04710E-05 7.53390E-05 461180 + 482 461190 Pd-119 1.10030E-05 1.50030E-05 461190 + 483 461200 Pd-120 5.97870E-06 5.97870E-06 461200 + 484 461210 Pd-121 1.07230E-06 1.07230E-06 461210 + 485 461220 Pd-122 1.09280E-06 1.09280E-06 461220 + 486 461230 Pd-123 4.68170E-08 4.68170E-08 461230 + 487 461240 Pd-124 3.54380E-09 3.54380E-09 461240 + 488 471080 Ag-108 4.60050E-10 5.53800E-10 471080 + 489 471081 Ag-108m 1.07760E-09 1.07760E-09 471081 + 490 471090 Ag-109 5.62560E-07 3.74320E-02 47109.82c + 491 471091 Ag-109m 3.67990E-06 3.74130E-02 471091 + 492 471100 Ag-110 7.32290E-06 7.55620E-06 471100 + 493 471101 Ag-110m 1.71520E-05 1.71520E-05 47510.82c + 494 471110 Ag-111 2.02110E-05 2.76280E-02 47111.82c + 495 471111 Ag-111m 1.32210E-04 2.73790E-02 471111 + 496 471120 Ag-112 3.42600E-04 1.72170E-02 471120 + 497 471130 Ag-113 1.11050E-04 7.92050E-03 471130 + 498 471131 Ag-113m 7.26470E-04 1.14590E-02 471131 + 499 471140 Ag-114 1.78700E-04 6.44830E-03 471140 + 500 471141 Ag-114m 7.51540E-04 7.51540E-04 471141 + 501 471150 Ag-115 1.52050E-04 1.52370E-03 471150 + 502 471151 Ag-115m 9.94650E-04 2.43840E-03 471151 + 503 471160 Ag-116 2.01850E-04 1.13310E-03 471160 + 504 471161 Ag-116m 4.72790E-04 4.72790E-04 471161 + 505 471170 Ag-117 6.50240E-05 2.04890E-04 471170 + 506 471171 Ag-117m 4.25360E-04 5.33230E-04 471171 + 507 471180 Ag-118 3.74130E-05 1.70910E-04 471180 + 508 471181 Ag-118m 1.57350E-04 1.68120E-04 471181 + 509 471190 Ag-119 1.66070E-05 2.41080E-05 471190 + 510 471191 Ag-119m 1.08630E-04 1.16130E-04 471191 + 511 471200 Ag-120 1.27770E-05 2.35840E-05 471200 + 512 471201 Ag-120m 1.81310E-05 2.11200E-05 471201 + 513 471210 Ag-121 2.14610E-05 2.25300E-05 471210 + 514 471220 Ag-122 7.47750E-06 8.57030E-06 471220 + 515 471221 Ag-122m 6.73550E-06 6.73550E-06 471221 + 516 471230 Ag-123 1.51840E-05 1.52310E-05 471230 + 517 471240 Ag-124 2.84900E-06 4.13580E-06 471240 + 518 471241 Ag-124m 2.56640E-06 2.56640E-06 471241 + 519 471250 Ag-125 2.23400E-06 2.23400E-06 471250 + 520 471260 Ag-126 6.00940E-08 6.00940E-08 471260 + 521 471270 Ag-127 2.44070E-09 2.44070E-09 471270 + 522 481110 Cd-111 3.84670E-09 2.77650E-02 48111.82c + 523 481111 Cd-111m 1.25850E-08 1.25850E-08 481111 + 524 481120 Cd-112 5.48550E-06 1.72230E-02 48112.82c + 525 481130 Cd-113 6.39770E-06 1.19160E-02 48113.82c + 526 481131 Cd-113m 2.09310E-05 1.57870E-04 481131 + 527 481140 Cd-114 7.68480E-05 6.52510E-03 48114.82c + 528 481150 Cd-115 3.19990E-05 3.33810E-03 481150 + 529 481151 Cd-115m 1.04690E-04 2.48570E-04 48515.82c + 530 481160 Cd-116 1.94940E-04 1.77240E-03 48116.82c + 531 481170 Cd-117 3.33310E-05 5.80610E-04 481170 + 532 481171 Cd-117m 1.09050E-04 2.67890E-04 481171 + 533 481180 Cd-118 1.95430E-04 4.65530E-04 481180 + 534 481190 Cd-119 4.00280E-05 1.68220E-04 481190 + 535 481191 Cd-119m 9.66320E-05 1.08690E-04 481191 + 536 481200 Cd-120 1.68350E-04 2.05240E-04 481200 + 537 481210 Cd-121 4.27750E-05 6.29510E-05 481210 + 538 481211 Cd-121m 1.03260E-04 1.05620E-04 481211 + 539 481220 Cd-122 1.91780E-04 2.07090E-04 481220 + 540 481230 Cd-123 4.49250E-05 5.73880E-05 481230 + 541 481231 Cd-123m 1.08460E-04 1.11230E-04 481231 + 542 481240 Cd-124 2.44520E-04 2.49940E-04 481240 + 543 481250 Cd-125 3.77990E-05 3.89160E-05 481250 + 544 481251 Cd-125m 9.12510E-05 9.23680E-05 481251 + 545 481260 Cd-126 8.74740E-05 8.75340E-05 481260 + 546 481270 Cd-127 2.87580E-05 2.87600E-05 481270 + 547 481280 Cd-128 4.85990E-06 4.85990E-06 481280 + 548 481290 Cd-129 9.28110E-09 9.28110E-09 481290 + 549 481291 Cd-129m 2.24060E-08 2.24060E-08 481291 + 550 481300 Cd-130 7.18000E-10 7.18000E-10 481300 + 551 491130 In-113 8.42490E-10 1.57650E-04 49113.82c + 552 491131 In-113m 1.94810E-10 1.94810E-10 491131 + 553 491140 In-114 6.31780E-09 2.47130E-08 491140 + 554 491141 In-114m 9.68360E-09 1.90630E-08 491141 + 555 491142 In-114m 9.37900E-09 9.37900E-09 491142 + 556 491150 In-115 4.05240E-07 3.42030E-03 49115.82c + 557 491151 In-115m 9.37010E-08 3.33820E-03 491151 + 558 491160 In-116 7.40850E-07 7.40850E-07 491160 + 559 491161 In-116m 1.13550E-06 2.23540E-06 491161 + 560 491162 In-116m 1.09980E-06 1.09980E-06 491162 + 561 491170 In-117 9.00650E-06 5.74860E-04 491170 + 562 491171 In-117m 2.08250E-06 5.38250E-04 491171 + 563 491180 In-118 5.48080E-06 4.71010E-04 491180 + 564 491181 In-118m 8.40060E-06 1.64230E-05 491181 + 565 491182 In-118m 8.13640E-06 8.13640E-06 491182 + 566 491190 In-119 2.43180E-05 1.57950E-04 491190 + 567 491191 In-119m 5.62290E-06 1.57720E-04 491191 + 568 491200 In-120 1.65710E-05 2.21810E-04 491200 + 569 491201 In-120m 1.65710E-05 1.65710E-05 491201 + 570 491202 In-120m 1.65710E-05 1.65710E-05 491202 + 571 491210 In-121 9.12590E-05 2.18830E-04 491210 + 572 491211 In-121m 2.11010E-05 6.28510E-05 491211 + 573 491220 In-122 4.96240E-05 2.56710E-04 491220 + 574 491221 In-122m 3.52080E-05 3.52080E-05 491221 + 575 491222 In-122m 3.52080E-05 3.52080E-05 491222 + 576 491230 In-123 2.41960E-04 3.69610E-04 491230 + 577 491231 In-123m 5.59470E-05 9.69170E-05 491231 + 578 491240 In-124 2.52850E-04 5.02790E-04 491240 + 579 491241 In-124m 2.27770E-04 2.27770E-04 491241 + 580 491250 In-125 9.67090E-04 1.07810E-03 491250 + 581 491251 In-125m 2.23610E-04 2.43900E-04 491251 + 582 491260 In-126 7.19440E-04 8.06980E-04 491260 + 583 491261 In-126m 6.48060E-04 6.48060E-04 491261 + 584 491270 In-127 1.07100E-03 1.07100E-03 491270 + 585 491271 In-127m 2.47630E-04 2.76390E-04 491271 + 586 491280 In-128 1.42580E-04 2.05480E-04 491280 + 587 491281 In-128m 5.80400E-05 6.29000E-05 491281 + 588 491282 In-128m 1.80720E-04 1.80720E-04 491282 + 589 491290 In-129 1.47200E-04 1.47220E-04 491290 + 590 491291 In-129m 3.40350E-05 3.40440E-05 491291 + 591 491300 In-130 1.20950E-05 1.20960E-05 491300 + 592 491301 In-130m 1.35090E-05 1.35090E-05 491301 + 593 491302 In-130m 2.29850E-05 2.29850E-05 491302 + 594 491310 In-131 2.97490E-06 3.00520E-06 491310 + 595 491311 In-131m 2.97490E-06 2.97490E-06 491311 + 596 491312 In-131m 2.97490E-06 2.97490E-06 491312 + 597 491320 In-132 1.32830E-08 1.32830E-08 491320 + 598 501160 Sn-116 1.73350E-09 2.97790E-06 50116.82c + 599 501170 Sn-117 6.46050E-09 8.59620E-04 50117.82c + 600 501171 Sn-117m 2.11360E-08 1.97970E-06 501171 + 601 501180 Sn-118 4.01840E-07 4.87950E-04 50118.82c + 602 501190 Sn-119 4.67870E-07 3.08840E-04 50119.82c + 603 501191 Sn-119m 1.53070E-06 1.44230E-04 501191 + 604 501200 Sn-120 1.99160E-06 2.56980E-04 50120.82c + 605 501210 Sn-121 2.19730E-06 2.81690E-04 501210 + 606 501211 Sn-121m 5.30440E-06 3.00950E-05 501211 + 607 501220 Sn-122 4.14330E-05 3.68640E-04 50122.82c + 608 501230 Sn-123 6.33650E-05 9.15450E-05 50123.82c + 609 501231 Sn-123m 2.62480E-05 4.64590E-04 501231 + 610 501240 Sn-124 3.64020E-04 1.09460E-03 50124.82c + 611 501250 Sn-125 6.05480E-04 7.87590E-04 50125.82c + 612 501251 Sn-125m 2.50800E-04 1.39070E-03 501251 + 613 501260 Sn-126 3.01020E-03 4.46710E-03 50126.82c + 614 501270 Sn-127 2.79840E-03 3.21590E-03 501270 + 615 501271 Sn-127m 1.15920E-03 2.08720E-03 501271 + 616 501280 Sn-128 1.45990E-03 5.26550E-03 501280 + 617 501281 Sn-128m 3.41940E-03 3.60010E-03 501281 + 618 501290 Sn-129 1.10130E-03 1.26690E-03 501290 + 619 501291 Sn-129m 2.65850E-03 2.67420E-03 501291 + 620 501300 Sn-130 8.87430E-04 9.19040E-04 501300 + 621 501301 Sn-130m 2.07860E-03 2.09560E-03 501301 + 622 501310 Sn-131 3.43340E-04 3.49100E-04 501310 + 623 501311 Sn-131m 8.28860E-04 8.31970E-04 501311 + 624 501320 Sn-132 3.45450E-04 3.45460E-04 501320 + 625 501330 Sn-133 1.85830E-05 1.85830E-05 501330 + 626 501340 Sn-134 1.95980E-06 1.95980E-06 501340 + 627 501350 Sn-135 2.01790E-09 2.01790E-09 501350 + 628 511180 Sb-118 1.97800E-11 1.97800E-11 511180 + 629 511181 Sb-118m 2.80670E-11 2.80670E-11 511181 + 630 511190 Sb-119 1.43120E-09 1.88620E-09 511190 + 631 511191 Sb-119m 4.54950E-10 4.54950E-10 511191 + 632 511200 Sb-120 1.53250E-08 1.53250E-08 511200 + 633 511201 Sb-120m 2.17460E-08 2.17460E-08 511201 + 634 511210 Sb-121 7.76660E-07 2.89210E-04 51121.82c + 635 511220 Sb-122 1.53600E-06 3.27720E-06 511220 + 636 511221 Sb-122m 1.74120E-06 1.74120E-06 511221 + 637 511230 Sb-123 5.41670E-06 5.61560E-04 51123.82c + 638 511240 Sb-124 1.04290E-05 2.44970E-05 51124.82c + 639 511241 Sb-124m 7.97390E-06 1.87590E-05 511241 + 640 511242 Sb-124m 1.07850E-05 1.07850E-05 511242 + 641 511250 Sb-125 8.67880E-05 2.26500E-03 51125.82c + 642 511260 Sb-126 1.24170E-04 1.53830E-04 51126.82c + 643 511261 Sb-126m 9.18090E-05 2.11880E-04 511261 + 644 511262 Sb-126m 1.20070E-04 1.20070E-04 511262 + 645 511270 Sb-127 1.53070E-03 6.83380E-03 511270 + 646 511280 Sb-128 9.93400E-04 6.31990E-03 511280 + 647 511281 Sb-128m 1.69510E-03 1.69510E-03 511281 + 648 511290 Sb-129 4.69890E-03 7.93410E-03 511290 + 649 511291 Sb-129m 2.87140E-03 4.20850E-03 511291 + 650 511300 Sb-130 5.09400E-03 7.06080E-03 511300 + 651 511301 Sb-130m 5.09400E-03 6.14180E-03 511301 + 652 511310 Sb-131 1.70860E-02 1.82670E-02 511310 + 653 511320 Sb-132 6.11220E-03 6.45770E-03 511320 + 654 511321 Sb-132m 4.50480E-03 4.50480E-03 511321 + 655 511330 Sb-133 4.97310E-03 4.99200E-03 511330 + 656 511340 Sb-134 1.98720E-04 2.00340E-04 511340 + 657 511341 Sb-134m 4.65440E-04 4.65440E-04 511341 + 658 511350 Sb-135 8.96820E-05 8.96840E-05 511350 + 659 511360 Sb-136 4.84150E-06 4.84150E-06 511360 + 660 511370 Sb-137 2.10020E-08 2.10020E-08 511370 + 661 521200 Te-120 9.31260E-12 9.31260E-12 52120.82c + 662 521210 Te-121 7.35290E-11 2.86910E-10 521210 + 663 521211 Te-121m 2.40560E-10 2.40560E-10 521211 + 664 521220 Te-122 1.80550E-08 3.21000E-06 52122.82c + 665 521240 Te-124 8.14650E-11 2.91870E-05 52124.82c + 666 521250 Te-125 2.61440E-07 2.26620E-03 52125.82c + 667 521251 Te-125m 8.55360E-07 5.07700E-04 521251 + 668 521260 Te-126 1.50960E-05 3.51150E-04 52126.82c + 669 521270 Te-127 1.67750E-05 6.86300E-03 521270 + 670 521271 Te-127m 4.04970E-05 1.16670E-03 52527.82c + 671 521280 Te-128 3.94260E-04 8.34840E-03 52128.82c + 672 521290 Te-129 4.52740E-04 1.08730E-02 521290 + 673 521291 Te-129m 1.09300E-03 5.90310E-03 52529.82c + 674 521300 Te-130 6.14570E-03 1.93480E-02 52130.82c + 675 521310 Te-131 4.01540E-03 2.31630E-02 521310 + 676 521311 Te-131m 9.69360E-03 1.11560E-02 521311 + 677 521320 Te-132 3.02570E-02 4.12190E-02 52132.82c + 678 521330 Te-133 8.82980E-03 1.68400E-02 521330 + 679 521331 Te-133m 2.13160E-02 2.21800E-02 521331 + 680 521340 Te-134 2.13770E-02 2.20560E-02 521340 + 681 521350 Te-135 5.10300E-03 5.17940E-03 521350 + 682 521360 Te-136 1.53090E-03 1.53490E-03 521360 + 683 521370 Te-137 2.24920E-04 2.24930E-04 521370 + 684 521380 Te-138 4.14240E-05 4.14240E-05 521380 + 685 521390 Te-139 1.28120E-06 1.28120E-06 521390 + 686 521400 Te-140 1.85780E-09 1.85780E-09 521400 + 687 531270 I-127 1.97930E-06 6.89300E-03 53127.82c + 688 531280 I-128 2.08190E-06 2.08190E-06 531280 + 689 531290 I-129 3.17070E-05 1.30890E-02 53129.82c + 690 531300 I-130 1.17490E-04 1.59620E-04 53130.82c + 691 531301 I-130m 5.01610E-05 5.01610E-05 531301 + 692 531310 I-131 1.60150E-03 3.35780E-02 53131.82c + 693 531320 I-132 3.18120E-03 4.64170E-02 531320 + 694 531321 I-132m 2.34450E-03 2.34450E-03 531321 + 695 531330 I-133 1.23490E-02 5.50330E-02 531330 + 696 531331 I-133m 7.54620E-03 7.54620E-03 531331 + 697 531340 I-134 1.75320E-02 5.22120E-02 531340 + 698 531341 I-134m 1.29210E-02 1.29210E-02 531341 + 699 531350 I-135 3.97590E-02 4.49380E-02 53135.82c + 700 531360 I-136 5.85150E-03 7.38980E-03 531360 + 701 531361 I-136m 1.37060E-02 1.37090E-02 531361 + 702 531370 I-137 1.11290E-02 1.13500E-02 531370 + 703 531380 I-138 2.75950E-03 2.79830E-03 531380 + 704 531390 I-139 1.07900E-03 1.08030E-03 531390 + 705 531400 I-140 1.03030E-04 1.03030E-04 531400 + 706 531410 I-141 1.59890E-05 1.59890E-05 531410 + 707 531420 I-142 1.10280E-08 1.10280E-08 531420 + 708 541290 Xe-129 2.81690E-10 1.20330E-09 54129.82c + 709 541291 Xe-129m 9.21610E-10 9.21610E-10 541291 + 710 541300 Xe-130 1.56220E-06 1.69210E-04 54130.82c + 711 541310 Xe-131 6.67640E-06 3.36000E-02 54131.82c + 712 541311 Xe-131m 1.61180E-05 3.80830E-04 541311 + 713 541320 Xe-132 1.12220E-04 4.69850E-02 54132.82c + 714 541321 Xe-132m 1.27200E-04 1.27200E-04 541321 + 715 541330 Xe-133 3.52770E-04 5.62380E-02 54133.82c + 716 541331 Xe-133m 8.51630E-04 2.41810E-03 541331 + 717 541340 Xe-134 2.13010E-03 5.96290E-02 54134.82c + 718 541341 Xe-134m 4.98930E-03 5.28650E-03 541341 + 719 541350 Xe-135 6.00650E-03 6.53140E-02 54135.82c + 720 541351 Xe-135m 1.45000E-02 2.19190E-02 541351 + 721 541360 Xe-136 5.05680E-02 7.24040E-02 54136.82c + 722 541370 Xe-137 4.16120E-02 5.23720E-02 541370 + 723 541380 Xe-138 3.44520E-02 3.72080E-02 541380 + 724 541390 Xe-139 1.52460E-02 1.62300E-02 541390 + 725 541400 Xe-140 6.25540E-03 6.35220E-03 541400 + 726 541410 Xe-141 1.63820E-03 1.65080E-03 541410 + 727 541420 Xe-142 3.40740E-04 3.40750E-04 541420 + 728 541430 Xe-143 4.17870E-05 4.17870E-05 541430 + 729 541440 Xe-144 3.53930E-06 3.53930E-06 541440 + 730 541450 Xe-145 9.99800E-10 9.99800E-10 541450 + 731 551320 Cs-132 2.65650E-08 2.65650E-08 551320 + 732 551330 Cs-133 6.55440E-06 5.62440E-02 55133.82c + 733 551340 Cs-134 3.27300E-05 5.68520E-05 55134.82c + 734 551341 Cs-134m 2.41220E-05 2.41220E-05 551341 + 735 551350 Cs-135 3.42760E-04 6.59980E-02 55135.82c + 736 551351 Cs-135m 2.09460E-04 2.09460E-04 551351 + 737 551360 Cs-136 2.18050E-03 2.81950E-03 55136.82c + 738 551361 Cs-136m 1.27790E-03 1.27790E-03 551361 + 739 551370 Cs-137 1.79690E-02 7.03410E-02 55137.82c + 740 551380 Cs-138 1.15790E-02 6.20940E-02 551380 + 741 551381 Cs-138m 1.64290E-02 1.64290E-02 551381 + 742 551390 Cs-139 3.73550E-02 5.35850E-02 551390 + 743 551400 Cs-140 2.04410E-02 2.67940E-02 551400 + 744 551410 Cs-141 2.00630E-02 2.17140E-02 551410 + 745 551420 Cs-142 7.81470E-03 8.15460E-03 551420 + 746 551430 Cs-143 2.83690E-03 2.87840E-03 551430 + 747 551440 Cs-144 2.60460E-04 3.94120E-04 551440 + 748 551441 Cs-144m 2.60460E-04 2.60460E-04 551441 + 749 551450 Cs-145 1.19310E-04 1.19310E-04 551450 + 750 551460 Cs-146 9.75220E-06 9.75220E-06 551460 + 751 551470 Cs-147 4.48640E-09 4.48640E-09 551470 + 752 561340 Ba-134 6.54530E-09 5.68580E-05 56134.82c + 753 561350 Ba-135 5.46810E-07 1.86690E-06 56135.82c + 754 561351 Ba-135m 1.32010E-06 1.32010E-06 561351 + 755 561360 Ba-136 1.65210E-05 3.51360E-03 56136.82c + 756 561361 Ba-136m 3.86950E-05 3.86950E-05 561361 + 757 561370 Ba-137 2.06750E-04 7.10470E-02 56137.82c + 758 561371 Ba-137m 4.99120E-04 6.69010E-02 561371 + 759 561380 Ba-138 5.78310E-03 7.09990E-02 56138.82c + 760 561390 Ba-139 1.37560E-02 6.73410E-02 561390 + 761 561400 Ba-140 2.38530E-02 5.06470E-02 56140.82c + 762 561410 Ba-141 2.63620E-02 4.80760E-02 561410 + 763 561420 Ba-142 3.47790E-02 4.29810E-02 561420 + 764 561430 Ba-143 2.08070E-02 2.36510E-02 561430 + 765 561440 Ba-144 1.15760E-02 1.21050E-02 561440 + 766 561450 Ba-145 4.17030E-03 4.27390E-03 561450 + 767 561460 Ba-146 1.13330E-03 1.14170E-03 561460 + 768 561470 Ba-147 1.88330E-04 1.88330E-04 561470 + 769 561480 Ba-148 2.81990E-05 2.81990E-05 561480 + 770 561490 Ba-149 2.60250E-06 2.60250E-06 561490 + 771 561500 Ba-150 4.81300E-10 4.81300E-10 561500 + 772 571370 La-137 1.07250E-06 1.07250E-06 571370 + 773 571380 La-138 1.89460E-05 1.89460E-05 57138.82c + 774 571390 La-139 3.16030E-04 6.76570E-02 57139.82c + 775 571400 La-140 9.69550E-04 5.16170E-02 57140.82c + 776 571410 La-141 3.90140E-03 5.19780E-02 571410 + 777 571420 La-142 6.48100E-03 4.94620E-02 571420 + 778 571430 La-143 1.55180E-02 3.91690E-02 571430 + 779 571440 La-144 1.50030E-02 2.71080E-02 571440 + 780 571450 La-145 1.80920E-02 2.23660E-02 571450 + 781 571460 La-146 2.78550E-03 3.92720E-03 571460 + 782 571461 La-146m 5.01050E-03 5.01050E-03 571461 + 783 571470 La-147 4.48880E-03 4.67720E-03 571470 + 784 571480 La-148 1.39440E-03 1.42250E-03 571480 + 785 571490 La-149 3.89730E-04 3.92320E-04 571490 + 786 571500 La-150 6.20030E-05 6.20040E-05 571500 + 787 571510 La-151 6.11440E-06 6.11440E-06 571510 + 788 571520 La-152 1.54000E-09 1.54000E-09 571520 + 789 581390 Ce-139 1.80650E-09 6.16750E-09 581390 + 790 581391 Ce-139m 4.36100E-09 4.36100E-09 581391 + 791 581400 Ce-140 1.97940E-05 5.16360E-02 58140.82c + 792 581410 Ce-141 1.28040E-04 5.21060E-02 58141.82c + 793 581420 Ce-142 6.20300E-04 5.00820E-02 58142.82c + 794 581430 Ce-143 1.65420E-03 4.08230E-02 58143.82c + 795 581440 Ce-144 5.30200E-03 3.24100E-02 58144.82c + 796 581450 Ce-145 1.05800E-02 3.29460E-02 581450 + 797 581460 Ce-146 1.42230E-02 2.31610E-02 581460 + 798 581470 Ce-147 1.21390E-02 1.68160E-02 581470 + 799 581480 Ce-148 1.21240E-02 1.35520E-02 581480 + 800 581490 Ce-149 6.27140E-03 6.65990E-03 581490 + 801 581500 Ce-150 2.85930E-03 2.91960E-03 581500 + 802 581510 Ce-151 7.12950E-04 7.19060E-04 581510 + 803 581520 Ce-152 1.31400E-04 1.31400E-04 581520 + 804 581530 Ce-153 1.29370E-05 1.29370E-05 581530 + 805 581540 Ce-154 8.42770E-09 8.42770E-09 581540 + 806 581550 Ce-155 1.01950E-10 1.01950E-10 581550 + 807 591420 Pr-142 3.18380E-07 1.06410E-06 59142.82c + 808 591421 Pr-142m 7.45720E-07 7.45720E-07 591421 + 809 591430 Pr-143 1.63080E-05 4.08390E-02 59143.82c + 810 591440 Pr-144 4.92040E-06 3.24580E-02 591440 + 811 591441 Pr-144m 4.37010E-05 4.90940E-04 591441 + 812 591450 Pr-145 3.94230E-04 3.33400E-02 591450 + 813 591460 Pr-146 9.65510E-04 2.41260E-02 591460 + 814 591470 Pr-147 2.58200E-03 1.93980E-02 591470 + 815 591480 Pr-148 8.10570E-04 1.43630E-02 591480 + 816 591481 Pr-148m 3.40890E-03 3.40890E-03 591481 + 817 591490 Pr-149 6.98130E-03 1.36410E-02 591490 + 818 591500 Pr-150 6.23770E-03 9.15730E-03 591500 + 819 591510 Pr-151 5.26380E-03 5.98290E-03 591510 + 820 591520 Pr-152 1.79800E-03 1.92950E-03 591520 + 821 591530 Pr-153 5.91230E-04 6.04090E-04 591530 + 822 591540 Pr-154 1.18600E-04 1.18610E-04 591540 + 823 591550 Pr-155 2.00320E-05 2.00320E-05 591550 + 824 591560 Pr-156 2.70730E-06 2.70730E-06 591560 + 825 591570 Pr-157 3.07970E-10 3.07970E-10 591570 + 826 601440 Nd-144 4.69840E-09 3.24580E-02 60144.82c + 827 601450 Nd-145 7.02340E-06 3.33470E-02 60145.82c + 828 601460 Nd-146 4.78260E-05 2.41740E-02 60146.82c + 829 601470 Nd-147 1.65590E-04 1.95640E-02 60147.82c + 830 601480 Nd-148 7.07100E-04 1.84790E-02 60148.82c + 831 601490 Nd-149 1.70710E-03 1.53480E-02 601490 + 832 601500 Nd-150 3.92640E-03 1.30840E-02 60150.82c + 833 601510 Nd-151 5.25670E-03 1.12400E-02 601510 + 834 601520 Nd-152 5.86590E-03 7.79540E-03 601520 + 835 601530 Nd-153 3.69640E-03 4.30050E-03 601530 + 836 601540 Nd-154 2.03460E-03 2.15320E-03 601540 + 837 601550 Nd-155 6.02920E-04 6.23030E-04 601550 + 838 601560 Nd-156 1.86520E-04 1.89150E-04 601560 + 839 601570 Nd-157 2.30800E-05 2.30800E-05 601570 + 840 601580 Nd-158 3.96910E-06 3.96910E-06 601580 + 841 601590 Nd-159 1.11860E-09 1.11860E-09 601590 + 842 601600 Nd-160 2.08740E-11 2.08740E-11 601600 + 843 611470 Pm-147 7.59600E-07 1.95650E-02 61147.82c + 844 611480 Pm-148 4.82040E-07 5.38490E-07 61148.82c + 845 611481 Pm-148m 1.12910E-06 1.12910E-06 61548.82c + 846 611490 Pm-149 2.51150E-05 1.53730E-02 61149.82c + 847 611500 Pm-150 1.15640E-04 1.15640E-04 611500 + 848 611510 Pm-151 5.31350E-04 1.17710E-02 61151.82c + 849 611520 Pm-152 1.87080E-04 7.98250E-03 611520 + 850 611521 Pm-152m 3.73570E-04 3.73570E-04 611521 + 851 611522 Pm-152m 4.13200E-04 4.13200E-04 611522 + 852 611530 Pm-153 1.71320E-03 6.01370E-03 611530 + 853 611540 Pm-154 8.93300E-04 3.04650E-03 611540 + 854 611541 Pm-154m 8.93300E-04 8.93300E-04 611541 + 855 611550 Pm-155 1.66020E-03 2.28320E-03 611550 + 856 611560 Pm-156 9.12890E-04 1.10200E-03 611560 + 857 611570 Pm-157 3.97960E-04 4.21040E-04 611570 + 858 611580 Pm-158 1.21090E-04 1.25060E-04 611580 + 859 611590 Pm-159 2.29310E-05 2.29320E-05 611590 + 860 611600 Pm-160 4.07960E-06 4.07960E-06 611600 + 861 611610 Pm-161 3.54540E-09 3.54540E-09 611610 + 862 611620 Pm-162 3.82790E-11 3.82790E-11 611620 + 863 621490 Sm-149 1.83540E-09 1.53730E-02 62149.82c + 864 621500 Sm-150 2.77020E-06 1.18410E-04 62150.82c + 865 621510 Sm-151 2.95060E-05 1.18000E-02 62151.82c + 866 621520 Sm-152 7.47860E-05 8.84400E-03 62152.82c + 867 621530 Sm-153 8.47270E-05 6.30300E-03 62153.82c + 868 621531 Sm-153m 2.04540E-04 2.04540E-04 621531 + 869 621540 Sm-154 7.15130E-04 4.65490E-03 62154.82c + 870 621550 Sm-155 1.05280E-03 3.33600E-03 621550 + 871 621560 Sm-156 1.50740E-03 2.60940E-03 621560 + 872 621570 Sm-157 1.13150E-03 1.55250E-03 621570 + 873 621580 Sm-158 8.26440E-04 9.51500E-04 621580 + 874 621590 Sm-159 3.36790E-04 3.59730E-04 621590 + 875 621600 Sm-160 1.24260E-04 1.28330E-04 621600 + 876 621610 Sm-161 3.84130E-05 3.84170E-05 621610 + 877 621620 Sm-162 4.20700E-06 4.20700E-06 621620 + 878 621630 Sm-163 7.50690E-09 7.50690E-09 621630 + 879 621640 Sm-164 1.25340E-10 1.25340E-10 621640 + 880 621650 Sm-165 1.77350E-12 1.77350E-12 621650 + 881 631520 Eu-152 3.08480E-09 6.52530E-09 63152.82c + 882 631521 Eu-152m 7.34710E-10 7.34710E-10 631521 + 883 631522 Eu-152m 3.44050E-09 3.44050E-09 631522 + 884 631530 Eu-153 1.84510E-06 6.30480E-03 63153.82c + 885 631540 Eu-154 6.11800E-06 1.16290E-05 63154.82c + 886 631541 Eu-154m 5.51100E-06 5.51100E-06 631541 + 887 631550 Eu-155 4.35510E-05 3.37960E-03 63155.82c + 888 631560 Eu-156 9.65170E-05 2.70600E-03 63156.82c + 889 631570 Eu-157 2.37030E-04 1.78960E-03 63157.82c + 890 631580 Eu-158 2.64820E-04 1.21630E-03 631580 + 891 631590 Eu-159 3.49360E-04 7.09090E-04 631590 + 892 631600 Eu-160 2.56830E-04 3.85160E-04 631600 + 893 631610 Eu-161 1.66190E-04 2.04610E-04 631610 + 894 631620 Eu-162 6.47970E-05 6.90040E-05 631620 + 895 631630 Eu-163 1.25630E-05 1.25700E-05 631630 + 896 631640 Eu-164 8.11130E-07 8.11250E-07 631640 + 897 631650 Eu-165 1.16390E-08 1.16410E-08 631650 + 898 631660 Eu-166 2.66390E-10 2.66390E-10 631660 + 899 631670 Eu-167 4.06510E-12 4.06510E-12 631670 + 900 641540 Gd-154 8.42770E-10 1.16280E-05 64154.82c + 901 641550 Gd-155 6.71910E-09 3.37960E-03 64155.82c + 902 641551 Gd-155m 1.62210E-08 1.62210E-08 641551 + 903 641560 Gd-156 4.50270E-06 2.71050E-03 64156.82c + 904 641570 Gd-157 1.77800E-05 1.80740E-03 64157.82c + 905 641580 Gd-158 5.73420E-05 1.27370E-03 64158.82c + 906 641590 Gd-159 1.09390E-04 8.18480E-04 641590 + 907 641600 Gd-160 1.79680E-04 5.64840E-04 64160.82c + 908 641610 Gd-161 2.12450E-04 4.17060E-04 641610 + 909 641620 Gd-162 1.69200E-04 2.38200E-04 641620 + 910 641630 Gd-163 9.63870E-05 1.08960E-04 641630 + 911 641640 Gd-164 4.54800E-05 4.62910E-05 641640 + 912 641650 Gd-165 9.77600E-06 9.78760E-06 641650 + 913 641660 Gd-166 2.86480E-06 2.86510E-06 641660 + 914 641670 Gd-167 2.26900E-08 2.26940E-08 641670 + 915 641680 Gd-168 9.33360E-10 9.33360E-10 641680 + 916 641690 Gd-169 6.15580E-12 6.15580E-12 641690 + 917 651560 Tb-156 2.41160E-11 6.56100E-11 651560 + 918 651561 Tb-156m 3.48650E-11 3.48650E-11 651561 + 919 651562 Tb-156m 6.64110E-12 6.64110E-12 651562 + 920 651570 Tb-157 1.84780E-09 1.84780E-09 651570 + 921 651580 Tb-158 3.55590E-08 3.95390E-08 651580 + 922 651581 Tb-158m 4.00380E-09 4.00380E-09 651581 + 923 651590 Tb-159 2.43930E-06 8.20920E-04 65159.82c + 924 651600 Tb-160 4.88360E-06 4.88360E-06 65160.82c + 925 651610 Tb-161 1.67050E-05 4.33760E-04 651610 + 926 651620 Tb-162 2.18040E-05 2.60010E-04 651620 + 927 651630 Tb-163 5.26320E-05 1.61590E-04 651630 + 928 651640 Tb-164 2.83690E-05 7.46600E-05 651640 + 929 651650 Tb-165 3.28730E-05 4.26610E-05 651650 + 930 651660 Tb-166 1.71920E-05 2.00570E-05 651660 + 931 651670 Tb-167 1.08810E-05 1.09040E-05 651670 + 932 651680 Tb-168 2.00220E-06 2.00310E-06 651680 + 933 651690 Tb-169 1.52610E-08 1.52670E-08 651690 + 934 651700 Tb-170 2.17950E-10 2.17950E-10 651700 + 935 651710 Tb-171 1.26720E-11 1.26720E-11 651710 + 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Ho-162m 1.78840E-10 1.78840E-10 671621 + 956 671630 Ho-163 6.15240E-09 7.09290E-09 671630 + 957 671631 Ho-163m 9.40520E-10 9.40520E-10 671631 + 958 671640 Ho-164 1.75150E-08 5.85400E-08 671640 + 959 671641 Ho-164m 4.10250E-08 4.10250E-08 671641 + 960 671650 Ho-165 5.40100E-07 5.91810E-05 67165.82c + 961 671660 Ho-166 8.56880E-07 4.09570E-05 671660 + 962 671661 Ho-166m 2.00700E-06 2.00700E-06 671661 + 963 671670 Ho-167 1.97770E-06 2.67240E-05 671670 + 964 671680 Ho-168 1.24140E-06 1.80120E-05 671680 + 965 671681 Ho-168m 1.76150E-06 1.76150E-06 671681 + 966 671690 Ho-169 9.16680E-07 5.51540E-06 671690 + 967 671700 Ho-170 4.79980E-07 4.79980E-07 671700 + 968 671701 Ho-170m 2.04920E-07 9.12940E-07 671701 + 969 671710 Ho-171 1.86030E-06 1.87650E-06 671710 + 970 671720 Ho-172 2.84190E-07 2.87010E-07 671720 + 971 671730 Ho-173 1.54930E-08 1.55190E-08 671730 + 972 671740 Ho-174 2.68060E-09 2.68060E-09 671740 + 973 671750 Ho-175 1.27110E-10 1.27110E-10 671750 + 974 681640 Er-164 1.83420E-11 3.02840E-08 68164.82c + 975 681650 Er-165 4.77080E-10 4.77080E-10 681650 + 976 681660 Er-166 1.10590E-08 4.09680E-05 68166.82c + 977 681670 Er-167 8.57720E-07 2.77130E-05 68167.82c + 978 681671 Er-167m 1.31120E-07 3.32450E-06 681671 + 979 681680 Er-168 1.00100E-06 1.90230E-05 68168.82c + 980 681690 Er-169 6.84190E-07 6.19960E-06 681690 + 981 681700 Er-170 7.07770E-07 2.10070E-06 68170.82c + 982 681710 Er-171 1.13560E-06 3.01210E-06 681710 + 983 681720 Er-172 2.47040E-06 2.75740E-06 681720 + 984 681730 Er-173 6.89950E-07 7.05470E-07 681730 + 985 681740 Er-174 1.22830E-06 1.23100E-06 681740 + 986 681750 Er-175 3.99930E-08 4.01200E-08 681750 + 987 681760 Er-176 5.21910E-09 5.21910E-09 681760 + 988 681770 Er-177 2.56160E-10 2.56160E-10 681770 + 989 691660 Tm-166 3.76200E-13 1.05290E-12 691660 + 990 691670 Tm-167 3.57710E-11 3.57710E-11 691670 + 991 691680 Tm-168 7.22030E-10 7.22030E-10 691680 + 992 691690 Tm-169 4.88420E-09 6.20450E-06 691690 + 993 691700 Tm-170 1.14620E-08 1.14620E-08 691700 + 994 691710 Tm-171 1.12210E-07 3.12430E-06 691710 + 995 691720 Tm-172 5.61470E-07 3.31890E-06 691720 + 996 691730 Tm-173 3.31160E-07 1.03660E-06 691730 + 997 691740 Tm-174 6.74440E-07 1.90540E-06 691740 + 998 691750 Tm-175 7.41650E-07 7.81770E-07 691750 + 999 691760 Tm-176 1.39750E-07 1.44970E-07 691760 + 1000 691770 Tm-177 3.83020E-08 3.85580E-08 691770 + 1001 691780 Tm-178 4.04830E-09 4.04830E-09 691780 + 1002 691790 Tm-179 3.61980E-10 3.61980E-10 691790 + 1003 701700 Yb-170 1.50320E-11 1.14620E-08 701700 + 1004 701710 Yb-171 5.69920E-11 3.12470E-06 701710 + 1005 701711 Yb-171m 3.72810E-10 3.72810E-10 701711 + 1006 701720 Yb-172 1.23130E-08 3.33120E-06 701720 + 1007 701730 Yb-173 1.88410E-08 1.05550E-06 701730 + 1008 701740 Yb-174 1.88940E-07 2.09530E-06 701740 + 1009 701750 Yb-175 2.30500E-07 1.04750E-06 701750 + 1010 701751 Yb-175m 3.52370E-08 6.37200E-07 701751 + 1011 701760 Yb-176 1.39020E-07 5.01800E-07 701760 + 1012 701761 Yb-176m 2.50060E-07 3.22550E-07 701761 + 1013 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721792 + 1051 721800 Hf-180 1.48230E-08 9.26720E-08 72180.82c + 1052 721801 Hf-180m 2.66620E-08 3.62260E-08 721801 + 1053 721810 Hf-181 3.67670E-08 5.56650E-08 721810 + 1054 721820 Hf-182 1.00120E-08 2.06140E-08 721820 + 1055 721821 Hf-182m 1.80080E-08 1.80080E-08 721821 + 1056 721830 Hf-183 1.10640E-08 1.15600E-08 721830 + 1057 721840 Hf-184 1.35390E-09 1.36960E-09 721840 + 1058 721841 Hf-184m 2.43530E-09 2.45110E-09 721841 + 1059 721850 Hf-185 4.92470E-10 4.92470E-10 721850 + 1060 721860 Hf-186 5.23820E-11 5.23820E-11 721860 + 1061 721870 Hf-187 2.50390E-12 2.50390E-12 721870 + 1062 731780 Ta-178 3.59620E-12 3.59620E-12 731780 + 1063 731781 Ta-178m 5.64340E-12 6.46880E-12 731781 + 1064 731790 Ta-179 1.12860E-10 1.48710E-10 731790 + 1065 731791 Ta-179m 3.45200E-11 3.58590E-11 731791 + 1066 731792 Ta-179m 1.33860E-12 1.33860E-12 731792 + 1067 731800 Ta-180 3.98700E-10 3.98700E-10 731800 + 1068 731801 Ta-180m 4.51960E-10 5.64260E-10 731801 + 1069 731810 Ta-181 3.85860E-09 5.95400E-08 73181.82c + 1070 731820 Ta-182 2.40820E-09 1.71850E-08 73182.82c + 1071 731821 Ta-182m 2.45810E-09 1.47770E-08 731821 + 1072 731822 Ta-182m 1.87380E-09 1.23190E-08 731822 + 1073 731830 Ta-183 1.19450E-08 2.35050E-08 731830 + 1074 731840 Ta-184 8.96130E-09 1.27820E-08 731840 + 1075 731850 Ta-185 3.75760E-09 6.07010E-09 731850 + 1076 731851 Ta-185m 1.82000E-09 1.82000E-09 731851 + 1077 731860 Ta-186 1.49660E-09 1.54900E-09 731860 + 1078 731870 Ta-187 4.00800E-10 4.03300E-10 731870 + 1079 731880 Ta-188 4.13830E-11 4.13830E-11 731880 + 1080 731890 Ta-189 3.58160E-12 3.58160E-12 731890 + 1081 741800 W-180 4.28550E-13 7.33650E-11 741800 + 1082 741810 W-181 1.58360E-11 1.58360E-11 741810 + 1083 741820 W-182 1.57920E-10 1.73430E-08 74182.82c + 1084 741830 W-183 1.69310E-10 2.42300E-08 74183.82c + 1085 741831 W-183m 5.53940E-10 1.35380E-09 741831 + 1086 741840 W-184 2.66120E-09 1.54580E-08 74184.82c + 1087 741850 W-185 1.07700E-09 9.74700E-09 741850 + 1088 741851 W-185m 2.59990E-09 2.59990E-09 741851 + 1089 741860 W-186 3.33190E-09 5.96510E-09 74186.82c + 1090 741861 W-186m 1.07480E-09 1.07480E-09 741861 + 1091 741870 W-187 2.65120E-09 3.05450E-09 741870 + 1092 741880 W-188 1.36640E-09 1.40780E-09 741880 + 1093 741890 W-189 3.10640E-10 3.14220E-10 741890 + 1094 741900 W-190 2.83340E-11 6.04520E-11 741900 + 1095 741901 W-190m 3.21180E-11 3.21180E-11 741901 + 1096 741910 W-191 4.65290E-12 4.65290E-12 741910 + 1097 751830 Re-183 9.96930E-13 1.39940E-12 751830 + 1098 751840 Re-184 7.70680E-12 1.29410E-11 751840 + 1099 751841 Re-184m 6.94220E-12 6.94220E-12 751841 + 1100 751850 Re-185 1.11760E-10 9.85870E-09 75185.82c + 1101 751860 Re-186 1.37250E-10 1.37250E-10 751860 + 1102 751861 Re-186m 1.94760E-10 1.94760E-10 751861 + 1103 751870 Re-187 9.41770E-10 3.99630E-09 75187.82c + 1104 751880 Re-188 3.16110E-10 2.46430E-09 751880 + 1105 751881 Re-188m 7.40400E-10 7.40400E-10 751881 + 1106 751890 Re-189 1.08510E-09 1.39930E-09 751890 + 1107 751900 Re-190 1.75710E-10 3.80280E-10 751900 + 1108 751901 Re-190m 3.16050E-10 3.16050E-10 751901 + 1109 751910 Re-191 1.97140E-10 2.01790E-10 751910 + 1110 751920 Re-192 3.17590E-11 3.17590E-11 751920 + 1111 751930 Re-193 5.04370E-12 5.04370E-12 751930 + 1112 761860 Os-186 2.02470E-12 1.29810E-10 761860 + 1113 761870 Os-187 1.58870E-11 1.58870E-11 761870 + 1114 761880 Os-188 9.47250E-11 2.55900E-09 761880 + 1115 761890 Os-189 5.41070E-11 1.63230E-09 761890 + 1116 761891 Os-189m 1.77020E-10 3.21060E-10 761891 + 1117 761900 Os-190 2.24260E-10 1.04120E-09 761900 + 1118 761901 Os-190m 2.54220E-10 4.28810E-10 761901 + 1119 761910 Os-191 3.18500E-10 6.17640E-10 761910 + 1120 761911 Os-191m 9.73500E-11 9.73500E-11 761911 + 1121 761920 Os-192 1.45570E-10 3.25720E-10 761920 + 1122 761921 Os-192m 1.65020E-10 1.65020E-10 761921 + 1123 761930 Os-193 1.19730E-10 1.24770E-10 761930 + 1124 761940 Os-194 4.00400E-11 4.00400E-11 761940 + 1125 761950 Os-195 5.06610E-12 5.06610E-12 761950 + 1126 771890 Ir-189 5.53290E-13 1.88900E-12 771890 + 1127 771891 Ir-189m 1.01080E-12 1.33570E-12 771891 + 1128 771900 Ir-190 5.54280E-12 7.80260E-12 771900 + 1129 771901 Ir-190m 2.00970E-12 2.00970E-12 771901 + 1130 771902 Ir-190m 2.90840E-12 2.90840E-12 771902 + 1131 771910 Ir-191 1.35750E-11 6.63990E-10 77191.82c + 1132 771911 Ir-191m 2.58660E-11 3.24300E-10 771911 + 1133 771912 Ir-191m 6.90560E-12 6.90560E-12 771912 + 1134 771920 Ir-192 2.63520E-11 1.00510E-10 771920 + 1135 771921 Ir-192m 2.63520E-11 2.63520E-11 771921 + 1136 771922 Ir-192m 2.63520E-11 4.78040E-11 771922 + 1137 771930 Ir-193 4.00190E-11 2.70210E-10 77193.82c + 1138 771931 Ir-193m 9.66110E-11 9.70450E-11 771931 + 1139 771940 Ir-194 3.34200E-11 1.06880E-10 771940 + 1140 771941 Ir-194m 3.34200E-11 3.34200E-11 771941 + 1141 771942 Ir-194m 3.34200E-11 3.34200E-11 771942 + 1142 771950 Ir-195 1.78640E-11 2.50870E-11 771950 + 1143 771951 Ir-195m 4.31270E-11 4.31270E-11 771951 + 1144 771960 Ir-196 7.97400E-12 7.99790E-12 771960 + 1145 771961 Ir-196m 7.97400E-12 7.97400E-12 771961 + 1146 771970 Ir-197 1.22360E-12 1.23100E-12 771970 + 1147 771971 Ir-197m 2.95400E-12 2.95400E-12 771971 + 1148 781920 Pt-192 1.97880E-12 9.76640E-11 781920 + 1149 781930 Pt-193 2.57840E-12 8.80300E-12 781930 + 1150 781931 Pt-193m 6.22460E-12 6.22460E-12 781931 + 1151 781940 Pt-194 3.15610E-11 1.71860E-10 781940 + 1152 781950 Pt-195 1.24510E-11 1.09940E-10 781950 + 1153 781951 Pt-195m 3.00580E-11 4.31690E-11 781951 + 1154 781960 Pt-196 4.96640E-11 6.92990E-11 781960 + 1155 781970 Pt-197 8.58690E-12 3.27130E-11 781970 + 1156 781971 Pt-197m 2.07300E-11 2.36770E-11 781971 + 1157 781980 Pt-198 1.48320E-11 1.48320E-11 781980 + 1158 781990 Pt-199 1.32820E-12 3.27800E-12 781990 + 1159 781991 Pt-199m 1.94970E-12 1.94970E-12 781991 + 1160 791950 Au-195 4.03500E-13 1.37760E-12 791950 + 1161 791960 Au-196 1.18880E-12 3.97340E-12 791960 + 1162 791961 Au-196m 1.98230E-12 2.78460E-12 791961 + 1163 791970 Au-197 3.22780E-12 4.45150E-11 79197.82c + 1164 791971 Au-197m 7.79220E-12 8.57360E-12 791971 + 1165 791980 Au-198 8.15510E-12 1.21230E-11 791980 + 1166 791981 Au-198m 3.96790E-12 3.96790E-12 791981 + 1167 791990 Au-199 1.21270E-11 1.54050E-11 791990 + 1168 792000 Au-200 3.37560E-12 3.73160E-12 792000 + 1169 792001 Au-200m 1.97820E-12 1.97820E-12 792001 + 1170 801980 Hg-198 1.15640E-12 1.32790E-11 80198.82c + 1171 801990 Hg-199 8.01780E-13 1.81420E-11 80199.82c + 1172 801991 Hg-199m 1.93560E-12 1.93560E-12 801991 + 1173 802000 Hg-200 5.50730E-12 1.08610E-11 80200.82c + + Neutron-induced fission: + + Interpolation region : 2 / 2 + Interpolation energy : 4.00000E-01 MeV + Number of products : 1123 / 1169 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 4.08110E-05 4.08110E-05 1001.82c + 2 10020 H-2 1.24720E-05 1.24720E-05 1002.82c + 3 10030 H-3 1.96000E-04 1.96000E-04 1003.82c + 4 20040 He-4 2.58000E-03 2.58000E-03 2004.82c + 5 190500 K-50 5.39170E-12 5.39170E-12 190500 + 6 190510 K-51 1.73150E-12 1.73150E-12 190510 + 7 200500 Ca-50 8.54290E-11 9.00710E-11 200500 + 8 200510 Ca-51 6.95660E-11 7.04840E-11 200510 + 9 200520 Ca-52 4.88730E-11 4.88730E-11 200520 + 10 200530 Ca-53 1.27720E-11 1.27720E-11 200530 + 11 200540 Ca-54 2.63570E-12 2.63570E-12 200540 + 12 210500 Sc-50 2.51290E-11 1.23180E-10 210500 + 13 210501 Sc-50m 9.21900E-12 9.92900E-11 210501 + 14 210510 Sc-51 1.26560E-10 1.98020E-10 210510 + 15 210520 Sc-52 2.00830E-10 2.52560E-10 210520 + 16 210530 Sc-53 2.64810E-10 2.73750E-10 210530 + 17 210540 Sc-54 1.44680E-10 1.47320E-10 210540 + 18 210550 Sc-55 7.97570E-11 7.97570E-11 210550 + 19 210560 Sc-56 1.67540E-11 1.67540E-11 210560 + 20 210570 Sc-57 2.68590E-12 2.68590E-12 210570 + 21 220500 Ti-50 1.43370E-12 1.25850E-10 22050.82c + 22 220510 Ti-51 1.33020E-11 2.11320E-10 220510 + 23 220520 Ti-52 1.01360E-10 3.53920E-10 220520 + 24 220530 Ti-53 2.93710E-10 5.67460E-10 220530 + 25 220540 Ti-54 7.33660E-10 8.80980E-10 220540 + 26 220550 Ti-55 9.48100E-10 1.02790E-09 220550 + 27 220560 Ti-56 1.05130E-09 1.06890E-09 220560 + 28 220570 Ti-57 4.63660E-10 4.65460E-10 220570 + 29 220580 Ti-58 1.41450E-10 1.41450E-10 220580 + 30 220590 Ti-59 2.63520E-11 2.63520E-11 220590 + 31 220600 Ti-60 3.03980E-12 3.03980E-12 220600 + 32 230520 V-52 1.03910E-12 3.54960E-10 230520 + 33 230530 V-53 1.63250E-11 5.83780E-10 230530 + 34 230540 V-54 9.81540E-11 9.79130E-10 230540 + 35 230550 V-55 5.88500E-10 1.61640E-09 230550 + 36 230560 V-56 1.42610E-09 2.49640E-09 230560 + 37 230570 V-57 2.95320E-09 3.41730E-09 230570 + 38 230580 V-58 2.20640E-09 2.34780E-09 230580 + 39 230590 V-59 2.26440E-09 2.29080E-09 230590 + 40 230600 V-60 7.42370E-10 7.45410E-10 230600 + 41 230610 V-61 2.20630E-10 2.20630E-10 230610 + 42 230620 V-62 2.52940E-11 2.52940E-11 230620 + 43 230630 V-63 2.12580E-12 2.12580E-12 230630 + 44 240540 Cr-54 1.13820E-12 9.80270E-10 24054.82c + 45 240550 Cr-55 1.85100E-11 1.63490E-09 240550 + 46 240560 Cr-56 2.32720E-10 2.74280E-09 240560 + 47 240570 Cr-57 1.11240E-09 6.39430E-09 240570 + 48 240580 Cr-58 6.09840E-09 6.56800E-09 240580 + 49 240590 Cr-59 8.57640E-09 1.08670E-08 240590 + 50 240600 Cr-60 1.37160E-08 1.44750E-08 240600 + 51 240610 Cr-61 1.04430E-08 1.06500E-08 240610 + 52 240620 Cr-62 6.84900E-09 6.87500E-09 240620 + 53 240630 Cr-63 1.68080E-09 1.68220E-09 240630 + 54 240640 Cr-64 3.23120E-10 3.23120E-10 240640 + 55 240650 Cr-65 2.83100E-11 2.83100E-11 240650 + 56 240660 Cr-66 1.42860E-12 1.42860E-12 240660 + 57 250570 Mn-57 1.78370E-11 6.41210E-09 250570 + 58 250580 Mn-58 1.43640E-10 6.71160E-09 250580 + 59 250581 Mn-58m 1.41190E-11 1.41190E-11 250581 + 60 250590 Mn-59 1.77670E-09 1.26440E-08 250590 + 61 250600 Mn-60 5.67950E-10 1.57070E-08 250600 + 62 250601 Mn-60m 5.77780E-09 5.77780E-09 250601 + 63 250610 Mn-61 2.18790E-08 3.25290E-08 250610 + 64 250620 Mn-62 2.82380E-08 3.16750E-08 250620 + 65 250621 Mn-62m 4.42220E-09 7.85970E-09 250621 + 66 250630 Mn-63 4.08640E-08 4.25460E-08 250630 + 67 250640 Mn-64 2.09930E-08 2.13160E-08 250640 + 68 250650 Mn-65 1.08640E-08 1.08920E-08 250650 + 69 250660 Mn-66 1.62940E-09 1.63080E-09 250660 + 70 250670 Mn-67 3.18310E-10 3.18310E-10 250670 + 71 250680 Mn-68 1.79410E-11 1.79410E-11 250680 + 72 260590 Fe-59 1.55900E-11 1.26590E-08 260590 + 73 260600 Fe-60 3.11420E-10 2.11320E-08 260600 + 74 260610 Fe-61 2.67570E-09 3.52050E-08 260610 + 75 260620 Fe-62 1.90100E-08 5.85450E-08 260620 + 76 260630 Fe-63 5.21230E-08 9.46690E-08 260630 + 77 260640 Fe-64 1.23020E-07 1.44340E-07 260640 + 78 260650 Fe-65 1.50680E-07 1.61570E-07 260650 + 79 260660 Fe-66 1.20520E-07 1.22150E-07 260660 + 80 260670 Fe-67 6.52940E-08 6.56120E-08 260670 + 81 260680 Fe-68 2.23250E-08 2.23430E-08 260680 + 82 260690 Fe-69 3.25380E-09 3.25380E-09 260690 + 83 260700 Fe-70 6.69730E-11 6.69730E-11 260700 + 84 260710 Fe-71 5.31210E-12 5.31210E-12 260710 + 85 270610 Co-61 1.16210E-11 3.52170E-08 270610 + 86 270620 Co-62 6.17720E-11 5.86080E-08 270620 + 87 270621 Co-62m 1.68380E-10 1.68380E-10 270621 + 88 270630 Co-63 3.38770E-09 9.80570E-08 270630 + 89 270640 Co-64 1.90520E-08 1.63390E-07 270640 + 90 270650 Co-65 1.07600E-07 2.69170E-07 270650 + 91 270660 Co-66 3.59340E-07 4.81490E-07 270660 + 92 270670 Co-67 4.82890E-07 5.48500E-07 270670 + 93 270680 Co-68 2.33960E-07 3.32560E-07 270680 + 94 270681 Co-68m 1.74630E-07 1.97200E-07 270681 + 95 270690 Co-69 3.31080E-07 3.34110E-07 270690 + 96 270700 Co-70 9.75000E-09 9.75000E-09 270700 + 97 270701 Co-70m 9.75000E-09 9.81700E-09 270701 + 98 270710 Co-71 9.58130E-09 9.58660E-09 270710 + 99 270720 Co-72 2.68280E-09 2.68280E-09 270720 + 100 270730 Co-73 2.03120E-10 2.03120E-10 270730 + 101 270740 Co-74 1.08940E-11 1.08940E-11 270740 + 102 280630 Ni-63 7.85090E-12 9.80650E-08 280630 + 103 280640 Ni-64 2.61890E-10 1.63650E-07 28064.82c + 104 280650 Ni-65 3.97690E-09 2.73150E-07 280650 + 105 280660 Ni-66 3.57360E-08 5.17230E-07 280660 + 106 280670 Ni-67 2.09690E-07 7.58190E-07 280670 + 107 280680 Ni-68 8.04320E-07 1.23880E-06 280680 + 108 280690 Ni-69 7.24850E-07 1.05560E-06 280690 + 109 280691 Ni-69m 7.24850E-07 7.24850E-07 280691 + 110 280700 Ni-70 4.20680E-07 4.40250E-07 280700 + 111 280710 Ni-71 1.35120E-06 1.36080E-06 280710 + 112 280720 Ni-72 8.63620E-07 8.66300E-07 280720 + 113 280730 Ni-73 1.91890E-07 1.92090E-07 280730 + 114 280740 Ni-74 6.30680E-08 6.30790E-08 280740 + 115 280750 Ni-75 3.50390E-09 3.50390E-09 280750 + 116 280760 Ni-76 1.77990E-10 1.77990E-10 280760 + 117 280770 Ni-77 4.30340E-12 4.30340E-12 280770 + 118 290650 Cu-65 4.46340E-12 2.73150E-07 29065.82c + 119 290660 Cu-66 1.17590E-10 5.17340E-07 290660 + 120 290670 Cu-67 3.96860E-09 7.62160E-07 290670 + 121 290680 Cu-68 1.05380E-08 1.27350E-06 290680 + 122 290681 Cu-68m 2.87240E-08 2.87240E-08 290681 + 123 290690 Cu-69 3.47470E-07 2.12790E-06 290690 + 124 290700 Cu-70 4.41890E-08 3.38470E-07 290700 + 125 290701 Cu-70m 5.64340E-07 5.88560E-07 290701 + 126 290702 Cu-70m 4.41890E-08 4.84440E-07 290702 + 127 290710 Cu-71 1.29130E-06 2.65210E-06 290710 + 128 290720 Cu-72 3.07340E-06 3.93970E-06 290720 + 129 290730 Cu-73 4.39910E-06 4.59120E-06 290730 + 130 290740 Cu-74 4.85590E-06 4.91900E-06 290740 + 131 290750 Cu-75 4.63520E-06 4.63870E-06 290750 + 132 290760 Cu-76 1.21970E-07 1.22060E-07 290760 + 133 290761 Cu-76m 1.21970E-07 1.22060E-07 290761 + 134 290770 Cu-77 4.17160E-08 4.17200E-08 290770 + 135 290780 Cu-78 2.67760E-09 2.67760E-09 290780 + 136 290790 Cu-79 9.78190E-11 9.78190E-11 290790 + 137 300670 Zn-67 2.32630E-12 7.62160E-07 300670 + 138 300680 Zn-68 1.42990E-10 1.27820E-06 300680 + 139 300690 Zn-69 6.05490E-10 2.13150E-06 300690 + 140 300691 Zn-69m 3.00720E-09 3.00720E-09 300691 + 141 300700 Zn-70 1.29010E-08 1.10590E-06 300700 + 142 300710 Zn-71 1.13220E-07 2.76530E-06 300710 + 143 300711 Zn-71m 5.62310E-07 5.62310E-07 300711 + 144 300720 Zn-72 6.14510E-06 1.00850E-05 300720 + 145 300730 Zn-73 7.71320E-07 9.90820E-06 300730 + 146 300731 Zn-73m 1.06680E-06 4.54570E-06 300731 + 147 300732 Zn-73m 6.95770E-06 6.95770E-06 300732 + 148 300740 Zn-74 3.39370E-05 3.90180E-05 300740 + 149 300750 Zn-75 2.43400E-05 2.88200E-05 300750 + 150 300760 Zn-76 3.33490E-05 3.35900E-05 300760 + 151 300770 Zn-77 9.87340E-06 1.05720E-05 300770 + 152 300771 Zn-77m 1.31460E-06 1.31460E-06 300771 + 153 300780 Zn-78 1.42150E-05 1.42180E-05 300780 + 154 300790 Zn-79 4.60450E-07 4.60490E-07 300790 + 155 300800 Zn-80 4.63530E-08 4.63530E-08 300800 + 156 300810 Zn-81 1.31010E-09 1.31010E-09 300810 + 157 300820 Zn-82 4.12080E-11 4.12080E-11 300820 + 158 310690 Ga-69 1.00320E-12 2.13150E-06 310690 + 159 310700 Ga-70 1.10040E-11 1.10040E-11 310700 + 160 310710 Ga-71 9.47650E-10 3.32860E-06 310710 + 161 310720 Ga-72 4.17330E-08 1.01310E-05 310720 + 162 310721 Ga-72m 4.10220E-09 3.40130E-07 310721 + 163 310730 Ga-73 1.09940E-06 1.44860E-05 310730 + 164 310740 Ga-74 3.18010E-06 3.48290E-05 310740 + 165 310741 Ga-74m 3.18010E-06 4.21980E-05 310741 + 166 310750 Ga-75 1.73650E-05 4.61850E-05 310750 + 167 310760 Ga-76 2.73460E-05 6.09350E-05 310760 + 168 310770 Ga-77 7.58690E-05 8.70990E-05 310770 + 169 310780 Ga-78 6.46980E-05 7.89220E-05 310780 + 170 310790 Ga-79 6.47690E-05 6.52240E-05 310790 + 171 310800 Ga-80 1.98380E-05 1.98840E-05 310800 + 172 310810 Ga-81 6.83550E-06 6.83670E-06 310810 + 173 310820 Ga-82 2.31690E-07 2.31730E-07 310820 + 174 310830 Ga-83 1.65100E-08 1.65100E-08 310830 + 175 310840 Ga-84 3.97010E-10 3.97010E-10 310840 + 176 320720 Ge-72 4.26490E-11 1.01310E-05 32072.82c + 177 320730 Ge-73 1.40270E-09 1.44880E-05 32073.82c + 178 320731 Ge-73m 2.82420E-10 1.42740E-05 320731 + 179 320740 Ge-74 9.59350E-08 4.54750E-05 32074.82c + 180 320750 Ge-75 4.08190E-07 4.96570E-05 320750 + 181 320751 Ge-75m 3.06580E-06 4.91320E-06 320751 + 182 320760 Ge-76 1.06980E-05 7.16340E-05 32076.82c + 183 320770 Ge-77 4.92360E-05 6.70310E-05 320770 + 184 320771 Ge-77m 6.55560E-06 9.36540E-05 320771 + 185 320780 Ge-78 1.89440E-04 2.68420E-04 320780 + 186 320790 Ge-79 3.39500E-05 1.09220E-04 320790 + 187 320791 Ge-79m 2.54990E-04 2.55090E-04 320791 + 188 320800 Ge-80 4.54970E-04 4.75670E-04 320800 + 189 320810 Ge-81 2.13920E-04 2.17580E-04 320810 + 190 320811 Ge-81m 4.30720E-05 4.59390E-05 320811 + 191 320820 Ge-82 1.57750E-04 1.57940E-04 320820 + 192 320830 Ge-83 2.05340E-05 2.05450E-05 320830 + 193 320840 Ge-84 5.37180E-06 5.37190E-06 320840 + 194 320850 Ge-85 1.54790E-07 1.54790E-07 320850 + 195 320860 Ge-86 6.71890E-09 6.71890E-09 320860 + 196 320870 Ge-87 1.83850E-10 1.83850E-10 320870 + 197 330740 As-74 2.07970E-11 2.07970E-11 330740 + 198 330750 As-75 2.59520E-10 4.96600E-05 33075.82c + 199 330751 As-75m 9.82780E-10 2.45670E-09 330751 + 200 330760 As-76 3.30560E-08 3.30560E-08 330760 + 201 330770 As-77 9.76480E-07 1.43870E-04 330770 + 202 330780 As-78 1.15920E-05 2.80010E-04 330780 + 203 330790 As-79 5.67790E-05 4.10880E-04 330790 + 204 330800 As-80 1.83170E-04 6.58840E-04 330800 + 205 330810 As-81 3.80090E-04 6.43150E-04 330810 + 206 330820 As-82 1.00440E-04 2.58380E-04 330820 + 207 330821 As-82m 3.49970E-04 3.49970E-04 330821 + 208 330830 As-83 5.83830E-04 6.04960E-04 330830 + 209 330840 As-84 1.23760E-04 1.26170E-04 330840 + 210 330841 As-84m 1.23760E-04 1.26170E-04 330841 + 211 330850 As-85 1.05880E-04 1.06010E-04 330850 + 212 330860 As-86 2.38960E-05 2.39030E-05 330860 + 213 330870 As-87 3.26750E-06 3.26770E-06 330870 + 214 330880 As-88 5.26350E-08 5.26350E-08 330880 + 215 330890 As-89 1.54930E-09 1.54930E-09 330890 + 216 340760 Se-76 7.73820E-12 3.30640E-08 34076.82c + 217 340770 Se-77 8.09060E-11 1.43870E-04 34077.82c + 218 340771 Se-77m 6.07650E-10 6.07650E-10 340771 + 219 340780 Se-78 4.78810E-08 2.80060E-04 34078.82c + 220 340790 Se-79 5.16520E-06 4.16510E-04 34079.82c + 221 340791 Se-79m 6.87720E-07 4.01840E-04 340791 + 222 340800 Se-80 1.85860E-05 6.77430E-04 34080.82c + 223 340810 Se-81 1.67430E-05 7.85570E-04 340810 + 224 340811 Se-81m 1.25750E-04 1.48840E-04 340811 + 225 340820 Se-82 5.17340E-04 1.12570E-03 34082.82c + 226 340830 Se-83 9.24380E-04 1.14230E-03 340830 + 227 340831 Se-83m 1.86120E-04 5.73470E-04 340831 + 228 340840 Se-84 2.12540E-03 2.40070E-03 340840 + 229 340850 Se-85 1.69320E-03 1.78380E-03 340850 + 230 340860 Se-86 1.35660E-03 1.37310E-03 340860 + 231 340870 Se-87 5.24190E-04 5.26950E-04 340870 + 232 340880 Se-88 1.80990E-04 1.81040E-04 340880 + 233 340890 Se-89 3.17090E-05 3.17110E-05 340890 + 234 340900 Se-90 5.48770E-06 5.48770E-06 340900 + 235 340910 Se-91 1.65620E-08 1.65620E-08 340910 + 236 350790 Br-79 6.64110E-11 2.25350E-07 35079.82c + 237 350791 Br-79m 2.51500E-10 2.51500E-10 350791 + 238 350800 Br-80 3.81530E-09 1.71090E-08 350800 + 239 350801 Br-80m 1.32940E-08 1.32940E-08 350801 + 240 350810 Br-81 5.20840E-07 7.86160E-04 35081.82c + 241 350820 Br-82 4.06500E-06 5.52050E-06 350820 + 242 350821 Br-82m 1.49130E-06 1.49130E-06 350821 + 243 350830 Br-83 7.75480E-05 1.79340E-03 350830 + 244 350840 Br-84 1.52660E-04 2.55340E-03 350840 + 245 350841 Br-84m 1.52660E-04 1.52660E-04 350841 + 246 350850 Br-85 1.30070E-03 3.08450E-03 350850 + 247 350860 Br-86 1.92650E-03 3.29960E-03 350860 + 248 350870 Br-87 2.88260E-03 3.41140E-03 350870 + 249 350880 Br-88 2.16970E-03 2.35140E-03 350880 + 250 350890 Br-89 1.34980E-03 1.37900E-03 350890 + 251 350900 Br-90 3.94730E-04 4.00220E-04 350900 + 252 350910 Br-91 1.28400E-04 1.28410E-04 350910 + 253 350920 Br-92 1.97720E-05 1.97720E-05 350920 + 254 350930 Br-93 3.31400E-06 3.31400E-06 350930 + 255 350940 Br-94 3.08700E-09 3.08700E-09 350940 + 256 360810 Kr-81 8.40860E-11 9.52820E-11 360810 + 257 360811 Kr-81m 1.11960E-11 1.11960E-11 360811 + 258 360820 Kr-82 8.24160E-09 5.56450E-06 36082.82c + 259 360830 Kr-83 2.56000E-07 1.79370E-03 36083.82c + 260 360831 Kr-83m 5.15450E-08 1.79180E-03 360831 + 261 360840 Kr-84 2.14660E-05 2.72750E-03 36084.82c + 262 360850 Kr-85 1.50080E-04 8.20570E-04 36085.82c + 263 360851 Kr-85m 3.02180E-05 3.10970E-03 360851 + 264 360860 Kr-86 1.00580E-03 4.39100E-03 36086.82c + 265 360870 Kr-87 2.56950E-03 6.05280E-03 360870 + 266 360880 Kr-88 5.71760E-03 8.10590E-03 360880 + 267 360890 Kr-89 6.96770E-03 8.25070E-03 360890 + 268 360900 Kr-90 7.12600E-03 7.45350E-03 360900 + 269 360910 Kr-91 4.05050E-03 4.15980E-03 360910 + 270 360920 Kr-92 1.97660E-03 1.99210E-03 360920 + 271 360930 Kr-93 4.58440E-04 4.59500E-04 360930 + 272 360940 Kr-94 1.23970E-04 1.23970E-04 360940 + 273 360950 Kr-95 8.84820E-06 8.84820E-06 360950 + 274 360960 Kr-96 3.79160E-08 3.79160E-08 360960 + 275 370840 Rb-84 7.26200E-10 2.24970E-09 370840 + 276 370841 Rb-84m 1.52350E-09 1.52350E-09 370841 + 277 370850 Rb-85 1.08540E-06 3.26590E-03 37085.82c + 278 370860 Rb-86 3.86130E-06 1.19620E-05 37086.82c + 279 370861 Rb-86m 8.10070E-06 8.10070E-06 370861 + 280 370870 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38088.82c + 300 380890 Sr-89 1.52150E-04 1.03990E-02 38089.82c + 301 380900 Sr-90 1.11250E-03 1.30460E-02 38090.82c + 302 380910 Sr-91 3.42250E-03 1.60850E-02 380910 + 303 380920 Sr-92 1.02640E-02 2.07540E-02 380920 + 304 380930 Sr-93 1.51550E-02 2.30920E-02 380930 + 305 380940 Sr-94 2.13410E-02 2.45140E-02 380940 + 306 380950 Sr-95 1.49800E-02 1.63460E-02 380950 + 307 380960 Sr-96 9.92740E-03 1.01840E-02 380960 + 308 380970 Sr-97 3.44930E-03 3.48870E-03 380970 + 309 380980 Sr-98 1.16080E-03 1.16470E-03 380980 + 310 380990 Sr-99 2.01360E-04 2.01360E-04 380990 + 311 381000 Sr-100 2.83460E-05 2.83460E-05 381000 + 312 381010 Sr-101 3.55120E-08 3.55120E-08 381010 + 313 390880 Y-88 1.11220E-10 2.09700E-10 390880 + 314 390881 Y-88m 9.84750E-11 9.84750E-11 390881 + 315 390890 Y-89 1.83290E-07 1.04010E-02 39089.82c + 316 390891 Y-89m 9.10310E-07 1.91270E-06 390891 + 317 390900 Y-90 1.23220E-06 1.30490E-02 39090.82c + 318 390901 Y-90m 2.06060E-06 2.06060E-06 390901 + 319 390910 Y-91 7.36350E-06 1.61290E-02 39091.82c + 320 390911 Y-91m 3.65720E-05 9.50050E-03 390911 + 321 390920 Y-92 3.23790E-04 2.10780E-02 390920 + 322 390930 Y-93 2.59530E-04 2.53010E-02 390930 + 323 390931 Y-93m 1.94930E-03 7.72790E-03 390931 + 324 390940 Y-94 5.73900E-03 3.02530E-02 390940 + 325 390950 Y-95 1.46590E-02 3.10050E-02 390950 + 326 390960 Y-96 5.89140E-03 1.60770E-02 390960 + 327 390961 Y-96m 1.23600E-02 1.23600E-02 390961 + 328 390970 Y-97 3.30980E-03 6.39070E-03 390970 + 329 390971 Y-97m 1.22340E-02 1.61160E-02 390971 + 330 390972 Y-97m 4.20430E-03 4.20430E-03 390972 + 331 390980 Y-98 2.00530E-03 3.17000E-03 390980 + 332 390981 Y-98m 9.72170E-03 9.72170E-03 390981 + 333 390990 Y-99 6.72580E-03 6.92740E-03 390990 + 334 391000 Y-100 1.02790E-03 1.05600E-03 391000 + 335 391001 Y-100m 1.02790E-03 1.02790E-03 391001 + 336 391010 Y-101 6.02480E-04 6.02510E-04 391010 + 337 391020 Y-102 3.61430E-05 3.61430E-05 391020 + 338 391021 Y-102m 3.61430E-05 3.61430E-05 391021 + 339 391030 Y-103 1.18100E-05 1.18100E-05 391030 + 340 391040 Y-104 3.00610E-09 3.00610E-09 391040 + 341 400910 Zr-91 2.92270E-09 1.61290E-02 40091.82c + 342 400920 Zr-92 7.69070E-06 2.10860E-02 40092.82c + 343 400930 Zr-93 8.84740E-05 2.53900E-02 40093.82c + 344 400940 Zr-94 6.67470E-04 3.09210E-02 40094.82c + 345 400950 Zr-95 2.45190E-03 3.34570E-02 40095.82c + 346 400960 Zr-96 1.02270E-02 3.86770E-02 40096.82c + 347 400970 Zr-97 1.86780E-02 4.22430E-02 400970 + 348 400980 Zr-98 3.30660E-02 4.57330E-02 400980 + 349 400990 Zr-99 2.96180E-02 3.64370E-02 400990 + 350 401000 Zr-100 2.57190E-02 2.77930E-02 401000 + 351 401010 Zr-101 1.21830E-02 1.27890E-02 401010 + 352 401020 Zr-102 5.48310E-03 5.55280E-03 401020 + 353 401030 Zr-103 1.23040E-03 1.24130E-03 401030 + 354 401040 Zr-104 2.74610E-04 2.74610E-04 401040 + 355 401050 Zr-105 3.07930E-05 3.07930E-05 401050 + 356 401060 Zr-106 3.22020E-08 3.22020E-08 401060 + 357 410930 Nb-93 6.16720E-10 7.40900E-10 41093.82c + 358 410931 Nb-93m 1.24170E-10 1.24170E-10 410931 + 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3.29560E-03 3.32600E-03 411050 + 379 411060 Nb-106 6.60360E-04 6.60390E-04 411060 + 380 411070 Nb-107 1.34640E-04 1.34640E-04 411070 + 381 411080 Nb-108 2.25170E-05 2.25170E-05 411080 + 382 411090 Nb-109 1.82170E-06 1.82170E-06 411090 + 383 420960 Mo-96 3.36860E-06 1.51800E-04 42096.82c + 384 420970 Mo-97 1.85170E-05 4.34720E-02 42097.82c + 385 420980 Mo-98 2.19840E-04 4.96660E-02 42098.82c + 386 420990 Mo-99 1.00380E-03 5.00700E-02 42099.82c + 387 421000 Mo-100 5.25540E-03 5.35260E-02 42100.82c + 388 421010 Mo-101 1.20400E-02 5.59010E-02 421010 + 389 421020 Mo-102 2.89600E-02 5.91690E-02 421020 + 390 421030 Mo-103 3.40020E-02 5.39190E-02 421030 + 391 421040 Mo-104 3.85480E-02 4.65580E-02 421040 + 392 421050 Mo-105 2.38840E-02 2.71830E-02 421050 + 393 421060 Mo-106 1.50090E-02 1.56480E-02 421060 + 394 421070 Mo-107 4.73520E-03 4.86320E-03 421070 + 395 421080 Mo-108 1.58620E-03 1.60750E-03 421080 + 396 421090 Mo-109 2.46470E-04 2.48060E-04 421090 + 397 421100 Mo-110 3.15660E-05 3.15660E-05 421100 + 398 421110 Mo-111 1.77640E-06 1.77640E-06 421110 + 399 430980 Tc-98 1.20790E-09 1.20790E-09 430980 + 400 430990 Tc-99 7.83430E-06 5.00780E-02 43099.82c + 401 430991 Tc-99m 1.57740E-06 4.40930E-02 430991 + 402 431000 Tc-100 5.25320E-05 5.25320E-05 431000 + 403 431010 Tc-101 3.99730E-04 5.63010E-02 431010 + 404 431020 Tc-102 7.88050E-04 5.99570E-02 431020 + 405 431021 Tc-102m 7.88050E-04 7.88050E-04 431021 + 406 431030 Tc-103 6.46380E-03 6.03820E-02 431030 + 407 431040 Tc-104 1.30160E-02 5.95740E-02 431040 + 408 431050 Tc-105 2.70960E-02 5.42790E-02 431050 + 409 431060 Tc-106 2.68490E-02 4.24970E-02 431060 + 410 431070 Tc-107 2.66480E-02 3.15110E-02 431070 + 411 431080 Tc-108 1.45130E-02 1.61220E-02 431080 + 412 431090 Tc-109 7.97490E-03 8.22170E-03 431090 + 413 431100 Tc-110 2.41830E-03 2.44990E-03 431100 + 414 431110 Tc-111 6.71720E-04 6.73480E-04 431110 + 415 431120 Tc-112 8.26800E-05 8.26800E-05 431120 + 416 431130 Tc-113 8.07780E-06 8.07780E-06 431130 + 417 431140 Tc-114 1.53410E-10 1.53410E-10 431140 + 418 441010 Ru-101 2.05010E-06 5.63030E-02 44101.82c + 419 441020 Ru-102 4.58650E-05 6.07910E-02 44102.82c + 420 441030 Ru-103 6.95770E-05 6.06470E-02 44103.82c + 421 441031 Ru-103m 1.94670E-04 1.94670E-04 441031 + 422 441040 Ru-104 1.43790E-03 6.10120E-02 44104.82c + 423 441050 Ru-105 4.40680E-03 5.86860E-02 44105.82c + 424 441060 Ru-106 1.27160E-02 5.52130E-02 44106.82c + 425 441070 Ru-107 1.80830E-02 4.95940E-02 441070 + 426 441080 Ru-108 2.56430E-02 4.17710E-02 441080 + 427 441090 Ru-109 2.01360E-02 2.83520E-02 441090 + 428 441100 Ru-110 1.54390E-02 1.78880E-02 441100 + 429 441110 Ru-111 6.54530E-03 7.22000E-03 441110 + 430 441120 Ru-112 2.55680E-03 2.63880E-03 441120 + 431 441130 Ru-113 2.45740E-04 3.76100E-04 441130 + 432 441131 Ru-113m 2.45740E-04 2.45740E-04 441131 + 433 441140 Ru-114 7.40380E-05 7.40380E-05 441140 + 434 441150 Ru-115 8.97530E-06 8.97530E-06 441150 + 435 441160 Ru-116 7.73400E-07 7.73400E-07 441160 + 436 451030 Rh-103 1.15660E-07 6.06480E-02 45103.82c + 437 451031 Rh-103m 8.68670E-07 5.99210E-02 451031 + 438 451040 Rh-104 1.48640E-06 6.65900E-06 451040 + 439 451041 Rh-104m 5.17920E-06 5.17920E-06 451041 + 440 451050 Rh-105 6.54450E-05 5.87600E-02 45105.82c + 441 451051 Rh-105m 8.71370E-06 1.66680E-02 451051 + 442 451060 Rh-106 1.00250E-04 5.53130E-02 451060 + 443 451061 Rh-106m 2.73280E-04 2.73280E-04 451061 + 444 451070 Rh-107 1.54780E-03 5.11420E-02 451070 + 445 451080 Rh-108 8.82970E-04 4.26540E-02 451080 + 446 451081 Rh-108m 3.07650E-03 3.07650E-03 451081 + 447 451090 Rh-109 8.96450E-03 3.73170E-02 451090 + 448 451100 Rh-110 1.10520E-02 2.89400E-02 451100 + 449 451101 Rh-110m 2.60180E-04 2.60180E-04 451101 + 450 451110 Rh-111 1.31380E-02 2.03580E-02 451110 + 451 451120 Rh-112 4.07350E-03 6.71230E-03 451120 + 452 451121 Rh-112m 4.07350E-03 4.07350E-03 451121 + 453 451130 Rh-113 4.78790E-03 5.28690E-03 451130 + 454 451140 Rh-114 7.85700E-04 8.59760E-04 451140 + 455 451141 Rh-114m 7.85700E-04 7.85700E-04 451141 + 456 451150 Rh-115 4.59790E-04 4.68750E-04 451150 + 457 451160 Rh-116 2.13010E-05 2.20660E-05 451160 + 458 451161 Rh-116m 5.80630E-05 5.80630E-05 451161 + 459 451170 Rh-117 3.15230E-05 3.15230E-05 451170 + 460 451180 Rh-118 6.66090E-06 6.66090E-06 451180 + 461 451190 Rh-119 2.70260E-06 2.70260E-06 451190 + 462 461060 Pd-106 2.87330E-06 5.55890E-02 46106.82c + 463 461070 Pd-107 8.08490E-06 5.11680E-02 46107.82c + 464 461071 Pd-107m 1.77700E-05 1.77700E-05 461071 + 465 461080 Pd-108 1.70640E-04 4.59020E-02 46108.82c + 466 461090 Pd-109 2.11250E-04 3.79920E-02 461090 + 467 461091 Pd-109m 4.64310E-04 1.91230E-02 461091 + 468 461100 Pd-110 2.03720E-03 3.12370E-02 46110.82c + 469 461110 Pd-111 1.06410E-03 2.31070E-02 461110 + 470 461111 Pd-111m 2.33880E-03 2.42030E-03 461111 + 471 461120 Pd-112 5.49040E-03 1.62760E-02 461120 + 472 461130 Pd-113 1.21810E-03 9.91300E-03 461130 + 473 461131 Pd-113m 3.40810E-03 3.40810E-03 461131 + 474 461140 Pd-114 3.57190E-03 5.21740E-03 461140 + 475 461150 Pd-115 4.24900E-04 9.05740E-04 461150 + 476 461151 Pd-115m 9.33900E-04 1.00200E-03 461151 + 477 461160 Pd-116 6.66420E-04 7.46550E-04 461160 + 478 461170 Pd-117 5.05700E-05 1.93440E-04 461170 + 479 461171 Pd-117m 1.11150E-04 1.11150E-04 461171 + 480 461180 Pd-118 4.68630E-05 5.33300E-05 461180 + 481 461190 Pd-119 8.83340E-06 1.15360E-05 461190 + 482 461200 Pd-120 1.91010E-06 1.91010E-06 461200 + 483 461210 Pd-121 8.45040E-11 8.45040E-11 461210 + 484 461230 Pd-123 4.72110E-08 4.72110E-08 461230 + 485 461240 Pd-124 3.04260E-09 3.04260E-09 461240 + 486 471080 Ag-108 6.04650E-10 7.48040E-10 471080 + 487 471081 Ag-108m 1.64810E-09 1.64810E-09 471081 + 488 471090 Ag-109 5.35270E-07 3.79970E-02 47109.82c + 489 471091 Ag-109m 4.02020E-06 3.79780E-02 471091 + 490 471100 Ag-110 6.30340E-06 6.53700E-06 471100 + 491 471101 Ag-110m 1.71820E-05 1.71820E-05 47510.82c + 492 471110 Ag-111 1.88410E-05 2.38030E-02 47111.82c + 493 471111 Ag-111m 1.41510E-04 2.35510E-02 471111 + 494 471120 Ag-112 3.86700E-04 1.66630E-02 471120 + 495 471130 Ag-113 1.00300E-04 7.07810E-03 471130 + 496 471131 Ag-113m 7.53320E-04 1.02460E-02 471131 + 497 471140 Ag-114 1.80350E-04 6.27210E-03 471140 + 498 471141 Ag-114m 8.74350E-04 8.74350E-04 471141 + 499 471150 Ag-115 1.26970E-04 1.23340E-03 471150 + 500 471151 Ag-115m 9.53630E-04 2.12000E-03 471151 + 501 471160 Ag-116 1.82150E-04 9.58490E-04 471160 + 502 471161 Ag-116m 4.96510E-04 4.96510E-04 471161 + 503 471170 Ag-117 5.55930E-05 1.83170E-04 471170 + 504 471171 Ag-117m 4.17540E-04 5.14260E-04 471171 + 505 471180 Ag-118 3.51150E-05 1.53740E-04 471180 + 506 471181 Ag-118m 1.70230E-04 1.77860E-04 471181 + 507 471190 Ag-119 1.23450E-05 1.81120E-05 471190 + 508 471191 Ag-119m 9.27150E-05 9.84830E-05 471191 + 509 471200 Ag-120 7.46570E-06 1.33940E-05 471200 + 510 471201 Ag-120m 1.24850E-05 1.34400E-05 471201 + 511 471210 Ag-121 3.99760E-05 3.99760E-05 471210 + 512 471220 Ag-122 1.01300E-05 1.01300E-05 471220 + 513 471221 Ag-122m 1.09210E-05 1.09210E-05 471221 + 514 471230 Ag-123 2.52430E-05 2.52900E-05 471230 + 515 471240 Ag-124 1.03710E-06 1.59920E-06 471240 + 516 471241 Ag-124m 1.11810E-06 1.11810E-06 471241 + 517 471250 Ag-125 1.01670E-06 1.01670E-06 471250 + 518 471260 Ag-126 3.78520E-08 3.78520E-08 471260 + 519 471270 Ag-127 1.75850E-09 1.75850E-09 471270 + 520 481110 Cd-111 1.85430E-07 2.39220E-02 48111.82c + 521 481111 Cd-111m 7.02200E-07 7.02200E-07 481111 + 522 481120 Cd-112 5.37530E-06 1.66680E-02 48112.82c + 523 481130 Cd-113 6.58850E-06 1.06510E-02 48113.82c + 524 481131 Cd-113m 2.49510E-05 1.47320E-04 481131 + 525 481140 Cd-114 7.56530E-05 6.34770E-03 48114.82c + 526 481150 Cd-115 2.28830E-05 2.81120E-03 481150 + 527 481151 Cd-115m 8.66570E-05 2.06490E-04 48515.82c + 528 481160 Cd-116 1.30650E-04 1.55590E-03 48116.82c + 529 481170 Cd-117 2.62880E-05 5.42110E-04 481170 + 530 481171 Cd-117m 9.95520E-05 2.50300E-04 481171 + 531 481180 Cd-118 1.44190E-04 4.02870E-04 481180 + 532 481190 Cd-119 2.79180E-05 1.35460E-04 481190 + 533 481191 Cd-119m 7.81120E-05 8.71690E-05 481191 + 534 481200 Cd-120 7.78430E-05 9.97040E-05 481200 + 535 481210 Cd-121 4.09060E-05 7.67050E-05 481210 + 536 481211 Cd-121m 1.14450E-04 1.18630E-04 481211 + 537 481220 Cd-122 1.93640E-04 2.14690E-04 481220 + 538 481230 Cd-123 5.77210E-05 7.84130E-05 481230 + 539 481231 Cd-123m 1.61500E-04 1.66100E-04 481231 + 540 481240 Cd-124 2.94670E-04 2.96830E-04 481240 + 541 481250 Cd-125 4.22410E-05 4.27500E-05 481250 + 542 481251 Cd-125m 1.18190E-04 1.18700E-04 481251 + 543 481260 Cd-126 6.27750E-05 6.28130E-05 481260 + 544 481270 Cd-127 1.90500E-05 1.90520E-05 481270 + 545 481280 Cd-128 3.73350E-06 3.73350E-06 481280 + 546 481290 Cd-129 8.45270E-09 8.45270E-09 481290 + 547 481291 Cd-129m 2.36500E-08 2.36500E-08 481291 + 548 481300 Cd-130 8.12090E-10 8.12090E-10 481300 + 549 491130 In-113 5.31370E-10 1.47120E-04 49113.82c + 550 491131 In-113m 1.06990E-10 1.06990E-10 491131 + 551 491140 In-114 1.91820E-07 8.36790E-07 491140 + 552 491141 In-114m 3.09750E-07 6.68360E-07 491141 + 553 491142 In-114m 3.58610E-07 3.58610E-07 491142 + 554 491150 In-115 2.70000E-06 2.88030E-03 49115.82c + 555 491151 In-115m 5.43630E-07 2.81180E-03 491151 + 556 491160 In-116 1.02480E-06 1.02480E-06 491160 + 557 491161 In-116m 1.65490E-06 3.57080E-06 491161 + 558 491162 In-116m 1.91590E-06 1.91590E-06 491162 + 559 491170 In-117 9.92220E-06 5.38450E-04 491170 + 560 491171 In-117m 1.99780E-06 5.02610E-04 491171 + 561 491180 In-118 3.81130E-06 4.06680E-04 491180 + 562 491181 In-118m 6.15450E-06 1.31800E-05 491181 + 563 491182 In-118m 7.12520E-06 7.12520E-06 491182 + 564 491190 In-119 1.61010E-05 1.23290E-04 491190 + 565 491191 In-119m 3.24190E-06 1.25720E-04 491191 + 566 491200 In-120 7.10530E-06 1.06810E-04 491200 + 567 491201 In-120m 7.10530E-06 7.10530E-06 491201 + 568 491202 In-120m 7.10530E-06 7.10530E-06 491202 + 569 491210 In-121 1.14320E-04 2.59670E-04 491210 + 570 491211 In-121m 2.30180E-05 7.38900E-05 491211 + 571 491220 In-122 5.76010E-05 2.72290E-04 491220 + 572 491221 In-122m 4.81650E-05 4.81650E-05 491221 + 573 491222 In-122m 4.81650E-05 4.81650E-05 491222 + 574 491230 In-123 2.82160E-04 4.70520E-04 491230 + 575 491231 In-123m 5.68110E-05 1.12960E-04 491231 + 576 491240 In-124 2.48080E-04 5.44910E-04 491240 + 577 491241 In-124m 2.67470E-04 2.67470E-04 491241 + 578 491250 In-125 8.89670E-04 1.02880E-03 491250 + 579 491251 In-125m 1.79130E-04 2.01420E-04 491251 + 580 491260 In-126 4.60770E-04 5.23590E-04 491260 + 581 491261 In-126m 4.96780E-04 4.96780E-04 491261 + 582 491270 In-127 8.83180E-04 8.83180E-04 491270 + 583 491271 In-127m 1.77820E-04 1.96880E-04 491271 + 584 491280 In-128 1.82260E-04 2.57360E-04 491280 + 585 491281 In-128m 7.13670E-05 7.51000E-05 491281 + 586 491282 In-128m 2.73450E-04 2.73450E-04 491282 + 587 491290 In-129 2.04930E-04 2.04950E-04 491290 + 588 491291 In-129m 4.12610E-05 4.12700E-05 491291 + 589 491300 In-130 9.67930E-06 9.68010E-06 491300 + 590 491301 In-130m 1.40940E-05 1.40940E-05 491301 + 591 491302 In-130m 1.96320E-05 1.96320E-05 491302 + 592 491310 In-131 2.45890E-06 2.48390E-06 491310 + 593 491311 In-131m 2.45890E-06 2.45890E-06 491311 + 594 491312 In-131m 2.45890E-06 2.45890E-06 491312 + 595 491320 In-132 8.56840E-09 8.56840E-09 491320 + 596 501160 Sn-116 1.18370E-09 4.59680E-06 50116.82c + 597 501170 Sn-117 4.37370E-09 8.04350E-04 50117.82c + 598 501171 Sn-117m 1.65630E-08 1.85110E-06 501171 + 599 501180 Sn-118 2.99030E-07 4.20260E-04 50118.82c + 600 501190 Sn-119 1.40600E-07 2.42640E-04 50119.82c + 601 501191 Sn-119m 5.32460E-07 1.11910E-04 501191 + 602 501200 Sn-120 1.50270E-06 1.22540E-04 50120.82c + 603 501210 Sn-121 4.05380E-06 3.38940E-04 501210 + 604 501211 Sn-121m 1.13420E-05 4.07590E-05 501211 + 605 501220 Sn-122 3.64700E-05 4.05180E-04 50122.82c + 606 501230 Sn-123 7.89820E-05 1.14850E-04 50123.82c + 607 501231 Sn-123m 2.82280E-05 5.75840E-04 501231 + 608 501240 Sn-124 3.93400E-04 1.20580E-03 50124.82c + 609 501250 Sn-125 6.56010E-04 8.29800E-04 50125.82c + 610 501251 Sn-125m 2.34460E-04 1.29090E-03 501251 + 611 501260 Sn-126 2.47600E-03 3.49770E-03 50126.82c + 612 501270 Sn-127 2.86640E-03 3.21070E-03 501270 + 613 501271 Sn-127m 1.02450E-03 1.75890E-03 501271 + 614 501280 Sn-128 1.66050E-03 6.71750E-03 501280 + 615 501281 Sn-128m 4.52620E-03 4.79960E-03 501281 + 616 501290 Sn-129 1.11030E-03 1.33480E-03 501290 + 617 501291 Sn-129m 3.10660E-03 3.12840E-03 501291 + 618 501300 Sn-130 7.54900E-04 7.81440E-04 501300 + 619 501301 Sn-130m 2.05770E-03 2.07460E-03 501301 + 620 501310 Sn-131 2.54830E-04 2.59590E-04 501310 + 621 501311 Sn-131m 7.12990E-04 7.15560E-04 501311 + 622 501320 Sn-132 2.35510E-04 2.35520E-04 501320 + 623 501330 Sn-133 1.59420E-05 1.59420E-05 501330 + 624 501340 Sn-134 1.15880E-07 1.15880E-07 501340 + 625 501350 Sn-135 2.06700E-09 2.06700E-09 501350 + 626 511180 Sb-118 1.14750E-11 1.14750E-11 511180 + 627 511181 Sb-118m 1.91910E-11 1.91910E-11 511181 + 628 511190 Sb-119 8.72970E-10 1.22350E-09 511190 + 629 511191 Sb-119m 3.50530E-10 3.50530E-10 511191 + 630 511200 Sb-120 5.64480E-09 5.64480E-09 511200 + 631 511201 Sb-120m 9.44020E-09 9.44020E-09 511201 + 632 511210 Sb-121 8.32950E-07 3.48900E-04 51121.82c + 633 511220 Sb-122 1.39110E-06 3.25490E-06 511220 + 634 511221 Sb-122m 1.86380E-06 1.86380E-06 511221 + 635 511230 Sb-123 9.57750E-06 7.00270E-04 51123.82c + 636 511240 Sb-124 1.00230E-05 2.57950E-05 51124.82c + 637 511241 Sb-124m 8.08520E-06 2.10290E-05 511241 + 638 511242 Sb-124m 1.29440E-05 1.29440E-05 511242 + 639 511250 Sb-125 1.15480E-04 2.23620E-03 51125.82c + 640 511260 Sb-126 1.32180E-04 1.58070E-04 51126.82c + 641 511261 Sb-126m 8.25620E-05 1.84910E-04 511261 + 642 511262 Sb-126m 1.02350E-04 1.02350E-04 511262 + 643 511270 Sb-127 1.63200E-03 6.60160E-03 511270 + 644 511280 Sb-128 1.66910E-03 8.47060E-03 511280 + 645 511281 Sb-128m 2.33440E-03 2.33440E-03 511281 + 646 511290 Sb-129 6.16190E-03 9.97950E-03 511290 + 647 511291 Sb-129m 4.56010E-03 6.12420E-03 511291 + 648 511300 Sb-130 5.66600E-03 7.48480E-03 511300 + 649 511301 Sb-130m 5.66600E-03 6.70330E-03 511301 + 650 511310 Sb-131 1.39680E-02 1.49430E-02 511310 + 651 511320 Sb-132 4.22370E-03 4.45920E-03 511320 + 652 511321 Sb-132m 3.73950E-03 3.73950E-03 511321 + 653 511330 Sb-133 3.72570E-03 3.74170E-03 511330 + 654 511340 Sb-134 1.43420E-04 1.43520E-04 511340 + 655 511341 Sb-134m 3.90930E-04 3.90930E-04 511341 + 656 511350 Sb-135 9.93660E-05 9.93680E-05 511350 + 657 511360 Sb-136 6.66840E-06 6.66840E-06 511360 + 658 511370 Sb-137 1.66650E-08 1.66650E-08 511370 + 659 521210 Te-121 6.39920E-11 2.78950E-10 521210 + 660 521211 Te-121m 2.42340E-10 2.42340E-10 521211 + 661 521220 Te-122 1.63980E-08 3.18670E-06 52122.82c + 662 521240 Te-124 1.07450E-06 3.21270E-05 52124.82c + 663 521250 Te-125 1.06020E-06 2.24130E-03 52125.82c + 664 521251 Te-125m 4.01490E-06 5.04400E-04 521251 + 665 521260 Te-126 1.16380E-05 3.28730E-04 52126.82c + 666 521270 Te-127 1.73460E-05 6.64020E-03 521270 + 667 521271 Te-127m 4.85330E-05 1.13640E-03 52527.82c + 668 521280 Te-128 5.31300E-04 1.12530E-02 52128.82c + 669 521290 Te-129 5.75130E-04 1.42800E-02 521290 + 670 521291 Te-129m 1.60920E-03 8.34890E-03 52529.82c + 671 521300 Te-130 8.22530E-03 2.24130E-02 52130.82c + 672 521310 Te-131 4.08850E-03 2.04890E-02 521310 + 673 521311 Te-131m 1.14400E-02 1.26360E-02 521311 + 674 521320 Te-132 3.00570E-02 3.82560E-02 52132.82c + 675 521330 Te-133 6.85030E-03 1.34130E-02 521330 + 676 521331 Te-133m 1.91670E-02 1.98140E-02 521331 + 677 521340 Te-134 1.84570E-02 1.90070E-02 521340 + 678 521350 Te-135 5.01260E-03 5.09740E-03 521350 + 679 521360 Te-136 1.50830E-03 1.51390E-03 521360 + 680 521370 Te-137 2.15050E-04 2.15060E-04 521370 + 681 521380 Te-138 3.06610E-05 3.06610E-05 521380 + 682 521390 Te-139 1.99150E-06 1.99150E-06 521390 + 683 521400 Te-140 1.79400E-09 1.79400E-09 521400 + 684 531270 I-127 4.88470E-09 6.66750E-03 53127.82c + 685 531280 I-128 5.57980E-06 5.57980E-06 531280 + 686 531290 I-129 4.56210E-05 1.74150E-02 53129.82c + 687 531300 I-130 1.66790E-04 2.18190E-04 53130.82c + 688 531301 I-130m 6.11900E-05 6.11900E-05 531301 + 689 531310 I-131 1.68990E-03 3.21610E-02 53131.82c + 690 531320 I-132 2.88010E-03 4.33290E-02 531320 + 691 531321 I-132m 2.55000E-03 2.55000E-03 531321 + 692 531330 I-133 1.08420E-02 4.86240E-02 531330 + 693 531331 I-133m 8.02330E-03 8.02330E-03 531331 + 694 531340 I-134 1.53040E-02 4.75490E-02 531340 + 695 531341 I-134m 1.35500E-02 1.35500E-02 531341 + 696 531350 I-135 4.02840E-02 4.53810E-02 53135.82c + 697 531360 I-136 5.06180E-03 6.57880E-03 531360 + 698 531361 I-136m 1.37970E-02 1.38010E-02 531361 + 699 531370 I-137 1.04860E-02 1.06970E-02 531370 + 700 531380 I-138 2.15290E-03 2.18160E-03 531380 + 701 531390 I-139 7.58870E-04 7.60860E-04 531390 + 702 531400 I-140 1.01730E-04 1.01730E-04 531400 + 703 531410 I-141 1.77410E-05 1.77410E-05 531410 + 704 531420 I-142 8.47220E-09 8.47220E-09 531420 + 705 541290 Xe-129 3.24480E-10 1.55330E-09 54129.82c + 706 541291 Xe-129m 1.22880E-09 1.22880E-09 541291 + 707 541300 Xe-130 4.35700E-06 2.32340E-04 54130.82c + 708 541310 Xe-131 4.86000E-06 3.21790E-02 54131.82c + 709 541311 Xe-131m 1.35980E-05 3.62930E-04 541311 + 710 541320 Xe-132 1.03690E-04 4.39290E-02 54132.82c + 711 541321 Xe-132m 1.38920E-04 1.38920E-04 541321 + 712 541330 Xe-133 3.34600E-04 4.98950E-02 54133.82c + 713 541331 Xe-133m 9.36200E-04 2.32020E-03 541331 + 714 541340 Xe-134 1.94740E-03 5.51160E-02 54134.82c + 715 541341 Xe-134m 5.30820E-03 5.61980E-03 541341 + 716 541350 Xe-135 5.81500E-03 6.73240E-02 54135.82c + 717 541351 Xe-135m 1.62700E-02 2.37620E-02 541351 + 718 541360 Xe-136 5.00770E-02 7.11520E-02 54136.82c + 719 541370 Xe-137 4.00790E-02 5.01960E-02 541370 + 720 541380 Xe-138 2.58910E-02 2.80320E-02 541380 + 721 541390 Xe-139 1.09920E-02 1.16880E-02 541390 + 722 541400 Xe-140 5.68790E-03 5.78390E-03 541400 + 723 541410 Xe-141 1.53930E-03 1.55330E-03 541410 + 724 541420 Xe-142 3.52920E-04 3.52930E-04 541420 + 725 541430 Xe-143 4.49740E-05 4.49740E-05 541430 + 726 541440 Xe-144 3.23720E-06 3.23720E-06 541440 + 727 541450 Xe-145 1.04210E-09 1.04210E-09 541450 + 728 551320 Cs-132 2.89190E-08 2.89190E-08 551320 + 729 551330 Cs-133 4.69070E-06 4.98990E-02 55133.82c + 730 551340 Cs-134 3.45080E-05 6.50600E-05 55134.82c + 731 551341 Cs-134m 3.05520E-05 3.05520E-05 551341 + 732 551350 Cs-135 3.87270E-04 6.81400E-02 55135.82c + 733 551351 Cs-135m 2.86590E-04 2.86590E-04 551351 + 734 551360 Cs-136 2.13420E-03 2.89710E-03 55136.82c + 735 551361 Cs-136m 1.52590E-03 1.52590E-03 551361 + 736 551370 Cs-137 1.88300E-02 6.90260E-02 55137.82c + 737 551380 Cs-138 8.71550E-03 4.85530E-02 551380 + 738 551381 Cs-138m 1.45750E-02 1.45750E-02 551381 + 739 551390 Cs-139 2.86280E-02 4.03160E-02 551390 + 740 551400 Cs-140 1.95530E-02 2.53380E-02 551400 + 741 551410 Cs-141 1.87160E-02 2.02700E-02 551410 + 742 551420 Cs-142 7.53030E-03 7.88240E-03 551420 + 743 551430 Cs-143 2.73730E-03 2.78190E-03 551430 + 744 551440 Cs-144 2.95100E-04 4.45790E-04 551440 + 745 551441 Cs-144m 2.95100E-04 2.95100E-04 551441 + 746 551450 Cs-145 1.13170E-04 1.13170E-04 551450 + 747 551460 Cs-146 3.17300E-06 3.17300E-06 551460 + 748 551470 Cs-147 5.47820E-09 5.47820E-09 551470 + 749 561340 Ba-134 7.99140E-09 6.50680E-05 56134.82c + 750 561350 Ba-135 5.03720E-07 1.91310E-06 56135.82c + 751 561351 Ba-135m 1.40940E-06 1.40940E-06 561351 + 752 561360 Ba-136 2.04740E-05 3.73630E-03 56136.82c + 753 561361 Ba-136m 5.58090E-05 5.58090E-05 561361 + 754 561370 Ba-137 1.97990E-04 6.97780E-02 56137.82c + 755 561371 Ba-137m 5.53980E-04 6.57140E-02 561371 + 756 561380 Ba-138 5.14480E-03 5.64670E-02 56138.82c + 757 561390 Ba-139 1.11830E-02 5.14990E-02 561390 + 758 561400 Ba-140 2.37140E-02 4.90520E-02 56140.82c + 759 561410 Ba-141 2.59170E-02 4.61870E-02 561410 + 760 561420 Ba-142 3.36380E-02 4.15660E-02 561420 + 761 561430 Ba-143 2.04180E-02 2.31690E-02 561430 + 762 561440 Ba-144 1.29630E-02 1.35580E-02 561440 + 763 561450 Ba-145 4.18060E-03 4.27800E-03 561450 + 764 561460 Ba-146 1.42230E-03 1.42500E-03 561460 + 765 561470 Ba-147 2.66840E-04 2.66840E-04 561470 + 766 561480 Ba-148 4.76070E-05 4.76070E-05 561480 + 767 561490 Ba-149 1.08280E-06 1.08280E-06 561490 + 768 561500 Ba-150 5.62000E-10 5.62000E-10 561500 + 769 571370 La-137 5.33190E-06 5.33190E-06 571370 + 770 571380 La-138 2.01350E-05 2.01350E-05 57138.82c + 771 571390 La-139 2.95850E-04 5.17970E-02 57139.82c + 772 571400 La-140 1.05000E-03 5.01020E-02 57140.82c + 773 571410 La-141 4.08640E-03 5.02730E-02 571410 + 774 571420 La-142 6.80450E-03 4.83700E-02 571420 + 775 571430 La-143 1.62410E-02 3.94100E-02 571430 + 776 571440 La-144 1.80700E-02 3.16280E-02 571440 + 777 571450 La-145 1.80760E-02 2.23540E-02 571450 + 778 571460 La-146 3.08460E-03 4.50970E-03 571460 + 779 571461 La-146m 6.47130E-03 6.47130E-03 571461 + 780 571470 La-147 5.66920E-03 5.93620E-03 571470 + 781 571480 La-148 1.75520E-03 1.80260E-03 571480 + 782 571490 La-149 4.78900E-04 4.79980E-04 571490 + 783 571500 La-150 5.75440E-05 5.75450E-05 571500 + 784 571510 La-151 5.42000E-06 5.42000E-06 571510 + 785 571520 La-152 1.52750E-09 1.52750E-09 571520 + 786 581390 Ce-139 5.24390E-07 1.99160E-06 581390 + 787 581391 Ce-139m 1.46720E-06 1.46720E-06 581391 + 788 581400 Ce-140 2.62280E-05 5.01280E-02 58140.82c + 789 581410 Ce-141 1.36650E-04 5.04100E-02 58141.82c + 790 581420 Ce-142 6.98380E-04 4.90690E-02 58142.82c + 791 581430 Ce-143 1.93640E-03 4.13460E-02 58143.82c + 792 581440 Ce-144 6.85390E-03 3.84820E-02 58144.82c + 793 581450 Ce-145 1.18090E-02 3.41630E-02 581450 + 794 581460 Ce-146 1.87050E-02 2.96860E-02 581460 + 795 581470 Ce-147 1.63680E-02 2.23040E-02 581470 + 796 581480 Ce-148 1.42790E-02 1.60880E-02 581480 + 797 581490 Ce-149 6.57030E-03 7.04510E-03 581490 + 798 581500 Ce-150 2.95730E-03 3.01330E-03 581500 + 799 581510 Ce-151 7.23690E-04 7.29110E-04 581510 + 800 581520 Ce-152 1.33170E-04 1.33170E-04 581520 + 801 581530 Ce-153 1.84750E-05 1.84750E-05 581530 + 802 581540 Ce-154 9.40230E-09 9.40230E-09 581540 + 803 581550 Ce-155 1.28110E-10 1.28110E-10 581550 + 804 591420 Pr-142 2.82870E-07 1.05390E-06 59142.82c + 805 591421 Pr-142m 7.71030E-07 7.71030E-07 591421 + 806 591430 Pr-143 1.57010E-05 4.13620E-02 59143.82c + 807 591440 Pr-144 6.95960E-06 3.85590E-02 591440 + 808 591441 Pr-144m 7.08010E-05 6.01830E-04 591441 + 809 591450 Pr-145 4.43380E-04 3.46060E-02 591450 + 810 591460 Pr-146 1.43570E-03 3.11220E-02 591460 + 811 591470 Pr-147 4.06840E-03 2.63730E-02 591470 + 812 591480 Pr-148 1.06740E-03 1.71560E-02 591480 + 813 591481 Pr-148m 5.17450E-03 5.17450E-03 591481 + 814 591490 Pr-149 9.18910E-03 1.62340E-02 591490 + 815 591500 Pr-150 6.87660E-03 9.88990E-03 591500 + 816 591510 Pr-151 5.06280E-03 5.79190E-03 591510 + 817 591520 Pr-152 2.00150E-03 2.13480E-03 591520 + 818 591530 Pr-153 6.82540E-04 7.00900E-04 591530 + 819 591540 Pr-154 1.21360E-04 1.21370E-04 591540 + 820 591550 Pr-155 2.83590E-05 2.83590E-05 591550 + 821 591560 Pr-156 1.09000E-06 1.09000E-06 591560 + 822 591570 Pr-157 4.22380E-10 4.22380E-10 591570 + 823 601440 Nd-144 1.07910E-06 3.85610E-02 60144.82c + 824 601450 Nd-145 2.11830E-06 3.46090E-02 60145.82c + 825 601460 Nd-146 5.71440E-05 3.11790E-02 60146.82c + 826 601470 Nd-147 2.60620E-04 2.66330E-02 60147.82c + 827 601480 Nd-148 1.06470E-03 2.33950E-02 60148.82c + 828 601490 Nd-149 2.49590E-03 1.87300E-02 601490 + 829 601500 Nd-150 5.52090E-03 1.54110E-02 60150.82c + 830 601510 Nd-151 6.36720E-03 1.21590E-02 601510 + 831 601520 Nd-152 6.86220E-03 8.99700E-03 601520 + 832 601530 Nd-153 4.21080E-03 4.91170E-03 601530 + 833 601540 Nd-154 2.35930E-03 2.48070E-03 601540 + 834 601550 Nd-155 7.44870E-04 7.73260E-04 601550 + 835 601560 Nd-156 2.21060E-04 2.22120E-04 601560 + 836 601570 Nd-157 3.28670E-05 3.28670E-05 601570 + 837 601580 Nd-158 6.48320E-06 6.48320E-06 601580 + 838 601590 Nd-159 1.36140E-09 1.36140E-09 601590 + 839 601600 Nd-160 2.69660E-11 2.69660E-11 601600 + 840 611470 Pm-147 2.58260E-08 2.66330E-02 61147.82c + 841 611480 Pm-148 1.45300E-06 1.65100E-06 61148.82c + 842 611481 Pm-148m 3.96050E-06 3.96050E-06 61548.82c + 843 611490 Pm-149 4.00730E-05 1.87700E-02 61149.82c + 844 611500 Pm-150 1.66300E-04 1.66300E-04 611500 + 845 611510 Pm-151 5.86220E-04 1.27450E-02 61151.82c + 846 611520 Pm-152 2.13310E-04 9.21030E-03 611520 + 847 611521 Pm-152m 4.48440E-04 4.48440E-04 611521 + 848 611522 Pm-152m 5.85780E-04 5.85780E-04 611522 + 849 611530 Pm-153 2.29270E-03 7.20440E-03 611530 + 850 611540 Pm-154 1.19410E-03 3.67480E-03 611540 + 851 611541 Pm-154m 1.19410E-03 1.19410E-03 611541 + 852 611550 Pm-155 2.06920E-03 2.84250E-03 611550 + 853 611560 Pm-156 1.07990E-03 1.30200E-03 611560 + 854 611570 Pm-157 5.22210E-04 5.55080E-04 611570 + 855 611580 Pm-158 1.36110E-04 1.42590E-04 611580 + 856 611590 Pm-159 2.65350E-05 2.65360E-05 611590 + 857 611600 Pm-160 4.15190E-06 4.15190E-06 611600 + 858 611610 Pm-161 4.05720E-09 4.05720E-09 611610 + 859 611620 Pm-162 4.37990E-11 4.37990E-11 611620 + 860 621490 Sm-149 1.08290E-06 1.87710E-02 62149.82c + 861 621500 Sm-150 1.08630E-06 1.67390E-04 62150.82c + 862 621510 Sm-151 2.38510E-05 1.27690E-02 62151.82c + 863 621520 Sm-152 1.23580E-04 1.03680E-02 62152.82c + 864 621530 Sm-153 8.91110E-05 7.54280E-03 62153.82c + 865 621531 Sm-153m 2.49330E-04 2.49330E-04 621531 + 866 621540 Sm-154 8.99060E-04 5.76790E-03 62154.82c + 867 621550 Sm-155 1.36220E-03 4.20470E-03 621550 + 868 621560 Sm-156 1.87890E-03 3.18090E-03 621560 + 869 621570 Sm-157 1.44520E-03 2.00030E-03 621570 + 870 621580 Sm-158 1.02400E-03 1.16660E-03 621580 + 871 621590 Sm-159 4.19550E-04 4.46090E-04 621590 + 872 621600 Sm-160 1.54990E-04 1.59130E-04 621600 + 873 621610 Sm-161 3.07720E-05 3.07760E-05 621610 + 874 621620 Sm-162 9.78290E-06 9.78290E-06 621620 + 875 621630 Sm-163 7.84690E-09 7.84690E-09 621630 + 876 621640 Sm-164 1.48000E-10 1.48000E-10 621640 + 877 621650 Sm-165 2.27200E-12 2.27200E-12 621650 + 878 631510 Eu-151 3.75920E-10 1.27690E-02 63151.82c + 879 631520 Eu-152 3.49020E-09 8.11280E-09 63152.82c + 880 631521 Eu-152m 7.97470E-10 7.97470E-10 631521 + 881 631522 Eu-152m 4.62270E-09 4.62270E-09 631522 + 882 631530 Eu-153 2.82510E-07 7.54310E-03 63153.82c + 883 631540 Eu-154 4.73860E-06 9.84750E-06 63154.82c + 884 631541 Eu-154m 5.10890E-06 5.10890E-06 631541 + 885 631550 Eu-155 4.48090E-05 4.24950E-03 63155.82c + 886 631560 Eu-156 1.52420E-04 3.33330E-03 63156.82c + 887 631570 Eu-157 3.58520E-04 2.35880E-03 63157.82c + 888 631580 Eu-158 3.93070E-04 1.55970E-03 631580 + 889 631590 Eu-159 4.74830E-04 9.20920E-04 631590 + 890 631600 Eu-160 3.28050E-04 4.87180E-04 631600 + 891 631610 Eu-161 1.87430E-04 2.18210E-04 631610 + 892 631620 Eu-162 7.75330E-05 8.73160E-05 631620 + 893 631630 Eu-163 1.78330E-05 1.78410E-05 631630 + 894 631640 Eu-164 2.84090E-06 2.84110E-06 631640 + 895 631650 Eu-165 1.46940E-08 1.46960E-08 631650 + 896 631660 Eu-166 3.42340E-10 3.42340E-10 631660 + 897 631670 Eu-167 4.32340E-12 4.32340E-12 631670 + 898 641540 Gd-154 1.04470E-09 9.84660E-06 64154.82c + 899 641550 Gd-155 7.85920E-09 4.24950E-03 64155.82c + 900 641551 Gd-155m 2.19900E-08 2.19900E-08 641551 + 901 641560 Gd-156 5.44390E-06 3.33880E-03 64156.82c + 902 641570 Gd-157 2.50780E-05 2.38390E-03 64157.82c + 903 641580 Gd-158 8.18310E-05 1.64150E-03 64158.82c + 904 641590 Gd-159 1.64250E-04 1.08520E-03 641590 + 905 641600 Gd-160 2.56540E-04 7.43720E-04 64160.82c + 906 641610 Gd-161 2.70150E-04 4.88360E-04 641610 + 907 641620 Gd-162 2.25420E-04 3.12740E-04 641620 + 908 641630 Gd-163 1.08410E-04 1.26250E-04 641630 + 909 641640 Gd-164 4.83530E-05 5.11940E-05 641640 + 910 641650 Gd-165 1.47110E-05 1.47260E-05 641650 + 911 641660 Gd-166 5.03850E-06 5.03880E-06 641660 + 912 641670 Gd-167 2.36950E-08 2.36990E-08 641670 + 913 641680 Gd-168 4.31290E-10 4.31290E-10 641680 + 914 641690 Gd-169 1.03500E-11 1.03500E-11 641690 + 915 651560 Tb-156 2.77600E-11 8.21400E-11 651560 + 916 651561 Tb-156m 4.70410E-11 4.70410E-11 651561 + 917 651562 Tb-156m 7.35280E-12 7.35280E-12 651562 + 918 651570 Tb-157 2.60460E-09 2.60460E-09 651570 + 919 651580 Tb-158 4.91250E-08 5.39250E-08 651580 + 920 651581 Tb-158m 4.82890E-09 4.82890E-09 651581 + 921 651590 Tb-159 8.52230E-07 1.08600E-03 65159.82c + 922 651600 Tb-160 3.11100E-06 3.11100E-06 65160.82c + 923 651610 Tb-161 3.45360E-05 5.22890E-04 651610 + 924 651620 Tb-162 3.69190E-05 3.49650E-04 651620 + 925 651630 Tb-163 5.39820E-05 1.80230E-04 651630 + 926 651640 Tb-164 3.96730E-05 9.08670E-05 651640 + 927 651650 Tb-165 3.42970E-05 4.90230E-05 651650 + 928 651660 Tb-166 1.81410E-05 2.31800E-05 651660 + 929 651670 Tb-167 8.09520E-06 8.11890E-06 651670 + 930 651680 Tb-168 1.75420E-07 1.75850E-07 651680 + 931 651690 Tb-169 2.58720E-08 2.58820E-08 651690 + 932 651700 Tb-170 1.13650E-09 1.13650E-09 651700 + 933 651710 Tb-171 5.23630E-12 5.23630E-12 651710 + 934 661590 Dy-159 1.62080E-10 1.62080E-10 661590 + 935 661600 Dy-160 6.66050E-09 3.11770E-06 66160.82c + 936 661610 Dy-161 1.04830E-07 5.23000E-04 66161.82c + 937 661620 Dy-162 4.87760E-06 3.54530E-04 66162.82c + 938 661630 Dy-163 3.94060E-06 1.84170E-04 66163.82c + 939 661640 Dy-164 1.41650E-05 1.05070E-04 66164.82c + 940 661650 Dy-165 2.07130E-05 7.24320E-05 661650 + 941 661651 Dy-165m 2.75780E-06 2.75780E-06 661651 + 942 661660 Dy-166 3.11870E-05 5.43670E-05 661660 + 943 661670 Dy-167 1.82010E-05 2.63200E-05 661670 + 944 661680 Dy-168 7.92850E-06 8.10430E-06 661680 + 945 661690 Dy-169 6.50090E-06 6.52680E-06 661690 + 946 661700 Dy-170 4.20400E-06 4.20510E-06 661700 + 947 661710 Dy-171 6.68780E-09 6.69300E-09 661710 + 948 661720 Dy-172 4.97510E-10 4.97510E-10 661720 + 949 661730 Dy-173 2.67970E-11 2.67970E-11 661730 + 950 671610 Ho-161 1.36650E-11 1.54850E-11 671610 + 951 671611 Ho-161m 1.81950E-12 1.81950E-12 671611 + 952 671620 Ho-162 9.40420E-11 2.52970E-10 671620 + 953 671621 Ho-162m 2.56340E-10 2.56340E-10 671621 + 954 671630 Ho-163 6.79550E-09 7.70030E-09 671630 + 955 671631 Ho-163m 9.04780E-10 9.04780E-10 671631 + 956 671640 Ho-164 1.94700E-08 7.25390E-08 671640 + 957 671641 Ho-164m 5.30690E-08 5.30690E-08 671641 + 958 671650 Ho-165 2.93700E-06 7.54310E-05 67165.82c + 959 671660 Ho-166 5.40500E-07 5.49070E-05 671660 + 960 671661 Ho-166m 1.47330E-06 1.47330E-06 671661 + 961 671670 Ho-167 3.03350E-06 2.93530E-05 671670 + 962 671680 Ho-168 3.70790E-07 9.09220E-06 671680 + 963 671681 Ho-168m 6.20110E-07 6.20110E-07 671681 + 964 671690 Ho-169 2.78530E-06 9.31210E-06 671690 + 965 671700 Ho-170 1.53750E-06 1.53750E-06 671700 + 966 671701 Ho-170m 5.64040E-07 4.76920E-06 671701 + 967 671710 Ho-171 2.50380E-07 2.57070E-07 671710 + 968 671720 Ho-172 5.37090E-07 5.37590E-07 671720 + 969 671730 Ho-173 1.60590E-08 1.60860E-08 671730 + 970 671740 Ho-174 1.20090E-09 1.20090E-09 671740 + 971 671750 Ho-175 5.09790E-11 5.09790E-11 671750 + 972 681640 Er-164 1.89750E-11 3.75220E-08 68164.82c + 973 681650 Er-165 5.97530E-10 5.97530E-10 681650 + 974 681660 Er-166 1.41930E-08 5.49210E-05 68166.82c + 975 681670 Er-167 8.00210E-08 2.94440E-05 68167.82c + 976 681671 Er-167m 1.06540E-08 3.51820E-06 681671 + 977 681680 Er-168 2.74730E-07 9.37030E-06 68168.82c + 978 681690 Er-169 1.13990E-06 1.04520E-05 681690 + 979 681700 Er-170 1.05070E-06 7.35740E-06 68170.82c + 980 681710 Er-171 7.65570E-07 1.02260E-06 681710 + 981 681720 Er-172 4.31610E-07 9.69200E-07 681720 + 982 681730 Er-173 3.30880E-07 3.46970E-07 681730 + 983 681740 Er-174 1.33610E-07 1.34810E-07 681740 + 984 681750 Er-175 1.58200E-08 1.58710E-08 681750 + 985 681760 Er-176 1.54570E-09 1.54570E-09 681760 + 986 681770 Er-177 6.71640E-11 6.71640E-11 681770 + 987 691660 Tm-166 4.47400E-13 1.38600E-12 691660 + 988 691670 Tm-167 3.63180E-11 3.63180E-11 691670 + 989 691680 Tm-168 3.28120E-10 3.28120E-10 691680 + 990 691690 Tm-169 8.04670E-09 1.04600E-05 691690 + 991 691700 Tm-170 5.83860E-08 5.83860E-08 691700 + 992 691710 Tm-171 4.55850E-08 1.06820E-06 691710 + 993 691720 Tm-172 9.73160E-08 1.06650E-06 691720 + 994 691730 Tm-173 7.02020E-07 1.04900E-06 691730 + 995 691740 Tm-174 2.96350E-07 4.31160E-07 691740 + 996 691750 Tm-175 1.67840E-07 1.83710E-07 691750 + 997 691760 Tm-176 4.11090E-08 4.26550E-08 691760 + 998 691770 Tm-177 1.00060E-08 1.00730E-08 691770 + 999 691780 Tm-178 9.36140E-10 9.36140E-10 691780 + 1000 691790 Tm-179 7.45070E-11 7.45070E-11 691790 + 1001 701690 Yb-169 1.48110E-12 1.67830E-12 701690 + 1002 701700 Yb-170 7.41670E-11 5.83840E-08 701700 + 1003 701710 Yb-171 1.98300E-11 1.06840E-06 701710 + 1004 701711 Yb-171m 1.48940E-10 1.48940E-10 701711 + 1005 701720 Yb-172 2.07290E-09 1.06860E-06 701720 + 1006 701730 Yb-173 1.85860E-08 1.06760E-06 701730 + 1007 701740 Yb-174 8.10130E-08 5.12580E-07 701740 + 1008 701750 Yb-175 9.00150E-08 2.85710E-07 701750 + 1009 701751 Yb-175m 1.19850E-08 1.53440E-07 701751 + 1010 701760 Yb-176 3.61180E-08 1.44840E-07 701760 + 1011 701761 Yb-176m 7.57720E-08 9.70990E-08 701761 + 1012 701770 Yb-177 5.06390E-08 7.09080E-08 701770 + 1013 701771 Yb-177m 1.01960E-08 2.02690E-08 701771 + 1014 701780 Yb-178 2.83570E-08 2.92930E-08 701780 + 1015 701790 Yb-179 5.89230E-09 5.96680E-09 701790 + 1016 701800 Yb-180 1.05690E-09 1.05690E-09 701800 + 1017 701810 Yb-181 7.40840E-11 7.40840E-11 701810 + 1018 711730 Lu-173 3.27010E-11 3.27010E-11 711730 + 1019 711740 Lu-174 1.09140E-10 4.04910E-10 711740 + 1020 711741 Lu-174m 2.97500E-10 2.97500E-10 711741 + 1021 711750 Lu-175 2.85180E-09 2.88570E-07 71175.82c + 1022 711760 Lu-176 5.27310E-09 1.49830E-08 71176.82c + 1023 711761 Lu-176m 2.51350E-09 2.51350E-09 711761 + 1024 711770 Lu-177 1.34190E-08 8.58070E-08 711770 + 1025 711771 Lu-177m 6.38970E-09 6.54870E-09 711771 + 1026 711772 Lu-177m 3.17970E-10 3.17970E-10 711772 + 1027 711780 Lu-178 8.72490E-09 3.80180E-08 711780 + 1028 711781 Lu-178m 1.16890E-08 1.16890E-08 711781 + 1029 711790 Lu-179 1.69240E-08 2.51440E-08 711790 + 1030 711791 Lu-179m 2.25330E-09 8.22010E-09 711791 + 1031 711800 Lu-180 2.10940E-09 5.56020E-09 711800 + 1032 711801 Lu-180m 2.10940E-09 3.16630E-09 711801 + 1033 711802 Lu-180m 3.73530E-09 3.73530E-09 711802 + 1034 711810 Lu-181 2.89860E-09 2.97270E-09 711810 + 1035 711820 Lu-182 4.20190E-10 4.20190E-10 711820 + 1036 711830 Lu-183 6.20730E-11 6.20730E-11 711830 + 1037 711840 Lu-184 3.50950E-12 3.50950E-12 711840 + 1038 721750 Hf-175 2.57860E-12 2.57860E-12 721750 + 1039 721760 Hf-176 4.24690E-11 2.55360E-09 72176.82c + 1040 721770 Hf-177 2.03150E-10 9.13400E-08 72177.82c + 1041 721771 Hf-177m 9.58490E-11 5.32920E-09 721771 + 1042 721772 Hf-177m 5.66690E-12 1.64650E-10 721772 + 1043 721780 Hf-178 5.35200E-10 5.13670E-08 72178.82c + 1044 721781 Hf-178m 9.98120E-10 1.28130E-08 721781 + 1045 721782 Hf-178m 1.24850E-10 1.24850E-10 721782 + 1046 721790 Hf-179 2.15210E-09 2.88870E-08 72179.82c + 1047 721791 Hf-179m 6.22750E-10 6.22750E-10 721791 + 1048 721792 Hf-179m 9.40810E-10 9.40810E-10 721792 + 1049 721800 Hf-180 2.28850E-09 1.61290E-08 72180.82c + 1050 721801 Hf-180m 4.80110E-09 6.66870E-09 721801 + 1051 721810 Hf-181 5.58730E-09 8.56000E-09 721810 + 1052 721820 Hf-182 1.51320E-09 3.26670E-09 721820 + 1053 721821 Hf-182m 3.17460E-09 3.17460E-09 721821 + 1054 721830 Hf-183 1.33480E-09 1.39690E-09 721830 + 1055 721840 Hf-184 1.31890E-10 1.33640E-10 721840 + 1056 721841 Hf-184m 2.76680E-10 2.78440E-10 721841 + 1057 721850 Hf-185 4.74350E-11 4.74350E-11 721850 + 1058 721860 Hf-186 4.53780E-12 4.53780E-12 721860 + 1059 731781 Ta-178m 1.17720E-12 1.40590E-12 731781 + 1060 731790 Ta-179 1.95980E-11 2.74670E-11 731790 + 1061 731791 Ta-179m 7.43530E-12 7.86930E-12 731791 + 1062 731800 Ta-180 6.01740E-11 6.01740E-11 731800 + 1063 731801 Ta-180m 8.06160E-11 1.01290E-10 731801 + 1064 731810 Ta-181 5.71190E-10 9.13340E-09 73181.82c + 1065 731820 Ta-182 2.83740E-10 2.72030E-09 73182.82c + 1066 731821 Ta-182m 3.09930E-10 2.43660E-09 731821 + 1067 731822 Ta-182m 2.85410E-10 2.12670E-09 731822 + 1068 731830 Ta-183 1.40920E-09 2.80610E-09 731830 + 1069 731840 Ta-184 9.42110E-10 1.35420E-09 731840 + 1070 731850 Ta-185 3.28490E-10 5.71930E-10 731850 + 1071 731851 Ta-185m 1.96010E-10 1.96010E-10 731851 + 1072 731860 Ta-186 1.26120E-10 1.30660E-10 731860 + 1073 731870 Ta-187 3.02340E-11 3.02340E-11 731870 + 1074 731880 Ta-188 2.78500E-12 2.78500E-12 731880 + 1075 741810 W-181 2.21660E-12 2.21660E-12 741810 + 1076 741820 W-182 1.95870E-11 2.73990E-09 74182.82c + 1077 741830 W-183 1.69710E-11 2.88730E-09 74183.82c + 1078 741831 W-183m 6.42670E-11 1.59670E-10 741831 + 1079 741840 W-184 2.67970E-10 1.62360E-09 74184.82c + 1080 741850 W-185 8.71730E-11 9.03020E-10 741850 + 1081 741851 W-185m 2.43910E-10 2.43910E-10 741851 + 1082 741860 W-186 2.53820E-10 4.87910E-10 74186.82c + 1083 741861 W-186m 1.02770E-10 1.02770E-10 741861 + 1084 741870 W-187 1.91330E-10 2.21560E-10 741870 + 1085 741880 W-188 8.80500E-11 9.08350E-11 741880 + 1086 741890 W-189 1.79480E-11 1.79480E-11 741890 + 1087 741900 W-190 1.34830E-12 3.15470E-12 741900 + 1088 741901 W-190m 1.80640E-12 1.80640E-12 741901 + 1089 751840 Re-184 6.77820E-13 1.22880E-12 751840 + 1090 751850 Re-185 9.67060E-12 9.12690E-10 75185.82c + 1091 751860 Re-186 9.67570E-12 9.67570E-12 751860 + 1092 751861 Re-186m 1.61810E-11 1.61810E-11 751861 + 1093 751870 Re-187 6.57850E-11 2.87350E-10 75187.82c + 1094 751880 Re-188 1.76670E-11 1.56660E-10 751880 + 1095 751881 Re-188m 4.81560E-11 4.81560E-11 751881 + 1096 751890 Re-189 6.07270E-11 7.86750E-11 751890 + 1097 751900 Re-190 7.98830E-12 1.87850E-11 751900 + 1098 751901 Re-190m 1.67590E-11 1.67590E-11 751901 + 1099 751910 Re-191 8.89890E-12 8.89890E-12 751910 + 1100 751920 Re-192 1.28530E-12 1.28530E-12 751920 + 1101 761870 Os-187 1.04180E-12 1.04180E-12 761870 + 1102 761880 Os-188 5.57800E-12 1.62240E-10 761880 + 1103 761890 Os-189 2.55760E-12 9.09180E-11 761890 + 1104 761891 Os-189m 9.68540E-12 1.77760E-11 761891 + 1105 761900 Os-190 9.79170E-12 5.08120E-11 761900 + 1106 761901 Os-190m 1.31180E-11 2.22350E-11 761901 + 1107 761910 Os-191 1.40970E-11 2.67180E-11 761910 + 1108 761911 Os-191m 3.72240E-12 3.72240E-12 761911 + 1109 761920 Os-192 5.10400E-12 1.25210E-11 761920 + 1110 761921 Os-192m 6.83800E-12 6.83800E-12 761921 + 1111 761930 Os-193 4.13110E-12 4.13110E-12 761930 + 1112 761940 Os-194 1.24460E-12 1.24460E-12 761940 + 1113 771910 Ir-191 4.99720E-13 2.86160E-11 77191.82c + 1114 771911 Ir-191m 1.04400E-12 1.40090E-11 771911 + 1115 771920 Ir-192 9.69500E-13 3.79730E-12 771920 + 1116 771922 Ir-192m 9.69500E-13 1.85840E-12 771922 + 1117 771930 Ir-193 1.19250E-12 8.66010E-12 77193.82c + 1118 771931 Ir-193m 3.33650E-12 3.35090E-12 771931 + 1119 771940 Ir-194 9.94470E-13 3.23350E-12 771940 + 1120 771951 Ir-195m 1.20460E-12 1.20460E-12 771951 + 1121 781950 Pt-195 2.82260E-13 2.70720E-12 781950 + 1122 781951 Pt-195m 7.89740E-13 1.15600E-12 781951 + 1123 781960 Pt-196 1.13470E-12 1.13470E-12 781960 + + Nuclide 96244.82c -- curium 244 (Cm-244) + + Neutron-induced fission: + + Interpolation region : 1 / 2 + Interpolation energy : 2.53000E-08 MeV + Number of products : 1137 / 1194 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 3.82810E-05 3.82810E-05 1001.82c + 2 10020 H-2 1.16990E-05 1.16990E-05 1002.82c + 3 10030 H-3 1.91000E-04 1.91000E-04 1003.82c + 4 20040 He-4 2.42000E-03 2.42000E-03 2004.82c + 5 190500 K-50 2.34480E-12 2.34480E-12 190500 + 6 190510 K-51 1.06580E-12 1.06580E-12 190510 + 7 200500 Ca-50 2.52830E-11 2.74490E-11 200500 + 8 200510 Ca-51 2.28750E-11 2.34400E-11 200510 + 9 200520 Ca-52 2.11170E-11 2.11170E-11 200520 + 10 200530 Ca-53 6.48850E-12 6.48850E-12 200530 + 11 200540 Ca-54 1.91190E-12 1.91190E-12 200540 + 12 210500 Sc-50 5.05590E-12 3.42930E-11 210500 + 13 210501 Sc-50m 2.15850E-12 2.96070E-11 210501 + 14 210510 Sc-51 3.22010E-11 5.60630E-11 210510 + 15 210520 Sc-52 5.41700E-11 7.68110E-11 210520 + 16 210530 Sc-53 8.79040E-11 9.24460E-11 210530 + 17 210540 Sc-54 5.35260E-11 5.54380E-11 210540 + 18 210550 Sc-55 3.97820E-11 3.97820E-11 210550 + 19 210560 Sc-56 9.80350E-12 9.80350E-12 210560 + 20 210570 Sc-57 2.33210E-12 2.33210E-12 210570 + 21 220510 Ti-51 2.51940E-12 5.85830E-11 220510 + 22 220520 Ti-52 2.23110E-11 9.91220E-11 220520 + 23 220530 Ti-53 6.58590E-11 1.58310E-10 220530 + 24 220540 Ti-54 1.97970E-10 2.53410E-10 220540 + 25 220550 Ti-55 2.74950E-10 3.14730E-10 220550 + 26 220560 Ti-56 3.71340E-10 3.81910E-10 220560 + 27 220570 Ti-57 1.89100E-10 1.90660E-10 220570 + 28 220580 Ti-58 9.87340E-11 9.87340E-11 220580 + 29 220590 Ti-59 1.88560E-11 1.88560E-11 220590 + 30 220600 Ti-60 3.14120E-12 3.14120E-12 220600 + 31 230530 V-53 3.25840E-12 1.61560E-10 230530 + 32 230540 V-54 1.94260E-11 2.72830E-10 230540 + 33 230550 V-55 1.37550E-10 4.52280E-10 230550 + 34 230560 V-56 3.33860E-10 7.16340E-10 230560 + 35 230570 V-57 8.51590E-10 1.04170E-09 230570 + 36 230580 V-58 8.59060E-10 9.57790E-10 230580 + 37 230590 V-59 9.33420E-10 9.52280E-10 230590 + 38 230600 V-60 3.43490E-10 3.46630E-10 230600 + 39 230610 V-61 1.46980E-10 1.46980E-10 230610 + 40 230620 V-62 2.19280E-11 2.19280E-11 230620 + 41 230630 V-63 2.82500E-12 2.82500E-12 230630 + 42 240550 Cr-55 3.36700E-12 4.55650E-10 240550 + 43 240560 Cr-56 4.60050E-11 7.66520E-10 240560 + 44 240570 Cr-57 2.24410E-10 2.02820E-09 240570 + 45 240580 Cr-58 1.12760E-09 1.31920E-09 240580 + 46 240590 Cr-59 2.20660E-09 3.15890E-09 240590 + 47 240600 Cr-60 4.17510E-09 4.53050E-09 240600 + 48 240610 Cr-61 3.58230E-09 3.72050E-09 240610 + 49 240620 Cr-62 3.14890E-09 3.17180E-09 240620 + 50 240630 Cr-63 9.20280E-10 9.22120E-10 240630 + 51 240640 Cr-64 2.55310E-10 2.55310E-10 240640 + 52 240650 Cr-65 2.97820E-11 2.97820E-11 240650 + 53 240660 Cr-66 3.02550E-12 3.02550E-12 240660 + 54 250570 Mn-57 3.36850E-12 2.03150E-09 250570 + 55 250580 Mn-58 3.22480E-11 1.35140E-09 250580 + 56 250581 Mn-58m 3.63090E-12 3.63090E-12 250581 + 57 250590 Mn-59 3.80610E-10 3.53950E-09 250590 + 58 250600 Mn-60 1.35070E-10 4.80360E-09 250600 + 59 250601 Mn-60m 1.19960E-09 1.19960E-09 250601 + 60 250610 Mn-61 5.64360E-09 9.36410E-09 250610 + 61 250620 Mn-62 7.69520E-09 9.28110E-09 250620 + 62 250621 Mn-62m 1.38150E-09 2.96740E-09 250621 + 63 250630 Mn-63 1.41100E-08 1.50320E-08 250630 + 64 250640 Mn-64 8.14710E-09 8.40240E-09 250640 + 65 250650 Mn-65 5.77510E-09 5.80490E-09 250650 + 66 250660 Mn-66 1.36170E-09 1.36470E-09 250660 + 67 250670 Mn-67 3.03810E-10 3.03810E-10 250670 + 68 250680 Mn-68 1.69530E-11 1.69530E-11 250680 + 69 250690 Mn-69 1.84630E-12 1.84630E-12 250690 + 70 260590 Fe-59 2.74900E-12 3.54220E-09 260590 + 71 260600 Fe-60 5.77400E-11 5.92300E-09 260600 + 72 260610 Fe-61 4.99140E-10 9.86320E-09 260610 + 73 260620 Fe-62 4.19740E-09 1.64460E-08 260620 + 74 260630 Fe-63 1.18280E-08 2.68600E-08 260630 + 75 260640 Fe-64 3.37760E-08 4.21780E-08 260640 + 76 260650 Fe-65 4.50100E-08 5.08150E-08 260650 + 77 260660 Fe-66 5.85970E-08 5.99620E-08 260660 + 78 260670 Fe-67 2.81700E-08 2.84740E-08 260670 + 79 260680 Fe-68 9.80780E-09 9.82520E-09 260680 + 80 260690 Fe-69 2.52620E-09 2.52760E-09 260690 + 81 260700 Fe-70 4.00440E-10 4.00440E-10 260700 + 82 260710 Fe-71 9.17380E-12 9.17380E-12 260710 + 83 270610 Co-61 2.15730E-12 9.86540E-09 270610 + 84 270620 Co-62 1.21630E-11 1.64580E-08 270620 + 85 270621 Co-62m 2.84880E-11 2.84880E-11 270621 + 86 270630 Co-63 6.63850E-10 2.75240E-08 270630 + 87 270640 Co-64 3.73240E-09 4.59110E-08 270640 + 88 270650 Co-65 2.52200E-08 7.60350E-08 270650 + 89 270660 Co-66 5.89640E-08 1.18930E-07 270660 + 90 270670 Co-67 1.42600E-07 1.71070E-07 270670 + 91 270680 Co-68 1.32060E-07 1.95310E-07 270680 + 92 270681 Co-68m 1.16500E-07 1.26500E-07 270681 + 93 270690 Co-69 1.42590E-07 1.44940E-07 270690 + 94 270700 Co-70 2.51050E-08 2.51050E-08 270700 + 95 270701 Co-70m 2.51050E-08 2.55050E-08 270701 + 96 270710 Co-71 7.33100E-09 7.34020E-09 270710 + 97 270720 Co-72 5.46000E-10 5.46000E-10 270720 + 98 270730 Co-73 9.71480E-11 9.71480E-11 270730 + 99 270740 Co-74 1.08200E-11 1.08200E-11 270740 + 100 280630 Ni-63 1.35210E-12 2.75250E-08 280630 + 101 280640 Ni-64 4.77790E-11 4.59590E-08 28064.82c + 102 280650 Ni-65 7.02740E-10 7.67380E-08 280650 + 103 280660 Ni-66 9.18120E-09 1.28110E-07 280660 + 104 280670 Ni-67 4.21770E-08 2.13250E-07 280670 + 105 280680 Ni-68 1.41890E-07 4.01900E-07 280680 + 106 280690 Ni-69 1.88960E-07 3.32460E-07 280690 + 107 280691 Ni-69m 1.88960E-07 1.88960E-07 280691 + 108 280700 Ni-70 6.88490E-07 7.39100E-07 280700 + 109 280710 Ni-71 6.01090E-07 6.08430E-07 280710 + 110 280720 Ni-72 5.58670E-07 5.59220E-07 280720 + 111 280730 Ni-73 3.63740E-08 3.64710E-08 280730 + 112 280740 Ni-74 2.62740E-08 2.62850E-08 280740 + 113 280750 Ni-75 1.02480E-09 1.02480E-09 280750 + 114 280760 Ni-76 2.14500E-10 2.14500E-10 280760 + 115 280770 Ni-77 1.34250E-11 1.34250E-11 280770 + 116 290660 Cu-66 2.56640E-11 1.28130E-07 290660 + 117 290670 Cu-67 7.22900E-10 2.13970E-07 290670 + 118 290680 Cu-68 1.53180E-09 4.06450E-07 290680 + 119 290681 Cu-68m 3.58780E-09 3.58780E-09 290681 + 120 290690 Cu-69 7.33810E-08 5.94800E-07 290690 + 121 290700 Cu-70 1.87560E-08 1.42180E-07 290700 + 122 290701 Cu-70m 2.08950E-07 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359 410941 Nb-94m 4.16420E-07 4.16420E-07 410941 + 360 410950 Nb-95 5.77390E-06 2.79660E-02 41095.82c + 361 410951 Nb-95m 1.33510E-06 3.03570E-04 410951 + 362 410960 Nb-96 5.89060E-05 5.89060E-05 410960 + 363 410970 Nb-97 5.02520E-04 3.80300E-02 410970 + 364 410971 Nb-97m 1.16200E-04 3.56750E-02 410971 + 365 410980 Nb-98 5.34240E-04 4.41480E-02 410980 + 366 410981 Nb-98m 1.61220E-03 1.61220E-03 410981 + 367 410990 Nb-99 6.77140E-03 3.18680E-02 410990 + 368 410991 Nb-99m 1.56570E-03 1.59930E-02 410991 + 369 411000 Nb-100 3.07740E-03 3.68350E-02 411000 + 370 411001 Nb-100m 1.29430E-02 1.29430E-02 411001 + 371 411010 Nb-101 2.87150E-02 4.60120E-02 411010 + 372 411020 Nb-102 1.26430E-02 2.13950E-02 411020 + 373 411021 Nb-102m 1.26430E-02 1.26430E-02 411021 + 374 411030 Nb-103 2.18440E-02 2.42470E-02 411030 + 375 411040 Nb-104 5.36600E-03 6.03810E-03 411040 + 376 411041 Nb-104m 5.36600E-03 5.36600E-03 411041 + 377 411050 Nb-105 5.31170E-03 5.37990E-03 411050 + 378 411060 Nb-106 1.28920E-03 1.29610E-03 411060 + 379 411070 Nb-107 3.16960E-04 3.16960E-04 411070 + 380 411080 Nb-108 4.33970E-05 4.33970E-05 411080 + 381 411090 Nb-109 6.92460E-06 6.92460E-06 411090 + 382 420960 Mo-96 1.01500E-06 5.99210E-05 42096.82c + 383 420970 Mo-97 7.04090E-06 3.80370E-02 42097.82c + 384 420980 Mo-98 9.55500E-05 4.58560E-02 42098.82c + 385 420990 Mo-99 5.70320E-04 4.81110E-02 42099.82c + 386 421000 Mo-100 3.35650E-03 5.31340E-02 42100.82c + 387 421010 Mo-101 9.05820E-03 5.50700E-02 421010 + 388 421020 Mo-102 2.49370E-02 5.89750E-02 421020 + 389 421030 Mo-103 3.30510E-02 5.73040E-02 421030 + 390 421040 Mo-104 4.41210E-02 5.56100E-02 421040 + 391 421050 Mo-105 3.06690E-02 3.60160E-02 421050 + 392 421060 Mo-106 2.12210E-02 2.24780E-02 421060 + 393 421070 Mo-107 8.27910E-03 8.57970E-03 421070 + 394 421080 Mo-108 3.18580E-03 3.22740E-03 421080 + 395 421090 Mo-109 6.60830E-04 6.66880E-04 421090 + 396 421100 Mo-110 1.23990E-04 1.23990E-04 421100 + 397 421110 Mo-111 7.88560E-06 7.88560E-06 421110 + 398 421120 Mo-112 2.41450E-09 2.41450E-09 421120 + 399 430980 Tc-98 1.08090E-09 1.08090E-09 430980 + 400 430990 Tc-99 1.63460E-06 4.81110E-02 43099.82c + 401 430991 Tc-99m 3.77970E-07 4.23670E-02 430991 + 402 431000 Tc-100 1.32790E-05 1.32790E-05 431000 + 403 431010 Tc-101 1.69390E-04 5.52400E-02 431010 + 404 431020 Tc-102 4.59510E-04 5.94350E-02 431020 + 405 431021 Tc-102m 4.59510E-04 4.59510E-04 431021 + 406 431030 Tc-103 4.27940E-03 6.15840E-02 431030 + 407 431040 Tc-104 1.01920E-02 6.58020E-02 431040 + 408 431050 Tc-105 2.42740E-02 6.02900E-02 431050 + 409 431060 Tc-106 2.80990E-02 5.05770E-02 431060 + 410 431070 Tc-107 3.24770E-02 4.10570E-02 431070 + 411 431080 Tc-108 1.96420E-02 2.28730E-02 431080 + 412 431090 Tc-109 1.20440E-02 1.27070E-02 431090 + 413 431100 Tc-110 4.37590E-03 4.50000E-03 431100 + 414 431110 Tc-111 1.41070E-03 1.41850E-03 431110 + 415 431120 Tc-112 2.22380E-04 2.22380E-04 431120 + 416 431130 Tc-113 3.21010E-05 3.21010E-05 431130 + 417 431140 Tc-114 3.23650E-09 3.23650E-09 431140 + 418 441000 Ru-100 1.02140E-06 1.43000E-05 44100.82c + 419 441010 Ru-101 1.00690E-06 5.52410E-02 44101.82c + 420 441020 Ru-102 2.69350E-05 5.99210E-02 44102.82c + 421 441030 Ru-103 4.21540E-05 6.17280E-02 44103.82c + 422 441031 Ru-103m 1.01770E-04 1.01770E-04 441031 + 423 441040 Ru-104 9.52880E-04 6.67550E-02 44104.82c + 424 441050 Ru-105 3.33800E-03 6.36280E-02 44105.82c + 425 441060 Ru-106 1.08470E-02 6.14240E-02 44106.82c + 426 441070 Ru-107 1.82590E-02 5.93160E-02 441070 + 427 441080 Ru-108 2.96900E-02 5.25730E-02 441080 + 428 441090 Ru-109 2.52850E-02 3.79840E-02 441090 + 429 441100 Ru-110 2.19410E-02 2.64390E-02 441100 + 430 441110 Ru-111 1.04890E-02 1.19110E-02 441110 + 431 441120 Ru-112 4.75970E-03 4.98100E-03 441120 + 432 441130 Ru-113 5.58850E-04 8.68070E-04 441130 + 433 441131 Ru-113m 5.58850E-04 5.58850E-04 441131 + 434 441140 Ru-114 2.36930E-04 2.36930E-04 441140 + 435 441150 Ru-115 1.75220E-05 1.75220E-05 441150 + 436 441160 Ru-116 2.90730E-06 2.90730E-06 441160 + 437 441170 Ru-117 4.12200E-11 4.12200E-11 441170 + 438 451030 Rh-103 1.32360E-07 6.17290E-02 45103.82c + 439 451031 Rh-103m 8.65850E-07 6.09890E-02 451031 + 440 451040 Rh-104 4.97000E-07 1.99490E-06 451040 + 441 451041 Rh-104m 1.49980E-06 1.49980E-06 451041 + 442 451050 Rh-105 2.43250E-05 6.36560E-02 45105.82c + 443 451051 Rh-105m 3.71860E-06 1.80660E-02 451051 + 444 451060 Rh-106 6.29220E-05 6.14870E-02 451060 + 445 451061 Rh-106m 1.47380E-04 1.47380E-04 451061 + 446 451070 Rh-107 1.08030E-03 6.03960E-02 451070 + 447 451080 Rh-108 7.61680E-04 5.33350E-02 451080 + 448 451081 Rh-108m 2.29850E-03 2.29850E-03 451081 + 449 451090 Rh-109 8.03190E-03 4.60160E-02 451090 + 450 451100 Rh-110 1.12480E-02 3.76870E-02 451100 + 451 451101 Rh-110m 3.00250E-04 3.00250E-04 451101 + 452 451110 Rh-111 1.54590E-02 2.73700E-02 451110 + 453 451120 Rh-112 5.30000E-03 1.02810E-02 451120 + 454 451121 Rh-112m 5.30000E-03 5.30000E-03 451121 + 455 451130 Rh-113 7.15090E-03 8.29840E-03 451130 + 456 451140 Rh-114 1.24340E-03 1.48040E-03 451140 + 457 451141 Rh-114m 1.24340E-03 1.24340E-03 451141 + 458 451150 Rh-115 8.35620E-04 8.53130E-04 451150 + 459 451160 Rh-116 4.75580E-05 5.04340E-05 451160 + 460 451161 Rh-116m 1.11390E-04 1.11390E-04 451161 + 461 451170 Rh-117 4.51640E-05 4.51640E-05 451170 + 462 451180 Rh-118 9.84320E-06 9.84320E-06 451180 + 463 451190 Rh-119 2.96780E-06 2.96780E-06 451190 + 464 461060 Pd-106 1.61660E-08 6.16340E-02 46106.82c + 465 461070 Pd-107 7.26760E-06 6.04170E-02 46107.82c + 466 461071 Pd-107m 1.36580E-05 1.36580E-05 461071 + 467 461080 Pd-108 1.20570E-04 5.57540E-02 46108.82c + 468 461090 Pd-109 1.71770E-04 4.65110E-02 461090 + 469 461091 Pd-109m 3.22820E-04 2.33310E-02 461091 + 470 461100 Pd-110 1.80480E-03 3.97920E-02 46110.82c + 471 461110 Pd-111 1.12730E-03 3.00140E-02 461110 + 472 461111 Pd-111m 2.11850E-03 2.22800E-03 461111 + 473 461120 Pd-112 5.76280E-03 2.13440E-02 461120 + 474 461130 Pd-113 1.51700E-03 1.34780E-02 461130 + 475 461131 Pd-113m 3.66230E-03 3.66230E-03 461131 + 476 461140 Pd-114 4.46230E-03 7.18620E-03 461140 + 477 461150 Pd-115 6.87580E-04 1.53010E-03 461150 + 478 461151 Pd-115m 1.29220E-03 1.41610E-03 461151 + 479 461160 Pd-116 9.15730E-04 1.07760E-03 461160 + 480 461170 Pd-117 6.76680E-05 2.40290E-04 461170 + 481 461171 Pd-117m 1.27170E-04 1.27170E-04 461171 + 482 461180 Pd-118 7.78410E-05 8.73970E-05 461180 + 483 461190 Pd-119 1.28630E-05 1.58310E-05 461190 + 484 461200 Pd-120 2.98540E-06 2.98540E-06 461200 + 485 461210 Pd-121 2.00320E-06 2.00320E-06 461210 + 486 461220 Pd-122 2.90000E-12 2.90000E-12 461220 + 487 461230 Pd-123 7.47260E-08 7.47260E-08 461230 + 488 461240 Pd-124 1.78630E-08 1.78630E-08 461240 + 489 471080 Ag-108 3.95180E-10 4.75710E-10 471080 + 490 471081 Ag-108m 9.25620E-10 9.25620E-10 471081 + 491 471090 Ag-109 3.93540E-07 4.65130E-02 47109.82c + 492 471091 Ag-109m 2.57440E-06 4.64900E-02 471091 + 493 471100 Ag-110 3.26790E-06 3.37200E-06 471100 + 494 471101 Ag-110m 7.65410E-06 7.65410E-06 47510.82c + 495 471110 Ag-111 1.21470E-05 3.05560E-02 47111.82c + 496 471111 Ag-111m 7.94600E-05 3.03100E-02 471111 + 497 471120 Ag-112 2.52430E-04 2.15960E-02 471120 + 498 471130 Ag-113 8.57920E-05 9.27650E-03 471130 + 499 471131 Ag-113m 5.61210E-04 1.34670E-02 471131 + 500 471140 Ag-114 1.56510E-04 8.00090E-03 471140 + 501 471141 Ag-114m 6.58200E-04 6.58200E-04 471141 + 502 471150 Ag-115 1.24460E-04 1.77280E-03 471150 + 503 471151 Ag-115m 8.14120E-04 2.53010E-03 471151 + 504 471160 Ag-116 1.71600E-04 1.27330E-03 471160 + 505 471161 Ag-116m 4.01920E-04 4.01920E-04 471161 + 506 471170 Ag-117 4.95130E-05 1.96300E-04 471170 + 507 471171 Ag-117m 3.23890E-04 4.44030E-04 471171 + 508 471180 Ag-118 2.04140E-05 1.35640E-04 471180 + 509 471181 Ag-118m 8.58560E-05 9.83500E-05 471181 + 510 471190 Ag-119 3.93540E-06 1.18510E-05 471190 + 511 471191 Ag-119m 2.57440E-05 3.36590E-05 471191 + 512 471200 Ag-120 3.29100E-06 7.06930E-06 471200 + 513 471201 Ag-120m 4.66990E-06 6.16260E-06 471201 + 514 471210 Ag-121 2.00320E-06 4.00100E-06 471210 + 515 471220 Ag-122 3.14900E-06 3.14900E-06 471220 + 516 471221 Ag-122m 2.83650E-06 2.83650E-06 471221 + 517 471230 Ag-123 6.03290E-06 6.10760E-06 471230 + 518 471240 Ag-124 3.77820E-06 5.49770E-06 471240 + 519 471241 Ag-124m 3.40330E-06 3.40330E-06 471241 + 520 471250 Ag-125 3.16290E-06 3.16290E-06 471250 + 521 471260 Ag-126 3.65730E-07 3.65730E-07 471260 + 522 471270 Ag-127 4.54900E-08 4.54900E-08 471270 + 523 471280 Ag-128 1.76520E-09 1.76520E-09 471280 + 524 481110 Cd-111 2.30770E-07 3.07080E-02 48111.82c + 525 481111 Cd-111m 7.55010E-07 7.55010E-07 481111 + 526 481120 Cd-112 1.95440E-06 2.15980E-02 48112.82c + 527 481130 Cd-113 3.41570E-06 1.39680E-02 48113.82c + 528 481131 Cd-113m 1.11750E-05 1.71560E-04 481131 + 529 481140 Cd-114 5.18350E-05 8.05270E-03 48114.82c + 530 481150 Cd-115 2.00240E-05 3.63120E-03 481150 + 531 481151 Cd-115m 6.55120E-05 2.25860E-04 48515.82c + 532 481160 Cd-116 1.13170E-04 1.76420E-03 48116.82c + 533 481170 Cd-117 2.18060E-05 4.98880E-04 481170 + 534 481171 Cd-117m 7.13420E-05 2.07960E-04 481171 + 535 481180 Cd-118 7.86770E-05 2.72340E-04 481180 + 536 481190 Cd-119 1.12980E-05 5.08820E-05 481190 + 537 481191 Cd-119m 2.72740E-05 3.32000E-05 481191 + 538 481200 Cd-120 1.79110E-05 2.88630E-05 481200 + 539 481210 Cd-121 3.52040E-06 7.10330E-06 481210 + 540 481211 Cd-121m 8.49860E-06 8.91670E-06 481211 + 541 481220 Cd-122 2.29450E-05 2.89310E-05 481220 + 542 481230 Cd-123 1.14870E-05 1.64870E-05 481230 + 543 481231 Cd-123m 2.77320E-05 2.88450E-05 481231 + 544 481240 Cd-124 1.20110E-04 1.27300E-04 481240 + 545 481250 Cd-125 3.95710E-05 4.11520E-05 481250 + 546 481251 Cd-125m 9.55290E-05 9.71110E-05 481251 + 547 481260 Cd-126 1.13580E-04 1.13950E-04 481260 + 548 481270 Cd-127 5.42770E-05 5.43230E-05 481270 + 549 481280 Cd-128 2.36150E-05 2.36170E-05 481280 + 550 481290 Cd-129 8.98210E-07 8.98210E-07 481290 + 551 481291 Cd-129m 2.16840E-06 2.16840E-06 481291 + 552 481300 Cd-130 4.73750E-08 4.73750E-08 481300 + 553 481310 Cd-131 8.88110E-10 8.88110E-10 481310 + 554 491130 In-113 3.51370E-10 1.71320E-04 49113.82c + 555 491131 In-113m 8.12460E-11 8.12460E-11 491131 + 556 491140 In-114 2.98530E-09 1.16770E-08 491140 + 557 491141 In-114m 4.57570E-09 9.00750E-09 491141 + 558 491142 In-114m 4.43180E-09 4.43180E-09 491142 + 559 491150 In-115 7.90710E-07 3.67640E-03 49115.82c + 560 491151 In-115m 1.82830E-07 3.63140E-03 491151 + 561 491160 In-116 2.41220E-07 2.41220E-07 491160 + 562 491161 In-116m 3.69720E-07 7.27820E-07 491161 + 563 491162 In-116m 3.58090E-07 3.58090E-07 491162 + 564 491170 In-117 3.98590E-06 4.67730E-04 491170 + 565 491171 In-117m 9.21630E-07 4.61270E-04 491171 + 566 491180 In-118 9.79850E-07 2.73320E-04 491180 + 567 491181 In-118m 1.50190E-06 2.93610E-06 491181 + 568 491182 In-118m 1.45460E-06 1.45460E-06 491182 + 569 491190 In-119 5.62380E-06 4.63480E-05 491190 + 570 491191 In-119m 1.30040E-06 4.73080E-05 491191 + 571 491200 In-120 1.65820E-06 3.05210E-05 491200 + 572 491201 In-120m 1.65820E-06 1.65820E-06 491201 + 573 491202 In-120m 1.65820E-06 1.65820E-06 491202 + 574 491210 In-121 4.88070E-06 1.62600E-05 491210 + 575 491211 In-121m 1.12850E-06 5.83940E-06 491211 + 576 491220 In-122 2.47420E-06 3.14050E-05 491220 + 577 491221 In-122m 1.75540E-06 1.75540E-06 491221 + 578 491222 In-122m 1.75540E-06 1.75540E-06 491222 + 579 491230 In-123 2.04140E-05 5.40140E-05 491230 + 580 491231 In-123m 4.72020E-06 1.64520E-05 491231 + 581 491240 In-124 4.80280E-05 1.75330E-04 491240 + 582 491241 In-124m 4.32620E-05 4.32620E-05 491241 + 583 491250 In-125 3.50590E-04 4.67390E-04 491250 + 584 491251 In-125m 8.10640E-05 1.02520E-04 491251 + 585 491260 In-126 3.83280E-04 4.97230E-04 491260 + 586 491261 In-126m 3.45250E-04 3.45250E-04 491261 + 587 491270 In-127 1.00530E-03 1.00530E-03 491270 + 588 491271 In-127m 2.32460E-04 2.86780E-04 491271 + 589 491280 In-128 3.27360E-04 4.84230E-04 491280 + 590 491281 In-128m 1.33250E-04 1.56870E-04 491281 + 591 491282 In-128m 4.14910E-04 4.14910E-04 491282 + 592 491290 In-129 4.69590E-04 4.71760E-04 491290 + 593 491291 In-129m 1.08580E-04 1.09480E-04 491291 + 594 491300 In-130 4.02150E-05 4.02600E-05 491300 + 595 491301 In-130m 4.49170E-05 4.49170E-05 491301 + 596 491302 In-130m 7.64230E-05 7.64230E-05 491302 + 597 491310 In-131 8.78240E-06 8.87270E-06 491310 + 598 491311 In-131m 8.78240E-06 8.78240E-06 491311 + 599 491312 In-131m 8.78240E-06 8.78240E-06 491312 + 600 491320 In-132 3.66250E-07 3.66250E-07 491320 + 601 491330 In-133 1.15530E-08 1.42240E-08 491330 + 602 491331 In-133m 2.67130E-09 2.67130E-09 491331 + 603 501160 Sn-116 6.56690E-10 9.69690E-07 50116.82c + 604 501170 Sn-117 1.97820E-09 7.11760E-04 50117.82c + 605 501171 Sn-117m 6.47210E-09 1.60010E-06 501171 + 606 501180 Sn-118 9.65160E-08 2.76380E-04 50118.82c + 607 501190 Sn-119 7.55790E-08 9.13290E-05 50119.82c + 608 501191 Sn-119m 2.47270E-07 4.21180E-05 501191 + 609 501200 Sn-120 9.95040E-07 3.48340E-05 50120.82c + 610 501210 Sn-121 2.93370E-07 2.24600E-05 501210 + 611 501211 Sn-121m 7.08230E-07 2.55020E-06 501211 + 612 501220 Sn-122 3.98980E-06 3.89150E-05 50122.82c + 613 501230 Sn-123 6.39750E-06 1.05160E-05 50123.82c + 614 501231 Sn-123m 2.65000E-06 6.89980E-05 501231 + 615 501240 Sn-124 4.30530E-05 2.61650E-04 50124.82c + 616 501250 Sn-125 1.31640E-04 2.10590E-04 50125.82c + 617 501251 Sn-125m 5.45290E-05 5.45490E-04 501251 + 618 501260 Sn-126 9.95530E-04 1.84000E-03 50126.82c + 619 501270 Sn-127 1.71220E-03 2.10400E-03 501270 + 620 501271 Sn-127m 7.09230E-04 1.60750E-03 501271 + 621 501280 Sn-128 1.67680E-03 6.50320E-03 501280 + 622 501281 Sn-128m 3.92730E-03 4.34230E-03 501281 + 623 501290 Sn-129 1.67770E-03 2.20880E-03 501290 + 624 501291 Sn-129m 4.05010E-03 4.10040E-03 501291 + 625 501300 Sn-130 1.68600E-03 1.79110E-03 501300 + 626 501301 Sn-130m 3.94900E-03 4.00570E-03 501301 + 627 501310 Sn-131 7.67280E-04 7.84290E-04 501310 + 628 501311 Sn-131m 1.85230E-03 1.86150E-03 501311 + 629 501320 Sn-132 9.58670E-04 9.59050E-04 501320 + 630 501330 Sn-133 6.33640E-05 6.33660E-05 501330 + 631 501340 Sn-134 7.15120E-06 7.15120E-06 501340 + 632 501350 Sn-135 1.28030E-07 1.28030E-07 501350 + 633 501360 Sn-136 2.75560E-09 2.75560E-09 501360 + 634 511180 Sb-118 2.72460E-12 2.72460E-12 511180 + 635 511181 Sb-118m 3.86620E-12 3.86620E-12 511181 + 636 511190 Sb-119 1.60960E-10 2.12130E-10 511190 + 637 511191 Sb-119m 5.11660E-11 5.11660E-11 511191 + 638 511200 Sb-120 7.81910E-10 7.81910E-10 511200 + 639 511201 Sb-120m 1.10950E-09 1.10950E-09 511201 + 640 511210 Sb-121 2.73830E-08 2.30580E-05 51121.82c + 641 511220 Sb-122 1.65280E-07 3.52640E-07 511220 + 642 511221 Sb-122m 1.87360E-07 1.87360E-07 511221 + 643 511230 Sb-123 3.01610E-06 8.25300E-05 51123.82c + 644 511240 Sb-124 7.33040E-07 1.72200E-06 51124.82c + 645 511241 Sb-124m 5.60500E-07 1.31860E-06 511241 + 646 511242 Sb-124m 7.58070E-07 7.58070E-07 511242 + 647 511250 Sb-125 1.15960E-05 7.67680E-04 51125.82c + 648 511260 Sb-126 1.86220E-05 2.30700E-05 51126.82c + 649 511261 Sb-126m 1.37690E-05 3.17750E-05 511261 + 650 511262 Sb-126m 1.80070E-05 1.80070E-05 511262 + 651 511270 Sb-127 4.03770E-04 4.11530E-03 511270 + 652 511280 Sb-128 5.70840E-04 7.10910E-03 511280 + 653 511281 Sb-128m 9.74060E-04 9.74060E-04 511281 + 654 511290 Sb-129 4.05900E-03 8.99750E-03 511290 + 655 511291 Sb-129m 2.48040E-03 4.53050E-03 511291 + 656 511300 Sb-130 5.34450E-03 9.13840E-03 511300 + 657 511301 Sb-130m 5.34450E-03 7.34730E-03 511301 + 658 511310 Sb-131 1.78190E-02 2.04650E-02 511310 + 659 511320 Sb-132 7.60330E-03 8.56230E-03 511320 + 660 511321 Sb-132m 5.60370E-03 5.60370E-03 511321 + 661 511330 Sb-133 8.32450E-03 8.38910E-03 511330 + 662 511340 Sb-134 5.08430E-04 5.14380E-04 511340 + 663 511341 Sb-134m 1.19090E-03 1.19090E-03 511341 + 664 511350 Sb-135 3.68600E-04 3.68700E-04 511350 + 665 511360 Sb-136 4.27100E-05 4.27120E-05 511360 + 666 511370 Sb-137 5.99780E-06 5.99780E-06 511370 + 667 511380 Sb-138 1.39190E-08 1.39190E-08 511380 + 668 521210 Te-121 2.03030E-12 7.92200E-12 521210 + 669 521211 Te-121m 6.64230E-12 6.64230E-12 521211 + 670 521220 Te-122 7.09020E-10 3.44180E-07 52122.82c + 671 521250 Te-125 9.36590E-11 7.67680E-04 52125.82c + 672 521251 Te-125m 3.06420E-10 1.71780E-04 521251 + 673 521260 Te-126 2.09990E-06 5.24970E-05 52126.82c + 674 521270 Te-127 2.44370E-06 4.10720E-03 521270 + 675 521271 Te-127m 5.89940E-06 6.84080E-04 52527.82c + 676 521280 Te-128 9.96230E-05 8.14780E-03 52128.82c + 677 521290 Te-129 1.97870E-04 1.14030E-02 521290 + 678 521291 Te-129m 4.77670E-04 5.73160E-03 52529.82c + 679 521300 Te-130 3.98020E-03 2.04660E-02 52130.82c + 680 521310 Te-131 2.85330E-03 2.34700E-02 521310 + 681 521311 Te-131m 6.88820E-03 8.52670E-03 521311 + 682 521320 Te-132 2.69410E-02 4.11070E-02 52132.82c + 683 521330 Te-133 9.72190E-03 2.10220E-02 521330 + 684 521331 Te-133m 2.34700E-02 2.49210E-02 521331 + 685 521340 Te-134 3.55680E-02 3.73300E-02 521340 + 686 521350 Te-135 1.14840E-02 1.18020E-02 521350 + 687 521360 Te-136 4.47740E-03 4.51600E-03 521360 + 688 521370 Te-137 7.54140E-04 7.57200E-04 521370 + 689 521380 Te-138 1.71200E-04 1.71210E-04 521380 + 690 521390 Te-139 1.39800E-05 1.39800E-05 521390 + 691 521400 Te-140 1.19750E-07 1.19750E-07 521400 + 692 521410 Te-141 1.46450E-09 1.46450E-09 521410 + 693 531270 I-127 2.54140E-10 4.12370E-03 53127.82c + 694 531280 I-128 2.25550E-08 2.25550E-08 531280 + 695 531290 I-129 2.04430E-06 1.35260E-02 53129.82c + 696 531300 I-130 2.70260E-05 3.67180E-05 53130.82c + 697 531301 I-130m 1.15380E-05 1.15380E-05 531301 + 698 531310 I-131 4.41050E-04 3.06470E-02 53131.82c + 699 531320 I-132 1.03990E-03 4.28060E-02 531320 + 700 531321 I-132m 7.66410E-04 7.66410E-04 531321 + 701 531330 I-133 6.02580E-03 5.12900E-02 531330 + 702 531331 I-133m 3.68230E-03 3.68230E-03 531331 + 703 531340 I-134 1.35270E-02 6.05970E-02 531340 + 704 531341 I-134m 9.96940E-03 9.96940E-03 531341 + 705 531350 I-135 4.82380E-02 6.00400E-02 53135.82c + 706 531360 I-136 8.39200E-03 1.29190E-02 531360 + 707 531361 I-136m 1.96560E-02 1.96670E-02 531361 + 708 531370 I-137 1.85950E-02 1.93400E-02 531370 + 709 531380 I-138 4.88680E-03 5.04720E-03 531380 + 710 531390 I-139 2.46930E-03 2.48330E-03 531390 + 711 531400 I-140 3.66720E-04 3.66840E-04 531400 + 712 531410 I-141 5.67800E-05 5.67810E-05 531410 + 713 531420 I-142 9.79310E-07 9.79310E-07 531420 + 714 531430 I-143 1.22810E-08 1.22810E-08 531430 + 715 541300 Xe-130 1.37540E-08 3.85780E-05 54130.82c + 716 541310 Xe-131 5.93560E-07 3.06490E-02 54131.82c + 717 541311 Xe-131m 1.43290E-06 3.34320E-04 541311 + 718 541320 Xe-132 1.50480E-05 4.29450E-02 54132.82c + 719 541321 Xe-132m 1.70570E-05 1.70570E-05 541321 + 720 541330 Xe-133 9.12940E-05 5.16020E-02 54133.82c + 721 541331 Xe-133m 2.20400E-04 1.68030E-03 541331 + 722 541340 Xe-134 7.55810E-04 6.33520E-02 54134.82c + 723 541341 Xe-134m 1.77030E-03 1.99960E-03 541341 + 724 541350 Xe-135 3.28190E-03 7.11380E-02 54135.82c + 725 541351 Xe-135m 7.92310E-03 1.78350E-02 541351 + 726 541360 Xe-136 4.14400E-02 7.52840E-02 54136.82c + 727 541370 Xe-137 4.29200E-02 6.12710E-02 541370 + 728 541380 Xe-138 4.15130E-02 4.65360E-02 541380 + 729 541390 Xe-139 2.01690E-02 2.24430E-02 541390 + 730 541400 Xe-140 1.38100E-02 1.41550E-02 541400 + 731 541410 Xe-141 3.91970E-03 3.96480E-03 541410 + 732 541420 Xe-142 1.31820E-03 1.31890E-03 541420 + 733 541430 Xe-143 1.53050E-04 1.53060E-04 541430 + 734 541440 Xe-144 2.50650E-05 2.50650E-05 541440 + 735 541450 Xe-145 6.23370E-08 6.23370E-08 541450 + 736 541460 Xe-146 1.11090E-09 1.11090E-09 541460 + 737 551320 Cs-132 2.02350E-09 2.02350E-09 551320 + 738 551330 Cs-133 1.80160E-07 5.16020E-02 55133.82c + 739 551340 Cs-134 4.70600E-06 8.17440E-06 55134.82c + 740 551341 Cs-134m 3.46840E-06 3.46840E-06 551341 + 741 551350 Cs-135 8.23790E-05 7.13770E-02 55135.82c + 742 551351 Cs-135m 5.03410E-05 5.03410E-05 551351 + 743 551360 Cs-136 6.30750E-04 8.15580E-04 55136.82c + 744 551361 Cs-136m 3.69650E-04 3.69650E-04 551361 + 745 551370 Cs-137 7.62020E-03 6.88910E-02 55137.82c + 746 551380 Cs-138 6.55030E-03 6.06150E-02 551380 + 747 551381 Cs-138m 9.29470E-03 9.29470E-03 551381 + 748 551390 Cs-139 2.60580E-02 4.85010E-02 551390 + 749 551400 Cs-140 2.24400E-02 3.65960E-02 551400 + 750 551410 Cs-141 2.59530E-02 2.99210E-02 551410 + 751 551420 Cs-142 1.27870E-02 1.41030E-02 551420 + 752 551430 Cs-143 6.67640E-03 6.82870E-03 551430 + 753 551440 Cs-144 8.69800E-04 1.32900E-03 551440 + 754 551441 Cs-144m 8.69800E-04 8.69800E-04 551441 + 755 551450 Cs-145 4.17890E-04 4.17950E-04 551450 + 756 551460 Cs-146 5.22070E-05 5.22080E-05 551460 + 757 551470 Cs-147 2.96200E-06 2.96200E-06 551470 + 758 551480 Cs-148 5.64960E-09 5.64960E-09 551480 + 759 561350 Ba-135 1.08870E-08 3.71700E-08 56135.82c + 760 561351 Ba-135m 2.62830E-08 2.62830E-08 561351 + 761 561360 Ba-136 2.37870E-06 1.00840E-03 56136.82c + 762 561361 Ba-136m 5.57140E-06 5.57140E-06 561361 + 763 561370 Ba-137 3.78190E-05 6.90200E-02 56137.82c + 764 561371 Ba-137m 9.13010E-05 6.51240E-02 561371 + 765 561380 Ba-138 1.55860E-03 6.39400E-02 56138.82c + 766 561390 Ba-139 4.89030E-03 5.33910E-02 561390 + 767 561400 Ba-140 1.40650E-02 5.06610E-02 56140.82c + 768 561410 Ba-141 1.93160E-02 4.92370E-02 561410 + 769 561420 Ba-142 3.46240E-02 4.88390E-02 561420 + 770 561430 Ba-143 2.80750E-02 3.48340E-02 561430 + 771 561440 Ba-144 2.29250E-02 2.47060E-02 561440 + 772 561450 Ba-145 8.63450E-03 9.00010E-03 561450 + 773 561460 Ba-146 3.98610E-03 4.03170E-03 561460 + 774 561470 Ba-147 8.42670E-04 8.44790E-04 561470 + 775 561480 Ba-148 2.01710E-04 2.01710E-04 561480 + 776 561490 Ba-149 2.07850E-05 2.07850E-05 561490 + 777 561500 Ba-150 1.98010E-06 1.98010E-06 561500 + 778 561510 Ba-151 3.28310E-10 3.28310E-10 561510 + 779 571370 La-137 4.28190E-09 4.28190E-09 571370 + 780 571380 La-138 1.01440E-06 1.01440E-06 57138.82c + 781 571390 La-139 5.09620E-05 5.34420E-02 57139.82c + 782 571400 La-140 2.31720E-04 5.08930E-02 57140.82c + 783 571410 La-141 1.10710E-03 5.03440E-02 571410 + 784 571420 La-142 2.61220E-03 5.14510E-02 571420 + 785 571430 La-143 8.82030E-03 4.36540E-02 571430 + 786 571440 La-144 1.41320E-02 3.88380E-02 571440 + 787 571450 La-145 1.87560E-02 2.77560E-02 571450 + 788 571460 La-146 4.30870E-03 8.34040E-03 571460 + 789 571461 La-146m 7.75030E-03 7.75030E-03 571461 + 790 571470 La-147 9.65460E-03 1.05000E-02 571470 + 791 571480 La-148 3.42600E-03 3.62700E-03 571480 + 792 571490 La-149 1.28420E-03 1.30490E-03 571490 + 793 571500 La-150 2.06420E-04 2.08400E-04 571500 + 794 571510 La-151 3.55820E-05 3.55820E-05 571510 + 795 571520 La-152 2.96150E-06 2.96150E-06 571520 + 796 571530 La-153 2.02970E-09 2.02970E-09 571530 + 797 581400 Ce-140 1.99320E-06 5.08950E-02 58140.82c + 798 581410 Ce-141 1.99390E-05 5.03640E-02 58141.82c + 799 581420 Ce-142 1.41270E-04 5.15920E-02 58142.82c + 800 581430 Ce-143 5.78700E-04 4.42330E-02 58143.82c + 801 581440 Ce-144 2.65540E-03 4.14940E-02 58144.82c + 802 581450 Ce-145 6.26110E-03 3.40170E-02 581450 + 803 581460 Ce-146 1.35030E-02 2.95940E-02 581460 + 804 581470 Ce-147 1.51320E-02 2.56320E-02 581470 + 805 581480 Ce-148 1.65180E-02 2.01630E-02 581480 + 806 581490 Ce-149 9.21850E-03 1.05110E-02 581490 + 807 581500 Ce-150 5.46240E-03 5.66520E-03 581500 + 808 581510 Ce-151 1.49480E-03 1.53060E-03 581510 + 809 581520 Ce-152 4.27130E-04 4.29910E-04 581520 + 810 581530 Ce-153 4.16040E-05 4.16060E-05 581530 + 811 581540 Ce-154 8.01440E-06 8.01440E-06 581540 + 812 581550 Ce-155 6.31440E-09 6.31440E-09 581550 + 813 581560 Ce-156 8.99170E-11 8.99170E-11 581560 + 814 591420 Pr-142 7.24000E-10 2.41980E-09 59142.82c + 815 591421 Pr-142m 1.69580E-09 1.69580E-09 591421 + 816 591430 Pr-143 9.95200E-07 4.42340E-02 59143.82c + 817 591440 Pr-144 1.01500E-06 4.15030E-02 591440 + 818 591441 Pr-144m 9.01500E-06 5.81600E-04 591441 + 819 591450 Pr-145 8.24110E-05 3.41000E-02 591450 + 820 591460 Pr-146 4.10980E-04 3.00050E-02 591460 + 821 591470 Pr-147 1.52170E-03 2.71540E-02 591470 + 822 591480 Pr-148 6.13720E-04 2.07770E-02 591480 + 823 591481 Pr-148m 2.58110E-03 2.58110E-03 591481 + 824 591490 Pr-149 6.05990E-03 1.65710E-02 591490 + 825 591500 Pr-150 6.16020E-03 1.18250E-02 591500 + 826 591510 Pr-151 5.75040E-03 7.28100E-03 591510 + 827 591520 Pr-152 2.64360E-03 3.07380E-03 591520 + 828 591530 Pr-153 1.29880E-03 1.34020E-03 591530 + 829 591540 Pr-154 2.68730E-04 2.76690E-04 591540 + 830 591550 Pr-155 6.15540E-05 6.15600E-05 591550 + 831 591560 Pr-156 1.00920E-05 1.00920E-05 591560 + 832 591570 Pr-157 1.99240E-08 1.99240E-08 591570 + 833 591580 Pr-158 2.78940E-10 2.78940E-10 591580 + 834 601450 Nd-145 1.68210E-08 3.41000E-02 60145.82c + 835 601460 Nd-146 1.18310E-05 3.00170E-02 60146.82c + 836 601470 Nd-147 6.22670E-05 2.72160E-02 60147.82c + 837 601480 Nd-148 2.99590E-04 2.36580E-02 60148.82c + 838 601490 Nd-149 9.71380E-04 1.75420E-02 601490 + 839 601500 Nd-150 2.59510E-03 1.44200E-02 60150.82c + 840 601510 Nd-151 3.87880E-03 1.11600E-02 601510 + 841 601520 Nd-152 5.49040E-03 8.56420E-03 601520 + 842 601530 Nd-153 4.07390E-03 5.41410E-03 601530 + 843 601540 Nd-154 2.77480E-03 3.05150E-03 601540 + 844 601550 Nd-155 1.03390E-03 1.09570E-03 601550 + 845 601560 Nd-156 3.52580E-04 3.62400E-04 601560 + 846 601570 Nd-157 7.50230E-05 7.50420E-05 601570 + 847 601580 Nd-158 1.33770E-05 1.33770E-05 601580 + 848 601590 Nd-159 3.92130E-08 3.92130E-08 601590 + 849 601600 Nd-160 1.08140E-09 1.08140E-09 601600 + 850 601610 Nd-161 7.44510E-12 7.44510E-12 601610 + 851 611470 Pm-147 1.66480E-09 2.72160E-02 61147.82c + 852 611480 Pm-148 1.87630E-08 2.09610E-08 61148.82c + 853 611481 Pm-148m 4.39490E-08 4.39490E-08 61548.82c + 854 611490 Pm-149 3.96040E-06 1.75460E-02 61149.82c + 855 611500 Pm-150 4.55750E-05 4.55750E-05 611500 + 856 611510 Pm-151 1.81370E-04 1.13410E-02 61151.82c + 857 611520 Pm-152 9.02740E-05 8.65440E-03 611520 + 858 611521 Pm-152m 1.80270E-04 1.80270E-04 611521 + 859 611522 Pm-152m 1.99390E-04 1.99390E-04 611522 + 860 611530 Pm-153 1.09200E-03 6.50610E-03 611530 + 861 611540 Pm-154 7.03350E-04 3.75480E-03 611540 + 862 611541 Pm-154m 7.03350E-04 7.03350E-04 611541 + 863 611550 Pm-155 1.59270E-03 2.68840E-03 611550 + 864 611560 Pm-156 1.00290E-03 1.36530E-03 611560 + 865 611570 Pm-157 5.69570E-04 6.44610E-04 611570 + 866 611580 Pm-158 1.64510E-04 1.77890E-04 611580 + 867 611590 Pm-159 5.54050E-05 5.54440E-05 611590 + 868 611600 Pm-160 8.84800E-06 8.84910E-06 611600 + 869 611610 Pm-161 6.74520E-08 6.74590E-08 611610 + 870 611620 Pm-162 1.91420E-09 1.91420E-09 611620 + 871 611630 Pm-163 3.26530E-11 3.26530E-11 611630 + 872 621500 Sm-150 9.20570E-09 4.55840E-05 62150.82c + 873 621510 Sm-151 2.96720E-06 1.13440E-02 62151.82c + 874 621520 Sm-152 3.16280E-05 9.06570E-03 62152.82c + 875 621530 Sm-153 3.08830E-05 6.61150E-03 62153.82c + 876 621531 Sm-153m 7.45570E-05 7.45570E-05 621531 + 877 621540 Sm-154 3.68630E-04 4.82680E-03 62154.82c + 878 621550 Sm-155 6.50280E-04 3.33870E-03 621550 + 879 621560 Sm-156 1.01320E-03 2.37850E-03 621560 + 880 621570 Sm-157 9.67260E-04 1.61190E-03 621570 + 881 621580 Sm-158 8.24370E-04 1.00230E-03 621580 + 882 621590 Sm-159 3.85820E-04 4.41280E-04 621590 + 883 621600 Sm-160 1.48950E-04 1.57770E-04 621600 + 884 621610 Sm-161 3.70020E-05 3.70700E-05 621610 + 885 621620 Sm-162 8.88960E-06 8.89150E-06 621620 + 886 621630 Sm-163 1.02030E-07 1.02060E-07 621630 + 887 621640 Sm-164 4.83930E-09 4.83930E-09 621640 + 888 621650 Sm-165 6.64040E-11 6.64040E-11 621650 + 889 631520 Eu-152 1.82870E-10 3.86830E-10 63152.82c + 890 631521 Eu-152m 4.35550E-11 4.35550E-11 631521 + 891 631522 Eu-152m 2.03960E-10 2.03960E-10 631522 + 892 631530 Eu-153 2.23260E-08 6.61160E-03 63153.82c + 893 631540 Eu-154 1.05390E-06 2.00330E-06 63154.82c + 894 631541 Eu-154m 9.49360E-07 9.49360E-07 631541 + 895 631550 Eu-155 9.07860E-06 3.34780E-03 63155.82c + 896 631560 Eu-156 4.11330E-05 2.41960E-03 63156.82c + 897 631570 Eu-157 1.15470E-04 1.72730E-03 63157.82c + 898 631580 Eu-158 1.64790E-04 1.16710E-03 631580 + 899 631590 Eu-159 2.19210E-04 6.60490E-04 631590 + 900 631600 Eu-160 1.89990E-04 3.47760E-04 631600 + 901 631610 Eu-161 1.26780E-04 1.63850E-04 631610 + 902 631620 Eu-162 6.20990E-05 7.09910E-05 631620 + 903 631630 Eu-163 1.41350E-05 1.42370E-05 631630 + 904 631640 Eu-164 3.76100E-06 3.76580E-06 631640 + 905 631650 Eu-165 1.19090E-07 1.19160E-07 631650 + 906 631660 Eu-166 4.18770E-09 4.18770E-09 631660 + 907 631670 Eu-167 3.31750E-11 3.31750E-11 631670 + 908 641550 Gd-155 2.95800E-07 3.34880E-03 64155.82c + 909 641551 Gd-155m 7.14100E-07 7.14100E-07 641551 + 910 641560 Gd-156 2.01820E-06 2.42170E-03 64156.82c + 911 641570 Gd-157 3.94940E-06 1.73130E-03 64157.82c + 912 641580 Gd-158 2.19000E-05 1.18900E-03 64158.82c + 913 641590 Gd-159 4.59080E-05 7.06400E-04 641590 + 914 641600 Gd-160 9.73240E-05 4.45090E-04 64160.82c + 915 641610 Gd-161 8.68180E-05 2.50670E-04 641610 + 916 641620 Gd-162 1.32880E-04 2.03870E-04 641620 + 917 641630 Gd-163 7.44360E-05 8.86730E-05 641630 + 918 641640 Gd-164 3.94940E-05 4.32600E-05 641640 + 919 641650 Gd-165 1.06160E-05 1.07350E-05 641650 + 920 641660 Gd-166 1.94110E-06 1.94530E-06 641660 + 921 641670 Gd-167 2.67970E-08 2.68300E-08 641670 + 922 641680 Gd-168 5.60580E-09 5.60580E-09 641680 + 923 641690 Gd-169 7.25670E-11 7.25670E-11 641690 + 924 651570 Tb-157 1.05140E-10 1.05140E-10 651570 + 925 651580 Tb-158 2.73270E-09 3.03850E-09 651580 + 926 651581 Tb-158m 3.07690E-10 3.07690E-10 651581 + 927 651590 Tb-159 9.05570E-07 7.07300E-04 65159.82c + 928 651600 Tb-160 8.83870E-07 8.83870E-07 65160.82c + 929 651610 Tb-161 5.97680E-06 2.56640E-04 651610 + 930 651620 Tb-162 6.21010E-06 2.10080E-04 651620 + 931 651630 Tb-163 1.79000E-05 1.06570E-04 651630 + 932 651640 Tb-164 1.78630E-05 6.11230E-05 651640 + 933 651650 Tb-165 2.02660E-05 3.10010E-05 651650 + 934 651660 Tb-166 1.16470E-05 1.35920E-05 651660 + 935 651670 Tb-167 9.33380E-07 9.60210E-07 651670 + 936 651680 Tb-168 4.18430E-07 4.24040E-07 651680 + 937 651690 Tb-169 3.34930E-08 3.35660E-08 651690 + 938 651700 Tb-170 1.07770E-08 1.07770E-08 651700 + 939 651710 Tb-171 4.27280E-10 4.27280E-10 651710 + 940 661600 Dy-160 2.82840E-10 8.84150E-07 66160.82c + 941 661610 Dy-161 4.50430E-09 2.56650E-04 66161.82c + 942 661620 Dy-162 9.84230E-08 2.10180E-04 66162.82c + 943 661630 Dy-163 4.66870E-07 1.07040E-04 66163.82c + 944 661640 Dy-164 5.64090E-06 6.67660E-05 66164.82c + 945 661650 Dy-165 2.51120E-06 3.38880E-05 661650 + 946 661651 Dy-165m 3.83890E-07 3.83890E-07 661651 + 947 661660 Dy-166 6.79340E-06 2.03860E-05 661660 + 948 661670 Dy-167 2.80230E-06 3.76250E-06 661670 + 949 661680 Dy-168 3.61100E-06 4.03500E-06 661680 + 950 661690 Dy-169 1.27720E-06 1.31080E-06 661690 + 951 661700 Dy-170 1.03510E-06 1.04590E-06 661700 + 952 661710 Dy-171 9.03700E-08 9.07970E-08 661710 + 953 661720 Dy-172 1.70360E-08 1.70360E-08 661720 + 954 661730 Dy-173 8.96710E-10 8.96710E-10 661730 + 955 671620 Ho-162 2.99860E-12 7.35310E-12 671620 + 956 671621 Ho-162m 7.02340E-12 7.02340E-12 671621 + 957 671630 Ho-163 3.03060E-10 3.49390E-10 671630 + 958 671631 Ho-163m 4.63290E-11 4.63290E-11 671631 + 959 671640 Ho-164 1.39940E-09 4.67700E-09 671640 + 960 671641 Ho-164m 3.27760E-09 3.27760E-09 671641 + 961 671650 Ho-165 9.65050E-07 3.48610E-05 67165.82c + 962 671660 Ho-166 6.24010E-08 2.04480E-05 671660 + 963 671661 Ho-166m 1.46160E-07 1.46160E-07 671661 + 964 671670 Ho-167 2.02470E-07 3.96500E-06 671670 + 965 671680 Ho-168 3.73190E-07 4.93510E-06 671680 + 966 671681 Ho-168m 5.29540E-07 5.29540E-07 671681 + 967 671690 Ho-169 6.40840E-07 1.95160E-06 671690 + 968 671700 Ho-170 1.47270E-06 1.47270E-06 671700 + 969 671701 Ho-170m 6.28740E-07 1.67460E-06 671701 + 970 671710 Ho-171 9.43640E-07 1.03440E-06 671710 + 971 671720 Ho-172 3.57050E-07 3.74090E-07 671720 + 972 671730 Ho-173 1.10470E-07 1.11370E-07 671730 + 973 671740 Ho-174 7.95420E-09 7.95420E-09 671740 + 974 671750 Ho-175 1.20670E-09 1.20670E-09 671750 + 975 681650 Er-165 1.71040E-11 1.71040E-11 681650 + 976 681660 Er-166 4.55010E-10 2.04480E-05 68166.82c + 977 681670 Er-167 8.77370E-10 3.96600E-06 68167.82c + 978 681671 Er-167m 1.34120E-10 4.73920E-07 681671 + 979 681680 Er-168 2.53200E-08 4.96310E-06 68168.82c + 980 681690 Er-169 3.95640E-08 1.99120E-06 681690 + 981 681700 Er-170 6.83790E-07 3.83110E-06 68170.82c + 982 681710 Er-171 1.60360E-06 2.63800E-06 681710 + 983 681720 Er-172 1.02520E-06 1.39930E-06 681720 + 984 681730 Er-173 5.78230E-07 6.89600E-07 681730 + 985 681740 Er-174 2.21360E-07 2.29310E-07 681740 + 986 681750 Er-175 6.97320E-08 7.09390E-08 681750 + 987 681760 Er-176 1.60400E-08 1.60400E-08 681760 + 988 681770 Er-177 1.30780E-09 1.30780E-09 681770 + 989 691680 Tm-168 1.14020E-11 1.14020E-11 691680 + 990 691690 Tm-169 1.14220E-10 1.99130E-06 691690 + 991 691700 Tm-170 4.42430E-09 4.42430E-09 691700 + 992 691710 Tm-171 2.10070E-08 2.65900E-06 691710 + 993 691720 Tm-172 7.69830E-08 1.47630E-06 691720 + 994 691730 Tm-173 2.21620E-07 9.11220E-07 691730 + 995 691740 Tm-174 3.88510E-07 6.17820E-07 691740 + 996 691750 Tm-175 2.33790E-07 3.04730E-07 691750 + 997 691760 Tm-176 1.00800E-07 1.16840E-07 691760 + 998 691770 Tm-177 4.52490E-08 4.65570E-08 691770 + 999 691780 Tm-178 7.10980E-09 7.10980E-09 691780 + 1000 691790 Tm-179 1.36280E-09 1.36280E-09 691790 + 1001 701700 Yb-170 2.39820E-12 4.42090E-09 701700 + 1002 701710 Yb-171 3.65780E-12 2.65910E-06 701710 + 1003 701711 Yb-171m 2.39270E-11 2.39270E-11 701711 + 1004 701720 Yb-172 6.34760E-10 1.47690E-06 701720 + 1005 701730 Yb-173 3.99800E-09 9.15220E-07 701730 + 1006 701740 Yb-174 1.54180E-08 6.33270E-07 701740 + 1007 701750 Yb-175 3.97170E-08 3.50520E-07 701750 + 1008 701751 Yb-175m 6.07160E-09 2.40710E-07 701751 + 1009 701760 Yb-176 3.50800E-08 2.02870E-07 701760 + 1010 701761 Yb-176m 6.31000E-08 1.21520E-07 701761 + 1011 701770 Yb-177 6.35200E-08 1.24760E-07 701770 + 1012 701771 Yb-177m 1.46870E-08 6.12440E-08 701771 + 1013 701780 Yb-178 6.14500E-08 6.85600E-08 701780 + 1014 701790 Yb-179 2.28220E-08 2.41850E-08 701790 + 1015 701800 Yb-180 8.65300E-09 8.65300E-09 701800 + 1016 701810 Yb-181 1.11550E-09 1.11550E-09 701810 + 1017 711730 Lu-173 2.97160E-12 2.97160E-12 711730 + 1018 711740 Lu-174 8.01110E-12 2.66660E-11 711740 + 1019 711741 Lu-174m 1.87640E-11 1.87640E-11 711741 + 1020 711750 Lu-175 4.88990E-10 3.51010E-07 71175.82c + 1021 711760 Lu-176 1.43320E-09 1.35850E-08 71176.82c + 1022 711761 Lu-176m 7.96780E-10 7.96780E-10 711761 + 1023 711770 Lu-177 6.90810E-09 1.32290E-07 711770 + 1024 711771 Lu-177m 2.70060E-09 2.74420E-09 711771 + 1025 711772 Lu-177m 8.72730E-11 8.72730E-11 711772 + 1026 711780 Lu-178 6.64520E-09 7.52050E-08 711780 + 1027 711781 Lu-178m 7.53280E-09 7.53280E-09 711781 + 1028 711790 Lu-179 2.23410E-08 4.99410E-08 711790 + 1029 711791 Lu-179m 3.41530E-09 2.76000E-08 711791 + 1030 711800 Lu-180 5.02760E-09 1.55730E-08 711800 + 1031 711801 Lu-180m 5.02760E-09 1.36810E-08 711801 + 1032 711802 Lu-180m 7.40960E-09 7.40960E-09 711802 + 1033 711810 Lu-181 1.15750E-08 1.26910E-08 711810 + 1034 711820 Lu-182 2.96680E-09 2.96680E-09 711820 + 1035 711830 Lu-183 9.18800E-10 9.18800E-10 711830 + 1036 711840 Lu-184 9.48220E-11 9.48220E-11 711840 + 1037 721760 Hf-176 4.83500E-12 8.00860E-10 72176.82c + 1038 721770 Hf-177 3.42680E-11 1.34510E-07 72177.82c + 1039 721771 Hf-177m 1.33150E-11 2.18150E-09 721771 + 1040 721772 Hf-177m 5.14690E-13 4.41510E-11 721772 + 1041 721780 Hf-178 1.50840E-10 8.31600E-08 72178.82c + 1042 721781 Hf-178m 2.48870E-10 7.80410E-09 721781 + 1043 721782 Hf-178m 2.24590E-11 2.24590E-11 721782 + 1044 721790 Hf-179 9.50470E-10 5.15250E-08 72179.82c + 1045 721791 Hf-179m 2.96710E-10 2.96710E-10 721791 + 1046 721792 Hf-179m 3.32730E-10 3.32730E-10 721792 + 1047 721800 Hf-180 2.01790E-09 3.17560E-08 72180.82c + 1048 721801 Hf-180m 3.62970E-09 7.33450E-09 721801 + 1049 721810 Hf-181 6.78650E-09 1.94770E-08 721810 + 1050 721820 Hf-182 3.02570E-09 8.27830E-09 721820 + 1051 721821 Hf-182m 5.44250E-09 5.44250E-09 721821 + 1052 721830 Hf-183 4.77960E-09 5.69840E-09 721830 + 1053 721840 Hf-184 9.36700E-10 9.84110E-10 721840 + 1054 721841 Hf-184m 1.68490E-09 1.73230E-09 721841 + 1055 721850 Hf-185 5.78410E-10 5.78410E-10 721850 + 1056 721860 Hf-186 1.33410E-10 1.33410E-10 721860 + 1057 721870 Hf-187 1.09000E-11 1.09000E-11 721870 + 1058 731790 Ta-179 3.43540E-12 4.52690E-12 731790 + 1059 731791 Ta-179m 1.05080E-12 1.09160E-12 731791 + 1060 731800 Ta-180 1.70090E-11 1.70090E-11 731800 + 1061 731801 Ta-180m 1.92800E-11 4.20170E-11 731801 + 1062 731810 Ta-181 2.54470E-10 1.97320E-08 73181.82c + 1063 731820 Ta-182 2.25790E-10 3.78850E-09 73182.82c + 1064 731821 Ta-182m 2.30460E-10 3.56280E-09 731821 + 1065 731822 Ta-182m 1.75680E-10 3.33230E-09 731822 + 1066 731830 Ta-183 1.82100E-09 7.51940E-09 731830 + 1067 731840 Ta-184 1.78100E-09 4.49740E-09 731840 + 1068 731850 Ta-185 1.29870E-09 2.50610E-09 731850 + 1069 731851 Ta-185m 6.29010E-10 6.29010E-10 731851 + 1070 731860 Ta-186 8.33140E-10 9.66550E-10 731860 + 1071 731870 Ta-187 3.74610E-10 3.85510E-10 731870 + 1072 731880 Ta-188 5.90000E-11 5.90000E-11 731880 + 1073 731890 Ta-189 1.13410E-11 1.13410E-11 731890 + 1074 741820 W-182 5.17360E-12 3.79370E-09 74182.82c + 1075 741830 W-183 7.63800E-12 7.55200E-09 74183.82c + 1076 741831 W-183m 2.49890E-11 2.80650E-10 741831 + 1077 741840 W-184 1.80370E-10 4.67780E-09 74184.82c + 1078 741850 W-185 1.09910E-10 2.88140E-09 741850 + 1079 741851 W-185m 2.65330E-10 2.65330E-10 741851 + 1080 741860 W-186 6.09970E-10 1.77380E-09 74186.82c + 1081 741861 W-186m 1.96760E-10 1.96760E-10 741861 + 1082 741870 W-187 6.43670E-10 1.02920E-09 741870 + 1083 741880 W-188 5.06810E-10 5.65810E-10 741880 + 1084 741890 W-189 1.88700E-10 2.00040E-10 741890 + 1085 741900 W-190 3.36100E-11 7.17080E-11 741900 + 1086 741901 W-190m 3.80990E-11 3.80990E-11 741901 + 1087 741910 W-191 9.26890E-12 9.26890E-12 741910 + 1088 741920 W-192 1.18780E-12 1.18780E-12 741920 + 1089 751850 Re-185 3.97940E-12 2.88530E-09 75185.82c + 1090 751860 Re-186 7.52470E-12 7.52470E-12 751860 + 1091 751861 Re-186m 1.06770E-11 1.06770E-11 751861 + 1092 751870 Re-187 7.93100E-11 1.10850E-09 75187.82c + 1093 751880 Re-188 3.47790E-11 6.82050E-10 751880 + 1094 751881 Re-188m 8.14610E-11 8.14610E-11 751881 + 1095 751890 Re-189 2.11720E-10 4.11760E-10 751890 + 1096 751900 Re-190 5.13980E-11 1.65260E-10 751900 + 1097 751901 Re-190m 9.24520E-11 9.24520E-11 751901 + 1098 751910 Re-191 9.55700E-11 1.04840E-10 751910 + 1099 751920 Re-192 2.45640E-11 2.57520E-11 751920 + 1100 751930 Re-193 7.62400E-12 7.62400E-12 751930 + 1101 761880 Os-188 3.43760E-12 6.85490E-10 761880 + 1102 761890 Os-189 3.02060E-12 4.24660E-10 761890 + 1103 761891 Os-189m 9.88240E-12 5.22240E-11 761891 + 1104 761900 Os-190 2.16730E-11 2.61800E-10 761900 + 1105 761901 Os-190m 2.45680E-11 7.48620E-11 761901 + 1106 761910 Os-191 4.26670E-11 1.60550E-10 761910 + 1107 761911 Os-191m 1.30410E-11 1.30410E-11 761911 + 1108 761920 Os-192 3.26710E-11 9.11220E-11 761920 + 1109 761921 Os-192m 3.70340E-11 3.70340E-11 761921 + 1110 761930 Os-193 3.94200E-11 4.70440E-11 761930 + 1111 761940 Os-194 2.16600E-11 2.16600E-11 761940 + 1112 761950 Os-195 4.79320E-12 4.79320E-12 761950 + 1113 761960 Os-196 1.10890E-12 1.10890E-12 761960 + 1114 771910 Ir-191 6.07740E-13 1.62620E-10 77191.82c + 1115 771911 Ir-191m 1.15800E-12 7.72450E-11 771911 + 1116 771920 Ir-192 1.72290E-12 9.98290E-12 771920 + 1117 771921 Ir-192m 1.72290E-12 1.72290E-12 771921 + 1118 771922 Ir-192m 1.72290E-12 6.53740E-12 771922 + 1119 771930 Ir-193 4.37300E-12 6.19740E-11 77193.82c + 1120 771931 Ir-193m 1.05570E-11 1.07210E-11 771931 + 1121 771940 Ir-194 4.87620E-12 3.14120E-11 771940 + 1122 771941 Ir-194m 4.87620E-12 4.87620E-12 771941 + 1123 771942 Ir-194m 4.87620E-12 4.87620E-12 771942 + 1124 771950 Ir-195 4.65100E-12 1.00060E-11 771950 + 1125 771951 Ir-195m 1.12280E-11 1.12280E-11 771951 + 1126 771960 Ir-196 3.44080E-12 4.56000E-12 771960 + 1127 771961 Ir-196m 3.44080E-12 3.44080E-12 771961 + 1128 771971 Ir-197m 2.19230E-12 2.19230E-12 771971 + 1129 781940 Pt-194 1.47200E-12 3.77600E-11 781940 + 1130 781950 Pt-195 8.99880E-13 2.37450E-11 781950 + 1131 781951 Pt-195m 2.17240E-12 5.58580E-12 781951 + 1132 781960 Pt-196 6.62450E-12 1.46150E-11 781960 + 1133 781970 Pt-197 1.55120E-12 8.20070E-12 781970 + 1134 781971 Pt-197m 3.74490E-12 5.93170E-12 781971 + 1135 781980 Pt-198 4.17900E-12 4.17900E-12 781980 + 1136 781990 Pt-199 6.32070E-13 1.55990E-12 781990 + 1137 791990 Au-199 1.74010E-12 3.30000E-12 791990 + + Neutron-induced fission: + + Interpolation region : 2 / 2 + Interpolation energy : 4.00000E-01 MeV + Number of products : 1101 / 1172 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 3.82810E-05 3.82810E-05 1001.82c + 2 10020 H-2 1.16990E-05 1.16990E-05 1002.82c + 3 10030 H-3 1.91000E-04 1.91000E-04 1003.82c + 4 20040 He-4 2.42000E-03 2.42000E-03 2004.82c + 5 200500 Ca-50 1.27950E-12 1.27950E-12 200500 + 6 200510 Ca-51 1.18030E-12 1.18030E-12 200510 + 7 200520 Ca-52 1.31410E-12 1.31410E-12 200520 + 8 210510 Sc-51 1.92520E-12 3.13180E-12 210510 + 9 210520 Sc-52 3.52890E-12 4.81670E-12 210520 + 10 210530 Sc-53 6.84660E-12 6.84660E-12 210530 + 11 210540 Sc-54 4.35330E-12 4.35330E-12 210540 + 12 210550 Sc-55 3.82120E-12 3.82120E-12 210550 + 13 220520 Ti-52 1.24640E-12 6.06310E-12 220520 + 14 220530 Ti-53 3.98940E-12 1.08360E-11 220530 + 15 220540 Ti-54 1.54920E-11 1.98450E-11 220540 + 16 220550 Ti-55 2.30710E-11 2.68920E-11 220550 + 17 220560 Ti-56 3.68630E-11 3.68630E-11 220560 + 18 220570 Ti-57 1.81230E-11 1.81230E-11 220570 + 19 220580 Ti-58 1.13070E-11 1.13070E-11 220580 + 20 220590 Ti-59 2.05520E-12 2.05520E-12 220590 + 21 230540 V-54 1.34190E-12 2.11870E-11 230540 + 22 230550 V-55 1.27470E-11 3.96390E-11 230550 + 23 230560 V-56 3.30540E-11 6.99710E-11 230560 + 24 230570 V-57 1.00920E-10 1.18990E-10 230570 + 25 230580 V-58 1.11210E-10 1.22520E-10 230580 + 26 230590 V-59 1.46130E-10 1.48180E-10 230590 + 27 230600 V-60 5.19230E-11 5.19230E-11 230600 + 28 230610 V-61 2.43170E-11 2.43170E-11 230610 + 29 230620 V-62 3.41450E-12 3.41450E-12 230620 + 30 240560 Cr-56 3.66300E-12 7.41100E-11 240560 + 31 240570 Cr-57 1.96440E-11 2.36170E-10 240570 + 32 240580 Cr-58 1.34030E-10 1.58530E-10 240580 + 33 240590 Cr-59 2.86140E-10 4.34320E-10 240590 + 34 240600 Cr-60 6.51560E-10 7.04940E-10 240600 + 35 240610 Cr-61 5.63540E-10 5.86400E-10 240610 + 36 240620 Cr-62 5.95880E-10 5.99290E-10 240620 + 37 240630 Cr-63 1.65510E-10 1.65510E-10 240630 + 38 240640 Cr-64 5.10480E-11 5.10480E-11 240640 + 39 240650 Cr-65 5.41860E-12 5.41860E-12 240650 + 40 250580 Mn-58 3.19450E-12 1.61730E-10 250580 + 41 250590 Mn-59 5.14960E-11 4.85820E-10 250590 + 42 250600 Mn-60 1.77250E-11 7.43400E-10 250600 + 43 250601 Mn-60m 1.80320E-10 1.80320E-10 250601 + 44 250610 Mn-61 1.04520E-09 1.63160E-09 250610 + 45 250620 Mn-62 1.58160E-09 1.88130E-09 250620 + 46 250621 Mn-62m 2.47690E-10 5.47330E-10 250621 + 47 250630 Mn-63 3.39210E-09 3.55760E-09 250630 + 48 250640 Mn-64 2.01920E-09 2.07020E-09 250640 + 49 250650 Mn-65 1.67260E-09 1.67800E-09 250650 + 50 250660 Mn-66 3.68170E-10 3.68170E-10 250660 + 51 250670 Mn-67 8.43090E-11 8.43090E-11 250670 + 52 250680 Mn-68 6.09030E-12 6.09030E-12 250680 + 53 260600 Fe-60 6.38730E-12 9.09380E-10 260600 + 54 260610 Fe-61 6.41080E-11 1.69570E-09 260610 + 55 260620 Fe-62 7.38150E-10 3.16670E-09 260620 + 56 260630 Fe-63 2.24720E-09 5.80480E-09 260630 + 57 260640 Fe-64 8.18730E-09 1.02570E-08 260640 + 58 260650 Fe-65 1.15980E-08 1.32760E-08 260650 + 59 260660 Fe-66 1.78230E-08 1.81910E-08 260660 + 60 260670 Fe-67 8.20170E-09 8.28600E-09 260670 + 61 260680 Fe-68 4.76190E-09 4.76800E-09 260680 + 62 260690 Fe-69 8.22920E-10 8.22920E-10 260690 + 63 260700 Fe-70 1.33030E-10 1.33030E-10 260700 + 64 260710 Fe-71 4.36030E-12 4.36030E-12 260710 + 65 270620 Co-62 1.45670E-12 3.16820E-09 270620 + 66 270621 Co-62m 3.97080E-12 3.97080E-12 270621 + 67 270630 Co-63 1.22780E-10 5.92760E-09 270630 + 68 270640 Co-64 8.13500E-10 1.10710E-08 270640 + 69 270650 Co-65 7.29660E-09 2.05730E-08 270650 + 70 270660 Co-66 1.81750E-08 3.63660E-08 270660 + 71 270670 Co-67 5.22360E-08 6.05220E-08 270670 + 72 270680 Co-68 3.09560E-08 4.49220E-08 270680 + 73 270681 Co-68m 2.31060E-08 2.79320E-08 270681 + 74 270690 Co-69 6.81550E-08 6.89200E-08 270690 + 75 270700 Co-70 1.14640E-08 1.14640E-08 270700 + 76 270701 Co-70m 1.14640E-08 1.15970E-08 270701 + 77 270710 Co-71 6.18380E-09 6.18820E-09 270710 + 78 270720 Co-72 9.84090E-10 9.84090E-10 270720 + 79 270730 Co-73 9.20910E-11 9.20910E-11 270730 + 80 270740 Co-74 1.13670E-11 1.13670E-11 270740 + 81 280640 Ni-64 7.14020E-12 1.10780E-08 28064.82c + 82 280650 Ni-65 1.30810E-10 2.07030E-08 280650 + 83 280660 Ni-66 2.32080E-09 3.86870E-08 280660 + 84 280670 Ni-67 1.16110E-08 7.21330E-08 280670 + 85 280680 Ni-68 7.40730E-08 1.33650E-07 280680 + 86 280690 Ni-69 7.60550E-08 1.44290E-07 280690 + 87 280691 Ni-69m 7.60550E-08 7.60550E-08 280691 + 88 280700 Ni-70 3.30590E-07 3.53650E-07 280700 + 89 280710 Ni-71 5.31750E-07 5.37940E-07 280710 + 90 280720 Ni-72 2.00840E-07 2.01820E-07 280720 + 91 280730 Ni-73 4.02620E-08 4.03540E-08 280730 + 92 280740 Ni-74 4.19270E-08 4.19380E-08 280740 + 93 280750 Ni-75 1.89890E-09 1.89890E-09 280750 + 94 280760 Ni-76 1.70750E-10 1.70750E-10 280760 + 95 280770 Ni-77 6.66850E-12 6.66850E-12 280770 + 96 290660 Cu-66 4.52000E-12 3.86910E-08 290660 + 97 290670 Cu-67 1.78920E-10 7.23120E-08 290670 + 98 290680 Cu-68 6.02420E-10 1.35630E-07 290680 + 99 290681 Cu-68m 1.64210E-09 1.64210E-09 290681 + 100 290690 Cu-69 3.13870E-08 2.51730E-07 290690 + 101 290700 Cu-70 7.74420E-09 6.62300E-08 290700 + 102 290701 Cu-70m 9.89020E-08 1.16970E-07 290701 + 103 290702 Cu-70m 7.74420E-09 3.61400E-07 290702 + 104 290710 Cu-71 3.50710E-07 8.88650E-07 290710 + 105 290720 Cu-72 1.30060E-06 1.50240E-06 290720 + 106 290730 Cu-73 8.70080E-07 9.10430E-07 290730 + 107 290740 Cu-74 3.36290E-06 3.40490E-06 290740 + 108 290750 Cu-75 6.87790E-07 6.89660E-07 290750 + 109 290760 Cu-76 6.78300E-08 6.79150E-08 290760 + 110 290761 Cu-76m 6.78300E-08 6.79150E-08 290761 + 111 290770 Cu-77 4.57850E-08 4.57920E-08 290770 + 112 290780 Cu-78 2.28540E-09 2.28540E-09 290780 + 113 290790 Cu-79 1.69850E-10 1.69850E-10 290790 + 114 290800 Cu-80 5.51720E-12 5.51720E-12 290800 + 115 300680 Zn-68 5.09830E-12 1.35900E-07 300680 + 116 300690 Zn-69 2.57580E-11 2.51880E-07 300690 + 117 300691 Zn-69m 1.27930E-10 1.27930E-10 300691 + 118 300700 Zn-70 4.28880E-09 4.72330E-07 300700 + 119 300710 Zn-71 4.15200E-09 8.92800E-07 300710 + 120 300711 Zn-71m 2.06210E-08 2.06210E-08 300711 + 121 300720 Zn-72 3.24930E-07 1.82730E-06 300720 + 122 300730 Zn-73 7.63050E-08 1.43640E-06 300730 + 123 300731 Zn-73m 1.05540E-07 4.49700E-07 300731 + 124 300732 Zn-73m 6.88310E-07 6.88310E-07 300732 + 125 300740 Zn-74 7.56600E-06 1.09950E-05 300740 + 126 300750 Zn-75 7.78010E-06 8.44770E-06 300750 + 127 300760 Zn-76 6.40810E-06 6.54190E-06 300760 + 128 300770 Zn-77 5.78760E-06 6.21870E-06 300770 + 129 300771 Zn-77m 7.70590E-07 7.70590E-07 300771 + 130 300780 Zn-78 3.81120E-06 3.81360E-06 300780 + 131 300790 Zn-79 1.93380E-06 1.93390E-06 300790 + 132 300800 Zn-80 4.90760E-08 4.90820E-08 300800 + 133 300810 Zn-81 2.19760E-09 2.19760E-09 300810 + 134 300820 Zn-82 8.09750E-11 8.09750E-11 300820 + 135 310700 Ga-70 2.12310E-12 2.12310E-12 310700 + 136 310710 Ga-71 1.01400E-10 9.13520E-07 310710 + 137 310720 Ga-72 2.53880E-09 1.83010E-06 310720 + 138 310721 Ga-72m 2.49560E-10 6.11380E-08 310721 + 139 310730 Ga-73 4.53670E-08 1.82600E-06 310730 + 140 310740 Ga-74 5.08650E-07 9.13640E-06 310740 + 141 310741 Ga-74m 5.08650E-07 1.15040E-05 310741 + 142 310750 Ga-75 1.72890E-06 1.01770E-05 310750 + 143 310760 Ga-76 9.15310E-06 1.56950E-05 310760 + 144 310770 Ga-77 3.09150E-05 3.75190E-05 310770 + 145 310780 Ga-78 2.28710E-05 2.67100E-05 310780 + 146 310790 Ga-79 2.32120E-05 2.51210E-05 310790 + 147 310800 Ga-80 1.18530E-05 1.19020E-05 310800 + 148 310810 Ga-81 7.11900E-06 7.12100E-06 310810 + 149 310820 Ga-82 3.07150E-07 3.07230E-07 310820 + 150 310830 Ga-83 3.77450E-08 3.77450E-08 310830 + 151 310840 Ga-84 1.13960E-09 1.13960E-09 310840 + 152 320720 Ge-72 1.57600E-12 1.83010E-06 32072.82c + 153 320730 Ge-73 4.79680E-11 1.82600E-06 32073.82c + 154 320731 Ge-73m 9.65810E-12 1.79920E-06 320731 + 155 320740 Ge-74 1.04540E-08 1.20230E-05 32074.82c + 156 320750 Ge-75 1.01570E-07 1.10410E-05 320750 + 157 320751 Ge-75m 7.62830E-07 1.16990E-06 320751 + 158 320760 Ge-76 2.74580E-06 1.84410E-05 32076.82c + 159 320770 Ge-77 1.15710E-05 1.89920E-05 320770 + 160 320771 Ge-77m 1.54050E-06 3.90600E-05 320771 + 161 320780 Ge-78 4.28570E-05 6.95890E-05 320780 + 162 320790 Ge-79 1.30610E-05 4.20480E-05 320790 + 163 320791 Ge-79m 9.80990E-05 9.81360E-05 320791 + 164 320800 Ge-80 1.67960E-04 1.80710E-04 320800 + 165 320810 Ge-81 1.36520E-04 1.40170E-04 320810 + 166 320811 Ge-81m 2.74880E-05 3.04810E-05 320811 + 167 320820 Ge-82 1.20250E-04 1.20510E-04 320820 + 168 320830 Ge-83 3.88570E-05 3.88820E-05 320830 + 169 320840 Ge-84 1.04760E-05 1.04760E-05 320840 + 170 320850 Ge-85 1.10710E-06 1.10710E-06 320850 + 171 320860 Ge-86 1.78050E-08 1.78050E-08 320860 + 172 320870 Ge-87 3.22650E-10 3.22650E-10 320870 + 173 330740 As-74 1.32170E-12 1.32170E-12 330740 + 174 330750 As-75 1.78110E-11 1.10410E-05 33075.82c + 175 330751 As-75m 6.74500E-11 4.18420E-10 330751 + 176 330760 As-76 2.97100E-09 2.97100E-09 330760 + 177 330770 As-77 1.73200E-07 5.08030E-05 330770 + 178 330780 As-78 2.85780E-06 7.24470E-05 330780 + 179 330790 As-79 7.73350E-06 1.43990E-04 330790 + 180 330800 As-80 4.24360E-05 2.23150E-04 330800 + 181 330810 As-81 1.83860E-04 3.54210E-04 330810 + 182 330820 As-82 5.26170E-05 1.73120E-04 330820 + 183 330821 As-82m 1.83330E-04 1.83330E-04 330821 + 184 330830 As-83 4.56070E-04 4.96080E-04 330830 + 185 330840 As-84 1.07940E-04 1.12690E-04 330840 + 186 330841 As-84m 1.07940E-04 1.12690E-04 330841 + 187 330850 As-85 1.18760E-04 1.19710E-04 330850 + 188 330860 As-86 2.47990E-05 2.48170E-05 330860 + 189 330870 As-87 9.87800E-06 9.87830E-06 330870 + 190 330880 As-88 1.26650E-07 1.26650E-07 330880 + 191 330890 As-89 5.56330E-09 5.56330E-09 330890 + 192 340770 Se-77 6.42550E-12 5.08030E-05 34077.82c + 193 340771 Se-77m 4.82590E-11 4.82590E-11 340771 + 194 340780 Se-78 4.02280E-09 7.24510E-05 34078.82c + 195 340790 Se-79 1.01700E-07 1.44030E-04 34079.82c + 196 340791 Se-79m 1.35410E-08 1.40600E-04 340791 + 197 340800 Se-80 5.92360E-06 2.29070E-04 34080.82c + 198 340810 Se-81 5.60910E-06 4.01920E-04 340810 + 199 340811 Se-81m 4.21280E-05 5.48430E-05 340811 + 200 340820 Se-82 1.92900E-04 5.49360E-04 34082.82c + 201 340830 Se-83 4.26330E-04 6.05080E-04 340830 + 202 340831 Se-83m 8.58400E-05 4.03490E-04 340831 + 203 340840 Se-84 1.31990E-03 1.57130E-03 340840 + 204 340850 Se-85 1.32380E-03 1.42540E-03 340850 + 205 340860 Se-86 1.24020E-03 1.25840E-03 340860 + 206 340870 Se-87 6.04250E-04 6.12610E-04 340870 + 207 340880 Se-88 2.55940E-04 2.56070E-04 340880 + 208 340890 Se-89 4.61100E-05 4.61160E-05 340890 + 209 340900 Se-90 6.83200E-06 6.83200E-06 340900 + 210 340910 Se-91 4.03870E-08 4.03870E-08 340910 + 211 340920 Se-92 1.08250E-09 1.08250E-09 340920 + 212 350790 Br-79 6.08280E-12 7.87620E-08 35079.82c + 213 350791 Br-79m 2.30350E-11 2.30350E-11 350791 + 214 350800 Br-80 3.66630E-10 1.64410E-09 350800 + 215 350801 Br-80m 1.27750E-09 1.27750E-09 350801 + 216 350810 Br-81 1.07700E-07 4.02050E-04 35081.82c + 217 350820 Br-82 1.51330E-06 2.05520E-06 350820 + 218 350821 Br-82m 5.55190E-07 5.55190E-07 350821 + 219 350830 Br-83 2.82980E-05 1.03690E-03 350830 + 220 350840 Br-84 6.43850E-05 1.63570E-03 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4.36390E-04 2.93380E-03 36086.82c + 241 360870 Kr-87 1.39670E-03 4.08530E-03 360870 + 242 360880 Kr-88 3.54760E-03 5.65270E-03 360880 + 243 360890 Kr-89 5.18690E-03 6.40370E-03 360890 + 244 360900 Kr-90 5.81410E-03 6.17410E-03 360900 + 245 360910 Kr-91 4.16420E-03 4.29070E-03 360910 + 246 360920 Kr-92 2.35530E-03 2.36910E-03 360920 + 247 360930 Kr-93 6.63200E-04 6.64440E-04 360930 + 248 360940 Kr-94 1.89640E-04 1.89640E-04 360940 + 249 360950 Kr-95 2.37700E-05 2.37700E-05 360950 + 250 360960 Kr-96 3.71690E-06 3.71690E-06 360960 + 251 360970 Kr-97 1.81620E-09 1.81620E-09 360970 + 252 370840 Rb-84 1.05100E-10 3.25590E-10 370840 + 253 370841 Rb-84m 2.20490E-10 2.20490E-10 370841 + 254 370850 Rb-85 2.51550E-08 2.04040E-03 37085.82c + 255 370860 Rb-86 3.47750E-07 1.07730E-06 37086.82c + 256 370861 Rb-86m 7.29550E-07 7.29550E-07 370861 + 257 370870 Rb-87 5.37040E-05 4.13900E-03 37087.82c + 258 370880 Rb-88 1.87120E-04 5.83980E-03 370880 + 259 370890 Rb-89 9.42060E-04 7.34580E-03 370890 + 260 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1.11590E-02 380910 + 280 380920 Sr-92 5.66400E-03 1.45970E-02 380920 + 281 380930 Sr-93 9.79580E-03 1.72830E-02 380930 + 282 380940 Sr-94 1.64090E-02 1.99590E-02 380940 + 283 380950 Sr-95 1.42030E-02 1.57850E-02 380950 + 284 380960 Sr-96 1.16500E-02 1.20300E-02 380960 + 285 380970 Sr-97 4.68990E-03 4.75470E-03 380970 + 286 380980 Sr-98 1.81790E-03 1.82560E-03 380980 + 287 380990 Sr-99 3.22120E-04 3.22140E-04 380990 + 288 381000 Sr-100 6.27660E-05 6.27660E-05 381000 + 289 381010 Sr-101 3.72120E-06 3.72120E-06 381010 + 290 381020 Sr-102 3.96820E-09 3.96820E-09 381020 + 291 390890 Y-89 4.23810E-10 7.41060E-03 39089.82c + 292 390891 Y-89m 2.10490E-09 7.16410E-07 390891 + 293 390900 Y-90 1.09520E-06 9.09260E-03 39090.82c + 294 390901 Y-90m 1.83150E-06 1.83150E-06 390901 + 295 390910 Y-91 3.91040E-06 1.11820E-02 39091.82c + 296 390911 Y-91m 1.94220E-05 6.58480E-03 390911 + 297 390920 Y-92 1.48400E-04 1.47450E-02 390920 + 298 390930 Y-93 1.10740E-04 1.82260E-02 390930 + 299 390931 Y-93m 8.31720E-04 5.15670E-03 390931 + 300 390940 Y-94 2.68360E-03 2.26420E-02 390940 + 301 390950 Y-95 8.17550E-03 2.39610E-02 390950 + 302 390960 Y-96 3.91430E-03 1.59460E-02 390960 + 303 390961 Y-96m 8.21170E-03 8.21290E-03 390961 + 304 390970 Y-97 2.83660E-03 6.98030E-03 390970 + 305 390971 Y-97m 1.04850E-02 1.40750E-02 390971 + 306 390972 Y-97m 3.60330E-03 3.60330E-03 390972 + 307 390980 Y-98 2.12540E-03 3.95100E-03 390980 + 308 390981 Y-98m 1.03040E-02 1.03040E-02 390981 + 309 390990 Y-99 8.05640E-03 8.37900E-03 390990 + 310 391000 Y-100 1.47090E-03 1.53330E-03 391000 + 311 391001 Y-100m 1.47090E-03 1.47100E-03 391001 + 312 391010 Y-101 9.51600E-04 9.55230E-04 391010 + 313 391020 Y-102 7.29800E-05 7.29820E-05 391020 + 314 391021 Y-102m 7.29800E-05 7.29820E-05 391021 + 315 391030 Y-103 2.09040E-05 2.09040E-05 391030 + 316 391040 Y-104 1.73310E-08 1.73310E-08 391040 + 317 400910 Zr-91 2.94790E-10 1.11820E-02 40091.82c + 318 400920 Zr-92 9.78150E-07 1.47460E-02 40092.82c + 319 400930 Zr-93 3.17280E-05 1.82570E-02 40093.82c + 320 400940 Zr-94 2.75990E-04 2.29180E-02 40094.82c + 321 400950 Zr-95 1.16670E-03 2.51280E-02 40095.82c + 322 400960 Zr-96 5.71280E-03 2.98830E-02 40096.82c + 323 400970 Zr-97 1.18730E-02 3.39040E-02 400970 + 324 400980 Zr-98 2.58240E-02 3.98560E-02 400980 + 325 400990 Zr-99 2.72280E-02 3.54790E-02 400990 + 326 401000 Zr-100 2.79430E-02 3.09330E-02 401000 + 327 401010 Zr-101 1.49250E-02 1.58870E-02 401010 + 328 401020 Zr-102 8.07450E-03 8.21500E-03 401020 + 329 401030 Zr-103 2.19800E-03 2.21720E-03 401030 + 330 401040 Zr-104 5.95940E-04 5.95960E-04 401040 + 331 401050 Zr-105 8.89220E-05 8.89220E-05 401050 + 332 401060 Zr-106 1.22690E-05 1.22690E-05 401060 + 333 401070 Zr-107 1.65110E-09 1.65110E-09 401070 + 334 410940 Nb-94 4.25510E-09 6.78680E-09 41094.82c + 335 410941 Nb-94m 2.54440E-09 2.54440E-09 410941 + 336 410950 Nb-95 7.60570E-06 2.51210E-02 41095.82c + 337 410951 Nb-95m 1.53140E-06 2.73000E-04 410951 + 338 410960 Nb-96 7.43540E-05 7.43540E-05 410960 + 339 410970 Nb-97 4.15950E-04 3.44040E-02 410970 + 340 410971 Nb-97m 8.37500E-05 3.23090E-02 410971 + 341 410980 Nb-98 4.27760E-04 4.02840E-02 410980 + 342 410981 Nb-98m 1.49040E-03 1.49040E-03 410981 + 343 410990 Nb-99 6.42950E-03 2.91390E-02 410990 + 344 410991 Nb-99m 1.29450E-03 1.43510E-02 410991 + 345 411000 Nb-100 2.48840E-03 3.34220E-02 411000 + 346 411001 Nb-100m 1.20640E-02 1.20640E-02 411001 + 347 411010 Nb-101 2.58320E-02 4.17190E-02 411010 + 348 411020 Nb-102 1.14540E-02 1.96680E-02 411020 + 349 411021 Nb-102m 1.14540E-02 1.14540E-02 411021 + 350 411030 Nb-103 2.05540E-02 2.27710E-02 411030 + 351 411040 Nb-104 5.33350E-03 5.93070E-03 411040 + 352 411041 Nb-104m 5.33350E-03 5.33350E-03 411041 + 353 411050 Nb-105 5.29440E-03 5.38230E-03 411050 + 354 411060 Nb-106 1.30410E-03 1.31620E-03 411060 + 355 411070 Nb-107 3.67080E-04 3.67080E-04 411070 + 356 411080 Nb-108 4.25300E-05 4.25300E-05 411080 + 357 411090 Nb-109 3.29600E-06 3.29600E-06 411090 + 358 420960 Mo-96 9.29160E-07 7.52830E-05 42096.82c + 359 420970 Mo-97 7.44130E-06 3.44110E-02 42097.82c + 360 420980 Mo-98 1.02100E-04 4.18760E-02 42098.82c + 361 420990 Mo-99 5.25410E-04 4.37280E-02 42099.82c + 362 421000 Mo-100 2.89610E-03 4.83810E-02 42100.82c + 363 421010 Mo-101 8.14880E-03 4.98680E-02 421010 + 364 421020 Mo-102 2.23830E-02 5.35050E-02 421020 + 365 421030 Mo-103 3.06020E-02 5.33800E-02 421030 + 366 421040 Mo-104 4.09770E-02 5.23260E-02 421040 + 367 421050 Mo-105 2.74580E-02 3.28080E-02 421050 + 368 421060 Mo-106 1.92430E-02 2.05220E-02 421060 + 369 421070 Mo-107 8.18570E-03 8.53340E-03 421070 + 370 421080 Mo-108 3.33380E-03 3.37410E-03 421080 + 371 421090 Mo-109 7.23080E-04 7.25960E-04 421090 + 372 421100 Mo-110 1.19840E-04 1.19840E-04 421100 + 373 421110 Mo-111 1.18590E-05 1.18590E-05 421110 + 374 421120 Mo-112 1.03070E-09 1.03070E-09 421120 + 375 430990 Tc-99 7.69900E-07 4.37280E-02 43099.82c + 376 430991 Tc-99m 1.55020E-07 3.85070E-02 430991 + 377 431000 Tc-100 1.59280E-05 1.59280E-05 431000 + 378 431010 Tc-101 1.51950E-04 5.00200E-02 431010 + 379 431020 Tc-102 3.91300E-04 5.38960E-02 431020 + 380 431021 Tc-102m 3.91300E-04 3.91300E-04 431021 + 381 431030 Tc-103 4.18780E-03 5.75670E-02 431030 + 382 431040 Tc-104 1.03910E-02 6.27170E-02 431040 + 383 431050 Tc-105 2.53520E-02 5.81600E-02 431050 + 384 431060 Tc-106 2.91690E-02 4.96910E-02 431060 + 385 431070 Tc-107 3.10550E-02 3.95880E-02 431070 + 386 431080 Tc-108 1.80140E-02 2.13920E-02 431080 + 387 431090 Tc-109 1.20080E-02 1.27300E-02 431090 + 388 431100 Tc-110 4.88590E-03 5.00590E-03 431100 + 389 431110 Tc-111 1.62910E-03 1.64080E-03 431110 + 390 431120 Tc-112 3.08180E-04 3.08180E-04 431120 + 391 431130 Tc-113 3.82780E-05 3.82780E-05 431130 + 392 431140 Tc-114 1.98020E-09 1.98020E-09 431140 + 393 441010 Ru-101 9.30330E-07 5.00210E-02 44101.82c + 394 441020 Ru-102 2.14190E-05 5.43090E-02 44102.82c + 395 441030 Ru-103 3.23730E-05 5.76900E-02 44103.82c + 396 441031 Ru-103m 9.05770E-05 9.05770E-05 441031 + 397 441040 Ru-104 9.53540E-04 6.36710E-02 44104.82c + 398 441050 Ru-105 3.34130E-03 6.15010E-02 44105.82c + 399 441060 Ru-106 1.17420E-02 6.14330E-02 44106.82c + 400 441070 Ru-107 2.09200E-02 6.05080E-02 441070 + 401 441080 Ru-108 3.42050E-02 5.56070E-02 441080 + 402 441090 Ru-109 2.93920E-02 4.21140E-02 441090 + 403 441100 Ru-110 2.43080E-02 2.93120E-02 441100 + 404 441110 Ru-111 1.15250E-02 1.31700E-02 441110 + 405 441120 Ru-112 5.75530E-03 6.06160E-03 441120 + 406 441130 Ru-113 7.21200E-04 1.11730E-03 441130 + 407 441131 Ru-113m 7.21200E-04 7.21200E-04 441131 + 408 441140 Ru-114 3.23060E-04 3.23060E-04 441140 + 409 441150 Ru-115 2.21360E-05 2.21360E-05 441150 + 410 441160 Ru-116 5.54130E-06 5.54130E-06 441160 + 411 441170 Ru-117 3.30410E-11 3.30410E-11 441170 + 412 451040 Rh-104 8.78620E-07 3.93600E-06 451040 + 413 451041 Rh-104m 3.06140E-06 3.06140E-06 451041 + 414 451050 Rh-105 2.56180E-05 6.15300E-02 45105.82c + 415 451051 Rh-105m 3.41090E-06 1.74620E-02 451051 + 416 451060 Rh-106 5.57550E-05 6.14890E-02 451060 + 417 451061 Rh-106m 1.51970E-04 1.51970E-04 451061 + 418 451070 Rh-107 1.12980E-03 6.16380E-02 451070 + 419 451080 Rh-108 7.47900E-04 5.63550E-02 451080 + 420 451081 Rh-108m 2.60590E-03 2.60590E-03 451081 + 421 451090 Rh-109 9.48990E-03 5.16040E-02 451090 + 422 451100 Rh-110 1.42950E-02 4.36070E-02 451100 + 423 451101 Rh-110m 3.36540E-04 3.36540E-04 451101 + 424 451110 Rh-111 1.95460E-02 3.27170E-02 451110 + 425 451120 Rh-112 6.66700E-03 1.27290E-02 451120 + 426 451121 Rh-112m 6.66700E-03 6.66700E-03 451121 + 427 451130 Rh-113 9.00350E-03 1.04810E-02 451130 + 428 451140 Rh-114 1.73650E-03 2.05970E-03 451140 + 429 451141 Rh-114m 1.73650E-03 1.73650E-03 451141 + 430 451150 Rh-115 1.21300E-03 1.23510E-03 451150 + 431 451160 Rh-116 5.88900E-05 6.43710E-05 451160 + 432 451161 Rh-116m 1.60520E-04 1.60520E-04 451161 + 433 451170 Rh-117 6.78130E-05 6.78130E-05 451170 + 434 451180 Rh-118 1.86770E-05 1.86770E-05 451180 + 435 451190 Rh-119 4.43500E-06 4.43500E-06 451190 + 436 461060 Pd-106 1.02260E-06 6.16420E-02 46106.82c + 437 461070 Pd-107 6.85440E-06 6.16600E-02 46107.82c + 438 461071 Pd-107m 1.50660E-05 1.50660E-05 461071 + 439 461080 Pd-108 1.11620E-04 5.90730E-02 46108.82c + 440 461090 Pd-109 1.64890E-04 5.21310E-02 461090 + 441 461091 Pd-109m 3.62410E-04 2.61640E-02 461091 + 442 461100 Pd-110 2.15100E-03 4.60950E-02 46110.82c + 443 461110 Pd-111 1.29590E-03 3.60560E-02 461110 + 444 461111 Pd-111m 2.84850E-03 2.97930E-03 461111 + 445 461120 Pd-112 8.03840E-03 2.74340E-02 461120 + 446 461130 Pd-113 1.91340E-03 1.77480E-02 461130 + 447 461131 Pd-113m 5.35350E-03 5.35350E-03 461131 + 448 461140 Pd-114 6.45620E-03 1.02520E-02 461140 + 449 461150 Pd-115 8.97260E-04 2.12520E-03 461150 + 450 461151 Pd-115m 1.97210E-03 2.15150E-03 461151 + 451 461160 Pd-116 1.38800E-03 1.61290E-03 461160 + 452 461170 Pd-117 1.24990E-04 4.68070E-04 461170 + 453 461171 Pd-117m 2.74720E-04 2.74720E-04 461171 + 454 461180 Pd-118 1.17260E-04 1.35390E-04 461180 + 455 461190 Pd-119 2.22330E-05 2.66680E-05 461190 + 456 461200 Pd-120 7.46730E-06 7.46730E-06 461200 + 457 461210 Pd-121 1.69860E-06 1.69860E-06 461210 + 458 461220 Pd-122 3.49650E-12 3.49650E-12 461220 + 459 461230 Pd-123 1.17810E-07 1.17810E-07 461230 + 460 461240 Pd-124 2.27020E-08 2.27020E-08 461240 + 461 471090 Ag-109 2.58270E-07 5.21330E-02 47109.82c + 462 471091 Ag-109m 1.93970E-06 5.21080E-02 471091 + 463 471100 Ag-110 4.70480E-06 4.87920E-06 471100 + 464 471101 Ag-110m 1.28240E-05 1.28240E-05 47510.82c + 465 471110 Ag-111 1.32280E-05 3.67910E-02 47111.82c + 466 471111 Ag-111m 9.93520E-05 3.64730E-02 471111 + 467 471120 Ag-112 3.32540E-04 2.77660E-02 471120 + 468 471130 Ag-113 1.08590E-04 1.22610E-02 471130 + 469 471131 Ag-113m 8.15550E-04 1.78110E-02 471131 + 470 471140 Ag-114 2.27480E-04 1.15830E-02 471140 + 471 471141 Ag-114m 1.10280E-03 1.10280E-03 471141 + 472 471150 Ag-115 2.02190E-04 2.60870E-03 471150 + 473 471151 Ag-115m 1.51860E-03 4.07180E-03 471151 + 474 471160 Ag-116 2.68780E-04 1.92560E-03 471160 + 475 471161 Ag-116m 7.32620E-04 7.32620E-04 471161 + 476 471170 Ag-117 7.76150E-05 3.60670E-04 471170 + 477 471171 Ag-117m 5.82940E-04 8.16970E-04 471171 + 478 471180 Ag-118 3.19800E-05 2.19520E-04 471180 + 479 471181 Ag-118m 1.55040E-04 1.74400E-04 471181 + 480 471190 Ag-119 8.28050E-06 2.16150E-05 471190 + 481 471191 Ag-119m 6.21910E-05 7.55260E-05 471191 + 482 471200 Ag-120 5.04050E-06 1.32790E-05 471200 + 483 471201 Ag-120m 8.42950E-06 1.21630E-05 471201 + 484 471210 Ag-121 1.19370E-05 1.36310E-05 471210 + 485 471220 Ag-122 7.82380E-06 7.82380E-06 471220 + 486 471221 Ag-122m 8.43520E-06 8.43520E-06 471221 + 487 471230 Ag-123 2.04060E-05 2.05240E-05 471230 + 488 471240 Ag-124 5.90380E-06 9.10910E-06 471240 + 489 471241 Ag-124m 6.36520E-06 6.36520E-06 471241 + 490 471250 Ag-125 5.91660E-06 5.91660E-06 471250 + 491 471260 Ag-126 4.27180E-07 4.27180E-07 471260 + 492 471270 Ag-127 3.96970E-08 3.96970E-08 471270 + 493 471280 Ag-128 1.22130E-09 1.22130E-09 471280 + 494 481110 Cd-111 2.47760E-07 3.69750E-02 48111.82c + 495 481111 Cd-111m 9.38250E-07 9.38250E-07 481111 + 496 481120 Cd-112 2.49510E-06 2.77690E-02 48112.82c + 497 481130 Cd-113 4.94240E-06 1.84660E-02 48113.82c + 498 481131 Cd-113m 1.87170E-05 2.30690E-04 481131 + 499 481140 Cd-114 7.04800E-05 1.16530E-02 48114.82c + 500 481150 Cd-115 2.05590E-05 5.60190E-03 481150 + 501 481151 Cd-115m 7.78570E-05 3.21820E-04 48515.82c + 502 481160 Cd-116 2.14510E-04 2.82880E-03 48116.82c + 503 481170 Cd-117 2.92020E-05 9.06540E-04 481170 + 504 481171 Cd-117m 1.10590E-04 3.61870E-04 481171 + 505 481180 Cd-118 1.32220E-04 4.54630E-04 481180 + 506 481190 Cd-119 1.50360E-05 1.01370E-04 481190 + 507 481191 Cd-119m 4.20700E-05 5.28770E-05 481191 + 508 481200 Cd-120 3.86250E-05 5.95660E-05 481200 + 509 481210 Cd-121 8.05910E-06 2.02660E-05 481210 + 510 481211 Cd-121m 2.25490E-05 2.39730E-05 481211 + 511 481220 Cd-122 5.03930E-05 6.66520E-05 481220 + 512 481230 Cd-123 2.83680E-05 4.51640E-05 481230 + 513 481231 Cd-123m 7.93720E-05 8.31090E-05 481231 + 514 481240 Cd-124 3.07920E-04 3.20200E-04 481240 + 515 481250 Cd-125 7.33660E-05 7.63240E-05 481250 + 516 481251 Cd-125m 2.05270E-04 2.08230E-04 481251 + 517 481260 Cd-126 2.19780E-04 2.20210E-04 481260 + 518 481270 Cd-127 8.32750E-05 8.33150E-05 481270 + 519 481280 Cd-128 2.60090E-05 2.60100E-05 481280 + 520 481290 Cd-129 7.46770E-07 7.46770E-07 481290 + 521 481291 Cd-129m 2.08940E-06 2.08940E-06 481291 + 522 481300 Cd-130 2.77010E-08 2.77010E-08 481300 + 523 491140 In-114 1.89250E-09 8.25580E-09 491140 + 524 491141 In-114m 3.05600E-09 6.59410E-09 491141 + 525 491142 In-114m 3.53810E-09 3.53810E-09 491142 + 526 491150 In-115 1.15170E-06 5.64500E-03 49115.82c + 527 491151 In-115m 2.31890E-07 5.60220E-03 491151 + 528 491160 In-116 6.16930E-07 6.16930E-07 491160 + 529 491161 In-116m 9.96220E-07 2.14960E-06 491161 + 530 491162 In-116m 1.15330E-06 1.15330E-06 491162 + 531 491170 In-117 7.02670E-06 8.33710E-04 491170 + 532 491171 In-117m 1.41480E-06 8.37700E-04 491171 + 533 491180 In-118 1.91080E-06 4.56540E-04 491180 + 534 491181 In-118m 3.08560E-06 6.60780E-06 491181 + 535 491182 In-118m 3.57220E-06 3.57220E-06 491182 + 536 491190 In-119 1.46220E-05 8.25350E-05 491190 + 537 491191 In-119m 2.94410E-06 9.45730E-05 491191 + 538 491200 In-120 4.96680E-07 6.00630E-05 491200 + 539 491201 In-120m 4.96680E-07 4.96680E-07 491201 + 540 491202 In-120m 4.96680E-07 4.96680E-07 491202 + 541 491210 In-121 1.82600E-05 4.92640E-05 491210 + 542 491211 In-121m 3.67660E-06 1.71170E-05 491211 + 543 491220 In-122 6.68960E-06 7.33420E-05 491220 + 544 491221 In-122m 5.59370E-06 5.59370E-06 491221 + 545 491222 In-122m 5.59370E-06 5.59370E-06 491222 + 546 491230 In-123 5.57780E-05 1.51860E-04 491230 + 547 491231 In-123m 1.12310E-05 4.34200E-05 491231 + 548 491240 In-124 9.29340E-05 4.13140E-04 491240 + 549 491241 In-124m 1.00200E-04 1.00200E-04 491241 + 550 491250 In-125 7.34910E-04 9.79670E-04 491250 + 551 491251 In-125m 1.47970E-04 1.87760E-04 491251 + 552 491260 In-126 6.09920E-04 8.30130E-04 491260 + 553 491261 In-126m 6.57580E-04 6.57580E-04 491261 + 554 491270 In-127 1.46970E-03 1.46970E-03 491270 + 555 491271 In-127m 2.95920E-04 3.79230E-04 491271 + 556 491280 In-128 4.22050E-04 6.13320E-04 491280 + 557 491281 In-128m 1.65260E-04 1.91270E-04 491281 + 558 491282 In-128m 6.33200E-04 6.33200E-04 491282 + 559 491290 In-129 5.72590E-04 5.74680E-04 491290 + 560 491291 In-129m 1.15290E-04 1.16040E-04 491291 + 561 491300 In-130 5.16330E-05 5.16600E-05 491300 + 562 491301 In-130m 7.51810E-05 7.51810E-05 491301 + 563 491302 In-130m 1.04730E-04 1.04730E-04 491302 + 564 491310 In-131 1.46560E-05 1.48060E-05 491310 + 565 491311 In-131m 1.46560E-05 1.46560E-05 491311 + 566 491312 In-131m 1.46560E-05 1.46560E-05 491312 + 567 491320 In-132 2.21760E-07 2.21760E-07 491320 + 568 491330 In-133 6.78890E-09 8.15580E-09 491330 + 569 491331 In-133m 1.36690E-09 1.36690E-09 491331 + 570 501160 Sn-116 4.08480E-10 2.76690E-06 50116.82c + 571 501170 Sn-117 1.54610E-09 1.27690E-03 50117.82c + 572 501171 Sn-117m 5.85520E-09 2.84640E-06 501171 + 573 501180 Sn-118 1.06240E-07 4.63310E-04 50118.82c + 574 501190 Sn-119 9.07210E-08 1.72250E-04 50119.82c + 575 501191 Sn-119m 3.43560E-07 7.49060E-05 501191 + 576 501200 Sn-120 1.84730E-06 6.29060E-05 50120.82c + 577 501210 Sn-121 8.93350E-07 6.77590E-05 501210 + 578 501211 Sn-121m 2.49960E-06 8.08040E-06 501211 + 579 501220 Sn-122 1.07540E-05 9.53020E-05 50122.82c + 580 501230 Sn-123 8.11700E-06 1.96950E-05 50123.82c + 581 501231 Sn-123m 2.90100E-06 1.86610E-04 501231 + 582 501240 Sn-124 9.06830E-05 6.04020E-04 50124.82c + 583 501250 Sn-125 2.46820E-04 4.12300E-04 50125.82c + 584 501251 Sn-125m 8.82130E-05 1.09020E-03 501251 + 585 501260 Sn-126 1.82420E-03 3.31450E-03 50126.82c + 586 501270 Sn-127 2.97460E-03 3.54740E-03 501270 + 587 501271 Sn-127m 1.06310E-03 2.33660E-03 501271 + 588 501280 Sn-128 2.35810E-03 1.00320E-02 501280 + 589 501281 Sn-128m 6.42760E-03 7.06080E-03 501281 + 590 501290 Sn-129 1.94570E-03 2.57540E-03 501290 + 591 501291 Sn-129m 5.44410E-03 5.50520E-03 501291 + 592 501300 Sn-130 1.80260E-03 1.94420E-03 501300 + 593 501301 Sn-130m 4.91350E-03 5.00380E-03 501301 + 594 501310 Sn-131 8.38720E-04 8.67110E-04 501310 + 595 501311 Sn-131m 2.34670E-03 2.36200E-03 501311 + 596 501320 Sn-132 1.04160E-03 1.04180E-03 501320 + 597 501330 Sn-133 8.07870E-05 8.07880E-05 501330 + 598 501340 Sn-134 9.11600E-06 9.11600E-06 501340 + 599 501350 Sn-135 9.88690E-07 9.88690E-07 501350 + 600 511180 Sb-118 4.18320E-12 4.18320E-12 511180 + 601 511181 Sb-118m 6.99580E-12 6.99580E-12 511181 + 602 511190 Sb-119 1.56530E-10 2.19390E-10 511190 + 603 511191 Sb-119m 6.28550E-11 6.28550E-11 511191 + 604 511200 Sb-120 7.76350E-10 7.76350E-10 511200 + 605 511201 Sb-120m 1.29830E-09 1.29830E-09 511201 + 606 511210 Sb-121 6.68430E-08 6.96360E-05 51121.82c + 607 511220 Sb-122 3.15880E-07 7.39080E-07 511220 + 608 511221 Sb-122m 4.23200E-07 4.23200E-07 511221 + 609 511230 Sb-123 3.67760E-06 2.09980E-04 51123.82c + 610 511240 Sb-124 1.31320E-06 3.37970E-06 51124.82c + 611 511241 Sb-124m 1.05930E-06 2.75530E-06 511241 + 612 511242 Sb-124m 1.69600E-06 1.69600E-06 511242 + 613 511250 Sb-125 1.17950E-05 1.51430E-03 51125.82c + 614 511260 Sb-126 4.72970E-05 5.65600E-05 51126.82c + 615 511261 Sb-126m 2.95420E-05 6.61640E-05 511261 + 616 511262 Sb-126m 3.66220E-05 3.66220E-05 511262 + 617 511270 Sb-127 6.67790E-04 6.55180E-03 511270 + 618 511280 Sb-128 1.09340E-03 1.11810E-02 511280 + 619 511281 Sb-128m 1.52930E-03 1.52930E-03 511281 + 620 511290 Sb-129 5.90560E-03 1.23020E-02 511290 + 621 511291 Sb-129m 4.37040E-03 7.12300E-03 511291 + 622 511300 Sb-130 7.65850E-03 1.21050E-02 511300 + 623 511301 Sb-130m 7.65850E-03 1.01600E-02 511301 + 624 511310 Sb-131 2.24460E-02 2.56750E-02 511310 + 625 511320 Sb-132 7.14020E-03 8.18210E-03 511320 + 626 511321 Sb-132m 6.32180E-03 6.32180E-03 511321 + 627 511330 Sb-133 8.62040E-03 8.70270E-03 511330 + 628 511340 Sb-134 4.89830E-04 4.97500E-04 511340 + 629 511341 Sb-134m 1.33520E-03 1.33530E-03 511341 + 630 511350 Sb-135 3.26400E-04 3.27180E-04 511350 + 631 511360 Sb-136 2.83950E-05 2.83950E-05 511360 + 632 511370 Sb-137 7.91370E-07 7.91370E-07 511370 + 633 511380 Sb-138 5.35910E-09 5.35910E-09 511380 + 634 521210 Te-121 2.30020E-12 1.00270E-11 521210 + 635 521211 Te-121m 8.71080E-12 8.71080E-12 521211 + 636 521220 Te-122 9.61480E-10 7.20820E-07 52122.82c + 637 521250 Te-125 6.87680E-11 1.51430E-03 52125.82c + 638 521251 Te-125m 2.60420E-10 3.38840E-04 521251 + 639 521260 Te-126 4.58140E-08 1.13510E-04 52126.82c + 640 521270 Te-127 2.81310E-06 6.53640E-03 521270 + 641 521271 Te-127m 7.87090E-06 1.08760E-03 52527.82c + 642 521280 Te-128 1.41980E-04 1.27970E-02 52128.82c + 643 521290 Te-129 2.41940E-04 1.60820E-02 521290 + 644 521291 Te-129m 6.76930E-04 8.63110E-03 52529.82c + 645 521300 Te-130 5.90940E-03 2.81740E-02 52130.82c + 646 521310 Te-131 3.93580E-03 3.03000E-02 521310 + 647 521311 Te-131m 1.10120E-02 1.30680E-02 521311 + 648 521320 Te-132 3.57640E-02 5.02680E-02 52132.82c + 649 521330 Te-133 1.01850E-02 2.26340E-02 521330 + 650 521331 Te-133m 2.84960E-02 3.00020E-02 521331 + 651 521340 Te-134 3.34130E-02 3.52960E-02 521340 + 652 521350 Te-135 9.76650E-03 1.00470E-02 521350 + 653 521360 Te-136 3.78900E-03 3.81310E-03 521360 + 654 521370 Te-137 6.24920E-04 6.25320E-04 521370 + 655 521380 Te-138 1.09360E-04 1.09360E-04 521380 + 656 521390 Te-139 5.53040E-06 5.53040E-06 521390 + 657 521400 Te-140 5.00720E-08 5.00720E-08 521400 + 658 531270 I-127 2.20530E-10 6.56250E-03 53127.82c + 659 531280 I-128 1.74040E-08 1.74040E-08 531280 + 660 531290 I-129 1.21390E-06 1.92770E-02 53129.82c + 661 531300 I-130 4.66640E-05 6.10440E-05 53130.82c + 662 531301 I-130m 1.71190E-05 1.71190E-05 531301 + 663 531310 I-131 6.44160E-04 4.12670E-02 53131.82c + 664 531320 I-132 1.25550E-03 5.24790E-02 531320 + 665 531321 I-132m 1.11160E-03 1.11160E-03 531321 + 666 531330 I-133 7.29410E-03 6.00770E-02 531330 + 667 531331 I-133m 5.39790E-03 5.39790E-03 531331 + 668 531340 I-134 1.57690E-02 6.47050E-02 531340 + 669 531341 I-134m 1.39610E-02 1.39610E-02 531341 + 670 531350 I-135 4.86310E-02 5.86780E-02 53135.82c + 671 531360 I-136 6.26500E-03 1.00870E-02 531360 + 672 531361 I-136m 1.70770E-02 1.70860E-02 531361 + 673 531370 I-137 1.37220E-02 1.43350E-02 531370 + 674 531380 I-138 4.18010E-03 4.28260E-03 531380 + 675 531390 I-139 2.21980E-03 2.22530E-03 531390 + 676 531400 I-140 3.29490E-04 3.29540E-04 531400 + 677 531410 I-141 6.08170E-05 6.08170E-05 531410 + 678 531420 I-142 5.58200E-06 5.58200E-06 531420 + 679 531430 I-143 5.27440E-09 5.27440E-09 531430 + 680 541300 Xe-130 8.20760E-09 6.37910E-05 54130.82c + 681 541310 Xe-131 3.52320E-07 4.12690E-02 54131.82c + 682 541311 Xe-131m 9.85780E-07 4.49230E-04 541311 + 683 541320 Xe-132 1.88910E-05 5.26790E-02 54132.82c + 684 541321 Xe-132m 2.53090E-05 2.53090E-05 541321 + 685 541330 Xe-133 1.06350E-04 6.04810E-02 54133.82c + 686 541331 Xe-133m 2.97580E-04 2.00760E-03 541331 + 687 541340 Xe-134 8.17710E-04 6.80730E-02 54134.82c + 688 541341 Xe-134m 2.22890E-03 2.55000E-03 541341 + 689 541350 Xe-135 3.09900E-03 7.03380E-02 54135.82c + 690 541351 Xe-135m 8.67100E-03 1.83580E-02 541351 + 691 541360 Xe-136 4.06960E-02 6.88020E-02 54136.82c + 692 541370 Xe-137 3.56570E-02 4.92880E-02 541370 + 693 541380 Xe-138 3.62020E-02 4.04760E-02 541380 + 694 541390 Xe-139 1.85770E-02 2.06150E-02 541390 + 695 541400 Xe-140 1.31480E-02 1.34600E-02 541400 + 696 541410 Xe-141 3.84620E-03 3.89560E-03 541410 + 697 541420 Xe-142 1.18390E-03 1.18810E-03 541420 + 698 541430 Xe-143 1.25510E-04 1.25510E-04 541430 + 699 541440 Xe-144 1.69090E-05 1.69090E-05 541440 + 700 541450 Xe-145 2.12120E-08 2.12120E-08 541450 + 701 551320 Cs-132 1.21850E-09 1.21850E-09 551320 + 702 551330 Cs-133 1.14180E-07 6.04810E-02 55133.82c + 703 551340 Cs-134 1.81390E-06 3.41980E-06 55134.82c + 704 551341 Cs-134m 1.60590E-06 1.60590E-06 551341 + 705 551350 Cs-135 7.22910E-05 7.05740E-02 55135.82c + 706 551351 Cs-135m 5.34990E-05 5.34990E-05 551351 + 707 551360 Cs-136 5.22980E-04 7.09940E-04 55136.82c + 708 551361 Cs-136m 3.73920E-04 3.73920E-04 551361 + 709 551370 Cs-137 6.11600E-03 5.54040E-02 55137.82c + 710 551380 Cs-138 5.06330E-03 5.23980E-02 551380 + 711 551381 Cs-138m 8.46770E-03 8.46770E-03 551381 + 712 551390 Cs-139 2.35370E-02 4.41520E-02 551390 + 713 551400 Cs-140 2.17820E-02 3.52430E-02 551400 + 714 551410 Cs-141 2.58980E-02 2.97960E-02 551410 + 715 551420 Cs-142 1.20950E-02 1.32800E-02 551420 + 716 551430 Cs-143 6.02810E-03 6.15290E-03 551430 + 717 551440 Cs-144 6.66950E-04 1.01680E-03 551440 + 718 551441 Cs-144m 6.66950E-04 6.66950E-04 551441 + 719 551450 Cs-145 3.54530E-04 3.54550E-04 551450 + 720 551460 Cs-146 4.16310E-05 4.16310E-05 551460 + 721 551470 Cs-147 5.53180E-06 5.53180E-06 551470 + 722 551480 Cs-148 2.22870E-09 2.22870E-09 551480 + 723 561350 Ba-135 5.20680E-07 1.97750E-06 56135.82c + 724 561351 Ba-135m 1.45680E-06 1.45680E-06 561351 + 725 561360 Ba-136 9.53570E-07 9.00450E-04 56136.82c + 726 561361 Ba-136m 2.59920E-06 2.59920E-06 561361 + 727 561370 Ba-137 2.48200E-05 5.54980E-02 56137.82c + 728 561371 Ba-137m 6.94450E-05 5.23700E-02 561371 + 729 561380 Ba-138 1.40770E-03 5.54140E-02 56138.82c + 730 561390 Ba-139 4.39930E-03 4.85510E-02 561390 + 731 561400 Ba-140 1.32300E-02 4.84730E-02 56140.82c + 732 561410 Ba-141 1.91480E-02 4.89440E-02 561410 + 733 561420 Ba-142 3.17280E-02 4.51090E-02 561420 + 734 561430 Ba-143 2.47570E-02 3.08420E-02 561430 + 735 561440 Ba-144 1.90000E-02 2.03690E-02 561440 + 736 561450 Ba-145 7.47140E-03 7.78120E-03 561450 + 737 561460 Ba-146 3.70500E-03 3.74230E-03 561460 + 738 561470 Ba-147 7.88200E-04 7.92160E-04 561470 + 739 561480 Ba-148 2.02760E-04 2.02760E-04 561480 + 740 561490 Ba-149 1.26250E-05 1.26250E-05 561490 + 741 561500 Ba-150 1.97370E-06 1.97370E-06 561500 + 742 571370 La-137 1.85070E-09 1.85070E-09 571370 + 743 571380 La-138 1.74000E-06 1.74000E-06 57138.82c + 744 571390 La-139 4.79540E-05 4.85990E-02 57139.82c + 745 571400 La-140 2.09840E-04 4.86830E-02 57140.82c + 746 571410 La-141 1.18010E-03 5.01240E-02 571410 + 747 571420 La-142 2.56110E-03 4.76700E-02 571420 + 748 571430 La-143 7.81670E-03 3.86580E-02 571430 + 749 571440 La-144 1.13400E-02 3.17090E-02 571440 + 750 571450 La-145 1.61850E-02 2.39660E-02 571450 + 751 571460 La-146 3.76060E-03 7.50290E-03 571460 + 752 571461 La-146m 7.88940E-03 7.88940E-03 571461 + 753 571470 La-147 9.60970E-03 1.04030E-02 571470 + 754 571480 La-148 3.51240E-03 3.71440E-03 571480 + 755 571490 La-149 1.20970E-03 1.22230E-03 571490 + 756 571500 La-150 2.13960E-04 2.15930E-04 571500 + 757 571510 La-151 3.20660E-05 3.20660E-05 571510 + 758 571520 La-152 3.14500E-06 3.14500E-06 571520 + 759 571530 La-153 9.39680E-10 9.39680E-10 571530 + 760 581400 Ce-140 4.85060E-06 4.86880E-02 58140.82c + 761 581410 Ce-141 2.59430E-05 5.01500E-02 58141.82c + 762 581420 Ce-142 1.41390E-04 4.78110E-02 58142.82c + 763 581430 Ce-143 4.67060E-04 3.91250E-02 58143.82c + 764 581440 Ce-144 2.11950E-03 3.38280E-02 58144.82c + 765 581450 Ce-145 4.98050E-03 2.89470E-02 581450 + 766 581460 Ce-146 1.09780E-02 2.63700E-02 581460 + 767 581470 Ce-147 1.36080E-02 2.40110E-02 581470 + 768 581480 Ce-148 1.62830E-02 2.00150E-02 581480 + 769 581490 Ce-149 9.94990E-03 1.11610E-02 581490 + 770 581500 Ce-150 6.06540E-03 6.27550E-03 581500 + 771 581510 Ce-151 1.61430E-03 1.64660E-03 581510 + 772 581520 Ce-152 5.24410E-04 5.27370E-04 581520 + 773 581530 Ce-153 5.72250E-05 5.72260E-05 581530 + 774 581540 Ce-154 1.13730E-05 1.13730E-05 581540 + 775 581550 Ce-155 3.41160E-09 3.41160E-09 581550 + 776 591420 Pr-142 3.06240E-10 1.14100E-09 59142.82c + 777 591421 Pr-142m 8.34760E-10 8.34760E-10 591421 + 778 591430 Pr-143 1.74480E-06 3.91270E-02 59143.82c + 779 591440 Pr-144 8.64790E-07 3.38370E-02 591440 + 780 591441 Pr-144m 8.79770E-06 4.75600E-04 591441 + 781 591450 Pr-145 7.12810E-05 2.90180E-02 591450 + 782 591460 Pr-146 3.41940E-04 2.67120E-02 591460 + 783 591470 Pr-147 1.49300E-03 2.55040E-02 591470 + 784 591480 Pr-148 5.10500E-04 2.05250E-02 591480 + 785 591481 Pr-148m 2.47490E-03 2.47490E-03 591481 + 786 591490 Pr-149 5.61740E-03 1.67780E-02 591490 + 787 591500 Pr-150 5.85200E-03 1.21270E-02 591500 + 788 591510 Pr-151 6.30270E-03 7.94930E-03 591510 + 789 591520 Pr-152 3.13330E-03 3.66100E-03 591520 + 790 591530 Pr-153 1.36360E-03 1.42050E-03 591530 + 791 591540 Pr-154 3.14830E-04 3.26130E-04 591540 + 792 591550 Pr-155 8.97540E-05 8.97570E-05 591550 + 793 591560 Pr-156 1.29540E-05 1.29540E-05 591560 + 794 591570 Pr-157 1.20590E-08 1.20590E-08 591570 + 795 591580 Pr-158 1.14640E-10 1.14640E-10 591580 + 796 601450 Nd-145 6.06070E-09 2.90180E-02 60145.82c + 797 601460 Nd-146 7.08590E-06 2.67190E-02 60146.82c + 798 601470 Nd-147 5.43190E-05 2.55580E-02 60147.82c + 799 601480 Nd-148 3.19950E-04 2.33200E-02 60148.82c + 800 601490 Nd-149 9.79440E-04 1.77580E-02 601490 + 801 601500 Nd-150 2.61640E-03 1.47440E-02 60150.82c + 802 601510 Nd-151 4.20420E-03 1.21530E-02 601510 + 803 601520 Nd-152 5.96860E-03 9.62960E-03 601520 + 804 601530 Nd-153 4.34360E-03 5.76410E-03 601530 + 805 601540 Nd-154 3.31090E-03 3.63700E-03 601540 + 806 601550 Nd-155 1.49610E-03 1.58620E-03 601550 + 807 601560 Nd-156 4.36350E-04 4.48950E-04 601560 + 808 601570 Nd-157 8.76940E-05 8.77050E-05 601570 + 809 601580 Nd-158 2.37910E-05 2.37910E-05 601580 + 810 601590 Nd-159 3.10840E-06 3.10840E-06 601590 + 811 601600 Nd-160 7.22000E-10 7.22000E-10 601600 + 812 611470 Pm-147 8.58380E-10 2.55580E-02 61147.82c + 813 611480 Pm-148 2.55290E-07 2.90080E-07 61148.82c + 814 611481 Pm-148m 6.95850E-07 6.95850E-07 61548.82c + 815 611490 Pm-149 9.70700E-06 1.77670E-02 61149.82c + 816 611500 Pm-150 3.84330E-05 3.84330E-05 611500 + 817 611510 Pm-151 1.75860E-04 1.23290E-02 61151.82c + 818 611520 Pm-152 8.92260E-05 9.71880E-03 611520 + 819 611521 Pm-152m 1.87580E-04 1.87580E-04 611521 + 820 611522 Pm-152m 2.45030E-04 2.45030E-04 611522 + 821 611530 Pm-153 1.12560E-03 6.88970E-03 611530 + 822 611540 Pm-154 7.73400E-04 4.41040E-03 611540 + 823 611541 Pm-154m 7.73400E-04 7.73400E-04 611541 + 824 611550 Pm-155 2.04480E-03 3.63100E-03 611550 + 825 611560 Pm-156 1.15300E-03 1.60190E-03 611560 + 826 611570 Pm-157 6.60230E-04 7.47940E-04 611570 + 827 611580 Pm-158 1.90340E-04 2.14140E-04 611580 + 828 611590 Pm-159 6.34690E-05 6.65700E-05 611590 + 829 611600 Pm-160 7.58620E-06 7.58690E-06 611600 + 830 611610 Pm-161 3.27840E-06 3.27840E-06 611610 + 831 611620 Pm-162 1.27510E-09 1.27510E-09 611620 + 832 611630 Pm-163 2.03120E-11 2.03120E-11 611630 + 833 621500 Sm-150 9.86730E-07 3.94200E-05 62150.82c + 834 621510 Sm-151 1.11710E-07 1.23290E-02 62151.82c + 835 621520 Sm-152 4.90940E-05 1.02010E-02 62152.82c + 836 621530 Sm-153 3.11040E-05 7.00790E-03 62153.82c + 837 621531 Sm-153m 8.70260E-05 8.70260E-05 621531 + 838 621540 Sm-154 4.23210E-04 5.60700E-03 62154.82c + 839 621550 Sm-155 8.35180E-04 4.46620E-03 621550 + 840 621560 Sm-156 1.06500E-03 2.66690E-03 621560 + 841 621570 Sm-157 1.01290E-03 1.76080E-03 621570 + 842 621580 Sm-158 7.56380E-04 9.70530E-04 621580 + 843 621590 Sm-159 4.96660E-04 5.63240E-04 621590 + 844 621600 Sm-160 2.42930E-04 2.50500E-04 621600 + 845 621610 Sm-161 6.35090E-05 6.67870E-05 621610 + 846 621620 Sm-162 1.24650E-05 1.24660E-05 621620 + 847 621630 Sm-163 2.31960E-06 2.31960E-06 621630 + 848 621640 Sm-164 4.25580E-09 4.25580E-09 621640 + 849 621650 Sm-165 4.69890E-11 4.69890E-11 621650 + 850 631520 Eu-152 9.73220E-11 2.26220E-10 63152.82c + 851 631521 Eu-152m 2.22370E-11 2.22370E-11 631521 + 852 631522 Eu-152m 1.28900E-10 1.28900E-10 631522 + 853 631530 Eu-153 1.29210E-08 7.00790E-03 63153.82c + 854 631540 Eu-154 1.49130E-06 3.09910E-06 63154.82c + 855 631541 Eu-154m 1.60780E-06 1.60780E-06 631541 + 856 631550 Eu-155 1.53320E-05 4.48150E-03 63155.82c + 857 631560 Eu-156 5.65020E-05 2.72350E-03 63156.82c + 858 631570 Eu-157 1.19990E-04 1.88080E-03 63157.82c + 859 631580 Eu-158 1.82710E-04 1.15320E-03 631580 + 860 631590 Eu-159 3.03540E-04 8.66780E-04 631590 + 861 631600 Eu-160 2.89810E-04 5.40310E-04 631600 + 862 631610 Eu-161 1.81580E-04 2.48370E-04 631610 + 863 631620 Eu-162 7.48520E-05 8.73180E-05 631620 + 864 631630 Eu-163 3.24940E-05 3.48140E-05 631630 + 865 631640 Eu-164 1.08560E-05 1.08600E-05 631640 + 866 631650 Eu-165 1.68880E-07 1.68930E-07 631650 + 867 631660 Eu-166 5.07910E-09 5.07910E-09 631660 + 868 631670 Eu-167 1.05520E-10 1.05520E-10 631670 + 869 641550 Gd-155 2.47800E-10 4.48150E-03 64155.82c + 870 641551 Gd-155m 6.93320E-10 6.93320E-10 641551 + 871 641560 Gd-156 9.95460E-07 2.72440E-03 64156.82c + 872 641570 Gd-157 3.96100E-06 1.88480E-03 64157.82c + 873 641580 Gd-158 2.93630E-05 1.18260E-03 64158.82c + 874 641590 Gd-159 6.09120E-05 9.27690E-04 641590 + 875 641600 Gd-160 1.37960E-04 6.78270E-04 64160.82c + 876 641610 Gd-161 1.54600E-04 4.02970E-04 641610 + 877 641620 Gd-162 1.75290E-04 2.62610E-04 641620 + 878 641630 Gd-163 9.27510E-05 1.27570E-04 641630 + 879 641640 Gd-164 5.79010E-05 6.87610E-05 641640 + 880 641650 Gd-165 2.45920E-05 2.47610E-05 641650 + 881 641660 Gd-166 4.96080E-06 4.96590E-06 641660 + 882 641670 Gd-167 1.11910E-07 1.12020E-07 641670 + 883 641680 Gd-168 7.67410E-09 7.67410E-09 641680 + 884 641690 Gd-169 1.74450E-10 1.74450E-10 641690 + 885 651570 Tb-157 6.38050E-11 6.38050E-11 651570 + 886 651580 Tb-158 1.40920E-09 1.54690E-09 651580 + 887 651581 Tb-158m 1.38520E-10 1.38520E-10 651581 + 888 651590 Tb-159 5.72750E-08 9.27750E-04 65159.82c + 889 651600 Tb-160 5.64580E-07 5.64580E-07 65160.82c + 890 651610 Tb-161 9.82710E-06 4.12790E-04 651610 + 891 651620 Tb-162 1.35840E-05 2.76190E-04 651620 + 892 651630 Tb-163 2.20190E-05 1.49580E-04 651630 + 893 651640 Tb-164 3.01290E-05 9.88900E-05 651640 + 894 651650 Tb-165 3.07210E-05 5.54820E-05 651650 + 895 651660 Tb-166 1.98430E-05 2.48090E-05 651660 + 896 651670 Tb-167 8.20080E-06 8.31280E-06 651670 + 897 651680 Tb-168 8.06630E-07 8.14300E-07 651680 + 898 651690 Tb-169 1.46210E-07 1.46380E-07 651690 + 899 651700 Tb-170 3.60940E-09 3.60940E-09 651700 + 900 651710 Tb-171 6.15640E-10 6.15640E-10 651710 + 901 661600 Dy-160 1.74280E-10 5.64750E-07 66160.82c + 902 661610 Dy-161 3.69100E-09 4.12800E-04 66161.82c + 903 661620 Dy-162 1.13240E-06 2.77320E-04 66162.82c + 904 661630 Dy-163 1.15960E-06 1.50740E-04 66163.82c + 905 661640 Dy-164 8.43720E-06 1.07330E-04 66164.82c + 906 661650 Dy-165 5.42230E-06 6.16100E-05 661650 + 907 661651 Dy-165m 7.21950E-07 7.21950E-07 661651 + 908 661660 Dy-166 1.48770E-05 3.96860E-05 661660 + 909 661670 Dy-167 8.19930E-06 1.65120E-05 661670 + 910 661680 Dy-168 4.66520E-06 5.47950E-06 661680 + 911 661690 Dy-169 3.65230E-06 3.79870E-06 661690 + 912 661700 Dy-170 4.39330E-07 4.42940E-07 661700 + 913 661710 Dy-171 1.54760E-07 1.55380E-07 661710 + 914 661720 Dy-172 1.76750E-08 1.76750E-08 661720 + 915 661730 Dy-173 8.29000E-10 8.29000E-10 661730 + 916 671620 Ho-162 1.80130E-12 4.84540E-12 671620 + 917 671621 Ho-162m 4.90980E-12 4.90980E-12 671621 + 918 671630 Ho-163 2.42010E-10 2.74230E-10 671630 + 919 671631 Ho-163m 3.22220E-11 3.22220E-11 671631 + 920 671640 Ho-164 1.26930E-09 4.72900E-09 671640 + 921 671641 Ho-164m 3.45970E-09 3.45970E-09 671641 + 922 671650 Ho-165 7.08860E-08 6.16970E-05 67165.82c + 923 671660 Ho-166 9.31540E-08 3.97790E-05 671660 + 924 671661 Ho-166m 2.53920E-07 2.53920E-07 671661 + 925 671670 Ho-167 1.20650E-06 1.77190E-05 671670 + 926 671680 Ho-168 1.74550E-06 1.01300E-05 671680 + 927 671681 Ho-168m 2.91920E-06 2.91920E-06 671681 + 928 671690 Ho-169 2.43470E-06 6.23340E-06 671690 + 929 671700 Ho-170 1.33170E-06 1.33170E-06 671700 + 930 671701 Ho-170m 4.88540E-07 9.31480E-07 671701 + 931 671710 Ho-171 2.24680E-06 2.40220E-06 671710 + 932 671720 Ho-172 4.76800E-07 4.94480E-07 671720 + 933 671730 Ho-173 1.68540E-07 1.69370E-07 671730 + 934 671740 Ho-174 1.42290E-08 1.42290E-08 671740 + 935 671750 Ho-175 1.36080E-09 1.36080E-09 671750 + 936 681650 Er-165 1.13420E-11 1.13420E-11 681650 + 937 681660 Er-166 4.89610E-10 3.97800E-05 68166.82c + 938 681670 Er-167 3.23240E-09 1.77220E-05 68167.82c + 939 681671 Er-167m 4.30380E-10 2.11770E-06 681671 + 940 681680 Er-168 4.08360E-08 1.01850E-05 68168.82c + 941 681690 Er-169 1.52450E-07 6.38580E-06 681690 + 942 681700 Er-170 2.92800E-07 2.55590E-06 68170.82c + 943 681710 Er-171 1.08980E-06 3.49200E-06 681710 + 944 681720 Er-172 1.85150E-06 2.34600E-06 681720 + 945 681730 Er-173 8.13640E-07 9.83010E-07 681730 + 946 681740 Er-174 4.60660E-07 4.74890E-07 681740 + 947 681750 Er-175 8.51550E-08 8.65160E-08 681750 + 948 681760 Er-176 2.03550E-08 2.03550E-08 681760 + 949 681770 Er-177 1.37950E-09 1.37950E-09 681770 + 950 691680 Tm-168 1.19600E-11 1.19600E-11 691680 + 951 691690 Tm-169 3.71140E-10 6.38620E-06 691690 + 952 691700 Tm-170 1.49960E-09 1.49960E-09 691700 + 953 691710 Tm-171 4.16340E-08 3.53360E-06 691710 + 954 691720 Tm-172 9.75020E-08 2.44350E-06 691720 + 955 691730 Tm-173 3.63190E-07 1.34620E-06 691730 + 956 691740 Tm-174 3.30560E-07 8.05450E-07 691740 + 957 691750 Tm-175 3.71340E-07 4.57860E-07 691750 + 958 691760 Tm-176 1.51960E-07 1.72310E-07 691760 + 959 691770 Tm-177 7.19850E-08 7.33640E-08 691770 + 960 691780 Tm-178 9.64520E-09 9.64520E-09 691780 + 961 691790 Tm-179 1.78630E-09 1.78630E-09 691790 + 962 701710 Yb-171 3.55120E-12 3.53360E-06 701710 + 963 701711 Yb-171m 2.66720E-11 2.66720E-11 701711 + 964 701720 Yb-172 5.72480E-10 2.44400E-06 701720 + 965 701730 Yb-173 4.36630E-09 1.35060E-06 701730 + 966 701740 Yb-174 2.85670E-08 8.34050E-07 701740 + 967 701750 Yb-175 4.98480E-08 5.14340E-07 701750 + 968 701751 Yb-175m 6.63700E-09 3.59190E-07 701751 + 969 701760 Yb-176 4.60440E-08 2.96680E-07 701760 + 970 701761 Yb-176m 9.65960E-08 1.82750E-07 701761 + 971 701770 Yb-177 8.99330E-08 1.81410E-07 701770 + 972 701771 Yb-177m 1.81070E-08 9.14720E-08 701771 + 973 701780 Yb-178 9.00980E-08 9.97430E-08 701780 + 974 701790 Yb-179 2.97350E-08 3.15210E-08 701790 + 975 701800 Yb-180 1.17670E-08 1.17670E-08 701800 + 976 701810 Yb-181 1.25250E-09 1.25250E-09 701810 + 977 711730 Lu-173 2.49230E-12 2.49230E-12 711730 + 978 711740 Lu-174 9.59930E-12 3.56130E-11 711740 + 979 711741 Lu-174m 2.61660E-11 2.61660E-11 711741 + 980 711750 Lu-175 5.59600E-10 5.14900E-07 71175.82c + 981 711760 Lu-176 1.89720E-09 2.01730E-08 71176.82c + 982 711761 Lu-176m 9.04360E-10 9.04360E-10 711761 + 983 711770 Lu-177 9.76930E-09 1.92250E-07 711770 + 984 711771 Lu-177m 4.65170E-09 4.76740E-09 711771 + 985 711772 Lu-177m 2.31490E-10 2.31490E-10 711772 + 986 711780 Lu-178 8.84080E-09 1.08580E-07 711780 + 987 711781 Lu-178m 1.18440E-08 1.18440E-08 711781 + 988 711790 Lu-179 3.64430E-08 7.28160E-08 711790 + 989 711791 Lu-179m 4.85220E-09 3.63730E-08 711791 + 990 711800 Lu-180 6.99860E-09 2.25780E-08 711800 + 991 711801 Lu-180m 6.99860E-09 1.87660E-08 711801 + 992 711802 Lu-180m 1.23930E-08 1.23930E-08 711802 + 993 711810 Lu-181 1.80920E-08 1.93450E-08 711810 + 994 711820 Lu-182 4.22910E-09 4.22910E-09 711820 + 995 711830 Lu-183 1.35730E-09 1.35730E-09 711830 + 996 711840 Lu-184 1.14670E-10 1.14670E-10 711840 + 997 721760 Hf-176 3.92640E-12 9.07420E-10 72176.82c + 998 721770 Hf-177 2.94870E-11 1.96100E-07 72177.82c + 999 721771 Hf-177m 1.39120E-11 3.82050E-09 721771 + 1000 721772 Hf-177m 8.22510E-13 1.16570E-10 721772 + 1001 721780 Hf-178 1.55280E-10 1.20910E-07 72178.82c + 1002 721781 Hf-178m 2.89590E-10 1.21700E-08 721781 + 1003 721782 Hf-178m 3.62220E-11 3.62220E-11 721782 + 1004 721790 Hf-179 1.06290E-09 7.46560E-08 72179.82c + 1005 721791 Hf-179m 3.07560E-10 3.07560E-10 721791 + 1006 721792 Hf-179m 4.64650E-10 4.64650E-10 721792 + 1007 721800 Hf-180 2.50730E-09 4.59030E-08 72180.82c + 1008 721801 Hf-180m 5.26000E-09 1.14560E-08 721801 + 1009 721810 Hf-181 8.73560E-09 2.80800E-08 721810 + 1010 721820 Hf-182 3.96530E-09 1.16880E-08 721820 + 1011 721821 Hf-182m 8.31870E-09 8.31870E-09 721821 + 1012 721830 Hf-183 6.52010E-09 7.87740E-09 721830 + 1013 721840 Hf-184 1.19200E-09 1.24930E-09 721840 + 1014 721841 Hf-184m 2.50070E-09 2.55800E-09 721841 + 1015 721850 Hf-185 6.83850E-10 6.83850E-10 721850 + 1016 721860 Hf-186 1.63770E-10 1.63770E-10 721860 + 1017 721870 Hf-187 1.11150E-11 1.11150E-11 721870 + 1018 731790 Ta-179 3.17010E-12 4.44300E-12 731790 + 1019 731791 Ta-179m 1.20270E-12 1.27290E-12 731791 + 1020 731800 Ta-180 1.69070E-11 1.69070E-11 731800 + 1021 731801 Ta-180m 2.26500E-11 5.81650E-11 731801 + 1022 731810 Ta-181 3.31920E-10 2.84120E-08 73181.82c + 1023 731820 Ta-182 2.76510E-10 5.68150E-09 73182.82c + 1024 731821 Ta-182m 3.02040E-10 5.40500E-09 731821 + 1025 731822 Ta-182m 2.78140E-10 5.10300E-09 731822 + 1026 731830 Ta-183 2.89700E-09 1.07740E-08 731830 + 1027 731840 Ta-184 2.63780E-09 6.44520E-09 731840 + 1028 731850 Ta-185 1.85870E-09 3.65160E-09 731850 + 1029 731851 Ta-185m 1.10910E-09 1.10910E-09 731851 + 1030 731860 Ta-186 1.21650E-09 1.38030E-09 731860 + 1031 731870 Ta-187 5.76910E-10 5.88030E-10 731870 + 1032 731880 Ta-188 7.74520E-11 7.74520E-11 731880 + 1033 731890 Ta-189 1.43790E-11 1.43790E-11 731890 + 1034 741820 W-182 5.00120E-12 5.68660E-09 74182.82c + 1035 741830 W-183 7.23550E-12 1.08090E-08 74183.82c + 1036 741831 W-183m 2.74010E-11 3.93730E-10 741831 + 1037 741840 W-184 2.26780E-10 6.67190E-09 74184.82c + 1038 741850 W-185 1.18290E-10 4.10090E-09 741850 + 1039 741851 W-185m 3.30970E-10 3.30970E-10 741851 + 1040 741860 W-186 8.09100E-10 2.51750E-09 74186.82c + 1041 741861 W-186m 3.27600E-10 3.27600E-10 741861 + 1042 741870 W-187 8.61910E-10 1.44990E-09 741870 + 1043 741880 W-188 7.19970E-10 7.97420E-10 741880 + 1044 741890 W-189 2.38110E-10 2.52490E-10 741890 + 1045 741900 W-190 4.03350E-11 9.43740E-11 741900 + 1046 741901 W-190m 5.40390E-11 5.40390E-11 741901 + 1047 741910 W-191 1.00660E-11 1.00660E-11 741910 + 1048 741920 W-192 1.27000E-12 1.27000E-12 741920 + 1049 751850 Re-185 4.42590E-12 4.10530E-09 75185.82c + 1050 751860 Re-186 8.30990E-12 8.30990E-12 751860 + 1051 751861 Re-186m 1.38970E-11 1.38970E-11 751861 + 1052 751870 Re-187 1.16300E-10 1.56620E-09 75187.82c + 1053 751880 Re-188 4.41570E-11 9.61940E-10 751880 + 1054 751881 Re-188m 1.20360E-10 1.20360E-10 751881 + 1055 751890 Re-189 3.29160E-10 5.81650E-10 751890 + 1056 751900 Re-190 6.80010E-11 2.27430E-10 751900 + 1057 751901 Re-190m 1.42660E-10 1.42660E-10 751901 + 1058 751910 Re-191 1.44670E-10 1.54740E-10 751910 + 1059 751920 Re-192 3.38930E-11 3.51630E-11 751920 + 1060 751930 Re-193 1.08980E-11 1.08980E-11 751930 + 1061 761880 Os-188 3.80500E-12 9.65750E-10 761880 + 1062 761890 Os-189 3.03970E-12 5.96200E-10 761890 + 1063 761891 Os-189m 1.15110E-11 7.13230E-11 761891 + 1064 761900 Os-190 2.63740E-11 3.66740E-10 761900 + 1065 761901 Os-190m 3.53330E-11 1.12940E-10 761901 + 1066 761910 Os-191 5.50040E-11 2.24270E-10 761910 + 1067 761911 Os-191m 1.45250E-11 1.45250E-11 761911 + 1068 761920 Os-192 4.18800E-11 1.26530E-10 761920 + 1069 761921 Os-192m 5.61070E-11 5.61070E-11 761921 + 1070 761930 Os-193 5.20990E-11 6.29970E-11 761930 + 1071 761940 Os-194 2.95460E-11 2.95460E-11 761940 + 1072 761950 Os-195 5.48450E-12 5.48450E-12 761950 + 1073 761960 Os-196 1.31670E-12 1.31670E-12 761960 + 1074 771910 Ir-191 6.91900E-13 2.26890E-10 77191.82c + 1075 771911 Ir-191m 1.44560E-12 1.07790E-10 771911 + 1076 771920 Ir-192 2.26610E-12 1.40920E-11 771920 + 1077 771921 Ir-192m 2.26610E-12 2.26610E-12 771921 + 1078 771922 Ir-192m 2.26610E-12 9.56000E-12 771922 + 1079 771930 Ir-193 6.06620E-12 8.60360E-11 77193.82c + 1080 771931 Ir-193m 1.69730E-11 1.71920E-11 771931 + 1081 771940 Ir-194 7.00230E-12 4.35510E-11 771940 + 1082 771941 Ir-194m 7.00230E-12 7.00230E-12 771941 + 1083 771942 Ir-194m 7.00230E-12 7.00230E-12 771942 + 1084 771950 Ir-195 6.23810E-12 1.25950E-11 771950 + 1085 771951 Ir-195m 1.74540E-11 1.74540E-11 771951 + 1086 771960 Ir-196 4.86540E-12 6.19670E-12 771960 + 1087 771961 Ir-196m 4.86540E-12 4.86540E-12 771961 + 1088 771970 Ir-197 1.21690E-12 1.22540E-12 771970 + 1089 771971 Ir-197m 3.40470E-12 3.40470E-12 771971 + 1090 781940 Pt-194 1.79690E-12 5.23500E-11 781940 + 1091 781950 Pt-195 9.39770E-13 3.27460E-11 781950 + 1092 781951 Pt-195m 2.62940E-12 7.93540E-12 781951 + 1093 781960 Pt-196 9.05060E-12 2.00980E-11 781960 + 1094 781970 Pt-197 1.80950E-12 1.12150E-11 781970 + 1095 781971 Pt-197m 5.06290E-12 8.45910E-12 781971 + 1096 781980 Pt-198 5.75120E-12 5.75120E-12 781980 + 1097 781990 Pt-199 7.00720E-13 1.90640E-12 781990 + 1098 781991 Pt-199m 1.20570E-12 1.20570E-12 781991 + 1099 791980 Au-198 8.19520E-13 1.30810E-12 791980 + 1100 791990 Au-199 2.62310E-12 4.52950E-12 791990 + 1101 792000 Au-200 9.80370E-13 1.10650E-12 792000 + + Spontaneous fission: + + Decay constant : 1.22025E-09 + SF decay fraction : 1.38000E-06 + Number of products : 1080 / 1134 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 4.57150E-05 4.57150E-05 1001.82c + 2 10020 H-2 1.39710E-05 1.39710E-05 1002.82c + 3 10030 H-3 1.86000E-04 1.86000E-04 1003.82c + 4 20040 He-4 2.89000E-03 2.89000E-03 2004.82c + 5 200520 Ca-52 1.04610E-12 1.04610E-12 200520 + 6 210520 Sc-52 3.27920E-12 4.30440E-12 210520 + 7 210530 Sc-53 4.75530E-12 4.75530E-12 210530 + 8 210540 Sc-54 3.20850E-12 3.20850E-12 210540 + 9 210550 Sc-55 2.02030E-12 2.02030E-12 210550 + 10 220520 Ti-52 1.63030E-12 5.93470E-12 220520 + 11 220530 Ti-53 5.57860E-12 1.03340E-11 220530 + 12 220540 Ti-54 1.49710E-11 1.81800E-11 220540 + 13 220550 Ti-55 2.32970E-11 2.53170E-11 220550 + 14 220560 Ti-56 2.91800E-11 2.91800E-11 220560 + 15 220570 Ti-57 1.67660E-11 1.67660E-11 220570 + 16 220580 Ti-58 7.02220E-12 7.02220E-12 220580 + 17 220590 Ti-59 1.38490E-12 1.38490E-12 220590 + 18 230540 V-54 1.71910E-12 1.98990E-11 230540 + 19 230550 V-55 1.08680E-11 3.61850E-11 230550 + 20 230560 V-56 3.18580E-11 6.10880E-11 230560 + 21 230570 V-57 7.43430E-11 9.10590E-11 230570 + 22 230580 V-58 7.99780E-11 8.70000E-11 230580 + 23 230590 V-59 7.37920E-11 7.51770E-11 230590 + 24 230600 V-60 3.11750E-11 3.11750E-11 230600 + 25 230610 V-61 1.12830E-11 1.12830E-11 230610 + 26 230620 V-62 1.70920E-12 1.70920E-12 230620 + 27 240560 Cr-56 5.35360E-12 6.68060E-11 240560 + 28 240570 Cr-57 3.08860E-11 1.91180E-10 240570 + 29 240580 Cr-58 1.32180E-10 1.49580E-10 240580 + 30 240590 Cr-59 2.87710E-10 3.62890E-10 240590 + 31 240600 Cr-60 5.09970E-10 5.41820E-10 240600 + 32 240610 Cr-61 4.93890E-10 5.04500E-10 240610 + 33 240620 Cr-62 3.62880E-10 3.64590E-10 240620 + 34 240630 Cr-63 1.12800E-10 1.12800E-10 240630 + 35 240640 Cr-64 2.55750E-11 2.55750E-11 240640 + 36 240650 Cr-65 3.01280E-12 3.01280E-12 240650 + 37 250580 Mn-58 4.46970E-12 1.54050E-10 250580 + 38 250590 Mn-59 4.67310E-11 4.09620E-10 250590 + 39 250600 Mn-60 2.00860E-11 5.82420E-10 250600 + 40 250601 Mn-60m 1.78390E-10 1.78390E-10 250601 + 41 250610 Mn-61 7.60080E-10 1.26460E-09 250610 + 42 250620 Mn-62 1.14270E-09 1.32500E-09 250620 + 43 250621 Mn-62m 2.05140E-10 3.87430E-10 250621 + 44 250630 Mn-63 1.82790E-09 1.94070E-09 250630 + 45 250640 Mn-64 1.15360E-09 1.17920E-09 250640 + 46 250650 Mn-65 6.80010E-10 6.83020E-10 250650 + 47 250660 Mn-66 1.76140E-10 1.76140E-10 250660 + 48 250670 Mn-67 3.21890E-11 3.21890E-11 250670 + 49 250680 Mn-68 2.40400E-12 2.40400E-12 250680 + 50 260600 Fe-60 1.05750E-11 7.50880E-10 260600 + 51 260610 Fe-61 1.07220E-10 1.37180E-09 260610 + 52 260620 Fe-62 7.90270E-10 2.50270E-09 260620 + 53 260630 Fe-63 2.51940E-09 4.46010E-09 260630 + 54 260640 Fe-64 6.35140E-09 7.53060E-09 260640 + 55 260650 Fe-65 9.34450E-09 1.00270E-08 260650 + 56 260660 Fe-66 1.10020E-08 1.11780E-08 260660 + 57 260670 Fe-67 5.79890E-09 5.83110E-09 260670 + 58 260680 Fe-68 2.22380E-09 2.22620E-09 260680 + 59 260690 Fe-69 4.10000E-10 4.10000E-10 260690 + 60 260700 Fe-70 5.47820E-11 5.47820E-11 260700 + 61 260710 Fe-71 3.46450E-12 3.46450E-12 260710 + 62 270620 Co-62 2.73080E-12 2.50540E-09 270620 + 63 270621 Co-62m 6.39610E-12 6.39610E-12 270621 + 64 270630 Co-63 1.34760E-10 4.59490E-09 270630 + 65 270640 Co-64 8.63580E-10 8.39420E-09 270640 + 66 270650 Co-65 5.12530E-09 1.51530E-08 270650 + 67 270660 Co-66 1.41320E-08 2.53100E-08 270660 + 68 270670 Co-67 3.04880E-08 3.63190E-08 270670 + 69 270680 Co-68 1.61330E-08 2.43760E-08 270680 + 70 270681 Co-68m 1.42320E-08 1.64870E-08 270681 + 71 270690 Co-69 2.64600E-08 2.68410E-08 270690 + 72 270700 Co-70 5.25500E-09 5.25500E-09 270700 + 73 270701 Co-70m 5.25500E-09 5.30980E-09 270701 + 74 270710 Co-71 3.48760E-09 3.49110E-09 270710 + 75 270720 Co-72 4.81120E-10 4.81120E-10 270720 + 76 270730 Co-73 4.54810E-11 4.54810E-11 270730 + 77 270740 Co-74 1.81240E-12 1.81240E-12 270740 + 78 280640 Ni-64 1.37070E-11 8.40790E-09 28064.82c + 79 280650 Ni-65 2.30400E-10 1.53830E-08 280650 + 80 280660 Ni-66 2.82550E-09 2.81360E-08 280660 + 81 280670 Ni-67 1.49300E-08 5.12490E-08 280670 + 82 280680 Ni-68 5.89610E-08 9.18490E-08 280680 + 83 280690 Ni-69 6.08950E-08 8.74680E-08 280690 + 84 280691 Ni-69m 6.08950E-08 6.08950E-08 280691 + 85 280700 Ni-70 2.05030E-07 2.15590E-07 280700 + 86 280710 Ni-71 1.84080E-07 1.87570E-07 280710 + 87 280720 Ni-72 1.24270E-07 1.24750E-07 280720 + 88 280730 Ni-73 3.58190E-08 3.58650E-08 280730 + 89 280740 Ni-74 7.53200E-09 7.53380E-09 280740 + 90 280750 Ni-75 8.22170E-10 8.22170E-10 280750 + 91 280760 Ni-76 6.34070E-11 6.34070E-11 280760 + 92 280770 Ni-77 2.17850E-12 2.17850E-12 280770 + 93 290660 Cu-66 9.46710E-12 2.81450E-08 290660 + 94 290670 Cu-67 2.46350E-10 5.14950E-08 290670 + 95 290680 Cu-68 7.93810E-10 9.42050E-08 290680 + 96 290681 Cu-68m 1.85930E-09 1.85930E-09 290681 + 97 290690 Cu-69 2.34070E-08 1.71770E-07 290690 + 98 290700 Cu-70 7.13860E-09 5.24710E-08 290700 + 99 290701 Cu-70m 7.95280E-08 9.06640E-08 290701 + 100 290702 Cu-70m 7.13860E-09 2.22730E-07 290702 + 101 290710 Cu-71 3.33400E-07 5.20970E-07 290710 + 102 290720 Cu-72 5.47690E-07 6.72440E-07 290720 + 103 290730 Cu-73 6.96440E-07 7.32300E-07 290730 + 104 290740 Cu-74 4.11790E-07 4.19340E-07 290740 + 105 290750 Cu-75 2.26570E-07 2.27380E-07 290750 + 106 290760 Cu-76 2.71790E-08 2.72100E-08 290760 + 107 290761 Cu-76m 2.71790E-08 2.72100E-08 290761 + 108 290770 Cu-77 9.00170E-09 9.00390E-09 290770 + 109 290780 Cu-78 6.06760E-10 6.06760E-10 290780 + 110 290790 Cu-79 9.16150E-12 9.16150E-12 290790 + 111 300680 Zn-68 1.19430E-11 9.45140E-08 300680 + 112 300690 Zn-69 5.91380E-11 1.72080E-07 300690 + 113 300691 Zn-69m 2.55760E-10 2.55760E-10 300691 + 114 300700 Zn-70 6.00810E-09 3.15410E-07 300700 + 115 300710 Zn-71 1.05000E-08 5.31470E-07 300710 + 116 300711 Zn-71m 4.54110E-08 4.54110E-08 300711 + 117 300720 Zn-72 3.78310E-07 1.05080E-06 300720 + 118 300730 Zn-73 1.11540E-07 1.42820E-06 300730 + 119 300731 Zn-73m 1.52480E-07 5.84370E-07 300731 + 120 300732 Zn-73m 8.63780E-07 8.63780E-07 300732 + 121 300740 Zn-74 2.67800E-06 3.10530E-06 300740 + 122 300750 Zn-75 3.71640E-06 3.93660E-06 300750 + 123 300760 Zn-76 4.09720E-06 4.15080E-06 300760 + 124 300770 Zn-77 1.71240E-06 1.85230E-06 300770 + 125 300771 Zn-77m 2.61780E-07 2.61780E-07 300771 + 126 300780 Zn-78 6.87730E-07 6.88340E-07 300780 + 127 300790 Zn-79 3.25530E-08 3.25570E-08 300790 + 128 300800 Zn-80 2.34430E-08 2.34430E-08 300800 + 129 300810 Zn-81 9.59920E-10 9.59920E-10 300810 + 130 300820 Zn-82 3.07940E-11 3.07940E-11 300820 + 131 310700 Ga-70 5.59830E-12 5.59830E-12 310700 + 132 310710 Ga-71 2.68700E-10 5.77150E-07 310710 + 133 310720 Ga-72 4.74360E-09 1.05600E-06 310720 + 134 310721 Ga-72m 5.34100E-10 3.55460E-08 310721 + 135 310730 Ga-73 7.20920E-08 1.93220E-06 310730 + 136 310740 Ga-74 2.15260E-07 2.70570E-06 310740 + 137 310741 Ga-74m 2.15260E-07 3.32060E-06 310741 + 138 310750 Ga-75 2.39550E-06 6.33210E-06 310750 + 139 310760 Ga-76 6.19490E-06 1.03460E-05 310760 + 140 310770 Ga-77 1.23260E-05 1.43090E-05 310770 + 141 310780 Ga-78 1.12780E-05 1.19670E-05 310780 + 142 310790 Ga-79 2.54790E-06 2.58000E-06 310790 + 143 310800 Ga-80 5.49530E-06 5.51880E-06 310800 + 144 310810 Ga-81 1.18530E-06 1.18620E-06 310810 + 145 310820 Ga-82 1.19720E-07 1.19750E-07 310820 + 146 310830 Ga-83 1.62230E-08 1.62230E-08 310830 + 147 310840 Ga-84 4.60190E-10 4.60190E-10 310840 + 148 320720 Ge-72 6.51640E-12 1.05600E-06 32072.82c + 149 320730 Ge-73 2.24100E-10 1.93250E-06 32073.82c + 150 320731 Ge-73m 5.18180E-11 1.90390E-06 320731 + 151 320740 Ge-74 8.28940E-09 3.54410E-06 32074.82c + 152 320750 Ge-75 1.71520E-08 6.46140E-06 320750 + 153 320751 Ge-75m 1.12200E-07 3.65480E-07 320751 + 154 320760 Ge-76 1.47140E-06 1.18170E-05 32076.82c + 155 320770 Ge-77 6.16360E-06 9.06130E-06 320770 + 156 320771 Ge-77m 9.42230E-07 1.52510E-05 320771 + 157 320780 Ge-78 2.57240E-05 3.76930E-05 320780 + 158 320790 Ge-79 1.83840E-06 4.89340E-06 320790 + 159 320791 Ge-79m 1.20260E-05 1.20300E-05 320791 + 160 320800 Ge-80 6.65730E-05 7.22330E-05 320800 + 161 320810 Ge-81 8.46310E-05 8.53970E-05 320810 + 162 320811 Ge-81m 1.95690E-05 2.00750E-05 320811 + 163 320820 Ge-82 1.02770E-04 1.02870E-04 320820 + 164 320830 Ge-83 1.56760E-05 1.56860E-05 320830 + 165 320840 Ge-84 2.44560E-06 2.44570E-06 320840 + 166 320850 Ge-85 1.65230E-07 1.65230E-07 320850 + 167 320860 Ge-86 8.17160E-09 8.17160E-09 320860 + 168 320870 Ge-87 1.07780E-10 1.07780E-10 320870 + 169 330740 As-74 2.11450E-12 2.11450E-12 330740 + 170 330750 As-75 4.06000E-11 6.46170E-06 33075.82c + 171 330751 As-75m 1.32830E-10 2.42470E-10 330751 + 172 330760 As-76 6.00290E-09 6.00290E-09 330760 + 173 330770 As-77 1.41550E-07 2.15570E-05 330770 + 174 330780 As-78 1.38240E-06 3.90760E-05 330780 + 175 330790 As-79 1.88980E-05 3.53400E-05 330790 + 176 330800 As-80 1.32810E-04 2.05040E-04 330800 + 177 330810 As-81 1.03880E-04 2.09150E-04 330810 + 178 330820 As-82 1.69960E-05 1.19870E-04 330820 + 179 330821 As-82m 5.12880E-05 5.12880E-05 330821 + 180 330830 As-83 1.73800E-04 1.89750E-04 330830 + 181 330840 As-84 3.75710E-05 3.86730E-05 330840 + 182 330841 As-84m 3.75710E-05 3.86730E-05 330841 + 183 330850 As-85 5.58860E-05 5.60280E-05 330850 + 184 330860 As-86 8.63210E-06 8.64030E-06 330860 + 185 330870 As-87 8.85190E-07 8.85300E-07 330870 + 186 330880 As-88 4.73350E-08 4.73350E-08 330880 + 187 330890 As-89 1.85190E-09 1.85190E-09 330890 + 188 340760 Se-76 1.85130E-12 6.00480E-09 34076.82c + 189 340770 Se-77 1.97390E-11 2.15570E-05 34077.82c + 190 340771 Se-77m 1.29120E-10 1.29120E-10 340771 + 191 340780 Se-78 7.59810E-09 3.90830E-05 34078.82c + 192 340790 Se-79 4.45320E-08 3.53720E-05 34079.82c + 193 340791 Se-79m 6.80770E-09 3.45090E-05 340791 + 194 340800 Se-80 5.29030E-06 2.10330E-04 34080.82c + 195 340810 Se-81 9.16600E-06 2.78240E-04 340810 + 196 340811 Se-81m 5.99590E-05 6.74670E-05 340811 + 197 340820 Se-82 2.37700E-04 4.08850E-04 34082.82c + 198 340830 Se-83 7.28060E-04 7.96430E-04 340830 + 199 340831 Se-83m 1.68350E-04 2.89840E-04 340831 + 200 340840 Se-84 1.08940E-03 1.17900E-03 340840 + 201 340850 Se-85 1.17950E-03 1.22610E-03 340850 + 202 340860 Se-86 8.29140E-04 8.35060E-04 340860 + 203 340870 Se-87 2.96470E-04 2.97220E-04 340870 + 204 340880 Se-88 7.03600E-05 7.04070E-05 340880 + 205 340890 Se-89 8.14860E-06 8.15040E-06 340890 + 206 340900 Se-90 5.91980E-07 5.91980E-07 340900 + 207 340910 Se-91 1.61380E-08 1.61380E-08 340910 + 208 340920 Se-92 4.62760E-10 4.62760E-10 340920 + 209 350790 Br-79 4.40860E-12 1.93440E-08 35079.82c + 210 350791 Br-79m 1.44230E-11 1.44230E-11 350791 + 211 350800 Br-80 1.50320E-09 6.03940E-09 350800 + 212 350801 Br-80m 4.53620E-09 4.53620E-09 350801 + 213 350810 Br-81 1.87600E-07 2.78460E-04 35081.82c + 214 350820 Br-82 1.89100E-06 2.67900E-06 350820 + 215 350821 Br-82m 8.07360E-07 8.07360E-07 350821 + 216 350830 Br-83 3.45730E-05 1.12080E-03 350830 + 217 350840 Br-84 1.48510E-04 1.32750E-03 350840 + 218 350841 Br-84m 1.48510E-04 1.48510E-04 350841 + 219 350850 Br-85 7.81120E-04 2.00720E-03 350850 + 220 350860 Br-86 1.00270E-03 1.83780E-03 350860 + 221 350870 Br-87 1.03680E-03 1.33470E-03 350870 + 222 350880 Br-88 7.41170E-04 8.11520E-04 350880 + 223 350890 Br-89 6.45500E-04 6.53010E-04 350890 + 224 350900 Br-90 2.26420E-04 2.27020E-04 350900 + 225 350910 Br-91 8.41790E-05 8.41920E-05 350910 + 226 350920 Br-92 2.36890E-06 2.36940E-06 350920 + 227 350930 Br-93 1.37400E-05 1.37400E-05 350930 + 228 350940 Br-94 3.19750E-09 3.19750E-09 350940 + 229 360810 Kr-81 4.75780E-11 5.48510E-11 360810 + 230 360811 Kr-81m 7.27320E-12 7.27320E-12 360811 + 231 360820 Kr-82 4.08020E-09 2.70250E-06 36082.82c + 232 360830 Kr-83 2.01600E-07 1.12110E-03 36083.82c + 233 360831 Kr-83m 4.66140E-08 1.11990E-03 360831 + 234 360840 Kr-84 3.76150E-05 1.51360E-03 36084.82c + 235 360850 Kr-85 3.78920E-05 4.71870E-04 36085.82c + 236 360851 Kr-85m 8.76160E-06 2.01270E-03 360851 + 237 360860 Kr-86 8.38000E-04 2.70930E-03 36086.82c + 238 360870 Kr-87 1.92420E-03 3.27980E-03 360870 + 239 360880 Kr-88 4.03600E-03 4.88520E-03 360880 + 240 360890 Kr-89 4.91700E-03 5.53380E-03 360890 + 241 360900 Kr-90 3.88410E-03 4.07210E-03 360900 + 242 360910 Kr-91 1.95950E-03 2.02760E-03 360910 + 243 360920 Kr-92 1.02170E-03 1.03260E-03 360920 + 244 360930 Kr-93 2.66210E-04 2.70610E-04 360930 + 245 360940 Kr-94 7.70940E-05 7.70950E-05 360940 + 246 360950 Kr-95 8.44500E-07 8.44500E-07 360950 + 247 360960 Kr-96 4.89920E-08 4.89920E-08 360960 + 248 360970 Kr-97 1.01900E-09 1.01900E-09 360970 + 249 370830 Rb-83 8.73490E-12 2.98220E-11 370830 + 250 370831 Rb-83m 2.10870E-11 2.10870E-11 370831 + 251 370840 Rb-84 6.07120E-10 1.69920E-09 370840 + 252 370841 Rb-84m 1.09210E-09 1.09210E-09 370841 + 253 370850 Rb-85 8.78140E-08 2.05390E-03 37085.82c + 254 370860 Rb-86 6.99810E-07 1.95860E-06 37086.82c + 255 370861 Rb-86m 1.25880E-06 1.25880E-06 370861 + 256 370870 Rb-87 7.73270E-05 3.35710E-03 37087.82c + 257 370880 Rb-88 2.32760E-04 5.11800E-03 370880 + 258 370890 Rb-89 1.31960E-03 6.85340E-03 370890 + 259 370900 Rb-90 2.83750E-04 3.90260E-03 370900 + 260 370901 Rb-90m 2.52010E-03 3.05270E-03 370901 + 261 370910 Rb-91 3.91470E-03 5.94230E-03 370910 + 262 370920 Rb-92 4.44460E-03 5.47720E-03 370920 + 263 370930 Rb-93 4.33720E-03 4.60870E-03 370930 + 264 370940 Rb-94 1.64820E-03 1.72450E-03 370940 + 265 370950 Rb-95 5.40240E-04 5.41060E-04 370950 + 266 370960 Rb-96 8.00200E-05 1.20060E-04 370960 + 267 370961 Rb-96m 8.00200E-05 8.00440E-05 370961 + 268 370970 Rb-97 1.38460E-05 1.38470E-05 370970 + 269 370980 Rb-98 1.51610E-07 1.51610E-07 370980 + 270 370981 Rb-98m 1.51610E-07 1.51610E-07 370981 + 271 370990 Rb-99 5.93500E-09 5.93500E-09 370990 + 272 380860 Sr-86 8.17150E-10 1.95930E-06 38086.82c + 273 380870 Sr-87 2.99390E-08 3.68400E-08 38087.82c + 274 380871 Sr-87m 6.92250E-09 6.92250E-09 380871 + 275 380880 Sr-88 3.57250E-05 5.15370E-03 38088.82c + 276 380890 Sr-89 8.22110E-05 6.93560E-03 38089.82c + 277 380900 Sr-90 9.38660E-04 7.81460E-03 38090.82c + 278 380910 Sr-91 2.13000E-03 8.07230E-03 380910 + 279 380920 Sr-92 6.74360E-03 1.22850E-02 380920 + 280 380930 Sr-93 9.69290E-03 1.44110E-02 380930 + 281 380940 Sr-94 1.41780E-02 1.57750E-02 380940 + 282 380950 Sr-95 8.21850E-03 8.72910E-03 380950 + 283 380960 Sr-96 8.21680E-03 8.36430E-03 380960 + 284 380970 Sr-97 3.07640E-03 3.08680E-03 380970 + 285 380980 Sr-98 1.08910E-03 1.08940E-03 380980 + 286 380990 Sr-99 1.46780E-04 1.46780E-04 380990 + 287 381000 Sr-100 4.10850E-05 4.10850E-05 381000 + 288 381010 Sr-101 7.39600E-08 7.39600E-08 381010 + 289 381020 Sr-102 2.68880E-09 2.68880E-09 381020 + 290 390880 Y-88 6.42770E-11 1.11650E-10 390880 + 291 390881 Y-88m 4.73730E-11 4.73730E-11 390881 + 292 390890 Y-89 2.22580E-09 6.93560E-03 39089.82c + 293 390891 Y-89m 9.62620E-09 6.78150E-07 390891 + 294 390900 Y-90 7.15180E-06 7.83190E-03 39090.82c + 295 390901 Y-90m 1.01480E-05 1.01480E-05 390901 + 296 390910 Y-91 8.62410E-06 8.11830E-03 39091.82c + 297 390911 Y-91m 3.72980E-05 4.78670E-03 390911 + 298 390920 Y-92 2.33910E-04 1.25190E-02 390920 + 299 390930 Y-93 1.85710E-04 1.58120E-02 390930 + 300 390931 Y-93m 1.21480E-03 4.82110E-03 390931 + 301 390940 Y-94 3.03280E-03 1.88080E-02 390940 + 302 390950 Y-95 6.28300E-03 1.50120E-02 390950 + 303 390960 Y-96 4.30080E-03 1.26660E-02 390960 + 304 390961 Y-96m 7.73620E-03 7.73700E-03 390961 + 305 390970 Y-97 2.53530E-03 5.23820E-03 390970 + 306 390971 Y-97m 8.64140E-03 1.09580E-02 390971 + 307 390972 Y-97m 2.32200E-03 2.32200E-03 390972 + 308 390980 Y-98 2.26350E-03 3.35290E-03 390980 + 309 390981 Y-98m 9.51950E-03 9.51950E-03 390981 + 310 390990 Y-99 4.35270E-03 4.49980E-03 390990 + 311 391000 Y-100 1.01370E-03 1.05440E-03 391000 + 312 391001 Y-100m 1.01370E-03 1.01370E-03 391001 + 313 391010 Y-101 7.67740E-04 7.67810E-04 391010 + 314 391020 Y-102 5.23450E-05 5.23460E-05 391020 + 315 391021 Y-102m 5.23450E-05 5.23460E-05 391021 + 316 391030 Y-103 3.67920E-07 3.67920E-07 391030 + 317 391040 Y-104 7.72330E-09 7.72330E-09 391040 + 318 400910 Zr-91 2.64560E-09 8.11830E-03 40091.82c + 319 400920 Zr-92 2.03620E-07 1.25190E-02 40092.82c + 320 400930 Zr-93 4.81550E-05 1.58600E-02 40093.82c + 321 400940 Zr-94 4.43850E-04 1.92520E-02 40094.82c + 322 400950 Zr-95 1.29830E-03 1.63100E-02 40095.82c + 323 400960 Zr-96 7.78980E-03 2.82010E-02 40096.82c + 324 400970 Zr-97 1.34970E-02 3.04090E-02 400970 + 325 400980 Zr-98 3.37870E-02 4.63990E-02 400980 + 326 400990 Zr-99 2.37690E-02 2.82020E-02 400990 + 327 401000 Zr-100 3.14150E-02 3.34730E-02 401000 + 328 401010 Zr-101 1.55970E-02 1.63700E-02 401010 + 329 401020 Zr-102 7.36610E-03 7.46570E-03 401020 + 330 401030 Zr-103 1.67790E-03 1.67820E-03 401030 + 331 401040 Zr-104 4.78940E-04 4.78950E-04 401040 + 332 401050 Zr-105 4.11950E-05 4.11950E-05 401050 + 333 401060 Zr-106 7.27870E-08 7.27870E-08 401060 + 334 410930 Nb-93 6.86970E-10 8.45820E-10 41093.82c + 335 410931 Nb-93m 1.58850E-10 1.58850E-10 410931 + 336 410940 Nb-94 2.22400E-08 3.78350E-08 41094.82c + 337 410941 Nb-94m 1.56730E-08 1.56730E-08 410941 + 338 410950 Nb-95 3.87400E-06 1.63050E-02 41095.82c + 339 410951 Nb-95m 8.95750E-07 1.77100E-04 410951 + 340 410960 Nb-96 1.01770E-04 1.01770E-04 410960 + 341 410970 Nb-97 5.78530E-04 3.11210E-02 410970 + 342 410971 Nb-97m 1.33770E-04 2.90370E-02 410971 + 343 410980 Nb-98 8.51710E-04 4.72510E-02 410980 + 344 410981 Nb-98m 2.57020E-03 2.57020E-03 410981 + 345 410990 Nb-99 6.26030E-03 2.43200E-02 410990 + 346 410991 Nb-99m 1.44750E-03 1.18260E-02 410991 + 347 411000 Nb-100 3.59670E-03 3.70700E-02 411000 + 348 411001 Nb-100m 1.51260E-02 1.51260E-02 411001 + 349 411010 Nb-101 3.35480E-02 4.99180E-02 411010 + 350 411020 Nb-102 1.43580E-02 2.18230E-02 411020 + 351 411021 Nb-102m 1.43580E-02 1.43580E-02 411021 + 352 411030 Nb-103 2.18440E-02 2.35220E-02 411030 + 353 411040 Nb-104 5.44450E-03 5.92400E-03 411040 + 354 411041 Nb-104m 5.44450E-03 5.44450E-03 411041 + 355 411050 Nb-105 5.26930E-03 5.30990E-03 411050 + 356 411060 Nb-106 1.17120E-03 1.17130E-03 411060 + 357 411070 Nb-107 1.79000E-04 1.79000E-04 411070 + 358 411080 Nb-108 1.75940E-07 1.75940E-07 411080 + 359 411090 Nb-109 3.85710E-09 3.85710E-09 411090 + 360 420960 Mo-96 1.49100E-08 1.01790E-04 42096.82c + 361 420970 Mo-97 2.07650E-05 3.11420E-02 42097.82c + 362 420980 Mo-98 1.67170E-04 4.99880E-02 42098.82c + 363 420990 Mo-99 8.14430E-04 3.67240E-02 42099.82c + 364 421000 Mo-100 5.25500E-03 5.74510E-02 42100.82c + 365 421010 Mo-101 1.39680E-02 6.38860E-02 421010 + 366 421020 Mo-102 3.30100E-02 6.91910E-02 421020 + 367 421030 Mo-103 3.82500E-02 6.17790E-02 421030 + 368 421040 Mo-104 5.31790E-02 6.46310E-02 421040 + 369 421050 Mo-105 4.24610E-02 4.77330E-02 421050 + 370 421060 Mo-106 2.39510E-02 2.50800E-02 421060 + 371 421070 Mo-107 6.58980E-03 6.75810E-03 421070 + 372 421080 Mo-108 2.47850E-03 2.47870E-03 421080 + 373 421090 Mo-109 5.04790E-04 5.04790E-04 421090 + 374 421100 Mo-110 7.40180E-05 7.40180E-05 421100 + 375 421110 Mo-111 1.83180E-08 1.83180E-08 421110 + 376 430980 Tc-98 2.37810E-09 2.37810E-09 430980 + 377 430990 Tc-99 8.75630E-08 3.67230E-02 43099.82c + 378 430991 Tc-99m 2.02470E-08 3.23390E-02 430991 + 379 431000 Tc-100 3.08080E-05 3.08080E-05 431000 + 380 431010 Tc-101 4.44070E-04 6.43300E-02 431010 + 381 431020 Tc-102 8.57950E-04 7.00490E-02 431020 + 382 431021 Tc-102m 8.57950E-04 8.57950E-04 431021 + 383 431030 Tc-103 6.47240E-03 6.82510E-02 431030 + 384 431040 Tc-104 1.42430E-02 7.88750E-02 431040 + 385 431050 Tc-105 3.56890E-02 8.34220E-02 431050 + 386 431060 Tc-106 3.05940E-02 5.56740E-02 431060 + 387 431070 Tc-107 2.68470E-02 3.36050E-02 431070 + 388 431080 Tc-108 1.58070E-02 1.82880E-02 431080 + 389 431090 Tc-109 1.09160E-02 1.14180E-02 431090 + 390 431100 Tc-110 3.36650E-03 3.44050E-03 431100 + 391 431110 Tc-111 1.08870E-03 1.08870E-03 431110 + 392 431120 Tc-112 1.03650E-04 1.03650E-04 431120 + 393 431130 Tc-113 2.71730E-05 2.71730E-05 431130 + 394 431140 Tc-114 1.82620E-10 1.82620E-10 431140 + 395 441010 Ru-101 4.01490E-08 6.43300E-02 44101.82c + 396 441020 Ru-102 5.81500E-05 7.09650E-02 44102.82c + 397 441030 Ru-103 8.68860E-05 6.85480E-02 44103.82c + 398 441031 Ru-103m 2.09750E-04 2.09750E-04 441031 + 399 441040 Ru-104 1.66850E-03 8.05430E-02 44104.82c + 400 441050 Ru-105 6.00390E-03 8.94260E-02 44105.82c + 401 441060 Ru-106 1.47700E-02 7.04440E-02 44106.82c + 402 441070 Ru-107 1.88400E-02 5.24450E-02 441070 + 403 441080 Ru-108 2.88120E-02 4.71090E-02 441080 + 404 441090 Ru-109 2.91850E-02 4.05950E-02 441090 + 405 441100 Ru-110 2.04950E-02 2.39340E-02 441100 + 406 441110 Ru-111 1.13920E-02 1.24820E-02 441110 + 407 441120 Ru-112 5.11330E-03 5.21730E-03 441120 + 408 441130 Ru-113 2.87040E-04 4.55780E-04 441130 + 409 441131 Ru-113m 2.87040E-04 2.87040E-04 441131 + 410 441140 Ru-114 8.22370E-05 8.22370E-05 441140 + 411 441150 Ru-115 4.63390E-08 4.63390E-08 441150 + 412 441160 Ru-116 3.25320E-10 3.25320E-10 441160 + 413 451030 Rh-103 7.42930E-10 6.85480E-02 45103.82c + 414 451031 Rh-103m 4.85990E-09 6.77270E-02 451031 + 415 451040 Rh-104 2.97440E-06 1.19380E-05 451040 + 416 451041 Rh-104m 8.97560E-06 8.97560E-06 451041 + 417 451050 Rh-105 1.07230E-04 8.95500E-02 45105.82c + 418 451051 Rh-105m 1.63920E-05 2.54020E-02 451051 + 419 451060 Rh-106 1.33180E-04 7.05780E-02 451060 + 420 451061 Rh-106m 3.11930E-04 3.11930E-04 451061 + 421 451070 Rh-107 1.01500E-03 5.34600E-02 451070 + 422 451080 Rh-108 6.14680E-04 4.77240E-02 451080 + 423 451081 Rh-108m 1.85490E-03 1.85490E-03 451081 + 424 451090 Rh-109 7.14230E-03 4.77380E-02 451090 + 425 451100 Rh-110 8.27410E-03 3.22080E-02 451100 + 426 451101 Rh-110m 2.20870E-04 2.20870E-04 451101 + 427 451110 Rh-111 1.28910E-02 2.53730E-02 451110 + 428 451120 Rh-112 4.99040E-03 1.02080E-02 451120 + 429 451121 Rh-112m 4.99040E-03 4.99040E-03 451121 + 430 451130 Rh-113 3.92480E-03 4.52410E-03 451130 + 431 451140 Rh-114 8.09450E-04 8.91690E-04 451140 + 432 451141 Rh-114m 8.09450E-04 8.09450E-04 451141 + 433 451150 Rh-115 6.10540E-04 6.10590E-04 451150 + 434 451160 Rh-116 4.78570E-05 4.78570E-05 451160 + 435 451161 Rh-116m 1.12090E-04 1.12090E-04 451161 + 436 451170 Rh-117 8.96420E-09 8.96420E-09 451170 + 437 451180 Rh-118 6.06060E-11 6.06060E-11 451180 + 438 451190 Rh-119 1.99090E-12 1.99090E-12 451190 + 439 461060 Pd-106 6.73970E-08 7.08890E-02 46106.82c + 440 461070 Pd-107 6.21320E-06 5.34780E-02 46107.82c + 441 461071 Pd-107m 1.16770E-05 1.16770E-05 461071 + 442 461080 Pd-108 5.31380E-05 4.96320E-02 46108.82c + 443 461090 Pd-109 1.22480E-04 4.80900E-02 461090 + 444 461091 Pd-109m 2.30170E-04 2.40990E-02 461091 + 445 461100 Pd-110 1.22080E-03 3.36500E-02 46110.82c + 446 461110 Pd-111 8.81200E-04 2.74360E-02 461110 + 447 461111 Pd-111m 1.65610E-03 1.75760E-03 461111 + 448 461120 Pd-112 4.20230E-03 1.94000E-02 461120 + 449 461130 Pd-113 8.54210E-04 7.44050E-03 461130 + 450 461131 Pd-113m 2.06220E-03 2.06220E-03 461131 + 451 461140 Pd-114 2.32360E-03 4.02470E-03 461140 + 452 461150 Pd-115 5.15460E-04 1.12200E-03 461150 + 453 461151 Pd-115m 9.68740E-04 1.05740E-03 461151 + 454 461160 Pd-116 3.33190E-04 4.93140E-04 461160 + 455 461170 Pd-117 1.23420E-05 3.55460E-05 461170 + 456 461171 Pd-117m 2.31950E-05 2.31950E-05 461171 + 457 461180 Pd-118 1.55700E-07 1.55760E-07 461180 + 458 461190 Pd-119 1.33090E-08 1.33110E-08 461190 + 459 461200 Pd-120 6.50120E-10 6.50120E-10 461200 + 460 461210 Pd-121 1.79310E-11 1.79310E-11 461210 + 461 461230 Pd-123 8.24970E-09 8.24970E-09 461230 + 462 461240 Pd-124 1.60400E-09 1.60400E-09 461240 + 463 471080 Ag-108 1.38530E-09 1.66760E-09 471080 + 464 471081 Ag-108m 3.24460E-09 3.24460E-09 471081 + 465 471090 Ag-109 3.15360E-08 4.80910E-02 47109.82c + 466 471091 Ag-109m 2.06290E-07 4.80670E-02 471091 + 467 471100 Ag-110 1.19050E-06 1.22850E-06 471100 + 468 471101 Ag-110m 2.78860E-06 2.78860E-06 47510.82c + 469 471110 Ag-111 7.13470E-06 2.78260E-02 47111.82c + 470 471111 Ag-111m 4.66710E-05 2.76270E-02 471111 + 471 471120 Ag-112 1.28160E-04 1.95290E-02 471120 + 472 471130 Ag-113 2.12090E-05 4.98560E-03 471130 + 473 471131 Ag-113m 1.38740E-04 7.26360E-03 471131 + 474 471140 Ag-114 3.39090E-05 4.20130E-03 471140 + 475 471141 Ag-114m 1.42610E-04 1.42610E-04 471141 + 476 471150 Ag-115 4.42340E-05 1.19190E-03 471150 + 477 471151 Ag-115m 2.89360E-04 1.56510E-03 471151 + 478 471160 Ag-116 3.26910E-05 5.30420E-04 471160 + 479 471161 Ag-116m 7.65690E-05 7.65690E-05 471161 + 480 471170 Ag-117 1.14860E-05 3.48330E-05 471170 + 481 471171 Ag-117m 7.51330E-05 9.29050E-05 471171 + 482 471180 Ag-118 5.54110E-06 1.52380E-05 471180 + 483 471181 Ag-118m 2.33040E-05 2.33260E-05 471181 + 484 471190 Ag-119 3.02330E-07 3.08980E-07 471190 + 485 471191 Ag-119m 1.97770E-06 1.98430E-06 471191 + 486 471200 Ag-120 1.41330E-07 2.15970E-07 471200 + 487 471201 Ag-120m 2.00540E-07 2.00870E-07 471201 + 488 471210 Ag-121 5.14640E-08 5.14820E-08 471210 + 489 471220 Ag-122 3.64300E-10 3.64300E-10 471220 + 490 471221 Ag-122m 3.28160E-10 3.28160E-10 471221 + 491 471230 Ag-123 1.16120E-06 1.16950E-06 471230 + 492 471240 Ag-124 3.56750E-07 5.19030E-07 471240 + 493 471241 Ag-124m 3.21350E-07 3.21350E-07 471241 + 494 471250 Ag-125 3.00390E-07 3.00390E-07 471250 + 495 471260 Ag-126 7.10540E-08 7.10540E-08 471260 + 496 471270 Ag-127 7.96850E-09 7.96850E-09 471270 + 497 471280 Ag-128 4.05640E-10 4.05640E-10 471280 + 498 481100 Cd-110 1.26380E-09 3.97670E-06 48110.82c + 499 481110 Cd-111 7.07540E-09 2.79640E-02 48111.82c + 500 481111 Cd-111m 2.31490E-08 2.31490E-08 481111 + 501 481120 Cd-112 8.38280E-07 1.95290E-02 48112.82c + 502 481130 Cd-113 3.15570E-06 7.51750E-03 48113.82c + 503 481131 Cd-113m 1.03240E-05 9.65190E-05 481131 + 504 481140 Cd-114 3.69640E-05 4.23820E-03 48114.82c + 505 481150 Cd-115 1.83930E-05 2.34210E-03 481150 + 506 481151 Cd-115m 6.01770E-05 1.64860E-04 48515.82c + 507 481160 Cd-116 1.30930E-04 7.33330E-04 48116.82c + 508 481170 Cd-117 1.40670E-05 1.08700E-04 481170 + 509 481171 Cd-117m 4.60220E-05 7.35510E-05 481171 + 510 481180 Cd-118 2.35730E-05 5.25740E-05 481180 + 511 481190 Cd-119 7.19920E-06 9.33800E-06 481190 + 512 481191 Cd-119m 1.73800E-05 1.75340E-05 481191 + 513 481200 Cd-120 1.65210E-05 1.68630E-05 481200 + 514 481210 Cd-121 2.07190E-06 2.11800E-06 481210 + 515 481211 Cd-121m 5.00190E-06 5.00730E-06 481211 + 516 481220 Cd-122 4.84070E-07 4.84760E-07 481220 + 517 481230 Cd-123 3.08600E-06 4.04310E-06 481230 + 518 481231 Cd-123m 7.45000E-06 7.66290E-06 481231 + 519 481240 Cd-124 2.69620E-05 2.76410E-05 481240 + 520 481250 Cd-125 9.70350E-06 9.85370E-06 481250 + 521 481251 Cd-125m 2.34260E-05 2.35760E-05 481251 + 522 481260 Cd-126 3.89720E-05 3.90430E-05 481260 + 523 481270 Cd-127 1.32490E-05 1.32570E-05 481270 + 524 481280 Cd-128 3.44110E-06 3.44150E-06 481280 + 525 481290 Cd-129 5.58180E-08 5.58180E-08 481290 + 526 481291 Cd-129m 1.34750E-07 1.34750E-07 481291 + 527 481300 Cd-130 1.39120E-08 1.39120E-08 481300 + 528 491130 In-113 8.00550E-10 9.63850E-05 49113.82c + 529 491131 In-113m 1.85110E-10 1.85110E-10 491131 + 530 491140 In-114 5.45440E-09 2.13360E-08 491140 + 531 491141 In-114m 8.36020E-09 1.64570E-08 491141 + 532 491142 In-114m 8.09720E-09 8.09720E-09 491142 + 533 491150 In-115 3.20290E-07 2.39020E-03 49115.82c + 534 491151 In-115m 7.40590E-08 2.34220E-03 491151 + 535 491160 In-116 3.10430E-07 3.10430E-07 491160 + 536 491161 In-116m 4.75810E-07 9.36650E-07 491161 + 537 491162 In-116m 4.60840E-07 4.60840E-07 491162 + 538 491170 In-117 2.04790E-06 1.31230E-04 491170 + 539 491171 In-117m 4.73520E-07 1.01210E-04 491171 + 540 491180 In-118 6.30790E-07 5.32050E-05 491180 + 541 491181 In-118m 9.66830E-07 1.89020E-06 491181 + 542 491182 In-118m 9.36420E-07 9.36420E-07 491182 + 543 491190 In-119 8.73360E-06 2.77250E-05 491190 + 544 491191 In-119m 2.01940E-06 1.04870E-05 491191 + 545 491200 In-120 5.63840E-06 2.25020E-05 491200 + 546 491201 In-120m 5.63840E-06 5.63840E-06 491201 + 547 491202 In-120m 5.63840E-06 5.63840E-06 491202 + 548 491210 In-121 2.38920E-05 2.96960E-05 491210 + 549 491211 In-121m 5.52450E-06 6.92920E-06 491211 + 550 491220 In-122 2.12850E-06 2.61330E-06 491220 + 551 491221 In-122m 1.51010E-06 1.51010E-06 491221 + 552 491222 In-122m 1.51010E-06 1.51010E-06 491222 + 553 491230 In-123 1.23890E-05 2.12100E-05 491230 + 554 491231 In-123m 2.86450E-06 5.74870E-06 491231 + 555 491240 In-124 9.42980E-06 3.70710E-05 491240 + 556 491241 In-124m 8.49420E-06 8.49420E-06 491241 + 557 491250 In-125 7.73470E-05 1.05640E-04 491250 + 558 491251 In-125m 1.78850E-05 2.30220E-05 491251 + 559 491260 In-126 1.57530E-04 1.96580E-04 491260 + 560 491261 In-126m 1.41910E-04 1.41910E-04 491261 + 561 491270 In-127 6.07290E-04 6.07290E-04 491270 + 562 491271 In-127m 1.40420E-04 1.53680E-04 491271 + 563 491280 In-128 1.02560E-04 1.47740E-04 491280 + 564 491281 In-128m 4.17470E-05 4.51880E-05 491281 + 565 491282 In-128m 1.29990E-04 1.29990E-04 491282 + 566 491290 In-129 1.06110E-04 1.06240E-04 491290 + 567 491291 In-129m 2.45340E-05 2.45900E-05 491291 + 568 491300 In-130 1.59680E-05 1.59820E-05 491300 + 569 491301 In-130m 1.78350E-05 1.78350E-05 491301 + 570 491302 In-130m 3.03450E-05 3.03450E-05 491302 + 571 491310 In-131 1.45350E-05 1.46830E-05 491310 + 572 491311 In-131m 1.45350E-05 1.45350E-05 491311 + 573 491312 In-131m 1.45350E-05 1.45350E-05 491312 + 574 491320 In-132 1.33650E-07 1.33650E-07 491320 + 575 491330 In-133 3.79900E-09 4.67740E-09 491330 + 576 491331 In-133m 8.78420E-10 8.78420E-10 491331 + 577 501150 Sn-115 7.73610E-11 1.17110E-04 50115.82c + 578 501160 Sn-116 9.32560E-10 1.24800E-06 50116.82c + 579 501170 Sn-117 1.39790E-09 1.84780E-04 50117.82c + 580 501171 Sn-117m 4.57370E-09 4.51700E-07 501171 + 581 501180 Sn-118 3.06990E-08 5.51390E-05 50118.82c + 582 501190 Sn-119 8.74860E-08 3.79990E-05 50119.82c + 583 501191 Sn-119m 2.86220E-07 2.53330E-05 501191 + 584 501200 Sn-120 2.64560E-06 3.64310E-05 50120.82c + 585 501210 Sn-121 3.33820E-06 4.53800E-05 501210 + 586 501211 Sn-121m 8.05880E-06 1.14230E-05 501211 + 587 501220 Sn-122 7.96940E-06 1.39550E-05 50122.82c + 588 501230 Sn-123 8.00720E-08 1.69720E-06 50123.82c + 589 501231 Sn-123m 3.31680E-08 2.53750E-05 501231 + 590 501240 Sn-124 3.53710E-05 8.09360E-05 50124.82c + 591 501250 Sn-125 4.87430E-05 6.65880E-05 50125.82c + 592 501251 Sn-125m 2.01910E-05 1.31010E-04 501251 + 593 501260 Sn-126 3.70870E-04 7.10410E-04 50126.82c + 594 501270 Sn-127 7.75260E-04 1.01200E-03 501270 + 595 501271 Sn-127m 3.21140E-04 8.44330E-04 501271 + 596 501280 Sn-128 1.15820E-03 4.14860E-03 501280 + 597 501281 Sn-128m 2.71270E-03 2.84270E-03 501281 + 598 501290 Sn-129 9.46100E-04 1.06570E-03 501290 + 599 501291 Sn-129m 2.28400E-03 2.29530E-03 501291 + 600 501300 Sn-130 1.24200E-03 1.28390E-03 501300 + 601 501301 Sn-130m 2.90920E-03 2.93180E-03 501301 + 602 501310 Sn-131 5.83960E-04 6.12110E-04 501310 + 603 501311 Sn-131m 1.40970E-03 1.42490E-03 501311 + 604 501320 Sn-132 5.90370E-04 5.90510E-04 501320 + 605 501330 Sn-133 4.48410E-05 4.48420E-05 501330 + 606 501340 Sn-134 1.94460E-06 1.94460E-06 501340 + 607 501350 Sn-135 4.83220E-08 4.83220E-08 501350 + 608 511180 Sb-118 1.97050E-12 1.97050E-12 511180 + 609 511181 Sb-118m 2.79610E-12 2.79610E-12 511181 + 610 511190 Sb-119 2.34160E-10 3.08590E-10 511190 + 611 511191 Sb-119m 7.44320E-11 7.44320E-11 511191 + 612 511200 Sb-120 2.79090E-09 2.79090E-09 511200 + 613 511201 Sb-120m 3.96020E-09 3.96020E-09 511201 + 614 511210 Sb-121 1.44910E-07 4.80840E-05 51121.82c + 615 511220 Sb-122 6.33920E-06 1.35250E-05 511220 + 616 511221 Sb-122m 7.18580E-06 7.18580E-06 511221 + 617 511230 Sb-123 7.59860E-11 2.70720E-05 51123.82c + 618 511240 Sb-124 2.19460E-09 5.15530E-09 51124.82c + 619 511241 Sb-124m 1.67810E-09 3.94760E-09 511241 + 620 511242 Sb-124m 2.26950E-09 2.26950E-09 511242 + 621 511250 Sb-125 2.32650E-05 2.20860E-04 51125.82c + 622 511260 Sb-126 4.09070E-05 5.06800E-05 51126.82c + 623 511261 Sb-126m 3.02460E-05 6.98030E-05 511261 + 624 511262 Sb-126m 3.95570E-05 3.95570E-05 511262 + 625 511270 Sb-127 1.61420E-04 2.01770E-03 511270 + 626 511280 Sb-128 4.35420E-04 4.61080E-03 511280 + 627 511281 Sb-128m 7.42980E-04 7.42980E-04 511281 + 628 511290 Sb-129 2.15580E-03 4.73880E-03 511290 + 629 511291 Sb-129m 1.31730E-03 2.46500E-03 511291 + 630 511300 Sb-130 4.47440E-03 7.22420E-03 511300 + 631 511301 Sb-130m 4.47440E-03 5.94030E-03 511301 + 632 511310 Sb-131 1.54070E-02 1.74440E-02 511310 + 633 511320 Sb-132 6.09490E-03 6.68540E-03 511320 + 634 511321 Sb-132m 4.49210E-03 4.49210E-03 511321 + 635 511330 Sb-133 7.30880E-03 7.35400E-03 511330 + 636 511340 Sb-134 3.99250E-04 4.00870E-04 511340 + 637 511341 Sb-134m 9.35150E-04 9.35150E-04 511341 + 638 511350 Sb-135 3.34650E-04 3.34690E-04 511350 + 639 511360 Sb-136 6.36360E-06 6.36360E-06 511360 + 640 511370 Sb-137 2.87280E-07 2.87280E-07 511370 + 641 511380 Sb-138 6.65340E-09 6.65340E-09 511380 + 642 521200 Te-120 1.38910E-12 1.38910E-12 52120.82c + 643 521210 Te-121 2.17520E-11 8.48740E-11 521210 + 644 521211 Te-121m 7.11640E-11 7.11640E-11 521211 + 645 521220 Te-122 9.52470E-10 1.31740E-05 52122.82c + 646 521250 Te-125 4.33790E-11 2.20860E-04 52125.82c + 647 521251 Te-125m 1.41920E-10 4.94210E-05 521251 + 648 521260 Te-126 3.06560E-08 1.10740E-04 52126.82c + 649 521270 Te-127 4.15830E-07 2.01110E-03 521270 + 650 521271 Te-127m 1.00390E-06 3.33510E-04 52527.82c + 651 521280 Te-128 1.14810E-04 5.44180E-03 52128.82c + 652 521290 Te-129 1.40630E-04 6.14050E-03 521290 + 653 521291 Te-129m 3.39500E-04 3.17210E-03 52529.82c + 654 521300 Te-130 4.32850E-03 1.74930E-02 52130.82c + 655 521310 Te-131 3.50720E-03 2.16260E-02 521310 + 656 521311 Te-131m 8.46680E-03 9.86340E-03 521311 + 657 521320 Te-132 2.83120E-02 3.94890E-02 52132.82c + 658 521330 Te-133 1.11610E-02 2.21830E-02 521330 + 659 521331 Te-133m 2.69460E-02 2.82170E-02 521331 + 660 521340 Te-134 3.82410E-02 3.96290E-02 521340 + 661 521350 Te-135 1.13040E-02 1.15870E-02 521350 + 662 521360 Te-136 3.69480E-03 3.70020E-03 521360 + 663 521370 Te-137 6.49090E-04 6.49240E-04 521370 + 664 521380 Te-138 8.19360E-05 8.19430E-05 521380 + 665 521390 Te-139 1.68720E-06 1.68720E-06 521390 + 666 521400 Te-140 4.50470E-08 4.50470E-08 521400 + 667 531270 I-127 2.27680E-10 2.01910E-03 53127.82c + 668 531280 I-128 2.59610E-08 2.59610E-08 531280 + 669 531290 I-129 1.00760E-06 7.31520E-03 53129.82c + 670 531300 I-130 1.09830E-05 1.49220E-05 53130.82c + 671 531301 I-130m 4.68910E-06 4.68910E-06 531301 + 672 531310 I-131 4.99410E-04 2.99170E-02 53131.82c + 673 531320 I-132 1.33840E-03 4.16760E-02 531320 + 674 531321 I-132m 9.86410E-04 9.86410E-04 531321 + 675 531330 I-133 6.98720E-03 5.67190E-02 531330 + 676 531331 I-133m 4.26980E-03 4.26980E-03 531331 + 677 531340 I-134 1.45950E-02 6.47320E-02 531340 + 678 531341 I-134m 1.07560E-02 1.07560E-02 531341 + 679 531350 I-135 4.99230E-02 6.15100E-02 53135.82c + 680 531360 I-136 8.86560E-03 1.25760E-02 531360 + 681 531361 I-136m 2.07650E-02 2.07750E-02 531361 + 682 531370 I-137 2.02350E-02 2.08700E-02 531370 + 683 531380 I-138 5.74450E-03 5.82130E-03 531380 + 684 531390 I-139 2.09810E-03 2.09980E-03 531390 + 685 531400 I-140 2.58490E-04 2.58540E-04 531400 + 686 531410 I-141 5.33110E-06 5.33110E-06 531410 + 687 531420 I-142 1.24950E-07 1.24950E-07 531420 + 688 531430 I-143 3.05550E-09 3.05550E-09 531430 + 689 541290 Xe-129 5.78560E-11 2.47140E-10 54129.82c + 690 541291 Xe-129m 1.89290E-10 1.89290E-10 541291 + 691 541300 Xe-130 2.05350E-08 1.56920E-05 54130.82c + 692 541310 Xe-131 3.10270E-07 2.99190E-02 54131.82c + 693 541311 Xe-131m 7.49030E-07 3.25710E-04 541311 + 694 541320 Xe-132 3.60280E-05 4.18910E-02 54132.82c + 695 541321 Xe-132m 4.08390E-05 4.08390E-05 541321 + 696 541330 Xe-133 1.51270E-04 5.72350E-02 54133.82c + 697 541331 Xe-133m 3.65190E-04 1.97960E-03 541331 + 698 541340 Xe-134 9.99360E-04 6.83200E-02 54134.82c + 699 541341 Xe-134m 2.34070E-03 2.58810E-03 541341 + 700 541350 Xe-135 3.75090E-03 7.42010E-02 54135.82c + 701 541351 Xe-135m 9.05510E-03 1.92100E-02 541351 + 702 541360 Xe-136 4.08960E-02 7.56030E-02 54136.82c + 703 541370 Xe-137 5.32370E-02 7.30590E-02 541370 + 704 541380 Xe-138 6.45060E-02 7.02240E-02 541380 + 705 541390 Xe-139 2.78280E-02 2.97460E-02 541390 + 706 541400 Xe-140 1.33000E-02 1.35360E-02 541400 + 707 541410 Xe-141 3.65620E-03 3.66040E-03 541410 + 708 541420 Xe-142 4.87640E-04 4.87730E-04 541420 + 709 541430 Xe-143 7.07900E-05 7.07920E-05 541430 + 710 541440 Xe-144 1.00400E-06 1.00400E-06 541440 + 711 541450 Xe-145 1.51390E-08 1.51390E-08 541450 + 712 551320 Cs-132 3.95970E-09 3.95970E-09 551320 + 713 551330 Cs-133 3.10270E-07 5.72360E-02 55133.82c + 714 551340 Cs-134 4.83840E-06 8.40430E-06 55134.82c + 715 551341 Cs-134m 3.56590E-06 3.56590E-06 551341 + 716 551350 Cs-135 1.13360E-04 7.44990E-02 55135.82c + 717 551351 Cs-135m 6.92720E-05 6.92720E-05 551351 + 718 551360 Cs-136 5.89880E-04 7.62730E-04 55136.82c + 719 551361 Cs-136m 3.45700E-04 3.45700E-04 551361 + 720 551370 Cs-137 8.64270E-03 8.17020E-02 55137.82c + 721 551380 Cs-138 9.34780E-03 9.03160E-02 551380 + 722 551381 Cs-138m 1.32640E-02 1.32640E-02 551381 + 723 551390 Cs-139 3.32230E-02 6.29690E-02 551390 + 724 551400 Cs-140 2.64930E-02 4.00300E-02 551400 + 725 551410 Cs-141 2.67030E-02 3.03640E-02 551410 + 726 551420 Cs-142 8.79930E-03 9.28600E-03 551420 + 727 551430 Cs-143 3.53510E-03 3.60520E-03 551430 + 728 551440 Cs-144 4.57340E-04 6.86980E-04 551440 + 729 551441 Cs-144m 4.57340E-04 4.57340E-04 551441 + 730 551450 Cs-145 2.13340E-04 2.13350E-04 551450 + 731 551460 Cs-146 2.38600E-05 2.38600E-05 551460 + 732 551470 Cs-147 5.72170E-08 5.72170E-08 551470 + 733 551480 Cs-148 7.55330E-10 7.55330E-10 551480 + 734 561340 Ba-134 2.60320E-09 8.40690E-06 56134.82c + 735 561350 Ba-135 2.26450E-08 7.73140E-08 56135.82c + 736 561351 Ba-135m 5.46690E-08 5.46690E-08 561351 + 737 561360 Ba-136 2.62510E-06 9.44350E-04 56136.82c + 738 561361 Ba-136m 6.14870E-06 6.14870E-06 561361 + 739 561370 Ba-137 4.22980E-05 8.18460E-02 56137.82c + 740 561371 Ba-137m 1.02110E-04 7.72280E-02 561371 + 741 561380 Ba-138 2.63300E-03 9.54690E-02 56138.82c + 742 561390 Ba-139 7.24030E-03 7.02090E-02 561390 + 743 561400 Ba-140 1.91200E-02 5.91500E-02 56140.82c + 744 561410 Ba-141 2.42350E-02 5.45990E-02 561410 + 745 561420 Ba-142 2.98840E-02 3.92290E-02 561420 + 746 561430 Ba-143 2.54350E-02 2.90030E-02 561430 + 747 561440 Ba-144 2.06500E-02 2.15740E-02 561440 + 748 561450 Ba-145 5.59840E-03 5.78460E-03 561450 + 749 561460 Ba-146 1.80530E-03 1.82580E-03 561460 + 750 561470 Ba-147 3.93480E-04 3.93520E-04 561470 + 751 561480 Ba-148 6.15500E-05 6.15510E-05 561480 + 752 561490 Ba-149 3.50350E-07 3.50350E-07 561490 + 753 561500 Ba-150 6.92050E-09 6.92050E-09 561500 + 754 571370 La-137 1.10490E-08 1.10490E-08 571370 + 755 571380 La-138 4.56870E-07 4.56870E-07 57138.82c + 756 571390 La-139 1.01100E-04 7.03100E-02 57139.82c + 757 571400 La-140 3.36580E-04 5.94870E-02 57140.82c + 758 571410 La-141 1.78110E-03 5.63800E-02 571410 + 759 571420 La-142 2.46940E-03 4.16980E-02 571420 + 760 571430 La-143 8.23020E-03 3.72330E-02 571430 + 761 571440 La-144 1.32920E-02 3.48660E-02 571440 + 762 571450 La-145 1.32080E-02 1.89930E-02 571450 + 763 571460 La-146 2.94540E-03 4.77120E-03 571460 + 764 571461 La-146m 5.29810E-03 5.29810E-03 571461 + 765 571470 La-147 5.30670E-03 5.70050E-03 571470 + 766 571480 La-148 1.84640E-03 1.90770E-03 571480 + 767 571490 La-149 6.02410E-04 6.02760E-04 571490 + 768 571500 La-150 1.39300E-04 1.39310E-04 571500 + 769 571510 La-151 2.88320E-05 2.88320E-05 571510 + 770 571520 La-152 2.14850E-08 2.14850E-08 571520 + 771 571530 La-153 2.84570E-10 2.84570E-10 571530 + 772 581390 Ce-139 6.83510E-10 2.33360E-09 581390 + 773 581391 Ce-139m 1.65010E-09 1.65010E-09 581391 + 774 581400 Ce-140 7.43300E-08 5.94870E-02 58140.82c + 775 581410 Ce-141 1.10270E-05 5.63910E-02 58141.82c + 776 581420 Ce-142 2.13240E-04 4.19120E-02 58142.82c + 777 581430 Ce-143 6.35560E-04 3.78690E-02 58143.82c + 778 581440 Ce-144 3.45120E-03 3.83170E-02 58144.82c + 779 581450 Ce-145 5.15000E-03 2.41430E-02 581450 + 780 581460 Ce-146 1.05820E-02 2.06510E-02 581460 + 781 581470 Ce-147 1.06950E-02 1.63960E-02 581470 + 782 581480 Ce-148 1.14590E-02 1.33750E-02 581480 + 783 581490 Ce-149 8.13640E-03 8.73450E-03 581490 + 784 581500 Ce-150 3.26780E-03 3.40330E-03 581500 + 785 581510 Ce-151 7.25190E-04 7.54020E-04 581510 + 786 581520 Ce-152 2.40380E-04 2.40400E-04 581520 + 787 581530 Ce-153 2.35630E-05 2.35630E-05 581530 + 788 581540 Ce-154 1.18750E-07 1.18750E-07 581540 + 789 581550 Ce-155 1.83190E-09 1.83190E-09 581550 + 790 591420 Pr-142 1.48340E-09 4.95800E-09 59142.82c + 791 591421 Pr-142m 3.47460E-09 3.47460E-09 591421 + 792 591430 Pr-143 7.86260E-06 3.78770E-02 59143.82c + 793 591440 Pr-144 1.76050E-06 3.83340E-02 591440 + 794 591441 Pr-144m 1.56350E-05 5.44390E-04 591441 + 795 591450 Pr-145 5.01240E-05 2.41930E-02 591450 + 796 591460 Pr-146 3.09170E-04 2.09600E-02 591460 + 797 591470 Pr-147 1.06400E-03 1.74590E-02 591470 + 798 591480 Pr-148 4.23910E-04 1.37990E-02 591480 + 799 591481 Pr-148m 1.78280E-03 1.78280E-03 591481 + 800 591490 Pr-149 5.62570E-03 1.43600E-02 591490 + 801 591500 Pr-150 4.10070E-03 7.50400E-03 591500 + 802 591510 Pr-151 3.01390E-03 3.76790E-03 591510 + 803 591520 Pr-152 2.06590E-03 2.30640E-03 591520 + 804 591530 Pr-153 8.19510E-04 8.42930E-04 591530 + 805 591540 Pr-154 1.54790E-04 1.54910E-04 591540 + 806 591550 Pr-155 5.86750E-05 5.86770E-05 591550 + 807 591560 Pr-156 1.51400E-07 1.51400E-07 591560 + 808 591570 Pr-157 3.73370E-09 3.73370E-09 591570 + 809 591580 Pr-158 3.68560E-11 3.68560E-11 591580 + 810 601440 Nd-144 1.43420E-09 3.83350E-02 60144.82c + 811 601450 Nd-145 2.78890E-08 2.41930E-02 60145.82c + 812 601460 Nd-146 5.96740E-06 2.09660E-02 60146.82c + 813 601470 Nd-147 3.07550E-05 1.74900E-02 60147.82c + 814 601480 Nd-148 2.44920E-04 1.58270E-02 60148.82c + 815 601490 Nd-149 1.03030E-03 1.53900E-02 601490 + 816 601500 Nd-150 2.53610E-03 1.00400E-02 60150.82c + 817 601510 Nd-151 2.92010E-03 6.68800E-03 601510 + 818 601520 Nd-152 5.23500E-03 7.54140E-03 601520 + 819 601530 Nd-153 3.25720E-03 4.10010E-03 601530 + 820 601540 Nd-154 2.54540E-03 2.70030E-03 601540 + 821 601550 Nd-155 9.19600E-04 9.78280E-04 601550 + 822 601560 Nd-156 2.76850E-04 2.77000E-04 601560 + 823 601570 Nd-157 6.73080E-06 6.73430E-06 601570 + 824 601580 Nd-158 3.98850E-07 3.98890E-07 601580 + 825 601590 Nd-159 5.53520E-09 5.53520E-09 601590 + 826 601600 Nd-160 1.32810E-10 1.32810E-10 601600 + 827 611470 Pm-147 2.36430E-09 1.74900E-02 61147.82c + 828 611480 Pm-148 1.84440E-06 2.06040E-06 61148.82c + 829 611481 Pm-148m 4.32010E-06 4.32010E-06 61548.82c + 830 611490 Pm-149 1.72510E-05 1.54080E-02 61149.82c + 831 611500 Pm-150 1.47150E-05 1.47150E-05 611500 + 832 611510 Pm-151 1.69570E-04 6.85760E-03 61151.82c + 833 611520 Pm-152 5.78890E-05 7.59930E-03 611520 + 834 611521 Pm-152m 1.15600E-04 1.15600E-04 611521 + 835 611522 Pm-152m 1.27860E-04 1.27860E-04 611522 + 836 611530 Pm-153 9.98630E-04 5.09880E-03 611530 + 837 611540 Pm-154 8.26250E-04 3.52660E-03 611540 + 838 611541 Pm-154m 8.26250E-04 8.26250E-04 611541 + 839 611550 Pm-155 1.45400E-03 2.43230E-03 611550 + 840 611560 Pm-156 7.91960E-04 1.06900E-03 611560 + 841 611570 Pm-157 5.65910E-04 5.72640E-04 611570 + 842 611580 Pm-158 8.01850E-05 8.05840E-05 611580 + 843 611590 Pm-159 3.33600E-06 3.34150E-06 611590 + 844 611600 Pm-160 2.46940E-07 2.47070E-07 611600 + 845 611610 Pm-161 5.93380E-09 5.93380E-09 611610 + 846 611620 Pm-162 2.21730E-10 2.21730E-10 611620 + 847 611630 Pm-163 2.04750E-12 2.04750E-12 611630 + 848 621490 Sm-149 5.16750E-10 1.54080E-02 62149.82c + 849 621500 Sm-150 1.38410E-08 1.47290E-05 62150.82c + 850 621510 Sm-151 2.76570E-07 6.85790E-03 62151.82c + 851 621520 Sm-152 1.00930E-05 7.85290E-03 62152.82c + 852 621530 Sm-153 2.43190E-05 5.18180E-03 62153.82c + 853 621531 Sm-153m 5.87100E-05 5.87100E-05 621531 + 854 621540 Sm-154 3.68040E-04 4.72090E-03 62154.82c + 855 621550 Sm-155 6.73110E-04 3.10540E-03 621550 + 856 621560 Sm-156 9.27060E-04 1.99600E-03 621560 + 857 621570 Sm-157 6.00060E-04 1.17270E-03 621570 + 858 621580 Sm-158 6.40260E-04 7.20840E-04 621580 + 859 621590 Sm-159 1.88770E-04 1.92110E-04 621590 + 860 621600 Sm-160 7.56820E-05 7.59280E-05 621600 + 861 621610 Sm-161 2.72070E-06 2.72660E-06 621610 + 862 621620 Sm-162 5.27350E-07 5.27570E-07 621620 + 863 621630 Sm-163 1.65940E-08 1.65960E-08 621630 + 864 621640 Sm-164 5.24550E-10 5.24550E-10 621640 + 865 621650 Sm-165 7.05860E-12 7.05860E-12 621650 + 866 631520 Eu-152 3.90110E-10 8.25220E-10 63152.82c + 867 631521 Eu-152m 9.29150E-11 9.29150E-11 631521 + 868 631522 Eu-152m 4.35100E-10 4.35100E-10 631522 + 869 631530 Eu-153 3.24410E-08 5.18180E-03 63153.82c + 870 631540 Eu-154 3.44310E-07 6.54460E-07 63154.82c + 871 631541 Eu-154m 3.10150E-07 3.10150E-07 631541 + 872 631550 Eu-155 6.91920E-06 3.11230E-03 63155.82c + 873 631560 Eu-156 1.88850E-05 2.01490E-03 63156.82c + 874 631570 Eu-157 6.22780E-05 1.23500E-03 63157.82c + 875 631580 Eu-158 3.99760E-05 7.60820E-04 631580 + 876 631590 Eu-159 5.64770E-05 2.48590E-04 631590 + 877 631600 Eu-160 7.55260E-05 1.51450E-04 631600 + 878 631610 Eu-161 5.32180E-05 5.59450E-05 631610 + 879 631620 Eu-162 3.44770E-05 3.50050E-05 631620 + 880 631630 Eu-163 2.59180E-06 2.60840E-06 631630 + 881 631640 Eu-164 2.46780E-07 2.47300E-07 631640 + 882 631650 Eu-165 1.76880E-08 1.76950E-08 631650 + 883 631660 Eu-166 5.28110E-10 5.28110E-10 631660 + 884 631670 Eu-167 1.19030E-11 1.19030E-11 631670 + 885 641540 Gd-154 1.80750E-10 6.54510E-07 64154.82c + 886 641550 Gd-155 1.10290E-09 3.11230E-03 64155.82c + 887 641551 Gd-155m 2.66260E-09 2.66260E-09 641551 + 888 641560 Gd-156 9.40760E-08 2.01500E-03 64156.82c + 889 641570 Gd-157 9.63430E-07 1.23590E-03 64157.82c + 890 641580 Gd-158 1.99880E-05 7.80810E-04 64158.82c + 891 641590 Gd-159 1.88290E-05 2.67420E-04 641590 + 892 641600 Gd-160 5.65610E-05 2.08020E-04 64160.82c + 893 641610 Gd-161 1.77270E-05 7.36720E-05 641610 + 894 641620 Gd-162 5.16600E-05 8.66650E-05 641620 + 895 641630 Gd-163 2.57570E-05 2.83650E-05 641630 + 896 641640 Gd-164 1.07480E-05 1.09950E-05 641640 + 897 641650 Gd-165 2.14570E-06 2.16340E-06 641650 + 898 641660 Gd-166 3.18880E-07 3.19410E-07 641660 + 899 641670 Gd-167 2.21250E-08 2.21370E-08 641670 + 900 641680 Gd-168 1.13060E-09 1.13060E-09 641680 + 901 641690 Gd-169 2.91310E-11 2.91310E-11 641690 + 902 651570 Tb-157 1.65200E-10 1.65200E-10 651570 + 903 651580 Tb-158 3.90890E-09 4.34630E-09 651580 + 904 651581 Tb-158m 4.40120E-10 4.40120E-10 651581 + 905 651590 Tb-159 4.21440E-08 2.67460E-04 65159.82c + 906 651600 Tb-160 4.18240E-07 4.18240E-07 65160.82c + 907 651610 Tb-161 1.35150E-06 7.50230E-05 651610 + 908 651620 Tb-162 7.03350E-06 9.36980E-05 651620 + 909 651630 Tb-163 1.04520E-05 3.88170E-05 651630 + 910 651640 Tb-164 1.00710E-05 2.10660E-05 651640 + 911 651650 Tb-165 7.99530E-06 1.01590E-05 651650 + 912 651660 Tb-166 2.97200E-06 3.29140E-06 651660 + 913 651670 Tb-167 9.37900E-07 9.60040E-07 651670 + 914 651680 Tb-168 1.37640E-07 1.38770E-07 651680 + 915 651690 Tb-169 1.80320E-08 1.80610E-08 651690 + 916 651700 Tb-170 1.01420E-09 1.01420E-09 651700 + 917 651710 Tb-171 3.88880E-11 3.88880E-11 651710 + 918 661590 Dy-159 8.70290E-12 8.70290E-12 661590 + 919 661600 Dy-160 3.04690E-10 4.18550E-07 66160.82c + 920 661610 Dy-161 3.01620E-09 7.50260E-05 66161.82c + 921 661620 Dy-162 7.91120E-08 9.37770E-05 66162.82c + 922 661630 Dy-163 3.33020E-07 3.91500E-05 66163.82c + 923 661640 Dy-164 1.43460E-06 2.25030E-05 66164.82c + 924 661650 Dy-165 2.42980E-06 1.29520E-05 661650 + 925 661651 Dy-165m 3.71440E-07 3.71440E-07 661651 + 926 661660 Dy-166 4.10260E-06 7.39400E-06 661660 + 927 661670 Dy-167 2.99910E-06 3.95910E-06 661670 + 928 661680 Dy-168 1.79810E-06 1.93690E-06 661680 + 929 661690 Dy-169 6.11600E-07 6.29660E-07 661690 + 930 661700 Dy-170 1.61940E-07 1.62950E-07 661700 + 931 661710 Dy-171 1.83040E-08 1.83430E-08 661710 + 932 661720 Dy-172 1.52820E-09 1.52820E-09 661720 + 933 661730 Dy-173 6.66680E-11 6.66680E-11 661730 + 934 671620 Ho-162 3.65170E-12 8.95480E-12 671620 + 935 671621 Ho-162m 8.55330E-12 8.55330E-12 671621 + 936 671630 Ho-163 2.16670E-10 2.49790E-10 671630 + 937 671631 Ho-163m 3.31220E-11 3.31220E-11 671631 + 938 671640 Ho-164 9.78350E-10 3.26990E-09 671640 + 939 671641 Ho-164m 2.29160E-09 2.29160E-09 671641 + 940 671650 Ho-165 3.14140E-08 1.29910E-05 67165.82c + 941 671660 Ho-166 3.77470E-08 7.43180E-06 671660 + 942 671661 Ho-166m 8.84130E-08 8.84130E-08 671661 + 943 671670 Ho-167 3.97120E-07 4.35630E-06 671670 + 944 671680 Ho-168 2.34650E-07 2.50280E-06 671680 + 945 671681 Ho-168m 3.32970E-07 3.32970E-07 671681 + 946 671690 Ho-169 7.52970E-07 1.38260E-06 671690 + 947 671700 Ho-170 3.29020E-07 3.29020E-07 671700 + 948 671701 Ho-170m 1.40470E-07 3.03430E-07 671701 + 949 671710 Ho-171 2.24340E-07 2.42680E-07 671710 + 950 671720 Ho-172 5.04650E-08 5.19930E-08 671720 + 951 671730 Ho-173 1.06870E-08 1.07540E-08 671730 + 952 671740 Ho-174 1.01750E-09 1.01750E-09 671740 + 953 671750 Ho-175 7.23620E-11 7.23620E-11 671750 + 954 681650 Er-165 1.76460E-11 1.76460E-11 681650 + 955 681660 Er-166 3.70850E-10 7.43210E-06 68166.82c + 956 681670 Er-167 3.01910E-09 4.35970E-06 68167.82c + 957 681671 Er-167m 4.61530E-10 5.21000E-07 681671 + 958 681680 Er-168 2.37930E-08 2.52830E-06 68168.82c + 959 681690 Er-169 8.34840E-08 1.46610E-06 681690 + 960 681700 Er-170 2.16150E-07 8.48600E-07 68170.82c + 961 681710 Er-171 2.40840E-07 4.83520E-07 681710 + 962 681720 Er-172 2.12020E-07 2.64010E-07 681720 + 963 681730 Er-173 1.08650E-07 1.19400E-07 681730 + 964 681740 Er-174 4.53990E-08 4.64160E-08 681740 + 965 681750 Er-175 9.00440E-09 9.07680E-09 681750 + 966 681760 Er-176 1.32520E-09 1.32520E-09 681760 + 967 681770 Er-177 9.11770E-11 9.11770E-11 681770 + 968 691680 Tm-168 1.38940E-11 1.38940E-11 691680 + 969 691690 Tm-169 2.50570E-10 1.46640E-06 691690 + 970 691700 Tm-170 1.88870E-09 1.88870E-09 691700 + 971 691710 Tm-171 9.74140E-09 4.93260E-07 691710 + 972 691720 Tm-172 2.18450E-08 2.85860E-07 691720 + 973 691730 Tm-173 4.50600E-08 1.64460E-07 691730 + 974 691740 Tm-174 4.34660E-08 8.98820E-08 691740 + 975 691750 Tm-175 3.43080E-08 4.33850E-08 691750 + 976 691760 Tm-176 1.26450E-08 1.39700E-08 691760 + 977 691770 Tm-177 3.96250E-09 4.05370E-09 691770 + 978 691780 Tm-178 5.76930E-10 5.76930E-10 691780 + 979 691790 Tm-179 7.47790E-11 7.47790E-11 691790 + 980 701700 Yb-170 1.41490E-12 1.88760E-09 701700 + 981 701710 Yb-171 2.96040E-12 4.93290E-07 701710 + 982 701711 Yb-171m 1.93660E-11 1.93660E-11 701711 + 983 701720 Yb-172 2.52060E-10 2.86110E-07 701720 + 984 701730 Yb-173 1.47120E-09 1.65940E-07 701730 + 985 701740 Yb-174 6.33670E-09 9.62340E-08 701740 + 986 701750 Yb-175 1.06580E-08 5.56720E-08 701750 + 987 701751 Yb-175m 1.62930E-09 3.50360E-08 701751 + 988 701760 Yb-176 6.37170E-09 2.99590E-08 701760 + 989 701761 Yb-176m 1.14610E-08 1.84460E-08 701761 + 990 701770 Yb-177 1.05170E-08 1.70030E-08 701770 + 991 701771 Yb-177m 2.43180E-09 6.48550E-09 701771 + 992 701780 Yb-178 7.71120E-09 8.28810E-09 701780 + 993 701790 Yb-179 2.59850E-09 2.67330E-09 701790 + 994 701800 Yb-180 6.80850E-10 6.80850E-10 701800 + 995 701810 Yb-181 7.61550E-11 7.61550E-11 701810 + 996 711730 Lu-173 1.13320E-12 1.13320E-12 711730 + 997 711740 Lu-174 4.43590E-12 1.47660E-11 711740 + 998 711741 Lu-174m 1.03900E-11 1.03900E-11 711741 + 999 711750 Lu-175 1.41300E-10 5.58130E-08 71175.82c + 1000 711760 Lu-176 3.60960E-10 2.20560E-09 71176.82c + 1001 711761 Lu-176m 2.00670E-10 2.00670E-10 711761 + 1002 711770 Lu-177 1.24920E-09 1.83640E-08 711770 + 1003 711771 Lu-177m 4.88350E-10 4.96240E-10 711771 + 1004 711772 Lu-177m 1.57810E-11 1.57810E-11 711772 + 1005 711780 Lu-178 1.16570E-09 9.45380E-09 711780 + 1006 711781 Lu-178m 1.32140E-09 1.32140E-09 711781 + 1007 711790 Lu-179 2.83490E-09 5.94160E-09 711790 + 1008 711791 Lu-179m 4.33380E-10 3.10670E-09 711791 + 1009 711800 Lu-180 5.81040E-10 1.64010E-09 711800 + 1010 711801 Lu-180m 5.81040E-10 1.26190E-09 711801 + 1011 711802 Lu-180m 8.56320E-10 8.56320E-10 711802 + 1012 711810 Lu-181 9.55680E-10 1.03180E-09 711810 + 1013 711820 Lu-182 2.13020E-10 2.13020E-10 711820 + 1014 711830 Lu-183 4.47380E-11 4.47380E-11 711830 + 1015 711840 Lu-184 4.22080E-12 4.22080E-12 711840 + 1016 721760 Hf-176 1.69500E-12 2.02180E-10 72176.82c + 1017 721770 Hf-177 1.12340E-11 1.87720E-08 72177.82c + 1018 721771 Hf-177m 4.36510E-12 3.96520E-10 721771 + 1019 721772 Hf-177m 1.68740E-13 8.05950E-12 721772 + 1020 721780 Hf-178 3.81780E-11 1.08820E-08 72178.82c + 1021 721781 Hf-178m 6.29880E-11 1.39010E-09 721781 + 1022 721782 Hf-178m 5.68440E-12 5.68440E-12 721782 + 1023 721790 Hf-179 2.23110E-10 6.31360E-09 72179.82c + 1024 721791 Hf-179m 6.96480E-11 6.96480E-11 721791 + 1025 721792 Hf-179m 7.81030E-11 7.81030E-11 721792 + 1026 721800 Hf-180 3.39350E-10 3.64900E-09 72180.82c + 1027 721801 Hf-180m 6.10400E-10 1.03860E-09 721801 + 1028 721810 Hf-181 1.04800E-09 2.07980E-09 721810 + 1029 721820 Hf-182 3.26780E-10 7.86670E-10 721820 + 1030 721821 Hf-182m 5.87790E-10 5.87790E-10 721821 + 1031 721830 Hf-183 4.65360E-10 5.10100E-10 721830 + 1032 721840 Hf-184 6.89480E-11 7.10590E-11 721840 + 1033 721841 Hf-184m 1.24020E-10 1.26130E-10 721841 + 1034 721850 Hf-185 3.78450E-11 3.78450E-11 721850 + 1035 721860 Hf-186 5.50540E-12 5.50540E-12 721860 + 1036 731790 Ta-179 8.67160E-13 1.14270E-12 731790 + 1037 731800 Ta-180 3.98900E-12 3.98900E-12 731800 + 1038 731801 Ta-180m 4.52170E-12 7.74130E-12 731801 + 1039 731810 Ta-181 4.34150E-11 2.12330E-09 73181.82c + 1040 731820 Ta-182 3.44330E-11 4.37290E-10 73182.82c + 1041 731821 Ta-182m 3.51460E-11 4.02860E-10 731821 + 1042 731822 Ta-182m 2.67910E-11 3.67710E-10 731822 + 1043 731830 Ta-183 1.97180E-10 7.07280E-10 731830 + 1044 731840 Ta-184 1.88740E-10 3.85930E-10 731840 + 1045 731850 Ta-185 9.93240E-11 1.85270E-10 731850 + 1046 731851 Ta-185m 4.81060E-11 4.81060E-11 731851 + 1047 731860 Ta-186 5.37880E-11 5.92930E-11 731860 + 1048 731870 Ta-187 1.67300E-11 1.67300E-11 731870 + 1049 731880 Ta-188 2.41630E-12 2.41630E-12 731880 + 1050 741820 W-182 1.14100E-12 4.38430E-10 74182.82c + 1051 741830 W-183 1.54470E-12 7.13880E-10 74183.82c + 1052 741831 W-183m 5.05380E-12 2.91010E-11 741831 + 1053 741840 W-184 2.81600E-11 4.14090E-10 74184.82c + 1054 741850 W-185 1.58070E-11 2.39240E-10 741850 + 1055 741851 W-185m 3.81610E-11 3.81610E-11 741851 + 1056 741860 W-186 5.85830E-11 1.36850E-10 74186.82c + 1057 741861 W-186m 1.88980E-11 1.88980E-11 741861 + 1058 741870 W-187 5.58660E-11 7.25960E-11 741870 + 1059 741880 W-188 3.30440E-11 3.54600E-11 741880 + 1060 741890 W-189 1.10320E-11 1.10320E-11 741890 + 1061 741900 W-190 1.34080E-12 2.86070E-12 741900 + 1062 741901 W-190m 1.51990E-12 1.51990E-12 741901 + 1063 751860 Re-186 1.03320E-12 1.03320E-12 751860 + 1064 751861 Re-186m 1.46610E-12 1.46610E-12 751861 + 1065 751870 Re-187 7.73730E-12 8.03330E-11 75187.82c + 1066 751880 Re-188 3.25800E-12 4.63490E-11 751880 + 1067 751881 Re-188m 7.63100E-12 7.63100E-12 751881 + 1068 751890 Re-189 1.41740E-11 2.52060E-11 751890 + 1069 751900 Re-190 3.09780E-12 8.49930E-12 751900 + 1070 751901 Re-190m 5.57210E-12 5.57210E-12 751901 + 1071 751910 Re-191 4.06870E-12 4.06870E-12 751910 + 1072 761890 Os-189 3.85330E-13 2.68520E-11 761890 + 1073 761891 Os-189m 1.26070E-12 3.85260E-12 761891 + 1074 761900 Os-190 1.95450E-12 1.57010E-11 761900 + 1075 761901 Os-190m 2.21560E-12 5.24680E-12 761901 + 1076 761910 Os-191 3.49070E-12 8.62630E-12 761910 + 1077 761911 Os-191m 1.06690E-12 1.06690E-12 761911 + 1078 761920 Os-192 1.84860E-12 3.68480E-12 761920 + 1079 761921 Os-192m 2.09550E-12 2.09550E-12 761921 + 1080 761930 Os-193 1.99260E-12 1.99260E-12 761930 + + Nuclide 96245.82c -- curium 245 (Cm-245) + + Neutron-induced fission: + + Interpolation region : 1 / 2 + Interpolation energy : 2.53000E-08 MeV + Number of products : 1112 / 1184 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 3.60660E-05 3.60660E-05 1001.82c + 2 10020 H-2 1.10220E-05 1.10220E-05 1002.82c + 3 10030 H-3 1.85000E-04 1.85000E-04 1003.82c + 4 20040 He-4 2.28000E-03 2.28000E-03 2004.82c + 5 190500 K-50 1.18450E-12 1.18450E-12 190500 + 6 200500 Ca-50 8.41660E-12 9.25760E-12 200500 + 7 200510 Ca-51 9.19830E-12 9.19830E-12 200510 + 8 200520 Ca-52 1.03800E-11 1.03800E-11 200520 + 9 200530 Ca-53 3.88800E-12 3.88800E-12 200530 + 10 200540 Ca-54 1.50040E-12 1.50040E-12 200540 + 11 210500 Sc-50 1.17270E-12 1.08090E-11 210500 + 12 210501 Sc-50m 5.00650E-13 9.75820E-12 210501 + 13 210510 Sc-51 9.30650E-12 1.87120E-11 210510 + 14 210520 Sc-52 1.85430E-11 2.98820E-11 210520 + 15 210530 Sc-53 3.67440E-11 3.94660E-11 210530 + 16 210540 Sc-54 2.80140E-11 2.95140E-11 210540 + 17 210550 Sc-55 2.55320E-11 2.55320E-11 210550 + 18 210560 Sc-56 7.46910E-12 7.46910E-12 210560 + 19 210570 Sc-57 2.30990E-12 2.30990E-12 210570 + 20 220520 Ti-52 4.94250E-12 3.48240E-11 220520 + 21 220530 Ti-53 1.77160E-11 5.71820E-11 220530 + 22 220540 Ti-54 6.81300E-11 9.76440E-11 220540 + 23 220550 Ti-55 1.11570E-10 1.37100E-10 220550 + 24 220560 Ti-56 1.78710E-10 1.86940E-10 220560 + 25 220570 Ti-57 1.13280E-10 1.14830E-10 220570 + 26 220580 Ti-58 7.75970E-11 7.75970E-11 220580 + 27 220590 Ti-59 1.78820E-11 1.78820E-11 220590 + 28 220600 Ti-60 3.77980E-12 3.77980E-12 220600 + 29 230540 V-54 4.47520E-12 1.02120E-10 230540 + 30 230550 V-55 3.91100E-11 1.76210E-10 230550 + 31 230560 V-56 1.11000E-10 2.98290E-10 230560 + 32 230570 V-57 3.56760E-10 4.71240E-10 230570 + 33 230580 V-58 4.51570E-10 5.29170E-10 230580 + 34 230590 V-59 5.91440E-10 6.09320E-10 230590 + 35 230600 V-60 2.65090E-10 2.68870E-10 230600 + 36 230610 V-61 1.46290E-10 1.46290E-10 230610 + 37 230620 V-62 2.71910E-11 2.71910E-11 230620 + 38 230630 V-63 4.49310E-12 4.49310E-12 230630 + 39 240560 Cr-56 9.46810E-12 3.09640E-10 240560 + 40 240570 Cr-57 5.84970E-11 9.51190E-10 240570 + 41 240580 Cr-58 3.83600E-10 4.89430E-10 240580 + 42 240590 Cr-59 8.83210E-10 1.49250E-09 240590 + 43 240600 Cr-60 2.04420E-09 2.32180E-09 240600 + 44 240610 Cr-61 2.15820E-09 2.29570E-09 240610 + 45 240620 Cr-62 2.36500E-09 2.39380E-09 240620 + 46 240630 Cr-63 8.53830E-10 8.56750E-10 240630 + 47 240640 Cr-64 3.15420E-10 3.15420E-10 240640 + 48 240650 Cr-65 4.57510E-11 4.57510E-11 240650 + 49 240660 Cr-66 5.79700E-12 5.79700E-12 240660 + 50 250580 Mn-58 7.00780E-12 4.96440E-10 250580 + 51 250590 Mn-59 1.02530E-10 1.59510E-09 250590 + 52 250600 Mn-60 4.45630E-11 2.41190E-09 250600 + 53 250601 Mn-60m 3.95790E-10 3.95790E-10 250601 + 54 250610 Mn-61 2.36120E-09 4.65690E-09 250610 + 55 250620 Mn-62 3.87980E-09 5.07670E-09 250620 + 56 250621 Mn-62m 6.96510E-10 1.89340E-09 250621 + 57 250630 Mn-63 8.77950E-09 9.63620E-09 250630 + 58 250640 Mn-64 6.44080E-09 6.75620E-09 250640 + 59 250650 Mn-65 5.69660E-09 5.74240E-09 250650 + 60 250660 Mn-66 1.61730E-09 1.62310E-09 250660 + 61 250670 Mn-67 4.78240E-10 4.78240E-10 250670 + 62 250680 Mn-68 5.01070E-11 5.01070E-11 250680 + 63 250690 Mn-69 4.89460E-12 4.89460E-12 250690 + 64 260600 Fe-60 1.12480E-11 2.77350E-09 260600 + 65 260610 Fe-61 1.24210E-10 4.78110E-09 260610 + 66 260620 Fe-62 1.32450E-09 8.29460E-09 260620 + 67 260630 Fe-63 4.57970E-09 1.42160E-08 260630 + 68 260640 Fe-64 1.69460E-08 2.37020E-08 260640 + 69 260650 Fe-65 2.70190E-08 3.27610E-08 260650 + 70 260660 Fe-66 4.22170E-08 4.38400E-08 260660 + 71 260670 Fe-67 2.57140E-08 2.61920E-08 260670 + 72 260680 Fe-68 1.69190E-08 1.69700E-08 260680 + 73 260690 Fe-69 3.77760E-09 3.78130E-09 260690 + 74 260700 Fe-70 8.05370E-10 8.05370E-10 260700 + 75 260710 Fe-71 2.57300E-11 2.57300E-11 260710 + 76 260720 Fe-72 1.51200E-12 1.51200E-12 260720 + 77 270620 Co-62 2.34070E-12 8.29700E-09 270620 + 78 270621 Co-62m 5.48260E-12 5.48260E-12 270621 + 79 270630 Co-63 1.64910E-10 1.43810E-08 270630 + 80 270640 Co-64 1.21150E-09 2.49140E-08 270640 + 81 270650 Co-65 1.02620E-08 4.30230E-08 270650 + 82 270660 Co-66 2.83560E-08 7.21960E-08 270660 + 83 270670 Co-67 8.77260E-08 1.13920E-07 270670 + 84 270680 Co-68 5.69240E-08 9.06490E-08 270680 + 85 270681 Co-68m 5.02160E-08 6.74520E-08 270681 + 86 270690 Co-69 1.36670E-07 1.40190E-07 270690 + 87 270700 Co-70 3.10290E-08 3.10290E-08 270700 + 88 270701 Co-70m 3.10290E-08 3.18340E-08 270701 + 89 270710 Co-71 1.27680E-08 1.27940E-08 270710 + 90 270720 Co-72 1.73350E-09 1.73500E-09 270720 + 91 270730 Co-73 8.02500E-10 8.02500E-10 270730 + 92 270740 Co-74 9.03950E-11 9.03950E-11 270740 + 93 270750 Co-75 5.55100E-12 5.55100E-12 270750 + 94 280640 Ni-64 8.75810E-12 2.49230E-08 28064.82c + 95 280650 Ni-65 1.62040E-10 4.31850E-08 280650 + 96 280660 Ni-66 2.63910E-09 7.48350E-08 280660 + 97 280670 Ni-67 1.56160E-08 1.29530E-07 280670 + 98 280680 Ni-68 9.84700E-08 2.24250E-07 280680 + 99 280690 Ni-69 1.10400E-07 2.49180E-07 280690 + 100 280691 Ni-69m 1.10400E-07 1.10400E-07 280691 + 101 280700 Ni-70 6.50670E-07 7.13530E-07 280700 + 102 280710 Ni-71 2.05530E-07 2.18320E-07 280710 + 103 280720 Ni-72 2.17620E-07 2.19350E-07 280720 + 104 280730 Ni-73 1.67830E-07 1.68630E-07 280730 + 105 280740 Ni-74 1.24210E-07 1.24300E-07 280740 + 106 280750 Ni-75 1.69930E-08 1.69990E-08 280750 + 107 280760 Ni-76 2.74850E-09 2.74850E-09 280760 + 108 280770 Ni-77 1.04360E-10 1.04360E-10 280770 + 109 280780 Ni-78 4.41630E-12 4.41630E-12 280780 + 110 290660 Cu-66 4.31340E-12 7.48390E-08 290660 + 111 290670 Cu-67 1.63770E-10 1.29700E-07 290670 + 112 290680 Cu-68 6.55010E-10 2.26190E-07 290680 + 113 290681 Cu-68m 1.53420E-09 1.53420E-09 290681 + 114 290690 Cu-69 2.78910E-08 3.87480E-07 290690 + 115 290700 Cu-70 9.22560E-09 7.86840E-08 290700 + 116 290701 Cu-70m 1.02780E-07 1.38920E-07 290701 + 117 290702 Cu-70m 9.22560E-09 7.22760E-07 290702 + 118 290710 Cu-71 3.16150E-07 5.34470E-07 290710 + 119 290720 Cu-72 3.46620E-07 5.65980E-07 290720 + 120 290730 Cu-73 7.79020E-07 9.47650E-07 290730 + 121 290740 Cu-74 6.28790E-07 7.53360E-07 290740 + 122 290750 Cu-75 3.92300E-06 3.93970E-06 290750 + 123 290760 Cu-76 6.80800E-07 6.82170E-07 290760 + 124 290761 Cu-76m 6.80800E-07 6.82170E-07 290761 + 125 290770 Cu-77 2.13510E-07 2.13610E-07 290770 + 126 290780 Cu-78 2.14330E-08 2.14370E-08 290780 + 127 290790 Cu-79 1.92090E-09 1.92090E-09 290790 + 128 290800 Cu-80 6.37750E-11 6.37750E-11 290800 + 129 300680 Zn-68 4.29170E-12 2.26440E-07 300680 + 130 300690 Zn-69 2.34510E-11 3.87600E-07 300690 + 131 300691 Zn-69m 1.01420E-10 1.01420E-10 300691 + 132 300700 Zn-70 3.39520E-09 8.38160E-07 300700 + 133 300710 Zn-71 2.96870E-08 5.64160E-07 300710 + 134 300711 Zn-71m 1.28390E-07 1.28390E-07 300711 + 135 300720 Zn-72 4.35250E-07 1.00120E-06 300720 + 136 300730 Zn-73 2.31130E-07 2.38970E-06 300730 + 137 300731 Zn-73m 3.15960E-07 1.21090E-06 300731 + 138 300732 Zn-73m 1.78990E-06 1.78990E-06 300732 + 139 300740 Zn-74 9.43190E-06 1.03230E-05 300740 + 140 300750 Zn-75 1.24220E-05 1.62440E-05 300750 + 141 300760 Zn-76 2.85970E-05 2.99410E-05 300760 + 142 300770 Zn-77 7.77030E-06 8.57790E-06 300770 + 143 300771 Zn-77m 1.18790E-06 1.18790E-06 300771 + 144 300780 Zn-78 1.88830E-05 1.89060E-05 300780 + 145 300790 Zn-79 4.47290E-06 4.47380E-06 300790 + 146 300800 Zn-80 3.87050E-07 3.87110E-07 300800 + 147 300810 Zn-81 2.46110E-08 2.46110E-08 300810 + 148 300820 Zn-82 1.55730E-09 1.55730E-09 300820 + 149 300830 Zn-83 4.29000E-11 4.29000E-11 300830 + 150 310700 Ga-70 1.47780E-12 1.47780E-12 310700 + 151 310710 Ga-71 4.05610E-11 6.92590E-07 310710 + 152 310720 Ga-72 6.35020E-10 1.00190E-06 310720 + 153 310721 Ga-72m 7.15000E-11 3.34330E-08 310721 + 154 310730 Ga-73 4.17430E-08 3.32640E-06 310730 + 155 310740 Ga-74 3.14390E-07 8.29260E-06 310740 + 156 310741 Ga-74m 3.14390E-07 1.06370E-05 310741 + 157 310750 Ga-75 3.26890E-06 1.95130E-05 310750 + 158 310760 Ga-76 6.80780E-06 3.67490E-05 310760 + 159 310770 Ga-77 4.70260E-05 5.61980E-05 310770 + 160 310780 Ga-78 3.43290E-05 5.32930E-05 310780 + 161 310790 Ga-79 4.65310E-05 5.09470E-05 310790 + 162 310800 Ga-80 1.66100E-05 1.69990E-05 310800 + 163 310810 Ga-81 1.43100E-05 1.43330E-05 310810 + 164 310820 Ga-82 1.98080E-06 1.98240E-06 310820 + 165 310830 Ga-83 3.17770E-07 3.17810E-07 310830 + 166 310840 Ga-84 1.51700E-08 1.51700E-08 310840 + 167 310850 Ga-85 5.46940E-10 5.46940E-10 310850 + 168 320730 Ge-73 4.12440E-11 3.32650E-06 32073.82c + 169 320731 Ge-73m 9.53670E-12 3.27760E-06 320731 + 170 320740 Ge-74 4.88790E-09 1.09570E-05 32074.82c + 171 320750 Ge-75 1.13060E-08 1.95980E-05 320750 + 172 320751 Ge-75m 7.39570E-08 8.54490E-07 320751 + 173 320760 Ge-76 6.80740E-06 4.35560E-05 32076.82c + 174 320770 Ge-77 9.71050E-06 2.06700E-05 320770 + 175 320771 Ge-77m 1.48450E-06 5.76820E-05 320771 + 176 320780 Ge-78 6.60560E-05 1.19390E-04 320780 + 177 320790 Ge-79 1.71970E-05 7.25250E-05 320790 + 178 320791 Ge-79m 1.12490E-04 1.12570E-04 320791 + 179 320800 Ge-80 2.95350E-04 3.14050E-04 320800 + 180 320810 Ge-81 2.27470E-04 2.34940E-04 320810 + 181 320811 Ge-81m 5.25970E-05 5.87670E-05 320811 + 182 320820 Ge-82 2.94530E-04 2.96210E-04 320820 + 183 320830 Ge-83 7.92550E-05 7.94660E-05 320830 + 184 320840 Ge-84 3.73910E-05 3.73960E-05 320840 + 185 320850 Ge-85 3.36980E-06 3.37030E-06 320850 + 186 320860 Ge-86 1.86580E-07 1.86580E-07 320860 + 187 320870 Ge-87 5.96610E-09 5.96610E-09 320870 + 188 320880 Ge-88 2.37590E-10 2.37590E-10 320880 + 189 330750 As-75 1.54500E-11 1.95980E-05 33075.82c + 190 330751 As-75m 5.05460E-11 3.06890E-10 330751 + 191 330760 As-76 3.19720E-09 3.19720E-09 330760 + 192 330770 As-77 1.03560E-07 6.74960E-05 330770 + 193 330780 As-78 8.58120E-07 1.20250E-04 330780 + 194 330790 As-79 1.60990E-05 1.96690E-04 330790 + 195 330800 As-80 5.76210E-05 3.71680E-04 330800 + 196 330810 As-81 2.32300E-04 5.25420E-04 330810 + 197 330820 As-82 9.49500E-05 3.91160E-04 330820 + 198 330821 As-82m 2.86530E-04 2.86530E-04 330821 + 199 330830 As-83 7.38500E-04 8.22010E-04 330830 + 200 330840 As-84 2.35300E-04 2.52220E-04 330840 + 201 330841 As-84m 2.35300E-04 2.52220E-04 330841 + 202 330850 As-85 2.95870E-04 2.98770E-04 330850 + 203 330860 As-86 7.54420E-05 7.56290E-05 330860 + 204 330870 As-87 2.38530E-05 2.38590E-05 330870 + 205 330880 As-88 2.04400E-06 2.04420E-06 330880 + 206 330890 As-89 6.00590E-08 6.00590E-08 330890 + 207 330900 As-90 1.31110E-09 1.31110E-09 330900 + 208 340770 Se-77 4.52900E-12 6.74960E-05 34077.82c + 209 340771 Se-77m 2.96260E-11 2.96260E-11 340771 + 210 340780 Se-78 2.87500E-09 1.20260E-04 34078.82c + 211 340790 Se-79 7.75800E-07 1.97480E-04 34079.82c + 212 340791 Se-79m 1.18600E-07 1.92150E-04 340791 + 213 340800 Se-80 7.80630E-06 3.79480E-04 34080.82c + 214 340810 Se-81 5.79180E-06 5.69070E-04 340810 + 215 340811 Se-81m 3.78870E-05 5.67490E-05 340811 + 216 340820 Se-82 2.04050E-04 8.81740E-04 34082.82c + 217 340830 Se-83 5.54250E-04 8.50530E-04 340830 + 218 340831 Se-83m 1.28160E-04 6.54590E-04 340831 + 219 340840 Se-84 1.58840E-03 2.15790E-03 340840 + 220 340850 Se-85 1.87300E-03 2.13100E-03 340850 + 221 340860 Se-86 1.95300E-03 2.00740E-03 340860 + 222 340870 Se-87 1.11770E-03 1.13790E-03 340870 + 223 340880 Se-88 4.67130E-04 4.69170E-04 340880 + 224 340890 Se-89 8.94290E-05 8.94890E-05 340890 + 225 340900 Se-90 1.67600E-05 1.67610E-05 340900 + 226 340910 Se-91 3.76900E-07 3.76900E-07 340910 + 227 340920 Se-92 1.97030E-08 1.97030E-08 340920 + 228 340930 Se-93 5.84910E-10 5.84910E-10 340930 + 229 350790 Br-79 4.36600E-12 1.07620E-07 35079.82c + 230 350791 Br-79m 1.42840E-11 1.42840E-11 350791 + 231 350800 Br-80 2.76650E-10 1.11150E-09 350800 + 232 350801 Br-80m 8.34850E-10 8.34850E-10 350801 + 233 350810 Br-81 6.06330E-08 5.69160E-04 35081.82c + 234 350820 Br-82 3.80690E-06 5.39320E-06 350820 + 235 350821 Br-82m 1.62530E-06 1.62530E-06 350821 + 236 350830 Br-83 1.48360E-05 1.52000E-03 350830 + 237 350840 Br-84 6.59400E-05 2.22380E-03 350840 + 238 350841 Br-84m 6.59400E-05 6.59400E-05 350841 + 239 350850 Br-85 6.23670E-04 2.75470E-03 350850 + 240 350860 Br-86 1.26210E-03 3.26950E-03 350860 + 241 350870 Br-87 2.60270E-03 3.74520E-03 350870 + 242 350880 Br-88 2.49580E-03 2.96730E-03 350880 + 243 350890 Br-89 1.87700E-03 1.95950E-03 350890 + 244 350900 Br-90 6.98010E-04 7.14850E-04 350900 + 245 350910 Br-91 3.17480E-04 3.17780E-04 350910 + 246 350920 Br-92 5.10960E-05 5.11160E-05 350920 + 247 350930 Br-93 7.95730E-06 7.95790E-06 350930 + 248 350940 Br-94 1.24090E-07 1.24090E-07 350940 + 249 350950 Br-95 3.83700E-09 3.83700E-09 350950 + 250 360820 Kr-82 6.48880E-10 5.43290E-06 36082.82c + 251 360830 Kr-83 2.55410E-08 1.52000E-03 36083.82c + 252 360831 Kr-83m 5.90570E-09 1.51860E-03 360831 + 253 360840 Kr-84 2.25590E-06 2.29200E-03 36084.82c + 254 360850 Kr-85 2.64530E-05 6.20780E-04 36085.82c + 255 360851 Kr-85m 6.11650E-06 2.75630E-03 360851 + 256 360860 Kr-86 3.81260E-04 3.74470E-03 36086.82c + 257 360870 Kr-87 1.28660E-03 5.13660E-03 360870 + 258 360880 Kr-88 3.41120E-03 6.45600E-03 360880 + 259 360890 Kr-89 5.28770E-03 7.14680E-03 360890 + 260 360900 Kr-90 6.31950E-03 6.92200E-03 360900 + 261 360910 Kr-91 4.99960E-03 5.27070E-03 360910 + 262 360920 Kr-92 3.36440E-03 3.40400E-03 360920 + 263 360930 Kr-93 1.26460E-03 1.26720E-03 360930 + 264 360940 Kr-94 3.97120E-04 3.97160E-04 360940 + 265 360950 Kr-95 5.15060E-05 5.15100E-05 360950 + 266 360960 Kr-96 5.62380E-06 5.62380E-06 360960 + 267 360970 Kr-97 2.76700E-08 2.76700E-08 360970 + 268 360980 Kr-98 1.27920E-09 1.27920E-09 360980 + 269 370840 Rb-84 5.95620E-11 1.66700E-10 370840 + 270 370841 Rb-84m 1.07140E-10 1.07140E-10 370841 + 271 370850 Rb-85 1.26710E-08 2.78720E-03 37085.82c + 272 370860 Rb-86 3.98000E-07 1.11390E-06 37086.82c + 273 370861 Rb-86m 7.15900E-07 7.15900E-07 370861 + 274 370870 Rb-87 1.58510E-05 5.15250E-03 37087.82c + 275 370880 Rb-88 1.26620E-04 6.58260E-03 370880 + 276 370890 Rb-89 6.92190E-04 7.83900E-03 370890 + 277 370900 Rb-90 1.83080E-04 6.26550E-03 370900 + 278 370901 Rb-90m 1.62600E-03 2.53140E-03 370901 + 279 370910 Rb-91 4.56350E-03 9.83420E-03 370910 + 280 370920 Rb-92 6.40070E-03 9.80470E-03 370920 + 281 370930 Rb-93 8.27690E-03 9.54850E-03 370930 + 282 370940 Rb-94 4.54590E-03 4.94010E-03 370940 + 283 370950 Rb-95 2.45690E-03 2.50710E-03 370950 + 284 370960 Rb-96 3.38600E-04 5.11960E-04 370960 + 285 370961 Rb-96m 3.38600E-04 3.41310E-04 370961 + 286 370970 Rb-97 1.88950E-04 1.88980E-04 370970 + 287 370980 Rb-98 7.39050E-06 7.39050E-06 370980 + 288 370981 Rb-98m 7.39050E-06 7.39170E-06 370981 + 289 370990 Rb-99 3.37020E-06 3.37020E-06 370990 + 290 371000 Rb-100 4.74760E-09 4.74760E-09 371000 + 291 380870 Sr-87 2.65350E-09 3.26530E-09 38087.82c + 292 380871 Sr-87m 6.13560E-10 6.13560E-10 380871 + 293 380880 Sr-88 3.06530E-06 6.58570E-03 38088.82c + 294 380890 Sr-89 2.50830E-05 7.86400E-03 38089.82c + 295 380900 Sr-90 2.52220E-04 8.98340E-03 38090.82c + 296 380910 Sr-91 1.04340E-03 1.08780E-02 380910 + 297 380920 Sr-92 4.46000E-03 1.43980E-02 380920 + 298 380930 Sr-93 1.04250E-02 2.03390E-02 380930 + 299 380940 Sr-94 1.74480E-02 2.21050E-02 380940 + 300 380950 Sr-95 1.41600E-02 1.65200E-02 380950 + 301 380960 Sr-96 1.14590E-02 1.21200E-02 380960 + 302 380970 Sr-97 5.49290E-03 5.63550E-03 380970 + 303 380980 Sr-98 2.36890E-03 2.38320E-03 380980 + 304 380990 Sr-99 5.13780E-04 5.16610E-04 380990 + 305 381000 Sr-100 1.55060E-04 1.55060E-04 381000 + 306 381010 Sr-101 1.55330E-05 1.55330E-05 381010 + 307 381020 Sr-102 2.49030E-06 2.49030E-06 381020 + 308 390890 Y-89 1.40400E-10 7.86400E-03 39089.82c + 309 390891 Y-89m 6.07210E-10 7.58630E-07 390891 + 310 390900 Y-90 1.42730E-08 8.98340E-03 39090.82c + 311 390901 Y-90m 2.02530E-08 2.02530E-08 390901 + 312 390910 Y-91 1.88570E-06 1.08880E-02 39091.82c + 313 390911 Y-91m 8.15530E-06 6.40810E-03 390911 + 314 390920 Y-92 7.15050E-05 1.44700E-02 390920 + 315 390930 Y-93 8.26310E-05 2.09620E-02 390930 + 316 390931 Y-93m 5.40530E-04 5.63010E-03 390931 + 317 390940 Y-94 2.00270E-03 2.41080E-02 390940 + 318 390950 Y-95 6.71940E-03 2.32390E-02 390950 + 319 390960 Y-96 4.10970E-03 1.62310E-02 390960 + 320 390961 Y-96m 7.39230E-03 7.39370E-03 390961 + 321 390970 Y-97 3.14040E-03 8.03180E-03 390970 + 322 390971 Y-97m 1.07040E-02 1.38430E-02 390971 + 323 390972 Y-97m 2.87620E-03 2.87620E-03 390972 + 324 390980 Y-98 2.30080E-03 4.68400E-03 390980 + 325 390981 Y-98m 9.67620E-03 9.67620E-03 390981 + 326 390990 Y-99 8.73690E-03 9.25470E-03 390990 + 327 391000 Y-100 2.17070E-03 2.32470E-03 391000 + 328 391001 Y-100m 2.17070E-03 2.17080E-03 391001 + 329 391010 Y-101 2.09620E-03 2.11150E-03 391010 + 330 391020 Y-102 1.90140E-04 1.91320E-04 391020 + 331 391021 Y-102m 1.90140E-04 1.91320E-04 391021 + 332 391030 Y-103 7.13960E-05 7.13960E-05 391030 + 333 391040 Y-104 8.85440E-06 8.85440E-06 391040 + 334 391050 Y-105 8.26030E-09 8.26030E-09 391050 + 335 400920 Zr-92 9.64250E-07 1.44710E-02 40092.82c + 336 400930 Zr-93 1.59250E-05 2.09780E-02 40093.82c + 337 400940 Zr-94 1.10870E-04 2.42180E-02 40094.82c + 338 400950 Zr-95 6.29390E-04 2.38690E-02 40095.82c + 339 400960 Zr-96 3.48710E-03 2.71230E-02 40096.82c + 340 400970 Zr-97 8.32250E-03 3.10100E-02 400970 + 341 400980 Zr-98 2.05820E-02 3.47540E-02 400980 + 342 400990 Zr-99 2.31040E-02 3.22230E-02 400990 + 343 401000 Zr-100 3.12690E-02 3.57430E-02 401000 + 344 401010 Zr-101 2.13410E-02 2.34710E-02 401010 + 345 401020 Zr-102 1.34980E-02 1.38680E-02 401020 + 346 401030 Zr-103 3.99740E-03 4.06390E-03 401030 + 347 401040 Zr-104 1.26300E-03 1.27110E-03 401040 + 348 401050 Zr-105 1.93070E-04 1.93080E-04 401050 + 349 401060 Zr-106 2.19920E-05 2.19920E-05 401060 + 350 401070 Zr-107 1.88850E-06 1.88850E-06 401070 + 351 410940 Nb-94 1.37340E-09 2.33650E-09 41094.82c + 352 410941 Nb-94m 9.67890E-10 9.67890E-10 410941 + 353 410950 Nb-95 7.61110E-07 2.38550E-02 41095.82c + 354 410951 Nb-95m 1.75990E-07 2.58040E-04 410951 + 355 410960 Nb-96 2.90790E-05 2.90790E-05 410960 + 356 410970 Nb-97 1.87250E-04 3.12410E-02 410970 + 357 410971 Nb-97m 4.32970E-05 2.95180E-02 410971 + 358 410980 Nb-98 2.50370E-04 3.50040E-02 410980 + 359 410981 Nb-98m 7.55530E-04 7.55530E-04 410981 + 360 410990 Nb-99 3.62220E-03 2.42410E-02 410990 + 361 410991 Nb-99m 8.37530E-04 1.26960E-02 410991 + 362 411000 Nb-100 2.24240E-03 3.79850E-02 411000 + 363 411001 Nb-100m 9.43060E-03 9.43060E-03 411001 + 364 411010 Nb-101 2.93610E-02 5.28320E-02 411010 + 365 411020 Nb-102 1.51810E-02 2.90490E-02 411020 + 366 411021 Nb-102m 1.51810E-02 1.51810E-02 411021 + 367 411030 Nb-103 2.75880E-02 3.16520E-02 411030 + 368 411040 Nb-104 7.35600E-03 8.62980E-03 411040 + 369 411041 Nb-104m 7.35600E-03 7.35600E-03 411041 + 370 411050 Nb-105 8.41230E-03 8.60300E-03 411050 + 371 411060 Nb-106 2.09970E-03 2.12140E-03 411060 + 372 411070 Nb-107 6.13660E-04 6.15480E-04 411070 + 373 411080 Nb-108 7.83010E-05 7.83010E-05 411080 + 374 411090 Nb-109 7.95790E-06 7.95790E-06 411090 + 375 411100 Nb-110 3.01310E-09 3.01310E-09 411100 + 376 420960 Mo-96 1.02240E-09 2.90800E-05 42096.82c + 377 420970 Mo-97 4.57350E-06 3.12450E-02 42097.82c + 378 420980 Mo-98 3.39490E-05 3.57940E-02 42098.82c + 379 420990 Mo-99 1.84960E-04 3.68670E-02 42099.82c + 380 421000 Mo-100 1.67240E-03 4.90890E-02 42100.82c + 381 421010 Mo-101 6.23380E-03 5.90660E-02 421010 + 382 421020 Mo-102 2.06980E-02 6.49280E-02 421020 + 383 421030 Mo-103 2.92910E-02 6.09520E-02 421030 + 384 421040 Mo-104 4.37160E-02 5.98390E-02 421040 + 385 421050 Mo-105 3.32460E-02 4.17980E-02 421050 + 386 421060 Mo-106 2.28850E-02 2.49480E-02 421060 + 387 421070 Mo-107 1.02470E-02 1.08300E-02 421070 + 388 421080 Mo-108 4.72710E-03 4.80150E-03 421080 + 389 421090 Mo-109 1.11490E-03 1.12180E-03 421090 + 390 421100 Mo-110 2.52580E-04 2.52580E-04 421100 + 391 421110 Mo-111 2.43280E-05 2.43280E-05 421110 + 392 421120 Mo-112 2.43940E-08 2.43940E-08 421120 + 393 430990 Tc-99 4.64020E-09 3.68660E-02 43099.82c + 394 430991 Tc-99m 1.07290E-09 3.24650E-02 430991 + 395 431000 Tc-100 3.07500E-06 3.07500E-06 431000 + 396 431010 Tc-101 1.00540E-04 5.91670E-02 431010 + 397 431020 Tc-102 2.67650E-04 6.51950E-02 431020 + 398 431021 Tc-102m 2.67650E-04 2.67650E-04 431021 + 399 431030 Tc-103 2.74800E-03 6.37000E-02 431030 + 400 431040 Tc-104 7.55360E-03 6.73930E-02 431040 + 401 431050 Tc-105 2.09690E-02 6.27670E-02 431050 + 402 431060 Tc-106 2.42800E-02 4.92280E-02 431060 + 403 431070 Tc-107 3.07640E-02 4.15940E-02 431070 + 404 431080 Tc-108 2.07060E-02 2.55140E-02 431080 + 405 431090 Tc-109 1.42910E-02 1.54070E-02 431090 + 406 431100 Tc-110 6.41530E-03 6.66810E-03 431100 + 407 431110 Tc-111 2.50380E-03 2.52790E-03 431110 + 408 431120 Tc-112 5.64800E-04 5.64820E-04 431120 + 409 431130 Tc-113 1.04620E-04 1.04620E-04 431130 + 410 431140 Tc-114 6.57270E-06 6.57270E-06 431140 + 411 431150 Tc-115 5.62510E-10 5.62510E-10 431150 + 412 441010 Ru-101 1.66140E-09 5.91670E-02 44101.82c + 413 441020 Ru-102 1.24520E-06 6.54640E-02 44102.82c + 414 441030 Ru-103 1.86680E-05 6.37640E-02 44103.82c + 415 441031 Ru-103m 4.50680E-05 4.50680E-05 441031 + 416 441040 Ru-104 5.17250E-04 6.79100E-02 44104.82c + 417 441050 Ru-105 1.95600E-03 6.47230E-02 44105.82c + 418 441060 Ru-106 6.85360E-03 5.60810E-02 44106.82c + 419 441070 Ru-107 1.32980E-02 5.48920E-02 441070 + 420 441080 Ru-108 2.60720E-02 5.15980E-02 441080 + 421 441090 Ru-109 2.42230E-02 3.96200E-02 441090 + 422 441100 Ru-110 2.54270E-02 3.20930E-02 441100 + 423 441110 Ru-111 1.36910E-02 1.62270E-02 441110 + 424 441120 Ru-112 9.76860E-03 1.03320E-02 441120 + 425 441130 Ru-113 1.20640E-03 1.90710E-03 441130 + 426 441131 Ru-113m 1.20640E-03 1.20640E-03 441131 + 427 441140 Ru-114 5.04780E-04 5.10920E-04 441140 + 428 441150 Ru-115 5.52210E-05 5.52210E-05 441150 + 429 441160 Ru-116 8.12070E-06 8.12070E-06 441160 + 430 441170 Ru-117 2.03420E-06 2.03420E-06 441170 + 431 451040 Rh-104 2.04120E-09 8.19290E-09 451040 + 432 451041 Rh-104m 6.15970E-09 6.15970E-09 451041 + 433 451050 Rh-105 1.72650E-05 6.47430E-02 45105.82c + 434 451051 Rh-105m 2.63930E-06 1.83760E-02 451051 + 435 451060 Rh-106 2.77860E-05 5.61090E-02 451060 + 436 451061 Rh-106m 6.50820E-05 6.50820E-05 451061 + 437 451070 Rh-107 5.33060E-04 5.54260E-02 451070 + 438 451080 Rh-108 4.79160E-04 5.20770E-02 451080 + 439 451081 Rh-108m 1.44590E-03 1.44590E-03 451081 + 440 451090 Rh-109 5.24890E-03 4.48690E-02 451090 + 441 451100 Rh-110 8.86880E-03 4.09610E-02 451100 + 442 451101 Rh-110m 2.36750E-04 2.36750E-04 451101 + 443 451110 Rh-111 1.45480E-02 3.07750E-02 451110 + 444 451120 Rh-112 8.01050E-03 1.83430E-02 451120 + 445 451121 Rh-112m 8.01050E-03 8.01050E-03 451121 + 446 451130 Rh-113 1.24390E-02 1.49490E-02 451130 + 447 451140 Rh-114 2.31900E-03 2.83000E-03 451140 + 448 451141 Rh-114m 2.31900E-03 2.31900E-03 451141 + 449 451150 Rh-115 1.75630E-03 1.81150E-03 451150 + 450 451160 Rh-116 1.05640E-04 1.13720E-04 451160 + 451 451161 Rh-116m 2.47440E-04 2.47440E-04 451161 + 452 451170 Rh-117 9.80720E-05 1.00060E-04 451170 + 453 451180 Rh-118 2.26580E-05 2.26580E-05 451180 + 454 451190 Rh-119 6.49940E-06 6.49940E-06 451190 + 455 451200 Rh-120 3.09870E-06 3.09870E-06 451200 + 456 451210 Rh-121 6.23720E-07 6.23720E-07 451210 + 457 461060 Pd-106 2.10120E-09 5.61740E-02 46106.82c + 458 461070 Pd-107 1.63970E-06 5.54300E-02 46107.82c + 459 461071 Pd-107m 3.08160E-06 3.08160E-06 461071 + 460 461080 Pd-108 6.15640E-05 5.35850E-02 46108.82c + 461 461090 Pd-109 8.36790E-05 4.51100E-02 461090 + 462 461091 Pd-109m 1.57260E-04 2.25920E-02 461091 + 463 461100 Pd-110 1.06470E-03 4.22630E-02 46110.82c + 464 461110 Pd-111 7.50830E-04 3.25230E-02 461110 + 465 461111 Pd-111m 1.41110E-03 1.53420E-03 461111 + 466 461120 Pd-112 5.75340E-03 3.21070E-02 461120 + 467 461130 Pd-113 1.75680E-03 2.09470E-02 461130 + 468 461131 Pd-113m 4.24100E-03 4.24100E-03 461131 + 469 461140 Pd-114 5.67950E-03 1.08280E-02 461140 + 470 461150 Pd-115 1.05310E-03 2.78090E-03 461150 + 471 461151 Pd-115m 1.97920E-03 2.24220E-03 461151 + 472 461160 Pd-116 1.71270E-03 2.07380E-03 461160 + 473 461170 Pd-117 1.81320E-04 6.22810E-04 461170 + 474 461171 Pd-117m 3.40760E-04 3.40760E-04 461171 + 475 461180 Pd-118 2.05400E-04 2.27400E-04 461180 + 476 461190 Pd-119 4.29730E-05 4.96560E-05 461190 + 477 461200 Pd-120 1.98490E-05 2.28490E-05 461200 + 478 461210 Pd-121 2.49520E-06 3.03430E-06 461210 + 479 461220 Pd-122 1.27870E-06 1.27870E-06 461220 + 480 461240 Pd-124 6.96880E-08 6.96880E-08 461240 + 481 471090 Ag-109 2.34500E-07 4.51120E-02 47109.82c + 482 471091 Ag-109m 1.53400E-06 4.50900E-02 471091 + 483 471100 Ag-110 2.99830E-06 3.09380E-06 471100 + 484 471101 Ag-110m 7.02270E-06 7.02270E-06 47510.82c + 485 471110 Ag-111 7.91760E-06 3.28340E-02 47111.82c + 486 471111 Ag-111m 5.17930E-05 3.26400E-02 471111 + 487 471120 Ag-112 2.20720E-04 3.23280E-02 471120 + 488 471130 Ag-113 7.87530E-05 1.41340E-02 471130 + 489 471131 Ag-113m 5.15160E-04 2.05740E-02 471131 + 490 471140 Ag-114 1.57780E-04 1.16500E-02 471140 + 491 471141 Ag-114m 6.63540E-04 6.63540E-04 471141 + 492 471150 Ag-115 1.46140E-04 2.96790E-03 471150 + 493 471151 Ag-115m 9.55960E-04 3.76960E-03 471151 + 494 471160 Ag-116 2.55890E-04 2.36570E-03 471160 + 495 471161 Ag-116m 5.99360E-04 5.99360E-04 471161 + 496 471170 Ag-117 9.00620E-05 4.55500E-04 471170 + 497 471171 Ag-117m 5.89140E-04 9.00540E-04 471171 + 498 471180 Ag-118 6.61550E-05 3.88450E-04 471180 + 499 471181 Ag-118m 2.78230E-04 3.10730E-04 471181 + 500 471190 Ag-119 2.09190E-05 4.57470E-05 471190 + 501 471191 Ag-119m 1.36840E-04 1.61670E-04 471191 + 502 471200 Ag-120 2.07480E-05 4.73010E-05 471200 + 503 471201 Ag-120m 2.94410E-05 4.08650E-05 471201 + 504 471210 Ag-121 3.43130E-05 3.73390E-05 471210 + 505 471220 Ag-122 7.06450E-06 8.34320E-06 471220 + 506 471221 Ag-122m 6.36350E-06 6.36350E-06 471221 + 507 471230 Ag-123 1.50880E-05 1.50880E-05 471230 + 508 471240 Ag-124 9.18200E-06 1.33870E-05 471240 + 509 471241 Ag-124m 8.27100E-06 8.27100E-06 471241 + 510 471250 Ag-125 1.21930E-05 1.21930E-05 471250 + 511 471260 Ag-126 1.56330E-06 1.56330E-06 471260 + 512 471270 Ag-127 1.46420E-07 1.46420E-07 471270 + 513 471280 Ag-128 5.28160E-09 5.28160E-09 471280 + 514 471290 Ag-129 3.40440E-10 3.40440E-10 471290 + 515 481110 Cd-111 2.14300E-10 3.29970E-02 48111.82c + 516 481111 Cd-111m 7.01110E-10 7.01110E-10 481111 + 517 481120 Cd-112 3.22000E-06 3.23310E-02 48112.82c + 518 481130 Cd-113 1.81370E-06 2.12990E-02 48113.82c + 519 481131 Cd-113m 5.93400E-06 2.50300E-04 481131 + 520 481140 Cd-114 5.07500E-05 1.17010E-02 48114.82c + 521 481150 Cd-115 1.89460E-05 5.70710E-03 481150 + 522 481151 Cd-115m 6.19840E-05 3.19700E-04 48515.82c + 523 481160 Cd-116 1.51710E-04 3.08080E-03 48116.82c + 524 481170 Cd-117 3.89870E-05 1.05420E-03 481170 + 525 481171 Cd-117m 1.27550E-04 4.14350E-04 481171 + 526 481180 Cd-118 1.66390E-04 7.38170E-04 481180 + 527 481190 Cd-119 2.69860E-05 2.11530E-04 481190 + 528 481191 Cd-119m 6.51480E-05 8.80220E-05 481191 + 529 481200 Cd-120 9.22420E-05 1.65290E-04 481200 + 530 481210 Cd-121 2.00930E-05 5.35310E-05 481210 + 531 481211 Cd-121m 4.85080E-05 5.24100E-05 481211 + 532 481220 Cd-122 7.48190E-05 8.95260E-05 481220 + 533 481230 Cd-123 2.13990E-05 3.37500E-05 481230 + 534 481231 Cd-123m 5.16610E-05 5.44110E-05 481231 + 535 481240 Cd-124 1.75460E-04 1.92970E-04 481240 + 536 481250 Cd-125 4.07450E-05 4.68420E-05 481250 + 537 481251 Cd-125m 9.83650E-05 1.04460E-04 481251 + 538 481260 Cd-126 1.91760E-04 1.93320E-04 481260 + 539 481270 Cd-127 9.00160E-05 9.01620E-05 481270 + 540 481280 Cd-128 3.77140E-05 3.77190E-05 481280 + 541 481290 Cd-129 2.00540E-06 2.00550E-06 481290 + 542 481291 Cd-129m 4.84120E-06 4.84140E-06 481291 + 543 481300 Cd-130 1.33340E-07 1.33340E-07 481300 + 544 481310 Cd-131 4.26500E-09 4.26500E-09 481310 + 545 491140 In-114 4.85160E-10 1.89780E-09 491140 + 546 491141 In-114m 7.43620E-10 1.46390E-09 491141 + 547 491142 In-114m 7.20230E-10 7.20230E-10 491142 + 548 491150 In-115 4.52300E-08 5.74150E-03 49115.82c + 549 491151 In-115m 1.04580E-08 5.70720E-03 491151 + 550 491160 In-116 6.73450E-07 6.73450E-07 491160 + 551 491161 In-116m 1.03220E-06 2.03200E-06 491161 + 552 491162 In-116m 9.99760E-07 9.99760E-07 491162 + 553 491170 In-117 6.05550E-06 9.60860E-04 491170 + 554 491171 In-117m 1.40020E-06 9.73800E-04 491171 + 555 491180 In-118 4.63580E-06 7.42800E-04 491180 + 556 491181 In-118m 7.10540E-06 1.38910E-05 491181 + 557 491182 In-118m 6.88190E-06 6.88190E-06 491182 + 558 491190 In-119 1.84580E-05 1.37800E-04 491190 + 559 491191 In-119m 4.26790E-06 1.95420E-04 491191 + 560 491200 In-120 6.19340E-06 1.71480E-04 491200 + 561 491201 In-120m 6.19340E-06 6.19340E-06 491201 + 562 491202 In-120m 6.19340E-06 6.19340E-06 491202 + 563 491210 In-121 2.58260E-05 9.67630E-05 491210 + 564 491211 In-121m 5.97170E-06 4.14740E-05 491211 + 565 491220 In-122 1.79680E-05 1.07490E-04 491220 + 566 491221 In-122m 1.27480E-05 1.27480E-05 491221 + 567 491222 In-122m 1.27480E-05 1.27480E-05 491222 + 568 491230 In-123 7.10650E-05 1.35270E-04 491230 + 569 491231 In-123m 1.64320E-05 4.03920E-05 491231 + 570 491240 In-124 6.93500E-05 2.62320E-04 491240 + 571 491241 In-124m 6.24690E-05 6.24690E-05 491241 + 572 491250 In-125 3.44800E-04 4.71690E-04 491250 + 573 491251 In-125m 7.97270E-05 1.04150E-04 491251 + 574 491260 In-126 4.56290E-04 6.49610E-04 491260 + 575 491261 In-126m 4.11010E-04 4.11010E-04 491261 + 576 491270 In-127 1.33390E-03 1.33390E-03 491270 + 577 491271 In-127m 3.08420E-04 3.98590E-04 491271 + 578 491280 In-128 4.08670E-04 6.12750E-04 491280 + 579 491281 In-128m 1.66360E-04 2.04070E-04 491281 + 580 491282 In-128m 5.17970E-04 5.17970E-04 491282 + 581 491290 In-129 6.13230E-04 6.18070E-04 491290 + 582 491291 In-129m 1.41790E-04 1.43800E-04 491291 + 583 491300 In-130 7.61410E-05 7.62700E-05 491300 + 584 491301 In-130m 8.50430E-05 8.50430E-05 491301 + 585 491302 In-130m 1.44690E-04 1.44690E-04 491302 + 586 491310 In-131 2.66910E-05 2.69670E-05 491310 + 587 491311 In-131m 2.66910E-05 2.66910E-05 491311 + 588 491312 In-131m 2.66910E-05 2.66910E-05 491312 + 589 491320 In-132 2.29970E-06 2.29970E-06 491320 + 590 491330 In-133 4.82350E-08 5.93880E-08 491330 + 591 491331 In-133m 1.11530E-08 1.11530E-08 491331 + 592 491340 In-134 1.46360E-09 1.46360E-09 491340 + 593 501160 Sn-116 1.12460E-10 2.70550E-06 50116.82c + 594 501170 Sn-117 5.08180E-10 1.47600E-03 50117.82c + 595 501171 Sn-117m 1.66260E-09 3.27540E-06 501171 + 596 501180 Sn-118 4.61500E-08 7.56840E-04 50118.82c + 597 501190 Sn-119 3.04140E-07 3.23580E-04 50119.82c + 598 501191 Sn-119m 9.95060E-07 1.25480E-04 501191 + 599 501200 Sn-120 2.08900E-06 1.85960E-04 50120.82c + 600 501210 Sn-121 5.47990E-07 1.36860E-04 501210 + 601 501211 Sn-121m 1.32290E-06 1.22850E-05 501211 + 602 501220 Sn-122 4.47400E-06 1.37480E-04 50122.82c + 603 501230 Sn-123 1.32140E-05 2.35260E-05 50123.82c + 604 501231 Sn-123m 5.47340E-06 1.70820E-04 501231 + 605 501240 Sn-124 6.71710E-05 3.91960E-04 50124.82c + 606 501250 Sn-125 1.22290E-04 2.01960E-04 50125.82c + 607 501251 Sn-125m 5.06540E-05 5.46810E-04 501251 + 608 501260 Sn-126 9.06820E-04 1.97020E-03 50126.82c + 609 501270 Sn-127 1.60670E-03 2.12660E-03 501270 + 610 501271 Sn-127m 6.65530E-04 1.87530E-03 501271 + 611 501280 Sn-128 1.36960E-03 5.70830E-03 501280 + 612 501281 Sn-128m 3.20800E-03 3.72600E-03 501281 + 613 501290 Sn-129 1.58880E-03 2.28500E-03 501290 + 614 501291 Sn-129m 3.83570E-03 3.90150E-03 501291 + 615 501300 Sn-130 2.03260E-03 2.23180E-03 501300 + 616 501301 Sn-130m 4.76090E-03 4.86830E-03 501301 + 617 501310 Sn-131 1.21590E-03 1.26760E-03 501310 + 618 501311 Sn-131m 2.93550E-03 2.96330E-03 501311 + 619 501320 Sn-132 1.90640E-03 1.90880E-03 501320 + 620 501330 Sn-133 1.77810E-04 1.77820E-04 501330 + 621 501340 Sn-134 2.44360E-05 2.44360E-05 501340 + 622 501350 Sn-135 3.99020E-07 3.99020E-07 501350 + 623 501360 Sn-136 1.13510E-08 1.13510E-08 501360 + 624 511190 Sb-119 6.17610E-11 8.13930E-11 511190 + 625 511191 Sb-119m 1.96320E-11 1.96320E-11 511191 + 626 511200 Sb-120 6.19440E-10 6.19440E-10 511200 + 627 511201 Sb-120m 8.78960E-10 8.78960E-10 511201 + 628 511210 Sb-121 3.48370E-08 1.39650E-04 51121.82c + 629 511220 Sb-122 2.99630E-07 6.39280E-07 511220 + 630 511221 Sb-122m 3.39650E-07 3.39650E-07 511221 + 631 511230 Sb-123 5.12510E-06 1.99470E-04 51123.82c + 632 511240 Sb-124 8.59700E-07 2.01950E-06 51124.82c + 633 511241 Sb-124m 6.57350E-07 1.54640E-06 511241 + 634 511242 Sb-124m 8.89050E-07 8.89050E-07 511242 + 635 511250 Sb-125 1.68180E-05 7.65590E-04 51125.82c + 636 511260 Sb-126 1.98910E-05 2.46430E-05 51126.82c + 637 511261 Sb-126m 1.47070E-05 3.39420E-05 511261 + 638 511262 Sb-126m 1.92350E-05 1.92350E-05 511262 + 639 511270 Sb-127 3.83600E-04 4.38550E-03 511270 + 640 511280 Sb-128 3.53810E-04 6.08390E-03 511280 + 641 511281 Sb-128m 6.03730E-04 6.03730E-04 511281 + 642 511290 Sb-129 2.61170E-03 7.37930E-03 511290 + 643 511291 Sb-129m 1.59590E-03 3.54660E-03 511291 + 644 511300 Sb-130 4.18140E-03 8.84740E-03 511300 + 645 511301 Sb-130m 4.18140E-03 6.61560E-03 511301 + 646 511310 Sb-131 1.80480E-02 2.22790E-02 511310 + 647 511320 Sb-132 1.06530E-02 1.25620E-02 511320 + 648 511321 Sb-132m 7.85170E-03 7.85170E-03 511321 + 649 511330 Sb-133 1.27290E-02 1.29110E-02 511330 + 650 511340 Sb-134 8.28130E-04 8.48450E-04 511340 + 651 511341 Sb-134m 1.93970E-03 1.93970E-03 511341 + 652 511350 Sb-135 6.62580E-04 6.62900E-04 511350 + 653 511360 Sb-136 9.63670E-05 9.63750E-05 511360 + 654 511370 Sb-137 1.17340E-05 1.17340E-05 511370 + 655 511380 Sb-138 5.60250E-08 5.60250E-08 511380 + 656 511390 Sb-139 2.26740E-09 2.26740E-09 511390 + 657 521210 Te-121 9.23760E-13 3.60450E-12 521210 + 658 521211 Te-121m 3.02220E-12 3.02220E-12 521211 + 659 521220 Te-122 3.04570E-10 6.22960E-07 52122.82c + 660 521230 Te-123 2.38290E-09 1.01790E-08 52123.82c + 661 521231 Te-123m 7.79610E-09 7.79610E-09 521231 + 662 521250 Te-125 2.02190E-11 7.65590E-04 52125.82c + 663 521251 Te-125m 6.61490E-11 1.71310E-04 521251 + 664 521260 Te-126 1.56310E-06 5.53960E-05 52126.82c + 665 521270 Te-127 7.80170E-07 4.37080E-03 521270 + 666 521271 Te-127m 1.88340E-06 7.24590E-04 52527.82c + 667 521280 Te-128 5.67920E-05 6.72270E-03 52128.82c + 668 521290 Te-129 9.13090E-05 9.08170E-03 521290 + 669 521291 Te-129m 2.20430E-04 4.38910E-03 52529.82c + 670 521300 Te-130 2.30550E-03 1.77680E-02 52130.82c + 671 521310 Te-131 2.06370E-03 2.39800E-02 521310 + 672 521311 Te-131m 4.98190E-03 6.76560E-03 521311 + 673 521320 Te-132 2.52950E-02 4.57090E-02 52132.82c + 674 521330 Te-133 9.89770E-03 2.51500E-02 521330 + 675 521331 Te-133m 2.38940E-02 2.61270E-02 521331 + 676 521340 Te-134 3.49960E-02 3.78870E-02 521340 + 677 521350 Te-135 1.36590E-02 1.42330E-02 521350 + 678 521360 Te-136 5.83700E-03 5.92320E-03 521360 + 679 521370 Te-137 1.18900E-03 1.19500E-03 521370 + 680 521380 Te-138 3.24820E-04 3.24880E-04 521380 + 681 521390 Te-139 3.51720E-05 3.51740E-05 521390 + 682 521400 Te-140 1.18730E-06 1.18730E-06 521400 + 683 521410 Te-141 7.59250E-09 7.59250E-09 521410 + 684 531270 I-127 1.38910E-10 4.38820E-03 53127.82c + 685 531280 I-128 4.95160E-09 4.95160E-09 531280 + 686 531290 I-129 3.04170E-06 1.07090E-02 53129.82c + 687 531300 I-130 1.27970E-05 1.73860E-05 53130.82c + 688 531301 I-130m 5.46340E-06 5.46340E-06 531301 + 689 531310 I-131 2.71460E-04 2.95960E-02 53131.82c + 690 531320 I-132 7.99990E-04 4.70160E-02 531320 + 691 531321 I-132m 5.89610E-04 5.89610E-04 531321 + 692 531330 I-133 4.85120E-03 5.45200E-02 531330 + 693 531331 I-133m 2.96450E-03 2.96450E-03 531331 + 694 531340 I-134 1.11290E-02 5.70290E-02 531340 + 695 531341 I-134m 8.20210E-03 8.20210E-03 531341 + 696 531350 I-135 4.49330E-02 5.91660E-02 53135.82c + 697 531360 I-136 7.81240E-03 1.37530E-02 531360 + 698 531361 I-136m 1.82990E-02 1.83160E-02 531361 + 699 531370 I-137 1.77110E-02 1.88910E-02 531370 + 700 531380 I-138 7.62960E-03 7.93400E-03 531380 + 701 531390 I-139 5.19540E-03 5.23060E-03 531390 + 702 531400 I-140 9.15700E-04 9.16890E-04 531400 + 703 531410 I-141 2.06810E-04 2.06820E-04 531410 + 704 531420 I-142 1.50810E-05 1.50810E-05 531420 + 705 531430 I-143 5.30140E-08 5.30140E-08 531430 + 706 531440 I-144 9.45510E-10 9.45510E-10 531440 + 707 541300 Xe-130 2.64050E-09 1.82630E-05 54130.82c + 708 541310 Xe-131 2.91830E-07 2.95970E-02 54131.82c + 709 541311 Xe-131m 7.04510E-07 3.22170E-04 541311 + 710 541320 Xe-132 1.18590E-05 4.71240E-02 54132.82c + 711 541321 Xe-132m 1.34430E-05 1.34430E-05 541321 + 712 541330 Xe-133 5.87590E-05 5.47210E-02 54133.82c + 713 541331 Xe-133m 1.41850E-04 1.69370E-03 541331 + 714 541340 Xe-134 4.69180E-04 5.87860E-02 54134.82c + 715 541341 Xe-134m 1.09890E-03 1.28760E-03 541341 + 716 541350 Xe-135 2.37510E-03 6.71820E-02 54135.82c + 717 541351 Xe-135m 5.73380E-03 1.55010E-02 541351 + 718 541360 Xe-136 3.01830E-02 6.34810E-02 54136.82c + 719 541370 Xe-137 3.11720E-02 4.92550E-02 541370 + 720 541380 Xe-138 4.32390E-02 5.12650E-02 541380 + 721 541390 Xe-139 3.12320E-02 3.60350E-02 541390 + 722 541400 Xe-140 1.95140E-02 2.03890E-02 541400 + 723 541410 Xe-141 6.64580E-03 6.81300E-03 541410 + 724 541420 Xe-142 2.05550E-03 2.06680E-03 541420 + 725 541430 Xe-143 3.32000E-04 3.32030E-04 541430 + 726 541440 Xe-144 5.01000E-05 5.01010E-05 541440 + 727 541450 Xe-145 3.61170E-06 3.61170E-06 541450 + 728 541460 Xe-146 5.68110E-09 5.68110E-09 541460 + 729 551330 Cs-133 5.06520E-08 5.47210E-02 55133.82c + 730 551340 Cs-134 1.12530E-06 1.95460E-06 55134.82c + 731 551341 Cs-134m 8.29340E-07 8.29340E-07 551341 + 732 551350 Cs-135 4.21700E-05 6.73430E-02 55135.82c + 733 551351 Cs-135m 2.57700E-05 2.57700E-05 551351 + 734 551360 Cs-136 3.84990E-04 4.97800E-04 55136.82c + 735 551361 Cs-136m 2.25620E-04 2.25620E-04 551361 + 736 551370 Cs-137 4.49860E-03 5.37540E-02 55137.82c + 737 551380 Cs-138 5.17080E-03 6.23790E-02 551380 + 738 551381 Cs-138m 7.33720E-03 7.33720E-03 551381 + 739 551390 Cs-139 3.11010E-02 6.71360E-02 551390 + 740 551400 Cs-140 2.46610E-02 4.50530E-02 551400 + 741 551410 Cs-141 2.93620E-02 3.61790E-02 551410 + 742 551420 Cs-142 1.52880E-02 1.73510E-02 551420 + 743 551430 Cs-143 9.05630E-03 9.38650E-03 551430 + 744 551440 Cs-144 1.33610E-03 2.05290E-03 551440 + 745 551441 Cs-144m 1.33610E-03 1.33620E-03 551441 + 746 551450 Cs-145 6.70340E-04 6.73770E-04 551450 + 747 551460 Cs-146 1.18280E-04 1.18280E-04 551460 + 748 551470 Cs-147 1.88770E-05 1.88770E-05 551470 + 749 551480 Cs-148 2.36290E-08 2.36290E-08 551480 + 750 551490 Cs-149 6.25480E-10 6.25480E-10 551490 + 751 561350 Ba-135 2.20520E-09 7.52880E-09 56135.82c + 752 561351 Ba-135m 5.32360E-09 5.32360E-09 561351 + 753 561360 Ba-136 1.61870E-06 6.16020E-04 56136.82c + 754 561361 Ba-136m 3.79130E-06 3.79130E-06 561361 + 755 561370 Ba-137 1.67080E-05 5.38110E-02 56137.82c + 756 561371 Ba-137m 4.03350E-05 5.07840E-02 561371 + 757 561380 Ba-138 9.76650E-04 6.47500E-02 56138.82c + 758 561390 Ba-139 4.52570E-03 7.16620E-02 561390 + 759 561400 Ba-140 1.15940E-02 5.66470E-02 56140.82c + 760 561410 Ba-141 1.62250E-02 5.24040E-02 561410 + 761 561420 Ba-142 2.96400E-02 4.71450E-02 561420 + 762 561430 Ba-143 2.70470E-02 3.63450E-02 561430 + 763 561440 Ba-144 2.18250E-02 2.45770E-02 561440 + 764 561450 Ba-145 9.52560E-03 1.01200E-02 561450 + 765 561460 Ba-146 4.59470E-03 4.70160E-03 561460 + 766 561470 Ba-147 1.40230E-03 1.41580E-03 561470 + 767 561480 Ba-148 3.52420E-04 3.52440E-04 561480 + 768 561490 Ba-149 6.43960E-05 6.43970E-05 561490 + 769 561500 Ba-150 3.51860E-06 3.51860E-06 561500 + 770 561510 Ba-151 1.90430E-09 1.90430E-09 561510 + 771 571380 La-138 1.07330E-06 1.07330E-06 57138.82c + 772 571390 La-139 3.38060E-05 7.16960E-02 57139.82c + 773 571400 La-140 1.83430E-04 5.68300E-02 57140.82c + 774 571410 La-141 7.90610E-04 5.31950E-02 571410 + 775 571420 La-142 1.83330E-03 4.89780E-02 571420 + 776 571430 La-143 7.01640E-03 4.33620E-02 571430 + 777 571440 La-144 1.13540E-02 3.59310E-02 571440 + 778 571450 La-145 1.62280E-02 2.63480E-02 571450 + 779 571460 La-146 3.91890E-03 8.62040E-03 571460 + 780 571461 La-146m 7.04910E-03 7.04910E-03 571461 + 781 571470 La-147 9.67170E-03 1.10890E-02 571470 + 782 571480 La-148 4.62330E-03 4.97460E-03 571480 + 783 571490 La-149 2.02990E-03 2.09400E-03 571490 + 784 571500 La-150 4.48790E-04 4.52310E-04 571500 + 785 571510 La-151 6.74250E-05 6.74270E-05 571510 + 786 571520 La-152 1.29530E-05 1.29530E-05 571520 + 787 571530 La-153 1.38630E-08 1.38630E-08 571530 + 788 571540 La-154 1.96540E-10 1.96540E-10 571540 + 789 581400 Ce-140 1.18740E-06 5.68320E-02 58140.82c + 790 581410 Ce-141 1.34530E-05 5.32080E-02 58141.82c + 791 581420 Ce-142 8.97820E-05 4.90680E-02 58142.82c + 792 581430 Ce-143 3.31210E-04 4.36930E-02 58143.82c + 793 581440 Ce-144 1.69170E-03 3.76220E-02 58144.82c + 794 581450 Ce-145 4.09780E-03 3.04460E-02 581450 + 795 581460 Ce-146 9.99460E-03 2.56640E-02 581460 + 796 581470 Ce-147 1.33370E-02 2.44260E-02 581470 + 797 581480 Ce-148 1.71740E-02 2.21780E-02 581480 + 798 581490 Ce-149 1.11720E-02 1.32490E-02 581490 + 799 581500 Ce-150 6.73840E-03 7.17850E-03 581500 + 800 581510 Ce-151 2.15900E-03 2.22720E-03 581510 + 801 581520 Ce-152 8.06460E-04 8.18630E-04 581520 + 802 581530 Ce-153 1.83560E-04 1.83570E-04 581530 + 803 581540 Ce-154 3.08350E-05 3.08350E-05 581540 + 804 581550 Ce-155 3.18610E-06 3.18610E-06 581550 + 805 581560 Ce-156 1.01030E-09 1.01030E-09 581560 + 806 591430 Pr-143 1.02490E-06 4.36940E-02 59143.82c + 807 591440 Pr-144 2.92740E-07 3.76250E-02 591440 + 808 591441 Pr-144m 2.60000E-06 5.21770E-04 591441 + 809 591450 Pr-145 4.61320E-05 3.04920E-02 591450 + 810 591460 Pr-146 2.06250E-04 2.58700E-02 591460 + 811 591470 Pr-147 1.02570E-03 2.54520E-02 591470 + 812 591480 Pr-148 4.84690E-04 2.26630E-02 591480 + 813 591481 Pr-148m 2.03840E-03 2.03840E-03 591481 + 814 591490 Pr-149 5.92160E-03 1.91710E-02 591490 + 815 591500 Pr-150 6.22220E-03 1.34010E-02 591500 + 816 591510 Pr-151 6.00620E-03 8.23340E-03 591510 + 817 591520 Pr-152 4.11070E-03 4.93050E-03 591520 + 818 591530 Pr-153 2.68980E-03 2.87240E-03 591530 + 819 591540 Pr-154 7.78610E-04 8.09250E-04 591540 + 820 591550 Pr-155 2.09320E-04 2.12510E-04 591550 + 821 591560 Pr-156 2.74910E-05 2.74920E-05 591560 + 822 591570 Pr-157 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2.25910E-04 651640 + 919 651650 Tb-165 4.75070E-05 1.13100E-04 651650 + 920 651660 Tb-166 3.25730E-05 5.82970E-05 651660 + 921 651670 Tb-167 1.92420E-05 2.12690E-05 651670 + 922 651680 Tb-168 7.13370E-06 7.22210E-06 651680 + 923 651690 Tb-169 4.04140E-06 4.04600E-06 651690 + 924 651700 Tb-170 5.86700E-08 5.86700E-08 651700 + 925 651710 Tb-171 3.66000E-09 3.66000E-09 651710 + 926 661600 Dy-160 1.30410E-10 4.35210E-07 66160.82c + 927 661610 Dy-161 2.83170E-09 7.39350E-04 66161.82c + 928 661620 Dy-162 6.81330E-08 5.17730E-04 66162.82c + 929 661630 Dy-163 9.39140E-07 3.19030E-04 66163.82c + 930 661640 Dy-164 7.85430E-06 2.33770E-04 66164.82c + 931 661650 Dy-165 1.31860E-05 1.28260E-04 661650 + 932 661651 Dy-165m 2.01580E-06 2.01580E-06 661651 + 933 661660 Dy-166 2.17110E-05 8.00080E-05 661660 + 934 661670 Dy-167 1.51880E-05 3.64570E-05 661670 + 935 661680 Dy-168 1.42670E-05 2.14890E-05 661680 + 936 661690 Dy-169 1.61640E-05 2.02100E-05 661690 + 937 661700 Dy-170 7.49350E-06 7.55220E-06 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721820 + 1034 721821 Hf-182m 5.22650E-09 5.22650E-09 721821 + 1035 721830 Hf-183 5.03710E-09 6.75160E-09 721830 + 1036 721840 Hf-184 1.09770E-09 1.19670E-09 721840 + 1037 721841 Hf-184m 1.97450E-09 2.07350E-09 721841 + 1038 721850 Hf-185 8.02800E-10 8.02800E-10 721850 + 1039 721860 Hf-186 2.27520E-10 2.27520E-10 721860 + 1040 721870 Hf-187 2.11700E-11 2.11700E-11 721870 + 1041 721880 Hf-188 1.90860E-12 1.90860E-12 721880 + 1042 731790 Ta-179 1.06600E-12 1.40470E-12 731790 + 1043 731800 Ta-180 6.17230E-12 6.17230E-12 731800 + 1044 731801 Ta-180m 6.99670E-12 2.78950E-11 731801 + 1045 731810 Ta-181 1.14290E-10 2.36550E-08 73181.82c + 1046 731820 Ta-182 1.26890E-10 3.38650E-09 73182.82c + 1047 731821 Ta-182m 1.29520E-10 3.25960E-09 731821 + 1048 731822 Ta-182m 9.87260E-11 3.13010E-09 731822 + 1049 731830 Ta-183 1.18780E-09 7.93940E-09 731830 + 1050 731840 Ta-184 1.28600E-09 4.55610E-09 731840 + 1051 731850 Ta-185 1.12960E-09 2.47950E-09 731850 + 1052 731851 Ta-185m 5.47110E-10 5.47110E-10 731851 + 1053 731860 Ta-186 8.49970E-10 1.07750E-09 731860 + 1054 731870 Ta-187 4.31950E-10 4.53120E-10 731870 + 1055 731880 Ta-188 7.94810E-11 8.13900E-11 731880 + 1056 731890 Ta-189 1.84540E-11 1.84540E-11 731890 + 1057 731900 Ta-190 1.41560E-12 1.41560E-12 731900 + 1058 741820 W-182 1.47390E-12 3.38800E-09 74182.82c + 1059 741830 W-183 2.53910E-12 7.95030E-09 74183.82c + 1060 741831 W-183m 8.30700E-12 2.78250E-10 741831 + 1061 741840 W-184 7.02860E-11 4.62640E-09 74184.82c + 1062 741850 W-185 5.23530E-11 2.65820E-09 741850 + 1063 741851 W-185m 1.26390E-10 1.26390E-10 741851 + 1064 741860 W-186 3.58260E-10 1.55150E-09 74186.82c + 1065 741861 W-186m 1.15570E-10 1.15570E-10 741861 + 1066 741870 W-187 4.20610E-10 8.73730E-10 741870 + 1067 741880 W-188 3.89330E-10 4.70720E-10 741880 + 1068 741890 W-189 1.66290E-10 1.84740E-10 741890 + 1069 741900 W-190 3.38140E-11 7.35610E-11 741900 + 1070 741901 W-190m 3.83310E-11 3.83310E-11 741901 + 1071 741910 W-191 1.10360E-11 1.10360E-11 741910 + 1072 741920 W-192 1.81010E-12 1.81010E-12 741920 + 1073 751850 Re-185 1.04390E-12 2.65930E-09 75185.82c + 1074 751860 Re-186 2.45710E-12 2.45710E-12 751860 + 1075 751861 Re-186m 3.48650E-12 3.48650E-12 751861 + 1076 751870 Re-187 3.05880E-11 9.04320E-10 75187.82c + 1077 751880 Re-188 1.59580E-11 5.24060E-10 751880 + 1078 751881 Re-188m 3.73790E-11 3.73790E-11 751881 + 1079 751890 Re-189 1.16100E-10 3.00840E-10 751890 + 1080 751900 Re-190 3.12950E-11 1.30520E-10 751900 + 1081 751901 Re-190m 5.62930E-11 5.62930E-11 751901 + 1082 751910 Re-191 6.87140E-11 7.97500E-11 751910 + 1083 751920 Re-192 2.14320E-11 2.32420E-11 751920 + 1084 751930 Re-193 7.64870E-12 7.64870E-12 751930 + 1085 761890 Os-189 8.61750E-13 3.04520E-10 761890 + 1086 761891 Os-189m 2.81940E-12 3.37550E-11 761891 + 1087 761900 Os-190 7.29110E-12 1.76710E-10 761900 + 1088 761901 Os-190m 8.26490E-12 3.88880E-11 761901 + 1089 761910 Os-191 1.70510E-11 1.02010E-10 761910 + 1090 761911 Os-191m 5.21180E-12 5.21180E-12 761911 + 1091 761920 Os-192 1.63150E-11 5.58340E-11 761920 + 1092 761921 Os-192m 1.84950E-11 1.84950E-11 761921 + 1093 761930 Os-193 2.17720E-11 2.94210E-11 761930 + 1094 761940 Os-194 1.34160E-11 1.34160E-11 761940 + 1095 761950 Os-195 3.55920E-12 3.55920E-12 761950 + 1096 761960 Os-196 1.02300E-12 1.02300E-12 761960 + 1097 771920 Ir-192 4.89680E-13 3.87330E-12 771920 + 1098 771922 Ir-192m 4.89680E-13 2.89400E-12 771922 + 1099 771930 Ir-193 1.45620E-12 3.43920E-11 77193.82c + 1100 771931 Ir-193m 3.51550E-12 3.61770E-12 771931 + 1101 771940 Ir-194 1.81490E-12 1.70460E-11 771940 + 1102 771941 Ir-194m 1.81490E-12 1.81490E-12 771941 + 1103 771942 Ir-194m 1.81490E-12 1.81490E-12 771942 + 1104 771950 Ir-195 2.11090E-12 5.92490E-12 771950 + 1105 771951 Ir-195m 5.09600E-12 5.09600E-12 771951 + 1106 771960 Ir-196 1.85000E-12 2.87860E-12 771960 + 1107 771961 Ir-196m 1.85000E-12 1.85000E-12 771961 + 1108 771971 Ir-197m 1.34380E-12 1.34380E-12 771971 + 1109 781960 Pt-196 1.99890E-12 6.72190E-12 781960 + 1110 781970 Pt-197 5.25640E-13 3.60900E-12 781970 + 1111 781971 Pt-197m 1.26900E-12 2.60940E-12 781971 + 1112 781980 Pt-198 1.68360E-12 1.68360E-12 781980 + + Neutron-induced fission: + + Interpolation region : 2 / 2 + Interpolation energy : 4.00000E-01 MeV + Number of products : 1138 / 1204 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 3.60660E-05 3.60660E-05 1001.82c + 2 10020 H-2 1.10220E-05 1.10220E-05 1002.82c + 3 10030 H-3 1.85000E-04 1.85000E-04 1003.82c + 4 20040 He-4 2.28000E-03 2.28000E-03 2004.82c + 5 200500 Ca-50 7.34650E-12 7.34650E-12 200500 + 6 200510 Ca-51 7.02670E-12 7.02670E-12 200510 + 7 200520 Ca-52 7.16820E-12 7.16820E-12 200520 + 8 200530 Ca-53 2.40950E-12 2.40950E-12 200530 + 9 210500 Sc-50 1.61440E-12 9.45400E-12 210500 + 10 210501 Sc-50m 5.92280E-13 7.93880E-12 210501 + 11 210510 Sc-51 1.04580E-11 1.76280E-11 210510 + 12 210520 Sc-52 1.87560E-11 2.65040E-11 210520 + 13 210530 Sc-53 3.33780E-11 3.50650E-11 210530 + 14 210540 Sc-54 2.23740E-11 2.23740E-11 210540 + 15 210550 Sc-55 1.86660E-11 1.86660E-11 210550 + 16 210560 Sc-56 5.10410E-12 5.10410E-12 210560 + 17 210570 Sc-57 1.39830E-12 1.39830E-12 210570 + 18 220520 Ti-52 7.52240E-12 3.40260E-11 220520 + 19 220530 Ti-53 2.34980E-11 5.85630E-11 220530 + 20 220540 Ti-54 7.80850E-11 1.00460E-10 220540 + 21 220550 Ti-55 1.17180E-10 1.35850E-10 220550 + 22 220560 Ti-56 1.75450E-10 1.81020E-10 220560 + 23 220570 Ti-57 9.85880E-11 9.95250E-11 220570 + 24 220580 Ti-58 6.01190E-11 6.01190E-11 220580 + 25 220590 Ti-59 1.30920E-11 1.30920E-11 220590 + 26 220600 Ti-60 2.57560E-12 2.57560E-12 220600 + 27 230530 V-53 1.21260E-12 5.97750E-11 230530 + 28 230540 V-54 7.70540E-12 1.08160E-10 230540 + 29 230550 V-55 5.92650E-11 1.95110E-10 230550 + 30 230560 V-56 1.53970E-10 3.35280E-10 230560 + 31 230570 V-57 4.34320E-10 5.33550E-10 230570 + 32 230580 V-58 4.90890E-10 5.51010E-10 230580 + 33 230590 V-59 6.05880E-10 6.18970E-10 230590 + 34 230600 V-60 2.51770E-10 2.54350E-10 230600 + 35 230610 V-61 1.26030E-10 1.26030E-10 230610 + 36 230620 V-62 2.20200E-11 2.20200E-11 230620 + 37 230630 V-63 3.42660E-12 3.42660E-12 230630 + 38 240550 Cr-55 1.34050E-12 1.96450E-10 240550 + 39 240560 Cr-56 1.96900E-11 3.57110E-10 240560 + 40 240570 Cr-57 1.02690E-10 1.07490E-09 240570 + 41 240580 Cr-58 5.81910E-10 6.92110E-10 240580 + 42 240590 Cr-59 1.24680E-09 1.86580E-09 240590 + 43 240600 Cr-60 2.66060E-09 2.92250E-09 240600 + 44 240610 Cr-61 2.55340E-09 2.67190E-09 240610 + 45 240620 Cr-62 2.61250E-09 2.63570E-09 240620 + 46 240630 Cr-63 8.80940E-10 8.83170E-10 240630 + 47 240640 Cr-64 2.90320E-10 2.90320E-10 240640 + 48 240650 Cr-65 4.14460E-11 4.14460E-11 240650 + 49 240660 Cr-66 5.13280E-12 5.13280E-12 240660 + 50 250570 Mn-57 1.52630E-12 1.07640E-09 250570 + 51 250580 Mn-58 1.61140E-11 7.08230E-10 250580 + 52 250581 Mn-58m 1.58400E-12 1.58400E-12 250581 + 53 250590 Mn-59 2.07130E-10 2.07290E-09 250590 + 54 250600 Mn-60 7.10130E-11 3.07660E-09 250600 + 55 250601 Mn-60m 7.22430E-10 7.22430E-10 250601 + 56 250610 Mn-61 3.77300E-09 6.44490E-09 250610 + 57 250620 Mn-62 5.86670E-09 7.18450E-09 250620 + 58 250621 Mn-62m 9.18740E-10 2.23660E-09 250621 + 59 250630 Mn-63 1.21080E-08 1.29910E-08 250630 + 60 250640 Mn-64 7.91790E-09 8.20820E-09 250640 + 61 250650 Mn-65 6.81670E-09 6.85810E-09 250650 + 62 250660 Mn-66 1.86940E-09 1.87450E-09 250660 + 63 250670 Mn-67 5.14440E-10 5.14440E-10 250670 + 64 250680 Mn-68 5.09430E-11 5.09430E-11 250680 + 65 250690 Mn-69 2.36270E-11 2.36270E-11 250690 + 66 260590 Fe-59 1.30960E-12 2.07420E-09 260590 + 67 260600 Fe-60 3.02010E-11 3.74610E-09 260600 + 68 260610 Fe-61 2.84400E-10 6.72930E-09 260610 + 69 260620 Fe-62 2.70120E-09 1.21220E-08 260620 + 70 260630 Fe-63 8.46310E-09 2.14540E-08 260630 + 71 260640 Fe-64 3.55810E-08 4.37890E-08 260640 + 72 260650 Fe-65 4.24650E-08 4.93230E-08 260650 + 73 260660 Fe-66 6.37460E-08 6.56210E-08 260660 + 74 260670 Fe-67 3.59630E-08 3.64770E-08 260670 + 75 260680 Fe-68 2.20330E-08 2.20900E-08 260680 + 76 260690 Fe-69 2.30810E-08 2.30990E-08 260690 + 77 260700 Fe-70 1.74970E-09 1.74970E-09 260700 + 78 260710 Fe-71 5.88830E-11 5.88830E-11 260710 + 79 260720 Fe-72 8.80200E-12 8.80200E-12 260720 + 80 270610 Co-61 1.15120E-12 6.73040E-09 270610 + 81 270620 Co-62 6.34980E-12 1.21290E-08 270620 + 82 270621 Co-62m 1.73080E-11 1.73080E-11 270621 + 83 270630 Co-63 4.33220E-10 2.18870E-08 270630 + 84 270640 Co-64 2.68670E-09 4.64760E-08 270640 + 85 270650 Co-65 2.13230E-08 7.06460E-08 270650 + 86 270660 Co-66 5.55430E-08 1.21160E-07 270660 + 87 270670 Co-67 1.57270E-07 1.93750E-07 270670 + 88 270680 Co-68 1.02210E-07 1.52210E-07 270680 + 89 270681 Co-68m 7.62910E-08 9.99970E-08 270681 + 90 270690 Co-69 1.82580E-06 1.84730E-06 270690 + 91 270700 Co-70 8.47750E-08 8.47750E-08 270700 + 92 270701 Co-70m 8.47750E-08 8.65250E-08 270701 + 93 270710 Co-71 3.60700E-08 3.61290E-08 270710 + 94 270720 Co-72 1.23770E-08 1.23860E-08 270720 + 95 270730 Co-73 1.10860E-09 1.10860E-09 270730 + 96 270740 Co-74 5.26640E-11 5.26640E-11 270740 + 97 270750 Co-75 5.23420E-12 5.23420E-12 270750 + 98 280640 Ni-64 2.85810E-11 4.65040E-08 28064.82c + 99 280650 Ni-65 4.78300E-10 7.11240E-08 280650 + 100 280660 Ni-66 7.04710E-09 1.28210E-07 280660 + 101 280670 Ni-67 3.69110E-08 2.30660E-07 280670 + 102 280680 Ni-68 2.10080E-07 4.30760E-07 280680 + 103 280690 Ni-69 9.12800E-07 2.74160E-06 280690 + 104 280691 Ni-69m 9.12800E-07 9.12800E-07 280691 + 105 280700 Ni-70 2.31770E-06 2.48900E-06 280700 + 106 280710 Ni-71 9.45760E-07 9.81890E-07 280710 + 107 280720 Ni-72 3.01890E-06 3.03130E-06 280720 + 108 280730 Ni-73 9.85750E-07 9.86860E-07 280730 + 109 280740 Ni-74 8.63020E-08 8.63550E-08 280740 + 110 280750 Ni-75 1.95250E-08 1.95300E-08 280750 + 111 280760 Ni-76 1.96260E-09 1.96260E-09 280760 + 112 280770 Ni-77 9.56290E-11 9.56290E-11 280770 + 113 280780 Ni-78 5.77580E-12 5.77580E-12 280780 + 114 290660 Cu-66 1.68070E-11 1.28230E-07 290660 + 115 290670 Cu-67 5.43960E-10 2.31200E-07 290670 + 116 290680 Cu-68 1.70120E-09 4.36360E-07 290680 + 117 290681 Cu-68m 4.63710E-09 4.63710E-09 290681 + 118 290690 Cu-69 3.56790E-07 4.01120E-06 290690 + 119 290700 Cu-70 3.56400E-08 3.26340E-07 290700 + 120 290701 Cu-70m 4.55160E-07 5.81390E-07 290701 + 121 290702 Cu-70m 3.56400E-08 2.52460E-06 290702 + 122 290710 Cu-71 9.45730E-07 1.92760E-06 290710 + 123 290720 Cu-72 3.01850E-06 6.04980E-06 290720 + 124 290730 Cu-73 1.97150E-06 2.95840E-06 290730 + 125 290740 Cu-74 9.48040E-07 1.03470E-06 290740 + 126 290750 Cu-75 4.16620E-06 4.18540E-06 290750 + 127 290760 Cu-76 5.33050E-07 5.34030E-07 290760 + 128 290761 Cu-76m 5.33050E-07 5.34030E-07 290761 + 129 290770 Cu-77 2.22500E-07 2.22600E-07 290770 + 130 290780 Cu-78 1.96130E-08 1.96190E-08 290780 + 131 290790 Cu-79 1.73350E-09 1.73350E-09 290790 + 132 290800 Cu-80 5.46470E-11 5.46470E-11 290800 + 133 300680 Zn-68 1.79620E-11 4.37120E-07 300680 + 134 300690 Zn-69 3.74820E-10 4.01340E-06 300690 + 135 300691 Zn-69m 1.86160E-09 1.86160E-09 300691 + 136 300700 Zn-70 1.98730E-08 3.03530E-06 300700 + 137 300710 Zn-71 1.33310E-08 1.94100E-06 300710 + 138 300711 Zn-71m 6.62070E-08 6.62070E-08 300711 + 139 300720 Zn-72 1.00620E-06 7.05600E-06 300720 + 140 300730 Zn-73 3.45770E-07 5.34190E-06 300730 + 141 300731 Zn-73m 4.78240E-07 2.03770E-06 300731 + 142 300732 Zn-73m 3.11900E-06 3.11900E-06 300732 + 143 300740 Zn-74 9.48000E-06 1.06610E-05 300740 + 144 300750 Zn-75 2.29130E-05 2.69680E-05 300750 + 145 300760 Zn-76 3.19930E-05 3.30450E-05 300760 + 146 300770 Zn-77 2.13340E-05 2.29770E-05 300770 + 147 300771 Zn-77m 2.84060E-06 2.84060E-06 300771 + 148 300780 Zn-78 1.53970E-05 1.54180E-05 300780 + 149 300790 Zn-79 5.40570E-06 5.40650E-06 300790 + 150 300800 Zn-80 3.47560E-07 3.47620E-07 300800 + 151 300810 Zn-81 1.97760E-08 1.97760E-08 300810 + 152 300820 Zn-82 1.24470E-09 1.24470E-09 300820 + 153 300830 Zn-83 3.80350E-11 3.80350E-11 300830 + 154 310700 Ga-70 1.23770E-11 1.23770E-11 310700 + 155 310710 Ga-71 3.19130E-10 2.00750E-06 310710 + 156 310720 Ga-72 1.17270E-08 7.06890E-06 310720 + 157 310721 Ga-72m 1.15280E-09 2.36260E-07 310721 + 158 310730 Ga-73 1.35740E-07 7.03710E-06 310730 + 159 310740 Ga-74 3.90160E-07 8.67870E-06 310740 + 160 310741 Ga-74m 3.90160E-07 1.10510E-05 310741 + 161 310750 Ga-75 6.24730E-06 3.32150E-05 310750 + 162 310760 Ga-76 1.38540E-05 4.68990E-05 310760 + 163 310770 Ga-77 6.03810E-05 8.47790E-05 310770 + 164 310780 Ga-78 3.73900E-05 5.28780E-05 310780 + 165 310790 Ga-79 7.58150E-05 8.11510E-05 310790 + 166 310800 Ga-80 2.40750E-05 2.44240E-05 310800 + 167 310810 Ga-81 2.35630E-05 2.35810E-05 310810 + 168 310820 Ga-82 1.72780E-06 1.72900E-06 310820 + 169 310830 Ga-83 2.20370E-07 2.20410E-07 310830 + 170 310840 Ga-84 1.06540E-08 1.06540E-08 310840 + 171 310850 Ga-85 4.12570E-10 4.12570E-10 310850 + 172 320720 Ge-72 9.32010E-12 7.06890E-06 32072.82c + 173 320730 Ge-73 1.88710E-10 7.03730E-06 32073.82c + 174 320731 Ge-73m 3.79970E-11 6.93380E-06 320731 + 175 320740 Ge-74 8.22980E-09 1.14500E-05 32074.82c + 176 320750 Ge-75 2.56470E-08 3.34330E-05 320750 + 177 320751 Ge-75m 1.92620E-07 1.52120E-06 320751 + 178 320760 Ge-76 1.06600E-06 4.79650E-05 32076.82c + 179 320770 Ge-77 1.06550E-05 2.70330E-05 320770 + 180 320771 Ge-77m 1.41870E-06 8.61970E-05 320771 + 181 320780 Ge-78 1.02070E-04 1.55020E-04 320780 + 182 320790 Ge-79 2.01740E-05 1.07200E-04 320790 + 183 320791 Ge-79m 1.51520E-04 1.51640E-04 320791 + 184 320800 Ge-80 3.64660E-04 3.91890E-04 320800 + 185 320810 Ge-81 2.71630E-04 2.83430E-04 320810 + 186 320811 Ge-81m 5.46910E-05 6.46790E-05 320811 + 187 320820 Ge-82 3.29220E-04 3.30660E-04 320820 + 188 320830 Ge-83 8.37280E-05 8.38740E-05 320830 + 189 320840 Ge-84 2.16770E-05 2.16800E-05 320840 + 190 320850 Ge-85 1.98090E-06 1.98130E-06 320850 + 191 320860 Ge-86 1.48530E-07 1.48530E-07 320860 + 192 320870 Ge-87 4.43090E-09 4.43090E-09 320870 + 193 320880 Ge-88 2.31190E-10 2.31190E-10 320880 + 194 330740 As-74 1.26000E-12 1.26000E-12 330740 + 195 330750 As-75 4.78920E-11 3.34340E-05 33075.82c + 196 330751 As-75m 1.81370E-10 6.37740E-10 330751 + 197 330760 As-76 6.16600E-09 6.16600E-09 330760 + 198 330770 As-77 2.27880E-07 9.70810E-05 330770 + 199 330780 As-78 2.19690E-06 1.57220E-04 330780 + 200 330790 As-79 7.55470E-06 2.60320E-04 330790 + 201 330800 As-80 6.24250E-05 4.54320E-04 330800 + 202 330810 As-81 2.29160E-04 5.76620E-04 330810 + 203 330820 As-82 8.82480E-05 4.18910E-04 330820 + 204 330821 As-82m 3.07480E-04 3.07480E-04 330821 + 205 330830 As-83 6.07540E-04 6.93760E-04 330830 + 206 330840 As-84 1.74990E-04 1.84790E-04 330840 + 207 330841 As-84m 1.74990E-04 1.84790E-04 330841 + 208 330850 As-85 2.23440E-04 2.25140E-04 330850 + 209 330860 As-86 6.97190E-05 6.98670E-05 330860 + 210 330870 As-87 2.70360E-05 2.70400E-05 330870 + 211 330880 As-88 5.01940E-06 5.01960E-06 330880 + 212 330890 As-89 5.60470E-08 5.60470E-08 330890 + 213 330900 As-90 1.25070E-09 1.25070E-09 330900 + 214 340760 Se-76 1.76330E-12 6.16780E-09 34076.82c + 215 340770 Se-77 1.15580E-11 9.70810E-05 34077.82c + 216 340771 Se-77m 8.68060E-11 8.68060E-11 340771 + 217 340780 Se-78 6.63640E-09 1.57220E-04 34078.82c + 218 340790 Se-79 9.53630E-07 2.61260E-04 34079.82c + 219 340791 Se-79m 1.26970E-07 2.54280E-04 340791 + 220 340800 Se-80 3.43390E-06 4.57750E-04 34080.82c + 221 340810 Se-81 5.25620E-06 6.21330E-04 340810 + 222 340811 Se-81m 3.94780E-05 6.01780E-05 340811 + 223 340820 Se-82 2.38260E-04 9.64650E-04 34082.82c + 224 340830 Se-83 5.10920E-04 7.60930E-04 340830 + 225 340831 Se-83m 1.02870E-04 5.47130E-04 340831 + 226 340840 Se-84 1.58210E-03 2.00070E-03 340840 + 227 340850 Se-85 1.78760E-03 1.98630E-03 340850 + 228 340860 Se-86 1.85880E-03 1.90980E-03 340860 + 229 340870 Se-87 9.08900E-04 9.31780E-04 340870 + 230 340880 Se-88 4.46140E-04 4.51160E-04 340880 + 231 340890 Se-89 1.22500E-04 1.22560E-04 340890 + 232 340900 Se-90 1.81760E-05 1.81770E-05 340900 + 233 340910 Se-91 3.93910E-07 3.93910E-07 340910 + 234 340920 Se-92 1.98620E-08 1.98620E-08 340920 + 235 340930 Se-93 5.21160E-10 5.21160E-10 340930 + 236 350790 Br-79 8.58140E-12 1.42440E-07 35079.82c + 237 350791 Br-79m 3.24980E-11 3.24980E-11 350791 + 238 350800 Br-80 5.26440E-10 2.36070E-09 350800 + 239 350801 Br-80m 1.83430E-09 1.83430E-09 350801 + 240 350810 Br-81 1.02860E-07 6.21460E-04 35081.82c + 241 350820 Br-82 1.52710E-06 2.07390E-06 350820 + 242 350821 Br-82m 5.60230E-07 5.60230E-07 350821 + 243 350830 Br-83 3.18320E-05 1.33990E-03 350830 + 244 350840 Br-84 5.65150E-05 2.05720E-03 350840 + 245 350841 Br-84m 5.65150E-05 5.65150E-05 350841 + 246 350850 Br-85 5.81860E-04 2.56810E-03 350850 + 247 350860 Br-86 1.29440E-03 3.20420E-03 350860 + 248 350870 Br-87 2.37120E-03 3.30740E-03 350870 + 249 350880 Br-88 2.35940E-03 2.81560E-03 350880 + 250 350890 Br-89 1.94800E-03 2.06100E-03 350890 + 251 350900 Br-90 8.30880E-04 8.49140E-04 350900 + 252 350910 Br-91 3.45140E-04 3.45450E-04 350910 + 253 350920 Br-92 6.66120E-05 6.66320E-05 350920 + 254 350930 Br-93 7.05850E-06 7.05900E-06 350930 + 255 350940 Br-94 1.26600E-07 1.26600E-07 350940 + 256 350950 Br-95 4.12110E-09 4.12110E-09 350950 + 257 360810 Kr-81 1.55130E-11 1.75780E-11 360810 + 258 360811 Kr-81m 2.06540E-12 2.06540E-12 360811 + 259 360820 Kr-82 1.24470E-09 2.08850E-06 36082.82c + 260 360830 Kr-83 3.59980E-08 1.33990E-03 36083.82c + 261 360831 Kr-83m 7.24800E-09 1.33870E-03 360831 + 262 360840 Kr-84 3.92650E-06 2.11770E-03 36084.82c + 263 360850 Kr-85 3.38120E-05 5.88130E-04 36085.82c + 264 360851 Kr-85m 6.80790E-06 2.57080E-03 360851 + 265 360860 Kr-86 3.28870E-04 3.61610E-03 36086.82c + 266 360870 Kr-87 1.15860E-03 4.57170E-03 360870 + 267 360880 Kr-88 3.36000E-03 6.27760E-03 360880 + 268 360890 Kr-89 5.46940E-03 7.44870E-03 360890 + 269 360900 Kr-90 7.12800E-03 7.83730E-03 360900 + 270 360910 Kr-91 5.35910E-03 5.65750E-03 360910 + 271 360920 Kr-92 3.44650E-03 3.49590E-03 360920 + 272 360930 Kr-93 1.13780E-03 1.14010E-03 360930 + 273 360940 Kr-94 3.76490E-04 3.76530E-04 360940 + 274 360950 Kr-95 4.85660E-05 4.85700E-05 360950 + 275 360960 Kr-96 1.32060E-05 1.32060E-05 360960 + 276 360970 Kr-97 3.45280E-08 3.45280E-08 360970 + 277 360980 Kr-98 1.47380E-09 1.47380E-09 360980 + 278 370840 Rb-84 8.03550E-11 2.48930E-10 370840 + 279 370841 Rb-84m 1.68580E-10 1.68580E-10 370841 + 280 370850 Rb-85 1.76580E-08 2.60880E-03 37085.82c + 281 370860 Rb-86 3.22620E-07 9.99430E-07 37086.82c + 282 370861 Rb-86m 6.76810E-07 6.76810E-07 370861 + 283 370870 Rb-87 1.30380E-05 4.58470E-03 37087.82c + 284 370880 Rb-88 1.32730E-04 6.41030E-03 370880 + 285 370890 Rb-89 7.14850E-04 8.16350E-03 370890 + 286 370900 Rb-90 1.84970E-04 7.07280E-03 370900 + 287 370901 Rb-90m 1.88170E-03 2.90680E-03 370901 + 288 370910 Rb-91 5.25350E-03 1.09110E-02 370910 + 289 370920 Rb-92 7.00290E-03 1.04990E-02 370920 + 290 370930 Rb-93 8.03570E-03 9.18000E-03 370930 + 291 370940 Rb-94 4.88940E-03 5.26310E-03 370940 + 292 370950 Rb-95 2.77750E-03 2.82520E-03 370950 + 293 370960 Rb-96 3.75690E-04 5.73070E-04 370960 + 294 370961 Rb-96m 3.75690E-04 3.82050E-04 370961 + 295 370970 Rb-97 1.97880E-04 1.97910E-04 370970 + 296 370980 Rb-98 1.49610E-05 1.49610E-05 370980 + 297 370981 Rb-98m 1.49610E-05 1.49620E-05 370981 + 298 370990 Rb-99 5.01200E-06 5.01200E-06 370990 + 299 371000 Rb-100 5.87560E-09 5.87560E-09 371000 + 300 380860 Sr-86 1.30630E-10 9.99510E-07 38086.82c + 301 380870 Sr-87 3.68830E-09 4.42870E-09 38087.82c + 302 380871 Sr-87m 7.42620E-10 7.42620E-10 380871 + 303 380880 Sr-88 2.00840E-06 6.41230E-03 38088.82c + 304 380890 Sr-89 2.21260E-05 8.18570E-03 38089.82c + 305 380900 Sr-90 2.68540E-04 1.01730E-02 38090.82c + 306 380910 Sr-91 1.12370E-03 1.20350E-02 380910 + 307 380920 Sr-92 4.43460E-03 1.50620E-02 380920 + 308 380930 Sr-93 8.71750E-03 1.83010E-02 380930 + 309 380940 Sr-94 1.68120E-02 2.17870E-02 380940 + 310 380950 Sr-95 1.57110E-02 1.83700E-02 380950 + 311 380960 Sr-96 1.36220E-02 1.43590E-02 380960 + 312 380970 Sr-97 6.47430E-03 6.62460E-03 380970 + 313 380980 Sr-98 2.86920E-03 2.89780E-03 380980 + 314 380990 Sr-99 6.38430E-04 6.42640E-04 380990 + 315 381000 Sr-100 1.53080E-04 1.53090E-04 381000 + 316 381010 Sr-101 1.51160E-05 1.51160E-05 381010 + 317 381020 Sr-102 2.01340E-06 2.01340E-06 381020 + 318 381030 Sr-103 1.59190E-09 1.59190E-09 381030 + 319 390890 Y-89 2.17440E-10 8.18570E-03 39089.82c + 320 390891 Y-89m 1.08000E-09 7.90100E-07 390891 + 321 390900 Y-90 3.77980E-07 1.01740E-02 39090.82c + 322 390901 Y-90m 6.32120E-07 6.32120E-07 390901 + 323 390910 Y-91 1.86220E-06 1.20460E-02 39091.82c + 324 390911 Y-91m 9.24880E-06 7.08990E-03 390911 + 325 390920 Y-92 7.27980E-05 1.51350E-02 390920 + 326 390930 Y-93 6.65920E-05 1.88670E-02 390930 + 327 390931 Y-93m 5.00150E-04 5.07970E-03 390931 + 328 390940 Y-94 1.90790E-03 2.36940E-02 390940 + 329 390950 Y-95 6.99190E-03 2.53620E-02 390950 + 330 390960 Y-96 3.77290E-03 1.81340E-02 390960 + 331 390961 Y-96m 7.91510E-03 7.91680E-03 390961 + 332 390970 Y-97 3.04460E-03 8.78800E-03 390970 + 333 390971 Y-97m 1.12540E-02 1.53330E-02 390971 + 334 390972 Y-97m 3.86750E-03 3.86750E-03 390972 + 335 390980 Y-98 2.43270E-03 5.33050E-03 390980 + 336 390981 Y-98m 1.17930E-02 1.17930E-02 390981 + 337 390990 Y-99 1.08140E-02 1.14580E-02 390990 + 338 391000 Y-100 2.15900E-03 2.31110E-03 391000 + 339 391001 Y-100m 2.15900E-03 2.15920E-03 391001 + 340 391010 Y-101 1.77490E-03 1.78980E-03 391010 + 341 391020 Y-102 1.66550E-04 1.67500E-04 391020 + 342 391021 Y-102m 1.66550E-04 1.67500E-04 391021 + 343 391030 Y-103 6.81640E-05 6.81660E-05 391030 + 344 391040 Y-104 3.97510E-06 3.97510E-06 391040 + 345 391050 Y-105 9.33690E-09 9.33690E-09 391050 + 346 400910 Zr-91 3.42830E-10 1.20460E-02 40091.82c + 347 400920 Zr-92 1.93110E-08 1.51350E-02 40092.82c + 348 400930 Zr-93 1.21040E-05 1.88790E-02 40093.82c + 349 400940 Zr-94 1.22590E-04 2.38170E-02 40094.82c + 350 400950 Zr-95 6.16230E-04 2.59780E-02 40095.82c + 351 400960 Zr-96 3.45860E-03 2.95210E-02 40096.82c + 352 400970 Zr-97 8.87130E-03 3.40660E-02 400970 + 353 400980 Zr-98 2.23240E-02 3.92230E-02 400980 + 354 400990 Zr-99 2.63160E-02 3.76000E-02 400990 + 355 401000 Zr-100 3.05370E-02 3.49860E-02 401000 + 356 401010 Zr-101 1.81440E-02 1.99500E-02 401010 + 357 401020 Zr-102 1.09250E-02 1.12490E-02 401020 + 358 401030 Zr-103 3.47770E-03 3.54080E-03 401030 + 359 401040 Zr-104 1.16480E-03 1.16840E-03 401040 + 360 401050 Zr-105 1.89080E-04 1.89090E-04 401050 + 361 401060 Zr-106 1.80840E-05 1.80840E-05 401060 + 362 401070 Zr-107 1.98940E-06 1.98940E-06 401070 + 363 401080 Zr-108 2.05390E-09 2.05390E-09 401080 + 364 410940 Nb-94 6.27930E-07 1.00150E-06 41094.82c + 365 410941 Nb-94m 3.75470E-07 3.75470E-07 410941 + 366 410950 Nb-95 2.52850E-06 2.59650E-02 41095.82c + 367 410951 Nb-95m 5.09100E-07 2.81160E-04 410951 + 368 410960 Nb-96 3.15110E-05 3.15110E-05 410960 + 369 410970 Nb-97 2.09230E-04 3.43180E-02 410970 + 370 410971 Nb-97m 4.21280E-05 3.24210E-02 410971 + 371 410980 Nb-98 2.55620E-04 3.94780E-02 410980 + 372 410981 Nb-98m 8.90670E-04 8.90670E-04 410981 + 373 410990 Nb-99 4.37650E-03 2.84340E-02 410990 + 374 410991 Nb-99m 8.81190E-04 1.47180E-02 410991 + 375 411000 Nb-100 1.95300E-03 3.69390E-02 411000 + 376 411001 Nb-100m 9.46800E-03 9.46800E-03 411001 + 377 411010 Nb-101 2.38570E-02 4.38070E-02 411010 + 378 411020 Nb-102 1.21790E-02 2.34280E-02 411020 + 379 411021 Nb-102m 1.21790E-02 1.21790E-02 411021 + 380 411030 Nb-103 2.45650E-02 2.81060E-02 411030 + 381 411040 Nb-104 6.67350E-03 7.84460E-03 411040 + 382 411041 Nb-104m 6.67350E-03 6.67350E-03 411041 + 383 411050 Nb-105 7.50460E-03 7.69130E-03 411050 + 384 411060 Nb-106 2.23690E-03 2.25480E-03 411060 + 385 411070 Nb-107 6.55000E-04 6.56920E-04 411070 + 386 411080 Nb-108 8.00580E-05 8.00600E-05 411080 + 387 411090 Nb-109 1.38700E-05 1.38700E-05 411090 + 388 411100 Nb-110 5.45370E-09 5.45370E-09 411100 + 389 420960 Mo-96 1.09620E-09 3.15120E-05 42096.82c + 390 420970 Mo-97 4.02840E-06 3.43220E-02 42097.82c + 391 420980 Mo-98 3.29420E-05 4.04020E-02 42098.82c + 392 420990 Mo-99 2.41180E-04 4.30990E-02 42099.82c + 393 421000 Mo-100 1.69520E-03 4.81020E-02 42100.82c + 394 421010 Mo-101 5.16580E-03 4.89730E-02 421010 + 395 421020 Mo-102 1.67880E-02 5.23940E-02 421020 + 396 421030 Mo-103 2.57390E-02 5.38530E-02 421030 + 397 421040 Mo-104 3.95350E-02 5.41760E-02 421040 + 398 421050 Mo-105 3.12410E-02 3.89030E-02 421050 + 399 421060 Mo-106 2.52530E-02 2.74460E-02 421060 + 400 421070 Mo-107 1.11330E-02 1.17560E-02 421070 + 401 421080 Mo-108 5.13530E-03 5.21210E-03 421080 + 402 421090 Mo-109 1.25610E-03 1.26820E-03 421090 + 403 421100 Mo-110 3.03090E-04 3.03090E-04 421100 + 404 421110 Mo-111 2.26770E-05 2.26770E-05 421110 + 405 421120 Mo-112 4.03110E-08 4.03110E-08 421120 + 406 421130 Mo-113 6.23900E-10 6.23900E-10 421130 + 407 430990 Tc-99 1.66900E-06 4.31000E-02 43099.82c + 408 430991 Tc-99m 3.36040E-07 3.79530E-02 430991 + 409 431000 Tc-100 6.09390E-06 6.09390E-06 431000 + 410 431010 Tc-101 7.86790E-05 4.90520E-02 431010 + 411 431020 Tc-102 2.38960E-04 5.26330E-02 431020 + 412 431021 Tc-102m 2.38960E-04 2.38960E-04 431021 + 413 431030 Tc-103 2.50190E-03 5.63550E-02 431030 + 414 431040 Tc-104 6.61980E-03 6.07960E-02 431040 + 415 431050 Tc-105 1.85250E-02 5.74280E-02 431050 + 416 431060 Tc-106 2.48180E-02 5.22640E-02 431060 + 417 431070 Tc-107 3.28150E-02 4.45700E-02 431070 + 418 431080 Tc-108 2.33090E-02 2.85280E-02 431080 + 419 431090 Tc-109 1.64360E-02 1.76980E-02 431090 + 420 431100 Tc-110 7.13020E-03 7.43350E-03 431100 + 421 431110 Tc-111 2.93380E-03 2.95620E-03 431110 + 422 431120 Tc-112 5.39670E-04 5.39710E-04 431120 + 423 431130 Tc-113 1.08120E-04 1.08120E-04 431130 + 424 431140 Tc-114 1.07520E-05 1.07520E-05 431140 + 425 431150 Tc-115 9.66880E-07 9.66880E-07 431150 + 426 441010 Ru-101 1.38750E-09 4.90520E-02 44101.82c + 427 441020 Ru-102 8.05460E-06 5.28800E-02 44102.82c + 428 441030 Ru-103 1.42720E-05 5.64090E-02 44103.82c + 429 441031 Ru-103m 3.99320E-05 3.99320E-05 441031 + 430 441040 Ru-104 4.47830E-04 6.12430E-02 44104.82c + 431 441050 Ru-105 1.87330E-03 5.93010E-02 44105.82c + 432 441060 Ru-106 6.95550E-03 5.92190E-02 44106.82c + 433 441070 Ru-107 1.34030E-02 5.79730E-02 441070 + 434 441080 Ru-108 2.55570E-02 5.40990E-02 441080 + 435 441090 Ru-109 2.57770E-02 4.34630E-02 441090 + 436 441100 Ru-110 2.60980E-02 3.35290E-02 441100 + 437 441110 Ru-111 1.47930E-02 1.77570E-02 441110 + 438 441120 Ru-112 8.37440E-03 8.91380E-03 441120 + 439 441130 Ru-113 1.27650E-03 2.01580E-03 441130 + 440 441131 Ru-113m 1.27650E-03 1.27650E-03 441131 + 441 441140 Ru-114 6.77770E-04 6.87960E-04 441140 + 442 441150 Ru-115 8.21420E-05 8.29700E-05 441150 + 443 441160 Ru-116 8.19310E-06 8.19310E-06 441160 + 444 441170 Ru-117 4.56420E-06 4.56420E-06 441170 + 445 441180 Ru-118 3.74750E-11 3.74750E-11 441180 + 446 451040 Rh-104 8.86540E-07 3.97150E-06 451040 + 447 451041 Rh-104m 3.08900E-06 3.08900E-06 451041 + 448 451050 Rh-105 1.15010E-05 5.93140E-02 45105.82c + 449 451051 Rh-105m 1.53130E-06 1.68360E-02 451051 + 450 451060 Rh-106 2.26720E-05 5.92420E-02 451060 + 451 451061 Rh-106m 6.18000E-05 6.18000E-05 451061 + 452 451070 Rh-107 5.65430E-04 5.85390E-02 451070 + 453 451080 Rh-108 4.47270E-04 5.45460E-02 451080 + 454 451081 Rh-108m 1.55840E-03 1.55840E-03 451081 + 455 451090 Rh-109 5.92800E-03 4.93910E-02 451090 + 456 451100 Rh-110 9.97520E-03 4.35040E-02 451100 + 457 451101 Rh-110m 2.34830E-04 2.34830E-04 451101 + 458 451110 Rh-111 1.64250E-02 3.41820E-02 451110 + 459 451120 Rh-112 6.91700E-03 1.58310E-02 451120 + 460 451121 Rh-112m 6.91700E-03 6.91700E-03 451121 + 461 451130 Rh-113 1.19890E-02 1.46430E-02 451130 + 462 451140 Rh-114 2.57540E-03 3.26350E-03 451140 + 463 451141 Rh-114m 2.57540E-03 2.57540E-03 451141 + 464 451150 Rh-115 2.29710E-03 2.38000E-03 451150 + 465 451160 Rh-116 1.47590E-04 1.55790E-04 451160 + 466 451161 Rh-116m 4.02310E-04 4.02310E-04 451161 + 467 451170 Rh-117 1.37030E-04 1.41500E-04 451170 + 468 451180 Rh-118 3.01890E-05 3.01890E-05 451180 + 469 451190 Rh-119 1.34520E-05 1.34520E-05 451190 + 470 451200 Rh-120 2.52480E-06 2.52480E-06 451200 + 471 461060 Pd-106 2.19820E-09 5.93040E-02 46106.82c + 472 461070 Pd-107 2.17760E-06 5.85460E-02 46107.82c + 473 461071 Pd-107m 4.78640E-06 4.78640E-06 461071 + 474 461080 Pd-108 5.24560E-05 5.61570E-02 46108.82c + 475 461090 Pd-109 7.92320E-05 4.96450E-02 461090 + 476 461091 Pd-109m 1.74150E-04 2.48700E-02 461091 + 477 461100 Pd-110 1.15620E-03 4.48950E-02 46110.82c + 478 461110 Pd-111 8.17370E-04 3.62740E-02 461110 + 479 461111 Pd-111m 1.79650E-03 1.93330E-03 461111 + 480 461120 Pd-112 5.81240E-03 2.85600E-02 461120 + 481 461130 Pd-113 1.73880E-03 2.12470E-02 461130 + 482 461131 Pd-113m 4.86520E-03 4.86520E-03 461131 + 483 461140 Pd-114 7.35180E-03 1.31910E-02 461140 + 484 461150 Pd-115 1.31160E-03 3.60430E-03 461150 + 485 461151 Pd-115m 2.88300E-03 3.22850E-03 461151 + 486 461160 Pd-116 2.48390E-03 3.04200E-03 461160 + 487 461170 Pd-117 2.53560E-04 9.53270E-04 461170 + 488 461171 Pd-117m 5.57330E-04 5.57330E-04 461171 + 489 461180 Pd-118 2.84030E-04 3.13340E-04 461180 + 490 461190 Pd-119 7.74610E-05 9.10630E-05 461190 + 491 461200 Pd-120 2.21150E-05 2.44900E-05 461200 + 492 461210 Pd-121 3.16490E-06 3.16490E-06 461210 + 493 461220 Pd-122 4.13480E-10 4.13480E-10 461220 + 494 461230 Pd-123 1.15420E-11 1.15420E-11 461230 + 495 461240 Pd-124 1.41380E-07 1.41380E-07 461240 + 496 471090 Ag-109 2.32870E-07 4.96470E-02 47109.82c + 497 471091 Ag-109m 1.74900E-06 4.96220E-02 471091 + 498 471100 Ag-110 2.13240E-06 2.21140E-06 471100 + 499 471101 Ag-110m 5.81240E-06 5.81240E-06 47510.82c + 500 471110 Ag-111 7.77990E-06 3.66800E-02 47111.82c + 501 471111 Ag-111m 5.84320E-05 3.64480E-02 471111 + 502 471120 Ag-112 1.92260E-04 2.87520E-02 471120 + 503 471130 Ag-113 7.93830E-05 1.43840E-02 471130 + 504 471131 Ag-113m 5.96220E-04 2.09420E-02 471131 + 505 471140 Ag-114 1.88030E-04 1.42900E-02 471140 + 506 471141 Ag-114m 9.11570E-04 9.11570E-04 471141 + 507 471150 Ag-115 2.17860E-04 4.02080E-03 471150 + 508 471151 Ag-115m 1.63620E-03 5.57970E-03 471151 + 509 471160 Ag-116 3.66550E-04 3.46850E-03 471160 + 510 471161 Ag-116m 9.99150E-04 9.99150E-04 471161 + 511 471170 Ag-117 1.39540E-04 7.07660E-04 471170 + 512 471171 Ag-117m 1.04810E-03 1.52470E-03 471171 + 513 471180 Ag-118 8.43170E-05 5.38820E-04 471180 + 514 471181 Ag-118m 4.08760E-04 4.53560E-04 471181 + 515 471190 Ag-119 3.15200E-05 7.70520E-05 471190 + 516 471191 Ag-119m 2.36740E-04 2.82270E-04 471191 + 517 471200 Ag-120 2.81900E-05 6.24180E-05 471200 + 518 471201 Ag-120m 4.71440E-05 5.93890E-05 471201 + 519 471210 Ag-121 4.85620E-05 5.17180E-05 471210 + 520 471220 Ag-122 1.82470E-05 1.82470E-05 471220 + 521 471221 Ag-122m 1.96720E-05 1.96720E-05 471221 + 522 471230 Ag-123 4.62780E-05 4.62780E-05 471230 + 523 471240 Ag-124 1.04250E-05 1.61870E-05 471240 + 524 471241 Ag-124m 1.12400E-05 1.12400E-05 471241 + 525 471250 Ag-125 7.92360E-06 7.92360E-06 471250 + 526 471260 Ag-126 2.20850E-06 2.20850E-06 471260 + 527 471270 Ag-127 1.80180E-07 1.80180E-07 471270 + 528 471280 Ag-128 7.46330E-09 7.46330E-09 471280 + 529 471290 Ag-129 4.68210E-10 4.68210E-10 471290 + 530 481110 Cd-111 2.18010E-10 3.68620E-02 48111.82c + 531 481111 Cd-111m 8.25590E-10 8.25590E-10 481111 + 532 481120 Cd-112 1.96850E-06 2.87540E-02 48112.82c + 533 481130 Cd-113 2.88240E-06 2.16770E-02 48113.82c + 534 481131 Cd-113m 1.09160E-05 2.59590E-04 481131 + 535 481140 Cd-114 4.10660E-05 1.43310E-02 48114.82c + 536 481150 Cd-115 2.33650E-05 8.09200E-03 481150 + 537 481151 Cd-115m 8.84840E-05 4.48500E-04 48515.82c + 538 481160 Cd-116 1.92000E-04 4.59970E-03 48116.82c + 539 481170 Cd-117 4.47990E-05 1.71090E-03 481170 + 540 481171 Cd-117m 1.69650E-04 6.44460E-04 481171 + 541 481180 Cd-118 2.20020E-04 1.02640E-03 481180 + 542 481190 Cd-119 4.00350E-05 3.60830E-04 481190 + 543 481191 Cd-119m 1.12020E-04 1.50540E-04 481191 + 544 481200 Cd-120 1.50280E-04 2.50110E-04 481200 + 545 481210 Cd-121 3.06930E-05 7.70070E-05 481210 + 546 481211 Cd-121m 8.58770E-05 9.12810E-05 481211 + 547 481220 Cd-122 1.48640E-04 1.86560E-04 481220 + 548 481230 Cd-123 4.47930E-05 8.26640E-05 481230 + 549 481231 Cd-123m 1.25330E-04 1.33750E-04 481231 + 550 481240 Cd-124 3.68650E-04 3.90440E-04 481240 + 551 481250 Cd-125 1.00900E-04 1.04860E-04 481250 + 552 481251 Cd-125m 2.82320E-04 2.86280E-04 481251 + 553 481260 Cd-126 3.16950E-04 3.19160E-04 481260 + 554 481270 Cd-127 1.13350E-04 1.13530E-04 481270 + 555 481280 Cd-128 4.76350E-05 4.76430E-05 481280 + 556 481290 Cd-129 2.39170E-06 2.39190E-06 481290 + 557 481291 Cd-129m 6.69170E-06 6.69200E-06 481291 + 558 481300 Cd-130 1.52440E-07 1.52440E-07 481300 + 559 481310 Cd-131 4.42270E-09 4.42270E-09 481310 + 560 491140 In-114 3.84520E-10 1.67740E-09 491140 + 561 491141 In-114m 6.20920E-10 1.33980E-09 491141 + 562 491142 In-114m 7.18860E-10 7.18860E-10 491142 + 563 491150 In-115 4.36390E-08 8.13600E-03 49115.82c + 564 491151 In-115m 8.78660E-09 8.09210E-03 491151 + 565 491160 In-116 8.08200E-07 8.08200E-07 491160 + 566 491161 In-116m 1.30510E-06 2.81600E-06 491161 + 567 491162 In-116m 1.51090E-06 1.51090E-06 491162 + 568 491170 In-117 8.99330E-06 1.53060E-03 491170 + 569 491171 In-117m 1.81070E-06 1.57950E-03 491171 + 570 491180 In-118 3.28860E-06 1.02970E-03 491180 + 571 491181 In-118m 5.31040E-06 1.13720E-05 491181 + 572 491182 In-118m 6.14800E-06 6.14800E-06 491182 + 573 491190 In-119 2.16680E-05 2.25470E-04 491190 + 574 491191 In-119m 4.36280E-06 3.30440E-04 491191 + 575 491200 In-120 8.73480E-06 2.58850E-04 491200 + 576 491201 In-120m 8.73480E-06 8.73480E-06 491201 + 577 491202 In-120m 8.73480E-06 8.73480E-06 491202 + 578 491210 In-121 4.62160E-05 1.64160E-04 491210 + 579 491211 In-121m 9.30530E-06 6.03770E-05 491211 + 580 491220 In-122 3.35140E-05 2.20070E-04 491220 + 581 491221 In-122m 2.80240E-05 2.80240E-05 491221 + 582 491222 In-122m 2.80240E-05 2.80240E-05 491222 + 583 491230 In-123 1.32920E-04 2.90640E-04 491230 + 584 491231 In-123m 2.67620E-05 8.54530E-05 491231 + 585 491240 In-124 1.35530E-04 5.25980E-04 491240 + 586 491241 In-124m 1.46120E-04 1.46120E-04 491241 + 587 491250 In-125 7.36930E-04 1.07340E-03 491250 + 588 491251 In-125m 1.48380E-04 2.03050E-04 491251 + 589 491260 In-126 6.00970E-04 9.20130E-04 491260 + 590 491261 In-126m 6.47930E-04 6.47930E-04 491261 + 591 491270 In-127 1.57040E-03 1.57040E-03 491270 + 592 491271 In-127m 3.16190E-04 4.29720E-04 491271 + 593 491280 In-128 4.93560E-04 7.34460E-04 491280 + 594 491281 In-128m 1.93260E-04 2.40900E-04 491281 + 595 491282 In-128m 7.40480E-04 7.40480E-04 491282 + 596 491290 In-129 7.81040E-04 7.87740E-04 491290 + 597 491291 In-129m 1.57260E-04 1.59650E-04 491291 + 598 491300 In-130 7.39290E-05 7.40760E-05 491300 + 599 491301 In-130m 1.07650E-04 1.07650E-04 491301 + 600 491302 In-130m 1.49950E-04 1.49950E-04 491302 + 601 491310 In-131 2.08000E-05 2.10160E-05 491310 + 602 491311 In-131m 2.08000E-05 2.08000E-05 491311 + 603 491312 In-131m 2.08000E-05 2.08000E-05 491312 + 604 491320 In-132 4.02600E-06 4.02600E-06 491320 + 605 491330 In-133 4.37070E-08 5.25070E-08 491330 + 606 491331 In-133m 8.80020E-09 8.80020E-09 491331 + 607 491340 In-134 1.53100E-09 1.53100E-09 491340 + 608 501160 Sn-116 1.61640E-10 3.62440E-06 50116.82c + 609 501170 Sn-117 4.26260E-10 2.36610E-03 50117.82c + 610 501171 Sn-117m 1.61420E-09 5.21640E-06 501171 + 611 501180 Sn-118 3.95340E-08 1.04120E-03 50118.82c + 612 501190 Sn-119 6.19430E-08 5.37700E-04 50119.82c + 613 501191 Sn-119m 2.34580E-07 2.03920E-04 501191 + 614 501200 Sn-120 2.21770E-06 2.78530E-04 50120.82c + 615 501210 Sn-121 6.22050E-07 2.21620E-04 501210 + 616 501211 Sn-121m 1.74040E-06 2.03370E-05 501211 + 617 501220 Sn-122 1.23460E-05 2.88480E-04 50122.82c + 618 501230 Sn-123 2.22650E-05 4.44240E-05 50123.82c + 619 501231 Sn-123m 7.95770E-06 3.61890E-04 501231 + 620 501240 Sn-124 1.51710E-04 8.23810E-04 50124.82c + 621 501250 Sn-125 2.58750E-04 4.40070E-04 50125.82c + 622 501251 Sn-125m 9.24790E-05 1.18760E-03 501251 + 623 501260 Sn-126 1.43140E-03 3.00240E-03 50126.82c + 624 501270 Sn-127 2.22720E-03 2.83930E-03 501270 + 625 501271 Sn-127m 7.96010E-04 2.18110E-03 501271 + 626 501280 Sn-128 1.81600E-03 8.24090E-03 501280 + 627 501281 Sn-128m 4.95000E-03 5.69050E-03 501281 + 628 501290 Sn-129 1.85630E-03 2.71990E-03 501290 + 629 501291 Sn-129m 5.19380E-03 5.27770E-03 501291 + 630 501300 Sn-130 1.99380E-03 2.19660E-03 501300 + 631 501301 Sn-130m 5.43470E-03 5.56400E-03 501301 + 632 501310 Sn-131 1.00440E-03 1.04470E-03 501310 + 633 501311 Sn-131m 2.81010E-03 2.83180E-03 501311 + 634 501320 Sn-132 1.48690E-03 1.49100E-03 501320 + 635 501330 Sn-133 1.52490E-04 1.52500E-04 501330 + 636 501340 Sn-134 2.34570E-05 2.34580E-05 501340 + 637 501350 Sn-135 3.81900E-07 3.81900E-07 501350 + 638 501360 Sn-136 1.25630E-08 1.25630E-08 501360 + 639 511190 Sb-119 5.92950E-11 8.31050E-11 511190 + 640 511191 Sb-119m 2.38100E-11 2.38100E-11 511191 + 641 511200 Sb-120 4.95520E-10 4.95520E-10 511200 + 642 511201 Sb-120m 8.28680E-10 8.28680E-10 511201 + 643 511210 Sb-121 3.46490E-08 2.26210E-04 51121.82c + 644 511220 Sb-122 2.08140E-07 4.87000E-07 511220 + 645 511221 Sb-122m 2.78860E-07 2.78860E-07 511221 + 646 511230 Sb-123 7.53300E-06 4.13850E-04 51123.82c + 647 511240 Sb-124 3.62150E-06 9.32050E-06 51124.82c + 648 511241 Sb-124m 2.92140E-06 7.59860E-06 511241 + 649 511242 Sb-124m 4.67720E-06 4.67720E-06 511242 + 650 511250 Sb-125 4.15040E-05 1.66920E-03 51125.82c + 651 511260 Sb-126 4.07910E-05 4.87790E-05 51126.82c + 652 511261 Sb-126m 2.54780E-05 5.70620E-05 511261 + 653 511262 Sb-126m 3.15840E-05 3.15840E-05 511262 + 654 511270 Sb-127 5.23720E-04 5.54410E-03 511270 + 655 511280 Sb-128 6.64120E-04 8.93850E-03 511280 + 656 511281 Sb-128m 9.28880E-04 9.28880E-04 511281 + 657 511290 Sb-129 3.70620E-03 9.87220E-03 511290 + 658 511291 Sb-129m 2.74280E-03 5.38150E-03 511291 + 659 511300 Sb-130 5.39400E-03 1.03730E-02 511300 + 660 511301 Sb-130m 5.39400E-03 8.17600E-03 511301 + 661 511310 Sb-131 1.93170E-02 2.31930E-02 511310 + 662 511320 Sb-132 8.32140E-03 9.81240E-03 511320 + 663 511321 Sb-132m 7.36750E-03 7.36750E-03 511321 + 664 511330 Sb-133 1.12320E-02 1.13880E-02 511330 + 665 511340 Sb-134 7.25140E-04 7.44650E-04 511340 + 666 511341 Sb-134m 1.97660E-03 1.97660E-03 511341 + 667 511350 Sb-135 6.74420E-04 6.74730E-04 511350 + 668 511360 Sb-136 1.01840E-04 1.01850E-04 511360 + 669 511370 Sb-137 1.10090E-05 1.10090E-05 511370 + 670 511380 Sb-138 4.77980E-08 4.77980E-08 511380 + 671 511390 Sb-139 1.59700E-09 1.59700E-09 511390 + 672 521210 Te-121 1.33760E-12 5.83060E-12 521210 + 673 521211 Te-121m 5.06540E-12 5.06540E-12 521211 + 674 521220 Te-122 3.39260E-10 4.74680E-07 52122.82c + 675 521230 Te-123 2.51730E-09 1.20500E-08 52123.82c + 676 521231 Te-123m 9.53280E-09 9.53280E-09 521231 + 677 521250 Te-125 6.12850E-11 1.66920E-03 52125.82c + 678 521251 Te-125m 2.32090E-10 3.73510E-04 521251 + 679 521260 Te-126 2.20420E-06 1.00060E-04 52126.82c + 680 521270 Te-127 4.36210E-06 5.53840E-03 521270 + 681 521271 Te-127m 1.22050E-05 9.25840E-04 52527.82c + 682 521280 Te-128 9.51490E-05 9.92910E-03 52128.82c + 683 521290 Te-129 1.37060E-04 1.25660E-02 521290 + 684 521291 Te-129m 3.83490E-04 6.48900E-03 52529.82c + 685 521300 Te-130 2.93540E-03 2.14840E-02 52130.82c + 686 521310 Te-131 2.05660E-03 2.49910E-02 521310 + 687 521311 Te-131m 5.75410E-03 7.61100E-03 521311 + 688 521320 Te-132 2.33490E-02 4.05290E-02 52132.82c + 689 521330 Te-133 8.72550E-03 2.27630E-02 521330 + 690 521331 Te-133m 2.44140E-02 2.63830E-02 521331 + 691 521340 Te-134 3.70480E-02 3.98740E-02 521340 + 692 521350 Te-135 1.39750E-02 1.45600E-02 521350 + 693 521360 Te-136 6.10130E-03 6.19170E-03 521360 + 694 521370 Te-137 1.35780E-03 1.36340E-03 521370 + 695 521380 Te-138 2.94840E-04 2.94890E-04 521380 + 696 521390 Te-139 1.79710E-05 1.79730E-05 521390 + 697 521400 Te-140 3.99880E-06 3.99880E-06 521400 + 698 521410 Te-141 6.67250E-09 6.67250E-09 521410 + 699 531270 I-127 1.78180E-10 5.56070E-03 53127.82c + 700 531280 I-128 9.63010E-09 9.63010E-09 531280 + 701 531290 I-129 2.00910E-06 1.49690E-02 53129.82c + 702 531300 I-130 3.31890E-05 4.34170E-05 53130.82c + 703 531301 I-130m 1.21760E-05 1.21760E-05 531301 + 704 531310 I-131 3.00130E-04 3.13040E-02 53131.82c + 705 531320 I-132 7.70350E-04 4.18860E-02 531320 + 706 531321 I-132m 6.82050E-04 6.82050E-04 531321 + 707 531330 I-133 4.41130E-03 5.22050E-02 531330 + 708 531331 I-133m 3.26450E-03 3.26450E-03 531331 + 709 531340 I-134 1.10840E-02 6.05450E-02 531340 + 710 531341 I-134m 9.81320E-03 9.81320E-03 531341 + 711 531350 I-135 4.44730E-02 5.90330E-02 53135.82c + 712 531360 I-136 7.79970E-03 1.40120E-02 531360 + 713 531361 I-136m 2.12600E-02 2.12810E-02 531361 + 714 531370 I-137 2.07360E-02 2.20770E-02 531370 + 715 531380 I-138 6.91000E-03 7.18630E-03 531380 + 716 531390 I-139 3.79830E-03 3.81630E-03 531390 + 717 531400 I-140 7.67400E-04 7.71400E-04 531400 + 718 531410 I-141 1.72300E-04 1.72310E-04 531410 + 719 531420 I-142 2.16010E-05 2.16010E-05 531420 + 720 531430 I-143 4.65050E-08 4.65050E-08 531430 + 721 531440 I-144 9.82860E-10 9.82860E-10 531440 + 722 541300 Xe-130 4.73890E-09 4.53700E-05 54130.82c + 723 541310 Xe-131 5.31020E-07 3.13060E-02 54131.82c + 724 541311 Xe-131m 1.48580E-06 3.41510E-04 541311 + 725 541320 Xe-132 1.11880E-05 4.20080E-02 54132.82c + 726 541321 Xe-132m 1.49890E-05 1.49890E-05 541321 + 727 541330 Xe-133 5.05960E-05 5.23970E-02 54133.82c + 728 541331 Xe-133m 1.41560E-04 1.62750E-03 541331 + 729 541340 Xe-134 5.18820E-04 6.27040E-02 54134.82c + 730 541341 Xe-134m 1.41420E-03 1.63990E-03 541341 + 731 541350 Xe-135 2.27690E-03 6.75840E-02 54135.82c + 732 541351 Xe-135m 6.37050E-03 1.61160E-02 541351 + 733 541360 Xe-136 3.29600E-02 6.96870E-02 54136.82c + 734 541370 Xe-137 3.57740E-02 5.67970E-02 541370 + 735 541380 Xe-138 3.89990E-02 4.61780E-02 541380 + 736 541390 Xe-139 2.13540E-02 2.48680E-02 541390 + 737 541400 Xe-140 1.58000E-02 1.65360E-02 541400 + 738 541410 Xe-141 5.60960E-03 5.75110E-03 541410 + 739 541420 Xe-142 1.87910E-03 1.89530E-03 541420 + 740 541430 Xe-143 3.05660E-04 3.05690E-04 541430 + 741 541440 Xe-144 6.01390E-05 6.01400E-05 541440 + 742 541450 Xe-145 2.97610E-06 2.97610E-06 541450 + 743 541460 Xe-146 5.39300E-09 5.39300E-09 541460 + 744 551320 Cs-132 1.00760E-09 1.00760E-09 551320 + 745 551330 Cs-133 1.00470E-06 5.23980E-02 55133.82c + 746 551340 Cs-134 1.62330E-06 3.06050E-06 55134.82c + 747 551341 Cs-134m 1.43720E-06 1.43720E-06 551341 + 748 551350 Cs-135 4.20860E-05 6.77540E-02 55135.82c + 749 551351 Cs-135m 3.11450E-05 3.11450E-05 551351 + 750 551360 Cs-136 4.55140E-04 6.17840E-04 55136.82c + 751 551361 Cs-136m 3.25410E-04 3.25410E-04 551361 + 752 551370 Cs-137 5.81470E-03 6.26120E-02 55137.82c + 753 551380 Cs-138 4.55550E-03 5.69050E-02 551380 + 754 551381 Cs-138m 7.61850E-03 7.61850E-03 551381 + 755 551390 Cs-139 2.23330E-02 4.72010E-02 551390 + 756 551400 Cs-140 2.07890E-02 3.73270E-02 551400 + 757 551410 Cs-141 2.59130E-02 3.16680E-02 551410 + 758 551420 Cs-142 1.48440E-02 1.67360E-02 551420 + 759 551430 Cs-143 8.38110E-03 8.68550E-03 551430 + 760 551440 Cs-144 1.37310E-03 2.11800E-03 551440 + 761 551441 Cs-144m 1.37310E-03 1.37310E-03 551441 + 762 551450 Cs-145 7.29230E-04 7.32060E-04 551450 + 763 551460 Cs-146 1.26410E-04 1.26420E-04 551460 + 764 551470 Cs-147 1.88020E-05 1.88020E-05 551470 + 765 551480 Cs-148 2.22790E-08 2.22790E-08 551480 + 766 551490 Cs-149 6.38040E-10 6.38040E-10 551490 + 767 561350 Ba-135 2.51380E-09 9.54720E-09 56135.82c + 768 561351 Ba-135m 7.03340E-09 7.03340E-09 561351 + 769 561360 Ba-136 1.34130E-06 7.85550E-04 56136.82c + 770 561361 Ba-136m 3.65610E-06 3.65610E-06 561361 + 771 561370 Ba-137 2.21570E-05 6.26960E-02 56137.82c + 772 561371 Ba-137m 6.19950E-05 5.91670E-02 561371 + 773 561380 Ba-138 1.04500E-03 5.93970E-02 56138.82c + 774 561390 Ba-139 3.23160E-03 5.04330E-02 561390 + 775 561400 Ba-140 1.01570E-02 4.74840E-02 56140.82c + 776 561410 Ba-141 1.45430E-02 4.62110E-02 561410 + 777 561420 Ba-142 2.92770E-02 4.61550E-02 561420 + 778 561430 Ba-143 2.63260E-02 3.49370E-02 561430 + 779 561440 Ba-144 2.38690E-02 2.67110E-02 561440 + 780 561450 Ba-145 1.06260E-02 1.12710E-02 561450 + 781 561460 Ba-146 5.14220E-03 5.25600E-03 561460 + 782 561470 Ba-147 1.45550E-03 1.46890E-03 561470 + 783 561480 Ba-148 3.65150E-04 3.65170E-04 561480 + 784 561490 Ba-149 4.77240E-05 4.77250E-05 561490 + 785 561500 Ba-150 3.97780E-06 3.97780E-06 561500 + 786 561510 Ba-151 2.00410E-09 2.00410E-09 561510 + 787 571370 La-137 1.99990E-09 1.99990E-09 571370 + 788 571380 La-138 2.01720E-06 2.01720E-06 57138.82c + 789 571390 La-139 3.39650E-05 5.04670E-02 57139.82c + 790 571400 La-140 1.46190E-04 4.76310E-02 57140.82c + 791 571410 La-141 7.67410E-04 4.69790E-02 571410 + 792 571420 La-142 1.97900E-03 4.81340E-02 571420 + 793 571430 La-143 6.90990E-03 4.18470E-02 571430 + 794 571440 La-144 1.16520E-02 3.83630E-02 571440 + 795 571450 La-145 1.76770E-02 2.89480E-02 571450 + 796 571460 La-146 4.20610E-03 9.46210E-03 571460 + 797 571461 La-146m 8.82390E-03 8.82390E-03 571461 + 798 571470 La-147 1.12580E-02 1.27280E-02 571470 + 799 571480 La-148 4.98560E-03 5.34950E-03 571480 + 800 571490 La-149 1.96650E-03 2.01400E-03 571490 + 801 571500 La-150 4.51360E-04 4.55340E-04 571500 + 802 571510 La-151 7.32520E-05 7.32540E-05 571510 + 803 571520 La-152 1.18340E-05 1.18340E-05 571520 + 804 571530 La-153 1.07300E-08 1.07300E-08 571530 + 805 571540 La-154 1.85990E-10 1.85990E-10 571540 + 806 581400 Ce-140 9.99750E-07 4.76320E-02 58140.82c + 807 581410 Ce-141 1.19720E-05 4.69910E-02 58141.82c + 808 581420 Ce-142 9.73540E-05 4.82310E-02 58142.82c + 809 581430 Ce-143 3.63570E-04 4.22100E-02 58143.82c + 810 581440 Ce-144 1.79670E-03 4.01590E-02 58144.82c + 811 581450 Ce-145 4.50890E-03 3.34570E-02 581450 + 812 581460 Ce-146 1.08570E-02 2.91430E-02 581460 + 813 581470 Ce-147 1.36640E-02 2.63920E-02 581470 + 814 581480 Ce-148 1.73200E-02 2.26980E-02 581480 + 815 581490 Ce-149 1.13040E-02 1.33020E-02 581490 + 816 581500 Ce-150 7.35750E-03 7.80050E-03 581500 + 817 581510 Ce-151 2.54660E-03 2.62060E-03 581510 + 818 581520 Ce-152 8.82130E-04 8.93250E-04 581520 + 819 581530 Ce-153 1.31600E-04 1.31610E-04 581530 + 820 581540 Ce-154 2.48290E-05 2.48290E-05 581540 + 821 581550 Ce-155 3.52090E-08 3.52090E-08 581550 + 822 581560 Ce-156 9.41200E-10 9.41200E-10 581560 + 823 591420 Pr-142 3.07990E-10 1.14750E-09 59142.82c + 824 591421 Pr-142m 8.39510E-10 8.39510E-10 591421 + 825 591430 Pr-143 9.92010E-07 4.22110E-02 59143.82c + 826 591440 Pr-144 1.61630E-06 4.01770E-02 591440 + 827 591441 Pr-144m 1.64430E-05 5.70620E-04 591441 + 828 591450 Pr-145 8.04500E-05 3.35380E-02 591450 + 829 591460 Pr-146 2.90760E-04 2.94340E-02 591460 + 830 591470 Pr-147 1.21480E-03 2.76070E-02 591470 + 831 591480 Pr-148 4.73070E-04 2.31710E-02 591480 + 832 591481 Pr-148m 2.29340E-03 2.29340E-03 591481 + 833 591490 Pr-149 6.15590E-03 1.94580E-02 591490 + 834 591500 Pr-150 6.87270E-03 1.46730E-02 591500 + 835 591510 Pr-151 7.22810E-03 9.84870E-03 591510 + 836 591520 Pr-152 4.14990E-03 5.04400E-03 591520 + 837 591530 Pr-153 2.18450E-03 2.31550E-03 591530 + 838 591540 Pr-154 7.22840E-04 7.47510E-04 591540 + 839 591550 Pr-155 1.59990E-04 1.60030E-04 591550 + 840 591560 Pr-156 1.99320E-05 1.99330E-05 591560 + 841 591570 Pr-157 6.00880E-06 6.00880E-06 591570 + 842 591580 Pr-158 2.35840E-09 2.35840E-09 591580 + 843 591590 Pr-159 5.29500E-11 5.29500E-11 591590 + 844 601450 Nd-145 4.75760E-09 3.35380E-02 60145.82c + 845 601460 Nd-146 6.92390E-06 2.94410E-02 60146.82c + 846 601470 Nd-147 3.36740E-05 2.76410E-02 60147.82c + 847 601480 Nd-148 2.30010E-04 2.56940E-02 60148.82c + 848 601490 Nd-149 7.30510E-04 2.01890E-02 601490 + 849 601500 Nd-150 2.39970E-03 1.70730E-02 60150.82c + 850 601510 Nd-151 4.18280E-03 1.40320E-02 601510 + 851 601520 Nd-152 6.43450E-03 1.14790E-02 601520 + 852 601530 Nd-153 5.68610E-03 8.00150E-03 601530 + 853 601540 Nd-154 4.75370E-03 5.50120E-03 601540 + 854 601550 Nd-155 2.13350E-03 2.29410E-03 601550 + 855 601560 Nd-156 9.75840E-04 9.95620E-04 601560 + 856 601570 Nd-157 2.43740E-04 2.49360E-04 601570 + 857 601580 Nd-158 5.41020E-05 5.41040E-05 601580 + 858 601590 Nd-159 6.00170E-06 6.00170E-06 601590 + 859 601600 Nd-160 1.02710E-08 1.02710E-08 601600 + 860 601610 Nd-161 1.38890E-10 1.38890E-10 601610 + 861 611470 Pm-147 8.66610E-10 2.76410E-02 61147.82c + 862 611480 Pm-148 5.64770E-09 6.41740E-09 61148.82c + 863 611481 Pm-148m 1.53940E-08 1.53940E-08 61548.82c + 864 611490 Pm-149 3.97980E-06 2.01920E-02 61149.82c + 865 611500 Pm-150 3.18410E-05 3.18410E-05 611500 + 866 611510 Pm-151 1.50910E-04 1.41820E-02 61151.82c + 867 611520 Pm-152 7.45440E-05 1.15530E-02 611520 + 868 611521 Pm-152m 1.56720E-04 1.56720E-04 611521 + 869 611522 Pm-152m 2.04710E-04 2.04710E-04 611522 + 870 611530 Pm-153 1.15200E-03 9.15350E-03 611530 + 871 611540 Pm-154 9.11450E-04 6.41270E-03 611540 + 872 611541 Pm-154m 9.11450E-04 9.11450E-04 611541 + 873 611550 Pm-155 2.42690E-03 4.72100E-03 611550 + 874 611560 Pm-156 1.80270E-03 2.79830E-03 611560 + 875 611570 Pm-157 1.33880E-03 1.58820E-03 611570 + 876 611580 Pm-158 5.37460E-04 5.91580E-04 611580 + 877 611590 Pm-159 1.95720E-04 2.01710E-04 611590 + 878 611600 Pm-160 3.69750E-05 3.69850E-05 611600 + 879 611610 Pm-161 1.35370E-05 1.35370E-05 611610 + 880 611620 Pm-162 1.85840E-06 1.85840E-06 611620 + 881 611630 Pm-163 4.01710E-10 4.01710E-10 611630 + 882 621500 Sm-150 3.16400E-09 3.18440E-05 62150.82c + 883 621510 Sm-151 9.90900E-07 1.41830E-02 62151.82c + 884 621520 Sm-152 2.26940E-05 1.19370E-02 62152.82c + 885 621530 Sm-153 2.27310E-05 9.23990E-03 62153.82c + 886 621531 Sm-153m 6.36000E-05 6.36000E-05 621531 + 887 621540 Sm-154 3.50030E-04 7.67410E-03 62154.82c + 888 621550 Sm-155 6.98540E-04 5.41950E-03 621550 + 889 621560 Sm-156 1.42690E-03 4.22520E-03 621560 + 890 621570 Sm-157 1.61140E-03 3.19960E-03 621570 + 891 621580 Sm-158 1.62900E-03 2.22060E-03 621580 + 892 621590 Sm-159 9.90080E-04 1.19180E-03 621590 + 893 621600 Sm-160 5.56660E-04 5.93550E-04 621600 + 894 621610 Sm-161 1.78750E-04 1.92290E-04 621610 + 895 621620 Sm-162 6.54300E-05 6.72880E-05 621620 + 896 621630 Sm-163 9.04180E-06 9.04220E-06 621630 + 897 621640 Sm-164 4.20140E-08 4.20140E-08 621640 + 898 621650 Sm-165 7.75190E-10 7.75190E-10 621650 + 899 631520 Eu-152 1.12440E-10 2.61360E-10 63152.82c + 900 631521 Eu-152m 2.56910E-11 2.56910E-11 631521 + 901 631522 Eu-152m 1.48920E-10 1.48920E-10 631522 + 902 631530 Eu-153 9.91200E-07 9.24090E-03 63153.82c + 903 631540 Eu-154 1.43460E-06 2.98120E-06 63154.82c + 904 631541 Eu-154m 1.54670E-06 1.54670E-06 631541 + 905 631550 Eu-155 1.39480E-05 5.43350E-03 63155.82c + 906 631560 Eu-156 4.09590E-05 4.26620E-03 63156.82c + 907 631570 Eu-157 1.41160E-04 3.34070E-03 63157.82c + 908 631580 Eu-158 2.52470E-04 2.47310E-03 631580 + 909 631590 Eu-159 4.27680E-04 1.61950E-03 631590 + 910 631600 Eu-160 4.14500E-04 1.00800E-03 631600 + 911 631610 Eu-161 3.97370E-04 5.89660E-04 631610 + 912 631620 Eu-162 1.69410E-04 2.36700E-04 631620 + 913 631630 Eu-163 9.27540E-05 1.01800E-04 631630 + 914 631640 Eu-164 2.39780E-05 2.40200E-05 631640 + 915 631650 Eu-165 1.82800E-06 1.82880E-06 631650 + 916 631660 Eu-166 4.21040E-08 4.21040E-08 631660 + 917 631670 Eu-167 2.05290E-09 2.05290E-09 631670 + 918 641550 Gd-155 2.62090E-07 5.43450E-03 64155.82c + 919 641551 Gd-155m 7.33300E-07 7.33300E-07 641551 + 920 641560 Gd-156 1.99310E-06 4.26820E-03 64156.82c + 921 641570 Gd-157 2.00250E-06 3.34270E-03 64157.82c + 922 641580 Gd-158 2.59580E-05 2.49900E-03 64158.82c + 923 641590 Gd-159 6.82260E-05 1.68780E-03 641590 + 924 641600 Gd-160 1.77440E-04 1.18550E-03 64160.82c + 925 641610 Gd-161 2.28570E-04 8.18230E-04 641610 + 926 641620 Gd-162 2.88780E-04 5.25480E-04 641620 + 927 641630 Gd-163 1.80860E-04 2.82660E-04 641630 + 928 641640 Gd-164 1.31480E-04 1.55500E-04 641640 + 929 641650 Gd-165 5.12220E-05 5.30510E-05 641650 + 930 641660 Gd-166 1.85260E-05 1.85680E-05 641660 + 931 641670 Gd-167 3.58350E-06 3.58550E-06 641670 + 932 641680 Gd-168 1.08210E-07 1.08210E-07 641680 + 933 641690 Gd-169 2.01360E-09 2.01360E-09 641690 + 934 651570 Tb-157 1.05150E-10 1.05150E-10 651570 + 935 651580 Tb-158 1.76200E-09 1.93410E-09 651580 + 936 651581 Tb-158m 1.73200E-10 1.73200E-10 651581 + 937 651590 Tb-159 5.48560E-08 1.68780E-03 65159.82c + 938 651600 Tb-160 9.72650E-07 9.72650E-07 65160.82c + 939 651610 Tb-161 4.82850E-06 8.23060E-04 651610 + 940 651620 Tb-162 1.39090E-05 5.39390E-04 651620 + 941 651630 Tb-163 3.32800E-05 3.15940E-04 651630 + 942 651640 Tb-164 3.81800E-05 1.93680E-04 651640 + 943 651650 Tb-165 4.74530E-05 1.00500E-04 651650 + 944 651660 Tb-166 2.77670E-05 4.63350E-05 651660 + 945 651670 Tb-167 2.32980E-05 2.68840E-05 651670 + 946 651680 Tb-168 7.49760E-06 7.60580E-06 651680 + 947 651690 Tb-169 2.96220E-06 2.96420E-06 651690 + 948 651700 Tb-170 2.74100E-08 2.74100E-08 651700 + 949 651710 Tb-171 3.73700E-09 3.73700E-09 651710 + 950 661600 Dy-160 1.73350E-10 9.72820E-07 66160.82c + 951 661610 Dy-161 4.44460E-09 8.23060E-04 66161.82c + 952 661620 Dy-162 9.46270E-08 5.39480E-04 66162.82c + 953 661630 Dy-163 2.70820E-06 3.18640E-04 66163.82c + 954 661640 Dy-164 1.70150E-06 1.95380E-04 66164.82c + 955 661650 Dy-165 9.66690E-06 1.11430E-04 661650 + 956 661651 Dy-165m 1.28710E-06 1.28710E-06 661651 + 957 661660 Dy-166 2.77320E-05 7.40670E-05 661660 + 958 661670 Dy-167 2.32740E-05 5.01580E-05 661670 + 959 661680 Dy-168 2.43570E-05 3.19630E-05 661680 + 960 661690 Dy-169 5.92380E-06 8.88800E-06 661690 + 961 661700 Dy-170 1.78810E-06 1.81550E-06 661700 + 962 661710 Dy-171 9.85040E-07 9.88780E-07 661710 + 963 661720 Dy-172 9.40560E-08 9.40560E-08 661720 + 964 661730 Dy-173 3.48880E-09 3.48880E-09 661730 + 965 671620 Ho-162 3.52490E-12 9.48190E-12 671620 + 966 671621 Ho-162m 9.60810E-12 9.60810E-12 671621 + 967 671630 Ho-163 2.74740E-10 3.11320E-10 671630 + 968 671631 Ho-163m 3.65800E-11 3.65800E-11 671631 + 969 671640 Ho-164 1.27440E-09 4.74830E-09 671640 + 970 671641 Ho-164m 3.47390E-09 3.47390E-09 671641 + 971 671650 Ho-165 6.63570E-08 1.11520E-04 67165.82c + 972 671660 Ho-166 1.00380E-07 7.41680E-05 671660 + 973 671661 Ho-166m 2.73630E-07 2.73630E-07 671661 + 974 671670 Ho-167 2.15170E-06 5.23090E-05 671670 + 975 671680 Ho-168 1.40210E-06 3.56980E-05 671680 + 976 671681 Ho-168m 2.34490E-06 2.34490E-06 671681 + 977 671690 Ho-169 1.97440E-06 1.08620E-05 671690 + 978 671700 Ho-170 1.96210E-06 1.96210E-06 671700 + 979 671701 Ho-170m 7.19850E-07 2.53540E-06 671701 + 980 671710 Ho-171 9.85000E-07 1.97380E-06 671710 + 981 671720 Ho-172 1.87700E-06 1.97110E-06 671720 + 982 671730 Ho-173 2.76270E-07 2.79760E-07 671730 + 983 671740 Ho-174 7.29770E-08 7.29770E-08 671740 + 984 671750 Ho-175 1.48890E-08 1.48890E-08 671750 + 985 681650 Er-165 1.26040E-11 1.26040E-11 681650 + 986 681660 Er-166 5.03430E-10 7.41680E-05 68166.82c + 987 681670 Er-167 5.75690E-09 5.23160E-05 68167.82c + 988 681671 Er-167m 7.66500E-10 6.25130E-06 681671 + 989 681680 Er-168 8.69950E-08 3.57970E-05 68168.82c + 990 681690 Er-169 9.87200E-07 1.18500E-05 681690 + 991 681700 Er-170 4.70910E-07 4.96840E-06 68170.82c + 992 681710 Er-171 2.95470E-06 4.92850E-06 681710 + 993 681720 Er-172 1.87690E-06 3.84800E-06 681720 + 994 681730 Er-173 1.45770E-06 1.73750E-06 681730 + 995 681740 Er-174 9.40010E-07 1.01300E-06 681740 + 996 681750 Er-175 9.14720E-07 9.29610E-07 681750 + 997 681760 Er-176 4.29230E-08 4.29230E-08 681760 + 998 681770 Er-177 2.93890E-09 2.93890E-09 681770 + 999 691670 Tm-167 1.57550E-12 1.57550E-12 691670 + 1000 691680 Tm-168 2.58090E-11 2.58090E-11 691680 + 1001 691690 Tm-169 3.61720E-10 1.18500E-05 691690 + 1002 691700 Tm-170 1.99380E-09 1.99380E-09 691700 + 1003 691710 Tm-171 3.16640E-08 4.96010E-06 691710 + 1004 691720 Tm-172 1.21910E-07 3.96990E-06 691720 + 1005 691730 Tm-173 2.44140E-07 1.98160E-06 691730 + 1006 691740 Tm-174 9.39970E-07 1.95300E-06 691740 + 1007 691750 Tm-175 9.14680E-07 1.84430E-06 691750 + 1008 691760 Tm-176 1.79360E-07 2.22280E-07 691760 + 1009 691770 Tm-177 6.67650E-08 6.97040E-08 691770 + 1010 691780 Tm-178 1.53330E-08 1.53330E-08 691780 + 1011 691790 Tm-179 3.38520E-09 3.38520E-09 691790 + 1012 701710 Yb-171 2.92880E-12 4.96020E-06 701710 + 1013 701711 Yb-171m 2.19970E-11 2.19970E-11 701711 + 1014 701720 Yb-172 6.16360E-10 3.97050E-06 701720 + 1015 701730 Yb-173 2.67540E-09 1.98430E-06 701730 + 1016 701740 Yb-174 3.82930E-08 1.99130E-06 701740 + 1017 701750 Yb-175 1.29050E-07 1.99050E-06 701750 + 1018 701751 Yb-175m 1.71820E-08 1.43730E-06 701751 + 1019 701760 Yb-176 3.66960E-08 3.17150E-07 701760 + 1020 701761 Yb-176m 7.69840E-08 1.88130E-07 701761 + 1021 701770 Yb-177 1.24640E-07 2.19440E-07 701770 + 1022 701771 Yb-177m 2.50960E-08 9.48000E-08 701771 + 1023 701780 Yb-178 8.42570E-08 9.95900E-08 701780 + 1024 701790 Yb-179 3.42390E-08 3.76240E-08 701790 + 1025 701800 Yb-180 1.42600E-08 1.42600E-08 701800 + 1026 701810 Yb-181 2.07010E-09 2.07010E-09 701810 + 1027 711730 Lu-173 1.32790E-12 1.32790E-12 711730 + 1028 711740 Lu-174 1.14850E-11 4.26100E-11 711740 + 1029 711741 Lu-174m 3.13070E-11 3.13070E-11 711741 + 1030 711750 Lu-175 1.03280E-09 1.99160E-06 71175.82c + 1031 711760 Lu-176 1.14920E-09 1.99620E-08 71176.82c + 1032 711761 Lu-176m 5.47790E-10 5.47790E-10 711761 + 1033 711770 Lu-177 4.14740E-09 2.24050E-07 711770 + 1034 711771 Lu-177m 1.97480E-09 2.02400E-09 711771 + 1035 711772 Lu-177m 9.82740E-11 9.82740E-11 711772 + 1036 711780 Lu-178 5.66430E-09 1.05250E-07 711780 + 1037 711781 Lu-178m 7.58870E-09 7.58870E-09 711781 + 1038 711790 Lu-179 2.38660E-08 6.46680E-08 711790 + 1039 711791 Lu-179m 3.17770E-09 4.08020E-08 711791 + 1040 711800 Lu-180 5.17300E-09 1.94700E-08 711800 + 1041 711801 Lu-180m 5.17300E-09 1.94330E-08 711801 + 1042 711802 Lu-180m 9.16000E-09 9.16000E-09 711802 + 1043 711810 Lu-181 1.44530E-08 1.65230E-08 711810 + 1044 711820 Lu-182 4.24720E-09 4.24720E-09 711820 + 1045 711830 Lu-183 1.45390E-09 1.45390E-09 711830 + 1046 711840 Lu-184 1.63350E-10 1.63350E-10 711840 + 1047 721760 Hf-176 2.22900E-12 5.49500E-10 72176.82c + 1048 721770 Hf-177 1.22500E-11 2.25680E-07 72177.82c + 1049 721771 Hf-177m 5.77950E-12 1.62180E-09 721771 + 1050 721772 Hf-177m 3.41700E-13 4.94790E-11 721772 + 1051 721780 Hf-178 7.82180E-11 1.13080E-07 72178.82c + 1052 721781 Hf-178m 1.45870E-10 7.75280E-09 721781 + 1053 721782 Hf-178m 1.82460E-11 1.82460E-11 721782 + 1054 721790 Hf-179 5.88180E-10 6.56860E-08 72179.82c + 1055 721791 Hf-179m 1.70200E-10 1.70200E-10 721791 + 1056 721792 Hf-179m 2.57120E-10 2.57120E-10 721792 + 1057 721800 Hf-180 1.29720E-09 3.77680E-08 72180.82c + 1058 721801 Hf-180m 2.72150E-09 7.30150E-09 721801 + 1059 721810 Hf-181 5.36280E-09 2.18860E-08 721810 + 1060 721820 Hf-182 2.52010E-09 8.98770E-09 721820 + 1061 721821 Hf-182m 5.28680E-09 5.28680E-09 721821 + 1062 721830 Hf-183 4.67620E-09 6.13010E-09 721830 + 1063 721840 Hf-184 8.90860E-10 9.72540E-10 721840 + 1064 721841 Hf-184m 1.86890E-09 1.95060E-09 721841 + 1065 721850 Hf-185 6.89640E-10 6.89640E-10 721850 + 1066 721860 Hf-186 1.87370E-10 1.87370E-10 721860 + 1067 721870 Hf-187 1.69540E-11 1.69540E-11 721870 + 1068 721880 Hf-188 1.47380E-12 1.47380E-12 721880 + 1069 731790 Ta-179 1.34990E-12 1.89200E-12 731790 + 1070 731800 Ta-180 7.08630E-12 7.08630E-12 731800 + 1071 731801 Ta-180m 9.49370E-12 3.21280E-11 731801 + 1072 731810 Ta-181 1.33620E-10 2.20200E-08 73181.82c + 1073 731820 Ta-182 1.24890E-10 3.45330E-09 73182.82c + 1074 731821 Ta-182m 1.36420E-10 3.32840E-09 731821 + 1075 731822 Ta-182m 1.25620E-10 3.19200E-09 731822 + 1076 731830 Ta-183 1.22930E-09 7.35940E-09 731830 + 1077 731840 Ta-184 1.27630E-09 4.19940E-09 731840 + 1078 731850 Ta-185 9.87740E-10 2.26670E-09 731850 + 1079 731851 Ta-185m 5.89360E-10 5.89360E-10 731851 + 1080 731860 Ta-186 7.65530E-10 9.52900E-10 731860 + 1081 731870 Ta-187 3.76060E-10 3.93010E-10 731870 + 1082 731880 Ta-188 6.65020E-11 6.79760E-11 731880 + 1083 731890 Ta-189 1.48250E-11 1.48250E-11 731890 + 1084 731900 Ta-190 1.10680E-12 1.10680E-12 731900 + 1085 741820 W-182 1.90580E-12 3.45520E-09 74182.82c + 1086 741830 W-183 2.74350E-12 7.37250E-09 74183.82c + 1087 741831 W-183m 1.03890E-11 2.60610E-10 741831 + 1088 741840 W-184 8.00150E-11 4.27950E-09 74184.82c + 1089 741850 W-185 5.00510E-11 2.45680E-09 741850 + 1090 741851 W-185m 1.40040E-10 1.40040E-10 741851 + 1091 741860 W-186 3.37980E-10 1.42790E-09 74186.82c + 1092 741861 W-186m 1.36840E-10 1.36840E-10 741861 + 1093 741870 W-187 4.04720E-10 7.97730E-10 741870 + 1094 741880 W-188 3.57490E-10 4.25470E-10 741880 + 1095 741890 W-189 1.46510E-10 1.61330E-10 741890 + 1096 741900 W-190 2.62650E-11 6.25590E-11 741900 + 1097 741901 W-190m 3.51870E-11 3.51870E-11 741901 + 1098 741910 W-191 9.01370E-12 9.01370E-12 741910 + 1099 741920 W-192 1.40850E-12 1.40850E-12 741920 + 1100 751850 Re-185 1.30820E-12 2.45810E-09 75185.82c + 1101 751860 Re-186 2.58750E-12 2.58750E-12 751860 + 1102 751861 Re-186m 4.32730E-12 4.32730E-12 751861 + 1103 751870 Re-187 3.34990E-11 8.31230E-10 75187.82c + 1104 751880 Re-188 1.47620E-11 4.80470E-10 751880 + 1105 751881 Re-188m 4.02390E-11 4.02390E-11 751881 + 1106 751890 Re-189 1.13280E-10 2.74610E-10 751890 + 1107 751900 Re-190 2.65560E-11 1.14520E-10 751900 + 1108 751901 Re-190m 5.57110E-11 5.57110E-11 751901 + 1109 751910 Re-191 6.15310E-11 7.05450E-11 751910 + 1110 751920 Re-192 1.82680E-11 1.96760E-11 751920 + 1111 751930 Re-193 6.30030E-12 6.30030E-12 751930 + 1112 761890 Os-189 8.67390E-13 2.78770E-10 761890 + 1113 761891 Os-189m 3.28480E-12 3.15240E-11 761891 + 1114 761900 Os-190 7.08070E-12 1.61390E-10 761900 + 1115 761901 Os-190m 9.48630E-12 3.97930E-11 761901 + 1116 761910 Os-191 1.76740E-11 9.28860E-11 761910 + 1117 761911 Os-191m 4.66700E-12 4.66700E-12 761911 + 1118 761920 Os-192 1.40490E-11 5.02950E-11 761920 + 1119 761921 Os-192m 1.88230E-11 1.88230E-11 761921 + 1120 761930 Os-193 1.98240E-11 2.61240E-11 761930 + 1121 761940 Os-194 1.17820E-11 1.17820E-11 761940 + 1122 761950 Os-195 2.97560E-12 2.97560E-12 761950 + 1123 771920 Ir-192 5.30380E-13 4.03800E-12 771920 + 1124 771922 Ir-192m 5.30380E-13 2.97730E-12 771922 + 1125 771930 Ir-193 1.34220E-12 3.12220E-11 77193.82c + 1126 771931 Ir-193m 3.75520E-12 3.84600E-12 771931 + 1127 771940 Ir-194 1.77760E-12 1.53370E-11 771940 + 1128 771941 Ir-194m 1.77760E-12 1.77760E-12 771941 + 1129 771942 Ir-194m 1.77760E-12 1.77760E-12 771942 + 1130 771950 Ir-195 1.75350E-12 4.97440E-12 771950 + 1131 771951 Ir-195m 4.90620E-12 4.90620E-12 771951 + 1132 771960 Ir-196 1.63090E-12 1.63570E-12 771960 + 1133 771961 Ir-196m 1.63090E-12 1.63090E-12 771961 + 1134 771971 Ir-197m 1.18910E-12 1.18910E-12 771971 + 1135 781960 Pt-196 1.97970E-12 5.24140E-12 781960 + 1136 781970 Pt-197 4.47740E-13 3.23410E-12 781970 + 1137 781971 Pt-197m 1.25280E-12 2.43890E-12 781971 + 1138 781980 Pt-198 1.51570E-12 1.51570E-12 781980 + + Nuclide 96246.82c -- curium 246 (Cm-246) is using NFY data from U-233 + + Nuclide 96247.82c -- curium 247 (Cm-247) is using NFY data from U-233 + + Nuclide 96248.82c -- curium 248 (Cm-248) is using NFY data from U-233 + + Nuclide 96249.82c -- curium 249 (Cm-249) is using NFY data from U-233 + + Nuclide 96250.82c -- curium 250 (Cm-250) is using NFY data from U-233 + + --- Table 4: Lost transmutation paths: + + No lost transmutation paths. + + + --- Table 1: Summary of material compositions: + + 6 materials included in calculation + + +Material "fuel": + + - Material is included in majorant + - Material is included in geometry + - Atom density 8.02292E-02 1/barn*cm + - Mass density 4.96020E+00 g/cm3 + - Volume 2.27175E+07 cm3 + - Mass 1.12683E+08 g + - Photon emission rate 0.00000E+00 1/s + - Neutron emission rate 0.00000E+00 1/s + - 1655 nuclides in composition + - No nuclides associated with S(a,b) data + - 24.69 Mb of memory allocated for data + +Isotopic composition (non-zero densities): + +------------------------------------------------------------------- + Nuclide a. weight temp a. dens a. frac m. frac +------------------------------------------------------------------- + 1001.82c 1.00783 900.0 1.18035E-09 1.47122E-08 3.98248E-10 + 1002.82c 2.01410 900.0 6.03514E-11 7.52237E-10 4.06935E-11 + 1003.82c 3.01605 900.0 4.04988E-09 5.04789E-08 4.08919E-09 + 2003.82c 3.01493 900.0 1.86083E-12 2.31940E-11 1.87820E-12 + 2004.82c 4.00258 900.0 3.18090E-08 3.96476E-07 4.26233E-08 + 20060 6.01889 900.0 5.31208E-17 6.62113E-16 1.07038E-16 + 20080 8.03393 900.0 6.14397E-22 7.65802E-21 1.65247E-21 + 3006.82c 6.01507 900.0 1.19687E-06 1.49181E-05 2.41015E-06 + 3007.82c 7.01600 900.0 2.05883E-02 2.56618E-01 4.83578E-02 + 30080 8.02249 900.0 7.58655E-15 9.45609E-14 2.03756E-14 + 30090 9.02679 900.0 1.60293E-19 1.99793E-18 4.84400E-19 + 40080 8.00531 900.0 2.05784E-34 2.56495E-33 5.51502E-34 + 4009.82c 9.01220 900.0 4.84275E-13 6.03614E-12 1.46110E-12 + 40100 10.01353 900.0 4.10694E-12 5.11901E-11 1.37677E-11 + 40110 11.02168 900.0 7.61236E-20 9.48826E-19 2.80882E-19 + 40120 12.02692 900.0 5.95014E-21 7.41642E-20 2.39573E-20 + 50090 9.01333 900.0 7.12517E-37 8.88102E-36 2.15000E-36 + 5010.82c 10.01294 900.0 4.06942E-12 5.07224E-11 1.36412E-11 + 5011.82c 11.00928 900.0 7.23568E-16 9.01876E-15 2.66683E-15 + 50120 12.01431 900.0 1.12159E-20 1.39799E-19 4.51119E-20 + 60120 11.99999 900.0 3.83104E-13 4.77511E-12 1.53905E-12 + 60130 13.00331 900.0 1.41439E-15 1.76293E-14 6.15713E-15 + 60140 14.00319 900.0 1.24591E-12 1.55293E-11 5.84076E-12 + 60150 15.01065 900.0 1.35448E-18 1.68827E-17 6.80660E-18 + 70130 13.00573 900.0 8.84680E-32 1.10269E-30 3.85192E-31 + 7014.82c 14.00307 900.0 2.13393E-18 2.65979E-17 1.00037E-17 + 7015.82c 14.99986 900.0 4.27272E-09 5.32564E-08 2.14560E-08 + 70160 16.00610 900.0 3.10212E-13 3.86657E-12 1.66227E-12 + 70170 17.00841 900.0 2.79301E-26 3.48129E-25 1.59035E-25 + 80150 15.00308 900.0 6.73379E-25 8.39319E-24 3.38218E-24 + 8016.82c 15.99492 900.0 1.55939E-08 1.94367E-07 8.35013E-08 + 8017.82c 16.99913 900.0 8.53435E-12 1.06375E-10 4.85684E-11 + 80180 17.99912 900.0 8.76023E-11 1.09190E-09 5.27866E-10 + 80190 19.00355 900.0 8.51773E-14 1.06167E-12 5.41896E-13 + 90180 18.00094 900.0 1.78160E-13 2.22064E-12 1.07365E-12 + 9019.82c 18.99820 900.0 5.18290E-02 6.46012E-01 3.29642E-01 + 90200 20.00001 900.0 1.71200E-13 2.13388E-12 1.14628E-12 + 100200 19.99245 900.0 5.56681E-09 6.93862E-08 3.72588E-08 + 100210 20.99385 900.0 1.69030E-12 2.10684E-11 1.18799E-11 + 190500 49.97279 900.0 7.27604E-26 9.06906E-25 1.21727E-24 + 190510 50.97641 900.0 2.04021E-26 2.54297E-25 3.48178E-25 + 200450 44.95620 900.0 7.71888E-33 9.62103E-32 1.16172E-31 + 200460 45.95367 900.0 1.31534E-29 1.63947E-28 2.02355E-28 + 200470 46.95456 900.0 1.59566E-28 1.98887E-27 2.50827E-27 + 200480 47.95254 900.0 1.08602E-34 1.35365E-33 1.74344E-33 + 200490 48.95566 900.0 2.33894E-23 2.91532E-22 3.83336E-22 + 200500 49.95756 900.0 7.13866E-23 8.89782E-22 1.19392E-21 + 200510 50.96149 900.0 2.44386E-23 3.04609E-22 4.16941E-22 + 200520 51.96511 900.0 7.77171E-24 9.68688E-23 1.35203E-22 + 200530 52.97004 900.0 3.68312E-26 4.59075E-25 6.53135E-25 + 200540 53.97437 900.0 6.27145E-27 7.81691E-26 1.13322E-25 + 21045.82c 44.95591 900.0 5.54633E-35 6.91311E-34 8.34737E-34 + 210470 46.95245 900.0 3.91087E-29 4.87462E-28 6.14736E-28 + 210480 47.95224 900.0 1.86808E-31 2.32843E-30 2.99889E-30 + 210490 48.95001 900.0 1.53425E-22 1.91233E-21 2.51423E-21 + 210500 49.95222 900.0 1.02982E-21 1.28359E-20 1.72216E-20 + 210501 49.95222 900.0 2.11401E-24 2.63497E-23 3.53524E-23 + 210510 50.95362 900.0 1.82453E-22 2.27415E-21 3.11232E-21 + 210520 51.95664 900.0 1.10229E-22 1.37392E-21 1.91731E-21 + 210530 52.95965 900.0 4.47687E-23 5.58010E-22 7.93737E-22 + 210540 53.96327 900.0 1.57610E-24 1.96450E-23 2.84735E-23 + 210550 54.96821 900.0 4.65688E-25 5.80447E-24 8.56966E-24 + 210560 55.97284 900.0 6.85750E-26 8.54739E-25 1.28499E-24 + 210570 56.97777 900.0 3.14671E-27 3.92215E-26 6.00232E-26 + 22047.82c 46.95134 900.0 1.35266E-29 1.68599E-28 2.12615E-28 + 22048.82c 47.94795 900.0 1.35703E-28 1.69145E-27 2.17830E-27 + 22049.82c 48.94788 900.0 1.58390E-20 1.97422E-19 2.59548E-19 + 22050.82c 49.94480 900.0 3.90712E-18 4.86994E-17 6.53287E-17 + 220510 50.94666 900.0 6.16426E-21 7.68331E-20 1.05137E-19 + 220520 51.94685 900.0 2.90208E-21 3.61724E-20 5.04692E-20 + 220530 52.94977 900.0 1.35546E-21 1.68949E-20 2.40275E-20 + 220540 53.95107 900.0 8.96911E-23 1.11794E-21 1.61997E-21 + 220550 54.95530 900.0 2.44710E-23 3.05014E-22 4.50214E-22 + 220560 55.95821 900.0 9.06618E-24 1.13003E-22 1.69842E-22 + 220570 56.96395 900.0 1.19535E-24 1.48992E-23 2.27957E-23 + 220580 57.96697 900.0 5.92454E-25 7.38452E-24 1.14972E-23 + 220590 58.97291 900.0 6.71251E-26 8.36666E-25 1.32524E-24 + 220600 59.97673 900.0 1.31140E-26 1.63456E-25 2.63314E-25 + 220610 60.98318 900.0 5.53559E-28 6.89972E-27 1.13014E-26 + 230500 49.94717 900.0 5.15126E-30 6.42067E-29 8.61353E-29 + 230510 50.94394 900.0 6.36270E-18 7.93065E-17 1.08515E-16 + 230520 51.94473 900.0 6.50939E-21 8.11348E-20 1.13198E-19 + 230530 52.94432 900.0 4.56019E-21 5.68394E-20 8.08274E-20 + 230540 53.94643 900.0 3.79068E-21 4.72481E-20 6.84600E-20 + 230550 54.94723 900.0 7.88313E-22 9.82576E-21 1.45011E-20 + 230560 55.95054 900.0 3.61418E-23 4.50482E-22 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8.96761E-27 + 832100 209.98387 900.0 7.82315E-30 9.75100E-29 5.49952E-28 + 832110 210.98749 900.0 7.23508E-31 9.01800E-30 5.11042E-29 + 832120 211.99112 900.0 5.01916E-27 6.25602E-26 3.56210E-25 + 832130 212.99474 900.0 4.74917E-30 5.91950E-29 3.38644E-28 + 832140 213.99836 900.0 5.32139E-34 6.63273E-33 3.81235E-32 + 832150 215.00198 900.0 1.19988E-33 1.49556E-32 8.63647E-32 + 842100 209.98286 900.0 9.90676E-31 1.23481E-29 6.96422E-29 + 842110 210.98649 900.0 7.98749E-36 9.95583E-35 5.64185E-34 + 842120 211.98910 900.0 2.65592E-37 3.31041E-36 1.88488E-35 + 842140 213.99533 900.0 1.96099E-34 2.44424E-33 1.40487E-32 + 842150 214.99896 900.0 1.02609E-35 1.27895E-34 7.38549E-34 + 842160 216.00157 900.0 3.65745E-31 4.55875E-30 2.64479E-29 + 842180 218.00881 900.0 8.50232E-35 1.05975E-33 6.20538E-33 + 852170 217.00519 900.0 5.74009E-35 7.15462E-34 4.17010E-33 + 852190 219.01142 900.0 1.52381E-34 1.89932E-33 1.11726E-32 + 862180 218.00579 900.0 4.34971E-32 5.42160E-31 3.17457E-30 + 862190 219.00941 900.0 2.29196E-32 2.85676E-31 1.68045E-30 + 862200 220.01101 900.0 1.37896E-28 1.71878E-27 1.01567E-26 + 862220 222.01725 900.0 1.52719E-31 1.90354E-30 1.13511E-29 + 872210 221.01463 900.0 5.10769E-31 6.36637E-30 3.77922E-29 + 872220 222.01725 900.0 2.29543E-34 2.86109E-33 1.70612E-32 + 872230 223.01986 900.0 1.79660E-29 2.23934E-28 1.34138E-27 + 882210 221.01362 900.0 2.39087E-36 2.98005E-35 1.76902E-34 + 882220 222.01523 900.0 4.37024E-29 5.44719E-28 3.24822E-27 + 882230 223.01885 900.0 5.68719E-27 7.08868E-26 4.24616E-25 + 882240 224.02045 900.0 7.75951E-25 9.67167E-24 5.81941E-23 + 882250 225.02408 900.0 1.50634E-27 1.87755E-26 1.13478E-25 + 882260 226.02568 900.0 1.05122E-25 1.31027E-24 7.95442E-24 + 882280 228.03091 900.0 1.71734E-29 2.14055E-28 1.31102E-27 + 892250 225.02307 900.0 1.53926E-27 1.91858E-26 1.15957E-25 + 892260 226.02568 900.0 4.78110E-28 5.95929E-27 3.61778E-26 + 892270 227.02728 900.0 6.83696E-22 8.52178E-21 5.19635E-20 + 892280 228.03091 900.0 1.75293E-33 2.18491E-32 1.33818E-31 + 902260 226.02467 900.0 2.21694E-27 2.76326E-26 1.67752E-25 + 90227.82c 227.02729 900.0 9.56271E-26 1.19192E-24 7.26802E-24 + 90228.82c 228.02889 900.0 8.75183E-22 1.09085E-20 6.68107E-20 + 90229.82c 229.03150 900.0 3.10918E-21 3.87538E-20 2.38396E-19 + 90230.82c 230.03613 900.0 2.08632E-18 2.60044E-17 1.60669E-16 + 902310 231.03673 900.0 1.59890E-15 1.99292E-14 1.23669E-13 + 902320 232.03833 900.0 6.36039E-17 7.92776E-16 4.94083E-15 + 902340 234.04356 900.0 1.73543E-14 2.16309E-13 1.35976E-12 + 912290 229.03251 900.0 3.69848E-25 4.60990E-24 2.83581E-23 + 912300 230.03412 900.0 3.95880E-22 4.93437E-21 3.04869E-20 + 91231.82c 231.03471 900.0 4.77638E-15 5.95342E-14 3.69431E-13 + 91232.82c 232.03833 900.0 4.93049E-18 6.14550E-17 3.83007E-16 + 91233.82c 233.03994 900.0 9.88351E-19 1.23191E-17 7.71078E-17 + 912340 234.04356 900.0 2.82832E-19 3.52529E-18 2.21606E-17 + 912341 234.04356 900.0 5.79476E-19 7.22275E-18 4.54034E-17 + 922300 230.03412 900.0 2.20342E-24 2.74641E-23 1.69686E-22 + 922310 231.03673 900.0 2.03157E-24 2.53220E-23 1.57133E-22 + 92232.82c 232.03329 900.0 2.16891E-17 2.70340E-16 1.68480E-15 + 92233.82c 233.03994 900.0 8.65672E-14 1.07900E-12 6.75368E-12 + 92234.82c 234.04053 900.0 9.01625E-11 1.12381E-09 7.06438E-09 + 92235.82c 235.04415 900.0 3.94150E-04 4.91279E-03 3.10147E-02 + 922351 235.04415 900.0 1.26787E-15 1.58031E-14 9.97656E-14 + 92236.82c 236.04556 900.0 2.64774E-07 3.30021E-06 2.09232E-05 + 92237.82c 237.04878 900.0 1.68092E-09 2.09514E-08 1.33395E-07 + 92238.82c 238.05078 900.0 7.41363E-03 9.24056E-02 5.90823E-01 + 922390 239.05461 900.0 3.42284E-09 4.26632E-08 2.73931E-07 + 922400 240.05621 900.0 3.16966E-33 3.95076E-32 2.54732E-31 + 932330 233.04095 900.0 3.64482E-34 4.54300E-33 2.84358E-32 + 932340 234.04255 900.0 5.88301E-28 7.33275E-27 4.60947E-26 + 93235.82c 235.04415 900.0 3.01497E-20 3.75794E-19 2.37241E-18 + 93236.82c 236.04677 900.0 9.20379E-18 1.14719E-16 7.27314E-16 + 932361 236.04677 900.0 9.52821E-24 1.18762E-22 7.52950E-22 + 93237.82c 237.04817 900.0 5.57914E-10 6.95400E-09 4.42753E-08 + 93238.82c 238.05098 900.0 4.93697E-13 6.15358E-12 3.93448E-11 + 93239.82c 239.05259 900.0 4.08701E-07 5.09417E-06 3.27082E-05 + 932400 240.05621 900.0 2.97688E-12 3.71047E-11 2.39238E-10 + 932401 240.05621 900.0 6.10636E-13 7.61114E-12 4.90741E-11 + 942340 234.04356 900.0 6.96364E-34 8.67968E-33 5.45619E-32 + 942350 235.04516 900.0 2.39270E-29 2.98232E-28 1.88276E-27 + 94236.82c 236.04576 900.0 1.06862E-21 1.33195E-20 8.44452E-20 + 94237.82c 237.04837 900.0 1.30781E-17 1.63009E-16 1.03786E-15 + 942371 237.04837 900.0 2.74565E-31 3.42225E-30 2.17891E-29 + 94238.82c 238.04998 900.0 2.90503E-13 3.62091E-12 2.31513E-11 + 94239.82c 239.05198 900.0 4.56989E-07 5.69604E-06 3.65725E-05 + 94240.82c 240.05379 900.0 1.08824E-09 1.35642E-08 8.74564E-08 + 94241.82c 241.05681 900.0 1.27740E-11 1.59219E-10 1.03087E-09 + 94242.82c 242.05841 900.0 5.71245E-15 7.12016E-14 4.62913E-13 + 94243.82c 243.06203 900.0 1.19019E-18 1.48348E-17 9.68478E-17 + 94244.82c 244.06465 900.0 2.89283E-22 3.60570E-21 2.36366E-20 + 942450 245.06827 900.0 7.21980E-27 8.99896E-26 5.92337E-25 + 952390 239.05259 900.0 2.45551E-27 3.06062E-26 1.96513E-25 + 952400 240.05520 900.0 9.41940E-24 1.17406E-22 7.56992E-22 + 95241.82c 241.05681 900.0 2.42301E-15 3.02011E-14 1.95538E-13 + 95242.82c 242.05942 900.0 2.32214E-18 2.89438E-17 1.88177E-16 + 95642.82c 242.05942 900.0 4.28174E-19 5.33689E-18 3.46976E-17 + 95243.82c 243.06102 900.0 4.43691E-18 5.53029E-17 3.61038E-16 + 95244.82c 244.06465 900.0 1.56167E-22 1.94651E-21 1.27600E-20 + 95644.82c 244.06465 900.0 1.55606E-22 1.93952E-21 1.27142E-20 + 952450 245.06625 900.0 1.50324E-26 1.87368E-25 1.23330E-24 + 96240.82c 240.05520 900.0 3.96122E-29 4.93738E-28 3.18344E-27 + 96241.82c 241.05781 900.0 6.71220E-27 8.36627E-26 5.41680E-25 + 96242.82c 242.05841 900.0 2.11156E-18 2.63191E-17 1.71112E-16 + 96243.82c 243.06102 900.0 1.58371E-22 1.97398E-21 1.28868E-20 + 96244.82c 244.06263 900.0 5.77324E-21 7.19593E-20 4.71713E-19 + 962441 244.06263 900.0 1.46031E-28 1.82017E-27 1.19317E-26 + 96245.82c 245.06524 900.0 1.58742E-24 1.97861E-23 1.30236E-22 + 96246.82c 246.06685 900.0 1.41580E-28 1.76470E-27 1.16631E-26 + 96247.82c 247.06946 900.0 6.98522E-33 8.70658E-32 5.77771E-31 + 96248.82c 248.07207 900.0 1.71154E-36 2.13332E-35 1.42142E-34 + sum 8.02292E-02 1.00000E+00 1.00000E+00 +------------------------------------------------------------------- + +Material "ctrlPois": + + - Material is included in majorant + - Material is included in geometry + - Atom density 8.62582E-02 1/barn*cm + - Mass density 5.87300E+00 g/cm3 + - Volume 1.11635E+04 cm3 + - Mass 6.55632E+04 g + - Photon emission rate 0.00000E+00 1/s + - Neutron emission rate 0.00000E+00 1/s + - 1655 nuclides in composition + - No nuclides associated with S(a,b) data + - 24.69 Mb of memory allocated for data + +Isotopic composition (non-zero densities): + +------------------------------------------------------------------- + Nuclide a. weight temp a. dens a. frac m. frac +------------------------------------------------------------------- + 1001.82c 1.00783 900.0 1.60678E-11 1.86276E-10 4.57867E-12 + 1002.82c 2.01410 900.0 5.18761E-15 6.01404E-14 2.95423E-15 + 1003.82c 3.01605 900.0 1.89861E-17 2.20107E-16 1.61908E-17 + 2003.82c 3.01493 900.0 2.89424E-18 3.35532E-17 2.46722E-18 + 2004.82c 4.00258 900.0 9.24041E-11 1.07125E-09 1.04575E-10 + 5011.82c 11.00928 900.0 1.82787E-35 2.11907E-34 5.68985E-35 + 60120 11.99999 900.0 2.47462E-37 2.86885E-36 8.39625E-37 + 60130 13.00331 900.0 9.00414E-11 1.04386E-09 3.31049E-10 + 60140 14.00319 900.0 4.48213E-21 5.19618E-20 1.77463E-20 + 7014.82c 14.00307 900.0 3.03925E-27 3.52344E-26 1.20333E-26 + 7015.82c 14.99986 900.0 8.21708E-37 9.52614E-36 3.48498E-36 + 8016.82c 15.99492 900.0 5.17714E-02 6.00191E-01 2.34136E-01 + 8017.82c 16.99913 900.0 1.43224E-13 1.66041E-12 6.88394E-13 + 80180 17.99912 900.0 1.19553E-23 1.38600E-22 6.08428E-23 + 100210 20.99385 900.0 8.02308E-22 9.30124E-21 4.76244E-21 + 100220 21.99142 900.0 7.82276E-29 9.06900E-28 4.86418E-28 + 110240 23.99100 900.0 6.77669E-13 7.85629E-12 4.59687E-12 + 110250 24.98998 900.0 6.30380E-33 7.30806E-32 4.45415E-32 + 12024.82c 23.98504 900.0 1.67145E-12 1.93773E-11 1.13352E-11 + 12025.82c 24.98584 900.0 8.40204E-20 9.74057E-19 5.93574E-19 + 12026.82c 25.98260 900.0 4.13430E-15 4.79294E-14 3.03726E-14 + 120270 26.98431 900.0 3.26803E-14 3.78866E-13 2.49341E-13 + 13027.82c 26.98154 900.0 2.08382E-02 2.41579E-01 1.58973E-01 + 130280 27.98188 900.0 7.08593E-14 8.21479E-13 5.60621E-13 + 130290 28.98046 900.0 7.69723E-31 8.92347E-30 6.30719E-30 + 14028.82c 27.97734 900.0 1.79848E-10 2.08499E-09 1.42268E-09 + 14029.82c 28.97652 900.0 8.10451E-19 9.39564E-18 6.64001E-18 + 14030.82c 30.00002 900.0 3.18413E-27 3.69140E-26 2.70090E-26 + 140310 30.97540 900.0 2.38581E-36 2.76589E-35 2.08953E-35 + 15031.82c 30.97378 900.0 2.11592E-35 2.45300E-34 1.85306E-34 + 60147.82c 146.91609 900.0 5.77918E-37 6.69986E-36 2.40066E-35 + 60148.82c 147.91668 900.0 3.76961E-28 4.37015E-27 1.57656E-26 + 601490 148.92030 900.0 4.01467E-29 4.65425E-28 1.69044E-27 + 60150.82c 149.92090 900.0 6.85240E-29 7.94406E-28 2.90470E-27 + 601510 150.92351 900.0 3.40772E-33 3.95061E-32 1.45418E-31 + 61148.82c 147.91668 900.0 2.90060E-31 3.36270E-30 1.21311E-29 + 61149.82c 148.91829 900.0 6.16090E-28 7.14239E-27 2.59411E-26 + 611500 149.92090 900.0 2.05999E-29 2.38817E-28 8.73220E-28 + 61151.82c 150.92150 900.0 1.75435E-26 2.03383E-25 7.48623E-25 + 611520 151.92310 900.0 5.62633E-28 6.52266E-27 2.41682E-26 + 611530 152.92370 900.0 1.30354E-31 1.51120E-30 5.63630E-30 + 611540 153.92631 900.0 1.32503E-33 1.53612E-32 5.76680E-32 + 62148.82c 147.91467 900.0 5.56522E-32 6.45181E-31 2.32750E-30 + 62149.82c 148.91728 900.0 3.73642E-28 4.33168E-27 1.57325E-26 + 62150.82c 149.91687 900.0 1.47715E-24 1.71247E-23 6.26138E-23 + 62151.82c 150.91645 900.0 4.17854E-16 4.84422E-15 1.78302E-14 + 62152.82c 151.92007 900.0 3.37018E-15 3.90708E-14 1.44765E-13 + 62153.82c 152.92168 900.0 1.68463E-15 1.95301E-14 7.28399E-14 + 62154.82c 153.92227 900.0 1.58046E-15 1.83224E-14 6.87829E-14 + 621550 154.92489 900.0 7.70554E-18 8.93311E-17 3.37536E-16 + 621560 155.92548 900.0 1.15071E-30 1.33403E-29 5.07315E-29 + 621570 156.92810 900.0 3.57259E-18 4.14174E-17 1.58518E-16 + 63151.82c 150.91948 900.0 2.35349E-20 2.72842E-19 1.00428E-18 + 63152.82c 151.92209 900.0 1.12329E-24 1.30225E-23 4.82515E-23 + 63153.82c 152.92168 900.0 2.24797E-15 2.60609E-14 9.71975E-14 + 63154.82c 153.92227 900.0 1.04959E-15 1.21680E-14 4.56792E-14 + 631541 153.92328 900.0 9.81867E-24 1.13829E-22 4.27320E-22 + 63155.82c 154.92287 900.0 1.19751E-14 1.38829E-13 5.24556E-13 + 63156.82c 155.92548 900.0 3.78986E-15 4.39363E-14 1.67085E-13 + 63157.82c 156.92507 900.0 1.32562E-15 1.53680E-14 5.88175E-14 + 631580 157.92768 900.0 1.99318E-17 2.31071E-16 8.90020E-16 + 631600 159.93190 900.0 1.13398E-19 1.31464E-18 5.12787E-18 + 64152.82c 151.92007 900.0 6.38577E-29 7.40309E-28 2.74299E-27 + 641530 152.92168 900.0 6.50923E-34 7.54621E-33 2.81446E-32 + 64154.82c 153.92127 900.0 2.98133E-04 3.45629E-03 1.29749E-02 + 64155.82c 154.92287 900.0 2.02397E-03 2.34641E-02 8.86576E-02 + 64156.82c 155.92205 900.0 2.79953E-03 3.24553E-02 1.23421E-01 + 64157.82c 156.92406 900.0 2.14024E-03 2.48120E-02 9.49615E-02 + 64158.82c 157.92466 900.0 3.39716E-03 3.93837E-02 1.51692E-01 + 641590 158.92626 900.0 1.63344E-09 1.89366E-08 7.33998E-08 + 64160.82c 159.92686 900.0 2.98956E-03 3.46583E-02 1.35184E-01 + 641610 160.92947 900.0 1.98985E-12 2.30685E-11 9.05423E-11 + 65159.82c 158.92525 900.0 7.10636E-09 8.23848E-08 3.19327E-07 + 65160.82c 159.92686 900.0 6.13046E-14 7.10710E-13 2.77211E-12 + 651610 160.92745 900.0 2.62924E-09 3.04811E-08 1.19635E-07 + 651620 161.92906 900.0 7.95161E-32 9.21839E-31 3.64063E-30 + 651630 162.93066 900.0 1.75759E-35 2.03759E-34 8.09687E-34 + 66160.82c 159.92484 900.0 1.01959E-15 1.18202E-14 4.61039E-14 + 66161.82c 160.92644 900.0 9.15829E-10 1.06173E-08 4.16714E-08 + 66162.82c 161.92704 900.0 8.81712E-15 1.02218E-13 4.03685E-13 + 66163.82c 162.92864 900.0 4.34890E-19 5.04172E-18 2.00342E-17 + 66164.82c 163.92823 900.0 2.99073E-24 3.46718E-23 1.38620E-22 + 661650 164.93185 900.0 9.92675E-31 1.15082E-29 4.62922E-29 + 661651 164.93185 900.0 6.41934E-33 7.44201E-32 2.99358E-31 + 67165.82c 164.92983 900.0 6.01332E-30 6.97131E-29 2.80421E-28 + 671660 165.93245 900.0 1.07359E-35 1.24462E-34 5.03693E-34 + 671661 165.93245 900.0 7.85659E-37 9.10823E-36 3.68605E-35 + 68166.82c 165.93043 900.0 3.88352E-36 4.50221E-35 1.82200E-34 + sum 8.62582E-02 1.00000E+00 1.00000E+00 +------------------------------------------------------------------- + +Material "zrh": + + - Material is included in majorant + - Material is included in geometry + - Atom density 9.75972E-02 1/barn*cm + - Mass density 5.66000E+00 g/cm3 + - Volume 0.00000E+00 cm3 + - Mass 0.00000E+00 g + - Photon emission rate 0.00000E+00 1/s + - Neutron emission rate 0.00000E+00 1/s + - 7 nuclides in composition + - 1 nuclides associated with S(a,b) data + - 11.96 Mb of memory allocated for data + +Isotopic composition (non-zero densities): + +------------------------------------------------------------------- + Nuclide a. weight temp a. dens a. frac m. frac +------------------------------------------------------------------- + 40090.82c 89.90473 900.0 1.88774E-02 1.93422E-01 4.97925E-01 + 40091.82c 90.90563 900.0 4.11688E-03 4.21823E-02 1.09799E-01 + 40092.82c 91.90501 900.0 6.29249E-03 6.44741E-02 1.69668E-01 + 40094.82c 93.90631 900.0 6.37689E-03 6.53388E-02 1.75688E-01 + 40096.82c 95.90830 900.0 1.02735E-03 1.05264E-02 2.89077E-02 + 1001.82s 1.00783 900.0 6.08992E-02 6.23985E-01 1.80068E-02 (s) + 1002.82c 2.01410 900.0 7.00422E-06 7.17666E-05 4.13886E-06 + sum 9.75972E-02 1.00000E+00 1.00000E+00 +------------------------------------------------------------------- + +Material "sic": + + - Material is included in majorant + - Material is included in geometry + - Atom density 9.64414E-02 1/barn*cm + - Mass density 3.21000E+00 g/cm3 + - Volume 0.00000E+00 cm3 + - Mass 0.00000E+00 g + - Photon emission rate 0.00000E+00 1/s + - Neutron emission rate 0.00000E+00 1/s + - 4 nuclides in composition + - No nuclides associated with S(a,b) data + - 11.96 Mb of memory allocated for data + +Isotopic composition (non-zero densities): + +------------------------------------------------------------------- + Nuclide a. weight temp a. dens a. frac m. frac +------------------------------------------------------------------- + 14028.82c 27.97734 900.0 4.44728E-02 4.61138E-01 6.43653E-01 + 14029.82c 28.97652 900.0 2.25927E-03 2.34264E-02 3.38661E-02 + 14030.82c 30.00002 900.0 1.48976E-03 1.54473E-02 2.31201E-02 + 6000.82c 12.00110 900.0 4.82196E-02 4.99989E-01 2.99361E-01 + sum 9.64414E-02 1.00000E+00 1.00000E+00 +------------------------------------------------------------------- + +Material "hast": + + - Material is included in majorant + - Material is included in geometry + - Atom density 8.75838E-02 1/barn*cm + - Mass density 8.86000E+00 g/cm3 + - Volume 0.00000E+00 cm3 + - Mass 0.00000E+00 g + - Photon emission rate 0.00000E+00 1/s + - Neutron emission rate 0.00000E+00 1/s + - 36 nuclides in composition + - No nuclides associated with S(a,b) data + - 12.00 Mb of memory allocated for data + +Isotopic composition (non-zero densities): + +------------------------------------------------------------------- + Nuclide a. weight temp a. dens a. frac m. frac +------------------------------------------------------------------- + 28058.82c 57.93570 900.0 4.45151E-02 5.08257E-01 4.83366E-01 + 28060.82c 59.93079 900.0 1.65762E-02 1.89261E-01 1.86191E-01 + 28061.82c 60.93143 900.0 2.96883E-03 3.38970E-02 3.39038E-02 + 28064.82c 63.92818 900.0 5.48747E-04 6.26540E-03 6.57486E-03 + 24050.82c 49.94606 900.0 3.24924E-04 3.70986E-03 3.04162E-03 + 24052.82c 51.93999 900.0 6.02529E-03 6.87946E-02 5.86546E-02 + 24053.82c 52.94079 900.0 6.70304E-04 7.65329E-03 6.65096E-03 + 24054.82c 53.93937 900.0 1.63764E-04 1.86980E-03 1.65557E-03 + 42092.82c 91.90683 900.0 1.36083E-03 1.55375E-02 2.34409E-02 + 42094.82c 93.90510 900.0 8.35490E-04 9.53932E-03 1.47046E-02 + 42095.82c 94.90589 900.0 1.42757E-03 1.62995E-02 2.53930E-02 + 42096.82c 95.90467 900.0 1.48392E-03 1.69429E-02 2.66731E-02 + 42097.82c 96.90597 900.0 8.43975E-04 9.63621E-03 1.53286E-02 + 42098.82c 97.90536 900.0 2.11805E-03 2.41831E-02 3.88655E-02 + 42100.82c 99.90746 900.0 8.32292E-04 9.50281E-03 1.55846E-02 + 26054.82c 53.93962 900.0 1.85761E-04 2.12095E-03 1.87795E-03 + 26056.82c 55.93491 900.0 2.80950E-03 3.20779E-02 2.94533E-02 + 26057.82c 56.93541 900.0 6.37763E-05 7.28175E-04 6.80556E-04 + 26058.82c 57.93329 900.0 8.27820E-06 9.45175E-05 8.98848E-05 + 14028.82c 27.97734 900.0 1.60023E-03 1.82708E-02 8.39095E-03 + 14029.82c 28.97652 900.0 7.87606E-05 8.99261E-04 4.27738E-04 + 14030.82c 30.00002 900.0 4.51661E-05 5.15691E-04 2.53955E-04 + 25055.82c 54.93805 900.0 5.82737E-04 6.65349E-03 6.00024E-03 + 23000.82c 50.94161 900.0 5.23711E-04 5.97955E-03 5.00020E-03 + 6000.82c 12.00110 900.0 2.66963E-04 3.04809E-03 6.00475E-04 + 27059.82c 58.93317 900.0 1.80873E-05 2.06515E-04 1.99782E-04 + 74182.82c 181.94803 900.0 2.33139E-05 2.66190E-04 7.95031E-04 + 74183.82c 182.95064 900.0 1.25205E-05 1.42955E-04 4.29317E-04 + 74184.82c 183.95124 900.0 2.66626E-05 3.04424E-04 9.19236E-04 + 74186.82c 185.95445 900.0 2.44730E-05 2.79423E-04 8.52934E-04 + 13027.82c 26.98154 900.0 3.95511E-04 4.51580E-03 2.00008E-03 + 22046.82c 45.95276 900.0 1.91587E-05 2.18748E-04 1.65007E-04 + 22047.82c 46.95134 900.0 1.69102E-05 1.93075E-04 1.48806E-04 + 22048.82c 47.94795 900.0 1.64074E-04 1.87334E-03 1.47446E-03 + 22049.82c 48.94788 900.0 1.17947E-05 1.34668E-04 1.08204E-04 + 22050.82c 49.94480 900.0 1.10679E-05 1.26369E-04 1.03604E-04 + sum 8.75838E-02 1.00000E+00 1.00000E+00 +------------------------------------------------------------------- + +Material "air": + + - Material is included in majorant + - Material is included in geometry + - Atom density 5.11533E-05 1/barn*cm + - Mass density 1.22500E-03 g/cm3 + - Volume 0.00000E+00 cm3 + - Mass 0.00000E+00 g + - Photon emission rate 0.00000E+00 1/s + - Neutron emission rate 0.00000E+00 1/s + - 2 nuclides in composition + - No nuclides associated with S(a,b) data + - 11.96 Mb of memory allocated for data + +Isotopic composition (non-zero densities): + +------------------------------------------------------------------- + Nuclide a. weight temp a. dens a. frac m. frac +------------------------------------------------------------------- + 8016.82c 15.99492 900.0 1.07422E-05 2.10000E-01 2.32914E-01 + 7014.82c 14.00307 900.0 4.04111E-05 7.90000E-01 7.67086E-01 + sum 5.11533E-05 1.00000E+00 1.00000E+00 +------------------------------------------------------------------- diff --git a/tests/serpent_data/tap_reference_nndc.out b/tests/serpent_data/tap_reference_nndc.out new file mode 100644 index 000000000..789dd34a5 --- /dev/null +++ b/tests/serpent_data/tap_reference_nndc.out @@ -0,0 +1,136448 @@ + + --- Table 1: Summary of nuclide data: + + Data for 1657 nuclides included in calculation: + + - 314 Transport nuclides + - No dosimetry nuclides + - 1343 Decay nuclides + - 7339 reaction channels + - 3577 special reactions + - 2521 transmutation reactions + - 1903 transmutation branch reactions + - 1930 decay reactions + - 120 decay branch reactions + - All reaction linked to target + + Columns: + + 1. Index + 2. Level (first occurence in transmutation paths) + 3. Name (nuclide identifier data) + 4. Library ID + 5. Primary data type: TRA = transport + DOS = dosimetry + SAB = thermal scattering + DEC = only decay data + STR = only structural data (mass) + PHO = photon interaction data + 6. Z (atomic number) + 7. A (isotope number) + 8. I (isomeric state) + 9. Atomic weight + 10. Temperature (in Kelvin) + 11. Decay constant (1/s) + 12. Flags: I - nuclide is present in initial composition + B - nuclide is involved in burnup calculation + A - nuclide is produced as activation product + D - nuclide is produced as decay product + F - nuclide is produced as fission product + B - nuclide is produced in decay or transmutation branching + T - nuclide has neutron transport cross section data + S - nuclide has S(a,b) data + I - nuclide has isomeric branching reactions + F - nuclide is fissile + P - nuclide is a delayed neutron precursor + D - nuclide has delayed neutron data + U - nuclide has uses ures ptable data + T - nuclide cross sections are adjusted by TMS + D - nuclide has dosimetry cross section data + R - nuclide has radioactive decay data + N - nuclide has neutron-induced fission yield data + S - nuclide has spontaneous fission yield data + P - nuclide has photon transport cross section data + T - nuclide has supplementary transmutation cross section data + + 1 0 1001.82c 82c TRA 1 1 0 1.00783 900.0 stable IBA-FBT--------R---- hydrogen (H-1) + 2 0 1001.82s 82s TRA 1 1 0 1.00783 900.0 stable IBA-FBTS-------R---- hydrogen (H-1) + 3 0 1002.82c 82c TRA 1 2 0 2.01410 900.0 stable IBA-FBT--------R---- deuterium (H-2) + 4 0 1003.82c 82c TRA 1 3 0 3.01605 900.0 1.78139E-09 IBA-FBT--------R---- tritium (H-3) + 5 0 2003.82c 82c TRA 2 3 0 3.01493 900.0 stable IB-D-BT--------R---- helium 3 (He-3) + 6 0 2004.82c 82c TRA 2 4 0 4.00258 900.0 stable IBADFBT--------R---- helium 4 (He-4) + 7 0 3006.82c 82c TRA 3 6 0 6.01507 900.0 stable IBAD--T--------R---- lithium 6 (Li-6) + 8 0 3007.82c 82c TRA 3 7 0 7.01600 900.0 stable IBADF-T--------R---- lithium 7 (Li-7) + 9 0 4009.82c 82c TRA 4 9 0 9.01220 900.0 stable IBADF-T--------R---- beryllium 9 (Be-9) + 10 0 5010.82c 82c TRA 5 10 0 10.01294 900.0 stable IBADF-T--------R---- boron 10 (B-10) + 11 0 5011.82c 82c TRA 5 11 0 11.00928 900.0 stable IBAD--T--------R---- boron 11 (B-11) + 12 0 6000.82c 82c TRA 6 0 0 12.00110 900.0 N/A I-----T------------- natural carbon (C-nat) + 13 0 7014.82c 82c TRA 7 14 0 14.00307 900.0 stable IBAD--T--------R---- nitrogen 14 (N-14) + 14 0 7015.82c 82c TRA 7 15 0 14.99986 900.0 stable IBAD--T--------R---- nitrogen 15 (N-15) + 15 0 8016.82c 82c TRA 8 16 0 15.99492 900.0 stable IBAD--T--------R---- oxygen 16 (O-16) + 16 0 8017.82c 82c TRA 8 17 0 16.99913 900.0 stable IBAD--T--------R---- oxygen 17 (O-17) + 17 0 9019.82c 82c TRA 9 19 0 18.99820 900.0 stable IBAD--T--------R---- fluorine 19 (F-19) + 18 0 11022.82c 82c TRA 11 22 0 21.99444 900.0 8.43866E-09 IBA---T--------R---- sodium 22 (Na-22) + 19 0 11023.82c 82c TRA 11 23 0 22.98980 900.0 stable IBAD--T-I------R---- sodium 23 (Na-23) + 20 0 12024.82c 82c TRA 12 24 0 23.98504 900.0 stable IBAD--T--------R---- magnesium 24 (Mg-24) + 21 0 12025.82c 82c TRA 12 25 0 24.98584 900.0 stable IBAD--T--------R---- magnesium 25 (Mg-25) + 22 0 12026.82c 82c TRA 12 26 0 25.98260 900.0 stable IBAD--T--------R---- magnesium 26 (Mg-26) + 23 0 13027.82c 82c TRA 13 27 0 26.98154 900.0 stable IBAD--T--------R---- aluminum 27 (Al-27) + 24 0 14028.82c 82c TRA 14 28 0 27.97734 900.0 stable IBAD--T--------R---- silicon 28 (Si-28) + 25 0 14029.82c 82c TRA 14 29 0 28.97652 900.0 stable IBAD--T--------R---- silicon 29 (Si-29) + 26 0 14030.82c 82c TRA 14 30 0 30.00002 900.0 stable IBAD--T--------R---- silicon 30 (Si-30) + 27 0 15031.82c 82c TRA 15 31 0 30.97378 900.0 stable IBAD--T--------R---- phosphorus 31 (P-31) + 28 0 16034.82c 82c TRA 16 34 0 33.96800 900.0 stable IBAD--T--------R---- sulfur 34 (S-34) + 29 0 16036.82c 82c TRA 16 36 0 35.96697 900.0 stable IBAD--T--------R---- sulfur 36 (S-36) + 30 0 17035.82c 82c TRA 17 35 0 34.96885 900.0 stable IBAD--T--------R---- chlorine 35 (Cl-35) + 31 0 17037.82c 82c TRA 17 37 0 36.96586 900.0 stable IBAD--T-I------R---- chlorine 37 (Cl-37) + 32 0 18038.82c 82c TRA 18 38 0 37.96272 900.0 stable IBAD--T--------R---- argon 38 (Ar-38) + 33 0 18040.82c 82c TRA 18 40 0 39.96240 900.0 stable IBAD--T--------R---- argon 40 (Ar-40) + 34 0 19039.82c 82c TRA 19 39 0 38.96402 900.0 stable IBAD--T--------R---- potassium 39 (K-39) + 35 0 19040.82c 82c TRA 19 40 0 39.96401 900.0 1.75664E-17 IBA---T--------R---- potassium 40 (K-40) + 36 0 19041.82c 82c TRA 19 41 0 40.96198 900.0 stable IBAD--T--------R---- potassium 41 (K-41) + 37 0 20042.82c 82c TRA 20 42 0 41.95863 900.0 stable IBAD--T--------R---- calcium 42 (Ca-42) + 38 0 20043.82c 82c TRA 20 43 0 42.95877 900.0 stable IBAD--T--------R---- calcium 43 (Ca-43) + 39 0 20044.82c 82c TRA 20 44 0 43.95548 900.0 stable IBAD--T--------R---- calcium 44 (Ca-44) + 40 0 21045.82c 82c TRA 21 45 0 44.95591 900.0 stable IBAD--T-I------R---- scandium 45 (Sc-45) + 41 0 22046.82c 82c TRA 22 46 0 45.95276 900.0 stable IBAD--T--------R---- titanium 46 (Ti-46) + 42 0 22047.82c 82c TRA 22 47 0 46.95134 900.0 stable IBAD--T--------R---- titanium 47 (Ti-47) + 43 0 22048.82c 82c TRA 22 48 0 47.94795 900.0 stable IBAD--T--------R---- titanium 48 (Ti-48) + 44 0 22049.82c 82c TRA 22 49 0 48.94788 900.0 stable IBAD--T--------R---- titanium 49 (Ti-49) + 45 0 22050.82c 82c TRA 22 50 0 49.94480 900.0 stable IBADF-T--------R---- titanium 50 (Ti-50) + 46 0 23000.82c 82c TRA 23 0 0 50.94161 900.0 N/A I-----T------------- natural vanadium (V-nat) + 47 0 24050.82c 82c TRA 24 50 0 49.94606 900.0 1.22025E-25 IBAD--T--------R---- chromium 50 (Cr-50) + 48 0 24052.82c 82c TRA 24 52 0 51.93999 900.0 stable IBADF-T--------R---- chromium 52 (Cr-52) + 49 0 24053.82c 82c TRA 24 53 0 52.94079 900.0 stable IBADF-T--------R---- chromium 53 (Cr-53) + 50 0 24054.82c 82c TRA 24 54 0 53.93937 900.0 stable IBADF-T--------R---- chromium 54 (Cr-54) + 51 0 25055.82c 82c TRA 25 55 0 54.93805 900.0 stable IBADF-T--------R---- manganese 55 (Mn-55) + 52 0 26054.82c 82c TRA 26 54 0 53.93962 900.0 stable IBA---T--------R---- iron 54 (Fe-54) + 53 0 26056.82c 82c TRA 26 56 0 55.93491 900.0 stable IBADF-T--------R---- iron 56 (Fe-56) + 54 0 26057.82c 82c TRA 26 57 0 56.93541 900.0 stable IBADF-T--------R---- iron 57 (Fe-57) + 55 0 26058.82c 82c TRA 26 58 0 57.93329 900.0 stable IBADF-T--------R---- iron 58 (Fe-58) + 56 0 27059.82c 82c TRA 27 59 0 58.93317 900.0 stable IBADF-T-I------R---- cobalt 59 (Co-59) + 57 0 28058.82c 82c TRA 28 58 0 57.93570 900.0 3.13779E-29 IBA---T--------R---- nickel 58 (Ni-58) + 58 0 28059.82c 82c TRA 28 59 0 58.93438 900.0 2.89012E-13 IBA---T--------R---- nickel 59 (Ni-59) + 59 0 28060.82c 82c TRA 28 60 0 59.93079 900.0 stable IBAD--T--------R---- nickel 60 (Ni-60) + 60 0 28061.82c 82c TRA 28 61 0 60.93143 900.0 stable IBADF-T--------R---- nickel 61 (Ni-61) + 61 0 28062.82c 82c TRA 28 62 0 61.92799 900.0 stable IBADF-T--------R---- nickel 62 (Ni-62) + 62 0 28064.82c 82c TRA 28 64 0 63.92818 900.0 stable IBADF-T--------R---- nickel 64 (Ni-64) + 63 0 29065.82c 82c TRA 29 65 0 64.92776 900.0 stable IBADF-T--------R---- copper 65 (Cu-65) + 64 0 32070.82c 82c TRA 32 70 0 69.92426 900.0 stable IBADF-T--------R---- germanium 70 (Ge-70) + 65 0 32072.82c 82c TRA 32 72 0 71.92209 900.0 stable IBADF-T-I------R---- germanium 72 (Ge-72) + 66 0 32073.82c 82c TRA 32 73 0 72.92347 900.0 stable IBADF-T--------R---- germanium 73 (Ge-73) + 67 0 32074.82c 82c TRA 32 74 0 73.92118 900.0 stable IBADF-T-I------R---- germanium 74 (Ge-74) + 68 0 32076.82c 82c TRA 32 76 0 75.92140 900.0 1.39016E-29 IBADF-T-I------R---- germanium 76 (Ge-76) + 69 0 33075.82c 82c TRA 33 75 0 74.92162 900.0 stable IBADF-T--------R---- arsenic 75 (As-75) + 70 0 34076.82c 82c TRA 34 76 0 75.91919 900.0 stable IB-DF-T-I------R---- selenium 76 (Se-76) + 71 0 34077.82c 82c TRA 34 77 0 76.91988 900.0 stable IBADF-T--------R---- selenium 77 (Se-77) + 72 0 34078.82c 82c TRA 34 78 0 77.91735 900.0 stable IBADF-T-I------R---- selenium 78 (Se-78) + 73 0 34079.82c 82c TRA 34 79 0 78.91845 900.0 5.82624E-14 IBADF-T--------R---- selenium 79 (Se-79) + 74 0 34080.82c 82c TRA 34 80 0 79.91652 900.0 stable IBADF-T-I------R---- selenium 80 (Se-80) + 75 0 34082.82c 82c TRA 34 82 0 81.91671 900.0 2.26443E-28 IBADF-T-I------R---- selenium 82 (Se-82) + 76 0 35079.82c 82c TRA 35 79 0 78.91835 900.0 stable IBADF-T-I------R---- bromine 79 (Br-79) + 77 0 35081.82c 82c TRA 35 81 0 80.91631 900.0 stable IBADF-T-I------R---- bromine 81 (Br-81) + 78 0 36080.82c 82c TRA 36 80 0 79.91632 900.0 stable IB-DF-T-I------R---- krypton 80 (Kr-80) + 79 0 36082.82c 82c TRA 36 82 0 81.91348 900.0 stable IBADF-T-I------R---- krypton 82 (Kr-82) + 80 0 36083.82c 82c TRA 36 83 0 82.91428 900.0 stable IBADF-T--------R---- krypton 83 (Kr-83) + 81 0 36084.82c 82c TRA 36 84 0 83.91144 900.0 stable IBADF-T-I------R---- krypton 84 (Kr-84) + 82 0 36085.82c 82c TRA 36 85 0 84.91254 900.0 2.04287E-09 IBADF-T--------R---- krypton 85 (Kr-85) + 83 0 36086.82c 82c TRA 36 86 0 85.91062 900.0 stable IBADF-T--------R---- krypton 86 (Kr-86) + 84 0 37085.82c 82c TRA 37 85 0 84.91184 900.0 stable IBADF-T-I------R---- rubidium 85 (Rb-85) + 85 0 37086.82c 82c TRA 37 86 0 85.91122 900.0 4.30393E-07 IBADF-T--------R---- rubidium 86 (Rb-86) + 86 0 37087.82c 82c TRA 37 87 0 86.90920 900.0 4.56652E-19 IBADF-T--------R---- rubidium 87 (Rb-87) + 87 0 38086.82c 82c TRA 38 86 0 85.90931 900.0 stable IBADF-T-I------R---- strontium 86 (Sr-86) + 88 0 38087.82c 82c TRA 38 87 0 86.90889 900.0 stable IBADF-T--------R---- strontium 87 (Sr-87) + 89 0 38088.82c 82c TRA 38 88 0 87.90566 900.0 stable IBADF-T--------R---- strontium 88 (Sr-88) + 90 0 38089.82c 82c TRA 38 89 0 88.90746 900.0 1.58642E-07 IBADF-T--------R---- strontium 89 (Sr-89) + 91 0 38090.82c 82c TRA 38 90 0 89.90775 900.0 7.62673E-10 IBADF-T--------R---- strontium 90 (Sr-90) + 92 0 39089.82c 82c TRA 39 89 0 88.90585 900.0 stable IBADF-T-I------R---- yttrium 89 (Y-89) + 93 0 39090.82c 82c TRA 39 90 0 89.90716 900.0 3.00845E-06 IBADF-T-I------R---- yttrium 90 (Y-90) + 94 0 39091.82c 82c TRA 39 91 0 90.90735 900.0 1.37114E-07 IBADF-T--------R---- yttrium 91 (Y-91) + 95 0 40090.82c 82c TRA 40 90 0 89.90473 900.0 stable IBADF-T--------R---- zirconium 90 (Zr-90) + 96 0 40091.82c 82c TRA 40 91 0 90.90563 900.0 stable IBADF-T--------R---- zirconium 91 (Zr-91) + 97 0 40092.82c 82c TRA 40 92 0 91.90501 900.0 stable IBADF-T--------R---- zirconium 92 (Zr-92) + 98 0 40093.82c 82c TRA 40 93 0 92.90652 900.0 1.36428E-14 IBADF-T--------R---- zirconium 93 (Zr-93) + 99 0 40094.82c 82c TRA 40 94 0 93.90631 900.0 1.99682E-25 IBADF-T--------R---- zirconium 94 (Zr-94) + 100 0 40095.82c 82c TRA 40 95 0 94.90801 900.0 1.25290E-07 IBADF-T--------R---- zirconium 95 (Zr-95) + 101 0 40096.82c 82c TRA 40 96 0 95.90830 900.0 1.09825E-27 IBADF-T--------R---- zirconium 96 (Zr-96) + 102 0 41093.82c 82c TRA 41 93 0 92.90319 900.0 stable IBADF-T-I------R---- niobium 93 (Nb-93) + 103 0 41094.82c 82c TRA 41 94 0 93.90731 900.0 1.09898E-12 IBADF-T-I------R---- niobium 94 (Nb-94) + 104 0 41095.82c 82c TRA 41 95 0 94.90680 900.0 2.29274E-07 IBADF-T--------R---- niobium 95 (Nb-95) + 105 0 42092.82c 82c TRA 42 92 0 91.90683 900.0 1.15603E-28 IBA---T-I------R---- molybdenum 92 (Mo-92) + 106 0 42094.82c 82c TRA 42 94 0 93.90510 900.0 stable IBAD--T--------R---- molybdenum 94 (Mo-94) + 107 0 42095.82c 82c TRA 42 95 0 94.90589 900.0 stable IBADF-T--------R---- molybdenum 95 (Mo-95) + 108 0 42096.82c 82c TRA 42 96 0 95.90467 900.0 stable IBADF-T--------R---- molybdenum 96 (Mo-96) + 109 0 42097.82c 82c TRA 42 97 0 96.90597 900.0 stable IBADF-T--------R---- molybdenum 97 (Mo-97) + 110 0 42098.82c 82c TRA 42 98 0 97.90536 900.0 2.19650E-22 IBADF-T--------R---- molybdenum 98 (Mo-98) + 111 0 42099.82c 82c TRA 42 99 0 98.90767 900.0 2.91951E-06 IBADF-T--------R---- molybdenum 99 (Mo-99) + 112 0 42100.82c 82c TRA 42 100 0 99.90746 900.0 3.00890E-27 IBADF-T--------R---- molybdenum 100 (Mo-100) + 113 0 43099.82c 82c TRA 43 99 0 98.90627 900.0 1.03853E-13 IBADF-T--------R---- technetium 99 (Tc-99) + 114 0 44100.82c 82c TRA 44 100 0 99.90423 900.0 stable IBADF-T--------R---- ruthenium 100 (Ru-100) + 115 0 44101.82c 82c TRA 44 101 0 100.90583 900.0 stable IBADF-T--------R---- ruthenium 101 (Ru-101) + 116 0 44102.82c 82c TRA 44 102 0 101.90542 900.0 stable IBADF-T--------R---- ruthenium 102 (Ru-102) + 117 0 44103.82c 82c TRA 44 103 0 102.90400 900.0 2.04344E-07 IBADF-T--------R---- ruthenium 103 (Ru-103) + 118 0 44104.82c 82c TRA 44 104 0 103.90258 900.0 stable IBADF-T--------R---- ruthenium 104 (Ru-104) + 119 0 44105.82c 82c TRA 44 105 0 104.91124 900.0 4.33651E-05 IBADF-T--------R---- ruthenium 105 (Ru-105) + 120 0 44106.82c 82c TRA 44 106 0 105.90780 900.0 2.15950E-08 IBADF-T--------R---- ruthenium 106 (Ru-106) + 121 0 45103.82c 82c TRA 45 103 0 102.90551 900.0 stable IBADF-T-I------R---- rhodium 103 (Rh-103) + 122 0 45105.82c 82c TRA 45 105 0 104.90116 900.0 5.44516E-06 IBADF-T-I------R---- rhodium 105 (Rh-105) + 123 0 46105.82c 82c TRA 46 105 0 104.90519 900.0 stable IBADF-T--------R---- palladium 105 (Pd-105) + 124 0 46106.82c 82c TRA 46 106 0 105.90347 900.0 stable IBADF-T-I------R---- palladium 106 (Pd-106) + 125 0 46107.82c 82c TRA 46 107 0 106.90537 900.0 3.37923E-15 IBADF-T--------R---- palladium 107 (Pd-107) + 126 0 46108.82c 82c TRA 46 108 0 107.90385 900.0 stable IBADF-T-I------R---- palladium 108 (Pd-108) + 127 0 46110.82c 82c TRA 46 110 0 109.90514 900.0 3.66082E-26 IBADF-T-I------R---- palladium 110 (Pd-110) + 128 0 47109.82c 82c TRA 47 109 0 108.90455 900.0 stable IBADF-T-I------R---- silver 109 (Ag-109) + 129 0 47510.82c 82c TRA 47 110 1 109.90615 900.0 3.21184E-08 IBA-F-T--------R---- silver 110m (Ag-110m) + 130 0 47111.82c 82c TRA 47 111 0 110.90574 900.0 1.07685E-06 IBADF-T--------R---- silver 111 (Ag-111) + 131 0 48110.82c 82c TRA 48 110 0 109.90313 900.0 stable IBADF-T-I------R---- cadmium 110 (Cd-110) + 132 0 48111.82c 82c TRA 48 111 0 110.90473 900.0 stable IBADF-T--------R---- cadmium 111 (Cd-111) + 133 0 48112.82c 82c TRA 48 112 0 111.90331 900.0 stable IBADF-T-I------R---- cadmium 112 (Cd-112) + 134 0 48113.82c 82c TRA 48 113 0 112.89987 900.0 2.73196E-24 IBADF-T--------R---- cadmium 113 (Cd-113) + 135 0 48114.82c 82c TRA 48 114 0 113.90349 900.0 2.38750E-25 IBADF-T-I------R---- cadmium 114 (Cd-114) + 136 0 48515.82c 82c TRA 48 115 1 114.90610 900.0 1.80039E-07 IBADF-T--------R---- cadmium 115m (Cd-115m) + 137 0 48116.82c 82c TRA 48 116 0 115.90468 900.0 7.32166E-28 IBADF-T-I------R---- cadmium 116 (Cd-116) + 138 0 49113.82c 82c TRA 49 113 0 112.90390 900.0 stable IBADF-T-I------R---- indium 113 (In-113) + 139 0 49115.82c 82c TRA 49 115 0 114.90409 900.0 4.98072E-23 IBADF-T--------R---- indium 115 (In-115) + 140 0 50115.82c 82c TRA 50 115 0 114.90308 900.0 stable IBADF-T--------R---- tin 115 (Sn-115) + 141 0 50116.82c 82c TRA 50 116 0 115.90166 900.0 stable IBADF-T-I------R---- tin 116 (Sn-116) + 142 0 50117.82c 82c TRA 50 117 0 116.90326 900.0 stable IBADF-T--------R---- tin 117 (Sn-117) + 143 0 50118.82c 82c TRA 50 118 0 117.90184 900.0 stable IBADF-T-I------R---- tin 118 (Sn-118) + 144 0 50119.82c 82c TRA 50 119 0 118.90344 900.0 stable IBADF-T--------R---- tin 119 (Sn-119) + 145 0 50120.82c 82c TRA 50 120 0 119.90202 900.0 stable IBADF-T-I------R---- tin 120 (Sn-120) + 146 0 50122.82c 82c TRA 50 122 0 121.90321 900.0 stable IBADF-T-I------R---- tin 122 (Sn-122) + 147 0 50123.82c 82c TRA 50 123 0 122.90583 900.0 6.20938E-08 IBADF-T--------R---- tin 123 (Sn-123) + 148 0 50124.82c 82c TRA 50 124 0 123.90541 900.0 2.19650E-25 IBADF-T-I------R---- tin 124 (Sn-124) + 149 0 50125.82c 82c TRA 50 125 0 124.90803 900.0 8.32213E-07 IBADF-T--------R---- tin 125 (Sn-125) + 150 0 50126.82c 82c TRA 50 126 0 125.90761 900.0 9.54999E-14 IBADF-T-I------R---- tin 126 (Sn-126) + 151 0 51121.82c 82c TRA 51 121 0 120.90363 900.0 stable IBADF-T-I------R---- antimony 121 (Sb-121) + 152 0 51123.82c 82c TRA 51 123 0 122.90381 900.0 stable IBADF-T--------R---- antimony 123 (Sb-123) + 153 0 51124.82c 82c TRA 51 124 0 123.90642 900.0 1.33247E-07 IBADF-T--------R---- antimony 124 (Sb-124) + 154 0 51125.82c 82c TRA 51 125 0 124.90500 900.0 7.96250E-09 IBADF-T--------R---- antimony 125 (Sb-125) + 155 0 51126.82c 82c TRA 51 126 0 125.90761 900.0 6.46460E-07 IBADF-T--------R---- antimony 126 (Sb-126) + 156 0 52120.82c 82c TRA 52 120 0 119.90000 900.0 stable IB--F-T-I------R---- tellurium 120 (Te-120) + 157 0 52122.82c 82c TRA 52 122 0 121.90321 900.0 stable IB-DF-T-I------R---- tellurium 122 (Te-122) + 158 0 52123.82c 82c TRA 52 123 0 122.90482 900.0 2.38750E-25 IBADF-T--------R---- tellurium 123 (Te-123) + 159 0 52124.82c 82c TRA 52 124 0 123.90340 900.0 stable IBADF-T-I------R---- tellurium 124 (Te-124) + 160 0 52125.82c 82c TRA 52 125 0 124.90399 900.0 stable IBADF-T--------R---- tellurium 125 (Te-125) + 161 0 52126.82c 82c TRA 52 126 0 125.90358 900.0 stable IBADF-T-I------R---- tellurium 126 (Te-126) + 162 0 52527.82c 82c TRA 52 127 1 126.90518 900.0 7.56130E-08 IBADF-T--------R---- tellurium 127m (Te-127m) + 163 0 52128.82c 82c TRA 52 128 0 127.90477 900.0 9.98409E-33 IBADF-T-I------R---- tellurium 128 (Te-128) + 164 0 52529.82c 82c TRA 52 129 1 128.90738 900.0 2.38766E-07 IBADF-T--------R---- tellurium 129m (Te-129m) + 165 0 52130.82c 82c TRA 52 130 0 129.90596 900.0 2.78037E-29 IBADF-T-I------R---- tellurium 130 (Te-130) + 166 0 52132.82c 82c TRA 52 132 0 131.90816 900.0 2.48376E-06 IBADF-T-I------R---- tellurium 132 (Te-132) + 167 0 53127.82c 82c TRA 53 127 0 126.90448 900.0 stable IBADF-T--------R---- iodine 127 (I-127) + 168 0 53129.82c 82c TRA 53 129 0 128.90496 900.0 1.36428E-15 IBADF-T-I------R---- iodine 129 (I-129) + 169 0 53130.82c 82c TRA 53 130 0 129.90697 900.0 1.55777E-05 IBADF-T--------R---- iodine 130 (I-130) + 170 0 53131.82c 82c TRA 53 131 0 130.90555 900.0 9.99905E-07 IBADF-T-I------R---- iodine 131 (I-131) + 171 0 53135.82c 82c TRA 53 135 0 134.90894 900.0 2.92615E-05 IBADF-T--------R---- iodine 135 (I-135) + 172 0 54128.82c 82c TRA 54 128 0 127.90275 900.0 stable IBADF-T-I------R---- xenon 128 (Xe-128) + 173 0 54129.82c 82c TRA 54 129 0 128.90536 900.0 stable IBADF-T--------R---- xenon 129 (Xe-129) + 174 0 54130.82c 82c TRA 54 130 0 129.90394 900.0 stable IBADF-T-I------R---- xenon 130 (Xe-130) + 175 0 54131.82c 82c TRA 54 131 0 130.90555 900.0 stable IBADF-T--------R---- xenon 131 (Xe-131) + 176 0 54132.82c 82c TRA 54 132 0 131.90312 900.0 stable IBADF-T-I------R---- xenon 132 (Xe-132) + 177 0 54133.82c 82c TRA 54 133 0 132.90573 900.0 1.52886E-06 IBADF-T-I------R---- xenon 133 (Xe-133) + 178 0 54134.82c 82c TRA 54 134 0 133.91036 900.0 1.99682E-24 IBADF-T-I------R---- xenon 134 (Xe-134) + 179 0 54135.82c 82c TRA 54 135 0 134.90692 900.0 2.10657E-05 IBADF-T--------R---- xenon 135 (Xe-135) + 180 0 54136.82c 82c TRA 54 136 0 135.90752 900.0 2.19650E-30 IBADF-T--------R---- xenon 136 (Xe-136) + 181 0 55133.82c 82c TRA 55 133 0 132.90573 900.0 stable IBADF-T-I------R---- cesium 133 (Cs-133) + 182 0 55134.82c 82c TRA 55 134 0 133.90733 900.0 1.06399E-08 IBADF-T-I------R---- cesium 134 (Cs-134) + 183 0 55135.82c 82c TRA 55 135 0 134.90591 900.0 9.54999E-15 IBADF-T-I------R---- cesium 135 (Cs-135) + 184 0 55136.82c 82c TRA 55 136 0 135.90752 900.0 6.15698E-07 IBADF-T--------R---- cesium 136 (Cs-136) + 185 0 55137.82c 82c TRA 55 137 0 136.90711 900.0 7.30947E-10 IBADF-T-I------R---- cesium 137 (Cs-137) + 186 0 56134.82c 82c TRA 56 134 0 133.90431 900.0 stable IBADF-T-I------R---- barium 134 (Ba-134) + 187 0 56135.82c 82c TRA 56 135 0 134.90591 900.0 stable IBADF-T-I------R---- barium 135 (Ba-135) + 188 0 56136.82c 82c TRA 56 136 0 135.90449 900.0 stable IBADF-T-I------R---- barium 136 (Ba-136) + 189 0 56137.82c 82c TRA 56 137 0 136.90610 900.0 stable IBADF-T--------R---- barium 137 (Ba-137) + 190 0 56138.82c 82c TRA 56 138 0 137.90467 900.0 stable IBADF-T--------R---- barium 138 (Ba-138) + 191 0 56140.82c 82c TRA 56 140 0 139.90990 900.0 6.29070E-07 IBADF-T--------R---- barium 140 (Ba-140) + 192 0 57138.82c 82c TRA 57 138 0 137.90669 900.0 2.12017E-19 IBA-F-T--------R---- lanthanum 138 (La-138) + 193 0 57139.82c 82c TRA 57 139 0 138.90325 900.0 stable IBADF-T--------R---- lanthanum 139 (La-139) + 194 0 57140.82c 82c TRA 57 140 0 139.90990 900.0 4.77937E-06 IBADF-T--------R---- lanthanum 140 (La-140) + 195 0 58140.82c 82c TRA 58 140 0 139.90587 900.0 stable IBADF-T--------R---- cerium 140 (Ce-140) + 196 0 58141.82c 82c TRA 58 141 0 140.91050 900.0 2.46824E-07 IBADF-T--------R---- cerium 141 (Ce-141) + 197 0 58142.82c 82c TRA 58 142 0 141.90907 900.0 4.39299E-25 IBADF-T--------R---- cerium 142 (Ce-142) + 198 0 58143.82c 82c TRA 58 143 0 142.91270 900.0 5.82770E-06 IBADF-T--------R---- cerium 143 (Ce-143) + 199 0 58144.82c 82c TRA 58 144 0 143.91430 900.0 2.81601E-08 IBADF-T--------R---- cerium 144 (Ce-144) + 200 0 59141.82c 82c TRA 59 141 0 140.90747 900.0 stable IBADF-T-I------R---- praseodymium 141 (Pr-141) + 201 0 59142.82c 82c TRA 59 142 0 141.91008 900.0 1.00701E-05 IBADF-T--------R---- praseodymium 142 (Pr-142) + 202 0 59143.82c 82c TRA 59 143 0 142.91068 900.0 5.91635E-07 IBADF-T-I------R---- praseodymium 143 (Pr-143) + 203 0 60144.82c 82c TRA 60 144 0 143.91027 900.0 9.59169E-24 IBADF-T--------R---- neodymium 144 (Nd-144) + 204 0 60145.82c 82c TRA 60 145 0 144.91288 900.0 stable IBADF-T--------R---- neodymium 145 (Nd-145) + 205 0 60146.82c 82c TRA 60 146 0 145.91347 900.0 stable IBADF-T--------R---- neodymium 146 (Nd-146) + 206 0 60147.82c 82c TRA 60 147 0 146.91609 900.0 7.27998E-07 IBADF-T--------R---- neodymium 147 (Nd-147) + 207 0 60148.82c 82c TRA 60 148 0 147.91668 900.0 7.32166E-27 IBADF-T--------R---- neodymium 148 (Nd-148) + 208 0 60150.82c 82c TRA 60 150 0 149.92090 900.0 3.27836E-27 IBADF-T--------R---- neodymium 150 (Nd-150) + 209 0 61147.82c 82c TRA 61 147 0 146.91508 900.0 8.37701E-09 IBADF-T-I------R---- promethium 147 (Pm-147) + 210 0 61148.82c 82c TRA 61 148 0 147.91668 900.0 1.49395E-06 IBADF-T--------R---- promethium 148 (Pm-148) + 211 0 61548.82c 82c TRA 61 148 1 147.92072 900.0 1.94297E-07 IBA-F-T--------R---- promethium 148m (Pm-148m) + 212 0 61149.82c 82c TRA 61 149 0 148.91829 900.0 3.62737E-06 IBADF-T--------R---- promethium 149 (Pm-149) + 213 0 61151.82c 82c TRA 61 151 0 150.92150 900.0 6.77961E-06 IBADF-T--------R---- promethium 151 (Pm-151) + 214 0 62147.82c 82c TRA 62 147 0 146.91508 900.0 2.05280E-19 IBAD--T--------R---- samarium 147 (Sm-147) + 215 0 62148.82c 82c TRA 62 148 0 147.91467 900.0 3.13786E-24 IBAD--T--------R---- samarium 148 (Sm-148) + 216 0 62149.82c 82c TRA 62 149 0 148.91728 900.0 1.09823E-23 IBADF-T--------R---- samarium 149 (Sm-149) + 217 0 62150.82c 82c TRA 62 150 0 149.91687 900.0 stable IBADF-T--------R---- samarium 150 (Sm-150) + 218 0 62151.82c 82c TRA 62 151 0 150.91645 900.0 2.31943E-10 IBADF-T--------R---- samarium 151 (Sm-151) + 219 0 62152.82c 82c TRA 62 152 0 151.92007 900.0 stable IBADF-T--------R---- samarium 152 (Sm-152) + 220 0 62153.82c 82c TRA 62 153 0 152.92168 900.0 4.15987E-06 IBADF-T--------R---- samarium 153 (Sm-153) + 221 0 62154.82c 82c TRA 62 154 0 153.92227 900.0 stable IBADF-T--------R---- samarium 154 (Sm-154) + 222 0 63151.82c 82c TRA 63 151 0 150.91948 900.0 stable IBADF-T--------R---- europium 151 (Eu-151) + 223 0 63152.82c 82c TRA 63 152 0 151.92209 900.0 1.62439E-09 IBADF-T--------R---- europium 152 (Eu-152) + 224 0 63153.82c 82c TRA 63 153 0 152.92168 900.0 stable IBADF-T-I------R---- europium 153 (Eu-153) + 225 0 63154.82c 82c TRA 63 154 0 153.92227 900.0 2.55377E-09 IBADF-T--------R---- europium 154 (Eu-154) + 226 0 63155.82c 82c TRA 63 155 0 154.92287 900.0 4.62129E-09 IBADF-T--------R---- europium 155 (Eu-155) + 227 0 63156.82c 82c TRA 63 156 0 155.92548 900.0 5.28144E-07 IBADF-T--------R---- europium 156 (Eu-156) + 228 0 63157.82c 82c TRA 63 157 0 156.92507 900.0 1.26839E-05 IBADF-T--------R---- europium 157 (Eu-157) + 229 0 64152.82c 82c TRA 64 152 0 151.92007 900.0 2.03379E-22 IB-D--T--------R---- gadolinium 152 (Gd-152) + 230 0 64154.82c 82c TRA 64 154 0 153.92127 900.0 stable IB-DF-T--------R---- gadolinium 154 (Gd-154) + 231 0 64155.82c 82c TRA 64 155 0 154.92287 900.0 stable IBADF-T--------R---- gadolinium 155 (Gd-155) + 232 0 64156.82c 82c TRA 64 156 0 155.92205 900.0 stable IBADF-T--------R---- gadolinium 156 (Gd-156) + 233 0 64157.82c 82c TRA 64 157 0 156.92406 900.0 stable IBADF-T--------R---- gadolinium 157 (Gd-157) + 234 0 64158.82c 82c TRA 64 158 0 157.92466 900.0 stable IBADF-T--------R---- gadolinium 158 (Gd-158) + 235 0 64160.82c 82c TRA 64 160 0 159.92686 900.0 1.68958E-25 IBADF-T--------R---- gadolinium 160 (Gd-160) + 236 0 65159.82c 82c TRA 65 159 0 158.92525 900.0 stable IBADF-T--------R---- terbium 159 (Tb-159) + 237 0 65160.82c 82c TRA 65 160 0 159.92686 900.0 1.10962E-07 IBA-F-T--------R---- terbium 160 (Tb-160) + 238 0 66160.82c 82c TRA 66 160 0 159.92484 900.0 stable IBADF-T--------R---- dysprosium 160 (Dy-160) + 239 0 66161.82c 82c TRA 66 161 0 160.92644 900.0 stable IBADF-T--------R---- dysprosium 161 (Dy-161) + 240 0 66162.82c 82c TRA 66 162 0 161.92704 900.0 stable IBADF-T--------R---- dysprosium 162 (Dy-162) + 241 0 66163.82c 82c TRA 66 163 0 162.92864 900.0 stable IBADF-T--------R---- dysprosium 163 (Dy-163) + 242 0 66164.82c 82c TRA 66 164 0 163.92823 900.0 stable IBADF-T-I------R---- dysprosium 164 (Dy-164) + 243 0 67165.82c 82c TRA 67 165 0 164.92983 900.0 stable IBADF-T-I------R---- holmium 165 (Ho-165) + 244 0 68164.82c 82c TRA 68 164 0 163.92924 900.0 stable IBADF-T--------R---- erbium 164 (Er-164) + 245 0 68166.82c 82c TRA 68 166 0 165.93043 900.0 stable IBADF-T-I------R---- erbium 166 (Er-166) + 246 0 68167.82c 82c TRA 68 167 0 166.93204 900.0 stable IBADF-T--------R---- erbium 167 (Er-167) + 247 0 68168.82c 82c TRA 68 168 0 167.92960 900.0 stable IBADF-T--------R---- erbium 168 (Er-168) + 248 0 68170.82c 82c TRA 68 170 0 169.93584 900.0 stable IB-DF-T--------R---- erbium 170 (Er-170) + 249 0 71175.82c 82c TRA 71 175 0 174.94083 900.0 stable IBADF-T-I------R---- lutetium 175 (Lu-175) + 250 0 71176.82c 82c TRA 71 176 0 175.94143 900.0 5.84175E-19 IBA-F-T-I------R---- lutetium 176 (Lu-176) + 251 0 72176.82c 82c TRA 72 176 0 175.94042 900.0 stable IBADF-T--------R---- hafnium 176 (Hf-176) + 252 0 72177.82c 82c TRA 72 177 0 176.94001 900.0 stable IBADF-T--------R---- hafnium 177 (Hf-177) + 253 0 72178.82c 82c TRA 72 178 0 177.93959 900.0 stable IBADF-T--------R---- hafnium 178 (Hf-178) + 254 0 72179.82c 82c TRA 72 179 0 178.95028 900.0 stable IBADF-T-I------R---- hafnium 179 (Hf-179) + 255 0 72180.82c 82c TRA 72 180 0 179.94986 900.0 stable IBADF-T--------R---- hafnium 180 (Hf-180) + 256 0 73181.82c 82c TRA 73 181 0 180.94844 900.0 stable IBADF-T--------R---- tantalum 181 (Ta-181) + 257 0 73182.82c 82c TRA 73 182 0 181.95005 900.0 6.99437E-08 IBADF-T--------R---- tantalum 182 (Ta-182) + 258 0 74182.82c 82c TRA 74 182 0 181.94803 900.0 stable IBADF-T-I------R---- tungsten 182 (W-182) + 259 0 74183.82c 82c TRA 74 183 0 182.95064 900.0 1.99677E-25 IBADF-T--------R---- tungsten 183 (W-183) + 260 0 74184.82c 82c TRA 74 184 0 183.95124 900.0 5.49114E-26 IBADF-T-I------R---- tungsten 184 (W-184) + 261 0 74186.82c 82c TRA 74 186 0 185.95445 900.0 3.72279E-26 IB-DF-T--------R---- tungsten 186 (W-186) + 262 0 75185.82c 82c TRA 75 185 0 184.95284 900.0 stable IBADF-T-I------R---- rhenium 185 (Re-185) + 263 0 75187.82c 82c TRA 75 187 0 186.95605 900.0 5.07276E-19 IB-DF-T-I------R---- rhenium 187 (Re-187) + 264 0 77191.82c 82c TRA 77 191 0 190.96045 900.0 stable IBADF-T--------R---- iridium 191 (Ir-191) + 265 0 77193.82c 82c TRA 77 193 0 192.96265 900.0 stable IB-DF-T--------R---- iridium 193 (Ir-193) + 266 0 79197.82c 82c TRA 79 197 0 196.96604 900.0 stable IBADF-T-I------R---- gold 197 (Au-197) + 267 0 80198.82c 82c TRA 80 198 0 197.96664 900.0 stable IBADF-T-I------R---- mercury 198 (Hg-198) + 268 0 80199.82c 82c TRA 80 199 0 198.96824 900.0 stable IBADF-T--------R---- mercury 199 (Hg-199) + 269 0 80200.82c 82c TRA 80 200 0 199.96783 900.0 stable IBADF-T--------R---- mercury 200 (Hg-200) + 270 0 90227.82c 82c TRA 90 227 0 227.02729 900.0 4.28599E-07 IBAD--T--F-D---RN--- thorium 227 (Th-227) + 271 0 90228.82c 82c TRA 90 228 0 228.02889 900.0 1.14844E-08 IBAD--T--F-----RN--- thorium 228 (Th-228) + 272 0 90229.82c 82c TRA 90 229 0 229.03150 900.0 2.99244E-12 IBAD--T--F-D---RN--- thorium 229 (Th-229) + 273 0 90230.82c 82c TRA 90 230 0 230.03613 900.0 2.91307E-13 IBAD--T--F-----RN--- thorium 230 (Th-230) + 274 0 91231.82c 82c TRA 91 231 0 231.03471 900.0 6.70465E-13 IBAD--T--F-D---RN--- protactinium 231 (Pa-231) + 275 0 91232.82c 82c TRA 91 232 0 232.03833 900.0 6.12407E-06 IBAD--T--F-----RN--- protactinium 232 (Pa-232) + 276 0 91233.82c 82c TRA 91 233 0 233.03994 900.0 2.97352E-07 IBAD--T-IF-----RN--- protactinium 233 (Pa-233) + 277 0 92232.82c 82c TRA 92 232 0 232.03329 900.0 3.14678E-10 IBAD--T--F-D---RN--- uranium 232 (U-232) + 278 0 92233.82c 82c TRA 92 233 0 233.03994 900.0 1.37925E-13 IBAD--T--F-D---RN--- uranium 233 (U-233) + 279 0 92234.82c 82c TRA 92 234 0 234.04053 900.0 8.93957E-14 IBAD--T-IF-D---RN--- uranium 234 (U-234) + 280 0 92235.82c 82c TRA 92 235 0 235.04415 900.0 3.12085E-17 IBAD--T--F-D---RN--- uranium 235 (U-235) + 281 0 92236.82c 82c TRA 92 236 0 236.04556 900.0 9.26773E-16 IBAD--T--F-D---RN--- uranium 236 (U-236) + 282 0 92237.82c 82c TRA 92 237 0 237.04878 900.0 1.18870E-06 IBAD--T--F-D---RN--- uranium 237 (U-237) + 283 0 92238.82c 82c TRA 92 238 0 238.05078 900.0 4.91608E-18 IBAD--T--F-D---RN--- uranium 238 (U-238) + 284 0 93235.82c 82c TRA 93 235 0 235.04415 900.0 2.02629E-08 IBAD--T-IF-----RN--- neptunium 235 (Np-235) + 285 0 93236.82c 82c TRA 93 236 0 236.04677 900.0 1.41710E-13 IBAD--T--F-----RN--- neptunium 236 (Np-236) + 286 0 93237.82c 82c TRA 93 237 0 237.04817 900.0 1.02449E-14 IBAD--T--F-D---RN--- neptunium 237 (Np-237) + 287 0 93238.82c 82c TRA 93 238 0 238.05098 900.0 3.81662E-06 IBAD--T--F-D---RN--- neptunium 238 (Np-238) + 288 0 93239.82c 82c TRA 93 239 0 239.05259 900.0 3.40516E-06 IBAD--T-IF-----RN--- neptunium 239 (Np-239) + 289 0 94236.82c 82c TRA 94 236 0 236.04576 900.0 7.68527E-09 IBAD--T-IF-----RN--- plutonium 236 (Pu-236) + 290 0 94237.82c 82c TRA 94 237 0 237.04837 900.0 1.77098E-07 IBAD--T--F-----RN--- plutonium 237 (Pu-237) + 291 0 94238.82c 82c TRA 94 238 0 238.04998 900.0 2.50456E-10 IBAD--T--F-D---RN--- plutonium 238 (Pu-238) + 292 0 94239.82c 82c TRA 94 239 0 239.05198 900.0 9.10900E-13 IBAD--T--F-D---RN--- plutonium 239 (Pu-239) + 293 0 94240.82c 82c TRA 94 240 0 240.05379 900.0 3.34679E-12 IBAD--T--F-D---RN--- plutonium 240 (Pu-240) + 294 0 94241.82c 82c TRA 94 241 0 241.05681 900.0 1.53280E-09 IBAD--T--F-D---RN--- plutonium 241 (Pu-241) + 295 0 94242.82c 82c TRA 94 242 0 242.05841 900.0 5.88071E-14 IBAD--T--F-D---RN--- plutonium 242 (Pu-242) + 296 0 94243.82c 82c TRA 94 243 0 243.06203 900.0 3.88501E-05 IBAD--T--F-----RN--- plutonium 243 (Pu-243) + 297 0 94244.82c 82c TRA 94 244 0 244.06465 900.0 2.74556E-16 IBAD--T--F-----RN--- plutonium 244 (Pu-244) + 298 0 95241.82c 82c TRA 95 241 0 241.05681 900.0 5.07499E-11 IBAD--T-IF-D---RN--- americium 241 (Am-241) + 299 0 95642.82c 82c TRA 95 242 0 242.05942 900.0 1.20263E-05 IBAD--T--F-----RN--- americium 242 (Am-242) + 300 0 95242.82c 82c TRA 95 242 1 242.05942 900.0 1.55777E-10 IBA---T--F-D---RN--- americium 242m (Am-242m) + 301 0 95243.82c 82c TRA 95 243 0 243.06102 900.0 2.98236E-12 IBAD--T-IF-D---RN--- americium 243 (Am-243) + 302 0 95244.82c 82c TRA 95 244 0 244.06465 900.0 1.90635E-05 IBA---T--F-----RN--- americium 244 (Am-244) + 303 0 95644.82c 82c TRA 95 244 1 244.06465 900.0 4.44325E-04 IBA---T--F-----RN--- americium 244m (Am-244m) + 304 0 96240.82c 82c TRA 96 240 0 240.05520 900.0 2.97131E-07 IBA---T--F-----RN--- curium 240 (Cm-240) + 305 0 96241.82c 82c TRA 96 241 0 241.05781 900.0 2.44590E-07 IBA---T--F-----RN--- curium 241 (Cm-241) + 306 0 96242.82c 82c TRA 96 242 0 242.05841 900.0 4.92390E-08 IBAD--T--F-D---RNS-- curium 242 (Cm-242) + 307 0 96243.82c 82c TRA 96 243 0 243.06102 900.0 7.60034E-10 IBA---T--F-D---RN--- curium 243 (Cm-243) + 308 0 96244.82c 82c TRA 96 244 0 244.06263 900.0 1.22025E-09 IBAD--T--F-D---RNS-- curium 244 (Cm-244) + 309 0 96245.82c 82c TRA 96 245 0 245.06524 900.0 2.66242E-12 IBAD--T--F-D---RN--- curium 245 (Cm-245) + 310 0 96246.82c 82c TRA 96 246 0 246.06685 900.0 4.64367E-12 IBAD--T--F-D---RN--- curium 246 (Cm-246) + 311 0 96247.82c 82c TRA 96 247 0 247.06946 900.0 1.37278E-15 IBAD--T--F-----RN--- curium 247 (Cm-247) + 312 0 96248.82c 82c TRA 96 248 0 248.07207 900.0 6.46014E-14 IBA---T--F-D---RN--- curium 248 (Cm-248) + 313 0 96249.82c 82c TRA 96 249 0 249.07569 900.0 1.80085E-04 IBA---T--F-----RN--- curium 249 (Cm-249) + 314 0 96250.82c 82c TRA 96 250 0 250.07831 900.0 2.74556E-12 IBA---T--F-----RN--- curium 250 (Cm-250) + 315 0 20060 82c DEC 2 6 0 6.01889 900.0 8.57749E-01 IBA-F----------R---- helium 6 (He-6) + 316 0 20080 82c DEC 2 8 0 8.03393 900.0 5.68153E+00 IB--F-----P----R---- helium 8 (He-8) + 317 0 30080 82c DEC 3 8 0 8.02249 900.0 8.27145E-01 IBADF----------R---- lithium 8 (Li-8) + 318 0 30090 82c DEC 3 9 0 9.02679 900.0 3.88753E+00 IBA-F-----P----R---- lithium 9 (Li-9) + 319 0 40060 82c DEC 4 6 0 6.01972 900.0 1.38629E+20 IB-D-----------R---- beryllium 6 (Be-6) + 320 0 40080 82c DEC 4 8 0 8.00531 900.0 9.90210E+15 IBADF----------R---- beryllium 8 (Be-8) + 321 0 40100 82c DEC 4 10 0 10.01353 900.0 1.37278E-14 IBA-F----------R---- beryllium 10 (Be-10) + 322 0 40110 82c DEC 4 11 0 11.02168 900.0 5.01917E-02 IBA-F----------R---- beryllium 11 (Be-11) + 323 0 40120 82c DEC 4 12 0 12.02692 900.0 3.25421E+01 IB--F----------R---- beryllium 12 (Be-12) + 324 0 50090 82c DEC 5 9 0 9.01333 900.0 8.66434E+17 IB--F----------R---- boron 9 (B-9) + 325 0 50120 82c DEC 5 12 0 12.01431 900.0 3.43142E+01 IBADF----------R---- boron 12 (B-12) + 326 0 60080 82c DEC 6 8 0 8.03768 900.0 3.46574E+20 IB--F----------R---- carbon 8 (C-8) + 327 0 60120 82c DEC 6 12 0 11.99999 900.0 stable IBAD-----------R---- carbon 12 (C-12) + 328 0 60130 82c DEC 6 13 0 13.00331 900.0 stable IBAD-----------R---- carbon 13 (C-13) + 329 0 60140 82c DEC 6 14 0 14.00319 900.0 3.85352E-12 IBA-F----------R---- carbon 14 (C-14) + 330 0 60150 82c DEC 6 15 0 15.01065 900.0 2.83033E-01 IBA-F----------R---- carbon 15 (C-15) + 331 0 70130 82c DEC 7 13 0 13.00573 900.0 1.15907E-03 IBA------------R---- nitrogen 13 (N-13) + 332 0 70160 82c DEC 7 16 0 16.00610 900.0 9.72156E-02 IBA------------R---- nitrogen 16 (N-16) + 333 0 70170 82c DEC 7 17 0 17.00841 900.0 1.66222E-01 IBA-------P----R---- nitrogen 17 (N-17) + 334 0 80150 82c DEC 8 15 0 15.00308 900.0 5.66019E-03 IBA------------R---- oxygen 15 (O-15) + 335 0 80180 82c DEC 8 18 0 17.99912 900.0 stable IBAD-----------R---- oxygen 18 (O-18) + 336 0 80190 82c DEC 8 19 0 19.00355 900.0 2.57580E-02 IBA------------R---- oxygen 19 (O-19) + 337 0 90180 82c DEC 9 18 0 18.00094 900.0 1.05277E-04 IBA------------R---- fluorine 18 (F-18) + 338 0 90200 82c DEC 9 20 0 20.00001 900.0 6.28420E-02 IBA------------R---- fluorine 20 (F-20) + 339 0 100200 82c DEC 10 20 0 19.99245 900.0 stable IBAD-----------R---- neon 20 (Ne-20) + 340 0 100210 82c DEC 10 21 0 20.99385 900.0 stable IBADF----------R---- neon 21 (Ne-21) + 341 0 100220 82c DEC 10 22 0 21.99142 900.0 stable IBAD-----------R---- neon 22 (Ne-22) + 342 0 100230 82c DEC 10 23 0 22.99443 900.0 1.86330E-02 IBA------------R---- neon 23 (Ne-23) + 343 0 110210 82c DEC 11 21 0 20.99768 900.0 3.08202E-02 IBA------------R---- sodium 21 (Na-21) + 344 0 110240 82c DEC 11 24 0 23.99100 900.0 1.28721E-05 IBAD-----------R---- sodium 24 (Na-24) + 345 0 110241 82c DEC 11 24 1 23.99100 900.0 3.43142E+01 IBA------------R---- sodium 24m (Na-24m) + 346 0 110250 82c DEC 11 25 0 24.98998 900.0 1.16300E-02 IBA------------R---- sodium 25 (Na-25) + 347 0 110260 82c DEC 11 26 0 25.99259 900.0 6.41803E-01 IBA------------R---- sodium 26 (Na-26) + 348 0 120230 82c DEC 12 23 0 22.99413 900.0 6.12483E-02 IBA------------R---- magnesium 23 (Mg-23) + 349 0 120270 82c DEC 12 27 0 26.98431 900.0 1.22145E-03 IBA------------R---- magnesium 27 (Mg-27) + 350 0 120280 82c DEC 12 28 0 27.98390 900.0 9.21248E-06 IBA------------R---- magnesium 28 (Mg-28) + 351 0 120290 82c DEC 12 29 0 28.98863 900.0 5.33190E-01 IBA------------R---- magnesium 29 (Mg-29) + 352 0 130260 82c DEC 13 26 0 25.98684 900.0 3.06346E-14 IBA------------R---- aluminum 26 (Al-26) + 353 0 130280 82c DEC 13 28 0 27.98188 900.0 5.15504E-03 IBAD-----------R---- aluminum 28 (Al-28) + 354 0 130290 82c DEC 13 29 0 28.98046 900.0 1.76104E-03 IBAD-----------R---- aluminum 29 (Al-29) + 355 0 130300 82c DEC 13 30 0 29.98297 900.0 1.89903E-01 IBA------------R---- aluminum 30 (Al-30) + 356 0 140270 82c DEC 14 27 0 26.98673 900.0 1.66622E-01 IBA------------R---- silicon 27 (Si-27) + 357 0 140310 82c DEC 14 31 0 30.97540 900.0 7.34889E-05 IBA------------R---- silicon 31 (Si-31) + 358 0 140320 82c DEC 14 32 0 31.97418 900.0 6.65592E-11 IBA------------R---- silicon 32 (Si-32) + 359 0 140330 82c DEC 14 33 0 32.97800 900.0 1.12160E-01 IBA------------R---- silicon 33 (Si-33) + 360 0 150300 82c DEC 15 30 0 29.97833 900.0 4.62468E-03 IBA------------R---- phosphorus 30 (P-30) + 361 0 150320 82c DEC 15 32 0 31.97387 900.0 5.62195E-07 IBAD-----------R---- phosphorus 32 (P-32) + 362 0 150330 82c DEC 15 33 0 32.97174 900.0 3.16060E-07 IBAD-----------R---- phosphorus 33 (P-33) + 363 0 150340 82c DEC 15 34 0 33.97365 900.0 5.58990E-02 IBA------------R---- phosphorus 34 (P-34) + 364 0 150350 82c DEC 15 35 0 34.97334 900.0 1.46543E-02 IBA------------R---- phosphorus 35 (P-35) + 365 0 150360 82c DEC 15 36 0 35.97827 900.0 1.23776E-01 IBA------------R---- phosphorus 36 (P-36) + 366 0 160320 82c DEC 16 32 0 31.97206 900.0 stable IB-D-----------R---- sulfur 32 (S-32) + 367 0 160330 82c DEC 16 33 0 32.97144 900.0 stable IBAD-----------R---- sulfur 33 (S-33) + 368 0 160350 82c DEC 16 35 0 34.96900 900.0 9.19488E-08 IBAD-----------R---- sulfur 35 (S-35) + 369 0 160370 82c DEC 16 37 0 36.97110 900.0 2.31512E-03 IBA------------R---- sulfur 37 (S-37) + 370 0 160380 82c DEC 16 38 0 37.97119 900.0 6.78359E-05 IBA------------R---- sulfur 38 (S-38) + 371 0 170340 82c DEC 17 34 0 33.97375 900.0 4.54225E-01 IBA------------R---- chlorine 34 (Cl-34) + 372 0 170360 82c DEC 17 36 0 35.96829 900.0 7.27317E-14 IBA------------R---- chlorine 36 (Cl-36) + 373 0 170380 82c DEC 17 38 0 37.96796 900.0 3.10550E-04 IBAD-----------R---- chlorine 38 (Cl-38) + 374 0 170381 82c DEC 17 38 1 37.96796 900.0 9.69437E-01 IBA------------R---- chlorine 38m (Cl-38m) + 375 0 170390 82c DEC 17 39 0 38.96806 900.0 2.07778E-04 IBA------------R---- chlorine 39 (Cl-39) + 376 0 170400 82c DEC 17 40 0 39.97037 900.0 8.55737E-03 IBA------------R---- chlorine 40 (Cl-40) + 377 0 180360 82c DEC 18 36 0 35.96758 900.0 stable IB-D-----------R---- argon 36 (Ar-36) + 378 0 180370 82c DEC 18 37 0 36.96676 900.0 2.29150E-07 IBA------------R---- argon 37 (Ar-37) + 379 0 180390 82c DEC 18 39 0 38.96432 900.0 8.16525E-11 IBAD-----------R---- argon 39 (Ar-39) + 380 0 180410 82c DEC 18 41 0 40.96451 900.0 1.05398E-04 IBA------------R---- argon 41 (Ar-41) + 381 0 180420 82c DEC 18 42 0 41.96309 900.0 6.65592E-10 IBA------------R---- argon 42 (Ar-42) + 382 0 180430 82c DEC 18 43 0 42.96560 900.0 2.15129E-03 IBA------------R---- argon 43 (Ar-43) + 383 0 190380 82c DEC 19 38 0 37.96907 900.0 1.51806E-03 IBA------------R---- potassium 38 (K-38) + 384 0 190420 82c DEC 19 42 0 41.96238 900.0 1.55790E-05 IBAD-----------R---- potassium 42 (K-42) + 385 0 190430 82c DEC 19 43 0 42.96076 900.0 8.67301E-06 IBAD-----------R---- potassium 43 (K-43) + 386 0 190440 82c DEC 19 44 0 43.96155 900.0 5.22027E-04 IBA------------R---- potassium 44 (K-44) + 387 0 190500 82c DEC 19 50 0 49.97279 900.0 1.46853E+00 IB--F-----P----R---- potassium 50 (K-50) + 388 0 190510 82c DEC 19 51 0 50.97641 900.0 1.89903E+00 IB--F-----P----R---- potassium 51 (K-51) + 389 0 200400 82c DEC 20 40 0 39.96260 900.0 stable IB-D-----------R---- calcium 40 (Ca-40) + 390 0 200410 82c DEC 20 41 0 40.96229 900.0 2.19212E-13 IBA------------R---- calcium 41 (Ca-41) + 391 0 200450 82c DEC 20 45 0 44.95620 900.0 4.93269E-08 IBA------------R---- calcium 45 (Ca-45) + 392 0 200460 82c DEC 20 46 0 45.95367 900.0 stable IBA------------R---- calcium 46 (Ca-46) + 393 0 200470 82c DEC 20 47 0 46.95456 900.0 1.76786E-06 IBA------------R---- calcium 47 (Ca-47) + 394 0 200480 82c DEC 20 48 0 47.95254 900.0 4.14425E-28 IBA------------R---- calcium 48 (Ca-48) + 395 0 200490 82c DEC 20 49 0 48.95566 900.0 1.32482E-03 IB-D-----------R---- calcium 49 (Ca-49) + 396 0 200500 82c DEC 20 50 0 49.95756 900.0 4.98667E-02 IB-DF----------R---- calcium 50 (Ca-50) + 397 0 200510 82c DEC 20 51 0 50.96149 900.0 6.93147E-02 IB-DF----------R---- calcium 51 (Ca-51) + 398 0 200520 82c DEC 20 52 0 51.96511 900.0 1.50684E-01 IB--F-----P----R---- calcium 52 (Ca-52) + 399 0 200530 82c DEC 20 53 0 52.97004 900.0 7.70164E+00 IB--F-----P----R---- calcium 53 (Ca-53) + 400 0 200540 82c DEC 20 54 0 53.97437 900.0 1.38629E+01 IB--F----------R---- calcium 54 (Ca-54) + 401 0 210440 82c DEC 21 44 0 43.95943 900.0 4.84990E-05 IBA------------R---- scandium 44 (Sc-44) + 402 0 210451 82c DEC 21 45 1 44.95589 900.0 2.13276E+00 IB-D-----------R---- scandium 45m (Sc-45m) + 403 0 210460 82c DEC 21 46 0 45.95518 900.0 9.57491E-08 IBAD-----------R---- scandium 46 (Sc-46) + 404 0 210461 82c DEC 21 46 1 45.95518 900.0 3.70667E-02 IBA------------R---- scandium 46m (Sc-46m) + 405 0 210470 82c DEC 21 47 0 46.95245 900.0 2.39586E-06 IBAD-----------R---- scandium 47 (Sc-47) + 406 0 210480 82c DEC 21 48 0 47.95224 900.0 4.40900E-06 IBAD-----------R---- scandium 48 (Sc-48) + 407 0 210490 82c DEC 21 49 0 48.95001 900.0 2.01966E-04 IBAD-----------R---- scandium 49 (Sc-49) + 408 0 210500 82c DEC 21 50 0 49.95222 900.0 6.76241E-03 IBADF----------R---- scandium 50 (Sc-50) + 409 0 210501 82c DEC 21 50 1 49.95222 900.0 1.98042E+00 IB-DF----------R---- scandium 50m (Sc-50m) + 410 0 210510 82c DEC 21 51 0 50.95362 900.0 5.58990E-02 IB-DF----------R---- scandium 51 (Sc-51) + 411 0 210520 82c DEC 21 52 0 51.95664 900.0 8.45301E-02 IB-DF----------R---- scandium 52 (Sc-52) + 412 0 210530 82c DEC 21 53 0 52.95965 900.0 2.31049E-01 IB-DF----------R---- scandium 53 (Sc-53) + 413 0 210540 82c DEC 21 54 0 53.96327 900.0 2.66595E+00 IB-DF----------R---- scandium 54 (Sc-54) + 414 0 210550 82c DEC 21 55 0 54.96821 900.0 5.77623E+00 IB--F----------R---- scandium 55 (Sc-55) + 415 0 210560 82c DEC 21 56 0 55.97284 900.0 8.66434E+00 IB--F----------R---- scandium 56 (Sc-56) + 416 0 210570 82c DEC 21 57 0 56.97777 900.0 5.33190E+01 IB--F-----P----R---- scandium 57 (Sc-57) + 417 0 220450 82c DEC 22 45 0 44.95811 900.0 6.25133E-05 IBA------------R---- titanium 45 (Ti-45) + 418 0 220510 82c DEC 22 51 0 50.94666 900.0 1.99180E-03 IBADF----------R---- titanium 51 (Ti-51) + 419 0 220520 82c DEC 22 52 0 51.94685 900.0 6.79556E-03 IB-DF----------R---- titanium 52 (Ti-52) + 420 0 220530 82c DEC 22 53 0 52.94977 900.0 2.11972E-02 IB-DF----------R---- titanium 53 (Ti-53) + 421 0 220540 82c DEC 22 54 0 53.95107 900.0 4.62098E-01 IB-DF----------R---- titanium 54 (Ti-54) + 422 0 220550 82c DEC 22 55 0 54.95530 900.0 1.41459E+00 IB-DF----------R---- titanium 55 (Ti-55) + 423 0 220560 82c DEC 22 56 0 55.95821 900.0 4.22651E+00 IB-DF----------R---- titanium 56 (Ti-56) + 424 0 220570 82c DEC 22 57 0 56.96395 900.0 1.15525E+01 IB-DF-----P----R---- titanium 57 (Ti-57) + 425 0 220580 82c DEC 22 58 0 57.96697 900.0 1.28361E+01 IB--F----------R---- titanium 58 (Ti-58) + 426 0 220590 82c DEC 22 59 0 58.97291 900.0 2.31049E+01 IB--F----------R---- titanium 59 (Ti-59) + 427 0 220600 82c DEC 22 60 0 59.97673 900.0 3.15067E+01 IB--F----------R---- titanium 60 (Ti-60) + 428 0 220610 82c DEC 22 61 0 60.98318 900.0 6.93147E+01 IB--F----------R---- titanium 61 (Ti-61) + 429 0 230490 82c DEC 23 49 0 48.94849 900.0 2.43107E-08 IBAD-----------R---- vanadium 49 (V-49) + 430 0 230500 82c DEC 23 50 0 49.94717 900.0 1.56893E-25 IBA-F----------R---- vanadium 50 (V-50) + 431 0 230510 82c DEC 23 51 0 50.94394 900.0 stable IBADF----------R---- vanadium 51 (V-51) + 432 0 230520 82c DEC 23 52 0 51.94473 900.0 3.08477E-03 IBADF----------R---- vanadium 52 (V-52) + 433 0 230530 82c DEC 23 53 0 52.94432 900.0 7.13114E-03 IBADF----------R---- vanadium 53 (V-53) + 434 0 230540 82c DEC 23 54 0 53.94643 900.0 1.39186E-02 IBADF----------R---- vanadium 54 (V-54) + 435 0 230550 82c DEC 23 55 0 54.94723 900.0 1.05986E-01 IB-DF----------R---- vanadium 55 (V-55) + 436 0 230560 82c DEC 23 56 0 55.95054 900.0 3.20901E+00 IB-DF----------R---- vanadium 56 (V-56) + 437 0 230570 82c DEC 23 57 0 56.95255 900.0 1.98042E+00 IB-DF-----P----R---- vanadium 57 (V-57) + 438 0 230580 82c DEC 23 58 0 57.95688 900.0 3.62904E+00 IB-DF-----P----R---- vanadium 58 (V-58) + 439 0 230590 82c DEC 23 59 0 58.96020 900.0 9.24196E+00 IB-DF----------R---- vanadium 59 (V-59) + 440 0 230600 82c DEC 23 60 0 59.96503 900.0 5.68153E+00 IB-DF----------R---- vanadium 60 (V-60) + 441 0 230610 82c DEC 23 61 0 60.96845 900.0 1.47478E+01 IB-DF-----P----R---- vanadium 61 (V-61) + 442 0 230620 82c DEC 23 62 0 61.97379 900.0 2.06910E+01 IB--F----------R---- vanadium 62 (V-62) + 443 0 230630 82c DEC 23 63 0 62.97751 900.0 4.07734E+01 IB--F-----P----R---- vanadium 63 (V-63) + 444 0 230640 82c DEC 23 64 0 63.98345 900.0 6.93147E+01 IB--F----------R---- vanadium 64 (V-64) + 445 0 230650 82c DEC 23 65 0 64.98788 900.0 6.93147E+01 IB--F----------R---- vanadium 65 (V-65) + 446 0 240490 82c DEC 24 49 0 48.95132 900.0 2.75715E-04 IBA------------R---- chromium 49 (Cr-49) + 447 0 240510 82c DEC 24 51 0 50.94474 900.0 2.89580E-07 IBA------------R---- chromium 51 (Cr-51) + 448 0 240550 82c DEC 24 55 0 54.94087 900.0 3.26340E-03 IBADF----------R---- chromium 55 (Cr-55) + 449 0 240560 82c DEC 24 56 0 55.94066 900.0 1.94486E-03 IBADF----------R---- chromium 56 (Cr-56) + 450 0 240570 82c DEC 24 57 0 56.94358 900.0 3.28506E-02 IB-DF----------R---- chromium 57 (Cr-57) + 451 0 240580 82c DEC 24 58 0 57.94437 900.0 9.90210E-02 IB-DF----------R---- chromium 58 (Cr-58) + 452 0 240590 82c DEC 24 59 0 58.94860 900.0 1.50684E+00 IB-DF----------R---- chromium 59 (Cr-59) + 453 0 240600 82c DEC 24 60 0 59.95010 900.0 1.23776E+00 IB-DF----------R---- chromium 60 (Cr-60) + 454 0 240610 82c DEC 24 61 0 60.95473 900.0 2.65574E+00 IB-DF----------R---- chromium 61 (Cr-61) + 455 0 240620 82c DEC 24 62 0 61.95664 900.0 3.48315E+00 IB-DF----------R---- chromium 62 (Cr-62) + 456 0 240630 82c DEC 24 63 0 62.96188 900.0 5.37323E+00 IB-DF----------R---- chromium 63 (Cr-63) + 457 0 240640 82c DEC 24 64 0 63.96439 900.0 1.61197E+01 IB-DF----------R---- chromium 64 (Cr-64) + 458 0 240650 82c DEC 24 65 0 64.97013 900.0 2.56721E+01 IB-DF----------R---- chromium 65 (Cr-65) + 459 0 240660 82c DEC 24 66 0 65.97335 900.0 6.93147E+01 IB--F----------R---- chromium 66 (Cr-66) + 460 0 240670 82c DEC 24 67 0 66.97959 900.0 6.93147E+01 IB--F----------R---- chromium 67 (Cr-67) + 461 0 250520 82c DEC 25 52 0 51.94554 900.0 1.43388E-06 IBA------------R---- manganese 52 (Mn-52) + 462 0 250530 82c DEC 25 53 0 52.94129 900.0 5.96861E-15 IBAD-----------R---- manganese 53 (Mn-53) + 463 0 250540 82c DEC 25 54 0 53.94038 900.0 2.56976E-08 IBA-F----------R---- manganese 54 (Mn-54) + 464 0 250560 82c DEC 25 56 0 55.93895 900.0 7.46635E-05 IBADF----------R---- manganese 56 (Mn-56) + 465 0 250570 82c DEC 25 57 0 56.93833 900.0 8.11648E-03 IBADF----------R---- manganese 57 (Mn-57) + 466 0 250580 82c DEC 25 58 0 57.94004 900.0 1.06311E-02 IBADF----------R---- manganese 58 (Mn-58) + 467 0 250581 82c DEC 25 58 1 57.94004 900.0 2.56721E-01 IB--F----------R---- manganese 58m (Mn-58m) + 468 0 250590 82c DEC 25 59 0 58.94043 900.0 1.51012E-01 IB-DF----------R---- manganese 59 (Mn-59) + 469 0 250600 82c DEC 25 60 0 59.94294 900.0 1.35911E-02 IB-DF----------R---- manganese 60 (Mn-60) + 470 0 250601 82c DEC 25 60 1 59.94294 900.0 3.91609E-01 IB--F----------R---- manganese 60m (Mn-60m) + 471 0 250610 82c DEC 25 61 0 60.94465 900.0 1.03455E+00 IB-DF----------R---- manganese 61 (Mn-61) + 472 0 250620 82c DEC 25 62 0 61.94847 900.0 7.87667E-01 IB-DF----------R---- manganese 62 (Mn-62) + 473 0 250621 82c DEC 25 62 1 61.94847 900.0 7.53421E+00 IB-DF----------R---- manganese 62m (Mn-62m) + 474 0 250630 82c DEC 25 63 0 62.95028 900.0 2.52054E+00 IB-DF----------R---- manganese 63 (Mn-63) + 475 0 250640 82c DEC 25 64 0 63.95420 900.0 7.80571E+00 IB-DF----------R---- manganese 64 (Mn-64) + 476 0 250650 82c DEC 25 65 0 64.95631 900.0 7.53421E+00 IB-DF----------R---- manganese 65 (Mn-65) + 477 0 250660 82c DEC 25 66 0 65.96104 900.0 1.07632E+01 IB-DF----------R---- manganese 66 (Mn-66) + 478 0 250670 82c DEC 25 67 0 66.96416 900.0 1.54033E+01 IB-DF----------R---- manganese 67 (Mn-67) + 479 0 250680 82c DEC 25 68 0 67.96929 900.0 2.47553E+01 IB--F----------R---- manganese 68 (Mn-68) + 480 0 250690 82c DEC 25 69 0 68.97281 900.0 4.95105E+01 IB--F-----P----R---- manganese 69 (Mn-69) + 481 0 260530 82c DEC 26 53 0 52.94533 900.0 1.35752E-03 IBA------------R---- iron 53 (Fe-53) + 482 0 260550 82c DEC 26 55 0 54.93825 900.0 7.99599E-09 IBA------------R---- iron 55 (Fe-55) + 483 0 260590 82c DEC 26 59 0 58.93488 900.0 1.80306E-07 IBADF----------R---- iron 59 (Fe-59) + 484 0 260600 82c DEC 26 60 0 59.93407 900.0 1.46430E-14 IBADF----------R---- iron 60 (Fe-60) + 485 0 260610 82c DEC 26 61 0 60.93678 900.0 1.93185E-03 IBADF----------R---- iron 61 (Fe-61) + 486 0 260620 82c DEC 26 62 0 61.93677 900.0 1.01933E-02 IB-DF----------R---- iron 62 (Fe-62) + 487 0 260630 82c DEC 26 63 0 62.94009 900.0 1.13631E-01 IB-DF----------R---- iron 63 (Fe-63) + 488 0 260640 82c DEC 26 64 0 63.94119 900.0 3.46574E-01 IB-DF----------R---- iron 64 (Fe-64) + 489 0 260650 82c DEC 26 65 0 64.94542 900.0 5.33190E-01 IB-DF----------R---- iron 65 (Fe-65) + 490 0 260660 82c DEC 26 66 0 65.94682 900.0 1.57533E+00 IB-DF----------R---- iron 66 (Fe-66) + 491 0 260670 82c DEC 26 67 0 66.95094 900.0 1.75926E+00 IB-DF----------R---- iron 67 (Fe-67) + 492 0 260680 82c DEC 26 68 0 67.95366 900.0 3.70667E+00 IB-DF----------R---- iron 68 (Fe-68) + 493 0 260690 82c DEC 26 69 0 68.95879 900.0 6.35915E+00 IB-DF-----P----R---- iron 69 (Fe-69) + 494 0 260700 82c DEC 26 70 0 69.96151 900.0 7.37391E+00 IB--F----------R---- iron 70 (Fe-70) + 495 0 260710 82c DEC 26 71 0 70.96674 900.0 2.31049E+01 IB--F----------R---- iron 71 (Fe-71) + 496 0 260720 82c DEC 26 72 0 71.96966 900.0 6.93147E+01 IB--F----------R---- iron 72 (Fe-72) + 497 0 270560 82c DEC 27 56 0 55.93985 900.0 1.03870E-07 IBA------------R---- cobalt 56 (Co-56) + 498 0 270570 82c DEC 27 57 0 56.93631 900.0 2.95163E-08 IBAD-----------R---- cobalt 57 (Co-57) + 499 0 270580 82c DEC 27 58 0 57.93580 900.0 1.13233E-07 IBA------------R---- cobalt 58 (Co-58) + 500 0 270600 82c DEC 27 60 0 59.93386 900.0 4.16705E-09 IBADF----------R---- cobalt 60 (Co-60) + 501 0 270601 82c DEC 27 60 1 59.93386 900.0 1.10370E-03 IBADF----------R---- cobalt 60m (Co-60m) + 502 0 270610 82c DEC 27 61 0 60.93244 900.0 1.16691E-04 IBADF----------R---- cobalt 61 (Co-61) + 503 0 270620 82c DEC 27 62 0 61.93405 900.0 7.50159E-03 IBADF----------R---- cobalt 62 (Co-62) + 504 0 270621 82c DEC 27 62 1 61.93405 900.0 8.30514E-04 IB--F----------R---- cobalt 62m (Co-62m) + 505 0 270630 82c DEC 27 63 0 62.93363 900.0 2.52973E-02 IBADF----------R---- cobalt 63 (Co-63) + 506 0 270640 82c DEC 27 64 0 63.93584 900.0 2.31049E+00 IBADF----------R---- cobalt 64 (Co-64) + 507 0 270650 82c DEC 27 65 0 64.93644 900.0 5.77623E-01 IB-DF----------R---- cobalt 65 (Co-65) + 508 0 270660 82c DEC 27 66 0 65.93976 900.0 3.46574E+00 IB-DF----------R---- cobalt 66 (Co-66) + 509 0 270670 82c DEC 27 67 0 66.94086 900.0 1.63093E+00 IB-DF----------R---- cobalt 67 (Co-67) + 510 0 270680 82c DEC 27 68 0 67.94488 900.0 3.46574E+00 IB-DF----------R---- cobalt 68 (Co-68) + 511 0 270681 82c DEC 27 68 1 67.94488 900.0 4.33217E-01 IB-DF----------R---- cobalt 68m (Co-68m) + 512 0 270690 82c DEC 27 69 0 68.94629 900.0 3.05351E+00 IB-DF-----P----R---- cobalt 69 (Co-69) + 513 0 270700 82c DEC 27 70 0 69.95102 900.0 5.82477E+00 IB--F----------R---- cobalt 70 (Co-70) + 514 0 270701 82c DEC 27 70 1 69.95102 900.0 1.38629E+00 IB-DF----------R---- cobalt 70m (Co-70m) + 515 0 270710 82c DEC 27 71 0 70.95292 900.0 7.14585E+00 IB-DF----------R---- cobalt 71 (Co-71) + 516 0 270720 82c DEC 27 72 0 71.95786 900.0 7.70164E+00 IB-DF----------R---- cobalt 72 (Co-72) + 517 0 270730 82c DEC 27 73 0 72.96027 900.0 8.66434E+00 IB--F----------R---- cobalt 73 (Co-73) + 518 0 270740 82c DEC 27 74 0 73.96540 900.0 1.38629E+01 IB--F----------R---- cobalt 74 (Co-74) + 519 0 270750 82c DEC 27 75 0 74.96832 900.0 1.73287E+01 IB--F----------R---- cobalt 75 (Co-75) + 520 0 280570 82c DEC 28 57 0 56.93974 900.0 5.36267E-06 IBA------------R---- nickel 57 (Ni-57) + 521 0 280630 82c DEC 28 63 0 62.92970 900.0 2.22543E-10 IBADF----------R---- nickel 63 (Ni-63) + 522 0 280650 82c DEC 28 65 0 64.93008 900.0 7.64051E-05 IBADF----------R---- nickel 65 (Ni-65) + 523 0 280660 82c DEC 28 66 0 65.92917 900.0 3.53935E-06 IBADF----------R---- nickel 66 (Ni-66) + 524 0 280670 82c DEC 28 67 0 66.93158 900.0 3.30070E-02 IB-DF----------R---- nickel 67 (Ni-67) + 525 0 280680 82c DEC 28 68 0 67.93187 900.0 2.39016E-02 IB-DF----------R---- nickel 68 (Ni-68) + 526 0 280690 82c DEC 28 69 0 68.93559 900.0 6.08024E-02 IB-DF----------R---- nickel 69 (Ni-69) + 527 0 280691 82c DEC 28 69 1 68.93559 900.0 1.98042E-01 IB--F----------R---- nickel 69m (Ni-69m) + 528 0 280700 82c DEC 28 70 0 69.93649 900.0 1.15525E-01 IB-DF----------R---- nickel 70 (Ni-70) + 529 0 280710 82c DEC 28 71 0 70.94072 900.0 2.70761E-01 IB-DF----------R---- nickel 71 (Ni-71) + 530 0 280720 82c DEC 28 72 0 71.94212 900.0 4.41495E-01 IB-DF----------R---- nickel 72 (Ni-72) + 531 0 280730 82c DEC 28 73 0 72.94645 900.0 8.25175E-01 IB-DF----------R---- nickel 73 (Ni-73) + 532 0 280740 82c DEC 28 74 0 73.94805 900.0 1.01933E+00 IB-DF----------R---- nickel 74 (Ni-74) + 533 0 280750 82c DEC 28 75 0 74.95289 900.0 1.15525E+00 IB-DF-----P----R---- nickel 75 (Ni-75) + 534 0 280760 82c DEC 28 76 0 75.95530 900.0 1.47478E+00 IB--F----------R---- nickel 76 (Ni-76) + 535 0 280770 82c DEC 28 77 0 76.96053 900.0 2.31049E+00 IB--F----------R---- nickel 77 (Ni-77) + 536 0 280780 82c DEC 28 78 0 77.96314 900.0 3.46574E+00 IB--F----------R---- nickel 78 (Ni-78) + 537 0 290630 82c DEC 29 63 0 62.92960 900.0 stable IB-D-----------R---- copper 63 (Cu-63) + 538 0 290640 82c DEC 29 64 0 63.92979 900.0 1.51602E-05 IBA-F----------R---- copper 64 (Cu-64) + 539 0 290660 82c DEC 29 66 0 65.92886 900.0 2.26519E-03 IBADF----------R---- copper 66 (Cu-66) + 540 0 290670 82c DEC 29 67 0 66.92774 900.0 3.11052E-06 IB-DF----------R---- copper 67 (Cu-67) + 541 0 290680 82c DEC 29 68 0 67.92965 900.0 2.22877E-02 IBADF----------R---- copper 68 (Cu-68) + 542 0 290681 82c DEC 29 68 1 67.92965 900.0 3.08065E-03 IB--F----------R---- copper 68m (Cu-68m) + 543 0 290690 82c DEC 29 69 0 68.92944 900.0 4.05349E-03 IBADF----------R---- copper 69 (Cu-69) + 544 0 290700 82c DEC 29 70 0 69.93236 900.0 1.55763E-02 IB-DF----------R---- copper 70 (Cu-70) + 545 0 290701 82c DEC 29 70 1 69.93236 900.0 2.10045E-02 IB-DF----------R---- copper 70m (Cu-70m) + 546 1 290702 82c DEC 29 70 2 69.93236 900.0 1.05022E-01 -B-DF----------R---- copper 70m (Cu-70m) + 547 0 290710 82c DEC 29 71 0 70.93265 900.0 3.57292E-02 IB-DF----------R---- copper 71 (Cu-71) + 548 0 290720 82c DEC 29 72 0 71.93587 900.0 1.04547E-01 IB-DF----------R---- copper 72 (Cu-72) + 549 0 290730 82c DEC 29 73 0 72.93666 900.0 1.65035E-01 IB-DF----------R---- copper 73 (Cu-73) + 550 0 290740 82c DEC 29 74 0 73.93988 900.0 4.34848E-01 IB-DF----------R---- copper 74 (Cu-74) + 551 0 290750 82c DEC 29 75 0 74.94189 900.0 5.66297E-01 IB-DF-----P----R---- copper 75 (Cu-75) + 552 0 290760 82c DEC 29 76 0 75.94531 900.0 1.08135E+00 IB-DF-----P----R---- copper 76 (Cu-76) + 553 0 290761 82c DEC 29 76 1 75.94531 900.0 5.45785E-01 IB-DF----------R---- copper 76m (Cu-76m) + 554 0 290770 82c DEC 29 77 0 76.94782 900.0 1.47793E+00 IB-DF----------R---- copper 77 (Cu-77) + 555 0 290780 82c DEC 29 78 0 77.95195 900.0 2.02675E+00 IB-DF----------R---- copper 78 (Cu-78) + 556 0 290790 82c DEC 29 79 0 78.95456 900.0 3.68695E+00 IB--F-----P----R---- copper 79 (Cu-79) + 557 0 290800 82c DEC 29 80 0 79.96091 900.0 6.93147E+00 IB--F----------R---- copper 80 (Cu-80) + 558 0 300640 82c DEC 30 64 0 63.92919 900.0 9.54978E-27 IB-D-----------R---- zinc 64 (Zn-64) + 559 0 300650 82c DEC 30 65 0 64.92928 900.0 3.28778E-08 IBA------------R---- zinc 65 (Zn-65) + 560 0 300660 82c DEC 30 66 0 65.92604 900.0 stable IBADF----------R---- zinc 66 (Zn-66) + 561 0 300670 82c DEC 30 67 0 66.92714 900.0 stable IBADF----------R---- zinc 67 (Zn-67) + 562 0 300680 82c DEC 30 68 0 67.92481 900.0 stable IBADF----------R---- zinc 68 (Zn-68) + 563 0 300690 82c DEC 30 69 0 68.92652 900.0 2.04831E-04 IBADF----------R---- zinc 69 (Zn-69) + 564 0 300691 82c DEC 30 69 1 68.92652 900.0 1.39725E-05 IB--F----------R---- zinc 69m (Zn-69m) + 565 0 300700 82c DEC 30 70 0 69.92530 900.0 stable IBADF----------R---- zinc 70 (Zn-70) + 566 0 300710 82c DEC 30 71 0 70.92771 900.0 4.71529E-03 IBADF----------R---- zinc 71 (Zn-71) + 567 0 300711 82c DEC 30 71 1 70.92771 900.0 4.86214E-05 IB--F----------R---- zinc 71m (Zn-71m) + 568 0 300720 82c DEC 30 72 0 71.92689 900.0 4.14066E-06 IBADF----------R---- zinc 72 (Zn-72) + 569 0 300730 82c DEC 30 73 0 72.92981 900.0 2.94956E-02 IBADF----------R---- zinc 73 (Zn-73) + 570 0 300731 82c DEC 30 73 1 72.92981 900.0 5.33190E-02 IB-DF----------R---- zinc 73m (Zn-73m) + 571 1 300732 82c DEC 30 73 2 72.92981 900.0 1.19508E-01 -B--F----------R---- zinc 73m (Zn-73m) + 572 0 300740 82c DEC 30 74 0 73.92949 900.0 7.25049E-03 IB-DF----------R---- zinc 74 (Zn-74) + 573 0 300750 82c DEC 30 75 0 74.93291 900.0 6.79556E-02 IB-DF----------R---- zinc 75 (Zn-75) + 574 0 300760 82c DEC 30 76 0 75.93331 900.0 1.21605E-01 IB-DF----------R---- zinc 76 (Zn-76) + 575 0 300770 82c DEC 30 77 0 76.93693 900.0 3.33244E-01 IB-DF----------R---- zinc 77 (Zn-77) + 576 0 300771 82c DEC 30 77 1 76.93693 900.0 6.60140E-01 IB--F----------R---- zinc 77m (Zn-77m) + 577 0 300780 82c DEC 30 78 0 77.93843 900.0 4.71529E-01 IB-DF----------R---- zinc 78 (Zn-78) + 578 0 300790 82c DEC 30 79 0 78.94266 900.0 6.96630E-01 IB-DF-----P----R---- zinc 79 (Zn-79) + 579 0 300800 82c DEC 30 80 0 79.94436 900.0 1.28361E+00 IB-DF----------R---- zinc 80 (Zn-80) + 580 0 300810 82c DEC 30 81 0 80.95051 900.0 2.39016E+00 IB--F-----P----R---- zinc 81 (Zn-81) + 581 0 300820 82c DEC 30 82 0 81.95443 900.0 6.93147E+00 IB--F----------R---- zinc 82 (Zn-82) + 582 0 300830 82c DEC 30 83 0 82.96108 900.0 8.66434E+00 IB--F----------R---- zinc 83 (Zn-83) + 583 0 310680 82c DEC 31 68 0 67.92794 900.0 1.70315E-04 IBA-F----------R---- gallium 68 (Ga-68) + 584 0 310690 82c DEC 31 69 0 68.92561 900.0 stable IBADF----------R---- gallium 69 (Ga-69) + 585 0 310700 82c DEC 31 70 0 69.92600 900.0 5.46474E-04 IBA-F----------R---- gallium 70 (Ga-70) + 586 0 310710 82c DEC 31 71 0 70.92468 900.0 stable IBADF----------R---- gallium 71 (Ga-71) + 587 0 310720 82c DEC 31 72 0 71.92639 900.0 1.36554E-05 IBADF----------R---- gallium 72 (Ga-72) + 588 0 310721 82c DEC 31 72 1 71.92639 900.0 1.74684E+01 IB-DF----------R---- gallium 72m (Ga-72m) + 589 0 310730 82c DEC 31 73 0 72.92517 900.0 3.96175E-05 IBADF----------R---- gallium 73 (Ga-73) + 590 0 310740 82c DEC 31 74 0 73.92697 900.0 1.42272E-03 IBADF----------R---- gallium 74 (Ga-74) + 591 0 310741 82c DEC 31 74 1 73.92697 900.0 7.29629E-02 IB-DF----------R---- gallium 74m (Ga-74m) + 592 0 310750 82c DEC 31 75 0 74.92646 900.0 5.50117E-03 IBADF----------R---- gallium 75 (Ga-75) + 593 0 310760 82c DEC 31 76 0 75.92887 900.0 2.12622E-02 IBADF----------R---- gallium 76 (Ga-76) + 594 0 310770 82c DEC 31 77 0 76.92926 900.0 5.33190E-02 IB-DF----------R---- gallium 77 (Ga-77) + 595 0 310780 82c DEC 31 78 0 77.93157 900.0 1.36178E-01 IB-DF----------R---- gallium 78 (Ga-78) + 596 0 310790 82c DEC 31 79 0 78.93288 900.0 2.43466E-01 IB-DF-----P----R---- gallium 79 (Ga-79) + 597 0 310800 82c DEC 31 80 0 79.93650 900.0 4.13572E-01 IB-DF----------R---- gallium 80 (Ga-80) + 598 0 310810 82c DEC 31 81 0 80.93780 900.0 5.69554E-01 IB-DF-----P----R---- gallium 81 (Ga-81) + 599 0 310820 82c DEC 31 82 0 81.94303 900.0 1.15717E+00 IB-DF-----P----R---- gallium 82 (Ga-82) + 600 0 310830 82c DEC 31 83 0 82.94696 900.0 2.25048E+00 IB-DF-----P----R---- gallium 83 (Ga-83) + 601 0 310840 82c DEC 31 84 0 83.95270 900.0 8.15467E+00 IB--F-----P----R---- gallium 84 (Ga-84) + 602 0 310850 82c DEC 31 85 0 84.95703 900.0 1.38629E+01 IB--F----------R---- gallium 85 (Ga-85) + 603 0 310860 82c DEC 31 86 0 85.96317 900.0 2.31049E+01 IB--F----------R---- gallium 86 (Ga-86) + 604 0 320690 82c DEC 32 69 0 68.92793 900.0 4.93062E-06 IBA------------R---- germanium 69 (Ge-69) + 605 0 320710 82c DEC 32 71 0 70.92498 900.0 7.01884E-07 IBADF----------R---- germanium 71 (Ge-71) + 606 0 320711 82c DEC 32 71 1 70.92498 900.0 3.39778E+01 IB--F----------R---- germanium 71m (Ge-71m) + 607 0 320731 82c DEC 32 73 1 72.92345 900.0 1.38629E+00 IBADF----------R---- germanium 73m (Ge-73m) + 608 0 320750 82c DEC 32 75 0 74.92283 900.0 1.39556E-04 IBADF----------R---- germanium 75 (Ge-75) + 609 0 320751 82c DEC 32 75 1 74.92283 900.0 1.44406E-02 IBADF----------R---- germanium 75m (Ge-75m) + 610 0 320770 82c DEC 32 77 0 76.92351 900.0 1.71743E-05 IBADF----------R---- germanium 77 (Ge-77) + 611 0 320771 82c DEC 32 77 1 76.92351 900.0 1.29078E-02 IBADF----------R---- germanium 77m (Ge-77m) + 612 0 320780 82c DEC 32 78 0 77.92290 900.0 1.31278E-04 IBADF----------R---- germanium 78 (Ge-78) + 613 0 320790 82c DEC 32 79 0 78.92541 900.0 3.65199E-02 IBADF----------R---- germanium 79 (Ge-79) + 614 0 320791 82c DEC 32 79 1 78.92541 900.0 1.77730E-02 IB-DF----------R---- germanium 79m (Ge-79m) + 615 0 320800 82c DEC 32 80 0 79.92540 900.0 2.34965E-02 IBADF----------R---- germanium 80 (Ge-80) + 616 0 320810 82c DEC 32 81 0 80.92882 900.0 8.66434E-02 IBADF----------R---- germanium 81 (Ge-81) + 617 0 320811 82c DEC 32 81 1 80.92882 900.0 9.12036E-02 IB-DF----------R---- germanium 81m (Ge-81m) + 618 0 320820 82c DEC 32 82 0 81.92952 900.0 1.52340E-01 IB-DF----------R---- germanium 82 (Ge-82) + 619 0 320830 82c DEC 32 83 0 82.93465 900.0 3.74674E-01 IB-DF----------R---- germanium 83 (Ge-83) + 620 0 320840 82c DEC 32 84 0 83.93747 900.0 7.26569E-01 IB-DF-----P----R---- germanium 84 (Ge-84) + 621 0 320850 82c DEC 32 85 0 84.94301 900.0 1.28361E+00 IB-DF-----P----R---- germanium 85 (Ge-85) + 622 0 320860 82c DEC 32 86 0 85.94653 900.0 2.31049E+00 IB-DF----------R---- germanium 86 (Ge-86) + 623 0 320870 82c DEC 32 87 0 86.95247 900.0 4.62098E+00 IB--F----------R---- germanium 87 (Ge-87) + 624 0 320880 82c DEC 32 88 0 87.95690 900.0 8.66434E+00 IB--F----------R---- germanium 88 (Ge-88) + 625 0 320890 82c DEC 32 89 0 88.96385 900.0 1.38629E+01 IB--F----------R---- germanium 89 (Ge-89) + 626 0 330730 82c DEC 33 73 0 72.92385 900.0 9.99071E-08 IB--F----------R---- arsenic 73 (As-73) + 627 0 330740 82c DEC 33 74 0 73.92395 900.0 4.51212E-07 IBA-F----------R---- arsenic 74 (As-74) + 628 0 330751 82c DEC 33 75 1 74.92162 900.0 3.93387E+01 IB-DF----------R---- arsenic 75m (As-75m) + 629 0 330760 82c DEC 33 76 0 75.92241 900.0 7.34328E-06 IBA-F----------R---- arsenic 76 (As-76) + 630 0 330770 82c DEC 33 77 0 76.92069 900.0 4.96367E-06 IBADF----------R---- arsenic 77 (As-77) + 631 0 330780 82c DEC 33 78 0 77.92179 900.0 1.27370E-04 IBADF----------R---- arsenic 78 (As-78) + 632 0 330790 82c DEC 33 79 0 78.92097 900.0 1.28218E-03 IBADF----------R---- arsenic 79 (As-79) + 633 0 330800 82c DEC 33 80 0 79.92258 900.0 4.56018E-02 IBADF----------R---- arsenic 80 (As-80) + 634 0 330810 82c DEC 33 81 0 80.92216 900.0 2.08152E-02 IBADF----------R---- arsenic 81 (As-81) + 635 0 330820 82c DEC 33 82 0 81.92447 900.0 3.62904E-02 IBADF----------R---- arsenic 82 (As-82) + 636 0 330821 82c DEC 33 82 1 81.92447 900.0 5.09667E-02 IB--F----------R---- arsenic 82m (As-82m) + 637 0 330830 82c DEC 33 83 0 82.92497 900.0 5.17274E-02 IB-DF----------R---- arsenic 83 (As-83) + 638 0 330840 82c DEC 33 84 0 83.92910 900.0 1.72425E-01 IB-DF-----P----R---- arsenic 84 (As-84) + 639 0 330841 82c DEC 33 84 1 83.92910 900.0 1.06638E+00 IB-DF----------R---- arsenic 84m (As-84m) + 640 0 330850 82c DEC 33 85 0 84.93181 900.0 3.39778E-01 IB-DF-----P----R---- arsenic 85 (As-85) + 641 0 330860 82c DEC 33 86 0 85.93654 900.0 7.33489E-01 IB-DF-----P----R---- arsenic 86 (As-86) + 642 0 330870 82c DEC 33 87 0 86.93986 900.0 1.13631E+00 IB-DF-----P----R---- arsenic 87 (As-87) + 643 0 330880 82c DEC 33 88 0 87.94489 900.0 2.31049E+00 IB-DF----------R---- arsenic 88 (As-88) + 644 0 330890 82c DEC 33 89 0 88.94942 900.0 3.46574E+00 IB-DF----------R---- arsenic 89 (As-89) + 645 0 330900 82c DEC 33 90 0 89.95547 900.0 8.66434E+00 IB--F----------R---- arsenic 90 (As-90) + 646 0 330910 82c DEC 33 91 0 90.96040 900.0 1.38629E+01 IB--F----------R---- arsenic 91 (As-91) + 647 0 340740 82c DEC 34 74 0 73.92243 900.0 stable IB-D-----------R---- selenium 74 (Se-74) + 648 0 340750 82c DEC 34 75 0 74.92252 900.0 6.69766E-08 IB--F----------R---- selenium 75 (Se-75) + 649 0 340771 82c DEC 34 77 1 76.91988 900.0 3.94956E-02 IBA-F----------R---- selenium 77m (Se-77m) + 650 0 340791 82c DEC 34 79 1 78.91855 900.0 2.96217E-03 IBA-F----------R---- selenium 79m (Se-79m) + 651 0 340810 82c DEC 34 81 0 80.91803 900.0 6.28192E-04 IBADF----------R---- selenium 81 (Se-81) + 652 0 340811 82c DEC 34 81 1 80.91803 900.0 2.01684E-04 IBADF----------R---- selenium 81m (Se-81m) + 653 0 340830 82c DEC 34 83 0 82.91912 900.0 5.18047E-04 IBADF----------R---- selenium 83 (Se-83) + 654 0 340831 82c DEC 34 83 1 82.91912 900.0 9.88798E-03 IBADF----------R---- selenium 83m (Se-83m) + 655 0 340840 82c DEC 34 84 0 83.91850 900.0 3.54370E-03 IBADF----------R---- selenium 84 (Se-84) + 656 0 340850 82c DEC 34 85 0 84.92223 900.0 2.18658E-02 IBADF----------R---- selenium 85 (Se-85) + 657 0 340860 82c DEC 34 86 0 85.92423 900.0 4.53037E-02 IB-DF----------R---- selenium 86 (Se-86) + 658 0 340870 82c DEC 34 87 0 86.92856 900.0 1.26027E-01 IB-DF----------R---- selenium 87 (Se-87) + 659 0 340880 82c DEC 34 88 0 87.93138 900.0 4.53037E-01 IB-DF-----P----R---- selenium 88 (Se-88) + 660 0 340890 82c DEC 34 89 0 88.93641 900.0 1.69060E+00 IB-DF-----P----R---- selenium 89 (Se-89) + 661 0 340900 82c DEC 34 90 0 89.93993 900.0 2.31049E+00 IB-DF----------R---- selenium 90 (Se-90) + 662 0 340910 82c DEC 34 91 0 90.94597 900.0 2.56721E+00 IB-DF-----P----R---- selenium 91 (Se-91) + 663 0 340920 82c DEC 34 92 0 91.94990 900.0 6.93147E+00 IB--F----------R---- selenium 92 (Se-92) + 664 0 340930 82c DEC 34 93 0 92.95624 900.0 1.38629E+01 IB--F----------R---- selenium 93 (Se-93) + 665 0 340940 82c DEC 34 94 0 93.96047 900.0 3.46574E+01 IB--F----------R---- selenium 94 (Se-94) + 666 0 350780 82c DEC 35 78 0 77.92118 900.0 1.79108E-03 IBA-F----------R---- bromine 78 (Br-78) + 667 0 350791 82c DEC 35 79 1 78.91835 900.0 1.42506E-01 IB--F----------R---- bromine 79m (Br-79m) + 668 0 350800 82c DEC 35 80 0 79.91854 900.0 6.56389E-04 IBADF----------R---- bromine 80 (Br-80) + 669 0 350801 82c DEC 35 80 1 79.91854 900.0 4.36601E-05 IBA-F----------R---- bromine 80m (Br-80m) + 670 0 350820 82c DEC 35 82 0 81.91681 900.0 5.45133E-06 IBADF----------R---- bromine 82 (Br-82) + 671 0 350821 82c DEC 35 82 1 81.91681 900.0 1.89695E-03 IBA-F----------R---- bromine 82m (Br-82m) + 672 0 350830 82c DEC 35 83 0 82.91519 900.0 8.02254E-05 IBADF----------R---- bromine 83 (Br-83) + 673 0 350840 82c DEC 35 84 0 83.91649 900.0 3.63742E-04 IBADF----------R---- bromine 84 (Br-84) + 674 0 350841 82c DEC 35 84 1 83.91649 900.0 1.92541E-03 IB--F----------R---- bromine 84m (Br-84m) + 675 0 350850 82c DEC 35 85 0 84.91557 900.0 3.98360E-03 IBADF----------R---- bromine 85 (Br-85) + 676 0 350860 82c DEC 35 86 0 85.91879 900.0 1.26027E-02 IBADF----------R---- bromine 86 (Br-86) + 677 0 350870 82c DEC 35 87 0 86.92069 900.0 1.24443E-02 IB-DF-----P----R---- bromine 87 (Br-87) + 678 0 350880 82c DEC 35 88 0 87.92411 900.0 4.20089E-02 IB-DF-----P----R---- bromine 88 (Br-88) + 679 0 350890 82c DEC 35 89 0 88.92643 900.0 1.58615E-01 IB-DF-----P----R---- bromine 89 (Br-89) + 680 0 350900 82c DEC 35 90 0 89.93065 900.0 3.64814E-01 IB-DF-----P----R---- bromine 90 (Br-90) + 681 0 350910 82c DEC 35 91 0 90.93397 900.0 1.28838E+00 IB-DF-----P----R---- bromine 91 (Br-91) + 682 0 350920 82c DEC 35 92 0 91.93931 900.0 2.02084E+00 IB-DF-----P----R---- bromine 92 (Br-92) + 683 0 350930 82c DEC 35 93 0 92.94303 900.0 6.79556E+00 IB-DF-----P----R---- bromine 93 (Br-93) + 684 0 350940 82c DEC 35 94 0 93.94867 900.0 9.90210E+00 IB-DF-----P----R---- bromine 94 (Br-94) + 685 0 350950 82c DEC 35 95 0 94.95290 900.0 1.38629E+01 IB--F----------R---- bromine 95 (Br-95) + 686 0 350960 82c DEC 35 96 0 95.95853 900.0 3.46574E+01 IB--F----------R---- bromine 96 (Br-96) + 687 0 360790 82c DEC 36 79 0 78.92007 900.0 5.49489E-06 IBA------------R---- krypton 79 (Kr-79) + 688 0 360810 82c DEC 36 81 0 80.91662 900.0 1.04593E-13 IBADF----------R---- krypton 81 (Kr-81) + 689 0 360811 82c DEC 36 81 1 80.91662 900.0 5.25112E-02 IBA-F----------R---- krypton 81m (Kr-81m) + 690 0 360831 82c DEC 36 83 1 82.91418 900.0 1.05214E-04 IBADF----------R---- krypton 83m (Kr-83m) + 691 0 360851 82c DEC 36 85 1 84.91254 900.0 4.29779E-05 IBADF----------R---- krypton 85m (Kr-85m) + 692 0 360870 82c DEC 36 87 0 86.91333 900.0 1.51408E-04 IBADF----------R---- krypton 87 (Kr-87) + 693 0 360880 82c DEC 36 88 0 87.91443 900.0 6.77961E-05 IBADF----------R---- krypton 88 (Kr-88) + 694 0 360890 82c DEC 36 89 0 88.91765 900.0 3.66745E-03 IBADF----------R---- krypton 89 (Kr-89) + 695 0 360900 82c DEC 36 90 0 89.91956 900.0 2.14464E-02 IB-DF----------R---- krypton 90 (Kr-90) + 696 0 360910 82c DEC 36 91 0 90.92348 900.0 8.08807E-02 IB-DF----------R---- krypton 91 (Kr-91) + 697 0 360920 82c DEC 36 92 0 91.92619 900.0 3.76710E-01 IB-DF----------R---- krypton 92 (Kr-92) + 698 0 360930 82c DEC 36 93 0 92.93123 900.0 5.38995E-01 IB-DF----------R---- krypton 93 (Kr-93) + 699 0 360940 82c DEC 36 94 0 93.93435 900.0 3.30070E+00 IB-DF-----P----R---- krypton 94 (Kr-94) + 700 0 360950 82c DEC 36 95 0 94.93988 900.0 6.08024E+00 IB-DF-----P----R---- krypton 95 (Kr-95) + 701 0 360960 82c DEC 36 96 0 95.94310 900.0 8.66434E+00 IB-DF-----P----R---- krypton 96 (Kr-96) + 702 0 360970 82c DEC 36 97 0 96.94854 900.0 1.10023E+01 IB--F-----P----R---- krypton 97 (Kr-97) + 703 0 360980 82c DEC 36 98 0 97.95196 900.0 1.50684E+01 IB--F-----P----R---- krypton 98 (Kr-98) + 704 0 360990 82c DEC 36 99 0 98.95760 900.0 1.73287E+01 IB--F-----P----R---- krypton 99 (Kr-99) + 705 0 370830 82c DEC 37 83 0 82.91508 900.0 9.30689E-08 IB-DF----------R---- rubidium 83 (Rb-83) + 706 0 370831 82c DEC 37 83 1 82.91508 900.0 8.88650E+01 IB--F----------R---- rubidium 83m (Rb-83m) + 707 0 370840 82c DEC 37 84 0 83.91437 900.0 2.39479E-07 IBADF----------R---- rubidium 84 (Rb-84) + 708 0 370841 82c DEC 37 84 1 83.91437 900.0 5.66297E-04 IB--F----------R---- rubidium 84m (Rb-84m) + 709 0 370861 82c DEC 37 86 1 85.91122 900.0 1.13631E-02 IBA-F----------R---- rubidium 86m (Rb-86m) + 710 0 370880 82c DEC 37 88 0 87.91130 900.0 6.49014E-04 IBADF----------R---- rubidium 88 (Rb-88) + 711 0 370890 82c DEC 37 89 0 88.91230 900.0 7.50159E-04 IBADF----------R---- rubidium 89 (Rb-89) + 712 0 370900 82c DEC 37 90 0 89.91482 900.0 4.41495E-03 IBADF----------R---- rubidium 90 (Rb-90) + 713 0 370901 82c DEC 37 90 1 89.91482 900.0 2.68662E-03 IB-DF----------R---- rubidium 90m (Rb-90m) + 714 0 370910 82c DEC 37 91 0 90.91652 900.0 1.18690E-02 IB-DF----------R---- rubidium 91 (Rb-91) + 715 0 370920 82c DEC 37 92 0 91.91974 900.0 1.54720E-01 IB-DF----------R---- rubidium 92 (Rb-92) + 716 0 370930 82c DEC 37 93 0 92.92205 900.0 1.19508E-01 IB-DF-----P----R---- rubidium 93 (Rb-93) + 717 0 370940 82c DEC 37 94 0 93.92648 900.0 2.56531E-01 IB-DF-----P----R---- rubidium 94 (Rb-94) + 718 0 370950 82c DEC 37 95 0 94.92929 900.0 1.81928E+00 IB-DF-----P----R---- rubidium 95 (Rb-95) + 719 0 370960 82c DEC 37 96 0 95.93433 900.0 3.48315E+00 IB-DF-----P----R---- rubidium 96 (Rb-96) + 720 0 370961 82c DEC 37 96 1 95.93433 900.0 3.46574E+00 IB-DF----------R---- rubidium 96m (Rb-96m) + 721 0 370970 82c DEC 37 97 0 96.93734 900.0 4.07974E+00 IB-DF-----P----R---- rubidium 97 (Rb-97) + 722 0 370980 82c DEC 37 98 0 97.94177 900.0 6.08024E+00 IB-DF-----P----R---- rubidium 98 (Rb-98) + 723 0 370981 82c DEC 37 98 1 97.94177 900.0 7.22028E+00 IB-DF----------R---- rubidium 98m (Rb-98m) + 724 0 370990 82c DEC 37 99 0 98.94539 900.0 1.37803E+01 IB-DF-----P----R---- rubidium 99 (Rb-99) + 725 0 371000 82c DEC 37 100 0 99.94982 900.0 1.35911E+01 IB--F-----P----R---- rubidium 100 (Rb-100) + 726 0 371010 82c DEC 37 101 0 100.95324 900.0 2.16608E+01 IB--F----------R---- rubidium 101 (Rb-101) + 727 0 380840 82c DEC 38 84 0 83.91346 900.0 stable IB-D-----------R---- strontium 84 (Sr-84) + 728 0 380850 82c DEC 38 85 0 84.91295 900.0 1.23709E-07 IB-DF----------R---- strontium 85 (Sr-85) + 729 0 380851 82c DEC 38 85 1 84.91295 900.0 1.70869E-04 IB--F----------R---- strontium 85m (Sr-85m) + 730 0 380871 82c DEC 38 87 1 86.90889 900.0 6.83739E-05 IBA-F----------R---- strontium 87m (Sr-87m) + 731 0 380910 82c DEC 38 91 0 90.91017 900.0 1.99524E-05 IBADF----------R---- strontium 91 (Sr-91) + 732 0 380920 82c DEC 38 92 0 91.91106 900.0 7.10483E-05 IBADF----------R---- strontium 92 (Sr-92) + 733 0 380930 82c DEC 38 93 0 92.91398 900.0 1.55631E-03 IBADF----------R---- strontium 93 (Sr-93) + 734 0 380940 82c DEC 38 94 0 93.91538 900.0 9.20514E-03 IB-DF----------R---- strontium 94 (Sr-94) + 735 0 380950 82c DEC 38 95 0 94.91931 900.0 2.90020E-02 IB-DF----------R---- strontium 95 (Sr-95) + 736 0 380960 82c DEC 38 96 0 95.92172 900.0 6.47801E-01 IB-DF----------R---- strontium 96 (Sr-96) + 737 0 380970 82c DEC 38 97 0 96.92615 900.0 1.61573E+00 IB-DF-----P----R---- strontium 97 (Sr-97) + 738 0 380980 82c DEC 38 98 0 97.92846 900.0 1.06148E+00 IB-DF----------R---- strontium 98 (Sr-98) + 739 0 380990 82c DEC 38 99 0 98.93319 900.0 2.56721E+00 IB-DF----------R---- strontium 99 (Sr-99) + 740 0 381000 82c DEC 38 100 0 99.93540 900.0 3.43142E+00 IB-DF-----P----R---- strontium 100 (Sr-100) + 741 0 381010 82c DEC 38 101 0 100.94013 900.0 5.87413E+00 IB-DF-----P----R---- strontium 101 (Sr-101) + 742 0 381020 82c DEC 38 102 0 101.94274 900.0 1.00456E+01 IB--F-----P----R---- strontium 102 (Sr-102) + 743 0 381030 82c DEC 38 103 0 102.94939 900.0 1.38629E+01 IB--F----------R---- strontium 103 (Sr-103) + 744 0 381040 82c DEC 38 104 0 103.95200 900.0 2.31049E+01 IB--F----------R---- strontium 104 (Sr-104) + 745 0 390880 82c DEC 39 88 0 87.90949 900.0 7.52372E-08 IBADF----------R---- yttrium 88 (Y-88) + 746 0 390881 82c DEC 39 88 1 87.90949 900.0 4.98667E+01 IB--F----------R---- yttrium 88m (Y-88m) + 747 0 390891 82c DEC 39 89 1 88.90585 900.0 4.42538E-02 IB-DF----------R---- yttrium 89m (Y-89m) + 748 0 390901 82c DEC 39 90 1 89.90715 900.0 6.03576E-05 IBA-F----------R---- yttrium 90m (Y-90m) + 749 0 390911 82c DEC 39 91 1 90.90734 900.0 2.32397E-04 IBADF----------R---- yttrium 91m (Y-91m) + 750 0 390920 82c DEC 39 92 0 91.90895 900.0 5.43901E-05 IBADF----------R---- yttrium 92 (Y-92) + 751 0 390930 82c DEC 39 93 0 92.90954 900.0 1.89136E-05 IBADF----------R---- yttrium 93 (Y-93) + 752 0 390931 82c DEC 39 93 1 92.90954 900.0 8.45301E-01 IB-DF----------R---- yttrium 93m (Y-93m) + 753 0 390940 82c DEC 39 94 0 93.91155 900.0 6.17778E-04 IBADF----------R---- yttrium 94 (Y-94) + 754 0 390950 82c DEC 39 95 0 94.91285 900.0 1.12160E-03 IBADF----------R---- yttrium 95 (Y-95) + 755 0 390960 82c DEC 39 96 0 95.91587 900.0 1.29803E-01 IBADF----------R---- yttrium 96 (Y-96) + 756 0 390961 82c DEC 39 96 1 95.91587 900.0 7.20527E-02 IB-DF----------R---- yttrium 96m (Y-96m) + 757 0 390970 82c DEC 39 97 0 96.91818 900.0 1.84839E-01 IB-DF-----P----R---- yttrium 97 (Y-97) + 758 0 390971 82c DEC 39 97 1 96.91818 900.0 5.92433E-01 IB-DF-----P----R---- yttrium 97m (Y-97m) + 759 1 390972 82c DEC 39 97 2 96.91818 900.0 4.88132E+00 -B--F----------R---- yttrium 97m (Y-97m) + 760 0 390980 82c DEC 39 98 0 97.92220 900.0 1.17483E+00 IB-DF-----P----R---- yttrium 98 (Y-98) + 761 0 390981 82c DEC 39 98 1 97.92220 900.0 3.46574E-01 IB--F-----P----R---- yttrium 98m (Y-98m) + 762 0 390990 82c DEC 39 99 0 98.92461 900.0 4.69294E-01 IB-DF-----P----R---- yttrium 99 (Y-99) + 763 0 391000 82c DEC 39 100 0 99.92773 900.0 9.43057E-01 IB-DF-----P----R---- yttrium 100 (Y-100) + 764 0 391001 82c DEC 39 100 1 99.92773 900.0 7.37391E-01 IB-DF----------R---- yttrium 100m (Y-100m) + 765 0 391010 82c DEC 39 101 0 100.93004 900.0 1.54033E+00 IB-DF----------R---- yttrium 101 (Y-101) + 766 0 391020 82c DEC 39 102 0 101.93366 900.0 2.31049E+00 IB-DF-----P----R---- yttrium 102 (Y-102) + 767 0 391021 82c DEC 39 102 1 101.93366 900.0 1.92541E+00 IB-DF-----P----R---- yttrium 102m (Y-102m) + 768 0 391030 82c DEC 39 103 0 102.93628 900.0 3.09441E+00 IB-DF-----P----R---- yttrium 103 (Y-103) + 769 0 391040 82c DEC 39 104 0 103.94091 900.0 5.33190E+00 IB-DF-----P----R---- yttrium 104 (Y-104) + 770 0 391050 82c DEC 39 105 0 104.94352 900.0 4.62098E+00 IB--F-----P----R---- yttrium 105 (Y-105) + 771 0 391060 82c DEC 39 106 0 105.95017 900.0 1.38629E+01 IB--F----------R---- yttrium 106 (Y-106) + 772 0 391070 82c DEC 39 107 0 106.95379 900.0 2.31049E+01 IB--F----------R---- yttrium 107 (Y-107) + 773 0 400880 82c DEC 40 88 0 87.91020 900.0 9.61935E-08 IBA------------R---- zirconium 88 (Zr-88) + 774 0 400890 82c DEC 40 89 0 88.90887 900.0 2.45525E-06 IBA------------R---- zirconium 89 (Zr-89) + 775 0 400901 82c DEC 40 90 1 89.90473 900.0 8.57643E-01 IB-DF----------R---- zirconium 90m (Zr-90m) + 776 0 400970 82c DEC 40 97 0 96.91092 900.0 1.14991E-05 IBADF----------R---- zirconium 97 (Zr-97) + 777 0 400980 82c DEC 40 98 0 97.91272 900.0 2.25781E-02 IB-DF----------R---- zirconium 98 (Zr-98) + 778 0 400990 82c DEC 40 99 0 98.91655 900.0 3.15067E-01 IB-DF----------R---- zirconium 99 (Zr-99) + 779 0 401000 82c DEC 40 100 0 99.91775 900.0 9.76264E-02 IB-DF----------R---- zirconium 100 (Zr-100) + 780 0 401010 82c DEC 40 101 0 100.92096 900.0 3.01368E-01 IB-DF----------R---- zirconium 101 (Zr-101) + 781 0 401020 82c DEC 40 102 0 101.92257 900.0 2.39016E-01 IB-DF----------R---- zirconium 102 (Zr-102) + 782 0 401030 82c DEC 40 103 0 102.92619 900.0 5.33190E-01 IB-DF----------R---- zirconium 103 (Zr-103) + 783 0 401040 82c DEC 40 104 0 103.92880 900.0 5.77623E-01 IB-DF----------R---- zirconium 104 (Zr-104) + 784 0 401050 82c DEC 40 105 0 104.93243 900.0 1.15525E+00 IB-DF-----P----R---- zirconium 105 (Zr-105) + 785 0 401060 82c DEC 40 106 0 105.93504 900.0 7.70164E-01 IB-DF-----P----R---- zirconium 106 (Zr-106) + 786 0 401070 82c DEC 40 107 0 106.94068 900.0 2.88811E+00 IB-DF-----P----R---- zirconium 107 (Zr-107) + 787 0 401080 82c DEC 40 108 0 107.94430 900.0 8.66434E+00 IB--F----------R---- zirconium 108 (Zr-108) + 788 0 401090 82c DEC 40 109 0 108.94893 900.0 1.15525E+01 IB--F----------R---- zirconium 109 (Zr-109) + 789 0 410900 82c DEC 41 90 0 89.91129 900.0 1.31968E-05 IBA------------R---- niobium 90 (Nb-90) + 790 0 410910 82c DEC 41 91 0 90.90704 900.0 3.23007E-11 IBAD-----------R---- niobium 91 (Nb-91) + 791 0 410911 82c DEC 41 91 1 90.90704 900.0 1.31733E-07 IB-D-----------R---- niobium 91m (Nb-91m) + 792 0 410920 82c DEC 41 92 0 91.90723 900.0 6.27555E-16 IBA------------R---- niobium 92 (Nb-92) + 793 0 410931 82c DEC 41 93 1 92.90642 900.0 1.36259E-09 IB-DF----------R---- niobium 93m (Nb-93m) + 794 0 410941 82c DEC 41 94 1 93.90731 900.0 1.84544E-03 IBA-F----------R---- niobium 94m (Nb-94m) + 795 0 410951 82c DEC 41 95 1 94.90680 900.0 2.22231E-06 IBADF----------R---- niobium 95m (Nb-95m) + 796 0 410960 82c DEC 41 96 0 95.90810 900.0 8.24586E-06 IBA-F----------R---- niobium 96 (Nb-96) + 797 0 410970 82c DEC 41 97 0 96.90809 900.0 1.60228E-04 IBADF----------R---- niobium 97 (Nb-97) + 798 0 410971 82c DEC 41 97 1 96.90809 900.0 1.31527E-02 IB-DF----------R---- niobium 97m (Nb-97m) + 799 0 410980 82c DEC 41 98 0 97.91030 900.0 2.42359E-01 IBADF----------R---- niobium 98 (Nb-98) + 800 0 410981 82c DEC 41 98 1 97.91030 900.0 2.25194E-04 IB--F----------R---- niobium 98m (Nb-98m) + 801 0 410990 82c DEC 41 99 0 98.91160 900.0 4.62098E-02 IBADF----------R---- niobium 99 (Nb-99) + 802 0 410991 82c DEC 41 99 1 98.91160 900.0 4.44325E-03 IB-DF----------R---- niobium 99m (Nb-99m) + 803 0 411000 82c DEC 41 100 0 99.91422 900.0 4.62098E-01 IBADF----------R---- niobium 100 (Nb-100) + 804 0 411001 82c DEC 41 100 1 99.91422 900.0 2.39016E-01 IB--F----------R---- niobium 100m (Nb-100m) + 805 0 411010 82c DEC 41 101 0 100.91491 900.0 9.76264E-02 IB-DF----------R---- niobium 101 (Nb-101) + 806 0 411020 82c DEC 41 102 0 101.91853 900.0 5.33190E-01 IB-DF----------R---- niobium 102 (Nb-102) + 807 0 411021 82c DEC 41 102 1 101.91853 900.0 1.61197E-01 IB--F----------R---- niobium 102m (Nb-102m) + 808 0 411030 82c DEC 41 103 0 102.91913 900.0 4.62098E-01 IB-DF----------R---- niobium 103 (Nb-103) + 809 0 411040 82c DEC 41 104 0 103.92275 900.0 1.41459E-01 IB-DF-----P----R---- niobium 104 (Nb-104) + 810 0 411041 82c DEC 41 104 1 103.92275 900.0 7.37391E-01 IB--F-----P----R---- niobium 104m (Nb-104m) + 811 0 411050 82c DEC 41 105 0 104.92436 900.0 2.34965E-01 IB-DF-----P----R---- niobium 105 (Nb-105) + 812 0 411060 82c DEC 41 106 0 105.92798 900.0 7.53421E-01 IB-DF-----P----R---- niobium 106 (Nb-106) + 813 0 411070 82c DEC 41 107 0 106.93059 900.0 2.31049E+00 IB-DF-----P----R---- niobium 107 (Nb-107) + 814 0 411080 82c DEC 41 108 0 107.93522 900.0 3.59144E+00 IB-DF-----P----R---- niobium 108 (Nb-108) + 815 0 411090 82c DEC 41 109 0 108.93783 900.0 3.64814E+00 IB-DF-----P----R---- niobium 109 (Nb-109) + 816 0 411100 82c DEC 41 110 0 109.94246 900.0 4.07734E+00 IB--F-----P----R---- niobium 110 (Nb-110) + 817 0 411110 82c DEC 41 111 0 110.94609 900.0 8.66434E+00 IB--F----------R---- niobium 111 (Nb-111) + 818 0 411120 82c DEC 41 112 0 111.95072 900.0 1.15525E+01 IB--F----------R---- niobium 112 (Nb-112) + 819 0 420910 82c DEC 42 91 0 90.91178 900.0 7.45801E-04 IBA------------R---- molybdenum 91 (Mo-91) + 820 0 420930 82c DEC 42 93 0 92.90682 900.0 7.29322E-12 IBAD-----------R---- molybdenum 93 (Mo-93) + 821 0 420931 82c DEC 42 93 1 92.90682 900.0 2.81082E-05 IBA------------R---- molybdenum 93m (Mo-93m) + 822 0 421010 82c DEC 42 101 0 100.90987 900.0 7.90722E-04 IBADF----------R---- molybdenum 101 (Mo-101) + 823 0 421020 82c DEC 42 102 0 101.91046 900.0 1.02234E-03 IBADF----------R---- molybdenum 102 (Mo-102) + 824 0 421030 82c DEC 42 103 0 102.91308 900.0 1.02084E-02 IBADF----------R---- molybdenum 103 (Mo-103) + 825 0 421040 82c DEC 42 104 0 103.91367 900.0 1.15525E-02 IBADF----------R---- molybdenum 104 (Mo-104) + 826 0 421050 82c DEC 42 105 0 104.91730 900.0 1.94704E-02 IBADF----------R---- molybdenum 105 (Mo-105) + 827 0 421060 82c DEC 42 106 0 105.91789 900.0 7.93983E-02 IB-DF----------R---- molybdenum 106 (Mo-106) + 828 0 421070 82c DEC 42 107 0 106.92151 900.0 1.98042E-01 IB-DF----------R---- molybdenum 107 (Mo-107) + 829 0 421080 82c DEC 42 108 0 107.92312 900.0 6.35915E-01 IB-DF----------R---- molybdenum 108 (Mo-108) + 830 0 421090 82c DEC 42 109 0 108.92775 900.0 1.38629E+00 IB-DF-----P----R---- molybdenum 109 (Mo-109) + 831 0 421100 82c DEC 42 110 0 109.92935 900.0 2.31049E+00 IB-DF----------R---- molybdenum 110 (Mo-110) + 832 0 421110 82c DEC 42 111 0 110.93499 900.0 1.38629E+00 IB-DF-----P----R---- molybdenum 111 (Mo-111) + 833 0 421120 82c DEC 42 112 0 111.93760 900.0 6.93147E-01 IB-DF-----P----R---- molybdenum 112 (Mo-112) + 834 0 421130 82c DEC 42 113 0 112.94223 900.0 6.93147E+00 IB--F----------R---- molybdenum 113 (Mo-113) + 835 0 421140 82c DEC 42 114 0 113.94485 900.0 8.66434E+00 IB--F----------R---- molybdenum 114 (Mo-114) + 836 0 421150 82c DEC 42 115 0 114.95049 900.0 1.15525E+01 IB--F----------R---- molybdenum 115 (Mo-115) + 837 0 430970 82c DEC 43 97 0 96.90638 900.0 8.44788E-15 IBA------------R---- technetium 97 (Tc-97) + 838 0 430980 82c DEC 43 98 0 97.90728 900.0 5.10813E-15 IBA-F----------R---- technetium 98 (Tc-98) + 839 0 430991 82c DEC 43 99 1 98.90626 900.0 3.20544E-05 IB-DF----------R---- technetium 99m (Tc-99m) + 840 0 431000 82c DEC 43 100 0 99.90766 900.0 4.48349E-02 IBA-F----------R---- technetium 100 (Tc-100) + 841 0 431010 82c DEC 43 101 0 100.90684 900.0 8.13553E-04 IBADF----------R---- technetium 101 (Tc-101) + 842 0 431020 82c DEC 43 102 0 101.90946 900.0 1.31278E-01 IBADF----------R---- technetium 102 (Tc-102) + 843 0 431021 82c DEC 43 102 1 101.90946 900.0 2.65574E-03 IB--F----------R---- technetium 102m (Tc-102m) + 844 0 431030 82c DEC 43 103 0 102.90904 900.0 1.27887E-02 IBADF----------R---- technetium 103 (Tc-103) + 845 0 431040 82c DEC 43 104 0 103.91166 900.0 6.31282E-04 IBADF----------R---- technetium 104 (Tc-104) + 846 0 431050 82c DEC 43 105 0 104.91124 900.0 1.52006E-03 IBADF----------R---- technetium 105 (Tc-105) + 847 0 431060 82c DEC 43 106 0 105.91386 900.0 1.94704E-02 IBADF----------R---- technetium 106 (Tc-106) + 848 0 431070 82c DEC 43 107 0 106.91546 900.0 3.26956E-02 IB-DF----------R---- technetium 107 (Tc-107) + 849 0 431080 82c DEC 43 108 0 107.91807 900.0 1.34071E-01 IB-DF----------R---- technetium 108 (Tc-108) + 850 0 431090 82c DEC 43 109 0 108.91968 900.0 8.05985E-01 IB-DF-----P----R---- technetium 109 (Tc-109) + 851 0 431100 82c DEC 43 110 0 109.92431 900.0 7.53421E-01 IB-DF-----P----R---- technetium 110 (Tc-110) + 852 0 431110 82c DEC 43 111 0 110.92591 900.0 2.39016E+00 IB-DF----------R---- technetium 111 (Tc-111) + 853 0 431120 82c DEC 43 112 0 111.92953 900.0 2.39016E+00 IB-DF-----P----R---- technetium 112 (Tc-112) + 854 0 431130 82c DEC 43 113 0 112.93215 900.0 5.33190E+00 IB-DF-----P----R---- technetium 113 (Tc-113) + 855 0 431140 82c DEC 43 114 0 113.93678 900.0 3.46574E+00 IB-DF-----P----R---- technetium 114 (Tc-114) + 856 0 431150 82c DEC 43 115 0 114.93939 900.0 2.56721E+00 IB-DF-----P----R---- technetium 115 (Tc-115) + 857 0 431160 82c DEC 43 116 0 115.94402 900.0 5.77623E+00 IB--F-----P----R---- technetium 116 (Tc-116) + 858 0 431170 82c DEC 43 117 0 116.94663 900.0 1.73287E+01 IB--F----------R---- technetium 117 (Tc-117) + 859 0 431180 82c DEC 43 118 0 117.95126 900.0 2.31049E+01 IB--F----------R---- technetium 118 (Tc-118) + 860 0 440980 82c DEC 44 98 0 97.90526 900.0 stable IBAD-----------R---- ruthenium 98 (Ru-98) + 861 0 440990 82c DEC 44 99 0 98.90595 900.0 stable IBAD-----------R---- ruthenium 99 (Ru-99) + 862 0 441031 82c DEC 44 103 1 102.90602 900.0 4.10146E+02 IB--F----------R---- ruthenium 103m (Ru-103m) + 863 0 441070 82c DEC 44 107 0 106.90941 900.0 3.08065E-03 IBADF----------R---- ruthenium 107 (Ru-107) + 864 0 441080 82c DEC 44 108 0 107.91000 900.0 2.53900E-03 IBADF----------R---- ruthenium 108 (Ru-108) + 865 0 441090 82c DEC 44 109 0 108.91363 900.0 2.00912E-02 IBADF----------R---- ruthenium 109 (Ru-109) + 866 0 441100 82c DEC 44 110 0 109.91422 900.0 5.75704E-02 IB-DF----------R---- ruthenium 110 (Ru-110) + 867 0 441110 82c DEC 44 111 0 110.91784 900.0 3.26956E-01 IB-DF----------R---- ruthenium 111 (Ru-111) + 868 0 441120 82c DEC 44 112 0 111.91945 900.0 3.96084E-01 IB-DF----------R---- ruthenium 112 (Ru-112) + 869 0 441130 82c DEC 44 113 0 112.92206 900.0 8.66434E-01 IB-DF----------R---- ruthenium 113 (Ru-113) + 870 0 441131 82c DEC 44 113 1 112.92206 900.0 1.35911E+00 IB--F----------R---- ruthenium 113m (Ru-113m) + 871 0 441140 82c DEC 44 114 0 113.92467 900.0 1.30782E+00 IB-DF----------R---- ruthenium 114 (Ru-114) + 872 0 441150 82c DEC 44 115 0 114.92830 900.0 9.90210E-01 IB-DF-----P----R---- ruthenium 115 (Ru-115) + 873 0 441160 82c DEC 44 116 0 115.93091 900.0 4.07734E-01 IB-DF-----P----R---- ruthenium 116 (Ru-116) + 874 0 441170 82c DEC 44 117 0 116.93554 900.0 2.03867E+00 IB-DF-----P----R---- ruthenium 117 (Ru-117) + 875 0 441180 82c DEC 44 118 0 117.93714 900.0 9.90210E-01 IB-DF-----P----R---- ruthenium 118 (Ru-118) + 876 0 441190 82c DEC 44 119 0 118.94177 900.0 3.64814E+00 IB--F-----P----R---- ruthenium 119 (Ru-119) + 877 0 441200 82c DEC 44 120 0 119.94539 900.0 8.66434E+00 IB--F----------R---- ruthenium 120 (Ru-120) + 878 0 451010 82c DEC 45 101 0 100.90583 900.0 6.86407E-09 IBA------------R---- rhodium 101 (Rh-101) + 879 0 451020 82c DEC 45 102 0 101.90643 900.0 7.56843E-09 IBA------------R---- rhodium 102 (Rh-102) + 880 0 451031 82c DEC 45 103 1 102.90602 900.0 2.05871E-04 IB-DF----------R---- rhodium 103m (Rh-103m) + 881 0 451040 82c DEC 45 104 0 103.90661 900.0 1.63865E-02 IBADF----------R---- rhodium 104 (Rh-104) + 882 0 451041 82c DEC 45 104 1 103.90661 900.0 2.66186E-03 IBA-F----------R---- rhodium 104m (Rh-104m) + 883 0 451051 82c DEC 45 105 1 104.90519 900.0 1.73287E-02 IB-DF----------R---- rhodium 105m (Rh-105m) + 884 0 451060 82c DEC 45 106 0 105.90680 900.0 2.30281E-02 IBADF----------R---- rhodium 106 (Rh-106) + 885 0 451061 82c DEC 45 106 1 105.90780 900.0 8.75186E-05 IBA-F----------R---- rhodium 106m (Rh-106m) + 886 0 451070 82c DEC 45 107 0 106.90638 900.0 5.32371E-04 IBADF----------R---- rhodium 107 (Rh-107) + 887 0 451080 82c DEC 45 108 0 107.90900 900.0 4.12588E-02 IBADF----------R---- rhodium 108 (Rh-108) + 888 0 451081 82c DEC 45 108 1 107.90900 900.0 1.92541E-03 IB--F----------R---- rhodium 108m (Rh-108m) + 889 0 451090 82c DEC 45 109 0 108.90858 900.0 8.66434E-03 IBADF----------R---- rhodium 109 (Rh-109) + 890 0 451100 82c DEC 45 110 0 109.91120 900.0 2.43210E-02 IBADF----------R---- rhodium 110 (Rh-110) + 891 0 451101 82c DEC 45 110 1 109.91120 900.0 2.16608E-01 IB--F----------R---- rhodium 110m (Rh-110m) + 892 0 451110 82c DEC 45 111 0 110.91179 900.0 5.77623E-02 IB-DF----------R---- rhodium 111 (Rh-111) + 893 0 451120 82c DEC 45 112 0 111.91440 900.0 3.30070E-01 IB-DF----------R---- rhodium 112 (Rh-112) + 894 0 451121 82c DEC 45 112 1 111.91440 900.0 1.01933E-01 IB--F----------R---- rhodium 112m (Rh-112m) + 895 0 451130 82c DEC 45 113 0 112.91601 900.0 2.47553E-01 IB-DF----------R---- rhodium 113 (Rh-113) + 896 0 451140 82c DEC 45 114 0 113.91862 900.0 3.74674E-01 IB-DF----------R---- rhodium 114 (Rh-114) + 897 0 451141 82c DEC 45 114 1 113.91862 900.0 3.74674E-01 IB--F----------R---- rhodium 114m (Rh-114m) + 898 0 451150 82c DEC 45 115 0 114.92023 900.0 7.00149E-01 IB-DF----------R---- rhodium 115 (Rh-115) + 899 0 451160 82c DEC 45 116 0 115.92385 900.0 1.01933E+00 IB-DF----------R---- rhodium 116 (Rh-116) + 900 0 451161 82c DEC 45 116 1 115.92385 900.0 1.21605E+00 IB--F----------R---- rhodium 116m (Rh-116m) + 901 0 451170 82c DEC 45 117 0 116.92646 900.0 1.57533E+00 IB-DF----------R---- rhodium 117 (Rh-117) + 902 0 451180 82c DEC 45 118 0 117.93008 900.0 2.16608E+00 IB-DF-----P----R---- rhodium 118 (Rh-118) + 903 0 451190 82c DEC 45 119 0 118.93169 900.0 2.31049E+00 IB-DF----------R---- rhodium 119 (Rh-119) + 904 0 451200 82c DEC 45 120 0 119.93632 900.0 4.07734E+00 IB-DF-----P----R---- rhodium 120 (Rh-120) + 905 0 451210 82c DEC 45 121 0 120.93792 900.0 2.77259E+00 IB--F-----P----R---- rhodium 121 (Rh-121) + 906 0 451220 82c DEC 45 122 0 121.94356 900.0 1.38629E+01 IB--F----------R---- rhodium 122 (Rh-122) + 907 0 461030 82c DEC 46 103 0 102.90602 900.0 4.72470E-07 IBA------------R---- palladium 103 (Pd-103) + 908 0 461040 82c DEC 46 104 0 103.90359 900.0 stable IBAD-----------R---- palladium 104 (Pd-104) + 909 0 461071 82c DEC 46 107 1 106.90537 900.0 3.25421E-02 IBA-F----------R---- palladium 107m (Pd-107m) + 910 0 461090 82c DEC 46 109 0 108.90556 900.0 1.41783E-05 IBADF----------R---- palladium 109 (Pd-109) + 911 0 461091 82c DEC 46 109 1 108.90556 900.0 2.46321E-03 IBADF----------R---- palladium 109m (Pd-109m) + 912 0 461110 82c DEC 46 111 0 110.90776 900.0 4.93695E-04 IBADF----------R---- palladium 111 (Pd-111) + 913 0 461111 82c DEC 46 111 1 110.90776 900.0 3.50074E-05 IBA-F----------R---- palladium 111m (Pd-111m) + 914 0 461120 82c DEC 46 112 0 111.90734 900.0 9.48477E-06 IBADF----------R---- palladium 112 (Pd-112) + 915 0 461130 82c DEC 46 113 0 112.91097 900.0 7.61700E-03 IBADF----------R---- palladium 113 (Pd-113) + 916 0 461131 82c DEC 46 113 1 112.91097 900.0 2.31049E+00 IB--F----------R---- palladium 113m (Pd-113m) + 917 0 461140 82c DEC 46 114 0 113.91055 900.0 4.77374E-03 IBADF----------R---- palladium 114 (Pd-114) + 918 0 461150 82c DEC 46 115 0 114.91417 900.0 2.77259E-02 IB-DF----------R---- palladium 115 (Pd-115) + 919 0 461151 82c DEC 46 115 1 114.91417 900.0 1.38629E-02 IB-DF----------R---- palladium 115m (Pd-115m) + 920 0 461160 82c DEC 46 116 0 115.91376 900.0 5.87413E-02 IB-DF----------R---- palladium 116 (Pd-116) + 921 0 461170 82c DEC 46 117 0 116.91738 900.0 1.61197E-01 IB-DF----------R---- palladium 117 (Pd-117) + 922 0 461171 82c DEC 46 117 1 116.91738 900.0 3.62904E+01 IB--F----------R---- palladium 117m (Pd-117m) + 923 0 461180 82c DEC 46 118 0 117.91899 900.0 3.64814E-01 IB-DF----------R---- palladium 118 (Pd-118) + 924 0 461190 82c DEC 46 119 0 118.92362 900.0 7.53421E-01 IB-DF----------R---- palladium 119 (Pd-119) + 925 0 461200 82c DEC 46 120 0 119.92421 900.0 1.38629E+00 IB-DF----------R---- palladium 120 (Pd-120) + 926 0 461210 82c DEC 46 121 0 120.92783 900.0 1.15525E+00 IB-DF-----P----R---- palladium 121 (Pd-121) + 927 0 461220 82c DEC 46 122 0 121.93045 900.0 2.31049E+00 IB-DF----------R---- palladium 122 (Pd-122) + 928 0 461230 82c DEC 46 123 0 122.93508 900.0 3.46574E+00 IB--F----------R---- palladium 123 (Pd-123) + 929 0 461240 82c DEC 46 124 0 123.93668 900.0 6.93147E+00 IB--F----------R---- palladium 124 (Pd-124) + 930 0 471070 82c DEC 47 107 0 106.90537 900.0 stable IBAD-----------R---- silver 107 (Ag-107) + 931 0 471080 82c DEC 47 108 0 107.90597 900.0 4.84990E-03 IBADF----------R---- silver 108 (Ag-108) + 932 0 471081 82c DEC 47 108 1 107.90597 900.0 5.01485E-11 IB--F----------R---- silver 108m (Ag-108m) + 933 0 471091 82c DEC 47 109 1 108.90455 900.0 1.74596E-02 IB-DF----------R---- silver 109m (Ag-109m) + 934 0 471100 82c DEC 47 110 0 109.90615 900.0 2.82226E-02 IBADF----------R---- silver 110 (Ag-110) + 935 0 471111 82c DEC 47 111 1 110.90574 900.0 1.06967E-02 IB-DF----------R---- silver 111m (Ag-111m) + 936 0 471120 82c DEC 47 112 0 111.90734 900.0 6.15147E-05 IBADF----------R---- silver 112 (Ag-112) + 937 0 471130 82c DEC 47 113 0 112.90693 900.0 3.58549E-05 IBADF----------R---- silver 113 (Ag-113) + 938 0 471131 82c DEC 47 113 1 112.90693 900.0 1.00895E-02 IB-DF----------R---- silver 113m (Ag-113m) + 939 0 471140 82c DEC 47 114 0 113.90853 900.0 1.50684E-01 IBADF----------R---- silver 114 (Ag-114) + 940 0 471141 82c DEC 47 114 1 113.90853 900.0 4.62098E+02 IB--F----------R---- silver 114m (Ag-114m) + 941 0 471150 82c DEC 47 115 0 114.90913 900.0 5.77623E-04 IBADF----------R---- silver 115 (Ag-115) + 942 0 471151 82c DEC 47 115 1 114.90913 900.0 3.72660E-02 IB-DF----------R---- silver 115m (Ag-115m) + 943 0 471160 82c DEC 47 116 0 115.91174 900.0 2.92467E-03 IBADF----------R---- silver 116 (Ag-116) + 944 0 471161 82c DEC 47 116 1 115.91174 900.0 8.05985E-02 IB--F----------R---- silver 116m (Ag-116m) + 945 0 471170 82c DEC 47 117 0 116.91133 900.0 9.41776E-03 IB-DF----------R---- silver 117 (Ag-117) + 946 0 471171 82c DEC 47 117 1 116.91133 900.0 1.29803E-01 IB-DF----------R---- silver 117m (Ag-117m) + 947 0 471180 82c DEC 47 118 0 117.91495 900.0 1.84348E-01 IB-DF----------R---- silver 118 (Ag-118) + 948 0 471181 82c DEC 47 118 1 117.91495 900.0 3.46574E-01 IB-DF----------R---- silver 118m (Ag-118m) + 949 0 471190 82c DEC 47 119 0 118.91555 900.0 1.15525E-01 IB-DF----------R---- silver 119 (Ag-119) + 950 0 471191 82c DEC 47 119 1 118.91555 900.0 3.30070E-01 IB-DF----------R---- silver 119m (Ag-119m) + 951 0 471200 82c DEC 47 120 0 119.91917 900.0 5.63534E-01 IB-DF-----P----R---- silver 120 (Ag-120) + 952 0 471201 82c DEC 47 120 1 119.91917 900.0 1.86832E+00 IB-DF----------R---- silver 120m (Ag-120m) + 953 0 471210 82c DEC 47 121 0 120.91976 900.0 8.88650E-01 IB-DF----------R---- silver 121 (Ag-121) + 954 0 471220 82c DEC 47 122 0 121.92339 900.0 1.31030E+00 IB-DF----------R---- silver 122 (Ag-122) + 955 0 471221 82c DEC 47 122 1 121.92339 900.0 4.62098E-01 IB--F----------R---- silver 122m (Ag-122m) + 956 0 471230 82c DEC 47 123 0 122.92499 900.0 2.31049E+00 IB-DF----------R---- silver 123 (Ag-123) + 957 0 471240 82c DEC 47 124 0 123.92861 900.0 4.02993E+00 IB-DF-----P----R---- silver 124 (Ag-124) + 958 0 471241 82c DEC 47 124 1 123.92861 900.0 3.46574E+00 IB--F----------R---- silver 124m (Ag-124m) + 959 0 471250 82c DEC 47 125 0 124.93022 900.0 4.17559E+00 IB--F----------R---- silver 125 (Ag-125) + 960 0 471260 82c DEC 47 126 0 125.93485 900.0 6.47801E+00 IB--F----------R---- silver 126 (Ag-126) + 961 0 471270 82c DEC 47 127 0 126.93645 900.0 8.77401E+00 IB--F----------R---- silver 127 (Ag-127) + 962 0 471280 82c DEC 47 128 0 127.94108 900.0 1.19508E+01 IB--F----------R---- silver 128 (Ag-128) + 963 0 471290 82c DEC 47 129 0 128.94369 900.0 1.57533E+01 IB--F----------R---- silver 129 (Ag-129) + 964 0 471300 82c DEC 47 130 0 129.95034 900.0 1.38629E+01 IB--F----------R---- silver 130 (Ag-130) + 965 0 481080 82c DEC 48 108 0 107.90395 900.0 5.35720E-26 IBAD-----------R---- cadmium 108 (Cd-108) + 966 0 481090 82c DEC 48 109 0 108.90455 900.0 1.73685E-08 IBA------------R---- cadmium 109 (Cd-109) + 967 0 481111 82c DEC 48 111 1 110.90372 900.0 2.37999E-04 IBADF----------R---- cadmium 111m (Cd-111m) + 968 0 481131 82c DEC 48 113 1 112.90390 900.0 1.55780E-09 IBADF----------R---- cadmium 113m (Cd-113m) + 969 0 481150 82c DEC 48 115 0 114.90510 900.0 3.60159E-06 IBADF----------R---- cadmium 115 (Cd-115) + 970 0 481170 82c DEC 48 117 0 116.90730 900.0 7.73257E-05 IBADF----------R---- cadmium 117 (Cd-117) + 971 0 481171 82c DEC 48 117 1 116.90730 900.0 5.73038E-05 IBADF----------R---- cadmium 117m (Cd-117m) + 972 0 481180 82c DEC 48 118 0 117.90688 900.0 2.29671E-04 IBADF----------R---- cadmium 118 (Cd-118) + 973 0 481190 82c DEC 48 119 0 118.90950 900.0 4.29459E-03 IBADF----------R---- cadmium 119 (Cd-119) + 974 0 481191 82c DEC 48 119 1 118.90950 900.0 5.25112E-03 IB-DF----------R---- cadmium 119m (Cd-119m) + 975 0 481200 82c DEC 48 120 0 119.91009 900.0 1.36446E-02 IBADF----------R---- cadmium 120 (Cd-120) + 976 0 481210 82c DEC 48 121 0 120.91270 900.0 5.13442E-02 IBADF----------R---- cadmium 121 (Cd-121) + 977 0 481211 82c DEC 48 121 1 120.91270 900.0 8.35117E-02 IB-DF----------R---- cadmium 121m (Cd-121m) + 978 0 481220 82c DEC 48 122 0 121.91330 900.0 1.32280E-01 IBADF----------R---- cadmium 122 (Cd-122) + 979 0 481230 82c DEC 48 123 0 122.91692 900.0 3.30070E-01 IBADF----------R---- cadmium 123 (Cd-123) + 980 0 481231 82c DEC 48 123 1 122.91692 900.0 3.80850E-01 IB-DF----------R---- cadmium 123m (Cd-123m) + 981 0 481240 82c DEC 48 124 0 123.91752 900.0 5.54518E-01 IBADF----------R---- cadmium 124 (Cd-124) + 982 0 481250 82c DEC 48 125 0 124.92114 900.0 1.01933E+00 IBADF----------R---- cadmium 125 (Cd-125) + 983 0 481251 82c DEC 48 125 1 124.92114 900.0 1.44406E+00 IB-DF----------R---- cadmium 125m (Cd-125m) + 984 0 481260 82c DEC 48 126 0 125.92274 900.0 1.34592E+00 IB-DF----------R---- cadmium 126 (Cd-126) + 985 0 481270 82c DEC 48 127 0 126.92636 900.0 1.87337E+00 IB-DF----------R---- cadmium 127 (Cd-127) + 986 0 481280 82c DEC 48 128 0 127.92797 900.0 2.47553E+00 IB-DF----------R---- cadmium 128 (Cd-128) + 987 0 481290 82c DEC 48 129 0 128.93260 900.0 2.86424E+00 IB-DF----------R---- cadmium 129 (Cd-129) + 988 0 481291 82c DEC 48 129 1 128.93260 900.0 6.66488E+00 IB-DF----------R---- cadmium 129m (Cd-129m) + 989 0 481300 82c DEC 48 130 0 129.93420 900.0 4.27869E+00 IB-DF-----P----R---- cadmium 130 (Cd-130) + 990 0 481310 82c DEC 48 131 0 130.94085 900.0 1.01933E+01 IB--F-----P----R---- cadmium 131 (Cd-131) + 991 0 481320 82c DEC 48 132 0 131.94548 900.0 7.14585E+00 IB--F-----P----R---- cadmium 132 (Cd-132) + 992 0 491110 82c DEC 49 111 0 110.90473 900.0 2.86019E-06 IBA------------R---- indium 111 (In-111) + 993 0 491120 82c DEC 49 112 0 111.90533 900.0 7.85881E-04 IBA------------R---- indium 112 (In-112) + 994 0 491131 82c DEC 49 113 1 112.90390 900.0 1.16135E-04 IB-DF----------R---- indium 113m (In-113m) + 995 0 491140 82c DEC 49 114 0 113.90450 900.0 9.64043E-03 IBADF----------R---- indium 114 (In-114) + 996 0 491141 82c DEC 49 114 1 113.90450 900.0 1.60451E-07 IBADF----------R---- indium 114m (In-114m) + 997 1 491142 82c DEC 49 114 2 113.90450 900.0 1.61197E+01 -B--F----------R---- indium 114m (In-114m) + 998 0 491151 82c DEC 49 115 1 114.90409 900.0 4.29204E-05 IB-DF----------R---- indium 115m (In-115m) + 999 0 491160 82c DEC 49 116 0 115.90569 900.0 4.88132E-02 IBA-F----------R---- indium 116 (In-116) + 1000 0 491161 82c DEC 49 116 1 115.90569 900.0 2.11583E-04 IB-DF----------R---- indium 116m (In-116m) + 1001 1 491162 82c DEC 49 116 2 115.90569 900.0 3.19423E-01 -B--F----------R---- indium 116m (In-116m) + 1002 0 491170 82c DEC 49 117 0 116.90427 900.0 2.67418E-04 IBADF----------R---- indium 117 (In-117) + 1003 0 491171 82c DEC 49 117 1 116.90427 900.0 9.94187E-05 IB-DF----------R---- indium 117m (In-117m) + 1004 0 491180 82c DEC 49 118 0 117.90587 900.0 1.38629E-01 IBADF----------R---- indium 118 (In-118) + 1005 0 491181 82c DEC 49 118 1 117.90587 900.0 2.59606E-03 IB-DF----------R---- indium 118m (In-118m) + 1006 1 491182 82c DEC 49 118 2 117.90587 900.0 8.15467E-02 -B--F----------R---- indium 118m (In-118m) + 1007 0 491190 82c DEC 49 119 0 118.90546 900.0 4.81352E-03 IBADF----------R---- indium 119 (In-119) + 1008 0 491191 82c DEC 49 119 1 118.90546 900.0 6.41803E-04 IB-DF----------R---- indium 119m (In-119m) + 1009 0 491200 82c DEC 49 120 0 119.90807 900.0 2.25048E-01 IBADF----------R---- indium 120 (In-120) + 1010 0 491201 82c DEC 49 120 1 119.90807 900.0 1.50032E-02 IB--F----------R---- indium 120m (In-120m) + 1011 1 491202 82c DEC 49 120 2 119.90807 900.0 1.46543E-02 -B--F----------R---- indium 120m (In-120m) + 1012 0 491210 82c DEC 49 121 0 120.90766 900.0 3.00064E-02 IBADF----------R---- indium 121 (In-121) + 1013 0 491211 82c DEC 49 121 1 120.90766 900.0 2.97744E-03 IB-DF----------R---- indium 121m (In-121m) + 1014 0 491220 82c DEC 49 122 0 121.91027 900.0 4.62098E-01 IBADF----------R---- indium 122 (In-122) + 1015 0 491221 82c DEC 49 122 1 121.91027 900.0 6.41803E-02 IB--F----------R---- indium 122m (In-122m) + 1016 1 491222 82c DEC 49 122 2 121.91027 900.0 6.41803E-02 -B--F----------R---- indium 122m (In-122m) + 1017 0 491230 82c DEC 49 123 0 122.91087 900.0 1.12342E-01 IBADF----------R---- indium 123 (In-123) + 1018 0 491231 82c DEC 49 123 1 122.91087 900.0 1.45010E-02 IB-DF----------R---- indium 123m (In-123m) + 1019 0 491240 82c DEC 49 124 0 123.91348 900.0 2.22163E-01 IBADF----------R---- indium 124 (In-124) + 1020 0 491241 82c DEC 49 124 1 123.91348 900.0 1.87337E-01 IB--F----------R---- indium 124m (In-124m) + 1021 0 491250 82c DEC 49 125 0 124.91408 900.0 2.93706E-01 IBADF----------R---- indium 125 (In-125) + 1022 0 491251 82c DEC 49 125 1 124.91408 900.0 5.68153E-02 IB-DF----------R---- indium 125m (In-125m) + 1023 0 491260 82c DEC 49 126 0 125.91669 900.0 4.53037E-01 IBADF----------R---- indium 126 (In-126) + 1024 0 491261 82c DEC 49 126 1 125.91669 900.0 4.22651E-01 IB--F----------R---- indium 126m (In-126m) + 1025 0 491270 82c DEC 49 127 0 126.91729 900.0 6.35915E-01 IB--F----------R---- indium 127 (In-127) + 1026 0 491271 82c DEC 49 127 1 126.91729 900.0 1.88868E-01 IB-DF-----P----R---- indium 127m (In-127m) + 1027 0 491280 82c DEC 49 128 0 127.91990 900.0 8.25175E-01 IB-DF----------R---- indium 128 (In-128) + 1028 0 491281 82c DEC 49 128 1 127.91990 900.0 6.93147E+01 IB-DF----------R---- indium 128m (In-128m) + 1029 1 491282 82c DEC 49 128 2 127.91990 900.0 9.62704E-01 -B--F----------R---- indium 128m (In-128m) + 1030 0 491290 82c DEC 49 129 0 128.92150 900.0 1.13631E+00 IB-DF----------R---- indium 129 (In-129) + 1031 0 491291 82c DEC 49 129 1 128.92150 900.0 5.63534E-01 IB-DF----------R---- indium 129m (In-129m) + 1032 0 491300 82c DEC 49 130 0 129.92513 900.0 2.39016E+00 IB-DF----------R---- indium 130 (In-130) + 1033 0 491301 82c DEC 49 130 1 129.92513 900.0 1.28361E+00 IB--F----------R---- indium 130m (In-130m) + 1034 1 491302 82c DEC 49 130 2 129.92513 900.0 1.28361E+00 -B--F----------R---- indium 130m (In-130m) + 1035 0 491310 82c DEC 49 131 0 130.92673 900.0 2.47553E+00 IB-DF----------R---- indium 131 (In-131) + 1036 0 491311 82c DEC 49 131 1 130.92673 900.0 1.98042E+00 IB-DF-----P----R---- indium 131m (In-131m) + 1037 1 491312 82c DEC 49 131 2 130.92673 900.0 2.16608E+00 -B--F-----P----R---- indium 131m (In-131m) + 1038 0 491320 82c DEC 49 132 0 131.93338 900.0 3.34854E+00 IB-DF----------R---- indium 132 (In-132) + 1039 0 491330 82c DEC 49 133 0 132.93801 900.0 4.20089E+00 IB-DF-----P----R---- indium 133 (In-133) + 1040 0 491331 82c DEC 49 133 1 132.93801 900.0 3.85082E+00 IB--F----------R---- indium 133m (In-133m) + 1041 0 491340 82c DEC 49 134 0 133.94466 900.0 4.95105E+00 IB--F-----P----R---- indium 134 (In-134) + 1042 0 491350 82c DEC 49 135 0 134.94929 900.0 7.53421E+00 IB--F----------R---- indium 135 (In-135) + 1043 0 501120 82c DEC 50 112 0 111.90533 900.0 stable IB-D-----------R---- tin 112 (Sn-112) + 1044 0 501130 82c DEC 50 113 0 112.90491 900.0 6.97066E-08 IBA------------R---- tin 113 (Sn-113) + 1045 0 501140 82c DEC 50 114 0 113.90248 900.0 stable IBAD-----------R---- tin 114 (Sn-114) + 1046 0 501171 82c DEC 50 117 1 116.90326 900.0 5.73038E-07 IBADF----------R---- tin 117m (Sn-117m) + 1047 0 501191 82c DEC 50 119 1 118.90344 900.0 2.73807E-08 IBADF----------R---- tin 119m (Sn-119m) + 1048 0 501210 82c DEC 50 121 0 120.90463 900.0 7.12323E-06 IBADF----------R---- tin 121 (Sn-121) + 1049 0 501211 82c DEC 50 121 1 120.90463 900.0 5.00341E-10 IBADF----------R---- tin 121m (Sn-121m) + 1050 0 501231 82c DEC 50 123 1 122.90583 900.0 2.88379E-04 IBADF----------R---- tin 123m (Sn-123m) + 1051 0 501251 82c DEC 50 125 1 124.90803 900.0 1.21349E-03 IBADF----------R---- tin 125m (Sn-125m) + 1052 0 501270 82c DEC 50 127 0 126.91023 900.0 9.16861E-05 IBADF----------R---- tin 127 (Sn-127) + 1053 0 501271 82c DEC 50 127 1 126.91023 900.0 2.79720E-03 IBADF----------R---- tin 127m (Sn-127m) + 1054 0 501280 82c DEC 50 128 0 127.91082 900.0 1.95572E-04 IBADF----------R---- tin 128 (Sn-128) + 1055 0 501281 82c DEC 50 128 1 127.91082 900.0 1.06638E-01 IB-DF----------R---- tin 128m (Sn-128m) + 1056 0 501290 82c DEC 50 129 0 128.91343 900.0 5.18047E-03 IBADF----------R---- tin 129 (Sn-129) + 1057 0 501291 82c DEC 50 129 1 128.91343 900.0 1.60451E-03 IB-DF----------R---- tin 129m (Sn-129m) + 1058 0 501300 82c DEC 50 130 0 129.91403 900.0 3.09717E-03 IBADF----------R---- tin 130 (Sn-130) + 1059 0 501301 82c DEC 50 130 1 129.91403 900.0 6.79556E-03 IB-DF----------R---- tin 130m (Sn-130m) + 1060 0 501310 82c DEC 50 131 0 130.91664 900.0 1.23776E-02 IBADF----------R---- tin 131 (Sn-131) + 1061 0 501311 82c DEC 50 131 1 130.91664 900.0 1.18690E-02 IB-DF----------R---- tin 131m (Sn-131m) + 1062 0 501320 82c DEC 50 132 0 131.91825 900.0 1.74596E-02 IB-DF----------R---- tin 132 (Sn-132) + 1063 0 501330 82c DEC 50 133 0 132.92389 900.0 4.74758E-01 IB-DF----------R---- tin 133 (Sn-133) + 1064 0 501340 82c DEC 50 134 0 133.92852 900.0 6.60140E-01 IB-DF-----P----R---- tin 134 (Sn-134) + 1065 0 501350 82c DEC 50 135 0 134.93516 900.0 1.30782E+00 IB-DF-----P----R---- tin 135 (Sn-135) + 1066 0 501360 82c DEC 50 136 0 135.93979 900.0 2.77259E+00 IB--F-----P----R---- tin 136 (Sn-136) + 1067 0 501370 82c DEC 50 137 0 136.94644 900.0 3.64814E+00 IB--F-----P----R---- tin 137 (Sn-137) + 1068 0 511180 82c DEC 51 118 0 117.90587 900.0 3.20901E-03 IBA-F----------R---- antimony 118 (Sb-118) + 1069 0 511181 82c DEC 51 118 1 117.90587 900.0 3.85082E-05 IB--F----------R---- antimony 118m (Sb-118m) + 1070 0 511190 82c DEC 51 119 0 118.90445 900.0 5.02718E-06 IBADF----------R---- antimony 119 (Sb-119) + 1071 0 511191 82c DEC 51 119 1 118.90445 900.0 8.15467E-01 IB--F----------R---- antimony 119m (Sb-119m) + 1072 0 511200 82c DEC 51 120 0 119.90505 900.0 7.26569E-04 IBA-F----------R---- antimony 120 (Sb-120) + 1073 0 511201 82c DEC 51 120 1 119.90505 900.0 1.39280E-06 IB--F----------R---- antimony 120m (Sb-120m) + 1074 0 511220 82c DEC 51 122 0 121.90523 900.0 2.97590E-06 IBADF----------R---- antimony 122 (Sb-122) + 1075 0 511221 82c DEC 51 122 1 121.90523 900.0 2.75715E-03 IBA-F----------R---- antimony 122m (Sb-122m) + 1076 0 511241 82c DEC 51 124 1 123.90642 900.0 7.45320E-03 IB-DF----------R---- antimony 124m (Sb-124m) + 1077 1 511242 82c DEC 51 124 2 123.90642 900.0 5.71904E-04 -B--F----------R---- antimony 124m (Sb-124m) + 1078 0 511261 82c DEC 51 126 1 125.90761 900.0 6.04840E-04 IB-DF----------R---- antimony 126m (Sb-126m) + 1079 1 511262 82c DEC 51 126 2 125.90761 900.0 6.30134E-02 -B-DF----------R---- antimony 126m (Sb-126m) + 1080 0 511270 82c DEC 51 127 0 126.90720 900.0 2.08378E-06 IBADF----------R---- antimony 127 (Sb-127) + 1081 0 511280 82c DEC 51 128 0 127.90880 900.0 2.13697E-05 IBADF----------R---- antimony 128 (Sb-128) + 1082 0 511281 82c DEC 51 128 1 127.90880 900.0 1.11081E-03 IB--F----------R---- antimony 128m (Sb-128m) + 1083 0 511290 82c DEC 51 129 0 128.90940 900.0 4.41608E-05 IBADF----------R---- antimony 129 (Sb-129) + 1084 0 511291 82c DEC 51 129 1 128.90940 900.0 6.52681E-04 IB-DF----------R---- antimony 129m (Sb-129m) + 1085 0 511300 82c DEC 51 130 0 129.91201 900.0 2.92467E-04 IBADF----------R---- antimony 130 (Sb-130) + 1086 0 511301 82c DEC 51 130 1 129.91201 900.0 1.83372E-03 IB-DF----------R---- antimony 130m (Sb-130m) + 1087 0 511310 82c DEC 51 131 0 130.91160 900.0 5.01626E-04 IBADF----------R---- antimony 131 (Sb-131) + 1088 0 511320 82c DEC 51 132 0 131.91421 900.0 4.14066E-03 IBADF----------R---- antimony 132 (Sb-132) + 1089 0 511321 82c DEC 51 132 1 131.91421 900.0 2.81767E-03 IB--F----------R---- antimony 132m (Sb-132m) + 1090 0 511330 82c DEC 51 133 0 132.91481 900.0 4.62098E-03 IB-DF----------R---- antimony 133 (Sb-133) + 1091 0 511340 82c DEC 51 134 0 133.92045 900.0 8.88650E-01 IB-DF----------R---- antimony 134 (Sb-134) + 1092 0 511341 82c DEC 51 134 1 133.92045 900.0 6.88329E-02 IB-DF-----P----R---- antimony 134m (Sb-134m) + 1093 0 511350 82c DEC 51 135 0 134.92508 900.0 3.98360E-01 IB-DF-----P----R---- antimony 135 (Sb-135) + 1094 0 511360 82c DEC 51 136 0 135.93072 900.0 7.50972E-01 IB-DF-----P----R---- antimony 136 (Sb-136) + 1095 0 511370 82c DEC 51 137 0 136.93535 900.0 1.54033E+00 IB-DF-----P----R---- antimony 137 (Sb-137) + 1096 0 511380 82c DEC 51 138 0 137.94099 900.0 1.38629E+00 IB--F----------R---- antimony 138 (Sb-138) + 1097 0 511390 82c DEC 51 139 0 138.94562 900.0 2.31049E+00 IB--F----------R---- antimony 139 (Sb-139) + 1098 0 521210 82c DEC 52 121 0 120.90463 900.0 4.18714E-07 IBADF----------R---- tellurium 121 (Te-121) + 1099 0 521211 82c DEC 52 121 1 120.90463 900.0 5.20944E-08 IBA-F----------R---- tellurium 121m (Te-121m) + 1100 0 521231 82c DEC 52 123 1 122.90381 900.0 6.71342E-08 IBA-F----------R---- tellurium 123m (Te-123m) + 1101 0 521251 82c DEC 52 125 1 124.90399 900.0 1.39765E-07 IBADF----------R---- tellurium 125m (Te-125m) + 1102 0 521270 82c DEC 52 127 0 126.90518 900.0 2.05926E-05 IBADF----------R---- tellurium 127 (Te-127) + 1103 0 521290 82c DEC 52 129 0 128.90637 900.0 1.65984E-04 IBADF----------R---- tellurium 129 (Te-129) + 1104 0 521310 82c DEC 52 131 0 130.90857 900.0 4.62098E-04 IBADF----------R---- tellurium 131 (Te-131) + 1105 0 521311 82c DEC 52 131 1 130.90857 900.0 6.41803E-06 IBADF----------R---- tellurium 131m (Te-131m) + 1106 0 521330 82c DEC 52 133 0 132.91077 900.0 9.27908E-04 IBADF----------R---- tellurium 133 (Te-133) + 1107 0 521331 82c DEC 52 133 1 132.91077 900.0 2.08528E-04 IBADF----------R---- tellurium 133m (Te-133m) + 1108 0 521340 82c DEC 52 134 0 133.91137 900.0 2.76374E-04 IBADF----------R---- tellurium 134 (Te-134) + 1109 0 521350 82c DEC 52 135 0 134.91600 900.0 3.64814E-02 IBADF----------R---- tellurium 135 (Te-135) + 1110 0 521360 82c DEC 52 136 0 135.91962 900.0 3.96084E-02 IB-DF----------R---- tellurium 136 (Te-136) + 1111 0 521370 82c DEC 52 137 0 136.92526 900.0 2.78372E-01 IB-DF-----P----R---- tellurium 137 (Te-137) + 1112 0 521380 82c DEC 52 138 0 137.92888 900.0 4.95105E-01 IB-DF-----P----R---- tellurium 138 (Te-138) + 1113 0 521390 82c DEC 52 139 0 138.93452 900.0 1.38629E+00 IB-DF----------R---- tellurium 139 (Te-139) + 1114 0 521400 82c DEC 52 140 0 139.93915 900.0 2.31049E+00 IB--F----------R---- tellurium 140 (Te-140) + 1115 0 521410 82c DEC 52 141 0 140.94479 900.0 6.93147E+00 IB--F----------R---- tellurium 141 (Te-141) + 1116 0 521420 82c DEC 52 142 0 141.94942 900.0 1.38629E+01 IB--F----------R---- tellurium 142 (Te-142) + 1117 0 531250 82c DEC 53 125 0 124.90500 900.0 1.35087E-07 IBA------------R---- iodine 125 (I-125) + 1118 0 531260 82c DEC 53 126 0 125.90560 900.0 6.18070E-07 IBA-F----------R---- iodine 126 (I-126) + 1119 0 531280 82c DEC 53 128 0 127.90578 900.0 4.62283E-04 IBA-F----------R---- iodine 128 (I-128) + 1120 0 531301 82c DEC 53 130 1 129.90697 900.0 1.30684E-03 IBA-F----------R---- iodine 130m (I-130m) + 1121 0 531320 82c DEC 53 132 0 131.90816 900.0 8.38958E-05 IBADF----------R---- iodine 132 (I-132) + 1122 0 531321 82c DEC 53 132 1 131.90816 900.0 1.39186E-04 IBA-F----------R---- iodine 132m (I-132m) + 1123 0 531330 82c DEC 53 133 0 132.90775 900.0 9.22573E-06 IBADF----------R---- iodine 133 (I-133) + 1124 0 531331 82c DEC 53 133 1 132.90775 900.0 7.70164E-02 IB--F----------R---- iodine 133m (I-133m) + 1125 0 531340 82c DEC 53 134 0 133.90935 900.0 2.20047E-04 IBADF----------R---- iodine 134 (I-134) + 1126 0 531341 82c DEC 53 134 1 133.91036 900.0 3.20901E-03 IB--F----------R---- iodine 134m (I-134m) + 1127 0 531360 82c DEC 53 136 0 135.91458 900.0 8.30116E-03 IBADF----------R---- iodine 136 (I-136) + 1128 0 531361 82c DEC 53 136 1 135.91458 900.0 1.47478E-02 IB-DF----------R---- iodine 136m (I-136m) + 1129 0 531370 82c DEC 53 137 0 136.91820 900.0 2.82802E-02 IB-DF-----P----R---- iodine 137 (I-137) + 1130 0 531380 82c DEC 53 138 0 137.92283 900.0 1.07298E-01 IB-DF-----P----R---- iodine 138 (I-138) + 1131 0 531390 82c DEC 53 139 0 138.92645 900.0 3.01368E-01 IB-DF-----P----R---- iodine 139 (I-139) + 1132 0 531400 82c DEC 53 140 0 139.93108 900.0 8.05985E-01 IB-DF-----P----R---- iodine 140 (I-140) + 1133 0 531410 82c DEC 53 141 0 140.93470 900.0 1.61197E+00 IB-DF-----P----R---- iodine 141 (I-141) + 1134 0 531420 82c DEC 53 142 0 141.94034 900.0 3.46574E+00 IB-DF-----P----R---- iodine 142 (I-142) + 1135 0 531430 82c DEC 53 143 0 142.94497 900.0 6.93147E+00 IB--F-----P----R---- iodine 143 (I-143) + 1136 0 531440 82c DEC 53 144 0 143.94960 900.0 1.38629E+01 IB--F-----P----R---- iodine 144 (I-144) + 1137 0 541260 82c DEC 54 126 0 125.90459 900.0 stable IBAD-----------R---- xenon 126 (Xe-126) + 1138 0 541270 82c DEC 54 127 0 126.90518 900.0 2.20654E-07 IBA------------R---- xenon 127 (Xe-127) + 1139 0 541291 82c DEC 54 129 1 128.90436 900.0 9.03439E-07 IBA-F----------R---- xenon 129m (Xe-129m) + 1140 0 541311 82c DEC 54 131 1 130.90555 900.0 6.70666E-07 IBADF----------R---- xenon 131m (Xe-131m) + 1141 0 541321 82c DEC 54 132 1 131.90413 900.0 8.26159E+01 IB--F----------R---- xenon 132m (Xe-132m) + 1142 0 541331 82c DEC 54 133 1 132.90573 900.0 3.64993E-06 IBADF----------R---- xenon 133m (Xe-133m) + 1143 0 541341 82c DEC 54 134 1 133.90532 900.0 2.39016E+00 IBADF----------R---- xenon 134m (Xe-134m) + 1144 0 541351 82c DEC 54 135 1 134.90692 900.0 7.55062E-04 IBADF----------R---- xenon 135m (Xe-135m) + 1145 0 541370 82c DEC 54 137 0 136.91114 900.0 3.02579E-03 IBADF----------R---- xenon 137 (Xe-137) + 1146 0 541380 82c DEC 54 138 0 137.91375 900.0 8.20487E-04 IBADF----------R---- xenon 138 (Xe-138) + 1147 0 541390 82c DEC 54 139 0 138.91838 900.0 1.74640E-02 IBADF----------R---- xenon 139 (Xe-139) + 1148 0 541400 82c DEC 54 140 0 139.92200 900.0 5.09667E-02 IB-DF----------R---- xenon 140 (Xe-140) + 1149 0 541410 82c DEC 54 141 0 140.92663 900.0 4.00663E-01 IB-DF-----P----R---- xenon 141 (Xe-141) + 1150 0 541420 82c DEC 54 142 0 141.92925 900.0 5.68153E-01 IB-DF-----P----R---- xenon 142 (Xe-142) + 1151 0 541430 82c DEC 54 143 0 142.93489 900.0 1.35645E+00 IB-DF-----P----R---- xenon 143 (Xe-143) + 1152 0 541440 82c DEC 54 144 0 143.93851 900.0 1.78646E+00 IB-DF-----P----R---- xenon 144 (Xe-144) + 1153 0 541450 82c DEC 54 145 0 144.94415 900.0 3.68695E+00 IB--F-----P----R---- xenon 145 (Xe-145) + 1154 0 541460 82c DEC 54 146 0 145.94777 900.0 4.74758E+00 IB--F-----P----R---- xenon 146 (Xe-146) + 1155 0 541470 82c DEC 54 147 0 146.95341 900.0 5.33190E+00 IB--F-----P----R---- xenon 147 (Xe-147) + 1156 0 551310 82c DEC 55 131 0 130.90555 900.0 8.27919E-07 IB--F----------R---- cesium 131 (Cs-131) + 1157 0 551320 82c DEC 55 132 0 131.90614 900.0 1.22857E-06 IBA-F----------R---- cesium 132 (Cs-132) + 1158 0 551341 82c DEC 55 134 1 133.90633 900.0 6.62108E-05 IBA-F----------R---- cesium 134m (Cs-134m) + 1159 0 551351 82c DEC 55 135 1 134.90591 900.0 2.17971E-04 IBA-F----------R---- cesium 135m (Cs-135m) + 1160 0 551361 82c DEC 55 136 1 135.90752 900.0 3.64814E-02 IBA-F----------R---- cesium 136m (Cs-136m) + 1161 0 551380 82c DEC 55 138 0 137.91073 900.0 3.45778E-04 IBADF----------R---- cesium 138 (Cs-138) + 1162 0 551381 82c DEC 55 138 1 137.91073 900.0 3.96992E-03 IBA-F----------R---- cesium 138m (Cs-138m) + 1163 0 551390 82c DEC 55 139 0 138.91334 900.0 1.24622E-03 IBADF----------R---- cesium 139 (Cs-139) + 1164 0 551400 82c DEC 55 140 0 139.91696 900.0 1.08304E-02 IBADF----------R---- cesium 140 (Cs-140) + 1165 0 551410 82c DEC 55 141 0 140.91957 900.0 2.79045E-02 IB-DF----------R---- cesium 141 (Cs-141) + 1166 0 551420 82c DEC 55 142 0 141.92420 900.0 4.11608E-01 IB-DF----------R---- cesium 142 (Cs-142) + 1167 0 551430 82c DEC 55 143 0 142.92783 900.0 3.87017E-01 IB-DF-----P----R---- cesium 143 (Cs-143) + 1168 0 551440 82c DEC 55 144 0 143.93246 900.0 6.97331E-01 IB-DF-----P----R---- cesium 144 (Cs-144) + 1169 0 551441 82c DEC 55 144 1 143.93246 900.0 6.93147E-01 IB-DF----------R---- cesium 144m (Cs-144m) + 1170 0 551450 82c DEC 55 145 0 144.93507 900.0 1.16691E+00 IB-DF-----P----R---- cesium 145 (Cs-145) + 1171 0 551460 82c DEC 55 146 0 145.94071 900.0 2.14597E+00 IB-DF-----P----R---- cesium 146 (Cs-146) + 1172 0 551470 82c DEC 55 147 0 146.94433 900.0 3.08065E+00 IB-DF-----P----R---- cesium 147 (Cs-147) + 1173 0 551480 82c DEC 55 148 0 147.94896 900.0 4.74758E+00 IB--F-----P----R---- cesium 148 (Cs-148) + 1174 0 551490 82c DEC 55 149 0 148.95258 900.0 4.62098E+00 IB--F----------R---- cesium 149 (Cs-149) + 1175 0 551500 82c DEC 55 150 0 149.95822 900.0 6.93147E+00 IB--F----------R---- cesium 150 (Cs-150) + 1176 0 561320 82c DEC 56 132 0 131.90514 900.0 stable IBAD-----------R---- barium 132 (Ba-132) + 1177 0 561330 82c DEC 56 133 0 132.90573 900.0 2.08416E-09 IBADF----------R---- barium 133 (Ba-133) + 1178 0 561331 82c DEC 56 133 1 132.90573 900.0 5.04034E-06 IB--F----------R---- barium 133m (Ba-133m) + 1179 0 561351 82c DEC 56 135 1 134.90591 900.0 6.70874E-06 IBA-F----------R---- barium 135m (Ba-135m) + 1180 0 561361 82c DEC 56 136 1 135.90449 900.0 2.24756E+00 IBA-F----------R---- barium 136m (Ba-136m) + 1181 0 561371 82c DEC 56 137 1 136.90610 900.0 4.52682E-03 IBADF----------R---- barium 137m (Ba-137m) + 1182 0 561390 82c DEC 56 139 0 138.90930 900.0 1.39086E-04 IBADF----------R---- barium 139 (Ba-139) + 1183 0 561410 82c DEC 56 141 0 140.91453 900.0 6.32318E-04 IBADF----------R---- barium 141 (Ba-141) + 1184 0 561420 82c DEC 56 142 0 141.91613 900.0 1.08985E-03 IBADF----------R---- barium 142 (Ba-142) + 1185 0 561430 82c DEC 56 143 0 142.92077 900.0 4.78033E-02 IB-DF----------R---- barium 143 (Ba-143) + 1186 0 561440 82c DEC 56 144 0 143.92338 900.0 6.02737E-02 IB-DF----------R---- barium 144 (Ba-144) + 1187 0 561450 82c DEC 56 145 0 144.92801 900.0 1.60823E-01 IB-DF----------R---- barium 145 (Ba-145) + 1188 0 561460 82c DEC 56 146 0 145.93062 900.0 3.12228E-01 IB-DF----------R---- barium 146 (Ba-146) + 1189 0 561470 82c DEC 56 147 0 146.93525 900.0 7.75332E-01 IB-DF----------R---- barium 147 (Ba-147) + 1190 0 561480 82c DEC 56 148 0 147.93786 900.0 1.13259E+00 IB-DF-----P----R---- barium 148 (Ba-148) + 1191 0 561490 82c DEC 56 149 0 148.94250 900.0 2.01496E+00 IB-DF-----P----R---- barium 149 (Ba-149) + 1192 0 561500 82c DEC 56 150 0 149.94612 900.0 2.31049E+00 IB-DF----------R---- barium 150 (Ba-150) + 1193 0 561510 82c DEC 56 151 0 150.95075 900.0 3.46574E+00 IB--F----------R---- barium 151 (Ba-151) + 1194 0 561520 82c DEC 56 152 0 151.95437 900.0 6.93147E+00 IB--F----------R---- barium 152 (Ba-152) + 1195 0 561530 82c DEC 56 153 0 152.96001 900.0 8.66434E+00 IB--F----------R---- barium 153 (Ba-153) + 1196 0 571360 82c DEC 57 136 0 135.90752 900.0 1.17046E-03 IBADF----------R---- lanthanum 136 (La-136) + 1197 0 571361 82c DEC 57 136 1 135.90752 900.0 6.08024E+00 IB--F----------R---- lanthanum 136m (La-136m) + 1198 0 571370 82c DEC 57 137 0 136.90610 900.0 3.66074E-13 IBA-F----------R---- lanthanum 137 (La-137) + 1199 0 571410 82c DEC 57 141 0 140.91050 900.0 4.91176E-05 IBADF----------R---- lanthanum 141 (La-141) + 1200 0 571420 82c DEC 57 142 0 141.91412 900.0 1.26811E-04 IBADF----------R---- lanthanum 142 (La-142) + 1201 0 571430 82c DEC 57 143 0 142.91572 900.0 8.17005E-04 IBADF----------R---- lanthanum 143 (La-143) + 1202 0 571440 82c DEC 57 144 0 143.91934 900.0 1.69889E-02 IBADF----------R---- lanthanum 144 (La-144) + 1203 0 571450 82c DEC 57 145 0 144.92196 900.0 2.79495E-02 IB-DF----------R---- lanthanum 145 (La-145) + 1204 0 571460 82c DEC 57 146 0 145.92558 900.0 1.10550E-01 IB-DF----------R---- lanthanum 146 (La-146) + 1205 0 571461 82c DEC 57 146 1 145.92558 900.0 6.93147E-02 IB--F----------R---- lanthanum 146m (La-146m) + 1206 0 571470 82c DEC 57 147 0 146.92819 900.0 1.70726E-01 IB-DF----------R---- lanthanum 147 (La-147) + 1207 0 571480 82c DEC 57 148 0 147.93181 900.0 5.50117E-01 IB-DF----------R---- lanthanum 148 (La-148) + 1208 0 571490 82c DEC 57 149 0 148.93443 900.0 6.60140E-01 IB-DF-----P----R---- lanthanum 149 (La-149) + 1209 0 571500 82c DEC 57 150 0 149.93906 900.0 1.35911E+00 IB-DF-----P----R---- lanthanum 150 (La-150) + 1210 0 571510 82c DEC 57 151 0 150.94167 900.0 2.31049E+00 IB-DF----------R---- lanthanum 151 (La-151) + 1211 0 571520 82c DEC 57 152 0 151.94428 900.0 2.47553E+00 IB-DF-----P----R---- lanthanum 152 (La-152) + 1212 0 571530 82c DEC 57 153 0 152.94992 900.0 4.62098E+00 IB-DF----------R---- lanthanum 153 (La-153) + 1213 0 571540 82c DEC 57 154 0 153.95455 900.0 6.93147E+00 IB--F----------R---- lanthanum 154 (La-154) + 1214 0 571550 82c DEC 57 155 0 154.95817 900.0 1.15525E+01 IB--F----------R---- lanthanum 155 (La-155) + 1215 0 581380 82c DEC 58 138 0 137.90568 900.0 stable IB-DF----------R---- cerium 138 (Ce-138) + 1216 0 581381 82c DEC 58 138 1 137.90568 900.0 8.01326E+01 IB--F----------R---- cerium 138m (Ce-138m) + 1217 0 581390 82c DEC 58 139 0 138.90628 900.0 5.82819E-08 IBADF----------R---- cerium 139 (Ce-139) + 1218 0 581391 82c DEC 58 139 1 138.90628 900.0 1.23556E-02 IB-DF----------R---- cerium 139m (Ce-139m) + 1219 0 581450 82c DEC 58 145 0 144.91691 900.0 3.91609E-03 IBADF----------R---- cerium 145 (Ce-145) + 1220 0 581460 82c DEC 58 146 0 145.91852 900.0 8.54471E-04 IBADF----------R---- cerium 146 (Ce-146) + 1221 0 581470 82c DEC 58 147 0 146.92214 900.0 1.21605E-02 IBADF----------R---- cerium 147 (Ce-147) + 1222 0 581480 82c DEC 58 148 0 147.92475 900.0 1.23776E-02 IBADF----------R---- cerium 148 (Ce-148) + 1223 0 581490 82c DEC 58 149 0 148.92837 900.0 1.30782E-01 IBADF----------R---- cerium 149 (Ce-149) + 1224 0 581500 82c DEC 58 150 0 149.92998 900.0 1.73287E-01 IB-DF----------R---- cerium 150 (Ce-150) + 1225 0 581510 82c DEC 58 151 0 150.93360 900.0 6.79556E-01 IB-DF----------R---- cerium 151 (Ce-151) + 1226 0 581520 82c DEC 58 152 0 151.93621 900.0 6.30134E-01 IB-DF----------R---- cerium 152 (Ce-152) + 1227 0 581530 82c DEC 58 153 0 152.93883 900.0 4.62098E-01 IB-DF-----P----R---- cerium 153 (Ce-153) + 1228 0 581540 82c DEC 58 154 0 153.94043 900.0 3.46574E-01 IB-DF-----P----R---- cerium 154 (Ce-154) + 1229 0 581550 82c DEC 58 155 0 154.94809 900.0 3.46574E+00 IB-DF----------R---- cerium 155 (Ce-155) + 1230 0 581560 82c DEC 58 156 0 155.95171 900.0 4.62098E+00 IB--F----------R---- cerium 156 (Ce-156) + 1231 0 581570 82c DEC 58 157 0 156.95634 900.0 1.38629E+01 IB--F----------R---- cerium 157 (Ce-157) + 1232 0 591390 82c DEC 59 139 0 138.90930 900.0 4.36601E-05 IBA------------R---- praseodymium 139 (Pr-139) + 1233 0 591400 82c DEC 59 140 0 139.90889 900.0 3.40780E-03 IBA------------R---- praseodymium 140 (Pr-140) + 1234 0 591421 82c DEC 59 142 1 141.91008 900.0 7.91264E-04 IBA-F----------R---- praseodymium 142m (Pr-142m) + 1235 0 591440 82c DEC 59 144 0 143.91329 900.0 6.68158E-04 IBADF----------R---- praseodymium 144 (Pr-144) + 1236 0 591441 82c DEC 59 144 1 143.91329 900.0 1.60451E-03 IBADF----------R---- praseodymium 144m (Pr-144m) + 1237 0 591450 82c DEC 59 145 0 144.91490 900.0 3.21759E-05 IBADF----------R---- praseodymium 145 (Pr-145) + 1238 0 591460 82c DEC 59 146 0 145.91751 900.0 4.78362E-04 IBADF----------R---- praseodymium 146 (Pr-146) + 1239 0 591470 82c DEC 59 147 0 146.91911 900.0 8.62123E-04 IBADF----------R---- praseodymium 147 (Pr-147) + 1240 0 591480 82c DEC 59 148 0 147.92173 900.0 5.04474E-03 IBADF----------R---- praseodymium 148 (Pr-148) + 1241 0 591481 82c DEC 59 148 1 147.92173 900.0 5.71904E-03 IB--F----------R---- praseodymium 148m (Pr-148m) + 1242 0 591490 82c DEC 59 149 0 148.92333 900.0 5.11170E-03 IBADF----------R---- praseodymium 149 (Pr-149) + 1243 0 591500 82c DEC 59 150 0 149.92695 900.0 1.13631E-01 IBADF----------R---- praseodymium 150 (Pr-150) + 1244 0 591510 82c DEC 59 151 0 150.92856 900.0 3.66745E-02 IB-DF----------R---- praseodymium 151 (Pr-151) + 1245 0 591520 82c DEC 59 152 0 151.93117 900.0 1.90950E-01 IB-DF----------R---- praseodymium 152 (Pr-152) + 1246 0 591530 82c DEC 59 153 0 152.93378 900.0 1.61950E-01 IB-DF----------R---- praseodymium 153 (Pr-153) + 1247 0 591540 82c DEC 59 154 0 153.93740 900.0 3.01368E-01 IB-DF----------R---- praseodymium 154 (Pr-154) + 1248 0 591550 82c DEC 59 155 0 154.94002 900.0 6.93147E-01 IB-DF----------R---- praseodymium 155 (Pr-155) + 1249 0 591560 82c DEC 59 156 0 155.94263 900.0 1.38629E+00 IB-DF-----P----R---- praseodymium 156 (Pr-156) + 1250 0 591570 82c DEC 59 157 0 156.94524 900.0 2.31049E+00 IB-DF-----P----R---- praseodymium 157 (Pr-157) + 1251 0 591580 82c DEC 59 158 0 157.95189 900.0 3.46574E+00 IB--F----------R---- praseodymium 158 (Pr-158) + 1252 0 591590 82c DEC 59 159 0 158.95551 900.0 6.93147E+00 IB--F----------R---- praseodymium 159 (Pr-159) + 1253 0 601420 82c DEC 60 142 0 141.90807 900.0 stable IBAD-----------R---- neodymium 142 (Nd-142) + 1254 0 601430 82c DEC 60 143 0 142.90967 900.0 stable IBAD-----------R---- neodymium 143 (Nd-143) + 1255 0 601490 82c DEC 60 149 0 148.92030 900.0 1.11424E-04 IBADF----------R---- neodymium 149 (Nd-149) + 1256 0 601510 82c DEC 60 151 0 150.92351 900.0 9.28654E-04 IBADF----------R---- neodymium 151 (Nd-151) + 1257 0 601520 82c DEC 60 152 0 151.92512 900.0 1.01337E-03 IB-DF----------R---- neodymium 152 (Nd-152) + 1258 0 601530 82c DEC 60 153 0 152.92773 900.0 2.19350E-02 IB-DF----------R---- neodymium 153 (Nd-153) + 1259 0 601540 82c DEC 60 154 0 153.92933 900.0 2.67624E-02 IB-DF----------R---- neodymium 154 (Nd-154) + 1260 0 601550 82c DEC 60 155 0 154.93296 900.0 7.78817E-02 IB-DF----------R---- neodymium 155 (Nd-155) + 1261 0 601560 82c DEC 60 156 0 155.93456 900.0 1.26256E-01 IB-DF----------R---- neodymium 156 (Nd-156) + 1262 0 601570 82c DEC 60 157 0 156.93717 900.0 2.77259E-01 IB-DF----------R---- neodymium 157 (Nd-157) + 1263 0 601580 82c DEC 60 158 0 157.93979 900.0 9.90210E-01 IB-DF-----P----R---- neodymium 158 (Nd-158) + 1264 0 601590 82c DEC 60 159 0 158.94442 900.0 1.38629E+00 IB-DF-----P----R---- neodymium 159 (Nd-159) + 1265 0 601600 82c DEC 60 160 0 159.94703 900.0 2.31049E+00 IB--F-----P----R---- neodymium 160 (Nd-160) + 1266 0 601610 82c DEC 60 161 0 160.95368 900.0 3.46574E+00 IB--F----------R---- neodymium 161 (Nd-161) + 1267 0 611450 82c DEC 61 145 0 144.91288 900.0 1.24093E-09 IBA------------R---- promethium 145 (Pm-145) + 1268 0 611460 82c DEC 61 146 0 145.91448 900.0 3.97155E-09 IBA-F----------R---- promethium 146 (Pm-146) + 1269 0 611500 82c DEC 61 150 0 149.92090 900.0 7.13643E-05 IBA-F----------R---- promethium 150 (Pm-150) + 1270 0 611520 82c DEC 61 152 0 151.92310 900.0 2.80399E-03 IBADF----------R---- promethium 152 (Pm-152) + 1271 0 611521 82c DEC 61 152 1 151.92310 900.0 1.53623E-03 IB--F----------R---- promethium 152m (Pm-152m) + 1272 1 611522 82c DEC 61 152 2 151.92310 900.0 8.02254E-04 -B--F----------R---- promethium 152m (Pm-152m) + 1273 0 611530 82c DEC 61 153 0 152.92370 900.0 2.20047E-03 IBADF----------R---- promethium 153 (Pm-153) + 1274 0 611540 82c DEC 61 154 0 153.92631 900.0 6.67772E-03 IBADF----------R---- promethium 154 (Pm-154) + 1275 0 611541 82c DEC 61 154 1 153.92631 900.0 4.31062E-03 IB--F----------R---- promethium 154m (Pm-154m) + 1276 0 611550 82c DEC 61 155 0 154.92791 900.0 1.67023E-02 IB-DF----------R---- promethium 155 (Pm-155) + 1277 0 611560 82c DEC 61 156 0 155.93153 900.0 2.59606E-02 IB-DF----------R---- promethium 156 (Pm-156) + 1278 0 611570 82c DEC 61 157 0 156.93314 900.0 6.56389E-02 IB-DF----------R---- promethium 157 (Pm-157) + 1279 0 611580 82c DEC 61 158 0 157.93676 900.0 1.44406E-01 IB-DF----------R---- promethium 158 (Pm-158) + 1280 0 611590 82c DEC 61 159 0 158.93836 900.0 2.31049E-01 IB-DF-----P----R---- promethium 159 (Pm-159) + 1281 0 611600 82c DEC 61 160 0 159.94199 900.0 3.46574E-01 IB-DF-----P----R---- promethium 160 (Pm-160) + 1282 0 611610 82c DEC 61 161 0 160.94561 900.0 9.90210E-01 IB-DF----------R---- promethium 161 (Pm-161) + 1283 0 611620 82c DEC 61 162 0 161.95024 900.0 1.38629E+00 IB--F----------R---- promethium 162 (Pm-162) + 1284 0 611630 82c DEC 61 163 0 162.95386 900.0 3.46574E+00 IB--F----------R---- promethium 163 (Pm-163) + 1285 0 621460 82c DEC 62 146 0 145.91347 900.0 2.19645E-16 IBAD-----------R---- samarium 146 (Sm-146) + 1286 0 621531 82c DEC 62 153 1 152.92168 900.0 6.53912E+01 IB--F----------R---- samarium 153m (Sm-153m) + 1287 0 621550 82c DEC 62 155 0 154.92489 900.0 5.18047E-04 IBADF----------R---- samarium 155 (Sm-155) + 1288 0 621560 82c DEC 62 156 0 155.92548 900.0 2.04831E-05 IBADF----------R---- samarium 156 (Sm-156) + 1289 0 621570 82c DEC 62 157 0 156.92810 900.0 1.43866E-03 IBADF----------R---- samarium 157 (Sm-157) + 1290 0 621580 82c DEC 62 158 0 157.92970 900.0 2.17971E-03 IB-DF----------R---- samarium 158 (Sm-158) + 1291 0 621590 82c DEC 62 159 0 158.93332 900.0 6.09628E-02 IB-DF----------R---- samarium 159 (Sm-159) + 1292 0 621600 82c DEC 62 160 0 159.93493 900.0 7.22028E-02 IB-DF----------R---- samarium 160 (Sm-160) + 1293 0 621610 82c DEC 62 161 0 160.93855 900.0 1.44406E-01 IB-DF----------R---- samarium 161 (Sm-161) + 1294 0 621620 82c DEC 62 162 0 161.94116 900.0 2.88811E-01 IB-DF----------R---- samarium 162 (Sm-162) + 1295 0 621630 82c DEC 62 163 0 162.94579 900.0 6.93147E-01 IB-DF----------R---- samarium 163 (Sm-163) + 1296 0 621640 82c DEC 62 164 0 163.94840 900.0 1.38629E+00 IB--F----------R---- samarium 164 (Sm-164) + 1297 0 621650 82c DEC 62 165 0 164.95303 900.0 3.46574E+00 IB--F----------R---- samarium 165 (Sm-165) + 1298 0 631490 82c DEC 63 149 0 148.91829 900.0 8.61712E-08 IBA------------R---- europium 149 (Eu-149) + 1299 0 631500 82c DEC 63 150 0 149.91989 900.0 6.04108E-10 IBA------------R---- europium 150 (Eu-150) + 1300 0 631521 82c DEC 63 152 1 151.92209 900.0 2.07591E-05 IB--F----------R---- europium 152m (Eu-152m) + 1301 1 631522 82c DEC 63 152 2 151.92209 900.0 1.20338E-04 -B--F----------R---- europium 152m (Eu-152m) + 1302 0 631541 82c DEC 63 154 1 153.92328 900.0 2.48975E-04 IBA-F----------R---- europium 154m (Eu-154m) + 1303 0 631580 82c DEC 63 158 0 157.92768 900.0 2.51687E-04 IBADF----------R---- europium 158 (Eu-158) + 1304 0 631590 82c DEC 63 159 0 158.92929 900.0 6.38257E-04 IBADF----------R---- europium 159 (Eu-159) + 1305 0 631600 82c DEC 63 160 0 159.93190 900.0 1.82407E-02 IBADF----------R---- europium 160 (Eu-160) + 1306 0 631610 82c DEC 63 161 0 160.93350 900.0 2.66595E-02 IB-DF----------R---- europium 161 (Eu-161) + 1307 0 631620 82c DEC 63 162 0 161.93713 900.0 6.53912E-02 IB-DF----------R---- europium 162 (Eu-162) + 1308 0 631630 82c DEC 63 163 0 162.93873 900.0 1.15525E-01 IB-DF----------R---- europium 163 (Eu-163) + 1309 0 631640 82c DEC 63 164 0 163.94336 900.0 3.46574E-01 IB-DF----------R---- europium 164 (Eu-164) + 1310 0 631650 82c DEC 63 165 0 164.94597 900.0 6.93147E-01 IB-DF----------R---- europium 165 (Eu-165) + 1311 0 631660 82c DEC 63 166 0 165.94960 900.0 1.73287E+00 IB--F----------R---- europium 166 (Eu-166) + 1312 0 631670 82c DEC 63 167 0 166.95322 900.0 3.46574E+00 IB--F----------R---- europium 167 (Eu-167) + 1313 0 641500 82c DEC 64 150 0 149.91888 900.0 1.20684E-14 IBA------------R---- gadolinium 150 (Gd-150) + 1314 0 641510 82c DEC 64 151 0 150.92049 900.0 6.46979E-08 IBA------------R---- gadolinium 151 (Gd-151) + 1315 0 641530 82c DEC 64 153 0 152.92168 900.0 3.33577E-08 IBA------------R---- gadolinium 153 (Gd-153) + 1316 0 641551 82c DEC 64 155 1 154.92287 900.0 2.16608E+01 IB--F----------R---- gadolinium 155m (Gd-155m) + 1317 0 641590 82c DEC 64 159 0 158.92626 900.0 1.04194E-05 IBADF----------R---- gadolinium 159 (Gd-159) + 1318 0 641610 82c DEC 64 161 0 160.92947 900.0 3.15641E-03 IBADF----------R---- gadolinium 161 (Gd-161) + 1319 0 641620 82c DEC 64 162 0 161.93107 900.0 1.37529E-03 IB-DF----------R---- gadolinium 162 (Gd-162) + 1320 0 641630 82c DEC 64 163 0 162.93369 900.0 1.01933E-02 IB-DF----------R---- gadolinium 163 (Gd-163) + 1321 0 641640 82c DEC 64 164 0 163.93630 900.0 1.54033E-02 IB-DF----------R---- gadolinium 164 (Gd-164) + 1322 0 641650 82c DEC 64 165 0 164.93891 900.0 6.72958E-02 IB-DF----------R---- gadolinium 165 (Gd-165) + 1323 0 641660 82c DEC 64 166 0 165.94153 900.0 1.44406E-01 IB-DF----------R---- gadolinium 166 (Gd-166) + 1324 0 641670 82c DEC 64 167 0 166.94515 900.0 2.31049E-01 IB-DF----------R---- gadolinium 167 (Gd-167) + 1325 0 641680 82c DEC 64 168 0 167.94877 900.0 2.31049E+00 IB--F----------R---- gadolinium 168 (Gd-168) + 1326 0 641690 82c DEC 64 169 0 168.95239 900.0 6.93147E-01 IB--F----------R---- gadolinium 169 (Gd-169) + 1327 0 651560 82c DEC 65 156 0 155.92447 900.0 1.55175E-06 IB-DF----------R---- terbium 156 (Tb-156) + 1328 0 651561 82c DEC 65 156 1 155.92447 900.0 7.89102E-06 IB--F----------R---- terbium 156m (Tb-156m) + 1329 1 651562 82c DEC 65 156 2 155.92447 900.0 3.77531E-05 -B--F----------R---- terbium 156m (Tb-156m) + 1330 0 651570 82c DEC 65 157 0 156.92406 900.0 2.21864E-10 IBA-F----------R---- terbium 157 (Tb-157) + 1331 0 651580 82c DEC 65 158 0 157.92567 900.0 1.22028E-10 IBADF----------R---- terbium 158 (Tb-158) + 1332 0 651581 82c DEC 65 158 1 157.92567 900.0 6.41803E-02 IB--F----------R---- terbium 158m (Tb-158m) + 1333 0 651610 82c DEC 65 161 0 160.92745 900.0 1.16437E-06 IBADF----------R---- terbium 161 (Tb-161) + 1334 0 651620 82c DEC 65 162 0 161.92906 900.0 1.52006E-03 IBADF----------R---- terbium 162 (Tb-162) + 1335 0 651630 82c DEC 65 163 0 162.93066 900.0 5.92433E-04 IBADF----------R---- terbium 163 (Tb-163) + 1336 0 651640 82c DEC 65 164 0 163.93327 900.0 3.85082E-03 IBADF----------R---- terbium 164 (Tb-164) + 1337 0 651650 82c DEC 65 165 0 164.93488 900.0 5.47510E-03 IB-DF----------R---- terbium 165 (Tb-165) + 1338 0 651660 82c DEC 65 166 0 165.93850 900.0 2.70761E-02 IB-DF----------R---- terbium 166 (Tb-166) + 1339 0 651670 82c DEC 65 167 0 166.94010 900.0 3.64814E-02 IB-DF----------R---- terbium 167 (Tb-167) + 1340 0 651680 82c DEC 65 168 0 167.94373 900.0 8.45301E-02 IB-DF----------R---- terbium 168 (Tb-168) + 1341 0 651690 82c DEC 65 169 0 168.94634 900.0 3.46574E-01 IB-DF----------R---- terbium 169 (Tb-169) + 1342 0 651700 82c DEC 65 170 0 169.94996 900.0 2.31049E-01 IB--F----------R---- terbium 170 (Tb-170) + 1343 0 651710 82c DEC 65 171 0 170.95358 900.0 1.38629E+00 IB--F----------R---- terbium 171 (Tb-171) + 1344 0 661580 82c DEC 66 158 0 157.92466 900.0 stable IB-DF----------R---- dysprosium 158 (Dy-158) + 1345 0 661590 82c DEC 66 159 0 158.92626 900.0 5.55576E-08 IBA-F----------R---- dysprosium 159 (Dy-159) + 1346 0 661650 82c DEC 66 165 0 164.93185 900.0 8.24940E-05 IBADF----------R---- dysprosium 165 (Dy-165) + 1347 0 661651 82c DEC 66 165 1 164.93185 900.0 9.19050E-03 IBA-F----------R---- dysprosium 165m (Dy-165m) + 1348 0 661660 82c DEC 66 166 0 165.93245 900.0 2.35957E-06 IBADF----------R---- dysprosium 166 (Dy-166) + 1349 0 661670 82c DEC 66 167 0 166.93607 900.0 1.86330E-03 IBADF----------R---- dysprosium 167 (Dy-167) + 1350 0 661680 82c DEC 66 168 0 167.93667 900.0 1.32787E-03 IB-DF----------R---- dysprosium 168 (Dy-168) + 1351 0 661690 82c DEC 66 169 0 168.94029 900.0 1.77730E-02 IB-DF----------R---- dysprosium 169 (Dy-169) + 1352 0 661700 82c DEC 66 170 0 169.94290 900.0 2.31049E-02 IB-DF----------R---- dysprosium 170 (Dy-170) + 1353 0 661710 82c DEC 66 171 0 170.94652 900.0 1.15525E-01 IB-DF----------R---- dysprosium 171 (Dy-171) + 1354 0 661720 82c DEC 66 172 0 171.94913 900.0 2.31049E-01 IB--F----------R---- dysprosium 172 (Dy-172) + 1355 0 661730 82c DEC 66 173 0 172.95276 900.0 3.46574E-01 IB--F----------R---- dysprosium 173 (Dy-173) + 1356 0 671610 82c DEC 67 161 0 160.92745 900.0 7.76375E-05 IB-DF----------R---- holmium 161 (Ho-161) + 1357 0 671611 82c DEC 67 161 1 160.92745 900.0 1.02385E-01 IB--F----------R---- holmium 161m (Ho-161m) + 1358 0 671620 82c DEC 67 162 0 161.92906 900.0 7.70164E-04 IBADF----------R---- holmium 162 (Ho-162) + 1359 0 671621 82c DEC 67 162 1 161.92906 900.0 1.72425E-04 IB--F----------R---- holmium 162m (Ho-162m) + 1360 0 671630 82c DEC 67 163 0 162.92864 900.0 4.80625E-12 IBADF----------R---- holmium 163 (Ho-163) + 1361 0 671631 82c DEC 67 163 1 162.92864 900.0 6.30134E-01 IB-DF----------R---- holmium 163m (Ho-163m) + 1362 0 671640 82c DEC 67 164 0 163.93025 900.0 4.03932E-04 IBADF----------R---- holmium 164 (Ho-164) + 1363 0 671641 82c DEC 67 164 1 163.93025 900.0 3.07246E-04 IB--F----------R---- holmium 164m (Ho-164m) + 1364 0 671660 82c DEC 67 166 0 165.93245 900.0 7.18570E-06 IBADF----------R---- holmium 166 (Ho-166) + 1365 0 671661 82c DEC 67 166 1 165.93245 900.0 1.93866E-11 IBA-F----------R---- holmium 166m (Ho-166m) + 1366 0 671670 82c DEC 67 167 0 166.93304 900.0 6.21100E-05 IBADF----------R---- holmium 167 (Ho-167) + 1367 0 671680 82c DEC 67 168 0 167.93566 900.0 3.86370E-03 IBADF----------R---- holmium 168 (Ho-168) + 1368 0 671681 82c DEC 67 168 1 167.93566 900.0 5.25112E-03 IB--F----------R---- holmium 168m (Ho-168m) + 1369 0 671690 82c DEC 67 169 0 168.93726 900.0 2.45797E-03 IBADF----------R---- holmium 169 (Ho-169) + 1370 0 671700 82c DEC 67 170 0 169.93987 900.0 4.15556E-03 IBA-F----------R---- holmium 170 (Ho-170) + 1371 0 671701 82c DEC 67 170 1 169.93987 900.0 1.61197E-02 IB-DF----------R---- holmium 170m (Ho-170m) + 1372 0 671710 82c DEC 67 171 0 170.94148 900.0 1.30782E-02 IB-DF----------R---- holmium 171 (Ho-171) + 1373 0 671720 82c DEC 67 172 0 171.94510 900.0 2.77259E-02 IB-DF----------R---- holmium 172 (Ho-172) + 1374 0 671730 82c DEC 67 173 0 172.94771 900.0 6.93147E-02 IB-DF----------R---- holmium 173 (Ho-173) + 1375 0 671740 82c DEC 67 174 0 173.95133 900.0 8.66434E-02 IB--F----------R---- holmium 174 (Ho-174) + 1376 0 671750 82c DEC 67 175 0 174.95395 900.0 1.38629E-01 IB--F----------R---- holmium 175 (Ho-175) + 1377 0 681620 82c DEC 68 162 0 161.92906 900.0 1.56889E-22 IBA------------R---- erbium 162 (Er-162) + 1378 0 681630 82c DEC 68 163 0 162.92965 900.0 1.54033E-04 IBA------------R---- erbium 163 (Er-163) + 1379 0 681650 82c DEC 68 165 0 164.93084 900.0 1.85850E-05 IBA-F----------R---- erbium 165 (Er-165) + 1380 0 681671 82c DEC 68 167 1 166.93203 900.0 3.05351E-01 IBADF----------R---- erbium 167m (Er-167m) + 1381 0 681690 82c DEC 68 169 0 168.93423 900.0 8.55281E-07 IBADF----------R---- erbium 169 (Er-169) + 1382 0 681710 82c DEC 68 171 0 170.93845 900.0 2.56175E-05 IBADF----------R---- erbium 171 (Er-171) + 1383 0 681720 82c DEC 68 172 0 171.93905 900.0 3.90549E-06 IB-DF----------R---- erbium 172 (Er-172) + 1384 0 681730 82c DEC 68 173 0 172.94267 900.0 8.25175E-03 IB-DF----------R---- erbium 173 (Er-173) + 1385 0 681740 82c DEC 68 174 0 173.94427 900.0 3.61014E-03 IB-DF----------R---- erbium 174 (Er-174) + 1386 0 681750 82c DEC 68 175 0 174.94790 900.0 9.62704E-03 IB-DF----------R---- erbium 175 (Er-175) + 1387 0 681760 82c DEC 68 176 0 175.95051 900.0 3.46574E-02 IB--F----------R---- erbium 176 (Er-176) + 1388 0 681770 82c DEC 68 177 0 176.95413 900.0 2.31049E-01 IB--F----------R---- erbium 177 (Er-177) + 1389 0 691660 82c DEC 69 166 0 165.93346 900.0 2.50053E-05 IB--F----------R---- thulium 166 (Tm-166) + 1390 0 691670 82c DEC 69 167 0 166.93304 900.0 8.67301E-07 IB--F----------R---- thulium 167 (Tm-167) + 1391 0 691680 82c DEC 69 168 0 167.93465 900.0 8.91393E-08 IB--F----------R---- thulium 168 (Tm-168) + 1392 0 691690 82c DEC 69 169 0 168.93423 900.0 stable IB-DF----------R---- thulium 169 (Tm-169) + 1393 0 691700 82c DEC 69 170 0 169.93584 900.0 6.23839E-08 IB--F----------R---- thulium 170 (Tm-170) + 1394 0 691710 82c DEC 69 171 0 170.93643 900.0 1.14608E-08 IB-DF----------R---- thulium 171 (Tm-171) + 1395 0 691720 82c DEC 69 172 0 171.93804 900.0 3.02737E-06 IBADF----------R---- thulium 172 (Tm-172) + 1396 0 691730 82c DEC 69 173 0 172.93964 900.0 2.33666E-05 IBADF----------R---- thulium 173 (Tm-173) + 1397 0 691740 82c DEC 69 174 0 173.94226 900.0 2.13934E-03 IB-DF----------R---- thulium 174 (Tm-174) + 1398 0 691750 82c DEC 69 175 0 174.94386 900.0 7.60030E-04 IB-DF----------R---- thulium 175 (Tm-175) + 1399 0 691760 82c DEC 69 176 0 175.94748 900.0 6.24457E-03 IB-DF----------R---- thulium 176 (Tm-176) + 1400 0 691770 82c DEC 69 177 0 176.94909 900.0 7.70164E-03 IB-DF----------R---- thulium 177 (Tm-177) + 1401 0 691780 82c DEC 69 178 0 177.95271 900.0 2.31049E-02 IB--F----------R---- thulium 178 (Tm-178) + 1402 0 691790 82c DEC 69 179 0 178.95532 900.0 3.46574E-02 IB--F----------R---- thulium 179 (Tm-179) + 1403 0 701680 82c DEC 70 168 0 167.93364 900.0 1.68958E-22 IB-D-----------R---- ytterbium 168 (Yb-168) + 1404 0 701690 82c DEC 70 169 0 168.93524 900.0 2.50563E-07 IB--F----------R---- ytterbium 169 (Yb-169) + 1405 0 701700 82c DEC 70 170 0 169.93483 900.0 stable IB-DF----------R---- ytterbium 170 (Yb-170) + 1406 0 701710 82c DEC 70 171 0 170.93643 900.0 stable IB-DF----------R---- ytterbium 171 (Yb-171) + 1407 0 701711 82c DEC 70 171 1 170.93643 900.0 1.32028E+02 IB--F----------R---- ytterbium 171m (Yb-171m) + 1408 0 701720 82c DEC 70 172 0 171.93602 900.0 stable IB-DF----------R---- ytterbium 172 (Yb-172) + 1409 0 701730 82c DEC 70 173 0 172.93863 900.0 stable IBADF----------R---- ytterbium 173 (Yb-173) + 1410 0 701740 82c DEC 70 174 0 173.93923 900.0 stable IBADF----------R---- ytterbium 174 (Yb-174) + 1411 0 701750 82c DEC 70 175 0 174.94083 900.0 1.91697E-06 IBADF----------R---- ytterbium 175 (Yb-175) + 1412 0 701751 82c DEC 70 175 1 174.94083 900.0 1.01634E+01 IB-DF----------R---- ytterbium 175m (Yb-175m) + 1413 0 701760 82c DEC 70 176 0 175.94244 900.0 stable IBADF----------R---- ytterbium 176 (Yb-176) + 1414 0 701761 82c DEC 70 176 1 175.94244 900.0 6.08024E-02 IB-DF----------R---- ytterbium 176m (Yb-176m) + 1415 0 701770 82c DEC 70 177 0 176.94505 900.0 1.00754E-04 IBADF----------R---- ytterbium 177 (Yb-177) + 1416 0 701771 82c DEC 70 177 1 176.94505 900.0 1.08135E-01 IB-DF----------R---- ytterbium 177m (Yb-177m) + 1417 0 701780 82c DEC 70 178 0 177.94666 900.0 1.56114E-04 IB-DF----------R---- ytterbium 178 (Yb-178) + 1418 0 701790 82c DEC 70 179 0 178.95028 900.0 1.44406E-03 IB-DF----------R---- ytterbium 179 (Yb-179) + 1419 0 701800 82c DEC 70 180 0 179.95188 900.0 4.81352E-03 IB--F----------R---- ytterbium 180 (Yb-180) + 1420 0 701810 82c DEC 70 181 0 180.95651 900.0 1.15525E-02 IB--F----------R---- ytterbium 181 (Yb-181) + 1421 0 711720 82c DEC 71 172 0 171.93905 900.0 1.19739E-06 IB--F----------R---- lutetium 172 (Lu-172) + 1422 0 711730 82c DEC 71 173 0 172.93863 900.0 1.64396E-08 IBA-F----------R---- lutetium 173 (Lu-173) + 1423 0 711740 82c DEC 71 174 0 173.94024 900.0 6.17118E-09 IBADF----------R---- lutetium 174 (Lu-174) + 1424 0 711741 82c DEC 71 174 1 173.94024 900.0 5.64967E-08 IB--F----------R---- lutetium 174m (Lu-174m) + 1425 0 711761 82c DEC 71 176 1 175.94244 900.0 5.29686E-05 IBA-F----------R---- lutetium 176m (Lu-176m) + 1426 0 711770 82c DEC 71 177 0 176.94404 900.0 1.20694E-06 IBADF----------R---- lutetium 177 (Lu-177) + 1427 0 711771 82c DEC 71 177 1 176.94404 900.0 5.00471E-08 IBADF----------R---- lutetium 177m (Lu-177m) + 1428 1 711772 82c DEC 71 177 2 176.94404 900.0 1.65035E-03 -B--F----------R---- lutetium 177m (Lu-177m) + 1429 0 711780 82c DEC 71 178 0 177.94565 900.0 4.06777E-04 IBADF----------R---- lutetium 178 (Lu-178) + 1430 0 711781 82c DEC 71 178 1 177.94565 900.0 5.00106E-04 IB--F----------R---- lutetium 178m (Lu-178m) + 1431 0 711790 82c DEC 71 179 0 178.94725 900.0 4.19479E-05 IBADF----------R---- lutetium 179 (Lu-179) + 1432 0 711791 82c DEC 71 179 1 178.94725 900.0 2.23596E+02 IB-DF----------R---- lutetium 179m (Lu-179m) + 1433 0 711800 82c DEC 71 180 0 179.94986 900.0 2.02675E-03 IBADF----------R---- lutetium 180 (Lu-180) + 1434 0 711801 82c DEC 71 180 1 179.94986 900.0 6.93147E-01 IB-DF----------R---- lutetium 180m (Lu-180m) + 1435 1 711802 82c DEC 71 180 2 179.94986 900.0 6.93147E+02 -B--F----------R---- lutetium 180m (Lu-180m) + 1436 0 711810 82c DEC 71 181 0 180.95248 900.0 3.30070E-03 IB-DF----------R---- lutetium 181 (Lu-181) + 1437 0 711820 82c DEC 71 182 0 181.95509 900.0 5.77623E-03 IB--F----------R---- lutetium 182 (Lu-182) + 1438 0 711830 82c DEC 71 183 0 182.95770 900.0 1.19508E-02 IB--F----------R---- lutetium 183 (Lu-183) + 1439 0 711840 82c DEC 71 184 0 183.96133 900.0 3.46574E-02 IB--F----------R---- lutetium 184 (Lu-184) + 1440 0 721740 82c DEC 72 174 0 173.94024 900.0 1.09823E-23 IBA------------R---- hafnium 174 (Hf-174) + 1441 0 721750 82c DEC 72 175 0 174.94184 900.0 1.14608E-07 IBA-F----------R---- hafnium 175 (Hf-175) + 1442 0 721771 82c DEC 72 177 1 176.94303 900.0 6.41803E-01 IB-DF----------R---- hafnium 177m (Hf-177m) + 1443 1 721772 82c DEC 72 177 2 176.94303 900.0 2.24756E-04 -B-DF----------R---- hafnium 177m (Hf-177m) + 1444 0 721781 82c DEC 72 178 1 177.94363 900.0 1.73287E-01 IB-DF----------R---- hafnium 178m (Hf-178m) + 1445 1 721782 82c DEC 72 178 2 177.94363 900.0 7.08532E-10 -B--F----------R---- hafnium 178m (Hf-178m) + 1446 0 721791 82c DEC 72 179 1 178.94624 900.0 3.71263E-02 IB-DF----------R---- hafnium 179m (Hf-179m) + 1447 1 721792 82c DEC 72 179 2 178.94624 900.0 3.19623E-07 -B-DF----------R---- hafnium 179m (Hf-179m) + 1448 0 721801 82c DEC 72 180 1 179.94684 900.0 3.50074E-05 IBADF----------R---- hafnium 180m (Hf-180m) + 1449 0 721810 82c DEC 72 181 0 180.94945 900.0 1.89300E-07 IBADF----------R---- hafnium 181 (Hf-181) + 1450 0 721820 82c DEC 72 182 0 181.95005 900.0 2.46797E-15 IBADF----------R---- hafnium 182 (Hf-182) + 1451 0 721821 82c DEC 72 182 1 181.95106 900.0 1.87845E-04 IB--F----------R---- hafnium 182m (Hf-182m) + 1452 0 721830 82c DEC 72 183 0 182.95367 900.0 1.80451E-04 IBADF----------R---- hafnium 183 (Hf-183) + 1453 0 721840 82c DEC 72 184 0 183.95527 900.0 4.67332E-05 IB-DF----------R---- hafnium 184 (Hf-184) + 1454 0 721841 82c DEC 72 184 1 183.95527 900.0 1.44406E-02 IB-DF----------R---- hafnium 184m (Hf-184m) + 1455 0 721850 82c DEC 72 185 0 184.95889 900.0 3.30070E-03 IB--F----------R---- hafnium 185 (Hf-185) + 1456 0 721860 82c DEC 72 186 0 185.96050 900.0 4.44325E-03 IB--F----------R---- hafnium 186 (Hf-186) + 1457 0 721870 82c DEC 72 187 0 186.96412 900.0 2.31049E-02 IB--F----------R---- hafnium 187 (Hf-187) + 1458 0 721880 82c DEC 72 188 0 187.96673 900.0 3.46574E-02 IB--F----------R---- hafnium 188 (Hf-188) + 1459 0 731780 82c DEC 73 178 0 177.94565 900.0 1.24086E-03 IB--F----------R---- tantalum 178 (Ta-178) + 1460 0 731781 82c DEC 73 178 1 177.94565 900.0 8.15851E-05 IB--F----------R---- tantalum 178m (Ta-178m) + 1461 0 731790 82c DEC 73 179 0 178.94624 900.0 1.36438E-08 IBADF----------R---- tantalum 179 (Ta-179) + 1462 0 731791 82c DEC 73 179 1 178.94624 900.0 7.70164E+01 IB-DF----------R---- tantalum 179m (Ta-179m) + 1463 1 731792 82c DEC 73 179 2 178.94624 900.0 1.28123E+01 -B--F----------R---- tantalum 179m (Ta-179m) + 1464 0 731800 82c DEC 73 180 0 179.94785 900.0 2.38293E-05 IBA-F----------R---- tantalum 180 (Ta-180) + 1465 0 731801 82c DEC 73 180 1 179.94785 900.0 1.22025E-23 IB-DF----------R---- tantalum 180m (Ta-180m) + 1466 0 731821 82c DEC 73 182 1 181.95005 900.0 2.44928E+00 IB-DF----------R---- tantalum 182m (Ta-182m) + 1467 1 731822 82c DEC 73 182 2 181.95005 900.0 7.29322E-04 -B--F----------R---- tantalum 182m (Ta-182m) + 1468 0 731830 82c DEC 73 183 0 182.95165 900.0 1.57614E-06 IBADF----------R---- tantalum 183 (Ta-183) + 1469 0 731840 82c DEC 73 184 0 183.95426 900.0 2.21311E-05 IBADF----------R---- tantalum 184 (Ta-184) + 1470 0 731850 82c DEC 73 185 0 184.95587 900.0 2.33855E-04 IBADF----------R---- tantalum 185 (Ta-185) + 1471 0 731851 82c DEC 73 185 1 184.95587 900.0 6.93147E+02 IB--F----------R---- tantalum 185m (Ta-185m) + 1472 0 731860 82c DEC 73 186 0 185.95848 900.0 1.10023E-03 IBADF----------R---- tantalum 186 (Ta-186) + 1473 0 731870 82c DEC 73 187 0 186.96009 900.0 5.77623E-03 IB-DF----------R---- tantalum 187 (Ta-187) + 1474 0 731880 82c DEC 73 188 0 187.96371 900.0 3.46574E-02 IB-DF----------R---- tantalum 188 (Ta-188) + 1475 0 731890 82c DEC 73 189 0 188.96632 900.0 2.31049E-01 IB--F----------R---- tantalum 189 (Ta-189) + 1476 0 731900 82c DEC 73 190 0 189.96893 900.0 2.31049E+00 IB--F----------R---- tantalum 190 (Ta-190) + 1477 0 741800 82c DEC 74 180 0 179.94684 900.0 stable IBADF----------R---- tungsten 180 (W-180) + 1478 0 741810 82c DEC 74 181 0 180.94844 900.0 6.63127E-08 IBA-F----------R---- tungsten 181 (W-181) + 1479 0 741831 82c DEC 74 183 1 182.95064 900.0 1.32028E-01 IBADF----------R---- tungsten 183m (W-183m) + 1480 0 741850 82c DEC 74 185 0 184.95385 900.0 1.06825E-07 IBADF----------R---- tungsten 185 (W-185) + 1481 0 741851 82c DEC 74 185 1 184.95385 900.0 6.93147E-03 IBA-F----------R---- tungsten 185m (W-185m) + 1482 0 741861 82c DEC 74 186 1 185.95445 900.0 2.31049E+02 IB--F----------R---- tungsten 186m (W-186m) + 1483 0 741870 82c DEC 74 187 0 186.95706 900.0 8.07299E-06 IBADF----------R---- tungsten 187 (W-187) + 1484 0 741880 82c DEC 74 188 0 187.95866 900.0 1.14969E-07 IB-DF----------R---- tungsten 188 (W-188) + 1485 0 741890 82c DEC 74 189 0 188.96229 900.0 1.07967E-03 IB-DF----------R---- tungsten 189 (W-189) + 1486 0 741900 82c DEC 74 190 0 189.96288 900.0 3.85082E-04 IB-DF----------R---- tungsten 190 (W-190) + 1487 0 741901 82c DEC 74 190 1 189.96288 900.0 2.23596E+02 IB--F----------R---- tungsten 190m (W-190m) + 1488 0 741910 82c DEC 74 191 0 190.96650 900.0 3.46574E-02 IB--F----------R---- tungsten 191 (W-191) + 1489 0 741920 82c DEC 74 192 0 191.96811 900.0 6.93147E-02 IB--F----------R---- tungsten 192 (W-192) + 1490 0 751830 82c DEC 75 183 0 182.95064 900.0 1.14608E-07 IBA-F----------R---- rhenium 183 (Re-183) + 1491 0 751840 82c DEC 75 184 0 183.95225 900.0 2.26625E-07 IBADF----------R---- rhenium 184 (Re-184) + 1492 0 751841 82c DEC 75 184 1 183.95225 900.0 4.77532E-08 IB--F----------R---- rhenium 184m (Re-184m) + 1493 0 751860 82c DEC 75 186 0 185.95546 900.0 2.13934E-06 IBADF----------R---- rhenium 186 (Re-186) + 1494 0 751861 82c DEC 75 186 1 185.95546 900.0 1.15605E-13 IBA-F----------R---- rhenium 186m (Re-186m) + 1495 0 751880 82c DEC 75 188 0 187.95766 900.0 1.13226E-05 IBADF----------R---- rhenium 188 (Re-188) + 1496 0 751881 82c DEC 75 188 1 187.95766 900.0 6.21434E-04 IBA-F----------R---- rhenium 188m (Re-188m) + 1497 0 751890 82c DEC 75 189 0 188.95926 900.0 7.92349E-06 IB-DF----------R---- rhenium 189 (Re-189) + 1498 0 751900 82c DEC 75 190 0 189.96187 900.0 3.72660E-03 IBADF----------R---- rhenium 190 (Re-190) + 1499 0 751901 82c DEC 75 190 1 189.96187 900.0 6.01690E-05 IB--F----------R---- rhenium 190m (Re-190m) + 1500 0 751910 82c DEC 75 191 0 190.96348 900.0 1.19097E-03 IB-DF----------R---- rhenium 191 (Re-191) + 1501 0 751920 82c DEC 75 192 0 191.96609 900.0 1.11798E-01 IB-DF----------R---- rhenium 192 (Re-192) + 1502 0 751930 82c DEC 75 193 0 192.96769 900.0 2.31049E-02 IB--F----------R---- rhenium 193 (Re-193) + 1503 0 751940 82c DEC 75 194 0 193.97031 900.0 3.46574E-01 IB--F----------R---- rhenium 194 (Re-194) + 1504 0 761860 82c DEC 76 186 0 185.95344 900.0 1.09823E-23 IB-DF----------R---- osmium 186 (Os-186) + 1505 0 761870 82c DEC 76 187 0 186.95605 900.0 stable IB-DF----------R---- osmium 187 (Os-187) + 1506 0 761880 82c DEC 76 188 0 187.95564 900.0 stable IB-DF----------R---- osmium 188 (Os-188) + 1507 0 761890 82c DEC 76 189 0 188.95825 900.0 stable IB-DF----------R---- osmium 189 (Os-189) + 1508 0 761891 82c DEC 76 189 1 188.95825 900.0 3.31396E-05 IB-DF----------R---- osmium 189m (Os-189m) + 1509 0 761900 82c DEC 76 190 0 189.95885 900.0 stable IB-DF----------R---- osmium 190 (Os-190) + 1510 0 761901 82c DEC 76 190 1 189.95885 900.0 1.16691E-03 IB-DF----------R---- osmium 190m (Os-190m) + 1511 0 761910 82c DEC 76 191 0 190.96146 900.0 5.24349E-07 IBADF----------R---- osmium 191 (Os-191) + 1512 0 761911 82c DEC 76 191 1 190.96146 900.0 1.46978E-05 IB--F----------R---- osmium 191m (Os-191m) + 1513 0 761920 82c DEC 76 192 0 191.96105 900.0 stable IB-DF----------R---- osmium 192 (Os-192) + 1514 0 761921 82c DEC 76 192 1 191.96105 900.0 1.17483E-01 IB--F----------R---- osmium 192m (Os-192m) + 1515 0 761930 82c DEC 76 193 0 192.96366 900.0 6.39458E-06 IBADF----------R---- osmium 193 (Os-193) + 1516 0 761940 82c DEC 76 194 0 193.96526 900.0 3.66082E-09 IB-DF----------R---- osmium 194 (Os-194) + 1517 0 761950 82c DEC 76 195 0 194.96788 900.0 1.77730E-03 IB--F----------R---- osmium 195 (Os-195) + 1518 0 761960 82c DEC 76 196 0 195.96948 900.0 3.31016E-04 IB--F----------R---- osmium 196 (Os-196) + 1519 0 771890 82c DEC 77 189 0 188.95825 900.0 6.07768E-07 IBADF----------R---- iridium 189 (Ir-189) + 1520 0 771891 82c DEC 77 189 1 188.95825 900.0 5.21163E+01 IB--F----------R---- iridium 189m (Ir-189m) + 1521 0 771900 82c DEC 77 190 0 189.96086 900.0 6.68545E-07 IBADF----------R---- iridium 190 (Ir-190) + 1522 0 771901 82c DEC 77 190 1 189.96086 900.0 1.71912E-04 IB--F----------R---- iridium 190m (Ir-190m) + 1523 1 771902 82c DEC 77 190 2 189.96086 900.0 6.23715E-05 -B--F----------R---- iridium 190m (Ir-190m) + 1524 0 771911 82c DEC 77 191 1 190.96045 900.0 1.41459E-01 IB-DF----------R---- iridium 191m (Ir-191m) + 1525 1 771912 82c DEC 77 191 2 190.96045 900.0 1.26027E-01 -B--F----------R---- iridium 191m (Ir-191m) + 1526 0 771920 82c DEC 77 192 0 191.96306 900.0 1.08674E-07 IBADF----------R---- iridium 192 (Ir-192) + 1527 0 771921 82c DEC 77 192 1 191.96306 900.0 8.02254E-03 IB-DF----------R---- iridium 192m (Ir-192m) + 1528 1 771922 82c DEC 77 192 2 191.96306 900.0 9.11410E-11 -B--F----------R---- iridium 192m (Ir-192m) + 1529 0 771931 82c DEC 77 193 1 192.96265 900.0 7.61874E-07 IB-DF----------R---- iridium 193m (Ir-193m) + 1530 0 771940 82c DEC 77 194 0 193.96526 900.0 9.97621E-06 IBADF----------R---- iridium 194 (Ir-194) + 1531 0 771941 82c DEC 77 194 1 193.96526 900.0 2.17765E+01 IB--F----------R---- iridium 194m (Ir-194m) + 1532 1 771942 82c DEC 77 194 2 193.96526 900.0 4.69154E-08 -B--F----------R---- iridium 194m (Ir-194m) + 1533 0 771950 82c DEC 77 195 0 194.96586 900.0 7.70164E-05 IB-DF----------R---- iridium 195 (Ir-195) + 1534 0 771951 82c DEC 77 195 1 194.96586 900.0 5.06687E-05 IB--F----------R---- iridium 195m (Ir-195m) + 1535 0 771960 82c DEC 77 196 0 195.96847 900.0 1.33298E-02 IB-DF----------R---- iridium 196 (Ir-196) + 1536 0 771961 82c DEC 77 196 1 195.96847 900.0 1.37529E-04 IB--F----------R---- iridium 196m (Ir-196m) + 1537 0 771970 82c DEC 77 197 0 196.97008 900.0 1.99180E-03 IB-DF----------R---- iridium 197 (Ir-197) + 1538 0 771971 82c DEC 77 197 1 196.97008 900.0 1.29803E-03 IB--F----------R---- iridium 197m (Ir-197m) + 1539 0 781920 82c DEC 78 192 0 191.96105 900.0 stable IB-DF----------R---- platinum 192 (Pt-192) + 1540 0 781930 82c DEC 78 193 0 192.96265 900.0 4.39290E-10 IB-DF----------R---- platinum 193 (Pt-193) + 1541 0 781931 82c DEC 78 193 1 192.96265 900.0 1.84851E-06 IB--F----------R---- platinum 193m (Pt-193m) + 1542 0 781940 82c DEC 78 194 0 193.96224 900.0 stable IBADF----------R---- platinum 194 (Pt-194) + 1543 0 781950 82c DEC 78 195 0 194.96485 900.0 stable IBADF----------R---- platinum 195 (Pt-195) + 1544 0 781951 82c DEC 78 195 1 194.96485 900.0 1.95672E-06 IB-DF----------R---- platinum 195m (Pt-195m) + 1545 0 781960 82c DEC 78 196 0 195.96545 900.0 stable IBADF----------R---- platinum 196 (Pt-196) + 1546 0 781970 82c DEC 78 197 0 196.96705 900.0 9.67956E-06 IBADF----------R---- platinum 197 (Pt-197) + 1547 0 781971 82c DEC 78 197 1 196.96705 900.0 1.21222E-04 IB-DF----------R---- platinum 197m (Pt-197m) + 1548 0 781980 82c DEC 78 198 0 197.96765 900.0 stable IB--F----------R---- platinum 198 (Pt-198) + 1549 0 781990 82c DEC 78 199 0 198.97026 900.0 3.75080E-04 IB-DF----------R---- platinum 199 (Pt-199) + 1550 0 781991 82c DEC 78 199 1 198.97026 900.0 5.09667E-02 IB--F----------R---- platinum 199m (Pt-199m) + 1551 0 791950 82c DEC 79 195 0 194.95476 900.0 4.31102E-08 IBA-F----------R---- gold 195 (Au-195) + 1552 0 791960 82c DEC 79 196 0 195.96646 900.0 1.30090E-06 IBADF----------R---- gold 196 (Au-196) + 1553 0 791961 82c DEC 79 196 1 195.96646 900.0 8.55737E-02 IB--F----------R---- gold 196m (Au-196m) + 1554 0 791971 82c DEC 79 197 1 196.96705 900.0 8.95539E-02 IB-DF----------R---- gold 197m (Au-197m) + 1555 0 791980 82c DEC 79 198 0 197.96866 900.0 2.97759E-06 IBADF----------R---- gold 198 (Au-198) + 1556 0 791981 82c DEC 79 198 1 197.96866 900.0 3.48806E-06 IBA-F----------R---- gold 198m (Au-198m) + 1557 0 791990 82c DEC 79 199 0 198.96925 900.0 2.55576E-06 IBADF----------R---- gold 199 (Au-199) + 1558 0 792000 82c DEC 79 200 0 199.97086 900.0 2.38687E-04 IBADF----------R---- gold 200 (Au-200) + 1559 0 792001 82c DEC 79 200 1 199.97086 900.0 1.02963E-05 IB--F----------R---- gold 200m (Au-200m) + 1560 0 801960 82c DEC 80 196 0 195.96545 900.0 8.78580E-27 IBAD-----------R---- mercury 196 (Hg-196) + 1561 0 801970 82c DEC 80 197 0 196.96705 900.0 2.98051E-06 IBA------------R---- mercury 197 (Hg-197) + 1562 0 801991 82c DEC 80 199 1 198.96824 900.0 2.74405E-04 IBA-F----------R---- mercury 199m (Hg-199m) + 1563 0 802010 82c DEC 80 201 0 200.97044 900.0 stable IBA------------R---- mercury 201 (Hg-201) + 1564 0 802060 82c DEC 80 206 0 205.97746 900.0 1.38852E-03 IB-D-----------R---- mercury 206 (Hg-206) + 1565 0 812050 82c DEC 81 205 0 204.97484 900.0 stable IB-D-----------R---- thallium 205 (Tl-205) + 1566 0 812060 82c DEC 81 206 0 205.97645 900.0 2.74927E-03 IB-D-----------R---- thallium 206 (Tl-206) + 1567 0 812070 82c DEC 81 207 0 206.97704 900.0 2.41987E-03 IB-D-----------R---- thallium 207 (Tl-207) + 1568 0 812080 82c DEC 81 208 0 207.98167 900.0 3.77778E-03 IB-D-----------R---- thallium 208 (Tl-208) + 1569 0 812090 82c DEC 81 209 0 208.98529 900.0 5.34588E-03 IB-D-----------R---- thallium 209 (Tl-209) + 1570 0 812100 82c DEC 81 210 0 209.98992 900.0 8.88650E-03 IB-D-----------R---- thallium 210 (Tl-210) + 1571 0 822060 82c DEC 82 206 0 205.97443 900.0 stable IB-D-----------R---- lead 206 (Pb-206) + 1572 0 822070 82c DEC 82 207 0 206.97603 900.0 stable IB-D-----------R---- lead 207 (Pb-207) + 1573 0 822080 82c DEC 82 208 0 207.97663 900.0 stable IB-D-----------R---- lead 208 (Pb-208) + 1574 0 822090 82c DEC 82 209 0 208.98126 900.0 5.87552E-05 IB-D-----------R---- lead 209 (Pb-209) + 1575 0 822100 82c DEC 82 210 0 209.98387 900.0 9.88079E-10 IB-D-----------R---- lead 210 (Pb-210) + 1576 0 822110 82c DEC 82 211 0 210.98850 900.0 3.20013E-04 IB-D-----------R---- lead 211 (Pb-211) + 1577 0 822120 82c DEC 82 212 0 211.99212 900.0 1.80959E-05 IB-D-----------R---- lead 212 (Pb-212) + 1578 0 822140 82c DEC 82 214 0 213.99937 900.0 4.29204E-04 IB-D-----------R---- lead 214 (Pb-214) + 1579 0 832090 82c DEC 83 209 0 208.98025 900.0 1.15603E-27 IB-D-----------R---- bismuth 209 (Bi-209) + 1580 0 832100 82c DEC 83 210 0 209.98387 900.0 1.60099E-06 IB-D-----------R---- bismuth 210 (Bi-210) + 1581 0 832110 82c DEC 83 211 0 210.98749 900.0 5.37323E-03 IB-D-----------R---- bismuth 211 (Bi-211) + 1582 0 832120 82c DEC 83 212 0 211.99112 900.0 1.90823E-04 IB-D-----------R---- bismuth 212 (Bi-212) + 1583 0 832130 82c DEC 83 213 0 212.99474 900.0 2.53399E-04 IB-D-----------R---- bismuth 213 (Bi-213) + 1584 0 832140 82c DEC 83 214 0 213.99836 900.0 5.83457E-04 IB-D-----------R---- bismuth 214 (Bi-214) + 1585 0 832150 82c DEC 83 215 0 215.00198 900.0 1.52006E-03 IB-D-----------R---- bismuth 215 (Bi-215) + 1586 0 842100 82c DEC 84 210 0 209.98286 900.0 5.79763E-08 IB-D-----------R---- polonium 210 (Po-210) + 1587 0 842110 82c DEC 84 211 0 210.98649 900.0 1.34331E+00 IB-D-----------R---- polonium 211 (Po-211) + 1588 0 842120 82c DEC 84 212 0 211.98910 900.0 2.31049E+06 IB-D-----------R---- polonium 212 (Po-212) + 1589 0 842130 82c DEC 84 213 0 212.99272 900.0 1.87337E+05 IB-D-----------R---- polonium 213 (Po-213) + 1590 0 842140 82c DEC 84 214 0 213.99533 900.0 4.27078E+03 IB-D-----------R---- polonium 214 (Po-214) + 1591 0 842150 82c DEC 84 215 0 214.99896 900.0 3.89190E+02 IB-D-----------R---- polonium 215 (Po-215) + 1592 0 842160 82c DEC 84 216 0 216.00157 900.0 4.68343E+00 IB-D-----------R---- polonium 216 (Po-216) + 1593 0 842180 82c DEC 84 218 0 218.00881 900.0 3.76179E-03 IB-D-----------R---- polonium 218 (Po-218) + 1594 0 852150 82c DEC 85 215 0 214.99896 900.0 6.93147E+03 IB-D-----------R---- astatine 215 (At-215) + 1595 0 852170 82c DEC 85 217 0 217.00519 900.0 2.14597E+01 IB-D-----------R---- astatine 217 (At-217) + 1596 0 852180 82c DEC 85 218 0 218.00881 900.0 4.95105E-01 IB-D-----------R---- astatine 218 (At-218) + 1597 0 852190 82c DEC 85 219 0 219.01142 900.0 1.23776E-02 IB-D-----------R---- astatine 219 (At-219) + 1598 0 862160 82c DEC 86 216 0 216.00056 900.0 1.54033E+04 IB-D-----------R---- radon 216 (Rn-216) + 1599 0 862170 82c DEC 86 217 0 217.00418 900.0 1.28361E+03 IB-D-----------R---- radon 217 (Rn-217) + 1600 0 862180 82c DEC 86 218 0 218.00579 900.0 1.92541E+01 IB-D-----------R---- radon 218 (Rn-218) + 1601 0 862190 82c DEC 86 219 0 219.00941 900.0 1.74158E-01 IB-D-----------R---- radon 219 (Rn-219) + 1602 0 862200 82c DEC 86 220 0 220.01101 900.0 1.24220E-02 IB-D-----------R---- radon 220 (Rn-220) + 1603 0 862220 82c DEC 86 222 0 222.01725 900.0 2.09839E-06 IB-D-----------R---- radon 222 (Rn-222) + 1604 0 872210 82c DEC 87 221 0 221.01463 900.0 2.41179E-03 IB-D-----------R---- francium 221 (Fr-221) + 1605 0 872220 82c DEC 87 222 0 222.01725 900.0 8.13553E-04 IB-D-----------R---- francium 222 (Fr-222) + 1606 0 872230 82c DEC 87 223 0 223.01986 900.0 5.25112E-04 IB-D-----------R---- francium 223 (Fr-223) + 1607 0 872240 82c DEC 87 224 0 224.02348 900.0 3.46921E-03 IB-D-----------R---- francium 224 (Fr-224) + 1608 0 882200 82c DEC 88 220 0 220.01101 900.0 3.85082E+01 IB-D-----------R---- radium 220 (Ra-220) + 1609 0 882210 82c DEC 88 221 0 221.01362 900.0 2.47553E-02 IB-D-----------R---- radium 221 (Ra-221) + 1610 0 882220 82c DEC 88 222 0 222.01523 900.0 1.91636E-02 IB-D-----------R---- radium 222 (Ra-222) + 1611 0 882230 82c DEC 88 223 0 223.01885 900.0 7.01884E-07 IB-D-----------R---- radium 223 (Ra-223) + 1612 0 882240 82c DEC 88 224 0 224.02045 900.0 2.20946E-06 IB-D-----------R---- radium 224 (Ra-224) + 1613 0 882250 82c DEC 88 225 0 225.02408 900.0 5.41331E-07 IB-D-----------R---- radium 225 (Ra-225) + 1614 0 882260 82c DEC 88 226 0 226.02568 900.0 1.37281E-11 IB-D-----------R---- radium 226 (Ra-226) + 1615 0 882280 82c DEC 88 228 0 228.03091 900.0 3.82000E-09 IB-D-----------R---- radium 228 (Ra-228) + 1616 0 892250 82c DEC 89 225 0 225.02307 900.0 8.02254E-07 IB-D-----------R---- actinium 225 (Ac-225) + 1617 0 892260 82c DEC 89 226 0 226.02568 900.0 6.55570E-06 IB-D-----------R---- actinium 226 (Ac-226) + 1618 0 892270 82c DEC 89 227 0 227.02728 900.0 1.00886E-09 IB-D-----------R---- actinium 227 (Ac-227) + 1619 0 892280 82c DEC 89 228 0 228.03091 900.0 3.13075E-05 IB-D-----------R---- actinium 228 (Ac-228) + 1620 0 902240 82c DEC 90 224 0 224.02146 900.0 6.60140E-01 IBA------------R---- thorium 224 (Th-224) + 1621 0 902250 82c DEC 90 225 0 225.02408 900.0 1.32482E-03 IBA------------R---- thorium 225 (Th-225) + 1622 0 902260 82c DEC 90 226 0 226.02467 900.0 3.77902E-04 IBAD-----------R---- thorium 226 (Th-226) + 1623 0 902310 82c DEC 90 231 0 231.03673 900.0 7.54411E-06 IBAD-----------R---- thorium 231 (Th-231) + 1624 0 902320 82c DEC 90 232 0 232.03833 900.0 1.56331E-18 IB-D-----------R---- thorium 232 (Th-232) + 1625 0 902340 82c DEC 90 234 0 234.04356 900.0 3.32885E-07 IB-D-----------R---- thorium 234 (Th-234) + 1626 0 912290 82c DEC 91 229 0 229.03251 900.0 5.34836E-06 IBA------------R---- protactinium 229 (Pa-229) + 1627 0 912300 82c DEC 91 230 0 230.03412 900.0 4.61065E-07 IBA------------R---- protactinium 230 (Pa-230) + 1628 0 912340 82c DEC 91 234 0 234.04356 900.0 2.87374E-05 IBAD-----------R---- protactinium 234 (Pa-234) + 1629 0 912341 82c DEC 91 234 1 234.04356 900.0 9.96760E-03 IBAD-----------R---- protactinium 234m (Pa-234m) + 1630 0 922300 82c DEC 92 230 0 230.03412 900.0 3.85699E-07 IBAD-----------R---- uranium 230 (U-230) + 1631 0 922310 82c DEC 92 231 0 231.03673 900.0 1.91013E-06 IBAD-----------R---- uranium 231 (U-231) + 1632 0 922351 82c DEC 92 235 1 235.04415 900.0 4.44325E-04 IBAD-----------R---- uranium 235m (U-235m) + 1633 0 922390 82c DEC 92 239 0 239.05461 900.0 4.92432E-04 IBA------------R---- uranium 239 (U-239) + 1634 0 922400 82c DEC 92 240 0 240.05621 900.0 1.36554E-05 IB-D-----------R---- uranium 240 (U-240) + 1635 0 932330 82c DEC 93 233 0 233.04095 900.0 3.19129E-04 IBA------------R---- neptunium 233 (Np-233) + 1636 0 932340 82c DEC 93 234 0 234.04255 900.0 1.82330E-06 IBAD-----------R---- neptunium 234 (Np-234) + 1637 0 932361 82c DEC 93 236 1 236.04677 900.0 8.55737E-06 IBA------------R---- neptunium 236m (Np-236m) + 1638 0 932400 82c DEC 93 240 0 240.05621 900.0 1.77730E-04 IBAD-----------R---- neptunium 240 (Np-240) + 1639 0 932401 82c DEC 93 240 1 240.05621 900.0 1.56114E-03 IBA------------R---- neptunium 240m (Np-240m) + 1640 0 942340 82c DEC 94 234 0 234.04356 900.0 2.18796E-05 IBAD-----------R---- plutonium 234 (Pu-234) + 1641 0 942350 82c DEC 94 235 0 235.04516 900.0 4.56619E-04 IBAD-----------R---- plutonium 235 (Pu-235) + 1642 0 942371 82c DEC 94 237 1 237.04837 900.0 3.85082E+00 IBA------------R---- plutonium 237m (Pu-237m) + 1643 0 942450 82c DEC 94 245 0 245.06827 900.0 1.83372E-05 IBA------------R---- plutonium 245 (Pu-245) + 1644 0 942460 82c DEC 94 246 0 246.06987 900.0 7.39404E-07 IB-D-----------R---- plutonium 246 (Pu-246) + 1645 0 952380 82c DEC 95 238 0 238.05199 900.0 1.17882E-04 IB-D-----------R---- americium 238 (Am-238) + 1646 0 952390 82c DEC 95 239 0 239.05259 900.0 1.61799E-05 IBAD-----------R---- americium 239 (Am-239) + 1647 0 952400 82c DEC 95 240 0 240.05520 900.0 3.79017E-06 IBA------------R---- americium 240 (Am-240) + 1648 0 952450 82c DEC 95 245 0 245.06625 900.0 9.39224E-05 IBAD-----------R---- americium 245 (Am-245) + 1649 0 952461 82c DEC 95 246 1 246.06987 900.0 4.62098E-04 IB-D-----------R---- americium 246m (Am-246m) + 1650 0 962380 82c DEC 96 238 0 238.05300 900.0 8.02254E-05 IBA------------R---- curium 238 (Cm-238) + 1651 0 962390 82c DEC 96 239 0 239.05461 900.0 6.63934E-05 IBA------------R---- curium 239 (Cm-239) + 1652 0 962441 82c DEC 96 244 1 244.06263 900.0 2.03867E+01 IB-D-----------R---- curium 244m (Cm-244m) + 1653 0 962510 82c DEC 96 251 0 251.08193 900.0 6.87646E-04 IBA------------R---- curium 251 (Cm-251) + 1654 0 972490 82c DEC 97 249 0 249.07468 900.0 2.50704E-08 IB-D-----------R---- berkelium 249 (Bk-249) + 1655 0 972510 82c DEC 97 251 0 251.08092 900.0 2.07778E-04 IB-D-----------R---- berkelium 251 (Bk-251) + 1656 0 982490 82c DEC 98 249 0 249.07468 900.0 6.25770E-11 IB-D-----------R---- californium 249 (Cf-249) + 1657 0 982510 82c DEC 98 251 0 251.07991 900.0 2.44594E-11 IB-D-----------R---- californium 251 (Cf-251) + + --- Table 2: Reaction and decay data: + + Nuclide 1 / 1657 : 1001.82c -- hydrogen (H-1) + + Pointers : 49939 25100 + Primary type : Transport + Nuclide ZAI : 10010 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/H1.ACE + Atomic weight (AW) : 1.00783 + Atomic weight ratio (AWR) : 0.99917 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 1.50000E+02 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 2 reaction channels + - 2 special reactions + - 1 transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 102 Q = 2.22460E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,gamma) + + 2 special reactions: + + 1 MT = 204 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total deuteron production + 2 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + + Nuclide 2 / 1657 : 1001.82s -- hydrogen (H-1) + + Pointers : 3524041 25100 + Primary type : Transport + Nuclide ZAI : 10010 + Library ID : 82s + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/H1.ACE + Atomic weight (AW) : 1.00783 + Atomic weight ratio (AWR) : 0.99917 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 1.50000E+02 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has inelastic S(a,b) channel between 1.00E-11 and 3.75E-06 MeV + - Nuclide has elastic S(a,b) channel between 1.00E-11 and 3.88E-06 MeV + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 4 reaction channels + - 2 special reactions + - 1 transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 4 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 102 Q = 2.22460E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,gamma) + 3 MT = 1004 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : S(a,b) inelastic scattering + 4 MT = 1002 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : S(a,b) elastic scattering + + 2 special reactions: + + 1 MT = 204 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total deuteron production + 2 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + + Nuclide 3 / 1657 : 1002.82c -- deuterium (H-2) + + Pointers : 50347 25146 + Primary type : Transport + Nuclide ZAI : 10020 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/H2.ACE + Atomic weight (AW) : 2.01410 + Atomic weight ratio (AWR) : 1.99680 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 1.50000E+02 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 3 reaction channels + - 3 special reactions + - 2 transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -2.22500E+00 MeV Emin = 3.33929E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82s : (n,2n) + 3 MT = 102 Q = 6.25740E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,gamma) + + 3 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.33929E+00 MeV : total proton production + 2 MT = 205 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total triton production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + + Nuclide 4 / 1657 : 1003.82c -- tritium (H-3) + + Pointers : 50896 25445 + Primary type : Transport + Nuclide ZAI : 10030 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/H3.ACE + Atomic weight (AW) : 3.01605 + Atomic weight ratio (AWR) : 2.99014 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 3.89E+08 seconds (12.3 years) + Specific ingestion toxicity : 4.20E-11 Sv/Bq + Specific inhalation toxicity : 2.60E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 3 reaction channels + - 3 special reactions + - 2 transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.25760E+00 MeV Emin = 8.35035E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,2n) + 3 MT = 17 Q = -8.47500E+00 MeV Emin = 1.13093E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,3n) + + 3 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.13093E+01 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.35035E+00 MeV : total deuteron production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 2.00000E-05 MeV : damage-energy production + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.85710E-02 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : beta- + + Nuclide 5 / 1657 : 2003.82c -- helium 3 (He-3) + + Pointers : 51551 25491 + Primary type : Transport + Nuclide ZAI : 20030 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/He3.ACE + Atomic weight (AW) : 3.01493 + Atomic weight ratio (AWR) : 2.98903 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 4 reaction channels + - 5 special reactions + - 3 transmutation reactions + - 2 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 4 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 102 Q = 2.05778E+01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,gamma) + 3 MT = 103 Q = 7.63752E-01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,p) + 4 MT = 104 Q = -3.26895E+00 MeV Emin = 4.36261E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + + 2 additional transport branches: + + 1 MT = 103 Q = 7.63752E-01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -3.26895E+00 MeV Emin = 4.36261E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + + 5 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 4.36261E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + + Nuclide 6 / 1657 : 2004.82c -- helium 4 (He-4) + + Pointers : 52465 25537 + Primary type : Transport + Nuclide ZAI : 20040 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/He4.ACE + Atomic weight (AW) : 4.00258 + Atomic weight ratio (AWR) : 3.96820 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 1 reaction channels + - 1 special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + 1 reaction channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + + 1 special reaction: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 3.50000E-05 MeV : damage-energy production + + Nuclide 7 / 1657 : 3006.82c -- lithium 6 (Li-6) + + Pointers : 53299 27423 + Primary type : Transport + Nuclide ZAI : 30060 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Li6.ACE + Atomic weight (AW) : 6.01507 + Atomic weight ratio (AWR) : 5.96340 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 36 reaction channels + - 6 special reactions + - 4 transmutation reactions + - 3 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 36 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 24 Q = -3.69800E+00 MeV Emin = 4.31812E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,2nalpha) + 3 MT = 51 Q = -1.50000E+00 MeV Emin = 1.70000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 4 MT = 52 Q = -2.00000E+00 MeV Emin = 2.33540E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 5 MT = 53 Q = -2.18500E+00 MeV Emin = 2.55140E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 6 MT = 54 Q = -2.50000E+00 MeV Emin = 2.91922E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 7 MT = 55 Q = -3.00000E+00 MeV Emin = 3.50310E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 8 MT = 56 Q = -3.50000E+00 MeV Emin = 4.08692E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 9 MT = 57 Q = -3.56200E+00 MeV Emin = 4.15931E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 10 MT = 58 Q = -4.00000E+00 MeV Emin = 4.67080E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 11 MT = 59 Q = -4.50000E+00 MeV Emin = 5.25460E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 12 MT = 60 Q = -5.00000E+00 MeV Emin = 5.83845E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 13 MT = 61 Q = -5.50000E+00 MeV Emin = 6.42230E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 14 MT = 62 Q = -6.00000E+00 MeV Emin = 7.00614E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 15 MT = 63 Q = -6.50000E+00 MeV Emin = 7.59000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 16 MT = 64 Q = -7.00000E+00 MeV Emin = 8.17383E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 17 MT = 65 Q = -7.50000E+00 MeV Emin = 8.75770E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 18 MT = 66 Q = -8.00000E+00 MeV Emin = 9.34152E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 19 MT = 67 Q = -8.50000E+00 MeV Emin = 9.92536E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 20 MT = 68 Q = -9.00000E+00 MeV Emin = 1.05092E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 21 MT = 69 Q = -9.50000E+00 MeV Emin = 1.10931E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 22 MT = 70 Q = -1.00000E+01 MeV Emin = 1.16770E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 23 MT = 71 Q = -1.05000E+01 MeV Emin = 1.22610E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 24 MT = 72 Q = -1.10000E+01 MeV Emin = 1.28450E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 25 MT = 73 Q = -1.15000E+01 MeV Emin = 1.34284E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 26 MT = 74 Q = -1.20000E+01 MeV Emin = 1.40123E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 27 MT = 75 Q = -1.25000E+01 MeV Emin = 1.45961E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 28 MT = 76 Q = -1.30000E+01 MeV Emin = 1.51800E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 29 MT = 77 Q = -1.35000E+01 MeV Emin = 1.57640E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 27. excited state + 30 MT = 78 Q = -1.40000E+01 MeV Emin = 1.63480E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 28. excited state + 31 MT = 79 Q = -1.45000E+01 MeV Emin = 1.69315E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 29. excited state + 32 MT = 80 Q = -1.50000E+01 MeV Emin = 1.75154E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 30. excited state + 33 MT = 81 Q = -1.55000E+01 MeV Emin = 1.80992E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 31. excited state + 34 MT = 102 Q = 7.25060E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 3007.82c : (n,gamma) + 35 MT = 103 Q = -2.72730E+00 MeV Emin = 3.18464E+00 MeV frac = 1.00000E+00 Product nuclide = 20060 : (n,p) + 36 MT = 105 Q = 4.78380E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,t) + + 3 additional transport branches: + + 1 MT = 24 Q = -3.69800E+00 MeV Emin = 4.31812E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,2nalpha) + 2 MT = 103 Q = -2.72730E+00 MeV Emin = 3.18464E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 105 Q = 4.78380E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.18464E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.70000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 1.70000E+00 MeV : total inelastic scattering + + Nuclide 8 / 1657 : 3007.82c -- lithium 7 (Li-7) + + Pointers : 56695 27469 + Primary type : Transport + Nuclide ZAI : 30070 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Li7.ACE + Atomic weight (AW) : 7.01600 + Atomic weight ratio (AWR) : 6.95573 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 11 reaction channels + - 6 special reactions + - 6 transmutation reactions + - 4 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 11 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.25050E+00 MeV Emin = 8.29288E+00 MeV frac = 1.00000E+00 Product nuclide = 3006.82c : (n,2n) + 3 MT = 24 Q = -8.72400E+00 MeV Emin = 9.97823E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,2nalpha) + 4 MT = 25 Q = -1.09486E+01 MeV Emin = 1.25227E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,3nalpha) + 5 MT = 28 Q = -7.75320E+00 MeV Emin = 8.86790E+00 MeV frac = 1.00000E+00 Product nuclide = 20060 : (n,np) + 6 MT = 51 Q = -4.77610E-01 MeV Emin = 5.43750E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -4.63000E+00 MeV Emin = 5.29564E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -6.68000E+00 MeV Emin = 7.64036E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 91 Q = -2.46670E+00 MeV Emin = 3.14540E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 10 MT = 102 Q = 2.03280E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 30080 : (n,gamma) + 11 MT = 104 Q = -7.75320E+00 MeV Emin = 8.86790E+00 MeV frac = 1.00000E+00 Product nuclide = 20060 : (n,d) + + 4 additional transport branches: + + 1 MT = 24 Q = -8.72400E+00 MeV Emin = 9.97823E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,2nalpha) + 2 MT = 25 Q = -1.09486E+01 MeV Emin = 1.25227E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,3nalpha) + 3 MT = 28 Q = -7.75320E+00 MeV Emin = 8.86790E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 4 MT = 104 Q = -7.75320E+00 MeV Emin = 8.86790E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 8.86790E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.86790E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 5.29564E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 5.29564E+00 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 5.43750E-01 MeV : total inelastic scattering + + Nuclide 9 / 1657 : 4009.82c -- beryllium 9 (Be-9) + + Pointers : 59623 20017 + Primary type : Transport + Nuclide ZAI : 40090 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Be9.ACE + Atomic weight (AW) : 9.01220 + Atomic weight ratio (AWR) : 8.93478 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 22 reaction channels + - 5 special reactions + - 21 transmutation reactions + - 4 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 22 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 875 Q = -1.68400E+00 MeV Emin = 2.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 40080 : (n,2n) to ground state + 3 MT = 876 Q = -2.42940E+00 MeV Emin = 2.70130E+00 MeV frac = 1.00000E+00 Product nuclide = 40080 : (n,2n) to 1. excited state + 4 MT = 877 Q = -2.78000E+00 MeV Emin = 3.09114E+00 MeV frac = 1.00000E+00 Product nuclide = 40080 : (n,2n) to 2. excited state + 5 MT = 878 Q = -3.04900E+00 MeV Emin = 3.39030E+00 MeV frac = 1.00000E+00 Product nuclide = 40080 : (n,2n) to 3. excited state + 6 MT = 879 Q = -4.70400E+00 MeV Emin = 5.23050E+00 MeV frac = 1.00000E+00 Product nuclide = 40080 : (n,2n) to 4. excited state + 7 MT = 880 Q = -5.59000E+00 MeV Emin = 6.21565E+00 MeV frac = 1.00000E+00 Product nuclide = 40080 : (n,2n) to 5. excited state + 8 MT = 881 Q = -6.38000E+00 MeV Emin = 7.09410E+00 MeV frac = 1.00000E+00 Product nuclide = 40080 : (n,2n) to 6. excited state + 9 MT = 882 Q = -6.76000E+00 MeV Emin = 7.51660E+00 MeV frac = 1.00000E+00 Product nuclide = 40080 : (n,2n) to 7. excited state + 10 MT = 883 Q = -7.94000E+00 MeV Emin = 8.82870E+00 MeV frac = 1.00000E+00 Product nuclide = 40080 : (n,2n) to 8. excited state + 11 MT = 884 Q = -1.12830E+01 MeV Emin = 1.25460E+01 MeV frac = 1.00000E+00 Product nuclide = 40080 : (n,2n) to 9. excited state + 12 MT = 885 Q = -1.18100E+01 MeV Emin = 1.31320E+01 MeV frac = 1.00000E+00 Product nuclide = 40080 : (n,2n) to 10. excited state + 13 MT = 886 Q = -2.39700E+00 MeV Emin = 2.80000E+00 MeV frac = 1.00000E+00 Product nuclide = 40080 : (n,2n) to 11. excited state + 14 MT = 887 Q = -4.00000E+00 MeV Emin = 4.44770E+00 MeV frac = 1.00000E+00 Product nuclide = 40080 : (n,2n) to 12. excited state + 15 MT = 888 Q = -3.35000E+00 MeV Emin = 3.72494E+00 MeV frac = 1.00000E+00 Product nuclide = 40080 : (n,2n) to 13. excited state + 16 MT = 889 Q = -1.66540E+00 MeV Emin = 1.86000E+00 MeV frac = 1.00000E+00 Product nuclide = 40080 : (n,2n) to 14. excited state + 17 MT = 890 Q = -2.46360E+00 MeV Emin = 2.73933E+00 MeV frac = 1.00000E+00 Product nuclide = 40080 : (n,2n) to 15. excited state + 18 MT = 102 Q = 6.81300E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 40100 : (n,gamma) + 19 MT = 103 Q = -1.28300E+01 MeV Emin = 1.42700E+01 MeV frac = 1.00000E+00 Product nuclide = 30090 : (n,p) + 20 MT = 104 Q = -1.46600E+01 MeV Emin = 1.63010E+01 MeV frac = 1.00000E+00 Product nuclide = 30080 : (n,d) + 21 MT = 105 Q = -1.04400E+01 MeV Emin = 1.16085E+01 MeV frac = 1.00000E+00 Product nuclide = 3007.82c : (n,t) + 22 MT = 107 Q = -6.00000E-01 MeV Emin = 6.65000E-01 MeV frac = 1.00000E+00 Product nuclide = 20060 : (n,alpha) + + 4 additional transport branches: + + 1 MT = 103 Q = -1.28300E+01 MeV Emin = 1.42700E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -1.46600E+01 MeV Emin = 1.63010E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -1.04400E+01 MeV Emin = 1.16085E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 107 Q = -6.00000E-01 MeV Emin = 6.65000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 5 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.42700E+01 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.63010E+01 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.16085E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 6.65000E-01 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + + Nuclide 10 / 1657 : 5010.82c -- boron 10 (B-10) + + Pointers : 63275 19373 + Primary type : Transport + Nuclide ZAI : 50100 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/B10.ACE + Atomic weight (AW) : 10.01294 + Atomic weight ratio (AWR) : 9.92692 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 41 reaction channels + - 14 special reactions + - 5 transmutation reactions + - 4 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 41 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -7.18350E-01 MeV Emin = 7.70357E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -1.74015E+00 MeV Emin = 1.91500E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -2.15430E+00 MeV Emin = 2.37132E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -3.58710E+00 MeV Emin = 3.94845E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -4.77400E+00 MeV Emin = 5.25491E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -5.11030E+00 MeV Emin = 5.62509E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 57 Q = -5.16390E+00 MeV Emin = 5.68409E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 9 MT = 58 Q = -5.18000E+00 MeV Emin = 5.70181E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 10 MT = 59 Q = -5.91950E+00 MeV Emin = 6.51581E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 11 MT = 60 Q = -6.02500E+00 MeV Emin = 6.63194E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 12 MT = 61 Q = -6.12720E+00 MeV Emin = 6.74443E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 13 MT = 62 Q = -6.50000E+00 MeV Emin = 7.15500E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 14 MT = 63 Q = -7.00000E+00 MeV Emin = 7.70515E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 15 MT = 64 Q = -7.50000E+00 MeV Emin = 8.25600E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 16 MT = 65 Q = -8.00000E+00 MeV Emin = 8.80600E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 17 MT = 66 Q = -8.50000E+00 MeV Emin = 9.35626E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 18 MT = 67 Q = -9.00000E+00 MeV Emin = 9.90700E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 19 MT = 68 Q = -9.50000E+00 MeV Emin = 1.04570E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 20 MT = 69 Q = -1.00000E+01 MeV Emin = 1.10074E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 21 MT = 70 Q = -1.05000E+01 MeV Emin = 1.15580E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 22 MT = 71 Q = -1.10000E+01 MeV Emin = 1.21081E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 23 MT = 72 Q = -1.15000E+01 MeV Emin = 1.26585E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 24 MT = 73 Q = -1.20000E+01 MeV Emin = 1.32090E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 25 MT = 74 Q = -1.25000E+01 MeV Emin = 1.37592E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 26 MT = 75 Q = -1.30000E+01 MeV Emin = 1.43100E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 27 MT = 76 Q = -1.35000E+01 MeV Emin = 1.48600E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 28 MT = 77 Q = -1.40000E+01 MeV Emin = 1.54103E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 27. excited state + 29 MT = 78 Q = -1.45000E+01 MeV Emin = 1.59610E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 28. excited state + 30 MT = 79 Q = -1.50000E+01 MeV Emin = 1.65111E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 29. excited state + 31 MT = 80 Q = -1.55000E+01 MeV Emin = 1.70614E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 30. excited state + 32 MT = 81 Q = -1.60000E+01 MeV Emin = 1.76120E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 31. excited state + 33 MT = 82 Q = -1.65000E+01 MeV Emin = 1.81622E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 32. excited state + 34 MT = 83 Q = -1.70000E+01 MeV Emin = 1.87130E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 33. excited state + 35 MT = 84 Q = -1.75000E+01 MeV Emin = 1.92630E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 34. excited state + 36 MT = 85 Q = -1.80000E+01 MeV Emin = 1.98133E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 35. excited state + 37 MT = 102 Q = 1.14560E+01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 5011.82c : (n,gamma) + 38 MT = 103 Q = 2.26241E-01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 40100 : (n,p) + 39 MT = 104 Q = -4.36100E+00 MeV Emin = 4.80031E+00 MeV frac = 1.00000E+00 Product nuclide = 4009.82c : (n,d) + 40 MT = 107 Q = 2.79000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 3007.82c : (n,alpha) + 41 MT = 113 Q = 3.24000E-01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t2alpha) + + 4 additional transport branches: + + 1 MT = 103 Q = 2.26241E-01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -4.36100E+00 MeV Emin = 4.80031E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 107 Q = 2.79000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 4 MT = 113 Q = 3.24000E-01 MeV Emin = 1.00000E-11 MeV frac = 2.00000E+00 Product nuclide = 2004.82c : (n,t2alpha) + + 14 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 4.80031E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 600 Q = 2.26241E-01 MeV Emin = 1.00000E-11 MeV : (n,p) to ground state + 7 MT = 601 Q = -3.14179E+00 MeV Emin = 3.45828E+00 MeV : (n,p1) + 8 MT = 602 Q = -5.73215E+00 MeV Emin = 6.30959E+00 MeV : (n,p2) + 9 MT = 603 Q = -5.73366E+00 MeV Emin = 6.31125E+00 MeV : (n,p3) + 10 MT = 604 Q = -5.95306E+00 MeV Emin = 6.55275E+00 MeV : (n,p4) + 11 MT = 605 Q = -6.03706E+00 MeV Emin = 6.64521E+00 MeV : (n,p5) + 12 MT = 800 Q = 2.79000E+00 MeV Emin = 1.00000E-11 MeV : (n,alpha) to ground state + 13 MT = 801 Q = 2.31239E+00 MeV Emin = 1.00000E-11 MeV : (n,a1) + 14 MT = 4 Q = 0.00000E+00 MeV Emin = 7.70357E-01 MeV : total inelastic scattering + + Nuclide 11 / 1657 : 5011.82c -- boron 11 (B-11) + + Pointers : 67693 19419 + Primary type : Transport + Nuclide ZAI : 50110 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/B11.ACE + Atomic weight (AW) : 11.00928 + Atomic weight ratio (AWR) : 10.91470 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 19 reaction channels + - 5 special reactions + - 7 transmutation reactions + - 5 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 19 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.14541E+01 MeV Emin = 1.25036E+01 MeV frac = 1.00000E+00 Product nuclide = 5010.82c : (n,2n) + 3 MT = 22 Q = -8.66370E+00 MeV Emin = 9.45750E+00 MeV frac = 1.00000E+00 Product nuclide = 3007.82c : (n,nalpha) + 4 MT = 28 Q = -1.12280E+01 MeV Emin = 1.22567E+01 MeV frac = 1.00000E+00 Product nuclide = 40100 : (n,np) + 5 MT = 51 Q = -2.12469E+00 MeV Emin = 2.31935E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -4.44489E+00 MeV Emin = 4.85213E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -5.02031E+00 MeV Emin = 5.48027E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -6.74290E+00 MeV Emin = 7.36070E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -6.79180E+00 MeV Emin = 7.41410E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -7.28551E+00 MeV Emin = 7.95301E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -7.97784E+00 MeV Emin = 8.70880E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -8.56030E+00 MeV Emin = 9.34460E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -8.92020E+00 MeV Emin = 9.73750E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -9.18500E+00 MeV Emin = 1.00270E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 91 Q = -9.18500E+00 MeV Emin = 1.00270E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 16 MT = 102 Q = 3.36987E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 50120 : (n,gamma) + 17 MT = 103 Q = -1.07237E+01 MeV Emin = 1.17062E+01 MeV frac = 1.00000E+00 Product nuclide = 40110 : (n,p) + 18 MT = 105 Q = -9.55824E+00 MeV Emin = 1.04340E+01 MeV frac = 1.00000E+00 Product nuclide = 4009.82c : (n,t) + 19 MT = 107 Q = -6.63095E+00 MeV Emin = 7.23850E+00 MeV frac = 1.00000E+00 Product nuclide = 30080 : (n,alpha) + + 5 additional transport branches: + + 1 MT = 22 Q = -8.66370E+00 MeV Emin = 9.45750E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.12280E+01 MeV Emin = 1.22567E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -1.07237E+01 MeV Emin = 1.17062E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 105 Q = -9.55824E+00 MeV Emin = 1.04340E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 5 MT = 107 Q = -6.63095E+00 MeV Emin = 7.23850E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 5 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.17062E+01 MeV : total proton production + 2 MT = 205 Q = 0.00000E+00 MeV Emin = 1.04340E+01 MeV : total triton production + 3 MT = 207 Q = 0.00000E+00 MeV Emin = 7.23850E+00 MeV : total alpha production + 4 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 5 MT = 4 Q = 0.00000E+00 MeV Emin = 2.31935E+00 MeV : total inelastic scattering + + Nuclide 12 / 1657 : 6000.82c -- natural carbon (C-nat) + + Pointers : 3496705 20339 + Primary type : Transport + Nuclide ZAI : 60000 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/C0.ACE + Atomic weight (AW) : 12.00110 + Atomic weight ratio (AWR) : 11.89800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 1.50000E+02 + Half-life : N/A + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is not involved in burnup calculation + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has no decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 20 reaction channels + - 5 special reactions + - No transmutation reactions + - 4 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + 20 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 : elastic scattering + 2 MT = 5 Q = 0.00000E+00 MeV Emin = 2.00000E+01 MeV frac = 1.00000E+00 : anything + 3 MT = 28 Q = -1.59570E+01 MeV Emin = 1.72982E+01 MeV frac = 1.00000E+00 : (n,np) + 4 MT = 51 Q = -4.43900E+00 MeV Emin = 4.81209E+00 MeV frac = 1.00000E+00 : inelastic scatt. to 1. excited state + 5 MT = 52 Q = -7.65300E+00 MeV Emin = 8.29622E+00 MeV frac = 1.00000E+00 : inelastic scatt. to 2. excited state + 6 MT = 53 Q = -9.63800E+00 MeV Emin = 1.04481E+01 MeV frac = 1.00000E+00 : inelastic scatt. to 3. excited state + 7 MT = 54 Q = -1.08000E+01 MeV Emin = 1.17080E+01 MeV frac = 1.00000E+00 : inelastic scatt. to 4. excited state + 8 MT = 55 Q = -1.18000E+01 MeV Emin = 1.27920E+01 MeV frac = 1.00000E+00 : inelastic scatt. to 5. excited state + 9 MT = 56 Q = -1.27000E+01 MeV Emin = 1.37674E+01 MeV frac = 1.00000E+00 : inelastic scatt. to 6. excited state + 10 MT = 57 Q = -1.33500E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 : inelastic scatt. to 7. excited state + 11 MT = 58 Q = -1.40800E+01 MeV Emin = 1.52634E+01 MeV frac = 1.00000E+00 : inelastic scatt. to 8. excited state + 12 MT = 59 Q = -1.50800E+01 MeV Emin = 1.63474E+01 MeV frac = 1.00000E+00 : inelastic scatt. to 9. excited state + 13 MT = 60 Q = -1.60800E+01 MeV Emin = 1.74315E+01 MeV frac = 1.00000E+00 : inelastic scatt. to 10. excited state + 14 MT = 61 Q = -1.70800E+01 MeV Emin = 1.85160E+01 MeV frac = 1.00000E+00 : inelastic scatt. to 11. excited state + 15 MT = 62 Q = -1.80800E+01 MeV Emin = 1.96000E+01 MeV frac = 1.00000E+00 : inelastic scatt. to 12. excited state + 16 MT = 91 Q = -7.27500E+00 MeV Emin = 7.88645E+00 MeV frac = 1.00000E+00 : inelastic scattering to continuum + 17 MT = 102 Q = 4.94700E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 : (n,gamma) + 18 MT = 103 Q = -1.25880E+01 MeV Emin = 1.44720E+01 MeV frac = 1.00000E+00 : (n,p) + 19 MT = 104 Q = -1.37330E+01 MeV Emin = 1.52630E+01 MeV frac = 1.00000E+00 : (n,d) + 20 MT = 107 Q = -5.70200E+00 MeV Emin = 6.18124E+00 MeV frac = 1.00000E+00 : (n,alpha) + + 4 additional transport branches: + + 1 MT = 28 Q = -1.59570E+01 MeV Emin = 1.72982E+01 MeV frac = 1.00000E+00 : (n,np) + 2 MT = 103 Q = -1.25880E+01 MeV Emin = 1.44720E+01 MeV frac = 1.00000E+00 : (n,p) + 3 MT = 104 Q = -1.37330E+01 MeV Emin = 1.52630E+01 MeV frac = 1.00000E+00 : (n,d) + 4 MT = 107 Q = -5.70200E+00 MeV Emin = 6.18124E+00 MeV frac = 1.00000E+00 : (n,alpha) + + 5 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.44720E+01 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.52630E+01 MeV : total deuteron production + 3 MT = 207 Q = 0.00000E+00 MeV Emin = 6.18124E+00 MeV : total alpha production + 4 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 5 MT = 4 Q = 0.00000E+00 MeV Emin = 4.81209E+00 MeV : total inelastic scattering + + Nuclide 13 / 1657 : 7014.82c -- nitrogen 14 (N-14) + + Pointers : 71785 28159 + Primary type : Transport + Nuclide ZAI : 70140 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/N14.ACE + Atomic weight (AW) : 14.00307 + Atomic weight ratio (AWR) : 13.88278 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 1.50000E+02 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 36 reaction channels + - 30 special reactions + - 7 transmutation reactions + - 5 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 36 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 5 Q = 0.00000E+00 MeV Emin = 2.00000E+01 MeV frac = 1.00000E+00 Product nuclide = self : anything + 3 MT = 16 Q = -1.05535E+01 MeV Emin = 1.13137E+01 MeV frac = 1.00000E+00 Product nuclide = 70130 : (n,2n) + 4 MT = 51 Q = -2.31280E+00 MeV Emin = 2.47939E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 5 MT = 52 Q = -3.94810E+00 MeV Emin = 4.23249E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 6 MT = 53 Q = -4.91510E+00 MeV Emin = 5.26914E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 7 MT = 54 Q = -5.10589E+00 MeV Emin = 5.47368E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 8 MT = 55 Q = -5.69144E+00 MeV Emin = 6.10141E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 9 MT = 56 Q = -5.83425E+00 MeV Emin = 6.25450E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 10 MT = 57 Q = -6.20350E+00 MeV Emin = 6.65035E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 11 MT = 58 Q = -6.44617E+00 MeV Emin = 6.91050E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 12 MT = 59 Q = -7.02912E+00 MeV Emin = 7.53544E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 13 MT = 60 Q = -7.96690E+00 MeV Emin = 8.54077E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 14 MT = 61 Q = -8.06200E+00 MeV Emin = 8.64272E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 15 MT = 62 Q = -8.48990E+00 MeV Emin = 9.10145E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 16 MT = 63 Q = -8.75000E+00 MeV Emin = 9.38028E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 17 MT = 64 Q = -9.25000E+00 MeV Emin = 9.91630E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 18 MT = 65 Q = -9.75000E+00 MeV Emin = 1.04523E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 19 MT = 66 Q = -1.02500E+01 MeV Emin = 1.09883E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 20 MT = 67 Q = -1.07500E+01 MeV Emin = 1.15244E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 21 MT = 68 Q = -1.12500E+01 MeV Emin = 1.20604E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 22 MT = 69 Q = -1.17500E+01 MeV Emin = 1.25964E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 23 MT = 70 Q = -1.22500E+01 MeV Emin = 1.31324E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 24 MT = 71 Q = -1.27500E+01 MeV Emin = 1.36684E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 25 MT = 72 Q = -1.32500E+01 MeV Emin = 1.42044E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 26 MT = 73 Q = -1.40000E+01 MeV Emin = 1.50084E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 27 MT = 74 Q = -1.50000E+01 MeV Emin = 1.60805E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 28 MT = 75 Q = -1.60000E+01 MeV Emin = 1.71525E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 29 MT = 76 Q = -1.70000E+01 MeV Emin = 1.82246E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 30 MT = 77 Q = -1.80000E+01 MeV Emin = 1.92970E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 27. excited state + 31 MT = 102 Q = 1.08334E+01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 7015.82c : (n,gamma) + 32 MT = 103 Q = 6.25876E-01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 60140 : (n,p) + 33 MT = 104 Q = -5.32604E+00 MeV Emin = 5.70969E+00 MeV frac = 1.00000E+00 Product nuclide = 60130 : (n,d) + 34 MT = 105 Q = -4.01510E+00 MeV Emin = 4.30432E+00 MeV frac = 1.00000E+00 Product nuclide = 60120 : (n,t) + 35 MT = 107 Q = -1.58297E-01 MeV Emin = 2.75000E-01 MeV frac = 1.00000E+00 Product nuclide = 5011.82c : (n,alpha) + 36 MT = 108 Q = -8.82201E+00 MeV Emin = 9.45747E+00 MeV frac = 1.00000E+00 Product nuclide = 3007.82c : (n,2alpha) + + 5 additional transport branches: + + 1 MT = 103 Q = 6.25876E-01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -5.32604E+00 MeV Emin = 5.70969E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -4.01510E+00 MeV Emin = 4.30432E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 107 Q = -1.58297E-01 MeV Emin = 2.75000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 5 MT = 108 Q = -8.82201E+00 MeV Emin = 9.45747E+00 MeV frac = 2.00000E+00 Product nuclide = 2004.82c : (n,2alpha) + + 30 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.70969E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 4.30432E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 2.75000E-01 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 600 Q = 6.25876E-01 MeV Emin = 1.00000E-11 MeV : (n,p) to ground state + 7 MT = 601 Q = -5.46793E+00 MeV Emin = 5.86179E+00 MeV : (n,p1) + 8 MT = 602 Q = -5.96352E+00 MeV Emin = 6.39309E+00 MeV : (n,p2) + 9 MT = 603 Q = -6.10233E+00 MeV Emin = 6.54189E+00 MeV : (n,p3) + 10 MT = 604 Q = -6.27672E+00 MeV Emin = 6.72885E+00 MeV : (n,p4) + 11 MT = 605 Q = -6.38612E+00 MeV Emin = 6.84613E+00 MeV : (n,p5) + 12 MT = 606 Q = -6.71553E+00 MeV Emin = 7.19926E+00 MeV : (n,p6) + 13 MT = 650 Q = -5.32604E+00 MeV Emin = 5.70969E+00 MeV : (n,d) to ground state + 14 MT = 651 Q = -8.41545E+00 MeV Emin = 9.02163E+00 MeV : (n,d1) + 15 MT = 652 Q = -9.01055E+00 MeV Emin = 9.65959E+00 MeV : (n,d2) + 16 MT = 653 Q = -9.17985E+00 MeV Emin = 9.84109E+00 MeV : (n,d3) + 17 MT = 700 Q = -4.01510E+00 MeV Emin = 4.30432E+00 MeV : (n,t) to ground state + 18 MT = 701 Q = -8.45401E+00 MeV Emin = 9.06297E+00 MeV : (n,t1) + 19 MT = 800 Q = -1.58297E-01 MeV Emin = 2.75000E-01 MeV : (n,alpha) to ground state + 20 MT = 801 Q = -2.28299E+00 MeV Emin = 2.44744E+00 MeV : (n,a1) + 21 MT = 802 Q = -4.60319E+00 MeV Emin = 4.93476E+00 MeV : (n,a2) + 22 MT = 803 Q = -5.17861E+00 MeV Emin = 5.55163E+00 MeV : (n,a3) + 23 MT = 804 Q = -6.90120E+00 MeV Emin = 7.39830E+00 MeV : (n,a4) + 24 MT = 805 Q = -6.95010E+00 MeV Emin = 7.45073E+00 MeV : (n,a5) + 25 MT = 806 Q = -7.44381E+00 MeV Emin = 7.98000E+00 MeV : (n,a6) + 26 MT = 807 Q = -8.13614E+00 MeV Emin = 8.72220E+00 MeV : (n,a7) + 27 MT = 808 Q = -8.71860E+00 MeV Emin = 9.34661E+00 MeV : (n,a8) + 28 MT = 809 Q = -9.07850E+00 MeV Emin = 9.73244E+00 MeV : (n,a9) + 29 MT = 810 Q = -9.34330E+00 MeV Emin = 1.00163E+01 MeV : (n,a10) + 30 MT = 4 Q = 0.00000E+00 MeV Emin = 2.47939E+00 MeV : total inelastic scattering + + Nuclide 14 / 1657 : 7015.82c -- nitrogen 15 (N-15) + + Pointers : 77079 28205 + Primary type : Transport + Nuclide ZAI : 70150 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/N15.ACE + Atomic weight (AW) : 14.99986 + Atomic weight ratio (AWR) : 14.87100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 17 reaction channels + - 6 special reactions + - 8 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 17 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.08330E+01 MeV Emin = 1.15615E+01 MeV frac = 1.00000E+00 Product nuclide = 7014.82c : (n,2n) + 3 MT = 22 Q = -1.09910E+01 MeV Emin = 1.17301E+01 MeV frac = 1.00000E+00 Product nuclide = 5011.82c : (n,nalpha) + 4 MT = 28 Q = -1.02070E+01 MeV Emin = 1.08934E+01 MeV frac = 1.00000E+00 Product nuclide = 60140 : (n,np) + 5 MT = 51 Q = -5.27010E+00 MeV Emin = 5.62450E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -5.29880E+00 MeV Emin = 5.65512E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -6.32390E+00 MeV Emin = 6.74915E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -7.15510E+00 MeV Emin = 7.63625E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -7.30110E+00 MeV Emin = 7.79210E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -7.56710E+00 MeV Emin = 8.07595E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -8.31280E+00 MeV Emin = 8.87180E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 91 Q = -8.31280E+00 MeV Emin = 8.87180E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 13 MT = 102 Q = 2.49000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 70160 : (n,gamma) + 14 MT = 103 Q = -8.98930E+00 MeV Emin = 9.59380E+00 MeV frac = 1.00000E+00 Product nuclide = 60150 : (n,p) + 15 MT = 104 Q = -7.98280E+00 MeV Emin = 8.51960E+00 MeV frac = 1.00000E+00 Product nuclide = 60140 : (n,d) + 16 MT = 105 Q = -9.90200E+00 MeV Emin = 1.05680E+01 MeV frac = 1.00000E+00 Product nuclide = 60130 : (n,t) + 17 MT = 107 Q = -7.62150E+00 MeV Emin = 8.13401E+00 MeV frac = 1.00000E+00 Product nuclide = 50120 : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = -1.09910E+01 MeV Emin = 1.17301E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.02070E+01 MeV Emin = 1.08934E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -8.98930E+00 MeV Emin = 9.59380E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -7.98280E+00 MeV Emin = 8.51960E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -9.90200E+00 MeV Emin = 1.05680E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 107 Q = -7.62150E+00 MeV Emin = 8.13401E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 9.59380E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.51960E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.05680E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 8.13401E+00 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 5.62450E+00 MeV : total inelastic scattering + + Nuclide 15 / 1657 : 8016.82c -- oxygen 16 (O-16) + + Pointers : 80953 29355 + Primary type : Transport + Nuclide ZAI : 80160 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/O16.ACE + Atomic weight (AW) : 15.99492 + Atomic weight ratio (AWR) : 15.85751 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 1.50000E+02 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 25 reaction channels + - 45 special reactions + - 10 transmutation reactions + - 15 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 25 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 5 Q = 0.00000E+00 MeV Emin = 3.00000E+01 MeV frac = 1.00000E+00 Product nuclide = self : anything + 3 MT = 16 Q = -1.56638E+01 MeV Emin = 1.66516E+01 MeV frac = 1.00000E+00 Product nuclide = 80150 : (n,2n) + 4 MT = 22 Q = -7.16195E+00 MeV Emin = 7.61360E+00 MeV frac = 1.00000E+00 Product nuclide = 60120 : (n,nalpha) + 5 MT = 23 Q = -1.44368E+01 MeV Emin = 1.64100E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,n3alpha) + 6 MT = 28 Q = -1.21276E+01 MeV Emin = 1.28924E+01 MeV frac = 1.00000E+00 Product nuclide = 7015.82c : (n,np) + 7 MT = 32 Q = -2.07363E+01 MeV Emin = 2.20440E+01 MeV frac = 1.00000E+00 Product nuclide = cut: N-14 : (n,nd) + 8 MT = 41 Q = -2.29609E+01 MeV Emin = 2.44089E+01 MeV frac = 1.00000E+00 Product nuclide = cut: N-14 : (n,2np) + 9 MT = 44 Q = -2.23350E+01 MeV Emin = 2.37435E+01 MeV frac = 1.00000E+00 Product nuclide = cut: C-14 : (n,n2p) + 10 MT = 45 Q = -2.31192E+01 MeV Emin = 2.45771E+01 MeV frac = 1.00000E+00 Product nuclide = cut: B-11 : (n,npalpha) + 11 MT = 51 Q = -6.04940E+00 MeV Emin = 6.43089E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 12 MT = 52 Q = -6.12989E+00 MeV Emin = 6.51646E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 13 MT = 53 Q = -6.91710E+00 MeV Emin = 7.35330E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 14 MT = 54 Q = -7.11685E+00 MeV Emin = 7.56565E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 15 MT = 55 Q = -8.87190E+00 MeV Emin = 9.43138E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 16 MT = 56 Q = -1.09570E+01 MeV Emin = 1.16480E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 17 MT = 57 Q = -1.10800E+01 MeV Emin = 1.17787E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 18 MT = 91 Q = -9.58500E+00 MeV Emin = 1.01895E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 19 MT = 102 Q = 4.14342E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 8017.82c : (n,gamma) + 20 MT = 103 Q = -9.63680E+00 MeV Emin = 1.02445E+01 MeV frac = 1.00000E+00 Product nuclide = 70160 : (n,p) + 21 MT = 104 Q = -9.90300E+00 MeV Emin = 1.05275E+01 MeV frac = 1.00000E+00 Product nuclide = 7015.82c : (n,d) + 22 MT = 105 Q = -1.44790E+01 MeV Emin = 1.53921E+01 MeV frac = 1.00000E+00 Product nuclide = 7014.82c : (n,t) + 23 MT = 107 Q = -2.21430E+00 MeV Emin = 2.35532E+00 MeV frac = 1.00000E+00 Product nuclide = 60130 : (n,alpha) + 24 MT = 108 Q = -1.28632E+01 MeV Emin = 1.36744E+01 MeV frac = 1.00000E+00 Product nuclide = 4009.82c : (n,2alpha) + 25 MT = 112 Q = -1.97491E+01 MeV Emin = 2.09945E+01 MeV frac = 1.00000E+00 Product nuclide = cut: B-12 : (n,palpha) + + 15 additional transport branches: + + 1 MT = 22 Q = -7.16195E+00 MeV Emin = 7.61360E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 23 Q = -1.44368E+01 MeV Emin = 1.64100E+01 MeV frac = 3.00000E+00 Product nuclide = 2004.82c : (n,n3alpha) + 3 MT = 28 Q = -1.21276E+01 MeV Emin = 1.28924E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 4 MT = 32 Q = -2.07363E+01 MeV Emin = 2.20440E+01 MeV frac = 1.00000E+00 Product nuclide = cut: H-2 : (n,nd) + 5 MT = 41 Q = -2.29609E+01 MeV Emin = 2.44089E+01 MeV frac = 1.00000E+00 Product nuclide = cut: H-1 : (n,2np) + 6 MT = 44 Q = -2.23350E+01 MeV Emin = 2.37435E+01 MeV frac = 2.00000E+00 Product nuclide = cut: H-1 : (n,n2p) + 7 MT = 45 Q = -2.31192E+01 MeV Emin = 2.45771E+01 MeV frac = 1.00000E+00 Product nuclide = cut: He-4 : (n,npalpha) + 8 MT = 45 Q = -2.31192E+01 MeV Emin = 2.45771E+01 MeV frac = 1.00000E+00 Product nuclide = cut: H-1 : (n,npalpha) + 9 MT = 103 Q = -9.63680E+00 MeV Emin = 1.02445E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 10 MT = 104 Q = -9.90300E+00 MeV Emin = 1.05275E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 11 MT = 105 Q = -1.44790E+01 MeV Emin = 1.53921E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 12 MT = 107 Q = -2.21430E+00 MeV Emin = 2.35532E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 13 MT = 108 Q = -1.28632E+01 MeV Emin = 1.36744E+01 MeV frac = 2.00000E+00 Product nuclide = 2004.82c : (n,2alpha) + 14 MT = 112 Q = -1.97491E+01 MeV Emin = 2.09945E+01 MeV frac = 1.00000E+00 Product nuclide = cut: He-4 : (n,palpha) + 15 MT = 112 Q = -1.97491E+01 MeV Emin = 2.09945E+01 MeV frac = 1.00000E+00 Product nuclide = cut: H-1 : (n,palpha) + + 45 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.02445E+01 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.05275E+01 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.53921E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 2.35532E+00 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 600 Q = -9.63680E+00 MeV Emin = 1.02445E+01 MeV : (n,p) to ground state + 7 MT = 601 Q = -9.75690E+00 MeV Emin = 1.03722E+01 MeV : (n,p1) + 8 MT = 602 Q = -9.93380E+00 MeV Emin = 1.05602E+01 MeV : (n,p2) + 9 MT = 603 Q = -1.00343E+01 MeV Emin = 1.06671E+01 MeV : (n,p3) + 10 MT = 650 Q = -9.90300E+00 MeV Emin = 1.05275E+01 MeV : (n,d) to ground state + 11 MT = 651 Q = -1.51731E+01 MeV Emin = 1.61300E+01 MeV : (n,d1) + 12 MT = 652 Q = -1.52018E+01 MeV Emin = 1.61610E+01 MeV : (n,d2) + 13 MT = 653 Q = -1.62269E+01 MeV Emin = 1.72502E+01 MeV : (n,d3) + 14 MT = 654 Q = -1.70581E+01 MeV Emin = 1.81338E+01 MeV : (n,d4) + 15 MT = 655 Q = -1.72041E+01 MeV Emin = 1.82890E+01 MeV : (n,d5) + 16 MT = 656 Q = -1.74701E+01 MeV Emin = 1.85718E+01 MeV : (n,d6) + 17 MT = 657 Q = -1.82158E+01 MeV Emin = 1.93645E+01 MeV : (n,d7) + 18 MT = 658 Q = -1.84744E+01 MeV Emin = 1.96394E+01 MeV : (n,d8) + 19 MT = 659 Q = -1.89530E+01 MeV Emin = 2.01482E+01 MeV : (n,d9) + 20 MT = 660 Q = -1.90546E+01 MeV Emin = 2.02562E+01 MeV : (n,d10) + 21 MT = 661 Q = -1.90579E+01 MeV Emin = 2.02597E+01 MeV : (n,d11) + 22 MT = 662 Q = -1.91280E+01 MeV Emin = 2.03343E+01 MeV : (n,d12) + 23 MT = 663 Q = -1.96630E+01 MeV Emin = 2.09030E+01 MeV : (n,d13) + 24 MT = 664 Q = -1.97320E+01 MeV Emin = 2.09763E+01 MeV : (n,d14) + 25 MT = 665 Q = -1.98310E+01 MeV Emin = 2.10816E+01 MeV : (n,d15) + 26 MT = 666 Q = -1.99730E+01 MeV Emin = 2.12325E+01 MeV : (n,d16) + 27 MT = 667 Q = -2.03527E+01 MeV Emin = 2.16362E+01 MeV : (n,d17) + 28 MT = 668 Q = -2.04363E+01 MeV Emin = 2.17251E+01 MeV : (n,d18) + 29 MT = 669 Q = -2.05962E+01 MeV Emin = 2.18950E+01 MeV : (n,d19) + 30 MT = 700 Q = -1.44790E+01 MeV Emin = 1.53921E+01 MeV : (n,t) to ground state + 31 MT = 701 Q = -1.67918E+01 MeV Emin = 1.78507E+01 MeV : (n,t1) + 32 MT = 702 Q = -1.84271E+01 MeV Emin = 1.95892E+01 MeV : (n,t2) + 33 MT = 703 Q = -1.93941E+01 MeV Emin = 2.06171E+01 MeV : (n,t3) + 34 MT = 704 Q = -1.95849E+01 MeV Emin = 2.08200E+01 MeV : (n,t4) + 35 MT = 705 Q = -2.01704E+01 MeV Emin = 2.14424E+01 MeV : (n,t5) + 36 MT = 706 Q = -2.03132E+01 MeV Emin = 2.15942E+01 MeV : (n,t6) + 37 MT = 707 Q = -2.06825E+01 MeV Emin = 2.19868E+01 MeV : (n,t7) + 38 MT = 708 Q = -2.09252E+01 MeV Emin = 2.22448E+01 MeV : (n,t8) + 39 MT = 709 Q = -2.15081E+01 MeV Emin = 2.28645E+01 MeV : (n,t9) + 40 MT = 749 Q = -2.15081E+01 MeV Emin = 2.28645E+01 MeV : (n,t) to continuum + 41 MT = 800 Q = -2.21430E+00 MeV Emin = 2.35532E+00 MeV : (n,alpha) to ground state + 42 MT = 801 Q = -5.30500E+00 MeV Emin = 5.63954E+00 MeV : (n,a1) + 43 MT = 802 Q = -5.90010E+00 MeV Emin = 6.27217E+00 MeV : (n,a2) + 44 MT = 803 Q = -6.06940E+00 MeV Emin = 6.45215E+00 MeV : (n,a3) + 45 MT = 4 Q = 0.00000E+00 MeV Emin = 6.43089E+00 MeV : total inelastic scattering + + Nuclide 16 / 1657 : 8017.82c -- oxygen 17 (O-17) + + Pointers : 87269 29401 + Primary type : Transport + Nuclide ZAI : 80170 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/O17.ACE + Atomic weight (AW) : 16.99913 + Atomic weight ratio (AWR) : 16.85310 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 21 reaction channels + - 5 special reactions + - 7 transmutation reactions + - 5 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 21 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -4.14430E+00 MeV Emin = 7.76000E+00 MeV frac = 1.00000E+00 Product nuclide = 8016.82c : (n,2n) + 3 MT = 22 Q = -6.35300E+00 MeV Emin = 7.76000E+00 MeV frac = 1.00000E+00 Product nuclide = 60130 : (n,nalpha) + 4 MT = 28 Q = -1.37810E+01 MeV Emin = 1.45987E+01 MeV frac = 1.00000E+00 Product nuclide = 70160 : (n,np) + 5 MT = 51 Q = -8.70800E-01 MeV Emin = 9.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -3.05500E+00 MeV Emin = 3.23627E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -3.84100E+00 MeV Emin = 4.06980E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -4.55300E+00 MeV Emin = 4.82316E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -5.08600E+00 MeV Emin = 5.38779E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -5.21500E+00 MeV Emin = 5.52444E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -5.38000E+00 MeV Emin = 5.69923E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -5.69800E+00 MeV Emin = 6.03610E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -5.73400E+00 MeV Emin = 6.07423E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -5.87000E+00 MeV Emin = 6.21830E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -5.94000E+00 MeV Emin = 6.29246E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -6.35700E+00 MeV Emin = 6.73420E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 91 Q = -6.35700E+00 MeV Emin = 6.90000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 18 MT = 102 Q = 8.04700E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 80180 : (n,gamma) + 19 MT = 103 Q = -7.89600E+00 MeV Emin = 8.36452E+00 MeV frac = 1.00000E+00 Product nuclide = 70170 : (n,p) + 20 MT = 104 Q = -1.15550E+01 MeV Emin = 1.22412E+01 MeV frac = 1.00000E+00 Product nuclide = 70160 : (n,d) + 21 MT = 107 Q = 1.81940E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 60140 : (n,alpha) + + 5 additional transport branches: + + 1 MT = 22 Q = -6.35300E+00 MeV Emin = 7.76000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.37810E+01 MeV Emin = 1.45987E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -7.89600E+00 MeV Emin = 8.36452E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -1.15550E+01 MeV Emin = 1.22412E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 107 Q = 1.81940E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 5 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 8.36452E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.22412E+01 MeV : total deuteron production + 3 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 4 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 5 MT = 4 Q = 0.00000E+00 MeV Emin = 9.00000E-01 MeV : total inelastic scattering + + Nuclide 17 / 1657 : 9019.82c -- fluorine 19 (F-19) + + Pointers : 90379 23973 + Primary type : Transport + Nuclide ZAI : 90190 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/F19.ACE + Atomic weight (AW) : 18.99820 + Atomic weight ratio (AWR) : 18.83500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 31 reaction channels + - 6 special reactions + - 8 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 31 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.04310E+01 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 90180 : (n,2n) + 3 MT = 22 Q = -4.01290E+00 MeV Emin = 4.22600E+00 MeV frac = 1.00000E+00 Product nuclide = 7015.82c : (n,nalpha) + 4 MT = 28 Q = -7.99300E+00 MeV Emin = 8.41740E+00 MeV frac = 1.00000E+00 Product nuclide = 80180 : (n,np) + 5 MT = 51 Q = -1.09900E-01 MeV Emin = 1.15125E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -1.97100E-01 MeV Emin = 2.05000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -1.34600E+00 MeV Emin = 1.41650E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -1.45900E+00 MeV Emin = 1.52000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -1.55400E+00 MeV Emin = 1.62825E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -2.78000E+00 MeV Emin = 2.92760E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -3.90700E+00 MeV Emin = 4.11443E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -3.99900E+00 MeV Emin = 4.21132E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -4.03200E+00 MeV Emin = 4.24610E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -4.37800E+00 MeV Emin = 4.61044E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -4.54900E+00 MeV Emin = 4.79052E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -4.55800E+00 MeV Emin = 4.80000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 63 Q = -4.64800E+00 MeV Emin = 4.89480E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 18 MT = 64 Q = -4.68300E+00 MeV Emin = 4.93163E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 19 MT = 65 Q = -5.10600E+00 MeV Emin = 5.37710E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 20 MT = 66 Q = -5.36600E+00 MeV Emin = 5.65090E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 21 MT = 67 Q = -5.43000E+00 MeV Emin = 5.71830E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 22 MT = 68 Q = -5.46400E+00 MeV Emin = 5.75410E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 23 MT = 69 Q = -5.49900E+00 MeV Emin = 5.79100E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 24 MT = 70 Q = -5.54000E+00 MeV Emin = 5.83413E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 25 MT = 71 Q = -5.62100E+00 MeV Emin = 5.91944E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 26 MT = 91 Q = -5.64000E+00 MeV Emin = 5.93944E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 27 MT = 102 Q = 6.60130E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 90200 : (n,gamma) + 28 MT = 103 Q = -4.03600E+00 MeV Emin = 4.25030E+00 MeV frac = 1.00000E+00 Product nuclide = 80190 : (n,p) + 29 MT = 104 Q = -5.76800E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 80180 : (n,d) + 30 MT = 105 Q = -7.55700E+00 MeV Emin = 9.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 8017.82c : (n,t) + 31 MT = 107 Q = -1.52300E+00 MeV Emin = 1.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 70160 : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = -4.01290E+00 MeV Emin = 4.22600E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -7.99300E+00 MeV Emin = 8.41740E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -4.03600E+00 MeV Emin = 4.25030E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -5.76800E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -7.55700E+00 MeV Emin = 9.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 107 Q = -1.52300E+00 MeV Emin = 1.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.25030E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.50000E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 1.60000E+00 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 1.15125E-01 MeV : total inelastic scattering + + Nuclide 18 / 1657 : 11022.82c -- sodium 22 (Na-22) + + Pointers : 94850 28251 + Primary type : Transport + Nuclide ZAI : 110220 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Na22.ACE + Atomic weight (AW) : 21.99444 + Atomic weight ratio (AWR) : 21.80550 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 8.21E+07 seconds (2.6 years) + Specific ingestion toxicity : 3.20E-09 Sv/Bq + Specific inhalation toxicity : 1.30E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 21 reaction channels + - 5 special reactions + - 8 transmutation reactions + - 6 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 21 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.05840E+01 MeV Emin = 1.10696E+01 MeV frac = 1.00000E+00 Product nuclide = 110210 : (n,2n) + 3 MT = 22 Q = -1.05180E+01 MeV Emin = 1.10004E+01 MeV frac = 1.00000E+00 Product nuclide = 90180 : (n,nalpha) + 4 MT = 28 Q = -6.69310E+00 MeV Emin = 7.00005E+00 MeV frac = 1.00000E+00 Product nuclide = 100210 : (n,np) + 5 MT = 51 Q = -5.83000E-01 MeV Emin = 6.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -6.57000E-01 MeV Emin = 6.57000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -8.90900E-01 MeV Emin = 9.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -1.52800E+00 MeV Emin = 1.57500E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -1.93700E+00 MeV Emin = 2.02583E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -1.95200E+00 MeV Emin = 2.04152E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -1.98400E+00 MeV Emin = 2.07499E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -2.21200E+00 MeV Emin = 2.31344E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -2.57200E+00 MeV Emin = 2.68995E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -2.96900E+00 MeV Emin = 3.10516E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -3.06000E+00 MeV Emin = 3.20033E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 91 Q = -3.36470E+00 MeV Emin = 3.51901E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 17 MT = 102 Q = 1.24200E+01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 11023.82c : (n,gamma) + 18 MT = 103 Q = 3.62500E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 100220 : (n,p) + 19 MT = 104 Q = -3.82460E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 100210 : (n,d) + 20 MT = 107 Q = 1.95000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 9019.82c : (n,alpha) + 21 MT = 108 Q = -2.06400E+00 MeV Emin = 2.15900E+00 MeV frac = 1.00000E+00 Product nuclide = 7015.82c : (n,2alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = -1.05180E+01 MeV Emin = 1.10004E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -6.69310E+00 MeV Emin = 7.00005E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = 3.62500E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -3.82460E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 107 Q = 1.95000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 108 Q = -2.06400E+00 MeV Emin = 2.15900E+00 MeV frac = 2.00000E+00 Product nuclide = 2004.82c : (n,2alpha) + + 5 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 4.00000E+00 MeV : total deuteron production + 3 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 4 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 5 MT = 4 Q = 0.00000E+00 MeV Emin = 6.00000E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 2 Q = 2.84302E+00 MeV frac = 1.00000E+00 Product nuclide = 100220 : EC/beta+ + + Nuclide 19 / 1657 : 11023.82c -- sodium 23 (Na-23) + + Pointers : 97473 28297 + Primary type : Transport + Nuclide ZAI : 110230 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Na23.ACE + Atomic weight (AW) : 22.98980 + Atomic weight ratio (AWR) : 22.79230 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 35 reaction channels + - 4 special reactions + - 6 transmutation reactions + - 5 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 35 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.24180E+01 MeV Emin = 1.29628E+01 MeV frac = 1.00000E+00 Product nuclide = 11022.82c : (n,2n) + 3 MT = 22 Q = -1.04680E+01 MeV Emin = 1.09273E+01 MeV frac = 1.00000E+00 Product nuclide = 9019.82c : (n,nalpha) + 4 MT = 28 Q = -8.79310E+00 MeV Emin = 9.17889E+00 MeV frac = 1.00000E+00 Product nuclide = 100220 : (n,np) + 5 MT = 51 Q = -4.39900E-01 MeV Emin = 4.58754E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -2.07640E+00 MeV Emin = 2.16750E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -2.39090E+00 MeV Emin = 2.49580E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -2.63980E+00 MeV Emin = 2.75562E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -2.70370E+00 MeV Emin = 2.82232E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -2.98240E+00 MeV Emin = 3.11325E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -3.67830E+00 MeV Emin = 3.83968E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -3.84800E+00 MeV Emin = 4.01683E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -3.91470E+00 MeV Emin = 4.08646E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -4.43200E+00 MeV Emin = 4.62645E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -4.77560E+00 MeV Emin = 4.98513E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -5.38000E+00 MeV Emin = 5.61605E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 63 Q = -5.53600E+00 MeV Emin = 5.77889E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 18 MT = 64 Q = -5.74100E+00 MeV Emin = 5.99288E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 19 MT = 65 Q = -5.76600E+00 MeV Emin = 6.01898E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 20 MT = 66 Q = -5.93100E+00 MeV Emin = 6.19122E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 21 MT = 67 Q = -5.96700E+00 MeV Emin = 6.22880E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 22 MT = 68 Q = -6.04300E+00 MeV Emin = 6.30813E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 23 MT = 69 Q = -6.11700E+00 MeV Emin = 6.38538E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 24 MT = 70 Q = -6.19100E+00 MeV Emin = 6.46263E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 25 MT = 71 Q = -6.23600E+00 MeV Emin = 6.50960E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 26 MT = 72 Q = -6.30800E+00 MeV Emin = 6.58476E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 27 MT = 73 Q = -6.35060E+00 MeV Emin = 6.62923E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 28 MT = 74 Q = -6.57700E+00 MeV Emin = 6.86556E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 29 MT = 75 Q = -6.61700E+00 MeV Emin = 6.90732E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 30 MT = 76 Q = -6.73400E+00 MeV Emin = 7.02945E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 31 MT = 77 Q = -6.86800E+00 MeV Emin = 7.16933E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 27. excited state + 32 MT = 91 Q = -6.90000E+00 MeV Emin = 7.20273E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 33 MT = 102 Q = 6.95930E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 110240 : (n,gamma) + 34 MT = 103 Q = -3.59650E+00 MeV Emin = 3.75430E+00 MeV frac = 1.00000E+00 Product nuclide = 100230 : (n,p) + 35 MT = 107 Q = -3.86660E+00 MeV Emin = 4.03625E+00 MeV frac = 1.00000E+00 Product nuclide = 90200 : (n,alpha) + + 5 additional transport branches: + + 1 MT = 22 Q = -1.04680E+01 MeV Emin = 1.09273E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -8.79310E+00 MeV Emin = 9.17889E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 102 Q = 6.95930E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 110241 : (n,gamma) + 4 MT = 103 Q = -3.59650E+00 MeV Emin = 3.75430E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 107 Q = -3.86660E+00 MeV Emin = 4.03625E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 4 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.75430E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 4.03625E+00 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 4 MT = 4 Q = 0.00000E+00 MeV Emin = 4.58754E-01 MeV : total inelastic scattering + + Nuclide 20 / 1657 : 12024.82c -- magnesium 24 (Mg-24) + + Pointers : 103107 27607 + Primary type : Transport + Nuclide ZAI : 120240 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Mg24.ACE + Atomic weight (AW) : 23.98504 + Atomic weight ratio (AWR) : 23.77900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 19 reaction channels + - 4 special reactions + - 6 transmutation reactions + - 4 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 19 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.65306E+01 MeV Emin = 1.72258E+01 MeV frac = 1.00000E+00 Product nuclide = 120230 : (n,2n) + 3 MT = 22 Q = -9.31453E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 100200 : (n,nalpha) + 4 MT = 28 Q = -1.16915E+01 MeV Emin = 1.21832E+01 MeV frac = 1.00000E+00 Product nuclide = 11023.82c : (n,np) + 5 MT = 51 Q = -1.36860E+00 MeV Emin = 1.41439E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -4.11999E+00 MeV Emin = 4.29330E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -4.23839E+00 MeV Emin = 4.41664E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -5.23609E+00 MeV Emin = 5.45630E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -6.01029E+00 MeV Emin = 6.26306E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -6.43219E+00 MeV Emin = 6.70270E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -7.34789E+00 MeV Emin = 7.65691E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -7.55299E+00 MeV Emin = 7.87063E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -7.61619E+00 MeV Emin = 7.93649E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -7.74719E+00 MeV Emin = 8.07300E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -7.81199E+00 MeV Emin = 8.14053E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 91 Q = -1.00000E+01 MeV Emin = 1.04206E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 17 MT = 102 Q = 7.33189E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 12025.82c : (n,gamma) + 18 MT = 103 Q = -4.73209E+00 MeV Emin = 4.93113E+00 MeV frac = 1.00000E+00 Product nuclide = 110240 : (n,p) + 19 MT = 107 Q = -2.55335E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 100210 : (n,alpha) + + 4 additional transport branches: + + 1 MT = 22 Q = -9.31453E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.16915E+01 MeV Emin = 1.21832E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -4.73209E+00 MeV Emin = 4.93113E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 107 Q = -2.55335E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 4 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.93113E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 4.00000E+00 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 4 MT = 4 Q = 0.00000E+00 MeV Emin = 1.41439E+00 MeV : total inelastic scattering + + Nuclide 21 / 1657 : 12025.82c -- magnesium 25 (Mg-25) + + Pointers : 105189 27653 + Primary type : Transport + Nuclide ZAI : 120250 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Mg25.ACE + Atomic weight (AW) : 24.98584 + Atomic weight ratio (AWR) : 24.77120 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 25 reaction channels + - 4 special reactions + - 6 transmutation reactions + - 4 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 25 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.33188E+00 MeV Emin = 7.62787E+00 MeV frac = 1.00000E+00 Product nuclide = 12024.82c : (n,2n) + 3 MT = 22 Q = -9.88523E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 100210 : (n,nalpha) + 4 MT = 28 Q = -1.20640E+01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 110240 : (n,np) + 5 MT = 51 Q = -5.85099E-01 MeV Emin = 6.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -9.74799E-01 MeV Emin = 1.00707E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -1.61180E+00 MeV Emin = 1.67243E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -1.96470E+00 MeV Emin = 2.04401E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -2.56380E+00 MeV Emin = 2.66730E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -2.73770E+00 MeV Emin = 2.84822E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -2.80110E+00 MeV Emin = 2.91418E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -3.40519E+00 MeV Emin = 3.54267E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -3.41369E+00 MeV Emin = 3.55151E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -3.90779E+00 MeV Emin = 4.06556E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -3.97069E+00 MeV Emin = 4.13100E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -4.05959E+00 MeV Emin = 4.22348E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 63 Q = -4.27699E+00 MeV Emin = 4.44966E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 18 MT = 64 Q = -4.35939E+00 MeV Emin = 4.53539E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 19 MT = 65 Q = -4.71139E+00 MeV Emin = 4.90160E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 20 MT = 66 Q = -4.72199E+00 MeV Emin = 4.91262E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 21 MT = 67 Q = -5.01219E+00 MeV Emin = 5.21454E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 22 MT = 91 Q = -7.99999E+00 MeV Emin = 8.32296E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 23 MT = 102 Q = 1.10933E+01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 12026.82c : (n,gamma) + 24 MT = 103 Q = -3.05303E+00 MeV Emin = 3.17628E+00 MeV frac = 1.00000E+00 Product nuclide = 110250 : (n,p) + 25 MT = 107 Q = 4.80349E-01 MeV Emin = 9.50000E-01 MeV frac = 1.00000E+00 Product nuclide = 100220 : (n,alpha) + + 4 additional transport branches: + + 1 MT = 22 Q = -9.88523E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.20640E+01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -3.05303E+00 MeV Emin = 3.17628E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 107 Q = 4.80349E-01 MeV Emin = 9.50000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 4 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.17628E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 9.50000E-01 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 4 MT = 4 Q = 0.00000E+00 MeV Emin = 6.00000E-01 MeV : total inelastic scattering + + Nuclide 22 / 1657 : 12026.82c -- magnesium 26 (Mg-26) + + Pointers : 107709 27699 + Primary type : Transport + Nuclide ZAI : 120260 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Mg26.ACE + Atomic weight (AW) : 25.98260 + Atomic weight ratio (AWR) : 25.75940 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 21 reaction channels + - 4 special reactions + - 6 transmutation reactions + - 4 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 21 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.10936E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 12025.82c : (n,2n) + 3 MT = 22 Q = -1.06132E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 100220 : (n,nalpha) + 4 MT = 28 Q = -1.41466E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 110250 : (n,np) + 5 MT = 51 Q = -1.80870E+00 MeV Emin = 1.68946E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -2.93840E+00 MeV Emin = 3.05247E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -3.58799E+00 MeV Emin = 3.72729E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -3.94049E+00 MeV Emin = 4.09347E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -4.31799E+00 MeV Emin = 4.48563E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -4.33199E+00 MeV Emin = 4.50017E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -4.34999E+00 MeV Emin = 4.51887E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -4.83399E+00 MeV Emin = 5.02166E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -4.89999E+00 MeV Emin = 5.09022E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -4.97199E+00 MeV Emin = 5.16502E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -5.29099E+00 MeV Emin = 5.49640E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -5.47399E+00 MeV Emin = 5.68650E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 63 Q = -5.68999E+00 MeV Emin = 5.91089E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 18 MT = 91 Q = -7.99999E+00 MeV Emin = 8.31057E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 19 MT = 102 Q = 6.44429E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 120270 : (n,gamma) + 20 MT = 103 Q = -7.92092E+00 MeV Emin = 8.22843E+00 MeV frac = 1.00000E+00 Product nuclide = 110260 : (n,p) + 21 MT = 107 Q = -5.41664E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 100230 : (n,alpha) + + 4 additional transport branches: + + 1 MT = 22 Q = -1.06132E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.41466E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -7.92092E+00 MeV Emin = 8.22843E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 107 Q = -5.41664E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 4 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 8.22843E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 7.00000E+00 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 4 MT = 4 Q = 0.00000E+00 MeV Emin = 1.68946E+00 MeV : total inelastic scattering + + Nuclide 23 / 1657 : 13027.82c -- aluminum 27 (Al-27) + + Pointers : 111687 18821 + Primary type : Transport + Nuclide ZAI : 130270 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Al27.ACE + Atomic weight (AW) : 26.98154 + Atomic weight ratio (AWR) : 26.74975 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 1.50000E+02 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 57 reaction channels + - 81 special reactions + - 15 transmutation reactions + - 16 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 57 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 5 Q = 0.00000E+00 MeV Emin = 2.00000E+01 MeV frac = 1.00000E+00 Product nuclide = self : anything + 3 MT = 16 Q = -1.30582E+01 MeV Emin = 1.35464E+01 MeV frac = 1.00000E+00 Product nuclide = 130260 : (n,2n) + 4 MT = 22 Q = -1.00898E+01 MeV Emin = 1.04670E+01 MeV frac = 1.00000E+00 Product nuclide = 11023.82c : (n,nalpha) + 5 MT = 28 Q = -8.27213E+00 MeV Emin = 8.58137E+00 MeV frac = 1.00000E+00 Product nuclide = 12026.82c : (n,np) + 6 MT = 32 Q = -1.71402E+01 MeV Emin = 1.77810E+01 MeV frac = 1.00000E+00 Product nuclide = 12025.82c : (n,nd) + 7 MT = 33 Q = -1.82136E+01 MeV Emin = 1.88945E+01 MeV frac = 1.00000E+00 Product nuclide = 12024.82c : (n,nt) + 8 MT = 45 Q = -1.88839E+01 MeV Emin = 1.95899E+01 MeV frac = 1.00000E+00 Product nuclide = 100220 : (n,npalpha) + 9 MT = 51 Q = -8.43750E-01 MeV Emin = 8.74000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 10 MT = 52 Q = -1.01445E+00 MeV Emin = 1.05000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 11 MT = 53 Q = -2.21110E+00 MeV Emin = 2.29376E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 12 MT = 54 Q = -2.73480E+00 MeV Emin = 2.83704E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 13 MT = 55 Q = -2.98110E+00 MeV Emin = 3.09254E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 14 MT = 56 Q = -3.00400E+00 MeV Emin = 3.11630E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 15 MT = 57 Q = -3.68010E+00 MeV Emin = 3.81768E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 16 MT = 58 Q = -3.95680E+00 MeV Emin = 4.10472E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 17 MT = 59 Q = -4.05430E+00 MeV Emin = 4.20587E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 18 MT = 60 Q = -4.41020E+00 MeV Emin = 4.57507E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 19 MT = 61 Q = -4.51030E+00 MeV Emin = 4.67891E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 20 MT = 62 Q = -4.58000E+00 MeV Emin = 4.75122E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 21 MT = 63 Q = -4.81170E+00 MeV Emin = 4.99158E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 22 MT = 64 Q = -5.15630E+00 MeV Emin = 5.34906E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 23 MT = 65 Q = -5.24820E+00 MeV Emin = 5.44440E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 24 MT = 66 Q = -5.41990E+00 MeV Emin = 5.62252E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 25 MT = 67 Q = -5.43280E+00 MeV Emin = 5.63590E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 26 MT = 68 Q = -5.43840E+00 MeV Emin = 5.64171E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 27 MT = 69 Q = -5.49980E+00 MeV Emin = 5.70540E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 28 MT = 70 Q = -5.55070E+00 MeV Emin = 5.75821E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 29 MT = 71 Q = -5.66700E+00 MeV Emin = 5.87885E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 30 MT = 72 Q = -5.75130E+00 MeV Emin = 5.96631E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 31 MT = 73 Q = -5.82680E+00 MeV Emin = 6.04463E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 32 MT = 74 Q = -5.95960E+00 MeV Emin = 6.18239E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 33 MT = 75 Q = -6.08000E+00 MeV Emin = 6.30729E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 34 MT = 76 Q = -6.11540E+00 MeV Emin = 6.34402E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 35 MT = 77 Q = -6.15920E+00 MeV Emin = 6.38945E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 27. excited state + 36 MT = 78 Q = -6.28700E+00 MeV Emin = 6.52203E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 28. excited state + 37 MT = 79 Q = -6.46400E+00 MeV Emin = 6.70565E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 29. excited state + 38 MT = 80 Q = -6.47730E+00 MeV Emin = 6.71945E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 30. excited state + 39 MT = 81 Q = -6.51180E+00 MeV Emin = 6.75523E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 31. excited state + 40 MT = 82 Q = -6.53300E+00 MeV Emin = 6.77723E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 32. excited state + 41 MT = 83 Q = -6.60530E+00 MeV Emin = 6.85223E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 33. excited state + 42 MT = 84 Q = -6.65150E+00 MeV Emin = 6.90016E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 34. excited state + 43 MT = 85 Q = -6.71300E+00 MeV Emin = 6.96396E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 35. excited state + 44 MT = 86 Q = -6.76500E+00 MeV Emin = 7.01790E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 36. excited state + 45 MT = 87 Q = -6.77540E+00 MeV Emin = 7.02869E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 37. excited state + 46 MT = 88 Q = -6.81420E+00 MeV Emin = 7.06894E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 38. excited state + 47 MT = 89 Q = -6.82000E+00 MeV Emin = 7.07496E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 39. excited state + 48 MT = 91 Q = -6.82000E+00 MeV Emin = 7.07496E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 49 MT = 102 Q = 7.72520E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 130280 : (n,gamma) + 50 MT = 103 Q = -1.82855E+00 MeV Emin = 1.89625E+00 MeV frac = 1.00000E+00 Product nuclide = 120270 : (n,p) + 51 MT = 104 Q = -6.04754E+00 MeV Emin = 6.27362E+00 MeV frac = 1.00000E+00 Product nuclide = 12026.82c : (n,d) + 52 MT = 105 Q = -1.08829E+01 MeV Emin = 1.12898E+01 MeV frac = 1.00000E+00 Product nuclide = 12025.82c : (n,t) + 53 MT = 107 Q = -3.13033E+00 MeV Emin = 3.24735E+00 MeV frac = 1.00000E+00 Product nuclide = 110240 : (n,alpha) + 54 MT = 108 Q = -1.39583E+01 MeV Emin = 1.44801E+01 MeV frac = 1.00000E+00 Product nuclide = 90200 : (n,2alpha) + 55 MT = 111 Q = -1.67999E+01 MeV Emin = 1.74279E+01 MeV frac = 1.00000E+00 Product nuclide = 110260 : (n,2p) + 56 MT = 112 Q = -1.36838E+01 MeV Emin = 1.41954E+01 MeV frac = 1.00000E+00 Product nuclide = 100230 : (n,palpha) + 57 MT = 117 Q = -1.66594E+01 MeV Emin = 1.72822E+01 MeV frac = 1.00000E+00 Product nuclide = 100220 : (n,dalpha) + + 16 additional transport branches: + + 1 MT = 22 Q = -1.00898E+01 MeV Emin = 1.04670E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -8.27213E+00 MeV Emin = 8.58137E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.71402E+01 MeV Emin = 1.77810E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.82136E+01 MeV Emin = 1.88945E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 45 Q = -1.88839E+01 MeV Emin = 1.95899E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,npalpha) + 6 MT = 45 Q = -1.88839E+01 MeV Emin = 1.95899E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,npalpha) + 7 MT = 103 Q = -1.82855E+00 MeV Emin = 1.89625E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 8 MT = 104 Q = -6.04754E+00 MeV Emin = 6.27362E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 9 MT = 105 Q = -1.08829E+01 MeV Emin = 1.12898E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 10 MT = 107 Q = -3.13033E+00 MeV Emin = 3.24735E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 11 MT = 108 Q = -1.39583E+01 MeV Emin = 1.44801E+01 MeV frac = 2.00000E+00 Product nuclide = 2004.82c : (n,2alpha) + 12 MT = 111 Q = -1.67999E+01 MeV Emin = 1.74279E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + 13 MT = 112 Q = -1.36838E+01 MeV Emin = 1.41954E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,palpha) + 14 MT = 112 Q = -1.36838E+01 MeV Emin = 1.41954E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,palpha) + 15 MT = 117 Q = -1.66594E+01 MeV Emin = 1.72822E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,dalpha) + 16 MT = 117 Q = -1.66594E+01 MeV Emin = 1.72822E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,dalpha) + + 81 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.89625E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.27362E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.12898E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 3.24735E+00 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 600 Q = -1.82855E+00 MeV Emin = 1.89625E+00 MeV : (n,p) to ground state + 7 MT = 601 Q = -2.81321E+00 MeV Emin = 2.91838E+00 MeV : (n,p1) + 8 MT = 602 Q = -3.52655E+00 MeV Emin = 3.65838E+00 MeV : (n,p2) + 9 MT = 603 Q = -3.76855E+00 MeV Emin = 3.90943E+00 MeV : (n,p3) + 10 MT = 604 Q = -4.93795E+00 MeV Emin = 5.12255E+00 MeV : (n,p4) + 11 MT = 605 Q = -5.25545E+00 MeV Emin = 5.45192E+00 MeV : (n,p5) + 12 MT = 606 Q = -5.30385E+00 MeV Emin = 5.50213E+00 MeV : (n,p6) + 13 MT = 607 Q = -5.31925E+00 MeV Emin = 5.51810E+00 MeV : (n,p7) + 14 MT = 608 Q = -5.38775E+00 MeV Emin = 5.58916E+00 MeV : (n,p8) + 15 MT = 609 Q = -5.58895E+00 MeV Emin = 5.79788E+00 MeV : (n,p9) + 16 MT = 610 Q = -5.61445E+00 MeV Emin = 5.82434E+00 MeV : (n,p10) + 17 MT = 611 Q = -5.71255E+00 MeV Emin = 5.92610E+00 MeV : (n,p11) + 18 MT = 612 Q = -5.97835E+00 MeV Emin = 6.20184E+00 MeV : (n,p12) + 19 MT = 613 Q = -6.22675E+00 MeV Emin = 6.45953E+00 MeV : (n,p13) + 20 MT = 614 Q = -6.38135E+00 MeV Emin = 6.61991E+00 MeV : (n,p14) + 21 MT = 615 Q = -6.60465E+00 MeV Emin = 6.85156E+00 MeV : (n,p15) + 22 MT = 616 Q = -6.65585E+00 MeV Emin = 6.90467E+00 MeV : (n,p16) + 23 MT = 617 Q = -6.82085E+00 MeV Emin = 7.07584E+00 MeV : (n,p17) + 24 MT = 618 Q = -6.85655E+00 MeV Emin = 7.11287E+00 MeV : (n,p18) + 25 MT = 619 Q = -7.00055E+00 MeV Emin = 7.26226E+00 MeV : (n,p19) + 26 MT = 649 Q = -7.00055E+00 MeV Emin = 7.26226E+00 MeV : (n,p) to continuum + 27 MT = 650 Q = -6.04754E+00 MeV Emin = 6.27362E+00 MeV : (n,d) to ground state + 28 MT = 651 Q = -7.85622E+00 MeV Emin = 8.14992E+00 MeV : (n,d1) + 29 MT = 652 Q = -8.98590E+00 MeV Emin = 9.32183E+00 MeV : (n,d2) + 30 MT = 653 Q = -9.63584E+00 MeV Emin = 9.99607E+00 MeV : (n,d3) + 31 MT = 654 Q = -9.98804E+00 MeV Emin = 1.03614E+01 MeV : (n,d4) + 32 MT = 655 Q = -1.03659E+01 MeV Emin = 1.07535E+01 MeV : (n,d5) + 33 MT = 656 Q = -1.03794E+01 MeV Emin = 1.07675E+01 MeV : (n,d6) + 34 MT = 657 Q = -1.03973E+01 MeV Emin = 1.07860E+01 MeV : (n,d7) + 35 MT = 658 Q = -1.08818E+01 MeV Emin = 1.12887E+01 MeV : (n,d8) + 36 MT = 659 Q = -1.09478E+01 MeV Emin = 1.13571E+01 MeV : (n,d9) + 37 MT = 660 Q = -1.10197E+01 MeV Emin = 1.14317E+01 MeV : (n,d10) + 38 MT = 661 Q = -1.13383E+01 MeV Emin = 1.17622E+01 MeV : (n,d11) + 39 MT = 662 Q = -1.15214E+01 MeV Emin = 1.19522E+01 MeV : (n,d12) + 40 MT = 663 Q = -1.17376E+01 MeV Emin = 1.21764E+01 MeV : (n,d13) + 41 MT = 664 Q = -1.17630E+01 MeV Emin = 1.22028E+01 MeV : (n,d14) + 42 MT = 665 Q = -1.21727E+01 MeV Emin = 1.26278E+01 MeV : (n,d15) + 43 MT = 666 Q = -1.23035E+01 MeV Emin = 1.27635E+01 MeV : (n,d16) + 44 MT = 667 Q = -1.26685E+01 MeV Emin = 1.31421E+01 MeV : (n,d17) + 45 MT = 668 Q = -1.27915E+01 MeV Emin = 1.32697E+01 MeV : (n,d18) + 46 MT = 669 Q = -1.29252E+01 MeV Emin = 1.34084E+01 MeV : (n,d19) + 47 MT = 699 Q = -1.29252E+01 MeV Emin = 1.34084E+01 MeV : (n,d) to continuum + 48 MT = 700 Q = -1.08829E+01 MeV Emin = 1.12898E+01 MeV : (n,t) to ground state + 49 MT = 701 Q = -1.14680E+01 MeV Emin = 1.18968E+01 MeV : (n,t1) + 50 MT = 702 Q = -1.18577E+01 MeV Emin = 1.23010E+01 MeV : (n,t2) + 51 MT = 703 Q = -1.24947E+01 MeV Emin = 1.29618E+01 MeV : (n,t3) + 52 MT = 704 Q = -1.28476E+01 MeV Emin = 1.33279E+01 MeV : (n,t4) + 53 MT = 705 Q = -1.34467E+01 MeV Emin = 1.39494E+01 MeV : (n,t5) + 54 MT = 706 Q = -1.36206E+01 MeV Emin = 1.41298E+01 MeV : (n,t6) + 55 MT = 707 Q = -1.36840E+01 MeV Emin = 1.41956E+01 MeV : (n,t7) + 56 MT = 708 Q = -1.42881E+01 MeV Emin = 1.48223E+01 MeV : (n,t8) + 57 MT = 709 Q = -1.42966E+01 MeV Emin = 1.48311E+01 MeV : (n,t9) + 58 MT = 710 Q = -1.47907E+01 MeV Emin = 1.53437E+01 MeV : (n,t10) + 59 MT = 749 Q = -1.47907E+01 MeV Emin = 1.53437E+01 MeV : (n,t) to continuum + 60 MT = 800 Q = -3.13033E+00 MeV Emin = 3.24735E+00 MeV : (n,alpha) to ground state + 61 MT = 801 Q = -3.60262E+00 MeV Emin = 3.73730E+00 MeV : (n,a1) + 62 MT = 802 Q = -3.69362E+00 MeV Emin = 3.83170E+00 MeV : (n,a2) + 63 MT = 803 Q = -4.47173E+00 MeV Emin = 4.63890E+00 MeV : (n,a3) + 64 MT = 804 Q = -4.47483E+00 MeV Emin = 4.64212E+00 MeV : (n,a4) + 65 MT = 805 Q = -4.47683E+00 MeV Emin = 4.64419E+00 MeV : (n,a5) + 66 MT = 806 Q = -4.64287E+00 MeV Emin = 4.81644E+00 MeV : (n,a6) + 67 MT = 807 Q = -4.97643E+00 MeV Emin = 5.16247E+00 MeV : (n,a7) + 68 MT = 808 Q = -5.01577E+00 MeV Emin = 5.20328E+00 MeV : (n,a8) + 69 MT = 809 Q = -5.64373E+00 MeV Emin = 5.85471E+00 MeV : (n,a9) + 70 MT = 810 Q = -5.69283E+00 MeV Emin = 5.90565E+00 MeV : (n,a10) + 71 MT = 811 Q = -6.03403E+00 MeV Emin = 6.25960E+00 MeV : (n,a11) + 72 MT = 812 Q = -6.10813E+00 MeV Emin = 6.33647E+00 MeV : (n,a12) + 73 MT = 813 Q = -6.34713E+00 MeV Emin = 6.58441E+00 MeV : (n,a13) + 74 MT = 814 Q = -6.50223E+00 MeV Emin = 6.74531E+00 MeV : (n,a14) + 75 MT = 815 Q = -6.54373E+00 MeV Emin = 6.78836E+00 MeV : (n,a15) + 76 MT = 816 Q = -6.71943E+00 MeV Emin = 6.97063E+00 MeV : (n,a16) + 77 MT = 817 Q = -6.75883E+00 MeV Emin = 7.01150E+00 MeV : (n,a17) + 78 MT = 818 Q = -6.78683E+00 MeV Emin = 7.04055E+00 MeV : (n,a18) + 79 MT = 819 Q = -6.81203E+00 MeV Emin = 7.06669E+00 MeV : (n,a19) + 80 MT = 849 Q = -6.81203E+00 MeV Emin = 7.06669E+00 MeV : (n,alpha) to continuum + 81 MT = 4 Q = 0.00000E+00 MeV Emin = 8.74000E-01 MeV : total inelastic scattering + + Nuclide 24 / 1657 : 14028.82c -- silicon 28 (Si-28) + + Pointers : 124393 32805 + Primary type : Transport + Nuclide ZAI : 140280 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Si28.ACE + Atomic weight (AW) : 27.97734 + Atomic weight ratio (AWR) : 27.73700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 29 reaction channels + - 39 special reactions + - 10 transmutation reactions + - 8 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 29 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.71770E+01 MeV Emin = 1.77963E+01 MeV frac = 1.00000E+00 Product nuclide = 140270 : (n,2n) + 3 MT = 22 Q = -9.98560E+00 MeV Emin = 1.03460E+01 MeV frac = 1.00000E+00 Product nuclide = 12024.82c : (n,nalpha) + 4 MT = 28 Q = -1.15860E+01 MeV Emin = 1.20037E+01 MeV frac = 1.00000E+00 Product nuclide = 13027.82c : (n,np) + 5 MT = 51 Q = -1.77900E+00 MeV Emin = 1.84213E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -4.61700E+00 MeV Emin = 4.89210E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -4.97900E+00 MeV Emin = 5.15851E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -6.27600E+00 MeV Emin = 6.50230E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -6.69100E+00 MeV Emin = 6.93223E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -6.87900E+00 MeV Emin = 7.12701E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -6.88900E+00 MeV Emin = 7.13740E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -7.38100E+00 MeV Emin = 7.64711E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -7.41700E+00 MeV Emin = 7.68441E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -7.79900E+00 MeV Emin = 8.08020E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -7.93300E+00 MeV Emin = 8.21901E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -8.25900E+00 MeV Emin = 8.55680E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 63 Q = -8.32800E+00 MeV Emin = 8.62830E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 18 MT = 64 Q = -8.41300E+00 MeV Emin = 8.71631E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 19 MT = 65 Q = -8.54300E+00 MeV Emin = 8.85100E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 20 MT = 66 Q = -8.58900E+00 MeV Emin = 8.89870E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 21 MT = 67 Q = -8.90400E+00 MeV Emin = 9.22502E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 22 MT = 91 Q = -9.00000E+00 MeV Emin = 9.32448E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 23 MT = 102 Q = 8.47390E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 14029.82c : (n,gamma) + 24 MT = 103 Q = -3.86000E+00 MeV Emin = 4.03128E+00 MeV frac = 1.00000E+00 Product nuclide = 130280 : (n,p) + 25 MT = 104 Q = -9.36130E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 13027.82c : (n,d) + 26 MT = 105 Q = -1.16000E+01 MeV Emin = 1.20182E+01 MeV frac = 1.00000E+00 Product nuclide = 130260 : (n,t) + 27 MT = 106 Q = -1.20700E+01 MeV Emin = 1.25052E+01 MeV frac = 1.00000E+00 Product nuclide = 12026.82c : (n,He-3) + 28 MT = 107 Q = -2.65000E+00 MeV Emin = 2.82000E+00 MeV frac = 1.00000E+00 Product nuclide = 12025.82c : (n,alpha) + 29 MT = 111 Q = -1.34130E+01 MeV Emin = 1.38966E+01 MeV frac = 1.00000E+00 Product nuclide = 120270 : (n,2p) + + 8 additional transport branches: + + 1 MT = 22 Q = -9.98560E+00 MeV Emin = 1.03460E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.15860E+01 MeV Emin = 1.20037E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -3.86000E+00 MeV Emin = 4.03128E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -9.36130E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -1.16000E+01 MeV Emin = 1.20182E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 106 Q = -1.20700E+01 MeV Emin = 1.25052E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 7 MT = 107 Q = -2.65000E+00 MeV Emin = 2.82000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 8 MT = 111 Q = -1.34130E+01 MeV Emin = 1.38966E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 39 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.03128E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.00000E+01 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.20182E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.25052E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 2.82000E+00 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 600 Q = -3.86000E+00 MeV Emin = 4.03128E+00 MeV : (n,p) to ground state + 8 MT = 601 Q = -3.89100E+00 MeV Emin = 4.03128E+00 MeV : (n,p1) + 9 MT = 602 Q = -4.83200E+00 MeV Emin = 5.00621E+00 MeV : (n,p2) + 10 MT = 603 Q = -4.87400E+00 MeV Emin = 5.04972E+00 MeV : (n,p3) + 11 MT = 604 Q = -5.23300E+00 MeV Emin = 5.42167E+00 MeV : (n,p4) + 12 MT = 605 Q = -5.48000E+00 MeV Emin = 5.67757E+00 MeV : (n,p5) + 13 MT = 606 Q = -5.48300E+00 MeV Emin = 5.68068E+00 MeV : (n,p6) + 14 MT = 607 Q = -5.99900E+00 MeV Emin = 6.21528E+00 MeV : (n,p7) + 15 MT = 608 Q = -6.06200E+00 MeV Emin = 6.28055E+00 MeV : (n,p8) + 16 MT = 609 Q = -6.13200E+00 MeV Emin = 6.35308E+00 MeV : (n,p9) + 17 MT = 610 Q = -6.34500E+00 MeV Emin = 6.57376E+00 MeV : (n,p10) + 18 MT = 611 Q = -6.44100E+00 MeV Emin = 6.67322E+00 MeV : (n,p11) + 19 MT = 612 Q = -6.51600E+00 MeV Emin = 6.75092E+00 MeV : (n,p12) + 20 MT = 613 Q = -6.84700E+00 MeV Emin = 7.09385E+00 MeV : (n,p13) + 21 MT = 649 Q = -6.86000E+00 MeV Emin = 7.10732E+00 MeV : (n,p) to continuum + 22 MT = 800 Q = -2.65000E+00 MeV Emin = 2.82000E+00 MeV : (n,alpha) to ground state + 23 MT = 801 Q = -3.23500E+00 MeV Emin = 3.35163E+00 MeV : (n,a1) + 24 MT = 802 Q = -3.62500E+00 MeV Emin = 3.75569E+00 MeV : (n,a2) + 25 MT = 803 Q = -4.26200E+00 MeV Emin = 4.41566E+00 MeV : (n,a3) + 26 MT = 804 Q = -4.61500E+00 MeV Emin = 4.78139E+00 MeV : (n,a4) + 27 MT = 805 Q = -5.21400E+00 MeV Emin = 5.40198E+00 MeV : (n,a5) + 28 MT = 806 Q = -5.38800E+00 MeV Emin = 5.58225E+00 MeV : (n,a6) + 29 MT = 807 Q = -5.45100E+00 MeV Emin = 5.64752E+00 MeV : (n,a7) + 30 MT = 808 Q = -6.05500E+00 MeV Emin = 6.27330E+00 MeV : (n,a8) + 31 MT = 809 Q = -6.06400E+00 MeV Emin = 6.28263E+00 MeV : (n,a9) + 32 MT = 810 Q = -6.55800E+00 MeV Emin = 6.79444E+00 MeV : (n,a10) + 33 MT = 811 Q = -6.62100E+00 MeV Emin = 6.85971E+00 MeV : (n,a11) + 34 MT = 812 Q = -6.71000E+00 MeV Emin = 6.95192E+00 MeV : (n,a12) + 35 MT = 813 Q = -6.92700E+00 MeV Emin = 7.17674E+00 MeV : (n,a13) + 36 MT = 814 Q = -7.00900E+00 MeV Emin = 7.26170E+00 MeV : (n,a14) + 37 MT = 815 Q = -7.36100E+00 MeV Emin = 7.62640E+00 MeV : (n,a15) + 38 MT = 849 Q = -7.45000E+00 MeV Emin = 7.71860E+00 MeV : (n,alpha) to continuum + 39 MT = 4 Q = 0.00000E+00 MeV Emin = 1.84213E+00 MeV : total inelastic scattering + + Nuclide 25 / 1657 : 14029.82c -- silicon 29 (Si-29) + + Pointers : 130052 32851 + Primary type : Transport + Nuclide ZAI : 140290 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Si29.ACE + Atomic weight (AW) : 28.97652 + Atomic weight ratio (AWR) : 28.72760 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 38 reaction channels + - 4 special reactions + - 7 transmutation reactions + - 5 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 38 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.47388E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 14028.82c : (n,2n) + 3 MT = 22 Q = -1.11267E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 12025.82c : (n,nalpha) + 4 MT = 28 Q = -1.23337E+01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 130280 : (n,np) + 5 MT = 51 Q = -1.27300E+00 MeV Emin = 1.15864E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -2.02800E+00 MeV Emin = 2.09859E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -2.42500E+00 MeV Emin = 2.50942E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -3.06700E+00 MeV Emin = 3.17376E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -3.62399E+00 MeV Emin = 3.75014E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -4.07999E+00 MeV Emin = 4.22201E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -4.74099E+00 MeV Emin = 4.90602E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -4.83999E+00 MeV Emin = 5.00847E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -4.89499E+00 MeV Emin = 5.06538E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -4.93399E+00 MeV Emin = 5.10574E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -5.25499E+00 MeV Emin = 5.43792E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -5.28599E+00 MeV Emin = 5.46999E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 63 Q = -5.65199E+00 MeV Emin = 5.84873E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 18 MT = 64 Q = -5.81299E+00 MeV Emin = 6.01534E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 19 MT = 65 Q = -5.94899E+00 MeV Emin = 6.15607E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 20 MT = 66 Q = -6.10699E+00 MeV Emin = 6.31957E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 21 MT = 67 Q = -6.19199E+00 MeV Emin = 6.40753E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 22 MT = 68 Q = -6.37799E+00 MeV Emin = 6.60001E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 23 MT = 69 Q = -6.42299E+00 MeV Emin = 6.64657E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 24 MT = 70 Q = -6.49599E+00 MeV Emin = 6.72211E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 25 MT = 71 Q = -6.52199E+00 MeV Emin = 6.74902E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 26 MT = 72 Q = -6.61499E+00 MeV Emin = 6.84526E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 27 MT = 73 Q = -6.69699E+00 MeV Emin = 6.93011E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 28 MT = 74 Q = -6.70999E+00 MeV Emin = 6.94356E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 29 MT = 75 Q = -6.71499E+00 MeV Emin = 6.94874E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 30 MT = 76 Q = -6.78199E+00 MeV Emin = 7.01807E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 31 MT = 77 Q = -6.90699E+00 MeV Emin = 7.14742E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 27. excited state + 32 MT = 78 Q = -6.92099E+00 MeV Emin = 7.16191E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 28. excited state + 33 MT = 79 Q = -7.01399E+00 MeV Emin = 7.25815E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 29. excited state + 34 MT = 91 Q = -7.05699E+00 MeV Emin = 7.30264E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 35 MT = 102 Q = 1.06143E+01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 14030.82c : (n,gamma) + 36 MT = 103 Q = -2.89783E+00 MeV Emin = 3.10000E+00 MeV frac = 1.00000E+00 Product nuclide = 130290 : (n,p) + 37 MT = 107 Q = -3.31500E-02 MeV Emin = 3.99455E-02 MeV frac = 1.00000E+00 Product nuclide = 12026.82c : (n,alpha) + 38 MT = 111 Q = -1.33831E+01 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 120280 : (n,2p) + + 5 additional transport branches: + + 1 MT = 22 Q = -1.11267E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.23337E+01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -2.89783E+00 MeV Emin = 3.10000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 107 Q = -3.31500E-02 MeV Emin = 3.99455E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 5 MT = 111 Q = -1.33831E+01 MeV Emin = 1.40000E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 4 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.10000E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 3.99455E-02 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 4 MT = 4 Q = 0.00000E+00 MeV Emin = 1.15864E+00 MeV : total inelastic scattering + + Nuclide 26 / 1657 : 14030.82c -- silicon 30 (Si-30) + + Pointers : 133594 32897 + Primary type : Transport + Nuclide ZAI : 140300 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Si30.ACE + Atomic weight (AW) : 30.00002 + Atomic weight ratio (AWR) : 29.74230 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 28 reaction channels + - 4 special reactions + - 7 transmutation reactions + - 5 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 28 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.06097E+01 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 14029.82c : (n,2n) + 3 MT = 22 Q = -1.06428E+01 MeV Emin = 1.10009E+01 MeV frac = 1.00000E+00 Product nuclide = 12026.82c : (n,nalpha) + 4 MT = 28 Q = -1.35075E+01 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 130290 : (n,np) + 5 MT = 51 Q = -2.23500E+00 MeV Emin = 2.31015E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -3.49819E+00 MeV Emin = 3.61582E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -3.76959E+00 MeV Emin = 3.89634E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -3.78769E+00 MeV Emin = 3.91505E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -4.80899E+00 MeV Emin = 4.97069E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -4.83049E+00 MeV Emin = 4.99291E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -5.22999E+00 MeV Emin = 5.40584E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -5.27899E+00 MeV Emin = 5.45649E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -5.37199E+00 MeV Emin = 5.55262E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -5.48759E+00 MeV Emin = 5.67211E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -5.61299E+00 MeV Emin = 5.80172E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -5.94999E+00 MeV Emin = 6.15005E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 63 Q = -6.50299E+00 MeV Emin = 6.72164E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 18 MT = 64 Q = -6.53699E+00 MeV Emin = 6.75679E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 19 MT = 65 Q = -6.63399E+00 MeV Emin = 6.85705E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 20 MT = 66 Q = -6.63999E+00 MeV Emin = 6.86325E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 21 MT = 67 Q = -6.74469E+00 MeV Emin = 6.97147E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 22 MT = 68 Q = -6.86499E+00 MeV Emin = 7.09582E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 23 MT = 69 Q = -6.91399E+00 MeV Emin = 7.14646E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 24 MT = 91 Q = -6.99899E+00 MeV Emin = 7.23432E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 25 MT = 102 Q = 6.59199E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 140310 : (n,gamma) + 26 MT = 103 Q = -7.75882E+00 MeV Emin = 8.01993E+00 MeV frac = 1.00000E+00 Product nuclide = 130300 : (n,p) + 27 MT = 107 Q = -4.19984E+00 MeV Emin = 4.40000E+00 MeV frac = 1.00000E+00 Product nuclide = 120270 : (n,alpha) + 28 MT = 111 Q = -1.83851E+01 MeV Emin = 1.90038E+01 MeV frac = 1.00000E+00 Product nuclide = 120290 : (n,2p) + + 5 additional transport branches: + + 1 MT = 22 Q = -1.06428E+01 MeV Emin = 1.10009E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.35075E+01 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -7.75882E+00 MeV Emin = 8.01993E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 107 Q = -4.19984E+00 MeV Emin = 4.40000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 5 MT = 111 Q = -1.83851E+01 MeV Emin = 1.90038E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 4 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 8.01993E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 4.40000E+00 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 4 MT = 4 Q = 0.00000E+00 MeV Emin = 2.31015E+00 MeV : total inelastic scattering + + Nuclide 27 / 1657 : 15031.82c -- phosphorus 31 (P-31) + + Pointers : 137409 29493 + Primary type : Transport + Nuclide ZAI : 150310 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/P31.ACE + Atomic weight (AW) : 30.97378 + Atomic weight ratio (AWR) : 30.70770 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 14 reaction channels + - 4 special reactions + - 6 transmutation reactions + - 4 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 14 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.23074E+01 MeV Emin = 1.32000E+01 MeV frac = 1.00000E+00 Product nuclide = 150300 : (n,2n) + 3 MT = 22 Q = -9.66952E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 13027.82c : (n,nalpha) + 4 MT = 28 Q = -7.29751E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 14030.82c : (n,np) + 5 MT = 51 Q = -1.26600E+00 MeV Emin = 1.15370E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -2.23400E+00 MeV Emin = 2.30675E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -3.13400E+00 MeV Emin = 3.23606E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -3.29500E+00 MeV Emin = 3.40230E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -3.41499E+00 MeV Emin = 3.52621E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -3.50599E+00 MeV Emin = 3.62017E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 91 Q = -3.99999E+00 MeV Emin = 4.13026E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 12 MT = 102 Q = 7.93699E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 150320 : (n,gamma) + 13 MT = 103 Q = -7.09229E-01 MeV Emin = 7.30000E-01 MeV frac = 1.00000E+00 Product nuclide = 140310 : (n,p) + 14 MT = 107 Q = -1.94352E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 130280 : (n,alpha) + + 4 additional transport branches: + + 1 MT = 22 Q = -9.66952E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -7.29751E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -7.09229E-01 MeV Emin = 7.30000E-01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 107 Q = -1.94352E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 4 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 7.30000E-01 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 3.00000E+00 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 4 MT = 4 Q = 0.00000E+00 MeV Emin = 1.15370E+00 MeV : total inelastic scattering + + Nuclide 28 / 1657 : 16034.82c -- sulfur 34 (S-34) + + Pointers : 140511 32115 + Primary type : Transport + Nuclide ZAI : 160340 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/S34.ACE + Atomic weight (AW) : 33.96800 + Atomic weight ratio (AWR) : 33.67620 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 13 reaction channels + - 4 special reactions + - 6 transmutation reactions + - 4 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 13 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.14149E+01 MeV Emin = 1.17539E+01 MeV frac = 1.00000E+00 Product nuclide = 160330 : (n,2n) + 3 MT = 22 Q = -7.92283E+00 MeV Emin = 8.20000E+00 MeV frac = 1.00000E+00 Product nuclide = 14030.82c : (n,nalpha) + 4 MT = 28 Q = -1.08814E+01 MeV Emin = 1.12045E+01 MeV frac = 1.00000E+00 Product nuclide = 150330 : (n,np) + 5 MT = 51 Q = -2.12700E+00 MeV Emin = 2.19016E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -3.30400E+00 MeV Emin = 3.40211E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -3.91399E+00 MeV Emin = 4.03022E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -4.07199E+00 MeV Emin = 4.19292E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -4.11499E+00 MeV Emin = 4.23719E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 91 Q = -4.49999E+00 MeV Emin = 4.63363E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 11 MT = 102 Q = 6.98699E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 160350 : (n,gamma) + 12 MT = 103 Q = -4.31672E+00 MeV Emin = 4.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 150340 : (n,p) + 13 MT = 107 Q = -1.33455E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 140310 : (n,alpha) + + 4 additional transport branches: + + 1 MT = 22 Q = -7.92283E+00 MeV Emin = 8.20000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.08814E+01 MeV Emin = 1.12045E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -4.31672E+00 MeV Emin = 4.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 107 Q = -1.33455E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 4 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.50000E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 4 MT = 4 Q = 0.00000E+00 MeV Emin = 2.19016E+00 MeV : total inelastic scattering + + Nuclide 29 / 1657 : 16036.82c -- sulfur 36 (S-36) + + Pointers : 142372 32161 + Primary type : Transport + Nuclide ZAI : 160360 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/S36.ACE + Atomic weight (AW) : 35.96697 + Atomic weight ratio (AWR) : 35.65800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 13 reaction channels + - 4 special reactions + - 6 transmutation reactions + - 4 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 13 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -9.89198E+00 MeV Emin = 1.02000E+01 MeV frac = 1.00000E+00 Product nuclide = 160350 : (n,2n) + 3 MT = 22 Q = -8.99983E+00 MeV Emin = 1.02000E+01 MeV frac = 1.00000E+00 Product nuclide = 140320 : (n,nalpha) + 4 MT = 28 Q = -1.30419E+01 MeV Emin = 1.34077E+01 MeV frac = 1.00000E+00 Product nuclide = 150350 : (n,np) + 5 MT = 51 Q = -3.29100E+00 MeV Emin = 3.38329E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -3.34600E+00 MeV Emin = 3.43984E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -4.19199E+00 MeV Emin = 4.30956E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -4.52299E+00 MeV Emin = 4.64984E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -4.57499E+00 MeV Emin = 4.70330E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 91 Q = -4.99999E+00 MeV Emin = 5.14022E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 11 MT = 102 Q = 4.31399E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 160370 : (n,gamma) + 12 MT = 103 Q = -8.99092E+00 MeV Emin = 9.24307E+00 MeV frac = 1.00000E+00 Product nuclide = 150360 : (n,p) + 13 MT = 107 Q = -3.95404E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 140330 : (n,alpha) + + 4 additional transport branches: + + 1 MT = 22 Q = -8.99983E+00 MeV Emin = 1.02000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.30419E+01 MeV Emin = 1.34077E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -8.99092E+00 MeV Emin = 9.24307E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 107 Q = -3.95404E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 4 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 9.24307E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 5.00000E+00 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 4 MT = 4 Q = 0.00000E+00 MeV Emin = 3.38329E+00 MeV : total inelastic scattering + + Nuclide 30 / 1657 : 17035.82c -- chlorine 35 (Cl-35) + + Pointers : 145031 21581 + Primary type : Transport + Nuclide ZAI : 170350 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Cl35.ACE + Atomic weight (AW) : 34.96885 + Atomic weight ratio (AWR) : 34.66845 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 43 reaction channels + - 123 special reactions + - 11 transmutation reactions + - 10 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 43 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.26450E+01 MeV Emin = 1.30098E+01 MeV frac = 1.00000E+00 Product nuclide = 170340 : (n,2n) + 3 MT = 22 Q = -6.99745E+00 MeV Emin = 7.19929E+00 MeV frac = 1.00000E+00 Product nuclide = 15031.82c : (n,nalpha) + 4 MT = 28 Q = -6.37040E+00 MeV Emin = 6.55415E+00 MeV frac = 1.00000E+00 Product nuclide = 16034.82c : (n,np) + 5 MT = 32 Q = -1.55629E+01 MeV Emin = 1.60118E+01 MeV frac = 1.00000E+00 Product nuclide = 160330 : (n,nd) + 6 MT = 51 Q = -1.21944E+00 MeV Emin = 1.25000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.76315E+00 MeV Emin = 1.79797E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -2.64560E+00 MeV Emin = 2.72191E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -2.69360E+00 MeV Emin = 2.77130E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -3.00274E+00 MeV Emin = 3.08935E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -3.16800E+00 MeV Emin = 3.25938E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -3.91848E+00 MeV Emin = 4.03151E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -3.94290E+00 MeV Emin = 4.05663E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -3.96750E+00 MeV Emin = 4.08194E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -4.05920E+00 MeV Emin = 4.17629E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -4.11330E+00 MeV Emin = 4.23195E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -4.17345E+00 MeV Emin = 4.29383E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -4.17790E+00 MeV Emin = 4.29841E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -4.34770E+00 MeV Emin = 4.47311E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -4.62440E+00 MeV Emin = 4.75779E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 21 MT = 66 Q = -4.76990E+00 MeV Emin = 4.90749E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 22 MT = 67 Q = -4.83909E+00 MeV Emin = 4.97867E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 23 MT = 68 Q = -4.85440E+00 MeV Emin = 4.99442E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 24 MT = 69 Q = -4.88110E+00 MeV Emin = 5.02189E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 25 MT = 70 Q = -5.01040E+00 MeV Emin = 5.15492E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 26 MT = 71 Q = -5.16331E+00 MeV Emin = 5.31224E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 27 MT = 72 Q = -5.21580E+00 MeV Emin = 5.36625E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 28 MT = 73 Q = -5.40360E+00 MeV Emin = 5.55947E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 29 MT = 74 Q = -5.40670E+00 MeV Emin = 5.56266E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 30 MT = 75 Q = -5.58600E+00 MeV Emin = 5.74713E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 31 MT = 76 Q = -5.59970E+00 MeV Emin = 5.76122E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 32 MT = 77 Q = -5.64600E+00 MeV Emin = 5.80886E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 27. excited state + 33 MT = 78 Q = -5.65400E+00 MeV Emin = 5.81709E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 28. excited state + 34 MT = 79 Q = -5.68300E+00 MeV Emin = 5.84692E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 29. excited state + 35 MT = 80 Q = -5.72352E+00 MeV Emin = 5.88861E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 30. excited state + 36 MT = 91 Q = -5.72352E+00 MeV Emin = 5.88861E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 37 MT = 102 Q = 8.57977E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 170360 : (n,gamma) + 38 MT = 103 Q = 6.15220E-01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 160350 : (n,p) + 39 MT = 104 Q = -4.14581E+00 MeV Emin = 4.29383E+00 MeV frac = 1.00000E+00 Product nuclide = 16034.82c : (n,d) + 40 MT = 105 Q = -9.30564E+00 MeV Emin = 9.64317E+00 MeV frac = 1.00000E+00 Product nuclide = 160330 : (n,t) + 41 MT = 107 Q = 9.38230E-01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 150320 : (n,alpha) + 42 MT = 111 Q = -1.09627E+01 MeV Emin = 1.12789E+01 MeV frac = 1.00000E+00 Product nuclide = 150340 : (n,2p) + 43 MT = 112 Q = -7.70570E+00 MeV Emin = 7.92797E+00 MeV frac = 1.00000E+00 Product nuclide = 140310 : (n,palpha) + + 10 additional transport branches: + + 1 MT = 22 Q = -6.99745E+00 MeV Emin = 7.19929E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -6.37040E+00 MeV Emin = 6.55415E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.55629E+01 MeV Emin = 1.60118E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 103 Q = 6.15220E-01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -4.14581E+00 MeV Emin = 4.29383E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -9.30564E+00 MeV Emin = 9.64317E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 107 Q = 9.38230E-01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 8 MT = 111 Q = -1.09627E+01 MeV Emin = 1.12789E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + 9 MT = 112 Q = -7.70570E+00 MeV Emin = 7.92797E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,palpha) + 10 MT = 112 Q = -7.70570E+00 MeV Emin = 7.92797E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,palpha) + + 123 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 4.29383E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.64317E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 600 Q = 6.15220E-01 MeV Emin = 1.00000E-11 MeV : (n,p) to ground state + 7 MT = 601 Q = -9.56759E-01 MeV Emin = 1.22000E+00 MeV : (n,p1) + 8 MT = 602 Q = -1.37568E+00 MeV Emin = 1.76597E+00 MeV : (n,p2) + 9 MT = 603 Q = -1.73198E+00 MeV Emin = 2.06309E+00 MeV : (n,p3) + 10 MT = 604 Q = -2.10198E+00 MeV Emin = 2.25000E+00 MeV : (n,p4) + 11 MT = 605 Q = -2.32368E+00 MeV Emin = 2.39286E+00 MeV : (n,p5) + 12 MT = 606 Q = -2.80548E+00 MeV Emin = 2.94113E+00 MeV : (n,p6) + 13 MT = 607 Q = -2.94528E+00 MeV Emin = 3.06748E+00 MeV : (n,p7) + 14 MT = 608 Q = -2.98148E+00 MeV Emin = 3.08935E+00 MeV : (n,p8) + 15 MT = 609 Q = -3.05948E+00 MeV Emin = 3.15739E+00 MeV : (n,p9) + 16 MT = 610 Q = -3.18668E+00 MeV Emin = 3.29496E+00 MeV : (n,p10) + 17 MT = 611 Q = -3.20258E+00 MeV Emin = 3.36482E+00 MeV : (n,p11) + 18 MT = 612 Q = -3.27048E+00 MeV Emin = 3.38642E+00 MeV : (n,p12) + 19 MT = 613 Q = -3.29148E+00 MeV Emin = 3.50000E+00 MeV : (n,p13) + 20 MT = 614 Q = -3.40648E+00 MeV Emin = 3.51091E+00 MeV : (n,p14) + 21 MT = 615 Q = -3.41248E+00 MeV Emin = 3.59219E+00 MeV : (n,p15) + 22 MT = 616 Q = -3.49148E+00 MeV Emin = 3.66730E+00 MeV : (n,p16) + 23 MT = 617 Q = -3.56448E+00 MeV Emin = 3.67748E+00 MeV : (n,p17) + 24 MT = 618 Q = -3.57438E+00 MeV Emin = 3.75000E+00 MeV : (n,p18) + 25 MT = 619 Q = -3.68648E+00 MeV Emin = 3.97595E+00 MeV : (n,p19) + 26 MT = 620 Q = -3.86448E+00 MeV Emin = 4.00000E+00 MeV : (n,p20) + 27 MT = 621 Q = -3.96048E+00 MeV Emin = 4.08194E+00 MeV : (n,p21) + 28 MT = 622 Q = -4.00148E+00 MeV Emin = 4.17629E+00 MeV : (n,p22) + 29 MT = 623 Q = -4.22348E+00 MeV Emin = 4.41166E+00 MeV : (n,p23) + 30 MT = 624 Q = -4.28798E+00 MeV Emin = 4.47309E+00 MeV : (n,p24) + 31 MT = 625 Q = -4.34768E+00 MeV Emin = 4.47311E+00 MeV : (n,p25) + 32 MT = 626 Q = -4.37448E+00 MeV Emin = 4.57062E+00 MeV : (n,p26) + 33 MT = 627 Q = -4.44248E+00 MeV Emin = 4.64161E+00 MeV : (n,p27) + 34 MT = 628 Q = -4.51148E+00 MeV Emin = 4.75000E+00 MeV : (n,p28) + 35 MT = 629 Q = -4.72748E+00 MeV Emin = 4.86384E+00 MeV : (n,p29) + 36 MT = 649 Q = -4.72748E+00 MeV Emin = 4.86384E+00 MeV : (n,p) to continuum + 37 MT = 650 Q = -4.14581E+00 MeV Emin = 4.29383E+00 MeV : (n,d) to ground state + 38 MT = 651 Q = -6.27311E+00 MeV Emin = 6.50000E+00 MeV : (n,d1) + 39 MT = 652 Q = -7.44901E+00 MeV Emin = 7.92797E+00 MeV : (n,d2) + 40 MT = 653 Q = -8.06001E+00 MeV Emin = 8.45691E+00 MeV : (n,d3) + 41 MT = 654 Q = -8.21981E+00 MeV Emin = 8.49817E+00 MeV : (n,d4) + 42 MT = 655 Q = -8.25991E+00 MeV Emin = 8.50000E+00 MeV : (n,d5) + 43 MT = 656 Q = -8.76851E+00 MeV Emin = 9.08821E+00 MeV : (n,d6) + 44 MT = 657 Q = -8.83341E+00 MeV Emin = 9.28184E+00 MeV : (n,d7) + 45 MT = 658 Q = -9.02161E+00 MeV Emin = 9.29573E+00 MeV : (n,d8) + 46 MT = 659 Q = -9.03511E+00 MeV Emin = 9.50000E+00 MeV : (n,d9) + 47 MT = 660 Q = -9.37281E+00 MeV Emin = 9.73680E+00 MeV : (n,d10) + 48 MT = 661 Q = -9.46381E+00 MeV Emin = 9.80264E+00 MeV : (n,d11) + 49 MT = 662 Q = -9.52781E+00 MeV Emin = 1.00000E+01 MeV : (n,d12) + 50 MT = 663 Q = -9.82581E+00 MeV Emin = 1.01185E+01 MeV : (n,d13) + 51 MT = 664 Q = -9.83481E+00 MeV Emin = 1.01843E+01 MeV : (n,d14) + 52 MT = 665 Q = -9.89881E+00 MeV Emin = 1.02821E+01 MeV : (n,d15) + 53 MT = 666 Q = -9.99381E+00 MeV Emin = 1.04313E+01 MeV : (n,d16) + 54 MT = 667 Q = -1.01388E+01 MeV Emin = 1.04392E+01 MeV : (n,d17) + 55 MT = 668 Q = -1.02658E+01 MeV Emin = 1.05619E+01 MeV : (n,d18) + 56 MT = 669 Q = -1.03193E+01 MeV Emin = 1.06957E+01 MeV : (n,d19) + 57 MT = 670 Q = -1.03958E+01 MeV Emin = 1.06957E+01 MeV : (n,d20) + 58 MT = 671 Q = -1.03968E+01 MeV Emin = 1.06967E+01 MeV : (n,d21) + 59 MT = 672 Q = -1.04908E+01 MeV Emin = 1.07934E+01 MeV : (n,d22) + 60 MT = 673 Q = -1.05618E+01 MeV Emin = 1.08665E+01 MeV : (n,d23) + 61 MT = 674 Q = -1.06258E+01 MeV Emin = 1.09868E+01 MeV : (n,d24) + 62 MT = 675 Q = -1.06788E+01 MeV Emin = 1.10000E+01 MeV : (n,d25) + 63 MT = 676 Q = -1.07848E+01 MeV Emin = 1.10959E+01 MeV : (n,d26) + 64 MT = 677 Q = -1.08288E+01 MeV Emin = 1.11412E+01 MeV : (n,d27) + 65 MT = 678 Q = -1.08338E+01 MeV Emin = 1.11885E+01 MeV : (n,d28) + 66 MT = 679 Q = -1.08748E+01 MeV Emin = 1.12019E+01 MeV : (n,d29) + 67 MT = 680 Q = -1.08878E+01 MeV Emin = 1.12019E+01 MeV : (n,d30) + 68 MT = 699 Q = -1.08878E+01 MeV Emin = 1.12019E+01 MeV : (n,d) to continuum + 69 MT = 700 Q = -9.30564E+00 MeV Emin = 9.64317E+00 MeV : (n,t) to ground state + 70 MT = 701 Q = -1.01466E+01 MeV Emin = 1.04392E+01 MeV : (n,t1) + 71 MT = 702 Q = -1.12719E+01 MeV Emin = 1.19533E+01 MeV : (n,t2) + 72 MT = 703 Q = -1.16181E+01 MeV Emin = 1.20000E+01 MeV : (n,t3) + 73 MT = 704 Q = -1.21720E+01 MeV Emin = 1.25924E+01 MeV : (n,t4) + 74 MT = 705 Q = -1.22393E+01 MeV Emin = 1.26283E+01 MeV : (n,t5) + 75 MT = 706 Q = -1.22742E+01 MeV Emin = 1.28868E+01 MeV : (n,t6) + 76 MT = 707 Q = -1.25255E+01 MeV Emin = 1.30000E+01 MeV : (n,t7) + 77 MT = 708 Q = -1.31372E+01 MeV Emin = 1.36221E+01 MeV : (n,t8) + 78 MT = 709 Q = -1.32402E+01 MeV Emin = 1.37384E+01 MeV : (n,t9) + 79 MT = 710 Q = -1.33532E+01 MeV Emin = 1.37440E+01 MeV : (n,t10) + 80 MT = 711 Q = -1.33586E+01 MeV Emin = 1.37861E+01 MeV : (n,t11) + 81 MT = 712 Q = -1.33996E+01 MeV Emin = 1.38373E+01 MeV : (n,t12) + 82 MT = 713 Q = -1.34493E+01 MeV Emin = 1.39059E+01 MeV : (n,t13) + 83 MT = 714 Q = -1.35160E+01 MeV Emin = 1.40000E+01 MeV : (n,t14) + 84 MT = 715 Q = -1.36805E+01 MeV Emin = 1.41262E+01 MeV : (n,t15) + 85 MT = 716 Q = -1.37301E+01 MeV Emin = 1.44399E+01 MeV : (n,t16) + 86 MT = 717 Q = -1.40350E+01 MeV Emin = 1.44570E+01 MeV : (n,t17) + 87 MT = 718 Q = -1.40516E+01 MeV Emin = 1.44570E+01 MeV : (n,t18) + 88 MT = 719 Q = -1.41713E+01 MeV Emin = 1.46349E+01 MeV : (n,t19) + 89 MT = 720 Q = -1.42246E+01 MeV Emin = 1.46586E+01 MeV : (n,t20) + 90 MT = 721 Q = -1.42476E+01 MeV Emin = 1.49004E+01 MeV : (n,t21) + 91 MT = 722 Q = -1.44826E+01 MeV Emin = 1.49333E+01 MeV : (n,t22) + 92 MT = 723 Q = -1.45146E+01 MeV Emin = 1.49992E+01 MeV : (n,t23) + 93 MT = 724 Q = -1.45786E+01 MeV Emin = 1.50000E+01 MeV : (n,t24) + 94 MT = 725 Q = -1.45876E+01 MeV Emin = 1.50650E+01 MeV : (n,t25) + 95 MT = 726 Q = -1.46426E+01 MeV Emin = 1.50650E+01 MeV : (n,t26) + 96 MT = 727 Q = -1.46526E+01 MeV Emin = 1.51247E+01 MeV : (n,t27) + 97 MT = 728 Q = -1.47006E+01 MeV Emin = 1.52071E+01 MeV : (n,t28) + 98 MT = 729 Q = -1.47807E+01 MeV Emin = 1.53325E+01 MeV : (n,t29) + 99 MT = 730 Q = -1.49026E+01 MeV Emin = 1.53325E+01 MeV : (n,t30) + 100 MT = 749 Q = -1.49026E+01 MeV Emin = 1.53325E+01 MeV : (n,t) to continuum + 101 MT = 800 Q = 9.38230E-01 MeV Emin = 1.00000E-11 MeV : (n,alpha) to ground state + 102 MT = 801 Q = 8.60130E-01 MeV Emin = 9.99658E-01 MeV : (n,a1) + 103 MT = 802 Q = 4.25230E-01 MeV Emin = 1.45768E+00 MeV : (n,a2) + 104 MT = 803 Q = -2.11470E-01 MeV Emin = 1.90700E+00 MeV : (n,a3) + 105 MT = 804 Q = -3.84970E-01 MeV Emin = 2.06309E+00 MeV : (n,a4) + 106 MT = 805 Q = -8.16270E-01 MeV Emin = 2.06309E+00 MeV : (n,a5) + 107 MT = 806 Q = -1.23957E+00 MeV Emin = 2.06309E+00 MeV : (n,a6) + 108 MT = 807 Q = -1.28067E+00 MeV Emin = 2.06309E+00 MeV : (n,a7) + 109 MT = 808 Q = -1.29157E+00 MeV Emin = 2.06309E+00 MeV : (n,a8) + 110 MT = 809 Q = -1.71957E+00 MeV Emin = 2.06309E+00 MeV : (n,a9) + 111 MT = 810 Q = -1.80647E+00 MeV Emin = 2.06309E+00 MeV : (n,a10) + 112 MT = 811 Q = -2.06657E+00 MeV Emin = 2.16261E+00 MeV : (n,a11) + 113 MT = 812 Q = -2.21117E+00 MeV Emin = 2.39071E+00 MeV : (n,a12) + 114 MT = 813 Q = -2.32577E+00 MeV Emin = 2.45284E+00 MeV : (n,a13) + 115 MT = 814 Q = -2.38407E+00 MeV Emin = 2.50000E+00 MeV : (n,a14) + 116 MT = 815 Q = -2.50477E+00 MeV Emin = 2.57908E+00 MeV : (n,a15) + 117 MT = 816 Q = -2.50677E+00 MeV Emin = 2.72191E+00 MeV : (n,a16) + 118 MT = 817 Q = -2.85867E+00 MeV Emin = 3.00000E+00 MeV : (n,a17) + 119 MT = 818 Q = -2.94177E+00 MeV Emin = 3.03023E+00 MeV : (n,a18) + 120 MT = 819 Q = -3.05127E+00 MeV Emin = 3.14773E+00 MeV : (n,a19) + 121 MT = 820 Q = -3.06887E+00 MeV Emin = 3.15739E+00 MeV : (n,a20) + 122 MT = 849 Q = -3.06887E+00 MeV Emin = 3.15739E+00 MeV : (n,alpha) to continuum + 123 MT = 4 Q = 0.00000E+00 MeV Emin = 1.25000E+00 MeV : total inelastic scattering + + Nuclide 31 / 1657 : 17037.82c -- chlorine 37 (Cl-37) + + Pointers : 158336 21627 + Primary type : Transport + Nuclide ZAI : 170370 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Cl37.ACE + Atomic weight (AW) : 36.96586 + Atomic weight ratio (AWR) : 36.64830 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 39 reaction channels + - 44 special reactions + - 10 transmutation reactions + - 8 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 39 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.03111E+01 MeV Emin = 1.05925E+01 MeV frac = 1.00000E+00 Product nuclide = 170360 : (n,2n) + 3 MT = 17 Q = -1.88908E+01 MeV Emin = 1.94063E+01 MeV frac = 1.00000E+00 Product nuclide = 17035.82c : (n,3n) + 4 MT = 22 Q = -7.84859E+00 MeV Emin = 8.06275E+00 MeV frac = 1.00000E+00 Product nuclide = 150330 : (n,nalpha) + 5 MT = 28 Q = -8.38656E+00 MeV Emin = 8.61540E+00 MeV frac = 1.00000E+00 Product nuclide = 16036.82c : (n,np) + 6 MT = 32 Q = -1.60507E+01 MeV Emin = 1.64887E+01 MeV frac = 1.00000E+00 Product nuclide = 160350 : (n,nd) + 7 MT = 51 Q = -1.72658E+00 MeV Emin = 1.75000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 8 MT = 52 Q = -3.08614E+00 MeV Emin = 3.17035E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 9 MT = 53 Q = -3.10350E+00 MeV Emin = 3.18818E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 10 MT = 54 Q = -3.62682E+00 MeV Emin = 3.72578E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 11 MT = 55 Q = -3.70779E+00 MeV Emin = 3.80896E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 12 MT = 56 Q = -3.74122E+00 MeV Emin = 3.84330E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 13 MT = 57 Q = -4.00987E+00 MeV Emin = 4.11929E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 14 MT = 58 Q = -4.01629E+00 MeV Emin = 4.12588E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 15 MT = 59 Q = -4.17664E+00 MeV Emin = 4.29061E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 16 MT = 60 Q = -4.26887E+00 MeV Emin = 4.38535E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 17 MT = 61 Q = -4.27259E+00 MeV Emin = 4.38917E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 18 MT = 62 Q = -4.39630E+00 MeV Emin = 4.51626E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 19 MT = 63 Q = -4.45997E+00 MeV Emin = 4.58167E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 20 MT = 64 Q = -4.54560E+00 MeV Emin = 4.66963E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 21 MT = 65 Q = -4.80121E+00 MeV Emin = 4.93222E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 22 MT = 66 Q = -4.81090E+00 MeV Emin = 4.94217E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 23 MT = 67 Q = -4.83761E+00 MeV Emin = 4.96961E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 24 MT = 68 Q = -4.85396E+00 MeV Emin = 4.98641E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 25 MT = 69 Q = -4.90420E+00 MeV Emin = 5.03802E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 26 MT = 70 Q = -4.92060E+00 MeV Emin = 5.05487E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 27 MT = 71 Q = -4.92300E+00 MeV Emin = 5.05733E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 28 MT = 72 Q = -4.96080E+00 MeV Emin = 5.09616E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 29 MT = 73 Q = -4.97400E+00 MeV Emin = 5.10972E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 30 MT = 74 Q = -5.00930E+00 MeV Emin = 5.14599E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 31 MT = 75 Q = -5.05520E+00 MeV Emin = 5.19314E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 32 MT = 76 Q = -5.05910E+00 MeV Emin = 5.19715E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 33 MT = 77 Q = -5.14300E+00 MeV Emin = 5.28334E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 27. excited state + 34 MT = 91 Q = -5.14300E+00 MeV Emin = 5.28334E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 35 MT = 102 Q = 6.10783E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 170380 : (n,gamma) + 36 MT = 103 Q = -4.08295E+00 MeV Emin = 4.19436E+00 MeV frac = 1.00000E+00 Product nuclide = 160370 : (n,p) + 37 MT = 104 Q = -6.16197E+00 MeV Emin = 6.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 16036.82c : (n,d) + 38 MT = 105 Q = -9.79340E+00 MeV Emin = 1.05000E+01 MeV frac = 1.00000E+00 Product nuclide = 160350 : (n,t) + 39 MT = 107 Q = -1.55761E+00 MeV Emin = 3.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 150340 : (n,alpha) + + 8 additional transport branches: + + 1 MT = 22 Q = -7.84859E+00 MeV Emin = 8.06275E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -8.38656E+00 MeV Emin = 8.61540E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.60507E+01 MeV Emin = 1.64887E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 102 Q = 6.10783E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 170381 : (n,gamma) + 5 MT = 103 Q = -4.08295E+00 MeV Emin = 4.19436E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 104 Q = -6.16197E+00 MeV Emin = 6.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 7 MT = 105 Q = -9.79340E+00 MeV Emin = 1.05000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 8 MT = 107 Q = -1.55761E+00 MeV Emin = 3.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 44 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.19436E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.50000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.05000E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 3.50000E+00 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 649 Q = -4.08295E+00 MeV Emin = 4.19436E+00 MeV : (n,p) to continuum + 7 MT = 650 Q = -6.16197E+00 MeV Emin = 6.50000E+00 MeV : (n,d) to ground state + 8 MT = 651 Q = -9.45297E+00 MeV Emin = 1.00000E+01 MeV : (n,d1) + 9 MT = 652 Q = -9.50797E+00 MeV Emin = 1.00000E+01 MeV : (n,d2) + 10 MT = 653 Q = -1.03545E+01 MeV Emin = 1.10000E+01 MeV : (n,d3) + 11 MT = 654 Q = -1.06850E+01 MeV Emin = 1.10000E+01 MeV : (n,d4) + 12 MT = 655 Q = -1.07372E+01 MeV Emin = 1.15000E+01 MeV : (n,d5) + 13 MT = 656 Q = -1.14132E+01 MeV Emin = 1.17246E+01 MeV : (n,d6) + 14 MT = 657 Q = -1.15534E+01 MeV Emin = 1.20000E+01 MeV : (n,d7) + 15 MT = 658 Q = -1.16711E+01 MeV Emin = 1.20000E+01 MeV : (n,d8) + 16 MT = 659 Q = -1.17351E+01 MeV Emin = 1.20553E+01 MeV : (n,d9) + 17 MT = 660 Q = -1.23489E+01 MeV Emin = 1.27252E+01 MeV : (n,d10) + 18 MT = 661 Q = -1.23872E+01 MeV Emin = 1.30000E+01 MeV : (n,d11) + 19 MT = 699 Q = -1.23872E+01 MeV Emin = 1.27252E+01 MeV : (n,d) to continuum + 20 MT = 700 Q = -9.79340E+00 MeV Emin = 1.05000E+01 MeV : (n,t) to ground state + 21 MT = 701 Q = -1.13657E+01 MeV Emin = 1.20000E+01 MeV : (n,t1) + 22 MT = 702 Q = -1.17846E+01 MeV Emin = 1.24722E+01 MeV : (n,t2) + 23 MT = 703 Q = -1.21409E+01 MeV Emin = 1.25000E+01 MeV : (n,t3) + 24 MT = 704 Q = -1.25109E+01 MeV Emin = 1.30000E+01 MeV : (n,t4) + 25 MT = 705 Q = -1.27326E+01 MeV Emin = 1.35000E+01 MeV : (n,t5) + 26 MT = 706 Q = -1.32144E+01 MeV Emin = 1.35750E+01 MeV : (n,t6) + 27 MT = 707 Q = -1.33542E+01 MeV Emin = 1.37558E+01 MeV : (n,t7) + 28 MT = 708 Q = -1.33904E+01 MeV Emin = 1.38359E+01 MeV : (n,t8) + 29 MT = 709 Q = -1.34684E+01 MeV Emin = 1.38359E+01 MeV : (n,t9) + 30 MT = 710 Q = -1.35956E+01 MeV Emin = 1.39666E+01 MeV : (n,t10) + 31 MT = 711 Q = -1.36115E+01 MeV Emin = 1.40000E+01 MeV : (n,t11) + 32 MT = 712 Q = -1.36794E+01 MeV Emin = 1.40742E+01 MeV : (n,t12) + 33 MT = 713 Q = -1.37004E+01 MeV Emin = 1.40742E+01 MeV : (n,t13) + 34 MT = 714 Q = -1.38154E+01 MeV Emin = 1.41924E+01 MeV : (n,t14) + 35 MT = 715 Q = -1.38214E+01 MeV Emin = 1.45000E+01 MeV : (n,t15) + 36 MT = 749 Q = -1.38214E+01 MeV Emin = 1.41985E+01 MeV : (n,t) to continuum + 37 MT = 800 Q = -1.55761E+00 MeV Emin = 3.50000E+00 MeV : (n,alpha) to ground state + 38 MT = 801 Q = -1.98668E+00 MeV Emin = 4.00000E+00 MeV : (n,a1) + 39 MT = 802 Q = -3.16521E+00 MeV Emin = 5.00000E+00 MeV : (n,a2) + 40 MT = 803 Q = -3.78261E+00 MeV Emin = 5.50000E+00 MeV : (n,a3) + 41 MT = 804 Q = -3.86661E+00 MeV Emin = 5.50000E+00 MeV : (n,a4) + 42 MT = 805 Q = -4.90261E+00 MeV Emin = 7.00000E+00 MeV : (n,a5) + 43 MT = 849 Q = -4.90261E+00 MeV Emin = 5.03639E+00 MeV : (n,alpha) to continuum + 44 MT = 4 Q = 0.00000E+00 MeV Emin = 1.75000E+00 MeV : total inelastic scattering + + Nuclide 32 / 1657 : 18038.82c -- argon 38 (Ar-38) + + Pointers : 168624 19189 + Primary type : Transport + Nuclide ZAI : 180380 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ar38.ACE + Atomic weight (AW) : 37.96272 + Atomic weight ratio (AWR) : 37.63660 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 29 reaction channels + - 5 special reactions + - 8 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 29 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.16890E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 180370 : (n,2n) + 3 MT = 22 Q = -7.20900E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 16034.82c : (n,nalpha) + 4 MT = 28 Q = -1.02400E+01 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 17037.82c : (n,np) + 5 MT = 51 Q = -2.16800E+00 MeV Emin = 2.22560E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -3.37800E+00 MeV Emin = 3.46775E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -3.81000E+00 MeV Emin = 3.91123E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -3.93700E+00 MeV Emin = 4.04161E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -4.48000E+00 MeV Emin = 4.59903E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -4.56500E+00 MeV Emin = 4.68629E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -4.58600E+00 MeV Emin = 4.70785E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -4.71000E+00 MeV Emin = 4.83514E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -4.87700E+00 MeV Emin = 5.00658E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -5.08400E+00 MeV Emin = 5.21908E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -5.15700E+00 MeV Emin = 5.29402E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -5.35000E+00 MeV Emin = 5.49215E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 63 Q = -5.51300E+00 MeV Emin = 5.65948E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 18 MT = 64 Q = -5.55200E+00 MeV Emin = 5.69952E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 19 MT = 65 Q = -5.59500E+00 MeV Emin = 5.74366E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 20 MT = 66 Q = -5.65800E+00 MeV Emin = 5.80833E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 21 MT = 67 Q = -5.73400E+00 MeV Emin = 5.88635E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 22 MT = 68 Q = -5.82500E+00 MeV Emin = 5.97977E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 23 MT = 69 Q = -5.85700E+00 MeV Emin = 6.01262E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 24 MT = 91 Q = -5.90000E+00 MeV Emin = 6.05676E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 25 MT = 102 Q = 6.59970E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 180390 : (n,gamma) + 26 MT = 103 Q = -4.87060E+00 MeV Emin = 5.00001E+00 MeV frac = 1.00000E+00 Product nuclide = 170380 : (n,p) + 27 MT = 104 Q = -7.79290E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 17037.82c : (n,d) + 28 MT = 107 Q = -2.22200E-01 MeV Emin = 2.12517E-01 MeV frac = 1.00000E+00 Product nuclide = 160350 : (n,alpha) + 29 MT = 108 Q = -8.54500E+00 MeV Emin = 8.77204E+00 MeV frac = 1.00000E+00 Product nuclide = 140310 : (n,2alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = -7.20900E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.02400E+01 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -4.87060E+00 MeV Emin = 5.00001E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -7.79290E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 107 Q = -2.22200E-01 MeV Emin = 2.12517E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 108 Q = -8.54500E+00 MeV Emin = 8.77204E+00 MeV frac = 2.00000E+00 Product nuclide = 2004.82c : (n,2alpha) + + 5 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 5.00001E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.00000E+00 MeV : total deuteron production + 3 MT = 207 Q = 0.00000E+00 MeV Emin = 2.12517E-01 MeV : total alpha production + 4 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 5 MT = 4 Q = 0.00000E+00 MeV Emin = 2.22560E+00 MeV : total inelastic scattering + + Nuclide 33 / 1657 : 18040.82c -- argon 40 (Ar-40) + + Pointers : 171872 19235 + Primary type : Transport + Nuclide ZAI : 180400 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ar40.ACE + Atomic weight (AW) : 39.96240 + Atomic weight ratio (AWR) : 39.61910 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 37 reaction channels + - 7 special reactions + - 10 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 37 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -9.87088E+00 MeV Emin = 1.01200E+01 MeV frac = 1.00000E+00 Product nuclide = 180390 : (n,2n) + 3 MT = 17 Q = -1.64682E+01 MeV Emin = 1.68839E+01 MeV frac = 1.00000E+00 Product nuclide = 18038.82c : (n,3n) + 4 MT = 22 Q = -6.79823E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 16036.82c : (n,nalpha) + 5 MT = 28 Q = -1.25264E+01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 170390 : (n,np) + 6 MT = 51 Q = -1.46090E+00 MeV Emin = 1.49730E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -2.12080E+00 MeV Emin = 2.17433E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -2.52410E+00 MeV Emin = 2.58781E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -2.89300E+00 MeV Emin = 2.96602E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -3.20830E+00 MeV Emin = 3.28928E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -3.46449E+00 MeV Emin = 3.55194E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -3.51129E+00 MeV Emin = 3.59992E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -3.51499E+00 MeV Emin = 3.60371E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -3.68099E+00 MeV Emin = 3.77390E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -3.91879E+00 MeV Emin = 4.01770E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -3.94199E+00 MeV Emin = 4.04149E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -4.04199E+00 MeV Emin = 4.14401E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -4.08249E+00 MeV Emin = 4.18553E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -4.17899E+00 MeV Emin = 4.28447E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -4.22599E+00 MeV Emin = 4.33266E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 21 MT = 66 Q = -4.22899E+00 MeV Emin = 4.33573E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 22 MT = 67 Q = -4.30119E+00 MeV Emin = 4.40975E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 23 MT = 68 Q = -4.32449E+00 MeV Emin = 4.43364E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 24 MT = 69 Q = -4.35799E+00 MeV Emin = 4.46799E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 25 MT = 70 Q = -4.41899E+00 MeV Emin = 4.53053E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 26 MT = 71 Q = -4.42699E+00 MeV Emin = 4.53873E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 27 MT = 72 Q = -4.48099E+00 MeV Emin = 4.59409E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 28 MT = 73 Q = -4.49399E+00 MeV Emin = 4.60742E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 29 MT = 74 Q = -4.56199E+00 MeV Emin = 4.67714E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 30 MT = 75 Q = -4.57799E+00 MeV Emin = 4.69354E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 31 MT = 91 Q = -4.57999E+00 MeV Emin = 4.69559E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 32 MT = 102 Q = 6.09939E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 180410 : (n,gamma) + 33 MT = 103 Q = -6.71672E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 170400 : (n,p) + 34 MT = 104 Q = -1.03018E+01 MeV Emin = 1.05618E+01 MeV frac = 1.00000E+00 Product nuclide = 170390 : (n,d) + 35 MT = 105 Q = -1.21179E+01 MeV Emin = 1.24238E+01 MeV frac = 1.00000E+00 Product nuclide = 170380 : (n,t) + 36 MT = 106 Q = -1.50362E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 160380 : (n,He-3) + 37 MT = 107 Q = -2.48545E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 160370 : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -6.79823E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.25264E+01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -6.71672E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -1.03018E+01 MeV Emin = 1.05618E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -1.21179E+01 MeV Emin = 1.24238E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 106 Q = -1.50362E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 7 MT = 107 Q = -2.48545E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 7.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.05618E+01 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.24238E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.60000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 3.00000E+00 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 1.49730E+00 MeV : total inelastic scattering + + Nuclide 34 / 1657 : 19039.82c -- potassium 39 (K-39) + + Pointers : 178044 26825 + Primary type : Transport + Nuclide ZAI : 190390 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/K39.ACE + Atomic weight (AW) : 38.96402 + Atomic weight ratio (AWR) : 38.62930 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 12 reaction channels + - 4 special reactions + - 6 transmutation reactions + - 4 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 12 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.30850E+01 MeV Emin = 1.35000E+01 MeV frac = 1.00000E+00 Product nuclide = 190380 : (n,2n) + 3 MT = 22 Q = -7.21723E+00 MeV Emin = 7.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 17035.82c : (n,nalpha) + 4 MT = 28 Q = -6.38011E+00 MeV Emin = 6.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 18038.82c : (n,np) + 5 MT = 51 Q = -2.52300E+00 MeV Emin = 2.58831E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -2.81400E+00 MeV Emin = 2.88685E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -3.01900E+00 MeV Emin = 3.09715E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -3.59799E+00 MeV Emin = 3.69114E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 91 Q = -3.79999E+00 MeV Emin = 3.89837E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 10 MT = 102 Q = 7.80099E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 19040.82c : (n,gamma) + 11 MT = 103 Q = 2.17170E-01 MeV Emin = 9.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 180390 : (n,p) + 12 MT = 107 Q = 1.36325E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 170360 : (n,alpha) + + 4 additional transport branches: + + 1 MT = 22 Q = -7.21723E+00 MeV Emin = 7.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -6.38011E+00 MeV Emin = 6.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = 2.17170E-01 MeV Emin = 9.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 107 Q = 1.36325E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 4 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 9.00000E-01 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 4 MT = 4 Q = 0.00000E+00 MeV Emin = 2.58831E+00 MeV : total inelastic scattering + + Nuclide 35 / 1657 : 19040.82c -- potassium 40 (K-40) + + Pointers : 179615 26871 + Primary type : Transport + Nuclide ZAI : 190400 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/K40.ACE + Atomic weight (AW) : 39.96401 + Atomic weight ratio (AWR) : 39.62070 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 3.95E+16 seconds (1.25 billion years) + Specific ingestion toxicity : 6.20E-09 Sv/Bq + Specific inhalation toxicity : 2.10E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 13 reaction channels + - 4 special reactions + - 6 transmutation reactions + - 4 transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 13 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.80048E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 19039.82c : (n,2n) + 3 MT = 22 Q = -6.43723E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 170360 : (n,nalpha) + 4 MT = 28 Q = -7.58331E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 180390 : (n,np) + 5 MT = 51 Q = -3.00000E-02 MeV Emin = 3.05078E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -7.99999E-01 MeV Emin = 8.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -8.91999E-01 MeV Emin = 9.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -1.64400E+00 MeV Emin = 1.59275E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -1.95900E+00 MeV Emin = 2.00845E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 91 Q = -2.10000E+00 MeV Emin = 2.15300E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 11 MT = 102 Q = 1.00960E+01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 19041.82c : (n,gamma) + 12 MT = 103 Q = 2.28757E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 18040.82c : (n,p) + 13 MT = 107 Q = 3.87414E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 17037.82c : (n,alpha) + + 4 additional transport branches: + + 1 MT = 22 Q = -6.43723E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -7.58331E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = 2.28757E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 107 Q = 3.87414E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 4 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 4 MT = 4 Q = 0.00000E+00 MeV Emin = 3.05078E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 2 Q = 1.50469E+00 MeV frac = 1.07500E-01 Product nuclide = 18040.82c : EC/beta+ + 2 RTYP = 1 Q = 1.31107E+00 MeV frac = 8.92500E-01 Product nuclide = 200400 : beta- + + Nuclide 36 / 1657 : 19041.82c -- potassium 41 (K-41) + + Pointers : 181550 26917 + Primary type : Transport + Nuclide ZAI : 190410 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/K41.ACE + Atomic weight (AW) : 40.96198 + Atomic weight ratio (AWR) : 40.61010 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 10 reaction channels + - 4 special reactions + - 6 transmutation reactions + - 4 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 10 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.00959E+01 MeV Emin = 1.03445E+01 MeV frac = 1.00000E+00 Product nuclide = 19040.82c : (n,2n) + 3 MT = 22 Q = -6.22173E+00 MeV Emin = 6.40000E+00 MeV frac = 1.00000E+00 Product nuclide = 17037.82c : (n,nalpha) + 4 MT = 28 Q = -7.80831E+00 MeV Emin = 8.00059E+00 MeV frac = 1.00000E+00 Product nuclide = 18040.82c : (n,np) + 5 MT = 51 Q = -9.79999E-01 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -1.29400E+00 MeV Emin = 1.28793E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 91 Q = -1.50000E+00 MeV Emin = 1.52459E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 8 MT = 102 Q = 7.53499E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 190420 : (n,gamma) + 9 MT = 103 Q = -1.70973E+00 MeV Emin = 1.75000E+00 MeV frac = 1.00000E+00 Product nuclide = 180410 : (n,p) + 10 MT = 107 Q = -1.11550E-01 MeV Emin = 1.14284E-01 MeV frac = 1.00000E+00 Product nuclide = 170380 : (n,alpha) + + 4 additional transport branches: + + 1 MT = 22 Q = -6.22173E+00 MeV Emin = 6.40000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -7.80831E+00 MeV Emin = 8.00059E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -1.70973E+00 MeV Emin = 1.75000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 107 Q = -1.11550E-01 MeV Emin = 1.14284E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 4 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.75000E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 1.14284E-01 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 4 MT = 4 Q = 0.00000E+00 MeV Emin = 1.00000E+00 MeV : total inelastic scattering + + Nuclide 37 / 1657 : 20042.82c -- calcium 42 (Ca-42) + + Pointers : 188411 20431 + Primary type : Transport + Nuclide ZAI : 200420 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ca42.ACE + Atomic weight (AW) : 41.95863 + Atomic weight ratio (AWR) : 41.59818 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+02 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 39 reaction channels + - 52 special reactions + - 16 transmutation reactions + - 17 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 39 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 5 Q = 0.00000E+00 MeV Emin = 2.99795E-01 MeV frac = 1.00000E+00 Product nuclide = self : anything + 3 MT = 16 Q = -1.14806E+01 MeV Emin = 1.17566E+01 MeV frac = 1.00000E+00 Product nuclide = 200410 : (n,2n) + 4 MT = 22 Q = -6.25691E+00 MeV Emin = 7.20000E+00 MeV frac = 1.00000E+00 Product nuclide = 18038.82c : (n,nalpha) + 5 MT = 28 Q = -1.02769E+01 MeV Emin = 1.05240E+01 MeV frac = 1.00000E+00 Product nuclide = 19041.82c : (n,np) + 6 MT = 29 Q = -1.34647E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 16034.82c : (n,n2alpha) + 7 MT = 32 Q = -1.81475E+01 MeV Emin = 1.85838E+01 MeV frac = 1.00000E+00 Product nuclide = 19040.82c : (n,nd) + 8 MT = 51 Q = -1.52473E+00 MeV Emin = 1.53069E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -1.83730E+00 MeV Emin = 1.85601E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -2.42417E+00 MeV Emin = 2.48245E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -2.75241E+00 MeV Emin = 2.81858E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -3.18933E+00 MeV Emin = 3.26600E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -3.25390E+00 MeV Emin = 3.33212E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -3.30000E+00 MeV Emin = 3.37933E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -3.39200E+00 MeV Emin = 3.47354E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -3.44696E+00 MeV Emin = 3.52982E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -3.65400E+00 MeV Emin = 3.74184E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -3.88500E+00 MeV Emin = 3.97839E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 62 Q = -3.95441E+00 MeV Emin = 4.04947E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 20 MT = 63 Q = -3.99967E+00 MeV Emin = 4.09582E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 21 MT = 64 Q = -4.04700E+00 MeV Emin = 4.14429E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 22 MT = 65 Q = -4.09970E+00 MeV Emin = 4.19826E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 23 MT = 66 Q = -4.11700E+00 MeV Emin = 4.21597E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 24 MT = 67 Q = -4.23200E+00 MeV Emin = 4.33374E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 25 MT = 68 Q = -4.35400E+00 MeV Emin = 4.45867E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 26 MT = 69 Q = -4.41800E+00 MeV Emin = 4.52421E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 27 MT = 70 Q = -4.44300E+00 MeV Emin = 4.54981E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 28 MT = 91 Q = -4.44300E+00 MeV Emin = 4.54981E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 29 MT = 102 Q = 7.93300E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 20043.82c : (n,gamma) + 30 MT = 103 Q = -2.74309E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 190420 : (n,p) + 31 MT = 104 Q = -8.05229E+00 MeV Emin = 8.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 19041.82c : (n,d) + 32 MT = 105 Q = -1.18902E+01 MeV Emin = 1.21761E+01 MeV frac = 1.00000E+00 Product nuclide = 19040.82c : (n,t) + 33 MT = 106 Q = -1.03668E+01 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 18040.82c : (n,He-3) + 34 MT = 107 Q = 3.41482E-01 MeV Emin = 6.50000E-01 MeV frac = 1.00000E+00 Product nuclide = 180390 : (n,alpha) + 35 MT = 108 Q = -6.47890E+00 MeV Emin = 9.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 160350 : (n,2alpha) + 36 MT = 111 Q = -1.19861E+01 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 180410 : (n,2p) + 37 MT = 112 Q = -1.03913E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 170380 : (n,palpha) + 38 MT = 115 Q = -1.58602E+01 MeV Emin = 1.70000E+01 MeV frac = 1.00000E+00 Product nuclide = 18040.82c : (n,pd) + 39 MT = 117 Q = -1.42746E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 17037.82c : (n,dalpha) + + 17 additional transport branches: + + 1 MT = 22 Q = -6.25691E+00 MeV Emin = 7.20000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.02769E+01 MeV Emin = 1.05240E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 29 Q = -1.34647E+01 MeV Emin = 1.60000E+01 MeV frac = 2.00000E+00 Product nuclide = 2004.82c : (n,n2alpha) + 4 MT = 32 Q = -1.81475E+01 MeV Emin = 1.85838E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 5 MT = 103 Q = -2.74309E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 104 Q = -8.05229E+00 MeV Emin = 8.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 7 MT = 105 Q = -1.18902E+01 MeV Emin = 1.21761E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 8 MT = 106 Q = -1.03668E+01 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 9 MT = 107 Q = 3.41482E-01 MeV Emin = 6.50000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 10 MT = 108 Q = -6.47890E+00 MeV Emin = 9.50000E+00 MeV frac = 2.00000E+00 Product nuclide = 2004.82c : (n,2alpha) + 11 MT = 111 Q = -1.19861E+01 MeV Emin = 1.25000E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + 12 MT = 112 Q = -1.03913E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,palpha) + 13 MT = 112 Q = -1.03913E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,palpha) + 14 MT = 115 Q = -1.58602E+01 MeV Emin = 1.70000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,pd) + 15 MT = 115 Q = -1.58602E+01 MeV Emin = 1.70000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,pd) + 16 MT = 117 Q = -1.42746E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,dalpha) + 17 MT = 117 Q = -1.42746E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,dalpha) + + 52 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.50000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.21761E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.10000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 6.50000E-01 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 3.87500E-04 MeV : damage-energy production + 7 MT = 600 Q = -2.74309E+00 MeV Emin = 3.00000E+00 MeV : (n,p) to ground state + 8 MT = 601 Q = -2.84992E+00 MeV Emin = 3.20000E+00 MeV : (n,p1) + 9 MT = 602 Q = -3.00135E+00 MeV Emin = 3.20000E+00 MeV : (n,p2) + 10 MT = 603 Q = -3.38182E+00 MeV Emin = 3.60000E+00 MeV : (n,p3) + 11 MT = 604 Q = -3.42504E+00 MeV Emin = 3.80000E+00 MeV : (n,p4) + 12 MT = 605 Q = -3.44217E+00 MeV Emin = 3.80000E+00 MeV : (n,p5) + 13 MT = 606 Q = -3.52696E+00 MeV Emin = 3.80000E+00 MeV : (n,p6) + 14 MT = 607 Q = -3.58503E+00 MeV Emin = 3.80000E+00 MeV : (n,p7) + 15 MT = 608 Q = -3.85384E+00 MeV Emin = 4.20000E+00 MeV : (n,p8) + 16 MT = 609 Q = -3.88668E+00 MeV Emin = 4.20000E+00 MeV : (n,p9) + 17 MT = 610 Q = -3.94099E+00 MeV Emin = 4.20000E+00 MeV : (n,p10) + 18 MT = 649 Q = -3.94099E+00 MeV Emin = 4.40000E+00 MeV : (n,p) to continuum + 19 MT = 650 Q = -8.05229E+00 MeV Emin = 8.50000E+00 MeV : (n,d) to ground state + 20 MT = 651 Q = -9.03277E+00 MeV Emin = 9.24991E+00 MeV : (n,d1) + 21 MT = 652 Q = -9.34590E+00 MeV Emin = 9.57057E+00 MeV : (n,d2) + 22 MT = 653 Q = -9.61219E+00 MeV Emin = 1.00000E+01 MeV : (n,d3) + 23 MT = 654 Q = -9.63429E+00 MeV Emin = 1.00000E+01 MeV : (n,d4) + 24 MT = 655 Q = -9.64540E+00 MeV Emin = 1.00000E+01 MeV : (n,d5) + 25 MT = 699 Q = -9.64540E+00 MeV Emin = 1.00000E+01 MeV : (n,d) to continuum + 26 MT = 700 Q = -1.18902E+01 MeV Emin = 1.21761E+01 MeV : (n,t) to ground state + 27 MT = 701 Q = -1.19201E+01 MeV Emin = 1.25000E+01 MeV : (n,t1) + 28 MT = 702 Q = -1.26904E+01 MeV Emin = 1.30000E+01 MeV : (n,t2) + 29 MT = 703 Q = -1.27816E+01 MeV Emin = 1.30889E+01 MeV : (n,t3) + 30 MT = 704 Q = -1.35339E+01 MeV Emin = 1.38593E+01 MeV : (n,t4) + 31 MT = 705 Q = -1.38493E+01 MeV Emin = 1.41822E+01 MeV : (n,t5) + 32 MT = 749 Q = -1.38493E+01 MeV Emin = 1.50000E+01 MeV : (n,t) to continuum + 33 MT = 750 Q = -1.03668E+01 MeV Emin = 1.10000E+01 MeV : (n,He-3) to ground state + 34 MT = 751 Q = -1.18276E+01 MeV Emin = 1.21119E+01 MeV : (n,He-3_1) + 35 MT = 752 Q = -1.24876E+01 MeV Emin = 1.30000E+01 MeV : (n,He-3_2) + 36 MT = 753 Q = -1.28909E+01 MeV Emin = 1.40000E+01 MeV : (n,He-3_3) + 37 MT = 754 Q = -1.32594E+01 MeV Emin = 1.40000E+01 MeV : (n,He-3_4) + 38 MT = 755 Q = -1.35748E+01 MeV Emin = 1.45000E+01 MeV : (n,He-3_5) + 39 MT = 799 Q = -1.35748E+01 MeV Emin = 1.50000E+01 MeV : (n,He-3) to continuum + 40 MT = 800 Q = 3.41482E-01 MeV Emin = 6.50000E-01 MeV : (n,alpha) to ground state + 41 MT = 801 Q = -9.25728E-01 MeV Emin = 2.00000E+00 MeV : (n,a1) + 42 MT = 802 Q = -1.17606E+00 MeV Emin = 2.00000E+00 MeV : (n,a2) + 43 MT = 803 Q = -1.75127E+00 MeV Emin = 2.60000E+00 MeV : (n,a3) + 44 MT = 804 Q = -2.00072E+00 MeV Emin = 2.80000E+00 MeV : (n,a4) + 45 MT = 805 Q = -2.01680E+00 MeV Emin = 2.80000E+00 MeV : (n,a5) + 46 MT = 806 Q = -2.09200E+00 MeV Emin = 2.80000E+00 MeV : (n,a6) + 47 MT = 807 Q = -2.14001E+00 MeV Emin = 3.00000E+00 MeV : (n,a7) + 48 MT = 808 Q = -2.16194E+00 MeV Emin = 3.00000E+00 MeV : (n,a8) + 49 MT = 809 Q = -2.18226E+00 MeV Emin = 3.00000E+00 MeV : (n,a9) + 50 MT = 810 Q = -2.29008E+00 MeV Emin = 3.00000E+00 MeV : (n,a10) + 51 MT = 849 Q = -2.29008E+00 MeV Emin = 4.00000E+00 MeV : (n,alpha) to continuum + 52 MT = 4 Q = 0.00000E+00 MeV Emin = 1.53069E+00 MeV : total inelastic scattering + + Nuclide 38 / 1657 : 20043.82c -- calcium 43 (Ca-43) + + Pointers : 196406 20477 + Primary type : Transport + Nuclide ZAI : 200430 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ca43.ACE + Atomic weight (AW) : 42.95877 + Atomic weight ratio (AWR) : 42.58973 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+02 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 39 reaction channels + - 52 special reactions + - 16 transmutation reactions + - 14 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 39 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 5 Q = 0.00000E+00 MeV Emin = 3.99661E-02 MeV frac = 1.00000E+00 Product nuclide = self : anything + 3 MT = 16 Q = -7.93300E+00 MeV Emin = 8.11927E+00 MeV frac = 1.00000E+00 Product nuclide = 20042.82c : (n,2n) + 4 MT = 17 Q = -1.94136E+01 MeV Emin = 1.98694E+01 MeV frac = 1.00000E+00 Product nuclide = 200410 : (n,3n) + 5 MT = 22 Q = -7.59152E+00 MeV Emin = 8.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 180390 : (n,nalpha) + 6 MT = 24 Q = -1.41899E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 18038.82c : (n,2nalpha) + 7 MT = 28 Q = -1.06761E+01 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 190420 : (n,np) + 8 MT = 32 Q = -1.59853E+01 MeV Emin = 1.63606E+01 MeV frac = 1.00000E+00 Product nuclide = 19041.82c : (n,nd) + 9 MT = 41 Q = -1.82099E+01 MeV Emin = 1.86375E+01 MeV frac = 1.00000E+00 Product nuclide = 19041.82c : (n,2np) + 10 MT = 51 Q = -3.72762E-01 MeV Emin = 3.65757E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 11 MT = 52 Q = -5.93394E-01 MeV Emin = 6.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 12 MT = 53 Q = -9.90257E-01 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 13 MT = 54 Q = -1.39447E+00 MeV Emin = 1.40000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 14 MT = 55 Q = -1.67780E+00 MeV Emin = 1.70000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 15 MT = 56 Q = -1.90180E+00 MeV Emin = 1.93193E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 16 MT = 57 Q = -1.93130E+00 MeV Emin = 1.96721E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 17 MT = 58 Q = -1.95740E+00 MeV Emin = 2.00336E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 18 MT = 59 Q = -2.04625E+00 MeV Emin = 2.09430E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 19 MT = 60 Q = -2.06730E+00 MeV Emin = 2.11584E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 20 MT = 61 Q = -2.09390E+00 MeV Emin = 2.14306E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 21 MT = 62 Q = -2.10270E+00 MeV Emin = 2.15207E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 22 MT = 63 Q = -2.22400E+00 MeV Emin = 2.27622E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 23 MT = 64 Q = -2.24900E+00 MeV Emin = 2.30181E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 24 MT = 65 Q = -2.27270E+00 MeV Emin = 2.32606E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 25 MT = 66 Q = -2.40980E+00 MeV Emin = 2.46638E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 26 MT = 67 Q = -2.52300E+00 MeV Emin = 2.58224E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 27 MT = 68 Q = -2.61100E+00 MeV Emin = 2.67231E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 28 MT = 69 Q = -2.67370E+00 MeV Emin = 2.73648E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 29 MT = 70 Q = -2.69690E+00 MeV Emin = 2.76022E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 30 MT = 91 Q = -2.69690E+00 MeV Emin = 2.76022E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 31 MT = 102 Q = 1.11320E+01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 20044.82c : (n,gamma) + 32 MT = 103 Q = -1.03305E+00 MeV Emin = 1.18437E+00 MeV frac = 1.00000E+00 Product nuclide = 190430 : (n,p) + 33 MT = 104 Q = -8.45152E+00 MeV Emin = 8.64996E+00 MeV frac = 1.00000E+00 Product nuclide = 190420 : (n,d) + 34 MT = 105 Q = -9.72804E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 19041.82c : (n,t) + 35 MT = 106 Q = -1.22011E+01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 180410 : (n,He-3) + 36 MT = 107 Q = 2.27786E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 18040.82c : (n,alpha) + 37 MT = 108 Q = -4.52299E+00 MeV Emin = 7.40000E+00 MeV frac = 1.00000E+00 Product nuclide = 16036.82c : (n,2alpha) + 38 MT = 111 Q = -1.04930E+01 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 180420 : (n,2p) + 39 MT = 112 Q = -1.02503E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 170390 : (n,palpha) + + 14 additional transport branches: + + 1 MT = 22 Q = -7.59152E+00 MeV Emin = 8.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 24 Q = -1.41899E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,2nalpha) + 3 MT = 28 Q = -1.06761E+01 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 4 MT = 32 Q = -1.59853E+01 MeV Emin = 1.63606E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 5 MT = 41 Q = -1.82099E+01 MeV Emin = 1.86375E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,2np) + 6 MT = 103 Q = -1.03305E+00 MeV Emin = 1.18437E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 7 MT = 104 Q = -8.45152E+00 MeV Emin = 8.64996E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 8 MT = 105 Q = -9.72804E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 9 MT = 106 Q = -1.22011E+01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 10 MT = 107 Q = 2.27786E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 11 MT = 108 Q = -4.52299E+00 MeV Emin = 7.40000E+00 MeV frac = 2.00000E+00 Product nuclide = 2004.82c : (n,2alpha) + 12 MT = 111 Q = -1.04930E+01 MeV Emin = 1.10000E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + 13 MT = 112 Q = -1.02503E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,palpha) + 14 MT = 112 Q = -1.02503E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,palpha) + + 52 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.18437E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.64996E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.00000E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.30000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 600 Q = -1.03305E+00 MeV Emin = 1.18437E+00 MeV : (n,p) to ground state + 8 MT = 601 Q = -1.59425E+00 MeV Emin = 1.77412E+00 MeV : (n,p1) + 9 MT = 602 Q = -1.77115E+00 MeV Emin = 1.98541E+00 MeV : (n,p2) + 10 MT = 603 Q = -2.00805E+00 MeV Emin = 2.20000E+00 MeV : (n,p3) + 11 MT = 604 Q = -2.14335E+00 MeV Emin = 2.40000E+00 MeV : (n,p4) + 12 MT = 605 Q = -2.23995E+00 MeV Emin = 2.40000E+00 MeV : (n,p5) + 13 MT = 606 Q = -2.54295E+00 MeV Emin = 2.60266E+00 MeV : (n,p6) + 14 MT = 607 Q = -2.58265E+00 MeV Emin = 2.80000E+00 MeV : (n,p7) + 15 MT = 608 Q = -2.84805E+00 MeV Emin = 2.91492E+00 MeV : (n,p8) + 16 MT = 609 Q = -2.88315E+00 MeV Emin = 3.00000E+00 MeV : (n,p9) + 17 MT = 610 Q = -2.89905E+00 MeV Emin = 3.00000E+00 MeV : (n,p10) + 18 MT = 649 Q = -2.89905E+00 MeV Emin = 3.20000E+00 MeV : (n,p) to continuum + 19 MT = 650 Q = -8.45152E+00 MeV Emin = 8.64996E+00 MeV : (n,d) to ground state + 20 MT = 651 Q = -8.55835E+00 MeV Emin = 9.00000E+00 MeV : (n,d1) + 21 MT = 652 Q = -8.70978E+00 MeV Emin = 9.00000E+00 MeV : (n,d2) + 22 MT = 653 Q = -9.09025E+00 MeV Emin = 9.30369E+00 MeV : (n,d3) + 23 MT = 654 Q = -9.13346E+00 MeV Emin = 9.50000E+00 MeV : (n,d4) + 24 MT = 655 Q = -9.15060E+00 MeV Emin = 9.50000E+00 MeV : (n,d5) + 25 MT = 699 Q = -9.15060E+00 MeV Emin = 9.50000E+00 MeV : (n,d) to continuum + 26 MT = 700 Q = -9.72804E+00 MeV Emin = 1.00000E+01 MeV : (n,t) to ground state + 27 MT = 701 Q = -1.07085E+01 MeV Emin = 1.09600E+01 MeV : (n,t1) + 28 MT = 702 Q = -1.10217E+01 MeV Emin = 1.15000E+01 MeV : (n,t2) + 29 MT = 703 Q = -1.12879E+01 MeV Emin = 1.15530E+01 MeV : (n,t3) + 30 MT = 704 Q = -1.13100E+01 MeV Emin = 1.15756E+01 MeV : (n,t4) + 31 MT = 705 Q = -1.13212E+01 MeV Emin = 1.15870E+01 MeV : (n,t5) + 32 MT = 749 Q = -1.13212E+01 MeV Emin = 1.20000E+01 MeV : (n,t) to continuum + 33 MT = 750 Q = -1.22011E+01 MeV Emin = 1.30000E+01 MeV : (n,He-3) to ground state + 34 MT = 751 Q = -1.23684E+01 MeV Emin = 1.35000E+01 MeV : (n,He-3_1) + 35 MT = 752 Q = -1.27171E+01 MeV Emin = 1.35000E+01 MeV : (n,He-3_2) + 36 MT = 753 Q = -1.32358E+01 MeV Emin = 1.40000E+01 MeV : (n,He-3_3) + 37 MT = 754 Q = -1.35551E+01 MeV Emin = 1.45000E+01 MeV : (n,He-3_4) + 38 MT = 755 Q = -1.38361E+01 MeV Emin = 1.50000E+01 MeV : (n,He-3_5) + 39 MT = 799 Q = -1.38361E+01 MeV Emin = 1.50000E+01 MeV : (n,He-3) to continuum + 40 MT = 800 Q = 2.27786E+00 MeV Emin = 1.00000E-11 MeV : (n,alpha) to ground state + 41 MT = 801 Q = 8.16999E-01 MeV Emin = 1.00000E-11 MeV : (n,a1) + 42 MT = 802 Q = 1.57059E-01 MeV Emin = 1.01445E+00 MeV : (n,a2) + 43 MT = 803 Q = -2.46241E-01 MeV Emin = 1.35000E+00 MeV : (n,a3) + 44 MT = 804 Q = -6.14741E-01 MeV Emin = 1.70000E+00 MeV : (n,a4) + 45 MT = 805 Q = -9.30141E-01 MeV Emin = 2.00000E+00 MeV : (n,a5) + 46 MT = 806 Q = -1.18662E+00 MeV Emin = 2.00000E+00 MeV : (n,a6) + 47 MT = 807 Q = -1.23344E+00 MeV Emin = 2.00000E+00 MeV : (n,a7) + 48 MT = 808 Q = -1.23714E+00 MeV Emin = 2.00000E+00 MeV : (n,a8) + 49 MT = 809 Q = -1.40294E+00 MeV Emin = 2.20000E+00 MeV : (n,a9) + 50 MT = 810 Q = -1.64094E+00 MeV Emin = 2.40000E+00 MeV : (n,a10) + 51 MT = 849 Q = -1.64094E+00 MeV Emin = 2.60000E+00 MeV : (n,alpha) to continuum + 52 MT = 4 Q = 0.00000E+00 MeV Emin = 3.65757E-01 MeV : total inelastic scattering + + Nuclide 39 / 1657 : 20044.82c -- calcium 44 (Ca-44) + + Pointers : 204182 20523 + Primary type : Transport + Nuclide ZAI : 200440 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ca44.ACE + Atomic weight (AW) : 43.95548 + Atomic weight ratio (AWR) : 43.57788 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+02 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 35 reaction channels + - 48 special reactions + - 12 transmutation reactions + - 9 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 35 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 5 Q = 0.00000E+00 MeV Emin = 4.99742E-01 MeV frac = 1.00000E+00 Product nuclide = self : anything + 3 MT = 16 Q = -1.11320E+01 MeV Emin = 1.13875E+01 MeV frac = 1.00000E+00 Product nuclide = 20043.82c : (n,2n) + 4 MT = 17 Q = -1.90650E+01 MeV Emin = 1.95025E+01 MeV frac = 1.00000E+00 Product nuclide = 20042.82c : (n,3n) + 5 MT = 22 Q = -8.85411E+00 MeV Emin = 9.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 18040.82c : (n,nalpha) + 6 MT = 28 Q = -1.21650E+01 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 190430 : (n,np) + 7 MT = 51 Q = -1.15705E+00 MeV Emin = 1.14180E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 8 MT = 52 Q = -1.88351E+00 MeV Emin = 1.90000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 9 MT = 53 Q = -2.28314E+00 MeV Emin = 2.33553E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 10 MT = 54 Q = -2.65650E+00 MeV Emin = 2.71746E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 11 MT = 55 Q = -3.04433E+00 MeV Emin = 3.11419E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 12 MT = 56 Q = -3.28500E+00 MeV Emin = 3.36038E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 13 MT = 57 Q = -3.30130E+00 MeV Emin = 3.37706E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 14 MT = 58 Q = -3.30786E+00 MeV Emin = 3.38377E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 15 MT = 59 Q = -3.35720E+00 MeV Emin = 3.43424E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 16 MT = 60 Q = -3.58040E+00 MeV Emin = 3.66256E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 17 MT = 61 Q = -3.66153E+00 MeV Emin = 3.74555E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 18 MT = 62 Q = -3.67607E+00 MeV Emin = 3.76043E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 19 MT = 63 Q = -3.71180E+00 MeV Emin = 3.79698E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 20 MT = 64 Q = -3.77620E+00 MeV Emin = 3.86286E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 21 MT = 65 Q = -3.86500E+00 MeV Emin = 3.95369E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 22 MT = 66 Q = -3.91355E+00 MeV Emin = 4.00336E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 23 MT = 67 Q = -3.92260E+00 MeV Emin = 4.01262E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 24 MT = 68 Q = -4.01140E+00 MeV Emin = 4.10345E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 25 MT = 69 Q = -4.09200E+00 MeV Emin = 4.18590E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 26 MT = 70 Q = -4.16900E+00 MeV Emin = 4.26467E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 27 MT = 91 Q = -4.16900E+00 MeV Emin = 4.26467E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 28 MT = 102 Q = 7.41477E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 200450 : (n,gamma) + 29 MT = 103 Q = -4.87652E+00 MeV Emin = 5.20000E+00 MeV frac = 1.00000E+00 Product nuclide = 190440 : (n,p) + 30 MT = 104 Q = -9.94044E+00 MeV Emin = 1.01686E+01 MeV frac = 1.00000E+00 Product nuclide = 190430 : (n,d) + 31 MT = 105 Q = -1.33262E+01 MeV Emin = 1.36320E+01 MeV frac = 1.00000E+00 Product nuclide = 190420 : (n,t) + 32 MT = 106 Q = -1.39069E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 180420 : (n,He-3) + 33 MT = 107 Q = -2.75541E+00 MeV Emin = 3.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 180410 : (n,alpha) + 34 MT = 108 Q = -1.13514E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 160370 : (n,2alpha) + 35 MT = 111 Q = -1.59982E+01 MeV Emin = 1.70000E+01 MeV frac = 1.00000E+00 Product nuclide = 180430 : (n,2p) + + 9 additional transport branches: + + 1 MT = 22 Q = -8.85411E+00 MeV Emin = 9.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.21650E+01 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -4.87652E+00 MeV Emin = 5.20000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -9.94044E+00 MeV Emin = 1.01686E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -1.33262E+01 MeV Emin = 1.36320E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 106 Q = -1.39069E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 7 MT = 107 Q = -2.75541E+00 MeV Emin = 3.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 8 MT = 108 Q = -1.13514E+01 MeV Emin = 1.50000E+01 MeV frac = 2.00000E+00 Product nuclide = 2004.82c : (n,2alpha) + 9 MT = 111 Q = -1.59982E+01 MeV Emin = 1.70000E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 48 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 5.20000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.01686E+01 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.36320E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.50000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 3.60000E+00 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 4.25000E-04 MeV : damage-energy production + 7 MT = 600 Q = -4.87652E+00 MeV Emin = 5.20000E+00 MeV : (n,p) to ground state + 8 MT = 601 Q = -5.05912E+00 MeV Emin = 5.40000E+00 MeV : (n,p1) + 9 MT = 602 Q = -5.25942E+00 MeV Emin = 5.60000E+00 MeV : (n,p2) + 10 MT = 603 Q = -5.39652E+00 MeV Emin = 5.80000E+00 MeV : (n,p3) + 11 MT = 604 Q = -5.68812E+00 MeV Emin = 5.81865E+00 MeV : (n,p4) + 12 MT = 605 Q = -5.84532E+00 MeV Emin = 6.00000E+00 MeV : (n,p5) + 13 MT = 606 Q = -5.88992E+00 MeV Emin = 6.20000E+00 MeV : (n,p6) + 14 MT = 607 Q = -5.92782E+00 MeV Emin = 6.20000E+00 MeV : (n,p7) + 15 MT = 608 Q = -5.95322E+00 MeV Emin = 6.20000E+00 MeV : (n,p8) + 16 MT = 609 Q = -6.11732E+00 MeV Emin = 6.25770E+00 MeV : (n,p9) + 17 MT = 610 Q = -6.24422E+00 MeV Emin = 6.40000E+00 MeV : (n,p10) + 18 MT = 649 Q = -6.24422E+00 MeV Emin = 6.60000E+00 MeV : (n,p) to continuum + 19 MT = 650 Q = -9.94044E+00 MeV Emin = 1.01686E+01 MeV : (n,d) to ground state + 20 MT = 651 Q = -1.05016E+01 MeV Emin = 1.07426E+01 MeV : (n,d1) + 21 MT = 652 Q = -1.06785E+01 MeV Emin = 1.10000E+01 MeV : (n,d2) + 22 MT = 653 Q = -1.09154E+01 MeV Emin = 1.11659E+01 MeV : (n,d3) + 23 MT = 654 Q = -1.10507E+01 MeV Emin = 1.15000E+01 MeV : (n,d4) + 24 MT = 655 Q = -1.11473E+01 MeV Emin = 1.15000E+01 MeV : (n,d5) + 25 MT = 699 Q = -1.11473E+01 MeV Emin = 1.15000E+01 MeV : (n,d) to continuum + 26 MT = 700 Q = -1.33262E+01 MeV Emin = 1.36320E+01 MeV : (n,t) to ground state + 27 MT = 701 Q = -1.34331E+01 MeV Emin = 1.40000E+01 MeV : (n,t1) + 28 MT = 702 Q = -1.35845E+01 MeV Emin = 1.40000E+01 MeV : (n,t2) + 29 MT = 703 Q = -1.39650E+01 MeV Emin = 1.45000E+01 MeV : (n,t3) + 30 MT = 704 Q = -1.40082E+01 MeV Emin = 1.45000E+01 MeV : (n,t4) + 31 MT = 705 Q = -1.40253E+01 MeV Emin = 1.45000E+01 MeV : (n,t5) + 32 MT = 749 Q = -1.40253E+01 MeV Emin = 1.45000E+01 MeV : (n,t) to continuum + 33 MT = 750 Q = -1.39069E+01 MeV Emin = 1.50000E+01 MeV : (n,He-3) to ground state + 34 MT = 751 Q = -1.51151E+01 MeV Emin = 1.54620E+01 MeV : (n,He-3_1) + 35 MT = 752 Q = -1.63219E+01 MeV Emin = 1.70000E+01 MeV : (n,He-3_2) + 36 MT = 800 Q = -2.75541E+00 MeV Emin = 3.60000E+00 MeV : (n,alpha) to ground state + 37 MT = 801 Q = -2.92271E+00 MeV Emin = 3.80000E+00 MeV : (n,a1) + 38 MT = 802 Q = -3.27141E+00 MeV Emin = 4.00000E+00 MeV : (n,a2) + 39 MT = 803 Q = -3.79011E+00 MeV Emin = 4.60000E+00 MeV : (n,a3) + 40 MT = 804 Q = -4.10942E+00 MeV Emin = 5.00000E+00 MeV : (n,a4) + 41 MT = 805 Q = -4.39042E+00 MeV Emin = 5.20000E+00 MeV : (n,a5) + 42 MT = 806 Q = -4.62441E+00 MeV Emin = 5.40000E+00 MeV : (n,a6) + 43 MT = 807 Q = -4.74042E+00 MeV Emin = 5.60000E+00 MeV : (n,a7) + 44 MT = 808 Q = -5.07642E+00 MeV Emin = 6.00000E+00 MeV : (n,a8) + 45 MT = 809 Q = -5.15372E+00 MeV Emin = 6.00000E+00 MeV : (n,a9) + 46 MT = 810 Q = -5.32442E+00 MeV Emin = 6.20000E+00 MeV : (n,a10) + 47 MT = 849 Q = -5.32442E+00 MeV Emin = 7.00000E+00 MeV : (n,alpha) to continuum + 48 MT = 4 Q = 0.00000E+00 MeV Emin = 1.14180E+00 MeV : total inelastic scattering + + Nuclide 40 / 1657 : 21045.82c -- scandium 45 (Sc-45) + + Pointers : 214163 32437 + Primary type : Transport + Nuclide ZAI : 210450 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Sc45.ACE + Atomic weight (AW) : 44.95591 + Atomic weight ratio (AWR) : 44.56972 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+02 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 39 reaction channels + - 52 special reactions + - 16 transmutation reactions + - 17 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 39 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 5 Q = 0.00000E+00 MeV Emin = 9.98750E-02 MeV frac = 1.00000E+00 Product nuclide = self : anything + 3 MT = 16 Q = -1.13248E+01 MeV Emin = 1.15789E+01 MeV frac = 1.00000E+00 Product nuclide = 210440 : (n,2n) + 4 MT = 22 Q = -7.93538E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 19041.82c : (n,nalpha) + 5 MT = 28 Q = -6.88922E+00 MeV Emin = 7.20000E+00 MeV frac = 1.00000E+00 Product nuclide = 20044.82c : (n,np) + 6 MT = 32 Q = -1.57966E+01 MeV Emin = 1.61510E+01 MeV frac = 1.00000E+00 Product nuclide = 20043.82c : (n,nd) + 7 MT = 33 Q = -1.74724E+01 MeV Emin = 1.80000E+01 MeV frac = 1.00000E+00 Product nuclide = 20042.82c : (n,nt) + 8 MT = 41 Q = -1.80212E+01 MeV Emin = 1.84256E+01 MeV frac = 1.00000E+00 Product nuclide = 20043.82c : (n,2np) + 9 MT = 51 Q = -1.24000E-02 MeV Emin = 1.26259E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 10 MT = 52 Q = -3.76500E-01 MeV Emin = 3.72474E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 11 MT = 53 Q = -5.43060E-01 MeV Emin = 5.41325E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 12 MT = 54 Q = -7.20120E-01 MeV Emin = 7.18100E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 13 MT = 55 Q = -9.39240E-01 MeV Emin = 9.30050E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 14 MT = 56 Q = -9.74380E-01 MeV Emin = 9.78278E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 15 MT = 57 Q = -1.06760E+00 MeV Emin = 1.09100E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 16 MT = 58 Q = -1.23670E+00 MeV Emin = 1.23826E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 17 MT = 59 Q = -1.30318E+00 MeV Emin = 1.33200E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 18 MT = 60 Q = -1.40887E+00 MeV Emin = 1.44000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 19 MT = 61 Q = -1.43348E+00 MeV Emin = 1.45601E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 20 MT = 62 Q = -1.47250E+00 MeV Emin = 1.50234E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 21 MT = 63 Q = -1.55620E+00 MeV Emin = 1.57987E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 22 MT = 64 Q = -1.66200E+00 MeV Emin = 1.68353E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 23 MT = 65 Q = -1.71600E+00 MeV Emin = 1.73725E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 24 MT = 66 Q = -1.80000E+00 MeV Emin = 1.83000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 25 MT = 67 Q = -1.90070E+00 MeV Emin = 1.93658E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 26 MT = 68 Q = -1.93060E+00 MeV Emin = 1.96914E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 27 MT = 69 Q = -1.93550E+00 MeV Emin = 1.97643E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 28 MT = 70 Q = -1.93550E+00 MeV Emin = 1.97643E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 29 MT = 91 Q = -1.93550E+00 MeV Emin = 1.97643E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 30 MT = 102 Q = 8.76062E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 210460 : (n,gamma) + 31 MT = 103 Q = 5.25545E-01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 200450 : (n,p) + 32 MT = 104 Q = -4.66465E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 20044.82c : (n,d) + 33 MT = 105 Q = -9.53937E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 20043.82c : (n,t) + 34 MT = 106 Q = -1.13362E+01 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 190430 : (n,He-3) + 35 MT = 107 Q = -4.01608E-01 MeV Emin = 1.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 190420 : (n,alpha) + 36 MT = 108 Q = -8.04986E+00 MeV Emin = 1.15000E+01 MeV frac = 1.00000E+00 Product nuclide = 170380 : (n,2alpha) + 37 MT = 111 Q = -1.17657E+01 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 190440 : (n,2p) + 38 MT = 112 Q = -9.64464E+00 MeV Emin = 1.15000E+01 MeV frac = 1.00000E+00 Product nuclide = 180410 : (n,palpha) + 39 MT = 117 Q = -1.35188E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 18040.82c : (n,dalpha) + + 17 additional transport branches: + + 1 MT = 22 Q = -7.93538E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -6.88922E+00 MeV Emin = 7.20000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.57966E+01 MeV Emin = 1.61510E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.74724E+01 MeV Emin = 1.80000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 41 Q = -1.80212E+01 MeV Emin = 1.84256E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,2np) + 6 MT = 102 Q = 8.76062E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 210461 : (n,gamma) + 7 MT = 103 Q = 5.25545E-01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 8 MT = 104 Q = -4.66465E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 9 MT = 105 Q = -9.53937E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 10 MT = 106 Q = -1.13362E+01 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 11 MT = 107 Q = -4.01608E-01 MeV Emin = 1.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 12 MT = 108 Q = -8.04986E+00 MeV Emin = 1.15000E+01 MeV frac = 2.00000E+00 Product nuclide = 2004.82c : (n,2alpha) + 13 MT = 111 Q = -1.17657E+01 MeV Emin = 1.25000E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + 14 MT = 112 Q = -9.64464E+00 MeV Emin = 1.15000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,palpha) + 15 MT = 112 Q = -9.64464E+00 MeV Emin = 1.15000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,palpha) + 16 MT = 117 Q = -1.35188E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,dalpha) + 17 MT = 117 Q = -1.35188E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,dalpha) + + 52 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.00000E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.25000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.60000E+00 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 600 Q = 5.25545E-01 MeV Emin = 1.00000E-11 MeV : (n,p) to ground state + 8 MT = 601 Q = 3.51279E-01 MeV Emin = 1.00000E-11 MeV : (n,p1) + 9 MT = 602 Q = -9.09165E-01 MeV Emin = 1.17289E+00 MeV : (n,p2) + 10 MT = 603 Q = -1.02882E+00 MeV Emin = 1.17289E+00 MeV : (n,p3) + 11 MT = 604 Q = -1.03245E+00 MeV Emin = 1.17289E+00 MeV : (n,p4) + 12 MT = 605 Q = -1.05845E+00 MeV Emin = 1.20000E+00 MeV : (n,p5) + 13 MT = 606 Q = -1.35436E+00 MeV Emin = 1.59556E+00 MeV : (n,p6) + 14 MT = 607 Q = -1.35885E+00 MeV Emin = 1.59556E+00 MeV : (n,p7) + 15 MT = 608 Q = -1.37432E+00 MeV Emin = 1.59556E+00 MeV : (n,p8) + 16 MT = 609 Q = -1.41464E+00 MeV Emin = 1.59556E+00 MeV : (n,p9) + 17 MT = 610 Q = -1.44745E+00 MeV Emin = 1.59556E+00 MeV : (n,p10) + 18 MT = 649 Q = -1.44745E+00 MeV Emin = 1.78578E+00 MeV : (n,p) to continuum + 19 MT = 650 Q = -4.66465E+00 MeV Emin = 5.00000E+00 MeV : (n,d) to ground state + 20 MT = 651 Q = -5.82170E+00 MeV Emin = 5.95232E+00 MeV : (n,d1) + 21 MT = 652 Q = -6.54816E+00 MeV Emin = 6.69508E+00 MeV : (n,d2) + 22 MT = 653 Q = -6.94779E+00 MeV Emin = 7.20000E+00 MeV : (n,d3) + 23 MT = 654 Q = -7.32115E+00 MeV Emin = 7.60000E+00 MeV : (n,d4) + 24 MT = 655 Q = -7.70898E+00 MeV Emin = 7.88195E+00 MeV : (n,d5) + 25 MT = 699 Q = -7.70898E+00 MeV Emin = 8.00000E+00 MeV : (n,d) to continuum + 26 MT = 700 Q = -9.53937E+00 MeV Emin = 1.00000E+01 MeV : (n,t) to ground state + 27 MT = 701 Q = -9.91213E+00 MeV Emin = 1.01345E+01 MeV : (n,t1) + 28 MT = 702 Q = -1.01328E+01 MeV Emin = 1.05000E+01 MeV : (n,t2) + 29 MT = 703 Q = -1.05296E+01 MeV Emin = 1.07659E+01 MeV : (n,t3) + 30 MT = 704 Q = -1.09338E+01 MeV Emin = 1.11792E+01 MeV : (n,t4) + 31 MT = 705 Q = -1.12172E+01 MeV Emin = 1.15000E+01 MeV : (n,t5) + 32 MT = 749 Q = -1.12172E+01 MeV Emin = 1.20000E+01 MeV : (n,t) to continuum + 33 MT = 750 Q = -1.13362E+01 MeV Emin = 1.25000E+01 MeV : (n,He-3) to ground state + 34 MT = 751 Q = -1.18974E+01 MeV Emin = 1.30000E+01 MeV : (n,He-3_1) + 35 MT = 752 Q = -1.20743E+01 MeV Emin = 1.30000E+01 MeV : (n,He-3_2) + 36 MT = 753 Q = -1.23112E+01 MeV Emin = 1.35000E+01 MeV : (n,He-3_3) + 37 MT = 754 Q = -1.24465E+01 MeV Emin = 1.35000E+01 MeV : (n,He-3_4) + 38 MT = 755 Q = -1.25431E+01 MeV Emin = 1.35000E+01 MeV : (n,He-3_5) + 39 MT = 799 Q = -1.25431E+01 MeV Emin = 1.40000E+01 MeV : (n,He-3) to continuum + 40 MT = 800 Q = -4.01608E-01 MeV Emin = 1.60000E+00 MeV : (n,alpha) to ground state + 41 MT = 801 Q = -5.08436E-01 MeV Emin = 1.64950E+00 MeV : (n,a1) + 42 MT = 802 Q = -6.59869E-01 MeV Emin = 1.81000E+00 MeV : (n,a2) + 43 MT = 803 Q = -1.04033E+00 MeV Emin = 2.00000E+00 MeV : (n,a3) + 44 MT = 804 Q = -1.08355E+00 MeV Emin = 2.00000E+00 MeV : (n,a4) + 45 MT = 805 Q = -1.10069E+00 MeV Emin = 2.00000E+00 MeV : (n,a5) + 46 MT = 806 Q = -1.18548E+00 MeV Emin = 2.00000E+00 MeV : (n,a6) + 47 MT = 807 Q = -1.24355E+00 MeV Emin = 2.00000E+00 MeV : (n,a7) + 48 MT = 808 Q = -1.51236E+00 MeV Emin = 2.40000E+00 MeV : (n,a8) + 49 MT = 809 Q = -1.54520E+00 MeV Emin = 2.40000E+00 MeV : (n,a9) + 50 MT = 810 Q = -1.59951E+00 MeV Emin = 2.40000E+00 MeV : (n,a10) + 51 MT = 849 Q = -1.59951E+00 MeV Emin = 2.80000E+00 MeV : (n,alpha) to continuum + 52 MT = 4 Q = 0.00000E+00 MeV Emin = 1.26259E-02 MeV : total inelastic scattering + + Nuclide 41 / 1657 : 22046.82c -- titanium 46 (Ti-46) + + Pointers : 228374 35289 + Primary type : Transport + Nuclide ZAI : 220460 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ti46.ACE + Atomic weight (AW) : 45.95276 + Atomic weight ratio (AWR) : 45.55800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 32 reaction channels + - 52 special reactions + - 10 transmutation reactions + - 8 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 32 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.31897E+01 MeV Emin = 1.34793E+01 MeV frac = 1.00000E+00 Product nuclide = 220450 : (n,2n) + 3 MT = 22 Q = -8.00348E+00 MeV Emin = 8.17920E+00 MeV frac = 1.00000E+00 Product nuclide = 20042.82c : (n,nalpha) + 4 MT = 28 Q = -1.03450E+01 MeV Emin = 1.05721E+01 MeV frac = 1.00000E+00 Product nuclide = 21045.82c : (n,np) + 5 MT = 51 Q = -8.89290E-01 MeV Emin = 9.07910E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -2.00990E+00 MeV Emin = 2.05402E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -2.61100E+00 MeV Emin = 2.66831E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -2.96180E+00 MeV Emin = 3.02681E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -3.05860E+00 MeV Emin = 3.12574E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -3.16818E+00 MeV Emin = 3.23772E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -3.21300E+00 MeV Emin = 3.28353E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -3.23570E+00 MeV Emin = 3.30673E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -3.29900E+00 MeV Emin = 3.37141E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -3.33800E+00 MeV Emin = 3.41127E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -3.44120E+00 MeV Emin = 3.51674E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -3.56940E+00 MeV Emin = 3.64775E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 63 Q = -3.57170E+00 MeV Emin = 3.65010E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 18 MT = 64 Q = -3.58200E+00 MeV Emin = 3.66063E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 19 MT = 65 Q = -3.60800E+00 MeV Emin = 3.68720E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 20 MT = 66 Q = -3.67700E+00 MeV Emin = 3.75771E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 21 MT = 67 Q = -3.69600E+00 MeV Emin = 3.77713E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 22 MT = 68 Q = -3.72390E+00 MeV Emin = 3.80564E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 23 MT = 69 Q = -3.73100E+00 MeV Emin = 3.81290E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 24 MT = 70 Q = -3.73790E+00 MeV Emin = 3.81995E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 25 MT = 91 Q = -3.73790E+00 MeV Emin = 3.81995E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 26 MT = 102 Q = 8.51370E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 22047.82c : (n,gamma) + 27 MT = 103 Q = -1.58500E+00 MeV Emin = 1.79700E+00 MeV frac = 1.00000E+00 Product nuclide = 210460 : (n,p) + 28 MT = 104 Q = -8.12040E+00 MeV Emin = 8.29864E+00 MeV frac = 1.00000E+00 Product nuclide = 21045.82c : (n,d) + 29 MT = 105 Q = -1.31890E+01 MeV Emin = 1.34785E+01 MeV frac = 1.00000E+00 Product nuclide = 210440 : (n,t) + 30 MT = 106 Q = -9.51780E+00 MeV Emin = 9.72672E+00 MeV frac = 1.00000E+00 Product nuclide = 20044.82c : (n,He-3) + 31 MT = 107 Q = -7.07340E-02 MeV Emin = 7.22009E-02 MeV frac = 1.00000E+00 Product nuclide = 20043.82c : (n,alpha) + 32 MT = 111 Q = -9.81940E+00 MeV Emin = 1.00350E+01 MeV frac = 1.00000E+00 Product nuclide = 200450 : (n,2p) + + 8 additional transport branches: + + 1 MT = 22 Q = -8.00348E+00 MeV Emin = 8.17920E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.03450E+01 MeV Emin = 1.05721E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -1.58500E+00 MeV Emin = 1.79700E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -8.12040E+00 MeV Emin = 8.29864E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -1.31890E+01 MeV Emin = 1.34785E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 106 Q = -9.51780E+00 MeV Emin = 9.72672E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 7 MT = 107 Q = -7.07340E-02 MeV Emin = 7.22009E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 8 MT = 111 Q = -9.81940E+00 MeV Emin = 1.00350E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 52 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.79700E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.29864E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.34785E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 9.72672E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 7.22009E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 4.09510E-04 MeV : damage-energy production + 7 MT = 600 Q = -1.58440E+00 MeV Emin = 1.79700E+00 MeV : (n,p) to ground state + 8 MT = 601 Q = -1.63640E+00 MeV Emin = 1.80000E+00 MeV : (n,p1) + 9 MT = 602 Q = -1.72690E+00 MeV Emin = 1.99900E+00 MeV : (n,p2) + 10 MT = 603 Q = -1.81210E+00 MeV Emin = 1.99900E+00 MeV : (n,p3) + 11 MT = 604 Q = -1.86510E+00 MeV Emin = 2.20000E+00 MeV : (n,p4) + 12 MT = 605 Q = -1.87390E+00 MeV Emin = 2.20000E+00 MeV : (n,p5) + 13 MT = 606 Q = -2.02850E+00 MeV Emin = 2.20000E+00 MeV : (n,p6) + 14 MT = 607 Q = -2.16910E+00 MeV Emin = 2.40000E+00 MeV : (n,p7) + 15 MT = 608 Q = -2.21180E+00 MeV Emin = 2.40000E+00 MeV : (n,p8) + 16 MT = 609 Q = -2.35840E+00 MeV Emin = 2.60000E+00 MeV : (n,p9) + 17 MT = 610 Q = -2.41940E+00 MeV Emin = 2.60000E+00 MeV : (n,p10) + 18 MT = 649 Q = -2.41940E+00 MeV Emin = 2.47260E+00 MeV : (n,p) to continuum + 19 MT = 650 Q = -8.12040E+00 MeV Emin = 8.29864E+00 MeV : (n,d) to ground state + 20 MT = 651 Q = -8.13280E+00 MeV Emin = 8.31132E+00 MeV : (n,d1) + 21 MT = 652 Q = -8.49690E+00 MeV Emin = 8.68341E+00 MeV : (n,d2) + 22 MT = 653 Q = -8.66350E+00 MeV Emin = 8.85366E+00 MeV : (n,d3) + 23 MT = 654 Q = -8.84050E+00 MeV Emin = 9.03460E+00 MeV : (n,d4) + 24 MT = 655 Q = -9.05960E+00 MeV Emin = 9.25850E+00 MeV : (n,d5) + 25 MT = 699 Q = -9.05960E+00 MeV Emin = 9.25850E+00 MeV : (n,d) to continuum + 26 MT = 700 Q = -1.31880E+01 MeV Emin = 1.34780E+01 MeV : (n,t) to ground state + 27 MT = 701 Q = -1.32560E+01 MeV Emin = 1.35470E+01 MeV : (n,t1) + 28 MT = 702 Q = -1.33340E+01 MeV Emin = 1.37490E+01 MeV : (n,t2) + 29 MT = 703 Q = -1.34230E+01 MeV Emin = 1.37490E+01 MeV : (n,t3) + 30 MT = 704 Q = -1.34590E+01 MeV Emin = 1.37550E+01 MeV : (n,t4) + 31 MT = 705 Q = -1.35380E+01 MeV Emin = 1.38352E+01 MeV : (n,t5) + 32 MT = 749 Q = -1.35380E+01 MeV Emin = 1.38352E+01 MeV : (n,t) to continuum + 33 MT = 750 Q = -9.51610E+00 MeV Emin = 9.72500E+00 MeV : (n,He-3) to ground state + 34 MT = 751 Q = -1.06730E+01 MeV Emin = 1.09080E+01 MeV : (n,He-3_1) + 35 MT = 752 Q = -1.14000E+01 MeV Emin = 1.16502E+01 MeV : (n,He-3_2) + 36 MT = 753 Q = -1.17990E+01 MeV Emin = 1.20580E+01 MeV : (n,He-3_3) + 37 MT = 754 Q = -1.21730E+01 MeV Emin = 1.24402E+01 MeV : (n,He-3_4) + 38 MT = 755 Q = -1.25610E+01 MeV Emin = 1.28367E+01 MeV : (n,He-3_5) + 39 MT = 799 Q = -1.25610E+01 MeV Emin = 1.28367E+01 MeV : (n,He-3) to continuum + 40 MT = 800 Q = -7.04850E-02 MeV Emin = 7.19549E-02 MeV : (n,alpha) to ground state + 41 MT = 801 Q = -4.43250E-01 MeV Emin = 4.50000E-01 MeV : (n,a1) + 42 MT = 802 Q = -6.63880E-01 MeV Emin = 6.77800E-01 MeV : (n,a2) + 43 MT = 803 Q = -1.06070E+00 MeV Emin = 1.08350E+00 MeV : (n,a3) + 44 MT = 804 Q = -1.46500E+00 MeV Emin = 1.49308E+00 MeV : (n,a4) + 45 MT = 805 Q = -1.74830E+00 MeV Emin = 1.78450E+00 MeV : (n,a5) + 46 MT = 806 Q = -1.97230E+00 MeV Emin = 2.01560E+00 MeV : (n,a6) + 47 MT = 807 Q = -2.00180E+00 MeV Emin = 2.04574E+00 MeV : (n,a7) + 48 MT = 808 Q = -2.02790E+00 MeV Emin = 2.07241E+00 MeV : (n,a8) + 49 MT = 809 Q = -2.11670E+00 MeV Emin = 2.16320E+00 MeV : (n,a9) + 50 MT = 810 Q = -2.13780E+00 MeV Emin = 2.18473E+00 MeV : (n,a10) + 51 MT = 849 Q = -2.13780E+00 MeV Emin = 2.18473E+00 MeV : (n,alpha) to continuum + 52 MT = 4 Q = 0.00000E+00 MeV Emin = 9.07910E-01 MeV : total inelastic scattering + + Nuclide 42 / 1657 : 22047.82c -- titanium 47 (Ti-47) + + Pointers : 235201 35335 + Primary type : Transport + Nuclide ZAI : 220470 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ti47.ACE + Atomic weight (AW) : 46.95134 + Atomic weight ratio (AWR) : 46.54800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 32 reaction channels + - 52 special reactions + - 10 transmutation reactions + - 8 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 32 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.87770E+00 MeV Emin = 9.06842E+00 MeV frac = 1.00000E+00 Product nuclide = 22046.82c : (n,2n) + 3 MT = 22 Q = -8.94820E+00 MeV Emin = 9.14044E+00 MeV frac = 1.00000E+00 Product nuclide = 20043.82c : (n,nalpha) + 4 MT = 28 Q = -1.04620E+01 MeV Emin = 1.06870E+01 MeV frac = 1.00000E+00 Product nuclide = 210460 : (n,np) + 5 MT = 51 Q = -1.59380E-01 MeV Emin = 1.62320E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -1.25060E+00 MeV Emin = 1.27632E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -1.25210E+00 MeV Emin = 1.27844E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -1.44425E+00 MeV Emin = 1.47300E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -1.54980E+00 MeV Emin = 1.58154E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -1.67000E+00 MeV Emin = 1.70200E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -1.79390E+00 MeV Emin = 1.82700E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -1.82500E+00 MeV Emin = 1.86000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -2.16320E+00 MeV Emin = 2.20967E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -2.16670E+00 MeV Emin = 2.21325E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -2.25950E+00 MeV Emin = 2.30804E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -2.29710E+00 MeV Emin = 2.34645E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 63 Q = -2.34400E+00 MeV Emin = 2.39436E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 18 MT = 64 Q = -2.36490E+00 MeV Emin = 2.41571E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 19 MT = 65 Q = -2.40620E+00 MeV Emin = 2.45789E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 20 MT = 66 Q = -2.41630E+00 MeV Emin = 2.46821E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 21 MT = 67 Q = -2.49940E+00 MeV Emin = 2.55310E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 22 MT = 68 Q = -2.52000E+00 MeV Emin = 2.57414E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 23 MT = 69 Q = -2.52580E+00 MeV Emin = 2.58006E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 24 MT = 70 Q = -2.54820E+00 MeV Emin = 2.60294E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 25 MT = 91 Q = -2.54820E+00 MeV Emin = 2.60294E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 26 MT = 102 Q = 1.16266E+01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 22048.82c : (n,gamma) + 27 MT = 103 Q = 1.82252E-01 MeV Emin = 6.59300E-01 MeV frac = 1.00000E+00 Product nuclide = 210470 : (n,p) + 28 MT = 104 Q = -8.23749E+00 MeV Emin = 8.41450E+00 MeV frac = 1.00000E+00 Product nuclide = 210460 : (n,d) + 29 MT = 105 Q = -1.07410E+01 MeV Emin = 1.09718E+01 MeV frac = 1.00000E+00 Product nuclide = 21045.82c : (n,t) + 30 MT = 106 Q = -1.09790E+01 MeV Emin = 1.12200E+01 MeV frac = 1.00000E+00 Product nuclide = 200450 : (n,He-3) + 31 MT = 107 Q = 2.18380E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 20044.82c : (n,alpha) + 32 MT = 111 Q = -8.30340E+00 MeV Emin = 8.48180E+00 MeV frac = 1.00000E+00 Product nuclide = 200460 : (n,2p) + + 8 additional transport branches: + + 1 MT = 22 Q = -8.94820E+00 MeV Emin = 9.14044E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.04620E+01 MeV Emin = 1.06870E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = 1.82252E-01 MeV Emin = 6.59300E-01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -8.23749E+00 MeV Emin = 8.41450E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -1.07410E+01 MeV Emin = 1.09718E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 106 Q = -1.09790E+01 MeV Emin = 1.12200E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 7 MT = 107 Q = 2.18380E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 8 MT = 111 Q = -8.30340E+00 MeV Emin = 8.48180E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 52 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 6.59300E-01 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.41450E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.09718E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.12200E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 600 Q = 1.82250E-01 MeV Emin = 6.59300E-01 MeV : (n,p) to ground state + 8 MT = 601 Q = -5.84580E-01 MeV Emin = 8.79822E-01 MeV : (n,p1) + 9 MT = 602 Q = -6.25640E-01 MeV Emin = 8.79881E-01 MeV : (n,p2) + 10 MT = 603 Q = -9.40750E-01 MeV Emin = 1.19969E+00 MeV : (n,p3) + 11 MT = 604 Q = -9.62750E-01 MeV Emin = 1.19969E+00 MeV : (n,p4) + 12 MT = 605 Q = -9.64740E-01 MeV Emin = 1.19984E+00 MeV : (n,p5) + 13 MT = 606 Q = -1.11490E+00 MeV Emin = 1.39900E+00 MeV : (n,p6) + 14 MT = 607 Q = -1.13380E+00 MeV Emin = 1.39900E+00 MeV : (n,p7) + 15 MT = 608 Q = -1.20910E+00 MeV Emin = 1.39900E+00 MeV : (n,p8) + 16 MT = 609 Q = -1.22220E+00 MeV Emin = 1.39900E+00 MeV : (n,p9) + 17 MT = 610 Q = -1.45670E+00 MeV Emin = 1.59900E+00 MeV : (n,p10) + 18 MT = 649 Q = -1.45670E+00 MeV Emin = 1.48750E+00 MeV : (n,p) to continuum + 19 MT = 650 Q = -8.23750E+00 MeV Emin = 8.41450E+00 MeV : (n,d) to ground state + 20 MT = 651 Q = -8.28950E+00 MeV Emin = 8.46760E+00 MeV : (n,d1) + 21 MT = 652 Q = -8.38000E+00 MeV Emin = 8.56010E+00 MeV : (n,d2) + 22 MT = 653 Q = -8.46530E+00 MeV Emin = 8.64716E+00 MeV : (n,d3) + 23 MT = 654 Q = -8.51820E+00 MeV Emin = 9.00000E+00 MeV : (n,d4) + 24 MT = 655 Q = -8.52700E+00 MeV Emin = 9.00000E+00 MeV : (n,d5) + 25 MT = 699 Q = -8.52700E+00 MeV Emin = 8.71020E+00 MeV : (n,d) to continuum + 26 MT = 700 Q = -1.07410E+01 MeV Emin = 1.10000E+01 MeV : (n,t) to ground state + 27 MT = 701 Q = -1.07530E+01 MeV Emin = 1.10000E+01 MeV : (n,t1) + 28 MT = 702 Q = -1.11170E+01 MeV Emin = 1.13560E+01 MeV : (n,t2) + 29 MT = 703 Q = -1.12840E+01 MeV Emin = 1.15264E+01 MeV : (n,t3) + 30 MT = 704 Q = -1.14610E+01 MeV Emin = 1.20000E+01 MeV : (n,t4) + 31 MT = 705 Q = -1.16800E+01 MeV Emin = 1.20000E+01 MeV : (n,t5) + 32 MT = 749 Q = -1.16800E+01 MeV Emin = 1.19310E+01 MeV : (n,t) to continuum + 33 MT = 750 Q = -1.09790E+01 MeV Emin = 1.12150E+01 MeV : (n,He-3) to ground state + 34 MT = 751 Q = -1.11530E+01 MeV Emin = 1.13930E+01 MeV : (n,He-3_1) + 35 MT = 752 Q = -1.24140E+01 MeV Emin = 1.26810E+01 MeV : (n,He-3_2) + 36 MT = 753 Q = -1.25340E+01 MeV Emin = 1.28033E+01 MeV : (n,He-3_3) + 37 MT = 754 Q = -1.25370E+01 MeV Emin = 1.28063E+01 MeV : (n,He-3_4) + 38 MT = 755 Q = -1.25630E+01 MeV Emin = 1.28330E+01 MeV : (n,He-3_5) + 39 MT = 799 Q = -1.25630E+01 MeV Emin = 1.28330E+01 MeV : (n,He-3) to continuum + 40 MT = 800 Q = 2.18377E+00 MeV Emin = 1.00000E-11 MeV : (n,alpha) to ground state + 41 MT = 801 Q = 1.02672E+00 MeV Emin = 1.00000E-11 MeV : (n,a1) + 42 MT = 802 Q = 3.00255E-01 MeV Emin = 1.02050E+00 MeV : (n,a2) + 43 MT = 803 Q = -9.93745E-02 MeV Emin = 1.38288E+00 MeV : (n,a3) + 44 MT = 804 Q = -4.72735E-01 MeV Emin = 1.79700E+00 MeV : (n,a4) + 45 MT = 805 Q = -8.60564E-01 MeV Emin = 2.00000E+00 MeV : (n,a5) + 46 MT = 806 Q = -1.10123E+00 MeV Emin = 2.00000E+00 MeV : (n,a6) + 47 MT = 807 Q = -1.11753E+00 MeV Emin = 2.00000E+00 MeV : (n,a7) + 48 MT = 808 Q = -1.12409E+00 MeV Emin = 2.00000E+00 MeV : (n,a8) + 49 MT = 809 Q = -1.17343E+00 MeV Emin = 2.00000E+00 MeV : (n,a9) + 50 MT = 810 Q = -1.39663E+00 MeV Emin = 2.40000E+00 MeV : (n,a10) + 51 MT = 849 Q = -1.39663E+00 MeV Emin = 1.42645E+00 MeV : (n,alpha) to continuum + 52 MT = 4 Q = 0.00000E+00 MeV Emin = 1.62320E-01 MeV : total inelastic scattering + + Nuclide 43 / 1657 : 22048.82c -- titanium 48 (Ti-48) + + Pointers : 242028 35381 + Primary type : Transport + Nuclide ZAI : 220480 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ti48.ACE + Atomic weight (AW) : 47.94795 + Atomic weight ratio (AWR) : 47.53605 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 32 reaction channels + - 52 special reactions + - 10 transmutation reactions + - 8 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 32 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.16270E+01 MeV Emin = 1.18716E+01 MeV frac = 1.00000E+00 Product nuclide = 22047.82c : (n,2n) + 3 MT = 22 Q = -9.44280E+00 MeV Emin = 9.64150E+00 MeV frac = 1.00000E+00 Product nuclide = 20044.82c : (n,nalpha) + 4 MT = 28 Q = -1.14440E+01 MeV Emin = 1.16850E+01 MeV frac = 1.00000E+00 Product nuclide = 210470 : (n,np) + 5 MT = 51 Q = -9.83520E-01 MeV Emin = 1.00200E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -2.29560E+00 MeV Emin = 2.34390E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -2.42100E+00 MeV Emin = 2.47200E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -2.46500E+00 MeV Emin = 2.51690E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -2.99720E+00 MeV Emin = 3.06025E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -3.06200E+00 MeV Emin = 3.12642E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -3.22390E+00 MeV Emin = 3.29172E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -3.23970E+00 MeV Emin = 3.30790E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -3.33320E+00 MeV Emin = 3.40332E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -3.35880E+00 MeV Emin = 3.42950E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -3.37080E+00 MeV Emin = 3.44180E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -3.50850E+00 MeV Emin = 3.58240E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 63 Q = -3.61680E+00 MeV Emin = 3.69290E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 18 MT = 64 Q = -3.63300E+00 MeV Emin = 3.70943E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 19 MT = 65 Q = -3.69950E+00 MeV Emin = 3.77733E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 20 MT = 66 Q = -3.71100E+00 MeV Emin = 3.78910E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 21 MT = 67 Q = -3.73850E+00 MeV Emin = 3.81720E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 22 MT = 68 Q = -3.78240E+00 MeV Emin = 3.86200E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 23 MT = 69 Q = -3.80280E+00 MeV Emin = 3.88280E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 24 MT = 70 Q = -3.85200E+00 MeV Emin = 3.93303E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 25 MT = 91 Q = -3.85200E+00 MeV Emin = 3.93303E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 26 MT = 102 Q = 8.14240E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 22049.82c : (n,gamma) + 27 MT = 103 Q = -3.21180E+00 MeV Emin = 3.27940E+00 MeV frac = 1.00000E+00 Product nuclide = 210480 : (n,p) + 28 MT = 104 Q = -9.21980E+00 MeV Emin = 9.41376E+00 MeV frac = 1.00000E+00 Product nuclide = 210470 : (n,d) + 29 MT = 105 Q = -1.36070E+01 MeV Emin = 1.38933E+01 MeV frac = 1.00000E+00 Product nuclide = 210460 : (n,t) + 30 MT = 106 Q = -1.22120E+01 MeV Emin = 1.24690E+01 MeV frac = 1.00000E+00 Product nuclide = 200460 : (n,He-3) + 31 MT = 107 Q = -2.02810E+00 MeV Emin = 2.07077E+00 MeV frac = 1.00000E+00 Product nuclide = 200450 : (n,alpha) + 32 MT = 111 Q = -1.26540E+01 MeV Emin = 1.29202E+01 MeV frac = 1.00000E+00 Product nuclide = 200470 : (n,2p) + + 8 additional transport branches: + + 1 MT = 22 Q = -9.44280E+00 MeV Emin = 9.64150E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.14440E+01 MeV Emin = 1.16850E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -3.21180E+00 MeV Emin = 3.27940E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -9.21980E+00 MeV Emin = 9.41376E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -1.36070E+01 MeV Emin = 1.38933E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 106 Q = -1.22120E+01 MeV Emin = 1.24690E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 7 MT = 107 Q = -2.02810E+00 MeV Emin = 2.07077E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 8 MT = 111 Q = -1.26540E+01 MeV Emin = 1.29202E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 52 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.27940E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 9.41376E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.38933E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.24690E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 2.07077E+00 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 4.32133E-04 MeV : damage-energy production + 7 MT = 600 Q = -3.21180E+00 MeV Emin = 3.40000E+00 MeV : (n,p) to ground state + 8 MT = 601 Q = -3.34280E+00 MeV Emin = 3.60000E+00 MeV : (n,p1) + 9 MT = 602 Q = -3.46420E+00 MeV Emin = 3.80000E+00 MeV : (n,p2) + 10 MT = 603 Q = -3.59980E+00 MeV Emin = 3.80000E+00 MeV : (n,p3) + 11 MT = 604 Q = -3.83450E+00 MeV Emin = 4.20000E+00 MeV : (n,p4) + 12 MT = 605 Q = -4.30780E+00 MeV Emin = 4.39850E+00 MeV : (n,p5) + 13 MT = 606 Q = -4.35440E+00 MeV Emin = 4.60000E+00 MeV : (n,p6) + 14 MT = 607 Q = -4.61350E+00 MeV Emin = 4.71060E+00 MeV : (n,p7) + 15 MT = 608 Q = -4.64380E+00 MeV Emin = 4.80000E+00 MeV : (n,p8) + 16 MT = 609 Q = -5.10290E+00 MeV Emin = 5.21030E+00 MeV : (n,p9) + 17 MT = 610 Q = -5.27590E+00 MeV Emin = 5.40000E+00 MeV : (n,p10) + 18 MT = 649 Q = -5.27590E+00 MeV Emin = 5.38690E+00 MeV : (n,p) to continuum + 19 MT = 650 Q = -9.21980E+00 MeV Emin = 9.50000E+00 MeV : (n,d) to ground state + 20 MT = 651 Q = -9.98660E+00 MeV Emin = 1.01970E+01 MeV : (n,d1) + 21 MT = 652 Q = -1.00280E+01 MeV Emin = 1.05000E+01 MeV : (n,d2) + 22 MT = 653 Q = -1.03430E+01 MeV Emin = 1.05606E+01 MeV : (n,d3) + 23 MT = 654 Q = -1.03650E+01 MeV Emin = 1.05831E+01 MeV : (n,d4) + 24 MT = 655 Q = -1.03670E+01 MeV Emin = 1.05851E+01 MeV : (n,d5) + 25 MT = 699 Q = -1.03670E+01 MeV Emin = 1.05851E+01 MeV : (n,d) to continuum + 26 MT = 700 Q = -1.36070E+01 MeV Emin = 1.40000E+01 MeV : (n,t) to ground state + 27 MT = 701 Q = -1.36590E+01 MeV Emin = 1.40000E+01 MeV : (n,t1) + 28 MT = 702 Q = -1.37490E+01 MeV Emin = 1.40390E+01 MeV : (n,t2) + 29 MT = 703 Q = -1.38350E+01 MeV Emin = 1.45000E+01 MeV : (n,t3) + 30 MT = 704 Q = -1.38880E+01 MeV Emin = 1.45000E+01 MeV : (n,t4) + 31 MT = 705 Q = -1.38960E+01 MeV Emin = 1.45000E+01 MeV : (n,t5) + 32 MT = 749 Q = -1.38960E+01 MeV Emin = 1.41890E+01 MeV : (n,t) to continuum + 33 MT = 750 Q = -1.22120E+01 MeV Emin = 1.35000E+01 MeV : (n,He-3) to ground state + 34 MT = 751 Q = -1.35580E+01 MeV Emin = 1.40000E+01 MeV : (n,He-3_1) + 35 MT = 752 Q = -1.46350E+01 MeV Emin = 1.50000E+01 MeV : (n,He-3_2) + 36 MT = 753 Q = -1.47870E+01 MeV Emin = 1.60000E+01 MeV : (n,He-3_3) + 37 MT = 754 Q = -1.51860E+01 MeV Emin = 1.60000E+01 MeV : (n,He-3_4) + 38 MT = 755 Q = -1.52350E+01 MeV Emin = 1.60000E+01 MeV : (n,He-3_5) + 39 MT = 799 Q = -1.52350E+01 MeV Emin = 1.55555E+01 MeV : (n,He-3) to continuum + 40 MT = 800 Q = -2.02810E+00 MeV Emin = 3.00000E+00 MeV : (n,alpha) to ground state + 41 MT = 801 Q = -2.20230E+00 MeV Emin = 3.20000E+00 MeV : (n,a1) + 42 MT = 802 Q = -3.46280E+00 MeV Emin = 4.00000E+00 MeV : (n,a2) + 43 MT = 803 Q = -3.58240E+00 MeV Emin = 4.60000E+00 MeV : (n,a3) + 44 MT = 804 Q = -3.58610E+00 MeV Emin = 4.60000E+00 MeV : (n,a4) + 45 MT = 805 Q = -3.61210E+00 MeV Emin = 4.60000E+00 MeV : (n,a5) + 46 MT = 806 Q = -3.90800E+00 MeV Emin = 5.00000E+00 MeV : (n,a6) + 47 MT = 807 Q = -3.91250E+00 MeV Emin = 5.00000E+00 MeV : (n,a7) + 48 MT = 808 Q = -3.92790E+00 MeV Emin = 5.00000E+00 MeV : (n,a8) + 49 MT = 809 Q = -3.96830E+00 MeV Emin = 5.00000E+00 MeV : (n,a9) + 50 MT = 810 Q = -4.00110E+00 MeV Emin = 5.00000E+00 MeV : (n,a10) + 51 MT = 849 Q = -4.00110E+00 MeV Emin = 4.08527E+00 MeV : (n,alpha) to continuum + 52 MT = 4 Q = 0.00000E+00 MeV Emin = 1.00200E+00 MeV : total inelastic scattering + + Nuclide 44 / 1657 : 22049.82c -- titanium 49 (Ti-49) + + Pointers : 248855 35427 + Primary type : Transport + Nuclide ZAI : 220490 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ti49.ACE + Atomic weight (AW) : 48.94788 + Atomic weight ratio (AWR) : 48.52739 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 32 reaction channels + - 50 special reactions + - 10 transmutation reactions + - 8 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 32 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.14240E+00 MeV Emin = 8.31020E+00 MeV frac = 1.00000E+00 Product nuclide = 22048.82c : (n,2n) + 3 MT = 22 Q = -1.01700E+01 MeV Emin = 1.03800E+01 MeV frac = 1.00000E+00 Product nuclide = 200450 : (n,nalpha) + 4 MT = 28 Q = -1.13540E+01 MeV Emin = 1.15880E+01 MeV frac = 1.00000E+00 Product nuclide = 210480 : (n,np) + 5 MT = 51 Q = -1.38180E+00 MeV Emin = 1.40900E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -1.54215E+00 MeV Emin = 1.57250E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -1.58597E+00 MeV Emin = 1.61721E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -1.61000E+00 MeV Emin = 1.64041E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -1.62293E+00 MeV Emin = 1.65210E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -1.72347E+00 MeV Emin = 1.75850E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -1.76201E+00 MeV Emin = 1.79700E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -2.26130E+00 MeV Emin = 2.30790E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -2.47140E+00 MeV Emin = 2.52233E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -2.50444E+00 MeV Emin = 2.55605E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -2.50550E+00 MeV Emin = 2.55713E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -2.51337E+00 MeV Emin = 2.56516E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 63 Q = -2.52010E+00 MeV Emin = 2.57203E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 18 MT = 64 Q = -2.66434E+00 MeV Emin = 2.71924E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 19 MT = 65 Q = -2.72060E+00 MeV Emin = 2.77666E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 20 MT = 66 Q = -2.72130E+00 MeV Emin = 2.77738E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 21 MT = 67 Q = -2.98050E+00 MeV Emin = 3.04192E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 22 MT = 68 Q = -3.03868E+00 MeV Emin = 3.10130E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 23 MT = 69 Q = -3.04250E+00 MeV Emin = 3.10520E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 24 MT = 70 Q = -3.17529E+00 MeV Emin = 3.24072E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 25 MT = 91 Q = -3.17530E+00 MeV Emin = 3.24073E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 26 MT = 102 Q = 1.09391E+01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 22050.82c : (n,gamma) + 27 MT = 103 Q = -1.22280E+00 MeV Emin = 1.49900E+00 MeV frac = 1.00000E+00 Product nuclide = 210490 : (n,p) + 28 MT = 104 Q = -9.12960E+00 MeV Emin = 9.31780E+00 MeV frac = 1.00000E+00 Product nuclide = 210480 : (n,d) + 29 MT = 105 Q = -1.11050E+01 MeV Emin = 1.13338E+01 MeV frac = 1.00000E+00 Product nuclide = 210470 : (n,t) + 30 MT = 106 Q = -1.30780E+01 MeV Emin = 1.33500E+01 MeV frac = 1.00000E+00 Product nuclide = 200470 : (n,He-3) + 31 MT = 107 Q = 2.23280E-01 MeV Emin = 1.07400E+00 MeV frac = 1.00000E+00 Product nuclide = 200460 : (n,alpha) + 32 MT = 111 Q = -1.08500E+01 MeV Emin = 1.10740E+01 MeV frac = 1.00000E+00 Product nuclide = 200480 : (n,2p) + + 8 additional transport branches: + + 1 MT = 22 Q = -1.01700E+01 MeV Emin = 1.03800E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.13540E+01 MeV Emin = 1.15880E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -1.22280E+00 MeV Emin = 1.49900E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -9.12960E+00 MeV Emin = 9.31780E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -1.11050E+01 MeV Emin = 1.13338E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 106 Q = -1.30780E+01 MeV Emin = 1.33500E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 7 MT = 107 Q = 2.23280E-01 MeV Emin = 1.07400E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 8 MT = 111 Q = -1.08500E+01 MeV Emin = 1.10740E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 50 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.49900E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 9.31780E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.13338E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.33500E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.07400E+00 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 4.54755E-04 MeV : damage-energy production + 7 MT = 600 Q = -1.22340E+00 MeV Emin = 1.49900E+00 MeV : (n,p) to ground state + 8 MT = 601 Q = -3.45150E+00 MeV Emin = 3.52263E+00 MeV : (n,p1) + 9 MT = 602 Q = -3.59470E+00 MeV Emin = 3.66880E+00 MeV : (n,p2) + 10 MT = 603 Q = -4.30790E+00 MeV Emin = 4.39670E+00 MeV : (n,p3) + 11 MT = 604 Q = -4.52340E+00 MeV Emin = 4.61662E+00 MeV : (n,p4) + 12 MT = 605 Q = -4.73960E+00 MeV Emin = 4.83730E+00 MeV : (n,p5) + 13 MT = 606 Q = -4.77340E+00 MeV Emin = 5.00000E+00 MeV : (n,p6) + 14 MT = 607 Q = -4.80440E+00 MeV Emin = 5.00000E+00 MeV : (n,p7) + 15 MT = 608 Q = -4.97840E+00 MeV Emin = 5.08100E+00 MeV : (n,p8) + 16 MT = 609 Q = -5.03180E+00 MeV Emin = 5.13550E+00 MeV : (n,p9) + 17 MT = 610 Q = -5.14440E+00 MeV Emin = 5.25041E+00 MeV : (n,p10) + 18 MT = 649 Q = -5.14440E+00 MeV Emin = 5.25041E+00 MeV : (n,p) to continuum + 19 MT = 650 Q = -9.12960E+00 MeV Emin = 9.31780E+00 MeV : (n,d) to ground state + 20 MT = 651 Q = -9.26060E+00 MeV Emin = 9.45144E+00 MeV : (n,d1) + 21 MT = 652 Q = -9.38200E+00 MeV Emin = 9.57534E+00 MeV : (n,d2) + 22 MT = 653 Q = -9.51760E+00 MeV Emin = 9.71380E+00 MeV : (n,d3) + 23 MT = 654 Q = -9.75230E+00 MeV Emin = 1.00000E+01 MeV : (n,d4) + 24 MT = 655 Q = -1.02260E+01 MeV Emin = 1.05000E+01 MeV : (n,d5) + 25 MT = 699 Q = -1.02260E+01 MeV Emin = 1.04367E+01 MeV : (n,d) to continuum + 26 MT = 700 Q = -1.11050E+01 MeV Emin = 1.15000E+01 MeV : (n,t) to ground state + 27 MT = 701 Q = -1.18720E+01 MeV Emin = 1.21167E+01 MeV : (n,t1) + 28 MT = 702 Q = -1.19130E+01 MeV Emin = 1.25000E+01 MeV : (n,t2) + 29 MT = 703 Q = -1.22280E+01 MeV Emin = 1.25000E+01 MeV : (n,t3) + 30 MT = 704 Q = -1.22500E+01 MeV Emin = 1.25024E+01 MeV : (n,t4) + 31 MT = 705 Q = -1.22520E+01 MeV Emin = 1.25045E+01 MeV : (n,t5) + 32 MT = 749 Q = -1.22520E+01 MeV Emin = 1.25045E+01 MeV : (n,t) to continuum + 33 MT = 750 Q = -1.30780E+01 MeV Emin = 1.40000E+01 MeV : (n,He-3) to ground state + 34 MT = 751 Q = -1.50920E+01 MeV Emin = 1.54030E+01 MeV : (n,He-3_1) + 35 MT = 752 Q = -1.56570E+01 MeV Emin = 1.60000E+01 MeV : (n,He-3_2) + 36 MT = 753 Q = -1.56780E+01 MeV Emin = 1.70000E+01 MeV : (n,He-3_3) + 37 MT = 799 Q = -1.56780E+01 MeV Emin = 1.60011E+01 MeV : (n,He-3) to continuum + 38 MT = 800 Q = 2.23281E-01 MeV Emin = 1.07400E+00 MeV : (n,alpha) to ground state + 39 MT = 801 Q = -1.12272E+00 MeV Emin = 2.00000E+00 MeV : (n,a1) + 40 MT = 802 Q = -2.19982E+00 MeV Emin = 3.00000E+00 MeV : (n,a2) + 41 MT = 803 Q = -2.35142E+00 MeV Emin = 3.20000E+00 MeV : (n,a3) + 42 MT = 804 Q = -2.75062E+00 MeV Emin = 3.60000E+00 MeV : (n,a4) + 43 MT = 805 Q = -2.79932E+00 MeV Emin = 3.80000E+00 MeV : (n,a5) + 44 MT = 806 Q = -3.39072E+00 MeV Emin = 4.20000E+00 MeV : (n,a6) + 45 MT = 807 Q = -3.41562E+00 MeV Emin = 4.40000E+00 MeV : (n,a7) + 46 MT = 808 Q = -3.63642E+00 MeV Emin = 4.60000E+00 MeV : (n,a8) + 47 MT = 809 Q = -3.72872E+00 MeV Emin = 4.80000E+00 MeV : (n,a9) + 48 MT = 810 Q = -3.76472E+00 MeV Emin = 4.80000E+00 MeV : (n,a10) + 49 MT = 849 Q = -3.76472E+00 MeV Emin = 3.84230E+00 MeV : (n,alpha) to continuum + 50 MT = 4 Q = 0.00000E+00 MeV Emin = 1.40900E+00 MeV : total inelastic scattering + + Nuclide 45 / 1657 : 22050.82c -- titanium 50 (Ti-50) + + Pointers : 255536 35473 + Primary type : Transport + Nuclide ZAI : 220500 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ti50.ACE + Atomic weight (AW) : 49.94480 + Atomic weight ratio (AWR) : 49.51575 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 31 reaction channels + - 47 special reactions + - 9 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 31 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.09390E+01 MeV Emin = 1.11600E+01 MeV frac = 1.00000E+00 Product nuclide = 22049.82c : (n,2n) + 3 MT = 22 Q = -1.07160E+01 MeV Emin = 1.09324E+01 MeV frac = 1.00000E+00 Product nuclide = 200460 : (n,nalpha) + 4 MT = 28 Q = -1.21630E+01 MeV Emin = 1.24086E+01 MeV frac = 1.00000E+00 Product nuclide = 210490 : (n,np) + 5 MT = 51 Q = -1.55380E+00 MeV Emin = 1.58480E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -2.67490E+00 MeV Emin = 2.72892E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -3.19870E+00 MeV Emin = 3.26330E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -3.86279E+00 MeV Emin = 3.94080E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -3.86820E+00 MeV Emin = 3.94632E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -3.97490E+00 MeV Emin = 4.05518E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -4.14700E+00 MeV Emin = 4.23075E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -4.14719E+00 MeV Emin = 4.23095E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -4.17197E+00 MeV Emin = 4.25623E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -4.17250E+00 MeV Emin = 4.25677E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -4.30985E+00 MeV Emin = 4.39689E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -4.40999E+00 MeV Emin = 4.49905E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 63 Q = -4.48671E+00 MeV Emin = 4.57732E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 18 MT = 64 Q = -4.53600E+00 MeV Emin = 4.62761E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 19 MT = 65 Q = -4.57600E+00 MeV Emin = 4.66842E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 20 MT = 66 Q = -4.78995E+00 MeV Emin = 4.88669E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 21 MT = 67 Q = -4.88068E+00 MeV Emin = 4.97925E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 22 MT = 68 Q = -4.92800E+00 MeV Emin = 5.02752E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 23 MT = 69 Q = -4.94000E+00 MeV Emin = 5.03977E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 24 MT = 70 Q = -5.12500E+00 MeV Emin = 5.22850E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 25 MT = 91 Q = -5.12500E+00 MeV Emin = 5.22850E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 26 MT = 102 Q = 6.37680E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 220510 : (n,gamma) + 27 MT = 103 Q = -6.10610E+00 MeV Emin = 6.22950E+00 MeV frac = 1.00000E+00 Product nuclide = 210500 : (n,p) + 28 MT = 104 Q = -9.93800E+00 MeV Emin = 1.01390E+01 MeV frac = 1.00000E+00 Product nuclide = 210490 : (n,d) + 29 MT = 105 Q = -1.38120E+01 MeV Emin = 1.49200E+01 MeV frac = 1.00000E+00 Product nuclide = 210480 : (n,t) + 30 MT = 106 Q = -1.40710E+01 MeV Emin = 1.43600E+01 MeV frac = 1.00000E+00 Product nuclide = 200480 : (n,He-3) + 31 MT = 107 Q = -3.44390E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 200470 : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -1.07160E+01 MeV Emin = 1.09324E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.21630E+01 MeV Emin = 1.24086E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -6.10610E+00 MeV Emin = 6.22950E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -9.93800E+00 MeV Emin = 1.01390E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -1.38120E+01 MeV Emin = 1.49200E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 106 Q = -1.40710E+01 MeV Emin = 1.43600E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 7 MT = 107 Q = -3.44390E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 47 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 6.22950E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.01390E+01 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.49200E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.43600E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 5.00000E+00 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 4.54755E-04 MeV : damage-energy production + 7 MT = 600 Q = -6.10600E+00 MeV Emin = 6.22931E+00 MeV : (n,p) to ground state + 8 MT = 601 Q = -6.36290E+00 MeV Emin = 6.49140E+00 MeV : (n,p1) + 9 MT = 602 Q = -6.43440E+00 MeV Emin = 6.56440E+00 MeV : (n,p2) + 10 MT = 603 Q = -6.86200E+00 MeV Emin = 7.00060E+00 MeV : (n,p3) + 11 MT = 604 Q = -7.95380E+00 MeV Emin = 8.11443E+00 MeV : (n,p4) + 12 MT = 605 Q = -8.33300E+00 MeV Emin = 8.50130E+00 MeV : (n,p5) + 13 MT = 606 Q = -8.43700E+00 MeV Emin = 8.60740E+00 MeV : (n,p6) + 14 MT = 607 Q = -8.63300E+00 MeV Emin = 8.80735E+00 MeV : (n,p7) + 15 MT = 608 Q = -8.72000E+00 MeV Emin = 9.00000E+00 MeV : (n,p8) + 16 MT = 609 Q = -9.13400E+00 MeV Emin = 9.31850E+00 MeV : (n,p9) + 17 MT = 610 Q = -9.19600E+00 MeV Emin = 9.38172E+00 MeV : (n,p10) + 18 MT = 649 Q = -9.19600E+00 MeV Emin = 9.38172E+00 MeV : (n,p) to continuum + 19 MT = 650 Q = -9.93800E+00 MeV Emin = 1.01390E+01 MeV : (n,d) to ground state + 20 MT = 651 Q = -1.21660E+01 MeV Emin = 1.24120E+01 MeV : (n,d1) + 21 MT = 652 Q = -1.23090E+01 MeV Emin = 1.25580E+01 MeV : (n,d2) + 22 MT = 653 Q = -1.30230E+01 MeV Emin = 1.32860E+01 MeV : (n,d3) + 23 MT = 654 Q = -1.32380E+01 MeV Emin = 1.35054E+01 MeV : (n,d4) + 24 MT = 655 Q = -1.34540E+01 MeV Emin = 1.37260E+01 MeV : (n,d5) + 25 MT = 699 Q = -1.34540E+01 MeV Emin = 1.37260E+01 MeV : (n,d) to continuum + 26 MT = 700 Q = -1.38120E+01 MeV Emin = 1.45000E+01 MeV : (n,t) to ground state + 27 MT = 701 Q = -1.39420E+01 MeV Emin = 1.45000E+01 MeV : (n,t1) + 28 MT = 702 Q = -1.40640E+01 MeV Emin = 1.47260E+01 MeV : (n,t2) + 29 MT = 703 Q = -1.42000E+01 MeV Emin = 1.47260E+01 MeV : (n,t3) + 30 MT = 704 Q = -1.44340E+01 MeV Emin = 1.50000E+01 MeV : (n,t4) + 31 MT = 705 Q = -1.49080E+01 MeV Emin = 1.52091E+01 MeV : (n,t5) + 32 MT = 749 Q = -1.49080E+01 MeV Emin = 1.52091E+01 MeV : (n,t) to continuum + 33 MT = 750 Q = -1.40710E+01 MeV Emin = 1.50000E+01 MeV : (n,He-3) to ground state + 34 MT = 751 Q = -1.79030E+01 MeV Emin = 1.82646E+01 MeV : (n,He-3_1) + 35 MT = 800 Q = -3.43970E+00 MeV Emin = 5.00000E+00 MeV : (n,alpha) to ground state + 36 MT = 801 Q = -5.45330E+00 MeV Emin = 5.56343E+00 MeV : (n,a1) + 37 MT = 802 Q = -6.01810E+00 MeV Emin = 7.00000E+00 MeV : (n,a2) + 38 MT = 803 Q = -6.03930E+00 MeV Emin = 7.00000E+00 MeV : (n,a3) + 39 MT = 804 Q = -6.28870E+00 MeV Emin = 7.00000E+00 MeV : (n,a4) + 40 MT = 805 Q = -6.31500E+00 MeV Emin = 7.00000E+00 MeV : (n,a5) + 41 MT = 806 Q = -6.70670E+00 MeV Emin = 7.00000E+00 MeV : (n,a6) + 42 MT = 807 Q = -6.73570E+00 MeV Emin = 7.00000E+00 MeV : (n,a7) + 43 MT = 808 Q = -6.86470E+00 MeV Emin = 8.00000E+00 MeV : (n,a8) + 44 MT = 809 Q = -7.00570E+00 MeV Emin = 8.00000E+00 MeV : (n,a9) + 45 MT = 810 Q = -7.28370E+00 MeV Emin = 8.00000E+00 MeV : (n,a10) + 46 MT = 849 Q = -7.28370E+00 MeV Emin = 7.43080E+00 MeV : (n,alpha) to continuum + 47 MT = 4 Q = 0.00000E+00 MeV Emin = 1.58480E+00 MeV : total inelastic scattering + + Nuclide 46 / 1657 : 23000.82c -- natural vanadium (V-nat) + + Pointers : 3498933 35887 + Primary type : Transport + Nuclide ZAI : 230000 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/V0.ACE + Atomic weight (AW) : 50.94161 + Atomic weight ratio (AWR) : 50.50400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : N/A + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is not involved in burnup calculation + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has no decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 38 reaction channels + - 7 special reactions + - No transmutation reactions + - 11 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + 38 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 : elastic scattering + 2 MT = 16 Q = -1.10510E+01 MeV Emin = 1.12700E+01 MeV frac = 1.00000E+00 : (n,2n) + 3 MT = 22 Q = -1.02940E+01 MeV Emin = 1.04978E+01 MeV frac = 1.00000E+00 : (n,nalpha) + 4 MT = 28 Q = -8.05700E+00 MeV Emin = 8.21653E+00 MeV frac = 1.00000E+00 : (n,np) + 5 MT = 32 Q = -1.67760E+01 MeV Emin = 1.71082E+01 MeV frac = 1.00000E+00 : (n,nd) + 6 MT = 51 Q = -3.20000E-01 MeV Emin = 3.26150E-01 MeV frac = 1.00000E+00 : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -9.29000E-01 MeV Emin = 9.47000E-01 MeV frac = 1.00000E+00 : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -1.60900E+00 MeV Emin = 1.64017E+00 MeV frac = 1.00000E+00 : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -1.81300E+00 MeV Emin = 1.84831E+00 MeV frac = 1.00000E+00 : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -2.41100E+00 MeV Emin = 2.45874E+00 MeV frac = 1.00000E+00 : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -2.54700E+00 MeV Emin = 2.59743E+00 MeV frac = 1.00000E+00 : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -2.67700E+00 MeV Emin = 2.73001E+00 MeV frac = 1.00000E+00 : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -2.69900E+00 MeV Emin = 2.75244E+00 MeV frac = 1.00000E+00 : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -3.08500E+00 MeV Emin = 3.14608E+00 MeV frac = 1.00000E+00 : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -3.15000E+00 MeV Emin = 3.21237E+00 MeV frac = 1.00000E+00 : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -3.19500E+00 MeV Emin = 3.25826E+00 MeV frac = 1.00000E+00 : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -3.21500E+00 MeV Emin = 3.27866E+00 MeV frac = 1.00000E+00 : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -3.26400E+00 MeV Emin = 3.32863E+00 MeV frac = 1.00000E+00 : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -3.28000E+00 MeV Emin = 3.34495E+00 MeV frac = 1.00000E+00 : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -3.37200E+00 MeV Emin = 3.43877E+00 MeV frac = 1.00000E+00 : inelastic scatt. to 15. excited state + 21 MT = 66 Q = -3.37700E+00 MeV Emin = 3.44387E+00 MeV frac = 1.00000E+00 : inelastic scatt. to 16. excited state + 22 MT = 67 Q = -3.37800E+00 MeV Emin = 3.44489E+00 MeV frac = 1.00000E+00 : inelastic scatt. to 17. excited state + 23 MT = 68 Q = -3.38100E+00 MeV Emin = 3.44795E+00 MeV frac = 1.00000E+00 : inelastic scatt. to 18. excited state + 24 MT = 69 Q = -3.38300E+00 MeV Emin = 3.44999E+00 MeV frac = 1.00000E+00 : inelastic scatt. to 19. excited state + 25 MT = 70 Q = -3.38600E+00 MeV Emin = 3.45304E+00 MeV frac = 1.00000E+00 : inelastic scatt. to 20. excited state + 26 MT = 71 Q = -3.39600E+00 MeV Emin = 3.46324E+00 MeV frac = 1.00000E+00 : inelastic scatt. to 21. excited state + 27 MT = 72 Q = -3.44400E+00 MeV Emin = 3.51219E+00 MeV frac = 1.00000E+00 : inelastic scatt. to 22. excited state + 28 MT = 73 Q = -3.44500E+00 MeV Emin = 3.51321E+00 MeV frac = 1.00000E+00 : inelastic scatt. to 23. excited state + 29 MT = 74 Q = -3.45400E+00 MeV Emin = 3.52239E+00 MeV frac = 1.00000E+00 : inelastic scatt. to 24. excited state + 30 MT = 91 Q = -3.38400E+00 MeV Emin = 3.45101E+00 MeV frac = 1.00000E+00 : inelastic scattering to continuum + 31 MT = 102 Q = 7.31100E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 : (n,gamma) + 32 MT = 103 Q = -1.68400E+00 MeV Emin = 1.71697E+00 MeV frac = 1.00000E+00 : (n,p) + 33 MT = 104 Q = -5.83200E+00 MeV Emin = 5.94748E+00 MeV frac = 1.00000E+00 : (n,d) + 34 MT = 105 Q = -1.05190E+01 MeV Emin = 1.07300E+01 MeV frac = 1.00000E+00 : (n,t) + 35 MT = 106 Q = -1.25040E+01 MeV Emin = 1.27516E+01 MeV frac = 1.00000E+00 : (n,He-3) + 36 MT = 107 Q = -2.05500E+00 MeV Emin = 2.09569E+00 MeV frac = 1.00000E+00 : (n,alpha) + 37 MT = 111 Q = -1.41690E+01 MeV Emin = 1.44500E+01 MeV frac = 1.00000E+00 : (n,2p) + 38 MT = 112 Q = -1.17255E+01 MeV Emin = 1.19600E+01 MeV frac = 1.00000E+00 : (n,palpha) + + 11 additional transport branches: + + 1 MT = 22 Q = -1.02940E+01 MeV Emin = 1.04978E+01 MeV frac = 1.00000E+00 : (n,nalpha) + 2 MT = 28 Q = -8.05700E+00 MeV Emin = 8.21653E+00 MeV frac = 1.00000E+00 : (n,np) + 3 MT = 32 Q = -1.67760E+01 MeV Emin = 1.71082E+01 MeV frac = 1.00000E+00 : (n,nd) + 4 MT = 103 Q = -1.68400E+00 MeV Emin = 1.71697E+00 MeV frac = 1.00000E+00 : (n,p) + 5 MT = 104 Q = -5.83200E+00 MeV Emin = 5.94748E+00 MeV frac = 1.00000E+00 : (n,d) + 6 MT = 105 Q = -1.05190E+01 MeV Emin = 1.07300E+01 MeV frac = 1.00000E+00 : (n,t) + 7 MT = 106 Q = -1.25040E+01 MeV Emin = 1.27516E+01 MeV frac = 1.00000E+00 : (n,He-3) + 8 MT = 107 Q = -2.05500E+00 MeV Emin = 2.09569E+00 MeV frac = 1.00000E+00 : (n,alpha) + 9 MT = 111 Q = -1.41690E+01 MeV Emin = 1.44500E+01 MeV frac = 2.00000E+00 : (n,2p) + 10 MT = 112 Q = -1.17255E+01 MeV Emin = 1.19600E+01 MeV frac = 1.00000E+00 : (n,palpha) + 11 MT = 112 Q = -1.17255E+01 MeV Emin = 1.19600E+01 MeV frac = 1.00000E+00 : (n,palpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.71697E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.94748E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.07300E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.27516E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 2.09569E+00 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 3.26150E-01 MeV : total inelastic scattering + + Nuclide 47 / 1657 : 24050.82c -- chromium 50 (Cr-50) + + Pointers : 270085 22317 + Primary type : Transport + Nuclide ZAI : 240500 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Cr50.ACE + Atomic weight (AW) : 49.94606 + Atomic weight ratio (AWR) : 49.51700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 5.68E+24 seconds (1.8E+17 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 15 reaction channels + - 5 special reactions + - 7 transmutation reactions + - 5 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 15 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.30000E+01 MeV Emin = 1.32630E+01 MeV frac = 1.00000E+00 Product nuclide = 240490 : (n,2n) + 3 MT = 22 Q = -8.56000E+00 MeV Emin = 8.73290E+00 MeV frac = 1.00000E+00 Product nuclide = 22046.82c : (n,nalpha) + 4 MT = 28 Q = -9.59000E+00 MeV Emin = 9.78370E+00 MeV frac = 1.00000E+00 Product nuclide = 230490 : (n,np) + 5 MT = 51 Q = -7.83000E-01 MeV Emin = 7.98189E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -1.88100E+00 MeV Emin = 1.91322E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -2.92500E+00 MeV Emin = 2.98410E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -3.16100E+00 MeV Emin = 3.22484E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -3.16400E+00 MeV Emin = 3.22790E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -3.32500E+00 MeV Emin = 3.39215E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 91 Q = -3.59500E+00 MeV Emin = 3.66760E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 12 MT = 102 Q = 9.26170E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 240510 : (n,gamma) + 13 MT = 103 Q = -2.56300E-01 MeV Emin = 9.99460E-01 MeV frac = 1.00000E+00 Product nuclide = 230500 : (n,p) + 14 MT = 104 Q = -7.36400E+00 MeV Emin = 7.51272E+00 MeV frac = 1.00000E+00 Product nuclide = 230490 : (n,d) + 15 MT = 107 Q = 3.19500E-01 MeV Emin = 2.25000E+00 MeV frac = 1.00000E+00 Product nuclide = 22047.82c : (n,alpha) + + 5 additional transport branches: + + 1 MT = 22 Q = -8.56000E+00 MeV Emin = 8.73290E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -9.59000E+00 MeV Emin = 9.78370E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -2.56300E-01 MeV Emin = 9.99460E-01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -7.36400E+00 MeV Emin = 7.51272E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 107 Q = 3.19500E-01 MeV Emin = 2.25000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 5 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 9.99460E-01 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.51272E+00 MeV : total deuteron production + 3 MT = 207 Q = 0.00000E+00 MeV Emin = 2.25000E+00 MeV : total alpha production + 4 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 5 MT = 4 Q = 0.00000E+00 MeV Emin = 7.98189E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 22 Q = 1.16720E+00 MeV frac = 1.00000E+00 Product nuclide = 22050.82c : EC/beta+ + EC/beta+ + + Nuclide 48 / 1657 : 24052.82c -- chromium 52 (Cr-52) + + Pointers : 272465 22363 + Primary type : Transport + Nuclide ZAI : 240520 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Cr52.ACE + Atomic weight (AW) : 51.93999 + Atomic weight ratio (AWR) : 51.49380 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 21 reaction channels + - 7 special reactions + - 9 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 21 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.20350E+01 MeV Emin = 1.22730E+01 MeV frac = 1.00000E+00 Product nuclide = 240510 : (n,2n) + 3 MT = 22 Q = -9.35300E+00 MeV Emin = 9.53463E+00 MeV frac = 1.00000E+00 Product nuclide = 22048.82c : (n,nalpha) + 4 MT = 28 Q = -1.05050E+01 MeV Emin = 1.07090E+01 MeV frac = 1.00000E+00 Product nuclide = 230510 : (n,np) + 5 MT = 51 Q = -1.43400E+00 MeV Emin = 1.46134E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -2.37000E+00 MeV Emin = 2.41603E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -2.64700E+00 MeV Emin = 2.69841E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -2.76800E+00 MeV Emin = 2.82176E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -2.96500E+00 MeV Emin = 3.02258E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -3.11400E+00 MeV Emin = 3.17447E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -3.16200E+00 MeV Emin = 3.22341E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -3.41500E+00 MeV Emin = 3.48132E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -3.47200E+00 MeV Emin = 3.53943E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -3.61600E+00 MeV Emin = 3.68622E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 91 Q = -3.70073E+00 MeV Emin = 3.77260E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 16 MT = 102 Q = 7.94010E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 24053.82c : (n,gamma) + 17 MT = 103 Q = -3.19270E+00 MeV Emin = 3.25600E+00 MeV frac = 1.00000E+00 Product nuclide = 230520 : (n,p) + 18 MT = 104 Q = -8.28000E+00 MeV Emin = 8.44080E+00 MeV frac = 1.00000E+00 Product nuclide = 230510 : (n,d) + 19 MT = 105 Q = -1.30740E+01 MeV Emin = 1.33279E+01 MeV frac = 1.00000E+00 Product nuclide = 230500 : (n,t) + 20 MT = 106 Q = -1.08470E+01 MeV Emin = 1.10577E+01 MeV frac = 1.00000E+00 Product nuclide = 22050.82c : (n,He-3) + 21 MT = 107 Q = -1.20970E+00 MeV Emin = 1.23325E+00 MeV frac = 1.00000E+00 Product nuclide = 22049.82c : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -9.35300E+00 MeV Emin = 9.53463E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.05050E+01 MeV Emin = 1.07090E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -3.19270E+00 MeV Emin = 3.25600E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -8.28000E+00 MeV Emin = 8.44080E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -1.30740E+01 MeV Emin = 1.33279E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 106 Q = -1.08470E+01 MeV Emin = 1.10577E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 7 MT = 107 Q = -1.20970E+00 MeV Emin = 1.23325E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.25600E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.44080E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.33279E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.10577E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.23325E+00 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 1.46134E+00 MeV : total inelastic scattering + + Nuclide 49 / 1657 : 24053.82c -- chromium 53 (Cr-53) + + Pointers : 275131 22409 + Primary type : Transport + Nuclide ZAI : 240530 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Cr53.ACE + Atomic weight (AW) : 52.94079 + Atomic weight ratio (AWR) : 52.48600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 21 reaction channels + - 4 special reactions + - 6 transmutation reactions + - 4 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 21 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.94000E+00 MeV Emin = 8.09130E+00 MeV frac = 1.00000E+00 Product nuclide = 24052.82c : (n,2n) + 3 MT = 22 Q = -9.15000E+00 MeV Emin = 9.32433E+00 MeV frac = 1.00000E+00 Product nuclide = 22049.82c : (n,nalpha) + 4 MT = 28 Q = -1.11340E+01 MeV Emin = 1.13461E+01 MeV frac = 1.00000E+00 Product nuclide = 230520 : (n,np) + 5 MT = 51 Q = -5.64000E-01 MeV Emin = 5.74507E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -1.00600E+00 MeV Emin = 1.02484E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -1.29000E+00 MeV Emin = 1.31421E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -1.53700E+00 MeV Emin = 1.56583E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -1.97400E+00 MeV Emin = 2.01161E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -2.17200E+00 MeV Emin = 2.21340E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -2.23300E+00 MeV Emin = 2.27555E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -2.32100E+00 MeV Emin = 2.36522E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -2.45300E+00 MeV Emin = 2.49974E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -2.65600E+00 MeV Emin = 2.70661E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -2.67000E+00 MeV Emin = 2.72090E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -2.70600E+00 MeV Emin = 2.75760E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 63 Q = -2.70700E+00 MeV Emin = 2.75860E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 18 MT = 91 Q = -2.77200E+00 MeV Emin = 2.82482E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 19 MT = 102 Q = 9.71990E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 24054.82c : (n,gamma) + 20 MT = 103 Q = -2.64000E+00 MeV Emin = 2.69030E+00 MeV frac = 1.00000E+00 Product nuclide = 230530 : (n,p) + 21 MT = 107 Q = 1.79500E+00 MeV Emin = 9.99018E-01 MeV frac = 1.00000E+00 Product nuclide = 22050.82c : (n,alpha) + + 4 additional transport branches: + + 1 MT = 22 Q = -9.15000E+00 MeV Emin = 9.32433E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.11340E+01 MeV Emin = 1.13461E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -2.64000E+00 MeV Emin = 2.69030E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 107 Q = 1.79500E+00 MeV Emin = 9.99018E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 4 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.69030E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 9.99018E-01 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 4 MT = 4 Q = 0.00000E+00 MeV Emin = 5.74507E-01 MeV : total inelastic scattering + + Nuclide 50 / 1657 : 24054.82c -- chromium 54 (Cr-54) + + Pointers : 277359 22455 + Primary type : Transport + Nuclide ZAI : 240540 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Cr54.ACE + Atomic weight (AW) : 53.93937 + Atomic weight ratio (AWR) : 53.47600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 10 reaction channels + - 4 special reactions + - 4 transmutation reactions + - 2 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 10 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -9.71900E+00 MeV Emin = 9.90075E+00 MeV frac = 1.00000E+00 Product nuclide = 24053.82c : (n,2n) + 3 MT = 51 Q = -8.35000E-01 MeV Emin = 8.50300E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 4 MT = 52 Q = -1.82400E+00 MeV Emin = 1.85595E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 5 MT = 53 Q = -2.62000E+00 MeV Emin = 2.66900E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 6 MT = 54 Q = -2.82900E+00 MeV Emin = 2.88190E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 7 MT = 91 Q = -3.07400E+00 MeV Emin = 3.13150E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 8 MT = 102 Q = 6.24630E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 240550 : (n,gamma) + 9 MT = 103 Q = -6.21400E+00 MeV Emin = 6.33020E+00 MeV frac = 1.00000E+00 Product nuclide = 230540 : (n,p) + 10 MT = 107 Q = -1.55200E+00 MeV Emin = 1.58078E+00 MeV frac = 1.00000E+00 Product nuclide = 220510 : (n,alpha) + + 2 additional transport branches: + + 1 MT = 103 Q = -6.21400E+00 MeV Emin = 6.33020E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 107 Q = -1.55200E+00 MeV Emin = 1.58078E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 4 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 6.33020E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 1.58078E+00 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 4 MT = 4 Q = 0.00000E+00 MeV Emin = 8.50300E-01 MeV : total inelastic scattering + + Nuclide 51 / 1657 : 25055.82c -- manganese 55 (Mn-55) + + Pointers : 283631 27745 + Primary type : Transport + Nuclide ZAI : 250550 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Mn55.ACE + Atomic weight (AW) : 54.93805 + Atomic weight ratio (AWR) : 54.46610 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 27 reaction channels + - 7 special reactions + - 9 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 27 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.02270E+01 MeV Emin = 1.04148E+01 MeV frac = 1.00000E+00 Product nuclide = 250540 : (n,2n) + 3 MT = 22 Q = -7.93579E+00 MeV Emin = 8.08150E+00 MeV frac = 1.00000E+00 Product nuclide = 230510 : (n,nalpha) + 4 MT = 28 Q = -8.06789E+00 MeV Emin = 8.21602E+00 MeV frac = 1.00000E+00 Product nuclide = 24054.82c : (n,np) + 5 MT = 51 Q = -1.26000E-01 MeV Emin = 1.28188E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -9.83999E-01 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -1.29000E+00 MeV Emin = 1.31156E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -1.29200E+00 MeV Emin = 1.31536E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -1.29300E+00 MeV Emin = 1.31620E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -1.52800E+00 MeV Emin = 1.54974E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -1.88400E+00 MeV Emin = 1.91754E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -2.01500E+00 MeV Emin = 2.05200E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -2.19800E+00 MeV Emin = 2.23836E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -2.21500E+00 MeV Emin = 2.25567E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -2.25200E+00 MeV Emin = 2.29335E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -2.26700E+00 MeV Emin = 2.30862E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 63 Q = -2.31200E+00 MeV Emin = 2.35445E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 18 MT = 64 Q = -2.36600E+00 MeV Emin = 2.40944E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 19 MT = 65 Q = -2.39800E+00 MeV Emin = 2.44203E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 20 MT = 66 Q = -2.42700E+00 MeV Emin = 2.47156E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 21 MT = 91 Q = -3.04600E+00 MeV Emin = 3.10193E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 22 MT = 102 Q = 7.27053E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 250560 : (n,gamma) + 23 MT = 103 Q = -1.82120E+00 MeV Emin = 1.85420E+00 MeV frac = 1.00000E+00 Product nuclide = 240550 : (n,p) + 24 MT = 104 Q = -5.84329E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 24054.82c : (n,d) + 25 MT = 105 Q = -9.30499E+00 MeV Emin = 1.15000E+01 MeV frac = 1.00000E+00 Product nuclide = 24053.82c : (n,t) + 26 MT = 106 Q = -1.27070E+01 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 230530 : (n,He-3) + 27 MT = 107 Q = -6.24299E-01 MeV Emin = 6.35000E-01 MeV frac = 1.00000E+00 Product nuclide = 230520 : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -7.93579E+00 MeV Emin = 8.08150E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -8.06789E+00 MeV Emin = 8.21602E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -1.82120E+00 MeV Emin = 1.85420E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -5.84329E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -9.30499E+00 MeV Emin = 1.15000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 106 Q = -1.27070E+01 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 7 MT = 107 Q = -6.24299E-01 MeV Emin = 6.35000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.85420E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.15000E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.40000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 6.35000E-01 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 1.28188E-01 MeV : total inelastic scattering + + Nuclide 52 / 1657 : 26054.82c -- iron 54 (Fe-54) + + Pointers : 294256 24019 + Primary type : Transport + Nuclide ZAI : 260540 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Fe54.ACE + Atomic weight (AW) : 53.93962 + Atomic weight ratio (AWR) : 53.47625 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+02 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 37 reaction channels + - 52 special reactions + - 14 transmutation reactions + - 14 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 37 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 5 Q = 0.00000E+00 MeV Emin = 6.99790E-01 MeV frac = 1.00000E+00 Product nuclide = self : anything + 3 MT = 16 Q = -1.33785E+01 MeV Emin = 1.36287E+01 MeV frac = 1.00000E+00 Product nuclide = 260530 : (n,2n) + 4 MT = 22 Q = -8.41886E+00 MeV Emin = 9.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 24050.82c : (n,nalpha) + 5 MT = 28 Q = -8.85375E+00 MeV Emin = 9.01932E+00 MeV frac = 1.00000E+00 Product nuclide = 250530 : (n,np) + 6 MT = 44 Q = -1.54136E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 24052.82c : (n,n2p) + 7 MT = 51 Q = -1.40819E+00 MeV Emin = 1.43385E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 8 MT = 52 Q = -2.53810E+00 MeV Emin = 2.58556E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 9 MT = 53 Q = -2.56130E+00 MeV Emin = 2.60920E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 10 MT = 54 Q = -2.94920E+00 MeV Emin = 3.00435E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 11 MT = 55 Q = -2.95900E+00 MeV Emin = 3.01433E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 12 MT = 56 Q = -3.16600E+00 MeV Emin = 3.22520E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 13 MT = 57 Q = -3.29480E+00 MeV Emin = 3.35641E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 14 MT = 58 Q = -3.34480E+00 MeV Emin = 3.40735E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 15 MT = 59 Q = -3.43740E+00 MeV Emin = 3.50168E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 16 MT = 60 Q = -3.79380E+00 MeV Emin = 3.86475E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 17 MT = 61 Q = -3.83320E+00 MeV Emin = 3.90488E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 18 MT = 62 Q = -3.84100E+00 MeV Emin = 3.91283E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 19 MT = 63 Q = -4.03090E+00 MeV Emin = 4.10628E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 20 MT = 64 Q = -4.04780E+00 MeV Emin = 4.12349E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 21 MT = 65 Q = -4.07160E+00 MeV Emin = 4.14774E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 22 MT = 66 Q = -4.09970E+00 MeV Emin = 4.17636E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 23 MT = 67 Q = -4.10340E+00 MeV Emin = 4.18013E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 24 MT = 68 Q = -4.26780E+00 MeV Emin = 4.34761E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 25 MT = 69 Q = -4.29080E+00 MeV Emin = 4.37104E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 26 MT = 70 Q = -4.57850E+00 MeV Emin = 4.66412E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 27 MT = 91 Q = -4.57850E+00 MeV Emin = 4.66412E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 28 MT = 102 Q = 9.29792E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 260550 : (n,gamma) + 29 MT = 103 Q = 8.52127E-02 MeV Emin = 3.39318E-01 MeV frac = 1.00000E+00 Product nuclide = 250540 : (n,p) + 30 MT = 104 Q = -6.62918E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 250530 : (n,d) + 31 MT = 105 Q = -1.24257E+01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 250520 : (n,t) + 32 MT = 106 Q = -7.69549E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 24052.82c : (n,He-3) + 33 MT = 107 Q = 8.42760E-01 MeV Emin = 6.75946E-01 MeV frac = 1.00000E+00 Product nuclide = 240510 : (n,alpha) + 34 MT = 108 Q = -8.09518E+00 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 22047.82c : (n,2alpha) + 35 MT = 111 Q = -7.47439E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 24053.82c : (n,2p) + 36 MT = 112 Q = -8.67343E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 230500 : (n,palpha) + 37 MT = 115 Q = -1.31890E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 24052.82c : (n,pd) + + 14 additional transport branches: + + 1 MT = 22 Q = -8.41886E+00 MeV Emin = 9.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -8.85375E+00 MeV Emin = 9.01932E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 44 Q = -1.54136E+01 MeV Emin = 1.60000E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,n2p) + 4 MT = 103 Q = 8.52127E-02 MeV Emin = 3.39318E-01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -6.62918E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -1.24257E+01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 106 Q = -7.69549E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 8 MT = 107 Q = 8.42760E-01 MeV Emin = 6.75946E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 9 MT = 108 Q = -8.09518E+00 MeV Emin = 1.25000E+01 MeV frac = 2.00000E+00 Product nuclide = 2004.82c : (n,2alpha) + 10 MT = 111 Q = -7.47439E+00 MeV Emin = 8.00000E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + 11 MT = 112 Q = -8.67343E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,palpha) + 12 MT = 112 Q = -8.67343E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,palpha) + 13 MT = 115 Q = -1.31890E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,pd) + 14 MT = 115 Q = -1.31890E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,pd) + + 52 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.39318E-01 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.30000E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 9.00000E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 6.75946E-01 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 5.00000E-04 MeV : damage-energy production + 7 MT = 600 Q = 8.52127E-02 MeV Emin = 3.40533E-01 MeV : (n,p) to ground state + 8 MT = 601 Q = 3.03427E-02 MeV Emin = 3.43705E-01 MeV : (n,p1) + 9 MT = 602 Q = -7.10873E-02 MeV Emin = 3.99862E-01 MeV : (n,p2) + 10 MT = 603 Q = -2.83077E-01 MeV Emin = 5.99924E-01 MeV : (n,p3) + 11 MT = 604 Q = -3.22337E-01 MeV Emin = 6.99893E-01 MeV : (n,p4) + 12 MT = 605 Q = -7.53697E-01 MeV Emin = 9.99868E-01 MeV : (n,p5) + 13 MT = 606 Q = -9.24407E-01 MeV Emin = 1.19983E+00 MeV : (n,p6) + 14 MT = 607 Q = -9.88087E-01 MeV Emin = 1.39979E+00 MeV : (n,p7) + 15 MT = 608 Q = -1.05153E+00 MeV Emin = 1.39979E+00 MeV : (n,p8) + 16 MT = 609 Q = -1.28978E+00 MeV Emin = 1.59892E+00 MeV : (n,p9) + 17 MT = 610 Q = -1.29037E+00 MeV Emin = 1.59892E+00 MeV : (n,p10) + 18 MT = 649 Q = -1.29037E+00 MeV Emin = 1.79960E+00 MeV : (n,p) to continuum + 19 MT = 650 Q = -6.62918E+00 MeV Emin = 7.00000E+00 MeV : (n,d) to ground state + 20 MT = 651 Q = -7.00707E+00 MeV Emin = 7.20000E+00 MeV : (n,d1) + 21 MT = 652 Q = -7.91885E+00 MeV Emin = 8.06693E+00 MeV : (n,d2) + 22 MT = 653 Q = -8.07030E+00 MeV Emin = 8.50000E+00 MeV : (n,d3) + 23 MT = 654 Q = -8.25038E+00 MeV Emin = 8.50000E+00 MeV : (n,d4) + 24 MT = 655 Q = -8.90295E+00 MeV Emin = 9.06944E+00 MeV : (n,d5) + 25 MT = 699 Q = -8.90295E+00 MeV Emin = 1.00000E+01 MeV : (n,d) to continuum + 26 MT = 700 Q = -1.24257E+01 MeV Emin = 1.30000E+01 MeV : (n,t) to ground state + 27 MT = 701 Q = -1.28035E+01 MeV Emin = 1.35000E+01 MeV : (n,t1) + 28 MT = 702 Q = -1.29722E+01 MeV Emin = 1.35000E+01 MeV : (n,t2) + 29 MT = 703 Q = -1.31574E+01 MeV Emin = 1.35000E+01 MeV : (n,t3) + 30 MT = 704 Q = -1.32509E+01 MeV Emin = 1.35000E+01 MeV : (n,t4) + 31 MT = 705 Q = -1.32956E+01 MeV Emin = 1.40000E+01 MeV : (n,t5) + 32 MT = 749 Q = -1.32956E+01 MeV Emin = 1.40000E+01 MeV : (n,t) to continuum + 33 MT = 750 Q = -7.69549E+00 MeV Emin = 9.00000E+00 MeV : (n,He-3) to ground state + 34 MT = 751 Q = -9.12958E+00 MeV Emin = 9.50000E+00 MeV : (n,He-3_1) + 35 MT = 752 Q = -1.00651E+01 MeV Emin = 1.10000E+01 MeV : (n,He-3_2) + 36 MT = 753 Q = -1.03424E+01 MeV Emin = 1.15000E+01 MeV : (n,He-3_3) + 37 MT = 754 Q = -1.04633E+01 MeV Emin = 1.15000E+01 MeV : (n,He-3_4) + 38 MT = 755 Q = -1.06603E+01 MeV Emin = 1.20000E+01 MeV : (n,He-3_5) + 39 MT = 799 Q = -1.06603E+01 MeV Emin = 1.30000E+01 MeV : (n,He-3) to continuum + 40 MT = 800 Q = 8.42760E-01 MeV Emin = 6.75946E-01 MeV : (n,alpha) to ground state + 41 MT = 801 Q = 9.36601E-02 MeV Emin = 1.47795E+00 MeV : (n,a1) + 42 MT = 802 Q = 6.58101E-02 MeV Emin = 1.54416E+00 MeV : (n,a2) + 43 MT = 803 Q = -3.21830E-01 MeV Emin = 1.98065E+00 MeV : (n,a3) + 44 MT = 804 Q = -5.09890E-01 MeV Emin = 2.00178E+00 MeV : (n,a4) + 45 MT = 805 Q = -6.37310E-01 MeV Emin = 2.00178E+00 MeV : (n,a5) + 46 MT = 806 Q = -7.14500E-01 MeV Emin = 2.00178E+00 MeV : (n,a6) + 47 MT = 807 Q = -1.05644E+00 MeV Emin = 2.20000E+00 MeV : (n,a7) + 48 MT = 808 Q = -1.15915E+00 MeV Emin = 2.40000E+00 MeV : (n,a8) + 49 MT = 809 Q = -1.41274E+00 MeV Emin = 2.60000E+00 MeV : (n,a9) + 50 MT = 810 Q = -1.46982E+00 MeV Emin = 2.60000E+00 MeV : (n,a10) + 51 MT = 849 Q = -1.46982E+00 MeV Emin = 2.80000E+00 MeV : (n,alpha) to continuum + 52 MT = 4 Q = 0.00000E+00 MeV Emin = 1.43385E+00 MeV : total inelastic scattering + + Nuclide 53 / 1657 : 26056.82c -- iron 56 (Fe-56) + + Pointers : 302201 24065 + Primary type : Transport + Nuclide ZAI : 260560 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Fe56.ACE + Atomic weight (AW) : 55.93491 + Atomic weight ratio (AWR) : 55.45440 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+02 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 44 reaction channels + - 34 special reactions + - 9 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 44 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 5 Q = 0.00000E+00 MeV Emin = 2.00000E+01 MeV frac = 1.00000E+00 Product nuclide = self : anything + 3 MT = 16 Q = -1.11970E+01 MeV Emin = 1.13989E+01 MeV frac = 1.00000E+00 Product nuclide = 260550 : (n,2n) + 4 MT = 22 Q = -7.61310E+00 MeV Emin = 7.75039E+00 MeV frac = 1.00000E+00 Product nuclide = 24052.82c : (n,nalpha) + 5 MT = 28 Q = -1.01840E+01 MeV Emin = 1.03677E+01 MeV frac = 1.00000E+00 Product nuclide = 25055.82c : (n,np) + 6 MT = 51 Q = -8.47000E-01 MeV Emin = 8.61932E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -2.08500E+00 MeV Emin = 2.12260E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -2.65800E+00 MeV Emin = 2.70593E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -2.94200E+00 MeV Emin = 2.99510E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -2.96000E+00 MeV Emin = 3.01340E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -3.12000E+00 MeV Emin = 3.17630E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -3.12300E+00 MeV Emin = 3.17932E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -3.37000E+00 MeV Emin = 3.43080E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -3.38900E+00 MeV Emin = 3.45011E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -3.44500E+00 MeV Emin = 3.50712E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -3.44900E+00 MeV Emin = 3.51120E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -3.59900E+00 MeV Emin = 3.66390E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -3.60100E+00 MeV Emin = 3.66594E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -3.60700E+00 MeV Emin = 3.67204E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -3.74800E+00 MeV Emin = 3.81560E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 21 MT = 66 Q = -3.75600E+00 MeV Emin = 3.82373E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 22 MT = 67 Q = -3.76000E+00 MeV Emin = 3.82780E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 23 MT = 68 Q = -3.83000E+00 MeV Emin = 3.89910E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 24 MT = 69 Q = -3.85600E+00 MeV Emin = 3.92554E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 25 MT = 70 Q = -4.04900E+00 MeV Emin = 4.12202E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 26 MT = 71 Q = -4.10000E+00 MeV Emin = 4.17394E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 27 MT = 72 Q = -4.12000E+00 MeV Emin = 4.19430E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 28 MT = 73 Q = -4.29800E+00 MeV Emin = 4.37551E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 29 MT = 74 Q = -4.30000E+00 MeV Emin = 4.37754E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 30 MT = 75 Q = -4.32000E+00 MeV Emin = 4.39790E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 31 MT = 76 Q = -4.37000E+00 MeV Emin = 4.44880E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 32 MT = 77 Q = -4.39200E+00 MeV Emin = 4.47120E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 27. excited state + 33 MT = 78 Q = -4.39500E+00 MeV Emin = 4.47430E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 28. excited state + 34 MT = 79 Q = -4.40100E+00 MeV Emin = 4.48040E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 29. excited state + 35 MT = 80 Q = -4.44700E+00 MeV Emin = 4.52719E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 30. excited state + 36 MT = 81 Q = -4.45800E+00 MeV Emin = 4.53840E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 31. excited state + 37 MT = 82 Q = -4.51000E+00 MeV Emin = 4.59133E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 32. excited state + 38 MT = 91 Q = -4.53600E+00 MeV Emin = 4.61780E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 39 MT = 102 Q = 7.64670E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 26057.82c : (n,gamma) + 40 MT = 103 Q = -2.91310E+00 MeV Emin = 4.09950E+00 MeV frac = 1.00000E+00 Product nuclide = 250560 : (n,p) + 41 MT = 104 Q = -7.95900E+00 MeV Emin = 8.10252E+00 MeV frac = 1.00000E+00 Product nuclide = 25055.82c : (n,d) + 42 MT = 105 Q = -1.19280E+01 MeV Emin = 1.21431E+01 MeV frac = 1.00000E+00 Product nuclide = 250540 : (n,t) + 43 MT = 106 Q = -1.05330E+01 MeV Emin = 1.07230E+01 MeV frac = 1.00000E+00 Product nuclide = 24054.82c : (n,He-3) + 44 MT = 107 Q = 3.26050E-01 MeV Emin = 3.43110E+00 MeV frac = 1.00000E+00 Product nuclide = 24053.82c : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -7.61310E+00 MeV Emin = 7.75039E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.01840E+01 MeV Emin = 1.03677E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -2.91310E+00 MeV Emin = 4.09950E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -7.95900E+00 MeV Emin = 8.10252E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -1.19280E+01 MeV Emin = 1.21431E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 106 Q = -1.05330E+01 MeV Emin = 1.07230E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 7 MT = 107 Q = 3.26050E-01 MeV Emin = 3.43110E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 34 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.09950E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.10252E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.21431E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.07230E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 3.43110E+00 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 600 Q = -2.91310E+00 MeV Emin = 4.09950E+00 MeV : (n,p) to ground state + 8 MT = 601 Q = -2.94010E+00 MeV Emin = 4.09950E+00 MeV : (n,p1) + 9 MT = 602 Q = -3.02410E+00 MeV Emin = 4.17440E+00 MeV : (n,p2) + 10 MT = 603 Q = -3.12510E+00 MeV Emin = 4.37590E+00 MeV : (n,p3) + 11 MT = 604 Q = -3.12810E+00 MeV Emin = 4.37590E+00 MeV : (n,p4) + 12 MT = 605 Q = -3.24910E+00 MeV Emin = 4.47170E+00 MeV : (n,p5) + 13 MT = 606 Q = -3.25410E+00 MeV Emin = 4.37590E+00 MeV : (n,p6) + 14 MT = 607 Q = -3.36710E+00 MeV Emin = 4.52760E+00 MeV : (n,p7) + 15 MT = 608 Q = -3.39910E+00 MeV Emin = 4.53880E+00 MeV : (n,p8) + 16 MT = 609 Q = -3.45410E+00 MeV Emin = 4.69560E+00 MeV : (n,p9) + 17 MT = 610 Q = -3.57310E+00 MeV Emin = 4.79450E+00 MeV : (n,p10) + 18 MT = 611 Q = -3.62910E+00 MeV Emin = 5.00000E+00 MeV : (n,p11) + 19 MT = 612 Q = -3.66610E+00 MeV Emin = 5.00000E+00 MeV : (n,p12) + 20 MT = 613 Q = -3.75310E+00 MeV Emin = 5.00000E+00 MeV : (n,p13) + 21 MT = 649 Q = -3.79810E+00 MeV Emin = 5.00000E+00 MeV : (n,p) to continuum + 22 MT = 800 Q = 3.26047E-01 MeV Emin = 3.43110E+00 MeV : (n,alpha) to ground state + 23 MT = 801 Q = -2.37953E-01 MeV Emin = 4.17440E+00 MeV : (n,a1) + 24 MT = 802 Q = -6.79953E-01 MeV Emin = 4.59200E+00 MeV : (n,a2) + 25 MT = 803 Q = -9.63953E-01 MeV Emin = 5.00000E+00 MeV : (n,a3) + 26 MT = 804 Q = -1.21095E+00 MeV Emin = 5.25000E+00 MeV : (n,a4) + 27 MT = 805 Q = -1.64795E+00 MeV Emin = 6.00000E+00 MeV : (n,a5) + 28 MT = 806 Q = -1.83895E+00 MeV Emin = 6.50000E+00 MeV : (n,a6) + 29 MT = 807 Q = -1.84595E+00 MeV Emin = 6.50000E+00 MeV : (n,a7) + 30 MT = 808 Q = -1.90695E+00 MeV Emin = 6.50000E+00 MeV : (n,a8) + 31 MT = 809 Q = -1.99495E+00 MeV Emin = 6.50000E+00 MeV : (n,a9) + 32 MT = 810 Q = -2.12695E+00 MeV Emin = 6.50000E+00 MeV : (n,a10) + 33 MT = 849 Q = -2.19295E+00 MeV Emin = 6.50000E+00 MeV : (n,alpha) to continuum + 34 MT = 4 Q = 0.00000E+00 MeV Emin = 8.61932E-01 MeV : total inelastic scattering + + Nuclide 54 / 1657 : 26057.82c -- iron 57 (Fe-57) + + Pointers : 308517 24111 + Primary type : Transport + Nuclide ZAI : 260570 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Fe57.ACE + Atomic weight (AW) : 56.93541 + Atomic weight ratio (AWR) : 56.44630 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+02 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 39 reaction channels + - 52 special reactions + - 16 transmutation reactions + - 14 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 39 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 5 Q = 0.00000E+00 MeV Emin = 1.99844E-01 MeV frac = 1.00000E+00 Product nuclide = self : anything + 3 MT = 16 Q = -7.64603E+00 MeV Emin = 7.78149E+00 MeV frac = 1.00000E+00 Product nuclide = 26056.82c : (n,2n) + 4 MT = 17 Q = -1.88433E+01 MeV Emin = 1.91772E+01 MeV frac = 1.00000E+00 Product nuclide = 260550 : (n,3n) + 5 MT = 22 Q = -7.31998E+00 MeV Emin = 8.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 24053.82c : (n,nalpha) + 6 MT = 24 Q = -1.52591E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 24052.82c : (n,2nalpha) + 7 MT = 28 Q = -1.05591E+01 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 250560 : (n,np) + 8 MT = 32 Q = -1.56050E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 25055.82c : (n,nd) + 9 MT = 41 Q = -1.78296E+01 MeV Emin = 1.81455E+01 MeV frac = 1.00000E+00 Product nuclide = 25055.82c : (n,2np) + 10 MT = 51 Q = -1.44130E-02 MeV Emin = 1.46227E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 11 MT = 52 Q = -1.36474E-01 MeV Emin = 1.38698E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 12 MT = 53 Q = -3.66759E-01 MeV Emin = 3.50363E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 13 MT = 54 Q = -7.06416E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 14 MT = 55 Q = -1.00713E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 15 MT = 56 Q = -1.13990E+00 MeV Emin = 1.14131E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 16 MT = 57 Q = -1.19781E+00 MeV Emin = 1.20000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 17 MT = 58 Q = -1.26552E+00 MeV Emin = 1.26632E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 18 MT = 59 Q = -1.35683E+00 MeV Emin = 1.38023E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 19 MT = 60 Q = -1.62726E+00 MeV Emin = 1.63856E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 20 MT = 61 Q = -1.72538E+00 MeV Emin = 1.73847E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 21 MT = 62 Q = -1.97663E+00 MeV Emin = 2.01165E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 22 MT = 63 Q = -1.98966E+00 MeV Emin = 2.02491E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 23 MT = 64 Q = -1.99100E+00 MeV Emin = 2.02627E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 24 MT = 65 Q = -2.11311E+00 MeV Emin = 2.15055E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 25 MT = 66 Q = -2.11860E+00 MeV Emin = 2.15613E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 26 MT = 67 Q = -2.20688E+00 MeV Emin = 2.24598E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 27 MT = 68 Q = -2.21766E+00 MeV Emin = 2.25695E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 28 MT = 69 Q = -2.22020E+00 MeV Emin = 2.25953E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 29 MT = 70 Q = -2.33041E+00 MeV Emin = 2.37170E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 30 MT = 91 Q = -2.33041E+00 MeV Emin = 2.37170E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 31 MT = 102 Q = 1.00445E+01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 26058.82c : (n,gamma) + 32 MT = 103 Q = -1.90850E+00 MeV Emin = 2.20000E+00 MeV frac = 1.00000E+00 Product nuclide = 250570 : (n,p) + 33 MT = 104 Q = -8.33455E+00 MeV Emin = 8.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 250560 : (n,d) + 34 MT = 105 Q = -9.34780E+00 MeV Emin = 9.51341E+00 MeV frac = 1.00000E+00 Product nuclide = 25055.82c : (n,t) + 35 MT = 106 Q = -1.19323E+01 MeV Emin = 1.35000E+01 MeV frac = 1.00000E+00 Product nuclide = 240550 : (n,He-3) + 36 MT = 107 Q = 2.39902E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 24054.82c : (n,alpha) + 37 MT = 108 Q = -5.52836E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 22050.82c : (n,2alpha) + 38 MT = 111 Q = -1.13937E+01 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 240560 : (n,2p) + 39 MT = 112 Q = -9.97366E+00 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 230530 : (n,palpha) + + 14 additional transport branches: + + 1 MT = 22 Q = -7.31998E+00 MeV Emin = 8.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 24 Q = -1.52591E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,2nalpha) + 3 MT = 28 Q = -1.05591E+01 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 4 MT = 32 Q = -1.56050E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 5 MT = 41 Q = -1.78296E+01 MeV Emin = 1.81455E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,2np) + 6 MT = 103 Q = -1.90850E+00 MeV Emin = 2.20000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 7 MT = 104 Q = -8.33455E+00 MeV Emin = 8.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 8 MT = 105 Q = -9.34780E+00 MeV Emin = 9.51341E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 9 MT = 106 Q = -1.19323E+01 MeV Emin = 1.35000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 10 MT = 107 Q = 2.39902E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 11 MT = 108 Q = -5.52836E+00 MeV Emin = 1.00000E+01 MeV frac = 2.00000E+00 Product nuclide = 2004.82c : (n,2alpha) + 12 MT = 111 Q = -1.13937E+01 MeV Emin = 1.25000E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + 13 MT = 112 Q = -9.97366E+00 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,palpha) + 14 MT = 112 Q = -9.97366E+00 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,palpha) + + 52 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.20000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.50000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.51341E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.35000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 600 Q = -1.90850E+00 MeV Emin = 2.20000E+00 MeV : (n,p) to ground state + 8 MT = 601 Q = -1.99169E+00 MeV Emin = 2.20000E+00 MeV : (n,p1) + 9 MT = 602 Q = -2.75857E+00 MeV Emin = 2.80744E+00 MeV : (n,p2) + 10 MT = 603 Q = -2.96433E+00 MeV Emin = 3.20000E+00 MeV : (n,p3) + 11 MT = 604 Q = -2.98140E+00 MeV Emin = 3.20000E+00 MeV : (n,p4) + 12 MT = 605 Q = -3.13600E+00 MeV Emin = 3.40000E+00 MeV : (n,p5) + 13 MT = 606 Q = -3.28350E+00 MeV Emin = 3.40000E+00 MeV : (n,p6) + 14 MT = 607 Q = -3.38550E+00 MeV Emin = 3.60000E+00 MeV : (n,p7) + 15 MT = 608 Q = -3.40117E+00 MeV Emin = 3.60000E+00 MeV : (n,p8) + 16 MT = 609 Q = -3.44333E+00 MeV Emin = 3.60000E+00 MeV : (n,p9) + 17 MT = 610 Q = -3.52650E+00 MeV Emin = 3.80000E+00 MeV : (n,p10) + 18 MT = 649 Q = -3.52650E+00 MeV Emin = 4.00000E+00 MeV : (n,p) to continuum + 19 MT = 650 Q = -8.33455E+00 MeV Emin = 8.50000E+00 MeV : (n,d) to ground state + 20 MT = 651 Q = -8.36116E+00 MeV Emin = 8.50929E+00 MeV : (n,d1) + 21 MT = 652 Q = -8.44506E+00 MeV Emin = 9.00000E+00 MeV : (n,d2) + 22 MT = 653 Q = -8.54658E+00 MeV Emin = 9.00000E+00 MeV : (n,d3) + 23 MT = 654 Q = -8.54968E+00 MeV Emin = 9.00000E+00 MeV : (n,d4) + 24 MT = 655 Q = -8.67008E+00 MeV Emin = 9.00000E+00 MeV : (n,d5) + 25 MT = 699 Q = -8.67008E+00 MeV Emin = 9.00000E+00 MeV : (n,d) to continuum + 26 MT = 700 Q = -9.34780E+00 MeV Emin = 9.51341E+00 MeV : (n,t) to ground state + 27 MT = 701 Q = -9.47374E+00 MeV Emin = 1.00000E+01 MeV : (n,t1) + 28 MT = 702 Q = -1.03321E+01 MeV Emin = 1.05152E+01 MeV : (n,t2) + 29 MT = 703 Q = -1.06369E+01 MeV Emin = 1.10000E+01 MeV : (n,t3) + 30 MT = 704 Q = -1.06399E+01 MeV Emin = 1.10000E+01 MeV : (n,t4) + 31 MT = 705 Q = -1.06408E+01 MeV Emin = 1.10000E+01 MeV : (n,t5) + 32 MT = 749 Q = -1.06408E+01 MeV Emin = 1.15000E+01 MeV : (n,t) to continuum + 33 MT = 750 Q = -1.19323E+01 MeV Emin = 1.35000E+01 MeV : (n,He-3) to ground state + 34 MT = 751 Q = -1.21742E+01 MeV Emin = 1.35000E+01 MeV : (n,He-3_1) + 35 MT = 752 Q = -1.24500E+01 MeV Emin = 1.40000E+01 MeV : (n,He-3_2) + 36 MT = 753 Q = -1.24982E+01 MeV Emin = 1.40000E+01 MeV : (n,He-3_3) + 37 MT = 754 Q = -1.28130E+01 MeV Emin = 1.40000E+01 MeV : (n,He-3_4) + 38 MT = 755 Q = -1.30633E+01 MeV Emin = 1.45000E+01 MeV : (n,He-3_5) + 39 MT = 799 Q = -1.30633E+01 MeV Emin = 1.50000E+01 MeV : (n,He-3) to continuum + 40 MT = 800 Q = 2.39902E+00 MeV Emin = 1.00000E-11 MeV : (n,alpha) to ground state + 41 MT = 801 Q = 1.56417E+00 MeV Emin = 1.00000E-11 MeV : (n,a1) + 42 MT = 802 Q = 5.75104E-01 MeV Emin = 1.06812E+00 MeV : (n,a2) + 43 MT = 803 Q = -2.20656E-01 MeV Emin = 1.91575E+00 MeV : (n,a3) + 44 MT = 804 Q = -4.30596E-01 MeV Emin = 2.00000E+00 MeV : (n,a4) + 45 MT = 805 Q = -6.75046E-01 MeV Emin = 2.00000E+00 MeV : (n,a5) + 46 MT = 806 Q = -7.60536E-01 MeV Emin = 2.00000E+00 MeV : (n,a6) + 47 MT = 807 Q = -8.23256E-01 MeV Emin = 2.00000E+00 MeV : (n,a7) + 48 MT = 808 Q = -9.94386E-01 MeV Emin = 2.20000E+00 MeV : (n,a8) + 49 MT = 809 Q = -1.03786E+00 MeV Emin = 2.20000E+00 MeV : (n,a9) + 50 MT = 810 Q = -1.06898E+00 MeV Emin = 2.20000E+00 MeV : (n,a10) + 51 MT = 849 Q = -1.06898E+00 MeV Emin = 3.00000E+00 MeV : (n,alpha) to continuum + 52 MT = 4 Q = 0.00000E+00 MeV Emin = 1.46227E-02 MeV : total inelastic scattering + + Nuclide 55 / 1657 : 26058.82c -- iron 58 (Fe-58) + + Pointers : 316293 24157 + Primary type : Transport + Nuclide ZAI : 260580 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Fe58.ACE + Atomic weight (AW) : 57.93329 + Atomic weight ratio (AWR) : 57.43561 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+02 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 34 reaction channels + - 48 special reactions + - 11 transmutation reactions + - 8 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 34 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 5 Q = 0.00000E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : anything + 3 MT = 16 Q = -1.00445E+01 MeV Emin = 1.02194E+01 MeV frac = 1.00000E+00 Product nuclide = 26057.82c : (n,2n) + 4 MT = 17 Q = -1.76905E+01 MeV Emin = 1.80000E+01 MeV frac = 1.00000E+00 Product nuclide = 26056.82c : (n,3n) + 5 MT = 22 Q = -7.64543E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 24054.82c : (n,nalpha) + 6 MT = 28 Q = -1.19530E+01 MeV Emin = 1.21611E+01 MeV frac = 1.00000E+00 Product nuclide = 250570 : (n,np) + 7 MT = 51 Q = -8.10784E-01 MeV Emin = 8.20858E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 8 MT = 52 Q = -1.67475E+00 MeV Emin = 1.70322E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 9 MT = 53 Q = -2.07654E+00 MeV Emin = 2.11269E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 10 MT = 54 Q = -2.13391E+00 MeV Emin = 2.17106E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 11 MT = 55 Q = -2.25796E+00 MeV Emin = 2.29727E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 12 MT = 56 Q = -2.60042E+00 MeV Emin = 2.64570E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 13 MT = 57 Q = -2.78214E+00 MeV Emin = 2.83058E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 14 MT = 58 Q = -2.86472E+00 MeV Emin = 2.91460E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 15 MT = 59 Q = -2.87646E+00 MeV Emin = 2.92654E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 16 MT = 60 Q = -2.96200E+00 MeV Emin = 3.01357E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 17 MT = 61 Q = -3.08371E+00 MeV Emin = 3.13740E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 18 MT = 62 Q = -3.13500E+00 MeV Emin = 3.18958E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 19 MT = 63 Q = -3.23328E+00 MeV Emin = 3.28958E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 20 MT = 64 Q = -3.24411E+00 MeV Emin = 3.30059E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 21 MT = 65 Q = -3.38300E+00 MeV Emin = 3.44190E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 22 MT = 66 Q = -3.44980E+00 MeV Emin = 3.50987E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 23 MT = 67 Q = -3.53799E+00 MeV Emin = 3.60000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 24 MT = 68 Q = -3.59690E+00 MeV Emin = 3.65953E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 25 MT = 69 Q = -3.62960E+00 MeV Emin = 3.69279E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 26 MT = 70 Q = -3.70300E+00 MeV Emin = 3.76747E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 27 MT = 91 Q = -3.70300E+00 MeV Emin = 3.76747E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 28 MT = 102 Q = 6.58090E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 260590 : (n,gamma) + 29 MT = 103 Q = -5.46424E+00 MeV Emin = 5.80000E+00 MeV frac = 1.00000E+00 Product nuclide = 250580 : (n,p) + 30 MT = 104 Q = -9.72839E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 250570 : (n,d) + 31 MT = 105 Q = -1.21218E+01 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 250560 : (n,t) + 32 MT = 106 Q = -1.37201E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 240560 : (n,He-3) + 33 MT = 107 Q = -1.39914E+00 MeV Emin = 2.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 240550 : (n,alpha) + 34 MT = 108 Q = -9.20049E+00 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 220510 : (n,2alpha) + + 8 additional transport branches: + + 1 MT = 22 Q = -7.64543E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.19530E+01 MeV Emin = 1.21611E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -5.46424E+00 MeV Emin = 5.80000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -9.72839E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -1.21218E+01 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 106 Q = -1.37201E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 7 MT = 107 Q = -1.39914E+00 MeV Emin = 2.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 8 MT = 108 Q = -9.20049E+00 MeV Emin = 1.40000E+01 MeV frac = 2.00000E+00 Product nuclide = 2004.82c : (n,2alpha) + + 48 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 5.80000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.00000E+01 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.25000E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.50000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 2.60000E+00 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 5.62500E-04 MeV : damage-energy production + 7 MT = 600 Q = -5.46424E+00 MeV Emin = 5.80000E+00 MeV : (n,p) to ground state + 8 MT = 601 Q = -5.53602E+00 MeV Emin = 5.80000E+00 MeV : (n,p1) + 9 MT = 602 Q = -5.62424E+00 MeV Emin = 6.00000E+00 MeV : (n,p2) + 10 MT = 603 Q = -5.71924E+00 MeV Emin = 6.00000E+00 MeV : (n,p3) + 11 MT = 604 Q = -5.82544E+00 MeV Emin = 6.20000E+00 MeV : (n,p4) + 12 MT = 605 Q = -5.91247E+00 MeV Emin = 6.20000E+00 MeV : (n,p5) + 13 MT = 606 Q = -5.99944E+00 MeV Emin = 6.40000E+00 MeV : (n,p6) + 14 MT = 607 Q = -6.19230E+00 MeV Emin = 6.40000E+00 MeV : (n,p7) + 15 MT = 608 Q = -6.21914E+00 MeV Emin = 6.60000E+00 MeV : (n,p8) + 16 MT = 609 Q = -6.28424E+00 MeV Emin = 6.60000E+00 MeV : (n,p9) + 17 MT = 610 Q = -6.34574E+00 MeV Emin = 6.60000E+00 MeV : (n,p10) + 18 MT = 649 Q = -6.34574E+00 MeV Emin = 6.60000E+00 MeV : (n,p) to continuum + 19 MT = 650 Q = -9.72839E+00 MeV Emin = 1.00000E+01 MeV : (n,d) to ground state + 20 MT = 651 Q = -9.81158E+00 MeV Emin = 1.00000E+01 MeV : (n,d1) + 21 MT = 652 Q = -1.05785E+01 MeV Emin = 1.07627E+01 MeV : (n,d2) + 22 MT = 653 Q = -1.07842E+01 MeV Emin = 1.10000E+01 MeV : (n,d3) + 23 MT = 654 Q = -1.08013E+01 MeV Emin = 1.10000E+01 MeV : (n,d4) + 24 MT = 655 Q = -1.09559E+01 MeV Emin = 1.15000E+01 MeV : (n,d5) + 25 MT = 699 Q = -1.09559E+01 MeV Emin = 1.15000E+01 MeV : (n,d) to continuum + 26 MT = 700 Q = -1.21218E+01 MeV Emin = 1.25000E+01 MeV : (n,t) to ground state + 27 MT = 701 Q = -1.21484E+01 MeV Emin = 1.25000E+01 MeV : (n,t1) + 28 MT = 702 Q = -1.22323E+01 MeV Emin = 1.25000E+01 MeV : (n,t2) + 29 MT = 703 Q = -1.23338E+01 MeV Emin = 1.25486E+01 MeV : (n,t3) + 30 MT = 704 Q = -1.23369E+01 MeV Emin = 1.25517E+01 MeV : (n,t4) + 31 MT = 705 Q = -1.24573E+01 MeV Emin = 1.30000E+01 MeV : (n,t5) + 32 MT = 749 Q = -1.24573E+01 MeV Emin = 1.30000E+01 MeV : (n,t) to continuum + 33 MT = 750 Q = -1.37201E+01 MeV Emin = 1.50000E+01 MeV : (n,He-3) to ground state + 34 MT = 751 Q = -1.47267E+01 MeV Emin = 1.50000E+01 MeV : (n,He-3_1) + 35 MT = 752 Q = -1.55517E+01 MeV Emin = 1.60000E+01 MeV : (n,He-3_2) + 36 MT = 800 Q = -1.39914E+00 MeV Emin = 2.60000E+00 MeV : (n,alpha) to ground state + 37 MT = 801 Q = -1.64105E+00 MeV Emin = 2.80000E+00 MeV : (n,a1) + 38 MT = 802 Q = -1.91684E+00 MeV Emin = 3.00000E+00 MeV : (n,a2) + 39 MT = 803 Q = -1.96505E+00 MeV Emin = 3.20000E+00 MeV : (n,a3) + 40 MT = 804 Q = -2.27985E+00 MeV Emin = 3.40000E+00 MeV : (n,a4) + 41 MT = 805 Q = -2.53014E+00 MeV Emin = 3.80000E+00 MeV : (n,a5) + 42 MT = 806 Q = -2.61389E+00 MeV Emin = 3.80000E+00 MeV : (n,a6) + 43 MT = 807 Q = -2.83795E+00 MeV Emin = 4.00000E+00 MeV : (n,a7) + 44 MT = 808 Q = -2.87334E+00 MeV Emin = 4.00000E+00 MeV : (n,a8) + 45 MT = 809 Q = -2.87817E+00 MeV Emin = 4.00000E+00 MeV : (n,a9) + 46 MT = 810 Q = -3.40714E+00 MeV Emin = 4.60000E+00 MeV : (n,a10) + 47 MT = 849 Q = -3.40714E+00 MeV Emin = 5.40000E+00 MeV : (n,alpha) to continuum + 48 MT = 4 Q = 0.00000E+00 MeV Emin = 8.20858E-01 MeV : total inelastic scattering + + Nuclide 56 / 1657 : 27059.82c -- cobalt 59 (Co-59) + + Pointers : 329547 22271 + Primary type : Transport + Nuclide ZAI : 270590 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Co59.ACE + Atomic weight (AW) : 58.93317 + Atomic weight ratio (AWR) : 58.42690 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 35 reaction channels + - 7 special reactions + - 14 transmutation reactions + - 14 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 35 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.04540E+01 MeV Emin = 1.06329E+01 MeV frac = 1.00000E+00 Product nuclide = 270580 : (n,2n) + 3 MT = 22 Q = -6.94200E+00 MeV Emin = 1.05000E+01 MeV frac = 1.00000E+00 Product nuclide = 25055.82c : (n,nalpha) + 4 MT = 28 Q = -7.36400E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 26058.82c : (n,np) + 5 MT = 32 Q = -1.51830E+01 MeV Emin = 1.67500E+01 MeV frac = 1.00000E+00 Product nuclide = 26057.82c : (n,nd) + 6 MT = 33 Q = -1.65730E+01 MeV Emin = 1.90000E+01 MeV frac = 1.00000E+00 Product nuclide = 26056.82c : (n,nt) + 7 MT = 51 Q = -1.09990E+00 MeV Emin = 1.11840E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 8 MT = 52 Q = -1.19030E+00 MeV Emin = 1.20980E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 9 MT = 53 Q = -1.29190E+00 MeV Emin = 1.31305E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 10 MT = 54 Q = -1.43400E+00 MeV Emin = 1.45814E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 11 MT = 55 Q = -1.45890E+00 MeV Emin = 1.48330E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 12 MT = 56 Q = -1.48150E+00 MeV Emin = 1.50644E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 13 MT = 57 Q = -1.74450E+00 MeV Emin = 1.77390E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 14 MT = 58 Q = -2.06130E+00 MeV Emin = 2.09658E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 15 MT = 59 Q = -2.08790E+00 MeV Emin = 2.12364E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 16 MT = 60 Q = -2.15280E+00 MeV Emin = 2.18965E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 17 MT = 61 Q = -2.18240E+00 MeV Emin = 2.21975E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 18 MT = 62 Q = -2.20500E+00 MeV Emin = 2.24280E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 19 MT = 63 Q = -2.39500E+00 MeV Emin = 2.43599E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 20 MT = 64 Q = -2.47830E+00 MeV Emin = 2.52072E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 21 MT = 65 Q = -2.54020E+00 MeV Emin = 2.58368E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 22 MT = 66 Q = -2.58420E+00 MeV Emin = 2.62843E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 23 MT = 67 Q = -2.71280E+00 MeV Emin = 2.75923E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 24 MT = 68 Q = -2.78070E+00 MeV Emin = 2.82829E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 25 MT = 69 Q = -2.82520E+00 MeV Emin = 2.87356E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 26 MT = 91 Q = -2.95000E+00 MeV Emin = 3.00049E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 27 MT = 102 Q = 7.49000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 270600 : (n,gamma) + 28 MT = 103 Q = -7.82000E-01 MeV Emin = 1.49900E+00 MeV frac = 1.00000E+00 Product nuclide = 260590 : (n,p) + 29 MT = 104 Q = -5.13900E+00 MeV Emin = 5.22696E+00 MeV frac = 1.00000E+00 Product nuclide = 26058.82c : (n,d) + 30 MT = 105 Q = -8.92700E+00 MeV Emin = 9.07979E+00 MeV frac = 1.00000E+00 Product nuclide = 26057.82c : (n,t) + 31 MT = 106 Q = -1.16000E+01 MeV Emin = 1.17986E+01 MeV frac = 1.00000E+00 Product nuclide = 250570 : (n,He-3) + 32 MT = 107 Q = 3.29000E-01 MeV Emin = 3.90000E+00 MeV frac = 1.00000E+00 Product nuclide = 250560 : (n,alpha) + 33 MT = 108 Q = -7.56600E+00 MeV Emin = 1.82500E+01 MeV frac = 1.00000E+00 Product nuclide = 230520 : (n,2alpha) + 34 MT = 111 Q = -1.29040E+01 MeV Emin = 1.65000E+01 MeV frac = 1.00000E+00 Product nuclide = 250580 : (n,2p) + 35 MT = 112 Q = -8.76400E+00 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 240550 : (n,palpha) + + 14 additional transport branches: + + 1 MT = 22 Q = -6.94200E+00 MeV Emin = 1.05000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -7.36400E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.51830E+01 MeV Emin = 1.67500E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.65730E+01 MeV Emin = 1.90000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 102 Q = 7.49000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 270601 : (n,gamma) + 6 MT = 103 Q = -7.82000E-01 MeV Emin = 1.49900E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 7 MT = 104 Q = -5.13900E+00 MeV Emin = 5.22696E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 8 MT = 105 Q = -8.92700E+00 MeV Emin = 9.07979E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 9 MT = 106 Q = -1.16000E+01 MeV Emin = 1.17986E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 10 MT = 107 Q = 3.29000E-01 MeV Emin = 3.90000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 11 MT = 108 Q = -7.56600E+00 MeV Emin = 1.82500E+01 MeV frac = 2.00000E+00 Product nuclide = 2004.82c : (n,2alpha) + 12 MT = 111 Q = -1.29040E+01 MeV Emin = 1.65000E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + 13 MT = 112 Q = -8.76400E+00 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,palpha) + 14 MT = 112 Q = -8.76400E+00 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,palpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.49900E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.22696E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.07979E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.17986E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 3.90000E+00 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 1.11840E+00 MeV : total inelastic scattering + + Nuclide 57 / 1657 : 28058.82c -- nickel 58 (Ni-58) + + Pointers : 341784 28849 + Primary type : Transport + Nuclide ZAI : 280580 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ni58.ACE + Atomic weight (AW) : 57.93570 + Atomic weight ratio (AWR) : 57.43800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.21E+28 seconds (7E+20 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 20 reaction channels + - 7 special reactions + - 10 transmutation reactions + - 9 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 20 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.22000E+01 MeV Emin = 1.24124E+01 MeV frac = 1.00000E+00 Product nuclide = 280570 : (n,2n) + 3 MT = 22 Q = -6.39800E+00 MeV Emin = 6.50940E+00 MeV frac = 1.00000E+00 Product nuclide = 26054.82c : (n,nalpha) + 4 MT = 28 Q = -8.17100E+00 MeV Emin = 9.23610E+00 MeV frac = 1.00000E+00 Product nuclide = 270570 : (n,np) + 5 MT = 51 Q = -1.45400E+00 MeV Emin = 1.47886E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -2.45900E+00 MeV Emin = 2.50280E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -2.77600E+00 MeV Emin = 2.82840E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -2.90300E+00 MeV Emin = 2.95354E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -2.94300E+00 MeV Emin = 2.99424E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -3.03800E+00 MeV Emin = 3.09090E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -3.26500E+00 MeV Emin = 3.32185E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -3.42100E+00 MeV Emin = 3.48056E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 91 Q = -3.52000E+00 MeV Emin = 3.58540E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 14 MT = 102 Q = 9.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 28059.82c : (n,gamma) + 15 MT = 103 Q = 4.00820E-01 MeV Emin = 3.99858E-01 MeV frac = 1.00000E+00 Product nuclide = 270580 : (n,p) + 16 MT = 104 Q = -5.94630E+00 MeV Emin = 6.04983E+00 MeV frac = 1.00000E+00 Product nuclide = 270570 : (n,d) + 17 MT = 105 Q = -1.10620E+01 MeV Emin = 1.35000E+01 MeV frac = 1.00000E+00 Product nuclide = 270560 : (n,t) + 18 MT = 106 Q = -6.47790E+00 MeV Emin = 1.80000E+01 MeV frac = 1.00000E+00 Product nuclide = 26056.82c : (n,He-3) + 19 MT = 107 Q = 2.90100E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 260550 : (n,alpha) + 20 MT = 112 Q = -6.31340E+00 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 250540 : (n,palpha) + + 9 additional transport branches: + + 1 MT = 22 Q = -6.39800E+00 MeV Emin = 6.50940E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -8.17100E+00 MeV Emin = 9.23610E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = 4.00820E-01 MeV Emin = 3.99858E-01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -5.94630E+00 MeV Emin = 6.04983E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -1.10620E+01 MeV Emin = 1.35000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 106 Q = -6.47790E+00 MeV Emin = 1.80000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 7 MT = 107 Q = 2.90100E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 8 MT = 112 Q = -6.31340E+00 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,palpha) + 9 MT = 112 Q = -6.31340E+00 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,palpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.99858E-01 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.04983E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.35000E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.79543E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 1.47886E+00 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 22 Q = 1.92570E+00 MeV frac = 1.00000E+00 Product nuclide = 26058.82c : EC/beta+ + EC/beta+ + + Nuclide 58 / 1657 : 28059.82c -- nickel 59 (Ni-59) + + Pointers : 344596 28895 + Primary type : Transport + Nuclide ZAI : 280590 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ni59.ACE + Atomic weight (AW) : 58.93438 + Atomic weight ratio (AWR) : 58.42810 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.40E+12 seconds (76,051 years) + Specific ingestion toxicity : 6.30E-11 Sv/Bq + Specific inhalation toxicity : 4.40E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 13 reaction channels + - 7 special reactions + - 12 transmutation reactions + - 10 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 13 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.99720E+00 MeV Emin = 9.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 28058.82c : (n,2n) + 3 MT = 22 Q = -6.09740E+00 MeV Emin = 6.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 260550 : (n,nalpha) + 4 MT = 28 Q = -8.59500E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 270580 : (n,np) + 5 MT = 32 Q = -1.49410E+01 MeV Emin = 1.55000E+01 MeV frac = 1.00000E+00 Product nuclide = 270570 : (n,nd) + 6 MT = 34 Q = -1.54750E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 26056.82c : (n,nHe-3) + 7 MT = 102 Q = 1.12400E+01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 28060.82c : (n,gamma) + 8 MT = 103 Q = 1.58400E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 27059.82c : (n,p) + 9 MT = 104 Q = -6.37090E+00 MeV Emin = 6.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 270580 : (n,d) + 10 MT = 105 Q = -8.68560E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 270570 : (n,t) + 11 MT = 106 Q = -7.83110E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 26057.82c : (n,He-3) + 12 MT = 107 Q = 4.87800E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 26056.82c : (n,alpha) + 13 MT = 111 Q = -5.50560E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 26058.82c : (n,2p) + + 10 additional transport branches: + + 1 MT = 22 Q = -6.09740E+00 MeV Emin = 6.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -8.59500E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.49410E+01 MeV Emin = 1.55000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 34 Q = -1.54750E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,nHe-3) + 5 MT = 103 Q = 1.58400E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 104 Q = -6.37090E+00 MeV Emin = 6.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 7 MT = 105 Q = -8.68560E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 8 MT = 106 Q = -7.83110E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 9 MT = 107 Q = 4.87800E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 10 MT = 111 Q = -5.50560E+00 MeV Emin = 6.00000E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.50000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.00000E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 8.00000E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 3 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : nonelastic + + 1 decay reaction: + + 1 RTYP = 2 Q = 1.07276E+00 MeV frac = 1.00000E+00 Product nuclide = 27059.82c : EC/beta+ + + Nuclide 59 / 1657 : 28060.82c -- nickel 60 (Ni-60) + + Pointers : 347101 28941 + Primary type : Transport + Nuclide ZAI : 280600 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ni60.ACE + Atomic weight (AW) : 59.93079 + Atomic weight ratio (AWR) : 59.41595 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 22 reaction channels + - 7 special reactions + - 9 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 22 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.13850E+01 MeV Emin = 1.16960E+01 MeV frac = 1.00000E+00 Product nuclide = 28059.82c : (n,2n) + 3 MT = 22 Q = -6.29100E+00 MeV Emin = 6.39690E+00 MeV frac = 1.00000E+00 Product nuclide = 26056.82c : (n,nalpha) + 4 MT = 28 Q = -9.52960E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 27059.82c : (n,np) + 5 MT = 51 Q = -1.33300E+00 MeV Emin = 1.35515E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -2.15900E+00 MeV Emin = 2.19540E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -2.28500E+00 MeV Emin = 2.32350E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -2.50600E+00 MeV Emin = 2.54820E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -2.62600E+00 MeV Emin = 2.67020E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -3.12000E+00 MeV Emin = 3.17251E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -3.12400E+00 MeV Emin = 3.17660E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -3.18600E+00 MeV Emin = 3.23962E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -3.19400E+00 MeV Emin = 3.24780E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -3.27000E+00 MeV Emin = 3.32504E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -3.31800E+00 MeV Emin = 3.37385E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 91 Q = -3.33900E+00 MeV Emin = 3.39520E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 17 MT = 102 Q = 7.82000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 28061.82c : (n,gamma) + 18 MT = 103 Q = -2.04150E+00 MeV Emin = 2.20000E+00 MeV frac = 1.00000E+00 Product nuclide = 270600 : (n,p) + 19 MT = 104 Q = -7.30830E+00 MeV Emin = 7.43130E+00 MeV frac = 1.00000E+00 Product nuclide = 27059.82c : (n,d) + 20 MT = 105 Q = -1.15010E+01 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 270580 : (n,t) + 21 MT = 106 Q = -9.17420E+00 MeV Emin = 9.32861E+00 MeV frac = 1.00000E+00 Product nuclide = 26058.82c : (n,He-3) + 22 MT = 107 Q = 1.35530E+00 MeV Emin = 2.55250E+00 MeV frac = 1.00000E+00 Product nuclide = 26057.82c : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -6.29100E+00 MeV Emin = 6.39690E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -9.52960E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -2.04150E+00 MeV Emin = 2.20000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -7.30830E+00 MeV Emin = 7.43130E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -1.15010E+01 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 106 Q = -9.17420E+00 MeV Emin = 9.32861E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 7 MT = 107 Q = 1.35530E+00 MeV Emin = 2.55250E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.20000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.43130E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.39914E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 9.32861E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 2.55240E+00 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 1.35515E+00 MeV : total inelastic scattering + + Nuclide 60 / 1657 : 28061.82c -- nickel 61 (Ni-61) + + Pointers : 349840 28987 + Primary type : Transport + Nuclide ZAI : 280610 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ni61.ACE + Atomic weight (AW) : 60.93143 + Atomic weight ratio (AWR) : 60.40800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 1.50000E+02 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 17 reaction channels + - 6 special reactions + - 6 transmutation reactions + - 4 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 17 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 5 Q = 0.00000E+00 MeV Emin = 2.00000E+01 MeV frac = 1.00000E+00 Product nuclide = self : anything + 3 MT = 16 Q = -7.82030E+00 MeV Emin = 7.94980E+00 MeV frac = 1.00000E+00 Product nuclide = 28060.82c : (n,2n) + 4 MT = 28 Q = -9.86200E+00 MeV Emin = 1.00253E+01 MeV frac = 1.00000E+00 Product nuclide = 270600 : (n,np) + 5 MT = 51 Q = -6.70000E-02 MeV Emin = 6.98727E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -2.83000E-01 MeV Emin = 2.85000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -6.56000E-01 MeV Emin = 6.66610E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -9.09000E-01 MeV Emin = 9.23622E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -1.01500E+00 MeV Emin = 1.03120E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -1.10000E+00 MeV Emin = 1.11788E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -1.13200E+00 MeV Emin = 1.15041E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -1.18500E+00 MeV Emin = 1.20422E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 91 Q = -1.45500E+00 MeV Emin = 1.47871E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 14 MT = 102 Q = 1.05973E+01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 28062.82c : (n,gamma) + 15 MT = 103 Q = -5.39700E-01 MeV Emin = 5.25000E-01 MeV frac = 1.00000E+00 Product nuclide = 270610 : (n,p) + 16 MT = 107 Q = 3.57900E+00 MeV Emin = 6.99363E-02 MeV frac = 1.00000E+00 Product nuclide = 26058.82c : (n,alpha) + 17 MT = 111 Q = -9.28870E+00 MeV Emin = 9.44250E+00 MeV frac = 1.00000E+00 Product nuclide = 260600 : (n,2p) + + 4 additional transport branches: + + 1 MT = 28 Q = -9.86200E+00 MeV Emin = 1.00253E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 2 MT = 103 Q = -5.39700E-01 MeV Emin = 5.25000E-01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 107 Q = 3.57900E+00 MeV Emin = 6.99363E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 4 MT = 111 Q = -9.28870E+00 MeV Emin = 9.44250E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 5.25000E-01 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 2.00000E+01 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 2.00000E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 6.99363E-02 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 6.98727E-02 MeV : total inelastic scattering + + Nuclide 61 / 1657 : 28062.82c -- nickel 62 (Ni-62) + + Pointers : 351922 29033 + Primary type : Transport + Nuclide ZAI : 280620 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ni62.ACE + Atomic weight (AW) : 61.92799 + Atomic weight ratio (AWR) : 61.39600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 1.50000E+02 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 14 reaction channels + - 6 special reactions + - 7 transmutation reactions + - 5 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 14 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 5 Q = 0.00000E+00 MeV Emin = 2.00000E+01 MeV frac = 1.00000E+00 Product nuclide = self : anything + 3 MT = 16 Q = -1.05980E+01 MeV Emin = 1.07710E+01 MeV frac = 1.00000E+00 Product nuclide = 28061.82c : (n,2n) + 4 MT = 22 Q = -7.01860E+00 MeV Emin = 7.13292E+00 MeV frac = 1.00000E+00 Product nuclide = 26058.82c : (n,nalpha) + 5 MT = 28 Q = -1.11380E+01 MeV Emin = 1.13194E+01 MeV frac = 1.00000E+00 Product nuclide = 270610 : (n,np) + 6 MT = 51 Q = -1.17300E+00 MeV Emin = 1.19168E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -2.04900E+00 MeV Emin = 2.08240E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -2.30200E+00 MeV Emin = 2.33950E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -2.33600E+00 MeV Emin = 2.37405E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 91 Q = -2.89100E+00 MeV Emin = 2.93810E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 11 MT = 102 Q = 6.83791E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 280630 : (n,gamma) + 12 MT = 103 Q = -4.45900E+00 MeV Emin = 4.53163E+00 MeV frac = 1.00000E+00 Product nuclide = 270620 : (n,p) + 13 MT = 104 Q = -8.91287E+00 MeV Emin = 9.05804E+00 MeV frac = 1.00000E+00 Product nuclide = 270610 : (n,d) + 14 MT = 107 Q = -4.37400E-01 MeV Emin = 4.44358E-01 MeV frac = 1.00000E+00 Product nuclide = 260590 : (n,alpha) + + 5 additional transport branches: + + 1 MT = 22 Q = -7.01860E+00 MeV Emin = 7.13292E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.11380E+01 MeV Emin = 1.13194E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -4.45900E+00 MeV Emin = 4.53163E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -8.91287E+00 MeV Emin = 9.05804E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 107 Q = -4.37400E-01 MeV Emin = 4.44358E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.53163E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 9.05804E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 2.00000E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 4.44358E-01 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 1.19168E+00 MeV : total inelastic scattering + + Nuclide 62 / 1657 : 28064.82c -- nickel 64 (Ni-64) + + Pointers : 354075 29079 + Primary type : Transport + Nuclide ZAI : 280640 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ni64.ACE + Atomic weight (AW) : 63.92818 + Atomic weight ratio (AWR) : 63.37900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 1.50000E+02 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 12 reaction channels + - 6 special reactions + - 7 transmutation reactions + - 5 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 12 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 5 Q = 0.00000E+00 MeV Emin = 2.00000E+01 MeV frac = 1.00000E+00 Product nuclide = self : anything + 3 MT = 16 Q = -9.65700E+00 MeV Emin = 9.80940E+00 MeV frac = 1.00000E+00 Product nuclide = 280630 : (n,2n) + 4 MT = 22 Q = -8.08200E+00 MeV Emin = 8.20952E+00 MeV frac = 1.00000E+00 Product nuclide = 260600 : (n,nalpha) + 5 MT = 28 Q = -1.25360E+01 MeV Emin = 1.27340E+01 MeV frac = 1.00000E+00 Product nuclide = 270630 : (n,np) + 6 MT = 51 Q = -1.34600E+00 MeV Emin = 1.36647E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -2.27700E+00 MeV Emin = 2.31293E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 91 Q = -2.60800E+00 MeV Emin = 2.64915E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 9 MT = 102 Q = 6.09806E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 280650 : (n,gamma) + 10 MT = 103 Q = -6.52400E+00 MeV Emin = 6.62694E+00 MeV frac = 1.00000E+00 Product nuclide = 270640 : (n,p) + 11 MT = 104 Q = -1.03114E+01 MeV Emin = 1.04741E+01 MeV frac = 1.00000E+00 Product nuclide = 270630 : (n,d) + 12 MT = 107 Q = -2.44200E+00 MeV Emin = 2.48053E+00 MeV frac = 1.00000E+00 Product nuclide = 260610 : (n,alpha) + + 5 additional transport branches: + + 1 MT = 22 Q = -8.08200E+00 MeV Emin = 8.20952E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.25360E+01 MeV Emin = 1.27340E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -6.52400E+00 MeV Emin = 6.62694E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -1.03114E+01 MeV Emin = 1.04741E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 107 Q = -2.44200E+00 MeV Emin = 2.48053E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 6.62694E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.04741E+01 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 2.00000E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 2.48053E+00 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 1.36647E+00 MeV : total inelastic scattering + + Nuclide 63 / 1657 : 29065.82c -- copper 65 (Cu-65) + + Pointers : 360503 22777 + Primary type : Transport + Nuclide ZAI : 290650 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Cu65.ACE + Atomic weight (AW) : 64.92776 + Atomic weight ratio (AWR) : 64.37000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 1.50000E+02 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 25 reaction channels + - 7 special reactions + - 9 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 25 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 5 Q = 0.00000E+00 MeV Emin = 2.00000E+01 MeV frac = 1.00000E+00 Product nuclide = self : anything + 3 MT = 16 Q = -9.91000E+00 MeV Emin = 1.00640E+01 MeV frac = 1.00000E+00 Product nuclide = 290640 : (n,2n) + 4 MT = 22 Q = -6.79000E+00 MeV Emin = 6.89550E+00 MeV frac = 1.00000E+00 Product nuclide = 270610 : (n,nalpha) + 5 MT = 28 Q = -7.45000E+00 MeV Emin = 7.56574E+00 MeV frac = 1.00000E+00 Product nuclide = 28064.82c : (n,np) + 6 MT = 51 Q = -7.71000E-01 MeV Emin = 7.82600E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.11600E+00 MeV Emin = 1.13262E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -1.48200E+00 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -1.62300E+00 MeV Emin = 1.64101E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -1.72500E+00 MeV Emin = 1.75000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -2.09400E+00 MeV Emin = 2.12653E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -2.10800E+00 MeV Emin = 2.14075E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -2.21300E+00 MeV Emin = 2.24740E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -2.27800E+00 MeV Emin = 2.31340E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -2.32700E+00 MeV Emin = 2.36320E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -2.40700E+00 MeV Emin = 2.44440E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -2.53300E+00 MeV Emin = 2.57240E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -2.53400E+00 MeV Emin = 2.57340E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 91 Q = -2.59400E+00 MeV Emin = 2.63430E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 20 MT = 102 Q = 7.06599E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 290660 : (n,gamma) + 21 MT = 103 Q = -1.35400E+00 MeV Emin = 1.37254E+00 MeV frac = 1.00000E+00 Product nuclide = 280650 : (n,p) + 22 MT = 104 Q = -5.22800E+00 MeV Emin = 5.30922E+00 MeV frac = 1.00000E+00 Product nuclide = 28064.82c : (n,d) + 23 MT = 105 Q = -8.62200E+00 MeV Emin = 8.75595E+00 MeV frac = 1.00000E+00 Product nuclide = 280630 : (n,t) + 24 MT = 106 Q = -1.22710E+01 MeV Emin = 1.24620E+01 MeV frac = 1.00000E+00 Product nuclide = 270630 : (n,He-3) + 25 MT = 107 Q = -1.10000E-01 MeV Emin = 1.11699E-01 MeV frac = 1.00000E+00 Product nuclide = 270620 : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -6.79000E+00 MeV Emin = 6.89550E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -7.45000E+00 MeV Emin = 7.56574E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -1.35400E+00 MeV Emin = 1.37254E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -5.22800E+00 MeV Emin = 5.30922E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -8.62200E+00 MeV Emin = 8.75595E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 106 Q = -1.22710E+01 MeV Emin = 1.24620E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 7 MT = 107 Q = -1.10000E-01 MeV Emin = 1.11699E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.37254E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.30922E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 8.75595E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.24620E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.11699E-01 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 7.82600E-01 MeV : total inelastic scattering + + Nuclide 64 / 1657 : 32070.82c -- germanium 70 (Ge-70) + + Pointers : 400688 24617 + Primary type : Transport + Nuclide ZAI : 320700 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ge70.ACE + Atomic weight (AW) : 69.92426 + Atomic weight ratio (AWR) : 69.32357 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+02 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 42 reaction channels + - 52 special reactions + - 19 transmutation reactions + - 21 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 42 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 5 Q = 0.00000E+00 MeV Emin = 1.49811E-02 MeV frac = 1.00000E+00 Product nuclide = self : anything + 3 MT = 16 Q = -1.15380E+01 MeV Emin = 1.17044E+01 MeV frac = 1.00000E+00 Product nuclide = 320690 : (n,2n) + 4 MT = 22 Q = -4.08893E+00 MeV Emin = 5.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 300660 : (n,nalpha) + 5 MT = 24 Q = -1.51488E+01 MeV Emin = 1.70000E+01 MeV frac = 1.00000E+00 Product nuclide = 300650 : (n,2nalpha) + 6 MT = 28 Q = -8.52837E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 310690 : (n,np) + 7 MT = 29 Q = -8.66746E+00 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 28062.82c : (n,n2alpha) + 8 MT = 32 Q = -1.66131E+01 MeV Emin = 1.70000E+01 MeV frac = 1.00000E+00 Product nuclide = 310680 : (n,nd) + 9 MT = 44 Q = -1.51342E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 300680 : (n,n2p) + 10 MT = 45 Q = -1.30145E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 29065.82c : (n,npalpha) + 11 MT = 51 Q = -1.03925E+00 MeV Emin = 1.02712E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 12 MT = 52 Q = -1.21541E+00 MeV Emin = 1.20000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 13 MT = 53 Q = -1.70790E+00 MeV Emin = 1.73125E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 14 MT = 54 Q = -2.15350E+00 MeV Emin = 2.18457E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 15 MT = 55 Q = -2.15740E+00 MeV Emin = 2.18852E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 16 MT = 56 Q = -2.30690E+00 MeV Emin = 2.34018E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 17 MT = 57 Q = -2.45150E+00 MeV Emin = 2.48686E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 18 MT = 58 Q = -2.53570E+00 MeV Emin = 2.57228E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 19 MT = 59 Q = -2.56140E+00 MeV Emin = 2.59835E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 20 MT = 60 Q = -2.80670E+00 MeV Emin = 2.84719E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 21 MT = 61 Q = -2.88780E+00 MeV Emin = 2.92946E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 22 MT = 62 Q = -2.94520E+00 MeV Emin = 2.98769E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 23 MT = 63 Q = -3.04680E+00 MeV Emin = 3.09075E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 24 MT = 64 Q = -3.05890E+00 MeV Emin = 3.10303E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 25 MT = 65 Q = -3.10700E+00 MeV Emin = 3.15182E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 26 MT = 66 Q = -3.18040E+00 MeV Emin = 3.22628E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 27 MT = 67 Q = -3.19420E+00 MeV Emin = 3.24028E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 28 MT = 68 Q = -3.24200E+00 MeV Emin = 3.28877E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 29 MT = 69 Q = -3.29610E+00 MeV Emin = 3.34365E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 30 MT = 70 Q = -3.29730E+00 MeV Emin = 3.34486E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 31 MT = 91 Q = -3.29730E+00 MeV Emin = 3.34486E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 32 MT = 102 Q = 7.41590E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 320710 : (n,gamma) + 33 MT = 103 Q = -8.73261E-01 MeV Emin = 1.20000E+00 MeV frac = 1.00000E+00 Product nuclide = 310700 : (n,p) + 34 MT = 104 Q = -6.30379E+00 MeV Emin = 6.80000E+00 MeV frac = 1.00000E+00 Product nuclide = 310690 : (n,d) + 35 MT = 105 Q = -1.03559E+01 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 310680 : (n,t) + 36 MT = 106 Q = -7.41617E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 300680 : (n,He-3) + 37 MT = 107 Q = 2.96325E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 300670 : (n,alpha) + 38 MT = 108 Q = -1.82960E+00 MeV Emin = 7.40000E+00 MeV frac = 1.00000E+00 Product nuclide = 280630 : (n,2alpha) + 39 MT = 111 Q = -8.65201E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 300690 : (n,2p) + 40 MT = 112 Q = -5.94855E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 290660 : (n,palpha) + 41 MT = 115 Q = -1.29097E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 300680 : (n,pd) + 42 MT = 117 Q = -1.07899E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 29065.82c : (n,dalpha) + + 21 additional transport branches: + + 1 MT = 22 Q = -4.08893E+00 MeV Emin = 5.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 24 Q = -1.51488E+01 MeV Emin = 1.70000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,2nalpha) + 3 MT = 28 Q = -8.52837E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 4 MT = 29 Q = -8.66746E+00 MeV Emin = 1.40000E+01 MeV frac = 2.00000E+00 Product nuclide = 2004.82c : (n,n2alpha) + 5 MT = 32 Q = -1.66131E+01 MeV Emin = 1.70000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 6 MT = 44 Q = -1.51342E+01 MeV Emin = 1.60000E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,n2p) + 7 MT = 45 Q = -1.30145E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,npalpha) + 8 MT = 45 Q = -1.30145E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,npalpha) + 9 MT = 103 Q = -8.73261E-01 MeV Emin = 1.20000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 10 MT = 104 Q = -6.30379E+00 MeV Emin = 6.80000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 11 MT = 105 Q = -1.03559E+01 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 12 MT = 106 Q = -7.41617E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 13 MT = 107 Q = 2.96325E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 14 MT = 108 Q = -1.82960E+00 MeV Emin = 7.40000E+00 MeV frac = 2.00000E+00 Product nuclide = 2004.82c : (n,2alpha) + 15 MT = 111 Q = -8.65201E+00 MeV Emin = 1.00000E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + 16 MT = 112 Q = -5.94855E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,palpha) + 17 MT = 112 Q = -5.94855E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,palpha) + 18 MT = 115 Q = -1.29097E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,pd) + 19 MT = 115 Q = -1.29097E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,pd) + 20 MT = 117 Q = -1.07899E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,dalpha) + 21 MT = 117 Q = -1.07899E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,dalpha) + + 52 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.20000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.80000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.10000E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 9.00000E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 600 Q = -8.73261E-01 MeV Emin = 1.20000E+00 MeV : (n,p) to ground state + 8 MT = 601 Q = -1.38146E+00 MeV Emin = 1.77500E+00 MeV : (n,p1) + 9 MT = 602 Q = -1.52436E+00 MeV Emin = 1.80113E+00 MeV : (n,p2) + 10 MT = 603 Q = -1.56416E+00 MeV Emin = 1.81420E+00 MeV : (n,p3) + 11 MT = 604 Q = -1.75236E+00 MeV Emin = 2.00000E+00 MeV : (n,p4) + 12 MT = 605 Q = -1.77466E+00 MeV Emin = 2.20000E+00 MeV : (n,p5) + 13 MT = 606 Q = -1.86876E+00 MeV Emin = 2.20000E+00 MeV : (n,p6) + 14 MT = 607 Q = -1.87586E+00 MeV Emin = 2.20000E+00 MeV : (n,p7) + 15 MT = 608 Q = -1.88246E+00 MeV Emin = 2.20000E+00 MeV : (n,p8) + 16 MT = 609 Q = -1.88266E+00 MeV Emin = 2.20000E+00 MeV : (n,p9) + 17 MT = 610 Q = -1.88816E+00 MeV Emin = 2.20000E+00 MeV : (n,p10) + 18 MT = 649 Q = -1.88816E+00 MeV Emin = 2.20000E+00 MeV : (n,p) to continuum + 19 MT = 650 Q = -6.30379E+00 MeV Emin = 6.80000E+00 MeV : (n,d) to ground state + 20 MT = 651 Q = -6.62248E+00 MeV Emin = 7.00000E+00 MeV : (n,d1) + 21 MT = 652 Q = -6.87800E+00 MeV Emin = 7.40000E+00 MeV : (n,d2) + 22 MT = 653 Q = -7.17592E+00 MeV Emin = 7.60000E+00 MeV : (n,d3) + 23 MT = 654 Q = -7.33237E+00 MeV Emin = 7.80000E+00 MeV : (n,d4) + 24 MT = 655 Q = -7.41082E+00 MeV Emin = 8.00000E+00 MeV : (n,d5) + 25 MT = 699 Q = -7.41082E+00 MeV Emin = 8.00000E+00 MeV : (n,d) to continuum + 26 MT = 700 Q = -1.03559E+01 MeV Emin = 1.10000E+01 MeV : (n,t) to ground state + 27 MT = 701 Q = -1.05309E+01 MeV Emin = 1.10000E+01 MeV : (n,t1) + 28 MT = 702 Q = -1.06768E+01 MeV Emin = 1.10000E+01 MeV : (n,t2) + 29 MT = 703 Q = -1.07304E+01 MeV Emin = 1.15000E+01 MeV : (n,t3) + 30 MT = 704 Q = -1.07314E+01 MeV Emin = 1.15000E+01 MeV : (n,t4) + 31 MT = 705 Q = -1.08520E+01 MeV Emin = 1.15000E+01 MeV : (n,t5) + 32 MT = 749 Q = -1.08520E+01 MeV Emin = 1.15000E+01 MeV : (n,t) to continuum + 33 MT = 750 Q = -7.41617E+00 MeV Emin = 9.00000E+00 MeV : (n,He-3) to ground state + 34 MT = 751 Q = -8.49354E+00 MeV Emin = 9.50000E+00 MeV : (n,He-3_1) + 35 MT = 752 Q = -9.07211E+00 MeV Emin = 1.05000E+01 MeV : (n,He-3_2) + 36 MT = 753 Q = -9.29931E+00 MeV Emin = 1.10000E+01 MeV : (n,He-3_3) + 37 MT = 754 Q = -9.75446E+00 MeV Emin = 1.15000E+01 MeV : (n,He-3_4) + 38 MT = 755 Q = -9.78647E+00 MeV Emin = 1.15000E+01 MeV : (n,He-3_5) + 39 MT = 799 Q = -9.78647E+00 MeV Emin = 1.20000E+01 MeV : (n,He-3) to continuum + 40 MT = 800 Q = 2.96325E+00 MeV Emin = 1.00000E-11 MeV : (n,alpha) to ground state + 41 MT = 801 Q = 2.86994E+00 MeV Emin = 1.00000E-11 MeV : (n,a1) + 42 MT = 802 Q = 2.77867E+00 MeV Emin = 1.00000E-11 MeV : (n,a2) + 43 MT = 803 Q = 2.56972E+00 MeV Emin = 1.00000E-11 MeV : (n,a3) + 44 MT = 804 Q = 2.35876E+00 MeV Emin = 1.00000E-11 MeV : (n,a4) + 45 MT = 805 Q = 2.14848E+00 MeV Emin = 1.00000E-11 MeV : (n,a5) + 46 MT = 806 Q = 2.09234E+00 MeV Emin = 1.00000E-11 MeV : (n,a6) + 47 MT = 807 Q = 2.07555E+00 MeV Emin = 1.00000E-11 MeV : (n,a7) + 48 MT = 808 Q = 1.98341E+00 MeV Emin = 1.00000E-11 MeV : (n,a8) + 49 MT = 809 Q = 1.97325E+00 MeV Emin = 1.00000E-11 MeV : (n,a9) + 50 MT = 810 Q = 1.90325E+00 MeV Emin = 1.00000E-11 MeV : (n,a10) + 51 MT = 849 Q = 1.90325E+00 MeV Emin = 1.00000E-11 MeV : (n,alpha) to continuum + 52 MT = 4 Q = 0.00000E+00 MeV Emin = 1.02712E+00 MeV : total inelastic scattering + + Nuclide 65 / 1657 : 32072.82c -- germanium 72 (Ge-72) + + Pointers : 409936 24663 + Primary type : Transport + Nuclide ZAI : 320720 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ge72.ACE + Atomic weight (AW) : 71.92209 + Atomic weight ratio (AWR) : 71.30424 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+02 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 38 reaction channels + - 52 special reactions + - 15 transmutation reactions + - 14 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 38 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 5 Q = 0.00000E+00 MeV Emin = 3.99702E-02 MeV frac = 1.00000E+00 Product nuclide = self : anything + 3 MT = 16 Q = -1.07520E+01 MeV Emin = 1.09028E+01 MeV frac = 1.00000E+00 Product nuclide = 320710 : (n,2n) + 4 MT = 17 Q = -1.81679E+01 MeV Emin = 1.84227E+01 MeV frac = 1.00000E+00 Product nuclide = 32070.82c : (n,3n) + 5 MT = 22 Q = -5.00644E+00 MeV Emin = 6.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 300680 : (n,nalpha) + 6 MT = 24 Q = -1.52046E+01 MeV Emin = 1.70000E+01 MeV frac = 1.00000E+00 Product nuclide = 300670 : (n,2nalpha) + 7 MT = 28 Q = -9.73771E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 310710 : (n,np) + 8 MT = 32 Q = -1.68166E+01 MeV Emin = 1.70525E+01 MeV frac = 1.00000E+00 Product nuclide = 310700 : (n,nd) + 9 MT = 51 Q = -6.91430E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 10 MT = 52 Q = -8.34011E-01 MeV Emin = 8.43750E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 11 MT = 53 Q = -1.46399E+00 MeV Emin = 1.45811E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 12 MT = 54 Q = -1.72830E+00 MeV Emin = 1.73612E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 13 MT = 55 Q = -2.02900E+00 MeV Emin = 2.05746E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 14 MT = 56 Q = -2.04900E+00 MeV Emin = 2.07774E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 15 MT = 57 Q = -2.06493E+00 MeV Emin = 2.09389E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 16 MT = 58 Q = -2.39610E+00 MeV Emin = 2.42970E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 17 MT = 59 Q = -2.40230E+00 MeV Emin = 2.43599E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 18 MT = 60 Q = -2.46390E+00 MeV Emin = 2.49846E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 19 MT = 61 Q = -2.50500E+00 MeV Emin = 2.54013E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 20 MT = 62 Q = -2.51479E+00 MeV Emin = 2.55006E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 21 MT = 63 Q = -2.57200E+00 MeV Emin = 2.60807E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 22 MT = 64 Q = -2.58350E+00 MeV Emin = 2.61973E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 23 MT = 65 Q = -2.75426E+00 MeV Emin = 2.79289E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 24 MT = 66 Q = -2.77211E+00 MeV Emin = 2.81099E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 25 MT = 67 Q = -2.87561E+00 MeV Emin = 2.91594E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 26 MT = 68 Q = -2.89700E+00 MeV Emin = 2.93763E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 27 MT = 69 Q = -2.93996E+00 MeV Emin = 2.98119E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 28 MT = 70 Q = -2.94347E+00 MeV Emin = 2.98475E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 29 MT = 91 Q = -2.94347E+00 MeV Emin = 2.98475E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 30 MT = 102 Q = 6.78290E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 32073.82c : (n,gamma) + 31 MT = 103 Q = -3.21671E+00 MeV Emin = 3.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 310720 : (n,p) + 32 MT = 104 Q = -7.51313E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 310710 : (n,d) + 33 MT = 105 Q = -1.05593E+01 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 310700 : (n,t) + 34 MT = 106 Q = -9.88601E+00 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 300700 : (n,He-3) + 35 MT = 107 Q = 1.47578E+00 MeV Emin = 5.25000E-01 MeV frac = 1.00000E+00 Product nuclide = 300690 : (n,alpha) + 36 MT = 108 Q = -4.24147E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 280650 : (n,2alpha) + 37 MT = 111 Q = -1.17705E+01 MeV Emin = 1.35000E+01 MeV frac = 1.00000E+00 Product nuclide = 300710 : (n,2p) + 38 MT = 112 Q = -8.68623E+00 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 290680 : (n,palpha) + + 14 additional transport branches: + + 1 MT = 22 Q = -5.00644E+00 MeV Emin = 6.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 24 Q = -1.52046E+01 MeV Emin = 1.70000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,2nalpha) + 3 MT = 28 Q = -9.73771E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 4 MT = 32 Q = -1.68166E+01 MeV Emin = 1.70525E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 5 MT = 102 Q = 6.78290E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 320731 : (n,gamma) + 6 MT = 103 Q = -3.21671E+00 MeV Emin = 3.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 7 MT = 104 Q = -7.51313E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 8 MT = 105 Q = -1.05593E+01 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 9 MT = 106 Q = -9.88601E+00 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 10 MT = 107 Q = 1.47578E+00 MeV Emin = 5.25000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 11 MT = 108 Q = -4.24147E+00 MeV Emin = 1.00000E+01 MeV frac = 2.00000E+00 Product nuclide = 2004.82c : (n,2alpha) + 12 MT = 111 Q = -1.17705E+01 MeV Emin = 1.35000E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + 13 MT = 112 Q = -8.68623E+00 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,palpha) + 14 MT = 112 Q = -8.68623E+00 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,palpha) + + 52 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.60000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.10000E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.20000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 5.25000E-01 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 4.34147E-04 MeV : damage-energy production + 7 MT = 600 Q = -3.21671E+00 MeV Emin = 3.60000E+00 MeV : (n,p) to ground state + 8 MT = 601 Q = -3.23315E+00 MeV Emin = 3.60000E+00 MeV : (n,p1) + 9 MT = 602 Q = -3.33637E+00 MeV Emin = 3.60000E+00 MeV : (n,p2) + 10 MT = 603 Q = -3.34550E+00 MeV Emin = 3.60000E+00 MeV : (n,p3) + 11 MT = 604 Q = -3.37824E+00 MeV Emin = 3.80000E+00 MeV : (n,p4) + 12 MT = 605 Q = -3.38222E+00 MeV Emin = 3.80000E+00 MeV : (n,p5) + 13 MT = 606 Q = -3.41465E+00 MeV Emin = 3.80000E+00 MeV : (n,p6) + 14 MT = 607 Q = -3.42516E+00 MeV Emin = 3.80000E+00 MeV : (n,p7) + 15 MT = 608 Q = -3.44557E+00 MeV Emin = 3.80000E+00 MeV : (n,p8) + 16 MT = 609 Q = -3.46565E+00 MeV Emin = 3.80000E+00 MeV : (n,p9) + 17 MT = 610 Q = -3.48861E+00 MeV Emin = 3.80000E+00 MeV : (n,p10) + 18 MT = 649 Q = -3.48861E+00 MeV Emin = 3.80000E+00 MeV : (n,p) to continuum + 19 MT = 650 Q = -7.51313E+00 MeV Emin = 8.00000E+00 MeV : (n,d) to ground state + 20 MT = 651 Q = -7.90315E+00 MeV Emin = 8.01399E+00 MeV : (n,d1) + 21 MT = 652 Q = -8.00042E+00 MeV Emin = 8.50000E+00 MeV : (n,d2) + 22 MT = 653 Q = -8.02466E+00 MeV Emin = 8.50000E+00 MeV : (n,d3) + 23 MT = 654 Q = -8.22713E+00 MeV Emin = 8.50000E+00 MeV : (n,d4) + 24 MT = 655 Q = -8.42324E+00 MeV Emin = 9.00000E+00 MeV : (n,d5) + 25 MT = 699 Q = -8.42324E+00 MeV Emin = 9.00000E+00 MeV : (n,d) to continuum + 26 MT = 700 Q = -1.05593E+01 MeV Emin = 1.10000E+01 MeV : (n,t) to ground state + 27 MT = 701 Q = -1.10675E+01 MeV Emin = 1.15000E+01 MeV : (n,t1) + 28 MT = 702 Q = -1.12104E+01 MeV Emin = 1.20000E+01 MeV : (n,t2) + 29 MT = 703 Q = -1.12502E+01 MeV Emin = 1.20000E+01 MeV : (n,t3) + 30 MT = 704 Q = -1.14384E+01 MeV Emin = 1.20000E+01 MeV : (n,t4) + 31 MT = 705 Q = -1.14607E+01 MeV Emin = 1.20000E+01 MeV : (n,t5) + 32 MT = 749 Q = -1.14607E+01 MeV Emin = 1.25000E+01 MeV : (n,t) to continuum + 33 MT = 750 Q = -9.88601E+00 MeV Emin = 1.20000E+01 MeV : (n,He-3) to ground state + 34 MT = 751 Q = -1.07708E+01 MeV Emin = 1.25000E+01 MeV : (n,He-3_1) + 35 MT = 752 Q = -1.09543E+01 MeV Emin = 1.30000E+01 MeV : (n,He-3_2) + 36 MT = 753 Q = -1.14400E+01 MeV Emin = 1.30000E+01 MeV : (n,He-3_3) + 37 MT = 754 Q = -1.16451E+01 MeV Emin = 1.35000E+01 MeV : (n,He-3_4) + 38 MT = 755 Q = -1.16725E+01 MeV Emin = 1.35000E+01 MeV : (n,He-3_5) + 39 MT = 799 Q = -1.16725E+01 MeV Emin = 1.40000E+01 MeV : (n,He-3) to continuum + 40 MT = 800 Q = 1.47578E+00 MeV Emin = 5.25000E-01 MeV : (n,alpha) to ground state + 41 MT = 801 Q = 1.03714E+00 MeV Emin = 1.03438E+00 MeV : (n,a1) + 42 MT = 802 Q = 9.44482E-01 MeV Emin = 1.10000E+00 MeV : (n,a2) + 43 MT = 803 Q = 6.41322E-01 MeV Emin = 1.42905E+00 MeV : (n,a3) + 44 MT = 804 Q = 6.03782E-01 MeV Emin = 1.50000E+00 MeV : (n,a4) + 45 MT = 805 Q = 5.08782E-01 MeV Emin = 1.60000E+00 MeV : (n,a5) + 46 MT = 806 Q = 4.68122E-01 MeV Emin = 1.66719E+00 MeV : (n,a6) + 47 MT = 807 Q = 3.39782E-01 MeV Emin = 1.85000E+00 MeV : (n,a7) + 48 MT = 808 Q = 2.95052E-01 MeV Emin = 1.80000E+00 MeV : (n,a8) + 49 MT = 809 Q = 2.51782E-01 MeV Emin = 2.00000E+00 MeV : (n,a9) + 50 MT = 810 Q = 2.24112E-01 MeV Emin = 1.95000E+00 MeV : (n,a10) + 51 MT = 849 Q = 2.24112E-01 MeV Emin = 1.95000E+00 MeV : (n,alpha) to continuum + 52 MT = 4 Q = 0.00000E+00 MeV Emin = 7.00000E-01 MeV : total inelastic scattering + + Nuclide 66 / 1657 : 32073.82c -- germanium 73 (Ge-73) + + Pointers : 417658 24709 + Primary type : Transport + Nuclide ZAI : 320730 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ge73.ACE + Atomic weight (AW) : 72.92347 + Atomic weight ratio (AWR) : 72.29702 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+02 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 40 reaction channels + - 52 special reactions + - 17 transmutation reactions + - 15 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 40 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 5 Q = 0.00000E+00 MeV Emin = 8.51279E-03 MeV frac = 1.00000E+00 Product nuclide = self : anything + 3 MT = 16 Q = -6.78290E+00 MeV Emin = 6.87672E+00 MeV frac = 1.00000E+00 Product nuclide = 32072.82c : (n,2n) + 4 MT = 17 Q = -1.75349E+01 MeV Emin = 1.77775E+01 MeV frac = 1.00000E+00 Product nuclide = 320710 : (n,3n) + 5 MT = 22 Q = -5.30712E+00 MeV Emin = 7.20000E+00 MeV frac = 1.00000E+00 Product nuclide = 300690 : (n,nalpha) + 6 MT = 24 Q = -1.17893E+01 MeV Emin = 1.35000E+01 MeV frac = 1.00000E+00 Product nuclide = 300680 : (n,2nalpha) + 7 MT = 28 Q = -9.99961E+00 MeV Emin = 1.05000E+01 MeV frac = 1.00000E+00 Product nuclide = 310720 : (n,np) + 8 MT = 32 Q = -1.42960E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 310710 : (n,nd) + 9 MT = 33 Q = -1.73422E+01 MeV Emin = 1.80000E+01 MeV frac = 1.00000E+00 Product nuclide = 310700 : (n,nt) + 10 MT = 41 Q = -1.65206E+01 MeV Emin = 1.70000E+01 MeV frac = 1.00000E+00 Product nuclide = 310710 : (n,2np) + 11 MT = 51 Q = -1.32750E-02 MeV Emin = 1.25939E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 12 MT = 52 Q = -6.67160E-02 MeV Emin = 6.38194E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 13 MT = 53 Q = -6.87520E-02 MeV Emin = 6.86709E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 14 MT = 54 Q = -3.53560E-01 MeV Emin = 3.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 15 MT = 55 Q = -3.64020E-01 MeV Emin = 3.63753E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 16 MT = 56 Q = -3.92450E-01 MeV Emin = 3.83467E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 17 MT = 57 Q = -4.99110E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 18 MT = 58 Q = -5.01450E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 19 MT = 59 Q = -5.51000E-01 MeV Emin = 5.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 20 MT = 60 Q = -5.54910E-01 MeV Emin = 5.60603E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 21 MT = 61 Q = -5.97620E-01 MeV Emin = 6.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 22 MT = 62 Q = -6.59000E-01 MeV Emin = 6.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 23 MT = 63 Q = -7.41700E-01 MeV Emin = 7.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 24 MT = 64 Q = -7.77000E-01 MeV Emin = 7.69853E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 25 MT = 65 Q = -8.09000E-01 MeV Emin = 8.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 26 MT = 66 Q = -8.20000E-01 MeV Emin = 8.26750E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 27 MT = 67 Q = -8.25770E-01 MeV Emin = 8.36007E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 28 MT = 68 Q = -8.68040E-01 MeV Emin = 8.72506E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 29 MT = 69 Q = -8.94100E-01 MeV Emin = 9.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 30 MT = 70 Q = -9.04000E-01 MeV Emin = 9.11486E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 31 MT = 91 Q = -9.04000E-01 MeV Emin = 9.11486E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 32 MT = 102 Q = 1.01962E+01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 32074.82c : (n,gamma) + 33 MT = 103 Q = -8.10941E-01 MeV Emin = 1.20000E+00 MeV frac = 1.00000E+00 Product nuclide = 310730 : (n,p) + 34 MT = 104 Q = -7.77504E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 310720 : (n,d) + 35 MT = 105 Q = -8.03879E+00 MeV Emin = 8.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 310710 : (n,t) + 36 MT = 106 Q = -1.08353E+01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 300710 : (n,He-3) + 37 MT = 107 Q = 3.90870E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 300700 : (n,alpha) + 38 MT = 108 Q = -2.04691E+00 MeV Emin = 8.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 280660 : (n,2alpha) + 39 MT = 111 Q = -9.67534E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 300720 : (n,2p) + 40 MT = 112 Q = -7.19978E+00 MeV Emin = 1.05000E+01 MeV frac = 1.00000E+00 Product nuclide = 290690 : (n,palpha) + + 15 additional transport branches: + + 1 MT = 22 Q = -5.30712E+00 MeV Emin = 7.20000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 24 Q = -1.17893E+01 MeV Emin = 1.35000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,2nalpha) + 3 MT = 28 Q = -9.99961E+00 MeV Emin = 1.05000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 4 MT = 32 Q = -1.42960E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 5 MT = 33 Q = -1.73422E+01 MeV Emin = 1.80000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 6 MT = 41 Q = -1.65206E+01 MeV Emin = 1.70000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,2np) + 7 MT = 103 Q = -8.10941E-01 MeV Emin = 1.20000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 8 MT = 104 Q = -7.77504E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 9 MT = 105 Q = -8.03879E+00 MeV Emin = 8.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 10 MT = 106 Q = -1.08353E+01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 11 MT = 107 Q = 3.90870E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 12 MT = 108 Q = -2.04691E+00 MeV Emin = 8.50000E+00 MeV frac = 2.00000E+00 Product nuclide = 2004.82c : (n,2alpha) + 13 MT = 111 Q = -9.67534E+00 MeV Emin = 1.10000E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + 14 MT = 112 Q = -7.19978E+00 MeV Emin = 1.05000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,palpha) + 15 MT = 112 Q = -7.19978E+00 MeV Emin = 1.05000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,palpha) + + 52 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.20000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 8.50000E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.30000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 600 Q = -8.10941E-01 MeV Emin = 1.20000E+00 MeV : (n,p) to ground state + 8 MT = 601 Q = -1.00894E+00 MeV Emin = 1.40000E+00 MeV : (n,p1) + 9 MT = 602 Q = -1.02889E+00 MeV Emin = 1.40000E+00 MeV : (n,p2) + 10 MT = 603 Q = -1.30676E+00 MeV Emin = 1.60625E+00 MeV : (n,p3) + 11 MT = 604 Q = -1.72191E+00 MeV Emin = 2.00000E+00 MeV : (n,p4) + 12 MT = 605 Q = -1.76694E+00 MeV Emin = 2.00000E+00 MeV : (n,p5) + 13 MT = 606 Q = -1.92794E+00 MeV Emin = 2.20000E+00 MeV : (n,p6) + 14 MT = 607 Q = -2.04594E+00 MeV Emin = 2.40000E+00 MeV : (n,p7) + 15 MT = 608 Q = -2.20694E+00 MeV Emin = 2.40000E+00 MeV : (n,p8) + 16 MT = 609 Q = -2.33894E+00 MeV Emin = 2.60000E+00 MeV : (n,p9) + 17 MT = 610 Q = -2.38894E+00 MeV Emin = 2.80000E+00 MeV : (n,p10) + 18 MT = 649 Q = -2.38894E+00 MeV Emin = 3.00000E+00 MeV : (n,p) to continuum + 19 MT = 650 Q = -7.77504E+00 MeV Emin = 8.00000E+00 MeV : (n,d) to ground state + 20 MT = 651 Q = -7.79148E+00 MeV Emin = 8.00000E+00 MeV : (n,d1) + 21 MT = 652 Q = -7.89470E+00 MeV Emin = 8.50000E+00 MeV : (n,d2) + 22 MT = 653 Q = -7.90383E+00 MeV Emin = 8.50000E+00 MeV : (n,d3) + 23 MT = 654 Q = -7.93657E+00 MeV Emin = 8.50000E+00 MeV : (n,d4) + 24 MT = 655 Q = -7.94055E+00 MeV Emin = 8.50000E+00 MeV : (n,d5) + 25 MT = 699 Q = -7.94055E+00 MeV Emin = 8.50000E+00 MeV : (n,d) to continuum + 26 MT = 700 Q = -8.03879E+00 MeV Emin = 8.50000E+00 MeV : (n,t) to ground state + 27 MT = 701 Q = -8.42881E+00 MeV Emin = 9.00000E+00 MeV : (n,t1) + 28 MT = 702 Q = -8.52607E+00 MeV Emin = 9.00000E+00 MeV : (n,t2) + 29 MT = 703 Q = -8.55031E+00 MeV Emin = 9.00000E+00 MeV : (n,t3) + 30 MT = 704 Q = -8.75279E+00 MeV Emin = 9.00000E+00 MeV : (n,t4) + 31 MT = 705 Q = -8.94890E+00 MeV Emin = 9.50000E+00 MeV : (n,t5) + 32 MT = 749 Q = -8.94890E+00 MeV Emin = 9.50000E+00 MeV : (n,t) to continuum + 33 MT = 750 Q = -1.08353E+01 MeV Emin = 1.30000E+01 MeV : (n,He-3) to ground state + 34 MT = 751 Q = -1.09930E+01 MeV Emin = 1.30000E+01 MeV : (n,He-3_1) + 35 MT = 752 Q = -1.11216E+01 MeV Emin = 1.30000E+01 MeV : (n,He-3_2) + 36 MT = 753 Q = -1.13003E+01 MeV Emin = 1.30000E+01 MeV : (n,He-3_3) + 37 MT = 754 Q = -1.13251E+01 MeV Emin = 1.35000E+01 MeV : (n,He-3_4) + 38 MT = 755 Q = -1.15100E+01 MeV Emin = 1.35000E+01 MeV : (n,He-3_5) + 39 MT = 799 Q = -1.15100E+01 MeV Emin = 1.40000E+01 MeV : (n,He-3) to continuum + 40 MT = 800 Q = 3.90870E+00 MeV Emin = 1.00000E-11 MeV : (n,alpha) to ground state + 41 MT = 801 Q = 3.02390E+00 MeV Emin = 1.00000E-11 MeV : (n,a1) + 42 MT = 802 Q = 2.84040E+00 MeV Emin = 1.00000E-11 MeV : (n,a2) + 43 MT = 803 Q = 2.35470E+00 MeV Emin = 1.00000E-11 MeV : (n,a3) + 44 MT = 804 Q = 2.14960E+00 MeV Emin = 1.00000E-11 MeV : (n,a4) + 45 MT = 805 Q = 2.12220E+00 MeV Emin = 1.00000E-11 MeV : (n,a5) + 46 MT = 806 Q = 1.95100E+00 MeV Emin = 1.00000E-11 MeV : (n,a6) + 47 MT = 807 Q = 1.76830E+00 MeV Emin = 8.00000E-01 MeV : (n,a7) + 48 MT = 808 Q = 1.53370E+00 MeV Emin = 9.00000E-01 MeV : (n,a8) + 49 MT = 809 Q = 1.37070E+00 MeV Emin = 1.09200E+00 MeV : (n,a9) + 50 MT = 810 Q = 1.24370E+00 MeV Emin = 1.25000E+00 MeV : (n,a10) + 51 MT = 849 Q = 1.24370E+00 MeV Emin = 1.17578E+00 MeV : (n,alpha) to continuum + 52 MT = 4 Q = 0.00000E+00 MeV Emin = 1.25939E-02 MeV : total inelastic scattering + + Nuclide 67 / 1657 : 32074.82c -- germanium 74 (Ge-74) + + Pointers : 426021 24755 + Primary type : Transport + Nuclide ZAI : 320740 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ge74.ACE + Atomic weight (AW) : 73.92118 + Atomic weight ratio (AWR) : 73.28616 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+02 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 35 reaction channels + - 50 special reactions + - 12 transmutation reactions + - 10 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 35 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 5 Q = 0.00000E+00 MeV Emin = 6.19220E-02 MeV frac = 1.00000E+00 Product nuclide = self : anything + 3 MT = 16 Q = -1.01962E+01 MeV Emin = 1.03353E+01 MeV frac = 1.00000E+00 Product nuclide = 32073.82c : (n,2n) + 4 MT = 17 Q = -1.69791E+01 MeV Emin = 1.72108E+01 MeV frac = 1.00000E+00 Product nuclide = 32072.82c : (n,3n) + 5 MT = 22 Q = -6.28750E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 300700 : (n,nalpha) + 6 MT = 28 Q = -1.10071E+01 MeV Emin = 1.15000E+01 MeV frac = 1.00000E+00 Product nuclide = 310730 : (n,np) + 7 MT = 32 Q = -1.79712E+01 MeV Emin = 1.82165E+01 MeV frac = 1.00000E+00 Product nuclide = 310720 : (n,nd) + 8 MT = 51 Q = -5.95850E-01 MeV Emin = 6.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -1.20420E+00 MeV Emin = 1.20000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -1.46376E+00 MeV Emin = 1.44186E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -1.48281E+00 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -1.69714E+00 MeV Emin = 1.70000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -1.72495E+00 MeV Emin = 1.73750E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -1.91300E+00 MeV Emin = 1.91980E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -2.16500E+00 MeV Emin = 2.19454E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -2.16526E+00 MeV Emin = 2.19481E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -2.19793E+00 MeV Emin = 2.22792E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -2.22777E+00 MeV Emin = 2.25817E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 62 Q = -2.30000E+00 MeV Emin = 2.33139E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 20 MT = 63 Q = -2.49000E+00 MeV Emin = 2.52398E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 21 MT = 64 Q = -2.53631E+00 MeV Emin = 2.57092E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 22 MT = 65 Q = -2.56933E+00 MeV Emin = 2.60439E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 23 MT = 66 Q = -2.60032E+00 MeV Emin = 2.63580E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 24 MT = 67 Q = -2.66962E+00 MeV Emin = 2.70605E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 25 MT = 68 Q = -2.69368E+00 MeV Emin = 2.73044E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 26 MT = 69 Q = -2.69692E+00 MeV Emin = 2.73372E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 27 MT = 70 Q = -2.71100E+00 MeV Emin = 2.74799E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 28 MT = 91 Q = -2.71100E+00 MeV Emin = 2.74799E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 29 MT = 102 Q = 6.50522E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 320750 : (n,gamma) + 30 MT = 103 Q = -4.58565E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 310740 : (n,p) + 31 MT = 104 Q = -8.78257E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 310730 : (n,d) + 32 MT = 105 Q = -1.17140E+01 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 310720 : (n,t) + 33 MT = 106 Q = -1.21535E+01 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 300720 : (n,He-3) + 34 MT = 107 Q = -4.53927E-01 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 300710 : (n,alpha) + 35 MT = 111 Q = -1.45186E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 300730 : (n,2p) + + 10 additional transport branches: + + 1 MT = 22 Q = -6.28750E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.10071E+01 MeV Emin = 1.15000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.79712E+01 MeV Emin = 1.82165E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 102 Q = 6.50522E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 320751 : (n,gamma) + 5 MT = 103 Q = -4.58565E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 104 Q = -8.78257E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 7 MT = 105 Q = -1.17140E+01 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 8 MT = 106 Q = -1.21535E+01 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 9 MT = 107 Q = -4.53927E-01 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 10 MT = 111 Q = -1.45186E+01 MeV Emin = 1.60000E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 50 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 5.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 9.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.25000E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.40000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 4.25000E-04 MeV : damage-energy production + 7 MT = 600 Q = -4.58565E+00 MeV Emin = 5.00000E+00 MeV : (n,p) to ground state + 8 MT = 601 Q = -4.64220E+00 MeV Emin = 5.00000E+00 MeV : (n,p1) + 9 MT = 602 Q = -4.64522E+00 MeV Emin = 5.00000E+00 MeV : (n,p2) + 10 MT = 603 Q = -4.68792E+00 MeV Emin = 5.00000E+00 MeV : (n,p3) + 11 MT = 604 Q = -4.69430E+00 MeV Emin = 5.00000E+00 MeV : (n,p4) + 12 MT = 605 Q = -4.72698E+00 MeV Emin = 5.00000E+00 MeV : (n,p5) + 13 MT = 606 Q = -4.73068E+00 MeV Emin = 5.00000E+00 MeV : (n,p6) + 14 MT = 607 Q = -4.81345E+00 MeV Emin = 5.20000E+00 MeV : (n,p7) + 15 MT = 608 Q = -4.83743E+00 MeV Emin = 5.20000E+00 MeV : (n,p8) + 16 MT = 609 Q = -5.04071E+00 MeV Emin = 5.40000E+00 MeV : (n,p9) + 17 MT = 610 Q = -5.47976E+00 MeV Emin = 5.60000E+00 MeV : (n,p10) + 18 MT = 649 Q = -5.47976E+00 MeV Emin = 6.00000E+00 MeV : (n,p) to continuum + 19 MT = 650 Q = -8.78257E+00 MeV Emin = 9.00000E+00 MeV : (n,d) to ground state + 20 MT = 651 Q = -8.98057E+00 MeV Emin = 9.50000E+00 MeV : (n,d1) + 21 MT = 652 Q = -9.00052E+00 MeV Emin = 9.50000E+00 MeV : (n,d2) + 22 MT = 653 Q = -9.27839E+00 MeV Emin = 9.50000E+00 MeV : (n,d3) + 23 MT = 654 Q = -9.69354E+00 MeV Emin = 1.00000E+01 MeV : (n,d4) + 24 MT = 655 Q = -9.73857E+00 MeV Emin = 1.00000E+01 MeV : (n,d5) + 25 MT = 699 Q = -9.73857E+00 MeV Emin = 1.05000E+01 MeV : (n,d) to continuum + 26 MT = 700 Q = -1.17140E+01 MeV Emin = 1.25000E+01 MeV : (n,t) to ground state + 27 MT = 701 Q = -1.17304E+01 MeV Emin = 1.25000E+01 MeV : (n,t1) + 28 MT = 702 Q = -1.18336E+01 MeV Emin = 1.25000E+01 MeV : (n,t2) + 29 MT = 703 Q = -1.18428E+01 MeV Emin = 1.25000E+01 MeV : (n,t3) + 30 MT = 704 Q = -1.18755E+01 MeV Emin = 1.25000E+01 MeV : (n,t4) + 31 MT = 705 Q = -1.18795E+01 MeV Emin = 1.25000E+01 MeV : (n,t5) + 32 MT = 749 Q = -1.18795E+01 MeV Emin = 1.25000E+01 MeV : (n,t) to continuum + 33 MT = 750 Q = -1.21535E+01 MeV Emin = 1.40000E+01 MeV : (n,He-3) to ground state + 34 MT = 751 Q = -1.28060E+01 MeV Emin = 1.45000E+01 MeV : (n,He-3_1) + 35 MT = 752 Q = -1.36526E+01 MeV Emin = 1.50000E+01 MeV : (n,He-3_2) + 36 MT = 753 Q = -1.38109E+01 MeV Emin = 1.50000E+01 MeV : (n,He-3_3) + 37 MT = 754 Q = -1.43453E+01 MeV Emin = 1.60000E+01 MeV : (n,He-3_4) + 38 MT = 800 Q = -4.53927E-01 MeV Emin = 2.00000E+00 MeV : (n,alpha) to ground state + 39 MT = 801 Q = -6.11627E-01 MeV Emin = 2.20000E+00 MeV : (n,a1) + 40 MT = 802 Q = -7.40227E-01 MeV Emin = 2.40000E+00 MeV : (n,a2) + 41 MT = 803 Q = -9.18927E-01 MeV Emin = 2.60000E+00 MeV : (n,a3) + 42 MT = 804 Q = -9.43727E-01 MeV Emin = 2.60000E+00 MeV : (n,a4) + 43 MT = 805 Q = -1.12863E+00 MeV Emin = 2.80000E+00 MeV : (n,a5) + 44 MT = 806 Q = -1.30693E+00 MeV Emin = 3.00000E+00 MeV : (n,a6) + 45 MT = 807 Q = -1.50593E+00 MeV Emin = 3.20000E+00 MeV : (n,a7) + 46 MT = 808 Q = -1.53193E+00 MeV Emin = 3.20000E+00 MeV : (n,a8) + 47 MT = 809 Q = -1.71523E+00 MeV Emin = 3.40000E+00 MeV : (n,a9) + 48 MT = 810 Q = -1.87493E+00 MeV Emin = 3.60000E+00 MeV : (n,a10) + 49 MT = 849 Q = -1.87493E+00 MeV Emin = 4.00000E+00 MeV : (n,alpha) to continuum + 50 MT = 4 Q = 0.00000E+00 MeV Emin = 6.00000E-01 MeV : total inelastic scattering + + Nuclide 68 / 1657 : 32076.82c -- germanium 76 (Ge-76) + + Pointers : 435161 24801 + Primary type : Transport + Nuclide ZAI : 320760 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ge76.ACE + Atomic weight (AW) : 75.92140 + Atomic weight ratio (AWR) : 75.26920 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+02 + Half-life : 4.99E+28 seconds (1.58E+21 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 32 reaction channels + - 39 special reactions + - 9 transmutation reactions + - 7 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 32 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 5 Q = 0.00000E+00 MeV Emin = 4.99445E-02 MeV frac = 1.00000E+00 Product nuclide = self : anything + 3 MT = 16 Q = -9.42830E+00 MeV Emin = 9.55356E+00 MeV frac = 1.00000E+00 Product nuclide = 320750 : (n,2n) + 4 MT = 17 Q = -1.59335E+01 MeV Emin = 1.61452E+01 MeV frac = 1.00000E+00 Product nuclide = 32074.82c : (n,3n) + 5 MT = 22 Q = -7.50938E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 300720 : (n,nalpha) + 6 MT = 28 Q = -1.20377E+01 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 310750 : (n,np) + 7 MT = 51 Q = -5.62930E-01 MeV Emin = 5.68750E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 8 MT = 52 Q = -1.10844E+00 MeV Emin = 1.10000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 9 MT = 53 Q = -1.41008E+00 MeV Emin = 1.40000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 10 MT = 54 Q = -1.53946E+00 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 11 MT = 55 Q = -1.91107E+00 MeV Emin = 1.90000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 12 MT = 56 Q = -2.01987E+00 MeV Emin = 2.04671E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 13 MT = 57 Q = -2.20490E+00 MeV Emin = 2.23420E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 14 MT = 58 Q = -2.28422E+00 MeV Emin = 2.31457E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 15 MT = 59 Q = -2.45600E+00 MeV Emin = 2.48863E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 16 MT = 60 Q = -2.47820E+00 MeV Emin = 2.51112E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 17 MT = 61 Q = -2.50360E+00 MeV Emin = 2.53686E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 18 MT = 62 Q = -2.55400E+00 MeV Emin = 2.58793E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 19 MT = 63 Q = -2.59110E+00 MeV Emin = 2.62553E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 20 MT = 64 Q = -2.62400E+00 MeV Emin = 2.65886E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 21 MT = 65 Q = -2.65451E+00 MeV Emin = 2.68978E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 22 MT = 66 Q = -2.69240E+00 MeV Emin = 2.72817E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 23 MT = 67 Q = -2.73340E+00 MeV Emin = 2.76972E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 24 MT = 68 Q = -2.74776E+00 MeV Emin = 2.78427E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 25 MT = 69 Q = -2.76876E+00 MeV Emin = 2.80555E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 26 MT = 70 Q = -2.84157E+00 MeV Emin = 2.87932E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 27 MT = 91 Q = -2.84157E+00 MeV Emin = 2.87932E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 28 MT = 102 Q = 6.07257E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 320770 : (n,gamma) + 29 MT = 103 Q = -6.22765E+00 MeV Emin = 6.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 310760 : (n,p) + 30 MT = 104 Q = -9.81309E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 310750 : (n,d) + 31 MT = 105 Q = -1.20373E+01 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 310740 : (n,t) + 32 MT = 107 Q = -2.15648E+00 MeV Emin = 3.80000E+00 MeV frac = 1.00000E+00 Product nuclide = 300730 : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -7.50938E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.20377E+01 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 102 Q = 6.07257E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 320771 : (n,gamma) + 4 MT = 103 Q = -6.22765E+00 MeV Emin = 6.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -9.81309E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -1.20373E+01 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 107 Q = -2.15648E+00 MeV Emin = 3.80000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 39 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 6.60000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.00000E+01 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.25000E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 2.00000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 3.80000E+00 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 4.45508E-04 MeV : damage-energy production + 7 MT = 600 Q = -6.22765E+00 MeV Emin = 6.60000E+00 MeV : (n,p) to ground state + 8 MT = 601 Q = -6.39994E+00 MeV Emin = 6.80000E+00 MeV : (n,p1) + 9 MT = 602 Q = -6.42715E+00 MeV Emin = 6.80000E+00 MeV : (n,p2) + 10 MT = 603 Q = -6.50293E+00 MeV Emin = 6.80000E+00 MeV : (n,p3) + 11 MT = 604 Q = -6.50922E+00 MeV Emin = 7.00000E+00 MeV : (n,p4) + 12 MT = 605 Q = -6.59746E+00 MeV Emin = 7.00000E+00 MeV : (n,p5) + 13 MT = 606 Q = -6.79318E+00 MeV Emin = 7.00000E+00 MeV : (n,p6) + 14 MT = 607 Q = -6.90848E+00 MeV Emin = 7.20000E+00 MeV : (n,p7) + 15 MT = 608 Q = -7.00920E+00 MeV Emin = 7.40000E+00 MeV : (n,p8) + 16 MT = 609 Q = -7.25795E+00 MeV Emin = 7.60000E+00 MeV : (n,p9) + 17 MT = 610 Q = -7.33368E+00 MeV Emin = 7.60000E+00 MeV : (n,p10) + 18 MT = 649 Q = -7.33368E+00 MeV Emin = 7.80000E+00 MeV : (n,p) to continuum + 19 MT = 650 Q = -9.81309E+00 MeV Emin = 1.00000E+01 MeV : (n,d) to ground state + 20 MT = 651 Q = -9.83559E+00 MeV Emin = 1.00000E+01 MeV : (n,d1) + 21 MT = 652 Q = -9.99145E+00 MeV Emin = 1.05000E+01 MeV : (n,d2) + 22 MT = 653 Q = -1.00417E+01 MeV Emin = 1.05000E+01 MeV : (n,d3) + 23 MT = 654 Q = -1.02453E+01 MeV Emin = 1.05000E+01 MeV : (n,d4) + 24 MT = 655 Q = -1.04195E+01 MeV Emin = 1.10000E+01 MeV : (n,d5) + 25 MT = 699 Q = -1.04195E+01 MeV Emin = 1.10000E+01 MeV : (n,d) to continuum + 26 MT = 700 Q = -1.20373E+01 MeV Emin = 1.25000E+01 MeV : (n,t) to ground state + 27 MT = 701 Q = -1.20939E+01 MeV Emin = 1.25000E+01 MeV : (n,t1) + 28 MT = 702 Q = -1.20969E+01 MeV Emin = 1.30000E+01 MeV : (n,t2) + 29 MT = 703 Q = -1.21396E+01 MeV Emin = 1.30000E+01 MeV : (n,t3) + 30 MT = 704 Q = -1.21460E+01 MeV Emin = 1.30000E+01 MeV : (n,t4) + 31 MT = 705 Q = -1.21787E+01 MeV Emin = 1.30000E+01 MeV : (n,t5) + 32 MT = 749 Q = -1.21787E+01 MeV Emin = 1.30000E+01 MeV : (n,t) to continuum + 33 MT = 800 Q = -2.15648E+00 MeV Emin = 3.80000E+00 MeV : (n,alpha) to ground state + 34 MT = 801 Q = -2.35198E+00 MeV Emin = 4.00000E+00 MeV : (n,a1) + 35 MT = 802 Q = -2.43648E+00 MeV Emin = 4.20000E+00 MeV : (n,a2) + 36 MT = 803 Q = -2.65648E+00 MeV Emin = 4.40000E+00 MeV : (n,a3) + 37 MT = 804 Q = -3.29648E+00 MeV Emin = 5.00000E+00 MeV : (n,a4) + 38 MT = 849 Q = -3.29648E+00 MeV Emin = 5.40000E+00 MeV : (n,alpha) to continuum + 39 MT = 4 Q = 0.00000E+00 MeV Emin = 5.68750E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 11 Q = 2.03910E+00 MeV frac = 1.00000E+00 Product nuclide = 34076.82c : beta- + beta- + + Nuclide 69 / 1657 : 33075.82c -- arsenic 75 (As-75) + + Pointers : 452491 19281 + Primary type : Transport + Nuclide ZAI : 330750 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/As75.ACE + Atomic weight (AW) : 74.92162 + Atomic weight ratio (AWR) : 74.27800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 22 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 22 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -1.98600E-01 MeV Emin = 2.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -2.64600E-01 MeV Emin = 2.63980E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -2.79500E-01 MeV Emin = 2.75711E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -3.03700E-01 MeV Emin = 3.04947E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -4.00500E-01 MeV Emin = 4.03089E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -4.68900E-01 MeV Emin = 4.57881E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 57 Q = -5.72100E-01 MeV Emin = 5.59850E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 9 MT = 58 Q = -6.17700E-01 MeV Emin = 6.21406E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 10 MT = 59 Q = -8.21800E-01 MeV Emin = 7.66430E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 11 MT = 60 Q = -1.02000E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 12 MT = 61 Q = -1.30000E+00 MeV Emin = 1.24656E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 13 MT = 62 Q = -1.60000E+00 MeV Emin = 1.60000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 14 MT = 63 Q = -1.80000E+00 MeV Emin = 1.81712E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 15 MT = 91 Q = -1.78600E+00 MeV Emin = 1.71577E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 16 MT = 102 Q = 7.32820E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 330760 : (n,gamma) + 17 MT = 103 Q = -3.94970E-01 MeV Emin = 3.85095E-01 MeV frac = 1.00000E+00 Product nuclide = 320750 : (n,p) + 18 MT = 104 Q = -4.67440E+00 MeV Emin = 4.73733E+00 MeV frac = 1.00000E+00 Product nuclide = 32074.82c : (n,d) + 19 MT = 105 Q = -8.61550E+00 MeV Emin = 8.73149E+00 MeV frac = 1.00000E+00 Product nuclide = 32073.82c : (n,t) + 20 MT = 106 Q = -1.01600E+01 MeV Emin = 1.02968E+01 MeV frac = 1.00000E+00 Product nuclide = 310730 : (n,He-3) + 21 MT = 107 Q = 1.20310E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 310720 : (n,alpha) + 22 MT = 111 Q = -1.15160E+01 MeV Emin = 1.16710E+01 MeV frac = 1.00000E+00 Product nuclide = 310740 : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = -3.94970E-01 MeV Emin = 3.85095E-01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -4.67440E+00 MeV Emin = 4.73733E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -8.61550E+00 MeV Emin = 8.73149E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -1.01600E+01 MeV Emin = 1.02968E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 1.20310E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -1.15160E+01 MeV Emin = 1.16710E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.85095E-01 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 4.73733E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 8.73149E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.02968E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.62500E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 2.00000E-01 MeV : total inelastic scattering + + Nuclide 70 / 1657 : 34076.82c -- selenium 76 (Se-76) + + Pointers : 469592 32529 + Primary type : Transport + Nuclide ZAI : 340760 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Se76.ACE + Atomic weight (AW) : 75.91919 + Atomic weight ratio (AWR) : 75.26700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 13 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 13 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -5.59000E-01 MeV Emin = 5.45347E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -1.11000E+00 MeV Emin = 1.06235E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -1.22000E+00 MeV Emin = 1.18047E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -1.34000E+00 MeV Emin = 1.35000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 91 Q = -2.96070E+00 MeV Emin = 3.00004E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 7 MT = 102 Q = 7.41800E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 34077.82c : (n,gamma) + 8 MT = 103 Q = -2.18520E+00 MeV Emin = 2.21423E+00 MeV frac = 1.00000E+00 Product nuclide = 330760 : (n,p) + 9 MT = 104 Q = -7.28710E+00 MeV Emin = 7.38392E+00 MeV frac = 1.00000E+00 Product nuclide = 33075.82c : (n,d) + 10 MT = 105 Q = -1.12740E+01 MeV Emin = 1.14238E+01 MeV frac = 1.00000E+00 Product nuclide = 330740 : (n,t) + 11 MT = 106 Q = -8.69400E+00 MeV Emin = 8.80951E+00 MeV frac = 1.00000E+00 Product nuclide = 32074.82c : (n,He-3) + 12 MT = 107 Q = 1.68020E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 32073.82c : (n,alpha) + 13 MT = 111 Q = -9.90610E+00 MeV Emin = 1.00377E+01 MeV frac = 1.00000E+00 Product nuclide = 320750 : (n,2p) + + 7 additional transport branches: + + 1 MT = 102 Q = 7.41800E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 340771 : (n,gamma) + 2 MT = 103 Q = -2.18520E+00 MeV Emin = 2.21423E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 104 Q = -7.28710E+00 MeV Emin = 7.38392E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 4 MT = 105 Q = -1.12740E+01 MeV Emin = 1.14238E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 5 MT = 106 Q = -8.69400E+00 MeV Emin = 8.80951E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 6 MT = 107 Q = 1.68020E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 7 MT = 111 Q = -9.90610E+00 MeV Emin = 1.00377E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.21423E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.38392E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.14238E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 8.80951E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.62500E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 5.45347E-01 MeV : total inelastic scattering + + Nuclide 71 / 1657 : 34077.82c -- selenium 77 (Se-77) + + Pointers : 471693 32575 + Primary type : Transport + Nuclide ZAI : 340770 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Se77.ACE + Atomic weight (AW) : 76.91988 + Atomic weight ratio (AWR) : 76.25910 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 19 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 19 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -1.61000E-01 MeV Emin = 1.47333E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -2.39000E-01 MeV Emin = 2.31598E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -2.50000E-01 MeV Emin = 2.52768E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -3.10000E-01 MeV Emin = 3.05937E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -4.40000E-01 MeV Emin = 4.35000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -5.22000E-01 MeV Emin = 5.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 57 Q = -6.80000E-01 MeV Emin = 6.87500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 9 MT = 58 Q = -8.20000E-01 MeV Emin = 7.65375E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 10 MT = 59 Q = -9.60000E-01 MeV Emin = 9.15377E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 11 MT = 60 Q = -1.00000E+00 MeV Emin = 1.01000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 12 MT = 91 Q = -1.57930E+00 MeV Emin = 1.55000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 13 MT = 102 Q = 1.04970E+01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 34078.82c : (n,gamma) + 14 MT = 103 Q = 9.21570E-02 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 330770 : (n,p) + 15 MT = 104 Q = -7.37720E+00 MeV Emin = 7.47394E+00 MeV frac = 1.00000E+00 Product nuclide = 330760 : (n,d) + 16 MT = 105 Q = -8.44740E+00 MeV Emin = 8.55817E+00 MeV frac = 1.00000E+00 Product nuclide = 33075.82c : (n,t) + 17 MT = 106 Q = -9.60660E+00 MeV Emin = 9.73257E+00 MeV frac = 1.00000E+00 Product nuclide = 320750 : (n,He-3) + 18 MT = 107 Q = 4.46100E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 32074.82c : (n,alpha) + 19 MT = 111 Q = -7.89630E+00 MeV Emin = 7.99985E+00 MeV frac = 1.00000E+00 Product nuclide = 32076.82c : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = 9.21570E-02 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -7.37720E+00 MeV Emin = 7.47394E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -8.44740E+00 MeV Emin = 8.55817E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -9.60660E+00 MeV Emin = 9.73257E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 4.46100E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -7.89630E+00 MeV Emin = 7.99985E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.62500E-02 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.47394E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 8.55817E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 9.73257E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.62500E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 1.47333E-01 MeV : total inelastic scattering + + Nuclide 72 / 1657 : 34078.82c -- selenium 78 (Se-78) + + Pointers : 474525 32621 + Primary type : Transport + Nuclide ZAI : 340780 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Se78.ACE + Atomic weight (AW) : 77.91735 + Atomic weight ratio (AWR) : 77.24800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 18 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 18 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -6.14000E-01 MeV Emin = 6.17902E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -1.31000E+00 MeV Emin = 1.31250E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -1.51000E+00 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -1.51001E+00 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -1.71000E+00 MeV Emin = 1.66605E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -1.88000E+00 MeV Emin = 1.81822E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 57 Q = -1.97000E+00 MeV Emin = 1.94992E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 9 MT = 58 Q = -2.03000E+00 MeV Emin = 2.05630E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 10 MT = 59 Q = -2.22000E+00 MeV Emin = 2.24874E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 11 MT = 91 Q = -2.96170E+00 MeV Emin = 3.00004E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 12 MT = 102 Q = 6.97800E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 34079.82c : (n,gamma) + 13 MT = 103 Q = -3.50770E+00 MeV Emin = 3.55311E+00 MeV frac = 1.00000E+00 Product nuclide = 330780 : (n,p) + 14 MT = 104 Q = -8.17730E+00 MeV Emin = 8.28316E+00 MeV frac = 1.00000E+00 Product nuclide = 330770 : (n,d) + 15 MT = 105 Q = -1.16150E+01 MeV Emin = 1.17654E+01 MeV frac = 1.00000E+00 Product nuclide = 330760 : (n,t) + 16 MT = 106 Q = -1.06740E+01 MeV Emin = 1.08122E+01 MeV frac = 1.00000E+00 Product nuclide = 32076.82c : (n,He-3) + 17 MT = 107 Q = 4.70960E-01 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 320750 : (n,alpha) + 18 MT = 111 Q = -1.23190E+01 MeV Emin = 1.24785E+01 MeV frac = 1.00000E+00 Product nuclide = 320770 : (n,2p) + + 7 additional transport branches: + + 1 MT = 102 Q = 6.97800E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 340791 : (n,gamma) + 2 MT = 103 Q = -3.50770E+00 MeV Emin = 3.55311E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 104 Q = -8.17730E+00 MeV Emin = 8.28316E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 4 MT = 105 Q = -1.16150E+01 MeV Emin = 1.17654E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 5 MT = 106 Q = -1.06740E+01 MeV Emin = 1.08122E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 6 MT = 107 Q = 4.70960E-01 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 7 MT = 111 Q = -1.23190E+01 MeV Emin = 1.24785E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.55311E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.28316E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.17654E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.08122E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.62500E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 6.17902E-01 MeV : total inelastic scattering + + Nuclide 73 / 1657 : 34079.82c -- selenium 79 (Se-79) + + Pointers : 476991 32667 + Primary type : Transport + Nuclide ZAI : 340790 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Se79.ACE + Atomic weight (AW) : 78.91845 + Atomic weight ratio (AWR) : 78.24050 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.19E+13 seconds (377,251 years) + Specific ingestion toxicity : 2.90E-09 Sv/Bq + Specific inhalation toxicity : 6.80E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 42 reaction channels + - 7 special reactions + - 11 transmutation reactions + - 8 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 42 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.96520E+00 MeV Emin = 7.05423E+00 MeV frac = 1.00000E+00 Product nuclide = 34078.82c : (n,2n) + 3 MT = 17 Q = -1.74667E+01 MeV Emin = 1.76900E+01 MeV frac = 1.00000E+00 Product nuclide = 34077.82c : (n,3n) + 4 MT = 22 Q = -6.48638E+00 MeV Emin = 7.05423E+00 MeV frac = 1.00000E+00 Product nuclide = 320750 : (n,nalpha) + 5 MT = 28 Q = -1.04742E+01 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 330780 : (n,np) + 6 MT = 32 Q = -1.50645E+01 MeV Emin = 1.52571E+01 MeV frac = 1.00000E+00 Product nuclide = 330770 : (n,nd) + 7 MT = 51 Q = -9.56999E-02 MeV Emin = 9.26924E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 8 MT = 52 Q = -1.28000E-01 MeV Emin = 1.24079E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 9 MT = 53 Q = -1.37000E-01 MeV Emin = 1.34194E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 10 MT = 54 Q = -3.64999E-01 MeV Emin = 3.52249E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 11 MT = 55 Q = -4.98999E-01 MeV Emin = 5.05029E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 12 MT = 56 Q = -5.27899E-01 MeV Emin = 5.30173E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 13 MT = 57 Q = -5.71999E-01 MeV Emin = 5.78423E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 14 MT = 58 Q = -6.29999E-01 MeV Emin = 6.36851E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 15 MT = 59 Q = -7.28599E-01 MeV Emin = 7.28769E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 16 MT = 60 Q = -7.90399E-01 MeV Emin = 8.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 17 MT = 61 Q = -8.18799E-01 MeV Emin = 8.28501E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 18 MT = 62 Q = -8.97099E-01 MeV Emin = 9.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 19 MT = 63 Q = -9.74599E-01 MeV Emin = 9.69886E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 20 MT = 64 Q = -9.82899E-01 MeV Emin = 9.95084E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 21 MT = 65 Q = -1.00820E+00 MeV Emin = 1.01055E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 22 MT = 66 Q = -1.07210E+00 MeV Emin = 1.06962E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 23 MT = 67 Q = -1.08000E+00 MeV Emin = 1.08980E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 24 MT = 68 Q = -1.08880E+00 MeV Emin = 1.09826E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 25 MT = 69 Q = -1.11010E+00 MeV Emin = 1.12099E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 26 MT = 70 Q = -1.14500E+00 MeV Emin = 1.14675E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 27 MT = 71 Q = -1.23130E+00 MeV Emin = 1.24469E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 28 MT = 72 Q = -1.25340E+00 MeV Emin = 1.25971E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 29 MT = 73 Q = -1.25670E+00 MeV Emin = 1.27109E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 30 MT = 74 Q = -1.33990E+00 MeV Emin = 1.33860E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 31 MT = 75 Q = -1.38500E+00 MeV Emin = 1.38557E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 32 MT = 76 Q = -1.49100E+00 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 33 MT = 77 Q = -1.58900E+00 MeV Emin = 1.56279E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 27. excited state + 34 MT = 78 Q = -1.66700E+00 MeV Emin = 1.65868E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 28. excited state + 35 MT = 79 Q = -1.73770E+00 MeV Emin = 1.75000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 29. excited state + 36 MT = 91 Q = -1.76010E+00 MeV Emin = 1.77126E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 37 MT = 102 Q = 9.91209E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 34080.82c : (n,gamma) + 38 MT = 103 Q = -1.41813E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 330790 : (n,p) + 39 MT = 104 Q = -8.16410E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 330780 : (n,d) + 40 MT = 105 Q = -8.87936E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 330770 : (n,t) + 41 MT = 106 Q = -1.15621E+01 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 320770 : (n,He-3) + 42 MT = 107 Q = 2.94712E+00 MeV Emin = 9.99543E-02 MeV frac = 1.00000E+00 Product nuclide = 32076.82c : (n,alpha) + + 8 additional transport branches: + + 1 MT = 22 Q = -6.48638E+00 MeV Emin = 7.05423E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.04742E+01 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.50645E+01 MeV Emin = 1.52571E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 103 Q = -1.41813E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -8.16410E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -8.87936E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 106 Q = -1.15621E+01 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 8 MT = 107 Q = 2.94712E+00 MeV Emin = 9.99543E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 9.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.00000E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.40000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 9.99543E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 9.26924E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.50900E-01 MeV frac = 1.00000E+00 Product nuclide = 35079.82c : beta- + + Nuclide 74 / 1657 : 34080.82c -- selenium 80 (Se-80) + + Pointers : 481841 32713 + Primary type : Transport + Nuclide ZAI : 340800 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Se80.ACE + Atomic weight (AW) : 79.91652 + Atomic weight ratio (AWR) : 79.23000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 17 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 17 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -6.66000E-01 MeV Emin = 6.36359E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -1.35000E+00 MeV Emin = 1.27525E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -1.44000E+00 MeV Emin = 1.45014E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -1.48000E+00 MeV Emin = 1.48338E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -1.69000E+00 MeV Emin = 1.65565E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -1.77000E+00 MeV Emin = 1.75182E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 57 Q = -1.86000E+00 MeV Emin = 1.88117E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 9 MT = 58 Q = -1.96000E+00 MeV Emin = 1.97000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 10 MT = 91 Q = -2.96270E+00 MeV Emin = 3.00009E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 11 MT = 102 Q = 6.70120E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 340810 : (n,gamma) + 12 MT = 103 Q = -4.91700E+00 MeV Emin = 4.97906E+00 MeV frac = 1.00000E+00 Product nuclide = 330800 : (n,p) + 13 MT = 104 Q = -9.10240E+00 MeV Emin = 9.21729E+00 MeV frac = 1.00000E+00 Product nuclide = 330790 : (n,d) + 14 MT = 105 Q = -1.18950E+01 MeV Emin = 1.20451E+01 MeV frac = 1.00000E+00 Product nuclide = 330780 : (n,t) + 15 MT = 106 Q = -1.28570E+01 MeV Emin = 1.30193E+01 MeV frac = 1.00000E+00 Product nuclide = 320780 : (n,He-3) + 16 MT = 107 Q = -9.00200E-01 MeV Emin = 9.11356E-01 MeV frac = 1.00000E+00 Product nuclide = 320770 : (n,alpha) + 17 MT = 111 Q = -1.46930E+01 MeV Emin = 1.48785E+01 MeV frac = 1.00000E+00 Product nuclide = 320790 : (n,2p) + + 7 additional transport branches: + + 1 MT = 102 Q = 6.70120E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 340811 : (n,gamma) + 2 MT = 103 Q = -4.91700E+00 MeV Emin = 4.97906E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 104 Q = -9.10240E+00 MeV Emin = 9.21729E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 4 MT = 105 Q = -1.18950E+01 MeV Emin = 1.20451E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 5 MT = 106 Q = -1.28570E+01 MeV Emin = 1.30193E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 6 MT = 107 Q = -9.00200E-01 MeV Emin = 9.11356E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 7 MT = 111 Q = -1.46930E+01 MeV Emin = 1.48785E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.97906E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 9.21729E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.20451E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.30193E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 9.11356E-01 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 6.36359E-01 MeV : total inelastic scattering + + Nuclide 75 / 1657 : 34082.82c -- selenium 82 (Se-82) + + Pointers : 486183 32759 + Primary type : Transport + Nuclide ZAI : 340820 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Se82.ACE + Atomic weight (AW) : 81.91671 + Atomic weight ratio (AWR) : 81.21300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 3.06E+27 seconds (9.71E+19 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 12 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 7 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 12 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -6.55000E-01 MeV Emin = 6.26436E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -1.49000E+00 MeV Emin = 1.38122E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -1.75000E+00 MeV Emin = 1.76000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 91 Q = -2.96360E+00 MeV Emin = 3.00009E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 6 MT = 102 Q = 5.92500E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 340830 : (n,gamma) + 7 MT = 103 Q = -6.61110E+00 MeV Emin = 6.69250E+00 MeV frac = 1.00000E+00 Product nuclide = 330820 : (n,p) + 8 MT = 104 Q = -1.00070E+01 MeV Emin = 1.01302E+01 MeV frac = 1.00000E+00 Product nuclide = 330810 : (n,d) + 9 MT = 105 Q = -1.24000E+01 MeV Emin = 1.25527E+01 MeV frac = 1.00000E+00 Product nuclide = 330800 : (n,t) + 10 MT = 106 Q = -1.50110E+01 MeV Emin = 1.51958E+01 MeV frac = 1.00000E+00 Product nuclide = 320800 : (n,He-3) + 11 MT = 107 Q = -2.36870E+00 MeV Emin = 2.39787E+00 MeV frac = 1.00000E+00 Product nuclide = 320790 : (n,alpha) + 12 MT = 111 Q = -1.77460E+01 MeV Emin = 1.79645E+01 MeV frac = 1.00000E+00 Product nuclide = 320810 : (n,2p) + + 7 additional transport branches: + + 1 MT = 102 Q = 5.92500E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 340831 : (n,gamma) + 2 MT = 103 Q = -6.61110E+00 MeV Emin = 6.69250E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 104 Q = -1.00070E+01 MeV Emin = 1.01302E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 4 MT = 105 Q = -1.24000E+01 MeV Emin = 1.25527E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 5 MT = 106 Q = -1.50110E+01 MeV Emin = 1.51958E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 6 MT = 107 Q = -2.36870E+00 MeV Emin = 2.39787E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 7 MT = 111 Q = -1.77460E+01 MeV Emin = 1.79645E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 6.69250E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.01302E+01 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.25527E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.51958E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 2.39787E+00 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 6.26436E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 11 Q = 2.99640E+00 MeV frac = 1.00000E+00 Product nuclide = 36082.82c : beta- + beta- + + Nuclide 76 / 1657 : 35079.82c -- bromine 79 (Br-79) + + Pointers : 492457 20247 + Primary type : Transport + Nuclide ZAI : 350790 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Br79.ACE + Atomic weight (AW) : 78.91835 + Atomic weight ratio (AWR) : 78.24040 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 20 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 20 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -2.08000E-01 MeV Emin = 2.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -2.17300E-01 MeV Emin = 2.19877E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -2.61300E-01 MeV Emin = 2.62224E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -3.06700E-01 MeV Emin = 2.96793E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -3.97400E-01 MeV Emin = 3.86250E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -5.23000E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 57 Q = -6.06100E-01 MeV Emin = 5.93553E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 9 MT = 58 Q = -7.61000E-01 MeV Emin = 7.37500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 10 MT = 59 Q = -8.33000E-01 MeV Emin = 8.12500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 11 MT = 60 Q = -1.16500E+00 MeV Emin = 1.17100E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 12 MT = 61 Q = -1.33200E+00 MeV Emin = 1.34552E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 13 MT = 91 Q = -1.32510E+00 MeV Emin = 1.25650E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 14 MT = 102 Q = 7.88300E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 350800 : (n,gamma) + 15 MT = 103 Q = 6.33090E-01 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 34079.82c : (n,p) + 16 MT = 104 Q = -4.10130E+00 MeV Emin = 4.15372E+00 MeV frac = 1.00000E+00 Product nuclide = 34078.82c : (n,d) + 17 MT = 105 Q = -8.33900E+00 MeV Emin = 8.44558E+00 MeV frac = 1.00000E+00 Product nuclide = 34077.82c : (n,t) + 18 MT = 106 Q = -9.01110E+00 MeV Emin = 9.12627E+00 MeV frac = 1.00000E+00 Product nuclide = 330770 : (n,He-3) + 19 MT = 107 Q = 1.86650E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 330760 : (n,alpha) + 20 MT = 111 Q = -9.83300E+00 MeV Emin = 9.95868E+00 MeV frac = 1.00000E+00 Product nuclide = 330780 : (n,2p) + + 7 additional transport branches: + + 1 MT = 102 Q = 7.88300E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 350801 : (n,gamma) + 2 MT = 103 Q = 6.33090E-01 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 104 Q = -4.10130E+00 MeV Emin = 4.15372E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 4 MT = 105 Q = -8.33900E+00 MeV Emin = 8.44558E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 5 MT = 106 Q = -9.01110E+00 MeV Emin = 9.12627E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 6 MT = 107 Q = 1.86650E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 7 MT = 111 Q = -9.83300E+00 MeV Emin = 9.95868E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.62500E-02 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 4.15372E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 8.44558E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 9.12627E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.62500E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 2.00000E-01 MeV : total inelastic scattering + + Nuclide 77 / 1657 : 35081.82c -- bromine 81 (Br-81) + + Pointers : 496787 20293 + Primary type : Transport + Nuclide ZAI : 350810 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Br81.ACE + Atomic weight (AW) : 80.91631 + Atomic weight ratio (AWR) : 80.22120 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 13 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 13 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -2.80000E-01 MeV Emin = 2.62618E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -5.50000E-01 MeV Emin = 5.33490E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -5.60000E-01 MeV Emin = 5.33490E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -8.30000E-01 MeV Emin = 8.40000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 91 Q = -8.30000E-01 MeV Emin = 8.40000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 7 MT = 102 Q = 7.60100E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 350820 : (n,gamma) + 8 MT = 103 Q = -8.02080E-01 MeV Emin = 7.55949E-01 MeV frac = 1.00000E+00 Product nuclide = 340810 : (n,p) + 9 MT = 104 Q = -5.27710E+00 MeV Emin = 5.34288E+00 MeV frac = 1.00000E+00 Product nuclide = 34080.82c : (n,d) + 10 MT = 105 Q = -8.93030E+00 MeV Emin = 9.04162E+00 MeV frac = 1.00000E+00 Product nuclide = 34079.82c : (n,t) + 11 MT = 106 Q = -1.11120E+01 MeV Emin = 1.12505E+01 MeV frac = 1.00000E+00 Product nuclide = 330790 : (n,He-3) + 12 MT = 107 Q = 4.10310E-01 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 330780 : (n,alpha) + 13 MT = 111 Q = -1.24180E+01 MeV Emin = 1.25728E+01 MeV frac = 1.00000E+00 Product nuclide = 330800 : (n,2p) + + 7 additional transport branches: + + 1 MT = 102 Q = 7.60100E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 350821 : (n,gamma) + 2 MT = 103 Q = -8.02080E-01 MeV Emin = 7.55949E-01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 104 Q = -5.27710E+00 MeV Emin = 5.34288E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 4 MT = 105 Q = -8.93030E+00 MeV Emin = 9.04162E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 5 MT = 106 Q = -1.11120E+01 MeV Emin = 1.12505E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 6 MT = 107 Q = 4.10310E-01 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 7 MT = 111 Q = -1.24180E+01 MeV Emin = 1.25728E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 7.55949E-01 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.34288E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.04162E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.12505E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.62500E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 2.62618E-01 MeV : total inelastic scattering + + Nuclide 78 / 1657 : 36080.82c -- krypton 80 (Kr-80) + + Pointers : 529500 27009 + Primary type : Transport + Nuclide ZAI : 360800 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Kr80.ACE + Atomic weight (AW) : 79.91632 + Atomic weight ratio (AWR) : 79.22980 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 16 reaction channels + - 7 special reactions + - 8 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 16 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.15250E+01 MeV Emin = 1.16900E+01 MeV frac = 1.00000E+00 Product nuclide = 360790 : (n,2n) + 3 MT = 51 Q = -6.16000E-01 MeV Emin = 6.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 4 MT = 52 Q = -1.25600E+00 MeV Emin = 1.25000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 5 MT = 53 Q = -1.32000E+00 MeV Emin = 1.33666E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 6 MT = 54 Q = -1.43600E+00 MeV Emin = 1.42706E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 7 MT = 55 Q = -2.39000E+00 MeV Emin = 2.42017E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 8 MT = 56 Q = -3.40000E+00 MeV Emin = 3.44291E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 9 MT = 91 Q = -6.16000E-01 MeV Emin = 1.34350E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 10 MT = 102 Q = 7.85000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 360810 : (n,gamma) + 11 MT = 103 Q = -1.22800E+00 MeV Emin = 1.95000E+00 MeV frac = 1.00000E+00 Product nuclide = 350800 : (n,p) + 12 MT = 104 Q = -6.88640E+00 MeV Emin = 9.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 35079.82c : (n,d) + 13 MT = 105 Q = -1.13220E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 350780 : (n,t) + 14 MT = 106 Q = -7.72960E+00 MeV Emin = 7.82716E+00 MeV frac = 1.00000E+00 Product nuclide = 34078.82c : (n,He-3) + 15 MT = 107 Q = 2.35600E+00 MeV Emin = 1.95000E+00 MeV frac = 1.00000E+00 Product nuclide = 34077.82c : (n,alpha) + 16 MT = 111 Q = -8.47990E+00 MeV Emin = 8.58693E+00 MeV frac = 1.00000E+00 Product nuclide = 34079.82c : (n,2p) + + 7 additional transport branches: + + 1 MT = 102 Q = 7.85000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 360811 : (n,gamma) + 2 MT = 103 Q = -1.22800E+00 MeV Emin = 1.95000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 104 Q = -6.88640E+00 MeV Emin = 9.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 4 MT = 105 Q = -1.13220E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 5 MT = 106 Q = -7.72960E+00 MeV Emin = 7.82716E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 6 MT = 107 Q = 2.35600E+00 MeV Emin = 1.95000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 7 MT = 111 Q = -8.47990E+00 MeV Emin = 8.58693E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.95000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 9.50000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.45000E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 7.82716E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.95000E+00 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 6.00000E-01 MeV : total inelastic scattering + + Nuclide 79 / 1657 : 36082.82c -- krypton 82 (Kr-82) + + Pointers : 532789 27055 + Primary type : Transport + Nuclide ZAI : 360820 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Kr82.ACE + Atomic weight (AW) : 81.91348 + Atomic weight ratio (AWR) : 81.20980 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 19 reaction channels + - 7 special reactions + - 8 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 19 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.09800E+01 MeV Emin = 1.12000E+01 MeV frac = 1.00000E+00 Product nuclide = 360810 : (n,2n) + 3 MT = 51 Q = -7.77000E-01 MeV Emin = 6.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 4 MT = 52 Q = -1.47500E+00 MeV Emin = 1.40000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 5 MT = 53 Q = -1.82000E+00 MeV Emin = 1.70000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 6 MT = 54 Q = -2.09400E+00 MeV Emin = 2.11979E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 7 MT = 55 Q = -2.17200E+00 MeV Emin = 2.19875E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 8 MT = 56 Q = -2.42700E+00 MeV Emin = 2.45689E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 9 MT = 57 Q = -2.64800E+00 MeV Emin = 2.68061E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 10 MT = 58 Q = -2.82800E+00 MeV Emin = 2.86282E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 11 MT = 59 Q = -2.92000E+00 MeV Emin = 2.95596E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 12 MT = 91 Q = -7.77000E-01 MeV Emin = 2.45600E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 13 MT = 102 Q = 7.46700E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 36083.82c : (n,gamma) + 14 MT = 103 Q = -2.30600E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 350820 : (n,p) + 15 MT = 104 Q = -7.76610E+00 MeV Emin = 7.86173E+00 MeV frac = 1.00000E+00 Product nuclide = 35081.82c : (n,d) + 16 MT = 105 Q = -1.15850E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 350800 : (n,t) + 17 MT = 106 Q = -9.69460E+00 MeV Emin = 1.70000E+01 MeV frac = 1.00000E+00 Product nuclide = 34080.82c : (n,He-3) + 18 MT = 107 Q = 1.11050E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 34079.82c : (n,alpha) + 19 MT = 111 Q = -1.07030E+01 MeV Emin = 1.08348E+01 MeV frac = 1.00000E+00 Product nuclide = 340810 : (n,2p) + + 7 additional transport branches: + + 1 MT = 102 Q = 7.46700E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 360831 : (n,gamma) + 2 MT = 103 Q = -2.30600E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 104 Q = -7.76610E+00 MeV Emin = 7.86173E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 4 MT = 105 Q = -1.15850E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 5 MT = 106 Q = -9.69460E+00 MeV Emin = 1.70000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 6 MT = 107 Q = 1.11050E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 7 MT = 111 Q = -1.07030E+01 MeV Emin = 1.08348E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.86173E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.45000E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.70000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 5.00000E+00 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 6.00000E-01 MeV : total inelastic scattering + + Nuclide 80 / 1657 : 36083.82c -- krypton 83 (Kr-83) + + Pointers : 535328 27101 + Primary type : Transport + Nuclide ZAI : 360830 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Kr83.ACE + Atomic weight (AW) : 82.91428 + Atomic weight ratio (AWR) : 82.20200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 28 reaction channels + - 7 special reactions + - 11 transmutation reactions + - 8 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 28 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.46240E+00 MeV Emin = 7.55320E+00 MeV frac = 1.00000E+00 Product nuclide = 36082.82c : (n,2n) + 3 MT = 17 Q = -1.84280E+01 MeV Emin = 1.86522E+01 MeV frac = 1.00000E+00 Product nuclide = 360810 : (n,3n) + 4 MT = 22 Q = -6.48720E+00 MeV Emin = 1.22500E+01 MeV frac = 1.00000E+00 Product nuclide = 34079.82c : (n,nalpha) + 5 MT = 28 Q = -9.77250E+00 MeV Emin = 1.17500E+01 MeV frac = 1.00000E+00 Product nuclide = 350820 : (n,np) + 6 MT = 51 Q = -9.40000E-03 MeV Emin = 9.25000E-03 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -4.15600E-02 MeV Emin = 4.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -5.62000E-01 MeV Emin = 5.66002E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -5.71200E-01 MeV Emin = 5.77175E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -6.90150E-01 MeV Emin = 6.96888E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -7.98900E-01 MeV Emin = 7.57543E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -8.11000E-01 MeV Emin = 8.20410E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -1.01190E+00 MeV Emin = 9.16410E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -1.10290E+00 MeV Emin = 1.07026E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -1.12200E+00 MeV Emin = 1.12596E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -1.17040E+00 MeV Emin = 1.16013E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -1.22190E+00 MeV Emin = 1.23562E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -1.27790E+00 MeV Emin = 1.26621E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -1.51680E+00 MeV Emin = 1.53190E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -1.52920E+00 MeV Emin = 1.53985E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 21 MT = 91 Q = -1.52920E+00 MeV Emin = 1.53985E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 22 MT = 102 Q = 1.05206E+01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 36084.82c : (n,gamma) + 23 MT = 103 Q = -1.90030E-01 MeV Emin = 1.53985E+00 MeV frac = 1.00000E+00 Product nuclide = 350830 : (n,p) + 24 MT = 104 Q = -7.54790E+00 MeV Emin = 1.02500E+01 MeV frac = 1.00000E+00 Product nuclide = 350820 : (n,d) + 25 MT = 105 Q = -8.88320E+00 MeV Emin = 8.99130E+00 MeV frac = 1.00000E+00 Product nuclide = 35081.82c : (n,t) + 26 MT = 106 Q = -1.04500E+01 MeV Emin = 1.65000E+01 MeV frac = 1.00000E+00 Product nuclide = 340810 : (n,He-3) + 27 MT = 107 Q = 3.42600E+00 MeV Emin = 2.28125E-07 MeV frac = 1.00000E+00 Product nuclide = 34080.82c : (n,alpha) + 28 MT = 111 Q = -8.89320E+00 MeV Emin = 1.72500E+01 MeV frac = 1.00000E+00 Product nuclide = 34082.82c : (n,2p) + + 8 additional transport branches: + + 1 MT = 22 Q = -6.48720E+00 MeV Emin = 1.22500E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -9.77250E+00 MeV Emin = 1.17500E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -1.90030E-01 MeV Emin = 1.53985E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -7.54790E+00 MeV Emin = 1.02500E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -8.88320E+00 MeV Emin = 8.99130E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 106 Q = -1.04500E+01 MeV Emin = 1.65000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 7 MT = 107 Q = 3.42600E+00 MeV Emin = 2.28125E-07 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 8 MT = 111 Q = -8.89320E+00 MeV Emin = 1.72500E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.53985E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.02500E+01 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 8.99130E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.65000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 2.28125E-07 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 2.18750E-07 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 9.25000E-03 MeV : total inelastic scattering + + Nuclide 81 / 1657 : 36084.82c -- krypton 84 (Kr-84) + + Pointers : 538977 27147 + Primary type : Transport + Nuclide ZAI : 360840 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Kr84.ACE + Atomic weight (AW) : 83.91144 + Atomic weight ratio (AWR) : 83.19060 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 23 reaction channels + - 7 special reactions + - 8 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 23 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.05180E+01 MeV Emin = 1.06444E+01 MeV frac = 1.00000E+00 Product nuclide = 36083.82c : (n,2n) + 3 MT = 51 Q = -8.82000E-01 MeV Emin = 8.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 4 MT = 52 Q = -1.83400E+00 MeV Emin = 1.70000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 5 MT = 53 Q = -1.90000E+00 MeV Emin = 1.90000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 6 MT = 54 Q = -2.08600E+00 MeV Emin = 2.11108E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 7 MT = 55 Q = -2.33700E+00 MeV Emin = 2.36509E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 8 MT = 56 Q = -2.70500E+00 MeV Emin = 2.73752E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 9 MT = 57 Q = -2.77500E+00 MeV Emin = 2.80836E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 10 MT = 58 Q = -3.04800E+00 MeV Emin = 3.08464E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 11 MT = 59 Q = -3.22500E+00 MeV Emin = 3.26377E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 12 MT = 60 Q = -3.44700E+00 MeV Emin = 3.48844E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 13 MT = 61 Q = -3.57000E+00 MeV Emin = 3.61292E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 14 MT = 62 Q = -3.65000E+00 MeV Emin = 3.69388E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 15 MT = 63 Q = -3.72100E+00 MeV Emin = 3.76573E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 16 MT = 91 Q = -8.82000E-01 MeV Emin = 8.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 17 MT = 102 Q = 7.11100E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 36085.82c : (n,gamma) + 18 MT = 103 Q = -3.92000E+00 MeV Emin = 5.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 350840 : (n,p) + 19 MT = 104 Q = -8.48040E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 350830 : (n,d) + 20 MT = 105 Q = -1.18080E+01 MeV Emin = 1.19499E+01 MeV frac = 1.00000E+00 Product nuclide = 350820 : (n,t) + 21 MT = 106 Q = -1.17070E+01 MeV Emin = 1.90000E+01 MeV frac = 1.00000E+00 Product nuclide = 34082.82c : (n,He-3) + 22 MT = 107 Q = -3.94400E-01 MeV Emin = 3.99000E-01 MeV frac = 1.00000E+00 Product nuclide = 340810 : (n,alpha) + 23 MT = 111 Q = -1.35240E+01 MeV Emin = 1.36866E+01 MeV frac = 1.00000E+00 Product nuclide = 340830 : (n,2p) + + 7 additional transport branches: + + 1 MT = 102 Q = 7.11100E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 360851 : (n,gamma) + 2 MT = 103 Q = -3.92000E+00 MeV Emin = 5.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 104 Q = -8.48040E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 4 MT = 105 Q = -1.18080E+01 MeV Emin = 1.19499E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 5 MT = 106 Q = -1.17070E+01 MeV Emin = 1.90000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 6 MT = 107 Q = -3.94400E-01 MeV Emin = 3.99000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 7 MT = 111 Q = -1.35240E+01 MeV Emin = 1.36866E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 5.50000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.10000E+01 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.19499E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.90000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 3.99000E-01 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 8.00000E-01 MeV : total inelastic scattering + + Nuclide 82 / 1657 : 36085.82c -- krypton 85 (Kr-85) + + Pointers : 541808 27193 + Primary type : Transport + Nuclide ZAI : 360850 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Kr85.ACE + Atomic weight (AW) : 84.91254 + Atomic weight ratio (AWR) : 84.18310 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 3.39E+08 seconds (10.8 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 10 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 6 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 10 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -3.05000E-01 MeV Emin = 2.81465E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 91 Q = -9.88270E-01 MeV Emin = 9.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 4 MT = 102 Q = 9.98000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 36086.82c : (n,gamma) + 5 MT = 103 Q = -2.01850E+00 MeV Emin = 2.04248E+00 MeV frac = 1.00000E+00 Product nuclide = 350850 : (n,p) + 6 MT = 104 Q = -8.77410E+00 MeV Emin = 8.87833E+00 MeV frac = 1.00000E+00 Product nuclide = 350840 : (n,d) + 7 MT = 105 Q = -9.32170E+00 MeV Emin = 9.43243E+00 MeV frac = 1.00000E+00 Product nuclide = 350830 : (n,t) + 8 MT = 106 Q = -1.29170E+01 MeV Emin = 1.30704E+01 MeV frac = 1.00000E+00 Product nuclide = 340830 : (n,He-3) + 9 MT = 107 Q = 1.76000E+00 MeV Emin = 4.81250E-02 MeV frac = 1.00000E+00 Product nuclide = 34082.82c : (n,alpha) + 10 MT = 111 Q = -1.20320E+01 MeV Emin = 1.21749E+01 MeV frac = 1.00000E+00 Product nuclide = 340840 : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = -2.01850E+00 MeV Emin = 2.04248E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -8.77410E+00 MeV Emin = 8.87833E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -9.32170E+00 MeV Emin = 9.43243E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -1.29170E+01 MeV Emin = 1.30704E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 1.76000E+00 MeV Emin = 4.81250E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -1.20320E+01 MeV Emin = 1.21749E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.04248E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.87833E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.43243E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.30704E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.81250E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 2.81465E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.87100E-01 MeV frac = 1.00000E+00 Product nuclide = 37085.82c : beta- + + Nuclide 83 / 1657 : 36086.82c -- krypton 86 (Kr-86) + + Pointers : 544694 27239 + Primary type : Transport + Nuclide ZAI : 360860 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Kr86.ACE + Atomic weight (AW) : 85.91062 + Atomic weight ratio (AWR) : 85.17260 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 25 reaction channels + - 7 special reactions + - 9 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 25 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -9.86000E+00 MeV Emin = 9.99000E+00 MeV frac = 1.00000E+00 Product nuclide = 36085.82c : (n,2n) + 3 MT = 17 Q = -1.69710E+01 MeV Emin = 1.73000E+01 MeV frac = 1.00000E+00 Product nuclide = 36084.82c : (n,3n) + 4 MT = 51 Q = -1.56300E+00 MeV Emin = 1.58000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 5 MT = 52 Q = -2.24800E+00 MeV Emin = 2.27439E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 6 MT = 53 Q = -2.35500E+00 MeV Emin = 2.38265E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 7 MT = 54 Q = -2.73300E+00 MeV Emin = 2.76509E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 8 MT = 55 Q = -3.10900E+00 MeV Emin = 3.14550E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 9 MT = 56 Q = -3.54200E+00 MeV Emin = 3.58359E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 10 MT = 57 Q = -3.83200E+00 MeV Emin = 3.87699E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 11 MT = 58 Q = -3.95900E+00 MeV Emin = 4.00548E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 12 MT = 59 Q = -4.11100E+00 MeV Emin = 4.15927E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 13 MT = 60 Q = -4.19400E+00 MeV Emin = 4.24324E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 14 MT = 61 Q = -4.29800E+00 MeV Emin = 4.34846E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 15 MT = 62 Q = -4.66800E+00 MeV Emin = 4.72281E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 16 MT = 63 Q = -4.82600E+00 MeV Emin = 4.88266E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 17 MT = 64 Q = -4.94800E+00 MeV Emin = 5.00610E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 18 MT = 91 Q = -1.56300E+00 MeV Emin = 1.58601E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 19 MT = 102 Q = 5.51100E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 360870 : (n,gamma) + 20 MT = 103 Q = -6.52000E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 350860 : (n,p) + 21 MT = 104 Q = -9.65540E+00 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 350850 : (n,d) + 22 MT = 105 Q = -1.24100E+01 MeV Emin = 1.55000E+01 MeV frac = 1.00000E+00 Product nuclide = 350840 : (n,t) + 23 MT = 106 Q = -1.41760E+01 MeV Emin = 1.43424E+01 MeV frac = 1.00000E+00 Product nuclide = 340840 : (n,He-3) + 24 MT = 107 Q = -2.20580E+00 MeV Emin = 2.23170E+00 MeV frac = 1.00000E+00 Product nuclide = 340830 : (n,alpha) + 25 MT = 111 Q = -1.71930E+01 MeV Emin = 1.73949E+01 MeV frac = 1.00000E+00 Product nuclide = 340850 : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = -6.52000E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -9.65540E+00 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -1.24100E+01 MeV Emin = 1.55000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -1.41760E+01 MeV Emin = 1.43424E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = -2.20580E+00 MeV Emin = 2.23170E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -1.71930E+01 MeV Emin = 1.73949E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 8.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.25000E+01 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.55000E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.43424E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 2.23170E+00 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 1.58000E+00 MeV : total inelastic scattering + + Nuclide 84 / 1657 : 37085.82c -- rubidium 85 (Rb-85) + + Pointers : 572577 31241 + Primary type : Transport + Nuclide ZAI : 370850 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Rb85.ACE + Atomic weight (AW) : 84.91184 + Atomic weight ratio (AWR) : 84.18240 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 12 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 12 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -1.51300E-01 MeV Emin = 1.52500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -5.14000E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -8.70000E-01 MeV Emin = 8.80000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 91 Q = -9.88270E-01 MeV Emin = 9.70084E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 6 MT = 102 Q = 8.65040E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 37086.82c : (n,gamma) + 7 MT = 103 Q = 9.56580E-02 MeV Emin = 4.75000E-02 MeV frac = 1.00000E+00 Product nuclide = 36085.82c : (n,p) + 8 MT = 104 Q = -4.78950E+00 MeV Emin = 4.84640E+00 MeV frac = 1.00000E+00 Product nuclide = 36084.82c : (n,d) + 9 MT = 105 Q = -9.04910E+00 MeV Emin = 9.15659E+00 MeV frac = 1.00000E+00 Product nuclide = 36083.82c : (n,t) + 10 MT = 106 Q = -9.99030E+00 MeV Emin = 1.01090E+01 MeV frac = 1.00000E+00 Product nuclide = 350830 : (n,He-3) + 11 MT = 107 Q = 9.85360E-01 MeV Emin = 4.75000E-02 MeV frac = 1.00000E+00 Product nuclide = 350820 : (n,alpha) + 12 MT = 111 Q = -1.09020E+01 MeV Emin = 1.10315E+01 MeV frac = 1.00000E+00 Product nuclide = 350840 : (n,2p) + + 7 additional transport branches: + + 1 MT = 102 Q = 8.65040E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 370861 : (n,gamma) + 2 MT = 103 Q = 9.56580E-02 MeV Emin = 4.75000E-02 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 104 Q = -4.78950E+00 MeV Emin = 4.84640E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 4 MT = 105 Q = -9.04910E+00 MeV Emin = 9.15659E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 5 MT = 106 Q = -9.99030E+00 MeV Emin = 1.01090E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 6 MT = 107 Q = 9.85360E-01 MeV Emin = 4.75000E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 7 MT = 111 Q = -1.09020E+01 MeV Emin = 1.10315E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.75000E-02 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 4.84640E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.15659E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.01090E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.75000E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 1.52500E-01 MeV : total inelastic scattering + + Nuclide 85 / 1657 : 37086.82c -- rubidium 86 (Rb-86) + + Pointers : 574605 31287 + Primary type : Transport + Nuclide ZAI : 370860 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Rb86.ACE + Atomic weight (AW) : 85.91122 + Atomic weight ratio (AWR) : 85.17320 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.61E+06 seconds (18.6 days) + Specific ingestion toxicity : 2.80E-09 Sv/Bq + Specific inhalation toxicity : 9.30E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 10 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 6 transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 10 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -5.60000E-01 MeV Emin = 5.49928E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 91 Q = -5.63390E-01 MeV Emin = 5.68287E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 4 MT = 102 Q = 1.03600E+01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 37087.82c : (n,gamma) + 5 MT = 103 Q = 1.30750E+00 MeV Emin = 4.81250E-02 MeV frac = 1.00000E+00 Product nuclide = 36086.82c : (n,p) + 6 MT = 104 Q = -6.32790E+00 MeV Emin = 6.40219E+00 MeV frac = 1.00000E+00 Product nuclide = 36085.82c : (n,d) + 7 MT = 105 Q = -7.18140E+00 MeV Emin = 7.26572E+00 MeV frac = 1.00000E+00 Product nuclide = 36084.82c : (n,t) + 8 MT = 106 Q = -1.18350E+01 MeV Emin = 1.19740E+01 MeV frac = 1.00000E+00 Product nuclide = 350840 : (n,He-3) + 9 MT = 107 Q = 1.93310E+00 MeV Emin = 4.81250E-02 MeV frac = 1.00000E+00 Product nuclide = 350830 : (n,alpha) + 10 MT = 111 Q = -1.05700E+01 MeV Emin = 1.06941E+01 MeV frac = 1.00000E+00 Product nuclide = 350850 : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = 1.30750E+00 MeV Emin = 4.81250E-02 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -6.32790E+00 MeV Emin = 6.40219E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -7.18140E+00 MeV Emin = 7.26572E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -1.18350E+01 MeV Emin = 1.19740E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 1.93310E+00 MeV Emin = 4.81250E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -1.05700E+01 MeV Emin = 1.06941E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.81250E-02 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.40219E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 7.26572E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.19740E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.81250E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 5.49928E-01 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 2 Q = 5.18000E-01 MeV frac = 5.20000E-05 Product nuclide = 36086.82c : EC/beta+ + 2 RTYP = 1 Q = 1.77430E+00 MeV frac = 9.99950E-01 Product nuclide = 38086.82c : beta- + + Nuclide 86 / 1657 : 37087.82c -- rubidium 87 (Rb-87) + + Pointers : 577113 31333 + Primary type : Transport + Nuclide ZAI : 370870 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Rb87.ACE + Atomic weight (AW) : 86.90920 + Atomic weight ratio (AWR) : 86.16260 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.52E+18 seconds (48.1 billion years) + Specific ingestion toxicity : 1.50E-09 Sv/Bq + Specific inhalation toxicity : 5.00E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 11 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 6 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 11 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -4.05000E-01 MeV Emin = 3.89850E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -8.50000E-01 MeV Emin = 8.19902E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 91 Q = -8.50000E-01 MeV Emin = 8.19902E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 5 MT = 102 Q = 6.08300E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 370880 : (n,gamma) + 6 MT = 103 Q = -3.10500E+00 MeV Emin = 3.14104E+00 MeV frac = 1.00000E+00 Product nuclide = 360870 : (n,p) + 7 MT = 104 Q = -6.39480E+00 MeV Emin = 6.46902E+00 MeV frac = 1.00000E+00 Product nuclide = 36086.82c : (n,d) + 8 MT = 105 Q = -9.99850E+00 MeV Emin = 1.01145E+01 MeV frac = 1.00000E+00 Product nuclide = 36085.82c : (n,t) + 9 MT = 106 Q = -1.27810E+01 MeV Emin = 1.29293E+01 MeV frac = 1.00000E+00 Product nuclide = 350850 : (n,He-3) + 10 MT = 107 Q = -1.18980E+00 MeV Emin = 1.20336E+00 MeV frac = 1.00000E+00 Product nuclide = 350840 : (n,alpha) + 11 MT = 111 Q = -1.51370E+01 MeV Emin = 1.53127E+01 MeV frac = 1.00000E+00 Product nuclide = 350860 : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = -3.10500E+00 MeV Emin = 3.14104E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -6.39480E+00 MeV Emin = 6.46902E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -9.99850E+00 MeV Emin = 1.01145E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -1.27810E+01 MeV Emin = 1.29293E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = -1.18980E+00 MeV Emin = 1.20336E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -1.51370E+01 MeV Emin = 1.53127E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.14104E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.46902E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.01145E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.29293E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.20336E+00 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 3.89850E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.83300E-01 MeV frac = 1.00000E+00 Product nuclide = 38087.82c : beta- + + Nuclide 87 / 1657 : 38086.82c -- strontium 86 (Sr-86) + + Pointers : 618703 34001 + Primary type : Transport + Nuclide ZAI : 380860 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Sr86.ACE + Atomic weight (AW) : 85.90931 + Atomic weight ratio (AWR) : 85.17130 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 16 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 16 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -1.08000E+00 MeV Emin = 1.09020E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -1.86000E+00 MeV Emin = 1.74090E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -2.23000E+00 MeV Emin = 2.25620E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -2.48000E+00 MeV Emin = 2.50912E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -2.68000E+00 MeV Emin = 2.71150E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -3.00000E+00 MeV Emin = 3.03522E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 57 Q = -3.19000E+00 MeV Emin = 3.22750E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 9 MT = 91 Q = -3.16280E+00 MeV Emin = 3.20000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 10 MT = 102 Q = 8.42830E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 38087.82c : (n,gamma) + 11 MT = 103 Q = -9.91450E-01 MeV Emin = 1.00288E+00 MeV frac = 1.00000E+00 Product nuclide = 37086.82c : (n,p) + 12 MT = 104 Q = -7.41500E+00 MeV Emin = 7.50206E+00 MeV frac = 1.00000E+00 Product nuclide = 37085.82c : (n,d) + 13 MT = 105 Q = -1.16340E+01 MeV Emin = 1.17706E+01 MeV frac = 1.00000E+00 Product nuclide = 370840 : (n,t) + 14 MT = 106 Q = -8.93710E+00 MeV Emin = 9.04203E+00 MeV frac = 1.00000E+00 Product nuclide = 36084.82c : (n,He-3) + 15 MT = 107 Q = 1.11860E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 36083.82c : (n,alpha) + 16 MT = 111 Q = -9.54340E+00 MeV Emin = 9.65545E+00 MeV frac = 1.00000E+00 Product nuclide = 36085.82c : (n,2p) + + 7 additional transport branches: + + 1 MT = 102 Q = 8.42830E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 380871 : (n,gamma) + 2 MT = 103 Q = -9.91450E-01 MeV Emin = 1.00288E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 104 Q = -7.41500E+00 MeV Emin = 7.50206E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 4 MT = 105 Q = -1.16340E+01 MeV Emin = 1.17706E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 5 MT = 106 Q = -8.93710E+00 MeV Emin = 9.04203E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 6 MT = 107 Q = 1.11860E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 7 MT = 111 Q = -9.54340E+00 MeV Emin = 9.65545E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.00288E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.50206E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.17706E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 9.04203E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.62500E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 1.09020E+00 MeV : total inelastic scattering + + Nuclide 88 / 1657 : 38087.82c -- strontium 87 (Sr-87) + + Pointers : 621023 34047 + Primary type : Transport + Nuclide ZAI : 380870 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Sr87.ACE + Atomic weight (AW) : 86.90889 + Atomic weight ratio (AWR) : 86.16230 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 16 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 16 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -3.88000E-01 MeV Emin = 3.70000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -8.71000E-01 MeV Emin = 8.79006E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -1.22000E+00 MeV Emin = 1.12500E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -1.70000E+00 MeV Emin = 1.60000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -2.10000E+00 MeV Emin = 2.12440E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -2.39000E+00 MeV Emin = 2.41774E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 57 Q = -2.61000E+00 MeV Emin = 2.64030E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 9 MT = 91 Q = -2.58990E+00 MeV Emin = 2.62000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 10 MT = 102 Q = 1.11130E+01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 38088.82c : (n,gamma) + 11 MT = 103 Q = 5.09310E-01 MeV Emin = 4.81250E-02 MeV frac = 1.00000E+00 Product nuclide = 37087.82c : (n,p) + 12 MT = 104 Q = -7.19290E+00 MeV Emin = 7.27638E+00 MeV frac = 1.00000E+00 Product nuclide = 37086.82c : (n,d) + 13 MT = 105 Q = -9.58480E+00 MeV Emin = 9.69604E+00 MeV frac = 1.00000E+00 Product nuclide = 37085.82c : (n,t) + 14 MT = 106 Q = -1.02530E+01 MeV Emin = 1.03720E+01 MeV frac = 1.00000E+00 Product nuclide = 36085.82c : (n,He-3) + 15 MT = 107 Q = 3.20840E+00 MeV Emin = 4.81250E-02 MeV frac = 1.00000E+00 Product nuclide = 36084.82c : (n,alpha) + 16 MT = 111 Q = -8.10950E+00 MeV Emin = 8.20362E+00 MeV frac = 1.00000E+00 Product nuclide = 36086.82c : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = 5.09310E-01 MeV Emin = 4.81250E-02 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -7.19290E+00 MeV Emin = 7.27638E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -9.58480E+00 MeV Emin = 9.69604E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -1.02530E+01 MeV Emin = 1.03720E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 3.20840E+00 MeV Emin = 4.81250E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -8.10950E+00 MeV Emin = 8.20362E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.81250E-02 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.27638E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.69604E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.03720E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.81250E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 3.70000E-01 MeV : total inelastic scattering + + Nuclide 89 / 1657 : 38088.82c -- strontium 88 (Sr-88) + + Pointers : 623849 34093 + Primary type : Transport + Nuclide ZAI : 380880 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Sr88.ACE + Atomic weight (AW) : 87.90566 + Atomic weight ratio (AWR) : 87.15050 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 14 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 14 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -1.84000E+00 MeV Emin = 1.79583E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -2.73000E+00 MeV Emin = 2.76133E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -3.24000E+00 MeV Emin = 3.27720E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -3.52000E+00 MeV Emin = 3.56040E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -3.68000E+00 MeV Emin = 3.72223E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 91 Q = -3.64820E+00 MeV Emin = 3.69006E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 8 MT = 102 Q = 6.36010E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 38089.82c : (n,gamma) + 9 MT = 103 Q = -4.52440E+00 MeV Emin = 4.57632E+00 MeV frac = 1.00000E+00 Product nuclide = 370880 : (n,p) + 10 MT = 104 Q = -8.37630E+00 MeV Emin = 8.47241E+00 MeV frac = 1.00000E+00 Product nuclide = 37087.82c : (n,d) + 11 MT = 105 Q = -1.20470E+01 MeV Emin = 1.21852E+01 MeV frac = 1.00000E+00 Product nuclide = 37086.82c : (n,t) + 12 MT = 106 Q = -1.15040E+01 MeV Emin = 1.16360E+01 MeV frac = 1.00000E+00 Product nuclide = 36086.82c : (n,He-3) + 13 MT = 107 Q = -7.92030E-01 MeV Emin = 8.00953E-01 MeV frac = 1.00000E+00 Product nuclide = 36085.82c : (n,alpha) + 14 MT = 111 Q = -1.37050E+01 MeV Emin = 1.38623E+01 MeV frac = 1.00000E+00 Product nuclide = 360870 : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = -4.52440E+00 MeV Emin = 4.57632E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -8.37630E+00 MeV Emin = 8.47241E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -1.20470E+01 MeV Emin = 1.21852E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -1.15040E+01 MeV Emin = 1.16360E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = -7.92030E-01 MeV Emin = 8.00953E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -1.37050E+01 MeV Emin = 1.38623E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.57632E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.47241E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.21852E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.16360E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 8.00953E-01 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 1.79583E+00 MeV : total inelastic scattering + + Nuclide 90 / 1657 : 38089.82c -- strontium 89 (Sr-89) + + Pointers : 625931 34139 + Primary type : Transport + Nuclide ZAI : 380890 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Sr89.ACE + Atomic weight (AW) : 88.90746 + Atomic weight ratio (AWR) : 88.14370 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 4.37E+06 seconds (50.6 days) + Specific ingestion toxicity : 2.60E-09 Sv/Bq + Specific inhalation toxicity : 7.90E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 21 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 6 transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 21 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -1.05000E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -2.00000E+00 MeV Emin = 2.02270E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -2.31000E+00 MeV Emin = 2.33621E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -2.44000E+00 MeV Emin = 2.46770E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -2.59000E+00 MeV Emin = 2.61940E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -2.67000E+00 MeV Emin = 2.70030E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 57 Q = -2.75000E+00 MeV Emin = 2.78120E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 9 MT = 58 Q = -2.99000E+00 MeV Emin = 3.02392E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 10 MT = 59 Q = -3.18000E+00 MeV Emin = 3.21610E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 11 MT = 60 Q = -3.25000E+00 MeV Emin = 3.28690E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 12 MT = 61 Q = -3.50000E+00 MeV Emin = 3.53971E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 13 MT = 62 Q = -3.74000E+00 MeV Emin = 3.78243E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 14 MT = 91 Q = -3.70800E+00 MeV Emin = 3.75007E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 15 MT = 102 Q = 7.71000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 38090.82c : (n,gamma) + 16 MT = 103 Q = -3.70210E+00 MeV Emin = 3.74410E+00 MeV frac = 1.00000E+00 Product nuclide = 370890 : (n,p) + 17 MT = 104 Q = -8.66230E+00 MeV Emin = 8.76058E+00 MeV frac = 1.00000E+00 Product nuclide = 370880 : (n,d) + 18 MT = 105 Q = -8.48240E+00 MeV Emin = 8.57864E+00 MeV frac = 1.00000E+00 Product nuclide = 37087.82c : (n,t) + 19 MT = 106 Q = -1.23520E+01 MeV Emin = 1.24921E+01 MeV frac = 1.00000E+00 Product nuclide = 360870 : (n,He-3) + 20 MT = 107 Q = 2.70550E+00 MeV Emin = 4.75000E-02 MeV frac = 1.00000E+00 Product nuclide = 36086.82c : (n,alpha) + 21 MT = 111 Q = -1.30160E+01 MeV Emin = 1.31637E+01 MeV frac = 1.00000E+00 Product nuclide = 360880 : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = -3.70210E+00 MeV Emin = 3.74410E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -8.66230E+00 MeV Emin = 8.76058E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -8.48240E+00 MeV Emin = 8.57864E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -1.23520E+01 MeV Emin = 1.24921E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 2.70550E+00 MeV Emin = 4.75000E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -1.30160E+01 MeV Emin = 1.31637E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.74410E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.76058E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 8.57864E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.24921E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.75000E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 1.00000E+00 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.49510E+00 MeV frac = 9.99904E-01 Product nuclide = 39089.82c : beta- + 2 RTYP = 1 Q = 5.86100E-01 MeV frac = 9.64000E-05 Product nuclide = 390891 : beta- + + Nuclide 91 / 1657 : 38090.82c -- strontium 90 (Sr-90) + + Pointers : 628717 34185 + Primary type : Transport + Nuclide ZAI : 380900 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Sr90.ACE + Atomic weight (AW) : 89.90775 + Atomic weight ratio (AWR) : 89.13540 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 9.09E+08 seconds (28.8 years) + Specific ingestion toxicity : 2.80E-08 Sv/Bq + Specific inhalation toxicity : 1.60E-07 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 13 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 6 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 13 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -8.30000E-01 MeV Emin = 8.21896E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -1.69000E+00 MeV Emin = 1.70000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -1.94000E+00 MeV Emin = 1.90000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -2.23000E+00 MeV Emin = 2.25502E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 91 Q = -2.21520E+00 MeV Emin = 2.24005E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 7 MT = 102 Q = 5.96000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 380910 : (n,gamma) + 8 MT = 103 Q = -5.58020E+00 MeV Emin = 5.64281E+00 MeV frac = 1.00000E+00 Product nuclide = 370900 : (n,p) + 9 MT = 104 Q = -9.27870E+00 MeV Emin = 9.38280E+00 MeV frac = 1.00000E+00 Product nuclide = 370890 : (n,d) + 10 MT = 105 Q = -1.02070E+01 MeV Emin = 1.03215E+01 MeV frac = 1.00000E+00 Product nuclide = 370880 : (n,t) + 11 MT = 106 Q = -1.31010E+01 MeV Emin = 1.32480E+01 MeV frac = 1.00000E+00 Product nuclide = 360880 : (n,He-3) + 12 MT = 107 Q = 4.18620E-01 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 360870 : (n,alpha) + 13 MT = 111 Q = -1.56460E+01 MeV Emin = 1.58215E+01 MeV frac = 1.00000E+00 Product nuclide = 360890 : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = -5.58020E+00 MeV Emin = 5.64281E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -9.27870E+00 MeV Emin = 9.38280E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -1.02070E+01 MeV Emin = 1.03215E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -1.31010E+01 MeV Emin = 1.32480E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 4.18620E-01 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -1.56460E+01 MeV Emin = 1.58215E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 5.64281E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 9.38280E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.03215E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.32480E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.62500E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 8.21896E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.45900E-01 MeV frac = 1.00000E+00 Product nuclide = 39090.82c : beta- + + Nuclide 92 / 1657 : 39089.82c -- yttrium 89 (Y-89) + + Pointers : 646829 36623 + Primary type : Transport + Nuclide ZAI : 390890 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Y89.ACE + Atomic weight (AW) : 88.90585 + Atomic weight ratio (AWR) : 88.14210 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 42 reaction channels + - 82 special reactions + - 7 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 42 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.14760E+01 MeV Emin = 1.16062E+01 MeV frac = 1.00000E+00 Product nuclide = 390880 : (n,2n) + 3 MT = 22 Q = -7.95900E+00 MeV Emin = 1.15000E+01 MeV frac = 1.00000E+00 Product nuclide = 37085.82c : (n,nalpha) + 4 MT = 28 Q = -7.07100E+00 MeV Emin = 8.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 38088.82c : (n,np) + 5 MT = 41 Q = -1.81840E+01 MeV Emin = 1.95000E+01 MeV frac = 1.00000E+00 Product nuclide = 38087.82c : (n,2np) + 6 MT = 51 Q = -9.08960E-01 MeV Emin = 9.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.50726E+00 MeV Emin = 1.51218E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -1.74457E+00 MeV Emin = 1.70000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -2.22239E+00 MeV Emin = 2.24761E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -2.52987E+00 MeV Emin = 2.55857E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -2.56624E+00 MeV Emin = 2.59536E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -2.62204E+00 MeV Emin = 2.65179E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -2.87180E+00 MeV Emin = 2.90438E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -2.88120E+00 MeV Emin = 2.91389E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -2.89470E+00 MeV Emin = 2.92754E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -3.06760E+00 MeV Emin = 3.10240E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -3.10706E+00 MeV Emin = 3.14231E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -3.13890E+00 MeV Emin = 3.17451E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -3.24750E+00 MeV Emin = 3.28435E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -3.34308E+00 MeV Emin = 3.38101E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 21 MT = 66 Q = -3.41050E+00 MeV Emin = 3.44919E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 22 MT = 67 Q = -3.45120E+00 MeV Emin = 3.49036E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 23 MT = 68 Q = -3.50360E+00 MeV Emin = 3.54335E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 24 MT = 69 Q = -3.51560E+00 MeV Emin = 3.55549E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 25 MT = 70 Q = -3.55710E+00 MeV Emin = 3.59746E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 26 MT = 71 Q = -3.56000E+00 MeV Emin = 3.60039E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 27 MT = 72 Q = -3.62100E+00 MeV Emin = 3.66208E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 28 MT = 73 Q = -3.63030E+00 MeV Emin = 3.67149E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 29 MT = 74 Q = -3.71530E+00 MeV Emin = 3.75745E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 30 MT = 75 Q = -3.74770E+00 MeV Emin = 3.79022E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 31 MT = 76 Q = -3.75270E+00 MeV Emin = 3.79528E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 32 MT = 77 Q = -3.84810E+00 MeV Emin = 3.89176E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 27. excited state + 33 MT = 78 Q = -3.86230E+00 MeV Emin = 3.90612E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 28. excited state + 34 MT = 79 Q = -3.92400E+00 MeV Emin = 3.96852E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 29. excited state + 35 MT = 80 Q = -3.97690E+00 MeV Emin = 4.02202E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 30. excited state + 36 MT = 81 Q = -3.99160E+00 MeV Emin = 4.03689E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 31. excited state + 37 MT = 82 Q = -4.01530E+00 MeV Emin = 4.06086E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 32. excited state + 38 MT = 83 Q = -4.02280E+00 MeV Emin = 4.06844E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 33. excited state + 39 MT = 91 Q = -9.78894E-01 MeV Emin = 9.54642E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 40 MT = 102 Q = 6.85704E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 39090.82c : (n,gamma) + 41 MT = 103 Q = 0.00000E+00 MeV Emin = 1.88240E+00 MeV frac = 1.00000E+00 Product nuclide = 38089.82c : (n,p) + 42 MT = 107 Q = 0.00000E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 37086.82c : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = -7.95900E+00 MeV Emin = 1.15000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -7.07100E+00 MeV Emin = 8.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 41 Q = -1.81840E+01 MeV Emin = 1.95000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,2np) + 4 MT = 102 Q = 6.85704E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 390901 : (n,gamma) + 5 MT = 103 Q = 0.00000E+00 MeV Emin = 1.88240E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 107 Q = 0.00000E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 82 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.88240E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 3.00000E+00 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 5.31250E-04 MeV : damage-energy production + 4 MT = 600 Q = -7.13000E-01 MeV Emin = 1.88240E+00 MeV : (n,p) to ground state + 5 MT = 601 Q = -1.74500E+00 MeV Emin = 3.00000E+00 MeV : (n,p1) + 6 MT = 602 Q = -2.18636E+00 MeV Emin = 3.50000E+00 MeV : (n,p2) + 7 MT = 603 Q = -2.65321E+00 MeV Emin = 4.00000E+00 MeV : (n,p3) + 8 MT = 604 Q = -2.72060E+00 MeV Emin = 4.00000E+00 MeV : (n,p4) + 9 MT = 605 Q = -2.77040E+00 MeV Emin = 4.00000E+00 MeV : (n,p5) + 10 MT = 606 Q = -2.77440E+00 MeV Emin = 4.00000E+00 MeV : (n,p6) + 11 MT = 607 Q = -2.79180E+00 MeV Emin = 4.00000E+00 MeV : (n,p7) + 12 MT = 608 Q = -2.99319E+00 MeV Emin = 4.00000E+00 MeV : (n,p8) + 13 MT = 609 Q = -3.16464E+00 MeV Emin = 4.50000E+00 MeV : (n,p9) + 14 MT = 610 Q = -3.28312E+00 MeV Emin = 4.50000E+00 MeV : (n,p10) + 15 MT = 611 Q = -3.38800E+00 MeV Emin = 4.50000E+00 MeV : (n,p11) + 16 MT = 612 Q = -3.42013E+00 MeV Emin = 4.50000E+00 MeV : (n,p12) + 17 MT = 613 Q = -3.51800E+00 MeV Emin = 4.50000E+00 MeV : (n,p13) + 18 MT = 614 Q = -3.62900E+00 MeV Emin = 5.00000E+00 MeV : (n,p14) + 19 MT = 615 Q = -3.64360E+00 MeV Emin = 5.00000E+00 MeV : (n,p15) + 20 MT = 616 Q = -3.67470E+00 MeV Emin = 5.00000E+00 MeV : (n,p16) + 21 MT = 617 Q = -3.78600E+00 MeV Emin = 5.00000E+00 MeV : (n,p17) + 22 MT = 618 Q = -3.83900E+00 MeV Emin = 5.00000E+00 MeV : (n,p18) + 23 MT = 619 Q = -3.91300E+00 MeV Emin = 5.00000E+00 MeV : (n,p19) + 24 MT = 620 Q = -3.94091E+00 MeV Emin = 5.00000E+00 MeV : (n,p20) + 25 MT = 621 Q = -3.96200E+00 MeV Emin = 5.00000E+00 MeV : (n,p21) + 26 MT = 622 Q = -4.01612E+00 MeV Emin = 5.00000E+00 MeV : (n,p22) + 27 MT = 623 Q = -4.10080E+00 MeV Emin = 5.50000E+00 MeV : (n,p23) + 28 MT = 624 Q = -4.11680E+00 MeV Emin = 5.50000E+00 MeV : (n,p24) + 29 MT = 625 Q = -4.13400E+00 MeV Emin = 5.50000E+00 MeV : (n,p25) + 30 MT = 626 Q = -4.14606E+00 MeV Emin = 5.50000E+00 MeV : (n,p26) + 31 MT = 627 Q = -4.22168E+00 MeV Emin = 5.50000E+00 MeV : (n,p27) + 32 MT = 628 Q = -4.23710E+00 MeV Emin = 5.50000E+00 MeV : (n,p28) + 33 MT = 629 Q = -4.24900E+00 MeV Emin = 5.50000E+00 MeV : (n,p29) + 34 MT = 630 Q = -4.31180E+00 MeV Emin = 5.50000E+00 MeV : (n,p30) + 35 MT = 631 Q = -4.34700E+00 MeV Emin = 5.50000E+00 MeV : (n,p31) + 36 MT = 632 Q = -4.36472E+00 MeV Emin = 5.50000E+00 MeV : (n,p32) + 37 MT = 633 Q = -4.38480E+00 MeV Emin = 5.50000E+00 MeV : (n,p33) + 38 MT = 634 Q = -4.38900E+00 MeV Emin = 5.50000E+00 MeV : (n,p34) + 39 MT = 635 Q = -4.41282E+00 MeV Emin = 5.50000E+00 MeV : (n,p35) + 40 MT = 636 Q = -4.44070E+00 MeV Emin = 5.50000E+00 MeV : (n,p36) + 41 MT = 637 Q = -4.45800E+00 MeV Emin = 5.50000E+00 MeV : (n,p37) + 42 MT = 638 Q = -4.46330E+00 MeV Emin = 5.50000E+00 MeV : (n,p38) + 43 MT = 639 Q = -4.46800E+00 MeV Emin = 5.50000E+00 MeV : (n,p39) + 44 MT = 649 Q = -4.46800E+00 MeV Emin = 4.51869E+00 MeV : (n,p) to continuum + 45 MT = 800 Q = 6.91000E-01 MeV Emin = 3.00000E+00 MeV : (n,alpha) to ground state + 46 MT = 801 Q = 2.02800E-01 MeV Emin = 3.50000E+00 MeV : (n,a1) + 47 MT = 802 Q = 1.34950E-01 MeV Emin = 3.50000E+00 MeV : (n,a2) + 48 MT = 803 Q = 1.34000E-01 MeV Emin = 3.50000E+00 MeV : (n,a3) + 49 MT = 804 Q = -8.93000E-02 MeV Emin = 3.70000E+00 MeV : (n,a4) + 50 MT = 805 Q = -1.82200E-01 MeV Emin = 3.70000E+00 MeV : (n,a5) + 51 MT = 806 Q = -2.87700E-01 MeV Emin = 4.00000E+00 MeV : (n,a6) + 52 MT = 807 Q = -3.36200E-01 MeV Emin = 4.00000E+00 MeV : (n,a7) + 53 MT = 808 Q = -3.41700E-01 MeV Emin = 4.00000E+00 MeV : (n,a8) + 54 MT = 809 Q = -4.01800E-01 MeV Emin = 4.00000E+00 MeV : (n,a9) + 55 MT = 810 Q = -4.14600E-01 MeV Emin = 4.00000E+00 MeV : (n,a10) + 56 MT = 811 Q = -4.31000E-01 MeV Emin = 4.00000E+00 MeV : (n,a11) + 57 MT = 812 Q = -4.65000E-01 MeV Emin = 4.00000E+00 MeV : (n,a12) + 58 MT = 813 Q = -5.05400E-01 MeV Emin = 4.00000E+00 MeV : (n,a13) + 59 MT = 814 Q = -5.57000E-01 MeV Emin = 4.00000E+00 MeV : (n,a14) + 60 MT = 815 Q = -6.14100E-01 MeV Emin = 4.00000E+00 MeV : (n,a15) + 61 MT = 816 Q = -6.18000E-01 MeV Emin = 4.00000E+00 MeV : (n,a16) + 62 MT = 817 Q = -6.98400E-01 MeV Emin = 4.50000E+00 MeV : (n,a17) + 63 MT = 818 Q = -7.21000E-01 MeV Emin = 4.50000E+00 MeV : (n,a18) + 64 MT = 819 Q = -7.48000E-01 MeV Emin = 4.50000E+00 MeV : (n,a19) + 65 MT = 820 Q = -7.79800E-01 MeV Emin = 4.50000E+00 MeV : (n,a20) + 66 MT = 821 Q = -8.10700E-01 MeV Emin = 4.50000E+00 MeV : (n,a21) + 67 MT = 822 Q = -8.59000E-01 MeV Emin = 4.50000E+00 MeV : (n,a22) + 68 MT = 823 Q = -8.67500E-01 MeV Emin = 4.50000E+00 MeV : (n,a23) + 69 MT = 824 Q = -9.75800E-01 MeV Emin = 4.50000E+00 MeV : (n,a24) + 70 MT = 825 Q = -9.92700E-01 MeV Emin = 4.50000E+00 MeV : (n,a25) + 71 MT = 826 Q = -1.01820E+00 MeV Emin = 4.50000E+00 MeV : (n,a26) + 72 MT = 827 Q = -1.04700E+00 MeV Emin = 4.50000E+00 MeV : (n,a27) + 73 MT = 828 Q = -1.07000E+00 MeV Emin = 4.50000E+00 MeV : (n,a28) + 74 MT = 829 Q = -1.12900E+00 MeV Emin = 4.50000E+00 MeV : (n,a29) + 75 MT = 830 Q = -1.19830E+00 MeV Emin = 4.50000E+00 MeV : (n,a30) + 76 MT = 831 Q = -1.21000E+00 MeV Emin = 4.50000E+00 MeV : (n,a31) + 77 MT = 832 Q = -1.22610E+00 MeV Emin = 5.00000E+00 MeV : (n,a32) + 78 MT = 833 Q = -1.23510E+00 MeV Emin = 5.00000E+00 MeV : (n,a33) + 79 MT = 834 Q = -1.26210E+00 MeV Emin = 5.00000E+00 MeV : (n,a34) + 80 MT = 835 Q = -1.33390E+00 MeV Emin = 5.00000E+00 MeV : (n,a35) + 81 MT = 849 Q = -1.33390E+00 MeV Emin = 5.00000E+00 MeV : (n,alpha) to continuum + 82 MT = 4 Q = 0.00000E+00 MeV Emin = 9.00000E-01 MeV : total inelastic scattering + + Nuclide 93 / 1657 : 39090.82c -- yttrium 90 (Y-90) + + Pointers : 656820 36669 + Primary type : Transport + Nuclide ZAI : 390900 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Y90.ACE + Atomic weight (AW) : 89.90716 + Atomic weight ratio (AWR) : 89.13481 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.30E+05 seconds (2.67 days) + Specific ingestion toxicity : 2.70E-09 Sv/Bq + Specific inhalation toxicity : 1.50E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 11 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 7 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 11 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -2.02000E-01 MeV Emin = 2.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -6.92240E-01 MeV Emin = 6.95000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 91 Q = -6.92240E-01 MeV Emin = 6.95000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 5 MT = 102 Q = 8.17000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 39091.82c : (n,gamma) + 6 MT = 103 Q = 2.36580E-01 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 38090.82c : (n,p) + 7 MT = 104 Q = -5.34010E+00 MeV Emin = 5.40001E+00 MeV frac = 1.00000E+00 Product nuclide = 38089.82c : (n,d) + 8 MT = 105 Q = -5.44620E+00 MeV Emin = 5.50730E+00 MeV frac = 1.00000E+00 Product nuclide = 38088.82c : (n,t) + 9 MT = 106 Q = -1.07350E+01 MeV Emin = 1.08554E+01 MeV frac = 1.00000E+00 Product nuclide = 370880 : (n,He-3) + 10 MT = 107 Q = 3.76020E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 37087.82c : (n,alpha) + 11 MT = 111 Q = -1.12660E+01 MeV Emin = 1.13924E+01 MeV frac = 1.00000E+00 Product nuclide = 370890 : (n,2p) + + 7 additional transport branches: + + 1 MT = 102 Q = 8.17000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 390911 : (n,gamma) + 2 MT = 103 Q = 2.36580E-01 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 104 Q = -5.34010E+00 MeV Emin = 5.40001E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 4 MT = 105 Q = -5.44620E+00 MeV Emin = 5.50730E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 5 MT = 106 Q = -1.07350E+01 MeV Emin = 1.08554E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 6 MT = 107 Q = 3.76020E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 7 MT = 111 Q = -1.12660E+01 MeV Emin = 1.13924E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.62500E-02 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.40001E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 5.50730E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.08554E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.62500E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 2.00000E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.28010E+00 MeV frac = 1.00000E+00 Product nuclide = 40090.82c : beta- + + Nuclide 94 / 1657 : 39091.82c -- yttrium 91 (Y-91) + + Pointers : 659448 36715 + Primary type : Transport + Nuclide ZAI : 390910 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Y91.ACE + Atomic weight (AW) : 90.90735 + Atomic weight ratio (AWR) : 90.12641 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 5.06E+06 seconds (58.5 days) + Specific ingestion toxicity : 2.40E-09 Sv/Bq + Specific inhalation toxicity : 8.90E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 16 reaction channels + - 7 special reactions + - 6 transmutation reactions + - 5 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 16 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -5.55600E-01 MeV Emin = 5.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -6.52900E-01 MeV Emin = 6.53000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -9.25800E-01 MeV Emin = 8.93035E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -1.18690E+00 MeV Emin = 1.18750E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -1.30540E+00 MeV Emin = 1.30000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -1.47370E+00 MeV Emin = 1.44257E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 57 Q = -1.54590E+00 MeV Emin = 1.54500E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 9 MT = 58 Q = -1.58000E+00 MeV Emin = 1.59000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 10 MT = 91 Q = -1.58250E+00 MeV Emin = 1.59969E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 11 MT = 102 Q = 6.50000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 390920 : (n,gamma) + 12 MT = 104 Q = -5.47720E+00 MeV Emin = 5.53797E+00 MeV frac = 1.00000E+00 Product nuclide = 38090.82c : (n,d) + 13 MT = 105 Q = -7.02210E+00 MeV Emin = 7.10001E+00 MeV frac = 1.00000E+00 Product nuclide = 38089.82c : (n,t) + 14 MT = 106 Q = -1.14880E+01 MeV Emin = 1.16155E+01 MeV frac = 1.00000E+00 Product nuclide = 370890 : (n,He-3) + 15 MT = 107 Q = 1.89840E+00 MeV Emin = 4.75000E-02 MeV frac = 1.00000E+00 Product nuclide = 370880 : (n,alpha) + 16 MT = 111 Q = -1.32810E+01 MeV Emin = 1.34284E+01 MeV frac = 1.00000E+00 Product nuclide = 370900 : (n,2p) + + 5 additional transport branches: + + 1 MT = 104 Q = -5.47720E+00 MeV Emin = 5.53797E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 2 MT = 105 Q = -7.02210E+00 MeV Emin = 7.10001E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 3 MT = 106 Q = -1.14880E+01 MeV Emin = 1.16155E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 4 MT = 107 Q = 1.89840E+00 MeV Emin = 4.75000E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 5 MT = 111 Q = -1.32810E+01 MeV Emin = 1.34284E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.34284E+01 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.53797E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 7.10001E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.16155E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.75000E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 5.50000E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.54480E+00 MeV frac = 1.00000E+00 Product nuclide = 40091.82c : beta- + + Nuclide 95 / 1657 : 40090.82c -- zirconium 90 (Zr-90) + + Pointers : 710624 36807 + Primary type : Transport + Nuclide ZAI : 400900 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Zr90.ACE + Atomic weight (AW) : 89.90473 + Atomic weight ratio (AWR) : 89.13240 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 20 reaction channels + - 7 special reactions + - 11 transmutation reactions + - 9 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 20 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.19812E+01 MeV Emin = 1.21156E+01 MeV frac = 1.00000E+00 Product nuclide = 400890 : (n,2n) + 3 MT = 22 Q = -6.67438E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 38086.82c : (n,nalpha) + 4 MT = 28 Q = -8.36293E+00 MeV Emin = 8.45677E+00 MeV frac = 1.00000E+00 Product nuclide = 39089.82c : (n,np) + 5 MT = 32 Q = -1.76099E+01 MeV Emin = 1.80000E+01 MeV frac = 1.00000E+00 Product nuclide = 390880 : (n,nd) + 6 MT = 51 Q = -1.76070E+00 MeV Emin = 1.77649E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -2.18650E+00 MeV Emin = 2.21103E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -2.31910E+00 MeV Emin = 2.34512E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -2.73880E+00 MeV Emin = 2.76953E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -2.74790E+00 MeV Emin = 2.77873E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -3.07720E+00 MeV Emin = 3.11172E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -3.30870E+00 MeV Emin = 3.34582E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 91 Q = -3.30900E+00 MeV Emin = 3.34613E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 14 MT = 102 Q = 7.19929E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 40091.82c : (n,gamma) + 15 MT = 103 Q = -1.50143E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 39090.82c : (n,p) + 16 MT = 104 Q = -6.05281E+00 MeV Emin = 6.74928E+00 MeV frac = 1.00000E+00 Product nuclide = 39089.82c : (n,d) + 17 MT = 105 Q = -1.13411E+01 MeV Emin = 1.21156E+01 MeV frac = 1.00000E+00 Product nuclide = 390880 : (n,t) + 18 MT = 106 Q = -7.70983E+00 MeV Emin = 9.17457E+00 MeV frac = 1.00000E+00 Product nuclide = 38088.82c : (n,He-3) + 19 MT = 107 Q = 1.75851E+00 MeV Emin = 6.75000E-01 MeV frac = 1.00000E+00 Product nuclide = 38087.82c : (n,alpha) + 20 MT = 111 Q = -9.07277E+00 MeV Emin = 1.14683E+01 MeV frac = 1.00000E+00 Product nuclide = 38089.82c : (n,2p) + + 9 additional transport branches: + + 1 MT = 22 Q = -6.67438E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -8.36293E+00 MeV Emin = 8.45677E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82s : (n,np) + 3 MT = 32 Q = -1.76099E+01 MeV Emin = 1.80000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 103 Q = -1.50143E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82s : (n,p) + 5 MT = 104 Q = -6.05281E+00 MeV Emin = 6.74928E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -1.13411E+01 MeV Emin = 1.21156E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 106 Q = -7.70983E+00 MeV Emin = 9.17457E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 8 MT = 107 Q = 1.75851E+00 MeV Emin = 6.75000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 9 MT = 111 Q = -9.07277E+00 MeV Emin = 1.14683E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82s : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.74928E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.21156E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 9.17457E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 6.75000E-01 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 1.77649E+00 MeV : total inelastic scattering + + Nuclide 96 / 1657 : 40091.82c -- zirconium 91 (Zr-91) + + Pointers : 713902 36853 + Primary type : Transport + Nuclide ZAI : 400910 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Zr91.ACE + Atomic weight (AW) : 90.90563 + Atomic weight ratio (AWR) : 90.12470 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 27 reaction channels + - 7 special reactions + - 11 transmutation reactions + - 8 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 27 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.20258E+00 MeV Emin = 7.28251E+00 MeV frac = 1.00000E+00 Product nuclide = 40090.82c : (n,2n) + 3 MT = 17 Q = -1.91859E+01 MeV Emin = 1.93988E+01 MeV frac = 1.00000E+00 Product nuclide = 400890 : (n,3n) + 4 MT = 22 Q = -5.45233E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 38087.82c : (n,nalpha) + 5 MT = 28 Q = -8.70881E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 39090.82c : (n,np) + 6 MT = 32 Q = -1.33442E+01 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 39089.82c : (n,nd) + 7 MT = 51 Q = -1.20480E+00 MeV Emin = 1.16363E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 8 MT = 52 Q = -1.46630E+00 MeV Emin = 1.44037E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 9 MT = 53 Q = -1.88210E+00 MeV Emin = 1.88514E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 10 MT = 54 Q = -2.04220E+00 MeV Emin = 2.06486E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 11 MT = 55 Q = -2.13130E+00 MeV Emin = 2.15495E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 12 MT = 56 Q = -2.17000E+00 MeV Emin = 2.19408E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 13 MT = 57 Q = -2.18990E+00 MeV Emin = 2.21420E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 14 MT = 58 Q = -2.20070E+00 MeV Emin = 2.22512E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 15 MT = 59 Q = -2.25970E+00 MeV Emin = 2.28477E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 16 MT = 60 Q = -2.28760E+00 MeV Emin = 2.31298E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 17 MT = 61 Q = -2.32010E+00 MeV Emin = 2.34584E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 18 MT = 62 Q = -2.35580E+00 MeV Emin = 2.38194E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 19 MT = 63 Q = -2.36690E+00 MeV Emin = 2.39316E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 20 MT = 64 Q = -2.39490E+00 MeV Emin = 2.42147E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 21 MT = 91 Q = -2.39500E+00 MeV Emin = 2.42157E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 22 MT = 102 Q = 8.63480E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 40092.82c : (n,gamma) + 23 MT = 103 Q = -7.60531E-01 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 39091.82c : (n,p) + 24 MT = 104 Q = -6.48420E+00 MeV Emin = 6.55616E+00 MeV frac = 1.00000E+00 Product nuclide = 39090.82c : (n,d) + 25 MT = 105 Q = -7.08660E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 39089.82c : (n,t) + 26 MT = 106 Q = -8.55750E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 38089.82c : (n,He-3) + 27 MT = 107 Q = 5.67229E+00 MeV Emin = 9.49999E-02 MeV frac = 1.00000E+00 Product nuclide = 38088.82c : (n,alpha) + + 8 additional transport branches: + + 1 MT = 22 Q = -5.45233E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -8.70881E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82s : (n,np) + 3 MT = 32 Q = -1.33442E+01 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 103 Q = -7.60531E-01 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82s : (n,p) + 5 MT = 104 Q = -6.48420E+00 MeV Emin = 6.55616E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -7.08660E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 106 Q = -8.55750E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 8 MT = 107 Q = 5.67229E+00 MeV Emin = 9.49999E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.55616E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 8.00000E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.00000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 9.49999E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 8.53457E-04 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 1.16363E+00 MeV : total inelastic scattering + + Nuclide 97 / 1657 : 40092.82c -- zirconium 92 (Zr-92) + + Pointers : 717079 36899 + Primary type : Transport + Nuclide ZAI : 400920 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Zr92.ACE + Atomic weight (AW) : 91.90501 + Atomic weight ratio (AWR) : 91.11550 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 30 reaction channels + - 6 special reactions + - 11 transmutation reactions + - 8 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 30 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.63508E+00 MeV Emin = 8.72986E+00 MeV frac = 1.00000E+00 Product nuclide = 40091.82c : (n,2n) + 3 MT = 17 Q = -1.58377E+01 MeV Emin = 1.60115E+01 MeV frac = 1.00000E+00 Product nuclide = 40090.82c : (n,3n) + 4 MT = 22 Q = -2.96741E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 38088.82c : (n,nalpha) + 5 MT = 28 Q = -9.40023E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 39091.82c : (n,np) + 6 MT = 32 Q = -1.50350E+01 MeV Emin = 1.58838E+01 MeV frac = 1.00000E+00 Product nuclide = 39090.82c : (n,nd) + 7 MT = 33 Q = -1.57114E+01 MeV Emin = 1.60176E+01 MeV frac = 1.00000E+00 Product nuclide = 39089.82c : (n,nt) + 8 MT = 51 Q = -9.34499E-01 MeV Emin = 9.41128E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -1.38280E+00 MeV Emin = 1.39702E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -1.49540E+00 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -1.84730E+00 MeV Emin = 1.86708E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -2.06670E+00 MeV Emin = 2.08938E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -2.15000E+00 MeV Emin = 2.17360E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -2.33970E+00 MeV Emin = 2.36538E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -2.39830E+00 MeV Emin = 2.42462E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -2.48590E+00 MeV Emin = 2.51318E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -2.74350E+00 MeV Emin = 2.77361E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -2.81970E+00 MeV Emin = 2.85065E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 62 Q = -2.86400E+00 MeV Emin = 2.89543E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 20 MT = 63 Q = -2.90360E+00 MeV Emin = 2.93547E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 21 MT = 64 Q = -2.90950E+00 MeV Emin = 2.94143E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 22 MT = 65 Q = -2.95780E+00 MeV Emin = 2.99026E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 23 MT = 66 Q = -3.03970E+00 MeV Emin = 3.07306E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 24 MT = 67 Q = -3.05780E+00 MeV Emin = 3.09136E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 25 MT = 91 Q = -3.05800E+00 MeV Emin = 3.09156E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 26 MT = 102 Q = 6.73199E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 40093.82c : (n,gamma) + 27 MT = 103 Q = -2.85164E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 390920 : (n,p) + 28 MT = 104 Q = -7.09011E+00 MeV Emin = 7.16794E+00 MeV frac = 1.00000E+00 Product nuclide = 39091.82c : (n,d) + 29 MT = 105 Q = -8.84985E+00 MeV Emin = 9.50341E+00 MeV frac = 1.00000E+00 Product nuclide = 39090.82c : (n,t) + 30 MT = 107 Q = 3.40109E+00 MeV Emin = 1.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 38089.82c : (n,alpha) + + 8 additional transport branches: + + 1 MT = 22 Q = -2.96741E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -9.40023E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82s : (n,np) + 3 MT = 32 Q = -1.50350E+01 MeV Emin = 1.58838E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.57114E+01 MeV Emin = 1.60176E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 103 Q = -2.85164E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82s : (n,p) + 6 MT = 104 Q = -7.09011E+00 MeV Emin = 7.16794E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 7 MT = 105 Q = -8.84985E+00 MeV Emin = 9.50341E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 8 MT = 107 Q = 3.40109E+00 MeV Emin = 1.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.16794E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.50341E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-01 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 9.41128E-01 MeV : total inelastic scattering + + Nuclide 98 / 1657 : 40093.82c -- zirconium 93 (Zr-93) + + Pointers : 720402 36945 + Primary type : Transport + Nuclide ZAI : 400930 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Zr93.ACE + Atomic weight (AW) : 92.90652 + Atomic weight ratio (AWR) : 92.10840 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 5.08E+13 seconds (1.61 million years) + Specific ingestion toxicity : 1.10E-09 Sv/Bq + Specific inhalation toxicity : 3.30E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 23 reaction channels + - 6 special reactions + - 11 transmutation reactions + - 8 transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 23 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.73669E+00 MeV Emin = 6.80984E+00 MeV frac = 1.00000E+00 Product nuclide = 40092.82c : (n,2n) + 3 MT = 17 Q = -1.53764E+01 MeV Emin = 1.55434E+01 MeV frac = 1.00000E+00 Product nuclide = 40091.82c : (n,3n) + 4 MT = 22 Q = -3.33560E+00 MeV Emin = 3.37181E+00 MeV frac = 1.00000E+00 Product nuclide = 38089.82c : (n,nalpha) + 5 MT = 28 Q = -9.58833E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 390920 : (n,np) + 6 MT = 32 Q = -1.38268E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 39091.82c : (n,nd) + 7 MT = 33 Q = -1.55866E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 39090.82c : (n,nt) + 8 MT = 51 Q = -2.67100E-01 MeV Emin = 2.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -9.48999E-01 MeV Emin = 9.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -1.42310E+00 MeV Emin = 1.36784E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -1.48000E+00 MeV Emin = 1.48169E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -1.60000E+00 MeV Emin = 1.58803E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -1.65000E+00 MeV Emin = 1.65528E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -1.92000E+00 MeV Emin = 1.89314E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -2.04000E+00 MeV Emin = 2.06215E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -2.08000E+00 MeV Emin = 2.10258E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -2.10000E+00 MeV Emin = 2.12280E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 91 Q = -2.18000E+00 MeV Emin = 2.20367E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 19 MT = 102 Q = 8.22112E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 40094.82c : (n,gamma) + 20 MT = 103 Q = -2.10723E+00 MeV Emin = 2.13011E+00 MeV frac = 1.00000E+00 Product nuclide = 390930 : (n,p) + 21 MT = 104 Q = -7.27821E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 390920 : (n,d) + 22 MT = 105 Q = -7.64165E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 39091.82c : (n,t) + 23 MT = 107 Q = 4.47221E+00 MeV Emin = 9.49999E-02 MeV frac = 1.00000E+00 Product nuclide = 38090.82c : (n,alpha) + + 8 additional transport branches: + + 1 MT = 22 Q = -3.33560E+00 MeV Emin = 3.37181E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -9.58833E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.38268E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.55866E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 103 Q = -2.10723E+00 MeV Emin = 2.13011E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 104 Q = -7.27821E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 7 MT = 105 Q = -7.64165E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 8 MT = 107 Q = 4.47221E+00 MeV Emin = 9.49999E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.13011E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 8.00000E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 9.49999E-02 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 8.54206E-04 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 2.50000E-01 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 1 Q = 9.03000E-02 MeV frac = 2.70000E-01 Product nuclide = 41093.82c : beta- + 2 RTYP = 1 Q = 5.95300E-02 MeV frac = 7.30000E-01 Product nuclide = 410931 : beta- + + Nuclide 99 / 1657 : 40094.82c -- zirconium 94 (Zr-94) + + Pointers : 723407 36991 + Primary type : Transport + Nuclide ZAI : 400940 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Zr94.ACE + Atomic weight (AW) : 93.90631 + Atomic weight ratio (AWR) : 93.09960 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 3.47E+24 seconds (1.1E+17 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 26 reaction channels + - 6 special reactions + - 10 transmutation reactions + - 7 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 26 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.19108E+00 MeV Emin = 8.27907E+00 MeV frac = 1.00000E+00 Product nuclide = 40093.82c : (n,2n) + 3 MT = 17 Q = -1.49496E+01 MeV Emin = 1.51102E+01 MeV frac = 1.00000E+00 Product nuclide = 40092.82c : (n,3n) + 4 MT = 22 Q = -3.75108E+00 MeV Emin = 4.14346E+00 MeV frac = 1.00000E+00 Product nuclide = 38090.82c : (n,nalpha) + 5 MT = 28 Q = -1.03305E+01 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 390930 : (n,np) + 6 MT = 32 Q = -1.55015E+01 MeV Emin = 1.60354E+01 MeV frac = 1.00000E+00 Product nuclide = 390920 : (n,nd) + 7 MT = 51 Q = -9.18699E-01 MeV Emin = 9.28063E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 8 MT = 52 Q = -1.30020E+00 MeV Emin = 1.31250E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 9 MT = 53 Q = -1.46960E+00 MeV Emin = 1.48407E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 10 MT = 54 Q = -1.67140E+00 MeV Emin = 1.68878E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 11 MT = 55 Q = -2.05760E+00 MeV Emin = 2.07970E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 12 MT = 56 Q = -2.15130E+00 MeV Emin = 2.17441E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 13 MT = 57 Q = -2.33020E+00 MeV Emin = 2.35523E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 14 MT = 58 Q = -2.36610E+00 MeV Emin = 2.39152E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 15 MT = 59 Q = -2.50770E+00 MeV Emin = 2.53464E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 16 MT = 60 Q = -2.60450E+00 MeV Emin = 2.63248E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 17 MT = 61 Q = -2.69850E+00 MeV Emin = 2.72749E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 18 MT = 62 Q = -2.82600E+00 MeV Emin = 2.85636E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 19 MT = 63 Q = -2.84630E+00 MeV Emin = 2.87687E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 20 MT = 64 Q = -2.86060E+00 MeV Emin = 2.89133E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 21 MT = 91 Q = -2.86100E+00 MeV Emin = 2.89173E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 22 MT = 102 Q = 6.47089E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 40095.82c : (n,gamma) + 23 MT = 103 Q = -4.09942E+00 MeV Emin = 4.14346E+00 MeV frac = 1.00000E+00 Product nuclide = 390940 : (n,p) + 24 MT = 104 Q = -8.02041E+00 MeV Emin = 8.31164E+00 MeV frac = 1.00000E+00 Product nuclide = 390930 : (n,d) + 25 MT = 105 Q = -9.31636E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 390920 : (n,t) + 26 MT = 107 Q = 2.05631E+00 MeV Emin = 1.71000E-01 MeV frac = 1.00000E+00 Product nuclide = 380910 : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -3.75108E+00 MeV Emin = 4.14346E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.03305E+01 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82s : (n,np) + 3 MT = 32 Q = -1.55015E+01 MeV Emin = 1.60354E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 103 Q = -4.09942E+00 MeV Emin = 4.14346E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82s : (n,p) + 5 MT = 104 Q = -8.02041E+00 MeV Emin = 8.31164E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -9.31636E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 107 Q = 2.05631E+00 MeV Emin = 1.71000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.14346E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.31164E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.00000E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 1.71000E-01 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 9.28063E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 11 Q = 1.14190E+00 MeV frac = 1.00000E+00 Product nuclide = 42094.82c : beta- + beta- + + Nuclide 100 / 1657 : 40095.82c -- zirconium 95 (Zr-95) + + Pointers : 726438 37037 + Primary type : Transport + Nuclide ZAI : 400950 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Zr95.ACE + Atomic weight (AW) : 94.90801 + Atomic weight ratio (AWR) : 94.09270 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 5.53E+06 seconds (64 days) + Specific ingestion toxicity : 9.50E-10 Sv/Bq + Specific inhalation toxicity : 5.90E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 35 reaction channels + - 6 special reactions + - 10 transmutation reactions + - 7 transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 35 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.47560E+00 MeV Emin = 6.54443E+00 MeV frac = 1.00000E+00 Product nuclide = 40094.82c : (n,2n) + 3 MT = 17 Q = -1.46989E+01 MeV Emin = 1.48551E+01 MeV frac = 1.00000E+00 Product nuclide = 40093.82c : (n,3n) + 4 MT = 22 Q = -4.41929E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 380910 : (n,nalpha) + 5 MT = 28 Q = -1.05750E+01 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 390940 : (n,np) + 6 MT = 32 Q = -1.44960E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 390930 : (n,nd) + 7 MT = 51 Q = -9.52999E-01 MeV Emin = 9.54260E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 8 MT = 52 Q = -1.17300E+00 MeV Emin = 1.18390E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 9 MT = 53 Q = -1.31900E+00 MeV Emin = 1.31227E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 10 MT = 54 Q = -1.61800E+00 MeV Emin = 1.56760E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 11 MT = 55 Q = -1.61826E+00 MeV Emin = 1.56760E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 12 MT = 56 Q = -1.71800E+00 MeV Emin = 1.71106E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 13 MT = 57 Q = -1.78900E+00 MeV Emin = 1.79351E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 14 MT = 58 Q = -1.89600E+00 MeV Emin = 1.88912E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 15 MT = 59 Q = -1.94000E+00 MeV Emin = 1.95909E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 16 MT = 60 Q = -2.01800E+00 MeV Emin = 2.03945E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 17 MT = 61 Q = -2.25200E+00 MeV Emin = 2.27594E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 18 MT = 62 Q = -2.28000E+00 MeV Emin = 2.30423E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 19 MT = 63 Q = -2.29100E+00 MeV Emin = 2.31535E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 20 MT = 64 Q = -2.37600E+00 MeV Emin = 2.40125E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 21 MT = 65 Q = -2.45000E+00 MeV Emin = 2.47604E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 22 MT = 66 Q = -2.62500E+00 MeV Emin = 2.65290E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 23 MT = 67 Q = -2.62550E+00 MeV Emin = 2.65340E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 24 MT = 68 Q = -2.72400E+00 MeV Emin = 2.75295E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 25 MT = 69 Q = -2.83400E+00 MeV Emin = 2.86412E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 26 MT = 70 Q = -2.83500E+00 MeV Emin = 2.86513E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 27 MT = 71 Q = -2.99600E+00 MeV Emin = 3.02784E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 28 MT = 72 Q = -3.06200E+00 MeV Emin = 3.09454E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 29 MT = 73 Q = -3.11700E+00 MeV Emin = 3.15013E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 30 MT = 91 Q = -3.20500E+00 MeV Emin = 3.23906E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 31 MT = 102 Q = 7.85635E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 40096.82c : (n,gamma) + 32 MT = 103 Q = -3.64793E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 390950 : (n,p) + 33 MT = 104 Q = -8.26491E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 390940 : (n,d) + 34 MT = 105 Q = -8.31086E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 390930 : (n,t) + 35 MT = 107 Q = 2.88281E+00 MeV Emin = 1.01563E-01 MeV frac = 1.00000E+00 Product nuclide = 380920 : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -4.41929E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.05750E+01 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.44960E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 103 Q = -3.64793E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -8.26491E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -8.31086E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 107 Q = 2.88281E+00 MeV Emin = 1.01563E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 9.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.00000E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 1.01563E-01 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 9.00000E-04 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 9.54260E-01 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.12480E+00 MeV frac = 9.89196E-01 Product nuclide = 41095.82c : beta- + 2 RTYP = 1 Q = 8.89110E-01 MeV frac = 1.08035E-02 Product nuclide = 410951 : beta- + + Nuclide 101 / 1657 : 40096.82c -- zirconium 96 (Zr-96) + + Pointers : 730456 37083 + Primary type : Transport + Nuclide ZAI : 400960 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Zr96.ACE + Atomic weight (AW) : 95.90830 + Atomic weight ratio (AWR) : 95.08440 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 6.31E+26 seconds (2E+19 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 18 reaction channels + - 6 special reactions + - 9 transmutation reactions + - 6 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 18 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.83168E+00 MeV Emin = 7.91406E+00 MeV frac = 1.00000E+00 Product nuclide = 40095.82c : (n,2n) + 3 MT = 17 Q = -1.43063E+01 MeV Emin = 1.44568E+01 MeV frac = 1.00000E+00 Product nuclide = 40094.82c : (n,3n) + 4 MT = 22 Q = -4.97458E+00 MeV Emin = 5.02691E+00 MeV frac = 1.00000E+00 Product nuclide = 380920 : (n,nalpha) + 5 MT = 28 Q = -1.15053E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 390950 : (n,np) + 6 MT = 51 Q = -1.59400E+00 MeV Emin = 1.60314E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.75050E+00 MeV Emin = 1.75000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -1.89710E+00 MeV Emin = 1.91003E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -2.22590E+00 MeV Emin = 2.24931E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -2.33000E+00 MeV Emin = 2.35451E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -2.44000E+00 MeV Emin = 2.46566E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -2.85740E+00 MeV Emin = 2.88745E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 91 Q = -2.85700E+00 MeV Emin = 2.88705E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 14 MT = 102 Q = 5.57518E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 400970 : (n,gamma) + 15 MT = 103 Q = -6.23222E+00 MeV Emin = 6.29777E+00 MeV frac = 1.00000E+00 Product nuclide = 390960 : (n,p) + 16 MT = 104 Q = -9.19521E+00 MeV Emin = 1.00417E+01 MeV frac = 1.00000E+00 Product nuclide = 390950 : (n,d) + 17 MT = 105 Q = -9.93715E+00 MeV Emin = 1.00417E+01 MeV frac = 1.00000E+00 Product nuclide = 390940 : (n,t) + 18 MT = 107 Q = 2.90000E-01 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 380930 : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = -4.97458E+00 MeV Emin = 5.02691E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.15053E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82s : (n,np) + 3 MT = 103 Q = -6.23222E+00 MeV Emin = 6.29777E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82s : (n,p) + 4 MT = 104 Q = -9.19521E+00 MeV Emin = 1.00417E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -9.93715E+00 MeV Emin = 1.00417E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 107 Q = 2.90000E-01 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 6.29777E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.00417E+01 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.00417E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 9.35566E-04 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 1.60314E+00 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 11 Q = 3.34900E+00 MeV frac = 1.00000E+00 Product nuclide = 42096.82c : beta- + beta- + + Nuclide 102 / 1657 : 41093.82c -- niobium 93 (Nb-93) + + Pointers : 759781 28343 + Primary type : Transport + Nuclide ZAI : 410930 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Nb93.ACE + Atomic weight (AW) : 92.90319 + Atomic weight ratio (AWR) : 92.10510 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 1.50000E+02 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 37 reaction channels + - 6 special reactions + - 11 transmutation reactions + - 9 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 37 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 5 Q = 0.00000E+00 MeV Emin = 2.00000E+01 MeV frac = 1.00000E+00 Product nuclide = self : anything + 3 MT = 16 Q = -8.83300E+00 MeV Emin = 8.92900E+00 MeV frac = 1.00000E+00 Product nuclide = 410920 : (n,2n) + 4 MT = 17 Q = -1.67150E+01 MeV Emin = 1.69000E+01 MeV frac = 1.00000E+00 Product nuclide = 410910 : (n,3n) + 5 MT = 22 Q = -1.93800E+00 MeV Emin = 1.95000E+00 MeV frac = 1.00000E+00 Product nuclide = 39089.82c : (n,nalpha) + 6 MT = 28 Q = -6.04200E+00 MeV Emin = 6.10760E+00 MeV frac = 1.00000E+00 Product nuclide = 40092.82c : (n,np) + 7 MT = 32 Q = -1.24600E+01 MeV Emin = 1.25953E+01 MeV frac = 1.00000E+00 Product nuclide = 40091.82c : (n,nd) + 8 MT = 33 Q = -1.33400E+01 MeV Emin = 1.34848E+01 MeV frac = 1.00000E+00 Product nuclide = 40090.82c : (n,nt) + 9 MT = 51 Q = -3.07300E-02 MeV Emin = 3.10000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 10 MT = 52 Q = -6.79900E-01 MeV Emin = 6.80000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 11 MT = 53 Q = -7.44000E-01 MeV Emin = 7.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 12 MT = 54 Q = -8.01000E-01 MeV Emin = 8.08000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 13 MT = 55 Q = -8.08000E-01 MeV Emin = 8.13350E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 14 MT = 56 Q = -9.49900E-01 MeV Emin = 9.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 15 MT = 57 Q = -9.79000E-01 MeV Emin = 9.84750E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 16 MT = 58 Q = -1.08000E+00 MeV Emin = 1.08000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 17 MT = 59 Q = -1.30000E+00 MeV Emin = 1.30000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 18 MT = 60 Q = -1.32000E+00 MeV Emin = 1.33400E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 19 MT = 61 Q = -1.33000E+00 MeV Emin = 1.34400E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 20 MT = 62 Q = -1.37000E+00 MeV Emin = 1.37000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 21 MT = 63 Q = -1.39000E+00 MeV Emin = 1.40000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 22 MT = 64 Q = -1.48000E+00 MeV Emin = 1.49000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 23 MT = 65 Q = -1.48400E+00 MeV Emin = 1.49804E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 24 MT = 66 Q = -1.50000E+00 MeV Emin = 1.51600E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 25 MT = 67 Q = -1.60000E+00 MeV Emin = 1.61700E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 26 MT = 68 Q = -1.67000E+00 MeV Emin = 1.68000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 27 MT = 69 Q = -1.68000E+00 MeV Emin = 1.69400E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 28 MT = 70 Q = -1.68100E+00 MeV Emin = 1.69862E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 29 MT = 71 Q = -1.69000E+00 MeV Emin = 1.70800E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 30 MT = 72 Q = -1.95000E+00 MeV Emin = 1.96000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 31 MT = 73 Q = -2.15500E+00 MeV Emin = 2.17840E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 32 MT = 91 Q = -2.17700E+00 MeV Emin = 2.20064E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 33 MT = 102 Q = 7.21400E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 41094.82c : (n,gamma) + 34 MT = 103 Q = 6.93000E-01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 40093.82c : (n,p) + 35 MT = 104 Q = -3.81700E+00 MeV Emin = 3.85900E+00 MeV frac = 1.00000E+00 Product nuclide = 40092.82c : (n,d) + 36 MT = 105 Q = -6.19500E+00 MeV Emin = 6.26300E+00 MeV frac = 1.00000E+00 Product nuclide = 40091.82c : (n,t) + 37 MT = 107 Q = 4.91800E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 39090.82c : (n,alpha) + + 9 additional transport branches: + + 1 MT = 22 Q = -1.93800E+00 MeV Emin = 1.95000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -6.04200E+00 MeV Emin = 6.10760E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.24600E+01 MeV Emin = 1.25953E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.33400E+01 MeV Emin = 1.34848E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 102 Q = 7.21400E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 410941 : (n,gamma) + 6 MT = 103 Q = 6.93000E-01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 7 MT = 104 Q = -3.81700E+00 MeV Emin = 3.85900E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 8 MT = 105 Q = -6.19500E+00 MeV Emin = 6.26300E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 9 MT = 107 Q = 4.91800E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 3.85900E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 6.26300E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 3.10000E-02 MeV : total inelastic scattering + + Nuclide 103 / 1657 : 41094.82c -- niobium 94 (Nb-94) + + Pointers : 764106 28389 + Primary type : Transport + Nuclide ZAI : 410940 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Nb94.ACE + Atomic weight (AW) : 93.90731 + Atomic weight ratio (AWR) : 93.10060 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 6.31E+11 seconds (19,1000 years) + Specific ingestion toxicity : 1.70E-09 Sv/Bq + Specific inhalation toxicity : 4.90E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 43 reaction channels + - 7 special reactions + - 12 transmutation reactions + - 10 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 43 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.23420E+00 MeV Emin = 7.31191E+00 MeV frac = 1.00000E+00 Product nuclide = 41093.82c : (n,2n) + 3 MT = 17 Q = -1.60712E+01 MeV Emin = 1.62438E+01 MeV frac = 1.00000E+00 Product nuclide = 410920 : (n,3n) + 4 MT = 22 Q = -2.30829E+00 MeV Emin = 2.33309E+00 MeV frac = 1.00000E+00 Product nuclide = 39090.82c : (n,nalpha) + 5 MT = 28 Q = -6.54404E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 40093.82c : (n,np) + 6 MT = 32 Q = -1.09706E+01 MeV Emin = 1.10885E+01 MeV frac = 1.00000E+00 Product nuclide = 40092.82c : (n,nd) + 7 MT = 33 Q = -1.34252E+01 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 40091.82c : (n,nt) + 8 MT = 51 Q = -4.09999E-02 MeV Emin = 4.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -5.86999E-02 MeV Emin = 5.87500E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -7.86999E-02 MeV Emin = 7.75000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -1.13400E-01 MeV Emin = 1.10964E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -1.40300E-01 MeV Emin = 1.38408E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -3.01600E-01 MeV Emin = 3.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -3.11900E-01 MeV Emin = 3.11346E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -3.34200E-01 MeV Emin = 3.32859E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -3.96299E-01 MeV Emin = 3.93201E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -4.50199E-01 MeV Emin = 4.42267E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -6.31699E-01 MeV Emin = 6.21174E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 62 Q = -6.40899E-01 MeV Emin = 6.43135E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 20 MT = 63 Q = -6.65699E-01 MeV Emin = 6.72458E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 21 MT = 64 Q = -7.84899E-01 MeV Emin = 7.69998E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 22 MT = 65 Q = -7.92899E-01 MeV Emin = 8.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 23 MT = 66 Q = -8.17799E-01 MeV Emin = 8.14001E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 24 MT = 67 Q = -8.95699E-01 MeV Emin = 9.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 25 MT = 68 Q = -9.23999E-01 MeV Emin = 9.23199E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 26 MT = 69 Q = -9.35199E-01 MeV Emin = 9.39585E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 27 MT = 70 Q = -9.58599E-01 MeV Emin = 9.51158E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 28 MT = 71 Q = -9.78999E-01 MeV Emin = 9.79206E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 29 MT = 72 Q = -1.00770E+00 MeV Emin = 1.00926E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 30 MT = 73 Q = -1.06120E+00 MeV Emin = 1.05908E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 31 MT = 74 Q = -1.08570E+00 MeV Emin = 1.08807E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 32 MT = 75 Q = -1.16330E+00 MeV Emin = 1.15619E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 33 MT = 76 Q = -1.17070E+00 MeV Emin = 1.17954E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 34 MT = 77 Q = -1.20200E+00 MeV Emin = 1.20304E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 27. excited state + 35 MT = 78 Q = -1.23270E+00 MeV Emin = 1.23430E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 28. excited state + 36 MT = 79 Q = -1.25690E+00 MeV Emin = 1.26020E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 29. excited state + 37 MT = 91 Q = -1.26390E+00 MeV Emin = 1.27394E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 38 MT = 102 Q = 8.49079E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 41095.82c : (n,gamma) + 39 MT = 103 Q = 1.67926E+00 MeV Emin = 9.76563E-02 MeV frac = 1.00000E+00 Product nuclide = 40094.82c : (n,p) + 40 MT = 104 Q = -4.23392E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 40093.82c : (n,d) + 41 MT = 105 Q = -4.78546E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 40092.82c : (n,t) + 42 MT = 106 Q = -8.40093E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 390920 : (n,He-3) + 43 MT = 107 Q = 5.63660E+00 MeV Emin = 9.76563E-02 MeV frac = 1.00000E+00 Product nuclide = 39091.82c : (n,alpha) + + 10 additional transport branches: + + 1 MT = 22 Q = -2.30829E+00 MeV Emin = 2.33309E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -6.54404E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.09706E+01 MeV Emin = 1.10885E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.34252E+01 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 102 Q = 8.49079E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 410951 : (n,gamma) + 6 MT = 103 Q = 1.67926E+00 MeV Emin = 9.76563E-02 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 7 MT = 104 Q = -4.23392E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 8 MT = 105 Q = -4.78546E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 9 MT = 106 Q = -8.40093E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 10 MT = 107 Q = 5.63660E+00 MeV Emin = 9.76563E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 9.76563E-02 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 5.00000E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.00000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 9.76563E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 4.00000E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.04530E+00 MeV frac = 1.00000E+00 Product nuclide = 42094.82c : beta- + + Nuclide 104 / 1657 : 41095.82c -- niobium 95 (Nb-95) + + Pointers : 769656 28435 + Primary type : Transport + Nuclide ZAI : 410950 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Nb95.ACE + Atomic weight (AW) : 94.90680 + Atomic weight ratio (AWR) : 94.09150 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 3.02E+06 seconds (35 days) + Specific ingestion toxicity : 5.80E-10 Sv/Bq + Specific inhalation toxicity : 1.80E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 34 reaction channels + - 7 special reactions + - 12 transmutation reactions + - 9 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 34 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.49549E+00 MeV Emin = 8.58579E+00 MeV frac = 1.00000E+00 Product nuclide = 41094.82c : (n,2n) + 3 MT = 17 Q = -1.57297E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 41093.82c : (n,3n) + 4 MT = 22 Q = -2.85889E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 39091.82c : (n,nalpha) + 5 MT = 28 Q = -6.81623E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 40094.82c : (n,np) + 6 MT = 32 Q = -1.27294E+01 MeV Emin = 1.34221E+01 MeV frac = 1.00000E+00 Product nuclide = 40093.82c : (n,nd) + 7 MT = 33 Q = -1.32810E+01 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 40092.82c : (n,nt) + 8 MT = 51 Q = -2.35700E-01 MeV Emin = 2.19103E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -7.24199E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -7.27999E-01 MeV Emin = 7.34501E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -7.56699E-01 MeV Emin = 7.64444E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -7.98999E-01 MeV Emin = 8.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -1.00000E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -1.08800E+00 MeV Emin = 1.08567E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -1.22300E+00 MeV Emin = 1.21681E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -1.27400E+00 MeV Emin = 1.27581E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -1.41900E+00 MeV Emin = 1.43253E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -1.51400E+00 MeV Emin = 1.51504E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 62 Q = -1.59000E+00 MeV Emin = 1.60350E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 20 MT = 63 Q = -1.64500E+00 MeV Emin = 1.64858E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 21 MT = 64 Q = -1.69100E+00 MeV Emin = 1.69444E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 22 MT = 65 Q = -1.81000E+00 MeV Emin = 1.82549E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 23 MT = 66 Q = -1.91300E+00 MeV Emin = 1.90406E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 24 MT = 67 Q = -1.98000E+00 MeV Emin = 2.00104E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 25 MT = 68 Q = -2.07000E+00 MeV Emin = 2.09200E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 26 MT = 69 Q = -2.12100E+00 MeV Emin = 2.14354E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 27 MT = 70 Q = -2.16500E+00 MeV Emin = 2.18801E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 28 MT = 91 Q = -2.26000E+00 MeV Emin = 2.28402E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 29 MT = 102 Q = 6.89312E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 410960 : (n,gamma) + 30 MT = 103 Q = -3.40631E-01 MeV Emin = 1.27581E+00 MeV frac = 1.00000E+00 Product nuclide = 40095.82c : (n,p) + 31 MT = 104 Q = -4.50611E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 40094.82c : (n,d) + 32 MT = 105 Q = -6.54426E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 40093.82c : (n,t) + 33 MT = 106 Q = -9.41532E+00 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 390930 : (n,He-3) + 34 MT = 107 Q = 3.68970E+00 MeV Emin = 9.49999E-02 MeV frac = 1.00000E+00 Product nuclide = 390920 : (n,alpha) + + 9 additional transport branches: + + 1 MT = 22 Q = -2.85889E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -6.81623E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.27294E+01 MeV Emin = 1.34221E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.32810E+01 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 103 Q = -3.40631E-01 MeV Emin = 1.27581E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 104 Q = -4.50611E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 7 MT = 105 Q = -6.54426E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 8 MT = 106 Q = -9.41532E+00 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 9 MT = 107 Q = 3.68970E+00 MeV Emin = 9.49999E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.27581E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 7.00000E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.20000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 9.49999E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 9.00000E-04 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 2.19103E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.25600E-01 MeV frac = 1.00000E+00 Product nuclide = 42095.82c : beta- + + Nuclide 105 / 1657 : 42092.82c -- molybdenum 92 (Mo-92) + + Pointers : 804864 27837 + Primary type : Transport + Nuclide ZAI : 420920 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Mo92.ACE + Atomic weight (AW) : 91.90683 + Atomic weight ratio (AWR) : 91.11730 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 6.00E+27 seconds (1.9E+20 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 28 reaction channels + - 7 special reactions + - 10 transmutation reactions + - 9 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 28 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -1.26921E+01 MeV Emin = 1.28314E+01 MeV frac = 1.00000E+00 Product nuclide = 420910 : (n,2n) + 3 MT = 22 Q = -5.62333E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 400880 : (n,nalpha) + 4 MT = 28 Q = -7.46561E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 410910 : (n,np) + 5 MT = 51 Q = -1.50950E+00 MeV Emin = 1.52556E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -2.28260E+00 MeV Emin = 2.30765E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -2.51970E+00 MeV Emin = 2.54735E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -2.52710E+00 MeV Emin = 2.55484E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -2.61240E+00 MeV Emin = 2.64107E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -2.76040E+00 MeV Emin = 2.79070E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -2.84970E+00 MeV Emin = 2.88098E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -3.00700E+00 MeV Emin = 3.04000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -3.06410E+00 MeV Emin = 3.09773E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -3.09130E+00 MeV Emin = 3.12523E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -3.36910E+00 MeV Emin = 3.40608E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -3.54199E+00 MeV Emin = 3.58087E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 63 Q = -3.58029E+00 MeV Emin = 3.61959E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 18 MT = 64 Q = -3.62119E+00 MeV Emin = 3.66094E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 19 MT = 65 Q = -3.62479E+00 MeV Emin = 3.66458E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 20 MT = 66 Q = -3.68799E+00 MeV Emin = 3.72848E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 21 MT = 91 Q = -3.68799E+00 MeV Emin = 3.72848E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 22 MT = 102 Q = 8.06739E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 420930 : (n,gamma) + 23 MT = 103 Q = 4.23561E-01 MeV Emin = 1.03125E-01 MeV frac = 1.00000E+00 Product nuclide = 410920 : (n,p) + 24 MT = 104 Q = -5.15362E+00 MeV Emin = 5.66944E+00 MeV frac = 1.00000E+00 Product nuclide = 410910 : (n,d) + 25 MT = 105 Q = -1.10275E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 410900 : (n,t) + 26 MT = 106 Q = -4.89824E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 40090.82c : (n,He-3) + 27 MT = 107 Q = 3.70670E+00 MeV Emin = 8.00000E-02 MeV frac = 1.00000E+00 Product nuclide = 400890 : (n,alpha) + 28 MT = 111 Q = -5.42568E+00 MeV Emin = 7.54566E+00 MeV frac = 1.00000E+00 Product nuclide = 40091.82c : (n,2p) + + 9 additional transport branches: + + 1 MT = 22 Q = -5.62333E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -7.46561E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 102 Q = 8.06739E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 420931 : (n,gamma) + 4 MT = 103 Q = 4.23561E-01 MeV Emin = 1.03125E-01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -5.15362E+00 MeV Emin = 5.66944E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -1.10275E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 106 Q = -4.89824E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 8 MT = 107 Q = 3.70670E+00 MeV Emin = 8.00000E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 9 MT = 111 Q = -5.42568E+00 MeV Emin = 7.54566E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.03125E-01 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.66944E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.20000E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 6.00000E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 8.00000E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 1.52556E+00 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 22 Q = 1.64890E+00 MeV frac = 1.00000E+00 Product nuclide = 40092.82c : EC/beta+ + EC/beta+ + + Nuclide 106 / 1657 : 42094.82c -- molybdenum 94 (Mo-94) + + Pointers : 809545 27883 + Primary type : Transport + Nuclide ZAI : 420940 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Mo94.ACE + Atomic weight (AW) : 93.90510 + Atomic weight ratio (AWR) : 93.09840 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 32 reaction channels + - 7 special reactions + - 11 transmutation reactions + - 8 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 32 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -9.67258E+00 MeV Emin = 9.77649E+00 MeV frac = 1.00000E+00 Product nuclide = 420930 : (n,2n) + 3 MT = 17 Q = -1.77449E+01 MeV Emin = 1.79355E+01 MeV frac = 1.00000E+00 Product nuclide = 42092.82c : (n,3n) + 4 MT = 22 Q = -2.07224E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 40090.82c : (n,nalpha) + 5 MT = 28 Q = -8.49201E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 41093.82c : (n,np) + 6 MT = 51 Q = -8.71099E-01 MeV Emin = 8.75000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.57370E+00 MeV Emin = 1.57995E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -1.74250E+00 MeV Emin = 1.76071E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -1.86430E+00 MeV Emin = 1.88390E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -2.06740E+00 MeV Emin = 2.08961E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -2.29520E+00 MeV Emin = 2.31985E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -2.39320E+00 MeV Emin = 2.41891E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -2.42350E+00 MeV Emin = 2.44953E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -2.53390E+00 MeV Emin = 2.56112E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -2.56680E+00 MeV Emin = 2.59437E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -2.61150E+00 MeV Emin = 2.63955E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -2.73980E+00 MeV Emin = 2.76923E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -2.76810E+00 MeV Emin = 2.79783E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -2.80580E+00 MeV Emin = 2.83594E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -2.83590E+00 MeV Emin = 2.86636E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 21 MT = 66 Q = -2.87020E+00 MeV Emin = 2.90103E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 22 MT = 67 Q = -2.87240E+00 MeV Emin = 2.90325E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 23 MT = 68 Q = -2.95580E+00 MeV Emin = 2.98755E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 24 MT = 69 Q = -2.96510E+00 MeV Emin = 2.99695E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 25 MT = 91 Q = -2.96500E+00 MeV Emin = 2.99685E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 26 MT = 102 Q = 7.37119E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 42095.82c : (n,gamma) + 27 MT = 103 Q = -1.26274E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 41094.82c : (n,p) + 28 MT = 104 Q = -6.18682E+00 MeV Emin = 6.88521E+00 MeV frac = 1.00000E+00 Product nuclide = 41093.82c : (n,d) + 29 MT = 105 Q = -8.83866E+00 MeV Emin = 9.78944E+00 MeV frac = 1.00000E+00 Product nuclide = 410920 : (n,t) + 30 MT = 106 Q = -6.81203E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 40092.82c : (n,He-3) + 31 MT = 107 Q = 5.13439E+00 MeV Emin = 9.49999E-02 MeV frac = 1.00000E+00 Product nuclide = 40091.82c : (n,alpha) + 32 MT = 111 Q = -7.80678E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 40093.82c : (n,2p) + + 8 additional transport branches: + + 1 MT = 22 Q = -2.07224E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -8.49201E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -1.26274E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -6.18682E+00 MeV Emin = 6.88521E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -8.83866E+00 MeV Emin = 9.78944E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 106 Q = -6.81203E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 7 MT = 107 Q = 5.13439E+00 MeV Emin = 9.49999E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 8 MT = 111 Q = -7.80678E+00 MeV Emin = 1.00000E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.88521E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.78944E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 9.00000E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 9.49999E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 8.75000E-01 MeV : total inelastic scattering + + Nuclide 107 / 1657 : 42095.82c -- molybdenum 95 (Mo-95) + + Pointers : 813087 27929 + Primary type : Transport + Nuclide ZAI : 420950 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Mo95.ACE + Atomic weight (AW) : 94.90589 + Atomic weight ratio (AWR) : 94.09060 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 14 reaction channels + - 14 special reactions + - 8 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 14 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.36900E+00 MeV Emin = 7.44732E+00 MeV frac = 1.00000E+00 Product nuclide = 42094.82c : (n,2n) + 3 MT = 17 Q = -1.70470E+01 MeV Emin = 1.72282E+01 MeV frac = 1.00000E+00 Product nuclide = 420930 : (n,3n) + 4 MT = 22 Q = -2.24200E+00 MeV Emin = 2.26583E+00 MeV frac = 1.00000E+00 Product nuclide = 40091.82c : (n,nalpha) + 5 MT = 28 Q = -8.63200E+00 MeV Emin = 8.72374E+00 MeV frac = 1.00000E+00 Product nuclide = 41094.82c : (n,np) + 6 MT = 51 Q = -2.04000E-01 MeV Emin = 2.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -7.66000E-01 MeV Emin = 7.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -7.86000E-01 MeV Emin = 7.87071E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -8.21000E-01 MeV Emin = 8.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 91 Q = -8.21000E-01 MeV Emin = 8.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 11 MT = 102 Q = 9.15433E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 42096.82c : (n,gamma) + 12 MT = 103 Q = 0.00000E+00 MeV Emin = 1.60000E-01 MeV frac = 1.00000E+00 Product nuclide = 41095.82c : (n,p) + 13 MT = 107 Q = 6.56751E+00 MeV Emin = 7.50000E-07 MeV frac = 1.00000E+00 Product nuclide = 40092.82c : (n,alpha) + 14 MT = 112 Q = -3.67000E+00 MeV Emin = 3.70901E+00 MeV frac = 1.00000E+00 Product nuclide = 39091.82c : (n,palpha) + + 6 additional transport branches: + + 1 MT = 22 Q = -2.24200E+00 MeV Emin = 2.26583E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -8.63200E+00 MeV Emin = 8.72374E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = 0.00000E+00 MeV Emin = 1.60000E-01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 107 Q = 6.56751E+00 MeV Emin = 7.50000E-07 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 5 MT = 112 Q = -3.67000E+00 MeV Emin = 3.70901E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,palpha) + 6 MT = 112 Q = -3.67000E+00 MeV Emin = 3.70901E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,palpha) + + 14 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.60000E-01 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 7.50000E-07 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 9.90999E-04 MeV : damage-energy production + 4 MT = 600 Q = -1.44000E-01 MeV Emin = 1.60000E-01 MeV : (n,p) to ground state + 5 MT = 601 Q = -3.80000E-01 MeV Emin = 3.50000E-01 MeV : (n,p1) + 6 MT = 649 Q = -3.80000E-01 MeV Emin = 3.50000E-01 MeV : (n,p) to continuum + 7 MT = 800 Q = 6.39300E+00 MeV Emin = 9.91599E-04 MeV : (n,alpha) to ground state + 8 MT = 801 Q = 5.45900E+00 MeV Emin = 9.91599E-04 MeV : (n,a1) + 9 MT = 802 Q = 5.01000E+00 MeV Emin = 9.92199E-04 MeV : (n,a2) + 10 MT = 803 Q = 4.89800E+00 MeV Emin = 9.91599E-04 MeV : (n,a3) + 11 MT = 804 Q = 4.54600E+00 MeV Emin = 9.92199E-04 MeV : (n,a4) + 12 MT = 805 Q = 4.32600E+00 MeV Emin = 1.48949E-03 MeV : (n,a5) + 13 MT = 849 Q = 4.32600E+00 MeV Emin = 1.54611E-03 MeV : (n,alpha) to continuum + 14 MT = 4 Q = 0.00000E+00 MeV Emin = 2.00000E-01 MeV : total inelastic scattering + + Nuclide 108 / 1657 : 42096.82c -- molybdenum 96 (Mo-96) + + Pointers : 815680 27975 + Primary type : Transport + Nuclide ZAI : 420960 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Mo96.ACE + Atomic weight (AW) : 95.90467 + Atomic weight ratio (AWR) : 95.08080 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 28 reaction channels + - 6 special reactions + - 9 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 28 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -9.15428E+00 MeV Emin = 9.25057E+00 MeV frac = 1.00000E+00 Product nuclide = 42095.82c : (n,2n) + 3 MT = 17 Q = -1.65294E+01 MeV Emin = 1.67033E+01 MeV frac = 1.00000E+00 Product nuclide = 42094.82c : (n,3n) + 4 MT = 22 Q = -2.76394E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 40092.82c : (n,nalpha) + 5 MT = 28 Q = -9.29661E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 41095.82c : (n,np) + 6 MT = 51 Q = -7.78199E-01 MeV Emin = 7.73648E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.14790E+00 MeV Emin = 1.15377E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -1.49770E+00 MeV Emin = 1.50673E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -1.62590E+00 MeV Emin = 1.64021E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -1.62810E+00 MeV Emin = 1.64411E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -1.86950E+00 MeV Emin = 1.88674E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -1.97840E+00 MeV Emin = 1.99239E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -2.09560E+00 MeV Emin = 2.11764E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -2.21930E+00 MeV Emin = 2.24264E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -2.23450E+00 MeV Emin = 2.25800E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -2.42610E+00 MeV Emin = 2.45162E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -2.43840E+00 MeV Emin = 2.46405E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -2.44060E+00 MeV Emin = 2.46627E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -2.48100E+00 MeV Emin = 2.50710E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -2.50150E+00 MeV Emin = 2.52781E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 21 MT = 66 Q = -2.54040E+00 MeV Emin = 2.56712E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 22 MT = 67 Q = -2.59430E+00 MeV Emin = 2.62159E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 23 MT = 91 Q = -2.59400E+00 MeV Emin = 2.62128E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 24 MT = 102 Q = 6.82127E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 42097.82c : (n,gamma) + 25 MT = 103 Q = -2.40443E+00 MeV Emin = 2.78973E+00 MeV frac = 1.00000E+00 Product nuclide = 410960 : (n,p) + 26 MT = 104 Q = -6.99191E+00 MeV Emin = 7.06546E+00 MeV frac = 1.00000E+00 Product nuclide = 41095.82c : (n,d) + 27 MT = 105 Q = -9.30226E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 41094.82c : (n,t) + 28 MT = 107 Q = 3.97600E+00 MeV Emin = 9.99218E-02 MeV frac = 1.00000E+00 Product nuclide = 40093.82c : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = -2.76394E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -9.29661E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -2.40443E+00 MeV Emin = 2.78973E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -6.99191E+00 MeV Emin = 7.06546E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -9.30226E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 107 Q = 3.97600E+00 MeV Emin = 9.99218E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.78973E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.06546E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.00000E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 9.99218E-02 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.32897E-03 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 7.73648E-01 MeV : total inelastic scattering + + Nuclide 109 / 1657 : 42097.82c -- molybdenum 97 (Mo-97) + + Pointers : 818711 28021 + Primary type : Transport + Nuclide ZAI : 420970 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Mo97.ACE + Atomic weight (AW) : 96.90597 + Atomic weight ratio (AWR) : 96.07350 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 25 reaction channels + - 7 special reactions + - 10 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 25 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.81598E+00 MeV Emin = 6.88694E+00 MeV frac = 1.00000E+00 Product nuclide = 42096.82c : (n,2n) + 3 MT = 17 Q = -1.59703E+01 MeV Emin = 1.61365E+01 MeV frac = 1.00000E+00 Product nuclide = 42095.82c : (n,3n) + 4 MT = 22 Q = -2.82144E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 40093.82c : (n,nalpha) + 5 MT = 28 Q = -9.22041E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 410960 : (n,np) + 6 MT = 51 Q = -4.80899E-01 MeV Emin = 4.52953E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -6.57899E-01 MeV Emin = 6.44874E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -6.79599E-01 MeV Emin = 6.81207E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -7.19199E-01 MeV Emin = 7.14194E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -7.20799E-01 MeV Emin = 7.27646E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -7.52999E-01 MeV Emin = 7.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -7.94999E-01 MeV Emin = 8.01827E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -8.40899E-01 MeV Emin = 8.49306E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -8.88099E-01 MeV Emin = 8.88902E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -9.92999E-01 MeV Emin = 1.00167E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -1.02450E+00 MeV Emin = 1.02323E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -1.09280E+00 MeV Emin = 1.09475E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -1.11680E+00 MeV Emin = 1.11927E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 91 Q = -1.11700E+00 MeV Emin = 1.12839E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 20 MT = 102 Q = 8.64260E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 42098.82c : (n,gamma) + 21 MT = 103 Q = -1.15043E+00 MeV Emin = 2.00149E+00 MeV frac = 1.00000E+00 Product nuclide = 410970 : (n,p) + 22 MT = 104 Q = -6.92001E+00 MeV Emin = 7.71191E+00 MeV frac = 1.00000E+00 Product nuclide = 410960 : (n,d) + 23 MT = 105 Q = -7.63246E+00 MeV Emin = 8.70061E+00 MeV frac = 1.00000E+00 Product nuclide = 41095.82c : (n,t) + 24 MT = 106 Q = -8.73692E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 40095.82c : (n,He-3) + 25 MT = 107 Q = 5.37360E+00 MeV Emin = 9.49999E-02 MeV frac = 1.00000E+00 Product nuclide = 40094.82c : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -2.82144E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -9.22041E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -1.15043E+00 MeV Emin = 2.00149E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -6.92001E+00 MeV Emin = 7.71191E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -7.63246E+00 MeV Emin = 8.70061E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 106 Q = -8.73692E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 7 MT = 107 Q = 5.37360E+00 MeV Emin = 9.49999E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.00149E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.71191E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 8.70061E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.10000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 9.49999E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.46367E-03 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 4.52953E-01 MeV : total inelastic scattering + + Nuclide 110 / 1657 : 42098.82c -- molybdenum 98 (Mo-98) + + Pointers : 821669 28067 + Primary type : Transport + Nuclide ZAI : 420980 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Mo98.ACE + Atomic weight (AW) : 97.90536 + Atomic weight ratio (AWR) : 97.06430 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 3.16E+21 seconds (1E+14 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 25 reaction channels + - 6 special reactions + - 9 transmutation reactions + - 6 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 25 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.64238E+00 MeV Emin = 8.73143E+00 MeV frac = 1.00000E+00 Product nuclide = 42097.82c : (n,2n) + 3 MT = 17 Q = -1.54584E+01 MeV Emin = 1.56177E+01 MeV frac = 1.00000E+00 Product nuclide = 42096.82c : (n,3n) + 4 MT = 22 Q = -3.27274E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 40094.82c : (n,nalpha) + 5 MT = 28 Q = -9.79511E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 410970 : (n,np) + 6 MT = 51 Q = -7.34800E-01 MeV Emin = 7.35488E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -7.87400E-01 MeV Emin = 7.94556E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -1.43230E+00 MeV Emin = 1.44396E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -1.51000E+00 MeV Emin = 1.51955E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -1.75850E+00 MeV Emin = 1.76892E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -1.88090E+00 MeV Emin = 1.89217E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -1.96500E+00 MeV Emin = 1.97737E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -2.01750E+00 MeV Emin = 2.03829E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -2.03760E+00 MeV Emin = 2.05859E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -2.10480E+00 MeV Emin = 2.12649E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -2.20630E+00 MeV Emin = 2.22903E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -2.22380E+00 MeV Emin = 2.24671E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -2.33340E+00 MeV Emin = 2.35744E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -2.34360E+00 MeV Emin = 2.36775E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 91 Q = -2.34400E+00 MeV Emin = 2.36815E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 21 MT = 102 Q = 5.92544E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 42099.82c : (n,gamma) + 22 MT = 103 Q = -3.80292E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 410980 : (n,p) + 23 MT = 104 Q = -7.48730E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 410970 : (n,d) + 24 MT = 105 Q = -9.38185E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 410960 : (n,t) + 25 MT = 107 Q = 3.20222E+00 MeV Emin = 1.00098E-01 MeV frac = 1.00000E+00 Product nuclide = 40095.82c : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = -3.27274E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -9.79511E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -3.80292E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -7.48730E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -9.38185E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 107 Q = 3.20222E+00 MeV Emin = 1.00098E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.00000E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00098E-01 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.46259E-03 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 7.35488E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 11 Q = 1.10000E-01 MeV frac = 1.00000E+00 Product nuclide = 440980 : beta- + beta- + + Nuclide 111 / 1657 : 42099.82c -- molybdenum 99 (Mo-99) + + Pointers : 824554 28113 + Primary type : Transport + Nuclide ZAI : 420990 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Mo99.ACE + Atomic weight (AW) : 98.90767 + Atomic weight ratio (AWR) : 98.05800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.37E+05 seconds (2.75 days) + Specific ingestion toxicity : 6.00E-10 Sv/Bq + Specific inhalation toxicity : 9.90E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 29 reaction channels + - 6 special reactions + - 11 transmutation reactions + - 8 transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 29 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.93020E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 42098.82c : (n,2n) + 3 MT = 17 Q = -1.45772E+01 MeV Emin = 1.47259E+01 MeV frac = 1.00000E+00 Product nuclide = 42097.82c : (n,3n) + 4 MT = 22 Q = -2.72799E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 40095.82c : (n,nalpha) + 5 MT = 28 Q = -9.73313E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 410980 : (n,np) + 6 MT = 32 Q = -1.34175E+01 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 410970 : (n,nd) + 7 MT = 33 Q = -1.53121E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 410960 : (n,nt) + 8 MT = 51 Q = -9.79999E-02 MeV Emin = 9.87499E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -2.35500E-01 MeV Emin = 2.18951E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -3.52000E-01 MeV Emin = 3.41693E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -5.25499E-01 MeV Emin = 5.29357E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -5.48999E-01 MeV Emin = 5.50325E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -6.14999E-01 MeV Emin = 6.08771E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -6.86999E-01 MeV Emin = 6.93045E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -7.53499E-01 MeV Emin = 7.45888E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -7.92999E-01 MeV Emin = 8.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -8.89499E-01 MeV Emin = 8.80293E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -9.04999E-01 MeV Emin = 9.13176E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 62 Q = -9.12999E-01 MeV Emin = 9.21411E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 20 MT = 63 Q = -9.44999E-01 MeV Emin = 9.42515E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 21 MT = 64 Q = -9.51999E-01 MeV Emin = 9.60566E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 22 MT = 65 Q = -1.03300E+00 MeV Emin = 1.02177E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 23 MT = 66 Q = -1.15000E+00 MeV Emin = 1.13403E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 24 MT = 91 Q = -1.19900E+00 MeV Emin = 1.20896E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 25 MT = 102 Q = 8.29089E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 42100.82c : (n,gamma) + 26 MT = 103 Q = -2.84103E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 410990 : (n,p) + 27 MT = 104 Q = -7.42301E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 410980 : (n,d) + 28 MT = 105 Q = -7.23235E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 410970 : (n,t) + 29 MT = 107 Q = 5.12940E+00 MeV Emin = 9.99608E-02 MeV frac = 1.00000E+00 Product nuclide = 40096.82c : (n,alpha) + + 8 additional transport branches: + + 1 MT = 22 Q = -2.72799E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -9.73313E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.34175E+01 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.53121E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 103 Q = -2.84103E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 104 Q = -7.42301E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 7 MT = 105 Q = -7.23235E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 8 MT = 107 Q = 5.12940E+00 MeV Emin = 9.99608E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 8.00000E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 9.99608E-02 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 9.87499E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.35720E+00 MeV frac = 1.21895E-01 Product nuclide = 43099.82c : beta- + 2 RTYP = 1 Q = 1.21452E+00 MeV frac = 8.78105E-01 Product nuclide = 430991 : beta- + + Nuclide 112 / 1657 : 42100.82c -- molybdenum 100 (Mo-100) + + Pointers : 829439 27791 + Primary type : Transport + Nuclide ZAI : 421000 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Mo100.ACE + Atomic weight (AW) : 99.90746 + Atomic weight ratio (AWR) : 99.04920 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.30E+26 seconds (7.3E+18 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 15 reaction channels + - 6 special reactions + - 9 transmutation reactions + - 6 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 15 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.30078E+00 MeV Emin = 8.38459E+00 MeV frac = 1.00000E+00 Product nuclide = 42099.82c : (n,2n) + 3 MT = 17 Q = -1.42176E+01 MeV Emin = 1.43612E+01 MeV frac = 1.00000E+00 Product nuclide = 42098.82c : (n,3n) + 4 MT = 22 Q = -3.18404E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 40096.82c : (n,nalpha) + 5 MT = 28 Q = -1.06143E+01 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 410990 : (n,np) + 6 MT = 51 Q = -5.35599E-01 MeV Emin = 5.36129E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -6.94399E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -1.06370E+00 MeV Emin = 1.07119E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -1.13610E+00 MeV Emin = 1.13810E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 91 Q = -1.13600E+00 MeV Emin = 1.13810E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 11 MT = 102 Q = 5.39825E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 421010 : (n,gamma) + 12 MT = 103 Q = -5.44653E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 411000 : (n,p) + 13 MT = 104 Q = -8.82651E+00 MeV Emin = 9.62972E+00 MeV frac = 1.00000E+00 Product nuclide = 410990 : (n,d) + 14 MT = 105 Q = -9.53346E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 410980 : (n,t) + 15 MT = 107 Q = 2.41940E+00 MeV Emin = 1.37500E-01 MeV frac = 1.00000E+00 Product nuclide = 400970 : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = -3.18404E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.06143E+01 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -5.44653E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -8.82651E+00 MeV Emin = 9.62972E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -9.53346E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 107 Q = 2.41940E+00 MeV Emin = 1.37500E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 6.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 9.62972E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.00000E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 1.37500E-01 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.46067E-03 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 5.36129E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 11 Q = 3.03437E+00 MeV frac = 1.00000E+00 Product nuclide = 44100.82c : beta- + beta- + + Nuclide 113 / 1657 : 43099.82c -- technetium 99 (Tc-99) + + Pointers : 857962 34415 + Primary type : Transport + Nuclide ZAI : 430990 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Tc99.ACE + Atomic weight (AW) : 98.90627 + Atomic weight ratio (AWR) : 98.05661 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+02 + Half-life : 6.67E+12 seconds (211,640 years) + Specific ingestion toxicity : 6.40E-10 Sv/Bq + Specific inhalation toxicity : 1.30E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 40 reaction channels + - 52 special reactions + - 17 transmutation reactions + - 15 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 40 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 5 Q = 0.00000E+00 MeV Emin = 8.50000E-02 MeV frac = 1.00000E+00 Product nuclide = self : anything + 3 MT = 16 Q = -8.96662E+00 MeV Emin = 9.05806E+00 MeV frac = 1.00000E+00 Product nuclide = 430980 : (n,2n) + 4 MT = 17 Q = -1.62454E+01 MeV Emin = 1.64111E+01 MeV frac = 1.00000E+00 Product nuclide = 430970 : (n,3n) + 5 MT = 22 Q = -2.96576E+00 MeV Emin = 5.40000E+00 MeV frac = 1.00000E+00 Product nuclide = 41095.82c : (n,nalpha) + 6 MT = 24 Q = -1.14546E+01 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 41094.82c : (n,2nalpha) + 7 MT = 28 Q = -6.50027E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 42098.82c : (n,np) + 8 MT = 32 Q = -1.29182E+01 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 42097.82c : (n,nd) + 9 MT = 33 Q = -1.34821E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 42096.82c : (n,nt) + 10 MT = 41 Q = -1.51428E+01 MeV Emin = 1.52972E+01 MeV frac = 1.00000E+00 Product nuclide = 42097.82c : (n,2np) + 11 MT = 51 Q = -1.40511E-01 MeV Emin = 1.36701E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 12 MT = 52 Q = -1.42683E-01 MeV Emin = 1.43041E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 13 MT = 53 Q = -1.81094E-01 MeV Emin = 1.75000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 14 MT = 54 Q = -5.09105E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 15 MT = 55 Q = -5.34430E-01 MeV Emin = 5.29910E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 16 MT = 56 Q = -5.36900E-01 MeV Emin = 5.41128E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 17 MT = 57 Q = -6.12490E-01 MeV Emin = 6.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 18 MT = 58 Q = -6.25410E-01 MeV Emin = 6.26571E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 19 MT = 59 Q = -6.52770E-01 MeV Emin = 6.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 20 MT = 60 Q = -6.71543E-01 MeV Emin = 6.69570E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 21 MT = 61 Q = -7.19800E-01 MeV Emin = 7.26524E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 22 MT = 62 Q = -7.26700E-01 MeV Emin = 7.31191E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 23 MT = 63 Q = -7.61690E-01 MeV Emin = 7.60194E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 24 MT = 64 Q = -7.61910E-01 MeV Emin = 7.69458E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 25 MT = 65 Q = -9.20596E-01 MeV Emin = 9.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 26 MT = 66 Q = -9.86150E-01 MeV Emin = 9.73104E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 27 MT = 67 Q = -1.00406E+00 MeV Emin = 1.00715E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 28 MT = 68 Q = -1.01746E+00 MeV Emin = 1.02291E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 29 MT = 69 Q = -1.07221E+00 MeV Emin = 1.04872E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 30 MT = 70 Q = -1.08147E+00 MeV Emin = 1.08782E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 31 MT = 91 Q = -1.08147E+00 MeV Emin = 1.08782E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 32 MT = 102 Q = 6.76441E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 431000 : (n,gamma) + 33 MT = 103 Q = -5.74874E-01 MeV Emin = 1.24138E+00 MeV frac = 1.00000E+00 Product nuclide = 42099.82c : (n,p) + 34 MT = 104 Q = -4.27569E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 42098.82c : (n,d) + 35 MT = 105 Q = -6.66095E+00 MeV Emin = 7.80000E+00 MeV frac = 1.00000E+00 Product nuclide = 42097.82c : (n,t) + 36 MT = 106 Q = -8.57624E+00 MeV Emin = 1.15000E+01 MeV frac = 1.00000E+00 Product nuclide = 410970 : (n,He-3) + 37 MT = 107 Q = 3.92732E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 410960 : (n,alpha) + 38 MT = 108 Q = 7.13659E-01 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 390920 : (n,2alpha) + 39 MT = 111 Q = -1.03035E+01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 410980 : (n,2p) + 40 MT = 112 Q = -3.30824E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 40095.82c : (n,palpha) + + 15 additional transport branches: + + 1 MT = 22 Q = -2.96576E+00 MeV Emin = 5.40000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 24 Q = -1.14546E+01 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,2nalpha) + 3 MT = 28 Q = -6.50027E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 4 MT = 32 Q = -1.29182E+01 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 5 MT = 33 Q = -1.34821E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 6 MT = 41 Q = -1.51428E+01 MeV Emin = 1.52972E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,2np) + 7 MT = 103 Q = -5.74874E-01 MeV Emin = 1.24138E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 8 MT = 104 Q = -4.27569E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 9 MT = 105 Q = -6.66095E+00 MeV Emin = 7.80000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 10 MT = 106 Q = -8.57624E+00 MeV Emin = 1.15000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 11 MT = 107 Q = 3.92732E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 12 MT = 108 Q = 7.13659E-01 MeV Emin = 2.00000E+00 MeV frac = 2.00000E+00 Product nuclide = 2004.82c : (n,2alpha) + 13 MT = 111 Q = -1.03035E+01 MeV Emin = 1.30000E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + 14 MT = 112 Q = -3.30824E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,palpha) + 15 MT = 112 Q = -3.30824E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,palpha) + + 52 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.24138E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 7.80000E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.15000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 600 Q = 0.00000E+00 MeV Emin = 1.30000E+00 MeV : (n,p) to ground state + 8 MT = 601 Q = -9.77850E-02 MeV Emin = 1.30000E+00 MeV : (n,p1) + 9 MT = 602 Q = -2.35508E-01 MeV Emin = 1.40000E+00 MeV : (n,p2) + 10 MT = 603 Q = -3.51240E-01 MeV Emin = 1.60000E+00 MeV : (n,p3) + 11 MT = 604 Q = -5.25197E-01 MeV Emin = 1.80000E+00 MeV : (n,p4) + 12 MT = 605 Q = -5.48680E-01 MeV Emin = 1.80000E+00 MeV : (n,p5) + 13 MT = 606 Q = -6.15080E-01 MeV Emin = 1.80000E+00 MeV : (n,p6) + 14 MT = 607 Q = -6.31770E-01 MeV Emin = 1.95000E+00 MeV : (n,p7) + 15 MT = 608 Q = -6.84500E-01 MeV Emin = 1.80000E+00 MeV : (n,p8) + 16 MT = 609 Q = -6.97970E-01 MeV Emin = 1.95000E+00 MeV : (n,p9) + 17 MT = 610 Q = -7.52400E-01 MeV Emin = 2.00000E+00 MeV : (n,p10) + 18 MT = 649 Q = -7.52400E-01 MeV Emin = 2.00000E+00 MeV : (n,p) to continuum + 19 MT = 650 Q = 0.00000E+00 MeV Emin = 5.00000E+00 MeV : (n,d) to ground state + 20 MT = 651 Q = -7.34750E-01 MeV Emin = 5.40000E+00 MeV : (n,d1) + 21 MT = 652 Q = -7.87384E-01 MeV Emin = 5.80000E+00 MeV : (n,d2) + 22 MT = 653 Q = -1.43221E+00 MeV Emin = 6.20000E+00 MeV : (n,d3) + 23 MT = 654 Q = -1.51004E+00 MeV Emin = 6.60000E+00 MeV : (n,d4) + 24 MT = 655 Q = -1.75848E+00 MeV Emin = 6.80000E+00 MeV : (n,d5) + 25 MT = 699 Q = -1.75848E+00 MeV Emin = 7.20000E+00 MeV : (n,d) to continuum + 26 MT = 700 Q = 0.00000E+00 MeV Emin = 7.80000E+00 MeV : (n,t) to ground state + 27 MT = 701 Q = -4.80900E-01 MeV Emin = 8.00000E+00 MeV : (n,t1) + 28 MT = 702 Q = -6.58130E-01 MeV Emin = 8.00000E+00 MeV : (n,t2) + 29 MT = 703 Q = -6.79590E-01 MeV Emin = 8.50000E+00 MeV : (n,t3) + 30 MT = 704 Q = -7.19190E-01 MeV Emin = 8.50000E+00 MeV : (n,t4) + 31 MT = 705 Q = -7.20920E-01 MeV Emin = 8.50000E+00 MeV : (n,t5) + 32 MT = 749 Q = -7.20920E-01 MeV Emin = 8.50000E+00 MeV : (n,t) to continuum + 33 MT = 750 Q = 0.00000E+00 MeV Emin = 1.15000E+01 MeV : (n,He-3) to ground state + 34 MT = 751 Q = -7.43350E-01 MeV Emin = 1.20000E+01 MeV : (n,He-3_1) + 35 MT = 752 Q = -1.14796E+00 MeV Emin = 1.25000E+01 MeV : (n,He-3_2) + 36 MT = 753 Q = -1.16000E+00 MeV Emin = 1.25000E+01 MeV : (n,He-3_3) + 37 MT = 754 Q = -1.25101E+00 MeV Emin = 1.25000E+01 MeV : (n,He-3_4) + 38 MT = 755 Q = -1.27609E+00 MeV Emin = 1.30000E+01 MeV : (n,He-3_5) + 39 MT = 799 Q = -1.27609E+00 MeV Emin = 1.35000E+01 MeV : (n,He-3) to continuum + 40 MT = 800 Q = 3.92732E+00 MeV Emin = 1.00000E-11 MeV : (n,alpha) to ground state + 41 MT = 801 Q = 3.88313E+00 MeV Emin = 1.00000E-11 MeV : (n,a1) + 42 MT = 802 Q = 3.78122E+00 MeV Emin = 1.00000E-11 MeV : (n,a2) + 43 MT = 803 Q = 3.74274E+00 MeV Emin = 1.00000E-11 MeV : (n,a3) + 44 MT = 804 Q = 3.69432E+00 MeV Emin = 1.00000E-11 MeV : (n,a4) + 45 MT = 805 Q = 3.41545E+00 MeV Emin = 1.00000E-11 MeV : (n,a5) + 46 MT = 806 Q = 3.29237E+00 MeV Emin = 1.00000E-11 MeV : (n,a6) + 47 MT = 807 Q = 3.23269E+00 MeV Emin = 1.00000E-11 MeV : (n,a7) + 48 MT = 808 Q = 3.05944E+00 MeV Emin = 1.00000E-11 MeV : (n,a8) + 49 MT = 809 Q = 2.92466E+00 MeV Emin = 1.00000E-11 MeV : (n,a9) + 50 MT = 810 Q = 2.88190E+00 MeV Emin = 1.00000E-11 MeV : (n,a10) + 51 MT = 849 Q = 2.88190E+00 MeV Emin = 1.00000E-11 MeV : (n,alpha) to continuum + 52 MT = 4 Q = 0.00000E+00 MeV Emin = 1.36701E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.93800E-01 MeV frac = 1.00000E+00 Product nuclide = 440990 : beta- + + Nuclide 114 / 1657 : 44100.82c -- ruthenium 100 (Ru-100) + + Pointers : 914002 31563 + Primary type : Transport + Nuclide ZAI : 441000 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ru100.ACE + Atomic weight (AW) : 99.90423 + Atomic weight ratio (AWR) : 99.04600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 28 reaction channels + - 6 special reactions + - 10 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 28 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -9.67789E+00 MeV Emin = 9.86186E+00 MeV frac = 1.00000E+00 Product nuclide = 440990 : (n,2n) + 3 MT = 17 Q = -1.71478E+01 MeV Emin = 1.73209E+01 MeV frac = 1.00000E+00 Product nuclide = 440980 : (n,3n) + 4 MT = 22 Q = -2.84860E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 42096.82c : (n,nalpha) + 5 MT = 28 Q = -9.18903E+00 MeV Emin = 9.75962E+00 MeV frac = 1.00000E+00 Product nuclide = 43099.82c : (n,np) + 6 MT = 32 Q = -1.58472E+01 MeV Emin = 1.60072E+01 MeV frac = 1.00000E+00 Product nuclide = 430980 : (n,nd) + 7 MT = 51 Q = -5.39599E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 8 MT = 52 Q = -1.13040E+00 MeV Emin = 1.07090E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 9 MT = 53 Q = -1.22650E+00 MeV Emin = 1.21461E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 10 MT = 54 Q = -1.36210E+00 MeV Emin = 1.34439E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 11 MT = 55 Q = -1.74070E+00 MeV Emin = 1.75000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 12 MT = 56 Q = -1.86530E+00 MeV Emin = 1.85660E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 13 MT = 57 Q = -1.88120E+00 MeV Emin = 1.89216E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 14 MT = 58 Q = -2.05170E+00 MeV Emin = 2.07242E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 15 MT = 59 Q = -2.06390E+00 MeV Emin = 2.08474E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 16 MT = 60 Q = -2.07770E+00 MeV Emin = 2.09868E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 17 MT = 61 Q = -2.09930E+00 MeV Emin = 2.12050E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 18 MT = 62 Q = -2.16730E+00 MeV Emin = 2.18918E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 19 MT = 63 Q = -2.24060E+00 MeV Emin = 2.26322E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 20 MT = 64 Q = -2.38720E+00 MeV Emin = 2.41130E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 21 MT = 65 Q = -2.46940E+00 MeV Emin = 2.49433E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 22 MT = 66 Q = -2.51680E+00 MeV Emin = 2.54221E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 23 MT = 91 Q = -2.61330E+00 MeV Emin = 2.63969E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 24 MT = 102 Q = 6.80206E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 44101.82c : (n,gamma) + 25 MT = 103 Q = -2.42034E+00 MeV Emin = 2.87736E+00 MeV frac = 1.00000E+00 Product nuclide = 431000 : (n,p) + 26 MT = 104 Q = -6.87891E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 43099.82c : (n,d) + 27 MT = 105 Q = -9.66206E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 430980 : (n,t) + 28 MT = 107 Q = 3.97709E+00 MeV Emin = 9.96875E-02 MeV frac = 1.00000E+00 Product nuclide = 42097.82c : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -2.84860E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -9.18903E+00 MeV Emin = 9.75962E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.58472E+01 MeV Emin = 1.60072E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 103 Q = -2.42034E+00 MeV Emin = 2.87736E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -6.87891E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -9.66206E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 107 Q = 3.97709E+00 MeV Emin = 9.96875E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.87736E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.00000E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 9.96875E-02 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 5.78125E-04 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 5.00000E-01 MeV : total inelastic scattering + + Nuclide 115 / 1657 : 44101.82c -- ruthenium 101 (Ru-101) + + Pointers : 917106 31609 + Primary type : Transport + Nuclide ZAI : 441010 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ru101.ACE + Atomic weight (AW) : 100.90583 + Atomic weight ratio (AWR) : 100.03900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 24 reaction channels + - 4 special reactions + - 7 transmutation reactions + - 4 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 24 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.80150E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 44100.82c : (n,2n) + 3 MT = 17 Q = -1.64750E+01 MeV Emin = 1.66397E+01 MeV frac = 1.00000E+00 Product nuclide = 440990 : (n,3n) + 4 MT = 22 Q = -2.83210E+00 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 42097.82c : (n,nalpha) + 5 MT = 28 Q = -9.22190E+00 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 431000 : (n,np) + 6 MT = 51 Q = -1.27200E-01 MeV Emin = 1.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -3.06800E-01 MeV Emin = 3.09007E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -3.11300E-01 MeV Emin = 3.12611E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -3.25200E-01 MeV Emin = 3.28314E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -3.44100E-01 MeV Emin = 3.45552E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -4.22100E-01 MeV Emin = 4.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -4.62300E-01 MeV Emin = 4.46620E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -5.27500E-01 MeV Emin = 5.30261E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -5.35000E-01 MeV Emin = 5.35304E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -5.45100E-01 MeV Emin = 5.49669E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -6.16300E-01 MeV Emin = 6.22224E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -6.23400E-01 MeV Emin = 6.25928E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -6.23500E-01 MeV Emin = 6.25928E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -6.43800E-01 MeV Emin = 6.48731E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -6.84000E-01 MeV Emin = 6.85000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 21 MT = 91 Q = -6.95000E-01 MeV Emin = 6.97660E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 22 MT = 102 Q = 9.21965E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 44102.82c : (n,gamma) + 23 MT = 103 Q = -8.42330E-01 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 431010 : (n,p) + 24 MT = 107 Q = 5.81030E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 42098.82c : (n,alpha) + + 4 additional transport branches: + + 1 MT = 22 Q = -2.83210E+00 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -9.22190E+00 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -8.42330E-01 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 107 Q = 5.81030E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 4 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.00000E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 5.00000E+00 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 6.05093E-04 MeV : damage-energy production + 4 MT = 4 Q = 0.00000E+00 MeV Emin = 1.00000E-01 MeV : total inelastic scattering + + Nuclide 116 / 1657 : 44102.82c -- ruthenium 102 (Ru-102) + + Pointers : 919553 31655 + Primary type : Transport + Nuclide ZAI : 441020 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ru102.ACE + Atomic weight (AW) : 101.90542 + Atomic weight ratio (AWR) : 101.03000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 18 reaction channels + - 7 special reactions + - 10 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 18 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -9.22060E+00 MeV Emin = 9.31190E+00 MeV frac = 1.00000E+00 Product nuclide = 44101.82c : (n,2n) + 3 MT = 17 Q = -1.60220E+01 MeV Emin = 1.61810E+01 MeV frac = 1.00000E+00 Product nuclide = 44100.82c : (n,3n) + 4 MT = 22 Q = -3.41130E+00 MeV Emin = 9.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 42098.82c : (n,nalpha) + 5 MT = 28 Q = -1.00510E+01 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 431010 : (n,np) + 6 MT = 51 Q = -4.75100E-01 MeV Emin = 4.75000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -9.43700E-01 MeV Emin = 9.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -1.10320E+00 MeV Emin = 1.05705E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -1.10640E+00 MeV Emin = 1.11624E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -1.52170E+00 MeV Emin = 1.53608E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -1.58060E+00 MeV Emin = 1.57215E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 91 Q = -1.58060E+00 MeV Emin = 1.75000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 13 MT = 102 Q = 6.23205E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 44103.82c : (n,gamma) + 14 MT = 103 Q = -3.74750E+00 MeV Emin = 6.25000E+00 MeV frac = 1.00000E+00 Product nuclide = 431020 : (n,p) + 15 MT = 104 Q = -7.82620E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 431010 : (n,d) + 16 MT = 105 Q = -9.96060E+00 MeV Emin = 1.35000E+01 MeV frac = 1.00000E+00 Product nuclide = 431000 : (n,t) + 17 MT = 106 Q = -9.77250E+00 MeV Emin = 1.95000E+01 MeV frac = 1.00000E+00 Product nuclide = 42100.82c : (n,He-3) + 18 MT = 107 Q = 2.65136E+00 MeV Emin = 1.75000E-01 MeV frac = 1.00000E+00 Product nuclide = 42099.82c : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -3.41130E+00 MeV Emin = 9.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.00510E+01 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -3.74750E+00 MeV Emin = 6.25000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -7.82620E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -9.96060E+00 MeV Emin = 1.35000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 106 Q = -9.77250E+00 MeV Emin = 1.95000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 7 MT = 107 Q = 2.65136E+00 MeV Emin = 1.75000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 6.25000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.10000E+01 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.35000E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.95000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.75000E-01 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 6.42994E-04 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 4.75000E-01 MeV : total inelastic scattering + + Nuclide 117 / 1657 : 44103.82c -- ruthenium 103 (Ru-103) + + Pointers : 922000 31701 + Primary type : Transport + Nuclide ZAI : 441030 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ru103.ACE + Atomic weight (AW) : 102.90400 + Atomic weight ratio (AWR) : 102.02000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 3.39E+06 seconds (39.3 days) + Specific ingestion toxicity : 7.30E-10 Sv/Bq + Specific inhalation toxicity : 3.00E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 33 reaction channels + - 6 special reactions + - 9 transmutation reactions + - 6 transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 33 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.23240E+00 MeV Emin = 6.29350E+00 MeV frac = 1.00000E+00 Product nuclide = 44102.82c : (n,2n) + 3 MT = 17 Q = -1.54530E+01 MeV Emin = 1.57500E+01 MeV frac = 1.00000E+00 Product nuclide = 44101.82c : (n,3n) + 4 MT = 22 Q = -3.71780E+00 MeV Emin = 1.42500E+01 MeV frac = 1.00000E+00 Product nuclide = 42099.82c : (n,nalpha) + 5 MT = 28 Q = -9.97990E+00 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 431020 : (n,np) + 6 MT = 51 Q = -2.70000E-03 MeV Emin = 2.50000E-03 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.36100E-01 MeV Emin = 1.30000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -1.74300E-01 MeV Emin = 1.75660E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -2.13600E-01 MeV Emin = 1.99267E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -2.38200E-01 MeV Emin = 2.28112E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -2.97500E-01 MeV Emin = 3.00289E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -3.46400E-01 MeV Emin = 3.22484E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -4.04100E-01 MeV Emin = 3.78930E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -4.06100E-01 MeV Emin = 4.09071E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -4.32100E-01 MeV Emin = 4.23210E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -5.01200E-01 MeV Emin = 4.71225E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -5.35400E-01 MeV Emin = 5.40223E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -5.48200E-01 MeV Emin = 5.47638E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -5.54600E-01 MeV Emin = 5.59871E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -5.57700E-01 MeV Emin = 5.61971E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 21 MT = 66 Q = -5.62900E-01 MeV Emin = 5.65795E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 22 MT = 67 Q = -5.68200E-01 MeV Emin = 5.73470E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 23 MT = 68 Q = -5.92000E-01 MeV Emin = 5.83110E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 24 MT = 69 Q = -6.22000E-01 MeV Emin = 6.24119E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 25 MT = 70 Q = -6.53700E-01 MeV Emin = 6.59208E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 26 MT = 71 Q = -6.61500E-01 MeV Emin = 6.59208E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 27 MT = 72 Q = -6.97200E-01 MeV Emin = 6.86007E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 28 MT = 91 Q = -6.97200E-01 MeV Emin = 6.86007E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 29 MT = 102 Q = 8.90142E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 44104.82c : (n,gamma) + 30 MT = 103 Q = -1.87710E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 431030 : (n,p) + 31 MT = 104 Q = -7.75540E+00 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 431020 : (n,d) + 32 MT = 105 Q = -7.80150E+00 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 431010 : (n,t) + 33 MT = 107 Q = 4.57230E+00 MeV Emin = 2.25000E+00 MeV frac = 1.00000E+00 Product nuclide = 42100.82c : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = -3.71780E+00 MeV Emin = 1.42500E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -9.97990E+00 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -1.87710E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -7.75540E+00 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -7.80150E+00 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 107 Q = 4.57230E+00 MeV Emin = 2.25000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 5.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.25000E+01 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.20000E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 2.25000E+00 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 6.00000E-04 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 2.50000E-03 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 1 Q = 7.66200E-01 MeV frac = 1.19763E-02 Product nuclide = 45103.82c : beta- + 2 RTYP = 1 Q = 7.26441E-01 MeV frac = 9.88024E-01 Product nuclide = 451031 : beta- + + Nuclide 118 / 1657 : 44104.82c -- ruthenium 104 (Ru-104) + + Pointers : 926926 31747 + Primary type : Transport + Nuclide ZAI : 441040 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ru104.ACE + Atomic weight (AW) : 103.90258 + Atomic weight ratio (AWR) : 103.01000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 16 reaction channels + - 6 special reactions + - 9 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 16 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.90390E+00 MeV Emin = 8.99034E+00 MeV frac = 1.00000E+00 Product nuclide = 44103.82c : (n,2n) + 3 MT = 17 Q = -1.51360E+01 MeV Emin = 1.52830E+01 MeV frac = 1.00000E+00 Product nuclide = 44102.82c : (n,3n) + 4 MT = 22 Q = -4.33160E+00 MeV Emin = 1.12500E+01 MeV frac = 1.00000E+00 Product nuclide = 42100.82c : (n,nalpha) + 5 MT = 28 Q = -1.07810E+01 MeV Emin = 1.32500E+01 MeV frac = 1.00000E+00 Product nuclide = 431030 : (n,np) + 6 MT = 51 Q = -3.58000E-01 MeV Emin = 3.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -8.88500E-01 MeV Emin = 8.75000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -8.93100E-01 MeV Emin = 9.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -9.88300E-01 MeV Emin = 9.75000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -1.24240E+00 MeV Emin = 1.25000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 91 Q = -1.24240E+00 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 12 MT = 102 Q = 5.91010E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 44105.82c : (n,gamma) + 13 MT = 103 Q = -4.82050E+00 MeV Emin = 7.25000E+00 MeV frac = 1.00000E+00 Product nuclide = 431040 : (n,p) + 14 MT = 104 Q = -8.55640E+00 MeV Emin = 1.17500E+01 MeV frac = 1.00000E+00 Product nuclide = 431030 : (n,d) + 15 MT = 105 Q = -1.04020E+01 MeV Emin = 1.37500E+01 MeV frac = 1.00000E+00 Product nuclide = 431020 : (n,t) + 16 MT = 107 Q = 1.13096E+00 MeV Emin = 6.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 421010 : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = -4.33160E+00 MeV Emin = 1.12500E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.07810E+01 MeV Emin = 1.32500E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -4.82050E+00 MeV Emin = 7.25000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -8.55640E+00 MeV Emin = 1.17500E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -1.04020E+01 MeV Emin = 1.37500E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 107 Q = 1.13096E+00 MeV Emin = 6.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 7.25000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.17500E+01 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.37500E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 6.50000E+00 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 6.42771E-04 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 3.50000E-01 MeV : total inelastic scattering + + Nuclide 119 / 1657 : 44105.82c -- ruthenium 105 (Ru-105) + + Pointers : 929081 31793 + Primary type : Transport + Nuclide ZAI : 441050 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ru105.ACE + Atomic weight (AW) : 104.91124 + Atomic weight ratio (AWR) : 104.01000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.60E+04 seconds (4.44 hours) + Specific ingestion toxicity : 2.60E-10 Sv/Bq + Specific inhalation toxicity : 1.80E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 17 reaction channels + - 6 special reactions + - 9 transmutation reactions + - 6 transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 17 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.91010E+00 MeV Emin = 5.96700E+00 MeV frac = 1.00000E+00 Product nuclide = 44104.82c : (n,2n) + 3 MT = 17 Q = -1.48140E+01 MeV Emin = 1.49564E+01 MeV frac = 1.00000E+00 Product nuclide = 44103.82c : (n,3n) + 4 MT = 22 Q = -4.84390E+00 MeV Emin = 1.15000E+01 MeV frac = 1.00000E+00 Product nuclide = 421010 : (n,nalpha) + 5 MT = 28 Q = -1.07310E+01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 431040 : (n,np) + 6 MT = 51 Q = -2.06000E-02 MeV Emin = 2.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.07900E-01 MeV Emin = 1.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -1.59500E-01 MeV Emin = 1.43015E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -1.63800E-01 MeV Emin = 1.63202E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -2.08600E-01 MeV Emin = 2.09375E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -2.29500E-01 MeV Emin = 2.31250E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 91 Q = -2.29500E-01 MeV Emin = 2.31250E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 13 MT = 102 Q = 8.46575E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 44106.82c : (n,gamma) + 14 MT = 103 Q = -2.79920E+00 MeV Emin = 5.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 431050 : (n,p) + 15 MT = 104 Q = -8.50610E+00 MeV Emin = 1.15000E+01 MeV frac = 1.00000E+00 Product nuclide = 431040 : (n,d) + 16 MT = 105 Q = -8.20950E+00 MeV Emin = 1.17500E+01 MeV frac = 1.00000E+00 Product nuclide = 431030 : (n,t) + 17 MT = 107 Q = 3.27380E+00 MeV Emin = 3.25000E+00 MeV frac = 1.00000E+00 Product nuclide = 421020 : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = -4.84390E+00 MeV Emin = 1.15000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.07310E+01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -2.79920E+00 MeV Emin = 5.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -8.50610E+00 MeV Emin = 1.15000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -8.20950E+00 MeV Emin = 1.17500E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 107 Q = 3.27380E+00 MeV Emin = 3.25000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 5.50000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.15000E+01 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.17500E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 3.25000E+00 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 6.25000E-04 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 2.00000E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.91800E+00 MeV frac = 7.16433E-01 Product nuclide = 45105.82c : beta- + 2 RTYP = 1 Q = 1.78822E+00 MeV frac = 2.83567E-01 Product nuclide = 451051 : beta- + + Nuclide 120 / 1657 : 44106.82c -- ruthenium 106 (Ru-106) + + Pointers : 933504 31839 + Primary type : Transport + Nuclide ZAI : 441060 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ru106.ACE + Atomic weight (AW) : 105.90780 + Atomic weight ratio (AWR) : 104.99800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 3.21E+07 seconds (1.02 years) + Specific ingestion toxicity : 7.00E-09 Sv/Bq + Specific inhalation toxicity : 6.60E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 13 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 6 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 13 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -2.70000E-01 MeV Emin = 2.64427E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -7.11000E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -7.91000E-01 MeV Emin = 7.58151E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -9.89000E-01 MeV Emin = 9.61315E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 91 Q = -2.37740E+00 MeV Emin = 2.40004E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 7 MT = 102 Q = 5.48000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 441070 : (n,gamma) + 8 MT = 103 Q = -5.51850E+00 MeV Emin = 5.57106E+00 MeV frac = 1.00000E+00 Product nuclide = 431060 : (n,p) + 9 MT = 104 Q = -8.85420E+00 MeV Emin = 8.93853E+00 MeV frac = 1.00000E+00 Product nuclide = 431050 : (n,d) + 10 MT = 105 Q = -1.05070E+01 MeV Emin = 1.06071E+01 MeV frac = 1.00000E+00 Product nuclide = 431040 : (n,t) + 11 MT = 106 Q = -1.26890E+01 MeV Emin = 1.28099E+01 MeV frac = 1.00000E+00 Product nuclide = 421040 : (n,He-3) + 12 MT = 107 Q = -7.64950E-02 MeV Emin = 7.00000E-02 MeV frac = 1.00000E+00 Product nuclide = 421030 : (n,alpha) + 13 MT = 111 Q = -1.56940E+01 MeV Emin = 1.58435E+01 MeV frac = 1.00000E+00 Product nuclide = 421050 : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = -5.51850E+00 MeV Emin = 5.57106E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -8.85420E+00 MeV Emin = 8.93853E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -1.05070E+01 MeV Emin = 1.06071E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -1.26890E+01 MeV Emin = 1.28099E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = -7.64950E-02 MeV Emin = 7.00000E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -1.56940E+01 MeV Emin = 1.58435E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 5.57106E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.93853E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.06071E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.28099E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 7.00000E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 2.64427E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.94000E-02 MeV frac = 1.00000E+00 Product nuclide = 451060 : beta- + + Nuclide 121 / 1657 : 45103.82c -- rhodium 103 (Rh-103) + + Pointers : 977468 31471 + Primary type : Transport + Nuclide ZAI : 451030 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Rh103.ACE + Atomic weight (AW) : 102.90551 + Atomic weight ratio (AWR) : 102.02150 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 3.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 45 reaction channels + - 92 special reactions + - 25 transmutation reactions + - 29 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 45 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 11 Q = -2.00105E+01 MeV Emin = 2.02067E+01 MeV frac = 1.00000E+00 Product nuclide = self : (n,2nd) + 3 MT = 16 Q = -9.31828E+00 MeV Emin = 9.40962E+00 MeV frac = 1.00000E+00 Product nuclide = 451020 : (n,2n) + 4 MT = 17 Q = -1.67568E+01 MeV Emin = 1.69211E+01 MeV frac = 1.00000E+00 Product nuclide = 451010 : (n,3n) + 5 MT = 22 Q = -3.12388E+00 MeV Emin = 3.15450E+00 MeV frac = 1.00000E+00 Product nuclide = 43099.82c : (n,nalpha) + 6 MT = 24 Q = -1.20905E+01 MeV Emin = 1.22090E+01 MeV frac = 1.00000E+00 Product nuclide = 430980 : (n,2nalpha) + 7 MT = 25 Q = -1.93693E+01 MeV Emin = 1.95592E+01 MeV frac = 1.00000E+00 Product nuclide = 430970 : (n,3nalpha) + 8 MT = 28 Q = -6.21339E+00 MeV Emin = 6.27429E+00 MeV frac = 1.00000E+00 Product nuclide = 44102.82c : (n,np) + 9 MT = 29 Q = -6.08964E+00 MeV Emin = 6.14933E+00 MeV frac = 1.00000E+00 Product nuclide = 41095.82c : (n,n2alpha) + 10 MT = 32 Q = -1.32084E+01 MeV Emin = 1.33379E+01 MeV frac = 1.00000E+00 Product nuclide = 44101.82c : (n,nd) + 11 MT = 33 Q = -1.37533E+01 MeV Emin = 1.38881E+01 MeV frac = 1.00000E+00 Product nuclide = 44100.82c : (n,nt) + 12 MT = 34 Q = -1.69371E+01 MeV Emin = 1.71031E+01 MeV frac = 1.00000E+00 Product nuclide = 431000 : (n,nHe-3) + 13 MT = 37 Q = -2.66474E+01 MeV Emin = 2.69086E+01 MeV frac = 1.00000E+00 Product nuclide = cut: Rh-100 : (n,4n) + 14 MT = 41 Q = -1.54330E+01 MeV Emin = 1.55843E+01 MeV frac = 1.00000E+00 Product nuclide = 44101.82c : (n,2np) + 15 MT = 42 Q = -2.22351E+01 MeV Emin = 2.24531E+01 MeV frac = 1.00000E+00 Product nuclide = cut: Ru-100 : (n,3np) + 16 MT = 44 Q = -1.62641E+01 MeV Emin = 1.64235E+01 MeV frac = 1.00000E+00 Product nuclide = 431010 : (n,n2p) + 17 MT = 45 Q = -9.62414E+00 MeV Emin = 9.71848E+00 MeV frac = 1.00000E+00 Product nuclide = 42098.82c : (n,npalpha) + 18 MT = 51 Q = -3.97560E-02 MeV Emin = 4.00653E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 19 MT = 52 Q = -9.30410E-02 MeV Emin = 9.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 20 MT = 53 Q = -2.94980E-01 MeV Emin = 2.89855E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 21 MT = 54 Q = -3.57408E-01 MeV Emin = 3.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 22 MT = 55 Q = -5.36838E-01 MeV Emin = 5.40832E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 23 MT = 56 Q = -6.07450E-01 MeV Emin = 6.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 24 MT = 57 Q = -6.50085E-01 MeV Emin = 6.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 25 MT = 58 Q = -6.51798E-01 MeV Emin = 6.57322E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 26 MT = 59 Q = -6.57720E-01 MeV Emin = 6.61177E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 27 MT = 60 Q = -7.80500E-01 MeV Emin = 7.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 28 MT = 61 Q = -8.03070E-01 MeV Emin = 8.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 29 MT = 62 Q = -8.21460E-01 MeV Emin = 8.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 30 MT = 63 Q = -8.47580E-01 MeV Emin = 8.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 31 MT = 64 Q = -8.80470E-01 MeV Emin = 8.69550E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 32 MT = 65 Q = -9.20100E-01 MeV Emin = 9.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 33 MT = 91 Q = -9.20100E-01 MeV Emin = 9.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 34 MT = 102 Q = 6.99896E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 451040 : (n,gamma) + 35 MT = 103 Q = 1.89981E-02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 44103.82c : (n,p) + 36 MT = 104 Q = -3.98882E+00 MeV Emin = 4.02792E+00 MeV frac = 1.00000E+00 Product nuclide = 44102.82c : (n,d) + 37 MT = 105 Q = -6.95116E+00 MeV Emin = 7.01930E+00 MeV frac = 1.00000E+00 Product nuclide = 44101.82c : (n,t) + 38 MT = 106 Q = -8.54607E+00 MeV Emin = 8.62984E+00 MeV frac = 1.00000E+00 Product nuclide = 431010 : (n,He-3) + 39 MT = 107 Q = 3.64052E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 431000 : (n,alpha) + 40 MT = 108 Q = 8.03440E-01 MeV Emin = 1.09993E-04 MeV frac = 1.00000E+00 Product nuclide = 410960 : (n,2alpha) + 41 MT = 111 Q = -9.96130E+00 MeV Emin = 1.00589E+01 MeV frac = 1.00000E+00 Product nuclide = 431020 : (n,2p) + 42 MT = 112 Q = -3.69875E+00 MeV Emin = 3.73501E+00 MeV frac = 1.00000E+00 Product nuclide = 42099.82c : (n,palpha) + 43 MT = 115 Q = -1.40396E+01 MeV Emin = 1.41772E+01 MeV frac = 1.00000E+00 Product nuclide = 431010 : (n,pd) + 44 MT = 116 Q = -1.61733E+01 MeV Emin = 1.63319E+01 MeV frac = 1.00000E+00 Product nuclide = 431000 : (n,pt) + 45 MT = 117 Q = -7.39957E+00 MeV Emin = 7.47210E+00 MeV frac = 1.00000E+00 Product nuclide = 42098.82c : (n,dalpha) + + 29 additional transport branches: + + 1 MT = 22 Q = -3.12388E+00 MeV Emin = 3.15450E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 24 Q = -1.20905E+01 MeV Emin = 1.22090E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,2nalpha) + 3 MT = 25 Q = -1.93693E+01 MeV Emin = 1.95592E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,3nalpha) + 4 MT = 28 Q = -6.21339E+00 MeV Emin = 6.27429E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 5 MT = 29 Q = -6.08964E+00 MeV Emin = 6.14933E+00 MeV frac = 2.00000E+00 Product nuclide = 2004.82c : (n,n2alpha) + 6 MT = 32 Q = -1.32084E+01 MeV Emin = 1.33379E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 7 MT = 33 Q = -1.37533E+01 MeV Emin = 1.38881E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 8 MT = 34 Q = -1.69371E+01 MeV Emin = 1.71031E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,nHe-3) + 9 MT = 41 Q = -1.54330E+01 MeV Emin = 1.55843E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,2np) + 10 MT = 42 Q = -2.22351E+01 MeV Emin = 2.24531E+01 MeV frac = 1.00000E+00 Product nuclide = cut: H-1 : (n,3np) + 11 MT = 44 Q = -1.62641E+01 MeV Emin = 1.64235E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,n2p) + 12 MT = 45 Q = -9.62414E+00 MeV Emin = 9.71848E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,npalpha) + 13 MT = 45 Q = -9.62414E+00 MeV Emin = 9.71848E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,npalpha) + 14 MT = 102 Q = 6.99896E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 451041 : (n,gamma) + 15 MT = 103 Q = 1.89981E-02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 16 MT = 104 Q = -3.98882E+00 MeV Emin = 4.02792E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 17 MT = 105 Q = -6.95116E+00 MeV Emin = 7.01930E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 18 MT = 106 Q = -8.54607E+00 MeV Emin = 8.62984E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 19 MT = 107 Q = 3.64052E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 20 MT = 108 Q = 8.03440E-01 MeV Emin = 1.09993E-04 MeV frac = 2.00000E+00 Product nuclide = 2004.82c : (n,2alpha) + 21 MT = 111 Q = -9.96130E+00 MeV Emin = 1.00589E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + 22 MT = 112 Q = -3.69875E+00 MeV Emin = 3.73501E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,palpha) + 23 MT = 112 Q = -3.69875E+00 MeV Emin = 3.73501E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,palpha) + 24 MT = 115 Q = -1.40396E+01 MeV Emin = 1.41772E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,pd) + 25 MT = 115 Q = -1.40396E+01 MeV Emin = 1.41772E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,pd) + 26 MT = 116 Q = -1.61733E+01 MeV Emin = 1.63319E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,pt) + 27 MT = 116 Q = -1.61733E+01 MeV Emin = 1.63319E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,pt) + 28 MT = 117 Q = -7.39957E+00 MeV Emin = 7.47210E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,dalpha) + 29 MT = 117 Q = -7.39957E+00 MeV Emin = 7.47210E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,dalpha) + + 92 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 4.02792E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 7.01930E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 8.62984E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 600 Q = 1.89981E-02 MeV Emin = 1.00000E+00 MeV : (n,p) to ground state + 8 MT = 601 Q = 1.61881E-02 MeV Emin = 6.00000E-02 MeV : (n,p1) + 9 MT = 602 Q = -1.17081E-01 MeV Emin = 6.17979E-01 MeV : (n,p2) + 10 MT = 603 Q = -1.55262E-01 MeV Emin = 1.00000E+00 MeV : (n,p3) + 11 MT = 604 Q = -1.94562E-01 MeV Emin = 1.02500E+00 MeV : (n,p4) + 12 MT = 605 Q = -2.19202E-01 MeV Emin = 1.10000E+00 MeV : (n,p5) + 13 MT = 606 Q = -2.78102E-01 MeV Emin = 1.10000E+00 MeV : (n,p6) + 14 MT = 607 Q = -2.79102E-01 MeV Emin = 1.20000E+00 MeV : (n,p7) + 15 MT = 608 Q = -3.27382E-01 MeV Emin = 1.20000E+00 MeV : (n,p8) + 16 MT = 609 Q = -3.85152E-01 MeV Emin = 1.20000E+00 MeV : (n,p9) + 17 MT = 610 Q = -3.87082E-01 MeV Emin = 1.20000E+00 MeV : (n,p10) + 18 MT = 611 Q = -4.13062E-01 MeV Emin = 1.30000E+00 MeV : (n,p11) + 19 MT = 612 Q = -4.82152E-01 MeV Emin = 1.40000E+00 MeV : (n,p12) + 20 MT = 613 Q = -5.16402E-01 MeV Emin = 1.40000E+00 MeV : (n,p13) + 21 MT = 614 Q = -5.29212E-01 MeV Emin = 1.40000E+00 MeV : (n,p14) + 22 MT = 615 Q = -5.35582E-01 MeV Emin = 1.60000E+00 MeV : (n,p15) + 23 MT = 649 Q = -5.35582E-01 MeV Emin = 5.37616E-01 MeV : (n,p) to continuum + 24 MT = 650 Q = -3.98882E+00 MeV Emin = 4.02792E+00 MeV : (n,d) to ground state + 25 MT = 651 Q = -4.46390E+00 MeV Emin = 4.50766E+00 MeV : (n,d1) + 26 MT = 652 Q = -4.93251E+00 MeV Emin = 4.98086E+00 MeV : (n,d2) + 27 MT = 653 Q = -5.09197E+00 MeV Emin = 5.14188E+00 MeV : (n,d3) + 28 MT = 654 Q = -5.09518E+00 MeV Emin = 5.14512E+00 MeV : (n,d4) + 29 MT = 655 Q = -5.51049E+00 MeV Emin = 5.56450E+00 MeV : (n,d5) + 30 MT = 656 Q = -5.56938E+00 MeV Emin = 5.62397E+00 MeV : (n,d6) + 31 MT = 657 Q = -5.59172E+00 MeV Emin = 5.64653E+00 MeV : (n,d7) + 32 MT = 658 Q = -5.78749E+00 MeV Emin = 5.84422E+00 MeV : (n,d8) + 33 MT = 659 Q = -5.82592E+00 MeV Emin = 5.88303E+00 MeV : (n,d9) + 34 MT = 660 Q = -5.86205E+00 MeV Emin = 5.91951E+00 MeV : (n,d10) + 35 MT = 661 Q = -5.95748E+00 MeV Emin = 6.01588E+00 MeV : (n,d11) + 36 MT = 662 Q = -6.02572E+00 MeV Emin = 6.08478E+00 MeV : (n,d12) + 37 MT = 663 Q = -6.03302E+00 MeV Emin = 6.09216E+00 MeV : (n,d13) + 38 MT = 664 Q = -6.17882E+00 MeV Emin = 6.23939E+00 MeV : (n,d14) + 39 MT = 665 Q = -6.20799E+00 MeV Emin = 6.26884E+00 MeV : (n,d15) + 40 MT = 699 Q = -6.20799E+00 MeV Emin = 6.26884E+00 MeV : (n,d) to continuum + 41 MT = 700 Q = -6.95116E+00 MeV Emin = 7.01930E+00 MeV : (n,t) to ground state + 42 MT = 701 Q = -7.07839E+00 MeV Emin = 7.14777E+00 MeV : (n,t1) + 43 MT = 702 Q = -7.25801E+00 MeV Emin = 7.32915E+00 MeV : (n,t2) + 44 MT = 703 Q = -7.26249E+00 MeV Emin = 7.33368E+00 MeV : (n,t3) + 45 MT = 704 Q = -7.27596E+00 MeV Emin = 7.34728E+00 MeV : (n,t4) + 46 MT = 705 Q = -7.29516E+00 MeV Emin = 7.36667E+00 MeV : (n,t5) + 47 MT = 706 Q = -7.37346E+00 MeV Emin = 7.44573E+00 MeV : (n,t6) + 48 MT = 707 Q = -7.47866E+00 MeV Emin = 7.55197E+00 MeV : (n,t7) + 49 MT = 708 Q = -7.48616E+00 MeV Emin = 7.55954E+00 MeV : (n,t8) + 50 MT = 709 Q = -7.49624E+00 MeV Emin = 7.56972E+00 MeV : (n,t9) + 51 MT = 710 Q = -7.54946E+00 MeV Emin = 7.62346E+00 MeV : (n,t10) + 52 MT = 711 Q = -7.56746E+00 MeV Emin = 7.64164E+00 MeV : (n,t11) + 53 MT = 712 Q = -7.57416E+00 MeV Emin = 7.64840E+00 MeV : (n,t12) + 54 MT = 713 Q = -7.57516E+00 MeV Emin = 7.64941E+00 MeV : (n,t13) + 55 MT = 714 Q = -7.63516E+00 MeV Emin = 7.71000E+00 MeV : (n,t14) + 56 MT = 715 Q = -7.66916E+00 MeV Emin = 7.74433E+00 MeV : (n,t15) + 57 MT = 749 Q = -7.66916E+00 MeV Emin = 7.74433E+00 MeV : (n,t) to continuum + 58 MT = 750 Q = -8.54607E+00 MeV Emin = 8.62984E+00 MeV : (n,He-3) to ground state + 59 MT = 751 Q = -8.55539E+00 MeV Emin = 8.63925E+00 MeV : (n,He-3_1) + 60 MT = 752 Q = -8.56167E+00 MeV Emin = 8.64559E+00 MeV : (n,He-3_2) + 61 MT = 753 Q = -8.75360E+00 MeV Emin = 8.83940E+00 MeV : (n,He-3_3) + 62 MT = 754 Q = -8.83452E+00 MeV Emin = 8.92112E+00 MeV : (n,He-3_4) + 63 MT = 755 Q = -8.94097E+00 MeV Emin = 9.02861E+00 MeV : (n,He-3_5) + 64 MT = 756 Q = -9.04652E+00 MeV Emin = 9.13519E+00 MeV : (n,He-3_6) + 65 MT = 757 Q = -9.06133E+00 MeV Emin = 9.15015E+00 MeV : (n,He-3_7) + 66 MT = 758 Q = -9.06667E+00 MeV Emin = 9.15554E+00 MeV : (n,He-3_8) + 67 MT = 759 Q = -9.07957E+00 MeV Emin = 9.16857E+00 MeV : (n,He-3_9) + 68 MT = 760 Q = -9.13597E+00 MeV Emin = 9.22552E+00 MeV : (n,He-3_10) + 69 MT = 761 Q = -9.15257E+00 MeV Emin = 9.24228E+00 MeV : (n,He-3_11) + 70 MT = 762 Q = -9.16232E+00 MeV Emin = 9.25213E+00 MeV : (n,He-3_12) + 71 MT = 763 Q = -9.16487E+00 MeV Emin = 9.25470E+00 MeV : (n,He-3_13) + 72 MT = 764 Q = -9.16817E+00 MeV Emin = 9.25804E+00 MeV : (n,He-3_14) + 73 MT = 765 Q = -9.18827E+00 MeV Emin = 9.27833E+00 MeV : (n,He-3_15) + 74 MT = 799 Q = -9.18827E+00 MeV Emin = 9.27833E+00 MeV : (n,He-3) to continuum + 75 MT = 800 Q = 3.64052E+00 MeV Emin = 2.10675E-01 MeV : (n,alpha) to ground state + 76 MT = 801 Q = 3.46837E+00 MeV Emin = 3.40296E-01 MeV : (n,a1) + 77 MT = 802 Q = 3.43985E+00 MeV Emin = 1.05000E+00 MeV : (n,a2) + 78 MT = 803 Q = 3.41705E+00 MeV Emin = 1.10000E+00 MeV : (n,a3) + 79 MT = 804 Q = 3.39656E+00 MeV Emin = 1.10000E+00 MeV : (n,a4) + 80 MT = 805 Q = 3.37696E+00 MeV Emin = 1.10000E+00 MeV : (n,a5) + 81 MT = 806 Q = 3.35299E+00 MeV Emin = 1.10000E+00 MeV : (n,a6) + 82 MT = 807 Q = 3.34559E+00 MeV Emin = 1.60000E+00 MeV : (n,a7) + 83 MT = 808 Q = 3.34082E+00 MeV Emin = 1.30000E+00 MeV : (n,a8) + 84 MT = 809 Q = 3.32103E+00 MeV Emin = 1.10000E+00 MeV : (n,a9) + 85 MT = 810 Q = 3.30532E+00 MeV Emin = 1.60000E+00 MeV : (n,a10) + 86 MT = 811 Q = 3.29955E+00 MeV Emin = 1.60000E+00 MeV : (n,a11) + 87 MT = 812 Q = 3.28500E+00 MeV Emin = 1.20000E+00 MeV : (n,a12) + 88 MT = 813 Q = 3.23989E+00 MeV Emin = 1.20000E+00 MeV : (n,a13) + 89 MT = 814 Q = 3.21616E+00 MeV Emin = 1.30000E+00 MeV : (n,a14) + 90 MT = 815 Q = 3.20012E+00 MeV Emin = 1.80000E+00 MeV : (n,a15) + 91 MT = 849 Q = 3.20012E+00 MeV Emin = 1.00000E-11 MeV : (n,alpha) to continuum + 92 MT = 4 Q = 0.00000E+00 MeV Emin = 4.00653E-02 MeV : total inelastic scattering + + Nuclide 122 / 1657 : 45105.82c -- rhodium 105 (Rh-105) + + Pointers : 992585 31517 + Primary type : Transport + Nuclide ZAI : 451050 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Rh105.ACE + Atomic weight (AW) : 104.90116 + Atomic weight ratio (AWR) : 104.00000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.27E+05 seconds (1.47 days) + Specific ingestion toxicity : 3.70E-10 Sv/Bq + Specific inhalation toxicity : 3.50E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 19 reaction channels + - 7 special reactions + - 10 transmutation reactions + - 8 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 19 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.96820E+00 MeV Emin = 9.05443E+00 MeV frac = 1.00000E+00 Product nuclide = 451040 : (n,2n) + 3 MT = 17 Q = -1.59670E+01 MeV Emin = 1.61210E+01 MeV frac = 1.00000E+00 Product nuclide = 45103.82c : (n,3n) + 4 MT = 22 Q = -3.93660E+00 MeV Emin = 1.05000E+01 MeV frac = 1.00000E+00 Product nuclide = 431010 : (n,nalpha) + 5 MT = 28 Q = -7.04480E+00 MeV Emin = 9.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 44104.82c : (n,np) + 6 MT = 51 Q = -1.29800E-01 MeV Emin = 1.25315E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.49200E-01 MeV Emin = 1.37973E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -3.92700E-01 MeV Emin = 3.96002E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -4.55600E-01 MeV Emin = 4.56699E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -4.69400E-01 MeV Emin = 4.66946E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -4.74000E-01 MeV Emin = 4.77687E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -4.99300E-01 MeV Emin = 4.89007E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 91 Q = -4.99300E-01 MeV Emin = 4.89007E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 14 MT = 102 Q = 6.58716E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 451060 : (n,gamma) + 15 MT = 103 Q = -1.13470E+00 MeV Emin = 3.40000E+00 MeV frac = 1.00000E+00 Product nuclide = 44105.82c : (n,p) + 16 MT = 104 Q = -4.82030E+00 MeV Emin = 8.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 44104.82c : (n,d) + 17 MT = 105 Q = -7.46710E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 44103.82c : (n,t) + 18 MT = 106 Q = -1.01080E+01 MeV Emin = 1.95000E+01 MeV frac = 1.00000E+00 Product nuclide = 431030 : (n,He-3) + 19 MT = 107 Q = 2.36660E+00 MeV Emin = 4.20000E+00 MeV frac = 1.00000E+00 Product nuclide = 431020 : (n,alpha) + + 8 additional transport branches: + + 1 MT = 22 Q = -3.93660E+00 MeV Emin = 1.05000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -7.04480E+00 MeV Emin = 9.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 102 Q = 6.58716E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 451061 : (n,gamma) + 4 MT = 103 Q = -1.13470E+00 MeV Emin = 3.40000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -4.82030E+00 MeV Emin = 8.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -7.46710E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 106 Q = -1.01080E+01 MeV Emin = 1.95000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 8 MT = 107 Q = 2.36660E+00 MeV Emin = 4.20000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.40000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.50000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.10000E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.95000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.20000E+00 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 6.30000E-04 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 1.25315E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.67200E-01 MeV frac = 1.00000E+00 Product nuclide = 46105.82c : beta- + + Nuclide 123 / 1657 : 46105.82c -- palladium 105 (Pd-105) + + Pointers : 1036342 29953 + Primary type : Transport + Nuclide ZAI : 461050 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Pd105.ACE + Atomic weight (AW) : 104.90519 + Atomic weight ratio (AWR) : 104.00400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 27 reaction channels + - 52 special reactions + - 9 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 27 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.09400E+00 MeV Emin = 7.16221E+00 MeV frac = 1.00000E+00 Product nuclide = 461040 : (n,2n) + 3 MT = 17 Q = -1.70770E+01 MeV Emin = 1.72412E+01 MeV frac = 1.00000E+00 Product nuclide = 461030 : (n,3n) + 4 MT = 22 Q = -2.88900E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 44101.82c : (n,nalpha) + 5 MT = 24 Q = -9.69100E+00 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 44100.82c : (n,2nalpha) + 6 MT = 28 Q = -8.75300E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 451040 : (n,np) + 7 MT = 41 Q = -1.57520E+01 MeV Emin = 1.70000E+01 MeV frac = 1.00000E+00 Product nuclide = 45103.82c : (n,2np) + 8 MT = 51 Q = -2.80510E-01 MeV Emin = 2.83030E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -3.06250E-01 MeV Emin = 3.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -3.19220E-01 MeV Emin = 3.15742E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -3.44510E-01 MeV Emin = 3.35056E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -4.42380E-01 MeV Emin = 4.46067E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -4.47000E-01 MeV Emin = 4.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -4.89140E-01 MeV Emin = 4.72571E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -5.35000E-01 MeV Emin = 5.16994E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -5.60750E-01 MeV Emin = 5.53143E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -6.44530E-01 MeV Emin = 6.25363E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -6.50700E-01 MeV Emin = 6.53842E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 62 Q = -6.73170E-01 MeV Emin = 6.68451E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 20 MT = 63 Q = -6.96660E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 21 MT = 64 Q = -7.27220E-01 MeV Emin = 7.18785E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 22 MT = 65 Q = -7.81940E-01 MeV Emin = 7.61835E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 23 MT = 66 Q = -7.87000E-01 MeV Emin = 7.92013E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 24 MT = 91 Q = -4.41257E-01 MeV Emin = 3.96661E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 25 MT = 102 Q = 9.56097E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 46106.82c : (n,gamma) + 26 MT = 103 Q = 0.00000E+00 MeV Emin = 9.50000E-01 MeV frac = 1.00000E+00 Product nuclide = 45105.82c : (n,p) + 27 MT = 107 Q = 0.00000E+00 MeV Emin = 1.80000E-01 MeV frac = 1.00000E+00 Product nuclide = 44102.82c : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = -2.88900E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 24 Q = -9.69100E+00 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,2nalpha) + 3 MT = 28 Q = -8.75300E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 4 MT = 41 Q = -1.57520E+01 MeV Emin = 1.70000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,2np) + 5 MT = 103 Q = 0.00000E+00 MeV Emin = 9.50000E-01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 107 Q = 0.00000E+00 MeV Emin = 1.80000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 52 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 9.50000E-01 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 1.80000E-01 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 6.05044E-04 MeV : damage-energy production + 4 MT = 600 Q = 2.15000E-01 MeV Emin = 9.50000E-01 MeV : (n,p) to ground state + 5 MT = 601 Q = 8.52200E-02 MeV Emin = 9.50000E-01 MeV : (n,p1) + 6 MT = 602 Q = 6.58100E-02 MeV Emin = 9.50000E-01 MeV : (n,p2) + 7 MT = 603 Q = -1.77650E-01 MeV Emin = 9.50000E-01 MeV : (n,p3) + 8 MT = 604 Q = -2.40610E-01 MeV Emin = 9.50000E-01 MeV : (n,p4) + 9 MT = 605 Q = -2.54380E-01 MeV Emin = 9.50000E-01 MeV : (n,p5) + 10 MT = 606 Q = -2.59000E-01 MeV Emin = 9.50000E-01 MeV : (n,p6) + 11 MT = 607 Q = -2.84310E-01 MeV Emin = 9.50000E-01 MeV : (n,p7) + 12 MT = 608 Q = -3.09000E-01 MeV Emin = 9.50000E-01 MeV : (n,p8) + 13 MT = 609 Q = -4.23680E-01 MeV Emin = 9.50000E-01 MeV : (n,p9) + 14 MT = 610 Q = -5.09330E-01 MeV Emin = 1.50481E+00 MeV : (n,p10) + 15 MT = 611 Q = -5.47110E-01 MeV Emin = 1.50481E+00 MeV : (n,p11) + 16 MT = 612 Q = -5.68000E-01 MeV Emin = 1.50481E+00 MeV : (n,p12) + 17 MT = 613 Q = -5.70930E-01 MeV Emin = 1.50481E+00 MeV : (n,p13) + 18 MT = 614 Q = -5.90940E-01 MeV Emin = 1.50481E+00 MeV : (n,p14) + 19 MT = 615 Q = -6.02000E-01 MeV Emin = 1.50481E+00 MeV : (n,p15) + 20 MT = 616 Q = -6.15000E-01 MeV Emin = 1.50481E+00 MeV : (n,p16) + 21 MT = 617 Q = -6.27610E-01 MeV Emin = 1.50481E+00 MeV : (n,p17) + 22 MT = 618 Q = -6.51000E-01 MeV Emin = 1.50481E+00 MeV : (n,p18) + 23 MT = 619 Q = -6.83000E-01 MeV Emin = 1.50481E+00 MeV : (n,p19) + 24 MT = 620 Q = -7.09000E-01 MeV Emin = 1.50481E+00 MeV : (n,p20) + 25 MT = 621 Q = -7.54450E-01 MeV Emin = 1.50481E+00 MeV : (n,p21) + 26 MT = 622 Q = -7.61000E-01 MeV Emin = 1.50481E+00 MeV : (n,p22) + 27 MT = 623 Q = -8.04000E-01 MeV Emin = 1.50481E+00 MeV : (n,p23) + 28 MT = 624 Q = -8.09000E-01 MeV Emin = 1.50481E+00 MeV : (n,p24) + 29 MT = 625 Q = -9.32000E-01 MeV Emin = 1.50481E+00 MeV : (n,p25) + 30 MT = 626 Q = -9.75000E-01 MeV Emin = 1.50481E+00 MeV : (n,p26) + 31 MT = 627 Q = -1.00000E+00 MeV Emin = 1.00962E+00 MeV : (n,p27) + 32 MT = 649 Q = -1.00000E+00 MeV Emin = 1.00962E+00 MeV : (n,p) to continuum + 33 MT = 800 Q = 6.33000E+00 MeV Emin = 1.80000E-01 MeV : (n,alpha) to ground state + 34 MT = 801 Q = 5.85492E+00 MeV Emin = 1.80000E-01 MeV : (n,a1) + 35 MT = 802 Q = 5.38631E+00 MeV Emin = 1.80000E-01 MeV : (n,a2) + 36 MT = 803 Q = 5.22685E+00 MeV Emin = 1.80000E-01 MeV : (n,a3) + 37 MT = 804 Q = 5.22364E+00 MeV Emin = 1.80000E-01 MeV : (n,a4) + 38 MT = 805 Q = 4.80833E+00 MeV Emin = 1.80000E-01 MeV : (n,a5) + 39 MT = 806 Q = 4.74944E+00 MeV Emin = 1.80000E-01 MeV : (n,a6) + 40 MT = 807 Q = 4.72710E+00 MeV Emin = 1.80000E-01 MeV : (n,a7) + 41 MT = 808 Q = 4.53133E+00 MeV Emin = 1.80000E-01 MeV : (n,a8) + 42 MT = 809 Q = 4.49290E+00 MeV Emin = 1.80000E-01 MeV : (n,a9) + 43 MT = 810 Q = 4.45677E+00 MeV Emin = 1.80000E-01 MeV : (n,a10) + 44 MT = 811 Q = 4.36134E+00 MeV Emin = 1.80000E-01 MeV : (n,a11) + 45 MT = 812 Q = 4.29310E+00 MeV Emin = 2.00000E-01 MeV : (n,a12) + 46 MT = 813 Q = 4.28580E+00 MeV Emin = 2.91604E-01 MeV : (n,a13) + 47 MT = 814 Q = 4.14000E+00 MeV Emin = 4.48317E-01 MeV : (n,a14) + 48 MT = 815 Q = 4.11083E+00 MeV Emin = 4.48317E-01 MeV : (n,a15) + 49 MT = 816 Q = 4.08700E+00 MeV Emin = 4.48317E-01 MeV : (n,a16) + 50 MT = 817 Q = 4.06876E+00 MeV Emin = 4.48317E-01 MeV : (n,a17) + 51 MT = 849 Q = 4.06876E+00 MeV Emin = 1.80000E-01 MeV : (n,alpha) to continuum + 52 MT = 4 Q = 0.00000E+00 MeV Emin = 2.83030E-01 MeV : total inelastic scattering + + Nuclide 124 / 1657 : 46106.82c -- palladium 106 (Pd-106) + + Pointers : 1042658 29999 + Primary type : Transport + Nuclide ZAI : 461060 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Pd106.ACE + Atomic weight (AW) : 105.90347 + Atomic weight ratio (AWR) : 104.99370 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 3.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 38 reaction channels + - 50 special reactions + - 11 transmutation reactions + - 9 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 38 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -9.56238E+00 MeV Emin = 9.65346E+00 MeV frac = 1.00000E+00 Product nuclide = 46105.82c : (n,2n) + 3 MT = 17 Q = -1.66568E+01 MeV Emin = 1.68155E+01 MeV frac = 1.00000E+00 Product nuclide = 461040 : (n,3n) + 4 MT = 22 Q = -3.23251E+00 MeV Emin = 3.26330E+00 MeV frac = 1.00000E+00 Product nuclide = 44102.82c : (n,nalpha) + 5 MT = 24 Q = -1.24529E+01 MeV Emin = 1.25715E+01 MeV frac = 1.00000E+00 Product nuclide = 44101.82c : (n,2nalpha) + 6 MT = 28 Q = -9.34703E+00 MeV Emin = 9.43606E+00 MeV frac = 1.00000E+00 Product nuclide = 45105.82c : (n,np) + 7 MT = 32 Q = -1.60908E+01 MeV Emin = 1.62441E+01 MeV frac = 1.00000E+00 Product nuclide = 451040 : (n,nd) + 8 MT = 37 Q = -2.66501E+01 MeV Emin = 2.69040E+01 MeV frac = 1.00000E+00 Product nuclide = cut: Pd-103 : (n,4n) + 9 MT = 41 Q = -1.83154E+01 MeV Emin = 1.84899E+01 MeV frac = 1.00000E+00 Product nuclide = 451040 : (n,2np) + 10 MT = 51 Q = -5.11851E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 11 MT = 52 Q = -1.12801E+00 MeV Emin = 1.10000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 12 MT = 53 Q = -1.13377E+00 MeV Emin = 1.14166E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 13 MT = 54 Q = -1.22925E+00 MeV Emin = 1.20000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 14 MT = 55 Q = -1.55765E+00 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 15 MT = 56 Q = -1.56225E+00 MeV Emin = 1.57481E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 16 MT = 57 Q = -1.70639E+00 MeV Emin = 1.70000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 17 MT = 58 Q = -1.90947E+00 MeV Emin = 1.90000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 18 MT = 59 Q = -1.93228E+00 MeV Emin = 1.93917E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 19 MT = 60 Q = -2.00149E+00 MeV Emin = 2.02055E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 20 MT = 61 Q = -2.07629E+00 MeV Emin = 2.09607E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 21 MT = 62 Q = -2.07663E+00 MeV Emin = 2.09641E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 22 MT = 63 Q = -2.08386E+00 MeV Emin = 2.10371E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 23 MT = 64 Q = -2.24249E+00 MeV Emin = 2.26385E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 24 MT = 65 Q = -2.27811E+00 MeV Emin = 2.29981E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 25 MT = 66 Q = -2.28294E+00 MeV Emin = 2.30469E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 26 MT = 67 Q = -2.30556E+00 MeV Emin = 2.32752E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 27 MT = 68 Q = -2.30881E+00 MeV Emin = 2.33080E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 28 MT = 69 Q = -2.35081E+00 MeV Emin = 2.37320E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 29 MT = 70 Q = -2.36596E+00 MeV Emin = 2.38849E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 30 MT = 71 Q = -2.39750E+00 MeV Emin = 2.42034E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 31 MT = 72 Q = -2.40140E+00 MeV Emin = 2.42427E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 32 MT = 73 Q = -2.43910E+00 MeV Emin = 2.46233E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 33 MT = 74 Q = -2.47270E+00 MeV Emin = 2.49625E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 34 MT = 91 Q = -2.47270E+00 MeV Emin = 2.49625E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 35 MT = 102 Q = 6.53644E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 46107.82c : (n,gamma) + 36 MT = 103 Q = -2.75965E+00 MeV Emin = 2.78593E+00 MeV frac = 1.00000E+00 Product nuclide = 451060 : (n,p) + 37 MT = 104 Q = -7.12244E+00 MeV Emin = 7.19028E+00 MeV frac = 1.00000E+00 Product nuclide = 45105.82c : (n,d) + 38 MT = 107 Q = 2.99987E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 44103.82c : (n,alpha) + + 9 additional transport branches: + + 1 MT = 22 Q = -3.23251E+00 MeV Emin = 3.26330E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 24 Q = -1.24529E+01 MeV Emin = 1.25715E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,2nalpha) + 3 MT = 28 Q = -9.34703E+00 MeV Emin = 9.43606E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 4 MT = 32 Q = -1.60908E+01 MeV Emin = 1.62441E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 5 MT = 41 Q = -1.83154E+01 MeV Emin = 1.84899E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,2np) + 6 MT = 102 Q = 6.53644E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 461071 : (n,gamma) + 7 MT = 103 Q = -2.75965E+00 MeV Emin = 2.78593E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 8 MT = 104 Q = -7.12244E+00 MeV Emin = 7.19028E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 9 MT = 107 Q = 2.99987E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 50 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.78593E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.19028E+00 MeV : total deuteron production + 3 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 4 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 5 MT = 600 Q = -2.75965E+00 MeV Emin = 2.78593E+00 MeV : (n,p) to ground state + 6 MT = 601 Q = -2.80159E+00 MeV Emin = 2.82827E+00 MeV : (n,p1) + 7 MT = 649 Q = -2.80159E+00 MeV Emin = 2.82827E+00 MeV : (n,p) to continuum + 8 MT = 650 Q = -7.12244E+00 MeV Emin = 7.19028E+00 MeV : (n,d) to ground state + 9 MT = 651 Q = -7.25223E+00 MeV Emin = 7.32130E+00 MeV : (n,d1) + 10 MT = 652 Q = -7.27163E+00 MeV Emin = 7.34089E+00 MeV : (n,d2) + 11 MT = 653 Q = -7.51509E+00 MeV Emin = 7.58667E+00 MeV : (n,d3) + 12 MT = 654 Q = -7.57805E+00 MeV Emin = 7.65023E+00 MeV : (n,d4) + 13 MT = 655 Q = -7.59182E+00 MeV Emin = 7.66413E+00 MeV : (n,d5) + 14 MT = 656 Q = -7.59644E+00 MeV Emin = 7.66880E+00 MeV : (n,d6) + 15 MT = 657 Q = -7.62175E+00 MeV Emin = 7.69435E+00 MeV : (n,d7) + 16 MT = 658 Q = -7.64644E+00 MeV Emin = 7.71927E+00 MeV : (n,d8) + 17 MT = 659 Q = -7.76112E+00 MeV Emin = 7.83505E+00 MeV : (n,d9) + 18 MT = 660 Q = -7.84677E+00 MeV Emin = 7.92151E+00 MeV : (n,d10) + 19 MT = 661 Q = -7.88455E+00 MeV Emin = 7.95965E+00 MeV : (n,d11) + 20 MT = 662 Q = -7.90544E+00 MeV Emin = 7.98074E+00 MeV : (n,d12) + 21 MT = 663 Q = -7.90837E+00 MeV Emin = 7.98370E+00 MeV : (n,d13) + 22 MT = 664 Q = -7.92838E+00 MeV Emin = 8.00390E+00 MeV : (n,d14) + 23 MT = 665 Q = -7.93944E+00 MeV Emin = 8.01506E+00 MeV : (n,d15) + 24 MT = 666 Q = -7.95244E+00 MeV Emin = 8.02819E+00 MeV : (n,d16) + 25 MT = 667 Q = -7.96505E+00 MeV Emin = 8.04092E+00 MeV : (n,d17) + 26 MT = 668 Q = -7.98844E+00 MeV Emin = 8.06453E+00 MeV : (n,d18) + 27 MT = 669 Q = -8.02044E+00 MeV Emin = 8.09684E+00 MeV : (n,d19) + 28 MT = 699 Q = -8.02044E+00 MeV Emin = 8.09684E+00 MeV : (n,d) to continuum + 29 MT = 800 Q = 2.99987E+00 MeV Emin = 1.00000E-11 MeV : (n,alpha) to ground state + 30 MT = 801 Q = 2.99706E+00 MeV Emin = 1.00000E-11 MeV : (n,a1) + 31 MT = 802 Q = 2.86379E+00 MeV Emin = 1.00000E-11 MeV : (n,a2) + 32 MT = 803 Q = 2.82561E+00 MeV Emin = 1.00000E-11 MeV : (n,a3) + 33 MT = 804 Q = 2.78631E+00 MeV Emin = 1.00000E-11 MeV : (n,a4) + 34 MT = 805 Q = 2.76167E+00 MeV Emin = 1.00000E-11 MeV : (n,a5) + 35 MT = 806 Q = 2.70239E+00 MeV Emin = 1.00000E-11 MeV : (n,a6) + 36 MT = 807 Q = 2.65349E+00 MeV Emin = 1.00000E-11 MeV : (n,a7) + 37 MT = 808 Q = 2.59572E+00 MeV Emin = 1.00000E-11 MeV : (n,a8) + 38 MT = 809 Q = 2.59379E+00 MeV Emin = 1.00000E-11 MeV : (n,a9) + 39 MT = 810 Q = 2.56781E+00 MeV Emin = 1.00000E-11 MeV : (n,a10) + 40 MT = 811 Q = 2.49872E+00 MeV Emin = 1.00000E-11 MeV : (n,a11) + 41 MT = 812 Q = 2.46447E+00 MeV Emin = 1.00000E-11 MeV : (n,a12) + 42 MT = 813 Q = 2.45166E+00 MeV Emin = 1.00000E-11 MeV : (n,a13) + 43 MT = 814 Q = 2.44529E+00 MeV Emin = 2.87734E-08 MeV : (n,a14) + 44 MT = 815 Q = 2.44217E+00 MeV Emin = 2.19875E-08 MeV : (n,a15) + 45 MT = 816 Q = 2.43700E+00 MeV Emin = 1.93750E-08 MeV : (n,a16) + 46 MT = 817 Q = 2.43170E+00 MeV Emin = 1.81250E-08 MeV : (n,a17) + 47 MT = 818 Q = 2.40790E+00 MeV Emin = 1.81250E-08 MeV : (n,a18) + 48 MT = 819 Q = 2.37787E+00 MeV Emin = 2.13250E-08 MeV : (n,a19) + 49 MT = 849 Q = 2.37787E+00 MeV Emin = 1.00000E-11 MeV : (n,alpha) to continuum + 50 MT = 4 Q = 0.00000E+00 MeV Emin = 5.00000E-01 MeV : total inelastic scattering + + Nuclide 125 / 1657 : 46107.82c -- palladium 107 (Pd-107) + + Pointers : 1049869 30045 + Primary type : Transport + Nuclide ZAI : 461070 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Pd107.ACE + Atomic weight (AW) : 106.90537 + Atomic weight ratio (AWR) : 105.98700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.05E+14 seconds (6.5 million years) + Specific ingestion toxicity : 3.70E-11 Sv/Bq + Specific inhalation toxicity : 5.90E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 32 reaction channels + - 6 special reactions + - 10 transmutation reactions + - 7 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 32 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.53410E+00 MeV Emin = 6.59576E+00 MeV frac = 1.00000E+00 Product nuclide = 46106.82c : (n,2n) + 3 MT = 17 Q = -1.61012E+01 MeV Emin = 1.62531E+01 MeV frac = 1.00000E+00 Product nuclide = 46105.82c : (n,3n) + 4 MT = 22 Q = -3.53149E+00 MeV Emin = 3.56482E+00 MeV frac = 1.00000E+00 Product nuclide = 44103.82c : (n,nalpha) + 5 MT = 28 Q = -9.29263E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 451060 : (n,np) + 6 MT = 32 Q = -1.35756E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 45105.82c : (n,nd) + 7 MT = 51 Q = -1.15700E-01 MeV Emin = 1.09151E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 8 MT = 52 Q = -2.14000E-01 MeV Emin = 2.08010E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 9 MT = 53 Q = -3.02800E-01 MeV Emin = 3.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 10 MT = 54 Q = -3.12200E-01 MeV Emin = 3.11588E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 11 MT = 55 Q = -3.48200E-01 MeV Emin = 3.42968E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 12 MT = 56 Q = -3.65999E-01 MeV Emin = 3.65523E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 13 MT = 57 Q = -3.81899E-01 MeV Emin = 3.85017E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 14 MT = 58 Q = -3.92399E-01 MeV Emin = 3.95186E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 15 MT = 59 Q = -4.11999E-01 MeV Emin = 4.11559E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 16 MT = 60 Q = -4.71199E-01 MeV Emin = 4.68410E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 17 MT = 61 Q = -5.67699E-01 MeV Emin = 5.54792E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 18 MT = 62 Q = -6.70099E-01 MeV Emin = 6.63905E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 19 MT = 63 Q = -6.84999E-01 MeV Emin = 6.85823E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 20 MT = 64 Q = -6.97999E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 21 MT = 65 Q = -7.58999E-01 MeV Emin = 7.51730E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 22 MT = 66 Q = -7.80999E-01 MeV Emin = 7.80041E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 23 MT = 67 Q = -8.05999E-01 MeV Emin = 8.06802E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 24 MT = 68 Q = -8.08999E-01 MeV Emin = 8.15624E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 25 MT = 69 Q = -8.88999E-01 MeV Emin = 8.77199E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 26 MT = 70 Q = -1.02300E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 27 MT = 91 Q = -1.03000E+00 MeV Emin = 1.03619E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 28 MT = 102 Q = 9.22803E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 46108.82c : (n,gamma) + 29 MT = 103 Q = -7.28534E-01 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 451070 : (n,p) + 30 MT = 104 Q = -6.98251E+00 MeV Emin = 7.46020E+00 MeV frac = 1.00000E+00 Product nuclide = 451060 : (n,d) + 31 MT = 105 Q = -7.39046E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 45105.82c : (n,t) + 32 MT = 107 Q = 5.38220E+00 MeV Emin = 9.98893E-02 MeV frac = 1.00000E+00 Product nuclide = 44104.82c : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -3.53149E+00 MeV Emin = 3.56482E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -9.29263E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.35756E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 103 Q = -7.28534E-01 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -6.98251E+00 MeV Emin = 7.46020E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -7.39046E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 107 Q = 5.38220E+00 MeV Emin = 9.98893E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.46020E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 8.00000E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 9.98893E-02 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 6.42872E-04 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 1.09151E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.41000E-02 MeV frac = 1.00000E+00 Product nuclide = 471070 : beta- + + Nuclide 126 / 1657 : 46108.82c -- palladium 108 (Pd-108) + + Pointers : 1053742 30091 + Primary type : Transport + Nuclide ZAI : 461080 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Pd108.ACE + Atomic weight (AW) : 107.90385 + Atomic weight ratio (AWR) : 106.97690 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 3.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 38 reaction channels + - 35 special reactions + - 11 transmutation reactions + - 9 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 38 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -9.22038E+00 MeV Emin = 9.30657E+00 MeV frac = 1.00000E+00 Product nuclide = 46107.82c : (n,2n) + 3 MT = 17 Q = -1.57588E+01 MeV Emin = 1.59061E+01 MeV frac = 1.00000E+00 Product nuclide = 46106.82c : (n,3n) + 4 MT = 22 Q = -3.85491E+00 MeV Emin = 3.89095E+00 MeV frac = 1.00000E+00 Product nuclide = 44104.82c : (n,nalpha) + 5 MT = 24 Q = -1.27589E+01 MeV Emin = 1.28782E+01 MeV frac = 1.00000E+00 Product nuclide = 44103.82c : (n,2nalpha) + 6 MT = 28 Q = -9.95003E+00 MeV Emin = 1.00430E+01 MeV frac = 1.00000E+00 Product nuclide = 451070 : (n,np) + 7 MT = 32 Q = -1.62938E+01 MeV Emin = 1.64461E+01 MeV frac = 1.00000E+00 Product nuclide = 451060 : (n,nd) + 8 MT = 37 Q = -2.53211E+01 MeV Emin = 2.55578E+01 MeV frac = 1.00000E+00 Product nuclide = cut: Pd-105 : (n,4n) + 9 MT = 41 Q = -1.85184E+01 MeV Emin = 1.86915E+01 MeV frac = 1.00000E+00 Product nuclide = 451060 : (n,2np) + 10 MT = 51 Q = -4.33938E-01 MeV Emin = 4.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 11 MT = 52 Q = -9.31200E-01 MeV Emin = 9.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 12 MT = 53 Q = -1.04822E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 13 MT = 54 Q = -1.05278E+00 MeV Emin = 1.06032E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 14 MT = 55 Q = -1.31421E+00 MeV Emin = 1.30000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 15 MT = 56 Q = -1.33520E+00 MeV Emin = 1.33709E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 16 MT = 57 Q = -1.44118E+00 MeV Emin = 1.40000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 17 MT = 58 Q = -1.53996E+00 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 18 MT = 59 Q = -1.62510E+00 MeV Emin = 1.60000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 19 MT = 60 Q = -1.77116E+00 MeV Emin = 1.70000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 20 MT = 61 Q = -1.95600E+00 MeV Emin = 1.90000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 21 MT = 62 Q = -1.98985E+00 MeV Emin = 2.00845E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 22 MT = 63 Q = -2.01500E+00 MeV Emin = 2.03384E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 23 MT = 64 Q = -2.04665E+00 MeV Emin = 2.06578E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 24 MT = 65 Q = -2.09867E+00 MeV Emin = 2.11829E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 25 MT = 66 Q = -2.14100E+00 MeV Emin = 2.16101E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 26 MT = 67 Q = -2.21800E+00 MeV Emin = 2.23873E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 27 MT = 68 Q = -2.28119E+00 MeV Emin = 2.30252E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 28 MT = 69 Q = -2.28247E+00 MeV Emin = 2.30381E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 29 MT = 70 Q = -2.31800E+00 MeV Emin = 2.33967E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 30 MT = 71 Q = -2.36200E+00 MeV Emin = 2.38408E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 31 MT = 72 Q = -2.39150E+00 MeV Emin = 2.41386E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 32 MT = 73 Q = -2.40410E+00 MeV Emin = 2.42657E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 33 MT = 74 Q = -2.41800E+00 MeV Emin = 2.44060E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 34 MT = 91 Q = -2.41800E+00 MeV Emin = 2.44060E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 35 MT = 102 Q = 6.15361E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 461090 : (n,gamma) + 36 MT = 103 Q = -3.66065E+00 MeV Emin = 3.69487E+00 MeV frac = 1.00000E+00 Product nuclide = 451080 : (n,p) + 37 MT = 104 Q = -7.72544E+00 MeV Emin = 7.79766E+00 MeV frac = 1.00000E+00 Product nuclide = 451070 : (n,d) + 38 MT = 107 Q = 2.05547E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 44105.82c : (n,alpha) + + 9 additional transport branches: + + 1 MT = 22 Q = -3.85491E+00 MeV Emin = 3.89095E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 24 Q = -1.27589E+01 MeV Emin = 1.28782E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,2nalpha) + 3 MT = 28 Q = -9.95003E+00 MeV Emin = 1.00430E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 4 MT = 32 Q = -1.62938E+01 MeV Emin = 1.64461E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 5 MT = 41 Q = -1.85184E+01 MeV Emin = 1.86915E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,2np) + 6 MT = 102 Q = 6.15361E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 461091 : (n,gamma) + 7 MT = 103 Q = -3.66065E+00 MeV Emin = 3.69487E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 8 MT = 104 Q = -7.72544E+00 MeV Emin = 7.79766E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 9 MT = 107 Q = 2.05547E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 35 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.69487E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.79766E+00 MeV : total deuteron production + 3 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 4 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 5 MT = 600 Q = -3.66065E+00 MeV Emin = 3.69487E+00 MeV : (n,p) to ground state + 6 MT = 601 Q = -3.70165E+00 MeV Emin = 3.73625E+00 MeV : (n,p1) + 7 MT = 649 Q = -3.70165E+00 MeV Emin = 3.73625E+00 MeV : (n,p) to continuum + 8 MT = 650 Q = -7.72544E+00 MeV Emin = 7.79766E+00 MeV : (n,d) to ground state + 9 MT = 651 Q = -7.91955E+00 MeV Emin = 7.99359E+00 MeV : (n,d1) + 10 MT = 652 Q = -8.00544E+00 MeV Emin = 8.08028E+00 MeV : (n,d2) + 11 MT = 653 Q = -8.13134E+00 MeV Emin = 8.20735E+00 MeV : (n,d3) + 12 MT = 654 Q = -8.18804E+00 MeV Emin = 8.26459E+00 MeV : (n,d4) + 13 MT = 699 Q = -8.18804E+00 MeV Emin = 8.26458E+00 MeV : (n,d) to continuum + 14 MT = 800 Q = 2.05547E+00 MeV Emin = 5.15625E-08 MeV : (n,alpha) to ground state + 15 MT = 801 Q = 2.03486E+00 MeV Emin = 4.03516E-08 MeV : (n,a1) + 16 MT = 802 Q = 1.94753E+00 MeV Emin = 4.13164E-08 MeV : (n,a2) + 17 MT = 803 Q = 1.89595E+00 MeV Emin = 8.75000E-08 MeV : (n,a3) + 18 MT = 804 Q = 1.89166E+00 MeV Emin = 5.62500E-08 MeV : (n,a4) + 19 MT = 805 Q = 1.84687E+00 MeV Emin = 7.50000E-08 MeV : (n,a5) + 20 MT = 806 Q = 1.82599E+00 MeV Emin = 5.00000E-08 MeV : (n,a6) + 21 MT = 807 Q = 1.81106E+00 MeV Emin = 4.61406E-08 MeV : (n,a7) + 22 MT = 808 Q = 1.80910E+00 MeV Emin = 5.00000E-08 MeV : (n,a8) + 23 MT = 809 Q = 1.78275E+00 MeV Emin = 5.93750E-08 MeV : (n,a9) + 24 MT = 810 Q = 1.75379E+00 MeV Emin = 5.15625E-08 MeV : (n,a10) + 25 MT = 811 Q = 1.73388E+00 MeV Emin = 5.78125E-08 MeV : (n,a11) + 26 MT = 812 Q = 1.61352E+00 MeV Emin = 6.56250E-08 MeV : (n,a12) + 27 MT = 813 Q = 1.58920E+00 MeV Emin = 6.87500E-08 MeV : (n,a13) + 28 MT = 814 Q = 1.56458E+00 MeV Emin = 6.56250E-08 MeV : (n,a14) + 29 MT = 815 Q = 1.47747E+00 MeV Emin = 6.56250E-08 MeV : (n,a15) + 30 MT = 816 Q = 1.47736E+00 MeV Emin = 6.25000E-08 MeV : (n,a16) + 31 MT = 817 Q = 1.47335E+00 MeV Emin = 7.81250E-08 MeV : (n,a17) + 32 MT = 818 Q = 1.42964E+00 MeV Emin = 6.87500E-08 MeV : (n,a18) + 33 MT = 819 Q = 1.42420E+00 MeV Emin = 1.34375E-07 MeV : (n,a19) + 34 MT = 849 Q = 1.42420E+00 MeV Emin = 1.00000E-11 MeV : (n,alpha) to continuum + 35 MT = 4 Q = 0.00000E+00 MeV Emin = 4.00000E-01 MeV : total inelastic scattering + + Nuclide 127 / 1657 : 46110.82c -- palladium 110 (Pd-110) + + Pointers : 1062955 30137 + Primary type : Transport + Nuclide ZAI : 461100 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Pd110.ACE + Atomic weight (AW) : 109.90514 + Atomic weight ratio (AWR) : 108.96100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.89E+25 seconds (6E+17 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 20 reaction channels + - 7 special reactions + - 8 transmutation reactions + - 7 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 20 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.72590E+00 MeV Emin = 8.80600E+00 MeV frac = 1.00000E+00 Product nuclide = 461090 : (n,2n) + 3 MT = 51 Q = -3.73800E-01 MeV Emin = 3.73800E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 4 MT = 52 Q = -8.13800E-01 MeV Emin = 8.20469E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 5 MT = 53 Q = -9.20500E-01 MeV Emin = 9.20500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 6 MT = 54 Q = -9.46300E-01 MeV Emin = 9.46711E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 7 MT = 55 Q = -1.17100E+00 MeV Emin = 1.17375E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 8 MT = 56 Q = -1.21200E+00 MeV Emin = 1.21881E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 9 MT = 57 Q = -1.21500E+00 MeV Emin = 1.22464E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 10 MT = 58 Q = -1.30900E+00 MeV Emin = 1.30915E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 11 MT = 59 Q = -1.39800E+00 MeV Emin = 1.40522E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 12 MT = 60 Q = -1.47000E+00 MeV Emin = 1.47441E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 13 MT = 91 Q = -1.55960E+00 MeV Emin = 1.53695E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 14 MT = 102 Q = 5.76600E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 461110 : (n,gamma) + 15 MT = 103 Q = -4.57880E+00 MeV Emin = 4.62082E+00 MeV frac = 1.00000E+00 Product nuclide = 451100 : (n,p) + 16 MT = 104 Q = -8.21110E+00 MeV Emin = 8.28646E+00 MeV frac = 1.00000E+00 Product nuclide = 451090 : (n,d) + 17 MT = 105 Q = -1.00970E+01 MeV Emin = 1.01897E+01 MeV frac = 1.00000E+00 Product nuclide = 451080 : (n,t) + 18 MT = 106 Q = -1.12680E+01 MeV Emin = 1.13714E+01 MeV frac = 1.00000E+00 Product nuclide = 441080 : (n,He-3) + 19 MT = 107 Q = 1.02100E+00 MeV Emin = 4.50000E-01 MeV frac = 1.00000E+00 Product nuclide = 441070 : (n,alpha) + 20 MT = 111 Q = -1.40270E+01 MeV Emin = 1.41557E+01 MeV frac = 1.00000E+00 Product nuclide = 441090 : (n,2p) + + 7 additional transport branches: + + 1 MT = 102 Q = 5.76600E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 461111 : (n,gamma) + 2 MT = 103 Q = -4.57880E+00 MeV Emin = 4.62082E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 104 Q = -8.21110E+00 MeV Emin = 8.28646E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 4 MT = 105 Q = -1.00970E+01 MeV Emin = 1.01897E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 5 MT = 106 Q = -1.12680E+01 MeV Emin = 1.13714E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 6 MT = 107 Q = 1.02100E+00 MeV Emin = 4.50000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 7 MT = 111 Q = -1.40270E+01 MeV Emin = 1.41557E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.62082E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.28646E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.01897E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.13714E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.50000E-01 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 3.73800E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 11 Q = 2.01720E+00 MeV frac = 1.00000E+00 Product nuclide = 48110.82c : beta- + beta- + + Nuclide 128 / 1657 : 47109.82c -- silver 109 (Ag-109) + + Pointers : 1083317 18683 + Primary type : Transport + Nuclide ZAI : 471090 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ag109.ACE + Atomic weight (AW) : 108.90455 + Atomic weight ratio (AWR) : 107.96900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 24 reaction channels + - 7 special reactions + - 8 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 24 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -9.10370E+00 MeV Emin = 9.18802E+00 MeV frac = 1.00000E+00 Product nuclide = 471080 : (n,2n) + 3 MT = 51 Q = -8.80000E-02 MeV Emin = 8.80000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 4 MT = 52 Q = -1.32800E-01 MeV Emin = 1.32800E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 5 MT = 53 Q = -3.11400E-01 MeV Emin = 3.10713E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 6 MT = 54 Q = -4.15300E-01 MeV Emin = 4.16753E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 7 MT = 55 Q = -6.97000E-01 MeV Emin = 7.01900E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 8 MT = 56 Q = -7.01900E-01 MeV Emin = 7.07000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 9 MT = 57 Q = -7.07000E-01 MeV Emin = 7.10974E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 10 MT = 58 Q = -7.24400E-01 MeV Emin = 7.24400E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 11 MT = 59 Q = -7.35300E-01 MeV Emin = 7.39360E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 12 MT = 60 Q = -8.11000E-01 MeV Emin = 8.11000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 13 MT = 61 Q = -8.39800E-01 MeV Emin = 8.43945E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 14 MT = 62 Q = -8.62700E-01 MeV Emin = 8.69500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 15 MT = 63 Q = -8.69500E-01 MeV Emin = 8.74122E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 16 MT = 64 Q = -9.11000E-01 MeV Emin = 9.16355E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 17 MT = 91 Q = -9.20000E-01 MeV Emin = 9.24466E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 18 MT = 102 Q = 6.80921E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 471100 : (n,gamma) + 19 MT = 103 Q = -3.33500E-01 MeV Emin = 3.35713E-01 MeV frac = 1.00000E+00 Product nuclide = 461090 : (n,p) + 20 MT = 104 Q = -4.26170E+00 MeV Emin = 4.30117E+00 MeV frac = 1.00000E+00 Product nuclide = 46108.82c : (n,d) + 21 MT = 105 Q = -7.22650E+00 MeV Emin = 7.29343E+00 MeV frac = 1.00000E+00 Product nuclide = 46107.82c : (n,t) + 22 MT = 106 Q = -8.71890E+00 MeV Emin = 8.79965E+00 MeV frac = 1.00000E+00 Product nuclide = 451070 : (n,He-3) + 23 MT = 107 Q = 3.29700E+00 MeV Emin = 7.20000E+00 MeV frac = 1.00000E+00 Product nuclide = 451060 : (n,alpha) + 24 MT = 111 Q = -1.02050E+01 MeV Emin = 1.02995E+01 MeV frac = 1.00000E+00 Product nuclide = 451080 : (n,2p) + + 7 additional transport branches: + + 1 MT = 102 Q = 6.80921E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 47510.82c : (n,gamma) + 2 MT = 103 Q = -3.33500E-01 MeV Emin = 3.35713E-01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 104 Q = -4.26170E+00 MeV Emin = 4.30117E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 4 MT = 105 Q = -7.22650E+00 MeV Emin = 7.29343E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 5 MT = 106 Q = -8.71890E+00 MeV Emin = 8.79965E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 6 MT = 107 Q = 3.29700E+00 MeV Emin = 7.20000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 7 MT = 111 Q = -1.02050E+01 MeV Emin = 1.02995E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.35713E-01 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 4.30117E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 7.29343E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 8.79965E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 7.20000E+00 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.50000E-03 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 8.80000E-02 MeV : total inelastic scattering + + Nuclide 129 / 1657 : 47510.82c -- silver 110m (Ag-110m) + + Pointers : 1087680 18729 + Primary type : Transport + Nuclide ZAI : 471101 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ag110M.ACE + Atomic weight (AW) : 109.90615 + Atomic weight ratio (AWR) : 108.96200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.16E+07 seconds (250 days) + Specific ingestion toxicity : 2.80E-09 Sv/Bq + Specific inhalation toxicity : 1.20E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 43 reaction channels + - 7 special reactions + - 12 transmutation reactions + - 9 transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 43 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.81009E+00 MeV Emin = 6.87260E+00 MeV frac = 1.00000E+00 Product nuclide = 47109.82c : (n,2n) + 3 MT = 17 Q = -1.60062E+01 MeV Emin = 1.61531E+01 MeV frac = 1.00000E+00 Product nuclide = 471080 : (n,3n) + 4 MT = 22 Q = -3.50589E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 451060 : (n,nalpha) + 5 MT = 28 Q = -7.14363E+00 MeV Emin = 7.20920E+00 MeV frac = 1.00000E+00 Product nuclide = 461090 : (n,np) + 6 MT = 32 Q = -1.09926E+01 MeV Emin = 1.10935E+01 MeV frac = 1.00000E+00 Product nuclide = 46108.82c : (n,nd) + 7 MT = 33 Q = -1.40356E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 46107.82c : (n,nt) + 8 MT = 51 Q = 1.17600E-01 MeV Emin = 4.75000E-03 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = 1.06600E-01 MeV Emin = 2.65625E-06 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -1.10000E-03 MeV Emin = 1.10156E-03 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -7.35999E-02 MeV Emin = 7.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -7.39999E-02 MeV Emin = 7.44595E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -8.10999E-02 MeV Emin = 8.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -1.19300E-01 MeV Emin = 1.14729E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -1.19400E-01 MeV Emin = 1.20395E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -1.49600E-01 MeV Emin = 1.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -1.51400E-01 MeV Emin = 1.51881E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -1.53900E-01 MeV Emin = 1.53420E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 62 Q = -1.84100E-01 MeV Emin = 1.78409E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 20 MT = 63 Q = -1.86900E-01 MeV Emin = 1.85790E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 21 MT = 64 Q = -2.19400E-01 MeV Emin = 2.10707E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 22 MT = 65 Q = -2.21300E-01 MeV Emin = 2.22373E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 23 MT = 66 Q = -2.43000E-01 MeV Emin = 2.34965E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 24 MT = 67 Q = -2.60400E-01 MeV Emin = 2.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 25 MT = 68 Q = -2.63600E-01 MeV Emin = 2.64404E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 26 MT = 69 Q = -2.94400E-01 MeV Emin = 2.81561E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 27 MT = 70 Q = -3.07100E-01 MeV Emin = 3.04959E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 28 MT = 71 Q = -3.14800E-01 MeV Emin = 3.11861E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 29 MT = 72 Q = -3.38900E-01 MeV Emin = 3.30610E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 30 MT = 73 Q = -3.49300E-01 MeV Emin = 3.47258E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 31 MT = 74 Q = -3.51300E-01 MeV Emin = 3.52506E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 32 MT = 75 Q = -3.53600E-01 MeV Emin = 3.55483E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 33 MT = 76 Q = -3.66399E-01 MeV Emin = 3.64111E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 34 MT = 77 Q = -3.68199E-01 MeV Emin = 3.70917E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 27. excited state + 35 MT = 78 Q = -3.79299E-01 MeV Emin = 3.74379E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 28. excited state + 36 MT = 79 Q = -4.08099E-01 MeV Emin = 3.98221E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 29. excited state + 37 MT = 91 Q = -4.09899E-01 MeV Emin = 4.12974E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 38 MT = 102 Q = 8.84139E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 47111.82c : (n,gamma) + 39 MT = 103 Q = 1.66146E+00 MeV Emin = 9.99438E-02 MeV frac = 1.00000E+00 Product nuclide = 46110.82c : (n,p) + 40 MT = 104 Q = -4.83351E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 461090 : (n,d) + 41 MT = 105 Q = -4.80746E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 46108.82c : (n,t) + 42 MT = 106 Q = -9.29182E+00 MeV Emin = 1.10935E+01 MeV frac = 1.00000E+00 Product nuclide = 451080 : (n,He-3) + 43 MT = 107 Q = 5.05820E+00 MeV Emin = 9.99438E-02 MeV frac = 1.00000E+00 Product nuclide = 451070 : (n,alpha) + + 9 additional transport branches: + + 1 MT = 22 Q = -3.50589E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -7.14363E+00 MeV Emin = 7.20920E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.09926E+01 MeV Emin = 1.10935E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.40356E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 103 Q = 1.66146E+00 MeV Emin = 9.99438E-02 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 104 Q = -4.83351E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 7 MT = 105 Q = -4.80746E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 8 MT = 106 Q = -9.29182E+00 MeV Emin = 1.10935E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 9 MT = 107 Q = 5.05820E+00 MeV Emin = 9.99438E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 9.99438E-02 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 6.00000E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.10935E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 9.99438E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 4.75000E-03 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 3 Q = 1.17600E-01 MeV frac = 1.36000E-02 Product nuclide = 471100 : IT + 2 RTYP = 1 Q = 3.00979E+00 MeV frac = 9.86400E-01 Product nuclide = 48110.82c : beta- + + Nuclide 130 / 1657 : 47111.82c -- silver 111 (Ag-111) + + Pointers : 1094237 18775 + Primary type : Transport + Nuclide ZAI : 471110 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ag111.ACE + Atomic weight (AW) : 110.90574 + Atomic weight ratio (AWR) : 109.95300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 6.44E+05 seconds (7.45 days) + Specific ingestion toxicity : 1.30E-09 Sv/Bq + Specific inhalation toxicity : 1.70E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 19 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 6 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 19 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -5.99000E-02 MeV Emin = 5.89987E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -1.30000E-01 MeV Emin = 1.23385E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -2.90000E-01 MeV Emin = 2.69480E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -3.77000E-01 MeV Emin = 3.79670E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -3.91000E-01 MeV Emin = 3.89340E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -4.05000E-01 MeV Emin = 4.03845E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 57 Q = -5.46000E-01 MeV Emin = 5.42195E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 9 MT = 58 Q = -5.69000E-01 MeV Emin = 5.70325E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 10 MT = 59 Q = -6.07000E-01 MeV Emin = 5.98455E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 11 MT = 60 Q = -6.42000E-01 MeV Emin = 6.32260E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 12 MT = 91 Q = -9.90990E-01 MeV Emin = 9.62500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 13 MT = 102 Q = 6.36000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 471120 : (n,gamma) + 14 MT = 103 Q = -1.41290E+00 MeV Emin = 1.42552E+00 MeV frac = 1.00000E+00 Product nuclide = 461110 : (n,p) + 15 MT = 104 Q = -4.95350E+00 MeV Emin = 4.99855E+00 MeV frac = 1.00000E+00 Product nuclide = 46110.82c : (n,d) + 16 MT = 105 Q = -7.49540E+00 MeV Emin = 7.56357E+00 MeV frac = 1.00000E+00 Product nuclide = 461090 : (n,t) + 17 MT = 106 Q = -9.97250E+00 MeV Emin = 1.00632E+01 MeV frac = 1.00000E+00 Product nuclide = 451090 : (n,He-3) + 18 MT = 107 Q = 2.43960E+00 MeV Emin = 4.76796E-01 MeV frac = 1.00000E+00 Product nuclide = 451080 : (n,alpha) + 19 MT = 111 Q = -1.17980E+01 MeV Emin = 1.19053E+01 MeV frac = 1.00000E+00 Product nuclide = 451100 : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = -1.41290E+00 MeV Emin = 1.42552E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -4.95350E+00 MeV Emin = 4.99855E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -7.49540E+00 MeV Emin = 7.56357E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -9.97250E+00 MeV Emin = 1.00632E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 2.43960E+00 MeV Emin = 4.76796E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -1.17980E+01 MeV Emin = 1.19053E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.42552E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 4.99855E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 7.56357E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.00632E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.76796E-01 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 5.89987E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.03680E+00 MeV frac = 1.00000E+00 Product nuclide = 48111.82c : beta- + + Nuclide 131 / 1657 : 48110.82c -- cadmium 110 (Cd-110) + + Pointers : 1121751 20753 + Primary type : Transport + Nuclide ZAI : 481100 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Cd110.ACE + Atomic weight (AW) : 109.90313 + Atomic weight ratio (AWR) : 108.95900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 28 reaction channels + - 7 special reactions + - 12 transmutation reactions + - 10 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 28 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -9.88030E+00 MeV Emin = 9.97100E+00 MeV frac = 1.00000E+00 Product nuclide = 481090 : (n,2n) + 3 MT = 17 Q = -1.72430E+01 MeV Emin = 1.74013E+01 MeV frac = 1.00000E+00 Product nuclide = 481080 : (n,3n) + 4 MT = 22 Q = -2.86100E+00 MeV Emin = 2.88726E+00 MeV frac = 1.00000E+00 Product nuclide = 46106.82c : (n,nalpha) + 5 MT = 28 Q = -8.91690E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 47109.82c : (n,np) + 6 MT = 32 Q = -1.58860E+01 MeV Emin = 1.60318E+01 MeV frac = 1.00000E+00 Product nuclide = 471080 : (n,nd) + 7 MT = 33 Q = -1.68960E+01 MeV Emin = 1.70511E+01 MeV frac = 1.00000E+00 Product nuclide = 471070 : (n,nt) + 8 MT = 51 Q = -6.58020E-01 MeV Emin = 6.60000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -1.47500E+00 MeV Emin = 1.40000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -1.47600E+00 MeV Emin = 1.40000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -1.54600E+00 MeV Emin = 1.53000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -1.73400E+00 MeV Emin = 1.67500E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -1.78300E+00 MeV Emin = 1.77500E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -1.81300E+00 MeV Emin = 1.81500E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -2.07900E+00 MeV Emin = 2.10000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -2.08000E+00 MeV Emin = 2.10000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -2.16000E+00 MeV Emin = 2.18000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -2.22000E+00 MeV Emin = 2.24038E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 62 Q = -2.28700E+00 MeV Emin = 2.31000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 20 MT = 63 Q = -2.32900E+00 MeV Emin = 2.35038E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 21 MT = 64 Q = -2.35600E+00 MeV Emin = 2.38000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 22 MT = 91 Q = -2.35860E+00 MeV Emin = 2.38025E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 23 MT = 102 Q = 6.97585E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 48111.82c : (n,gamma) + 24 MT = 103 Q = -2.11080E+00 MeV Emin = 2.13017E+00 MeV frac = 1.00000E+00 Product nuclide = 471100 : (n,p) + 25 MT = 104 Q = -6.69220E+00 MeV Emin = 6.75362E+00 MeV frac = 1.00000E+00 Product nuclide = 47109.82c : (n,d) + 26 MT = 105 Q = -9.88000E+00 MeV Emin = 9.97100E+00 MeV frac = 1.00000E+00 Product nuclide = 471080 : (n,t) + 27 MT = 106 Q = -7.68710E+00 MeV Emin = 7.75765E+00 MeV frac = 1.00000E+00 Product nuclide = 46108.82c : (n,He-3) + 28 MT = 107 Q = 3.70100E+00 MeV Emin = 1.68750E-04 MeV frac = 1.00000E+00 Product nuclide = 46107.82c : (n,alpha) + + 10 additional transport branches: + + 1 MT = 22 Q = -2.86100E+00 MeV Emin = 2.88726E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -8.91690E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.58860E+01 MeV Emin = 1.60318E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.68960E+01 MeV Emin = 1.70511E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 102 Q = 6.97585E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 481111 : (n,gamma) + 6 MT = 103 Q = -2.11080E+00 MeV Emin = 2.13017E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 7 MT = 104 Q = -6.69220E+00 MeV Emin = 6.75362E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 8 MT = 105 Q = -9.88000E+00 MeV Emin = 9.97100E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 9 MT = 106 Q = -7.68710E+00 MeV Emin = 7.75765E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 10 MT = 107 Q = 3.70100E+00 MeV Emin = 1.68750E-04 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.13017E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.75362E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.97100E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 7.75765E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.68750E-04 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.65625E-04 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 6.60000E-01 MeV : total inelastic scattering + + Nuclide 132 / 1657 : 48111.82c -- cadmium 111 (Cd-111) + + Pointers : 1125166 20799 + Primary type : Transport + Nuclide ZAI : 481110 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Cd111.ACE + Atomic weight (AW) : 110.90473 + Atomic weight ratio (AWR) : 109.95200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 25 reaction channels + - 7 special reactions + - 12 transmutation reactions + - 9 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 25 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.97560E+00 MeV Emin = 7.03904E+00 MeV frac = 1.00000E+00 Product nuclide = 48110.82c : (n,2n) + 3 MT = 17 Q = -1.68580E+01 MeV Emin = 1.70113E+01 MeV frac = 1.00000E+00 Product nuclide = 481090 : (n,3n) + 4 MT = 22 Q = -3.30820E+00 MeV Emin = 3.33829E+00 MeV frac = 1.00000E+00 Product nuclide = 46107.82c : (n,nalpha) + 5 MT = 28 Q = -9.08710E+00 MeV Emin = 9.16975E+00 MeV frac = 1.00000E+00 Product nuclide = 471100 : (n,np) + 6 MT = 32 Q = -1.36670E+01 MeV Emin = 1.37913E+01 MeV frac = 1.00000E+00 Product nuclide = 47109.82c : (n,nd) + 7 MT = 33 Q = -1.66000E+01 MeV Emin = 1.67510E+01 MeV frac = 1.00000E+00 Product nuclide = 471080 : (n,nt) + 8 MT = 51 Q = -2.44790E-01 MeV Emin = 2.40000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -3.45000E-01 MeV Emin = 3.48000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -3.96000E-01 MeV Emin = 3.87035E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -4.17000E-01 MeV Emin = 4.12500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -6.20400E-01 MeV Emin = 6.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -6.80000E-01 MeV Emin = 6.86000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -7.00000E-01 MeV Emin = 7.06000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -7.53000E-01 MeV Emin = 7.53183E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -7.55000E-01 MeV Emin = 7.53183E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -8.54000E-01 MeV Emin = 8.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -8.65000E-01 MeV Emin = 8.72656E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 91 Q = -8.54000E-01 MeV Emin = 8.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 20 MT = 102 Q = 9.39432E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 48112.82c : (n,gamma) + 21 MT = 103 Q = -2.44800E-01 MeV Emin = 2.40000E-01 MeV frac = 1.00000E+00 Product nuclide = 47111.82c : (n,p) + 22 MT = 104 Q = -6.86320E+00 MeV Emin = 6.92562E+00 MeV frac = 1.00000E+00 Product nuclide = 471100 : (n,d) + 23 MT = 105 Q = -7.41120E+00 MeV Emin = 7.47861E+00 MeV frac = 1.00000E+00 Product nuclide = 47109.82c : (n,t) + 24 MT = 106 Q = -8.50930E+00 MeV Emin = 8.58669E+00 MeV frac = 1.00000E+00 Product nuclide = 461090 : (n,He-3) + 25 MT = 107 Q = 5.96930E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 46108.82c : (n,alpha) + + 9 additional transport branches: + + 1 MT = 22 Q = -3.30820E+00 MeV Emin = 3.33829E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -9.08710E+00 MeV Emin = 9.16975E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.36670E+01 MeV Emin = 1.37913E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.66000E+01 MeV Emin = 1.67510E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 103 Q = -2.44800E-01 MeV Emin = 2.40000E-01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 104 Q = -6.86320E+00 MeV Emin = 6.92562E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 7 MT = 105 Q = -7.41120E+00 MeV Emin = 7.47861E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 8 MT = 106 Q = -8.50930E+00 MeV Emin = 8.58669E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 9 MT = 107 Q = 5.96930E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.40000E-01 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.92562E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 7.47861E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 8.58669E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 2.40000E-01 MeV : total inelastic scattering + + Nuclide 133 / 1657 : 48112.82c -- cadmium 112 (Cd-112) + + Pointers : 1128711 20845 + Primary type : Transport + Nuclide ZAI : 481120 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Cd112.ACE + Atomic weight (AW) : 111.90331 + Atomic weight ratio (AWR) : 110.94200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 22 reaction channels + - 7 special reactions + - 12 transmutation reactions + - 10 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 22 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -9.39710E+00 MeV Emin = 9.48181E+00 MeV frac = 1.00000E+00 Product nuclide = 48111.82c : (n,2n) + 3 MT = 17 Q = -1.63740E+01 MeV Emin = 1.65216E+01 MeV frac = 1.00000E+00 Product nuclide = 48110.82c : (n,3n) + 4 MT = 22 Q = -3.47990E+00 MeV Emin = 3.51127E+00 MeV frac = 1.00000E+00 Product nuclide = 46108.82c : (n,nalpha) + 5 MT = 28 Q = -9.64190E+00 MeV Emin = 9.72881E+00 MeV frac = 1.00000E+00 Product nuclide = 47111.82c : (n,np) + 6 MT = 32 Q = -1.62650E+01 MeV Emin = 1.64116E+01 MeV frac = 1.00000E+00 Product nuclide = 471100 : (n,nd) + 7 MT = 33 Q = -1.68100E+01 MeV Emin = 1.69615E+01 MeV frac = 1.00000E+00 Product nuclide = 47109.82c : (n,nt) + 8 MT = 51 Q = -6.18000E-01 MeV Emin = 6.20000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -1.22900E+00 MeV Emin = 1.20000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -1.30800E+00 MeV Emin = 1.28004E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -1.41700E+00 MeV Emin = 1.40000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -1.43700E+00 MeV Emin = 1.44000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -1.46700E+00 MeV Emin = 1.46500E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -1.87300E+00 MeV Emin = 1.80000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -2.00200E+00 MeV Emin = 2.02005E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 91 Q = -1.98230E+00 MeV Emin = 2.00017E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 17 MT = 102 Q = 6.53980E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 48113.82c : (n,gamma) + 18 MT = 103 Q = -3.17600E+00 MeV Emin = 3.20463E+00 MeV frac = 1.00000E+00 Product nuclide = 471120 : (n,p) + 19 MT = 104 Q = -7.41680E+00 MeV Emin = 7.48366E+00 MeV frac = 1.00000E+00 Product nuclide = 47111.82c : (n,d) + 20 MT = 105 Q = -1.00030E+01 MeV Emin = 1.00932E+01 MeV frac = 1.00000E+00 Product nuclide = 471100 : (n,t) + 21 MT = 106 Q = -9.10470E+00 MeV Emin = 9.18677E+00 MeV frac = 1.00000E+00 Product nuclide = 46110.82c : (n,He-3) + 22 MT = 107 Q = 2.69800E+00 MeV Emin = 1.81811E-03 MeV frac = 1.00000E+00 Product nuclide = 461090 : (n,alpha) + + 10 additional transport branches: + + 1 MT = 22 Q = -3.47990E+00 MeV Emin = 3.51127E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -9.64190E+00 MeV Emin = 9.72881E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.62650E+01 MeV Emin = 1.64116E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.68100E+01 MeV Emin = 1.69615E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 102 Q = 6.53980E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 481131 : (n,gamma) + 6 MT = 103 Q = -3.17600E+00 MeV Emin = 3.20463E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 7 MT = 104 Q = -7.41680E+00 MeV Emin = 7.48366E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 8 MT = 105 Q = -1.00030E+01 MeV Emin = 1.00932E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 9 MT = 106 Q = -9.10470E+00 MeV Emin = 9.18677E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 10 MT = 107 Q = 2.69800E+00 MeV Emin = 1.81811E-03 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.20463E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.48366E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.00932E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 9.18677E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.81811E-03 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 6.20000E-01 MeV : total inelastic scattering + + Nuclide 134 / 1657 : 48113.82c -- cadmium 113 (Cd-113) + + Pointers : 1131688 20891 + Primary type : Transport + Nuclide ZAI : 481130 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Cd113.ACE + Atomic weight (AW) : 112.89987 + Atomic weight ratio (AWR) : 111.93000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.54E+23 seconds (8.05E+15 years) + Specific ingestion toxicity : 2.50E-08 Sv/Bq + Specific inhalation toxicity : 1.20E-07 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 26 reaction channels + - 7 special reactions + - 12 transmutation reactions + - 9 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 26 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.54410E+00 MeV Emin = 6.60257E+00 MeV frac = 1.00000E+00 Product nuclide = 48112.82c : (n,2n) + 3 MT = 17 Q = -1.59390E+01 MeV Emin = 1.60814E+01 MeV frac = 1.00000E+00 Product nuclide = 48111.82c : (n,3n) + 4 MT = 22 Q = -3.86970E+00 MeV Emin = 3.90428E+00 MeV frac = 1.00000E+00 Product nuclide = 461090 : (n,nalpha) + 5 MT = 28 Q = -9.71990E+00 MeV Emin = 9.80674E+00 MeV frac = 1.00000E+00 Product nuclide = 471120 : (n,np) + 6 MT = 32 Q = -1.39660E+01 MeV Emin = 1.40908E+01 MeV frac = 1.00000E+00 Product nuclide = 47111.82c : (n,nd) + 7 MT = 33 Q = -1.65440E+01 MeV Emin = 1.66918E+01 MeV frac = 1.00000E+00 Product nuclide = 471100 : (n,nt) + 8 MT = 51 Q = -2.63660E-01 MeV Emin = 2.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -2.98330E-01 MeV Emin = 3.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -3.16000E-01 MeV Emin = 3.10000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -4.58000E-01 MeV Emin = 4.26250E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -5.22000E-01 MeV Emin = 5.25546E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -5.30000E-01 MeV Emin = 5.33478E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -5.84000E-01 MeV Emin = 5.89000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -6.38000E-01 MeV Emin = 6.43500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -6.81000E-01 MeV Emin = 6.65250E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -7.08000E-01 MeV Emin = 7.14000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -7.60000E-01 MeV Emin = 7.42494E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 62 Q = -8.20000E-01 MeV Emin = 8.27000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 20 MT = 91 Q = -9.91200E-01 MeV Emin = 9.13663E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 21 MT = 102 Q = 9.04298E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 48114.82c : (n,gamma) + 22 MT = 103 Q = -1.22800E+00 MeV Emin = 1.80000E+00 MeV frac = 1.00000E+00 Product nuclide = 471130 : (n,p) + 23 MT = 104 Q = -7.49570E+00 MeV Emin = 7.56267E+00 MeV frac = 1.00000E+00 Product nuclide = 471120 : (n,d) + 24 MT = 105 Q = -7.70380E+00 MeV Emin = 7.77263E+00 MeV frac = 1.00000E+00 Product nuclide = 47111.82c : (n,t) + 25 MT = 106 Q = -9.88250E+00 MeV Emin = 9.97080E+00 MeV frac = 1.00000E+00 Product nuclide = 461110 : (n,He-3) + 26 MT = 107 Q = 5.31030E+00 MeV Emin = 1.85906E-07 MeV frac = 1.00000E+00 Product nuclide = 46110.82c : (n,alpha) + + 9 additional transport branches: + + 1 MT = 22 Q = -3.86970E+00 MeV Emin = 3.90428E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -9.71990E+00 MeV Emin = 9.80674E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.39660E+01 MeV Emin = 1.40908E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.65440E+01 MeV Emin = 1.66918E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 103 Q = -1.22800E+00 MeV Emin = 1.80000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 104 Q = -7.49570E+00 MeV Emin = 7.56267E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 7 MT = 105 Q = -7.70380E+00 MeV Emin = 7.77263E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 8 MT = 106 Q = -9.88250E+00 MeV Emin = 9.97080E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 9 MT = 107 Q = 5.31030E+00 MeV Emin = 1.85906E-07 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.80000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.56267E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 7.77263E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 9.97080E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.85906E-07 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.84875E-07 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 2.50000E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.22000E-01 MeV frac = 1.00000E+00 Product nuclide = 49113.82c : beta- + + Nuclide 135 / 1657 : 48114.82c -- cadmium 114 (Cd-114) + + Pointers : 1135429 20937 + Primary type : Transport + Nuclide ZAI : 481140 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Cd114.ACE + Atomic weight (AW) : 113.90349 + Atomic weight ratio (AWR) : 112.92500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.90E+24 seconds (9.21E+16 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 24 reaction channels + - 7 special reactions + - 12 transmutation reactions + - 10 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 24 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -9.04070E+00 MeV Emin = 9.12076E+00 MeV frac = 1.00000E+00 Product nuclide = 48113.82c : (n,2n) + 3 MT = 17 Q = -1.55830E+01 MeV Emin = 1.57210E+01 MeV frac = 1.00000E+00 Product nuclide = 48112.82c : (n,3n) + 4 MT = 22 Q = -4.07700E+00 MeV Emin = 4.11311E+00 MeV frac = 1.00000E+00 Product nuclide = 46110.82c : (n,nalpha) + 5 MT = 28 Q = -1.02700E+01 MeV Emin = 1.03610E+01 MeV frac = 1.00000E+00 Product nuclide = 471130 : (n,np) + 6 MT = 32 Q = -1.65350E+01 MeV Emin = 1.66814E+01 MeV frac = 1.00000E+00 Product nuclide = 471120 : (n,nd) + 7 MT = 33 Q = -1.67430E+01 MeV Emin = 1.68913E+01 MeV frac = 1.00000E+00 Product nuclide = 47111.82c : (n,nt) + 8 MT = 51 Q = -5.58100E-01 MeV Emin = 5.60000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -1.13000E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -1.21000E+00 MeV Emin = 1.22000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -1.27900E+00 MeV Emin = 1.29000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -1.30800E+00 MeV Emin = 1.30516E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -1.36800E+00 MeV Emin = 1.35000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -1.73500E+00 MeV Emin = 1.75000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -1.84200E+00 MeV Emin = 1.80000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -1.86300E+00 MeV Emin = 1.87000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -1.86310E+00 MeV Emin = 1.87000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 91 Q = -1.86310E+00 MeV Emin = 1.87000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 19 MT = 102 Q = 6.14800E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 481150 : (n,gamma) + 20 MT = 103 Q = -4.07700E+00 MeV Emin = 4.11311E+00 MeV frac = 1.00000E+00 Product nuclide = 471140 : (n,p) + 21 MT = 104 Q = -8.04440E+00 MeV Emin = 8.11564E+00 MeV frac = 1.00000E+00 Product nuclide = 471130 : (n,d) + 22 MT = 105 Q = -1.02790E+01 MeV Emin = 1.03700E+01 MeV frac = 1.00000E+00 Product nuclide = 471120 : (n,t) + 23 MT = 106 Q = -9.04000E+00 MeV Emin = 9.12005E+00 MeV frac = 1.00000E+00 Product nuclide = 461120 : (n,He-3) + 24 MT = 107 Q = 1.67150E+00 MeV Emin = 1.40000E-02 MeV frac = 1.00000E+00 Product nuclide = 461110 : (n,alpha) + + 10 additional transport branches: + + 1 MT = 22 Q = -4.07700E+00 MeV Emin = 4.11311E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.02700E+01 MeV Emin = 1.03610E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.65350E+01 MeV Emin = 1.66814E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.67430E+01 MeV Emin = 1.68913E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 102 Q = 6.14800E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 48515.82c : (n,gamma) + 6 MT = 103 Q = -4.07700E+00 MeV Emin = 4.11311E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 7 MT = 104 Q = -8.04440E+00 MeV Emin = 8.11564E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 8 MT = 105 Q = -1.02790E+01 MeV Emin = 1.03700E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 9 MT = 106 Q = -9.04000E+00 MeV Emin = 9.12005E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 10 MT = 107 Q = 1.67150E+00 MeV Emin = 1.40000E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.11311E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.11564E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.03700E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 9.12005E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.40000E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 5.60000E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 11 Q = 5.42500E-01 MeV frac = 1.00000E+00 Product nuclide = 501140 : beta- + beta- + + Nuclide 136 / 1657 : 48515.82c -- cadmium 115m (Cd-115m) + + Pointers : 1139741 20983 + Primary type : Transport + Nuclide ZAI : 481151 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Cd115M.ACE + Atomic weight (AW) : 114.90610 + Atomic weight ratio (AWR) : 113.91900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 3.85E+06 seconds (44.6 days) + Specific ingestion toxicity : 3.30E-09 Sv/Bq + Specific inhalation toxicity : 7.70E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 9 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 6 transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 9 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 91 Q = -6.93890E-01 MeV Emin = 6.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 3 MT = 102 Q = 8.79000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 48116.82c : (n,gamma) + 4 MT = 103 Q = -2.58050E+00 MeV Emin = 2.60315E+00 MeV frac = 1.00000E+00 Product nuclide = 471150 : (n,p) + 5 MT = 104 Q = -8.17550E+00 MeV Emin = 8.24727E+00 MeV frac = 1.00000E+00 Product nuclide = 471140 : (n,d) + 6 MT = 105 Q = -8.10930E+00 MeV Emin = 8.18049E+00 MeV frac = 1.00000E+00 Product nuclide = 471130 : (n,t) + 7 MT = 106 Q = -1.14900E+01 MeV Emin = 1.15909E+01 MeV frac = 1.00000E+00 Product nuclide = 461130 : (n,He-3) + 8 MT = 107 Q = 3.69720E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 461120 : (n,alpha) + 9 MT = 111 Q = -1.06310E+01 MeV Emin = 1.07243E+01 MeV frac = 1.00000E+00 Product nuclide = 461140 : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = -2.58050E+00 MeV Emin = 2.60315E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -8.17550E+00 MeV Emin = 8.24727E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -8.10930E+00 MeV Emin = 8.18049E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -1.14900E+01 MeV Emin = 1.15909E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 3.69720E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -1.06310E+01 MeV Emin = 1.07243E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.60315E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.24727E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 8.18049E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.15909E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.62500E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 6.50000E-01 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.62970E+00 MeV frac = 9.99894E-01 Product nuclide = 49115.82c : beta- + 2 RTYP = 1 Q = 1.29345E+00 MeV frac = 1.05757E-04 Product nuclide = 491151 : beta- + + Nuclide 137 / 1657 : 48116.82c -- cadmium 116 (Cd-116) + + Pointers : 1142757 21029 + Primary type : Transport + Nuclide ZAI : 481160 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Cd116.ACE + Atomic weight (AW) : 115.90468 + Atomic weight ratio (AWR) : 114.90900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 9.47E+26 seconds (3E+19 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 20 reaction channels + - 7 special reactions + - 12 transmutation reactions + - 10 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 20 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.69700E+00 MeV Emin = 8.77269E+00 MeV frac = 1.00000E+00 Product nuclide = 481150 : (n,2n) + 3 MT = 17 Q = -1.48420E+01 MeV Emin = 1.49712E+01 MeV frac = 1.00000E+00 Product nuclide = 48114.82c : (n,3n) + 4 MT = 22 Q = -4.81750E+00 MeV Emin = 4.85942E+00 MeV frac = 1.00000E+00 Product nuclide = 461120 : (n,nalpha) + 5 MT = 28 Q = -1.10940E+01 MeV Emin = 1.11906E+01 MeV frac = 1.00000E+00 Product nuclide = 471150 : (n,np) + 6 MT = 32 Q = -1.66960E+01 MeV Emin = 1.68413E+01 MeV frac = 1.00000E+00 Product nuclide = 471140 : (n,nd) + 7 MT = 33 Q = -1.66250E+01 MeV Emin = 1.67700E+01 MeV frac = 1.00000E+00 Product nuclide = 471130 : (n,nt) + 8 MT = 51 Q = -5.12580E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -1.20900E+00 MeV Emin = 1.20000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -1.21900E+00 MeV Emin = 1.22500E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -1.27900E+00 MeV Emin = 1.26000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -1.37800E+00 MeV Emin = 1.34007E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -1.64600E+00 MeV Emin = 1.66000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 91 Q = -1.78460E+00 MeV Emin = 1.73016E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 15 MT = 102 Q = 5.76500E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 481170 : (n,gamma) + 16 MT = 103 Q = -5.31600E+00 MeV Emin = 5.36226E+00 MeV frac = 1.00000E+00 Product nuclide = 471160 : (n,p) + 17 MT = 104 Q = -8.87350E+00 MeV Emin = 8.95072E+00 MeV frac = 1.00000E+00 Product nuclide = 471150 : (n,d) + 18 MT = 105 Q = -1.04380E+01 MeV Emin = 1.05300E+01 MeV frac = 1.00000E+00 Product nuclide = 471140 : (n,t) + 19 MT = 106 Q = -1.12330E+01 MeV Emin = 1.13308E+01 MeV frac = 1.00000E+00 Product nuclide = 461140 : (n,He-3) + 20 MT = 107 Q = 5.72900E-01 MeV Emin = 2.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 461130 : (n,alpha) + + 10 additional transport branches: + + 1 MT = 22 Q = -4.81750E+00 MeV Emin = 4.85942E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.10940E+01 MeV Emin = 1.11906E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.66960E+01 MeV Emin = 1.68413E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.66250E+01 MeV Emin = 1.67700E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 102 Q = 5.76500E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 481171 : (n,gamma) + 6 MT = 103 Q = -5.31600E+00 MeV Emin = 5.36226E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 7 MT = 104 Q = -8.87350E+00 MeV Emin = 8.95072E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 8 MT = 105 Q = -1.04380E+01 MeV Emin = 1.05300E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 9 MT = 106 Q = -1.12330E+01 MeV Emin = 1.13308E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 10 MT = 107 Q = 5.72900E-01 MeV Emin = 2.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 5.36226E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.95072E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.05300E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.13308E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 2.00000E-01 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 5.00000E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 11 Q = 2.81344E+00 MeV frac = 1.00000E+00 Product nuclide = 50116.82c : beta- + beta- + + Nuclide 138 / 1657 : 49113.82c -- indium 113 (In-113) + + Pointers : 1166336 26641 + Primary type : Transport + Nuclide ZAI : 491130 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/In113.ACE + Atomic weight (AW) : 112.90390 + Atomic weight ratio (AWR) : 111.93400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 38 reaction channels + - 7 special reactions + - 12 transmutation reactions + - 10 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 38 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -9.44809E+00 MeV Emin = 9.53251E+00 MeV frac = 1.00000E+00 Product nuclide = 491120 : (n,2n) + 3 MT = 17 Q = -1.71192E+01 MeV Emin = 1.72722E+01 MeV frac = 1.00000E+00 Product nuclide = 491110 : (n,3n) + 4 MT = 22 Q = -3.07190E+00 MeV Emin = 3.09935E+00 MeV frac = 1.00000E+00 Product nuclide = 47109.82c : (n,nalpha) + 5 MT = 28 Q = -6.08773E+00 MeV Emin = 7.05494E+00 MeV frac = 1.00000E+00 Product nuclide = 48112.82c : (n,np) + 6 MT = 32 Q = -1.31776E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 48111.82c : (n,nd) + 7 MT = 33 Q = -1.39736E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 48110.82c : (n,nt) + 8 MT = 51 Q = -3.91699E-01 MeV Emin = 3.47600E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -6.46799E-01 MeV Emin = 6.49517E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -1.02420E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -1.02970E+00 MeV Emin = 1.03613E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -1.06420E+00 MeV Emin = 1.06066E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -1.10640E+00 MeV Emin = 1.09766E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -1.13150E+00 MeV Emin = 1.13211E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -1.17310E+00 MeV Emin = 1.17440E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -1.19110E+00 MeV Emin = 1.19266E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -1.34480E+00 MeV Emin = 1.32343E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -1.35100E+00 MeV Emin = 1.35994E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 62 Q = -1.38070E+00 MeV Emin = 1.38554E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 20 MT = 63 Q = -1.47180E+00 MeV Emin = 1.48453E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 21 MT = 64 Q = -1.50940E+00 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 22 MT = 65 Q = -1.53610E+00 MeV Emin = 1.53972E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 23 MT = 66 Q = -1.56700E+00 MeV Emin = 1.56541E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 24 MT = 67 Q = -1.56950E+00 MeV Emin = 1.58320E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 25 MT = 68 Q = -1.63050E+00 MeV Emin = 1.61814E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 26 MT = 69 Q = -1.68820E+00 MeV Emin = 1.69055E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 27 MT = 70 Q = -1.70000E+00 MeV Emin = 1.70924E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 28 MT = 71 Q = -1.70700E+00 MeV Emin = 1.71872E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 29 MT = 72 Q = -1.75800E+00 MeV Emin = 1.75000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 30 MT = 73 Q = -1.76800E+00 MeV Emin = 1.77876E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 31 MT = 74 Q = -1.82270E+00 MeV Emin = 1.81139E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 32 MT = 91 Q = -1.83610E+00 MeV Emin = 1.84574E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 33 MT = 102 Q = 7.27539E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 491140 : (n,gamma) + 34 MT = 103 Q = 4.60756E-01 MeV Emin = 1.56541E+00 MeV frac = 1.00000E+00 Product nuclide = 48113.82c : (n,p) + 35 MT = 104 Q = -3.77761E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 48112.82c : (n,d) + 36 MT = 105 Q = -6.99246E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 48111.82c : (n,t) + 37 MT = 106 Q = -8.00183E+00 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 47111.82c : (n,He-3) + 38 MT = 107 Q = 3.73819E+00 MeV Emin = 1.00098E-01 MeV frac = 1.00000E+00 Product nuclide = 471100 : (n,alpha) + + 10 additional transport branches: + + 1 MT = 22 Q = -3.07190E+00 MeV Emin = 3.09935E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -6.08773E+00 MeV Emin = 7.05494E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.31776E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.39736E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 102 Q = 7.27539E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 491141 : (n,gamma) + 6 MT = 103 Q = 4.60756E-01 MeV Emin = 1.56541E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 7 MT = 104 Q = -3.77761E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 8 MT = 105 Q = -6.99246E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 9 MT = 106 Q = -8.00183E+00 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 10 MT = 107 Q = 3.73819E+00 MeV Emin = 1.00098E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.56541E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.00000E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.20000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00098E-01 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 3.47600E-01 MeV : total inelastic scattering + + Nuclide 139 / 1657 : 49115.82c -- indium 115 (In-115) + + Pointers : 1171964 26687 + Primary type : Transport + Nuclide ZAI : 491150 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/In115.ACE + Atomic weight (AW) : 114.90409 + Atomic weight ratio (AWR) : 113.91700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.39E+22 seconds (4.41E+14 years) + Specific ingestion toxicity : 3.20E-08 Sv/Bq + Specific inhalation toxicity : 3.90E-07 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 26 reaction channels + - 6 special reactions + - 11 transmutation reactions + - 8 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 26 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -9.04110E+00 MeV Emin = 9.12048E+00 MeV frac = 1.00000E+00 Product nuclide = 491140 : (n,2n) + 3 MT = 17 Q = -1.63212E+01 MeV Emin = 1.64645E+01 MeV frac = 1.00000E+00 Product nuclide = 49113.82c : (n,3n) + 4 MT = 22 Q = -3.73689E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 47111.82c : (n,nalpha) + 5 MT = 28 Q = -6.81504E+00 MeV Emin = 7.42983E+00 MeV frac = 1.00000E+00 Product nuclide = 48114.82c : (n,np) + 6 MT = 32 Q = -1.35503E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 48113.82c : (n,nd) + 7 MT = 33 Q = -1.39137E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 48112.82c : (n,nt) + 8 MT = 51 Q = -3.36200E-01 MeV Emin = 3.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -5.96999E-01 MeV Emin = 6.00488E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -8.28399E-01 MeV Emin = 8.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -8.63999E-01 MeV Emin = 8.64284E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -9.33599E-01 MeV Emin = 9.20898E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -9.41199E-01 MeV Emin = 9.45628E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -1.07800E+00 MeV Emin = 1.06560E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -1.13250E+00 MeV Emin = 1.12870E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -1.29050E+00 MeV Emin = 1.30081E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -1.41800E+00 MeV Emin = 1.42919E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -1.44870E+00 MeV Emin = 1.45677E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 62 Q = -1.46250E+00 MeV Emin = 1.46605E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 20 MT = 63 Q = -1.48580E+00 MeV Emin = 1.48709E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 21 MT = 91 Q = -1.50000E+00 MeV Emin = 1.51286E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 22 MT = 102 Q = 6.78473E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 491160 : (n,gamma) + 23 MT = 103 Q = -6.65537E-01 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 481150 : (n,p) + 24 MT = 104 Q = -4.50492E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 48114.82c : (n,d) + 25 MT = 105 Q = -7.36516E+00 MeV Emin = 9.43898E+00 MeV frac = 1.00000E+00 Product nuclide = 48113.82c : (n,t) + 26 MT = 107 Q = 2.73321E+00 MeV Emin = 1.18750E-01 MeV frac = 1.00000E+00 Product nuclide = 471120 : (n,alpha) + + 8 additional transport branches: + + 1 MT = 22 Q = -3.73689E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -6.81504E+00 MeV Emin = 7.42983E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.35503E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.39137E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 103 Q = -6.65537E-01 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 104 Q = -4.50492E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 7 MT = 105 Q = -7.36516E+00 MeV Emin = 9.43898E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 8 MT = 107 Q = 2.73321E+00 MeV Emin = 1.18750E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.43898E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 1.18750E-01 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 7.07357E-04 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 3.00000E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.97489E-01 MeV frac = 1.00000E+00 Product nuclide = 50115.82c : beta- + + Nuclide 140 / 1657 : 50115.82c -- tin 115 (Sn-115) + + Pointers : 1205655 33449 + Primary type : Transport + Nuclide ZAI : 501150 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Sn115.ACE + Atomic weight (AW) : 114.90308 + Atomic weight ratio (AWR) : 113.91600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 29 reaction channels + - 7 special reactions + - 11 transmutation reactions + - 8 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 29 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.55119E+00 MeV Emin = 7.61749E+00 MeV frac = 1.00000E+00 Product nuclide = 501140 : (n,2n) + 3 MT = 17 Q = -1.78553E+01 MeV Emin = 1.80121E+01 MeV frac = 1.00000E+00 Product nuclide = 501130 : (n,3n) + 4 MT = 22 Q = -3.20300E+00 MeV Emin = 3.23112E+00 MeV frac = 1.00000E+00 Product nuclide = 48111.82c : (n,nalpha) + 5 MT = 28 Q = -8.75274E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 491140 : (n,np) + 6 MT = 32 Q = -1.37227E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 49113.82c : (n,nd) + 7 MT = 51 Q = -4.97299E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 8 MT = 52 Q = -6.12799E-01 MeV Emin = 6.03615E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 9 MT = 53 Q = -7.13399E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 10 MT = 54 Q = -9.86499E-01 MeV Emin = 9.71370E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 11 MT = 55 Q = -1.28010E+00 MeV Emin = 1.25000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 12 MT = 56 Q = -1.41680E+00 MeV Emin = 1.42896E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 13 MT = 57 Q = -1.63380E+00 MeV Emin = 1.60185E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 14 MT = 58 Q = -1.73390E+00 MeV Emin = 1.71756E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 15 MT = 59 Q = -1.78560E+00 MeV Emin = 1.78845E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 16 MT = 60 Q = -1.82500E+00 MeV Emin = 1.82115E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 17 MT = 61 Q = -1.85750E+00 MeV Emin = 1.85740E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 18 MT = 62 Q = -1.94400E+00 MeV Emin = 1.93380E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 19 MT = 63 Q = -1.96400E+00 MeV Emin = 1.97115E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 20 MT = 64 Q = -1.97380E+00 MeV Emin = 1.99062E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 21 MT = 65 Q = -2.02460E+00 MeV Emin = 2.04237E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 22 MT = 66 Q = -2.06010E+00 MeV Emin = 2.07818E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 23 MT = 91 Q = -2.08420E+00 MeV Emin = 2.10250E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 24 MT = 102 Q = 9.56239E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 50116.82c : (n,gamma) + 25 MT = 103 Q = 2.88364E-01 MeV Emin = 1.75080E+00 MeV frac = 1.00000E+00 Product nuclide = 49115.82c : (n,p) + 26 MT = 104 Q = -6.44262E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 491140 : (n,d) + 27 MT = 105 Q = -7.53756E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 49113.82c : (n,t) + 28 MT = 106 Q = -7.84063E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 48113.82c : (n,He-3) + 29 MT = 107 Q = 6.19700E+00 MeV Emin = 9.49999E-02 MeV frac = 1.00000E+00 Product nuclide = 48112.82c : (n,alpha) + + 8 additional transport branches: + + 1 MT = 22 Q = -3.20300E+00 MeV Emin = 3.23112E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -8.75274E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.37227E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 103 Q = 2.88364E-01 MeV Emin = 1.75080E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -6.44262E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -7.53756E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 106 Q = -7.84063E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 8 MT = 107 Q = 6.19700E+00 MeV Emin = 9.49999E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.75080E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.00000E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.10000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 9.49999E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 5.00000E-01 MeV : total inelastic scattering + + Nuclide 141 / 1657 : 50116.82c -- tin 116 (Sn-116) + + Pointers : 1208978 33495 + Primary type : Transport + Nuclide ZAI : 501160 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Sn116.ACE + Atomic weight (AW) : 115.90166 + Atomic weight ratio (AWR) : 114.90600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 21 reaction channels + - 6 special reactions + - 9 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 21 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -9.56709E+00 MeV Emin = 9.65036E+00 MeV frac = 1.00000E+00 Product nuclide = 50115.82c : (n,2n) + 3 MT = 17 Q = -1.71183E+01 MeV Emin = 1.72673E+01 MeV frac = 1.00000E+00 Product nuclide = 501140 : (n,3n) + 4 MT = 22 Q = -3.37009E+00 MeV Emin = 3.39942E+00 MeV frac = 1.00000E+00 Product nuclide = 48112.82c : (n,nalpha) + 5 MT = 28 Q = -9.27873E+00 MeV Emin = 1.00308E+01 MeV frac = 1.00000E+00 Product nuclide = 49115.82c : (n,np) + 6 MT = 51 Q = -1.29350E+00 MeV Emin = 1.25000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.75680E+00 MeV Emin = 1.76523E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -2.02730E+00 MeV Emin = 2.04494E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -2.11230E+00 MeV Emin = 2.13068E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -2.22530E+00 MeV Emin = 2.24467E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -2.26610E+00 MeV Emin = 2.28582E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -2.36590E+00 MeV Emin = 2.38649E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -2.39080E+00 MeV Emin = 2.41161E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -2.39220E+00 MeV Emin = 2.41302E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -2.52910E+00 MeV Emin = 2.55111E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 91 Q = -2.54600E+00 MeV Emin = 2.56816E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 17 MT = 102 Q = 6.94419E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 50117.82c : (n,gamma) + 18 MT = 103 Q = -2.49064E+00 MeV Emin = 3.39942E+00 MeV frac = 1.00000E+00 Product nuclide = 491160 : (n,p) + 19 MT = 104 Q = -6.96861E+00 MeV Emin = 8.43511E+00 MeV frac = 1.00000E+00 Product nuclide = 49115.82c : (n,d) + 20 MT = 105 Q = -9.82456E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 491140 : (n,t) + 21 MT = 107 Q = 3.17841E+00 MeV Emin = 1.04375E-01 MeV frac = 1.00000E+00 Product nuclide = 48113.82c : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -3.37009E+00 MeV Emin = 3.39942E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -9.27873E+00 MeV Emin = 1.00308E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 102 Q = 6.94419E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 501171 : (n,gamma) + 4 MT = 103 Q = -2.49064E+00 MeV Emin = 3.39942E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -6.96861E+00 MeV Emin = 8.43511E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -9.82456E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 107 Q = 3.17841E+00 MeV Emin = 1.04375E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.39942E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.43511E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.10000E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 1.04375E-01 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 1.25000E+00 MeV : total inelastic scattering + + Nuclide 142 / 1657 : 50117.82c -- tin 117 (Sn-117) + + Pointers : 1211590 33541 + Primary type : Transport + Nuclide ZAI : 501170 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Sn117.ACE + Atomic weight (AW) : 116.90326 + Atomic weight ratio (AWR) : 115.89900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 24 reaction channels + - 6 special reactions + - 10 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 24 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.94890E+00 MeV Emin = 7.00886E+00 MeV frac = 1.00000E+00 Product nuclide = 50116.82c : (n,2n) + 3 MT = 17 Q = -1.65160E+01 MeV Emin = 1.66585E+01 MeV frac = 1.00000E+00 Product nuclide = 50115.82c : (n,3n) + 4 MT = 22 Q = -3.77049E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 48113.82c : (n,nalpha) + 5 MT = 28 Q = -9.43953E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 491160 : (n,np) + 6 MT = 32 Q = -1.39175E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 49115.82c : (n,nd) + 7 MT = 51 Q = -1.58600E-01 MeV Emin = 1.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 8 MT = 52 Q = -3.14600E-01 MeV Emin = 3.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 9 MT = 53 Q = -7.11599E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 10 MT = 54 Q = -1.00450E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 11 MT = 55 Q = -1.01990E+00 MeV Emin = 1.02093E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 12 MT = 56 Q = -1.17960E+00 MeV Emin = 1.18855E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 13 MT = 57 Q = -1.30430E+00 MeV Emin = 1.28277E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 14 MT = 58 Q = -1.44640E+00 MeV Emin = 1.42305E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 15 MT = 59 Q = -1.49720E+00 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 16 MT = 60 Q = -1.57830E+00 MeV Emin = 1.57147E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 17 MT = 61 Q = -1.66800E+00 MeV Emin = 1.65977E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 18 MT = 62 Q = -1.77000E+00 MeV Emin = 1.75000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 19 MT = 91 Q = -1.94800E+00 MeV Emin = 1.92273E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 20 MT = 102 Q = 9.32619E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 50118.82c : (n,gamma) + 21 MT = 103 Q = -6.72430E-01 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 491170 : (n,p) + 22 MT = 104 Q = -7.12941E+00 MeV Emin = 8.26316E+00 MeV frac = 1.00000E+00 Product nuclide = 491160 : (n,d) + 23 MT = 105 Q = -7.73235E+00 MeV Emin = 9.52099E+00 MeV frac = 1.00000E+00 Product nuclide = 49115.82c : (n,t) + 24 MT = 107 Q = 5.27490E+00 MeV Emin = 9.99804E-02 MeV frac = 1.00000E+00 Product nuclide = 48114.82c : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -3.77049E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -9.43953E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.39175E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 103 Q = -6.72430E-01 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -7.12941E+00 MeV Emin = 8.26316E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -7.73235E+00 MeV Emin = 9.52099E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 107 Q = 5.27490E+00 MeV Emin = 9.99804E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.26316E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.52099E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 9.99804E-02 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 1.50000E-01 MeV : total inelastic scattering + + Nuclide 143 / 1657 : 50118.82c -- tin 118 (Sn-118) + + Pointers : 1214913 33587 + Primary type : Transport + Nuclide ZAI : 501180 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Sn118.ACE + Atomic weight (AW) : 117.90184 + Atomic weight ratio (AWR) : 116.88900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 18 reaction channels + - 6 special reactions + - 9 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 18 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -9.33080E+00 MeV Emin = 9.41063E+00 MeV frac = 1.00000E+00 Product nuclide = 50117.82c : (n,2n) + 3 MT = 17 Q = -1.62797E+01 MeV Emin = 1.64190E+01 MeV frac = 1.00000E+00 Product nuclide = 50116.82c : (n,3n) + 4 MT = 22 Q = -4.05589E+00 MeV Emin = 4.09060E+00 MeV frac = 1.00000E+00 Product nuclide = 48114.82c : (n,nalpha) + 5 MT = 28 Q = -1.00032E+01 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 491170 : (n,np) + 6 MT = 51 Q = -1.22960E+00 MeV Emin = 1.16508E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.75780E+00 MeV Emin = 1.76705E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -2.04310E+00 MeV Emin = 2.06058E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -2.05650E+00 MeV Emin = 2.07409E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -2.28030E+00 MeV Emin = 2.29981E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -2.31000E+00 MeV Emin = 2.32976E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -2.32110E+00 MeV Emin = 2.34096E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 91 Q = -2.32650E+00 MeV Emin = 2.34640E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 14 MT = 102 Q = 6.48449E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 50119.82c : (n,gamma) + 15 MT = 103 Q = -3.42113E+00 MeV Emin = 4.09060E+00 MeV frac = 1.00000E+00 Product nuclide = 491180 : (n,p) + 16 MT = 104 Q = -7.69311E+00 MeV Emin = 9.41063E+00 MeV frac = 1.00000E+00 Product nuclide = 491170 : (n,d) + 17 MT = 105 Q = -1.02751E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 491160 : (n,t) + 18 MT = 107 Q = 2.09361E+00 MeV Emin = 1.08254E+00 MeV frac = 1.00000E+00 Product nuclide = 481150 : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -4.05589E+00 MeV Emin = 4.09060E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.00032E+01 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 102 Q = 6.48449E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 501191 : (n,gamma) + 4 MT = 103 Q = -3.42113E+00 MeV Emin = 4.09060E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -7.69311E+00 MeV Emin = 9.41063E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -1.02751E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 107 Q = 2.09361E+00 MeV Emin = 1.08254E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.09060E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 9.41063E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.20000E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 1.08254E+00 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 1.16508E+00 MeV : total inelastic scattering + + Nuclide 144 / 1657 : 50119.82c -- tin 119 (Sn-119) + + Pointers : 1217306 33633 + Primary type : Transport + Nuclide ZAI : 501190 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Sn119.ACE + Atomic weight (AW) : 118.90344 + Atomic weight ratio (AWR) : 117.88200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 32 reaction channels + - 6 special reactions + - 10 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 32 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.48919E+00 MeV Emin = 6.54425E+00 MeV frac = 1.00000E+00 Product nuclide = 50118.82c : (n,2n) + 3 MT = 17 Q = -1.58200E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 50117.82c : (n,3n) + 4 MT = 22 Q = -4.39558E+00 MeV Emin = 4.43288E+00 MeV frac = 1.00000E+00 Product nuclide = 481150 : (n,nalpha) + 5 MT = 28 Q = -9.91033E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 491180 : (n,np) + 6 MT = 32 Q = -1.41823E+01 MeV Emin = 1.59542E+01 MeV frac = 1.00000E+00 Product nuclide = 491170 : (n,nd) + 7 MT = 51 Q = -2.39000E-02 MeV Emin = 2.20514E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 8 MT = 52 Q = -8.94999E-02 MeV Emin = 8.87824E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 9 MT = 53 Q = -7.86999E-01 MeV Emin = 7.70257E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 10 MT = 54 Q = -9.20499E-01 MeV Emin = 9.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 11 MT = 55 Q = -9.21399E-01 MeV Emin = 9.28975E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 12 MT = 56 Q = -1.06240E+00 MeV Emin = 1.03571E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 13 MT = 57 Q = -1.08940E+00 MeV Emin = 1.08843E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 14 MT = 58 Q = -1.18770E+00 MeV Emin = 1.19110E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 15 MT = 59 Q = -1.24970E+00 MeV Emin = 1.25000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 16 MT = 60 Q = -1.35490E+00 MeV Emin = 1.33987E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 17 MT = 61 Q = -1.55440E+00 MeV Emin = 1.53371E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 18 MT = 62 Q = -1.57160E+00 MeV Emin = 1.57626E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 19 MT = 63 Q = -1.61730E+00 MeV Emin = 1.61374E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 20 MT = 64 Q = -1.63100E+00 MeV Emin = 1.63793E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 21 MT = 65 Q = -1.71840E+00 MeV Emin = 1.71094E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 22 MT = 66 Q = -1.77470E+00 MeV Emin = 1.76988E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 23 MT = 67 Q = -1.78970E+00 MeV Emin = 1.79732E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 24 MT = 68 Q = -1.90500E+00 MeV Emin = 1.89391E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 25 MT = 69 Q = -1.92960E+00 MeV Emin = 1.94230E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 26 MT = 70 Q = -1.93880E+00 MeV Emin = 1.95463E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 27 MT = 91 Q = -1.98300E+00 MeV Emin = 1.97754E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 28 MT = 102 Q = 9.10659E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 50120.82c : (n,gamma) + 29 MT = 103 Q = -1.55424E+00 MeV Emin = 2.00351E+00 MeV frac = 1.00000E+00 Product nuclide = 491190 : (n,p) + 30 MT = 104 Q = -7.60021E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 491180 : (n,d) + 31 MT = 105 Q = -7.99715E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 491170 : (n,t) + 32 MT = 107 Q = 4.30510E+00 MeV Emin = 1.00148E-01 MeV frac = 1.00000E+00 Product nuclide = 48116.82c : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -4.39558E+00 MeV Emin = 4.43288E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -9.91033E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.41823E+01 MeV Emin = 1.59542E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 103 Q = -1.55424E+00 MeV Emin = 2.00351E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -7.60021E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -7.99715E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 107 Q = 4.30510E+00 MeV Emin = 1.00148E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.00351E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 9.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.00000E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00148E-01 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 2.20514E-02 MeV : total inelastic scattering + + Nuclide 145 / 1657 : 50120.82c -- tin 120 (Sn-120) + + Pointers : 1221143 33679 + Primary type : Transport + Nuclide ZAI : 501200 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Sn120.ACE + Atomic weight (AW) : 119.90202 + Atomic weight ratio (AWR) : 118.87200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 27 reaction channels + - 6 special reactions + - 9 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 27 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -9.11120E+00 MeV Emin = 9.18785E+00 MeV frac = 1.00000E+00 Product nuclide = 50119.82c : (n,2n) + 3 MT = 17 Q = -1.56004E+01 MeV Emin = 1.57317E+01 MeV frac = 1.00000E+00 Product nuclide = 50118.82c : (n,3n) + 4 MT = 22 Q = -4.80608E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 48116.82c : (n,nalpha) + 5 MT = 28 Q = -1.06654E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 491190 : (n,np) + 6 MT = 51 Q = -1.17150E+00 MeV Emin = 1.10201E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.87500E+00 MeV Emin = 1.75000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -2.09750E+00 MeV Emin = 2.11515E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -2.15980E+00 MeV Emin = 2.17797E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -2.19460E+00 MeV Emin = 2.21306E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -2.28460E+00 MeV Emin = 2.30382E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -2.29000E+00 MeV Emin = 2.30926E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -2.35560E+00 MeV Emin = 2.37542E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -2.39970E+00 MeV Emin = 2.41989E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -2.42110E+00 MeV Emin = 2.44147E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -2.46610E+00 MeV Emin = 2.48685E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -2.48200E+00 MeV Emin = 2.50288E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -2.58680E+00 MeV Emin = 2.60856E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -2.64270E+00 MeV Emin = 2.66493E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -2.69720E+00 MeV Emin = 2.71989E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 21 MT = 66 Q = -2.72130E+00 MeV Emin = 2.74419E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 22 MT = 91 Q = -2.76000E+00 MeV Emin = 2.78322E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 23 MT = 102 Q = 6.17139E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 501210 : (n,gamma) + 24 MT = 103 Q = -4.61932E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 491200 : (n,p) + 25 MT = 104 Q = -8.35531E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 491190 : (n,d) + 26 MT = 105 Q = -1.05263E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 491180 : (n,t) + 27 MT = 107 Q = 9.68414E-01 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 481170 : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -4.80608E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.06654E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 102 Q = 6.17139E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 501211 : (n,gamma) + 4 MT = 103 Q = -4.61932E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -8.35531E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -1.05263E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 107 Q = 9.68414E-01 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 6.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.00000E+01 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.20000E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 1.10201E+00 MeV : total inelastic scattering + + Nuclide 146 / 1657 : 50122.82c -- tin 122 (Sn-122) + + Pointers : 1224994 33725 + Primary type : Transport + Nuclide ZAI : 501220 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Sn122.ACE + Atomic weight (AW) : 121.90321 + Atomic weight ratio (AWR) : 120.85600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 20 reaction channels + - 6 special reactions + - 9 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 20 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.82030E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 501210 : (n,2n) + 3 MT = 17 Q = -1.49964E+01 MeV Emin = 1.51205E+01 MeV frac = 1.00000E+00 Product nuclide = 50120.82c : (n,3n) + 4 MT = 22 Q = -5.66088E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 481180 : (n,nalpha) + 5 MT = 28 Q = -1.13976E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 491210 : (n,np) + 6 MT = 51 Q = -1.14020E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -2.09000E+00 MeV Emin = 2.10729E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -2.14500E+00 MeV Emin = 2.16275E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -2.15300E+00 MeV Emin = 2.17082E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -2.24900E+00 MeV Emin = 2.26761E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -2.33600E+00 MeV Emin = 2.35533E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -2.40000E+00 MeV Emin = 2.41986E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -2.41500E+00 MeV Emin = 2.43498E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -2.49200E+00 MeV Emin = 2.51262E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 91 Q = -2.55600E+00 MeV Emin = 2.57715E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 16 MT = 102 Q = 5.94639E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 50123.82c : (n,gamma) + 17 MT = 103 Q = -5.56352E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 491220 : (n,p) + 18 MT = 104 Q = -9.08751E+00 MeV Emin = 1.12125E+01 MeV frac = 1.00000E+00 Product nuclide = 491210 : (n,d) + 19 MT = 105 Q = -1.11205E+01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 491200 : (n,t) + 20 MT = 107 Q = -6.17863E-02 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 481190 : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -5.66088E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.13976E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 102 Q = 5.94639E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 501231 : (n,gamma) + 4 MT = 103 Q = -5.56352E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -9.08751E+00 MeV Emin = 1.12125E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -1.11205E+01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 107 Q = -6.17863E-02 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 7.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.12125E+01 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.30000E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 1.00000E+00 MeV : total inelastic scattering + + Nuclide 147 / 1657 : 50123.82c -- tin 123 (Sn-123) + + Pointers : 1227533 33771 + Primary type : Transport + Nuclide ZAI : 501230 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Sn123.ACE + Atomic weight (AW) : 122.90583 + Atomic weight ratio (AWR) : 121.85000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.12E+07 seconds (129 days) + Specific ingestion toxicity : 2.10E-09 Sv/Bq + Specific inhalation toxicity : 8.10E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 18 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 6 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 18 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -2.40000E-02 MeV Emin = 2.32268E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -1.98370E-01 MeV Emin = 1.82090E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -9.30000E-01 MeV Emin = 8.18815E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -1.03000E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -1.16000E+00 MeV Emin = 1.08475E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -1.20000E+00 MeV Emin = 1.18966E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 57 Q = -1.49000E+00 MeV Emin = 1.35603E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 9 MT = 58 Q = -1.78000E+00 MeV Emin = 1.60000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 10 MT = 59 Q = -1.83000E+00 MeV Emin = 1.84250E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 11 MT = 91 Q = -1.82500E+00 MeV Emin = 1.81730E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 12 MT = 102 Q = 8.56000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 50124.82c : (n,gamma) + 13 MT = 103 Q = -3.59710E+00 MeV Emin = 3.62662E+00 MeV frac = 1.00000E+00 Product nuclide = 491230 : (n,p) + 14 MT = 104 Q = -9.28210E+00 MeV Emin = 9.35828E+00 MeV frac = 1.00000E+00 Product nuclide = 491220 : (n,d) + 15 MT = 105 Q = -8.85400E+00 MeV Emin = 8.92666E+00 MeV frac = 1.00000E+00 Product nuclide = 491210 : (n,t) + 16 MT = 106 Q = -1.09130E+01 MeV Emin = 1.10026E+01 MeV frac = 1.00000E+00 Product nuclide = 481210 : (n,He-3) + 17 MT = 107 Q = 1.80590E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 481200 : (n,alpha) + 18 MT = 111 Q = -1.14630E+01 MeV Emin = 1.15571E+01 MeV frac = 1.00000E+00 Product nuclide = 481220 : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = -3.59710E+00 MeV Emin = 3.62662E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -9.28210E+00 MeV Emin = 9.35828E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -8.85400E+00 MeV Emin = 8.92666E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -1.09130E+01 MeV Emin = 1.10026E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 1.80590E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -1.14630E+01 MeV Emin = 1.15571E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.62662E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 9.35828E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 8.92666E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.10026E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 2.32268E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.40360E+00 MeV frac = 1.00000E+00 Product nuclide = 51123.82c : beta- + + Nuclide 148 / 1657 : 50124.82c -- tin 124 (Sn-124) + + Pointers : 1230832 33817 + Primary type : Transport + Nuclide ZAI : 501240 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Sn124.ACE + Atomic weight (AW) : 123.90541 + Atomic weight ratio (AWR) : 122.84100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 3.16E+24 seconds (1E+17 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 31 reaction channels + - 6 special reactions + - 9 transmutation reactions + - 7 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 31 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.49509E+00 MeV Emin = 8.56426E+00 MeV frac = 1.00000E+00 Product nuclide = 50123.82c : (n,2n) + 3 MT = 17 Q = -1.44462E+01 MeV Emin = 1.45638E+01 MeV frac = 1.00000E+00 Product nuclide = 50122.82c : (n,3n) + 4 MT = 22 Q = -6.68088E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 481200 : (n,nalpha) + 5 MT = 28 Q = -1.20936E+01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 491230 : (n,np) + 6 MT = 51 Q = -1.13160E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -2.10160E+00 MeV Emin = 2.11871E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -2.12930E+00 MeV Emin = 2.14663E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -2.12940E+00 MeV Emin = 2.14674E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -2.19200E+00 MeV Emin = 2.20985E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -2.20450E+00 MeV Emin = 2.22245E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -2.22150E+00 MeV Emin = 2.23958E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -2.32490E+00 MeV Emin = 2.34383E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -2.36640E+00 MeV Emin = 2.38566E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -2.42640E+00 MeV Emin = 2.44615E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -2.44690E+00 MeV Emin = 2.46682E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -2.56800E+00 MeV Emin = 2.58891E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -2.60240E+00 MeV Emin = 2.62359E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -2.61420E+00 MeV Emin = 2.63548E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -2.68660E+00 MeV Emin = 2.70847E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 21 MT = 66 Q = -2.68870E+00 MeV Emin = 2.71059E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 22 MT = 67 Q = -2.70290E+00 MeV Emin = 2.72490E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 23 MT = 68 Q = -2.83630E+00 MeV Emin = 2.85939E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 24 MT = 69 Q = -2.87510E+00 MeV Emin = 2.89851E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 25 MT = 70 Q = -2.87830E+00 MeV Emin = 2.90173E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 26 MT = 91 Q = -2.90000E+00 MeV Emin = 2.92361E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 27 MT = 102 Q = 5.73339E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 50125.82c : (n,gamma) + 28 MT = 103 Q = -6.35752E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 491240 : (n,p) + 29 MT = 104 Q = -9.78351E+00 MeV Emin = 1.21921E+01 MeV frac = 1.00000E+00 Product nuclide = 491230 : (n,d) + 30 MT = 105 Q = -1.15145E+01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 491220 : (n,t) + 31 MT = 107 Q = -1.25822E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 481210 : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -6.68088E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -1.20936E+01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 102 Q = 5.73339E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 501251 : (n,gamma) + 4 MT = 103 Q = -6.35752E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -9.78351E+00 MeV Emin = 1.21921E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -1.15145E+01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 107 Q = -1.25822E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 8.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.21921E+01 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.30000E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 3.00000E+00 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 1.00000E+00 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 11 Q = 2.29110E+00 MeV frac = 1.00000E+00 Product nuclide = 52124.82c : beta- + beta- + + Nuclide 149 / 1657 : 50125.82c -- tin 125 (Sn-125) + + Pointers : 1234247 33863 + Primary type : Transport + Nuclide ZAI : 501250 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Sn125.ACE + Atomic weight (AW) : 124.90803 + Atomic weight ratio (AWR) : 123.83500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 8.33E+05 seconds (9.64 days) + Specific ingestion toxicity : 3.10E-09 Sv/Bq + Specific inhalation toxicity : 3.10E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 12 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 6 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 12 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -2.60000E-02 MeV Emin = 2.56327E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -2.10000E-01 MeV Emin = 2.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -9.36000E-01 MeV Emin = 8.23000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 91 Q = -9.91990E-01 MeV Emin = 9.73000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 6 MT = 102 Q = 8.16000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 50126.82c : (n,gamma) + 7 MT = 103 Q = -4.61780E+00 MeV Emin = 4.65509E+00 MeV frac = 1.00000E+00 Product nuclide = 491250 : (n,p) + 8 MT = 104 Q = -9.86280E+00 MeV Emin = 9.94245E+00 MeV frac = 1.00000E+00 Product nuclide = 491240 : (n,d) + 9 MT = 105 Q = -9.33680E+00 MeV Emin = 9.41220E+00 MeV frac = 1.00000E+00 Product nuclide = 491230 : (n,t) + 10 MT = 106 Q = -1.25660E+01 MeV Emin = 1.26675E+01 MeV frac = 1.00000E+00 Product nuclide = 481230 : (n,He-3) + 11 MT = 107 Q = 4.80000E-01 MeV Emin = 1.06250E-08 MeV frac = 1.00000E+00 Product nuclide = 481220 : (n,alpha) + 12 MT = 111 Q = -1.32970E+01 MeV Emin = 1.34044E+01 MeV frac = 1.00000E+00 Product nuclide = 481240 : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = -4.61780E+00 MeV Emin = 4.65509E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -9.86280E+00 MeV Emin = 9.94245E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -9.33680E+00 MeV Emin = 9.41220E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -1.25660E+01 MeV Emin = 1.26675E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 4.80000E-01 MeV Emin = 1.06250E-08 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -1.32970E+01 MeV Emin = 1.34044E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.65509E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 9.94245E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.41220E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.26675E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.06250E-08 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 2.56327E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.35700E+00 MeV frac = 1.00000E+00 Product nuclide = 51125.82c : beta- + + Nuclide 150 / 1657 : 50126.82c -- tin 126 (Sn-126) + + Pointers : 1238858 33909 + Primary type : Transport + Nuclide ZAI : 501260 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Sn126.ACE + Atomic weight (AW) : 125.90761 + Atomic weight ratio (AWR) : 124.82600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 7.26E+12 seconds (230,153 years) + Specific ingestion toxicity : 4.70E-09 Sv/Bq + Specific inhalation toxicity : 2.80E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 19 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 7 transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 19 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -1.14000E+00 MeV Emin = 1.11183E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -2.05000E+00 MeV Emin = 2.06642E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -2.17000E+00 MeV Emin = 2.18740E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -2.22000E+00 MeV Emin = 2.23780E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -2.38000E+00 MeV Emin = 2.39910E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -2.66000E+00 MeV Emin = 2.68131E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 57 Q = -2.72000E+00 MeV Emin = 2.74180E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 9 MT = 58 Q = -2.89000E+00 MeV Emin = 2.91320E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 10 MT = 59 Q = -3.28000E+00 MeV Emin = 3.30630E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 11 MT = 60 Q = -3.42000E+00 MeV Emin = 3.44740E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 12 MT = 91 Q = -3.40270E+00 MeV Emin = 3.43000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 13 MT = 102 Q = 5.62000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 501270 : (n,gamma) + 14 MT = 103 Q = -7.33890E+00 MeV Emin = 7.39769E+00 MeV frac = 1.00000E+00 Product nuclide = 491260 : (n,p) + 15 MT = 104 Q = -1.05850E+01 MeV Emin = 1.06698E+01 MeV frac = 1.00000E+00 Product nuclide = 491250 : (n,d) + 16 MT = 105 Q = -1.17980E+01 MeV Emin = 1.18925E+01 MeV frac = 1.00000E+00 Product nuclide = 491240 : (n,t) + 17 MT = 106 Q = -1.37720E+01 MeV Emin = 1.38823E+01 MeV frac = 1.00000E+00 Product nuclide = 481240 : (n,He-3) + 18 MT = 107 Q = -1.86100E-01 MeV Emin = 1.65683E-01 MeV frac = 1.00000E+00 Product nuclide = 481230 : (n,alpha) + 19 MT = 111 Q = -1.64250E+01 MeV Emin = 1.65566E+01 MeV frac = 1.00000E+00 Product nuclide = 481250 : (n,2p) + + 7 additional transport branches: + + 1 MT = 102 Q = 5.62000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 501271 : (n,gamma) + 2 MT = 103 Q = -7.33890E+00 MeV Emin = 7.39769E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 104 Q = -1.05850E+01 MeV Emin = 1.06698E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 4 MT = 105 Q = -1.17980E+01 MeV Emin = 1.18925E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 5 MT = 106 Q = -1.37720E+01 MeV Emin = 1.38823E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 6 MT = 107 Q = -1.86100E-01 MeV Emin = 1.65683E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 7 MT = 111 Q = -1.64250E+01 MeV Emin = 1.65566E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 7.39769E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.06698E+01 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.18925E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.38823E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.65683E-01 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 1.11183E+00 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 1 Q = 3.60300E-01 MeV frac = 3.30685E-01 Product nuclide = 511261 : beta- + 2 RTYP = 1 Q = 3.37600E-01 MeV frac = 6.69315E-01 Product nuclide = 511262 : beta- + + Nuclide 151 / 1657 : 51121.82c -- antimony 121 (Sb-121) + + Pointers : 1263591 32207 + Primary type : Transport + Nuclide ZAI : 511210 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Sb121.ACE + Atomic weight (AW) : 120.90363 + Atomic weight ratio (AWR) : 119.86500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 24 reaction channels + - 6 special reactions + - 9 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 24 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -9.24758E+00 MeV Emin = 9.32474E+00 MeV frac = 1.00000E+00 Product nuclide = 511200 : (n,2n) + 3 MT = 17 Q = -1.62503E+01 MeV Emin = 1.63859E+01 MeV frac = 1.00000E+00 Product nuclide = 511190 : (n,3n) + 4 MT = 22 Q = -3.08584E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 491170 : (n,nalpha) + 5 MT = 28 Q = -5.78481E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 50120.82c : (n,np) + 6 MT = 51 Q = -3.70999E-02 MeV Emin = 3.55500E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -5.07599E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -5.73099E-01 MeV Emin = 5.61369E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -9.46999E-01 MeV Emin = 9.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -1.02400E+00 MeV Emin = 1.01625E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -1.03540E+00 MeV Emin = 1.03829E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -1.13930E+00 MeV Emin = 1.12427E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -1.14470E+00 MeV Emin = 1.15150E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -1.38620E+00 MeV Emin = 1.36082E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -1.40750E+00 MeV Emin = 1.40850E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -1.41050E+00 MeV Emin = 1.42076E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -1.42720E+00 MeV Emin = 1.43068E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -1.44800E+00 MeV Emin = 1.44959E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 91 Q = -1.44900E+00 MeV Emin = 1.46084E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 20 MT = 102 Q = 6.80643E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 511220 : (n,gamma) + 21 MT = 103 Q = 3.95269E-01 MeV Emin = 4.50000E-01 MeV frac = 1.00000E+00 Product nuclide = 501210 : (n,p) + 22 MT = 104 Q = -3.56020E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 50120.82c : (n,d) + 23 MT = 105 Q = -6.39616E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 50119.82c : (n,t) + 24 MT = 107 Q = 3.50684E+00 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 491180 : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -3.08584E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -5.78481E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 102 Q = 6.80643E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 511221 : (n,gamma) + 4 MT = 103 Q = 3.95269E-01 MeV Emin = 4.50000E-01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -3.56020E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -6.39616E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 107 Q = 3.50684E+00 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.50000E-01 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 4.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 8.00000E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 5.00000E-01 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 3.55500E-02 MeV : total inelastic scattering + + Nuclide 152 / 1657 : 51123.82c -- antimony 123 (Sb-123) + + Pointers : 1267545 32253 + Primary type : Transport + Nuclide ZAI : 511230 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Sb123.ACE + Atomic weight (AW) : 122.90381 + Atomic weight ratio (AWR) : 121.84800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 19 reaction channels + - 6 special reactions + - 9 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 19 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.96518E+00 MeV Emin = 9.03877E+00 MeV frac = 1.00000E+00 Product nuclide = 511220 : (n,2n) + 3 MT = 17 Q = -1.57726E+01 MeV Emin = 1.59020E+01 MeV frac = 1.00000E+00 Product nuclide = 51121.82c : (n,3n) + 4 MT = 22 Q = -3.93003E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 491190 : (n,nalpha) + 5 MT = 28 Q = -6.57271E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 50122.82c : (n,np) + 6 MT = 51 Q = -1.60300E-01 MeV Emin = 1.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -5.41799E-01 MeV Emin = 5.44833E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -7.12799E-01 MeV Emin = 7.12500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -1.03020E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -1.08860E+00 MeV Emin = 1.08280E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -1.18130E+00 MeV Emin = 1.18968E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -1.26090E+00 MeV Emin = 1.25000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -1.33740E+00 MeV Emin = 1.33151E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 91 Q = -1.33800E+00 MeV Emin = 1.34869E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 15 MT = 102 Q = 6.46843E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 51124.82c : (n,gamma) + 16 MT = 103 Q = -6.27629E-01 MeV Emin = 1.46460E+00 MeV frac = 1.00000E+00 Product nuclide = 50123.82c : (n,p) + 17 MT = 104 Q = -4.34810E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 50122.82c : (n,d) + 18 MT = 105 Q = -6.89017E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 501210 : (n,t) + 19 MT = 107 Q = 1.91765E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 491200 : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = -3.93003E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -6.57271E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -6.27629E-01 MeV Emin = 1.46460E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -4.34810E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -6.89017E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 107 Q = 1.91765E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.46460E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.00000E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 1.50000E-01 MeV : total inelastic scattering + + Nuclide 153 / 1657 : 51124.82c -- antimony 124 (Sb-124) + + Pointers : 1269919 32299 + Primary type : Transport + Nuclide ZAI : 511240 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Sb124.ACE + Atomic weight (AW) : 123.90642 + Atomic weight ratio (AWR) : 122.84200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 5.20E+06 seconds (60.2 days) + Specific ingestion toxicity : 2.50E-09 Sv/Bq + Specific inhalation toxicity : 8.60E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 16 reaction channels + - 6 special reactions + - 6 transmutation reactions + - 5 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 16 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -1.07000E-02 MeV Emin = 1.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -3.50000E-02 MeV Emin = 3.31803E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -4.08000E-02 MeV Emin = 3.82085E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -7.71000E-02 MeV Emin = 7.42620E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -8.07000E-02 MeV Emin = 8.03742E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -8.76000E-02 MeV Emin = 8.56667E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 57 Q = -1.04000E-01 MeV Emin = 1.04134E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 9 MT = 58 Q = -1.32000E-01 MeV Emin = 1.24802E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 10 MT = 91 Q = -1.40860E-01 MeV Emin = 1.37537E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 11 MT = 102 Q = 8.77000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 51125.82c : (n,gamma) + 12 MT = 103 Q = 1.40880E+00 MeV Emin = 4.55661E-02 MeV frac = 1.00000E+00 Product nuclide = 50124.82c : (n,p) + 13 MT = 104 Q = -4.85490E+00 MeV Emin = 4.89442E+00 MeV frac = 1.00000E+00 Product nuclide = 50123.82c : (n,d) + 14 MT = 105 Q = -4.54380E+00 MeV Emin = 4.58079E+00 MeV frac = 1.00000E+00 Product nuclide = 50122.82c : (n,t) + 15 MT = 107 Q = 3.87380E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 491210 : (n,alpha) + 16 MT = 111 Q = -1.06760E+01 MeV Emin = 1.07629E+01 MeV frac = 1.00000E+00 Product nuclide = 491230 : (n,2p) + + 5 additional transport branches: + + 1 MT = 103 Q = 1.40880E+00 MeV Emin = 4.55661E-02 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -4.85490E+00 MeV Emin = 4.89442E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -4.54380E+00 MeV Emin = 4.58079E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 107 Q = 3.87380E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 5 MT = 111 Q = -1.06760E+01 MeV Emin = 1.07629E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.55661E-02 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 4.89442E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 4.58079E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 1.00000E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.90430E+00 MeV frac = 1.00000E+00 Product nuclide = 52124.82c : beta- + + Nuclide 154 / 1657 : 51125.82c -- antimony 125 (Sb-125) + + Pointers : 1276247 32345 + Primary type : Transport + Nuclide ZAI : 511250 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Sb125.ACE + Atomic weight (AW) : 124.90500 + Atomic weight ratio (AWR) : 123.83200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 8.71E+07 seconds (2.76 years) + Specific ingestion toxicity : 1.10E-09 Sv/Bq + Specific inhalation toxicity : 1.20E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 28 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 6 transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 28 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -3.31900E-01 MeV Emin = 3.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -6.43000E-01 MeV Emin = 5.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -9.21600E-01 MeV Emin = 8.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -1.06660E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -1.08890E+00 MeV Emin = 1.08926E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -1.34920E+00 MeV Emin = 1.30000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 57 Q = -1.41950E+00 MeV Emin = 1.40475E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 9 MT = 58 Q = -1.48390E+00 MeV Emin = 1.47458E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 10 MT = 59 Q = -1.56000E+00 MeV Emin = 1.54441E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 11 MT = 60 Q = -1.59100E+00 MeV Emin = 1.60000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 12 MT = 61 Q = -1.66000E+00 MeV Emin = 1.64048E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 13 MT = 62 Q = -1.70080E+00 MeV Emin = 1.69395E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 14 MT = 63 Q = -1.73600E+00 MeV Emin = 1.73227E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 15 MT = 64 Q = -1.80570E+00 MeV Emin = 1.81450E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 16 MT = 65 Q = -1.80571E+00 MeV Emin = 1.81450E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 17 MT = 66 Q = -1.88990E+00 MeV Emin = 1.89165E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 18 MT = 67 Q = -1.91350E+00 MeV Emin = 1.92732E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 19 MT = 68 Q = -1.94730E+00 MeV Emin = 1.94516E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 20 MT = 69 Q = -1.98210E+00 MeV Emin = 1.98056E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 21 MT = 91 Q = -1.98211E+00 MeV Emin = 1.99953E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 22 MT = 102 Q = 6.19000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 51126.82c : (n,gamma) + 23 MT = 103 Q = -1.56680E+00 MeV Emin = 1.54441E+00 MeV frac = 1.00000E+00 Product nuclide = 50125.82c : (n,p) + 24 MT = 104 Q = -5.07450E+00 MeV Emin = 5.11548E+00 MeV frac = 1.00000E+00 Product nuclide = 50124.82c : (n,d) + 25 MT = 105 Q = -7.30650E+00 MeV Emin = 7.36550E+00 MeV frac = 1.00000E+00 Product nuclide = 50123.82c : (n,t) + 26 MT = 106 Q = -1.16680E+01 MeV Emin = 1.17622E+01 MeV frac = 1.00000E+00 Product nuclide = 491230 : (n,He-3) + 27 MT = 107 Q = 9.94120E-01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 491220 : (n,alpha) + 28 MT = 111 Q = -1.36540E+01 MeV Emin = 1.37643E+01 MeV frac = 1.00000E+00 Product nuclide = 491240 : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = -1.56680E+00 MeV Emin = 1.54441E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -5.07450E+00 MeV Emin = 5.11548E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -7.30650E+00 MeV Emin = 7.36550E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -1.16680E+01 MeV Emin = 1.17622E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 9.94120E-01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -1.36540E+01 MeV Emin = 1.37643E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.54441E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.11548E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 7.36550E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.17622E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 3.00000E-01 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 1 Q = 7.66700E-01 MeV frac = 7.69044E-01 Product nuclide = 52125.82c : beta- + 2 RTYP = 1 Q = 6.21869E-01 MeV frac = 2.30956E-01 Product nuclide = 521251 : beta- + + Nuclide 155 / 1657 : 51126.82c -- antimony 126 (Sb-126) + + Pointers : 1281112 32391 + Primary type : Transport + Nuclide ZAI : 511260 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Sb126.ACE + Atomic weight (AW) : 125.90761 + Atomic weight ratio (AWR) : 124.82600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.07E+06 seconds (12.4 days) + Specific ingestion toxicity : 2.40E-09 Sv/Bq + Specific inhalation toxicity : 3.20E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 14 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 6 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 14 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -1.77000E-02 MeV Emin = 1.68617E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -8.31000E-02 MeV Emin = 7.95452E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -1.05000E-01 MeV Emin = 1.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -1.05001E-01 MeV Emin = 1.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -3.67050E-01 MeV Emin = 3.54692E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 91 Q = -1.98400E-01 MeV Emin = 1.84500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 8 MT = 102 Q = 8.31000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 511270 : (n,gamma) + 9 MT = 103 Q = 4.04520E-01 MeV Emin = 4.76810E-02 MeV frac = 1.00000E+00 Product nuclide = 50126.82c : (n,p) + 10 MT = 104 Q = -5.56230E+00 MeV Emin = 5.60686E+00 MeV frac = 1.00000E+00 Product nuclide = 50125.82c : (n,d) + 11 MT = 105 Q = -5.03830E+00 MeV Emin = 5.07866E+00 MeV frac = 1.00000E+00 Product nuclide = 50124.82c : (n,t) + 12 MT = 106 Q = -1.21580E+01 MeV Emin = 1.22554E+01 MeV frac = 1.00000E+00 Product nuclide = 491240 : (n,He-3) + 13 MT = 107 Q = 2.68350E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 491230 : (n,alpha) + 14 MT = 111 Q = -1.24040E+01 MeV Emin = 1.25034E+01 MeV frac = 1.00000E+00 Product nuclide = 491250 : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = 4.04520E-01 MeV Emin = 4.76810E-02 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -5.56230E+00 MeV Emin = 5.60686E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -5.03830E+00 MeV Emin = 5.07866E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -1.21580E+01 MeV Emin = 1.22554E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 2.68350E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -1.24040E+01 MeV Emin = 1.25034E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.76810E-02 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.60686E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 5.07866E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.22554E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 1.68617E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.67200E+00 MeV frac = 1.00000E+00 Product nuclide = 52126.82c : beta- + + Nuclide 156 / 1657 : 52120.82c -- tellurium 120 (Te-120) + + Pointers : 1305439 34461 + Primary type : Transport + Nuclide ZAI : 521200 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Te120.ACE + Atomic weight (AW) : 119.90000 + Atomic weight ratio (AWR) : 118.87000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 9 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 9 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 91 Q = -4.96000E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 3 MT = 102 Q = 7.17600E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 521210 : (n,gamma) + 4 MT = 103 Q = -2.00270E-01 MeV Emin = 2.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 511200 : (n,p) + 5 MT = 104 Q = -4.98350E+00 MeV Emin = 5.02543E+00 MeV frac = 1.00000E+00 Product nuclide = 511190 : (n,d) + 6 MT = 105 Q = -8.31210E+00 MeV Emin = 8.38203E+00 MeV frac = 1.00000E+00 Product nuclide = 511180 : (n,t) + 7 MT = 106 Q = -4.60870E+00 MeV Emin = 4.64747E+00 MeV frac = 1.00000E+00 Product nuclide = 50118.82c : (n,He-3) + 8 MT = 107 Q = 6.63910E+00 MeV Emin = 4.51500E-02 MeV frac = 1.00000E+00 Product nuclide = 50117.82c : (n,alpha) + 9 MT = 111 Q = -5.84170E+00 MeV Emin = 5.89084E+00 MeV frac = 1.00000E+00 Product nuclide = 50119.82c : (n,2p) + + 7 additional transport branches: + + 1 MT = 102 Q = 7.17600E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 521211 : (n,gamma) + 2 MT = 103 Q = -2.00270E-01 MeV Emin = 2.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 104 Q = -4.98350E+00 MeV Emin = 5.02543E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 4 MT = 105 Q = -8.31210E+00 MeV Emin = 8.38203E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 5 MT = 106 Q = -4.60870E+00 MeV Emin = 4.64747E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 6 MT = 107 Q = 6.63910E+00 MeV Emin = 4.51500E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 7 MT = 111 Q = -5.84170E+00 MeV Emin = 5.89084E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.00000E-01 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.02543E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 8.38203E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 4.64747E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.51500E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 5.00000E-01 MeV : total inelastic scattering + + Nuclide 157 / 1657 : 52122.82c -- tellurium 122 (Te-122) + + Pointers : 1309099 34507 + Primary type : Transport + Nuclide ZAI : 521220 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Te122.ACE + Atomic weight (AW) : 121.90321 + Atomic weight ratio (AWR) : 120.85600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 13 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 13 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -5.64000E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -1.17000E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -1.25000E+00 MeV Emin = 1.23391E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -1.35000E+00 MeV Emin = 1.36000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 91 Q = -1.98350E+00 MeV Emin = 1.90000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 7 MT = 102 Q = 6.92990E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 52123.82c : (n,gamma) + 8 MT = 103 Q = -1.19760E+00 MeV Emin = 1.20733E+00 MeV frac = 1.00000E+00 Product nuclide = 511220 : (n,p) + 9 MT = 104 Q = -5.77790E+00 MeV Emin = 5.82571E+00 MeV frac = 1.00000E+00 Product nuclide = 51121.82c : (n,d) + 10 MT = 105 Q = -8.75800E+00 MeV Emin = 8.83047E+00 MeV frac = 1.00000E+00 Product nuclide = 511200 : (n,t) + 11 MT = 106 Q = -6.06000E+00 MeV Emin = 6.11014E+00 MeV frac = 1.00000E+00 Product nuclide = 50120.82c : (n,He-3) + 12 MT = 107 Q = 5.40730E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 50119.82c : (n,alpha) + 13 MT = 111 Q = -7.60600E+00 MeV Emin = 7.66894E+00 MeV frac = 1.00000E+00 Product nuclide = 501210 : (n,2p) + + 7 additional transport branches: + + 1 MT = 102 Q = 6.92990E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 521231 : (n,gamma) + 2 MT = 103 Q = -1.19760E+00 MeV Emin = 1.20733E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 104 Q = -5.77790E+00 MeV Emin = 5.82571E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 4 MT = 105 Q = -8.75800E+00 MeV Emin = 8.83047E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 5 MT = 106 Q = -6.06000E+00 MeV Emin = 6.11014E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 6 MT = 107 Q = 5.40730E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 7 MT = 111 Q = -7.60600E+00 MeV Emin = 7.66894E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.20733E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.82571E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 8.83047E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 6.11014E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.62500E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 5.00000E-01 MeV : total inelastic scattering + + Nuclide 158 / 1657 : 52123.82c -- tellurium 123 (Te-123) + + Pointers : 1311200 34553 + Primary type : Transport + Nuclide ZAI : 521230 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Te123.ACE + Atomic weight (AW) : 122.90482 + Atomic weight ratio (AWR) : 121.84900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.90E+24 seconds (9.21E+16 years) + Specific ingestion toxicity : 4.40E-09 Sv/Bq + Specific inhalation toxicity : 3.90E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 17 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 6 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 17 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -1.59000E-01 MeV Emin = 1.52762E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -2.48000E-01 MeV Emin = 2.43510E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -4.40000E-01 MeV Emin = 4.06805E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -5.10000E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -6.90000E-01 MeV Emin = 6.50293E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -7.00000E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 57 Q = -7.80000E-01 MeV Emin = 7.46073E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 9 MT = 58 Q = -8.90000E-01 MeV Emin = 8.41851E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 10 MT = 91 Q = -8.92680E-01 MeV Emin = 8.98652E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 11 MT = 102 Q = 9.42380E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 52124.82c : (n,gamma) + 12 MT = 103 Q = 8.34390E-01 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 51123.82c : (n,p) + 13 MT = 104 Q = -5.90440E+00 MeV Emin = 5.95286E+00 MeV frac = 1.00000E+00 Product nuclide = 511220 : (n,d) + 14 MT = 105 Q = -6.45290E+00 MeV Emin = 6.50586E+00 MeV frac = 1.00000E+00 Product nuclide = 51121.82c : (n,t) + 15 MT = 106 Q = -6.82120E+00 MeV Emin = 6.87718E+00 MeV frac = 1.00000E+00 Product nuclide = 501210 : (n,He-3) + 16 MT = 107 Q = 7.58020E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 50120.82c : (n,alpha) + 17 MT = 111 Q = -5.72390E+00 MeV Emin = 5.77088E+00 MeV frac = 1.00000E+00 Product nuclide = 50122.82c : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = 8.34390E-01 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -5.90440E+00 MeV Emin = 5.95286E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -6.45290E+00 MeV Emin = 6.50586E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -6.82120E+00 MeV Emin = 6.87718E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 7.58020E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -5.72390E+00 MeV Emin = 5.77088E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.62500E-02 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.95286E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 6.50586E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 6.87718E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.62500E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 1.52762E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 2 Q = 5.22000E-02 MeV frac = 1.00000E+00 Product nuclide = 51123.82c : EC/beta+ + + Nuclide 159 / 1657 : 52124.82c -- tellurium 124 (Te-124) + + Pointers : 1314202 34599 + Primary type : Transport + Nuclide ZAI : 521240 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Te124.ACE + Atomic weight (AW) : 123.90340 + Atomic weight ratio (AWR) : 122.83900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 20 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 20 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -6.03000E-01 MeV Emin = 5.53955E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -1.16000E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -1.25000E+00 MeV Emin = 1.25512E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -1.33000E+00 MeV Emin = 1.29796E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -1.66000E+00 MeV Emin = 1.60000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -1.75000E+00 MeV Emin = 1.71886E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 57 Q = -1.88000E+00 MeV Emin = 1.82977E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 9 MT = 58 Q = -1.96000E+00 MeV Emin = 1.94765E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 10 MT = 59 Q = -2.02000E+00 MeV Emin = 2.03645E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 11 MT = 60 Q = -2.04000E+00 MeV Emin = 2.05661E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 12 MT = 61 Q = -2.09000E+00 MeV Emin = 2.10702E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 13 MT = 91 Q = -2.08310E+00 MeV Emin = 2.10006E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 14 MT = 102 Q = 6.58490E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 52125.82c : (n,gamma) + 15 MT = 103 Q = -2.12160E+00 MeV Emin = 2.13887E+00 MeV frac = 1.00000E+00 Product nuclide = 51124.82c : (n,p) + 16 MT = 104 Q = -6.36280E+00 MeV Emin = 6.41460E+00 MeV frac = 1.00000E+00 Product nuclide = 51123.82c : (n,d) + 17 MT = 105 Q = -9.06990E+00 MeV Emin = 9.14374E+00 MeV frac = 1.00000E+00 Product nuclide = 511220 : (n,t) + 18 MT = 106 Q = -7.42970E+00 MeV Emin = 7.49018E+00 MeV frac = 1.00000E+00 Product nuclide = 50122.82c : (n,He-3) + 19 MT = 107 Q = 4.32850E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 501210 : (n,alpha) + 20 MT = 111 Q = -9.20050E+00 MeV Emin = 9.27540E+00 MeV frac = 1.00000E+00 Product nuclide = 50123.82c : (n,2p) + + 7 additional transport branches: + + 1 MT = 102 Q = 6.58490E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 521251 : (n,gamma) + 2 MT = 103 Q = -2.12160E+00 MeV Emin = 2.13887E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 104 Q = -6.36280E+00 MeV Emin = 6.41460E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 4 MT = 105 Q = -9.06990E+00 MeV Emin = 9.14374E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 5 MT = 106 Q = -7.42970E+00 MeV Emin = 7.49018E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 6 MT = 107 Q = 4.32850E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 7 MT = 111 Q = -9.20050E+00 MeV Emin = 9.27540E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.13887E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.41460E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.14374E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 7.49018E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.62500E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 5.53955E-01 MeV : total inelastic scattering + + Nuclide 160 / 1657 : 52125.82c -- tellurium 125 (Te-125) + + Pointers : 1316814 34645 + Primary type : Transport + Nuclide ZAI : 521250 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Te125.ACE + Atomic weight (AW) : 124.90399 + Atomic weight ratio (AWR) : 123.83100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 15 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 15 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -3.55000E-02 MeV Emin = 3.38136E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -1.98400E-01 MeV Emin = 1.86542E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -3.21000E-01 MeV Emin = 2.92693E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -4.43000E-01 MeV Emin = 4.42555E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -4.63000E-01 MeV Emin = 4.54647E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -5.25000E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 91 Q = -6.94390E-01 MeV Emin = 6.58750E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 9 MT = 102 Q = 9.10930E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 52126.82c : (n,gamma) + 10 MT = 103 Q = 1.56250E-02 MeV Emin = 4.64468E-02 MeV frac = 1.00000E+00 Product nuclide = 51125.82c : (n,p) + 11 MT = 104 Q = -6.46770E+00 MeV Emin = 6.51993E+00 MeV frac = 1.00000E+00 Product nuclide = 51124.82c : (n,d) + 12 MT = 105 Q = -6.67730E+00 MeV Emin = 6.73122E+00 MeV frac = 1.00000E+00 Product nuclide = 51123.82c : (n,t) + 13 MT = 106 Q = -8.05520E+00 MeV Emin = 8.12025E+00 MeV frac = 1.00000E+00 Product nuclide = 50123.82c : (n,He-3) + 14 MT = 107 Q = 6.57120E+00 MeV Emin = 4.64468E-02 MeV frac = 1.00000E+00 Product nuclide = 50122.82c : (n,alpha) + 15 MT = 111 Q = -7.28290E+00 MeV Emin = 7.34171E+00 MeV frac = 1.00000E+00 Product nuclide = 50124.82c : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = 1.56250E-02 MeV Emin = 4.64468E-02 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -6.46770E+00 MeV Emin = 6.51993E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -6.67730E+00 MeV Emin = 6.73122E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -8.05520E+00 MeV Emin = 8.12025E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 6.57120E+00 MeV Emin = 4.64468E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -7.28290E+00 MeV Emin = 7.34171E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.64468E-02 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.51993E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 6.73122E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 8.12025E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.64468E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 3.38136E-02 MeV : total inelastic scattering + + Nuclide 161 / 1657 : 52126.82c -- tellurium 126 (Te-126) + + Pointers : 1319382 34691 + Primary type : Transport + Nuclide ZAI : 521260 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Te126.ACE + Atomic weight (AW) : 125.90358 + Atomic weight ratio (AWR) : 124.82200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 22 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 22 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -6.66000E-01 MeV Emin = 5.85670E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -1.36000E+00 MeV Emin = 1.20560E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -1.40000E+00 MeV Emin = 1.20560E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -1.42000E+00 MeV Emin = 1.42231E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -1.68000E+00 MeV Emin = 1.60000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -1.78000E+00 MeV Emin = 1.74572E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 57 Q = -1.78001E+00 MeV Emin = 1.74572E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 9 MT = 58 Q = -1.88000E+00 MeV Emin = 1.84573E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 10 MT = 59 Q = -2.01000E+00 MeV Emin = 2.02610E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 11 MT = 60 Q = -2.04000E+00 MeV Emin = 2.05634E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 12 MT = 61 Q = -2.05000E+00 MeV Emin = 2.06642E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 13 MT = 62 Q = -2.06000E+00 MeV Emin = 2.07651E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 14 MT = 63 Q = -2.08000E+00 MeV Emin = 2.09670E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 15 MT = 91 Q = -2.07340E+00 MeV Emin = 2.09001E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 16 MT = 102 Q = 6.28900E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 521270 : (n,gamma) + 17 MT = 103 Q = -2.88030E+00 MeV Emin = 2.90338E+00 MeV frac = 1.00000E+00 Product nuclide = 51126.82c : (n,p) + 18 MT = 104 Q = -6.87580E+00 MeV Emin = 6.93089E+00 MeV frac = 1.00000E+00 Product nuclide = 51125.82c : (n,d) + 19 MT = 105 Q = -9.32740E+00 MeV Emin = 9.40213E+00 MeV frac = 1.00000E+00 Product nuclide = 51124.82c : (n,t) + 20 MT = 106 Q = -8.68290E+00 MeV Emin = 8.75246E+00 MeV frac = 1.00000E+00 Product nuclide = 50124.82c : (n,He-3) + 21 MT = 107 Q = 3.40030E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 50123.82c : (n,alpha) + 22 MT = 111 Q = -1.06670E+01 MeV Emin = 1.07525E+01 MeV frac = 1.00000E+00 Product nuclide = 50125.82c : (n,2p) + + 7 additional transport branches: + + 1 MT = 102 Q = 6.28900E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 52527.82c : (n,gamma) + 2 MT = 103 Q = -2.88030E+00 MeV Emin = 2.90338E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 104 Q = -6.87580E+00 MeV Emin = 6.93089E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 4 MT = 105 Q = -9.32740E+00 MeV Emin = 9.40213E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 5 MT = 106 Q = -8.68290E+00 MeV Emin = 8.75246E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 6 MT = 107 Q = 3.40030E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 7 MT = 111 Q = -1.06670E+01 MeV Emin = 1.07525E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.90338E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.93089E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.40213E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 8.75246E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 5.85670E-01 MeV : total inelastic scattering + + Nuclide 162 / 1657 : 52527.82c -- tellurium 127m (Te-127m) + + Pointers : 1323141 34737 + Primary type : Transport + Nuclide ZAI : 521271 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Te127M.ACE + Atomic weight (AW) : 126.90518 + Atomic weight ratio (AWR) : 125.81500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 9.17E+06 seconds (106 days) + Specific ingestion toxicity : 2.30E-09 Sv/Bq + Specific inhalation toxicity : 9.80E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 3 reaction channels + - 2 special reactions + - 1 transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 91 Q = -6.94510E-01 MeV Emin = 6.58750E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 3 MT = 102 Q = 8.68000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 52128.82c : (n,gamma) + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 6.58750E-01 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 3 Q = 8.82300E-02 MeV frac = 9.72700E-01 Product nuclide = 521270 : IT + 2 RTYP = 1 Q = 7.90030E-01 MeV frac = 2.73000E-02 Product nuclide = 53127.82c : beta- + + Nuclide 163 / 1657 : 52128.82c -- tellurium 128 (Te-128) + + Pointers : 1324440 34783 + Primary type : Transport + Nuclide ZAI : 521280 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Te128.ACE + Atomic weight (AW) : 127.90477 + Atomic weight ratio (AWR) : 126.80600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 6.94E+31 seconds (2.2E+24 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 18 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 7 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 18 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -7.43200E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -1.49710E+00 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -1.52320E+00 MeV Emin = 1.52206E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -1.81110E+00 MeV Emin = 1.78769E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -1.97220E+00 MeV Emin = 1.94716E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -1.98220E+00 MeV Emin = 1.99279E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 57 Q = -2.03000E+00 MeV Emin = 2.04601E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 9 MT = 58 Q = -2.13200E+00 MeV Emin = 2.14881E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 10 MT = 59 Q = -2.13350E+00 MeV Emin = 2.15033E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 11 MT = 91 Q = -2.19700E+00 MeV Emin = 2.21433E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 12 MT = 102 Q = 6.08600E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 521290 : (n,gamma) + 13 MT = 103 Q = -3.47850E+00 MeV Emin = 3.50593E+00 MeV frac = 1.00000E+00 Product nuclide = 511280 : (n,p) + 14 MT = 104 Q = -7.35010E+00 MeV Emin = 7.40806E+00 MeV frac = 1.00000E+00 Product nuclide = 511270 : (n,d) + 15 MT = 105 Q = -9.46510E+00 MeV Emin = 9.53974E+00 MeV frac = 1.00000E+00 Product nuclide = 51126.82c : (n,t) + 16 MT = 106 Q = -9.82480E+00 MeV Emin = 9.90228E+00 MeV frac = 1.00000E+00 Product nuclide = 50126.82c : (n,He-3) + 17 MT = 107 Q = 2.55530E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 50125.82c : (n,alpha) + 18 MT = 111 Q = -1.18950E+01 MeV Emin = 1.19888E+01 MeV frac = 1.00000E+00 Product nuclide = 501270 : (n,2p) + + 7 additional transport branches: + + 1 MT = 102 Q = 6.08600E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 52529.82c : (n,gamma) + 2 MT = 103 Q = -3.47850E+00 MeV Emin = 3.50593E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 104 Q = -7.35010E+00 MeV Emin = 7.40806E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 4 MT = 105 Q = -9.46510E+00 MeV Emin = 9.53974E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 5 MT = 106 Q = -9.82480E+00 MeV Emin = 9.90228E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 6 MT = 107 Q = 2.55530E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 7 MT = 111 Q = -1.18950E+01 MeV Emin = 1.19888E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.50593E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.40806E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.53974E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 9.90228E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 7.00000E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 11 Q = 8.66500E-01 MeV frac = 1.00000E+00 Product nuclide = 54128.82c : beta- + beta- + + Nuclide 164 / 1657 : 52529.82c -- tellurium 129m (Te-129m) + + Pointers : 1328820 34829 + Primary type : Transport + Nuclide ZAI : 521291 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Te129M.ACE + Atomic weight (AW) : 128.90738 + Atomic weight ratio (AWR) : 127.80000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.90E+06 seconds (33.6 days) + Specific ingestion toxicity : 3.00E-09 Sv/Bq + Specific inhalation toxicity : 7.90E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 9 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 6 transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 9 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 91 Q = -9.92260E-01 MeV Emin = 9.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 3 MT = 102 Q = 8.41000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 52130.82c : (n,gamma) + 4 MT = 103 Q = -1.69880E+00 MeV Emin = 1.65599E+00 MeV frac = 1.00000E+00 Product nuclide = 511290 : (n,p) + 5 MT = 104 Q = -7.44370E+00 MeV Emin = 7.50195E+00 MeV frac = 1.00000E+00 Product nuclide = 511280 : (n,d) + 6 MT = 105 Q = -7.28360E+00 MeV Emin = 7.34059E+00 MeV frac = 1.00000E+00 Product nuclide = 511270 : (n,t) + 7 MT = 106 Q = -1.03680E+01 MeV Emin = 1.04491E+01 MeV frac = 1.00000E+00 Product nuclide = 501270 : (n,He-3) + 8 MT = 107 Q = 4.55690E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 50126.82c : (n,alpha) + 9 MT = 111 Q = -1.01750E+01 MeV Emin = 1.02546E+01 MeV frac = 1.00000E+00 Product nuclide = 501280 : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = -1.69880E+00 MeV Emin = 1.65599E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -7.44370E+00 MeV Emin = 7.50195E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -7.28360E+00 MeV Emin = 7.34059E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -1.03680E+01 MeV Emin = 1.04491E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 4.55690E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -1.01750E+01 MeV Emin = 1.02546E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.65599E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.50195E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 7.34059E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.04491E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.62500E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 9.25000E-01 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.60340E+00 MeV frac = 3.70000E-01 Product nuclide = 53129.82c : beta- + 2 RTYP = 3 Q = 1.05500E-01 MeV frac = 6.30000E-01 Product nuclide = 521290 : IT + + Nuclide 165 / 1657 : 52130.82c -- tellurium 130 (Te-130) + + Pointers : 1332186 34875 + Primary type : Transport + Nuclide ZAI : 521300 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Te130.ACE + Atomic weight (AW) : 129.90596 + Atomic weight ratio (AWR) : 128.79000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.49E+28 seconds (7.91E+20 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 19 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 7 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 19 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -8.40000E-01 MeV Emin = 8.09890E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -1.60000E+00 MeV Emin = 1.60000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -1.63000E+00 MeV Emin = 1.63636E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -1.81000E+00 MeV Emin = 1.80391E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -1.88000E+00 MeV Emin = 1.85178E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -1.97000E+00 MeV Emin = 1.94753E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 57 Q = -1.98000E+00 MeV Emin = 1.94753E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 9 MT = 58 Q = -2.10000E+00 MeV Emin = 2.11631E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 10 MT = 59 Q = -2.19000E+00 MeV Emin = 2.20701E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 11 MT = 60 Q = -2.19001E+00 MeV Emin = 2.20702E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 12 MT = 91 Q = -2.18310E+00 MeV Emin = 2.20005E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 13 MT = 102 Q = 5.92700E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 521310 : (n,gamma) + 14 MT = 103 Q = -4.18400E+00 MeV Emin = 4.21649E+00 MeV frac = 1.00000E+00 Product nuclide = 511300 : (n,p) + 15 MT = 104 Q = -7.77960E+00 MeV Emin = 7.84001E+00 MeV frac = 1.00000E+00 Product nuclide = 511290 : (n,d) + 16 MT = 105 Q = -9.49280E+00 MeV Emin = 9.56651E+00 MeV frac = 1.00000E+00 Product nuclide = 511280 : (n,t) + 17 MT = 106 Q = -1.07640E+01 MeV Emin = 1.08476E+01 MeV frac = 1.00000E+00 Product nuclide = 501280 : (n,He-3) + 18 MT = 107 Q = 1.89780E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 501270 : (n,alpha) + 19 MT = 111 Q = -1.32100E+01 MeV Emin = 1.33126E+01 MeV frac = 1.00000E+00 Product nuclide = 501290 : (n,2p) + + 7 additional transport branches: + + 1 MT = 102 Q = 5.92700E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 521311 : (n,gamma) + 2 MT = 103 Q = -4.18400E+00 MeV Emin = 4.21649E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 104 Q = -7.77960E+00 MeV Emin = 7.84001E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 4 MT = 105 Q = -9.49280E+00 MeV Emin = 9.56651E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 5 MT = 106 Q = -1.07640E+01 MeV Emin = 1.08476E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 6 MT = 107 Q = 1.89780E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 7 MT = 111 Q = -1.32100E+01 MeV Emin = 1.33126E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.21649E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.84001E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.56651E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.08476E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 8.09890E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 11 Q = 2.52751E+00 MeV frac = 1.00000E+00 Product nuclide = 54130.82c : beta- + beta- + + Nuclide 166 / 1657 : 52132.82c -- tellurium 132 (Te-132) + + Pointers : 1338483 34921 + Primary type : Transport + Nuclide ZAI : 521320 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Te132.ACE + Atomic weight (AW) : 131.90816 + Atomic weight ratio (AWR) : 130.77500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.79E+05 seconds (3.23 days) + Specific ingestion toxicity : 3.80E-09 Sv/Bq + Specific inhalation toxicity : 2.00E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 15 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 7 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 15 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -9.75000E-01 MeV Emin = 9.11845E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -1.67000E+00 MeV Emin = 1.60000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -1.78000E+00 MeV Emin = 1.74520E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -1.98480E+00 MeV Emin = 1.89681E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -2.05000E+00 MeV Emin = 2.06570E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -2.11000E+00 MeV Emin = 2.12614E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 91 Q = -2.10390E+00 MeV Emin = 2.12000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 9 MT = 102 Q = 5.81000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 521330 : (n,gamma) + 10 MT = 103 Q = -4.81870E+00 MeV Emin = 4.85555E+00 MeV frac = 1.00000E+00 Product nuclide = 511320 : (n,p) + 11 MT = 104 Q = -8.17440E+00 MeV Emin = 8.23691E+00 MeV frac = 1.00000E+00 Product nuclide = 511310 : (n,d) + 12 MT = 105 Q = -9.70770E+00 MeV Emin = 9.78193E+00 MeV frac = 1.00000E+00 Product nuclide = 511300 : (n,t) + 13 MT = 106 Q = -1.16890E+01 MeV Emin = 1.17784E+01 MeV frac = 1.00000E+00 Product nuclide = 501300 : (n,He-3) + 14 MT = 107 Q = 1.07310E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 501290 : (n,alpha) + 15 MT = 111 Q = -1.42350E+01 MeV Emin = 1.43439E+01 MeV frac = 1.00000E+00 Product nuclide = 501310 : (n,2p) + + 7 additional transport branches: + + 1 MT = 102 Q = 5.81000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 521331 : (n,gamma) + 2 MT = 103 Q = -4.81870E+00 MeV Emin = 4.85555E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 104 Q = -8.17440E+00 MeV Emin = 8.23691E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 4 MT = 105 Q = -9.70770E+00 MeV Emin = 9.78193E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 5 MT = 106 Q = -1.16890E+01 MeV Emin = 1.17784E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 6 MT = 107 Q = 1.07310E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 7 MT = 111 Q = -1.42350E+01 MeV Emin = 1.43439E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.85555E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.23691E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.78193E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.17784E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 9.11845E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.18000E-01 MeV frac = 1.00000E+00 Product nuclide = 531320 : beta- + + Nuclide 167 / 1657 : 53127.82c -- iodine 127 (I-127) + + Pointers : 1354394 26411 + Primary type : Transport + Nuclide ZAI : 531270 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/I127.ACE + Atomic weight (AW) : 126.90448 + Atomic weight ratio (AWR) : 125.81430 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 3.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 43 reaction channels + - 92 special reactions + - 23 transmutation reactions + - 26 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 43 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 11 Q = -1.96711E+01 MeV Emin = 1.98275E+01 MeV frac = 1.00000E+00 Product nuclide = self : (n,2nd) + 3 MT = 16 Q = -9.14344E+00 MeV Emin = 9.21612E+00 MeV frac = 1.00000E+00 Product nuclide = 531260 : (n,2n) + 4 MT = 17 Q = -1.62877E+01 MeV Emin = 1.64172E+01 MeV frac = 1.00000E+00 Product nuclide = 531250 : (n,3n) + 5 MT = 22 Q = -2.18950E+00 MeV Emin = 2.20690E+00 MeV frac = 1.00000E+00 Product nuclide = 51123.82c : (n,nalpha) + 6 MT = 24 Q = -1.11548E+01 MeV Emin = 1.12435E+01 MeV frac = 1.00000E+00 Product nuclide = 511220 : (n,2nalpha) + 7 MT = 25 Q = -1.79617E+01 MeV Emin = 1.81045E+01 MeV frac = 1.00000E+00 Product nuclide = 51121.82c : (n,3nalpha) + 8 MT = 28 Q = -6.20576E+00 MeV Emin = 6.25509E+00 MeV frac = 1.00000E+00 Product nuclide = 52126.82c : (n,np) + 9 MT = 32 Q = -1.30950E+01 MeV Emin = 1.31991E+01 MeV frac = 1.00000E+00 Product nuclide = 52125.82c : (n,nd) + 10 MT = 33 Q = -1.34138E+01 MeV Emin = 1.35204E+01 MeV frac = 1.00000E+00 Product nuclide = 52124.82c : (n,nt) + 11 MT = 34 Q = -1.62997E+01 MeV Emin = 1.64293E+01 MeV frac = 1.00000E+00 Product nuclide = 51124.82c : (n,nHe-3) + 12 MT = 37 Q = -2.58376E+01 MeV Emin = 2.60430E+01 MeV frac = 1.00000E+00 Product nuclide = cut: I-124 : (n,4n) + 13 MT = 41 Q = -1.53196E+01 MeV Emin = 1.54414E+01 MeV frac = 1.00000E+00 Product nuclide = 52125.82c : (n,2np) + 14 MT = 42 Q = -2.18956E+01 MeV Emin = 2.20697E+01 MeV frac = 1.00000E+00 Product nuclide = cut: Te-124 : (n,3np) + 15 MT = 44 Q = -1.53039E+01 MeV Emin = 1.54256E+01 MeV frac = 1.00000E+00 Product nuclide = 51125.82c : (n,n2p) + 16 MT = 45 Q = -8.75604E+00 MeV Emin = 8.82564E+00 MeV frac = 1.00000E+00 Product nuclide = 50122.82c : (n,npalpha) + 17 MT = 51 Q = -5.76080E-02 MeV Emin = 5.78370E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 18 MT = 52 Q = -2.02860E-01 MeV Emin = 2.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 19 MT = 53 Q = -2.95000E-01 MeV Emin = 2.91725E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 20 MT = 54 Q = -3.74992E-01 MeV Emin = 3.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 21 MT = 55 Q = -4.17990E-01 MeV Emin = 4.10656E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 22 MT = 56 Q = -4.73000E-01 MeV Emin = 4.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 23 MT = 57 Q = -6.18310E-01 MeV Emin = 6.14357E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 24 MT = 58 Q = -6.28690E-01 MeV Emin = 6.28456E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 25 MT = 59 Q = -6.50920E-01 MeV Emin = 6.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 26 MT = 60 Q = -7.16500E-01 MeV Emin = 7.17365E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 27 MT = 61 Q = -7.44710E-01 MeV Emin = 7.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 28 MT = 62 Q = -8.31000E-01 MeV Emin = 8.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 29 MT = 63 Q = -8.83000E-01 MeV Emin = 8.89119E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 30 MT = 64 Q = -9.90940E-01 MeV Emin = 9.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 31 MT = 65 Q = -1.04410E+00 MeV Emin = 1.05000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 32 MT = 91 Q = -1.04410E+00 MeV Emin = 1.05000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 33 MT = 102 Q = 6.82614E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 531280 : (n,gamma) + 34 MT = 103 Q = 8.47855E-02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 521270 : (n,p) + 35 MT = 104 Q = -3.98118E+00 MeV Emin = 4.01283E+00 MeV frac = 1.00000E+00 Product nuclide = 52126.82c : (n,d) + 36 MT = 105 Q = -6.83776E+00 MeV Emin = 6.89211E+00 MeV frac = 1.00000E+00 Product nuclide = 52125.82c : (n,t) + 37 MT = 106 Q = -7.58587E+00 MeV Emin = 7.64617E+00 MeV frac = 1.00000E+00 Product nuclide = 51125.82c : (n,He-3) + 38 MT = 107 Q = 4.27795E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 51124.82c : (n,alpha) + 39 MT = 111 Q = -9.09592E+00 MeV Emin = 9.16822E+00 MeV frac = 1.00000E+00 Product nuclide = 51126.82c : (n,2p) + 40 MT = 112 Q = -2.81017E+00 MeV Emin = 2.83251E+00 MeV frac = 1.00000E+00 Product nuclide = 50123.82c : (n,palpha) + 41 MT = 115 Q = -1.30794E+01 MeV Emin = 1.31834E+01 MeV frac = 1.00000E+00 Product nuclide = 51125.82c : (n,pd) + 42 MT = 116 Q = -1.55359E+01 MeV Emin = 1.56594E+01 MeV frac = 1.00000E+00 Product nuclide = 51124.82c : (n,pt) + 43 MT = 117 Q = -6.53147E+00 MeV Emin = 6.58338E+00 MeV frac = 1.00000E+00 Product nuclide = 50122.82c : (n,dalpha) + + 26 additional transport branches: + + 1 MT = 22 Q = -2.18950E+00 MeV Emin = 2.20690E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 24 Q = -1.11548E+01 MeV Emin = 1.12435E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,2nalpha) + 3 MT = 25 Q = -1.79617E+01 MeV Emin = 1.81045E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,3nalpha) + 4 MT = 28 Q = -6.20576E+00 MeV Emin = 6.25509E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 5 MT = 32 Q = -1.30950E+01 MeV Emin = 1.31991E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 6 MT = 33 Q = -1.34138E+01 MeV Emin = 1.35204E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 7 MT = 34 Q = -1.62997E+01 MeV Emin = 1.64293E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,nHe-3) + 8 MT = 41 Q = -1.53196E+01 MeV Emin = 1.54414E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,2np) + 9 MT = 42 Q = -2.18956E+01 MeV Emin = 2.20697E+01 MeV frac = 1.00000E+00 Product nuclide = cut: H-1 : (n,3np) + 10 MT = 44 Q = -1.53039E+01 MeV Emin = 1.54256E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,n2p) + 11 MT = 45 Q = -8.75604E+00 MeV Emin = 8.82564E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,npalpha) + 12 MT = 45 Q = -8.75604E+00 MeV Emin = 8.82564E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,npalpha) + 13 MT = 103 Q = 8.47855E-02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 14 MT = 104 Q = -3.98118E+00 MeV Emin = 4.01283E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 15 MT = 105 Q = -6.83776E+00 MeV Emin = 6.89211E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 16 MT = 106 Q = -7.58587E+00 MeV Emin = 7.64617E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 17 MT = 107 Q = 4.27795E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 18 MT = 111 Q = -9.09592E+00 MeV Emin = 9.16822E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + 19 MT = 112 Q = -2.81017E+00 MeV Emin = 2.83251E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,palpha) + 20 MT = 112 Q = -2.81017E+00 MeV Emin = 2.83251E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,palpha) + 21 MT = 115 Q = -1.30794E+01 MeV Emin = 1.31834E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,pd) + 22 MT = 115 Q = -1.30794E+01 MeV Emin = 1.31834E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,pd) + 23 MT = 116 Q = -1.55359E+01 MeV Emin = 1.56594E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,pt) + 24 MT = 116 Q = -1.55359E+01 MeV Emin = 1.56594E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,pt) + 25 MT = 117 Q = -6.53147E+00 MeV Emin = 6.58338E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,dalpha) + 26 MT = 117 Q = -6.53147E+00 MeV Emin = 6.58338E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,dalpha) + + 92 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 4.01283E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 6.89211E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 7.64617E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 600 Q = 8.47855E-02 MeV Emin = 1.20000E+00 MeV : (n,p) to ground state + 8 MT = 601 Q = 2.36655E-02 MeV Emin = 1.20000E+00 MeV : (n,p1) + 9 MT = 602 Q = -3.47454E-03 MeV Emin = 1.20000E+00 MeV : (n,p2) + 10 MT = 603 Q = -2.55815E-01 MeV Emin = 1.40000E+00 MeV : (n,p3) + 11 MT = 604 Q = -2.81215E-01 MeV Emin = 1.50000E+00 MeV : (n,p4) + 12 MT = 605 Q = -3.88485E-01 MeV Emin = 1.60000E+00 MeV : (n,p5) + 13 MT = 606 Q = -4.18115E-01 MeV Emin = 1.60000E+00 MeV : (n,p6) + 14 MT = 607 Q = -5.18215E-01 MeV Emin = 1.70000E+00 MeV : (n,p7) + 15 MT = 608 Q = -5.46715E-01 MeV Emin = 1.80000E+00 MeV : (n,p8) + 16 MT = 609 Q = -5.47715E-01 MeV Emin = 1.80000E+00 MeV : (n,p9) + 17 MT = 610 Q = -6.00715E-01 MeV Emin = 1.80000E+00 MeV : (n,p10) + 18 MT = 611 Q = -6.78915E-01 MeV Emin = 1.90000E+00 MeV : (n,p11) + 19 MT = 612 Q = -6.98615E-01 MeV Emin = 2.00000E+00 MeV : (n,p12) + 20 MT = 613 Q = -7.00915E-01 MeV Emin = 2.00000E+00 MeV : (n,p13) + 21 MT = 614 Q = -8.39715E-01 MeV Emin = 2.00000E+00 MeV : (n,p14) + 22 MT = 615 Q = -8.81215E-01 MeV Emin = 2.00000E+00 MeV : (n,p15) + 23 MT = 649 Q = -8.81215E-01 MeV Emin = 8.69109E-01 MeV : (n,p) to continuum + 24 MT = 650 Q = -3.98118E+00 MeV Emin = 4.01283E+00 MeV : (n,d) to ground state + 25 MT = 651 Q = -4.64752E+00 MeV Emin = 4.68446E+00 MeV : (n,d1) + 26 MT = 652 Q = -5.34261E+00 MeV Emin = 5.38508E+00 MeV : (n,d2) + 27 MT = 653 Q = -5.40138E+00 MeV Emin = 5.44432E+00 MeV : (n,d3) + 28 MT = 654 Q = -5.56118E+00 MeV Emin = 5.60539E+00 MeV : (n,d4) + 29 MT = 655 Q = -5.66118E+00 MeV Emin = 5.70618E+00 MeV : (n,d5) + 30 MT = 656 Q = -5.75743E+00 MeV Emin = 5.80320E+00 MeV : (n,d6) + 31 MT = 657 Q = -5.85457E+00 MeV Emin = 5.90111E+00 MeV : (n,d7) + 32 MT = 658 Q = -5.99437E+00 MeV Emin = 6.04202E+00 MeV : (n,d8) + 33 MT = 659 Q = -6.02634E+00 MeV Emin = 6.07424E+00 MeV : (n,d9) + 34 MT = 660 Q = -6.03418E+00 MeV Emin = 6.08215E+00 MeV : (n,d10) + 35 MT = 661 Q = -6.06118E+00 MeV Emin = 6.10936E+00 MeV : (n,d11) + 36 MT = 662 Q = -6.09476E+00 MeV Emin = 6.14321E+00 MeV : (n,d12) + 37 MT = 663 Q = -6.10958E+00 MeV Emin = 6.15815E+00 MeV : (n,d13) + 38 MT = 664 Q = -6.16270E+00 MeV Emin = 6.21169E+00 MeV : (n,d14) + 39 MT = 665 Q = -6.16555E+00 MeV Emin = 6.21456E+00 MeV : (n,d15) + 40 MT = 699 Q = -6.16555E+00 MeV Emin = 6.21456E+00 MeV : (n,d) to continuum + 41 MT = 700 Q = -6.83776E+00 MeV Emin = 6.89211E+00 MeV : (n,t) to ground state + 42 MT = 701 Q = -6.87325E+00 MeV Emin = 6.92788E+00 MeV : (n,t1) + 43 MT = 702 Q = -6.98256E+00 MeV Emin = 7.03806E+00 MeV : (n,t2) + 44 MT = 703 Q = -7.15887E+00 MeV Emin = 7.21577E+00 MeV : (n,t3) + 45 MT = 704 Q = -7.28132E+00 MeV Emin = 7.33920E+00 MeV : (n,t4) + 46 MT = 705 Q = -7.30113E+00 MeV Emin = 7.35916E+00 MeV : (n,t5) + 47 MT = 706 Q = -7.36301E+00 MeV Emin = 7.42153E+00 MeV : (n,t6) + 48 MT = 707 Q = -7.37576E+00 MeV Emin = 7.43439E+00 MeV : (n,t7) + 49 MT = 708 Q = -7.47385E+00 MeV Emin = 7.53326E+00 MeV : (n,t8) + 50 MT = 709 Q = -7.47997E+00 MeV Emin = 7.53942E+00 MeV : (n,t9) + 51 MT = 710 Q = -7.50921E+00 MeV Emin = 7.56890E+00 MeV : (n,t10) + 52 MT = 711 Q = -7.56704E+00 MeV Emin = 7.62719E+00 MeV : (n,t11) + 53 MT = 712 Q = -7.62376E+00 MeV Emin = 7.68436E+00 MeV : (n,t12) + 54 MT = 713 Q = -7.64176E+00 MeV Emin = 7.70250E+00 MeV : (n,t13) + 55 MT = 714 Q = -7.67869E+00 MeV Emin = 7.73972E+00 MeV : (n,t14) + 56 MT = 715 Q = -7.85476E+00 MeV Emin = 7.91719E+00 MeV : (n,t15) + 57 MT = 749 Q = -7.85476E+00 MeV Emin = 7.91719E+00 MeV : (n,t) to continuum + 58 MT = 750 Q = -7.58587E+00 MeV Emin = 7.64617E+00 MeV : (n,He-3) to ground state + 59 MT = 751 Q = -7.91801E+00 MeV Emin = 7.98095E+00 MeV : (n,He-3_1) + 60 MT = 752 Q = -8.22907E+00 MeV Emin = 8.29448E+00 MeV : (n,He-3_2) + 61 MT = 753 Q = -8.50757E+00 MeV Emin = 8.57519E+00 MeV : (n,He-3_3) + 62 MT = 754 Q = -8.65317E+00 MeV Emin = 8.72195E+00 MeV : (n,He-3_4) + 63 MT = 755 Q = -8.67550E+00 MeV Emin = 8.74446E+00 MeV : (n,He-3_5) + 64 MT = 756 Q = -8.93533E+00 MeV Emin = 9.00635E+00 MeV : (n,He-3_6) + 65 MT = 757 Q = -9.00573E+00 MeV Emin = 9.07731E+00 MeV : (n,He-3_7) + 66 MT = 758 Q = -9.06997E+00 MeV Emin = 9.14206E+00 MeV : (n,He-3_8) + 67 MT = 759 Q = -9.14587E+00 MeV Emin = 9.21856E+00 MeV : (n,He-3_9) + 68 MT = 760 Q = -9.17745E+00 MeV Emin = 9.25040E+00 MeV : (n,He-3_10) + 69 MT = 761 Q = -9.24587E+00 MeV Emin = 9.31936E+00 MeV : (n,He-3_11) + 70 MT = 762 Q = -9.28677E+00 MeV Emin = 9.36058E+00 MeV : (n,He-3_12) + 71 MT = 763 Q = -9.32157E+00 MeV Emin = 9.39566E+00 MeV : (n,He-3_13) + 72 MT = 764 Q = -9.38587E+00 MeV Emin = 9.46047E+00 MeV : (n,He-3_14) + 73 MT = 765 Q = -9.39258E+00 MeV Emin = 9.46724E+00 MeV : (n,He-3_15) + 74 MT = 799 Q = -9.39258E+00 MeV Emin = 9.46724E+00 MeV : (n,He-3) to continuum + 75 MT = 800 Q = 4.27795E+00 MeV Emin = 1.20000E+00 MeV : (n,alpha) to ground state + 76 MT = 801 Q = 4.26709E+00 MeV Emin = 1.20000E+00 MeV : (n,a1) + 77 MT = 802 Q = 4.24111E+00 MeV Emin = 1.20000E+00 MeV : (n,a2) + 78 MT = 803 Q = 4.23715E+00 MeV Emin = 1.20000E+00 MeV : (n,a3) + 79 MT = 804 Q = 4.19719E+00 MeV Emin = 1.20000E+00 MeV : (n,a4) + 80 MT = 805 Q = 4.19035E+00 MeV Emin = 1.20000E+00 MeV : (n,a5) + 81 MT = 806 Q = 4.17430E+00 MeV Emin = 1.20000E+00 MeV : (n,a6) + 82 MT = 807 Q = 4.15272E+00 MeV Emin = 1.20000E+00 MeV : (n,a7) + 83 MT = 808 Q = 4.14626E+00 MeV Emin = 1.20000E+00 MeV : (n,a8) + 84 MT = 809 Q = 4.12795E+00 MeV Emin = 1.20000E+00 MeV : (n,a9) + 85 MT = 810 Q = 4.09790E+00 MeV Emin = 1.20000E+00 MeV : (n,a10) + 86 MT = 811 Q = 4.08197E+00 MeV Emin = 1.40000E+00 MeV : (n,a11) + 87 MT = 812 Q = 4.06335E+00 MeV Emin = 1.40000E+00 MeV : (n,a12) + 88 MT = 813 Q = 4.05645E+00 MeV Emin = 1.40000E+00 MeV : (n,a13) + 89 MT = 814 Q = 4.04645E+00 MeV Emin = 1.40000E+00 MeV : (n,a14) + 90 MT = 815 Q = 4.02958E+00 MeV Emin = 1.40000E+00 MeV : (n,a15) + 91 MT = 849 Q = 4.02958E+00 MeV Emin = 1.00000E-11 MeV : (n,alpha) to continuum + 92 MT = 4 Q = 0.00000E+00 MeV Emin = 5.78370E-02 MeV : total inelastic scattering + + Nuclide 168 / 1657 : 53129.82c -- iodine 129 (I-129) + + Pointers : 1366968 26457 + Primary type : Transport + Nuclide ZAI : 531290 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/I129.ACE + Atomic weight (AW) : 128.90496 + Atomic weight ratio (AWR) : 127.79760 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 3.00000E+01 + Half-life : 5.08E+14 seconds (16.1 million years) + Specific ingestion toxicity : 1.10E-07 Sv/Bq + Specific inhalation toxicity : 3.60E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 43 reaction channels + - 82 special reactions + - 23 transmutation reactions + - 27 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 43 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 11 Q = -1.96403E+01 MeV Emin = 1.97940E+01 MeV frac = 1.00000E+00 Product nuclide = self : (n,2nd) + 3 MT = 16 Q = -8.83307E+00 MeV Emin = 8.90219E+00 MeV frac = 1.00000E+00 Product nuclide = 531280 : (n,2n) + 4 MT = 17 Q = -1.56591E+01 MeV Emin = 1.57817E+01 MeV frac = 1.00000E+00 Product nuclide = 53127.82c : (n,3n) + 5 MT = 22 Q = -2.66740E+00 MeV Emin = 2.68827E+00 MeV frac = 1.00000E+00 Product nuclide = 51125.82c : (n,nalpha) + 6 MT = 24 Q = -1.13812E+01 MeV Emin = 1.14703E+01 MeV frac = 1.00000E+00 Product nuclide = 51124.82c : (n,2nalpha) + 7 MT = 25 Q = -1.78486E+01 MeV Emin = 1.79883E+01 MeV frac = 1.00000E+00 Product nuclide = 51123.82c : (n,3nalpha) + 8 MT = 28 Q = -6.79891E+00 MeV Emin = 6.85211E+00 MeV frac = 1.00000E+00 Product nuclide = 52128.82c : (n,np) + 9 MT = 32 Q = -1.33498E+01 MeV Emin = 1.34543E+01 MeV frac = 1.00000E+00 Product nuclide = 521270 : (n,nd) + 10 MT = 33 Q = -1.33831E+01 MeV Emin = 1.34878E+01 MeV frac = 1.00000E+00 Product nuclide = 52126.82c : (n,nt) + 11 MT = 34 Q = -1.70370E+01 MeV Emin = 1.71703E+01 MeV frac = 1.00000E+00 Product nuclide = 51126.82c : (n,nHe-3) + 12 MT = 37 Q = -2.48026E+01 MeV Emin = 2.49967E+01 MeV frac = 1.00000E+00 Product nuclide = cut: I-126 : (n,4n) + 13 MT = 41 Q = -1.55744E+01 MeV Emin = 1.56963E+01 MeV frac = 1.00000E+00 Product nuclide = 521270 : (n,2np) + 14 MT = 42 Q = -2.18649E+01 MeV Emin = 2.20360E+01 MeV frac = 1.00000E+00 Product nuclide = cut: Te-126 : (n,3np) + 15 MT = 44 Q = -1.63730E+01 MeV Emin = 1.65011E+01 MeV frac = 1.00000E+00 Product nuclide = 511270 : (n,n2p) + 16 MT = 45 Q = -9.98135E+00 MeV Emin = 1.00595E+01 MeV frac = 1.00000E+00 Product nuclide = 50124.82c : (n,npalpha) + 17 MT = 51 Q = -2.78000E-02 MeV Emin = 2.79088E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 18 MT = 52 Q = -2.78380E-01 MeV Emin = 2.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 19 MT = 53 Q = -4.87350E-01 MeV Emin = 4.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 20 MT = 54 Q = -5.59620E-01 MeV Emin = 5.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 21 MT = 55 Q = -6.95890E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 22 MT = 56 Q = -7.29570E-01 MeV Emin = 7.28391E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 23 MT = 57 Q = -7.68760E-01 MeV Emin = 7.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 24 MT = 58 Q = -8.29920E-01 MeV Emin = 8.31964E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 25 MT = 59 Q = -8.44820E-01 MeV Emin = 8.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 26 MT = 60 Q = -1.04735E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 27 MT = 61 Q = -1.05021E+00 MeV Emin = 1.05699E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 28 MT = 62 Q = -1.11165E+00 MeV Emin = 1.11994E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 29 MT = 63 Q = -1.19665E+00 MeV Emin = 1.20000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 30 MT = 64 Q = -1.20361E+00 MeV Emin = 1.21264E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 31 MT = 65 Q = -1.20980E+00 MeV Emin = 1.21596E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 32 MT = 91 Q = -1.20980E+00 MeV Emin = 1.21596E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 33 MT = 102 Q = 6.50033E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 53130.82c : (n,gamma) + 34 MT = 103 Q = -7.15589E-01 MeV Emin = 7.11261E-01 MeV frac = 1.00000E+00 Product nuclide = 521290 : (n,p) + 35 MT = 104 Q = -4.57434E+00 MeV Emin = 4.61013E+00 MeV frac = 1.00000E+00 Product nuclide = 52128.82c : (n,d) + 36 MT = 105 Q = -7.09253E+00 MeV Emin = 7.14803E+00 MeV frac = 1.00000E+00 Product nuclide = 521270 : (n,t) + 37 MT = 106 Q = -8.65494E+00 MeV Emin = 8.72267E+00 MeV frac = 1.00000E+00 Product nuclide = 511270 : (n,He-3) + 38 MT = 107 Q = 3.54061E+00 MeV Emin = 1.81250E-08 MeV frac = 1.00000E+00 Product nuclide = 51126.82c : (n,alpha) + 39 MT = 111 Q = -1.04001E+01 MeV Emin = 1.04815E+01 MeV frac = 1.00000E+00 Product nuclide = 511280 : (n,2p) + 40 MT = 112 Q = -4.24835E+00 MeV Emin = 4.28160E+00 MeV frac = 1.00000E+00 Product nuclide = 50125.82c : (n,palpha) + 41 MT = 115 Q = -1.41484E+01 MeV Emin = 1.42591E+01 MeV frac = 1.00000E+00 Product nuclide = 511270 : (n,pd) + 42 MT = 116 Q = -1.62732E+01 MeV Emin = 1.64006E+01 MeV frac = 1.00000E+00 Product nuclide = 51126.82c : (n,pt) + 43 MT = 117 Q = -7.75678E+00 MeV Emin = 7.81748E+00 MeV frac = 1.00000E+00 Product nuclide = 50124.82c : (n,dalpha) + + 27 additional transport branches: + + 1 MT = 22 Q = -2.66740E+00 MeV Emin = 2.68827E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 24 Q = -1.13812E+01 MeV Emin = 1.14703E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,2nalpha) + 3 MT = 25 Q = -1.78486E+01 MeV Emin = 1.79883E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,3nalpha) + 4 MT = 28 Q = -6.79891E+00 MeV Emin = 6.85211E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 5 MT = 32 Q = -1.33498E+01 MeV Emin = 1.34543E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 6 MT = 33 Q = -1.33831E+01 MeV Emin = 1.34878E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 7 MT = 34 Q = -1.70370E+01 MeV Emin = 1.71703E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,nHe-3) + 8 MT = 41 Q = -1.55744E+01 MeV Emin = 1.56963E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,2np) + 9 MT = 42 Q = -2.18649E+01 MeV Emin = 2.20360E+01 MeV frac = 1.00000E+00 Product nuclide = cut: H-1 : (n,3np) + 10 MT = 44 Q = -1.63730E+01 MeV Emin = 1.65011E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,n2p) + 11 MT = 45 Q = -9.98135E+00 MeV Emin = 1.00595E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,npalpha) + 12 MT = 45 Q = -9.98135E+00 MeV Emin = 1.00595E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,npalpha) + 13 MT = 102 Q = 6.50033E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 531301 : (n,gamma) + 14 MT = 103 Q = -7.15589E-01 MeV Emin = 7.11261E-01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 15 MT = 104 Q = -4.57434E+00 MeV Emin = 4.61013E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 16 MT = 105 Q = -7.09253E+00 MeV Emin = 7.14803E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 17 MT = 106 Q = -8.65494E+00 MeV Emin = 8.72267E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 18 MT = 107 Q = 3.54061E+00 MeV Emin = 1.81250E-08 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 19 MT = 111 Q = -1.04001E+01 MeV Emin = 1.04815E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + 20 MT = 112 Q = -4.24835E+00 MeV Emin = 4.28160E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,palpha) + 21 MT = 112 Q = -4.24835E+00 MeV Emin = 4.28160E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,palpha) + 22 MT = 115 Q = -1.41484E+01 MeV Emin = 1.42591E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,pd) + 23 MT = 115 Q = -1.41484E+01 MeV Emin = 1.42591E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,pd) + 24 MT = 116 Q = -1.62732E+01 MeV Emin = 1.64006E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,pt) + 25 MT = 116 Q = -1.62732E+01 MeV Emin = 1.64006E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,pt) + 26 MT = 117 Q = -7.75678E+00 MeV Emin = 7.81748E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,dalpha) + 27 MT = 117 Q = -7.75678E+00 MeV Emin = 7.81748E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,dalpha) + + 82 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 7.11261E-01 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 4.61013E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 7.14803E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 8.72267E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.81250E-08 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 600 Q = -7.15589E-01 MeV Emin = 2.00000E+00 MeV : (n,p) to ground state + 8 MT = 601 Q = -8.21089E-01 MeV Emin = 2.00000E+00 MeV : (n,p1) + 9 MT = 602 Q = -8.95889E-01 MeV Emin = 2.00000E+00 MeV : (n,p2) + 10 MT = 603 Q = -9.60089E-01 MeV Emin = 2.00000E+00 MeV : (n,p3) + 11 MT = 604 Q = -1.07559E+00 MeV Emin = 2.00000E+00 MeV : (n,p4) + 12 MT = 605 Q = -1.17059E+00 MeV Emin = 2.00000E+00 MeV : (n,p5) + 13 MT = 606 Q = -1.18049E+00 MeV Emin = 2.00000E+00 MeV : (n,p6) + 14 MT = 607 Q = -1.26009E+00 MeV Emin = 2.00000E+00 MeV : (n,p7) + 15 MT = 608 Q = -1.34949E+00 MeV Emin = 2.00000E+00 MeV : (n,p8) + 16 MT = 609 Q = -1.47559E+00 MeV Emin = 2.00000E+00 MeV : (n,p9) + 17 MT = 610 Q = -1.49059E+00 MeV Emin = 2.00000E+00 MeV : (n,p10) + 18 MT = 611 Q = -1.52839E+00 MeV Emin = 2.00000E+00 MeV : (n,p11) + 19 MT = 612 Q = -1.53459E+00 MeV Emin = 2.00000E+00 MeV : (n,p12) + 20 MT = 613 Q = -1.58259E+00 MeV Emin = 2.00000E+00 MeV : (n,p13) + 21 MT = 614 Q = -1.58759E+00 MeV Emin = 2.00000E+00 MeV : (n,p14) + 22 MT = 615 Q = -1.59159E+00 MeV Emin = 2.00000E+00 MeV : (n,p15) + 23 MT = 649 Q = -1.59159E+00 MeV Emin = 1.60203E+00 MeV : (n,p) to continuum + 24 MT = 650 Q = -4.57434E+00 MeV Emin = 4.61013E+00 MeV : (n,d) to ground state + 25 MT = 651 Q = -5.31764E+00 MeV Emin = 5.35925E+00 MeV : (n,d1) + 26 MT = 652 Q = -6.07164E+00 MeV Emin = 6.11915E+00 MeV : (n,d2) + 27 MT = 653 Q = -6.09443E+00 MeV Emin = 6.14212E+00 MeV : (n,d3) + 28 MT = 654 Q = -6.38570E+00 MeV Emin = 6.43567E+00 MeV : (n,d4) + 29 MT = 655 Q = -6.54308E+00 MeV Emin = 6.59428E+00 MeV : (n,d5) + 30 MT = 656 Q = -6.55339E+00 MeV Emin = 6.60467E+00 MeV : (n,d6) + 31 MT = 657 Q = -6.60242E+00 MeV Emin = 6.65408E+00 MeV : (n,d7) + 32 MT = 658 Q = -6.61434E+00 MeV Emin = 6.66610E+00 MeV : (n,d8) + 33 MT = 659 Q = -6.70788E+00 MeV Emin = 6.76037E+00 MeV : (n,d9) + 34 MT = 660 Q = -6.71234E+00 MeV Emin = 6.76486E+00 MeV : (n,d10) + 35 MT = 661 Q = -6.73802E+00 MeV Emin = 6.79075E+00 MeV : (n,d11) + 36 MT = 662 Q = -6.76793E+00 MeV Emin = 6.82089E+00 MeV : (n,d12) + 37 MT = 663 Q = -6.79238E+00 MeV Emin = 6.84553E+00 MeV : (n,d13) + 38 MT = 664 Q = -6.84496E+00 MeV Emin = 6.89852E+00 MeV : (n,d14) + 39 MT = 665 Q = -6.88264E+00 MeV Emin = 6.93650E+00 MeV : (n,d15) + 40 MT = 699 Q = -6.88264E+00 MeV Emin = 6.93650E+00 MeV : (n,d) to continuum + 41 MT = 700 Q = -7.09253E+00 MeV Emin = 7.14803E+00 MeV : (n,t) to ground state + 42 MT = 701 Q = -7.15365E+00 MeV Emin = 7.20963E+00 MeV : (n,t1) + 43 MT = 702 Q = -7.18079E+00 MeV Emin = 7.23698E+00 MeV : (n,t2) + 44 MT = 703 Q = -7.43313E+00 MeV Emin = 7.49130E+00 MeV : (n,t3) + 45 MT = 704 Q = -7.45853E+00 MeV Emin = 7.51690E+00 MeV : (n,t4) + 46 MT = 705 Q = -7.56580E+00 MeV Emin = 7.62500E+00 MeV : (n,t5) + 47 MT = 706 Q = -7.59543E+00 MeV Emin = 7.65487E+00 MeV : (n,t6) + 48 MT = 707 Q = -7.69553E+00 MeV Emin = 7.75575E+00 MeV : (n,t7) + 49 MT = 708 Q = -7.72403E+00 MeV Emin = 7.78447E+00 MeV : (n,t8) + 50 MT = 709 Q = -7.72503E+00 MeV Emin = 7.78548E+00 MeV : (n,t9) + 51 MT = 710 Q = -7.77803E+00 MeV Emin = 7.83890E+00 MeV : (n,t10) + 52 MT = 711 Q = -7.85623E+00 MeV Emin = 7.91771E+00 MeV : (n,t11) + 53 MT = 712 Q = -7.87593E+00 MeV Emin = 7.93756E+00 MeV : (n,t12) + 54 MT = 713 Q = -7.87823E+00 MeV Emin = 7.93988E+00 MeV : (n,t13) + 55 MT = 714 Q = -8.01703E+00 MeV Emin = 8.07976E+00 MeV : (n,t14) + 56 MT = 715 Q = -8.05853E+00 MeV Emin = 8.12159E+00 MeV : (n,t15) + 57 MT = 749 Q = -8.05853E+00 MeV Emin = 8.12159E+00 MeV : (n,t) to continuum + 58 MT = 750 Q = -8.65494E+00 MeV Emin = 8.72267E+00 MeV : (n,He-3) to ground state + 59 MT = 751 Q = -9.14614E+00 MeV Emin = 9.21771E+00 MeV : (n,He-3_1) + 60 MT = 752 Q = -9.43294E+00 MeV Emin = 9.50675E+00 MeV : (n,He-3_2) + 61 MT = 753 Q = -9.75042E+00 MeV Emin = 9.82672E+00 MeV : (n,He-3_3) + 62 MT = 754 Q = -9.76494E+00 MeV Emin = 9.84135E+00 MeV : (n,He-3_4) + 63 MT = 755 Q = -9.76929E+00 MeV Emin = 9.84574E+00 MeV : (n,He-3_5) + 64 MT = 756 Q = -9.84994E+00 MeV Emin = 9.92702E+00 MeV : (n,He-3_6) + 65 MT = 757 Q = -1.01263E+01 MeV Emin = 1.02056E+01 MeV : (n,He-3_7) + 66 MT = 758 Q = -1.02393E+01 MeV Emin = 1.03194E+01 MeV : (n,He-3_8) + 67 MT = 759 Q = -1.02649E+01 MeV Emin = 1.03453E+01 MeV : (n,He-3_9) + 68 MT = 760 Q = -1.03666E+01 MeV Emin = 1.04478E+01 MeV : (n,He-3_10) + 69 MT = 761 Q = -1.05751E+01 MeV Emin = 1.06579E+01 MeV : (n,He-3_11) + 70 MT = 762 Q = -1.05924E+01 MeV Emin = 1.06753E+01 MeV : (n,He-3_12) + 71 MT = 763 Q = -1.06100E+01 MeV Emin = 1.06930E+01 MeV : (n,He-3_13) + 72 MT = 764 Q = -1.06455E+01 MeV Emin = 1.07288E+01 MeV : (n,He-3_14) + 73 MT = 765 Q = -1.06584E+01 MeV Emin = 1.07418E+01 MeV : (n,He-3_15) + 74 MT = 799 Q = -1.06584E+01 MeV Emin = 1.07418E+01 MeV : (n,He-3) to continuum + 75 MT = 800 Q = 3.54061E+00 MeV Emin = 2.00000E+00 MeV : (n,alpha) to ground state + 76 MT = 801 Q = 3.52291E+00 MeV Emin = 2.00000E+00 MeV : (n,a1) + 77 MT = 802 Q = 3.50021E+00 MeV Emin = 2.00000E+00 MeV : (n,a2) + 78 MT = 803 Q = 3.45761E+00 MeV Emin = 2.00000E+00 MeV : (n,a3) + 79 MT = 804 Q = 3.43601E+00 MeV Emin = 2.00000E+00 MeV : (n,a4) + 80 MT = 805 Q = 3.41271E+00 MeV Emin = 2.00000E+00 MeV : (n,a5) + 81 MT = 849 Q = 3.41271E+00 MeV Emin = 1.00000E-11 MeV : (n,alpha) to continuum + 82 MT = 4 Q = 0.00000E+00 MeV Emin = 2.79088E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.90800E-01 MeV frac = 1.00000E+00 Product nuclide = 54129.82c : beta- + + Nuclide 169 / 1657 : 53130.82c -- iodine 130 (I-130) + + Pointers : 1378482 26503 + Primary type : Transport + Nuclide ZAI : 531300 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/I130.ACE + Atomic weight (AW) : 129.90697 + Atomic weight ratio (AWR) : 128.79100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 4.45E+04 seconds (12.4 hours) + Specific ingestion toxicity : 2.00E-09 Sv/Bq + Specific inhalation toxicity : 6.70E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 9 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 6 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 9 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 91 Q = -4.96130E-02 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 3 MT = 102 Q = 8.43000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 53131.82c : (n,gamma) + 4 MT = 103 Q = 1.23330E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 52130.82c : (n,p) + 5 MT = 104 Q = -4.95250E+00 MeV Emin = 4.99095E+00 MeV frac = 1.00000E+00 Product nuclide = 521290 : (n,d) + 6 MT = 105 Q = -4.78100E+00 MeV Emin = 4.81812E+00 MeV frac = 1.00000E+00 Product nuclide = 52128.82c : (n,t) + 7 MT = 106 Q = -9.02380E+00 MeV Emin = 9.09387E+00 MeV frac = 1.00000E+00 Product nuclide = 511280 : (n,He-3) + 8 MT = 107 Q = 5.45160E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 511270 : (n,alpha) + 9 MT = 111 Q = -8.77040E+00 MeV Emin = 8.83850E+00 MeV frac = 1.00000E+00 Product nuclide = 511290 : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = 1.23330E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -4.95250E+00 MeV Emin = 4.99095E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -4.78100E+00 MeV Emin = 4.81812E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -9.02380E+00 MeV Emin = 9.09387E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 5.45160E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -8.77040E+00 MeV Emin = 8.83850E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.62500E-02 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 4.99095E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 4.81812E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 9.09387E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.62500E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 4.62500E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.94900E+00 MeV frac = 1.00000E+00 Product nuclide = 54130.82c : beta- + + Nuclide 170 / 1657 : 53131.82c -- iodine 131 (I-131) + + Pointers : 1381640 26549 + Primary type : Transport + Nuclide ZAI : 531310 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/I131.ACE + Atomic weight (AW) : 130.90555 + Atomic weight ratio (AWR) : 129.78100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 6.93E+05 seconds (8.02 days) + Specific ingestion toxicity : 2.20E-08 Sv/Bq + Specific inhalation toxicity : 7.40E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 28 reaction channels + - 6 special reactions + - 11 transmutation reactions + - 9 transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 28 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.63010E+00 MeV Emin = 8.69660E+00 MeV frac = 1.00000E+00 Product nuclide = 53130.82c : (n,2n) + 3 MT = 17 Q = -1.50982E+01 MeV Emin = 1.52146E+01 MeV frac = 1.00000E+00 Product nuclide = 53129.82c : (n,3n) + 4 MT = 22 Q = -3.16890E+00 MeV Emin = 3.19332E+00 MeV frac = 1.00000E+00 Product nuclide = 511270 : (n,nalpha) + 5 MT = 28 Q = -7.39664E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 52130.82c : (n,np) + 6 MT = 32 Q = -1.35036E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 521290 : (n,nd) + 7 MT = 33 Q = -1.34093E+01 MeV Emin = 1.52146E+01 MeV frac = 1.00000E+00 Product nuclide = 52128.82c : (n,nt) + 8 MT = 51 Q = -1.49700E-01 MeV Emin = 1.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -4.92699E-01 MeV Emin = 4.47372E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -6.01999E-01 MeV Emin = 5.93309E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -7.73699E-01 MeV Emin = 7.59746E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -8.52199E-01 MeV Emin = 8.44074E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -8.76699E-01 MeV Emin = 8.74197E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -1.00580E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -1.05970E+00 MeV Emin = 1.05429E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -1.09830E+00 MeV Emin = 1.09218E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -1.14690E+00 MeV Emin = 1.13737E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -1.14890E+00 MeV Emin = 1.15750E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 62 Q = -1.28400E+00 MeV Emin = 1.25000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 20 MT = 63 Q = -1.29820E+00 MeV Emin = 1.30105E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 21 MT = 64 Q = -1.31520E+00 MeV Emin = 1.31677E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 22 MT = 65 Q = -1.34650E+00 MeV Emin = 1.34110E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 23 MT = 91 Q = -1.37680E+00 MeV Emin = 1.37596E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 24 MT = 102 Q = 6.32685E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 531320 : (n,gamma) + 25 MT = 103 Q = -1.46754E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 521310 : (n,p) + 26 MT = 104 Q = -5.08652E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 52130.82c : (n,d) + 27 MT = 105 Q = -7.31846E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 521290 : (n,t) + 28 MT = 107 Q = 2.93321E+00 MeV Emin = 2.37500E-01 MeV frac = 1.00000E+00 Product nuclide = 511280 : (n,alpha) + + 9 additional transport branches: + + 1 MT = 22 Q = -3.16890E+00 MeV Emin = 3.19332E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -7.39664E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.35036E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.34093E+01 MeV Emin = 1.52146E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 102 Q = 6.32685E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 531321 : (n,gamma) + 6 MT = 103 Q = -1.46754E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 7 MT = 104 Q = -5.08652E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 8 MT = 105 Q = -7.31846E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 9 MT = 107 Q = 2.93321E+00 MeV Emin = 2.37500E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.00000E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 2.37500E-01 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 7.60000E-04 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 1.50000E-01 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 1 Q = 9.70800E-01 MeV frac = 9.89105E-01 Product nuclide = 54131.82c : beta- + 2 RTYP = 1 Q = 8.06870E-01 MeV frac = 1.08945E-02 Product nuclide = 541311 : beta- + + Nuclide 171 / 1657 : 53135.82c -- iodine 135 (I-135) + + Pointers : 1396941 26595 + Primary type : Transport + Nuclide ZAI : 531350 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/I135.ACE + Atomic weight (AW) : 134.90894 + Atomic weight ratio (AWR) : 133.75000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.37E+04 seconds (6.58 hours) + Specific ingestion toxicity : 9.30E-10 Sv/Bq + Specific inhalation toxicity : 3.20E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 13 reaction channels + - 6 special reactions + - 9 transmutation reactions + - 6 transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 13 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.90260E+00 MeV Emin = 7.96170E+00 MeV frac = 1.00000E+00 Product nuclide = 531340 : (n,2n) + 3 MT = 17 Q = -1.40750E+01 MeV Emin = 1.41810E+01 MeV frac = 1.00000E+00 Product nuclide = 531330 : (n,3n) + 4 MT = 22 Q = -4.22630E+00 MeV Emin = 1.22500E+01 MeV frac = 1.00000E+00 Product nuclide = 511310 : (n,nalpha) + 5 MT = 28 Q = -8.67950E+00 MeV Emin = 1.17480E+01 MeV frac = 1.00000E+00 Product nuclide = 521340 : (n,np) + 6 MT = 51 Q = -6.03500E-01 MeV Emin = 5.54006E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -8.70300E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 91 Q = -8.70300E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 9 MT = 102 Q = 3.78098E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 531360 : (n,gamma) + 10 MT = 103 Q = -5.16890E+00 MeV Emin = 8.25000E+00 MeV frac = 1.00000E+00 Product nuclide = 521350 : (n,p) + 11 MT = 104 Q = -6.45500E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 521340 : (n,d) + 12 MT = 105 Q = -7.72970E+00 MeV Emin = 1.22500E+01 MeV frac = 1.00000E+00 Product nuclide = 521330 : (n,t) + 13 MT = 107 Q = 1.55530E+00 MeV Emin = 6.75000E+00 MeV frac = 1.00000E+00 Product nuclide = 511320 : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = -4.22630E+00 MeV Emin = 1.22500E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -8.67950E+00 MeV Emin = 1.17480E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -5.16890E+00 MeV Emin = 8.25000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -6.45500E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -7.72970E+00 MeV Emin = 1.22500E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 107 Q = 1.55530E+00 MeV Emin = 6.75000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 8.25000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.00000E+01 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.22500E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 6.75000E+00 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 8.12500E-04 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 5.54006E-01 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 1 Q = 2.62700E+00 MeV frac = 8.34918E-01 Product nuclide = 54135.82c : beta- + 2 RTYP = 1 Q = 2.10045E+00 MeV frac = 1.65082E-01 Product nuclide = 541351 : beta- + + Nuclide 172 / 1657 : 54128.82c -- xenon 128 (Xe-128) + + Pointers : 1426636 36209 + Primary type : Transport + Nuclide ZAI : 541280 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Xe128.ACE + Atomic weight (AW) : 127.90275 + Atomic weight ratio (AWR) : 126.80400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 34 reaction channels + - 6 special reactions + - 9 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 34 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -9.62129E+00 MeV Emin = 9.69717E+00 MeV frac = 1.00000E+00 Product nuclide = 541270 : (n,2n) + 3 MT = 17 Q = -1.68514E+01 MeV Emin = 1.70000E+01 MeV frac = 1.00000E+00 Product nuclide = 541260 : (n,3n) + 4 MT = 22 Q = -1.76480E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 52124.82c : (n,nalpha) + 5 MT = 28 Q = -8.17483E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 53127.82c : (n,np) + 6 MT = 51 Q = -4.42899E-01 MeV Emin = 3.73196E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -9.69499E-01 MeV Emin = 9.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -1.03310E+00 MeV Emin = 1.02062E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -1.42960E+00 MeV Emin = 1.41949E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -1.58300E+00 MeV Emin = 1.54774E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -1.60340E+00 MeV Emin = 1.60576E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -1.73700E+00 MeV Emin = 1.75000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -1.87730E+00 MeV Emin = 1.85675E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -1.99650E+00 MeV Emin = 2.01225E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -1.99960E+00 MeV Emin = 2.01537E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -2.12710E+00 MeV Emin = 2.14388E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -2.22900E+00 MeV Emin = 2.24658E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -2.25290E+00 MeV Emin = 2.27067E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -2.27280E+00 MeV Emin = 2.29073E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -2.28090E+00 MeV Emin = 2.29889E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 21 MT = 66 Q = -2.36180E+00 MeV Emin = 2.38043E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 22 MT = 67 Q = -2.42110E+00 MeV Emin = 2.44019E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 23 MT = 68 Q = -2.43070E+00 MeV Emin = 2.44987E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 24 MT = 69 Q = -2.44390E+00 MeV Emin = 2.46317E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 25 MT = 70 Q = -2.48250E+00 MeV Emin = 2.50208E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 26 MT = 71 Q = -2.50080E+00 MeV Emin = 2.52052E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 27 MT = 72 Q = -2.51070E+00 MeV Emin = 2.53050E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 28 MT = 73 Q = -2.51250E+00 MeV Emin = 2.53232E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 29 MT = 91 Q = -2.52140E+00 MeV Emin = 2.54128E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 30 MT = 102 Q = 6.90867E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 54129.82c : (n,gamma) + 31 MT = 103 Q = -1.34473E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 531280 : (n,p) + 32 MT = 104 Q = -5.86471E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 53127.82c : (n,d) + 33 MT = 105 Q = -8.82466E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 531260 : (n,t) + 34 MT = 107 Q = 4.81200E+00 MeV Emin = 8.99999E-02 MeV frac = 1.00000E+00 Product nuclide = 52125.82c : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -1.76480E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -8.17483E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 102 Q = 6.90867E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 541291 : (n,gamma) + 4 MT = 103 Q = -1.34473E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -5.86471E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -8.82466E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 107 Q = 4.81200E+00 MeV Emin = 8.99999E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.00000E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 8.99999E-02 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 7.77933E-04 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 3.73196E-01 MeV : total inelastic scattering + + Nuclide 173 / 1657 : 54129.82c -- xenon 129 (Xe-129) + + Pointers : 1430197 36255 + Primary type : Transport + Nuclide ZAI : 541290 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Xe129.ACE + Atomic weight (AW) : 128.90536 + Atomic weight ratio (AWR) : 127.79800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 29 reaction channels + - 7 special reactions + - 11 transmutation reactions + - 8 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 29 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.91240E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 54128.82c : (n,2n) + 3 MT = 17 Q = -1.65337E+01 MeV Emin = 1.66631E+01 MeV frac = 1.00000E+00 Product nuclide = 541270 : (n,3n) + 4 MT = 22 Q = -2.10040E+00 MeV Emin = 2.11684E+00 MeV frac = 1.00000E+00 Product nuclide = 52125.82c : (n,nalpha) + 5 MT = 28 Q = -8.25713E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 531280 : (n,np) + 6 MT = 32 Q = -1.27771E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 53127.82c : (n,nd) + 7 MT = 51 Q = -3.95999E-02 MeV Emin = 3.74550E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 8 MT = 52 Q = -2.36100E-01 MeV Emin = 2.18973E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 9 MT = 53 Q = -3.18200E-01 MeV Emin = 3.10345E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 10 MT = 54 Q = -3.21700E-01 MeV Emin = 3.23335E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 11 MT = 55 Q = -4.11499E-01 MeV Emin = 4.13986E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 12 MT = 56 Q = -5.18699E-01 MeV Emin = 5.15894E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 13 MT = 57 Q = -5.72699E-01 MeV Emin = 5.63576E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 14 MT = 58 Q = -5.88499E-01 MeV Emin = 5.89124E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 15 MT = 59 Q = -6.24499E-01 MeV Emin = 6.20317E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 16 MT = 60 Q = -6.65399E-01 MeV Emin = 6.61590E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 17 MT = 61 Q = -7.71099E-01 MeV Emin = 7.57850E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 18 MT = 62 Q = -8.22199E-01 MeV Emin = 8.14317E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 19 MT = 63 Q = -8.23199E-01 MeV Emin = 8.29389E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 20 MT = 64 Q = -8.67999E-01 MeV Emin = 8.73680E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 21 MT = 65 Q = -9.04299E-01 MeV Emin = 9.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 22 MT = 66 Q = -9.45999E-01 MeV Emin = 9.37642E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 23 MT = 91 Q = -9.85799E-01 MeV Emin = 9.92719E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 24 MT = 102 Q = 9.25565E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 54130.82c : (n,gamma) + 25 MT = 103 Q = 5.89955E-01 MeV Emin = 1.67188E+00 MeV frac = 1.00000E+00 Product nuclide = 53129.82c : (n,p) + 26 MT = 104 Q = -5.94701E+00 MeV Emin = 7.32521E+00 MeV frac = 1.00000E+00 Product nuclide = 531280 : (n,d) + 27 MT = 105 Q = -6.59196E+00 MeV Emin = 8.32175E+00 MeV frac = 1.00000E+00 Product nuclide = 53127.82c : (n,t) + 28 MT = 106 Q = -7.26833E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 521270 : (n,He-3) + 29 MT = 107 Q = 7.02269E+00 MeV Emin = 9.99608E-02 MeV frac = 1.00000E+00 Product nuclide = 52126.82c : (n,alpha) + + 8 additional transport branches: + + 1 MT = 22 Q = -2.10040E+00 MeV Emin = 2.11684E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -8.25713E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.27771E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 103 Q = 5.89955E-01 MeV Emin = 1.67188E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -5.94701E+00 MeV Emin = 7.32521E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -6.59196E+00 MeV Emin = 8.32175E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 106 Q = -7.26833E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 8 MT = 107 Q = 7.02269E+00 MeV Emin = 9.99608E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.67188E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.32521E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 8.32175E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.10000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 9.99608E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 7.78058E-04 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 3.74550E-02 MeV : total inelastic scattering + + Nuclide 174 / 1657 : 54130.82c -- xenon 130 (Xe-130) + + Pointers : 1433947 36301 + Primary type : Transport + Nuclide ZAI : 541300 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Xe130.ACE + Atomic weight (AW) : 129.90394 + Atomic weight ratio (AWR) : 128.78800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 15 reaction channels + - 6 special reactions + - 7 transmutation reactions + - 5 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 15 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -9.25800E+00 MeV Emin = 9.32990E+00 MeV frac = 1.00000E+00 Product nuclide = 54129.82c : (n,2n) + 3 MT = 17 Q = -1.61630E+01 MeV Emin = 1.62889E+01 MeV frac = 1.00000E+00 Product nuclide = 54128.82c : (n,3n) + 4 MT = 51 Q = -5.36000E-01 MeV Emin = 5.40000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 5 MT = 52 Q = -1.12200E+00 MeV Emin = 1.06550E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 6 MT = 53 Q = -1.20400E+00 MeV Emin = 1.21000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 7 MT = 54 Q = -1.63300E+00 MeV Emin = 1.60950E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 8 MT = 55 Q = -1.80800E+00 MeV Emin = 1.82100E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 9 MT = 56 Q = -1.94400E+00 MeV Emin = 1.94750E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 10 MT = 91 Q = -2.08382E+00 MeV Emin = 2.10000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 11 MT = 102 Q = 6.60482E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 54131.82c : (n,gamma) + 12 MT = 103 Q = -2.20970E+00 MeV Emin = 2.22686E+00 MeV frac = 1.00000E+00 Product nuclide = 53130.82c : (n,p) + 13 MT = 104 Q = -6.44140E+00 MeV Emin = 6.49142E+00 MeV frac = 1.00000E+00 Product nuclide = 53129.82c : (n,d) + 14 MT = 105 Q = -9.02370E+00 MeV Emin = 9.09380E+00 MeV frac = 1.00000E+00 Product nuclide = 531280 : (n,t) + 15 MT = 107 Q = 4.05500E+00 MeV Emin = 6.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 521270 : (n,alpha) + + 5 additional transport branches: + + 1 MT = 102 Q = 6.60482E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 541311 : (n,gamma) + 2 MT = 103 Q = -2.20970E+00 MeV Emin = 2.22686E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 104 Q = -6.44140E+00 MeV Emin = 6.49142E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 4 MT = 105 Q = -9.02370E+00 MeV Emin = 9.09380E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 5 MT = 107 Q = 4.05500E+00 MeV Emin = 6.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.22686E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.49142E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.09380E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 6.50000E+00 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 7.99056E-04 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 5.40000E-01 MeV : total inelastic scattering + + Nuclide 175 / 1657 : 54131.82c -- xenon 131 (Xe-131) + + Pointers : 1435975 36347 + Primary type : Transport + Nuclide ZAI : 541310 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Xe131.ACE + Atomic weight (AW) : 130.90555 + Atomic weight ratio (AWR) : 129.78100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 17 reaction channels + - 7 special reactions + - 9 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 17 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.60560E+00 MeV Emin = 6.65650E+00 MeV frac = 1.00000E+00 Product nuclide = 54130.82c : (n,2n) + 3 MT = 17 Q = -1.58640E+01 MeV Emin = 1.59863E+01 MeV frac = 1.00000E+00 Product nuclide = 54129.82c : (n,3n) + 4 MT = 51 Q = -8.00000E-02 MeV Emin = 8.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 5 MT = 52 Q = -1.64000E-01 MeV Emin = 1.64750E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 6 MT = 53 Q = -3.64000E-01 MeV Emin = 3.48000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 7 MT = 54 Q = -6.37000E-01 MeV Emin = 6.31000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 8 MT = 55 Q = -7.23000E-01 MeV Emin = 7.28000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 9 MT = 56 Q = -8.06000E-01 MeV Emin = 8.12000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 10 MT = 91 Q = -9.42740E-01 MeV Emin = 9.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 11 MT = 102 Q = 8.93659E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 54132.82c : (n,gamma) + 12 MT = 103 Q = -1.88400E-01 MeV Emin = 1.82000E-01 MeV frac = 1.00000E+00 Product nuclide = 53131.82c : (n,p) + 13 MT = 104 Q = -6.59040E+00 MeV Emin = 6.64120E+00 MeV frac = 1.00000E+00 Product nuclide = 53130.82c : (n,d) + 14 MT = 105 Q = -6.78900E+00 MeV Emin = 6.84131E+00 MeV frac = 1.00000E+00 Product nuclide = 53129.82c : (n,t) + 15 MT = 106 Q = -8.27110E+00 MeV Emin = 8.33483E+00 MeV frac = 1.00000E+00 Product nuclide = 521290 : (n,He-3) + 16 MT = 107 Q = 6.22100E+00 MeV Emin = 4.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 52128.82c : (n,alpha) + 17 MT = 111 Q = -7.57680E+00 MeV Emin = 7.63518E+00 MeV frac = 1.00000E+00 Product nuclide = 52130.82c : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = -1.88400E-01 MeV Emin = 1.82000E-01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -6.59040E+00 MeV Emin = 6.64120E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -6.78900E+00 MeV Emin = 6.84131E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -8.27110E+00 MeV Emin = 8.33483E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 6.22100E+00 MeV Emin = 4.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -7.57680E+00 MeV Emin = 7.63518E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.82000E-01 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.64120E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 6.84131E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 8.33483E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.50000E+00 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 7.99069E-04 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 8.00000E-02 MeV : total inelastic scattering + + Nuclide 176 / 1657 : 54132.82c -- xenon 132 (Xe-132) + + Pointers : 1438647 36393 + Primary type : Transport + Nuclide ZAI : 541320 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Xe132.ACE + Atomic weight (AW) : 131.90312 + Atomic weight ratio (AWR) : 130.77000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 28 reaction channels + - 6 special reactions + - 9 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 28 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.93460E+00 MeV Emin = 9.00300E+00 MeV frac = 1.00000E+00 Product nuclide = 54131.82c : (n,2n) + 3 MT = 17 Q = -1.55540E+01 MeV Emin = 1.56730E+01 MeV frac = 1.00000E+00 Product nuclide = 54130.82c : (n,3n) + 4 MT = 22 Q = -2.72480E+00 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 52128.82c : (n,nalpha) + 5 MT = 28 Q = -9.12390E+00 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 53131.82c : (n,np) + 6 MT = 51 Q = -6.67700E-01 MeV Emin = 6.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.29790E+00 MeV Emin = 1.15000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -1.44030E+00 MeV Emin = 1.37956E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -1.80370E+00 MeV Emin = 1.60000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -1.96300E+00 MeV Emin = 1.89775E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -1.98570E+00 MeV Emin = 2.00090E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -2.04040E+00 MeV Emin = 2.05600E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -2.11030E+00 MeV Emin = 2.12644E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -2.11190E+00 MeV Emin = 2.12805E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -2.16710E+00 MeV Emin = 2.18370E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -2.18720E+00 MeV Emin = 2.20393E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -2.21410E+00 MeV Emin = 2.23103E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -2.30340E+00 MeV Emin = 2.32102E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -2.35060E+00 MeV Emin = 2.36860E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -2.39490E+00 MeV Emin = 2.41322E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 21 MT = 66 Q = -2.42480E+00 MeV Emin = 2.44334E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 22 MT = 67 Q = -2.46910E+00 MeV Emin = 2.48800E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 23 MT = 91 Q = -2.46910E+00 MeV Emin = 2.48800E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 24 MT = 102 Q = 6.43444E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 54133.82c : (n,gamma) + 25 MT = 103 Q = -2.79460E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 531320 : (n,p) + 26 MT = 104 Q = -6.89930E+00 MeV Emin = 1.07500E+01 MeV frac = 1.00000E+00 Product nuclide = 53131.82c : (n,d) + 27 MT = 105 Q = -9.27320E+00 MeV Emin = 1.35000E+01 MeV frac = 1.00000E+00 Product nuclide = 53130.82c : (n,t) + 28 MT = 107 Q = 3.36050E+00 MeV Emin = 7.20000E+00 MeV frac = 1.00000E+00 Product nuclide = 521290 : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -2.72480E+00 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -9.12390E+00 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 102 Q = 6.43444E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 541331 : (n,gamma) + 4 MT = 103 Q = -2.79460E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -6.89930E+00 MeV Emin = 1.07500E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -9.27320E+00 MeV Emin = 1.35000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 107 Q = 3.36050E+00 MeV Emin = 7.20000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 6.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.07500E+01 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.35000E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 7.20000E+00 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 8.04891E-04 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 6.00000E-01 MeV : total inelastic scattering + + Nuclide 177 / 1657 : 54133.82c -- xenon 133 (Xe-133) + + Pointers : 1442309 36439 + Primary type : Transport + Nuclide ZAI : 541330 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Xe133.ACE + Atomic weight (AW) : 132.90573 + Atomic weight ratio (AWR) : 131.76400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 4.53E+05 seconds (5.25 days) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 26 reaction channels + - 6 special reactions + - 10 transmutation reactions + - 8 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 26 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.45210E+00 MeV Emin = 6.50108E+00 MeV frac = 1.00000E+00 Product nuclide = 54132.82c : (n,2n) + 3 MT = 17 Q = -1.53932E+01 MeV Emin = 1.55100E+01 MeV frac = 1.00000E+00 Product nuclide = 54131.82c : (n,3n) + 4 MT = 22 Q = -3.07689E+00 MeV Emin = 3.10025E+00 MeV frac = 1.00000E+00 Product nuclide = 521290 : (n,nalpha) + 5 MT = 28 Q = -9.24963E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 531320 : (n,np) + 6 MT = 32 Q = -1.32706E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 53131.82c : (n,nd) + 7 MT = 51 Q = -2.33200E-01 MeV Emin = 2.34375E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 8 MT = 52 Q = -2.62700E-01 MeV Emin = 2.64152E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 9 MT = 53 Q = -5.29899E-01 MeV Emin = 5.22678E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 10 MT = 54 Q = -6.80199E-01 MeV Emin = 6.61699E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 11 MT = 55 Q = -7.43799E-01 MeV Emin = 7.37084E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 12 MT = 56 Q = -8.75299E-01 MeV Emin = 8.61457E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 13 MT = 57 Q = -9.11499E-01 MeV Emin = 9.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 14 MT = 58 Q = -1.05230E+00 MeV Emin = 1.03015E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 15 MT = 59 Q = -1.23640E+00 MeV Emin = 1.22404E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 16 MT = 60 Q = -1.29820E+00 MeV Emin = 1.29354E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 17 MT = 61 Q = -1.35030E+00 MeV Emin = 1.34086E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 18 MT = 62 Q = -1.38500E+00 MeV Emin = 1.38240E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 19 MT = 63 Q = -1.40480E+00 MeV Emin = 1.40549E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 20 MT = 64 Q = -1.59010E+00 MeV Emin = 1.55109E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 21 MT = 91 Q = -1.65000E+00 MeV Emin = 1.63989E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 22 MT = 102 Q = 8.55221E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 54134.82c : (n,gamma) + 23 MT = 103 Q = -9.77534E-01 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 531330 : (n,p) + 24 MT = 104 Q = -6.93951E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 531320 : (n,d) + 25 MT = 105 Q = -7.08545E+00 MeV Emin = 9.02818E+00 MeV frac = 1.00000E+00 Product nuclide = 53131.82c : (n,t) + 26 MT = 107 Q = 5.34020E+00 MeV Emin = 1.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 52130.82c : (n,alpha) + + 8 additional transport branches: + + 1 MT = 22 Q = -3.07689E+00 MeV Emin = 3.10025E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -9.24963E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.32706E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 102 Q = 8.55221E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 541341 : (n,gamma) + 5 MT = 103 Q = -9.77534E-01 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 104 Q = -6.93951E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 7 MT = 105 Q = -7.08545E+00 MeV Emin = 9.02818E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 8 MT = 107 Q = 5.34020E+00 MeV Emin = 1.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.02818E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-01 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 7.60000E-04 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 2.34375E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.27400E-01 MeV frac = 1.00000E+00 Product nuclide = 55133.82c : beta- + + Nuclide 178 / 1657 : 54134.82c -- xenon 134 (Xe-134) + + Pointers : 1446382 36485 + Primary type : Transport + Nuclide ZAI : 541340 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Xe134.ACE + Atomic weight (AW) : 133.91036 + Atomic weight ratio (AWR) : 132.76000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 3.47E+23 seconds (1.1E+16 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 30 reaction channels + - 6 special reactions + - 9 transmutation reactions + - 7 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 30 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.53690E+00 MeV Emin = 8.60120E+00 MeV frac = 1.00000E+00 Product nuclide = 54133.82c : (n,2n) + 3 MT = 17 Q = -1.49750E+01 MeV Emin = 1.50880E+01 MeV frac = 1.00000E+00 Product nuclide = 54132.82c : (n,3n) + 4 MT = 22 Q = -3.20170E+00 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 52130.82c : (n,nalpha) + 5 MT = 28 Q = -9.52530E+00 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 531330 : (n,np) + 6 MT = 51 Q = -8.47000E-01 MeV Emin = 8.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.61380E+00 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -1.73120E+00 MeV Emin = 1.68510E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -1.91960E+00 MeV Emin = 1.93235E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -1.96550E+00 MeV Emin = 1.95079E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -2.13660E+00 MeV Emin = 2.15270E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -2.27200E+00 MeV Emin = 2.28911E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -2.30220E+00 MeV Emin = 2.31954E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -2.35300E+00 MeV Emin = 2.37073E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -2.40850E+00 MeV Emin = 2.42664E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -2.54750E+00 MeV Emin = 2.56670E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -2.58850E+00 MeV Emin = 2.60800E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -2.65390E+00 MeV Emin = 2.67390E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -2.77290E+00 MeV Emin = 2.79380E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -2.86740E+00 MeV Emin = 2.88900E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 21 MT = 66 Q = -3.08380E+00 MeV Emin = 3.10703E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 22 MT = 67 Q = -3.25570E+00 MeV Emin = 3.28022E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 23 MT = 68 Q = -3.31450E+00 MeV Emin = 3.33950E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 24 MT = 69 Q = -3.36050E+00 MeV Emin = 3.38581E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 25 MT = 91 Q = -3.36050E+00 MeV Emin = 3.38581E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 26 MT = 102 Q = 6.36387E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 54135.82c : (n,gamma) + 27 MT = 103 Q = -3.35250E+00 MeV Emin = 6.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 531340 : (n,p) + 28 MT = 104 Q = -7.30080E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 531330 : (n,d) + 29 MT = 105 Q = -9.28810E+00 MeV Emin = 1.35000E+01 MeV frac = 1.00000E+00 Product nuclide = 531320 : (n,t) + 30 MT = 107 Q = 2.72800E+00 MeV Emin = 7.35580E+00 MeV frac = 1.00000E+00 Product nuclide = 521310 : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -3.20170E+00 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -9.52530E+00 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 102 Q = 6.36387E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 541351 : (n,gamma) + 4 MT = 103 Q = -3.35250E+00 MeV Emin = 6.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -7.30080E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -9.28810E+00 MeV Emin = 1.35000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 107 Q = 2.72800E+00 MeV Emin = 7.35580E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 6.50000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.10000E+01 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.35000E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 7.35580E+00 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 8.01105E-04 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 8.00000E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 11 Q = 8.25800E-01 MeV frac = 1.00000E+00 Product nuclide = 56134.82c : beta- + beta- + + Nuclide 179 / 1657 : 54135.82c -- xenon 135 (Xe-135) + + Pointers : 1450235 36531 + Primary type : Transport + Nuclide ZAI : 541350 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Xe135.ACE + Atomic weight (AW) : 134.90692 + Atomic weight ratio (AWR) : 133.74800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 3.29E+04 seconds (9.14 hours) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 4 reaction channels + - 2 special reactions + - 1 transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 4 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -5.27000E-01 MeV Emin = 5.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 91 Q = -5.27000E-01 MeV Emin = 9.62500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 4 MT = 102 Q = 8.07943E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 54136.82c : (n,gamma) + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 7.80000E-04 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 5.25000E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.16500E+00 MeV frac = 1.00000E+00 Product nuclide = 55135.82c : beta- + + Nuclide 180 / 1657 : 54136.82c -- xenon 136 (Xe-136) + + Pointers : 1451950 36577 + Primary type : Transport + Nuclide ZAI : 541360 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Xe136.ACE + Atomic weight (AW) : 135.90752 + Atomic weight ratio (AWR) : 134.74000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 3.16E+29 seconds (1E+22 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 27 reaction channels + - 6 special reactions + - 9 transmutation reactions + - 6 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 27 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.99480E+00 MeV Emin = 8.05414E+00 MeV frac = 1.00000E+00 Product nuclide = 54135.82c : (n,2n) + 3 MT = 17 Q = -1.44470E+01 MeV Emin = 1.45542E+01 MeV frac = 1.00000E+00 Product nuclide = 54134.82c : (n,3n) + 4 MT = 22 Q = -3.63210E+00 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 52132.82c : (n,nalpha) + 5 MT = 28 Q = -9.89700E+00 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 53135.82c : (n,np) + 6 MT = 51 Q = -1.31300E+00 MeV Emin = 1.25000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.69440E+00 MeV Emin = 1.55000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -1.89170E+00 MeV Emin = 1.80635E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -2.12570E+00 MeV Emin = 2.14150E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -2.26150E+00 MeV Emin = 2.27830E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -2.28950E+00 MeV Emin = 2.30650E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -2.41480E+00 MeV Emin = 2.43272E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -2.46500E+00 MeV Emin = 2.48330E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -2.55990E+00 MeV Emin = 2.57890E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -2.60850E+00 MeV Emin = 2.62790E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -2.63420E+00 MeV Emin = 2.65380E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -2.84930E+00 MeV Emin = 2.87045E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -2.86900E+00 MeV Emin = 2.89030E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -2.97910E+00 MeV Emin = 3.00121E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -3.21190E+00 MeV Emin = 3.23574E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 21 MT = 66 Q = -3.27520E+00 MeV Emin = 3.29951E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 22 MT = 91 Q = -3.27520E+00 MeV Emin = 3.29951E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 23 MT = 102 Q = 4.02554E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 541370 : (n,gamma) + 24 MT = 103 Q = -6.09670E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 531360 : (n,p) + 25 MT = 104 Q = -7.67250E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 53135.82c : (n,d) + 26 MT = 105 Q = -9.31790E+00 MeV Emin = 1.35000E+01 MeV frac = 1.00000E+00 Product nuclide = 531340 : (n,t) + 27 MT = 107 Q = 2.18680E+00 MeV Emin = 7.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 521330 : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = -3.63210E+00 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -9.89700E+00 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -6.09670E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -7.67250E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -9.31790E+00 MeV Emin = 1.35000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 107 Q = 2.18680E+00 MeV Emin = 7.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 9.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.10000E+01 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.35000E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 7.50000E+00 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 7.50000E-04 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 1.25000E+00 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 11 Q = 2.45799E+00 MeV frac = 1.00000E+00 Product nuclide = 56136.82c : beta- + beta- + + Nuclide 181 / 1657 : 55133.82c -- cesium 133 (Cs-133) + + Pointers : 1470109 22501 + Primary type : Transport + Nuclide ZAI : 551330 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Cs133.ACE + Atomic weight (AW) : 132.90573 + Atomic weight ratio (AWR) : 131.76400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 11 reaction channels + - 4 special reactions + - 4 transmutation reactions + - 3 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 11 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -9.03800E+00 MeV Emin = 9.10659E+00 MeV frac = 1.00000E+00 Product nuclide = 551320 : (n,2n) + 3 MT = 51 Q = -8.10000E-02 MeV Emin = 7.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 4 MT = 52 Q = -1.61000E-01 MeV Emin = 1.52610E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 5 MT = 53 Q = -3.84000E-01 MeV Emin = 3.44000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 6 MT = 54 Q = -4.37000E-01 MeV Emin = 4.37000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 7 MT = 55 Q = -6.33000E-01 MeV Emin = 6.18900E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 8 MT = 91 Q = -6.45000E-01 MeV Emin = 6.44000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 9 MT = 102 Q = 6.89155E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 55134.82c : (n,gamma) + 10 MT = 103 Q = 1.21000E-01 MeV Emin = 2.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 54133.82c : (n,p) + 11 MT = 107 Q = 3.69500E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 53130.82c : (n,alpha) + + 3 additional transport branches: + + 1 MT = 102 Q = 6.89155E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 551341 : (n,gamma) + 2 MT = 103 Q = 1.21000E-01 MeV Emin = 2.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 107 Q = 3.69500E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 4 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.50000E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 6.00000E+00 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 8.00000E-04 MeV : damage-energy production + 4 MT = 4 Q = 0.00000E+00 MeV Emin = 7.00000E-02 MeV : total inelastic scattering + + Nuclide 182 / 1657 : 55134.82c -- cesium 134 (Cs-134) + + Pointers : 1471553 22547 + Primary type : Transport + Nuclide ZAI : 551340 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Cs134.ACE + Atomic weight (AW) : 133.90733 + Atomic weight ratio (AWR) : 132.75700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 6.51E+07 seconds (2.07 years) + Specific ingestion toxicity : 1.90E-08 Sv/Bq + Specific inhalation toxicity : 2.00E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 14 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 7 transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 14 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -1.10000E-02 MeV Emin = 1.06250E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -6.30000E-02 MeV Emin = 6.29078E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -1.38000E-01 MeV Emin = 1.37577E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -1.76000E-01 MeV Emin = 1.75154E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -1.93000E-01 MeV Emin = 1.85890E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 91 Q = -2.01490E-01 MeV Emin = 2.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 8 MT = 102 Q = 8.76199E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 55135.82c : (n,gamma) + 9 MT = 103 Q = 1.99800E+00 MeV Emin = 4.54004E-02 MeV frac = 1.00000E+00 Product nuclide = 54134.82c : (n,p) + 10 MT = 104 Q = -4.30980E+00 MeV Emin = 4.34227E+00 MeV frac = 1.00000E+00 Product nuclide = 54133.82c : (n,d) + 11 MT = 105 Q = -4.49950E+00 MeV Emin = 4.53339E+00 MeV frac = 1.00000E+00 Product nuclide = 54132.82c : (n,t) + 12 MT = 106 Q = -8.06010E+00 MeV Emin = 8.12081E+00 MeV frac = 1.00000E+00 Product nuclide = 531320 : (n,He-3) + 13 MT = 107 Q = 6.18640E+00 MeV Emin = 4.54004E-02 MeV frac = 1.00000E+00 Product nuclide = 53131.82c : (n,alpha) + 14 MT = 111 Q = -7.51090E+00 MeV Emin = 7.56748E+00 MeV frac = 1.00000E+00 Product nuclide = 531330 : (n,2p) + + 7 additional transport branches: + + 1 MT = 102 Q = 8.76199E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 551351 : (n,gamma) + 2 MT = 103 Q = 1.99800E+00 MeV Emin = 4.54004E-02 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 104 Q = -4.30980E+00 MeV Emin = 4.34227E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 4 MT = 105 Q = -4.49950E+00 MeV Emin = 4.53339E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 5 MT = 106 Q = -8.06010E+00 MeV Emin = 8.12081E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 6 MT = 107 Q = 6.18640E+00 MeV Emin = 4.54004E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 7 MT = 111 Q = -7.51090E+00 MeV Emin = 7.56748E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.54004E-02 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 4.34227E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 4.53339E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 8.12081E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.54004E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 7.86321E-04 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 1.06250E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 2 Q = 1.23330E+00 MeV frac = 3.00000E-06 Product nuclide = 54134.82c : EC/beta+ + 2 RTYP = 1 Q = 2.05898E+00 MeV frac = 9.99997E-01 Product nuclide = 56134.82c : beta- + + Nuclide 183 / 1657 : 55135.82c -- cesium 135 (Cs-135) + + Pointers : 1475411 22593 + Primary type : Transport + Nuclide ZAI : 551350 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Cs135.ACE + Atomic weight (AW) : 134.90591 + Atomic weight ratio (AWR) : 133.74700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 7.26E+13 seconds (2.3 million years) + Specific ingestion toxicity : 2.00E-09 Sv/Bq + Specific inhalation toxicity : 8.60E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 17 reaction channels + - 6 special reactions + - 11 transmutation reactions + - 9 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 17 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.83209E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 55134.82c : (n,2n) + 3 MT = 17 Q = -1.57282E+01 MeV Emin = 1.58458E+01 MeV frac = 1.00000E+00 Product nuclide = 55133.82c : (n,3n) + 4 MT = 22 Q = -2.63589E+00 MeV Emin = 2.65560E+00 MeV frac = 1.00000E+00 Product nuclide = 53131.82c : (n,nalpha) + 5 MT = 28 Q = -6.83363E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 54134.82c : (n,np) + 6 MT = 32 Q = -1.30626E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 54133.82c : (n,nd) + 7 MT = 33 Q = -1.33296E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 54132.82c : (n,nt) + 8 MT = 51 Q = -2.49800E-01 MeV Emin = 2.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -4.07999E-01 MeV Emin = 4.04466E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -6.08199E-01 MeV Emin = 5.84560E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -7.86899E-01 MeV Emin = 7.69587E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 91 Q = -9.80999E-01 MeV Emin = 9.44168E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 13 MT = 102 Q = 6.82818E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 55136.82c : (n,gamma) + 14 MT = 103 Q = -3.76530E-01 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 54135.82c : (n,p) + 15 MT = 104 Q = -4.52351E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 54134.82c : (n,d) + 16 MT = 105 Q = -6.87746E+00 MeV Emin = 8.89814E+00 MeV frac = 1.00000E+00 Product nuclide = 54133.82c : (n,t) + 17 MT = 107 Q = 3.69520E+00 MeV Emin = 1.01563E-01 MeV frac = 1.00000E+00 Product nuclide = 531320 : (n,alpha) + + 9 additional transport branches: + + 1 MT = 22 Q = -2.63589E+00 MeV Emin = 2.65560E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -6.83363E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.30626E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.33296E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 102 Q = 6.82818E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 551361 : (n,gamma) + 6 MT = 103 Q = -3.76530E-01 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 7 MT = 104 Q = -4.52351E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 8 MT = 105 Q = -6.87746E+00 MeV Emin = 8.89814E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 9 MT = 107 Q = 3.69520E+00 MeV Emin = 1.01563E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 8.89814E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 1.01563E-01 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 7.60000E-04 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 2.50000E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.68700E-01 MeV frac = 1.00000E+00 Product nuclide = 56135.82c : beta- + + Nuclide 184 / 1657 : 55136.82c -- cesium 136 (Cs-136) + + Pointers : 1478424 22639 + Primary type : Transport + Nuclide ZAI : 551360 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Cs136.ACE + Atomic weight (AW) : 135.90752 + Atomic weight ratio (AWR) : 134.74000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.13E+06 seconds (13 days) + Specific ingestion toxicity : 3.00E-09 Sv/Bq + Specific inhalation toxicity : 2.80E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 9 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 6 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 9 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 91 Q = -3.67280E-01 MeV Emin = 3.48750E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 3 MT = 102 Q = 8.27640E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 55137.82c : (n,gamma) + 4 MT = 103 Q = 8.49380E-01 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 54136.82c : (n,p) + 5 MT = 104 Q = -4.91450E+00 MeV Emin = 4.95097E+00 MeV frac = 1.00000E+00 Product nuclide = 54135.82c : (n,d) + 6 MT = 105 Q = -5.10920E+00 MeV Emin = 5.14712E+00 MeV frac = 1.00000E+00 Product nuclide = 54134.82c : (n,t) + 7 MT = 106 Q = -9.24470E+00 MeV Emin = 9.31331E+00 MeV frac = 1.00000E+00 Product nuclide = 531340 : (n,He-3) + 8 MT = 107 Q = 5.18870E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 531330 : (n,alpha) + 9 MT = 111 Q = -9.06530E+00 MeV Emin = 9.13258E+00 MeV frac = 1.00000E+00 Product nuclide = 53135.82c : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = 8.49380E-01 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -4.91450E+00 MeV Emin = 4.95097E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -5.10920E+00 MeV Emin = 5.14712E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -9.24470E+00 MeV Emin = 9.31331E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 5.18870E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -9.06530E+00 MeV Emin = 9.13258E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.62500E-02 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 4.95097E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 5.14712E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 9.31331E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 3.48750E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.54850E+00 MeV frac = 1.00000E+00 Product nuclide = 56136.82c : beta- + + Nuclide 185 / 1657 : 55137.82c -- cesium 137 (Cs-137) + + Pointers : 1481848 22685 + Primary type : Transport + Nuclide ZAI : 551370 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Cs137.ACE + Atomic weight (AW) : 136.90711 + Atomic weight ratio (AWR) : 135.73100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 9.48E+08 seconds (30.1 years) + Specific ingestion toxicity : 1.30E-08 Sv/Bq + Specific inhalation toxicity : 3.90E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 20 reaction channels + - 6 special reactions + - 11 transmutation reactions + - 9 transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 20 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.27810E+00 MeV Emin = 8.33910E+00 MeV frac = 1.00000E+00 Product nuclide = 55136.82c : (n,2n) + 3 MT = 17 Q = -1.50472E+01 MeV Emin = 1.51581E+01 MeV frac = 1.00000E+00 Product nuclide = 55135.82c : (n,3n) + 4 MT = 22 Q = -3.07990E+00 MeV Emin = 3.10259E+00 MeV frac = 1.00000E+00 Product nuclide = 531330 : (n,nalpha) + 5 MT = 28 Q = -7.42864E+00 MeV Emin = 8.33910E+00 MeV frac = 1.00000E+00 Product nuclide = 54136.82c : (n,np) + 6 MT = 32 Q = -1.31136E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 54135.82c : (n,nd) + 7 MT = 33 Q = -1.33856E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 54134.82c : (n,nt) + 8 MT = 51 Q = -4.55999E-01 MeV Emin = 4.56250E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -8.48999E-01 MeV Emin = 8.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -9.79999E-01 MeV Emin = 9.65415E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -1.49000E+00 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -1.87000E+00 MeV Emin = 1.81689E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -2.07000E+00 MeV Emin = 2.08525E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -2.15000E+00 MeV Emin = 2.16584E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 91 Q = -2.30000E+00 MeV Emin = 2.31695E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 16 MT = 102 Q = 4.41313E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 551380 : (n,gamma) + 17 MT = 103 Q = -3.56252E+00 MeV Emin = 5.15624E+00 MeV frac = 1.00000E+00 Product nuclide = 541370 : (n,p) + 18 MT = 104 Q = -5.11852E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 54136.82c : (n,d) + 19 MT = 105 Q = -6.92846E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 54135.82c : (n,t) + 20 MT = 107 Q = 3.06421E+00 MeV Emin = 2.75000E-01 MeV frac = 1.00000E+00 Product nuclide = 531340 : (n,alpha) + + 9 additional transport branches: + + 1 MT = 22 Q = -3.07990E+00 MeV Emin = 3.10259E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -7.42864E+00 MeV Emin = 8.33910E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.31136E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.33856E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 102 Q = 4.41313E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 551381 : (n,gamma) + 6 MT = 103 Q = -3.56252E+00 MeV Emin = 5.15624E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 7 MT = 104 Q = -5.11852E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 8 MT = 105 Q = -6.92846E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 9 MT = 107 Q = 3.06421E+00 MeV Emin = 2.75000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 5.15624E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.00000E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 2.75000E-01 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 8.12500E-04 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 4.56250E-01 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.17563E+00 MeV frac = 5.64058E-02 Product nuclide = 56137.82c : beta- + 2 RTYP = 1 Q = 5.13971E-01 MeV frac = 9.43594E-01 Product nuclide = 561371 : beta- + + Nuclide 186 / 1657 : 56134.82c -- barium 134 (Ba-134) + + Pointers : 1514109 19557 + Primary type : Transport + Nuclide ZAI : 561340 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ba134.ACE + Atomic weight (AW) : 133.90431 + Atomic weight ratio (AWR) : 132.75400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 24 reaction channels + - 6 special reactions + - 9 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 24 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -9.47510E+00 MeV Emin = 9.54648E+00 MeV frac = 1.00000E+00 Product nuclide = 561330 : (n,2n) + 3 MT = 17 Q = -1.66672E+01 MeV Emin = 1.67928E+01 MeV frac = 1.00000E+00 Product nuclide = 561320 : (n,3n) + 4 MT = 22 Q = -1.50880E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 54130.82c : (n,nalpha) + 5 MT = 28 Q = -8.17264E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 55133.82c : (n,np) + 6 MT = 51 Q = -6.04699E-01 MeV Emin = 5.54628E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.16790E+00 MeV Emin = 1.17425E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -1.40060E+00 MeV Emin = 1.37086E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -1.64330E+00 MeV Emin = 1.63949E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -1.76050E+00 MeV Emin = 1.75000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -1.96990E+00 MeV Emin = 1.94518E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -2.02920E+00 MeV Emin = 2.04449E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -2.08830E+00 MeV Emin = 2.10403E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -2.15970E+00 MeV Emin = 2.17597E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -2.25460E+00 MeV Emin = 2.27158E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -2.33680E+00 MeV Emin = 2.35440E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -2.37910E+00 MeV Emin = 2.39702E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -2.48860E+00 MeV Emin = 2.50735E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 91 Q = -2.54000E+00 MeV Emin = 2.55913E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 20 MT = 102 Q = 6.97197E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 56135.82c : (n,gamma) + 21 MT = 103 Q = -1.27654E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 55134.82c : (n,p) + 22 MT = 104 Q = -5.86252E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 55133.82c : (n,d) + 23 MT = 105 Q = -8.66746E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 551320 : (n,t) + 24 MT = 107 Q = 5.10720E+00 MeV Emin = 9.99804E-02 MeV frac = 1.00000E+00 Product nuclide = 54131.82c : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -1.50880E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -8.17264E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 102 Q = 6.97197E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 561351 : (n,gamma) + 4 MT = 103 Q = -1.27654E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -5.86252E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -8.66746E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 107 Q = 5.10720E+00 MeV Emin = 9.99804E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.00000E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 9.99804E-02 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 7.77217E-04 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 5.54628E-01 MeV : total inelastic scattering + + Nuclide 187 / 1657 : 56135.82c -- barium 135 (Ba-135) + + Pointers : 1516940 19603 + Primary type : Transport + Nuclide ZAI : 561350 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ba135.ACE + Atomic weight (AW) : 134.90591 + Atomic weight ratio (AWR) : 133.74700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 20 reaction channels + - 7 special reactions + - 11 transmutation reactions + - 9 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 20 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.97810E+00 MeV Emin = 7.11666E+00 MeV frac = 1.00000E+00 Product nuclide = 56134.82c : (n,2n) + 3 MT = 17 Q = -1.64532E+01 MeV Emin = 1.65762E+01 MeV frac = 1.00000E+00 Product nuclide = 561330 : (n,3n) + 4 MT = 22 Q = -1.87090E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 54131.82c : (n,nalpha) + 5 MT = 28 Q = -8.25464E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 55134.82c : (n,np) + 6 MT = 32 Q = -1.28406E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 55133.82c : (n,nd) + 7 MT = 51 Q = -2.21000E-01 MeV Emin = 2.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 8 MT = 52 Q = -2.68200E-01 MeV Emin = 2.60103E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 9 MT = 53 Q = -4.80599E-01 MeV Emin = 4.83983E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 10 MT = 54 Q = -5.87899E-01 MeV Emin = 5.91338E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 11 MT = 55 Q = -8.54999E-01 MeV Emin = 8.30696E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 12 MT = 56 Q = -8.74499E-01 MeV Emin = 8.80696E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 13 MT = 57 Q = -9.79999E-01 MeV Emin = 9.81956E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 14 MT = 91 Q = -1.17000E+00 MeV Emin = 1.17566E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 15 MT = 102 Q = 9.10739E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 56136.82c : (n,gamma) + 16 MT = 103 Q = 5.77454E-01 MeV Emin = 1.67188E+00 MeV frac = 1.00000E+00 Product nuclide = 55135.82c : (n,p) + 17 MT = 104 Q = -5.94452E+00 MeV Emin = 7.11666E+00 MeV frac = 1.00000E+00 Product nuclide = 55134.82c : (n,d) + 18 MT = 105 Q = -6.65546E+00 MeV Emin = 8.31636E+00 MeV frac = 1.00000E+00 Product nuclide = 55133.82c : (n,t) + 19 MT = 106 Q = -7.06383E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 54133.82c : (n,He-3) + 20 MT = 107 Q = 7.07019E+00 MeV Emin = 9.49999E-02 MeV frac = 1.00000E+00 Product nuclide = 54132.82c : (n,alpha) + + 9 additional transport branches: + + 1 MT = 22 Q = -1.87090E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -8.25464E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.28406E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 102 Q = 9.10739E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 561361 : (n,gamma) + 5 MT = 103 Q = 5.77454E-01 MeV Emin = 1.67188E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 104 Q = -5.94452E+00 MeV Emin = 7.11666E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 7 MT = 105 Q = -6.65546E+00 MeV Emin = 8.31636E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 8 MT = 106 Q = -7.06383E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 9 MT = 107 Q = 7.07019E+00 MeV Emin = 9.49999E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.67188E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.11666E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 8.31636E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.10000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 9.49999E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 2.00000E-01 MeV : total inelastic scattering + + Nuclide 188 / 1657 : 56136.82c -- barium 136 (Ba-136) + + Pointers : 1520069 19649 + Primary type : Transport + Nuclide ZAI : 561360 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ba136.ACE + Atomic weight (AW) : 135.90449 + Atomic weight ratio (AWR) : 134.73700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 21 reaction channels + - 6 special reactions + - 9 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 21 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -9.11209E+00 MeV Emin = 9.17973E+00 MeV frac = 1.00000E+00 Product nuclide = 56135.82c : (n,2n) + 3 MT = 17 Q = -1.60902E+01 MeV Emin = 1.62096E+01 MeV frac = 1.00000E+00 Product nuclide = 56134.82c : (n,3n) + 4 MT = 22 Q = -2.04190E+00 MeV Emin = 2.05706E+00 MeV frac = 1.00000E+00 Product nuclide = 54132.82c : (n,nalpha) + 5 MT = 28 Q = -8.53464E+00 MeV Emin = 9.17973E+00 MeV frac = 1.00000E+00 Product nuclide = 55135.82c : (n,np) + 6 MT = 51 Q = -8.18599E-01 MeV Emin = 8.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.55050E+00 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -1.57920E+00 MeV Emin = 1.58008E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -1.86630E+00 MeV Emin = 1.81507E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -2.05400E+00 MeV Emin = 2.06925E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -2.07990E+00 MeV Emin = 2.09534E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -2.12800E+00 MeV Emin = 2.14379E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -2.14020E+00 MeV Emin = 2.15609E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -2.14150E+00 MeV Emin = 2.15740E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -2.20710E+00 MeV Emin = 2.22348E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 91 Q = -2.28400E+00 MeV Emin = 2.30095E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 17 MT = 102 Q = 6.89839E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 56137.82c : (n,gamma) + 18 MT = 103 Q = -1.76554E+00 MeV Emin = 2.05706E+00 MeV frac = 1.00000E+00 Product nuclide = 55136.82c : (n,p) + 19 MT = 104 Q = -6.22452E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 55135.82c : (n,d) + 20 MT = 105 Q = -8.87146E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 55134.82c : (n,t) + 21 MT = 107 Q = 4.41020E+00 MeV Emin = 1.00098E-01 MeV frac = 1.00000E+00 Product nuclide = 54133.82c : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -2.04190E+00 MeV Emin = 2.05706E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -8.53464E+00 MeV Emin = 9.17973E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 102 Q = 6.89839E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 561371 : (n,gamma) + 4 MT = 103 Q = -1.76554E+00 MeV Emin = 2.05706E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -6.22452E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -8.87146E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 107 Q = 4.41020E+00 MeV Emin = 1.00098E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.05706E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.00000E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00098E-01 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 8.00000E-01 MeV : total inelastic scattering + + Nuclide 189 / 1657 : 56137.82c -- barium 137 (Ba-137) + + Pointers : 1523262 19695 + Primary type : Transport + Nuclide ZAI : 561370 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ba137.ACE + Atomic weight (AW) : 136.90610 + Atomic weight ratio (AWR) : 135.73000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 20 reaction channels + - 6 special reactions + - 10 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 20 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.90309E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 56136.82c : (n,2n) + 3 MT = 17 Q = -1.60152E+01 MeV Emin = 1.61332E+01 MeV frac = 1.00000E+00 Product nuclide = 56135.82c : (n,3n) + 4 MT = 22 Q = -2.49290E+00 MeV Emin = 2.51127E+00 MeV frac = 1.00000E+00 Product nuclide = 54133.82c : (n,nalpha) + 5 MT = 28 Q = -8.66863E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 55136.82c : (n,np) + 6 MT = 32 Q = -1.31276E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 55135.82c : (n,nd) + 7 MT = 51 Q = -2.79200E-01 MeV Emin = 2.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 8 MT = 52 Q = -6.61599E-01 MeV Emin = 6.24856E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 9 MT = 53 Q = -1.29000E+00 MeV Emin = 1.29652E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 10 MT = 54 Q = -1.46290E+00 MeV Emin = 1.45191E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 11 MT = 55 Q = -1.79000E+00 MeV Emin = 1.79934E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 12 MT = 56 Q = -1.84000E+00 MeV Emin = 1.83467E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 13 MT = 57 Q = -1.90000E+00 MeV Emin = 1.91282E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 14 MT = 58 Q = -2.04000E+00 MeV Emin = 2.05503E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 15 MT = 91 Q = -2.12000E+00 MeV Emin = 2.13562E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 16 MT = 102 Q = 8.61139E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 56138.82c : (n,gamma) + 17 MT = 103 Q = -3.90530E-01 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 55137.82c : (n,p) + 18 MT = 104 Q = -6.35851E+00 MeV Emin = 8.14238E+00 MeV frac = 1.00000E+00 Product nuclide = 55136.82c : (n,d) + 19 MT = 105 Q = -6.94246E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 55135.82c : (n,t) + 20 MT = 107 Q = 6.04620E+00 MeV Emin = 9.00000E-02 MeV frac = 1.00000E+00 Product nuclide = 54134.82c : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -2.49290E+00 MeV Emin = 2.51127E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -8.66863E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.31276E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 103 Q = -3.90530E-01 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -6.35851E+00 MeV Emin = 8.14238E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -6.94246E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 107 Q = 6.04620E+00 MeV Emin = 9.00000E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.14238E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.00000E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 9.00000E-02 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 2.50000E-01 MeV : total inelastic scattering + + Nuclide 190 / 1657 : 56138.82c -- barium 138 (Ba-138) + + Pointers : 1526125 19741 + Primary type : Transport + Nuclide ZAI : 561380 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ba138.ACE + Atomic weight (AW) : 137.90467 + Atomic weight ratio (AWR) : 136.72000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 30 reaction channels + - 6 special reactions + - 9 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 30 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.61609E+00 MeV Emin = 8.76750E+00 MeV frac = 1.00000E+00 Product nuclide = 56137.82c : (n,2n) + 3 MT = 17 Q = -1.55192E+01 MeV Emin = 1.56724E+01 MeV frac = 1.00000E+00 Product nuclide = 56136.82c : (n,3n) + 4 MT = 22 Q = -2.56990E+00 MeV Emin = 2.58870E+00 MeV frac = 1.00000E+00 Product nuclide = 54134.82c : (n,nalpha) + 5 MT = 28 Q = -9.00663E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 55137.82c : (n,np) + 6 MT = 51 Q = -1.43590E+00 MeV Emin = 1.38502E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.89870E+00 MeV Emin = 1.83129E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -2.09070E+00 MeV Emin = 2.10599E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -2.18960E+00 MeV Emin = 2.20562E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -2.20320E+00 MeV Emin = 2.21932E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -2.21800E+00 MeV Emin = 2.23422E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -2.30770E+00 MeV Emin = 2.32458E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -2.41560E+00 MeV Emin = 2.43327E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -2.44570E+00 MeV Emin = 2.46359E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -2.58320E+00 MeV Emin = 2.60209E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -2.58400E+00 MeV Emin = 2.60290E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -2.63960E+00 MeV Emin = 2.65891E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -2.77950E+00 MeV Emin = 2.79983E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -2.85170E+00 MeV Emin = 2.87256E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -2.88100E+00 MeV Emin = 2.90207E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 21 MT = 66 Q = -2.93150E+00 MeV Emin = 2.95294E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 22 MT = 67 Q = -2.99120E+00 MeV Emin = 3.01308E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 23 MT = 68 Q = -3.05000E+00 MeV Emin = 3.07231E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 24 MT = 69 Q = -3.15600E+00 MeV Emin = 3.17909E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 25 MT = 91 Q = -3.16360E+00 MeV Emin = 3.18674E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 26 MT = 102 Q = 4.72339E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 561390 : (n,gamma) + 27 MT = 103 Q = -4.72052E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 551380 : (n,p) + 28 MT = 104 Q = -6.69651E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 55137.82c : (n,d) + 29 MT = 105 Q = -8.78946E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 55136.82c : (n,t) + 30 MT = 107 Q = 3.88720E+00 MeV Emin = 1.03125E-01 MeV frac = 1.00000E+00 Product nuclide = 54135.82c : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = -2.56990E+00 MeV Emin = 2.58870E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -9.00663E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -4.72052E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -6.69651E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -8.78946E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 107 Q = 3.88720E+00 MeV Emin = 1.03125E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 6.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.00000E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 1.03125E-01 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 1.38502E+00 MeV : total inelastic scattering + + Nuclide 191 / 1657 : 56140.82c -- barium 140 (Ba-140) + + Pointers : 1530191 19787 + Primary type : Transport + Nuclide ZAI : 561400 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ba140.ACE + Atomic weight (AW) : 139.90990 + Atomic weight ratio (AWR) : 138.70800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.10E+06 seconds (12.8 days) + Specific ingestion toxicity : 2.60E-09 Sv/Bq + Specific inhalation toxicity : 5.80E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 11 reaction channels + - 7 special reactions + - 9 transmutation reactions + - 6 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 11 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.24110E+00 MeV Emin = 6.28700E+00 MeV frac = 1.00000E+00 Product nuclide = 561390 : (n,2n) + 3 MT = 17 Q = -1.09590E+01 MeV Emin = 1.10390E+01 MeV frac = 1.00000E+00 Product nuclide = 56138.82c : (n,3n) + 4 MT = 91 Q = -1.00000E-01 MeV Emin = 1.00350E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 5 MT = 102 Q = 4.82520E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 561410 : (n,gamma) + 6 MT = 103 Q = -5.26050E+00 MeV Emin = 5.29843E+00 MeV frac = 1.00000E+00 Product nuclide = 551400 : (n,p) + 7 MT = 104 Q = -7.71660E+00 MeV Emin = 7.77223E+00 MeV frac = 1.00000E+00 Product nuclide = 551390 : (n,d) + 8 MT = 105 Q = -7.39040E+00 MeV Emin = 7.44368E+00 MeV frac = 1.00000E+00 Product nuclide = 551380 : (n,t) + 9 MT = 106 Q = -1.01110E+01 MeV Emin = 1.01839E+01 MeV frac = 1.00000E+00 Product nuclide = 541380 : (n,He-3) + 10 MT = 107 Q = 4.57490E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 541370 : (n,alpha) + 11 MT = 111 Q = -1.40370E+01 MeV Emin = 1.41382E+01 MeV frac = 1.00000E+00 Product nuclide = 541390 : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = -5.26050E+00 MeV Emin = 5.29843E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -7.71660E+00 MeV Emin = 7.77223E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -7.39040E+00 MeV Emin = 7.44368E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -1.01110E+01 MeV Emin = 1.01839E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 4.57490E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -1.40370E+01 MeV Emin = 1.41382E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 5.29843E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.77223E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 7.44368E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.01839E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 1.00350E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.04800E+00 MeV frac = 1.00000E+00 Product nuclide = 57140.82c : beta- + + Nuclide 192 / 1657 : 57138.82c -- lanthanum 138 (La-138) + + Pointers : 1543591 27285 + Primary type : Transport + Nuclide ZAI : 571380 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/La138.ACE + Atomic weight (AW) : 137.90669 + Atomic weight ratio (AWR) : 136.72200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 3.27E+18 seconds (104 billion years) + Specific ingestion toxicity : 1.10E-09 Sv/Bq + Specific inhalation toxicity : 1.50E-07 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 29 reaction channels + - 7 special reactions + - 12 transmutation reactions + - 9 transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 29 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.47010E+00 MeV Emin = 7.52475E+00 MeV frac = 1.00000E+00 Product nuclide = 571370 : (n,2n) + 3 MT = 17 Q = -1.66362E+01 MeV Emin = 1.67579E+01 MeV frac = 1.00000E+00 Product nuclide = 571360 : (n,3n) + 4 MT = 22 Q = -2.03690E+00 MeV Emin = 2.05180E+00 MeV frac = 1.00000E+00 Product nuclide = 55134.82c : (n,nalpha) + 5 MT = 28 Q = -6.08464E+00 MeV Emin = 7.07320E+00 MeV frac = 1.00000E+00 Product nuclide = 56137.82c : (n,np) + 6 MT = 32 Q = -1.06776E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 56136.82c : (n,nd) + 7 MT = 33 Q = -1.36046E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 56135.82c : (n,nt) + 8 MT = 51 Q = -7.25999E-02 MeV Emin = 7.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -1.16200E-01 MeV Emin = 1.14518E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -1.61200E-01 MeV Emin = 1.56190E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -1.92200E-01 MeV Emin = 1.92900E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -2.30400E-01 MeV Emin = 2.24064E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -2.93000E-01 MeV Emin = 2.83857E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -4.13299E-01 MeV Emin = 3.99965E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -4.79299E-01 MeV Emin = 4.81834E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -5.10499E-01 MeV Emin = 5.07117E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -5.18699E-01 MeV Emin = 5.22083E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -6.42299E-01 MeV Emin = 6.27544E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 62 Q = -7.37699E-01 MeV Emin = 7.21548E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 20 MT = 63 Q = -7.38699E-01 MeV Emin = 7.43596E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 21 MT = 64 Q = -8.23399E-01 MeV Emin = 8.14711E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 22 MT = 65 Q = -8.35999E-01 MeV Emin = 8.35769E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 23 MT = 91 Q = -8.42789E-01 MeV Emin = 8.48446E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 24 MT = 102 Q = 8.77839E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 57139.82c : (n,gamma) + 25 MT = 103 Q = 2.53145E+00 MeV Emin = 1.00182E-01 MeV frac = 1.00000E+00 Product nuclide = 56138.82c : (n,p) + 26 MT = 104 Q = -3.77452E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 56137.82c : (n,d) + 27 MT = 105 Q = -4.49247E+00 MeV Emin = 6.12916E+00 MeV frac = 1.00000E+00 Product nuclide = 56136.82c : (n,t) + 28 MT = 106 Q = -7.02183E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 55136.82c : (n,He-3) + 29 MT = 107 Q = 6.79519E+00 MeV Emin = 9.56249E-02 MeV frac = 1.00000E+00 Product nuclide = 55135.82c : (n,alpha) + + 9 additional transport branches: + + 1 MT = 22 Q = -2.03690E+00 MeV Emin = 2.05180E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -6.08464E+00 MeV Emin = 7.07320E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.06776E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.36046E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 103 Q = 2.53145E+00 MeV Emin = 1.00182E-01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 104 Q = -3.77452E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 7 MT = 105 Q = -4.49247E+00 MeV Emin = 6.12916E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 8 MT = 106 Q = -7.02183E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 9 MT = 107 Q = 6.79519E+00 MeV Emin = 9.56249E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.00182E-01 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 6.12916E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.00000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 9.56249E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 7.00000E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 2 Q = 1.74000E+00 MeV frac = 6.52000E-01 Product nuclide = 56138.82c : EC/beta+ + 2 RTYP = 1 Q = 1.05170E+00 MeV frac = 3.48000E-01 Product nuclide = 581380 : beta- + + Nuclide 193 / 1657 : 57139.82c -- lanthanum 139 (La-139) + + Pointers : 1547474 27331 + Primary type : Transport + Nuclide ZAI : 571390 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/La139.ACE + Atomic weight (AW) : 138.90325 + Atomic weight ratio (AWR) : 137.71000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 23 reaction channels + - 7 special reactions + - 10 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 23 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.77820E+00 MeV Emin = 8.84195E+00 MeV frac = 1.00000E+00 Product nuclide = 57138.82c : (n,2n) + 3 MT = 17 Q = -1.62500E+01 MeV Emin = 1.63680E+01 MeV frac = 1.00000E+00 Product nuclide = 571370 : (n,3n) + 4 MT = 22 Q = -2.00100E+00 MeV Emin = 1.22500E+01 MeV frac = 1.00000E+00 Product nuclide = 55135.82c : (n,nalpha) + 5 MT = 28 Q = -6.25490E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 56138.82c : (n,np) + 6 MT = 51 Q = -1.65900E-01 MeV Emin = 1.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.20900E+00 MeV Emin = 1.21366E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -1.21900E+00 MeV Emin = 1.22434E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -1.25680E+00 MeV Emin = 1.24690E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -1.38130E+00 MeV Emin = 1.32861E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -1.42000E+00 MeV Emin = 1.41082E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -1.42050E+00 MeV Emin = 1.43056E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -1.47630E+00 MeV Emin = 1.45891E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -1.53770E+00 MeV Emin = 1.54503E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -1.53790E+00 MeV Emin = 1.54503E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -1.55840E+00 MeV Emin = 1.55940E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 91 Q = -1.55840E+00 MeV Emin = 2.50000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 18 MT = 102 Q = 5.16098E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 57140.82c : (n,gamma) + 19 MT = 103 Q = -1.53150E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 561390 : (n,p) + 20 MT = 104 Q = -4.03040E+00 MeV Emin = 8.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 56138.82c : (n,d) + 21 MT = 105 Q = -6.38470E+00 MeV Emin = 1.12500E+01 MeV frac = 1.00000E+00 Product nuclide = 56137.82c : (n,t) + 22 MT = 106 Q = -7.54160E+00 MeV Emin = 1.70000E+01 MeV frac = 1.00000E+00 Product nuclide = 55137.82c : (n,He-3) + 23 MT = 107 Q = 4.76230E+00 MeV Emin = 5.25000E+00 MeV frac = 1.00000E+00 Product nuclide = 55136.82c : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -2.00100E+00 MeV Emin = 1.22500E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -6.25490E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -1.53150E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -4.03040E+00 MeV Emin = 8.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -6.38470E+00 MeV Emin = 1.12500E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 106 Q = -7.54160E+00 MeV Emin = 1.70000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 7 MT = 107 Q = 4.76230E+00 MeV Emin = 5.25000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 5.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.50000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.12500E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.70000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 5.25000E+00 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 8.03178E-04 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 1.50000E-01 MeV : total inelastic scattering + + Nuclide 194 / 1657 : 57140.82c -- lanthanum 140 (La-140) + + Pointers : 1550286 27377 + Primary type : Transport + Nuclide ZAI : 571400 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/La140.ACE + Atomic weight (AW) : 139.90990 + Atomic weight ratio (AWR) : 138.70800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.45E+05 seconds (1.68 days) + Specific ingestion toxicity : 2.00E-09 Sv/Bq + Specific inhalation toxicity : 1.10E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 14 reaction channels + - 7 special reactions + - 6 transmutation reactions + - 5 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 14 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -3.00000E-02 MeV Emin = 2.89390E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -4.38000E-02 MeV Emin = 4.38176E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -1.63000E-01 MeV Emin = 1.63993E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -2.50000E-01 MeV Emin = 2.38850E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -4.68000E-01 MeV Emin = 4.20685E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -5.81000E-01 MeV Emin = 5.45500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 91 Q = -5.86770E-01 MeV Emin = 5.45500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 9 MT = 102 Q = 6.73000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 571410 : (n,gamma) + 10 MT = 104 Q = -4.45770E+00 MeV Emin = 4.48984E+00 MeV frac = 1.00000E+00 Product nuclide = 561390 : (n,d) + 11 MT = 105 Q = -2.92400E+00 MeV Emin = 2.94508E+00 MeV frac = 1.00000E+00 Product nuclide = 56138.82c : (n,t) + 12 MT = 106 Q = -8.40700E+00 MeV Emin = 8.46761E+00 MeV frac = 1.00000E+00 Product nuclide = 551380 : (n,He-3) + 13 MT = 107 Q = 7.88380E+00 MeV Emin = 4.87635E-02 MeV frac = 1.00000E+00 Product nuclide = 55137.82c : (n,alpha) + 14 MT = 111 Q = -1.01930E+01 MeV Emin = 1.02665E+01 MeV frac = 1.00000E+00 Product nuclide = 551390 : (n,2p) + + 5 additional transport branches: + + 1 MT = 104 Q = -4.45770E+00 MeV Emin = 4.48984E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 2 MT = 105 Q = -2.92400E+00 MeV Emin = 2.94508E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 3 MT = 106 Q = -8.40700E+00 MeV Emin = 8.46761E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 4 MT = 107 Q = 7.88380E+00 MeV Emin = 4.87635E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 5 MT = 111 Q = -1.01930E+01 MeV Emin = 1.02665E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.02665E+01 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 4.48984E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 2.94508E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 8.46761E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.87635E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 2.89390E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.76090E+00 MeV frac = 1.00000E+00 Product nuclide = 58140.82c : beta- + + Nuclide 195 / 1657 : 58140.82c -- cerium 140 (Ce-140) + + Pointers : 1583778 21075 + Primary type : Transport + Nuclide ZAI : 581400 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ce140.ACE + Atomic weight (AW) : 139.90587 + Atomic weight ratio (AWR) : 138.70400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 17 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 17 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -1.59600E+00 MeV Emin = 1.60000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -1.90200E+00 MeV Emin = 1.88760E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -2.08300E+00 MeV Emin = 2.09802E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -2.10000E+00 MeV Emin = 2.11514E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -2.35000E+00 MeV Emin = 2.36694E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -2.41200E+00 MeV Emin = 2.42940E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 57 Q = -2.52100E+00 MeV Emin = 2.53920E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 9 MT = 58 Q = -2.65300E+00 MeV Emin = 2.67213E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 10 MT = 91 Q = -2.64400E+00 MeV Emin = 2.66306E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 11 MT = 102 Q = 5.42850E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 58141.82c : (n,gamma) + 12 MT = 103 Q = -2.97740E+00 MeV Emin = 2.99887E+00 MeV frac = 1.00000E+00 Product nuclide = 57140.82c : (n,p) + 13 MT = 104 Q = -5.91220E+00 MeV Emin = 5.95483E+00 MeV frac = 1.00000E+00 Product nuclide = 57139.82c : (n,d) + 14 MT = 105 Q = -8.43220E+00 MeV Emin = 8.49299E+00 MeV frac = 1.00000E+00 Product nuclide = 57138.82c : (n,t) + 15 MT = 106 Q = -6.66560E+00 MeV Emin = 6.71366E+00 MeV frac = 1.00000E+00 Product nuclide = 56138.82c : (n,He-3) + 16 MT = 107 Q = 5.29670E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 56137.82c : (n,alpha) + 17 MT = 111 Q = -9.65910E+00 MeV Emin = 9.72874E+00 MeV frac = 1.00000E+00 Product nuclide = 561390 : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = -2.97740E+00 MeV Emin = 2.99887E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -5.91220E+00 MeV Emin = 5.95483E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -8.43220E+00 MeV Emin = 8.49299E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -6.66560E+00 MeV Emin = 6.71366E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 5.29670E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -9.65910E+00 MeV Emin = 9.72874E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.99887E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.95483E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 8.49299E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 6.71366E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 1.60000E+00 MeV : total inelastic scattering + + Nuclide 196 / 1657 : 58141.82c -- cerium 141 (Ce-141) + + Pointers : 1586079 21121 + Primary type : Transport + Nuclide ZAI : 581410 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ce141.ACE + Atomic weight (AW) : 140.91050 + Atomic weight ratio (AWR) : 139.70000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.81E+06 seconds (32.5 days) + Specific ingestion toxicity : 7.10E-10 Sv/Bq + Specific inhalation toxicity : 3.80E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 26 reaction channels + - 7 special reactions + - 10 transmutation reactions + - 7 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 26 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.42760E+00 MeV Emin = 5.46650E+00 MeV frac = 1.00000E+00 Product nuclide = 58140.82c : (n,2n) + 3 MT = 17 Q = -1.46140E+01 MeV Emin = 1.47186E+01 MeV frac = 1.00000E+00 Product nuclide = 581390 : (n,3n) + 4 MT = 22 Q = -1.38080E-01 MeV Emin = 8.73990E+00 MeV frac = 1.00000E+00 Product nuclide = 56137.82c : (n,nalpha) + 5 MT = 28 Q = -8.40660E+00 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 57140.82c : (n,np) + 6 MT = 51 Q = -6.62100E-01 MeV Emin = 6.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.13700E+00 MeV Emin = 1.13657E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -1.35450E+00 MeV Emin = 1.27315E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -1.36870E+00 MeV Emin = 1.37135E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -1.37800E+00 MeV Emin = 1.38320E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -1.49700E+00 MeV Emin = 1.44780E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -1.62650E+00 MeV Emin = 1.57291E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -1.69330E+00 MeV Emin = 1.69699E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -1.73900E+00 MeV Emin = 1.72841E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -1.78500E+00 MeV Emin = 1.79749E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -1.80870E+00 MeV Emin = 1.81283E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -1.81200E+00 MeV Emin = 1.82416E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -1.91500E+00 MeV Emin = 1.87685E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -1.94200E+00 MeV Emin = 1.94230E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 91 Q = -1.94200E+00 MeV Emin = 1.97795E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 21 MT = 102 Q = 7.16970E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 58142.82c : (n,gamma) + 22 MT = 103 Q = -1.67960E+00 MeV Emin = 4.75000E+00 MeV frac = 1.00000E+00 Product nuclide = 571410 : (n,p) + 23 MT = 104 Q = -6.18210E+00 MeV Emin = 9.75000E+00 MeV frac = 1.00000E+00 Product nuclide = 57140.82c : (n,d) + 24 MT = 105 Q = -5.08530E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 57139.82c : (n,t) + 25 MT = 106 Q = -7.38050E+00 MeV Emin = 1.70000E+01 MeV frac = 1.00000E+00 Product nuclide = 561390 : (n,He-3) + 26 MT = 107 Q = 8.47330E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 56138.82c : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -1.38080E-01 MeV Emin = 8.73990E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -8.40660E+00 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -1.67960E+00 MeV Emin = 4.75000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -6.18210E+00 MeV Emin = 9.75000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -5.08530E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 106 Q = -7.38050E+00 MeV Emin = 1.70000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 7 MT = 107 Q = 8.47330E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.75000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 9.75000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.00000E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.70000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 6.00000E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.80400E-01 MeV frac = 1.00000E+00 Product nuclide = 59141.82c : beta- + + Nuclide 197 / 1657 : 58142.82c -- cerium 142 (Ce-142) + + Pointers : 1589398 21167 + Primary type : Transport + Nuclide ZAI : 581420 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ce142.ACE + Atomic weight (AW) : 141.90907 + Atomic weight ratio (AWR) : 140.69000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.58E+24 seconds (5E+16 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 22 reaction channels + - 6 special reactions + - 11 transmutation reactions + - 8 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 22 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.17310E+00 MeV Emin = 7.22409E+00 MeV frac = 1.00000E+00 Product nuclide = 58141.82c : (n,2n) + 3 MT = 17 Q = -1.26062E+01 MeV Emin = 1.26958E+01 MeV frac = 1.00000E+00 Product nuclide = 58140.82c : (n,3n) + 4 MT = 22 Q = 1.31609E+00 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 56138.82c : (n,nalpha) + 5 MT = 28 Q = -8.82063E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 571410 : (n,np) + 6 MT = 32 Q = -1.32746E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 57140.82c : (n,nd) + 7 MT = 33 Q = -1.22546E+01 MeV Emin = 1.33690E+01 MeV frac = 1.00000E+00 Product nuclide = 57139.82c : (n,nt) + 8 MT = 51 Q = -6.41199E-01 MeV Emin = 6.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -1.21930E+00 MeV Emin = 1.17188E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -1.53610E+00 MeV Emin = 1.54107E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -1.65260E+00 MeV Emin = 1.64062E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -2.00420E+00 MeV Emin = 2.01845E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -2.03000E+00 MeV Emin = 2.04443E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -2.18700E+00 MeV Emin = 2.20255E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -2.36400E+00 MeV Emin = 2.38080E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -2.39800E+00 MeV Emin = 2.41505E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 91 Q = -2.50000E+00 MeV Emin = 2.51777E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 18 MT = 102 Q = 5.14484E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 58143.82c : (n,gamma) + 19 MT = 103 Q = -3.73452E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 571420 : (n,p) + 20 MT = 104 Q = -6.51051E+00 MeV Emin = 8.16345E+00 MeV frac = 1.00000E+00 Product nuclide = 571410 : (n,d) + 21 MT = 105 Q = -7.08946E+00 MeV Emin = 8.88334E+00 MeV frac = 1.00000E+00 Product nuclide = 57140.82c : (n,t) + 22 MT = 107 Q = 6.04420E+00 MeV Emin = 8.99999E-02 MeV frac = 1.00000E+00 Product nuclide = 561390 : (n,alpha) + + 8 additional transport branches: + + 1 MT = 22 Q = 1.31609E+00 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -8.82063E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.32746E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.22546E+01 MeV Emin = 1.33690E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 103 Q = -3.73452E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 104 Q = -6.51051E+00 MeV Emin = 8.16345E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 7 MT = 105 Q = -7.08946E+00 MeV Emin = 8.88334E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 8 MT = 107 Q = 6.04420E+00 MeV Emin = 8.99999E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 5.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.16345E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 8.88334E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 8.99999E-02 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 8.55469E-04 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 6.25000E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 11 Q = 1.41720E+00 MeV frac = 1.00000E+00 Product nuclide = 601420 : beta- + beta- + + Nuclide 198 / 1657 : 58143.82c -- cerium 143 (Ce-143) + + Pointers : 1592210 21213 + Primary type : Transport + Nuclide ZAI : 581430 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ce143.ACE + Atomic weight (AW) : 142.91270 + Atomic weight ratio (AWR) : 141.68500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.19E+05 seconds (1.38 days) + Specific ingestion toxicity : 1.10E-09 Sv/Bq + Specific inhalation toxicity : 8.30E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 9 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 6 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 9 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 91 Q = -6.95070E-01 MeV Emin = 6.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 3 MT = 102 Q = 6.94000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 58144.82c : (n,gamma) + 4 MT = 103 Q = -2.51650E+00 MeV Emin = 2.53426E+00 MeV frac = 1.00000E+00 Product nuclide = 571430 : (n,p) + 5 MT = 104 Q = -6.65390E+00 MeV Emin = 6.70086E+00 MeV frac = 1.00000E+00 Product nuclide = 571420 : (n,d) + 6 MT = 105 Q = -5.47810E+00 MeV Emin = 5.51677E+00 MeV frac = 1.00000E+00 Product nuclide = 571410 : (n,t) + 7 MT = 106 Q = -8.48700E+00 MeV Emin = 8.54690E+00 MeV frac = 1.00000E+00 Product nuclide = 561410 : (n,He-3) + 8 MT = 107 Q = 7.31900E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 56140.82c : (n,alpha) + 9 MT = 111 Q = -1.02930E+01 MeV Emin = 1.03657E+01 MeV frac = 1.00000E+00 Product nuclide = 561420 : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = -2.51650E+00 MeV Emin = 2.53426E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -6.65390E+00 MeV Emin = 6.70086E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -5.47810E+00 MeV Emin = 5.51677E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -8.48700E+00 MeV Emin = 8.54690E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 7.31900E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -1.02930E+01 MeV Emin = 1.03657E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.53426E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.70086E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 5.51677E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 8.54690E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.62500E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 6.50000E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.46190E+00 MeV frac = 1.00000E+00 Product nuclide = 59143.82c : beta- + + Nuclide 199 / 1657 : 58144.82c -- cerium 144 (Ce-144) + + Pointers : 1596399 21259 + Primary type : Transport + Nuclide ZAI : 581440 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ce144.ACE + Atomic weight (AW) : 143.91430 + Atomic weight ratio (AWR) : 142.67800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.46E+07 seconds (285 days) + Specific ingestion toxicity : 5.20E-09 Sv/Bq + Specific inhalation toxicity : 5.30E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 15 reaction channels + - 6 special reactions + - 11 transmutation reactions + - 8 transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 15 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.89710E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 58143.82c : (n,2n) + 3 MT = 17 Q = -1.20482E+01 MeV Emin = 1.21327E+01 MeV frac = 1.00000E+00 Product nuclide = 58142.82c : (n,3n) + 4 MT = 22 Q = 4.32094E-01 MeV Emin = 1.38519E+00 MeV frac = 1.00000E+00 Product nuclide = 56140.82c : (n,nalpha) + 5 MT = 28 Q = -9.41463E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 571430 : (n,np) + 6 MT = 32 Q = -1.34726E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 571420 : (n,nd) + 7 MT = 33 Q = -1.23736E+01 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 571410 : (n,nt) + 8 MT = 51 Q = -3.97299E-01 MeV Emin = 3.50042E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -9.38399E-01 MeV Emin = 9.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 91 Q = -1.24220E+00 MeV Emin = 1.25000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 11 MT = 102 Q = 4.73117E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 581450 : (n,gamma) + 12 MT = 103 Q = -4.71852E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 571440 : (n,p) + 13 MT = 104 Q = -7.10451E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 571430 : (n,d) + 14 MT = 105 Q = -7.28746E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 571420 : (n,t) + 15 MT = 107 Q = 5.20319E+00 MeV Emin = 1.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 561410 : (n,alpha) + + 8 additional transport branches: + + 1 MT = 22 Q = 4.32094E-01 MeV Emin = 1.38519E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -9.41463E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.34726E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.23736E+01 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 103 Q = -4.71852E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 104 Q = -7.10451E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 7 MT = 105 Q = -7.28746E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 8 MT = 107 Q = 5.20319E+00 MeV Emin = 1.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 6.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 9.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 9.00000E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-01 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 8.50000E-04 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 3.50042E-01 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 1 Q = 3.18600E-01 MeV frac = 9.88508E-01 Product nuclide = 591440 : beta- + 2 RTYP = 1 Q = 2.59569E-01 MeV frac = 1.14915E-02 Product nuclide = 591441 : beta- + + Nuclide 200 / 1657 : 59141.82c -- praseodymium 141 (Pr-141) + + Pointers : 1619693 30413 + Primary type : Transport + Nuclide ZAI : 591410 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Pr141.ACE + Atomic weight (AW) : 140.90747 + Atomic weight ratio (AWR) : 139.69700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 24 reaction channels + - 28 special reactions + - 9 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 24 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -9.39700E+00 MeV Emin = 9.46427E+00 MeV frac = 1.00000E+00 Product nuclide = 591400 : (n,2n) + 3 MT = 17 Q = -1.73390E+01 MeV Emin = 1.74631E+01 MeV frac = 1.00000E+00 Product nuclide = 591390 : (n,3n) + 4 MT = 22 Q = -1.32400E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 571370 : (n,nalpha) + 5 MT = 24 Q = -1.05000E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 571360 : (n,2nalpha) + 6 MT = 28 Q = -5.22700E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 58140.82c : (n,np) + 7 MT = 41 Q = -1.44280E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 581390 : (n,2np) + 8 MT = 51 Q = -1.45440E-01 MeV Emin = 1.43235E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -1.11770E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -1.12680E+00 MeV Emin = 1.13028E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -1.29260E+00 MeV Emin = 1.30000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -1.29860E+00 MeV Emin = 1.30395E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -1.43630E+00 MeV Emin = 1.37724E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -1.45220E+00 MeV Emin = 1.45459E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -1.45550E+00 MeV Emin = 1.46521E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -1.45740E+00 MeV Emin = 1.46718E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -1.49410E+00 MeV Emin = 1.50240E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -1.51300E+00 MeV Emin = 1.51432E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 62 Q = -1.52100E+00 MeV Emin = 1.52786E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 20 MT = 63 Q = -1.58000E+00 MeV Emin = 1.56160E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 21 MT = 91 Q = -1.27785E+00 MeV Emin = 1.23621E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 22 MT = 102 Q = 5.84315E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 59142.82c : (n,gamma) + 23 MT = 103 Q = 0.00000E+00 MeV Emin = 1.29350E+00 MeV frac = 1.00000E+00 Product nuclide = 58141.82c : (n,p) + 24 MT = 107 Q = 0.00000E+00 MeV Emin = 1.10000E-01 MeV frac = 1.00000E+00 Product nuclide = 57138.82c : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -1.32400E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 24 Q = -1.05000E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,2nalpha) + 3 MT = 28 Q = -5.22700E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 4 MT = 41 Q = -1.44280E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,2np) + 5 MT = 102 Q = 5.84315E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 591421 : (n,gamma) + 6 MT = 103 Q = 0.00000E+00 MeV Emin = 1.29350E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 7 MT = 107 Q = 0.00000E+00 MeV Emin = 1.10000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 28 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.29350E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 1.10000E-01 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 8.85156E-04 MeV : damage-energy production + 4 MT = 600 Q = 2.01000E-01 MeV Emin = 1.29350E+00 MeV : (n,p) to ground state + 5 MT = 601 Q = -4.61060E-01 MeV Emin = 1.90000E+00 MeV : (n,p1) + 6 MT = 602 Q = -9.36000E-01 MeV Emin = 2.00000E+00 MeV : (n,p2) + 7 MT = 603 Q = -1.15352E+00 MeV Emin = 2.60000E+00 MeV : (n,p3) + 8 MT = 604 Q = -1.16770E+00 MeV Emin = 2.60000E+00 MeV : (n,p4) + 9 MT = 605 Q = -1.17700E+00 MeV Emin = 2.60000E+00 MeV : (n,p5) + 10 MT = 606 Q = -1.29600E+00 MeV Emin = 2.60000E+00 MeV : (n,p6) + 11 MT = 607 Q = -1.42550E+00 MeV Emin = 3.00000E+00 MeV : (n,p7) + 12 MT = 608 Q = -1.49230E+00 MeV Emin = 3.00000E+00 MeV : (n,p8) + 13 MT = 609 Q = -1.53800E+00 MeV Emin = 3.00000E+00 MeV : (n,p9) + 14 MT = 610 Q = -1.58400E+00 MeV Emin = 3.00000E+00 MeV : (n,p10) + 15 MT = 611 Q = -1.60770E+00 MeV Emin = 3.00000E+00 MeV : (n,p11) + 16 MT = 612 Q = -1.61100E+00 MeV Emin = 3.00000E+00 MeV : (n,p12) + 17 MT = 613 Q = -1.71400E+00 MeV Emin = 3.00000E+00 MeV : (n,p13) + 18 MT = 614 Q = -1.74100E+00 MeV Emin = 3.00000E+00 MeV : (n,p14) + 19 MT = 649 Q = -1.74100E+00 MeV Emin = 3.00000E+00 MeV : (n,p) to continuum + 20 MT = 800 Q = 6.14900E+00 MeV Emin = 1.10000E-01 MeV : (n,alpha) to ground state + 21 MT = 801 Q = 6.07643E+00 MeV Emin = 1.10000E-01 MeV : (n,a1) + 22 MT = 802 Q = 6.03283E+00 MeV Emin = 1.10000E-01 MeV : (n,a2) + 23 MT = 803 Q = 5.98782E+00 MeV Emin = 1.10000E-01 MeV : (n,a3) + 24 MT = 804 Q = 5.95681E+00 MeV Emin = 1.10000E-01 MeV : (n,a4) + 25 MT = 805 Q = 5.91859E+00 MeV Emin = 1.10000E-01 MeV : (n,a5) + 26 MT = 806 Q = 5.85602E+00 MeV Emin = 1.70000E-01 MeV : (n,a6) + 27 MT = 849 Q = 5.85602E+00 MeV Emin = 1.70000E-01 MeV : (n,alpha) to continuum + 28 MT = 4 Q = 0.00000E+00 MeV Emin = 1.43235E-01 MeV : total inelastic scattering + + Nuclide 201 / 1657 : 59142.82c -- praseodymium 142 (Pr-142) + + Pointers : 1624130 30459 + Primary type : Transport + Nuclide ZAI : 591420 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Pr142.ACE + Atomic weight (AW) : 141.91008 + Atomic weight ratio (AWR) : 140.69100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 6.88E+04 seconds (19.1 hours) + Specific ingestion toxicity : 1.30E-09 Sv/Bq + Specific inhalation toxicity : 5.50E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 9 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 6 transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 9 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 91 Q = -1.98590E-01 MeV Emin = 1.87500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 3 MT = 102 Q = 7.21000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 59143.82c : (n,gamma) + 4 MT = 103 Q = 1.52720E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 58142.82c : (n,p) + 5 MT = 104 Q = -3.41500E+00 MeV Emin = 3.43927E+00 MeV frac = 1.00000E+00 Product nuclide = 58141.82c : (n,d) + 6 MT = 105 Q = -2.58610E+00 MeV Emin = 2.60448E+00 MeV frac = 1.00000E+00 Product nuclide = 58140.82c : (n,t) + 7 MT = 106 Q = -6.32770E+00 MeV Emin = 6.37268E+00 MeV frac = 1.00000E+00 Product nuclide = 57140.82c : (n,He-3) + 8 MT = 107 Q = 9.08440E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 57139.82c : (n,alpha) + 9 MT = 111 Q = -7.28590E+00 MeV Emin = 7.33769E+00 MeV frac = 1.00000E+00 Product nuclide = 571410 : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = 1.52720E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -3.41500E+00 MeV Emin = 3.43927E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -2.58610E+00 MeV Emin = 2.60448E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -6.32770E+00 MeV Emin = 6.37268E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 9.08440E+00 MeV Emin = 4.62500E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -7.28590E+00 MeV Emin = 7.33769E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.62500E-02 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 3.43927E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 2.60448E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 6.37268E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.62500E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 1.87500E-01 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 2 Q = 7.45800E-01 MeV frac = 1.64000E-04 Product nuclide = 58142.82c : EC/beta+ + 2 RTYP = 1 Q = 2.16220E+00 MeV frac = 9.99800E-01 Product nuclide = 601420 : beta- + + Nuclide 202 / 1657 : 59143.82c -- praseodymium 143 (Pr-143) + + Pointers : 1626378 30505 + Primary type : Transport + Nuclide ZAI : 591430 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Pr143.ACE + Atomic weight (AW) : 142.91068 + Atomic weight ratio (AWR) : 141.68300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.17E+06 seconds (13.6 days) + Specific ingestion toxicity : 1.20E-09 Sv/Bq + Specific inhalation toxicity : 2.40E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 24 reaction channels + - 7 special reactions + - 12 transmutation reactions + - 10 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 24 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.35110E+00 MeV Emin = 7.40299E+00 MeV frac = 1.00000E+00 Product nuclide = 59142.82c : (n,2n) + 3 MT = 17 Q = -1.31992E+01 MeV Emin = 1.32924E+01 MeV frac = 1.00000E+00 Product nuclide = 59141.82c : (n,3n) + 4 MT = 22 Q = 1.74409E+00 MeV Emin = 9.99804E-02 MeV frac = 1.00000E+00 Product nuclide = 57139.82c : (n,nalpha) + 5 MT = 28 Q = -5.82363E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 58142.82c : (n,np) + 6 MT = 32 Q = -1.06866E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 58141.82c : (n,nd) + 7 MT = 33 Q = -9.93458E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 58140.82c : (n,nt) + 8 MT = 51 Q = -5.73999E-02 MeV Emin = 5.58538E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -3.50600E-01 MeV Emin = 3.26537E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -4.90399E-01 MeV Emin = 4.74063E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -7.21899E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -7.40099E-01 MeV Emin = 7.38451E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -9.37799E-01 MeV Emin = 9.38525E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -1.06030E+00 MeV Emin = 1.03389E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -1.16040E+00 MeV Emin = 1.14496E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -1.38200E+00 MeV Emin = 1.35631E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -1.39770E+00 MeV Emin = 1.40163E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 91 Q = -1.52600E+00 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 19 MT = 102 Q = 5.75347E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 591440 : (n,gamma) + 20 MT = 103 Q = -6.72533E-01 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 58143.82c : (n,p) + 21 MT = 104 Q = -3.51351E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 58142.82c : (n,d) + 22 MT = 105 Q = -4.50146E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 58141.82c : (n,t) + 23 MT = 106 Q = -6.91283E+00 MeV Emin = 1.00047E+01 MeV frac = 1.00000E+00 Product nuclide = 571410 : (n,He-3) + 24 MT = 107 Q = 6.90920E+00 MeV Emin = 9.99608E-02 MeV frac = 1.00000E+00 Product nuclide = 57140.82c : (n,alpha) + + 10 additional transport branches: + + 1 MT = 22 Q = 1.74409E+00 MeV Emin = 9.99804E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -5.82363E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.06866E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -9.93458E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 102 Q = 5.75347E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 591441 : (n,gamma) + 6 MT = 103 Q = -6.72533E-01 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 7 MT = 104 Q = -3.51351E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 8 MT = 105 Q = -4.50146E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 9 MT = 106 Q = -6.91283E+00 MeV Emin = 1.00047E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 10 MT = 107 Q = 6.90920E+00 MeV Emin = 9.99608E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 6.00000E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.00047E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 9.99608E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 8.50000E-04 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 5.58538E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.33900E-01 MeV frac = 1.00000E+00 Product nuclide = 601430 : beta- + + Nuclide 203 / 1657 : 60144.82c -- neodymium 144 (Nd-144) + + Pointers : 1657626 28573 + Primary type : Transport + Nuclide ZAI : 601440 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Nd144.ACE + Atomic weight (AW) : 143.91027 + Atomic weight ratio (AWR) : 142.67400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 7.23E+22 seconds (2.29E+15 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 50 reaction channels + - 18 special reactions + - 9 transmutation reactions + - 6 transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 50 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.81600E+00 MeV Emin = 7.87078E+00 MeV frac = 1.00000E+00 Product nuclide = 601430 : (n,2n) + 3 MT = 17 Q = -1.39390E+01 MeV Emin = 1.40367E+01 MeV frac = 1.00000E+00 Product nuclide = 601420 : (n,3n) + 4 MT = 22 Q = 1.90600E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 58140.82c : (n,nalpha) + 5 MT = 24 Q = -7.29500E+00 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 581390 : (n,2nalpha) + 6 MT = 28 Q = -7.96800E+00 MeV Emin = 8.02385E+00 MeV frac = 1.00000E+00 Product nuclide = 59143.82c : (n,np) + 7 MT = 41 Q = -1.53200E+01 MeV Emin = 1.70000E+01 MeV frac = 1.00000E+00 Product nuclide = 59142.82c : (n,2np) + 8 MT = 51 Q = -6.96510E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -1.31454E+00 MeV Emin = 1.30000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -1.51053E+00 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -1.56091E+00 MeV Emin = 1.54649E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -1.79145E+00 MeV Emin = 1.80000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -2.07274E+00 MeV Emin = 2.08727E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -2.08445E+00 MeV Emin = 2.09906E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -2.09346E+00 MeV Emin = 2.10813E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -2.10946E+00 MeV Emin = 2.12425E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -2.17837E+00 MeV Emin = 2.19364E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -2.18568E+00 MeV Emin = 2.20100E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 62 Q = -2.20458E+00 MeV Emin = 2.22003E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 20 MT = 63 Q = -2.21812E+00 MeV Emin = 2.23367E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 21 MT = 64 Q = -2.27012E+00 MeV Emin = 2.28603E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 22 MT = 65 Q = -2.29510E+00 MeV Emin = 2.31119E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 23 MT = 66 Q = -2.32170E+00 MeV Emin = 2.33797E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 24 MT = 67 Q = -2.36823E+00 MeV Emin = 2.38483E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 25 MT = 68 Q = -2.39940E+00 MeV Emin = 2.41622E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 26 MT = 69 Q = -2.41993E+00 MeV Emin = 2.43689E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 27 MT = 70 Q = -2.44720E+00 MeV Emin = 2.46435E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 28 MT = 71 Q = -2.45127E+00 MeV Emin = 2.46845E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 29 MT = 72 Q = -2.50841E+00 MeV Emin = 2.52599E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 30 MT = 73 Q = -2.52692E+00 MeV Emin = 2.54463E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 31 MT = 74 Q = -2.56384E+00 MeV Emin = 2.58181E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 32 MT = 75 Q = -2.58165E+00 MeV Emin = 2.59975E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 33 MT = 76 Q = -2.59177E+00 MeV Emin = 2.60994E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 34 MT = 77 Q = -2.60079E+00 MeV Emin = 2.61902E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 27. excited state + 35 MT = 78 Q = -2.60508E+00 MeV Emin = 2.62334E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 28. excited state + 36 MT = 79 Q = -2.61257E+00 MeV Emin = 2.63088E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 29. excited state + 37 MT = 80 Q = -2.61390E+00 MeV Emin = 2.63222E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 30. excited state + 38 MT = 81 Q = -2.65460E+00 MeV Emin = 2.67321E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 31. excited state + 39 MT = 82 Q = -2.65478E+00 MeV Emin = 2.67339E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 32. excited state + 40 MT = 83 Q = -2.67533E+00 MeV Emin = 2.69408E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 33. excited state + 41 MT = 84 Q = -2.68134E+00 MeV Emin = 2.70013E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 34. excited state + 42 MT = 85 Q = -2.69264E+00 MeV Emin = 2.71151E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 35. excited state + 43 MT = 86 Q = -2.70988E+00 MeV Emin = 2.72887E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 36. excited state + 44 MT = 87 Q = -2.71537E+00 MeV Emin = 2.73440E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 37. excited state + 45 MT = 88 Q = -2.71910E+00 MeV Emin = 2.73816E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 38. excited state + 46 MT = 89 Q = -2.73208E+00 MeV Emin = 2.75123E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 39. excited state + 47 MT = 91 Q = -6.88177E-01 MeV Emin = 6.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 48 MT = 102 Q = 5.75529E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 60145.82c : (n,gamma) + 49 MT = 103 Q = 0.00000E+00 MeV Emin = 3.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 591440 : (n,p) + 50 MT = 107 Q = 0.00000E+00 MeV Emin = 2.75000E-01 MeV frac = 1.00000E+00 Product nuclide = 58141.82c : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = 1.90600E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 24 Q = -7.29500E+00 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,2nalpha) + 3 MT = 28 Q = -7.96800E+00 MeV Emin = 8.02385E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 4 MT = 41 Q = -1.53200E+01 MeV Emin = 1.70000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,2np) + 5 MT = 103 Q = 0.00000E+00 MeV Emin = 3.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 107 Q = 0.00000E+00 MeV Emin = 2.75000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 18 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.50000E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 2.75000E-01 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 8.83648E-04 MeV : damage-energy production + 4 MT = 600 Q = -2.21500E+00 MeV Emin = 3.50000E+00 MeV : (n,p) to ground state + 5 MT = 649 Q = -2.21500E+00 MeV Emin = 3.50000E+00 MeV : (n,p) to continuum + 6 MT = 800 Q = 7.33400E+00 MeV Emin = 2.75000E-01 MeV : (n,alpha) to ground state + 7 MT = 801 Q = 6.67194E+00 MeV Emin = 2.75000E-01 MeV : (n,a1) + 8 MT = 802 Q = 6.19700E+00 MeV Emin = 2.75000E-01 MeV : (n,a2) + 9 MT = 803 Q = 5.97948E+00 MeV Emin = 2.75000E-01 MeV : (n,a3) + 10 MT = 804 Q = 5.96530E+00 MeV Emin = 3.00000E-01 MeV : (n,a4) + 11 MT = 805 Q = 5.95600E+00 MeV Emin = 2.75000E-01 MeV : (n,a5) + 12 MT = 806 Q = 5.83700E+00 MeV Emin = 2.75000E-01 MeV : (n,a6) + 13 MT = 807 Q = 5.70750E+00 MeV Emin = 3.00000E-01 MeV : (n,a7) + 14 MT = 808 Q = 5.64070E+00 MeV Emin = 4.00000E-01 MeV : (n,a8) + 15 MT = 809 Q = 5.59500E+00 MeV Emin = 5.00000E-01 MeV : (n,a9) + 16 MT = 810 Q = 5.54900E+00 MeV Emin = 5.00000E-01 MeV : (n,a10) + 17 MT = 849 Q = 5.54900E+00 MeV Emin = 2.75000E-01 MeV : (n,alpha) to continuum + 18 MT = 4 Q = 0.00000E+00 MeV Emin = 6.00000E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 4 Q = 1.90520E+00 MeV frac = 1.00000E+00 Product nuclide = 58140.82c : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 1.90520E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 204 / 1657 : 60145.82c -- neodymium 145 (Nd-145) + + Pointers : 1663318 28619 + Primary type : Transport + Nuclide ZAI : 601450 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Nd145.ACE + Atomic weight (AW) : 144.91288 + Atomic weight ratio (AWR) : 143.66800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 24 reaction channels + - 7 special reactions + - 8 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 24 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.71550E+00 MeV Emin = 5.75530E+00 MeV frac = 1.00000E+00 Product nuclide = 60144.82c : (n,2n) + 3 MT = 51 Q = -6.72000E-02 MeV Emin = 6.72000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 4 MT = 52 Q = -7.24000E-02 MeV Emin = 7.24000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 5 MT = 53 Q = -5.06600E-01 MeV Emin = 5.06600E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 6 MT = 54 Q = -6.57600E-01 MeV Emin = 6.57600E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 7 MT = 55 Q = -7.48200E-01 MeV Emin = 7.50400E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 8 MT = 56 Q = -7.80300E-01 MeV Emin = 7.80300E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 9 MT = 57 Q = -8.40700E-01 MeV Emin = 8.40733E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 10 MT = 58 Q = -9.20200E-01 MeV Emin = 9.23552E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 11 MT = 59 Q = -9.20500E-01 MeV Emin = 9.26681E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 12 MT = 60 Q = -9.34000E-01 MeV Emin = 9.34000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 13 MT = 61 Q = -1.05100E+00 MeV Emin = 1.05120E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 14 MT = 62 Q = -1.08500E+00 MeV Emin = 1.08490E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 15 MT = 63 Q = -1.11200E+00 MeV Emin = 1.11200E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 16 MT = 64 Q = -1.15000E+00 MeV Emin = 1.15000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 17 MT = 91 Q = -1.15300E+00 MeV Emin = 1.16096E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 18 MT = 102 Q = 7.56524E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 60146.82c : (n,gamma) + 19 MT = 103 Q = -7.24300E-01 MeV Emin = 6.95759E-01 MeV frac = 1.00000E+00 Product nuclide = 591450 : (n,p) + 20 MT = 104 Q = -6.06970E+00 MeV Emin = 6.11195E+00 MeV frac = 1.00000E+00 Product nuclide = 591440 : (n,d) + 21 MT = 105 Q = -5.24730E+00 MeV Emin = 5.28383E+00 MeV frac = 1.00000E+00 Product nuclide = 59143.82c : (n,t) + 22 MT = 106 Q = -7.00850E+00 MeV Emin = 7.05730E+00 MeV frac = 1.00000E+00 Product nuclide = 58143.82c : (n,He-3) + 23 MT = 107 Q = 8.75200E+00 MeV Emin = 4.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 58142.82c : (n,alpha) + 24 MT = 111 Q = -7.50280E+00 MeV Emin = 7.55502E+00 MeV frac = 1.00000E+00 Product nuclide = 58144.82c : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = -7.24300E-01 MeV Emin = 6.95759E-01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -6.06970E+00 MeV Emin = 6.11195E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -5.24730E+00 MeV Emin = 5.28383E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -7.00850E+00 MeV Emin = 7.05730E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 8.75200E+00 MeV Emin = 4.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -7.50280E+00 MeV Emin = 7.55502E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 6.95759E-01 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.11195E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 5.28383E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 7.05730E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.00000E-01 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 8.85850E-04 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 6.72000E-02 MeV : total inelastic scattering + + Nuclide 205 / 1657 : 60146.82c -- neodymium 146 (Nd-146) + + Pointers : 1666130 28665 + Primary type : Transport + Nuclide ZAI : 601460 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Nd146.ACE + Atomic weight (AW) : 145.91347 + Atomic weight ratio (AWR) : 144.66000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 33 reaction channels + - 24 special reactions + - 9 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 33 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.56500E+00 MeV Emin = 7.61730E+00 MeV frac = 1.00000E+00 Product nuclide = 60145.82c : (n,2n) + 3 MT = 17 Q = -1.33210E+01 MeV Emin = 1.34131E+01 MeV frac = 1.00000E+00 Product nuclide = 60144.82c : (n,3n) + 4 MT = 22 Q = 1.18200E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 58142.82c : (n,nalpha) + 5 MT = 24 Q = -5.98700E+00 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 58141.82c : (n,2nalpha) + 6 MT = 28 Q = -8.58900E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 591450 : (n,np) + 7 MT = 41 Q = -1.55360E+01 MeV Emin = 1.70000E+01 MeV frac = 1.00000E+00 Product nuclide = 591440 : (n,2np) + 8 MT = 51 Q = -4.53860E-01 MeV Emin = 4.56000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -9.15500E-01 MeV Emin = 9.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -1.04317E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -1.18951E+00 MeV Emin = 1.10000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -1.30320E+00 MeV Emin = 1.30000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -1.37675E+00 MeV Emin = 1.34924E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -1.47060E+00 MeV Emin = 1.44038E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -1.51770E+00 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -1.60270E+00 MeV Emin = 1.60000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -1.69710E+00 MeV Emin = 1.70000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -1.74510E+00 MeV Emin = 1.73300E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 62 Q = -1.76970E+00 MeV Emin = 1.76955E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 20 MT = 63 Q = -1.77720E+00 MeV Emin = 1.78571E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 21 MT = 64 Q = -1.78010E+00 MeV Emin = 1.79095E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 22 MT = 65 Q = -1.78740E+00 MeV Emin = 1.79608E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 23 MT = 66 Q = -1.81200E+00 MeV Emin = 1.81226E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 24 MT = 67 Q = -1.83400E+00 MeV Emin = 1.83560E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 25 MT = 68 Q = -1.88470E+00 MeV Emin = 1.87220E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 26 MT = 69 Q = -1.90540E+00 MeV Emin = 1.90928E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 27 MT = 70 Q = -1.91890E+00 MeV Emin = 1.92537E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 28 MT = 71 Q = -1.97794E+00 MeV Emin = 1.96189E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 29 MT = 72 Q = -1.98930E+00 MeV Emin = 2.00305E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 30 MT = 91 Q = -6.88242E-01 MeV Emin = 6.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 31 MT = 102 Q = 5.29221E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 60147.82c : (n,gamma) + 32 MT = 103 Q = 0.00000E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 591460 : (n,p) + 33 MT = 107 Q = 0.00000E+00 MeV Emin = 1.70000E-02 MeV frac = 1.00000E+00 Product nuclide = 58143.82c : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = 1.18200E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 24 Q = -5.98700E+00 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,2nalpha) + 3 MT = 28 Q = -8.58900E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 4 MT = 41 Q = -1.55360E+01 MeV Emin = 1.70000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,2np) + 5 MT = 103 Q = 0.00000E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 107 Q = 0.00000E+00 MeV Emin = 1.70000E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 24 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.00000E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 1.70000E-02 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 8.85156E-04 MeV : damage-energy production + 4 MT = 600 Q = -3.38800E+00 MeV Emin = 4.00000E+00 MeV : (n,p) to ground state + 5 MT = 601 Q = -3.40023E+00 MeV Emin = 4.00000E+00 MeV : (n,p1) + 6 MT = 602 Q = -3.42305E+00 MeV Emin = 5.00000E+00 MeV : (n,p2) + 7 MT = 603 Q = -3.47519E+00 MeV Emin = 5.00000E+00 MeV : (n,p3) + 8 MT = 604 Q = -3.48888E+00 MeV Emin = 5.00000E+00 MeV : (n,p4) + 9 MT = 605 Q = -3.52152E+00 MeV Emin = 5.00000E+00 MeV : (n,p5) + 10 MT = 649 Q = -3.52152E+00 MeV Emin = 5.00000E+00 MeV : (n,p) to continuum + 11 MT = 800 Q = 6.32600E+00 MeV Emin = 1.70000E-02 MeV : (n,alpha) to ground state + 12 MT = 801 Q = 6.30710E+00 MeV Emin = 1.70000E-02 MeV : (n,a1) + 13 MT = 802 Q = 6.28372E+00 MeV Emin = 1.70000E-02 MeV : (n,a2) + 14 MT = 803 Q = 5.69350E+00 MeV Emin = 4.00000E-01 MeV : (n,a3) + 15 MT = 804 Q = 5.68570E+00 MeV Emin = 4.00000E-01 MeV : (n,a4) + 16 MT = 805 Q = 5.66330E+00 MeV Emin = 4.78499E-01 MeV : (n,a5) + 17 MT = 806 Q = 5.51780E+00 MeV Emin = 5.50000E-01 MeV : (n,a6) + 18 MT = 807 Q = 5.50900E+00 MeV Emin = 5.50000E-01 MeV : (n,a7) + 19 MT = 808 Q = 5.46390E+00 MeV Emin = 6.00000E-01 MeV : (n,a8) + 20 MT = 809 Q = 5.23070E+00 MeV Emin = 8.00000E-01 MeV : (n,a9) + 21 MT = 810 Q = 5.20920E+00 MeV Emin = 8.00000E-01 MeV : (n,a10) + 22 MT = 811 Q = 5.17190E+00 MeV Emin = 8.00000E-01 MeV : (n,a11) + 23 MT = 849 Q = 5.17190E+00 MeV Emin = 7.00000E-02 MeV : (n,alpha) to continuum + 24 MT = 4 Q = 0.00000E+00 MeV Emin = 4.56000E-01 MeV : total inelastic scattering + + Nuclide 206 / 1657 : 60147.82c -- neodymium 147 (Nd-147) + + Pointers : 1670840 28711 + Primary type : Transport + Nuclide ZAI : 601470 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Nd147.ACE + Atomic weight (AW) : 146.91609 + Atomic weight ratio (AWR) : 145.65400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 9.52E+05 seconds (11 days) + Specific ingestion toxicity : 1.10E-09 Sv/Bq + Specific inhalation toxicity : 2.40E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 34 reaction channels + - 42 special reactions + - 9 transmutation reactions + - 6 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 34 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.29100E+00 MeV Emin = 5.32733E+00 MeV frac = 1.00000E+00 Product nuclide = 60146.82c : (n,2n) + 3 MT = 17 Q = -1.28560E+01 MeV Emin = 1.29443E+01 MeV frac = 1.00000E+00 Product nuclide = 60145.82c : (n,3n) + 4 MT = 22 Q = 1.03500E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 58143.82c : (n,nalpha) + 5 MT = 24 Q = -4.10900E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 58142.82c : (n,2nalpha) + 6 MT = 28 Q = -8.67900E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 591460 : (n,np) + 7 MT = 41 Q = -1.38800E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 591450 : (n,2np) + 8 MT = 51 Q = -4.99300E-02 MeV Emin = 5.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -1.27920E-01 MeV Emin = 1.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -1.90290E-01 MeV Emin = 1.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -2.14600E-01 MeV Emin = 2.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -3.14670E-01 MeV Emin = 3.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -4.63620E-01 MeV Emin = 4.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -5.16710E-01 MeV Emin = 5.10129E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -5.81310E-01 MeV Emin = 5.52779E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -6.04520E-01 MeV Emin = 6.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -6.31490E-01 MeV Emin = 6.22248E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -6.56000E-01 MeV Emin = 6.48165E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 62 Q = -7.49000E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 20 MT = 63 Q = -7.69180E-01 MeV Emin = 7.65107E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 21 MT = 64 Q = -7.92560E-01 MeV Emin = 7.87036E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 22 MT = 65 Q = -8.09000E-01 MeV Emin = 8.07277E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 23 MT = 66 Q = -8.59000E-01 MeV Emin = 8.39726E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 24 MT = 67 Q = -9.04000E-01 MeV Emin = 9.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 25 MT = 68 Q = -9.34000E-01 MeV Emin = 9.25310E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 26 MT = 69 Q = -9.42060E-01 MeV Emin = 9.44470E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 27 MT = 70 Q = -9.57260E-01 MeV Emin = 9.56180E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 28 MT = 71 Q = -9.83000E-01 MeV Emin = 9.81916E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 29 MT = 72 Q = -1.02900E+00 MeV Emin = 1.01803E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 30 MT = 73 Q = -1.04148E+00 MeV Emin = 1.04235E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 31 MT = 91 Q = -4.91625E-01 MeV Emin = 4.80902E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 32 MT = 102 Q = 7.33279E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 60148.82c : (n,gamma) + 33 MT = 103 Q = 0.00000E+00 MeV Emin = 3.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 591470 : (n,p) + 34 MT = 107 Q = 0.00000E+00 MeV Emin = 1.50000E-02 MeV frac = 1.00000E+00 Product nuclide = 58144.82c : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = 1.03500E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 24 Q = -4.10900E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,2nalpha) + 3 MT = 28 Q = -8.67900E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 4 MT = 41 Q = -1.38800E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,2np) + 5 MT = 103 Q = 0.00000E+00 MeV Emin = 3.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 107 Q = 0.00000E+00 MeV Emin = 1.50000E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 42 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.50000E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 1.50000E-02 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 8.50000E-04 MeV : damage-energy production + 4 MT = 600 Q = -1.90300E+00 MeV Emin = 3.50000E+00 MeV : (n,p) to ground state + 5 MT = 601 Q = -1.90560E+00 MeV Emin = 3.50000E+00 MeV : (n,p1) + 6 MT = 602 Q = -1.93110E+00 MeV Emin = 3.50000E+00 MeV : (n,p2) + 7 MT = 603 Q = -1.99590E+00 MeV Emin = 3.50000E+00 MeV : (n,p3) + 8 MT = 604 Q = -2.14900E+00 MeV Emin = 3.50000E+00 MeV : (n,p4) + 9 MT = 605 Q = -2.19500E+00 MeV Emin = 3.50000E+00 MeV : (n,p5) + 10 MT = 606 Q = -2.26470E+00 MeV Emin = 3.50000E+00 MeV : (n,p6) + 11 MT = 607 Q = -2.28730E+00 MeV Emin = 3.50000E+00 MeV : (n,p7) + 12 MT = 608 Q = -2.35400E+00 MeV Emin = 4.00000E+00 MeV : (n,p8) + 13 MT = 609 Q = -2.37010E+00 MeV Emin = 4.00000E+00 MeV : (n,p9) + 14 MT = 610 Q = -2.37370E+00 MeV Emin = 4.00000E+00 MeV : (n,p10) + 15 MT = 611 Q = -2.44860E+00 MeV Emin = 4.00000E+00 MeV : (n,p11) + 16 MT = 612 Q = -2.48350E+00 MeV Emin = 4.00000E+00 MeV : (n,p12) + 17 MT = 613 Q = -2.51000E+00 MeV Emin = 4.00000E+00 MeV : (n,p13) + 18 MT = 614 Q = -2.53990E+00 MeV Emin = 4.00000E+00 MeV : (n,p14) + 19 MT = 649 Q = -2.53990E+00 MeV Emin = 4.00000E+00 MeV : (n,p) to continuum + 20 MT = 800 Q = 7.93100E+00 MeV Emin = 1.50000E-02 MeV : (n,alpha) to ground state + 21 MT = 801 Q = 7.53356E+00 MeV Emin = 1.50000E-02 MeV : (n,a1) + 22 MT = 802 Q = 6.99235E+00 MeV Emin = 1.50000E-02 MeV : (n,a2) + 23 MT = 803 Q = 6.68879E+00 MeV Emin = 1.50000E-02 MeV : (n,a3) + 24 MT = 804 Q = 6.58490E+00 MeV Emin = 1.50000E-02 MeV : (n,a4) + 25 MT = 805 Q = 6.44200E+00 MeV Emin = 1.50000E-02 MeV : (n,a5) + 26 MT = 806 Q = 6.40733E+00 MeV Emin = 1.50000E-02 MeV : (n,a6) + 27 MT = 807 Q = 6.25733E+00 MeV Emin = 1.50000E-02 MeV : (n,a7) + 28 MT = 808 Q = 6.23947E+00 MeV Emin = 1.50000E-02 MeV : (n,a8) + 29 MT = 809 Q = 6.11200E+00 MeV Emin = 6.00000E-02 MeV : (n,a9) + 30 MT = 810 Q = 6.10199E+00 MeV Emin = 6.00000E-02 MeV : (n,a10) + 31 MT = 811 Q = 6.06650E+00 MeV Emin = 6.00000E-02 MeV : (n,a11) + 32 MT = 812 Q = 6.04008E+00 MeV Emin = 9.00000E-02 MeV : (n,a12) + 33 MT = 813 Q = 5.93945E+00 MeV Emin = 1.95798E-01 MeV : (n,a13) + 34 MT = 814 Q = 5.90990E+00 MeV Emin = 1.95798E-01 MeV : (n,a14) + 35 MT = 815 Q = 5.90230E+00 MeV Emin = 2.00000E-01 MeV : (n,a15) + 36 MT = 816 Q = 5.89030E+00 MeV Emin = 2.00000E-01 MeV : (n,a16) + 37 MT = 817 Q = 5.81890E+00 MeV Emin = 2.50000E-01 MeV : (n,a17) + 38 MT = 818 Q = 5.80400E+00 MeV Emin = 2.50000E-01 MeV : (n,a18) + 39 MT = 819 Q = 5.77820E+00 MeV Emin = 3.00000E-01 MeV : (n,a19) + 40 MT = 820 Q = 5.71020E+00 MeV Emin = 3.58415E-01 MeV : (n,a20) + 41 MT = 849 Q = 5.71020E+00 MeV Emin = 1.50000E-02 MeV : (n,alpha) to continuum + 42 MT = 4 Q = 0.00000E+00 MeV Emin = 5.00000E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.96100E-01 MeV frac = 1.00000E+00 Product nuclide = 61147.82c : beta- + + Nuclide 207 / 1657 : 60148.82c -- neodymium 148 (Nd-148) + + Pointers : 1677953 28757 + Primary type : Transport + Nuclide ZAI : 601480 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Nd148.ACE + Atomic weight (AW) : 147.91668 + Atomic weight ratio (AWR) : 146.64600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 9.47E+25 seconds (3E+18 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 17 reaction channels + - 7 special reactions + - 8 transmutation reactions + - 6 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 17 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.27450E+00 MeV Emin = 7.32411E+00 MeV frac = 1.00000E+00 Product nuclide = 60147.82c : (n,2n) + 3 MT = 51 Q = -3.01700E-01 MeV Emin = 3.02136E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 4 MT = 52 Q = -7.52000E-01 MeV Emin = 7.52000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 5 MT = 53 Q = -7.91100E-01 MeV Emin = 7.91100E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 6 MT = 54 Q = -9.16900E-01 MeV Emin = 9.16900E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 7 MT = 55 Q = -9.98800E-01 MeV Emin = 1.00280E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 8 MT = 56 Q = -1.02000E+00 MeV Emin = 1.02000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 9 MT = 57 Q = -1.17100E+00 MeV Emin = 1.17050E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 10 MT = 91 Q = -3.01700E-01 MeV Emin = 1.22050E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 11 MT = 102 Q = 5.03879E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 601490 : (n,gamma) + 12 MT = 103 Q = -4.90780E+00 MeV Emin = 4.94127E+00 MeV frac = 1.00000E+00 Product nuclide = 591480 : (n,p) + 13 MT = 104 Q = -7.11150E+00 MeV Emin = 7.16003E+00 MeV frac = 1.00000E+00 Product nuclide = 591470 : (n,d) + 14 MT = 105 Q = -7.31710E+00 MeV Emin = 7.36700E+00 MeV frac = 1.00000E+00 Product nuclide = 591460 : (n,t) + 15 MT = 106 Q = -8.35920E+00 MeV Emin = 8.41620E+00 MeV frac = 1.00000E+00 Product nuclide = 581460 : (n,He-3) + 16 MT = 107 Q = 5.36000E+00 MeV Emin = 4.50000E-01 MeV frac = 1.00000E+00 Product nuclide = 581450 : (n,alpha) + 17 MT = 111 Q = -1.16690E+01 MeV Emin = 1.17486E+01 MeV frac = 1.00000E+00 Product nuclide = 581470 : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = -4.90780E+00 MeV Emin = 4.94127E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -7.11150E+00 MeV Emin = 7.16003E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -7.31710E+00 MeV Emin = 7.36700E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -8.35920E+00 MeV Emin = 8.41620E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 5.36000E+00 MeV Emin = 4.50000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -1.16690E+01 MeV Emin = 1.17486E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.94127E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.16003E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 7.36700E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 8.41620E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.50000E-01 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 8.87549E-04 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 3.02136E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 11 Q = 1.92830E+00 MeV frac = 1.00000E+00 Product nuclide = 62148.82c : beta- + beta- + + Nuclide 208 / 1657 : 60150.82c -- neodymium 150 (Nd-150) + + Pointers : 1687278 28803 + Primary type : Transport + Nuclide ZAI : 601500 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Nd150.ACE + Atomic weight (AW) : 149.92090 + Atomic weight ratio (AWR) : 148.63300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.11E+26 seconds (6.7E+18 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 22 reaction channels + - 7 special reactions + - 11 transmutation reactions + - 8 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 22 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.95320E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 601490 : (n,2n) + 3 MT = 17 Q = -1.24230E+01 MeV Emin = 1.25066E+01 MeV frac = 1.00000E+00 Product nuclide = 60148.82c : (n,3n) + 4 MT = 22 Q = -3.67530E-01 MeV Emin = 3.52500E-01 MeV frac = 1.00000E+00 Product nuclide = 581460 : (n,nalpha) + 5 MT = 28 Q = -9.43660E+00 MeV Emin = 9.50009E+00 MeV frac = 1.00000E+00 Product nuclide = 591490 : (n,np) + 6 MT = 51 Q = -1.29130E-01 MeV Emin = 1.30000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -3.67530E-01 MeV Emin = 3.90002E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -5.46330E-01 MeV Emin = 6.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -6.95320E-01 MeV Emin = 8.45313E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -8.44320E-01 MeV Emin = 8.87500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -9.10000E-01 MeV Emin = 9.85938E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -9.93350E-01 MeV Emin = 1.03693E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -1.05990E+00 MeV Emin = 1.11078E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -1.29130E+00 MeV Emin = 1.30000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 91 Q = -1.35000E+00 MeV Emin = 1.48000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 16 MT = 102 Q = 5.33456E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 601510 : (n,gamma) + 17 MT = 103 Q = -7.94650E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 591500 : (n,p) + 18 MT = 104 Q = -1.14230E+01 MeV Emin = 1.15000E+01 MeV frac = 1.00000E+00 Product nuclide = 591490 : (n,d) + 19 MT = 105 Q = -1.29130E+01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 591480 : (n,t) + 20 MT = 106 Q = -9.82850E+00 MeV Emin = 9.89463E+00 MeV frac = 1.00000E+00 Product nuclide = 581480 : (n,He-3) + 21 MT = 107 Q = 4.21650E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 581470 : (n,alpha) + 22 MT = 111 Q = -1.27140E+01 MeV Emin = 1.27995E+01 MeV frac = 1.00000E+00 Product nuclide = 581490 : (n,2p) + + 8 additional transport branches: + + 1 MT = 22 Q = -3.67530E-01 MeV Emin = 3.52500E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -9.43660E+00 MeV Emin = 9.50009E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -7.94650E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -1.14230E+01 MeV Emin = 1.15000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -1.29130E+01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 106 Q = -9.82850E+00 MeV Emin = 9.89463E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 7 MT = 107 Q = 4.21650E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 8 MT = 111 Q = -1.27140E+01 MeV Emin = 1.27995E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 8.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.15000E+01 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.30000E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 9.89463E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 1.30000E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 11 Q = 3.37138E+00 MeV frac = 1.00000E+00 Product nuclide = 62150.82c : beta- + beta- + + Nuclide 209 / 1657 : 61147.82c -- promethium 147 (Pm-147) + + Pointers : 1719452 30183 + Primary type : Transport + Nuclide ZAI : 611470 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Pm147.ACE + Atomic weight (AW) : 146.91508 + Atomic weight ratio (AWR) : 145.65300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 8.27E+07 seconds (2.62 years) + Specific ingestion toxicity : 2.60E-10 Sv/Bq + Specific inhalation toxicity : 5.00E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 20 reaction channels + - 7 special reactions + - 12 transmutation reactions + - 10 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 20 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.67410E+00 MeV Emin = 7.72679E+00 MeV frac = 1.00000E+00 Product nuclide = 611460 : (n,2n) + 3 MT = 17 Q = -1.39222E+01 MeV Emin = 1.40178E+01 MeV frac = 1.00000E+00 Product nuclide = 611450 : (n,3n) + 4 MT = 22 Q = 1.60309E+00 MeV Emin = 1.02590E-01 MeV frac = 1.00000E+00 Product nuclide = 59143.82c : (n,nalpha) + 5 MT = 28 Q = -5.41064E+00 MeV Emin = 6.31389E+00 MeV frac = 1.00000E+00 Product nuclide = 60146.82c : (n,np) + 6 MT = 32 Q = -1.06696E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 60145.82c : (n,nd) + 7 MT = 33 Q = -1.02446E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 60144.82c : (n,nt) + 8 MT = 51 Q = -9.10999E-02 MeV Emin = 8.99999E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -4.10499E-01 MeV Emin = 4.09606E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -4.89299E-01 MeV Emin = 4.87947E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -5.30999E-01 MeV Emin = 5.25984E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -6.79999E-01 MeV Emin = 6.65916E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -6.85799E-01 MeV Emin = 6.87589E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 91 Q = -6.99999E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 15 MT = 102 Q = 5.89528E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 61148.82c : (n,gamma) + 16 MT = 103 Q = -1.13541E-01 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 60147.82c : (n,p) + 17 MT = 104 Q = -3.10053E+00 MeV Emin = 4.51526E+00 MeV frac = 1.00000E+00 Product nuclide = 60146.82c : (n,d) + 18 MT = 105 Q = -4.48446E+00 MeV Emin = 6.31389E+00 MeV frac = 1.00000E+00 Product nuclide = 60145.82c : (n,t) + 19 MT = 106 Q = -6.27083E+00 MeV Emin = 1.03149E+01 MeV frac = 1.00000E+00 Product nuclide = 591450 : (n,He-3) + 20 MT = 107 Q = 7.36420E+00 MeV Emin = 9.99218E-02 MeV frac = 1.00000E+00 Product nuclide = 591440 : (n,alpha) + + 10 additional transport branches: + + 1 MT = 22 Q = 1.60309E+00 MeV Emin = 1.02590E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -5.41064E+00 MeV Emin = 6.31389E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.06696E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.02446E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 102 Q = 5.89528E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 61548.82c : (n,gamma) + 6 MT = 103 Q = -1.13541E-01 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 7 MT = 104 Q = -3.10053E+00 MeV Emin = 4.51526E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 8 MT = 105 Q = -4.48446E+00 MeV Emin = 6.31389E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 9 MT = 106 Q = -6.27083E+00 MeV Emin = 1.03149E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 10 MT = 107 Q = 7.36420E+00 MeV Emin = 9.99218E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 4.51526E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 6.31389E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.03149E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 9.99218E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 8.50000E-04 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 8.99999E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.24100E-01 MeV frac = 1.00000E+00 Product nuclide = 62147.82c : beta- + + Nuclide 210 / 1657 : 61148.82c -- promethium 148 (Pm-148) + + Pointers : 1722725 30229 + Primary type : Transport + Nuclide ZAI : 611480 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Pm148.ACE + Atomic weight (AW) : 147.91668 + Atomic weight ratio (AWR) : 146.64600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 4.64E+05 seconds (5.37 days) + Specific ingestion toxicity : 2.70E-09 Sv/Bq + Specific inhalation toxicity : 2.20E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 16 reaction channels + - 7 special reactions + - 12 transmutation reactions + - 9 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 16 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.90610E+00 MeV Emin = 6.06070E+00 MeV frac = 1.00000E+00 Product nuclide = 61147.82c : (n,2n) + 3 MT = 17 Q = -1.35802E+01 MeV Emin = 1.36728E+01 MeV frac = 1.00000E+00 Product nuclide = 611460 : (n,3n) + 4 MT = 22 Q = 1.45810E+00 MeV Emin = 1.92188E+00 MeV frac = 1.00000E+00 Product nuclide = 591440 : (n,nalpha) + 5 MT = 28 Q = -6.01964E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 60147.82c : (n,np) + 6 MT = 32 Q = -9.00663E+00 MeV Emin = 1.04614E+01 MeV frac = 1.00000E+00 Product nuclide = 60146.82c : (n,nd) + 7 MT = 33 Q = -1.03906E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 60145.82c : (n,nt) + 8 MT = 51 Q = -7.56999E-02 MeV Emin = 7.50000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -1.37000E-01 MeV Emin = 1.28451E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 91 Q = -2.00000E-01 MeV Emin = 2.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 11 MT = 102 Q = 7.27067E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 61149.82c : (n,gamma) + 12 MT = 103 Q = 1.31946E+00 MeV Emin = 1.04297E+00 MeV frac = 1.00000E+00 Product nuclide = 60148.82c : (n,p) + 13 MT = 104 Q = -3.70952E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 60147.82c : (n,d) + 14 MT = 105 Q = -2.82148E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 60146.82c : (n,t) + 15 MT = 106 Q = -6.88583E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 591460 : (n,He-3) + 16 MT = 107 Q = 8.40919E+00 MeV Emin = 9.99218E-02 MeV frac = 1.00000E+00 Product nuclide = 591450 : (n,alpha) + + 9 additional transport branches: + + 1 MT = 22 Q = 1.45810E+00 MeV Emin = 1.92188E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -6.01964E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -9.00663E+00 MeV Emin = 1.04614E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.03906E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 103 Q = 1.31946E+00 MeV Emin = 1.04297E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 104 Q = -3.70952E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 7 MT = 105 Q = -2.82148E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 8 MT = 106 Q = -6.88583E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 9 MT = 107 Q = 8.40919E+00 MeV Emin = 9.99218E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.04297E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 4.00000E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.00000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 9.99218E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 8.50000E-04 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 7.50000E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.47100E+00 MeV frac = 1.00000E+00 Product nuclide = 62148.82c : beta- + + Nuclide 211 / 1657 : 61548.82c -- promethium 148m (Pm-148m) + + Pointers : 1726902 30275 + Primary type : Transport + Nuclide ZAI : 611481 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Pm148M.ACE + Atomic weight (AW) : 147.92072 + Atomic weight ratio (AWR) : 146.65000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 3.57E+06 seconds (41.3 days) + Specific ingestion toxicity : 1.70E-09 Sv/Bq + Specific inhalation toxicity : 5.70E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 13 reaction channels + - 6 special reactions + - 9 transmutation reactions + - 6 transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 13 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.75550E+00 MeV Emin = 5.79475E+00 MeV frac = 1.00000E+00 Product nuclide = 61147.82c : (n,2n) + 3 MT = 17 Q = -1.34210E+01 MeV Emin = 1.35125E+01 MeV frac = 1.00000E+00 Product nuclide = 611460 : (n,3n) + 4 MT = 22 Q = 1.59920E+00 MeV Emin = 2.33125E-08 MeV frac = 1.00000E+00 Product nuclide = 591440 : (n,nalpha) + 5 MT = 28 Q = -5.86920E+00 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 60147.82c : (n,np) + 6 MT = 51 Q = 1.37900E-01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = 6.22000E-02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 91 Q = 0.00000E+00 MeV Emin = 1.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 9 MT = 102 Q = 7.34637E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 61149.82c : (n,gamma) + 10 MT = 103 Q = 1.46420E+00 MeV Emin = 2.06625E-08 MeV frac = 1.00000E+00 Product nuclide = 60148.82c : (n,p) + 11 MT = 104 Q = -3.64470E+00 MeV Emin = 1.15000E+01 MeV frac = 1.00000E+00 Product nuclide = 60147.82c : (n,d) + 12 MT = 105 Q = -2.67920E+00 MeV Emin = 1.15000E+01 MeV frac = 1.00000E+00 Product nuclide = 60146.82c : (n,t) + 13 MT = 107 Q = 8.54600E+00 MeV Emin = 2.13250E-08 MeV frac = 1.00000E+00 Product nuclide = 591450 : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = 1.59920E+00 MeV Emin = 2.33125E-08 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -5.86920E+00 MeV Emin = 1.25000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = 1.46420E+00 MeV Emin = 2.06625E-08 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -3.64470E+00 MeV Emin = 1.15000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -2.67920E+00 MeV Emin = 1.15000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 107 Q = 8.54600E+00 MeV Emin = 2.13250E-08 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.06625E-08 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 1.15000E+01 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.15000E+01 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 2.13250E-08 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 3 Q = 1.37100E-01 MeV frac = 5.60000E-02 Product nuclide = 61148.82c : IT + 2 RTYP = 1 Q = 2.60800E+00 MeV frac = 9.44000E-01 Product nuclide = 62148.82c : beta- + + Nuclide 212 / 1657 : 61149.82c -- promethium 149 (Pm-149) + + Pointers : 1730851 30321 + Primary type : Transport + Nuclide ZAI : 611490 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Pm149.ACE + Atomic weight (AW) : 148.91829 + Atomic weight ratio (AWR) : 147.63900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.91E+05 seconds (2.21 days) + Specific ingestion toxicity : 9.90E-10 Sv/Bq + Specific inhalation toxicity : 7.30E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 27 reaction channels + - 6 special reactions + - 11 transmutation reactions + - 8 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 27 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.26910E+00 MeV Emin = 7.31835E+00 MeV frac = 1.00000E+00 Product nuclide = 61148.82c : (n,2n) + 3 MT = 17 Q = -1.31752E+01 MeV Emin = 1.32645E+01 MeV frac = 1.00000E+00 Product nuclide = 61147.82c : (n,3n) + 4 MT = 22 Q = 1.14009E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 591450 : (n,nalpha) + 5 MT = 28 Q = -5.94964E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 60148.82c : (n,np) + 6 MT = 32 Q = -1.09786E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 60147.82c : (n,nd) + 7 MT = 33 Q = -1.00906E+01 MeV Emin = 1.10530E+01 MeV frac = 1.00000E+00 Product nuclide = 60146.82c : (n,nt) + 8 MT = 51 Q = -1.14300E-01 MeV Emin = 1.07537E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -1.88600E-01 MeV Emin = 1.69938E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -2.11300E-01 MeV Emin = 2.06366E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -2.40200E-01 MeV Emin = 2.38304E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -2.70200E-01 MeV Emin = 2.66522E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -2.88200E-01 MeV Emin = 2.85905E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -3.60000E-01 MeV Emin = 3.46828E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -3.87599E-01 MeV Emin = 3.83278E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -3.96799E-01 MeV Emin = 3.99059E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -4.25299E-01 MeV Emin = 4.21008E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -4.62199E-01 MeV Emin = 4.57205E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 62 Q = -5.15599E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 20 MT = 63 Q = -5.37899E-01 MeV Emin = 5.37334E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 21 MT = 64 Q = -6.54799E-01 MeV Emin = 6.58393E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 22 MT = 91 Q = -6.99999E-01 MeV Emin = 7.03859E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 23 MT = 102 Q = 5.60342E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 611500 : (n,gamma) + 24 MT = 103 Q = -9.06544E-01 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 601490 : (n,p) + 25 MT = 104 Q = -3.63952E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 60148.82c : (n,d) + 26 MT = 105 Q = -4.79347E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 60147.82c : (n,t) + 27 MT = 107 Q = 6.43119E+00 MeV Emin = 8.99999E-02 MeV frac = 1.00000E+00 Product nuclide = 591460 : (n,alpha) + + 8 additional transport branches: + + 1 MT = 22 Q = 1.14009E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -5.94964E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.09786E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.00906E+01 MeV Emin = 1.10530E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 103 Q = -9.06544E-01 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 104 Q = -3.63952E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 7 MT = 105 Q = -4.79347E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 8 MT = 107 Q = 6.43119E+00 MeV Emin = 8.99999E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 7.00000E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 8.99999E-02 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 8.50000E-04 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 1.07537E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.07100E+00 MeV frac = 1.00000E+00 Product nuclide = 62149.82c : beta- + + Nuclide 213 / 1657 : 61151.82c -- promethium 151 (Pm-151) + + Pointers : 1739444 30367 + Primary type : Transport + Nuclide ZAI : 611510 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Pm151.ACE + Atomic weight (AW) : 150.92150 + Atomic weight ratio (AWR) : 149.62500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.02E+05 seconds (1.18 days) + Specific ingestion toxicity : 7.30E-10 Sv/Bq + Specific inhalation toxicity : 4.60E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 22 reaction channels + - 20 special reactions + - 9 transmutation reactions + - 6 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 22 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.86300E+00 MeV Emin = 7.91555E+00 MeV frac = 1.00000E+00 Product nuclide = 611500 : (n,2n) + 3 MT = 17 Q = -1.34650E+01 MeV Emin = 1.35550E+01 MeV frac = 1.00000E+00 Product nuclide = 61149.82c : (n,3n) + 4 MT = 22 Q = -3.53000E-01 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 591470 : (n,nalpha) + 5 MT = 24 Q = -7.12900E+00 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 591460 : (n,2nalpha) + 6 MT = 28 Q = -6.99400E+00 MeV Emin = 7.04075E+00 MeV frac = 1.00000E+00 Product nuclide = 60150.82c : (n,np) + 7 MT = 41 Q = -1.43740E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 601490 : (n,2np) + 8 MT = 51 Q = -8.51200E-02 MeV Emin = 8.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -1.16790E-01 MeV Emin = 1.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -1.75080E-01 MeV Emin = 1.46910E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -1.97270E-01 MeV Emin = 1.87419E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -2.55690E-01 MeV Emin = 2.56162E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -2.61160E-01 MeV Emin = 2.60000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -3.24680E-01 MeV Emin = 3.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -3.29600E-01 MeV Emin = 3.29327E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -3.43800E-01 MeV Emin = 3.38950E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -4.26450E-01 MeV Emin = 3.87699E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -4.27150E-01 MeV Emin = 4.29653E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 91 Q = -4.27150E-01 MeV Emin = 4.29653E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 20 MT = 102 Q = 5.93837E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 611520 : (n,gamma) + 21 MT = 103 Q = 0.00000E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 601510 : (n,p) + 22 MT = 107 Q = 0.00000E+00 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 591480 : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = -3.53000E-01 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 24 Q = -7.12900E+00 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,2nalpha) + 3 MT = 28 Q = -6.99400E+00 MeV Emin = 7.04075E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 4 MT = 41 Q = -1.43740E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,2np) + 5 MT = 103 Q = 0.00000E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 107 Q = 0.00000E+00 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 20 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.00000E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 1.50000E+00 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 8.50000E-04 MeV : damage-energy production + 4 MT = 600 Q = -1.66000E+00 MeV Emin = 3.00000E+00 MeV : (n,p) to ground state + 5 MT = 601 Q = -1.68245E+00 MeV Emin = 3.00000E+00 MeV : (n,p1) + 6 MT = 602 Q = -1.71767E+00 MeV Emin = 3.00000E+00 MeV : (n,p2) + 7 MT = 603 Q = -1.73586E+00 MeV Emin = 3.00000E+00 MeV : (n,p3) + 8 MT = 604 Q = -1.75590E+00 MeV Emin = 3.00000E+00 MeV : (n,p4) + 9 MT = 649 Q = -1.75590E+00 MeV Emin = 3.00000E+00 MeV : (n,p) to continuum + 10 MT = 800 Q = 4.73300E+00 MeV Emin = 1.50000E+00 MeV : (n,alpha) to ground state + 11 MT = 801 Q = 4.64300E+00 MeV Emin = 1.60000E+00 MeV : (n,a1) + 12 MT = 802 Q = 4.63483E+00 MeV Emin = 1.60000E+00 MeV : (n,a2) + 13 MT = 803 Q = 4.63401E+00 MeV Emin = 1.60000E+00 MeV : (n,a3) + 14 MT = 804 Q = 4.62780E+00 MeV Emin = 1.60000E+00 MeV : (n,a4) + 15 MT = 805 Q = 4.61183E+00 MeV Emin = 1.60000E+00 MeV : (n,a5) + 16 MT = 806 Q = 4.53700E+00 MeV Emin = 1.70000E+00 MeV : (n,a6) + 17 MT = 807 Q = 4.45920E+00 MeV Emin = 1.70000E+00 MeV : (n,a7) + 18 MT = 808 Q = 4.44570E+00 MeV Emin = 1.80000E+00 MeV : (n,a8) + 19 MT = 849 Q = 4.44570E+00 MeV Emin = 1.80000E+00 MeV : (n,alpha) to continuum + 20 MT = 4 Q = 0.00000E+00 MeV Emin = 8.00000E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.18700E+00 MeV frac = 1.00000E+00 Product nuclide = 62151.82c : beta- + + Nuclide 214 / 1657 : 62147.82c -- samarium 147 (Sm-147) + + Pointers : 1771072 32989 + Primary type : Transport + Nuclide ZAI : 621470 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Sm147.ACE + Atomic weight (AW) : 146.91508 + Atomic weight ratio (AWR) : 145.65300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 3.38E+18 seconds (107 billion years) + Specific ingestion toxicity : 4.90E-08 Sv/Bq + Specific inhalation toxicity : 9.60E-06 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 24 reaction channels + - 7 special reactions + - 8 transmutation reactions + - 6 transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 24 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.32950E+00 MeV Emin = 6.37300E+00 MeV frac = 1.00000E+00 Product nuclide = 621460 : (n,2n) + 3 MT = 51 Q = -1.23000E-01 MeV Emin = 1.23000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 4 MT = 52 Q = -1.97300E-01 MeV Emin = 1.97300E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 5 MT = 53 Q = -7.15500E-01 MeV Emin = 7.15500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 6 MT = 54 Q = -7.98800E-01 MeV Emin = 8.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 7 MT = 55 Q = -8.08000E-01 MeV Emin = 8.10774E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 8 MT = 56 Q = -9.00000E-01 MeV Emin = 9.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 9 MT = 57 Q = -9.25000E-01 MeV Emin = 9.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 10 MT = 58 Q = -1.00700E+00 MeV Emin = 1.00696E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 11 MT = 59 Q = -1.02900E+00 MeV Emin = 1.02900E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 12 MT = 60 Q = -1.05400E+00 MeV Emin = 1.05400E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 13 MT = 61 Q = -1.06500E+00 MeV Emin = 1.06865E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 14 MT = 62 Q = -1.07700E+00 MeV Emin = 1.08069E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 15 MT = 63 Q = -1.10300E+00 MeV Emin = 1.10300E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 16 MT = 64 Q = -1.16600E+00 MeV Emin = 1.16600E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 17 MT = 91 Q = -1.17200E+00 MeV Emin = 1.17850E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 18 MT = 102 Q = 8.14142E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 62148.82c : (n,gamma) + 19 MT = 103 Q = 5.57400E-01 MeV Emin = 4.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 61147.82c : (n,p) + 20 MT = 104 Q = -4.79300E+00 MeV Emin = 4.82592E+00 MeV frac = 1.00000E+00 Product nuclide = 611460 : (n,d) + 21 MT = 105 Q = -4.20050E+00 MeV Emin = 4.22936E+00 MeV frac = 1.00000E+00 Product nuclide = 611450 : (n,t) + 22 MT = 106 Q = -4.21260E+00 MeV Emin = 4.24152E+00 MeV frac = 1.00000E+00 Product nuclide = 60145.82c : (n,He-3) + 23 MT = 107 Q = 1.01300E+01 MeV Emin = 4.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 60144.82c : (n,alpha) + 24 MT = 111 Q = -4.84670E+00 MeV Emin = 4.87998E+00 MeV frac = 1.00000E+00 Product nuclide = 60146.82c : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = 5.57400E-01 MeV Emin = 4.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -4.79300E+00 MeV Emin = 4.82592E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -4.20050E+00 MeV Emin = 4.22936E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -4.21260E+00 MeV Emin = 4.24152E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 1.01300E+01 MeV Emin = 4.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -4.84670E+00 MeV Emin = 4.87998E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.00000E-01 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 4.82592E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 4.22936E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 4.24152E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.00000E-01 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 9.00000E-04 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 1.23000E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 4 Q = 2.31100E+00 MeV frac = 1.00000E+00 Product nuclide = 601430 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 2.31100E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 215 / 1657 : 62148.82c -- samarium 148 (Sm-148) + + Pointers : 1774063 33035 + Primary type : Transport + Nuclide ZAI : 621480 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Sm148.ACE + Atomic weight (AW) : 147.91467 + Atomic weight ratio (AWR) : 146.64400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.21E+23 seconds (7E+15 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 24 reaction channels + - 67 special reactions + - 9 transmutation reactions + - 6 transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 24 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.14200E+00 MeV Emin = 8.19752E+00 MeV frac = 1.00000E+00 Product nuclide = 62147.82c : (n,2n) + 3 MT = 17 Q = -1.44830E+01 MeV Emin = 1.45818E+01 MeV frac = 1.00000E+00 Product nuclide = 621460 : (n,3n) + 4 MT = 22 Q = 1.98500E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 60144.82c : (n,nalpha) + 5 MT = 24 Q = -5.83100E+00 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 601430 : (n,2nalpha) + 6 MT = 28 Q = -7.58400E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 61147.82c : (n,np) + 7 MT = 41 Q = -1.52430E+01 MeV Emin = 1.70000E+01 MeV frac = 1.00000E+00 Product nuclide = 611460 : (n,2np) + 8 MT = 51 Q = -5.50270E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -1.16154E+00 MeV Emin = 1.10000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -1.18026E+00 MeV Emin = 1.17889E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -1.42445E+00 MeV Emin = 1.40000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -1.43420E+00 MeV Emin = 1.43907E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -1.45412E+00 MeV Emin = 1.45401E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -1.46512E+00 MeV Emin = 1.46958E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -1.59429E+00 MeV Emin = 1.60000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -1.64860E+00 MeV Emin = 1.63250E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -1.65930E+00 MeV Emin = 1.66523E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -1.66424E+00 MeV Emin = 1.67410E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 62 Q = -1.71800E+00 MeV Emin = 1.71486E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 20 MT = 63 Q = -1.73349E+00 MeV Emin = 1.73751E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 21 MT = 91 Q = -3.93318E-01 MeV Emin = 3.77000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 22 MT = 102 Q = 5.87108E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 62149.82c : (n,gamma) + 23 MT = 103 Q = 0.00000E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 61148.82c : (n,p) + 24 MT = 107 Q = 0.00000E+00 MeV Emin = 1.80000E-02 MeV frac = 1.00000E+00 Product nuclide = 60145.82c : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = 1.98500E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 24 Q = -5.83100E+00 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,2nalpha) + 3 MT = 28 Q = -7.58400E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 4 MT = 41 Q = -1.52430E+01 MeV Emin = 1.70000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,2np) + 5 MT = 103 Q = 0.00000E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 107 Q = 0.00000E+00 MeV Emin = 1.80000E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 67 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.00000E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 1.80000E-02 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 8.85907E-04 MeV : damage-energy production + 4 MT = 600 Q = -1.68700E+00 MeV Emin = 3.00000E+00 MeV : (n,p) to ground state + 5 MT = 601 Q = -1.76270E+00 MeV Emin = 3.00000E+00 MeV : (n,p1) + 6 MT = 602 Q = -1.82420E+00 MeV Emin = 3.00000E+00 MeV : (n,p2) + 7 MT = 603 Q = -1.82490E+00 MeV Emin = 3.00000E+00 MeV : (n,p3) + 8 MT = 604 Q = -1.90240E+00 MeV Emin = 3.00000E+00 MeV : (n,p4) + 9 MT = 605 Q = -1.90690E+00 MeV Emin = 3.00000E+00 MeV : (n,p5) + 10 MT = 606 Q = -1.97900E+00 MeV Emin = 3.00000E+00 MeV : (n,p6) + 11 MT = 607 Q = -1.98930E+00 MeV Emin = 3.00000E+00 MeV : (n,p7) + 12 MT = 608 Q = -1.99170E+00 MeV Emin = 3.00000E+00 MeV : (n,p8) + 13 MT = 609 Q = -1.99590E+00 MeV Emin = 3.00000E+00 MeV : (n,p9) + 14 MT = 610 Q = -2.05040E+00 MeV Emin = 3.00000E+00 MeV : (n,p10) + 15 MT = 611 Q = -2.06670E+00 MeV Emin = 3.00000E+00 MeV : (n,p11) + 16 MT = 612 Q = -2.07250E+00 MeV Emin = 3.00000E+00 MeV : (n,p12) + 17 MT = 613 Q = -2.07510E+00 MeV Emin = 3.00000E+00 MeV : (n,p13) + 18 MT = 614 Q = -2.09660E+00 MeV Emin = 3.00000E+00 MeV : (n,p14) + 19 MT = 615 Q = -2.10060E+00 MeV Emin = 3.00000E+00 MeV : (n,p15) + 20 MT = 616 Q = -2.12710E+00 MeV Emin = 3.00000E+00 MeV : (n,p16) + 21 MT = 617 Q = -2.13900E+00 MeV Emin = 3.00000E+00 MeV : (n,p17) + 22 MT = 618 Q = -2.14900E+00 MeV Emin = 3.00000E+00 MeV : (n,p18) + 23 MT = 619 Q = -2.21350E+00 MeV Emin = 3.00000E+00 MeV : (n,p19) + 24 MT = 620 Q = -2.21650E+00 MeV Emin = 3.00000E+00 MeV : (n,p20) + 25 MT = 621 Q = -2.23040E+00 MeV Emin = 3.00000E+00 MeV : (n,p21) + 26 MT = 622 Q = -2.23270E+00 MeV Emin = 3.00000E+00 MeV : (n,p22) + 27 MT = 623 Q = -2.23730E+00 MeV Emin = 3.00000E+00 MeV : (n,p23) + 28 MT = 624 Q = -2.24820E+00 MeV Emin = 3.00000E+00 MeV : (n,p24) + 29 MT = 625 Q = -2.25120E+00 MeV Emin = 3.00000E+00 MeV : (n,p25) + 30 MT = 626 Q = -2.26010E+00 MeV Emin = 3.00000E+00 MeV : (n,p26) + 31 MT = 627 Q = -2.29820E+00 MeV Emin = 3.00000E+00 MeV : (n,p27) + 32 MT = 628 Q = -2.30970E+00 MeV Emin = 3.00000E+00 MeV : (n,p28) + 33 MT = 629 Q = -2.32890E+00 MeV Emin = 4.00000E+00 MeV : (n,p29) + 34 MT = 630 Q = -2.34220E+00 MeV Emin = 3.00000E+00 MeV : (n,p30) + 35 MT = 631 Q = -2.34730E+00 MeV Emin = 3.00000E+00 MeV : (n,p31) + 36 MT = 632 Q = -2.35650E+00 MeV Emin = 3.00000E+00 MeV : (n,p32) + 37 MT = 633 Q = -2.35990E+00 MeV Emin = 3.00000E+00 MeV : (n,p33) + 38 MT = 634 Q = -2.38700E+00 MeV Emin = 3.00000E+00 MeV : (n,p34) + 39 MT = 649 Q = -2.38700E+00 MeV Emin = 4.00000E+00 MeV : (n,p) to continuum + 40 MT = 800 Q = 7.74100E+00 MeV Emin = 1.80000E-02 MeV : (n,alpha) to ground state + 41 MT = 801 Q = 7.67378E+00 MeV Emin = 1.80000E-02 MeV : (n,a1) + 42 MT = 802 Q = 7.66850E+00 MeV Emin = 1.80000E-02 MeV : (n,a2) + 43 MT = 803 Q = 7.08333E+00 MeV Emin = 2.10000E-02 MeV : (n,a3) + 44 MT = 804 Q = 6.99272E+00 MeV Emin = 1.90000E-02 MeV : (n,a4) + 45 MT = 805 Q = 6.96055E+00 MeV Emin = 1.80000E-02 MeV : (n,a5) + 46 MT = 806 Q = 6.82117E+00 MeV Emin = 1.80000E-02 MeV : (n,a6) + 47 MT = 807 Q = 6.82028E+00 MeV Emin = 2.20000E-02 MeV : (n,a7) + 48 MT = 808 Q = 6.80395E+00 MeV Emin = 1.80000E-02 MeV : (n,a8) + 49 MT = 809 Q = 6.72978E+00 MeV Emin = 1.17000E-01 MeV : (n,a9) + 50 MT = 810 Q = 6.68959E+00 MeV Emin = 1.80000E-02 MeV : (n,a10) + 51 MT = 811 Q = 6.65575E+00 MeV Emin = 1.80000E-02 MeV : (n,a11) + 52 MT = 812 Q = 6.62980E+00 MeV Emin = 1.17000E-01 MeV : (n,a12) + 53 MT = 813 Q = 6.59074E+00 MeV Emin = 1.80000E-02 MeV : (n,a13) + 54 MT = 814 Q = 6.57995E+00 MeV Emin = 1.80000E-02 MeV : (n,a14) + 55 MT = 815 Q = 6.57868E+00 MeV Emin = 2.60000E-02 MeV : (n,a15) + 56 MT = 816 Q = 6.52730E+00 MeV Emin = 1.80000E-02 MeV : (n,a16) + 57 MT = 817 Q = 6.49127E+00 MeV Emin = 1.80000E-02 MeV : (n,a17) + 58 MT = 818 Q = 6.45540E+00 MeV Emin = 1.80000E-02 MeV : (n,a18) + 59 MT = 819 Q = 6.42420E+00 MeV Emin = 1.80000E-02 MeV : (n,a19) + 60 MT = 820 Q = 6.41470E+00 MeV Emin = 1.80000E-02 MeV : (n,a20) + 61 MT = 821 Q = 6.40240E+00 MeV Emin = 1.90000E-02 MeV : (n,a21) + 62 MT = 822 Q = 6.34010E+00 MeV Emin = 1.80000E-02 MeV : (n,a22) + 63 MT = 823 Q = 6.33970E+00 MeV Emin = 3.27000E-01 MeV : (n,a23) + 64 MT = 824 Q = 6.33708E+00 MeV Emin = 1.90000E-02 MeV : (n,a24) + 65 MT = 825 Q = 6.31340E+00 MeV Emin = 3.27000E-01 MeV : (n,a25) + 66 MT = 849 Q = 6.31340E+00 MeV Emin = 1.80000E-02 MeV : (n,alpha) to continuum + 67 MT = 4 Q = 0.00000E+00 MeV Emin = 3.77000E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 4 Q = 1.98600E+00 MeV frac = 1.00000E+00 Product nuclide = 60144.82c : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 1.98600E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 216 / 1657 : 62149.82c -- samarium 149 (Sm-149) + + Pointers : 1781434 33081 + Primary type : Transport + Nuclide ZAI : 621490 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Sm149.ACE + Atomic weight (AW) : 148.91728 + Atomic weight ratio (AWR) : 147.63800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 6.31E+22 seconds (2E+15 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 17 reaction channels + - 4 special reactions + - 5 transmutation reactions + - 2 transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 17 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.86000E+00 MeV Emin = 5.90000E+00 MeV frac = 1.00000E+00 Product nuclide = 62148.82c : (n,2n) + 3 MT = 17 Q = -1.40700E+01 MeV Emin = 1.41653E+01 MeV frac = 1.00000E+00 Product nuclide = 62147.82c : (n,3n) + 4 MT = 51 Q = -2.20000E-02 MeV Emin = 2.20000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 5 MT = 52 Q = -2.77000E-01 MeV Emin = 2.68994E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 6 MT = 53 Q = -2.86000E-01 MeV Emin = 2.83388E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 7 MT = 54 Q = -3.50000E-01 MeV Emin = 3.26150E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 8 MT = 55 Q = -3.98000E-01 MeV Emin = 4.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 9 MT = 56 Q = -5.29000E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 10 MT = 57 Q = -5.58000E-01 MeV Emin = 5.47142E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 11 MT = 58 Q = -5.82000E-01 MeV Emin = 5.73840E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 12 MT = 59 Q = -6.50000E-01 MeV Emin = 6.27150E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 13 MT = 60 Q = -8.53000E-01 MeV Emin = 8.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 14 MT = 91 Q = -1.98654E+00 MeV Emin = 1.90000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 15 MT = 102 Q = 7.98674E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 62150.82c : (n,gamma) + 16 MT = 103 Q = -2.77000E-01 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 61149.82c : (n,p) + 17 MT = 107 Q = 9.60000E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 60146.82c : (n,alpha) + + 2 additional transport branches: + + 1 MT = 103 Q = -2.77000E-01 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 107 Q = 9.60000E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 4 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.00000E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 4.00000E+00 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 8.50000E-04 MeV : damage-energy production + 4 MT = 4 Q = 0.00000E+00 MeV Emin = 2.20000E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 4 Q = 1.86970E+00 MeV frac = 1.00000E+00 Product nuclide = 60145.82c : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 1.86970E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 217 / 1657 : 62150.82c -- samarium 150 (Sm-150) + + Pointers : 1783403 33127 + Primary type : Transport + Nuclide ZAI : 621500 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Sm150.ACE + Atomic weight (AW) : 149.91687 + Atomic weight ratio (AWR) : 148.62900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 25 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 25 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -3.34000E-01 MeV Emin = 3.36018E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -7.37000E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -7.40000E-01 MeV Emin = 7.43470E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -7.73000E-01 MeV Emin = 7.61590E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -1.05000E+00 MeV Emin = 1.04195E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -1.07000E+00 MeV Emin = 1.07341E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 57 Q = -1.16000E+00 MeV Emin = 1.12585E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 9 MT = 58 Q = -1.19000E+00 MeV Emin = 1.18290E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 10 MT = 59 Q = -1.26000E+00 MeV Emin = 1.24330E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 11 MT = 60 Q = -1.28000E+00 MeV Emin = 1.24330E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 12 MT = 61 Q = -1.36000E+00 MeV Emin = 1.36788E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 13 MT = 62 Q = -1.42000E+00 MeV Emin = 1.42073E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 14 MT = 63 Q = -1.45000E+00 MeV Emin = 1.44715E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 15 MT = 64 Q = -1.50000E+00 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 16 MT = 65 Q = -1.64000E+00 MeV Emin = 1.60000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 17 MT = 66 Q = -1.67000E+00 MeV Emin = 1.68000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 18 MT = 91 Q = -1.67000E+00 MeV Emin = 1.68000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 19 MT = 102 Q = 5.59646E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 62151.82c : (n,gamma) + 20 MT = 103 Q = -2.71540E+00 MeV Emin = 2.73367E+00 MeV frac = 1.00000E+00 Product nuclide = 611500 : (n,p) + 21 MT = 104 Q = -6.04810E+00 MeV Emin = 6.08879E+00 MeV frac = 1.00000E+00 Product nuclide = 61149.82c : (n,d) + 22 MT = 105 Q = -7.05460E+00 MeV Emin = 7.10206E+00 MeV frac = 1.00000E+00 Product nuclide = 61148.82c : (n,t) + 23 MT = 106 Q = -6.49960E+00 MeV Emin = 6.54333E+00 MeV frac = 1.00000E+00 Product nuclide = 60148.82c : (n,He-3) + 24 MT = 107 Q = 6.73920E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 60147.82c : (n,alpha) + 25 MT = 111 Q = -9.17820E+00 MeV Emin = 9.23995E+00 MeV frac = 1.00000E+00 Product nuclide = 601490 : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = -2.71540E+00 MeV Emin = 2.73367E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -6.04810E+00 MeV Emin = 6.08879E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -7.05460E+00 MeV Emin = 7.10206E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -6.49960E+00 MeV Emin = 6.54333E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 6.73920E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -9.17820E+00 MeV Emin = 9.23995E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.73367E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.08879E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 7.10206E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 6.54333E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 3.36018E-01 MeV : total inelastic scattering + + Nuclide 218 / 1657 : 62151.82c -- samarium 151 (Sm-151) + + Pointers : 1786288 33173 + Primary type : Transport + Nuclide ZAI : 621510 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Sm151.ACE + Atomic weight (AW) : 150.91645 + Atomic weight ratio (AWR) : 149.62000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.99E+09 seconds (94.8 years) + Specific ingestion toxicity : 9.80E-11 Sv/Bq + Specific inhalation toxicity : 4.00E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 50 reaction channels + - 7 special reactions + - 8 transmutation reactions + - 6 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 50 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.60960E+00 MeV Emin = 5.64800E+00 MeV frac = 1.00000E+00 Product nuclide = 62150.82c : (n,2n) + 3 MT = 51 Q = -4.80000E-03 MeV Emin = 4.62408E-03 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 4 MT = 52 Q = -6.58000E-02 MeV Emin = 6.61250E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 5 MT = 53 Q = -6.97000E-02 MeV Emin = 7.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 6 MT = 54 Q = -9.16000E-02 MeV Emin = 9.14877E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 7 MT = 55 Q = -1.04800E-01 MeV Emin = 1.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 8 MT = 56 Q = -1.47900E-01 MeV Emin = 1.45943E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 9 MT = 57 Q = -1.67800E-01 MeV Emin = 1.59500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 10 MT = 58 Q = -1.68400E-01 MeV Emin = 1.69250E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 11 MT = 59 Q = -1.75400E-01 MeV Emin = 1.73285E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 12 MT = 60 Q = -2.09000E-01 MeV Emin = 2.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 13 MT = 61 Q = -2.20000E-01 MeV Emin = 2.16103E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 14 MT = 62 Q = -2.30000E-01 MeV Emin = 2.26770E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 15 MT = 63 Q = -2.45600E-01 MeV Emin = 2.39620E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 16 MT = 64 Q = -2.61100E-01 MeV Emin = 2.56500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 17 MT = 65 Q = -2.70000E-01 MeV Emin = 2.67500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 18 MT = 66 Q = -2.80000E-01 MeV Emin = 2.80000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 19 MT = 67 Q = -2.85000E-01 MeV Emin = 2.84500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 20 MT = 68 Q = -2.94800E-01 MeV Emin = 2.92000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 21 MT = 69 Q = -3.02500E-01 MeV Emin = 3.02260E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 22 MT = 70 Q = -3.06800E-01 MeV Emin = 3.07000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 23 MT = 71 Q = -3.13400E-01 MeV Emin = 3.12245E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 24 MT = 72 Q = -3.15300E-01 MeV Emin = 3.16452E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 25 MT = 73 Q = -3.24000E-01 MeV Emin = 3.22085E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 26 MT = 74 Q = -3.30000E-01 MeV Emin = 3.31497E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 27 MT = 75 Q = -3.34000E-01 MeV Emin = 3.34615E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 28 MT = 76 Q = -3.36000E-01 MeV Emin = 3.37000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 29 MT = 77 Q = -3.40000E-01 MeV Emin = 3.40635E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 27. excited state + 30 MT = 78 Q = -3.44900E-01 MeV Emin = 3.45105E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 28. excited state + 31 MT = 79 Q = -3.50000E-01 MeV Emin = 3.51500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 29. excited state + 32 MT = 80 Q = -3.55000E-01 MeV Emin = 3.55185E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 30. excited state + 33 MT = 81 Q = -3.57600E-01 MeV Emin = 3.59000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 31. excited state + 34 MT = 82 Q = -3.60000E-01 MeV Emin = 3.61205E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 32. excited state + 35 MT = 83 Q = -3.65000E-01 MeV Emin = 3.64925E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 33. excited state + 36 MT = 84 Q = -3.70000E-01 MeV Emin = 3.70235E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 34. excited state + 37 MT = 85 Q = -3.75000E-01 MeV Emin = 3.76255E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 35. excited state + 38 MT = 86 Q = -3.80000E-01 MeV Emin = 3.80492E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 36. excited state + 39 MT = 87 Q = -3.85000E-01 MeV Emin = 3.85285E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 37. excited state + 40 MT = 88 Q = -3.86000E-01 MeV Emin = 3.88000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 38. excited state + 41 MT = 89 Q = -3.90000E-01 MeV Emin = 3.90000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 39. excited state + 42 MT = 90 Q = -3.92000E-01 MeV Emin = 3.94000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 40. excited state + 43 MT = 91 Q = -3.93000E-01 MeV Emin = 3.95315E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 44 MT = 102 Q = 8.25761E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 62152.82c : (n,gamma) + 45 MT = 103 Q = -4.05190E-01 MeV Emin = 4.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 61151.82c : (n,p) + 46 MT = 104 Q = -6.08610E+00 MeV Emin = 6.12678E+00 MeV frac = 1.00000E+00 Product nuclide = 611500 : (n,d) + 47 MT = 105 Q = -5.38720E+00 MeV Emin = 5.42321E+00 MeV frac = 1.00000E+00 Product nuclide = 61149.82c : (n,t) + 48 MT = 106 Q = -7.05750E+00 MeV Emin = 7.10467E+00 MeV frac = 1.00000E+00 Product nuclide = 601490 : (n,He-3) + 49 MT = 107 Q = 8.47660E+00 MeV Emin = 4.50000E-02 MeV frac = 1.00000E+00 Product nuclide = 60148.82c : (n,alpha) + 50 MT = 111 Q = -7.39590E+00 MeV Emin = 7.44533E+00 MeV frac = 1.00000E+00 Product nuclide = 60150.82c : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = -4.05190E-01 MeV Emin = 4.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -6.08610E+00 MeV Emin = 6.12678E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -5.38720E+00 MeV Emin = 5.42321E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -7.05750E+00 MeV Emin = 7.10467E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 8.47660E+00 MeV Emin = 4.50000E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -7.39590E+00 MeV Emin = 7.44533E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.00000E-01 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.12678E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 5.42321E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 7.10467E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.50000E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 8.50000E-04 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 4.62408E-03 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.64000E-02 MeV frac = 1.00000E+00 Product nuclide = 63151.82c : beta- + + Nuclide 219 / 1657 : 62152.82c -- samarium 152 (Sm-152) + + Pointers : 1791216 33219 + Primary type : Transport + Nuclide ZAI : 621520 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Sm152.ACE + Atomic weight (AW) : 151.92007 + Atomic weight ratio (AWR) : 150.61500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 23 reaction channels + - 7 special reactions + - 8 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 23 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.20350E+00 MeV Emin = 8.25800E+00 MeV frac = 1.00000E+00 Product nuclide = 62151.82c : (n,2n) + 3 MT = 51 Q = -1.21800E-01 MeV Emin = 1.22500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 4 MT = 52 Q = -3.66400E-01 MeV Emin = 3.65625E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 5 MT = 53 Q = -6.84800E-01 MeV Emin = 6.84800E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 6 MT = 54 Q = -7.06900E-01 MeV Emin = 7.06900E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 7 MT = 55 Q = -8.10400E-01 MeV Emin = 8.10400E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 8 MT = 56 Q = -9.63400E-01 MeV Emin = 9.63400E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 9 MT = 57 Q = -1.02300E+00 MeV Emin = 1.02300E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 10 MT = 58 Q = -1.04100E+00 MeV Emin = 1.04110E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 11 MT = 59 Q = -1.08300E+00 MeV Emin = 1.08280E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 12 MT = 60 Q = -1.12600E+00 MeV Emin = 1.12560E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 13 MT = 61 Q = -1.22200E+00 MeV Emin = 1.22200E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 14 MT = 62 Q = -1.23400E+00 MeV Emin = 1.23799E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 15 MT = 63 Q = -1.29300E+00 MeV Emin = 1.29280E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 16 MT = 91 Q = -1.30240E+00 MeV Emin = 1.30629E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 17 MT = 102 Q = 5.86840E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 62153.82c : (n,gamma) + 18 MT = 103 Q = -4.36770E+00 MeV Emin = 4.39670E+00 MeV frac = 1.00000E+00 Product nuclide = 611520 : (n,p) + 19 MT = 104 Q = -6.51660E+00 MeV Emin = 6.55987E+00 MeV frac = 1.00000E+00 Product nuclide = 61151.82c : (n,d) + 20 MT = 105 Q = -7.95900E+00 MeV Emin = 8.01188E+00 MeV frac = 1.00000E+00 Product nuclide = 611500 : (n,t) + 21 MT = 106 Q = -7.96510E+00 MeV Emin = 8.01798E+00 MeV frac = 1.00000E+00 Product nuclide = 60150.82c : (n,He-3) + 22 MT = 107 Q = 5.25900E+00 MeV Emin = 4.50000E-01 MeV frac = 1.00000E+00 Product nuclide = 601490 : (n,alpha) + 23 MT = 111 Q = -1.03190E+01 MeV Emin = 1.03875E+01 MeV frac = 1.00000E+00 Product nuclide = 601510 : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = -4.36770E+00 MeV Emin = 4.39670E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -6.51660E+00 MeV Emin = 6.55987E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -7.95900E+00 MeV Emin = 8.01188E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -7.96510E+00 MeV Emin = 8.01798E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 5.25900E+00 MeV Emin = 4.50000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -1.03190E+01 MeV Emin = 1.03875E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.39670E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.55987E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 8.01188E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 8.01798E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 4.50000E-01 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 8.84701E-04 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 1.22500E-01 MeV : total inelastic scattering + + Nuclide 220 / 1657 : 62153.82c -- samarium 153 (Sm-153) + + Pointers : 1793955 33265 + Primary type : Transport + Nuclide ZAI : 621530 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Sm153.ACE + Atomic weight (AW) : 152.92168 + Atomic weight ratio (AWR) : 151.60800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.67E+05 seconds (1.93 days) + Specific ingestion toxicity : 7.40E-10 Sv/Bq + Specific inhalation toxicity : 6.30E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 27 reaction channels + - 21 special reactions + - 9 transmutation reactions + - 6 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 27 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.86700E+00 MeV Emin = 5.90570E+00 MeV frac = 1.00000E+00 Product nuclide = 62152.82c : (n,2n) + 3 MT = 17 Q = -1.41250E+01 MeV Emin = 1.42182E+01 MeV frac = 1.00000E+00 Product nuclide = 62151.82c : (n,3n) + 4 MT = 22 Q = -6.09000E-01 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 601490 : (n,nalpha) + 5 MT = 24 Q = -5.64700E+00 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 60148.82c : (n,2nalpha) + 6 MT = 28 Q = -8.59000E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 611520 : (n,np) + 7 MT = 41 Q = -1.45300E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 61151.82c : (n,2np) + 8 MT = 51 Q = -7.54000E-03 MeV Emin = 7.00000E-03 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -3.58400E-02 MeV Emin = 3.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -5.35300E-02 MeV Emin = 5.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -6.54800E-02 MeV Emin = 5.98975E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -9.08700E-02 MeV Emin = 8.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -9.84000E-02 MeV Emin = 9.52592E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -1.12950E-01 MeV Emin = 1.06847E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -1.27300E-01 MeV Emin = 1.20917E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -1.74170E-01 MeV Emin = 1.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -1.82900E-01 MeV Emin = 1.79712E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -1.89200E-01 MeV Emin = 1.87277E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 62 Q = -1.94650E-01 MeV Emin = 1.93820E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 20 MT = 63 Q = -1.95900E-01 MeV Emin = 1.93820E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 21 MT = 64 Q = -2.37000E-01 MeV Emin = 2.19281E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 22 MT = 65 Q = -2.46300E-01 MeV Emin = 2.43244E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 23 MT = 66 Q = -2.61000E-01 MeV Emin = 2.55323E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 24 MT = 91 Q = -2.61000E-01 MeV Emin = 2.55323E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 25 MT = 102 Q = 7.96707E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 62154.82c : (n,gamma) + 26 MT = 103 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 611530 : (n,p) + 27 MT = 107 Q = 0.00000E+00 MeV Emin = 4.00000E-03 MeV frac = 1.00000E+00 Product nuclide = 60150.82c : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = -6.09000E-01 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 24 Q = -5.64700E+00 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,2nalpha) + 3 MT = 28 Q = -8.59000E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 4 MT = 41 Q = -1.45300E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,2np) + 5 MT = 103 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 107 Q = 0.00000E+00 MeV Emin = 4.00000E-03 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 21 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 4.00000E-03 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 8.50000E-04 MeV : damage-energy production + 4 MT = 600 Q = -1.09900E+00 MeV Emin = 2.00000E+00 MeV : (n,p) to ground state + 5 MT = 601 Q = -1.13100E+00 MeV Emin = 2.00000E+00 MeV : (n,p1) + 6 MT = 602 Q = -1.16500E+00 MeV Emin = 2.00000E+00 MeV : (n,p2) + 7 MT = 603 Q = -1.20600E+00 MeV Emin = 2.00000E+00 MeV : (n,p3) + 8 MT = 604 Q = -1.25000E+00 MeV Emin = 2.00000E+00 MeV : (n,p4) + 9 MT = 605 Q = -1.29900E+00 MeV Emin = 2.00000E+00 MeV : (n,p5) + 10 MT = 606 Q = -1.35400E+00 MeV Emin = 3.00000E+00 MeV : (n,p6) + 11 MT = 649 Q = -1.35400E+00 MeV Emin = 3.00000E+00 MeV : (n,p) to continuum + 12 MT = 800 Q = 6.77100E+00 MeV Emin = 4.00000E-03 MeV : (n,alpha) to ground state + 13 MT = 801 Q = 6.64079E+00 MeV Emin = 4.00000E-03 MeV : (n,a1) + 14 MT = 802 Q = 6.38955E+00 MeV Emin = 4.50000E-03 MeV : (n,a2) + 15 MT = 803 Q = 6.09563E+00 MeV Emin = 3.00000E-01 MeV : (n,a3) + 16 MT = 804 Q = 6.05060E+00 MeV Emin = 3.01563E-01 MeV : (n,a4) + 17 MT = 805 Q = 5.92034E+00 MeV Emin = 4.00000E-01 MeV : (n,a5) + 18 MT = 806 Q = 5.91806E+00 MeV Emin = 4.00000E-01 MeV : (n,a6) + 19 MT = 807 Q = 5.83614E+00 MeV Emin = 5.00000E-01 MeV : (n,a7) + 20 MT = 849 Q = 5.83614E+00 MeV Emin = 4.00000E-03 MeV : (n,alpha) to continuum + 21 MT = 4 Q = 0.00000E+00 MeV Emin = 7.00000E-03 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.07600E-01 MeV frac = 1.00000E+00 Product nuclide = 63153.82c : beta- + + Nuclide 221 / 1657 : 62154.82c -- samarium 154 (Sm-154) + + Pointers : 1800314 33311 + Primary type : Transport + Nuclide ZAI : 621540 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Sm154.ACE + Atomic weight (AW) : 153.92227 + Atomic weight ratio (AWR) : 152.60000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 36 reaction channels + - 21 special reactions + - 9 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 36 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.96700E+00 MeV Emin = 8.01921E+00 MeV frac = 1.00000E+00 Product nuclide = 62153.82c : (n,2n) + 3 MT = 17 Q = -1.38340E+01 MeV Emin = 1.39247E+01 MeV frac = 1.00000E+00 Product nuclide = 62152.82c : (n,3n) + 4 MT = 22 Q = -1.19600E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 60150.82c : (n,nalpha) + 5 MT = 24 Q = -8.57600E+00 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 601490 : (n,2nalpha) + 6 MT = 28 Q = -9.06600E+00 MeV Emin = 9.12541E+00 MeV frac = 1.00000E+00 Product nuclide = 611530 : (n,np) + 7 MT = 41 Q = -1.65570E+01 MeV Emin = 1.80000E+01 MeV frac = 1.00000E+00 Product nuclide = 611520 : (n,2np) + 8 MT = 51 Q = -8.19800E-02 MeV Emin = 8.24546E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -2.66790E-01 MeV Emin = 2.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -5.43730E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -9.02640E-01 MeV Emin = 9.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -9.21400E-01 MeV Emin = 9.17997E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -1.01239E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -1.09933E+00 MeV Emin = 1.10000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -1.10400E+00 MeV Emin = 1.10888E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -1.12000E+00 MeV Emin = 1.11929E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -1.17781E+00 MeV Emin = 1.15644E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -1.18065E+00 MeV Emin = 1.18696E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 62 Q = -1.20238E+00 MeV Emin = 1.20000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 20 MT = 63 Q = -1.28636E+00 MeV Emin = 1.25253E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 21 MT = 64 Q = -1.29500E+00 MeV Emin = 1.30000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 22 MT = 65 Q = -1.33280E+00 MeV Emin = 1.32251E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 23 MT = 66 Q = -1.33764E+00 MeV Emin = 1.34397E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 24 MT = 67 Q = -1.36500E+00 MeV Emin = 1.36018E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 25 MT = 68 Q = -1.37100E+00 MeV Emin = 1.37696E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 26 MT = 69 Q = -1.43100E+00 MeV Emin = 1.40000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 27 MT = 70 Q = -1.44005E+00 MeV Emin = 1.44493E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 28 MT = 71 Q = -1.47213E+00 MeV Emin = 1.46563E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 29 MT = 72 Q = -1.47500E+00 MeV Emin = 1.48322E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 30 MT = 73 Q = -1.47571E+00 MeV Emin = 1.48467E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 31 MT = 74 Q = -1.51519E+00 MeV Emin = 1.51256E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 32 MT = 75 Q = -1.53926E+00 MeV Emin = 1.53723E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 33 MT = 91 Q = -3.93422E-01 MeV Emin = 3.48000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 34 MT = 102 Q = 5.80697E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 621550 : (n,gamma) + 35 MT = 103 Q = 0.00000E+00 MeV Emin = 3.28338E+00 MeV frac = 1.00000E+00 Product nuclide = 611540 : (n,p) + 36 MT = 107 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 601510 : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = -1.19600E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 24 Q = -8.57600E+00 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,2nalpha) + 3 MT = 28 Q = -9.06600E+00 MeV Emin = 9.12541E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 4 MT = 41 Q = -1.65570E+01 MeV Emin = 1.80000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,2np) + 5 MT = 103 Q = 0.00000E+00 MeV Emin = 3.28338E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 107 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 21 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.28338E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 8.84982E-04 MeV : damage-energy production + 4 MT = 600 Q = -3.26200E+00 MeV Emin = 3.28338E+00 MeV : (n,p) to ground state + 5 MT = 601 Q = -3.26300E+00 MeV Emin = 3.28438E+00 MeV : (n,p1) + 6 MT = 602 Q = -3.31269E+00 MeV Emin = 3.33440E+00 MeV : (n,p2) + 7 MT = 603 Q = -3.33001E+00 MeV Emin = 5.00000E+00 MeV : (n,p3) + 8 MT = 604 Q = -3.34138E+00 MeV Emin = 5.00000E+00 MeV : (n,p4) + 9 MT = 605 Q = -3.36769E+00 MeV Emin = 5.00000E+00 MeV : (n,p5) + 10 MT = 606 Q = -3.41370E+00 MeV Emin = 5.00000E+00 MeV : (n,p6) + 11 MT = 607 Q = -3.41690E+00 MeV Emin = 5.00000E+00 MeV : (n,p7) + 12 MT = 608 Q = -3.43579E+00 MeV Emin = 5.00000E+00 MeV : (n,p8) + 13 MT = 609 Q = -3.44269E+00 MeV Emin = 5.00000E+00 MeV : (n,p9) + 14 MT = 610 Q = -3.44749E+00 MeV Emin = 5.00000E+00 MeV : (n,p10) + 15 MT = 611 Q = -3.45619E+00 MeV Emin = 5.00000E+00 MeV : (n,p11) + 16 MT = 612 Q = -3.50660E+00 MeV Emin = 5.00000E+00 MeV : (n,p12) + 17 MT = 613 Q = -3.53080E+00 MeV Emin = 5.00000E+00 MeV : (n,p13) + 18 MT = 649 Q = -3.53080E+00 MeV Emin = 5.00000E+00 MeV : (n,p) to continuum + 19 MT = 800 Q = 4.13800E+00 MeV Emin = 2.00000E+00 MeV : (n,alpha) to ground state + 20 MT = 849 Q = 4.13800E+00 MeV Emin = 2.00000E+00 MeV : (n,alpha) to continuum + 21 MT = 4 Q = 0.00000E+00 MeV Emin = 8.24546E-02 MeV : total inelastic scattering + + Nuclide 222 / 1657 : 63151.82c -- europium 151 (Eu-151) + + Pointers : 1819649 23651 + Primary type : Transport + Nuclide ZAI : 631510 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Eu151.ACE + Atomic weight (AW) : 150.91948 + Atomic weight ratio (AWR) : 149.62300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 22 reaction channels + - 7 special reactions + - 11 transmutation reactions + - 8 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 22 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.97050E+00 MeV Emin = 8.02377E+00 MeV frac = 1.00000E+00 Product nuclide = 631500 : (n,2n) + 3 MT = 17 Q = -1.44140E+01 MeV Emin = 1.45104E+01 MeV frac = 1.00000E+00 Product nuclide = 631490 : (n,3n) + 4 MT = 22 Q = 1.96400E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 61147.82c : (n,nalpha) + 5 MT = 28 Q = -4.89000E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 62150.82c : (n,np) + 6 MT = 51 Q = -2.20000E-02 MeV Emin = 2.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.94000E-01 MeV Emin = 1.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -1.96000E-01 MeV Emin = 1.96299E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -2.43000E-01 MeV Emin = 2.22307E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -3.08000E-01 MeV Emin = 3.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -3.50000E-01 MeV Emin = 3.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -5.05000E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -5.10000E-01 MeV Emin = 5.10881E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -6.20000E-01 MeV Emin = 6.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 91 Q = -6.95380E-01 MeV Emin = 6.67072E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 16 MT = 102 Q = 6.35100E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 63152.82c : (n,gamma) + 17 MT = 103 Q = 7.06440E-01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 62151.82c : (n,p) + 18 MT = 104 Q = -2.66540E+00 MeV Emin = 2.68322E+00 MeV frac = 1.00000E+00 Product nuclide = 62150.82c : (n,d) + 19 MT = 105 Q = -4.39350E+00 MeV Emin = 4.42286E+00 MeV frac = 1.00000E+00 Product nuclide = 62149.82c : (n,t) + 20 MT = 106 Q = -5.44680E+00 MeV Emin = 5.48320E+00 MeV frac = 1.00000E+00 Product nuclide = 61149.82c : (n,He-3) + 21 MT = 107 Q = 7.86550E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 61148.82c : (n,alpha) + 22 MT = 111 Q = -7.60380E+00 MeV Emin = 7.65462E+00 MeV frac = 1.00000E+00 Product nuclide = 611500 : (n,2p) + + 8 additional transport branches: + + 1 MT = 22 Q = 1.96400E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -4.89000E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = 7.06440E-01 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -2.66540E+00 MeV Emin = 2.68322E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -4.39350E+00 MeV Emin = 4.42286E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 106 Q = -5.44680E+00 MeV Emin = 5.48320E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 7 MT = 107 Q = 7.86550E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 8 MT = 111 Q = -7.60380E+00 MeV Emin = 7.65462E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 2.68322E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 4.42286E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 5.48320E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 2.00000E-02 MeV : total inelastic scattering + + Nuclide 223 / 1657 : 63152.82c -- europium 152 (Eu-152) + + Pointers : 1822461 23697 + Primary type : Transport + Nuclide ZAI : 631520 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Eu152.ACE + Atomic weight (AW) : 151.92209 + Atomic weight ratio (AWR) : 150.61700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 4.27E+08 seconds (13.5 years) + Specific ingestion toxicity : 1.40E-09 Sv/Bq + Specific inhalation toxicity : 4.20E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 25 reaction channels + - 7 special reactions + - 12 transmutation reactions + - 9 transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 25 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.31010E+00 MeV Emin = 6.35201E+00 MeV frac = 1.00000E+00 Product nuclide = 63151.82c : (n,2n) + 3 MT = 17 Q = -1.42802E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 631500 : (n,3n) + 4 MT = 22 Q = 1.56409E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 61148.82c : (n,nalpha) + 5 MT = 28 Q = -5.60364E+00 MeV Emin = 6.35201E+00 MeV frac = 1.00000E+00 Product nuclide = 62151.82c : (n,np) + 6 MT = 32 Q = -8.89463E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 62150.82c : (n,nd) + 7 MT = 33 Q = -1.06996E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 62149.82c : (n,nt) + 8 MT = 51 Q = -4.84999E-02 MeV Emin = 4.44110E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -6.81999E-02 MeV Emin = 6.43264E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -7.22999E-02 MeV Emin = 7.18231E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -8.98999E-02 MeV Emin = 9.04342E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -9.22999E-02 MeV Emin = 9.28341E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -1.08100E-01 MeV Emin = 1.04409E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -1.14800E-01 MeV Emin = 1.12612E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -1.25800E-01 MeV Emin = 1.24213E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -1.42700E-01 MeV Emin = 1.39660E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -1.47800E-01 MeV Emin = 1.46856E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -1.50700E-01 MeV Emin = 1.51458E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 91 Q = -1.70000E-01 MeV Emin = 1.66576E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 20 MT = 102 Q = 8.55039E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 63153.82c : (n,gamma) + 21 MT = 103 Q = 2.65945E+00 MeV Emin = 1.00138E-01 MeV frac = 1.00000E+00 Product nuclide = 62152.82c : (n,p) + 22 MT = 104 Q = -3.29353E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 62151.82c : (n,d) + 23 MT = 105 Q = -2.70948E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 62150.82c : (n,t) + 24 MT = 106 Q = -6.18984E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 611500 : (n,He-3) + 25 MT = 107 Q = 8.83319E+00 MeV Emin = 9.83389E-02 MeV frac = 1.00000E+00 Product nuclide = 61149.82c : (n,alpha) + + 9 additional transport branches: + + 1 MT = 22 Q = 1.56409E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -5.60364E+00 MeV Emin = 6.35201E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -8.89463E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.06996E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 103 Q = 2.65945E+00 MeV Emin = 1.00138E-01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 104 Q = -3.29353E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 7 MT = 105 Q = -2.70948E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 8 MT = 106 Q = -6.18984E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 9 MT = 107 Q = 8.83319E+00 MeV Emin = 9.83389E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.00138E-01 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 4.00000E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 9.00000E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 9.83389E-02 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 4.44110E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 2 Q = 1.87430E+00 MeV frac = 7.21000E-01 Product nuclide = 62152.82c : EC/beta+ + 2 RTYP = 1 Q = 1.81880E+00 MeV frac = 2.79000E-01 Product nuclide = 64152.82c : beta- + + Nuclide 224 / 1657 : 63153.82c -- europium 153 (Eu-153) + + Pointers : 1836114 23743 + Primary type : Transport + Nuclide ZAI : 631530 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Eu153.ACE + Atomic weight (AW) : 152.92168 + Atomic weight ratio (AWR) : 151.60800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 20 reaction channels + - 4 special reactions + - 7 transmutation reactions + - 5 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 20 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.55568E+00 MeV Emin = 8.61212E+00 MeV frac = 1.00000E+00 Product nuclide = 63152.82c : (n,2n) + 3 MT = 17 Q = -1.48614E+01 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 63151.82c : (n,3n) + 4 MT = 22 Q = 2.74060E-01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 61149.82c : (n,nalpha) + 5 MT = 28 Q = -5.88721E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 62152.82c : (n,np) + 6 MT = 51 Q = -8.33999E-02 MeV Emin = 8.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -9.73999E-02 MeV Emin = 9.63414E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -1.03200E-01 MeV Emin = 1.01941E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -1.51600E-01 MeV Emin = 1.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -1.72900E-01 MeV Emin = 1.71445E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -1.93100E-01 MeV Emin = 1.89293E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -2.35300E-01 MeV Emin = 2.27639E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -2.69700E-01 MeV Emin = 2.66109E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -3.21900E-01 MeV Emin = 3.12011E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -3.25100E-01 MeV Emin = 3.26122E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -3.96399E-01 MeV Emin = 3.90046E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 91 Q = -3.99999E-01 MeV Emin = 4.01330E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 18 MT = 102 Q = 6.44223E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 63154.82c : (n,gamma) + 19 MT = 103 Q = -2.05300E-02 MeV Emin = 9.50000E-01 MeV frac = 1.00000E+00 Product nuclide = 62153.82c : (n,p) + 20 MT = 107 Q = 5.87529E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 611500 : (n,alpha) + + 5 additional transport branches: + + 1 MT = 22 Q = 2.74060E-01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -5.88721E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 102 Q = 6.44223E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 631541 : (n,gamma) + 4 MT = 103 Q = -2.05300E-02 MeV Emin = 9.50000E-01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 107 Q = 5.87529E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 4 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 9.50000E-01 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 4 MT = 4 Q = 0.00000E+00 MeV Emin = 8.00000E-02 MeV : total inelastic scattering + + Nuclide 225 / 1657 : 63154.82c -- europium 154 (Eu-154) + + Pointers : 1838361 23789 + Primary type : Transport + Nuclide ZAI : 631540 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Eu154.ACE + Atomic weight (AW) : 153.92227 + Atomic weight ratio (AWR) : 152.60000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.71E+08 seconds (8.61 years) + Specific ingestion toxicity : 2.00E-09 Sv/Bq + Specific inhalation toxicity : 5.30E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 17 reaction channels + - 7 special reactions + - 10 transmutation reactions + - 7 transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 17 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.43800E+00 MeV Emin = 6.80000E+00 MeV frac = 1.00000E+00 Product nuclide = 63153.82c : (n,2n) + 3 MT = 17 Q = -1.49900E+01 MeV Emin = 1.50882E+01 MeV frac = 1.00000E+00 Product nuclide = 63152.82c : (n,3n) + 4 MT = 22 Q = -6.07000E-01 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 611500 : (n,nalpha) + 5 MT = 28 Q = -6.46500E+00 MeV Emin = 6.50737E+00 MeV frac = 1.00000E+00 Product nuclide = 62153.82c : (n,np) + 6 MT = 51 Q = -6.80000E-02 MeV Emin = 6.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -8.28000E-02 MeV Emin = 8.16695E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -1.22100E-01 MeV Emin = 1.11450E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -1.72200E-01 MeV Emin = 1.53114E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -1.80000E-01 MeV Emin = 1.77755E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 91 Q = -2.31900E-01 MeV Emin = 2.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 12 MT = 102 Q = 8.15141E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 63155.82c : (n,gamma) + 13 MT = 103 Q = 1.51240E+00 MeV Emin = 9.25000E-03 MeV frac = 1.00000E+00 Product nuclide = 62154.82c : (n,p) + 14 MT = 104 Q = -4.24040E+00 MeV Emin = 4.26819E+00 MeV frac = 1.00000E+00 Product nuclide = 62153.82c : (n,d) + 15 MT = 105 Q = -3.84950E+00 MeV Emin = 3.87473E+00 MeV frac = 1.00000E+00 Product nuclide = 62152.82c : (n,t) + 16 MT = 106 Q = -7.33190E+00 MeV Emin = 7.37995E+00 MeV frac = 1.00000E+00 Product nuclide = 611520 : (n,He-3) + 17 MT = 107 Q = 7.30150E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 61151.82c : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -6.07000E-01 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -6.46500E+00 MeV Emin = 6.50737E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = 1.51240E+00 MeV Emin = 9.25000E-03 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -4.24040E+00 MeV Emin = 4.26819E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -3.84950E+00 MeV Emin = 3.87473E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 106 Q = -7.33190E+00 MeV Emin = 7.37995E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 7 MT = 107 Q = 7.30150E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 9.25000E-03 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 4.26819E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 3.87473E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 7.37995E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 6.00000E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 2 Q = 7.17300E-01 MeV frac = 1.80000E-04 Product nuclide = 62154.82c : EC/beta+ + 2 RTYP = 1 Q = 1.96840E+00 MeV frac = 9.99820E-01 Product nuclide = 64154.82c : beta- + + Nuclide 226 / 1657 : 63155.82c -- europium 155 (Eu-155) + + Pointers : 1845163 23835 + Primary type : Transport + Nuclide ZAI : 631550 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Eu155.ACE + Atomic weight (AW) : 154.92287 + Atomic weight ratio (AWR) : 153.59200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.50E+08 seconds (4.76 years) + Specific ingestion toxicity : 3.20E-10 Sv/Bq + Specific inhalation toxicity : 6.90E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 21 reaction channels + - 7 special reactions + - 10 transmutation reactions + - 7 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 21 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.94820E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 63154.82c : (n,2n) + 3 MT = 17 Q = -1.44060E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 63153.82c : (n,3n) + 4 MT = 22 Q = -8.70000E-01 MeV Emin = 8.50000E-01 MeV frac = 1.00000E+00 Product nuclide = 61151.82c : (n,nalpha) + 5 MT = 28 Q = -6.45800E+00 MeV Emin = 6.50005E+00 MeV frac = 1.00000E+00 Product nuclide = 62154.82c : (n,np) + 6 MT = 51 Q = -6.95470E-02 MeV Emin = 7.37500E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -9.93530E-02 MeV Emin = 1.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -1.58960E-01 MeV Emin = 1.70000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -2.38450E-01 MeV Emin = 2.47500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -2.98060E-01 MeV Emin = 3.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -6.95470E-01 MeV Emin = 7.32475E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -8.44510E-01 MeV Emin = 8.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -9.93530E-01 MeV Emin = 1.09625E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -1.09000E+00 MeV Emin = 1.27781E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 91 Q = -1.27000E+00 MeV Emin = 1.27891E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 16 MT = 102 Q = 6.33968E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 63156.82c : (n,gamma) + 17 MT = 103 Q = -4.96770E+00 MeV Emin = 5.00004E+00 MeV frac = 1.00000E+00 Product nuclide = 621550 : (n,p) + 18 MT = 104 Q = -8.94190E+00 MeV Emin = 9.00012E+00 MeV frac = 1.00000E+00 Product nuclide = 62154.82c : (n,d) + 19 MT = 105 Q = -1.09290E+01 MeV Emin = 1.10002E+01 MeV frac = 1.00000E+00 Product nuclide = 62153.82c : (n,t) + 20 MT = 106 Q = -1.88770E+01 MeV Emin = 1.90000E+01 MeV frac = 1.00000E+00 Product nuclide = 611530 : (n,He-3) + 21 MT = 107 Q = 5.07850E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 611520 : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = -8.70000E-01 MeV Emin = 8.50000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -6.45800E+00 MeV Emin = 6.50005E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -4.96770E+00 MeV Emin = 5.00004E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -8.94190E+00 MeV Emin = 9.00012E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -1.09290E+01 MeV Emin = 1.10002E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 106 Q = -1.88770E+01 MeV Emin = 1.90000E+01 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 7 MT = 107 Q = 5.07850E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 5.00004E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 9.00012E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 1.10002E+01 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 1.90000E+01 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 7.37500E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.52100E-01 MeV frac = 1.00000E+00 Product nuclide = 64155.82c : beta- + + Nuclide 227 / 1657 : 63156.82c -- europium 156 (Eu-156) + + Pointers : 1848705 23881 + Primary type : Transport + Nuclide ZAI : 631560 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Eu156.ACE + Atomic weight (AW) : 155.92548 + Atomic weight ratio (AWR) : 154.58600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.31E+06 seconds (15.2 days) + Specific ingestion toxicity : 2.20E-09 Sv/Bq + Specific inhalation toxicity : 3.40E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 18 reaction channels + - 6 special reactions + - 11 transmutation reactions + - 8 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 18 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.33410E+00 MeV Emin = 6.37508E+00 MeV frac = 1.00000E+00 Product nuclide = 63155.82c : (n,2n) + 3 MT = 17 Q = -1.45092E+01 MeV Emin = 1.46031E+01 MeV frac = 1.00000E+00 Product nuclide = 63154.82c : (n,3n) + 4 MT = 22 Q = -1.21490E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 611520 : (n,nalpha) + 5 MT = 28 Q = -7.18063E+00 MeV Emin = 8.54375E+00 MeV frac = 1.00000E+00 Product nuclide = 621550 : (n,np) + 6 MT = 32 Q = -1.06886E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 62154.82c : (n,nd) + 7 MT = 33 Q = -1.24766E+01 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 62153.82c : (n,nt) + 8 MT = 51 Q = -2.26000E-02 MeV Emin = 2.22183E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -4.77999E-02 MeV Emin = 4.40546E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -8.71999E-02 MeV Emin = 8.38820E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -1.25300E-01 MeV Emin = 1.19583E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -2.91100E-01 MeV Emin = 2.71491E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 91 Q = -3.30000E-01 MeV Emin = 3.24101E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 14 MT = 102 Q = 7.44592E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 63157.82c : (n,gamma) + 15 MT = 103 Q = 6.74684E-02 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 621560 : (n,p) + 16 MT = 104 Q = -4.87051E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 621550 : (n,d) + 17 MT = 105 Q = -4.50346E+00 MeV Emin = 6.37508E+00 MeV frac = 1.00000E+00 Product nuclide = 62154.82c : (n,t) + 18 MT = 107 Q = 6.33120E+00 MeV Emin = 9.99883E-02 MeV frac = 1.00000E+00 Product nuclide = 611530 : (n,alpha) + + 8 additional transport branches: + + 1 MT = 22 Q = -1.21490E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -7.18063E+00 MeV Emin = 8.54375E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.06886E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.24766E+01 MeV Emin = 1.40000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 103 Q = 6.74684E-02 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 104 Q = -4.87051E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 7 MT = 105 Q = -4.50346E+00 MeV Emin = 6.37508E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 8 MT = 107 Q = 6.33120E+00 MeV Emin = 9.99883E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 6.37508E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 9.99883E-02 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 9.00000E-04 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 2.22183E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.44900E+00 MeV frac = 1.00000E+00 Product nuclide = 64156.82c : beta- + + Nuclide 228 / 1657 : 63157.82c -- europium 157 (Eu-157) + + Pointers : 1855178 23927 + Primary type : Transport + Nuclide ZAI : 631570 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Eu157.ACE + Atomic weight (AW) : 156.92507 + Atomic weight ratio (AWR) : 155.57700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 5.46E+04 seconds (15.2 hours) + Specific ingestion toxicity : 6.00E-10 Sv/Bq + Specific inhalation toxicity : 2.80E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 46 reaction channels + - 21 special reactions + - 9 transmutation reactions + - 6 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 46 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.44800E+00 MeV Emin = 7.49587E+00 MeV frac = 1.00000E+00 Product nuclide = 63156.82c : (n,2n) + 3 MT = 17 Q = -1.37850E+01 MeV Emin = 1.38736E+01 MeV frac = 1.00000E+00 Product nuclide = 63155.82c : (n,3n) + 4 MT = 22 Q = -1.20800E+00 MeV Emin = 7.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 611530 : (n,nalpha) + 5 MT = 24 Q = -8.69900E+00 MeV Emin = 1.55000E+01 MeV frac = 1.00000E+00 Product nuclide = 611520 : (n,2nalpha) + 6 MT = 28 Q = -7.38800E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 621560 : (n,np) + 7 MT = 41 Q = -1.46300E+01 MeV Emin = 1.65000E+01 MeV frac = 1.00000E+00 Product nuclide = 621550 : (n,2np) + 8 MT = 51 Q = -7.67100E-02 MeV Emin = 7.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -1.77000E-01 MeV Emin = 1.74566E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -1.97860E-01 MeV Emin = 1.86849E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -2.63230E-01 MeV Emin = 2.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -2.96000E-01 MeV Emin = 2.81413E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -3.50000E-01 MeV Emin = 3.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -3.94330E-01 MeV Emin = 3.93750E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -4.53500E-01 MeV Emin = 4.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -4.57000E-01 MeV Emin = 4.58176E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -5.39000E-01 MeV Emin = 5.21232E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -5.84000E-01 MeV Emin = 5.75000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 62 Q = -6.45000E-01 MeV Emin = 6.24573E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 20 MT = 63 Q = -6.70420E-01 MeV Emin = 6.62365E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 21 MT = 64 Q = -7.16310E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 22 MT = 65 Q = -7.24000E-01 MeV Emin = 7.28186E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 23 MT = 66 Q = -9.71990E-01 MeV Emin = 9.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 24 MT = 67 Q = -9.88380E-01 MeV Emin = 9.86486E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 25 MT = 68 Q = -1.02127E+00 MeV Emin = 1.01391E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 26 MT = 69 Q = -1.05700E+00 MeV Emin = 1.04581E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 27 MT = 70 Q = -1.07300E+00 MeV Emin = 1.07285E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 28 MT = 71 Q = -1.09800E+00 MeV Emin = 1.10000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 29 MT = 72 Q = -1.14500E+00 MeV Emin = 1.12871E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 30 MT = 73 Q = -1.24700E+00 MeV Emin = 1.20000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 31 MT = 74 Q = -1.30000E+00 MeV Emin = 1.28890E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 32 MT = 75 Q = -1.32200E+00 MeV Emin = 1.32224E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 33 MT = 76 Q = -1.36092E+00 MeV Emin = 1.35557E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 34 MT = 77 Q = -1.36900E+00 MeV Emin = 1.35557E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 27. excited state + 35 MT = 78 Q = -1.37732E+00 MeV Emin = 1.38199E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 28. excited state + 36 MT = 79 Q = -1.38294E+00 MeV Emin = 1.38900E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 29. excited state + 37 MT = 80 Q = -1.40400E+00 MeV Emin = 1.40243E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 30. excited state + 38 MT = 81 Q = -1.41847E+00 MeV Emin = 1.42046E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 31. excited state + 39 MT = 82 Q = -1.46312E+00 MeV Emin = 1.44277E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 32. excited state + 40 MT = 83 Q = -1.56200E+00 MeV Emin = 1.53602E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 33. excited state + 41 MT = 84 Q = -1.60300E+00 MeV Emin = 1.59267E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 34. excited state + 42 MT = 85 Q = -1.63500E+00 MeV Emin = 1.63498E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 35. excited state + 43 MT = 91 Q = -4.91839E-01 MeV Emin = 4.77469E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 44 MT = 102 Q = 5.81557E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 631580 : (n,gamma) + 45 MT = 103 Q = 0.00000E+00 MeV Emin = 3.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 621570 : (n,p) + 46 MT = 107 Q = 0.00000E+00 MeV Emin = 1.70000E+00 MeV frac = 1.00000E+00 Product nuclide = 611540 : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = -1.20800E+00 MeV Emin = 7.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 24 Q = -8.69900E+00 MeV Emin = 1.55000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,2nalpha) + 3 MT = 28 Q = -7.38800E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 4 MT = 41 Q = -1.46300E+01 MeV Emin = 1.65000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,2np) + 5 MT = 103 Q = 0.00000E+00 MeV Emin = 3.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 107 Q = 0.00000E+00 MeV Emin = 1.70000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 21 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.50000E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 1.70000E+00 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 9.00000E-04 MeV : damage-energy production + 4 MT = 600 Q = -1.95200E+00 MeV Emin = 3.50000E+00 MeV : (n,p) to ground state + 5 MT = 649 Q = -1.95200E+00 MeV Emin = 3.70000E+00 MeV : (n,p) to continuum + 6 MT = 800 Q = 4.59600E+00 MeV Emin = 1.70000E+00 MeV : (n,alpha) to ground state + 7 MT = 801 Q = 4.59500E+00 MeV Emin = 4.75000E+00 MeV : (n,a1) + 8 MT = 802 Q = 4.54531E+00 MeV Emin = 1.70000E+00 MeV : (n,a2) + 9 MT = 803 Q = 4.52799E+00 MeV Emin = 1.70000E+00 MeV : (n,a3) + 10 MT = 804 Q = 4.51662E+00 MeV Emin = 1.70000E+00 MeV : (n,a4) + 11 MT = 805 Q = 4.49031E+00 MeV Emin = 1.70000E+00 MeV : (n,a5) + 12 MT = 806 Q = 4.44430E+00 MeV Emin = 2.00000E+00 MeV : (n,a6) + 13 MT = 807 Q = 4.44110E+00 MeV Emin = 2.00000E+00 MeV : (n,a7) + 14 MT = 808 Q = 4.42221E+00 MeV Emin = 2.00000E+00 MeV : (n,a8) + 15 MT = 809 Q = 4.41531E+00 MeV Emin = 2.00000E+00 MeV : (n,a9) + 16 MT = 810 Q = 4.41051E+00 MeV Emin = 2.00000E+00 MeV : (n,a10) + 17 MT = 811 Q = 4.40181E+00 MeV Emin = 2.00000E+00 MeV : (n,a11) + 18 MT = 812 Q = 4.35140E+00 MeV Emin = 2.00000E+00 MeV : (n,a12) + 19 MT = 813 Q = 4.32720E+00 MeV Emin = 2.00000E+00 MeV : (n,a13) + 20 MT = 849 Q = 4.32720E+00 MeV Emin = 2.20000E+00 MeV : (n,alpha) to continuum + 21 MT = 4 Q = 0.00000E+00 MeV Emin = 7.00000E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.36300E+00 MeV frac = 1.00000E+00 Product nuclide = 64157.82c : beta- + + Nuclide 229 / 1657 : 64152.82c -- gadolinium 152 (Gd-152) + + Pointers : 1873153 24295 + Primary type : Transport + Nuclide ZAI : 641520 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Gd152.ACE + Atomic weight (AW) : 151.92007 + Atomic weight ratio (AWR) : 150.61500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 3.41E+21 seconds (1.08E+14 years) + Specific ingestion toxicity : 4.10E-08 Sv/Bq + Specific inhalation toxicity : 1.90E-05 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 43 reaction channels + - 7 special reactions + - 12 transmutation reactions + - 9 transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 43 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.61109E+00 MeV Emin = 8.66828E+00 MeV frac = 1.00000E+00 Product nuclide = 641510 : (n,2n) + 3 MT = 17 Q = -1.50902E+01 MeV Emin = 1.51904E+01 MeV frac = 1.00000E+00 Product nuclide = 641500 : (n,3n) + 4 MT = 22 Q = 2.21009E+00 MeV Emin = 1.01563E-01 MeV frac = 1.00000E+00 Product nuclide = 62148.82c : (n,nalpha) + 5 MT = 28 Q = -7.34664E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 63151.82c : (n,np) + 6 MT = 32 Q = -1.30066E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 631500 : (n,nd) + 7 MT = 33 Q = -1.32146E+01 MeV Emin = 1.51904E+01 MeV frac = 1.00000E+00 Product nuclide = 631490 : (n,nt) + 8 MT = 51 Q = -3.44300E-01 MeV Emin = 3.23293E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -6.15399E-01 MeV Emin = 6.16736E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -7.55399E-01 MeV Emin = 7.60156E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -9.30599E-01 MeV Emin = 9.18389E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -1.04780E+00 MeV Emin = 1.04909E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -1.10920E+00 MeV Emin = 1.10111E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -1.12320E+00 MeV Emin = 1.12361E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -1.22730E+00 MeV Emin = 1.21089E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -1.28230E+00 MeV Emin = 1.27551E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -1.31470E+00 MeV Emin = 1.31120E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -1.31840E+00 MeV Emin = 1.32529E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 62 Q = -1.43400E+00 MeV Emin = 1.41625E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 20 MT = 63 Q = -1.46050E+00 MeV Emin = 1.46020E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 21 MT = 64 Q = -1.47050E+00 MeV Emin = 1.47523E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 22 MT = 65 Q = -1.55020E+00 MeV Emin = 1.53025E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 23 MT = 66 Q = -1.60560E+00 MeV Emin = 1.59535E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 24 MT = 67 Q = -1.64340E+00 MeV Emin = 1.63529E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 25 MT = 68 Q = -1.66810E+00 MeV Emin = 1.66675E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 26 MT = 69 Q = -1.69240E+00 MeV Emin = 1.69141E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 27 MT = 70 Q = -1.74670E+00 MeV Emin = 1.75000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 28 MT = 71 Q = -1.75600E+00 MeV Emin = 1.75830E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 29 MT = 72 Q = -1.77160E+00 MeV Emin = 1.77551E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 30 MT = 73 Q = -1.80770E+00 MeV Emin = 1.80607E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 31 MT = 74 Q = -1.83960E+00 MeV Emin = 1.83576E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 32 MT = 75 Q = -1.86150E+00 MeV Emin = 1.86284E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 33 MT = 76 Q = -1.86200E+00 MeV Emin = 1.87411E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 34 MT = 77 Q = -1.88020E+00 MeV Emin = 1.88352E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 27. excited state + 35 MT = 78 Q = -1.91540E+00 MeV Emin = 1.91483E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 28. excited state + 36 MT = 79 Q = -1.94120E+00 MeV Emin = 1.94541E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 29. excited state + 37 MT = 91 Q = -1.97540E+00 MeV Emin = 1.97561E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 38 MT = 102 Q = 6.48739E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 641530 : (n,gamma) + 39 MT = 103 Q = -1.03654E+00 MeV Emin = 2.00391E+00 MeV frac = 1.00000E+00 Product nuclide = 63152.82c : (n,p) + 40 MT = 104 Q = -5.03652E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 63151.82c : (n,d) + 41 MT = 105 Q = -6.82147E+00 MeV Emin = 8.66828E+00 MeV frac = 1.00000E+00 Product nuclide = 631500 : (n,t) + 42 MT = 106 Q = -4.50984E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 62150.82c : (n,He-3) + 43 MT = 107 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 62149.82c : (n,alpha) + + 9 additional transport branches: + + 1 MT = 22 Q = 2.21009E+00 MeV Emin = 1.01563E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -7.34664E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.30066E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.32146E+01 MeV Emin = 1.51904E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 103 Q = -1.03654E+00 MeV Emin = 2.00391E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 104 Q = -5.03652E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 7 MT = 105 Q = -6.82147E+00 MeV Emin = 8.66828E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 8 MT = 106 Q = -4.50984E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 9 MT = 107 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.00391E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 8.66828E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 9.00000E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 3.23293E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 4 Q = 2.20460E+00 MeV frac = 1.00000E+00 Product nuclide = 62148.82c : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 2.20460E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 230 / 1657 : 64154.82c -- gadolinium 154 (Gd-154) + + Pointers : 1878961 24341 + Primary type : Transport + Nuclide ZAI : 641540 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Gd154.ACE + Atomic weight (AW) : 153.92127 + Atomic weight ratio (AWR) : 152.59900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 24 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 24 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -1.23000E-01 MeV Emin = 1.12500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -3.71000E-01 MeV Emin = 3.70000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -6.81000E-01 MeV Emin = 5.27731E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -7.18000E-01 MeV Emin = 7.15169E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -8.16000E-01 MeV Emin = 7.60675E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -9.99000E-01 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 57 Q = -1.05000E+00 MeV Emin = 1.03122E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 9 MT = 58 Q = -1.06000E+00 MeV Emin = 1.06190E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 10 MT = 59 Q = -1.13000E+00 MeV Emin = 1.10217E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 11 MT = 60 Q = -1.26000E+00 MeV Emin = 1.23552E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 12 MT = 61 Q = -1.40000E+00 MeV Emin = 1.38415E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 13 MT = 62 Q = -1.62000E+00 MeV Emin = 1.60000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 14 MT = 63 Q = -1.65000E+00 MeV Emin = 1.64571E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 15 MT = 64 Q = -1.72000E+00 MeV Emin = 1.72041E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 16 MT = 65 Q = -1.77000E+00 MeV Emin = 1.78000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 17 MT = 91 Q = -1.77000E+00 MeV Emin = 1.78000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 18 MT = 102 Q = 6.44600E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 64155.82c : (n,gamma) + 19 MT = 103 Q = -1.19490E+00 MeV Emin = 1.17000E+00 MeV frac = 1.00000E+00 Product nuclide = 63154.82c : (n,p) + 20 MT = 104 Q = -5.40330E+00 MeV Emin = 5.43871E+00 MeV frac = 1.00000E+00 Product nuclide = 63153.82c : (n,d) + 21 MT = 105 Q = -7.69540E+00 MeV Emin = 7.74583E+00 MeV frac = 1.00000E+00 Product nuclide = 63152.82c : (n,t) + 22 MT = 106 Q = -5.80080E+00 MeV Emin = 5.83881E+00 MeV frac = 1.00000E+00 Product nuclide = 62152.82c : (n,He-3) + 23 MT = 107 Q = 6.51430E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 62151.82c : (n,alpha) + 24 MT = 111 Q = -7.65080E+00 MeV Emin = 7.70094E+00 MeV frac = 1.00000E+00 Product nuclide = 62153.82c : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = -1.19490E+00 MeV Emin = 1.17000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -5.40330E+00 MeV Emin = 5.43871E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -7.69540E+00 MeV Emin = 7.74583E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -5.80080E+00 MeV Emin = 5.83881E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 6.51430E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -7.65080E+00 MeV Emin = 7.70094E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.17000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.43871E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 7.74583E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 5.83881E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 1.12500E-01 MeV : total inelastic scattering + + Nuclide 231 / 1657 : 64155.82c -- gadolinium 155 (Gd-155) + + Pointers : 1881773 24387 + Primary type : Transport + Nuclide ZAI : 641550 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Gd155.ACE + Atomic weight (AW) : 154.92287 + Atomic weight ratio (AWR) : 153.59200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 38 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 38 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -6.00000E-02 MeV Emin = 6.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -8.65000E-02 MeV Emin = 8.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -1.05300E-01 MeV Emin = 1.02993E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -1.07600E-01 MeV Emin = 1.07433E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -1.18000E-01 MeV Emin = 1.16478E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -1.21500E-01 MeV Emin = 1.21631E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 57 Q = -1.46100E-01 MeV Emin = 1.41635E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 9 MT = 58 Q = -2.14300E-01 MeV Emin = 2.07847E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 10 MT = 59 Q = -2.35200E-01 MeV Emin = 2.27528E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 11 MT = 60 Q = -2.51000E-01 MeV Emin = 2.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 12 MT = 61 Q = -2.66700E-01 MeV Emin = 2.64485E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 13 MT = 62 Q = -2.68600E-01 MeV Emin = 2.69393E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 14 MT = 63 Q = -2.86900E-01 MeV Emin = 2.84739E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 15 MT = 64 Q = -3.21500E-01 MeV Emin = 3.11796E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 16 MT = 65 Q = -3.26000E-01 MeV Emin = 3.25858E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 17 MT = 66 Q = -3.67700E-01 MeV Emin = 3.62225E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 18 MT = 67 Q = -3.90000E-01 MeV Emin = 3.86928E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 19 MT = 68 Q = -3.93000E-01 MeV Emin = 3.94049E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 20 MT = 69 Q = -4.22500E-01 MeV Emin = 4.17828E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 21 MT = 70 Q = -4.27200E-01 MeV Emin = 4.27616E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 22 MT = 71 Q = -4.51300E-01 MeV Emin = 4.48174E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 23 MT = 72 Q = -4.87000E-01 MeV Emin = 4.81188E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 24 MT = 73 Q = -4.88800E-01 MeV Emin = 4.91077E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 25 MT = 74 Q = -5.33000E-01 MeV Emin = 5.27353E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 26 MT = 75 Q = -5.56000E-01 MeV Emin = 5.50939E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 27 MT = 76 Q = -5.59900E-01 MeV Emin = 5.61583E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 28 MT = 77 Q = -5.92400E-01 MeV Emin = 5.88079E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 27. excited state + 29 MT = 78 Q = -6.15500E-01 MeV Emin = 6.10788E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 28. excited state + 30 MT = 79 Q = -6.17000E-01 MeV Emin = 6.20828E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 29. excited state + 31 MT = 91 Q = -6.48000E-01 MeV Emin = 6.44419E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 32 MT = 102 Q = 8.53640E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 64156.82c : (n,gamma) + 33 MT = 103 Q = 5.36450E-01 MeV Emin = 4.00000E-02 MeV frac = 1.00000E+00 Product nuclide = 63155.82c : (n,p) + 34 MT = 104 Q = -5.40740E+00 MeV Emin = 5.44261E+00 MeV frac = 1.00000E+00 Product nuclide = 63154.82c : (n,d) + 35 MT = 105 Q = -5.58410E+00 MeV Emin = 5.62046E+00 MeV frac = 1.00000E+00 Product nuclide = 63153.82c : (n,t) + 36 MT = 106 Q = -6.37170E+00 MeV Emin = 6.41319E+00 MeV frac = 1.00000E+00 Product nuclide = 62153.82c : (n,He-3) + 37 MT = 107 Q = 8.33370E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 62152.82c : (n,alpha) + 38 MT = 111 Q = -6.12130E+00 MeV Emin = 6.16115E+00 MeV frac = 1.00000E+00 Product nuclide = 62154.82c : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = 5.36450E-01 MeV Emin = 4.00000E-02 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -5.40740E+00 MeV Emin = 5.44261E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -5.58410E+00 MeV Emin = 5.62046E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -6.37170E+00 MeV Emin = 6.41319E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 8.33370E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -6.12130E+00 MeV Emin = 6.16115E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.00000E-02 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.44261E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 5.62046E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 6.41319E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 6.00000E-02 MeV : total inelastic scattering + + Nuclide 232 / 1657 : 64156.82c -- gadolinium 156 (Gd-156) + + Pointers : 1885791 24433 + Primary type : Transport + Nuclide ZAI : 641560 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Gd156.ACE + Atomic weight (AW) : 155.92205 + Atomic weight ratio (AWR) : 154.58260 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 24 reaction channels + - 7 special reactions + - 8 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 24 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.52690E+00 MeV Emin = 8.58210E+00 MeV frac = 1.00000E+00 Product nuclide = 64155.82c : (n,2n) + 3 MT = 51 Q = -8.90000E-02 MeV Emin = 8.82875E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 4 MT = 52 Q = -2.88000E-01 MeV Emin = 2.44930E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 5 MT = 53 Q = -5.85000E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 6 MT = 54 Q = -9.60000E-01 MeV Emin = 1.27660E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 7 MT = 55 Q = -1.04950E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 8 MT = 56 Q = -1.13200E+00 MeV Emin = 1.09815E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 9 MT = 57 Q = -1.15400E+00 MeV Emin = 1.15075E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 10 MT = 58 Q = -1.16800E+00 MeV Emin = 1.16880E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 11 MT = 59 Q = -1.24200E+00 MeV Emin = 1.20000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 12 MT = 60 Q = -1.24900E+00 MeV Emin = 1.25405E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 13 MT = 61 Q = -1.26800E+00 MeV Emin = 1.26710E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 14 MT = 62 Q = -1.32000E+00 MeV Emin = 1.30275E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 15 MT = 63 Q = -1.35800E+00 MeV Emin = 1.34790E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 16 MT = 64 Q = -1.36600E+00 MeV Emin = 1.37090E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 17 MT = 91 Q = -1.40800E+00 MeV Emin = 1.40000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 18 MT = 102 Q = 6.35980E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 64157.82c : (n,gamma) + 19 MT = 103 Q = -1.66980E+00 MeV Emin = 1.68041E+00 MeV frac = 1.00000E+00 Product nuclide = 63156.82c : (n,p) + 20 MT = 104 Q = -5.77330E+00 MeV Emin = 5.81065E+00 MeV frac = 1.00000E+00 Product nuclide = 63155.82c : (n,d) + 21 MT = 105 Q = -7.68540E+00 MeV Emin = 7.73512E+00 MeV frac = 1.00000E+00 Product nuclide = 63154.82c : (n,t) + 22 MT = 106 Q = -6.93950E+00 MeV Emin = 6.98439E+00 MeV frac = 1.00000E+00 Product nuclide = 62154.82c : (n,He-3) + 23 MT = 107 Q = 5.66550E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 62153.82c : (n,alpha) + 24 MT = 111 Q = -8.84330E+00 MeV Emin = 8.90051E+00 MeV frac = 1.00000E+00 Product nuclide = 621550 : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = -1.66980E+00 MeV Emin = 1.68041E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -5.77330E+00 MeV Emin = 5.81065E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -7.68540E+00 MeV Emin = 7.73512E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -6.93950E+00 MeV Emin = 6.98439E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 5.66550E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -8.84330E+00 MeV Emin = 8.90051E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.68041E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.81065E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 7.73512E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 6.98439E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 8.82875E-02 MeV : total inelastic scattering + + Nuclide 233 / 1657 : 64157.82c -- gadolinium 157 (Gd-157) + + Pointers : 1888603 24479 + Primary type : Transport + Nuclide ZAI : 641570 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Gd157.ACE + Atomic weight (AW) : 156.92406 + Atomic weight ratio (AWR) : 155.57600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 37 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 37 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -5.45000E-02 MeV Emin = 5.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -6.40000E-02 MeV Emin = 6.32163E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -1.15800E-01 MeV Emin = 1.08272E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -1.31500E-01 MeV Emin = 1.28642E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -1.81000E-01 MeV Emin = 1.74122E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -2.27400E-01 MeV Emin = 2.21646E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 57 Q = -3.46000E-01 MeV Emin = 3.36168E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 9 MT = 58 Q = -3.60000E-01 MeV Emin = 3.57030E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 10 MT = 59 Q = -4.25000E-01 MeV Emin = 4.17511E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 11 MT = 60 Q = -4.36600E-01 MeV Emin = 4.35028E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 12 MT = 61 Q = -4.77200E-01 MeV Emin = 4.71329E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 13 MT = 62 Q = -5.17000E-01 MeV Emin = 5.10162E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 14 MT = 63 Q = -5.27000E-01 MeV Emin = 5.25355E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 15 MT = 64 Q = -6.17000E-01 MeV Emin = 6.00896E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 16 MT = 65 Q = -6.39000E-01 MeV Emin = 6.34804E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 17 MT = 66 Q = -6.83000E-01 MeV Emin = 6.65249E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 18 MT = 67 Q = -6.85000E-01 MeV Emin = 6.88397E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 19 MT = 68 Q = -6.87000E-01 MeV Emin = 6.90410E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 20 MT = 69 Q = -7.00000E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 21 MT = 70 Q = -7.04000E-01 MeV Emin = 7.07519E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 22 MT = 71 Q = -7.21000E-01 MeV Emin = 7.19218E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 23 MT = 72 Q = -7.45000E-01 MeV Emin = 7.40731E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 24 MT = 73 Q = -7.51000E-01 MeV Emin = 7.52808E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 25 MT = 74 Q = -7.65000E-01 MeV Emin = 7.62872E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 26 MT = 75 Q = -7.91000E-01 MeV Emin = 7.86272E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 27 MT = 76 Q = -8.10000E-01 MeV Emin = 8.07603E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 28 MT = 77 Q = -8.13000E-01 MeV Emin = 8.16716E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 27. excited state + 29 MT = 78 Q = -8.39000E-01 MeV Emin = 8.43638E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 28. excited state + 30 MT = 91 Q = -8.50000E-01 MeV Emin = 8.49928E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 31 MT = 102 Q = 7.93740E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 64158.82c : (n,gamma) + 32 MT = 103 Q = -5.77180E-01 MeV Emin = 5.69004E-01 MeV frac = 1.00000E+00 Product nuclide = 63157.82c : (n,p) + 33 MT = 104 Q = -5.80430E+00 MeV Emin = 5.84161E+00 MeV frac = 1.00000E+00 Product nuclide = 63156.82c : (n,d) + 34 MT = 105 Q = -5.87600E+00 MeV Emin = 5.91377E+00 MeV frac = 1.00000E+00 Product nuclide = 63155.82c : (n,t) + 35 MT = 106 Q = -7.48630E+00 MeV Emin = 7.53442E+00 MeV frac = 1.00000E+00 Product nuclide = 621550 : (n,He-3) + 36 MT = 107 Q = 7.27300E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 62154.82c : (n,alpha) + 37 MT = 111 Q = -7.96070E+00 MeV Emin = 8.01187E+00 MeV frac = 1.00000E+00 Product nuclide = 621560 : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = -5.77180E-01 MeV Emin = 5.69004E-01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -5.80430E+00 MeV Emin = 5.84161E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -5.87600E+00 MeV Emin = 5.91377E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -7.48630E+00 MeV Emin = 7.53442E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 7.27300E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -7.96070E+00 MeV Emin = 8.01187E+00 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 5.69004E-01 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.84161E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 5.91377E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 7.53442E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 5.00000E-02 MeV : total inelastic scattering + + Nuclide 234 / 1657 : 64158.82c -- gadolinium 158 (Gd-158) + + Pointers : 1892364 24525 + Primary type : Transport + Nuclide ZAI : 641580 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Gd158.ACE + Atomic weight (AW) : 157.92466 + Atomic weight ratio (AWR) : 156.56800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 20 reaction channels + - 7 special reactions + - 7 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 20 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -7.95000E-02 MeV Emin = 7.81262E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -2.61000E-01 MeV Emin = 2.42500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -5.39000E-01 MeV Emin = 6.17500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -8.98000E-01 MeV Emin = 1.56500E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -9.78000E-01 MeV Emin = 9.13188E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -1.02000E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 57 Q = -1.04000E+00 MeV Emin = 1.03656E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 9 MT = 58 Q = -1.18000E+00 MeV Emin = 1.11707E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 10 MT = 59 Q = -1.27000E+00 MeV Emin = 1.23282E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 11 MT = 60 Q = -1.40000E+00 MeV Emin = 1.34351E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 12 MT = 61 Q = -1.52000E+00 MeV Emin = 1.46932E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 13 MT = 91 Q = -1.52000E+00 MeV Emin = 1.56500E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 14 MT = 102 Q = 5.94310E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 641590 : (n,gamma) + 15 MT = 103 Q = -2.66740E+00 MeV Emin = 2.68444E+00 MeV frac = 1.00000E+00 Product nuclide = 631580 : (n,p) + 16 MT = 104 Q = -6.28810E+00 MeV Emin = 6.32826E+00 MeV frac = 1.00000E+00 Product nuclide = 63157.82c : (n,d) + 17 MT = 105 Q = -7.48350E+00 MeV Emin = 7.53130E+00 MeV frac = 1.00000E+00 Product nuclide = 63156.82c : (n,t) + 18 MT = 106 Q = -8.18010E+00 MeV Emin = 8.23235E+00 MeV frac = 1.00000E+00 Product nuclide = 621560 : (n,He-3) + 19 MT = 107 Q = 5.14970E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 621550 : (n,alpha) + 20 MT = 111 Q = -1.03340E+01 MeV Emin = 1.04000E+01 MeV frac = 1.00000E+00 Product nuclide = 621570 : (n,2p) + + 6 additional transport branches: + + 1 MT = 103 Q = -2.66740E+00 MeV Emin = 2.68444E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -6.28810E+00 MeV Emin = 6.32826E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -7.48350E+00 MeV Emin = 7.53130E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 106 Q = -8.18010E+00 MeV Emin = 8.23235E+00 MeV frac = 1.00000E+00 Product nuclide = 2003.82c : (n,He-3) + 5 MT = 107 Q = 5.14970E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + 6 MT = 111 Q = -1.03340E+01 MeV Emin = 1.04000E+01 MeV frac = 2.00000E+00 Product nuclide = 1001.82c : (n,2p) + + 7 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.68444E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.32826E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 7.53130E+00 MeV : total triton production + 4 MT = 206 Q = 0.00000E+00 MeV Emin = 8.23235E+00 MeV : total He-3 production + 5 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 6 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 7 MT = 4 Q = 0.00000E+00 MeV Emin = 7.81262E-02 MeV : total inelastic scattering + + Nuclide 235 / 1657 : 64160.82c -- gadolinium 160 (Gd-160) + + Pointers : 1896501 24571 + Primary type : Transport + Nuclide ZAI : 641600 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Gd160.ACE + Atomic weight (AW) : 159.92686 + Atomic weight ratio (AWR) : 158.55300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 4.10E+24 seconds (1.3E+17 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 13 reaction channels + - 6 special reactions + - 5 transmutation reactions + - 4 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 13 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -7.53000E-02 MeV Emin = 7.11702E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -2.48000E-01 MeV Emin = 2.24780E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -5.13000E-01 MeV Emin = 4.52500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -8.70000E-01 MeV Emin = 1.40000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -1.01000E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -1.19000E+00 MeV Emin = 1.10695E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 91 Q = -1.19000E+00 MeV Emin = 1.40000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 9 MT = 102 Q = 5.63300E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 641610 : (n,gamma) + 10 MT = 103 Q = -3.61910E+00 MeV Emin = 3.64193E+00 MeV frac = 1.00000E+00 Product nuclide = 631600 : (n,p) + 11 MT = 104 Q = -7.07480E+00 MeV Emin = 7.11942E+00 MeV frac = 1.00000E+00 Product nuclide = 631590 : (n,d) + 12 MT = 105 Q = -7.57840E+00 MeV Emin = 7.62620E+00 MeV frac = 1.00000E+00 Product nuclide = 631580 : (n,t) + 13 MT = 107 Q = 4.56190E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 621570 : (n,alpha) + + 4 additional transport branches: + + 1 MT = 103 Q = -3.61910E+00 MeV Emin = 3.64193E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 104 Q = -7.07480E+00 MeV Emin = 7.11942E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 3 MT = 105 Q = -7.57840E+00 MeV Emin = 7.62620E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 4 MT = 107 Q = 4.56190E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.64193E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.11942E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 7.62620E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 7.11702E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 11 Q = 1.72950E+00 MeV frac = 1.00000E+00 Product nuclide = 66160.82c : beta- + beta- + + Nuclide 236 / 1657 : 65159.82c -- terbium 159 (Tb-159) + + Pointers : 1911567 34323 + Primary type : Transport + Nuclide ZAI : 651590 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Tb159.ACE + Atomic weight (AW) : 158.92525 + Atomic weight ratio (AWR) : 157.56000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 35 reaction channels + - 6 special reactions + - 11 transmutation reactions + - 8 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 35 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.13710E+00 MeV Emin = 8.18875E+00 MeV frac = 1.00000E+00 Product nuclide = 651580 : (n,2n) + 3 MT = 17 Q = -1.49212E+01 MeV Emin = 1.50159E+01 MeV frac = 1.00000E+00 Product nuclide = 651570 : (n,3n) + 4 MT = 22 Q = -1.32906E-01 MeV Emin = 3.37581E-01 MeV frac = 1.00000E+00 Product nuclide = 63155.82c : (n,nalpha) + 5 MT = 28 Q = -6.13864E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 64158.82c : (n,np) + 6 MT = 32 Q = -1.17706E+01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 64157.82c : (n,nd) + 7 MT = 33 Q = -1.19506E+01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 64156.82c : (n,nt) + 8 MT = 51 Q = -5.79999E-02 MeV Emin = 5.41840E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -1.37500E-01 MeV Emin = 1.33750E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -2.41400E-01 MeV Emin = 2.32199E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -3.47900E-01 MeV Emin = 3.37581E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -3.62599E-01 MeV Emin = 3.59354E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -3.63699E-01 MeV Emin = 3.65731E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -3.89499E-01 MeV Emin = 3.86292E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -4.28999E-01 MeV Emin = 4.23792E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -4.55199E-01 MeV Emin = 4.52321E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -5.10599E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -5.33999E-01 MeV Emin = 5.28559E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 62 Q = -5.45699E-01 MeV Emin = 5.43276E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 20 MT = 63 Q = -5.48299E-01 MeV Emin = 5.50843E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 21 MT = 64 Q = -5.80899E-01 MeV Emin = 5.76385E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 22 MT = 65 Q = -6.17699E-01 MeV Emin = 6.13519E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 23 MT = 66 Q = -6.68999E-01 MeV Emin = 6.62692E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 24 MT = 67 Q = -6.74299E-01 MeV Emin = 6.73246E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 25 MT = 68 Q = -6.78699E-01 MeV Emin = 6.80794E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 26 MT = 69 Q = -7.61299E-01 MeV Emin = 7.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 27 MT = 70 Q = -7.77999E-01 MeV Emin = 7.74535E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 28 MT = 71 Q = -8.22999E-01 MeV Emin = 8.14111E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 29 MT = 72 Q = -8.54999E-01 MeV Emin = 8.48351E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 30 MT = 91 Q = -8.59999E-01 MeV Emin = 8.62942E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 31 MT = 102 Q = 6.37521E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 65160.82c : (n,gamma) + 32 MT = 103 Q = -1.91535E-01 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 641590 : (n,p) + 33 MT = 104 Q = -3.82852E+00 MeV Emin = 5.62092E+00 MeV frac = 1.00000E+00 Product nuclide = 64158.82c : (n,d) + 34 MT = 105 Q = -5.58546E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 64157.82c : (n,t) + 35 MT = 107 Q = 6.20119E+00 MeV Emin = 9.99463E-02 MeV frac = 1.00000E+00 Product nuclide = 63156.82c : (n,alpha) + + 8 additional transport branches: + + 1 MT = 22 Q = -1.32906E-01 MeV Emin = 3.37581E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -6.13864E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.17706E+01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 33 Q = -1.19506E+01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,nt) + 5 MT = 103 Q = -1.91535E-01 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 104 Q = -3.82852E+00 MeV Emin = 5.62092E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 7 MT = 105 Q = -5.58546E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 8 MT = 107 Q = 6.20119E+00 MeV Emin = 9.99463E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 5.62092E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 7.00000E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 9.99463E-02 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 9.41508E-04 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 5.41840E-02 MeV : total inelastic scattering + + Nuclide 237 / 1657 : 65160.82c -- terbium 160 (Tb-160) + + Pointers : 1915255 34369 + Primary type : Transport + Nuclide ZAI : 651600 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Tb160.ACE + Atomic weight (AW) : 159.92686 + Atomic weight ratio (AWR) : 158.55300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 6.25E+06 seconds (72.3 days) + Specific ingestion toxicity : 1.60E-09 Sv/Bq + Specific inhalation toxicity : 7.00E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 3 reaction channels + - 2 special reactions + - 1 transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 91 Q = -9.93740E-02 MeV Emin = 9.68750E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 3 MT = 102 Q = 7.85000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 651610 : (n,gamma) + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 9.68750E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.83510E+00 MeV frac = 1.00000E+00 Product nuclide = 66160.82c : beta- + + Nuclide 238 / 1657 : 66160.82c -- dysprosium 160 (Dy-160) + + Pointers : 1930622 23007 + Primary type : Transport + Nuclide ZAI : 661600 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Dy160.ACE + Atomic weight (AW) : 159.92484 + Atomic weight ratio (AWR) : 158.55100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 17 reaction channels + - 2 special reactions + - 1 transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 17 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 51 Q = -8.68000E-02 MeV Emin = 7.80103E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 3 MT = 52 Q = -2.84000E-01 MeV Emin = 2.64342E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 4 MT = 53 Q = -6.95620E-01 MeV Emin = 6.17500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 5 MT = 54 Q = -9.66000E-01 MeV Emin = 8.36049E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 6 MT = 55 Q = -1.05000E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 7 MT = 56 Q = -1.16000E+00 MeV Emin = 1.11196E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 8 MT = 57 Q = -1.26000E+00 MeV Emin = 1.21761E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 9 MT = 58 Q = -1.29000E+00 MeV Emin = 1.28302E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 10 MT = 59 Q = -1.29001E+00 MeV Emin = 1.28302E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 11 MT = 60 Q = -1.36000E+00 MeV Emin = 1.33337E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 12 MT = 61 Q = -1.39000E+00 MeV Emin = 1.38370E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 13 MT = 62 Q = -1.40000E+00 MeV Emin = 1.40380E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 14 MT = 63 Q = -1.59000E+00 MeV Emin = 1.52500E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 15 MT = 64 Q = -1.49060E+01 MeV Emin = 1.75000E+01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 16 MT = 91 Q = -1.59000E+00 MeV Emin = 1.52500E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 17 MT = 102 Q = 6.45110E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 66161.82c : (n,gamma) + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 7.80103E-02 MeV : total inelastic scattering + + Nuclide 239 / 1657 : 66161.82c -- dysprosium 161 (Dy-161) + + Pointers : 1932120 23053 + Primary type : Transport + Nuclide ZAI : 661610 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Dy161.ACE + Atomic weight (AW) : 160.92644 + Atomic weight ratio (AWR) : 159.54400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 30 reaction channels + - 38 special reactions + - 9 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 30 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.45400E+00 MeV Emin = 6.49445E+00 MeV frac = 1.00000E+00 Product nuclide = 66160.82c : (n,2n) + 3 MT = 17 Q = -1.50300E+01 MeV Emin = 1.51242E+01 MeV frac = 1.00000E+00 Product nuclide = 661590 : (n,3n) + 4 MT = 22 Q = 3.44000E-01 MeV Emin = 6.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 64157.82c : (n,nalpha) + 5 MT = 24 Q = -6.01600E+00 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 64156.82c : (n,2nalpha) + 6 MT = 28 Q = -7.50800E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 65160.82c : (n,np) + 7 MT = 41 Q = -1.38830E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 65159.82c : (n,2np) + 8 MT = 51 Q = -2.56500E-02 MeV Emin = 2.25000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -4.38200E-02 MeV Emin = 4.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -7.45700E-02 MeV Emin = 7.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -1.00400E-01 MeV Emin = 1.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -1.03060E-01 MeV Emin = 1.02368E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -1.31760E-01 MeV Emin = 1.20000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -1.84230E-01 MeV Emin = 1.67692E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -2.01090E-01 MeV Emin = 2.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -2.12950E-01 MeV Emin = 2.08318E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -2.67440E-01 MeV Emin = 2.41701E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -3.14940E-01 MeV Emin = 3.11943E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 62 Q = -3.20690E-01 MeV Emin = 3.19807E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 20 MT = 63 Q = -3.66970E-01 MeV Emin = 3.50166E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 21 MT = 64 Q = -4.06990E-01 MeV Emin = 4.04770E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 22 MT = 65 Q = -4.18240E-01 MeV Emin = 4.16595E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 23 MT = 66 Q = -4.43400E-01 MeV Emin = 4.33520E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 24 MT = 67 Q = -4.51430E-01 MeV Emin = 4.51814E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 25 MT = 68 Q = -4.57230E-01 MeV Emin = 4.57178E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 26 MT = 69 Q = -4.85560E-01 MeV Emin = 4.74349E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 27 MT = 91 Q = -2.95150E-01 MeV Emin = 2.92955E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 28 MT = 102 Q = 8.19700E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 66162.82c : (n,gamma) + 29 MT = 103 Q = 0.00000E+00 MeV Emin = 1.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 651610 : (n,p) + 30 MT = 107 Q = 0.00000E+00 MeV Emin = 1.75000E-02 MeV frac = 1.00000E+00 Product nuclide = 64158.82c : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = 3.44000E-01 MeV Emin = 6.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 24 Q = -6.01600E+00 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,2nalpha) + 3 MT = 28 Q = -7.50800E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 4 MT = 41 Q = -1.38830E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,2np) + 5 MT = 103 Q = 0.00000E+00 MeV Emin = 1.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 107 Q = 0.00000E+00 MeV Emin = 1.75000E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 38 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.60000E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 1.75000E-02 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 9.74491E-04 MeV : damage-energy production + 4 MT = 600 Q = 1.89000E-01 MeV Emin = 1.60000E+00 MeV : (n,p) to ground state + 5 MT = 601 Q = 1.32710E-01 MeV Emin = 1.60000E+00 MeV : (n,p1) + 6 MT = 602 Q = 5.53200E-02 MeV Emin = 1.70000E+00 MeV : (n,p2) + 7 MT = 603 Q = -4.17200E-02 MeV Emin = 1.80000E+00 MeV : (n,p3) + 8 MT = 604 Q = -1.25910E-01 MeV Emin = 1.90000E+00 MeV : (n,p4) + 9 MT = 605 Q = -2.05370E-01 MeV Emin = 2.00000E+00 MeV : (n,p5) + 10 MT = 606 Q = -2.28230E-01 MeV Emin = 2.00000E+00 MeV : (n,p6) + 11 MT = 607 Q = -2.91130E-01 MeV Emin = 2.00000E+00 MeV : (n,p7) + 12 MT = 608 Q = -2.99790E-01 MeV Emin = 2.00000E+00 MeV : (n,p8) + 13 MT = 609 Q = -3.10000E-01 MeV Emin = 2.00000E+00 MeV : (n,p9) + 14 MT = 610 Q = -3.29000E-01 MeV Emin = 2.00000E+00 MeV : (n,p10) + 15 MT = 611 Q = -3.69000E-01 MeV Emin = 2.00000E+00 MeV : (n,p11) + 16 MT = 612 Q = -3.95000E-01 MeV Emin = 2.00000E+00 MeV : (n,p12) + 17 MT = 613 Q = -3.96770E-01 MeV Emin = 2.00000E+00 MeV : (n,p13) + 18 MT = 614 Q = -4.14000E-01 MeV Emin = 2.00000E+00 MeV : (n,p14) + 19 MT = 615 Q = -4.49000E-01 MeV Emin = 2.00000E+00 MeV : (n,p15) + 20 MT = 616 Q = -5.09000E-01 MeV Emin = 2.00000E+00 MeV : (n,p16) + 21 MT = 649 Q = -5.09000E-01 MeV Emin = 2.00000E+00 MeV : (n,p) to continuum + 22 MT = 800 Q = 8.28100E+00 MeV Emin = 1.75000E-02 MeV : (n,alpha) to ground state + 23 MT = 801 Q = 8.20149E+00 MeV Emin = 1.75000E-02 MeV : (n,a1) + 24 MT = 802 Q = 8.01956E+00 MeV Emin = 1.75000E-02 MeV : (n,a2) + 25 MT = 803 Q = 7.74202E+00 MeV Emin = 1.75000E-02 MeV : (n,a3) + 26 MT = 804 Q = 7.37660E+00 MeV Emin = 4.00000E-02 MeV : (n,a4) + 27 MT = 805 Q = 7.30391E+00 MeV Emin = 1.75000E-02 MeV : (n,a5) + 28 MT = 806 Q = 7.25735E+00 MeV Emin = 1.75000E-02 MeV : (n,a6) + 29 MT = 807 Q = 7.23941E+00 MeV Emin = 1.75000E-02 MeV : (n,a7) + 30 MT = 808 Q = 7.12208E+00 MeV Emin = 1.75000E-02 MeV : (n,a8) + 31 MT = 809 Q = 7.10457E+00 MeV Emin = 1.75000E-02 MeV : (n,a9) + 32 MT = 810 Q = 7.09390E+00 MeV Emin = 1.75000E-02 MeV : (n,a10) + 33 MT = 811 Q = 7.08490E+00 MeV Emin = 1.75000E-02 MeV : (n,a11) + 34 MT = 812 Q = 7.02119E+00 MeV Emin = 1.75000E-02 MeV : (n,a12) + 35 MT = 813 Q = 7.01754E+00 MeV Emin = 1.75000E-02 MeV : (n,a13) + 36 MT = 814 Q = 7.01552E+00 MeV Emin = 1.75000E-02 MeV : (n,a14) + 37 MT = 849 Q = 7.01552E+00 MeV Emin = 1.75000E-02 MeV : (n,alpha) to continuum + 38 MT = 4 Q = 0.00000E+00 MeV Emin = 2.25000E-02 MeV : total inelastic scattering + + Nuclide 240 / 1657 : 66162.82c -- dysprosium 162 (Dy-162) + + Pointers : 1937633 23099 + Primary type : Transport + Nuclide ZAI : 661620 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Dy162.ACE + Atomic weight (AW) : 161.92704 + Atomic weight ratio (AWR) : 160.53600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 43 reaction channels + - 23 special reactions + - 9 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 43 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.19600E+00 MeV Emin = 8.24705E+00 MeV frac = 1.00000E+00 Product nuclide = 66161.82c : (n,2n) + 3 MT = 17 Q = -1.46500E+01 MeV Emin = 1.47413E+01 MeV frac = 1.00000E+00 Product nuclide = 66160.82c : (n,3n) + 4 MT = 22 Q = 8.50000E-02 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 64158.82c : (n,nalpha) + 5 MT = 24 Q = -7.85200E+00 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 64157.82c : (n,2nalpha) + 6 MT = 28 Q = -8.00700E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 651610 : (n,np) + 7 MT = 41 Q = -1.57040E+01 MeV Emin = 1.70000E+01 MeV frac = 1.00000E+00 Product nuclide = 65160.82c : (n,2np) + 8 MT = 51 Q = -8.06600E-02 MeV Emin = 7.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -2.65660E-01 MeV Emin = 2.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -5.48530E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -8.88190E-01 MeV Emin = 8.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -9.20990E-01 MeV Emin = 9.13363E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -9.62970E-01 MeV Emin = 9.47848E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -1.06102E+00 MeV Emin = 1.05000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -1.14826E+00 MeV Emin = 1.12770E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -1.18279E+00 MeV Emin = 1.17279E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -1.21012E+00 MeV Emin = 1.20000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -1.27610E+00 MeV Emin = 1.27941E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 62 Q = -1.29704E+00 MeV Emin = 1.30000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 20 MT = 63 Q = -1.32443E+00 MeV Emin = 1.31890E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 21 MT = 64 Q = -1.35777E+00 MeV Emin = 1.34946E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 22 MT = 65 Q = -1.37491E+00 MeV Emin = 1.37485E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 23 MT = 66 Q = -1.39069E+00 MeV Emin = 1.39141E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 24 MT = 67 Q = -1.40014E+00 MeV Emin = 1.40443E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 25 MT = 68 Q = -1.40833E+00 MeV Emin = 1.41298E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 26 MT = 69 Q = -1.45344E+00 MeV Emin = 1.43980E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 27 MT = 70 Q = -1.48571E+00 MeV Emin = 1.47873E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 28 MT = 71 Q = -1.49027E+00 MeV Emin = 1.49726E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 29 MT = 72 Q = -1.51880E+00 MeV Emin = 1.51413E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 30 MT = 73 Q = -1.53017E+00 MeV Emin = 1.53398E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 31 MT = 74 Q = -1.53586E+00 MeV Emin = 1.54257E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 32 MT = 75 Q = -1.57120E+00 MeV Emin = 1.56321E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 33 MT = 76 Q = -1.57410E+00 MeV Emin = 1.58245E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 34 MT = 77 Q = -1.57611E+00 MeV Emin = 1.58492E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 27. excited state + 35 MT = 78 Q = -1.63461E+00 MeV Emin = 1.62240E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 28. excited state + 36 MT = 79 Q = -1.63710E+00 MeV Emin = 1.64605E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 29. excited state + 37 MT = 80 Q = -1.63774E+00 MeV Emin = 1.64763E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 30. excited state + 38 MT = 81 Q = -1.63841E+00 MeV Emin = 1.64796E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 31. excited state + 39 MT = 82 Q = -1.66492E+00 MeV Emin = 1.66196E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 32. excited state + 40 MT = 91 Q = -3.93549E-01 MeV Emin = 3.48000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 41 MT = 102 Q = 6.27101E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 66163.82c : (n,gamma) + 42 MT = 103 Q = 0.00000E+00 MeV Emin = 3.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 651620 : (n,p) + 43 MT = 107 Q = 0.00000E+00 MeV Emin = 7.50000E-01 MeV frac = 1.00000E+00 Product nuclide = 641590 : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = 8.50000E-02 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 24 Q = -7.85200E+00 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,2nalpha) + 3 MT = 28 Q = -8.00700E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 4 MT = 41 Q = -1.57040E+01 MeV Emin = 1.70000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,2np) + 5 MT = 103 Q = 0.00000E+00 MeV Emin = 3.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 107 Q = 0.00000E+00 MeV Emin = 7.50000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 23 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.50000E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 7.50000E-01 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 9.73504E-04 MeV : damage-energy production + 4 MT = 600 Q = -1.72400E+00 MeV Emin = 3.50000E+00 MeV : (n,p) to ground state + 5 MT = 601 Q = -1.76310E+00 MeV Emin = 3.50000E+00 MeV : (n,p1) + 6 MT = 602 Q = -1.82100E+00 MeV Emin = 3.50000E+00 MeV : (n,p2) + 7 MT = 603 Q = -1.90000E+00 MeV Emin = 3.50000E+00 MeV : (n,p3) + 8 MT = 604 Q = -1.94000E+00 MeV Emin = 3.50000E+00 MeV : (n,p4) + 9 MT = 605 Q = -1.99100E+00 MeV Emin = 3.50000E+00 MeV : (n,p5) + 10 MT = 606 Q = -2.03400E+00 MeV Emin = 3.50000E+00 MeV : (n,p6) + 11 MT = 649 Q = -2.03400E+00 MeV Emin = 3.50000E+00 MeV : (n,p) to continuum + 12 MT = 800 Q = 6.02800E+00 MeV Emin = 7.50000E-01 MeV : (n,alpha) to ground state + 13 MT = 801 Q = 5.97734E+00 MeV Emin = 7.50000E-01 MeV : (n,a1) + 14 MT = 802 Q = 5.96021E+00 MeV Emin = 7.50000E-01 MeV : (n,a2) + 15 MT = 803 Q = 5.90908E+00 MeV Emin = 8.96861E-01 MeV : (n,a3) + 16 MT = 804 Q = 5.90607E+00 MeV Emin = 8.96861E-01 MeV : (n,a4) + 17 MT = 805 Q = 5.88161E+00 MeV Emin = 9.84484E-01 MeV : (n,a5) + 18 MT = 806 Q = 5.84260E+00 MeV Emin = 9.84484E-01 MeV : (n,a6) + 19 MT = 807 Q = 5.81570E+00 MeV Emin = 1.00000E+00 MeV : (n,a7) + 20 MT = 808 Q = 5.80051E+00 MeV Emin = 9.84484E-01 MeV : (n,a8) + 21 MT = 809 Q = 5.75500E+00 MeV Emin = 1.00000E+00 MeV : (n,a9) + 22 MT = 849 Q = 5.75500E+00 MeV Emin = 1.08750E+00 MeV : (n,alpha) to continuum + 23 MT = 4 Q = 0.00000E+00 MeV Emin = 7.00000E-02 MeV : total inelastic scattering + + Nuclide 241 / 1657 : 66163.82c -- dysprosium 163 (Dy-163) + + Pointers : 1943000 23145 + Primary type : Transport + Nuclide ZAI : 661630 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Dy163.ACE + Atomic weight (AW) : 162.92864 + Atomic weight ratio (AWR) : 161.52900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 37 reaction channels + - 30 special reactions + - 9 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 37 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.27100E+00 MeV Emin = 6.30982E+00 MeV frac = 1.00000E+00 Product nuclide = 66162.82c : (n,2n) + 3 MT = 17 Q = -1.44670E+01 MeV Emin = 1.45566E+01 MeV frac = 1.00000E+00 Product nuclide = 66161.82c : (n,3n) + 4 MT = 22 Q = -2.43000E-01 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 641590 : (n,nalpha) + 5 MT = 24 Q = -6.18600E+00 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 64158.82c : (n,2nalpha) + 6 MT = 28 Q = -7.99500E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 651620 : (n,np) + 7 MT = 41 Q = -1.42780E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 651610 : (n,2np) + 8 MT = 51 Q = -7.34400E-02 MeV Emin = 6.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -1.67340E-01 MeV Emin = 1.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -2.50880E-01 MeV Emin = 2.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -2.81560E-01 MeV Emin = 2.67868E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -2.85580E-01 MeV Emin = 2.85326E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -3.36540E-01 MeV Emin = 3.19312E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -3.51140E-01 MeV Emin = 3.52006E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -3.89740E-01 MeV Emin = 3.78771E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -4.12390E-01 MeV Emin = 4.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -4.15240E-01 MeV Emin = 4.16377E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -4.21830E-01 MeV Emin = 4.21126E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 62 Q = -4.27670E-01 MeV Emin = 4.27380E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 20 MT = 63 Q = -4.50000E-01 MeV Emin = 4.41552E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 21 MT = 64 Q = -4.62580E-01 MeV Emin = 4.59115E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 22 MT = 65 Q = -4.75380E-01 MeV Emin = 4.71884E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 23 MT = 66 Q = -4.97000E-01 MeV Emin = 4.89162E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 24 MT = 67 Q = -5.14540E-01 MeV Emin = 5.08901E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 25 MT = 68 Q = -5.14600E-01 MeV Emin = 5.08901E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 26 MT = 69 Q = -5.53010E-01 MeV Emin = 5.37110E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 27 MT = 70 Q = -5.68710E-01 MeV Emin = 5.64333E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 28 MT = 71 Q = -5.73990E-01 MeV Emin = 5.74887E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 29 MT = 72 Q = -5.91000E-01 MeV Emin = 5.86102E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 30 MT = 73 Q = -6.12000E-01 MeV Emin = 6.07895E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 31 MT = 74 Q = -6.17300E-01 MeV Emin = 6.18455E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 32 MT = 75 Q = -6.45000E-01 MeV Emin = 6.35058E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 33 MT = 76 Q = -6.51000E-01 MeV Emin = 6.52012E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 34 MT = 91 Q = -2.95173E-01 MeV Emin = 2.92174E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 35 MT = 102 Q = 7.65812E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 66164.82c : (n,gamma) + 36 MT = 103 Q = 0.00000E+00 MeV Emin = 2.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 651630 : (n,p) + 37 MT = 107 Q = 0.00000E+00 MeV Emin = 1.70000E-02 MeV frac = 1.00000E+00 Product nuclide = 64160.82c : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = -2.43000E-01 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 24 Q = -6.18600E+00 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,2nalpha) + 3 MT = 28 Q = -7.99500E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 4 MT = 41 Q = -1.42780E+01 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,2np) + 5 MT = 103 Q = 0.00000E+00 MeV Emin = 2.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 107 Q = 0.00000E+00 MeV Emin = 1.70000E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 30 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.50000E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 1.70000E-02 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 9.74487E-04 MeV : damage-energy production + 4 MT = 600 Q = -1.00300E+00 MeV Emin = 2.50000E+00 MeV : (n,p) to ground state + 5 MT = 601 Q = -1.06000E+00 MeV Emin = 2.50000E+00 MeV : (n,p1) + 6 MT = 602 Q = -1.12500E+00 MeV Emin = 2.50000E+00 MeV : (n,p2) + 7 MT = 603 Q = -1.23800E+00 MeV Emin = 3.00000E+00 MeV : (n,p3) + 8 MT = 604 Q = -1.34600E+00 MeV Emin = 3.00000E+00 MeV : (n,p4) + 9 MT = 605 Q = -1.39940E+00 MeV Emin = 3.00000E+00 MeV : (n,p5) + 10 MT = 606 Q = -1.44000E+00 MeV Emin = 3.00000E+00 MeV : (n,p6) + 11 MT = 607 Q = -1.46800E+00 MeV Emin = 3.00000E+00 MeV : (n,p7) + 12 MT = 608 Q = -1.54000E+00 MeV Emin = 3.00000E+00 MeV : (n,p8) + 13 MT = 609 Q = -1.57810E+00 MeV Emin = 3.00000E+00 MeV : (n,p9) + 14 MT = 610 Q = -1.67700E+00 MeV Emin = 3.00000E+00 MeV : (n,p10) + 15 MT = 611 Q = -1.67700E+00 MeV Emin = 3.00000E+00 MeV : (n,p11) + 16 MT = 612 Q = -1.71200E+00 MeV Emin = 3.50000E+00 MeV : (n,p12) + 17 MT = 649 Q = -1.71200E+00 MeV Emin = 3.50000E+00 MeV : (n,p) to continuum + 18 MT = 800 Q = 7.20800E+00 MeV Emin = 1.70000E-02 MeV : (n,alpha) to ground state + 19 MT = 801 Q = 7.13274E+00 MeV Emin = 1.70000E-02 MeV : (n,a1) + 20 MT = 802 Q = 6.95948E+00 MeV Emin = 1.70000E-02 MeV : (n,a2) + 21 MT = 803 Q = 6.69325E+00 MeV Emin = 1.20000E-01 MeV : (n,a3) + 22 MT = 804 Q = 6.34010E+00 MeV Emin = 4.00000E-01 MeV : (n,a4) + 23 MT = 805 Q = 6.29500E+00 MeV Emin = 4.89162E-01 MeV : (n,a5) + 24 MT = 806 Q = 6.26200E+00 MeV Emin = 5.97329E-01 MeV : (n,a6) + 25 MT = 807 Q = 6.21960E+00 MeV Emin = 5.97329E-01 MeV : (n,a7) + 26 MT = 808 Q = 6.19200E+00 MeV Emin = 6.00000E-01 MeV : (n,a8) + 27 MT = 809 Q = 6.15046E+00 MeV Emin = 6.00000E-01 MeV : (n,a9) + 28 MT = 810 Q = 6.13758E+00 MeV Emin = 6.99989E-01 MeV : (n,a10) + 29 MT = 849 Q = 6.13758E+00 MeV Emin = 1.70000E-02 MeV : (n,alpha) to continuum + 30 MT = 4 Q = 0.00000E+00 MeV Emin = 6.00000E-02 MeV : total inelastic scattering + + Nuclide 242 / 1657 : 66164.82c -- dysprosium 164 (Dy-164) + + Pointers : 1948440 23191 + Primary type : Transport + Nuclide ZAI : 661640 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Dy164.ACE + Atomic weight (AW) : 163.92823 + Atomic weight ratio (AWR) : 162.52000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 19 reaction channels + - 4 special reactions + - 5 transmutation reactions + - 3 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 19 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.64000E+00 MeV Emin = 7.68701E+00 MeV frac = 1.00000E+00 Product nuclide = 66163.82c : (n,2n) + 3 MT = 17 Q = -1.38950E+01 MeV Emin = 1.39805E+01 MeV frac = 1.00000E+00 Product nuclide = 66162.82c : (n,3n) + 4 MT = 51 Q = -7.33900E-02 MeV Emin = 7.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 5 MT = 52 Q = -2.42200E-01 MeV Emin = 2.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 6 MT = 53 Q = -5.01300E-01 MeV Emin = 7.83250E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 7 MT = 54 Q = -7.61800E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 8 MT = 55 Q = -8.28200E-01 MeV Emin = 8.31250E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 9 MT = 56 Q = -8.39000E-01 MeV Emin = 8.43750E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 10 MT = 57 Q = -9.16000E-01 MeV Emin = 9.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 11 MT = 58 Q = -9.76900E-01 MeV Emin = 9.52268E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 12 MT = 59 Q = -1.02500E+00 MeV Emin = 1.03100E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 13 MT = 60 Q = -1.03900E+00 MeV Emin = 1.04500E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 14 MT = 61 Q = -1.12300E+00 MeV Emin = 1.10000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 15 MT = 62 Q = -1.15700E+00 MeV Emin = 1.16393E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 16 MT = 91 Q = -1.98800E+00 MeV Emin = 2.00023E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 17 MT = 102 Q = 5.63440E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 661650 : (n,gamma) + 18 MT = 103 Q = -2.98200E+00 MeV Emin = 3.00035E+00 MeV frac = 1.00000E+00 Product nuclide = 651640 : (n,p) + 19 MT = 107 Q = 5.19000E+00 MeV Emin = 1.40000E+00 MeV frac = 1.00000E+00 Product nuclide = 641610 : (n,alpha) + + 3 additional transport branches: + + 1 MT = 102 Q = 5.63440E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 661651 : (n,gamma) + 2 MT = 103 Q = -2.98200E+00 MeV Emin = 3.00035E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 107 Q = 5.19000E+00 MeV Emin = 1.40000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 4 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.00035E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 1.40000E+00 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 4 MT = 4 Q = 0.00000E+00 MeV Emin = 7.00000E-02 MeV : total inelastic scattering + + Nuclide 243 / 1657 : 67165.82c -- holmium 165 (Ho-165) + + Pointers : 1965977 26181 + Primary type : Transport + Nuclide ZAI : 671650 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ho165.ACE + Atomic weight (AW) : 164.92983 + Atomic weight ratio (AWR) : 163.51300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 3.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 19 reaction channels + - 2 special reactions + - 3 transmutation reactions + - 1 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 19 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.03040E+00 MeV Emin = 8.07951E+00 MeV frac = 1.00000E+00 Product nuclide = 671640 : (n,2n) + 3 MT = 17 Q = -1.46600E+01 MeV Emin = 1.47500E+01 MeV frac = 1.00000E+00 Product nuclide = 671630 : (n,3n) + 4 MT = 37 Q = -2.30630E+01 MeV Emin = 2.32041E+01 MeV frac = 1.00000E+00 Product nuclide = cut: Ho-162 : (n,4n) + 5 MT = 51 Q = -9.47000E-02 MeV Emin = 8.76395E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -2.09800E-01 MeV Emin = 2.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -3.45000E-01 MeV Emin = 3.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -3.61700E-01 MeV Emin = 3.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -4.19500E-01 MeV Emin = 4.21875E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -4.29400E-01 MeV Emin = 4.31250E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -4.49200E-01 MeV Emin = 4.51562E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -4.91000E-01 MeV Emin = 4.75000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -4.99200E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -5.15500E-01 MeV Emin = 5.10452E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -5.39000E-01 MeV Emin = 5.30476E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -5.66800E-01 MeV Emin = 5.68750E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 63 Q = -5.89800E-01 MeV Emin = 5.92969E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 18 MT = 91 Q = -5.89800E-01 MeV Emin = 5.92969E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 19 MT = 102 Q = 6.24240E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 671660 : (n,gamma) + + 1 additional transport branch: + + 1 MT = 102 Q = 6.24240E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 671661 : (n,gamma) + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 8.76395E-02 MeV : total inelastic scattering + + Nuclide 244 / 1657 : 68164.82c -- erbium 164 (Er-164) + + Pointers : 1984341 23283 + Primary type : Transport + Nuclide ZAI : 681640 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Er164.ACE + Atomic weight (AW) : 163.92924 + Atomic weight ratio (AWR) : 162.52100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 27 reaction channels + - 6 special reactions + - 9 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 27 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.84637E+00 MeV Emin = 8.90080E+00 MeV frac = 1.00000E+00 Product nuclide = 681630 : (n,2n) + 3 MT = 17 Q = -1.57477E+01 MeV Emin = 1.58446E+01 MeV frac = 1.00000E+00 Product nuclide = 681620 : (n,3n) + 4 MT = 22 Q = 1.30691E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 66160.82c : (n,nalpha) + 5 MT = 28 Q = -6.85403E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 671630 : (n,np) + 6 MT = 51 Q = -9.13900E-02 MeV Emin = 9.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -2.99470E-01 MeV Emin = 3.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -6.14400E-01 MeV Emin = 6.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -8.60310E-01 MeV Emin = 8.32802E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -9.46350E-01 MeV Emin = 9.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -1.02460E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -1.05830E+00 MeV Emin = 1.04786E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -1.19750E+00 MeV Emin = 1.20000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -1.24600E+00 MeV Emin = 1.24539E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -1.31460E+00 MeV Emin = 1.28591E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -1.35860E+00 MeV Emin = 1.34670E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -1.38680E+00 MeV Emin = 1.38115E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -1.41660E+00 MeV Emin = 1.42141E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -1.43400E+00 MeV Emin = 1.43212E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -1.46990E+00 MeV Emin = 1.46088E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 21 MT = 66 Q = -1.48390E+00 MeV Emin = 1.48599E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 22 MT = 91 Q = -1.50000E+00 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 23 MT = 102 Q = 6.64970E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 681650 : (n,gamma) + 24 MT = 103 Q = -2.30661E-01 MeV Emin = 1.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 671640 : (n,p) + 25 MT = 104 Q = -4.62946E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 671630 : (n,d) + 26 MT = 105 Q = -6.77872E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 671620 : (n,t) + 27 MT = 107 Q = 7.76028E+00 MeV Emin = 1.50000E-01 MeV frac = 1.00000E+00 Product nuclide = 66161.82c : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = 1.30691E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -6.85403E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -2.30661E-01 MeV Emin = 1.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -4.62946E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 105 Q = -6.77872E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 6 MT = 107 Q = 7.76028E+00 MeV Emin = 1.50000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.60000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 8.00000E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 1.50000E-01 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 9.00000E-02 MeV : total inelastic scattering + + Nuclide 245 / 1657 : 68166.82c -- erbium 166 (Er-166) + + Pointers : 1987600 23329 + Primary type : Transport + Nuclide ZAI : 681660 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Er166.ACE + Atomic weight (AW) : 165.93043 + Atomic weight ratio (AWR) : 164.50500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 36 reaction channels + - 6 special reactions + - 10 transmutation reactions + - 8 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 36 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.47537E+00 MeV Emin = 8.52689E+00 MeV frac = 1.00000E+00 Product nuclide = 681650 : (n,2n) + 3 MT = 17 Q = -1.51257E+01 MeV Emin = 1.52177E+01 MeV frac = 1.00000E+00 Product nuclide = 68164.82c : (n,3n) + 4 MT = 22 Q = 8.30908E-01 MeV Emin = 5.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 66162.82c : (n,nalpha) + 5 MT = 28 Q = -7.31603E+00 MeV Emin = 8.75000E+00 MeV frac = 1.00000E+00 Product nuclide = 67165.82c : (n,np) + 6 MT = 32 Q = -1.31318E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 671640 : (n,nd) + 7 MT = 51 Q = -8.05800E-02 MeV Emin = 8.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 8 MT = 52 Q = -2.65000E-01 MeV Emin = 2.60000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 9 MT = 53 Q = -5.45500E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 10 MT = 54 Q = -7.85900E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 11 MT = 55 Q = -8.59400E-01 MeV Emin = 8.32312E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 12 MT = 56 Q = -9.11200E-01 MeV Emin = 9.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 13 MT = 57 Q = -9.56200E-01 MeV Emin = 9.58370E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 14 MT = 58 Q = -1.07530E+00 MeV Emin = 1.07817E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 15 MT = 59 Q = -1.21600E+00 MeV Emin = 1.20000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 16 MT = 60 Q = -1.34960E+00 MeV Emin = 1.30000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 17 MT = 61 Q = -1.37600E+00 MeV Emin = 1.37108E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 18 MT = 62 Q = -1.45820E+00 MeV Emin = 1.43353E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 19 MT = 63 Q = -1.45990E+00 MeV Emin = 1.46792E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 20 MT = 64 Q = -1.51340E+00 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 21 MT = 65 Q = -1.52840E+00 MeV Emin = 1.53015E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 22 MT = 66 Q = -1.55570E+00 MeV Emin = 1.55327E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 23 MT = 67 Q = -1.57220E+00 MeV Emin = 1.56885E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 24 MT = 68 Q = -1.59620E+00 MeV Emin = 1.60000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 25 MT = 69 Q = -1.66240E+00 MeV Emin = 1.63921E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 26 MT = 70 Q = -1.66580E+00 MeV Emin = 1.67422E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 27 MT = 71 Q = -1.67880E+00 MeV Emin = 1.68796E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 28 MT = 72 Q = -1.69230E+00 MeV Emin = 1.70000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 29 MT = 73 Q = -1.70310E+00 MeV Emin = 1.70802E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 30 MT = 74 Q = -1.78700E+00 MeV Emin = 1.75566E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 31 MT = 91 Q = -1.80000E+00 MeV Emin = 1.80547E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 32 MT = 102 Q = 6.43670E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 68167.82c : (n,gamma) + 33 MT = 103 Q = -1.07166E+00 MeV Emin = 2.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 671660 : (n,p) + 34 MT = 104 Q = -5.09146E+00 MeV Emin = 6.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 67165.82c : (n,d) + 35 MT = 105 Q = -6.87372E+00 MeV Emin = 8.75000E+00 MeV frac = 1.00000E+00 Product nuclide = 671640 : (n,t) + 36 MT = 107 Q = 7.10228E+00 MeV Emin = 3.75000E-01 MeV frac = 1.00000E+00 Product nuclide = 66163.82c : (n,alpha) + + 8 additional transport branches: + + 1 MT = 22 Q = 8.30908E-01 MeV Emin = 5.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -7.31603E+00 MeV Emin = 8.75000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.31318E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 102 Q = 6.43670E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 681671 : (n,gamma) + 5 MT = 103 Q = -1.07166E+00 MeV Emin = 2.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 6 MT = 104 Q = -5.09146E+00 MeV Emin = 6.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 7 MT = 105 Q = -6.87372E+00 MeV Emin = 8.75000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 8 MT = 107 Q = 7.10228E+00 MeV Emin = 3.75000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.50000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.50000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 8.75000E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 3.75000E-01 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 8.00000E-02 MeV : total inelastic scattering + + Nuclide 246 / 1657 : 68167.82c -- erbium 167 (Er-167) + + Pointers : 1991380 23375 + Primary type : Transport + Nuclide ZAI : 681670 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Er167.ACE + Atomic weight (AW) : 166.93204 + Atomic weight ratio (AWR) : 165.49800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 35 reaction channels + - 6 special reactions + - 10 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 35 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.43537E+00 MeV Emin = 6.47426E+00 MeV frac = 1.00000E+00 Product nuclide = 68166.82c : (n,2n) + 3 MT = 17 Q = -1.49107E+01 MeV Emin = 1.50008E+01 MeV frac = 1.00000E+00 Product nuclide = 681650 : (n,3n) + 4 MT = 22 Q = 6.66908E-01 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 66163.82c : (n,nalpha) + 5 MT = 28 Q = -7.50703E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 671660 : (n,np) + 6 MT = 32 Q = -1.15268E+01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 67165.82c : (n,nd) + 7 MT = 51 Q = -7.93200E-02 MeV Emin = 7.50000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 8 MT = 52 Q = -1.78000E-01 MeV Emin = 1.70000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 9 MT = 53 Q = -2.07800E-01 MeV Emin = 2.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 10 MT = 54 Q = -2.64900E-01 MeV Emin = 2.60000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 11 MT = 55 Q = -2.81600E-01 MeV Emin = 2.80000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 12 MT = 56 Q = -2.94900E-01 MeV Emin = 2.90000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 13 MT = 57 Q = -3.46600E-01 MeV Emin = 3.36847E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 14 MT = 58 Q = -4.13300E-01 MeV Emin = 4.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 15 MT = 59 Q = -4.30000E-01 MeV Emin = 4.24198E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 16 MT = 60 Q = -4.34400E-01 MeV Emin = 4.34774E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 17 MT = 61 Q = -4.42000E-01 MeV Emin = 4.41299E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 18 MT = 62 Q = -5.31500E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 19 MT = 63 Q = -5.35800E-01 MeV Emin = 5.36874E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 20 MT = 64 Q = -5.73800E-01 MeV Emin = 5.63634E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 21 MT = 65 Q = -5.87400E-01 MeV Emin = 5.84108E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 22 MT = 66 Q = -6.40800E-01 MeV Emin = 6.22336E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 23 MT = 67 Q = -6.45200E-01 MeV Emin = 6.46886E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 24 MT = 68 Q = -6.62400E-01 MeV Emin = 6.58201E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 25 MT = 69 Q = -6.67900E-01 MeV Emin = 6.69169E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 26 MT = 70 Q = -6.83300E-01 MeV Emin = 6.85968E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 27 MT = 71 Q = -7.11000E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 28 MT = 72 Q = -7.11100E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 29 MT = 73 Q = -7.45300E-01 MeV Emin = 7.32600E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 30 MT = 91 Q = -7.50000E-01 MeV Emin = 7.52168E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 31 MT = 102 Q = 7.77070E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 68168.82c : (n,gamma) + 32 MT = 103 Q = -2.24661E-01 MeV Emin = 1.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 671670 : (n,p) + 33 MT = 104 Q = -5.28246E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 671660 : (n,d) + 34 MT = 105 Q = -5.26872E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 67165.82c : (n,t) + 35 MT = 107 Q = 8.32528E+00 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 66164.82c : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = 6.66908E-01 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -7.50703E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.15268E+01 MeV Emin = 1.30000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 103 Q = -2.24661E-01 MeV Emin = 1.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -5.28246E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -5.26872E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 107 Q = 8.32528E+00 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.60000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.00000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 7.00000E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 1.50000E+00 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 7.50000E-02 MeV : total inelastic scattering + + Nuclide 247 / 1657 : 68168.82c -- erbium 168 (Er-168) + + Pointers : 1995394 23421 + Primary type : Transport + Nuclide ZAI : 681680 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Er168.ACE + Atomic weight (AW) : 167.92960 + Atomic weight ratio (AWR) : 166.48700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 41 reaction channels + - 6 special reactions + - 10 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 41 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.77137E+00 MeV Emin = 7.81805E+00 MeV frac = 1.00000E+00 Product nuclide = 68167.82c : (n,2n) + 3 MT = 17 Q = -1.42067E+01 MeV Emin = 1.42920E+01 MeV frac = 1.00000E+00 Product nuclide = 68166.82c : (n,3n) + 4 MT = 22 Q = 5.53908E-01 MeV Emin = 5.25000E+00 MeV frac = 1.00000E+00 Product nuclide = 66164.82c : (n,nalpha) + 5 MT = 28 Q = -7.99603E+00 MeV Emin = 9.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 671670 : (n,np) + 6 MT = 32 Q = -1.30538E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 671660 : (n,nd) + 7 MT = 51 Q = -7.98000E-02 MeV Emin = 8.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 8 MT = 52 Q = -2.64100E-01 MeV Emin = 2.60000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 9 MT = 53 Q = -5.48700E-01 MeV Emin = 5.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 10 MT = 54 Q = -8.21800E-01 MeV Emin = 8.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 11 MT = 55 Q = -8.95800E-01 MeV Emin = 9.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 12 MT = 56 Q = -9.28300E-01 MeV Emin = 9.25886E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 13 MT = 57 Q = -9.94800E-01 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 14 MT = 58 Q = -1.09400E+00 MeV Emin = 1.10000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 15 MT = 59 Q = -1.11760E+00 MeV Emin = 1.11244E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 16 MT = 60 Q = -1.19300E+00 MeV Emin = 1.16216E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 17 MT = 61 Q = -1.21720E+00 MeV Emin = 1.21234E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 18 MT = 62 Q = -1.26390E+00 MeV Emin = 1.24800E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 19 MT = 63 Q = -1.27630E+00 MeV Emin = 1.27862E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 20 MT = 64 Q = -1.31150E+00 MeV Emin = 1.31676E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 21 MT = 65 Q = -1.35890E+00 MeV Emin = 1.35030E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 22 MT = 66 Q = -1.39680E+00 MeV Emin = 1.40000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 23 MT = 67 Q = -1.40370E+00 MeV Emin = 1.40866E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 24 MT = 68 Q = -1.41110E+00 MeV Emin = 1.41676E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 25 MT = 69 Q = -1.42210E+00 MeV Emin = 1.42601E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 26 MT = 70 Q = -1.43150E+00 MeV Emin = 1.43537E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 27 MT = 71 Q = -1.43300E+00 MeV Emin = 1.44085E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 28 MT = 72 Q = -1.44900E+00 MeV Emin = 1.44965E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 29 MT = 73 Q = -1.49310E+00 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 30 MT = 74 Q = -1.54160E+00 MeV Emin = 1.52646E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 31 MT = 75 Q = -1.54170E+00 MeV Emin = 1.52646E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 32 MT = 76 Q = -1.56950E+00 MeV Emin = 1.56726E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 33 MT = 77 Q = -1.57410E+00 MeV Emin = 1.56726E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 27. excited state + 34 MT = 78 Q = -1.60590E+00 MeV Emin = 1.60000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 28. excited state + 35 MT = 79 Q = -1.61530E+00 MeV Emin = 1.60000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 29. excited state + 36 MT = 91 Q = -1.62000E+00 MeV Emin = 1.62737E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 37 MT = 102 Q = 6.00370E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 681690 : (n,gamma) + 38 MT = 103 Q = -1.93666E+00 MeV Emin = 3.25000E+00 MeV frac = 1.00000E+00 Product nuclide = 671680 : (n,p) + 39 MT = 104 Q = -5.77146E+00 MeV Emin = 7.25000E+00 MeV frac = 1.00000E+00 Product nuclide = 671670 : (n,d) + 40 MT = 105 Q = -6.79572E+00 MeV Emin = 8.75000E+00 MeV frac = 1.00000E+00 Product nuclide = 671660 : (n,t) + 41 MT = 107 Q = 6.27028E+00 MeV Emin = 3.75000E-01 MeV frac = 1.00000E+00 Product nuclide = 661650 : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = 5.53908E-01 MeV Emin = 5.25000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -7.99603E+00 MeV Emin = 9.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.30538E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 103 Q = -1.93666E+00 MeV Emin = 3.25000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -5.77146E+00 MeV Emin = 7.25000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -6.79572E+00 MeV Emin = 8.75000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 107 Q = 6.27028E+00 MeV Emin = 3.75000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.25000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.25000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 8.75000E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 3.75000E-01 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 8.00000E-02 MeV : total inelastic scattering + + Nuclide 248 / 1657 : 68170.82c -- erbium 170 (Er-170) + + Pointers : 1999972 23467 + Primary type : Transport + Nuclide ZAI : 681700 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Er170.ACE + Atomic weight (AW) : 169.93584 + Atomic weight ratio (AWR) : 168.47600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 26 reaction channels + - 6 special reactions + - 10 transmutation reactions + - 7 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 26 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.25837E+00 MeV Emin = 7.30145E+00 MeV frac = 1.00000E+00 Product nuclide = 681690 : (n,2n) + 3 MT = 17 Q = -1.32617E+01 MeV Emin = 1.33407E+01 MeV frac = 1.00000E+00 Product nuclide = 68168.82c : (n,3n) + 4 MT = 22 Q = 5.19080E-02 MeV Emin = 5.75000E+00 MeV frac = 1.00000E+00 Product nuclide = 661660 : (n,nalpha) + 5 MT = 28 Q = -8.60103E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 671690 : (n,np) + 6 MT = 32 Q = -1.29738E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 671680 : (n,nd) + 7 MT = 51 Q = -7.86800E-02 MeV Emin = 7.50000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 8 MT = 52 Q = -2.60200E-01 MeV Emin = 2.60000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 9 MT = 53 Q = -5.40800E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 10 MT = 54 Q = -8.91000E-01 MeV Emin = 8.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 11 MT = 55 Q = -9.12300E-01 MeV Emin = 9.08857E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 12 MT = 56 Q = -9.34000E-01 MeV Emin = 9.38286E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 13 MT = 57 Q = -9.59900E-01 MeV Emin = 9.58858E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 14 MT = 58 Q = -1.01040E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 15 MT = 59 Q = -1.10330E+00 MeV Emin = 1.10000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 16 MT = 60 Q = -1.12720E+00 MeV Emin = 1.12542E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 17 MT = 61 Q = -1.21740E+00 MeV Emin = 1.20000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 18 MT = 62 Q = -1.23620E+00 MeV Emin = 1.23696E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 19 MT = 63 Q = -1.26640E+00 MeV Emin = 1.25544E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 20 MT = 64 Q = -1.26860E+00 MeV Emin = 1.27503E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 21 MT = 91 Q = -1.30000E+00 MeV Emin = 1.30000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 22 MT = 102 Q = 5.68170E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 681710 : (n,gamma) + 23 MT = 103 Q = -3.08566E+00 MeV Emin = 4.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 671700 : (n,p) + 24 MT = 104 Q = -6.37645E+00 MeV Emin = 7.75000E+00 MeV frac = 1.00000E+00 Product nuclide = 671690 : (n,d) + 25 MT = 105 Q = -6.71572E+00 MeV Emin = 8.75000E+00 MeV frac = 1.00000E+00 Product nuclide = 671680 : (n,t) + 26 MT = 107 Q = 5.46928E+00 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 661670 : (n,alpha) + + 7 additional transport branches: + + 1 MT = 22 Q = 5.19080E-02 MeV Emin = 5.75000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -8.60103E+00 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 32 Q = -1.29738E+01 MeV Emin = 1.45000E+01 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,nd) + 4 MT = 103 Q = -3.08566E+00 MeV Emin = 4.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -6.37645E+00 MeV Emin = 7.75000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 105 Q = -6.71572E+00 MeV Emin = 8.75000E+00 MeV frac = 1.00000E+00 Product nuclide = 1003.82c : (n,t) + 7 MT = 107 Q = 5.46928E+00 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 6 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.50000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.75000E+00 MeV : total deuteron production + 3 MT = 205 Q = 0.00000E+00 MeV Emin = 8.75000E+00 MeV : total triton production + 4 MT = 207 Q = 0.00000E+00 MeV Emin = 5.00000E-01 MeV : total alpha production + 5 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 6 MT = 4 Q = 0.00000E+00 MeV Emin = 7.50000E-02 MeV : total inelastic scattering + + Nuclide 249 / 1657 : 71175.82c -- lutetium 175 (Lu-175) + + Pointers : 2055486 27515 + Primary type : Transport + Nuclide ZAI : 711750 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Lu175.ACE + Atomic weight (AW) : 174.94083 + Atomic weight ratio (AWR) : 173.43800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 15 reaction channels + - 4 special reactions + - 5 transmutation reactions + - 3 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 15 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.81000E+00 MeV Emin = 7.85503E+00 MeV frac = 1.00000E+00 Product nuclide = 711740 : (n,2n) + 3 MT = 17 Q = -1.44200E+01 MeV Emin = 1.45031E+01 MeV frac = 1.00000E+00 Product nuclide = 711730 : (n,3n) + 4 MT = 51 Q = -1.14000E-01 MeV Emin = 1.10000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 5 MT = 52 Q = -2.52000E-01 MeV Emin = 2.52832E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 6 MT = 53 Q = -3.43000E-01 MeV Emin = 3.22500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 7 MT = 54 Q = -3.45000E-01 MeV Emin = 3.46853E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 8 MT = 55 Q = -3.96000E-01 MeV Emin = 3.85000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 9 MT = 56 Q = -4.32000E-01 MeV Emin = 4.17250E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 10 MT = 57 Q = -5.05000E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 11 MT = 58 Q = -7.50000E-01 MeV Emin = 7.48332E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 12 MT = 91 Q = -1.98900E+00 MeV Emin = 2.00047E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 13 MT = 102 Q = 6.19140E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 71176.82c : (n,gamma) + 14 MT = 103 Q = 3.12500E-01 MeV Emin = 2.77250E-01 MeV frac = 1.00000E+00 Product nuclide = 701750 : (n,p) + 15 MT = 107 Q = 7.80000E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 691720 : (n,alpha) + + 3 additional transport branches: + + 1 MT = 102 Q = 6.19140E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 711761 : (n,gamma) + 2 MT = 103 Q = 3.12500E-01 MeV Emin = 2.77250E-01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 107 Q = 7.80000E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 4 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.77250E-01 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 1.10000E+01 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 4 MT = 4 Q = 0.00000E+00 MeV Emin = 1.10000E-01 MeV : total inelastic scattering + + Nuclide 250 / 1657 : 71176.82c -- lutetium 176 (Lu-176) + + Pointers : 2057222 27561 + Primary type : Transport + Nuclide ZAI : 711760 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Lu176.ACE + Atomic weight (AW) : 175.94143 + Atomic weight ratio (AWR) : 174.43000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.19E+18 seconds (37.6 billion years) + Specific ingestion toxicity : 1.80E-09 Sv/Bq + Specific inhalation toxicity : 7.00E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 15 reaction channels + - 4 special reactions + - 5 transmutation reactions + - 3 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 15 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.34000E+00 MeV Emin = 6.37635E+00 MeV frac = 1.00000E+00 Product nuclide = 71175.82c : (n,2n) + 3 MT = 17 Q = -1.41500E+01 MeV Emin = 1.42311E+01 MeV frac = 1.00000E+00 Product nuclide = 711740 : (n,3n) + 4 MT = 51 Q = -1.27000E-01 MeV Emin = 1.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 5 MT = 52 Q = -1.84000E-01 MeV Emin = 1.75000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 6 MT = 53 Q = -2.43000E-01 MeV Emin = 2.22200E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 7 MT = 54 Q = -2.75000E-01 MeV Emin = 2.63300E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 8 MT = 55 Q = -3.88000E-01 MeV Emin = 3.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 9 MT = 56 Q = -4.45000E-01 MeV Emin = 4.47214E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 10 MT = 57 Q = -5.10000E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 11 MT = 58 Q = -6.21000E-01 MeV Emin = 6.24037E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 12 MT = 91 Q = -1.98900E+00 MeV Emin = 2.00040E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 13 MT = 102 Q = 7.07200E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 711770 : (n,gamma) + 14 MT = 103 Q = 7.62500E-01 MeV Emin = 2.90000E-01 MeV frac = 1.00000E+00 Product nuclide = 701760 : (n,p) + 15 MT = 107 Q = 8.49100E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 691730 : (n,alpha) + + 3 additional transport branches: + + 1 MT = 102 Q = 7.07200E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 711771 : (n,gamma) + 2 MT = 103 Q = 7.62500E-01 MeV Emin = 2.90000E-01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 107 Q = 8.49100E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 4 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.90000E-01 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 1.10000E+01 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 4 MT = 4 Q = 0.00000E+00 MeV Emin = 1.25000E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.19020E+00 MeV frac = 1.00000E+00 Product nuclide = 72176.82c : beta- + + Nuclide 251 / 1657 : 72176.82c -- hafnium 176 (Hf-176) + + Pointers : 2069430 25629 + Primary type : Transport + Nuclide ZAI : 721760 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Hf176.ACE + Atomic weight (AW) : 175.94042 + Atomic weight ratio (AWR) : 174.42900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 30 reaction channels + - 4 special reactions + - 5 transmutation reactions + - 2 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 30 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.08868E+00 MeV Emin = 8.13506E+00 MeV frac = 1.00000E+00 Product nuclide = 721750 : (n,2n) + 3 MT = 17 Q = -1.49424E+01 MeV Emin = 1.50281E+01 MeV frac = 1.00000E+00 Product nuclide = 721740 : (n,3n) + 4 MT = 51 Q = -8.82999E-02 MeV Emin = 8.81777E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 5 MT = 52 Q = -2.90200E-01 MeV Emin = 2.70932E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 6 MT = 53 Q = -5.96999E-01 MeV Emin = 6.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 7 MT = 54 Q = -9.97999E-01 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 8 MT = 55 Q = -1.14990E+00 MeV Emin = 1.14800E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 9 MT = 56 Q = -1.22660E+00 MeV Emin = 1.22002E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 10 MT = 57 Q = -1.24770E+00 MeV Emin = 1.25000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 11 MT = 58 Q = -1.29320E+00 MeV Emin = 1.29824E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 12 MT = 59 Q = -1.31330E+00 MeV Emin = 1.32047E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 13 MT = 60 Q = -1.34130E+00 MeV Emin = 1.34425E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 14 MT = 61 Q = -1.37940E+00 MeV Emin = 1.38203E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 15 MT = 62 Q = -1.40460E+00 MeV Emin = 1.40244E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 16 MT = 63 Q = -1.44580E+00 MeV Emin = 1.45348E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 17 MT = 64 Q = -1.57770E+00 MeV Emin = 1.57538E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 18 MT = 65 Q = -1.64340E+00 MeV Emin = 1.64930E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 19 MT = 66 Q = -1.67230E+00 MeV Emin = 1.67007E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 20 MT = 67 Q = -1.70460E+00 MeV Emin = 1.69813E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 21 MT = 68 Q = -1.71020E+00 MeV Emin = 1.71719E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 22 MT = 69 Q = -1.72210E+00 MeV Emin = 1.72599E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 23 MT = 70 Q = -1.76750E+00 MeV Emin = 1.75000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 24 MT = 71 Q = -1.78610E+00 MeV Emin = 1.78699E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 25 MT = 72 Q = -1.79370E+00 MeV Emin = 1.80016E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 26 MT = 73 Q = -1.81900E+00 MeV Emin = 1.82727E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 27 MT = 91 Q = -1.84000E+00 MeV Emin = 1.83891E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 28 MT = 102 Q = 6.38369E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 72177.82c : (n,gamma) + 29 MT = 103 Q = -4.06529E-01 MeV Emin = 1.32990E+00 MeV frac = 1.00000E+00 Product nuclide = 71176.82c : (n,p) + 30 MT = 107 Q = 8.62274E+00 MeV Emin = 4.75000E-01 MeV frac = 1.00000E+00 Product nuclide = 701730 : (n,alpha) + + 2 additional transport branches: + + 1 MT = 103 Q = -4.06529E-01 MeV Emin = 1.32990E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 107 Q = 8.62274E+00 MeV Emin = 4.75000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 4 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.32990E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 4.75000E-01 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 4 MT = 4 Q = 0.00000E+00 MeV Emin = 8.81777E-02 MeV : total inelastic scattering + + Nuclide 252 / 1657 : 72177.82c -- hafnium 177 (Hf-177) + + Pointers : 2072169 25675 + Primary type : Transport + Nuclide ZAI : 721770 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Hf177.ACE + Atomic weight (AW) : 176.94001 + Atomic weight ratio (AWR) : 175.42000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 23 reaction channels + - 4 special reactions + - 5 transmutation reactions + - 2 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 23 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.38068E+00 MeV Emin = 6.41706E+00 MeV frac = 1.00000E+00 Product nuclide = 72176.82c : (n,2n) + 3 MT = 17 Q = -1.44694E+01 MeV Emin = 1.45519E+01 MeV frac = 1.00000E+00 Product nuclide = 721750 : (n,3n) + 4 MT = 51 Q = -1.13000E-01 MeV Emin = 1.10000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 5 MT = 52 Q = -2.49700E-01 MeV Emin = 2.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 6 MT = 53 Q = -3.21300E-01 MeV Emin = 3.16731E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 7 MT = 54 Q = -4.09499E-01 MeV Emin = 4.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 8 MT = 55 Q = -4.26699E-01 MeV Emin = 4.29021E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 9 MT = 56 Q = -5.08099E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 10 MT = 57 Q = -5.55199E-01 MeV Emin = 5.44474E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 11 MT = 58 Q = -5.91299E-01 MeV Emin = 5.82700E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 12 MT = 59 Q = -6.04399E-01 MeV Emin = 6.07614E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 13 MT = 60 Q = -7.08499E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 14 MT = 61 Q = -7.45899E-01 MeV Emin = 7.33696E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 15 MT = 62 Q = -7.94499E-01 MeV Emin = 7.88337E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 16 MT = 63 Q = -8.05699E-01 MeV Emin = 8.05146E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 17 MT = 64 Q = -8.47399E-01 MeV Emin = 8.43166E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 18 MT = 65 Q = -8.72999E-01 MeV Emin = 8.75105E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 19 MT = 66 Q = -8.82799E-01 MeV Emin = 8.82904E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 20 MT = 91 Q = -9.47999E-01 MeV Emin = 9.40053E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 21 MT = 102 Q = 7.62669E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 72178.82c : (n,gamma) + 22 MT = 103 Q = 2.85470E-01 MeV Emin = 1.92528E+00 MeV frac = 1.00000E+00 Product nuclide = 711770 : (n,p) + 23 MT = 107 Q = 9.71174E+00 MeV Emin = 1.92528E+00 MeV frac = 1.00000E+00 Product nuclide = 701740 : (n,alpha) + + 2 additional transport branches: + + 1 MT = 103 Q = 2.85470E-01 MeV Emin = 1.92528E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 107 Q = 9.71174E+00 MeV Emin = 1.92528E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 4 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.92528E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 1.92528E+00 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 4 MT = 4 Q = 0.00000E+00 MeV Emin = 1.10000E-01 MeV : total inelastic scattering + + Nuclide 253 / 1657 : 72178.82c -- hafnium 178 (Hf-178) + + Pointers : 2076896 25721 + Primary type : Transport + Nuclide ZAI : 721780 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Hf178.ACE + Atomic weight (AW) : 177.93959 + Atomic weight ratio (AWR) : 176.41100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 28 reaction channels + - 4 special reactions + - 5 transmutation reactions + - 2 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 28 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.62568E+00 MeV Emin = 7.66892E+00 MeV frac = 1.00000E+00 Product nuclide = 72177.82c : (n,2n) + 3 MT = 17 Q = -1.40064E+01 MeV Emin = 1.40858E+01 MeV frac = 1.00000E+00 Product nuclide = 72176.82c : (n,3n) + 4 MT = 51 Q = -9.31999E-02 MeV Emin = 9.07623E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 5 MT = 52 Q = -3.06600E-01 MeV Emin = 3.04169E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 6 MT = 53 Q = -6.32199E-01 MeV Emin = 6.34758E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 7 MT = 54 Q = -1.05850E+00 MeV Emin = 1.03678E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 8 MT = 55 Q = -1.14740E+00 MeV Emin = 1.14800E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 9 MT = 56 Q = -1.17460E+00 MeV Emin = 1.15649E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 10 MT = 57 Q = -1.19930E+00 MeV Emin = 1.19368E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 11 MT = 58 Q = -1.26020E+00 MeV Emin = 1.25867E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 12 MT = 59 Q = -1.27660E+00 MeV Emin = 1.27919E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 13 MT = 60 Q = -1.30990E+00 MeV Emin = 1.31629E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 14 MT = 61 Q = -1.32240E+00 MeV Emin = 1.32393E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 15 MT = 62 Q = -1.36240E+00 MeV Emin = 1.35692E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 16 MT = 63 Q = -1.36410E+00 MeV Emin = 1.37098E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 17 MT = 64 Q = -1.43400E+00 MeV Emin = 1.44134E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 18 MT = 65 Q = -1.44380E+00 MeV Emin = 1.45127E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 19 MT = 66 Q = -1.47900E+00 MeV Emin = 1.47906E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 20 MT = 67 Q = -1.49610E+00 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 21 MT = 68 Q = -1.51360E+00 MeV Emin = 1.52050E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 22 MT = 69 Q = -1.56130E+00 MeV Emin = 1.55260E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 23 MT = 70 Q = -1.56650E+00 MeV Emin = 1.57277E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 24 MT = 71 Q = -1.60150E+00 MeV Emin = 1.61020E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 25 MT = 91 Q = -1.64000E+00 MeV Emin = 1.63366E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 26 MT = 102 Q = 6.09969E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 72179.82c : (n,gamma) + 27 MT = 103 Q = -1.46953E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 711780 : (n,p) + 28 MT = 107 Q = 7.90574E+00 MeV Emin = 4.75000E-01 MeV frac = 1.00000E+00 Product nuclide = 701750 : (n,alpha) + + 2 additional transport branches: + + 1 MT = 103 Q = -1.46953E+00 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 107 Q = 7.90574E+00 MeV Emin = 4.75000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 4 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 4.75000E-01 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 4 MT = 4 Q = 0.00000E+00 MeV Emin = 9.07623E-02 MeV : total inelastic scattering + + Nuclide 254 / 1657 : 72179.82c -- hafnium 179 (Hf-179) + + Pointers : 2080112 25767 + Primary type : Transport + Nuclide ZAI : 721790 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Hf179.ACE + Atomic weight (AW) : 178.95028 + Atomic weight ratio (AWR) : 177.41300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 19 reaction channels + - 4 special reactions + - 5 transmutation reactions + - 3 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 19 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.09968E+00 MeV Emin = 6.13407E+00 MeV frac = 1.00000E+00 Product nuclide = 72178.82c : (n,2n) + 3 MT = 17 Q = -1.37254E+01 MeV Emin = 1.38028E+01 MeV frac = 1.00000E+00 Product nuclide = 72177.82c : (n,3n) + 4 MT = 51 Q = -1.22700E-01 MeV Emin = 1.16696E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 5 MT = 52 Q = -2.14300E-01 MeV Emin = 2.13900E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 6 MT = 53 Q = -2.68800E-01 MeV Emin = 2.60157E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 7 MT = 54 Q = -3.37700E-01 MeV Emin = 3.19802E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 8 MT = 55 Q = -3.74999E-01 MeV Emin = 3.76111E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 9 MT = 56 Q = -4.38599E-01 MeV Emin = 4.30804E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 10 MT = 57 Q = -5.18399E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 11 MT = 58 Q = -6.16899E-01 MeV Emin = 6.11928E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 12 MT = 59 Q = -6.31199E-01 MeV Emin = 6.27567E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 13 MT = 60 Q = -8.48299E-01 MeV Emin = 8.52231E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 14 MT = 61 Q = -8.70199E-01 MeV Emin = 8.66846E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 15 MT = 62 Q = -1.00340E+00 MeV Emin = 1.00372E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 16 MT = 91 Q = -1.07000E+00 MeV Emin = 1.06836E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 17 MT = 102 Q = 7.38869E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 72180.82c : (n,gamma) + 18 MT = 103 Q = -5.67529E-01 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 711790 : (n,p) + 19 MT = 107 Q = 8.68174E+00 MeV Emin = 4.85728E-01 MeV frac = 1.00000E+00 Product nuclide = 701760 : (n,alpha) + + 3 additional transport branches: + + 1 MT = 102 Q = 7.38869E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 721801 : (n,gamma) + 2 MT = 103 Q = -5.67529E-01 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 107 Q = 8.68174E+00 MeV Emin = 4.85728E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 4 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 4.85728E-01 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 4 MT = 4 Q = 0.00000E+00 MeV Emin = 1.16696E-01 MeV : total inelastic scattering + + Nuclide 255 / 1657 : 72180.82c -- hafnium 180 (Hf-180) + + Pointers : 2082651 25813 + Primary type : Transport + Nuclide ZAI : 721800 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Hf180.ACE + Atomic weight (AW) : 179.94986 + Atomic weight ratio (AWR) : 178.40400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 18 reaction channels + - 4 special reactions + - 5 transmutation reactions + - 2 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 18 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.38768E+00 MeV Emin = 7.42910E+00 MeV frac = 1.00000E+00 Product nuclide = 72179.82c : (n,2n) + 3 MT = 17 Q = -1.34874E+01 MeV Emin = 1.35630E+01 MeV frac = 1.00000E+00 Product nuclide = 72178.82c : (n,3n) + 4 MT = 51 Q = -9.32999E-02 MeV Emin = 9.08451E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 5 MT = 52 Q = -3.08600E-01 MeV Emin = 3.05165E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 6 MT = 53 Q = -6.40899E-01 MeV Emin = 6.40138E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 7 MT = 54 Q = -1.08390E+00 MeV Emin = 1.07603E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 8 MT = 55 Q = -1.14160E+00 MeV Emin = 1.12262E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 9 MT = 56 Q = -1.18320E+00 MeV Emin = 1.15649E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 10 MT = 57 Q = -1.19970E+00 MeV Emin = 1.20610E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 11 MT = 58 Q = -1.29100E+00 MeV Emin = 1.27655E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 12 MT = 59 Q = -1.37440E+00 MeV Emin = 1.37696E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 13 MT = 60 Q = -1.40920E+00 MeV Emin = 1.39960E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 14 MT = 61 Q = -1.53930E+00 MeV Emin = 1.52218E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 15 MT = 91 Q = -1.60760E+00 MeV Emin = 1.61058E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 16 MT = 102 Q = 5.69569E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 721810 : (n,gamma) + 17 MT = 103 Q = -2.51353E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 711800 : (n,p) + 18 MT = 107 Q = 6.85574E+00 MeV Emin = 4.75000E-01 MeV frac = 1.00000E+00 Product nuclide = 701770 : (n,alpha) + + 2 additional transport branches: + + 1 MT = 103 Q = -2.51353E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 107 Q = 6.85574E+00 MeV Emin = 4.75000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 4 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.00000E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 4.75000E-01 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 4 MT = 4 Q = 0.00000E+00 MeV Emin = 9.08451E-02 MeV : total inelastic scattering + + Nuclide 256 / 1657 : 73181.82c -- tantalum 181 (Ta-181) + + Pointers : 2092281 34231 + Primary type : Transport + Nuclide ZAI : 731810 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ta181.ACE + Atomic weight (AW) : 180.94844 + Atomic weight ratio (AWR) : 179.39400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 22 reaction channels + - 4 special reactions + - 6 transmutation reactions + - 3 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 22 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.64368E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 731800 : (n,2n) + 3 MT = 17 Q = -1.42244E+01 MeV Emin = 1.43037E+01 MeV frac = 1.00000E+00 Product nuclide = 731790 : (n,3n) + 4 MT = 28 Q = -5.93521E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 72180.82c : (n,np) + 5 MT = 51 Q = -6.20000E-03 MeV Emin = 6.00000E-03 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -1.36000E-01 MeV Emin = 1.27569E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -1.59000E-01 MeV Emin = 1.59585E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -3.01000E-01 MeV Emin = 3.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -3.38000E-01 MeV Emin = 3.21482E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -4.81999E-01 MeV Emin = 4.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -4.94999E-01 MeV Emin = 4.91273E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -5.42999E-01 MeV Emin = 5.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -6.14999E-01 MeV Emin = 6.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -6.18999E-01 MeV Emin = 6.20490E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -7.16999E-01 MeV Emin = 7.20595E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -7.72999E-01 MeV Emin = 7.49153E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 63 Q = -9.64999E-01 MeV Emin = 9.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 18 MT = 64 Q = -1.02800E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 19 MT = 91 Q = -1.03000E+00 MeV Emin = 1.03474E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 20 MT = 102 Q = 6.06369E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 73182.82c : (n,gamma) + 21 MT = 103 Q = -2.40530E-01 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 721810 : (n,p) + 22 MT = 107 Q = 7.40474E+00 MeV Emin = 4.98930E-01 MeV frac = 1.00000E+00 Product nuclide = 711780 : (n,alpha) + + 3 additional transport branches: + + 1 MT = 28 Q = -5.93521E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 2 MT = 103 Q = -2.40530E-01 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 107 Q = 7.40474E+00 MeV Emin = 4.98930E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 4 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.50000E+00 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 4.98930E-01 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 4 MT = 4 Q = 0.00000E+00 MeV Emin = 6.00000E-03 MeV : total inelastic scattering + + Nuclide 257 / 1657 : 73182.82c -- tantalum 182 (Ta-182) + + Pointers : 2094509 34277 + Primary type : Transport + Nuclide ZAI : 731820 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ta182.ACE + Atomic weight (AW) : 181.95005 + Atomic weight ratio (AWR) : 180.38700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 9.91E+06 seconds (115 days) + Specific ingestion toxicity : 1.50E-09 Sv/Bq + Specific inhalation toxicity : 1.00E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 14 reaction channels + - 3 special reactions + - 4 transmutation reactions + - 1 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 14 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.06640E+00 MeV Emin = 6.10003E+00 MeV frac = 1.00000E+00 Product nuclide = 73181.82c : (n,2n) + 3 MT = 17 Q = -1.37240E+01 MeV Emin = 1.38001E+01 MeV frac = 1.00000E+00 Product nuclide = 731800 : (n,3n) + 4 MT = 51 Q = -9.70000E-02 MeV Emin = 8.56250E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 5 MT = 52 Q = -1.14000E-01 MeV Emin = 1.05000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 6 MT = 53 Q = -1.73000E-01 MeV Emin = 1.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 7 MT = 54 Q = -2.37000E-01 MeV Emin = 2.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 8 MT = 55 Q = -2.70000E-01 MeV Emin = 2.71140E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 9 MT = 56 Q = -2.92000E-01 MeV Emin = 2.79778E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 10 MT = 57 Q = -3.15000E-01 MeV Emin = 3.08350E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 11 MT = 58 Q = -3.60000E-01 MeV Emin = 3.39373E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 12 MT = 91 Q = -3.97800E-01 MeV Emin = 3.81000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 13 MT = 102 Q = 6.93000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 731830 : (n,gamma) + 14 MT = 107 Q = 8.29400E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 711790 : (n,alpha) + + 1 additional transport branch: + + 1 MT = 107 Q = 8.29400E+00 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 3 special reactions: + + 1 MT = 207 Q = 0.00000E+00 MeV Emin = 1.10000E+01 MeV : total alpha production + 2 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 3 MT = 4 Q = 0.00000E+00 MeV Emin = 8.56250E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.81360E+00 MeV frac = 1.00000E+00 Product nuclide = 74182.82c : beta- + + Nuclide 258 / 1657 : 74182.82c -- tungsten 182 (W-182) + + Pointers : 2104563 35933 + Primary type : Transport + Nuclide ZAI : 741820 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/W182.ACE + Atomic weight (AW) : 181.94803 + Atomic weight ratio (AWR) : 180.38500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 30 reaction channels + - 5 special reactions + - 8 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 30 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.05468E+00 MeV Emin = 8.09934E+00 MeV frac = 1.00000E+00 Product nuclide = 741810 : (n,2n) + 3 MT = 17 Q = -1.47014E+01 MeV Emin = 1.47829E+01 MeV frac = 1.00000E+00 Product nuclide = 741800 : (n,3n) + 4 MT = 22 Q = 1.78906E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 72178.82c : (n,nalpha) + 5 MT = 28 Q = -7.08521E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 73181.82c : (n,np) + 6 MT = 51 Q = -1.00100E-01 MeV Emin = 1.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -3.29400E-01 MeV Emin = 3.15613E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -6.80500E-01 MeV Emin = 6.63204E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -1.13570E+00 MeV Emin = 1.12100E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -1.14450E+00 MeV Emin = 1.15000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -1.22140E+00 MeV Emin = 1.20000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -1.33110E+00 MeV Emin = 1.31924E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -1.44280E+00 MeV Emin = 1.43000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -1.71190E+00 MeV Emin = 1.68000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -1.75680E+00 MeV Emin = 1.75000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -1.76540E+00 MeV Emin = 1.77496E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -1.76900E+00 MeV Emin = 1.77661E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -1.80970E+00 MeV Emin = 1.79987E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -1.81090E+00 MeV Emin = 1.82064E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -1.81340E+00 MeV Emin = 1.82282E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 21 MT = 66 Q = -1.82950E+00 MeV Emin = 1.83000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 22 MT = 67 Q = -1.83310E+00 MeV Emin = 1.84145E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 23 MT = 68 Q = -1.85600E+00 MeV Emin = 1.85814E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 24 MT = 69 Q = -1.85690E+00 MeV Emin = 1.86674E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 25 MT = 70 Q = -1.87120E+00 MeV Emin = 1.87579E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 26 MT = 91 Q = -1.87200E+00 MeV Emin = 1.88198E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 27 MT = 102 Q = 6.19070E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 74183.82c : (n,gamma) + 28 MT = 103 Q = -1.02253E+00 MeV Emin = 2.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 73182.82c : (n,p) + 29 MT = 104 Q = -4.86060E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 73181.82c : (n,d) + 30 MT = 107 Q = 7.88874E+00 MeV Emin = 9.00000E-02 MeV frac = 1.00000E+00 Product nuclide = 72179.82c : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = 1.78906E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -7.08521E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 102 Q = 6.19070E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 741831 : (n,gamma) + 4 MT = 103 Q = -1.02253E+00 MeV Emin = 2.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -4.86060E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 107 Q = 7.88874E+00 MeV Emin = 9.00000E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 5 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.50000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.00000E+00 MeV : total deuteron production + 3 MT = 207 Q = 0.00000E+00 MeV Emin = 9.00000E-02 MeV : total alpha production + 4 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 5 MT = 4 Q = 0.00000E+00 MeV Emin = 1.00000E-01 MeV : total inelastic scattering + + Nuclide 259 / 1657 : 74183.82c -- tungsten 183 (W-183) + + Pointers : 2107686 35979 + Primary type : Transport + Nuclide ZAI : 741830 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/W183.ACE + Atomic weight (AW) : 182.95064 + Atomic weight ratio (AWR) : 181.37900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 3.47E+24 seconds (1.1E+17 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 20 reaction channels + - 5 special reactions + - 8 transmutation reactions + - 5 transmutation branch reactions + - 3 decay reactions + - 3 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 20 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.19139E+00 MeV Emin = 6.22553E+00 MeV frac = 1.00000E+00 Product nuclide = 74182.82c : (n,2n) + 3 MT = 17 Q = -1.42454E+01 MeV Emin = 1.43239E+01 MeV frac = 1.00000E+00 Product nuclide = 741810 : (n,3n) + 4 MT = 22 Q = 1.69806E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 72179.82c : (n,nalpha) + 5 MT = 28 Q = -7.21322E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 73182.82c : (n,np) + 6 MT = 51 Q = -4.65000E-02 MeV Emin = 4.58782E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -9.91000E-02 MeV Emin = 9.34406E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -2.07000E-01 MeV Emin = 2.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -2.08800E-01 MeV Emin = 2.09046E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -2.91700E-01 MeV Emin = 2.90206E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -3.08900E-01 MeV Emin = 3.05302E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -3.09500E-01 MeV Emin = 3.10905E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -4.12100E-01 MeV Emin = 4.07186E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -4.87000E-01 MeV Emin = 4.81264E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -5.50000E-01 MeV Emin = 5.39774E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 91 Q = -6.24000E-01 MeV Emin = 6.27000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 17 MT = 102 Q = 7.41170E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 74184.82c : (n,gamma) + 18 MT = 103 Q = -2.85530E-01 MeV Emin = 1.75000E+00 MeV frac = 1.00000E+00 Product nuclide = 731830 : (n,p) + 19 MT = 104 Q = -4.98860E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 73182.82c : (n,d) + 20 MT = 107 Q = 9.08574E+00 MeV Emin = 7.25000E-01 MeV frac = 1.00000E+00 Product nuclide = 72180.82c : (n,alpha) + + 5 additional transport branches: + + 1 MT = 22 Q = 1.69806E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -7.21322E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -2.85530E-01 MeV Emin = 1.75000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -4.98860E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 107 Q = 9.08574E+00 MeV Emin = 7.25000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 5 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.75000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.00000E+00 MeV : total deuteron production + 3 MT = 207 Q = 0.00000E+00 MeV Emin = 7.25000E-01 MeV : total alpha production + 4 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 5 MT = 4 Q = 0.00000E+00 MeV Emin = 4.58782E-02 MeV : total inelastic scattering + + 3 decay reactions: + + 1 RTYP = 4 Q = 1.68000E+00 MeV frac = 3.34000E-01 Product nuclide = 72179.82c : alpha + 2 RTYP = 4 Q = 1.30496E+00 MeV frac = 3.33000E-01 Product nuclide = 721791 : alpha + 3 RTYP = 4 Q = 5.74160E-01 MeV frac = 3.33000E-01 Product nuclide = 721792 : alpha + + 3 additional decay branches: + + 1 RTYP = 4 Q = 1.68000E+00 MeV frac = 3.34000E-01 Product nuclide = 2004.82c : alpha + 2 RTYP = 4 Q = 1.30496E+00 MeV frac = 3.33000E-01 Product nuclide = 2004.82c : alpha + 3 RTYP = 4 Q = 5.74160E-01 MeV frac = 3.33000E-01 Product nuclide = 2004.82c : alpha + + Nuclide 260 / 1657 : 74184.82c -- tungsten 184 (W-184) + + Pointers : 2111076 36025 + Primary type : Transport + Nuclide ZAI : 741840 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/W184.ACE + Atomic weight (AW) : 183.95124 + Atomic weight ratio (AWR) : 182.37100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.26E+25 seconds (4E+17 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 20 reaction channels + - 5 special reactions + - 8 transmutation reactions + - 6 transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 20 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.41168E+00 MeV Emin = 7.45233E+00 MeV frac = 1.00000E+00 Product nuclide = 74183.82c : (n,2n) + 3 MT = 17 Q = -1.36024E+01 MeV Emin = 1.36770E+01 MeV frac = 1.00000E+00 Product nuclide = 74182.82c : (n,3n) + 4 MT = 22 Q = 1.67406E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 72180.82c : (n,nalpha) + 5 MT = 28 Q = -7.69721E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 731830 : (n,np) + 6 MT = 51 Q = -1.11200E-01 MeV Emin = 1.10905E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -3.64100E-01 MeV Emin = 3.33048E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -7.48300E-01 MeV Emin = 7.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -9.03300E-01 MeV Emin = 9.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -1.00230E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -1.00590E+00 MeV Emin = 1.01000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -1.12140E+00 MeV Emin = 1.10000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -1.22130E+00 MeV Emin = 1.20000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -1.28500E+00 MeV Emin = 1.27103E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -1.32210E+00 MeV Emin = 1.31000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 91 Q = -1.43200E+00 MeV Emin = 1.43885E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 17 MT = 102 Q = 5.75470E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 741850 : (n,gamma) + 18 MT = 103 Q = -2.24753E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 731840 : (n,p) + 19 MT = 104 Q = -5.47260E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 731830 : (n,d) + 20 MT = 107 Q = 7.36874E+00 MeV Emin = 9.00000E-02 MeV frac = 1.00000E+00 Product nuclide = 721810 : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = 1.67406E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -7.69721E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 102 Q = 5.75470E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 741851 : (n,gamma) + 4 MT = 103 Q = -2.24753E+00 MeV Emin = 3.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -5.47260E+00 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 107 Q = 7.36874E+00 MeV Emin = 9.00000E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 5 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 3.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 7.00000E+00 MeV : total deuteron production + 3 MT = 207 Q = 0.00000E+00 MeV Emin = 9.00000E-02 MeV : total alpha production + 4 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 5 MT = 4 Q = 0.00000E+00 MeV Emin = 1.10905E-01 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 4 Q = 1.65620E+00 MeV frac = 1.00000E+00 Product nuclide = 72180.82c : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 1.65620E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 261 / 1657 : 74186.82c -- tungsten 186 (W-186) + + Pointers : 2115071 36071 + Primary type : Transport + Nuclide ZAI : 741860 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/W186.ACE + Atomic weight (AW) : 185.95445 + Atomic weight ratio (AWR) : 184.35700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.86E+25 seconds (5.9E+17 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 22 reaction channels + - 5 special reactions + - 8 transmutation reactions + - 5 transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 22 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.19537E+00 MeV Emin = 7.23440E+00 MeV frac = 1.00000E+00 Product nuclide = 741850 : (n,2n) + 3 MT = 17 Q = -1.29514E+01 MeV Emin = 1.30217E+01 MeV frac = 1.00000E+00 Product nuclide = 74184.82c : (n,3n) + 4 MT = 22 Q = 1.12190E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 721820 : (n,nalpha) + 5 MT = 28 Q = -8.38421E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 731850 : (n,np) + 6 MT = 51 Q = -1.22600E-01 MeV Emin = 1.21633E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -3.96800E-01 MeV Emin = 3.74214E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -7.37700E-01 MeV Emin = 7.20850E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -8.08800E-01 MeV Emin = 8.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -8.61800E-01 MeV Emin = 8.40237E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -8.82000E-01 MeV Emin = 8.76892E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -9.52600E-01 MeV Emin = 9.28883E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -1.00700E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -1.03160E+00 MeV Emin = 1.03000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -1.04520E+00 MeV Emin = 1.04000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -1.15000E+00 MeV Emin = 1.15250E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -1.28400E+00 MeV Emin = 1.25000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 91 Q = -1.32300E+00 MeV Emin = 1.32917E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 19 MT = 102 Q = 5.46670E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 741870 : (n,gamma) + 20 MT = 103 Q = -3.11253E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 731860 : (n,p) + 21 MT = 104 Q = -6.15960E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 731850 : (n,d) + 22 MT = 107 Q = 6.39074E+00 MeV Emin = 1.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 721830 : (n,alpha) + + 5 additional transport branches: + + 1 MT = 22 Q = 1.12190E+00 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -8.38421E+00 MeV Emin = 9.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -3.11253E+00 MeV Emin = 4.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -6.15960E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 107 Q = 6.39074E+00 MeV Emin = 1.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 5 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 4.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 8.00000E+00 MeV : total deuteron production + 3 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-01 MeV : total alpha production + 4 MT = 444 Q = 0.00000E+00 MeV Emin = 2.46375E-08 MeV : damage-energy production + 5 MT = 4 Q = 0.00000E+00 MeV Emin = 1.21633E-01 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 11 Q = 4.89998E-01 MeV frac = 5.00000E-01 Product nuclide = 761860 : beta- + beta- + 2 RTYP = 4 Q = 1.12460E+00 MeV frac = 5.00000E-01 Product nuclide = 721820 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 1.12460E+00 MeV frac = 5.00000E-01 Product nuclide = 2004.82c : alpha + + Nuclide 262 / 1657 : 75185.82c -- rhenium 185 (Re-185) + + Pointers : 2129090 31379 + Primary type : Transport + Nuclide ZAI : 751850 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Re185.ACE + Atomic weight (AW) : 184.95284 + Atomic weight ratio (AWR) : 183.36400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 14 reaction channels + - 2 special reactions + - 3 transmutation reactions + - 1 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 14 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.67738E+00 MeV Emin = 7.71925E+00 MeV frac = 1.00000E+00 Product nuclide = 751840 : (n,2n) + 3 MT = 17 Q = -1.41558E+01 MeV Emin = 1.42330E+01 MeV frac = 1.00000E+00 Product nuclide = 751830 : (n,3n) + 4 MT = 51 Q = -1.25400E-01 MeV Emin = 1.08042E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 5 MT = 52 Q = -2.84100E-01 MeV Emin = 2.84375E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 6 MT = 53 Q = -3.68200E-01 MeV Emin = 3.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 7 MT = 54 Q = -4.75600E-01 MeV Emin = 4.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 8 MT = 55 Q = -5.46900E-01 MeV Emin = 5.24940E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 9 MT = 56 Q = -6.46100E-01 MeV Emin = 6.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 10 MT = 57 Q = -6.97000E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 11 MT = 58 Q = -7.17400E-01 MeV Emin = 7.11056E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 12 MT = 59 Q = -7.57400E-01 MeV Emin = 7.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 13 MT = 91 Q = -7.57400E-01 MeV Emin = 7.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 14 MT = 102 Q = 6.17800E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 751860 : (n,gamma) + + 1 additional transport branch: + + 1 MT = 102 Q = 6.17800E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 751861 : (n,gamma) + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 1.08042E-01 MeV : total inelastic scattering + + Nuclide 263 / 1657 : 75187.82c -- rhenium 187 (Re-187) + + Pointers : 2132046 31425 + Primary type : Transport + Nuclide ZAI : 751870 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Re187.ACE + Atomic weight (AW) : 186.95605 + Atomic weight ratio (AWR) : 185.35000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.37E+18 seconds (43.3 billion years) + Specific ingestion toxicity : 5.10E-12 Sv/Bq + Specific inhalation toxicity : 6.30E-12 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 21 reaction channels + - 2 special reactions + - 3 transmutation reactions + - 1 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 21 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.36038E+00 MeV Emin = 7.40009E+00 MeV frac = 1.00000E+00 Product nuclide = 751860 : (n,2n) + 3 MT = 17 Q = -1.35388E+01 MeV Emin = 1.36118E+01 MeV frac = 1.00000E+00 Product nuclide = 75185.82c : (n,3n) + 4 MT = 51 Q = -1.34200E-01 MeV Emin = 9.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 5 MT = 52 Q = -2.06200E-01 MeV Emin = 2.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 6 MT = 53 Q = -3.02700E-01 MeV Emin = 3.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 7 MT = 54 Q = -3.90000E-01 MeV Emin = 3.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 8 MT = 55 Q = -5.09000E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 9 MT = 56 Q = -5.11600E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 10 MT = 57 Q = -5.89000E-01 MeV Emin = 5.87500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 11 MT = 58 Q = -6.18300E-01 MeV Emin = 6.14435E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 12 MT = 59 Q = -6.25500E-01 MeV Emin = 6.25261E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 13 MT = 60 Q = -6.47300E-01 MeV Emin = 6.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 14 MT = 61 Q = -6.85700E-01 MeV Emin = 6.87698E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 15 MT = 62 Q = -7.43000E-01 MeV Emin = 7.23505E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 16 MT = 63 Q = -7.71000E-01 MeV Emin = 7.62580E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 17 MT = 64 Q = -7.72900E-01 MeV Emin = 7.76115E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 18 MT = 65 Q = -8.16600E-01 MeV Emin = 8.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 19 MT = 66 Q = -8.26600E-01 MeV Emin = 8.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 20 MT = 91 Q = -8.26600E-01 MeV Emin = 8.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 21 MT = 102 Q = 5.87300E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 751880 : (n,gamma) + + 1 additional transport branch: + + 1 MT = 102 Q = 5.87300E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 751881 : (n,gamma) + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 9.00000E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.46900E-03 MeV frac = 1.00000E+00 Product nuclide = 761870 : beta- + + Nuclide 264 / 1657 : 77191.82c -- iridium 191 (Ir-191) + + Pointers : 2156450 26733 + Primary type : Transport + Nuclide ZAI : 771910 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ir191.ACE + Atomic weight (AW) : 190.96045 + Atomic weight ratio (AWR) : 189.32000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 11 reaction channels + - 4 special reactions + - 5 transmutation reactions + - 2 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 11 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.76500E+00 MeV Emin = 7.80602E+00 MeV frac = 1.00000E+00 Product nuclide = 771900 : (n,2n) + 3 MT = 17 Q = -1.39640E+01 MeV Emin = 1.40378E+01 MeV frac = 1.00000E+00 Product nuclide = 771890 : (n,3n) + 4 MT = 51 Q = -8.24000E-02 MeV Emin = 7.71251E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 5 MT = 52 Q = -1.29400E-01 MeV Emin = 1.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 6 MT = 53 Q = -1.71000E-01 MeV Emin = 1.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 7 MT = 54 Q = -1.78900E-01 MeV Emin = 1.75872E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 8 MT = 91 Q = -1.89006E-01 MeV Emin = 2.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 9 MT = 102 Q = 6.19808E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 771920 : (n,gamma) + 10 MT = 103 Q = 4.72400E-01 MeV Emin = 8.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 761910 : (n,p) + 11 MT = 107 Q = 7.95480E+00 MeV Emin = 8.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 751880 : (n,alpha) + + 2 additional transport branches: + + 1 MT = 103 Q = 4.72400E-01 MeV Emin = 8.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 107 Q = 7.95480E+00 MeV Emin = 8.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 4 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 8.00000E-01 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 8.00000E-01 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 4 MT = 4 Q = 0.00000E+00 MeV Emin = 7.71251E-02 MeV : total inelastic scattering + + Nuclide 265 / 1657 : 77193.82c -- iridium 193 (Ir-193) + + Pointers : 2161203 26779 + Primary type : Transport + Nuclide ZAI : 771930 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Ir193.ACE + Atomic weight (AW) : 192.96265 + Atomic weight ratio (AWR) : 191.30500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 11 reaction channels + - 4 special reactions + - 5 transmutation reactions + - 2 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 11 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.76500E+00 MeV Emin = 7.80600E+00 MeV frac = 1.00000E+00 Product nuclide = 771920 : (n,2n) + 3 MT = 17 Q = -1.39640E+01 MeV Emin = 1.40370E+01 MeV frac = 1.00000E+00 Product nuclide = 77191.82c : (n,3n) + 4 MT = 51 Q = -7.30000E-02 MeV Emin = 7.25000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 5 MT = 52 Q = -8.03000E-02 MeV Emin = 8.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 6 MT = 53 Q = -1.38000E-01 MeV Emin = 1.37500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 7 MT = 54 Q = -1.80000E-01 MeV Emin = 1.70000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 8 MT = 91 Q = -1.89006E-01 MeV Emin = 2.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 9 MT = 102 Q = 6.06680E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 771940 : (n,gamma) + 10 MT = 103 Q = 4.72400E-01 MeV Emin = 8.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 761930 : (n,p) + 11 MT = 107 Q = 6.79000E+00 MeV Emin = 8.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 751900 : (n,alpha) + + 2 additional transport branches: + + 1 MT = 103 Q = 4.72400E-01 MeV Emin = 8.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 2 MT = 107 Q = 6.79000E+00 MeV Emin = 8.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 4 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 8.00000E-01 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 8.00000E-01 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 4 MT = 4 Q = 0.00000E+00 MeV Emin = 7.25000E-02 MeV : total inelastic scattering + + Nuclide 266 / 1657 : 79197.82c -- gold 197 (Au-197) + + Pointers : 2180021 19327 + Primary type : Transport + Nuclide ZAI : 791970 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Au197.ACE + Atomic weight (AW) : 196.96604 + Atomic weight ratio (AWR) : 195.27400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 3.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 21 reaction channels + - 4 special reactions + - 5 transmutation reactions + - 3 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 21 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.05940E+00 MeV Emin = 8.10070E+00 MeV frac = 1.00000E+00 Product nuclide = 791960 : (n,2n) + 3 MT = 17 Q = -1.47210E+01 MeV Emin = 1.47964E+01 MeV frac = 1.00000E+00 Product nuclide = 791950 : (n,3n) + 4 MT = 37 Q = -2.31080E+01 MeV Emin = 2.32270E+01 MeV frac = 1.00000E+00 Product nuclide = cut: Au-194 : (n,4n) + 5 MT = 51 Q = -7.74000E-02 MeV Emin = 7.77500E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -2.69000E-01 MeV Emin = 2.70000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -2.79000E-01 MeV Emin = 2.80000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -4.09000E-01 MeV Emin = 4.10000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -5.03000E-01 MeV Emin = 5.05000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -5.48000E-01 MeV Emin = 5.50625E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -7.37000E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -8.55000E-01 MeV Emin = 8.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -8.88000E-01 MeV Emin = 8.92384E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -9.36000E-01 MeV Emin = 9.40000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -1.04500E+00 MeV Emin = 1.05000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -1.15000E+00 MeV Emin = 1.15000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 63 Q = -1.21740E+00 MeV Emin = 1.20000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 18 MT = 91 Q = -9.94900E-02 MeV Emin = 9.95000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 19 MT = 102 Q = 6.51238E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 791980 : (n,gamma) + 20 MT = 103 Q = 6.34000E-02 MeV Emin = 5.75000E-03 MeV frac = 1.00000E+00 Product nuclide = 781970 : (n,p) + 21 MT = 107 Q = 7.01050E+00 MeV Emin = 5.75000E-03 MeV frac = 1.00000E+00 Product nuclide = 771940 : (n,alpha) + + 3 additional transport branches: + + 1 MT = 102 Q = 6.51238E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 791981 : (n,gamma) + 2 MT = 103 Q = 6.34000E-02 MeV Emin = 5.75000E-03 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 3 MT = 107 Q = 7.01050E+00 MeV Emin = 5.75000E-03 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 4 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 5.75000E-03 MeV : total proton production + 2 MT = 207 Q = 0.00000E+00 MeV Emin = 5.75000E-03 MeV : total alpha production + 3 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 4 MT = 4 Q = 0.00000E+00 MeV Emin = 7.77500E-02 MeV : total inelastic scattering + + Nuclide 267 / 1657 : 80198.82c -- mercury 198 (Hg-198) + + Pointers : 2191904 25905 + Primary type : Transport + Nuclide ZAI : 801980 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Hg198.ACE + Atomic weight (AW) : 197.96664 + Atomic weight ratio (AWR) : 196.26600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 29 reaction channels + - 5 special reactions + - 8 transmutation reactions + - 6 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 29 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.30069E+00 MeV Emin = 8.34298E+00 MeV frac = 1.00000E+00 Product nuclide = 801970 : (n,2n) + 3 MT = 17 Q = -1.52814E+01 MeV Emin = 1.53593E+01 MeV frac = 1.00000E+00 Product nuclide = 801960 : (n,3n) + 4 MT = 22 Q = 1.33306E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 781940 : (n,nalpha) + 5 MT = 28 Q = -7.10322E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 79197.82c : (n,np) + 6 MT = 51 Q = -4.11800E-01 MeV Emin = 3.81949E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.04850E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -1.08770E+00 MeV Emin = 1.08336E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -1.40150E+00 MeV Emin = 1.36898E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -1.41940E+00 MeV Emin = 1.41766E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -1.54850E+00 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -1.61240E+00 MeV Emin = 1.60015E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -1.63560E+00 MeV Emin = 1.63296E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -1.68330E+00 MeV Emin = 1.66791E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -1.76000E+00 MeV Emin = 1.75000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -1.81580E+00 MeV Emin = 1.81103E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -1.83250E+00 MeV Emin = 1.83345E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -1.83490E+00 MeV Emin = 1.84302E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -1.84720E+00 MeV Emin = 1.85128E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -1.85880E+00 MeV Emin = 1.86244E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 21 MT = 66 Q = -1.89930E+00 MeV Emin = 1.88863E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 22 MT = 67 Q = -1.90140E+00 MeV Emin = 1.91003E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 23 MT = 68 Q = -1.90970E+00 MeV Emin = 1.91526E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 24 MT = 69 Q = -1.91080E+00 MeV Emin = 1.92010E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 25 MT = 91 Q = -1.91100E+00 MeV Emin = 1.92010E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 26 MT = 102 Q = 6.64900E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 80199.82c : (n,gamma) + 27 MT = 103 Q = -5.90530E-01 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 791980 : (n,p) + 28 MT = 104 Q = -4.87861E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 79197.82c : (n,d) + 29 MT = 107 Q = 7.45775E+00 MeV Emin = 1.00000E-02 MeV frac = 1.00000E+00 Product nuclide = 781950 : (n,alpha) + + 6 additional transport branches: + + 1 MT = 22 Q = 1.33306E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -7.10322E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 102 Q = 6.64900E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 801991 : (n,gamma) + 4 MT = 103 Q = -5.90530E-01 MeV Emin = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 5 MT = 104 Q = -4.87861E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 6 MT = 107 Q = 7.45775E+00 MeV Emin = 1.00000E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 5 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.00000E+00 MeV : total deuteron production + 3 MT = 207 Q = 0.00000E+00 MeV Emin = 1.00000E-02 MeV : total alpha production + 4 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 5 MT = 4 Q = 0.00000E+00 MeV Emin = 3.81949E-01 MeV : total inelastic scattering + + Nuclide 268 / 1657 : 80199.82c -- mercury 199 (Hg-199) + + Pointers : 2194954 25951 + Primary type : Transport + Nuclide ZAI : 801990 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Hg199.ACE + Atomic weight (AW) : 198.96824 + Atomic weight ratio (AWR) : 197.25900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 23 reaction channels + - 5 special reactions + - 8 transmutation reactions + - 5 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 23 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.64869E+00 MeV Emin = 6.68240E+00 MeV frac = 1.00000E+00 Product nuclide = 80198.82c : (n,2n) + 3 MT = 17 Q = -1.49494E+01 MeV Emin = 1.50252E+01 MeV frac = 1.00000E+00 Product nuclide = 801970 : (n,3n) + 4 MT = 22 Q = 8.09060E-01 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 781950 : (n,nalpha) + 5 MT = 28 Q = -7.23922E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 791980 : (n,np) + 6 MT = 51 Q = -1.58380E-01 MeV Emin = 1.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -2.08200E-01 MeV Emin = 2.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -4.03500E-01 MeV Emin = 4.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -4.13900E-01 MeV Emin = 4.11998E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -4.55500E-01 MeV Emin = 4.47356E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -4.92300E-01 MeV Emin = 4.89452E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -5.32500E-01 MeV Emin = 5.26400E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -6.38000E-01 MeV Emin = 6.20617E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -6.68900E-01 MeV Emin = 6.64527E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -6.95900E-01 MeV Emin = 6.94403E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -7.12900E-01 MeV Emin = 7.05458E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -7.37400E-01 MeV Emin = 7.28826E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -7.50400E-01 MeV Emin = 7.54003E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 91 Q = -7.50000E-01 MeV Emin = 7.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 20 MT = 102 Q = 8.02900E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 80200.82c : (n,gamma) + 21 MT = 103 Q = 3.29470E-01 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 791990 : (n,p) + 22 MT = 104 Q = -5.01461E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 791980 : (n,d) + 23 MT = 107 Q = 8.72975E+00 MeV Emin = 5.84812E-01 MeV frac = 1.00000E+00 Product nuclide = 781960 : (n,alpha) + + 5 additional transport branches: + + 1 MT = 22 Q = 8.09060E-01 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -7.23922E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = 3.29470E-01 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -5.01461E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 107 Q = 8.72975E+00 MeV Emin = 5.84812E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 5 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 1.00000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.00000E+00 MeV : total deuteron production + 3 MT = 207 Q = 0.00000E+00 MeV Emin = 5.84812E-01 MeV : total alpha production + 4 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 5 MT = 4 Q = 0.00000E+00 MeV Emin = 1.50000E-01 MeV : total inelastic scattering + + Nuclide 269 / 1657 : 80200.82c -- mercury 200 (Hg-200) + + Pointers : 2198041 25997 + Primary type : Transport + Nuclide ZAI : 802000 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Hg200.ACE + Atomic weight (AW) : 199.96783 + Atomic weight ratio (AWR) : 198.25000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - 44 reaction channels + - 5 special reactions + - 8 transmutation reactions + - 5 transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 44 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -8.02869E+00 MeV Emin = 8.06919E+00 MeV frac = 1.00000E+00 Product nuclide = 80199.82c : (n,2n) + 3 MT = 17 Q = -1.46774E+01 MeV Emin = 1.47514E+01 MeV frac = 1.00000E+00 Product nuclide = 80198.82c : (n,3n) + 4 MT = 22 Q = 7.01060E-01 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 781960 : (n,nalpha) + 5 MT = 28 Q = -7.69922E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 791990 : (n,np) + 6 MT = 51 Q = -3.67900E-01 MeV Emin = 3.40000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -9.47200E-01 MeV Emin = 8.75989E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -1.02930E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -1.25410E+00 MeV Emin = 1.25000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -1.51520E+00 MeV Emin = 1.50000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -1.57030E+00 MeV Emin = 1.56438E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -1.57370E+00 MeV Emin = 1.57993E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -1.59340E+00 MeV Emin = 1.59792E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -1.63090E+00 MeV Emin = 1.63048E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -1.64140E+00 MeV Emin = 1.64676E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -1.65900E+00 MeV Emin = 1.65940E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -1.70670E+00 MeV Emin = 1.70332E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -1.71830E+00 MeV Emin = 1.72114E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -1.73090E+00 MeV Emin = 1.73726E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -1.73430E+00 MeV Emin = 1.74134E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 21 MT = 66 Q = -1.77560E+00 MeV Emin = 1.76754E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 22 MT = 67 Q = -1.84580E+00 MeV Emin = 1.84441E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 23 MT = 68 Q = -1.85150E+00 MeV Emin = 1.85796E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 24 MT = 69 Q = -1.85680E+00 MeV Emin = 1.86433E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 25 MT = 70 Q = -1.88290E+00 MeV Emin = 1.88875E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 26 MT = 71 Q = -1.96260E+00 MeV Emin = 1.94459E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 27 MT = 72 Q = -1.97230E+00 MeV Emin = 1.97738E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 28 MT = 73 Q = -1.97430E+00 MeV Emin = 1.98325E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 29 MT = 74 Q = -2.04910E+00 MeV Emin = 2.05944E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 30 MT = 75 Q = -2.06130E+00 MeV Emin = 2.07170E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 31 MT = 76 Q = -2.07430E+00 MeV Emin = 2.08476E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 32 MT = 77 Q = -2.11430E+00 MeV Emin = 2.12497E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 27. excited state + 33 MT = 78 Q = -2.11650E+00 MeV Emin = 2.12718E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 28. excited state + 34 MT = 79 Q = -2.12690E+00 MeV Emin = 2.13763E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 29. excited state + 35 MT = 80 Q = -2.12790E+00 MeV Emin = 2.13863E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 30. excited state + 36 MT = 81 Q = -2.13550E+00 MeV Emin = 2.14627E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 31. excited state + 37 MT = 82 Q = -2.14380E+00 MeV Emin = 2.15462E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 32. excited state + 38 MT = 83 Q = -2.15140E+00 MeV Emin = 2.16225E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 33. excited state + 39 MT = 84 Q = -2.18950E+00 MeV Emin = 2.20054E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 34. excited state + 40 MT = 91 Q = -2.12700E+00 MeV Emin = 2.13773E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 41 MT = 102 Q = 6.22500E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 802010 : (n,gamma) + 42 MT = 103 Q = -1.41653E+00 MeV Emin = 2.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 792000 : (n,p) + 43 MT = 104 Q = -5.47461E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 791990 : (n,d) + 44 MT = 107 Q = 6.55175E+00 MeV Emin = 4.20000E-01 MeV frac = 1.00000E+00 Product nuclide = 781970 : (n,alpha) + + 5 additional transport branches: + + 1 MT = 22 Q = 7.01060E-01 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,nalpha) + 2 MT = 28 Q = -7.69922E+00 MeV Emin = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,np) + 3 MT = 103 Q = -1.41653E+00 MeV Emin = 2.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : (n,p) + 4 MT = 104 Q = -5.47461E+00 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 1002.82c : (n,d) + 5 MT = 107 Q = 6.55175E+00 MeV Emin = 4.20000E-01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : (n,alpha) + + 5 special reactions: + + 1 MT = 203 Q = 0.00000E+00 MeV Emin = 2.50000E+00 MeV : total proton production + 2 MT = 204 Q = 0.00000E+00 MeV Emin = 6.00000E+00 MeV : total deuteron production + 3 MT = 207 Q = 0.00000E+00 MeV Emin = 4.20000E-01 MeV : total alpha production + 4 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 5 MT = 4 Q = 0.00000E+00 MeV Emin = 3.40000E-01 MeV : total inelastic scattering + + Nuclide 270 / 1657 : 90227.82c -- thorium 227 (Th-227) + + Pointers : 2284498 34967 + Primary type : Transport + Nuclide ZAI : 902270 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Th227.ACE + Atomic weight (AW) : 227.02729 + Atomic weight ratio (AWR) : 225.07700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.62E+06 seconds (18.7 days) + Specific ingestion toxicity : 8.80E-09 Sv/Bq + Specific inhalation toxicity : 1.00E-05 Sv/Bq + Energy deposited per fission : 208.83 MeV + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has delayed neutron data in 8 precursor groups + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide is using NFY data from U-233 + - Nuclide has no SFY data + + - 7 reaction channels + - 2 special reactions + - 5 transmutation reactions + - 2 transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 7 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.45439E+00 MeV Emin = 5.47862E+00 MeV frac = 1.00000E+00 Product nuclide = 902260 : (n,2n) + 3 MT = 17 Q = -1.26401E+01 MeV Emin = 1.26963E+01 MeV frac = 1.00000E+00 Product nuclide = 902250 : (n,3n) + 4 MT = 18 Q = 1.99999E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : total fission + 5 MT = 37 Q = -1.84018E+01 MeV Emin = 1.84836E+01 MeV frac = 1.00000E+00 Product nuclide = 902240 : (n,4n) + 6 MT = 91 Q = -2.45000E-02 MeV Emin = 2.34567E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 7 MT = 102 Q = 7.12869E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 90228.82c : (n,gamma) + + 2 additional transport branches: + + 1 MT = 18 Q = 1.99999E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 1.40000E+01 MeV) : total fission + 2 MT = 18 Q = 1.99999E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 2.34567E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 4 Q = 6.14643E+00 MeV frac = 1.00000E+00 Product nuclide = 882230 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 6.14643E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 271 / 1657 : 90228.82c -- thorium 228 (Th-228) + + Pointers : 2319326 35013 + Primary type : Transport + Nuclide ZAI : 902280 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Th228.ACE + Atomic weight (AW) : 228.02889 + Atomic weight ratio (AWR) : 226.07000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 6.04E+07 seconds (1.91 years) + Specific ingestion toxicity : 7.20E-08 Sv/Bq + Specific inhalation toxicity : 4.00E-05 Sv/Bq + Energy deposited per fission : 193.16 MeV + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide is using NFY data from U-233 + - Nuclide has no SFY data + + - 18 reaction channels + - 2 special reactions + - 4 transmutation reactions + - 2 transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 18 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.11998E+00 MeV Emin = 7.15149E+00 MeV frac = 1.00000E+00 Product nuclide = 90227.82c : (n,2n) + 3 MT = 17 Q = -1.25744E+01 MeV Emin = 1.26300E+01 MeV frac = 1.00000E+00 Product nuclide = 902260 : (n,3n) + 4 MT = 18 Q = 1.84999E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : total fission + 5 MT = 51 Q = -5.75999E-02 MeV Emin = 5.39274E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -1.86900E-01 MeV Emin = 1.87500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -3.28000E-01 MeV Emin = 3.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -3.96099E-01 MeV Emin = 3.86426E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -5.19299E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -8.31699E-01 MeV Emin = 8.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -8.74599E-01 MeV Emin = 8.75000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -9.44099E-01 MeV Emin = 9.36638E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -9.51999E-01 MeV Emin = 9.53106E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -9.68798E-01 MeV Emin = 9.64668E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -1.01600E+00 MeV Emin = 1.02000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -1.02240E+00 MeV Emin = 1.02537E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 91 Q = -1.02500E+00 MeV Emin = 1.02823E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 18 MT = 102 Q = 5.24879E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 90229.82c : (n,gamma) + + 2 additional transport branches: + + 1 MT = 18 Q = 1.84999E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 1.40000E+01 MeV) : total fission + 2 MT = 18 Q = 1.84999E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 5.39274E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 4 Q = 5.52008E+00 MeV frac = 1.00000E+00 Product nuclide = 882240 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.52008E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 272 / 1657 : 90229.82c -- thorium 229 (Th-229) + + Pointers : 2349973 35059 + Primary type : Transport + Nuclide ZAI : 902290 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Th229.ACE + Atomic weight (AW) : 229.03150 + Atomic weight ratio (AWR) : 227.06400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.32E+11 seconds (7,345 years) + Specific ingestion toxicity : 4.90E-07 Sv/Bq + Specific inhalation toxicity : 2.40E-04 Sv/Bq + Energy deposited per fission : 208.83 MeV + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has delayed neutron data in 8 precursor groups + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide is using NFY data from U-233 + - Nuclide has no SFY data + + - 11 reaction channels + - 2 special reactions + - 5 transmutation reactions + - 2 transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 11 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.24879E+00 MeV Emin = 5.27191E+00 MeV frac = 1.00000E+00 Product nuclide = 90228.82c : (n,2n) + 3 MT = 17 Q = -1.23688E+01 MeV Emin = 1.24233E+01 MeV frac = 1.00000E+00 Product nuclide = 90227.82c : (n,3n) + 4 MT = 18 Q = 1.99999E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : total fission + 5 MT = 37 Q = -1.78232E+01 MeV Emin = 1.79017E+01 MeV frac = 1.00000E+00 Product nuclide = 902260 : (n,4n) + 6 MT = 51 Q = -1.00000E-04 MeV Emin = 9.43750E-05 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -2.00000E-02 MeV Emin = 2.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -2.92000E-02 MeV Emin = 2.84623E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -4.24999E-02 MeV Emin = 4.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 91 Q = -6.69999E-02 MeV Emin = 6.46036E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 11 MT = 102 Q = 6.78969E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 90230.82c : (n,gamma) + + 2 additional transport branches: + + 1 MT = 18 Q = 1.99999E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 1.40000E+01 MeV) : total fission + 2 MT = 18 Q = 1.99999E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 9.43750E-05 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 4 Q = 5.16860E+00 MeV frac = 1.00000E+00 Product nuclide = 882250 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.16860E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 273 / 1657 : 90230.82c -- thorium 230 (Th-230) + + Pointers : 2381425 35105 + Primary type : Transport + Nuclide ZAI : 902300 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Th230.ACE + Atomic weight (AW) : 230.03613 + Atomic weight ratio (AWR) : 228.06000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.38E+12 seconds (75,452 years) + Specific ingestion toxicity : 2.10E-07 Sv/Bq + Specific inhalation toxicity : 1.00E-04 Sv/Bq + Energy deposited per fission : 198.85 MeV + Spontaneous fission nubar : 1.39000 + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide is using NFY data from U-233 + - Nuclide has no SFY data + + - 23 reaction channels + - 2 special reactions + - 4 transmutation reactions + - 2 transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 23 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.79110E+00 MeV Emin = 6.82088E+00 MeV frac = 1.00000E+00 Product nuclide = 90229.82c : (n,2n) + 3 MT = 17 Q = -1.20400E+01 MeV Emin = 1.20930E+01 MeV frac = 1.00000E+00 Product nuclide = 90228.82c : (n,3n) + 4 MT = 18 Q = 1.90442E+02 MeV Emin = 2.45654E-04 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : total fission + 5 MT = 51 Q = -5.27690E-02 MeV Emin = 5.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -1.73240E-01 MeV Emin = 1.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -3.55440E-01 MeV Emin = 3.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -5.04790E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -5.69500E-01 MeV Emin = 5.39502E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -6.30240E-01 MeV Emin = 6.02500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -6.74040E-01 MeV Emin = 6.55002E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -6.79020E-01 MeV Emin = 6.79500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -7.67630E-01 MeV Emin = 7.35500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -7.77590E-01 MeV Emin = 7.76000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -8.26380E-01 MeV Emin = 8.05500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -8.48280E-01 MeV Emin = 8.41002E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 63 Q = -8.77150E-01 MeV Emin = 8.52000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 18 MT = 64 Q = -9.29920E-01 MeV Emin = 9.07500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 19 MT = 65 Q = -9.47840E-01 MeV Emin = 9.43000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 20 MT = 66 Q = -9.49840E-01 MeV Emin = 9.53000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 21 MT = 67 Q = -9.68750E-01 MeV Emin = 9.63503E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 22 MT = 91 Q = -9.95630E-01 MeV Emin = 9.86500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 23 MT = 102 Q = 5.12100E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 902310 : (n,gamma) + + 2 additional transport branches: + + 1 MT = 18 Q = 1.90442E+02 MeV Emin = 2.45654E-04 MeV frac = 1.00000E+00 NFY (E = 1.40000E+01 MeV) : total fission + 2 MT = 18 Q = 1.90442E+02 MeV Emin = 2.45654E-04 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 5.00000E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 4 Q = 4.77060E+00 MeV frac = 1.00000E+00 Product nuclide = 882260 : alpha + 2 RTYP = 6 Q = 1.69700E+02 MeV frac = 2.50000E-13 SF without yield : spontaneous fission + + 1 additional decay branch: + + 1 RTYP = 4 Q = 4.77060E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 274 / 1657 : 91231.82c -- protactinium 231 (Pa-231) + + Pointers : 2420509 29539 + Primary type : Transport + Nuclide ZAI : 912310 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Pa231.ACE + Atomic weight (AW) : 231.03471 + Atomic weight ratio (AWR) : 229.05000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.03E+12 seconds (32,783 years) + Specific ingestion toxicity : 7.10E-07 Sv/Bq + Specific inhalation toxicity : 1.40E-04 Sv/Bq + Energy deposited per fission : 208.83 MeV + Spontaneous fission nubar : 1.71000 + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has delayed neutron data in 8 precursor groups + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide is using NFY data from U-233 + - Nuclide has no SFY data + + - 18 reaction channels + - 2 special reactions + - 4 transmutation reactions + - 2 transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 18 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.81380E+00 MeV Emin = 6.84360E+00 MeV frac = 1.00000E+00 Product nuclide = 912300 : (n,2n) + 3 MT = 17 Q = -1.26060E+01 MeV Emin = 1.26610E+01 MeV frac = 1.00000E+00 Product nuclide = 912290 : (n,3n) + 4 MT = 18 Q = 2.00000E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : total fission + 5 MT = 51 Q = -8.96090E-03 MeV Emin = 5.00000E-03 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -5.77480E-02 MeV Emin = 5.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -7.76610E-02 MeV Emin = 6.80001E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -8.46310E-02 MeV Emin = 8.15000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -1.00560E-01 MeV Emin = 1.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -1.01560E-01 MeV Emin = 1.01500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -1.11510E-01 MeV Emin = 1.07002E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -1.33420E-01 MeV Emin = 1.23000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -1.71250E-01 MeV Emin = 1.53001E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -1.73240E-01 MeV Emin = 1.72000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -1.83200E-01 MeV Emin = 1.79000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -1.88180E-01 MeV Emin = 1.86500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 91 Q = -2.98700E-01 MeV Emin = 2.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 18 MT = 102 Q = 5.56100E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 91232.82c : (n,gamma) + + 2 additional transport branches: + + 1 MT = 18 Q = 2.00000E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 1.40000E+01 MeV) : total fission + 2 MT = 18 Q = 2.00000E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 5.00000E-03 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 4 Q = 5.14820E+00 MeV frac = 1.00000E+00 Product nuclide = 892270 : alpha + 2 RTYP = 6 Q = 1.77100E+02 MeV frac = 3.00000E-12 SF without yield : spontaneous fission + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.14820E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 275 / 1657 : 91232.82c -- protactinium 232 (Pa-232) + + Pointers : 2453838 29585 + Primary type : Transport + Nuclide ZAI : 912320 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Pa232.ACE + Atomic weight (AW) : 232.03833 + Atomic weight ratio (AWR) : 230.04500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.13E+05 seconds (1.31 days) + Specific ingestion toxicity : 7.20E-10 Sv/Bq + Specific inhalation toxicity : 1.00E-08 Sv/Bq + Energy deposited per fission : 208.83 MeV + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide is using NFY data from U-233 + - Nuclide has no SFY data + + - 7 reaction channels + - 2 special reactions + - 5 transmutation reactions + - 2 transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 7 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.56079E+00 MeV Emin = 5.58500E+00 MeV frac = 1.00000E+00 Product nuclide = 91231.82c : (n,2n) + 3 MT = 17 Q = -1.23749E+01 MeV Emin = 1.24287E+01 MeV frac = 1.00000E+00 Product nuclide = 912300 : (n,3n) + 4 MT = 18 Q = 1.99999E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : total fission + 5 MT = 37 Q = -1.81681E+01 MeV Emin = 1.82471E+01 MeV frac = 1.00000E+00 Product nuclide = 912290 : (n,4n) + 6 MT = 91 Q = -4.99999E-02 MeV Emin = 5.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 7 MT = 102 Q = 6.51669E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 91233.82c : (n,gamma) + + 2 additional transport branches: + + 1 MT = 18 Q = 1.99999E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 1.40000E+01 MeV) : total fission + 2 MT = 18 Q = 1.99999E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 5.00000E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.33700E+00 MeV frac = 9.99970E-01 Product nuclide = 92232.82c : beta- + 2 RTYP = 2 Q = 4.80000E-01 MeV frac = 3.00000E-05 Product nuclide = 902320 : EC/beta+ + + Nuclide 276 / 1657 : 91233.82c -- protactinium 233 (Pa-233) + + Pointers : 2484998 29631 + Primary type : Transport + Nuclide ZAI : 912330 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Pa233.ACE + Atomic weight (AW) : 233.03994 + Atomic weight ratio (AWR) : 231.03800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.33E+06 seconds (27 days) + Specific ingestion toxicity : 8.70E-10 Sv/Bq + Specific inhalation toxicity : 3.90E-09 Sv/Bq + Energy deposited per fission : 203.98 MeV + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide is using NFY data from Th-232 + - Nuclide has no SFY data + + - 11 reaction channels + - 2 special reactions + - 4 transmutation reactions + - 2 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 11 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.65560E+00 MeV Emin = 6.68441E+00 MeV frac = 1.00000E+00 Product nuclide = 91232.82c : (n,2n) + 3 MT = 17 Q = -1.21790E+01 MeV Emin = 1.22322E+01 MeV frac = 1.00000E+00 Product nuclide = 91231.82c : (n,3n) + 4 MT = 18 Q = 1.95361E+02 MeV Emin = 4.60000E-01 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + 5 MT = 51 Q = -1.87000E-02 MeV Emin = 1.80000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -5.69000E-02 MeV Emin = 5.50000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -7.12000E-02 MeV Emin = 7.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -8.68000E-02 MeV Emin = 8.50000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -1.04000E-01 MeV Emin = 1.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 91 Q = -1.99140E-01 MeV Emin = 1.80000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 11 MT = 102 Q = 5.19700E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 912340 : (n,gamma) + + 2 additional transport branches: + + 1 MT = 18 Q = 1.95361E+02 MeV Emin = 4.60000E-01 MeV frac = 1.00000E+00 NFY (E = 1.40000E+01 MeV) : total fission + 2 MT = 102 Q = 5.19700E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 912341 : (n,gamma) + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 1.80000E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.70100E-01 MeV frac = 1.00000E+00 Product nuclide = 92233.82c : beta- + + Nuclide 277 / 1657 : 92232.82c -- uranium 232 (U-232) + + Pointers : 2528048 35565 + Primary type : Transport + Nuclide ZAI : 922320 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/U232.ACE + Atomic weight (AW) : 232.03329 + Atomic weight ratio (AWR) : 230.04000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.20E+09 seconds (69.8 years) + Specific ingestion toxicity : 3.30E-07 Sv/Bq + Specific inhalation toxicity : 3.70E-05 Sv/Bq + Energy deposited per fission : 208.83 MeV + Spontaneous fission nubar : 1.71000 + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has delayed neutron data in 8 precursor groups + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide is using NFY data from U-233 + - Nuclide has no SFY data + + - 19 reaction channels + - 2 special reactions + - 4 transmutation reactions + - 2 transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 19 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.26000E+00 MeV Emin = 7.29160E+00 MeV frac = 1.00000E+00 Product nuclide = 922310 : (n,2n) + 3 MT = 17 Q = -1.31530E+01 MeV Emin = 1.32102E+01 MeV frac = 1.00000E+00 Product nuclide = 922300 : (n,3n) + 4 MT = 18 Q = 2.00000E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : total fission + 5 MT = 51 Q = -4.77920E-02 MeV Emin = 4.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -1.56320E-01 MeV Emin = 1.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -3.20610E-01 MeV Emin = 3.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -5.60560E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -6.26280E-01 MeV Emin = 5.96000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -6.88010E-01 MeV Emin = 6.60001E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -7.06930E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -7.31820E-01 MeV Emin = 7.22502E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -8.31390E-01 MeV Emin = 7.85001E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -8.63250E-01 MeV Emin = 8.51002E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -9.08050E-01 MeV Emin = 8.89501E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -9.66800E-01 MeV Emin = 9.41500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 63 Q = -9.82730E-01 MeV Emin = 9.79001E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 18 MT = 91 Q = -9.95670E-01 MeV Emin = 9.93501E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 19 MT = 102 Q = 5.75400E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 92233.82c : (n,gamma) + + 2 additional transport branches: + + 1 MT = 18 Q = 2.00000E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 1.40000E+01 MeV) : total fission + 2 MT = 18 Q = 2.00000E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 4.00000E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 4 Q = 5.41362E+00 MeV frac = 1.00000E+00 Product nuclide = 90228.82c : alpha + 2 RTYP = 6 Q = 1.76600E+02 MeV frac = 9.00000E-13 SF without yield : spontaneous fission + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.41362E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 278 / 1657 : 92233.82c -- uranium 233 (U-233) + + Pointers : 2558888 35611 + Primary type : Transport + Nuclide ZAI : 922330 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/U233.ACE + Atomic weight (AW) : 233.03994 + Atomic weight ratio (AWR) : 231.03800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 5.03E+12 seconds (159,359 years) + Specific ingestion toxicity : 5.10E-08 Sv/Bq + Specific inhalation toxicity : 9.60E-06 Sv/Bq + Energy deposited per fission : 199.27 MeV + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has delayed neutron data in 8 precursor groups + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has NFY data + - Nuclide has no SFY data + + - 25 reaction channels + - 2 special reactions + - 4 transmutation reactions + - 2 transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 25 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.75369E+00 MeV Emin = 5.77860E+00 MeV frac = 1.00000E+00 Product nuclide = 92232.82c : (n,2n) + 3 MT = 17 Q = -1.30080E+01 MeV Emin = 1.30645E+01 MeV frac = 1.00000E+00 Product nuclide = 922310 : (n,3n) + 4 MT = 18 Q = 1.90850E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : total fission + 5 MT = 51 Q = -4.03999E-02 MeV Emin = 4.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -9.21999E-02 MeV Emin = 9.25000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -1.55100E-01 MeV Emin = 1.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -2.28000E-01 MeV Emin = 2.26993E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -2.98800E-01 MeV Emin = 3.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -3.11900E-01 MeV Emin = 3.10000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -3.18000E-01 MeV Emin = 3.17079E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -3.20000E-01 MeV Emin = 3.20692E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -3.20800E-01 MeV Emin = 3.21938E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -3.40500E-01 MeV Emin = 3.40000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -3.53700E-01 MeV Emin = 3.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -3.96999E-01 MeV Emin = 3.90000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 63 Q = -3.98499E-01 MeV Emin = 4.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 18 MT = 64 Q = -4.15799E-01 MeV Emin = 4.13800E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 19 MT = 65 Q = -4.24999E-01 MeV Emin = 4.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 20 MT = 66 Q = -5.03899E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 21 MT = 67 Q = -5.46699E-01 MeV Emin = 5.40000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 22 MT = 68 Q = -5.59999E-01 MeV Emin = 5.60000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 23 MT = 69 Q = -5.97099E-01 MeV Emin = 5.90000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 24 MT = 91 Q = -5.99999E-01 MeV Emin = 6.01298E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 25 MT = 102 Q = 6.84380E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 92234.82c : (n,gamma) + + 2 additional transport branches: + + 1 MT = 18 Q = 1.90850E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 1.40000E+01 MeV) : total fission + 2 MT = 18 Q = 1.90850E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 4.00000E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 4 Q = 4.90890E+00 MeV frac = 1.00000E+00 Product nuclide = 90229.82c : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 4.90890E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 279 / 1657 : 92234.82c -- uranium 234 (U-234) + + Pointers : 2594414 35657 + Primary type : Transport + Nuclide ZAI : 922340 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/U234.ACE + Atomic weight (AW) : 234.04053 + Atomic weight ratio (AWR) : 232.03000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 7.75E+12 seconds (245,868 years) + Specific ingestion toxicity : 4.90E-08 Sv/Bq + Specific inhalation toxicity : 9.40E-06 Sv/Bq + Energy deposited per fission : 198.70 MeV + Spontaneous fission nubar : 1.80000 + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has delayed neutron data in 8 precursor groups + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has NFY data + - Nuclide has no SFY data + + - 45 reaction channels + - 2 special reactions + - 7 transmutation reactions + - 1 transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 45 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.84320E+00 MeV Emin = 6.87269E+00 MeV frac = 1.00000E+00 Product nuclide = 92233.82c : (n,2n) + 3 MT = 17 Q = -1.25872E+01 MeV Emin = 1.26415E+01 MeV frac = 1.00000E+00 Product nuclide = 92232.82c : (n,3n) + 4 MT = 19 Q = 1.90300E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : (n,f) + 5 MT = 20 Q = 1.90300E+02 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : (n,nf) + 6 MT = 21 Q = 1.90300E+02 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : (n,2nf) + 7 MT = 38 Q = 1.90300E+02 MeV Emin = 1.60000E+01 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : (n,3nf) + 8 MT = 51 Q = -4.34980E-02 MeV Emin = 4.25000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 9 MT = 52 Q = -1.43350E-01 MeV Emin = 1.41982E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 10 MT = 53 Q = -2.96070E-01 MeV Emin = 2.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 11 MT = 54 Q = -4.97040E-01 MeV Emin = 4.99164E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 12 MT = 55 Q = -7.41200E-01 MeV Emin = 8.13370E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 13 MT = 56 Q = -7.86290E-01 MeV Emin = 7.44368E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 14 MT = 57 Q = -8.09880E-01 MeV Emin = 8.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 15 MT = 58 Q = -8.49300E-01 MeV Emin = 8.33150E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 16 MT = 59 Q = -8.51700E-01 MeV Emin = 8.54150E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 17 MT = 60 Q = -9.26740E-01 MeV Emin = 9.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 18 MT = 61 Q = -9.47850E-01 MeV Emin = 9.41318E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 19 MT = 62 Q = -9.62600E-01 MeV Emin = 9.59325E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 20 MT = 63 Q = -9.68600E-01 MeV Emin = 9.69744E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 21 MT = 64 Q = -9.89450E-01 MeV Emin = 9.83226E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 22 MT = 65 Q = -1.02370E+00 MeV Emin = 1.01404E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 23 MT = 66 Q = -1.02380E+00 MeV Emin = 1.30556E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 24 MT = 67 Q = -1.02383E+00 MeV Emin = 1.02807E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 25 MT = 68 Q = -1.04450E+00 MeV Emin = 1.03862E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 26 MT = 69 Q = -1.06930E+00 MeV Emin = 1.06144E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 27 MT = 70 Q = -1.08530E+00 MeV Emin = 1.08193E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 28 MT = 71 Q = -1.09090E+00 MeV Emin = 1.09277E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 29 MT = 72 Q = -1.09590E+00 MeV Emin = 1.09809E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 30 MT = 73 Q = -1.12520E+00 MeV Emin = 1.11533E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 31 MT = 74 Q = -1.12670E+00 MeV Emin = 1.13077E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 32 MT = 75 Q = -1.12760E+00 MeV Emin = 1.13222E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 33 MT = 76 Q = -1.15000E+00 MeV Emin = 1.14369E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 34 MT = 77 Q = -1.16520E+00 MeV Emin = 1.16257E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 27. excited state + 35 MT = 78 Q = -1.17210E+00 MeV Emin = 1.17367E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 28. excited state + 36 MT = 79 Q = -1.17420E+00 MeV Emin = 1.17819E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 29. excited state + 37 MT = 80 Q = -1.19470E+00 MeV Emin = 1.18955E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 30. excited state + 38 MT = 81 Q = -1.21460E+00 MeV Emin = 1.20989E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 31. excited state + 39 MT = 82 Q = -1.23720E+00 MeV Emin = 1.23118E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 32. excited state + 40 MT = 83 Q = -1.26180E+00 MeV Emin = 1.25488E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 33. excited state + 41 MT = 84 Q = -1.27440E+00 MeV Emin = 1.27353E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 34. excited state + 42 MT = 85 Q = -1.27750E+00 MeV Emin = 1.28142E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 35. excited state + 43 MT = 86 Q = -1.29260E+00 MeV Emin = 1.29056E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 36. excited state + 44 MT = 91 Q = -1.30000E+00 MeV Emin = 1.30187E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 45 MT = 102 Q = 5.29790E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 92235.82c : (n,gamma) + + 1 additional transport branch: + + 1 MT = 102 Q = 5.29790E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 922351 : (n,gamma) + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 4.25000E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 4 Q = 4.85790E+00 MeV frac = 1.00000E+00 Product nuclide = 90230.82c : alpha + 2 RTYP = 6 Q = 1.76100E+02 MeV frac = 1.70000E-11 SF without yield : spontaneous fission + + 1 additional decay branch: + + 1 RTYP = 4 Q = 4.85790E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 280 / 1657 : 92235.82c -- uranium 235 (U-235) + + Pointers : 2606584 35703 + Primary type : Transport + Nuclide ZAI : 922350 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/U235.ACE + Atomic weight (AW) : 235.04415 + Atomic weight ratio (AWR) : 233.02500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.22E+16 seconds (704 million years) + Specific ingestion toxicity : 4.70E-08 Sv/Bq + Specific inhalation toxicity : 8.50E-06 Sv/Bq + Energy deposited per fission : 202.27 MeV + Spontaneous fission nubar : 1.87000 + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has delayed neutron data in 8 precursor groups + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has NFY data + - Nuclide has no SFY data + + - 41 reaction channels + - 2 special reactions + - 5 transmutation reactions + - 2 transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 41 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.29778E+00 MeV Emin = 5.32052E+00 MeV frac = 1.00000E+00 Product nuclide = 92234.82c : (n,2n) + 3 MT = 17 Q = -1.21423E+01 MeV Emin = 1.21944E+01 MeV frac = 1.00000E+00 Product nuclide = 92233.82c : (n,3n) + 4 MT = 18 Q = 1.93720E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : total fission + 5 MT = 37 Q = -1.78856E+01 MeV Emin = 1.79624E+01 MeV frac = 1.00000E+00 Product nuclide = 92232.82c : (n,4n) + 6 MT = 51 Q = -7.68000E-05 MeV Emin = 2.24303E-03 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.30400E-02 MeV Emin = 1.28000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -4.62000E-02 MeV Emin = 4.60000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -5.17010E-02 MeV Emin = 5.15000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -8.17000E-02 MeV Emin = 8.20000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -1.03000E-01 MeV Emin = 1.01717E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -1.29300E-01 MeV Emin = 1.20000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -1.50500E-01 MeV Emin = 1.50630E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -1.70700E-01 MeV Emin = 1.70000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -1.71400E-01 MeV Emin = 1.71718E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -1.97100E-01 MeV Emin = 1.97827E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -2.25400E-01 MeV Emin = 2.25945E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -2.49100E-01 MeV Emin = 2.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -2.91400E-01 MeV Emin = 2.80000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -2.94700E-01 MeV Emin = 2.94305E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 21 MT = 66 Q = -3.32800E-01 MeV Emin = 3.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 22 MT = 67 Q = -3.38500E-01 MeV Emin = 3.37175E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 23 MT = 68 Q = -3.57300E-01 MeV Emin = 3.54111E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 24 MT = 69 Q = -3.67100E-01 MeV Emin = 3.68541E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 25 MT = 70 Q = -3.93200E-01 MeV Emin = 3.81785E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 26 MT = 71 Q = -4.14800E-01 MeV Emin = 4.15739E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 27 MT = 72 Q = -4.26700E-01 MeV Emin = 4.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 28 MT = 73 Q = -4.30000E-01 MeV Emin = 4.30317E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 29 MT = 74 Q = -4.38500E-01 MeV Emin = 4.36113E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 30 MT = 75 Q = -4.45700E-01 MeV Emin = 4.43996E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 31 MT = 76 Q = -4.74300E-01 MeV Emin = 4.75991E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 32 MT = 77 Q = -5.50000E-01 MeV Emin = 5.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 27. excited state + 33 MT = 78 Q = -6.50000E-01 MeV Emin = 6.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 28. excited state + 34 MT = 79 Q = -7.70000E-01 MeV Emin = 7.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 29. excited state + 35 MT = 80 Q = -9.00000E-01 MeV Emin = 9.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 30. excited state + 36 MT = 81 Q = -1.04000E+00 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 31. excited state + 37 MT = 82 Q = -1.08500E+00 MeV Emin = 1.06708E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 32. excited state + 38 MT = 83 Q = -1.33000E+00 MeV Emin = 1.30000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 33. excited state + 39 MT = 84 Q = -1.43000E+00 MeV Emin = 1.40000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 34. excited state + 40 MT = 91 Q = -4.97864E-01 MeV Emin = 4.88170E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 41 MT = 102 Q = 6.54520E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 92236.82c : (n,gamma) + + 2 additional transport branches: + + 1 MT = 18 Q = 1.93720E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 1.40000E+01 MeV) : total fission + 2 MT = 18 Q = 1.93720E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 2.24303E-03 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 4 Q = 4.67870E+00 MeV frac = 1.00000E+00 Product nuclide = 902310 : alpha + 2 RTYP = 6 Q = 1.76400E+02 MeV frac = 7.20000E-11 SF without yield : spontaneous fission + + 1 additional decay branch: + + 1 RTYP = 4 Q = 4.67870E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 281 / 1657 : 92236.82c -- uranium 236 (U-236) + + Pointers : 2639462 35749 + Primary type : Transport + Nuclide ZAI : 922360 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/U236.ACE + Atomic weight (AW) : 236.04556 + Atomic weight ratio (AWR) : 234.01780 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 3.00000E+01 + Half-life : 7.48E+14 seconds (23.7 million years) + Specific ingestion toxicity : 4.70E-08 Sv/Bq + Specific inhalation toxicity : 8.70E-06 Sv/Bq + Energy deposited per fission : 206.68 MeV + Spontaneous fission nubar : 1.90000 + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has delayed neutron data in 8 precursor groups + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has NFY data + - Nuclide has no SFY data + + - 38 reaction channels + - 2 special reactions + - 5 transmutation reactions + - 1 transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 38 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.54520E+00 MeV Emin = 6.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 92235.82c : (n,2n) + 3 MT = 17 Q = -1.18430E+01 MeV Emin = 1.20000E+01 MeV frac = 1.00000E+00 Product nuclide = 92234.82c : (n,3n) + 4 MT = 18 Q = 1.97939E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : total fission + 5 MT = 37 Q = -1.86874E+01 MeV Emin = 1.90000E+01 MeV frac = 1.00000E+00 Product nuclide = 92233.82c : (n,4n) + 6 MT = 51 Q = -4.52420E-02 MeV Emin = 4.51800E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.49476E-01 MeV Emin = 1.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -3.09784E-01 MeV Emin = 3.10000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -5.22240E-01 MeV Emin = 5.20000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -6.87600E-01 MeV Emin = 6.90000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -7.44150E-01 MeV Emin = 7.40000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -7.82300E-01 MeV Emin = 7.90000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -8.48300E-01 MeV Emin = 8.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -9.19210E-01 MeV Emin = 9.20000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -9.57990E-01 MeV Emin = 9.60000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -9.60300E-01 MeV Emin = 9.63244E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -9.66630E-01 MeV Emin = 9.70000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -9.87670E-01 MeV Emin = 9.90000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -9.99800E-01 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -1.00150E+00 MeV Emin = 1.00493E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 21 MT = 66 Q = -1.03560E+00 MeV Emin = 1.02290E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 22 MT = 67 Q = -1.05085E+00 MeV Emin = 1.04768E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 23 MT = 68 Q = -1.05289E+00 MeV Emin = 1.05688E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 24 MT = 69 Q = -1.05861E+00 MeV Emin = 1.06026E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 25 MT = 70 Q = -1.06610E+00 MeV Emin = 1.06690E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 26 MT = 71 Q = -1.07000E+00 MeV Emin = 1.07262E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 27 MT = 72 Q = -1.08530E+00 MeV Emin = 1.09924E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 28 MT = 73 Q = -1.09380E+00 MeV Emin = 1.09250E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 29 MT = 74 Q = -1.10440E+00 MeV Emin = 1.10456E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 30 MT = 75 Q = -1.11067E+00 MeV Emin = 1.11227E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 31 MT = 76 Q = -1.12690E+00 MeV Emin = 1.12357E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 32 MT = 77 Q = -1.14700E+00 MeV Emin = 1.14181E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 27. excited state + 33 MT = 78 Q = -1.14940E+00 MeV Emin = 1.15311E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 28. excited state + 34 MT = 79 Q = -1.16400E+00 MeV Emin = 1.16164E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 29. excited state + 35 MT = 80 Q = -1.17180E+00 MeV Emin = 1.17289E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 30. excited state + 36 MT = 81 Q = -1.19860E+00 MeV Emin = 1.20000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 31. excited state + 37 MT = 91 Q = -1.20000E+00 MeV Emin = 1.20443E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 38 MT = 102 Q = 5.12580E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 92237.82c : (n,gamma) + + 1 additional transport branch: + + 1 MT = 18 Q = 1.97939E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 4.51800E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 4 Q = 4.57200E+00 MeV frac = 1.00000E+00 Product nuclide = 902320 : alpha + 2 RTYP = 6 Q = 1.75600E+02 MeV frac = 9.00000E-10 SF without yield : spontaneous fission + + 1 additional decay branch: + + 1 RTYP = 4 Q = 4.57200E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 282 / 1657 : 92237.82c -- uranium 237 (U-237) + + Pointers : 2657840 35795 + Primary type : Transport + Nuclide ZAI : 922370 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/U237.ACE + Atomic weight (AW) : 237.04878 + Atomic weight ratio (AWR) : 235.01240 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 3.00000E+01 + Half-life : 5.83E+05 seconds (6.75 days) + Specific ingestion toxicity : 7.60E-10 Sv/Bq + Specific inhalation toxicity : 1.90E-09 Sv/Bq + Energy deposited per fission : 208.83 MeV + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has delayed neutron data in 8 precursor groups + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide is using NFY data from Np-238 + - Nuclide has no SFY data + + - 41 reaction channels + - 2 special reactions + - 5 transmutation reactions + - 1 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 41 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.12580E+00 MeV Emin = 5.20000E+00 MeV frac = 1.00000E+00 Product nuclide = 92236.82c : (n,2n) + 3 MT = 17 Q = -1.16710E+01 MeV Emin = 1.18000E+01 MeV frac = 1.00000E+00 Product nuclide = 92235.82c : (n,3n) + 4 MT = 18 Q = 2.00000E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : total fission + 5 MT = 37 Q = -1.69687E+01 MeV Emin = 1.70409E+01 MeV frac = 1.00000E+00 Product nuclide = 92234.82c : (n,4n) + 6 MT = 51 Q = -1.13900E-02 MeV Emin = 1.07192E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -5.63000E-02 MeV Emin = 5.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -8.28600E-02 MeV Emin = 8.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -1.59960E-01 MeV Emin = 1.60000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -1.63000E-01 MeV Emin = 1.62167E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -2.04190E-01 MeV Emin = 2.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -2.05000E-01 MeV Emin = 2.05669E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -2.60950E-01 MeV Emin = 2.60000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -2.74000E-01 MeV Emin = 2.70000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -3.16000E-01 MeV Emin = 3.10000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -3.27000E-01 MeV Emin = 3.24196E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -3.67000E-01 MeV Emin = 3.60000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -4.26150E-01 MeV Emin = 4.20000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -4.32000E-01 MeV Emin = 4.30000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -4.82000E-01 MeV Emin = 4.80000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 21 MT = 66 Q = -4.84000E-01 MeV Emin = 4.85055E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 22 MT = 67 Q = -5.06000E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 23 MT = 68 Q = -5.30000E-01 MeV Emin = 5.30000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 24 MT = 69 Q = -5.40620E-01 MeV Emin = 5.40000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 25 MT = 70 Q = -5.45000E-01 MeV Emin = 5.45120E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 26 MT = 71 Q = -5.51000E-01 MeV Emin = 5.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 27 MT = 72 Q = -5.54980E-01 MeV Emin = 5.55343E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 28 MT = 73 Q = -5.75000E-01 MeV Emin = 5.80000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 29 MT = 74 Q = -5.78010E-01 MeV Emin = 5.80000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 30 MT = 75 Q = -6.32000E-01 MeV Emin = 6.30000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 31 MT = 76 Q = -6.57000E-01 MeV Emin = 6.60000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 32 MT = 77 Q = -6.64270E-01 MeV Emin = 6.63548E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 27. excited state + 33 MT = 78 Q = -6.66450E-01 MeV Emin = 6.68191E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 28. excited state + 34 MT = 79 Q = -6.77590E-01 MeV Emin = 6.80000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 29. excited state + 35 MT = 80 Q = -6.88000E-01 MeV Emin = 6.90000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 30. excited state + 36 MT = 81 Q = -6.97650E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 31. excited state + 37 MT = 82 Q = -6.98000E-01 MeV Emin = 7.00882E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 32. excited state + 38 MT = 83 Q = -7.18000E-01 MeV Emin = 7.49375E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 33. excited state + 39 MT = 84 Q = -7.20450E-01 MeV Emin = 7.21055E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 34. excited state + 40 MT = 91 Q = -7.21450E-01 MeV Emin = 7.27260E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 41 MT = 102 Q = 6.15280E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 92238.82c : (n,gamma) + + 1 additional transport branch: + + 1 MT = 18 Q = 2.00000E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 1.07192E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.18600E-01 MeV frac = 1.00000E+00 Product nuclide = 93237.82c : beta- + + Nuclide 283 / 1657 : 92238.82c -- uranium 238 (U-238) + + Pointers : 2680079 35841 + Primary type : Transport + Nuclide ZAI : 922380 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/U238.ACE + Atomic weight (AW) : 238.05078 + Atomic weight ratio (AWR) : 236.00580 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 3.00000E+01 + Half-life : 1.41E+17 seconds (4.47 billion years) + Specific ingestion toxicity : 4.50E-08 Sv/Bq + Specific inhalation toxicity : 8.00E-06 Sv/Bq + Energy deposited per fission : 206.02 MeV + Spontaneous fission nubar : 2.00000 + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has delayed neutron data in 8 precursor groups + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has NFY data + - Nuclide has no SFY data + + - 47 reaction channels + - 2 special reactions + - 5 transmutation reactions + - 1 transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 47 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.15280E+00 MeV Emin = 6.20000E+00 MeV frac = 1.00000E+00 Product nuclide = 92237.82c : (n,2n) + 3 MT = 17 Q = -1.12786E+01 MeV Emin = 1.14000E+01 MeV frac = 1.00000E+00 Product nuclide = 92236.82c : (n,3n) + 4 MT = 18 Q = 1.97314E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + 5 MT = 37 Q = -1.78237E+01 MeV Emin = 1.80000E+01 MeV frac = 1.00000E+00 Product nuclide = 92235.82c : (n,4n) + 6 MT = 51 Q = -4.49100E-02 MeV Emin = 4.50000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.48410E-01 MeV Emin = 1.40000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -3.07200E-01 MeV Emin = 2.99251E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -5.17800E-01 MeV Emin = 5.10000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -6.80100E-01 MeV Emin = 6.80000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -7.31900E-01 MeV Emin = 7.30000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -7.75700E-01 MeV Emin = 7.70000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -8.26700E-01 MeV Emin = 8.30000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -9.27200E-01 MeV Emin = 9.30000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -9.30500E-01 MeV Emin = 9.32786E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -9.49900E-01 MeV Emin = 9.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -9.66300E-01 MeV Emin = 9.70000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -9.67300E-01 MeV Emin = 9.70395E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -9.93000E-01 MeV Emin = 9.90000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -9.97500E-01 MeV Emin = 1.00000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 21 MT = 66 Q = -1.03730E+00 MeV Emin = 1.02171E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 22 MT = 67 Q = -1.05500E+00 MeV Emin = 1.05058E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 23 MT = 68 Q = -1.05950E+00 MeV Emin = 1.06173E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 24 MT = 69 Q = -1.06020E+00 MeV Emin = 1.06452E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 25 MT = 70 Q = -1.07650E+00 MeV Emin = 1.07288E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 26 MT = 71 Q = -1.10560E+00 MeV Emin = 1.10000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 27 MT = 72 Q = -1.10700E+00 MeV Emin = 1.11152E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 28 MT = 73 Q = -1.12700E+00 MeV Emin = 1.12173E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 29 MT = 74 Q = -1.12830E+00 MeV Emin = 1.13292E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 30 MT = 75 Q = -1.15030E+00 MeV Emin = 1.14413E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 31 MT = 76 Q = -1.16750E+00 MeV Emin = 1.16381E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 32 MT = 77 Q = -1.16890E+00 MeV Emin = 1.17368E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 27. excited state + 33 MT = 78 Q = -1.20900E+00 MeV Emin = 1.20000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 28. excited state + 34 MT = 79 Q = -1.25000E+00 MeV Emin = 1.23521E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 29. excited state + 35 MT = 80 Q = -1.44000E+00 MeV Emin = 1.40000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 30. excited state + 36 MT = 81 Q = -1.75000E+00 MeV Emin = 1.70000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 31. excited state + 37 MT = 82 Q = -1.95000E+00 MeV Emin = 1.90000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 32. excited state + 38 MT = 83 Q = -2.15000E+00 MeV Emin = 2.15911E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 33. excited state + 39 MT = 84 Q = -2.30000E+00 MeV Emin = 2.30975E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 34. excited state + 40 MT = 85 Q = -2.49280E+00 MeV Emin = 2.50336E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 35. excited state + 41 MT = 86 Q = -2.94000E+00 MeV Emin = 2.95246E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 36. excited state + 42 MT = 87 Q = -3.18900E+00 MeV Emin = 3.20251E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 37. excited state + 43 MT = 88 Q = -3.38800E+00 MeV Emin = 3.40236E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 38. excited state + 44 MT = 89 Q = -3.53800E+00 MeV Emin = 3.55299E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 39. excited state + 45 MT = 90 Q = -3.73700E+00 MeV Emin = 3.75284E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 40. excited state + 46 MT = 91 Q = -1.21000E+00 MeV Emin = 1.27765E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 47 MT = 102 Q = 4.80650E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 922390 : (n,gamma) + + 1 additional transport branch: + + 1 MT = 18 Q = 1.97314E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 1.40000E+01 MeV) : total fission + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 4.50000E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 4 Q = 4.27000E+00 MeV frac = 9.99999E-01 Product nuclide = 902340 : alpha + 2 RTYP = 6 Q = 1.73600E+02 MeV frac = 5.46000E-07 SF without yield : spontaneous fission + + 1 additional decay branch: + + 1 RTYP = 4 Q = 4.27000E+00 MeV frac = 9.99999E-01 Product nuclide = 2004.82c : alpha + + Nuclide 284 / 1657 : 93235.82c -- neptunium 235 (Np-235) + + Pointers : 2709992 29125 + Primary type : Transport + Nuclide ZAI : 932350 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Np235.ACE + Atomic weight (AW) : 235.04415 + Atomic weight ratio (AWR) : 233.02500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 3.42E+07 seconds (1.08 years) + Specific ingestion toxicity : 5.30E-11 Sv/Bq + Specific inhalation toxicity : 6.30E-10 Sv/Bq + Energy deposited per fission : 208.83 MeV + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide is using NFY data from Th-232 + - Nuclide has no SFY data + + - 22 reaction channels + - 2 special reactions + - 4 transmutation reactions + - 2 transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 22 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.98340E+00 MeV Emin = 7.01337E+00 MeV frac = 1.00000E+00 Product nuclide = 932340 : (n,2n) + 3 MT = 17 Q = -1.31047E+01 MeV Emin = 1.31609E+01 MeV frac = 1.00000E+00 Product nuclide = 932330 : (n,3n) + 4 MT = 18 Q = 2.00000E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + 5 MT = 51 Q = -3.42300E-02 MeV Emin = 3.21885E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -4.91000E-02 MeV Emin = 4.69830E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -7.91000E-02 MeV Emin = 7.57595E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -9.16000E-02 MeV Emin = 9.04940E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -1.33000E-01 MeV Emin = 1.29375E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -1.46800E-01 MeV Emin = 1.44182E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -2.00000E-01 MeV Emin = 2.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -3.52000E-01 MeV Emin = 3.51229E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -3.71000E-01 MeV Emin = 3.67822E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -4.08000E-01 MeV Emin = 4.09552E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -4.41000E-01 MeV Emin = 4.35643E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -5.20000E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 63 Q = -5.65000E-01 MeV Emin = 5.56127E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 18 MT = 64 Q = -6.02000E-01 MeV Emin = 5.95294E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 19 MT = 65 Q = -6.44000E-01 MeV Emin = 6.36219E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 20 MT = 66 Q = -7.00000E-01 MeV Emin = 7.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 21 MT = 91 Q = -7.50000E-01 MeV Emin = 7.42235E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 22 MT = 102 Q = 5.73943E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 93236.82c : (n,gamma) + + 2 additional transport branches: + + 1 MT = 18 Q = 2.00000E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 1.40000E+01 MeV) : total fission + 2 MT = 102 Q = 5.73943E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 932361 : (n,gamma) + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 3.21885E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 2 Q = 1.23700E-01 MeV frac = 9.99985E-01 Product nuclide = 92235.82c : EC/beta+ + 2 RTYP = 4 Q = 5.19140E+00 MeV frac = 1.40000E-05 Product nuclide = 91231.82c : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.19140E+00 MeV frac = 1.40000E-05 Product nuclide = 2004.82c : alpha + + Nuclide 285 / 1657 : 93236.82c -- neptunium 236 (Np-236) + + Pointers : 2727748 29171 + Primary type : Transport + Nuclide ZAI : 932360 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Np236.ACE + Atomic weight (AW) : 236.04677 + Atomic weight ratio (AWR) : 234.01900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 4.89E+12 seconds (155,103 years) + Specific ingestion toxicity : 1.70E-08 Sv/Bq + Specific inhalation toxicity : 8.00E-06 Sv/Bq + Energy deposited per fission : 208.83 MeV + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide is using NFY data from U-235 + - Nuclide has no SFY data + + - 10 reaction channels + - 2 special reactions + - 4 transmutation reactions + - 2 transmutation branch reactions + - 3 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 10 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.72979E+00 MeV Emin = 5.75428E+00 MeV frac = 1.00000E+00 Product nuclide = 93235.82c : (n,2n) + 3 MT = 17 Q = -1.27090E+01 MeV Emin = 1.27633E+01 MeV frac = 1.00000E+00 Product nuclide = 932340 : (n,3n) + 4 MT = 18 Q = 1.99999E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : total fission + 5 MT = 51 Q = -5.99999E-02 MeV Emin = 5.51282E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -2.31000E-01 MeV Emin = 2.15994E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -2.73000E-01 MeV Emin = 2.62084E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -3.24000E-01 MeV Emin = 3.19039E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 91 Q = -3.69999E-01 MeV Emin = 3.71154E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 10 MT = 102 Q = 6.57335E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 93237.82c : (n,gamma) + + 2 additional transport branches: + + 1 MT = 18 Q = 1.99999E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 1.40000E+01 MeV) : total fission + 2 MT = 18 Q = 1.99999E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 5.51282E-02 MeV : total inelastic scattering + + 3 decay reactions: + + 1 RTYP = 2 Q = 9.30000E-01 MeV frac = 8.78000E-01 Product nuclide = 92236.82c : EC/beta+ + 2 RTYP = 4 Q = 5.01000E+00 MeV frac = 1.60000E-03 Product nuclide = 91232.82c : alpha + 3 RTYP = 1 Q = 4.80000E-01 MeV frac = 1.20000E-01 Product nuclide = 94236.82c : beta- + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.01000E+00 MeV frac = 1.60000E-03 Product nuclide = 2004.82c : alpha + + Nuclide 286 / 1657 : 93237.82c -- neptunium 237 (Np-237) + + Pointers : 2756600 29217 + Primary type : Transport + Nuclide ZAI : 932370 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Np237.ACE + Atomic weight (AW) : 237.04817 + Atomic weight ratio (AWR) : 235.01180 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 6.77E+13 seconds (2.15 million years) + Specific ingestion toxicity : 1.10E-07 Sv/Bq + Specific inhalation toxicity : 5.00E-05 Sv/Bq + Energy deposited per fission : 205.04 MeV + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has delayed neutron data in 8 precursor groups + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has NFY data + - Nuclide has no SFY data + + - 37 reaction channels + - 2 special reactions + - 4 transmutation reactions + - 1 transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 37 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.64600E+00 MeV Emin = 6.67428E+00 MeV frac = 1.00000E+00 Product nuclide = 93236.82c : (n,2n) + 3 MT = 17 Q = -1.23630E+01 MeV Emin = 1.24156E+01 MeV frac = 1.00000E+00 Product nuclide = 93235.82c : (n,3n) + 4 MT = 18 Q = 1.96370E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : total fission + 5 MT = 51 Q = -3.31920E-02 MeV Emin = 3.25000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -5.95370E-02 MeV Emin = 5.97500E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -7.58900E-02 MeV Emin = 7.61200E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -1.02960E-01 MeV Emin = 1.02500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -1.30000E-01 MeV Emin = 1.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -1.58510E-01 MeV Emin = 1.58700E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -1.91500E-01 MeV Emin = 1.80000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -2.25960E-01 MeV Emin = 2.20000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -2.67540E-01 MeV Emin = 2.60000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -2.69900E-01 MeV Emin = 2.70888E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -2.81350E-01 MeV Emin = 2.82200E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -3.05060E-01 MeV Emin = 3.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 63 Q = -3.16800E-01 MeV Emin = 3.12255E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 18 MT = 64 Q = -3.24420E-01 MeV Emin = 3.25400E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 19 MT = 65 Q = -3.32360E-01 MeV Emin = 3.33400E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 20 MT = 66 Q = -3.48500E-01 MeV Emin = 3.40000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 21 MT = 67 Q = -3.59700E-01 MeV Emin = 3.60000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 22 MT = 68 Q = -3.68590E-01 MeV Emin = 3.65830E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 23 MT = 69 Q = -3.70930E-01 MeV Emin = 3.71555E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 24 MT = 70 Q = -3.95520E-01 MeV Emin = 3.80000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 25 MT = 71 Q = -4.34120E-01 MeV Emin = 4.35800E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 26 MT = 72 Q = -4.52530E-01 MeV Emin = 4.53900E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 27 MT = 73 Q = -4.54400E-01 MeV Emin = 4.55395E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 28 MT = 74 Q = -4.59680E-01 MeV Emin = 4.60000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 29 MT = 75 Q = -4.86000E-01 MeV Emin = 4.87100E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 30 MT = 76 Q = -4.97000E-01 MeV Emin = 4.95000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 31 MT = 77 Q = -5.14200E-01 MeV Emin = 5.16200E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 27. excited state + 32 MT = 78 Q = -5.45600E-01 MeV Emin = 5.47300E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 28. excited state + 33 MT = 79 Q = -5.46900E-01 MeV Emin = 5.48576E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 29. excited state + 34 MT = 80 Q = -9.84000E-01 MeV Emin = 9.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 30. excited state + 35 MT = 81 Q = -1.01300E+00 MeV Emin = 1.00866E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 31. excited state + 36 MT = 91 Q = -5.46900E-01 MeV Emin = 5.48576E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 37 MT = 102 Q = 5.48200E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 93238.82c : (n,gamma) + + 1 additional transport branch: + + 1 MT = 18 Q = 1.96370E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 3.25000E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 4 Q = 4.95830E+00 MeV frac = 1.00000E+00 Product nuclide = 91233.82c : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 4.95830E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 287 / 1657 : 93238.82c -- neptunium 238 (Np-238) + + Pointers : 2779342 29263 + Primary type : Transport + Nuclide ZAI : 932380 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Np238.ACE + Atomic weight (AW) : 238.05098 + Atomic weight ratio (AWR) : 236.00600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.82E+05 seconds (2.1 days) + Specific ingestion toxicity : 9.10E-10 Sv/Bq + Specific inhalation toxicity : 3.50E-09 Sv/Bq + Energy deposited per fission : 208.83 MeV + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has delayed neutron data in 8 precursor groups + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has NFY data + - Nuclide has no SFY data + + - 6 reaction channels + - 2 special reactions + - 4 transmutation reactions + - 1 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 6 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.48800E+00 MeV Emin = 5.51200E+00 MeV frac = 1.00000E+00 Product nuclide = 93237.82c : (n,2n) + 3 MT = 17 Q = -1.21160E+01 MeV Emin = 1.21674E+01 MeV frac = 1.00000E+00 Product nuclide = 93236.82c : (n,3n) + 4 MT = 18 Q = 2.00000E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : total fission + 5 MT = 91 Q = -3.48520E-02 MeV Emin = 3.37500E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 6 MT = 102 Q = 6.22700E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 93239.82c : (n,gamma) + + 1 additional transport branch: + + 1 MT = 18 Q = 2.00000E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 3.37500E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.29150E+00 MeV frac = 1.00000E+00 Product nuclide = 94238.82c : beta- + + Nuclide 288 / 1657 : 93239.82c -- neptunium 239 (Np-239) + + Pointers : 2799334 29309 + Primary type : Transport + Nuclide ZAI : 932390 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Np239.ACE + Atomic weight (AW) : 239.05259 + Atomic weight ratio (AWR) : 236.99900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.04E+05 seconds (2.36 days) + Specific ingestion toxicity : 8.00E-10 Sv/Bq + Specific inhalation toxicity : 1.00E-09 Sv/Bq + Energy deposited per fission : 198.39 MeV + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide is using NFY data from U-238 + - Nuclide has no SFY data + + - 14 reaction channels + - 2 special reactions + - 4 transmutation reactions + - 2 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 14 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.22702E+00 MeV Emin = 6.25330E+00 MeV frac = 1.00000E+00 Product nuclide = 93238.82c : (n,2n) + 3 MT = 17 Q = -1.17056E+01 MeV Emin = 1.17550E+01 MeV frac = 1.00000E+00 Product nuclide = 93237.82c : (n,3n) + 4 MT = 18 Q = 1.90000E+02 MeV Emin = 2.87500E-02 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + 5 MT = 51 Q = -3.11400E-02 MeV Emin = 3.06250E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -7.11200E-02 MeV Emin = 7.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -7.46700E-02 MeV Emin = 7.40976E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -1.17659E-01 MeV Emin = 1.13617E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -1.23000E-01 MeV Emin = 1.23438E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -1.73050E-01 MeV Emin = 1.67835E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -2.41400E-01 MeV Emin = 2.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -3.20000E-01 MeV Emin = 3.10675E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 91 Q = -4.30000E-01 MeV Emin = 4.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 14 MT = 102 Q = 5.16810E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 932400 : (n,gamma) + + 2 additional transport branches: + + 1 MT = 18 Q = 1.90000E+02 MeV Emin = 2.87500E-02 MeV frac = 1.00000E+00 NFY (E = 1.40000E+01 MeV) : total fission + 2 MT = 102 Q = 5.16810E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 932401 : (n,gamma) + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 3.06250E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.22500E-01 MeV frac = 1.00000E+00 Product nuclide = 94239.82c : beta- + + Nuclide 289 / 1657 : 94236.82c -- plutonium 236 (Pu-236) + + Pointers : 2823662 30597 + Primary type : Transport + Nuclide ZAI : 942360 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Pu236.ACE + Atomic weight (AW) : 236.04576 + Atomic weight ratio (AWR) : 234.01800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 9.02E+07 seconds (2.86 years) + Specific ingestion toxicity : 8.70E-08 Sv/Bq + Specific inhalation toxicity : 4.00E-05 Sv/Bq + Energy deposited per fission : 211.56 MeV + Spontaneous fission nubar : 2.12000 + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide is using NFY data from Th-232 + - Nuclide has no SFY data + + - 10 reaction channels + - 2 special reactions + - 4 transmutation reactions + - 2 transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 10 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.35725E+00 MeV Emin = 7.38869E+00 MeV frac = 1.00000E+00 Product nuclide = 942350 : (n,2n) + 3 MT = 17 Q = -1.35872E+01 MeV Emin = 1.36453E+01 MeV frac = 1.00000E+00 Product nuclide = 942340 : (n,3n) + 4 MT = 18 Q = 2.02618E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + 5 MT = 51 Q = -4.46300E-02 MeV Emin = 4.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -1.47450E-01 MeV Emin = 1.36060E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -3.05800E-01 MeV Emin = 3.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -5.15700E-01 MeV Emin = 5.17304E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 91 Q = -6.40000E-01 MeV Emin = 6.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 10 MT = 102 Q = 5.87702E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 94237.82c : (n,gamma) + + 2 additional transport branches: + + 1 MT = 18 Q = 2.02618E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 1.40000E+01 MeV) : total fission + 2 MT = 102 Q = 5.87702E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 942371 : (n,gamma) + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 4.00000E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 4 Q = 5.86707E+00 MeV frac = 1.00000E+00 Product nuclide = 92232.82c : alpha + 2 RTYP = 6 Q = 1.85300E+02 MeV frac = 8.20000E-10 SF without yield : spontaneous fission + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.86707E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 290 / 1657 : 94237.82c -- plutonium 237 (Pu-237) + + Pointers : 2842045 30643 + Primary type : Transport + Nuclide ZAI : 942370 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Pu237.ACE + Atomic weight (AW) : 237.04837 + Atomic weight ratio (AWR) : 235.01200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 3.91E+06 seconds (45.3 days) + Specific ingestion toxicity : 1.00E-10 Sv/Bq + Specific inhalation toxicity : 3.90E-10 Sv/Bq + Energy deposited per fission : 212.55 MeV + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide is using NFY data from U-235 + - Nuclide has no SFY data + + - 17 reaction channels + - 2 special reactions + - 5 transmutation reactions + - 4 transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 17 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.83420E+00 MeV Emin = 5.85903E+00 MeV frac = 1.00000E+00 Product nuclide = 94236.82c : (n,2n) + 3 MT = 17 Q = -1.32200E+01 MeV Emin = 1.32763E+01 MeV frac = 1.00000E+00 Product nuclide = 942350 : (n,3n) + 4 MT = 19 Q = 2.03565E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : (n,f) + 5 MT = 20 Q = 2.03565E+02 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : (n,nf) + 6 MT = 51 Q = -4.77970E-02 MeV Emin = 4.75000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.02560E-01 MeV Emin = 1.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -1.45380E-01 MeV Emin = 1.35500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -1.56330E-01 MeV Emin = 1.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -1.70280E-01 MeV Emin = 1.65750E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -1.99150E-01 MeV Emin = 1.95000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -2.28030E-01 MeV Emin = 2.15000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -2.78810E-01 MeV Emin = 2.70000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -3.09680E-01 MeV Emin = 3.03000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -3.19640E-01 MeV Emin = 3.15000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 91 Q = -3.19640E-01 MeV Emin = 3.15000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 17 MT = 102 Q = 6.99800E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 94238.82c : (n,gamma) + + 4 additional transport branches: + + 1 MT = 19 Q = 2.03565E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 1.40000E+01 MeV) : (n,f) + 2 MT = 19 Q = 2.03565E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : (n,f) + 3 MT = 20 Q = 2.03565E+02 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 NFY (E = 1.40000E+01 MeV) : (n,nf) + 4 MT = 20 Q = 2.03565E+02 MeV Emin = 7.00000E+00 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : (n,nf) + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 4.75000E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 2 Q = 2.22000E-01 MeV frac = 9.99958E-01 Product nuclide = 93237.82c : EC/beta+ + 2 RTYP = 4 Q = 5.74700E+00 MeV frac = 4.20000E-05 Product nuclide = 92233.82c : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.74700E+00 MeV frac = 4.20000E-05 Product nuclide = 2004.82c : alpha + + Nuclide 291 / 1657 : 94238.82c -- plutonium 238 (Pu-238) + + Pointers : 2872327 30689 + Primary type : Transport + Nuclide ZAI : 942380 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Pu238.ACE + Atomic weight (AW) : 238.04998 + Atomic weight ratio (AWR) : 236.00500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.77E+09 seconds (87.8 years) + Specific ingestion toxicity : 2.30E-07 Sv/Bq + Specific inhalation toxicity : 1.10E-04 Sv/Bq + Energy deposited per fission : 206.09 MeV + Spontaneous fission nubar : 2.21000 + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has delayed neutron data in 8 precursor groups + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has NFY data + - Nuclide has no SFY data + + - 34 reaction channels + - 2 special reactions + - 4 transmutation reactions + - 1 transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 34 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.99789E+00 MeV Emin = 7.02755E+00 MeV frac = 1.00000E+00 Product nuclide = 94237.82c : (n,2n) + 3 MT = 17 Q = -1.28716E+01 MeV Emin = 1.29261E+01 MeV frac = 1.00000E+00 Product nuclide = 94236.82c : (n,3n) + 4 MT = 18 Q = 1.97381E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : total fission + 5 MT = 51 Q = -4.40799E-02 MeV Emin = 4.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -1.45980E-01 MeV Emin = 1.40000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -3.03400E-01 MeV Emin = 2.94519E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -5.13999E-01 MeV Emin = 4.97291E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -6.05099E-01 MeV Emin = 6.07130E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -6.61399E-01 MeV Emin = 6.45939E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -7.63199E-01 MeV Emin = 7.42667E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -9.41499E-01 MeV Emin = 9.10119E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -9.62769E-01 MeV Emin = 9.58839E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -9.68199E-01 MeV Emin = 9.69576E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -9.82999E-01 MeV Emin = 9.79734E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -9.85499E-01 MeV Emin = 9.88421E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 63 Q = -1.02860E+00 MeV Emin = 1.02349E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 18 MT = 64 Q = -1.07000E+00 MeV Emin = 1.06544E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 19 MT = 65 Q = -1.08260E+00 MeV Emin = 1.08086E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 20 MT = 66 Q = -1.12580E+00 MeV Emin = 1.10953E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 21 MT = 67 Q = -1.17450E+00 MeV Emin = 1.16114E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 22 MT = 68 Q = -1.20270E+00 MeV Emin = 1.19364E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 23 MT = 69 Q = -1.22860E+00 MeV Emin = 1.22080E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 24 MT = 70 Q = -1.26420E+00 MeV Emin = 1.25615E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 25 MT = 71 Q = -1.31030E+00 MeV Emin = 1.29849E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 26 MT = 72 Q = -1.42660E+00 MeV Emin = 1.39846E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 27 MT = 73 Q = -1.44730E+00 MeV Emin = 1.44304E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 28 MT = 74 Q = -1.45850E+00 MeV Emin = 1.45906E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 29 MT = 75 Q = -1.56000E+00 MeV Emin = 1.54113E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 30 MT = 76 Q = -1.59650E+00 MeV Emin = 1.58494E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 31 MT = 77 Q = -1.62140E+00 MeV Emin = 1.61577E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 27. excited state + 32 MT = 78 Q = -1.63660E+00 MeV Emin = 1.63590E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 28. excited state + 33 MT = 91 Q = -1.65000E+00 MeV Emin = 1.65026E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 34 MT = 102 Q = 5.64739E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 94239.82c : (n,gamma) + + 1 additional transport branch: + + 1 MT = 18 Q = 1.97381E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 4.00000E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 4 Q = 5.59327E+00 MeV frac = 1.00000E+00 Product nuclide = 92234.82c : alpha + 2 RTYP = 6 Q = 1.84500E+02 MeV frac = 1.86000E-09 SF without yield : spontaneous fission + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.59327E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 292 / 1657 : 94239.82c -- plutonium 239 (Pu-239) + + Pointers : 2895957 30735 + Primary type : Transport + Nuclide ZAI : 942390 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Pu239.ACE + Atomic weight (AW) : 239.05198 + Atomic weight ratio (AWR) : 236.99840 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 3.00000E+01 + Half-life : 7.61E+11 seconds (24,130 years) + Specific ingestion toxicity : 2.50E-07 Sv/Bq + Specific inhalation toxicity : 1.20E-04 Sv/Bq + Energy deposited per fission : 207.86 MeV + Spontaneous fission nubar : 2.32000 + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has delayed neutron data in 8 precursor groups + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has NFY data + - Nuclide has no SFY data + + - 34 reaction channels + - 2 special reactions + - 5 transmutation reactions + - 1 transmutation branch reactions + - 3 decay reactions + - 2 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 34 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.64668E+00 MeV Emin = 5.70000E+00 MeV frac = 1.00000E+00 Product nuclide = 94238.82c : (n,2n) + 3 MT = 17 Q = -1.26480E+01 MeV Emin = 1.28000E+01 MeV frac = 1.00000E+00 Product nuclide = 94237.82c : (n,3n) + 4 MT = 18 Q = 1.99073E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : total fission + 5 MT = 37 Q = -1.85083E+01 MeV Emin = 1.90000E+01 MeV frac = 1.00000E+00 Product nuclide = 94236.82c : (n,4n) + 6 MT = 51 Q = -7.86000E-03 MeV Emin = 7.87500E-03 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -5.73000E-02 MeV Emin = 5.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -7.57000E-02 MeV Emin = 7.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -1.63800E-01 MeV Emin = 1.60000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -1.92800E-01 MeV Emin = 1.90000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -2.85500E-01 MeV Emin = 2.80000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -3.18100E-01 MeV Emin = 3.10000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -3.30100E-01 MeV Emin = 3.30000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -3.58100E-01 MeV Emin = 3.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -3.87400E-01 MeV Emin = 3.80000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -3.91600E-01 MeV Emin = 3.92500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -4.34000E-01 MeV Emin = 4.30000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -4.62000E-01 MeV Emin = 4.60000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -4.69800E-01 MeV Emin = 4.70000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -4.87000E-01 MeV Emin = 4.80000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 21 MT = 66 Q = -4.92200E-01 MeV Emin = 4.92500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 22 MT = 67 Q = -5.05500E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 23 MT = 68 Q = -5.11800E-01 MeV Emin = 5.12500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 24 MT = 69 Q = -5.19200E-01 MeV Emin = 5.20000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 25 MT = 70 Q = -5.38000E-01 MeV Emin = 5.40000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 26 MT = 71 Q = -5.56100E-01 MeV Emin = 5.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 27 MT = 72 Q = -5.65000E-01 MeV Emin = 5.65000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 28 MT = 73 Q = -5.70100E-01 MeV Emin = 5.70000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 29 MT = 74 Q = -5.83000E-01 MeV Emin = 5.80000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 30 MT = 75 Q = -6.20000E-01 MeV Emin = 6.20000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 31 MT = 76 Q = -6.34000E-01 MeV Emin = 6.30000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 26. excited state + 32 MT = 77 Q = -6.59000E-01 MeV Emin = 6.60000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 27. excited state + 33 MT = 91 Q = -6.59972E-01 MeV Emin = 6.61781E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 34 MT = 102 Q = 6.53300E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 94240.82c : (n,gamma) + + 1 additional transport branch: + + 1 MT = 18 Q = 1.99073E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 7.87500E-03 MeV : total inelastic scattering + + 3 decay reactions: + + 1 RTYP = 4 Q = 5.24450E+00 MeV frac = 6.00000E-04 Product nuclide = 92235.82c : alpha + 2 RTYP = 4 Q = 5.24442E+00 MeV frac = 9.99400E-01 Product nuclide = 922351 : alpha + 3 RTYP = 6 Q = 1.84300E+02 MeV frac = 3.10000E-12 SF without yield : spontaneous fission + + 2 additional decay branches: + + 1 RTYP = 4 Q = 5.24450E+00 MeV frac = 6.00000E-04 Product nuclide = 2004.82c : alpha + 2 RTYP = 4 Q = 5.24442E+00 MeV frac = 9.99400E-01 Product nuclide = 2004.82c : alpha + + Nuclide 293 / 1657 : 94240.82c -- plutonium 240 (Pu-240) + + Pointers : 2930085 30781 + Primary type : Transport + Nuclide ZAI : 942400 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Pu240.ACE + Atomic weight (AW) : 240.05379 + Atomic weight ratio (AWR) : 237.99160 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 3.00000E+01 + Half-life : 2.07E+11 seconds (6,567 years) + Specific ingestion toxicity : 2.50E-07 Sv/Bq + Specific inhalation toxicity : 1.20E-04 Sv/Bq + Energy deposited per fission : 211.96 MeV + Spontaneous fission nubar : 2.15100 + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has delayed neutron data in 8 precursor groups + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has NFY data + - Nuclide has no SFY data + + - 31 reaction channels + - 2 special reactions + - 5 transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 31 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.53370E+00 MeV Emin = 6.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 94239.82c : (n,2n) + 3 MT = 17 Q = -1.21804E+01 MeV Emin = 1.24000E+01 MeV frac = 1.00000E+00 Product nuclide = 94238.82c : (n,3n) + 4 MT = 18 Q = 2.03004E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + 5 MT = 37 Q = -1.91816E+01 MeV Emin = 1.95000E+01 MeV frac = 1.00000E+00 Product nuclide = 94237.82c : (n,4n) + 6 MT = 51 Q = -4.28200E-02 MeV Emin = 4.15000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.41690E-01 MeV Emin = 1.40000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -2.94310E-01 MeV Emin = 2.90000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -4.97600E-01 MeV Emin = 4.90000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -5.97400E-01 MeV Emin = 5.90000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -6.48900E-01 MeV Emin = 6.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -7.42500E-01 MeV Emin = 7.40000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -7.47800E-01 MeV Emin = 7.90000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -8.60700E-01 MeV Emin = 8.60000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -9.00300E-01 MeV Emin = 9.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -9.38100E-01 MeV Emin = 9.40000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -9.58900E-01 MeV Emin = 9.60000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -9.93000E-01 MeV Emin = 9.90000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -1.00210E+00 MeV Emin = 1.00316E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -1.03060E+00 MeV Emin = 1.02062E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 21 MT = 66 Q = -1.03790E+00 MeV Emin = 1.03860E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 22 MT = 67 Q = -1.04180E+00 MeV Emin = 1.09714E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 23 MT = 68 Q = -1.07640E+00 MeV Emin = 1.06159E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 24 MT = 69 Q = -1.08970E+00 MeV Emin = 1.09214E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 25 MT = 70 Q = -1.11570E+00 MeV Emin = 1.11019E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 26 MT = 71 Q = -1.13130E+00 MeV Emin = 1.12822E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 27 MT = 72 Q = -1.13750E+00 MeV Emin = 1.13917E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 28 MT = 73 Q = -1.16130E+00 MeV Emin = 1.15423E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 29 MT = 74 Q = -1.17780E+00 MeV Emin = 1.17447E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 30 MT = 91 Q = -1.17880E+00 MeV Emin = 1.18350E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 31 MT = 102 Q = 5.24190E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 94241.82c : (n,gamma) + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 4.15000E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 4 Q = 5.25590E+00 MeV frac = 1.00000E+00 Product nuclide = 92236.82c : alpha + 2 RTYP = 6 Q = 1.84700E+02 MeV frac = 5.70000E-08 SF without yield : spontaneous fission + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.25590E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 294 / 1657 : 94241.82c -- plutonium 241 (Pu-241) + + Pointers : 2942310 30827 + Primary type : Transport + Nuclide ZAI : 942410 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Pu241.ACE + Atomic weight (AW) : 241.05681 + Atomic weight ratio (AWR) : 238.98600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 4.52E+08 seconds (14.3 years) + Specific ingestion toxicity : 4.80E-09 Sv/Bq + Specific inhalation toxicity : 2.30E-06 Sv/Bq + Energy deposited per fission : 210.89 MeV + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has delayed neutron data in 8 precursor groups + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has NFY data + - Nuclide has no SFY data + + - 18 reaction channels + - 2 special reactions + - 5 transmutation reactions + - 1 transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 18 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.23999E+00 MeV Emin = 5.26192E+00 MeV frac = 1.00000E+00 Product nuclide = 94240.82c : (n,2n) + 3 MT = 17 Q = -1.17700E+01 MeV Emin = 1.18193E+01 MeV frac = 1.00000E+00 Product nuclide = 94239.82c : (n,3n) + 4 MT = 18 Q = 2.01980E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : total fission + 5 MT = 37 Q = -1.74300E+01 MeV Emin = 1.75030E+01 MeV frac = 1.00000E+00 Product nuclide = 94238.82c : (n,4n) + 6 MT = 51 Q = -4.17999E-02 MeV Emin = 4.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -9.39999E-02 MeV Emin = 9.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -1.61500E-01 MeV Emin = 1.60000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -1.70800E-01 MeV Emin = 1.70000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -2.23100E-01 MeV Emin = 2.20000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -2.30000E-01 MeV Emin = 2.30000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -2.42700E-01 MeV Emin = 2.40000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -3.00000E-01 MeV Emin = 3.00628E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -3.35000E-01 MeV Emin = 3.28201E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -3.67999E-01 MeV Emin = 3.60000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -4.44999E-01 MeV Emin = 4.40000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 91 Q = -4.89999E-01 MeV Emin = 4.80000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 18 MT = 102 Q = 6.31000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 94242.82c : (n,gamma) + + 1 additional transport branch: + + 1 MT = 18 Q = 2.01980E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 4.00000E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 4 Q = 5.14000E+00 MeV frac = 2.44000E-05 Product nuclide = 92237.82c : alpha + 2 RTYP = 1 Q = 2.08000E-02 MeV frac = 9.99976E-01 Product nuclide = 95241.82c : beta- + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.14000E+00 MeV frac = 2.44000E-05 Product nuclide = 2004.82c : alpha + + Nuclide 295 / 1657 : 94242.82c -- plutonium 242 (Pu-242) + + Pointers : 2962100 30873 + Primary type : Transport + Nuclide ZAI : 942420 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Pu242.ACE + Atomic weight (AW) : 242.05841 + Atomic weight ratio (AWR) : 239.97900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.18E+13 seconds (373,757 years) + Specific ingestion toxicity : 2.40E-07 Sv/Bq + Specific inhalation toxicity : 1.10E-04 Sv/Bq + Energy deposited per fission : 210.48 MeV + Spontaneous fission nubar : 2.14100 + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has delayed neutron data in 8 precursor groups + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has NFY data + - Nuclide has no SFY data + + - 27 reaction channels + - 2 special reactions + - 5 transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 27 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.30969E+00 MeV Emin = 6.33599E+00 MeV frac = 1.00000E+00 Product nuclide = 94241.82c : (n,2n) + 3 MT = 17 Q = -1.15512E+01 MeV Emin = 1.15994E+01 MeV frac = 1.00000E+00 Product nuclide = 94240.82c : (n,3n) + 4 MT = 18 Q = 2.01580E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + 5 MT = 37 Q = -1.80852E+01 MeV Emin = 1.81606E+01 MeV frac = 1.00000E+00 Product nuclide = 94239.82c : (n,4n) + 6 MT = 51 Q = -4.45400E-02 MeV Emin = 4.20000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.47300E-01 MeV Emin = 1.47800E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -3.06400E-01 MeV Emin = 3.05900E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -5.18100E-01 MeV Emin = 5.19500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -7.78780E-01 MeV Emin = 8.35789E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -7.80460E-01 MeV Emin = 7.81945E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -8.32300E-01 MeV Emin = 8.27576E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -9.27000E-01 MeV Emin = 9.29996E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -9.56000E-01 MeV Emin = 9.49988E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -9.92500E-01 MeV Emin = 9.94175E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -1.01940E+00 MeV Emin = 1.02300E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -1.03920E+00 MeV Emin = 1.04100E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -1.06400E+00 MeV Emin = 1.06800E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -1.08400E+00 MeV Emin = 1.38000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -1.09210E+00 MeV Emin = 1.09599E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 21 MT = 66 Q = -1.10200E+00 MeV Emin = 1.10100E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 22 MT = 67 Q = -1.12200E+00 MeV Emin = 1.11684E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 23 MT = 68 Q = -1.15010E+00 MeV Emin = 1.15000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 24 MT = 69 Q = -1.15460E+00 MeV Emin = 1.15715E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 25 MT = 70 Q = -1.18160E+00 MeV Emin = 1.17297E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 26 MT = 91 Q = -1.19000E+00 MeV Emin = 1.19074E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 27 MT = 102 Q = 5.03419E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 94243.82c : (n,gamma) + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 4.20000E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 4 Q = 4.98310E+00 MeV frac = 1.00000E+00 Product nuclide = 92238.82c : alpha + 2 RTYP = 6 Q = 1.84700E+02 MeV frac = 5.50000E-06 SF without yield : spontaneous fission + + 1 additional decay branch: + + 1 RTYP = 4 Q = 4.98310E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 296 / 1657 : 94243.82c -- plutonium 243 (Pu-243) + + Pointers : 2973673 30919 + Primary type : Transport + Nuclide ZAI : 942430 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Pu243.ACE + Atomic weight (AW) : 243.06203 + Atomic weight ratio (AWR) : 240.97400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.78E+04 seconds (4.96 hours) + Specific ingestion toxicity : 8.50E-11 Sv/Bq + Specific inhalation toxicity : 8.60E-11 Sv/Bq + Energy deposited per fission : 208.83 MeV + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide is using NFY data from Cm-245 + - Nuclide has no SFY data + + - 7 reaction channels + - 2 special reactions + - 5 transmutation reactions + - 1 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 7 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.03920E+00 MeV Emin = 5.06011E+00 MeV frac = 1.00000E+00 Product nuclide = 94242.82c : (n,2n) + 3 MT = 17 Q = -1.13330E+01 MeV Emin = 1.13800E+01 MeV frac = 1.00000E+00 Product nuclide = 94241.82c : (n,3n) + 4 MT = 18 Q = 2.00000E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : total fission + 5 MT = 37 Q = -1.65810E+01 MeV Emin = 1.66500E+01 MeV frac = 1.00000E+00 Product nuclide = 94240.82c : (n,4n) + 6 MT = 91 Q = -5.97520E-02 MeV Emin = 5.50355E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 7 MT = 102 Q = 6.02000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 94244.82c : (n,gamma) + + 1 additional transport branch: + + 1 MT = 18 Q = 2.00000E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 5.50355E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.82000E-01 MeV frac = 1.00000E+00 Product nuclide = 95243.82c : beta- + + Nuclide 297 / 1657 : 94244.82c -- plutonium 244 (Pu-244) + + Pointers : 2996177 30965 + Primary type : Transport + Nuclide ZAI : 942440 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Pu244.ACE + Atomic weight (AW) : 244.06465 + Atomic weight ratio (AWR) : 241.96800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.52E+15 seconds (80.1 million years) + Specific ingestion toxicity : 2.40E-07 Sv/Bq + Specific inhalation toxicity : 1.10E-04 Sv/Bq + Energy deposited per fission : 216.82 MeV + Spontaneous fission nubar : 2.29000 + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide is using NFY data from U-233 + - Nuclide has no SFY data + + - 13 reaction channels + - 2 special reactions + - 6 transmutation reactions + - 4 transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 13 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.99320E+00 MeV Emin = 6.01800E+00 MeV frac = 1.00000E+00 Product nuclide = 94243.82c : (n,2n) + 3 MT = 17 Q = -1.10550E+01 MeV Emin = 1.11007E+01 MeV frac = 1.00000E+00 Product nuclide = 94242.82c : (n,3n) + 4 MT = 19 Q = 2.07654E+02 MeV Emin = 2.46932E-04 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : (n,f) + 5 MT = 20 Q = 2.07654E+02 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : (n,nf) + 6 MT = 37 Q = -1.73560E+01 MeV Emin = 1.74280E+01 MeV frac = 1.00000E+00 Product nuclide = 94241.82c : (n,4n) + 7 MT = 51 Q = -4.38190E-02 MeV Emin = 4.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 8 MT = 52 Q = -1.42410E-01 MeV Emin = 1.25000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 9 MT = 53 Q = -2.94780E-01 MeV Emin = 2.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 10 MT = 54 Q = -5.97530E-01 MeV Emin = 5.91000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 11 MT = 55 Q = -6.47320E-01 MeV Emin = 6.40000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 12 MT = 91 Q = -6.47320E-01 MeV Emin = 6.40000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 13 MT = 102 Q = 4.72000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 942450 : (n,gamma) + + 4 additional transport branches: + + 1 MT = 19 Q = 2.07654E+02 MeV Emin = 2.46932E-04 MeV frac = 1.00000E+00 NFY (E = 1.40000E+01 MeV) : (n,f) + 2 MT = 19 Q = 2.07654E+02 MeV Emin = 2.46932E-04 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : (n,f) + 3 MT = 20 Q = 2.07654E+02 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 NFY (E = 1.40000E+01 MeV) : (n,nf) + 4 MT = 20 Q = 2.07654E+02 MeV Emin = 5.00000E+00 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : (n,nf) + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 4.00000E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 4 Q = 4.66580E+00 MeV frac = 9.98750E-01 Product nuclide = 922400 : alpha + 2 RTYP = 6 Q = 1.84200E+02 MeV frac = 1.25000E-03 SF without yield : spontaneous fission + + 1 additional decay branch: + + 1 RTYP = 4 Q = 4.66580E+00 MeV frac = 9.98750E-01 Product nuclide = 2004.82c : alpha + + Nuclide 298 / 1657 : 95241.82c -- americium 241 (Am-241) + + Pointers : 3034095 18867 + Primary type : Transport + Nuclide ZAI : 952410 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Am241.ACE + Atomic weight (AW) : 241.05681 + Atomic weight ratio (AWR) : 238.98600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.37E+10 seconds (433 years) + Specific ingestion toxicity : 2.00E-07 Sv/Bq + Specific inhalation toxicity : 9.60E-05 Sv/Bq + Energy deposited per fission : 210.87 MeV + Spontaneous fission nubar : 2.50000 + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has delayed neutron data in 8 precursor groups + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has NFY data + - Nuclide has no SFY data + + - 16 reaction channels + - 2 special reactions + - 4 transmutation reactions + - 2 transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 16 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.64114E+00 MeV Emin = 6.66893E+00 MeV frac = 1.00000E+00 Product nuclide = 952400 : (n,2n) + 3 MT = 17 Q = -1.26060E+01 MeV Emin = 1.26590E+01 MeV frac = 1.00000E+00 Product nuclide = 952390 : (n,3n) + 4 MT = 18 Q = 2.01960E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : total fission + 5 MT = 51 Q = -4.11760E-02 MeV Emin = 4.06742E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -9.36500E-02 MeV Emin = 9.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -1.58000E-01 MeV Emin = 1.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -2.05880E-01 MeV Emin = 2.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -2.34000E-01 MeV Emin = 2.20861E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -2.35000E-01 MeV Emin = 2.35481E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -2.39000E-01 MeV Emin = 2.37992E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -2.72000E-01 MeV Emin = 2.61569E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -2.73000E-01 MeV Emin = 2.73640E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -3.12000E-01 MeV Emin = 3.12500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 91 Q = -3.13000E-01 MeV Emin = 3.14063E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 16 MT = 102 Q = 5.54100E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 95642.82c : (n,gamma) + + 2 additional transport branches: + + 1 MT = 18 Q = 2.01960E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + 2 MT = 102 Q = 5.54100E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 95242.82c : (n,gamma) + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 4.06742E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 4 Q = 5.63781E+00 MeV frac = 1.00000E+00 Product nuclide = 93237.82c : alpha + 2 RTYP = 6 Q = 1.88100E+02 MeV frac = 4.30000E-12 SF without yield : spontaneous fission + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.63781E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 299 / 1657 : 95642.82c -- americium 242 (Am-242) + + Pointers : 3065598 18913 + Primary type : Transport + Nuclide ZAI : 952420 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Am242G.ACE + Atomic weight (AW) : 242.05942 + Atomic weight ratio (AWR) : 239.98000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 5.76E+04 seconds (16 hours) + Specific ingestion toxicity : 3.00E-10 Sv/Bq + Specific inhalation toxicity : 2.00E-08 Sv/Bq + Energy deposited per fission : 208.83 MeV + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide is using NFY data from Am-242m + - Nuclide has no SFY data + + - 33 reaction channels + - 2 special reactions + - 6 transmutation reactions + - 3 transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 33 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.53900E+00 MeV Emin = 5.56208E+00 MeV frac = 1.00000E+00 Product nuclide = 95241.82c : (n,2n) + 3 MT = 17 Q = -1.21801E+01 MeV Emin = 1.22309E+01 MeV frac = 1.00000E+00 Product nuclide = 952400 : (n,3n) + 4 MT = 19 Q = 2.00000E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : (n,f) + 5 MT = 20 Q = 2.00000E+02 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : (n,nf) + 6 MT = 21 Q = 2.00000E+02 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : (n,2nf) + 7 MT = 51 Q = -4.41000E-02 MeV Emin = 3.50000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 8 MT = 52 Q = -4.86300E-02 MeV Emin = 4.65582E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 9 MT = 53 Q = -5.29000E-02 MeV Emin = 5.15602E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 10 MT = 54 Q = -7.58000E-02 MeV Emin = 7.50000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 11 MT = 55 Q = -1.14000E-01 MeV Emin = 1.07237E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 12 MT = 56 Q = -1.40000E-01 MeV Emin = 1.34056E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 13 MT = 57 Q = -1.48000E-01 MeV Emin = 1.47813E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 14 MT = 58 Q = -1.49900E-01 MeV Emin = 1.49621E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 15 MT = 59 Q = -1.90000E-01 MeV Emin = 1.90741E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 16 MT = 60 Q = -1.97600E-01 MeV Emin = 1.94808E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 17 MT = 61 Q = -2.17000E-01 MeV Emin = 2.08952E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 18 MT = 62 Q = -2.20000E-01 MeV Emin = 2.19411E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 19 MT = 63 Q = -2.30500E-01 MeV Emin = 2.26188E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 20 MT = 64 Q = -2.42000E-01 MeV Emin = 2.37234E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 21 MT = 65 Q = -2.44100E-01 MeV Emin = 2.44063E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 22 MT = 66 Q = -2.63000E-01 MeV Emin = 2.54607E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 23 MT = 67 Q = -2.63100E-01 MeV Emin = 2.64096E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 24 MT = 68 Q = -2.70100E-01 MeV Emin = 2.70910E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 25 MT = 69 Q = -2.75000E-01 MeV Emin = 2.75945E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 26 MT = 70 Q = -2.83300E-01 MeV Emin = 2.84336E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 27 MT = 71 Q = -2.88400E-01 MeV Emin = 2.89371E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 28 MT = 72 Q = -2.91800E-01 MeV Emin = 2.92168E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 29 MT = 73 Q = -3.05000E-01 MeV Emin = 3.06134E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 30 MT = 74 Q = -3.06900E-01 MeV Emin = 3.06134E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 31 MT = 75 Q = -3.19000E-01 MeV Emin = 3.14254E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 32 MT = 91 Q = -3.20000E-01 MeV Emin = 3.20831E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 33 MT = 102 Q = 6.36710E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 95243.82c : (n,gamma) + + 3 additional transport branches: + + 1 MT = 19 Q = 2.00000E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : (n,f) + 2 MT = 20 Q = 2.00000E+02 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : (n,nf) + 3 MT = 21 Q = 2.00000E+02 MeV Emin = 1.00000E+01 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : (n,2nf) + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 3.50000E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 2 Q = 7.51300E-01 MeV frac = 1.69000E-01 Product nuclide = 94242.82c : EC/beta+ + 2 RTYP = 1 Q = 6.64500E-01 MeV frac = 8.31000E-01 Product nuclide = 96242.82c : beta- + + Nuclide 300 / 1657 : 95242.82c -- americium 242m (Am-242m) + + Pointers : 3088156 18959 + Primary type : Transport + Nuclide ZAI : 952421 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Am242M.ACE + Atomic weight (AW) : 242.05942 + Atomic weight ratio (AWR) : 239.98000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 4.45E+09 seconds (141 years) + Specific ingestion toxicity : 1.90E-07 Sv/Bq + Specific inhalation toxicity : 9.20E-05 Sv/Bq + Energy deposited per fission : 219.75 MeV + Spontaneous fission nubar : 2.56000 + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has delayed neutron data in 8 precursor groups + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has NFY data + - Nuclide has no SFY data + + - 31 reaction channels + - 2 special reactions + - 4 transmutation reactions + - 1 transmutation branch reactions + - 3 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 31 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.53900E+00 MeV Emin = 5.56208E+00 MeV frac = 1.00000E+00 Product nuclide = 95241.82c : (n,2n) + 3 MT = 17 Q = -1.21801E+01 MeV Emin = 1.22309E+01 MeV frac = 1.00000E+00 Product nuclide = 952400 : (n,3n) + 4 MT = 18 Q = 2.10464E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : total fission + 5 MT = 51 Q = 4.86300E-02 MeV Emin = 4.20473E-05 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = 4.53000E-03 MeV Emin = 9.00000E-03 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -4.27000E-03 MeV Emin = 4.01889E-03 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -2.71700E-02 MeV Emin = 2.72475E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -6.53700E-02 MeV Emin = 6.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -9.13700E-02 MeV Emin = 9.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -9.93700E-02 MeV Emin = 9.48921E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -1.01270E-01 MeV Emin = 1.00846E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -1.41370E-01 MeV Emin = 1.31892E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -1.48970E-01 MeV Emin = 1.45775E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -1.68370E-01 MeV Emin = 1.66563E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -1.71370E-01 MeV Emin = 1.70704E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 63 Q = -1.81870E-01 MeV Emin = 1.81159E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 18 MT = 64 Q = -1.93370E-01 MeV Emin = 1.94015E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 19 MT = 65 Q = -1.95470E-01 MeV Emin = 1.95528E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 20 MT = 66 Q = -2.14370E-01 MeV Emin = 2.07631E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 21 MT = 67 Q = -2.14470E-01 MeV Emin = 2.15288E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 22 MT = 68 Q = -2.21470E-01 MeV Emin = 2.22085E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 23 MT = 69 Q = -2.26370E-01 MeV Emin = 2.24326E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 24 MT = 70 Q = -2.34670E-01 MeV Emin = 2.31481E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 25 MT = 71 Q = -2.39770E-01 MeV Emin = 2.38208E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 26 MT = 72 Q = -2.43170E-01 MeV Emin = 2.42476E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 27 MT = 73 Q = -2.56370E-01 MeV Emin = 2.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 28 MT = 74 Q = -2.58270E-01 MeV Emin = 2.58392E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 29 MT = 75 Q = -2.70370E-01 MeV Emin = 2.71364E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 30 MT = 91 Q = -2.73000E-01 MeV Emin = 2.73213E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 31 MT = 102 Q = 6.37000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 95243.82c : (n,gamma) + + 1 additional transport branch: + + 1 MT = 18 Q = 2.10464E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 4.20473E-05 MeV : total inelastic scattering + + 3 decay reactions: + + 1 RTYP = 3 Q = 4.86300E-02 MeV frac = 9.95370E-01 Product nuclide = 95642.82c : IT + 2 RTYP = 4 Q = 5.63690E+00 MeV frac = 4.63000E-03 Product nuclide = 93238.82c : alpha + 3 RTYP = 6 Q = 1.88400E+02 MeV frac = 1.60000E-10 SF without yield : spontaneous fission + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.63690E+00 MeV frac = 4.63000E-03 Product nuclide = 2004.82c : alpha + + Nuclide 301 / 1657 : 95243.82c -- americium 243 (Am-243) + + Pointers : 3114955 19005 + Primary type : Transport + Nuclide ZAI : 952430 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Am243.ACE + Atomic weight (AW) : 243.06102 + Atomic weight ratio (AWR) : 240.97300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.32E+11 seconds (7,370 years) + Specific ingestion toxicity : 2.00E-07 Sv/Bq + Specific inhalation toxicity : 9.60E-05 Sv/Bq + Energy deposited per fission : 212.61 MeV + Spontaneous fission nubar : 2.61000 + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has delayed neutron data in 8 precursor groups + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has NFY data + - Nuclide has no SFY data + + - 16 reaction channels + - 2 special reactions + - 4 transmutation reactions + - 2 transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 16 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.36400E+00 MeV Emin = 6.39041E+00 MeV frac = 1.00000E+00 Product nuclide = 95642.82c : (n,2n) + 3 MT = 17 Q = -1.19030E+01 MeV Emin = 1.19524E+01 MeV frac = 1.00000E+00 Product nuclide = 95241.82c : (n,3n) + 4 MT = 18 Q = 2.03620E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : total fission + 5 MT = 51 Q = -4.22000E-02 MeV Emin = 4.23175E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -8.40000E-02 MeV Emin = 8.37500E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -9.64000E-02 MeV Emin = 9.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -1.09200E-01 MeV Emin = 1.04827E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -1.43500E-01 MeV Emin = 1.43533E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -1.62300E-01 MeV Emin = 1.62591E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -1.89300E-01 MeV Emin = 1.88707E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -2.38000E-01 MeV Emin = 2.38794E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -2.44000E-01 MeV Emin = 2.44823E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -2.66000E-01 MeV Emin = 2.58716E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 91 Q = -2.67000E-01 MeV Emin = 2.67606E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 16 MT = 102 Q = 5.16000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 95244.82c : (n,gamma) + + 2 additional transport branches: + + 1 MT = 18 Q = 2.03620E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + 2 MT = 102 Q = 5.16000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 95644.82c : (n,gamma) + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 4.23175E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 4 Q = 5.43870E+00 MeV frac = 1.00000E+00 Product nuclide = 93239.82c : alpha + 2 RTYP = 6 Q = 1.92900E+02 MeV frac = 3.70000E-11 SF without yield : spontaneous fission + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.43870E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 302 / 1657 : 95244.82c -- americium 244 (Am-244) + + Pointers : 3136399 19051 + Primary type : Transport + Nuclide ZAI : 952440 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Am244.ACE + Atomic weight (AW) : 244.06465 + Atomic weight ratio (AWR) : 241.96800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 3.64E+04 seconds (10.1 hours) + Specific ingestion toxicity : 4.60E-10 Sv/Bq + Specific inhalation toxicity : 3.70E-09 Sv/Bq + Energy deposited per fission : 208.83 MeV + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide is using NFY data from Cm-245 + - Nuclide has no SFY data + + - 32 reaction channels + - 2 special reactions + - 5 transmutation reactions + - 1 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 32 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.36319E+00 MeV Emin = 5.38540E+00 MeV frac = 1.00000E+00 Product nuclide = 95243.82c : (n,2n) + 3 MT = 17 Q = -1.17275E+01 MeV Emin = 1.17760E+01 MeV frac = 1.00000E+00 Product nuclide = 95642.82c : (n,3n) + 4 MT = 18 Q = 1.99999E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : total fission + 5 MT = 37 Q = -1.72687E+01 MeV Emin = 1.73401E+01 MeV frac = 1.00000E+00 Product nuclide = 95241.82c : (n,4n) + 6 MT = 51 Q = -8.79999E-02 MeV Emin = 8.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.00309E-01 MeV Emin = 1.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -1.23281E-01 MeV Emin = 1.20000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -1.48283E-01 MeV Emin = 1.44448E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -1.75657E-01 MeV Emin = 1.72287E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -1.83511E-01 MeV Emin = 1.80000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -1.97295E-01 MeV Emin = 1.95082E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -2.28299E-01 MeV Emin = 2.20000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -2.61696E-01 MeV Emin = 2.60000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -2.72202E-01 MeV Emin = 2.68712E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -2.89212E-01 MeV Emin = 2.85203E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -2.96658E-01 MeV Emin = 2.94146E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -3.22751E-01 MeV Emin = 3.18064E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -3.35575E-01 MeV Emin = 3.31328E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -3.42650E-01 MeV Emin = 3.38738E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 21 MT = 66 Q = -3.43658E-01 MeV Emin = 3.44572E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 22 MT = 67 Q = -3.48405E-01 MeV Emin = 3.47462E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 23 MT = 68 Q = -3.61837E-01 MeV Emin = 3.62519E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 24 MT = 69 Q = -3.77056E-01 MeV Emin = 3.71461E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 25 MT = 70 Q = -3.90027E-01 MeV Emin = 3.91356E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 26 MT = 71 Q = -3.98742E-01 MeV Emin = 4.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 27 MT = 72 Q = -4.14688E-01 MeV Emin = 4.15897E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 28 MT = 73 Q = -4.18956E-01 MeV Emin = 4.20478E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 29 MT = 74 Q = -4.20130E-01 MeV Emin = 4.21712E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 30 MT = 75 Q = -4.21203E-01 MeV Emin = 4.22240E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 31 MT = 91 Q = -4.34999E-01 MeV Emin = 4.36547E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 32 MT = 102 Q = 6.05299E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 952450 : (n,gamma) + + 1 additional transport branch: + + 1 MT = 18 Q = 1.99999E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 8.00000E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.87111E-01 MeV frac = 1.00000E+00 Product nuclide = 962441 : beta- + + Nuclide 303 / 1657 : 95644.82c -- americium 244m (Am-244m) + + Pointers : 3159538 19097 + Primary type : Transport + Nuclide ZAI : 952441 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Am244M.ACE + Atomic weight (AW) : 244.06465 + Atomic weight ratio (AWR) : 241.96800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.56E+03 seconds (26 minutes) + Specific ingestion toxicity : 2.90E-11 Sv/Bq + Specific inhalation toxicity : 1.60E-10 Sv/Bq + Energy deposited per fission : 208.83 MeV + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide is using NFY data from Cm-245 + - Nuclide has no SFY data + + - 32 reaction channels + - 2 special reactions + - 5 transmutation reactions + - 1 transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 32 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.36319E+00 MeV Emin = 5.38540E+00 MeV frac = 1.00000E+00 Product nuclide = 95243.82c : (n,2n) + 3 MT = 17 Q = -1.17275E+01 MeV Emin = 1.17760E+01 MeV frac = 1.00000E+00 Product nuclide = 95642.82c : (n,3n) + 4 MT = 18 Q = 1.99999E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : total fission + 5 MT = 37 Q = -1.72687E+01 MeV Emin = 1.73401E+01 MeV frac = 1.00000E+00 Product nuclide = 95241.82c : (n,4n) + 6 MT = 51 Q = 8.79999E-02 MeV Emin = 1.90000E-03 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.23090E-02 MeV Emin = 1.20000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -3.52810E-02 MeV Emin = 3.50000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -6.02829E-02 MeV Emin = 6.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -8.76569E-02 MeV Emin = 8.40097E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -9.55109E-02 MeV Emin = 9.36911E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -1.09295E-01 MeV Emin = 1.04873E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -1.40299E-01 MeV Emin = 1.40000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -1.73696E-01 MeV Emin = 1.70811E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -1.84202E-01 MeV Emin = 1.82481E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -2.01212E-01 MeV Emin = 2.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -2.08658E-01 MeV Emin = 2.06716E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -2.34751E-01 MeV Emin = 2.31791E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -2.47575E-01 MeV Emin = 2.44299E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -2.54650E-01 MeV Emin = 2.53038E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 21 MT = 66 Q = -2.55658E-01 MeV Emin = 2.56366E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 22 MT = 67 Q = -2.60405E-01 MeV Emin = 2.60000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 23 MT = 68 Q = -2.73838E-01 MeV Emin = 2.69069E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 24 MT = 69 Q = -2.89057E-01 MeV Emin = 2.85126E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 25 MT = 70 Q = -3.02028E-01 MeV Emin = 3.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 26 MT = 71 Q = -3.10743E-01 MeV Emin = 3.07652E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 21. excited state + 27 MT = 72 Q = -3.26689E-01 MeV Emin = 3.20033E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 22. excited state + 28 MT = 73 Q = -3.30957E-01 MeV Emin = 3.32138E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 23. excited state + 29 MT = 74 Q = -3.32131E-01 MeV Emin = 3.32821E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 24. excited state + 30 MT = 75 Q = -3.33204E-01 MeV Emin = 3.34043E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 25. excited state + 31 MT = 91 Q = -3.47000E-01 MeV Emin = 3.43239E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 32 MT = 102 Q = 6.14099E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 952450 : (n,gamma) + + 1 additional transport branch: + + 1 MT = 18 Q = 1.99999E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 1.90000E-03 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 2 Q = 1.64000E-01 MeV frac = 3.60000E-04 Product nuclide = 94244.82c : EC/beta+ + 2 RTYP = 1 Q = 1.51600E+00 MeV frac = 9.99640E-01 Product nuclide = 96244.82c : beta- + + Nuclide 304 / 1657 : 96240.82c -- curium 240 (Cm-240) + + Pointers : 3190564 21673 + Primary type : Transport + Nuclide ZAI : 962400 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Cm240.ACE + Atomic weight (AW) : 240.05520 + Atomic weight ratio (AWR) : 237.99300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.33E+06 seconds (27 days) + Specific ingestion toxicity : 7.60E-09 Sv/Bq + Specific inhalation toxicity : 3.50E-06 Sv/Bq + Energy deposited per fission : 208.83 MeV + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide is using NFY data from U-236 + - Nuclide has no SFY data + + - 7 reaction channels + - 2 special reactions + - 4 transmutation reactions + - 1 transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 7 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -7.44964E+00 MeV Emin = 7.48094E+00 MeV frac = 1.00000E+00 Product nuclide = 962390 : (n,2n) + 3 MT = 17 Q = -1.38173E+01 MeV Emin = 1.38754E+01 MeV frac = 1.00000E+00 Product nuclide = 962380 : (n,3n) + 4 MT = 18 Q = 2.00000E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : total fission + 5 MT = 51 Q = -3.80000E-02 MeV Emin = 3.81250E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 91 Q = -6.00000E-02 MeV Emin = 5.51261E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 7 MT = 102 Q = 6.07643E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 96241.82c : (n,gamma) + + 1 additional transport branch: + + 1 MT = 18 Q = 2.00000E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 3.81250E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 4 Q = 6.39780E+00 MeV frac = 9.97000E-01 Product nuclide = 94236.82c : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 6.39780E+00 MeV frac = 9.97000E-01 Product nuclide = 2004.82c : alpha + + Nuclide 305 / 1657 : 96241.82c -- curium 241 (Cm-241) + + Pointers : 3206251 21719 + Primary type : Transport + Nuclide ZAI : 962410 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Cm241.ACE + Atomic weight (AW) : 241.05781 + Atomic weight ratio (AWR) : 238.98700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.83E+06 seconds (32.8 days) + Specific ingestion toxicity : 9.10E-10 Sv/Bq + Specific inhalation toxicity : 3.70E-08 Sv/Bq + Energy deposited per fission : 218.09 MeV + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide is using NFY data from Np-238 + - Nuclide has no SFY data + + - 11 reaction channels + - 2 special reactions + - 5 transmutation reactions + - 2 transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 11 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.04470E+00 MeV Emin = 6.07000E+00 MeV frac = 1.00000E+00 Product nuclide = 96240.82c : (n,2n) + 3 MT = 17 Q = -1.35300E+01 MeV Emin = 1.35866E+01 MeV frac = 1.00000E+00 Product nuclide = 962390 : (n,3n) + 4 MT = 19 Q = 2.08867E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : (n,f) + 5 MT = 20 Q = 2.08867E+02 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : (n,nf) + 6 MT = 51 Q = -1.59330E-02 MeV Emin = 1.50000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -5.27790E-02 MeV Emin = 5.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -1.03570E-01 MeV Emin = 1.03750E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -2.53940E-01 MeV Emin = 2.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 91 Q = -2.53940E-01 MeV Emin = 2.65001E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 11 MT = 102 Q = 6.96800E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 96242.82c : (n,gamma) + + 2 additional transport branches: + + 1 MT = 19 Q = 2.08867E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : (n,f) + 2 MT = 20 Q = 2.08867E+02 MeV Emin = 1.50000E+01 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : (n,nf) + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 1.50000E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 2 Q = 7.69000E-01 MeV frac = 9.90000E-01 Product nuclide = 95241.82c : EC/beta+ + 2 RTYP = 4 Q = 6.18430E+00 MeV frac = 1.00000E-02 Product nuclide = 94237.82c : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 6.18430E+00 MeV frac = 1.00000E-02 Product nuclide = 2004.82c : alpha + + Nuclide 306 / 1657 : 96242.82c -- curium 242 (Cm-242) + + Pointers : 3227751 21765 + Primary type : Transport + Nuclide ZAI : 962420 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Cm242.ACE + Atomic weight (AW) : 242.05841 + Atomic weight ratio (AWR) : 239.97900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.41E+07 seconds (163 days) + Specific ingestion toxicity : 1.20E-08 Sv/Bq + Specific inhalation toxicity : 5.90E-06 Sv/Bq + Energy deposited per fission : 220.44 MeV + Spontaneous fission nubar : 2.52800 + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has delayed neutron data in 8 precursor groups + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide is using NFY data from U-238 + - Nuclide has SFY data + + - 9 reaction channels + - 2 special reactions + - 4 transmutation reactions + - 1 transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 9 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.96900E+00 MeV Emin = 6.99804E+00 MeV frac = 1.00000E+00 Product nuclide = 96241.82c : (n,2n) + 3 MT = 17 Q = -1.30539E+01 MeV Emin = 1.31083E+01 MeV frac = 1.00000E+00 Product nuclide = 96240.82c : (n,3n) + 4 MT = 18 Q = 2.11122E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + 5 MT = 51 Q = -4.22000E-02 MeV Emin = 4.20000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -1.38000E-01 MeV Emin = 1.30000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -2.84000E-01 MeV Emin = 2.82000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 91 Q = -2.90000E-01 MeV Emin = 2.90000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 9 MT = 102 Q = 5.69329E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 96243.82c : (n,gamma) + + 1 additional transport branch: + + 1 MT = 18 Q = 2.11122E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 1.40000E+01 MeV) : total fission + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 4.20000E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 4 Q = 6.21556E+00 MeV frac = 1.00000E+00 Product nuclide = 94238.82c : alpha + 2 RTYP = 6 Q = 1.93200E+02 MeV frac = 6.10000E-08 SFY (E = 0.00000E+00 MeV) : spontaneous fission + + 1 additional decay branch: + + 1 RTYP = 4 Q = 6.21556E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 307 / 1657 : 96243.82c -- curium 243 (Cm-243) + + Pointers : 3256600 21811 + Primary type : Transport + Nuclide ZAI : 962430 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Cm243.ACE + Atomic weight (AW) : 243.06102 + Atomic weight ratio (AWR) : 240.97300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 9.12E+08 seconds (28.9 years) + Specific ingestion toxicity : 1.50E-07 Sv/Bq + Specific inhalation toxicity : 6.90E-05 Sv/Bq + Energy deposited per fission : 221.65 MeV + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has delayed neutron data in 8 precursor groups + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has NFY data + - Nuclide has no SFY data + + - 19 reaction channels + - 2 special reactions + - 5 transmutation reactions + - 1 transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 19 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.70100E+00 MeV Emin = 5.72470E+00 MeV frac = 1.00000E+00 Product nuclide = 96242.82c : (n,2n) + 3 MT = 17 Q = -1.26620E+01 MeV Emin = 1.27146E+01 MeV frac = 1.00000E+00 Product nuclide = 96241.82c : (n,3n) + 4 MT = 18 Q = 2.12282E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : total fission + 5 MT = 37 Q = -1.87497E+01 MeV Emin = 1.88275E+01 MeV frac = 1.00000E+00 Product nuclide = 96240.82c : (n,4n) + 6 MT = 51 Q = -4.20000E-02 MeV Emin = 4.10000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -8.70000E-02 MeV Emin = 8.50000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -9.30000E-02 MeV Emin = 9.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -9.40000E-02 MeV Emin = 9.40000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -1.33000E-01 MeV Emin = 1.26776E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -1.53000E-01 MeV Emin = 1.46817E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -1.56000E-01 MeV Emin = 1.55325E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -1.64000E-01 MeV Emin = 1.60000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -1.73000E-01 MeV Emin = 1.69360E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -2.19000E-01 MeV Emin = 2.10000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -2.28000E-01 MeV Emin = 2.24475E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -2.60000E-01 MeV Emin = 2.56000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 91 Q = -2.70000E-01 MeV Emin = 2.70000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 19 MT = 102 Q = 6.79949E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 96244.82c : (n,gamma) + + 1 additional transport branch: + + 1 MT = 18 Q = 2.12282E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 4.10000E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 2 Q = 7.50000E-03 MeV frac = 2.90000E-03 Product nuclide = 95243.82c : EC/beta+ + 2 RTYP = 4 Q = 6.16880E+00 MeV frac = 9.97100E-01 Product nuclide = 94239.82c : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 6.16880E+00 MeV frac = 9.97100E-01 Product nuclide = 2004.82c : alpha + + Nuclide 308 / 1657 : 96244.82c -- curium 244 (Cm-244) + + Pointers : 3281310 21857 + Primary type : Transport + Nuclide ZAI : 962440 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Cm244.ACE + Atomic weight (AW) : 244.06263 + Atomic weight ratio (AWR) : 241.96600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 5.68E+08 seconds (18 years) + Specific ingestion toxicity : 1.20E-07 Sv/Bq + Specific inhalation toxicity : 5.70E-05 Sv/Bq + Energy deposited per fission : 213.43 MeV + Spontaneous fission nubar : 2.68750 + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has delayed neutron data in 8 precursor groups + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has NFY data + - Nuclide has SFY data + + - 10 reaction channels + - 2 special reactions + - 5 transmutation reactions + - 2 transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 10 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.77100E+00 MeV Emin = 6.79900E+00 MeV frac = 1.00000E+00 Product nuclide = 96243.82c : (n,2n) + 3 MT = 17 Q = -1.24987E+01 MeV Emin = 1.25504E+01 MeV frac = 1.00000E+00 Product nuclide = 96242.82c : (n,3n) + 4 MT = 19 Q = 2.04409E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : (n,f) + 5 MT = 20 Q = 2.04409E+02 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : (n,nf) + 6 MT = 51 Q = -4.28230E-02 MeV Emin = 4.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.41420E-01 MeV Emin = 1.40000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -2.94780E-01 MeV Emin = 2.60000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 91 Q = -2.94780E-01 MeV Emin = 2.60000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 10 MT = 102 Q = 5.52000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 96245.82c : (n,gamma) + + 2 additional transport branches: + + 1 MT = 19 Q = 2.04409E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : (n,f) + 2 MT = 20 Q = 2.04409E+02 MeV Emin = 6.00000E+00 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : (n,nf) + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 4.00000E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 4 Q = 5.90161E+00 MeV frac = 9.99999E-01 Product nuclide = 94240.82c : alpha + 2 RTYP = 6 Q = 1.91800E+02 MeV frac = 1.38000E-06 SFY (E = 0.00000E+00 MeV) : spontaneous fission + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.90161E+00 MeV frac = 9.99999E-01 Product nuclide = 2004.82c : alpha + + Nuclide 309 / 1657 : 96245.82c -- curium 245 (Cm-245) + + Pointers : 3314766 21903 + Primary type : Transport + Nuclide ZAI : 962450 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Cm245.ACE + Atomic weight (AW) : 245.06524 + Atomic weight ratio (AWR) : 242.96000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.60E+11 seconds (8,255 years) + Specific ingestion toxicity : 2.10E-07 Sv/Bq + Specific inhalation toxicity : 9.90E-05 Sv/Bq + Energy deposited per fission : 208.83 MeV + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has delayed neutron data in 8 precursor groups + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has NFY data + - Nuclide has no SFY data + + - 23 reaction channels + - 2 special reactions + - 4 transmutation reactions + - 1 transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 23 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.52000E+00 MeV Emin = 5.54272E+00 MeV frac = 1.00000E+00 Product nuclide = 96244.82c : (n,2n) + 3 MT = 17 Q = -1.23200E+01 MeV Emin = 1.23707E+01 MeV frac = 1.00000E+00 Product nuclide = 96243.82c : (n,3n) + 4 MT = 18 Q = 2.00000E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : total fission + 5 MT = 51 Q = -5.47300E-02 MeV Emin = 5.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -1.21400E-01 MeV Emin = 1.20000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -1.97100E-01 MeV Emin = 1.85933E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -2.52850E-01 MeV Emin = 2.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -2.92300E-01 MeV Emin = 2.73697E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -2.95840E-01 MeV Emin = 2.96955E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -3.50500E-01 MeV Emin = 3.50000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -3.55950E-01 MeV Emin = 3.54679E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -3.61500E-01 MeV Emin = 3.62738E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -3.87950E-01 MeV Emin = 3.89354E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -3.95700E-01 MeV Emin = 3.94677E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -4.17000E-01 MeV Emin = 4.09358E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 63 Q = -4.18800E-01 MeV Emin = 4.19595E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 18 MT = 64 Q = -4.31000E-01 MeV Emin = 4.25745E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 19 MT = 65 Q = -4.42800E-01 MeV Emin = 4.38699E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 20 MT = 66 Q = -4.98000E-01 MeV Emin = 4.87500E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 21 MT = 67 Q = -5.08700E-01 MeV Emin = 5.05422E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 22 MT = 91 Q = -5.11000E-01 MeV Emin = 5.11949E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 23 MT = 102 Q = 6.45000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 96246.82c : (n,gamma) + + 1 additional transport branch: + + 1 MT = 18 Q = 2.00000E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 5.00000E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 4 Q = 5.62230E+00 MeV frac = 1.00000E+00 Product nuclide = 94241.82c : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.62230E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 310 / 1657 : 96246.82c -- curium 246 (Cm-246) + + Pointers : 3338567 21949 + Primary type : Transport + Nuclide ZAI : 962460 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Cm246.ACE + Atomic weight (AW) : 246.06685 + Atomic weight ratio (AWR) : 243.95300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.49E+11 seconds (4,733 years) + Specific ingestion toxicity : 2.10E-07 Sv/Bq + Specific inhalation toxicity : 9.80E-05 Sv/Bq + Energy deposited per fission : 208.83 MeV + Spontaneous fission nubar : 2.94800 + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has delayed neutron data in 8 precursor groups + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide is using NFY data from U-233 + - Nuclide has no SFY data + + - 28 reaction channels + - 2 special reactions + - 6 transmutation reactions + - 6 transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 28 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.45800E+00 MeV Emin = 6.48447E+00 MeV frac = 1.00000E+00 Product nuclide = 96245.82c : (n,2n) + 3 MT = 17 Q = -1.19780E+01 MeV Emin = 1.20271E+01 MeV frac = 1.00000E+00 Product nuclide = 96244.82c : (n,3n) + 4 MT = 19 Q = 2.00000E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : (n,f) + 5 MT = 20 Q = 2.00000E+02 MeV Emin = 5.50000E+00 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : (n,nf) + 6 MT = 21 Q = 2.00000E+02 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : (n,2nf) + 7 MT = 51 Q = -4.28520E-02 MeV Emin = 3.75000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 8 MT = 52 Q = -1.42010E-01 MeV Emin = 1.21296E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 9 MT = 53 Q = -2.94900E-01 MeV Emin = 2.48055E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 10 MT = 54 Q = -5.00400E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 11 MT = 55 Q = -7.82070E-01 MeV Emin = 7.75000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 12 MT = 56 Q = -8.41670E-01 MeV Emin = 8.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 13 MT = 57 Q = -8.76430E-01 MeV Emin = 8.62572E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 14 MT = 58 Q = -9.23310E-01 MeV Emin = 9.26912E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 15 MT = 59 Q = -9.80000E-01 MeV Emin = 9.63013E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 16 MT = 60 Q = -1.05170E+00 MeV Emin = 1.02801E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 17 MT = 61 Q = -1.07885E+00 MeV Emin = 1.06964E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 18 MT = 62 Q = -1.10485E+00 MeV Emin = 1.10893E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 19 MT = 63 Q = -1.12427E+00 MeV Emin = 1.11748E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 20 MT = 64 Q = -1.12802E+00 MeV Emin = 1.13076E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 21 MT = 65 Q = -1.12940E+00 MeV Emin = 1.13334E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 22 MT = 66 Q = -1.16549E+00 MeV Emin = 1.16997E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 23 MT = 67 Q = -1.17474E+00 MeV Emin = 1.17934E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 24 MT = 68 Q = -1.17920E+00 MeV Emin = 1.18247E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 25 MT = 69 Q = -1.19590E+00 MeV Emin = 1.20000E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 26 MT = 70 Q = -1.21053E+00 MeV Emin = 1.20815E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 20. excited state + 27 MT = 91 Q = -1.22000E+00 MeV Emin = 1.22025E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 28 MT = 102 Q = 5.16000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 96247.82c : (n,gamma) + + 6 additional transport branches: + + 1 MT = 19 Q = 2.00000E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 1.40000E+01 MeV) : (n,f) + 2 MT = 19 Q = 2.00000E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : (n,f) + 3 MT = 20 Q = 2.00000E+02 MeV Emin = 5.50000E+00 MeV frac = 1.00000E+00 NFY (E = 1.40000E+01 MeV) : (n,nf) + 4 MT = 20 Q = 2.00000E+02 MeV Emin = 5.50000E+00 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : (n,nf) + 5 MT = 21 Q = 2.00000E+02 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 NFY (E = 1.40000E+01 MeV) : (n,2nf) + 6 MT = 21 Q = 2.00000E+02 MeV Emin = 1.10000E+01 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : (n,2nf) + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 3.75000E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 4 Q = 5.47620E+00 MeV frac = 9.99739E-01 Product nuclide = 94242.82c : alpha + 2 RTYP = 6 Q = 1.90400E+02 MeV frac = 2.61400E-04 SF without yield : spontaneous fission + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.47620E+00 MeV frac = 9.99739E-01 Product nuclide = 2004.82c : alpha + + Nuclide 311 / 1657 : 96247.82c -- curium 247 (Cm-247) + + Pointers : 3369474 21995 + Primary type : Transport + Nuclide ZAI : 962470 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Cm247.ACE + Atomic weight (AW) : 247.06946 + Atomic weight ratio (AWR) : 244.94700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 5.05E+14 seconds (16 million years) + Specific ingestion toxicity : 1.90E-07 Sv/Bq + Specific inhalation toxicity : 9.00E-05 Sv/Bq + Energy deposited per fission : 208.83 MeV + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide is using NFY data from U-233 + - Nuclide has no SFY data + + - 22 reaction channels + - 2 special reactions + - 5 transmutation reactions + - 2 transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 22 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.15769E+00 MeV Emin = 5.17876E+00 MeV frac = 1.00000E+00 Product nuclide = 96246.82c : (n,2n) + 3 MT = 17 Q = -1.16147E+01 MeV Emin = 1.16621E+01 MeV frac = 1.00000E+00 Product nuclide = 96245.82c : (n,3n) + 4 MT = 18 Q = 1.99999E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : total fission + 5 MT = 37 Q = -1.71347E+01 MeV Emin = 1.72047E+01 MeV frac = 1.00000E+00 Product nuclide = 96244.82c : (n,4n) + 6 MT = 51 Q = -6.14999E-02 MeV Emin = 6.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.35000E-01 MeV Emin = 1.26663E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -2.17000E-01 MeV Emin = 2.08943E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -2.27000E-01 MeV Emin = 2.23534E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -2.66000E-01 MeV Emin = 2.58543E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -2.85000E-01 MeV Emin = 2.81394E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -3.18000E-01 MeV Emin = 3.09649E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -3.44000E-01 MeV Emin = 3.39286E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 59 Q = -3.60999E-01 MeV Emin = 3.56237E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 15 MT = 60 Q = -3.95999E-01 MeV Emin = 3.89380E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 16 MT = 61 Q = -4.03599E-01 MeV Emin = 4.02624E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 17 MT = 62 Q = -4.32999E-01 MeV Emin = 4.27849E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 18 MT = 63 Q = -4.48999E-01 MeV Emin = 4.50663E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 19 MT = 64 Q = -5.05999E-01 MeV Emin = 5.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 20 MT = 65 Q = -5.19999E-01 MeV Emin = 5.16852E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 21 MT = 91 Q = -5.49999E-01 MeV Emin = 5.39067E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 22 MT = 102 Q = 6.45699E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 96248.82c : (n,gamma) + + 2 additional transport branches: + + 1 MT = 18 Q = 1.99999E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 1.40000E+01 MeV) : total fission + 2 MT = 18 Q = 1.99999E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 6.00000E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 4 Q = 5.35300E+00 MeV frac = 1.00000E+00 Product nuclide = 94243.82c : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.35300E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 312 / 1657 : 96248.82c -- curium 248 (Cm-248) + + Pointers : 3399881 22041 + Primary type : Transport + Nuclide ZAI : 962480 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Cm248.ACE + Atomic weight (AW) : 248.07207 + Atomic weight ratio (AWR) : 245.94100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 1.07E+13 seconds (340,233 years) + Specific ingestion toxicity : 7.70E-07 Sv/Bq + Specific inhalation toxicity : 3.60E-04 Sv/Bq + Energy deposited per fission : 225.00 MeV + Spontaneous fission nubar : 3.16100 + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has delayed neutron data in 8 precursor groups + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide is using NFY data from U-233 + - Nuclide has no SFY data + + - 15 reaction channels + - 2 special reactions + - 5 transmutation reactions + - 2 transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 15 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -6.21269E+00 MeV Emin = 6.23800E+00 MeV frac = 1.00000E+00 Product nuclide = 96247.82c : (n,2n) + 3 MT = 17 Q = -1.13704E+01 MeV Emin = 1.14166E+01 MeV frac = 1.00000E+00 Product nuclide = 96246.82c : (n,3n) + 4 MT = 18 Q = 2.15490E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : total fission + 5 MT = 37 Q = -1.78274E+01 MeV Emin = 1.78999E+01 MeV frac = 1.00000E+00 Product nuclide = 96245.82c : (n,4n) + 6 MT = 51 Q = -4.33999E-02 MeV Emin = 4.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 7 MT = 52 Q = -1.43600E-01 MeV Emin = 1.37092E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 8 MT = 53 Q = -2.97000E-01 MeV Emin = 2.86156E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 9 MT = 54 Q = -5.09999E-01 MeV Emin = 5.06037E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 10 MT = 55 Q = -1.04800E+00 MeV Emin = 1.02613E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 11 MT = 56 Q = -1.05000E+00 MeV Emin = 1.05358E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 12 MT = 57 Q = -1.08400E+00 MeV Emin = 1.07561E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 13 MT = 58 Q = -1.09400E+00 MeV Emin = 1.09792E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 14 MT = 91 Q = -1.12600E+00 MeV Emin = 1.12936E+00 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 15 MT = 102 Q = 4.71269E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 96249.82c : (n,gamma) + + 2 additional transport branches: + + 1 MT = 18 Q = 2.15490E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 1.40000E+01 MeV) : total fission + 2 MT = 18 Q = 2.15490E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 4.00000E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 4 Q = 5.16180E+00 MeV frac = 9.17400E-01 Product nuclide = 94244.82c : alpha + 2 RTYP = 6 Q = 1.89600E+02 MeV frac = 8.26000E-02 SF without yield : spontaneous fission + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.16180E+00 MeV frac = 9.17400E-01 Product nuclide = 2004.82c : alpha + + Nuclide 313 / 1657 : 96249.82c -- curium 249 (Cm-249) + + Pointers : 3429575 22087 + Primary type : Transport + Nuclide ZAI : 962490 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Cm249.ACE + Atomic weight (AW) : 249.07569 + Atomic weight ratio (AWR) : 246.93600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 3.85E+03 seconds (1.07 hours) + Specific ingestion toxicity : 3.10E-11 Sv/Bq + Specific inhalation toxicity : 4.00E-11 Sv/Bq + Energy deposited per fission : 208.83 MeV + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide is using NFY data from U-233 + - Nuclide has no SFY data + + - 25 reaction channels + - 2 special reactions + - 4 transmutation reactions + - 2 transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 25 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -4.71340E+00 MeV Emin = 4.73249E+00 MeV frac = 1.00000E+00 Product nuclide = 96248.82c : (n,2n) + 3 MT = 17 Q = -1.09248E+01 MeV Emin = 1.09690E+01 MeV frac = 1.00000E+00 Product nuclide = 96247.82c : (n,3n) + 4 MT = 18 Q = 2.00000E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : total fission + 5 MT = 51 Q = -2.62340E-02 MeV Emin = 2.56701E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -4.82030E-02 MeV Emin = 4.60984E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 53 Q = -4.87430E-02 MeV Emin = 4.88988E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 3. excited state + 8 MT = 54 Q = -1.09000E-01 MeV Emin = 1.04720E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 4. excited state + 9 MT = 55 Q = -1.10160E-01 MeV Emin = 1.10024E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 5. excited state + 10 MT = 56 Q = -1.46000E-01 MeV Emin = 1.42980E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 6. excited state + 11 MT = 57 Q = -2.07990E-01 MeV Emin = 2.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 7. excited state + 12 MT = 58 Q = -2.20000E-01 MeV Emin = 2.17876E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 8. excited state + 13 MT = 59 Q = -2.42010E-01 MeV Emin = 2.37465E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 9. excited state + 14 MT = 60 Q = -2.88990E-01 MeV Emin = 2.80120E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 10. excited state + 15 MT = 61 Q = -3.00000E-01 MeV Emin = 3.00000E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 11. excited state + 16 MT = 62 Q = -3.50000E-01 MeV Emin = 3.42004E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 12. excited state + 17 MT = 63 Q = -4.70210E-01 MeV Emin = 4.57027E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 13. excited state + 18 MT = 64 Q = -4.94490E-01 MeV Emin = 4.90398E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 14. excited state + 19 MT = 65 Q = -4.98000E-01 MeV Emin = 4.98246E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 15. excited state + 20 MT = 66 Q = -5.29610E-01 MeV Emin = 5.23821E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 16. excited state + 21 MT = 67 Q = -5.46860E-01 MeV Emin = 5.42580E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 17. excited state + 22 MT = 68 Q = -5.78430E-01 MeV Emin = 5.72848E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 18. excited state + 23 MT = 69 Q = -6.34000E-01 MeV Emin = 6.24362E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 19. excited state + 24 MT = 91 Q = -6.88000E-01 MeV Emin = 6.78926E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 25 MT = 102 Q = 5.83243E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 96250.82c : (n,gamma) + + 2 additional transport branches: + + 1 MT = 18 Q = 2.00000E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 1.40000E+01 MeV) : total fission + 2 MT = 18 Q = 2.00000E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 2.56701E-02 MeV : total inelastic scattering + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.03000E-01 MeV frac = 1.00000E+00 Product nuclide = 972490 : beta- + + Nuclide 314 / 1657 : 96250.82c -- curium 250 (Cm-250) + + Pointers : 3460870 22133 + Primary type : Transport + Nuclide ZAI : 962500 + Library ID : 82c + Cross section data file : /home/andrei2/serpent/xsdata/jeff312/ACEs_900K/Cm250.ACE + Atomic weight (AW) : 250.07831 + Atomic weight ratio (AWR) : 247.93000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 1.00000E-11 2.00000E+01 + Half-life : 2.52E+11 seconds (8,005 years) + Specific ingestion toxicity : 4.40E-06 Sv/Bq + Specific inhalation toxicity : 2.10E-03 Sv/Bq + Energy deposited per fission : 208.83 MeV + Spontaneous fission nubar : 3.30000 + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has ures ptable data but it is not used + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide is using NFY data from U-233 + - Nuclide has no SFY data + + - 8 reaction channels + - 2 special reactions + - 4 transmutation reactions + - 2 transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 8 reactions channel: + + 1 MT = 2 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = self : elastic scattering + 2 MT = 16 Q = -5.82930E+00 MeV Emin = 5.85281E+00 MeV frac = 1.00000E+00 Product nuclide = 96249.82c : (n,2n) + 3 MT = 17 Q = -1.05482E+01 MeV Emin = 1.05908E+01 MeV frac = 1.00000E+00 Product nuclide = 96248.82c : (n,3n) + 4 MT = 18 Q = 2.00000E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 2.53000E-08 MeV) : total fission + 5 MT = 51 Q = -4.30000E-02 MeV Emin = 4.00000E-02 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 1. excited state + 6 MT = 52 Q = -1.42000E-01 MeV Emin = 1.37251E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scatt. to 2. excited state + 7 MT = 91 Q = -1.60000E-01 MeV Emin = 1.57984E-01 MeV frac = 1.00000E+00 Product nuclide = self : inelastic scattering to continuum + 8 MT = 102 Q = 4.40643E+00 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 Product nuclide = 962510 : (n,gamma) + + 2 additional transport branches: + + 1 MT = 18 Q = 2.00000E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 1.40000E+01 MeV) : total fission + 2 MT = 18 Q = 2.00000E+02 MeV Emin = 1.00000E-11 MeV frac = 1.00000E+00 NFY (E = 4.00000E-01 MeV) : total fission + + 2 special reactions: + + 1 MT = 444 Q = 0.00000E+00 MeV Emin = 1.00000E-11 MeV : damage-energy production + 2 MT = 4 Q = 0.00000E+00 MeV Emin = 4.00000E-02 MeV : total inelastic scattering + + 2 decay reactions: + + 1 RTYP = 4 Q = 5.17000E+00 MeV frac = 3.00000E-01 Product nuclide = 942460 : alpha + 2 RTYP = 6 Q = 1.89900E+02 MeV frac = 7.00000E-01 SF without yield : spontaneous fission + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.17000E+00 MeV frac = 3.00000E-01 Product nuclide = 2004.82c : alpha + + Nuclide 315 / 1657 : 20060 -- helium 6 (He-6) + + Pointers : 52722 -1000000 + Primary type : Decay + Nuclide ZAI : 20060 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 6.01889 + Atomic weight ratio (AWR) : 5.96718 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.808 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.50700E+00 MeV frac = 1.00000E+00 Product nuclide = 3006.82c : beta- + + Nuclide 316 / 1657 : 20080 -- helium 8 (He-8) + + Pointers : 52939 -1000000 + Primary type : Decay + Nuclide ZAI : 20080 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 8.03393 + Atomic weight ratio (AWR) : 7.96491 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.122 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.06490E+01 MeV frac = 8.80000E-01 Product nuclide = 30080 : beta- + 2 RTYP = 15 Q = 8.61600E+00 MeV frac = 1.20000E-01 Product nuclide = 3007.82c : beta- + neutron emission + + Nuclide 317 / 1657 : 30080 -- lithium 8 (Li-8) + + Pointers : 58339 -1000000 + Primary type : Decay + Nuclide ZAI : 30080 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 8.02249 + Atomic weight ratio (AWR) : 7.95357 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.838 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 14 Q = 1.60970E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : beta- + alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 1.60970E+01 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 318 / 1657 : 30090 -- lithium 9 (Li-9) + + Pointers : 58657 -1000000 + Primary type : Decay + Nuclide ZAI : 30090 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 9.02679 + Atomic weight ratio (AWR) : 8.94925 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.178 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.36060E+01 MeV frac = 5.05000E-01 Product nuclide = 4009.82c : beta- + 2 RTYP = 15 Q = 1.19410E+01 MeV frac = 4.95000E-01 Product nuclide = 40080 : beta- + neutron emission + + Nuclide 319 / 1657 : 40060 -- beryllium 6 (Be-6) + + Pointers : 59003 -1000000 + Primary type : Decay + Nuclide ZAI : 40060 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 6.01972 + Atomic weight ratio (AWR) : 5.96801 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5E-12 nanoseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 2 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 77 Q = 1.37208E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : proton emission + proton emission + + 2 additional decay branches: + + 1 RTYP = 7 Q = 1.37208E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : proton emission + 2 RTYP = 7 Q = 1.37208E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : proton emission + + Nuclide 320 / 1657 : 40080 -- beryllium 8 (Be-8) + + Pointers : 59333 -1000000 + Primary type : Decay + Nuclide ZAI : 40080 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 8.00531 + Atomic weight ratio (AWR) : 7.93654 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7E-08 nanoseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 4 Q = 9.18900E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 9.18900E-02 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 321 / 1657 : 40100 -- beryllium 10 (Be-10) + + Pointers : 61997 -1000000 + Primary type : Decay + Nuclide ZAI : 40100 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 10.01353 + Atomic weight ratio (AWR) : 9.92751 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.05E+13 seconds (1.6 million years) + Specific ingestion toxicity : 1.10E-09 Sv/Bq + Specific inhalation toxicity : 3.50E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.55900E-01 MeV frac = 1.00000E+00 Product nuclide = 5010.82c : beta- + + Nuclide 322 / 1657 : 40110 -- beryllium 11 (Be-11) + + Pointers : 62214 -1000000 + Primary type : Decay + Nuclide ZAI : 40110 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 11.02168 + Atomic weight ratio (AWR) : 10.92700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 13.8 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.15080E+01 MeV frac = 9.70000E-01 Product nuclide = 5011.82c : beta- + 2 RTYP = 14 Q = 2.84300E+00 MeV frac = 3.00000E-02 Product nuclide = 3007.82c : beta- + alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 2.84300E+00 MeV frac = 3.00000E-02 Product nuclide = 2004.82c : alpha + + Nuclide 323 / 1657 : 40120 -- beryllium 12 (Be-12) + + Pointers : 62801 -1000000 + Primary type : Decay + Nuclide ZAI : 40120 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 12.02692 + Atomic weight ratio (AWR) : 11.92360 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 21.3 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.17080E+01 MeV frac = 1.00000E+00 Product nuclide = 50120 : beta- + + Nuclide 324 / 1657 : 50090 -- boron 9 (B-9) + + Pointers : 63018 -1000000 + Primary type : Decay + Nuclide ZAI : 50090 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 9.01333 + Atomic weight ratio (AWR) : 8.93590 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8E-10 nanoseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 7 Q = 1.85031E-01 MeV frac = 1.00000E+00 Product nuclide = 40080 : proton emission + + 1 additional decay branch: + + 1 RTYP = 7 Q = 1.85031E-01 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : proton emission + + Nuclide 325 / 1657 : 50120 -- boron 12 (B-12) + + Pointers : 69921 -1000000 + Primary type : Decay + Nuclide ZAI : 50120 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 12.01431 + Atomic weight ratio (AWR) : 11.91110 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 20.2 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.33700E+01 MeV frac = 9.84200E-01 Product nuclide = 60120 : beta- + 2 RTYP = 14 Q = 6.00300E+00 MeV frac = 1.58000E-02 Product nuclide = 40080 : beta- + alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 6.00300E+00 MeV frac = 1.58000E-02 Product nuclide = 2004.82c : alpha + + Nuclide 326 / 1657 : 60080 -- carbon 8 (C-8) + + Pointers : 70396 -1000000 + Primary type : Decay + Nuclide ZAI : 60080 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 8.03768 + Atomic weight ratio (AWR) : 7.96863 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2E-12 nanoseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 2 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 77 Q = 2.14100E+00 MeV frac = 1.00000E+00 Product nuclide = 40060 : proton emission + proton emission + + 2 additional decay branches: + + 1 RTYP = 7 Q = 2.14100E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : proton emission + 2 RTYP = 7 Q = 2.14100E+00 MeV frac = 1.00000E+00 Product nuclide = 1001.82c : proton emission + + Nuclide 327 / 1657 : 60120 -- carbon 12 (C-12) + + Pointers : 70726 -1000000 + Primary type : Decay + Nuclide ZAI : 60120 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 11.99999 + Atomic weight ratio (AWR) : 11.89690 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 328 / 1657 : 60130 -- carbon 13 (C-13) + + Pointers : 70832 -1000000 + Primary type : Decay + Nuclide ZAI : 60130 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 13.00331 + Atomic weight ratio (AWR) : 12.89160 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 329 / 1657 : 60140 -- carbon 14 (C-14) + + Pointers : 70938 -1000000 + Primary type : Decay + Nuclide ZAI : 60140 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 14.00319 + Atomic weight ratio (AWR) : 13.88290 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.80E+11 seconds (5,704 years) + Specific ingestion toxicity : 5.80E-10 Sv/Bq + Specific inhalation toxicity : 5.80E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.56476E-01 MeV frac = 1.00000E+00 Product nuclide = 7014.82c : beta- + + Nuclide 330 / 1657 : 60150 -- carbon 15 (C-15) + + Pointers : 71155 -1000000 + Primary type : Decay + Nuclide ZAI : 60150 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 15.01065 + Atomic weight ratio (AWR) : 14.88170 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.45 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.77170E+00 MeV frac = 1.00000E+00 Product nuclide = 7015.82c : beta- + + Nuclide 331 / 1657 : 70130 -- nitrogen 13 (N-13) + + Pointers : 71526 -1000000 + Primary type : Decay + Nuclide ZAI : 70130 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 13.00573 + Atomic weight ratio (AWR) : 12.89400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.98E+02 seconds (9.97 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 2.22045E+00 MeV frac = 1.00000E+00 Product nuclide = 60130 : EC/beta+ + + Nuclide 332 / 1657 : 70160 -- nitrogen 16 (N-16) + + Pointers : 79307 -1000000 + Primary type : Decay + Nuclide ZAI : 70160 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 16.00610 + Atomic weight ratio (AWR) : 15.86860 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.13 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.04180E+01 MeV frac = 9.99988E-01 Product nuclide = 8016.82c : beta- + 2 RTYP = 14 Q = 3.25600E+00 MeV frac = 1.20000E-05 Product nuclide = 60120 : beta- + alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 3.25600E+00 MeV frac = 1.20000E-05 Product nuclide = 2004.82c : alpha + + Nuclide 333 / 1657 : 70170 -- nitrogen 17 (N-17) + + Pointers : 79964 -1000000 + Primary type : Decay + Nuclide ZAI : 70170 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 17.00841 + Atomic weight ratio (AWR) : 16.86230 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.17 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 1 Q = 8.68000E+00 MeV frac = 5.00000E-02 Product nuclide = 8017.82c : beta- + 2 RTYP = 15 Q = 4.53700E+00 MeV frac = 9.49975E-01 Product nuclide = 8016.82c : beta- + neutron emission + 3 RTYP = 14 Q = 2.32100E+00 MeV frac = 2.50000E-05 Product nuclide = 60130 : beta- + alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 2.32100E+00 MeV frac = 2.50000E-05 Product nuclide = 2004.82c : alpha + + Nuclide 334 / 1657 : 80150 -- oxygen 15 (O-15) + + Pointers : 80694 -1000000 + Primary type : Decay + Nuclide ZAI : 80150 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 15.00308 + Atomic weight ratio (AWR) : 14.87420 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.22E+02 seconds (2.04 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 2.75700E+00 MeV frac = 1.00000E+00 Product nuclide = 7015.82c : EC/beta+ + + Nuclide 335 / 1657 : 80180 -- oxygen 18 (O-18) + + Pointers : 89643 -1000000 + Primary type : Decay + Nuclide ZAI : 80180 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 17.99912 + Atomic weight ratio (AWR) : 17.84450 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 336 / 1657 : 80190 -- oxygen 19 (O-19) + + Pointers : 89749 -1000000 + Primary type : Decay + Nuclide ZAI : 80190 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 19.00355 + Atomic weight ratio (AWR) : 18.84030 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 26.9 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.81900E+00 MeV frac = 1.00000E+00 Product nuclide = 9019.82c : beta- + + Nuclide 337 / 1657 : 90180 -- fluorine 18 (F-18) + + Pointers : 90120 -1000000 + Primary type : Decay + Nuclide ZAI : 90180 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 18.00094 + Atomic weight ratio (AWR) : 17.84630 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.58E+03 seconds (1.83 hours) + Specific ingestion toxicity : 4.90E-11 Sv/Bq + Specific inhalation toxicity : 5.90E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 1.65590E+00 MeV frac = 1.00000E+00 Product nuclide = 80180 : EC/beta+ + + Nuclide 338 / 1657 : 90200 -- fluorine 20 (F-20) + + Pointers : 93629 -1000000 + Primary type : Decay + Nuclide ZAI : 90200 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 20.00001 + Atomic weight ratio (AWR) : 19.82820 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 11 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.02590E+00 MeV frac = 1.00000E+00 Product nuclide = 100200 : beta- + + Nuclide 339 / 1657 : 100200 -- neon 20 (Ne-20) + + Pointers : 93902 -1000000 + Primary type : Decay + Nuclide ZAI : 100200 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 19.99245 + Atomic weight ratio (AWR) : 19.82070 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 340 / 1657 : 100210 -- neon 21 (Ne-21) + + Pointers : 94008 -1000000 + Primary type : Decay + Nuclide ZAI : 100210 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 20.99385 + Atomic weight ratio (AWR) : 20.81350 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 341 / 1657 : 100220 -- neon 22 (Ne-22) + + Pointers : 94114 -1000000 + Primary type : Decay + Nuclide ZAI : 100220 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 21.99142 + Atomic weight ratio (AWR) : 21.80250 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 342 / 1657 : 100230 -- neon 23 (Ne-23) + + Pointers : 94220 -1000000 + Primary type : Decay + Nuclide ZAI : 100230 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 22.99443 + Atomic weight ratio (AWR) : 22.79690 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 37.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.37500E+00 MeV frac = 1.00000E+00 Product nuclide = 11023.82c : beta- + + Nuclide 343 / 1657 : 110210 -- sodium 21 (Na-21) + + Pointers : 94563 -1000000 + Primary type : Decay + Nuclide ZAI : 110210 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 20.99768 + Atomic weight ratio (AWR) : 20.81730 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 22.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 3.54760E+00 MeV frac = 1.00000E+00 Product nuclide = 100210 : EC/beta+ + + Nuclide 344 / 1657 : 110240 -- sodium 24 (Na-24) + + Pointers : 100815 -1000000 + Primary type : Decay + Nuclide ZAI : 110240 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 23.99100 + Atomic weight ratio (AWR) : 23.78490 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.38E+04 seconds (15 hours) + Specific ingestion toxicity : 4.30E-10 Sv/Bq + Specific inhalation toxicity : 2.70E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.51561E+00 MeV frac = 1.00000E+00 Product nuclide = 12024.82c : beta- + + Nuclide 345 / 1657 : 110241 -- sodium 24m (Na-24m) + + Pointers : 101452 -1000000 + Primary type : Decay + Nuclide ZAI : 110241 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 23.99100 + Atomic weight ratio (AWR) : 23.78490 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 20.2 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 4.72300E-01 MeV frac = 9.95000E-01 Product nuclide = 110240 : IT + 2 RTYP = 1 Q = 5.98810E+00 MeV frac = 5.00000E-03 Product nuclide = 12024.82c : beta- + + Nuclide 346 / 1657 : 110250 -- sodium 25 (Na-25) + + Pointers : 101770 -1000000 + Primary type : Decay + Nuclide ZAI : 110250 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 24.98998 + Atomic weight ratio (AWR) : 24.77530 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 59.6 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.83300E+00 MeV frac = 1.00000E+00 Product nuclide = 12025.82c : beta- + + Nuclide 347 / 1657 : 110260 -- sodium 26 (Na-26) + + Pointers : 102197 -1000000 + Primary type : Decay + Nuclide ZAI : 110260 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 25.99259 + Atomic weight ratio (AWR) : 25.76930 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.08 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.32500E+00 MeV frac = 1.00000E+00 Product nuclide = 12026.82c : beta- + + Nuclide 348 / 1657 : 120230 -- magnesium 23 (Mg-23) + + Pointers : 102806 -1000000 + Primary type : Decay + Nuclide ZAI : 120230 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 22.99413 + Atomic weight ratio (AWR) : 22.79660 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 11.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 4.05610E+00 MeV frac = 1.00000E+00 Product nuclide = 11023.82c : EC/beta+ + + Nuclide 349 / 1657 : 120270 -- magnesium 27 (Mg-27) + + Pointers : 109937 -1000000 + Primary type : Decay + Nuclide ZAI : 120270 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 26.98431 + Atomic weight ratio (AWR) : 26.75250 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.67E+02 seconds (9.46 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.60930E+00 MeV frac = 1.00000E+00 Product nuclide = 13027.82c : beta- + + Nuclide 350 / 1657 : 120280 -- magnesium 28 (Mg-28) + + Pointers : 110224 -1000000 + Primary type : Decay + Nuclide ZAI : 120280 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 27.98390 + Atomic weight ratio (AWR) : 27.74350 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.52E+04 seconds (20.9 hours) + Specific ingestion toxicity : 2.20E-09 Sv/Bq + Specific inhalation toxicity : 1.20E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.83180E+00 MeV frac = 1.00000E+00 Product nuclide = 130280 : beta- + + Nuclide 351 / 1657 : 120290 -- magnesium 29 (Mg-29) + + Pointers : 110707 -1000000 + Primary type : Decay + Nuclide ZAI : 120290 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 28.98863 + Atomic weight ratio (AWR) : 28.73960 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.61300E+00 MeV frac = 1.00000E+00 Product nuclide = 130290 : beta- + + Nuclide 352 / 1657 : 130260 -- aluminum 26 (Al-26) + + Pointers : 111302 -1000000 + Primary type : Decay + Nuclide ZAI : 130260 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 25.98684 + Atomic weight ratio (AWR) : 25.76360 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.26E+13 seconds (717,475 years) + Specific ingestion toxicity : 3.50E-09 Sv/Bq + Specific inhalation toxicity : 2.00E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 4.00419E+00 MeV frac = 1.00000E+00 Product nuclide = 12026.82c : EC/beta+ + + Nuclide 353 / 1657 : 130280 -- aluminum 28 (Al-28) + + Pointers : 123040 -1000000 + Primary type : Decay + Nuclide ZAI : 130280 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 27.98188 + Atomic weight ratio (AWR) : 27.74150 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.34E+02 seconds (2.24 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.64310E+00 MeV frac = 1.00000E+00 Product nuclide = 14028.82c : beta- + + Nuclide 354 / 1657 : 130290 -- aluminum 29 (Al-29) + + Pointers : 123285 -1000000 + Primary type : Decay + Nuclide ZAI : 130290 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 28.98046 + Atomic weight ratio (AWR) : 28.73150 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.94E+02 seconds (6.56 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.68100E+00 MeV frac = 1.00000E+00 Product nuclide = 14029.82c : beta- + + Nuclide 355 / 1657 : 130300 -- aluminum 30 (Al-30) + + Pointers : 123656 -1000000 + Primary type : Decay + Nuclide ZAI : 130300 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 29.98297 + Atomic weight ratio (AWR) : 29.72540 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.65 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.53900E+00 MeV frac = 1.00000E+00 Product nuclide = 14030.82c : beta- + + Nuclide 356 / 1657 : 140270 -- silicon 27 (Si-27) + + Pointers : 124209 -1000000 + Primary type : Decay + Nuclide ZAI : 140270 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 26.98673 + Atomic weight ratio (AWR) : 26.75490 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.16 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 4.81236E+00 MeV frac = 1.00000E+00 Product nuclide = 13027.82c : EC/beta+ + + Nuclide 357 / 1657 : 140310 -- silicon 31 (Si-31) + + Pointers : 136406 -1000000 + Primary type : Decay + Nuclide ZAI : 140310 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 30.97540 + Atomic weight ratio (AWR) : 30.70930 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.43E+03 seconds (2.62 hours) + Specific ingestion toxicity : 1.60E-10 Sv/Bq + Specific inhalation toxicity : 7.90E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.49080E+00 MeV frac = 1.00000E+00 Product nuclide = 15031.82c : beta- + + Nuclide 358 / 1657 : 140320 -- silicon 32 (Si-32) + + Pointers : 136665 -1000000 + Primary type : Decay + Nuclide ZAI : 140320 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 31.97418 + Atomic weight ratio (AWR) : 31.69950 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.04E+10 seconds (330 years) + Specific ingestion toxicity : 5.60E-10 Sv/Bq + Specific inhalation toxicity : 1.10E-07 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.13000E-01 MeV frac = 1.00000E+00 Product nuclide = 150320 : beta- + + Nuclide 359 / 1657 : 140330 -- silicon 33 (Si-33) + + Pointers : 136882 -1000000 + Primary type : Decay + Nuclide ZAI : 140330 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 32.97800 + Atomic weight ratio (AWR) : 32.69470 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.18 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.84450E+00 MeV frac = 1.00000E+00 Product nuclide = 150330 : beta- + + Nuclide 360 / 1657 : 150300 -- phosphorus 30 (P-30) + + Pointers : 137066 -1000000 + Primary type : Decay + Nuclide ZAI : 150300 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 29.97833 + Atomic weight ratio (AWR) : 29.72080 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.50E+02 seconds (2.5 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 4.23240E+00 MeV frac = 1.00000E+00 Product nuclide = 14030.82c : EC/beta+ + + Nuclide 361 / 1657 : 150320 -- phosphorus 32 (P-32) + + Pointers : 139126 -1000000 + Primary type : Decay + Nuclide ZAI : 150320 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 31.97387 + Atomic weight ratio (AWR) : 31.69920 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.23E+06 seconds (14.3 days) + Specific ingestion toxicity : 2.40E-09 Sv/Bq + Specific inhalation toxicity : 3.40E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.71040E+00 MeV frac = 1.00000E+00 Product nuclide = 160320 : beta- + + Nuclide 362 / 1657 : 150330 -- phosphorus 33 (P-33) + + Pointers : 139343 -1000000 + Primary type : Decay + Nuclide ZAI : 150330 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 32.97174 + Atomic weight ratio (AWR) : 32.68850 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.19E+06 seconds (25.4 days) + Specific ingestion toxicity : 2.40E-10 Sv/Bq + Specific inhalation toxicity : 1.50E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.48500E-01 MeV frac = 1.00000E+00 Product nuclide = 160330 : beta- + + Nuclide 363 / 1657 : 150340 -- phosphorus 34 (P-34) + + Pointers : 139560 -1000000 + Primary type : Decay + Nuclide ZAI : 150340 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 33.97365 + Atomic weight ratio (AWR) : 33.68180 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 12.4 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.37430E+00 MeV frac = 1.00000E+00 Product nuclide = 16034.82c : beta- + + Nuclide 364 / 1657 : 150350 -- phosphorus 35 (P-35) + + Pointers : 139931 -1000000 + Primary type : Decay + Nuclide ZAI : 150350 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 34.97334 + Atomic weight ratio (AWR) : 34.67290 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 47.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.98866E+00 MeV frac = 1.00000E+00 Product nuclide = 160350 : beta- + + Nuclide 365 / 1657 : 150360 -- phosphorus 36 (P-36) + + Pointers : 140115 -1000000 + Primary type : Decay + Nuclide ZAI : 150360 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 35.97827 + Atomic weight ratio (AWR) : 35.66920 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.6 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.04131E+01 MeV frac = 1.00000E+00 Product nuclide = 16036.82c : beta- + + Nuclide 366 / 1657 : 160320 -- sulfur 32 (S-32) + + Pointers : 140299 -1000000 + Primary type : Decay + Nuclide ZAI : 160320 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 31.97206 + Atomic weight ratio (AWR) : 31.69740 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 367 / 1657 : 160330 -- sulfur 33 (S-33) + + Pointers : 140405 -1000000 + Primary type : Decay + Nuclide ZAI : 160330 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 32.97144 + Atomic weight ratio (AWR) : 32.68820 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 368 / 1657 : 160350 -- sulfur 35 (S-35) + + Pointers : 142155 -1000000 + Primary type : Decay + Nuclide ZAI : 160350 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 34.96900 + Atomic weight ratio (AWR) : 34.66860 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.54E+06 seconds (87.2 days) + Specific ingestion toxicity : 7.70E-10 Sv/Bq + Specific inhalation toxicity : 1.90E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.67330E-01 MeV frac = 1.00000E+00 Product nuclide = 17035.82c : beta- + + Nuclide 369 / 1657 : 160370 -- sulfur 37 (S-37) + + Pointers : 144016 -1000000 + Primary type : Decay + Nuclide ZAI : 160370 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 36.97110 + Atomic weight ratio (AWR) : 36.65350 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.99E+02 seconds (4.99 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.85400E+00 MeV frac = 1.00000E+00 Product nuclide = 17037.82c : beta- + + Nuclide 370 / 1657 : 160380 -- sulfur 38 (S-38) + + Pointers : 144345 -1000000 + Primary type : Decay + Nuclide ZAI : 160380 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 37.97119 + Atomic weight ratio (AWR) : 37.64500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.02E+04 seconds (2.84 hours) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.93700E+00 MeV frac = 1.00000E+00 Product nuclide = 170380 : beta- + + Nuclide 371 / 1657 : 170340 -- chlorine 34 (Cl-34) + + Pointers : 144730 -1000000 + Primary type : Decay + Nuclide ZAI : 170340 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 33.97375 + Atomic weight ratio (AWR) : 33.68190 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.53 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 5.49230E+00 MeV frac = 1.00000E+00 Product nuclide = 16034.82c : EC/beta+ + + Nuclide 372 / 1657 : 170360 -- chlorine 36 (Cl-36) + + Pointers : 157990 -1000000 + Primary type : Decay + Nuclide ZAI : 170360 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 35.96829 + Atomic weight ratio (AWR) : 35.65930 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.53E+12 seconds (302,200 years) + Specific ingestion toxicity : 9.30E-10 Sv/Bq + Specific inhalation toxicity : 7.30E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 1.14214E+00 MeV frac = 1.90000E-02 Product nuclide = 16036.82c : EC/beta+ + 2 RTYP = 1 Q = 7.09550E-01 MeV frac = 9.81000E-01 Product nuclide = 180360 : beta- + + Nuclide 373 / 1657 : 170380 -- chlorine 38 (Cl-38) + + Pointers : 165109 -1000000 + Primary type : Decay + Nuclide ZAI : 170380 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 37.96796 + Atomic weight ratio (AWR) : 37.64180 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.23E+03 seconds (37.2 minutes) + Specific ingestion toxicity : 1.20E-10 Sv/Bq + Specific inhalation toxicity : 4.50E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.91700E+00 MeV frac = 1.00000E+00 Product nuclide = 18038.82c : beta- + + Nuclide 374 / 1657 : 170381 -- chlorine 38m (Cl-38m) + + Pointers : 165410 -1000000 + Primary type : Decay + Nuclide ZAI : 170381 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 37.96796 + Atomic weight ratio (AWR) : 37.64180 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.715 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 6.71300E-01 MeV frac = 1.00000E+00 Product nuclide = 170380 : IT + + Nuclide 375 / 1657 : 170390 -- chlorine 39 (Cl-39) + + Pointers : 165753 -1000000 + Primary type : Decay + Nuclide ZAI : 170390 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 38.96806 + Atomic weight ratio (AWR) : 38.63330 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.34E+03 seconds (55.6 minutes) + Specific ingestion toxicity : 8.50E-11 Sv/Bq + Specific inhalation toxicity : 4.60E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.44200E+00 MeV frac = 1.00000E+00 Product nuclide = 180390 : beta- + + Nuclide 376 / 1657 : 170400 -- chlorine 40 (Cl-40) + + Pointers : 166544 -1000000 + Primary type : Decay + Nuclide ZAI : 170400 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 39.97037 + Atomic weight ratio (AWR) : 39.62700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.10E+01 seconds (1.35 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.48000E+00 MeV frac = 1.00000E+00 Product nuclide = 18040.82c : beta- + + Nuclide 377 / 1657 : 180360 -- argon 36 (Ar-36) + + Pointers : 168273 -1000000 + Primary type : Decay + Nuclide ZAI : 180360 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 35.96758 + Atomic weight ratio (AWR) : 35.65860 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 378 / 1657 : 180370 -- argon 37 (Ar-37) + + Pointers : 168379 -1000000 + Primary type : Decay + Nuclide ZAI : 180370 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 36.96676 + Atomic weight ratio (AWR) : 36.64920 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.02E+06 seconds (35 days) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 8.13870E-01 MeV frac = 1.00000E+00 Product nuclide = 17037.82c : EC/beta+ + + Nuclide 379 / 1657 : 180390 -- argon 39 (Ar-39) + + Pointers : 171655 -1000000 + Primary type : Decay + Nuclide ZAI : 180390 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 38.96432 + Atomic weight ratio (AWR) : 38.62960 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.49E+09 seconds (269 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.65000E-01 MeV frac = 1.00000E+00 Product nuclide = 19039.82c : beta- + + Nuclide 380 / 1657 : 180410 -- argon 41 (Ar-41) + + Pointers : 175706 -1000000 + Primary type : Decay + Nuclide ZAI : 180410 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 40.96451 + Atomic weight ratio (AWR) : 40.61260 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.58E+03 seconds (1.83 hours) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.49160E+00 MeV frac = 1.00000E+00 Product nuclide = 19041.82c : beta- + + Nuclide 381 / 1657 : 180420 -- argon 42 (Ar-42) + + Pointers : 176077 -1000000 + Primary type : Decay + Nuclide ZAI : 180420 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 41.96309 + Atomic weight ratio (AWR) : 41.60260 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.04E+09 seconds (33 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 190420 : beta- + + Nuclide 382 / 1657 : 180430 -- argon 43 (Ar-43) + + Pointers : 176294 -1000000 + Primary type : Decay + Nuclide ZAI : 180430 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 42.96560 + Atomic weight ratio (AWR) : 42.59650 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.22E+02 seconds (5.37 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.61600E+00 MeV frac = 1.00000E+00 Product nuclide = 190430 : beta- + + Nuclide 383 / 1657 : 190380 -- potassium 38 (K-38) + + Pointers : 177687 -1000000 + Primary type : Decay + Nuclide ZAI : 190380 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 37.96907 + Atomic weight ratio (AWR) : 37.64290 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.57E+02 seconds (7.61 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 5.91300E+00 MeV frac = 1.00000E+00 Product nuclide = 18038.82c : EC/beta+ + + Nuclide 384 / 1657 : 190420 -- potassium 42 (K-42) + + Pointers : 182975 -1000000 + Primary type : Decay + Nuclide ZAI : 190420 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 41.96238 + Atomic weight ratio (AWR) : 41.60190 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.45E+04 seconds (12.4 hours) + Specific ingestion toxicity : 4.30E-10 Sv/Bq + Specific inhalation toxicity : 1.20E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.52540E+00 MeV frac = 1.00000E+00 Product nuclide = 20042.82c : beta- + + Nuclide 385 / 1657 : 190430 -- potassium 43 (K-43) + + Pointers : 183472 -1000000 + Primary type : Decay + Nuclide ZAI : 190430 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 42.96076 + Atomic weight ratio (AWR) : 42.59170 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.99E+04 seconds (22.2 hours) + Specific ingestion toxicity : 2.50E-10 Sv/Bq + Specific inhalation toxicity : 1.40E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.81700E+00 MeV frac = 1.00000E+00 Product nuclide = 20043.82c : beta- + + Nuclide 386 / 1657 : 190440 -- potassium 44 (K-44) + + Pointers : 184109 -1000000 + Primary type : Decay + Nuclide ZAI : 190440 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 43.96155 + Atomic weight ratio (AWR) : 43.58390 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.33E+03 seconds (22.1 minutes) + Specific ingestion toxicity : 8.40E-11 Sv/Bq + Specific inhalation toxicity : 2.00E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.65900E+00 MeV frac = 1.00000E+00 Product nuclide = 20044.82c : beta- + + Nuclide 387 / 1657 : 190500 -- potassium 50 (K-50) + + Pointers : 187546 -1000000 + Primary type : Decay + Nuclide ZAI : 190500 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 49.97279 + Atomic weight ratio (AWR) : 49.54350 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.472 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.42210E+01 MeV frac = 7.10000E-01 Product nuclide = 200500 : beta- + 2 RTYP = 15 Q = 7.86770E+00 MeV frac = 2.90000E-01 Product nuclide = 200490 : beta- + neutron emission + + Nuclide 388 / 1657 : 190510 -- potassium 51 (K-51) + + Pointers : 187803 -1000000 + Primary type : Decay + Nuclide ZAI : 190510 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 50.97641 + Atomic weight ratio (AWR) : 50.53850 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.365 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.38600E+01 MeV frac = 5.30000E-01 Product nuclide = 200510 : beta- + 2 RTYP = 15 Q = 9.49970E+00 MeV frac = 4.70000E-01 Product nuclide = 200500 : beta- + neutron emission + + Nuclide 389 / 1657 : 200400 -- calcium 40 (Ca-40) + + Pointers : 188060 -1000000 + Primary type : Decay + Nuclide ZAI : 200400 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 39.96260 + Atomic weight ratio (AWR) : 39.61930 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 390 / 1657 : 200410 -- calcium 41 (Ca-41) + + Pointers : 188166 -1000000 + Primary type : Decay + Nuclide ZAI : 200410 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 40.96229 + Atomic weight ratio (AWR) : 40.61040 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.16E+12 seconds (100,266 years) + Specific ingestion toxicity : 1.90E-10 Sv/Bq + Specific inhalation toxicity : 1.80E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 4.21630E-01 MeV frac = 1.00000E+00 Product nuclide = 19041.82c : EC/beta+ + + Nuclide 391 / 1657 : 200450 -- calcium 45 (Ca-45) + + Pointers : 211009 -1000000 + Primary type : Decay + Nuclide ZAI : 200450 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 44.95620 + Atomic weight ratio (AWR) : 44.57000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.41E+07 seconds (163 days) + Specific ingestion toxicity : 7.10E-10 Sv/Bq + Specific inhalation toxicity : 3.70E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 2.58000E-01 MeV frac = 9.99980E-01 Product nuclide = 21045.82c : beta- + 2 RTYP = 1 Q = 2.45600E-01 MeV frac = 2.00000E-05 Product nuclide = 210451 : beta- + + Nuclide 392 / 1657 : 200460 -- calcium 46 (Ca-46) + + Pointers : 211313 -1000000 + Primary type : Decay + Nuclide ZAI : 200460 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 45.95367 + Atomic weight ratio (AWR) : 45.55890 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 393 / 1657 : 200470 -- calcium 47 (Ca-47) + + Pointers : 211419 -1000000 + Primary type : Decay + Nuclide ZAI : 200470 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 46.95456 + Atomic weight ratio (AWR) : 46.55120 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.92E+05 seconds (4.54 days) + Specific ingestion toxicity : 1.60E-09 Sv/Bq + Specific inhalation toxicity : 2.10E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.98800E+00 MeV frac = 1.00000E+00 Product nuclide = 210470 : beta- + + Nuclide 394 / 1657 : 200480 -- calcium 48 (Ca-48) + + Pointers : 211916 -1000000 + Primary type : Decay + Nuclide ZAI : 200480 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 47.95254 + Atomic weight ratio (AWR) : 47.54060 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.67E+27 seconds (5.3E+19 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 11 Q = 4.27370E+00 MeV frac = 5.00000E-01 Product nuclide = 22048.82c : beta- + beta- + 2 RTYP = 1 Q = 2.82002E-01 MeV frac = 5.00000E-01 Product nuclide = 210480 : beta- + + Nuclide 395 / 1657 : 200490 -- calcium 49 (Ca-49) + + Pointers : 212173 -1000000 + Primary type : Decay + Nuclide ZAI : 200490 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 48.95566 + Atomic weight ratio (AWR) : 48.53510 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.23E+02 seconds (8.72 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.26800E+00 MeV frac = 1.00000E+00 Product nuclide = 210490 : beta- + + Nuclide 396 / 1657 : 200500 -- calcium 50 (Ca-50) + + Pointers : 212628 -1000000 + Primary type : Decay + Nuclide ZAI : 200500 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 49.95756 + Atomic weight ratio (AWR) : 49.52840 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 13.9 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.70911E+00 MeV frac = 1.00000E+00 Product nuclide = 210501 : beta- + + Nuclide 397 / 1657 : 200510 -- calcium 51 (Ca-51) + + Pointers : 212812 -1000000 + Primary type : Decay + Nuclide ZAI : 200510 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 50.96149 + Atomic weight ratio (AWR) : 50.52370 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 10 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.35800E+00 MeV frac = 1.00000E+00 Product nuclide = 210510 : beta- + + Nuclide 398 / 1657 : 200520 -- calcium 52 (Ca-52) + + Pointers : 212996 -1000000 + Primary type : Decay + Nuclide ZAI : 200520 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 51.96511 + Atomic weight ratio (AWR) : 51.51870 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.6 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 7.85000E+00 MeV frac = 9.80000E-01 Product nuclide = 210520 : beta- + 2 RTYP = 15 Q = 2.63670E+00 MeV frac = 2.00000E-02 Product nuclide = 210510 : beta- + neutron emission + + Nuclide 399 / 1657 : 200530 -- calcium 53 (Ca-53) + + Pointers : 213253 -1000000 + Primary type : Decay + Nuclide ZAI : 200530 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 52.97004 + Atomic weight ratio (AWR) : 52.51500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 90 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 9.72000E+00 MeV frac = 7.00000E-01 Product nuclide = 210530 : beta- + 2 RTYP = 15 Q = 4.38870E+00 MeV frac = 3.00000E-01 Product nuclide = 210520 : beta- + neutron emission + + Nuclide 400 / 1657 : 200540 -- calcium 54 (Ca-54) + + Pointers : 213510 -1000000 + Primary type : Decay + Nuclide ZAI : 200540 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 53.97437 + Atomic weight ratio (AWR) : 53.51070 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 50 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.03300E+01 MeV frac = 1.00000E+00 Product nuclide = 210540 : beta- + + Nuclide 401 / 1657 : 210440 -- scandium 44 (Sc-44) + + Pointers : 213694 -1000000 + Primary type : Decay + Nuclide ZAI : 210440 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 43.95943 + Atomic weight ratio (AWR) : 43.58180 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.43E+04 seconds (3.97 hours) + Specific ingestion toxicity : 3.50E-10 Sv/Bq + Specific inhalation toxicity : 1.80E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 3.65330E+00 MeV frac = 1.00000E+00 Product nuclide = 20044.82c : EC/beta+ + + Nuclide 402 / 1657 : 210451 -- scandium 45m (Sc-45m) + + Pointers : 222177 -1000000 + Primary type : Decay + Nuclide ZAI : 210451 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 44.95589 + Atomic weight ratio (AWR) : 44.56970 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.325 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.24000E-02 MeV frac = 1.00000E+00 Product nuclide = 21045.82c : IT + + Nuclide 403 / 1657 : 210460 -- scandium 46 (Sc-46) + + Pointers : 222534 -1000000 + Primary type : Decay + Nuclide ZAI : 210460 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 45.95518 + Atomic weight ratio (AWR) : 45.56040 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.24E+06 seconds (83.8 days) + Specific ingestion toxicity : 1.50E-09 Sv/Bq + Specific inhalation toxicity : 6.80E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.36650E+00 MeV frac = 1.00000E+00 Product nuclide = 22046.82c : beta- + + Nuclide 404 / 1657 : 210461 -- scandium 46m (Sc-46m) + + Pointers : 223073 -1000000 + Primary type : Decay + Nuclide ZAI : 210461 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 45.95518 + Atomic weight ratio (AWR) : 45.56040 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 18.7 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.42530E-01 MeV frac = 1.00000E+00 Product nuclide = 210460 : IT + + Nuclide 405 / 1657 : 210470 -- scandium 47 (Sc-47) + + Pointers : 223430 -1000000 + Primary type : Decay + Nuclide ZAI : 210470 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 46.95245 + Atomic weight ratio (AWR) : 46.54910 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.89E+05 seconds (3.35 days) + Specific ingestion toxicity : 5.40E-10 Sv/Bq + Specific inhalation toxicity : 7.30E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.00800E-01 MeV frac = 1.00000E+00 Product nuclide = 22047.82c : beta- + + Nuclide 406 / 1657 : 210480 -- scandium 48 (Sc-48) + + Pointers : 223829 -1000000 + Primary type : Decay + Nuclide ZAI : 210480 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 47.95224 + Atomic weight ratio (AWR) : 47.54030 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.57E+05 seconds (1.82 days) + Specific ingestion toxicity : 1.70E-09 Sv/Bq + Specific inhalation toxicity : 1.10E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.99000E+00 MeV frac = 1.00000E+00 Product nuclide = 22048.82c : beta- + + Nuclide 407 / 1657 : 210490 -- scandium 49 (Sc-49) + + Pointers : 224144 -1000000 + Primary type : Decay + Nuclide ZAI : 210490 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 48.95001 + Atomic weight ratio (AWR) : 48.52950 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.43E+03 seconds (57.2 minutes) + Specific ingestion toxicity : 8.20E-11 Sv/Bq + Specific inhalation toxicity : 4.00E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.00400E+00 MeV frac = 1.00000E+00 Product nuclide = 22049.82c : beta- + + Nuclide 408 / 1657 : 210500 -- scandium 50 (Sc-50) + + Pointers : 224431 -1000000 + Primary type : Decay + Nuclide ZAI : 210500 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 49.95222 + Atomic weight ratio (AWR) : 49.52310 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.02E+02 seconds (1.71 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.88800E+00 MeV frac = 1.00000E+00 Product nuclide = 22050.82c : beta- + + Nuclide 409 / 1657 : 210501 -- scandium 50m (Sc-50m) + + Pointers : 224900 -1000000 + Primary type : Decay + Nuclide ZAI : 210501 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 49.95222 + Atomic weight ratio (AWR) : 49.52310 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.35 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 7.14500E+00 MeV frac = 1.25000E-02 Product nuclide = 22050.82c : beta- + 2 RTYP = 3 Q = 2.56895E-01 MeV frac = 9.87500E-01 Product nuclide = 210500 : IT + + Nuclide 410 / 1657 : 210510 -- scandium 51 (Sc-51) + + Pointers : 225358 -1000000 + Primary type : Decay + Nuclide ZAI : 210510 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 50.95362 + Atomic weight ratio (AWR) : 50.51590 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 12.4 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.51000E+00 MeV frac = 1.00000E+00 Product nuclide = 220510 : beta- + + Nuclide 411 / 1657 : 210520 -- scandium 52 (Sc-52) + + Pointers : 226149 -1000000 + Primary type : Decay + Nuclide ZAI : 210520 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 51.95664 + Atomic weight ratio (AWR) : 51.51030 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.11000E+00 MeV frac = 1.00000E+00 Product nuclide = 220520 : beta- + + Nuclide 412 / 1657 : 210530 -- scandium 53 (Sc-53) + + Pointers : 226814 -1000000 + Primary type : Decay + Nuclide ZAI : 210530 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 52.95965 + Atomic weight ratio (AWR) : 52.50470 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.21000E+00 MeV frac = 1.00000E+00 Product nuclide = 220530 : beta- + + Nuclide 413 / 1657 : 210540 -- scandium 54 (Sc-54) + + Pointers : 226998 -1000000 + Primary type : Decay + Nuclide ZAI : 210540 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 53.96327 + Atomic weight ratio (AWR) : 53.49970 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.26 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.13700E+01 MeV frac = 1.00000E+00 Product nuclide = 220540 : beta- + + Nuclide 414 / 1657 : 210550 -- scandium 55 (Sc-55) + + Pointers : 227182 -1000000 + Primary type : Decay + Nuclide ZAI : 210550 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 54.96821 + Atomic weight ratio (AWR) : 54.49600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.12 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.20900E+01 MeV frac = 1.00000E+00 Product nuclide = 220550 : beta- + + Nuclide 415 / 1657 : 210560 -- scandium 56 (Sc-56) + + Pointers : 227366 -1000000 + Primary type : Decay + Nuclide ZAI : 210560 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 55.97284 + Atomic weight ratio (AWR) : 55.49200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 80 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.36700E+01 MeV frac = 1.00000E+00 Product nuclide = 220560 : beta- + + Nuclide 416 / 1657 : 210570 -- scandium 57 (Sc-57) + + Pointers : 227550 -1000000 + Primary type : Decay + Nuclide ZAI : 210570 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 56.97777 + Atomic weight ratio (AWR) : 56.48830 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 13 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.28500E+01 MeV frac = 6.70000E-01 Product nuclide = 220570 : beta- + 2 RTYP = 15 Q = 1.01787E+01 MeV frac = 3.30000E-01 Product nuclide = 220560 : beta- + neutron emission + + Nuclide 417 / 1657 : 220450 -- titanium 45 (Ti-45) + + Pointers : 227807 -1000000 + Primary type : Decay + Nuclide ZAI : 220450 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 44.95811 + Atomic weight ratio (AWR) : 44.57190 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.11E+04 seconds (3.08 hours) + Specific ingestion toxicity : 1.50E-10 Sv/Bq + Specific inhalation toxicity : 9.30E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 2.06260E+00 MeV frac = 1.00000E+00 Product nuclide = 21045.82c : EC/beta+ + + Nuclide 418 / 1657 : 220510 -- titanium 51 (Ti-51) + + Pointers : 261852 -1000000 + Primary type : Decay + Nuclide ZAI : 220510 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 50.94666 + Atomic weight ratio (AWR) : 50.50900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.48E+02 seconds (5.8 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.47260E+00 MeV frac = 1.00000E+00 Product nuclide = 230510 : beta- + + Nuclide 419 / 1657 : 220520 -- titanium 52 (Ti-52) + + Pointers : 262265 -1000000 + Primary type : Decay + Nuclide ZAI : 220520 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 51.94685 + Atomic weight ratio (AWR) : 51.50060 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.02E+02 seconds (1.7 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.97600E+00 MeV frac = 1.00000E+00 Product nuclide = 230520 : beta- + + Nuclide 420 / 1657 : 220530 -- titanium 53 (Ti-53) + + Pointers : 262524 -1000000 + Primary type : Decay + Nuclide ZAI : 220530 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 52.94977 + Atomic weight ratio (AWR) : 52.49490 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 32.7 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.01900E+00 MeV frac = 1.00000E+00 Product nuclide = 230530 : beta- + + Nuclide 421 / 1657 : 220540 -- titanium 54 (Ti-54) + + Pointers : 262708 -1000000 + Primary type : Decay + Nuclide ZAI : 220540 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 53.95107 + Atomic weight ratio (AWR) : 53.48760 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.30100E+00 MeV frac = 1.00000E+00 Product nuclide = 230540 : beta- + + Nuclide 422 / 1657 : 220550 -- titanium 55 (Ti-55) + + Pointers : 262892 -1000000 + Primary type : Decay + Nuclide ZAI : 220550 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 54.95530 + Atomic weight ratio (AWR) : 54.48320 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.49 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.48000E+00 MeV frac = 1.00000E+00 Product nuclide = 230550 : beta- + + Nuclide 423 / 1657 : 220560 -- titanium 56 (Ti-56) + + Pointers : 263076 -1000000 + Primary type : Decay + Nuclide ZAI : 220560 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 55.95821 + Atomic weight ratio (AWR) : 55.47750 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.164 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.14000E+00 MeV frac = 1.00000E+00 Product nuclide = 230560 : beta- + + Nuclide 424 / 1657 : 220570 -- titanium 57 (Ti-57) + + Pointers : 263260 -1000000 + Primary type : Decay + Nuclide ZAI : 220570 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 56.96395 + Atomic weight ratio (AWR) : 56.47460 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 60 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.06500E+01 MeV frac = 9.97000E-01 Product nuclide = 230570 : beta- + 2 RTYP = 15 Q = 4.46870E+00 MeV frac = 3.00000E-03 Product nuclide = 230560 : beta- + neutron emission + + Nuclide 425 / 1657 : 220580 -- titanium 58 (Ti-58) + + Pointers : 263517 -1000000 + Primary type : Decay + Nuclide ZAI : 220580 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 57.96697 + Atomic weight ratio (AWR) : 57.46900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 54 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.44000E+00 MeV frac = 1.00000E+00 Product nuclide = 230580 : beta- + + Nuclide 426 / 1657 : 220590 -- titanium 59 (Ti-59) + + Pointers : 263701 -1000000 + Primary type : Decay + Nuclide ZAI : 220590 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 58.97291 + Atomic weight ratio (AWR) : 58.46630 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 30 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.18500E+01 MeV frac = 1.00000E+00 Product nuclide = 230590 : beta- + + Nuclide 427 / 1657 : 220600 -- titanium 60 (Ti-60) + + Pointers : 263885 -1000000 + Primary type : Decay + Nuclide ZAI : 220600 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 59.97673 + Atomic weight ratio (AWR) : 59.46150 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 22 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.09300E+01 MeV frac = 1.00000E+00 Product nuclide = 230600 : beta- + + Nuclide 428 / 1657 : 220610 -- titanium 61 (Ti-61) + + Pointers : 264069 -1000000 + Primary type : Decay + Nuclide ZAI : 220610 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 60.98318 + Atomic weight ratio (AWR) : 60.45930 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 10 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.37100E+01 MeV frac = 1.00000E+00 Product nuclide = 230610 : beta- + + Nuclide 429 / 1657 : 230490 -- vanadium 49 (V-49) + + Pointers : 264253 -1000000 + Primary type : Decay + Nuclide ZAI : 230490 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 48.94849 + Atomic weight ratio (AWR) : 48.52800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.85E+07 seconds (330 days) + Specific ingestion toxicity : 1.80E-11 Sv/Bq + Specific inhalation toxicity : 3.40E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 6.02000E-01 MeV frac = 1.00000E+00 Product nuclide = 22049.82c : EC/beta+ + + Nuclide 430 / 1657 : 230500 -- vanadium 50 (V-50) + + Pointers : 264554 -1000000 + Primary type : Decay + Nuclide ZAI : 230500 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 49.94717 + Atomic weight ratio (AWR) : 49.51810 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.42E+24 seconds (1.4E+17 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.03790E+00 MeV frac = 1.70000E-01 Product nuclide = 24050.82c : beta- + 2 RTYP = 2 Q = 2.20510E+00 MeV frac = 8.30000E-01 Product nuclide = 22050.82c : EC/beta+ + + Nuclide 431 / 1657 : 230510 -- vanadium 51 (V-51) + + Pointers : 264970 -1000000 + Primary type : Decay + Nuclide ZAI : 230510 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 50.94394 + Atomic weight ratio (AWR) : 50.50630 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 432 / 1657 : 230520 -- vanadium 52 (V-52) + + Pointers : 265076 -1000000 + Primary type : Decay + Nuclide ZAI : 230520 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 51.94473 + Atomic weight ratio (AWR) : 51.49850 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.25E+02 seconds (3.74 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.97570E+00 MeV frac = 1.00000E+00 Product nuclide = 24052.82c : beta- + + Nuclide 433 / 1657 : 230530 -- vanadium 53 (V-53) + + Pointers : 265853 -1000000 + Primary type : Decay + Nuclide ZAI : 230530 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 52.94432 + Atomic weight ratio (AWR) : 52.48950 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.72E+01 seconds (1.62 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.43600E+00 MeV frac = 1.00000E+00 Product nuclide = 24053.82c : beta- + + Nuclide 434 / 1657 : 230540 -- vanadium 54 (V-54) + + Pointers : 266210 -1000000 + Primary type : Decay + Nuclide ZAI : 230540 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 53.94643 + Atomic weight ratio (AWR) : 53.48300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 49.8 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.04200E+00 MeV frac = 1.00000E+00 Product nuclide = 24054.82c : beta- + + Nuclide 435 / 1657 : 230550 -- vanadium 55 (V-55) + + Pointers : 266875 -1000000 + Primary type : Decay + Nuclide ZAI : 230550 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 54.94723 + Atomic weight ratio (AWR) : 54.47520 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.54 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.98000E+00 MeV frac = 1.00000E+00 Product nuclide = 240550 : beta- + + Nuclide 436 / 1657 : 230560 -- vanadium 56 (V-56) + + Pointers : 267344 -1000000 + Primary type : Decay + Nuclide ZAI : 230560 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 55.95054 + Atomic weight ratio (AWR) : 55.46990 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.216 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.20120E+00 MeV frac = 1.00000E+00 Product nuclide = 240560 : beta- + + Nuclide 437 / 1657 : 230570 -- vanadium 57 (V-57) + + Pointers : 267528 -1000000 + Primary type : Decay + Nuclide ZAI : 230570 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 56.95255 + Atomic weight ratio (AWR) : 56.46330 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.35 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.33410E+00 MeV frac = 9.96000E-01 Product nuclide = 240570 : beta- + 2 RTYP = 15 Q = 3.01990E+00 MeV frac = 4.00000E-03 Product nuclide = 240560 : beta- + neutron emission + + Nuclide 438 / 1657 : 230580 -- vanadium 58 (V-58) + + Pointers : 267785 -1000000 + Primary type : Decay + Nuclide ZAI : 230580 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 57.95688 + Atomic weight ratio (AWR) : 57.45900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.191 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.16200E+01 MeV frac = 2.00000E-01 Product nuclide = 240580 : beta- + 2 RTYP = 15 Q = 4.24280E+00 MeV frac = 8.00000E-01 Product nuclide = 240570 : beta- + neutron emission + + Nuclide 439 / 1657 : 230590 -- vanadium 59 (V-59) + + Pointers : 268042 -1000000 + Primary type : Decay + Nuclide ZAI : 230590 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 58.96020 + Atomic weight ratio (AWR) : 58.45370 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 75 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.08200E+01 MeV frac = 1.00000E+00 Product nuclide = 240590 : beta- + + Nuclide 440 / 1657 : 230600 -- vanadium 60 (V-60) + + Pointers : 268226 -1000000 + Primary type : Decay + Nuclide ZAI : 230600 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 59.96503 + Atomic weight ratio (AWR) : 59.44990 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.122 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.39200E+01 MeV frac = 1.00000E+00 Product nuclide = 240600 : beta- + + Nuclide 441 / 1657 : 230610 -- vanadium 61 (V-61) + + Pointers : 268410 -1000000 + Primary type : Decay + Nuclide ZAI : 230610 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 60.96845 + Atomic weight ratio (AWR) : 60.44470 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 47 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.28200E+01 MeV frac = 9.40000E-01 Product nuclide = 240610 : beta- + 2 RTYP = 15 Q = 9.06870E+00 MeV frac = 6.00000E-02 Product nuclide = 240600 : beta- + neutron emission + + Nuclide 442 / 1657 : 230620 -- vanadium 62 (V-62) + + Pointers : 268667 -1000000 + Primary type : Decay + Nuclide ZAI : 230620 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 61.97379 + Atomic weight ratio (AWR) : 61.44140 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 33.5 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.59900E+01 MeV frac = 1.00000E+00 Product nuclide = 240620 : beta- + + Nuclide 443 / 1657 : 230630 -- vanadium 63 (V-63) + + Pointers : 268851 -1000000 + Primary type : Decay + Nuclide ZAI : 230630 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 62.97751 + Atomic weight ratio (AWR) : 62.43650 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 17 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.46200E+01 MeV frac = 6.50000E-01 Product nuclide = 240630 : beta- + 2 RTYP = 15 Q = 1.14287E+01 MeV frac = 3.50000E-01 Product nuclide = 240620 : beta- + neutron emission + + Nuclide 444 / 1657 : 230640 -- vanadium 64 (V-64) + + Pointers : 269108 -1000000 + Primary type : Decay + Nuclide ZAI : 230640 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 63.98345 + Atomic weight ratio (AWR) : 63.43380 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 10 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.77500E+01 MeV frac = 1.00000E+00 Product nuclide = 240640 : beta- + + Nuclide 445 / 1657 : 230650 -- vanadium 65 (V-65) + + Pointers : 269292 -1000000 + Primary type : Decay + Nuclide ZAI : 230650 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 64.98788 + Atomic weight ratio (AWR) : 64.42960 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 10 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.65500E+01 MeV frac = 1.00000E+00 Product nuclide = 240650 : beta- + + Nuclide 446 / 1657 : 240490 -- chromium 49 (Cr-49) + + Pointers : 269476 -1000000 + Primary type : Decay + Nuclide ZAI : 240490 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 48.95132 + Atomic weight ratio (AWR) : 48.53080 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.51E+03 seconds (41.9 minutes) + Specific ingestion toxicity : 6.10E-11 Sv/Bq + Specific inhalation toxicity : 3.50E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 2.62800E+00 MeV frac = 1.00000E+00 Product nuclide = 230490 : EC/beta+ + + Nuclide 447 / 1657 : 240510 -- chromium 51 (Cr-51) + + Pointers : 272094 -1000000 + Primary type : Decay + Nuclide ZAI : 240510 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 50.94474 + Atomic weight ratio (AWR) : 50.50710 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.39E+06 seconds (27.7 days) + Specific ingestion toxicity : 3.80E-11 Sv/Bq + Specific inhalation toxicity : 3.70E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 7.52620E-01 MeV frac = 1.00000E+00 Product nuclide = 230510 : EC/beta+ + + Nuclide 448 / 1657 : 240550 -- chromium 55 (Cr-55) + + Pointers : 278638 -1000000 + Primary type : Decay + Nuclide ZAI : 240550 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 54.94087 + Atomic weight ratio (AWR) : 54.46890 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.12E+02 seconds (3.54 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.60320E+00 MeV frac = 1.00000E+00 Product nuclide = 25055.82c : beta- + + Nuclide 449 / 1657 : 240560 -- chromium 56 (Cr-56) + + Pointers : 279149 -1000000 + Primary type : Decay + Nuclide ZAI : 240560 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 55.94066 + Atomic weight ratio (AWR) : 55.46010 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.56E+02 seconds (5.94 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.62850E+00 MeV frac = 1.00000E+00 Product nuclide = 250560 : beta- + + Nuclide 450 / 1657 : 240570 -- chromium 57 (Cr-57) + + Pointers : 279548 -1000000 + Primary type : Decay + Nuclide ZAI : 240570 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 56.94358 + Atomic weight ratio (AWR) : 56.45440 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 21.1 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.09000E+00 MeV frac = 1.00000E+00 Product nuclide = 250570 : beta- + + Nuclide 451 / 1657 : 240580 -- chromium 58 (Cr-58) + + Pointers : 280409 -1000000 + Primary type : Decay + Nuclide ZAI : 240580 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 57.94437 + Atomic weight ratio (AWR) : 57.44660 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.08000E+00 MeV frac = 1.00000E+00 Product nuclide = 250580 : beta- + + Nuclide 452 / 1657 : 240590 -- chromium 59 (Cr-59) + + Pointers : 280593 -1000000 + Primary type : Decay + Nuclide ZAI : 240590 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 58.94860 + Atomic weight ratio (AWR) : 58.44220 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.46 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.59000E+00 MeV frac = 1.00000E+00 Product nuclide = 250590 : beta- + + Nuclide 453 / 1657 : 240600 -- chromium 60 (Cr-60) + + Pointers : 280777 -1000000 + Primary type : Decay + Nuclide ZAI : 240600 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 59.95010 + Atomic weight ratio (AWR) : 59.43510 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.56 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.68000E+00 MeV frac = 1.00000E+00 Product nuclide = 250600 : beta- + + Nuclide 454 / 1657 : 240610 -- chromium 61 (Cr-61) + + Pointers : 280961 -1000000 + Primary type : Decay + Nuclide ZAI : 240610 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 60.95473 + Atomic weight ratio (AWR) : 60.43110 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.261 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.38000E+00 MeV frac = 1.00000E+00 Product nuclide = 250610 : beta- + + Nuclide 455 / 1657 : 240620 -- chromium 62 (Cr-62) + + Pointers : 281145 -1000000 + Primary type : Decay + Nuclide ZAI : 240620 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 61.95664 + Atomic weight ratio (AWR) : 61.42440 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.199 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 7.63000E+00 MeV frac = 5.00000E-01 Product nuclide = 250620 : beta- + 2 RTYP = 1 Q = 7.62900E+00 MeV frac = 5.00000E-01 Product nuclide = 250621 : beta- + + Nuclide 456 / 1657 : 240630 -- chromium 63 (Cr-63) + + Pointers : 281402 -1000000 + Primary type : Decay + Nuclide ZAI : 240630 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 62.96188 + Atomic weight ratio (AWR) : 62.42100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.129 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.08200E+01 MeV frac = 1.00000E+00 Product nuclide = 250630 : beta- + + Nuclide 457 / 1657 : 240640 -- chromium 64 (Cr-64) + + Pointers : 281586 -1000000 + Primary type : Decay + Nuclide ZAI : 240640 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 63.96439 + Atomic weight ratio (AWR) : 63.41490 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 43 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.47000E+00 MeV frac = 1.00000E+00 Product nuclide = 250640 : beta- + + Nuclide 458 / 1657 : 240650 -- chromium 65 (Cr-65) + + Pointers : 281770 -1000000 + Primary type : Decay + Nuclide ZAI : 240650 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 64.97013 + Atomic weight ratio (AWR) : 64.41200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 27 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.28700E+01 MeV frac = 1.00000E+00 Product nuclide = 250650 : beta- + + Nuclide 459 / 1657 : 240660 -- chromium 66 (Cr-66) + + Pointers : 281954 -1000000 + Primary type : Decay + Nuclide ZAI : 240660 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 65.97335 + Atomic weight ratio (AWR) : 65.40660 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 10 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.14500E+01 MeV frac = 1.00000E+00 Product nuclide = 250660 : beta- + + Nuclide 460 / 1657 : 240670 -- chromium 67 (Cr-67) + + Pointers : 282138 -1000000 + Primary type : Decay + Nuclide ZAI : 240670 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 66.97959 + Atomic weight ratio (AWR) : 66.40420 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 10 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.43500E+01 MeV frac = 1.00000E+00 Product nuclide = 250670 : beta- + + Nuclide 461 / 1657 : 250520 -- manganese 52 (Mn-52) + + Pointers : 282322 -1000000 + Primary type : Decay + Nuclide ZAI : 250520 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 51.94554 + Atomic weight ratio (AWR) : 51.49930 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.83E+05 seconds (5.59 days) + Specific ingestion toxicity : 1.80E-09 Sv/Bq + Specific inhalation toxicity : 1.40E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 4.71170E+00 MeV frac = 1.00000E+00 Product nuclide = 24052.82c : EC/beta+ + + Nuclide 462 / 1657 : 250530 -- manganese 53 (Mn-53) + + Pointers : 282945 -1000000 + Primary type : Decay + Nuclide ZAI : 250530 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 52.94129 + Atomic weight ratio (AWR) : 52.48650 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.16E+14 seconds (3.68 million years) + Specific ingestion toxicity : 3.00E-11 Sv/Bq + Specific inhalation toxicity : 5.40E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 5.96100E-01 MeV frac = 1.00000E+00 Product nuclide = 24053.82c : EC/beta+ + + Nuclide 463 / 1657 : 250540 -- manganese 54 (Mn-54) + + Pointers : 283246 -1000000 + Primary type : Decay + Nuclide ZAI : 250540 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 53.94038 + Atomic weight ratio (AWR) : 53.47700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.70E+07 seconds (312 days) + Specific ingestion toxicity : 7.10E-10 Sv/Bq + Specific inhalation toxicity : 1.50E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 1.37720E+00 MeV frac = 1.00000E+00 Product nuclide = 24054.82c : EC/beta+ + + Nuclide 464 / 1657 : 250560 -- manganese 56 (Mn-56) + + Pointers : 286735 -1000000 + Primary type : Decay + Nuclide ZAI : 250560 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 55.93895 + Atomic weight ratio (AWR) : 55.45840 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.28E+03 seconds (2.58 hours) + Specific ingestion toxicity : 2.50E-10 Sv/Bq + Specific inhalation toxicity : 1.20E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.69550E+00 MeV frac = 1.00000E+00 Product nuclide = 26056.82c : beta- + + Nuclide 465 / 1657 : 250570 -- manganese 57 (Mn-57) + + Pointers : 287442 -1000000 + Primary type : Decay + Nuclide ZAI : 250570 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 56.93833 + Atomic weight ratio (AWR) : 56.44920 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.54E+01 seconds (1.42 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.69100E+00 MeV frac = 1.00000E+00 Product nuclide = 26057.82c : beta- + + Nuclide 466 / 1657 : 250580 -- manganese 58 (Mn-58) + + Pointers : 288275 -1000000 + Primary type : Decay + Nuclide ZAI : 250580 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 57.94004 + Atomic weight ratio (AWR) : 57.44230 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.52E+01 seconds (1.09 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.24700E+00 MeV frac = 1.00000E+00 Product nuclide = 26058.82c : beta- + + Nuclide 467 / 1657 : 250581 -- manganese 58m (Mn-58m) + + Pointers : 289654 -1000000 + Primary type : Decay + Nuclide ZAI : 250581 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 57.94004 + Atomic weight ratio (AWR) : 57.44230 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.7 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.32000E+00 MeV frac = 1.00000E+00 Product nuclide = 26058.82c : beta- + + Nuclide 468 / 1657 : 250590 -- manganese 59 (Mn-59) + + Pointers : 290221 -1000000 + Primary type : Decay + Nuclide ZAI : 250590 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 58.94043 + Atomic weight ratio (AWR) : 58.43410 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.59 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.18500E+00 MeV frac = 1.00000E+00 Product nuclide = 260590 : beta- + + Nuclide 469 / 1657 : 250600 -- manganese 60 (Mn-60) + + Pointers : 291040 -1000000 + Primary type : Decay + Nuclide ZAI : 250600 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 59.94294 + Atomic weight ratio (AWR) : 59.42800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 51 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.24000E+00 MeV frac = 1.00000E+00 Product nuclide = 260600 : beta- + + Nuclide 470 / 1657 : 250601 -- manganese 60m (Mn-60m) + + Pointers : 291257 -1000000 + Primary type : Decay + Nuclide ZAI : 250601 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 59.94294 + Atomic weight ratio (AWR) : 59.42800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.77 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.50390E+00 MeV frac = 8.85000E-01 Product nuclide = 260600 : beta- + 2 RTYP = 3 Q = 2.71900E-01 MeV frac = 1.15000E-01 Product nuclide = 250600 : IT + + Nuclide 471 / 1657 : 250610 -- manganese 61 (Mn-61) + + Pointers : 291514 -1000000 + Primary type : Decay + Nuclide ZAI : 250610 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 60.94465 + Atomic weight ratio (AWR) : 60.42110 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.67 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.18000E+00 MeV frac = 1.00000E+00 Product nuclide = 260610 : beta- + + Nuclide 472 / 1657 : 250620 -- manganese 62 (Mn-62) + + Pointers : 291857 -1000000 + Primary type : Decay + Nuclide ZAI : 250620 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 61.94847 + Atomic weight ratio (AWR) : 61.41630 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.88 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.04000E+01 MeV frac = 1.00000E+00 Product nuclide = 260620 : beta- + + Nuclide 473 / 1657 : 250621 -- manganese 62m (Mn-62m) + + Pointers : 292214 -1000000 + Primary type : Decay + Nuclide ZAI : 250621 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 61.94847 + Atomic weight ratio (AWR) : 61.41630 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 92 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.08620E+01 MeV frac = 1.00000E+00 Product nuclide = 260620 : beta- + + Nuclide 474 / 1657 : 250630 -- manganese 63 (Mn-63) + + Pointers : 292398 -1000000 + Primary type : Decay + Nuclide ZAI : 250630 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 62.95028 + Atomic weight ratio (AWR) : 62.40950 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.275 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.20000E+00 MeV frac = 1.00000E+00 Product nuclide = 260630 : beta- + + Nuclide 475 / 1657 : 250640 -- manganese 64 (Mn-64) + + Pointers : 292582 -1000000 + Primary type : Decay + Nuclide ZAI : 250640 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 63.95420 + Atomic weight ratio (AWR) : 63.40480 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 88.8 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.21500E+01 MeV frac = 1.00000E+00 Product nuclide = 260640 : beta- + + Nuclide 476 / 1657 : 250650 -- manganese 65 (Mn-65) + + Pointers : 292766 -1000000 + Primary type : Decay + Nuclide ZAI : 250650 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 64.95631 + Atomic weight ratio (AWR) : 64.39830 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 92 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.02100E+01 MeV frac = 1.00000E+00 Product nuclide = 260650 : beta- + + Nuclide 477 / 1657 : 250660 -- manganese 66 (Mn-66) + + Pointers : 292950 -1000000 + Primary type : Decay + Nuclide ZAI : 250660 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 65.96104 + Atomic weight ratio (AWR) : 65.39440 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 64.4 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.33200E+01 MeV frac = 1.00000E+00 Product nuclide = 260660 : beta- + + Nuclide 478 / 1657 : 250670 -- manganese 67 (Mn-67) + + Pointers : 293134 -1000000 + Primary type : Decay + Nuclide ZAI : 250670 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 66.96416 + Atomic weight ratio (AWR) : 66.38890 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 45 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.22900E+01 MeV frac = 1.00000E+00 Product nuclide = 260670 : beta- + + Nuclide 479 / 1657 : 250680 -- manganese 68 (Mn-68) + + Pointers : 293318 -1000000 + Primary type : Decay + Nuclide ZAI : 250680 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 67.96929 + Atomic weight ratio (AWR) : 67.38540 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 28 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.45300E+01 MeV frac = 1.00000E+00 Product nuclide = 260680 : beta- + + Nuclide 480 / 1657 : 250690 -- manganese 69 (Mn-69) + + Pointers : 293502 -1000000 + Primary type : Decay + Nuclide ZAI : 250690 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 68.97281 + Atomic weight ratio (AWR) : 68.38030 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 14 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.31000E+01 MeV frac = 7.60000E-01 Product nuclide = 260690 : beta- + 2 RTYP = 15 Q = 9.75870E+00 MeV frac = 2.40000E-01 Product nuclide = 260680 : beta- + neutron emission + + Nuclide 481 / 1657 : 260530 -- iron 53 (Fe-53) + + Pointers : 293759 -1000000 + Primary type : Decay + Nuclide ZAI : 260530 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 52.94533 + Atomic weight ratio (AWR) : 52.49050 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.11E+02 seconds (8.51 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 3.74360E+00 MeV frac = 1.00000E+00 Product nuclide = 250530 : EC/beta+ + + Nuclide 482 / 1657 : 260550 -- iron 55 (Fe-55) + + Pointers : 301886 -1000000 + Primary type : Decay + Nuclide ZAI : 260550 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 54.93825 + Atomic weight ratio (AWR) : 54.46630 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.67E+07 seconds (2.75 years) + Specific ingestion toxicity : 3.30E-10 Sv/Bq + Specific inhalation toxicity : 3.80E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 2.31210E-01 MeV frac = 1.00000E+00 Product nuclide = 25055.82c : EC/beta+ + + Nuclide 483 / 1657 : 260590 -- iron 59 (Fe-59) + + Pointers : 322974 -1000000 + Primary type : Decay + Nuclide ZAI : 260590 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 58.93488 + Atomic weight ratio (AWR) : 58.42860 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.84E+06 seconds (44.5 days) + Specific ingestion toxicity : 1.80E-09 Sv/Bq + Specific inhalation toxicity : 4.00E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.56500E+00 MeV frac = 1.00000E+00 Product nuclide = 27059.82c : beta- + + Nuclide 484 / 1657 : 260600 -- iron 60 (Fe-60) + + Pointers : 323835 -1000000 + Primary type : Decay + Nuclide ZAI : 260600 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 59.93407 + Atomic weight ratio (AWR) : 59.41920 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.73E+13 seconds (1.5 million years) + Specific ingestion toxicity : 1.10E-07 Sv/Bq + Specific inhalation toxicity : 2.80E-07 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.40000E-01 MeV frac = 1.00000E+00 Product nuclide = 270601 : beta- + + Nuclide 485 / 1657 : 260610 -- iron 61 (Fe-61) + + Pointers : 324052 -1000000 + Primary type : Decay + Nuclide ZAI : 260610 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 60.93678 + Atomic weight ratio (AWR) : 60.41330 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.59E+02 seconds (5.98 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.97740E+00 MeV frac = 1.00000E+00 Product nuclide = 270610 : beta- + + Nuclide 486 / 1657 : 260620 -- iron 62 (Fe-62) + + Pointers : 324236 -1000000 + Primary type : Decay + Nuclide ZAI : 260620 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 61.93677 + Atomic weight ratio (AWR) : 61.40470 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.80E+01 seconds (1.13 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.55300E+00 MeV frac = 1.00000E+00 Product nuclide = 270620 : beta- + + Nuclide 487 / 1657 : 260630 -- iron 63 (Fe-63) + + Pointers : 324481 -1000000 + Primary type : Decay + Nuclide ZAI : 260630 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 62.94009 + Atomic weight ratio (AWR) : 62.39940 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.1 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.05700E+00 MeV frac = 1.00000E+00 Product nuclide = 270630 : beta- + + Nuclide 488 / 1657 : 260640 -- iron 64 (Fe-64) + + Pointers : 325496 -1000000 + Primary type : Decay + Nuclide ZAI : 260640 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 63.94119 + Atomic weight ratio (AWR) : 63.39190 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.02000E+00 MeV frac = 1.00000E+00 Product nuclide = 270640 : beta- + + Nuclide 489 / 1657 : 260650 -- iron 65 (Fe-65) + + Pointers : 325783 -1000000 + Primary type : Decay + Nuclide ZAI : 260650 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 64.94542 + Atomic weight ratio (AWR) : 64.38750 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.29000E+00 MeV frac = 1.00000E+00 Product nuclide = 270650 : beta- + + Nuclide 490 / 1657 : 260660 -- iron 66 (Fe-66) + + Pointers : 325967 -1000000 + Primary type : Decay + Nuclide ZAI : 260660 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 65.94682 + Atomic weight ratio (AWR) : 65.38030 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.44 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.54000E+00 MeV frac = 1.00000E+00 Product nuclide = 270660 : beta- + + Nuclide 491 / 1657 : 260670 -- iron 67 (Fe-67) + + Pointers : 326151 -1000000 + Primary type : Decay + Nuclide ZAI : 260670 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 66.95094 + Atomic weight ratio (AWR) : 66.37580 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.394 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.37000E+00 MeV frac = 1.00000E+00 Product nuclide = 270670 : beta- + + Nuclide 492 / 1657 : 260680 -- iron 68 (Fe-68) + + Pointers : 326335 -1000000 + Primary type : Decay + Nuclide ZAI : 260680 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 67.95366 + Atomic weight ratio (AWR) : 67.36990 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.187 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.07000E+00 MeV frac = 1.00000E+00 Product nuclide = 270681 : beta- + + Nuclide 493 / 1657 : 260690 -- iron 69 (Fe-69) + + Pointers : 326519 -1000000 + Primary type : Decay + Nuclide ZAI : 260690 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 68.95879 + Atomic weight ratio (AWR) : 68.36640 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.109 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.16000E+01 MeV frac = 9.30000E-01 Product nuclide = 270690 : beta- + 2 RTYP = 15 Q = 4.72870E+00 MeV frac = 7.00000E-02 Product nuclide = 270681 : beta- + neutron emission + + Nuclide 494 / 1657 : 260700 -- iron 70 (Fe-70) + + Pointers : 326776 -1000000 + Primary type : Decay + Nuclide ZAI : 260700 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 69.96151 + Atomic weight ratio (AWR) : 69.36050 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 94 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.54000E+00 MeV frac = 1.00000E+00 Product nuclide = 270701 : beta- + + Nuclide 495 / 1657 : 260710 -- iron 71 (Fe-71) + + Pointers : 326960 -1000000 + Primary type : Decay + Nuclide ZAI : 260710 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 70.96674 + Atomic weight ratio (AWR) : 70.35710 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 30 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.28700E+01 MeV frac = 1.00000E+00 Product nuclide = 270710 : beta- + + Nuclide 496 / 1657 : 260720 -- iron 72 (Fe-72) + + Pointers : 327144 -1000000 + Primary type : Decay + Nuclide ZAI : 260720 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 71.96966 + Atomic weight ratio (AWR) : 71.35140 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 10 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 270720 : beta- + + Nuclide 497 / 1657 : 270560 -- cobalt 56 (Co-56) + + Pointers : 327328 -1000000 + Primary type : Decay + Nuclide ZAI : 270560 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 55.93985 + Atomic weight ratio (AWR) : 55.45930 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.67E+06 seconds (77.2 days) + Specific ingestion toxicity : 2.50E-09 Sv/Bq + Specific inhalation toxicity : 6.70E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 4.56600E+00 MeV frac = 1.00000E+00 Product nuclide = 26056.82c : EC/beta+ + + Nuclide 498 / 1657 : 270570 -- cobalt 57 (Co-57) + + Pointers : 328287 -1000000 + Primary type : Decay + Nuclide ZAI : 270570 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 56.93631 + Atomic weight ratio (AWR) : 56.44720 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.35E+07 seconds (272 days) + Specific ingestion toxicity : 2.10E-10 Sv/Bq + Specific inhalation toxicity : 1.00E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 8.36000E-01 MeV frac = 1.00000E+00 Product nuclide = 26057.82c : EC/beta+ + + Nuclide 499 / 1657 : 270580 -- cobalt 58 (Co-58) + + Pointers : 329106 -1000000 + Primary type : Decay + Nuclide ZAI : 270580 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 57.93580 + Atomic weight ratio (AWR) : 57.43810 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.12E+06 seconds (70.8 days) + Specific ingestion toxicity : 7.40E-10 Sv/Bq + Specific inhalation toxicity : 2.10E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 2.30790E+00 MeV frac = 1.00000E+00 Product nuclide = 26058.82c : EC/beta+ + + Nuclide 500 / 1657 : 270600 -- cobalt 60 (Co-60) + + Pointers : 333765 -1000000 + Primary type : Decay + Nuclide ZAI : 270600 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 59.93386 + Atomic weight ratio (AWR) : 59.41900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.66E+08 seconds (5.27 years) + Specific ingestion toxicity : 3.40E-09 Sv/Bq + Specific inhalation toxicity : 3.10E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.82307E+00 MeV frac = 1.00000E+00 Product nuclide = 28060.82c : beta- + + Nuclide 501 / 1657 : 270601 -- cobalt 60m (Co-60m) + + Pointers : 334360 -1000000 + Primary type : Decay + Nuclide ZAI : 270601 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 59.93386 + Atomic weight ratio (AWR) : 59.41900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.28E+02 seconds (10.5 minutes) + Specific ingestion toxicity : 1.70E-12 Sv/Bq + Specific inhalation toxicity : 1.40E-12 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 5.86030E-02 MeV frac = 9.97600E-01 Product nuclide = 270600 : IT + 2 RTYP = 1 Q = 2.88224E+00 MeV frac = 2.40000E-03 Product nuclide = 28060.82c : beta- + + Nuclide 502 / 1657 : 270610 -- cobalt 61 (Co-61) + + Pointers : 334846 -1000000 + Primary type : Decay + Nuclide ZAI : 270610 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 60.93244 + Atomic weight ratio (AWR) : 60.40900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.94E+03 seconds (1.65 hours) + Specific ingestion toxicity : 7.40E-11 Sv/Bq + Specific inhalation toxicity : 5.10E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.32170E+00 MeV frac = 1.00000E+00 Product nuclide = 28061.82c : beta- + + Nuclide 503 / 1657 : 270620 -- cobalt 62 (Co-62) + + Pointers : 335245 -1000000 + Primary type : Decay + Nuclide ZAI : 270620 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 61.93405 + Atomic weight ratio (AWR) : 61.40200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.24E+01 seconds (1.54 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.31500E+00 MeV frac = 1.00000E+00 Product nuclide = 28062.82c : beta- + + Nuclide 504 / 1657 : 270621 -- cobalt 62m (Co-62m) + + Pointers : 336204 -1000000 + Primary type : Decay + Nuclide ZAI : 270621 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 61.93405 + Atomic weight ratio (AWR) : 61.40200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.35E+02 seconds (13.9 minutes) + Specific ingestion toxicity : 4.70E-11 Sv/Bq + Specific inhalation toxicity : 2.10E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 5.33610E+00 MeV frac = 9.90000E-01 Product nuclide = 28062.82c : beta- + 2 RTYP = 3 Q = 2.20000E-02 MeV frac = 1.00000E-02 Product nuclide = 270620 : IT + + Nuclide 505 / 1657 : 270630 -- cobalt 63 (Co-63) + + Pointers : 336461 -1000000 + Primary type : Decay + Nuclide ZAI : 270630 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 62.93363 + Atomic weight ratio (AWR) : 62.39300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 27.4 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.67200E+00 MeV frac = 1.00000E+00 Product nuclide = 280630 : beta- + + Nuclide 506 / 1657 : 270640 -- cobalt 64 (Co-64) + + Pointers : 337042 -1000000 + Primary type : Decay + Nuclide ZAI : 270640 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 63.93584 + Atomic weight ratio (AWR) : 63.38660 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.30700E+00 MeV frac = 1.00000E+00 Product nuclide = 28064.82c : beta- + + Nuclide 507 / 1657 : 270650 -- cobalt 65 (Co-65) + + Pointers : 337329 -1000000 + Primary type : Decay + Nuclide ZAI : 270650 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 64.93644 + Atomic weight ratio (AWR) : 64.37860 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.95800E+00 MeV frac = 1.00000E+00 Product nuclide = 280650 : beta- + + Nuclide 508 / 1657 : 270660 -- cobalt 66 (Co-66) + + Pointers : 337840 -1000000 + Primary type : Decay + Nuclide ZAI : 270660 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 65.93976 + Atomic weight ratio (AWR) : 65.37330 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.89000E+00 MeV frac = 1.00000E+00 Product nuclide = 280660 : beta- + + Nuclide 509 / 1657 : 270670 -- cobalt 67 (Co-67) + + Pointers : 338141 -1000000 + Primary type : Decay + Nuclide ZAI : 270670 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 66.94086 + Atomic weight ratio (AWR) : 66.36580 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.425 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.68000E+00 MeV frac = 1.00000E+00 Product nuclide = 280670 : beta- + + Nuclide 510 / 1657 : 270680 -- cobalt 68 (Co-68) + + Pointers : 338442 -1000000 + Primary type : Decay + Nuclide ZAI : 270680 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 67.94488 + Atomic weight ratio (AWR) : 67.36120 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.15500E+01 MeV frac = 1.00000E+00 Product nuclide = 280680 : beta- + + Nuclide 511 / 1657 : 270681 -- cobalt 68m (Co-68m) + + Pointers : 339093 -1000000 + Primary type : Decay + Nuclide ZAI : 270681 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 67.94488 + Atomic weight ratio (AWR) : 67.36120 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.6 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.22638E+01 MeV frac = 5.00000E-01 Product nuclide = 280680 : beta- + 2 RTYP = 3 Q = 1.50000E-01 MeV frac = 5.00000E-01 Product nuclide = 270680 : IT + + Nuclide 512 / 1657 : 270690 -- cobalt 69 (Co-69) + + Pointers : 339350 -1000000 + Primary type : Decay + Nuclide ZAI : 270690 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 68.94629 + Atomic weight ratio (AWR) : 68.35400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.227 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 9.97900E+00 MeV frac = 9.90000E-01 Product nuclide = 280690 : beta- + 2 RTYP = 15 Q = 5.39250E+00 MeV frac = 1.00000E-02 Product nuclide = 280680 : beta- + neutron emission + + Nuclide 513 / 1657 : 270700 -- cobalt 70 (Co-70) + + Pointers : 339607 -1000000 + Primary type : Decay + Nuclide ZAI : 270700 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 69.95102 + Atomic weight ratio (AWR) : 69.35010 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.119 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.35100E+01 MeV frac = 1.00000E+00 Product nuclide = 280700 : beta- + + Nuclide 514 / 1657 : 270701 -- cobalt 70m (Co-70m) + + Pointers : 339791 -1000000 + Primary type : Decay + Nuclide ZAI : 270701 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 69.95102 + Atomic weight ratio (AWR) : 69.35010 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.37100E+01 MeV frac = 1.00000E+00 Product nuclide = 280700 : beta- + + Nuclide 515 / 1657 : 270710 -- cobalt 71 (Co-71) + + Pointers : 339975 -1000000 + Primary type : Decay + Nuclide ZAI : 270710 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 70.95292 + Atomic weight ratio (AWR) : 70.34340 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 97 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.13300E+01 MeV frac = 1.00000E+00 Product nuclide = 280710 : beta- + + Nuclide 516 / 1657 : 270720 -- cobalt 72 (Co-72) + + Pointers : 340159 -1000000 + Primary type : Decay + Nuclide ZAI : 270720 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 71.95786 + Atomic weight ratio (AWR) : 71.33970 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 90 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.46400E+01 MeV frac = 1.00000E+00 Product nuclide = 280720 : beta- + + Nuclide 517 / 1657 : 270730 -- cobalt 73 (Co-73) + + Pointers : 340343 -1000000 + Primary type : Decay + Nuclide ZAI : 270730 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 72.96027 + Atomic weight ratio (AWR) : 72.33350 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 80 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.28200E+01 MeV frac = 1.00000E+00 Product nuclide = 280730 : beta- + + Nuclide 518 / 1657 : 270740 -- cobalt 74 (Co-74) + + Pointers : 340527 -1000000 + Primary type : Decay + Nuclide ZAI : 270740 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 73.96540 + Atomic weight ratio (AWR) : 73.33000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 50 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.61200E+01 MeV frac = 1.00000E+00 Product nuclide = 280740 : beta- + + Nuclide 519 / 1657 : 270750 -- cobalt 75 (Co-75) + + Pointers : 340711 -1000000 + Primary type : Decay + Nuclide ZAI : 270750 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 74.96832 + Atomic weight ratio (AWR) : 74.32430 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 40 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.44000E+01 MeV frac = 1.00000E+00 Product nuclide = 280750 : beta- + + Nuclide 520 / 1657 : 280570 -- nickel 57 (Ni-57) + + Pointers : 340895 -1000000 + Primary type : Decay + Nuclide ZAI : 280570 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 56.93974 + Atomic weight ratio (AWR) : 56.45060 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.29E+05 seconds (1.5 days) + Specific ingestion toxicity : 8.70E-10 Sv/Bq + Specific inhalation toxicity : 5.30E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 3.26420E+00 MeV frac = 1.00000E+00 Product nuclide = 270570 : EC/beta+ + + Nuclide 521 / 1657 : 280630 -- nickel 63 (Ni-63) + + Pointers : 353858 -1000000 + Primary type : Decay + Nuclide ZAI : 280630 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 62.92970 + Atomic weight ratio (AWR) : 62.38910 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.11E+09 seconds (98.8 years) + Specific ingestion toxicity : 1.50E-10 Sv/Bq + Specific inhalation toxicity : 1.30E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.69800E-02 MeV frac = 1.00000E+00 Product nuclide = 290630 : beta- + + Nuclide 522 / 1657 : 280650 -- nickel 65 (Ni-65) + + Pointers : 355865 -1000000 + Primary type : Decay + Nuclide ZAI : 280650 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 64.93008 + Atomic weight ratio (AWR) : 64.37230 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.07E+03 seconds (2.52 hours) + Specific ingestion toxicity : 1.80E-10 Sv/Bq + Specific inhalation toxicity : 9.00E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.13620E+00 MeV frac = 1.00000E+00 Product nuclide = 29065.82c : beta- + + Nuclide 523 / 1657 : 280660 -- nickel 66 (Ni-66) + + Pointers : 356586 -1000000 + Primary type : Decay + Nuclide ZAI : 280660 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 65.92917 + Atomic weight ratio (AWR) : 65.36280 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.96E+05 seconds (2.27 days) + Specific ingestion toxicity : 3.00E-09 Sv/Bq + Specific inhalation toxicity : 1.80E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.27000E-01 MeV frac = 1.00000E+00 Product nuclide = 290660 : beta- + + Nuclide 524 / 1657 : 280670 -- nickel 67 (Ni-67) + + Pointers : 356803 -1000000 + Primary type : Decay + Nuclide ZAI : 280670 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 66.93158 + Atomic weight ratio (AWR) : 66.35660 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 21 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.55800E+00 MeV frac = 1.00000E+00 Product nuclide = 290670 : beta- + + Nuclide 525 / 1657 : 280680 -- nickel 68 (Ni-68) + + Pointers : 357202 -1000000 + Primary type : Decay + Nuclide ZAI : 280680 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 67.93187 + Atomic weight ratio (AWR) : 67.34830 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 29 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.10320E+00 MeV frac = 1.00000E+00 Product nuclide = 290680 : beta- + + Nuclide 526 / 1657 : 280690 -- nickel 69 (Ni-69) + + Pointers : 357386 -1000000 + Primary type : Decay + Nuclide ZAI : 280690 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 68.93559 + Atomic weight ratio (AWR) : 68.34340 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 11.4 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.36000E+00 MeV frac = 1.00000E+00 Product nuclide = 290690 : beta- + + Nuclide 527 / 1657 : 280691 -- nickel 69m (Ni-69m) + + Pointers : 357967 -1000000 + Primary type : Decay + Nuclide ZAI : 280691 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 68.93559 + Atomic weight ratio (AWR) : 68.34340 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.07820E+00 MeV frac = 1.00000E+00 Product nuclide = 290690 : beta- + + Nuclide 528 / 1657 : 280700 -- nickel 70 (Ni-70) + + Pointers : 358151 -1000000 + Primary type : Decay + Nuclide ZAI : 280700 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 69.93649 + Atomic weight ratio (AWR) : 69.33570 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.58350E+00 MeV frac = 1.00000E+00 Product nuclide = 290702 : beta- + + Nuclide 529 / 1657 : 280710 -- nickel 71 (Ni-71) + + Pointers : 358335 -1000000 + Primary type : Decay + Nuclide ZAI : 280710 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 70.94072 + Atomic weight ratio (AWR) : 70.33130 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.56 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.51111E+00 MeV frac = 1.00000E+00 Product nuclide = 290710 : beta- + + Nuclide 530 / 1657 : 280720 -- nickel 72 (Ni-72) + + Pointers : 358519 -1000000 + Primary type : Decay + Nuclide ZAI : 280720 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 71.94212 + Atomic weight ratio (AWR) : 71.32410 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.57 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.84300E+00 MeV frac = 1.00000E+00 Product nuclide = 290720 : beta- + + Nuclide 531 / 1657 : 280730 -- nickel 73 (Ni-73) + + Pointers : 358703 -1000000 + Primary type : Decay + Nuclide ZAI : 280730 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 72.94645 + Atomic weight ratio (AWR) : 72.31980 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.84 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.12700E+00 MeV frac = 1.00000E+00 Product nuclide = 290730 : beta- + + Nuclide 532 / 1657 : 280740 -- nickel 74 (Ni-74) + + Pointers : 358887 -1000000 + Primary type : Decay + Nuclide ZAI : 280740 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 73.94805 + Atomic weight ratio (AWR) : 73.31280 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.68 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.63600E+00 MeV frac = 1.00000E+00 Product nuclide = 290740 : beta- + + Nuclide 533 / 1657 : 280750 -- nickel 75 (Ni-75) + + Pointers : 359071 -1000000 + Primary type : Decay + Nuclide ZAI : 280750 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 74.95289 + Atomic weight ratio (AWR) : 74.30900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.6 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.02200E+01 MeV frac = 9.84000E-01 Product nuclide = 290750 : beta- + 2 RTYP = 15 Q = 4.03470E+00 MeV frac = 1.60000E-02 Product nuclide = 290740 : beta- + neutron emission + + Nuclide 534 / 1657 : 280760 -- nickel 76 (Ni-76) + + Pointers : 359328 -1000000 + Primary type : Decay + Nuclide ZAI : 280760 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 75.95530 + Atomic weight ratio (AWR) : 75.30280 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.47 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 9.36600E+00 MeV frac = 5.00000E-01 Product nuclide = 290760 : beta- + 2 RTYP = 1 Q = 9.36600E+00 MeV frac = 5.00000E-01 Product nuclide = 290761 : beta- + + Nuclide 535 / 1657 : 280770 -- nickel 77 (Ni-77) + + Pointers : 359585 -1000000 + Primary type : Decay + Nuclide ZAI : 280770 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 76.96053 + Atomic weight ratio (AWR) : 76.29940 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.18300E+01 MeV frac = 1.00000E+00 Product nuclide = 290770 : beta- + + Nuclide 536 / 1657 : 280780 -- nickel 78 (Ni-78) + + Pointers : 359769 -1000000 + Primary type : Decay + Nuclide ZAI : 280780 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 77.96314 + Atomic weight ratio (AWR) : 77.29340 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.04500E+01 MeV frac = 1.00000E+00 Product nuclide = 290780 : beta- + + Nuclide 537 / 1657 : 290630 -- copper 63 (Cu-63) + + Pointers : 359953 -1000000 + Primary type : Decay + Nuclide ZAI : 290630 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 62.92960 + Atomic weight ratio (AWR) : 62.38900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 538 / 1657 : 290640 -- copper 64 (Cu-64) + + Pointers : 360059 -1000000 + Primary type : Decay + Nuclide ZAI : 290640 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 63.92979 + Atomic weight ratio (AWR) : 63.38060 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.57E+04 seconds (12.7 hours) + Specific ingestion toxicity : 1.20E-10 Sv/Bq + Specific inhalation toxicity : 1.20E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 1.67503E+00 MeV frac = 6.15200E-01 Product nuclide = 28064.82c : EC/beta+ + 2 RTYP = 1 Q = 5.79400E-01 MeV frac = 3.84800E-01 Product nuclide = 300640 : beta- + + Nuclide 539 / 1657 : 290660 -- copper 66 (Cu-66) + + Pointers : 363461 -1000000 + Primary type : Decay + Nuclide ZAI : 290660 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 65.92886 + Atomic weight ratio (AWR) : 65.36250 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.06E+02 seconds (5.1 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.64160E+00 MeV frac = 1.00000E+00 Product nuclide = 300660 : beta- + + Nuclide 540 / 1657 : 290670 -- copper 67 (Cu-67) + + Pointers : 363776 -1000000 + Primary type : Decay + Nuclide ZAI : 290670 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 66.92774 + Atomic weight ratio (AWR) : 66.35280 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.23E+05 seconds (2.58 days) + Specific ingestion toxicity : 3.40E-10 Sv/Bq + Specific inhalation toxicity : 6.10E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.76000E-01 MeV frac = 1.00000E+00 Product nuclide = 300670 : beta- + + Nuclide 541 / 1657 : 290680 -- copper 68 (Cu-68) + + Pointers : 364469 -1000000 + Primary type : Decay + Nuclide ZAI : 290680 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 67.92965 + Atomic weight ratio (AWR) : 67.34610 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 31.1 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.46200E+00 MeV frac = 1.00000E+00 Product nuclide = 300680 : beta- + + Nuclide 542 / 1657 : 290681 -- copper 68m (Cu-68m) + + Pointers : 365344 -1000000 + Primary type : Decay + Nuclide ZAI : 290681 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 67.92965 + Atomic weight ratio (AWR) : 67.34610 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.25E+02 seconds (3.75 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 7.21600E-01 MeV frac = 8.40000E-01 Product nuclide = 290680 : IT + 2 RTYP = 1 Q = 5.16181E+00 MeV frac = 1.60000E-01 Product nuclide = 300680 : beta- + + Nuclide 543 / 1657 : 290690 -- copper 69 (Cu-69) + + Pointers : 365601 -1000000 + Primary type : Decay + Nuclide ZAI : 290690 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 68.92944 + Atomic weight ratio (AWR) : 68.33730 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.71E+02 seconds (2.85 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.67500E+00 MeV frac = 1.00000E+00 Product nuclide = 300690 : beta- + + Nuclide 544 / 1657 : 290700 -- copper 70 (Cu-70) + + Pointers : 366378 -1000000 + Primary type : Decay + Nuclide ZAI : 290700 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 69.93236 + Atomic weight ratio (AWR) : 69.33160 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 44.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.58850E+00 MeV frac = 1.00000E+00 Product nuclide = 300700 : beta- + + Nuclide 545 / 1657 : 290701 -- copper 70m (Cu-70m) + + Pointers : 367337 -1000000 + Primary type : Decay + Nuclide ZAI : 290701 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 69.93236 + Atomic weight ratio (AWR) : 69.33160 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 33 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 6.68960E+00 MeV frac = 5.20000E-01 Product nuclide = 300700 : beta- + 2 RTYP = 3 Q = 1.01100E-01 MeV frac = 4.80000E-01 Product nuclide = 290700 : IT + + Nuclide 546 / 1657 : 290702 -- copper 70m (Cu-70m) + + Pointers : 3503132 -1000000 + Primary type : Decay + Nuclide ZAI : 290702 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 69.93236 + Atomic weight ratio (AWR) : 69.33160 + Temperature : 900.0 Kelvin + XS temperature : -1.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.6 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is not present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 6.83110E+00 MeV frac = 9.32000E-01 Product nuclide = 300700 : beta- + 2 RTYP = 3 Q = 1.41500E-01 MeV frac = 6.80000E-02 Product nuclide = 290701 : IT + + Nuclide 547 / 1657 : 290710 -- copper 71 (Cu-71) + + Pointers : 367594 -1000000 + Primary type : Decay + Nuclide ZAI : 290710 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 70.93265 + Atomic weight ratio (AWR) : 70.32330 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 19.4 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.61590E+00 MeV frac = 1.00000E+00 Product nuclide = 300710 : beta- + + Nuclide 548 / 1657 : 290720 -- copper 72 (Cu-72) + + Pointers : 367778 -1000000 + Primary type : Decay + Nuclide ZAI : 290720 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 71.93587 + Atomic weight ratio (AWR) : 71.31790 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.63 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.36200E+00 MeV frac = 1.00000E+00 Product nuclide = 300720 : beta- + + Nuclide 549 / 1657 : 290730 -- copper 73 (Cu-73) + + Pointers : 369171 -1000000 + Primary type : Decay + Nuclide ZAI : 290730 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 72.93666 + Atomic weight ratio (AWR) : 72.31010 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.60620E+00 MeV frac = 1.00000E+00 Product nuclide = 300730 : beta- + + Nuclide 550 / 1657 : 290740 -- copper 74 (Cu-74) + + Pointers : 369542 -1000000 + Primary type : Decay + Nuclide ZAI : 290740 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 73.93988 + Atomic weight ratio (AWR) : 73.30470 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.59 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.70400E+00 MeV frac = 1.00000E+00 Product nuclide = 300740 : beta- + + Nuclide 551 / 1657 : 290750 -- copper 75 (Cu-75) + + Pointers : 369726 -1000000 + Primary type : Decay + Nuclide ZAI : 290750 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 74.94189 + Atomic weight ratio (AWR) : 74.29810 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.22 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.35000E+00 MeV frac = 9.65000E-01 Product nuclide = 300750 : beta- + 2 RTYP = 15 Q = 3.51870E+00 MeV frac = 3.50000E-02 Product nuclide = 300740 : beta- + neutron emission + + Nuclide 552 / 1657 : 290760 -- copper 76 (Cu-76) + + Pointers : 369983 -1000000 + Primary type : Decay + Nuclide ZAI : 290760 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 75.94531 + Atomic weight ratio (AWR) : 75.29290 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.641 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.11640E+01 MeV frac = 9.70000E-01 Product nuclide = 300760 : beta- + 2 RTYP = 15 Q = 3.42270E+00 MeV frac = 3.00000E-02 Product nuclide = 300750 : beta- + neutron emission + + Nuclide 553 / 1657 : 290761 -- copper 76m (Cu-76m) + + Pointers : 370240 -1000000 + Primary type : Decay + Nuclide ZAI : 290761 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 75.94531 + Atomic weight ratio (AWR) : 75.29290 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.27 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.11640E+01 MeV frac = 1.00000E+00 Product nuclide = 300760 : beta- + + Nuclide 554 / 1657 : 290770 -- copper 77 (Cu-77) + + Pointers : 370424 -1000000 + Primary type : Decay + Nuclide ZAI : 290770 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 76.94782 + Atomic weight ratio (AWR) : 76.28680 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.469 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.01400E+01 MeV frac = 1.00000E+00 Product nuclide = 300770 : beta- + + Nuclide 555 / 1657 : 290780 -- copper 78 (Cu-78) + + Pointers : 370608 -1000000 + Primary type : Decay + Nuclide ZAI : 290780 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 77.95195 + Atomic weight ratio (AWR) : 77.28230 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.342 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.25900E+01 MeV frac = 1.00000E+00 Product nuclide = 300780 : beta- + + Nuclide 556 / 1657 : 290790 -- copper 79 (Cu-79) + + Pointers : 370792 -1000000 + Primary type : Decay + Nuclide ZAI : 290790 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 78.95456 + Atomic weight ratio (AWR) : 78.27630 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.188 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.10900E+01 MeV frac = 4.50000E-01 Product nuclide = 300790 : beta- + 2 RTYP = 15 Q = 6.93870E+00 MeV frac = 5.50000E-01 Product nuclide = 300780 : beta- + neutron emission + + Nuclide 557 / 1657 : 290800 -- copper 80 (Cu-80) + + Pointers : 371049 -1000000 + Primary type : Decay + Nuclide ZAI : 290800 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 79.96091 + Atomic weight ratio (AWR) : 79.27400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 100 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.53900E+01 MeV frac = 1.00000E+00 Product nuclide = 300800 : beta- + + Nuclide 558 / 1657 : 300640 -- zinc 64 (Zn-64) + + Pointers : 371233 -1000000 + Primary type : Decay + Nuclide ZAI : 300640 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 63.92919 + Atomic weight ratio (AWR) : 63.38000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.26E+25 seconds (2.3E+18 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 22 Q = 1.09570E+00 MeV frac = 1.00000E+00 Product nuclide = 28064.82c : EC/beta+ + EC/beta+ + + Nuclide 559 / 1657 : 300650 -- zinc 65 (Zn-65) + + Pointers : 371417 -1000000 + Primary type : Decay + Nuclide ZAI : 300650 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 64.92928 + Atomic weight ratio (AWR) : 64.37150 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.11E+07 seconds (244 days) + Specific ingestion toxicity : 3.90E-09 Sv/Bq + Specific inhalation toxicity : 2.20E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 1.35210E+00 MeV frac = 1.00000E+00 Product nuclide = 29065.82c : EC/beta+ + + Nuclide 560 / 1657 : 300660 -- zinc 66 (Zn-66) + + Pointers : 371858 -1000000 + Primary type : Decay + Nuclide ZAI : 300660 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 65.92604 + Atomic weight ratio (AWR) : 65.35970 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 561 / 1657 : 300670 -- zinc 67 (Zn-67) + + Pointers : 371964 -1000000 + Primary type : Decay + Nuclide ZAI : 300670 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 66.92714 + Atomic weight ratio (AWR) : 66.35220 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 562 / 1657 : 300680 -- zinc 68 (Zn-68) + + Pointers : 372070 -1000000 + Primary type : Decay + Nuclide ZAI : 300680 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 67.92481 + Atomic weight ratio (AWR) : 67.34130 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 563 / 1657 : 300690 -- zinc 69 (Zn-69) + + Pointers : 372176 -1000000 + Primary type : Decay + Nuclide ZAI : 300690 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 68.92652 + Atomic weight ratio (AWR) : 68.33440 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.38E+03 seconds (56.4 minutes) + Specific ingestion toxicity : 3.10E-11 Sv/Bq + Specific inhalation toxicity : 2.80E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.09800E-01 MeV frac = 1.00000E+00 Product nuclide = 310690 : beta- + + Nuclide 564 / 1657 : 300691 -- zinc 69m (Zn-69m) + + Pointers : 372631 -1000000 + Primary type : Decay + Nuclide ZAI : 300691 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 68.92652 + Atomic weight ratio (AWR) : 68.33440 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.96E+04 seconds (13.8 hours) + Specific ingestion toxicity : 3.30E-10 Sv/Bq + Specific inhalation toxicity : 2.70E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.34840E+00 MeV frac = 3.30000E-04 Product nuclide = 310690 : beta- + 2 RTYP = 3 Q = 4.38636E-01 MeV frac = 9.99670E-01 Product nuclide = 300690 : IT + + Nuclide 565 / 1657 : 300700 -- zinc 70 (Zn-70) + + Pointers : 373215 -1000000 + Primary type : Decay + Nuclide ZAI : 300700 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 69.92530 + Atomic weight ratio (AWR) : 69.32460 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 566 / 1657 : 300710 -- zinc 71 (Zn-71) + + Pointers : 373321 -1000000 + Primary type : Decay + Nuclide ZAI : 300710 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 70.92771 + Atomic weight ratio (AWR) : 70.31840 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.47E+02 seconds (2.45 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.81020E+00 MeV frac = 1.00000E+00 Product nuclide = 310710 : beta- + + Nuclide 567 / 1657 : 300711 -- zinc 71m (Zn-71m) + + Pointers : 374252 -1000000 + Primary type : Decay + Nuclide ZAI : 300711 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 70.92771 + Atomic weight ratio (AWR) : 70.31840 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.43E+04 seconds (3.96 hours) + Specific ingestion toxicity : 2.40E-10 Sv/Bq + Specific inhalation toxicity : 1.60E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.96790E+00 MeV frac = 1.00000E+00 Product nuclide = 310710 : beta- + + Nuclide 568 / 1657 : 300720 -- zinc 72 (Zn-72) + + Pointers : 375953 -1000000 + Primary type : Decay + Nuclide ZAI : 300720 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 71.92689 + Atomic weight ratio (AWR) : 71.30900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.67E+05 seconds (1.94 days) + Specific ingestion toxicity : 1.40E-09 Sv/Bq + Specific inhalation toxicity : 1.30E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 4.42800E-01 MeV frac = 9.66406E-01 Product nuclide = 310720 : beta- + 2 RTYP = 1 Q = 3.23600E-01 MeV frac = 3.35941E-02 Product nuclide = 310721 : beta- + + Nuclide 569 / 1657 : 300730 -- zinc 73 (Zn-73) + + Pointers : 377013 -1000000 + Primary type : Decay + Nuclide ZAI : 300730 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 72.92981 + Atomic weight ratio (AWR) : 72.30330 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 23.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.29400E+00 MeV frac = 1.00000E+00 Product nuclide = 310730 : beta- + + Nuclide 570 / 1657 : 300731 -- zinc 73m (Zn-73m) + + Pointers : 377664 -1000000 + Primary type : Decay + Nuclide ZAI : 300731 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 72.92981 + Atomic weight ratio (AWR) : 72.30330 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 13 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.95500E-01 MeV frac = 1.00000E+00 Product nuclide = 300730 : IT + + Nuclide 571 / 1657 : 300732 -- zinc 73m (Zn-73m) + + Pointers : 3506326 -1000000 + Primary type : Decay + Nuclide ZAI : 300732 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 72.92981 + Atomic weight ratio (AWR) : 72.30330 + Temperature : 900.0 Kelvin + XS temperature : -1.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.8 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is not present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 4.21000E-02 MeV frac = 5.00000E-01 Product nuclide = 300731 : IT + 2 RTYP = 1 Q = 4.52690E+00 MeV frac = 5.00000E-01 Product nuclide = 310730 : beta- + + Nuclide 572 / 1657 : 300740 -- zinc 74 (Zn-74) + + Pointers : 377848 -1000000 + Primary type : Decay + Nuclide ZAI : 300740 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 73.92949 + Atomic weight ratio (AWR) : 73.29440 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.56E+01 seconds (1.59 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.28043E+00 MeV frac = 1.00000E+00 Product nuclide = 310741 : beta- + + Nuclide 573 / 1657 : 300750 -- zinc 75 (Zn-75) + + Pointers : 378032 -1000000 + Primary type : Decay + Nuclide ZAI : 300750 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 74.93291 + Atomic weight ratio (AWR) : 74.28920 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 10.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.90600E+00 MeV frac = 1.00000E+00 Product nuclide = 310750 : beta- + + Nuclide 574 / 1657 : 300760 -- zinc 76 (Zn-76) + + Pointers : 380209 -1000000 + Primary type : Decay + Nuclide ZAI : 300760 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 75.93331 + Atomic weight ratio (AWR) : 75.28100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.7 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.16000E+00 MeV frac = 1.00000E+00 Product nuclide = 310760 : beta- + + Nuclide 575 / 1657 : 300770 -- zinc 77 (Zn-77) + + Pointers : 381546 -1000000 + Primary type : Decay + Nuclide ZAI : 300770 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 76.93693 + Atomic weight ratio (AWR) : 76.27600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.08 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.27230E+00 MeV frac = 1.00000E+00 Product nuclide = 310770 : beta- + + Nuclide 576 / 1657 : 300771 -- zinc 77m (Zn-77m) + + Pointers : 381730 -1000000 + Primary type : Decay + Nuclide ZAI : 300771 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 76.93693 + Atomic weight ratio (AWR) : 76.27600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.05 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 7.72390E-01 MeV frac = 5.00000E-01 Product nuclide = 300770 : IT + 2 RTYP = 1 Q = 8.04469E+00 MeV frac = 5.00000E-01 Product nuclide = 310770 : beta- + + Nuclide 577 / 1657 : 300780 -- zinc 78 (Zn-78) + + Pointers : 381987 -1000000 + Primary type : Decay + Nuclide ZAI : 300780 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 77.93843 + Atomic weight ratio (AWR) : 77.26890 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.47 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.36660E+00 MeV frac = 1.00000E+00 Product nuclide = 310780 : beta- + + Nuclide 578 / 1657 : 300790 -- zinc 79 (Zn-79) + + Pointers : 382171 -1000000 + Primary type : Decay + Nuclide ZAI : 300790 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 78.94266 + Atomic weight ratio (AWR) : 78.26450 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.995 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 9.09000E+00 MeV frac = 9.87000E-01 Product nuclide = 310790 : beta- + 2 RTYP = 15 Q = 2.21530E+00 MeV frac = 1.30000E-02 Product nuclide = 310780 : beta- + neutron emission + + Nuclide 579 / 1657 : 300800 -- zinc 80 (Zn-80) + + Pointers : 382428 -1000000 + Primary type : Decay + Nuclide ZAI : 300800 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 79.94436 + Atomic weight ratio (AWR) : 79.25760 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.54 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.29000E+00 MeV frac = 1.00000E+00 Product nuclide = 310800 : beta- + + Nuclide 580 / 1657 : 300810 -- zinc 81 (Zn-81) + + Pointers : 383163 -1000000 + Primary type : Decay + Nuclide ZAI : 300810 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 80.95051 + Atomic weight ratio (AWR) : 80.25510 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.29 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.18500E+01 MeV frac = 9.25000E-01 Product nuclide = 310810 : beta- + 2 RTYP = 15 Q = 4.93870E+00 MeV frac = 7.50000E-02 Product nuclide = 310800 : beta- + neutron emission + + Nuclide 581 / 1657 : 300820 -- zinc 82 (Zn-82) + + Pointers : 383420 -1000000 + Primary type : Decay + Nuclide ZAI : 300820 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 81.95443 + Atomic weight ratio (AWR) : 81.25040 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 100 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.06400E+01 MeV frac = 1.00000E+00 Product nuclide = 310820 : beta- + + Nuclide 582 / 1657 : 300830 -- zinc 83 (Zn-83) + + Pointers : 383604 -1000000 + Primary type : Decay + Nuclide ZAI : 300830 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 82.96108 + Atomic weight ratio (AWR) : 82.24840 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 80 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.30900E+01 MeV frac = 1.00000E+00 Product nuclide = 310830 : beta- + + Nuclide 583 / 1657 : 310680 -- gallium 68 (Ga-68) + + Pointers : 383788 -1000000 + Primary type : Decay + Nuclide ZAI : 310680 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 67.92794 + Atomic weight ratio (AWR) : 67.34440 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.07E+03 seconds (1.13 hours) + Specific ingestion toxicity : 1.00E-10 Sv/Bq + Specific inhalation toxicity : 4.90E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 2.92110E+00 MeV frac = 1.00000E+00 Product nuclide = 300680 : EC/beta+ + + Nuclide 584 / 1657 : 310690 -- gallium 69 (Ga-69) + + Pointers : 385013 -1000000 + Primary type : Decay + Nuclide ZAI : 310690 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 68.92561 + Atomic weight ratio (AWR) : 68.33350 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 585 / 1657 : 310700 -- gallium 70 (Ga-70) + + Pointers : 385119 -1000000 + Primary type : Decay + Nuclide ZAI : 310700 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 69.92600 + Atomic weight ratio (AWR) : 69.32530 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.27E+03 seconds (21.1 minutes) + Specific ingestion toxicity : 3.10E-11 Sv/Bq + Specific inhalation toxicity : 1.60E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.65300E+00 MeV frac = 9.95900E-01 Product nuclide = 32070.82c : beta- + 2 RTYP = 2 Q = 6.54500E-01 MeV frac = 4.10000E-03 Product nuclide = 300700 : EC/beta+ + + Nuclide 586 / 1657 : 310710 -- gallium 71 (Ga-71) + + Pointers : 385773 -1000000 + Primary type : Decay + Nuclide ZAI : 310710 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 70.92468 + Atomic weight ratio (AWR) : 70.31540 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 587 / 1657 : 310720 -- gallium 72 (Ga-72) + + Pointers : 385879 -1000000 + Primary type : Decay + Nuclide ZAI : 310720 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 71.92639 + Atomic weight ratio (AWR) : 71.30850 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.08E+04 seconds (14.1 hours) + Specific ingestion toxicity : 1.10E-09 Sv/Bq + Specific inhalation toxicity : 5.30E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.99750E+00 MeV frac = 1.00000E+00 Product nuclide = 32072.82c : beta- + + Nuclide 588 / 1657 : 310721 -- gallium 72m (Ga-72m) + + Pointers : 388266 -1000000 + Primary type : Decay + Nuclide ZAI : 310721 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 71.92639 + Atomic weight ratio (AWR) : 71.30850 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 39.7 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.19660E-01 MeV frac = 1.00000E+00 Product nuclide = 310720 : IT + + Nuclide 589 / 1657 : 310730 -- gallium 73 (Ga-73) + + Pointers : 388450 -1000000 + Primary type : Decay + Nuclide ZAI : 310730 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 72.92517 + Atomic weight ratio (AWR) : 72.29870 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.75E+04 seconds (4.86 hours) + Specific ingestion toxicity : 2.60E-10 Sv/Bq + Specific inhalation toxicity : 1.40E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.59300E+00 MeV frac = 1.46824E-02 Product nuclide = 32073.82c : beta- + 2 RTYP = 1 Q = 1.52626E+00 MeV frac = 9.85318E-01 Product nuclide = 320731 : beta- + + Nuclide 590 / 1657 : 310740 -- gallium 74 (Ga-74) + + Pointers : 389216 -1000000 + Primary type : Decay + Nuclide ZAI : 310740 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 73.92697 + Atomic weight ratio (AWR) : 73.29190 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.87E+02 seconds (8.12 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.37300E+00 MeV frac = 1.00000E+00 Product nuclide = 32074.82c : beta- + + Nuclide 591 / 1657 : 310741 -- gallium 74m (Ga-74m) + + Pointers : 391463 -1000000 + Primary type : Decay + Nuclide ZAI : 310741 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 73.92697 + Atomic weight ratio (AWR) : 73.29190 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 5.95710E-02 MeV frac = 7.50000E-01 Product nuclide = 310740 : IT + 2 RTYP = 1 Q = 5.43197E+00 MeV frac = 2.50000E-01 Product nuclide = 32074.82c : beta- + + Nuclide 592 / 1657 : 310750 -- gallium 75 (Ga-75) + + Pointers : 391720 -1000000 + Primary type : Decay + Nuclide ZAI : 310750 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 74.92646 + Atomic weight ratio (AWR) : 74.28280 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.26E+02 seconds (2.1 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 3.39179E+00 MeV frac = 9.60000E-01 Product nuclide = 320750 : beta- + 2 RTYP = 1 Q = 3.25210E+00 MeV frac = 4.00000E-02 Product nuclide = 320751 : beta- + + Nuclide 593 / 1657 : 310760 -- gallium 76 (Ga-76) + + Pointers : 391977 -1000000 + Primary type : Decay + Nuclide ZAI : 310760 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 75.92887 + Atomic weight ratio (AWR) : 75.27660 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 32.6 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.01000E+00 MeV frac = 1.00000E+00 Product nuclide = 32076.82c : beta- + + Nuclide 594 / 1657 : 310770 -- gallium 77 (Ga-77) + + Pointers : 394140 -1000000 + Primary type : Decay + Nuclide ZAI : 310770 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 76.92926 + Atomic weight ratio (AWR) : 76.26840 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 13 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.18000E+00 MeV frac = 1.00000E+00 Product nuclide = 320771 : beta- + + Nuclide 595 / 1657 : 310780 -- gallium 78 (Ga-78) + + Pointers : 395043 -1000000 + Primary type : Decay + Nuclide ZAI : 310780 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 77.93157 + Atomic weight ratio (AWR) : 77.26210 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.09 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.15600E+00 MeV frac = 1.00000E+00 Product nuclide = 320780 : beta- + + Nuclide 596 / 1657 : 310790 -- gallium 79 (Ga-79) + + Pointers : 396520 -1000000 + Primary type : Decay + Nuclide ZAI : 310790 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 78.93288 + Atomic weight ratio (AWR) : 78.25480 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.85 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 1 Q = 6.98000E+00 MeV frac = 9.97611E-01 Product nuclide = 320790 : beta- + 2 RTYP = 1 Q = 6.79405E+00 MeV frac = 1.49867E-03 Product nuclide = 320791 : beta- + 3 RTYP = 15 Q = 1.28071E+00 MeV frac = 8.90000E-04 Product nuclide = 320780 : beta- + neutron emission + + Nuclide 597 / 1657 : 310800 -- gallium 80 (Ga-80) + + Pointers : 396850 -1000000 + Primary type : Decay + Nuclide ZAI : 310800 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 79.93650 + Atomic weight ratio (AWR) : 79.24980 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.68 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.03800E+01 MeV frac = 1.00000E+00 Product nuclide = 320800 : beta- + + Nuclide 598 / 1657 : 310810 -- gallium 81 (Ga-81) + + Pointers : 398299 -1000000 + Primary type : Decay + Nuclide ZAI : 310810 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 80.93780 + Atomic weight ratio (AWR) : 80.24250 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.22 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 1 Q = 8.32000E+00 MeV frac = 4.65256E-01 Product nuclide = 320810 : beta- + 2 RTYP = 1 Q = 7.64087E+00 MeV frac = 4.15744E-01 Product nuclide = 320811 : beta- + 3 RTYP = 15 Q = 3.46370E+00 MeV frac = 1.19000E-01 Product nuclide = 320800 : beta- + neutron emission + + Nuclide 599 / 1657 : 310820 -- gallium 82 (Ga-82) + + Pointers : 398629 -1000000 + Primary type : Decay + Nuclide ZAI : 310820 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 81.94303 + Atomic weight ratio (AWR) : 81.23910 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.599 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 1 Q = 1.25200E+01 MeV frac = 7.87000E-01 Product nuclide = 320820 : beta- + 2 RTYP = 15 Q = 5.12870E+00 MeV frac = 1.06500E-01 Product nuclide = 320810 : beta- + neutron emission + 3 RTYP = 15 Q = 4.44957E+00 MeV frac = 1.06500E-01 Product nuclide = 320811 : beta- + neutron emission + + Nuclide 600 / 1657 : 310830 -- gallium 83 (Ga-83) + + Pointers : 398959 -1000000 + Primary type : Decay + Nuclide ZAI : 310830 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 82.94696 + Atomic weight ratio (AWR) : 82.23440 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.308 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.15100E+01 MeV frac = 6.30000E-01 Product nuclide = 320830 : beta- + 2 RTYP = 15 Q = 8.15870E+00 MeV frac = 3.70000E-01 Product nuclide = 320820 : beta- + neutron emission + + Nuclide 601 / 1657 : 310840 -- gallium 84 (Ga-84) + + Pointers : 399216 -1000000 + Primary type : Decay + Nuclide ZAI : 310840 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 83.95270 + Atomic weight ratio (AWR) : 83.23150 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 85 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.41400E+01 MeV frac = 3.00000E-01 Product nuclide = 320840 : beta- + 2 RTYP = 15 Q = 8.71870E+00 MeV frac = 7.00000E-01 Product nuclide = 320830 : beta- + neutron emission + + Nuclide 602 / 1657 : 310850 -- gallium 85 (Ga-85) + + Pointers : 399473 -1000000 + Primary type : Decay + Nuclide ZAI : 310850 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 84.95703 + Atomic weight ratio (AWR) : 84.22720 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 50 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.30200E+01 MeV frac = 1.00000E+00 Product nuclide = 320850 : beta- + + Nuclide 603 / 1657 : 310860 -- gallium 86 (Ga-86) + + Pointers : 399657 -1000000 + Primary type : Decay + Nuclide ZAI : 310860 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 85.96317 + Atomic weight ratio (AWR) : 85.22470 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 30 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.54900E+01 MeV frac = 1.00000E+00 Product nuclide = 320860 : beta- + + Nuclide 604 / 1657 : 320690 -- germanium 69 (Ge-69) + + Pointers : 399841 -1000000 + Primary type : Decay + Nuclide ZAI : 320690 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 68.92793 + Atomic weight ratio (AWR) : 68.33580 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.41E+05 seconds (1.63 days) + Specific ingestion toxicity : 2.40E-10 Sv/Bq + Specific inhalation toxicity : 2.90E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 2.22730E+00 MeV frac = 1.00000E+00 Product nuclide = 310690 : EC/beta+ + + Nuclide 605 / 1657 : 320710 -- germanium 71 (Ge-71) + + Pointers : 409194 -1000000 + Primary type : Decay + Nuclide ZAI : 320710 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 70.92498 + Atomic weight ratio (AWR) : 70.31570 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.88E+05 seconds (11.4 days) + Specific ingestion toxicity : 1.20E-11 Sv/Bq + Specific inhalation toxicity : 1.10E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 2.33000E-01 MeV frac = 1.00000E+00 Product nuclide = 310710 : EC/beta+ + + Nuclide 606 / 1657 : 320711 -- germanium 71m (Ge-71m) + + Pointers : 409495 -1000000 + Primary type : Decay + Nuclide ZAI : 320711 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 70.92498 + Atomic weight ratio (AWR) : 70.31570 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 20.4 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.98367E-01 MeV frac = 1.00000E+00 Product nuclide = 320710 : IT + + Nuclide 607 / 1657 : 320731 -- germanium 73m (Ge-73m) + + Pointers : 425580 -1000000 + Primary type : Decay + Nuclide ZAI : 320731 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 72.92345 + Atomic weight ratio (AWR) : 72.29700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 6.67260E-02 MeV frac = 1.00000E+00 Product nuclide = 32073.82c : IT + + Nuclide 608 / 1657 : 320750 -- germanium 75 (Ge-75) + + Pointers : 433086 -1000000 + Primary type : Decay + Nuclide ZAI : 320750 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 74.92283 + Atomic weight ratio (AWR) : 74.27920 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.97E+03 seconds (1.38 hours) + Specific ingestion toxicity : 4.60E-11 Sv/Bq + Specific inhalation toxicity : 3.60E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.17600E+00 MeV frac = 1.00000E+00 Product nuclide = 33075.82c : beta- + + Nuclide 609 / 1657 : 320751 -- germanium 75m (Ge-75m) + + Pointers : 433849 -1000000 + Primary type : Decay + Nuclide ZAI : 320751 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 74.92283 + Atomic weight ratio (AWR) : 74.27920 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 48 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.31600E+00 MeV frac = 3.30000E-04 Product nuclide = 33075.82c : beta- + 2 RTYP = 3 Q = 1.39690E-01 MeV frac = 9.99670E-01 Product nuclide = 320750 : IT + + Nuclide 610 / 1657 : 320770 -- germanium 77 (Ge-77) + + Pointers : 441058 -1000000 + Primary type : Decay + Nuclide ZAI : 320770 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 76.92351 + Atomic weight ratio (AWR) : 76.26270 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.04E+04 seconds (11.2 hours) + Specific ingestion toxicity : 3.30E-10 Sv/Bq + Specific inhalation toxicity : 3.70E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.70250E+00 MeV frac = 1.00000E+00 Product nuclide = 330770 : beta- + + Nuclide 611 / 1657 : 320771 -- germanium 77m (Ge-77m) + + Pointers : 444593 -1000000 + Primary type : Decay + Nuclide ZAI : 320771 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 76.92351 + Atomic weight ratio (AWR) : 76.26270 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 53.7 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 1.59700E-01 MeV frac = 1.90000E-01 Product nuclide = 320770 : IT + 2 RTYP = 1 Q = 2.86220E+00 MeV frac = 8.10000E-01 Product nuclide = 330770 : beta- + + Nuclide 612 / 1657 : 320780 -- germanium 78 (Ge-78) + + Pointers : 445639 -1000000 + Primary type : Decay + Nuclide ZAI : 320780 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 77.92290 + Atomic weight ratio (AWR) : 77.25350 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.28E+03 seconds (1.47 hours) + Specific ingestion toxicity : 1.20E-10 Sv/Bq + Specific inhalation toxicity : 9.50E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.55000E-01 MeV frac = 1.00000E+00 Product nuclide = 330780 : beta- + + Nuclide 613 / 1657 : 320790 -- germanium 79 (Ge-79) + + Pointers : 445912 -1000000 + Primary type : Decay + Nuclide ZAI : 320790 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 78.92541 + Atomic weight ratio (AWR) : 78.24740 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 19 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.14800E+00 MeV frac = 1.00000E+00 Product nuclide = 330790 : beta- + + Nuclide 614 / 1657 : 320791 -- germanium 79m (Ge-79m) + + Pointers : 446661 -1000000 + Primary type : Decay + Nuclide ZAI : 320791 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 78.92541 + Atomic weight ratio (AWR) : 78.24740 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 39 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 4.33400E+00 MeV frac = 9.60000E-01 Product nuclide = 330790 : beta- + 2 RTYP = 3 Q = 1.86020E-01 MeV frac = 4.00000E-02 Product nuclide = 320790 : IT + + Nuclide 615 / 1657 : 320800 -- germanium 80 (Ge-80) + + Pointers : 447651 -1000000 + Primary type : Decay + Nuclide ZAI : 320800 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 79.92540 + Atomic weight ratio (AWR) : 79.23880 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 29.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.64400E+00 MeV frac = 1.00000E+00 Product nuclide = 330800 : beta- + + Nuclide 616 / 1657 : 320810 -- germanium 81 (Ge-81) + + Pointers : 448092 -1000000 + Primary type : Decay + Nuclide ZAI : 320810 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 80.92882 + Atomic weight ratio (AWR) : 80.23360 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.23300E+00 MeV frac = 1.00000E+00 Product nuclide = 330810 : beta- + + Nuclide 617 / 1657 : 320811 -- germanium 81m (Ge-81m) + + Pointers : 448276 -1000000 + Primary type : Decay + Nuclide ZAI : 320811 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 80.92882 + Atomic weight ratio (AWR) : 80.23360 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.6 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.92114E+00 MeV frac = 1.00000E+00 Product nuclide = 330810 : beta- + + Nuclide 618 / 1657 : 320820 -- germanium 82 (Ge-82) + + Pointers : 449375 -1000000 + Primary type : Decay + Nuclide ZAI : 320820 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 81.92952 + Atomic weight ratio (AWR) : 81.22570 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.55 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.70000E+00 MeV frac = 1.00000E+00 Product nuclide = 330820 : beta- + + Nuclide 619 / 1657 : 320830 -- germanium 83 (Ge-83) + + Pointers : 449690 -1000000 + Primary type : Decay + Nuclide ZAI : 320830 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 82.93465 + Atomic weight ratio (AWR) : 82.22220 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.85 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.98000E+00 MeV frac = 1.00000E+00 Product nuclide = 330830 : beta- + + Nuclide 620 / 1657 : 320840 -- germanium 84 (Ge-84) + + Pointers : 449874 -1000000 + Primary type : Decay + Nuclide ZAI : 320840 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 83.93747 + Atomic weight ratio (AWR) : 83.21640 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.954 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 1 Q = 7.83000E+00 MeV frac = 4.46000E-01 Product nuclide = 330840 : beta- + 2 RTYP = 1 Q = 7.83000E+00 MeV frac = 4.46000E-01 Product nuclide = 330841 : beta- + 3 RTYP = 15 Q = 3.55870E+00 MeV frac = 1.08000E-01 Product nuclide = 330830 : beta- + neutron emission + + Nuclide 621 / 1657 : 320850 -- germanium 85 (Ge-85) + + Pointers : 450204 -1000000 + Primary type : Decay + Nuclide ZAI : 320850 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 84.94301 + Atomic weight ratio (AWR) : 84.21330 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.54 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 1 Q = 1.02500E+01 MeV frac = 8.60000E-01 Product nuclide = 330850 : beta- + 2 RTYP = 15 Q = 4.93870E+00 MeV frac = 7.00000E-02 Product nuclide = 330840 : beta- + neutron emission + 3 RTYP = 15 Q = 4.93870E+00 MeV frac = 7.00000E-02 Product nuclide = 330841 : beta- + neutron emission + + Nuclide 622 / 1657 : 320860 -- germanium 86 (Ge-86) + + Pointers : 450534 -1000000 + Primary type : Decay + Nuclide ZAI : 320860 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 85.94653 + Atomic weight ratio (AWR) : 85.20820 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.31000E+00 MeV frac = 1.00000E+00 Product nuclide = 330860 : beta- + + Nuclide 623 / 1657 : 320870 -- germanium 87 (Ge-87) + + Pointers : 450718 -1000000 + Primary type : Decay + Nuclide ZAI : 320870 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 86.95247 + Atomic weight ratio (AWR) : 86.20550 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.15 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.17400E+01 MeV frac = 1.00000E+00 Product nuclide = 330870 : beta- + + Nuclide 624 / 1657 : 320880 -- germanium 88 (Ge-88) + + Pointers : 450902 -1000000 + Primary type : Decay + Nuclide ZAI : 320880 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 87.95690 + Atomic weight ratio (AWR) : 87.20130 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 80 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.11500E+01 MeV frac = 1.00000E+00 Product nuclide = 330880 : beta- + + Nuclide 625 / 1657 : 320890 -- germanium 89 (Ge-89) + + Pointers : 451086 -1000000 + Primary type : Decay + Nuclide ZAI : 320890 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 88.96385 + Atomic weight ratio (AWR) : 88.19960 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 50 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.34500E+01 MeV frac = 1.00000E+00 Product nuclide = 330890 : beta- + + Nuclide 626 / 1657 : 330730 -- arsenic 73 (As-73) + + Pointers : 451270 -1000000 + Primary type : Decay + Nuclide ZAI : 330730 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 72.92385 + Atomic weight ratio (AWR) : 72.29740 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.94E+06 seconds (80.3 days) + Specific ingestion toxicity : 2.60E-10 Sv/Bq + Specific inhalation toxicity : 1.00E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 2.74000E-01 MeV frac = 1.00000E+00 Product nuclide = 320731 : EC/beta+ + + Nuclide 627 / 1657 : 330740 -- arsenic 74 (As-74) + + Pointers : 451599 -1000000 + Primary type : Decay + Nuclide ZAI : 330740 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 73.92395 + Atomic weight ratio (AWR) : 73.28890 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.54E+06 seconds (17.8 days) + Specific ingestion toxicity : 1.30E-09 Sv/Bq + Specific inhalation toxicity : 2.10E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.35390E+00 MeV frac = 3.40000E-01 Product nuclide = 340740 : beta- + 2 RTYP = 2 Q = 2.56220E+00 MeV frac = 6.60000E-01 Product nuclide = 32074.82c : EC/beta+ + + Nuclide 628 / 1657 : 330751 -- arsenic 75m (As-75m) + + Pointers : 455157 -1000000 + Primary type : Decay + Nuclide ZAI : 330751 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 74.92162 + Atomic weight ratio (AWR) : 74.27800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 17.6 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 3.03920E-01 MeV frac = 1.00000E+00 Product nuclide = 33075.82c : IT + + Nuclide 629 / 1657 : 330760 -- arsenic 76 (As-76) + + Pointers : 455808 -1000000 + Primary type : Decay + Nuclide ZAI : 330760 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 75.92241 + Atomic weight ratio (AWR) : 75.27020 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.44E+04 seconds (1.09 days) + Specific ingestion toxicity : 1.60E-09 Sv/Bq + Specific inhalation toxicity : 7.40E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.96250E+00 MeV frac = 1.00000E+00 Product nuclide = 34076.82c : beta- + + Nuclide 630 / 1657 : 330770 -- arsenic 77 (As-77) + + Pointers : 458223 -1000000 + Primary type : Decay + Nuclide ZAI : 330770 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 76.92069 + Atomic weight ratio (AWR) : 76.25990 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.40E+05 seconds (1.62 days) + Specific ingestion toxicity : 4.00E-10 Sv/Bq + Specific inhalation toxicity : 3.90E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.83000E-01 MeV frac = 1.00000E+00 Product nuclide = 34077.82c : beta- + + Nuclide 631 / 1657 : 330780 -- arsenic 78 (As-78) + + Pointers : 459504 -1000000 + Primary type : Decay + Nuclide ZAI : 330780 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 77.92179 + Atomic weight ratio (AWR) : 77.25240 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.44E+03 seconds (1.51 hours) + Specific ingestion toxicity : 2.10E-10 Sv/Bq + Specific inhalation toxicity : 8.90E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.20900E+00 MeV frac = 1.00000E+00 Product nuclide = 34078.82c : beta- + + Nuclide 632 / 1657 : 330790 -- arsenic 79 (As-79) + + Pointers : 460869 -1000000 + Primary type : Decay + Nuclide ZAI : 330790 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 78.92097 + Atomic weight ratio (AWR) : 78.24300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.41E+02 seconds (9.01 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.28090E+00 MeV frac = 1.00000E+00 Product nuclide = 34079.82c : beta- + + Nuclide 633 / 1657 : 330800 -- arsenic 80 (As-80) + + Pointers : 461478 -1000000 + Primary type : Decay + Nuclide ZAI : 330800 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 79.92258 + Atomic weight ratio (AWR) : 79.23600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 15.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.60100E+00 MeV frac = 1.00000E+00 Product nuclide = 34080.82c : beta- + + Nuclide 634 / 1657 : 330810 -- arsenic 81 (As-81) + + Pointers : 462157 -1000000 + Primary type : Decay + Nuclide ZAI : 330810 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 80.92216 + Atomic weight ratio (AWR) : 80.22700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 33.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 3.85600E+00 MeV frac = 9.64110E-01 Product nuclide = 340810 : beta- + 2 RTYP = 1 Q = 3.75310E+00 MeV frac = 3.58897E-02 Product nuclide = 340811 : beta- + + Nuclide 635 / 1657 : 330820 -- arsenic 82 (As-82) + + Pointers : 463273 -1000000 + Primary type : Decay + Nuclide ZAI : 330820 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 81.92447 + Atomic weight ratio (AWR) : 81.22070 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 19.1 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.27000E+00 MeV frac = 1.00000E+00 Product nuclide = 34082.82c : beta- + + Nuclide 636 / 1657 : 330821 -- arsenic 82m (As-82m) + + Pointers : 463714 -1000000 + Primary type : Decay + Nuclide ZAI : 330821 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 81.92447 + Atomic weight ratio (AWR) : 81.22070 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 13.6 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.51500E+00 MeV frac = 1.00000E+00 Product nuclide = 34082.82c : beta- + + Nuclide 637 / 1657 : 330830 -- arsenic 83 (As-83) + + Pointers : 464477 -1000000 + Primary type : Decay + Nuclide ZAI : 330830 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 82.92497 + Atomic weight ratio (AWR) : 82.21260 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 13.4 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 5.46100E+00 MeV frac = 3.60000E-01 Product nuclide = 340830 : beta- + 2 RTYP = 1 Q = 5.23250E+00 MeV frac = 6.40000E-01 Product nuclide = 340831 : beta- + + Nuclide 638 / 1657 : 330840 -- arsenic 84 (As-84) + + Pointers : 464734 -1000000 + Primary type : Decay + Nuclide ZAI : 330840 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 83.92910 + Atomic weight ratio (AWR) : 83.20810 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.02 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 1 Q = 9.87200E+00 MeV frac = 9.97200E-01 Product nuclide = 340840 : beta- + 2 RTYP = 15 Q = 1.18970E+00 MeV frac = 1.40000E-03 Product nuclide = 340830 : beta- + neutron emission + 3 RTYP = 15 Q = 9.61202E-01 MeV frac = 1.40000E-03 Product nuclide = 340831 : beta- + neutron emission + + Nuclide 639 / 1657 : 330841 -- arsenic 84m (As-84m) + + Pointers : 465064 -1000000 + Primary type : Decay + Nuclide ZAI : 330841 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 83.92910 + Atomic weight ratio (AWR) : 83.20810 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.65 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.87200E+00 MeV frac = 1.00000E+00 Product nuclide = 340840 : beta- + + Nuclide 640 / 1657 : 330850 -- arsenic 85 (As-85) + + Pointers : 465248 -1000000 + Primary type : Decay + Nuclide ZAI : 330850 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 84.93181 + Atomic weight ratio (AWR) : 84.20220 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.04 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.91000E+00 MeV frac = 7.80000E-01 Product nuclide = 340850 : beta- + 2 RTYP = 15 Q = 4.37000E+00 MeV frac = 2.20000E-01 Product nuclide = 340840 : beta- + neutron emission + + Nuclide 641 / 1657 : 330860 -- arsenic 86 (As-86) + + Pointers : 466448 -1000000 + Primary type : Decay + Nuclide ZAI : 330860 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 85.93654 + Atomic weight ratio (AWR) : 85.19830 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.945 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.13910E+01 MeV frac = 6.70000E-01 Product nuclide = 340860 : beta- + 2 RTYP = 15 Q = 5.20670E+00 MeV frac = 3.30000E-01 Product nuclide = 340850 : beta- + neutron emission + + Nuclide 642 / 1657 : 330870 -- arsenic 87 (As-87) + + Pointers : 466705 -1000000 + Primary type : Decay + Nuclide ZAI : 330870 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 86.93986 + Atomic weight ratio (AWR) : 86.19300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.61 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.06000E+01 MeV frac = 8.46000E-01 Product nuclide = 340870 : beta- + 2 RTYP = 15 Q = 6.48970E+00 MeV frac = 1.54000E-01 Product nuclide = 340860 : beta- + neutron emission + + Nuclide 643 / 1657 : 330880 -- arsenic 88 (As-88) + + Pointers : 466962 -1000000 + Primary type : Decay + Nuclide ZAI : 330880 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 87.94489 + Atomic weight ratio (AWR) : 87.18940 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.25900E+01 MeV frac = 1.00000E+00 Product nuclide = 340880 : beta- + + Nuclide 644 / 1657 : 330890 -- arsenic 89 (As-89) + + Pointers : 467146 -1000000 + Primary type : Decay + Nuclide ZAI : 330890 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 88.94942 + Atomic weight ratio (AWR) : 88.18530 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.20600E+01 MeV frac = 1.00000E+00 Product nuclide = 340890 : beta- + + Nuclide 645 / 1657 : 330900 -- arsenic 90 (As-90) + + Pointers : 467330 -1000000 + Primary type : Decay + Nuclide ZAI : 330900 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 89.95547 + Atomic weight ratio (AWR) : 89.18270 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 80 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.44800E+01 MeV frac = 1.00000E+00 Product nuclide = 340900 : beta- + + Nuclide 646 / 1657 : 330910 -- arsenic 91 (As-91) + + Pointers : 467514 -1000000 + Primary type : Decay + Nuclide ZAI : 330910 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 90.96040 + Atomic weight ratio (AWR) : 90.17900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 50 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.34800E+01 MeV frac = 1.00000E+00 Product nuclide = 340910 : beta- + + Nuclide 647 / 1657 : 340740 -- selenium 74 (Se-74) + + Pointers : 467698 -1000000 + Primary type : Decay + Nuclide ZAI : 340740 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 73.92243 + Atomic weight ratio (AWR) : 73.28740 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 648 / 1657 : 340750 -- selenium 75 (Se-75) + + Pointers : 467804 -1000000 + Primary type : Decay + Nuclide ZAI : 340750 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 74.92252 + Atomic weight ratio (AWR) : 74.27890 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.03E+07 seconds (120 days) + Specific ingestion toxicity : 2.60E-09 Sv/Bq + Specific inhalation toxicity : 1.30E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 8.63600E-01 MeV frac = 9.39590E-01 Product nuclide = 33075.82c : EC/beta+ + 2 RTYP = 2 Q = 5.59676E-01 MeV frac = 6.04100E-02 Product nuclide = 330751 : EC/beta+ + + Nuclide 649 / 1657 : 340771 -- selenium 77m (Se-77m) + + Pointers : 474140 -1000000 + Primary type : Decay + Nuclide ZAI : 340771 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 76.91988 + Atomic weight ratio (AWR) : 76.25910 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 17.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.61922E-01 MeV frac = 1.00000E+00 Product nuclide = 34077.82c : IT + + Nuclide 650 / 1657 : 340791 -- selenium 79m (Se-79m) + + Pointers : 481369 -1000000 + Primary type : Decay + Nuclide ZAI : 340791 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 78.91855 + Atomic weight ratio (AWR) : 78.24060 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.34E+02 seconds (3.9 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 9.57700E-02 MeV frac = 9.99440E-01 Product nuclide = 34079.82c : IT + 2 RTYP = 1 Q = 2.46800E-01 MeV frac = 5.60000E-04 Product nuclide = 35079.82c : beta- + + Nuclide 651 / 1657 : 340810 -- selenium 81 (Se-81) + + Pointers : 484234 -1000000 + Primary type : Decay + Nuclide ZAI : 340810 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 80.91803 + Atomic weight ratio (AWR) : 80.22290 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.10E+03 seconds (18.4 minutes) + Specific ingestion toxicity : 2.70E-11 Sv/Bq + Specific inhalation toxicity : 1.50E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.58500E+00 MeV frac = 1.00000E+00 Product nuclide = 35081.82c : beta- + + Nuclide 652 / 1657 : 340811 -- selenium 81m (Se-81m) + + Pointers : 485193 -1000000 + Primary type : Decay + Nuclide ZAI : 340811 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 80.91803 + Atomic weight ratio (AWR) : 80.22290 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.44E+03 seconds (57.3 minutes) + Specific ingestion toxicity : 5.30E-11 Sv/Bq + Specific inhalation toxicity : 5.10E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.68800E+00 MeV frac = 6.80000E-04 Product nuclide = 35081.82c : beta- + 2 RTYP = 3 Q = 1.02990E-01 MeV frac = 9.99320E-01 Product nuclide = 340810 : IT + + Nuclide 653 / 1657 : 340830 -- selenium 83 (Se-83) + + Pointers : 488284 -1000000 + Primary type : Decay + Nuclide ZAI : 340830 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 82.91912 + Atomic weight ratio (AWR) : 82.20680 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.34E+03 seconds (22.3 minutes) + Specific ingestion toxicity : 4.70E-11 Sv/Bq + Specific inhalation toxicity : 3.40E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.66800E+00 MeV frac = 1.00000E+00 Product nuclide = 350830 : beta- + + Nuclide 654 / 1657 : 340831 -- selenium 83m (Se-83m) + + Pointers : 488468 -1000000 + Primary type : Decay + Nuclide ZAI : 340831 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 82.91912 + Atomic weight ratio (AWR) : 82.20680 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.01E+01 seconds (1.17 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.89750E+00 MeV frac = 1.00000E+00 Product nuclide = 350830 : beta- + + Nuclide 655 / 1657 : 340840 -- selenium 84 (Se-84) + + Pointers : 489217 -1000000 + Primary type : Decay + Nuclide ZAI : 340840 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 83.91850 + Atomic weight ratio (AWR) : 83.19760 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.96E+02 seconds (3.26 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.86300E+00 MeV frac = 1.00000E+00 Product nuclide = 350840 : beta- + + Nuclide 656 / 1657 : 340850 -- selenium 85 (Se-85) + + Pointers : 489476 -1000000 + Primary type : Decay + Nuclide ZAI : 340850 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 84.92223 + Atomic weight ratio (AWR) : 84.19270 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 31.7 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.18200E+00 MeV frac = 1.00000E+00 Product nuclide = 350850 : beta- + + Nuclide 657 / 1657 : 340860 -- selenium 86 (Se-86) + + Pointers : 489660 -1000000 + Primary type : Decay + Nuclide ZAI : 340860 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 85.92423 + Atomic weight ratio (AWR) : 85.18610 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 15.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.09901E+00 MeV frac = 1.00000E+00 Product nuclide = 350860 : beta- + + Nuclide 658 / 1657 : 340870 -- selenium 87 (Se-87) + + Pointers : 489844 -1000000 + Primary type : Decay + Nuclide ZAI : 340870 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 86.92856 + Atomic weight ratio (AWR) : 86.18180 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.27500E+00 MeV frac = 1.00000E+00 Product nuclide = 350870 : beta- + + Nuclide 659 / 1657 : 340880 -- selenium 88 (Se-88) + + Pointers : 490355 -1000000 + Primary type : Decay + Nuclide ZAI : 340880 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 87.93138 + Atomic weight ratio (AWR) : 87.17600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.53 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 6.85000E+00 MeV frac = 9.90100E-01 Product nuclide = 350880 : beta- + 2 RTYP = 15 Q = 1.90570E+00 MeV frac = 9.90000E-03 Product nuclide = 350870 : beta- + neutron emission + + Nuclide 660 / 1657 : 340890 -- selenium 89 (Se-89) + + Pointers : 490612 -1000000 + Primary type : Decay + Nuclide ZAI : 340890 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 88.93641 + Atomic weight ratio (AWR) : 88.17240 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.41 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 9.37000E+00 MeV frac = 9.22000E-01 Product nuclide = 350890 : beta- + 2 RTYP = 15 Q = 3.45870E+00 MeV frac = 7.80000E-02 Product nuclide = 350880 : beta- + neutron emission + + Nuclide 661 / 1657 : 340900 -- selenium 90 (Se-90) + + Pointers : 490869 -1000000 + Primary type : Decay + Nuclide ZAI : 340900 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 89.93993 + Atomic weight ratio (AWR) : 89.16730 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.69000E+00 MeV frac = 1.00000E+00 Product nuclide = 350900 : beta- + + Nuclide 662 / 1657 : 340910 -- selenium 91 (Se-91) + + Pointers : 491053 -1000000 + Primary type : Decay + Nuclide ZAI : 340910 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 90.94597 + Atomic weight ratio (AWR) : 90.16470 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.27 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.11700E+01 MeV frac = 7.90000E-01 Product nuclide = 350910 : beta- + 2 RTYP = 15 Q = 6.20870E+00 MeV frac = 2.10000E-01 Product nuclide = 350900 : beta- + neutron emission + + Nuclide 663 / 1657 : 340920 -- selenium 92 (Se-92) + + Pointers : 491310 -1000000 + Primary type : Decay + Nuclide ZAI : 340920 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 91.94990 + Atomic weight ratio (AWR) : 91.16000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 100 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.93000E+00 MeV frac = 1.00000E+00 Product nuclide = 350920 : beta- + + Nuclide 664 / 1657 : 340930 -- selenium 93 (Se-93) + + Pointers : 491494 -1000000 + Primary type : Decay + Nuclide ZAI : 340930 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 92.95624 + Atomic weight ratio (AWR) : 92.15770 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 50 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.23300E+01 MeV frac = 1.00000E+00 Product nuclide = 350930 : beta- + + Nuclide 665 / 1657 : 340940 -- selenium 94 (Se-94) + + Pointers : 491678 -1000000 + Primary type : Decay + Nuclide ZAI : 340940 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 93.96047 + Atomic weight ratio (AWR) : 93.15330 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 20 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.10000E+01 MeV frac = 1.00000E+00 Product nuclide = 350940 : beta- + + Nuclide 666 / 1657 : 350780 -- bromine 78 (Br-78) + + Pointers : 491862 -1000000 + Primary type : Decay + Nuclide ZAI : 350780 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 77.92118 + Atomic weight ratio (AWR) : 77.25180 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.87E+02 seconds (6.45 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 3.57400E+00 MeV frac = 1.00000E+00 Product nuclide = 34078.82c : EC/beta+ + + Nuclide 667 / 1657 : 350791 -- bromine 79m (Br-79m) + + Pointers : 495069 -1000000 + Primary type : Decay + Nuclide ZAI : 350791 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 78.91835 + Atomic weight ratio (AWR) : 78.24040 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.86 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 2.07200E-01 MeV frac = 1.00000E+00 Product nuclide = 35079.82c : IT + + Nuclide 668 / 1657 : 350800 -- bromine 80 (Br-80) + + Pointers : 495412 -1000000 + Primary type : Decay + Nuclide ZAI : 350800 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 79.91854 + Atomic weight ratio (AWR) : 79.23200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.06E+03 seconds (17.6 minutes) + Specific ingestion toxicity : 3.10E-11 Sv/Bq + Specific inhalation toxicity : 9.40E-12 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 2.00600E+00 MeV frac = 9.17000E-01 Product nuclide = 36080.82c : beta- + 2 RTYP = 2 Q = 1.87030E+00 MeV frac = 8.30000E-02 Product nuclide = 34080.82c : EC/beta+ + + Nuclide 669 / 1657 : 350801 -- bromine 80m (Br-80m) + + Pointers : 496346 -1000000 + Primary type : Decay + Nuclide ZAI : 350801 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 79.91854 + Atomic weight ratio (AWR) : 79.23200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.59E+04 seconds (4.41 hours) + Specific ingestion toxicity : 1.10E-10 Sv/Bq + Specific inhalation toxicity : 7.60E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 8.58500E-02 MeV frac = 1.00000E+00 Product nuclide = 350800 : IT + + Nuclide 670 / 1657 : 350820 -- bromine 82 (Br-82) + + Pointers : 498888 -1000000 + Primary type : Decay + Nuclide ZAI : 350820 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 81.91681 + Atomic weight ratio (AWR) : 81.21310 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.27E+05 seconds (1.47 days) + Specific ingestion toxicity : 5.40E-10 Sv/Bq + Specific inhalation toxicity : 6.30E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.09250E+00 MeV frac = 1.00000E+00 Product nuclide = 36082.82c : beta- + + Nuclide 671 / 1657 : 350821 -- bromine 82m (Br-82m) + + Pointers : 500589 -1000000 + Primary type : Decay + Nuclide ZAI : 350821 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 81.91681 + Atomic weight ratio (AWR) : 81.21310 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.65E+02 seconds (6.09 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 3.13840E+00 MeV frac = 2.40000E-02 Product nuclide = 36082.82c : beta- + 2 RTYP = 3 Q = 4.59490E-02 MeV frac = 9.76000E-01 Product nuclide = 350820 : IT + + Nuclide 672 / 1657 : 350830 -- bromine 83 (Br-83) + + Pointers : 502013 -1000000 + Primary type : Decay + Nuclide ZAI : 350830 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 82.91519 + Atomic weight ratio (AWR) : 82.20290 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.64E+03 seconds (2.4 hours) + Specific ingestion toxicity : 4.30E-11 Sv/Bq + Specific inhalation toxicity : 4.80E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 9.73000E-01 MeV frac = 8.89466E-04 Product nuclide = 36083.82c : beta- + 2 RTYP = 1 Q = 9.31445E-01 MeV frac = 9.99111E-01 Product nuclide = 360831 : beta- + + Nuclide 673 / 1657 : 350840 -- bromine 84 (Br-84) + + Pointers : 502499 -1000000 + Primary type : Decay + Nuclide ZAI : 350840 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 83.91649 + Atomic weight ratio (AWR) : 83.19560 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.91E+03 seconds (31.8 minutes) + Specific ingestion toxicity : 8.80E-11 Sv/Bq + Specific inhalation toxicity : 3.70E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.62900E+00 MeV frac = 1.00000E+00 Product nuclide = 36084.82c : beta- + + Nuclide 674 / 1657 : 350841 -- bromine 84m (Br-84m) + + Pointers : 504298 -1000000 + Primary type : Decay + Nuclide ZAI : 350841 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 83.91649 + Atomic weight ratio (AWR) : 83.19560 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.60E+02 seconds (6 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.94900E+00 MeV frac = 1.00000E+00 Product nuclide = 36084.82c : beta- + + Nuclide 675 / 1657 : 350850 -- bromine 85 (Br-85) + + Pointers : 504865 -1000000 + Primary type : Decay + Nuclide ZAI : 350850 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 84.91557 + Atomic weight ratio (AWR) : 84.18610 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.74E+02 seconds (2.9 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 2.87000E+00 MeV frac = 1.62621E-03 Product nuclide = 36085.82c : beta- + 2 RTYP = 1 Q = 2.56512E+00 MeV frac = 9.98374E-01 Product nuclide = 360851 : beta- + + Nuclide 676 / 1657 : 350860 -- bromine 86 (Br-86) + + Pointers : 505631 -1000000 + Primary type : Decay + Nuclide ZAI : 350860 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 85.91879 + Atomic weight ratio (AWR) : 85.18070 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 55 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.62600E+00 MeV frac = 1.00000E+00 Product nuclide = 36086.82c : beta- + + Nuclide 677 / 1657 : 350870 -- bromine 87 (Br-87) + + Pointers : 506352 -1000000 + Primary type : Decay + Nuclide ZAI : 350870 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 86.92069 + Atomic weight ratio (AWR) : 86.17400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 55.7 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 6.85300E+00 MeV frac = 9.74900E-01 Product nuclide = 360870 : beta- + 2 RTYP = 15 Q = 1.33700E+00 MeV frac = 2.51000E-02 Product nuclide = 36086.82c : beta- + neutron emission + + Nuclide 678 / 1657 : 350880 -- bromine 88 (Br-88) + + Pointers : 515560 -1000000 + Primary type : Decay + Nuclide ZAI : 350880 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 87.92411 + Atomic weight ratio (AWR) : 87.16880 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 16.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.96000E+00 MeV frac = 9.33000E-01 Product nuclide = 360880 : beta- + 2 RTYP = 15 Q = 1.92000E+00 MeV frac = 6.70000E-02 Product nuclide = 360870 : beta- + neutron emission + + Nuclide 679 / 1657 : 350890 -- bromine 89 (Br-89) + + Pointers : 520288 -1000000 + Primary type : Decay + Nuclide ZAI : 350890 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 88.92643 + Atomic weight ratio (AWR) : 88.16250 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.37 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.15500E+00 MeV frac = 8.59000E-01 Product nuclide = 360890 : beta- + 2 RTYP = 15 Q = 3.05100E+00 MeV frac = 1.41000E-01 Product nuclide = 360880 : beta- + neutron emission + + Nuclide 680 / 1657 : 350900 -- bromine 90 (Br-90) + + Pointers : 523588 -1000000 + Primary type : Decay + Nuclide ZAI : 350900 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 89.93065 + Atomic weight ratio (AWR) : 89.15810 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.9 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.03500E+01 MeV frac = 7.54000E-01 Product nuclide = 360900 : beta- + 2 RTYP = 15 Q = 4.04000E+00 MeV frac = 2.46000E-01 Product nuclide = 360890 : beta- + neutron emission + + Nuclide 681 / 1657 : 350910 -- bromine 91 (Br-91) + + Pointers : 525936 -1000000 + Primary type : Decay + Nuclide ZAI : 350910 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 90.93397 + Atomic weight ratio (AWR) : 90.15280 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.538 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 9.80200E+00 MeV frac = 8.00000E-01 Product nuclide = 360910 : beta- + 2 RTYP = 15 Q = 5.70000E+00 MeV frac = 2.00000E-01 Product nuclide = 360900 : beta- + neutron emission + + Nuclide 682 / 1657 : 350920 -- bromine 92 (Br-92) + + Pointers : 526688 -1000000 + Primary type : Decay + Nuclide ZAI : 350920 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 91.93931 + Atomic weight ratio (AWR) : 91.14950 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.343 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.22050E+01 MeV frac = 6.69000E-01 Product nuclide = 360920 : beta- + 2 RTYP = 15 Q = 6.65870E+00 MeV frac = 3.31000E-01 Product nuclide = 360910 : beta- + neutron emission + + Nuclide 683 / 1657 : 350930 -- bromine 93 (Br-93) + + Pointers : 526945 -1000000 + Primary type : Decay + Nuclide ZAI : 350930 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 92.94303 + Atomic weight ratio (AWR) : 92.14460 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.102 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.09700E+01 MeV frac = 3.20000E-01 Product nuclide = 360930 : beta- + 2 RTYP = 15 Q = 7.66370E+00 MeV frac = 6.80000E-01 Product nuclide = 360920 : beta- + neutron emission + + Nuclide 684 / 1657 : 350940 -- bromine 94 (Br-94) + + Pointers : 527202 -1000000 + Primary type : Decay + Nuclide ZAI : 350940 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 93.94867 + Atomic weight ratio (AWR) : 93.14160 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 70 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.33400E+01 MeV frac = 3.00000E-01 Product nuclide = 360940 : beta- + 2 RTYP = 15 Q = 8.14870E+00 MeV frac = 7.00000E-01 Product nuclide = 360930 : beta- + neutron emission + + Nuclide 685 / 1657 : 350950 -- bromine 95 (Br-95) + + Pointers : 527459 -1000000 + Primary type : Decay + Nuclide ZAI : 350950 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 94.95290 + Atomic weight ratio (AWR) : 94.13720 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 50 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.21400E+01 MeV frac = 1.00000E+00 Product nuclide = 360950 : beta- + + Nuclide 686 / 1657 : 350960 -- bromine 96 (Br-96) + + Pointers : 527643 -1000000 + Primary type : Decay + Nuclide ZAI : 350960 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 95.95853 + Atomic weight ratio (AWR) : 95.13420 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 20 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.44000E+01 MeV frac = 1.00000E+00 Product nuclide = 360960 : beta- + + Nuclide 687 / 1657 : 360790 -- krypton 79 (Kr-79) + + Pointers : 527827 -1000000 + Primary type : Decay + Nuclide ZAI : 360790 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 78.92007 + Atomic weight ratio (AWR) : 78.24210 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.26E+05 seconds (1.46 days) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 1.63100E+00 MeV frac = 1.00000E+00 Product nuclide = 35079.82c : EC/beta+ + + Nuclide 688 / 1657 : 360810 -- krypton 81 (Kr-81) + + Pointers : 531820 -1000000 + Primary type : Decay + Nuclide ZAI : 360810 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 80.91662 + Atomic weight ratio (AWR) : 80.22150 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.63E+12 seconds (210,144 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 2.80800E-01 MeV frac = 1.00000E+00 Product nuclide = 35081.82c : EC/beta+ + + Nuclide 689 / 1657 : 360811 -- krypton 81m (Kr-81m) + + Pointers : 532205 -1000000 + Primary type : Decay + Nuclide ZAI : 360811 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 80.91662 + Atomic weight ratio (AWR) : 80.22150 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 13.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 4.71300E-01 MeV frac = 2.50000E-05 Product nuclide = 35081.82c : EC/beta+ + 2 RTYP = 3 Q = 1.90530E-01 MeV frac = 9.99975E-01 Product nuclide = 360810 : IT + + Nuclide 690 / 1657 : 360831 -- krypton 83m (Kr-83m) + + Pointers : 538578 -1000000 + Primary type : Decay + Nuclide ZAI : 360831 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 82.91418 + Atomic weight ratio (AWR) : 82.20190 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.59E+03 seconds (1.83 hours) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 4.15430E-02 MeV frac = 1.00000E+00 Product nuclide = 36083.82c : IT + + Nuclide 691 / 1657 : 360851 -- krypton 85m (Kr-85m) + + Pointers : 544026 -1000000 + Primary type : Decay + Nuclide ZAI : 360851 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 84.91254 + Atomic weight ratio (AWR) : 84.18310 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.61E+04 seconds (4.48 hours) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 9.92260E-01 MeV frac = 7.86000E-01 Product nuclide = 37085.82c : beta- + 2 RTYP = 3 Q = 3.04870E-01 MeV frac = 2.14000E-01 Product nuclide = 36085.82c : IT + + Nuclide 692 / 1657 : 360870 -- krypton 87 (Kr-87) + + Pointers : 547579 -1000000 + Primary type : Decay + Nuclide ZAI : 360870 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 86.91333 + Atomic weight ratio (AWR) : 86.16670 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.58E+03 seconds (1.27 hours) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.88700E+00 MeV frac = 1.00000E+00 Product nuclide = 37087.82c : beta- + + Nuclide 693 / 1657 : 360880 -- krypton 88 (Kr-88) + + Pointers : 548482 -1000000 + Primary type : Decay + Nuclide ZAI : 360880 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 87.91443 + Atomic weight ratio (AWR) : 87.15920 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.02E+04 seconds (2.84 hours) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.91700E+00 MeV frac = 1.00000E+00 Product nuclide = 370880 : beta- + + Nuclide 694 / 1657 : 360890 -- krypton 89 (Kr-89) + + Pointers : 550407 -1000000 + Primary type : Decay + Nuclide ZAI : 360890 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 88.91765 + Atomic weight ratio (AWR) : 88.15380 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.89E+02 seconds (3.15 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.17650E+00 MeV frac = 1.00000E+00 Product nuclide = 370890 : beta- + + Nuclide 695 / 1657 : 360900 -- krypton 90 (Kr-90) + + Pointers : 555454 -1000000 + Primary type : Decay + Nuclide ZAI : 360900 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 89.91956 + Atomic weight ratio (AWR) : 89.14710 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 32.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 4.40600E+00 MeV frac = 8.72000E-01 Product nuclide = 370900 : beta- + 2 RTYP = 1 Q = 4.29900E+00 MeV frac = 1.28000E-01 Product nuclide = 370901 : beta- + + Nuclide 696 / 1657 : 360910 -- krypton 91 (Kr-91) + + Pointers : 558194 -1000000 + Primary type : Decay + Nuclide ZAI : 360910 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 90.92348 + Atomic weight ratio (AWR) : 90.14240 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.57 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.77100E+00 MeV frac = 1.00000E+00 Product nuclide = 370910 : beta- + + Nuclide 697 / 1657 : 360920 -- krypton 92 (Kr-92) + + Pointers : 562541 -1000000 + Primary type : Decay + Nuclide ZAI : 360920 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 91.92619 + Atomic weight ratio (AWR) : 91.13650 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.84 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.00300E+00 MeV frac = 1.00000E+00 Product nuclide = 370920 : beta- + + Nuclide 698 / 1657 : 360930 -- krypton 93 (Kr-93) + + Pointers : 564410 -1000000 + Primary type : Decay + Nuclide ZAI : 360930 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 92.93123 + Atomic weight ratio (AWR) : 92.13290 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.29 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.48500E+00 MeV frac = 1.00000E+00 Product nuclide = 370930 : beta- + + Nuclide 699 / 1657 : 360940 -- krypton 94 (Kr-94) + + Pointers : 568617 -1000000 + Primary type : Decay + Nuclide ZAI : 360940 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 93.93435 + Atomic weight ratio (AWR) : 93.12740 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.21 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 7.41300E+00 MeV frac = 9.88900E-01 Product nuclide = 370940 : beta- + 2 RTYP = 15 Q = 3.40670E+00 MeV frac = 1.11000E-02 Product nuclide = 370930 : beta- + neutron emission + + Nuclide 700 / 1657 : 360950 -- krypton 95 (Kr-95) + + Pointers : 568874 -1000000 + Primary type : Decay + Nuclide ZAI : 360950 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 94.93988 + Atomic weight ratio (AWR) : 94.12430 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.114 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 9.81400E+00 MeV frac = 9.71300E-01 Product nuclide = 370950 : beta- + 2 RTYP = 15 Q = 4.44170E+00 MeV frac = 2.87000E-02 Product nuclide = 370940 : beta- + neutron emission + + Nuclide 701 / 1657 : 360960 -- krypton 96 (Kr-96) + + Pointers : 569131 -1000000 + Primary type : Decay + Nuclide ZAI : 360960 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 95.94310 + Atomic weight ratio (AWR) : 95.11890 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 80 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 1 Q = 8.19500E+00 MeV frac = 4.81500E-01 Product nuclide = 370960 : beta- + 2 RTYP = 1 Q = 8.19500E+00 MeV frac = 4.81500E-01 Product nuclide = 370961 : beta- + 3 RTYP = 15 Q = 4.75270E+00 MeV frac = 3.70000E-02 Product nuclide = 370950 : beta- + neutron emission + + Nuclide 702 / 1657 : 360970 -- krypton 97 (Kr-97) + + Pointers : 569461 -1000000 + Primary type : Decay + Nuclide ZAI : 360970 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 96.94854 + Atomic weight ratio (AWR) : 96.11570 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 63 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 1 Q = 1.04400E+01 MeV frac = 9.33000E-01 Product nuclide = 370970 : beta- + 2 RTYP = 15 Q = 5.23370E+00 MeV frac = 3.35000E-02 Product nuclide = 370960 : beta- + neutron emission + 3 RTYP = 15 Q = 5.23370E+00 MeV frac = 3.35000E-02 Product nuclide = 370961 : beta- + neutron emission + + Nuclide 703 / 1657 : 360980 -- krypton 98 (Kr-98) + + Pointers : 569791 -1000000 + Primary type : Decay + Nuclide ZAI : 360980 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 97.95196 + Atomic weight ratio (AWR) : 97.11050 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 46 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 9.03000E+00 MeV frac = 9.30000E-01 Product nuclide = 370981 : beta- + 2 RTYP = 15 Q = 5.48870E+00 MeV frac = 7.00000E-02 Product nuclide = 370970 : beta- + neutron emission + + Nuclide 704 / 1657 : 360990 -- krypton 99 (Kr-99) + + Pointers : 570048 -1000000 + Primary type : Decay + Nuclide ZAI : 360990 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 98.95760 + Atomic weight ratio (AWR) : 98.10750 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 40 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 1 Q = 1.13800E+01 MeV frac = 8.90000E-01 Product nuclide = 370990 : beta- + 2 RTYP = 15 Q = 6.64870E+00 MeV frac = 5.50000E-02 Product nuclide = 370980 : beta- + neutron emission + 3 RTYP = 15 Q = 6.25870E+00 MeV frac = 5.50000E-02 Product nuclide = 370981 : beta- + neutron emission + + Nuclide 705 / 1657 : 370830 -- rubidium 83 (Rb-83) + + Pointers : 570378 -1000000 + Primary type : Decay + Nuclide ZAI : 370830 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 82.91508 + Atomic weight ratio (AWR) : 82.20280 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.45E+06 seconds (86.2 days) + Specific ingestion toxicity : 1.90E-09 Sv/Bq + Specific inhalation toxicity : 6.90E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 9.40000E-01 MeV frac = 2.50000E-01 Product nuclide = 36083.82c : EC/beta+ + 2 RTYP = 2 Q = 8.98000E-01 MeV frac = 7.50000E-01 Product nuclide = 360831 : EC/beta+ + + Nuclide 706 / 1657 : 370831 -- rubidium 83m (Rb-83m) + + Pointers : 571396 -1000000 + Primary type : Decay + Nuclide ZAI : 370831 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 82.91508 + Atomic weight ratio (AWR) : 82.20280 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.8 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 4.21100E-02 MeV frac = 1.00000E+00 Product nuclide = 370830 : IT + + Nuclide 707 / 1657 : 370840 -- rubidium 84 (Rb-84) + + Pointers : 571580 -1000000 + Primary type : Decay + Nuclide ZAI : 370840 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 83.91437 + Atomic weight ratio (AWR) : 83.19350 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.89E+06 seconds (33.5 days) + Specific ingestion toxicity : 2.80E-09 Sv/Bq + Specific inhalation toxicity : 1.00E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.94000E-01 MeV frac = 3.20000E-02 Product nuclide = 380840 : beta- + 2 RTYP = 2 Q = 2.68500E+00 MeV frac = 9.68000E-01 Product nuclide = 36084.82c : EC/beta+ + + Nuclide 708 / 1657 : 370841 -- rubidium 84m (Rb-84m) + + Pointers : 572066 -1000000 + Primary type : Decay + Nuclide ZAI : 370841 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 83.91437 + Atomic weight ratio (AWR) : 83.19350 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.22E+03 seconds (20.4 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 4.63600E-01 MeV frac = 1.00000E+00 Product nuclide = 370840 : IT + + Nuclide 709 / 1657 : 370861 -- rubidium 86m (Rb-86m) + + Pointers : 576714 -1000000 + Primary type : Decay + Nuclide ZAI : 370861 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 85.91122 + Atomic weight ratio (AWR) : 85.17320 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.10E+01 seconds (1.02 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 5.56000E-01 MeV frac = 1.00000E+00 Product nuclide = 37086.82c : IT + + Nuclide 710 / 1657 : 370880 -- rubidium 88 (Rb-88) + + Pointers : 579082 -1000000 + Primary type : Decay + Nuclide ZAI : 370880 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 87.91130 + Atomic weight ratio (AWR) : 87.15610 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.07E+03 seconds (17.8 minutes) + Specific ingestion toxicity : 9.00E-11 Sv/Bq + Specific inhalation toxicity : 1.60E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.31600E+00 MeV frac = 1.00000E+00 Product nuclide = 38088.82c : beta- + + Nuclide 711 / 1657 : 370890 -- rubidium 89 (Rb-89) + + Pointers : 579985 -1000000 + Primary type : Decay + Nuclide ZAI : 370890 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 88.91230 + Atomic weight ratio (AWR) : 88.14850 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.24E+02 seconds (15.4 minutes) + Specific ingestion toxicity : 4.70E-11 Sv/Bq + Specific inhalation toxicity : 1.40E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.49600E+00 MeV frac = 1.00000E+00 Product nuclide = 38089.82c : beta- + + Nuclide 712 / 1657 : 370900 -- rubidium 90 (Rb-90) + + Pointers : 583058 -1000000 + Primary type : Decay + Nuclide ZAI : 370900 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 89.91482 + Atomic weight ratio (AWR) : 89.14240 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.57E+02 seconds (2.62 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.58400E+00 MeV frac = 1.00000E+00 Product nuclide = 38090.82c : beta- + + Nuclide 713 / 1657 : 370901 -- rubidium 90m (Rb-90m) + + Pointers : 585683 -1000000 + Primary type : Decay + Nuclide ZAI : 370901 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 89.91482 + Atomic weight ratio (AWR) : 89.14240 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.58E+02 seconds (4.3 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 1.06900E-01 MeV frac = 2.60000E-02 Product nuclide = 370900 : IT + 2 RTYP = 1 Q = 6.69390E+00 MeV frac = 9.74000E-01 Product nuclide = 38090.82c : beta- + + Nuclide 714 / 1657 : 370910 -- rubidium 91 (Rb-91) + + Pointers : 588241 -1000000 + Primary type : Decay + Nuclide ZAI : 370910 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 90.91652 + Atomic weight ratio (AWR) : 90.13550 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 58.4 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.89100E+00 MeV frac = 1.00000E+00 Product nuclide = 380910 : beta- + + Nuclide 715 / 1657 : 370920 -- rubidium 92 (Rb-92) + + Pointers : 591020 -1000000 + Primary type : Decay + Nuclide ZAI : 370920 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 91.91974 + Atomic weight ratio (AWR) : 91.13010 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.48 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.09500E+00 MeV frac = 1.00000E+00 Product nuclide = 380920 : beta- + + Nuclide 716 / 1657 : 370930 -- rubidium 93 (Rb-93) + + Pointers : 592875 -1000000 + Primary type : Decay + Nuclide ZAI : 370930 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 92.92205 + Atomic weight ratio (AWR) : 92.12380 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.8 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 7.46200E+00 MeV frac = 9.86000E-01 Product nuclide = 380930 : beta- + 2 RTYP = 15 Q = 2.20600E+00 MeV frac = 1.40000E-02 Product nuclide = 380920 : beta- + neutron emission + + Nuclide 717 / 1657 : 370940 -- rubidium 94 (Rb-94) + + Pointers : 599409 -1000000 + Primary type : Decay + Nuclide ZAI : 370940 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 93.92648 + Atomic weight ratio (AWR) : 93.11960 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.7 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.02910E+01 MeV frac = 8.99000E-01 Product nuclide = 380940 : beta- + 2 RTYP = 15 Q = 3.46500E+00 MeV frac = 1.01000E-01 Product nuclide = 380930 : beta- + neutron emission + + Nuclide 718 / 1657 : 370950 -- rubidium 95 (Rb-95) + + Pointers : 604389 -1000000 + Primary type : Decay + Nuclide ZAI : 370950 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 94.92929 + Atomic weight ratio (AWR) : 94.11380 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.381 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 9.27900E+00 MeV frac = 9.14000E-01 Product nuclide = 380950 : beta- + 2 RTYP = 15 Q = 4.93200E+00 MeV frac = 8.60000E-02 Product nuclide = 380940 : beta- + neutron emission + + Nuclide 719 / 1657 : 370960 -- rubidium 96 (Rb-96) + + Pointers : 610587 -1000000 + Primary type : Decay + Nuclide ZAI : 370960 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 95.93433 + Atomic weight ratio (AWR) : 95.11020 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.199 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.17700E+01 MeV frac = 8.66000E-01 Product nuclide = 380960 : beta- + 2 RTYP = 15 Q = 5.86100E+00 MeV frac = 1.34000E-01 Product nuclide = 380950 : beta- + neutron emission + + Nuclide 720 / 1657 : 370961 -- rubidium 96m (Rb-96m) + + Pointers : 612543 -1000000 + Primary type : Decay + Nuclide ZAI : 370961 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 95.93433 + Atomic weight ratio (AWR) : 95.11020 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.17140E+01 MeV frac = 5.00000E-01 Product nuclide = 380960 : beta- + 2 RTYP = 3 Q = 0.00000E+00 MeV frac = 5.00000E-01 Product nuclide = 370960 : IT + + Nuclide 721 / 1657 : 370970 -- rubidium 97 (Rb-97) + + Pointers : 612800 -1000000 + Primary type : Decay + Nuclide ZAI : 370970 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 96.93734 + Atomic weight ratio (AWR) : 96.10460 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.17 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.05200E+01 MeV frac = 7.49000E-01 Product nuclide = 380970 : beta- + 2 RTYP = 15 Q = 6.53700E+00 MeV frac = 2.51000E-01 Product nuclide = 380960 : beta- + neutron emission + + Nuclide 722 / 1657 : 370980 -- rubidium 98 (Rb-98) + + Pointers : 614952 -1000000 + Primary type : Decay + Nuclide ZAI : 370980 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 97.94177 + Atomic weight ratio (AWR) : 97.10040 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.114 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 1 Q = 1.24260E+01 MeV frac = 8.61490E-01 Product nuclide = 380980 : beta- + 2 RTYP = 15 Q = 6.49670E+00 MeV frac = 1.38000E-01 Product nuclide = 380970 : beta- + neutron emission + 3 RTYP = 155 Q = 2.57640E+00 MeV frac = 5.10000E-04 Product nuclide = 380960 : beta- + neutron emission + neutron emission + + Nuclide 723 / 1657 : 370981 -- rubidium 98m (Rb-98m) + + Pointers : 615282 -1000000 + Primary type : Decay + Nuclide ZAI : 370981 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 97.94177 + Atomic weight ratio (AWR) : 97.10040 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 96 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.28160E+01 MeV frac = 1.00000E+00 Product nuclide = 380980 : beta- + + Nuclide 724 / 1657 : 370990 -- rubidium 99 (Rb-99) + + Pointers : 615466 -1000000 + Primary type : Decay + Nuclide ZAI : 370990 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 98.94539 + Atomic weight ratio (AWR) : 98.09540 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 50.3 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.13100E+01 MeV frac = 8.41000E-01 Product nuclide = 380990 : beta- + 2 RTYP = 15 Q = 7.69470E+00 MeV frac = 1.59000E-01 Product nuclide = 380980 : beta- + neutron emission + + Nuclide 725 / 1657 : 371000 -- rubidium 100 (Rb-100) + + Pointers : 615723 -1000000 + Primary type : Decay + Nuclide ZAI : 371000 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 99.94982 + Atomic weight ratio (AWR) : 99.09120 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 51 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 1 Q = 1.35200E+01 MeV frac = 9.42500E-01 Product nuclide = 381000 : beta- + 2 RTYP = 15 Q = 7.41870E+00 MeV frac = 5.60000E-02 Product nuclide = 380990 : beta- + neutron emission + 3 RTYP = 155 Q = 3.80340E+00 MeV frac = 1.50000E-03 Product nuclide = 380980 : beta- + neutron emission + neutron emission + + Nuclide 726 / 1657 : 371010 -- rubidium 101 (Rb-101) + + Pointers : 616053 -1000000 + Primary type : Decay + Nuclide ZAI : 371010 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 100.95324 + Atomic weight ratio (AWR) : 100.08600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 32 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.18100E+01 MeV frac = 1.00000E+00 Product nuclide = 381010 : beta- + + Nuclide 727 / 1657 : 380840 -- strontium 84 (Sr-84) + + Pointers : 616830 -1000000 + Primary type : Decay + Nuclide ZAI : 380840 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 83.91346 + Atomic weight ratio (AWR) : 83.19260 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 728 / 1657 : 380850 -- strontium 85 (Sr-85) + + Pointers : 616936 -1000000 + Primary type : Decay + Nuclide ZAI : 380850 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 84.91295 + Atomic weight ratio (AWR) : 84.18350 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.60E+06 seconds (64.8 days) + Specific ingestion toxicity : 5.60E-10 Sv/Bq + Specific inhalation toxicity : 8.10E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 1.06500E+00 MeV frac = 1.00000E+00 Product nuclide = 37085.82c : EC/beta+ + + Nuclide 729 / 1657 : 380851 -- strontium 85m (Sr-85m) + + Pointers : 617727 -1000000 + Primary type : Decay + Nuclide ZAI : 380851 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 84.91295 + Atomic weight ratio (AWR) : 84.18350 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.06E+03 seconds (1.13 hours) + Specific ingestion toxicity : 6.10E-12 Sv/Bq + Specific inhalation toxicity : 4.30E-12 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 1.30400E+00 MeV frac = 1.34000E-01 Product nuclide = 37085.82c : EC/beta+ + 2 RTYP = 3 Q = 2.38660E-01 MeV frac = 8.66000E-01 Product nuclide = 380850 : IT + + Nuclide 730 / 1657 : 380871 -- strontium 87m (Sr-87m) + + Pointers : 623251 -1000000 + Primary type : Decay + Nuclide ZAI : 380871 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 86.90889 + Atomic weight ratio (AWR) : 86.16230 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.01E+04 seconds (2.82 hours) + Specific ingestion toxicity : 3.00E-11 Sv/Bq + Specific inhalation toxicity : 2.10E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 1.05900E-01 MeV frac = 3.00000E-03 Product nuclide = 37087.82c : EC/beta+ + 2 RTYP = 3 Q = 3.88533E-01 MeV frac = 9.97000E-01 Product nuclide = 38087.82c : IT + + Nuclide 731 / 1657 : 380910 -- strontium 91 (Sr-91) + + Pointers : 630832 -1000000 + Primary type : Decay + Nuclide ZAI : 380910 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 90.91017 + Atomic weight ratio (AWR) : 90.12920 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.47E+04 seconds (9.65 hours) + Specific ingestion toxicity : 6.50E-10 Sv/Bq + Specific inhalation toxicity : 4.10E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 2.69900E+00 MeV frac = 4.11637E-01 Product nuclide = 39091.82c : beta- + 2 RTYP = 1 Q = 2.14342E+00 MeV frac = 5.88363E-01 Product nuclide = 390911 : beta- + + Nuclide 732 / 1657 : 380920 -- strontium 92 (Sr-92) + + Pointers : 632466 -1000000 + Primary type : Decay + Nuclide ZAI : 380920 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 91.91106 + Atomic weight ratio (AWR) : 91.12150 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.76E+03 seconds (2.71 hours) + Specific ingestion toxicity : 4.30E-10 Sv/Bq + Specific inhalation toxicity : 2.30E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.94000E+00 MeV frac = 1.00000E+00 Product nuclide = 390920 : beta- + + Nuclide 733 / 1657 : 380930 -- strontium 93 (Sr-93) + + Pointers : 633145 -1000000 + Primary type : Decay + Nuclide ZAI : 380930 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 92.91398 + Atomic weight ratio (AWR) : 92.11580 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.45E+02 seconds (7.42 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 4.13700E+00 MeV frac = 7.49759E-01 Product nuclide = 390930 : beta- + 2 RTYP = 1 Q = 3.37828E+00 MeV frac = 2.50241E-01 Product nuclide = 390931 : beta- + + Nuclide 734 / 1657 : 380940 -- strontium 94 (Sr-94) + + Pointers : 636011 -1000000 + Primary type : Decay + Nuclide ZAI : 380940 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 93.91538 + Atomic weight ratio (AWR) : 93.10860 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.53E+01 seconds (1.25 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.51000E+00 MeV frac = 1.00000E+00 Product nuclide = 390940 : beta- + + Nuclide 735 / 1657 : 380950 -- strontium 95 (Sr-95) + + Pointers : 637264 -1000000 + Primary type : Decay + Nuclide ZAI : 380950 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 94.91931 + Atomic weight ratio (AWR) : 94.10390 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 23.9 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.09000E+00 MeV frac = 1.00000E+00 Product nuclide = 390950 : beta- + + Nuclide 736 / 1657 : 380960 -- strontium 96 (Sr-96) + + Pointers : 639287 -1000000 + Primary type : Decay + Nuclide ZAI : 380960 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 95.92172 + Atomic weight ratio (AWR) : 95.09770 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.07 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.41500E+00 MeV frac = 1.00000E+00 Product nuclide = 390960 : beta- + + Nuclide 737 / 1657 : 380970 -- strontium 97 (Sr-97) + + Pointers : 640232 -1000000 + Primary type : Decay + Nuclide ZAI : 380970 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 96.92615 + Atomic weight ratio (AWR) : 96.09350 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.429 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 4 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 4 decay reactions: + + 1 RTYP = 1 Q = 7.47000E+00 MeV frac = 8.50774E-01 Product nuclide = 390970 : beta- + 2 RTYP = 1 Q = 6.80249E+00 MeV frac = 1.48726E-01 Product nuclide = 390971 : beta- + 3 RTYP = 15 Q = 1.48770E+00 MeV frac = 2.50000E-04 Product nuclide = 390960 : beta- + neutron emission + 4 RTYP = 15 Q = 3.47698E-01 MeV frac = 2.50000E-04 Product nuclide = 390961 : beta- + neutron emission + + Nuclide 738 / 1657 : 380980 -- strontium 98 (Sr-98) + + Pointers : 640635 -1000000 + Primary type : Decay + Nuclide ZAI : 380980 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 97.92846 + Atomic weight ratio (AWR) : 97.08720 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.653 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.82300E+00 MeV frac = 1.00000E+00 Product nuclide = 390980 : beta- + + Nuclide 739 / 1657 : 380990 -- strontium 99 (Sr-99) + + Pointers : 642406 -1000000 + Primary type : Decay + Nuclide ZAI : 380990 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 98.93319 + Atomic weight ratio (AWR) : 98.08330 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.27 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.53000E+00 MeV frac = 1.00000E+00 Product nuclide = 390990 : beta- + + Nuclide 740 / 1657 : 381000 -- strontium 100 (Sr-100) + + Pointers : 644555 -1000000 + Primary type : Decay + Nuclide ZAI : 381000 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 99.93540 + Atomic weight ratio (AWR) : 99.07690 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.202 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 7.07000E+00 MeV frac = 9.92200E-01 Product nuclide = 391000 : beta- + 2 RTYP = 15 Q = 1.90970E+00 MeV frac = 7.80000E-03 Product nuclide = 390990 : beta- + neutron emission + + Nuclide 741 / 1657 : 381010 -- strontium 101 (Sr-101) + + Pointers : 644812 -1000000 + Primary type : Decay + Nuclide ZAI : 381010 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 100.94013 + Atomic weight ratio (AWR) : 100.07300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.118 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 1 Q = 9.50000E+00 MeV frac = 9.76300E-01 Product nuclide = 391010 : beta- + 2 RTYP = 15 Q = 3.80870E+00 MeV frac = 1.18500E-02 Product nuclide = 391000 : beta- + neutron emission + 3 RTYP = 15 Q = 3.60870E+00 MeV frac = 1.18500E-02 Product nuclide = 391001 : beta- + neutron emission + + Nuclide 742 / 1657 : 381020 -- strontium 102 (Sr-102) + + Pointers : 645142 -1000000 + Primary type : Decay + Nuclide ZAI : 381020 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 101.94274 + Atomic weight ratio (AWR) : 101.06700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 69 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 1 Q = 8.81000E+00 MeV frac = 4.72500E-01 Product nuclide = 391020 : beta- + 2 RTYP = 1 Q = 8.61000E+00 MeV frac = 4.72500E-01 Product nuclide = 391021 : beta- + 3 RTYP = 15 Q = 3.75870E+00 MeV frac = 5.50000E-02 Product nuclide = 391010 : beta- + neutron emission + + Nuclide 743 / 1657 : 381030 -- strontium 103 (Sr-103) + + Pointers : 645472 -1000000 + Primary type : Decay + Nuclide ZAI : 381030 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 102.94939 + Atomic weight ratio (AWR) : 102.06500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 50 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.13900E+01 MeV frac = 1.00000E+00 Product nuclide = 391030 : beta- + + Nuclide 744 / 1657 : 381040 -- strontium 104 (Sr-104) + + Pointers : 645656 -1000000 + Primary type : Decay + Nuclide ZAI : 381040 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 103.95200 + Atomic weight ratio (AWR) : 103.05900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 30 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.05100E+01 MeV frac = 1.00000E+00 Product nuclide = 391040 : beta- + + Nuclide 745 / 1657 : 390880 -- yttrium 88 (Y-88) + + Pointers : 645840 -1000000 + Primary type : Decay + Nuclide ZAI : 390880 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 87.90949 + Atomic weight ratio (AWR) : 87.15430 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.21E+06 seconds (107 days) + Specific ingestion toxicity : 1.30E-09 Sv/Bq + Specific inhalation toxicity : 4.40E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 3.62260E+00 MeV frac = 1.00000E+00 Product nuclide = 38088.82c : EC/beta+ + + Nuclide 746 / 1657 : 390881 -- yttrium 88m (Y-88m) + + Pointers : 646645 -1000000 + Primary type : Decay + Nuclide ZAI : 390881 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 87.90949 + Atomic weight ratio (AWR) : 87.15430 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 13.9 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 6.74550E-01 MeV frac = 1.00000E+00 Product nuclide = 390880 : IT + + Nuclide 747 / 1657 : 390891 -- yttrium 89m (Y-89m) + + Pointers : 656449 -1000000 + Primary type : Decay + Nuclide ZAI : 390891 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 88.90585 + Atomic weight ratio (AWR) : 88.14210 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 15.7 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 9.08960E-01 MeV frac = 1.00000E+00 Product nuclide = 39089.82c : IT + + Nuclide 748 / 1657 : 390901 -- yttrium 90m (Y-90m) + + Pointers : 659049 -1000000 + Primary type : Decay + Nuclide ZAI : 390901 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 89.90715 + Atomic weight ratio (AWR) : 89.13480 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.15E+04 seconds (3.19 hours) + Specific ingestion toxicity : 1.70E-10 Sv/Bq + Specific inhalation toxicity : 1.00E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 6.82040E-01 MeV frac = 9.99979E-01 Product nuclide = 39090.82c : IT + + Nuclide 749 / 1657 : 390911 -- yttrium 91m (Y-91m) + + Pointers : 661765 -1000000 + Primary type : Decay + Nuclide ZAI : 390911 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 90.90734 + Atomic weight ratio (AWR) : 90.12640 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.98E+03 seconds (49.7 minutes) + Specific ingestion toxicity : 1.10E-11 Sv/Bq + Specific inhalation toxicity : 1.10E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 5.55570E-01 MeV frac = 1.00000E+00 Product nuclide = 39091.82c : IT + + Nuclide 750 / 1657 : 390920 -- yttrium 92 (Y-92) + + Pointers : 662136 -1000000 + Primary type : Decay + Nuclide ZAI : 390920 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 91.90895 + Atomic weight ratio (AWR) : 91.11940 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.27E+04 seconds (3.54 hours) + Specific ingestion toxicity : 4.90E-10 Sv/Bq + Specific inhalation toxicity : 1.80E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.63900E+00 MeV frac = 1.00000E+00 Product nuclide = 40092.82c : beta- + + Nuclide 751 / 1657 : 390930 -- yttrium 93 (Y-93) + + Pointers : 662941 -1000000 + Primary type : Decay + Nuclide ZAI : 390930 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 92.90954 + Atomic weight ratio (AWR) : 92.11140 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.66E+04 seconds (10.2 hours) + Specific ingestion toxicity : 1.20E-09 Sv/Bq + Specific inhalation toxicity : 4.20E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.89500E+00 MeV frac = 1.00000E+00 Product nuclide = 40093.82c : beta- + + Nuclide 752 / 1657 : 390931 -- yttrium 93m (Y-93m) + + Pointers : 663872 -1000000 + Primary type : Decay + Nuclide ZAI : 390931 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 92.90954 + Atomic weight ratio (AWR) : 92.11140 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.82 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 7.58739E-01 MeV frac = 1.00000E+00 Product nuclide = 390930 : IT + + Nuclide 753 / 1657 : 390940 -- yttrium 94 (Y-94) + + Pointers : 664313 -1000000 + Primary type : Decay + Nuclide ZAI : 390940 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 93.91155 + Atomic weight ratio (AWR) : 93.10480 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.12E+03 seconds (18.7 minutes) + Specific ingestion toxicity : 8.10E-11 Sv/Bq + Specific inhalation toxicity : 2.80E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.91800E+00 MeV frac = 1.00000E+00 Product nuclide = 40094.82c : beta- + + Nuclide 754 / 1657 : 390950 -- yttrium 95 (Y-95) + + Pointers : 665720 -1000000 + Primary type : Decay + Nuclide ZAI : 390950 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 94.91285 + Atomic weight ratio (AWR) : 94.09750 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.18E+02 seconds (10.3 minutes) + Specific ingestion toxicity : 4.60E-11 Sv/Bq + Specific inhalation toxicity : 1.60E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.45000E+00 MeV frac = 1.00000E+00 Product nuclide = 40095.82c : beta- + + Nuclide 755 / 1657 : 390960 -- yttrium 96 (Y-96) + + Pointers : 666973 -1000000 + Primary type : Decay + Nuclide ZAI : 390960 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 95.91587 + Atomic weight ratio (AWR) : 95.09190 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.34 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.09600E+00 MeV frac = 1.00000E+00 Product nuclide = 40096.82c : beta- + + Nuclide 756 / 1657 : 390961 -- yttrium 96m (Y-96m) + + Pointers : 669360 -1000000 + Primary type : Decay + Nuclide ZAI : 390961 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 95.91587 + Atomic weight ratio (AWR) : 95.09190 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.62 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.70000E+00 MeV frac = 1.00000E+00 Product nuclide = 40096.82c : beta- + + Nuclide 757 / 1657 : 390970 -- yttrium 97 (Y-97) + + Pointers : 672335 -1000000 + Primary type : Decay + Nuclide ZAI : 390970 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 96.91818 + Atomic weight ratio (AWR) : 96.08560 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.75 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 6.68900E+00 MeV frac = 9.99450E-01 Product nuclide = 400970 : beta- + 2 RTYP = 15 Q = 1.11400E+00 MeV frac = 5.50000E-04 Product nuclide = 40096.82c : beta- + neutron emission + + Nuclide 758 / 1657 : 390971 -- yttrium 97m (Y-97m) + + Pointers : 673661 -1000000 + Primary type : Decay + Nuclide ZAI : 390971 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 96.91818 + Atomic weight ratio (AWR) : 96.08560 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.17 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 1 Q = 7.35700E+00 MeV frac = 9.92500E-01 Product nuclide = 400970 : beta- + 2 RTYP = 3 Q = 6.67500E-01 MeV frac = 7.00000E-03 Product nuclide = 390970 : IT + 3 RTYP = 15 Q = 1.78200E+00 MeV frac = 5.00000E-04 Product nuclide = 40096.82c : beta- + neutron emission + + Nuclide 759 / 1657 : 390972 -- yttrium 97m (Y-97m) + + Pointers : 3506583 -1000000 + Primary type : Decay + Nuclide ZAI : 390972 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 96.91818 + Atomic weight ratio (AWR) : 96.08560 + Temperature : 900.0 Kelvin + XS temperature : -1.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.142 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is not present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.02120E+01 MeV frac = 1.60000E-02 Product nuclide = 400970 : beta- + 2 RTYP = 3 Q = 2.85580E+00 MeV frac = 9.84000E-01 Product nuclide = 390971 : IT + + Nuclide 760 / 1657 : 390980 -- yttrium 98 (Y-98) + + Pointers : 676194 -1000000 + Primary type : Decay + Nuclide ZAI : 390980 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 97.92220 + Atomic weight ratio (AWR) : 97.08100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.59 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.82400E+00 MeV frac = 9.97300E-01 Product nuclide = 400980 : beta- + 2 RTYP = 15 Q = 2.42600E+00 MeV frac = 2.70000E-03 Product nuclide = 400970 : beta- + neutron emission + + Nuclide 761 / 1657 : 390981 -- yttrium 98m (Y-98m) + + Pointers : 678700 -1000000 + Primary type : Decay + Nuclide ZAI : 390981 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 97.92220 + Atomic weight ratio (AWR) : 97.08100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 9.80000E+00 MeV frac = 9.65600E-01 Product nuclide = 400980 : beta- + 2 RTYP = 15 Q = 3.42600E+00 MeV frac = 3.44000E-02 Product nuclide = 400970 : beta- + neutron emission + + Nuclide 762 / 1657 : 390990 -- yttrium 99 (Y-99) + + Pointers : 681408 -1000000 + Primary type : Decay + Nuclide ZAI : 390990 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 98.92461 + Atomic weight ratio (AWR) : 98.07480 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.48 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 7.56700E+00 MeV frac = 9.83000E-01 Product nuclide = 400990 : beta- + 2 RTYP = 15 Q = 3.09000E+00 MeV frac = 1.70000E-02 Product nuclide = 400980 : beta- + neutron emission + + Nuclide 763 / 1657 : 391000 -- yttrium 100 (Y-100) + + Pointers : 687906 -1000000 + Primary type : Decay + Nuclide ZAI : 391000 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 99.92773 + Atomic weight ratio (AWR) : 99.06930 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.735 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 9.31001E+00 MeV frac = 9.90800E-01 Product nuclide = 401000 : beta- + 2 RTYP = 15 Q = 2.40670E+00 MeV frac = 9.20000E-03 Product nuclide = 400990 : beta- + neutron emission + + Nuclide 764 / 1657 : 391001 -- yttrium 100m (Y-100m) + + Pointers : 688163 -1000000 + Primary type : Decay + Nuclide ZAI : 391001 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 99.92773 + Atomic weight ratio (AWR) : 99.06930 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.94 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.51001E+00 MeV frac = 1.00000E+00 Product nuclide = 401000 : beta- + + Nuclide 765 / 1657 : 391010 -- yttrium 101 (Y-101) + + Pointers : 688347 -1000000 + Primary type : Decay + Nuclide ZAI : 391010 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 100.93004 + Atomic weight ratio (AWR) : 100.06300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.45 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.54500E+00 MeV frac = 1.00000E+00 Product nuclide = 401010 : beta- + + Nuclide 766 / 1657 : 391020 -- yttrium 102 (Y-102) + + Pointers : 690356 -1000000 + Primary type : Decay + Nuclide ZAI : 391020 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 101.93366 + Atomic weight ratio (AWR) : 101.05800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 9.85000E+00 MeV frac = 9.51000E-01 Product nuclide = 401020 : beta- + 2 RTYP = 15 Q = 3.49870E+00 MeV frac = 4.90000E-02 Product nuclide = 401010 : beta- + neutron emission + + Nuclide 767 / 1657 : 391021 -- yttrium 102m (Y-102m) + + Pointers : 690613 -1000000 + Primary type : Decay + Nuclide ZAI : 391021 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 101.93366 + Atomic weight ratio (AWR) : 101.05800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.36 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.00500E+01 MeV frac = 9.51000E-01 Product nuclide = 401020 : beta- + 2 RTYP = 15 Q = 3.69870E+00 MeV frac = 4.90000E-02 Product nuclide = 401010 : beta- + neutron emission + + Nuclide 768 / 1657 : 391030 -- yttrium 103 (Y-103) + + Pointers : 690870 -1000000 + Primary type : Decay + Nuclide ZAI : 391030 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 102.93628 + Atomic weight ratio (AWR) : 102.05200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.224 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 9.43000E+00 MeV frac = 9.20000E-01 Product nuclide = 401030 : beta- + 2 RTYP = 15 Q = 4.72870E+00 MeV frac = 8.00000E-02 Product nuclide = 401020 : beta- + neutron emission + + Nuclide 769 / 1657 : 391040 -- yttrium 104 (Y-104) + + Pointers : 691127 -1000000 + Primary type : Decay + Nuclide ZAI : 391040 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 103.94091 + Atomic weight ratio (AWR) : 103.04800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.13 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.27370E+01 MeV frac = 9.12230E-01 Product nuclide = 401040 : beta- + 2 RTYP = 15 Q = 5.50800E+00 MeV frac = 8.77690E-02 Product nuclide = 401030 : beta- + neutron emission + + Nuclide 770 / 1657 : 391050 -- yttrium 105 (Y-105) + + Pointers : 700614 -1000000 + Primary type : Decay + Nuclide ZAI : 391050 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 104.94352 + Atomic weight ratio (AWR) : 104.04200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.15 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.08350E+01 MeV frac = 8.02470E-01 Product nuclide = 401050 : beta- + 2 RTYP = 15 Q = 6.83900E+00 MeV frac = 1.97530E-01 Product nuclide = 401040 : beta- + neutron emission + + Nuclide 771 / 1657 : 391060 -- yttrium 106 (Y-106) + + Pointers : 709357 -1000000 + Primary type : Decay + Nuclide ZAI : 391060 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 105.95017 + Atomic weight ratio (AWR) : 105.04000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 50 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.29300E+01 MeV frac = 1.00000E+00 Product nuclide = 401060 : beta- + + Nuclide 772 / 1657 : 391070 -- yttrium 107 (Y-107) + + Pointers : 709541 -1000000 + Primary type : Decay + Nuclide ZAI : 391070 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 106.95379 + Atomic weight ratio (AWR) : 106.03500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 30 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.24700E+01 MeV frac = 1.00000E+00 Product nuclide = 401070 : beta- + + Nuclide 773 / 1657 : 400880 -- zirconium 88 (Zr-88) + + Pointers : 709725 -1000000 + Primary type : Decay + Nuclide ZAI : 400880 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 87.91020 + Atomic weight ratio (AWR) : 87.15500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.21E+06 seconds (83.4 days) + Specific ingestion toxicity : 4.50E-10 Sv/Bq + Specific inhalation toxicity : 3.60E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 6.68000E-01 MeV frac = 1.00000E+00 Product nuclide = 390880 : EC/beta+ + + Nuclide 774 / 1657 : 400890 -- zirconium 89 (Zr-89) + + Pointers : 710124 -1000000 + Primary type : Decay + Nuclide ZAI : 400890 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 88.90887 + Atomic weight ratio (AWR) : 88.14510 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.82E+05 seconds (3.27 days) + Specific ingestion toxicity : 7.90E-10 Sv/Bq + Specific inhalation toxicity : 5.50E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 2.83280E+00 MeV frac = 1.22965E-03 Product nuclide = 39089.82c : EC/beta+ + 2 RTYP = 2 Q = 1.92383E+00 MeV frac = 9.98770E-01 Product nuclide = 390891 : EC/beta+ + + Nuclide 775 / 1657 : 400901 -- zirconium 90m (Zr-90m) + + Pointers : 713363 -1000000 + Primary type : Decay + Nuclide ZAI : 400901 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 89.90473 + Atomic weight ratio (AWR) : 89.13240 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.808 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 2.31900E+00 MeV frac = 1.00000E+00 Product nuclide = 40090.82c : IT + + Nuclide 776 / 1657 : 400970 -- zirconium 97 (Zr-97) + + Pointers : 732830 -1000000 + Primary type : Decay + Nuclide ZAI : 400970 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 96.91092 + Atomic weight ratio (AWR) : 96.07840 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.03E+04 seconds (16.7 hours) + Specific ingestion toxicity : 2.10E-09 Sv/Bq + Specific inhalation toxicity : 8.90E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 2.65830E+00 MeV frac = 4.95212E-02 Product nuclide = 410970 : beta- + 2 RTYP = 1 Q = 1.91495E+00 MeV frac = 9.50479E-01 Product nuclide = 410971 : beta- + + Nuclide 777 / 1657 : 400980 -- zirconium 98 (Zr-98) + + Pointers : 733848 -1000000 + Primary type : Decay + Nuclide ZAI : 400980 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 97.91272 + Atomic weight ratio (AWR) : 97.07160 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 30.7 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.25000E+00 MeV frac = 1.00000E+00 Product nuclide = 410980 : beta- + + Nuclide 778 / 1657 : 400990 -- zirconium 99 (Zr-99) + + Pointers : 734065 -1000000 + Primary type : Decay + Nuclide ZAI : 400990 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 98.91655 + Atomic weight ratio (AWR) : 98.06680 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 4.19300E+00 MeV frac = 3.68000E-01 Product nuclide = 410991 : beta- + 2 RTYP = 1 Q = 4.55800E+00 MeV frac = 6.32000E-01 Product nuclide = 410990 : beta- + + Nuclide 779 / 1657 : 401000 -- zirconium 100 (Zr-100) + + Pointers : 735307 -1000000 + Primary type : Decay + Nuclide ZAI : 401000 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 99.91775 + Atomic weight ratio (AWR) : 99.05940 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.1 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.42600E+00 MeV frac = 1.00000E+00 Product nuclide = 411000 : beta- + + Nuclide 780 / 1657 : 401010 -- zirconium 101 (Zr-101) + + Pointers : 735748 -1000000 + Primary type : Decay + Nuclide ZAI : 401010 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 100.92096 + Atomic weight ratio (AWR) : 100.05400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.48500E+00 MeV frac = 1.00000E+00 Product nuclide = 411010 : beta- + + Nuclide 781 / 1657 : 401020 -- zirconium 102 (Zr-102) + + Pointers : 737911 -1000000 + Primary type : Decay + Nuclide ZAI : 401020 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 101.92257 + Atomic weight ratio (AWR) : 101.04700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.9 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.62600E+00 MeV frac = 1.00000E+00 Product nuclide = 411020 : beta- + + Nuclide 782 / 1657 : 401030 -- zirconium 103 (Zr-103) + + Pointers : 738702 -1000000 + Primary type : Decay + Nuclide ZAI : 401030 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 102.92619 + Atomic weight ratio (AWR) : 102.04200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.95001E+00 MeV frac = 1.00000E+00 Product nuclide = 411030 : beta- + + Nuclide 783 / 1657 : 401040 -- zirconium 104 (Zr-104) + + Pointers : 738886 -1000000 + Primary type : Decay + Nuclide ZAI : 401040 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 103.92880 + Atomic weight ratio (AWR) : 103.03600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.88000E+00 MeV frac = 1.00000E+00 Product nuclide = 411040 : beta- + + Nuclide 784 / 1657 : 401050 -- zirconium 105 (Zr-105) + + Pointers : 739070 -1000000 + Primary type : Decay + Nuclide ZAI : 401050 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 104.93243 + Atomic weight ratio (AWR) : 104.03100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.6 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.30060E+00 MeV frac = 9.86000E-01 Product nuclide = 411050 : beta- + 2 RTYP = 15 Q = 1.79400E+00 MeV frac = 1.40000E-02 Product nuclide = 411040 : beta- + neutron emission + + Nuclide 785 / 1657 : 401060 -- zirconium 106 (Zr-106) + + Pointers : 744783 -1000000 + Primary type : Decay + Nuclide ZAI : 401060 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 105.93504 + Atomic weight ratio (AWR) : 105.02500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.9 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 6.39860E+00 MeV frac = 9.84760E-01 Product nuclide = 411060 : beta- + 2 RTYP = 15 Q = 2.56300E+00 MeV frac = 1.52420E-02 Product nuclide = 411050 : beta- + neutron emission + + Nuclide 786 / 1657 : 401070 -- zirconium 107 (Zr-107) + + Pointers : 749581 -1000000 + Primary type : Decay + Nuclide ZAI : 401070 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 106.94068 + Atomic weight ratio (AWR) : 106.02200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.24 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 9.24790E+00 MeV frac = 9.62870E-01 Product nuclide = 411070 : beta- + 2 RTYP = 15 Q = 3.96900E+00 MeV frac = 3.71270E-02 Product nuclide = 411060 : beta- + neutron emission + + Nuclide 787 / 1657 : 401080 -- zirconium 108 (Zr-108) + + Pointers : 756509 -1000000 + Primary type : Decay + Nuclide ZAI : 401080 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 107.94430 + Atomic weight ratio (AWR) : 107.01700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 80 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 411080 : beta- + + Nuclide 788 / 1657 : 401090 -- zirconium 109 (Zr-109) + + Pointers : 756693 -1000000 + Primary type : Decay + Nuclide ZAI : 401090 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 108.94893 + Atomic weight ratio (AWR) : 108.01300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 60 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.08200E+01 MeV frac = 1.00000E+00 Product nuclide = 411090 : beta- + + Nuclide 789 / 1657 : 410900 -- niobium 90 (Nb-90) + + Pointers : 756877 -1000000 + Primary type : Decay + Nuclide ZAI : 410900 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 89.91129 + Atomic weight ratio (AWR) : 89.13890 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.25E+04 seconds (14.6 hours) + Specific ingestion toxicity : 1.20E-09 Sv/Bq + Specific inhalation toxicity : 6.60E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 3.79200E+00 MeV frac = 9.81000E-01 Product nuclide = 400901 : EC/beta+ + 2 RTYP = 2 Q = 6.11100E+00 MeV frac = 1.90000E-02 Product nuclide = 40090.82c : EC/beta+ + + Nuclide 790 / 1657 : 410910 -- niobium 91 (Nb-91) + + Pointers : 758357 -1000000 + Primary type : Decay + Nuclide ZAI : 410910 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 90.90704 + Atomic weight ratio (AWR) : 90.12610 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.15E+10 seconds (680 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 1.25460E+00 MeV frac = 1.00000E+00 Product nuclide = 40091.82c : EC/beta+ + + Nuclide 791 / 1657 : 410911 -- niobium 91m (Nb-91m) + + Pointers : 758714 -1000000 + Primary type : Decay + Nuclide ZAI : 410911 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 90.90704 + Atomic weight ratio (AWR) : 90.12610 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.26E+06 seconds (60.9 days) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 1.04490E-01 MeV frac = 9.76000E-01 Product nuclide = 410910 : IT + 2 RTYP = 2 Q = 1.35910E+00 MeV frac = 2.40000E-02 Product nuclide = 40091.82c : EC/beta+ + + Nuclide 792 / 1657 : 410920 -- niobium 92 (Nb-92) + + Pointers : 759326 -1000000 + Primary type : Decay + Nuclide ZAI : 410920 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 91.90723 + Atomic weight ratio (AWR) : 91.11770 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.10E+15 seconds (35 million years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 2.00590E+00 MeV frac = 1.00000E+00 Product nuclide = 40092.82c : EC/beta+ + + Nuclide 793 / 1657 : 410931 -- niobium 93m (Nb-93m) + + Pointers : 763707 -1000000 + Primary type : Decay + Nuclide ZAI : 410931 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 92.90642 + Atomic weight ratio (AWR) : 92.10830 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.09E+08 seconds (16.1 years) + Specific ingestion toxicity : 1.20E-10 Sv/Bq + Specific inhalation toxicity : 1.80E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 3.08200E-02 MeV frac = 1.00000E+00 Product nuclide = 41093.82c : IT + + Nuclide 794 / 1657 : 410941 -- niobium 94m (Nb-94m) + + Pointers : 768974 -1000000 + Primary type : Decay + Nuclide ZAI : 410941 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 93.90731 + Atomic weight ratio (AWR) : 93.10060 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.76E+02 seconds (6.26 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 2.08630E+00 MeV frac = 5.00000E-03 Product nuclide = 42094.82c : beta- + 2 RTYP = 3 Q = 4.09500E-02 MeV frac = 9.95000E-01 Product nuclide = 41094.82c : IT + + Nuclide 795 / 1657 : 410951 -- niobium 95m (Nb-95m) + + Pointers : 773761 -1000000 + Primary type : Decay + Nuclide ZAI : 410951 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 94.90680 + Atomic weight ratio (AWR) : 94.09150 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.12E+05 seconds (3.61 days) + Specific ingestion toxicity : 5.60E-10 Sv/Bq + Specific inhalation toxicity : 8.80E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 2.35690E-01 MeV frac = 9.75000E-01 Product nuclide = 41095.82c : IT + 2 RTYP = 1 Q = 1.16129E+00 MeV frac = 2.50000E-02 Product nuclide = 42095.82c : beta- + + Nuclide 796 / 1657 : 410960 -- niobium 96 (Nb-96) + + Pointers : 774415 -1000000 + Primary type : Decay + Nuclide ZAI : 410960 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 95.90810 + Atomic weight ratio (AWR) : 95.08420 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.41E+04 seconds (23.3 hours) + Specific ingestion toxicity : 1.10E-09 Sv/Bq + Specific inhalation toxicity : 6.60E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.18700E+00 MeV frac = 1.00000E+00 Product nuclide = 42096.82c : beta- + + Nuclide 797 / 1657 : 410970 -- niobium 97 (Nb-97) + + Pointers : 776676 -1000000 + Primary type : Decay + Nuclide ZAI : 410970 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 96.90809 + Atomic weight ratio (AWR) : 96.07560 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.33E+03 seconds (1.2 hours) + Specific ingestion toxicity : 6.80E-11 Sv/Bq + Specific inhalation toxicity : 4.50E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.93480E+00 MeV frac = 1.00000E+00 Product nuclide = 42097.82c : beta- + + Nuclide 798 / 1657 : 410971 -- niobium 97m (Nb-97m) + + Pointers : 777271 -1000000 + Primary type : Decay + Nuclide ZAI : 410971 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 96.90809 + Atomic weight ratio (AWR) : 96.07560 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 52.7 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 7.43400E-01 MeV frac = 1.00000E+00 Product nuclide = 410970 : IT + + Nuclide 799 / 1657 : 410980 -- niobium 98 (Nb-98) + + Pointers : 777614 -1000000 + Primary type : Decay + Nuclide ZAI : 410980 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 97.91030 + Atomic weight ratio (AWR) : 97.06920 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.86 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.58600E+00 MeV frac = 1.00000E+00 Product nuclide = 42098.82c : beta- + + Nuclide 800 / 1657 : 410981 -- niobium 98m (Nb-98m) + + Pointers : 778195 -1000000 + Primary type : Decay + Nuclide ZAI : 410981 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 97.91030 + Atomic weight ratio (AWR) : 97.06920 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.08E+03 seconds (51.3 minutes) + Specific ingestion toxicity : 1.10E-10 Sv/Bq + Specific inhalation toxicity : 5.80E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.67000E+00 MeV frac = 1.00000E+00 Product nuclide = 42098.82c : beta- + + Nuclide 801 / 1657 : 410990 -- niobium 99 (Nb-99) + + Pointers : 782626 -1000000 + Primary type : Decay + Nuclide ZAI : 410990 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 98.91160 + Atomic weight ratio (AWR) : 98.06190 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 15 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.63900E+00 MeV frac = 1.00000E+00 Product nuclide = 42099.82c : beta- + + Nuclide 802 / 1657 : 410991 -- niobium 99m (Nb-99m) + + Pointers : 785993 -1000000 + Primary type : Decay + Nuclide ZAI : 410991 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 98.91160 + Atomic weight ratio (AWR) : 98.06190 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.56E+02 seconds (2.6 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 4.00420E+00 MeV frac = 9.80000E-01 Product nuclide = 42099.82c : beta- + 2 RTYP = 3 Q = 3.65290E-01 MeV frac = 2.00000E-02 Product nuclide = 410990 : IT + + Nuclide 803 / 1657 : 411000 -- niobium 100 (Nb-100) + + Pointers : 788719 -1000000 + Primary type : Decay + Nuclide ZAI : 411000 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 99.91422 + Atomic weight ratio (AWR) : 99.05590 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.38400E+00 MeV frac = 1.00000E+00 Product nuclide = 42100.82c : beta- + + Nuclide 804 / 1657 : 411001 -- niobium 100m (Nb-100m) + + Pointers : 790476 -1000000 + Primary type : Decay + Nuclide ZAI : 411001 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 99.91422 + Atomic weight ratio (AWR) : 99.05590 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.9 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.72500E+00 MeV frac = 1.00000E+00 Product nuclide = 42100.82c : beta- + + Nuclide 805 / 1657 : 411010 -- niobium 101 (Nb-101) + + Pointers : 792149 -1000000 + Primary type : Decay + Nuclide ZAI : 411010 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 100.91491 + Atomic weight ratio (AWR) : 100.04800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.1 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.56900E+00 MeV frac = 1.00000E+00 Product nuclide = 421010 : beta- + + Nuclide 806 / 1657 : 411020 -- niobium 102 (Nb-102) + + Pointers : 793556 -1000000 + Primary type : Decay + Nuclide ZAI : 411020 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 101.91853 + Atomic weight ratio (AWR) : 101.04300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.20700E+00 MeV frac = 1.00000E+00 Product nuclide = 421020 : beta- + + Nuclide 807 / 1657 : 411021 -- niobium 102m (Nb-102m) + + Pointers : 793740 -1000000 + Primary type : Decay + Nuclide ZAI : 411021 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 101.91853 + Atomic weight ratio (AWR) : 101.04300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.34000E+00 MeV frac = 1.00000E+00 Product nuclide = 421020 : beta- + + Nuclide 808 / 1657 : 411030 -- niobium 103 (Nb-103) + + Pointers : 794531 -1000000 + Primary type : Decay + Nuclide ZAI : 411030 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 102.91913 + Atomic weight ratio (AWR) : 102.03500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.53000E+00 MeV frac = 1.00000E+00 Product nuclide = 421030 : beta- + + Nuclide 809 / 1657 : 411040 -- niobium 104 (Nb-104) + + Pointers : 794715 -1000000 + Primary type : Decay + Nuclide ZAI : 411040 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 103.92275 + Atomic weight ratio (AWR) : 103.03000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.9 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.11000E+00 MeV frac = 9.99400E-01 Product nuclide = 421040 : beta- + 2 RTYP = 15 Q = 5.58705E-01 MeV frac = 6.00000E-04 Product nuclide = 421030 : beta- + neutron emission + + Nuclide 810 / 1657 : 411041 -- niobium 104m (Nb-104m) + + Pointers : 794972 -1000000 + Primary type : Decay + Nuclide ZAI : 411041 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 103.92275 + Atomic weight ratio (AWR) : 103.03000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.94 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.33000E+00 MeV frac = 9.99500E-01 Product nuclide = 421040 : beta- + 2 RTYP = 15 Q = 7.78705E-01 MeV frac = 5.00000E-04 Product nuclide = 421030 : beta- + neutron emission + + Nuclide 811 / 1657 : 411050 -- niobium 105 (Nb-105) + + Pointers : 795229 -1000000 + Primary type : Decay + Nuclide ZAI : 411050 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 104.92436 + Atomic weight ratio (AWR) : 104.02300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.95 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 6.49000E+00 MeV frac = 9.83000E-01 Product nuclide = 421050 : beta- + 2 RTYP = 15 Q = 1.40870E+00 MeV frac = 1.70000E-02 Product nuclide = 421040 : beta- + neutron emission + + Nuclide 812 / 1657 : 411060 -- niobium 106 (Nb-106) + + Pointers : 795486 -1000000 + Primary type : Decay + Nuclide ZAI : 411060 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 105.92798 + Atomic weight ratio (AWR) : 105.01800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.92 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 9.15500E+00 MeV frac = 9.55000E-01 Product nuclide = 421060 : beta- + 2 RTYP = 15 Q = 2.16870E+00 MeV frac = 4.50000E-02 Product nuclide = 421050 : beta- + neutron emission + + Nuclide 813 / 1657 : 411070 -- niobium 107 (Nb-107) + + Pointers : 795743 -1000000 + Primary type : Decay + Nuclide ZAI : 411070 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 106.93059 + Atomic weight ratio (AWR) : 106.01200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.02000E+00 MeV frac = 9.40000E-01 Product nuclide = 421070 : beta- + 2 RTYP = 15 Q = 3.26370E+00 MeV frac = 6.00000E-02 Product nuclide = 421060 : beta- + neutron emission + + Nuclide 814 / 1657 : 411080 -- niobium 108 (Nb-108) + + Pointers : 796000 -1000000 + Primary type : Decay + Nuclide ZAI : 411080 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 107.93522 + Atomic weight ratio (AWR) : 107.00800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.193 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.06000E+01 MeV frac = 9.38000E-01 Product nuclide = 421080 : beta- + 2 RTYP = 15 Q = 4.16870E+00 MeV frac = 6.20000E-02 Product nuclide = 421070 : beta- + neutron emission + + Nuclide 815 / 1657 : 411090 -- niobium 109 (Nb-109) + + Pointers : 796257 -1000000 + Primary type : Decay + Nuclide ZAI : 411090 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 108.93783 + Atomic weight ratio (AWR) : 108.00200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.19 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.77730E+00 MeV frac = 8.73470E-01 Product nuclide = 421090 : beta- + 2 RTYP = 15 Q = 5.30900E+00 MeV frac = 1.26530E-01 Product nuclide = 421080 : beta- + neutron emission + + Nuclide 816 / 1657 : 411100 -- niobium 110 (Nb-110) + + Pointers : 803305 -1000000 + Primary type : Decay + Nuclide ZAI : 411100 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 109.94246 + Atomic weight ratio (AWR) : 108.99800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.17 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.18400E+01 MeV frac = 6.00000E-01 Product nuclide = 421100 : beta- + 2 RTYP = 15 Q = 5.55870E+00 MeV frac = 4.00000E-01 Product nuclide = 421090 : beta- + neutron emission + + Nuclide 817 / 1657 : 411110 -- niobium 111 (Nb-111) + + Pointers : 803562 -1000000 + Primary type : Decay + Nuclide ZAI : 411110 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 110.94609 + Atomic weight ratio (AWR) : 109.99300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 80 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.04700E+01 MeV frac = 1.00000E+00 Product nuclide = 421110 : beta- + + Nuclide 818 / 1657 : 411120 -- niobium 112 (Nb-112) + + Pointers : 803746 -1000000 + Primary type : Decay + Nuclide ZAI : 411120 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 111.95072 + Atomic weight ratio (AWR) : 110.98900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 60 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.30300E+01 MeV frac = 1.00000E+00 Product nuclide = 421120 : beta- + + Nuclide 819 / 1657 : 420910 -- molybdenum 91 (Mo-91) + + Pointers : 803930 -1000000 + Primary type : Decay + Nuclide ZAI : 420910 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 90.91178 + Atomic weight ratio (AWR) : 90.13080 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.29E+02 seconds (15.5 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 4.43000E+00 MeV frac = 9.99658E-01 Product nuclide = 410910 : EC/beta+ + 2 RTYP = 2 Q = 4.32539E+00 MeV frac = 3.42163E-04 Product nuclide = 410911 : EC/beta+ + + Nuclide 820 / 1657 : 420930 -- molybdenum 93 (Mo-93) + + Pointers : 808279 -1000000 + Primary type : Decay + Nuclide ZAI : 420930 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 92.90682 + Atomic weight ratio (AWR) : 92.10870 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.50E+10 seconds (3,014 years) + Specific ingestion toxicity : 3.10E-09 Sv/Bq + Specific inhalation toxicity : 2.30E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 4.06000E-01 MeV frac = 1.50000E-01 Product nuclide = 41093.82c : EC/beta+ + 2 RTYP = 2 Q = 3.75000E-01 MeV frac = 8.50000E-01 Product nuclide = 410931 : EC/beta+ + + Nuclide 821 / 1657 : 420931 -- molybdenum 93m (Mo-93m) + + Pointers : 808695 -1000000 + Primary type : Decay + Nuclide ZAI : 420931 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 92.90682 + Atomic weight ratio (AWR) : 92.10870 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.47E+04 seconds (6.85 hours) + Specific ingestion toxicity : 1.10E-10 Sv/Bq + Specific inhalation toxicity : 1.70E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 2.83100E+00 MeV frac = 1.20000E-03 Product nuclide = 41093.82c : EC/beta+ + 2 RTYP = 3 Q = 2.42493E+00 MeV frac = 9.98800E-01 Product nuclide = 420930 : IT + + Nuclide 822 / 1657 : 421010 -- molybdenum 101 (Mo-101) + + Pointers : 831594 -1000000 + Primary type : Decay + Nuclide ZAI : 421010 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 100.90987 + Atomic weight ratio (AWR) : 100.04300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.77E+02 seconds (14.6 minutes) + Specific ingestion toxicity : 4.10E-11 Sv/Bq + Specific inhalation toxicity : 2.60E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.82400E+00 MeV frac = 1.00000E+00 Product nuclide = 431010 : beta- + + Nuclide 823 / 1657 : 421020 -- molybdenum 102 (Mo-102) + + Pointers : 834905 -1000000 + Primary type : Decay + Nuclide ZAI : 421020 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 101.91046 + Atomic weight ratio (AWR) : 101.03500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.78E+02 seconds (11.3 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.00800E+00 MeV frac = 1.00000E+00 Product nuclide = 431020 : beta- + + Nuclide 824 / 1657 : 421030 -- molybdenum 103 (Mo-103) + + Pointers : 835276 -1000000 + Primary type : Decay + Nuclide ZAI : 421030 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 102.91308 + Atomic weight ratio (AWR) : 102.02900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.79E+01 seconds (1.13 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.75000E+00 MeV frac = 1.00000E+00 Product nuclide = 431030 : beta- + + Nuclide 825 / 1657 : 421040 -- molybdenum 104 (Mo-104) + + Pointers : 837677 -1000000 + Primary type : Decay + Nuclide ZAI : 421040 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 103.91367 + Atomic weight ratio (AWR) : 103.02100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 60 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.16000E+00 MeV frac = 1.00000E+00 Product nuclide = 431040 : beta- + + Nuclide 826 / 1657 : 421050 -- molybdenum 105 (Mo-105) + + Pointers : 837861 -1000000 + Primary type : Decay + Nuclide ZAI : 421050 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 104.91730 + Atomic weight ratio (AWR) : 104.01600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 35.6 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.95000E+00 MeV frac = 1.00000E+00 Product nuclide = 431050 : beta- + + Nuclide 827 / 1657 : 421060 -- molybdenum 106 (Mo-106) + + Pointers : 841144 -1000000 + Primary type : Decay + Nuclide ZAI : 421060 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 105.91789 + Atomic weight ratio (AWR) : 105.00800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.73 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.52000E+00 MeV frac = 1.00000E+00 Product nuclide = 431060 : beta- + + Nuclide 828 / 1657 : 421070 -- molybdenum 107 (Mo-107) + + Pointers : 841328 -1000000 + Primary type : Decay + Nuclide ZAI : 421070 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 106.92151 + Atomic weight ratio (AWR) : 106.00300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.16000E+00 MeV frac = 1.00000E+00 Product nuclide = 431070 : beta- + + Nuclide 829 / 1657 : 421080 -- molybdenum 108 (Mo-108) + + Pointers : 841512 -1000000 + Primary type : Decay + Nuclide ZAI : 421080 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 107.92312 + Atomic weight ratio (AWR) : 106.99600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.09 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.65000E+00 MeV frac = 1.00000E+00 Product nuclide = 431080 : beta- + + Nuclide 830 / 1657 : 421090 -- molybdenum 109 (Mo-109) + + Pointers : 841696 -1000000 + Primary type : Decay + Nuclide ZAI : 421090 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 108.92775 + Atomic weight ratio (AWR) : 107.99200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 6.71570E+00 MeV frac = 9.94700E-01 Product nuclide = 431090 : beta- + 2 RTYP = 15 Q = 6.20000E-01 MeV frac = 5.30000E-03 Product nuclide = 431080 : beta- + neutron emission + + Nuclide 831 / 1657 : 421100 -- molybdenum 110 (Mo-110) + + Pointers : 846101 -1000000 + Primary type : Decay + Nuclide ZAI : 421100 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 109.92935 + Atomic weight ratio (AWR) : 108.98500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 431100 : beta- + + Nuclide 832 / 1657 : 421110 -- molybdenum 111 (Mo-111) + + Pointers : 846285 -1000000 + Primary type : Decay + Nuclide ZAI : 421110 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 110.93499 + Atomic weight ratio (AWR) : 109.98200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.03170E+00 MeV frac = 9.89700E-01 Product nuclide = 431110 : beta- + 2 RTYP = 15 Q = 2.22900E+00 MeV frac = 1.03030E-02 Product nuclide = 431100 : beta- + neutron emission + + Nuclide 833 / 1657 : 421120 -- molybdenum 112 (Mo-112) + + Pointers : 851965 -1000000 + Primary type : Decay + Nuclide ZAI : 421120 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 111.93760 + Atomic weight ratio (AWR) : 110.97600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 6.03210E+00 MeV frac = 9.79210E-01 Product nuclide = 431120 : beta- + 2 RTYP = 15 Q = 2.73900E+00 MeV frac = 2.07880E-02 Product nuclide = 431110 : beta- + neutron emission + + Nuclide 834 / 1657 : 421130 -- molybdenum 113 (Mo-113) + + Pointers : 856598 -1000000 + Primary type : Decay + Nuclide ZAI : 421130 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 112.94223 + Atomic weight ratio (AWR) : 111.97200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 100 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.58000E+00 MeV frac = 1.00000E+00 Product nuclide = 431130 : beta- + + Nuclide 835 / 1657 : 421140 -- molybdenum 114 (Mo-114) + + Pointers : 856782 -1000000 + Primary type : Decay + Nuclide ZAI : 421140 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 113.94485 + Atomic weight ratio (AWR) : 112.96600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 80 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.42000E+00 MeV frac = 1.00000E+00 Product nuclide = 431140 : beta- + + Nuclide 836 / 1657 : 421150 -- molybdenum 115 (Mo-115) + + Pointers : 856966 -1000000 + Primary type : Decay + Nuclide ZAI : 421150 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 114.95049 + Atomic weight ratio (AWR) : 113.96300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 60 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.08000E+01 MeV frac = 1.00000E+00 Product nuclide = 431150 : beta- + + Nuclide 837 / 1657 : 430970 -- technetium 97 (Tc-97) + + Pointers : 857150 -1000000 + Primary type : Decay + Nuclide ZAI : 430970 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 96.90638 + Atomic weight ratio (AWR) : 96.07390 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.20E+13 seconds (2.6 million years) + Specific ingestion toxicity : 6.80E-11 Sv/Bq + Specific inhalation toxicity : 1.80E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 3.20000E-01 MeV frac = 1.00000E+00 Product nuclide = 42097.82c : EC/beta+ + + Nuclide 838 / 1657 : 430980 -- technetium 98 (Tc-98) + + Pointers : 857493 -1000000 + Primary type : Decay + Nuclide ZAI : 430980 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 97.90728 + Atomic weight ratio (AWR) : 97.06620 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.36E+14 seconds (4.3 million years) + Specific ingestion toxicity : 2.00E-09 Sv/Bq + Specific inhalation toxicity : 4.50E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.79700E+00 MeV frac = 1.00000E+00 Product nuclide = 440980 : beta- + + Nuclide 839 / 1657 : 430991 -- technetium 99m (Tc-99m) + + Pointers : 866172 -1000000 + Primary type : Decay + Nuclide ZAI : 430991 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 98.90626 + Atomic weight ratio (AWR) : 98.05660 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.16E+04 seconds (6.01 hours) + Specific ingestion toxicity : 2.20E-11 Sv/Bq + Specific inhalation toxicity : 2.00E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 1.42684E-01 MeV frac = 9.99963E-01 Product nuclide = 43099.82c : IT + 2 RTYP = 1 Q = 4.35883E-01 MeV frac = 3.70000E-05 Product nuclide = 440990 : beta- + + Nuclide 840 / 1657 : 431000 -- technetium 100 (Tc-100) + + Pointers : 867064 -1000000 + Primary type : Decay + Nuclide ZAI : 431000 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 99.90766 + Atomic weight ratio (AWR) : 99.04940 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 15.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 1.68000E-01 MeV frac = 1.80000E-05 Product nuclide = 42100.82c : EC/beta+ + 2 RTYP = 1 Q = 3.20280E+00 MeV frac = 9.99982E-01 Product nuclide = 44100.82c : beta- + + Nuclide 841 / 1657 : 431010 -- technetium 101 (Tc-101) + + Pointers : 868264 -1000000 + Primary type : Decay + Nuclide ZAI : 431010 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 100.90684 + Atomic weight ratio (AWR) : 100.04000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.52E+02 seconds (14.2 minutes) + Specific ingestion toxicity : 1.90E-11 Sv/Bq + Specific inhalation toxicity : 1.20E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.61300E+00 MeV frac = 1.00000E+00 Product nuclide = 44101.82c : beta- + + Nuclide 842 / 1657 : 431020 -- technetium 102 (Tc-102) + + Pointers : 869517 -1000000 + Primary type : Decay + Nuclide ZAI : 431020 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 101.90946 + Atomic weight ratio (AWR) : 101.03400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.28 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.53200E+00 MeV frac = 1.00000E+00 Product nuclide = 44102.82c : beta- + + Nuclide 843 / 1657 : 431021 -- technetium 102m (Tc-102m) + + Pointers : 870042 -1000000 + Primary type : Decay + Nuclide ZAI : 431021 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 101.90946 + Atomic weight ratio (AWR) : 101.03400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.61E+02 seconds (4.35 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.55200E+00 MeV frac = 1.00000E+00 Product nuclide = 44102.82c : beta- + + Nuclide 844 / 1657 : 431030 -- technetium 103 (Tc-103) + + Pointers : 870903 -1000000 + Primary type : Decay + Nuclide ZAI : 431030 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 102.90904 + Atomic weight ratio (AWR) : 102.02500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 54.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.66200E+00 MeV frac = 1.00000E+00 Product nuclide = 44103.82c : beta- + + Nuclide 845 / 1657 : 431040 -- technetium 104 (Tc-104) + + Pointers : 872254 -1000000 + Primary type : Decay + Nuclide ZAI : 431040 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 103.91166 + Atomic weight ratio (AWR) : 103.01900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.10E+03 seconds (18.3 minutes) + Specific ingestion toxicity : 8.00E-11 Sv/Bq + Specific inhalation toxicity : 2.90E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 44104.82c : beta- + + Nuclide 846 / 1657 : 431050 -- technetium 105 (Tc-105) + + Pointers : 874697 -1000000 + Primary type : Decay + Nuclide ZAI : 431050 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 104.91124 + Atomic weight ratio (AWR) : 104.01000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.56E+02 seconds (7.6 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.64000E+00 MeV frac = 1.00000E+00 Product nuclide = 44105.82c : beta- + + Nuclide 847 / 1657 : 431060 -- technetium 106 (Tc-106) + + Pointers : 876566 -1000000 + Primary type : Decay + Nuclide ZAI : 431060 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 105.91386 + Atomic weight ratio (AWR) : 105.00400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 35.6 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.54700E+00 MeV frac = 1.00000E+00 Product nuclide = 44106.82c : beta- + + Nuclide 848 / 1657 : 431070 -- technetium 107 (Tc-107) + + Pointers : 877861 -1000000 + Primary type : Decay + Nuclide ZAI : 431070 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 106.91546 + Atomic weight ratio (AWR) : 105.99700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 21.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.82000E+00 MeV frac = 1.00000E+00 Product nuclide = 441070 : beta- + + Nuclide 849 / 1657 : 431080 -- technetium 108 (Tc-108) + + Pointers : 881018 -1000000 + Primary type : Decay + Nuclide ZAI : 431080 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 107.91807 + Atomic weight ratio (AWR) : 106.99100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.17 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.72000E+00 MeV frac = 1.00000E+00 Product nuclide = 441080 : beta- + + Nuclide 850 / 1657 : 431090 -- technetium 109 (Tc-109) + + Pointers : 881202 -1000000 + Primary type : Decay + Nuclide ZAI : 431090 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 108.91968 + Atomic weight ratio (AWR) : 107.98400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.86 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 6.31001E+00 MeV frac = 9.99200E-01 Product nuclide = 441090 : beta- + 2 RTYP = 15 Q = 1.05871E+00 MeV frac = 8.00000E-04 Product nuclide = 441080 : beta- + neutron emission + + Nuclide 851 / 1657 : 431100 -- technetium 110 (Tc-110) + + Pointers : 881459 -1000000 + Primary type : Decay + Nuclide ZAI : 431100 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 109.92431 + Atomic weight ratio (AWR) : 108.98000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.92 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 9.02000E+00 MeV frac = 9.99600E-01 Product nuclide = 441100 : beta- + 2 RTYP = 15 Q = 1.81870E+00 MeV frac = 4.00000E-04 Product nuclide = 441090 : beta- + neutron emission + + Nuclide 852 / 1657 : 431110 -- technetium 111 (Tc-111) + + Pointers : 881716 -1000000 + Primary type : Decay + Nuclide ZAI : 431110 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 110.92591 + Atomic weight ratio (AWR) : 109.97300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.29 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.45000E+00 MeV frac = 1.00000E+00 Product nuclide = 441110 : beta- + + Nuclide 853 / 1657 : 431120 -- technetium 112 (Tc-112) + + Pointers : 882591 -1000000 + Primary type : Decay + Nuclide ZAI : 431120 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 111.92953 + Atomic weight ratio (AWR) : 110.96800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.29 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 9.48000E+00 MeV frac = 9.85000E-01 Product nuclide = 441120 : beta- + 2 RTYP = 15 Q = 2.59871E+00 MeV frac = 1.50000E-02 Product nuclide = 441110 : beta- + neutron emission + + Nuclide 854 / 1657 : 431130 -- technetium 113 (Tc-113) + + Pointers : 882848 -1000000 + Primary type : Decay + Nuclide ZAI : 431130 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 112.93215 + Atomic weight ratio (AWR) : 111.96200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.13 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 7.55570E+00 MeV frac = 9.28140E-01 Product nuclide = 441130 : beta- + 2 RTYP = 15 Q = 4.09900E+00 MeV frac = 7.18640E-02 Product nuclide = 441120 : beta- + neutron emission + + Nuclide 855 / 1657 : 431140 -- technetium 114 (Tc-114) + + Pointers : 888801 -1000000 + Primary type : Decay + Nuclide ZAI : 431140 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 113.93678 + Atomic weight ratio (AWR) : 112.95800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.06210E+01 MeV frac = 9.34640E-01 Product nuclide = 441140 : beta- + 2 RTYP = 15 Q = 4.80900E+00 MeV frac = 6.53580E-02 Product nuclide = 441130 : beta- + neutron emission + + Nuclide 856 / 1657 : 431150 -- technetium 115 (Tc-115) + + Pointers : 896809 -1000000 + Primary type : Decay + Nuclide ZAI : 431150 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 114.93939 + Atomic weight ratio (AWR) : 113.95200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.27 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.88590E+00 MeV frac = 8.56630E-01 Product nuclide = 441150 : beta- + 2 RTYP = 15 Q = 5.92900E+00 MeV frac = 1.43370E-01 Product nuclide = 441140 : beta- + neutron emission + + Nuclide 857 / 1657 : 431160 -- technetium 116 (Tc-116) + + Pointers : 904109 -1000000 + Primary type : Decay + Nuclide ZAI : 431160 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 115.94402 + Atomic weight ratio (AWR) : 114.94800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.12 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.18720E+01 MeV frac = 8.77770E-01 Product nuclide = 441160 : beta- + 2 RTYP = 15 Q = 6.65900E+00 MeV frac = 1.22230E-01 Product nuclide = 441150 : beta- + neutron emission + + Nuclide 858 / 1657 : 431170 -- technetium 117 (Tc-117) + + Pointers : 913422 -1000000 + Primary type : Decay + Nuclide ZAI : 431170 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 116.94663 + Atomic weight ratio (AWR) : 115.94200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 40 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.01600E+01 MeV frac = 1.00000E+00 Product nuclide = 441170 : beta- + + Nuclide 859 / 1657 : 431180 -- technetium 118 (Tc-118) + + Pointers : 913606 -1000000 + Primary type : Decay + Nuclide ZAI : 431180 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 117.95126 + Atomic weight ratio (AWR) : 116.93800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 30 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.27200E+01 MeV frac = 1.00000E+00 Product nuclide = 441180 : beta- + + Nuclide 860 / 1657 : 440980 -- ruthenium 98 (Ru-98) + + Pointers : 913790 -1000000 + Primary type : Decay + Nuclide ZAI : 440980 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 97.90526 + Atomic weight ratio (AWR) : 97.06420 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 861 / 1657 : 440990 -- ruthenium 99 (Ru-99) + + Pointers : 913896 -1000000 + Primary type : Decay + Nuclide ZAI : 440990 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 98.90595 + Atomic weight ratio (AWR) : 98.05630 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 862 / 1657 : 441031 -- ruthenium 103m (Ru-103m) + + Pointers : 926429 -1000000 + Primary type : Decay + Nuclide ZAI : 441031 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 102.90602 + Atomic weight ratio (AWR) : 102.02200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.69 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 2.38000E-01 MeV frac = 1.00000E+00 Product nuclide = 44103.82c : IT + + Nuclide 863 / 1657 : 441070 -- ruthenium 107 (Ru-107) + + Pointers : 935619 -1000000 + Primary type : Decay + Nuclide ZAI : 441070 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 106.90941 + Atomic weight ratio (AWR) : 105.99100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.25E+02 seconds (3.75 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.94000E+00 MeV frac = 1.00000E+00 Product nuclide = 451070 : beta- + + Nuclide 864 / 1657 : 441080 -- ruthenium 108 (Ru-108) + + Pointers : 939392 -1000000 + Primary type : Decay + Nuclide ZAI : 441080 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 107.91000 + Atomic weight ratio (AWR) : 106.98300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.73E+02 seconds (4.55 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.35000E+00 MeV frac = 1.00000E+00 Product nuclide = 451080 : beta- + + Nuclide 865 / 1657 : 441090 -- ruthenium 109 (Ru-109) + + Pointers : 939576 -1000000 + Primary type : Decay + Nuclide ZAI : 441090 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 108.91363 + Atomic weight ratio (AWR) : 107.97800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 34.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.16000E+00 MeV frac = 1.00000E+00 Product nuclide = 451090 : beta- + + Nuclide 866 / 1657 : 441100 -- ruthenium 110 (Ru-110) + + Pointers : 945519 -1000000 + Primary type : Decay + Nuclide ZAI : 441100 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 109.91422 + Atomic weight ratio (AWR) : 108.97000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 12 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.77400E+00 MeV frac = 1.00000E+00 Product nuclide = 451100 : beta- + + Nuclide 867 / 1657 : 441110 -- ruthenium 111 (Ru-111) + + Pointers : 946114 -1000000 + Primary type : Decay + Nuclide ZAI : 441110 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 110.91784 + Atomic weight ratio (AWR) : 109.96500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.12 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.68700E+00 MeV frac = 1.00000E+00 Product nuclide = 451110 : beta- + + Nuclide 868 / 1657 : 441120 -- ruthenium 112 (Ru-112) + + Pointers : 946298 -1000000 + Primary type : Decay + Nuclide ZAI : 441120 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 111.91945 + Atomic weight ratio (AWR) : 110.95800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.75 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.26000E+00 MeV frac = 1.00000E+00 Product nuclide = 451120 : beta- + + Nuclide 869 / 1657 : 441130 -- ruthenium 113 (Ru-113) + + Pointers : 946482 -1000000 + Primary type : Decay + Nuclide ZAI : 441130 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 112.92206 + Atomic weight ratio (AWR) : 111.95200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.8 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.63000E+00 MeV frac = 1.00000E+00 Product nuclide = 451130 : beta- + + Nuclide 870 / 1657 : 441131 -- ruthenium 113m (Ru-113m) + + Pointers : 947343 -1000000 + Primary type : Decay + Nuclide ZAI : 441131 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 112.92206 + Atomic weight ratio (AWR) : 111.95200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.51 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 1.30000E-01 MeV frac = 5.00000E-01 Product nuclide = 441130 : IT + 2 RTYP = 1 Q = 6.61000E+00 MeV frac = 5.00000E-01 Product nuclide = 451130 : beta- + + Nuclide 871 / 1657 : 441140 -- ruthenium 114 (Ru-114) + + Pointers : 947600 -1000000 + Primary type : Decay + Nuclide ZAI : 441140 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 113.92467 + Atomic weight ratio (AWR) : 112.94600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.53 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.10000E+00 MeV frac = 1.00000E+00 Product nuclide = 451140 : beta- + + Nuclide 872 / 1657 : 441150 -- ruthenium 115 (Ru-115) + + Pointers : 947784 -1000000 + Primary type : Decay + Nuclide ZAI : 441150 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 114.92830 + Atomic weight ratio (AWR) : 113.94100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.7 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 7.26180E+00 MeV frac = 9.97720E-01 Product nuclide = 451150 : beta- + 2 RTYP = 15 Q = 1.41900E+00 MeV frac = 2.27600E-03 Product nuclide = 451140 : beta- + neutron emission + + Nuclide 873 / 1657 : 441160 -- ruthenium 116 (Ru-116) + + Pointers : 952759 -1000000 + Primary type : Decay + Nuclide ZAI : 441160 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 115.93091 + Atomic weight ratio (AWR) : 114.93500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.7 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 5.52690E+00 MeV frac = 9.89190E-01 Product nuclide = 451160 : beta- + 2 RTYP = 15 Q = 2.15900E+00 MeV frac = 1.08110E-02 Product nuclide = 451150 : beta- + neutron emission + + Nuclide 874 / 1657 : 441170 -- ruthenium 117 (Ru-117) + + Pointers : 956912 -1000000 + Primary type : Decay + Nuclide ZAI : 441170 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 116.93554 + Atomic weight ratio (AWR) : 115.93100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.34 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.51310E+00 MeV frac = 9.79490E-01 Product nuclide = 451170 : beta- + 2 RTYP = 15 Q = 3.19900E+00 MeV frac = 2.05090E-02 Product nuclide = 451160 : beta- + neutron emission + + Nuclide 875 / 1657 : 441180 -- ruthenium 118 (Ru-118) + + Pointers : 963171 -1000000 + Primary type : Decay + Nuclide ZAI : 441180 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 117.93714 + Atomic weight ratio (AWR) : 116.92400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.7 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 6.54810E+00 MeV frac = 9.58910E-01 Product nuclide = 451180 : beta- + 2 RTYP = 15 Q = 3.68900E+00 MeV frac = 4.10920E-02 Product nuclide = 451170 : beta- + neutron emission + + Nuclide 876 / 1657 : 441190 -- ruthenium 119 (Ru-119) + + Pointers : 968395 -1000000 + Primary type : Decay + Nuclide ZAI : 441190 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 118.94177 + Atomic weight ratio (AWR) : 117.92000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.19 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 9.30710E+00 MeV frac = 9.56420E-01 Product nuclide = 451190 : beta- + 2 RTYP = 15 Q = 4.45900E+00 MeV frac = 4.35800E-02 Product nuclide = 451180 : beta- + neutron emission + + Nuclide 877 / 1657 : 441200 -- ruthenium 120 (Ru-120) + + Pointers : 975506 -1000000 + Primary type : Decay + Nuclide ZAI : 441200 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 119.94539 + Atomic weight ratio (AWR) : 118.91500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 80 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.29000E+00 MeV frac = 1.00000E+00 Product nuclide = 451200 : beta- + + Nuclide 878 / 1657 : 451010 -- rhodium 101 (Rh-101) + + Pointers : 975690 -1000000 + Primary type : Decay + Nuclide ZAI : 451010 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 100.90583 + Atomic weight ratio (AWR) : 100.03900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.01E+08 seconds (3.2 years) + Specific ingestion toxicity : 5.50E-10 Sv/Bq + Specific inhalation toxicity : 5.40E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 5.42000E-01 MeV frac = 1.00000E+00 Product nuclide = 44101.82c : EC/beta+ + + Nuclide 879 / 1657 : 451020 -- rhodium 102 (Rh-102) + + Pointers : 976481 -1000000 + Primary type : Decay + Nuclide ZAI : 451020 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 101.90643 + Atomic weight ratio (AWR) : 101.03100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.16E+07 seconds (2.9 years) + Specific ingestion toxicity : 1.20E-09 Sv/Bq + Specific inhalation toxicity : 7.10E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 2.32300E+00 MeV frac = 1.00000E+00 Product nuclide = 44102.82c : EC/beta+ + + Nuclide 880 / 1657 : 451031 -- rhodium 103m (Rh-103m) + + Pointers : 989716 -1000000 + Primary type : Decay + Nuclide ZAI : 451031 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 102.90602 + Atomic weight ratio (AWR) : 102.02200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.37E+03 seconds (56.1 minutes) + Specific ingestion toxicity : 3.80E-12 Sv/Bq + Specific inhalation toxicity : 2.70E-12 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 3.97560E-02 MeV frac = 1.00000E+00 Product nuclide = 45103.82c : IT + + Nuclide 881 / 1657 : 451040 -- rhodium 104 (Rh-104) + + Pointers : 990115 -1000000 + Primary type : Decay + Nuclide ZAI : 451040 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 103.90661 + Atomic weight ratio (AWR) : 103.01400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 42.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 2.44800E+00 MeV frac = 9.95500E-01 Product nuclide = 461040 : beta- + 2 RTYP = 2 Q = 1.14600E+00 MeV frac = 4.50000E-03 Product nuclide = 44104.82c : EC/beta+ + + Nuclide 882 / 1657 : 451041 -- rhodium 104m (Rh-104m) + + Pointers : 991343 -1000000 + Primary type : Decay + Nuclide ZAI : 451041 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 103.90661 + Atomic weight ratio (AWR) : 103.01400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.60E+02 seconds (4.34 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 2.57700E+00 MeV frac = 1.30000E-03 Product nuclide = 461040 : beta- + 2 RTYP = 3 Q = 1.28956E-01 MeV frac = 9.98700E-01 Product nuclide = 451040 : IT + + Nuclide 883 / 1657 : 451051 -- rhodium 105m (Rh-105m) + + Pointers : 995653 -1000000 + Primary type : Decay + Nuclide ZAI : 451051 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 104.90519 + Atomic weight ratio (AWR) : 104.00400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 40 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.29570E-01 MeV frac = 1.00000E+00 Product nuclide = 45105.82c : IT + + Nuclide 884 / 1657 : 451060 -- rhodium 106 (Rh-106) + + Pointers : 996010 -1000000 + Primary type : Decay + Nuclide ZAI : 451060 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 105.90680 + Atomic weight ratio (AWR) : 104.99700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 30.1 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.54600E+00 MeV frac = 1.00000E+00 Product nuclide = 46106.82c : beta- + + Nuclide 885 / 1657 : 451061 -- rhodium 106m (Rh-106m) + + Pointers : 999839 -1000000 + Primary type : Decay + Nuclide ZAI : 451061 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 105.90780 + Atomic weight ratio (AWR) : 104.99800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.92E+03 seconds (2.2 hours) + Specific ingestion toxicity : 1.60E-10 Sv/Bq + Specific inhalation toxicity : 1.10E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.67800E+00 MeV frac = 1.00000E+00 Product nuclide = 46106.82c : beta- + + Nuclide 886 / 1657 : 451070 -- rhodium 107 (Rh-107) + + Pointers : 1001946 -1000000 + Primary type : Decay + Nuclide ZAI : 451070 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 106.90638 + Atomic weight ratio (AWR) : 105.98800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.30E+03 seconds (21.7 minutes) + Specific ingestion toxicity : 2.40E-11 Sv/Bq + Specific inhalation toxicity : 1.70E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.50400E+00 MeV frac = 1.00000E+00 Product nuclide = 46107.82c : beta- + + Nuclide 887 / 1657 : 451080 -- rhodium 108 (Rh-108) + + Pointers : 1002877 -1000000 + Primary type : Decay + Nuclide ZAI : 451080 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 107.90900 + Atomic weight ratio (AWR) : 106.98200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 16.8 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.51000E+00 MeV frac = 1.00000E+00 Product nuclide = 46108.82c : beta- + + Nuclide 888 / 1657 : 451081 -- rhodium 108m (Rh-108m) + + Pointers : 1003206 -1000000 + Primary type : Decay + Nuclide ZAI : 451081 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 107.90900 + Atomic weight ratio (AWR) : 106.98200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.60E+02 seconds (6 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.50400E+00 MeV frac = 1.00000E+00 Product nuclide = 46108.82c : beta- + + Nuclide 889 / 1657 : 451090 -- rhodium 109 (Rh-109) + + Pointers : 1003390 -1000000 + Primary type : Decay + Nuclide ZAI : 451090 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 108.90858 + Atomic weight ratio (AWR) : 107.97300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.00E+01 seconds (1.33 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 2.59600E+00 MeV frac = 5.00000E-01 Product nuclide = 461090 : beta- + 2 RTYP = 1 Q = 2.40701E+00 MeV frac = 5.00000E-01 Product nuclide = 461091 : beta- + + Nuclide 890 / 1657 : 451100 -- rhodium 110 (Rh-110) + + Pointers : 1003647 -1000000 + Primary type : Decay + Nuclide ZAI : 451100 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 109.91120 + Atomic weight ratio (AWR) : 108.96700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 28.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.40000E+00 MeV frac = 1.00000E+00 Product nuclide = 46110.82c : beta- + + Nuclide 891 / 1657 : 451101 -- rhodium 110m (Rh-110m) + + Pointers : 1004998 -1000000 + Primary type : Decay + Nuclide ZAI : 451101 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 109.91120 + Atomic weight ratio (AWR) : 108.96700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 46110.82c : beta- + + Nuclide 892 / 1657 : 451110 -- rhodium 111 (Rh-111) + + Pointers : 1005873 -1000000 + Primary type : Decay + Nuclide ZAI : 451110 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 110.91179 + Atomic weight ratio (AWR) : 109.95900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 12 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.64700E+00 MeV frac = 1.00000E+00 Product nuclide = 461110 : beta- + + Nuclide 893 / 1657 : 451120 -- rhodium 112 (Rh-112) + + Pointers : 1008302 -1000000 + Primary type : Decay + Nuclide ZAI : 451120 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 111.91440 + Atomic weight ratio (AWR) : 110.95300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.1 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 461120 : beta- + + Nuclide 894 / 1657 : 451121 -- rhodium 112m (Rh-112m) + + Pointers : 1008687 -1000000 + Primary type : Decay + Nuclide ZAI : 451121 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 111.91440 + Atomic weight ratio (AWR) : 110.95300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.8 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.96000E+00 MeV frac = 1.00000E+00 Product nuclide = 461120 : beta- + + Nuclide 895 / 1657 : 451130 -- rhodium 113 (Rh-113) + + Pointers : 1009394 -1000000 + Primary type : Decay + Nuclide ZAI : 451130 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 112.91601 + Atomic weight ratio (AWR) : 111.94600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.8 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.01000E+00 MeV frac = 1.00000E+00 Product nuclide = 461130 : beta- + + Nuclide 896 / 1657 : 451140 -- rhodium 114 (Rh-114) + + Pointers : 1009578 -1000000 + Primary type : Decay + Nuclide ZAI : 451140 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 113.91862 + Atomic weight ratio (AWR) : 112.94000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.85 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.90000E+00 MeV frac = 1.00000E+00 Product nuclide = 461140 : beta- + + Nuclide 897 / 1657 : 451141 -- rhodium 114m (Rh-114m) + + Pointers : 1010089 -1000000 + Primary type : Decay + Nuclide ZAI : 451141 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 113.91862 + Atomic weight ratio (AWR) : 112.94000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.85 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.06700E+00 MeV frac = 1.00000E+00 Product nuclide = 461140 : beta- + + Nuclide 898 / 1657 : 451150 -- rhodium 115 (Rh-115) + + Pointers : 1010273 -1000000 + Primary type : Decay + Nuclide ZAI : 451150 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 114.92023 + Atomic weight ratio (AWR) : 113.93300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.99 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 6.19000E+00 MeV frac = 8.54800E-01 Product nuclide = 461150 : beta- + 2 RTYP = 1 Q = 6.10082E+00 MeV frac = 1.45200E-01 Product nuclide = 461151 : beta- + + Nuclide 899 / 1657 : 451160 -- rhodium 116 (Rh-116) + + Pointers : 1010530 -1000000 + Primary type : Decay + Nuclide ZAI : 451160 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 115.92385 + Atomic weight ratio (AWR) : 114.92800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.68 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 461160 : beta- + + Nuclide 900 / 1657 : 451161 -- rhodium 116m (Rh-116m) + + Pointers : 1011083 -1000000 + Primary type : Decay + Nuclide ZAI : 451161 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 115.92385 + Atomic weight ratio (AWR) : 114.92800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.57 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.37000E+00 MeV frac = 1.00000E+00 Product nuclide = 461160 : beta- + + Nuclide 901 / 1657 : 451170 -- rhodium 117 (Rh-117) + + Pointers : 1012224 -1000000 + Primary type : Decay + Nuclide ZAI : 451170 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 116.92646 + Atomic weight ratio (AWR) : 115.92200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.44 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.58000E+00 MeV frac = 1.00000E+00 Product nuclide = 461170 : beta- + + Nuclide 902 / 1657 : 451180 -- rhodium 118 (Rh-118) + + Pointers : 1012408 -1000000 + Primary type : Decay + Nuclide ZAI : 451180 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 117.93008 + Atomic weight ratio (AWR) : 116.91700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.32 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 9.98510E+00 MeV frac = 9.70830E-01 Product nuclide = 461180 : beta- + 2 RTYP = 15 Q = 3.41900E+00 MeV frac = 2.91670E-02 Product nuclide = 461170 : beta- + neutron emission + + Nuclide 903 / 1657 : 451190 -- rhodium 119 (Rh-119) + + Pointers : 1019615 -1000000 + Primary type : Decay + Nuclide ZAI : 451190 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 118.93169 + Atomic weight ratio (AWR) : 117.91000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.38000E+00 MeV frac = 1.00000E+00 Product nuclide = 461190 : beta- + + Nuclide 904 / 1657 : 451200 -- rhodium 120 (Rh-120) + + Pointers : 1019799 -1000000 + Primary type : Decay + Nuclide ZAI : 451200 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 119.93632 + Atomic weight ratio (AWR) : 118.90600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.17 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.07790E+01 MeV frac = 9.40720E-01 Product nuclide = 461200 : beta- + 2 RTYP = 15 Q = 4.84900E+00 MeV frac = 5.92820E-02 Product nuclide = 461190 : beta- + neutron emission + + Nuclide 905 / 1657 : 451210 -- rhodium 121 (Rh-121) + + Pointers : 1027912 -1000000 + Primary type : Decay + Nuclide ZAI : 451210 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 120.93792 + Atomic weight ratio (AWR) : 119.89900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.25 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.80710E+00 MeV frac = 8.64320E-01 Product nuclide = 461210 : beta- + 2 RTYP = 15 Q = 6.00900E+00 MeV frac = 1.35680E-01 Product nuclide = 461200 : beta- + neutron emission + + Nuclide 906 / 1657 : 451220 -- rhodium 122 (Rh-122) + + Pointers : 1035188 -1000000 + Primary type : Decay + Nuclide ZAI : 451220 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 121.94356 + Atomic weight ratio (AWR) : 120.89600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 50 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.17900E+01 MeV frac = 1.00000E+00 Product nuclide = 461220 : beta- + + Nuclide 907 / 1657 : 461030 -- palladium 103 (Pd-103) + + Pointers : 1035372 -1000000 + Primary type : Decay + Nuclide ZAI : 461030 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 102.90602 + Atomic weight ratio (AWR) : 102.02200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.47E+06 seconds (17 days) + Specific ingestion toxicity : 1.90E-10 Sv/Bq + Specific inhalation toxicity : 4.50E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 5.72200E-01 MeV frac = 2.60000E-04 Product nuclide = 45103.82c : EC/beta+ + 2 RTYP = 2 Q = 5.32400E-01 MeV frac = 9.99740E-01 Product nuclide = 451031 : EC/beta+ + + Nuclide 908 / 1657 : 461040 -- palladium 104 (Pd-104) + + Pointers : 1036236 -1000000 + Primary type : Decay + Nuclide ZAI : 461040 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 103.90359 + Atomic weight ratio (AWR) : 103.01100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 909 / 1657 : 461071 -- palladium 107m (Pd-107m) + + Pointers : 1053371 -1000000 + Primary type : Decay + Nuclide ZAI : 461071 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 106.90537 + Atomic weight ratio (AWR) : 105.98700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 21.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 2.14900E-01 MeV frac = 1.00000E+00 Product nuclide = 46107.82c : IT + + Nuclide 910 / 1657 : 461090 -- palladium 109 (Pd-109) + + Pointers : 1059858 -1000000 + Primary type : Decay + Nuclide ZAI : 461090 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 108.90556 + Atomic weight ratio (AWR) : 107.97000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.89E+04 seconds (13.6 hours) + Specific ingestion toxicity : 5.50E-10 Sv/Bq + Specific inhalation toxicity : 3.70E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.11610E+00 MeV frac = 4.86934E-04 Product nuclide = 47109.82c : beta- + 2 RTYP = 1 Q = 1.02807E+00 MeV frac = 9.99513E-01 Product nuclide = 471091 : beta- + + Nuclide 911 / 1657 : 461091 -- palladium 109m (Pd-109m) + + Pointers : 1062584 -1000000 + Primary type : Decay + Nuclide ZAI : 461091 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 108.90556 + Atomic weight ratio (AWR) : 107.97000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.81E+02 seconds (4.69 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.88900E-01 MeV frac = 1.00000E+00 Product nuclide = 461090 : IT + + Nuclide 912 / 1657 : 461110 -- palladium 111 (Pd-111) + + Pointers : 1065640 -1000000 + Primary type : Decay + Nuclide ZAI : 461110 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 110.90776 + Atomic weight ratio (AWR) : 109.95500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.40E+03 seconds (23.4 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 2.18800E+00 MeV frac = 7.04165E-03 Product nuclide = 47111.82c : beta- + 2 RTYP = 1 Q = 2.12815E+00 MeV frac = 9.92958E-01 Product nuclide = 471111 : beta- + + Nuclide 913 / 1657 : 461111 -- palladium 111m (Pd-111m) + + Pointers : 1067610 -1000000 + Primary type : Decay + Nuclide ZAI : 461111 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 110.90776 + Atomic weight ratio (AWR) : 109.95500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.98E+04 seconds (5.5 hours) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 3 Q = 1.72180E-01 MeV frac = 7.30000E-01 Product nuclide = 461110 : IT + 2 RTYP = 1 Q = 2.38918E+00 MeV frac = 7.81380E-02 Product nuclide = 47111.82c : beta- + 3 RTYP = 1 Q = 2.32936E+00 MeV frac = 1.91862E-01 Product nuclide = 471111 : beta- + + Nuclide 914 / 1657 : 461120 -- palladium 112 (Pd-112) + + Pointers : 1067940 -1000000 + Primary type : Decay + Nuclide ZAI : 461120 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 111.90734 + Atomic weight ratio (AWR) : 110.94600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.31E+04 seconds (20.3 hours) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.88000E-01 MeV frac = 1.00000E+00 Product nuclide = 471120 : beta- + + Nuclide 915 / 1657 : 461130 -- palladium 113 (Pd-113) + + Pointers : 1068269 -1000000 + Primary type : Decay + Nuclide ZAI : 461130 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 112.91097 + Atomic weight ratio (AWR) : 111.94100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.10E+01 seconds (1.52 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 3.29700E+00 MeV frac = 9.50000E-01 Product nuclide = 471131 : beta- + 2 RTYP = 1 Q = 3.34000E+00 MeV frac = 5.00000E-02 Product nuclide = 471130 : beta- + + Nuclide 916 / 1657 : 461131 -- palladium 113m (Pd-113m) + + Pointers : 1070561 -1000000 + Primary type : Decay + Nuclide ZAI : 461131 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 112.91097 + Atomic weight ratio (AWR) : 111.94100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 8.11000E-02 MeV frac = 1.00000E+00 Product nuclide = 461130 : IT + + Nuclide 917 / 1657 : 461140 -- palladium 114 (Pd-114) + + Pointers : 1070960 -1000000 + Primary type : Decay + Nuclide ZAI : 461140 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 113.91055 + Atomic weight ratio (AWR) : 112.93200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.45E+02 seconds (2.42 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.44000E+00 MeV frac = 1.00000E+00 Product nuclide = 471140 : beta- + + Nuclide 918 / 1657 : 461150 -- palladium 115 (Pd-115) + + Pointers : 1071639 -1000000 + Primary type : Decay + Nuclide ZAI : 461150 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 114.91417 + Atomic weight ratio (AWR) : 113.92700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 25 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 4.59000E+00 MeV frac = 7.30000E-01 Product nuclide = 471150 : beta- + 2 RTYP = 1 Q = 4.54884E+00 MeV frac = 2.70000E-01 Product nuclide = 471151 : beta- + + Nuclide 919 / 1657 : 461151 -- palladium 115m (Pd-115m) + + Pointers : 1071896 -1000000 + Primary type : Decay + Nuclide ZAI : 461151 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 114.91417 + Atomic weight ratio (AWR) : 113.92700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 50 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 4.63802E+00 MeV frac = 9.20000E-01 Product nuclide = 471151 : beta- + 2 RTYP = 3 Q = 8.91800E-02 MeV frac = 8.00000E-02 Product nuclide = 461150 : IT + + Nuclide 920 / 1657 : 461160 -- palladium 116 (Pd-116) + + Pointers : 1072153 -1000000 + Primary type : Decay + Nuclide ZAI : 461160 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 115.91376 + Atomic weight ratio (AWR) : 114.91800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 11.8 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.61000E+00 MeV frac = 1.00000E+00 Product nuclide = 471160 : beta- + + Nuclide 921 / 1657 : 461170 -- palladium 117 (Pd-117) + + Pointers : 1072748 -1000000 + Primary type : Decay + Nuclide ZAI : 461170 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 116.91738 + Atomic weight ratio (AWR) : 115.91300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 5.74000E+00 MeV frac = 5.00000E-01 Product nuclide = 471170 : beta- + 2 RTYP = 1 Q = 5.71140E+00 MeV frac = 5.00000E-01 Product nuclide = 471171 : beta- + + Nuclide 922 / 1657 : 461171 -- palladium 117m (Pd-117m) + + Pointers : 1073005 -1000000 + Primary type : Decay + Nuclide ZAI : 461171 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 116.91738 + Atomic weight ratio (AWR) : 115.91300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 19.1 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 2.03200E-01 MeV frac = 1.00000E+00 Product nuclide = 461170 : IT + + Nuclide 923 / 1657 : 461180 -- palladium 118 (Pd-118) + + Pointers : 1073614 -1000000 + Primary type : Decay + Nuclide ZAI : 461180 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 117.91899 + Atomic weight ratio (AWR) : 116.90600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.9 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 4.10000E+00 MeV frac = 8.57042E-01 Product nuclide = 471180 : beta- + 2 RTYP = 1 Q = 3.97237E+00 MeV frac = 1.42958E-01 Product nuclide = 471181 : beta- + + Nuclide 924 / 1657 : 461190 -- palladium 119 (Pd-119) + + Pointers : 1075304 -1000000 + Primary type : Decay + Nuclide ZAI : 461190 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 118.92362 + Atomic weight ratio (AWR) : 117.90200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.92 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 6.94000E+00 MeV frac = 5.00000E-01 Product nuclide = 471190 : beta- + 2 RTYP = 1 Q = 6.92000E+00 MeV frac = 5.00000E-01 Product nuclide = 471191 : beta- + + Nuclide 925 / 1657 : 461200 -- palladium 120 (Pd-120) + + Pointers : 1075561 -1000000 + Primary type : Decay + Nuclide ZAI : 461200 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 119.92421 + Atomic weight ratio (AWR) : 118.89400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 5.50000E+00 MeV frac = 5.00000E-01 Product nuclide = 471200 : beta- + 2 RTYP = 1 Q = 5.29700E+00 MeV frac = 5.00000E-01 Product nuclide = 471201 : beta- + + Nuclide 926 / 1657 : 461210 -- palladium 121 (Pd-121) + + Pointers : 1075818 -1000000 + Primary type : Decay + Nuclide ZAI : 461210 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 120.92783 + Atomic weight ratio (AWR) : 119.88900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.6 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 7.57010E+00 MeV frac = 9.97280E-01 Product nuclide = 471210 : beta- + 2 RTYP = 15 Q = 1.53600E+00 MeV frac = 2.72200E-03 Product nuclide = 471200 : beta- + neutron emission + + Nuclide 927 / 1657 : 461220 -- palladium 122 (Pd-122) + + Pointers : 1081015 -1000000 + Primary type : Decay + Nuclide ZAI : 461220 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 121.93045 + Atomic weight ratio (AWR) : 120.88300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.54000E+00 MeV frac = 1.00000E+00 Product nuclide = 471220 : beta- + + Nuclide 928 / 1657 : 461230 -- palladium 123 (Pd-123) + + Pointers : 1081199 -1000000 + Primary type : Decay + Nuclide ZAI : 461230 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 122.93508 + Atomic weight ratio (AWR) : 121.87900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.35000E+00 MeV frac = 1.00000E+00 Product nuclide = 471230 : beta- + + Nuclide 929 / 1657 : 461240 -- palladium 124 (Pd-124) + + Pointers : 1081383 -1000000 + Primary type : Decay + Nuclide ZAI : 461240 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 123.93668 + Atomic weight ratio (AWR) : 122.87200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 100 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.67000E+00 MeV frac = 1.00000E+00 Product nuclide = 471240 : beta- + + Nuclide 930 / 1657 : 471070 -- silver 107 (Ag-107) + + Pointers : 1081567 -1000000 + Primary type : Decay + Nuclide ZAI : 471070 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 106.90537 + Atomic weight ratio (AWR) : 105.98700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 931 / 1657 : 471080 -- silver 108 (Ag-108) + + Pointers : 1081673 -1000000 + Primary type : Decay + Nuclide ZAI : 471080 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 107.90597 + Atomic weight ratio (AWR) : 106.97900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.43E+02 seconds (2.38 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 1.92200E+00 MeV frac = 2.47000E-02 Product nuclide = 46108.82c : EC/beta+ + 2 RTYP = 1 Q = 1.64900E+00 MeV frac = 9.75300E-01 Product nuclide = 481080 : beta- + + Nuclide 932 / 1657 : 471081 -- silver 108m (Ag-108m) + + Pointers : 1082509 -1000000 + Primary type : Decay + Nuclide ZAI : 471081 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 107.90597 + Atomic weight ratio (AWR) : 106.97900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.38E+10 seconds (438 years) + Specific ingestion toxicity : 2.30E-09 Sv/Bq + Specific inhalation toxicity : 3.70E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 1.09440E-01 MeV frac = 9.10000E-02 Product nuclide = 471080 : IT + 2 RTYP = 2 Q = 2.03144E+00 MeV frac = 9.09000E-01 Product nuclide = 46108.82c : EC/beta+ + + Nuclide 933 / 1657 : 471091 -- silver 109m (Ag-109m) + + Pointers : 1086221 -1000000 + Primary type : Decay + Nuclide ZAI : 471091 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 108.90455 + Atomic weight ratio (AWR) : 107.96900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 39.7 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 8.80340E-02 MeV frac = 1.00000E+00 Product nuclide = 47109.82c : IT + + Nuclide 934 / 1657 : 471100 -- silver 110 (Ag-110) + + Pointers : 1086620 -1000000 + Primary type : Decay + Nuclide ZAI : 471100 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 109.90615 + Atomic weight ratio (AWR) : 108.96200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 24.6 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 8.92000E-01 MeV frac = 3.00000E-03 Product nuclide = 46110.82c : EC/beta+ + 2 RTYP = 1 Q = 2.89220E+00 MeV frac = 9.97000E-01 Product nuclide = 48110.82c : beta- + + Nuclide 935 / 1657 : 471111 -- silver 111m (Ag-111m) + + Pointers : 1097406 -1000000 + Primary type : Decay + Nuclide ZAI : 471111 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 110.90574 + Atomic weight ratio (AWR) : 109.95300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.48E+01 seconds (1.08 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.09660E+00 MeV frac = 5.00000E-03 Product nuclide = 48111.82c : beta- + 2 RTYP = 3 Q = 5.98200E-02 MeV frac = 9.95000E-01 Product nuclide = 47111.82c : IT + + Nuclide 936 / 1657 : 471120 -- silver 112 (Ag-112) + + Pointers : 1098620 -1000000 + Primary type : Decay + Nuclide ZAI : 471120 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 111.90734 + Atomic weight ratio (AWR) : 110.94600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.13E+04 seconds (3.13 hours) + Specific ingestion toxicity : 4.30E-10 Sv/Bq + Specific inhalation toxicity : 1.70E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.95651E+00 MeV frac = 1.00000E+00 Product nuclide = 48112.82c : beta- + + Nuclide 937 / 1657 : 471130 -- silver 113 (Ag-113) + + Pointers : 1098804 -1000000 + Primary type : Decay + Nuclide ZAI : 471130 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 112.90693 + Atomic weight ratio (AWR) : 111.93700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.93E+04 seconds (5.37 hours) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 2.01600E+00 MeV frac = 9.82635E-01 Product nuclide = 48113.82c : beta- + 2 RTYP = 1 Q = 1.75242E+00 MeV frac = 1.73647E-02 Product nuclide = 481131 : beta- + + Nuclide 938 / 1657 : 471131 -- silver 113m (Ag-113m) + + Pointers : 1100144 -1000000 + Primary type : Decay + Nuclide ZAI : 471131 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 112.90693 + Atomic weight ratio (AWR) : 111.93700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.87E+01 seconds (1.14 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 4.36000E-02 MeV frac = 6.40000E-01 Product nuclide = 471130 : IT + 2 RTYP = 1 Q = 2.05920E+00 MeV frac = 3.60000E-01 Product nuclide = 48113.82c : beta- + + Nuclide 939 / 1657 : 471140 -- silver 114 (Ag-114) + + Pointers : 1101260 -1000000 + Primary type : Decay + Nuclide ZAI : 471140 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 113.90853 + Atomic weight ratio (AWR) : 112.93000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.6 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.08700E+00 MeV frac = 1.00000E+00 Product nuclide = 48114.82c : beta- + + Nuclide 940 / 1657 : 471141 -- silver 114m (Ag-114m) + + Pointers : 1102387 -1000000 + Primary type : Decay + Nuclide ZAI : 471141 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 113.90853 + Atomic weight ratio (AWR) : 112.93000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.5 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.99000E-01 MeV frac = 1.00000E+00 Product nuclide = 471140 : IT + + Nuclide 941 / 1657 : 471150 -- silver 115 (Ag-115) + + Pointers : 1102954 -1000000 + Primary type : Decay + Nuclide ZAI : 471150 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 114.90913 + Atomic weight ratio (AWR) : 113.92200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.20E+03 seconds (20 minutes) + Specific ingestion toxicity : 6.00E-11 Sv/Bq + Specific inhalation toxicity : 2.90E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 3.10000E+00 MeV frac = 9.41622E-01 Product nuclide = 481150 : beta- + 2 RTYP = 1 Q = 2.91899E+00 MeV frac = 5.83779E-02 Product nuclide = 48515.82c : beta- + + Nuclide 942 / 1657 : 471151 -- silver 115m (Ag-115m) + + Pointers : 1105778 -1000000 + Primary type : Decay + Nuclide ZAI : 471151 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 114.90913 + Atomic weight ratio (AWR) : 113.92200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 18.6 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 1 Q = 3.14400E+00 MeV frac = 7.67000E-01 Product nuclide = 481150 : beta- + 2 RTYP = 1 Q = 2.96300E+00 MeV frac = 2.30000E-02 Product nuclide = 48515.82c : beta- + 3 RTYP = 3 Q = 4.11000E-02 MeV frac = 2.10000E-01 Product nuclide = 471150 : IT + + Nuclide 943 / 1657 : 471160 -- silver 116 (Ag-116) + + Pointers : 1107723 -1000000 + Primary type : Decay + Nuclide ZAI : 471160 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 115.91174 + Atomic weight ratio (AWR) : 114.91600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.37E+02 seconds (3.95 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.17600E+00 MeV frac = 1.00000E+00 Product nuclide = 48116.82c : beta- + + Nuclide 944 / 1657 : 471161 -- silver 116m (Ag-116m) + + Pointers : 1111930 -1000000 + Primary type : Decay + Nuclide ZAI : 471161 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 115.91174 + Atomic weight ratio (AWR) : 114.91600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.6 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 6.24190E+00 MeV frac = 9.40000E-01 Product nuclide = 48116.82c : beta- + 2 RTYP = 3 Q = 8.19000E-02 MeV frac = 6.00000E-02 Product nuclide = 471160 : IT + + Nuclide 945 / 1657 : 471170 -- silver 117 (Ag-117) + + Pointers : 1112668 -1000000 + Primary type : Decay + Nuclide ZAI : 471170 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 116.91133 + Atomic weight ratio (AWR) : 115.90700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.36E+01 seconds (1.23 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 4.15500E+00 MeV frac = 8.30700E-01 Product nuclide = 481170 : beta- + 2 RTYP = 1 Q = 4.01860E+00 MeV frac = 1.69300E-01 Product nuclide = 481171 : beta- + + Nuclide 946 / 1657 : 471171 -- silver 117m (Ag-117m) + + Pointers : 1112925 -1000000 + Primary type : Decay + Nuclide ZAI : 471171 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 116.91133 + Atomic weight ratio (AWR) : 115.90700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.34 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 1 Q = 4.18360E+00 MeV frac = 7.07162E-01 Product nuclide = 481170 : beta- + 2 RTYP = 1 Q = 4.04720E+00 MeV frac = 2.32838E-01 Product nuclide = 481171 : beta- + 3 RTYP = 3 Q = 2.86000E-02 MeV frac = 6.00000E-02 Product nuclide = 471170 : IT + + Nuclide 947 / 1657 : 471180 -- silver 118 (Ag-118) + + Pointers : 1113255 -1000000 + Primary type : Decay + Nuclide ZAI : 471180 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 117.91495 + Atomic weight ratio (AWR) : 116.90200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.76 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.13900E+00 MeV frac = 1.00000E+00 Product nuclide = 481180 : beta- + + Nuclide 948 / 1657 : 471181 -- silver 118m (Ag-118m) + + Pointers : 1113439 -1000000 + Primary type : Decay + Nuclide ZAI : 471181 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 117.91495 + Atomic weight ratio (AWR) : 116.90200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 7.26649E+00 MeV frac = 5.90000E-01 Product nuclide = 481180 : beta- + 2 RTYP = 3 Q = 1.27490E-01 MeV frac = 4.10000E-01 Product nuclide = 471180 : IT + + Nuclide 949 / 1657 : 471190 -- silver 119 (Ag-119) + + Pointers : 1113696 -1000000 + Primary type : Decay + Nuclide ZAI : 471190 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 118.91555 + Atomic weight ratio (AWR) : 117.89400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 5.35000E+00 MeV frac = 5.00000E-01 Product nuclide = 481190 : beta- + 2 RTYP = 1 Q = 5.20346E+00 MeV frac = 5.00000E-01 Product nuclide = 481191 : beta- + + Nuclide 950 / 1657 : 471191 -- silver 119m (Ag-119m) + + Pointers : 1113953 -1000000 + Primary type : Decay + Nuclide ZAI : 471191 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 118.91555 + Atomic weight ratio (AWR) : 117.89400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.1 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.37000E+00 MeV frac = 1.00000E+00 Product nuclide = 481190 : beta- + + Nuclide 951 / 1657 : 471200 -- silver 120 (Ag-120) + + Pointers : 1114137 -1000000 + Primary type : Decay + Nuclide ZAI : 471200 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 119.91917 + Atomic weight ratio (AWR) : 118.88900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.23 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 1 Q = 8.32401E+00 MeV frac = 9.99970E-01 Product nuclide = 481200 : beta- + 2 RTYP = 15 Q = 1.88702E-01 MeV frac = 1.50000E-05 Product nuclide = 481190 : beta- + neutron emission + 3 RTYP = 15 Q = 4.21621E-02 MeV frac = 1.50000E-05 Product nuclide = 481191 : beta- + neutron emission + + Nuclide 952 / 1657 : 471201 -- silver 120m (Ag-120m) + + Pointers : 1114467 -1000000 + Primary type : Decay + Nuclide ZAI : 471201 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 119.91917 + Atomic weight ratio (AWR) : 118.88900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.371 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.52701E+00 MeV frac = 6.30000E-01 Product nuclide = 481200 : beta- + 2 RTYP = 3 Q = 2.03000E-01 MeV frac = 3.70000E-01 Product nuclide = 471200 : IT + + Nuclide 953 / 1657 : 471210 -- silver 121 (Ag-121) + + Pointers : 1114724 -1000000 + Primary type : Decay + Nuclide ZAI : 471210 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 120.91976 + Atomic weight ratio (AWR) : 119.88100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.78 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 6.67000E+00 MeV frac = 8.96067E-01 Product nuclide = 481210 : beta- + 2 RTYP = 1 Q = 6.45510E+00 MeV frac = 1.03933E-01 Product nuclide = 481211 : beta- + + Nuclide 954 / 1657 : 471220 -- silver 122 (Ag-122) + + Pointers : 1117464 -1000000 + Primary type : Decay + Nuclide ZAI : 471220 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 121.92339 + Atomic weight ratio (AWR) : 120.87600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.529 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.50000E+00 MeV frac = 9.98000E-01 Product nuclide = 481220 : beta- + + Nuclide 955 / 1657 : 471221 -- silver 122m (Ag-122m) + + Pointers : 1117807 -1000000 + Primary type : Decay + Nuclide ZAI : 471221 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 121.92339 + Atomic weight ratio (AWR) : 120.87600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.58000E+00 MeV frac = 1.00000E+00 Product nuclide = 481220 : beta- + + Nuclide 956 / 1657 : 471230 -- silver 123 (Ag-123) + + Pointers : 1117991 -1000000 + Primary type : Decay + Nuclide ZAI : 471230 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 122.92499 + Atomic weight ratio (AWR) : 121.86900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 7.36000E+00 MeV frac = 8.18164E-01 Product nuclide = 481230 : beta- + 2 RTYP = 1 Q = 7.04348E+00 MeV frac = 1.81836E-01 Product nuclide = 481231 : beta- + + Nuclide 957 / 1657 : 471240 -- silver 124 (Ag-124) + + Pointers : 1119429 -1000000 + Primary type : Decay + Nuclide ZAI : 471240 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 123.92861 + Atomic weight ratio (AWR) : 122.86400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.172 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 1 Q = 1.02400E+01 MeV frac = 9.99000E-01 Product nuclide = 481240 : beta- + 2 RTYP = 15 Q = 2.76870E+00 MeV frac = 5.00000E-04 Product nuclide = 481230 : beta- + neutron emission + 3 RTYP = 15 Q = 2.45218E+00 MeV frac = 5.00000E-04 Product nuclide = 481231 : beta- + neutron emission + + Nuclide 958 / 1657 : 471241 -- silver 124m (Ag-124m) + + Pointers : 1119759 -1000000 + Primary type : Decay + Nuclide ZAI : 471241 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 123.92861 + Atomic weight ratio (AWR) : 122.86400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.02400E+01 MeV frac = 5.00000E-01 Product nuclide = 481240 : beta- + 2 RTYP = 3 Q = 0.00000E+00 MeV frac = 5.00000E-01 Product nuclide = 471240 : IT + + Nuclide 959 / 1657 : 471250 -- silver 125 (Ag-125) + + Pointers : 1120016 -1000000 + Primary type : Decay + Nuclide ZAI : 471250 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 124.93022 + Atomic weight ratio (AWR) : 123.85700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.166 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.56000E+00 MeV frac = 5.00000E-01 Product nuclide = 481250 : beta- + 2 RTYP = 1 Q = 8.51000E+00 MeV frac = 5.00000E-01 Product nuclide = 481251 : beta- + + Nuclide 960 / 1657 : 471260 -- silver 126 (Ag-126) + + Pointers : 1120273 -1000000 + Primary type : Decay + Nuclide ZAI : 471260 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 125.93485 + Atomic weight ratio (AWR) : 124.85300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.107 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.13200E+01 MeV frac = 1.00000E+00 Product nuclide = 481260 : beta- + + Nuclide 961 / 1657 : 471270 -- silver 127 (Ag-127) + + Pointers : 1120457 -1000000 + Primary type : Decay + Nuclide ZAI : 471270 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 126.93645 + Atomic weight ratio (AWR) : 125.84600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 79 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.62000E+00 MeV frac = 1.00000E+00 Product nuclide = 481270 : beta- + + Nuclide 962 / 1657 : 471280 -- silver 128 (Ag-128) + + Pointers : 1120641 -1000000 + Primary type : Decay + Nuclide ZAI : 471280 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 127.94108 + Atomic weight ratio (AWR) : 126.84200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 58 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.24900E+01 MeV frac = 1.00000E+00 Product nuclide = 481280 : beta- + + Nuclide 963 / 1657 : 471290 -- silver 129 (Ag-129) + + Pointers : 1120825 -1000000 + Primary type : Decay + Nuclide ZAI : 471290 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 128.94369 + Atomic weight ratio (AWR) : 127.83600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 44 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.07500E+01 MeV frac = 5.00000E-01 Product nuclide = 481290 : beta- + 2 RTYP = 1 Q = 1.07500E+01 MeV frac = 5.00000E-01 Product nuclide = 481291 : beta- + + Nuclide 964 / 1657 : 471300 -- silver 130 (Ag-130) + + Pointers : 1121082 -1000000 + Primary type : Decay + Nuclide ZAI : 471300 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 129.95034 + Atomic weight ratio (AWR) : 128.83400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 50 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.54100E+01 MeV frac = 1.00000E+00 Product nuclide = 481300 : beta- + + Nuclide 965 / 1657 : 481080 -- cadmium 108 (Cd-108) + + Pointers : 1121266 -1000000 + Primary type : Decay + Nuclide ZAI : 481080 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 107.90395 + Atomic weight ratio (AWR) : 106.97700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.29E+25 seconds (4.1E+17 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 22 Q = 2.71996E-01 MeV frac = 1.00000E+00 Product nuclide = 46108.82c : EC/beta+ + EC/beta+ + + Nuclide 966 / 1657 : 481090 -- cadmium 109 (Cd-109) + + Pointers : 1121450 -1000000 + Primary type : Decay + Nuclide ZAI : 481090 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 108.90455 + Atomic weight ratio (AWR) : 107.96900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.99E+07 seconds (1.27 years) + Specific ingestion toxicity : 2.00E-09 Sv/Bq + Specific inhalation toxicity : 8.10E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 1.27466E-01 MeV frac = 1.00000E+00 Product nuclide = 471091 : EC/beta+ + + Nuclide 967 / 1657 : 481111 -- cadmium 111m (Cd-111m) + + Pointers : 1128270 -1000000 + Primary type : Decay + Nuclide ZAI : 481111 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 110.90372 + Atomic weight ratio (AWR) : 109.95100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.91E+03 seconds (48.5 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 3.96220E-01 MeV frac = 1.00000E+00 Product nuclide = 48111.82c : IT + + Nuclide 968 / 1657 : 481131 -- cadmium 113m (Cd-113m) + + Pointers : 1134971 -1000000 + Primary type : Decay + Nuclide ZAI : 481131 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 112.90390 + Atomic weight ratio (AWR) : 111.93400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.45E+08 seconds (14.1 years) + Specific ingestion toxicity : 2.30E-08 Sv/Bq + Specific inhalation toxicity : 1.10E-07 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 2.63700E-01 MeV frac = 1.40000E-03 Product nuclide = 48113.82c : IT + 2 RTYP = 1 Q = 5.85700E-01 MeV frac = 9.98600E-01 Product nuclide = 49113.82c : beta- + + Nuclide 969 / 1657 : 481150 -- cadmium 115 (Cd-115) + + Pointers : 1138625 -1000000 + Primary type : Decay + Nuclide ZAI : 481150 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 114.90510 + Atomic weight ratio (AWR) : 113.91800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.92E+05 seconds (2.23 days) + Specific ingestion toxicity : 1.40E-09 Sv/Bq + Specific inhalation toxicity : 1.10E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.44870E+00 MeV frac = 6.99783E-07 Product nuclide = 49115.82c : beta- + 2 RTYP = 1 Q = 1.11244E+00 MeV frac = 9.99999E-01 Product nuclide = 491151 : beta- + + Nuclide 970 / 1657 : 481170 -- cadmium 117 (Cd-117) + + Pointers : 1145661 -1000000 + Primary type : Decay + Nuclide ZAI : 481170 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 116.90730 + Atomic weight ratio (AWR) : 115.90300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.96E+03 seconds (2.49 hours) + Specific ingestion toxicity : 2.80E-10 Sv/Bq + Specific inhalation toxicity : 1.70E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 2.52200E+00 MeV frac = 8.34229E-02 Product nuclide = 491170 : beta- + 2 RTYP = 1 Q = 2.20670E+00 MeV frac = 9.16577E-01 Product nuclide = 491171 : beta- + + Nuclide 971 / 1657 : 481171 -- cadmium 117m (Cd-117m) + + Pointers : 1148247 -1000000 + Primary type : Decay + Nuclide ZAI : 481171 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 116.90730 + Atomic weight ratio (AWR) : 115.90300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.21E+04 seconds (3.36 hours) + Specific ingestion toxicity : 2.80E-10 Sv/Bq + Specific inhalation toxicity : 2.10E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 2.66140E+00 MeV frac = 9.84760E-01 Product nuclide = 491170 : beta- + 2 RTYP = 1 Q = 2.34609E+00 MeV frac = 1.52398E-02 Product nuclide = 491171 : beta- + + Nuclide 972 / 1657 : 481180 -- cadmium 118 (Cd-118) + + Pointers : 1149713 -1000000 + Primary type : Decay + Nuclide ZAI : 481180 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 117.90688 + Atomic weight ratio (AWR) : 116.89400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.02E+03 seconds (50.3 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.20000E-01 MeV frac = 1.00000E+00 Product nuclide = 491180 : beta- + + Nuclide 973 / 1657 : 481190 -- cadmium 119 (Cd-119) + + Pointers : 1149930 -1000000 + Primary type : Decay + Nuclide ZAI : 481190 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 118.90950 + Atomic weight ratio (AWR) : 117.88800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.61E+02 seconds (2.69 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 3.73000E+00 MeV frac = 9.72332E-02 Product nuclide = 491190 : beta- + 2 RTYP = 1 Q = 3.41893E+00 MeV frac = 9.02767E-01 Product nuclide = 491191 : beta- + + Nuclide 974 / 1657 : 481191 -- cadmium 119m (Cd-119m) + + Pointers : 1151648 -1000000 + Primary type : Decay + Nuclide ZAI : 481191 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 118.90950 + Atomic weight ratio (AWR) : 117.88800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.32E+02 seconds (2.2 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 3.87654E+00 MeV frac = 9.98121E-01 Product nuclide = 491190 : beta- + 2 RTYP = 1 Q = 3.56573E+00 MeV frac = 1.87880E-03 Product nuclide = 491191 : beta- + + Nuclide 975 / 1657 : 481200 -- cadmium 120 (Cd-120) + + Pointers : 1153464 -1000000 + Primary type : Decay + Nuclide ZAI : 481200 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 119.91009 + Atomic weight ratio (AWR) : 118.88000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 50.8 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.76000E+00 MeV frac = 1.00000E+00 Product nuclide = 491200 : beta- + + Nuclide 976 / 1657 : 481210 -- cadmium 121 (Cd-121) + + Pointers : 1153681 -1000000 + Primary type : Decay + Nuclide ZAI : 481210 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 120.91270 + Atomic weight ratio (AWR) : 119.87400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 13.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 4.78000E+00 MeV frac = 3.25652E-01 Product nuclide = 491210 : beta- + 2 RTYP = 1 Q = 4.46631E+00 MeV frac = 6.74348E-01 Product nuclide = 491211 : beta- + + Nuclide 977 / 1657 : 481211 -- cadmium 121m (Cd-121m) + + Pointers : 1155609 -1000000 + Primary type : Decay + Nuclide ZAI : 481211 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 120.91270 + Atomic weight ratio (AWR) : 119.87400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.99489E+00 MeV frac = 1.00000E+00 Product nuclide = 491210 : beta- + + Nuclide 978 / 1657 : 481220 -- cadmium 122 (Cd-122) + + Pointers : 1157338 -1000000 + Primary type : Decay + Nuclide ZAI : 481220 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 121.91330 + Atomic weight ratio (AWR) : 120.86600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.24 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.85000E+00 MeV frac = 1.00000E+00 Product nuclide = 491220 : beta- + + Nuclide 979 / 1657 : 481230 -- cadmium 123 (Cd-123) + + Pointers : 1157555 -1000000 + Primary type : Decay + Nuclide ZAI : 481230 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 122.91692 + Atomic weight ratio (AWR) : 121.86100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.1 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 6.10000E+00 MeV frac = 3.09747E-01 Product nuclide = 491230 : beta- + 2 RTYP = 1 Q = 5.77279E+00 MeV frac = 6.90253E-01 Product nuclide = 491231 : beta- + + Nuclide 980 / 1657 : 481231 -- cadmium 123m (Cd-123m) + + Pointers : 1158867 -1000000 + Primary type : Decay + Nuclide ZAI : 481231 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 122.91692 + Atomic weight ratio (AWR) : 121.86100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.82 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 6.43153E+00 MeV frac = 9.83421E-01 Product nuclide = 491230 : beta- + 2 RTYP = 1 Q = 6.10430E+00 MeV frac = 1.65791E-02 Product nuclide = 491231 : beta- + + Nuclide 981 / 1657 : 481240 -- cadmium 124 (Cd-124) + + Pointers : 1160879 -1000000 + Primary type : Decay + Nuclide ZAI : 481240 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 123.91752 + Atomic weight ratio (AWR) : 122.85300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.25 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.17000E+00 MeV frac = 1.00000E+00 Product nuclide = 491240 : beta- + + Nuclide 982 / 1657 : 481250 -- cadmium 125 (Cd-125) + + Pointers : 1161063 -1000000 + Primary type : Decay + Nuclide ZAI : 481250 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 124.92114 + Atomic weight ratio (AWR) : 123.84800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.68 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 7.12000E+00 MeV frac = 4.58570E-01 Product nuclide = 491250 : beta- + 2 RTYP = 1 Q = 6.75988E+00 MeV frac = 5.41430E-01 Product nuclide = 491251 : beta- + + Nuclide 983 / 1657 : 481251 -- cadmium 125m (Cd-125m) + + Pointers : 1161829 -1000000 + Primary type : Decay + Nuclide ZAI : 481251 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 124.92114 + Atomic weight ratio (AWR) : 123.84800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.48 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.30400E+00 MeV frac = 1.00000E+00 Product nuclide = 491250 : beta- + + Nuclide 984 / 1657 : 481260 -- cadmium 126 (Cd-126) + + Pointers : 1163040 -1000000 + Primary type : Decay + Nuclide ZAI : 481260 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 125.92274 + Atomic weight ratio (AWR) : 124.84100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.515 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.48000E+00 MeV frac = 1.00000E+00 Product nuclide = 491260 : beta- + + Nuclide 985 / 1657 : 481270 -- cadmium 127 (Cd-127) + + Pointers : 1163224 -1000000 + Primary type : Decay + Nuclide ZAI : 481270 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 126.92636 + Atomic weight ratio (AWR) : 125.83600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.37 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.01000E+00 MeV frac = 1.00000E+00 Product nuclide = 491271 : beta- + + Nuclide 986 / 1657 : 481280 -- cadmium 128 (Cd-128) + + Pointers : 1163408 -1000000 + Primary type : Decay + Nuclide ZAI : 481280 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 127.92797 + Atomic weight ratio (AWR) : 126.82900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.28 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.82213E+00 MeV frac = 1.00000E+00 Product nuclide = 491281 : beta- + + Nuclide 987 / 1657 : 481290 -- cadmium 129 (Cd-129) + + Pointers : 1163592 -1000000 + Primary type : Decay + Nuclide ZAI : 481290 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 128.93260 + Atomic weight ratio (AWR) : 127.82500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.242 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.36000E+00 MeV frac = 1.00000E+00 Product nuclide = 491291 : beta- + + Nuclide 988 / 1657 : 481291 -- cadmium 129m (Cd-129m) + + Pointers : 1163776 -1000000 + Primary type : Decay + Nuclide ZAI : 481291 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 128.93260 + Atomic weight ratio (AWR) : 127.82500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.104 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.74000E+00 MeV frac = 1.00000E+00 Product nuclide = 491290 : beta- + + Nuclide 989 / 1657 : 481300 -- cadmium 130 (Cd-130) + + Pointers : 1163960 -1000000 + Primary type : Decay + Nuclide ZAI : 481300 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 129.93420 + Atomic weight ratio (AWR) : 128.81800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.162 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 1 Q = 8.32000E+00 MeV frac = 9.65000E-01 Product nuclide = 491300 : beta- + 2 RTYP = 15 Q = 3.29870E+00 MeV frac = 1.75000E-02 Product nuclide = 491290 : beta- + neutron emission + 3 RTYP = 15 Q = 2.91870E+00 MeV frac = 1.75000E-02 Product nuclide = 491291 : beta- + neutron emission + + Nuclide 990 / 1657 : 481310 -- cadmium 131 (Cd-131) + + Pointers : 1164290 -1000000 + Primary type : Decay + Nuclide ZAI : 481310 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 130.94085 + Atomic weight ratio (AWR) : 129.81600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 68 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.28670E+01 MeV frac = 9.65000E-01 Product nuclide = 491310 : beta- + 2 RTYP = 15 Q = 6.54870E+00 MeV frac = 3.50000E-02 Product nuclide = 491300 : beta- + neutron emission + + Nuclide 991 / 1657 : 481320 -- cadmium 132 (Cd-132) + + Pointers : 1164547 -1000000 + Primary type : Decay + Nuclide ZAI : 481320 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 131.94548 + Atomic weight ratio (AWR) : 130.81200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 97 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.17000E+01 MeV frac = 4.00000E-01 Product nuclide = 491320 : beta- + 2 RTYP = 15 Q = 8.99570E+00 MeV frac = 6.00000E-01 Product nuclide = 491311 : beta- + neutron emission + + Nuclide 992 / 1657 : 491110 -- indium 111 (In-111) + + Pointers : 1164804 -1000000 + Primary type : Decay + Nuclide ZAI : 491110 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 110.90473 + Atomic weight ratio (AWR) : 109.95200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.42E+05 seconds (2.8 days) + Specific ingestion toxicity : 2.90E-10 Sv/Bq + Specific inhalation toxicity : 2.30E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 8.61800E-01 MeV frac = 9.99950E-01 Product nuclide = 48111.82c : EC/beta+ + 2 RTYP = 2 Q = 4.65640E-01 MeV frac = 5.00171E-05 Product nuclide = 481111 : EC/beta+ + + Nuclide 993 / 1657 : 491120 -- indium 112 (In-112) + + Pointers : 1165290 -1000000 + Primary type : Decay + Nuclide ZAI : 491120 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 111.90533 + Atomic weight ratio (AWR) : 110.94400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.82E+02 seconds (14.7 minutes) + Specific ingestion toxicity : 1.00E-11 Sv/Bq + Specific inhalation toxicity : 7.40E-12 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 6.64000E-01 MeV frac = 4.40000E-01 Product nuclide = 501120 : beta- + 2 RTYP = 2 Q = 2.58900E+00 MeV frac = 5.60000E-01 Product nuclide = 48112.82c : EC/beta+ + + Nuclide 994 / 1657 : 491131 -- indium 113m (In-113m) + + Pointers : 1170481 -1000000 + Primary type : Decay + Nuclide ZAI : 491131 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 112.90390 + Atomic weight ratio (AWR) : 111.93400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.97E+03 seconds (1.66 hours) + Specific ingestion toxicity : 2.80E-11 Sv/Bq + Specific inhalation toxicity : 2.00E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 3.91699E-01 MeV frac = 1.00000E+00 Product nuclide = 49113.82c : IT + + Nuclide 995 / 1657 : 491140 -- indium 114 (In-114) + + Pointers : 1170838 -1000000 + Primary type : Decay + Nuclide ZAI : 491140 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 113.90450 + Atomic weight ratio (AWR) : 112.92600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.19E+01 seconds (1.2 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.98630E+00 MeV frac = 9.95000E-01 Product nuclide = 501140 : beta- + 2 RTYP = 2 Q = 1.44400E+00 MeV frac = 5.00000E-03 Product nuclide = 48114.82c : EC/beta+ + + Nuclide 996 / 1657 : 491141 -- indium 114m (In-114m) + + Pointers : 1171338 -1000000 + Primary type : Decay + Nuclide ZAI : 491141 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 113.90450 + Atomic weight ratio (AWR) : 112.92600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.32E+06 seconds (50 days) + Specific ingestion toxicity : 4.10E-09 Sv/Bq + Specific inhalation toxicity : 9.30E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 1.63400E+00 MeV frac = 3.50000E-02 Product nuclide = 48114.82c : EC/beta+ + 2 RTYP = 3 Q = 1.90340E-01 MeV frac = 9.65000E-01 Product nuclide = 491140 : IT + + Nuclide 997 / 1657 : 491142 -- indium 114m (In-114m) + + Pointers : 3508889 -1000000 + Primary type : Decay + Nuclide ZAI : 491142 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 113.90450 + Atomic weight ratio (AWR) : 112.92600 + Temperature : 900.0 Kelvin + XS temperature : -1.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 43 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is not present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 3.11600E-01 MeV frac = 1.00000E+00 Product nuclide = 491141 : IT + + Nuclide 998 / 1657 : 491151 -- indium 115m (In-115m) + + Pointers : 1175143 -1000000 + Primary type : Decay + Nuclide ZAI : 491151 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 114.90409 + Atomic weight ratio (AWR) : 113.91700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.61E+04 seconds (4.49 hours) + Specific ingestion toxicity : 8.60E-11 Sv/Bq + Specific inhalation toxicity : 5.90E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.23733E-01 MeV frac = 5.00000E-02 Product nuclide = 50115.82c : beta- + 2 RTYP = 3 Q = 3.36244E-01 MeV frac = 9.50000E-01 Product nuclide = 49115.82c : IT + + Nuclide 999 / 1657 : 491160 -- indium 116 (In-116) + + Pointers : 1175755 -1000000 + Primary type : Decay + Nuclide ZAI : 491160 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 115.90569 + Atomic weight ratio (AWR) : 114.91000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 14.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.27600E+00 MeV frac = 1.00000E+00 Product nuclide = 50116.82c : beta- + + Nuclide 1000 / 1657 : 491161 -- indium 116m (In-116m) + + Pointers : 1176616 -1000000 + Primary type : Decay + Nuclide ZAI : 491161 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 115.90569 + Atomic weight ratio (AWR) : 114.91000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.28E+03 seconds (54.6 minutes) + Specific ingestion toxicity : 6.40E-11 Sv/Bq + Specific inhalation toxicity : 4.50E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.40300E+00 MeV frac = 1.00000E+00 Product nuclide = 50116.82c : beta- + + Nuclide 1001 / 1657 : 491162 -- indium 116m (In-116m) + + Pointers : 3509288 -1000000 + Primary type : Decay + Nuclide ZAI : 491162 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 115.90569 + Atomic weight ratio (AWR) : 114.91000 + Temperature : 900.0 Kelvin + XS temperature : -1.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.17 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is not present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.62390E-01 MeV frac = 1.00000E+00 Product nuclide = 491161 : IT + + Nuclide 1002 / 1657 : 491170 -- indium 117 (In-117) + + Pointers : 1179171 -1000000 + Primary type : Decay + Nuclide ZAI : 491170 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 116.90427 + Atomic weight ratio (AWR) : 115.90000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.59E+03 seconds (43.2 minutes) + Specific ingestion toxicity : 3.10E-11 Sv/Bq + Specific inhalation toxicity : 2.90E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.45500E+00 MeV frac = 9.96590E-01 Product nuclide = 50117.82c : beta- + 2 RTYP = 1 Q = 1.14040E+00 MeV frac = 3.40992E-03 Product nuclide = 501171 : beta- + + Nuclide 1003 / 1657 : 491171 -- indium 117m (In-117m) + + Pointers : 1179671 -1000000 + Primary type : Decay + Nuclide ZAI : 491171 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 116.90427 + Atomic weight ratio (AWR) : 115.90000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.97E+03 seconds (1.94 hours) + Specific ingestion toxicity : 1.20E-10 Sv/Bq + Specific inhalation toxicity : 7.20E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 3.15302E-01 MeV frac = 4.71000E-01 Product nuclide = 491170 : IT + 2 RTYP = 1 Q = 1.77030E+00 MeV frac = 5.29000E-01 Product nuclide = 50117.82c : beta- + + Nuclide 1004 / 1657 : 491180 -- indium 118 (In-118) + + Pointers : 1180381 -1000000 + Primary type : Decay + Nuclide ZAI : 491180 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 117.90587 + Atomic weight ratio (AWR) : 116.89300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.42300E+00 MeV frac = 1.00000E+00 Product nuclide = 50118.82c : beta- + + Nuclide 1005 / 1657 : 491181 -- indium 118m (In-118m) + + Pointers : 1180948 -1000000 + Primary type : Decay + Nuclide ZAI : 491181 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 117.90587 + Atomic weight ratio (AWR) : 116.89300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.67E+02 seconds (4.45 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.52300E+00 MeV frac = 1.00000E+00 Product nuclide = 50118.82c : beta- + + Nuclide 1006 / 1657 : 491182 -- indium 118m (In-118m) + + Pointers : 3509687 -1000000 + Primary type : Decay + Nuclide ZAI : 491182 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 117.90587 + Atomic weight ratio (AWR) : 116.89300 + Temperature : 900.0 Kelvin + XS temperature : -1.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is not present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 1.40000E-01 MeV frac = 9.86000E-01 Product nuclide = 491181 : IT + 2 RTYP = 1 Q = 4.66610E+00 MeV frac = 1.40000E-02 Product nuclide = 50118.82c : beta- + + Nuclide 1007 / 1657 : 491190 -- indium 119 (In-119) + + Pointers : 1182467 -1000000 + Primary type : Decay + Nuclide ZAI : 491190 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 118.90546 + Atomic weight ratio (AWR) : 117.88400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.44E+02 seconds (2.4 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 2.36440E+00 MeV frac = 9.66000E-02 Product nuclide = 50119.82c : beta- + 2 RTYP = 1 Q = 2.27487E+00 MeV frac = 9.03400E-01 Product nuclide = 501191 : beta- + + Nuclide 1008 / 1657 : 491191 -- indium 119m (In-119m) + + Pointers : 1182724 -1000000 + Primary type : Decay + Nuclide ZAI : 491191 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 118.90546 + Atomic weight ratio (AWR) : 117.88400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.08E+03 seconds (18 minutes) + Specific ingestion toxicity : 4.70E-11 Sv/Bq + Specific inhalation toxicity : 1.70E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 2.67577E+00 MeV frac = 9.44000E-01 Product nuclide = 50119.82c : beta- + 2 RTYP = 3 Q = 3.11370E-01 MeV frac = 5.60000E-02 Product nuclide = 491190 : IT + + Nuclide 1009 / 1657 : 491200 -- indium 120 (In-120) + + Pointers : 1182981 -1000000 + Primary type : Decay + Nuclide ZAI : 491200 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 119.90807 + Atomic weight ratio (AWR) : 118.87800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.08 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.37000E+00 MeV frac = 1.00000E+00 Product nuclide = 50120.82c : beta- + + Nuclide 1010 / 1657 : 491201 -- indium 120m (In-120m) + + Pointers : 1183380 -1000000 + Primary type : Decay + Nuclide ZAI : 491201 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 119.90807 + Atomic weight ratio (AWR) : 118.87800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 46.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.44000E+00 MeV frac = 1.00000E+00 Product nuclide = 50120.82c : beta- + + Nuclide 1011 / 1657 : 491202 -- indium 120m (In-120m) + + Pointers : 3509944 -1000000 + Primary type : Decay + Nuclide ZAI : 491202 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 119.90807 + Atomic weight ratio (AWR) : 118.87800 + Temperature : 900.0 Kelvin + XS temperature : -1.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 47.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is not present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.66510E+00 MeV frac = 1.00000E+00 Product nuclide = 50120.82c : beta- + + Nuclide 1012 / 1657 : 491210 -- indium 121 (In-121) + + Pointers : 1184829 -1000000 + Primary type : Decay + Nuclide ZAI : 491210 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 120.90766 + Atomic weight ratio (AWR) : 119.86900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 23.1 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 3.36300E+00 MeV frac = 8.86480E-01 Product nuclide = 501210 : beta- + 2 RTYP = 1 Q = 3.35670E+00 MeV frac = 1.13520E-01 Product nuclide = 501211 : beta- + + Nuclide 1013 / 1657 : 491211 -- indium 121m (In-121m) + + Pointers : 1185609 -1000000 + Primary type : Decay + Nuclide ZAI : 491211 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 120.90766 + Atomic weight ratio (AWR) : 119.86900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.33E+02 seconds (3.88 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 3.13600E-01 MeV frac = 1.20000E-02 Product nuclide = 491210 : IT + 2 RTYP = 1 Q = 3.67660E+00 MeV frac = 9.88000E-01 Product nuclide = 501210 : beta- + + Nuclide 1014 / 1657 : 491220 -- indium 122 (In-122) + + Pointers : 1186459 -1000000 + Primary type : Decay + Nuclide ZAI : 491220 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 121.91027 + Atomic weight ratio (AWR) : 120.86300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.37000E+00 MeV frac = 1.00000E+00 Product nuclide = 50122.82c : beta- + + Nuclide 1015 / 1657 : 491221 -- indium 122m (In-122m) + + Pointers : 1187236 -1000000 + Primary type : Decay + Nuclide ZAI : 491221 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 121.91027 + Atomic weight ratio (AWR) : 120.86300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 10.8 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.57000E+00 MeV frac = 1.00000E+00 Product nuclide = 50122.82c : beta- + + Nuclide 1016 / 1657 : 491222 -- indium 122m (In-122m) + + Pointers : 3510128 -1000000 + Primary type : Decay + Nuclide ZAI : 491222 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 121.91027 + Atomic weight ratio (AWR) : 120.86300 + Temperature : 900.0 Kelvin + XS temperature : -1.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 10.8 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is not present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.66000E+00 MeV frac = 1.00000E+00 Product nuclide = 50122.82c : beta- + + Nuclide 1017 / 1657 : 491230 -- indium 123 (In-123) + + Pointers : 1188139 -1000000 + Primary type : Decay + Nuclide ZAI : 491230 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 122.91087 + Atomic weight ratio (AWR) : 121.85500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.17 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 4.39400E+00 MeV frac = 3.23587E-02 Product nuclide = 50123.82c : beta- + 2 RTYP = 1 Q = 4.36940E+00 MeV frac = 9.67641E-01 Product nuclide = 501231 : beta- + + Nuclide 1018 / 1657 : 491231 -- indium 123m (In-123m) + + Pointers : 1189045 -1000000 + Primary type : Decay + Nuclide ZAI : 491231 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 122.91087 + Atomic weight ratio (AWR) : 121.85500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 47.8 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 4.72721E+00 MeV frac = 0.00000E+00 Product nuclide = 50123.82c : beta- + 2 RTYP = 1 Q = 4.70261E+00 MeV frac = 1.00000E+00 Product nuclide = 501231 : beta- + + Nuclide 1019 / 1657 : 491240 -- indium 124 (In-124) + + Pointers : 1189713 -1000000 + Primary type : Decay + Nuclide ZAI : 491240 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 123.91348 + Atomic weight ratio (AWR) : 122.84900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.12 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.36000E+00 MeV frac = 1.00000E+00 Product nuclide = 50124.82c : beta- + + Nuclide 1020 / 1657 : 491241 -- indium 124m (In-124m) + + Pointers : 1191498 -1000000 + Primary type : Decay + Nuclide ZAI : 491241 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 123.91348 + Atomic weight ratio (AWR) : 122.84900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.7 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.41000E+00 MeV frac = 1.00000E+00 Product nuclide = 50124.82c : beta- + + Nuclide 1021 / 1657 : 491250 -- indium 125 (In-125) + + Pointers : 1192541 -1000000 + Primary type : Decay + Nuclide ZAI : 491250 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 124.91408 + Atomic weight ratio (AWR) : 123.84100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.36 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 5.41800E+00 MeV frac = 1.86908E-01 Product nuclide = 50125.82c : beta- + 2 RTYP = 1 Q = 5.39050E+00 MeV frac = 8.13092E-01 Product nuclide = 501251 : beta- + + Nuclide 1022 / 1657 : 491251 -- indium 125m (In-125m) + + Pointers : 1193265 -1000000 + Primary type : Decay + Nuclide ZAI : 491251 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 124.91408 + Atomic weight ratio (AWR) : 123.84100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 12.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.75112E+00 MeV frac = 1.00000E+00 Product nuclide = 501251 : beta- + + Nuclide 1023 / 1657 : 491260 -- indium 126 (In-126) + + Pointers : 1193449 -1000000 + Primary type : Decay + Nuclide ZAI : 491260 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 125.91669 + Atomic weight ratio (AWR) : 124.83500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.53 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.20700E+00 MeV frac = 1.00000E+00 Product nuclide = 50126.82c : beta- + + Nuclide 1024 / 1657 : 491261 -- indium 126m (In-126m) + + Pointers : 1194758 -1000000 + Primary type : Decay + Nuclide ZAI : 491261 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 125.91669 + Atomic weight ratio (AWR) : 124.83500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.64 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.31000E+00 MeV frac = 1.00000E+00 Product nuclide = 50126.82c : beta- + + Nuclide 1025 / 1657 : 491270 -- indium 127 (In-127) + + Pointers : 1194942 -1000000 + Primary type : Decay + Nuclide ZAI : 491270 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 126.91729 + Atomic weight ratio (AWR) : 125.82700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.09 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 6.51000E+00 MeV frac = 1.72768E-01 Product nuclide = 501270 : beta- + 2 RTYP = 1 Q = 6.50493E+00 MeV frac = 8.27232E-01 Product nuclide = 501271 : beta- + + Nuclide 1026 / 1657 : 491271 -- indium 127m (In-127m) + + Pointers : 1197136 -1000000 + Primary type : Decay + Nuclide ZAI : 491271 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 126.91729 + Atomic weight ratio (AWR) : 125.82700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.67 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 6.96430E+00 MeV frac = 9.93100E-01 Product nuclide = 501271 : beta- + 2 RTYP = 15 Q = 1.41870E+00 MeV frac = 6.90000E-03 Product nuclide = 50126.82c : beta- + neutron emission + + Nuclide 1027 / 1657 : 491280 -- indium 128 (In-128) + + Pointers : 1197393 -1000000 + Primary type : Decay + Nuclide ZAI : 491280 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 127.91990 + Atomic weight ratio (AWR) : 126.82100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.84 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.97600E+00 MeV frac = 1.00000E+00 Product nuclide = 501280 : beta- + + Nuclide 1028 / 1657 : 491281 -- indium 128m (In-128m) + + Pointers : 1198506 -1000000 + Primary type : Decay + Nuclide ZAI : 491281 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 127.91990 + Atomic weight ratio (AWR) : 126.82100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 10 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 2.47870E-01 MeV frac = 1.00000E+00 Product nuclide = 491280 : IT + + Nuclide 1029 / 1657 : 491282 -- indium 128m (In-128m) + + Pointers : 3511031 -1000000 + Primary type : Decay + Nuclide ZAI : 491282 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 127.91990 + Atomic weight ratio (AWR) : 126.82100 + Temperature : 900.0 Kelvin + XS temperature : -1.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.72 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is not present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.20351E+00 MeV frac = 1.00000E+00 Product nuclide = 501281 : beta- + + Nuclide 1030 / 1657 : 491290 -- indium 129 (In-129) + + Pointers : 1198690 -1000000 + Primary type : Decay + Nuclide ZAI : 491290 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 128.92150 + Atomic weight ratio (AWR) : 127.81400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.61 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 7.66000E+00 MeV frac = 8.93541E-01 Product nuclide = 501290 : beta- + 2 RTYP = 1 Q = 7.62480E+00 MeV frac = 1.06459E-01 Product nuclide = 501291 : beta- + + Nuclide 1031 / 1657 : 491291 -- indium 129m (In-129m) + + Pointers : 1199498 -1000000 + Primary type : Decay + Nuclide ZAI : 491291 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 128.92150 + Atomic weight ratio (AWR) : 127.81400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.23 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.04000E+00 MeV frac = 9.97000E-01 Product nuclide = 501290 : beta- + + Nuclide 1032 / 1657 : 491300 -- indium 130 (In-130) + + Pointers : 1199981 -1000000 + Primary type : Decay + Nuclide ZAI : 491300 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 129.92513 + Atomic weight ratio (AWR) : 128.80900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.29 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.02490E+01 MeV frac = 7.10609E-01 Product nuclide = 501300 : beta- + 2 RTYP = 1 Q = 8.30216E+00 MeV frac = 2.89391E-01 Product nuclide = 501301 : beta- + + Nuclide 1033 / 1657 : 491301 -- indium 130m (In-130m) + + Pointers : 1200789 -1000000 + Primary type : Decay + Nuclide ZAI : 491301 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 129.92513 + Atomic weight ratio (AWR) : 128.80900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.54 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.35212E+00 MeV frac = 1.00000E+00 Product nuclide = 501301 : beta- + + Nuclide 1034 / 1657 : 491302 -- indium 130m (In-130m) + + Pointers : 3511215 -1000000 + Primary type : Decay + Nuclide ZAI : 491302 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 129.92513 + Atomic weight ratio (AWR) : 128.80900 + Temperature : 900.0 Kelvin + XS temperature : -1.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.54 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is not present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.06490E+01 MeV frac = 1.00000E+00 Product nuclide = 501300 : beta- + + Nuclide 1035 / 1657 : 491310 -- indium 131 (In-131) + + Pointers : 1201244 -1000000 + Primary type : Decay + Nuclide ZAI : 491310 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 130.92673 + Atomic weight ratio (AWR) : 129.80200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.28 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 9.18400E+00 MeV frac = 9.46928E-01 Product nuclide = 501310 : beta- + 2 RTYP = 1 Q = 8.94220E+00 MeV frac = 5.30721E-02 Product nuclide = 501311 : beta- + + Nuclide 1036 / 1657 : 491311 -- indium 131m (In-131m) + + Pointers : 1201800 -1000000 + Primary type : Decay + Nuclide ZAI : 491311 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 130.92673 + Atomic weight ratio (AWR) : 129.80200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.35 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 4 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 4 decay reactions: + + 1 RTYP = 1 Q = 9.52700E+00 MeV frac = 9.79820E-01 Product nuclide = 501310 : beta- + 2 RTYP = 15 Q = 4.28071E+00 MeV frac = 1.00000E-02 Product nuclide = 501300 : beta- + neutron emission + 3 RTYP = 15 Q = 2.33383E+00 MeV frac = 1.00000E-02 Product nuclide = 501301 : beta- + neutron emission + 4 RTYP = 3 Q = 3.50000E-01 MeV frac = 1.80000E-04 Product nuclide = 491310 : IT + + Nuclide 1037 / 1657 : 491312 -- indium 131m (In-131m) + + Pointers : 3512216 -1000000 + Primary type : Decay + Nuclide ZAI : 491312 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 130.92673 + Atomic weight ratio (AWR) : 129.80200 + Temperature : 900.0 Kelvin + XS temperature : -1.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.32 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is not present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 4 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 4 decay reactions: + + 1 RTYP = 1 Q = 1.31970E+01 MeV frac = 9.89720E-01 Product nuclide = 501311 : beta- + 2 RTYP = 15 Q = 8.03071E+00 MeV frac = 1.40000E-04 Product nuclide = 501300 : beta- + neutron emission + 3 RTYP = 15 Q = 6.08383E+00 MeV frac = 1.40000E-04 Product nuclide = 501301 : beta- + neutron emission + 4 RTYP = 3 Q = 4.10000E+00 MeV frac = 1.00000E-02 Product nuclide = 491310 : IT + + Nuclide 1038 / 1657 : 491320 -- indium 132 (In-132) + + Pointers : 1202203 -1000000 + Primary type : Decay + Nuclide ZAI : 491320 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 131.93338 + Atomic weight ratio (AWR) : 130.80000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.207 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.41400E+01 MeV frac = 1.00000E+00 Product nuclide = 501320 : beta- + + Nuclide 1039 / 1657 : 491330 -- indium 133 (In-133) + + Pointers : 1204002 -1000000 + Primary type : Decay + Nuclide ZAI : 491330 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 132.93801 + Atomic weight ratio (AWR) : 131.79600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.165 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.30200E+01 MeV frac = 1.50000E-01 Product nuclide = 501330 : beta- + 2 RTYP = 15 Q = 1.05527E+01 MeV frac = 8.50000E-01 Product nuclide = 501320 : beta- + neutron emission + + Nuclide 1040 / 1657 : 491331 -- indium 133m (In-133m) + + Pointers : 1204259 -1000000 + Primary type : Decay + Nuclide ZAI : 491331 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 132.93801 + Atomic weight ratio (AWR) : 131.79600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.18 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 3.30000E-01 MeV frac = 1.00000E+00 Product nuclide = 491330 : IT + + Nuclide 1041 / 1657 : 491340 -- indium 134 (In-134) + + Pointers : 1204443 -1000000 + Primary type : Decay + Nuclide ZAI : 491340 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 133.94466 + Atomic weight ratio (AWR) : 132.79400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.14 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 1 Q = 1.47800E+01 MeV frac = 3.10000E-01 Product nuclide = 501340 : beta- + 2 RTYP = 15 Q = 1.08587E+01 MeV frac = 6.50000E-01 Product nuclide = 501330 : beta- + neutron emission + 3 RTYP = 155 Q = 8.39140E+00 MeV frac = 4.00000E-02 Product nuclide = 501320 : beta- + neutron emission + neutron emission + + Nuclide 1042 / 1657 : 491350 -- indium 135 (In-135) + + Pointers : 1204773 -1000000 + Primary type : Decay + Nuclide ZAI : 491350 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 134.94929 + Atomic weight ratio (AWR) : 133.79000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 92 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.36000E+01 MeV frac = 1.00000E+00 Product nuclide = 501350 : beta- + + Nuclide 1043 / 1657 : 501120 -- tin 112 (Sn-112) + + Pointers : 1204957 -1000000 + Primary type : Decay + Nuclide ZAI : 501120 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 111.90533 + Atomic weight ratio (AWR) : 110.94400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1044 / 1657 : 501130 -- tin 113 (Sn-113) + + Pointers : 1205063 -1000000 + Primary type : Decay + Nuclide ZAI : 501130 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 112.90491 + Atomic weight ratio (AWR) : 111.93500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.94E+06 seconds (115 days) + Specific ingestion toxicity : 7.30E-10 Sv/Bq + Specific inhalation toxicity : 2.70E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 1.03600E+00 MeV frac = 4.00005E-08 Product nuclide = 49113.82c : EC/beta+ + 2 RTYP = 2 Q = 6.44301E-01 MeV frac = 1.00000E+00 Product nuclide = 491131 : EC/beta+ + + Nuclide 1045 / 1657 : 501140 -- tin 114 (Sn-114) + + Pointers : 1205549 -1000000 + Primary type : Decay + Nuclide ZAI : 501140 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 113.90248 + Atomic weight ratio (AWR) : 112.92400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1046 / 1657 : 501171 -- tin 117m (Sn-117m) + + Pointers : 1214402 -1000000 + Primary type : Decay + Nuclide ZAI : 501171 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 116.90326 + Atomic weight ratio (AWR) : 115.89900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.21E+06 seconds (14 days) + Specific ingestion toxicity : 7.10E-10 Sv/Bq + Specific inhalation toxicity : 2.40E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 3.14580E-01 MeV frac = 1.00000E+00 Product nuclide = 50117.82c : IT + + Nuclide 1047 / 1657 : 501191 -- tin 119m (Sn-119m) + + Pointers : 1220702 -1000000 + Primary type : Decay + Nuclide ZAI : 501191 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 118.90344 + Atomic weight ratio (AWR) : 117.88200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.53E+07 seconds (293 days) + Specific ingestion toxicity : 3.40E-10 Sv/Bq + Specific inhalation toxicity : 2.20E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 8.95300E-02 MeV frac = 1.00000E+00 Product nuclide = 50119.82c : IT + + Nuclide 1048 / 1657 : 501210 -- tin 121 (Sn-121) + + Pointers : 1224193 -1000000 + Primary type : Decay + Nuclide ZAI : 501210 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 120.90463 + Atomic weight ratio (AWR) : 119.86600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.73E+04 seconds (1.13 days) + Specific ingestion toxicity : 2.30E-10 Sv/Bq + Specific inhalation toxicity : 2.30E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.90600E-01 MeV frac = 1.00000E+00 Product nuclide = 51121.82c : beta- + + Nuclide 1049 / 1657 : 501211 -- tin 121m (Sn-121m) + + Pointers : 1224410 -1000000 + Primary type : Decay + Nuclide ZAI : 501211 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 120.90463 + Atomic weight ratio (AWR) : 119.86600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.39E+09 seconds (43.9 years) + Specific ingestion toxicity : 3.80E-10 Sv/Bq + Specific inhalation toxicity : 4.50E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 3.97300E-01 MeV frac = 2.24000E-01 Product nuclide = 51121.82c : beta- + 2 RTYP = 3 Q = 6.30000E-03 MeV frac = 7.76000E-01 Product nuclide = 501210 : IT + + Nuclide 1050 / 1657 : 501231 -- tin 123m (Sn-123m) + + Pointers : 1230363 -1000000 + Primary type : Decay + Nuclide ZAI : 501231 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 122.90583 + Atomic weight ratio (AWR) : 121.85000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.40E+03 seconds (40.1 minutes) + Specific ingestion toxicity : 3.80E-11 Sv/Bq + Specific inhalation toxicity : 2.70E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.42820E+00 MeV frac = 1.00000E+00 Product nuclide = 51123.82c : beta- + + Nuclide 1051 / 1657 : 501251 -- tin 125m (Sn-125m) + + Pointers : 1238011 -1000000 + Primary type : Decay + Nuclide ZAI : 501251 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 124.90803 + Atomic weight ratio (AWR) : 123.83500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.71E+02 seconds (9.52 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.38450E+00 MeV frac = 1.00000E+00 Product nuclide = 51125.82c : beta- + + Nuclide 1052 / 1657 : 501270 -- tin 127 (Sn-127) + + Pointers : 1242108 -1000000 + Primary type : Decay + Nuclide ZAI : 501270 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 126.91023 + Atomic weight ratio (AWR) : 125.82000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.56E+03 seconds (2.1 hours) + Specific ingestion toxicity : 2.00E-10 Sv/Bq + Specific inhalation toxicity : 1.30E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.20100E+00 MeV frac = 1.00000E+00 Product nuclide = 511270 : beta- + + Nuclide 1053 / 1657 : 501271 -- tin 127m (Sn-127m) + + Pointers : 1242292 -1000000 + Primary type : Decay + Nuclide ZAI : 501271 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 126.91023 + Atomic weight ratio (AWR) : 125.82000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.48E+02 seconds (4.13 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.20570E+00 MeV frac = 1.00000E+00 Product nuclide = 511270 : beta- + + Nuclide 1054 / 1657 : 501280 -- tin 128 (Sn-128) + + Pointers : 1242476 -1000000 + Primary type : Decay + Nuclide ZAI : 501280 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 127.91082 + Atomic weight ratio (AWR) : 126.81200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.54E+03 seconds (59.1 minutes) + Specific ingestion toxicity : 1.50E-10 Sv/Bq + Specific inhalation toxicity : 9.20E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.27400E+00 MeV frac = 1.00000E+00 Product nuclide = 511280 : beta- + + Nuclide 1055 / 1657 : 501281 -- tin 128m (Sn-128m) + + Pointers : 1243197 -1000000 + Primary type : Decay + Nuclide ZAI : 501281 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 127.91082 + Atomic weight ratio (AWR) : 126.81200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 2.09150E+00 MeV frac = 1.00000E+00 Product nuclide = 501280 : IT + + Nuclide 1056 / 1657 : 501290 -- tin 129 (Sn-129) + + Pointers : 1243596 -1000000 + Primary type : Decay + Nuclide ZAI : 501290 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 128.91343 + Atomic weight ratio (AWR) : 127.80600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.34E+02 seconds (2.23 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.03000E+00 MeV frac = 1.00000E+00 Product nuclide = 511290 : beta- + + Nuclide 1057 / 1657 : 501291 -- tin 129m (Sn-129m) + + Pointers : 1246697 -1000000 + Primary type : Decay + Nuclide ZAI : 501291 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 128.91343 + Atomic weight ratio (AWR) : 127.80600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.32E+02 seconds (7.2 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 2.21400E+00 MeV frac = 3.10000E-01 Product nuclide = 511291 : beta- + 2 RTYP = 1 Q = 4.06500E+00 MeV frac = 6.90000E-01 Product nuclide = 511290 : beta- + + Nuclide 1058 / 1657 : 501300 -- tin 130 (Sn-130) + + Pointers : 1250571 -1000000 + Primary type : Decay + Nuclide ZAI : 501300 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 129.91403 + Atomic weight ratio (AWR) : 128.79800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.24E+02 seconds (3.73 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.14800E+00 MeV frac = 1.00000E+00 Product nuclide = 511301 : beta- + + Nuclide 1059 / 1657 : 501301 -- tin 130m (Sn-130m) + + Pointers : 1252048 -1000000 + Primary type : Decay + Nuclide ZAI : 501301 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 129.91403 + Atomic weight ratio (AWR) : 128.79800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.02E+02 seconds (1.7 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 4.09500E+00 MeV frac = 1.60000E-01 Product nuclide = 511301 : beta- + 2 RTYP = 1 Q = 4.10000E+00 MeV frac = 8.40000E-01 Product nuclide = 511300 : beta- + + Nuclide 1060 / 1657 : 501310 -- tin 131 (Sn-131) + + Pointers : 1255110 -1000000 + Primary type : Decay + Nuclide ZAI : 501310 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 130.91664 + Atomic weight ratio (AWR) : 129.79200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 56 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.67400E+00 MeV frac = 1.00000E+00 Product nuclide = 511310 : beta- + + Nuclide 1061 / 1657 : 501311 -- tin 131m (Sn-131m) + + Pointers : 1255294 -1000000 + Primary type : Decay + Nuclide ZAI : 501311 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 130.91664 + Atomic weight ratio (AWR) : 129.79200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 58.4 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 4.75400E+00 MeV frac = 9.99996E-01 Product nuclide = 511310 : beta- + 2 RTYP = 3 Q = 8.00000E-02 MeV frac = 3.99998E-06 Product nuclide = 501310 : IT + + Nuclide 1062 / 1657 : 501320 -- tin 132 (Sn-132) + + Pointers : 1255551 -1000000 + Primary type : Decay + Nuclide ZAI : 501320 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 131.91825 + Atomic weight ratio (AWR) : 130.78500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 39.7 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.11900E+00 MeV frac = 1.00000E+00 Product nuclide = 511320 : beta- + + Nuclide 1063 / 1657 : 501330 -- tin 133 (Sn-133) + + Pointers : 1256636 -1000000 + Primary type : Decay + Nuclide ZAI : 501330 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 132.92389 + Atomic weight ratio (AWR) : 131.78200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.46 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.09500E+00 MeV frac = 1.00000E+00 Product nuclide = 511330 : beta- + + Nuclide 1064 / 1657 : 501340 -- tin 134 (Sn-134) + + Pointers : 1259639 -1000000 + Primary type : Decay + Nuclide ZAI : 501340 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 133.92852 + Atomic weight ratio (AWR) : 132.77800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.05 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 7.37000E+00 MeV frac = 8.30000E-01 Product nuclide = 511340 : beta- + 2 RTYP = 15 Q = 4.07170E+00 MeV frac = 1.70000E-01 Product nuclide = 511330 : beta- + neutron emission + + Nuclide 1065 / 1657 : 501350 -- tin 135 (Sn-135) + + Pointers : 1259896 -1000000 + Primary type : Decay + Nuclide ZAI : 501350 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 134.93516 + Atomic weight ratio (AWR) : 133.77600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.53 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 1 Q = 8.91000E+00 MeV frac = 7.90000E-01 Product nuclide = 511350 : beta- + 2 RTYP = 15 Q = 5.29870E+00 MeV frac = 1.05000E-01 Product nuclide = 511340 : beta- + neutron emission + 3 RTYP = 15 Q = 5.21870E+00 MeV frac = 1.05000E-01 Product nuclide = 511341 : beta- + neutron emission + + Nuclide 1066 / 1657 : 501360 -- tin 136 (Sn-136) + + Pointers : 1260226 -1000000 + Primary type : Decay + Nuclide ZAI : 501360 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 135.93979 + Atomic weight ratio (AWR) : 134.77200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.25 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.38000E+00 MeV frac = 7.00000E-01 Product nuclide = 511360 : beta- + 2 RTYP = 15 Q = 5.13870E+00 MeV frac = 3.00000E-01 Product nuclide = 511350 : beta- + neutron emission + + Nuclide 1067 / 1657 : 501370 -- tin 137 (Sn-137) + + Pointers : 1260483 -1000000 + Primary type : Decay + Nuclide ZAI : 501370 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 136.94644 + Atomic weight ratio (AWR) : 135.77000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.19 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 9.95000E+00 MeV frac = 4.20000E-01 Product nuclide = 511370 : beta- + 2 RTYP = 15 Q = 6.49870E+00 MeV frac = 5.80000E-01 Product nuclide = 511360 : beta- + neutron emission + + Nuclide 1068 / 1657 : 511180 -- antimony 118 (Sb-118) + + Pointers : 1260740 -1000000 + Primary type : Decay + Nuclide ZAI : 511180 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 117.90587 + Atomic weight ratio (AWR) : 116.89300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.16E+02 seconds (3.6 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 3.65660E+00 MeV frac = 1.00000E+00 Product nuclide = 50118.82c : EC/beta+ + + Nuclide 1069 / 1657 : 511181 -- antimony 118m (Sb-118m) + + Pointers : 1261321 -1000000 + Primary type : Decay + Nuclide ZAI : 511181 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 117.90587 + Atomic weight ratio (AWR) : 116.89300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.80E+04 seconds (5 hours) + Specific ingestion toxicity : 2.10E-10 Sv/Bq + Specific inhalation toxicity : 1.20E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 3.90660E+00 MeV frac = 1.00000E+00 Product nuclide = 50118.82c : EC/beta+ + + Nuclide 1070 / 1657 : 511190 -- antimony 119 (Sb-119) + + Pointers : 1261916 -1000000 + Primary type : Decay + Nuclide ZAI : 511190 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 118.90445 + Atomic weight ratio (AWR) : 117.88300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.38E+05 seconds (1.6 days) + Specific ingestion toxicity : 8.00E-11 Sv/Bq + Specific inhalation toxicity : 3.60E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 5.93000E-01 MeV frac = 1.00000E+00 Product nuclide = 50119.82c : EC/beta+ + + Nuclide 1071 / 1657 : 511191 -- antimony 119m (Sb-119m) + + Pointers : 1262301 -1000000 + Primary type : Decay + Nuclide ZAI : 511191 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 118.90445 + Atomic weight ratio (AWR) : 117.88300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.85 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 2.85200E+00 MeV frac = 1.00000E+00 Product nuclide = 511190 : IT + + Nuclide 1072 / 1657 : 511200 -- antimony 120 (Sb-120) + + Pointers : 1262485 -1000000 + Primary type : Decay + Nuclide ZAI : 511200 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 119.90505 + Atomic weight ratio (AWR) : 118.87500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.54E+02 seconds (15.9 minutes) + Specific ingestion toxicity : 1.40E-11 Sv/Bq + Specific inhalation toxicity : 7.30E-12 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 2.68100E+00 MeV frac = 1.00000E+00 Product nuclide = 50120.82c : EC/beta+ + + Nuclide 1073 / 1657 : 511201 -- antimony 120m (Sb-120m) + + Pointers : 1263010 -1000000 + Primary type : Decay + Nuclide ZAI : 511201 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 119.90505 + Atomic weight ratio (AWR) : 118.87500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.98E+05 seconds (5.76 days) + Specific ingestion toxicity : 1.20E-09 Sv/Bq + Specific inhalation toxicity : 1.10E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 2.88000E+00 MeV frac = 1.00000E+00 Product nuclide = 50120.82c : EC/beta+ + + Nuclide 1074 / 1657 : 511220 -- antimony 122 (Sb-122) + + Pointers : 1266422 -1000000 + Primary type : Decay + Nuclide ZAI : 511220 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 121.90523 + Atomic weight ratio (AWR) : 120.85800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.33E+05 seconds (2.7 days) + Specific ingestion toxicity : 1.70E-09 Sv/Bq + Specific inhalation toxicity : 1.10E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.98300E+00 MeV frac = 9.76300E-01 Product nuclide = 52122.82c : beta- + 2 RTYP = 2 Q = 1.62000E+00 MeV frac = 2.37000E-02 Product nuclide = 50122.82c : EC/beta+ + + Nuclide 1075 / 1657 : 511221 -- antimony 122m (Sb-122m) + + Pointers : 1267048 -1000000 + Primary type : Decay + Nuclide ZAI : 511221 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 121.90523 + Atomic weight ratio (AWR) : 120.85800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.51E+02 seconds (4.19 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.63560E-01 MeV frac = 1.00000E+00 Product nuclide = 511220 : IT + + Nuclide 1076 / 1657 : 511241 -- antimony 124m (Sb-124m) + + Pointers : 1275509 -1000000 + Primary type : Decay + Nuclide ZAI : 511241 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 123.90642 + Atomic weight ratio (AWR) : 122.84200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.30E+01 seconds (1.55 minutes) + Specific ingestion toxicity : 8.00E-12 Sv/Bq + Specific inhalation toxicity : 5.90E-12 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 2.91600E+00 MeV frac = 2.50000E-01 Product nuclide = 52124.82c : beta- + 2 RTYP = 3 Q = 1.08600E-02 MeV frac = 7.50000E-01 Product nuclide = 51124.82c : IT + + Nuclide 1077 / 1657 : 511242 -- antimony 124m (Sb-124m) + + Pointers : 3512619 -1000000 + Primary type : Decay + Nuclide ZAI : 511242 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 123.90642 + Atomic weight ratio (AWR) : 122.84200 + Temperature : 900.0 Kelvin + XS temperature : -1.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.21E+03 seconds (20.2 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is not present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 2.59800E-02 MeV frac = 1.00000E+00 Product nuclide = 511241 : IT + + Nuclide 1078 / 1657 : 511261 -- antimony 126m (Sb-126m) + + Pointers : 1285134 -1000000 + Primary type : Decay + Nuclide ZAI : 511261 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 125.90761 + Atomic weight ratio (AWR) : 124.82600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.15E+03 seconds (19.1 minutes) + Specific ingestion toxicity : 3.60E-11 Sv/Bq + Specific inhalation toxicity : 2.00E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 1.77000E-02 MeV frac = 1.40000E-01 Product nuclide = 51126.82c : IT + 2 RTYP = 1 Q = 3.69000E+00 MeV frac = 8.60000E-01 Product nuclide = 52126.82c : beta- + + Nuclide 1079 / 1657 : 511262 -- antimony 126m (Sb-126m) + + Pointers : 3503389 -1000000 + Primary type : Decay + Nuclide ZAI : 511262 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 125.90761 + Atomic weight ratio (AWR) : 124.82600 + Temperature : 900.0 Kelvin + XS temperature : -1.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 11 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is not present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 2.27000E-02 MeV frac = 1.00000E+00 Product nuclide = 511261 : IT + + Nuclide 1080 / 1657 : 511270 -- antimony 127 (Sb-127) + + Pointers : 1286152 -1000000 + Primary type : Decay + Nuclide ZAI : 511270 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 126.90720 + Atomic weight ratio (AWR) : 125.81700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.33E+05 seconds (3.85 days) + Specific ingestion toxicity : 1.70E-09 Sv/Bq + Specific inhalation toxicity : 1.90E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.58200E+00 MeV frac = 8.31773E-01 Product nuclide = 521270 : beta- + 2 RTYP = 1 Q = 1.49379E+00 MeV frac = 1.68227E-01 Product nuclide = 52527.82c : beta- + + Nuclide 1081 / 1657 : 511280 -- antimony 128 (Sb-128) + + Pointers : 1289172 -1000000 + Primary type : Decay + Nuclide ZAI : 511280 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 127.90880 + Atomic weight ratio (AWR) : 126.81000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.24E+04 seconds (9.01 hours) + Specific ingestion toxicity : 7.60E-10 Sv/Bq + Specific inhalation toxicity : 4.20E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.38400E+00 MeV frac = 1.00000E+00 Product nuclide = 52128.82c : beta- + + Nuclide 1082 / 1657 : 511281 -- antimony 128m (Sb-128m) + + Pointers : 1290509 -1000000 + Primary type : Decay + Nuclide ZAI : 511281 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 127.90880 + Atomic weight ratio (AWR) : 126.81000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.24E+02 seconds (10.4 minutes) + Specific ingestion toxicity : 3.30E-11 Sv/Bq + Specific inhalation toxicity : 1.50E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 1.00000E-02 MeV frac = 3.60000E-02 Product nuclide = 511280 : IT + 2 RTYP = 1 Q = 4.39400E+00 MeV frac = 9.64000E-01 Product nuclide = 52128.82c : beta- + + Nuclide 1083 / 1657 : 511290 -- antimony 129 (Sb-129) + + Pointers : 1291051 -1000000 + Primary type : Decay + Nuclide ZAI : 511290 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 128.90940 + Atomic weight ratio (AWR) : 127.80200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.57E+04 seconds (4.36 hours) + Specific ingestion toxicity : 4.20E-10 Sv/Bq + Specific inhalation toxicity : 2.50E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 2.37700E+00 MeV frac = 8.34000E-01 Product nuclide = 521290 : beta- + 2 RTYP = 1 Q = 2.27200E+00 MeV frac = 1.66000E-01 Product nuclide = 52529.82c : beta- + + Nuclide 1084 / 1657 : 511291 -- antimony 129m (Sb-129m) + + Pointers : 1293497 -1000000 + Primary type : Decay + Nuclide ZAI : 511291 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 128.90940 + Atomic weight ratio (AWR) : 127.80200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.06E+03 seconds (17.7 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 1 Q = 4.22800E+00 MeV frac = 2.00000E-02 Product nuclide = 521290 : beta- + 2 RTYP = 1 Q = 4.12300E+00 MeV frac = 8.30000E-01 Product nuclide = 52529.82c : beta- + 3 RTYP = 3 Q = 1.85130E+00 MeV frac = 1.50000E-01 Product nuclide = 511290 : IT + + Nuclide 1085 / 1657 : 511300 -- antimony 130 (Sb-130) + + Pointers : 1295246 -1000000 + Primary type : Decay + Nuclide ZAI : 511300 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 129.91201 + Atomic weight ratio (AWR) : 128.79600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.37E+03 seconds (39.5 minutes) + Specific ingestion toxicity : 9.10E-11 Sv/Bq + Specific inhalation toxicity : 5.30E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.95900E+00 MeV frac = 1.00000E+00 Product nuclide = 52130.82c : beta- + + Nuclide 1086 / 1657 : 511301 -- antimony 130m (Sb-130m) + + Pointers : 1296709 -1000000 + Primary type : Decay + Nuclide ZAI : 511301 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 129.91201 + Atomic weight ratio (AWR) : 128.79600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.78E+02 seconds (6.3 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.06420E+00 MeV frac = 1.00000E+00 Product nuclide = 52130.82c : beta- + + Nuclide 1087 / 1657 : 511310 -- antimony 131 (Sb-131) + + Pointers : 1296893 -1000000 + Primary type : Decay + Nuclide ZAI : 511310 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 130.91160 + Atomic weight ratio (AWR) : 129.78700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.38E+03 seconds (23 minutes) + Specific ingestion toxicity : 1.00E-10 Sv/Bq + Specific inhalation toxicity : 4.40E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 3.19000E+00 MeV frac = 9.19939E-01 Product nuclide = 521310 : beta- + 2 RTYP = 1 Q = 3.00775E+00 MeV frac = 8.00613E-02 Product nuclide = 521311 : beta- + + Nuclide 1088 / 1657 : 511320 -- antimony 132 (Sb-132) + + Pointers : 1298681 -1000000 + Primary type : Decay + Nuclide ZAI : 511320 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 131.91421 + Atomic weight ratio (AWR) : 130.78100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.67E+02 seconds (2.79 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.49000E+00 MeV frac = 1.00000E+00 Product nuclide = 52132.82c : beta- + + Nuclide 1089 / 1657 : 511321 -- antimony 132m (Sb-132m) + + Pointers : 1299724 -1000000 + Primary type : Decay + Nuclide ZAI : 511321 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 131.91421 + Atomic weight ratio (AWR) : 130.78100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.46E+02 seconds (4.1 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.69000E+00 MeV frac = 1.00000E+00 Product nuclide = 52132.82c : beta- + + Nuclide 1090 / 1657 : 511330 -- antimony 133 (Sb-133) + + Pointers : 1300459 -1000000 + Primary type : Decay + Nuclide ZAI : 511330 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 132.91481 + Atomic weight ratio (AWR) : 131.77300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.50E+02 seconds (2.5 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 4.00300E+00 MeV frac = 8.27113E-01 Product nuclide = 521330 : beta- + 2 RTYP = 1 Q = 3.66874E+00 MeV frac = 1.72887E-01 Product nuclide = 521331 : beta- + + Nuclide 1091 / 1657 : 511340 -- antimony 134 (Sb-134) + + Pointers : 1301463 -1000000 + Primary type : Decay + Nuclide ZAI : 511340 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 133.92045 + Atomic weight ratio (AWR) : 132.77000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.78 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.39400E+00 MeV frac = 1.00000E+00 Product nuclide = 521340 : beta- + + Nuclide 1092 / 1657 : 511341 -- antimony 134m (Sb-134m) + + Pointers : 1302002 -1000000 + Primary type : Decay + Nuclide ZAI : 511341 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 133.92045 + Atomic weight ratio (AWR) : 132.77000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 10.1 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 1 Q = 8.46900E+00 MeV frac = 9.99090E-01 Product nuclide = 521340 : beta- + 2 RTYP = 15 Q = 7.83702E-01 MeV frac = 4.55000E-04 Product nuclide = 521330 : beta- + neutron emission + 3 RTYP = 15 Q = 4.49442E-01 MeV frac = 4.55000E-04 Product nuclide = 521331 : beta- + neutron emission + + Nuclide 1093 / 1657 : 511350 -- antimony 135 (Sb-135) + + Pointers : 1302332 -1000000 + Primary type : Decay + Nuclide ZAI : 511350 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 134.92508 + Atomic weight ratio (AWR) : 133.76600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.74 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.12000E+00 MeV frac = 8.43000E-01 Product nuclide = 521350 : beta- + 2 RTYP = 15 Q = 4.62000E+00 MeV frac = 1.57000E-01 Product nuclide = 521340 : beta- + neutron emission + + Nuclide 1094 / 1657 : 511360 -- antimony 136 (Sb-136) + + Pointers : 1304484 -1000000 + Primary type : Decay + Nuclide ZAI : 511360 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 135.93072 + Atomic weight ratio (AWR) : 134.76300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.923 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 1 Q = 9.55000E+00 MeV frac = 8.34200E-01 Product nuclide = 521360 : beta- + 2 RTYP = 15 Q = 4.87870E+00 MeV frac = 1.63000E-01 Product nuclide = 521350 : beta- + neutron emission + 3 RTYP = 155 Q = 1.53640E+00 MeV frac = 2.80000E-03 Product nuclide = 521340 : beta- + neutron emission + neutron emission + + Nuclide 1095 / 1657 : 511370 -- antimony 137 (Sb-137) + + Pointers : 1304814 -1000000 + Primary type : Decay + Nuclide ZAI : 511370 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 136.93535 + Atomic weight ratio (AWR) : 135.75900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.45 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 9.30000E+00 MeV frac = 5.10000E-01 Product nuclide = 521370 : beta- + 2 RTYP = 15 Q = 6.09870E+00 MeV frac = 4.90000E-01 Product nuclide = 521360 : beta- + neutron emission + + Nuclide 1096 / 1657 : 511380 -- antimony 138 (Sb-138) + + Pointers : 1305071 -1000000 + Primary type : Decay + Nuclide ZAI : 511380 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 137.94099 + Atomic weight ratio (AWR) : 136.75600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.07800E+01 MeV frac = 1.00000E+00 Product nuclide = 521380 : beta- + + Nuclide 1097 / 1657 : 511390 -- antimony 139 (Sb-139) + + Pointers : 1305255 -1000000 + Primary type : Decay + Nuclide ZAI : 511390 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 138.94562 + Atomic weight ratio (AWR) : 137.75200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.04800E+01 MeV frac = 1.00000E+00 Product nuclide = 521390 : beta- + + Nuclide 1098 / 1657 : 521210 -- tellurium 121 (Te-121) + + Pointers : 1307248 -1000000 + Primary type : Decay + Nuclide ZAI : 521210 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 120.90463 + Atomic weight ratio (AWR) : 119.86600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.66E+06 seconds (19.2 days) + Specific ingestion toxicity : 4.30E-10 Sv/Bq + Specific inhalation toxicity : 4.10E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 1.03600E+00 MeV frac = 1.00000E+00 Product nuclide = 51121.82c : EC/beta+ + + Nuclide 1099 / 1657 : 521211 -- tellurium 121m (Te-121m) + + Pointers : 1307871 -1000000 + Primary type : Decay + Nuclide ZAI : 521211 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 120.90463 + Atomic weight ratio (AWR) : 119.86600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.33E+07 seconds (154 days) + Specific ingestion toxicity : 2.30E-09 Sv/Bq + Specific inhalation toxicity : 5.70E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 1.33000E+00 MeV frac = 1.13000E-01 Product nuclide = 51121.82c : EC/beta+ + 2 RTYP = 3 Q = 2.93991E-01 MeV frac = 8.87000E-01 Product nuclide = 521210 : IT + + Nuclide 1100 / 1657 : 521231 -- tellurium 123m (Te-123m) + + Pointers : 1313691 -1000000 + Primary type : Decay + Nuclide ZAI : 521231 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 122.90381 + Atomic weight ratio (AWR) : 121.84800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.03E+07 seconds (119 days) + Specific ingestion toxicity : 1.40E-09 Sv/Bq + Specific inhalation toxicity : 5.10E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 2.47430E-01 MeV frac = 1.00000E+00 Product nuclide = 52123.82c : IT + + Nuclide 1101 / 1657 : 521251 -- tellurium 125m (Te-125m) + + Pointers : 1318969 -1000000 + Primary type : Decay + Nuclide ZAI : 521251 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 124.90399 + Atomic weight ratio (AWR) : 123.83100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.96E+06 seconds (57.4 days) + Specific ingestion toxicity : 8.70E-10 Sv/Bq + Specific inhalation toxicity : 4.20E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.44766E-01 MeV frac = 1.00000E+00 Product nuclide = 52125.82c : IT + + Nuclide 1102 / 1657 : 521270 -- tellurium 127 (Te-127) + + Pointers : 1322140 -1000000 + Primary type : Decay + Nuclide ZAI : 521270 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 126.90518 + Atomic weight ratio (AWR) : 125.81500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.37E+04 seconds (9.35 hours) + Specific ingestion toxicity : 1.70E-10 Sv/Bq + Specific inhalation toxicity : 1.40E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.02000E-01 MeV frac = 1.00000E+00 Product nuclide = 53127.82c : beta- + + Nuclide 1103 / 1657 : 521290 -- tellurium 129 (Te-129) + + Pointers : 1326979 -1000000 + Primary type : Decay + Nuclide ZAI : 521290 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 128.90637 + Atomic weight ratio (AWR) : 127.79900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.18E+03 seconds (1.16 hours) + Specific ingestion toxicity : 6.30E-11 Sv/Bq + Specific inhalation toxicity : 3.90E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.49790E+00 MeV frac = 1.00000E+00 Product nuclide = 53129.82c : beta- + + Nuclide 1104 / 1657 : 521310 -- tellurium 131 (Te-131) + + Pointers : 1334798 -1000000 + Primary type : Decay + Nuclide ZAI : 521310 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 130.90857 + Atomic weight ratio (AWR) : 129.78400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.50E+03 seconds (25 minutes) + Specific ingestion toxicity : 8.70E-11 Sv/Bq + Specific inhalation toxicity : 2.80E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.24900E+00 MeV frac = 1.00000E+00 Product nuclide = 53131.82c : beta- + + Nuclide 1105 / 1657 : 521311 -- tellurium 131m (Te-131m) + + Pointers : 1336079 -1000000 + Primary type : Decay + Nuclide ZAI : 521311 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 130.90857 + Atomic weight ratio (AWR) : 129.78400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.08E+05 seconds (1.25 days) + Specific ingestion toxicity : 1.90E-09 Sv/Bq + Specific inhalation toxicity : 9.40E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 1.82320E-01 MeV frac = 2.10000E-01 Product nuclide = 521310 : IT + 2 RTYP = 1 Q = 2.43132E+00 MeV frac = 7.90000E-01 Product nuclide = 53131.82c : beta- + + Nuclide 1106 / 1657 : 521330 -- tellurium 133 (Te-133) + + Pointers : 1341214 -1000000 + Primary type : Decay + Nuclide ZAI : 521330 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 132.91077 + Atomic weight ratio (AWR) : 131.76900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.47E+02 seconds (12.4 minutes) + Specific ingestion toxicity : 7.20E-11 Sv/Bq + Specific inhalation toxicity : 2.00E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.92000E+00 MeV frac = 1.00000E+00 Product nuclide = 531330 : beta- + + Nuclide 1107 / 1657 : 521331 -- tellurium 133m (Te-133m) + + Pointers : 1344595 -1000000 + Primary type : Decay + Nuclide ZAI : 521331 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 132.91077 + Atomic weight ratio (AWR) : 131.76900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.32E+03 seconds (55.4 minutes) + Specific ingestion toxicity : 2.80E-10 Sv/Bq + Specific inhalation toxicity : 8.70E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 3.25426E+00 MeV frac = 8.25000E-01 Product nuclide = 531330 : beta- + 2 RTYP = 3 Q = 3.34270E-01 MeV frac = 1.75000E-01 Product nuclide = 521330 : IT + + Nuclide 1108 / 1657 : 521340 -- tellurium 134 (Te-134) + + Pointers : 1349029 -1000000 + Primary type : Decay + Nuclide ZAI : 521340 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 133.91137 + Atomic weight ratio (AWR) : 132.76100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.51E+03 seconds (41.8 minutes) + Specific ingestion toxicity : 1.10E-10 Sv/Bq + Specific inhalation toxicity : 6.80E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.55000E+00 MeV frac = 1.00000E+00 Product nuclide = 531340 : beta- + + Nuclide 1109 / 1657 : 521350 -- tellurium 135 (Te-135) + + Pointers : 1349848 -1000000 + Primary type : Decay + Nuclide ZAI : 521350 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 134.91600 + Atomic weight ratio (AWR) : 133.75700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 19 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.88800E+00 MeV frac = 1.00000E+00 Product nuclide = 53135.82c : beta- + + Nuclide 1110 / 1657 : 521360 -- tellurium 136 (Te-136) + + Pointers : 1350891 -1000000 + Primary type : Decay + Nuclide ZAI : 521360 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 135.91962 + Atomic weight ratio (AWR) : 134.75200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 17.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.07000E+00 MeV frac = 1.00000E+00 Product nuclide = 531360 : beta- + + Nuclide 1111 / 1657 : 521370 -- tellurium 137 (Te-137) + + Pointers : 1351752 -1000000 + Primary type : Decay + Nuclide ZAI : 521370 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 136.92526 + Atomic weight ratio (AWR) : 135.74900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.49 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 1 Q = 6.94300E+00 MeV frac = 9.70100E-01 Product nuclide = 531370 : beta- + 2 RTYP = 15 Q = 1.86870E+00 MeV frac = 1.49500E-02 Product nuclide = 531360 : beta- + neutron emission + 3 RTYP = 15 Q = 1.21870E+00 MeV frac = 1.49500E-02 Product nuclide = 531361 : beta- + neutron emission + + Nuclide 1112 / 1657 : 521380 -- tellurium 138 (Te-138) + + Pointers : 1352082 -1000000 + Primary type : Decay + Nuclide ZAI : 521380 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 137.92888 + Atomic weight ratio (AWR) : 136.74400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.4 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 6.40000E+00 MeV frac = 9.37000E-01 Product nuclide = 531380 : beta- + 2 RTYP = 15 Q = 2.50171E+00 MeV frac = 6.30000E-02 Product nuclide = 531370 : beta- + neutron emission + + Nuclide 1113 / 1657 : 521390 -- tellurium 139 (Te-139) + + Pointers : 1352339 -1000000 + Primary type : Decay + Nuclide ZAI : 521390 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 138.93452 + Atomic weight ratio (AWR) : 137.74100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.04000E+00 MeV frac = 1.00000E+00 Product nuclide = 531390 : beta- + + Nuclide 1114 / 1657 : 521400 -- tellurium 140 (Te-140) + + Pointers : 1352523 -1000000 + Primary type : Decay + Nuclide ZAI : 521400 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 139.93915 + Atomic weight ratio (AWR) : 138.73700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.31000E+00 MeV frac = 1.00000E+00 Product nuclide = 531400 : beta- + + Nuclide 1115 / 1657 : 521410 -- tellurium 141 (Te-141) + + Pointers : 1352707 -1000000 + Primary type : Decay + Nuclide ZAI : 521410 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 140.94479 + Atomic weight ratio (AWR) : 139.73400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 100 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.96000E+00 MeV frac = 1.00000E+00 Product nuclide = 531410 : beta- + + Nuclide 1116 / 1657 : 521420 -- tellurium 142 (Te-142) + + Pointers : 1352891 -1000000 + Primary type : Decay + Nuclide ZAI : 521420 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 141.94942 + Atomic weight ratio (AWR) : 140.73000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 50 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.29000E+00 MeV frac = 1.00000E+00 Product nuclide = 531420 : beta- + + Nuclide 1117 / 1657 : 531250 -- iodine 125 (I-125) + + Pointers : 1353075 -1000000 + Primary type : Decay + Nuclide ZAI : 531250 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 124.90500 + Atomic weight ratio (AWR) : 123.83200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.13E+06 seconds (59.4 days) + Specific ingestion toxicity : 1.50E-08 Sv/Bq + Specific inhalation toxicity : 5.10E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 1.85770E-01 MeV frac = 1.00000E+00 Product nuclide = 52125.82c : EC/beta+ + + Nuclide 1118 / 1657 : 531260 -- iodine 126 (I-126) + + Pointers : 1353446 -1000000 + Primary type : Decay + Nuclide ZAI : 531260 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 125.90560 + Atomic weight ratio (AWR) : 124.82400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.12E+06 seconds (13 days) + Specific ingestion toxicity : 2.90E-08 Sv/Bq + Specific inhalation toxicity : 9.80E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.25100E+00 MeV frac = 4.37000E-01 Product nuclide = 541260 : beta- + 2 RTYP = 2 Q = 2.15600E+00 MeV frac = 5.63000E-01 Product nuclide = 52126.82c : EC/beta+ + + Nuclide 1119 / 1657 : 531280 -- iodine 128 (I-128) + + Pointers : 1366258 -1000000 + Primary type : Decay + Nuclide ZAI : 531280 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 127.90578 + Atomic weight ratio (AWR) : 126.80700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.50E+03 seconds (25 minutes) + Specific ingestion toxicity : 4.60E-11 Sv/Bq + Specific inhalation toxicity : 2.00E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 1.25200E+00 MeV frac = 6.90000E-02 Product nuclide = 52128.82c : EC/beta+ + 2 RTYP = 1 Q = 2.11900E+00 MeV frac = 9.31000E-01 Product nuclide = 54128.82c : beta- + + Nuclide 1120 / 1657 : 531301 -- iodine 130m (I-130m) + + Pointers : 1381383 -1000000 + Primary type : Decay + Nuclide ZAI : 531301 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 129.90697 + Atomic weight ratio (AWR) : 128.79100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.30E+02 seconds (8.84 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 3.99525E-02 MeV frac = 8.40000E-01 Product nuclide = 53130.82c : IT + 2 RTYP = 1 Q = 2.98965E+00 MeV frac = 1.60000E-01 Product nuclide = 54130.82c : beta- + + Nuclide 1121 / 1657 : 531320 -- iodine 132 (I-132) + + Pointers : 1386488 -1000000 + Primary type : Decay + Nuclide ZAI : 531320 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 131.90816 + Atomic weight ratio (AWR) : 130.77500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.26E+03 seconds (2.29 hours) + Specific ingestion toxicity : 2.90E-10 Sv/Bq + Specific inhalation toxicity : 1.10E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.58100E+00 MeV frac = 1.00000E+00 Product nuclide = 54132.82c : beta- + + Nuclide 1122 / 1657 : 531321 -- iodine 132m (I-132m) + + Pointers : 1390737 -1000000 + Primary type : Decay + Nuclide ZAI : 531321 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 131.90816 + Atomic weight ratio (AWR) : 130.77500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.98E+03 seconds (1.38 hours) + Specific ingestion toxicity : 2.20E-10 Sv/Bq + Specific inhalation toxicity : 8.50E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 1.20000E-01 MeV frac = 8.60000E-01 Product nuclide = 531320 : IT + 2 RTYP = 1 Q = 3.69700E+00 MeV frac = 1.40000E-01 Product nuclide = 54132.82c : beta- + + Nuclide 1123 / 1657 : 531330 -- iodine 133 (I-133) + + Pointers : 1391783 -1000000 + Primary type : Decay + Nuclide ZAI : 531330 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 132.90775 + Atomic weight ratio (AWR) : 131.76600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.51E+04 seconds (20.9 hours) + Specific ingestion toxicity : 4.30E-09 Sv/Bq + Specific inhalation toxicity : 1.50E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.75700E+00 MeV frac = 9.71189E-01 Product nuclide = 54133.82c : beta- + 2 RTYP = 1 Q = 1.52378E+00 MeV frac = 2.88108E-02 Product nuclide = 541331 : beta- + + Nuclide 1124 / 1657 : 531331 -- iodine 133m (I-133m) + + Pointers : 1393809 -1000000 + Primary type : Decay + Nuclide ZAI : 531331 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 132.90775 + Atomic weight ratio (AWR) : 131.76600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.63415E+00 MeV frac = 1.00000E+00 Product nuclide = 531330 : IT + + Nuclide 1125 / 1657 : 531340 -- iodine 134 (I-134) + + Pointers : 1394320 -1000000 + Primary type : Decay + Nuclide ZAI : 531340 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 133.90935 + Atomic weight ratio (AWR) : 132.75900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.15E+03 seconds (52.5 minutes) + Specific ingestion toxicity : 1.10E-10 Sv/Bq + Specific inhalation toxicity : 5.50E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.17500E+00 MeV frac = 1.00000E+00 Product nuclide = 54134.82c : beta- + + Nuclide 1126 / 1657 : 531341 -- iodine 134m (I-134m) + + Pointers : 1396357 -1000000 + Primary type : Decay + Nuclide ZAI : 531341 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 133.91036 + Atomic weight ratio (AWR) : 132.76000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.16E+02 seconds (3.6 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 3.16500E-01 MeV frac = 9.77000E-01 Product nuclide = 531340 : IT + 2 RTYP = 1 Q = 2.52020E+00 MeV frac = 2.30000E-02 Product nuclide = 541341 : beta- + + Nuclide 1127 / 1657 : 531360 -- iodine 136 (I-136) + + Pointers : 1401716 -1000000 + Primary type : Decay + Nuclide ZAI : 531360 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 135.91458 + Atomic weight ratio (AWR) : 134.74700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.35E+01 seconds (1.39 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.85700E+00 MeV frac = 1.00000E+00 Product nuclide = 54136.82c : beta- + + Nuclide 1128 / 1657 : 531361 -- iodine 136m (I-136m) + + Pointers : 1406371 -1000000 + Primary type : Decay + Nuclide ZAI : 531361 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 135.91458 + Atomic weight ratio (AWR) : 134.74700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 47 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 54136.82c : beta- + + Nuclide 1129 / 1657 : 531370 -- iodine 137 (I-137) + + Pointers : 1408408 -1000000 + Primary type : Decay + Nuclide ZAI : 531370 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 136.91820 + Atomic weight ratio (AWR) : 135.74200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 24.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 5.87700E+00 MeV frac = 9.35000E-01 Product nuclide = 541370 : beta- + 2 RTYP = 15 Q = 1.86000E+00 MeV frac = 6.50000E-02 Product nuclide = 54136.82c : beta- + neutron emission + + Nuclide 1130 / 1657 : 531380 -- iodine 138 (I-138) + + Pointers : 1417056 -1000000 + Primary type : Decay + Nuclide ZAI : 531380 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 137.92283 + Atomic weight ratio (AWR) : 136.73800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.46 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 7.82000E+00 MeV frac = 9.47000E-01 Product nuclide = 541380 : beta- + 2 RTYP = 15 Q = 2.00000E+00 MeV frac = 5.30000E-02 Product nuclide = 541370 : beta- + neutron emission + + Nuclide 1131 / 1657 : 531390 -- iodine 139 (I-139) + + Pointers : 1420272 -1000000 + Primary type : Decay + Nuclide ZAI : 531390 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 138.92645 + Atomic weight ratio (AWR) : 137.73300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 6.80700E+00 MeV frac = 9.02000E-01 Product nuclide = 541390 : beta- + 2 RTYP = 15 Q = 3.18000E+00 MeV frac = 9.80000E-02 Product nuclide = 541380 : beta- + neutron emission + + Nuclide 1132 / 1657 : 531400 -- iodine 140 (I-140) + + Pointers : 1424524 -1000000 + Primary type : Decay + Nuclide ZAI : 531400 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 139.93108 + Atomic weight ratio (AWR) : 138.72900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.86 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.72000E+00 MeV frac = 9.07000E-01 Product nuclide = 541400 : beta- + 2 RTYP = 15 Q = 3.30270E+00 MeV frac = 9.30000E-02 Product nuclide = 541390 : beta- + neutron emission + + Nuclide 1133 / 1657 : 531410 -- iodine 141 (I-141) + + Pointers : 1424781 -1000000 + Primary type : Decay + Nuclide ZAI : 531410 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 140.93470 + Atomic weight ratio (AWR) : 139.72400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.43 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 7.81000E+00 MeV frac = 7.90000E-01 Product nuclide = 541410 : beta- + 2 RTYP = 15 Q = 4.39870E+00 MeV frac = 2.10000E-01 Product nuclide = 541400 : beta- + neutron emission + + Nuclide 1134 / 1657 : 531420 -- iodine 142 (I-142) + + Pointers : 1425038 -1000000 + Primary type : Decay + Nuclide ZAI : 531420 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 141.94034 + Atomic weight ratio (AWR) : 140.72100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 9.76000E+00 MeV frac = 7.50000E-01 Product nuclide = 541420 : beta- + 2 RTYP = 15 Q = 4.53870E+00 MeV frac = 2.50000E-01 Product nuclide = 541410 : beta- + neutron emission + + Nuclide 1135 / 1657 : 531430 -- iodine 143 (I-143) + + Pointers : 1425295 -1000000 + Primary type : Decay + Nuclide ZAI : 531430 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 142.94497 + Atomic weight ratio (AWR) : 141.71700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 100 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.81000E+00 MeV frac = 6.00000E-01 Product nuclide = 541430 : beta- + 2 RTYP = 15 Q = 5.76870E+00 MeV frac = 4.00000E-01 Product nuclide = 541420 : beta- + neutron emission + + Nuclide 1136 / 1657 : 531440 -- iodine 144 (I-144) + + Pointers : 1425552 -1000000 + Primary type : Decay + Nuclide ZAI : 531440 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 143.94960 + Atomic weight ratio (AWR) : 142.71300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 50 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.07000E+01 MeV frac = 6.00000E-01 Product nuclide = 541440 : beta- + 2 RTYP = 15 Q = 5.79870E+00 MeV frac = 4.00000E-01 Product nuclide = 541430 : beta- + neutron emission + + Nuclide 1137 / 1657 : 541260 -- xenon 126 (Xe-126) + + Pointers : 1425809 -1000000 + Primary type : Decay + Nuclide ZAI : 541260 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 125.90459 + Atomic weight ratio (AWR) : 124.82300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1138 / 1657 : 541270 -- xenon 127 (Xe-127) + + Pointers : 1425915 -1000000 + Primary type : Decay + Nuclide ZAI : 541270 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 126.90518 + Atomic weight ratio (AWR) : 125.81500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.14E+06 seconds (36.4 days) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 6.62300E-01 MeV frac = 1.00000E+00 Product nuclide = 53127.82c : EC/beta+ + + Nuclide 1139 / 1657 : 541291 -- xenon 129m (Xe-129m) + + Pointers : 1433520 -1000000 + Primary type : Decay + Nuclide ZAI : 541291 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 128.90436 + Atomic weight ratio (AWR) : 127.79700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.67E+05 seconds (8.88 days) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 2.36140E-01 MeV frac = 1.00000E+00 Product nuclide = 54129.82c : IT + + Nuclide 1140 / 1657 : 541311 -- xenon 131m (Xe-131m) + + Pointers : 1438276 -1000000 + Primary type : Decay + Nuclide ZAI : 541311 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 130.90555 + Atomic weight ratio (AWR) : 129.78100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.03E+06 seconds (12 days) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.63930E-01 MeV frac = 1.00000E+00 Product nuclide = 54131.82c : IT + + Nuclide 1141 / 1657 : 541321 -- xenon 132m (Xe-132m) + + Pointers : 1441770 -1000000 + Primary type : Decay + Nuclide ZAI : 541321 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 131.90413 + Atomic weight ratio (AWR) : 130.77100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.39 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 2.75216E+00 MeV frac = 1.00000E+00 Product nuclide = 54132.82c : IT + + Nuclide 1142 / 1657 : 541331 -- xenon 133m (Xe-133m) + + Pointers : 1446011 -1000000 + Primary type : Decay + Nuclide ZAI : 541331 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 132.90573 + Atomic weight ratio (AWR) : 131.76400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.90E+05 seconds (2.2 days) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 2.33219E-01 MeV frac = 1.00000E+00 Product nuclide = 54133.82c : IT + + Nuclide 1143 / 1657 : 541341 -- xenon 134m (Xe-134m) + + Pointers : 1449724 -1000000 + Primary type : Decay + Nuclide ZAI : 541341 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 133.90532 + Atomic weight ratio (AWR) : 132.75500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.29 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.96550E+00 MeV frac = 1.00000E+00 Product nuclide = 54134.82c : IT + + Nuclide 1144 / 1657 : 541351 -- xenon 135m (Xe-135m) + + Pointers : 1451394 -1000000 + Primary type : Decay + Nuclide ZAI : 541351 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 134.90692 + Atomic weight ratio (AWR) : 133.74800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.18E+02 seconds (15.3 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 5.26571E-01 MeV frac = 9.99960E-01 Product nuclide = 54135.82c : IT + 2 RTYP = 1 Q = 1.69197E+00 MeV frac = 4.00000E-05 Product nuclide = 55135.82c : beta- + + Nuclide 1145 / 1657 : 541370 -- xenon 137 (Xe-137) + + Pointers : 1454981 -1000000 + Primary type : Decay + Nuclide ZAI : 541370 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 136.91114 + Atomic weight ratio (AWR) : 135.73500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.29E+02 seconds (3.82 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.17300E+00 MeV frac = 1.00000E+00 Product nuclide = 55137.82c : beta- + + Nuclide 1146 / 1657 : 541380 -- xenon 138 (Xe-138) + + Pointers : 1456962 -1000000 + Primary type : Decay + Nuclide ZAI : 541380 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 137.91375 + Atomic weight ratio (AWR) : 136.72900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.45E+02 seconds (14.1 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.77000E+00 MeV frac = 1.00000E+00 Product nuclide = 551380 : beta- + + Nuclide 1147 / 1657 : 541390 -- xenon 139 (Xe-139) + + Pointers : 1459223 -1000000 + Primary type : Decay + Nuclide ZAI : 541390 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 138.91838 + Atomic weight ratio (AWR) : 137.72500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 39.7 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.05700E+00 MeV frac = 1.00000E+00 Product nuclide = 551390 : beta- + + Nuclide 1148 / 1657 : 541400 -- xenon 140 (Xe-140) + + Pointers : 1466398 -1000000 + Primary type : Decay + Nuclide ZAI : 541400 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 139.92200 + Atomic weight ratio (AWR) : 138.72000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 13.6 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.06100E+00 MeV frac = 1.00000E+00 Product nuclide = 551400 : beta- + + Nuclide 1149 / 1657 : 541410 -- xenon 141 (Xe-141) + + Pointers : 1466582 -1000000 + Primary type : Decay + Nuclide ZAI : 541410 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 140.92663 + Atomic weight ratio (AWR) : 139.71600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.73 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 6.14700E+00 MeV frac = 9.99560E-01 Product nuclide = 551410 : beta- + 2 RTYP = 15 Q = 6.49701E-01 MeV frac = 4.40000E-04 Product nuclide = 551400 : beta- + neutron emission + + Nuclide 1150 / 1657 : 541420 -- xenon 142 (Xe-142) + + Pointers : 1466839 -1000000 + Primary type : Decay + Nuclide ZAI : 541420 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 141.92925 + Atomic weight ratio (AWR) : 140.71000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.22 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 5.03500E+00 MeV frac = 9.96400E-01 Product nuclide = 551420 : beta- + 2 RTYP = 15 Q = 9.25702E-01 MeV frac = 3.60000E-03 Product nuclide = 551410 : beta- + neutron emission + + Nuclide 1151 / 1657 : 541430 -- xenon 143 (Xe-143) + + Pointers : 1467096 -1000000 + Primary type : Decay + Nuclide ZAI : 541430 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 142.93489 + Atomic weight ratio (AWR) : 141.70700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.511 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 7.22100E+00 MeV frac = 9.90000E-01 Product nuclide = 551430 : beta- + 2 RTYP = 15 Q = 1.99370E+00 MeV frac = 1.00000E-02 Product nuclide = 551420 : beta- + neutron emission + + Nuclide 1152 / 1657 : 541440 -- xenon 144 (Xe-144) + + Pointers : 1467353 -1000000 + Primary type : Decay + Nuclide ZAI : 541440 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 143.93851 + Atomic weight ratio (AWR) : 142.70200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.388 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 5.99000E+00 MeV frac = 9.70000E-01 Product nuclide = 551440 : beta- + 2 RTYP = 15 Q = 2.31970E+00 MeV frac = 3.00000E-02 Product nuclide = 551430 : beta- + neutron emission + + Nuclide 1153 / 1657 : 541450 -- xenon 145 (Xe-145) + + Pointers : 1467610 -1000000 + Primary type : Decay + Nuclide ZAI : 541450 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 144.94415 + Atomic weight ratio (AWR) : 143.69900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.188 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 1 Q = 7.95700E+00 MeV frac = 9.50000E-01 Product nuclide = 551450 : beta- + 2 RTYP = 15 Q = 3.09870E+00 MeV frac = 2.50000E-02 Product nuclide = 551440 : beta- + neutron emission + 3 RTYP = 15 Q = 2.79870E+00 MeV frac = 2.50000E-02 Product nuclide = 551441 : beta- + neutron emission + + Nuclide 1154 / 1657 : 541460 -- xenon 146 (Xe-146) + + Pointers : 1467940 -1000000 + Primary type : Decay + Nuclide ZAI : 541460 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 145.94777 + Atomic weight ratio (AWR) : 144.69400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.146 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 6.95000E+00 MeV frac = 9.31000E-01 Product nuclide = 551460 : beta- + 2 RTYP = 15 Q = 3.31570E+00 MeV frac = 6.90000E-02 Product nuclide = 551450 : beta- + neutron emission + + Nuclide 1155 / 1657 : 541470 -- xenon 147 (Xe-147) + + Pointers : 1468197 -1000000 + Primary type : Decay + Nuclide ZAI : 541470 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 146.95341 + Atomic weight ratio (AWR) : 145.69100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.13 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.76000E+00 MeV frac = 9.60000E-01 Product nuclide = 551470 : beta- + 2 RTYP = 15 Q = 4.28870E+00 MeV frac = 4.00000E-02 Product nuclide = 551460 : beta- + neutron emission + + Nuclide 1156 / 1657 : 551310 -- cesium 131 (Cs-131) + + Pointers : 1468454 -1000000 + Primary type : Decay + Nuclide ZAI : 551310 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 130.90555 + Atomic weight ratio (AWR) : 129.78100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.37E+05 seconds (9.69 days) + Specific ingestion toxicity : 5.80E-11 Sv/Bq + Specific inhalation toxicity : 4.70E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 3.55000E-01 MeV frac = 1.00000E+00 Product nuclide = 54131.82c : EC/beta+ + + Nuclide 1157 / 1657 : 551320 -- cesium 132 (Cs-132) + + Pointers : 1468797 -1000000 + Primary type : Decay + Nuclide ZAI : 551320 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 131.90614 + Atomic weight ratio (AWR) : 130.77300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.64E+05 seconds (6.53 days) + Specific ingestion toxicity : 5.00E-10 Sv/Bq + Specific inhalation toxicity : 3.00E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.27900E+00 MeV frac = 1.80000E-02 Product nuclide = 561320 : beta- + 2 RTYP = 2 Q = 2.13000E+00 MeV frac = 9.82000E-01 Product nuclide = 54132.82c : EC/beta+ + + Nuclide 1158 / 1657 : 551341 -- cesium 134m (Cs-134m) + + Pointers : 1474914 -1000000 + Primary type : Decay + Nuclide ZAI : 551341 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 133.90633 + Atomic weight ratio (AWR) : 132.75600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.05E+04 seconds (2.91 hours) + Specific ingestion toxicity : 2.00E-11 Sv/Bq + Specific inhalation toxicity : 6.00E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.38747E-01 MeV frac = 1.00000E+00 Product nuclide = 55134.82c : IT + + Nuclide 1159 / 1657 : 551351 -- cesium 135m (Cs-135m) + + Pointers : 1477983 -1000000 + Primary type : Decay + Nuclide ZAI : 551351 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 134.90591 + Atomic weight ratio (AWR) : 133.74700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.18E+03 seconds (53 minutes) + Specific ingestion toxicity : 1.90E-11 Sv/Bq + Specific inhalation toxicity : 1.60E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.63330E+00 MeV frac = 1.00000E+00 Product nuclide = 55135.82c : IT + + Nuclide 1160 / 1657 : 551361 -- cesium 136m (Cs-136m) + + Pointers : 1481591 -1000000 + Primary type : Decay + Nuclide ZAI : 551361 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 135.90752 + Atomic weight ratio (AWR) : 134.74000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 19 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 3.10000E+00 MeV frac = 5.00000E-01 Product nuclide = 56136.82c : beta- + 2 RTYP = 3 Q = 6.00000E-01 MeV frac = 5.00000E-01 Product nuclide = 55136.82c : IT + + Nuclide 1161 / 1657 : 551380 -- cesium 138 (Cs-138) + + Pointers : 1484894 -1000000 + Primary type : Decay + Nuclide ZAI : 551380 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 137.91073 + Atomic weight ratio (AWR) : 136.72600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.00E+03 seconds (33.4 minutes) + Specific ingestion toxicity : 9.20E-11 Sv/Bq + Specific inhalation toxicity : 4.30E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.37400E+00 MeV frac = 1.00000E+00 Product nuclide = 56138.82c : beta- + + Nuclide 1162 / 1657 : 551381 -- cesium 138m (Cs-138m) + + Pointers : 1487337 -1000000 + Primary type : Decay + Nuclide ZAI : 551381 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 137.91073 + Atomic weight ratio (AWR) : 136.72600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.75E+02 seconds (2.91 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 7.99000E-02 MeV frac = 8.10000E-01 Product nuclide = 551380 : IT + 2 RTYP = 1 Q = 5.45450E+00 MeV frac = 1.90000E-01 Product nuclide = 56138.82c : beta- + + Nuclide 1163 / 1657 : 551390 -- cesium 139 (Cs-139) + + Pointers : 1487594 -1000000 + Primary type : Decay + Nuclide ZAI : 551390 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 138.91334 + Atomic weight ratio (AWR) : 137.72000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.56E+02 seconds (9.27 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.21300E+00 MeV frac = 1.00000E+00 Product nuclide = 561390 : beta- + + Nuclide 1164 / 1657 : 551400 -- cesium 140 (Cs-140) + + Pointers : 1491171 -1000000 + Primary type : Decay + Nuclide ZAI : 551400 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 139.91696 + Atomic weight ratio (AWR) : 138.71500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.40E+01 seconds (1.07 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.22000E+00 MeV frac = 1.00000E+00 Product nuclide = 56140.82c : beta- + + Nuclide 1165 / 1657 : 551410 -- cesium 141 (Cs-141) + + Pointers : 1502490 -1000000 + Primary type : Decay + Nuclide ZAI : 551410 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 140.91957 + Atomic weight ratio (AWR) : 139.70900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 24.8 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.25600E+00 MeV frac = 1.00000E+00 Product nuclide = 561410 : beta- + + Nuclide 1166 / 1657 : 551420 -- cesium 142 (Cs-142) + + Pointers : 1506529 -1000000 + Primary type : Decay + Nuclide ZAI : 551420 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 141.92420 + Atomic weight ratio (AWR) : 140.70500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.68 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.30800E+00 MeV frac = 1.00000E+00 Product nuclide = 561420 : beta- + + Nuclide 1167 / 1657 : 551430 -- cesium 143 (Cs-143) + + Pointers : 1507754 -1000000 + Primary type : Decay + Nuclide ZAI : 551430 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 142.92783 + Atomic weight ratio (AWR) : 141.70000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.79 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 6.26500E+00 MeV frac = 9.83600E-01 Product nuclide = 561430 : beta- + 2 RTYP = 15 Q = 2.08070E+00 MeV frac = 1.64000E-02 Product nuclide = 561420 : beta- + neutron emission + + Nuclide 1168 / 1657 : 551440 -- cesium 144 (Cs-144) + + Pointers : 1508011 -1000000 + Primary type : Decay + Nuclide ZAI : 551440 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 143.93246 + Atomic weight ratio (AWR) : 142.69600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.994 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.49900E+00 MeV frac = 9.68000E-01 Product nuclide = 561440 : beta- + 2 RTYP = 15 Q = 2.59470E+00 MeV frac = 3.20000E-02 Product nuclide = 561430 : beta- + neutron emission + + Nuclide 1169 / 1657 : 551441 -- cesium 144m (Cs-144m) + + Pointers : 1508268 -1000000 + Primary type : Decay + Nuclide ZAI : 551441 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 143.93246 + Atomic weight ratio (AWR) : 142.69600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.79900E+00 MeV frac = 5.00000E-01 Product nuclide = 561440 : beta- + 2 RTYP = 3 Q = 3.00000E-01 MeV frac = 5.00000E-01 Product nuclide = 551440 : IT + + Nuclide 1170 / 1657 : 551450 -- cesium 145 (Cs-145) + + Pointers : 1508525 -1000000 + Primary type : Decay + Nuclide ZAI : 551450 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 144.93507 + Atomic weight ratio (AWR) : 143.69000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.594 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 7.93000E+00 MeV frac = 8.57000E-01 Product nuclide = 561450 : beta- + 2 RTYP = 15 Q = 3.52400E+00 MeV frac = 1.43000E-01 Product nuclide = 561440 : beta- + neutron emission + + Nuclide 1171 / 1657 : 551460 -- cesium 146 (Cs-146) + + Pointers : 1511181 -1000000 + Primary type : Decay + Nuclide ZAI : 551460 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 145.94071 + Atomic weight ratio (AWR) : 144.68700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.323 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 9.38000E+00 MeV frac = 8.58000E-01 Product nuclide = 561460 : beta- + 2 RTYP = 15 Q = 3.71870E+00 MeV frac = 1.42000E-01 Product nuclide = 561450 : beta- + neutron emission + + Nuclide 1172 / 1657 : 551470 -- cesium 147 (Cs-147) + + Pointers : 1511438 -1000000 + Primary type : Decay + Nuclide ZAI : 551470 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 146.94433 + Atomic weight ratio (AWR) : 145.68200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.225 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.58000E+00 MeV frac = 7.15000E-01 Product nuclide = 561470 : beta- + 2 RTYP = 15 Q = 4.90870E+00 MeV frac = 2.85000E-01 Product nuclide = 561460 : beta- + neutron emission + + Nuclide 1173 / 1657 : 551480 -- cesium 148 (Cs-148) + + Pointers : 1511695 -1000000 + Primary type : Decay + Nuclide ZAI : 551480 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 147.94896 + Atomic weight ratio (AWR) : 146.67800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.146 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.07100E+01 MeV frac = 7.49000E-01 Product nuclide = 561480 : beta- + 2 RTYP = 15 Q = 5.22870E+00 MeV frac = 2.51000E-01 Product nuclide = 561470 : beta- + neutron emission + + Nuclide 1174 / 1657 : 551490 -- cesium 149 (Cs-149) + + Pointers : 1511952 -1000000 + Primary type : Decay + Nuclide ZAI : 551490 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 148.95258 + Atomic weight ratio (AWR) : 147.67300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.15 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.64000E+00 MeV frac = 1.00000E+00 Product nuclide = 561490 : beta- + + Nuclide 1175 / 1657 : 551500 -- cesium 150 (Cs-150) + + Pointers : 1512136 -1000000 + Primary type : Decay + Nuclide ZAI : 551500 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 149.95822 + Atomic weight ratio (AWR) : 148.67000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 100 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.16400E+01 MeV frac = 1.00000E+00 Product nuclide = 561500 : beta- + + Nuclide 1176 / 1657 : 561320 -- barium 132 (Ba-132) + + Pointers : 1512320 -1000000 + Primary type : Decay + Nuclide ZAI : 561320 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 131.90514 + Atomic weight ratio (AWR) : 130.77200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1177 / 1657 : 561330 -- barium 133 (Ba-133) + + Pointers : 1512426 -1000000 + Primary type : Decay + Nuclide ZAI : 561330 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 132.90573 + Atomic weight ratio (AWR) : 131.76400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.33E+08 seconds (10.5 years) + Specific ingestion toxicity : 1.50E-09 Sv/Bq + Specific inhalation toxicity : 1.00E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 5.17300E-01 MeV frac = 1.00000E+00 Product nuclide = 55133.82c : EC/beta+ + + Nuclide 1178 / 1657 : 561331 -- barium 133m (Ba-133m) + + Pointers : 1513357 -1000000 + Primary type : Decay + Nuclide ZAI : 561331 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 132.90573 + Atomic weight ratio (AWR) : 131.76400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.38E+05 seconds (1.59 days) + Specific ingestion toxicity : 5.40E-10 Sv/Bq + Specific inhalation toxicity : 4.60E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 8.09000E-01 MeV frac = 1.01000E-04 Product nuclide = 55133.82c : EC/beta+ + 2 RTYP = 3 Q = 2.88250E-01 MeV frac = 9.99899E-01 Product nuclide = 561330 : IT + + Nuclide 1179 / 1657 : 561351 -- barium 135m (Ba-135m) + + Pointers : 1519698 -1000000 + Primary type : Decay + Nuclide ZAI : 561351 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 134.90591 + Atomic weight ratio (AWR) : 133.74700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.03E+05 seconds (1.2 days) + Specific ingestion toxicity : 4.30E-10 Sv/Bq + Specific inhalation toxicity : 3.60E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 2.68218E-01 MeV frac = 1.00000E+00 Product nuclide = 56135.82c : IT + + Nuclide 1180 / 1657 : 561361 -- barium 136m (Ba-136m) + + Pointers : 1522681 -1000000 + Primary type : Decay + Nuclide ZAI : 561361 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 135.90449 + Atomic weight ratio (AWR) : 134.73700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.308 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 2.03047E+00 MeV frac = 1.00000E+00 Product nuclide = 56136.82c : IT + + Nuclide 1181 / 1657 : 561371 -- barium 137m (Ba-137m) + + Pointers : 1525782 -1000000 + Primary type : Decay + Nuclide ZAI : 561371 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 136.90610 + Atomic weight ratio (AWR) : 135.73000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.53E+02 seconds (2.55 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 6.61659E-01 MeV frac = 1.00000E+00 Product nuclide = 56137.82c : IT + + Nuclide 1182 / 1657 : 561390 -- barium 139 (Ba-139) + + Pointers : 1529302 -1000000 + Primary type : Decay + Nuclide ZAI : 561390 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 138.90930 + Atomic weight ratio (AWR) : 137.71600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.98E+03 seconds (1.38 hours) + Specific ingestion toxicity : 1.20E-10 Sv/Bq + Specific inhalation toxicity : 5.90E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.31680E+00 MeV frac = 1.00000E+00 Product nuclide = 57139.82c : beta- + + Nuclide 1183 / 1657 : 561410 -- barium 141 (Ba-141) + + Pointers : 1533196 -1000000 + Primary type : Decay + Nuclide ZAI : 561410 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 140.91453 + Atomic weight ratio (AWR) : 139.70400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.10E+03 seconds (18.3 minutes) + Specific ingestion toxicity : 7.00E-11 Sv/Bq + Specific inhalation toxicity : 3.40E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.23000E+00 MeV frac = 1.00000E+00 Product nuclide = 571410 : beta- + + Nuclide 1184 / 1657 : 561420 -- barium 142 (Ba-142) + + Pointers : 1535723 -1000000 + Primary type : Decay + Nuclide ZAI : 561420 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 141.91613 + Atomic weight ratio (AWR) : 140.69700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.36E+02 seconds (10.6 minutes) + Specific ingestion toxicity : 3.50E-11 Sv/Bq + Specific inhalation toxicity : 2.20E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.21100E+00 MeV frac = 1.00000E+00 Product nuclide = 571420 : beta- + + Nuclide 1185 / 1657 : 561430 -- barium 143 (Ba-143) + + Pointers : 1538152 -1000000 + Primary type : Decay + Nuclide ZAI : 561430 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 142.92077 + Atomic weight ratio (AWR) : 141.69300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 14.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.25100E+00 MeV frac = 1.00000E+00 Product nuclide = 571430 : beta- + + Nuclide 1186 / 1657 : 561440 -- barium 144 (Ba-144) + + Pointers : 1538336 -1000000 + Primary type : Decay + Nuclide ZAI : 561440 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 143.92338 + Atomic weight ratio (AWR) : 142.68700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 11.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.12100E+00 MeV frac = 1.00000E+00 Product nuclide = 571440 : beta- + + Nuclide 1187 / 1657 : 561450 -- barium 145 (Ba-145) + + Pointers : 1538520 -1000000 + Primary type : Decay + Nuclide ZAI : 561450 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 144.92801 + Atomic weight ratio (AWR) : 143.68300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.31 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.58000E+00 MeV frac = 1.00000E+00 Product nuclide = 571450 : beta- + + Nuclide 1188 / 1657 : 561460 -- barium 146 (Ba-146) + + Pointers : 1538704 -1000000 + Primary type : Decay + Nuclide ZAI : 561460 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 145.93062 + Atomic weight ratio (AWR) : 144.67700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.22 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.12000E+00 MeV frac = 1.00000E+00 Product nuclide = 571460 : beta- + + Nuclide 1189 / 1657 : 561470 -- barium 147 (Ba-147) + + Pointers : 1538888 -1000000 + Primary type : Decay + Nuclide ZAI : 561470 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 146.93525 + Atomic weight ratio (AWR) : 145.67300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.894 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.25000E+00 MeV frac = 1.00000E+00 Product nuclide = 571470 : beta- + + Nuclide 1190 / 1657 : 561480 -- barium 148 (Ba-148) + + Pointers : 1541205 -1000000 + Primary type : Decay + Nuclide ZAI : 561480 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 147.93786 + Atomic weight ratio (AWR) : 146.66700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.612 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 5.12000E+00 MeV frac = 9.96000E-01 Product nuclide = 571480 : beta- + 2 RTYP = 15 Q = 7.68704E-01 MeV frac = 4.00000E-03 Product nuclide = 571470 : beta- + neutron emission + + Nuclide 1191 / 1657 : 561490 -- barium 149 (Ba-149) + + Pointers : 1541462 -1000000 + Primary type : Decay + Nuclide ZAI : 561490 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 148.94250 + Atomic weight ratio (AWR) : 147.66300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.344 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 7.31000E+00 MeV frac = 9.95700E-01 Product nuclide = 571490 : beta- + 2 RTYP = 15 Q = 1.56870E+00 MeV frac = 4.30000E-03 Product nuclide = 571480 : beta- + neutron emission + + Nuclide 1192 / 1657 : 561500 -- barium 150 (Ba-150) + + Pointers : 1541719 -1000000 + Primary type : Decay + Nuclide ZAI : 561500 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 149.94612 + Atomic weight ratio (AWR) : 148.65800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.44000E+00 MeV frac = 1.00000E+00 Product nuclide = 571500 : beta- + + Nuclide 1193 / 1657 : 561510 -- barium 151 (Ba-151) + + Pointers : 1541903 -1000000 + Primary type : Decay + Nuclide ZAI : 561510 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 150.95075 + Atomic weight ratio (AWR) : 149.65400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.47000E+00 MeV frac = 1.00000E+00 Product nuclide = 571510 : beta- + + Nuclide 1194 / 1657 : 561520 -- barium 152 (Ba-152) + + Pointers : 1542087 -1000000 + Primary type : Decay + Nuclide ZAI : 561520 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 151.95437 + Atomic weight ratio (AWR) : 150.64900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 100 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.47000E+00 MeV frac = 1.00000E+00 Product nuclide = 571520 : beta- + + Nuclide 1195 / 1657 : 561530 -- barium 153 (Ba-153) + + Pointers : 1542271 -1000000 + Primary type : Decay + Nuclide ZAI : 561530 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 152.96001 + Atomic weight ratio (AWR) : 151.64600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 80 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.31000E+00 MeV frac = 1.00000E+00 Product nuclide = 571530 : beta- + + Nuclide 1196 / 1657 : 571360 -- lanthanum 136 (La-136) + + Pointers : 1542455 -1000000 + Primary type : Decay + Nuclide ZAI : 571360 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 135.90752 + Atomic weight ratio (AWR) : 134.74000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.92E+02 seconds (9.87 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 2.87000E+00 MeV frac = 1.00000E+00 Product nuclide = 56136.82c : EC/beta+ + + Nuclide 1197 / 1657 : 571361 -- lanthanum 136m (La-136m) + + Pointers : 1543064 -1000000 + Primary type : Decay + Nuclide ZAI : 571361 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 135.90752 + Atomic weight ratio (AWR) : 134.74000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.114 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 2.55000E-01 MeV frac = 1.00000E+00 Product nuclide = 571360 : IT + + Nuclide 1198 / 1657 : 571370 -- lanthanum 137 (La-137) + + Pointers : 1543248 -1000000 + Primary type : Decay + Nuclide ZAI : 571370 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 136.90610 + Atomic weight ratio (AWR) : 135.73000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.89E+12 seconds (60,041 years) + Specific ingestion toxicity : 8.10E-11 Sv/Bq + Specific inhalation toxicity : 8.70E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 5.97000E-01 MeV frac = 1.00000E+00 Product nuclide = 56137.82c : EC/beta+ + + Nuclide 1199 / 1657 : 571410 -- lanthanum 141 (La-141) + + Pointers : 1555355 -1000000 + Primary type : Decay + Nuclide ZAI : 571410 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 140.91050 + Atomic weight ratio (AWR) : 139.70000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.41E+04 seconds (3.92 hours) + Specific ingestion toxicity : 3.60E-10 Sv/Bq + Specific inhalation toxicity : 1.50E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.44600E+00 MeV frac = 1.00000E+00 Product nuclide = 58141.82c : beta- + + Nuclide 1200 / 1657 : 571420 -- lanthanum 142 (La-142) + + Pointers : 1556174 -1000000 + Primary type : Decay + Nuclide ZAI : 571420 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 141.91412 + Atomic weight ratio (AWR) : 140.69500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.47E+03 seconds (1.52 hours) + Specific ingestion toxicity : 1.80E-10 Sv/Bq + Specific inhalation toxicity : 8.90E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.50400E+00 MeV frac = 1.00000E+00 Product nuclide = 58142.82c : beta- + + Nuclide 1201 / 1657 : 571430 -- lanthanum 143 (La-143) + + Pointers : 1560241 -1000000 + Primary type : Decay + Nuclide ZAI : 571430 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 142.91572 + Atomic weight ratio (AWR) : 141.68800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.48E+02 seconds (14.1 minutes) + Specific ingestion toxicity : 5.60E-11 Sv/Bq + Specific inhalation toxicity : 2.10E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.29000E+00 MeV frac = 1.00000E+00 Product nuclide = 58143.82c : beta- + + Nuclide 1202 / 1657 : 571440 -- lanthanum 144 (La-144) + + Pointers : 1561816 -1000000 + Primary type : Decay + Nuclide ZAI : 571440 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 143.91934 + Atomic weight ratio (AWR) : 142.68300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 40.8 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.54100E+00 MeV frac = 1.00000E+00 Product nuclide = 58144.82c : beta- + + Nuclide 1203 / 1657 : 571450 -- lanthanum 145 (La-145) + + Pointers : 1565393 -1000000 + Primary type : Decay + Nuclide ZAI : 571450 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 144.92196 + Atomic weight ratio (AWR) : 143.67700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 24.8 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.12000E+00 MeV frac = 1.00000E+00 Product nuclide = 581450 : beta- + + Nuclide 1204 / 1657 : 571460 -- lanthanum 146 (La-146) + + Pointers : 1567374 -1000000 + Primary type : Decay + Nuclide ZAI : 571460 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 145.92558 + Atomic weight ratio (AWR) : 144.67200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.27 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.53000E+00 MeV frac = 1.00000E+00 Product nuclide = 581460 : beta- + + Nuclide 1205 / 1657 : 571461 -- lanthanum 146m (La-146m) + + Pointers : 1570993 -1000000 + Primary type : Decay + Nuclide ZAI : 571461 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 145.92558 + Atomic weight ratio (AWR) : 144.67200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 10 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.69000E+00 MeV frac = 1.00000E+00 Product nuclide = 581460 : beta- + + Nuclide 1206 / 1657 : 571470 -- lanthanum 147 (La-147) + + Pointers : 1571177 -1000000 + Primary type : Decay + Nuclide ZAI : 571470 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 146.92819 + Atomic weight ratio (AWR) : 145.66600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.06 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.18000E+00 MeV frac = 1.00000E+00 Product nuclide = 581470 : beta- + + Nuclide 1207 / 1657 : 571480 -- lanthanum 148 (La-148) + + Pointers : 1573200 -1000000 + Primary type : Decay + Nuclide ZAI : 571480 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 147.93181 + Atomic weight ratio (AWR) : 146.66100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.26 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.26000E+00 MeV frac = 1.00000E+00 Product nuclide = 581480 : beta- + + Nuclide 1208 / 1657 : 571490 -- lanthanum 149 (La-149) + + Pointers : 1574761 -1000000 + Primary type : Decay + Nuclide ZAI : 571490 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 148.93443 + Atomic weight ratio (AWR) : 147.65500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.05 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 5.90000E+00 MeV frac = 9.86000E-01 Product nuclide = 581490 : beta- + 2 RTYP = 15 Q = 1.51970E+00 MeV frac = 1.40000E-02 Product nuclide = 581480 : beta- + neutron emission + + Nuclide 1209 / 1657 : 571500 -- lanthanum 150 (La-150) + + Pointers : 1575018 -1000000 + Primary type : Decay + Nuclide ZAI : 571500 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 149.93906 + Atomic weight ratio (AWR) : 148.65100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.51 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 7.78000E+00 MeV frac = 9.73000E-01 Product nuclide = 581500 : beta- + 2 RTYP = 15 Q = 1.58870E+00 MeV frac = 2.70000E-02 Product nuclide = 581490 : beta- + neutron emission + + Nuclide 1210 / 1657 : 571510 -- lanthanum 151 (La-151) + + Pointers : 1575275 -1000000 + Primary type : Decay + Nuclide ZAI : 571510 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 150.94167 + Atomic weight ratio (AWR) : 149.64500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.21000E+00 MeV frac = 1.00000E+00 Product nuclide = 581510 : beta- + + Nuclide 1211 / 1657 : 571520 -- lanthanum 152 (La-152) + + Pointers : 1575459 -1000000 + Primary type : Decay + Nuclide ZAI : 571520 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 151.94428 + Atomic weight ratio (AWR) : 150.63900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.28 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.82000E+00 MeV frac = 9.39610E-01 Product nuclide = 581520 : beta- + 2 RTYP = 15 Q = 3.98900E+00 MeV frac = 6.03930E-02 Product nuclide = 581510 : beta- + neutron emission + + Nuclide 1212 / 1657 : 571530 -- lanthanum 153 (La-153) + + Pointers : 1582138 -1000000 + Primary type : Decay + Nuclide ZAI : 571530 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 152.94992 + Atomic weight ratio (AWR) : 151.63600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.15 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.42000E+00 MeV frac = 1.00000E+00 Product nuclide = 581530 : beta- + + Nuclide 1213 / 1657 : 571540 -- lanthanum 154 (La-154) + + Pointers : 1582322 -1000000 + Primary type : Decay + Nuclide ZAI : 571540 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 153.95455 + Atomic weight ratio (AWR) : 152.63200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 100 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.03200E+01 MeV frac = 1.00000E+00 Product nuclide = 581540 : beta- + + Nuclide 1214 / 1657 : 571550 -- lanthanum 155 (La-155) + + Pointers : 1582506 -1000000 + Primary type : Decay + Nuclide ZAI : 571550 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 154.95817 + Atomic weight ratio (AWR) : 153.62700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 60 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 581550 : beta- + + Nuclide 1215 / 1657 : 581380 -- cerium 138 (Ce-138) + + Pointers : 1582690 -1000000 + Primary type : Decay + Nuclide ZAI : 581380 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 137.90568 + Atomic weight ratio (AWR) : 136.72100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1216 / 1657 : 581381 -- cerium 138m (Ce-138m) + + Pointers : 1582796 -1000000 + Primary type : Decay + Nuclide ZAI : 581381 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 137.90568 + Atomic weight ratio (AWR) : 136.72100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.65 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 2.12917E+00 MeV frac = 1.00000E+00 Product nuclide = 581380 : IT + + Nuclide 1217 / 1657 : 581390 -- cerium 139 (Ce-139) + + Pointers : 1582980 -1000000 + Primary type : Decay + Nuclide ZAI : 581390 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 138.90628 + Atomic weight ratio (AWR) : 137.71300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.19E+07 seconds (138 days) + Specific ingestion toxicity : 2.60E-10 Sv/Bq + Specific inhalation toxicity : 1.90E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 2.77000E-01 MeV frac = 1.00000E+00 Product nuclide = 57139.82c : EC/beta+ + + Nuclide 1218 / 1657 : 581391 -- cerium 139m (Ce-139m) + + Pointers : 1583379 -1000000 + Primary type : Decay + Nuclide ZAI : 581391 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 138.90628 + Atomic weight ratio (AWR) : 137.71300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 56.1 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 7.54240E-01 MeV frac = 1.00000E+00 Product nuclide = 581390 : IT + + Nuclide 1219 / 1657 : 581450 -- cerium 145 (Ce-145) + + Pointers : 1599324 -1000000 + Primary type : Decay + Nuclide ZAI : 581450 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 144.91691 + Atomic weight ratio (AWR) : 143.67200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.77E+02 seconds (2.95 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.53500E+00 MeV frac = 1.00000E+00 Product nuclide = 591450 : beta- + + Nuclide 1220 / 1657 : 581460 -- cerium 146 (Ce-146) + + Pointers : 1603307 -1000000 + Primary type : Decay + Nuclide ZAI : 581460 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 145.91852 + Atomic weight ratio (AWR) : 144.66500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.11E+02 seconds (13.5 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.03001E+00 MeV frac = 1.00000E+00 Product nuclide = 591460 : beta- + + Nuclide 1221 / 1657 : 581470 -- cerium 147 (Ce-147) + + Pointers : 1603491 -1000000 + Primary type : Decay + Nuclide ZAI : 581470 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 146.92214 + Atomic weight ratio (AWR) : 145.66000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 57 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.29000E+00 MeV frac = 1.00000E+00 Product nuclide = 591470 : beta- + + Nuclide 1222 / 1657 : 581480 -- cerium 148 (Ce-148) + + Pointers : 1606830 -1000000 + Primary type : Decay + Nuclide ZAI : 581480 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 147.92475 + Atomic weight ratio (AWR) : 146.65400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 56 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.14000E+00 MeV frac = 1.00000E+00 Product nuclide = 591480 : beta- + + Nuclide 1223 / 1657 : 581490 -- cerium 149 (Ce-149) + + Pointers : 1607014 -1000000 + Primary type : Decay + Nuclide ZAI : 581490 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 148.92837 + Atomic weight ratio (AWR) : 147.64900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.36000E+00 MeV frac = 1.00000E+00 Product nuclide = 591490 : beta- + + Nuclide 1224 / 1657 : 581500 -- cerium 150 (Ce-150) + + Pointers : 1608575 -1000000 + Primary type : Decay + Nuclide ZAI : 581500 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 149.92998 + Atomic weight ratio (AWR) : 148.64200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.48400E+00 MeV frac = 1.00000E+00 Product nuclide = 591500 : beta- + + Nuclide 1225 / 1657 : 581510 -- cerium 151 (Ce-151) + + Pointers : 1608759 -1000000 + Primary type : Decay + Nuclide ZAI : 581510 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 150.93360 + Atomic weight ratio (AWR) : 149.63700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.02 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.27100E+00 MeV frac = 1.00000E+00 Product nuclide = 591510 : beta- + + Nuclide 1226 / 1657 : 581520 -- cerium 152 (Ce-152) + + Pointers : 1608943 -1000000 + Primary type : Decay + Nuclide ZAI : 581520 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 151.93621 + Atomic weight ratio (AWR) : 150.63100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.1 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.70000E+00 MeV frac = 1.00000E+00 Product nuclide = 591520 : beta- + + Nuclide 1227 / 1657 : 581530 -- cerium 153 (Ce-153) + + Pointers : 1609127 -1000000 + Primary type : Decay + Nuclide ZAI : 581530 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 152.93883 + Atomic weight ratio (AWR) : 151.62500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 5.83900E+00 MeV frac = 9.93780E-01 Product nuclide = 591530 : beta- + 2 RTYP = 15 Q = 1.63600E+00 MeV frac = 6.21900E-03 Product nuclide = 591520 : beta- + neutron emission + + Nuclide 1228 / 1657 : 581540 -- cerium 154 (Ce-154) + + Pointers : 1613310 -1000000 + Primary type : Decay + Nuclide ZAI : 581540 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 153.94043 + Atomic weight ratio (AWR) : 152.61800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 5.02000E+00 MeV frac = 9.93630E-01 Product nuclide = 591540 : beta- + 2 RTYP = 15 Q = 1.65900E+00 MeV frac = 6.37300E-03 Product nuclide = 591530 : beta- + neutron emission + + Nuclide 1229 / 1657 : 581550 -- cerium 155 (Ce-155) + + Pointers : 1617010 -1000000 + Primary type : Decay + Nuclide ZAI : 581550 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 154.94809 + Atomic weight ratio (AWR) : 153.61700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.38000E+00 MeV frac = 1.00000E+00 Product nuclide = 591550 : beta- + + Nuclide 1230 / 1657 : 581560 -- cerium 156 (Ce-156) + + Pointers : 1617194 -1000000 + Primary type : Decay + Nuclide ZAI : 581560 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 155.95171 + Atomic weight ratio (AWR) : 154.61200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.15 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.51000E+00 MeV frac = 1.00000E+00 Product nuclide = 591560 : beta- + + Nuclide 1231 / 1657 : 581570 -- cerium 157 (Ce-157) + + Pointers : 1617378 -1000000 + Primary type : Decay + Nuclide ZAI : 581570 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 156.95634 + Atomic weight ratio (AWR) : 155.60800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 50 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.30000E+00 MeV frac = 1.00000E+00 Product nuclide = 591570 : beta- + + Nuclide 1232 / 1657 : 591390 -- praseodymium 139 (Pr-139) + + Pointers : 1617562 -1000000 + Primary type : Decay + Nuclide ZAI : 591390 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 138.90930 + Atomic weight ratio (AWR) : 137.71600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.59E+04 seconds (4.41 hours) + Specific ingestion toxicity : 3.10E-11 Sv/Bq + Specific inhalation toxicity : 2.00E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 2.12900E+00 MeV frac = 9.99836E-01 Product nuclide = 581390 : EC/beta+ + 2 RTYP = 2 Q = 1.37476E+00 MeV frac = 1.63980E-04 Product nuclide = 581391 : EC/beta+ + + Nuclide 1233 / 1657 : 591400 -- praseodymium 140 (Pr-140) + + Pointers : 1618496 -1000000 + Primary type : Decay + Nuclide ZAI : 591400 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 139.90889 + Atomic weight ratio (AWR) : 138.70700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.03E+02 seconds (3.39 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 3.38800E+00 MeV frac = 1.00000E+00 Product nuclide = 58140.82c : EC/beta+ + + Nuclide 1234 / 1657 : 591421 -- praseodymium 142m (Pr-142m) + + Pointers : 1626194 -1000000 + Primary type : Decay + Nuclide ZAI : 591421 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 141.91008 + Atomic weight ratio (AWR) : 140.69100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.76E+02 seconds (14.6 minutes) + Specific ingestion toxicity : 1.70E-11 Sv/Bq + Specific inhalation toxicity : 7.00E-12 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 3.69400E-03 MeV frac = 1.00000E+00 Product nuclide = 59142.82c : IT + + Nuclide 1235 / 1657 : 591440 -- praseodymium 144 (Pr-144) + + Pointers : 1629691 -1000000 + Primary type : Decay + Nuclide ZAI : 591440 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 143.91329 + Atomic weight ratio (AWR) : 142.67700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.04E+03 seconds (17.3 minutes) + Specific ingestion toxicity : 5.00E-11 Sv/Bq + Specific inhalation toxicity : 1.80E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.99740E+00 MeV frac = 1.00000E+00 Product nuclide = 60144.82c : beta- + + Nuclide 1236 / 1657 : 591441 -- praseodymium 144m (Pr-144m) + + Pointers : 1631266 -1000000 + Primary type : Decay + Nuclide ZAI : 591441 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 143.91329 + Atomic weight ratio (AWR) : 142.67700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.32E+02 seconds (7.2 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 5.90300E-02 MeV frac = 9.99400E-01 Product nuclide = 591440 : IT + 2 RTYP = 1 Q = 3.05643E+00 MeV frac = 6.00000E-04 Product nuclide = 60144.82c : beta- + + Nuclide 1237 / 1657 : 591450 -- praseodymium 145 (Pr-145) + + Pointers : 1632130 -1000000 + Primary type : Decay + Nuclide ZAI : 591450 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 144.91490 + Atomic weight ratio (AWR) : 143.67000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.15E+04 seconds (5.98 hours) + Specific ingestion toxicity : 3.90E-10 Sv/Bq + Specific inhalation toxicity : 1.70E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.80510E+00 MeV frac = 1.00000E+00 Product nuclide = 60145.82c : beta- + + Nuclide 1238 / 1657 : 591460 -- praseodymium 146 (Pr-146) + + Pointers : 1632314 -1000000 + Primary type : Decay + Nuclide ZAI : 591460 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 145.91751 + Atomic weight ratio (AWR) : 144.66400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.45E+03 seconds (24.1 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.16900E+00 MeV frac = 1.00000E+00 Product nuclide = 60146.82c : beta- + + Nuclide 1239 / 1657 : 591470 -- praseodymium 147 (Pr-147) + + Pointers : 1634323 -1000000 + Primary type : Decay + Nuclide ZAI : 591470 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 146.91911 + Atomic weight ratio (AWR) : 145.65700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.04E+02 seconds (13.4 minutes) + Specific ingestion toxicity : 3.30E-11 Sv/Bq + Specific inhalation toxicity : 1.80E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.69690E+00 MeV frac = 1.00000E+00 Product nuclide = 60147.82c : beta- + + Nuclide 1240 / 1657 : 591480 -- praseodymium 148 (Pr-148) + + Pointers : 1634507 -1000000 + Primary type : Decay + Nuclide ZAI : 591480 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 147.92173 + Atomic weight ratio (AWR) : 146.65100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.37E+02 seconds (2.29 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.93000E+00 MeV frac = 1.00000E+00 Product nuclide = 60148.82c : beta- + + Nuclide 1241 / 1657 : 591481 -- praseodymium 148m (Pr-148m) + + Pointers : 1635942 -1000000 + Primary type : Decay + Nuclide ZAI : 591481 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 147.92173 + Atomic weight ratio (AWR) : 146.65100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.21E+02 seconds (2.02 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.05000E+00 MeV frac = 1.00000E+00 Product nuclide = 60148.82c : beta- + + Nuclide 1242 / 1657 : 591490 -- praseodymium 149 (Pr-149) + + Pointers : 1636327 -1000000 + Primary type : Decay + Nuclide ZAI : 591490 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 148.92333 + Atomic weight ratio (AWR) : 147.64400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.36E+02 seconds (2.26 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.39700E+00 MeV frac = 1.00000E+00 Product nuclide = 601490 : beta- + + Nuclide 1243 / 1657 : 591500 -- praseodymium 150 (Pr-150) + + Pointers : 1639064 -1000000 + Primary type : Decay + Nuclide ZAI : 591500 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 149.92695 + Atomic weight ratio (AWR) : 148.63900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.1 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.69000E+00 MeV frac = 1.00000E+00 Product nuclide = 60150.82c : beta- + + Nuclide 1244 / 1657 : 591510 -- praseodymium 151 (Pr-151) + + Pointers : 1641311 -1000000 + Primary type : Decay + Nuclide ZAI : 591510 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 150.92856 + Atomic weight ratio (AWR) : 149.63200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 18.9 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.18200E+00 MeV frac = 1.00000E+00 Product nuclide = 601510 : beta- + + Nuclide 1245 / 1657 : 591520 -- praseodymium 152 (Pr-152) + + Pointers : 1641495 -1000000 + Primary type : Decay + Nuclide ZAI : 591520 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 151.93117 + Atomic weight ratio (AWR) : 150.62600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.63 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.44000E+00 MeV frac = 1.00000E+00 Product nuclide = 601520 : beta- + + Nuclide 1246 / 1657 : 591530 -- praseodymium 153 (Pr-153) + + Pointers : 1644078 -1000000 + Primary type : Decay + Nuclide ZAI : 591530 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 152.93378 + Atomic weight ratio (AWR) : 151.62000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.28 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.71901E+00 MeV frac = 1.00000E+00 Product nuclide = 601530 : beta- + + Nuclide 1247 / 1657 : 591540 -- praseodymium 154 (Pr-154) + + Pointers : 1644262 -1000000 + Primary type : Decay + Nuclide ZAI : 591540 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 153.93740 + Atomic weight ratio (AWR) : 152.61500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.49000E+00 MeV frac = 1.00000E+00 Product nuclide = 601540 : beta- + + Nuclide 1248 / 1657 : 591550 -- praseodymium 155 (Pr-155) + + Pointers : 1644446 -1000000 + Primary type : Decay + Nuclide ZAI : 591550 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 154.94002 + Atomic weight ratio (AWR) : 153.60900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.69000E+00 MeV frac = 1.00000E+00 Product nuclide = 601550 : beta- + + Nuclide 1249 / 1657 : 591560 -- praseodymium 156 (Pr-156) + + Pointers : 1644630 -1000000 + Primary type : Decay + Nuclide ZAI : 591560 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 155.94263 + Atomic weight ratio (AWR) : 154.60300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.70600E+00 MeV frac = 9.72830E-01 Product nuclide = 601560 : beta- + 2 RTYP = 15 Q = 2.80900E+00 MeV frac = 2.71700E-02 Product nuclide = 601550 : beta- + neutron emission + + Nuclide 1250 / 1657 : 591570 -- praseodymium 157 (Pr-157) + + Pointers : 1650886 -1000000 + Primary type : Decay + Nuclide ZAI : 591570 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 156.94524 + Atomic weight ratio (AWR) : 155.59700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 8.14700E+00 MeV frac = 9.36130E-01 Product nuclide = 601570 : beta- + 2 RTYP = 15 Q = 3.60900E+00 MeV frac = 6.38740E-02 Product nuclide = 601560 : beta- + neutron emission + + Nuclide 1251 / 1657 : 591580 -- praseodymium 158 (Pr-158) + + Pointers : 1657046 -1000000 + Primary type : Decay + Nuclide ZAI : 591580 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 157.95189 + Atomic weight ratio (AWR) : 156.59500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.67000E+00 MeV frac = 1.00000E+00 Product nuclide = 601580 : beta- + + Nuclide 1252 / 1657 : 591590 -- praseodymium 159 (Pr-159) + + Pointers : 1657230 -1000000 + Primary type : Decay + Nuclide ZAI : 591590 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 158.95551 + Atomic weight ratio (AWR) : 157.59000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 100 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.77000E+00 MeV frac = 1.00000E+00 Product nuclide = 601590 : beta- + + Nuclide 1253 / 1657 : 601420 -- neodymium 142 (Nd-142) + + Pointers : 1657414 -1000000 + Primary type : Decay + Nuclide ZAI : 601420 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 141.90807 + Atomic weight ratio (AWR) : 140.68900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1254 / 1657 : 601430 -- neodymium 143 (Nd-143) + + Pointers : 1657520 -1000000 + Primary type : Decay + Nuclide ZAI : 601430 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 142.90967 + Atomic weight ratio (AWR) : 141.68200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1255 / 1657 : 601490 -- neodymium 149 (Nd-149) + + Pointers : 1680327 -1000000 + Primary type : Decay + Nuclide ZAI : 601490 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 148.92030 + Atomic weight ratio (AWR) : 147.64100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.22E+03 seconds (1.73 hours) + Specific ingestion toxicity : 1.20E-10 Sv/Bq + Specific inhalation toxicity : 8.90E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.69100E+00 MeV frac = 1.00000E+00 Product nuclide = 61149.82c : beta- + + Nuclide 1256 / 1657 : 601510 -- neodymium 151 (Nd-151) + + Pointers : 1690163 -1000000 + Primary type : Decay + Nuclide ZAI : 601510 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 150.92351 + Atomic weight ratio (AWR) : 149.62700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.46E+02 seconds (12.4 minutes) + Specific ingestion toxicity : 3.00E-11 Sv/Bq + Specific inhalation toxicity : 1.70E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.44200E+00 MeV frac = 1.00000E+00 Product nuclide = 61151.82c : beta- + + Nuclide 1257 / 1657 : 601520 -- neodymium 152 (Nd-152) + + Pointers : 1700656 -1000000 + Primary type : Decay + Nuclide ZAI : 601520 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 151.92512 + Atomic weight ratio (AWR) : 150.62000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.84E+02 seconds (11.4 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.10400E+00 MeV frac = 1.00000E+00 Product nuclide = 611520 : beta- + + Nuclide 1258 / 1657 : 601530 -- neodymium 153 (Nd-153) + + Pointers : 1700840 -1000000 + Primary type : Decay + Nuclide ZAI : 601530 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 152.92773 + Atomic weight ratio (AWR) : 151.61400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 31.6 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.33600E+00 MeV frac = 1.00000E+00 Product nuclide = 611530 : beta- + + Nuclide 1259 / 1657 : 601540 -- neodymium 154 (Nd-154) + + Pointers : 1701024 -1000000 + Primary type : Decay + Nuclide ZAI : 601540 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 153.92933 + Atomic weight ratio (AWR) : 152.60700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 25.9 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.81000E+00 MeV frac = 1.00000E+00 Product nuclide = 611540 : beta- + + Nuclide 1260 / 1657 : 601550 -- neodymium 155 (Nd-155) + + Pointers : 1701208 -1000000 + Primary type : Decay + Nuclide ZAI : 601550 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 154.93296 + Atomic weight ratio (AWR) : 153.60200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.9 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 611550 : beta- + + Nuclide 1261 / 1657 : 601560 -- neodymium 156 (Nd-156) + + Pointers : 1701392 -1000000 + Primary type : Decay + Nuclide ZAI : 601560 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 155.93456 + Atomic weight ratio (AWR) : 154.59500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.49 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.69000E+00 MeV frac = 1.00000E+00 Product nuclide = 611560 : beta- + + Nuclide 1262 / 1657 : 601570 -- neodymium 157 (Nd-157) + + Pointers : 1701576 -1000000 + Primary type : Decay + Nuclide ZAI : 601570 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 156.93717 + Atomic weight ratio (AWR) : 155.58900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.57000E+00 MeV frac = 1.00000E+00 Product nuclide = 611570 : beta- + + Nuclide 1263 / 1657 : 601580 -- neodymium 158 (Nd-158) + + Pointers : 1705004 -1000000 + Primary type : Decay + Nuclide ZAI : 601580 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 157.93979 + Atomic weight ratio (AWR) : 156.58300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.7 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 5.01100E+00 MeV frac = 9.99950E-01 Product nuclide = 611580 : beta- + 2 RTYP = 15 Q = 3.39000E-01 MeV frac = 5.30000E-05 Product nuclide = 611570 : beta- + neutron emission + + Nuclide 1264 / 1657 : 601590 -- neodymium 159 (Nd-159) + + Pointers : 1708305 -1000000 + Primary type : Decay + Nuclide ZAI : 601590 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 158.94442 + Atomic weight ratio (AWR) : 157.57900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 7.16600E+00 MeV frac = 9.97640E-01 Product nuclide = 611590 : beta- + 2 RTYP = 15 Q = 1.24900E+00 MeV frac = 2.36100E-03 Product nuclide = 611580 : beta- + neutron emission + + Nuclide 1265 / 1657 : 601600 -- neodymium 160 (Nd-160) + + Pointers : 1713169 -1000000 + Primary type : Decay + Nuclide ZAI : 601600 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 159.94703 + Atomic weight ratio (AWR) : 158.57300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 6.36500E+00 MeV frac = 9.90530E-01 Product nuclide = 611600 : beta- + 2 RTYP = 15 Q = 1.84900E+00 MeV frac = 9.46900E-03 Product nuclide = 611590 : beta- + neutron emission + + Nuclide 1266 / 1657 : 601610 -- neodymium 161 (Nd-161) + + Pointers : 1717733 -1000000 + Primary type : Decay + Nuclide ZAI : 601610 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 160.95368 + Atomic weight ratio (AWR) : 159.57100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.47000E+00 MeV frac = 1.00000E+00 Product nuclide = 611610 : beta- + + Nuclide 1267 / 1657 : 611450 -- promethium 145 (Pm-145) + + Pointers : 1717917 -1000000 + Primary type : Decay + Nuclide ZAI : 611450 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 144.91288 + Atomic weight ratio (AWR) : 143.66800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.59E+08 seconds (17.7 years) + Specific ingestion toxicity : 1.10E-10 Sv/Bq + Specific inhalation toxicity : 3.60E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 1.61400E-01 MeV frac = 1.00000E+00 Product nuclide = 60145.82c : EC/beta+ + 2 RTYP = 4 Q = 2.32200E+00 MeV frac = 2.80000E-09 Product nuclide = 59141.82c : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 2.32200E+00 MeV frac = 2.80000E-09 Product nuclide = 2004.82c : alpha + + Nuclide 1268 / 1657 : 611460 -- promethium 146 (Pm-146) + + Pointers : 1718546 -1000000 + Primary type : Decay + Nuclide ZAI : 611460 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 145.91448 + Atomic weight ratio (AWR) : 144.66100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.75E+08 seconds (5.53 years) + Specific ingestion toxicity : 9.00E-10 Sv/Bq + Specific inhalation toxicity : 2.10E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.54200E+00 MeV frac = 3.40000E-01 Product nuclide = 621460 : beta- + 2 RTYP = 2 Q = 1.48200E+00 MeV frac = 6.60000E-01 Product nuclide = 60146.82c : EC/beta+ + + Nuclide 1269 / 1657 : 611500 -- promethium 150 (Pm-150) + + Pointers : 1735699 -1000000 + Primary type : Decay + Nuclide ZAI : 611500 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 149.92090 + Atomic weight ratio (AWR) : 148.63300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.71E+03 seconds (2.7 hours) + Specific ingestion toxicity : 2.60E-10 Sv/Bq + Specific inhalation toxicity : 1.30E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.45400E+00 MeV frac = 1.00000E+00 Product nuclide = 62150.82c : beta- + + Nuclide 1270 / 1657 : 611520 -- promethium 152 (Pm-152) + + Pointers : 1752755 -1000000 + Primary type : Decay + Nuclide ZAI : 611520 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 151.92310 + Atomic weight ratio (AWR) : 150.61800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.47E+02 seconds (4.12 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 62152.82c : beta- + + Nuclide 1271 / 1657 : 611521 -- promethium 152m (Pm-152m) + + Pointers : 1755394 -1000000 + Primary type : Decay + Nuclide ZAI : 611521 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 151.92310 + Atomic weight ratio (AWR) : 150.61800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.51E+02 seconds (7.52 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.65000E+00 MeV frac = 1.00000E+00 Product nuclide = 62152.82c : beta- + + Nuclide 1272 / 1657 : 611522 -- promethium 152m (Pm-152m) + + Pointers : 3512934 -1000000 + Primary type : Decay + Nuclide ZAI : 611522 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 151.92310 + Atomic weight ratio (AWR) : 150.61800 + Temperature : 900.0 Kelvin + XS temperature : -1.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.64E+02 seconds (14.4 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is not present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.82500E+00 MeV frac = 1.00000E+00 Product nuclide = 62152.82c : beta- + + Nuclide 1273 / 1657 : 611530 -- promethium 153 (Pm-153) + + Pointers : 1757151 -1000000 + Primary type : Decay + Nuclide ZAI : 611530 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 152.92370 + Atomic weight ratio (AWR) : 151.61000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.15E+02 seconds (5.25 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.88100E+00 MeV frac = 1.00000E+00 Product nuclide = 62153.82c : beta- + + Nuclide 1274 / 1657 : 611540 -- promethium 154 (Pm-154) + + Pointers : 1759230 -1000000 + Primary type : Decay + Nuclide ZAI : 611540 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 153.92631 + Atomic weight ratio (AWR) : 152.60400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.04E+02 seconds (1.73 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.96160E+00 MeV frac = 1.00000E+00 Product nuclide = 62154.82c : beta- + + Nuclide 1275 / 1657 : 611541 -- promethium 154m (Pm-154m) + + Pointers : 1759414 -1000000 + Primary type : Decay + Nuclide ZAI : 611541 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 153.92631 + Atomic weight ratio (AWR) : 152.60400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.61E+02 seconds (2.68 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.01160E+00 MeV frac = 1.00000E+00 Product nuclide = 62154.82c : beta- + + Nuclide 1276 / 1657 : 611550 -- promethium 155 (Pm-155) + + Pointers : 1759598 -1000000 + Primary type : Decay + Nuclide ZAI : 611550 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 154.92791 + Atomic weight ratio (AWR) : 153.59700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 41.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.22000E+00 MeV frac = 1.00000E+00 Product nuclide = 621550 : beta- + + Nuclide 1277 / 1657 : 611560 -- promethium 156 (Pm-156) + + Pointers : 1760739 -1000000 + Primary type : Decay + Nuclide ZAI : 611560 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 155.93153 + Atomic weight ratio (AWR) : 154.59200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 26.7 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.15000E+00 MeV frac = 1.00000E+00 Product nuclide = 621560 : beta- + + Nuclide 1278 / 1657 : 611570 -- promethium 157 (Pm-157) + + Pointers : 1760923 -1000000 + Primary type : Decay + Nuclide ZAI : 611570 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 156.93314 + Atomic weight ratio (AWR) : 155.58500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 10.6 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.36000E+00 MeV frac = 1.00000E+00 Product nuclide = 621570 : beta- + + Nuclide 1279 / 1657 : 611580 -- promethium 158 (Pm-158) + + Pointers : 1761107 -1000000 + Primary type : Decay + Nuclide ZAI : 611580 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 157.93676 + Atomic weight ratio (AWR) : 156.58000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.8 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.12000E+00 MeV frac = 1.00000E+00 Product nuclide = 621580 : beta- + + Nuclide 1280 / 1657 : 611590 -- promethium 159 (Pm-159) + + Pointers : 1761291 -1000000 + Primary type : Decay + Nuclide ZAI : 611590 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 158.93836 + Atomic weight ratio (AWR) : 157.57300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 5.66400E+00 MeV frac = 9.99820E-01 Product nuclide = 621590 : beta- + 2 RTYP = 15 Q = 4.19000E-01 MeV frac = 1.85000E-04 Product nuclide = 621580 : beta- + neutron emission + + Nuclide 1281 / 1657 : 611600 -- promethium 160 (Pm-160) + + Pointers : 1765006 -1000000 + Primary type : Decay + Nuclide ZAI : 611600 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 159.94199 + Atomic weight ratio (AWR) : 158.56800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 7.81900E+00 MeV frac = 9.97320E-01 Product nuclide = 621600 : beta- + 2 RTYP = 15 Q = 1.14900E+00 MeV frac = 2.67600E-03 Product nuclide = 621590 : beta- + neutron emission + + Nuclide 1282 / 1657 : 611610 -- promethium 161 (Pm-161) + + Pointers : 1770230 -1000000 + Primary type : Decay + Nuclide ZAI : 611610 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 160.94561 + Atomic weight ratio (AWR) : 159.56300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.7 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.55000E+00 MeV frac = 1.00000E+00 Product nuclide = 621610 : beta- + + Nuclide 1283 / 1657 : 611620 -- promethium 162 (Pm-162) + + Pointers : 1770414 -1000000 + Primary type : Decay + Nuclide ZAI : 611620 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 161.95024 + Atomic weight ratio (AWR) : 160.55900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.44000E+00 MeV frac = 1.00000E+00 Product nuclide = 621620 : beta- + + Nuclide 1284 / 1657 : 611630 -- promethium 163 (Pm-163) + + Pointers : 1770598 -1000000 + Primary type : Decay + Nuclide ZAI : 611630 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 162.95386 + Atomic weight ratio (AWR) : 161.55400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.75000E+00 MeV frac = 1.00000E+00 Product nuclide = 621630 : beta- + + Nuclide 1285 / 1657 : 621460 -- samarium 146 (Sm-146) + + Pointers : 1770782 -1000000 + Primary type : Decay + Nuclide ZAI : 621460 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 145.91347 + Atomic weight ratio (AWR) : 144.66000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.16E+15 seconds (100 million years) + Specific ingestion toxicity : 5.40E-08 Sv/Bq + Specific inhalation toxicity : 1.10E-05 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 4 Q = 2.57000E+00 MeV frac = 1.00000E+00 Product nuclide = 601420 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 2.57000E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 1286 / 1657 : 621531 -- samarium 153m (Sm-153m) + + Pointers : 1800130 -1000000 + Primary type : Decay + Nuclide ZAI : 621531 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 152.92168 + Atomic weight ratio (AWR) : 151.60800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 10.6 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 9.83700E-02 MeV frac = 1.00000E+00 Product nuclide = 62153.82c : IT + + Nuclide 1287 / 1657 : 621550 -- samarium 155 (Sm-155) + + Pointers : 1805024 -1000000 + Primary type : Decay + Nuclide ZAI : 621550 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 154.92489 + Atomic weight ratio (AWR) : 153.59400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.34E+03 seconds (22.3 minutes) + Specific ingestion toxicity : 2.90E-11 Sv/Bq + Specific inhalation toxicity : 1.70E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.62720E+00 MeV frac = 1.00000E+00 Product nuclide = 63155.82c : beta- + + Nuclide 1288 / 1657 : 621560 -- samarium 156 (Sm-156) + + Pointers : 1806935 -1000000 + Primary type : Decay + Nuclide ZAI : 621560 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 155.92548 + Atomic weight ratio (AWR) : 154.58600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.38E+04 seconds (9.4 hours) + Specific ingestion toxicity : 2.50E-10 Sv/Bq + Specific inhalation toxicity : 2.20E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.22000E-01 MeV frac = 1.00000E+00 Product nuclide = 63156.82c : beta- + + Nuclide 1289 / 1657 : 621570 -- samarium 157 (Sm-157) + + Pointers : 1807922 -1000000 + Primary type : Decay + Nuclide ZAI : 621570 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 156.92810 + Atomic weight ratio (AWR) : 155.58000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.82E+02 seconds (8.03 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.73700E+00 MeV frac = 1.00000E+00 Product nuclide = 63157.82c : beta- + + Nuclide 1290 / 1657 : 621580 -- samarium 158 (Sm-158) + + Pointers : 1808106 -1000000 + Primary type : Decay + Nuclide ZAI : 621580 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 157.92970 + Atomic weight ratio (AWR) : 156.57300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.18E+02 seconds (5.3 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 631580 : beta- + + Nuclide 1291 / 1657 : 621590 -- samarium 159 (Sm-159) + + Pointers : 1808290 -1000000 + Primary type : Decay + Nuclide ZAI : 621590 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 158.93332 + Atomic weight ratio (AWR) : 157.56800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 11.4 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.80500E+00 MeV frac = 1.00000E+00 Product nuclide = 631590 : beta- + + Nuclide 1292 / 1657 : 621600 -- samarium 160 (Sm-160) + + Pointers : 1809809 -1000000 + Primary type : Decay + Nuclide ZAI : 621600 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 159.93493 + Atomic weight ratio (AWR) : 158.56100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.6 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.95000E+00 MeV frac = 1.00000E+00 Product nuclide = 631600 : beta- + + Nuclide 1293 / 1657 : 621610 -- samarium 161 (Sm-161) + + Pointers : 1809993 -1000000 + Primary type : Decay + Nuclide ZAI : 621610 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 160.93855 + Atomic weight ratio (AWR) : 159.55600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.8 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.80000E+00 MeV frac = 1.00000E+00 Product nuclide = 631610 : beta- + + Nuclide 1294 / 1657 : 621620 -- samarium 162 (Sm-162) + + Pointers : 1810177 -1000000 + Primary type : Decay + Nuclide ZAI : 621620 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 161.94116 + Atomic weight ratio (AWR) : 160.55000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.4 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.90000E+00 MeV frac = 1.00000E+00 Product nuclide = 631620 : beta- + + Nuclide 1295 / 1657 : 621630 -- samarium 163 (Sm-163) + + Pointers : 1810361 -1000000 + Primary type : Decay + Nuclide ZAI : 621630 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 162.94579 + Atomic weight ratio (AWR) : 161.54600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.73000E+00 MeV frac = 1.00000E+00 Product nuclide = 631630 : beta- + + Nuclide 1296 / 1657 : 621640 -- samarium 164 (Sm-164) + + Pointers : 1810545 -1000000 + Primary type : Decay + Nuclide ZAI : 621640 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 163.94840 + Atomic weight ratio (AWR) : 162.54000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.92000E+00 MeV frac = 1.00000E+00 Product nuclide = 631640 : beta- + + Nuclide 1297 / 1657 : 621650 -- samarium 165 (Sm-165) + + Pointers : 1810729 -1000000 + Primary type : Decay + Nuclide ZAI : 621650 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 164.95303 + Atomic weight ratio (AWR) : 163.53600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.76000E+00 MeV frac = 1.00000E+00 Product nuclide = 631650 : beta- + + Nuclide 1298 / 1657 : 631490 -- europium 149 (Eu-149) + + Pointers : 1810913 -1000000 + Primary type : Decay + Nuclide ZAI : 631490 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 148.91829 + Atomic weight ratio (AWR) : 147.63900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.04E+06 seconds (93.1 days) + Specific ingestion toxicity : 1.00E-10 Sv/Bq + Specific inhalation toxicity : 2.90E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 6.95000E-01 MeV frac = 1.00000E+00 Product nuclide = 62149.82c : EC/beta+ + + Nuclide 1299 / 1657 : 631500 -- europium 150 (Eu-150) + + Pointers : 1812670 -1000000 + Primary type : Decay + Nuclide ZAI : 631500 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 149.91989 + Atomic weight ratio (AWR) : 148.63200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.15E+09 seconds (36.4 years) + Specific ingestion toxicity : 1.30E-09 Sv/Bq + Specific inhalation toxicity : 5.30E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 2.29500E+00 MeV frac = 1.00000E+00 Product nuclide = 62150.82c : EC/beta+ + + Nuclide 1300 / 1657 : 631521 -- europium 152m (Eu-152m) + + Pointers : 1833374 -1000000 + Primary type : Decay + Nuclide ZAI : 631521 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 151.92209 + Atomic weight ratio (AWR) : 150.61700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.34E+04 seconds (9.27 hours) + Specific ingestion toxicity : 5.00E-10 Sv/Bq + Specific inhalation toxicity : 2.20E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.86770E+00 MeV frac = 7.20000E-01 Product nuclide = 64152.82c : beta- + 2 RTYP = 2 Q = 1.92170E+00 MeV frac = 2.80000E-01 Product nuclide = 62152.82c : EC/beta+ + + Nuclide 1301 / 1657 : 631522 -- europium 152m (Eu-152m) + + Pointers : 3516175 -1000000 + Primary type : Decay + Nuclide ZAI : 631522 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 151.92209 + Atomic weight ratio (AWR) : 150.61700 + Temperature : 900.0 Kelvin + XS temperature : -1.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.76E+03 seconds (1.6 hours) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is not present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.47800E-01 MeV frac = 1.00000E+00 Product nuclide = 63152.82c : IT + + Nuclide 1302 / 1657 : 631541 -- europium 154m (Eu-154m) + + Pointers : 1844134 -1000000 + Primary type : Decay + Nuclide ZAI : 631541 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 153.92328 + Atomic weight ratio (AWR) : 152.60100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.78E+03 seconds (46.4 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.57000E-01 MeV frac = 1.00000E+00 Product nuclide = 63154.82c : IT + + Nuclide 1303 / 1657 : 631580 -- europium 158 (Eu-158) + + Pointers : 1864140 -1000000 + Primary type : Decay + Nuclide ZAI : 631580 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 157.92768 + Atomic weight ratio (AWR) : 156.57100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.75E+03 seconds (45.9 minutes) + Specific ingestion toxicity : 9.40E-11 Sv/Bq + Specific inhalation toxicity : 4.70E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.48500E+00 MeV frac = 1.00000E+00 Product nuclide = 64158.82c : beta- + + Nuclide 1304 / 1657 : 631590 -- europium 159 (Eu-159) + + Pointers : 1867409 -1000000 + Primary type : Decay + Nuclide ZAI : 631590 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 158.92929 + Atomic weight ratio (AWR) : 157.56400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.09E+03 seconds (18.1 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.51500E+00 MeV frac = 1.00000E+00 Product nuclide = 641590 : beta- + + Nuclide 1305 / 1657 : 631600 -- europium 160 (Eu-160) + + Pointers : 1869376 -1000000 + Primary type : Decay + Nuclide ZAI : 631600 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 159.93190 + Atomic weight ratio (AWR) : 158.55800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 38 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.57861E+00 MeV frac = 1.00000E+00 Product nuclide = 64160.82c : beta- + + Nuclide 1306 / 1657 : 631610 -- europium 161 (Eu-161) + + Pointers : 1869560 -1000000 + Primary type : Decay + Nuclide ZAI : 631610 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 160.93350 + Atomic weight ratio (AWR) : 159.55100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 26 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.73270E+00 MeV frac = 1.00000E+00 Product nuclide = 641610 : beta- + + Nuclide 1307 / 1657 : 631620 -- europium 162 (Eu-162) + + Pointers : 1869744 -1000000 + Primary type : Decay + Nuclide ZAI : 631620 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 161.93713 + Atomic weight ratio (AWR) : 160.54600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 10.6 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.63700E+00 MeV frac = 1.00000E+00 Product nuclide = 641620 : beta- + + Nuclide 1308 / 1657 : 631630 -- europium 163 (Eu-163) + + Pointers : 1869928 -1000000 + Primary type : Decay + Nuclide ZAI : 631630 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 162.93873 + Atomic weight ratio (AWR) : 161.53900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.86000E+00 MeV frac = 1.00000E+00 Product nuclide = 641630 : beta- + + Nuclide 1309 / 1657 : 631640 -- europium 164 (Eu-164) + + Pointers : 1870112 -1000000 + Primary type : Decay + Nuclide ZAI : 631640 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 163.94336 + Atomic weight ratio (AWR) : 162.53500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.65000E+00 MeV frac = 1.00000E+00 Product nuclide = 641640 : beta- + + Nuclide 1310 / 1657 : 631650 -- europium 165 (Eu-165) + + Pointers : 1870296 -1000000 + Primary type : Decay + Nuclide ZAI : 631650 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 164.94597 + Atomic weight ratio (AWR) : 163.52900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.91000E+00 MeV frac = 1.00000E+00 Product nuclide = 641650 : beta- + + Nuclide 1311 / 1657 : 631660 -- europium 166 (Eu-166) + + Pointers : 1870480 -1000000 + Primary type : Decay + Nuclide ZAI : 631660 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 165.94960 + Atomic weight ratio (AWR) : 164.52400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.4 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.80000E+00 MeV frac = 1.00000E+00 Product nuclide = 641660 : beta- + + Nuclide 1312 / 1657 : 631670 -- europium 167 (Eu-167) + + Pointers : 1870664 -1000000 + Primary type : Decay + Nuclide ZAI : 631670 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 166.95322 + Atomic weight ratio (AWR) : 165.51900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.11000E+00 MeV frac = 1.00000E+00 Product nuclide = 641670 : beta- + + Nuclide 1313 / 1657 : 641500 -- gadolinium 150 (Gd-150) + + Pointers : 1870848 -1000000 + Primary type : Decay + Nuclide ZAI : 641500 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 149.91888 + Atomic weight ratio (AWR) : 148.63100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.74E+13 seconds (1.82 million years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 4 Q = 2.79700E+00 MeV frac = 1.00000E+00 Product nuclide = 621460 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 2.79700E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 1314 / 1657 : 641510 -- gadolinium 151 (Gd-151) + + Pointers : 1871138 -1000000 + Primary type : Decay + Nuclide ZAI : 641510 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 150.92049 + Atomic weight ratio (AWR) : 149.62400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.07E+07 seconds (124 days) + Specific ingestion toxicity : 2.00E-10 Sv/Bq + Specific inhalation toxicity : 8.60E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 4.65000E-01 MeV frac = 1.00000E+00 Product nuclide = 63151.82c : EC/beta+ + 2 RTYP = 4 Q = 2.67000E+00 MeV frac = 1.00000E-08 Product nuclide = 62147.82c : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 2.67000E+00 MeV frac = 1.00000E-08 Product nuclide = 2004.82c : alpha + + Nuclide 1315 / 1657 : 641530 -- gadolinium 153 (Gd-153) + + Pointers : 1877750 -1000000 + Primary type : Decay + Nuclide ZAI : 641530 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 152.92168 + Atomic weight ratio (AWR) : 151.60800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.08E+07 seconds (240 days) + Specific ingestion toxicity : 2.70E-10 Sv/Bq + Specific inhalation toxicity : 2.10E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 4.83900E-01 MeV frac = 1.00000E+00 Product nuclide = 63153.82c : EC/beta+ + + Nuclide 1316 / 1657 : 641551 -- gadolinium 155m (Gd-155m) + + Pointers : 1885607 -1000000 + Primary type : Decay + Nuclide ZAI : 641551 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 154.92287 + Atomic weight ratio (AWR) : 153.59200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 32 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.21050E-01 MeV frac = 1.00000E+00 Product nuclide = 64155.82c : IT + + Nuclide 1317 / 1657 : 641590 -- gadolinium 159 (Gd-159) + + Pointers : 1894884 -1000000 + Primary type : Decay + Nuclide ZAI : 641590 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 158.92626 + Atomic weight ratio (AWR) : 157.56100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.65E+04 seconds (18.5 hours) + Specific ingestion toxicity : 4.90E-10 Sv/Bq + Specific inhalation toxicity : 2.70E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.70500E-01 MeV frac = 1.00000E+00 Product nuclide = 65159.82c : beta- + + Nuclide 1318 / 1657 : 641610 -- gadolinium 161 (Gd-161) + + Pointers : 1898364 -1000000 + Primary type : Decay + Nuclide ZAI : 641610 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 160.92947 + Atomic weight ratio (AWR) : 159.54700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.20E+02 seconds (3.66 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.95550E+00 MeV frac = 1.00000E+00 Product nuclide = 651610 : beta- + + Nuclide 1319 / 1657 : 641620 -- gadolinium 162 (Gd-162) + + Pointers : 1901493 -1000000 + Primary type : Decay + Nuclide ZAI : 641620 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 161.93107 + Atomic weight ratio (AWR) : 160.54000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.04E+02 seconds (8.4 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.39000E+00 MeV frac = 1.00000E+00 Product nuclide = 651620 : beta- + + Nuclide 1320 / 1657 : 641630 -- gadolinium 163 (Gd-163) + + Pointers : 1902032 -1000000 + Primary type : Decay + Nuclide ZAI : 641630 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 162.93369 + Atomic weight ratio (AWR) : 161.53400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.80E+01 seconds (1.13 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.11000E+00 MeV frac = 1.00000E+00 Product nuclide = 651630 : beta- + + Nuclide 1321 / 1657 : 641640 -- gadolinium 164 (Gd-164) + + Pointers : 1903271 -1000000 + Primary type : Decay + Nuclide ZAI : 641640 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 163.93630 + Atomic weight ratio (AWR) : 162.52800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 45 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.33000E+00 MeV frac = 1.00000E+00 Product nuclide = 651640 : beta- + + Nuclide 1322 / 1657 : 641650 -- gadolinium 165 (Gd-165) + + Pointers : 1903455 -1000000 + Primary type : Decay + Nuclide ZAI : 641650 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 164.93891 + Atomic weight ratio (AWR) : 163.52200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 10.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.19000E+00 MeV frac = 1.00000E+00 Product nuclide = 651650 : beta- + + Nuclide 1323 / 1657 : 641660 -- gadolinium 166 (Gd-166) + + Pointers : 1903639 -1000000 + Primary type : Decay + Nuclide ZAI : 641660 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 165.94153 + Atomic weight ratio (AWR) : 164.51600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.8 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.36000E+00 MeV frac = 1.00000E+00 Product nuclide = 651660 : beta- + + Nuclide 1324 / 1657 : 641670 -- gadolinium 167 (Gd-167) + + Pointers : 1903823 -1000000 + Primary type : Decay + Nuclide ZAI : 641670 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 166.94515 + Atomic weight ratio (AWR) : 165.51100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.14000E+00 MeV frac = 1.00000E+00 Product nuclide = 651670 : beta- + + Nuclide 1325 / 1657 : 641680 -- gadolinium 168 (Gd-168) + + Pointers : 1904007 -1000000 + Primary type : Decay + Nuclide ZAI : 641680 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 167.94877 + Atomic weight ratio (AWR) : 166.50600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.40000E+00 MeV frac = 1.00000E+00 Product nuclide = 651680 : beta- + + Nuclide 1326 / 1657 : 641690 -- gadolinium 169 (Gd-169) + + Pointers : 1904191 -1000000 + Primary type : Decay + Nuclide ZAI : 641690 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 168.95239 + Atomic weight ratio (AWR) : 167.50100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.20000E+00 MeV frac = 1.00000E+00 Product nuclide = 651690 : beta- + + Nuclide 1327 / 1657 : 651560 -- terbium 156 (Tb-156) + + Pointers : 1904375 -1000000 + Primary type : Decay + Nuclide ZAI : 651560 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 155.92447 + Atomic weight ratio (AWR) : 154.58500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.47E+05 seconds (5.17 days) + Specific ingestion toxicity : 1.20E-09 Sv/Bq + Specific inhalation toxicity : 1.20E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 2.44400E+00 MeV frac = 1.00000E+00 Product nuclide = 64156.82c : EC/beta+ + + Nuclide 1328 / 1657 : 651561 -- terbium 156m (Tb-156m) + + Pointers : 1909044 -1000000 + Primary type : Decay + Nuclide ZAI : 651561 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 155.92447 + Atomic weight ratio (AWR) : 154.58500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.78E+04 seconds (1.02 days) + Specific ingestion toxicity : 1.70E-10 Sv/Bq + Specific inhalation toxicity : 2.10E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 6.00000E-02 MeV frac = 1.00000E+00 Product nuclide = 651560 : IT + + Nuclide 1329 / 1657 : 651562 -- terbium 156m (Tb-156m) + + Pointers : 3521071 -1000000 + Primary type : Decay + Nuclide ZAI : 651562 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 155.92447 + Atomic weight ratio (AWR) : 154.58500 + Temperature : 900.0 Kelvin + XS temperature : -1.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.84E+04 seconds (5.1 hours) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is not present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 2.53200E+00 MeV frac = 1.90000E-03 Product nuclide = 64156.82c : EC/beta+ + 2 RTYP = 3 Q = 8.84000E-02 MeV frac = 9.98100E-01 Product nuclide = 651560 : IT + + Nuclide 1330 / 1657 : 651570 -- terbium 157 (Tb-157) + + Pointers : 1909401 -1000000 + Primary type : Decay + Nuclide ZAI : 651570 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 156.92406 + Atomic weight ratio (AWR) : 155.57600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.12E+09 seconds (99.1 years) + Specific ingestion toxicity : 3.40E-11 Sv/Bq + Specific inhalation toxicity : 1.20E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 6.29000E-02 MeV frac = 1.00000E+00 Product nuclide = 64157.82c : EC/beta+ + + Nuclide 1331 / 1657 : 651580 -- terbium 158 (Tb-158) + + Pointers : 1909800 -1000000 + Primary type : Decay + Nuclide ZAI : 651580 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 157.92567 + Atomic weight ratio (AWR) : 156.56900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.68E+09 seconds (180 years) + Specific ingestion toxicity : 1.10E-09 Sv/Bq + Specific inhalation toxicity : 4.60E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 9.34900E-01 MeV frac = 1.68000E-01 Product nuclide = 661580 : beta- + 2 RTYP = 2 Q = 1.21960E+00 MeV frac = 8.32000E-01 Product nuclide = 64158.82c : EC/beta+ + + Nuclide 1332 / 1657 : 651581 -- terbium 158m (Tb-158m) + + Pointers : 1911168 -1000000 + Primary type : Decay + Nuclide ZAI : 651581 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 157.92567 + Atomic weight ratio (AWR) : 156.56900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 10.8 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.10300E-01 MeV frac = 1.00000E+00 Product nuclide = 651580 : IT + + Nuclide 1333 / 1657 : 651610 -- terbium 161 (Tb-161) + + Pointers : 1918189 -1000000 + Primary type : Decay + Nuclide ZAI : 651610 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 160.92745 + Atomic weight ratio (AWR) : 159.54500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.95E+05 seconds (6.89 days) + Specific ingestion toxicity : 7.20E-10 Sv/Bq + Specific inhalation toxicity : 1.30E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.93100E-01 MeV frac = 1.00000E+00 Product nuclide = 66161.82c : beta- + + Nuclide 1334 / 1657 : 651620 -- terbium 162 (Tb-162) + + Pointers : 1920660 -1000000 + Primary type : Decay + Nuclide ZAI : 651620 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 161.92906 + Atomic weight ratio (AWR) : 160.53800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.56E+02 seconds (7.6 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.51000E+00 MeV frac = 1.00000E+00 Product nuclide = 66162.82c : beta- + + Nuclide 1335 / 1657 : 651630 -- terbium 163 (Tb-163) + + Pointers : 1923131 -1000000 + Primary type : Decay + Nuclide ZAI : 651630 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 162.93066 + Atomic weight ratio (AWR) : 161.53100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.17E+03 seconds (19.5 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.78500E+00 MeV frac = 1.00000E+00 Product nuclide = 66163.82c : beta- + + Nuclide 1336 / 1657 : 651640 -- terbium 164 (Tb-164) + + Pointers : 1927842 -1000000 + Primary type : Decay + Nuclide ZAI : 651640 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 163.93327 + Atomic weight ratio (AWR) : 162.52500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.80E+02 seconds (3 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.89330E+00 MeV frac = 1.00000E+00 Product nuclide = 66164.82c : beta- + + Nuclide 1337 / 1657 : 651650 -- terbium 165 (Tb-165) + + Pointers : 1928026 -1000000 + Primary type : Decay + Nuclide ZAI : 651650 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 164.93488 + Atomic weight ratio (AWR) : 163.51800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.27E+02 seconds (2.11 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.96000E+00 MeV frac = 1.00000E+00 Product nuclide = 661650 : beta- + + Nuclide 1338 / 1657 : 651660 -- terbium 166 (Tb-166) + + Pointers : 1928565 -1000000 + Primary type : Decay + Nuclide ZAI : 651660 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 165.93850 + Atomic weight ratio (AWR) : 164.51300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 25.6 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.83010E+00 MeV frac = 1.00000E+00 Product nuclide = 661660 : beta- + + Nuclide 1339 / 1657 : 651670 -- terbium 167 (Tb-167) + + Pointers : 1928749 -1000000 + Primary type : Decay + Nuclide ZAI : 651670 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 166.94010 + Atomic weight ratio (AWR) : 165.50600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 19 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.10000E+00 MeV frac = 1.00000E+00 Product nuclide = 661670 : beta- + + Nuclide 1340 / 1657 : 651680 -- terbium 168 (Tb-168) + + Pointers : 1928933 -1000000 + Primary type : Decay + Nuclide ZAI : 651680 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 167.94373 + Atomic weight ratio (AWR) : 166.50100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.06000E+00 MeV frac = 1.00000E+00 Product nuclide = 661680 : beta- + + Nuclide 1341 / 1657 : 651690 -- terbium 169 (Tb-169) + + Pointers : 1929117 -1000000 + Primary type : Decay + Nuclide ZAI : 651690 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 168.94634 + Atomic weight ratio (AWR) : 167.49500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.50000E+00 MeV frac = 1.00000E+00 Product nuclide = 661690 : beta- + + Nuclide 1342 / 1657 : 651700 -- terbium 170 (Tb-170) + + Pointers : 1929301 -1000000 + Primary type : Decay + Nuclide ZAI : 651700 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 169.94996 + Atomic weight ratio (AWR) : 168.49000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.32000E+00 MeV frac = 1.00000E+00 Product nuclide = 661700 : beta- + + Nuclide 1343 / 1657 : 651710 -- terbium 171 (Tb-171) + + Pointers : 1929485 -1000000 + Primary type : Decay + Nuclide ZAI : 651710 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 170.95358 + Atomic weight ratio (AWR) : 169.48500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.61000E+00 MeV frac = 1.00000E+00 Product nuclide = 661710 : beta- + + Nuclide 1344 / 1657 : 661580 -- dysprosium 158 (Dy-158) + + Pointers : 1929669 -1000000 + Primary type : Decay + Nuclide ZAI : 661580 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 157.92466 + Atomic weight ratio (AWR) : 156.56800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1345 / 1657 : 661590 -- dysprosium 159 (Dy-159) + + Pointers : 1929775 -1000000 + Primary type : Decay + Nuclide ZAI : 661590 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 158.92626 + Atomic weight ratio (AWR) : 157.56100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.25E+07 seconds (144 days) + Specific ingestion toxicity : 1.00E-10 Sv/Bq + Specific inhalation toxicity : 3.70E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 3.65600E-01 MeV frac = 1.00000E+00 Product nuclide = 65159.82c : EC/beta+ + + Nuclide 1346 / 1657 : 661650 -- dysprosium 165 (Dy-165) + + Pointers : 1950468 -1000000 + Primary type : Decay + Nuclide ZAI : 661650 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 164.93185 + Atomic weight ratio (AWR) : 163.51500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.40E+03 seconds (2.33 hours) + Specific ingestion toxicity : 1.10E-10 Sv/Bq + Specific inhalation toxicity : 6.00E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.28660E+00 MeV frac = 1.00000E+00 Product nuclide = 67165.82c : beta- + + Nuclide 1347 / 1657 : 661651 -- dysprosium 165m (Dy-165m) + + Pointers : 1952715 -1000000 + Primary type : Decay + Nuclide ZAI : 661651 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 164.93185 + Atomic weight ratio (AWR) : 163.51500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.54E+01 seconds (1.26 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 1.08160E-01 MeV frac = 9.77600E-01 Product nuclide = 661650 : IT + 2 RTYP = 1 Q = 1.39486E+00 MeV frac = 2.24000E-02 Product nuclide = 67165.82c : beta- + + Nuclide 1348 / 1657 : 661660 -- dysprosium 166 (Dy-166) + + Pointers : 1952972 -1000000 + Primary type : Decay + Nuclide ZAI : 661660 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 165.93245 + Atomic weight ratio (AWR) : 164.50700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.94E+05 seconds (3.4 days) + Specific ingestion toxicity : 1.60E-09 Sv/Bq + Specific inhalation toxicity : 1.90E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.86800E-01 MeV frac = 1.00000E+00 Product nuclide = 671660 : beta- + + Nuclide 1349 / 1657 : 661670 -- dysprosium 167 (Dy-167) + + Pointers : 1953735 -1000000 + Primary type : Decay + Nuclide ZAI : 661670 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 166.93607 + Atomic weight ratio (AWR) : 165.50200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.72E+02 seconds (6.2 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.35000E+00 MeV frac = 1.00000E+00 Product nuclide = 671670 : beta- + + Nuclide 1350 / 1657 : 661680 -- dysprosium 168 (Dy-168) + + Pointers : 1955086 -1000000 + Primary type : Decay + Nuclide ZAI : 661680 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 167.93667 + Atomic weight ratio (AWR) : 166.49400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.22E+02 seconds (8.7 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.51000E+00 MeV frac = 1.00000E+00 Product nuclide = 671680 : beta- + + Nuclide 1351 / 1657 : 661690 -- dysprosium 169 (Dy-169) + + Pointers : 1955270 -1000000 + Primary type : Decay + Nuclide ZAI : 661690 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 168.94029 + Atomic weight ratio (AWR) : 167.48900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 39 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.20300E+00 MeV frac = 1.00000E+00 Product nuclide = 671690 : beta- + + Nuclide 1352 / 1657 : 661700 -- dysprosium 170 (Dy-170) + + Pointers : 1955454 -1000000 + Primary type : Decay + Nuclide ZAI : 661700 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 169.94290 + Atomic weight ratio (AWR) : 168.48300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 30 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.48000E+00 MeV frac = 1.00000E+00 Product nuclide = 671701 : beta- + + Nuclide 1353 / 1657 : 661710 -- dysprosium 171 (Dy-171) + + Pointers : 1955638 -1000000 + Primary type : Decay + Nuclide ZAI : 661710 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 170.94652 + Atomic weight ratio (AWR) : 169.47800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.41000E+00 MeV frac = 1.00000E+00 Product nuclide = 671710 : beta- + + Nuclide 1354 / 1657 : 661720 -- dysprosium 172 (Dy-172) + + Pointers : 1955822 -1000000 + Primary type : Decay + Nuclide ZAI : 661720 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 171.94913 + Atomic weight ratio (AWR) : 170.47200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.67000E+00 MeV frac = 1.00000E+00 Product nuclide = 671720 : beta- + + Nuclide 1355 / 1657 : 661730 -- dysprosium 173 (Dy-173) + + Pointers : 1956006 -1000000 + Primary type : Decay + Nuclide ZAI : 661730 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 172.95276 + Atomic weight ratio (AWR) : 171.46700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.32000E+00 MeV frac = 1.00000E+00 Product nuclide = 671730 : beta- + + Nuclide 1356 / 1657 : 671610 -- holmium 161 (Ho-161) + + Pointers : 1956190 -1000000 + Primary type : Decay + Nuclide ZAI : 671610 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 160.92745 + Atomic weight ratio (AWR) : 159.54500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.93E+03 seconds (2.48 hours) + Specific ingestion toxicity : 1.30E-11 Sv/Bq + Specific inhalation toxicity : 6.00E-12 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 8.56500E-01 MeV frac = 1.00000E+00 Product nuclide = 66161.82c : EC/beta+ + + Nuclide 1357 / 1657 : 671611 -- holmium 161m (Ho-161m) + + Pointers : 1959319 -1000000 + Primary type : Decay + Nuclide ZAI : 671611 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 160.92745 + Atomic weight ratio (AWR) : 159.54500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.77 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 2.11140E-01 MeV frac = 1.00000E+00 Product nuclide = 671610 : IT + + Nuclide 1358 / 1657 : 671620 -- holmium 162 (Ho-162) + + Pointers : 1959718 -1000000 + Primary type : Decay + Nuclide ZAI : 671620 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 161.92906 + Atomic weight ratio (AWR) : 160.53800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.00E+02 seconds (15 minutes) + Specific ingestion toxicity : 3.30E-12 Sv/Bq + Specific inhalation toxicity : 2.80E-12 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 2.14000E+00 MeV frac = 1.00000E+00 Product nuclide = 66162.82c : EC/beta+ + + Nuclide 1359 / 1657 : 671621 -- holmium 162m (Ho-162m) + + Pointers : 1960845 -1000000 + Primary type : Decay + Nuclide ZAI : 671621 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 161.92906 + Atomic weight ratio (AWR) : 160.53800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.02E+03 seconds (1.12 hours) + Specific ingestion toxicity : 2.60E-11 Sv/Bq + Specific inhalation toxicity : 2.10E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 2.24600E+00 MeV frac = 4.50000E-01 Product nuclide = 66162.82c : EC/beta+ + 2 RTYP = 3 Q = 1.05870E-01 MeV frac = 5.50000E-01 Product nuclide = 671620 : IT + + Nuclide 1360 / 1657 : 671630 -- holmium 163 (Ho-163) + + Pointers : 1964061 -1000000 + Primary type : Decay + Nuclide ZAI : 671630 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 162.92864 + Atomic weight ratio (AWR) : 161.52900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.44E+11 seconds (4,573 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 2.65000E-03 MeV frac = 1.00000E+00 Product nuclide = 66163.82c : EC/beta+ + + Nuclide 1361 / 1657 : 671631 -- holmium 163m (Ho-163m) + + Pointers : 1964245 -1000000 + Primary type : Decay + Nuclide ZAI : 671631 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 162.92864 + Atomic weight ratio (AWR) : 161.52900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.1 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 2.97880E-01 MeV frac = 1.00000E+00 Product nuclide = 671630 : IT + + Nuclide 1362 / 1657 : 671640 -- holmium 164 (Ho-164) + + Pointers : 1964644 -1000000 + Primary type : Decay + Nuclide ZAI : 671640 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 163.93025 + Atomic weight ratio (AWR) : 162.52200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.72E+03 seconds (28.6 minutes) + Specific ingestion toxicity : 9.50E-12 Sv/Bq + Specific inhalation toxicity : 8.40E-12 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 9.63000E-01 MeV frac = 5.17000E-01 Product nuclide = 68164.82c : beta- + 2 RTYP = 2 Q = 9.87000E-01 MeV frac = 4.83000E-01 Product nuclide = 66164.82c : EC/beta+ + + Nuclide 1363 / 1657 : 671641 -- holmium 164m (Ho-164m) + + Pointers : 1965438 -1000000 + Primary type : Decay + Nuclide ZAI : 671641 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 163.93025 + Atomic weight ratio (AWR) : 162.52200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.26E+03 seconds (37.6 minutes) + Specific ingestion toxicity : 1.60E-11 Sv/Bq + Specific inhalation toxicity : 1.20E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.40000E-01 MeV frac = 1.00000E+00 Product nuclide = 671640 : IT + + Nuclide 1364 / 1657 : 671660 -- holmium 166 (Ho-166) + + Pointers : 1967713 -1000000 + Primary type : Decay + Nuclide ZAI : 671660 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 165.93245 + Atomic weight ratio (AWR) : 164.50700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.65E+04 seconds (1.12 days) + Specific ingestion toxicity : 1.40E-09 Sv/Bq + Specific inhalation toxicity : 6.50E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.85450E+00 MeV frac = 1.00000E+00 Product nuclide = 68166.82c : beta- + + Nuclide 1365 / 1657 : 671661 -- holmium 166m (Ho-166m) + + Pointers : 1968882 -1000000 + Primary type : Decay + Nuclide ZAI : 671661 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 165.93245 + Atomic weight ratio (AWR) : 164.50700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.58E+10 seconds (1,134 years) + Specific ingestion toxicity : 2.00E-09 Sv/Bq + Specific inhalation toxicity : 1.20E-07 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.86048E+00 MeV frac = 1.00000E+00 Product nuclide = 68166.82c : beta- + + Nuclide 1366 / 1657 : 671670 -- holmium 167 (Ho-167) + + Pointers : 1973089 -1000000 + Primary type : Decay + Nuclide ZAI : 671670 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 166.93304 + Atomic weight ratio (AWR) : 165.49900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.12E+04 seconds (3.1 hours) + Specific ingestion toxicity : 8.30E-11 Sv/Bq + Specific inhalation toxicity : 7.10E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.00700E+00 MeV frac = 8.80508E-01 Product nuclide = 68167.82c : beta- + 2 RTYP = 1 Q = 7.99180E-01 MeV frac = 1.19492E-01 Product nuclide = 681671 : beta- + + Nuclide 1367 / 1657 : 671680 -- holmium 168 (Ho-168) + + Pointers : 1975017 -1000000 + Primary type : Decay + Nuclide ZAI : 671680 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 167.93566 + Atomic weight ratio (AWR) : 166.49300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.79E+02 seconds (2.99 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.91000E+00 MeV frac = 1.00000E+00 Product nuclide = 68168.82c : beta- + + Nuclide 1368 / 1657 : 671681 -- holmium 168m (Ho-168m) + + Pointers : 1977572 -1000000 + Primary type : Decay + Nuclide ZAI : 671681 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 167.93566 + Atomic weight ratio (AWR) : 166.49300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.32E+02 seconds (2.2 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 5.90000E-02 MeV frac = 9.95000E-01 Product nuclide = 671680 : IT + 2 RTYP = 1 Q = 2.98570E+00 MeV frac = 5.00000E-03 Product nuclide = 68168.82c : beta- + + Nuclide 1369 / 1657 : 671690 -- holmium 169 (Ho-169) + + Pointers : 1977829 -1000000 + Primary type : Decay + Nuclide ZAI : 671690 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 168.93726 + Atomic weight ratio (AWR) : 167.48600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.82E+02 seconds (4.7 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.12570E+00 MeV frac = 1.00000E+00 Product nuclide = 681690 : beta- + + Nuclide 1370 / 1657 : 671700 -- holmium 170 (Ho-170) + + Pointers : 1978013 -1000000 + Primary type : Decay + Nuclide ZAI : 671700 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 169.93987 + Atomic weight ratio (AWR) : 168.48000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.67E+02 seconds (2.78 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.87000E+00 MeV frac = 1.00000E+00 Product nuclide = 68170.82c : beta- + + Nuclide 1371 / 1657 : 671701 -- holmium 170m (Ho-170m) + + Pointers : 1980316 -1000000 + Primary type : Decay + Nuclide ZAI : 671701 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 169.93987 + Atomic weight ratio (AWR) : 168.48000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 43 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.99000E+00 MeV frac = 1.00000E+00 Product nuclide = 68170.82c : beta- + + Nuclide 1372 / 1657 : 671710 -- holmium 171 (Ho-171) + + Pointers : 1981695 -1000000 + Primary type : Decay + Nuclide ZAI : 671710 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 170.94148 + Atomic weight ratio (AWR) : 169.47300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 53 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.20490E+00 MeV frac = 1.00000E+00 Product nuclide = 681710 : beta- + + Nuclide 1373 / 1657 : 671720 -- holmium 172 (Ho-172) + + Pointers : 1981879 -1000000 + Primary type : Decay + Nuclide ZAI : 671720 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 171.94510 + Atomic weight ratio (AWR) : 170.46800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 25 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.08900E+00 MeV frac = 1.00000E+00 Product nuclide = 681720 : beta- + + Nuclide 1374 / 1657 : 671730 -- holmium 173 (Ho-173) + + Pointers : 1982063 -1000000 + Primary type : Decay + Nuclide ZAI : 671730 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 172.94771 + Atomic weight ratio (AWR) : 171.46200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 10 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.55000E+00 MeV frac = 1.00000E+00 Product nuclide = 681730 : beta- + + Nuclide 1375 / 1657 : 671740 -- holmium 174 (Ho-174) + + Pointers : 1982247 -1000000 + Primary type : Decay + Nuclide ZAI : 671740 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 173.95133 + Atomic weight ratio (AWR) : 172.45700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.45000E+00 MeV frac = 1.00000E+00 Product nuclide = 681740 : beta- + + Nuclide 1376 / 1657 : 671750 -- holmium 175 (Ho-175) + + Pointers : 1982431 -1000000 + Primary type : Decay + Nuclide ZAI : 671750 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 174.95395 + Atomic weight ratio (AWR) : 173.45100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.85000E+00 MeV frac = 1.00000E+00 Product nuclide = 681750 : beta- + + Nuclide 1377 / 1657 : 681620 -- erbium 162 (Er-162) + + Pointers : 1982615 -1000000 + Primary type : Decay + Nuclide ZAI : 681620 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 161.92906 + Atomic weight ratio (AWR) : 160.53800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.42E+21 seconds (1.4E+14 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 4 Q = 1.64410E+00 MeV frac = 5.00000E-01 Product nuclide = 661580 : alpha + 2 RTYP = 22 Q = 1.84380E+00 MeV frac = 5.00000E-01 Product nuclide = 66162.82c : EC/beta+ + EC/beta+ + + 1 additional decay branch: + + 1 RTYP = 4 Q = 1.64410E+00 MeV frac = 5.00000E-01 Product nuclide = 2004.82c : alpha + + Nuclide 1378 / 1657 : 681630 -- erbium 163 (Er-163) + + Pointers : 1982945 -1000000 + Primary type : Decay + Nuclide ZAI : 681630 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 162.92965 + Atomic weight ratio (AWR) : 161.53000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.50E+03 seconds (1.25 hours) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 1.21000E+00 MeV frac = 9.99847E-01 Product nuclide = 671630 : EC/beta+ + 2 RTYP = 2 Q = 9.12190E-01 MeV frac = 1.52868E-04 Product nuclide = 671631 : EC/beta+ + + Nuclide 1379 / 1657 : 681650 -- erbium 165 (Er-165) + + Pointers : 1987299 -1000000 + Primary type : Decay + Nuclide ZAI : 681650 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 164.93084 + Atomic weight ratio (AWR) : 163.51400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.73E+04 seconds (10.4 hours) + Specific ingestion toxicity : 1.90E-11 Sv/Bq + Specific inhalation toxicity : 7.90E-12 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 3.76300E-01 MeV frac = 1.00000E+00 Product nuclide = 67165.82c : EC/beta+ + + Nuclide 1380 / 1657 : 681671 -- erbium 167m (Er-167m) + + Pointers : 1994995 -1000000 + Primary type : Decay + Nuclide ZAI : 681671 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 166.93203 + Atomic weight ratio (AWR) : 165.49800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.27 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 2.07801E-01 MeV frac = 1.00000E+00 Product nuclide = 68167.82c : IT + + Nuclide 1381 / 1657 : 681690 -- erbium 169 (Er-169) + + Pointers : 1999447 -1000000 + Primary type : Decay + Nuclide ZAI : 681690 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 168.93423 + Atomic weight ratio (AWR) : 167.48300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.10E+05 seconds (9.38 days) + Specific ingestion toxicity : 3.70E-10 Sv/Bq + Specific inhalation toxicity : 1.00E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.53000E-01 MeV frac = 1.00000E+00 Product nuclide = 691690 : beta- + + Nuclide 1382 / 1657 : 681710 -- erbium 171 (Er-171) + + Pointers : 2002930 -1000000 + Primary type : Decay + Nuclide ZAI : 681710 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 170.93845 + Atomic weight ratio (AWR) : 169.47000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.71E+04 seconds (7.52 hours) + Specific ingestion toxicity : 3.60E-10 Sv/Bq + Specific inhalation toxicity : 2.20E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.49070E+00 MeV frac = 1.00000E+00 Product nuclide = 691710 : beta- + + Nuclide 1383 / 1657 : 681720 -- erbium 172 (Er-172) + + Pointers : 2005667 -1000000 + Primary type : Decay + Nuclide ZAI : 681720 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 171.93905 + Atomic weight ratio (AWR) : 170.46200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.77E+05 seconds (2.05 days) + Specific ingestion toxicity : 1.00E-09 Sv/Bq + Specific inhalation toxicity : 1.10E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.91000E-01 MeV frac = 1.00000E+00 Product nuclide = 691720 : beta- + + Nuclide 1384 / 1657 : 681730 -- erbium 173 (Er-173) + + Pointers : 2008530 -1000000 + Primary type : Decay + Nuclide ZAI : 681730 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 172.94267 + Atomic weight ratio (AWR) : 171.45700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.40E+01 seconds (1.4 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.60000E+00 MeV frac = 1.00000E+00 Product nuclide = 691730 : beta- + + Nuclide 1385 / 1657 : 681740 -- erbium 174 (Er-174) + + Pointers : 2009349 -1000000 + Primary type : Decay + Nuclide ZAI : 681740 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 173.94427 + Atomic weight ratio (AWR) : 172.45000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.92E+02 seconds (3.2 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.92000E+00 MeV frac = 1.00000E+00 Product nuclide = 691740 : beta- + + Nuclide 1386 / 1657 : 681750 -- erbium 175 (Er-175) + + Pointers : 2009533 -1000000 + Primary type : Decay + Nuclide ZAI : 681750 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 174.94790 + Atomic weight ratio (AWR) : 173.44500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.20E+01 seconds (1.2 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.67000E+00 MeV frac = 1.00000E+00 Product nuclide = 691750 : beta- + + Nuclide 1387 / 1657 : 681760 -- erbium 176 (Er-176) + + Pointers : 2009717 -1000000 + Primary type : Decay + Nuclide ZAI : 681760 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 175.95051 + Atomic weight ratio (AWR) : 174.43900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 20 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.87000E+00 MeV frac = 1.00000E+00 Product nuclide = 691760 : beta- + + Nuclide 1388 / 1657 : 681770 -- erbium 177 (Er-177) + + Pointers : 2009901 -1000000 + Primary type : Decay + Nuclide ZAI : 681770 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 176.95413 + Atomic weight ratio (AWR) : 175.43400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.67000E+00 MeV frac = 1.00000E+00 Product nuclide = 691770 : beta- + + Nuclide 1389 / 1657 : 691660 -- thulium 166 (Tm-166) + + Pointers : 2010085 -1000000 + Primary type : Decay + Nuclide ZAI : 691660 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 165.93346 + Atomic weight ratio (AWR) : 164.50800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.77E+04 seconds (7.7 hours) + Specific ingestion toxicity : 2.80E-10 Sv/Bq + Specific inhalation toxicity : 1.70E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 3.03800E+00 MeV frac = 1.00000E+00 Product nuclide = 68166.82c : EC/beta+ + + Nuclide 1390 / 1657 : 691670 -- thulium 167 (Tm-167) + + Pointers : 2020774 -1000000 + Primary type : Decay + Nuclide ZAI : 691670 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 166.93304 + Atomic weight ratio (AWR) : 165.49900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.99E+05 seconds (9.25 days) + Specific ingestion toxicity : 5.60E-10 Sv/Bq + Specific inhalation toxicity : 1.10E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 5.40600E-01 MeV frac = 9.82500E-01 Product nuclide = 681671 : EC/beta+ + 2 RTYP = 2 Q = 7.48400E-01 MeV frac = 1.75000E-02 Product nuclide = 68167.82c : EC/beta+ + + Nuclide 1391 / 1657 : 691680 -- thulium 168 (Tm-168) + + Pointers : 2021666 -1000000 + Primary type : Decay + Nuclide ZAI : 691680 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 167.93465 + Atomic weight ratio (AWR) : 166.49200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.78E+06 seconds (90 days) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 2.57000E-01 MeV frac = 1.00000E-04 Product nuclide = 701680 : beta- + 2 RTYP = 2 Q = 1.67900E+00 MeV frac = 9.99900E-01 Product nuclide = 68168.82c : EC/beta+ + + Nuclide 1392 / 1657 : 691690 -- thulium 169 (Tm-169) + + Pointers : 2025596 -1000000 + Primary type : Decay + Nuclide ZAI : 691690 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 168.93423 + Atomic weight ratio (AWR) : 167.48300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1393 / 1657 : 691700 -- thulium 170 (Tm-170) + + Pointers : 2025702 -1000000 + Primary type : Decay + Nuclide ZAI : 691700 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 169.93584 + Atomic weight ratio (AWR) : 168.47600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.11E+07 seconds (129 days) + Specific ingestion toxicity : 1.30E-09 Sv/Bq + Specific inhalation toxicity : 7.00E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 3.14400E-01 MeV frac = 1.31000E-03 Product nuclide = 68170.82c : EC/beta+ + 2 RTYP = 1 Q = 9.68000E-01 MeV frac = 9.98690E-01 Product nuclide = 701700 : beta- + + Nuclide 1394 / 1657 : 691710 -- thulium 171 (Tm-171) + + Pointers : 2026328 -1000000 + Primary type : Decay + Nuclide ZAI : 691710 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 170.93643 + Atomic weight ratio (AWR) : 169.46800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.05E+07 seconds (1.92 years) + Specific ingestion toxicity : 1.10E-10 Sv/Bq + Specific inhalation toxicity : 1.40E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.65000E-02 MeV frac = 1.00000E+00 Product nuclide = 701710 : beta- + + Nuclide 1395 / 1657 : 691720 -- thulium 172 (Tm-172) + + Pointers : 2026755 -1000000 + Primary type : Decay + Nuclide ZAI : 691720 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 171.93804 + Atomic weight ratio (AWR) : 170.46100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.29E+05 seconds (2.65 days) + Specific ingestion toxicity : 1.70E-09 Sv/Bq + Specific inhalation toxicity : 1.10E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.88000E+00 MeV frac = 1.00000E+00 Product nuclide = 701720 : beta- + + Nuclide 1396 / 1657 : 691730 -- thulium 173 (Tm-173) + + Pointers : 2028946 -1000000 + Primary type : Decay + Nuclide ZAI : 691730 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 172.93964 + Atomic weight ratio (AWR) : 171.45400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.97E+04 seconds (8.24 hours) + Specific ingestion toxicity : 3.10E-10 Sv/Bq + Specific inhalation toxicity : 1.80E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.29800E+00 MeV frac = 1.00000E+00 Product nuclide = 701730 : beta- + + Nuclide 1397 / 1657 : 691740 -- thulium 174 (Tm-174) + + Pointers : 2029499 -1000000 + Primary type : Decay + Nuclide ZAI : 691740 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 173.94226 + Atomic weight ratio (AWR) : 172.44800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.24E+02 seconds (5.4 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.08000E+00 MeV frac = 1.00000E+00 Product nuclide = 701740 : beta- + + Nuclide 1398 / 1657 : 691750 -- thulium 175 (Tm-175) + + Pointers : 2032264 -1000000 + Primary type : Decay + Nuclide ZAI : 691750 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 174.94386 + Atomic weight ratio (AWR) : 173.44100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.12E+02 seconds (15.2 minutes) + Specific ingestion toxicity : 2.70E-11 Sv/Bq + Specific inhalation toxicity : 1.80E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 2.38060E+00 MeV frac = 2.30000E-01 Product nuclide = 701750 : beta- + 2 RTYP = 1 Q = 1.86574E+00 MeV frac = 7.70000E-01 Product nuclide = 701751 : beta- + + Nuclide 1399 / 1657 : 691760 -- thulium 176 (Tm-176) + + Pointers : 2032521 -1000000 + Primary type : Decay + Nuclide ZAI : 691760 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 175.94748 + Atomic weight ratio (AWR) : 174.43600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.11E+02 seconds (1.85 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 4.12410E+00 MeV frac = 5.00000E-01 Product nuclide = 701760 : beta- + 2 RTYP = 1 Q = 3.07410E+00 MeV frac = 5.00000E-01 Product nuclide = 701761 : beta- + + Nuclide 1400 / 1657 : 691770 -- thulium 177 (Tm-177) + + Pointers : 2032778 -1000000 + Primary type : Decay + Nuclide ZAI : 691770 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 176.94909 + Atomic weight ratio (AWR) : 175.42900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.00E+01 seconds (1.5 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.18770E+00 MeV frac = 1.00000E+00 Product nuclide = 701771 : beta- + + Nuclide 1401 / 1657 : 691780 -- thulium 178 (Tm-178) + + Pointers : 2032962 -1000000 + Primary type : Decay + Nuclide ZAI : 691780 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 177.95271 + Atomic weight ratio (AWR) : 176.42400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 30 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.57800E+00 MeV frac = 1.00000E+00 Product nuclide = 701780 : beta- + + Nuclide 1402 / 1657 : 691790 -- thulium 179 (Tm-179) + + Pointers : 2033146 -1000000 + Primary type : Decay + Nuclide ZAI : 691790 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 178.95532 + Atomic weight ratio (AWR) : 177.41800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 20 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.82000E+00 MeV frac = 1.00000E+00 Product nuclide = 701790 : beta- + + Nuclide 1403 / 1657 : 701680 -- ytterbium 168 (Yb-168) + + Pointers : 2033330 -1000000 + Primary type : Decay + Nuclide ZAI : 701680 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 167.93364 + Atomic weight ratio (AWR) : 166.49100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.10E+21 seconds (1.3E+14 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 4 Q = 1.95010E+00 MeV frac = 5.00000E-01 Product nuclide = 68164.82c : alpha + 2 RTYP = 22 Q = 1.42170E+00 MeV frac = 5.00000E-01 Product nuclide = 68168.82c : EC/beta+ + EC/beta+ + + 1 additional decay branch: + + 1 RTYP = 4 Q = 1.95010E+00 MeV frac = 5.00000E-01 Product nuclide = 2004.82c : alpha + + Nuclide 1404 / 1657 : 701690 -- ytterbium 169 (Yb-169) + + Pointers : 2033660 -1000000 + Primary type : Decay + Nuclide ZAI : 701690 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 168.93524 + Atomic weight ratio (AWR) : 167.48400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.77E+06 seconds (32 days) + Specific ingestion toxicity : 7.10E-10 Sv/Bq + Specific inhalation toxicity : 3.00E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 9.09000E-01 MeV frac = 1.00000E+00 Product nuclide = 691690 : EC/beta+ + + Nuclide 1405 / 1657 : 701700 -- ytterbium 170 (Yb-170) + + Pointers : 2035697 -1000000 + Primary type : Decay + Nuclide ZAI : 701700 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 169.93483 + Atomic weight ratio (AWR) : 168.47500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1406 / 1657 : 701710 -- ytterbium 171 (Yb-171) + + Pointers : 2035803 -1000000 + Primary type : Decay + Nuclide ZAI : 701710 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 170.93643 + Atomic weight ratio (AWR) : 169.46800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1407 / 1657 : 701711 -- ytterbium 171m (Yb-171m) + + Pointers : 2035909 -1000000 + Primary type : Decay + Nuclide ZAI : 701711 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 170.93643 + Atomic weight ratio (AWR) : 169.46800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.25 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 9.52820E-02 MeV frac = 1.00000E+00 Product nuclide = 701710 : IT + + Nuclide 1408 / 1657 : 701720 -- ytterbium 172 (Yb-172) + + Pointers : 2036093 -1000000 + Primary type : Decay + Nuclide ZAI : 701720 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 171.93602 + Atomic weight ratio (AWR) : 170.45900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1409 / 1657 : 701730 -- ytterbium 173 (Yb-173) + + Pointers : 2036199 -1000000 + Primary type : Decay + Nuclide ZAI : 701730 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 172.93863 + Atomic weight ratio (AWR) : 171.45300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1410 / 1657 : 701740 -- ytterbium 174 (Yb-174) + + Pointers : 2036305 -1000000 + Primary type : Decay + Nuclide ZAI : 701740 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 173.93923 + Atomic weight ratio (AWR) : 172.44500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1411 / 1657 : 701750 -- ytterbium 175 (Yb-175) + + Pointers : 2036411 -1000000 + Primary type : Decay + Nuclide ZAI : 701750 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 174.94083 + Atomic weight ratio (AWR) : 173.43800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.62E+05 seconds (4.18 days) + Specific ingestion toxicity : 4.40E-10 Sv/Bq + Specific inhalation toxicity : 7.30E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.68800E-01 MeV frac = 1.00000E+00 Product nuclide = 71175.82c : beta- + + Nuclide 1412 / 1657 : 701751 -- ytterbium 175m (Yb-175m) + + Pointers : 2037132 -1000000 + Primary type : Decay + Nuclide ZAI : 701751 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 174.94083 + Atomic weight ratio (AWR) : 173.43800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 68.2 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 5.14865E-01 MeV frac = 1.00000E+00 Product nuclide = 701750 : IT + + Nuclide 1413 / 1657 : 701760 -- ytterbium 176 (Yb-176) + + Pointers : 2037316 -1000000 + Primary type : Decay + Nuclide ZAI : 701760 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 175.94244 + Atomic weight ratio (AWR) : 174.43100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1414 / 1657 : 701761 -- ytterbium 176m (Yb-176m) + + Pointers : 2037422 -1000000 + Primary type : Decay + Nuclide ZAI : 701761 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 175.94244 + Atomic weight ratio (AWR) : 174.43100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 11.4 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.04980E+00 MeV frac = 1.00000E+00 Product nuclide = 701760 : IT + + Nuclide 1415 / 1657 : 701770 -- ytterbium 177 (Yb-177) + + Pointers : 2038045 -1000000 + Primary type : Decay + Nuclide ZAI : 701770 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 176.94505 + Atomic weight ratio (AWR) : 175.42500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.88E+03 seconds (1.91 hours) + Specific ingestion toxicity : 8.80E-11 Sv/Bq + Specific inhalation toxicity : 6.90E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.39920E+00 MeV frac = 1.00000E+00 Product nuclide = 711770 : beta- + + Nuclide 1416 / 1657 : 701771 -- ytterbium 177m (Yb-177m) + + Pointers : 2040544 -1000000 + Primary type : Decay + Nuclide ZAI : 701771 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 176.94505 + Atomic weight ratio (AWR) : 175.42500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.41 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 3.31500E-01 MeV frac = 1.00000E+00 Product nuclide = 701770 : IT + + Nuclide 1417 / 1657 : 701780 -- ytterbium 178 (Yb-178) + + Pointers : 2040985 -1000000 + Primary type : Decay + Nuclide ZAI : 701780 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 177.94666 + Atomic weight ratio (AWR) : 176.41800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.44E+03 seconds (1.23 hours) + Specific ingestion toxicity : 1.20E-10 Sv/Bq + Specific inhalation toxicity : 7.50E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.45001E-01 MeV frac = 1.00000E+00 Product nuclide = 711780 : beta- + + Nuclide 1418 / 1657 : 701790 -- ytterbium 179 (Yb-179) + + Pointers : 2041169 -1000000 + Primary type : Decay + Nuclide ZAI : 701790 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 178.95028 + Atomic weight ratio (AWR) : 177.41300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.80E+02 seconds (8 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.05160E+00 MeV frac = 1.00000E+00 Product nuclide = 711791 : beta- + + Nuclide 1419 / 1657 : 701800 -- ytterbium 180 (Yb-180) + + Pointers : 2041353 -1000000 + Primary type : Decay + Nuclide ZAI : 701800 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 179.95188 + Atomic weight ratio (AWR) : 178.40600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.44E+02 seconds (2.4 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.27610E+00 MeV frac = 1.00000E+00 Product nuclide = 711801 : beta- + + Nuclide 1420 / 1657 : 701810 -- ytterbium 181 (Yb-181) + + Pointers : 2041537 -1000000 + Primary type : Decay + Nuclide ZAI : 701810 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 180.95651 + Atomic weight ratio (AWR) : 179.40200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 60 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.89000E+00 MeV frac = 1.00000E+00 Product nuclide = 711810 : beta- + + Nuclide 1421 / 1657 : 711720 -- lutetium 172 (Lu-172) + + Pointers : 2041721 -1000000 + Primary type : Decay + Nuclide ZAI : 711720 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 171.93905 + Atomic weight ratio (AWR) : 170.46200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.79E+05 seconds (6.7 days) + Specific ingestion toxicity : 1.30E-09 Sv/Bq + Specific inhalation toxicity : 1.60E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 2.52090E+00 MeV frac = 1.00000E+00 Product nuclide = 701720 : EC/beta+ + + Nuclide 1422 / 1657 : 711730 -- lutetium 173 (Lu-173) + + Pointers : 2052270 -1000000 + Primary type : Decay + Nuclide ZAI : 711730 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 172.93863 + Atomic weight ratio (AWR) : 171.45300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.22E+07 seconds (1.34 years) + Specific ingestion toxicity : 2.60E-10 Sv/Bq + Specific inhalation toxicity : 2.40E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 6.72300E-01 MeV frac = 1.00000E+00 Product nuclide = 701730 : EC/beta+ + + Nuclide 1423 / 1657 : 711740 -- lutetium 174 (Lu-174) + + Pointers : 2053663 -1000000 + Primary type : Decay + Nuclide ZAI : 711740 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 173.94024 + Atomic weight ratio (AWR) : 172.44600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.12E+08 seconds (3.56 years) + Specific ingestion toxicity : 2.70E-10 Sv/Bq + Specific inhalation toxicity : 4.20E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 1.37600E+00 MeV frac = 1.00000E+00 Product nuclide = 701740 : EC/beta+ + + Nuclide 1424 / 1657 : 711741 -- lutetium 174m (Lu-174m) + + Pointers : 2054300 -1000000 + Primary type : Decay + Nuclide ZAI : 711741 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 173.94024 + Atomic weight ratio (AWR) : 172.44600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.23E+07 seconds (142 days) + Specific ingestion toxicity : 5.30E-10 Sv/Bq + Specific inhalation toxicity : 4.20E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 1.54700E+00 MeV frac = 5.80000E-03 Product nuclide = 701740 : EC/beta+ + 2 RTYP = 3 Q = 1.70830E-01 MeV frac = 9.94200E-01 Product nuclide = 711740 : IT + + Nuclide 1425 / 1657 : 711761 -- lutetium 176m (Lu-176m) + + Pointers : 2059456 -1000000 + Primary type : Decay + Nuclide ZAI : 711761 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 175.94244 + Atomic weight ratio (AWR) : 174.43100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.31E+04 seconds (3.63 hours) + Specific ingestion toxicity : 1.70E-10 Sv/Bq + Specific inhalation toxicity : 1.20E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 2.33200E-01 MeV frac = 9.50000E-04 Product nuclide = 701760 : EC/beta+ + 2 RTYP = 1 Q = 1.31980E+00 MeV frac = 9.99050E-01 Product nuclide = 72176.82c : beta- + + Nuclide 1426 / 1657 : 711770 -- lutetium 177 (Lu-177) + + Pointers : 2060250 -1000000 + Primary type : Decay + Nuclide ZAI : 711770 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 176.94404 + Atomic weight ratio (AWR) : 175.42400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.74E+05 seconds (6.65 days) + Specific ingestion toxicity : 5.30E-10 Sv/Bq + Specific inhalation toxicity : 1.20E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.98300E-01 MeV frac = 1.00000E+00 Product nuclide = 72177.82c : beta- + + Nuclide 1427 / 1657 : 711771 -- lutetium 177m (Lu-177m) + + Pointers : 2060943 -1000000 + Primary type : Decay + Nuclide ZAI : 711771 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 176.94404 + Atomic weight ratio (AWR) : 175.42400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.38E+07 seconds (160 days) + Specific ingestion toxicity : 1.70E-09 Sv/Bq + Specific inhalation toxicity : 1.60E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.52500E-01 MeV frac = 7.74000E-01 Product nuclide = 721771 : beta- + 2 RTYP = 3 Q = 9.70175E-01 MeV frac = 2.26000E-01 Product nuclide = 711770 : IT + + Nuclide 1428 / 1657 : 711772 -- lutetium 177m (Lu-177m) + + Pointers : 3516756 -1000000 + Primary type : Decay + Nuclide ZAI : 711772 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 176.94404 + Atomic weight ratio (AWR) : 175.42400 + Temperature : 900.0 Kelvin + XS temperature : -1.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.20E+02 seconds (7 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is not present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.66058E+00 MeV frac = 5.00000E-01 Product nuclide = 721772 : beta- + 2 RTYP = 3 Q = 2.92983E+00 MeV frac = 5.00000E-01 Product nuclide = 711771 : IT + + Nuclide 1429 / 1657 : 711780 -- lutetium 178 (Lu-178) + + Pointers : 2061933 -1000000 + Primary type : Decay + Nuclide ZAI : 711780 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 177.94565 + Atomic weight ratio (AWR) : 176.41700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.70E+03 seconds (28.4 minutes) + Specific ingestion toxicity : 4.70E-11 Sv/Bq + Specific inhalation toxicity : 2.60E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.10130E+00 MeV frac = 1.00000E+00 Product nuclide = 72178.82c : beta- + + Nuclide 1430 / 1657 : 711781 -- lutetium 178m (Lu-178m) + + Pointers : 2062850 -1000000 + Primary type : Decay + Nuclide ZAI : 711781 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 177.94565 + Atomic weight ratio (AWR) : 176.41700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.39E+03 seconds (23.1 minutes) + Specific ingestion toxicity : 3.80E-11 Sv/Bq + Specific inhalation toxicity : 3.30E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.07758E+00 MeV frac = 1.00000E+00 Product nuclide = 721781 : beta- + + Nuclide 1431 / 1657 : 711790 -- lutetium 179 (Lu-179) + + Pointers : 2063034 -1000000 + Primary type : Decay + Nuclide ZAI : 711790 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 178.94725 + Atomic weight ratio (AWR) : 177.41000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.65E+04 seconds (4.59 hours) + Specific ingestion toxicity : 2.10E-10 Sv/Bq + Specific inhalation toxicity : 1.20E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.40800E+00 MeV frac = 1.00000E+00 Product nuclide = 72179.82c : beta- + + Nuclide 1432 / 1657 : 711791 -- lutetium 179m (Lu-179m) + + Pointers : 2064777 -1000000 + Primary type : Decay + Nuclide ZAI : 711791 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 178.94725 + Atomic weight ratio (AWR) : 177.41000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.1 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 5.92400E-01 MeV frac = 1.00000E+00 Product nuclide = 711790 : IT + + Nuclide 1433 / 1657 : 711800 -- lutetium 180 (Lu-180) + + Pointers : 2064961 -1000000 + Primary type : Decay + Nuclide ZAI : 711800 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 179.94986 + Atomic weight ratio (AWR) : 178.40400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.42E+02 seconds (5.7 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.10000E+00 MeV frac = 1.00000E+00 Product nuclide = 72180.82c : beta- + + Nuclide 1434 / 1657 : 711801 -- lutetium 180m (Lu-180m) + + Pointers : 2066410 -1000000 + Primary type : Decay + Nuclide ZAI : 711801 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 179.94986 + Atomic weight ratio (AWR) : 178.40400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 3.11230E+00 MeV frac = 5.00000E-01 Product nuclide = 72180.82c : beta- + 2 RTYP = 3 Q = 1.39000E-02 MeV frac = 5.00000E-01 Product nuclide = 711800 : IT + + Nuclide 1435 / 1657 : 711802 -- lutetium 180m (Lu-180m) + + Pointers : 3517832 -1000000 + Primary type : Decay + Nuclide ZAI : 711802 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 179.94986 + Atomic weight ratio (AWR) : 178.40400 + Temperature : 900.0 Kelvin + XS temperature : -1.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is not present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 2.58090E+00 MeV frac = 5.00000E-01 Product nuclide = 721801 : beta- + 2 RTYP = 3 Q = 6.24000E-01 MeV frac = 5.00000E-01 Product nuclide = 711800 : IT + + Nuclide 1436 / 1657 : 711810 -- lutetium 181 (Lu-181) + + Pointers : 2066667 -1000000 + Primary type : Decay + Nuclide ZAI : 711810 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 180.95248 + Atomic weight ratio (AWR) : 179.39800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.10E+02 seconds (3.5 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.67190E+00 MeV frac = 1.00000E+00 Product nuclide = 721810 : beta- + + Nuclide 1437 / 1657 : 711820 -- lutetium 182 (Lu-182) + + Pointers : 2066851 -1000000 + Primary type : Decay + Nuclide ZAI : 711820 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 181.95509 + Atomic weight ratio (AWR) : 180.39200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.20E+02 seconds (2 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.17900E+00 MeV frac = 1.00000E+00 Product nuclide = 721820 : beta- + + Nuclide 1438 / 1657 : 711830 -- lutetium 183 (Lu-183) + + Pointers : 2067035 -1000000 + Primary type : Decay + Nuclide ZAI : 711830 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 182.95770 + Atomic weight ratio (AWR) : 181.38600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 58 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.40000E+00 MeV frac = 1.00000E+00 Product nuclide = 721830 : beta- + + Nuclide 1439 / 1657 : 711840 -- lutetium 184 (Lu-184) + + Pointers : 2068092 -1000000 + Primary type : Decay + Nuclide ZAI : 711840 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 183.96133 + Atomic weight ratio (AWR) : 182.38100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 20 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 5.09000E+00 MeV frac = 5.00000E-01 Product nuclide = 721840 : beta- + 2 RTYP = 1 Q = 3.81760E+00 MeV frac = 5.00000E-01 Product nuclide = 721841 : beta- + + Nuclide 1440 / 1657 : 721740 -- hafnium 174 (Hf-174) + + Pointers : 2068349 -1000000 + Primary type : Decay + Nuclide ZAI : 721740 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 173.94024 + Atomic weight ratio (AWR) : 172.44600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.31E+22 seconds (2E+15 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 4 Q = 2.50400E+00 MeV frac = 1.00000E+00 Product nuclide = 701700 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 2.50400E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 1441 / 1657 : 721750 -- hafnium 175 (Hf-175) + + Pointers : 2068639 -1000000 + Primary type : Decay + Nuclide ZAI : 721750 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 174.94184 + Atomic weight ratio (AWR) : 173.43900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.05E+06 seconds (70 days) + Specific ingestion toxicity : 4.10E-10 Sv/Bq + Specific inhalation toxicity : 1.20E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 6.19000E-01 MeV frac = 1.00000E+00 Product nuclide = 71175.82c : EC/beta+ + + Nuclide 1442 / 1657 : 721771 -- hafnium 177m (Hf-177m) + + Pointers : 2074397 -1000000 + Primary type : Decay + Nuclide ZAI : 721771 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 176.94303 + Atomic weight ratio (AWR) : 175.42300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.08 seconds + Specific ingestion toxicity : 8.10E-11 Sv/Bq + Specific inhalation toxicity : 9.00E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.31545E+00 MeV frac = 1.00000E+00 Product nuclide = 72177.82c : IT + + Nuclide 1443 / 1657 : 721772 -- hafnium 177m (Hf-177m) + + Pointers : 3517013 -1000000 + Primary type : Decay + Nuclide ZAI : 721772 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 176.94303 + Atomic weight ratio (AWR) : 175.42300 + Temperature : 900.0 Kelvin + XS temperature : -1.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.08E+03 seconds (51.4 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is not present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.42455E+00 MeV frac = 1.00000E+00 Product nuclide = 721771 : IT + + Nuclide 1444 / 1657 : 721781 -- hafnium 178m (Hf-178m) + + Pointers : 2079489 -1000000 + Primary type : Decay + Nuclide ZAI : 721781 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 177.94363 + Atomic weight ratio (AWR) : 176.41500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4 seconds + Specific ingestion toxicity : 4.70E-09 Sv/Bq + Specific inhalation toxicity : 2.60E-07 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.14742E+00 MeV frac = 1.00000E+00 Product nuclide = 72178.82c : IT + + Nuclide 1445 / 1657 : 721782 -- hafnium 178m (Hf-178m) + + Pointers : 3518089 -1000000 + Primary type : Decay + Nuclide ZAI : 721782 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 177.94363 + Atomic weight ratio (AWR) : 176.41500 + Temperature : 900.0 Kelvin + XS temperature : -1.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.78E+08 seconds (31 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is not present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.29863E+00 MeV frac = 1.00000E+00 Product nuclide = 721781 : IT + + Nuclide 1446 / 1657 : 721791 -- hafnium 179m (Hf-179m) + + Pointers : 2082140 -1000000 + Primary type : Decay + Nuclide ZAI : 721791 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 178.94624 + Atomic weight ratio (AWR) : 177.40900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 18.7 seconds + Specific ingestion toxicity : 1.20E-09 Sv/Bq + Specific inhalation toxicity : 3.80E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 3.75037E-01 MeV frac = 1.00000E+00 Product nuclide = 72179.82c : IT + + Nuclide 1447 / 1657 : 721792 -- hafnium 179m (Hf-179m) + + Pointers : 3503704 -1000000 + Primary type : Decay + Nuclide ZAI : 721792 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 178.94624 + Atomic weight ratio (AWR) : 177.40900 + Temperature : 900.0 Kelvin + XS temperature : -1.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.17E+06 seconds (25.1 days) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is not present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.10580E+00 MeV frac = 1.00000E+00 Product nuclide = 72179.82c : IT + + Nuclide 1448 / 1657 : 721801 -- hafnium 180m (Hf-180m) + + Pointers : 2084514 -1000000 + Primary type : Decay + Nuclide ZAI : 721801 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 179.94684 + Atomic weight ratio (AWR) : 178.40100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.98E+04 seconds (5.5 hours) + Specific ingestion toxicity : 1.70E-10 Sv/Bq + Specific inhalation toxicity : 1.30E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 2.12000E-01 MeV frac = 3.10000E-03 Product nuclide = 731801 : beta- + 2 RTYP = 3 Q = 1.14148E+00 MeV frac = 9.96900E-01 Product nuclide = 72180.82c : IT + + Nuclide 1449 / 1657 : 721810 -- hafnium 181 (Hf-181) + + Pointers : 2085462 -1000000 + Primary type : Decay + Nuclide ZAI : 721810 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 180.94945 + Atomic weight ratio (AWR) : 179.39500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.66E+06 seconds (42.4 days) + Specific ingestion toxicity : 1.10E-09 Sv/Bq + Specific inhalation toxicity : 5.00E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.02830E+00 MeV frac = 1.00000E+00 Product nuclide = 73181.82c : beta- + + Nuclide 1450 / 1657 : 721820 -- hafnium 182 (Hf-182) + + Pointers : 2086337 -1000000 + Primary type : Decay + Nuclide ZAI : 721820 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 181.95005 + Atomic weight ratio (AWR) : 180.38700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.81E+14 seconds (8.91 million years) + Specific ingestion toxicity : 3.00E-09 Sv/Bq + Specific inhalation toxicity : 3.10E-07 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.75000E-01 MeV frac = 1.00000E+00 Product nuclide = 73182.82c : beta- + + Nuclide 1451 / 1657 : 721821 -- hafnium 182m (Hf-182m) + + Pointers : 2087002 -1000000 + Primary type : Decay + Nuclide ZAI : 721821 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 181.95106 + Atomic weight ratio (AWR) : 180.38800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.69E+03 seconds (1.02 hours) + Specific ingestion toxicity : 4.20E-11 Sv/Bq + Specific inhalation toxicity : 4.60E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.02761E+00 MeV frac = 5.80000E-01 Product nuclide = 731821 : beta- + 2 RTYP = 3 Q = 1.17288E+00 MeV frac = 4.20000E-01 Product nuclide = 721820 : IT + + Nuclide 1452 / 1657 : 721830 -- hafnium 183 (Hf-183) + + Pointers : 2087259 -1000000 + Primary type : Decay + Nuclide ZAI : 721830 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 182.95367 + Atomic weight ratio (AWR) : 181.38200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.84E+03 seconds (1.07 hours) + Specific ingestion toxicity : 7.30E-11 Sv/Bq + Specific inhalation toxicity : 5.70E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.00610E+00 MeV frac = 1.00000E+00 Product nuclide = 731830 : beta- + + Nuclide 1453 / 1657 : 721840 -- hafnium 184 (Hf-184) + + Pointers : 2087443 -1000000 + Primary type : Decay + Nuclide ZAI : 721840 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 183.95527 + Atomic weight ratio (AWR) : 182.37500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.48E+04 seconds (4.12 hours) + Specific ingestion toxicity : 5.20E-10 Sv/Bq + Specific inhalation toxicity : 3.30E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.34100E+00 MeV frac = 1.00000E+00 Product nuclide = 731840 : beta- + + Nuclide 1454 / 1657 : 721841 -- hafnium 184m (Hf-184m) + + Pointers : 2087627 -1000000 + Primary type : Decay + Nuclide ZAI : 721841 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 183.95527 + Atomic weight ratio (AWR) : 182.37500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 48 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.61340E+00 MeV frac = 1.00000E+00 Product nuclide = 731840 : beta- + + Nuclide 1455 / 1657 : 721850 -- hafnium 185 (Hf-185) + + Pointers : 2087811 -1000000 + Primary type : Decay + Nuclide ZAI : 721850 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 184.95889 + Atomic weight ratio (AWR) : 183.37000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.10E+02 seconds (3.5 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.03600E+00 MeV frac = 1.00000E+00 Product nuclide = 731850 : beta- + + Nuclide 1456 / 1657 : 721860 -- hafnium 186 (Hf-186) + + Pointers : 2087995 -1000000 + Primary type : Decay + Nuclide ZAI : 721860 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 185.96050 + Atomic weight ratio (AWR) : 184.36300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.56E+02 seconds (2.6 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.18000E+00 MeV frac = 1.00000E+00 Product nuclide = 731860 : beta- + + Nuclide 1457 / 1657 : 721870 -- hafnium 187 (Hf-187) + + Pointers : 2088179 -1000000 + Primary type : Decay + Nuclide ZAI : 721870 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 186.96412 + Atomic weight ratio (AWR) : 185.35800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 30 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.79000E+00 MeV frac = 1.00000E+00 Product nuclide = 731870 : beta- + + Nuclide 1458 / 1657 : 721880 -- hafnium 188 (Hf-188) + + Pointers : 2088363 -1000000 + Primary type : Decay + Nuclide ZAI : 721880 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 187.96673 + Atomic weight ratio (AWR) : 186.35200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 20 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.93000E+00 MeV frac = 1.00000E+00 Product nuclide = 731880 : beta- + + Nuclide 1459 / 1657 : 731780 -- tantalum 178 (Ta-178) + + Pointers : 2088547 -1000000 + Primary type : Decay + Nuclide ZAI : 731780 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 177.94565 + Atomic weight ratio (AWR) : 176.41700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.59E+02 seconds (9.31 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 1.91000E+00 MeV frac = 1.00000E+00 Product nuclide = 72178.82c : EC/beta+ + + Nuclide 1460 / 1657 : 731781 -- tantalum 178m (Ta-178m) + + Pointers : 2089996 -1000000 + Primary type : Decay + Nuclide ZAI : 731781 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 177.94565 + Atomic weight ratio (AWR) : 176.41700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.50E+03 seconds (2.36 hours) + Specific ingestion toxicity : 7.20E-11 Sv/Bq + Specific inhalation toxicity : 6.80E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 7.89875E-01 MeV frac = 1.00000E+00 Product nuclide = 721781 : EC/beta+ + + Nuclide 1461 / 1657 : 731790 -- tantalum 179 (Ta-179) + + Pointers : 2090180 -1000000 + Primary type : Decay + Nuclide ZAI : 731790 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 178.94624 + Atomic weight ratio (AWR) : 177.40900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.08E+07 seconds (1.61 years) + Specific ingestion toxicity : 6.50E-11 Sv/Bq + Specific inhalation toxicity : 5.60E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 1.10000E-01 MeV frac = 1.00000E+00 Product nuclide = 72179.82c : EC/beta+ + + Nuclide 1462 / 1657 : 731791 -- tantalum 179m (Ta-179m) + + Pointers : 2090523 -1000000 + Primary type : Decay + Nuclide ZAI : 731791 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 178.94624 + Atomic weight ratio (AWR) : 177.40900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.31730E+00 MeV frac = 1.00000E+00 Product nuclide = 731790 : IT + + Nuclide 1463 / 1657 : 731792 -- tantalum 179m (Ta-179m) + + Pointers : 3521683 -1000000 + Primary type : Decay + Nuclide ZAI : 731792 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 178.94624 + Atomic weight ratio (AWR) : 177.40900 + Temperature : 900.0 Kelvin + XS temperature : -1.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 54.1 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is not present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.32200E+00 MeV frac = 1.00000E+00 Product nuclide = 731791 : IT + + Nuclide 1464 / 1657 : 731800 -- tantalum 180 (Ta-180) + + Pointers : 2090707 -1000000 + Primary type : Decay + Nuclide ZAI : 731800 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 179.94785 + Atomic weight ratio (AWR) : 178.40200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.91E+04 seconds (8.08 hours) + Specific ingestion toxicity : 5.40E-11 Sv/Bq + Specific inhalation toxicity : 4.20E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 7.08000E-01 MeV frac = 1.81000E-01 Product nuclide = 741800 : beta- + 2 RTYP = 2 Q = 8.53000E-01 MeV frac = 8.19000E-01 Product nuclide = 72180.82c : EC/beta+ + + Nuclide 1465 / 1657 : 731801 -- tantalum 180m (Ta-180m) + + Pointers : 2091389 -1000000 + Primary type : Decay + Nuclide ZAI : 731801 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 179.94785 + Atomic weight ratio (AWR) : 178.40200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.68E+22 seconds (1.8E+15 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 7.83000E-01 MeV frac = 2.00000E-01 Product nuclide = 741800 : beta- + 2 RTYP = 2 Q = 9.28000E-01 MeV frac = 8.00000E-01 Product nuclide = 72180.82c : EC/beta+ + + Nuclide 1466 / 1657 : 731821 -- tantalum 182m (Ta-182m) + + Pointers : 2098658 -1000000 + Primary type : Decay + Nuclide ZAI : 731821 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 181.95005 + Atomic weight ratio (AWR) : 180.38700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.283 seconds + Specific ingestion toxicity : 1.20E-11 Sv/Bq + Specific inhalation toxicity : 2.10E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.62630E-02 MeV frac = 1.00000E+00 Product nuclide = 73182.82c : IT + + Nuclide 1467 / 1657 : 731822 -- tantalum 182m (Ta-182m) + + Pointers : 3519034 -1000000 + Primary type : Decay + Nuclide ZAI : 731822 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 181.95005 + Atomic weight ratio (AWR) : 180.38700 + Temperature : 900.0 Kelvin + XS temperature : -1.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.50E+02 seconds (15.8 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is not present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 5.03310E-01 MeV frac = 1.00000E+00 Product nuclide = 731821 : IT + + Nuclide 1468 / 1657 : 731830 -- tantalum 183 (Ta-183) + + Pointers : 2098973 -1000000 + Primary type : Decay + Nuclide ZAI : 731830 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 182.95165 + Atomic weight ratio (AWR) : 181.38000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.40E+05 seconds (5.09 days) + Specific ingestion toxicity : 1.30E-09 Sv/Bq + Specific inhalation toxicity : 2.10E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.07010E+00 MeV frac = 9.66000E-01 Product nuclide = 74183.82c : beta- + 2 RTYP = 1 Q = 7.60600E-01 MeV frac = 3.40000E-02 Product nuclide = 741831 : beta- + + Nuclide 1469 / 1657 : 731840 -- tantalum 184 (Ta-184) + + Pointers : 2101139 -1000000 + Primary type : Decay + Nuclide ZAI : 731840 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 183.95426 + Atomic weight ratio (AWR) : 182.37400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.13E+04 seconds (8.7 hours) + Specific ingestion toxicity : 6.80E-10 Sv/Bq + Specific inhalation toxicity : 4.30E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.86630E+00 MeV frac = 1.00000E+00 Product nuclide = 74184.82c : beta- + + Nuclide 1470 / 1657 : 731850 -- tantalum 185 (Ta-185) + + Pointers : 2101323 -1000000 + Primary type : Decay + Nuclide ZAI : 731850 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 184.95587 + Atomic weight ratio (AWR) : 183.36700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.96E+03 seconds (49.4 minutes) + Specific ingestion toxicity : 6.80E-11 Sv/Bq + Specific inhalation toxicity : 4.80E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.99400E+00 MeV frac = 1.00000E+00 Product nuclide = 741850 : beta- + + Nuclide 1471 / 1657 : 731851 -- tantalum 185m (Ta-185m) + + Pointers : 2102870 -1000000 + Primary type : Decay + Nuclide ZAI : 731851 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 184.95587 + Atomic weight ratio (AWR) : 183.36700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.30800E+00 MeV frac = 1.00000E+00 Product nuclide = 731850 : IT + + Nuclide 1472 / 1657 : 731860 -- tantalum 186 (Ta-186) + + Pointers : 2103054 -1000000 + Primary type : Decay + Nuclide ZAI : 731860 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 185.95848 + Atomic weight ratio (AWR) : 184.36100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.30E+02 seconds (10.5 minutes) + Specific ingestion toxicity : 3.30E-11 Sv/Bq + Specific inhalation toxicity : 1.80E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.89950E+00 MeV frac = 1.00000E+00 Product nuclide = 74186.82c : beta- + + Nuclide 1473 / 1657 : 731870 -- tantalum 187 (Ta-187) + + Pointers : 2103238 -1000000 + Primary type : Decay + Nuclide ZAI : 731870 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 186.96009 + Atomic weight ratio (AWR) : 185.35400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.20E+02 seconds (2 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.13480E+00 MeV frac = 1.00000E+00 Product nuclide = 741870 : beta- + + Nuclide 1474 / 1657 : 731880 -- tantalum 188 (Ta-188) + + Pointers : 2103422 -1000000 + Primary type : Decay + Nuclide ZAI : 731880 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 187.96371 + Atomic weight ratio (AWR) : 186.34900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 20 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.85700E+00 MeV frac = 1.00000E+00 Product nuclide = 741880 : beta- + + Nuclide 1475 / 1657 : 731890 -- tantalum 189 (Ta-189) + + Pointers : 2103606 -1000000 + Primary type : Decay + Nuclide ZAI : 731890 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 188.96632 + Atomic weight ratio (AWR) : 187.34300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.65000E+00 MeV frac = 1.00000E+00 Product nuclide = 741890 : beta- + + Nuclide 1476 / 1657 : 731900 -- tantalum 190 (Ta-190) + + Pointers : 2103790 -1000000 + Primary type : Decay + Nuclide ZAI : 731900 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 189.96893 + Atomic weight ratio (AWR) : 188.33700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.3 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.64000E+00 MeV frac = 1.00000E+00 Product nuclide = 741900 : beta- + + Nuclide 1477 / 1657 : 741800 -- tungsten 180 (W-180) + + Pointers : 2103974 -1000000 + Primary type : Decay + Nuclide ZAI : 741800 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 179.94684 + Atomic weight ratio (AWR) : 178.40100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1478 / 1657 : 741810 -- tungsten 181 (W-181) + + Pointers : 2104080 -1000000 + Primary type : Decay + Nuclide ZAI : 741810 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 180.94844 + Atomic weight ratio (AWR) : 179.39400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.05E+07 seconds (121 days) + Specific ingestion toxicity : 7.60E-11 Sv/Bq + Specific inhalation toxicity : 2.70E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 1.86000E-01 MeV frac = 1.00000E+00 Product nuclide = 73181.82c : EC/beta+ + + Nuclide 1479 / 1657 : 741831 -- tungsten 183m (W-183m) + + Pointers : 2110425 -1000000 + Primary type : Decay + Nuclide ZAI : 741831 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 182.95064 + Atomic weight ratio (AWR) : 181.37900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.25 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 3.09500E-01 MeV frac = 1.00000E+00 Product nuclide = 74183.82c : IT + + Nuclide 1480 / 1657 : 741850 -- tungsten 185 (W-185) + + Pointers : 2113615 -1000000 + Primary type : Decay + Nuclide ZAI : 741850 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 184.95385 + Atomic weight ratio (AWR) : 183.36500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.49E+06 seconds (75.1 days) + Specific ingestion toxicity : 4.40E-10 Sv/Bq + Specific inhalation toxicity : 1.20E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.32800E-01 MeV frac = 1.00000E+00 Product nuclide = 75185.82c : beta- + + Nuclide 1481 / 1657 : 741851 -- tungsten 185m (W-185m) + + Pointers : 2114042 -1000000 + Primary type : Decay + Nuclide ZAI : 741851 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 184.95385 + Atomic weight ratio (AWR) : 183.36500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.00E+02 seconds (1.67 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.97430E-01 MeV frac = 1.00000E+00 Product nuclide = 741850 : IT + + Nuclide 1482 / 1657 : 741861 -- tungsten 186m (W-186m) + + Pointers : 2117737 -1000000 + Primary type : Decay + Nuclide ZAI : 741861 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 185.95445 + Atomic weight ratio (AWR) : 184.35700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 3.54280E+00 MeV frac = 1.00000E+00 Product nuclide = 74186.82c : IT + + Nuclide 1483 / 1657 : 741870 -- tungsten 187 (W-187) + + Pointers : 2117921 -1000000 + Primary type : Decay + Nuclide ZAI : 741870 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 186.95706 + Atomic weight ratio (AWR) : 185.35100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.59E+04 seconds (23.8 hours) + Specific ingestion toxicity : 6.30E-10 Sv/Bq + Specific inhalation toxicity : 1.90E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.31250E+00 MeV frac = 1.00000E+00 Product nuclide = 75187.82c : beta- + + Nuclide 1484 / 1657 : 741880 -- tungsten 188 (W-188) + + Pointers : 2120784 -1000000 + Primary type : Decay + Nuclide ZAI : 741880 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 187.95866 + Atomic weight ratio (AWR) : 186.34400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.03E+06 seconds (69.8 days) + Specific ingestion toxicity : 2.10E-09 Sv/Bq + Specific inhalation toxicity : 5.70E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.49000E-01 MeV frac = 1.00000E+00 Product nuclide = 751880 : beta- + + Nuclide 1485 / 1657 : 741890 -- tungsten 189 (W-189) + + Pointers : 2121505 -1000000 + Primary type : Decay + Nuclide ZAI : 741890 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 188.96229 + Atomic weight ratio (AWR) : 187.33900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.42E+02 seconds (10.7 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.49800E+00 MeV frac = 1.00000E+00 Product nuclide = 751890 : beta- + + Nuclide 1486 / 1657 : 741900 -- tungsten 190 (W-190) + + Pointers : 2121689 -1000000 + Primary type : Decay + Nuclide ZAI : 741900 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 189.96288 + Atomic weight ratio (AWR) : 188.33100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.80E+03 seconds (30 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.27000E+00 MeV frac = 1.00000E+00 Product nuclide = 751900 : beta- + + Nuclide 1487 / 1657 : 741901 -- tungsten 190m (W-190m) + + Pointers : 2122144 -1000000 + Primary type : Decay + Nuclide ZAI : 741901 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 189.96288 + Atomic weight ratio (AWR) : 188.33100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.1 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 2.38100E+00 MeV frac = 1.00000E+00 Product nuclide = 741900 : IT + + Nuclide 1488 / 1657 : 741910 -- tungsten 191 (W-191) + + Pointers : 2122328 -1000000 + Primary type : Decay + Nuclide ZAI : 741910 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 190.96650 + Atomic weight ratio (AWR) : 189.32600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 20 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.23900E+00 MeV frac = 1.00000E+00 Product nuclide = 751910 : beta- + + Nuclide 1489 / 1657 : 741920 -- tungsten 192 (W-192) + + Pointers : 2122512 -1000000 + Primary type : Decay + Nuclide ZAI : 741920 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 191.96811 + Atomic weight ratio (AWR) : 190.31900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 10 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.06000E+00 MeV frac = 1.00000E+00 Product nuclide = 751920 : beta- + + Nuclide 1490 / 1657 : 751830 -- rhenium 183 (Re-183) + + Pointers : 2122696 -1000000 + Primary type : Decay + Nuclide ZAI : 751830 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 182.95064 + Atomic weight ratio (AWR) : 181.37900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.05E+06 seconds (70 days) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 5.56000E-01 MeV frac = 1.00000E+00 Product nuclide = 74183.82c : EC/beta+ + + Nuclide 1491 / 1657 : 751840 -- rhenium 184 (Re-184) + + Pointers : 2124565 -1000000 + Primary type : Decay + Nuclide ZAI : 751840 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 183.95225 + Atomic weight ratio (AWR) : 182.37200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.06E+06 seconds (35.4 days) + Specific ingestion toxicity : 1.00E-09 Sv/Bq + Specific inhalation toxicity : 1.90E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 1.48000E+00 MeV frac = 1.00000E+00 Product nuclide = 74184.82c : EC/beta+ + + Nuclide 1492 / 1657 : 751841 -- rhenium 184m (Re-184m) + + Pointers : 2126560 -1000000 + Primary type : Decay + Nuclide ZAI : 751841 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 183.95225 + Atomic weight ratio (AWR) : 182.37200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.45E+07 seconds (168 days) + Specific ingestion toxicity : 1.50E-09 Sv/Bq + Specific inhalation toxicity : 6.50E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 1.66800E+00 MeV frac = 2.52000E-01 Product nuclide = 74184.82c : EC/beta+ + 2 RTYP = 3 Q = 1.88010E-01 MeV frac = 7.48000E-01 Product nuclide = 751840 : IT + + Nuclide 1493 / 1657 : 751860 -- rhenium 186 (Re-186) + + Pointers : 2130461 -1000000 + Primary type : Decay + Nuclide ZAI : 751860 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 185.95546 + Atomic weight ratio (AWR) : 184.35800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.24E+05 seconds (3.75 days) + Specific ingestion toxicity : 1.50E-09 Sv/Bq + Specific inhalation toxicity : 1.10E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.06930E+00 MeV frac = 9.31300E-01 Product nuclide = 761860 : beta- + 2 RTYP = 2 Q = 5.79000E-01 MeV frac = 6.87000E-02 Product nuclide = 74186.82c : EC/beta+ + + Nuclide 1494 / 1657 : 751861 -- rhenium 186m (Re-186m) + + Pointers : 2131521 -1000000 + Primary type : Decay + Nuclide ZAI : 751861 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 185.95546 + Atomic weight ratio (AWR) : 184.35800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.00E+12 seconds (190,126 years) + Specific ingestion toxicity : 2.20E-09 Sv/Bq + Specific inhalation toxicity : 1.20E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.49000E-01 MeV frac = 1.00000E+00 Product nuclide = 751860 : IT + + Nuclide 1495 / 1657 : 751880 -- rhenium 188 (Re-188) + + Pointers : 2134034 -1000000 + Primary type : Decay + Nuclide ZAI : 751880 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 187.95766 + Atomic weight ratio (AWR) : 186.34300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.12E+04 seconds (17 hours) + Specific ingestion toxicity : 1.40E-09 Sv/Bq + Specific inhalation toxicity : 5.40E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.12040E+00 MeV frac = 1.00000E+00 Product nuclide = 761880 : beta- + + Nuclide 1496 / 1657 : 751881 -- rhenium 188m (Re-188m) + + Pointers : 2136001 -1000000 + Primary type : Decay + Nuclide ZAI : 751881 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 187.95766 + Atomic weight ratio (AWR) : 186.34300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.12E+03 seconds (18.6 minutes) + Specific ingestion toxicity : 3.00E-11 Sv/Bq + Specific inhalation toxicity : 1.30E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.72069E-01 MeV frac = 1.00000E+00 Product nuclide = 751880 : IT + + Nuclide 1497 / 1657 : 751890 -- rhenium 189 (Re-189) + + Pointers : 2136185 -1000000 + Primary type : Decay + Nuclide ZAI : 751890 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 188.95926 + Atomic weight ratio (AWR) : 187.33600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.75E+04 seconds (1.01 days) + Specific ingestion toxicity : 7.80E-10 Sv/Bq + Specific inhalation toxicity : 4.30E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.00900E+00 MeV frac = 8.97169E-01 Product nuclide = 761890 : beta- + 2 RTYP = 1 Q = 9.78188E-01 MeV frac = 1.02831E-01 Product nuclide = 761891 : beta- + + Nuclide 1498 / 1657 : 751900 -- rhenium 190 (Re-190) + + Pointers : 2140703 -1000000 + Primary type : Decay + Nuclide ZAI : 751900 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 189.96187 + Atomic weight ratio (AWR) : 188.33000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.86E+02 seconds (3.1 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.14000E+00 MeV frac = 1.00000E+00 Product nuclide = 761900 : beta- + + Nuclide 1499 / 1657 : 751901 -- rhenium 190m (Re-190m) + + Pointers : 2142222 -1000000 + Primary type : Decay + Nuclide ZAI : 751901 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 189.96187 + Atomic weight ratio (AWR) : 188.33000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.15E+04 seconds (3.2 hours) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.64090E+00 MeV frac = 5.44000E-01 Product nuclide = 761901 : beta- + 2 RTYP = 3 Q = 2.10000E-01 MeV frac = 4.56000E-01 Product nuclide = 751900 : IT + + Nuclide 1500 / 1657 : 751910 -- rhenium 191 (Re-191) + + Pointers : 2142479 -1000000 + Primary type : Decay + Nuclide ZAI : 751910 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 190.96348 + Atomic weight ratio (AWR) : 189.32300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.82E+02 seconds (9.7 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.97000E+00 MeV frac = 1.00000E+00 Product nuclide = 761910 : beta- + + Nuclide 1501 / 1657 : 751920 -- rhenium 192 (Re-192) + + Pointers : 2142696 -1000000 + Primary type : Decay + Nuclide ZAI : 751920 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 191.96609 + Atomic weight ratio (AWR) : 190.31700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.17400E+00 MeV frac = 1.00000E+00 Product nuclide = 761920 : beta- + + Nuclide 1502 / 1657 : 751930 -- rhenium 193 (Re-193) + + Pointers : 2143375 -1000000 + Primary type : Decay + Nuclide ZAI : 751930 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 192.96769 + Atomic weight ratio (AWR) : 191.31000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 30 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.09260E+00 MeV frac = 1.00000E+00 Product nuclide = 761930 : beta- + + Nuclide 1503 / 1657 : 751940 -- rhenium 194 (Re-194) + + Pointers : 2143559 -1000000 + Primary type : Decay + Nuclide ZAI : 751940 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 193.97031 + Atomic weight ratio (AWR) : 192.30400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.88270E+00 MeV frac = 1.00000E+00 Product nuclide = 761940 : beta- + + Nuclide 1504 / 1657 : 761860 -- osmium 186 (Os-186) + + Pointers : 2143743 -1000000 + Primary type : Decay + Nuclide ZAI : 761860 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 185.95344 + Atomic weight ratio (AWR) : 184.35600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.31E+22 seconds (2E+15 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 4 Q = 2.82310E+00 MeV frac = 1.00000E+00 Product nuclide = 74182.82c : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 2.82310E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 1505 / 1657 : 761870 -- osmium 187 (Os-187) + + Pointers : 2144000 -1000000 + Primary type : Decay + Nuclide ZAI : 761870 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 186.95605 + Atomic weight ratio (AWR) : 185.35000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1506 / 1657 : 761880 -- osmium 188 (Os-188) + + Pointers : 2144106 -1000000 + Primary type : Decay + Nuclide ZAI : 761880 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 187.95564 + Atomic weight ratio (AWR) : 186.34100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1507 / 1657 : 761890 -- osmium 189 (Os-189) + + Pointers : 2144212 -1000000 + Primary type : Decay + Nuclide ZAI : 761890 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 188.95825 + Atomic weight ratio (AWR) : 187.33500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1508 / 1657 : 761891 -- osmium 189m (Os-189m) + + Pointers : 2144318 -1000000 + Primary type : Decay + Nuclide ZAI : 761891 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 188.95825 + Atomic weight ratio (AWR) : 187.33500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.09E+04 seconds (5.81 hours) + Specific ingestion toxicity : 1.80E-11 Sv/Bq + Specific inhalation toxicity : 5.30E-12 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 3.08120E-02 MeV frac = 1.00000E+00 Product nuclide = 761890 : IT + + Nuclide 1509 / 1657 : 761900 -- osmium 190 (Os-190) + + Pointers : 2144633 -1000000 + Primary type : Decay + Nuclide ZAI : 761900 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 189.95885 + Atomic weight ratio (AWR) : 188.32700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1510 / 1657 : 761901 -- osmium 190m (Os-190m) + + Pointers : 2144739 -1000000 + Primary type : Decay + Nuclide ZAI : 761901 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 189.95885 + Atomic weight ratio (AWR) : 188.32700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.94E+02 seconds (9.9 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.70540E+00 MeV frac = 1.00000E+00 Product nuclide = 761900 : IT + + Nuclide 1511 / 1657 : 761910 -- osmium 191 (Os-191) + + Pointers : 2145348 -1000000 + Primary type : Decay + Nuclide ZAI : 761910 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 190.96146 + Atomic weight ratio (AWR) : 189.32100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.32E+06 seconds (15.3 days) + Specific ingestion toxicity : 5.70E-10 Sv/Bq + Specific inhalation toxicity : 1.90E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.41500E-01 MeV frac = 1.00000E+00 Product nuclide = 771911 : beta- + + Nuclide 1512 / 1657 : 761911 -- osmium 191m (Os-191m) + + Pointers : 2145565 -1000000 + Primary type : Decay + Nuclide ZAI : 761911 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 190.96146 + Atomic weight ratio (AWR) : 189.32100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.72E+04 seconds (13.1 hours) + Specific ingestion toxicity : 9.60E-11 Sv/Bq + Specific inhalation toxicity : 1.60E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 7.43820E-02 MeV frac = 1.00000E+00 Product nuclide = 761910 : IT + + Nuclide 1513 / 1657 : 761920 -- osmium 192 (Os-192) + + Pointers : 2145964 -1000000 + Primary type : Decay + Nuclide ZAI : 761920 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 191.96105 + Atomic weight ratio (AWR) : 190.31200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1514 / 1657 : 761921 -- osmium 192m (Os-192m) + + Pointers : 2146070 -1000000 + Primary type : Decay + Nuclide ZAI : 761921 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 191.96105 + Atomic weight ratio (AWR) : 190.31200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.9 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 2.01540E+00 MeV frac = 8.70000E-01 Product nuclide = 761920 : IT + 2 RTYP = 1 Q = 7.99962E-01 MeV frac = 1.30000E-01 Product nuclide = 771921 : beta- + + Nuclide 1515 / 1657 : 761930 -- osmium 193 (Os-193) + + Pointers : 2146327 -1000000 + Primary type : Decay + Nuclide ZAI : 761930 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 192.96366 + Atomic weight ratio (AWR) : 191.30600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.08E+05 seconds (1.25 days) + Specific ingestion toxicity : 8.10E-10 Sv/Bq + Specific inhalation toxicity : 5.20E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.14120E+00 MeV frac = 9.97348E-01 Product nuclide = 77193.82c : beta- + 2 RTYP = 1 Q = 1.06096E+00 MeV frac = 2.65208E-03 Product nuclide = 771931 : beta- + + Nuclide 1516 / 1657 : 761940 -- osmium 194 (Os-194) + + Pointers : 2148493 -1000000 + Primary type : Decay + Nuclide ZAI : 761940 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 193.96526 + Atomic weight ratio (AWR) : 192.29900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.89E+08 seconds (6 years) + Specific ingestion toxicity : 2.40E-09 Sv/Bq + Specific inhalation toxicity : 8.50E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 9.66000E-02 MeV frac = 1.00000E+00 Product nuclide = 771940 : beta- + + Nuclide 1517 / 1657 : 761950 -- osmium 195 (Os-195) + + Pointers : 2148976 -1000000 + Primary type : Decay + Nuclide ZAI : 761950 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 194.96788 + Atomic weight ratio (AWR) : 193.29300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.90E+02 seconds (6.5 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.00000E+00 MeV frac = 1.00000E+00 Product nuclide = 771950 : beta- + + Nuclide 1518 / 1657 : 761960 -- osmium 196 (Os-196) + + Pointers : 2150215 -1000000 + Primary type : Decay + Nuclide ZAI : 761960 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 195.96948 + Atomic weight ratio (AWR) : 194.28600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.09E+03 seconds (34.9 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.15800E+00 MeV frac = 1.00000E+00 Product nuclide = 771960 : beta- + + Nuclide 1519 / 1657 : 771890 -- iridium 189 (Ir-189) + + Pointers : 2151188 -1000000 + Primary type : Decay + Nuclide ZAI : 771890 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 188.95825 + Atomic weight ratio (AWR) : 187.33500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.14E+06 seconds (13.2 days) + Specific ingestion toxicity : 2.40E-10 Sv/Bq + Specific inhalation toxicity : 6.00E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 5.01000E-01 MeV frac = 7.50000E-02 Product nuclide = 761891 : EC/beta+ + 2 RTYP = 2 Q = 5.32000E-01 MeV frac = 9.25000E-01 Product nuclide = 761890 : EC/beta+ + + Nuclide 1520 / 1657 : 771891 -- iridium 189m (Ir-189m) + + Pointers : 2152906 -1000000 + Primary type : Decay + Nuclide ZAI : 771891 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 188.95825 + Atomic weight ratio (AWR) : 187.33500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 13.3 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 3.72170E-01 MeV frac = 1.00000E+00 Product nuclide = 771890 : IT + + Nuclide 1521 / 1657 : 771900 -- iridium 190 (Ir-190) + + Pointers : 2153090 -1000000 + Primary type : Decay + Nuclide ZAI : 771900 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 189.96086 + Atomic weight ratio (AWR) : 188.32900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.04E+06 seconds (12 days) + Specific ingestion toxicity : 1.20E-09 Sv/Bq + Specific inhalation toxicity : 2.40E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 2.08000E+00 MeV frac = 1.00000E+00 Product nuclide = 761900 : EC/beta+ + + Nuclide 1522 / 1657 : 771901 -- iridium 190m (Ir-190m) + + Pointers : 2156135 -1000000 + Primary type : Decay + Nuclide ZAI : 771901 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 189.96086 + Atomic weight ratio (AWR) : 188.32900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.03E+03 seconds (1.12 hours) + Specific ingestion toxicity : 1.20E-10 Sv/Bq + Specific inhalation toxicity : 8.30E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 2.61000E-02 MeV frac = 1.00000E+00 Product nuclide = 771900 : IT + + Nuclide 1523 / 1657 : 771902 -- iridium 190m (Ir-190m) + + Pointers : 3521867 -1000000 + Primary type : Decay + Nuclide ZAI : 771902 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 189.96086 + Atomic weight ratio (AWR) : 188.32900 + Temperature : 900.0 Kelvin + XS temperature : -1.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.11E+04 seconds (3.09 hours) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is not present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 3.76400E-01 MeV frac = 8.60000E-02 Product nuclide = 771900 : IT + 2 RTYP = 2 Q = 7.51000E-01 MeV frac = 9.14000E-01 Product nuclide = 761901 : EC/beta+ + + Nuclide 1524 / 1657 : 771911 -- iridium 191m (Ir-191m) + + Pointers : 2157802 -1000000 + Primary type : Decay + Nuclide ZAI : 771911 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 190.96045 + Atomic weight ratio (AWR) : 189.32000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.9 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.71240E-01 MeV frac = 1.00000E+00 Product nuclide = 77191.82c : IT + + Nuclide 1525 / 1657 : 771912 -- iridium 191m (Ir-191m) + + Pointers : 3522703 -1000000 + Primary type : Decay + Nuclide ZAI : 771912 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 190.96045 + Atomic weight ratio (AWR) : 189.32000 + Temperature : 900.0 Kelvin + XS temperature : -1.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.5 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is not present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.91400E+00 MeV frac = 1.00000E+00 Product nuclide = 771911 : IT + + Nuclide 1526 / 1657 : 771920 -- iridium 192 (Ir-192) + + Pointers : 2158341 -1000000 + Primary type : Decay + Nuclide ZAI : 771920 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 191.96306 + Atomic weight ratio (AWR) : 190.31400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.38E+06 seconds (73.8 days) + Specific ingestion toxicity : 1.40E-09 Sv/Bq + Specific inhalation toxicity : 6.60E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.45970E+00 MeV frac = 9.52000E-01 Product nuclide = 781920 : beta- + 2 RTYP = 2 Q = 1.04620E+00 MeV frac = 4.80000E-02 Product nuclide = 761920 : EC/beta+ + + Nuclide 1527 / 1657 : 771921 -- iridium 192m (Ir-192m) + + Pointers : 2160479 -1000000 + Primary type : Decay + Nuclide ZAI : 771921 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 191.96306 + Atomic weight ratio (AWR) : 190.31400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.64E+01 seconds (1.44 minutes) + Specific ingestion toxicity : 3.10E-10 Sv/Bq + Specific inhalation toxicity : 3.90E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.51640E+00 MeV frac = 1.75000E-04 Product nuclide = 781920 : beta- + 2 RTYP = 3 Q = 5.67200E-02 MeV frac = 9.99825E-01 Product nuclide = 771920 : IT + + Nuclide 1528 / 1657 : 771922 -- iridium 192m (Ir-192m) + + Pointers : 3519657 -1000000 + Primary type : Decay + Nuclide ZAI : 771922 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 191.96306 + Atomic weight ratio (AWR) : 190.31400 + Temperature : 900.0 Kelvin + XS temperature : -1.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.61E+09 seconds (241 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is not present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.68140E-01 MeV frac = 1.00000E+00 Product nuclide = 771920 : IT + + Nuclide 1529 / 1657 : 771931 -- iridium 193m (Ir-193m) + + Pointers : 2162555 -1000000 + Primary type : Decay + Nuclide ZAI : 771931 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 192.96265 + Atomic weight ratio (AWR) : 191.30500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.10E+05 seconds (10.5 days) + Specific ingestion toxicity : 2.70E-10 Sv/Bq + Specific inhalation toxicity : 1.30E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 8.02400E-02 MeV frac = 1.00000E+00 Product nuclide = 77193.82c : IT + + Nuclide 1530 / 1657 : 771940 -- iridium 194 (Ir-194) + + Pointers : 2162954 -1000000 + Primary type : Decay + Nuclide ZAI : 771940 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 193.96526 + Atomic weight ratio (AWR) : 192.29900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.95E+04 seconds (19.3 hours) + Specific ingestion toxicity : 1.30E-09 Sv/Bq + Specific inhalation toxicity : 5.60E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.24680E+00 MeV frac = 1.00000E+00 Product nuclide = 781940 : beta- + + Nuclide 1531 / 1657 : 771941 -- iridium 194m (Ir-194m) + + Pointers : 2165579 -1000000 + Primary type : Decay + Nuclide ZAI : 771941 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 193.96526 + Atomic weight ratio (AWR) : 192.29900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 31.8 milliseconds + Specific ingestion toxicity : 2.10E-09 Sv/Bq + Specific inhalation toxicity : 1.30E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.47072E-01 MeV frac = 1.00000E+00 Product nuclide = 771940 : IT + + Nuclide 1532 / 1657 : 771942 -- iridium 194m (Ir-194m) + + Pointers : 3520084 -1000000 + Primary type : Decay + Nuclide ZAI : 771942 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 193.96526 + Atomic weight ratio (AWR) : 192.29900 + Temperature : 900.0 Kelvin + XS temperature : -1.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.48E+07 seconds (171 days) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is not present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.50600E+00 MeV frac = 1.00000E+00 Product nuclide = 781940 : beta- + + Nuclide 1533 / 1657 : 771950 -- iridium 195 (Ir-195) + + Pointers : 2166384 -1000000 + Primary type : Decay + Nuclide ZAI : 771950 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 194.96586 + Atomic weight ratio (AWR) : 193.29100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.00E+03 seconds (2.5 hours) + Specific ingestion toxicity : 1.00E-10 Sv/Bq + Specific inhalation toxicity : 7.10E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.10700E+00 MeV frac = 1.00000E+00 Product nuclide = 781950 : beta- + + Nuclide 1534 / 1657 : 771951 -- iridium 195m (Ir-195m) + + Pointers : 2167007 -1000000 + Primary type : Decay + Nuclide ZAI : 771951 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 194.96586 + Atomic weight ratio (AWR) : 193.29100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.37E+04 seconds (3.8 hours) + Specific ingestion toxicity : 2.10E-10 Sv/Bq + Specific inhalation toxicity : 1.70E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 1 Q = 1.23000E+00 MeV frac = 6.46000E-01 Product nuclide = 781950 : beta- + 2 RTYP = 1 Q = 9.70700E-01 MeV frac = 3.04000E-01 Product nuclide = 781951 : beta- + 3 RTYP = 3 Q = 1.23000E-01 MeV frac = 5.00000E-02 Product nuclide = 771950 : IT + + Nuclide 1535 / 1657 : 771960 -- iridium 196 (Ir-196) + + Pointers : 2167337 -1000000 + Primary type : Decay + Nuclide ZAI : 771960 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 195.96847 + Atomic weight ratio (AWR) : 194.28500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 52 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.20900E+00 MeV frac = 1.00000E+00 Product nuclide = 781960 : beta- + + Nuclide 1536 / 1657 : 771961 -- iridium 196m (Ir-196m) + + Pointers : 2168296 -1000000 + Primary type : Decay + Nuclide ZAI : 771961 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 195.96847 + Atomic weight ratio (AWR) : 194.28500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.04E+03 seconds (1.4 hours) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 3.41740E+00 MeV frac = 9.97000E-01 Product nuclide = 781960 : beta- + 2 RTYP = 3 Q = 2.10000E-01 MeV frac = 3.00000E-03 Product nuclide = 771960 : IT + + Nuclide 1537 / 1657 : 771970 -- iridium 197 (Ir-197) + + Pointers : 2168553 -1000000 + Primary type : Decay + Nuclide ZAI : 771970 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 196.97008 + Atomic weight ratio (AWR) : 195.27800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.48E+02 seconds (5.8 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.15500E+00 MeV frac = 1.00000E+00 Product nuclide = 781970 : beta- + + Nuclide 1538 / 1657 : 771971 -- iridium 197m (Ir-197m) + + Pointers : 2171010 -1000000 + Primary type : Decay + Nuclide ZAI : 771971 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 196.97008 + Atomic weight ratio (AWR) : 195.27800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.34E+02 seconds (8.9 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 1.87000E+00 MeV frac = 9.97500E-01 Product nuclide = 781971 : beta- + 2 RTYP = 3 Q = 1.15000E-01 MeV frac = 2.50000E-03 Product nuclide = 771970 : IT + + Nuclide 1539 / 1657 : 781920 -- platinum 192 (Pt-192) + + Pointers : 2171496 -1000000 + Primary type : Decay + Nuclide ZAI : 781920 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 191.96105 + Atomic weight ratio (AWR) : 190.31200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1540 / 1657 : 781930 -- platinum 193 (Pt-193) + + Pointers : 2171602 -1000000 + Primary type : Decay + Nuclide ZAI : 781930 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 192.96265 + Atomic weight ratio (AWR) : 191.30500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.58E+09 seconds (50 years) + Specific ingestion toxicity : 3.10E-11 Sv/Bq + Specific inhalation toxicity : 2.10E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 5.66000E-02 MeV frac = 1.00000E+00 Product nuclide = 77193.82c : EC/beta+ + + Nuclide 1541 / 1657 : 781931 -- platinum 193m (Pt-193m) + + Pointers : 2171945 -1000000 + Primary type : Decay + Nuclide ZAI : 781931 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 192.96265 + Atomic weight ratio (AWR) : 191.30500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.75E+05 seconds (4.34 days) + Specific ingestion toxicity : 4.50E-10 Sv/Bq + Specific inhalation toxicity : 1.20E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.49780E-01 MeV frac = 1.00000E+00 Product nuclide = 781930 : IT + + Nuclide 1542 / 1657 : 781940 -- platinum 194 (Pt-194) + + Pointers : 2172386 -1000000 + Primary type : Decay + Nuclide ZAI : 781940 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 193.96224 + Atomic weight ratio (AWR) : 192.29600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1543 / 1657 : 781950 -- platinum 195 (Pt-195) + + Pointers : 2172492 -1000000 + Primary type : Decay + Nuclide ZAI : 781950 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 194.96485 + Atomic weight ratio (AWR) : 193.29000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1544 / 1657 : 781951 -- platinum 195m (Pt-195m) + + Pointers : 2172598 -1000000 + Primary type : Decay + Nuclide ZAI : 781951 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 194.96485 + Atomic weight ratio (AWR) : 193.29000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.54E+05 seconds (4.1 days) + Specific ingestion toxicity : 6.30E-10 Sv/Bq + Specific inhalation toxicity : 1.80E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 2.59300E-01 MeV frac = 1.00000E+00 Product nuclide = 781950 : IT + + Nuclide 1545 / 1657 : 781960 -- platinum 196 (Pt-196) + + Pointers : 2173403 -1000000 + Primary type : Decay + Nuclide ZAI : 781960 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 195.96545 + Atomic weight ratio (AWR) : 194.28200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1546 / 1657 : 781970 -- platinum 197 (Pt-197) + + Pointers : 2173509 -1000000 + Primary type : Decay + Nuclide ZAI : 781970 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 196.96705 + Atomic weight ratio (AWR) : 195.27500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.16E+04 seconds (19.9 hours) + Specific ingestion toxicity : 4.00E-10 Sv/Bq + Specific inhalation toxicity : 8.50E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 7.18900E-01 MeV frac = 1.00000E+00 Product nuclide = 79197.82c : beta- + + Nuclide 1547 / 1657 : 781971 -- platinum 197m (Pt-197m) + + Pointers : 2174048 -1000000 + Primary type : Decay + Nuclide ZAI : 781971 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 196.96705 + Atomic weight ratio (AWR) : 195.27500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.72E+03 seconds (1.59 hours) + Specific ingestion toxicity : 8.40E-11 Sv/Bq + Specific inhalation toxicity : 2.40E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 7.09300E-01 MeV frac = 3.30000E-02 Product nuclide = 791971 : beta- + 2 RTYP = 3 Q = 3.99590E-01 MeV frac = 9.67000E-01 Product nuclide = 781970 : IT + + Nuclide 1548 / 1657 : 781980 -- platinum 198 (Pt-198) + + Pointers : 2174576 -1000000 + Primary type : Decay + Nuclide ZAI : 781980 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 197.96765 + Atomic weight ratio (AWR) : 196.26700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1549 / 1657 : 781990 -- platinum 199 (Pt-199) + + Pointers : 2174682 -1000000 + Primary type : Decay + Nuclide ZAI : 781990 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 198.97026 + Atomic weight ratio (AWR) : 197.26100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.85E+03 seconds (30.8 minutes) + Specific ingestion toxicity : 3.90E-11 Sv/Bq + Specific inhalation toxicity : 1.20E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.70300E+00 MeV frac = 1.00000E+00 Product nuclide = 791990 : beta- + + Nuclide 1550 / 1657 : 781991 -- platinum 199m (Pt-199m) + + Pointers : 2177293 -1000000 + Primary type : Decay + Nuclide ZAI : 781991 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 198.97026 + Atomic weight ratio (AWR) : 197.26100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 13.6 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 4.24000E-01 MeV frac = 1.00000E+00 Product nuclide = 781990 : IT + + Nuclide 1551 / 1657 : 791950 -- gold 195 (Au-195) + + Pointers : 2177706 -1000000 + Primary type : Decay + Nuclide ZAI : 791950 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 194.95476 + Atomic weight ratio (AWR) : 193.28000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.61E+07 seconds (186 days) + Specific ingestion toxicity : 2.50E-10 Sv/Bq + Specific inhalation toxicity : 1.70E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 2.26800E-01 MeV frac = 1.00000E+00 Product nuclide = 781950 : EC/beta+ + + Nuclide 1552 / 1657 : 791960 -- gold 196 (Au-196) + + Pointers : 2178315 -1000000 + Primary type : Decay + Nuclide ZAI : 791960 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 195.96646 + Atomic weight ratio (AWR) : 194.28300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.33E+05 seconds (6.17 days) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 6.87000E-01 MeV frac = 7.00000E-02 Product nuclide = 801960 : beta- + 2 RTYP = 2 Q = 1.50700E+00 MeV frac = 9.30000E-01 Product nuclide = 781960 : EC/beta+ + + Nuclide 1553 / 1657 : 791961 -- gold 196m (Au-196m) + + Pointers : 2179837 -1000000 + Primary type : Decay + Nuclide ZAI : 791961 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 195.96646 + Atomic weight ratio (AWR) : 194.28300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.1 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 8.46600E-02 MeV frac = 1.00000E+00 Product nuclide = 791960 : IT + + Nuclide 1554 / 1657 : 791971 -- gold 197m (Au-197m) + + Pointers : 2182195 -1000000 + Primary type : Decay + Nuclide ZAI : 791971 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 196.96705 + Atomic weight ratio (AWR) : 195.27500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.74 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 4.09150E-01 MeV frac = 1.00000E+00 Product nuclide = 79197.82c : IT + + Nuclide 1555 / 1657 : 791980 -- gold 198 (Au-198) + + Pointers : 2182804 -1000000 + Primary type : Decay + Nuclide ZAI : 791980 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 197.96866 + Atomic weight ratio (AWR) : 196.26800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.33E+05 seconds (2.69 days) + Specific ingestion toxicity : 1.00E-09 Sv/Bq + Specific inhalation toxicity : 8.60E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.37280E+00 MeV frac = 1.00000E+00 Product nuclide = 80198.82c : beta- + + Nuclide 1556 / 1657 : 791981 -- gold 198m (Au-198m) + + Pointers : 2183357 -1000000 + Primary type : Decay + Nuclide ZAI : 791981 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 197.96866 + Atomic weight ratio (AWR) : 196.26800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.99E+05 seconds (2.3 days) + Specific ingestion toxicity : 1.30E-09 Sv/Bq + Specific inhalation toxicity : 2.00E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 8.12000E-01 MeV frac = 1.00000E+00 Product nuclide = 791980 : IT + + Nuclide 1557 / 1657 : 791990 -- gold 199 (Au-199) + + Pointers : 2183994 -1000000 + Primary type : Decay + Nuclide ZAI : 791990 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 198.96925 + Atomic weight ratio (AWR) : 197.26000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.71E+05 seconds (3.14 days) + Specific ingestion toxicity : 4.40E-10 Sv/Bq + Specific inhalation toxicity : 7.90E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.52300E-01 MeV frac = 1.00000E+00 Product nuclide = 80199.82c : beta- + + Nuclide 1558 / 1657 : 792000 -- gold 200 (Au-200) + + Pointers : 2184533 -1000000 + Primary type : Decay + Nuclide ZAI : 792000 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 199.97086 + Atomic weight ratio (AWR) : 198.25300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.90E+03 seconds (48.4 minutes) + Specific ingestion toxicity : 6.80E-11 Sv/Bq + Specific inhalation toxicity : 3.50E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.24000E+00 MeV frac = 1.00000E+00 Product nuclide = 80200.82c : beta- + + Nuclide 1559 / 1657 : 792001 -- gold 200m (Au-200m) + + Pointers : 2190966 -1000000 + Primary type : Decay + Nuclide ZAI : 792001 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 199.97086 + Atomic weight ratio (AWR) : 198.25300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.73E+04 seconds (18.7 hours) + Specific ingestion toxicity : 1.10E-09 Sv/Bq + Specific inhalation toxicity : 7.20E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 3.19410E+00 MeV frac = 8.20000E-01 Product nuclide = 80200.82c : beta- + 2 RTYP = 3 Q = 9.60000E-01 MeV frac = 1.80000E-01 Product nuclide = 792000 : IT + + Nuclide 1560 / 1657 : 801960 -- mercury 196 (Hg-196) + + Pointers : 2191223 -1000000 + Primary type : Decay + Nuclide ZAI : 801960 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 195.96545 + Atomic weight ratio (AWR) : 194.28200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.89E+25 seconds (2.5E+18 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 22 Q = 8.20704E-01 MeV frac = 1.00000E+00 Product nuclide = 781960 : EC/beta+ + EC/beta+ + + Nuclide 1561 / 1657 : 801970 -- mercury 197 (Hg-197) + + Pointers : 2191407 -1000000 + Primary type : Decay + Nuclide ZAI : 801970 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 196.96705 + Atomic weight ratio (AWR) : 195.27500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.33E+05 seconds (2.69 days) + Specific ingestion toxicity : 2.30E-10 Sv/Bq + Specific inhalation toxicity : 3.00E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 6.00000E-01 MeV frac = 1.00000E+00 Product nuclide = 79197.82c : EC/beta+ + + Nuclide 1562 / 1657 : 801991 -- mercury 199m (Hg-199m) + + Pointers : 2197474 -1000000 + Primary type : Decay + Nuclide ZAI : 801991 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 198.96824 + Atomic weight ratio (AWR) : 197.25900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.53E+03 seconds (42.1 minutes) + Specific ingestion toxicity : 3.10E-11 Sv/Bq + Specific inhalation toxicity : 3.20E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 5.32500E-01 MeV frac = 1.00000E+00 Product nuclide = 80199.82c : IT + + Nuclide 1563 / 1657 : 802010 -- mercury 201 (Hg-201) + + Pointers : 2202094 -1000000 + Primary type : Decay + Nuclide ZAI : 802010 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 200.97044 + Atomic weight ratio (AWR) : 199.24400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1564 / 1657 : 802060 -- mercury 206 (Hg-206) + + Pointers : 2202200 -1000000 + Primary type : Decay + Nuclide ZAI : 802060 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 205.97746 + Atomic weight ratio (AWR) : 204.20800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.99E+02 seconds (8.32 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.30800E+00 MeV frac = 1.00000E+00 Product nuclide = 812060 : beta- + + Nuclide 1565 / 1657 : 812050 -- thallium 205 (Tl-205) + + Pointers : 2202893 -1000000 + Primary type : Decay + Nuclide ZAI : 812050 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 204.97484 + Atomic weight ratio (AWR) : 203.21400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1566 / 1657 : 812060 -- thallium 206 (Tl-206) + + Pointers : 2202999 -1000000 + Primary type : Decay + Nuclide ZAI : 812060 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 205.97645 + Atomic weight ratio (AWR) : 204.20700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.52E+02 seconds (4.2 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.53240E+00 MeV frac = 1.00000E+00 Product nuclide = 822060 : beta- + + Nuclide 1567 / 1657 : 812070 -- thallium 207 (Tl-207) + + Pointers : 2203482 -1000000 + Primary type : Decay + Nuclide ZAI : 812070 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 206.97704 + Atomic weight ratio (AWR) : 205.19900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.86E+02 seconds (4.77 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.41800E+00 MeV frac = 1.00000E+00 Product nuclide = 822070 : beta- + + Nuclide 1568 / 1657 : 812080 -- thallium 208 (Tl-208) + + Pointers : 2204035 -1000000 + Primary type : Decay + Nuclide ZAI : 812080 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 207.98167 + Atomic weight ratio (AWR) : 206.19500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.83E+02 seconds (3.06 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.99900E+00 MeV frac = 1.00000E+00 Product nuclide = 822080 : beta- + + Nuclide 1569 / 1657 : 812090 -- thallium 209 (Tl-209) + + Pointers : 2206436 -1000000 + Primary type : Decay + Nuclide ZAI : 812090 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 208.98529 + Atomic weight ratio (AWR) : 207.19000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.30E+02 seconds (2.16 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.97600E+00 MeV frac = 1.00000E+00 Product nuclide = 822090 : beta- + + Nuclide 1570 / 1657 : 812100 -- thallium 210 (Tl-210) + + Pointers : 2207745 -1000000 + Primary type : Decay + Nuclide ZAI : 812100 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 209.98992 + Atomic weight ratio (AWR) : 208.18600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.80E+01 seconds (1.3 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.48200E+00 MeV frac = 1.00000E+00 Product nuclide = 822100 : beta- + + Nuclide 1571 / 1657 : 822060 -- lead 206 (Pb-206) + + Pointers : 2208564 -1000000 + Primary type : Decay + Nuclide ZAI : 822060 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 205.97443 + Atomic weight ratio (AWR) : 204.20500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1572 / 1657 : 822070 -- lead 207 (Pb-207) + + Pointers : 2208670 -1000000 + Primary type : Decay + Nuclide ZAI : 822070 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 206.97603 + Atomic weight ratio (AWR) : 205.19800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1573 / 1657 : 822080 -- lead 208 (Pb-208) + + Pointers : 2208776 -1000000 + Primary type : Decay + Nuclide ZAI : 822080 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 207.97663 + Atomic weight ratio (AWR) : 206.19000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : stable + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - No decay reactions + - No decay branch reactions + - No transmutation paths + + Nuclide 1574 / 1657 : 822090 -- lead 209 (Pb-209) + + Pointers : 2208882 -1000000 + Primary type : Decay + Nuclide ZAI : 822090 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 208.98126 + Atomic weight ratio (AWR) : 207.18600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.18E+04 seconds (3.28 hours) + Specific ingestion toxicity : 5.70E-11 Sv/Bq + Specific inhalation toxicity : 6.10E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 6.44000E-01 MeV frac = 1.00000E+00 Product nuclide = 832090 : beta- + + Nuclide 1575 / 1657 : 822100 -- lead 210 (Pb-210) + + Pointers : 2209099 -1000000 + Primary type : Decay + Nuclide ZAI : 822100 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 209.98387 + Atomic weight ratio (AWR) : 208.18000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.02E+08 seconds (22.2 years) + Specific ingestion toxicity : 6.90E-07 Sv/Bq + Specific inhalation toxicity : 5.60E-06 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 4 Q = 3.79200E+00 MeV frac = 1.90000E-08 Product nuclide = 802060 : alpha + 2 RTYP = 1 Q = 6.35000E-02 MeV frac = 1.00000E+00 Product nuclide = 832100 : beta- + + 1 additional decay branch: + + 1 RTYP = 4 Q = 3.79200E+00 MeV frac = 1.90000E-08 Product nuclide = 2004.82c : alpha + + Nuclide 1576 / 1657 : 822110 -- lead 211 (Pb-211) + + Pointers : 2209602 -1000000 + Primary type : Decay + Nuclide ZAI : 822110 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 210.98850 + Atomic weight ratio (AWR) : 209.17600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.17E+03 seconds (36.1 minutes) + Specific ingestion toxicity : 1.80E-10 Sv/Bq + Specific inhalation toxicity : 1.20E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.36700E+00 MeV frac = 1.00000E+00 Product nuclide = 832110 : beta- + + Nuclide 1577 / 1657 : 822120 -- lead 212 (Pb-212) + + Pointers : 2210897 -1000000 + Primary type : Decay + Nuclide ZAI : 822120 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 211.99212 + Atomic weight ratio (AWR) : 210.17100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.83E+04 seconds (10.6 hours) + Specific ingestion toxicity : 6.00E-09 Sv/Bq + Specific inhalation toxicity : 1.90E-07 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 5.69900E-01 MeV frac = 1.00000E+00 Product nuclide = 832120 : beta- + + Nuclide 1578 / 1657 : 822140 -- lead 214 (Pb-214) + + Pointers : 2211660 -1000000 + Primary type : Decay + Nuclide ZAI : 822140 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 213.99937 + Atomic weight ratio (AWR) : 212.16100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.61E+03 seconds (26.9 minutes) + Specific ingestion toxicity : 1.40E-10 Sv/Bq + Specific inhalation toxicity : 1.50E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.01900E+00 MeV frac = 1.00000E+00 Product nuclide = 832140 : beta- + + Nuclide 1579 / 1657 : 832090 -- bismuth 209 (Bi-209) + + Pointers : 2213095 -1000000 + Primary type : Decay + Nuclide ZAI : 832090 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 208.98025 + Atomic weight ratio (AWR) : 207.18500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.00E+26 seconds (1.9E+19 years) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 4 Q = 3.13720E+00 MeV frac = 1.00000E+00 Product nuclide = 812050 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 3.13720E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 1580 / 1657 : 832100 -- bismuth 210 (Bi-210) + + Pointers : 2213352 -1000000 + Primary type : Decay + Nuclide ZAI : 832100 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 209.98387 + Atomic weight ratio (AWR) : 208.18000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.33E+05 seconds (5.01 days) + Specific ingestion toxicity : 1.30E-09 Sv/Bq + Specific inhalation toxicity : 9.30E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 4 Q = 5.03650E+00 MeV frac = 1.40000E-06 Product nuclide = 812060 : alpha + 2 RTYP = 1 Q = 1.16120E+00 MeV frac = 9.99999E-01 Product nuclide = 842100 : beta- + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.03650E+00 MeV frac = 1.40000E-06 Product nuclide = 2004.82c : alpha + + Nuclide 1581 / 1657 : 832110 -- bismuth 211 (Bi-211) + + Pointers : 2213995 -1000000 + Primary type : Decay + Nuclide ZAI : 832110 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 210.98749 + Atomic weight ratio (AWR) : 209.17500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.29E+02 seconds (2.15 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 4 Q = 6.75033E+00 MeV frac = 9.97240E-01 Product nuclide = 812070 : alpha + 2 RTYP = 1 Q = 5.74000E-01 MeV frac = 2.76000E-03 Product nuclide = 842110 : beta- + + 1 additional decay branch: + + 1 RTYP = 4 Q = 6.75033E+00 MeV frac = 9.97240E-01 Product nuclide = 2004.82c : alpha + + Nuclide 1582 / 1657 : 832120 -- bismuth 212 (Bi-212) + + Pointers : 2214568 -1000000 + Primary type : Decay + Nuclide ZAI : 832120 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 211.99112 + Atomic weight ratio (AWR) : 210.17000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.63E+03 seconds (1.01 hours) + Specific ingestion toxicity : 2.60E-10 Sv/Bq + Specific inhalation toxicity : 3.10E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 4 Q = 6.20726E+00 MeV frac = 3.59300E-01 Product nuclide = 812080 : alpha + 2 RTYP = 1 Q = 2.25210E+00 MeV frac = 6.40700E-01 Product nuclide = 842120 : beta- + + 1 additional decay branch: + + 1 RTYP = 4 Q = 6.20726E+00 MeV frac = 3.59300E-01 Product nuclide = 2004.82c : alpha + + Nuclide 1583 / 1657 : 832130 -- bismuth 213 (Bi-213) + + Pointers : 2216793 -1000000 + Primary type : Decay + Nuclide ZAI : 832130 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 212.99474 + Atomic weight ratio (AWR) : 211.16500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.74E+03 seconds (45.6 minutes) + Specific ingestion toxicity : 2.00E-10 Sv/Bq + Specific inhalation toxicity : 3.00E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 4 Q = 5.98300E+00 MeV frac = 2.09000E-02 Product nuclide = 812090 : alpha + 2 RTYP = 1 Q = 1.42300E+00 MeV frac = 9.79100E-01 Product nuclide = 842130 : beta- + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.98300E+00 MeV frac = 2.09000E-02 Product nuclide = 2004.82c : alpha + + Nuclide 1584 / 1657 : 832140 -- bismuth 214 (Bi-214) + + Pointers : 2217996 -1000000 + Primary type : Decay + Nuclide ZAI : 832140 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 213.99836 + Atomic weight ratio (AWR) : 212.16000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.19E+03 seconds (19.8 minutes) + Specific ingestion toxicity : 1.10E-10 Sv/Bq + Specific inhalation toxicity : 1.40E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 4 Q = 5.62100E+00 MeV frac = 2.10000E-04 Product nuclide = 812100 : alpha + 2 RTYP = 1 Q = 3.27000E+00 MeV frac = 9.99790E-01 Product nuclide = 842140 : beta- + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.62100E+00 MeV frac = 2.10000E-04 Product nuclide = 2004.82c : alpha + + Nuclide 1585 / 1657 : 832150 -- bismuth 215 (Bi-215) + + Pointers : 2226605 -1000000 + Primary type : Decay + Nuclide ZAI : 832150 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 215.00198 + Atomic weight ratio (AWR) : 213.15500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.56E+02 seconds (7.6 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.18900E+00 MeV frac = 1.00000E+00 Product nuclide = 842150 : beta- + + Nuclide 1586 / 1657 : 842100 -- polonium 210 (Po-210) + + Pointers : 2227704 -1000000 + Primary type : Decay + Nuclide ZAI : 842100 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 209.98286 + Atomic weight ratio (AWR) : 208.17900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.20E+07 seconds (138 days) + Specific ingestion toxicity : 1.20E-06 Sv/Bq + Specific inhalation toxicity : 4.30E-06 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 4 Q = 5.40745E+00 MeV frac = 1.00000E+00 Product nuclide = 822060 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.40745E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 1587 / 1657 : 842110 -- polonium 211 (Po-211) + + Pointers : 2228190 -1000000 + Primary type : Decay + Nuclide ZAI : 842110 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 210.98649 + Atomic weight ratio (AWR) : 209.17400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.516 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 4 Q = 7.59450E+00 MeV frac = 1.00000E+00 Product nuclide = 822070 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 7.59450E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 1588 / 1657 : 842120 -- polonium 212 (Po-212) + + Pointers : 2228830 -1000000 + Primary type : Decay + Nuclide ZAI : 842120 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 211.98910 + Atomic weight ratio (AWR) : 210.16800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.3 microseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 4 Q = 8.95412E+00 MeV frac = 1.00000E+00 Product nuclide = 822080 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 8.95412E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 1589 / 1657 : 842130 -- polonium 213 (Po-213) + + Pointers : 2229120 -1000000 + Primary type : Decay + Nuclide ZAI : 842130 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 212.99272 + Atomic weight ratio (AWR) : 211.16300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.7 microseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 4 Q = 8.53610E+00 MeV frac = 1.00000E+00 Product nuclide = 822090 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 8.53610E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 1590 / 1657 : 842140 -- polonium 214 (Po-214) + + Pointers : 2229606 -1000000 + Primary type : Decay + Nuclide ZAI : 842140 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 213.99533 + Atomic weight ratio (AWR) : 212.15700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.162 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 4 Q = 7.83346E+00 MeV frac = 1.00000E+00 Product nuclide = 822100 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 7.83346E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 1591 / 1657 : 842150 -- polonium 215 (Po-215) + + Pointers : 2230176 -1000000 + Primary type : Decay + Nuclide ZAI : 842150 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 214.99896 + Atomic weight ratio (AWR) : 213.15200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.78 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 4 Q = 7.52630E+00 MeV frac = 9.99998E-01 Product nuclide = 822110 : alpha + 2 RTYP = 1 Q = 7.15000E-01 MeV frac = 2.30000E-06 Product nuclide = 852150 : beta- + + 1 additional decay branch: + + 1 RTYP = 4 Q = 7.52630E+00 MeV frac = 9.99998E-01 Product nuclide = 2004.82c : alpha + + Nuclide 1592 / 1657 : 842160 -- polonium 216 (Po-216) + + Pointers : 2230819 -1000000 + Primary type : Decay + Nuclide ZAI : 842160 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 216.00157 + Atomic weight ratio (AWR) : 214.14600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.148 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 4 Q = 6.90630E+00 MeV frac = 1.00000E+00 Product nuclide = 822120 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 6.90630E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 1593 / 1657 : 842180 -- polonium 218 (Po-218) + + Pointers : 2231305 -1000000 + Primary type : Decay + Nuclide ZAI : 842180 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 218.00881 + Atomic weight ratio (AWR) : 216.13600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.84E+02 seconds (3.07 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 4 Q = 6.11468E+00 MeV frac = 9.99780E-01 Product nuclide = 822140 : alpha + 2 RTYP = 1 Q = 2.60000E-01 MeV frac = 2.20000E-04 Product nuclide = 852180 : beta- + + 1 additional decay branch: + + 1 RTYP = 4 Q = 6.11468E+00 MeV frac = 9.99780E-01 Product nuclide = 2004.82c : alpha + + Nuclide 1594 / 1657 : 852150 -- astatine 215 (At-215) + + Pointers : 2231738 -1000000 + Primary type : Decay + Nuclide ZAI : 852150 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 214.99896 + Atomic weight ratio (AWR) : 213.15200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 100 microseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 4 Q = 8.17800E+00 MeV frac = 1.00000E+00 Product nuclide = 832110 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 8.17800E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 1595 / 1657 : 852170 -- astatine 217 (At-217) + + Pointers : 2232224 -1000000 + Primary type : Decay + Nuclide ZAI : 852170 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 217.00519 + Atomic weight ratio (AWR) : 215.14100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 32.3 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 4 Q = 7.20130E+00 MeV frac = 9.99933E-01 Product nuclide = 832130 : alpha + 2 RTYP = 1 Q = 7.37000E-01 MeV frac = 6.70000E-05 Product nuclide = 862170 : beta- + + 1 additional decay branch: + + 1 RTYP = 4 Q = 7.20130E+00 MeV frac = 9.99933E-01 Product nuclide = 2004.82c : alpha + + Nuclide 1596 / 1657 : 852180 -- astatine 218 (At-218) + + Pointers : 2232881 -1000000 + Primary type : Decay + Nuclide ZAI : 852180 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 218.00881 + Atomic weight ratio (AWR) : 216.13600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.4 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 4 Q = 6.87400E+00 MeV frac = 9.99000E-01 Product nuclide = 832140 : alpha + 2 RTYP = 1 Q = 2.88100E+00 MeV frac = 1.00000E-03 Product nuclide = 862180 : beta- + + 1 additional decay branch: + + 1 RTYP = 4 Q = 6.87400E+00 MeV frac = 9.99000E-01 Product nuclide = 2004.82c : alpha + + Nuclide 1597 / 1657 : 852190 -- astatine 219 (At-219) + + Pointers : 2233300 -1000000 + Primary type : Decay + Nuclide ZAI : 852190 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 219.01142 + Atomic weight ratio (AWR) : 217.13000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 56 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 4 Q = 6.32400E+00 MeV frac = 9.70000E-01 Product nuclide = 832150 : alpha + 2 RTYP = 1 Q = 1.56600E+00 MeV frac = 3.00000E-02 Product nuclide = 862190 : beta- + + 1 additional decay branch: + + 1 RTYP = 4 Q = 6.32400E+00 MeV frac = 9.70000E-01 Product nuclide = 2004.82c : alpha + + Nuclide 1598 / 1657 : 862160 -- radon 216 (Rn-216) + + Pointers : 2233691 -1000000 + Primary type : Decay + Nuclide ZAI : 862160 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 216.00056 + Atomic weight ratio (AWR) : 214.14500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 45 microseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 4 Q = 8.20050E+00 MeV frac = 1.00000E+00 Product nuclide = 842120 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 8.20050E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 1599 / 1657 : 862170 -- radon 217 (Rn-217) + + Pointers : 2233948 -1000000 + Primary type : Decay + Nuclide ZAI : 862170 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 217.00418 + Atomic weight ratio (AWR) : 215.14000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.54 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 4 Q = 7.88700E+00 MeV frac = 1.00000E+00 Product nuclide = 842130 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 7.88700E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 1600 / 1657 : 862180 -- radon 218 (Rn-218) + + Pointers : 2234238 -1000000 + Primary type : Decay + Nuclide ZAI : 862180 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 218.00579 + Atomic weight ratio (AWR) : 216.13300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 36 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 4 Q = 7.26250E+00 MeV frac = 1.00000E+00 Product nuclide = 842140 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 7.26250E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 1601 / 1657 : 862190 -- radon 219 (Rn-219) + + Pointers : 2234724 -1000000 + Primary type : Decay + Nuclide ZAI : 862190 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 219.00941 + Atomic weight ratio (AWR) : 217.12800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.98 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 4 Q = 6.94610E+00 MeV frac = 1.00000E+00 Product nuclide = 842150 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 6.94610E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 1602 / 1657 : 862200 -- radon 220 (Rn-220) + + Pointers : 2236162 -1000000 + Primary type : Decay + Nuclide ZAI : 862200 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 220.01101 + Atomic weight ratio (AWR) : 218.12100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 55.8 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 4 Q = 6.40467E+00 MeV frac = 1.00000E+00 Product nuclide = 842160 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 6.40467E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 1603 / 1657 : 862220 -- radon 222 (Rn-222) + + Pointers : 2236648 -1000000 + Primary type : Decay + Nuclide ZAI : 862220 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 222.01725 + Atomic weight ratio (AWR) : 220.11000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.30E+05 seconds (3.82 days) + Specific ingestion toxicity : 8.20E-08 Sv/Bq + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 4 Q = 5.59030E+00 MeV frac = 1.00000E+00 Product nuclide = 842180 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.59030E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 1604 / 1657 : 872210 -- francium 221 (Fr-221) + + Pointers : 2237148 -1000000 + Primary type : Decay + Nuclide ZAI : 872210 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 221.01463 + Atomic weight ratio (AWR) : 219.11600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.87E+02 seconds (4.79 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 4 Q = 6.45780E+00 MeV frac = 9.99952E-01 Product nuclide = 852170 : alpha + 2 RTYP = 1 Q = 3.14000E-01 MeV frac = 4.80000E-05 Product nuclide = 882210 : beta- + + 1 additional decay branch: + + 1 RTYP = 4 Q = 6.45780E+00 MeV frac = 9.99952E-01 Product nuclide = 2004.82c : alpha + + Nuclide 1605 / 1657 : 872220 -- francium 222 (Fr-222) + + Pointers : 2238911 -1000000 + Primary type : Decay + Nuclide ZAI : 872220 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 222.01725 + Atomic weight ratio (AWR) : 220.11000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.52E+02 seconds (14.2 minutes) + Specific ingestion toxicity : 7.20E-10 Sv/Bq + Specific inhalation toxicity : 1.40E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.03200E+00 MeV frac = 1.00000E+00 Product nuclide = 882220 : beta- + + Nuclide 1606 / 1657 : 872230 -- francium 223 (Fr-223) + + Pointers : 2240948 -1000000 + Primary type : Decay + Nuclide ZAI : 872230 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 223.01986 + Atomic weight ratio (AWR) : 221.10400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.32E+03 seconds (22 minutes) + Specific ingestion toxicity : 2.40E-09 Sv/Bq + Specific inhalation toxicity : 8.90E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 4 Q = 5.56200E+00 MeV frac = 2.00000E-04 Product nuclide = 852190 : alpha + 2 RTYP = 1 Q = 1.14920E+00 MeV frac = 9.99800E-01 Product nuclide = 882230 : beta- + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.56200E+00 MeV frac = 2.00000E-04 Product nuclide = 2004.82c : alpha + + Nuclide 1607 / 1657 : 872240 -- francium 224 (Fr-224) + + Pointers : 2246001 -1000000 + Primary type : Decay + Nuclide ZAI : 872240 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 224.02348 + Atomic weight ratio (AWR) : 222.09900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.00E+02 seconds (3.33 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.83000E+00 MeV frac = 1.00000E+00 Product nuclide = 882240 : beta- + + Nuclide 1608 / 1657 : 882200 -- radium 220 (Ra-220) + + Pointers : 2249298 -1000000 + Primary type : Decay + Nuclide ZAI : 882200 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 220.01101 + Atomic weight ratio (AWR) : 218.12100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 18 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 4 Q = 7.59200E+00 MeV frac = 1.00000E+00 Product nuclide = 862160 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 7.59200E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 1609 / 1657 : 882210 -- radium 221 (Ra-221) + + Pointers : 2249630 -1000000 + Primary type : Decay + Nuclide ZAI : 882210 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 221.01362 + Atomic weight ratio (AWR) : 219.11500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 28 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 4 Q = 6.88010E+00 MeV frac = 1.00000E+00 Product nuclide = 862170 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 6.88010E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 1610 / 1657 : 882220 -- radium 222 (Ra-222) + + Pointers : 2249887 -1000000 + Primary type : Decay + Nuclide ZAI : 882220 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 222.01523 + Atomic weight ratio (AWR) : 220.10800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 36.2 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 4 Q = 6.67900E+00 MeV frac = 1.00000E+00 Product nuclide = 862180 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 6.67900E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 1611 / 1657 : 882230 -- radium 223 (Ra-223) + + Pointers : 2250625 -1000000 + Primary type : Decay + Nuclide ZAI : 882230 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 223.01885 + Atomic weight ratio (AWR) : 221.10300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.88E+05 seconds (11.4 days) + Specific ingestion toxicity : 1.00E-07 Sv/Bq + Specific inhalation toxicity : 8.70E-06 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 4 Q = 5.97899E+00 MeV frac = 1.00000E+00 Product nuclide = 862190 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.97899E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 1612 / 1657 : 882240 -- radium 224 (Ra-224) + + Pointers : 2253841 -1000000 + Primary type : Decay + Nuclide ZAI : 882240 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 224.02045 + Atomic weight ratio (AWR) : 222.09600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.14E+05 seconds (3.63 days) + Specific ingestion toxicity : 6.50E-08 Sv/Bq + Specific inhalation toxicity : 3.40E-06 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 4 Q = 5.78885E+00 MeV frac = 1.00000E+00 Product nuclide = 862200 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.78885E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 1613 / 1657 : 882250 -- radium 225 (Ra-225) + + Pointers : 2254649 -1000000 + Primary type : Decay + Nuclide ZAI : 882250 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 225.02408 + Atomic weight ratio (AWR) : 223.09100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.28E+06 seconds (14.8 days) + Specific ingestion toxicity : 9.90E-08 Sv/Bq + Specific inhalation toxicity : 7.70E-06 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.56000E-01 MeV frac = 1.00000E+00 Product nuclide = 892250 : beta- + + Nuclide 1614 / 1657 : 882260 -- radium 226 (Ra-226) + + Pointers : 2255006 -1000000 + Primary type : Decay + Nuclide ZAI : 882260 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 226.02568 + Atomic weight ratio (AWR) : 224.08400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.05E+10 seconds (1,601 years) + Specific ingestion toxicity : 2.80E-07 Sv/Bq + Specific inhalation toxicity : 9.50E-06 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 4 Q = 4.87062E+00 MeV frac = 1.00000E+00 Product nuclide = 862220 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 4.87062E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 1615 / 1657 : 882280 -- radium 228 (Ra-228) + + Pointers : 2255814 -1000000 + Primary type : Decay + Nuclide ZAI : 882280 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 228.03091 + Atomic weight ratio (AWR) : 226.07200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.81E+08 seconds (5.75 years) + Specific ingestion toxicity : 6.90E-07 Sv/Bq + Specific inhalation toxicity : 1.60E-05 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 4.58000E-02 MeV frac = 1.00000E+00 Product nuclide = 892280 : beta- + + Nuclide 1616 / 1657 : 892250 -- actinium 225 (Ac-225) + + Pointers : 2256339 -1000000 + Primary type : Decay + Nuclide ZAI : 892250 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 225.02307 + Atomic weight ratio (AWR) : 223.09000 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.64E+05 seconds (10 days) + Specific ingestion toxicity : 2.40E-08 Sv/Bq + Specific inhalation toxicity : 8.50E-06 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 4 Q = 5.93510E+00 MeV frac = 1.00000E+00 Product nuclide = 872210 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.93510E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 1617 / 1657 : 892260 -- actinium 226 (Ac-226) + + Pointers : 2263713 -1000000 + Primary type : Decay + Nuclide ZAI : 892260 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 226.02568 + Atomic weight ratio (AWR) : 224.08400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.06E+05 seconds (1.22 days) + Specific ingestion toxicity : 1.00E-08 Sv/Bq + Specific inhalation toxicity : 1.30E-06 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 1 Q = 1.11300E+00 MeV frac = 8.29950E-01 Product nuclide = 902260 : beta- + 2 RTYP = 2 Q = 6.40902E-01 MeV frac = 1.69990E-01 Product nuclide = 882260 : EC/beta+ + 3 RTYP = 4 Q = 5.53610E+00 MeV frac = 5.99964E-05 Product nuclide = 872220 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.53610E+00 MeV frac = 5.99964E-05 Product nuclide = 2004.82c : alpha + + Nuclide 1618 / 1657 : 892270 -- actinium 227 (Ac-227) + + Pointers : 2264116 -1000000 + Primary type : Decay + Nuclide ZAI : 892270 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 227.02728 + Atomic weight ratio (AWR) : 225.07700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.87E+08 seconds (21.8 years) + Specific ingestion toxicity : 1.10E-06 Sv/Bq + Specific inhalation toxicity : 5.50E-04 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 4 Q = 5.04219E+00 MeV frac = 1.38000E-02 Product nuclide = 872230 : alpha + 2 RTYP = 1 Q = 4.48000E-02 MeV frac = 9.86200E-01 Product nuclide = 90227.82c : beta- + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.04219E+00 MeV frac = 1.38000E-02 Product nuclide = 2004.82c : alpha + + Nuclide 1619 / 1657 : 892280 -- actinium 228 (Ac-228) + + Pointers : 2267993 -1000000 + Primary type : Decay + Nuclide ZAI : 892280 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 228.03091 + Atomic weight ratio (AWR) : 226.07200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.21E+04 seconds (6.15 hours) + Specific ingestion toxicity : 4.30E-10 Sv/Bq + Specific inhalation toxicity : 2.50E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 4 Q = 4.81000E+00 MeV frac = 5.50000E-08 Product nuclide = 872240 : alpha + 2 RTYP = 1 Q = 2.12380E+00 MeV frac = 1.00000E+00 Product nuclide = 90228.82c : beta- + + 1 additional decay branch: + + 1 RTYP = 4 Q = 4.81000E+00 MeV frac = 5.50000E-08 Product nuclide = 2004.82c : alpha + + Nuclide 1620 / 1657 : 902240 -- thorium 224 (Th-224) + + Pointers : 2282370 -1000000 + Primary type : Decay + Nuclide ZAI : 902240 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 224.02146 + Atomic weight ratio (AWR) : 222.09700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.05 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 4 Q = 7.29800E+00 MeV frac = 1.00000E+00 Product nuclide = 882200 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 7.29800E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 1621 / 1657 : 902250 -- thorium 225 (Th-225) + + Pointers : 2283094 -1000000 + Primary type : Decay + Nuclide ZAI : 902250 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 225.02408 + Atomic weight ratio (AWR) : 223.09100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.23E+02 seconds (8.72 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 4 Q = 6.92110E+00 MeV frac = 9.00000E-01 Product nuclide = 882210 : alpha + 2 RTYP = 2 Q = 6.72001E-01 MeV frac = 1.00000E-01 Product nuclide = 892250 : EC/beta+ + + 1 additional decay branch: + + 1 RTYP = 4 Q = 6.92110E+00 MeV frac = 9.00000E-01 Product nuclide = 2004.82c : alpha + + Nuclide 1622 / 1657 : 902260 -- thorium 226 (Th-226) + + Pointers : 2283424 -1000000 + Primary type : Decay + Nuclide ZAI : 902260 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 226.02467 + Atomic weight ratio (AWR) : 224.08300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.83E+03 seconds (30.6 minutes) + Specific ingestion toxicity : 3.50E-10 Sv/Bq + Specific inhalation toxicity : 6.10E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 4 Q = 6.45090E+00 MeV frac = 1.00000E+00 Product nuclide = 882220 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 6.45090E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 1623 / 1657 : 902310 -- thorium 231 (Th-231) + + Pointers : 2412221 -1000000 + Primary type : Decay + Nuclide ZAI : 902310 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 231.03673 + Atomic weight ratio (AWR) : 229.05200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.19E+04 seconds (1.06 days) + Specific ingestion toxicity : 3.40E-10 Sv/Bq + Specific inhalation toxicity : 3.30E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.91600E-01 MeV frac = 1.00000E+00 Product nuclide = 91231.82c : beta- + + Nuclide 1624 / 1657 : 902320 -- thorium 232 (Th-232) + + Pointers : 2415574 -1000000 + Primary type : Decay + Nuclide ZAI : 902320 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 232.03833 + Atomic weight ratio (AWR) : 230.04500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.43E+17 seconds (14.1 billion years) + Specific ingestion toxicity : 2.30E-07 Sv/Bq + Specific inhalation toxicity : 1.10E-04 Sv/Bq + Spontaneous fission nubar : 1.50000 + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 4 Q = 4.08100E+00 MeV frac = 1.00000E+00 Product nuclide = 882280 : alpha + 2 RTYP = 6 Q = 1.69400E+02 MeV frac = 1.40000E-11 SF without yield : spontaneous fission + + 1 additional decay branch: + + 1 RTYP = 4 Q = 4.08100E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 1625 / 1657 : 902340 -- thorium 234 (Th-234) + + Pointers : 2416432 -1000000 + Primary type : Decay + Nuclide ZAI : 902340 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 234.04356 + Atomic weight ratio (AWR) : 232.03300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.08E+06 seconds (24.1 days) + Specific ingestion toxicity : 3.40E-09 Sv/Bq + Specific inhalation toxicity : 7.70E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.88000E-01 MeV frac = 1.00000E+00 Product nuclide = 912341 : beta- + + Nuclide 1626 / 1657 : 912290 -- protactinium 229 (Pa-229) + + Pointers : 2417307 -1000000 + Primary type : Decay + Nuclide ZAI : 912290 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 229.03251 + Atomic weight ratio (AWR) : 227.06500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.30E+05 seconds (1.5 days) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 4 Q = 5.83500E+00 MeV frac = 4.80000E-03 Product nuclide = 892250 : alpha + 2 RTYP = 2 Q = 3.11000E-01 MeV frac = 9.95200E-01 Product nuclide = 90229.82c : EC/beta+ + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.83500E+00 MeV frac = 4.80000E-03 Product nuclide = 2004.82c : alpha + + Nuclide 1627 / 1657 : 912300 -- protactinium 230 (Pa-230) + + Pointers : 2420106 -1000000 + Primary type : Decay + Nuclide ZAI : 912300 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 230.03412 + Atomic weight ratio (AWR) : 228.05800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.50E+06 seconds (17.4 days) + Specific ingestion toxicity : 9.20E-10 Sv/Bq + Specific inhalation toxicity : 7.60E-07 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 2 Q = 1.31100E+00 MeV frac = 9.15971E-01 Product nuclide = 90230.82c : EC/beta+ + 2 RTYP = 1 Q = 5.60001E-01 MeV frac = 8.39973E-02 Product nuclide = 922300 : beta- + 3 RTYP = 4 Q = 5.44010E+00 MeV frac = 3.19990E-05 Product nuclide = 892260 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.44010E+00 MeV frac = 3.19990E-05 Product nuclide = 2004.82c : alpha + + Nuclide 1628 / 1657 : 912340 -- protactinium 234 (Pa-234) + + Pointers : 2502799 -1000000 + Primary type : Decay + Nuclide ZAI : 912340 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 234.04356 + Atomic weight ratio (AWR) : 232.03300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.41E+04 seconds (6.7 hours) + Specific ingestion toxicity : 5.10E-10 Sv/Bq + Specific inhalation toxicity : 4.00E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.19500E+00 MeV frac = 1.00000E+00 Product nuclide = 92234.82c : beta- + + Nuclide 1629 / 1657 : 912341 -- protactinium 234m (Pa-234m) + + Pointers : 2520600 -1000000 + Primary type : Decay + Nuclide ZAI : 912341 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 234.04356 + Atomic weight ratio (AWR) : 232.03300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 6.95E+01 seconds (1.16 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 3 Q = 8.40000E-02 MeV frac = 1.50000E-03 Product nuclide = 912340 : IT + 2 RTYP = 1 Q = 2.27910E+00 MeV frac = 9.98500E-01 Product nuclide = 92234.82c : beta- + + Nuclide 1630 / 1657 : 922300 -- uranium 230 (U-230) + + Pointers : 2526812 -1000000 + Primary type : Decay + Nuclide ZAI : 922300 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 230.03412 + Atomic weight ratio (AWR) : 228.05800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.80E+06 seconds (20.8 days) + Specific ingestion toxicity : 5.60E-08 Sv/Bq + Specific inhalation toxicity : 1.60E-05 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 4 Q = 5.99270E+00 MeV frac = 1.00000E+00 Product nuclide = 902260 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.99270E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 1631 / 1657 : 922310 -- uranium 231 (U-231) + + Pointers : 2527718 -1000000 + Primary type : Decay + Nuclide ZAI : 922310 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 231.03673 + Atomic weight ratio (AWR) : 229.05200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.63E+05 seconds (4.2 days) + Specific ingestion toxicity : 2.80E-10 Sv/Bq + Specific inhalation toxicity : 5.20E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 3.81302E-01 MeV frac = 9.99960E-01 Product nuclide = 91231.82c : EC/beta+ + 2 RTYP = 4 Q = 5.57590E+00 MeV frac = 4.00000E-05 Product nuclide = 90227.82c : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.57590E+00 MeV frac = 4.00000E-05 Product nuclide = 2004.82c : alpha + + Nuclide 1632 / 1657 : 922351 -- uranium 235m (U-235m) + + Pointers : 2639217 -1000000 + Primary type : Decay + Nuclide ZAI : 922351 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 235.04415 + Atomic weight ratio (AWR) : 233.02500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.56E+03 seconds (26 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 7.68000E-05 MeV frac = 1.00000E+00 Product nuclide = 92235.82c : IT + + Nuclide 1633 / 1657 : 922390 -- uranium 239 (U-239) + + Pointers : 2700878 -1000000 + Primary type : Decay + Nuclide ZAI : 922390 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 239.05461 + Atomic weight ratio (AWR) : 237.00100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.41E+03 seconds (23.5 minutes) + Specific ingestion toxicity : 2.70E-11 Sv/Bq + Specific inhalation toxicity : 2.40E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.26150E+00 MeV frac = 1.00000E+00 Product nuclide = 93239.82c : beta- + + Nuclide 1634 / 1657 : 922400 -- uranium 240 (U-240) + + Pointers : 2705071 -1000000 + Primary type : Decay + Nuclide ZAI : 922400 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 240.05621 + Atomic weight ratio (AWR) : 237.99400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.08E+04 seconds (14.1 hours) + Specific ingestion toxicity : 1.10E-09 Sv/Bq + Specific inhalation toxicity : 5.80E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.90000E-01 MeV frac = 1.00000E+00 Product nuclide = 932400 : beta- + + Nuclide 1635 / 1657 : 932330 -- neptunium 233 (Np-233) + + Pointers : 2705456 -1000000 + Primary type : Decay + Nuclide ZAI : 932330 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 233.04095 + Atomic weight ratio (AWR) : 231.03900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.17E+03 seconds (36.2 minutes) + Specific ingestion toxicity : 2.20E-12 Sv/Bq + Specific inhalation toxicity : 1.70E-12 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 1.03000E+00 MeV frac = 1.00000E+00 Product nuclide = 92233.82c : EC/beta+ + + Nuclide 1636 / 1657 : 932340 -- neptunium 234 (Np-234) + + Pointers : 2706051 -1000000 + Primary type : Decay + Nuclide ZAI : 932340 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 234.04255 + Atomic weight ratio (AWR) : 232.03200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.80E+05 seconds (4.4 days) + Specific ingestion toxicity : 8.10E-10 Sv/Bq + Specific inhalation toxicity : 5.50E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 2 Q = 1.81000E+00 MeV frac = 1.00000E+00 Product nuclide = 92234.82c : EC/beta+ + + Nuclide 1637 / 1657 : 932361 -- neptunium 236m (Np-236m) + + Pointers : 2755876 -1000000 + Primary type : Decay + Nuclide ZAI : 932361 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 236.04677 + Atomic weight ratio (AWR) : 234.01900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.10E+04 seconds (22.5 hours) + Specific ingestion toxicity : 1.90E-10 Sv/Bq + Specific inhalation toxicity : 9.00E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 9.90000E-01 MeV frac = 5.30000E-01 Product nuclide = 92236.82c : EC/beta+ + 2 RTYP = 1 Q = 5.40000E-01 MeV frac = 4.70000E-01 Product nuclide = 94236.82c : beta- + + Nuclide 1638 / 1657 : 932400 -- neptunium 240 (Np-240) + + Pointers : 2819051 -1000000 + Primary type : Decay + Nuclide ZAI : 932400 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 240.05621 + Atomic weight ratio (AWR) : 237.99400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.90E+03 seconds (1.08 hours) + Specific ingestion toxicity : 8.20E-11 Sv/Bq + Specific inhalation toxicity : 9.00E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.19900E+00 MeV frac = 1.00000E+00 Product nuclide = 94240.82c : beta- + + Nuclide 1639 / 1657 : 932401 -- neptunium 240m (Np-240m) + + Pointers : 2820304 -1000000 + Primary type : Decay + Nuclide ZAI : 932401 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 240.05621 + Atomic weight ratio (AWR) : 237.99400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.44E+02 seconds (7.4 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 1 Q = 2.21900E+00 MeV frac = 9.98900E-01 Product nuclide = 94240.82c : beta- + 2 RTYP = 3 Q = 2.00000E-02 MeV frac = 1.10000E-03 Product nuclide = 932400 : IT + + Nuclide 1640 / 1657 : 942340 -- plutonium 234 (Pu-234) + + Pointers : 2823002 -1000000 + Primary type : Decay + Nuclide ZAI : 942340 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 234.04356 + Atomic weight ratio (AWR) : 232.03300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.17E+04 seconds (8.8 hours) + Specific ingestion toxicity : 1.60E-10 Sv/Bq + Specific inhalation toxicity : 2.40E-08 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 3.94001E-01 MeV frac = 9.40000E-01 Product nuclide = 932340 : EC/beta+ + 2 RTYP = 4 Q = 6.31010E+00 MeV frac = 6.00000E-02 Product nuclide = 922300 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 6.31010E+00 MeV frac = 6.00000E-02 Product nuclide = 2004.82c : alpha + + Nuclide 1641 / 1657 : 942350 -- plutonium 235 (Pu-235) + + Pointers : 2823332 -1000000 + Primary type : Decay + Nuclide ZAI : 942350 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 235.04516 + Atomic weight ratio (AWR) : 233.02600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.52E+03 seconds (25.3 minutes) + Specific ingestion toxicity : 2.10E-12 Sv/Bq + Specific inhalation toxicity : 1.50E-12 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 1.13930E+00 MeV frac = 9.99972E-01 Product nuclide = 93235.82c : EC/beta+ + 2 RTYP = 4 Q = 5.95210E+00 MeV frac = 2.80000E-05 Product nuclide = 922310 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.95210E+00 MeV frac = 2.80000E-05 Product nuclide = 2004.82c : alpha + + Nuclide 1642 / 1657 : 942371 -- plutonium 237m (Pu-237m) + + Pointers : 2872143 -1000000 + Primary type : Decay + Nuclide ZAI : 942371 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 237.04837 + Atomic weight ratio (AWR) : 235.01200 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 0.18 seconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.45544E-01 MeV frac = 1.00000E+00 Product nuclide = 94237.82c : IT + + Nuclide 1643 / 1657 : 942450 -- plutonium 245 (Pu-245) + + Pointers : 3025843 -1000000 + Primary type : Decay + Nuclide ZAI : 942450 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 245.06827 + Atomic weight ratio (AWR) : 242.96300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.78E+04 seconds (10.5 hours) + Specific ingestion toxicity : 7.20E-10 Sv/Bq + Specific inhalation toxicity : 4.30E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.28400E+00 MeV frac = 1.00000E+00 Product nuclide = 952450 : beta- + + Nuclide 1644 / 1657 : 942460 -- plutonium 246 (Pu-246) + + Pointers : 3028958 -1000000 + Primary type : Decay + Nuclide ZAI : 942460 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 246.06987 + Atomic weight ratio (AWR) : 243.95600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 9.37E+05 seconds (10.8 days) + Specific ingestion toxicity : 3.30E-09 Sv/Bq + Specific inhalation toxicity : 8.00E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 3.96000E-01 MeV frac = 1.00000E+00 Product nuclide = 952461 : beta- + + Nuclide 1645 / 1657 : 952380 -- americium 238 (Am-238) + + Pointers : 3029931 -1000000 + Primary type : Decay + Nuclide ZAI : 952380 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 238.05199 + Atomic weight ratio (AWR) : 236.00700 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 5.88E+03 seconds (1.63 hours) + Specific ingestion toxicity : 3.20E-11 Sv/Bq + Specific inhalation toxicity : 1.90E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 4 Q = 6.04000E+00 MeV frac = 1.00000E-06 Product nuclide = 932340 : alpha + 2 RTYP = 2 Q = 2.25800E+00 MeV frac = 1.00000E+00 Product nuclide = 94238.82c : EC/beta+ + + 1 additional decay branch: + + 1 RTYP = 4 Q = 6.04000E+00 MeV frac = 1.00000E-06 Product nuclide = 2004.82c : alpha + + Nuclide 1646 / 1657 : 952390 -- americium 239 (Am-239) + + Pointers : 3032268 -1000000 + Primary type : Decay + Nuclide ZAI : 952390 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 239.05259 + Atomic weight ratio (AWR) : 236.99900 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 4.28E+04 seconds (11.9 hours) + Specific ingestion toxicity : 2.40E-10 Sv/Bq + Specific inhalation toxicity : 2.40E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 8.02101E-01 MeV frac = 9.99900E-01 Product nuclide = 94239.82c : EC/beta+ + 2 RTYP = 4 Q = 5.92240E+00 MeV frac = 1.00000E-04 Product nuclide = 93235.82c : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.92240E+00 MeV frac = 1.00000E-04 Product nuclide = 2004.82c : alpha + + Nuclide 1647 / 1657 : 952400 -- americium 240 (Am-240) + + Pointers : 3032598 -1000000 + Primary type : Decay + Nuclide ZAI : 952400 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 240.05520 + Atomic weight ratio (AWR) : 237.99300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.83E+05 seconds (2.12 days) + Specific ingestion toxicity : 5.80E-10 Sv/Bq + Specific inhalation toxicity : 4.30E-10 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 1.37600E+00 MeV frac = 1.00000E+00 Product nuclide = 94240.82c : EC/beta+ + 2 RTYP = 4 Q = 5.70000E+00 MeV frac = 1.90000E-06 Product nuclide = 93236.82c : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.70000E+00 MeV frac = 1.90000E-06 Product nuclide = 2004.82c : alpha + + Nuclide 1648 / 1657 : 952450 -- americium 245 (Am-245) + + Pointers : 3183310 -1000000 + Primary type : Decay + Nuclide ZAI : 952450 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 245.06625 + Atomic weight ratio (AWR) : 242.96100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 7.38E+03 seconds (2.05 hours) + Specific ingestion toxicity : 6.20E-11 Sv/Bq + Specific inhalation toxicity : 5.60E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 8.96000E-01 MeV frac = 1.00000E+00 Product nuclide = 96245.82c : beta- + + Nuclide 1649 / 1657 : 952461 -- americium 246m (Am-246m) + + Pointers : 3184017 -1000000 + Primary type : Decay + Nuclide ZAI : 952461 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 246.06987 + Atomic weight ratio (AWR) : 243.95600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.50E+03 seconds (25 minutes) + Specific ingestion toxicity : 3.40E-11 Sv/Bq + Specific inhalation toxicity : 2.30E-11 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 2.38100E+00 MeV frac = 1.00000E+00 Product nuclide = 96246.82c : beta- + + Nuclide 1650 / 1657 : 962380 -- curium 238 (Cm-238) + + Pointers : 3189904 -1000000 + Primary type : Decay + Nuclide ZAI : 962380 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 238.05300 + Atomic weight ratio (AWR) : 236.00800 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 8.64E+03 seconds (2.4 hours) + Specific ingestion toxicity : 8.00E-11 Sv/Bq + Specific inhalation toxicity : 4.90E-09 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 9.80000E-01 MeV frac = 9.00000E-01 Product nuclide = 952380 : EC/beta+ + 2 RTYP = 4 Q = 6.62510E+00 MeV frac = 1.00000E-01 Product nuclide = 942340 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 6.62510E+00 MeV frac = 1.00000E-01 Product nuclide = 2004.82c : alpha + + Nuclide 1651 / 1657 : 962390 -- curium 239 (Cm-239) + + Pointers : 3190234 -1000000 + Primary type : Decay + Nuclide ZAI : 962390 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 239.05461 + Atomic weight ratio (AWR) : 237.00100 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.04E+04 seconds (2.9 hours) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 2 Q = 1.79800E+00 MeV frac = 9.99000E-01 Product nuclide = 952390 : EC/beta+ + 2 RTYP = 4 Q = 6.58110E+00 MeV frac = 1.00000E-03 Product nuclide = 942350 : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 6.58110E+00 MeV frac = 1.00000E-03 Product nuclide = 2004.82c : alpha + + Nuclide 1652 / 1657 : 962441 -- curium 244m (Cm-244m) + + Pointers : 3314003 -1000000 + Primary type : Decay + Nuclide ZAI : 962441 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 244.06263 + Atomic weight ratio (AWR) : 241.96600 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 34 milliseconds + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 3 Q = 1.04019E+00 MeV frac = 1.00000E+00 Product nuclide = 96244.82c : IT + + Nuclide 1653 / 1657 : 962510 -- curium 251 (Cm-251) + + Pointers : 3489899 -1000000 + Primary type : Decay + Nuclide ZAI : 962510 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 251.08193 + Atomic weight ratio (AWR) : 248.92500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.01E+03 seconds (16.8 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is produced in transmutation + - Nuclide is not produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.42000E+00 MeV frac = 1.00000E+00 Product nuclide = 972510 : beta- + + Nuclide 1654 / 1657 : 972490 -- berkelium 249 (Bk-249) + + Pointers : 3491152 -1000000 + Primary type : Decay + Nuclide ZAI : 972490 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 249.07468 + Atomic weight ratio (AWR) : 246.93500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.76E+07 seconds (320 days) + Specific ingestion toxicity : 9.70E-10 Sv/Bq + Specific inhalation toxicity : 1.60E-07 Sv/Bq + Spontaneous fission nubar : 3.40000 + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 3 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 3 decay reactions: + + 1 RTYP = 1 Q = 1.25000E-01 MeV frac = 9.99986E-01 Product nuclide = 982490 : beta- + 2 RTYP = 4 Q = 5.52600E+00 MeV frac = 1.45000E-05 Product nuclide = 952450 : alpha + 3 RTYP = 6 Q = 1.92700E+02 MeV frac = 4.69000E-10 SF without yield : spontaneous fission + + 1 additional decay branch: + + 1 RTYP = 4 Q = 5.52600E+00 MeV frac = 1.45000E-05 Product nuclide = 2004.82c : alpha + + Nuclide 1655 / 1657 : 972510 -- berkelium 251 (Bk-251) + + Pointers : 3492293 -1000000 + Primary type : Decay + Nuclide ZAI : 972510 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 251.08092 + Atomic weight ratio (AWR) : 248.92400 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 3.34E+03 seconds (55.6 minutes) + Specific ingestion toxicity : N/A + Specific inhalation toxicity : N/A + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - No decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 1 Q = 1.09300E+00 MeV frac = 1.00000E+00 Product nuclide = 982510 : beta- + + Nuclide 1656 / 1657 : 982490 -- californium 249 (Cf-249) + + Pointers : 3492477 -1000000 + Primary type : Decay + Nuclide ZAI : 982490 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 249.07468 + Atomic weight ratio (AWR) : 246.93500 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 1.11E+10 seconds (351 years) + Specific ingestion toxicity : 3.50E-07 Sv/Bq + Specific inhalation toxicity : 7.00E-05 Sv/Bq + Spontaneous fission nubar : 3.40000 + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 2 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 2 decay reactions: + + 1 RTYP = 4 Q = 6.29560E+00 MeV frac = 1.00000E+00 Product nuclide = 96245.82c : alpha + 2 RTYP = 6 Q = 1.96000E+02 MeV frac = 5.20000E-09 SF without yield : spontaneous fission + + 1 additional decay branch: + + 1 RTYP = 4 Q = 6.29560E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + Nuclide 1657 / 1657 : 982510 -- californium 251 (Cf-251) + + Pointers : 3495099 -1000000 + Primary type : Decay + Nuclide ZAI : 982510 + Library ID : 82c + Cross section data file : N/A + Atomic weight (AW) : 251.07991 + Atomic weight ratio (AWR) : 248.92300 + Temperature : 900.0 Kelvin + XS temperature : 900.0 Kelvin + Minimum and maximum energy : 0.00000E+00 0.00000E+00 + Half-life : 2.83E+10 seconds (899 years) + Specific ingestion toxicity : 3.60E-07 Sv/Bq + Specific inhalation toxicity : 7.10E-05 Sv/Bq + + - Nuclide is present in initial composition + - Nuclide is not produced in transmustation + - Nuclide is produced in decay + - Nuclide is not produced in fission + - Nuclide has no neutron transport data + - Nuclide has no photon transport data + - Nuclide has no S(a,b) data + - Nuclide has no isomeric branching data + - Nuclide is not fissile + - Nuclide is not a delayed neutron precursor + - Nuclide has no delayed neutron data + - Nuclide has no ures ptable data + - Nuclide temperature is not adjusted with TMS + - Nuclide has no dosimetry data + - Nuclide has decay data + - Nuclide has no supplementary transmutation cross section data + - Nuclide has no NFY data + - Nuclide has no SFY data + + - No reaction channels + - No special reactions + - No transmutation reactions + - No transmutation branch reactions + - 1 decay reactions + - 1 decay branch reactions + - No transmutation paths + - All reaction paths linked to target + + 1 decay reaction: + + 1 RTYP = 4 Q = 6.17240E+00 MeV frac = 1.00000E+00 Product nuclide = 96247.82c : alpha + + 1 additional decay branch: + + 1 RTYP = 4 Q = 6.17240E+00 MeV frac = 1.00000E+00 Product nuclide = 2004.82c : alpha + + --- Table 3: Fission yield data: + + Nuclide 90227.82c -- thorium 227 (Th-227) is using NFY data from U-233 + + Nuclide 90228.82c -- thorium 228 (Th-228) is using NFY data from U-233 + + Nuclide 90229.82c -- thorium 229 (Th-229) is using NFY data from U-233 + + Nuclide 90230.82c -- thorium 230 (Th-230) is using NFY data from U-233 + + Nuclide 91231.82c -- protactinium 231 (Pa-231) is using NFY data from U-233 + + Nuclide 91232.82c -- protactinium 232 (Pa-232) is using NFY data from U-233 + + Nuclide 91233.82c -- protactinium 233 (Pa-233) is using NFY data from Th-232 + + Nuclide 92232.82c -- uranium 232 (U-232) is using NFY data from U-233 + + Nuclide 92233.82c -- uranium 233 (U-233) + + Neutron-induced fission: + + Interpolation region : 1 / 3 + Interpolation energy : 2.53000E-08 MeV + Number of products : 901 / 966 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 3.33770E-05 3.33770E-05 1001.82c + 2 10020 H-2 8.46600E-06 8.46600E-06 1002.82c + 3 10030 H-3 1.14000E-04 1.14000E-04 1003.82c + 4 20040 He-4 2.11000E-03 2.11110E-03 2004.82c + 5 20060 He-6 2.15300E-05 2.15300E-05 20060 + 6 20080 He-8 3.71700E-07 3.71700E-07 20080 + 7 30070 Li-7 7.64000E-07 8.08600E-07 3007.82c + 8 30080 Li-8 3.71700E-07 6.98800E-07 30080 + 9 30090 Li-9 7.43400E-07 7.43400E-07 30090 + 10 40090 Be-9 7.43400E-07 1.11880E-06 4009.82c + 11 40100 Be-10 8.88000E-06 8.88000E-06 40100 + 12 240590 Cr-59 2.37470E-12 2.37470E-12 240590 + 13 240600 Cr-60 6.31200E-12 6.31200E-12 240600 + 14 240610 Cr-61 5.49010E-12 5.49010E-12 240610 + 15 240620 Cr-62 6.35880E-12 6.35880E-12 240620 + 16 240630 Cr-63 2.06430E-12 2.06430E-12 240630 + 17 250590 Mn-59 1.01890E-12 3.39360E-12 250590 + 18 250600 Mn-60 4.06800E-13 7.13430E-12 250600 + 19 250601 Mn-60m 3.61300E-12 3.61300E-12 250601 + 20 250610 Mn-61 2.15490E-11 2.70390E-11 250610 + 21 250620 Mn-62 3.32050E-11 3.63840E-11 250620 + 22 250621 Mn-62m 5.96110E-12 9.14050E-12 250621 + 23 250630 Mn-63 8.89450E-11 9.10090E-11 250630 + 24 250640 Mn-64 5.47820E-11 5.47820E-11 250640 + 25 250650 Mn-65 5.28980E-11 5.28980E-11 250650 + 26 250660 Mn-66 1.41450E-11 1.41450E-11 250660 + 27 250670 Mn-67 3.90080E-12 3.90080E-12 250670 + 28 260610 Fe-61 3.49680E-12 3.05360E-11 260610 + 29 260620 Fe-62 3.97980E-11 8.53230E-11 260620 + 30 260630 Fe-63 1.33460E-10 2.24470E-10 260630 + 31 260640 Fe-64 5.16790E-10 5.71570E-10 260640 + 32 260650 Fe-65 8.10580E-10 8.63480E-10 260650 + 33 260660 Fe-66 1.57020E-09 1.58440E-09 260660 + 34 260670 Fe-67 8.07700E-10 8.11600E-10 260670 + 35 260680 Fe-68 5.15770E-10 5.15770E-10 260680 + 36 260690 Fe-69 1.12320E-10 1.12320E-10 260690 + 37 260700 Fe-70 2.40810E-11 2.40810E-11 260700 + 38 260710 Fe-71 1.55530E-12 1.55530E-12 260710 + 39 270630 Co-63 1.70320E-11 2.41500E-10 270630 + 40 270640 Co-64 1.02950E-10 6.74520E-10 270640 + 41 270650 Co-65 9.92920E-10 1.85640E-09 270650 + 42 270660 Co-66 2.86100E-09 4.44540E-09 270660 + 43 270670 Co-67 9.52140E-09 1.03330E-08 270670 + 44 270680 Co-68 5.44100E-09 8.10280E-09 270680 + 45 270681 Co-68m 4.80000E-09 5.32360E-09 270681 + 46 270690 Co-69 1.66830E-08 1.67880E-08 270690 + 47 270700 Co-70 3.41640E-09 3.41640E-09 270700 + 48 270701 Co-70m 3.41640E-09 3.44050E-09 270701 + 49 270710 Co-71 3.60750E-09 3.60910E-09 270710 + 50 270720 Co-72 2.00740E-10 2.00740E-10 270720 + 51 270730 Co-73 1.09180E-10 1.09180E-10 270730 + 52 270740 Co-74 4.49020E-12 4.49020E-12 270740 + 53 280640 Ni-64 2.73380E-12 6.77260E-10 28064.82c + 54 280650 Ni-65 4.60790E-11 1.90250E-09 280650 + 55 280660 Ni-66 8.90390E-10 5.33570E-09 280660 + 56 280670 Ni-67 4.49660E-09 1.48300E-08 280670 + 57 280680 Ni-68 2.95430E-08 4.04750E-08 280680 + 58 280690 Ni-69 3.64730E-08 5.30930E-08 280690 + 59 280691 Ni-69m 3.64730E-08 3.64730E-08 280691 + 60 280700 Ni-70 2.00010E-07 2.06870E-07 280700 + 61 280710 Ni-71 1.84240E-07 1.87850E-07 280710 + 62 280720 Ni-72 7.88920E-08 7.90930E-08 280720 + 63 280730 Ni-73 8.36330E-08 8.37420E-08 280730 + 64 280740 Ni-74 2.94680E-08 2.94730E-08 280740 + 65 280750 Ni-75 3.25740E-09 3.25740E-09 280750 + 66 280760 Ni-76 3.59450E-10 3.59450E-10 280760 + 67 280770 Ni-77 1.03520E-11 1.03520E-11 280770 + 68 290660 Cu-66 4.15910E-12 5.33990E-09 290660 + 69 290670 Cu-67 1.57350E-10 1.49870E-08 290670 + 70 290680 Cu-68 5.21920E-10 4.20240E-08 290680 + 71 290681 Cu-68m 1.22250E-09 1.22250E-09 290681 + 72 290690 Cu-69 2.79100E-08 1.17480E-07 290690 + 73 290700 Cu-70 8.66860E-09 6.23430E-08 290700 + 74 290701 Cu-70m 9.65730E-08 1.07350E-07 290701 + 75 290702 Cu-70m 8.66860E-09 2.15540E-07 290702 + 76 290710 Cu-71 6.44800E-07 8.32650E-07 290710 + 77 290720 Cu-72 4.30310E-07 5.09400E-07 290720 + 78 290730 Cu-73 2.69210E-06 2.77580E-06 290730 + 79 290740 Cu-74 2.01080E-06 2.04030E-06 290740 + 80 290750 Cu-75 1.31000E-06 1.31320E-06 290750 + 81 290760 Cu-76 1.91340E-07 1.91520E-07 290760 + 82 290761 Cu-76m 1.91340E-07 1.91520E-07 290761 + 83 290770 Cu-77 1.35850E-07 1.35860E-07 290770 + 84 290780 Cu-78 7.00660E-09 7.00660E-09 290780 + 85 290790 Cu-79 5.32180E-10 5.32180E-10 290790 + 86 300680 Zn-68 1.14110E-11 4.22310E-08 300680 + 87 300690 Zn-69 6.40300E-11 1.17820E-07 300690 + 88 300691 Zn-69m 2.76920E-10 2.76920E-10 300691 + 89 300700 Zn-70 1.00970E-08 3.30870E-07 300700 + 90 300710 Zn-71 1.74670E-08 8.50120E-07 300710 + 91 300711 Zn-71m 7.55430E-08 7.55430E-08 300711 + 92 300720 Zn-72 9.28880E-07 1.43830E-06 300720 + 93 300730 Zn-73 5.32520E-07 6.09830E-06 300730 + 94 300731 Zn-73m 7.27970E-07 2.78990E-06 300731 + 95 300732 Zn-73m 4.12390E-06 4.12390E-06 300732 + 96 300740 Zn-74 1.71190E-05 1.92050E-05 300740 + 97 300750 Zn-75 3.27430E-05 3.40160E-05 300750 + 98 300760 Zn-76 4.60910E-05 4.64680E-05 300760 + 99 300770 Zn-77 3.61860E-05 3.90880E-05 300770 + 100 300771 Zn-77m 5.53180E-06 5.53180E-06 300771 + 101 300780 Zn-78 2.94690E-05 2.94760E-05 300780 + 102 300790 Zn-79 6.32060E-06 6.32080E-06 300790 + 103 300800 Zn-80 2.38020E-06 2.38020E-06 300800 + 104 300810 Zn-81 9.51700E-09 9.51700E-09 300810 + 105 300820 Zn-82 4.48790E-10 4.48790E-10 300820 + 106 310700 Ga-70 1.13060E-11 1.13060E-11 310700 + 107 310710 Ga-71 8.25550E-10 9.26480E-07 310710 + 108 310720 Ga-72 5.66270E-09 1.44460E-06 310720 + 109 310721 Ga-72m 6.37590E-10 4.85620E-08 310721 + 110 310730 Ga-73 4.79750E-07 8.64000E-06 310730 + 111 310740 Ga-74 1.22280E-06 1.65440E-05 310740 + 112 310741 Ga-74m 1.22280E-06 2.04280E-05 310741 + 113 310750 Ga-75 1.31020E-05 4.71180E-05 310750 + 114 310760 Ga-76 4.96810E-05 9.61490E-05 310760 + 115 310770 Ga-77 1.69750E-04 2.11600E-04 310770 + 116 310780 Ga-78 1.11690E-04 1.41250E-04 310780 + 117 310790 Ga-79 1.69260E-04 1.75500E-04 310790 + 118 310800 Ga-80 7.25010E-05 7.48820E-05 310800 + 119 310810 Ga-81 3.21550E-05 3.21640E-05 310810 + 120 310820 Ga-82 3.83420E-06 3.83460E-06 310820 + 121 310830 Ga-83 1.91330E-07 1.91330E-07 310830 + 122 310840 Ga-84 5.59290E-09 5.59290E-09 310840 + 123 320720 Ge-72 9.66930E-12 1.44460E-06 32072.82c + 124 320730 Ge-73 1.16900E-09 8.64140E-06 32073.82c + 125 320731 Ge-73m 2.70300E-10 8.51340E-06 320731 + 126 320740 Ge-74 6.96290E-08 2.17200E-05 32074.82c + 127 320750 Ge-75 6.94930E-07 5.23570E-05 320750 + 128 320751 Ge-75m 4.54590E-06 6.43060E-06 320751 + 129 320760 Ge-76 2.48490E-05 1.21000E-04 32076.82c + 130 320770 Ge-77 1.43810E-04 1.88190E-04 320770 + 131 320771 Ge-77m 2.19840E-05 2.33590E-04 320771 + 132 320780 Ge-78 4.55250E-04 5.96650E-04 320780 + 133 320790 Ge-79 1.25770E-04 3.33760E-04 320790 + 134 320791 Ge-79m 8.22690E-04 8.22960E-04 320791 + 135 320800 Ge-80 1.66210E-03 1.74080E-03 320800 + 136 320810 Ge-81 1.11820E-03 1.13630E-03 320810 + 137 320811 Ge-81m 2.58560E-04 2.72340E-04 320811 + 138 320820 Ge-82 9.73420E-04 9.76510E-04 320820 + 139 320830 Ge-83 2.33530E-04 2.33650E-04 320830 + 140 320840 Ge-84 5.02130E-05 5.02150E-05 320840 + 141 320850 Ge-85 9.45350E-06 9.45350E-06 320850 + 142 320860 Ge-86 1.09620E-06 1.09620E-06 320860 + 143 320870 Ge-87 2.09770E-09 2.09770E-09 320870 + 144 330740 As-74 1.79610E-11 1.79610E-11 330740 + 145 330750 As-75 5.27640E-10 5.23610E-05 33075.82c + 146 330751 As-75m 1.72630E-09 3.65540E-09 330751 + 147 330760 As-76 6.81610E-08 6.81610E-08 330760 + 148 330770 As-77 4.31960E-06 3.81710E-04 330770 + 149 330780 As-78 2.58130E-05 6.22470E-04 330780 + 150 330790 As-79 1.20300E-04 1.24410E-03 330790 + 151 330800 As-80 6.51380E-04 2.39220E-03 330800 + 152 330810 As-81 1.59110E-03 2.99700E-03 330810 + 153 330820 As-82 5.31600E-04 1.50810E-03 330820 + 154 330821 As-82m 1.60420E-03 1.60420E-03 330821 + 155 330830 As-83 2.52180E-03 2.76090E-03 330830 + 156 330840 As-84 6.65400E-04 6.88460E-04 330840 + 157 330841 As-84m 6.65400E-04 6.88460E-04 330841 + 158 330850 As-85 8.04600E-04 8.12730E-04 330850 + 159 330860 As-86 1.75050E-04 1.76150E-04 330860 + 160 330870 As-87 6.37110E-05 6.37130E-05 330870 + 161 330880 As-88 6.55810E-06 6.55810E-06 330880 + 162 330890 As-89 1.14750E-06 1.14750E-06 330890 + 163 340760 Se-76 2.33410E-11 6.81840E-08 34076.82c + 164 340770 Se-77 3.08850E-10 3.81720E-04 34077.82c + 165 340771 Se-77m 2.02030E-09 2.02030E-09 340771 + 166 340780 Se-78 1.36100E-07 6.22600E-04 34078.82c + 167 340790 Se-79 5.48610E-06 1.24970E-03 34079.82c + 168 340791 Se-79m 8.38670E-07 1.21550E-03 340791 + 169 340800 Se-80 1.14010E-04 2.50620E-03 34080.82c + 170 340810 Se-81 9.74860E-05 3.73190E-03 340810 + 171 340811 Se-81m 6.37700E-04 7.45290E-04 340811 + 172 340820 Se-82 2.72300E-03 5.83530E-03 34082.82c + 173 340830 Se-83 6.09840E-03 7.09330E-03 340830 + 174 340831 Se-83m 1.41010E-03 3.17800E-03 340831 + 175 340840 Se-84 1.36590E-02 1.52130E-02 340840 + 176 340850 Se-85 1.24580E-02 1.31500E-02 340850 + 177 340860 Se-86 9.46630E-03 9.59410E-03 340860 + 178 340870 Se-87 4.20600E-03 4.25990E-03 340870 + 179 340880 Se-88 1.60130E-03 1.60790E-03 340880 + 180 340890 Se-89 2.94150E-04 2.95300E-04 340890 + 181 340900 Se-90 6.53360E-05 6.53360E-05 340900 + 182 340910 Se-91 2.40160E-07 2.40160E-07 340910 + 183 340920 Se-92 7.54730E-09 7.54730E-09 340920 + 184 350780 Br-78 1.42690E-11 1.42690E-11 350780 + 185 350790 Br-79 3.16250E-10 6.82020E-07 35079.82c + 186 350791 Br-79m 1.03460E-09 1.03460E-09 350791 + 187 350800 Br-80 1.60340E-08 6.44200E-08 350800 + 188 350801 Br-80m 4.83860E-08 4.83860E-08 350801 + 189 350810 Br-81 5.36730E-06 3.73760E-03 35081.82c + 190 350820 Br-82 2.15450E-05 3.05230E-05 350820 + 191 350821 Br-82m 9.19860E-06 9.19860E-06 350821 + 192 350830 Br-83 3.14280E-04 1.05860E-02 350830 + 193 350840 Br-84 8.56700E-04 1.60700E-02 350840 + 194 350841 Br-84m 8.56700E-04 8.56700E-04 350841 + 195 350850 Br-85 7.77110E-03 2.09210E-02 350850 + 196 350860 Br-86 1.37340E-02 2.33280E-02 350860 + 197 350870 Br-87 1.73830E-02 2.16590E-02 350870 + 198 350880 Br-88 1.19080E-02 1.35230E-02 350880 + 199 350890 Br-89 7.90110E-03 8.17340E-03 350890 + 200 350900 Br-90 2.42940E-03 2.49480E-03 350900 + 201 350910 Br-91 8.12440E-04 8.12630E-04 350910 + 202 350920 Br-92 5.59100E-05 5.59180E-05 350920 + 203 350930 Br-93 1.21710E-05 1.21710E-05 350930 + 204 350940 Br-94 3.72700E-08 3.72700E-08 350940 + 205 360810 Kr-81 3.55040E-10 4.09320E-10 360810 + 206 360811 Kr-81m 5.42760E-11 5.42760E-11 360811 + 207 360820 Kr-82 9.58820E-07 3.17030E-05 36082.82c + 208 360830 Kr-83 8.97720E-06 1.05970E-02 36083.82c + 209 360831 Kr-83m 2.07570E-06 1.05780E-02 360831 + 210 360840 Kr-84 1.23330E-04 1.70490E-02 36084.82c + 211 360850 Kr-85 7.77430E-04 5.31980E-03 36085.82c + 212 360851 Kr-85m 1.79760E-04 2.10670E-02 360851 + 213 360860 Kr-86 7.32210E-03 3.11940E-02 36086.82c + 214 360870 Kr-87 1.78830E-02 3.99040E-02 360870 + 215 360880 Kr-88 3.90420E-02 5.28110E-02 360880 + 216 360890 Kr-89 4.54190E-02 5.30540E-02 360890 + 217 360900 Kr-90 4.12010E-02 4.32450E-02 360900 + 218 360910 Kr-91 2.15840E-02 2.22530E-02 360910 + 219 360920 Kr-92 9.03970E-03 9.08540E-03 360920 + 220 360930 Kr-93 2.26920E-03 2.27310E-03 360930 + 221 360940 Kr-94 4.92480E-04 4.92490E-04 360940 + 222 360950 Kr-95 4.66500E-05 4.66500E-05 360950 + 223 360960 Kr-96 2.62500E-06 2.62500E-06 360960 + 224 360970 Kr-97 4.47990E-09 4.47990E-09 360970 + 225 370840 Rb-84 3.59690E-09 1.00670E-08 370840 + 226 370841 Rb-84m 6.47010E-09 6.47010E-09 370841 + 227 370850 Rb-85 6.88250E-07 2.18790E-02 37085.82c + 228 370860 Rb-86 8.62240E-06 2.41320E-05 37086.82c + 229 370861 Rb-86m 1.55100E-05 1.55100E-05 370861 + 230 370870 Rb-87 4.09780E-04 4.03140E-02 37087.82c + 231 370880 Rb-88 1.81710E-03 5.46290E-02 370880 + 232 370890 Rb-89 8.87530E-03 6.19290E-02 370890 + 233 370900 Rb-90 1.90910E-03 4.00850E-02 370900 + 234 370901 Rb-90m 1.69560E-02 2.26120E-02 370901 + 235 370910 Rb-91 3.14860E-02 5.37390E-02 370910 + 236 370920 Rb-92 2.61580E-02 3.52430E-02 370920 + 237 370930 Rb-93 2.12780E-02 2.35570E-02 370930 + 238 370940 Rb-94 8.58550E-03 9.07390E-03 370940 + 239 370950 Rb-95 3.80190E-03 3.84730E-03 370950 + 240 370960 Rb-96 3.05590E-04 4.60290E-04 370960 + 241 370961 Rb-96m 3.05590E-04 3.06860E-04 370961 + 242 370970 Rb-97 1.24760E-04 1.24760E-04 370970 + 243 370980 Rb-98 2.21430E-06 2.21430E-06 370980 + 244 370981 Rb-98m 2.21430E-06 2.21430E-06 370981 + 245 370990 Rb-99 4.10450E-08 4.10450E-08 370990 + 246 380860 Sr-86 3.59850E-09 2.41340E-05 38086.82c + 247 380870 Sr-87 1.76520E-06 2.17220E-06 38087.82c + 248 380871 Sr-87m 4.08170E-07 4.08170E-07 380871 + 249 380880 Sr-88 9.08890E-05 5.47190E-02 38088.82c + 250 380890 Sr-89 5.28290E-04 6.24570E-02 38089.82c + 251 380900 Sr-90 4.24830E-03 6.63580E-02 38090.82c + 252 380910 Sr-91 1.18310E-02 6.55700E-02 380910 + 253 380920 Sr-92 3.00450E-02 6.56180E-02 380920 + 254 380930 Sr-93 4.27800E-02 6.69230E-02 380930 + 255 380940 Sr-94 5.08480E-02 5.93360E-02 380940 + 256 380950 Sr-95 3.42940E-02 3.78720E-02 380950 + 257 380960 Sr-96 1.90200E-02 1.96030E-02 380960 + 258 380970 Sr-97 6.98230E-03 7.07610E-03 380970 + 259 380980 Sr-98 2.03820E-03 2.04230E-03 380980 + 260 380990 Sr-99 3.16680E-04 3.16720E-04 380990 + 261 381000 Sr-100 5.22920E-05 5.22920E-05 381000 + 262 381010 Sr-101 4.78010E-06 4.78010E-06 381010 + 263 381020 Sr-102 3.78560E-09 3.78560E-09 381020 + 264 390890 Y-89 2.15540E-07 6.24580E-02 39089.82c + 265 390891 Y-89m 9.32160E-07 6.95250E-06 390891 + 266 390900 Y-90 3.44550E-06 6.63660E-02 39090.82c + 267 390901 Y-90m 4.88910E-06 4.88910E-06 390901 + 268 390910 Y-91 2.35650E-05 6.56950E-02 39091.82c + 269 390911 Y-91m 1.01920E-04 3.86800E-02 390911 + 270 390920 Y-92 5.18730E-04 6.61370E-02 390920 + 271 390930 Y-93 4.44770E-04 7.02780E-02 390930 + 272 390931 Y-93m 2.90940E-03 1.96560E-02 390931 + 273 390940 Y-94 8.15890E-03 6.74950E-02 390940 + 274 390950 Y-95 2.31700E-02 6.10420E-02 390950 + 275 390960 Y-96 8.95640E-03 2.85620E-02 390960 + 276 390961 Y-96m 1.61110E-02 1.61120E-02 390961 + 277 390970 Y-97 4.70550E-03 1.08690E-02 390970 + 278 390971 Y-97m 1.60380E-02 2.05380E-02 390971 + 279 390972 Y-97m 4.30960E-03 4.30960E-03 390972 + 280 390980 Y-98 2.41890E-03 4.46120E-03 390980 + 281 390981 Y-98m 1.01730E-02 1.01730E-02 390981 + 282 390990 Y-99 7.68130E-03 7.99840E-03 390990 + 283 391000 Y-100 1.18420E-03 1.23610E-03 391000 + 284 391001 Y-100m 1.18420E-03 1.18430E-03 391001 + 285 391010 Y-101 6.30520E-04 6.35190E-04 391010 + 286 391020 Y-102 3.48600E-05 3.48620E-05 391020 + 287 391021 Y-102m 3.48600E-05 3.48620E-05 391021 + 288 391030 Y-103 1.23480E-05 1.23480E-05 391030 + 289 391040 Y-104 7.81110E-09 7.81110E-09 391040 + 290 391050 Y-105 1.67050E-10 1.67050E-10 391050 + 291 400910 Zr-91 2.27770E-06 6.56970E-02 40091.82c + 292 400920 Zr-92 1.59940E-05 6.61530E-02 40092.82c + 293 400930 Zr-93 1.16950E-04 7.03940E-02 40093.82c + 294 400940 Zr-94 8.68540E-04 6.83640E-02 40094.82c + 295 400950 Zr-95 3.34790E-03 6.43900E-02 40095.82c + 296 400960 Zr-96 1.28580E-02 5.75480E-02 40096.82c + 297 400970 Zr-97 2.26440E-02 5.51160E-02 400970 + 298 400980 Zr-98 3.42060E-02 4.86140E-02 400980 + 299 400990 Zr-99 3.09470E-02 3.88210E-02 400990 + 300 401000 Zr-100 2.68670E-02 2.92760E-02 401000 + 301 401010 Zr-101 1.09370E-02 1.15760E-02 401010 + 302 401020 Zr-102 4.52010E-03 4.58740E-03 401020 + 303 401030 Zr-103 7.75780E-04 7.87140E-04 401030 + 304 401040 Zr-104 1.23960E-04 1.23970E-04 401040 + 305 401050 Zr-105 8.42170E-06 8.42180E-06 401050 + 306 401060 Zr-106 2.09970E-06 2.09970E-06 401060 + 307 401070 Zr-107 1.58670E-10 1.58670E-10 401070 + 308 410940 Nb-94 1.71100E-08 2.91080E-08 41094.82c + 309 410941 Nb-94m 1.20580E-08 1.20580E-08 410941 + 310 410950 Nb-95 1.18490E-05 6.43660E-02 41095.82c + 311 410951 Nb-95m 2.73980E-06 6.98380E-04 410951 + 312 410960 Nb-96 9.19990E-05 9.19990E-05 410960 + 313 410970 Nb-97 5.16600E-04 5.57520E-02 410970 + 314 410971 Nb-97m 1.19450E-04 5.25060E-02 410971 + 315 410980 Nb-98 4.55740E-04 4.90700E-02 410980 + 316 410981 Nb-98m 1.37530E-03 1.37530E-03 410981 + 317 410990 Nb-99 5.40400E-03 3.02490E-02 410990 + 318 410991 Nb-99m 1.24950E-03 1.55360E-02 410991 + 319 411000 Nb-100 2.19010E-03 3.14660E-02 411000 + 320 411001 Nb-100m 9.21090E-03 9.21090E-03 411001 + 321 411010 Nb-101 1.57050E-02 2.72810E-02 411010 + 322 411020 Nb-102 5.91350E-03 1.05010E-02 411020 + 323 411021 Nb-102m 5.91350E-03 5.91350E-03 411021 + 324 411030 Nb-103 7.26650E-03 8.05360E-03 411030 + 325 411040 Nb-104 1.18240E-03 1.30650E-03 411040 + 326 411041 Nb-104m 1.18240E-03 1.18240E-03 411041 + 327 411050 Nb-105 6.92340E-04 7.00680E-04 411050 + 328 411060 Nb-106 1.26070E-04 1.28140E-04 411060 + 329 411070 Nb-107 4.92440E-06 4.92460E-06 411070 + 330 411080 Nb-108 2.48800E-08 2.48800E-08 411080 + 331 411090 Nb-109 5.71530E-10 5.71530E-10 411090 + 332 411100 Nb-110 9.23390E-12 9.23390E-12 411100 + 333 420960 Mo-96 4.56320E-09 9.20040E-05 42096.82c + 334 420970 Mo-97 7.65300E-06 5.57590E-02 42097.82c + 335 420980 Mo-98 9.58900E-05 5.05410E-02 42098.82c + 336 420990 Mo-99 4.55900E-04 4.59300E-02 42099.82c + 337 421000 Mo-100 2.13100E-03 4.28080E-02 42100.82c + 338 421010 Mo-101 4.11830E-03 3.13990E-02 421010 + 339 421020 Mo-102 7.93180E-03 2.43460E-02 421020 + 340 421030 Mo-103 7.25570E-03 1.53110E-02 421030 + 341 421040 Mo-104 6.48060E-03 8.98000E-03 421040 + 342 421050 Mo-105 2.94850E-03 3.64300E-03 421050 + 343 421060 Mo-106 1.30380E-03 1.42650E-03 421060 + 344 421070 Mo-107 2.69900E-04 2.74530E-04 421070 + 345 421080 Mo-108 9.07910E-05 9.08140E-05 421080 + 346 421090 Mo-109 6.30800E-06 6.30850E-06 421090 + 347 421100 Mo-110 1.04390E-07 1.04400E-07 421100 + 348 421110 Mo-111 1.87210E-09 1.87210E-09 421110 + 349 421120 Mo-112 3.37090E-11 3.37090E-11 421120 + 350 430990 Tc-99 1.99600E-06 4.59310E-02 43099.82c + 351 430991 Tc-99m 4.61520E-07 4.04470E-02 430991 + 352 431000 Tc-100 2.85530E-06 2.85530E-06 431000 + 353 431010 Tc-101 3.82470E-05 3.14370E-02 431010 + 354 431020 Tc-102 1.03680E-04 2.44500E-02 431020 + 355 431021 Tc-102m 1.03680E-04 1.03680E-04 431021 + 356 431030 Tc-103 5.80220E-04 1.58910E-02 431030 + 357 431040 Tc-104 8.50800E-04 9.83080E-03 431040 + 358 431050 Tc-105 1.30890E-03 4.95190E-03 431050 + 359 431060 Tc-106 9.00930E-04 2.32740E-03 431060 + 360 431070 Tc-107 6.15480E-04 8.90010E-04 431070 + 361 431080 Tc-108 3.51320E-04 4.42170E-04 431080 + 362 431090 Tc-109 1.19720E-04 1.26000E-04 431090 + 363 431100 Tc-110 3.82930E-05 3.83970E-05 431100 + 364 431110 Tc-111 9.34840E-06 9.35030E-06 431110 + 365 431120 Tc-112 3.22610E-06 3.22610E-06 431120 + 366 431130 Tc-113 8.38990E-09 8.38990E-09 431130 + 367 431140 Tc-114 2.01420E-10 2.01420E-10 431140 + 368 431150 Tc-115 6.43180E-12 6.43180E-12 431150 + 369 431180 Tc-118 1.98770E-11 1.98770E-11 431180 + 370 441010 Ru-101 1.67510E-09 3.14370E-02 44101.82c + 371 441020 Ru-102 3.17100E-06 2.45570E-02 44102.82c + 372 441030 Ru-103 2.95970E-06 1.59010E-02 44103.82c + 373 441031 Ru-103m 7.14520E-06 7.14520E-06 441031 + 374 441040 Ru-104 5.22110E-05 9.88300E-03 44104.82c + 375 441050 Ru-105 1.11410E-04 5.06330E-03 44105.82c + 376 441060 Ru-106 2.19230E-04 2.54660E-03 44106.82c + 377 441070 Ru-107 2.69280E-04 1.15930E-03 441070 + 378 441080 Ru-108 3.52900E-04 7.95170E-04 441080 + 379 441090 Ru-109 2.55680E-04 3.81590E-04 441090 + 380 441100 Ru-110 2.58460E-04 2.96840E-04 441100 + 381 441110 Ru-111 1.37030E-04 1.46430E-04 441110 + 382 441120 Ru-112 5.05180E-05 5.36960E-05 441120 + 383 441130 Ru-113 9.86900E-06 1.48110E-05 441130 + 384 441131 Ru-113m 9.86900E-06 9.86900E-06 441131 + 385 441140 Ru-114 5.98270E-06 5.98290E-06 441140 + 386 441150 Ru-115 4.14320E-08 4.14380E-08 441150 + 387 441160 Ru-116 2.16370E-09 2.16370E-09 441160 + 388 441170 Ru-117 3.28550E-11 3.28550E-11 441170 + 389 441180 Ru-118 1.51610E-07 1.51630E-07 441180 + 390 441190 Ru-119 6.06470E-09 6.06470E-09 441190 + 391 441200 Ru-120 2.94220E-10 2.94220E-10 441200 + 392 451040 Rh-104 6.86190E-10 2.75420E-09 451040 + 393 451041 Rh-104m 2.07070E-09 2.07070E-09 451041 + 394 451050 Rh-105 6.95540E-08 5.06340E-03 45105.82c + 395 451051 Rh-105m 1.06330E-08 1.43740E-03 451051 + 396 451060 Rh-106 1.87440E-07 2.54680E-03 451060 + 397 451061 Rh-106m 4.39030E-07 4.39030E-07 451061 + 398 451070 Rh-107 9.85130E-06 1.16910E-03 451070 + 399 451080 Rh-108 2.95290E-06 7.98120E-04 451080 + 400 451081 Rh-108m 8.91110E-06 8.91110E-06 451081 + 401 451090 Rh-109 4.10330E-05 4.22620E-04 451090 + 402 451100 Rh-110 9.33900E-05 3.90230E-04 451100 + 403 451101 Rh-110m 2.49300E-06 2.49300E-06 451101 + 404 451110 Rh-111 9.04420E-05 2.36870E-04 451110 + 405 451120 Rh-112 3.06540E-05 8.43500E-05 451120 + 406 451121 Rh-112m 3.06540E-05 3.06540E-05 451121 + 407 451130 Rh-113 7.68800E-05 9.66260E-05 451130 + 408 451140 Rh-114 2.79080E-05 3.38910E-05 451140 + 409 451141 Rh-114m 2.79080E-05 2.79080E-05 451141 + 410 451150 Rh-115 3.27360E-05 3.27770E-05 451150 + 411 451160 Rh-116 1.23640E-06 1.23850E-06 451160 + 412 451161 Rh-116m 2.89590E-06 2.89590E-06 451161 + 413 451170 Rh-117 1.05840E-06 1.06470E-06 451170 + 414 451180 Rh-118 1.24480E-05 1.25940E-05 451180 + 415 451190 Rh-119 4.00500E-06 4.01080E-06 451190 + 416 451200 Rh-120 3.88940E-07 3.89230E-07 451200 + 417 451210 Rh-121 3.91070E-08 3.91070E-08 451210 + 418 451220 Rh-122 1.19690E-09 1.19690E-09 451220 + 419 461060 Pd-106 9.90450E-11 2.54730E-03 46106.82c + 420 461070 Pd-107 8.26570E-10 1.16910E-03 46107.82c + 421 461071 Pd-107m 1.55340E-09 1.55340E-09 461071 + 422 461080 Pd-108 6.99460E-08 8.07100E-04 46108.82c + 423 461090 Pd-109 1.09560E-06 4.25780E-04 461090 + 424 461091 Pd-109m 2.05910E-06 2.13370E-04 461091 + 425 461100 Pd-110 9.58090E-06 4.02310E-04 46110.82c + 426 461110 Pd-111 4.87230E-06 2.48170E-04 461110 + 427 461111 Pd-111m 9.15670E-06 1.01040E-05 461111 + 428 461120 Pd-112 3.01250E-05 1.45130E-04 461120 + 429 461130 Pd-113 1.88840E-05 1.61100E-04 461130 + 430 461131 Pd-113m 4.55870E-05 4.55870E-05 461131 + 431 461140 Pd-114 1.06760E-04 1.68560E-04 461140 + 432 461150 Pd-115 4.99040E-05 8.58050E-05 461150 + 433 461151 Pd-115m 9.37860E-05 9.85460E-05 461151 + 434 461160 Pd-116 1.23920E-04 1.28050E-04 461160 + 435 461170 Pd-117 1.69010E-05 5.00970E-05 461170 + 436 461171 Pd-117m 3.17640E-05 3.17640E-05 461171 + 437 461180 Pd-118 2.98880E-05 4.21140E-05 461180 + 438 461190 Pd-119 6.93130E-06 1.09650E-05 461190 + 439 461200 Pd-120 2.67890E-06 3.05040E-06 461200 + 440 461210 Pd-121 8.86040E-06 8.89420E-06 461210 + 441 461220 Pd-122 2.22430E-06 2.22550E-06 461220 + 442 461230 Pd-123 1.52690E-07 1.52690E-07 461230 + 443 461240 Pd-124 1.82240E-08 1.82240E-08 461240 + 444 471090 Ag-109 1.84830E-11 4.25780E-04 47109.82c + 445 471091 Ag-109m 1.20910E-10 4.25570E-04 471091 + 446 471100 Ag-110 1.11340E-09 1.14890E-09 471100 + 447 471101 Ag-110m 2.60780E-09 2.60780E-09 47510.82c + 448 471110 Ag-111 1.00500E-08 2.49730E-04 47111.82c + 449 471111 Ag-111m 6.57420E-08 2.48430E-04 471111 + 450 471120 Ag-112 4.03450E-07 1.45530E-04 471120 + 451 471130 Ag-113 1.37810E-07 1.06280E-04 471130 + 452 471131 Ag-113m 9.01490E-07 1.55160E-04 471131 + 453 471140 Ag-114 1.34120E-06 1.75540E-04 471140 + 454 471141 Ag-114m 5.64050E-06 5.64050E-06 471141 + 455 471150 Ag-115 2.52200E-06 9.25290E-05 471150 + 456 471151 Ag-115m 1.64980E-05 1.30330E-04 471151 + 457 471160 Ag-116 1.08230E-05 1.40400E-04 471160 + 458 471161 Ag-116m 2.53500E-05 2.53500E-05 471161 + 459 471170 Ag-117 1.10900E-05 4.19940E-05 471170 + 460 471171 Ag-117m 7.25460E-05 9.75940E-05 471171 + 461 471180 Ag-118 1.22790E-05 7.20150E-05 471180 + 462 471181 Ag-118m 5.16430E-05 5.76630E-05 471181 + 463 471190 Ag-119 1.07200E-05 1.62030E-05 471190 + 464 471191 Ag-119m 7.01250E-05 7.56080E-05 471191 + 465 471200 Ag-120 1.49460E-05 2.49070E-05 471200 + 466 471201 Ag-120m 2.12080E-05 2.27330E-05 471201 + 467 471210 Ag-121 2.68910E-05 3.57610E-05 471210 + 468 471220 Ag-122 5.35990E-06 7.58540E-06 471220 + 469 471221 Ag-122m 4.82810E-06 4.82810E-06 471221 + 470 471230 Ag-123 7.68840E-06 7.84110E-06 471230 + 471 471240 Ag-124 1.46630E-06 2.14500E-06 471240 + 472 471241 Ag-124m 1.32090E-06 1.32090E-06 471241 + 473 471250 Ag-125 3.68330E-06 3.68330E-06 471250 + 474 471260 Ag-126 3.71530E-07 3.71530E-07 471260 + 475 471270 Ag-127 3.98910E-08 3.98910E-08 471270 + 476 471280 Ag-128 1.36480E-09 1.36480E-09 471280 + 477 481110 Cd-111 1.59360E-12 2.50980E-04 48111.82c + 478 481111 Cd-111m 5.21390E-12 5.21390E-12 481111 + 479 481120 Cd-112 3.48330E-10 1.45530E-04 48112.82c + 480 481130 Cd-113 1.96790E-09 1.60300E-04 48113.82c + 481 481131 Cd-113m 6.43840E-09 1.84380E-06 481131 + 482 481140 Cd-114 2.27750E-07 1.75770E-04 48114.82c + 483 481150 Cd-115 2.47300E-07 1.87400E-04 481150 + 484 481151 Cd-115m 8.09100E-07 9.13840E-06 48515.82c + 485 481160 Cd-116 6.19980E-06 1.70430E-04 48116.82c + 486 481170 Cd-117 4.21330E-06 1.08110E-04 481170 + 487 481171 Cd-117m 1.37850E-05 4.36180E-05 481171 + 488 481180 Cd-118 4.95190E-05 1.55560E-04 481180 + 489 481190 Cd-119 1.89610E-05 1.02670E-04 481190 + 490 481191 Cd-119m 4.57730E-05 5.38750E-05 481191 + 491 481200 Cd-120 1.19250E-04 1.58480E-04 481200 + 492 481210 Cd-121 3.50220E-05 6.70470E-05 481210 + 493 481211 Cd-121m 8.45480E-05 8.82850E-05 481211 + 494 481220 Cd-122 1.06930E-04 1.19340E-04 481220 + 495 481230 Cd-123 2.11570E-05 2.75740E-05 481230 + 496 481231 Cd-123m 5.10770E-05 5.25040E-05 481231 + 497 481240 Cd-124 1.21090E-04 1.23890E-04 481240 + 498 481250 Cd-125 7.12600E-05 7.31010E-05 481250 + 499 481251 Cd-125m 1.72030E-04 1.73870E-04 481251 + 500 481260 Cd-126 1.48370E-04 1.48740E-04 481260 + 501 481270 Cd-127 4.83860E-05 4.84260E-05 481270 + 502 481280 Cd-128 1.73780E-05 1.73790E-05 481280 + 503 481290 Cd-129 1.30470E-06 1.30470E-06 481290 + 504 481291 Cd-129m 3.14970E-06 3.14970E-06 481291 + 505 481300 Cd-130 4.17740E-08 4.17740E-08 481300 + 506 481310 Cd-131 9.91230E-10 9.91230E-10 481310 + 507 491140 In-114 8.02150E-12 3.13780E-11 491140 + 508 491141 In-114m 1.22950E-11 2.42030E-11 491141 + 509 491142 In-114m 1.19080E-11 1.19080E-11 491142 + 510 491150 In-115 1.77090E-09 1.87180E-04 49115.82c + 511 491151 In-115m 4.09480E-10 1.87410E-04 491151 + 512 491160 In-116 7.76740E-09 7.76740E-09 491160 + 513 491161 In-116m 1.19060E-08 2.34360E-08 491161 + 514 491162 In-116m 1.15310E-08 1.15310E-08 491162 + 515 491170 In-117 4.33040E-07 9.94480E-05 491170 + 516 491171 In-117m 1.00130E-07 9.98420E-05 491171 + 517 491180 In-118 2.56620E-07 1.55810E-04 491180 + 518 491181 In-118m 3.93330E-07 7.68950E-07 491181 + 519 491182 In-118m 3.80960E-07 3.80960E-07 491182 + 520 491190 In-119 2.81530E-06 7.17880E-05 491190 + 521 491191 In-119m 6.50970E-07 9.34570E-05 491191 + 522 491200 In-120 6.25240E-06 1.64730E-04 491200 + 523 491201 In-120m 6.25240E-06 6.25240E-06 491201 + 524 491202 In-120m 6.25240E-06 6.25240E-06 491202 + 525 491210 In-121 2.55010E-05 1.36970E-04 491210 + 526 491211 In-121m 5.89640E-06 5.03620E-05 491211 + 527 491220 In-122 2.31790E-05 1.42520E-04 491220 + 528 491221 In-122m 1.64450E-05 1.64450E-05 491221 + 529 491222 In-122m 1.64450E-05 1.64450E-05 491222 + 530 491230 In-123 7.62220E-05 1.36630E-04 491230 + 531 491231 In-123m 1.76240E-05 3.72980E-05 491231 + 532 491240 In-124 6.30690E-05 1.86960E-04 491240 + 533 491241 In-124m 5.68110E-05 5.68110E-05 491241 + 534 491250 In-125 4.50700E-04 6.59560E-04 491250 + 535 491251 In-125m 1.04210E-04 1.42320E-04 491251 + 536 491260 In-126 4.46730E-04 5.95470E-04 491260 + 537 491261 In-126m 4.02410E-04 4.02410E-04 491261 + 538 491270 In-127 8.04170E-04 8.04170E-04 491270 + 539 491271 In-127m 1.85940E-04 2.34370E-04 491271 + 540 491280 In-128 2.94530E-04 4.31800E-04 491280 + 541 491281 In-128m 1.19890E-04 1.37270E-04 491281 + 542 491282 In-128m 3.73300E-04 3.73300E-04 491282 + 543 491290 In-129 3.93020E-04 3.96170E-04 491290 + 544 491291 In-129m 9.08760E-05 9.21820E-05 491291 + 545 491300 In-130 2.78250E-05 2.78650E-05 491300 + 546 491301 In-130m 3.10780E-05 3.10780E-05 491301 + 547 491302 In-130m 5.28770E-05 5.28770E-05 491302 + 548 491310 In-131 6.32670E-06 6.39210E-06 491310 + 549 491311 In-131m 6.32670E-06 6.32670E-06 491311 + 550 491312 In-131m 6.32670E-06 6.32670E-06 491312 + 551 491320 In-132 3.02450E-07 3.02450E-07 491320 + 552 491330 In-133 9.93080E-09 1.22270E-08 491330 + 553 491331 In-133m 2.29620E-09 2.29620E-09 491331 + 554 501160 Sn-116 6.59670E-12 3.12110E-08 50116.82c + 555 501170 Sn-117 4.90350E-11 1.52260E-04 50117.82c + 556 501171 Sn-117m 1.60420E-10 3.38990E-07 501171 + 557 501200 Sn-120 6.84270E-11 1.77240E-04 50120.82c + 558 501210 Sn-121 5.68200E-10 1.83250E-04 501210 + 559 501211 Sn-121m 1.37170E-09 1.55180E-05 501211 + 560 501220 Sn-122 2.20890E-05 1.97500E-04 50122.82c + 561 501230 Sn-123 2.28490E-05 3.32660E-05 50123.82c + 562 501231 Sn-123m 9.46480E-06 1.72970E-04 501231 + 563 501240 Sn-124 8.09290E-05 3.24700E-04 50124.82c + 564 501250 Sn-125 2.51510E-04 3.62920E-04 50125.82c + 565 501251 Sn-125m 1.04180E-04 7.94650E-04 501251 + 566 501260 Sn-126 1.33550E-03 2.33500E-03 50126.82c + 567 501270 Sn-127 2.24110E-03 2.55450E-03 501270 + 568 501271 Sn-127m 9.28320E-04 1.65180E-03 501271 + 569 501280 Sn-128 2.25080E-03 8.32780E-03 501280 + 570 501281 Sn-128m 5.27190E-03 5.64520E-03 501281 + 571 501290 Sn-129 2.80430E-03 3.25060E-03 501290 + 572 501291 Sn-129m 6.77000E-03 6.81220E-03 501291 + 573 501300 Sn-130 2.52980E-03 2.60250E-03 501300 + 574 501301 Sn-130m 5.92540E-03 5.96460E-03 501301 + 575 501310 Sn-131 1.08870E-03 1.10090E-03 501310 + 576 501311 Sn-131m 2.62820E-03 2.63480E-03 501311 + 577 501320 Sn-132 1.26560E-03 1.26590E-03 501320 + 578 501330 Sn-133 8.36820E-05 8.36840E-05 501330 + 579 501340 Sn-134 1.04630E-05 1.04630E-05 501340 + 580 501350 Sn-135 6.48130E-08 6.48130E-08 501350 + 581 501360 Sn-136 2.92890E-09 2.92890E-09 501360 + 582 511220 Sb-122 2.10110E-12 4.48280E-12 511220 + 583 511221 Sb-122m 2.38170E-12 2.38170E-12 511221 + 584 511230 Sb-123 4.51970E-10 2.06240E-04 51123.82c + 585 511240 Sb-124 4.97970E-07 1.16980E-06 51124.82c + 586 511241 Sb-124m 3.80760E-07 8.95730E-07 511241 + 587 511242 Sb-124m 5.14970E-07 5.14970E-07 511242 + 588 511250 Sb-125 1.43590E-05 1.17190E-03 51125.82c + 589 511260 Sb-126 2.42110E-05 2.99940E-05 51126.82c + 590 511261 Sb-126m 1.79010E-05 4.13120E-05 511261 + 591 511262 Sb-126m 2.34110E-05 2.34110E-05 511262 + 592 511270 Sb-127 3.38020E-04 4.54430E-03 511270 + 593 511280 Sb-128 6.01840E-04 8.96660E-03 511280 + 594 511281 Sb-128m 1.02700E-03 1.02700E-03 511281 + 595 511290 Sb-129 3.86300E-03 1.13850E-02 511290 + 596 511291 Sb-129m 2.36070E-03 5.76670E-03 511291 + 597 511300 Sb-130 5.77200E-03 1.13570E-02 511300 + 598 511301 Sb-130m 5.77200E-03 8.75430E-03 511301 + 599 511310 Sb-131 1.71430E-02 2.08790E-02 511310 + 600 511320 Sb-132 7.28840E-03 8.55430E-03 511320 + 601 511321 Sb-132m 5.37160E-03 5.37160E-03 511321 + 602 511330 Sb-133 7.57460E-03 7.66010E-03 511330 + 603 511340 Sb-134 3.71310E-04 3.80000E-04 511340 + 604 511341 Sb-134m 8.69690E-04 8.69700E-04 511341 + 605 511350 Sb-135 1.67750E-04 1.67800E-04 511350 + 606 511360 Sb-136 1.12130E-05 1.12150E-05 511360 + 607 511370 Sb-137 1.60750E-06 1.60750E-06 511370 + 608 511380 Sb-138 8.34470E-09 8.34470E-09 511380 + 609 521250 Te-125 7.41890E-11 1.17190E-03 52125.82c + 610 521251 Te-125m 2.42720E-10 2.62240E-04 521251 + 611 521260 Te-126 1.77160E-06 6.72950E-05 52126.82c + 612 521270 Te-127 4.61050E-06 4.54180E-03 521270 + 613 521271 Te-127m 1.11300E-05 7.60010E-04 52527.82c + 614 521280 Te-128 1.06540E-04 1.00630E-02 52128.82c + 615 521290 Te-129 2.60520E-04 1.44730E-02 521290 + 616 521291 Te-129m 6.28930E-04 7.30510E-03 52529.82c + 617 521300 Te-130 4.75900E-03 2.48700E-02 52130.82c + 618 521310 Te-131 4.32120E-03 2.60700E-02 521310 + 619 521311 Te-131m 1.04320E-02 1.21030E-02 521311 + 620 521320 Te-132 3.22030E-02 4.61290E-02 52132.82c + 621 521330 Te-133 1.28380E-02 2.48300E-02 521330 + 622 521331 Te-133m 3.09930E-02 3.23180E-02 521331 + 623 521340 Te-134 3.64200E-02 3.76950E-02 521340 + 624 521350 Te-135 1.04830E-02 1.06260E-02 521350 + 625 521360 Te-136 3.94400E-03 3.95410E-03 521360 + 626 521370 Te-137 7.11370E-04 7.12190E-04 521370 + 627 521380 Te-138 1.14680E-04 1.14690E-04 521380 + 628 521390 Te-139 7.67670E-06 7.67670E-06 521390 + 629 521400 Te-140 1.15430E-06 1.15430E-06 521400 + 630 521410 Te-141 1.70380E-09 1.70380E-09 521410 + 631 531270 I-127 1.48290E-10 4.56010E-03 53127.82c + 632 531280 I-128 1.15900E-06 1.15900E-06 531280 + 633 531290 I-129 2.22750E-06 1.71780E-02 53129.82c + 634 531300 I-130 1.82680E-05 2.48190E-05 53130.82c + 635 531301 I-130m 7.79920E-06 7.79920E-06 531301 + 636 531310 I-131 3.13170E-04 3.59450E-02 53131.82c + 637 531320 I-132 1.16900E-03 4.80390E-02 531320 + 638 531321 I-132m 8.61540E-04 8.61540E-04 531321 + 639 531330 I-133 5.21000E-03 5.98860E-02 531330 + 640 531331 I-133m 3.18380E-03 3.18380E-03 531331 + 641 531340 I-134 1.30360E-02 6.01170E-02 531340 + 642 531341 I-134m 9.60740E-03 9.60740E-03 531341 + 643 531350 I-135 3.35840E-02 4.42100E-02 53135.82c + 644 531360 I-136 7.44620E-03 1.14110E-02 531360 + 645 531361 I-136m 1.74410E-02 1.74520E-02 531361 + 646 531370 I-137 1.16540E-02 1.23520E-02 531370 + 647 531380 I-138 3.47620E-03 3.58370E-03 531380 + 648 531390 I-139 1.50360E-03 1.51130E-03 531390 + 649 531400 I-140 2.62340E-04 2.63490E-04 531400 + 650 531410 I-141 3.67190E-05 3.67210E-05 531410 + 651 531420 I-142 4.28700E-07 4.28700E-07 531420 + 652 531430 I-143 1.21240E-08 1.21240E-08 531430 + 653 541300 Xe-130 8.74330E-09 2.60760E-05 54130.82c + 654 541310 Xe-131 3.08890E-07 3.59460E-02 54131.82c + 655 541311 Xe-131m 7.45710E-07 3.91180E-04 541311 + 656 541320 Xe-132 2.31750E-05 4.82090E-02 54132.82c + 657 541321 Xe-132m 2.62710E-05 2.62710E-05 541321 + 658 541330 Xe-133 1.19090E-04 6.02920E-02 54133.82c + 659 541331 Xe-133m 2.87510E-04 1.99210E-03 541331 + 660 541340 Xe-134 7.92730E-04 6.29880E-02 54134.82c + 661 541341 Xe-134m 1.85680E-03 2.07770E-03 541341 + 662 541350 Xe-135 3.03390E-03 5.44810E-02 54135.82c + 663 541351 Xe-135m 7.32410E-03 1.46230E-02 541351 + 664 541360 Xe-136 4.98250E-02 7.94900E-02 54136.82c + 665 541370 Xe-137 4.62640E-02 5.80030E-02 541370 + 666 541380 Xe-138 4.37080E-02 4.72500E-02 541380 + 667 541390 Xe-139 2.56710E-02 2.70590E-02 541390 + 668 541400 Xe-140 1.66130E-02 1.68600E-02 541400 + 669 541410 Xe-141 5.92880E-03 5.95790E-03 541410 + 670 541420 Xe-142 1.42410E-03 1.42440E-03 541420 + 671 541430 Xe-143 1.66560E-04 1.66570E-04 541430 + 672 541440 Xe-144 1.55740E-05 1.55740E-05 541440 + 673 541450 Xe-145 4.29780E-08 4.29780E-08 541450 + 674 541460 Xe-146 9.77500E-10 9.77500E-10 541460 + 675 551320 Cs-132 1.11610E-09 1.11610E-09 551320 + 676 551330 Cs-133 1.32460E-07 6.02920E-02 55133.82c + 677 551340 Cs-134 1.81700E-06 3.15620E-06 55134.82c + 678 551341 Cs-134m 1.33920E-06 1.33920E-06 551341 + 679 551350 Cs-135 3.09870E-05 5.46180E-02 55135.82c + 680 551351 Cs-135m 1.89350E-05 1.89350E-05 551351 + 681 551360 Cs-136 3.95920E-04 5.11940E-04 55136.82c + 682 551361 Cs-136m 2.32030E-04 2.32030E-04 551361 + 683 551370 Cs-137 4.60350E-03 6.26070E-02 55137.82c + 684 551380 Cs-138 4.88230E-03 5.77440E-02 551380 + 685 551381 Cs-138m 6.92770E-03 6.92770E-03 551381 + 686 551390 Cs-139 2.48830E-02 5.19420E-02 551390 + 687 551400 Cs-140 2.74570E-02 4.43190E-02 551400 + 688 551410 Cs-141 2.82850E-02 3.42450E-02 551410 + 689 551420 Cs-142 1.57210E-02 1.71420E-02 551420 + 690 551430 Cs-143 6.66460E-03 6.83000E-03 551430 + 691 551440 Cs-144 8.27100E-04 1.25580E-03 551440 + 692 551441 Cs-144m 8.27100E-04 8.27100E-04 551441 + 693 551450 Cs-145 2.54400E-04 2.54440E-04 551450 + 694 551460 Cs-146 2.64830E-05 2.64840E-05 551460 + 695 551470 Cs-147 9.01520E-07 9.01520E-07 551470 + 696 551480 Cs-148 1.85510E-09 1.85510E-09 551480 + 697 561350 Ba-135 3.88300E-09 1.32570E-08 56135.82c + 698 561351 Ba-135m 9.37400E-09 9.37400E-09 561351 + 699 561360 Ba-136 5.59260E-07 6.29820E-04 56136.82c + 700 561361 Ba-136m 1.30990E-06 1.30990E-06 561361 + 701 561370 Ba-137 1.90810E-05 6.26720E-02 56137.82c + 702 561371 Ba-137m 4.60650E-05 5.91460E-02 561371 + 703 561380 Ba-138 1.25820E-03 6.03180E-02 56138.82c + 704 561390 Ba-139 4.93030E-03 5.68720E-02 561390 + 705 561400 Ba-140 2.04810E-02 6.48000E-02 56140.82c + 706 561410 Ba-141 2.76150E-02 6.18600E-02 561410 + 707 561420 Ba-142 4.89210E-02 6.61750E-02 561420 + 708 561430 Ba-143 4.24730E-02 4.92310E-02 561430 + 709 561440 Ba-144 2.62540E-02 2.79190E-02 561440 + 710 561450 Ba-145 9.93550E-03 1.01570E-02 561450 + 711 561460 Ba-146 2.75000E-03 2.77300E-03 561460 + 712 561470 Ba-147 6.18090E-04 6.18740E-04 561470 + 713 561480 Ba-148 8.83900E-05 8.83910E-05 561480 + 714 561490 Ba-149 3.25650E-06 3.25650E-06 561490 + 715 561500 Ba-150 8.67540E-09 8.67540E-09 561500 + 716 561510 Ba-151 9.25070E-11 9.25070E-11 561510 + 717 571370 La-137 1.99460E-09 1.99460E-09 571370 + 718 571380 La-138 9.04040E-08 9.04040E-08 57138.82c + 719 571390 La-139 2.59230E-05 5.68980E-02 57139.82c + 720 571400 La-140 1.53840E-04 6.49540E-02 57140.82c + 721 571410 La-141 1.05000E-03 6.29100E-02 571410 + 722 571420 La-142 2.45210E-03 6.86270E-02 571420 + 723 571430 La-143 9.95470E-03 5.91860E-02 571430 + 724 571440 La-144 1.59620E-02 4.38810E-02 571440 + 725 571450 La-145 1.73360E-02 2.74930E-02 571450 + 726 571460 La-146 3.44800E-03 6.22100E-03 571460 + 727 571461 La-146m 6.20230E-03 6.20230E-03 571461 + 728 571470 La-147 5.16500E-03 5.78410E-03 571470 + 729 571480 La-148 1.81460E-03 1.90270E-03 571480 + 730 571490 La-149 4.38560E-04 4.41800E-04 571490 + 731 571500 La-150 5.59500E-05 5.59590E-05 571500 + 732 571510 La-151 9.96300E-06 9.96310E-06 571510 + 733 571520 La-152 1.78710E-06 1.78710E-06 571520 + 734 571530 La-153 2.72420E-10 2.72420E-10 571530 + 735 581400 Ce-140 1.15430E-06 6.49550E-02 58140.82c + 736 581410 Ce-141 1.54140E-05 6.29260E-02 58141.82c + 737 581420 Ce-142 1.76070E-04 6.88030E-02 58142.82c + 738 581430 Ce-143 5.66530E-04 5.97520E-02 58143.82c + 739 581440 Ce-144 3.25050E-03 4.71320E-02 58144.82c + 740 581450 Ce-145 6.87990E-03 3.43730E-02 581450 + 741 581460 Ce-146 1.30270E-02 2.54500E-02 581460 + 742 581470 Ce-147 1.20740E-02 1.78580E-02 581470 + 743 581480 Ce-148 9.65960E-03 1.15680E-02 581480 + 744 581490 Ce-149 4.68290E-03 5.12000E-03 581490 + 745 581500 Ce-150 1.85560E-03 1.91000E-03 581500 + 746 581510 Ce-151 5.56920E-04 5.66990E-04 581510 + 747 581520 Ce-152 8.35040E-05 8.51830E-05 581520 + 748 581530 Ce-153 9.03060E-06 9.03090E-06 581530 + 749 581540 Ce-154 2.73550E-08 2.73550E-08 581540 + 750 581550 Ce-155 2.96470E-10 2.96470E-10 581550 + 751 581560 Ce-156 4.42760E-12 4.42760E-12 581560 + 752 591420 Pr-142 4.66450E-10 1.55900E-09 59142.82c + 753 591421 Pr-142m 1.09250E-09 1.09250E-09 591421 + 754 591430 Pr-143 1.29320E-07 5.97530E-02 59143.82c + 755 591440 Pr-144 6.06580E-07 4.71380E-02 591440 + 756 591441 Pr-144m 5.38730E-06 6.55780E-04 591441 + 757 591450 Pr-145 5.32860E-05 3.44260E-02 591450 + 758 591460 Pr-146 1.85250E-04 2.56350E-02 591460 + 759 591470 Pr-147 7.00570E-04 1.85590E-02 591470 + 760 591480 Pr-148 2.78560E-04 1.18470E-02 591480 + 761 591481 Pr-148m 1.17150E-03 1.17150E-03 591481 + 762 591490 Pr-149 2.42520E-03 7.54520E-03 591490 + 763 591500 Pr-150 2.21810E-03 4.12810E-03 591500 + 764 591510 Pr-151 1.61810E-03 2.18510E-03 591510 + 765 591520 Pr-152 6.56310E-04 7.41550E-04 591520 + 766 591530 Pr-153 2.36630E-04 2.45600E-04 591530 + 767 591540 Pr-154 3.03830E-05 3.04100E-05 591540 + 768 591550 Pr-155 1.98200E-06 1.98230E-06 591550 + 769 591560 Pr-156 1.00360E-06 1.00360E-06 591560 + 770 591570 Pr-157 6.16230E-10 6.16230E-10 591570 + 771 591580 Pr-158 6.36380E-12 6.36380E-12 591580 + 772 601450 Nd-145 1.10530E-06 3.44280E-02 60145.82c + 773 601460 Nd-146 1.96340E-06 2.56380E-02 60146.82c + 774 601470 Nd-147 1.62500E-05 1.85750E-02 60147.82c + 775 601480 Nd-148 1.09890E-04 1.31280E-02 60148.82c + 776 601490 Nd-149 2.91910E-04 7.83710E-03 601490 + 777 601500 Nd-150 8.23960E-04 4.95210E-03 60150.82c + 778 601510 Nd-151 1.22140E-03 3.40650E-03 601510 + 779 601520 Nd-152 1.22070E-03 1.96230E-03 601520 + 780 601530 Nd-153 1.00880E-03 1.25440E-03 601530 + 781 601540 Nd-154 3.14080E-04 3.44490E-04 601540 + 782 601550 Nd-155 1.03980E-04 1.05990E-04 601550 + 783 601560 Nd-156 2.40790E-05 2.50550E-05 601560 + 784 601570 Nd-157 5.51070E-07 5.51650E-07 601570 + 785 601580 Nd-158 5.09200E-08 5.09260E-08 601580 + 786 601590 Nd-159 3.80970E-10 3.80970E-10 601590 + 787 601600 Nd-160 4.51760E-12 4.51760E-12 601600 + 788 611470 Pm-147 6.01750E-10 1.85750E-02 61147.82c + 789 611480 Pm-148 5.92060E-09 6.61390E-09 61148.82c + 790 611481 Pm-148m 1.38670E-08 1.38670E-08 61548.82c + 791 611490 Pm-149 8.14270E-07 7.83790E-03 61149.82c + 792 611500 Pm-150 2.55250E-06 2.55250E-06 611500 + 793 611510 Pm-151 2.72180E-05 3.43370E-03 61151.82c + 794 611520 Pm-152 8.93550E-06 1.97120E-03 611520 + 795 611521 Pm-152m 1.78430E-05 1.78430E-05 611521 + 796 611522 Pm-152m 1.97360E-05 1.97360E-05 611522 + 797 611530 Pm-153 1.22180E-04 1.37660E-03 611530 + 798 611540 Pm-154 5.28500E-05 3.97340E-04 611540 + 799 611541 Pm-154m 5.28500E-05 5.28500E-05 611541 + 800 611550 Pm-155 1.16000E-04 2.21990E-04 611550 + 801 611560 Pm-156 4.91730E-05 7.42280E-05 611560 + 802 611570 Pm-157 2.74820E-05 2.80340E-05 611570 + 803 611580 Pm-158 1.20530E-05 1.21040E-05 611580 + 804 611590 Pm-159 2.45330E-07 2.45710E-07 611590 + 805 611600 Pm-160 5.82670E-09 5.83120E-09 611600 + 806 611610 Pm-161 2.74690E-10 2.74690E-10 611610 + 807 611620 Pm-162 2.53920E-12 2.53920E-12 611620 + 808 621500 Sm-150 1.73510E-09 2.55420E-06 62150.82c + 809 621510 Sm-151 9.06490E-07 3.43460E-03 62151.82c + 810 621520 Sm-152 7.05230E-07 2.00950E-03 62152.82c + 811 621530 Sm-153 3.30920E-06 1.38790E-03 62153.82c + 812 621531 Sm-153m 7.98880E-06 7.98880E-06 621531 + 813 621540 Sm-154 1.84060E-05 4.68600E-04 62154.82c + 814 621550 Sm-155 2.08180E-05 2.42810E-04 621550 + 815 621560 Sm-156 4.01630E-05 1.14390E-04 621560 + 816 621570 Sm-157 3.92760E-05 6.73100E-05 621570 + 817 621580 Sm-158 3.01390E-05 4.22430E-05 621580 + 818 621590 Sm-159 4.62130E-06 4.86700E-06 621590 + 819 621600 Sm-160 2.53780E-06 2.54360E-06 621600 + 820 621610 Sm-161 6.07210E-08 6.09960E-08 621610 + 821 621620 Sm-162 4.60760E-09 4.61010E-09 621620 + 822 621630 Sm-163 1.18910E-10 1.18910E-10 621630 + 823 621640 Sm-164 3.00530E-12 3.00530E-12 621640 + 824 631520 Eu-152 1.95150E-11 4.12800E-11 63152.82c + 825 631521 Eu-152m 4.64790E-12 4.64790E-12 631521 + 826 631522 Eu-152m 2.17650E-11 2.17650E-11 631522 + 827 631530 Eu-153 2.86040E-09 1.38790E-03 63153.82c + 828 631540 Eu-154 1.13320E-08 2.15390E-08 63154.82c + 829 631541 Eu-154m 1.02070E-08 1.02070E-08 631541 + 830 631550 Eu-155 2.83930E-07 2.43090E-04 63155.82c + 831 631560 Eu-156 9.55340E-07 1.15350E-04 63156.82c + 832 631570 Eu-157 4.69740E-06 7.20070E-05 63157.82c + 833 631580 Eu-158 2.00920E-06 4.42520E-05 631580 + 834 631590 Eu-159 4.62160E-06 9.48860E-06 631590 + 835 631600 Eu-160 1.29370E-06 3.83730E-06 631600 + 836 631610 Eu-161 7.58090E-07 8.19090E-07 631610 + 837 631620 Eu-162 9.84610E-08 1.03070E-07 631620 + 838 631630 Eu-163 1.93270E-08 1.94460E-08 631630 + 839 631640 Eu-164 9.48530E-10 9.51540E-10 631640 + 840 631650 Eu-165 5.82890E-11 5.82890E-11 631650 + 841 631660 Eu-166 1.06910E-12 1.06910E-12 631660 + 842 641550 Gd-155 1.73670E-11 2.43090E-04 64155.82c + 843 641551 Gd-155m 4.19270E-11 4.19270E-11 641551 + 844 641560 Gd-156 1.68690E-09 1.15350E-04 64156.82c + 845 641570 Gd-157 1.63900E-08 7.20230E-05 64157.82c + 846 641580 Gd-158 2.00930E-06 4.62610E-05 64158.82c + 847 641590 Gd-159 2.36600E-07 9.72520E-06 641590 + 848 641600 Gd-160 4.20820E-07 4.25810E-06 64160.82c + 849 641610 Gd-161 3.77520E-07 1.19660E-06 641610 + 850 641620 Gd-162 3.02780E-07 4.05850E-07 641620 + 851 641630 Gd-163 9.13700E-08 1.10820E-07 641630 + 852 641640 Gd-164 3.05390E-08 3.14900E-08 641640 + 853 641650 Gd-165 3.33440E-09 3.39270E-09 641650 + 854 641660 Gd-166 4.79180E-10 4.80250E-10 641660 + 855 641670 Gd-167 1.91010E-11 1.91010E-11 641670 + 856 651570 Tb-157 2.18520E-12 2.18520E-12 651570 + 857 651580 Tb-158 6.00590E-11 6.67800E-11 651580 + 858 651581 Tb-158m 6.76230E-12 6.76230E-12 651581 + 859 651590 Tb-159 6.01180E-10 9.72580E-06 65159.82c + 860 651600 Tb-160 2.06870E-09 2.06870E-09 65160.82c + 861 651610 Tb-161 1.40410E-08 1.21070E-06 651610 + 862 651620 Tb-162 1.91530E-08 4.25000E-07 651620 + 863 651630 Tb-163 3.77180E-08 1.48530E-07 651630 + 864 651640 Tb-164 1.89300E-08 5.04200E-08 651640 + 865 651650 Tb-165 1.28690E-08 1.62620E-08 651650 + 866 651660 Tb-166 2.93320E-09 3.41350E-09 651660 + 867 651670 Tb-167 8.27780E-10 8.46880E-10 651670 + 868 651680 Tb-168 6.28230E-11 6.28230E-11 651680 + 869 651690 Tb-169 7.38580E-12 7.38580E-12 651690 + 870 661610 Dy-161 1.21500E-11 1.21070E-06 66161.82c + 871 661620 Dy-162 1.35520E-10 4.25140E-07 66162.82c + 872 661630 Dy-163 5.03160E-10 1.49040E-07 66163.82c + 873 661640 Dy-164 1.84570E-09 5.22670E-08 66164.82c + 874 661650 Dy-165 1.78040E-09 1.83080E-08 661650 + 875 661651 Dy-165m 2.72170E-10 2.72170E-10 661651 + 876 661660 Dy-166 2.96360E-09 6.37710E-09 661660 + 877 661670 Dy-167 1.24840E-09 2.09530E-09 661670 + 878 661680 Dy-168 6.02530E-10 6.65350E-10 661680 + 879 661690 Dy-169 1.16580E-10 1.23970E-10 661690 + 880 661700 Dy-170 2.76940E-11 2.76940E-11 661700 + 881 661710 Dy-171 1.72530E-12 1.72530E-12 661710 + 882 671640 Ho-164 6.87710E-13 2.29850E-12 671640 + 883 671641 Ho-164m 1.61080E-12 1.61080E-12 671641 + 884 671650 Ho-165 2.04620E-11 1.83350E-08 67165.82c + 885 671660 Ho-166 1.61680E-11 6.39320E-09 671660 + 886 671661 Ho-166m 3.78700E-11 3.78700E-11 671661 + 887 671670 Ho-167 1.60190E-10 2.25550E-09 671670 + 888 671680 Ho-168 5.04220E-11 7.86960E-10 671680 + 889 671681 Ho-168m 7.15480E-11 7.15480E-11 671681 + 890 671690 Ho-169 1.46620E-10 2.70590E-10 671690 + 891 671700 Ho-170 3.67320E-11 3.67320E-11 671700 + 892 671701 Ho-170m 1.56820E-11 4.33760E-11 671701 + 893 671710 Ho-171 2.14230E-11 2.31480E-11 671710 + 894 671720 Ho-172 2.78660E-12 2.78660E-12 671720 + 895 681680 Er-168 3.29970E-12 7.90620E-10 68168.82c + 896 681690 Er-169 7.00880E-12 2.77600E-10 681690 + 897 681700 Er-170 1.69600E-11 9.70680E-11 68170.82c + 898 681710 Er-171 1.06150E-11 3.37630E-11 681710 + 899 681720 Er-172 8.52600E-12 1.13130E-11 681720 + 900 681730 Er-173 2.57900E-12 2.57900E-12 681730 + 901 691730 Tm-173 1.05920E-12 3.63820E-12 691730 + + Neutron-induced fission: + + Interpolation region : 2 / 3 + Interpolation energy : 4.00000E-01 MeV + Number of products : 986 / 1051 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 3.33770E-05 3.33770E-05 1001.82c + 2 10020 H-2 1.02000E-05 1.02000E-05 1002.82c + 3 10030 H-3 1.14000E-04 1.14000E-04 1003.82c + 4 20040 He-4 2.11000E-03 2.11000E-03 2004.82c + 5 190500 K-50 1.12580E-11 1.12580E-11 190500 + 6 190510 K-51 2.53560E-12 2.53560E-12 190510 + 7 200500 Ca-50 4.53140E-10 4.62330E-10 200500 + 8 200510 Ca-51 1.87210E-10 1.88550E-10 200510 + 9 200520 Ca-52 9.94480E-11 9.94480E-11 200520 + 10 200530 Ca-53 1.58120E-11 1.58120E-11 200530 + 11 200540 Ca-54 2.51390E-12 2.51390E-12 200540 + 12 210500 Sc-50 2.60110E-10 8.10890E-10 210500 + 13 210501 Sc-50m 9.54270E-11 5.57750E-10 210501 + 14 210510 Sc-51 8.80700E-10 1.07120E-09 210510 + 15 210520 Sc-52 7.66380E-10 8.68580E-10 210520 + 16 210530 Sc-53 8.34800E-10 8.45870E-10 210530 + 17 210540 Sc-54 2.50880E-10 2.53390E-10 210540 + 18 210550 Sc-55 1.11020E-10 1.11020E-10 210550 + 19 210560 Sc-56 1.43950E-11 1.43950E-11 210560 + 20 210570 Sc-57 1.85280E-12 1.85280E-12 210570 + 21 220500 Ti-50 4.30700E-11 8.60930E-10 22050.82c + 22 220510 Ti-51 1.75490E-10 1.24670E-09 220510 + 23 220520 Ti-52 9.17710E-10 1.78630E-09 220520 + 24 220530 Ti-53 1.52440E-09 2.37030E-09 220530 + 25 220540 Ti-54 2.81120E-09 3.06460E-09 220540 + 26 220550 Ti-55 2.11090E-09 2.22190E-09 220550 + 27 220560 Ti-56 1.93960E-09 1.95460E-09 220560 + 28 220570 Ti-57 4.84350E-10 4.85590E-10 220570 + 29 220580 Ti-58 1.42360E-10 1.42360E-10 220580 + 30 220590 Ti-59 1.49890E-11 1.49890E-11 220590 + 31 220600 Ti-60 1.53260E-12 1.53260E-12 220600 + 32 230510 V-51 2.20530E-12 1.24890E-09 230510 + 33 230520 V-52 2.12360E-11 1.80750E-09 230520 + 34 230530 V-53 2.34200E-10 2.60450E-09 230530 + 35 230540 V-54 6.87990E-10 3.75260E-09 230540 + 36 230550 V-55 3.06090E-09 5.28280E-09 230550 + 37 230560 V-56 4.33800E-09 6.29410E-09 230560 + 38 230570 V-57 6.85480E-09 7.33890E-09 230570 + 39 230580 V-58 3.54320E-09 3.68560E-09 230580 + 40 230590 V-59 2.72560E-09 2.74060E-09 230590 + 41 230600 V-60 5.53130E-10 5.54660E-10 230600 + 42 230610 V-61 1.34300E-10 1.34300E-10 230610 + 43 230620 V-62 1.01900E-11 1.01900E-11 230620 + 44 240530 Cr-53 1.02100E-12 2.60550E-09 24053.82c + 45 240540 Cr-54 2.21410E-11 3.77470E-09 24054.82c + 46 240550 Cr-55 1.75470E-10 5.45830E-09 240550 + 47 240560 Cr-56 1.59330E-09 7.91670E-09 240560 + 48 240570 Cr-57 3.91060E-09 1.41690E-08 240570 + 49 240580 Cr-58 1.19500E-08 1.26870E-08 240580 + 50 240590 Cr-59 1.44950E-08 1.72360E-08 240590 + 51 240600 Cr-60 1.92730E-08 1.98360E-08 240600 + 52 240610 Cr-61 8.51520E-09 8.64140E-09 240610 + 53 240620 Cr-62 4.84890E-09 4.85910E-09 240620 + 54 240630 Cr-63 8.08250E-10 8.08250E-10 240630 + 55 240640 Cr-64 1.36710E-10 1.36710E-10 240640 + 56 240650 Cr-65 8.45900E-12 8.45900E-12 240650 + 57 250560 Mn-56 9.41680E-12 7.92610E-09 250560 + 58 250570 Mn-57 1.65710E-10 1.43340E-08 250570 + 59 250580 Mn-58 7.92660E-10 1.34800E-08 250580 + 60 250581 Mn-58m 7.79170E-11 7.79170E-11 250581 + 61 250590 Mn-59 6.54860E-09 2.37840E-08 250590 + 62 250600 Mn-60 1.19180E-09 2.24220E-08 250600 + 63 250601 Mn-60m 1.21240E-08 1.21240E-08 250601 + 64 250610 Mn-61 3.51290E-08 4.37700E-08 250610 + 65 250620 Mn-62 2.80990E-08 3.05290E-08 250620 + 66 250621 Mn-62m 4.40050E-09 6.83000E-09 250621 + 67 250630 Mn-63 3.67920E-08 3.76000E-08 250630 + 68 250640 Mn-64 1.16820E-08 1.18190E-08 250640 + 69 250650 Mn-65 5.54710E-09 5.55560E-09 250650 + 70 250660 Mn-66 7.61750E-10 7.61750E-10 250660 + 71 250670 Mn-67 1.04640E-10 1.04640E-10 250670 + 72 250680 Mn-68 4.24850E-12 4.24850E-12 250680 + 73 260580 Fe-58 6.91200E-12 1.35650E-08 26058.82c + 74 260590 Fe-59 9.92840E-11 2.38840E-08 260590 + 75 260600 Fe-60 1.40080E-09 3.45520E-08 260600 + 76 260610 Fe-61 6.13040E-09 4.99010E-08 260610 + 77 260620 Fe-62 3.42600E-08 7.16190E-08 260620 + 78 260630 Fe-63 5.90890E-08 9.66890E-08 260630 + 79 260640 Fe-64 1.14380E-07 1.26200E-07 260640 + 80 260650 Fe-65 9.13420E-08 9.68980E-08 260650 + 81 260660 Fe-66 8.81780E-08 8.89400E-08 260660 + 82 260670 Fe-67 2.33640E-08 2.34690E-08 260670 + 83 260680 Fe-68 7.41730E-09 7.42150E-09 260680 + 84 260690 Fe-69 4.33910E-10 4.33910E-10 260690 + 85 260700 Fe-70 1.29350E-10 1.29350E-10 260700 + 86 260710 Fe-71 1.03410E-12 1.03410E-12 260710 + 87 270600 Co-60 1.45130E-12 1.98240E-12 270600 + 88 270610 Co-61 6.60820E-11 4.99670E-08 270610 + 89 270620 Co-62 1.83920E-10 7.18080E-08 270620 + 90 270621 Co-62m 5.01310E-10 5.01310E-10 270621 + 91 270630 Co-63 7.91620E-09 1.04610E-07 270630 + 92 270640 Co-64 2.45910E-08 1.50790E-07 270640 + 93 270650 Co-65 1.16640E-07 2.13540E-07 270650 + 94 270660 Co-66 1.73010E-07 2.61950E-07 270660 + 95 270670 Co-67 2.87750E-07 3.11220E-07 270670 + 96 270680 Co-68 9.11810E-08 1.28940E-07 270680 + 97 270681 Co-68m 6.80590E-08 7.55110E-08 270681 + 98 270690 Co-69 6.75810E-08 6.79840E-08 270690 + 99 270700 Co-70 1.98840E-08 1.98840E-08 270700 + 100 270701 Co-70m 1.98840E-08 2.00130E-08 270701 + 101 270710 Co-71 2.51230E-09 2.51330E-09 270710 + 102 270720 Co-72 3.52860E-10 3.52860E-10 270720 + 103 270730 Co-73 5.27660E-11 5.27660E-11 270730 + 104 270740 Co-74 5.64890E-12 5.64890E-12 270740 + 105 280620 Ni-62 1.27360E-12 7.23060E-08 28062.82c + 106 280630 Ni-63 2.95100E-11 1.04630E-07 280630 + 107 280640 Ni-64 6.81120E-10 1.51470E-07 28064.82c + 108 280650 Ni-65 5.80350E-09 2.19340E-07 280650 + 109 280660 Ni-66 5.56280E-08 3.17580E-07 280660 + 110 280670 Ni-67 1.44490E-07 4.55710E-07 280670 + 111 280680 Ni-68 4.72430E-07 6.39800E-07 280680 + 112 280690 Ni-69 1.57090E-07 2.24390E-07 280690 + 113 280691 Ni-69m 1.57090E-07 1.57090E-07 280691 + 114 280700 Ni-70 1.97650E-06 2.01640E-06 280700 + 115 280710 Ni-71 1.36910E-07 1.39420E-07 280710 + 116 280720 Ni-72 1.43420E-07 1.43770E-07 280720 + 117 280730 Ni-73 4.32080E-08 4.32610E-08 280730 + 118 280740 Ni-74 3.67250E-08 3.67310E-08 280740 + 119 280750 Ni-75 4.45300E-09 4.45300E-09 280750 + 120 280760 Ni-76 3.67780E-10 3.67780E-10 280760 + 121 280770 Ni-77 1.12950E-11 1.12950E-11 280770 + 122 290650 Cu-65 1.49430E-11 2.19360E-07 29065.82c + 123 290660 Cu-66 2.81920E-10 3.17860E-07 290660 + 124 290670 Cu-67 5.28950E-09 4.61000E-07 290670 + 125 290680 Cu-68 8.05170E-09 6.66290E-07 290680 + 126 290681 Cu-68m 2.19470E-08 2.19470E-08 290681 + 127 290690 Cu-69 5.21360E-07 9.02830E-07 290690 + 128 290700 Cu-70 4.94580E-08 4.16920E-07 290700 + 129 290701 Cu-70m 6.31620E-07 7.34920E-07 290701 + 130 290702 Cu-70m 4.94580E-08 2.06580E-06 290702 + 131 290710 Cu-71 6.88960E-07 8.28380E-07 290710 + 132 290720 Cu-72 8.36910E-07 9.80680E-07 290720 + 133 290730 Cu-73 8.95790E-07 9.39050E-07 290730 + 134 290740 Cu-74 2.68880E-06 2.72560E-06 290740 + 135 290750 Cu-75 6.41940E-06 6.42380E-06 290750 + 136 290760 Cu-76 2.09660E-07 2.09840E-07 290760 + 137 290761 Cu-76m 2.09660E-07 2.09840E-07 290761 + 138 290770 Cu-77 1.33660E-07 1.33670E-07 290770 + 139 290780 Cu-78 7.12380E-09 7.12380E-09 290780 + 140 290790 Cu-79 5.19120E-10 5.19120E-10 290790 + 141 300670 Zn-67 4.59790E-12 4.61000E-07 300670 + 142 300680 Zn-68 2.03600E-10 6.70000E-07 300680 + 143 300690 Zn-69 2.72500E-10 9.04460E-07 300690 + 144 300691 Zn-69m 1.35340E-09 1.35340E-09 300691 + 145 300700 Zn-70 6.66700E-08 2.81360E-06 300700 + 146 300710 Zn-71 1.26850E-08 8.41070E-07 300710 + 147 300711 Zn-71m 6.30030E-08 6.30030E-08 300711 + 148 300720 Zn-72 1.80880E-06 2.78950E-06 300720 + 149 300730 Zn-73 2.35660E-07 2.56350E-06 300730 + 150 300731 Zn-73m 3.25940E-07 1.38880E-06 300731 + 151 300732 Zn-73m 2.12580E-06 2.12580E-06 300732 + 152 300740 Zn-74 2.48990E-05 2.78490E-05 300740 + 153 300750 Zn-75 4.62510E-05 5.24560E-05 300750 + 154 300760 Zn-76 7.50520E-05 7.54650E-05 300760 + 155 300770 Zn-77 4.01400E-05 4.29450E-05 300770 + 156 300771 Zn-77m 5.34440E-06 5.34440E-06 300771 + 157 300780 Zn-78 2.97130E-05 2.97200E-05 300780 + 158 300790 Zn-79 4.32190E-06 4.32210E-06 300790 + 159 300800 Zn-80 8.97490E-07 8.97490E-07 300800 + 160 300810 Zn-81 6.78380E-09 6.78380E-09 300810 + 161 300820 Zn-82 3.86160E-10 3.86160E-10 300820 + 162 310700 Ga-70 8.04910E-11 8.04910E-11 310700 + 163 310710 Ga-71 6.99330E-10 9.04770E-07 310710 + 164 310720 Ga-72 1.22090E-08 2.80290E-06 310720 + 165 310721 Ga-72m 1.20010E-09 9.41470E-08 310721 + 166 310730 Ga-73 8.95630E-07 4.52210E-06 310730 + 167 310740 Ga-74 1.08240E-06 2.27810E-05 310740 + 168 310741 Ga-74m 1.08240E-06 2.89320E-05 310741 + 169 310750 Ga-75 2.56500E-05 7.81060E-05 310750 + 170 310760 Ga-76 5.06120E-05 1.26080E-04 310760 + 171 310770 Ga-77 2.03990E-04 2.49610E-04 310770 + 172 310780 Ga-78 1.56330E-04 1.86110E-04 310780 + 173 310790 Ga-79 2.08400E-04 2.12670E-04 310790 + 174 310800 Ga-80 6.46150E-05 6.55130E-05 310800 + 175 310810 Ga-81 3.16500E-05 3.16560E-05 310810 + 176 310820 Ga-82 2.36290E-06 2.36330E-06 310820 + 177 310830 Ga-83 1.67440E-07 1.67440E-07 310830 + 178 310840 Ga-84 5.18410E-09 5.18410E-09 310840 + 179 320720 Ge-72 2.11970E-11 2.80290E-06 32072.82c + 180 320730 Ge-73 7.42200E-10 4.52290E-06 32073.82c + 181 320731 Ge-73m 1.49440E-10 4.45580E-06 320731 + 182 320740 Ge-74 1.03480E-07 3.01180E-05 32074.82c + 183 320750 Ge-75 1.50620E-07 7.93870E-05 320750 + 184 320751 Ge-75m 1.13130E-06 4.25550E-06 320751 + 185 320760 Ge-76 1.61930E-05 1.42270E-04 32076.82c + 186 320770 Ge-77 1.42930E-04 1.93970E-04 320770 + 187 320771 Ge-77m 1.90300E-05 2.68640E-04 320771 + 188 320780 Ge-78 4.43210E-04 6.29510E-04 320780 + 189 320790 Ge-79 1.10170E-04 3.55430E-04 320790 + 190 320791 Ge-79m 8.27420E-04 8.27740E-04 320791 + 191 320800 Ge-80 1.32510E-03 1.39440E-03 320800 + 192 320810 Ge-81 9.01320E-04 9.18250E-04 320810 + 193 320811 Ge-81m 1.81480E-04 1.94890E-04 320811 + 194 320820 Ge-82 8.09230E-04 8.11150E-04 320820 + 195 320830 Ge-83 2.33410E-04 2.33520E-04 320830 + 196 320840 Ge-84 5.47020E-05 5.47040E-05 320840 + 197 320850 Ge-85 2.01300E-06 2.01300E-06 320850 + 198 320860 Ge-86 1.11280E-07 1.11280E-07 320860 + 199 320870 Ge-87 2.16670E-09 2.16670E-09 320870 + 200 330740 As-74 2.82450E-11 2.82450E-11 330740 + 201 330750 As-75 7.90350E-10 7.93920E-05 33075.82c + 202 330751 As-75m 2.99310E-09 4.26970E-09 330751 + 203 330760 As-76 8.77760E-08 8.77760E-08 330760 + 204 330770 As-77 1.27680E-06 4.12840E-04 330770 + 205 330780 As-78 1.96710E-05 6.49180E-04 330780 + 206 330790 As-79 1.35490E-04 1.28560E-03 330790 + 207 330800 As-80 5.58980E-04 1.95340E-03 330800 + 208 330810 As-81 1.25390E-03 2.36510E-03 330810 + 209 330820 As-82 4.48790E-04 1.25990E-03 330820 + 210 330821 As-82m 1.56370E-03 1.56370E-03 330821 + 211 330830 As-83 2.57950E-03 2.81890E-03 330830 + 212 330840 As-84 6.91150E-04 7.15690E-04 330840 + 213 330841 As-84m 6.91150E-04 7.15690E-04 330841 + 214 330850 As-85 8.26760E-04 8.28490E-04 330850 + 215 330860 As-86 1.74610E-04 1.74720E-04 330860 + 216 330870 As-87 5.86980E-05 5.87000E-05 330870 + 217 330880 As-88 1.04300E-06 1.04300E-06 330880 + 218 330890 As-89 3.61710E-08 3.61710E-08 330890 + 219 340760 Se-76 3.24510E-11 8.78090E-08 34076.82c + 220 340770 Se-77 3.31790E-10 4.12850E-04 34077.82c + 221 340771 Se-77m 2.49190E-09 2.49190E-09 340771 + 222 340780 Se-78 1.64030E-07 6.49340E-04 34078.82c + 223 340790 Se-79 1.04310E-05 1.29670E-03 34079.82c + 224 340791 Se-79m 1.38890E-06 1.25650E-03 340791 + 225 340800 Se-80 8.17260E-05 2.03510E-03 34080.82c + 226 340810 Se-81 6.03290E-05 2.87830E-03 340810 + 227 340811 Se-81m 4.53110E-04 5.38010E-04 340811 + 228 340820 Se-82 2.23700E-03 5.06060E-03 34082.82c + 229 340830 Se-83 5.62100E-03 6.63680E-03 340830 + 230 340831 Se-83m 1.13170E-03 2.93690E-03 340831 + 231 340840 Se-84 1.30680E-02 1.46800E-02 340840 + 232 340850 Se-85 1.20190E-02 1.27230E-02 340850 + 233 340860 Se-86 8.77610E-03 8.90220E-03 340860 + 234 340870 Se-87 4.27350E-03 4.32320E-03 340870 + 235 340880 Se-88 1.62760E-03 1.62860E-03 340880 + 236 340890 Se-89 2.92020E-04 2.92060E-04 340890 + 237 340900 Se-90 5.57280E-05 5.57280E-05 340900 + 238 340910 Se-91 2.19910E-07 2.19910E-07 340910 + 239 340920 Se-92 7.37980E-09 7.37980E-09 340920 + 240 350780 Br-78 1.61170E-11 1.61170E-11 350780 + 241 350790 Br-79 3.64780E-10 7.05380E-07 35079.82c + 242 350791 Br-79m 1.38140E-09 1.38140E-09 350791 + 243 350800 Br-80 1.35380E-08 6.07090E-08 350800 + 244 350801 Br-80m 4.71710E-08 4.71710E-08 350801 + 245 350810 Br-81 8.33700E-07 2.87940E-03 35081.82c + 246 350820 Br-82 2.64420E-05 3.59100E-05 350820 + 247 350821 Br-82m 9.70080E-06 9.70080E-06 350821 + 248 350830 Br-83 3.44930E-04 9.91860E-03 350830 + 249 350840 Br-84 8.53050E-04 1.55330E-02 350840 + 250 350841 Br-84m 8.53050E-04 8.53050E-04 350841 + 251 350850 Br-85 7.31230E-03 2.00350E-02 350850 + 252 350860 Br-86 1.23540E-02 2.12560E-02 350860 + 253 350870 Br-87 1.78080E-02 2.21470E-02 350870 + 254 350880 Br-88 1.16200E-02 1.32550E-02 350880 + 255 350890 Br-89 8.14730E-03 8.41660E-03 350890 + 256 350900 Br-90 2.45140E-03 2.50720E-03 350900 + 257 350910 Br-91 8.02320E-04 8.02490E-04 350910 + 258 350920 Br-92 6.30770E-05 6.30840E-05 350920 + 259 350930 Br-93 1.32690E-05 1.32690E-05 350930 + 260 350940 Br-94 3.53370E-08 3.53370E-08 350940 + 261 360810 Kr-81 3.56350E-10 4.03790E-10 360810 + 262 360811 Kr-81m 4.74450E-11 4.74450E-11 360811 + 263 360820 Kr-82 1.56790E-06 3.77110E-05 36082.82c + 264 360830 Kr-83 7.78310E-06 9.92790E-03 36083.82c + 265 360831 Kr-83m 1.56710E-06 9.91130E-03 360831 + 266 360840 Kr-84 1.15710E-04 1.65010E-02 36084.82c + 267 360850 Kr-85 8.35400E-04 5.18450E-03 36085.82c + 268 360851 Kr-85m 1.68200E-04 2.01710E-02 360851 + 269 360860 Kr-86 6.41830E-03 2.82300E-02 36086.82c + 270 360870 Kr-87 1.83130E-02 4.07930E-02 360870 + 271 360880 Kr-88 3.63730E-02 4.99270E-02 360880 + 272 360890 Kr-89 4.49160E-02 5.27630E-02 360890 + 273 360900 Kr-90 3.91270E-02 4.11780E-02 360900 + 274 360910 Kr-91 1.97940E-02 2.04570E-02 360910 + 275 360920 Kr-92 8.83290E-03 8.88410E-03 360920 + 276 360930 Kr-93 2.18330E-03 2.18760E-03 360930 + 277 360940 Kr-94 5.22800E-04 5.22810E-04 360940 + 278 360950 Kr-95 4.26290E-05 4.26290E-05 360950 + 279 360960 Kr-96 6.14850E-06 6.14850E-06 360960 + 280 360970 Kr-97 4.48400E-09 4.48400E-09 360970 + 281 370840 Rb-84 3.46620E-09 1.07380E-08 370840 + 282 370841 Rb-84m 7.27180E-09 7.27180E-09 370841 + 283 370850 Rb-85 2.01350E-06 2.10410E-02 37085.82c + 284 370860 Rb-86 8.27660E-06 2.56400E-05 37086.82c + 285 370861 Rb-86m 1.73630E-05 1.73630E-05 370861 + 286 370870 Rb-87 3.67170E-04 4.11600E-02 37087.82c + 287 370880 Rb-88 1.71330E-03 5.16400E-02 370880 + 288 370890 Rb-89 8.97150E-03 6.17340E-02 370890 + 289 370900 Rb-90 1.72620E-03 3.81150E-02 370900 + 290 370901 Rb-90m 1.75610E-02 2.29470E-02 370901 + 291 370910 Rb-91 3.14850E-02 5.19420E-02 370910 + 292 370920 Rb-92 2.68620E-02 3.57460E-02 370920 + 293 370930 Rb-93 2.22880E-02 2.44810E-02 370930 + 294 370940 Rb-94 8.87920E-03 9.39740E-03 370940 + 295 370950 Rb-95 3.68260E-03 3.72420E-03 370950 + 296 370960 Rb-96 2.91850E-04 4.42220E-04 370960 + 297 370961 Rb-96m 2.91850E-04 2.94820E-04 370961 + 298 370970 Rb-97 1.29190E-04 1.29190E-04 370970 + 299 370980 Rb-98 5.79400E-06 5.79400E-06 370980 + 300 370981 Rb-98m 5.79400E-06 5.79400E-06 370981 + 301 370990 Rb-99 8.97220E-07 8.97220E-07 370990 + 302 380860 Sr-86 4.28000E-09 2.56430E-05 38086.82c + 303 380870 Sr-87 1.88760E-06 2.26650E-06 38087.82c + 304 380871 Sr-87m 3.80050E-07 3.80050E-07 380871 + 305 380880 Sr-88 7.93490E-05 5.17200E-02 38088.82c + 306 380890 Sr-89 5.32850E-04 6.22670E-02 38089.82c + 307 380900 Sr-90 4.13530E-03 6.46000E-02 38090.82c + 308 380910 Sr-91 1.09550E-02 6.28970E-02 380910 + 309 380920 Sr-92 2.87940E-02 6.48830E-02 380920 + 310 380930 Sr-93 4.21570E-02 6.72450E-02 380930 + 311 380940 Sr-94 4.99550E-02 5.87240E-02 380940 + 312 380950 Sr-95 3.44760E-02 3.79390E-02 380950 + 313 380960 Sr-96 2.01170E-02 2.06800E-02 380960 + 314 380970 Sr-97 7.11430E-03 7.21190E-03 380970 + 315 380980 Sr-98 2.20660E-03 2.21750E-03 380980 + 316 380990 Sr-99 3.34320E-04 3.35070E-04 380990 + 317 381000 Sr-100 5.42740E-05 5.42740E-05 381000 + 318 381010 Sr-101 6.29370E-06 6.29370E-06 381010 + 319 381020 Sr-102 3.86570E-09 3.86570E-09 381020 + 320 390890 Y-89 7.74630E-09 6.22670E-02 39089.82c + 321 390891 Y-89m 3.84730E-08 6.04040E-06 390891 + 322 390900 Y-90 2.17580E-06 6.46060E-02 39090.82c + 323 390901 Y-90m 3.63880E-06 3.63880E-06 390901 + 324 390910 Y-91 1.83960E-05 6.30070E-02 39091.82c + 325 390911 Y-91m 9.13640E-05 3.70970E-02 390911 + 326 390920 Y-92 5.62760E-04 6.54460E-02 390920 + 327 390930 Y-93 3.96600E-04 7.06200E-02 390930 + 328 390931 Y-93m 2.97870E-03 1.98060E-02 390931 + 329 390940 Y-94 8.12170E-03 6.68450E-02 390940 + 330 390950 Y-95 2.21760E-02 6.01150E-02 390950 + 331 390960 Y-96 8.12160E-03 2.88030E-02 390960 + 332 390961 Y-96m 1.70380E-02 1.70400E-02 390961 + 333 390970 Y-97 4.38780E-03 1.06760E-02 390970 + 334 390971 Y-97m 1.62190E-02 2.17500E-02 390971 + 335 390972 Y-97m 5.57370E-03 5.57370E-03 390972 + 336 390980 Y-98 2.46240E-03 4.67990E-03 390980 + 337 390981 Y-98m 1.19380E-02 1.19380E-02 390981 + 338 390990 Y-99 8.82770E-03 9.16320E-03 390990 + 339 391000 Y-100 1.30130E-03 1.35520E-03 391000 + 340 391001 Y-100m 1.30130E-03 1.30130E-03 391001 + 341 391010 Y-101 6.98150E-04 7.04290E-04 391010 + 342 391020 Y-102 3.57450E-05 3.57470E-05 391020 + 343 391021 Y-102m 3.57450E-05 3.57470E-05 391021 + 344 391030 Y-103 1.07900E-05 1.07900E-05 391030 + 345 391040 Y-104 9.59140E-09 9.59140E-09 391040 + 346 391050 Y-105 2.11820E-10 2.11820E-10 391050 + 347 400910 Zr-91 3.28950E-06 6.30100E-02 40091.82c + 348 400920 Zr-92 1.48010E-05 6.54600E-02 40092.82c + 349 400930 Zr-93 1.19620E-04 7.07400E-02 40093.82c + 350 400940 Zr-94 8.29350E-04 6.76750E-02 40094.82c + 351 400950 Zr-95 3.19420E-03 6.33090E-02 40095.82c + 352 400960 Zr-96 1.19390E-02 5.78000E-02 40096.82c + 353 400970 Zr-97 2.09150E-02 5.47090E-02 400970 + 354 400980 Zr-98 3.36730E-02 5.00230E-02 400980 + 355 400990 Zr-99 3.21440E-02 4.11640E-02 400990 + 356 401000 Zr-100 2.76540E-02 3.02980E-02 401000 + 357 401010 Zr-101 1.16990E-02 1.24070E-02 401010 + 358 401020 Zr-102 4.39880E-03 4.46770E-03 401020 + 359 401030 Zr-103 7.99200E-04 8.09130E-04 401030 + 360 401040 Zr-104 1.84590E-04 1.84600E-04 401040 + 361 401050 Zr-105 1.34240E-05 1.34240E-05 401050 + 362 401060 Zr-106 2.68140E-08 2.68140E-08 401060 + 363 401070 Zr-107 1.93340E-10 1.93340E-10 401070 + 364 410940 Nb-94 5.91940E-07 9.44120E-07 41094.82c + 365 410941 Nb-94m 3.53950E-07 3.53950E-07 410941 + 366 410950 Nb-95 1.18350E-05 6.32850E-02 41095.82c + 367 410951 Nb-95m 2.38290E-06 6.86350E-04 410951 + 368 410960 Nb-96 9.14310E-05 9.14310E-05 410960 + 369 410970 Nb-97 5.33670E-04 5.53500E-02 410970 + 370 410971 Nb-97m 1.07450E-04 5.21070E-02 410971 + 371 410980 Nb-98 4.48140E-04 5.04710E-02 410980 + 372 410981 Nb-98m 1.56150E-03 1.56150E-03 410981 + 373 410990 Nb-99 6.08680E-03 3.24300E-02 410990 + 374 410991 Nb-99m 1.22560E-03 1.63740E-02 410991 + 375 411000 Nb-100 2.05590E-03 3.23540E-02 411000 + 376 411001 Nb-100m 9.96710E-03 9.96710E-03 411001 + 377 411010 Nb-101 1.69810E-02 2.93880E-02 411010 + 378 411020 Nb-102 5.85850E-03 1.03260E-02 411020 + 379 411021 Nb-102m 5.85850E-03 5.85850E-03 411021 + 380 411030 Nb-103 6.75400E-03 7.56310E-03 411030 + 381 411040 Nb-104 1.37590E-03 1.56060E-03 411040 + 382 411041 Nb-104m 1.37590E-03 1.37590E-03 411041 + 383 411050 Nb-105 8.83980E-04 8.97220E-04 411050 + 384 411060 Nb-106 1.09340E-04 1.09370E-04 411060 + 385 411070 Nb-107 7.61600E-06 7.61620E-06 411070 + 386 411080 Nb-108 5.30530E-06 5.30530E-06 411080 + 387 411090 Nb-109 7.44810E-10 7.44810E-10 411090 + 388 411100 Nb-110 1.42190E-11 1.42190E-11 411100 + 389 420960 Mo-96 4.49130E-09 9.14360E-05 42096.82c + 390 420970 Mo-97 1.01450E-05 5.53600E-02 42097.82c + 391 420980 Mo-98 7.80770E-05 5.21110E-02 42098.82c + 392 420990 Mo-99 4.61410E-04 4.89380E-02 42099.82c + 393 421000 Mo-100 2.25210E-03 4.45730E-02 42100.82c + 394 421010 Mo-101 4.76230E-03 3.41500E-02 421010 + 395 421020 Mo-102 8.82270E-03 2.50070E-02 421020 + 396 421030 Mo-103 7.53590E-03 1.51010E-02 421030 + 397 421040 Mo-104 7.83290E-03 1.07830E-02 421040 + 398 421050 Mo-105 3.68000E-03 4.56690E-03 421050 + 399 421060 Mo-106 1.44810E-03 1.55300E-03 421060 + 400 421070 Mo-107 3.25730E-04 3.33220E-04 421070 + 401 421080 Mo-108 8.43550E-05 8.93310E-05 421080 + 402 421090 Mo-109 2.82980E-06 2.83050E-06 421090 + 403 421100 Mo-110 6.00660E-06 6.00660E-06 421100 + 404 421110 Mo-111 4.30070E-09 4.30070E-09 421110 + 405 421120 Mo-112 1.82000E-10 1.82000E-10 421120 + 406 430990 Tc-99 1.97040E-08 4.89360E-02 43099.82c + 407 430991 Tc-99m 3.96730E-09 4.30950E-02 430991 + 408 431000 Tc-100 6.03520E-06 6.03520E-06 431000 + 409 431010 Tc-101 6.51320E-05 3.42150E-02 431010 + 410 431020 Tc-102 1.07780E-04 2.51150E-02 431020 + 411 431021 Tc-102m 1.07780E-04 1.07780E-04 431021 + 412 431030 Tc-103 5.74110E-04 1.56750E-02 431030 + 413 431040 Tc-104 1.15960E-03 1.19430E-02 431040 + 414 431050 Tc-105 1.68560E-03 6.25250E-03 431050 + 415 431060 Tc-106 1.09660E-03 2.64960E-03 431060 + 416 431070 Tc-107 7.69740E-04 1.10300E-03 431070 + 417 431080 Tc-108 2.76360E-04 3.65710E-04 431080 + 418 431090 Tc-109 1.53620E-04 1.56430E-04 431090 + 419 431100 Tc-110 6.27330E-05 6.87400E-05 431100 + 420 431110 Tc-111 2.84680E-05 2.84720E-05 431110 + 421 431120 Tc-112 4.71000E-07 4.71180E-07 431120 + 422 431130 Tc-113 3.36110E-08 3.36110E-08 431130 + 423 431140 Tc-114 7.39730E-10 7.39730E-10 431140 + 424 431150 Tc-115 1.89590E-11 1.89590E-11 431150 + 425 431180 Tc-118 5.18600E-11 5.18600E-11 431180 + 426 441010 Ru-101 1.04920E-06 3.42160E-02 44101.82c + 427 441020 Ru-102 3.20490E-06 2.52260E-02 44102.82c + 428 441030 Ru-103 5.13330E-06 1.56940E-02 44103.82c + 429 441031 Ru-103m 1.43630E-05 1.43630E-05 441031 + 430 441040 Ru-104 7.82590E-05 1.20210E-02 44104.82c + 431 441050 Ru-105 1.51160E-04 6.40370E-03 44105.82c + 432 441060 Ru-106 2.62450E-04 2.91200E-03 44106.82c + 433 441070 Ru-107 3.01560E-04 1.40450E-03 441070 + 434 441080 Ru-108 3.39920E-04 7.05750E-04 441080 + 435 441090 Ru-109 3.30430E-04 4.86770E-04 441090 + 436 441100 Ru-110 4.08020E-04 4.76730E-04 441100 + 437 441110 Ru-111 2.88740E-04 3.17220E-04 441110 + 438 441120 Ru-112 2.57410E-04 2.57880E-04 441120 + 439 441130 Ru-113 3.33620E-05 5.00740E-05 441130 + 440 441131 Ru-113m 3.33620E-05 3.33620E-05 441131 + 441 441140 Ru-114 1.55490E-05 1.55500E-05 441140 + 442 441150 Ru-115 6.20430E-06 6.20430E-06 441150 + 443 441160 Ru-116 2.98910E-06 2.98910E-06 441160 + 444 441170 Ru-117 1.47530E-10 1.47530E-10 441170 + 445 441180 Ru-118 4.66380E-07 4.66430E-07 441180 + 446 441190 Ru-119 2.18170E-08 2.18170E-08 441190 + 447 441200 Ru-120 9.88150E-10 9.88150E-10 441200 + 448 451040 Rh-104 7.54900E-10 3.38180E-09 451040 + 449 451041 Rh-104m 2.63030E-09 2.63030E-09 451041 + 450 451050 Rh-105 8.71100E-08 6.40370E-03 45105.82c + 451 451051 Rh-105m 1.15980E-08 1.81790E-03 451051 + 452 451060 Rh-106 1.17740E-06 2.91320E-03 451060 + 453 451061 Rh-106m 3.20950E-06 3.20950E-06 451061 + 454 451070 Rh-107 2.53970E-06 1.40710E-03 451070 + 455 451080 Rh-108 2.95880E-06 7.08710E-04 451080 + 456 451081 Rh-108m 1.03090E-05 1.03090E-05 451081 + 457 451090 Rh-109 4.80500E-05 5.34820E-04 451090 + 458 451100 Rh-110 1.28470E-04 6.05210E-04 451100 + 459 451101 Rh-110m 3.02450E-06 3.02450E-06 451101 + 460 451110 Rh-111 1.98510E-04 5.15730E-04 451110 + 461 451120 Rh-112 1.49000E-04 4.06880E-04 451120 + 462 451121 Rh-112m 1.49000E-04 1.49000E-04 451121 + 463 451130 Rh-113 3.33660E-04 4.00410E-04 451130 + 464 451140 Rh-114 8.94300E-05 1.04990E-04 451140 + 465 451141 Rh-114m 8.94300E-05 8.94300E-05 451141 + 466 451150 Rh-115 1.12720E-04 1.18940E-04 451150 + 467 451160 Rh-116 8.86180E-06 1.18190E-05 451160 + 468 451161 Rh-116m 2.41550E-05 2.41550E-05 451161 + 469 451170 Rh-117 1.84470E-05 1.84660E-05 451170 + 470 451180 Rh-118 4.41140E-05 4.45620E-05 451180 + 471 451190 Rh-119 1.60220E-05 1.60430E-05 451190 + 472 451200 Rh-120 1.53010E-06 1.53110E-06 451200 + 473 451210 Rh-121 1.03150E-07 1.03150E-07 451210 + 474 451220 Rh-122 3.88740E-09 3.88740E-09 451220 + 475 461060 Pd-106 1.13620E-10 2.91640E-03 46106.82c + 476 461070 Pd-107 8.70560E-10 1.40710E-03 46107.82c + 477 461071 Pd-107m 1.91340E-09 1.91340E-09 461071 + 478 461080 Pd-108 5.91590E-08 7.19080E-04 46108.82c + 479 461090 Pd-109 1.67630E-07 5.35350E-04 461090 + 480 461091 Pd-109m 3.68440E-07 2.67780E-04 461091 + 481 461100 Pd-110 9.00650E-06 6.17240E-04 46110.82c + 482 461110 Pd-111 9.88190E-06 5.40910E-04 461110 + 483 461111 Pd-111m 2.17200E-05 2.37830E-05 461111 + 484 461120 Pd-112 1.21950E-04 6.77830E-04 461120 + 485 461130 Pd-113 5.65170E-05 6.15070E-04 461130 + 486 461131 Pd-113m 1.58130E-04 1.58130E-04 461131 + 487 461140 Pd-114 3.89300E-04 5.83720E-04 461140 + 488 461150 Pd-115 1.21750E-04 2.46210E-04 461150 + 489 461151 Pd-115m 2.67610E-04 2.84880E-04 461151 + 490 461160 Pd-116 3.39130E-04 3.75100E-04 461160 + 491 461170 Pd-117 6.70870E-05 2.34310E-04 461170 + 492 461171 Pd-117m 1.47450E-04 1.47450E-04 461171 + 493 461180 Pd-118 1.26370E-04 1.69630E-04 461180 + 494 461190 Pd-119 5.71770E-05 7.33110E-05 461190 + 495 461200 Pd-120 1.73900E-05 1.88440E-05 461200 + 496 461210 Pd-121 2.64760E-05 2.65650E-05 461210 + 497 461220 Pd-122 7.91790E-06 7.92180E-06 461220 + 498 461230 Pd-123 5.06380E-07 5.06380E-07 461230 + 499 461240 Pd-124 5.20600E-08 5.20600E-08 461240 + 500 471090 Ag-109 1.83170E-11 5.35350E-04 47109.82c + 501 471091 Ag-109m 1.37570E-10 5.35090E-04 471091 + 502 471100 Ag-110 1.46170E-09 1.51580E-09 471100 + 503 471101 Ag-110m 3.98420E-09 3.98420E-09 47510.82c + 504 471110 Ag-111 1.83630E-08 5.44780E-04 47111.82c + 505 471111 Ag-111m 1.37920E-07 5.41800E-04 471111 + 506 471120 Ag-112 3.08430E-06 6.80910E-04 471120 + 507 471130 Ag-113 3.70520E-07 4.05190E-04 471130 + 508 471131 Ag-113m 2.78290E-06 5.91760E-04 471131 + 509 471140 Ag-114 2.11850E-06 5.96110E-04 471140 + 510 471141 Ag-114m 1.02700E-05 1.02700E-05 471141 + 511 471150 Ag-115 8.66740E-06 2.71070E-04 471150 + 512 471151 Ag-115m 6.50980E-05 3.93660E-04 471151 + 513 471160 Ag-116 5.92090E-05 4.44000E-04 471160 + 514 471161 Ag-116m 1.61390E-04 1.61390E-04 471161 + 515 471170 Ag-117 3.70550E-05 1.77930E-04 471170 + 516 471171 Ag-117m 2.78310E-04 3.95460E-04 471171 + 517 471180 Ag-118 3.89540E-05 2.71710E-04 471180 + 518 471181 Ag-118m 1.88850E-04 2.13100E-04 471181 + 519 471190 Ag-119 3.31620E-05 6.98170E-05 471190 + 520 471191 Ag-119m 2.49070E-04 2.85720E-04 471191 + 521 471200 Ag-120 7.22360E-05 1.29910E-04 471200 + 522 471201 Ag-120m 1.20800E-04 1.30230E-04 471201 + 523 471210 Ag-121 8.35460E-05 1.10040E-04 471210 + 524 471220 Ag-122 2.00150E-05 2.79360E-05 471220 + 525 471221 Ag-122m 2.15780E-05 2.15780E-05 471221 + 526 471230 Ag-123 2.48210E-05 2.53270E-05 471230 + 527 471240 Ag-124 1.99600E-06 3.12400E-06 471240 + 528 471241 Ag-124m 2.15190E-06 2.15190E-06 471241 + 529 471250 Ag-125 2.41720E-06 2.41720E-06 471250 + 530 471260 Ag-126 4.12280E-07 4.12280E-07 471260 + 531 471270 Ag-127 3.65450E-08 3.65450E-08 471270 + 532 471280 Ag-128 1.56570E-09 1.56570E-09 471280 + 533 481110 Cd-111 3.10860E-12 5.47490E-04 48111.82c + 534 481111 Cd-111m 1.17720E-11 1.17720E-11 481111 + 535 481120 Cd-112 1.50800E-09 6.80910E-04 48112.82c + 536 481130 Cd-113 6.33780E-09 6.11230E-04 48113.82c + 537 481131 Cd-113m 2.40010E-08 7.02920E-06 481131 + 538 481140 Cd-114 3.09990E-06 5.99210E-04 48114.82c + 539 481150 Cd-115 1.07640E-06 5.58470E-04 481150 + 540 481151 Cd-115m 4.07630E-06 2.87510E-05 48515.82c + 541 481160 Cd-116 2.37930E-05 6.19500E-04 48116.82c + 542 481170 Cd-117 1.08080E-05 4.38270E-04 481170 + 543 481171 Cd-117m 4.09290E-05 1.63130E-04 481171 + 544 481180 Cd-118 1.96600E-04 5.94030E-04 481180 + 545 481190 Cd-119 9.05700E-05 4.11200E-04 481190 + 546 481191 Cd-119m 2.53410E-04 2.88320E-04 481191 + 547 481200 Cd-120 5.59500E-04 7.71450E-04 481200 + 548 481210 Cd-121 8.58570E-05 1.84400E-04 481210 + 549 481211 Cd-121m 2.40220E-04 2.51720E-04 481211 + 550 481220 Cd-122 4.51270E-04 5.00790E-04 481220 + 551 481230 Cd-123 7.30180E-05 9.37420E-05 481230 + 552 481231 Cd-123m 2.04300E-04 2.08910E-04 481231 + 553 481240 Cd-124 4.20990E-04 4.25190E-04 481240 + 554 481250 Cd-125 6.71680E-05 6.83760E-05 481250 + 555 481251 Cd-125m 1.87930E-04 1.89140E-04 481251 + 556 481260 Cd-126 1.76140E-04 1.76550E-04 481260 + 557 481270 Cd-127 7.27200E-05 7.27570E-05 481270 + 558 481280 Cd-128 2.43460E-05 2.43480E-05 481280 + 559 481290 Cd-129 2.04270E-06 2.04270E-06 481290 + 560 481291 Cd-129m 5.71520E-06 5.71520E-06 481291 + 561 481300 Cd-130 3.13240E-08 3.13240E-08 481300 + 562 481310 Cd-131 1.05600E-09 1.05600E-09 481310 + 563 491140 In-114 2.49000E-11 1.08620E-10 491140 + 564 491141 In-114m 4.02090E-11 8.67600E-11 491141 + 565 491142 In-114m 4.65510E-11 4.65510E-11 491142 + 566 491150 In-115 4.95520E-09 5.59300E-04 49115.82c + 567 491151 In-115m 9.97710E-10 5.58470E-04 491151 + 568 491160 In-116 2.38360E-08 2.38360E-08 491160 + 569 491161 In-116m 3.84910E-08 8.30530E-08 491161 + 570 491162 In-116m 4.45620E-08 4.45620E-08 491162 + 571 491170 In-117 1.65390E-06 3.89430E-04 491170 + 572 491171 In-117m 3.33000E-07 4.04460E-04 491171 + 573 491180 In-118 1.21070E-06 5.95240E-04 491180 + 574 491181 In-118m 1.95510E-06 4.18690E-06 491181 + 575 491182 In-118m 2.26350E-06 2.26350E-06 491182 + 576 491190 In-119 3.04810E-05 3.79320E-04 491190 + 577 491191 In-119m 6.13720E-06 3.77990E-04 491191 + 578 491200 In-120 1.74610E-05 7.88910E-04 491200 + 579 491201 In-120m 1.74610E-05 1.74610E-05 491201 + 580 491202 In-120m 1.74610E-05 1.74610E-05 491202 + 581 491210 In-121 1.28010E-04 4.43610E-04 491210 + 582 491211 In-121m 2.57730E-05 1.48070E-04 491211 + 583 491220 In-122 1.14060E-04 6.14850E-04 491220 + 584 491221 In-122m 9.53750E-05 9.53750E-05 491221 + 585 491222 In-122m 9.53750E-05 9.53750E-05 491222 + 586 491230 In-123 3.51900E-04 5.87290E-04 491230 + 587 491231 In-123m 7.08530E-05 1.38110E-04 491231 + 588 491240 In-124 2.19270E-04 6.44460E-04 491240 + 589 491241 In-124m 2.36410E-04 2.36410E-04 491241 + 590 491250 In-125 5.97820E-04 8.19690E-04 491250 + 591 491251 In-125m 1.20370E-04 1.56020E-04 491251 + 592 491260 In-126 5.58100E-04 7.34650E-04 491260 + 593 491261 In-126m 6.01700E-04 6.01700E-04 491261 + 594 491270 In-127 9.77490E-04 9.77490E-04 491270 + 595 491271 In-127m 1.96810E-04 2.69570E-04 491271 + 596 491280 In-128 3.47600E-04 5.08050E-04 491280 + 597 491281 In-128m 1.36100E-04 1.60450E-04 491281 + 598 491282 In-128m 5.21500E-04 5.21500E-04 491282 + 599 491290 In-129 3.91370E-04 3.97080E-04 491290 + 600 491291 In-129m 7.88000E-05 8.08440E-05 491291 + 601 491300 In-130 2.53800E-05 2.54100E-05 491300 + 602 491301 In-130m 3.69540E-05 3.69540E-05 491301 + 603 491302 In-130m 5.14760E-05 5.14760E-05 491302 + 604 491310 In-131 6.26770E-06 6.33250E-06 491310 + 605 491311 In-131m 6.26770E-06 6.26770E-06 491311 + 606 491312 In-131m 6.26770E-06 6.26770E-06 491312 + 607 491320 In-132 2.36030E-07 2.36030E-07 491320 + 608 491330 In-133 7.86730E-09 9.45130E-09 491330 + 609 491331 In-133m 1.58400E-09 1.58400E-09 491331 + 610 501160 Sn-116 2.36770E-11 1.06910E-07 50116.82c + 611 501170 Sn-117 1.60950E-10 6.03390E-04 50117.82c + 612 501171 Sn-117m 6.09490E-10 1.32740E-06 501171 + 613 501200 Sn-120 4.14380E-10 8.23840E-04 50120.82c + 614 501210 Sn-121 6.28870E-06 5.98590E-04 501210 + 615 501211 Sn-121m 1.75950E-05 6.78490E-05 501211 + 616 501220 Sn-122 2.08240E-05 8.26420E-04 50122.82c + 617 501230 Sn-123 7.70440E-05 1.21820E-04 50123.82c + 618 501231 Sn-123m 2.75360E-05 7.08160E-04 501231 + 619 501240 Sn-124 3.05870E-04 1.18670E-03 50124.82c + 620 501250 Sn-125 3.65920E-04 5.04380E-04 50125.82c + 621 501251 Sn-125m 1.30780E-04 9.68030E-04 501251 + 622 501260 Sn-126 1.87020E-03 3.20840E-03 50126.82c + 623 501270 Sn-127 2.78560E-03 3.16660E-03 501270 + 624 501271 Sn-127m 9.95590E-04 1.85980E-03 501271 + 625 501280 Sn-128 2.71810E-03 1.11560E-02 501280 + 626 501281 Sn-128m 7.40890E-03 7.93040E-03 501281 + 627 501290 Sn-129 2.35050E-03 2.78630E-03 501290 + 628 501291 Sn-129m 6.57650E-03 6.61880E-03 501291 + 629 501300 Sn-130 1.89340E-03 1.96300E-03 501300 + 630 501301 Sn-130m 5.16100E-03 5.20540E-03 501301 + 631 501310 Sn-131 9.19390E-04 9.31540E-04 501310 + 632 501311 Sn-131m 2.57240E-03 2.57890E-03 501311 + 633 501320 Sn-132 1.02750E-03 1.02770E-03 501320 + 634 501330 Sn-133 6.27310E-05 6.27320E-05 501330 + 635 501340 Sn-134 9.27440E-06 9.27440E-06 501340 + 636 501350 Sn-135 5.96050E-08 5.96050E-08 501350 + 637 501360 Sn-136 2.52490E-09 2.52490E-09 501360 + 638 511220 Sb-122 1.63690E-11 3.83000E-11 511220 + 639 511221 Sb-122m 2.19310E-11 2.19310E-11 511221 + 640 511230 Sb-123 4.14030E-06 8.34120E-04 51123.82c + 641 511240 Sb-124 2.67980E-06 6.89690E-06 51124.82c + 642 511241 Sb-124m 2.16180E-06 5.62280E-06 511241 + 643 511242 Sb-124m 3.46100E-06 3.46100E-06 511242 + 644 511250 Sb-125 2.66260E-05 1.49900E-03 51125.82c + 645 511260 Sb-126 3.89810E-05 4.66150E-05 51126.82c + 646 511261 Sb-126m 2.43480E-05 5.45300E-05 511261 + 647 511262 Sb-126m 3.01820E-05 3.01820E-05 511262 + 648 511270 Sb-127 3.88750E-04 5.41510E-03 511270 + 649 511280 Sb-128 9.69670E-04 1.21750E-02 511280 + 650 511281 Sb-128m 1.35620E-03 1.35620E-03 511281 + 651 511290 Sb-129 4.21040E-03 1.12700E-02 511290 + 652 511291 Sb-129m 3.11590E-03 6.42520E-03 511291 + 653 511300 Sb-130 6.00900E-03 1.05750E-02 511300 + 654 511301 Sb-130m 6.00900E-03 8.61170E-03 511301 + 655 511310 Sb-131 1.86650E-02 2.21760E-02 511310 + 656 511320 Sb-132 6.46190E-03 7.48960E-03 511320 + 657 511321 Sb-132m 5.72110E-03 5.72110E-03 511321 + 658 511330 Sb-133 6.95220E-03 7.01650E-03 511330 + 659 511340 Sb-134 3.04630E-04 3.12340E-04 511340 + 660 511341 Sb-134m 8.30370E-04 8.30370E-04 511341 + 661 511350 Sb-135 1.59360E-04 1.59410E-04 511350 + 662 511360 Sb-136 1.54410E-05 1.54430E-05 511360 + 663 511370 Sb-137 1.72040E-06 1.72040E-06 511370 + 664 511380 Sb-138 7.64570E-09 7.64570E-09 511380 + 665 521250 Te-125 1.10180E-10 1.49900E-03 52125.82c + 666 521251 Te-125m 4.17240E-10 3.35430E-04 521251 + 667 521260 Te-126 5.95660E-06 9.94670E-05 52126.82c + 668 521270 Te-127 4.36050E-06 5.41000E-03 521270 + 669 521271 Te-127m 1.22000E-05 9.04590E-04 52527.82c + 670 521280 Te-128 1.85970E-04 1.36680E-02 52128.82c + 671 521290 Te-129 2.81200E-04 1.48430E-02 521290 + 672 521291 Te-129m 7.86800E-04 7.99050E-03 52529.82c + 673 521300 Te-130 4.84060E-03 2.40270E-02 52130.82c + 674 521310 Te-131 4.25940E-03 2.75350E-02 521310 + 675 521311 Te-131m 1.19180E-02 1.36930E-02 521311 + 676 521320 Te-132 3.19200E-02 4.51310E-02 52132.82c + 677 521330 Te-133 1.08330E-02 2.21530E-02 521330 + 678 521331 Te-133m 3.03100E-02 3.15240E-02 521331 + 679 521340 Te-134 3.65880E-02 3.77550E-02 521340 + 680 521350 Te-135 1.16010E-02 1.17380E-02 521350 + 681 521360 Te-136 3.28650E-03 3.30020E-03 521360 + 682 521370 Te-137 6.38770E-04 6.39650E-04 521370 + 683 521380 Te-138 9.95010E-05 9.95090E-05 521380 + 684 521390 Te-139 9.81260E-06 9.81260E-06 521390 + 685 521400 Te-140 1.11490E-06 1.11490E-06 521400 + 686 521410 Te-141 1.77640E-09 1.77640E-09 521410 + 687 531270 I-127 3.48050E-10 5.43170E-03 53127.82c + 688 531280 I-128 2.66170E-08 2.66170E-08 531280 + 689 531290 I-129 2.22010E-06 1.78010E-02 53129.82c + 690 531300 I-130 2.71170E-05 3.54730E-05 53130.82c + 691 531301 I-130m 9.94820E-06 9.94820E-06 531301 + 692 531310 I-131 3.81810E-04 3.87340E-02 53131.82c + 693 531320 I-132 1.10320E-03 4.70740E-02 531320 + 694 531321 I-132m 9.76770E-04 9.76770E-04 531321 + 695 531330 I-133 4.91280E-03 5.67090E-02 531330 + 696 531331 I-133m 3.63570E-03 3.63570E-03 531331 + 697 531340 I-134 1.18150E-02 5.97900E-02 531340 + 698 531341 I-134m 1.04610E-02 1.04610E-02 531341 + 699 531350 I-135 3.87370E-02 5.04750E-02 53135.82c + 700 531360 I-136 5.99180E-03 9.30160E-03 531360 + 701 531361 I-136m 1.63320E-02 1.63420E-02 531361 + 702 531370 I-137 1.24780E-02 1.31050E-02 531370 + 703 531380 I-138 3.59990E-03 3.69310E-03 531380 + 704 531390 I-139 1.56920E-03 1.57900E-03 531390 + 705 531400 I-140 2.22550E-04 2.23670E-04 531400 + 706 531410 I-141 4.45700E-05 4.45720E-05 531410 + 707 531420 I-142 1.10780E-06 1.10780E-06 531420 + 708 531430 I-143 8.96840E-09 8.96840E-09 531430 + 709 541300 Xe-130 1.10560E-08 3.70760E-05 54130.82c + 710 541310 Xe-131 1.74840E-06 3.87410E-02 54131.82c + 711 541311 Xe-131m 4.89200E-06 4.25620E-04 541311 + 712 541320 Xe-132 1.92590E-05 4.72560E-02 54132.82c + 713 541321 Xe-132m 2.58020E-05 2.58020E-05 541321 + 714 541330 Xe-133 1.03830E-04 5.71030E-02 54133.82c + 715 541331 Xe-133m 2.90500E-04 1.90460E-03 541331 + 716 541340 Xe-134 7.39630E-04 6.27870E-02 54134.82c + 717 541341 Xe-134m 2.01610E-03 2.25670E-03 541341 + 718 541350 Xe-135 3.16880E-03 6.24070E-02 54135.82c + 719 541351 Xe-135m 8.86620E-03 1.71990E-02 541351 + 720 541360 Xe-136 4.18360E-02 6.83310E-02 54136.82c + 721 541370 Xe-137 4.69110E-02 5.93600E-02 541370 + 722 541380 Xe-138 4.68610E-02 5.05130E-02 541380 + 723 541390 Xe-139 2.77030E-02 2.91480E-02 541390 + 724 541400 Xe-140 1.54170E-02 1.56290E-02 541400 + 725 541410 Xe-141 5.61760E-03 5.65310E-03 541410 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Cs-142 1.40670E-02 1.52340E-02 551420 + 746 551430 Cs-143 5.83150E-03 5.97770E-03 551430 + 747 551440 Cs-144 7.32650E-04 1.11920E-03 551440 + 748 551441 Cs-144m 7.32650E-04 7.32650E-04 551441 + 749 551450 Cs-145 2.45060E-04 2.45090E-04 551450 + 750 551460 Cs-146 1.77340E-05 1.77350E-05 551460 + 751 551470 Cs-147 2.55760E-06 2.55760E-06 551470 + 752 551480 Cs-148 1.44190E-09 1.44190E-09 551480 + 753 561350 Ba-135 5.38080E-09 2.04360E-08 56135.82c + 754 561351 Ba-135m 1.50550E-08 1.50550E-08 561351 + 755 561360 Ba-136 1.96380E-06 5.42020E-04 56136.82c + 756 561361 Ba-136m 5.35280E-06 5.35280E-06 561361 + 757 561370 Ba-137 2.58430E-05 6.48480E-02 56137.82c + 758 561371 Ba-137m 7.23080E-05 6.11960E-02 561371 + 759 561380 Ba-138 1.48890E-03 6.55170E-02 56138.82c + 760 561390 Ba-139 6.20370E-03 6.39310E-02 561390 + 761 561400 Ba-140 2.04030E-02 6.18900E-02 56140.82c + 762 561410 Ba-141 2.92380E-02 6.35970E-02 561410 + 763 561420 Ba-142 4.61800E-02 6.15120E-02 561420 + 764 561430 Ba-143 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581510 + 803 581520 Ce-152 7.59820E-05 7.59920E-05 581520 + 804 581530 Ce-153 3.81740E-06 3.81760E-06 581530 + 805 581540 Ce-154 2.10780E-08 2.10780E-08 581540 + 806 581550 Ce-155 1.79010E-10 1.79010E-10 581550 + 807 581560 Ce-156 6.14790E-12 6.14790E-12 581560 + 808 591420 Pr-142 3.92000E-10 1.46050E-09 59142.82c + 809 591421 Pr-142m 1.06850E-09 1.06850E-09 591421 + 810 591430 Pr-143 1.13260E-06 5.36410E-02 59143.82c + 811 591440 Pr-144 1.03840E-07 4.51090E-02 591440 + 812 591441 Pr-144m 1.05640E-06 6.23520E-04 591441 + 813 591450 Pr-145 5.72030E-05 3.25260E-02 591450 + 814 591460 Pr-146 1.96330E-04 2.43650E-02 591460 + 815 591470 Pr-147 7.61840E-04 1.75140E-02 591470 + 816 591480 Pr-148 2.34530E-04 1.09490E-02 591480 + 817 591481 Pr-148m 1.13700E-03 1.13700E-03 591481 + 818 591490 Pr-149 2.27870E-03 7.00240E-03 591490 + 819 591500 Pr-150 2.04040E-03 3.80660E-03 591500 + 820 591510 Pr-151 1.48270E-03 1.94870E-03 591510 + 821 591520 Pr-152 6.11300E-04 6.87320E-04 591520 + 822 591530 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4.49600E-07 611590 + 861 611600 Pm-160 2.23990E-09 2.24150E-09 611600 + 862 611610 Pm-161 1.03920E-09 1.03920E-09 611610 + 863 611620 Pm-162 4.11180E-11 4.11180E-11 611620 + 864 621500 Sm-150 1.99980E-09 5.39030E-06 62150.82c + 865 621510 Sm-151 8.38240E-07 3.15420E-03 62151.82c + 866 621520 Sm-152 7.20920E-07 1.95490E-03 62152.82c + 867 621530 Sm-153 1.19380E-06 1.10900E-03 62153.82c + 868 621531 Sm-153m 3.34000E-06 3.34000E-06 621531 + 869 621540 Sm-154 1.57120E-05 4.63210E-04 62154.82c + 870 621550 Sm-155 1.69130E-05 1.66040E-04 621550 + 871 621560 Sm-156 5.72250E-05 1.57860E-04 621560 + 872 621570 Sm-157 6.66380E-05 1.06600E-04 621570 + 873 621580 Sm-158 1.73910E-05 2.47670E-05 621580 + 874 621590 Sm-159 1.64140E-05 1.68630E-05 621590 + 875 621600 Sm-160 1.02920E-06 1.03140E-06 621600 + 876 621610 Sm-161 2.40940E-07 2.41980E-07 621610 + 877 621620 Sm-162 7.55750E-08 7.56160E-08 621620 + 878 621630 Sm-163 7.66270E-10 7.66270E-10 621630 + 879 621640 Sm-164 2.30400E-11 2.30400E-11 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651610 Tb-161 6.02070E-08 4.95750E-06 651610 + 919 651620 Tb-162 3.49420E-07 7.21730E-06 651620 + 920 651630 Tb-163 2.61210E-07 1.92860E-06 651630 + 921 651640 Tb-164 1.60900E-07 4.16970E-07 651640 + 922 651650 Tb-165 1.35490E-07 1.70780E-07 651650 + 923 651660 Tb-166 3.94180E-08 4.55950E-08 651660 + 924 651670 Tb-167 1.37940E-08 1.41090E-08 651670 + 925 651680 Tb-168 1.34770E-09 1.36390E-09 651680 + 926 651690 Tb-169 1.95200E-10 1.95200E-10 651690 + 927 651700 Tb-170 8.07560E-12 8.07560E-12 651700 + 928 661610 Dy-161 5.43970E-11 4.95750E-06 66161.82c + 929 661620 Dy-162 2.49540E-09 7.21980E-06 66162.82c + 930 661630 Dy-163 3.62330E-09 1.93220E-06 66163.82c + 931 661640 Dy-164 1.57520E-08 4.32730E-07 66164.82c + 932 661650 Dy-165 1.97250E-08 1.93080E-07 661650 + 933 661651 Dy-165m 2.62620E-09 2.62620E-09 661651 + 934 661660 Dy-166 3.97990E-08 8.53940E-08 661660 + 935 661670 Dy-167 2.14460E-08 3.55550E-08 661670 + 936 661680 Dy-168 1.29000E-08 1.42640E-08 661680 + 937 661690 Dy-169 3.17590E-09 3.37110E-09 661690 + 938 661700 Dy-170 9.34970E-10 9.43050E-10 661700 + 939 661710 Dy-171 7.48190E-11 7.48190E-11 661710 + 940 661720 Dy-172 7.07640E-12 7.07640E-12 661720 + 941 671630 Ho-163 2.00570E-12 2.27270E-12 671630 + 942 671640 Ho-164 5.52180E-12 2.05730E-11 671640 + 943 671641 Ho-164m 1.50510E-11 1.50510E-11 671641 + 944 671650 Ho-165 2.25770E-10 1.93360E-07 67165.82c + 945 671660 Ho-166 2.03350E-10 8.55970E-08 671660 + 946 671661 Ho-166m 5.54280E-10 5.54280E-10 671661 + 947 671670 Ho-167 2.77480E-09 3.83290E-08 671670 + 948 671680 Ho-168 1.01540E-09 1.69690E-08 671680 + 949 671681 Ho-168m 1.69810E-09 1.69810E-09 671681 + 950 671690 Ho-169 4.01260E-09 7.38370E-09 671690 + 951 671700 Ho-170 1.34230E-09 1.34230E-09 671700 + 952 671701 Ho-170m 4.92430E-10 1.43550E-09 671701 + 953 671710 Ho-171 9.32390E-10 1.00720E-09 671710 + 954 671720 Ho-172 1.55780E-10 1.62860E-10 671720 + 955 671730 Ho-173 3.78850E-11 3.78850E-11 671730 + 956 671740 Ho-174 2.40390E-12 2.40390E-12 671740 + 957 681660 Er-166 1.33230E-12 8.55990E-08 68166.82c + 958 681670 Er-167 8.77220E-12 3.83390E-08 68167.82c + 959 681671 Er-167m 1.16800E-12 4.58120E-09 681671 + 960 681680 Er-168 7.32780E-11 1.70510E-08 68168.82c + 961 681690 Er-169 1.97280E-10 7.58100E-09 681690 + 962 681700 Er-170 5.90010E-10 3.36780E-09 68170.82c + 963 681710 Er-171 4.73340E-10 1.48060E-09 681710 + 964 681720 Er-172 4.72350E-10 6.35210E-10 681720 + 965 681730 Er-173 1.82240E-10 2.20130E-10 681730 + 966 681740 Er-174 7.61860E-11 7.85900E-11 681740 + 967 681750 Er-175 1.07030E-11 1.07030E-11 681750 + 968 681760 Er-176 1.91600E-12 1.91600E-12 681760 + 969 691700 Tm-170 2.99040E-12 2.99040E-12 691700 + 970 691710 Tm-171 1.75470E-11 1.49810E-09 691710 + 971 691720 Tm-172 3.07060E-11 6.65910E-10 691720 + 972 691730 Tm-173 7.47460E-11 2.94870E-10 691730 + 973 691740 Tm-174 4.84000E-11 1.26990E-10 691740 + 974 691750 Tm-175 4.09500E-11 5.16530E-11 691750 + 975 691760 Tm-176 1.19950E-11 1.39110E-11 691760 + 976 691770 Tm-177 4.21800E-12 4.21800E-12 691770 + 977 701730 Yb-173 1.01310E-12 2.95880E-10 701730 + 978 701740 Yb-174 4.63580E-12 1.31630E-10 701740 + 979 701750 Yb-175 5.84050E-12 5.82710E-11 701750 + 980 701751 Yb-175m 7.77630E-13 4.05500E-11 701751 + 981 701760 Yb-176 3.83360E-12 2.42870E-11 701760 + 982 701761 Yb-176m 8.04240E-12 1.49980E-11 701761 + 983 701770 Yb-177 5.35250E-12 1.06480E-11 701770 + 984 701771 Yb-177m 1.07770E-12 5.29570E-12 701771 + 985 701780 Yb-178 3.89570E-12 3.89570E-12 701780 + 986 711790 Lu-179 1.05800E-12 1.19890E-12 711790 + + Neutron-induced fission: + + Interpolation region : 3 / 3 + Interpolation energy : 1.40000E+01 MeV + Number of products : 1162 / 1197 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 3.09570E-05 3.09570E-05 1001.82c + 2 10020 H-2 9.46060E-06 9.46060E-06 1002.82c + 3 10030 H-3 2.48000E-04 2.48000E-04 1003.82c + 4 20040 He-4 1.95700E-03 1.95700E-03 2004.82c + 5 190500 K-50 7.08760E-11 7.08760E-11 190500 + 6 190510 K-51 9.33630E-12 9.33630E-12 190510 + 7 200500 Ca-50 6.62280E-09 6.67750E-09 200500 + 8 200510 Ca-51 2.06010E-09 2.06510E-09 200510 + 9 200520 Ca-52 6.28110E-10 6.28110E-10 200520 + 10 200530 Ca-53 7.78500E-11 7.78500E-11 200530 + 11 200540 Ca-54 8.05200E-12 8.05200E-12 200540 + 12 210500 Sc-50 1.04880E-08 1.93750E-08 210500 + 13 210501 Sc-50m 2.32240E-09 9.00000E-09 210501 + 14 210510 Sc-51 2.03770E-08 2.24550E-08 210510 + 15 210520 Sc-52 1.32040E-08 1.38430E-08 210520 + 16 210530 Sc-53 9.69710E-09 9.75160E-09 210530 + 17 210540 Sc-54 2.42540E-09 2.43350E-09 210540 + 18 210550 Sc-55 6.16440E-10 6.16440E-10 210550 + 19 210560 Sc-56 5.81910E-11 5.81910E-11 210560 + 20 210570 Sc-57 4.73180E-12 4.73180E-12 210570 + 21 220500 Ti-50 3.22940E-09 2.27170E-08 22050.82c + 22 220510 Ti-51 9.90310E-09 3.23580E-08 220510 + 23 220520 Ti-52 3.10870E-08 4.49300E-08 220520 + 24 220530 Ti-53 4.36340E-08 5.33860E-08 220530 + 25 220540 Ti-54 5.76890E-08 6.01230E-08 220540 + 26 220550 Ti-55 3.22670E-08 3.28830E-08 220550 + 27 220560 Ti-56 1.85670E-08 1.86270E-08 220560 + 28 220570 Ti-57 3.72440E-09 3.72760E-09 220570 + 29 220580 Ti-58 6.63990E-10 6.63990E-10 220580 + 30 220590 Ti-59 5.08340E-11 5.08340E-11 220590 + 31 220600 Ti-60 2.97210E-12 2.97210E-12 220600 + 32 230500 V-50 1.50240E-11 1.50240E-11 230500 + 33 230510 V-51 2.75970E-10 3.26340E-08 230510 + 34 230520 V-52 1.86500E-09 4.67950E-08 230520 + 35 230530 V-53 1.35430E-08 6.69290E-08 230530 + 36 230540 V-54 3.38110E-08 9.39330E-08 230540 + 37 230550 V-55 9.19640E-08 1.24850E-07 230550 + 38 230560 V-56 1.03830E-07 1.22470E-07 230560 + 39 230570 V-57 1.14060E-07 1.17780E-07 230570 + 40 230580 V-58 4.62250E-08 4.68890E-08 230580 + 41 230590 V-59 2.21000E-08 2.21510E-08 230590 + 42 230600 V-60 3.24670E-09 3.24970E-09 230600 + 43 230610 V-61 8.42080E-10 8.42080E-10 230610 + 44 230620 V-62 4.49280E-11 4.49280E-11 230620 + 45 240520 Cr-52 9.25720E-12 4.68040E-08 24052.82c + 46 240530 Cr-53 1.60200E-10 6.70890E-08 24053.82c + 47 240540 Cr-54 2.32330E-09 9.62590E-08 24054.82c + 48 240550 Cr-55 1.31280E-08 1.37970E-07 240550 + 49 240560 Cr-56 7.44230E-08 1.97360E-07 240560 + 50 240570 Cr-57 1.52840E-07 3.07660E-07 240570 + 51 240580 Cr-58 3.05850E-07 3.15230E-07 240580 + 52 240590 Cr-59 2.96310E-07 3.18460E-07 240590 + 53 240600 Cr-60 2.46950E-07 2.50250E-07 240600 + 54 240610 Cr-61 1.49870E-07 1.50660E-07 240610 + 55 240620 Cr-62 5.09690E-08 5.10140E-08 240620 + 56 240630 Cr-63 1.28800E-09 1.28800E-09 240630 + 57 240640 Cr-64 3.37670E-10 3.37670E-10 240640 + 58 240650 Cr-65 6.10100E-12 6.10100E-12 240650 + 59 250540 Mn-54 2.46790E-12 2.46790E-12 250540 + 60 250550 Mn-55 8.84220E-11 1.38060E-07 25055.82c + 61 250560 Mn-56 1.16360E-09 1.98530E-07 250560 + 62 250570 Mn-57 1.34200E-08 3.21080E-07 250570 + 63 250580 Mn-58 5.07510E-08 3.65980E-07 250580 + 64 250581 Mn-58m 3.13620E-09 3.13620E-09 250581 + 65 250590 Mn-59 2.56350E-07 5.74810E-07 250590 + 66 250600 Mn-60 2.22220E-08 3.13830E-07 250600 + 67 250601 Mn-60m 3.59600E-07 3.59600E-07 250601 + 68 250610 Mn-61 1.40290E-06 1.55360E-06 250610 + 69 250620 Mn-62 7.98900E-07 8.24410E-07 250620 + 70 250621 Mn-62m 7.85300E-08 1.04040E-07 250621 + 71 250630 Mn-63 1.29990E-07 1.31280E-07 250630 + 72 250640 Mn-64 8.17650E-08 8.21030E-08 250640 + 73 250650 Mn-65 9.61600E-09 9.62210E-09 250650 + 74 250660 Mn-66 2.79510E-09 2.79510E-09 250660 + 75 250670 Mn-67 4.50890E-10 4.50890E-10 250670 + 76 250680 Mn-68 1.51910E-11 1.51910E-11 250680 + 77 260560 Fe-56 1.28620E-12 1.98530E-07 26056.82c + 78 260570 Fe-57 3.71190E-11 3.21110E-07 26057.82c + 79 260580 Fe-58 9.24700E-10 3.70040E-07 26058.82c + 80 260590 Fe-59 9.90970E-09 5.84720E-07 260590 + 81 260600 Fe-60 3.81820E-07 1.01390E-06 260600 + 82 260610 Fe-61 4.67640E-07 2.02120E-06 260610 + 83 260620 Fe-62 2.26260E-06 3.19100E-06 260620 + 84 260630 Fe-63 7.56590E-07 8.87870E-07 260630 + 85 260640 Fe-64 1.44830E-06 1.53040E-06 260640 + 86 260650 Fe-65 4.10060E-07 4.19680E-07 260650 + 87 260660 Fe-66 7.19850E-07 7.22650E-07 260660 + 88 260670 Fe-67 2.84670E-07 2.85120E-07 260670 + 89 260680 Fe-68 6.26890E-08 6.27040E-08 260680 + 90 260690 Fe-69 4.82270E-09 4.82270E-09 260690 + 91 260700 Fe-70 3.30040E-10 3.30040E-10 260700 + 92 260710 Fe-71 9.63840E-12 9.63840E-12 260710 + 93 270590 Co-59 1.51870E-11 5.84740E-07 27059.82c + 94 270600 Co-60 2.57990E-10 3.14980E-10 270600 + 95 270601 Co-60m 5.71310E-11 5.71310E-11 270601 + 96 270610 Co-61 1.13900E-08 2.03260E-06 270610 + 97 270620 Co-62 6.83660E-08 3.26250E-06 270620 + 98 270621 Co-62m 3.08720E-07 3.08720E-07 270621 + 99 270630 Co-63 1.26480E-07 1.01440E-06 270630 + 100 270640 Co-64 9.65500E-07 2.49590E-06 270640 + 101 270650 Co-65 1.49890E-06 1.91860E-06 270650 + 102 270660 Co-66 4.07950E-06 4.80220E-06 270660 + 103 270670 Co-67 6.13210E-06 6.41720E-06 270670 + 104 270680 Co-68 1.11310E-06 1.38570E-06 270680 + 105 270681 Co-68m 4.82070E-07 5.45110E-07 270681 + 106 270690 Co-69 1.60590E-06 1.61040E-06 270690 + 107 270700 Co-70 1.43810E-07 1.43810E-07 270700 + 108 270701 Co-70m 1.43810E-07 1.44140E-07 270701 + 109 270710 Co-71 5.81400E-08 5.81500E-08 270710 + 110 270720 Co-72 3.85130E-09 3.85130E-09 270720 + 111 270730 Co-73 2.56810E-10 2.56810E-10 270730 + 112 270740 Co-74 9.09100E-12 9.09100E-12 270740 + 113 280610 Ni-61 7.02390E-12 2.03260E-06 28061.82c + 114 280620 Ni-62 3.43450E-10 3.56850E-06 28062.82c + 115 280630 Ni-63 1.21390E-09 1.01560E-06 280630 + 116 280640 Ni-64 4.45000E-08 2.54040E-06 28064.82c + 117 280650 Ni-65 1.16100E-07 2.03470E-06 280650 + 118 280660 Ni-66 2.26640E-06 7.06860E-06 280660 + 119 280670 Ni-67 9.19770E-06 1.56150E-05 280670 + 120 280680 Ni-68 1.91420E-05 2.08160E-05 280680 + 121 280690 Ni-69 8.03000E-06 9.62430E-06 280690 + 122 280691 Ni-69m 8.03000E-06 8.03000E-06 280691 + 123 280700 Ni-70 1.76050E-05 1.78930E-05 280700 + 124 280710 Ni-71 9.89060E-06 9.94880E-06 280710 + 125 280720 Ni-72 4.73430E-06 4.73810E-06 280720 + 126 280730 Ni-73 5.90940E-07 5.91200E-07 280730 + 127 280740 Ni-74 8.33090E-08 8.33180E-08 280740 + 128 280750 Ni-75 4.18940E-09 4.18940E-09 280750 + 129 280760 Ni-76 2.00460E-10 2.00460E-10 280760 + 130 290640 Cu-64 3.78980E-11 3.78980E-11 290640 + 131 290650 Cu-65 6.31450E-10 2.03530E-06 29065.82c + 132 290660 Cu-66 2.55830E-08 7.09410E-06 290660 + 133 290670 Cu-67 7.66500E-07 1.63810E-05 290670 + 134 290680 Cu-68 5.78370E-07 2.35890E-05 290680 + 135 290681 Cu-68m 2.61170E-06 2.61170E-06 290681 + 136 290690 Cu-69 1.52550E-05 3.29090E-05 290690 + 137 290700 Cu-70 9.67810E-07 1.12740E-05 290700 + 138 290701 Cu-70m 1.96690E-05 2.06130E-05 290701 + 139 290702 Cu-70m 9.67810E-07 1.88610E-05 290702 + 140 290710 Cu-71 4.86260E-05 5.85750E-05 290710 + 141 290720 Cu-72 4.81390E-05 5.28770E-05 290720 + 142 290730 Cu-73 6.16850E-05 6.22760E-05 290730 + 143 290740 Cu-74 2.04960E-05 2.05790E-05 290740 + 144 290750 Cu-75 7.66800E-06 7.67210E-06 290750 + 145 290760 Cu-76 8.84950E-07 8.85050E-07 290760 + 146 290761 Cu-76m 8.84950E-07 8.85050E-07 290761 + 147 290770 Cu-77 6.67800E-08 6.67800E-08 290770 + 148 290780 Cu-78 2.73440E-09 2.73440E-09 290780 + 149 290790 Cu-79 9.86220E-11 9.86220E-11 290790 + 150 300660 Zn-66 2.26210E-11 7.09410E-06 300660 + 151 300670 Zn-67 1.29650E-09 1.63830E-05 300670 + 152 300680 Zn-68 3.99880E-08 2.40460E-05 300680 + 153 300690 Zn-69 1.79220E-07 3.45150E-05 300690 + 154 300691 Zn-69m 1.42670E-06 1.42670E-06 300691 + 155 300700 Zn-70 8.80080E-06 4.82990E-05 300700 + 156 300710 Zn-71 2.66690E-06 6.12420E-05 300710 + 157 300711 Zn-71m 2.12300E-05 2.12300E-05 300711 + 158 300720 Zn-72 7.88830E-05 1.31760E-04 300720 + 159 300730 Zn-73 8.55540E-06 1.47030E-04 300730 + 160 300731 Zn-73m 1.21710E-05 7.62030E-05 300731 + 161 300732 Zn-73m 1.28060E-04 1.28060E-04 300732 + 162 300740 Zn-74 2.58820E-04 2.79670E-04 300740 + 163 300750 Zn-75 2.34510E-04 2.41940E-04 300750 + 164 300760 Zn-76 1.91380E-04 1.93120E-04 300760 + 165 300770 Zn-77 8.44090E-05 8.79920E-05 300770 + 166 300771 Zn-77m 7.03180E-06 7.03180E-06 300771 + 167 300780 Zn-78 3.12420E-05 3.12450E-05 300780 + 168 300790 Zn-79 7.99610E-06 7.99610E-06 300790 + 169 300800 Zn-80 5.79150E-08 5.79150E-08 300800 + 170 300810 Zn-81 1.52900E-09 1.52900E-09 300810 + 171 310680 Ga-68 7.59530E-12 7.59530E-12 310680 + 172 310690 Ga-69 5.27440E-10 3.45160E-05 310690 + 173 310700 Ga-70 1.27780E-08 1.27780E-08 310700 + 174 310710 Ga-71 1.64820E-06 8.41200E-05 310710 + 175 310720 Ga-72 2.97220E-06 1.34920E-04 310720 + 176 310721 Ga-72m 1.83670E-07 4.57400E-06 310721 + 177 310730 Ga-73 2.63060E-05 2.37370E-04 310730 + 178 310740 Ga-74 4.01180E-05 2.79960E-04 310740 + 179 310741 Ga-74m 4.01180E-05 3.19790E-04 310741 + 180 310750 Ga-75 2.87780E-04 5.29720E-04 310750 + 181 310760 Ga-76 4.51420E-04 6.44540E-04 310760 + 182 310770 Ga-77 6.04040E-04 6.95550E-04 310770 + 183 310780 Ga-78 4.31340E-04 4.62690E-04 310780 + 184 310790 Ga-79 3.07340E-04 3.15230E-04 310790 + 185 310800 Ga-80 1.06610E-04 1.06670E-04 310800 + 186 310810 Ga-81 2.85210E-05 2.85220E-05 310810 + 187 310820 Ga-82 1.89590E-06 1.89590E-06 310820 + 188 310830 Ga-83 2.69230E-08 2.69230E-08 310830 + 189 310840 Ga-84 4.61510E-10 4.61510E-10 310840 + 190 320700 Ge-70 1.74620E-12 1.27270E-08 32070.82c + 191 320710 Ge-71 1.98980E-11 1.78300E-10 320710 + 192 320711 Ge-71m 1.58400E-10 1.58400E-10 320711 + 193 320720 Ge-72 1.07970E-08 1.34930E-04 32072.82c + 194 320730 Ge-73 2.26630E-07 2.37630E-04 32073.82c + 195 320731 Ge-73m 2.84690E-08 2.33920E-04 320731 + 196 320740 Ge-74 1.28070E-05 3.72710E-04 32074.82c + 197 320750 Ge-75 4.38720E-06 5.86750E-04 320750 + 198 320751 Ge-75m 5.26640E-05 7.38530E-05 320751 + 199 320760 Ge-76 2.73030E-04 9.17570E-04 32076.82c + 200 320770 Ge-77 6.47680E-04 7.90080E-04 320770 + 201 320771 Ge-77m 5.39550E-05 7.49500E-04 320771 + 202 320780 Ge-78 1.74030E-03 2.20330E-03 320780 + 203 320790 Ge-79 1.60520E-04 5.52090E-04 320790 + 204 320791 Ge-79m 1.92690E-03 1.92730E-03 320791 + 205 320800 Ge-80 2.59020E-03 2.70030E-03 320800 + 206 320810 Ge-81 1.30490E-03 1.32010E-03 320810 + 207 320811 Ge-81m 1.63920E-04 1.75980E-04 320811 + 208 320820 Ge-82 7.90030E-04 7.91530E-04 320820 + 209 320830 Ge-83 1.35360E-04 1.35380E-04 320830 + 210 320840 Ge-84 1.99660E-05 1.99660E-05 320840 + 211 320850 Ge-85 2.67170E-07 2.67170E-07 320850 + 212 320860 Ge-86 1.09810E-08 1.09810E-08 320860 + 213 330730 As-73 6.60350E-11 6.60350E-11 330730 + 214 330740 As-74 3.42730E-09 3.42730E-09 330740 + 215 330750 As-75 2.20620E-08 5.86930E-04 33075.82c + 216 330751 As-75m 1.36320E-07 1.58470E-07 330751 + 217 330760 As-76 8.84860E-07 8.84860E-07 330760 + 218 330770 As-77 3.15740E-05 1.42870E-03 330770 + 219 330780 As-78 1.83180E-04 2.38650E-03 330780 + 220 330790 As-79 7.50400E-04 3.15280E-03 330790 + 221 330800 As-80 1.79330E-03 4.49360E-03 330800 + 222 330810 As-81 3.49400E-03 4.98830E-03 330810 + 223 330820 As-82 6.26440E-04 1.41800E-03 330820 + 224 330821 As-82m 3.54430E-03 3.54430E-03 330821 + 225 330830 As-83 3.74000E-03 3.87750E-03 330830 + 226 330840 As-84 6.58150E-04 6.67070E-04 330840 + 227 330841 As-84m 6.58150E-04 6.67070E-04 330841 + 228 330850 As-85 4.68440E-04 4.68670E-04 330850 + 229 330860 As-86 8.86800E-05 8.86910E-05 330860 + 230 330870 As-87 1.63590E-05 1.63590E-05 330870 + 231 330880 As-88 8.81510E-08 8.81510E-08 330880 + 232 330890 As-89 3.03990E-09 3.03990E-09 330890 + 233 340750 Se-75 1.68250E-11 1.68250E-11 340750 + 234 340760 Se-76 1.83750E-09 8.86700E-07 34076.82c + 235 340770 Se-77 1.35080E-07 1.43050E-03 34077.82c + 236 340771 Se-77m 1.62150E-06 1.62150E-06 340771 + 237 340780 Se-78 3.67300E-06 2.39010E-03 34078.82c + 238 340790 Se-79 5.71780E-05 3.21300E-03 34079.82c + 239 340791 Se-79m 4.76330E-06 3.08280E-03 340791 + 240 340800 Se-80 4.20090E-04 4.91380E-03 34080.82c + 241 340810 Se-81 1.23530E-04 6.59390E-03 340810 + 242 340811 Se-81m 1.48290E-03 1.66190E-03 340811 + 243 340820 Se-82 4.92760E-03 9.88980E-03 34082.82c + 244 340830 Se-83 7.52170E-03 8.91860E-03 340830 + 245 340831 Se-83m 9.44870E-04 3.42740E-03 340831 + 246 340840 Se-84 1.33710E-02 1.48060E-02 340840 + 247 340850 Se-85 8.99800E-03 9.39280E-03 340850 + 248 340860 Se-86 6.16880E-03 6.23070E-03 340860 + 249 340870 Se-87 2.09600E-03 2.10980E-03 340870 + 250 340880 Se-88 5.92800E-04 5.92890E-04 340880 + 251 340890 Se-89 9.09940E-05 9.09970E-05 340890 + 252 340900 Se-90 8.70570E-06 8.70570E-06 340900 + 253 340910 Se-91 2.09330E-08 2.09330E-08 340910 + 254 350780 Br-78 4.07250E-10 4.07250E-10 350780 + 255 350790 Br-79 3.94270E-09 1.75470E-06 35079.82c + 256 350791 Br-79m 2.43610E-08 2.43610E-08 350791 + 257 350800 Br-80 2.75170E-07 1.83200E-06 350800 + 258 350801 Br-80m 1.55680E-06 1.55680E-06 350801 + 259 350810 Br-81 2.66200E-05 6.62130E-03 35081.82c + 260 350820 Br-82 1.48500E-04 1.80590E-04 350820 + 261 350821 Br-82m 3.28840E-05 3.28840E-05 350821 + 262 350830 Br-83 1.08480E-03 1.34310E-02 350830 + 263 350840 Br-84 1.80650E-03 1.66130E-02 350840 + 264 350841 Br-84m 1.80650E-03 1.80650E-03 350841 + 265 350850 Br-85 1.01900E-02 1.95830E-02 350850 + 266 350860 Br-86 1.22100E-02 1.84410E-02 350860 + 267 350870 Br-87 1.64540E-02 1.85700E-02 350870 + 268 350880 Br-88 8.42790E-03 9.02200E-03 350880 + 269 350890 Br-89 4.72290E-03 4.80680E-03 350890 + 270 350900 Br-90 1.04870E-03 1.05740E-03 350900 + 271 350910 Br-91 3.06670E-04 3.06690E-04 350910 + 272 350920 Br-92 2.31120E-05 2.31120E-05 350920 + 273 350930 Br-93 1.00780E-06 1.00780E-06 350930 + 274 350940 Br-94 2.75870E-09 2.75870E-09 350940 + 275 360800 Kr-80 1.76570E-10 1.68010E-06 36080.82c + 276 360810 Kr-81 7.23370E-09 7.83630E-09 360810 + 277 360811 Kr-81m 6.02610E-10 6.02610E-10 360811 + 278 360820 Kr-82 1.89570E-06 1.83280E-04 36082.82c + 279 360830 Kr-83 2.83330E-05 1.34630E-02 36083.82c + 280 360831 Kr-83m 3.55920E-06 1.34220E-02 360831 + 281 360840 Kr-84 3.70860E-04 1.87910E-02 36084.82c + 282 360850 Kr-85 1.69010E-03 5.95130E-03 36085.82c + 283 360851 Kr-85m 2.12310E-04 1.97630E-02 360851 + 284 360860 Kr-86 8.71700E-03 2.76240E-02 36086.82c + 285 360870 Kr-87 1.87060E-02 3.74140E-02 360870 + 286 360880 Kr-88 3.01020E-02 3.91970E-02 360880 + 287 360890 Kr-89 3.05540E-02 3.49430E-02 360890 + 288 360900 Kr-90 2.35520E-02 2.44110E-02 360900 + 289 360910 Kr-91 9.50470E-03 9.75770E-03 360910 + 290 360920 Kr-92 3.43610E-03 3.45230E-03 360920 + 291 360930 Kr-93 7.27180E-04 7.27500E-04 360930 + 292 360940 Kr-94 1.57360E-04 1.57360E-04 360940 + 293 360950 Kr-95 1.36540E-05 1.36540E-05 360950 + 294 360960 Kr-96 8.80990E-07 8.80990E-07 360960 + 295 370830 Rb-83 3.82270E-10 2.13680E-09 370830 + 296 370831 Rb-83m 1.75450E-09 1.75450E-09 370831 + 297 370840 Rb-84 2.11040E-07 9.49330E-07 370840 + 298 370841 Rb-84m 7.38290E-07 7.38290E-07 370841 + 299 370850 Rb-85 1.57160E-05 2.15010E-02 37085.82c + 300 370860 Rb-86 2.43600E-05 1.09580E-04 37086.82c + 301 370861 Rb-86m 8.52200E-05 8.52200E-05 370861 + 302 370870 Rb-87 1.14940E-03 3.85640E-02 37087.82c + 303 370880 Rb-88 3.48560E-03 4.26830E-02 370880 + 304 370890 Rb-89 1.29720E-02 4.79150E-02 370890 + 305 370900 Rb-90 1.11450E-03 2.28840E-02 370900 + 306 370901 Rb-90m 1.80340E-02 2.12270E-02 370901 + 307 370910 Rb-91 2.77060E-02 3.74640E-02 370910 + 308 370920 Rb-92 1.99720E-02 2.34240E-02 370920 + 309 370930 Rb-93 1.59410E-02 1.66700E-02 370930 + 310 370940 Rb-94 5.33240E-03 5.48840E-03 370940 + 311 370950 Rb-95 1.76180E-03 1.77510E-03 370950 + 312 370960 Rb-96 1.43790E-04 2.16320E-04 370960 + 313 370961 Rb-96m 1.43790E-04 1.44210E-04 370961 + 314 370970 Rb-97 4.82240E-05 4.82240E-05 370970 + 315 370980 Rb-98 4.27650E-07 4.27650E-07 370980 + 316 370981 Rb-98m 4.27650E-07 4.27650E-07 370981 + 317 370990 Rb-99 8.67960E-07 8.67960E-07 370990 + 318 380850 Sr-85 5.53230E-10 6.13420E-10 380850 + 319 380851 Sr-85m 6.94970E-11 6.94970E-11 380851 + 320 380860 Sr-86 1.00520E-06 1.10580E-04 38086.82c + 321 380870 Sr-87 8.30170E-06 9.34140E-06 38087.82c + 322 380871 Sr-87m 1.04290E-06 1.04290E-06 380871 + 323 380880 Sr-88 2.32910E-04 4.29160E-02 38088.82c + 324 380890 Sr-89 1.08770E-03 4.90030E-02 38089.82c + 325 380900 Sr-90 5.36770E-03 4.89270E-02 38090.82c + 326 380910 Sr-91 1.14390E-02 4.89030E-02 380910 + 327 380920 Sr-92 2.26820E-02 4.63400E-02 380920 + 328 380930 Sr-93 3.12390E-02 4.82300E-02 380930 + 329 380940 Sr-94 3.65040E-02 4.15910E-02 380940 + 330 380950 Sr-95 2.04030E-02 2.20540E-02 380950 + 331 380960 Sr-96 1.09580E-02 1.12290E-02 380960 + 332 380970 Sr-97 3.14710E-03 3.18330E-03 380970 + 333 380980 Sr-98 8.19540E-04 8.20470E-04 380980 + 334 380990 Sr-99 9.88650E-05 9.95950E-05 380990 + 335 381000 Sr-100 1.29220E-05 1.29220E-05 381000 + 336 381010 Sr-101 2.54500E-08 2.54500E-08 381010 + 337 390880 Y-88 1.60160E-09 4.14820E-09 390880 + 338 390881 Y-88m 2.54660E-09 2.54660E-09 390881 + 339 390890 Y-89 6.59310E-07 4.90090E-02 39089.82c + 340 390891 Y-89m 5.24850E-06 9.97190E-06 390891 + 341 390900 Y-90 6.20450E-06 4.89510E-02 39090.82c + 342 390901 Y-90m 1.77330E-05 1.77330E-05 390901 + 343 390910 Y-91 3.75960E-05 4.92400E-02 39091.82c + 344 390911 Y-91m 2.99280E-04 2.90710E-02 390911 + 345 390920 Y-92 1.21860E-03 4.75580E-02 390920 + 346 390930 Y-93 4.56920E-04 5.41720E-02 390930 + 347 390931 Y-93m 5.48480E-03 1.75540E-02 390931 + 348 390940 Y-94 1.19900E-02 5.35810E-02 390940 + 349 390950 Y-95 2.29290E-02 4.49830E-02 390950 + 350 390960 Y-96 4.88860E-03 1.61190E-02 390960 + 351 390961 Y-96m 1.71020E-02 1.71030E-02 390961 + 352 390970 Y-97 2.30330E-03 5.13250E-03 390970 + 353 390971 Y-97m 1.06660E-02 1.72750E-02 390971 + 354 390972 Y-97m 7.66950E-03 7.66950E-03 390972 + 355 390980 Y-98 1.17880E-03 1.99930E-03 390980 + 356 390981 Y-98m 9.24420E-03 9.24420E-03 390981 + 357 390990 Y-99 5.06960E-03 5.16930E-03 390990 + 358 391000 Y-100 6.55500E-04 6.68320E-04 391000 + 359 391001 Y-100m 6.55500E-04 6.55500E-04 391001 + 360 391010 Y-101 3.51110E-04 3.51130E-04 391010 + 361 391020 Y-102 2.28050E-05 2.28050E-05 391020 + 362 391021 Y-102m 2.28050E-05 2.28050E-05 391021 + 363 391030 Y-103 7.32470E-06 7.32470E-06 391030 + 364 391040 Y-104 2.07770E-09 2.07770E-09 391040 + 365 400910 Zr-91 1.02270E-06 4.92410E-02 40091.82c + 366 400920 Zr-92 3.91200E-05 4.75970E-02 40092.82c + 367 400930 Zr-93 2.63450E-04 5.44350E-02 40093.82c + 368 400940 Zr-94 1.55610E-03 5.51370E-02 40094.82c + 369 400950 Zr-95 4.66170E-03 4.96450E-02 40095.82c + 370 400960 Zr-96 1.40560E-02 4.72920E-02 40096.82c + 371 400970 Zr-97 2.10010E-02 4.51310E-02 400970 + 372 400980 Zr-98 2.92370E-02 4.02450E-02 400980 + 373 400990 Zr-99 2.11090E-02 2.61970E-02 400990 + 374 401000 Zr-100 1.57670E-02 1.70850E-02 401000 + 375 401010 Zr-101 6.52370E-03 6.87710E-03 401010 + 376 401020 Zr-102 2.72250E-03 2.76650E-03 401020 + 377 401030 Zr-103 5.29670E-04 5.36410E-04 401030 + 378 401040 Zr-104 1.09770E-04 1.09770E-04 401040 + 379 401050 Zr-105 1.00180E-05 1.00180E-05 401050 + 380 401060 Zr-106 2.15850E-06 2.15850E-06 401060 + 381 401070 Zr-107 3.89970E-10 3.89970E-10 401070 + 382 410930 Nb-93 4.55590E-09 5.12820E-09 41093.82c + 383 410931 Nb-93m 5.72310E-10 5.72310E-10 410931 + 384 410940 Nb-94 5.03290E-06 6.78510E-06 41094.82c + 385 410941 Nb-94m 1.76100E-06 1.76100E-06 410941 + 386 410950 Nb-95 5.25970E-05 4.96740E-02 41095.82c + 387 410951 Nb-95m 6.60720E-06 5.42950E-04 410951 + 388 410960 Nb-96 2.73090E-04 2.73090E-04 410960 + 389 410970 Nb-97 1.44280E-03 4.67550E-02 410970 + 390 410971 Nb-97m 1.81240E-04 4.30780E-02 410971 + 391 410980 Nb-98 6.16020E-04 4.08610E-02 410980 + 392 410981 Nb-98m 3.48530E-03 3.48530E-03 410981 + 393 410990 Nb-99 9.60450E-03 2.63780E-02 410990 + 394 410991 Nb-99m 1.20650E-03 1.08470E-02 410991 + 395 411000 Nb-100 1.66130E-03 1.87460E-02 411000 + 396 411001 Nb-100m 1.30280E-02 1.30280E-02 411001 + 397 411010 Nb-101 1.97380E-02 2.66150E-02 411010 + 398 411020 Nb-102 6.80700E-03 9.57350E-03 411020 + 399 411021 Nb-102m 6.80700E-03 6.80700E-03 411021 + 400 411030 Nb-103 9.78240E-03 1.03190E-02 411030 + 401 411040 Nb-104 1.69860E-03 1.80850E-03 411040 + 402 411041 Nb-104m 1.69860E-03 1.69860E-03 411041 + 403 411050 Nb-105 1.36350E-03 1.37340E-03 411050 + 404 411060 Nb-106 2.28730E-04 2.30860E-04 411060 + 405 411070 Nb-107 6.46840E-05 6.46840E-05 411070 + 406 411080 Nb-108 6.01410E-06 6.01410E-06 411080 + 407 411090 Nb-109 2.18450E-09 2.18450E-09 411090 + 408 420950 Mo-95 9.10190E-07 4.97050E-02 42095.82c + 409 420960 Mo-96 2.64300E-06 2.75730E-04 42096.82c + 410 420970 Mo-97 3.24440E-05 4.67880E-02 42097.82c + 411 420980 Mo-98 2.08110E-04 4.45540E-02 42098.82c + 412 420990 Mo-99 8.99630E-04 3.79070E-02 42099.82c + 413 421000 Mo-100 3.22590E-03 3.50000E-02 42100.82c + 414 421010 Mo-101 6.45130E-03 3.30660E-02 421010 + 415 421020 Mo-102 1.23330E-02 2.87130E-02 421020 + 416 421030 Mo-103 1.30780E-02 2.33990E-02 421030 + 417 421040 Mo-104 1.28620E-02 1.63900E-02 421040 + 418 421050 Mo-105 7.35670E-03 8.71710E-03 421050 + 419 421060 Mo-106 3.99310E-03 4.21750E-03 421060 + 420 421070 Mo-107 1.38990E-03 1.45110E-03 421070 + 421 421080 Mo-108 5.63410E-04 5.69050E-04 421080 + 422 421090 Mo-109 1.16040E-04 1.16040E-04 421090 + 423 421100 Mo-110 2.53010E-05 2.53010E-05 421100 + 424 421110 Mo-111 1.15120E-06 1.15120E-06 421110 + 425 421120 Mo-112 5.62960E-10 5.62960E-10 421120 + 426 430980 Tc-98 2.15710E-09 2.15710E-09 430980 + 427 430990 Tc-99 6.93990E-06 3.79140E-02 43099.82c + 428 430991 Tc-99m 8.71790E-07 3.33820E-02 430991 + 429 431000 Tc-100 2.86220E-05 2.86220E-05 431000 + 430 431010 Tc-101 2.67810E-04 3.33340E-02 431010 + 431 431020 Tc-102 4.38320E-04 2.91520E-02 431020 + 432 431021 Tc-102m 4.38320E-04 4.38320E-04 431021 + 433 431030 Tc-103 2.77460E-03 2.61730E-02 431030 + 434 431040 Tc-104 4.41460E-03 2.08050E-02 431040 + 435 431050 Tc-105 7.73530E-03 1.64520E-02 431050 + 436 431060 Tc-106 6.53100E-03 1.07480E-02 431060 + 437 431070 Tc-107 7.80160E-03 9.25270E-03 431070 + 438 431080 Tc-108 4.72440E-03 5.29410E-03 431080 + 439 431090 Tc-109 2.89110E-03 3.00650E-03 431090 + 440 431100 Tc-110 1.09120E-03 1.11650E-03 431100 + 441 431110 Tc-111 3.67390E-04 3.68530E-04 431110 + 442 431120 Tc-112 9.87360E-05 9.87370E-05 431120 + 443 431130 Tc-113 1.13900E-05 1.13900E-05 431130 + 444 431140 Tc-114 8.40490E-07 8.40490E-07 431140 + 445 441010 Ru-101 1.13110E-08 3.33340E-02 44101.82c + 446 441020 Ru-102 2.06500E-05 2.96110E-02 44102.82c + 447 441030 Ru-103 1.83610E-05 2.62760E-02 44103.82c + 448 441031 Ru-103m 8.42690E-05 8.42690E-05 441031 + 449 441040 Ru-104 3.67900E-04 2.11730E-02 44104.82c + 450 441050 Ru-105 9.23190E-04 1.73760E-02 44105.82c + 451 441060 Ru-106 2.25790E-03 1.30060E-02 44106.82c + 452 441070 Ru-107 3.99720E-03 1.32500E-02 441070 + 453 441080 Ru-108 6.78030E-03 1.20770E-02 441080 + 454 441090 Ru-109 6.55750E-03 9.56210E-03 441090 + 455 441100 Ru-110 6.88540E-03 8.00150E-03 441100 + 456 441110 Ru-111 3.90880E-03 4.27880E-03 441110 + 457 441120 Ru-112 2.70640E-03 2.80450E-03 441120 + 458 441130 Ru-113 2.10320E-04 3.26110E-04 441130 + 459 441131 Ru-113m 2.10320E-04 2.10320E-04 441131 + 460 441140 Ru-114 1.42860E-04 1.43650E-04 441140 + 461 441150 Ru-115 3.00000E-05 3.00000E-05 441150 + 462 441160 Ru-116 2.39240E-06 2.39240E-06 441160 + 463 441170 Ru-117 3.81710E-10 3.81710E-10 441170 + 464 441180 Ru-118 9.73560E-08 9.73560E-08 441180 + 465 441190 Ru-119 1.69940E-09 1.69940E-09 441190 + 466 451030 Rh-103 6.27340E-11 2.62760E-02 45103.82c + 467 451031 Rh-103m 7.53060E-10 2.59610E-02 451031 + 468 451040 Rh-104 1.81290E-07 1.20570E-06 451040 + 469 451041 Rh-104m 1.02570E-06 1.02570E-06 451041 + 470 451050 Rh-105 1.73400E-05 1.73940E-02 45105.82c + 471 451051 Rh-105m 1.44460E-06 4.93400E-03 451051 + 472 451060 Rh-106 1.07610E-05 1.30170E-02 451060 + 473 451061 Rh-106m 4.85960E-05 4.85960E-05 451061 + 474 451070 Rh-107 3.25690E-04 1.35760E-02 451070 + 475 451080 Rh-108 1.25760E-04 1.22020E-02 451080 + 476 451081 Rh-108m 7.11550E-04 7.11550E-04 451081 + 477 451090 Rh-109 2.17500E-03 1.17370E-02 451090 + 478 451100 Rh-110 3.85660E-03 1.18580E-02 451100 + 479 451101 Rh-110m 5.79350E-05 5.79350E-05 451101 + 480 451110 Rh-111 6.94080E-03 1.12200E-02 451110 + 481 451120 Rh-112 4.27360E-03 7.07810E-03 451120 + 482 451121 Rh-112m 4.27360E-03 4.27360E-03 451121 + 483 451130 Rh-113 5.54170E-03 5.97300E-03 451130 + 484 451140 Rh-114 1.22980E-03 1.37360E-03 451140 + 485 451141 Rh-114m 1.22980E-03 1.22980E-03 451141 + 486 451150 Rh-115 1.67280E-03 1.70280E-03 451150 + 487 451160 Rh-116 7.92080E-05 8.15750E-05 451160 + 488 451161 Rh-116m 3.57680E-04 3.57680E-04 451161 + 489 451170 Rh-117 1.21410E-04 1.21410E-04 451170 + 490 451180 Rh-118 1.45600E-05 1.46530E-05 451180 + 491 451190 Rh-119 8.71740E-06 8.71900E-06 451190 + 492 451200 Rh-120 3.71250E-07 3.71250E-07 451200 + 493 451210 Rh-121 1.37040E-08 1.37040E-08 451210 + 494 451220 Rh-122 2.81860E-10 2.81860E-10 451220 + 495 461060 Pd-106 1.07920E-06 1.30670E-02 46106.82c + 496 461070 Pd-107 7.66920E-07 1.35790E-02 46107.82c + 497 461071 Pd-107m 2.82690E-06 2.82690E-06 461071 + 498 461080 Pd-108 2.64410E-05 1.29410E-02 46108.82c + 499 461090 Pd-109 2.49150E-05 1.18540E-02 461090 + 500 461091 Pd-109m 9.18350E-05 5.96040E-03 461091 + 501 461100 Pd-110 4.48940E-04 1.23650E-02 46110.82c + 502 461110 Pd-111 2.64400E-04 1.21830E-02 461110 + 503 461111 Pd-111m 9.74600E-04 1.01950E-03 461111 + 504 461120 Pd-112 4.12750E-03 1.54790E-02 461120 + 505 461130 Pd-113 6.86060E-04 9.80790E-03 461130 + 506 461131 Pd-113m 3.14880E-03 3.14880E-03 461131 + 507 461140 Pd-114 6.00020E-03 8.60360E-03 461140 + 508 461150 Pd-115 1.40650E-03 3.29650E-03 461150 + 509 461151 Pd-115m 5.18420E-03 5.43150E-03 461151 + 510 461160 Pd-116 5.46660E-03 5.90590E-03 461160 + 511 461170 Pd-117 4.58680E-04 2.27120E-03 461170 + 512 461171 Pd-117m 1.69070E-03 1.69070E-03 461171 + 513 461180 Pd-118 1.04770E-03 1.06190E-03 461180 + 514 461190 Pd-119 2.39000E-04 2.47740E-04 461190 + 515 461200 Pd-120 7.05110E-05 7.08620E-05 461200 + 516 461210 Pd-121 1.00960E-05 1.01080E-05 461210 + 517 461220 Pd-122 2.68220E-06 2.68250E-06 461220 + 518 461230 Pd-123 9.49330E-08 9.49330E-08 461230 + 519 461240 Pd-124 2.96980E-09 2.96980E-09 461240 + 520 471080 Ag-108 5.69750E-11 7.93590E-11 471080 + 521 471081 Ag-108m 2.57290E-10 2.57290E-10 471081 + 522 471090 Ag-109 1.45590E-09 1.18540E-02 47109.82c + 523 471091 Ag-109m 1.74760E-08 1.18480E-02 471091 + 524 471100 Ag-110 2.08510E-07 2.21320E-07 471100 + 525 471101 Ag-110m 9.41590E-07 9.41590E-07 47510.82c + 526 471110 Ag-111 3.35660E-06 1.24410E-02 47111.82c + 527 471111 Ag-111m 4.02920E-05 1.23330E-02 471111 + 528 471120 Ag-112 1.56550E-04 1.56360E-02 471120 + 529 471130 Ag-113 3.77530E-05 6.75460E-03 471130 + 530 471131 Ag-113m 4.53180E-04 9.84490E-03 471131 + 531 471140 Ag-114 1.41520E-04 9.85490E-03 471140 + 532 471141 Ag-114m 1.10980E-03 1.10980E-03 471141 + 533 471150 Ag-115 3.29530E-04 4.80290E-03 471150 + 534 471151 Ag-115m 3.95570E-03 9.84270E-03 471151 + 535 471160 Ag-116 1.05620E-03 7.24820E-03 471160 + 536 471161 Ag-116m 4.76950E-03 4.76950E-03 471161 + 537 471170 Ag-117 6.10450E-04 2.25390E-03 471170 + 538 471171 Ag-117m 7.32780E-03 8.46350E-03 471171 + 539 471180 Ag-118 6.57550E-04 3.74400E-03 471180 + 540 471181 Ag-118m 5.15630E-03 5.30820E-03 471181 + 541 471190 Ag-119 3.30820E-04 4.54690E-04 471190 + 542 471191 Ag-119m 3.97110E-03 4.09490E-03 471191 + 543 471200 Ag-120 4.69850E-04 1.01530E-03 471200 + 544 471201 Ag-120m 1.34290E-03 1.37830E-03 471201 + 545 471210 Ag-121 8.54180E-04 8.64260E-04 471210 + 546 471220 Ag-122 6.58970E-05 6.85800E-05 471220 + 547 471221 Ag-122m 1.26220E-04 1.26220E-04 471221 + 548 471230 Ag-123 9.82480E-05 9.83430E-05 471230 + 549 471240 Ag-124 2.37780E-06 4.65810E-06 471240 + 550 471241 Ag-124m 4.55460E-06 4.55460E-06 471241 + 551 471250 Ag-125 3.38530E-06 3.38530E-06 471250 + 552 471260 Ag-126 2.15150E-08 2.15150E-08 471260 + 553 471270 Ag-127 6.67290E-10 6.67290E-10 471270 + 554 481110 Cd-111 2.96930E-10 1.25020E-02 48111.82c + 555 481111 Cd-111m 1.83470E-09 1.83470E-09 481111 + 556 481120 Cd-112 1.54250E-07 1.56360E-02 48112.82c + 557 481130 Cd-113 1.95080E-06 1.01840E-02 48113.82c + 558 481131 Cd-113m 1.20530E-05 1.28830E-04 481131 + 559 481140 Cd-114 6.20050E-05 9.91690E-03 48114.82c + 560 481150 Cd-115 4.86780E-05 1.21240E-02 481150 + 561 481151 Cd-115m 3.00770E-04 8.03910E-04 48515.82c + 562 481160 Cd-116 1.38360E-03 1.31150E-02 48116.82c + 563 481170 Cd-117 3.96990E-04 8.25430E-03 481170 + 564 481171 Cd-117m 2.45290E-03 4.80510E-03 481171 + 565 481180 Cd-118 5.49100E-03 1.23670E-02 481180 + 566 481190 Cd-119 1.04320E-03 5.36560E-03 481190 + 567 481191 Cd-119m 4.78820E-03 5.01550E-03 481191 + 568 481200 Cd-120 7.30050E-03 9.18410E-03 481200 + 569 481210 Cd-121 8.83910E-04 1.65790E-03 481210 + 570 481211 Cd-121m 4.05690E-03 4.14720E-03 481211 + 571 481220 Cd-122 3.69020E-03 3.88500E-03 481220 + 572 481230 Cd-123 2.97030E-04 3.77490E-04 481230 + 573 481231 Cd-123m 1.36330E-03 1.38120E-03 481231 + 574 481240 Cd-124 1.02610E-03 1.03300E-03 481240 + 575 481250 Cd-125 6.14490E-05 6.31410E-05 481250 + 576 481251 Cd-125m 2.82030E-04 2.83720E-04 481251 + 577 481260 Cd-126 1.22560E-04 1.22580E-04 481260 + 578 481270 Cd-127 3.07440E-05 3.07450E-05 481270 + 579 481280 Cd-128 7.60380E-06 7.60380E-06 481280 + 580 481290 Cd-129 1.34430E-09 1.34430E-09 481290 + 581 481291 Cd-129m 6.17000E-09 6.17000E-09 481291 + 582 491130 In-113 2.79890E-10 1.28650E-04 49113.82c + 583 491131 In-113m 3.51600E-11 3.51600E-11 491131 + 584 491140 In-114 1.42520E-09 9.20650E-09 491140 + 585 491141 In-114m 2.64360E-09 8.06350E-09 491141 + 586 491142 In-114m 5.41990E-09 5.41990E-09 491142 + 587 491150 In-115 2.04840E-06 1.23240E-02 49115.82c + 588 491151 In-115m 2.57320E-07 1.21240E-02 491151 + 589 491160 In-116 3.77210E-06 3.77210E-06 491160 + 590 491161 In-116m 6.99680E-06 2.13420E-05 491161 + 591 491162 In-116m 1.43450E-05 1.43450E-05 491162 + 592 491170 In-117 1.17170E-04 9.14320E-03 491170 + 593 491171 In-117m 1.47190E-05 7.65240E-03 491171 + 594 491180 In-118 7.06770E-05 1.24380E-02 491180 + 595 491181 In-118m 1.31090E-04 3.96110E-04 491181 + 596 491182 In-118m 2.68780E-04 2.68780E-04 491182 + 597 491190 In-119 1.24500E-03 7.05190E-03 491190 + 598 491191 In-119m 1.56400E-04 5.01120E-03 491191 + 599 491200 In-120 9.01680E-04 1.00860E-02 491200 + 600 491201 In-120m 9.01680E-04 9.01680E-04 491201 + 601 491202 In-120m 9.01680E-04 9.01680E-04 491202 + 602 491210 In-121 4.86220E-03 9.58830E-03 491210 + 603 491211 In-121m 6.10790E-04 1.71030E-03 491211 + 604 491220 In-122 1.47770E-03 5.36270E-03 491220 + 605 491221 In-122m 2.11160E-03 2.11160E-03 491221 + 606 491222 In-122m 2.11160E-03 2.11160E-03 491222 + 607 491230 In-123 6.68360E-03 8.16480E-03 491230 + 608 491231 In-123m 8.39590E-04 1.11700E-03 491231 + 609 491240 In-124 1.82800E-03 2.86100E-03 491240 + 610 491241 In-124m 3.50130E-03 3.50130E-03 491241 + 611 491250 In-125 4.52880E-03 4.84270E-03 491250 + 612 491251 In-125m 5.68900E-04 6.01820E-04 491251 + 613 491260 In-126 9.74910E-04 1.09750E-03 491260 + 614 491261 In-126m 1.86740E-03 1.86740E-03 491261 + 615 491270 In-127 1.76230E-03 1.76230E-03 491270 + 616 491271 In-127m 2.21380E-04 2.52130E-04 491271 + 617 491280 In-128 1.65740E-04 2.31880E-04 491280 + 618 491281 In-128m 5.85370E-05 6.61410E-05 491281 + 619 491282 In-128m 4.29710E-04 4.29710E-04 491282 + 620 491290 In-129 2.14160E-04 2.14160E-04 491290 + 621 491291 In-129m 2.69020E-05 2.69040E-05 491291 + 622 491300 In-130 5.51770E-06 5.51770E-06 491300 + 623 491301 In-130m 1.78830E-05 1.78830E-05 491301 + 624 491302 In-130m 1.33350E-05 1.33350E-05 491302 + 625 491310 In-131 1.54950E-06 1.56520E-06 491310 + 626 491311 In-131m 1.54950E-06 1.54950E-06 491311 + 627 491312 In-131m 1.54950E-06 1.54950E-06 491312 + 628 491320 In-132 9.86210E-10 9.86210E-10 491320 + 629 501160 Sn-116 2.39630E-09 2.51160E-05 50116.82c + 630 501170 Sn-117 1.70170E-07 1.31930E-02 50117.82c + 631 501171 Sn-117m 1.05140E-06 3.22030E-05 501171 + 632 501180 Sn-118 3.63810E-06 1.28410E-02 50118.82c + 633 501190 Sn-119 4.32920E-06 1.18130E-02 50119.82c + 634 501191 Sn-119m 2.67490E-05 6.39750E-03 501191 + 635 501200 Sn-120 2.48550E-04 1.21400E-02 50120.82c + 636 501210 Sn-121 1.15160E-04 1.15600E-02 501210 + 637 501211 Sn-121m 5.28530E-04 1.61470E-03 501211 + 638 501220 Sn-122 1.90930E-03 1.14960E-02 50122.82c + 639 501230 Sn-123 2.72490E-03 3.34740E-03 50123.82c + 640 501231 Sn-123m 5.93700E-04 9.25300E-03 501231 + 641 501240 Sn-124 6.64290E-03 1.30050E-02 50124.82c + 642 501250 Sn-125 6.29420E-03 7.11230E-03 50125.82c + 643 501251 Sn-125m 1.37140E-03 5.99790E-03 501251 + 644 501260 Sn-126 1.18420E-02 1.48090E-02 50126.82c + 645 501270 Sn-127 8.29390E-03 8.98080E-03 501270 + 646 501271 Sn-127m 1.80710E-03 3.13290E-03 501271 + 647 501280 Sn-128 1.93460E-03 1.13330E-02 501280 + 648 501281 Sn-128m 8.73640E-03 9.16610E-03 501281 + 649 501290 Sn-129 9.86130E-04 1.20450E-03 501290 + 650 501291 Sn-129m 4.52610E-03 4.54890E-03 501291 + 651 501300 Sn-130 5.42650E-04 5.59920E-04 501300 + 652 501301 Sn-130m 2.45040E-03 2.46990E-03 501301 + 653 501310 Sn-131 1.48400E-04 1.51400E-04 501310 + 654 501311 Sn-131m 6.81090E-04 6.82710E-04 501311 + 655 501320 Sn-132 1.19580E-04 1.19580E-04 501320 + 656 501330 Sn-133 4.92600E-06 4.92600E-06 501330 + 657 501340 Sn-134 1.58300E-06 1.58300E-06 501340 + 658 511200 Sb-120 6.40350E-07 6.40350E-07 511200 + 659 511201 Sb-120m 1.83010E-06 1.83010E-06 511201 + 660 511210 Sb-121 1.76650E-05 1.19390E-02 51121.82c + 661 511220 Sb-122 1.42450E-05 4.71390E-05 511220 + 662 511221 Sb-122m 3.28940E-05 3.28940E-05 511221 + 663 511230 Sb-123 2.41520E-04 1.28420E-02 51123.82c + 664 511240 Sb-124 1.36400E-04 4.94280E-04 51124.82c + 665 511241 Sb-124m 1.26700E-04 4.77170E-04 511241 + 666 511242 Sb-124m 3.50470E-04 3.50470E-04 511242 + 667 511250 Sb-125 2.01420E-03 1.51240E-02 51125.82c + 668 511260 Sb-126 2.03760E-03 2.25170E-03 51126.82c + 669 511261 Sb-126m 7.36630E-04 1.52960E-03 511261 + 670 511262 Sb-126m 7.92990E-04 7.92990E-04 511262 + 671 511270 Sb-127 8.36220E-03 2.04760E-02 511270 + 672 511280 Sb-128 6.32260E-03 1.78260E-02 511280 + 673 511281 Sb-128m 4.74640E-03 4.74640E-03 511281 + 674 511290 Sb-129 7.71570E-03 1.31070E-02 511290 + 675 511291 Sb-129m 1.04770E-02 1.27520E-02 511291 + 676 511300 Sb-130 7.27900E-03 9.07390E-03 511300 + 677 511301 Sb-130m 7.27900E-03 8.51400E-03 511301 + 678 511310 Sb-131 1.47620E-02 1.55960E-02 511310 + 679 511320 Sb-132 1.70590E-03 1.82550E-03 511320 + 680 511321 Sb-132m 2.71240E-03 2.71240E-03 511321 + 681 511330 Sb-133 1.68950E-03 1.69470E-03 511330 + 682 511340 Sb-134 3.25110E-05 3.38250E-05 511340 + 683 511341 Sb-134m 1.46810E-04 1.46810E-04 511341 + 684 511350 Sb-135 2.18620E-05 2.18620E-05 511350 + 685 511360 Sb-136 1.61790E-06 1.61790E-06 511360 + 686 511370 Sb-137 1.52920E-09 1.52920E-09 511370 + 687 521220 Te-122 1.17830E-06 4.70920E-05 52122.82c + 688 521230 Te-123 6.59560E-07 4.73480E-06 52123.82c + 689 521231 Te-123m 4.07520E-06 4.07520E-06 521231 + 690 521240 Te-124 2.42680E-05 6.37840E-04 52124.82c + 691 521250 Te-125 1.39970E-05 1.52250E-02 52125.82c + 692 521251 Te-125m 8.64830E-05 3.47080E-03 521251 + 693 521260 Te-126 4.23730E-04 3.99290E-03 52126.82c + 694 521270 Te-127 1.84960E-04 2.14080E-02 521270 + 695 521271 Te-127m 8.48930E-04 4.22330E-03 52527.82c + 696 521280 Te-128 3.70590E-03 2.61140E-02 52128.82c + 697 521290 Te-129 1.42520E-03 2.47710E-02 521290 + 698 521291 Te-129m 6.54140E-03 1.93010E-02 52529.82c + 699 521300 Te-130 1.85290E-02 3.61170E-02 52130.82c + 700 521310 Te-131 4.84000E-03 2.41150E-02 521310 + 701 521311 Te-131m 2.22140E-02 2.34630E-02 521311 + 702 521320 Te-132 2.61410E-02 3.06790E-02 52132.82c + 703 521330 Te-133 3.31210E-03 7.42550E-03 521330 + 704 521331 Te-133m 1.52020E-02 1.54950E-02 521331 + 705 521340 Te-134 1.11840E-02 1.13680E-02 521340 + 706 521350 Te-135 2.22190E-03 2.24060E-03 521350 + 707 521360 Te-136 5.88200E-04 5.89550E-04 521360 + 708 521370 Te-137 7.91280E-05 7.91290E-05 521370 + 709 521380 Te-138 1.53440E-05 1.53440E-05 521380 + 710 521390 Te-139 1.98870E-08 1.98870E-08 521390 + 711 531260 I-126 3.43880E-06 3.43880E-06 531260 + 712 531270 I-127 2.19700E-05 2.15320E-02 53127.82c + 713 531280 I-128 8.91670E-05 8.91670E-05 531280 + 714 531290 I-129 4.74230E-04 3.23870E-02 53129.82c + 715 531300 I-130 1.06260E-03 1.26030E-03 53130.82c + 716 531301 I-130m 2.35310E-04 2.35310E-04 531301 + 717 531310 I-131 5.45100E-03 4.81010E-02 53131.82c + 718 531320 I-132 3.24760E-03 3.83670E-02 531320 + 719 531321 I-132m 5.16380E-03 5.16380E-03 531321 + 720 531330 I-133 9.18560E-03 4.18680E-02 531330 + 721 531331 I-133m 1.24730E-02 1.24730E-02 531331 + 722 531340 I-134 9.39960E-03 3.53690E-02 531340 + 723 531341 I-134m 1.49450E-02 1.49450E-02 531341 + 724 531350 I-135 2.55400E-02 2.77810E-02 53135.82c + 725 531360 I-136 1.72370E-03 2.31450E-03 531360 + 726 531361 I-136m 7.78390E-03 7.78510E-03 531361 + 727 531370 I-137 4.18600E-03 4.26370E-03 531370 + 728 531380 I-138 8.82280E-04 8.96660E-04 531380 + 729 531390 I-139 3.77130E-04 3.77150E-04 531390 + 730 531400 I-140 3.45960E-05 3.45960E-05 531400 + 731 531410 I-141 2.41260E-06 2.41260E-06 531410 + 732 531420 I-142 1.96310E-09 1.96310E-09 531420 + 733 541280 Xe-128 2.17270E-06 8.51870E-05 54128.82c + 734 541290 Xe-129 1.62840E-06 1.16900E-05 54129.82c + 735 541291 Xe-129m 1.00620E-05 1.00620E-05 541291 + 736 541300 Xe-130 5.25120E-05 1.35040E-03 54130.82c + 737 541310 Xe-131 4.14300E-05 4.83330E-02 54131.82c + 738 541311 Xe-131m 1.90150E-04 7.12620E-04 541311 + 739 541320 Xe-132 2.63540E-04 3.99660E-02 54132.82c + 740 541321 Xe-132m 6.08530E-04 6.08530E-04 541321 + 741 541330 Xe-133 5.78450E-04 4.51010E-02 54133.82c + 742 541331 Xe-133m 2.65490E-03 3.84670E-03 541331 + 743 541340 Xe-134 2.06660E-03 4.71120E-02 54134.82c + 744 541341 Xe-134m 9.33240E-03 9.67610E-03 541341 + 745 541350 Xe-135 3.96410E-03 4.98020E-02 54135.82c + 746 541351 Xe-135m 1.81940E-02 2.27800E-02 541351 + 747 541360 Xe-136 4.05590E-02 5.09360E-02 54136.82c + 748 541370 Xe-137 2.79490E-02 3.19830E-02 541370 + 749 541380 Xe-138 2.32560E-02 2.41420E-02 541380 + 750 541390 Xe-139 9.62940E-03 9.97280E-03 541390 + 751 541400 Xe-140 3.70820E-03 3.74010E-03 541400 + 752 541410 Xe-141 7.77870E-04 7.79780E-04 541410 + 753 541420 Xe-142 1.52350E-04 1.52350E-04 541420 + 754 541430 Xe-143 8.34890E-06 8.34890E-06 541430 + 755 541440 Xe-144 9.73310E-07 9.73310E-07 541440 + 756 551310 Cs-131 7.50750E-09 7.50750E-09 551310 + 757 551320 Cs-132 3.98820E-06 3.98820E-06 551320 + 758 551330 Cs-133 4.76130E-05 4.51500E-02 55133.82c + 759 551340 Cs-134 9.09770E-05 2.35630E-04 55134.82c + 760 551341 Cs-134m 1.44650E-04 1.44650E-04 551341 + 761 551350 Cs-135 6.78010E-04 5.15370E-02 55135.82c + 762 551351 Cs-135m 9.20690E-04 9.20690E-04 551351 + 763 551360 Cs-136 2.14550E-03 3.57450E-03 55136.82c + 764 551361 Cs-136m 2.85800E-03 2.85800E-03 551361 + 765 551370 Cs-137 1.60150E-02 4.79980E-02 55137.82c + 766 551380 Cs-138 5.74210E-03 4.31770E-02 551380 + 767 551381 Cs-138m 1.64110E-02 1.64110E-02 551381 + 768 551390 Cs-139 2.88850E-02 3.88580E-02 551390 + 769 551400 Cs-140 1.52230E-02 1.89630E-02 551400 + 770 551410 Cs-141 1.29960E-02 1.37760E-02 551410 + 771 551420 Cs-142 4.15390E-03 4.30580E-03 551420 + 772 551430 Cs-143 1.36090E-03 1.36920E-03 551430 + 773 551440 Cs-144 1.12390E-04 1.69540E-04 551440 + 774 551441 Cs-144m 1.12390E-04 1.12390E-04 551441 + 775 551450 Cs-145 3.19180E-05 3.19180E-05 551450 + 776 551460 Cs-146 8.94360E-07 8.94360E-07 551460 + 777 551470 Cs-147 7.45580E-10 7.45580E-10 551470 + 778 561330 Ba-133 1.14370E-07 8.20960E-07 561330 + 779 561331 Ba-133m 7.06660E-07 7.06660E-07 561331 + 780 561340 Ba-134 6.33170E-06 2.41960E-04 56134.82c + 781 561350 Ba-135 5.72770E-06 3.20160E-05 56135.82c + 782 561351 Ba-135m 2.62880E-05 2.62880E-05 561351 + 783 561360 Ba-136 5.19820E-05 5.29020E-03 56136.82c + 784 561361 Ba-136m 2.34740E-04 2.34740E-04 561361 + 785 561370 Ba-137 2.88660E-04 4.96120E-02 56137.82c + 786 561371 Ba-137m 1.32480E-03 4.66350E-02 561371 + 787 561380 Ba-138 8.87310E-03 5.51680E-02 56138.82c + 788 561390 Ba-139 1.72310E-02 5.60890E-02 561390 + 789 561400 Ba-140 2.49040E-02 4.38670E-02 56140.82c + 790 561410 Ba-141 2.43040E-02 3.80800E-02 561410 + 791 561420 Ba-142 2.69880E-02 3.13160E-02 561420 + 792 561430 Ba-143 1.38770E-02 1.52290E-02 561430 + 793 561440 Ba-144 7.31270E-03 7.53760E-03 561440 + 794 561450 Ba-145 1.78250E-03 1.81000E-03 561450 + 795 561460 Ba-146 4.80000E-04 4.80770E-04 561460 + 796 561470 Ba-147 7.18180E-05 7.18190E-05 561470 + 797 561480 Ba-148 1.34710E-05 1.34710E-05 561480 + 798 561490 Ba-149 9.79990E-07 9.79990E-07 561490 + 799 571360 La-136 2.68980E-09 5.37960E-09 571360 + 800 571361 La-136m 2.68980E-09 2.68980E-09 571361 + 801 571370 La-137 8.79520E-06 8.79520E-06 571370 + 802 571380 La-138 1.04130E-04 1.04130E-04 57138.82c + 803 571390 La-139 8.65380E-04 5.69670E-02 57139.82c + 804 571400 La-140 1.74460E-03 4.56120E-02 57140.82c + 805 571410 La-141 5.65730E-03 4.37370E-02 571410 + 806 571420 La-142 7.26260E-03 3.85790E-02 571420 + 807 571430 La-143 1.34440E-02 2.86730E-02 571430 + 808 571440 La-144 1.22070E-02 1.97450E-02 571440 + 809 571450 La-145 1.01400E-02 1.19500E-02 571450 + 810 571460 La-146 9.27790E-04 1.40860E-03 571460 + 811 571461 La-146m 3.24580E-03 3.24580E-03 571461 + 812 571470 La-147 2.04870E-03 2.12060E-03 571470 + 813 571480 La-148 5.11990E-04 5.25410E-04 571480 + 814 571490 La-149 1.05290E-04 1.06270E-04 571490 + 815 571500 La-150 1.83320E-05 1.83320E-05 571500 + 816 571510 La-151 1.99130E-08 1.99130E-08 571510 + 817 571520 La-152 1.94910E-10 1.94910E-10 571520 + 818 581380 Ce-138 3.97410E-07 2.19200E-06 581380 + 819 581381 Ce-138m 1.79460E-06 1.79460E-06 581381 + 820 581390 Ce-139 2.37060E-06 1.32510E-05 581390 + 821 581391 Ce-139m 1.08800E-05 1.08800E-05 581391 + 822 581400 Ce-140 9.03630E-05 4.57020E-02 58140.82c + 823 581410 Ce-141 3.33920E-04 4.40710E-02 58141.82c + 824 581420 Ce-142 1.35950E-03 3.99380E-02 58142.82c + 825 581430 Ce-143 2.48900E-03 3.11620E-02 58143.82c + 826 581440 Ce-144 6.29760E-03 2.60420E-02 58144.82c + 827 581450 Ce-145 8.39900E-03 2.03490E-02 581450 + 828 581460 Ce-146 1.06840E-02 1.53380E-02 581460 + 829 581470 Ce-147 7.66560E-03 9.78620E-03 581470 + 830 581480 Ce-148 5.97500E-03 6.50190E-03 581480 + 831 581490 Ce-149 2.38000E-03 2.48530E-03 581490 + 832 581500 Ce-150 9.22900E-04 9.40740E-04 581500 + 833 581510 Ce-151 1.68300E-04 1.68320E-04 581510 + 834 581520 Ce-152 3.18600E-05 3.18600E-05 581520 + 835 581530 Ce-153 2.36780E-06 2.36780E-06 581530 + 836 581540 Ce-154 8.61190E-10 8.61190E-10 581540 + 837 591410 Pr-141 1.20620E-06 4.40720E-02 59141.82c + 838 591420 Pr-142 1.00710E-06 5.55470E-06 59142.82c + 839 591421 Pr-142m 4.54760E-06 4.54760E-06 591421 + 840 591430 Pr-143 3.96050E-05 3.12020E-02 59143.82c + 841 591440 Pr-144 7.61490E-06 2.61730E-02 591440 + 842 591441 Pr-144m 1.23230E-04 4.82590E-04 591441 + 843 591450 Pr-145 4.88070E-04 2.08370E-02 591450 + 844 591460 Pr-146 1.09510E-03 1.64340E-02 591460 + 845 591470 Pr-147 2.27930E-03 1.20650E-02 591470 + 846 591480 Pr-148 3.38080E-04 6.84000E-03 591480 + 847 591481 Pr-148m 2.65110E-03 2.65110E-03 591481 + 848 591490 Pr-149 3.93870E-03 6.42400E-03 591490 + 849 591500 Pr-150 2.82840E-03 3.76910E-03 591500 + 850 591510 Pr-151 1.67550E-03 1.84380E-03 591510 + 851 591520 Pr-152 4.41670E-04 4.73550E-04 591520 + 852 591530 Pr-153 1.19120E-04 1.21470E-04 591530 + 853 591540 Pr-154 2.01250E-05 2.01260E-05 591540 + 854 591550 Pr-155 1.59820E-06 1.59820E-06 591550 + 855 591560 Pr-156 1.97650E-09 1.97650E-09 591560 + 856 591570 Pr-157 3.43570E-11 3.43570E-11 591570 + 857 601440 Nd-144 9.73220E-07 2.61740E-02 60144.82c + 858 601450 Nd-145 1.31280E-05 2.08500E-02 60145.82c + 859 601460 Nd-146 6.58110E-05 1.64990E-02 60146.82c + 860 601470 Nd-147 2.38840E-04 1.23040E-02 60147.82c + 861 601480 Nd-148 6.58440E-04 1.01500E-02 60148.82c + 862 601490 Nd-149 1.31390E-03 7.73790E-03 601490 + 863 601500 Nd-150 2.30000E-03 6.06910E-03 60150.82c + 864 601510 Nd-151 2.11880E-03 3.96260E-03 601510 + 865 601520 Nd-152 1.70600E-03 2.17950E-03 601520 + 866 601530 Nd-153 7.31510E-04 8.52980E-04 601530 + 867 601540 Nd-154 3.25980E-04 3.46110E-04 601540 + 868 601550 Nd-155 8.31640E-05 8.47620E-05 601550 + 869 601560 Nd-156 2.42180E-05 2.42200E-05 601560 + 870 601570 Nd-157 1.72980E-07 1.73010E-07 601570 + 871 601580 Nd-158 6.30510E-09 6.30510E-09 601580 + 872 601590 Nd-159 1.00410E-10 1.00410E-10 601590 + 873 601600 Nd-160 2.84890E-12 2.84890E-12 601600 + 874 611460 Pm-146 7.96490E-10 7.96490E-10 611460 + 875 611470 Pm-147 1.70860E-06 1.23060E-02 61147.82c + 876 611480 Pm-148 3.25490E-07 3.98980E-07 61148.82c + 877 611481 Pm-148m 1.46980E-06 1.46980E-06 61548.82c + 878 611490 Pm-149 3.51950E-05 7.77310E-03 61149.82c + 879 611500 Pm-150 1.09320E-04 1.09320E-04 611500 + 880 611510 Pm-151 3.18550E-04 4.28120E-03 61151.82c + 881 611520 Pm-152 4.67860E-05 2.22630E-03 611520 + 882 611521 Pm-152m 1.12930E-04 1.12930E-04 611521 + 883 611522 Pm-152m 2.53950E-04 2.53950E-04 611522 + 884 611530 Pm-153 4.59010E-04 1.31200E-03 611530 + 885 611540 Pm-154 1.96520E-04 5.42630E-04 611540 + 886 611541 Pm-154m 1.96520E-04 1.96520E-04 611541 + 887 611550 Pm-155 2.96590E-04 3.81350E-04 611550 + 888 611560 Pm-156 1.52280E-04 1.76500E-04 611560 + 889 611570 Pm-157 6.02850E-05 6.04580E-05 611570 + 890 611580 Pm-158 1.27940E-05 1.28000E-05 611580 + 891 611590 Pm-159 2.75740E-07 2.75840E-07 611590 + 892 611600 Pm-160 1.11210E-08 1.11240E-08 611600 + 893 611610 Pm-161 3.31610E-10 3.31610E-10 611610 + 894 611620 Pm-162 3.65420E-12 3.65420E-12 611620 + 895 621490 Sm-149 9.79880E-07 7.77410E-03 62149.82c + 896 621500 Sm-150 5.38450E-06 1.14700E-04 62150.82c + 897 621510 Sm-151 1.04380E-05 4.29160E-03 62151.82c + 898 621520 Sm-152 4.38710E-05 2.63770E-03 62152.82c + 899 621530 Sm-153 1.59300E-05 1.40100E-03 62153.82c + 900 621531 Sm-153m 7.31160E-05 7.31160E-05 621531 + 901 621540 Sm-154 1.68990E-04 9.08140E-04 62154.82c + 902 621550 Sm-155 1.96330E-04 5.77680E-04 621550 + 903 621560 Sm-156 2.33310E-04 4.09810E-04 621560 + 904 621570 Sm-157 1.63550E-04 2.24010E-04 621570 + 905 621580 Sm-158 8.44480E-05 9.72480E-05 621580 + 906 621590 Sm-159 4.02730E-05 4.05490E-05 621590 + 907 621600 Sm-160 1.62770E-05 1.62880E-05 621600 + 908 621610 Sm-161 3.68740E-07 3.69070E-07 621610 + 909 621620 Sm-162 2.79930E-08 2.79970E-08 621620 + 910 621630 Sm-163 7.05070E-10 7.05070E-10 621630 + 911 621640 Sm-164 3.11230E-11 3.11230E-11 621640 + 912 631510 Eu-151 2.69100E-10 4.29160E-03 63151.82c + 913 631520 Eu-152 2.66050E-07 8.80010E-07 63152.82c + 914 631521 Eu-152m 5.43870E-08 5.43870E-08 631521 + 915 631522 Eu-152m 6.13960E-07 6.13960E-07 631522 + 916 631530 Eu-153 1.20730E-07 1.40120E-03 63153.82c + 917 631540 Eu-154 7.95420E-07 2.31900E-06 63154.82c + 918 631541 Eu-154m 1.52360E-06 1.52360E-06 631541 + 919 631550 Eu-155 1.35810E-05 5.91260E-04 63155.82c + 920 631560 Eu-156 2.50700E-05 4.34880E-04 63156.82c + 921 631570 Eu-157 4.99090E-05 2.73920E-04 63157.82c + 922 631580 Eu-158 4.77460E-05 1.44990E-04 631580 + 923 631590 Eu-159 5.39870E-05 9.45360E-05 631590 + 924 631600 Eu-160 3.76370E-05 5.39250E-05 631600 + 925 631610 Eu-161 1.59190E-05 1.62880E-05 631610 + 926 631620 Eu-162 9.57810E-06 9.60610E-06 631620 + 927 631630 Eu-163 1.19440E-06 1.19510E-06 631630 + 928 631640 Eu-164 4.83630E-08 4.83940E-08 631640 + 929 631650 Eu-165 2.29450E-09 2.29450E-09 631650 + 930 631660 Eu-166 1.57750E-11 1.57750E-11 631660 + 931 641540 Gd-154 4.30590E-10 2.31900E-06 64154.82c + 932 641550 Gd-155 1.50990E-09 5.91270E-04 64155.82c + 933 641551 Gd-155m 6.93010E-09 6.93010E-09 641551 + 934 641560 Gd-156 2.59390E-06 4.37470E-04 64156.82c + 935 641570 Gd-157 3.44330E-06 2.77360E-04 64157.82c + 936 641580 Gd-158 9.37990E-06 1.54380E-04 64158.82c + 937 641590 Gd-159 1.18950E-05 1.06430E-04 641590 + 938 641600 Gd-160 2.33910E-05 7.73160E-05 64160.82c + 939 641610 Gd-161 2.57130E-05 4.20010E-05 641610 + 940 641620 Gd-162 1.55630E-05 2.51690E-05 641620 + 941 641630 Gd-163 1.31380E-05 1.43330E-05 641630 + 942 641640 Gd-164 5.99230E-06 6.04070E-06 641640 + 943 641650 Gd-165 1.17860E-06 1.18090E-06 641650 + 944 641660 Gd-166 2.58730E-08 2.58890E-08 641660 + 945 641670 Gd-167 2.83680E-09 2.83680E-09 641670 + 946 641680 Gd-168 1.69170E-10 1.69170E-10 641680 + 947 641690 Gd-169 1.04820E-12 1.04820E-12 641690 + 948 651560 Tb-156 2.60690E-12 1.06830E-11 651560 + 949 651561 Tb-156m 7.45530E-12 7.45530E-12 651561 + 950 651570 Tb-157 6.52770E-10 6.52770E-10 651570 + 951 651580 Tb-158 8.12200E-09 8.62080E-09 651580 + 952 651581 Tb-158m 5.01910E-10 5.01910E-10 651581 + 953 651590 Tb-159 1.28760E-07 1.06560E-04 65159.82c + 954 651600 Tb-160 1.01720E-06 1.01720E-06 65160.82c + 955 651610 Tb-161 4.89780E-06 4.68990E-05 651610 + 956 651620 Tb-162 3.59150E-06 2.87610E-05 651620 + 957 651630 Tb-163 2.38870E-06 1.67220E-05 651630 + 958 651640 Tb-164 1.19840E-05 1.80250E-05 651640 + 959 651650 Tb-165 7.07130E-06 8.25220E-06 651650 + 960 651660 Tb-166 1.12940E-06 1.15530E-06 651660 + 961 651670 Tb-167 4.07870E-07 4.10710E-07 651670 + 962 651680 Tb-168 5.93760E-08 5.95450E-08 651680 + 963 651690 Tb-169 2.40520E-09 2.40630E-09 651690 + 964 651700 Tb-170 8.56320E-11 8.56320E-11 651700 + 965 651710 Tb-171 1.44370E-12 1.44370E-12 651710 + 966 661590 Dy-159 3.04280E-11 3.04280E-11 661590 + 967 661600 Dy-160 1.14810E-09 1.01830E-06 66160.82c + 968 661610 Dy-161 1.23860E-08 4.69110E-05 66161.82c + 969 661620 Dy-162 1.19720E-06 2.99580E-05 66162.82c + 970 661630 Dy-163 1.19440E-06 1.79160E-05 66163.82c + 971 661640 Dy-164 2.39670E-06 2.04290E-05 66164.82c + 972 661650 Dy-165 2.17580E-06 1.06050E-05 661650 + 973 661651 Dy-165m 1.81260E-07 1.81260E-07 661651 + 974 661660 Dy-166 1.12940E-06 2.28470E-06 661660 + 975 661670 Dy-167 3.26580E-06 3.67650E-06 661670 + 976 661680 Dy-168 1.66500E-06 1.72460E-06 661680 + 977 661690 Dy-169 1.46060E-07 1.48470E-07 661690 + 978 661700 Dy-170 3.20450E-08 3.21310E-08 661700 + 979 661710 Dy-171 1.34640E-09 1.34780E-09 661710 + 980 661720 Dy-172 1.21820E-10 1.21820E-10 661720 + 981 661730 Dy-173 4.71760E-12 4.71760E-12 661730 + 982 671610 Ho-161 1.33090E-12 1.44180E-12 671610 + 983 671620 Ho-162 7.94980E-12 3.02070E-11 671620 + 984 671621 Ho-162m 3.58990E-11 3.58990E-11 671621 + 985 671630 Ho-163 9.63900E-10 1.04420E-09 671630 + 986 671631 Ho-163m 8.02990E-11 8.02990E-11 671631 + 987 671640 Ho-164 3.00610E-09 1.65810E-08 671640 + 988 671641 Ho-164m 1.35750E-08 1.35750E-08 671641 + 989 671650 Ho-165 1.11570E-07 1.07210E-05 67165.82c + 990 671660 Ho-166 2.02040E-08 2.30490E-06 671660 + 991 671661 Ho-166m 9.12360E-08 9.12360E-08 671661 + 992 671670 Ho-167 7.27920E-07 4.40440E-06 671670 + 993 671680 Ho-168 2.87710E-07 2.83040E-06 671680 + 994 671681 Ho-168m 8.22290E-07 8.22290E-07 671681 + 995 671690 Ho-169 4.59990E-07 6.08460E-07 671690 + 996 671700 Ho-170 1.68640E-07 1.68640E-07 671700 + 997 671701 Ho-170m 3.73460E-08 6.94770E-08 671701 + 998 671710 Ho-171 1.31240E-07 1.32590E-07 671710 + 999 671720 Ho-172 1.00030E-08 1.01250E-08 671720 + 1000 671730 Ho-173 2.44510E-09 2.44980E-09 671730 + 1001 671740 Ho-174 1.38300E-10 1.38300E-10 671740 + 1002 671750 Ho-175 5.82180E-12 5.82180E-12 671750 + 1003 681640 Er-164 5.92830E-12 8.57830E-09 68164.82c + 1004 681650 Er-165 9.88110E-11 9.88110E-11 681650 + 1005 681660 Er-166 6.37730E-10 2.30550E-06 68166.82c + 1006 681670 Er-167 9.15170E-09 4.41440E-06 68167.82c + 1007 681671 Er-167m 7.62390E-10 5.27060E-07 681671 + 1008 681680 Er-168 8.44300E-08 2.91910E-06 68168.82c + 1009 681690 Er-169 2.29990E-07 8.38450E-07 681690 + 1010 681700 Er-170 1.68150E-07 4.06270E-07 68170.82c + 1011 681710 Er-171 7.35140E-08 2.06100E-07 681710 + 1012 681720 Er-172 7.63110E-08 8.64360E-08 681720 + 1013 681730 Er-173 3.83090E-08 4.07590E-08 681730 + 1014 681740 Er-174 1.24620E-08 1.26000E-08 681740 + 1015 681750 Er-175 1.24240E-09 1.24820E-09 681750 + 1016 681760 Er-176 1.85390E-10 1.85390E-10 681760 + 1017 681770 Er-177 1.11750E-11 1.11750E-11 681770 + 1018 691670 Tm-167 4.85710E-12 4.85710E-12 691670 + 1019 691680 Tm-168 1.04550E-10 1.04550E-10 691680 + 1020 691690 Tm-169 6.05370E-10 8.39050E-07 691690 + 1021 691700 Tm-170 3.05510E-09 3.05510E-09 691700 + 1022 691710 Tm-171 7.46420E-09 2.13570E-07 691710 + 1023 691720 Tm-172 9.39700E-08 1.80410E-07 691720 + 1024 691730 Tm-173 3.81110E-08 7.88700E-08 691730 + 1025 691740 Tm-174 2.33630E-08 3.59630E-08 691740 + 1026 691750 Tm-175 1.19350E-08 1.31830E-08 691750 + 1027 691760 Tm-176 3.79350E-09 3.97890E-09 691760 + 1028 691770 Tm-177 1.35900E-09 1.37020E-09 691770 + 1029 691780 Tm-178 1.65380E-10 1.65380E-10 691780 + 1030 691790 Tm-179 2.04420E-11 2.04420E-11 691790 + 1031 701700 Yb-170 3.99560E-12 3.05510E-09 701700 + 1032 701710 Yb-171 1.87240E-12 2.13590E-07 701710 + 1033 701711 Yb-171m 2.24770E-11 2.24770E-11 701711 + 1034 701720 Yb-172 3.12540E-10 1.80720E-07 701720 + 1035 701730 Yb-173 1.72640E-09 8.05990E-08 701730 + 1036 701740 Yb-174 5.70170E-09 4.16910E-08 701740 + 1037 701750 Yb-175 5.21070E-09 1.88280E-08 701750 + 1038 701751 Yb-175m 4.34090E-10 1.05850E-08 701751 + 1039 701760 Yb-176 1.93950E-09 1.18260E-08 701760 + 1040 701761 Yb-176m 6.78520E-09 8.77460E-09 701761 + 1041 701770 Yb-177 5.32190E-09 7.36060E-09 701770 + 1042 701771 Yb-177m 6.68530E-10 2.03870E-09 701771 + 1043 701780 Yb-178 3.86370E-09 4.02910E-09 701780 + 1044 701790 Yb-179 1.05430E-09 1.07470E-09 701790 + 1045 701800 Yb-180 2.94880E-10 2.94880E-10 701800 + 1046 701810 Yb-181 2.86310E-11 2.86310E-11 701810 + 1047 711730 Lu-173 3.15590E-12 3.15590E-12 711730 + 1048 711740 Lu-174 4.63280E-12 2.54320E-11 711740 + 1049 711741 Lu-174m 2.09200E-11 2.09200E-11 711741 + 1050 711750 Lu-175 1.52430E-10 1.89800E-08 71175.82c + 1051 711760 Lu-176 3.96770E-10 1.27420E-09 71176.82c + 1052 711761 Lu-176m 1.13410E-10 1.13410E-10 711761 + 1053 711770 Lu-177 9.25660E-10 8.47460E-09 711770 + 1054 711771 Lu-177m 7.71170E-10 8.33660E-10 711771 + 1055 711772 Lu-177m 1.24980E-10 1.24980E-10 711772 + 1056 711780 Lu-178 6.73390E-10 4.70250E-09 711780 + 1057 711781 Lu-178m 1.55490E-09 1.55490E-09 711781 + 1058 711790 Lu-179 2.73870E-09 4.04160E-09 711790 + 1059 711791 Lu-179m 2.28150E-10 1.30290E-09 711791 + 1060 711800 Lu-180 3.15230E-10 1.12160E-09 711800 + 1061 711801 Lu-180m 3.15230E-10 6.10110E-10 711801 + 1062 711802 Lu-180m 1.00270E-09 1.00270E-09 711802 + 1063 711810 Lu-181 8.71620E-10 9.00250E-10 711810 + 1064 711820 Lu-182 1.71180E-10 1.71180E-10 711820 + 1065 711830 Lu-183 3.95300E-11 3.95300E-11 711830 + 1066 711840 Lu-184 3.19390E-12 3.19390E-12 711840 + 1067 721760 Hf-176 2.46060E-12 1.15770E-10 72176.82c + 1068 721770 Hf-177 1.06940E-11 9.20340E-09 72177.82c + 1069 721771 Hf-177m 8.71140E-12 7.18090E-10 721771 + 1070 721772 Hf-177m 1.64380E-12 6.41320E-11 721772 + 1071 721780 Hf-178 3.34230E-11 6.40770E-09 72178.82c + 1072 721781 Hf-178m 8.86160E-11 1.67180E-09 721781 + 1073 721782 Hf-178m 2.83110E-11 2.83110E-11 721782 + 1074 721790 Hf-179 1.99120E-10 4.46240E-09 72179.82c + 1075 721791 Hf-179m 4.66440E-11 4.66440E-11 721791 + 1076 721792 Hf-179m 1.72200E-10 1.72200E-10 721792 + 1077 721800 Hf-180 2.57930E-10 3.08840E-09 72180.82c + 1078 721801 Hf-180m 9.02370E-10 1.40370E-09 721801 + 1079 721810 Hf-181 1.16180E-09 2.06200E-09 721810 + 1080 721820 Hf-182 2.51380E-10 7.91920E-10 721820 + 1081 721821 Hf-182m 8.79420E-10 8.79420E-10 721821 + 1082 721830 Hf-183 5.31200E-10 5.70730E-10 721830 + 1083 721840 Hf-184 5.43660E-11 5.59630E-11 721840 + 1084 721841 Hf-184m 1.90190E-10 1.91790E-10 721841 + 1085 721850 Hf-185 3.98220E-11 3.98220E-11 721850 + 1086 721860 Hf-186 6.41300E-12 6.41300E-12 721860 + 1087 731790 Ta-179 1.52670E-12 2.77230E-12 731790 + 1088 731791 Ta-179m 1.05540E-12 1.24560E-12 731791 + 1089 731800 Ta-180 5.42570E-12 5.42570E-12 731800 + 1090 731801 Ta-180m 1.25280E-11 1.68800E-11 731801 + 1091 731810 Ta-181 1.01430E-10 2.16350E-09 73181.82c + 1092 731820 Ta-182 4.42110E-11 7.08940E-10 73182.82c + 1093 731821 Ta-182m 5.78540E-11 6.64730E-10 731821 + 1094 731822 Ta-182m 9.68150E-11 6.06880E-10 731822 + 1095 731830 Ta-183 4.60500E-10 1.03120E-09 731830 + 1096 731840 Ta-184 3.98500E-10 6.46250E-10 731840 + 1097 731850 Ta-185 1.54170E-10 3.69660E-10 731850 + 1098 731851 Ta-185m 1.75670E-10 1.75670E-10 731851 + 1099 731860 Ta-186 1.12040E-10 1.18450E-10 731860 + 1100 731870 Ta-187 4.22000E-11 4.22000E-11 731870 + 1101 731880 Ta-188 5.41690E-12 5.41690E-12 731880 + 1102 741820 W-182 3.40660E-12 7.12350E-10 74182.82c + 1103 741830 W-183 2.48570E-12 1.04910E-09 74183.82c + 1104 741831 W-183m 1.53580E-11 5.04200E-11 741831 + 1105 741840 W-184 8.40020E-11 7.30260E-10 74184.82c + 1106 741850 W-185 2.42800E-11 5.05380E-10 741850 + 1107 741851 W-185m 1.11440E-10 1.11440E-10 741851 + 1108 741860 W-186 1.23920E-10 3.43120E-10 74186.82c + 1109 741861 W-186m 1.00540E-10 1.00540E-10 741861 + 1110 741870 W-187 1.61140E-10 2.03340E-10 741870 + 1111 741880 W-188 1.08600E-10 1.14020E-10 741880 + 1112 741890 W-189 3.17360E-11 3.17360E-11 741890 + 1113 741900 W-190 2.86890E-12 9.49340E-12 741900 + 1114 741901 W-190m 6.62450E-12 6.62450E-12 741901 + 1115 751850 Re-185 3.11970E-12 5.08500E-10 75185.82c + 1116 751860 Re-186 2.92350E-12 2.92350E-12 751860 + 1117 751861 Re-186m 8.35550E-12 8.35550E-12 751861 + 1118 751870 Re-187 4.24990E-11 2.45840E-10 75187.82c + 1119 751880 Re-188 9.89440E-12 1.68590E-10 751880 + 1120 751881 Re-188m 4.46810E-11 4.46810E-11 751881 + 1121 751890 Re-189 7.76530E-11 1.09390E-10 751890 + 1122 751900 Re-190 1.00840E-11 3.56640E-11 751900 + 1123 751901 Re-190m 3.52780E-11 3.52780E-11 751901 + 1124 751910 Re-191 2.53580E-11 2.53580E-11 751910 + 1125 751920 Re-192 5.29490E-12 5.29490E-12 751920 + 1126 751930 Re-193 1.30510E-12 1.30510E-12 751930 + 1127 761880 Os-188 3.14790E-12 1.71740E-10 761880 + 1128 761890 Os-189 1.31540E-12 1.18830E-10 761890 + 1129 761891 Os-189m 8.12770E-12 1.93760E-11 761891 + 1130 761900 Os-190 8.47070E-12 8.28850E-11 761900 + 1131 761901 Os-190m 1.95590E-11 3.87510E-11 761901 + 1132 761910 Os-191 2.53470E-11 5.48070E-11 761910 + 1133 761911 Os-191m 4.10220E-12 4.10220E-12 761911 + 1134 761920 Os-192 9.16030E-12 3.32110E-11 761920 + 1135 761921 Os-192m 2.11520E-11 2.11520E-11 761921 + 1136 761930 Os-193 1.50600E-11 1.63650E-11 761930 + 1137 761940 Os-194 7.27650E-12 7.27650E-12 761940 + 1138 761950 Os-195 1.26670E-12 1.26670E-12 761950 + 1139 771910 Ir-191 3.94970E-13 5.70150E-11 77191.82c + 1140 771911 Ir-191m 1.06570E-12 2.76820E-11 771911 + 1141 771920 Ir-192 1.54030E-12 7.37030E-12 771920 + 1142 771921 Ir-192m 1.54030E-12 1.54030E-12 771921 + 1143 771922 Ir-192m 1.54030E-12 4.29000E-12 771922 + 1144 771930 Ir-193 2.03500E-12 2.77400E-11 77193.82c + 1145 771931 Ir-193m 9.34000E-12 9.39690E-12 771931 + 1146 771940 Ir-194 3.43700E-12 1.41510E-11 771940 + 1147 771941 Ir-194m 3.43700E-12 3.43700E-12 771941 + 1148 771942 Ir-194m 3.43700E-12 3.43700E-12 771942 + 1149 771950 Ir-195 1.62020E-12 3.25870E-12 771950 + 1150 771951 Ir-195m 7.43620E-12 7.43620E-12 771951 + 1151 771960 Ir-196 1.64370E-12 1.64860E-12 771960 + 1152 771961 Ir-196m 1.64370E-12 1.64370E-12 771961 + 1153 771971 Ir-197m 1.06760E-12 1.06760E-12 771971 + 1154 781940 Pt-194 1.87540E-12 1.94630E-11 781940 + 1155 781950 Pt-195 5.79670E-13 1.35630E-11 781950 + 1156 781951 Pt-195m 2.66050E-12 4.92110E-12 781951 + 1157 781960 Pt-196 5.73850E-12 9.02590E-12 781960 + 1158 781970 Pt-197 7.70130E-13 5.45320E-12 781970 + 1159 781971 Pt-197m 3.53470E-12 4.59960E-12 781971 + 1160 781980 Pt-198 3.03350E-12 3.03350E-12 781980 + 1161 791980 Au-198 6.24640E-13 1.32790E-12 791980 + 1162 791990 Au-199 2.01920E-12 2.01920E-12 791990 + + Nuclide 92234.82c -- uranium 234 (U-234) + + Neutron-induced fission: + + Interpolation region : 1 / 1 + Interpolation energy : 4.00000E-01 MeV + Number of products : 845 / 929 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 3.65250E-05 3.65250E-05 1001.82c + 2 10020 H-2 1.11620E-05 1.11620E-05 1002.82c + 3 10030 H-3 1.59250E-04 1.59250E-04 1003.82c + 4 20040 He-4 2.30900E-03 2.30900E-03 2004.82c + 5 240590 Cr-59 1.45230E-12 1.45230E-12 240590 + 6 240600 Cr-60 3.98610E-12 3.98610E-12 240600 + 7 240610 Cr-61 2.78460E-12 2.78460E-12 240610 + 8 240620 Cr-62 3.62560E-12 3.62560E-12 240620 + 9 250600 Mn-60 1.70920E-13 4.35700E-12 250600 + 10 250601 Mn-60m 1.73880E-12 1.73880E-12 250601 + 11 250610 Mn-61 1.15600E-11 1.43450E-11 250610 + 12 250620 Mn-62 1.58810E-11 1.76940E-11 250620 + 13 250621 Mn-62m 2.48700E-12 4.29980E-12 250621 + 14 250630 Mn-63 4.51720E-11 4.51720E-11 250630 + 15 250640 Mn-64 2.13400E-11 2.13400E-11 250640 + 16 250650 Mn-65 2.32230E-11 2.32230E-11 250650 + 17 250660 Mn-66 4.78780E-12 4.78780E-12 250660 + 18 250670 Mn-67 1.28380E-12 1.28380E-12 250670 + 19 260610 Fe-61 1.23080E-12 1.55750E-11 260610 + 20 260620 Fe-62 1.75210E-11 3.95150E-11 260620 + 21 260630 Fe-63 4.94100E-11 9.45820E-11 260630 + 22 260640 Fe-64 2.06180E-10 2.27520E-10 260640 + 23 260650 Fe-65 2.84330E-10 3.07550E-10 260650 + 24 260660 Fe-66 6.09530E-10 6.14320E-10 260660 + 25 260670 Fe-67 2.43630E-10 2.44910E-10 260670 + 26 260680 Fe-68 1.71270E-10 1.71270E-10 260680 + 27 260690 Fe-69 2.99130E-11 2.99130E-11 260690 + 28 260700 Fe-70 6.02310E-12 6.02310E-12 260700 + 29 270630 Co-63 5.33620E-12 9.99180E-11 270630 + 30 270640 Co-64 2.76940E-11 2.55210E-10 270640 + 31 270650 Co-65 3.33710E-10 6.41260E-10 270650 + 32 270660 Co-66 8.23070E-10 1.43740E-09 270660 + 33 270670 Co-67 2.99360E-09 3.23850E-09 270670 + 34 270680 Co-68 1.58970E-09 2.26970E-09 270680 + 35 270681 Co-68m 1.18660E-09 1.36000E-09 270681 + 36 270690 Co-69 5.22670E-09 5.25450E-09 270690 + 37 270700 Co-70 8.05300E-10 8.05300E-10 270700 + 38 270701 Co-70m 8.05300E-10 8.11320E-10 270701 + 39 270710 Co-71 9.32630E-10 9.32630E-10 270710 + 40 270720 Co-72 1.22300E-10 1.22300E-10 270720 + 41 270730 Co-73 1.23160E-11 1.23160E-11 270730 + 42 280650 Ni-65 8.80510E-12 6.50070E-10 280650 + 43 280660 Ni-66 2.12920E-10 1.65030E-09 280660 + 44 280670 Ni-67 9.29810E-10 4.16830E-09 280670 + 45 280680 Ni-68 7.43690E-09 1.04390E-08 280680 + 46 280690 Ni-69 8.18850E-09 1.33910E-08 280690 + 47 280691 Ni-69m 8.18850E-09 8.18850E-09 280691 + 48 280700 Ni-70 4.76330E-08 4.92500E-08 280700 + 49 280710 Ni-71 3.78600E-08 3.87930E-08 280710 + 50 280720 Ni-72 5.52450E-08 5.53670E-08 280720 + 51 280730 Ni-73 8.71120E-09 8.72350E-09 280730 + 52 280740 Ni-74 7.30310E-09 7.30310E-09 280740 + 53 280750 Ni-75 2.62960E-10 2.62960E-10 280750 + 54 280760 Ni-76 8.51840E-11 8.51840E-11 280760 + 55 280770 Ni-77 2.30480E-12 2.30480E-12 280770 + 56 290670 Cu-67 2.35940E-11 4.19190E-09 290670 + 57 290680 Cu-68 6.93900E-11 1.06670E-08 290680 + 58 290681 Cu-68m 1.89140E-10 1.89140E-10 290681 + 59 290690 Cu-69 5.36370E-09 2.69430E-08 290690 + 60 290700 Cu-70 1.23410E-09 1.03770E-08 290700 + 61 290701 Cu-70m 1.57610E-08 1.82850E-08 290701 + 62 290702 Cu-70m 1.23410E-09 5.04840E-08 290702 + 63 290710 Cu-71 1.24990E-07 1.63780E-07 290710 + 64 290720 Cu-72 2.19330E-07 2.74700E-07 290720 + 65 290730 Cu-73 6.70000E-07 6.78720E-07 290730 + 66 290740 Cu-74 4.05610E-07 4.12920E-07 290740 + 67 290750 Cu-75 1.67010E-07 1.67270E-07 290750 + 68 290760 Cu-76 4.29880E-08 4.30310E-08 290760 + 69 290761 Cu-76m 4.29880E-08 4.30310E-08 290761 + 70 290770 Cu-77 2.64090E-08 2.64110E-08 290770 + 71 290780 Cu-78 2.45070E-09 2.45070E-09 290780 + 72 290790 Cu-79 2.58780E-10 2.58780E-10 290790 + 73 300690 Zn-69 5.30440E-12 2.69740E-08 300690 + 74 300691 Zn-69m 2.63450E-11 2.63450E-11 300691 + 75 300700 Zn-70 1.15750E-09 6.86360E-08 300700 + 76 300710 Zn-71 1.75140E-09 1.65530E-07 300710 + 77 300711 Zn-71m 8.69860E-09 8.69860E-09 300711 + 78 300720 Zn-72 1.66580E-07 4.41280E-07 300720 + 79 300730 Zn-73 2.60230E-08 8.58110E-07 300730 + 80 300731 Zn-73m 3.59930E-08 1.53360E-07 300731 + 81 300732 Zn-73m 2.34740E-07 2.34740E-07 300732 + 82 300740 Zn-74 3.25890E-06 3.67770E-06 300740 + 83 300750 Zn-75 3.32060E-06 3.48330E-06 300750 + 84 300760 Zn-76 1.09770E-05 1.10620E-05 300760 + 85 300770 Zn-77 2.64980E-06 2.85260E-06 300770 + 86 300771 Zn-77m 3.52810E-07 3.52810E-07 300771 + 87 300780 Zn-78 1.41300E-05 1.41330E-05 300780 + 88 300790 Zn-79 1.01030E-06 1.01040E-06 300790 + 89 300800 Zn-80 1.01980E-06 1.01980E-06 300800 + 90 300810 Zn-81 6.48270E-09 6.48270E-09 300810 + 91 300820 Zn-82 4.52890E-10 4.52890E-10 300820 + 92 310710 Ga-71 5.68050E-11 1.74290E-07 310710 + 93 310720 Ga-72 1.22730E-09 4.42630E-07 310720 + 94 310721 Ga-72m 1.20650E-10 1.48240E-08 310721 + 95 310730 Ga-73 2.49220E-08 1.00040E-06 310730 + 96 310740 Ga-74 1.64590E-07 3.04630E-06 310740 + 97 310741 Ga-74m 1.64590E-07 3.84230E-06 310741 + 98 310750 Ga-75 1.48980E-06 4.97310E-06 310750 + 99 310760 Ga-76 6.98580E-06 1.80480E-05 310760 + 100 310770 Ga-77 2.00160E-05 2.30450E-05 310770 + 101 310780 Ga-78 3.33060E-05 4.74520E-05 310780 + 102 310790 Ga-79 5.35170E-05 5.45140E-05 310790 + 103 310800 Ga-80 2.85430E-05 2.95630E-05 310800 + 104 310810 Ga-81 1.83500E-05 1.83560E-05 310810 + 105 310820 Ga-82 5.12910E-06 5.12950E-06 310820 + 106 310830 Ga-83 2.63120E-07 2.63120E-07 310830 + 107 310840 Ga-84 8.17130E-09 8.17130E-09 310840 + 108 320720 Ge-72 1.02460E-12 4.42630E-07 32072.82c + 109 320730 Ge-73 2.53070E-11 1.00040E-06 32073.82c + 110 320731 Ge-73m 5.09550E-12 9.85720E-07 320731 + 111 320740 Ge-74 4.63580E-09 4.01150E-06 32074.82c + 112 320750 Ge-75 3.55770E-09 5.00330E-06 320750 + 113 320751 Ge-75m 2.67200E-08 2.25650E-07 320751 + 114 320760 Ge-76 1.99590E-06 2.00430E-05 32076.82c + 115 320770 Ge-77 2.03190E-05 2.52110E-05 320770 + 116 320771 Ge-77m 2.70530E-06 2.57500E-05 320771 + 117 320780 Ge-78 1.07060E-04 1.54560E-04 320780 + 118 320790 Ge-79 3.87110E-05 1.04730E-04 320790 + 119 320791 Ge-79m 2.90750E-04 2.90830E-04 320791 + 120 320800 Ge-80 6.98190E-04 7.29940E-04 320800 + 121 320810 Ge-81 7.31720E-04 7.42360E-04 320810 + 122 320811 Ge-81m 1.47330E-04 1.55510E-04 320811 + 123 320820 Ge-82 9.22630E-04 9.26760E-04 320820 + 124 320830 Ge-83 3.52750E-04 3.52920E-04 320830 + 125 320840 Ge-84 1.20890E-04 1.20890E-04 320840 + 126 320850 Ge-85 2.71910E-05 2.71910E-05 320850 + 127 320860 Ge-86 2.13440E-06 2.13440E-06 320860 + 128 320870 Ge-87 3.32720E-09 3.32720E-09 320870 + 129 330750 As-75 6.91690E-12 5.00340E-06 33075.82c + 130 330751 As-75m 2.61940E-11 9.38880E-11 330751 + 131 330760 As-76 3.14010E-09 3.14010E-09 330760 + 132 330770 As-77 1.74630E-07 4.62440E-05 330770 + 133 330780 As-78 3.02870E-06 1.57590E-04 330780 + 134 330790 As-79 1.92010E-05 4.03130E-04 330790 + 135 330800 As-80 2.16570E-04 9.46510E-04 330800 + 136 330810 As-81 6.15570E-04 1.51190E-03 330810 + 137 330820 As-82 3.32340E-04 1.25910E-03 330820 + 138 330821 As-82m 1.15800E-03 1.15800E-03 330821 + 139 330830 As-83 2.43260E-03 2.79860E-03 330830 + 140 330840 As-84 8.38850E-04 8.94670E-04 330840 + 141 330841 As-84m 8.38850E-04 8.94670E-04 330841 + 142 330850 As-85 9.85540E-04 1.00890E-03 330850 + 143 330860 As-86 2.73010E-04 2.75140E-04 330860 + 144 330870 As-87 9.08790E-05 9.08820E-05 330870 + 145 330880 As-88 5.96710E-06 5.96710E-06 330880 + 146 330890 As-89 7.39110E-08 7.39110E-08 330890 + 147 330900 As-90 1.35300E-09 1.35300E-09 330900 + 148 340770 Se-77 4.87460E-12 4.62440E-05 34077.82c + 149 340771 Se-77m 3.66110E-11 3.66110E-11 340771 + 150 340780 Se-78 8.58140E-09 1.57600E-04 34078.82c + 151 340790 Se-79 1.78330E-06 4.04930E-04 34079.82c + 152 340791 Se-79m 2.37430E-07 3.93820E-04 340791 + 153 340800 Se-80 3.26520E-05 9.79240E-04 34080.82c + 154 340810 Se-81 2.74160E-05 1.74510E-03 340810 + 155 340811 Se-81m 2.05910E-04 2.60190E-04 340811 + 156 340820 Se-82 1.22170E-03 3.63880E-03 34082.82c + 157 340830 Se-83 3.70270E-03 4.71140E-03 340830 + 158 340831 Se-83m 7.45520E-04 2.53790E-03 340831 + 159 340840 Se-84 1.13340E-02 1.33430E-02 340840 + 160 340850 Se-85 1.27490E-02 1.36270E-02 340850 + 161 340860 Se-86 1.16910E-02 1.18890E-02 340860 + 162 340870 Se-87 5.99240E-03 6.06930E-03 340870 + 163 340880 Se-88 2.65210E-03 2.65810E-03 340880 + 164 340890 Se-89 5.64130E-04 5.64200E-04 340890 + 165 340900 Se-90 1.38470E-04 1.38470E-04 340900 + 166 340910 Se-91 8.44450E-06 8.44450E-06 340910 + 167 340920 Se-92 1.62980E-08 1.62980E-08 340920 + 168 350790 Br-79 1.20130E-11 2.20590E-07 35079.82c + 169 350791 Br-79m 4.54920E-11 4.54920E-11 350791 + 170 350800 Br-80 2.27420E-07 1.01980E-06 350800 + 171 350801 Br-80m 7.92390E-07 7.92390E-07 350801 + 172 350810 Br-81 1.01980E-06 1.74620E-03 35081.82c + 173 350820 Br-82 4.50410E-06 6.11680E-06 350820 + 174 350821 Br-82m 1.65240E-06 1.65240E-06 350821 + 175 350830 Br-83 1.37760E-04 7.38700E-03 350830 + 176 350840 Br-84 4.85210E-04 1.38280E-02 350840 + 177 350841 Br-84m 4.85210E-04 4.85210E-04 350841 + 178 350850 Br-85 4.51360E-03 1.81400E-02 350850 + 179 350860 Br-86 1.00900E-02 2.19790E-02 350860 + 180 350870 Br-87 1.51130E-02 2.12090E-02 350870 + 181 350880 Br-88 1.22720E-02 1.49480E-02 350880 + 182 350890 Br-89 8.78250E-03 9.30270E-03 350890 + 183 350900 Br-90 3.39460E-03 3.53480E-03 350900 + 184 350910 Br-91 1.33410E-03 1.34080E-03 350910 + 185 350920 Br-92 1.48520E-04 1.48540E-04 350920 + 186 350930 Br-93 3.12890E-05 3.12890E-05 350930 + 187 350940 Br-94 8.96090E-08 8.96090E-08 350940 + 188 350950 Br-95 2.59230E-09 2.59230E-09 350950 + 189 360820 Kr-82 3.77410E-09 6.16030E-06 36082.82c + 190 360830 Kr-83 4.26940E-06 7.39220E-03 36083.82c + 191 360831 Kr-83m 8.59620E-07 7.38130E-03 360831 + 192 360840 Kr-84 5.69760E-05 1.43700E-02 36084.82c + 193 360850 Kr-85 4.09090E-04 4.33190E-03 36085.82c + 194 360851 Kr-85m 8.23690E-05 1.81930E-02 360851 + 195 360860 Kr-86 4.11700E-03 2.66290E-02 36086.82c + 196 360870 Kr-87 1.21440E-02 3.38220E-02 360870 + 197 360880 Kr-88 3.12750E-02 4.65330E-02 360880 + 198 360890 Kr-89 4.02860E-02 4.91470E-02 360890 + 199 360900 Kr-90 4.12790E-02 4.42120E-02 360900 + 200 360910 Kr-91 2.43230E-02 2.54450E-02 360910 + 201 360920 Kr-92 1.24260E-02 1.25470E-02 360920 + 202 360930 Kr-93 3.70480E-03 3.71490E-03 360930 + 203 360940 Kr-94 1.08590E-03 1.08590E-03 360940 + 204 360950 Kr-95 1.38090E-04 1.38090E-04 360950 + 205 360960 Kr-96 1.95770E-05 1.95770E-05 360960 + 206 360970 Kr-97 1.61440E-08 1.61440E-08 360970 + 207 370840 Rb-84 2.93080E-10 9.07920E-10 370840 + 208 370841 Rb-84m 6.14840E-10 6.14840E-10 370841 + 209 370850 Rb-85 1.04640E-06 1.86330E-02 37085.82c + 210 370860 Rb-86 3.10130E-06 9.60740E-06 37086.82c + 211 370861 Rb-86m 6.50610E-06 6.50610E-06 370861 + 212 370870 Rb-87 1.78650E-04 3.40000E-02 37087.82c + 213 370880 Rb-88 8.63000E-04 4.73960E-02 370880 + 214 370890 Rb-89 4.97030E-03 5.41170E-02 370890 + 215 370900 Rb-90 1.18250E-03 4.00750E-02 370900 + 216 370901 Rb-90m 1.20300E-02 1.78120E-02 370901 + 217 370910 Rb-91 2.73790E-02 5.28240E-02 370910 + 218 370920 Rb-92 2.69700E-02 3.95170E-02 370920 + 219 370930 Rb-93 2.14160E-02 2.51430E-02 370930 + 220 370940 Rb-94 1.09820E-02 1.20600E-02 370940 + 221 370950 Rb-95 5.89040E-03 6.02530E-03 370950 + 222 370960 Rb-96 6.90300E-04 1.04960E-03 370960 + 223 370961 Rb-96m 6.90300E-04 6.99730E-04 370961 + 224 370970 Rb-97 3.09550E-04 3.09560E-04 370970 + 225 370980 Rb-98 1.02490E-05 1.02490E-05 370980 + 226 370981 Rb-98m 1.02490E-05 1.02490E-05 370981 + 227 370990 Rb-99 3.86550E-06 3.86550E-06 370990 + 228 371000 Rb-100 1.05590E-09 1.05590E-09 371000 + 229 380870 Sr-87 2.58480E-06 3.10360E-06 38087.82c + 230 380871 Sr-87m 5.20430E-07 5.20430E-07 380871 + 231 380880 Sr-88 4.48150E-05 4.74410E-02 38088.82c + 232 380890 Sr-89 2.13990E-04 5.43310E-02 38089.82c + 233 380900 Sr-90 2.37620E-03 5.98010E-02 38090.82c + 234 380910 Sr-91 7.56720E-03 6.03910E-02 380910 + 235 380920 Sr-92 2.67450E-02 6.66140E-02 380920 + 236 380930 Sr-93 4.17570E-02 6.77660E-02 380930 + 237 380940 Sr-94 5.85340E-02 6.98940E-02 380940 + 238 380950 Sr-95 4.36860E-02 4.93340E-02 380950 + 239 380960 Sr-96 2.88230E-02 3.01590E-02 380960 + 240 380970 Sr-97 1.17610E-02 1.19940E-02 380970 + 241 380980 Sr-98 4.70780E-03 4.72750E-03 380980 + 242 380990 Sr-99 8.97600E-04 9.00850E-04 380990 + 243 381000 Sr-100 1.63230E-04 1.63230E-04 381000 + 244 381010 Sr-101 8.65400E-06 8.65400E-06 381010 + 245 381020 Sr-102 1.33590E-08 1.33590E-08 381020 + 246 390890 Y-89 6.35240E-10 5.43310E-02 39089.82c + 247 390891 Y-89m 3.15500E-09 5.24020E-06 390891 + 248 390900 Y-90 3.96910E-07 5.98020E-02 39090.82c + 249 390901 Y-90m 6.63790E-07 6.63790E-07 390901 + 250 390910 Y-91 7.26260E-06 6.04340E-02 39091.82c + 251 390911 Y-91m 3.60700E-05 3.55670E-02 390911 + 252 390920 Y-92 2.50630E-04 6.68640E-02 390920 + 253 390930 Y-93 2.13970E-04 6.95870E-02 390930 + 254 390931 Y-93m 1.60700E-03 1.85650E-02 390931 + 255 390940 Y-94 5.43760E-03 7.53320E-02 390940 + 256 390950 Y-95 1.91050E-02 6.84390E-02 390950 + 257 390960 Y-96 8.76850E-03 3.89310E-02 390960 + 258 390961 Y-96m 1.83950E-02 1.83990E-02 390961 + 259 390970 Y-97 5.30070E-03 1.56930E-02 390970 + 260 390971 Y-97m 1.95930E-02 2.67630E-02 390971 + 261 390972 Y-97m 6.73340E-03 6.73340E-03 390972 + 262 390980 Y-98 3.29620E-03 8.02370E-03 390980 + 263 390981 Y-98m 1.59800E-02 1.59800E-02 390981 + 264 390990 Y-99 1.24360E-02 1.33380E-02 390990 + 265 391000 Y-100 2.08080E-03 2.24280E-03 391000 + 266 391001 Y-100m 2.08080E-03 2.08080E-03 391001 + 267 391010 Y-101 1.26030E-03 1.26870E-03 391010 + 268 391020 Y-102 7.03950E-05 7.04010E-05 391020 + 269 391021 Y-102m 7.03950E-05 7.04010E-05 391021 + 270 391030 Y-103 1.48080E-05 1.48080E-05 391030 + 271 391040 Y-104 1.70400E-08 1.70400E-08 391040 + 272 391050 Y-105 1.80800E-10 1.80800E-10 391050 + 273 400920 Zr-92 3.04210E-06 6.68670E-02 40092.82c + 274 400930 Zr-93 5.19400E-05 6.96390E-02 40093.82c + 275 400940 Zr-94 4.41700E-04 7.57730E-02 40094.82c + 276 400950 Zr-95 2.05840E-03 7.04970E-02 40095.82c + 277 400960 Zr-96 1.03400E-02 6.76910E-02 40096.82c + 278 400970 Zr-97 2.08610E-02 6.50260E-02 400970 + 279 400980 Zr-98 4.25350E-02 6.61940E-02 400980 + 280 400990 Zr-99 3.84680E-02 5.16000E-02 400990 + 281 401000 Zr-100 3.20960E-02 3.63990E-02 401000 + 282 401010 Zr-101 1.41820E-02 1.54580E-02 401010 + 283 401020 Zr-102 6.01980E-03 6.15490E-03 401020 + 284 401030 Zr-103 1.23920E-03 1.25280E-03 401030 + 285 401040 Zr-104 2.11690E-04 2.11710E-04 401040 + 286 401050 Zr-105 1.01540E-05 1.01540E-05 401050 + 287 401060 Zr-106 3.05870E-08 3.05870E-08 401060 + 288 401070 Zr-107 1.27820E-10 1.27820E-10 401070 + 289 410940 Nb-94 6.03060E-07 9.61870E-07 41094.82c + 290 410941 Nb-94m 3.60610E-07 3.60610E-07 410941 + 291 410950 Nb-95 5.98000E-06 7.04620E-02 41095.82c + 292 410951 Nb-95m 1.20410E-06 7.62820E-04 410951 + 293 410960 Nb-96 4.85040E-05 4.85040E-05 410960 + 294 410970 Nb-97 3.23720E-04 6.54150E-02 410970 + 295 410971 Nb-97m 6.51800E-05 6.18710E-02 410971 + 296 410980 Nb-98 3.17890E-04 6.65120E-02 410980 + 297 410981 Nb-98m 1.10760E-03 1.10760E-03 410981 + 298 410990 Nb-99 4.54540E-03 3.75550E-02 410990 + 299 410991 Nb-99m 9.15200E-04 1.99040E-02 410991 + 300 411000 Nb-100 1.64300E-03 3.80420E-02 411000 + 301 411001 Nb-100m 7.96500E-03 7.96500E-03 411001 + 302 411010 Nb-101 1.49020E-02 3.03600E-02 411010 + 303 411020 Nb-102 5.11550E-03 1.12700E-02 411020 + 304 411021 Nb-102m 5.11550E-03 5.11550E-03 411021 + 305 411030 Nb-103 6.39170E-03 7.64450E-03 411030 + 306 411040 Nb-104 9.74550E-04 1.18640E-03 411040 + 307 411041 Nb-104m 9.74550E-04 9.74550E-04 411041 + 308 411050 Nb-105 5.21320E-04 5.31330E-04 411050 + 309 411060 Nb-106 5.26260E-05 5.26560E-05 411060 + 310 411070 Nb-107 6.86280E-06 6.86290E-06 411070 + 311 411080 Nb-108 1.97910E-06 1.97910E-06 411080 + 312 411090 Nb-109 5.84260E-10 5.84260E-10 411090 + 313 411100 Nb-110 5.72540E-12 5.72540E-12 411100 + 314 420960 Mo-96 1.03090E-06 4.95350E-05 42096.82c + 315 420970 Mo-97 5.84670E-06 6.54210E-02 42097.82c + 316 420980 Mo-98 5.51070E-05 6.76740E-02 42098.82c + 317 420990 Mo-99 2.95250E-04 5.73560E-02 42099.82c + 318 421000 Mo-100 1.50020E-03 4.75070E-02 42100.82c + 319 421010 Mo-101 3.27030E-03 3.36300E-02 421010 + 320 421020 Mo-102 6.51350E-03 2.28990E-02 421020 + 321 421030 Mo-103 5.65630E-03 1.33020E-02 421030 + 322 421040 Mo-104 4.25770E-03 6.42650E-03 421040 + 323 421050 Mo-105 1.63510E-03 2.15980E-03 421050 + 324 421060 Mo-106 5.70850E-04 6.21550E-04 421060 + 325 421070 Mo-107 8.52510E-05 9.18250E-05 421070 + 326 421080 Mo-108 2.57210E-05 2.75780E-05 421080 + 327 421090 Mo-109 2.97770E-06 2.97820E-06 421090 + 328 421100 Mo-110 1.97850E-06 1.97850E-06 421100 + 329 421110 Mo-111 2.55270E-09 2.55270E-09 421110 + 330 421120 Mo-112 9.39430E-11 9.39430E-11 421120 + 331 430990 Tc-99 1.67990E-09 5.73540E-02 43099.82c + 332 430991 Tc-99m 3.38230E-10 5.05070E-02 430991 + 333 431000 Tc-100 2.96060E-06 2.96060E-06 431000 + 334 431010 Tc-101 2.40630E-05 3.36540E-02 431010 + 335 431020 Tc-102 3.32390E-05 2.29330E-02 431020 + 336 431021 Tc-102m 3.32390E-05 3.32390E-05 431021 + 337 431030 Tc-103 2.43960E-04 1.35460E-02 431030 + 338 431040 Tc-104 2.90210E-04 6.71670E-03 431040 + 339 431050 Tc-105 3.62940E-04 2.52270E-03 431050 + 340 431060 Tc-106 2.29080E-04 8.50630E-04 431060 + 341 431070 Tc-107 1.31460E-04 2.23280E-04 431070 + 342 431080 Tc-108 4.74980E-05 7.50910E-05 431080 + 343 431090 Tc-109 3.07640E-05 3.37260E-05 431090 + 344 431100 Tc-110 9.89180E-06 1.18700E-05 431100 + 345 431110 Tc-111 9.90290E-06 9.90540E-06 431110 + 346 431120 Tc-112 4.94080E-06 4.94090E-06 431120 + 347 431130 Tc-113 2.02080E-08 2.02080E-08 431130 + 348 431140 Tc-114 4.54140E-10 4.54140E-10 431140 + 349 431150 Tc-115 2.43010E-11 2.43010E-11 431150 + 350 431180 Tc-118 3.38000E-11 3.38000E-11 431180 + 351 441020 Ru-102 9.48010E-07 2.29670E-02 44102.82c + 352 441030 Ru-103 7.31390E-07 1.35490E-02 44103.82c + 353 441031 Ru-103m 2.04640E-06 2.04640E-06 441031 + 354 441040 Ru-104 1.96070E-05 6.73630E-03 44104.82c + 355 441050 Ru-105 1.94000E-05 2.54210E-03 44105.82c + 356 441060 Ru-106 3.29480E-05 8.83580E-04 44106.82c + 357 441070 Ru-107 1.86360E-05 2.41920E-04 441070 + 358 441080 Ru-108 4.45530E-05 1.19670E-04 441080 + 359 441090 Ru-109 5.85780E-05 9.22820E-05 441090 + 360 441100 Ru-110 7.02440E-05 8.21100E-05 441100 + 361 441110 Ru-111 5.24870E-05 6.24670E-05 441110 + 362 441120 Ru-112 4.34750E-05 4.83430E-05 441120 + 363 441130 Ru-113 8.80350E-06 1.32240E-05 441130 + 364 441131 Ru-113m 8.80350E-06 8.80350E-06 441131 + 365 441140 Ru-114 1.08520E-05 1.08520E-05 441140 + 366 441150 Ru-115 9.92440E-07 9.92460E-07 441150 + 367 441160 Ru-116 6.85900E-09 6.85900E-09 441160 + 368 441170 Ru-117 1.04570E-10 1.04570E-10 441170 + 369 441180 Ru-118 2.53630E-07 2.53660E-07 441180 + 370 441190 Ru-119 8.64700E-09 8.64700E-09 441190 + 371 441200 Ru-120 5.49740E-10 5.49740E-10 441200 + 372 451050 Rh-105 2.47320E-09 2.54210E-03 45105.82c + 373 451051 Rh-105m 3.29290E-10 7.21650E-04 451051 + 374 451060 Rh-106 5.86270E-09 8.83580E-04 451060 + 375 451061 Rh-106m 1.59800E-08 1.59800E-08 451061 + 376 451070 Rh-107 9.80590E-07 2.42900E-04 451070 + 377 451080 Rh-108 4.41380E-07 1.20110E-04 451080 + 378 451081 Rh-108m 1.53790E-06 1.53790E-06 451081 + 379 451090 Rh-109 3.97070E-06 9.62530E-05 451090 + 380 451100 Rh-110 6.76640E-06 8.88760E-05 451100 + 381 451101 Rh-110m 1.59290E-07 1.59290E-07 451101 + 382 451110 Rh-111 2.37760E-05 8.62420E-05 451110 + 383 451120 Rh-112 8.89550E-06 5.72390E-05 451120 + 384 451121 Rh-112m 8.89550E-06 8.89550E-06 451121 + 385 451130 Rh-113 5.67480E-05 7.43740E-05 451130 + 386 451140 Rh-114 1.43060E-05 2.51610E-05 451140 + 387 451141 Rh-114m 1.43060E-05 1.43060E-05 451141 + 388 451150 Rh-115 3.76990E-05 3.86890E-05 451150 + 389 451160 Rh-116 2.62250E-06 2.62930E-06 451160 + 390 451161 Rh-116m 7.14840E-06 7.14840E-06 451161 + 391 451170 Rh-117 1.00910E-06 1.01960E-06 451170 + 392 451180 Rh-118 1.00690E-06 1.25050E-06 451180 + 393 451190 Rh-119 4.80060E-06 4.80890E-06 451190 + 394 451200 Rh-120 4.90870E-07 4.91420E-07 451200 + 395 451210 Rh-121 4.81060E-08 4.81060E-08 451210 + 396 451220 Rh-122 1.65560E-09 1.65560E-09 451220 + 397 461070 Pd-107 5.70960E-12 2.42900E-04 46107.82c + 398 461071 Pd-107m 1.25490E-11 1.25490E-11 461071 + 399 461080 Pd-108 8.57450E-10 1.21650E-04 46108.82c + 400 461090 Pd-109 3.64200E-09 9.62650E-05 461090 + 401 461091 Pd-109m 8.00500E-09 4.81340E-05 461091 + 402 461100 Pd-110 2.81420E-07 8.93170E-05 46110.82c + 403 461110 Pd-111 6.19460E-07 8.77630E-05 461110 + 404 461111 Pd-111m 1.36150E-06 1.70650E-06 461111 + 405 461120 Pd-112 6.91870E-06 7.30530E-05 461120 + 406 461130 Pd-113 3.34940E-06 8.70950E-05 461130 + 407 461131 Pd-113m 9.37160E-06 9.37160E-06 461131 + 408 461140 Pd-114 4.63920E-05 8.58590E-05 461140 + 409 461150 Pd-115 2.51410E-05 6.30830E-05 461150 + 410 461151 Pd-115m 5.52590E-05 6.08770E-05 461151 + 411 461160 Pd-116 7.52390E-05 8.50170E-05 461160 + 412 461170 Pd-117 1.38800E-05 4.54440E-05 461170 + 413 461171 Pd-117m 3.05080E-05 3.05080E-05 461171 + 414 461180 Pd-118 2.01340E-05 2.13480E-05 461180 + 415 461190 Pd-119 4.76270E-06 9.60070E-06 461190 + 416 461200 Pd-120 2.01620E-06 2.48500E-06 461200 + 417 461210 Pd-121 6.19640E-06 6.23800E-06 461210 + 418 461220 Pd-122 2.52050E-06 2.52220E-06 461220 + 419 461230 Pd-123 1.38070E-07 1.38070E-07 461230 + 420 461240 Pd-124 1.39140E-08 1.39140E-08 461240 + 421 471100 Ag-110 1.07570E-11 1.11550E-11 471100 + 422 471101 Ag-110m 2.93200E-11 2.93200E-11 47510.82c + 423 471110 Ag-111 3.04340E-10 8.77890E-05 47111.82c + 424 471111 Ag-111m 2.28580E-09 8.74750E-05 471111 + 425 471120 Ag-112 2.82450E-08 7.30810E-05 471120 + 426 471130 Ag-113 7.95390E-08 5.75330E-05 471130 + 427 471131 Ag-113m 5.97390E-07 8.39970E-05 471131 + 428 471140 Ag-114 1.68740E-07 8.68450E-05 471140 + 429 471141 Ag-114m 8.18040E-07 8.18040E-07 471141 + 430 471150 Ag-115 2.09950E-06 6.68000E-05 471150 + 431 471151 Ag-115m 1.57680E-05 8.88070E-05 471151 + 432 471160 Ag-116 4.45950E-06 9.02060E-05 471160 + 433 471161 Ag-116m 1.21560E-05 1.21560E-05 471161 + 434 471170 Ag-117 4.26920E-06 3.02790E-05 471170 + 435 471171 Ag-117m 3.20650E-05 5.47870E-05 471171 + 436 471180 Ag-118 7.40410E-06 4.16690E-05 471180 + 437 471181 Ag-118m 3.58950E-05 3.89470E-05 471181 + 438 471190 Ag-119 4.47670E-06 9.27710E-06 471190 + 439 471191 Ag-119m 3.36230E-05 3.84240E-05 471191 + 440 471200 Ag-120 6.78910E-06 1.27090E-05 471200 + 441 471201 Ag-120m 1.13540E-05 1.25960E-05 471201 + 442 471210 Ag-121 1.10530E-05 1.72740E-05 471210 + 443 471220 Ag-122 2.36020E-06 4.88230E-06 471220 + 444 471221 Ag-122m 2.54460E-06 2.54460E-06 471221 + 445 471230 Ag-123 1.00430E-06 1.14240E-06 471230 + 446 471240 Ag-124 1.25650E-06 1.94770E-06 471240 + 447 471241 Ag-124m 1.35460E-06 1.35460E-06 471241 + 448 471250 Ag-125 1.00770E-06 1.00770E-06 471250 + 449 471260 Ag-126 1.30190E-07 1.30190E-07 471260 + 450 471270 Ag-127 3.55560E-08 3.55560E-08 471270 + 451 471280 Ag-128 2.15320E-09 2.15320E-09 471280 + 452 481120 Cd-112 6.06060E-12 7.30810E-05 48112.82c + 453 481130 Cd-113 5.41780E-11 8.67780E-05 48113.82c + 454 481131 Cd-113m 2.05170E-10 9.94880E-07 481131 + 455 481140 Cd-114 1.28490E-08 8.68580E-05 48114.82c + 456 481150 Cd-115 4.27350E-08 1.31110E-04 481150 + 457 481151 Cd-115m 1.61830E-07 6.05360E-06 48515.82c + 458 481160 Cd-116 1.95450E-06 1.03590E-04 48116.82c + 459 481170 Cd-117 1.89750E-06 6.57930E-05 481170 + 460 481171 Cd-117m 7.18570E-06 2.50680E-05 481171 + 461 481180 Cd-118 2.31650E-05 8.78120E-05 481180 + 462 481190 Cd-119 1.02870E-05 5.33490E-05 481190 + 463 481191 Cd-119m 2.87820E-05 3.34210E-05 481191 + 464 481200 Cd-120 7.25980E-05 9.32430E-05 481200 + 465 481210 Cd-121 1.11580E-05 2.66270E-05 481210 + 466 481211 Cd-121m 3.12180E-05 3.30230E-05 481211 + 467 481220 Cd-122 5.39490E-05 6.13760E-05 481220 + 468 481230 Cd-123 8.72470E-06 9.66030E-06 481230 + 469 481231 Cd-123m 2.44110E-05 2.46200E-05 481231 + 470 481240 Cd-124 1.54830E-05 1.81060E-05 481240 + 471 481250 Cd-125 3.71390E-06 4.21770E-06 481250 + 472 481251 Cd-125m 1.03910E-05 1.08950E-05 481251 + 473 481260 Cd-126 3.25010E-05 3.26310E-05 481260 + 474 481270 Cd-127 2.90370E-05 2.90730E-05 481270 + 475 481280 Cd-128 2.68400E-05 2.68420E-05 481280 + 476 481290 Cd-129 1.67100E-06 1.67100E-06 481290 + 477 481291 Cd-129m 4.67520E-06 4.67520E-06 481291 + 478 481300 Cd-130 1.36270E-07 1.36270E-07 481300 + 479 481310 Cd-131 2.59200E-09 2.59200E-09 481310 + 480 491150 In-115 5.66370E-11 1.30610E-04 49115.82c + 481 491151 In-115m 1.14040E-11 1.31110E-04 491151 + 482 491160 In-116 2.93110E-10 2.93110E-10 491160 + 483 491161 In-116m 4.73320E-10 1.02130E-09 491161 + 484 491162 In-116m 5.47970E-10 5.47970E-10 491162 + 485 491170 In-117 3.66540E-08 5.88040E-05 491170 + 486 491171 In-117m 7.38010E-09 6.06840E-05 491171 + 487 491180 In-118 1.67500E-12 8.78120E-05 491180 + 488 491181 In-118m 2.70470E-12 5.79220E-12 491181 + 489 491182 In-118m 3.13130E-12 3.13130E-12 491182 + 490 491190 In-119 4.86410E-10 4.12360E-05 491190 + 491 491191 In-119m 9.79350E-11 4.82350E-05 491191 + 492 491200 In-120 6.72030E-07 9.39150E-05 491200 + 493 491201 In-120m 6.72030E-07 6.72030E-07 491201 + 494 491202 In-120m 6.72030E-07 6.72030E-07 491202 + 495 491210 In-121 1.22710E-05 5.45040E-05 491210 + 496 491211 In-121m 2.47080E-06 2.01300E-05 491211 + 497 491220 In-122 8.44490E-06 6.98210E-05 491220 + 498 491221 In-122m 7.06150E-06 7.06150E-06 491221 + 499 491222 In-122m 7.06150E-06 7.06150E-06 491222 + 500 491230 In-123 2.25760E-05 4.98870E-05 491230 + 501 491231 In-123m 4.54550E-06 1.15140E-05 491231 + 502 491240 In-124 1.35070E-05 3.16130E-05 491240 + 503 491241 In-124m 1.45620E-05 1.45620E-05 491241 + 504 491250 In-125 3.69040E-05 4.98180E-05 491250 + 505 491251 In-125m 7.43060E-06 9.62950E-06 491251 + 506 491260 In-126 4.34990E-05 7.61310E-05 491260 + 507 491261 In-126m 4.68980E-05 4.68980E-05 491261 + 508 491270 In-127 2.32700E-04 2.32700E-04 491270 + 509 491271 In-127m 4.68530E-05 7.59250E-05 491271 + 510 491280 In-128 1.44300E-04 2.27640E-04 491280 + 511 491281 In-128m 5.65010E-05 8.33430E-05 491281 + 512 491282 In-128m 2.16490E-04 2.16490E-04 491282 + 513 491290 In-129 3.49320E-04 3.54000E-04 491290 + 514 491291 In-129m 7.03350E-05 7.20080E-05 491291 + 515 491300 In-130 4.72070E-05 4.73390E-05 491300 + 516 491301 In-130m 6.87360E-05 6.87360E-05 491301 + 517 491302 In-130m 9.57470E-05 9.57470E-05 491302 + 518 491310 In-131 2.18640E-05 2.20890E-05 491310 + 519 491311 In-131m 2.18640E-05 2.18640E-05 491311 + 520 491312 In-131m 2.18640E-05 2.18640E-05 491312 + 521 491320 In-132 2.07890E-06 2.07890E-06 491320 + 522 491330 In-133 5.23000E-08 6.28300E-08 491330 + 523 491331 In-133m 1.05300E-08 1.05300E-08 491331 + 524 501170 Sn-117 4.74850E-13 9.09050E-05 50117.82c + 525 501171 Sn-117m 1.79820E-12 2.00350E-07 501171 + 526 501210 Sn-121 1.21290E-11 7.30090E-05 501210 + 527 501211 Sn-121m 3.39370E-11 6.17440E-06 501211 + 528 501220 Sn-122 3.92440E-06 8.78680E-05 50122.82c + 529 501230 Sn-123 5.92000E-06 9.72350E-06 50123.82c + 530 501231 Sn-123m 2.11580E-06 5.97140E-05 501231 + 531 501240 Sn-124 2.42040E-05 7.03790E-05 50124.82c + 532 501250 Sn-125 3.26780E-05 4.10930E-05 50125.82c + 533 501251 Sn-125m 1.16790E-05 6.27120E-05 501251 + 534 501260 Sn-126 1.37300E-04 2.60850E-04 50126.82c + 535 501270 Sn-127 4.20390E-04 5.11090E-04 501270 + 536 501271 Sn-127m 1.50250E-04 3.67650E-04 501271 + 537 501280 Sn-128 7.82090E-04 3.35800E-03 501280 + 538 501281 Sn-128m 2.13180E-03 2.34830E-03 501281 + 539 501290 Sn-129 1.29820E-03 1.68660E-03 501290 + 540 501291 Sn-129m 3.63220E-03 3.66990E-03 501291 + 541 501300 Sn-130 2.12780E-03 2.25740E-03 501300 + 542 501301 Sn-130m 5.79990E-03 5.88260E-03 501301 + 543 501310 Sn-131 1.33560E-03 1.37790E-03 501310 + 544 501311 Sn-131m 3.73690E-03 3.75970E-03 501311 + 545 501320 Sn-132 2.55970E-03 2.56180E-03 501320 + 546 501330 Sn-133 2.57910E-04 2.57920E-04 501330 + 547 501340 Sn-134 4.86600E-05 4.86600E-05 501340 + 548 501350 Sn-135 1.02430E-06 1.02430E-06 501350 + 549 501360 Sn-136 1.54770E-08 1.54770E-08 501360 + 550 511230 Sb-123 7.37790E-12 6.94370E-05 51123.82c + 551 511240 Sb-124 7.78210E-11 2.00280E-10 51124.82c + 552 511241 Sb-124m 6.27770E-11 1.63280E-10 511241 + 553 511242 Sb-124m 1.00510E-10 1.00510E-10 511242 + 554 511250 Sb-125 2.01560E-06 1.05820E-04 51125.82c + 555 511260 Sb-126 1.69470E-06 2.02660E-06 51126.82c + 556 511261 Sb-126m 1.05850E-06 2.37060E-06 511261 + 557 511262 Sb-126m 1.31220E-06 1.31220E-06 511262 + 558 511270 Sb-127 4.88030E-05 9.27540E-04 511270 + 559 511280 Sb-128 8.89000E-05 3.45140E-03 511280 + 560 511281 Sb-128m 1.24340E-04 1.24340E-04 511281 + 561 511290 Sb-129 1.39510E-03 5.34670E-03 511290 + 562 511291 Sb-129m 1.03240E-03 2.86730E-03 511291 + 563 511300 Sb-130 2.90220E-03 8.10090E-03 511300 + 564 511301 Sb-130m 2.90220E-03 5.84350E-03 511301 + 565 511310 Sb-131 1.45610E-02 1.96990E-02 511310 + 566 511320 Sb-132 7.15350E-03 9.71530E-03 511320 + 567 511321 Sb-132m 6.33350E-03 6.33350E-03 511321 + 568 511330 Sb-133 1.07210E-02 1.09870E-02 511330 + 569 511340 Sb-134 7.94060E-04 8.34560E-04 511340 + 570 511341 Sb-134m 2.16440E-03 2.16450E-03 511341 + 571 511350 Sb-135 6.80420E-04 6.81230E-04 511350 + 572 511360 Sb-136 8.13680E-05 8.13790E-05 511360 + 573 511370 Sb-137 6.86240E-06 6.86240E-06 511370 + 574 511380 Sb-138 6.99650E-08 6.99650E-08 511380 + 575 511390 Sb-139 2.15040E-09 2.15040E-09 511390 + 576 521260 Te-126 2.40840E-10 4.06560E-06 52126.82c + 577 521270 Te-127 2.73200E-07 9.24890E-04 521270 + 578 521271 Te-127m 7.64400E-07 1.53620E-04 52527.82c + 579 521280 Te-128 1.93430E-05 3.59060E-03 52128.82c + 580 521290 Te-129 3.35020E-05 6.66750E-03 521290 + 581 521291 Te-129m 9.37380E-05 3.36120E-03 52529.82c + 582 521300 Te-130 1.84410E-03 1.57890E-02 52130.82c + 583 521310 Te-131 1.62020E-03 2.10250E-02 521310 + 584 521311 Te-131m 4.53310E-03 6.11020E-03 521311 + 585 521320 Te-132 2.73180E-02 4.33670E-02 52132.82c + 586 521330 Te-133 1.00450E-02 2.43840E-02 521330 + 587 521331 Te-133m 2.81040E-02 3.00050E-02 521331 + 588 521340 Te-134 6.10850E-02 6.41890E-02 521340 + 589 521350 Te-135 2.07360E-02 2.13230E-02 521350 + 590 521360 Te-136 1.05160E-02 1.05870E-02 521360 + 591 521370 Te-137 2.02380E-03 2.02730E-03 521370 + 592 521380 Te-138 5.05480E-04 5.05550E-04 521380 + 593 521390 Te-139 3.17060E-05 3.17080E-05 521390 + 594 521400 Te-140 7.21200E-06 7.21200E-06 521400 + 595 521410 Te-141 8.48010E-09 8.48010E-09 521410 + 596 531280 I-128 1.53800E-10 1.53800E-10 531280 + 597 531290 I-129 3.86530E-08 7.91120E-03 53129.82c + 598 531300 I-130 5.38730E-06 7.04750E-06 53130.82c + 599 531301 I-130m 1.97640E-06 1.97640E-06 531301 + 600 531310 I-131 9.71590E-05 2.59490E-02 53131.82c + 601 531320 I-132 2.52990E-04 4.38120E-02 531320 + 602 531321 I-132m 2.23990E-04 2.23990E-04 531321 + 603 531330 I-133 2.43510E-03 5.33750E-02 531330 + 604 531331 I-133m 1.80210E-03 1.80210E-03 531331 + 605 531340 I-134 6.63320E-03 7.65600E-02 531340 + 606 531341 I-134m 5.87280E-03 5.87280E-03 531341 + 607 531350 I-135 4.30360E-02 6.43600E-02 53135.82c + 608 531360 I-136 7.71840E-03 1.83360E-02 531360 + 609 531361 I-136m 2.10390E-02 2.10690E-02 531361 + 610 531370 I-137 2.19870E-02 2.39850E-02 531370 + 611 531380 I-138 6.56740E-03 7.04110E-03 531380 + 612 531390 I-139 4.11870E-03 4.15040E-03 531390 + 613 531400 I-140 8.05880E-04 8.13090E-04 531400 + 614 531410 I-141 1.32070E-04 1.32080E-04 531410 + 615 531420 I-142 1.17860E-05 1.17860E-05 531420 + 616 531430 I-143 9.43710E-08 9.43710E-08 531430 + 617 531440 I-144 1.19230E-09 1.19230E-09 531440 + 618 541310 Xe-131 3.07110E-09 2.59490E-02 54131.82c + 619 541311 Xe-131m 8.59290E-09 2.81870E-04 541311 + 620 541320 Xe-132 4.44370E-06 4.38540E-02 54132.82c + 621 541321 Xe-132m 5.95330E-06 5.95330E-06 541321 + 622 541330 Xe-133 2.24590E-05 5.34610E-02 54133.82c + 623 541331 Xe-133m 6.28380E-05 1.58210E-03 541331 + 624 541340 Xe-134 3.16100E-04 7.78730E-02 54134.82c + 625 541341 Xe-134m 8.61600E-04 9.96680E-04 541341 + 626 541350 Xe-135 1.41150E-03 6.96330E-02 54135.82c + 627 541351 Xe-135m 3.94940E-03 1.45740E-02 541351 + 628 541360 Xe-136 3.77020E-02 7.86660E-02 54136.82c + 629 541370 Xe-137 4.91940E-02 7.19940E-02 541370 + 630 541380 Xe-138 6.24000E-02 6.94750E-02 541380 + 631 541390 Xe-139 3.14720E-02 3.52910E-02 541390 + 632 541400 Xe-140 2.70540E-02 2.78190E-02 541400 + 633 541410 Xe-141 8.60290E-03 8.71020E-03 541410 + 634 541420 Xe-142 3.58590E-03 3.59480E-03 541420 + 635 541430 Xe-143 5.30400E-04 5.30460E-04 541430 + 636 541440 Xe-144 1.06200E-04 1.06200E-04 541440 + 637 541450 Xe-145 5.81890E-06 5.81890E-06 541450 + 638 541460 Xe-146 9.16600E-09 9.16600E-09 541460 + 639 551330 Cs-133 3.69600E-09 5.34610E-02 55133.82c + 640 551340 Cs-134 1.04180E-07 1.96410E-07 55134.82c + 641 551341 Cs-134m 9.22340E-08 9.22340E-08 551341 + 642 551350 Cs-135 6.47690E-06 6.97320E-02 55135.82c + 643 551351 Cs-135m 4.79310E-06 4.79310E-06 551351 + 644 551360 Cs-136 9.18090E-05 1.24630E-04 55136.82c + 645 551361 Cs-136m 6.56410E-05 6.56410E-05 551361 + 646 551370 Cs-137 2.22990E-03 7.42240E-02 55137.82c + 647 551380 Cs-138 2.82230E-03 7.61200E-02 551380 + 648 551381 Cs-138m 4.71990E-03 4.71990E-03 551381 + 649 551390 Cs-139 2.08370E-02 5.61280E-02 551390 + 650 551400 Cs-140 2.15790E-02 4.94020E-02 551400 + 651 551410 Cs-141 3.10640E-02 3.97830E-02 551410 + 652 551420 Cs-142 1.52270E-02 1.88140E-02 551420 + 653 551430 Cs-143 1.07090E-02 1.12370E-02 551430 + 654 551440 Cs-144 1.66660E-03 2.60310E-03 551440 + 655 551441 Cs-144m 1.66660E-03 1.66680E-03 551441 + 656 551450 Cs-145 7.84250E-04 7.89780E-04 551450 + 657 551460 Cs-146 1.01600E-04 1.01610E-04 551460 + 658 551470 Cs-147 1.14610E-05 1.14610E-05 551470 + 659 551480 Cs-148 2.45350E-08 2.45350E-08 551480 + 660 551490 Cs-149 3.66420E-10 3.66420E-10 551490 + 661 561360 Ba-136 1.16310E-08 1.57490E-04 56136.82c + 662 561361 Ba-136m 3.17030E-08 3.17030E-08 561361 + 663 561370 Ba-137 5.94140E-06 7.42460E-02 56137.82c + 664 561371 Ba-137m 1.66240E-05 7.00830E-02 561371 + 665 561380 Ba-138 4.26630E-04 7.74430E-02 56138.82c + 666 561390 Ba-139 2.29430E-03 5.84230E-02 561390 + 667 561400 Ba-140 9.54960E-03 5.89520E-02 56140.82c + 668 561410 Ba-141 1.64350E-02 5.62180E-02 561410 + 669 561420 Ba-142 4.10370E-02 6.00350E-02 561420 + 670 561430 Ba-143 3.76840E-02 4.88200E-02 561430 + 671 561440 Ba-144 4.00810E-02 4.35470E-02 561440 + 672 561450 Ba-145 1.41110E-02 1.48020E-02 561450 + 673 561460 Ba-146 7.56480E-03 7.65520E-03 561460 + 674 561470 Ba-147 1.66260E-03 1.67080E-03 561470 + 675 561480 Ba-148 4.31260E-04 4.31280E-04 561480 + 676 561490 Ba-149 4.93760E-05 4.93760E-05 561490 + 677 561500 Ba-150 9.45720E-07 9.45720E-07 561500 + 678 561510 Ba-151 8.78790E-10 8.78790E-10 561510 + 679 571380 La-138 3.33170E-09 3.33170E-09 57138.82c + 680 571390 La-139 2.04710E-06 5.84250E-02 57139.82c + 681 571400 La-140 2.06210E-05 5.89720E-02 57140.82c + 682 571410 La-141 2.60590E-04 5.64790E-02 571410 + 683 571420 La-142 7.80290E-04 6.08160E-02 571420 + 684 571430 La-143 4.14970E-03 5.29700E-02 571430 + 685 571440 La-144 8.78640E-03 5.23330E-02 571440 + 686 571450 La-145 1.67840E-02 3.15860E-02 571450 + 687 571460 La-146 3.51980E-03 1.11750E-02 571460 + 688 571461 La-146m 7.38420E-03 7.38420E-03 571461 + 689 571470 La-147 1.01640E-02 1.18360E-02 571470 + 690 571480 La-148 3.43770E-03 3.86750E-03 571480 + 691 571490 La-149 1.26040E-03 1.30960E-03 571490 + 692 571500 La-150 2.14730E-04 2.15680E-04 571500 + 693 571510 La-151 2.91250E-05 2.91260E-05 571510 + 694 571520 La-152 1.94050E-06 1.94050E-06 571520 + 695 571530 La-153 2.64730E-09 2.64730E-09 571530 + 696 571540 La-154 1.08910E-11 1.08910E-11 571540 + 697 581410 Ce-141 1.96270E-06 5.64810E-02 58141.82c + 698 581420 Ce-142 2.81450E-05 6.08440E-02 58142.82c + 699 581430 Ce-143 1.81790E-04 5.31520E-02 58143.82c + 700 581440 Ce-144 1.06530E-03 5.33990E-02 58144.82c + 701 581450 Ce-145 3.21260E-03 3.47990E-02 581450 + 702 581460 Ce-146 8.97740E-03 2.75370E-02 581460 + 703 581470 Ce-147 1.06940E-02 2.25300E-02 581470 + 704 581480 Ce-148 1.40940E-02 1.79800E-02 581480 + 705 581490 Ce-149 7.11160E-03 8.40870E-03 581490 + 706 581500 Ce-150 4.38690E-03 4.59680E-03 581500 + 707 581510 Ce-151 9.94180E-04 1.02340E-03 581510 + 708 581520 Ce-152 2.82080E-04 2.83900E-04 581520 + 709 581530 Ce-153 3.51710E-05 3.51740E-05 581530 + 710 581540 Ce-154 1.96550E-06 1.96550E-06 581540 + 711 581550 Ce-155 2.10060E-09 2.10060E-09 581550 + 712 581560 Ce-156 3.10600E-11 3.10600E-11 581560 + 713 591430 Pr-143 1.85040E-09 5.31520E-02 59143.82c + 714 591440 Pr-144 8.98850E-08 5.33990E-02 591440 + 715 591441 Pr-144m 9.14410E-07 7.37790E-04 591441 + 716 591450 Pr-145 1.26150E-05 3.48120E-02 591450 + 717 591460 Pr-146 4.67040E-05 2.75830E-02 591460 + 718 591470 Pr-147 2.69020E-04 2.28000E-02 591470 + 719 591480 Pr-148 1.04550E-04 1.80840E-02 591480 + 720 591481 Pr-148m 5.06870E-04 5.06870E-04 591481 + 721 591490 Pr-149 1.77270E-03 1.01810E-02 591490 + 722 591500 Pr-150 1.68880E-03 6.28550E-03 591500 + 723 591510 Pr-151 1.82880E-03 2.85220E-03 591510 + 724 591520 Pr-152 7.33260E-04 1.01740E-03 591520 + 725 591530 Pr-153 3.16970E-04 3.51940E-04 591530 + 726 591540 Pr-154 6.97230E-05 7.16760E-05 591540 + 727 591550 Pr-155 1.18570E-05 1.18590E-05 591550 + 728 591560 Pr-156 7.10300E-08 7.10610E-08 591560 + 729 591570 Pr-157 2.30770E-09 2.30770E-09 591570 + 730 591580 Pr-158 1.57980E-11 1.57980E-11 591580 + 731 601460 Nd-146 9.52000E-07 2.75840E-02 60146.82c + 732 601470 Nd-147 2.86670E-06 2.28020E-02 60147.82c + 733 601480 Nd-148 3.56070E-05 1.86270E-02 60148.82c + 734 601490 Nd-149 1.24940E-04 1.03060E-02 601490 + 735 601500 Nd-150 4.44740E-04 6.73030E-03 60150.82c + 736 601510 Nd-151 6.53590E-04 3.50580E-03 601510 + 737 601520 Nd-152 9.50180E-04 1.96760E-03 601520 + 738 601530 Nd-153 5.88090E-04 9.40030E-04 601530 + 739 601540 Nd-154 3.94200E-04 4.65880E-04 601540 + 740 601550 Nd-155 9.87960E-05 1.10660E-04 601550 + 741 601560 Nd-156 2.27990E-05 2.28680E-05 601560 + 742 601570 Nd-157 5.90540E-06 5.90760E-06 601570 + 743 601580 Nd-158 6.22970E-08 6.23130E-08 601580 + 744 601590 Nd-159 2.19560E-10 2.19560E-10 601590 + 745 601600 Nd-160 5.46210E-11 5.46210E-11 601600 + 746 611480 Pm-148 1.04520E-10 1.18770E-10 61148.82c + 747 611481 Pm-148m 2.84910E-10 2.84910E-10 61548.82c + 748 611490 Pm-149 2.27180E-08 1.03060E-02 61149.82c + 749 611500 Pm-150 3.11150E-07 3.11150E-07 611500 + 750 611510 Pm-151 4.85820E-06 3.51070E-03 61151.82c + 751 611520 Pm-152 1.32760E-06 1.96890E-03 611520 + 752 611521 Pm-152m 2.79110E-06 2.79110E-06 611521 + 753 611522 Pm-152m 3.64590E-06 3.64590E-06 611522 + 754 611530 Pm-153 2.93430E-05 9.69370E-04 611530 + 755 611540 Pm-154 1.96650E-05 4.85540E-04 611540 + 756 611541 Pm-154m 1.96650E-05 1.96650E-05 611541 + 757 611550 Pm-155 4.25110E-05 1.53170E-04 611550 + 758 611560 Pm-156 2.67710E-05 4.96390E-05 611560 + 759 611570 Pm-157 9.84270E-06 1.57500E-05 611570 + 760 611580 Pm-158 9.90600E-07 1.05290E-06 611580 + 761 611590 Pm-159 6.64350E-08 6.66550E-08 611590 + 762 611600 Pm-160 2.61270E-08 2.61810E-08 611600 + 763 611610 Pm-161 9.37900E-10 9.37900E-10 611610 + 764 611620 Pm-162 1.37750E-11 1.37750E-11 611620 + 765 621510 Sm-151 7.03030E-10 3.51070E-03 62151.82c + 766 621520 Sm-152 2.93320E-08 1.97540E-03 62152.82c + 767 621530 Sm-153 5.90580E-08 9.69590E-04 62153.82c + 768 621531 Sm-153m 1.65240E-07 1.65240E-07 621531 + 769 621540 Sm-154 2.94860E-06 5.08160E-04 62154.82c + 770 621550 Sm-155 7.90750E-06 1.61080E-04 621550 + 771 621560 Sm-156 1.28920E-05 6.25310E-05 621560 + 772 621570 Sm-157 5.90610E-06 2.16560E-05 621570 + 773 621580 Sm-158 5.94390E-06 6.99680E-06 621580 + 774 621590 Sm-159 3.32660E-07 3.99370E-07 621590 + 775 621600 Sm-160 2.10900E-06 2.13510E-06 621600 + 776 621610 Sm-161 6.66780E-08 6.76160E-08 621610 + 777 621620 Sm-162 1.13200E-08 1.13340E-08 621620 + 778 621630 Sm-163 3.81660E-10 3.81660E-10 621630 + 779 621640 Sm-164 1.60190E-11 1.60190E-11 621640 + 780 631530 Eu-153 3.43800E-11 9.69590E-04 63153.82c + 781 631540 Eu-154 2.67280E-10 5.55450E-10 63154.82c + 782 631541 Eu-154m 2.88170E-10 2.88170E-10 631541 + 783 631550 Eu-155 1.03130E-08 1.61090E-04 63155.82c + 784 631560 Eu-156 4.68860E-08 6.25780E-05 63156.82c + 785 631570 Eu-157 2.89760E-07 2.19460E-05 63157.82c + 786 631580 Eu-158 9.90620E-07 7.98740E-06 631580 + 787 631590 Eu-159 5.98760E-07 9.98130E-07 631590 + 788 631600 Eu-160 7.78600E-07 2.91370E-06 631600 + 789 631610 Eu-161 3.54090E-07 4.21710E-07 631610 + 790 631620 Eu-162 7.54760E-08 8.68100E-08 631620 + 791 631630 Eu-163 2.62600E-08 2.66420E-08 631630 + 792 631640 Eu-164 1.64030E-09 1.65630E-09 631640 + 793 631650 Eu-165 2.26920E-10 2.26920E-10 631650 + 794 631660 Eu-166 6.23450E-12 6.23450E-12 631660 + 795 641560 Gd-156 1.55300E-11 6.25780E-05 64156.82c + 796 641570 Gd-157 1.61510E-10 2.19460E-05 64157.82c + 797 641580 Gd-158 2.60160E-09 7.99000E-06 64158.82c + 798 641590 Gd-159 1.74030E-09 9.99870E-07 641590 + 799 641600 Gd-160 8.31310E-08 2.99680E-06 64160.82c + 800 641610 Gd-161 4.85780E-08 4.70280E-07 641610 + 801 641620 Gd-162 9.25440E-08 1.79350E-07 641620 + 802 641630 Gd-163 3.73090E-08 6.39510E-08 641630 + 803 641640 Gd-164 2.11060E-08 2.27620E-08 641640 + 804 641650 Gd-165 3.82420E-09 4.05110E-09 641650 + 805 641660 Gd-166 1.12880E-09 1.13500E-09 641660 + 806 641670 Gd-167 5.88130E-11 5.88130E-11 641670 + 807 641680 Gd-168 5.04870E-12 5.04870E-12 641680 + 808 651600 Tb-160 6.86680E-11 6.86680E-11 65160.82c + 809 651610 Tb-161 4.70700E-10 4.70750E-07 651610 + 810 651620 Tb-162 1.31430E-09 1.80670E-07 651620 + 811 651630 Tb-163 5.36530E-09 6.93160E-08 651630 + 812 651640 Tb-164 3.74530E-09 2.65080E-08 651640 + 813 651650 Tb-165 5.94110E-09 9.99220E-09 651650 + 814 651660 Tb-166 2.05490E-09 3.18990E-09 651660 + 815 651670 Tb-167 1.00540E-09 1.06420E-09 651670 + 816 651680 Tb-168 1.18010E-10 1.23060E-10 651680 + 817 651690 Tb-169 2.97640E-11 2.97640E-11 651690 + 818 651700 Tb-170 1.22630E-12 1.22630E-12 651700 + 819 661620 Dy-162 1.85740E-12 1.80670E-07 66162.82c + 820 661630 Dy-163 1.21160E-11 6.93280E-08 66163.82c + 821 661640 Dy-164 9.65340E-11 2.66040E-08 66164.82c + 822 661650 Dy-165 1.90750E-10 1.02080E-08 661650 + 823 661651 Dy-165m 2.53980E-11 2.53980E-11 661651 + 824 661660 Dy-166 7.25070E-10 3.91500E-09 661660 + 825 661670 Dy-167 4.23380E-10 1.48760E-09 661670 + 826 661680 Dy-168 4.32410E-10 5.55470E-10 661680 + 827 661690 Dy-169 1.31030E-10 1.60790E-10 661690 + 828 661700 Dy-170 5.28630E-11 5.40890E-11 661700 + 829 661710 Dy-171 5.19300E-12 5.19300E-12 661710 + 830 671660 Ho-166 6.38550E-13 3.91560E-09 671660 + 831 671661 Ho-166m 1.74060E-12 1.74060E-12 671661 + 832 671670 Ho-167 1.53550E-11 1.50300E-09 671670 + 833 671680 Ho-168 7.94730E-12 5.76640E-10 671680 + 834 671681 Ho-168m 1.32910E-11 1.32910E-11 671681 + 835 671690 Ho-169 5.99100E-11 2.20700E-10 671690 + 836 671700 Ho-170 2.06410E-11 2.06410E-11 671700 + 837 671701 Ho-170m 7.57240E-12 6.16620E-11 671701 + 838 671710 Ho-171 2.43480E-11 2.95410E-11 671710 + 839 671720 Ho-172 5.50610E-12 5.50610E-12 671720 + 840 671730 Ho-173 1.97180E-12 1.97180E-12 671730 + 841 681700 Er-170 2.62710E-12 8.49290E-11 68170.82c + 842 681710 Er-171 2.94080E-12 3.24820E-11 681710 + 843 681720 Er-172 5.98110E-12 1.14870E-11 681720 + 844 681730 Er-173 2.48090E-12 4.45270E-12 681730 + 845 681740 Er-174 1.47360E-12 1.47360E-12 681740 + + Nuclide 92235.82c -- uranium 235 (U-235) + + Neutron-induced fission: + + Interpolation region : 1 / 3 + Interpolation energy : 2.53000E-08 MeV + Number of products : 873 / 983 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 1.71100E-05 1.71100E-05 1001.82c + 2 10020 H-2 8.40000E-06 8.40000E-06 1002.82c + 3 10030 H-3 1.08000E-04 1.08000E-04 1003.82c + 4 20040 He-4 1.70000E-03 1.70210E-03 2004.82c + 5 20060 He-6 2.66800E-05 2.66800E-05 20060 + 6 30080 Li-8 7.29200E-07 7.29200E-07 30080 + 7 30090 Li-9 4.07100E-07 4.07100E-07 30090 + 8 40080 Be-8 7.29200E-07 1.34180E-06 40080 + 9 40090 Be-9 4.07100E-07 6.12680E-07 4009.82c + 10 40100 Be-10 5.20100E-06 5.20100E-06 40100 + 11 40120 Be-12 1.26100E-07 1.26100E-07 40120 + 12 50090 B-9 4.07100E-07 4.07100E-07 50090 + 13 50100 B-10 5.20100E-06 5.20100E-06 5010.82c + 14 50120 B-12 1.26100E-07 2.52200E-07 50120 + 15 60140 C-14 1.57800E-06 1.57800E-06 60140 + 16 60150 C-15 2.52800E-07 2.52800E-07 60150 + 17 100210 Ne-21 2.14600E-06 2.14600E-06 100210 + 18 220560 Ti-56 1.01040E-12 1.01040E-12 220560 + 19 230560 V-56 1.31210E-12 2.32250E-12 230560 + 20 230570 V-57 4.17090E-12 4.17090E-12 230570 + 21 230580 V-58 3.49080E-12 3.49080E-12 230580 + 22 230590 V-59 5.78070E-12 5.78070E-12 230590 + 23 230600 V-60 1.48530E-12 1.48530E-12 230600 + 24 240570 Cr-57 1.02360E-12 7.97050E-12 240570 + 25 240580 Cr-58 7.88200E-12 8.58020E-12 240580 + 26 240590 Cr-59 1.47600E-11 2.05410E-11 240590 + 27 240600 Cr-60 3.79930E-11 3.94780E-11 240600 + 28 240610 Cr-61 2.53250E-11 2.53250E-11 240610 + 29 240620 Cr-62 3.39050E-11 3.39050E-11 240620 + 30 240630 Cr-63 7.36830E-12 7.36830E-12 240630 + 31 240640 Cr-64 2.48330E-12 2.48330E-12 240640 + 32 250590 Mn-59 4.62960E-12 2.51700E-11 250590 + 33 250600 Mn-60 1.37700E-12 4.22620E-11 250600 + 34 250601 Mn-60m 1.22300E-11 1.22300E-11 250601 + 35 250610 Mn-61 8.32000E-11 1.08520E-10 250610 + 36 250620 Mn-62 1.09690E-10 1.26640E-10 250620 + 37 250621 Mn-62m 1.96920E-11 3.66440E-11 250621 + 38 250630 Mn-63 2.93570E-10 3.00940E-10 250630 + 39 250640 Mn-64 1.37240E-10 1.39720E-10 250640 + 40 250650 Mn-65 1.48780E-10 1.48780E-10 250650 + 41 250660 Mn-66 2.73720E-11 2.73720E-11 250660 + 42 250670 Mn-67 7.11780E-12 7.11780E-12 250670 + 43 260610 Fe-61 5.26970E-12 1.13800E-10 260610 + 44 260620 Fe-62 8.02440E-11 2.43530E-10 260620 + 45 260630 Fe-63 2.03800E-10 5.04740E-10 260630 + 46 260640 Fe-64 8.83860E-10 1.02360E-09 260640 + 47 260650 Fe-65 1.15340E-09 1.30220E-09 260650 + 48 260660 Fe-66 2.31060E-09 2.33800E-09 260660 + 49 260670 Fe-67 8.62940E-10 8.70060E-10 260670 + 50 260680 Fe-68 6.60880E-10 6.60880E-10 260680 + 51 260690 Fe-69 1.03850E-10 1.03850E-10 260690 + 52 260700 Fe-70 1.99300E-11 1.99300E-11 260700 + 53 270630 Co-63 1.56330E-11 5.20370E-10 270630 + 54 270640 Co-64 8.46230E-11 1.10820E-09 270640 + 55 270650 Co-65 1.04630E-09 2.34850E-09 270650 + 56 270660 Co-66 2.33090E-09 4.66890E-09 270660 + 57 270670 Co-67 8.27360E-09 9.14370E-09 270670 + 58 270680 Co-68 4.22080E-09 6.41660E-09 270680 + 59 270681 Co-68m 3.72350E-09 4.39160E-09 270681 + 60 270690 Co-69 1.41440E-08 1.42410E-08 270690 + 61 270700 Co-70 2.00900E-09 2.00900E-09 270700 + 62 270701 Co-70m 2.00900E-09 2.02890E-09 270701 + 63 270710 Co-71 2.37290E-09 2.37290E-09 270710 + 64 270720 Co-72 3.02930E-10 3.02930E-10 270720 + 65 270730 Co-73 4.63620E-11 4.63620E-11 270730 + 66 270740 Co-74 2.40200E-12 2.40200E-12 270740 + 67 280650 Ni-65 1.52990E-11 2.36380E-09 280650 + 68 280660 Ni-66 3.69460E-10 5.03830E-09 280660 + 69 280670 Ni-67 1.57200E-09 1.07160E-08 280670 + 70 280680 Ni-68 1.39780E-08 2.27330E-08 280680 + 71 280690 Ni-69 1.39500E-08 2.80480E-08 280690 + 72 280691 Ni-69m 1.39500E-08 1.39500E-08 280691 + 73 280700 Ni-70 7.79170E-08 8.19550E-08 280700 + 74 280710 Ni-71 6.01760E-08 6.25490E-08 280710 + 75 280720 Ni-72 9.02260E-08 9.05290E-08 280720 + 76 280730 Ni-73 2.09680E-08 2.10140E-08 280730 + 77 280740 Ni-74 1.41310E-08 1.41330E-08 280740 + 78 280750 Ni-75 1.00690E-09 1.00690E-09 280750 + 79 280760 Ni-76 5.14040E-10 5.14040E-10 280760 + 80 280770 Ni-77 1.21280E-11 1.21280E-11 280770 + 81 290670 Cu-67 2.63490E-11 1.07420E-08 290670 + 82 290680 Cu-68 9.68360E-11 2.30200E-08 290680 + 83 290681 Cu-68m 2.26810E-10 2.26810E-10 290681 + 84 290690 Cu-69 6.71390E-09 4.87110E-08 290690 + 85 290700 Cu-70 1.65190E-09 1.29440E-08 290700 + 86 290701 Cu-70m 1.84030E-08 2.25830E-08 290701 + 87 290702 Cu-70m 1.65190E-09 8.36070E-08 290702 + 88 290710 Cu-71 1.53720E-07 2.16270E-07 290710 + 89 290720 Cu-72 2.63930E-07 3.54460E-07 290720 + 90 290730 Cu-73 6.27620E-07 6.48630E-07 290730 + 91 290740 Cu-74 6.40030E-07 6.54180E-07 290740 + 92 290750 Cu-75 4.97490E-07 4.98480E-07 290750 + 93 290760 Cu-76 1.96910E-07 1.97170E-07 290760 + 94 290761 Cu-76m 1.96910E-07 1.97170E-07 290761 + 95 290770 Cu-77 1.12840E-07 1.12850E-07 290770 + 96 290780 Cu-78 8.73600E-09 8.73600E-09 290780 + 97 290790 Cu-79 1.06310E-09 1.06310E-09 290790 + 98 290800 Cu-80 3.39210E-11 3.39210E-11 290800 + 99 300690 Zn-69 3.83770E-12 4.87320E-08 300690 + 100 300691 Zn-69m 1.65970E-11 1.65970E-11 300691 + 101 300700 Zn-70 7.85580E-10 1.04450E-07 300700 + 102 300710 Zn-71 1.38760E-09 2.17660E-07 300710 + 103 300711 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1.47490E-04 6.13990E-02 42099.82c + 340 421000 Mo-100 9.66880E-04 6.25490E-02 42100.82c + 341 421010 Mo-101 2.80510E-03 5.17820E-02 421010 + 342 421020 Mo-102 7.04180E-03 4.28530E-02 421020 + 343 421030 Mo-103 9.16260E-03 3.08170E-02 421030 + 344 421040 Mo-104 1.05210E-02 1.82460E-02 421040 + 345 421050 Mo-105 6.21270E-03 8.60100E-03 421050 + 346 421060 Mo-106 3.07740E-03 3.39700E-03 421060 + 347 421070 Mo-107 6.58610E-04 7.05950E-04 421070 + 348 421080 Mo-108 1.56480E-04 1.61220E-04 421080 + 349 421090 Mo-109 3.48130E-05 3.62020E-05 421090 + 350 421100 Mo-110 3.61460E-06 3.61460E-06 421100 + 351 421110 Mo-111 1.64380E-08 1.64380E-08 421110 + 352 421120 Mo-112 5.18850E-10 5.18850E-10 421120 + 353 421130 Mo-113 7.52280E-12 7.52280E-12 421130 + 354 431000 Tc-100 1.07410E-08 1.07410E-08 431000 + 355 431010 Tc-101 1.07590E-05 5.17930E-02 431010 + 356 431020 Tc-102 4.18080E-05 4.28950E-02 431020 + 357 431021 Tc-102m 4.18080E-05 4.18080E-05 431021 + 358 431030 Tc-103 2.97550E-04 3.11140E-02 431030 + 359 431040 Tc-104 5.62140E-04 1.88080E-02 431040 + 360 431050 Tc-105 8.45760E-04 9.44680E-03 431050 + 361 431060 Tc-106 6.44680E-04 4.04170E-03 431060 + 362 431070 Tc-107 6.13280E-04 1.31920E-03 431070 + 363 431080 Tc-108 3.19460E-04 4.80870E-04 431080 + 364 431090 Tc-109 1.54520E-04 1.90530E-04 431090 + 365 431100 Tc-110 9.08310E-05 9.44460E-05 431100 + 366 431110 Tc-111 3.67140E-05 3.67300E-05 431110 + 367 431120 Tc-112 4.35940E-06 4.35990E-06 431120 + 368 431130 Tc-113 1.48820E-06 1.48820E-06 431130 + 369 431140 Tc-114 1.05880E-06 1.05880E-06 431140 + 370 431150 Tc-115 8.42590E-11 8.42590E-11 431150 + 371 441020 Ru-102 2.30620E-06 4.29390E-02 44102.82c + 372 441030 Ru-103 1.03720E-06 3.11180E-02 44103.82c + 373 441031 Ru-103m 2.50410E-06 2.50410E-06 441031 + 374 441040 Ru-104 2.37220E-05 1.88320E-02 44104.82c + 375 441050 Ru-105 4.13410E-05 9.48810E-03 44105.82c + 376 441060 Ru-106 5.40910E-05 4.09580E-03 44106.82c + 377 441070 Ru-107 6.79620E-05 1.38720E-03 441070 + 378 441080 Ru-108 8.36350E-05 5.64650E-04 441080 + 379 441090 Ru-109 8.94480E-05 2.79860E-04 441090 + 380 441100 Ru-110 1.40280E-04 2.34690E-04 441100 + 381 441110 Ru-111 1.11450E-04 1.48250E-04 441110 + 382 441120 Ru-112 7.15240E-05 7.59250E-05 441120 + 383 441130 Ru-113 2.03290E-05 3.19440E-05 441130 + 384 441131 Ru-113m 2.03290E-05 2.03290E-05 441131 + 385 441140 Ru-114 1.92080E-05 2.01980E-05 441140 + 386 441150 Ru-115 3.79540E-06 3.79550E-06 441150 + 387 441160 Ru-116 2.70030E-06 2.70030E-06 441160 + 388 441170 Ru-117 5.00590E-10 5.00590E-10 441170 + 389 441180 Ru-118 1.78750E-11 1.78750E-11 441180 + 390 441190 Ru-119 6.64460E-08 6.64460E-08 441190 + 391 441200 Ru-120 5.36150E-09 5.36150E-09 441200 + 392 451050 Rh-105 1.35750E-09 9.48810E-03 45105.82c + 393 451051 Rh-105m 2.07520E-10 2.69350E-03 451051 + 394 451060 Rh-106 5.25330E-09 4.09580E-03 451060 + 395 451061 Rh-106m 1.23050E-08 1.23050E-08 451061 + 396 451070 Rh-107 3.14810E-07 1.38750E-03 451070 + 397 451080 Rh-108 8.88500E-07 5.65540E-04 451080 + 398 451081 Rh-108m 2.68120E-06 2.68120E-06 451081 + 399 451090 Rh-109 4.71060E-06 2.84570E-04 451090 + 400 451100 Rh-110 1.20300E-05 2.46720E-04 451100 + 401 451101 Rh-110m 3.21130E-07 3.21130E-07 451101 + 402 451110 Rh-111 4.13650E-05 1.89610E-04 451110 + 403 451120 Rh-112 1.64630E-05 9.23880E-05 451120 + 404 451121 Rh-112m 1.64630E-05 1.64630E-05 451121 + 405 451130 Rh-113 8.83520E-05 1.30460E-04 451130 + 406 451140 Rh-114 2.44160E-05 4.46220E-05 451140 + 407 451141 Rh-114m 2.44160E-05 2.44160E-05 451141 + 408 451150 Rh-115 5.07870E-05 5.46030E-05 451150 + 409 451160 Rh-116 5.28240E-06 7.95350E-06 451160 + 410 451161 Rh-116m 1.23730E-05 1.23730E-05 451161 + 411 451170 Rh-117 7.60840E-06 7.60890E-06 451170 + 412 451180 Rh-118 3.97750E-06 3.98040E-06 451180 + 413 451190 Rh-119 2.00220E-05 2.00860E-05 451190 + 414 451200 Rh-120 2.48180E-06 2.48720E-06 451200 + 415 451210 Rh-121 3.82360E-07 3.82360E-07 451210 + 416 451220 Rh-122 1.80850E-08 1.80850E-08 451220 + 417 461080 Pd-108 6.47570E-10 5.68230E-04 46108.82c + 418 461090 Pd-109 2.72160E-09 2.84580E-04 461090 + 419 461091 Pd-109m 5.11490E-09 1.42290E-04 461091 + 420 461100 Pd-110 2.54160E-07 2.47290E-04 46110.82c + 421 461110 Pd-111 2.45700E-06 1.95230E-04 461110 + 422 461111 Pd-111m 4.61770E-06 5.37610E-06 461111 + 423 461120 Pd-112 8.54250E-06 1.17390E-04 461120 + 424 461130 Pd-113 7.69300E-06 1.56730E-04 461130 + 425 461131 Pd-113m 1.85720E-05 1.85720E-05 461131 + 426 461140 Pd-114 5.78560E-05 1.26890E-04 461140 + 427 461150 Pd-115 1.88160E-05 6.89540E-05 461150 + 428 461151 Pd-115m 3.53620E-05 4.32900E-05 461151 + 429 461160 Pd-116 1.19790E-04 1.40120E-04 461160 + 430 461170 Pd-117 2.32720E-05 7.47340E-05 461170 + 431 461171 Pd-117m 4.37370E-05 4.37370E-05 461171 + 432 461180 Pd-118 7.26310E-05 7.64950E-05 461180 + 433 461190 Pd-119 2.53810E-05 4.56140E-05 461190 + 434 461200 Pd-120 1.37120E-05 1.61040E-05 461200 + 435 461210 Pd-121 1.32190E-06 1.65240E-06 461210 + 436 461220 Pd-122 1.28190E-05 1.28370E-05 461220 + 437 461230 Pd-123 9.06310E-07 9.06310E-07 461230 + 438 461240 Pd-124 2.25040E-07 2.25040E-07 461240 + 439 471100 Ag-110 5.12110E-12 5.28420E-12 471100 + 440 471101 Ag-110m 1.19950E-11 1.19950E-11 47510.82c + 441 471110 Ag-111 1.64620E-10 1.95710E-04 47111.82c + 442 471111 Ag-111m 1.07690E-09 1.94890E-04 471111 + 443 471120 Ag-112 1.26220E-08 1.17410E-04 471120 + 444 471130 Ag-113 1.96060E-07 1.03720E-04 471130 + 445 471131 Ag-113m 1.28250E-06 1.51360E-04 471131 + 446 471140 Ag-114 2.02470E-07 1.27950E-04 471140 + 447 471141 Ag-114m 8.51530E-07 8.51530E-07 471141 + 448 471150 Ag-115 5.00500E-07 6.37980E-05 471150 + 449 471151 Ag-115m 3.27400E-06 6.17190E-05 471151 + 450 471160 Ag-116 4.79620E-06 1.45590E-04 471160 + 451 471161 Ag-116m 1.12340E-05 1.12340E-05 471161 + 452 471170 Ag-117 6.68650E-06 4.89200E-05 471170 + 453 471171 Ag-117m 4.37390E-05 8.11070E-05 471171 + 454 471180 Ag-118 9.58620E-06 9.61590E-05 471180 + 455 471181 Ag-118m 4.03160E-05 5.12510E-05 471181 + 456 471190 Ag-119 1.04430E-05 3.32500E-05 471190 + 457 471191 Ag-119m 6.83140E-05 9.11210E-05 471191 + 458 471200 Ag-120 2.22150E-05 4.49140E-05 471200 + 459 471201 Ag-120m 3.15230E-05 3.95740E-05 471201 + 460 471210 Ag-121 2.95910E-05 3.12390E-05 471210 + 461 471220 Ag-122 7.27180E-06 2.01090E-05 471220 + 462 471221 Ag-122m 6.55020E-06 6.55020E-06 471221 + 463 471230 Ag-123 2.57000E-06 3.47630E-06 471230 + 464 471240 Ag-124 3.57290E-06 5.40710E-06 471240 + 465 471241 Ag-124m 3.21830E-06 3.21830E-06 471241 + 466 471250 Ag-125 3.48300E-06 3.48300E-06 471250 + 467 471260 Ag-126 1.36730E-06 1.36730E-06 471260 + 468 471270 Ag-127 9.35480E-07 9.35480E-07 471270 + 469 471280 Ag-128 1.58900E-08 1.58900E-08 471280 + 470 471290 Ag-129 9.91810E-10 9.91810E-10 471290 + 471 481130 Cd-113 1.76110E-11 1.56410E-04 48113.82c + 472 481131 Cd-113m 5.76170E-11 1.79320E-06 481131 + 473 481140 Cd-114 4.18260E-09 1.27950E-04 48114.82c + 474 481150 Cd-115 1.13480E-08 1.07470E-04 481150 + 475 481151 Cd-115m 3.71280E-08 5.13290E-06 48515.82c + 476 481160 Cd-116 2.68620E-06 1.58830E-04 48116.82c + 477 481170 Cd-117 6.63560E-07 9.86570E-05 481170 + 478 481171 Cd-117m 2.17090E-06 2.93380E-05 481171 + 479 481180 Cd-118 2.22220E-05 1.48620E-04 481180 + 480 481190 Cd-119 9.78080E-06 1.17530E-04 481190 + 481 481191 Cd-119m 2.36120E-05 4.02380E-05 481191 + 482 481200 Cd-120 7.78530E-05 1.47700E-04 481200 + 483 481210 Cd-121 2.43160E-05 5.22910E-05 481210 + 484 481211 Cd-121m 5.87030E-05 6.19670E-05 481211 + 485 481220 Cd-122 1.22640E-04 1.49300E-04 481220 + 486 481230 Cd-123 2.04400E-05 2.32870E-05 481230 + 487 481231 Cd-123m 4.93450E-05 4.99800E-05 481231 + 488 481240 Cd-124 1.27820E-04 1.34830E-04 481240 + 489 481250 Cd-125 3.47350E-05 3.64770E-05 481250 + 490 481251 Cd-125m 8.38550E-05 8.55970E-05 481251 + 491 481260 Cd-126 1.88760E-04 1.90130E-04 481260 + 492 481270 Cd-127 1.47720E-04 1.48660E-04 481270 + 493 481280 Cd-128 8.75240E-05 8.75400E-05 481280 + 494 481290 Cd-129 8.49530E-06 8.49580E-06 481290 + 495 481291 Cd-129m 2.05090E-05 2.05090E-05 481291 + 496 481300 Cd-130 1.11330E-05 1.11330E-05 481300 + 497 481310 Cd-131 2.11000E-08 2.11000E-08 481310 + 498 491150 In-115 6.84350E-12 1.07230E-04 49115.82c + 499 491151 In-115m 1.58240E-12 1.07470E-04 491151 + 500 491160 In-116 9.69440E-11 9.69440E-11 491160 + 501 491161 In-116m 1.48590E-10 2.92510E-10 491161 + 502 491162 In-116m 1.43920E-10 1.43920E-10 491162 + 503 491170 In-117 1.35430E-08 7.99460E-05 491170 + 504 491171 In-117m 3.13140E-09 9.08610E-05 491171 + 505 491180 In-118 4.87990E-08 1.48670E-04 491180 + 506 491181 In-118m 7.47970E-08 1.46230E-07 491181 + 507 491182 In-118m 7.24440E-08 7.24440E-08 491182 + 508 491190 In-119 7.15080E-11 5.75220E-05 491190 + 509 491191 In-119m 1.65340E-11 1.06190E-04 491191 + 510 491200 In-120 1.78470E-06 1.49480E-04 491200 + 511 491201 In-120m 1.78470E-06 1.78470E-06 491201 + 512 491202 In-120m 1.78470E-06 1.78470E-06 491202 + 513 491210 In-121 1.03400E-05 9.03630E-05 491210 + 514 491211 In-121m 2.39090E-06 3.70700E-05 491211 + 515 491220 In-122 1.29600E-05 1.62260E-04 491220 + 516 491221 In-122m 9.19500E-06 9.19500E-06 491221 + 517 491222 In-122m 9.19500E-06 9.19500E-06 491222 + 518 491230 In-123 4.73270E-05 1.03910E-04 491230 + 519 491231 In-123m 1.09430E-05 2.76270E-05 491231 + 520 491240 In-124 3.94130E-05 1.74240E-04 491240 + 521 491241 In-124m 3.55030E-05 3.55030E-05 491241 + 522 491250 In-125 1.05530E-04 2.08590E-04 491250 + 523 491251 In-125m 2.44010E-05 4.34180E-05 491251 + 524 491260 In-126 1.12880E-04 3.03000E-04 491260 + 525 491261 In-126m 1.01680E-04 1.01680E-04 491261 + 526 491270 In-127 4.33250E-04 4.33250E-04 491270 + 527 491271 In-127m 1.00180E-04 2.48830E-04 491271 + 528 491280 In-128 2.96820E-04 5.05180E-04 491280 + 529 491281 In-128m 1.20820E-04 2.08360E-04 491281 + 530 491282 In-128m 3.76200E-04 3.76200E-04 491282 + 531 491290 In-129 8.12190E-04 8.32900E-04 491290 + 532 491291 In-129m 1.87800E-04 1.96490E-04 491291 + 533 491300 In-130 1.48660E-04 1.59400E-04 491300 + 534 491301 In-130m 1.66040E-04 1.66040E-04 491301 + 535 491302 In-130m 2.82500E-04 2.82500E-04 491302 + 536 491310 In-131 6.77270E-05 6.84360E-05 491310 + 537 491311 In-131m 6.77270E-05 6.77270E-05 491311 + 538 491312 In-131m 6.77270E-05 6.77270E-05 491312 + 539 491320 In-132 1.06030E-05 1.06030E-05 491320 + 540 491330 In-133 4.66630E-07 5.74530E-07 491330 + 541 491331 In-133m 1.07900E-07 1.07900E-07 491331 + 542 491340 In-134 6.95940E-09 6.95940E-09 491340 + 543 501180 Sn-118 7.74560E-11 1.48820E-04 50118.82c + 544 501210 Sn-121 1.74380E-12 1.24700E-04 501210 + 545 501211 Sn-121m 4.20970E-12 1.02370E-05 501211 + 546 501220 Sn-122 3.38120E-06 1.84030E-04 50122.82c + 547 501230 Sn-123 4.47710E-06 1.23990E-05 50123.82c + 548 501231 Sn-123m 1.85460E-06 1.25470E-04 501231 + 549 501240 Sn-124 3.96920E-05 2.49440E-04 50124.82c + 550 501250 Sn-125 3.35940E-05 6.88280E-05 50125.82c + 551 501251 Sn-125m 1.39150E-05 2.30680E-04 501251 + 552 501260 Sn-126 1.70550E-04 5.76940E-04 50126.82c + 553 501270 Sn-127 3.74830E-04 5.43700E-04 501270 + 554 501271 Sn-127m 1.55260E-04 6.66760E-04 501271 + 555 501280 Sn-128 6.76400E-04 3.14210E-03 501280 + 556 501281 Sn-128m 1.58430E-03 1.96050E-03 501281 + 557 501290 Sn-129 1.68520E-03 2.62600E-03 501290 + 558 501291 Sn-129m 4.06830E-03 4.15700E-03 501291 + 559 501300 Sn-130 3.64580E-03 4.04220E-03 501300 + 560 501301 Sn-130m 8.53920E-03 8.75210E-03 501301 + 561 501310 Sn-131 3.33090E-03 3.46210E-03 501310 + 562 501311 Sn-131m 8.04110E-03 8.11180E-03 501311 + 563 501320 Sn-132 7.36720E-03 7.37830E-03 501320 + 564 501330 Sn-133 9.58620E-04 9.58710E-04 501330 + 565 501340 Sn-134 1.08880E-04 1.08880E-04 501340 + 566 501350 Sn-135 9.90980E-06 9.90980E-06 501350 + 567 501360 Sn-136 8.92730E-07 8.92730E-07 501360 + 568 511240 Sb-124 2.68920E-11 6.31710E-11 51124.82c + 569 511241 Sb-124m 2.05620E-11 4.83720E-11 511241 + 570 511242 Sb-124m 2.78100E-11 2.78100E-11 511242 + 571 511250 Sb-125 3.44320E-06 3.02950E-04 51125.82c + 572 511260 Sb-126 3.00310E-06 3.72050E-06 51126.82c + 573 511261 Sb-126m 2.22040E-06 5.12430E-06 511261 + 574 511262 Sb-126m 2.90390E-06 2.90390E-06 511262 + 575 511270 Sb-127 2.87000E-05 1.23920E-03 511270 + 576 511280 Sb-128 7.03340E-05 3.21670E-03 511280 + 577 511281 Sb-128m 1.20020E-04 1.20020E-04 511281 + 578 511290 Sb-129 7.88660E-04 5.87720E-03 511290 + 579 511291 Sb-129m 4.81940E-04 2.56040E-03 511291 + 580 511300 Sb-130 2.53300E-03 1.09510E-02 511300 + 581 511301 Sb-130m 2.53300E-03 6.90900E-03 511301 + 582 511310 Sb-131 1.32970E-02 2.48710E-02 511310 + 583 511320 Sb-132 1.17900E-02 1.91690E-02 511320 + 584 511321 Sb-132m 8.68970E-03 8.68970E-03 511321 + 585 511330 Sb-133 2.41420E-02 2.51190E-02 511330 + 586 511340 Sb-134 1.91940E-03 2.01080E-03 511340 + 587 511341 Sb-134m 4.49570E-03 4.49670E-03 511341 + 588 511350 Sb-135 1.40460E-03 1.41270E-03 511350 + 589 511360 Sb-136 2.14620E-04 2.15250E-04 511360 + 590 511370 Sb-137 2.25880E-05 2.25880E-05 511370 + 591 511380 Sb-138 3.93920E-07 3.93920E-07 511380 + 592 511390 Sb-139 1.21320E-08 1.21320E-08 511390 + 593 521260 Te-126 2.43920E-11 8.12740E-06 52126.82c + 594 521270 Te-127 5.46410E-07 1.23610E-03 521270 + 595 521271 Te-127m 1.31910E-06 2.05530E-04 52527.82c + 596 521280 Te-128 5.41960E-06 3.33780E-03 52128.82c + 597 521290 Te-129 2.45650E-05 6.96810E-03 521290 + 598 521291 Te-129m 5.93040E-05 3.16000E-03 52529.82c + 599 521300 Te-130 8.03010E-04 1.86630E-02 52130.82c + 600 521310 Te-131 1.26240E-03 2.52000E-02 521310 + 601 521311 Te-131m 3.04750E-03 5.03870E-03 521311 + 602 521320 Te-132 1.50420E-02 4.29000E-02 52132.82c + 603 521330 Te-133 1.15360E-02 3.79490E-02 521330 + 604 521331 Te-133m 2.78500E-02 3.21950E-02 521331 + 605 521340 Te-134 6.30010E-02 6.97270E-02 521340 + 606 521350 Te-135 3.47770E-02 3.60030E-02 521350 + 607 521360 Te-136 1.66520E-02 1.68430E-02 521360 + 608 521370 Te-137 4.84400E-03 4.85550E-03 521370 + 609 521380 Te-138 1.12800E-03 1.12840E-03 521380 + 610 521390 Te-139 1.69770E-04 1.69780E-04 521390 + 611 521400 Te-140 2.47710E-05 2.47710E-05 521400 + 612 521410 Te-141 6.06940E-08 6.06940E-08 521410 + 613 521420 Te-142 2.31770E-09 2.31770E-09 521420 + 614 531290 I-129 3.63660E-09 8.13740E-03 53129.82c + 615 531300 I-130 1.51160E-06 2.05360E-06 53130.82c + 616 531301 I-130m 6.45340E-07 6.45340E-07 531301 + 617 531310 I-131 2.96040E-05 2.92100E-02 53131.82c + 618 531320 I-132 1.63490E-04 4.31670E-02 531320 + 619 531321 I-132m 1.20500E-04 1.20500E-04 531321 + 620 531330 I-133 1.23020E-03 6.64910E-02 531330 + 621 531331 I-133m 7.51740E-04 7.51740E-04 531331 + 622 531340 I-134 4.41730E-03 7.73250E-02 531340 + 623 531341 I-134m 3.25570E-03 3.25570E-03 531341 + 624 531350 I-135 2.46350E-02 6.06380E-02 53135.82c + 625 531360 I-136 9.09030E-03 2.60060E-02 531360 + 626 531361 I-136m 2.12920E-02 2.13640E-02 531361 + 627 531370 I-137 2.70260E-02 3.18070E-02 531370 + 628 531380 I-138 1.24190E-02 1.34760E-02 531380 + 629 531390 I-139 7.38460E-03 7.55440E-03 531390 + 630 531400 I-140 1.93130E-03 1.95610E-03 531400 + 631 531410 I-141 4.68430E-04 4.68490E-04 531410 + 632 531420 I-142 4.67730E-05 4.67750E-05 531420 + 633 531430 I-143 4.31870E-06 4.31870E-06 531430 + 634 531440 I-144 7.40820E-09 7.40820E-09 531440 + 635 541310 Xe-131 2.06000E-10 2.92100E-02 54131.82c + 636 541311 Xe-131m 4.97310E-10 3.17280E-04 541311 + 637 541320 Xe-132 1.65400E-06 4.31880E-02 54132.82c + 638 541321 Xe-132m 1.87480E-06 1.87480E-06 541321 + 639 541330 Xe-133 1.24490E-05 6.65340E-02 54133.82c + 640 541331 Xe-133m 3.00530E-05 1.92260E-03 541331 + 641 541340 Xe-134 1.04710E-04 7.77500E-02 54134.82c + 642 541341 Xe-134m 2.45270E-04 3.20150E-04 541341 + 643 541350 Xe-135 7.31220E-04 6.30640E-02 54135.82c + 644 541351 Xe-135m 1.76530E-03 1.17760E-02 541351 + 645 541360 Xe-136 1.60280E-02 6.54650E-02 54136.82c + 646 541370 Xe-137 2.96320E-02 6.00860E-02 541370 + 647 541380 Xe-138 4.98260E-02 6.33280E-02 541380 + 648 541390 Xe-139 4.34330E-02 5.04290E-02 541390 + 649 541400 Xe-140 3.83430E-02 4.02160E-02 541400 + 650 541410 Xe-141 1.94660E-02 1.98480E-02 541410 + 651 541420 Xe-142 6.84910E-03 6.88590E-03 541420 + 652 541430 Xe-143 1.82220E-03 1.82480E-03 541430 + 653 541440 Xe-144 3.15460E-04 3.15460E-04 541440 + 654 541450 Xe-145 3.17270E-05 3.17270E-05 541450 + 655 541460 Xe-146 5.55350E-06 5.55350E-06 541460 + 656 541470 Xe-147 5.38480E-10 5.38480E-10 541470 + 657 551340 Cs-134 1.00160E-08 1.73980E-08 55134.82c + 658 551341 Cs-134m 7.38200E-09 7.38200E-09 551341 + 659 551350 Cs-135 5.59030E-07 6.31350E-02 55135.82c + 660 551351 Cs-135m 3.41620E-07 3.41620E-07 551351 + 661 551360 Cs-136 2.25160E-05 2.91130E-05 55136.82c + 662 551361 Cs-136m 1.31950E-05 1.31950E-05 551361 + 663 551370 Cs-137 8.10950E-04 6.08970E-02 55137.82c + 664 551380 Cs-138 1.39000E-03 6.63160E-02 551380 + 665 551381 Cs-138m 1.97230E-03 1.97230E-03 551381 + 666 551390 Cs-139 1.19490E-02 6.23780E-02 551390 + 667 551400 Cs-140 1.81940E-02 5.84180E-02 551400 + 668 551410 Cs-141 2.90800E-02 4.89440E-02 551410 + 669 551420 Cs-142 2.33290E-02 3.02080E-02 551420 + 670 551430 Cs-143 1.56820E-02 1.74980E-02 551430 + 671 551440 Cs-144 3.43280E-03 5.45630E-03 551440 + 672 551441 Cs-144m 3.43280E-03 3.43350E-03 551441 + 673 551450 Cs-145 1.96810E-03 1.99860E-03 551450 + 674 551460 Cs-146 3.23460E-04 3.28630E-04 551460 + 675 551470 Cs-147 6.65080E-05 6.65090E-05 551470 + 676 551480 Cs-148 2.72070E-06 2.72070E-06 551480 + 677 551490 Cs-149 2.80620E-09 2.80620E-09 551490 + 678 561360 Ba-136 2.67100E-07 3.66040E-05 56136.82c + 679 561361 Ba-136m 6.25610E-07 6.25610E-07 561361 + 680 561370 Ba-137 2.03540E-06 6.09040E-02 56137.82c + 681 561371 Ba-137m 4.91380E-06 5.74920E-02 561371 + 682 561380 Ba-138 1.39440E-04 6.68300E-02 56138.82c + 683 561390 Ba-139 8.53770E-04 6.32320E-02 561390 + 684 561400 Ba-140 5.02540E-03 6.34440E-02 56140.82c + 685 561410 Ba-141 9.59550E-03 5.85390E-02 561410 + 686 561420 Ba-142 2.76210E-02 5.81160E-02 561420 + 687 561430 Ba-143 3.99330E-02 5.73190E-02 561430 + 688 561440 Ba-144 4.14180E-02 4.87020E-02 561440 + 689 561450 Ba-145 2.35530E-02 2.53130E-02 561450 + 690 561460 Ba-146 1.07710E-02 1.10720E-02 561460 + 691 561470 Ba-147 3.88810E-03 3.93630E-03 561470 + 692 561480 Ba-148 8.75120E-04 8.77160E-04 561480 + 693 561490 Ba-149 1.22130E-04 1.22130E-04 561490 + 694 561500 Ba-150 1.05240E-05 1.05240E-05 561500 + 695 561510 Ba-151 6.67960E-09 6.67960E-09 561510 + 696 561520 Ba-152 1.01530E-10 1.01530E-10 561520 + 697 571390 La-139 1.94120E-08 6.32320E-02 57139.82c + 698 571400 La-140 6.46280E-06 6.34500E-02 57140.82c + 699 571410 La-141 1.06780E-04 5.86460E-02 571410 + 700 571420 La-142 3.16290E-04 5.84330E-02 571420 + 701 571430 La-143 2.15620E-03 5.94750E-02 571430 + 702 571440 La-144 5.66650E-03 5.43690E-02 571440 + 703 571450 La-145 1.27090E-02 3.80210E-02 571450 + 704 571460 La-146 4.64060E-03 1.57130E-02 571460 + 705 571461 La-146m 8.34740E-03 8.34740E-03 571461 + 706 571470 La-147 9.46310E-03 1.34030E-02 571470 + 707 571480 La-148 4.70010E-03 5.57430E-03 571480 + 708 571490 La-149 1.86280E-03 1.98440E-03 571490 + 709 571500 La-150 4.87830E-04 4.98350E-04 571500 + 710 571510 La-151 8.65670E-05 8.65740E-05 571510 + 711 571520 La-152 1.13090E-05 1.13090E-05 571520 + 712 571530 La-153 2.20260E-08 2.20260E-08 571530 + 713 571540 La-154 1.30040E-10 1.30040E-10 571540 + 714 581410 Ce-141 1.41150E-09 5.86460E-02 58141.82c + 715 581420 Ce-142 1.09560E-05 5.84440E-02 58142.82c + 716 581430 Ce-143 4.76340E-05 5.95220E-02 58143.82c + 717 581440 Ce-144 4.11930E-04 5.47810E-02 58144.82c + 718 581450 Ce-145 1.53660E-03 3.95580E-02 581450 + 719 581460 Ce-146 5.88910E-03 2.99490E-02 581460 + 720 581470 Ce-147 8.94430E-03 2.23470E-02 581470 + 721 581480 Ce-148 1.09360E-02 1.65380E-02 581480 + 722 581490 Ce-149 7.29820E-03 9.26830E-03 581490 + 723 581500 Ce-150 4.24740E-03 4.73230E-03 581500 + 724 581510 Ce-151 1.78780E-03 1.87510E-03 581510 + 725 581520 Ce-152 5.17680E-04 5.28310E-04 581520 + 726 581530 Ce-153 7.89880E-05 7.90100E-05 581530 + 727 581540 Ce-154 8.37770E-06 8.37780E-06 581540 + 728 581550 Ce-155 1.70060E-08 1.70060E-08 581550 + 729 581560 Ce-156 3.78400E-10 3.78400E-10 581560 + 730 581570 Ce-157 1.56570E-12 1.56570E-12 581570 + 731 591440 Pr-144 7.49710E-10 5.47800E-02 591440 + 732 591441 Pr-144m 6.65850E-09 7.55950E-04 591441 + 733 591450 Pr-145 2.18980E-06 3.95600E-02 591450 + 734 591460 Pr-146 2.00660E-05 2.99690E-02 591460 + 735 591470 Pr-147 1.16710E-04 2.24640E-02 591470 + 736 591480 Pr-148 7.19110E-05 1.66100E-02 591480 + 737 591481 Pr-148m 3.02430E-04 3.02430E-04 591481 + 738 591490 Pr-149 9.61350E-04 1.02300E-02 591490 + 739 591500 Pr-150 1.57350E-03 6.30580E-03 591500 + 740 591510 Pr-151 1.84110E-03 3.71620E-03 591510 + 741 591520 Pr-152 1.06050E-03 1.58930E-03 591520 + 742 591530 Pr-153 4.75120E-04 5.53690E-04 591530 + 743 591540 Pr-154 1.13040E-04 1.21360E-04 591540 + 744 591550 Pr-155 2.61920E-05 2.62090E-05 591550 + 745 591560 Pr-156 2.91610E-06 2.91650E-06 591560 + 746 591570 Pr-157 3.15160E-08 3.15180E-08 591570 + 747 591580 Pr-158 2.15330E-10 2.15330E-10 591580 + 748 591590 Pr-159 3.75590E-12 3.75590E-12 591590 + 749 601460 Nd-146 1.26120E-09 2.99690E-02 60146.82c + 750 601470 Nd-147 9.95240E-07 2.24650E-02 60147.82c + 751 601480 Nd-148 1.46330E-05 1.69270E-02 60148.82c + 752 601490 Nd-149 4.59200E-05 1.02760E-02 601490 + 753 601500 Nd-150 2.31860E-04 6.53770E-03 60150.82c + 754 601510 Nd-151 5.72770E-04 4.28890E-03 601510 + 755 601520 Nd-152 9.43460E-04 2.53280E-03 601520 + 756 601530 Nd-153 8.93360E-04 1.44710E-03 601530 + 757 601540 Nd-154 5.80620E-04 7.01980E-04 601540 + 758 601550 Nd-155 2.42970E-04 2.69260E-04 601550 + 759 601560 Nd-156 8.89850E-05 9.18240E-05 601560 + 760 601570 Nd-157 2.27740E-05 2.28030E-05 601570 + 761 601580 Nd-158 2.99570E-06 2.99590E-06 601580 + 762 601590 Nd-159 1.17210E-08 1.17250E-08 601590 + 763 601600 Nd-160 4.98160E-10 4.98160E-10 601600 + 764 611490 Pm-149 2.00440E-09 1.02760E-02 61149.82c + 765 611500 Pm-150 9.55140E-07 9.55140E-07 611500 + 766 611510 Pm-151 1.07770E-06 4.29000E-03 61151.82c + 767 611520 Pm-152 1.72550E-06 2.53450E-03 611520 + 768 611521 Pm-152m 3.44570E-06 3.44570E-06 611521 + 769 611522 Pm-152m 3.81130E-06 3.81130E-06 611522 + 770 611530 Pm-153 2.03490E-05 1.46740E-03 611530 + 771 611540 Pm-154 1.46980E-05 7.16680E-04 611540 + 772 611541 Pm-154m 1.46980E-05 1.46980E-05 611541 + 773 611550 Pm-155 3.35610E-05 3.02820E-04 611550 + 774 611560 Pm-156 3.49140E-05 1.26740E-04 611560 + 775 611570 Pm-157 2.73810E-05 5.01850E-05 611570 + 776 611580 Pm-158 5.91940E-06 8.91520E-06 611580 + 777 611590 Pm-159 3.04560E-06 3.05730E-06 611590 + 778 611600 Pm-160 1.32870E-07 1.33360E-07 611600 + 779 611610 Pm-161 3.20810E-09 3.20810E-09 611610 + 780 611620 Pm-162 2.03710E-10 2.03710E-10 611620 + 781 611630 Pm-163 5.55700E-12 5.55700E-12 611630 + 782 621510 Sm-151 1.09500E-10 4.29000E-03 62151.82c + 783 621520 Sm-152 3.85810E-09 2.54170E-03 62152.82c + 784 621530 Sm-153 1.40050E-08 1.46740E-03 62153.82c + 785 621531 Sm-153m 3.38100E-08 3.38100E-08 621531 + 786 621540 Sm-154 9.29100E-07 7.32310E-04 62154.82c + 787 621550 Sm-155 8.59820E-06 3.11420E-04 621550 + 788 621560 Sm-156 7.56700E-06 1.34310E-04 621560 + 789 621570 Sm-157 1.57390E-05 6.59240E-05 621570 + 790 621580 Sm-158 1.02930E-05 1.92090E-05 621580 + 791 621590 Sm-159 6.08100E-06 9.13810E-06 621590 + 792 621600 Sm-160 3.49530E-06 3.62830E-06 621600 + 793 621610 Sm-161 4.41010E-07 4.44220E-07 621610 + 794 621620 Sm-162 8.27410E-08 8.29450E-08 621620 + 795 621630 Sm-163 3.52700E-09 3.53260E-09 621630 + 796 621640 Sm-164 2.27180E-10 2.27180E-10 621640 + 797 621650 Sm-165 3.75840E-12 3.75840E-12 621650 + 798 631540 Eu-154 3.04050E-11 5.77940E-11 63154.82c + 799 631541 Eu-154m 2.73890E-11 2.73890E-11 631541 + 800 631550 Eu-155 2.47980E-09 3.11420E-04 63155.82c + 801 631560 Eu-156 1.93130E-08 1.34320E-04 63156.82c + 802 631570 Eu-157 2.60930E-07 6.61850E-05 63157.82c + 803 631580 Eu-158 3.85920E-07 1.95950E-05 631580 + 804 631590 Eu-159 1.49480E-06 1.06330E-05 631590 + 805 631600 Eu-160 6.98530E-07 4.32680E-06 631600 + 806 631610 Eu-161 3.47010E-07 7.91230E-07 631610 + 807 631620 Eu-162 3.15130E-07 3.98070E-07 631620 + 808 631630 Eu-163 1.42570E-07 1.46100E-07 631630 + 809 631640 Eu-164 1.29740E-08 1.32010E-08 631640 + 810 631650 Eu-165 2.68830E-09 2.69210E-09 631650 + 811 631660 Eu-166 9.40870E-11 9.40870E-11 631660 + 812 631670 Eu-167 4.52260E-12 4.52260E-12 631670 + 813 641570 Gd-157 5.01010E-11 6.61850E-05 64157.82c + 814 641580 Gd-158 9.82130E-10 1.95960E-05 64158.82c + 815 641590 Gd-159 5.88260E-09 1.06390E-05 641590 + 816 641600 Gd-160 5.35490E-08 4.38040E-06 64160.82c + 817 641610 Gd-161 2.15950E-08 8.12820E-07 641610 + 818 641620 Gd-162 1.95060E-07 5.93130E-07 641620 + 819 641630 Gd-163 1.00220E-07 2.46320E-07 641630 + 820 641640 Gd-164 8.59140E-08 9.91150E-08 641640 + 821 641650 Gd-165 2.18170E-08 2.45090E-08 641650 + 822 641660 Gd-166 8.48470E-09 8.57880E-09 641660 + 823 641670 Gd-167 5.98430E-10 6.02950E-10 641670 + 824 641680 Gd-168 8.44570E-11 8.44570E-11 641680 + 825 641690 Gd-169 2.46670E-12 2.46670E-12 641690 + 826 651590 Tb-159 1.36580E-12 1.06390E-05 65159.82c + 827 651600 Tb-160 1.85170E-11 1.85170E-11 65160.82c + 828 651610 Tb-161 9.74600E-11 8.12920E-07 651610 + 829 651620 Tb-162 1.32320E-09 5.94460E-07 651620 + 830 651630 Tb-163 7.79750E-09 2.54120E-07 651630 + 831 651640 Tb-164 8.46280E-09 1.07580E-07 651640 + 832 651650 Tb-165 2.06250E-08 4.51340E-08 651650 + 833 651660 Tb-166 9.05210E-09 1.76310E-08 651660 + 834 651670 Tb-167 6.18120E-09 6.78420E-09 651670 + 835 651680 Tb-168 1.11830E-09 1.20280E-09 651680 + 836 651690 Tb-169 3.78910E-10 3.81380E-10 651690 + 837 651700 Tb-170 2.00000E-11 2.00000E-11 651700 + 838 651710 Tb-171 2.09800E-12 2.09800E-12 651710 + 839 661630 Dy-163 6.44560E-12 2.54130E-07 66163.82c + 840 661640 Dy-164 8.94110E-11 1.07670E-07 66164.82c + 841 661650 Dy-165 2.74660E-10 4.54500E-08 661650 + 842 661651 Dy-165m 4.19880E-11 4.19880E-11 661651 + 843 661660 Dy-166 1.52530E-09 1.91560E-08 661660 + 844 661670 Dy-167 1.26190E-09 8.04610E-09 661670 + 845 661680 Dy-168 2.14010E-09 3.34290E-09 661680 + 846 661690 Dy-169 8.27160E-10 1.20850E-09 661690 + 847 661700 Dy-170 4.39280E-10 4.59280E-10 661700 + 848 661710 Dy-171 6.18530E-11 6.39510E-11 661710 + 849 661720 Dy-172 1.69400E-11 1.69400E-11 661720 + 850 671660 Ho-166 6.70390E-13 1.91570E-08 671660 + 851 671661 Ho-166m 1.57020E-12 1.57020E-12 671661 + 852 671670 Ho-167 2.30330E-11 8.06910E-09 671670 + 853 671680 Ho-168 2.25610E-11 3.39730E-09 671680 + 854 671681 Ho-168m 3.20140E-11 3.20140E-11 671681 + 855 671690 Ho-169 2.21090E-10 1.42960E-09 671690 + 856 671700 Ho-170 9.60940E-11 9.60940E-11 671700 + 857 671701 Ho-170m 4.10260E-11 5.00310E-10 671701 + 858 671710 Ho-171 1.79560E-10 2.43510E-10 671710 + 859 671720 Ho-172 5.75790E-11 7.45190E-11 671720 + 860 671730 Ho-173 2.63670E-11 2.63670E-11 671730 + 861 671740 Ho-174 2.52810E-12 2.52810E-12 671740 + 862 681700 Er-170 5.67470E-12 6.02080E-10 68170.82c + 863 681710 Er-171 9.93770E-12 2.53450E-10 681710 + 864 681720 Er-172 3.19520E-11 1.06470E-10 681720 + 865 681730 Er-173 1.66660E-11 4.30330E-11 681730 + 866 681740 Er-174 1.49990E-11 1.75270E-11 681740 + 867 681750 Er-175 3.98050E-12 3.98050E-12 681750 + 868 681760 Er-176 1.58450E-12 1.58450E-12 681760 + 869 691730 Tm-173 1.14800E-12 4.41810E-11 691730 + 870 691740 Tm-174 1.31940E-12 1.88470E-11 691740 + 871 691750 Tm-175 3.38110E-12 7.36160E-12 691750 + 872 691760 Tm-176 1.51860E-12 3.10310E-12 691760 + 873 691770 Tm-177 1.08900E-12 1.08900E-12 691770 + + Neutron-induced fission: + + Interpolation region : 2 / 3 + Interpolation energy : 4.00000E-01 MeV + Number of products : 867 / 971 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 2.68910E-05 2.68910E-05 1001.82c + 2 10020 H-2 8.21820E-06 8.21820E-06 1002.82c + 3 10030 H-3 1.08000E-04 1.08000E-04 1003.82c + 4 20040 He-4 1.70000E-03 1.70000E-03 2004.82c + 5 230570 V-57 2.30530E-12 2.30530E-12 230570 + 6 230580 V-58 2.14100E-12 2.14100E-12 230580 + 7 230590 V-59 3.87110E-12 3.87110E-12 230590 + 8 230600 V-60 1.11060E-12 1.11060E-12 230600 + 9 240580 Cr-58 4.69150E-12 5.11970E-12 240580 + 10 240590 Cr-59 9.63840E-12 1.35090E-11 240590 + 11 240600 Cr-60 2.71110E-11 2.82220E-11 240600 + 12 240610 Cr-61 2.01280E-11 2.01280E-11 240610 + 13 240620 Cr-62 2.95040E-11 2.95040E-11 240620 + 14 240630 Cr-63 7.15320E-12 7.15320E-12 240630 + 15 240640 Cr-64 2.68370E-12 2.68370E-12 240640 + 16 250590 Mn-59 2.94860E-12 1.64580E-11 250590 + 17 250600 Mn-60 8.53290E-13 3.00730E-11 250600 + 18 250601 Mn-60m 8.68070E-12 8.68070E-12 250601 + 19 250610 Mn-61 6.37820E-11 8.39100E-11 250610 + 20 250620 Mn-62 9.42500E-11 1.09000E-10 250620 + 21 250621 Mn-62m 1.47600E-11 2.95120E-11 250621 + 22 250630 Mn-63 2.69840E-10 2.76990E-10 250630 + 23 250640 Mn-64 1.40430E-10 1.43110E-10 250640 + 24 250650 Mn-65 1.67280E-10 1.67280E-10 250650 + 25 250660 Mn-66 3.42920E-11 3.42920E-11 250660 + 26 250670 Mn-67 9.95080E-12 9.95080E-12 250670 + 27 260610 Fe-61 4.02780E-12 8.79380E-11 260610 + 28 260620 Fe-62 6.62310E-11 2.04740E-10 260620 + 29 260630 Fe-63 1.84720E-10 4.61710E-10 260630 + 30 260640 Fe-64 8.75400E-10 1.01850E-09 260640 + 31 260650 Fe-65 1.25870E-09 1.42600E-09 260650 + 32 260660 Fe-66 2.74580E-09 2.78010E-09 260660 + 33 260670 Fe-67 1.14430E-09 1.15430E-09 260670 + 34 260680 Fe-68 9.65480E-10 9.65480E-10 260680 + 35 260690 Fe-69 1.69120E-10 1.69120E-10 260690 + 36 260700 Fe-70 3.61780E-11 3.61780E-11 260700 + 37 260710 Fe-71 1.89240E-12 1.89240E-12 260710 + 38 270630 Co-63 1.39710E-11 4.75680E-10 270630 + 39 270640 Co-64 8.30790E-11 1.10160E-09 270640 + 40 270650 Co-65 1.11230E-09 2.53830E-09 270650 + 41 270660 Co-66 2.71520E-09 5.49530E-09 270660 + 42 270670 Co-67 1.05460E-08 1.17000E-08 270670 + 43 270680 Co-68 6.40000E-09 9.27710E-09 270680 + 44 270681 Co-68m 4.77700E-09 5.75440E-09 270681 + 45 270690 Co-69 2.16720E-08 2.18290E-08 270690 + 46 270700 Co-70 3.43080E-09 3.43080E-09 270700 + 47 270701 Co-70m 3.43080E-09 3.46700E-09 270701 + 48 270710 Co-71 4.49420E-09 4.49610E-09 270710 + 49 270720 Co-72 6.44460E-10 6.44460E-10 270720 + 50 270730 Co-73 1.16110E-10 1.16110E-10 270730 + 51 270740 Co-74 2.67100E-12 2.67100E-12 270740 + 52 270750 Co-75 1.04530E-12 1.04530E-12 270750 + 53 280650 Ni-65 1.64160E-11 2.55470E-09 280650 + 54 280660 Ni-66 4.25930E-10 5.92120E-09 280660 + 55 280670 Ni-67 1.99470E-09 1.36950E-08 280670 + 56 280680 Ni-68 1.92420E-08 3.16150E-08 280680 + 57 280690 Ni-69 2.10260E-08 4.26370E-08 280690 + 58 280691 Ni-69m 2.10260E-08 2.10260E-08 280691 + 59 280700 Ni-70 1.28240E-07 1.35140E-07 280700 + 60 280710 Ni-71 1.09980E-07 1.14480E-07 280710 + 61 280720 Ni-72 1.80920E-07 1.81560E-07 280720 + 62 280730 Ni-73 4.94780E-08 4.95940E-08 280730 + 63 280740 Ni-74 1.45340E-08 1.45370E-08 280740 + 64 280750 Ni-75 5.38950E-09 5.39050E-09 280750 + 65 280760 Ni-76 4.13930E-10 4.13930E-10 280760 + 66 280770 Ni-77 1.14020E-11 1.14020E-11 280770 + 67 290670 Cu-67 3.34170E-11 1.37280E-08 290670 + 68 290680 Cu-68 1.19900E-10 3.20090E-08 290680 + 69 290681 Cu-68m 3.26820E-10 3.26820E-10 290681 + 70 290690 Cu-69 9.95610E-09 7.36190E-08 290690 + 71 290700 Cu-70 2.39430E-09 2.11210E-08 290700 + 72 290701 Cu-70m 3.05770E-08 3.74540E-08 290701 + 73 290702 Cu-70m 2.39430E-09 1.37530E-07 290702 + 74 290710 Cu-71 2.73270E-07 3.87750E-07 290710 + 75 290720 Cu-72 5.17130E-07 6.98690E-07 290720 + 76 290730 Cu-73 1.41650E-06 1.46610E-06 290730 + 77 290740 Cu-74 5.67130E-07 5.81750E-07 290740 + 78 290750 Cu-75 2.48930E-06 2.49460E-06 290750 + 79 290760 Cu-76 1.48270E-07 1.48480E-07 290760 + 80 290761 Cu-76m 1.48270E-07 1.48480E-07 290761 + 81 290770 Cu-77 1.12770E-07 1.12780E-07 290770 + 82 290780 Cu-78 1.05440E-08 1.05440E-08 290780 + 83 290790 Cu-79 1.31140E-09 1.31140E-09 290790 + 84 290800 Cu-80 2.35080E-11 2.35080E-11 290800 + 85 300690 Zn-69 5.20210E-12 7.36500E-08 300690 + 86 300691 Zn-69m 2.58370E-11 2.58370E-11 300691 + 87 300700 Zn-70 1.28300E-09 1.71790E-07 300700 + 88 300710 Zn-71 2.21500E-09 3.89960E-07 300710 + 89 300711 Zn-71m 1.10010E-08 1.10010E-08 300711 + 90 300720 Zn-72 2.44910E-07 9.43600E-07 300720 + 91 300730 Zn-73 6.68040E-08 1.92660E-06 300730 + 92 300731 Zn-73m 9.23980E-08 3.93700E-07 300731 + 93 300732 Zn-73m 6.02600E-07 6.02600E-07 300732 + 94 300740 Zn-74 3.09600E-06 3.76510E-06 300740 + 95 300750 Zn-75 2.64060E-05 2.88180E-05 300750 + 96 300760 Zn-76 2.56370E-05 2.59290E-05 300760 + 97 300770 Zn-77 1.92130E-05 2.06050E-05 300770 + 98 300771 Zn-77m 2.55810E-06 2.55810E-06 300771 + 99 300780 Zn-78 3.45930E-05 3.46040E-05 300780 + 100 300790 Zn-79 7.96360E-06 7.96420E-06 300790 + 101 300800 Zn-80 7.04370E-06 7.04370E-06 300800 + 102 300810 Zn-81 1.77240E-08 1.77240E-08 300810 + 103 300820 Zn-82 1.13300E-09 1.13300E-09 300820 + 104 310710 Ga-71 4.49420E-11 4.01010E-07 310710 + 105 310720 Ga-72 1.13580E-09 9.44850E-07 310720 + 106 310721 Ga-72m 1.11640E-10 3.15530E-08 310721 + 107 310730 Ga-73 4.36480E-08 2.27150E-06 310730 + 108 310740 Ga-74 1.01120E-07 3.00080E-06 310740 + 109 310741 Ga-74m 1.01120E-07 3.86620E-06 310741 + 110 310750 Ga-75 1.65010E-06 3.04680E-05 310750 + 111 310760 Ga-76 7.99460E-06 3.39240E-05 310760 + 112 310770 Ga-77 3.86320E-05 6.05160E-05 310770 + 113 310780 Ga-78 7.03030E-05 1.05010E-04 310780 + 114 310790 Ga-79 1.63500E-04 1.71360E-04 310790 + 115 310800 Ga-80 7.26590E-05 7.97040E-05 310800 + 116 310810 Ga-81 4.42590E-05 4.42750E-05 310810 + 117 310820 Ga-82 5.65720E-06 5.65830E-06 310820 + 118 310830 Ga-83 6.00900E-07 6.00900E-07 310830 + 119 310840 Ga-84 1.91760E-08 1.91760E-08 310840 + 120 310850 Ga-85 4.98120E-10 4.98120E-10 310850 + 121 320730 Ge-73 2.22580E-11 2.27160E-06 32073.82c + 122 320731 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340771 + 162 340780 Se-78 3.38960E-09 2.35130E-04 34078.82c + 163 340790 Se-79 1.39210E-06 5.55720E-04 34079.82c + 164 340791 Se-79m 1.85360E-07 5.41500E-04 340791 + 165 340800 Se-80 1.80600E-05 9.85720E-04 34080.82c + 166 340810 Se-81 1.38520E-05 1.59120E-03 340810 + 167 340811 Se-81m 1.04040E-04 1.56930E-04 340811 + 168 340820 Se-82 7.20540E-04 2.78600E-03 34082.82c + 169 340830 Se-83 2.61410E-03 3.55640E-03 340830 + 170 340831 Se-83m 5.26350E-04 2.20050E-03 340831 + 171 340840 Se-84 8.32930E-03 1.02490E-02 340840 + 172 340850 Se-85 9.62420E-03 1.05780E-02 340850 + 173 340860 Se-86 1.03040E-02 1.05760E-02 340860 + 174 340870 Se-87 5.91810E-03 6.02180E-03 340870 + 175 340880 Se-88 2.94550E-03 2.95970E-03 340880 + 176 340890 Se-89 8.29680E-04 8.31700E-04 340890 + 177 340900 Se-90 1.98510E-04 1.98510E-04 340900 + 178 340910 Se-91 1.35060E-05 1.35060E-05 340910 + 179 340920 Se-92 4.00140E-06 4.00140E-06 340920 + 180 350790 Br-79 4.64340E-12 3.03260E-07 35079.82c + 181 350791 Br-79m 1.75850E-11 1.75850E-11 350791 + 182 350800 Br-80 2.41130E-10 1.08130E-09 350800 + 183 350801 Br-80m 8.40170E-10 8.40170E-10 350801 + 184 350810 Br-81 1.01900E-07 1.59140E-03 35081.82c + 185 350820 Br-82 4.89240E-06 6.64420E-06 350820 + 186 350821 Br-82m 1.79490E-06 1.79490E-06 350821 + 187 350830 Br-83 6.90100E-05 5.82590E-03 350830 + 188 350840 Br-84 2.07510E-04 1.04570E-02 350840 + 189 350841 Br-84m 2.07510E-04 2.07510E-04 350841 + 190 350850 Br-85 2.49760E-03 1.30750E-02 350850 + 191 350860 Br-86 7.01010E-03 1.75860E-02 350860 + 192 350870 Br-87 1.27620E-02 1.88130E-02 350870 + 193 350880 Br-88 1.14750E-02 1.44700E-02 350880 + 194 350890 Br-89 9.14950E-03 9.91630E-03 350890 + 195 350900 Br-90 4.24150E-03 4.44280E-03 350900 + 196 350910 Br-91 1.91500E-03 1.92570E-03 350910 + 197 350920 Br-92 2.98470E-04 3.02470E-04 350920 + 198 350930 Br-93 6.31800E-05 6.31800E-05 350930 + 199 350940 Br-94 1.72750E-06 1.72750E-06 350940 + 200 350950 Br-95 9.60780E-09 9.60780E-09 350950 + 201 360820 Kr-82 5.66480E-10 6.68790E-06 36082.82c + 202 360830 Kr-83 1.90730E-06 5.82820E-03 36083.82c + 203 360831 Kr-83m 3.84020E-07 5.82110E-03 360831 + 204 360840 Kr-84 1.62890E-05 1.06810E-02 36084.82c + 205 360850 Kr-85 1.69800E-04 2.99200E-03 36085.82c + 206 360851 Kr-85m 3.41890E-05 1.30880E-02 360851 + 207 360860 Kr-86 2.08740E-03 2.01460E-02 36086.82c + 208 360870 Kr-87 7.03730E-03 2.63480E-02 360870 + 209 360880 Kr-88 2.16680E-02 3.65670E-02 360880 + 210 360890 Kr-89 3.26820E-02 4.22930E-02 360890 + 211 360900 Kr-90 3.95850E-02 4.33200E-02 360900 + 212 360910 Kr-91 2.86250E-02 3.02660E-02 360910 + 213 360920 Kr-92 1.71920E-02 1.74370E-02 360920 + 214 360930 Kr-93 5.72940E-03 5.75080E-03 360930 + 215 360940 Kr-94 1.75680E-03 1.75730E-03 360940 + 216 360950 Kr-95 2.85060E-04 2.85070E-04 360950 + 217 360960 Kr-96 3.87950E-05 3.87950E-05 360960 + 218 360970 Kr-97 2.69230E-06 2.69230E-06 360970 + 219 360980 Kr-98 8.79630E-07 8.79630E-07 360980 + 220 370850 Rb-85 1.49440E-08 1.32790E-02 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280 391030 Y-103 7.75810E-05 7.75820E-05 391030 + 281 391040 Y-104 9.47620E-06 9.47620E-06 391040 + 282 391050 Y-105 4.34710E-09 4.34710E-09 391050 + 283 400920 Zr-92 2.00110E-06 5.90040E-02 40092.82c + 284 400930 Zr-93 2.73840E-05 6.05620E-02 40093.82c + 285 400940 Zr-94 2.20240E-04 6.24640E-02 40094.82c + 286 400950 Zr-95 9.73090E-04 6.45890E-02 40095.82c + 287 400960 Zr-96 5.06040E-03 6.31760E-02 40096.82c + 288 400970 Zr-97 1.20680E-02 6.03010E-02 400970 + 289 400980 Zr-98 2.91490E-02 6.02920E-02 400980 + 290 400990 Zr-99 3.54810E-02 5.51520E-02 400990 + 291 401000 Zr-100 4.64300E-02 5.48820E-02 401000 + 292 401010 Zr-101 2.88830E-02 3.20000E-02 401010 + 293 401020 Zr-102 1.65530E-02 1.70800E-02 401020 + 294 401030 Zr-103 4.49600E-03 4.56820E-03 401030 + 295 401040 Zr-104 1.11560E-03 1.12430E-03 401040 + 296 401050 Zr-105 1.14330E-04 1.14330E-04 401050 + 297 401060 Zr-106 8.69720E-06 8.69720E-06 401060 + 298 401070 Zr-107 3.60850E-09 3.60850E-09 401070 + 299 401080 Zr-108 3.59330E-11 3.59330E-11 401080 + 300 410950 Nb-95 2.29390E-06 6.45530E-02 41095.82c + 301 410951 Nb-95m 4.61870E-07 6.98250E-04 410951 + 302 410960 Nb-96 1.80480E-05 1.80480E-05 410960 + 303 410970 Nb-97 1.47870E-04 6.04790E-02 410970 + 304 410971 Nb-97m 2.97720E-05 5.73450E-02 410971 + 305 410980 Nb-98 1.70650E-04 6.04630E-02 410980 + 306 410981 Nb-98m 5.94590E-04 5.94590E-04 410981 + 307 410990 Nb-99 3.04020E-03 3.83140E-02 410990 + 308 410991 Nb-99m 6.12130E-04 2.09080E-02 410991 + 309 411000 Nb-100 1.43780E-03 5.63200E-02 411000 + 310 411001 Nb-100m 6.97020E-03 6.97020E-03 411001 + 311 411010 Nb-101 1.74600E-02 4.94600E-02 411010 + 312 411020 Nb-102 9.39950E-03 2.64800E-02 411020 + 313 411021 Nb-102m 9.39950E-03 9.39950E-03 411021 + 314 411030 Nb-103 1.70990E-02 2.16670E-02 411030 + 315 411040 Nb-104 3.59620E-03 4.72200E-03 411040 + 316 411041 Nb-104m 3.59620E-03 3.59620E-03 411041 + 317 411050 Nb-105 3.16540E-03 3.27830E-03 411050 + 318 411060 Nb-106 4.37380E-04 4.45950E-04 411060 + 319 411070 Nb-107 9.00330E-05 9.00360E-05 411070 + 320 411080 Nb-108 2.99290E-06 2.99290E-06 411080 + 321 411090 Nb-109 9.23150E-09 9.23150E-09 411090 + 322 411100 Nb-110 9.82570E-11 9.82570E-11 411100 + 323 420970 Mo-97 2.69230E-06 6.04810E-02 42097.82c + 324 420980 Mo-98 2.28660E-05 6.10800E-02 42098.82c + 325 420990 Mo-99 1.52490E-04 5.89570E-02 42099.82c + 326 421000 Mo-100 1.04060E-03 6.43310E-02 42100.82c + 327 421010 Mo-101 2.96600E-03 5.24260E-02 421010 + 328 421020 Mo-102 8.50730E-03 4.43870E-02 421020 + 329 421030 Mo-103 1.07270E-02 3.23990E-02 421030 + 330 421040 Mo-104 1.21760E-02 2.05450E-02 421040 + 331 421050 Mo-105 7.86450E-03 1.11070E-02 421050 + 332 421060 Mo-106 3.08340E-03 3.51470E-03 421060 + 333 421070 Mo-107 7.95120E-04 8.79940E-04 421070 + 334 421080 Mo-108 2.60230E-04 2.63040E-04 421080 + 335 421090 Mo-109 3.67700E-05 3.67780E-05 421090 + 336 421100 Mo-110 6.09900E-06 6.09910E-06 421100 + 337 421110 Mo-111 2.84260E-08 2.84260E-08 421110 + 338 421120 Mo-112 1.23540E-09 1.23540E-09 421120 + 339 421130 Mo-113 1.63480E-11 1.63480E-11 421130 + 340 431000 Tc-100 4.10120E-06 4.10120E-06 431000 + 341 431010 Tc-101 1.52360E-05 5.24410E-02 431010 + 342 431020 Tc-102 4.34220E-05 4.44300E-02 431020 + 343 431021 Tc-102m 4.34220E-05 4.34220E-05 431021 + 344 431030 Tc-103 4.04040E-04 3.28030E-02 431030 + 345 431040 Tc-104 8.30520E-04 2.13760E-02 431040 + 346 431050 Tc-105 1.60960E-03 1.27170E-02 431050 + 347 431060 Tc-106 9.88030E-04 4.50270E-03 431060 + 348 431070 Tc-107 8.78370E-04 1.75830E-03 431070 + 349 431080 Tc-108 4.38130E-04 7.01360E-04 431080 + 350 431090 Tc-109 2.06790E-04 2.43370E-04 431090 + 351 431100 Tc-110 8.29200E-05 8.90190E-05 431100 + 352 431110 Tc-111 5.84230E-05 5.84510E-05 431110 + 353 431120 Tc-112 1.29780E-05 1.29790E-05 431120 + 354 431130 Tc-113 2.50320E-06 2.50320E-06 431130 + 355 431140 Tc-114 4.45600E-09 4.45600E-09 431140 + 356 431150 Tc-115 2.09810E-10 2.09810E-10 431150 + 357 441020 Ru-102 2.38120E-06 4.44760E-02 44102.82c + 358 441030 Ru-103 1.59660E-06 3.28090E-02 44103.82c + 359 441031 Ru-103m 4.46720E-06 4.46720E-06 441031 + 360 441040 Ru-104 2.73320E-05 2.14030E-02 44104.82c + 361 441050 Ru-105 9.40670E-05 1.28110E-02 44105.82c + 362 441060 Ru-106 1.56980E-04 4.65970E-03 44106.82c + 363 441070 Ru-107 1.63400E-04 1.92170E-03 441070 + 364 441080 Ru-108 1.88820E-04 8.90380E-04 441080 + 365 441090 Ru-109 1.73920E-04 4.17130E-04 441090 + 366 441100 Ru-110 2.31900E-04 3.20880E-04 441100 + 367 441110 Ru-111 1.93500E-04 2.52150E-04 441110 + 368 441120 Ru-112 1.61570E-04 1.74530E-04 441120 + 369 441130 Ru-113 4.19130E-05 6.51920E-05 441130 + 370 441131 Ru-113m 4.19130E-05 4.19130E-05 441131 + 371 441140 Ru-114 4.75600E-05 4.75640E-05 441140 + 372 441150 Ru-115 1.19980E-05 1.19980E-05 441150 + 373 441160 Ru-116 1.99210E-06 1.99210E-06 441160 + 374 441170 Ru-117 1.55910E-09 1.55910E-09 441170 + 375 441180 Ru-118 4.76070E-11 4.76070E-11 441180 + 376 441190 Ru-119 1.33150E-07 1.33150E-07 441190 + 377 441200 Ru-120 1.13790E-08 1.13790E-08 441200 + 378 451050 Rh-105 2.55750E-09 1.28110E-02 45105.82c + 379 451051 Rh-105m 3.40510E-10 3.63670E-03 451051 + 380 451060 Rh-106 7.61750E-09 4.65970E-03 451060 + 381 451061 Rh-106m 2.07630E-08 2.07630E-08 451061 + 382 451070 Rh-107 1.23360E-06 1.92290E-03 451070 + 383 451080 Rh-108 3.33670E-07 8.90710E-04 451080 + 384 451081 Rh-108m 1.16260E-06 1.16260E-06 451081 + 385 451090 Rh-109 1.05100E-05 4.27640E-04 451090 + 386 451100 Rh-110 2.17940E-05 3.42680E-04 451100 + 387 451101 Rh-110m 5.13060E-07 5.13060E-07 451101 + 388 451110 Rh-111 7.74090E-05 3.29550E-04 451110 + 389 451120 Rh-112 3.86370E-05 2.13170E-04 451120 + 390 451121 Rh-112m 3.86370E-05 3.86370E-05 451121 + 391 451130 Rh-113 1.82590E-04 2.68740E-04 451130 + 392 451140 Rh-114 5.66950E-05 1.04290E-04 451140 + 393 451141 Rh-114m 5.66950E-05 5.66950E-05 451141 + 394 451150 Rh-115 9.49550E-05 1.06950E-04 451150 + 395 451160 Rh-116 1.02250E-05 1.21960E-05 451160 + 396 451161 Rh-116m 2.78720E-05 2.78720E-05 451161 + 397 451170 Rh-117 3.31040E-05 3.31050E-05 451170 + 398 451180 Rh-118 1.00910E-05 1.00970E-05 451180 + 399 451190 Rh-119 4.07990E-05 4.09260E-05 451190 + 400 451200 Rh-120 5.37150E-06 5.38290E-06 451200 + 401 451210 Rh-121 8.53040E-07 8.53040E-07 451210 + 402 451220 Rh-122 2.61310E-08 2.61310E-08 451220 + 403 461070 Pd-107 1.44660E-11 1.92290E-03 46107.82c + 404 461071 Pd-107m 3.17960E-11 3.17960E-11 461071 + 405 461080 Pd-108 1.22180E-09 8.91880E-04 46108.82c + 406 461090 Pd-109 4.06700E-09 4.27660E-04 461090 + 407 461091 Pd-109m 8.93900E-09 2.13830E-04 461091 + 408 461100 Pd-110 3.58800E-07 3.43550E-04 46110.82c + 409 461110 Pd-111 2.03130E-06 3.34490E-04 461110 + 410 461111 Pd-111m 4.46480E-06 5.78300E-06 461111 + 411 461120 Pd-112 1.47750E-05 2.66580E-04 461120 + 412 461130 Pd-113 1.94920E-05 3.42770E-04 461130 + 413 461131 Pd-113m 5.45360E-05 5.45360E-05 461131 + 414 461140 Pd-114 7.83890E-05 2.39370E-04 461140 + 415 461150 Pd-115 4.54600E-05 1.46110E-04 461150 + 416 461151 Pd-115m 9.99200E-05 1.15450E-04 461151 + 417 461160 Pd-116 2.67210E-04 3.07280E-04 461160 + 418 461170 Pd-117 7.02700E-05 2.58120E-04 461170 + 419 461171 Pd-117m 1.54450E-04 1.54450E-04 461171 + 420 461180 Pd-118 1.81610E-04 1.91410E-04 461180 + 421 461190 Pd-119 3.96270E-05 8.08730E-05 461190 + 422 461200 Pd-120 2.36500E-05 2.88290E-05 461200 + 423 461210 Pd-121 9.32300E-06 1.00600E-05 461210 + 424 461220 Pd-122 1.85870E-05 1.86130E-05 461220 + 425 461230 Pd-123 1.72910E-06 1.72910E-06 461230 + 426 461240 Pd-124 3.40720E-07 3.40720E-07 461240 + 427 471100 Ag-110 8.11450E-12 8.41530E-12 471100 + 428 471101 Ag-110m 2.21190E-11 2.21190E-11 47510.82c + 429 471110 Ag-111 2.72060E-10 3.34390E-04 47111.82c + 430 471111 Ag-111m 2.04330E-09 3.33250E-04 471111 + 431 471120 Ag-112 3.11380E-08 2.66610E-04 471120 + 432 471130 Ag-113 1.25320E-07 2.25330E-04 471130 + 433 471131 Ag-113m 9.41270E-07 3.29170E-04 471131 + 434 471140 Ag-114 5.92570E-07 2.42840E-04 471140 + 435 471141 Ag-114m 2.87270E-06 2.87270E-06 471141 + 436 471150 Ag-115 1.59990E-06 1.41380E-04 471150 + 437 471151 Ag-115m 1.20160E-05 1.57680E-04 471151 + 438 471160 Ag-116 1.27120E-05 3.22070E-04 471160 + 439 471161 Ag-116m 3.46490E-05 3.46490E-05 471161 + 440 471170 Ag-117 1.26750E-05 1.55190E-04 471170 + 441 471171 Ag-117m 9.51950E-05 2.24260E-04 471171 + 442 471180 Ag-118 2.31070E-05 2.44300E-04 471180 + 443 471181 Ag-118m 1.12020E-04 1.39390E-04 471181 + 444 471190 Ag-119 1.92610E-05 5.96970E-05 471190 + 445 471191 Ag-119m 1.44660E-04 1.85100E-04 471191 + 446 471200 Ag-120 5.59650E-05 1.10370E-04 471200 + 447 471201 Ag-120m 9.35950E-05 1.08010E-04 471201 + 448 471210 Ag-121 7.73630E-05 8.73960E-05 471210 + 449 471220 Ag-122 1.03510E-05 2.89640E-05 471220 + 450 471221 Ag-122m 1.11590E-05 1.11590E-05 471221 + 451 471230 Ag-123 1.93310E-05 2.10600E-05 471230 + 452 471240 Ag-124 3.56090E-06 5.82120E-06 471240 + 453 471241 Ag-124m 3.83920E-06 3.83920E-06 471241 + 454 471250 Ag-125 7.69160E-06 7.69160E-06 471250 + 455 471260 Ag-126 1.91120E-06 1.91120E-06 471260 + 456 471270 Ag-127 6.03020E-07 6.03020E-07 471270 + 457 471280 Ag-128 2.04050E-08 2.04050E-08 471280 + 458 471290 Ag-129 1.29410E-09 1.29410E-09 471290 + 459 481130 Cd-113 3.92730E-11 3.39940E-04 48113.82c + 460 481131 Cd-113m 1.48730E-10 3.89590E-06 481131 + 461 481140 Cd-114 8.76150E-09 2.42840E-04 48114.82c + 462 481150 Cd-115 3.56510E-07 2.54530E-04 481150 + 463 481151 Cd-115m 1.35010E-06 1.31230E-05 48515.82c + 464 481160 Cd-116 3.37310E-06 3.58010E-04 48116.82c + 465 481170 Cd-117 3.69000E-06 2.91190E-04 481170 + 466 481171 Cd-117m 1.39740E-05 9.24630E-05 481171 + 467 481180 Cd-118 6.96060E-05 3.96150E-04 481180 + 468 481190 Cd-119 2.33090E-05 2.38250E-04 481190 + 469 481191 Cd-119m 6.52170E-05 9.50670E-05 481191 + 470 481200 Cd-120 1.57320E-04 3.35730E-04 481200 + 471 481210 Cd-121 4.83180E-05 1.26580E-04 481210 + 472 481211 Cd-121m 1.35190E-04 1.44320E-04 481211 + 473 481220 Cd-122 1.92860E-04 2.32980E-04 481220 + 474 481230 Cd-123 3.39710E-05 5.12050E-05 481230 + 475 481231 Cd-123m 9.50490E-05 9.88810E-05 481231 + 476 481240 Cd-124 1.51070E-04 1.58810E-04 481240 + 477 481250 Cd-125 6.22490E-05 6.60950E-05 481250 + 478 481251 Cd-125m 1.74170E-04 1.78020E-04 481251 + 479 481260 Cd-126 2.46330E-04 2.48240E-04 481260 + 480 481270 Cd-127 2.21250E-04 2.21850E-04 481270 + 481 481280 Cd-128 8.89760E-05 8.89960E-05 481280 + 482 481290 Cd-129 6.52720E-06 6.52780E-06 481290 + 483 481291 Cd-129m 1.82630E-05 1.82630E-05 481291 + 484 481300 Cd-130 3.35240E-06 3.35240E-06 481300 + 485 481310 Cd-131 2.35320E-08 2.35320E-08 481310 + 486 491150 In-115 1.66320E-11 2.54920E-04 49115.82c + 487 491151 In-115m 3.34880E-12 2.54530E-04 491151 + 488 491160 In-116 2.21960E-10 2.21960E-10 491160 + 489 491161 In-116m 3.58430E-10 7.73390E-10 491161 + 490 491162 In-116m 4.14970E-10 4.14970E-10 491162 + 491 491170 In-117 4.55860E-08 2.41790E-04 491170 + 492 491171 In-117m 9.17860E-09 2.68270E-04 491171 + 493 491180 In-118 1.25410E-07 3.96270E-04 491180 + 494 491181 In-118m 2.02520E-07 4.33700E-07 491181 + 495 491182 In-118m 2.34470E-07 2.34470E-07 491182 + 496 491190 In-119 5.46660E-06 1.35610E-04 491190 + 497 491191 In-119m 1.10070E-06 2.16400E-04 491191 + 498 491200 In-120 5.48840E-06 3.41220E-04 491200 + 499 491201 In-120m 5.48840E-06 5.48840E-06 491201 + 500 491202 In-120m 5.48840E-06 5.48840E-06 491202 + 501 491210 In-121 2.51860E-05 2.13210E-04 491210 + 502 491211 In-121m 5.07110E-06 8.90210E-05 491211 + 503 491220 In-122 1.52890E-05 2.48270E-04 491220 + 504 491221 In-122m 1.27840E-05 1.27840E-05 491221 + 505 491222 In-122m 1.27840E-05 1.27840E-05 491222 + 506 491230 In-123 8.87500E-05 2.02290E-04 491230 + 507 491231 In-123m 1.78690E-05 5.44200E-05 491231 + 508 491240 In-124 6.80220E-05 2.26830E-04 491240 + 509 491241 In-124m 7.33380E-05 7.33380E-05 491241 + 510 491250 In-125 2.54650E-04 4.64300E-04 491250 + 511 491251 In-125m 5.12720E-05 8.57320E-05 491251 + 512 491260 In-126 2.11980E-04 4.60220E-04 491260 + 513 491261 In-126m 2.28540E-04 2.28540E-04 491261 + 514 491270 In-127 1.08580E-03 1.08580E-03 491270 + 515 491271 In-127m 2.18620E-04 4.40470E-04 491271 + 516 491280 In-128 3.83180E-04 6.22210E-04 491280 + 517 491281 In-128m 1.50040E-04 2.39030E-04 491281 + 518 491282 In-128m 5.74880E-04 5.74880E-04 491282 + 519 491290 In-129 1.01650E-03 1.03480E-03 491290 + 520 491291 In-129m 2.04670E-04 2.11260E-04 491291 + 521 491300 In-130 1.43310E-04 1.46540E-04 491300 + 522 491301 In-130m 2.08660E-04 2.08660E-04 491301 + 523 491302 In-130m 2.90660E-04 2.90660E-04 491302 + 524 491310 In-131 7.99020E-05 8.07380E-05 491310 + 525 491311 In-131m 7.99020E-05 7.99020E-05 491311 + 526 491312 In-131m 7.99020E-05 7.99020E-05 491312 + 527 491320 In-132 1.08720E-05 1.08720E-05 491320 + 528 491330 In-133 1.92300E-06 2.31020E-06 491330 + 529 491331 In-133m 3.87190E-07 3.87190E-07 491331 + 530 491340 In-134 6.83220E-09 6.83220E-09 491340 + 531 501180 Sn-118 2.38030E-10 3.96710E-04 50118.82c + 532 501210 Sn-121 3.79310E-12 2.95750E-04 501210 + 533 501211 Sn-121m 1.06130E-11 2.41530E-05 501211 + 534 501220 Sn-122 2.14500E-06 2.75990E-04 50122.82c + 535 501230 Sn-123 1.60020E-05 3.14240E-05 50123.82c + 536 501231 Sn-123m 5.71910E-06 2.47000E-04 501231 + 537 501240 Sn-124 9.15570E-05 3.91720E-04 50124.82c + 538 501250 Sn-125 9.67430E-05 1.75170E-04 50125.82c + 539 501251 Sn-125m 3.45770E-05 5.06180E-04 501251 + 540 501260 Sn-126 3.07940E-04 9.99740E-04 50126.82c + 541 501270 Sn-127 1.08900E-03 1.51220E-03 501270 + 542 501271 Sn-127m 3.89210E-04 1.48920E-03 501271 + 543 501280 Sn-128 9.94130E-04 4.90100E-03 501280 + 544 501281 Sn-128m 2.70980E-03 3.28470E-03 501281 + 545 501290 Sn-129 2.22180E-03 3.35790E-03 501290 + 546 501291 Sn-129m 6.21660E-03 6.32670E-03 501291 + 547 501300 Sn-130 3.64840E-03 4.04400E-03 501300 + 548 501301 Sn-130m 9.94460E-03 1.01970E-02 501301 + 549 501310 Sn-131 3.15620E-03 3.31100E-03 501310 + 550 501311 Sn-131m 8.83080E-03 8.91420E-03 501311 + 551 501320 Sn-132 6.81810E-03 6.83090E-03 501320 + 552 501330 Sn-133 9.40480E-04 9.40830E-04 501330 + 553 501340 Sn-134 1.12860E-04 1.12860E-04 501340 + 554 501350 Sn-135 1.35680E-05 1.35680E-05 501350 + 555 501360 Sn-136 8.41580E-07 8.41580E-07 501360 + 556 501370 Sn-137 1.43190E-09 1.43190E-09 501370 + 557 511240 Sb-124 7.95640E-07 2.04770E-06 51124.82c + 558 511241 Sb-124m 6.41830E-07 1.66940E-06 511241 + 559 511242 Sb-124m 1.02760E-06 1.02760E-06 511242 + 560 511250 Sb-125 7.68720E-06 6.89040E-04 51125.82c + 561 511260 Sb-126 4.45540E-06 5.32800E-06 51126.82c + 562 511261 Sb-126m 2.78290E-06 6.23270E-06 511261 + 563 511262 Sb-126m 3.44980E-06 3.44980E-06 511262 + 564 511270 Sb-127 5.46290E-05 3.05600E-03 511270 + 565 511280 Sb-128 1.02290E-04 5.00840E-03 511280 + 566 511281 Sb-128m 1.43060E-04 1.43060E-04 511281 + 567 511290 Sb-129 1.05140E-03 8.16380E-03 511290 + 568 511291 Sb-129m 7.78090E-04 3.94140E-03 511291 + 569 511300 Sb-130 3.20000E-03 1.23420E-02 511300 + 570 511301 Sb-130m 3.20000E-03 8.29820E-03 511301 + 571 511310 Sb-131 1.65610E-02 2.87860E-02 511310 + 572 511320 Sb-132 1.18650E-02 1.86960E-02 511320 + 573 511321 Sb-132m 1.05040E-02 1.05040E-02 511321 + 574 511330 Sb-133 2.22080E-02 2.31680E-02 511330 + 575 511340 Sb-134 1.59550E-03 1.69060E-03 511340 + 576 511341 Sb-134m 4.34910E-03 4.35050E-03 511341 + 577 511350 Sb-135 1.38400E-03 1.39500E-03 511350 + 578 511360 Sb-136 2.23960E-04 2.24550E-04 511360 + 579 511370 Sb-137 2.77630E-05 2.77640E-05 511370 + 580 511380 Sb-138 3.79580E-07 3.79580E-07 511380 + 581 511390 Sb-139 1.19390E-08 1.19390E-08 511390 + 582 521260 Te-126 8.05300E-11 1.06880E-05 52126.82c + 583 521270 Te-127 2.18760E-09 3.04400E-03 521270 + 584 521271 Te-127m 6.12070E-09 5.03630E-04 52527.82c + 585 521280 Te-128 8.98390E-06 5.15530E-03 52128.82c + 586 521290 Te-129 3.40550E-05 9.89630E-03 521290 + 587 521291 Te-129m 9.52850E-05 4.72180E-03 52529.82c + 588 521300 Te-130 9.40230E-04 2.15810E-02 52130.82c + 589 521310 Te-131 1.35480E-03 2.91160E-02 521310 + 590 521311 Te-131m 3.79080E-03 6.09540E-03 521311 + 591 521320 Te-132 1.78930E-02 4.70930E-02 52132.82c + 592 521330 Te-133 1.08500E-02 3.60290E-02 521330 + 593 521331 Te-133m 3.03580E-02 3.43650E-02 521331 + 594 521340 Te-134 6.20020E-02 6.82590E-02 521340 + 595 521350 Te-135 3.28690E-02 3.40820E-02 521350 + 596 521360 Te-136 1.48990E-02 1.51000E-02 521360 + 597 521370 Te-137 4.33730E-03 4.35150E-03 521370 + 598 521380 Te-138 9.90910E-04 9.91290E-04 521380 + 599 521390 Te-139 1.35220E-04 1.35230E-04 521390 + 600 521400 Te-140 2.16700E-05 2.16700E-05 521400 + 601 521410 Te-141 2.18650E-06 2.18650E-06 521410 + 602 521420 Te-142 2.27900E-09 2.27900E-09 521420 + 603 531290 I-129 6.47000E-09 1.16430E-02 53129.82c + 604 531300 I-130 3.27120E-06 4.27930E-06 53130.82c + 605 531301 I-130m 1.20010E-06 1.20010E-06 531301 + 606 531310 I-131 3.18460E-05 3.39640E-02 53131.82c + 607 531320 I-132 1.82500E-04 4.74140E-02 531320 + 608 531321 I-132m 1.61590E-04 1.61590E-04 531321 + 609 531330 I-133 1.22010E-03 6.65030E-02 531330 + 610 531331 I-133m 9.02910E-04 9.02910E-04 531331 + 611 531340 I-134 4.33320E-03 7.63400E-02 531340 + 612 531341 I-134m 3.83640E-03 3.83640E-03 531341 + 613 531350 I-135 2.65250E-02 6.06070E-02 53135.82c + 614 531360 I-136 7.95320E-03 2.31180E-02 531360 + 615 531361 I-136m 2.16790E-02 2.17440E-02 531361 + 616 531370 I-137 2.60700E-02 3.03540E-02 531370 + 617 531380 I-138 1.18560E-02 1.27850E-02 531380 + 618 531390 I-139 7.35820E-03 7.49340E-03 531390 + 619 531400 I-140 1.89560E-03 1.91730E-03 531400 + 620 531410 I-141 4.49280E-04 4.51470E-04 531410 + 621 531420 I-142 4.41200E-05 4.41220E-05 531420 + 622 531430 I-143 5.23470E-06 5.23470E-06 531430 + 623 531440 I-144 6.98660E-09 6.98660E-09 531440 + 624 541310 Xe-131 4.27310E-10 3.39640E-02 54131.82c + 625 541311 Xe-131m 1.19560E-09 3.68910E-04 541311 + 626 541320 Xe-132 1.03250E-06 4.74390E-02 54132.82c + 627 541321 Xe-132m 1.38330E-06 1.38330E-06 541321 + 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Cs-134m 9.62490E-09 9.62490E-09 551341 + 648 551350 Cs-135 5.19750E-07 6.31640E-02 55135.82c + 649 551351 Cs-135m 3.84640E-07 3.84640E-07 551351 + 650 551360 Cs-136 2.50270E-05 3.39730E-05 55136.82c + 651 551361 Cs-136m 1.78930E-05 1.78930E-05 551361 + 652 551370 Cs-137 8.32950E-04 5.85720E-02 55137.82c + 653 551380 Cs-138 1.29270E-03 6.40200E-02 551380 + 654 551381 Cs-138m 2.16180E-03 2.16180E-03 551381 + 655 551390 Cs-139 1.20250E-02 6.18520E-02 551390 + 656 551400 Cs-140 1.68930E-02 5.56740E-02 551400 + 657 551410 Cs-141 2.90800E-02 4.89370E-02 551410 + 658 551420 Cs-142 2.25270E-02 2.91370E-02 551420 + 659 551430 Cs-143 1.45100E-02 1.60860E-02 551430 + 660 551440 Cs-144 3.18730E-03 5.05710E-03 551440 + 661 551441 Cs-144m 3.18730E-03 3.18800E-03 551441 + 662 551450 Cs-145 1.93930E-03 1.96410E-03 551450 + 663 551460 Cs-146 3.22430E-04 3.28550E-04 551460 + 664 551470 Cs-147 6.25570E-05 6.25570E-05 551470 + 665 551480 Cs-148 1.38520E-07 1.38520E-07 551480 + 666 551490 Cs-149 3.22710E-09 3.22710E-09 551490 + 667 561360 Ba-136 6.49070E-10 4.29220E-05 56136.82c + 668 561361 Ba-136m 1.76920E-09 1.76920E-09 561361 + 669 561370 Ba-137 8.86060E-07 5.85760E-02 56137.82c + 670 561371 Ba-137m 2.47910E-06 5.52950E-02 561371 + 671 561380 Ba-138 1.40180E-04 6.45710E-02 56138.82c + 672 561390 Ba-139 9.49980E-04 6.28020E-02 561390 + 673 561400 Ba-140 4.91200E-03 6.05860E-02 56140.82c + 674 561410 Ba-141 1.00590E-02 5.89960E-02 561410 + 675 561420 Ba-142 2.77160E-02 5.71160E-02 561420 + 676 561430 Ba-143 3.73250E-02 5.33090E-02 561430 + 677 561440 Ba-144 3.89210E-02 4.56910E-02 561440 + 678 561450 Ba-145 2.19760E-02 2.37060E-02 561450 + 679 561460 Ba-146 1.03830E-02 1.06830E-02 561460 + 680 561470 Ba-147 3.55340E-03 3.59820E-03 561470 + 681 561480 Ba-148 8.66140E-04 8.66240E-04 561480 + 682 561490 Ba-149 9.97720E-05 9.97750E-05 561490 + 683 561500 Ba-150 8.30910E-06 8.30910E-06 561500 + 684 561510 Ba-151 6.95140E-09 6.95140E-09 561510 + 685 561520 Ba-152 1.23470E-10 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5.51100E-05 1.66850E-02 591480 + 725 591481 Pr-148m 2.67170E-04 2.67170E-04 591481 + 726 591490 Pr-149 9.83210E-04 1.07240E-02 591490 + 727 591500 Pr-150 1.48560E-03 6.64510E-03 591500 + 728 591510 Pr-151 1.82040E-03 3.92350E-03 591510 + 729 591520 Pr-152 1.50490E-03 2.14330E-03 591520 + 730 591530 Pr-153 5.60710E-04 6.57640E-04 591530 + 731 591540 Pr-154 2.25720E-04 2.40430E-04 591540 + 732 591550 Pr-155 2.04030E-05 2.04180E-05 591550 + 733 591560 Pr-156 1.12060E-05 1.12070E-05 591560 + 734 591570 Pr-157 9.90880E-09 9.90880E-09 591570 + 735 591580 Pr-158 2.34990E-10 2.34990E-10 591580 + 736 591590 Pr-159 1.21090E-11 1.21090E-11 591590 + 737 601460 Nd-146 1.19880E-09 2.88750E-02 60146.82c + 738 601470 Nd-147 2.71550E-08 2.18340E-02 60147.82c + 739 601480 Nd-148 9.96600E-06 1.69620E-02 60148.82c + 740 601490 Nd-149 4.45900E-05 1.07690E-02 601490 + 741 601500 Nd-150 2.02040E-04 6.84720E-03 60150.82c + 742 601510 Nd-151 4.56310E-04 4.37990E-03 601510 + 743 601520 Nd-152 9.69200E-04 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1.67500E-06 1.68770E-06 621610 + 783 621620 Sm-162 1.94560E-07 1.95070E-07 621620 + 784 621630 Sm-163 8.87480E-09 8.88960E-09 621630 + 785 621640 Sm-164 6.05190E-10 6.05190E-10 621640 + 786 621650 Sm-165 1.07220E-11 1.07220E-11 621650 + 787 631540 Eu-154 5.56890E-11 1.15730E-10 63154.82c + 788 631541 Eu-154m 6.00410E-11 6.00410E-11 631541 + 789 631550 Eu-155 2.20810E-09 2.78930E-04 63155.82c + 790 631560 Eu-156 2.83630E-08 1.81480E-04 63156.82c + 791 631570 Eu-157 8.00970E-08 1.91900E-05 63157.82c + 792 631580 Eu-158 3.92900E-07 1.95890E-05 631580 + 793 631590 Eu-159 4.42640E-06 3.15490E-05 631590 + 794 631600 Eu-160 1.13960E-06 5.47250E-06 631600 + 795 631610 Eu-161 1.30680E-06 2.99450E-06 631610 + 796 631620 Eu-162 7.28120E-07 9.23190E-07 631620 + 797 631630 Eu-163 3.44220E-07 3.53110E-07 631630 + 798 631640 Eu-164 3.31060E-08 3.37110E-08 631640 + 799 631650 Eu-165 7.15470E-09 7.16540E-09 631650 + 800 631660 Eu-166 2.65250E-10 2.65250E-10 631660 + 801 631670 Eu-167 1.35250E-11 1.35250E-11 631670 + 802 641570 Gd-157 1.64820E-11 1.91900E-05 64157.82c + 803 641580 Gd-158 1.04190E-09 1.95890E-05 64158.82c + 804 641590 Gd-159 1.81070E-08 3.15670E-05 641590 + 805 641600 Gd-160 5.42470E-08 5.52680E-06 64160.82c + 806 641610 Gd-161 8.25250E-08 3.07700E-06 641610 + 807 641620 Gd-162 4.47860E-07 1.37100E-06 641620 + 808 641630 Gd-163 2.41390E-07 5.94500E-07 641630 + 809 641640 Gd-164 2.14260E-07 2.47970E-07 641640 + 810 641650 Gd-165 5.68030E-08 6.39680E-08 641650 + 811 641660 Gd-166 2.28210E-08 2.30860E-08 641660 + 812 641670 Gd-167 1.70330E-09 1.71680E-09 641670 + 813 641680 Gd-168 2.51750E-10 2.51750E-10 641680 + 814 641690 Gd-169 7.80470E-12 7.80470E-12 641690 + 815 651590 Tb-159 4.03620E-12 3.15670E-05 65159.82c + 816 651600 Tb-160 1.96750E-11 1.96750E-11 65160.82c + 817 651610 Tb-161 3.81680E-10 3.07740E-06 651610 + 818 651620 Tb-162 3.10890E-09 1.37420E-06 651620 + 819 651630 Tb-163 1.87670E-08 6.13270E-07 651630 + 820 651640 Tb-164 2.11320E-08 2.69100E-07 651640 + 821 651650 Tb-165 5.27020E-08 1.16670E-07 651650 + 822 651660 Tb-166 2.39880E-08 4.70740E-08 651660 + 823 651670 Tb-167 1.69600E-08 1.86770E-08 651670 + 824 651680 Tb-168 3.21190E-09 3.46370E-09 651680 + 825 651690 Tb-169 1.12550E-09 1.13330E-09 651690 + 826 651700 Tb-170 6.29400E-11 6.29400E-11 651700 + 827 651710 Tb-171 6.97520E-12 6.97520E-12 651710 + 828 661620 Dy-162 1.64440E-12 1.37420E-06 66162.82c + 829 661630 Dy-163 1.62210E-11 6.13280E-07 66163.82c + 830 661640 Dy-164 2.27400E-10 2.69330E-07 66164.82c + 831 661650 Dy-165 7.26860E-10 1.17490E-07 661650 + 832 661651 Dy-165m 9.67780E-11 9.67780E-11 661651 + 833 661660 Dy-166 4.02280E-09 5.10970E-08 661660 + 834 661670 Dy-167 3.45750E-09 2.21340E-08 661670 + 835 661680 Dy-168 6.01830E-09 9.48200E-09 661680 + 836 661690 Dy-169 2.41300E-09 3.54630E-09 661690 + 837 661700 Dy-170 1.32640E-09 1.38930E-09 661700 + 838 661710 Dy-171 1.96970E-10 2.03950E-10 661710 + 839 661720 Dy-172 5.60600E-11 5.60600E-11 661720 + 840 661730 Dy-173 2.59090E-12 2.59090E-12 661730 + 841 671660 Ho-166 1.63070E-12 5.10990E-08 671660 + 842 671661 Ho-166m 4.44500E-12 4.44500E-12 671661 + 843 671670 Ho-167 6.32890E-11 2.21980E-08 671670 + 844 671680 Ho-168 5.76230E-11 9.63550E-09 671680 + 845 671681 Ho-168m 9.63670E-11 9.63670E-11 671681 + 846 671690 Ho-169 6.33510E-10 4.17980E-09 671690 + 847 671700 Ho-170 2.98750E-10 2.98750E-10 671700 + 848 671701 Ho-170m 1.09600E-10 1.49890E-09 671701 + 849 671710 Ho-171 5.52870E-10 7.56820E-10 671710 + 850 671720 Ho-172 1.84560E-10 2.40620E-10 671720 + 851 671730 Ho-173 8.75410E-11 9.01320E-11 671730 + 852 671740 Ho-174 8.88740E-12 8.88740E-12 671740 + 853 671750 Ho-175 2.03100E-12 2.03100E-12 671750 + 854 681690 Er-169 2.22950E-12 4.18200E-09 681690 + 855 681700 Er-170 1.68630E-11 1.81450E-09 68170.82c + 856 681710 Er-171 3.05860E-11 7.87400E-10 681710 + 857 681720 Er-172 1.00340E-10 3.40960E-10 681720 + 858 681730 Er-173 5.44500E-11 1.44580E-10 681730 + 859 681740 Er-174 5.08140E-11 5.97010E-11 681740 + 860 681750 Er-175 1.41190E-11 1.61500E-11 681750 + 861 681760 Er-176 5.81930E-12 5.81930E-12 681760 + 862 691730 Tm-173 3.68960E-12 1.48270E-10 691730 + 863 691740 Tm-174 4.41070E-12 6.41120E-11 691740 + 864 691750 Tm-175 1.16080E-11 2.77580E-11 691750 + 865 691760 Tm-176 5.41970E-12 1.12390E-11 691760 + 866 691770 Tm-177 4.04920E-12 4.04920E-12 691770 + 867 701780 Yb-178 1.35910E-12 1.35910E-12 701780 + + Neutron-induced fission: + + Interpolation region : 3 / 3 + Interpolation energy : 1.40000E+01 MeV + Number of products : 1112 / 1173 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 2.63690E-05 2.63690E-05 1001.82c + 2 10020 H-2 8.05870E-06 8.05870E-06 1002.82c + 3 10030 H-3 1.74200E-04 1.74200E-04 1003.82c + 4 20040 He-4 1.66700E-03 1.66700E-03 2004.82c + 5 190500 K-50 1.90050E-11 1.90050E-11 190500 + 6 190510 K-51 4.31580E-12 4.31580E-12 190510 + 7 200500 Ca-50 9.08480E-10 9.24000E-10 200500 + 8 200510 Ca-51 3.74840E-10 3.77130E-10 200510 + 9 200520 Ca-52 2.00070E-10 2.00070E-10 200520 + 10 200530 Ca-53 3.51760E-11 3.51760E-11 200530 + 11 200540 Ca-54 6.14320E-12 6.14320E-12 200540 + 12 210500 Sc-50 8.39740E-10 1.93580E-09 210500 + 13 210501 Sc-50m 1.85960E-10 1.11000E-09 210501 + 14 210510 Sc-51 2.38080E-09 2.76190E-09 210510 + 15 210520 Sc-52 2.08490E-09 2.29150E-09 210520 + 16 210530 Sc-53 2.33760E-09 2.36220E-09 210530 + 17 210540 Sc-54 7.59750E-10 7.65890E-10 210540 + 18 210550 Sc-55 3.35970E-10 3.35970E-10 210550 + 19 210560 Sc-56 4.84650E-11 4.84650E-11 210560 + 20 210570 Sc-57 6.97430E-12 6.97430E-12 210570 + 21 220500 Ti-50 1.70720E-10 2.12040E-09 22050.82c + 22 220510 Ti-51 6.30740E-10 3.39270E-09 220510 + 23 220520 Ti-52 3.05540E-09 5.34690E-09 220520 + 24 220530 Ti-53 5.20530E-09 7.56750E-09 220530 + 25 220540 Ti-54 9.73550E-09 1.05010E-08 220540 + 26 220550 Ti-55 7.27750E-09 7.61350E-09 220550 + 27 220560 Ti-56 6.88090E-09 6.93170E-09 220560 + 28 220570 Ti-57 1.88180E-09 1.88650E-09 220570 + 29 220580 Ti-58 5.98140E-10 5.98140E-10 220580 + 30 220590 Ti-59 7.11010E-11 7.11010E-11 220590 + 31 220600 Ti-60 2.53170E-11 2.53170E-11 220600 + 32 220610 Ti-61 2.29120E-12 2.29120E-12 220610 + 33 230510 V-51 1.32070E-11 3.40590E-09 230510 + 34 230520 V-52 1.12910E-10 5.45980E-09 230520 + 35 230530 V-53 1.15320E-09 8.72070E-09 230530 + 36 230540 V-54 3.35270E-09 1.38540E-08 230540 + 37 230550 V-55 1.37700E-08 2.13840E-08 230550 + 38 230560 V-56 2.00560E-08 2.69930E-08 230560 + 39 230570 V-57 3.24340E-08 3.43150E-08 230570 + 40 230580 V-58 1.79510E-08 1.85490E-08 230580 + 41 230590 V-59 1.43380E-08 1.44090E-08 230590 + 42 230600 V-60 9.87810E-09 9.90340E-09 230600 + 43 230610 V-61 6.54710E-09 6.54940E-09 230610 + 44 230620 V-62 5.03250E-10 5.03250E-10 230620 + 45 230630 V-63 7.57830E-12 7.57830E-12 230630 + 46 240530 Cr-53 7.70600E-12 8.72840E-09 24053.82c + 47 240540 Cr-54 1.48610E-10 1.40030E-08 24054.82c + 48 240550 Cr-55 1.04640E-09 2.24300E-08 240550 + 49 240560 Cr-56 8.87920E-09 3.60100E-08 240560 + 50 240570 Cr-57 2.19370E-08 7.09540E-08 240570 + 51 240580 Cr-58 6.68770E-08 7.05870E-08 240580 + 52 240590 Cr-59 8.40260E-08 9.84350E-08 240590 + 53 240600 Cr-60 7.09580E-07 7.19880E-07 240600 + 54 240610 Cr-61 4.18520E-07 4.24680E-07 240610 + 55 240620 Cr-62 2.20930E-07 2.21440E-07 240620 + 56 240630 Cr-63 6.52760E-09 6.53250E-09 240630 + 57 240640 Cr-64 1.47190E-09 1.47190E-09 240640 + 58 240650 Cr-65 2.47990E-11 2.47990E-11 240650 + 59 240660 Cr-66 5.76520E-12 5.76520E-12 240660 + 60 250550 Mn-55 5.25510E-12 2.24350E-08 25055.82c + 61 250560 Mn-56 8.38420E-11 3.60940E-08 250560 + 62 250570 Mn-57 1.33850E-09 7.22920E-08 250570 + 63 250580 Mn-58 6.39340E-09 7.69800E-08 250580 + 64 250581 Mn-58m 3.95090E-10 3.95090E-10 250581 + 65 250590 Mn-59 4.84610E-08 1.46900E-07 250590 + 66 250600 Mn-60 1.79150E-08 7.71130E-07 250600 + 67 250601 Mn-60m 2.89910E-07 2.89910E-07 250601 + 68 250610 Mn-61 1.84370E-06 2.26840E-06 250610 + 69 250620 Mn-62 9.06950E-07 1.01770E-06 250620 + 70 250621 Mn-62m 8.91510E-08 1.99870E-07 250621 + 71 250630 Mn-63 3.21740E-07 3.28270E-07 250630 + 72 250640 Mn-64 1.33290E-07 1.34760E-07 250640 + 73 250650 Mn-65 1.57120E-08 1.57370E-08 250650 + 74 250660 Mn-66 7.24260E-09 7.24840E-09 250660 + 75 250670 Mn-67 1.50580E-09 1.50580E-09 250670 + 76 250680 Mn-68 3.34870E-11 3.34870E-11 250680 + 77 250690 Mn-69 4.86950E-12 4.86950E-12 250690 + 78 260570 Fe-57 2.08630E-12 7.22940E-08 26057.82c + 79 260580 Fe-58 7.40590E-11 7.74490E-08 26058.82c + 80 260590 Fe-59 9.71830E-10 1.47870E-07 260590 + 81 260600 Fe-60 3.87650E-08 1.06650E-06 260600 + 82 260610 Fe-61 9.21850E-07 3.19020E-06 260610 + 83 260620 Fe-62 2.98830E-06 4.20580E-06 260620 + 84 260630 Fe-63 5.52250E-07 8.80520E-07 260630 + 85 260640 Fe-64 8.26100E-07 9.60860E-07 260640 + 86 260650 Fe-65 6.56230E-07 6.71970E-07 260650 + 87 260660 Fe-66 1.06290E-06 1.07020E-06 260660 + 88 260670 Fe-67 2.96140E-07 2.97650E-07 260670 + 89 260680 Fe-68 4.68290E-08 4.68640E-08 260680 + 90 260690 Fe-69 1.43030E-08 1.43070E-08 260690 + 91 260700 Fe-70 1.37510E-09 1.37510E-09 260700 + 92 260710 Fe-71 4.84860E-11 4.84860E-11 260710 + 93 260720 Fe-72 4.17800E-12 4.17800E-12 260720 + 94 270590 Co-59 1.11040E-12 1.47870E-07 27059.82c + 95 270600 Co-60 7.14030E-11 8.71760E-11 270600 + 96 270601 Co-60m 1.58120E-11 1.58120E-11 270601 + 97 270610 Co-61 6.40260E-09 3.19660E-06 270610 + 98 270620 Co-62 9.88230E-09 4.21620E-06 270620 + 99 270621 Co-62m 4.46260E-08 4.46260E-08 270621 + 100 270630 Co-63 9.32300E-08 9.73750E-07 270630 + 101 270640 Co-64 3.45230E-07 1.30610E-06 270640 + 102 270650 Co-65 3.72730E-07 1.04470E-06 270650 + 103 270660 Co-66 1.06290E-06 2.13300E-06 270660 + 104 270670 Co-67 6.12020E-07 9.09670E-07 270670 + 105 270680 Co-68 9.40630E-07 1.16820E-06 270680 + 106 270681 Co-68m 4.07370E-07 4.55230E-07 270681 + 107 270690 Co-69 1.41570E-06 1.42900E-06 270690 + 108 270700 Co-70 1.94850E-07 1.94850E-07 270700 + 109 270701 Co-70m 1.94850E-07 1.96220E-07 270701 + 110 270710 Co-71 9.84070E-08 9.84560E-08 270710 + 111 270720 Co-72 1.41220E-08 1.41260E-08 270720 + 112 270730 Co-73 1.96210E-09 1.96210E-09 270730 + 113 270740 Co-74 6.76160E-11 6.76160E-11 270740 + 114 280610 Ni-61 2.21730E-12 3.19660E-06 28061.82c + 115 280620 Ni-62 1.37900E-10 4.26050E-06 28062.82c + 116 280630 Ni-63 4.56760E-10 9.74210E-07 280630 + 117 280640 Ni-64 8.26100E-07 2.13220E-06 28064.82c + 118 280650 Ni-65 2.13870E-08 1.06610E-06 280650 + 119 280660 Ni-66 1.06290E-06 3.19590E-06 280660 + 120 280670 Ni-67 5.50820E-06 6.41790E-06 280670 + 121 280680 Ni-68 2.02200E-06 3.43220E-06 280680 + 122 280690 Ni-69 6.72450E-06 8.13920E-06 280690 + 123 280691 Ni-69m 6.72450E-06 6.72450E-06 280691 + 124 280700 Ni-70 1.09020E-05 1.12930E-05 280700 + 125 280710 Ni-71 6.93040E-06 7.02890E-06 280710 + 126 280720 Ni-72 6.47070E-06 6.48480E-06 280720 + 127 280730 Ni-73 3.19680E-06 3.19880E-06 280730 + 128 280740 Ni-74 1.04030E-06 1.04040E-06 280740 + 129 280750 Ni-75 2.04040E-08 2.04040E-08 280750 + 130 280760 Ni-76 1.70790E-09 1.70790E-09 280760 + 131 280770 Ni-77 5.43530E-11 5.43530E-11 280770 + 132 290640 Cu-64 5.80660E-12 5.80660E-12 290640 + 133 290650 Cu-65 7.82940E-11 1.06620E-06 29065.82c + 134 290660 Cu-66 4.00420E-09 3.20000E-06 290660 + 135 290670 Cu-67 9.20580E-08 6.50990E-06 290670 + 136 290680 Cu-68 1.22190E-07 4.01790E-06 290680 + 137 290681 Cu-68m 5.51800E-07 5.51800E-07 290681 + 138 290690 Cu-69 1.41570E-06 1.62790E-05 290690 + 139 290700 Cu-70 2.93050E-07 3.56060E-06 290700 + 140 290701 Cu-70m 5.95580E-06 6.53520E-06 290701 + 141 290702 Cu-70m 2.93050E-07 1.15860E-05 290702 + 142 290710 Cu-71 1.00110E-05 1.70400E-05 290710 + 143 290720 Cu-72 2.75000E-05 3.39850E-05 290720 + 144 290730 Cu-73 4.36890E-05 4.68880E-05 290730 + 145 290740 Cu-74 2.08070E-05 2.18480E-05 290740 + 146 290750 Cu-75 1.22630E-05 1.22830E-05 290750 + 147 290760 Cu-76 2.51930E-06 2.52010E-06 290760 + 148 290761 Cu-76m 2.51930E-06 2.52010E-06 290761 + 149 290770 Cu-77 3.24320E-07 3.24370E-07 290770 + 150 290780 Cu-78 2.20590E-08 2.20590E-08 290780 + 151 290790 Cu-79 1.52330E-09 1.52330E-09 290790 + 152 300660 Zn-66 2.23550E-12 3.20000E-06 300660 + 153 300670 Zn-67 1.04020E-10 6.51000E-06 300670 + 154 300680 Zn-68 1.85130E-09 4.10800E-06 300680 + 155 300690 Zn-69 6.96860E-09 1.63420E-05 300690 + 156 300691 Zn-69m 5.54740E-08 5.54740E-08 300691 + 157 300700 Zn-70 7.26820E-07 1.85620E-05 300700 + 158 300710 Zn-71 7.73430E-07 1.78130E-05 300710 + 159 300711 Zn-71m 6.15700E-06 6.15700E-06 300711 + 160 300720 Zn-72 2.02200E-05 5.42050E-05 300720 + 161 300730 Zn-73 3.55370E-06 8.20940E-05 300730 + 162 300731 Zn-73m 5.05560E-06 3.16530E-05 300731 + 163 300732 Zn-73m 5.31950E-05 5.31950E-05 300732 + 164 300740 Zn-74 1.41480E-04 1.63760E-04 300740 + 165 300750 Zn-75 1.67590E-04 1.79520E-04 300750 + 166 300760 Zn-76 1.56200E-04 1.61170E-04 300760 + 167 300770 Zn-77 7.36270E-05 7.70190E-05 300770 + 168 300771 Zn-77m 6.13360E-06 6.13360E-06 300771 + 169 300780 Zn-78 6.72790E-05 6.73020E-05 300780 + 170 300790 Zn-79 1.32790E-05 1.32800E-05 300790 + 171 300800 Zn-80 1.95170E-06 1.95170E-06 300800 + 172 300810 Zn-81 1.93050E-08 1.93050E-08 300810 + 173 300820 Zn-82 1.00290E-09 1.00290E-09 300820 + 174 310690 Ga-69 5.14010E-11 1.63420E-05 310690 + 175 310700 Ga-70 1.09520E-09 1.09520E-09 310700 + 176 310710 Ga-71 3.07540E-08 2.40010E-05 310710 + 177 310720 Ga-72 2.28520E-06 5.66310E-05 310720 + 178 310721 Ga-72m 1.41220E-07 1.94740E-06 310721 + 179 310730 Ga-73 6.39350E-06 1.15090E-04 310730 + 180 310740 Ga-74 1.09240E-05 1.41930E-04 310740 + 181 310741 Ga-74m 1.09240E-05 1.74680E-04 310741 + 182 310750 Ga-75 6.94900E-05 2.49010E-04 310750 + 183 310760 Ga-76 1.74330E-04 3.35490E-04 310760 + 184 310770 Ga-77 3.80470E-04 4.60560E-04 310770 + 185 310780 Ga-78 3.45710E-04 4.13180E-04 310780 + 186 310790 Ga-79 3.65060E-04 3.78170E-04 310790 + 187 310800 Ga-80 1.34180E-04 1.36130E-04 310800 + 188 310810 Ga-81 5.57590E-05 5.57770E-05 310810 + 189 310820 Ga-82 6.29030E-06 6.29130E-06 310820 + 190 310830 Ga-83 3.67330E-07 3.67330E-07 310830 + 191 310840 Ga-84 1.21810E-08 1.21810E-08 310840 + 192 310850 Ga-85 5.79500E-10 5.79500E-10 310850 + 193 320710 Ge-71 8.54350E-13 7.65550E-12 320710 + 194 320711 Ge-71m 6.80110E-12 6.80110E-12 320711 + 195 320720 Ge-72 8.94100E-10 5.66320E-05 32072.82c + 196 320730 Ge-73 2.43180E-08 1.15110E-04 32073.82c + 197 320731 Ge-73m 3.05480E-09 1.13400E-04 320731 + 198 320740 Ge-74 2.08070E-06 1.87690E-04 32074.82c + 199 320750 Ge-75 7.07260E-07 2.58200E-04 320750 + 200 320751 Ge-75m 8.48980E-06 1.84500E-05 320751 + 201 320760 Ge-76 6.34830E-05 3.98980E-04 32076.82c + 202 320770 Ge-77 1.96340E-04 2.86960E-04 320770 + 203 320771 Ge-77m 1.63570E-05 4.76910E-04 320771 + 204 320780 Ge-78 7.56570E-04 1.17010E-03 320780 + 205 320790 Ge-79 1.01010E-04 5.26790E-04 320790 + 206 320791 Ge-79m 1.21250E-03 1.21310E-03 320791 + 207 320800 Ge-80 1.97740E-03 2.12020E-03 320800 + 208 320810 Ge-81 1.51040E-03 1.53910E-03 320810 + 209 320811 Ge-81m 1.89730E-04 2.13590E-04 320811 + 210 320820 Ge-82 1.32260E-03 1.32770E-03 320820 + 211 320830 Ge-83 3.06810E-04 3.07050E-04 320830 + 212 320840 Ge-84 7.77750E-05 7.77790E-05 320840 + 213 320850 Ge-85 1.63170E-05 1.63180E-05 320850 + 214 320860 Ge-86 2.10750E-07 2.10750E-07 320860 + 215 320870 Ge-87 4.46920E-09 4.46920E-09 320870 + 216 330730 As-73 3.82470E-12 3.82470E-12 330730 + 217 330740 As-74 2.79470E-10 2.79470E-10 330740 + 218 330750 As-75 2.07420E-09 2.58220E-04 33075.82c + 219 330751 As-75m 1.28160E-08 1.83510E-08 330751 + 220 330760 As-76 2.74630E-07 2.74630E-07 330760 + 221 330770 As-77 5.11040E-06 6.78370E-04 330770 + 222 330780 As-78 3.80230E-05 1.20810E-03 330780 + 223 330790 As-79 2.23560E-04 1.91490E-03 330790 + 224 330800 As-80 6.89280E-04 2.80940E-03 330800 + 225 330810 As-81 1.73760E-03 3.48820E-03 330810 + 226 330820 As-82 4.04610E-04 1.73230E-03 330820 + 227 330821 As-82m 2.28920E-03 2.28920E-03 330821 + 228 330830 As-83 2.94580E-03 3.26120E-03 330830 + 229 330840 As-84 7.19150E-04 7.54980E-04 330840 + 230 330841 As-84m 7.19150E-04 7.54980E-04 330841 + 231 330850 As-85 9.25250E-04 9.39280E-04 330850 + 232 330860 As-86 2.27990E-04 2.28200E-04 330860 + 233 330870 As-87 6.13240E-05 6.13290E-05 330870 + 234 330880 As-88 4.67550E-06 4.67550E-06 330880 + 235 330890 As-89 7.58720E-08 7.58720E-08 330890 + 236 330900 As-90 1.05170E-09 1.05170E-09 330900 + 237 340760 Se-76 1.17790E-10 2.74750E-07 34076.82c + 238 340770 Se-77 3.98470E-10 6.78370E-04 34077.82c + 239 340771 Se-77m 4.78320E-09 4.78320E-09 340771 + 240 340780 Se-78 2.81830E-07 1.20840E-03 34078.82c + 241 340790 Se-79 9.42760E-06 1.92410E-03 34079.82c + 242 340791 Se-79m 7.85380E-07 1.87030E-03 340791 + 243 340800 Se-80 8.88840E-05 2.89830E-03 34080.82c + 244 340810 Se-81 4.02690E-05 4.01150E-03 340810 + 245 340811 Se-81m 4.83390E-04 6.08610E-04 340811 + 246 340820 Se-82 2.51930E-03 6.54080E-03 34082.82c + 247 340830 Se-83 5.73810E-03 6.91320E-03 340830 + 248 340831 Se-83m 7.20810E-04 2.80910E-03 340831 + 249 340840 Se-84 1.12590E-02 1.29740E-02 340840 + 250 340850 Se-85 8.81740E-03 9.62530E-03 340850 + 251 340860 Se-86 6.27560E-03 6.43790E-03 340860 + 252 340870 Se-87 2.74380E-03 2.79570E-03 340870 + 253 340880 Se-88 1.31340E-03 1.31810E-03 340880 + 254 340890 Se-89 2.78290E-04 2.78370E-04 340890 + 255 340900 Se-90 4.62920E-05 4.62930E-05 340900 + 256 340910 Se-91 4.94430E-06 4.94430E-06 340910 + 257 340920 Se-92 9.65890E-07 9.65890E-07 340920 + 258 350780 Br-78 2.90250E-11 2.90250E-11 350780 + 259 350790 Br-79 3.53680E-10 1.04990E-06 35079.82c + 260 350791 Br-79m 2.18530E-09 2.18530E-09 350791 + 261 350800 Br-80 1.21970E-08 8.12040E-08 350800 + 262 350801 Br-80m 6.90070E-08 6.90070E-08 350801 + 263 350810 Br-81 4.04510E-06 4.01590E-03 35081.82c + 264 350820 Br-82 3.44510E-05 4.18970E-05 350820 + 265 350821 Br-82m 7.62910E-06 7.62910E-06 350821 + 266 350830 Br-83 3.12850E-04 1.00350E-02 350830 + 267 350840 Br-84 6.87000E-04 1.36610E-02 350840 + 268 350841 Br-84m 6.87000E-04 6.87000E-04 350841 + 269 350850 Br-85 6.73010E-03 1.63550E-02 350850 + 270 350860 Br-86 1.03870E-02 1.68250E-02 350860 + 271 350870 Br-87 1.29560E-02 1.57650E-02 350870 + 272 350880 Br-88 9.42290E-03 1.07500E-02 350880 + 273 350890 Br-89 6.84090E-03 7.09760E-03 350890 + 274 350900 Br-90 2.42840E-03 2.47570E-03 350900 + 275 350910 Br-91 8.93770E-04 8.97680E-04 350910 + 276 350920 Br-92 1.18610E-04 1.19580E-04 350920 + 277 350930 Br-93 2.23130E-05 2.23130E-05 350930 + 278 350940 Br-94 9.14320E-07 9.14320E-07 350940 + 279 350950 Br-95 3.35020E-09 3.35020E-09 350950 + 280 360810 Kr-81 5.03380E-10 5.45310E-10 360810 + 281 360811 Kr-81m 4.19340E-11 4.19340E-11 360811 + 282 360820 Kr-82 4.73890E-08 4.21270E-05 36082.82c + 283 360830 Kr-83 8.11300E-06 1.00440E-02 36083.82c + 284 360831 Kr-83m 1.01910E-06 1.00270E-02 360831 + 285 360840 Kr-84 8.46810E-05 1.44320E-02 36084.82c + 286 360850 Kr-85 5.07120E-04 4.04170E-03 36085.82c + 287 360851 Kr-85m 6.37050E-05 1.63930E-02 360851 + 288 360860 Kr-86 4.10100E-03 2.13220E-02 36086.82c + 289 360870 Kr-87 8.88570E-03 2.49750E-02 360870 + 290 360880 Kr-88 2.34200E-02 3.44500E-02 360880 + 291 360890 Kr-89 2.81260E-02 3.48320E-02 360890 + 292 360900 Kr-90 2.84840E-02 3.05300E-02 360900 + 293 360910 Kr-91 1.66030E-02 1.73610E-02 360910 + 294 360920 Kr-92 8.62470E-03 8.71990E-03 360920 + 295 360930 Kr-93 2.21420E-03 2.22200E-03 360930 + 296 360940 Kr-94 5.67720E-04 5.67990E-04 360940 + 297 360950 Kr-95 6.81050E-05 6.81080E-05 360950 + 298 360960 Kr-96 7.55590E-06 7.55590E-06 360960 + 299 360970 Kr-97 2.47890E-08 2.47890E-08 360970 + 300 370840 Rb-84 1.82950E-09 8.23010E-09 370840 + 301 370841 Rb-84m 6.40060E-09 6.40060E-09 370841 + 302 370850 Rb-85 1.01990E-06 1.69270E-02 37085.82c + 303 370860 Rb-86 4.33970E-06 1.95220E-05 37086.82c + 304 370861 Rb-86m 1.51820E-05 1.51820E-05 370861 + 305 370870 Rb-87 2.10720E-04 2.51860E-02 37087.82c + 306 370880 Rb-88 1.05020E-03 3.55000E-02 370880 + 307 370890 Rb-89 5.25190E-03 4.00840E-02 370890 + 308 370900 Rb-90 6.59520E-04 2.75780E-02 370900 + 309 370901 Rb-90m 1.06720E-02 1.46660E-02 370901 + 310 370910 Rb-91 2.27420E-02 4.01030E-02 370910 + 311 370920 Rb-92 2.39010E-02 3.26210E-02 370920 + 312 370930 Rb-93 2.18360E-02 2.40640E-02 370930 + 313 370940 Rb-94 1.00460E-02 1.06100E-02 370940 + 314 370950 Rb-95 4.57730E-03 4.64370E-03 370950 + 315 370960 Rb-96 4.96460E-04 7.50140E-04 370960 + 316 370961 Rb-96m 4.96460E-04 5.00090E-04 370961 + 317 370970 Rb-97 2.38620E-04 2.38640E-04 370970 + 318 370980 Rb-98 1.13540E-05 1.13540E-05 370980 + 319 370981 Rb-98m 1.13540E-05 1.13540E-05 370981 + 320 370990 Rb-99 4.78230E-06 4.78230E-06 370990 + 321 371000 Rb-100 3.33690E-09 3.33690E-09 371000 + 322 380860 Sr-86 1.95090E-06 2.14720E-05 38086.82c + 323 380870 Sr-87 2.38940E-06 2.68870E-06 38087.82c + 324 380871 Sr-87m 3.00160E-07 3.00160E-07 380871 + 325 380880 Sr-88 5.14810E-05 3.55520E-02 38088.82c + 326 380890 Sr-89 2.96100E-04 4.03800E-02 38089.82c + 327 380900 Sr-90 1.92720E-03 4.37890E-02 38090.82c + 328 380910 Sr-91 5.64990E-03 4.57530E-02 380910 + 329 380920 Sr-92 1.66870E-02 4.96450E-02 380920 + 330 380930 Sr-93 2.45900E-02 4.93890E-02 380930 + 331 380940 Sr-94 3.89240E-02 4.88610E-02 380940 + 332 380950 Sr-95 3.01870E-02 3.45320E-02 380950 + 333 380960 Sr-96 2.18750E-02 2.28350E-02 380960 + 334 380970 Sr-97 8.84580E-03 9.02610E-03 380970 + 335 380980 Sr-98 3.22930E-03 3.25120E-03 380980 + 336 380990 Sr-99 5.76670E-04 5.80690E-04 380990 + 337 381000 Sr-100 1.20270E-04 1.20270E-04 381000 + 338 381010 Sr-101 9.36860E-06 9.36860E-06 381010 + 339 381020 Sr-102 1.09540E-06 1.09540E-06 381020 + 340 381030 Sr-103 8.49810E-10 8.49810E-10 381030 + 341 390890 Y-89 2.33580E-09 4.03800E-02 39089.82c + 342 390891 Y-89m 1.85940E-08 3.91080E-06 390891 + 343 390900 Y-90 1.53590E-06 4.37950E-02 39090.82c + 344 390901 Y-90m 4.38980E-06 4.38980E-06 390901 + 345 390910 Y-91 5.95820E-06 4.58060E-02 39091.82c + 346 390911 Y-91m 4.74310E-05 2.69660E-02 390911 + 347 390920 Y-92 3.64890E-04 5.00100E-02 390920 + 348 390930 Y-93 1.70900E-04 5.16110E-02 390930 + 349 390931 Y-93m 2.05140E-03 1.44100E-02 390931 + 350 390940 Y-94 5.66300E-03 5.45240E-02 390940 + 351 390950 Y-95 1.43510E-02 4.88830E-02 390950 + 352 390960 Y-96 4.31770E-03 2.71550E-02 390960 + 353 390961 Y-96m 1.51050E-02 1.51070E-02 390961 + 354 390970 Y-97 3.13200E-03 1.09810E-02 390970 + 355 390971 Y-97m 1.45040E-02 2.41900E-02 390971 + 356 390972 Y-97m 1.04290E-02 1.04290E-02 390972 + 357 390980 Y-98 2.29400E-03 5.54520E-03 390980 + 358 390981 Y-98m 1.79890E-02 1.79890E-02 390981 + 359 390990 Y-99 1.36250E-02 1.42070E-02 390990 + 360 391000 Y-100 2.15930E-03 2.27880E-03 391000 + 361 391001 Y-100m 2.15930E-03 2.15950E-03 391001 + 362 391010 Y-101 1.52280E-03 1.53200E-03 391010 + 363 391020 Y-102 1.06320E-04 1.06830E-04 391020 + 364 391021 Y-102m 1.06320E-04 1.06830E-04 391021 + 365 391030 Y-103 4.72500E-05 4.72510E-05 391030 + 366 391040 Y-104 1.09560E-06 1.09560E-06 391040 + 367 391050 Y-105 2.74240E-09 2.74240E-09 391050 + 368 400910 Zr-91 9.89130E-07 4.58070E-02 40091.82c + 369 400920 Zr-92 6.76100E-06 5.00160E-02 40092.82c + 370 400930 Zr-93 4.64730E-05 5.16580E-02 40093.82c + 371 400940 Zr-94 4.75980E-04 5.50000E-02 40094.82c + 372 400950 Zr-95 1.73670E-03 5.06200E-02 40095.82c + 373 400960 Zr-96 6.65780E-03 4.89390E-02 40096.82c + 374 400970 Zr-97 1.35760E-02 5.12770E-02 400970 + 375 400980 Zr-98 2.75430E-02 5.06850E-02 400980 + 376 400990 Zr-99 2.94060E-02 4.33920E-02 400990 + 377 401000 Zr-100 2.90010E-02 3.34180E-02 401000 + 378 401010 Zr-101 1.54430E-02 1.69860E-02 401010 + 379 401020 Zr-102 7.65890E-03 7.86590E-03 401020 + 380 401030 Zr-103 2.04300E-03 2.08660E-03 401030 + 381 401040 Zr-104 5.15230E-04 5.16230E-04 401040 + 382 401050 Zr-105 7.56580E-05 7.56600E-05 401050 + 383 401060 Zr-106 7.46130E-06 7.46130E-06 401060 + 384 401070 Zr-107 3.03310E-06 3.03310E-06 401070 + 385 401080 Zr-108 5.05730E-10 5.05730E-10 401080 + 386 410940 Nb-94 1.35460E-06 1.82620E-06 41094.82c + 387 410941 Nb-94m 4.73970E-07 4.73970E-07 410941 + 388 410950 Nb-95 1.30130E-05 5.06040E-02 41095.82c + 389 410951 Nb-95m 1.63470E-06 5.48500E-04 410951 + 390 410960 Nb-96 5.53780E-05 5.53780E-05 410960 + 391 410970 Nb-97 4.53090E-04 5.17870E-02 410970 + 392 410971 Nb-97m 5.69170E-05 4.87950E-02 410971 + 393 410980 Nb-98 2.76340E-04 5.09610E-02 410980 + 394 410981 Nb-98m 1.56350E-03 1.56350E-03 410981 + 395 410990 Nb-99 5.83610E-03 3.35940E-02 410990 + 396 410991 Nb-99m 7.33120E-04 1.67010E-02 410991 + 397 411000 Nb-100 1.23170E-03 3.46500E-02 411000 + 398 411001 Nb-100m 9.65830E-03 9.65830E-03 411001 + 399 411010 Nb-101 1.92820E-02 3.62680E-02 411010 + 400 411020 Nb-102 8.28200E-03 1.61480E-02 411020 + 401 411021 Nb-102m 8.28200E-03 8.28200E-03 411021 + 402 411030 Nb-103 1.43010E-02 1.63880E-02 411030 + 403 411040 Nb-104 3.05660E-03 3.57390E-03 411040 + 404 411041 Nb-104m 3.05660E-03 3.05660E-03 411041 + 405 411050 Nb-105 2.72000E-03 2.79470E-03 411050 + 406 411060 Nb-106 9.30200E-04 9.37660E-04 411060 + 407 411070 Nb-107 2.72450E-04 2.75370E-04 411070 + 408 411080 Nb-108 5.39880E-05 5.39880E-05 411080 + 409 411090 Nb-109 1.39740E-05 1.39740E-05 411090 + 410 411100 Nb-110 1.54230E-06 1.54230E-06 411100 + 411 420960 Mo-96 1.79440E-09 5.53800E-05 42096.82c + 412 420970 Mo-97 4.35920E-06 5.17910E-02 42097.82c + 413 420980 Mo-98 5.26850E-05 5.25770E-02 42098.82c + 414 420990 Mo-99 3.39410E-04 5.03010E-02 42099.82c + 415 421000 Mo-100 1.68830E-03 4.59970E-02 42100.82c + 416 421010 Mo-101 4.38940E-03 4.06570E-02 421010 + 417 421020 Mo-102 1.07150E-02 3.51450E-02 421020 + 418 421030 Mo-103 1.34920E-02 2.98830E-02 421030 + 419 421040 Mo-104 1.42190E-02 2.08930E-02 421040 + 420 421050 Mo-105 8.36900E-03 1.11580E-02 421050 + 421 421060 Mo-106 7.93880E-03 8.85080E-03 421060 + 422 421070 Mo-107 3.46390E-03 3.72610E-03 421070 + 423 421080 Mo-108 1.64890E-03 1.70130E-03 421080 + 424 421090 Mo-109 4.41150E-04 4.53970E-04 421090 + 425 421100 Mo-110 1.49060E-04 1.49980E-04 421100 + 426 421110 Mo-111 2.51920E-05 2.51920E-05 421110 + 427 421120 Mo-112 4.45400E-06 4.45400E-06 421120 + 428 421130 Mo-113 2.90020E-10 2.90020E-10 421130 + 429 430990 Tc-99 8.98970E-09 5.02990E-02 43099.82c + 430 430991 Tc-99m 1.12930E-09 4.42950E-02 430991 + 431 431000 Tc-100 7.68940E-06 7.68940E-06 431000 + 432 431010 Tc-101 6.15230E-05 4.07180E-02 431010 + 433 431020 Tc-102 1.55790E-04 3.53010E-02 431020 + 434 431021 Tc-102m 1.55790E-04 1.55790E-04 431021 + 435 431030 Tc-103 1.30070E-03 3.11840E-02 431030 + 436 431040 Tc-104 2.47770E-03 2.33710E-02 431040 + 437 431050 Tc-105 4.90680E-03 1.60650E-02 431050 + 438 431060 Tc-106 7.75660E-03 1.66070E-02 431060 + 439 431070 Tc-107 8.99990E-03 1.27260E-02 431070 + 440 431080 Tc-108 6.57370E-03 8.27740E-03 431080 + 441 431090 Tc-109 5.26370E-03 5.71530E-03 431090 + 442 431100 Tc-110 2.46340E-03 2.61360E-03 431100 + 443 431110 Tc-111 1.17100E-03 1.19600E-03 431110 + 444 431120 Tc-112 1.67610E-04 1.71970E-04 431120 + 445 431130 Tc-113 7.81520E-05 7.81520E-05 431130 + 446 431140 Tc-114 3.52960E-06 3.52960E-06 431140 + 447 431150 Tc-115 4.18030E-09 4.18030E-09 431150 + 448 441010 Ru-101 1.10980E-09 4.07180E-02 44101.82c + 449 441020 Ru-102 3.28660E-06 3.54600E-02 44102.82c + 450 441030 Ru-103 4.65320E-06 3.12100E-02 44103.82c + 451 441031 Ru-103m 2.13570E-05 2.13570E-05 441031 + 452 441040 Ru-104 1.19870E-04 2.34910E-02 44104.82c + 453 441050 Ru-105 3.24490E-04 1.63900E-02 44105.82c + 454 441060 Ru-106 1.39220E-03 1.80000E-02 44106.82c + 455 441070 Ru-107 2.59380E-03 1.53200E-02 441070 + 456 441080 Ru-108 5.25360E-03 1.35360E-02 441080 + 457 441090 Ru-109 6.23930E-03 1.19510E-02 441090 + 458 441100 Ru-110 7.93240E-03 1.05450E-02 441100 + 459 441110 Ru-111 5.71200E-03 6.91060E-03 441110 + 460 441120 Ru-112 2.61320E-03 2.78820E-03 441120 + 461 441130 Ru-113 7.31900E-04 1.17060E-03 441130 + 462 441131 Ru-113m 7.31900E-04 7.31900E-04 441131 + 463 441140 Ru-114 5.72950E-04 5.76250E-04 441140 + 464 441150 Ru-115 8.60680E-05 8.60720E-05 441150 + 465 441160 Ru-116 3.12630E-05 3.12630E-05 441160 + 466 441170 Ru-117 1.38250E-06 1.38250E-06 441170 + 467 441180 Ru-118 8.25940E-10 8.25940E-10 441180 + 468 441190 Ru-119 1.14470E-07 1.14470E-07 441190 + 469 441200 Ru-120 4.34390E-09 4.34390E-09 441200 + 470 451040 Rh-104 3.40440E-10 2.26410E-09 451040 + 471 451041 Rh-104m 1.92620E-09 1.92620E-09 451041 + 472 451050 Rh-105 2.91280E-06 1.63930E-02 45105.82c + 473 451051 Rh-105m 2.42660E-07 4.65290E-03 451051 + 474 451060 Rh-106 3.78920E-06 1.80030E-02 451060 + 475 451061 Rh-106m 1.71110E-05 1.71110E-05 451061 + 476 451070 Rh-107 1.03190E-04 1.54230E-02 451070 + 477 451080 Rh-108 4.29380E-05 1.35790E-02 451080 + 478 451081 Rh-108m 2.42930E-04 2.42930E-04 451081 + 479 451090 Rh-109 1.04110E-03 1.29920E-02 451090 + 480 451100 Rh-110 2.21210E-03 1.27570E-02 451100 + 481 451101 Rh-110m 3.32300E-05 3.32300E-05 451101 + 482 451110 Rh-111 4.65500E-03 1.15660E-02 451110 + 483 451120 Rh-112 1.80570E-03 4.59390E-03 451120 + 484 451121 Rh-112m 1.80570E-03 1.80570E-03 451121 + 485 451130 Rh-113 7.21840E-03 8.75500E-03 451130 + 486 451140 Rh-114 2.47750E-03 3.05400E-03 451140 + 487 451141 Rh-114m 2.47750E-03 2.47750E-03 451141 + 488 451150 Rh-115 3.19690E-03 3.28310E-03 451150 + 489 451160 Rh-116 1.84110E-04 2.15060E-04 451160 + 490 451161 Rh-116m 8.31390E-04 8.31390E-04 451161 + 491 451170 Rh-117 4.25630E-04 4.26980E-04 451170 + 492 451180 Rh-118 7.12620E-05 7.12680E-05 451180 + 493 451190 Rh-119 2.92880E-05 2.93980E-05 451190 + 494 451200 Rh-120 4.56950E-06 4.57380E-06 451200 + 495 451210 Rh-121 8.06440E-07 8.06440E-07 451210 + 496 451220 Rh-122 2.16670E-08 2.16670E-08 451220 + 497 461070 Pd-107 3.23620E-07 1.54250E-02 46107.82c + 498 461071 Pd-107m 1.19290E-06 1.19290E-06 461071 + 499 461080 Pd-108 1.08090E-05 1.38320E-02 46108.82c + 500 461090 Pd-109 3.64250E-06 1.30090E-02 461090 + 501 461091 Pd-109m 1.34260E-05 6.50950E-03 461091 + 502 461100 Pd-110 1.57200E-04 1.29480E-02 46110.82c + 503 461110 Pd-111 9.15190E-05 1.18910E-02 461110 + 504 461111 Pd-111m 3.37340E-04 3.83600E-04 461111 + 505 461120 Pd-112 8.97710E-04 7.29720E-03 461120 + 506 461130 Pd-113 4.25780E-04 1.11350E-02 461130 + 507 461131 Pd-113m 1.95420E-03 1.95420E-03 461131 + 508 461140 Pd-114 4.36000E-03 9.89140E-03 461140 + 509 461150 Pd-115 1.05710E-03 4.21330E-03 461150 + 510 461151 Pd-115m 3.89630E-03 4.37300E-03 461151 + 511 461160 Pd-116 6.74800E-03 7.79440E-03 461160 + 512 461170 Pd-117 8.67790E-04 4.49560E-03 461170 + 513 461171 Pd-117m 3.19870E-03 3.19870E-03 461171 + 514 461180 Pd-118 2.50290E-03 2.57210E-03 461180 + 515 461190 Pd-119 8.09460E-04 8.39130E-04 461190 + 516 461200 Pd-120 3.16900E-04 3.21310E-04 461200 + 517 461210 Pd-121 5.27450E-05 5.34420E-05 461210 + 518 461220 Pd-122 9.49060E-06 9.51230E-06 461220 + 519 461230 Pd-123 3.43310E-06 3.43310E-06 461230 + 520 461240 Pd-124 2.46000E-07 2.46000E-07 461240 + 521 471090 Ag-109 6.60460E-11 1.30090E-02 47109.82c + 522 471091 Ag-109m 7.92800E-10 1.30030E-02 471091 + 523 471100 Ag-110 5.89210E-09 6.25390E-09 471100 + 524 471101 Ag-110m 2.66070E-08 2.66070E-08 47510.82c + 525 471110 Ag-111 3.41860E-07 1.19400E-02 47111.82c + 526 471111 Ag-111m 4.10360E-06 1.18850E-02 471111 + 527 471120 Ag-112 8.00930E-06 7.30520E-03 471120 + 528 471130 Ag-113 1.08430E-05 7.39060E-03 471130 + 529 471131 Ag-113m 1.30160E-04 1.07930E-02 471131 + 530 471140 Ag-114 4.95300E-05 1.03290E-02 471140 + 531 471141 Ag-114m 3.88400E-04 3.88400E-04 471141 + 532 471150 Ag-115 1.08140E-04 4.54020E-03 471150 + 533 471151 Ag-115m 1.29810E-03 6.45890E-03 471151 + 534 471160 Ag-116 5.09940E-04 8.44260E-03 471160 + 535 471161 Ag-116m 2.30280E-03 2.30280E-03 471161 + 536 471170 Ag-117 4.13950E-04 3.09470E-03 471170 + 537 471171 Ag-117m 4.96910E-03 7.21680E-03 471171 + 538 471180 Ag-118 6.26850E-04 4.99740E-03 471180 + 539 471181 Ag-118m 4.91560E-03 5.28330E-03 471181 + 540 471190 Ag-119 4.59530E-04 8.79100E-04 471190 + 541 471191 Ag-119m 5.51620E-03 5.93570E-03 471191 + 542 471200 Ag-120 9.06990E-04 2.08630E-03 471200 + 543 471201 Ag-120m 2.59220E-03 2.75290E-03 471201 + 544 471210 Ag-121 2.35390E-03 2.40720E-03 471210 + 545 471220 Ag-122 2.78180E-04 2.87700E-04 471220 + 546 471221 Ag-122m 5.32850E-04 5.32850E-04 471221 + 547 471230 Ag-123 3.69030E-04 3.72460E-04 471230 + 548 471240 Ag-124 3.20530E-05 6.29960E-05 471240 + 549 471241 Ag-124m 6.13950E-05 6.13950E-05 471241 + 550 471250 Ag-125 3.90480E-05 3.90480E-05 471250 + 551 471260 Ag-126 6.16500E-06 6.16500E-06 471260 + 552 471270 Ag-127 7.68550E-08 7.68550E-08 471270 + 553 471280 Ag-128 1.03500E-09 1.03500E-09 471280 + 554 481120 Cd-112 3.71500E-09 7.30520E-03 48112.82c + 555 481130 Cd-113 1.90670E-08 1.11480E-02 48113.82c + 556 481131 Cd-113m 1.17810E-07 1.27890E-04 481131 + 557 481140 Cd-114 1.40950E-05 1.03440E-02 48114.82c + 558 481150 Cd-115 9.82570E-06 9.24240E-03 481150 + 559 481151 Cd-115m 6.07100E-05 4.70880E-04 48515.82c + 560 481160 Cd-116 3.78670E-04 1.09860E-02 48116.82c + 561 481170 Cd-117 1.37260E-04 7.81150E-03 481170 + 562 481171 Cd-117m 8.48120E-04 3.05240E-03 481171 + 563 481180 Cd-118 2.70790E-03 1.08220E-02 481180 + 564 481190 Cd-119 7.20560E-04 7.09590E-03 481190 + 565 481191 Cd-119m 3.30710E-03 3.74670E-03 481191 + 566 481200 Cd-120 6.57900E-03 1.04000E-02 481200 + 567 481210 Cd-121 1.04340E-03 3.19910E-03 481210 + 568 481211 Cd-121m 4.78910E-03 5.04060E-03 481211 + 569 481220 Cd-122 5.89640E-03 6.71690E-03 481220 + 570 481230 Cd-123 6.10140E-04 9.14910E-04 481230 + 571 481231 Cd-123m 2.80040E-03 2.86810E-03 481231 + 572 481240 Cd-124 2.51190E-03 2.60550E-03 481240 + 573 481250 Cd-125 2.05770E-04 2.25300E-04 481250 + 574 481251 Cd-125m 9.44430E-04 9.63950E-04 481251 + 575 481260 Cd-126 5.92890E-04 5.99060E-04 481260 + 576 481270 Cd-127 1.57760E-04 1.57840E-04 481270 + 577 481280 Cd-128 4.23390E-05 4.23400E-05 481280 + 578 481290 Cd-129 1.19240E-06 1.19240E-06 481290 + 579 481291 Cd-129m 5.47300E-06 5.47300E-06 481291 + 580 481300 Cd-130 8.82100E-07 8.82100E-07 481300 + 581 491140 In-114 3.76150E-11 2.42980E-10 491140 + 582 491141 In-114m 6.97700E-11 2.12820E-10 491141 + 583 491142 In-114m 1.43050E-10 1.43050E-10 491142 + 584 491150 In-115 1.97110E-08 9.25110E-03 49115.82c + 585 491151 In-115m 2.47610E-09 9.24240E-03 491151 + 586 491160 In-116 5.85480E-07 5.85480E-07 491160 + 587 491161 In-116m 1.08600E-06 3.31250E-06 491161 + 588 491162 In-116m 2.22650E-06 2.22650E-06 491162 + 589 491170 In-117 1.84130E-05 7.07190E-03 491170 + 590 491171 In-117m 2.31300E-06 7.20750E-03 491171 + 591 491180 In-118 1.31610E-05 1.08350E-02 491180 + 592 491181 In-118m 2.44110E-05 7.37600E-05 491181 + 593 491182 In-118m 5.00490E-05 5.00490E-05 491182 + 594 491190 In-119 4.18600E-04 5.20920E-03 491190 + 595 491191 In-119m 5.25840E-05 6.46670E-03 491191 + 596 491200 In-120 3.72500E-04 1.07720E-02 491200 + 597 491201 In-120m 3.72500E-04 3.72500E-04 491201 + 598 491202 In-120m 3.72500E-04 3.72500E-04 491202 + 599 491210 In-121 2.57840E-03 8.72580E-03 491210 + 600 491211 In-121m 3.23900E-04 2.44560E-03 491211 + 601 491220 In-122 1.05240E-03 7.76930E-03 491220 + 602 491221 In-122m 1.50380E-03 1.50380E-03 491221 + 603 491222 In-122m 1.50380E-03 1.50380E-03 491222 + 604 491230 In-123 6.17900E-03 9.29550E-03 491230 + 605 491231 In-123m 7.76200E-04 1.44270E-03 491231 + 606 491240 In-124 2.09420E-03 4.69970E-03 491240 + 607 491241 In-124m 4.01130E-03 4.01130E-03 491241 + 608 491250 In-125 6.67120E-03 7.74300E-03 491250 + 609 491251 In-125m 8.38030E-04 9.55490E-04 491251 + 610 491260 In-126 1.75980E-03 2.35890E-03 491260 + 611 491261 In-126m 3.37080E-03 3.37080E-03 491261 + 612 491270 In-127 4.03630E-03 4.03630E-03 491270 + 613 491271 In-127m 5.07030E-04 6.64870E-04 491271 + 614 491280 In-128 4.46310E-04 6.46290E-04 491280 + 615 491281 In-128m 1.57640E-04 1.99980E-04 491281 + 616 491282 In-128m 1.15720E-03 1.15720E-03 491282 + 617 491290 In-129 5.81710E-04 5.87190E-04 491290 + 618 491291 In-129m 7.30730E-05 7.42810E-05 491291 + 619 491300 In-130 2.83430E-05 2.91940E-05 491300 + 620 491301 In-130m 9.18590E-05 9.18590E-05 491301 + 621 491302 In-130m 6.84980E-05 6.84980E-05 491302 + 622 491310 In-131 1.02260E-05 1.03300E-05 491310 + 623 491311 In-131m 1.02260E-05 1.02260E-05 491311 + 624 491312 In-131m 1.02260E-05 1.02260E-05 491312 + 625 491320 In-132 8.88760E-07 8.88760E-07 491320 + 626 491330 In-133 4.95950E-09 5.58250E-09 491330 + 627 491331 In-133m 6.23010E-10 6.23010E-10 491331 + 628 501170 Sn-117 3.77380E-10 1.08850E-02 50117.82c + 629 501171 Sn-117m 2.33170E-09 2.40970E-05 501171 + 630 501180 Sn-118 1.41450E-06 1.09110E-02 50118.82c + 631 501190 Sn-119 1.21980E-06 1.13220E-02 50119.82c + 632 501191 Sn-119m 7.53670E-06 4.71350E-03 501191 + 633 501200 Sn-120 5.18210E-05 1.15690E-02 50120.82c + 634 501210 Sn-121 3.09030E-05 1.10620E-02 501210 + 635 501211 Sn-121m 1.41840E-04 1.13030E-03 501211 + 636 501220 Sn-122 7.67350E-04 1.15440E-02 50122.82c + 637 501230 Sn-123 1.29180E-03 2.00050E-03 50123.82c + 638 501231 Sn-123m 2.81460E-04 1.03110E-02 501231 + 639 501240 Sn-124 4.35720E-03 1.30680E-02 50124.82c + 640 501250 Sn-125 4.88600E-03 6.19390E-03 50125.82c + 641 501251 Sn-125m 1.06450E-03 8.45510E-03 501251 + 642 501260 Sn-126 1.12480E-02 1.69820E-02 50126.82c + 643 501270 Sn-127 1.00340E-02 1.16070E-02 501270 + 644 501271 Sn-127m 2.18620E-03 5.30950E-03 501271 + 645 501280 Sn-128 2.30180E-03 1.45000E-02 501280 + 646 501281 Sn-128m 1.03940E-02 1.15510E-02 501281 + 647 501290 Sn-129 1.22460E-03 1.82370E-03 501290 + 648 501291 Sn-129m 5.62040E-03 5.68290E-03 501291 + 649 501300 Sn-130 1.22330E-03 1.31260E-03 501300 + 650 501301 Sn-130m 5.52400E-03 5.62440E-03 501301 + 651 501310 Sn-131 5.81250E-04 6.01060E-04 501310 + 652 501311 Sn-131m 2.66770E-03 2.67840E-03 501311 + 653 501320 Sn-132 9.68970E-04 9.69860E-04 501320 + 654 501330 Sn-133 7.57720E-05 7.57730E-05 501330 + 655 501340 Sn-134 6.17330E-06 6.17330E-06 501340 + 656 501350 Sn-135 4.08940E-08 4.08940E-08 501350 + 657 501360 Sn-136 1.95700E-09 1.95700E-09 501360 + 658 511210 Sb-121 3.18580E-06 1.13180E-02 51121.82c + 659 511220 Sb-122 1.43340E-06 4.74310E-06 511220 + 660 511221 Sb-122m 3.30970E-06 3.30970E-06 511221 + 661 511230 Sb-123 6.58340E-05 1.23770E-02 51123.82c + 662 511240 Sb-124 4.66720E-05 1.69130E-04 51124.82c + 663 511241 Sb-124m 4.33550E-05 1.63280E-04 511241 + 664 511242 Sb-124m 1.19920E-04 1.19920E-04 511242 + 665 511250 Sb-125 7.98120E-04 1.54470E-02 51125.82c + 666 511260 Sb-126 9.38430E-04 1.03710E-03 51126.82c + 667 511261 Sb-126m 3.39260E-04 7.04470E-04 511261 + 668 511262 Sb-126m 3.65220E-04 3.65220E-04 511262 + 669 511270 Sb-127 4.75560E-03 2.16720E-02 511270 + 670 511280 Sb-128 3.41650E-03 1.80080E-02 511280 + 671 511281 Sb-128m 2.56470E-03 2.56470E-03 511281 + 672 511290 Sb-129 4.12930E-03 1.00620E-02 511290 + 673 511291 Sb-129m 5.60740E-03 8.44880E-03 511291 + 674 511300 Sb-130 6.90250E-03 1.10270E-02 511300 + 675 511301 Sb-130m 6.90250E-03 9.71470E-03 511301 + 676 511310 Sb-131 2.15880E-02 2.48680E-02 511310 + 677 511320 Sb-132 4.77490E-03 5.74480E-03 511320 + 678 511321 Sb-132m 7.59210E-03 7.59210E-03 511321 + 679 511330 Sb-133 7.71650E-03 7.79330E-03 511330 + 680 511340 Sb-134 2.19050E-04 2.24170E-04 511340 + 681 511341 Sb-134m 9.89150E-04 9.89160E-04 511341 + 682 511350 Sb-135 2.25870E-04 2.25900E-04 511350 + 683 511360 Sb-136 2.31630E-05 2.31640E-05 511360 + 684 511370 Sb-137 9.59920E-07 9.59920E-07 511370 + 685 511380 Sb-138 6.22650E-09 6.22650E-09 511380 + 686 521240 Te-124 4.91020E-10 2.09950E-04 52124.82c + 687 521250 Te-125 3.48420E-06 1.54720E-02 52125.82c + 688 521251 Te-125m 2.15280E-05 3.47810E-03 521251 + 689 521260 Te-126 1.25060E-04 1.76800E-03 52126.82c + 690 521270 Te-127 5.28860E-05 2.18760E-02 521270 + 691 521271 Te-127m 2.42730E-04 3.81420E-03 52527.82c + 692 521280 Te-128 9.86400E-04 2.14680E-02 52128.82c + 693 521290 Te-129 3.30000E-04 1.53150E-02 521290 + 694 521291 Te-129m 1.51460E-03 1.01970E-02 52529.82c + 695 521300 Te-130 6.78770E-03 2.75300E-02 52130.82c + 696 521310 Te-131 2.73020E-03 2.86560E-02 521310 + 697 521311 Te-131m 1.25310E-02 1.45220E-02 521311 + 698 521320 Te-132 2.81700E-02 4.15070E-02 52132.82c + 699 521330 Te-133 6.38570E-03 1.81970E-02 521330 + 700 521331 Te-133m 2.93080E-02 3.06560E-02 521331 + 701 521340 Te-134 3.20890E-02 3.33370E-02 521340 + 702 521350 Te-135 9.10520E-03 9.29940E-03 521350 + 703 521360 Te-136 3.05470E-03 3.07450E-03 521360 + 704 521370 Te-137 6.34060E-04 6.34550E-04 521370 + 705 521380 Te-138 1.16040E-04 1.16050E-04 521380 + 706 521390 Te-139 8.72420E-06 8.72420E-06 521390 + 707 521400 Te-140 6.57340E-08 6.57340E-08 521400 + 708 521410 Te-141 1.20830E-09 1.20830E-09 521410 + 709 531270 I-127 4.40010E-06 2.19720E-02 53127.82c + 710 531280 I-128 1.19570E-05 1.19570E-05 531280 + 711 531290 I-129 5.70360E-05 1.91450E-02 53129.82c + 712 531300 I-130 1.91990E-04 2.27710E-04 53130.82c + 713 531301 I-130m 4.25170E-05 4.25170E-05 531301 + 714 531310 I-131 1.22200E-03 4.13500E-02 53131.82c + 715 531320 I-132 1.22500E-03 4.44070E-02 531320 + 716 531321 I-132m 1.94770E-03 1.94770E-03 531321 + 717 531330 I-133 5.05400E-03 5.54050E-02 531330 + 718 531331 I-133m 6.86300E-03 6.86300E-03 531331 + 719 531340 I-134 7.86990E-03 5.34320E-02 531340 + 720 531341 I-134m 1.25130E-02 1.25130E-02 531341 + 721 531350 I-135 3.42250E-02 4.35240E-02 53135.82c + 722 531360 I-136 3.50220E-03 6.58610E-03 531360 + 723 531361 I-136m 1.58150E-02 1.58240E-02 531361 + 724 531370 I-137 1.39380E-02 1.45610E-02 531370 + 725 531380 I-138 3.40990E-03 3.51860E-03 531380 + 726 531390 I-139 1.91340E-03 1.92210E-03 531390 + 727 531400 I-140 3.03120E-04 3.03190E-04 531400 + 728 531410 I-141 4.39950E-05 4.39960E-05 531410 + 729 531420 I-142 6.55330E-06 6.55330E-06 531420 + 730 531430 I-143 9.96600E-09 9.96600E-09 531430 + 731 541290 Xe-129 2.06370E-07 1.48150E-06 54129.82c + 732 541291 Xe-129m 1.27510E-06 1.27510E-06 541291 + 733 541300 Xe-130 7.93870E-06 2.42450E-04 54130.82c + 734 541310 Xe-131 6.77310E-06 4.13880E-02 54131.82c + 735 541311 Xe-131m 3.10870E-05 4.80230E-04 541311 + 736 541320 Xe-132 6.19240E-05 4.48850E-02 54132.82c + 737 541321 Xe-132m 1.42990E-04 1.42990E-04 541321 + 738 541330 Xe-133 1.59660E-04 5.62980E-02 54133.82c + 739 541331 Xe-133m 7.32820E-04 2.30990E-03 541331 + 740 541340 Xe-134 7.36400E-04 5.77820E-02 54134.82c + 741 541341 Xe-134m 3.32540E-03 3.61320E-03 541341 + 742 541350 Xe-135 2.00030E-03 5.46070E-02 54135.82c + 743 541351 Xe-135m 9.18070E-03 1.63660E-02 541351 + 744 541360 Xe-136 2.82850E-02 5.16420E-02 54136.82c + 745 541370 Xe-137 3.55650E-02 4.93660E-02 541370 + 746 541380 Xe-138 3.44600E-02 3.79810E-02 541380 + 747 541390 Xe-139 2.06160E-02 2.23780E-02 541390 + 748 541400 Xe-140 1.24990E-02 1.27830E-02 541400 + 749 541410 Xe-141 3.75470E-03 3.79110E-03 541410 + 750 541420 Xe-142 1.19980E-03 1.20470E-03 541420 + 751 541430 Xe-143 1.81900E-04 1.81910E-04 541430 + 752 541440 Xe-144 2.31730E-05 2.31730E-05 541440 + 753 541450 Xe-145 2.11930E-06 2.11930E-06 541450 + 754 541460 Xe-146 7.57990E-10 7.57990E-10 541460 + 755 551320 Cs-132 6.47890E-09 6.47890E-09 551320 + 756 551330 Cs-133 9.71900E-06 5.63070E-02 55133.82c + 757 551340 Cs-134 1.66770E-05 4.31930E-05 55134.82c + 758 551341 Cs-134m 2.65160E-05 2.65160E-05 551341 + 759 551350 Cs-135 1.48260E-04 5.50550E-02 55135.82c + 760 551351 Cs-135m 2.01320E-04 2.01320E-04 551351 + 761 551360 Cs-136 5.92300E-04 9.86800E-04 55136.82c + 762 551361 Cs-136m 7.89000E-04 7.89000E-04 551361 + 763 551370 Cs-137 7.64740E-03 5.70130E-02 55137.82c + 764 551380 Cs-138 3.10990E-03 4.82900E-02 551380 + 765 551381 Cs-138m 8.88810E-03 8.88810E-03 551381 + 766 551390 Cs-139 2.18560E-02 4.42340E-02 551390 + 767 551400 Cs-140 1.84490E-02 3.12340E-02 551400 + 768 551410 Cs-141 2.14700E-02 2.52640E-02 551410 + 769 551420 Cs-142 1.13460E-02 1.25480E-02 551420 + 770 551430 Cs-143 5.96390E-03 6.14470E-03 551430 + 771 551440 Cs-144 6.85800E-04 1.05130E-03 551440 + 772 551441 Cs-144m 6.85800E-04 6.85850E-04 551441 + 773 551450 Cs-145 2.93120E-04 2.95130E-04 551450 + 774 551460 Cs-146 4.19910E-05 4.19920E-05 551460 + 775 551470 Cs-147 3.84350E-06 3.84350E-06 551470 + 776 551480 Cs-148 8.82650E-07 8.82650E-07 551480 + 777 561340 Ba-134 2.09900E-09 4.31950E-05 56134.82c + 778 561350 Ba-135 5.93300E-07 3.31640E-06 56135.82c + 779 561351 Ba-135m 2.72310E-06 2.72310E-06 561351 + 780 561360 Ba-136 6.71640E-06 1.41840E-03 56136.82c + 781 561361 Ba-136m 3.03300E-05 3.03300E-05 561361 + 782 561370 Ba-137 5.31980E-05 5.73110E-02 56137.82c + 783 561371 Ba-137m 2.44160E-04 5.40640E-02 561371 + 784 561380 Ba-138 2.14540E-03 5.21240E-02 56138.82c + 785 561390 Ba-139 5.79770E-03 5.00320E-02 561390 + 786 561400 Ba-140 1.36950E-02 4.49290E-02 56140.82c + 787 561410 Ba-141 1.77250E-02 4.29890E-02 561410 + 788 561420 Ba-142 3.04630E-02 4.31120E-02 561420 + 789 561430 Ba-143 2.55110E-02 3.15880E-02 561430 + 790 561440 Ba-144 1.63300E-02 1.77330E-02 561440 + 791 561450 Ba-145 6.58800E-03 6.84690E-03 561450 + 792 561460 Ba-146 2.56060E-03 2.59770E-03 561460 + 793 561470 Ba-147 5.46580E-04 5.49550E-04 561470 + 794 561480 Ba-148 5.23650E-05 5.30260E-05 561480 + 795 561490 Ba-149 1.25740E-05 1.25740E-05 561490 + 796 561500 Ba-150 1.57130E-06 1.57130E-06 561500 + 797 561510 Ba-151 2.24070E-10 2.24070E-10 561510 + 798 571370 La-137 2.87990E-06 2.87990E-06 571370 + 799 571380 La-138 1.29830E-05 1.29830E-05 57138.82c + 800 571390 La-139 1.02610E-04 5.01360E-02 57139.82c + 801 571400 La-140 3.54170E-04 4.52830E-02 57140.82c + 802 571410 La-141 1.51810E-03 4.45070E-02 571410 + 803 571420 La-142 2.78780E-03 4.59000E-02 571420 + 804 571430 La-143 8.98160E-03 4.05700E-02 571430 + 805 571440 La-144 1.10740E-02 2.88070E-02 571440 + 806 571450 La-145 1.32840E-02 2.01310E-02 571450 + 807 571460 La-146 1.59610E-03 4.19390E-03 571460 + 808 571461 La-146m 5.58400E-03 5.58400E-03 571461 + 809 571470 La-147 4.81380E-03 5.36360E-03 571470 + 810 571480 La-148 8.86990E-04 9.39860E-04 571480 + 811 571490 La-149 4.23690E-04 4.36210E-04 571490 + 812 571500 La-150 9.53130E-05 9.68840E-05 571500 + 813 571510 La-151 1.30400E-05 1.30400E-05 571510 + 814 571520 La-152 3.31330E-06 3.31330E-06 571520 + 815 571530 La-153 1.08260E-09 1.08260E-09 571530 + 816 581390 Ce-139 3.90180E-07 2.18100E-06 581390 + 817 581391 Ce-139m 1.79080E-06 1.79080E-06 581391 + 818 581400 Ce-140 9.22940E-06 4.52920E-02 58140.82c + 819 581410 Ce-141 3.22370E-05 4.45390E-02 58141.82c + 820 581420 Ce-142 2.27680E-04 4.61280E-02 58142.82c + 821 581430 Ce-143 6.88330E-04 4.12580E-02 58143.82c + 822 581440 Ce-144 2.76790E-03 3.15750E-02 58144.82c + 823 581450 Ce-145 5.42050E-03 2.55510E-02 581450 + 824 581460 Ce-146 1.08060E-02 2.05840E-02 581460 + 825 581470 Ce-147 1.02570E-02 1.56210E-02 581470 + 826 581480 Ce-148 4.18630E-03 5.13230E-03 581480 + 827 581490 Ce-149 3.11380E-03 3.54650E-03 581490 + 828 581500 Ce-150 1.97480E-03 2.06910E-03 581500 + 829 581510 Ce-151 6.48380E-04 6.61620E-04 581510 + 830 581520 Ce-152 1.85150E-04 1.88260E-04 581520 + 831 581530 Ce-153 1.86020E-05 1.86030E-05 581530 + 832 581540 Ce-154 2.37430E-06 2.37430E-06 581540 + 833 581550 Ce-155 2.26660E-09 2.26660E-09 581550 + 834 581560 Ce-156 3.84740E-11 3.84740E-11 581560 + 835 591420 Pr-142 6.12430E-10 3.37800E-09 59142.82c + 836 591421 Pr-142m 2.76560E-09 2.76560E-09 591421 + 837 591430 Pr-143 4.72730E-06 4.12630E-02 59143.82c + 838 591440 Pr-144 9.21190E-07 3.15900E-02 591440 + 839 591441 Pr-144m 1.49070E-05 4.50620E-04 591441 + 840 591450 Pr-145 9.51430E-05 2.56460E-02 591450 + 841 591460 Pr-146 3.11520E-04 2.08950E-02 591460 + 842 591470 Pr-147 1.02790E-03 1.66490E-02 591470 + 843 591480 Pr-148 9.04570E-05 5.22270E-03 591480 + 844 591481 Pr-148m 7.09340E-04 7.09340E-04 591481 + 845 591490 Pr-149 2.04780E-03 5.59430E-03 591490 + 846 591500 Pr-150 2.40290E-03 4.47200E-03 591500 + 847 591510 Pr-151 2.32020E-03 2.98180E-03 591510 + 848 591520 Pr-152 1.23560E-03 1.42400E-03 591520 + 849 591530 Pr-153 5.62210E-04 5.80710E-04 591530 + 850 591540 Pr-154 1.32910E-04 1.35270E-04 591540 + 851 591550 Pr-155 3.15250E-05 3.15270E-05 591550 + 852 591560 Pr-156 3.12280E-06 3.12280E-06 591560 + 853 591570 Pr-157 7.75390E-09 7.75390E-09 591570 + 854 591580 Pr-158 9.73280E-11 9.73280E-11 591580 + 855 601440 Nd-144 1.05350E-06 3.15920E-02 60144.82c + 856 601450 Nd-145 1.05970E-06 2.56480E-02 60145.82c + 857 601460 Nd-146 7.00870E-06 2.09020E-02 60146.82c + 858 601470 Nd-147 3.17150E-05 1.66800E-02 60147.82c + 859 601480 Nd-148 7.84740E-05 6.01050E-03 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Sm-153m 2.19480E-05 2.19480E-05 621531 + 899 621540 Sm-154 8.06840E-05 1.52500E-03 62154.82c + 900 621550 Sm-155 1.02190E-04 8.21730E-04 621550 + 901 621560 Sm-156 1.59210E-04 5.16050E-04 621560 + 902 621570 Sm-157 1.62920E-04 3.32580E-04 621570 + 903 621580 Sm-158 1.45850E-04 1.80520E-04 621580 + 904 621590 Sm-159 6.54630E-05 8.60810E-05 621590 + 905 621600 Sm-160 4.73920E-05 4.78550E-05 621600 + 906 621610 Sm-161 1.43200E-05 1.43470E-05 621610 + 907 621620 Sm-162 6.42160E-07 6.42830E-07 621620 + 908 621630 Sm-163 4.53450E-08 4.53680E-08 621630 + 909 621640 Sm-164 6.98920E-10 6.98920E-10 621640 + 910 621650 Sm-165 3.70150E-11 3.70150E-11 621650 + 911 631520 Eu-152 2.40740E-11 7.96280E-11 63152.82c + 912 631521 Eu-152m 4.92130E-12 4.92130E-12 631521 + 913 631522 Eu-152m 5.55550E-11 5.55550E-11 631522 + 914 631530 Eu-153 5.18090E-09 2.30580E-03 63153.82c + 915 631540 Eu-154 2.39050E-08 6.96940E-08 63154.82c + 916 631541 Eu-154m 4.57890E-08 4.57890E-08 631541 + 917 631550 Eu-155 1.12340E-06 8.22860E-04 63155.82c + 918 631560 Eu-156 5.20330E-06 5.21250E-04 63156.82c + 919 631570 Eu-157 2.47180E-05 3.57300E-04 63157.82c + 920 631580 Eu-158 2.86920E-05 2.09220E-04 631580 + 921 631590 Eu-159 3.51560E-05 1.21240E-04 631590 + 922 631600 Eu-160 4.46840E-05 9.25380E-05 631600 + 923 631610 Eu-161 2.29120E-05 3.72590E-05 631610 + 924 631620 Eu-162 5.33120E-06 5.97400E-06 631620 + 925 631630 Eu-163 6.22120E-06 6.26660E-06 631630 + 926 631640 Eu-164 1.38560E-07 1.39260E-07 631640 + 927 631650 Eu-165 5.28140E-08 5.28510E-08 631650 + 928 631660 Eu-166 9.26870E-10 9.26870E-10 631660 + 929 631670 Eu-167 5.15900E-11 5.15900E-11 631670 + 930 641550 Gd-155 3.54310E-11 8.22860E-04 64155.82c + 931 641551 Gd-155m 1.62620E-10 1.62620E-10 641551 + 932 641560 Gd-156 6.30970E-09 5.21260E-04 64156.82c + 933 641570 Gd-157 6.91510E-08 3.57370E-04 64157.82c + 934 641580 Gd-158 3.58660E-06 2.12800E-04 64158.82c + 935 641590 Gd-159 6.06140E-06 1.27300E-04 641590 + 936 641600 Gd-160 1.35410E-05 1.06080E-04 64160.82c + 937 641610 Gd-161 1.28880E-05 5.01470E-05 641610 + 938 641620 Gd-162 2.53230E-05 3.12970E-05 641620 + 939 641630 Gd-163 1.49310E-05 2.11980E-05 641630 + 940 641640 Gd-164 4.11510E-06 4.25440E-06 641640 + 941 641650 Gd-165 4.12210E-06 4.17490E-06 641650 + 942 641660 Gd-166 1.23570E-06 1.23660E-06 641660 + 943 641670 Gd-167 2.30110E-08 2.30630E-08 641670 + 944 641680 Gd-168 2.01010E-09 2.01010E-09 641680 + 945 641690 Gd-169 8.50740E-11 8.50740E-11 641690 + 946 651570 Tb-157 1.18740E-11 1.18740E-11 651570 + 947 651580 Tb-158 2.36390E-10 2.50910E-10 651580 + 948 651581 Tb-158m 1.46080E-11 1.46080E-11 651581 + 949 651590 Tb-159 6.07060E-09 1.27310E-04 65159.82c + 950 651600 Tb-160 6.31420E-08 6.31420E-08 65160.82c + 951 651610 Tb-161 4.23330E-07 5.05710E-05 651610 + 952 651620 Tb-162 1.33280E-06 3.26300E-05 651620 + 953 651630 Tb-163 4.97690E-06 2.61750E-05 651630 + 954 651640 Tb-164 1.36510E-06 5.61950E-06 651640 + 955 651650 Tb-165 2.06100E-06 6.23590E-06 651650 + 956 651660 Tb-166 9.40580E-07 2.17720E-06 651660 + 957 651670 Tb-167 6.70830E-07 6.93890E-07 651670 + 958 651680 Tb-168 9.78160E-08 9.98260E-08 651680 + 959 651690 Tb-169 2.85940E-08 2.86790E-08 651690 + 960 651700 Tb-170 7.78410E-09 7.78410E-09 651700 + 961 651710 Tb-171 1.89970E-10 1.89970E-10 651710 + 962 661600 Dy-160 2.33810E-11 6.31650E-08 66160.82c + 963 661610 Dy-161 3.24150E-10 5.05710E-05 66161.82c + 964 661620 Dy-162 6.62360E-09 3.26360E-05 66162.82c + 965 661630 Dy-163 5.33310E-08 2.62280E-05 66163.82c + 966 661640 Dy-164 9.38030E-08 5.71330E-06 66164.82c + 967 661650 Dy-165 9.51350E-07 7.26480E-06 661650 + 968 661651 Dy-165m 7.92530E-08 7.92530E-08 661651 + 969 661660 Dy-166 6.17860E-07 2.79510E-06 661660 + 970 661670 Dy-167 6.70830E-07 1.36470E-06 661670 + 971 661680 Dy-168 5.54810E-07 6.54640E-07 661680 + 972 661690 Dy-169 5.34320E-07 5.63000E-07 661690 + 973 661700 Dy-170 4.06310E-07 4.14090E-07 661700 + 974 661710 Dy-171 2.03570E-08 2.05470E-08 661710 + 975 661720 Dy-172 4.85070E-09 4.85070E-09 661720 + 976 661730 Dy-173 1.55190E-09 1.55190E-09 661730 + 977 671630 Ho-163 2.80550E-11 3.03920E-11 671630 + 978 671631 Ho-163m 2.33710E-12 2.33710E-12 671631 + 979 671640 Ho-164 1.94500E-11 1.07280E-10 671640 + 980 671641 Ho-164m 8.78300E-11 8.78300E-11 671641 + 981 671650 Ho-165 4.71520E-09 7.27130E-06 67165.82c + 982 671660 Ho-166 1.70560E-09 2.79680E-06 671660 + 983 671661 Ho-166m 7.70220E-09 7.70220E-09 671661 + 984 671670 Ho-167 6.03210E-08 1.42500E-06 671670 + 985 671680 Ho-168 2.24580E-08 7.40960E-07 671680 + 986 671681 Ho-168m 6.41860E-08 6.41860E-08 671681 + 987 671690 Ho-169 2.30820E-07 7.93820E-07 671690 + 988 671700 Ho-170 6.65300E-07 6.65300E-07 671700 + 989 671701 Ho-170m 1.47330E-07 5.61420E-07 671701 + 990 671710 Ho-171 1.55340E-07 1.75890E-07 671710 + 991 671720 Ho-172 6.18670E-08 6.67180E-08 671720 + 992 671730 Ho-173 1.28610E-07 1.30160E-07 671730 + 993 671740 Ho-174 2.66790E-08 2.66790E-08 671740 + 994 671750 Ho-175 4.37330E-09 4.37330E-09 671750 + 995 681660 Er-166 1.21740E-11 2.79680E-06 68166.82c + 996 681670 Er-167 1.43380E-10 1.42520E-06 68167.82c + 997 681671 Er-167m 1.19450E-11 1.70290E-07 681671 + 998 681680 Er-168 1.54880E-09 7.42830E-07 68168.82c + 999 681690 Er-169 7.47200E-09 8.01290E-07 681690 + 1000 681700 Er-170 1.20260E-07 1.34700E-06 68170.82c + 1001 681710 Er-171 4.91610E-08 2.25050E-07 681710 + 1002 681720 Er-172 1.08640E-07 1.75360E-07 681720 + 1003 681730 Er-173 5.88810E-07 7.18970E-07 681730 + 1004 681740 Er-174 6.00180E-07 6.26860E-07 681740 + 1005 681750 Er-175 1.19210E-07 1.23580E-07 681750 + 1006 681760 Er-176 3.97530E-09 3.97530E-09 681760 + 1007 681770 Er-177 3.82920E-10 3.82920E-10 681770 + 1008 691690 Tm-169 1.44720E-11 8.01310E-07 691690 + 1009 691700 Tm-170 4.55060E-10 4.55060E-10 691700 + 1010 691710 Tm-171 1.26280E-09 2.26310E-07 691710 + 1011 691720 Tm-172 4.90820E-09 1.80270E-07 691720 + 1012 691730 Tm-173 9.35660E-08 8.12540E-07 691730 + 1013 691740 Tm-174 1.76520E-07 8.03380E-07 691740 + 1014 691750 Tm-175 2.76000E-07 3.99580E-07 691750 + 1015 691760 Tm-176 1.43960E-08 1.83710E-08 691760 + 1016 691770 Tm-177 8.36900E-09 8.75190E-09 691770 + 1017 691780 Tm-178 1.60160E-09 1.60160E-09 691780 + 1018 691790 Tm-179 4.43880E-10 4.43880E-10 691790 + 1019 701720 Yb-172 2.14170E-11 1.80290E-07 701720 + 1020 701730 Yb-173 7.83260E-10 8.13320E-07 701730 + 1021 701740 Yb-174 9.77460E-09 8.13160E-07 701740 + 1022 701750 Yb-175 3.81780E-07 8.13160E-07 701750 + 1023 701751 Yb-175m 3.18040E-08 3.39480E-07 701751 + 1024 701760 Yb-176 1.75230E-09 2.47220E-08 701760 + 1025 701761 Yb-176m 6.13010E-09 1.53160E-08 701761 + 1026 701770 Yb-177 6.22830E-09 1.57630E-08 701770 + 1027 701771 Yb-177m 7.82390E-10 9.53430E-09 701771 + 1028 701780 Yb-178 7.47160E-09 9.07320E-09 701780 + 1029 701790 Yb-179 3.32020E-09 3.76410E-09 701790 + 1030 701800 Yb-180 1.67320E-09 1.67320E-09 701800 + 1031 701810 Yb-181 2.67380E-10 2.67380E-10 701810 + 1032 711740 Lu-174 1.59780E-12 8.77140E-12 711740 + 1033 711741 Lu-174m 7.21540E-12 7.21540E-12 711741 + 1034 711750 Lu-175 1.67380E-10 8.13330E-07 71175.82c + 1035 711760 Lu-176 7.39100E-11 1.60550E-09 71176.82c + 1036 711761 Lu-176m 2.11270E-11 2.11270E-11 711761 + 1037 711770 Lu-177 2.76080E-10 1.60950E-08 711770 + 1038 711771 Lu-177m 2.30000E-10 2.48640E-10 711771 + 1039 711772 Lu-177m 3.72740E-11 3.72740E-11 711772 + 1040 711780 Lu-178 2.89190E-10 9.36240E-09 711780 + 1041 711781 Lu-178m 6.67750E-10 6.67750E-10 711781 + 1042 711790 Lu-179 2.22290E-09 6.17220E-09 711790 + 1043 711791 Lu-179m 1.85180E-10 3.94930E-09 711791 + 1044 711800 Lu-180 3.56450E-10 1.93820E-09 711800 + 1045 711801 Lu-180m 3.56450E-10 2.02960E-09 711801 + 1046 711802 Lu-180m 1.13380E-09 1.13380E-09 711802 + 1047 711810 Lu-181 1.67030E-09 1.93770E-09 711810 + 1048 711820 Lu-182 5.66820E-10 5.66820E-10 711820 + 1049 711830 Lu-183 2.44570E-10 2.44570E-10 711830 + 1050 711840 Lu-184 3.04510E-11 3.04510E-11 711840 + 1051 721770 Hf-177 5.61650E-13 1.63070E-08 72177.82c + 1052 721771 Hf-177m 4.57530E-13 2.11630E-10 721771 + 1053 721772 Hf-177m 8.63320E-14 1.87240E-11 721772 + 1054 721780 Hf-178 3.02860E-12 1.00440E-08 72178.82c + 1055 721781 Hf-178m 8.03000E-12 6.78350E-10 721781 + 1056 721782 Hf-178m 2.56540E-12 2.56540E-12 721782 + 1057 721790 Hf-179 2.98960E-11 6.23490E-09 72179.82c + 1058 721791 Hf-179m 7.00340E-12 7.00340E-12 721791 + 1059 721792 Hf-179m 2.58550E-11 2.58550E-11 721792 + 1060 721800 Hf-180 6.66920E-11 3.81740E-09 72180.82c + 1061 721801 Hf-180m 2.33320E-10 8.00220E-10 721801 + 1062 721810 Hf-181 4.35390E-10 2.37310E-09 721810 + 1063 721820 Hf-182 1.82960E-10 1.01860E-09 721820 + 1064 721821 Hf-182m 6.40070E-10 6.40070E-10 721821 + 1065 721830 Hf-183 5.43140E-10 7.87710E-10 721830 + 1066 721840 Hf-184 8.71150E-11 1.02340E-10 721840 + 1067 721841 Hf-184m 3.04760E-10 3.19990E-10 721841 + 1068 721850 Hf-185 1.12320E-10 1.12320E-10 721850 + 1069 721860 Hf-186 4.05160E-11 4.05160E-11 721860 + 1070 721870 Hf-187 4.20510E-12 4.20510E-12 721870 + 1071 731810 Ta-181 8.94790E-12 2.38200E-09 73181.82c + 1072 731820 Ta-182 6.69150E-12 4.01340E-10 73182.82c + 1073 731821 Ta-182m 8.75640E-12 3.94650E-10 731821 + 1074 731822 Ta-182m 1.46530E-11 3.85890E-10 731822 + 1075 731830 Ta-183 1.20000E-10 9.07710E-10 731830 + 1076 731840 Ta-184 1.35500E-10 5.57830E-10 731840 + 1077 731850 Ta-185 1.00400E-10 3.27130E-10 731850 + 1078 731851 Ta-185m 1.14410E-10 1.14410E-10 731851 + 1079 731860 Ta-186 1.20240E-10 1.60760E-10 731860 + 1080 731870 Ta-187 7.44150E-11 7.86200E-11 731870 + 1081 731880 Ta-188 1.56210E-11 1.56210E-11 731880 + 1082 731890 Ta-189 4.71150E-12 4.71150E-12 731890 + 1083 741840 W-184 6.03440E-12 5.63860E-10 74184.82c + 1084 741850 W-185 2.95420E-12 3.43640E-10 741850 + 1085 741851 W-185m 1.35590E-11 1.35590E-11 741851 + 1086 741860 W-186 2.99150E-11 2.14940E-10 74186.82c + 1087 741861 W-186m 2.42690E-11 2.42690E-11 741861 + 1088 741870 W-187 5.15480E-11 1.30170E-10 741870 + 1089 741880 W-188 6.00260E-11 7.56470E-11 741880 + 1090 741890 W-189 2.87290E-11 3.34410E-11 741890 + 1091 741900 W-190 4.63000E-12 1.53210E-11 741900 + 1092 741901 W-190m 1.06910E-11 1.06910E-11 741901 + 1093 741910 W-191 2.68960E-12 2.68960E-12 741910 + 1094 751870 Re-187 3.23060E-12 1.33400E-10 75187.82c + 1095 751880 Re-188 1.14090E-12 8.19400E-11 751880 + 1096 751881 Re-188m 5.15210E-12 5.15210E-12 751881 + 1097 751890 Re-189 1.72020E-11 5.06430E-11 751890 + 1098 751900 Re-190 3.10640E-12 2.33830E-11 751900 + 1099 751901 Re-190m 1.08680E-11 1.08680E-11 751901 + 1100 751910 Re-191 1.37820E-11 1.64720E-11 751910 + 1101 751920 Re-192 5.12210E-12 5.12210E-12 751920 + 1102 751930 Re-193 2.34550E-12 2.34550E-12 751930 + 1103 761900 Os-190 5.57890E-13 3.11410E-11 761900 + 1104 761901 Os-190m 1.28820E-12 7.20020E-12 761901 + 1105 761910 Os-191 2.54280E-12 1.94260E-11 761910 + 1106 761920 Os-192 1.85840E-12 1.07410E-11 761920 + 1107 761921 Os-192m 4.29130E-12 4.29130E-12 761921 + 1108 761930 Os-193 4.29370E-12 6.63920E-12 761930 + 1109 761940 Os-194 3.31630E-12 3.31630E-12 761940 + 1110 761950 Os-195 1.04300E-12 1.04300E-12 761950 + 1111 771950 Ir-195 2.94970E-13 1.40570E-12 771950 + 1112 771951 Ir-195m 1.35380E-12 1.35380E-12 771951 + + Nuclide 92236.82c -- uranium 236 (U-236) + + Neutron-induced fission: + + Interpolation region : 1 / 2 + Interpolation energy : 2.53000E-08 MeV + Number of products : 811 / 920 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 3.33770E-05 3.33770E-05 1001.82c + 2 10020 H-2 8.46600E-06 8.46600E-06 1002.82c + 3 10030 H-3 1.14000E-04 1.14000E-04 1003.82c + 4 20040 He-4 2.11000E-03 2.11000E-03 2004.82c + 5 230590 V-59 1.09560E-12 1.09560E-12 230590 + 6 230600 V-60 7.13840E-11 7.13840E-11 230600 + 7 230610 V-61 5.46880E-11 5.46880E-11 230610 + 8 230620 V-62 7.73020E-12 7.73020E-12 230620 + 9 240590 Cr-59 2.47900E-12 3.57460E-12 240590 + 10 240600 Cr-60 1.42070E-09 1.49540E-09 240600 + 11 240610 Cr-61 2.16440E-09 2.21580E-09 240610 + 12 240620 Cr-62 3.44920E-09 3.45690E-09 240620 + 13 240630 Cr-63 1.07330E-09 1.07330E-09 240630 + 14 240640 Cr-64 3.89480E-10 3.89480E-10 240640 + 15 240650 Cr-65 3.78060E-11 3.78060E-11 240650 + 16 240660 Cr-66 2.83730E-12 2.83730E-12 240660 + 17 250600 Mn-60 3.12220E-11 1.55850E-09 250600 + 18 250601 Mn-60m 2.77300E-10 2.77300E-10 250601 + 19 250610 Mn-61 3.80420E-09 6.02000E-09 250610 + 20 250620 Mn-62 8.49500E-09 1.02230E-08 250620 + 21 250621 Mn-62m 1.52500E-09 3.25350E-09 250621 + 22 250630 Mn-63 2.90250E-08 3.00980E-08 250630 + 23 250640 Mn-64 2.21730E-08 2.25630E-08 250640 + 24 250650 Mn-65 2.53000E-08 2.53380E-08 250650 + 25 250660 Mn-66 4.72890E-09 4.73170E-09 250660 + 26 250670 Mn-67 9.06890E-10 9.06890E-10 250670 + 27 250680 Mn-68 3.92170E-11 3.92170E-11 250680 + 28 250690 Mn-69 1.57590E-12 1.57590E-12 250690 + 29 260600 Fe-60 5.20510E-12 1.80910E-09 260600 + 30 260610 Fe-61 1.35530E-10 6.15550E-09 260610 + 31 260620 Fe-62 3.33400E-09 1.68110E-08 260620 + 32 260630 Fe-63 1.59940E-08 4.60920E-08 260630 + 33 260640 Fe-64 9.88320E-08 1.21390E-07 260640 + 34 260650 Fe-65 1.94680E-07 2.20020E-07 260650 + 35 260660 Fe-66 3.59700E-07 3.64430E-07 260660 + 36 260670 Fe-67 1.52820E-07 1.53730E-07 260670 + 37 260680 Fe-68 8.04000E-08 8.04400E-08 260680 + 38 260690 Fe-69 8.47930E-09 8.48050E-09 260690 + 39 260700 Fe-70 7.85820E-10 7.85820E-10 260700 + 40 260710 Fe-71 2.11690E-11 2.11690E-11 260710 + 41 270620 Co-62 2.14470E-12 1.68130E-08 270620 + 42 270621 Co-62m 5.02350E-12 5.02350E-12 270621 + 43 270630 Co-63 3.88660E-10 4.64810E-08 270630 + 44 270640 Co-64 4.79170E-09 1.26190E-07 270640 + 45 270650 Co-65 8.32620E-08 3.03280E-07 270650 + 46 270660 Co-66 2.47990E-07 6.12420E-07 270660 + 47 270670 Co-67 8.70600E-07 1.02430E-06 270670 + 48 270680 Co-68 4.43890E-07 6.80200E-07 270680 + 49 270681 Co-68m 3.91590E-07 4.72620E-07 270681 + 50 270690 Co-69 9.23080E-07 9.30970E-07 270690 + 51 270700 Co-70 9.89700E-08 9.89700E-08 270700 + 52 270701 Co-70m 9.89700E-08 9.97560E-08 270701 + 53 270710 Co-71 6.65870E-08 6.66080E-08 270710 + 54 270720 Co-72 4.72800E-09 4.72800E-09 270720 + 55 270730 Co-73 3.79090E-10 3.79090E-10 270730 + 56 270740 Co-74 1.09330E-11 1.09330E-11 270740 + 57 280640 Ni-64 1.30000E-11 1.26200E-07 28064.82c + 58 280650 Ni-65 5.32580E-10 3.03810E-07 280650 + 59 280660 Ni-66 1.70730E-08 6.29500E-07 280660 + 60 280670 Ni-67 1.12620E-07 1.13690E-06 280670 + 61 280680 Ni-68 9.09260E-07 1.83510E-06 280680 + 62 280690 Ni-69 8.05150E-07 1.72680E-06 280690 + 63 280691 Ni-69m 8.05150E-07 8.05150E-07 280691 + 64 280700 Ni-70 2.97010E-06 3.16880E-06 280700 + 65 280710 Ni-71 1.93490E-06 2.00150E-06 280710 + 66 280720 Ni-72 1.51680E-06 1.52150E-06 280720 + 67 280730 Ni-73 2.91650E-07 2.92030E-07 280730 + 68 280740 Ni-74 1.07090E-07 1.07100E-07 280740 + 69 280750 Ni-75 1.19910E-08 1.19910E-08 280750 + 70 280760 Ni-76 1.07370E-09 1.07370E-09 280760 + 71 280770 Ni-77 4.08570E-11 4.08570E-11 280770 + 72 290660 Cu-66 5.65350E-12 6.29500E-07 290660 + 73 290670 Cu-67 4.60120E-10 1.13740E-06 290670 + 74 290680 Cu-68 2.51870E-09 1.84260E-06 290680 + 75 290681 Cu-68m 5.89940E-09 5.89940E-09 290681 + 76 290690 Cu-69 1.51790E-07 2.68370E-06 290690 + 77 290700 Cu-70 3.77660E-08 3.28300E-07 290700 + 78 290701 Cu-70m 4.20740E-07 5.81070E-07 290701 + 79 290702 Cu-70m 3.77660E-08 3.20660E-06 290702 + 80 290710 Cu-71 2.63610E-06 4.63760E-06 290710 + 81 290720 Cu-72 3.36800E-06 4.88950E-06 290720 + 82 290730 Cu-73 5.87430E-06 6.16630E-06 290730 + 83 290740 Cu-74 4.43030E-06 4.53760E-06 290740 + 84 290750 Cu-75 5.72970E-06 5.74150E-06 290750 + 85 290760 Cu-76 6.34200E-07 6.34740E-07 290760 + 86 290761 Cu-76m 6.34200E-07 6.34740E-07 290761 + 87 290770 Cu-77 5.75530E-07 5.75570E-07 290770 + 88 290780 Cu-78 2.67850E-08 2.67850E-08 290780 + 89 290790 Cu-79 1.72950E-09 1.72950E-09 290790 + 90 300680 Zn-68 3.42170E-12 1.84350E-06 300680 + 91 300690 Zn-69 2.90620E-11 2.68390E-06 300690 + 92 300691 Zn-69m 1.25690E-10 1.25690E-10 300691 + 93 300700 Zn-70 6.05600E-09 3.67110E-06 300700 + 94 300710 Zn-71 1.30570E-08 4.65070E-06 300710 + 95 300711 Zn-71m 5.64710E-08 5.64710E-08 300711 + 96 300720 Zn-72 8.52090E-07 5.74160E-06 300720 + 97 300730 Zn-73 2.47800E-07 7.71240E-06 300730 + 98 300731 Zn-73m 3.38760E-07 1.29830E-06 300731 + 99 300732 Zn-73m 1.91900E-06 1.91900E-06 300732 + 100 300740 Zn-74 1.81520E-05 2.28910E-05 300740 + 101 300750 Zn-75 2.61580E-05 3.17180E-05 300750 + 102 300760 Zn-76 1.07010E-04 1.08260E-04 300760 + 103 300770 Zn-77 4.16670E-05 4.54280E-05 300770 + 104 300771 Zn-77m 6.36970E-06 6.36970E-06 300771 + 105 300780 Zn-78 1.08930E-04 1.08960E-04 300780 + 106 300790 Zn-79 4.40330E-05 4.40340E-05 300790 + 107 300800 Zn-80 2.63300E-05 2.63300E-05 300800 + 108 300810 Zn-81 3.70480E-08 3.70480E-08 300810 + 109 300820 Zn-82 1.44300E-09 1.44300E-09 300820 + 110 310710 Ga-71 4.34290E-11 4.70720E-06 310710 + 111 310720 Ga-72 1.17960E-09 5.74290E-06 310720 + 112 310721 Ga-72m 1.32810E-10 1.91450E-07 310721 + 113 310730 Ga-73 4.44660E-08 8.71640E-06 310730 + 114 310740 Ga-74 2.76960E-07 1.76530E-05 310740 + 115 310741 Ga-74m 2.76960E-07 2.31680E-05 310741 + 116 310750 Ga-75 2.61580E-05 5.78760E-05 310750 + 117 310760 Ga-76 3.79600E-05 1.46220E-04 310760 + 118 310770 Ga-77 1.92150E-04 2.40760E-04 310770 + 119 310780 Ga-78 3.26800E-04 4.36330E-04 310780 + 120 310790 Ga-79 3.08230E-04 3.51690E-04 310790 + 121 310800 Ga-80 2.36970E-04 2.63300E-04 310800 + 122 310810 Ga-81 1.48330E-04 1.48360E-04 310810 + 123 310820 Ga-82 2.45940E-05 2.45950E-05 310820 + 124 310830 Ga-83 9.97380E-07 9.97380E-07 310830 + 125 310840 Ga-84 2.36940E-08 2.36940E-08 310840 + 126 310850 Ga-85 7.39760E-10 7.39760E-10 310850 + 127 320730 Ge-73 5.44950E-12 8.71640E-06 32073.82c + 128 320731 Ge-73m 1.26000E-12 8.58840E-06 320731 + 129 320740 Ge-74 1.06820E-09 2.34460E-05 32074.82c + 130 320750 Ge-75 6.70320E-09 5.79250E-05 320750 + 131 320751 Ge-75m 4.38490E-08 2.35890E-06 320751 + 132 320760 Ge-76 1.92980E-06 1.48150E-04 32076.82c + 133 320770 Ge-77 1.25000E-04 1.74380E-04 320770 + 134 320771 Ge-77m 1.91090E-05 2.59870E-04 320771 + 135 320780 Ge-78 1.90630E-04 6.27270E-04 320780 + 136 320790 Ge-79 1.14830E-04 4.95750E-04 320790 + 137 320791 Ge-79m 7.51150E-04 7.51680E-04 320791 + 138 320800 Ge-80 1.97470E-03 2.25570E-03 320800 + 139 320810 Ge-81 2.16250E-03 2.23980E-03 320810 + 140 320811 Ge-81m 5.00020E-04 5.64320E-04 320811 + 141 320820 Ge-82 2.83330E-03 2.85300E-03 320820 + 142 320830 Ge-83 1.65640E-03 1.65700E-03 320830 + 143 320840 Ge-84 4.98030E-04 4.98040E-04 320840 + 144 320850 Ge-85 1.23600E-04 1.23600E-04 320850 + 145 320860 Ge-86 1.35770E-05 1.35770E-05 320860 + 146 320870 Ge-87 9.63460E-09 9.63460E-09 320870 + 147 330750 As-75 1.22790E-12 5.79260E-05 33075.82c + 148 330751 As-75m 4.01710E-12 7.11680E-10 330751 + 149 330760 As-76 4.51160E-10 4.51160E-10 330760 + 150 330770 As-77 8.73960E-08 3.84960E-04 330770 + 151 330780 As-78 1.71790E-06 6.28990E-04 330780 + 152 330790 As-79 4.40330E-05 1.26140E-03 330790 + 153 330800 As-80 2.76460E-04 2.53210E-03 330800 + 154 330810 As-81 8.15800E-04 3.61420E-03 330810 + 155 330820 As-82 5.24010E-04 3.37700E-03 330820 + 156 330821 As-82m 1.58130E-03 1.58130E-03 330821 + 157 330830 As-83 4.57800E-03 6.28880E-03 330830 + 158 330840 As-84 1.74160E-03 1.97240E-03 330840 + 159 330841 As-84m 1.74160E-03 1.97240E-03 330841 + 160 330850 As-85 2.36190E-03 2.46820E-03 330850 + 161 330860 As-86 8.30140E-04 8.43720E-04 330860 + 162 330870 As-87 3.83660E-04 3.83670E-04 330870 + 163 330880 As-88 4.67210E-05 4.67210E-05 330880 + 164 330890 As-89 4.67820E-06 4.67820E-06 330890 + 165 330900 As-90 1.52950E-09 1.52950E-09 330900 + 166 340780 Se-78 4.98780E-10 6.28990E-04 34078.82c + 167 340790 Se-79 3.00880E-08 1.26070E-03 34079.82c + 168 340791 Se-79m 4.59960E-09 1.23150E-03 340791 + 169 340800 Se-80 2.63300E-05 2.55840E-03 34080.82c + 170 340810 Se-81 1.86850E-05 3.75500E-03 340810 + 171 340811 Se-81m 1.22230E-04 2.51970E-04 340811 + 172 340820 Se-82 1.07720E-03 6.03550E-03 34082.82c + 173 340830 Se-83 3.83830E-03 6.10500E-03 340830 + 174 340831 Se-83m 8.87510E-04 4.91510E-03 340831 + 175 340840 Se-84 1.26550E-02 1.71370E-02 340840 + 176 340850 Se-85 1.67510E-02 1.89550E-02 340850 + 177 340860 Se-86 2.07040E-02 2.13280E-02 340860 + 178 340870 Se-87 1.56290E-02 1.59540E-02 340870 + 179 340880 Se-88 8.67040E-03 8.71710E-03 340880 + 180 340890 Se-89 2.54500E-03 2.54970E-03 340890 + 181 340900 Se-90 5.54590E-04 5.54590E-04 340900 + 182 340910 Se-91 6.12050E-05 6.12050E-05 340910 + 183 340920 Se-92 7.54490E-06 7.54490E-06 340920 + 184 350800 Br-80 2.82150E-11 1.13360E-10 350800 + 185 350801 Br-80m 8.51450E-11 8.51450E-11 350801 + 186 350810 Br-81 1.59900E-08 3.75520E-03 35081.82c + 187 350820 Br-82 4.63660E-07 6.56860E-07 350820 + 188 350821 Br-82m 1.97950E-07 1.97950E-07 350821 + 189 350830 Br-83 5.65180E-05 1.10770E-02 350830 + 190 350840 Br-84 2.41600E-04 1.73790E-02 350840 + 191 350841 Br-84m 2.41600E-04 2.41600E-04 350841 + 192 350850 Br-85 2.73710E-03 2.16920E-02 350850 + 193 350860 Br-86 7.37780E-03 2.87060E-02 350860 + 194 350870 Br-87 1.73490E-02 3.33890E-02 350870 + 195 350880 Br-88 2.11130E-02 2.99430E-02 350880 + 196 350890 Br-89 1.88340E-02 2.11850E-02 350890 + 197 350900 Br-90 8.40740E-03 8.97480E-03 350900 + 198 350910 Br-91 3.73460E-03 3.78300E-03 350910 + 199 350920 Br-92 6.10070E-04 6.17610E-04 350920 + 200 350930 Br-93 1.82660E-04 1.82660E-04 350930 + 201 350940 Br-94 8.50090E-06 8.50090E-06 350940 + 202 350950 Br-95 4.35390E-09 4.35390E-09 350950 + 203 360830 Kr-83 3.53100E-06 1.10810E-02 36083.82c + 204 360831 Kr-83m 8.16460E-07 1.10680E-02 360831 + 205 360840 Kr-84 1.18580E-05 1.76320E-02 36084.82c + 206 360850 Kr-85 1.31410E-04 4.80770E-03 36085.82c + 207 360851 Kr-85m 3.03860E-05 2.16870E-02 360851 + 208 360860 Kr-86 1.96290E-03 3.15070E-02 36086.82c + 209 360870 Kr-87 6.86410E-03 4.14210E-02 360870 + 210 360880 Kr-88 2.47780E-02 5.57020E-02 360880 + 211 360890 Kr-89 4.11640E-02 6.15700E-02 360890 + 212 360900 Kr-90 5.26870E-02 6.02110E-02 360900 + 213 360910 Kr-91 4.25680E-02 4.57990E-02 360910 + 214 360920 Kr-92 2.93200E-02 2.98570E-02 360920 + 215 360930 Kr-93 1.19370E-02 1.20010E-02 360930 + 216 360940 Kr-94 3.81870E-03 3.82120E-03 360940 + 217 360950 Kr-95 6.54080E-04 6.54080E-04 360950 + 218 360960 Kr-96 1.16520E-04 1.16520E-04 360960 + 219 360970 Kr-97 4.92830E-06 4.92830E-06 360970 + 220 370850 Rb-85 7.39760E-10 2.18540E-02 37085.82c + 221 370860 Rb-86 2.09270E-08 5.85690E-08 37086.82c + 222 370861 Rb-86m 3.76420E-08 3.76420E-08 370861 + 223 370870 Rb-87 5.48090E-05 4.14760E-02 37087.82c + 224 370880 Rb-88 3.28780E-04 5.60300E-02 370880 + 225 370890 Rb-89 2.47640E-03 6.40460E-02 370890 + 226 370900 Rb-90 6.30940E-04 5.33170E-02 370900 + 227 370901 Rb-90m 5.60370E-03 1.34790E-02 370901 + 228 370910 Rb-91 1.71970E-02 6.29960E-02 370910 + 229 370920 Rb-92 2.45120E-02 5.43690E-02 370920 + 230 370930 Rb-93 3.27690E-02 4.48130E-02 370930 + 231 370940 Rb-94 1.91460E-02 2.29440E-02 370940 + 232 370950 Rb-95 1.16410E-02 1.22810E-02 370950 + 233 370960 Rb-96 1.58610E-03 2.46360E-03 370960 + 234 370961 Rb-96m 1.58610E-03 1.64240E-03 370961 + 235 370970 Rb-97 1.05060E-03 1.05520E-03 370970 + 236 370980 Rb-98 5.71800E-05 5.71800E-05 370980 + 237 370981 Rb-98m 5.71800E-05 5.71800E-05 370981 + 238 370990 Rb-99 1.74520E-05 1.74520E-05 370990 + 239 371000 Rb-100 1.30620E-06 1.30620E-06 371000 + 240 380880 Sr-88 1.21130E-05 5.60430E-02 38088.82c + 241 380890 Sr-89 9.51210E-05 6.41410E-02 38089.82c + 242 380900 Sr-90 6.81390E-04 6.71270E-02 38090.82c + 243 380910 Sr-91 2.80040E-03 6.57960E-02 380910 + 244 380920 Sr-92 1.18350E-02 6.68320E-02 380920 + 245 380930 Sr-93 2.48520E-02 7.13550E-02 380930 + 246 380940 Sr-94 4.46510E-02 6.63330E-02 380940 + 247 380950 Sr-95 4.50400E-02 5.65950E-02 380950 + 248 380960 Sr-96 3.99790E-02 4.31990E-02 380960 + 249 380970 Sr-97 2.29770E-02 2.37750E-02 380970 + 250 380980 Sr-98 1.06850E-02 1.07940E-02 380980 + 251 380990 Sr-99 2.63940E-03 2.65420E-03 380990 + 252 381000 Sr-100 6.50480E-04 6.51710E-04 381000 + 253 381010 Sr-101 6.08320E-05 6.08320E-05 381010 + 254 381020 Sr-102 7.75060E-06 7.75060E-06 381020 + 255 390900 Y-90 6.32300E-10 6.71270E-02 39090.82c + 256 390901 Y-90m 8.97210E-10 8.97210E-10 390901 + 257 390910 Y-91 8.67490E-07 6.58010E-02 39091.82c + 258 390911 Y-91m 3.75170E-06 3.87150E-02 390911 + 259 390920 Y-92 6.03600E-05 6.68920E-02 390920 + 260 390930 Y-93 8.26790E-05 7.19780E-02 390930 + 261 390931 Y-93m 5.40840E-04 1.83970E-02 390931 + 262 390940 Y-94 1.78710E-03 6.81210E-02 390940 + 263 390950 Y-95 7.28020E-03 6.38750E-02 390950 + 264 390960 Y-96 4.28550E-03 4.74900E-02 390960 + 265 390961 Y-96m 7.70850E-03 7.71450E-03 390961 + 266 390970 Y-97 4.48770E-03 2.48700E-02 390970 + 267 390971 Y-97m 1.52960E-02 2.21200E-02 390971 + 268 390972 Y-97m 4.11010E-03 4.11010E-03 390972 + 269 390980 Y-98 3.96400E-03 1.47580E-02 390980 + 270 390981 Y-98m 1.66710E-02 1.66710E-02 390981 + 271 390990 Y-99 1.74100E-02 2.00690E-02 390990 + 272 391000 Y-100 3.63370E-03 4.28110E-03 391000 + 273 391001 Y-100m 3.63370E-03 3.63450E-03 391001 + 274 391010 Y-101 2.99310E-03 3.05290E-03 391010 + 275 391020 Y-102 2.69010E-04 2.72670E-04 391020 + 276 391021 Y-102m 2.69010E-04 2.72670E-04 391021 + 277 391030 Y-103 1.04880E-04 1.04880E-04 391030 + 278 391040 Y-104 6.70530E-06 6.70530E-06 391040 + 279 391050 Y-105 8.49590E-10 8.49590E-10 391050 + 280 400920 Zr-92 1.07790E-06 6.68930E-02 40092.82c + 281 400930 Zr-93 1.46580E-05 7.19930E-02 40093.82c + 282 400940 Zr-94 8.50090E-05 6.82060E-02 40094.82c + 283 400950 Zr-95 5.24360E-04 6.43990E-02 40095.82c + 284 400960 Zr-96 2.74290E-03 5.79650E-02 40096.82c + 285 400970 Zr-97 7.76600E-03 5.60190E-02 400970 + 286 400980 Zr-98 2.01680E-02 5.13250E-02 400980 + 287 400990 Zr-99 2.54850E-02 4.52520E-02 400990 + 288 401000 Zr-100 3.16820E-02 3.95580E-02 401000 + 289 401010 Zr-101 1.97180E-02 2.27980E-02 401010 + 290 401020 Zr-102 1.20900E-02 1.26170E-02 401020 + 291 401030 Zr-103 3.59930E-03 3.69640E-03 401030 + 292 401040 Zr-104 9.99090E-04 1.00520E-03 401040 + 293 401050 Zr-105 1.34510E-04 1.34510E-04 401050 + 294 401060 Zr-106 1.76000E-05 1.76000E-05 401060 + 295 401070 Zr-107 1.55630E-09 1.55630E-09 401070 + 296 401080 Zr-108 3.21480E-11 3.21480E-11 401080 + 297 410950 Nb-95 7.26790E-07 6.43610E-02 41095.82c + 298 410951 Nb-95m 1.68050E-07 6.95900E-04 410951 + 299 410960 Nb-96 4.78840E-06 4.78840E-06 410960 + 300 410970 Nb-97 6.13760E-05 5.60940E-02 410970 + 301 410971 Nb-97m 1.41920E-05 5.32590E-02 410971 + 302 410980 Nb-98 8.93000E-05 5.14140E-02 410980 + 303 410981 Nb-98m 2.69480E-04 2.69480E-04 410981 + 304 410990 Nb-99 1.34490E-03 3.02840E-02 410990 + 305 410991 Nb-99m 3.10980E-04 1.69640E-02 410991 + 306 411000 Nb-100 7.06060E-04 4.02640E-02 411000 + 307 411001 Nb-100m 2.96940E-03 2.96940E-03 411001 + 308 411010 Nb-101 8.01340E-03 3.08110E-02 411010 + 309 411020 Nb-102 4.37010E-03 1.69870E-02 411020 + 310 411021 Nb-102m 4.37010E-03 4.37010E-03 411021 + 311 411030 Nb-103 8.13600E-03 1.18320E-02 411030 + 312 411040 Nb-104 1.91650E-03 2.92360E-03 411040 + 313 411041 Nb-104m 1.91650E-03 1.91650E-03 411041 + 314 411050 Nb-105 1.67610E-03 1.80900E-03 411050 + 315 411060 Nb-106 3.69610E-04 3.86940E-04 411060 + 316 411070 Nb-107 1.01400E-04 1.01400E-04 411070 + 317 411080 Nb-108 2.63290E-05 2.63290E-05 411080 + 318 411090 Nb-109 1.51300E-05 1.51300E-05 411090 + 319 411100 Nb-110 6.00190E-11 6.00190E-11 411100 + 320 420970 Mo-97 8.21380E-07 5.60950E-02 42097.82c + 321 420980 Mo-98 8.96970E-06 5.16930E-02 42098.82c + 322 420990 Mo-99 6.21320E-05 4.69700E-02 42099.82c + 323 421000 Mo-100 3.55940E-04 4.35900E-02 42100.82c + 324 421010 Mo-101 1.06930E-03 3.18800E-02 421010 + 325 421020 Mo-102 3.24340E-03 2.46010E-02 421020 + 326 421030 Mo-103 4.14930E-03 1.59840E-02 421030 + 327 421040 Mo-104 4.90420E-03 9.77230E-03 421040 + 328 421050 Mo-105 2.96170E-03 4.75740E-03 421050 + 329 421060 Mo-106 1.82430E-03 2.19990E-03 421060 + 330 421070 Mo-107 6.92660E-04 7.89610E-04 421070 + 331 421080 Mo-108 3.86150E-04 4.12760E-04 421080 + 332 421090 Mo-109 6.80840E-05 8.13000E-05 421090 + 333 421100 Mo-110 2.26090E-05 2.26090E-05 421100 + 334 421110 Mo-111 2.13130E-08 2.13130E-08 421110 + 335 421120 Mo-112 4.38180E-10 4.38180E-10 421120 + 336 421130 Mo-113 4.43910E-12 4.43910E-12 421130 + 337 431010 Tc-101 6.27120E-06 3.18870E-02 431010 + 338 431020 Tc-102 1.38860E-05 2.46150E-02 431020 + 339 431021 Tc-102m 1.38860E-05 1.38860E-05 431021 + 340 431030 Tc-103 7.69530E-05 1.60610E-02 431030 + 341 431040 Tc-104 1.54220E-04 9.92650E-03 431040 + 342 431050 Tc-105 3.00320E-04 5.05770E-03 431050 + 343 431060 Tc-106 3.15930E-04 2.51580E-03 431060 + 344 431070 Tc-107 3.41330E-04 1.13090E-03 431070 + 345 431080 Tc-108 3.02770E-04 7.15960E-04 431080 + 346 431090 Tc-109 1.89120E-04 2.69990E-04 431090 + 347 431100 Tc-110 1.46960E-04 1.69570E-04 431100 + 348 431110 Tc-111 3.68770E-05 3.68980E-05 431110 + 349 431120 Tc-112 8.73470E-07 8.73900E-07 431120 + 350 431130 Tc-113 1.03950E-07 1.03950E-07 431130 + 351 431140 Tc-114 2.68930E-09 2.68930E-09 431140 + 352 431150 Tc-115 7.23180E-11 7.23180E-11 431150 + 353 441020 Ru-102 6.45880E-07 2.46290E-02 44102.82c + 354 441030 Ru-103 1.81770E-07 1.60620E-02 44103.82c + 355 441031 Ru-103m 4.38820E-07 4.38820E-07 441031 + 356 441040 Ru-104 3.65750E-06 9.93020E-03 44104.82c + 357 441050 Ru-105 1.19860E-05 5.06970E-03 44105.82c + 358 441060 Ru-106 3.25610E-05 2.54840E-03 44106.82c + 359 441070 Ru-107 3.42760E-05 1.16520E-03 441070 + 360 441080 Ru-108 9.21490E-05 8.08330E-04 441080 + 361 441090 Ru-109 1.51300E-04 4.21140E-04 441090 + 362 441100 Ru-110 2.14780E-04 3.84280E-04 441100 + 363 441110 Ru-111 1.77010E-04 2.13920E-04 441110 + 364 441120 Ru-112 1.14320E-04 1.15190E-04 441120 + 365 441130 Ru-113 4.83500E-05 7.26220E-05 441130 + 366 441131 Ru-113m 4.83500E-05 4.83500E-05 441131 + 367 441140 Ru-114 3.95270E-05 3.95300E-05 441140 + 368 441150 Ru-115 1.84430E-05 1.84430E-05 441150 + 369 441160 Ru-116 1.45410E-05 1.45410E-05 441160 + 370 441170 Ru-117 4.60390E-10 4.60390E-10 441170 + 371 441180 Ru-118 6.24700E-12 6.24700E-12 441180 + 372 441190 Ru-119 1.62010E-07 1.62010E-07 441190 + 373 441200 Ru-120 1.36710E-08 1.36710E-08 441200 + 374 451060 Rh-106 2.73380E-10 2.54840E-03 451060 + 375 451061 Rh-106m 6.40340E-10 6.40340E-10 451061 + 376 451070 Rh-107 1.42820E-06 1.16660E-03 451070 + 377 451080 Rh-108 1.05790E-07 8.08430E-04 451080 + 378 451081 Rh-108m 3.19230E-07 3.19230E-07 451081 + 379 451090 Rh-109 4.59830E-06 4.25740E-04 451090 + 380 451100 Rh-110 1.92910E-05 4.03570E-04 451100 + 381 451101 Rh-110m 5.14960E-07 5.14960E-07 451101 + 382 451110 Rh-111 3.68770E-05 2.50800E-04 451110 + 383 451120 Rh-112 1.33370E-05 1.28520E-04 451120 + 384 451121 Rh-112m 1.33370E-05 1.33370E-05 451121 + 385 451130 Rh-113 4.39550E-05 1.40750E-04 451130 + 386 451140 Rh-114 4.79950E-05 8.75670E-05 451140 + 387 451141 Rh-114m 4.79950E-05 4.79950E-05 451141 + 388 451150 Rh-115 5.53290E-05 7.38870E-05 451150 + 389 451160 Rh-116 8.70070E-06 2.30850E-05 451160 + 390 451161 Rh-116m 2.03790E-05 2.03790E-05 451161 + 391 451170 Rh-117 2.82710E-05 2.82710E-05 451170 + 392 451180 Rh-118 8.77580E-08 9.48240E-08 451180 + 393 451190 Rh-119 3.02340E-05 3.03890E-05 451190 + 394 451200 Rh-120 6.10960E-06 6.12330E-06 451200 + 395 451210 Rh-121 1.20220E-06 1.20220E-06 451210 + 396 451220 Rh-122 4.58410E-08 4.58410E-08 451220 + 397 461080 Pd-108 3.21480E-11 8.08750E-04 46108.82c + 398 461090 Pd-109 4.10580E-10 4.25740E-04 461090 + 399 461091 Pd-109m 7.71620E-10 2.12870E-04 461091 + 400 461100 Pd-110 6.39070E-08 4.04150E-04 46110.82c + 401 461110 Pd-111 1.93260E-07 2.50990E-04 461110 + 402 461111 Pd-111m 3.63210E-07 1.36640E-06 461111 + 403 461120 Pd-112 3.81070E-06 1.45670E-04 461120 + 404 461130 Pd-113 7.72440E-06 1.67130E-04 461130 + 405 461131 Pd-113m 1.86480E-05 1.86480E-05 461131 + 406 461140 Pd-114 5.08180E-05 1.86380E-04 461140 + 407 461150 Pd-115 3.84320E-05 1.08230E-04 461150 + 408 461151 Pd-115m 7.22280E-05 8.29560E-05 461151 + 409 461160 Pd-116 1.21170E-04 1.64630E-04 461160 + 410 461170 Pd-117 3.43650E-05 1.27220E-04 461170 + 411 461171 Pd-117m 6.45840E-05 6.45840E-05 461171 + 412 461180 Pd-118 9.61620E-05 9.62540E-05 461180 + 413 461190 Pd-119 2.68290E-05 5.75810E-05 461190 + 414 461200 Pd-120 1.14110E-05 1.73340E-05 461200 + 415 461210 Pd-121 6.87400E-06 7.91310E-06 461210 + 416 461220 Pd-122 2.60830E-05 2.61290E-05 461220 + 417 461230 Pd-123 3.57830E-06 3.57830E-06 461230 + 418 461240 Pd-124 6.49160E-07 6.49160E-07 461240 + 419 471110 Ag-111 1.11120E-11 2.50110E-04 47111.82c + 420 471111 Ag-111m 7.26900E-11 2.49480E-04 471111 + 421 471120 Ag-112 1.93490E-09 1.45680E-04 471120 + 422 471130 Ag-113 1.29540E-08 1.09580E-04 471130 + 423 471131 Ag-113m 8.47400E-08 1.60120E-04 471131 + 424 471140 Ag-114 2.05760E-07 1.87450E-04 471140 + 425 471141 Ag-114m 8.65340E-07 8.65340E-07 471141 + 426 471150 Ag-115 1.63030E-06 1.05040E-04 471150 + 427 471151 Ag-115m 1.06650E-05 1.16210E-04 471151 + 428 471160 Ag-116 2.90040E-06 1.67940E-04 471160 + 429 471161 Ag-116m 6.79330E-06 6.79330E-06 471161 + 430 471170 Ag-117 2.81150E-06 7.13430E-05 471170 + 431 471171 Ag-117m 1.83910E-05 8.20030E-05 471171 + 432 471180 Ag-118 5.83330E-06 1.04030E-04 471180 + 433 471181 Ag-118m 2.45330E-05 3.82930E-05 471181 + 434 471190 Ag-119 9.48690E-06 3.82770E-05 471190 + 435 471191 Ag-119m 6.20580E-05 9.08490E-05 471191 + 436 471200 Ag-120 2.12280E-05 4.42690E-05 471200 + 437 471201 Ag-120m 3.01220E-05 3.87890E-05 471201 + 438 471210 Ag-121 6.87400E-05 7.66310E-05 471210 + 439 471220 Ag-122 1.50220E-05 4.11510E-05 471220 + 440 471221 Ag-122m 1.35320E-05 1.35320E-05 471221 + 441 471230 Ag-123 1.86280E-05 2.22060E-05 471230 + 442 471240 Ag-124 2.49410E-05 3.68240E-05 471240 + 443 471241 Ag-124m 2.24670E-05 2.24670E-05 471241 + 444 471250 Ag-125 6.80660E-05 6.80660E-05 471250 + 445 471260 Ag-126 4.64150E-05 4.64150E-05 471260 + 446 471270 Ag-127 2.36420E-06 2.36420E-06 471270 + 447 471280 Ag-128 1.13460E-07 1.13460E-07 471280 + 448 471290 Ag-129 4.63500E-09 4.63500E-09 471290 + 449 481130 Cd-113 1.03920E-12 1.65330E-04 48113.82c + 450 481131 Cd-113m 3.39990E-12 1.89450E-06 481131 + 451 481140 Cd-114 5.19330E-10 1.87450E-04 48114.82c + 452 481150 Cd-115 3.64990E-09 1.88120E-04 481150 + 453 481151 Cd-115m 1.19410E-08 8.73740E-06 48515.82c + 454 481160 Cd-116 4.43570E-07 1.74770E-04 48116.82c + 455 481170 Cd-117 8.27260E-07 1.18080E-04 481170 + 456 481171 Cd-117m 2.70650E-06 3.38780E-05 481171 + 457 481180 Cd-118 3.03660E-05 1.56990E-04 481180 + 458 481190 Cd-119 9.16780E-06 1.19160E-04 481190 + 459 481191 Cd-119m 2.21320E-05 4.12720E-05 481191 + 460 481200 Cd-120 1.08410E-04 1.77110E-04 481200 + 461 481210 Cd-121 3.22160E-05 1.00840E-04 481210 + 462 481211 Cd-121m 7.77740E-05 8.57810E-05 481211 + 463 481220 Cd-122 1.42770E-04 1.97450E-04 481220 + 464 481230 Cd-123 4.18320E-05 6.00190E-05 481230 + 465 481231 Cd-123m 1.00990E-04 1.05040E-04 481231 + 466 481240 Cd-124 1.47260E-04 1.95280E-04 481240 + 467 481250 Cd-125 9.07900E-05 1.24820E-04 481250 + 468 481251 Cd-125m 2.19180E-04 2.53210E-04 481251 + 469 481260 Cd-126 5.10570E-04 5.56980E-04 481260 + 470 481270 Cd-127 7.11760E-04 7.14120E-04 481270 + 471 481280 Cd-128 4.53140E-04 4.53250E-04 481280 + 472 481290 Cd-129 5.02760E-05 5.02790E-05 481290 + 473 481291 Cd-129m 1.21370E-04 1.21380E-04 481291 + 474 481300 Cd-130 2.54080E-05 2.54080E-05 481300 + 475 481310 Cd-131 7.84440E-08 7.84440E-08 481310 + 476 481320 Cd-132 1.92200E-09 1.92200E-09 481320 + 477 491160 In-116 6.78180E-12 6.78180E-12 491160 + 478 491161 In-116m 1.03950E-11 2.04620E-11 491161 + 479 491162 In-116m 1.00680E-11 1.00680E-11 491162 + 480 491170 In-117 1.69930E-09 9.44440E-05 491170 + 481 491171 In-117m 3.92910E-10 1.08730E-04 491171 + 482 491180 In-118 1.12310E-08 1.57000E-04 491180 + 483 491181 In-118m 1.72140E-08 3.36530E-08 491181 + 484 491182 In-118m 1.66720E-08 1.66720E-08 491182 + 485 491200 In-120 2.41800E-11 1.77110E-04 491200 + 486 491201 In-120m 2.41800E-11 2.41800E-11 491201 + 487 491202 In-120m 2.41800E-11 2.41800E-11 491202 + 488 491210 In-121 5.04280E-09 1.20550E-04 491210 + 489 491211 In-121m 1.16600E-09 6.68790E-05 491211 + 490 491220 In-122 4.24150E-08 1.97500E-04 491220 + 491 491221 In-122m 3.00930E-08 3.00930E-08 491221 + 492 491222 In-122m 3.00930E-08 3.00930E-08 491222 + 493 491230 In-123 3.53030E-05 1.57660E-04 491230 + 494 491231 In-123m 8.16290E-06 5.08730E-05 491231 + 495 491240 In-124 4.30400E-05 2.38320E-04 491240 + 496 491241 In-124m 3.87700E-05 3.87700E-05 491241 + 497 491250 In-125 3.23700E-04 6.36660E-04 491250 + 498 491251 In-125m 7.48480E-05 1.39930E-04 491251 + 499 491260 In-126 5.12800E-04 1.06980E-03 491260 + 500 491261 In-126m 4.61930E-04 4.61930E-04 491261 + 501 491270 In-127 1.54930E-03 1.54930E-03 491270 + 502 491271 In-127m 3.58230E-04 1.07230E-03 491271 + 503 491280 In-128 9.16650E-04 1.74300E-03 491280 + 504 491281 In-128m 3.73130E-04 8.26390E-04 491281 + 505 491282 In-128m 1.16180E-03 1.16180E-03 491282 + 506 491290 In-129 2.35520E-03 2.47700E-03 491290 + 507 491291 In-129m 5.44580E-04 5.95310E-04 491291 + 508 491300 In-130 3.16200E-04 3.40720E-04 491300 + 509 491301 In-130m 3.53170E-04 3.53170E-04 491301 + 510 491302 In-130m 6.00900E-04 6.00900E-04 491302 + 511 491310 In-131 2.04890E-04 2.07050E-04 491310 + 512 491311 In-131m 2.04890E-04 2.04890E-04 491311 + 513 491312 In-131m 2.04890E-04 2.04890E-04 491312 + 514 491320 In-132 6.60520E-05 6.60530E-05 491320 + 515 491330 In-133 6.71950E-06 8.27320E-06 491330 + 516 491331 In-133m 1.55370E-06 1.55370E-06 491331 + 517 491340 In-134 1.68360E-08 1.68360E-08 491340 + 518 501180 Sn-118 6.24700E-12 1.57030E-04 50118.82c + 519 501220 Sn-122 1.36420E-11 1.97560E-04 50122.82c + 520 501230 Sn-123 4.89040E-10 1.20200E-05 50123.82c + 521 501231 Sn-123m 2.02570E-10 1.96510E-04 501231 + 522 501240 Sn-124 4.90850E-05 3.26180E-04 50124.82c + 523 501250 Sn-125 2.81810E-04 3.89360E-04 50125.82c + 524 501251 Sn-125m 1.16730E-04 7.85780E-04 501251 + 525 501260 Sn-126 8.81890E-04 2.42100E-03 50126.82c + 526 501270 Sn-127 1.28840E-03 1.89230E-03 501270 + 527 501271 Sn-127m 5.33690E-04 2.54400E-03 501271 + 528 501280 Sn-128 2.09280E-03 9.89960E-03 501280 + 529 501281 Sn-128m 4.90190E-03 6.06370E-03 501281 + 530 501290 Sn-129 3.64510E-03 6.45400E-03 501290 + 531 501291 Sn-129m 8.79990E-03 9.06360E-03 501291 + 532 501300 Sn-130 5.82000E-03 6.66510E-03 501300 + 533 501301 Sn-130m 1.36320E-02 1.40860E-02 501301 + 534 501310 Sn-131 5.21510E-03 5.61200E-03 501310 + 535 501311 Sn-131m 1.25900E-02 1.28040E-02 501311 + 536 501320 Sn-132 1.42770E-02 1.43500E-02 501320 + 537 501330 Sn-133 2.34140E-03 2.34260E-03 501330 + 538 501340 Sn-134 3.60370E-04 3.60380E-04 501340 + 539 501350 Sn-135 3.79140E-05 3.79140E-05 501350 + 540 501360 Sn-136 7.90330E-06 7.90330E-06 501360 + 541 501370 Sn-137 1.67010E-09 1.67010E-09 501370 + 542 511250 Sb-125 4.80950E-10 1.17510E-03 51125.82c + 543 511260 Sb-126 1.71500E-05 2.12470E-05 51126.82c + 544 511261 Sb-126m 1.26810E-05 2.92650E-05 511261 + 545 511262 Sb-126m 1.65840E-05 1.65840E-05 511262 + 546 511270 Sb-127 1.70820E-04 4.60710E-03 511270 + 547 511280 Sb-128 8.58640E-05 9.99070E-03 511280 + 548 511281 Sb-128m 1.46520E-04 1.46520E-04 511281 + 549 511290 Sb-129 1.09590E-03 1.28620E-02 511290 + 550 511291 Sb-129m 6.69690E-04 5.20140E-03 511291 + 551 511300 Sb-130 1.90000E-03 1.56080E-02 511300 + 552 511301 Sb-130m 1.90000E-03 8.94300E-03 511301 + 553 511310 Sb-131 1.53270E-02 3.37430E-02 511310 + 554 511320 Sb-132 1.19500E-02 2.63010E-02 511320 + 555 511321 Sb-132m 8.80760E-03 8.80760E-03 511321 + 556 511330 Sb-133 2.98180E-02 3.22220E-02 511330 + 557 511340 Sb-134 2.32920E-03 2.63230E-03 511340 + 558 511341 Sb-134m 5.45560E-03 5.45960E-03 511341 + 559 511350 Sb-135 2.98270E-03 3.01500E-03 511350 + 560 511360 Sb-136 7.00430E-04 7.05960E-04 511360 + 561 511370 Sb-137 9.41040E-05 9.41050E-05 511370 + 562 511380 Sb-138 7.69910E-06 7.69910E-06 511380 + 563 511390 Sb-139 1.80900E-06 1.80900E-06 511390 + 564 521270 Te-127 3.59040E-11 4.58890E-03 521270 + 565 521271 Te-127m 8.66760E-11 7.59240E-04 52527.82c + 566 521280 Te-128 3.71140E-08 1.01320E-02 52128.82c + 567 521290 Te-129 1.61600E-05 1.49360E-02 521290 + 568 521291 Te-129m 3.90130E-05 6.49120E-03 52529.82c + 569 521300 Te-130 5.98500E-04 2.51500E-02 52130.82c + 570 521310 Te-131 6.56740E-04 3.25980E-02 521310 + 571 521311 Te-131m 1.58550E-03 4.28690E-03 521311 + 572 521320 Te-132 1.31140E-02 4.82220E-02 52132.82c + 573 521330 Te-133 7.99820E-03 3.90060E-02 521330 + 574 521331 Te-133m 1.93090E-02 2.48820E-02 521331 + 575 521340 Te-134 5.23220E-02 6.08840E-02 521340 + 576 521350 Te-135 3.44540E-02 3.71110E-02 521350 + 577 521360 Te-136 3.48330E-02 3.54680E-02 521360 + 578 521370 Te-137 8.92280E-03 8.97080E-03 521370 + 579 521380 Te-138 3.35250E-03 3.36020E-03 521380 + 580 521390 Te-139 3.61790E-04 3.63600E-04 521390 + 581 521400 Te-140 1.07170E-04 1.07170E-04 521400 + 582 521410 Te-141 3.16420E-06 3.16420E-06 521410 + 583 521420 Te-142 5.36790E-09 5.36790E-09 521420 + 584 531300 I-130 3.53810E-09 4.80690E-09 53130.82c + 585 531301 I-130m 1.51050E-09 1.51050E-09 531301 + 586 531310 I-131 6.25160E-06 3.59910E-02 53131.82c + 587 531320 I-132 3.33880E-05 4.82770E-02 531320 + 588 531321 I-132m 2.46070E-05 2.46070E-05 531321 + 589 531330 I-133 5.16960E-04 6.03670E-02 531330 + 590 531331 I-133m 3.15910E-04 3.15910E-04 531331 + 591 531340 I-134 1.34030E-03 6.31900E-02 531340 + 592 531341 I-134m 9.87850E-04 9.87850E-04 531341 + 593 531350 I-135 1.59380E-02 5.30490E-02 53135.82c + 594 531360 I-136 7.93690E-03 4.35390E-02 531360 + 595 531361 I-136m 1.85900E-02 1.87240E-02 531361 + 596 531370 I-137 3.41260E-02 4.30400E-02 531370 + 597 531380 I-138 1.36560E-02 1.68040E-02 531380 + 598 531390 I-139 1.36050E-02 1.39690E-02 531390 + 599 531400 I-140 3.43630E-03 3.54350E-03 531400 + 600 531410 I-141 1.43440E-03 1.43760E-03 531410 + 601 531420 I-142 2.01140E-04 2.01150E-04 531420 + 602 531430 I-143 2.75140E-05 2.75140E-05 531430 + 603 531440 I-144 1.48190E-06 1.48190E-06 531440 + 604 541320 Xe-132 9.00840E-10 4.82800E-02 54132.82c + 605 541321 Xe-132m 1.02120E-09 1.02120E-09 541321 + 606 541330 Xe-133 3.23100E-06 6.03780E-02 54133.82c + 607 541331 Xe-133m 7.80000E-06 1.72610E-03 541331 + 608 541340 Xe-134 2.87020E-05 6.33080E-02 54134.82c + 609 541341 Xe-134m 6.72270E-05 8.99480E-05 541341 + 610 541350 Xe-135 2.00380E-04 5.36770E-02 54135.82c + 611 541351 Xe-135m 4.83740E-04 9.24140E-03 541351 + 612 541360 Xe-136 9.23250E-03 7.42930E-02 54136.82c + 613 541370 Xe-137 1.94540E-02 6.05870E-02 541370 + 614 541380 Xe-138 4.09590E-02 5.82420E-02 541380 + 615 541390 Xe-139 3.73230E-02 5.02520E-02 541390 + 616 541400 Xe-140 5.05720E-02 5.40880E-02 541400 + 617 541410 Xe-141 2.89130E-02 3.00990E-02 541410 + 618 541420 Xe-142 2.09930E-02 2.11550E-02 541420 + 619 541430 Xe-143 4.05970E-03 4.07680E-03 541430 + 620 541440 Xe-144 8.74360E-04 8.75250E-04 541440 + 621 541450 Xe-145 9.71860E-05 9.71860E-05 541450 + 622 541460 Xe-146 1.27930E-05 1.27930E-05 541460 + 623 541470 Xe-147 1.45470E-09 1.45470E-09 541470 + 624 551350 Cs-135 1.02320E-06 5.37340E-02 55135.82c + 625 551351 Cs-135m 6.25240E-07 6.25240E-07 551351 + 626 551360 Cs-136 6.22890E-06 8.05410E-06 55136.82c + 627 551361 Cs-136m 3.65040E-06 3.65040E-06 551361 + 628 551370 Cs-137 2.43780E-04 6.08310E-02 55137.82c + 629 551380 Cs-138 5.20220E-04 5.93600E-02 551380 + 630 551381 Cs-138m 7.38180E-04 7.38180E-04 551381 + 631 551390 Cs-139 5.29190E-03 5.55440E-02 551390 + 632 551400 Cs-140 8.57490E-03 6.26760E-02 551400 + 633 551410 Cs-141 2.76700E-02 5.78320E-02 551410 + 634 551420 Cs-142 2.68920E-02 4.80110E-02 551420 + 635 551430 Cs-143 2.69720E-02 3.10340E-02 551430 + 636 551440 Cs-144 4.19630E-03 7.14720E-03 551440 + 637 551441 Cs-144m 4.19630E-03 4.19880E-03 551441 + 638 551450 Cs-145 3.99170E-03 4.08490E-03 551450 + 639 551460 Cs-146 6.56500E-04 6.68410E-04 551460 + 640 551470 Cs-147 1.18170E-04 1.18170E-04 551470 + 641 551480 Cs-148 1.26820E-05 1.26820E-05 551480 + 642 551490 Cs-149 5.43810E-07 5.43810E-07 551490 + 643 561370 Ba-137 2.62510E-07 6.08320E-02 56137.82c + 644 561371 Ba-137m 6.33730E-07 5.74250E-02 561371 + 645 561380 Ba-138 3.16530E-05 5.95320E-02 56138.82c + 646 561390 Ba-139 2.80380E-04 5.58240E-02 561390 + 647 561400 Ba-140 1.50740E-03 6.41830E-02 56140.82c + 648 561410 Ba-141 4.74500E-03 6.25770E-02 561410 + 649 561420 Ba-142 1.92410E-02 6.77610E-02 561420 + 650 561430 Ba-143 2.77010E-02 5.84550E-02 561430 + 651 561440 Ba-144 3.56020E-02 4.52040E-02 561440 + 652 561450 Ba-145 2.34650E-02 2.70610E-02 561450 + 653 561460 Ba-146 1.71310E-02 1.77380E-02 561460 + 654 561470 Ba-147 5.21440E-03 5.30210E-03 561470 + 655 561480 Ba-148 1.97410E-03 1.98360E-03 561480 + 656 561490 Ba-149 2.37100E-04 2.37640E-04 561490 + 657 561500 Ba-150 2.57330E-05 2.57330E-05 561500 + 658 561510 Ba-151 2.62710E-08 2.62710E-08 561510 + 659 561520 Ba-152 3.18650E-10 3.18650E-10 561520 + 660 571400 La-140 7.16060E-09 6.41830E-02 57140.82c + 661 571410 La-141 2.42590E-05 6.26010E-02 571410 + 662 571420 La-142 8.39930E-05 6.78450E-02 571420 + 663 571430 La-143 7.22540E-04 5.91780E-02 571430 + 664 571440 La-144 1.92500E-03 4.71290E-02 571440 + 665 571450 La-145 6.26090E-03 3.33220E-02 571450 + 666 571460 La-146 2.17140E-03 1.99100E-02 571460 + 667 571461 La-146m 3.90580E-03 3.90580E-03 571461 + 668 571470 La-147 9.59760E-03 1.49080E-02 571470 + 669 571480 La-148 4.81580E-03 6.79250E-03 571480 + 670 571490 La-149 2.69820E-03 2.93480E-03 571490 + 671 571500 La-150 5.56600E-04 5.82330E-04 571500 + 672 571510 La-151 1.95820E-04 1.95850E-04 571510 + 673 571520 La-152 2.45940E-05 2.45940E-05 571520 + 674 571530 La-153 1.10670E-06 1.10670E-06 571530 + 675 571540 La-154 4.69720E-10 4.69720E-10 571540 + 676 581430 Ce-143 5.09520E-06 5.91830E-02 58143.82c + 677 581440 Ce-144 1.09660E-04 4.72390E-02 58144.82c + 678 581450 Ce-145 4.78110E-04 3.38000E-02 581450 + 679 581460 Ce-146 1.64770E-03 2.54630E-02 581460 + 680 581470 Ce-147 3.28790E-03 1.81950E-02 581470 + 681 581480 Ce-148 6.20090E-03 1.30340E-02 581480 + 682 581490 Ce-149 4.55020E-03 7.45970E-03 581490 + 683 581500 Ce-150 3.93150E-03 4.49810E-03 581500 + 684 581510 Ce-151 2.04630E-03 2.24360E-03 581510 + 685 581520 Ce-152 9.38520E-04 9.61630E-04 581520 + 686 581530 Ce-153 2.02530E-04 2.03640E-04 581530 + 687 581540 Ce-154 2.04870E-05 2.04870E-05 581540 + 688 581550 Ce-155 1.77810E-06 1.77810E-06 581550 + 689 581560 Ce-156 1.80830E-09 1.80830E-09 581560 + 690 581570 Ce-157 1.14320E-11 1.14320E-11 581570 + 691 591450 Pr-145 3.43820E-09 3.38000E-02 591450 + 692 591460 Pr-146 4.04000E-06 2.54670E-02 591460 + 693 591470 Pr-147 2.67070E-05 1.82220E-02 591470 + 694 591480 Pr-148 1.43860E-05 1.30490E-02 591480 + 695 591481 Pr-148m 6.05000E-05 6.05000E-05 591481 + 696 591490 Pr-149 2.64290E-04 7.72400E-03 591490 + 697 591500 Pr-150 3.93140E-04 4.89120E-03 591500 + 698 591510 Pr-151 1.00850E-03 3.25210E-03 591510 + 699 591520 Pr-152 6.88620E-04 1.65150E-03 591520 + 700 591530 Pr-153 6.45220E-04 8.47720E-04 591530 + 701 591540 Pr-154 1.40950E-04 1.61310E-04 591540 + 702 591550 Pr-155 4.80110E-05 4.97890E-05 591550 + 703 591560 Pr-156 4.55360E-06 4.55540E-06 591560 + 704 591570 Pr-157 1.46650E-07 1.46660E-07 591570 + 705 591580 Pr-158 2.74220E-09 2.74220E-09 591580 + 706 591590 Pr-159 1.31930E-11 1.31930E-11 591590 + 707 601480 Nd-148 6.03920E-07 1.31100E-02 60148.82c + 708 601490 Nd-149 8.70110E-06 7.73260E-03 601490 + 709 601500 Nd-150 4.19350E-05 4.93320E-03 60150.82c + 710 601510 Nd-151 1.46110E-04 3.39820E-03 601510 + 711 601520 Nd-152 3.47480E-04 1.99900E-03 601520 + 712 601530 Nd-153 4.60400E-04 1.30810E-03 601530 + 713 601540 Nd-154 2.98290E-04 4.59600E-04 601540 + 714 601550 Nd-155 1.45810E-04 1.95720E-04 601550 + 715 601560 Nd-156 8.65180E-05 9.09590E-05 601560 + 716 601570 Nd-157 2.95190E-05 2.96560E-05 601570 + 717 601580 Nd-158 3.14720E-06 3.14990E-06 601580 + 718 601590 Nd-159 4.05990E-08 4.06120E-08 601590 + 719 601600 Nd-160 3.15770E-09 3.15770E-09 601600 + 720 601610 Nd-161 1.72890E-11 1.72890E-11 601610 + 721 611500 Pm-150 2.20800E-10 2.20800E-10 611500 + 722 611510 Pm-151 1.85030E-08 3.39830E-03 61151.82c + 723 611520 Pm-152 3.04810E-07 1.99930E-03 611520 + 724 611521 Pm-152m 6.08660E-07 6.08660E-07 611521 + 725 611522 Pm-152m 6.73240E-07 6.73240E-07 611522 + 726 611530 Pm-153 7.74700E-06 1.31590E-03 611530 + 727 611540 Pm-154 4.09730E-06 4.63690E-04 611540 + 728 611541 Pm-154m 4.09730E-06 4.09730E-06 611541 + 729 611550 Pm-155 2.22270E-05 2.17950E-04 611550 + 730 611560 Pm-156 2.04910E-05 1.11450E-04 611560 + 731 611570 Pm-157 3.79530E-05 6.76100E-05 611570 + 732 611580 Pm-158 2.83240E-05 3.14740E-05 611580 + 733 611590 Pm-159 6.26630E-06 6.30680E-06 611590 + 734 611600 Pm-160 9.85280E-07 9.88410E-07 611600 + 735 611610 Pm-161 3.25770E-08 3.25940E-08 611610 + 736 611620 Pm-162 1.81330E-09 1.81330E-09 611620 + 737 611630 Pm-163 9.42520E-11 9.42520E-11 611630 + 738 621530 Sm-153 1.74280E-10 1.31590E-03 62153.82c + 739 621531 Sm-153m 4.20750E-10 4.20750E-10 621531 + 740 621540 Sm-154 1.76060E-08 4.67810E-04 62154.82c + 741 621550 Sm-155 3.55620E-06 2.21510E-04 621550 + 742 621560 Sm-156 3.41510E-06 1.14870E-04 621560 + 743 621570 Sm-157 4.21700E-06 7.18260E-05 621570 + 744 621580 Sm-158 1.25890E-05 4.40640E-05 621580 + 745 621590 Sm-159 3.22100E-06 9.52930E-06 621590 + 746 621600 Sm-160 3.94120E-06 4.92700E-06 621600 + 747 621610 Sm-161 6.04250E-07 6.36840E-07 621610 + 748 621620 Sm-162 3.61350E-07 3.63160E-07 621620 + 749 621630 Sm-163 4.43440E-08 4.44380E-08 621630 + 750 621640 Sm-164 6.94330E-09 6.94330E-09 621640 + 751 621650 Sm-165 2.83560E-10 2.83560E-10 621650 + 752 631550 Eu-155 7.39830E-12 2.21510E-04 63155.82c + 753 631560 Eu-156 3.05210E-10 1.14870E-04 63156.82c + 754 631570 Eu-157 1.12770E-08 7.18380E-05 63157.82c + 755 631580 Eu-158 9.12130E-08 4.41550E-05 631580 + 756 631590 Eu-159 1.94390E-07 9.72370E-06 631590 + 757 631600 Eu-160 5.32880E-07 5.45980E-06 631600 + 758 631610 Eu-161 5.64320E-07 1.20120E-06 631610 + 759 631620 Eu-162 5.45570E-07 9.08730E-07 631620 + 760 631630 Eu-163 5.89430E-07 6.33870E-07 631630 + 761 631640 Eu-164 1.83770E-07 1.90710E-07 631640 + 762 631650 Eu-165 8.48920E-08 8.51760E-08 631650 + 763 631660 Eu-166 7.25320E-09 7.25320E-09 631660 + 764 631670 Eu-167 8.52740E-10 8.52740E-10 631670 + 765 641580 Gd-158 2.10510E-11 4.41550E-05 64158.82c + 766 641590 Gd-159 1.17570E-10 9.72380E-06 641590 + 767 641600 Gd-160 3.96800E-09 5.46380E-06 64160.82c + 768 641610 Gd-161 9.43970E-09 1.21060E-06 641610 + 769 641620 Gd-162 9.15850E-08 1.00030E-06 641620 + 770 641630 Gd-163 1.73020E-07 8.06890E-07 641630 + 771 641640 Gd-164 4.39310E-07 6.30020E-07 641640 + 772 641650 Gd-165 3.36370E-07 4.21550E-07 641650 + 773 641660 Gd-166 2.68090E-07 2.75340E-07 641660 + 774 641670 Gd-167 6.65840E-08 6.74370E-08 641670 + 775 641680 Gd-168 2.21690E-08 2.21690E-08 641680 + 776 641690 Gd-169 1.41680E-09 1.41680E-09 641690 + 777 651610 Tb-161 3.50770E-12 1.21060E-06 651610 + 778 651620 Tb-162 8.61290E-11 1.00040E-06 651620 + 779 651630 Tb-163 1.93580E-09 8.08820E-07 651630 + 780 651640 Tb-164 1.04890E-08 6.40510E-07 651640 + 781 651650 Tb-165 7.57520E-08 4.97300E-07 651650 + 782 651660 Tb-166 1.00750E-07 3.76090E-07 651660 + 783 651670 Tb-167 2.03350E-07 2.70790E-07 651670 + 784 651680 Tb-168 1.17270E-07 1.39440E-07 651680 + 785 651690 Tb-169 7.43770E-08 7.57940E-08 651690 + 786 651700 Tb-170 1.07720E-08 1.07720E-08 651700 + 787 651710 Tb-171 2.48730E-09 2.48730E-09 651710 + 788 661640 Dy-164 1.24080E-11 6.40520E-07 66164.82c + 789 661650 Dy-165 1.90950E-10 4.97520E-07 661650 + 790 661651 Dy-165m 2.91910E-11 2.91910E-11 661651 + 791 661660 Dy-166 3.34000E-09 3.79430E-07 661660 + 792 661670 Dy-167 1.35730E-08 2.84360E-07 661670 + 793 661680 Dy-168 6.95910E-08 2.09030E-07 661680 + 794 661690 Dy-169 7.15610E-08 1.47360E-07 661690 + 795 661700 Dy-170 8.60220E-08 9.67940E-08 661700 + 796 661710 Dy-171 3.64050E-08 3.88920E-08 661710 + 797 661720 Dy-172 1.39700E-08 1.39700E-08 661720 + 798 671670 Ho-167 2.50170E-11 2.84380E-07 671670 + 799 671680 Ho-168 1.26040E-10 2.09330E-07 671680 + 800 671681 Ho-168m 1.78850E-10 1.78850E-10 671681 + 801 671690 Ho-169 3.40190E-09 1.50760E-07 671690 + 802 671700 Ho-170 5.42420E-09 5.42420E-09 671700 + 803 671701 Ho-170m 2.31580E-09 9.91100E-08 671701 + 804 671710 Ho-171 2.77240E-08 6.66160E-08 671710 + 805 671720 Ho-172 1.71410E-08 3.11110E-08 671720 + 806 671730 Ho-173 3.15000E-12 3.15000E-12 671730 + 807 681690 Er-169 1.55920E-12 1.50760E-07 681690 + 808 681700 Er-170 4.41990E-11 1.04580E-07 68170.82c + 809 681710 Er-171 3.61340E-10 6.69780E-08 681710 + 810 681720 Er-172 2.28930E-09 3.34000E-08 681720 + 811 691720 Tm-172 1.64080E-12 3.34020E-08 691720 + + Neutron-induced fission: + + Interpolation region : 2 / 2 + Interpolation energy : 4.00000E-01 MeV + Number of products : 801 / 933 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 3.00310E-05 3.00310E-05 1001.82c + 2 10020 H-2 9.17770E-06 9.17770E-06 1002.82c + 3 10030 H-3 1.30940E-04 1.30940E-04 1003.82c + 4 20040 He-4 1.89850E-03 1.89850E-03 2004.82c + 5 220550 Ti-55 1.36370E-12 1.36370E-12 220550 + 6 220560 Ti-56 2.25450E-12 2.25450E-12 220560 + 7 230560 V-56 2.24750E-12 4.50200E-12 230560 + 8 230570 V-57 7.35950E-12 7.35950E-12 230570 + 9 230580 V-58 7.41320E-12 7.41320E-12 230580 + 10 230590 V-59 1.02930E-11 1.02930E-11 230590 + 11 230600 V-60 2.85480E-12 2.85480E-12 230600 + 12 230610 V-61 1.24100E-12 1.24100E-12 230610 + 13 240570 Cr-57 1.42120E-12 1.46820E-11 240570 + 14 240580 Cr-58 1.16080E-11 1.30910E-11 240580 + 15 240590 Cr-59 2.59090E-11 3.62020E-11 240590 + 16 240600 Cr-60 6.27810E-11 6.57100E-11 240600 + 17 240610 Cr-61 5.42880E-11 5.54540E-11 240610 + 18 240620 Cr-62 6.20490E-11 6.20490E-11 240620 + 19 240630 Cr-63 1.38570E-11 1.38570E-11 240630 + 20 240640 Cr-64 3.61460E-12 3.61460E-12 240640 + 21 250590 Mn-59 3.69940E-12 3.99010E-11 250590 + 22 250600 Mn-60 1.36700E-12 6.86770E-11 250600 + 23 250601 Mn-60m 1.39070E-11 1.39070E-11 250601 + 24 250610 Mn-61 1.05200E-10 1.60650E-10 250610 + 25 250620 Mn-62 1.71930E-10 2.02960E-10 250620 + 26 250621 Mn-62m 2.69260E-11 5.79500E-11 250621 + 27 250630 Mn-63 4.10220E-10 4.24080E-10 250630 + 28 250640 Mn-64 2.24760E-10 2.28370E-10 250640 + 29 250650 Mn-65 2.09360E-10 2.09360E-10 250650 + 30 250660 Mn-66 3.79380E-11 3.79380E-11 250660 + 31 250670 Mn-67 7.90550E-12 7.90550E-12 250670 + 32 260610 Fe-61 4.32000E-12 1.64970E-10 260610 + 33 260620 Fe-62 7.41560E-11 3.35070E-10 260620 + 34 260630 Fe-63 2.50400E-10 6.74480E-10 260630 + 35 260640 Fe-64 1.09620E-09 1.32460E-09 260640 + 36 260650 Fe-65 1.76520E-09 1.97460E-09 260650 + 37 260660 Fe-66 3.13140E-09 3.16930E-09 260660 + 38 260670 Fe-67 1.43850E-09 1.44640E-09 260670 + 39 260680 Fe-68 9.15070E-10 9.15070E-10 260680 + 40 260690 Fe-69 1.32510E-10 1.32510E-10 260690 + 41 260700 Fe-70 1.80400E-11 1.80400E-11 260700 + 42 270630 Co-63 7.02240E-12 6.81500E-10 270630 + 43 270640 Co-64 6.01260E-11 1.38470E-09 270640 + 44 270650 Co-65 8.33090E-10 2.80760E-09 270650 + 45 270660 Co-66 2.36450E-09 5.53380E-09 270660 + 46 270670 Co-67 8.88790E-09 1.03340E-08 270670 + 47 270680 Co-68 5.90870E-09 8.57600E-09 270680 + 48 270681 Co-68m 4.41030E-09 5.33470E-09 270681 + 49 270690 Co-69 1.54630E-08 1.55860E-08 270690 + 50 270700 Co-70 2.41810E-09 2.41810E-09 270700 + 51 270701 Co-70m 2.41810E-09 2.43610E-09 270701 + 52 270710 Co-71 2.49260E-09 2.49260E-09 270710 + 53 270720 Co-72 2.92030E-10 2.92030E-10 270720 + 54 270730 Co-73 3.10950E-11 3.10950E-11 270730 + 55 280650 Ni-65 6.22330E-12 2.81390E-09 280650 + 56 280660 Ni-66 1.84650E-10 5.71850E-09 280660 + 57 280670 Ni-67 1.28090E-09 1.16150E-08 280670 + 58 280680 Ni-68 1.22500E-08 2.36490E-08 280680 + 59 280690 Ni-69 1.46560E-08 3.00860E-08 280690 + 60 280691 Ni-69m 1.46560E-08 1.46560E-08 280691 + 61 280700 Ni-70 7.81420E-08 8.29960E-08 280700 + 62 280710 Ni-71 7.78890E-08 8.03820E-08 280710 + 63 280720 Ni-72 9.92740E-08 9.95660E-08 280720 + 64 280730 Ni-73 2.51240E-08 2.51550E-08 280730 + 65 280740 Ni-74 6.24440E-09 6.24440E-09 280740 + 66 280750 Ni-75 1.16220E-09 1.16220E-09 280750 + 67 280760 Ni-76 2.42430E-11 2.42430E-11 280760 + 68 290670 Cu-67 6.10980E-12 1.16210E-08 290670 + 69 290680 Cu-68 3.48710E-11 2.37640E-08 290680 + 70 290681 Cu-68m 9.50500E-11 9.50500E-11 290681 + 71 290690 Cu-69 3.07700E-09 4.78180E-08 290690 + 72 290700 Cu-70 9.69600E-10 9.26010E-09 290700 + 73 290701 Cu-70m 1.23830E-08 1.65810E-08 290701 + 74 290702 Cu-70m 9.69600E-10 8.39660E-08 290702 + 75 290710 Cu-71 1.14420E-07 1.94800E-07 290710 + 76 290720 Cu-72 2.37300E-07 3.36870E-07 290720 + 77 290730 Cu-73 5.39420E-07 5.64580E-07 290730 + 78 290740 Cu-74 2.74380E-07 2.80640E-07 290740 + 79 290750 Cu-75 5.79890E-07 5.81030E-07 290750 + 80 290760 Cu-76 1.48110E-08 1.48230E-08 290760 + 81 290761 Cu-76m 1.48110E-08 1.48230E-08 290761 + 82 290770 Cu-77 1.62690E-08 1.62690E-08 290770 + 83 290780 Cu-78 1.34530E-09 1.34530E-09 290780 + 84 290790 Cu-79 1.67400E-10 1.67400E-10 290790 + 85 300690 Zn-69 6.20170E-13 4.78220E-08 300690 + 86 300691 Zn-69m 3.08010E-12 3.08010E-12 300691 + 87 300700 Zn-70 2.00600E-10 9.75190E-08 300700 + 88 300710 Zn-71 5.69770E-10 1.95370E-07 300710 + 89 300711 Zn-71m 2.82980E-09 2.82980E-09 300711 + 90 300720 Zn-72 6.58620E-08 4.02730E-07 300720 + 91 300730 Zn-73 2.18780E-08 7.15390E-07 300730 + 92 300731 Zn-73m 3.02610E-08 1.28940E-07 300731 + 93 300732 Zn-73m 1.97360E-07 1.97360E-07 300732 + 94 300740 Zn-74 1.18160E-06 1.48260E-06 300740 + 95 300750 Zn-75 5.70380E-06 6.26490E-06 300750 + 96 300760 Zn-76 1.75140E-06 1.78060E-06 300760 + 97 300770 Zn-77 1.32810E-06 1.43280E-06 300770 + 98 300771 Zn-77m 1.76830E-07 1.76830E-07 300771 + 99 300780 Zn-78 1.36590E-05 1.36600E-05 300780 + 100 300790 Zn-79 3.15280E-06 3.15290E-06 300790 + 101 300800 Zn-80 1.55130E-07 1.55130E-07 300800 + 102 300810 Zn-81 1.66770E-06 1.66770E-06 300810 + 103 300820 Zn-82 4.05480E-10 4.05480E-10 300820 + 104 310710 Ga-71 2.49790E-12 1.98200E-07 310710 + 105 310720 Ga-72 1.06920E-10 4.02850E-07 310720 + 106 310721 Ga-72m 1.05100E-11 1.34300E-08 310721 + 107 310730 Ga-73 4.98650E-09 8.19060E-07 310730 + 108 310740 Ga-74 2.02930E-08 1.14740E-06 310740 + 109 310741 Ga-74m 2.02930E-08 1.50290E-06 310741 + 110 310750 Ga-75 1.27870E-06 7.54360E-06 310750 + 111 310760 Ga-76 1.82200E-06 3.60260E-06 310760 + 112 310770 Ga-77 4.51450E-06 6.03570E-06 310770 + 113 310780 Ga-78 6.07110E-06 1.97730E-05 310780 + 114 310790 Ga-79 2.99480E-05 3.30600E-05 310790 + 115 310800 Ga-80 2.50670E-05 2.53470E-05 310800 + 116 310810 Ga-81 3.83540E-05 3.98970E-05 310810 + 117 310820 Ga-82 3.32300E-06 3.32340E-06 310820 + 118 310830 Ga-83 3.62940E-07 3.62940E-07 310830 + 119 310840 Ga-84 1.27910E-08 1.27910E-08 310840 + 120 310850 Ga-85 5.26490E-10 5.26490E-10 310850 + 121 320740 Ge-74 9.06660E-11 1.52320E-06 32074.82c + 122 320750 Ge-75 7.89750E-10 7.55030E-06 320750 + 123 320751 Ge-75m 5.93160E-09 3.07680E-07 320751 + 124 320760 Ge-76 9.10990E-07 4.51360E-06 32076.82c + 125 320770 Ge-77 5.31210E-06 6.59330E-06 320770 + 126 320771 Ge-77m 7.07280E-07 6.74300E-06 320771 + 127 320780 Ge-78 1.51790E-05 3.49810E-05 320780 + 128 320790 Ge-79 1.14850E-05 4.79190E-05 320790 + 129 320791 Ge-79m 8.62630E-05 8.63120E-05 320791 + 130 320800 Ge-80 2.82540E-04 3.12640E-04 320800 + 131 320810 Ge-81 4.59950E-04 4.79960E-04 320810 + 132 320811 Ge-81m 9.26090E-05 1.09550E-04 320811 + 133 320820 Ge-82 1.00950E-03 1.01220E-03 320820 + 134 320830 Ge-83 5.68300E-04 5.68540E-04 320830 + 135 320840 Ge-84 2.89930E-04 2.89930E-04 320840 + 136 320850 Ge-85 7.05370E-05 7.05380E-05 320850 + 137 320860 Ge-86 1.79160E-05 1.79160E-05 320860 + 138 320870 Ge-87 5.79250E-09 5.79250E-09 320870 + 139 330760 As-76 1.54380E-11 1.54380E-11 330760 + 140 330770 As-77 3.40320E-09 1.20580E-05 330770 + 141 330780 As-78 1.12150E-07 3.50930E-05 330780 + 142 330790 As-79 4.72930E-06 1.35510E-04 330790 + 143 330800 As-80 4.68060E-05 3.59440E-04 330800 + 144 330810 As-81 1.60260E-04 7.48680E-04 330810 + 145 330820 As-82 1.58400E-04 1.17070E-03 330820 + 146 330821 As-82m 5.51920E-04 5.51920E-04 330821 + 147 330830 As-83 2.00000E-03 2.59980E-03 330830 + 148 330840 As-84 1.23770E-03 1.37200E-03 330840 + 149 330841 As-84m 1.23770E-03 1.37200E-03 330841 + 150 330850 As-85 1.78690E-03 1.84760E-03 330850 + 151 330860 As-86 5.98710E-04 6.16630E-04 330860 + 152 330870 As-87 2.37680E-04 2.37690E-04 330870 + 153 330880 As-88 2.79100E-05 2.79100E-05 330880 + 154 330890 As-89 1.60610E-06 1.60610E-06 330890 + 155 330900 As-90 1.05390E-09 1.05390E-09 330900 + 156 340780 Se-78 3.74950E-11 3.50930E-05 34078.82c + 157 340790 Se-79 4.18730E-09 1.35440E-04 34079.82c + 158 340791 Se-79m 5.57510E-10 1.32300E-04 340791 + 159 340800 Se-80 6.68200E-06 3.66120E-04 34080.82c + 160 340810 Se-81 2.93400E-06 7.73620E-04 340810 + 161 340811 Se-81m 2.20360E-05 4.89130E-05 340811 + 162 340820 Se-82 3.25110E-04 2.04770E-03 34082.82c + 163 340830 Se-83 1.41750E-03 2.35540E-03 340830 + 164 340831 Se-83m 2.85410E-04 1.95120E-03 340831 + 165 340840 Se-84 6.11700E-03 9.26350E-03 340840 + 166 340850 Se-85 1.03180E-02 1.19630E-02 340850 + 167 340860 Se-86 1.23980E-02 1.28480E-02 340860 + 168 340870 Se-87 8.17190E-03 8.37300E-03 340870 + 169 340880 Se-88 4.16830E-03 4.19620E-03 340880 + 170 340890 Se-89 1.16520E-03 1.16680E-03 340890 + 171 340900 Se-90 4.05280E-04 4.05280E-04 340900 + 172 340910 Se-91 4.75590E-05 4.75590E-05 340910 + 173 340920 Se-92 1.11330E-05 1.11330E-05 340920 + 174 350800 Br-80 3.59480E-12 1.61200E-11 350800 + 175 350801 Br-80m 1.25250E-11 1.25250E-11 350801 + 176 350810 Br-81 4.27930E-09 7.73650E-04 35081.82c + 177 350820 Br-82 1.21540E-06 1.65060E-06 350820 + 178 350821 Br-82m 4.45890E-07 4.45890E-07 350821 + 179 350830 Br-83 2.83240E-05 4.33490E-03 350830 + 180 350840 Br-84 1.46890E-04 9.41040E-03 350840 + 181 350841 Br-84m 1.46890E-04 1.46890E-04 350841 + 182 350850 Br-85 2.15250E-03 1.41150E-02 350850 + 183 350860 Br-86 5.41760E-03 1.82650E-02 350860 + 184 350870 Br-87 1.08020E-02 1.92170E-02 350870 + 185 350880 Br-88 1.09220E-02 1.51680E-02 350880 + 186 350890 Br-89 8.60130E-03 9.67710E-03 350890 + 187 350900 Br-90 5.18550E-03 5.60080E-03 350900 + 188 350910 Br-91 3.04420E-03 3.08180E-03 350910 + 189 350920 Br-92 6.07420E-04 6.18550E-04 350920 + 190 350930 Br-93 1.31140E-04 1.31140E-04 350930 + 191 350940 Br-94 1.03270E-05 1.03270E-05 350940 + 192 350950 Br-95 4.27500E-09 4.27500E-09 350950 + 193 360830 Kr-83 1.62670E-09 4.33490E-03 36083.82c + 194 360831 Kr-83m 3.27520E-10 4.33110E-03 360831 + 195 360840 Kr-84 1.54920E-05 9.57280E-03 36084.82c + 196 360850 Kr-85 9.53100E-05 3.13810E-03 36085.82c + 197 360851 Kr-85m 1.91900E-05 1.41110E-02 360851 + 198 360860 Kr-86 1.36030E-03 2.01080E-02 36086.82c + 199 360870 Kr-87 4.33820E-03 2.40890E-02 360870 + 200 360880 Kr-88 1.58430E-02 3.13590E-02 360880 + 201 360890 Kr-89 2.33070E-02 3.29970E-02 360890 + 202 360900 Kr-90 3.71340E-02 4.19730E-02 360900 + 203 360910 Kr-91 3.21640E-02 3.48340E-02 360910 + 204 360920 Kr-92 2.12530E-02 2.17560E-02 360920 + 205 360930 Kr-93 7.60840E-03 7.65760E-03 360930 + 206 360940 Kr-94 2.96130E-03 2.96440E-03 360940 + 207 360950 Kr-95 6.16420E-04 6.16420E-04 360950 + 208 360960 Kr-96 1.26210E-04 1.26210E-04 360960 + 209 360970 Kr-97 3.27350E-06 3.27350E-06 360970 + 210 370850 Rb-85 5.26490E-10 1.42300E-02 37085.82c + 211 370860 Rb-86 4.44240E-07 1.37620E-06 37086.82c + 212 370861 Rb-86m 9.31960E-07 9.31960E-07 370861 + 213 370870 Rb-87 4.41050E-05 2.41330E-02 37087.82c + 214 370880 Rb-88 1.67800E-04 3.15270E-02 370880 + 215 370890 Rb-89 1.25230E-03 3.42500E-02 370890 + 216 370900 Rb-90 4.17800E-04 3.71540E-02 370900 + 217 370901 Rb-90m 4.25040E-03 9.74050E-03 370901 + 218 370910 Rb-91 1.67110E-02 5.15450E-02 370910 + 219 370920 Rb-92 2.46330E-02 4.63890E-02 370920 + 220 370930 Rb-93 2.30980E-02 3.07880E-02 370930 + 221 370940 Rb-94 1.39530E-02 1.69020E-02 370940 + 222 370950 Rb-95 1.02500E-02 1.08530E-02 370950 + 223 370960 Rb-96 1.62160E-03 2.52370E-03 370960 + 224 370961 Rb-96m 1.62160E-03 1.68250E-03 370961 + 225 370970 Rb-97 1.03650E-03 1.03950E-03 370970 + 226 370980 Rb-98 6.69650E-05 6.69650E-05 370980 + 227 370981 Rb-98m 6.69650E-05 6.69650E-05 370981 + 228 370990 Rb-99 2.15310E-05 2.15310E-05 370990 + 229 371000 Rb-100 9.40170E-07 9.40170E-07 371000 + 230 380880 Sr-88 9.60510E-06 3.15360E-02 38088.82c + 231 380890 Sr-89 4.58380E-05 3.42960E-02 38089.82c + 232 380900 Sr-90 5.41130E-04 4.71830E-02 38090.82c + 233 380910 Sr-91 2.48870E-03 5.40340E-02 380910 + 234 380920 Sr-92 1.21700E-02 5.89900E-02 380920 + 235 380930 Sr-93 2.23890E-02 5.44540E-02 380930 + 236 380940 Sr-94 4.39840E-02 6.01120E-02 380940 + 237 380950 Sr-95 4.60740E-02 5.63320E-02 380950 + 238 380960 Sr-96 3.85450E-02 4.18330E-02 380960 + 239 380970 Sr-97 1.96210E-02 2.04090E-02 380970 + 240 380980 Sr-98 1.01800E-02 1.03080E-02 380980 + 241 380990 Sr-99 2.95070E-03 2.96890E-03 380990 + 242 381000 Sr-100 8.68000E-04 8.68890E-04 381000 + 243 381010 Sr-101 1.01390E-04 1.01390E-04 381010 + 244 381020 Sr-102 1.55290E-05 1.55290E-05 381020 + 245 390900 Y-90 3.94370E-10 4.71830E-02 39090.82c + 246 390901 Y-90m 6.59530E-10 6.59530E-10 390901 + 247 390910 Y-91 1.69910E-06 5.40440E-02 39091.82c + 248 390911 Y-91m 8.43890E-06 3.17990E-02 390911 + 249 390920 Y-92 5.88010E-05 5.90490E-02 390920 + 250 390930 Y-93 4.94520E-05 5.48740E-02 390930 + 251 390931 Y-93m 3.71420E-04 1.39980E-02 390931 + 252 390940 Y-94 1.56050E-03 6.16730E-02 390940 + 253 390950 Y-95 7.81570E-03 6.41480E-02 390950 + 254 390960 Y-96 4.74710E-03 4.65850E-02 390960 + 255 390961 Y-96m 9.95890E-03 9.96400E-03 390961 + 256 390970 Y-97 4.40600E-03 2.19360E-02 390970 + 257 390971 Y-97m 1.62860E-02 2.37990E-02 390971 + 258 390972 Y-97m 5.59690E-03 5.59690E-03 390972 + 259 390980 Y-98 3.87690E-03 1.41850E-02 390980 + 260 390981 Y-98m 1.87950E-02 1.87950E-02 390981 + 261 390990 Y-99 1.90520E-02 2.20280E-02 390990 + 262 391000 Y-100 4.82180E-03 5.68510E-03 391000 + 263 391001 Y-100m 4.82180E-03 4.82300E-03 391001 + 264 391010 Y-101 4.89100E-03 4.99080E-03 391010 + 265 391020 Y-102 5.80700E-04 5.88040E-04 391020 + 266 391021 Y-102m 5.80700E-04 5.88040E-04 391021 + 267 391030 Y-103 2.31290E-04 2.31290E-04 391030 + 268 391040 Y-104 2.80060E-05 2.80060E-05 391040 + 269 391050 Y-105 3.31870E-09 3.31870E-09 391050 + 270 400930 Zr-93 7.69750E-06 5.48820E-02 40093.82c + 271 400940 Zr-94 9.39940E-05 6.17670E-02 40094.82c + 272 400950 Zr-95 5.00960E-04 6.46490E-02 40095.82c + 273 400960 Zr-96 3.17210E-03 5.97400E-02 40096.82c + 274 400970 Zr-97 8.58570E-03 5.59390E-02 400970 + 275 400980 Zr-98 2.57460E-02 5.84160E-02 400980 + 276 400990 Zr-99 3.37620E-02 5.54680E-02 400990 + 277 401000 Zr-100 4.72400E-02 5.76960E-02 401000 + 278 401010 Zr-101 3.32680E-02 3.83170E-02 401010 + 279 401020 Zr-102 2.33680E-02 2.45050E-02 401020 + 280 401030 Zr-103 8.04690E-03 8.26210E-03 401030 + 281 401040 Zr-104 3.04920E-03 3.07470E-03 401040 + 282 401050 Zr-105 4.08890E-04 4.08890E-04 401050 + 283 401060 Zr-106 6.24740E-05 6.24740E-05 401060 + 284 401070 Zr-107 6.14540E-06 6.14540E-06 401070 + 285 401080 Zr-108 1.04340E-10 1.04340E-10 401080 + 286 410950 Nb-95 7.34980E-07 6.46110E-02 41095.82c + 287 410951 Nb-95m 1.47980E-07 6.98580E-04 410951 + 288 410960 Nb-96 6.84360E-06 6.84360E-06 410960 + 289 410970 Nb-97 6.47920E-05 5.60170E-02 410970 + 290 410971 Nb-97m 1.30460E-05 5.31820E-02 410971 + 291 410980 Nb-98 8.80400E-05 5.85040E-02 410980 + 292 410981 Nb-98m 3.06760E-04 3.06760E-04 410981 + 293 410990 Nb-99 1.78500E-03 3.72560E-02 410990 + 294 410991 Nb-99m 3.59400E-04 2.07710E-02 410991 + 295 411000 Nb-100 9.69060E-04 5.86650E-02 411000 + 296 411001 Nb-100m 4.69790E-03 4.69790E-03 411001 + 297 411010 Nb-101 1.48650E-02 5.31810E-02 411010 + 298 411020 Nb-102 9.35250E-03 3.38570E-02 411020 + 299 411021 Nb-102m 9.35250E-03 9.35250E-03 411021 + 300 411030 Nb-103 1.94470E-02 2.77090E-02 411030 + 301 411040 Nb-104 5.97600E-03 9.05650E-03 411040 + 302 411041 Nb-104m 5.97600E-03 5.97600E-03 411041 + 303 411050 Nb-105 6.50730E-03 6.91140E-03 411050 + 304 411060 Nb-106 1.43080E-03 1.49260E-03 411060 + 305 411070 Nb-107 5.70520E-04 5.76440E-04 411070 + 306 411080 Nb-108 8.35080E-05 8.35080E-05 411080 + 307 411090 Nb-109 1.50310E-08 1.50310E-08 411090 + 308 411100 Nb-110 1.05880E-10 1.05880E-10 411100 + 309 420980 Mo-98 9.06690E-06 5.88200E-02 42098.82c + 310 420990 Mo-99 7.21540E-05 5.76840E-02 42099.82c + 311 421000 Mo-100 5.76980E-04 6.39400E-02 42100.82c + 312 421010 Mo-101 1.92310E-03 5.51050E-02 421010 + 313 421020 Mo-102 6.98970E-03 5.02000E-02 421020 + 314 421030 Mo-103 1.05340E-02 3.82520E-02 421030 + 315 421040 Mo-104 1.62750E-02 3.14160E-02 421040 + 316 421050 Mo-105 1.11360E-02 1.79970E-02 421050 + 317 421060 Mo-106 6.46450E-03 7.92450E-03 421060 + 318 421070 Mo-107 3.28820E-03 3.83520E-03 421070 + 319 421080 Mo-108 1.23320E-03 1.31150E-03 421080 + 320 421090 Mo-109 1.97410E-04 1.97420E-04 421090 + 321 421100 Mo-110 3.19900E-05 3.19900E-05 421100 + 322 421110 Mo-111 3.30790E-05 3.30790E-05 421110 + 323 421120 Mo-112 3.45250E-09 3.45250E-09 421120 + 324 421130 Mo-113 1.44010E-11 1.44010E-11 421130 + 325 431010 Tc-101 9.73170E-06 5.51140E-02 431010 + 326 431020 Tc-102 2.20700E-05 5.02220E-02 431020 + 327 431021 Tc-102m 2.20700E-05 2.20700E-05 431021 + 328 431030 Tc-103 2.14990E-04 3.84670E-02 431030 + 329 431040 Tc-104 5.15100E-04 3.19320E-02 431040 + 330 431050 Tc-105 1.29880E-03 1.92960E-02 431050 + 331 431060 Tc-106 1.24890E-03 9.17340E-03 431060 + 332 431070 Tc-107 2.04390E-03 5.87910E-03 431070 + 333 431080 Tc-108 1.02150E-03 2.33410E-03 431080 + 334 431090 Tc-109 4.49780E-04 6.46160E-04 431090 + 335 431100 Tc-110 1.12140E-04 1.44470E-04 431100 + 336 431110 Tc-111 6.62970E-05 9.90350E-05 431110 + 337 431120 Tc-112 4.58640E-05 4.58670E-05 431120 + 338 431130 Tc-113 2.16410E-05 2.16410E-05 431130 + 339 431140 Tc-114 1.52670E-08 1.52670E-08 431140 + 340 431150 Tc-115 4.35150E-10 4.35150E-10 431150 + 341 441020 Ru-102 1.29460E-06 5.02450E-02 44102.82c + 342 441030 Ru-103 7.54140E-07 3.84690E-02 44103.82c + 343 441031 Ru-103m 2.11010E-06 2.11010E-06 441031 + 344 441040 Ru-104 1.68300E-05 3.19480E-02 44104.82c + 345 441050 Ru-105 4.04620E-05 1.93360E-02 44105.82c + 346 441060 Ru-106 1.25960E-04 9.29930E-03 44106.82c + 347 441070 Ru-107 2.60710E-04 6.13980E-03 441070 + 348 441080 Ru-108 2.71960E-04 2.60660E-03 441080 + 349 441090 Ru-109 2.62180E-04 9.07880E-04 441090 + 350 441100 Ru-110 4.17110E-04 5.61520E-04 441100 + 351 441110 Ru-111 4.48370E-04 5.48090E-04 441110 + 352 441120 Ru-112 6.87720E-04 7.34450E-04 441120 + 353 441130 Ru-113 1.62220E-04 2.63420E-04 441130 + 354 441131 Ru-113m 1.62220E-04 1.62220E-04 441131 + 355 441140 Ru-114 7.66600E-05 7.66740E-05 441140 + 356 441150 Ru-115 1.06380E-04 1.06380E-04 441150 + 357 441160 Ru-116 3.14700E-05 3.14700E-05 441160 + 358 441170 Ru-117 3.33780E-09 3.33780E-09 441170 + 359 441180 Ru-118 5.81010E-11 5.81010E-11 441180 + 360 441190 Ru-119 1.19880E-06 1.19880E-06 441190 + 361 441200 Ru-120 6.95560E-08 6.95560E-08 441200 + 362 451060 Rh-106 9.80840E-10 9.29930E-03 451060 + 363 451061 Rh-106m 2.67360E-09 2.67360E-09 451061 + 364 451070 Rh-107 1.91850E-07 6.14000E-03 451070 + 365 451080 Rh-108 3.17190E-07 2.60690E-03 451080 + 366 451081 Rh-108m 1.10520E-06 1.10520E-06 451081 + 367 451090 Rh-109 9.92750E-06 9.17810E-04 451090 + 368 451100 Rh-110 3.13110E-05 5.92830E-04 451100 + 369 451101 Rh-110m 7.37100E-07 7.37100E-07 451101 + 370 451110 Rh-111 4.97510E-05 5.97840E-04 451110 + 371 451120 Rh-112 1.14750E-04 8.49210E-04 451120 + 372 451121 Rh-112m 1.14750E-04 1.14750E-04 451121 + 373 451130 Rh-113 1.29910E-04 4.74450E-04 451130 + 374 451140 Rh-114 2.29930E-04 3.06850E-04 451140 + 375 451141 Rh-114m 2.29930E-04 2.29930E-04 451141 + 376 451150 Rh-115 3.72330E-04 4.78810E-04 451150 + 377 451160 Rh-116 5.06630E-05 8.17930E-05 451160 + 378 451161 Rh-116m 1.38100E-04 1.38100E-04 451161 + 379 451170 Rh-117 1.18910E-04 1.18910E-04 451170 + 380 451180 Rh-118 4.59700E-07 5.12000E-07 451180 + 381 451190 Rh-119 2.67470E-05 2.78940E-05 451190 + 382 451200 Rh-120 2.83870E-05 2.84570E-05 451200 + 383 451210 Rh-121 5.75950E-06 5.75950E-06 451210 + 384 451220 Rh-122 2.42510E-07 2.42510E-07 451220 + 385 461080 Pd-108 1.04340E-10 2.60800E-03 46108.82c + 386 461090 Pd-109 8.38880E-10 9.17810E-04 461090 + 387 461091 Pd-109m 1.84380E-09 4.58900E-04 461091 + 388 461100 Pd-110 1.01250E-07 5.93670E-04 46110.82c + 389 461110 Pd-111 4.17240E-07 5.98290E-04 461110 + 390 461111 Pd-111m 9.17060E-07 3.30840E-06 461111 + 391 461120 Pd-112 2.29390E-05 9.86890E-04 461120 + 392 461130 Pd-113 1.71040E-05 5.39410E-04 461130 + 393 461131 Pd-113m 4.78570E-05 4.78570E-05 461131 + 394 461140 Pd-114 3.83820E-04 9.20600E-04 461140 + 395 461150 Pd-115 1.33280E-04 5.71570E-04 461150 + 396 461151 Pd-115m 2.92950E-04 3.62470E-04 461151 + 397 461160 Pd-116 7.55760E-04 9.75650E-04 461160 + 398 461170 Pd-117 1.48740E-04 5.94600E-04 461170 + 399 461171 Pd-117m 3.26930E-04 3.26930E-04 461171 + 400 461180 Pd-118 4.46930E-04 4.47430E-04 461180 + 401 461190 Pd-119 2.93880E-04 3.23460E-04 461190 + 402 461200 Pd-120 7.76640E-05 1.05220E-04 461200 + 403 461210 Pd-121 2.92720E-05 3.42500E-05 461210 + 404 461220 Pd-122 1.97160E-05 1.99580E-05 461220 + 405 461230 Pd-123 1.82490E-05 1.82490E-05 461230 + 406 461240 Pd-124 2.37240E-06 2.37240E-06 461240 + 407 471110 Ag-111 2.57390E-11 5.96210E-04 47111.82c + 408 471111 Ag-111m 1.93320E-10 5.94710E-04 471111 + 409 471120 Ag-112 1.35430E-08 9.86910E-04 471120 + 410 471130 Ag-113 3.72450E-08 3.53680E-04 471130 + 411 471131 Ag-113m 2.79740E-07 5.16800E-04 471131 + 412 471140 Ag-114 8.94720E-07 9.25830E-04 471140 + 413 471141 Ag-114m 4.33760E-06 4.33760E-06 471141 + 414 471150 Ag-115 3.12740E-06 5.27740E-04 471150 + 415 471151 Ag-115m 2.34890E-05 5.11280E-04 471151 + 416 471160 Ag-116 1.69010E-05 9.95320E-04 471160 + 417 471161 Ag-116m 4.60670E-05 4.60670E-05 471161 + 418 471170 Ag-117 3.14840E-05 3.60810E-04 471170 + 419 471171 Ag-117m 2.36470E-04 5.33760E-04 471171 + 420 471180 Ag-118 4.43660E-05 5.42240E-04 471180 + 421 471181 Ag-118m 2.15080E-04 2.79050E-04 471181 + 422 471190 Ag-119 5.03430E-05 2.12070E-04 471190 + 423 471191 Ag-119m 3.78110E-04 5.39840E-04 471191 + 424 471200 Ag-120 7.75080E-05 1.97630E-04 471200 + 425 471201 Ag-120m 1.29620E-04 1.82230E-04 471201 + 426 471210 Ag-121 3.21660E-04 3.55820E-04 471210 + 427 471220 Ag-122 2.84470E-05 4.84050E-05 471220 + 428 471221 Ag-122m 3.06690E-05 3.06690E-05 471221 + 429 471230 Ag-123 5.96910E-05 7.79400E-05 471230 + 430 471240 Ag-124 1.55410E-05 2.62910E-05 471240 + 431 471241 Ag-124m 1.67550E-05 1.67550E-05 471241 + 432 471250 Ag-125 6.17920E-05 6.17920E-05 471250 + 433 471260 Ag-126 1.59330E-05 1.59330E-05 471260 + 434 471270 Ag-127 2.03310E-06 2.03310E-06 471270 + 435 471280 Ag-128 6.98010E-08 6.98010E-08 471280 + 436 471290 Ag-129 2.79890E-09 2.79890E-09 471290 + 437 481130 Cd-113 3.00840E-12 5.33620E-04 48113.82c + 438 481131 Cd-113m 1.13930E-11 6.11470E-06 481131 + 439 481140 Cd-114 2.59920E-09 9.25830E-04 48114.82c + 440 481150 Cd-115 1.54260E-08 8.89500E-04 481150 + 441 481151 Cd-115m 5.84200E-08 4.22280E-05 48515.82c + 442 481160 Cd-116 2.59270E-06 1.04120E-03 48116.82c + 443 481170 Cd-117 1.24340E-05 6.89620E-04 481170 + 444 481171 Cd-117m 4.70870E-05 2.32450E-04 481171 + 445 481180 Cd-118 2.35650E-05 7.30440E-04 481180 + 446 481190 Cd-119 2.82070E-05 6.74080E-04 481190 + 447 481191 Cd-119m 7.89230E-05 1.84960E-04 481191 + 448 481200 Cd-120 4.41300E-04 7.53730E-04 481200 + 449 481210 Cd-121 1.08070E-04 4.26700E-04 481210 + 450 481211 Cd-121m 3.02360E-04 3.39540E-04 481211 + 451 481220 Cd-122 6.68820E-04 7.47900E-04 481220 + 452 481230 Cd-123 1.88200E-04 2.51980E-04 481230 + 453 481231 Cd-123m 5.26560E-04 5.40750E-04 481231 + 454 481240 Cd-124 4.80850E-04 5.15490E-04 481240 + 455 481250 Cd-125 7.01190E-05 1.01010E-04 481250 + 456 481251 Cd-125m 1.96190E-04 2.27090E-04 481251 + 457 481260 Cd-126 1.04000E-03 1.05590E-03 481260 + 458 481270 Cd-127 5.17590E-04 5.19620E-04 481270 + 459 481280 Cd-128 2.25900E-04 2.25970E-04 481280 + 460 481290 Cd-129 2.10510E-05 2.10520E-05 481290 + 461 481291 Cd-129m 5.88980E-05 5.89000E-05 481291 + 462 481300 Cd-130 2.64810E-05 2.64810E-05 481300 + 463 481310 Cd-131 7.65120E-08 7.65120E-08 481310 + 464 481320 Cd-132 1.68880E-09 1.68880E-09 481320 + 465 491160 In-116 3.62020E-11 3.62020E-11 491160 + 466 491161 In-116m 5.84590E-11 1.26140E-10 491161 + 467 491162 In-116m 6.76800E-11 6.76800E-11 491162 + 468 491170 In-117 1.04770E-08 5.85890E-04 491170 + 469 491171 In-117m 2.10960E-09 6.35520E-04 491171 + 470 491180 In-118 4.57680E-08 7.30490E-04 491180 + 471 491181 In-118m 7.39070E-08 1.58270E-07 491181 + 472 491182 In-118m 8.55650E-08 8.55650E-08 491182 + 473 491200 In-120 8.63880E-06 7.62370E-04 491200 + 474 491201 In-120m 8.63880E-06 8.63880E-06 491201 + 475 491202 In-120m 8.63880E-06 8.63880E-06 491202 + 476 491210 In-121 4.87760E-05 5.35550E-04 491210 + 477 491211 In-121m 9.82090E-06 2.92810E-04 491211 + 478 491220 In-122 1.47750E-05 7.62670E-04 491220 + 479 491221 In-122m 1.23540E-05 1.23540E-05 491221 + 480 491222 In-122m 1.23540E-05 1.23540E-05 491222 + 481 491230 In-123 1.49280E-04 7.61480E-04 491230 + 482 491231 In-123m 3.00570E-05 2.10580E-04 491231 + 483 491240 In-124 1.39610E-04 6.55100E-04 491240 + 484 491241 In-124m 1.50520E-04 1.50520E-04 491241 + 485 491250 In-125 3.87290E-04 6.62730E-04 491250 + 486 491251 In-125m 7.79790E-05 1.30650E-04 491251 + 487 491260 In-126 4.65600E-04 1.52150E-03 491260 + 488 491261 In-126m 5.01990E-04 5.01990E-04 491261 + 489 491270 In-127 1.38650E-03 1.38650E-03 491270 + 490 491271 In-127m 2.79160E-04 7.98780E-04 491271 + 491 491280 In-128 4.36740E-04 8.33730E-04 491280 + 492 491281 In-128m 1.71010E-04 3.96980E-04 491281 + 493 491282 In-128m 6.55240E-04 6.55240E-04 491282 + 494 491290 In-129 1.13170E-03 1.19110E-03 491290 + 495 491291 In-129m 2.27870E-04 2.49380E-04 491291 + 496 491300 In-130 2.08300E-04 2.33860E-04 491300 + 497 491301 In-130m 3.03300E-04 3.03300E-04 491301 + 498 491302 In-130m 4.22480E-04 4.22480E-04 491302 + 499 491310 In-131 1.55770E-04 1.57430E-04 491310 + 500 491311 In-131m 1.55770E-04 1.55770E-04 491311 + 501 491312 In-131m 1.55770E-04 1.55770E-04 491312 + 502 491320 In-132 4.99610E-05 4.99620E-05 491320 + 503 491330 In-133 3.79640E-06 4.56080E-06 491330 + 504 491331 In-133m 7.64390E-07 7.64390E-07 491331 + 505 491340 In-134 2.26690E-08 2.26690E-08 491340 + 506 501180 Sn-118 2.90500E-11 7.30650E-04 50118.82c + 507 501220 Sn-122 1.98230E-05 8.07200E-04 50122.82c + 508 501230 Sn-123 2.20740E-05 8.01310E-05 50123.82c + 509 501231 Sn-123m 7.88930E-06 9.21900E-04 501231 + 510 501240 Sn-124 1.30800E-04 9.36420E-04 50124.82c + 511 501250 Sn-125 1.75750E-04 2.87690E-04 50125.82c + 512 501251 Sn-125m 6.28130E-05 7.44240E-04 501251 + 513 501260 Sn-126 8.58010E-04 2.88700E-03 50126.82c + 514 501270 Sn-127 1.04230E-03 1.58270E-03 501270 + 515 501271 Sn-127m 3.72520E-04 2.01180E-03 501271 + 516 501280 Sn-128 1.13100E-03 5.70270E-03 501280 + 517 501281 Sn-128m 3.08270E-03 3.73800E-03 501281 + 518 501290 Sn-129 1.89870E-03 3.21250E-03 501290 + 519 501291 Sn-129m 5.31240E-03 5.43920E-03 501291 + 520 501300 Sn-130 4.11110E-03 4.70130E-03 501300 + 521 501301 Sn-130m 1.12060E-02 1.15790E-02 501301 + 522 501310 Sn-131 3.90840E-03 4.21020E-03 501310 + 523 501311 Sn-131m 1.09360E-02 1.10980E-02 501311 + 524 501320 Sn-132 1.14100E-02 1.14640E-02 501320 + 525 501330 Sn-133 2.57710E-03 2.57780E-03 501330 + 526 501340 Sn-134 4.58160E-04 4.58170E-04 501340 + 527 501350 Sn-135 4.10370E-05 4.10370E-05 501350 + 528 501360 Sn-136 1.56110E-06 1.56110E-06 501360 + 529 501370 Sn-137 3.28660E-09 3.28660E-09 501370 + 530 511250 Sb-125 4.54050E-10 1.03190E-03 51125.82c + 531 511260 Sb-126 2.06580E-08 2.47040E-08 51126.82c + 532 511261 Sb-126m 1.29030E-08 2.88980E-08 511261 + 533 511262 Sb-126m 1.59950E-08 1.59950E-08 511262 + 534 511270 Sb-127 3.08320E-05 3.62530E-03 511270 + 535 511280 Sb-128 4.79020E-05 5.75300E-03 511280 + 536 511281 Sb-128m 6.69980E-05 6.69980E-05 511281 + 537 511290 Sb-129 6.25220E-04 7.03460E-03 511290 + 538 511291 Sb-129m 4.62680E-04 3.18220E-03 511291 + 539 511300 Sb-130 1.58200E-03 1.20730E-02 511300 + 540 511301 Sb-130m 1.58200E-03 7.37130E-03 511301 + 541 511310 Sb-131 1.45270E-02 2.98350E-02 511310 + 542 511320 Sb-132 9.83570E-03 2.13000E-02 511320 + 543 511321 Sb-132m 8.70830E-03 8.70830E-03 511321 + 544 511330 Sb-133 3.08850E-02 3.35410E-02 511330 + 545 511340 Sb-134 2.45730E-03 2.84180E-03 511340 + 546 511341 Sb-134m 6.69790E-03 6.70220E-03 511341 + 547 511350 Sb-135 3.66590E-03 3.69880E-03 511350 + 548 511360 Sb-136 5.61070E-04 5.62160E-04 511360 + 549 511370 Sb-137 1.09250E-04 1.09250E-04 511370 + 550 511380 Sb-138 7.67710E-06 7.67710E-06 511380 + 551 511390 Sb-139 3.68620E-08 3.68620E-08 511390 + 552 521270 Te-127 2.57230E-11 3.61100E-03 521270 + 553 521271 Te-127m 7.19710E-11 5.97440E-04 52527.82c + 554 521280 Te-128 9.96280E-06 5.82750E-03 52128.82c + 555 521290 Te-129 2.19050E-06 8.33620E-03 521290 + 556 521291 Te-129m 6.12880E-06 3.81510E-03 52529.82c + 557 521300 Te-130 3.65650E-04 1.98100E-02 52130.82c + 558 521310 Te-131 5.18460E-04 2.87710E-02 521310 + 559 521311 Te-131m 1.45060E-03 3.83930E-03 521311 + 560 521320 Te-132 1.24080E-02 4.24160E-02 52132.82c + 561 521330 Te-133 8.99850E-03 4.21650E-02 521330 + 562 521331 Te-133m 2.51770E-02 3.09790E-02 521331 + 563 521340 Te-134 6.65640E-02 7.66840E-02 521340 + 564 521350 Te-135 3.80320E-02 4.12420E-02 521350 + 565 521360 Te-136 2.25160E-02 2.30380E-02 521360 + 566 521370 Te-137 7.90600E-03 7.96170E-03 521370 + 567 521380 Te-138 2.88490E-03 2.89260E-03 521380 + 568 521390 Te-139 3.74810E-04 3.74850E-04 521390 + 569 521400 Te-140 1.00800E-04 1.00800E-04 521400 + 570 521410 Te-141 2.83430E-06 2.83430E-06 521410 + 571 521420 Te-142 4.28330E-09 4.28330E-09 521420 + 572 531300 I-130 3.13240E-09 4.09770E-09 53130.82c + 573 531301 I-130m 1.14920E-09 1.14920E-09 531301 + 574 531310 I-131 1.19190E-05 3.18160E-02 53131.82c + 575 531320 I-132 3.45270E-05 4.24770E-02 531320 + 576 531321 I-132m 3.05700E-05 3.05700E-05 531321 + 577 531330 I-133 5.98780E-04 6.87650E-02 531330 + 578 531331 I-133m 4.43120E-04 4.43120E-04 531331 + 579 531340 I-134 1.57980E-03 7.96310E-02 531340 + 580 531341 I-134m 1.39870E-03 1.39870E-03 531341 + 581 531350 I-135 2.17520E-02 6.29940E-02 53135.82c + 582 531360 I-136 6.15090E-03 2.93080E-02 531360 + 583 531361 I-136m 1.67660E-02 1.68850E-02 531361 + 584 531370 I-137 3.09810E-02 3.88870E-02 531370 + 585 531380 I-138 1.08800E-02 1.35900E-02 531380 + 586 531390 I-139 1.32900E-02 1.36650E-02 531390 + 587 531400 I-140 3.26110E-03 3.36190E-03 531400 + 588 531410 I-141 1.18140E-03 1.18420E-03 531410 + 589 531420 I-142 1.56830E-04 1.56830E-04 531420 + 590 531430 I-143 2.18850E-05 2.18850E-05 531430 + 591 531440 I-144 1.51490E-06 1.51490E-06 531440 + 592 541320 Xe-132 7.21790E-10 4.24810E-02 54132.82c + 593 541321 Xe-132m 9.67010E-10 9.67010E-10 541321 + 594 541330 Xe-133 4.00560E-06 6.87800E-02 54133.82c + 595 541331 Xe-133m 1.12070E-05 1.96850E-03 541331 + 596 541340 Xe-134 3.30130E-05 7.97860E-02 54134.82c + 597 541341 Xe-134m 8.99870E-05 1.22160E-04 541341 + 598 541350 Xe-135 2.19630E-04 6.37620E-02 54135.82c + 599 541351 Xe-135m 6.14530E-04 1.10140E-02 541351 + 600 541360 Xe-136 8.29010E-03 5.70110E-02 54136.82c + 601 541370 Xe-137 2.22400E-02 5.93190E-02 541370 + 602 541380 Xe-138 4.24480E-02 5.66570E-02 541380 + 603 541390 Xe-139 4.48050E-02 5.74430E-02 541390 + 604 541400 Xe-140 4.38480E-02 4.71460E-02 541400 + 605 541410 Xe-141 2.04940E-02 2.14690E-02 541410 + 606 541420 Xe-142 1.29770E-02 1.31030E-02 541420 + 607 541430 Xe-143 2.93020E-03 2.94390E-03 541430 + 608 541440 Xe-144 8.34050E-04 8.34960E-04 541440 + 609 541450 Xe-145 1.24860E-04 1.24860E-04 541450 + 610 541460 Xe-146 1.95830E-05 1.95830E-05 541460 + 611 541470 Xe-147 1.70340E-09 1.70340E-09 541470 + 612 551350 Cs-135 5.75500E-07 6.38290E-02 55135.82c + 613 551351 Cs-135m 4.25890E-07 4.25890E-07 551351 + 614 551360 Cs-136 3.18660E-06 4.32580E-06 55136.82c + 615 551361 Cs-136m 2.27840E-06 2.27840E-06 551361 + 616 551370 Cs-137 2.46330E-04 5.95660E-02 55137.82c + 617 551380 Cs-138 4.77630E-04 5.77820E-02 551380 + 618 551381 Cs-138m 7.98770E-04 7.98770E-04 551381 + 619 551390 Cs-139 6.73520E-03 6.41780E-02 551390 + 620 551400 Cs-140 9.25410E-03 5.64100E-02 551400 + 621 551410 Cs-141 2.80200E-02 4.95270E-02 551410 + 622 551420 Cs-142 2.17960E-02 3.48820E-02 551420 + 623 551430 Cs-143 1.87900E-02 2.17290E-02 551430 + 624 551440 Cs-144 3.76800E-03 6.46670E-03 551440 + 625 551441 Cs-144m 3.76800E-03 3.77120E-03 551441 + 626 551450 Cs-145 4.40480E-03 4.52480E-03 551450 + 627 551460 Cs-146 9.73420E-04 9.91650E-04 551460 + 628 551470 Cs-147 1.44630E-04 1.44630E-04 551470 + 629 551480 Cs-148 2.85130E-05 2.85130E-05 551480 + 630 551490 Cs-149 3.42660E-06 3.42660E-06 551490 + 631 561370 Ba-137 4.60990E-07 5.95680E-02 56137.82c + 632 561371 Ba-137m 1.28980E-06 5.62310E-02 561371 + 633 561380 Ba-138 2.45960E-05 5.79580E-02 56138.82c + 634 561390 Ba-139 3.42370E-04 6.45210E-02 561390 + 635 561400 Ba-140 1.60090E-03 5.80100E-02 56140.82c + 636 561410 Ba-141 4.70350E-03 5.42300E-02 561410 + 637 561420 Ba-142 1.86860E-02 5.39240E-02 561420 + 638 561430 Ba-143 2.48700E-02 4.64500E-02 561430 + 639 561440 Ba-144 3.82510E-02 4.70430E-02 561440 + 640 561450 Ba-145 2.72890E-02 3.13080E-02 561450 + 641 561460 Ba-146 2.23240E-02 2.32160E-02 561460 + 642 561470 Ba-147 5.51500E-03 5.62560E-03 561470 + 643 561480 Ba-148 2.72990E-03 2.75130E-03 561480 + 644 561490 Ba-149 4.45840E-04 4.49270E-04 561490 + 645 561500 Ba-150 5.91410E-05 5.91410E-05 561500 + 646 561510 Ba-151 2.91760E-06 2.91760E-06 561510 + 647 561520 Ba-152 8.02920E-10 8.02920E-10 561520 + 648 571400 La-140 2.52500E-06 5.80130E-02 57140.82c + 649 571410 La-141 2.17470E-05 5.42520E-02 571410 + 650 571420 La-142 1.01930E-04 5.40260E-02 571420 + 651 571430 La-143 6.56840E-04 4.71070E-02 571430 + 652 571440 La-144 1.95340E-03 4.89970E-02 571440 + 653 571450 La-145 8.53200E-03 3.98390E-02 571450 + 654 571460 La-146 3.24870E-03 2.64650E-02 571460 + 655 571461 La-146m 6.81530E-03 6.81530E-03 571461 + 656 571470 La-147 1.14940E-02 1.71310E-02 571470 + 657 571480 La-148 7.36360E-03 1.01060E-02 571480 + 658 571490 La-149 5.36670E-03 5.81400E-03 571490 + 659 571500 La-150 1.19780E-03 1.25690E-03 571500 + 660 571510 La-151 3.79980E-04 3.82900E-04 571510 + 661 571520 La-152 5.68890E-05 5.68900E-05 571520 + 662 571530 La-153 6.00650E-06 6.00650E-06 571530 + 663 571540 La-154 1.26870E-09 1.26870E-09 571540 + 664 581420 Ce-142 3.59810E-06 5.40300E-02 58142.82c + 665 581430 Ce-143 8.92480E-06 4.71160E-02 58143.82c + 666 581440 Ce-144 1.03420E-04 4.91000E-02 58144.82c + 667 581450 Ce-145 6.20250E-04 4.04600E-02 581450 + 668 581460 Ce-146 2.63950E-03 3.59200E-02 581460 + 669 581470 Ce-147 4.13420E-03 2.12650E-02 581470 + 670 581480 Ce-148 1.06550E-02 2.08420E-02 581480 + 671 581490 Ce-149 1.01180E-02 1.58850E-02 581490 + 672 581500 Ce-150 8.85990E-03 1.00830E-02 581500 + 673 581510 Ce-151 4.57050E-03 4.95680E-03 581510 + 674 581520 Ce-152 2.72960E-03 2.78310E-03 581520 + 675 581530 Ce-153 3.51720E-04 3.57730E-04 581530 + 676 581540 Ce-154 5.93720E-05 5.93730E-05 581540 + 677 581550 Ce-155 7.47130E-06 7.47130E-06 581550 + 678 581560 Ce-156 4.36760E-09 4.36760E-09 581560 + 679 581570 Ce-157 1.63460E-11 1.63460E-11 581570 + 680 591450 Pr-145 9.78260E-07 4.04610E-02 591450 + 681 591460 Pr-146 6.18510E-06 3.59260E-02 591460 + 682 591470 Pr-147 2.52000E-05 2.12900E-02 591470 + 683 591480 Pr-148 2.10060E-05 2.08630E-02 591480 + 684 591481 Pr-148m 1.01830E-04 1.01830E-04 591481 + 685 591490 Pr-149 5.35870E-04 1.64200E-02 591490 + 686 591500 Pr-150 7.88390E-04 1.08710E-02 591500 + 687 591510 Pr-151 1.64360E-03 6.60040E-03 591510 + 688 591520 Pr-152 1.60060E-03 4.38590E-03 591520 + 689 591530 Pr-153 1.15350E-03 1.50940E-03 591530 + 690 591540 Pr-154 4.14580E-04 4.73580E-04 591540 + 691 591550 Pr-155 1.09350E-04 1.16820E-04 591550 + 692 591560 Pr-156 3.61860E-05 3.61900E-05 591560 + 693 591570 Pr-157 2.26930E-07 2.26950E-07 591570 + 694 591580 Pr-158 2.77960E-09 2.77960E-09 591580 + 695 591590 Pr-159 2.12630E-11 2.12630E-11 591590 + 696 601480 Nd-148 9.83930E-07 2.09660E-02 60148.82c + 697 601490 Nd-149 2.16670E-05 1.64420E-02 601490 + 698 601500 Nd-150 7.70680E-05 1.09480E-02 60150.82c + 699 601510 Nd-151 3.18330E-04 6.91880E-03 601510 + 700 601520 Nd-152 7.84020E-04 5.16990E-03 601520 + 701 601530 Nd-153 7.59300E-04 2.26870E-03 601530 + 702 601540 Nd-154 8.84670E-04 1.35820E-03 601540 + 703 601550 Nd-155 3.75490E-04 4.93300E-04 601550 + 704 601560 Nd-156 2.13840E-04 2.49060E-04 601560 + 705 601570 Nd-157 5.54610E-05 5.56740E-05 601570 + 706 601580 Nd-158 1.50580E-05 1.50610E-05 601580 + 707 601590 Nd-159 6.78490E-08 6.78700E-08 601590 + 708 601600 Nd-160 6.42540E-09 6.42540E-09 601600 + 709 601610 Nd-161 5.07030E-11 5.07030E-11 601610 + 710 611500 Pm-150 6.88610E-10 6.88610E-10 611500 + 711 611510 Pm-151 4.51660E-08 6.91880E-03 61151.82c + 712 611520 Pm-152 6.92930E-07 5.17060E-03 611520 + 713 611521 Pm-152m 1.45680E-06 1.45680E-06 611521 + 714 611522 Pm-152m 1.90290E-06 1.90290E-06 611522 + 715 611530 Pm-153 6.00220E-06 2.27470E-03 611530 + 716 611540 Pm-154 1.01920E-05 1.36840E-03 611540 + 717 611541 Pm-154m 1.01920E-05 1.01920E-05 611541 + 718 611550 Pm-155 6.22230E-05 5.55520E-04 611550 + 719 611560 Pm-156 4.27850E-05 2.91850E-04 611560 + 720 611570 Pm-157 5.15160E-05 1.07190E-04 611570 + 721 611580 Pm-158 1.00390E-05 2.50990E-05 611580 + 722 611590 Pm-159 5.79220E-06 5.86000E-06 611590 + 723 611600 Pm-160 1.03320E-06 1.03960E-06 611600 + 724 611610 Pm-161 9.96750E-08 9.97260E-08 611610 + 725 611620 Pm-162 1.43660E-08 1.43660E-08 611620 + 726 611630 Pm-163 5.44750E-11 5.44750E-11 611630 + 727 621530 Sm-153 3.72460E-10 2.27470E-03 62153.82c + 728 621531 Sm-153m 1.04210E-09 1.04210E-09 621531 + 729 621540 Sm-154 2.26470E-06 1.38090E-03 62154.82c + 730 621550 Sm-155 4.54200E-07 5.55970E-04 621550 + 731 621560 Sm-156 1.64550E-05 3.08300E-04 621560 + 732 621570 Sm-157 1.58520E-05 1.23040E-04 621570 + 733 621580 Sm-158 2.51010E-05 5.02010E-05 621580 + 734 621590 Sm-159 5.79240E-06 1.16540E-05 621590 + 735 621600 Sm-160 1.13660E-05 1.24030E-05 621600 + 736 621610 Sm-161 1.98280E-06 2.08250E-06 621610 + 737 621620 Sm-162 9.61730E-06 9.63170E-06 621620 + 738 621630 Sm-163 2.72400E-08 2.72940E-08 621630 + 739 621640 Sm-164 1.87170E-09 1.87170E-09 621640 + 740 621650 Sm-165 3.50790E-11 3.50790E-11 621650 + 741 631550 Eu-155 3.70280E-11 5.55970E-04 63155.82c + 742 631560 Eu-156 1.09110E-09 3.08300E-04 63156.82c + 743 631570 Eu-157 2.42020E-08 1.23070E-04 63157.82c + 744 631580 Eu-158 1.23740E-07 5.03250E-05 631580 + 745 631590 Eu-159 4.06710E-07 1.20610E-05 631590 + 746 631600 Eu-160 1.33550E-06 1.37380E-05 631600 + 747 631610 Eu-161 1.99430E-06 4.07680E-06 631610 + 748 631620 Eu-162 4.96340E-06 1.45950E-05 631620 + 749 631630 Eu-163 3.89100E-07 4.16390E-07 631630 + 750 631640 Eu-164 5.34550E-08 5.53270E-08 631640 + 751 631650 Eu-165 1.12330E-08 1.12680E-08 631650 + 752 631660 Eu-166 4.47990E-10 4.47990E-10 631660 + 753 631670 Eu-167 2.43350E-11 2.43350E-11 631670 + 754 641580 Gd-158 3.39450E-11 5.03250E-05 64158.82c + 755 641590 Gd-159 2.86740E-10 1.20610E-05 641590 + 756 641600 Gd-160 1.13600E-08 1.37500E-05 64160.82c + 757 641610 Gd-161 3.76520E-08 4.11450E-06 641610 + 758 641620 Gd-162 9.20380E-07 1.55150E-05 641620 + 759 641630 Gd-163 1.25070E-07 5.41460E-07 641630 + 760 641640 Gd-164 1.38380E-07 1.93710E-07 641640 + 761 641650 Gd-165 4.84170E-08 5.96850E-08 641650 + 762 641660 Gd-166 1.79510E-08 1.83990E-08 641660 + 763 641670 Gd-167 2.06640E-09 2.09070E-09 641670 + 764 641680 Gd-168 3.24430E-10 3.24430E-10 641680 + 765 641690 Gd-169 1.02280E-11 1.02280E-11 641690 + 766 651610 Tb-161 1.65490E-11 4.11450E-06 651610 + 767 651620 Tb-162 1.00950E-09 1.55160E-05 651620 + 768 651630 Tb-163 1.59800E-09 5.43060E-07 651630 + 769 651640 Tb-164 3.72430E-09 1.97430E-07 651640 + 770 651650 Tb-165 1.20340E-08 7.17190E-08 651650 + 771 651660 Tb-166 7.39890E-09 2.57980E-08 651660 + 772 651670 Tb-167 6.86870E-09 8.95940E-09 651670 + 773 651680 Tb-168 1.87990E-09 2.20430E-09 651680 + 774 651690 Tb-169 5.86010E-10 5.96240E-10 651690 + 775 651700 Tb-170 4.26350E-11 4.26350E-11 651700 + 776 651710 Tb-171 5.32630E-12 5.32630E-12 651710 + 777 661640 Dy-164 5.20270E-12 1.97440E-07 66164.82c + 778 661650 Dy-165 3.60720E-11 7.17600E-08 661650 + 779 661651 Dy-165m 4.80280E-12 4.80280E-12 661651 + 780 661660 Dy-166 2.80350E-10 2.60780E-08 661660 + 781 661670 Dy-167 5.16900E-10 9.47630E-09 661670 + 782 661680 Dy-168 1.23330E-09 3.43760E-09 661680 + 783 661690 Dy-169 6.21620E-10 1.21790E-09 661690 + 784 661700 Dy-170 3.73760E-10 4.16390E-10 661700 + 785 661710 Dy-171 8.62020E-11 9.15280E-11 661710 + 786 661720 Dy-172 2.33460E-11 2.33460E-11 661720 + 787 661730 Dy-173 1.37110E-12 1.37110E-12 661730 + 788 671670 Ho-167 1.12680E-12 9.47750E-09 671670 + 789 671680 Ho-168 2.36150E-12 3.44390E-09 671680 + 790 671681 Ho-168m 3.94930E-12 3.94930E-12 671681 + 791 671690 Ho-169 3.37130E-11 1.25160E-09 671690 + 792 671700 Ho-170 2.76940E-11 2.76940E-11 671700 + 793 671701 Ho-170m 1.01600E-11 4.26550E-10 671701 + 794 671710 Ho-171 7.26520E-11 1.64180E-10 671710 + 795 671720 Ho-172 3.17440E-11 5.50900E-11 671720 + 796 671730 Ho-173 1.60940E-11 1.74650E-11 671730 + 797 671740 Ho-174 2.43310E-12 2.43310E-12 671740 + 798 681710 Er-171 1.10650E-12 1.65290E-10 681710 + 799 681720 Er-172 4.83510E-12 5.99250E-11 681720 + 800 681730 Er-173 4.31670E-12 2.17820E-11 681730 + 801 681740 Er-174 5.27850E-12 7.71160E-12 681740 + + Nuclide 92237.82c -- uranium 237 (U-237) is using NFY data from Np-238 + + Nuclide 92238.82c -- uranium 238 (U-238) + + Neutron-induced fission: + + Interpolation region : 1 / 2 + Interpolation energy : 4.00000E-01 MeV + Number of products : 771 / 935 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 2.35370E-05 2.35370E-05 1001.82c + 2 10020 H-2 7.19320E-06 7.19320E-06 1002.82c + 3 10030 H-3 1.02620E-04 1.02620E-04 1003.82c + 4 20040 He-4 1.48800E-03 1.48800E-03 2004.82c + 5 240600 Cr-60 8.12710E-12 8.12710E-12 240600 + 6 240610 Cr-61 8.55480E-12 8.55480E-12 240610 + 7 240620 Cr-62 9.66660E-12 9.66660E-12 240620 + 8 240630 Cr-63 2.71880E-12 2.71880E-12 240630 + 9 250600 Mn-60 2.14070E-13 8.59160E-12 250600 + 10 250601 Mn-60m 2.17770E-12 2.17770E-12 250601 + 11 250610 Mn-61 1.63150E-11 2.48700E-11 250610 + 12 250620 Mn-62 3.19300E-11 3.67640E-11 250620 + 13 250621 Mn-62m 5.00050E-12 9.83380E-12 250621 + 14 250630 Mn-63 7.95210E-11 8.22400E-11 250630 + 15 250640 Mn-64 5.38390E-11 5.38390E-11 250640 + 16 250650 Mn-65 5.14680E-11 5.14680E-11 250650 + 17 250660 Mn-66 1.24280E-11 1.24280E-11 250660 + 18 250670 Mn-67 2.93300E-12 2.93300E-12 250670 + 19 260620 Fe-62 1.51280E-11 6.17260E-11 260620 + 20 260630 Fe-63 6.35300E-11 1.45770E-10 260630 + 21 260640 Fe-64 2.80650E-10 3.34490E-10 260640 + 22 260650 Fe-65 5.59630E-10 6.11100E-10 260650 + 23 260660 Fe-66 1.08760E-09 1.10000E-09 260660 + 24 260670 Fe-67 6.83380E-10 6.86310E-10 260670 + 25 260680 Fe-68 4.61420E-10 4.61420E-10 260680 + 26 260690 Fe-69 8.76880E-11 8.76880E-11 260690 + 27 260700 Fe-70 1.38970E-11 1.38970E-11 260700 + 28 270630 Co-63 1.55770E-12 1.47330E-10 270630 + 29 270640 Co-64 1.61020E-11 3.50590E-10 270640 + 30 270650 Co-65 2.24840E-10 8.35940E-10 270650 + 31 270660 Co-66 8.37010E-10 1.93700E-09 270660 + 32 270670 Co-67 3.50700E-09 4.19330E-09 270670 + 33 270680 Co-68 2.96480E-09 4.30510E-09 270680 + 34 270681 Co-68m 2.21300E-09 2.68050E-09 270681 + 35 270690 Co-69 8.30810E-09 8.38970E-09 270690 + 36 270700 Co-70 1.81620E-09 1.81620E-09 270700 + 37 270701 Co-70m 1.81620E-09 1.83010E-09 270701 + 38 270710 Co-71 2.19450E-09 2.19450E-09 270710 + 39 270720 Co-72 3.59520E-10 3.59520E-10 270720 + 40 270730 Co-73 4.71980E-11 4.71980E-11 270730 + 41 270740 Co-74 1.75320E-12 1.75320E-12 270740 + 42 280650 Ni-65 1.91340E-12 8.37850E-10 280650 + 43 280660 Ni-66 6.11150E-11 1.99820E-09 280660 + 44 280670 Ni-67 5.69870E-10 4.76320E-09 280670 + 45 280680 Ni-68 5.67200E-09 1.14010E-08 280680 + 46 280690 Ni-69 8.69200E-09 1.69980E-08 280690 + 47 280691 Ni-69m 8.69200E-09 8.69200E-09 280691 + 48 280700 Ni-70 5.24530E-08 5.60990E-08 280700 + 49 280710 Ni-71 7.28510E-08 7.50450E-08 280710 + 50 280720 Ni-72 1.05280E-07 1.05640E-07 280720 + 51 280730 Ni-73 3.93000E-08 3.93470E-08 280730 + 52 280740 Ni-74 1.47860E-08 1.47880E-08 280740 + 53 280750 Ni-75 1.92610E-09 1.92610E-09 280750 + 54 280760 Ni-76 1.97710E-10 1.97710E-10 280760 + 55 280770 Ni-77 7.11990E-12 7.11990E-12 280770 + 56 290670 Cu-67 1.95710E-12 4.76510E-09 290670 + 57 290680 Cu-68 1.41050E-11 1.14480E-08 290680 + 58 290681 Cu-68m 3.84470E-11 3.84470E-11 290681 + 59 290690 Cu-69 1.31900E-09 2.70090E-08 290690 + 60 290700 Cu-70 5.71190E-10 5.63530E-09 290700 + 61 290701 Cu-70m 7.29470E-09 1.01280E-08 290701 + 62 290702 Cu-70m 5.71190E-10 5.66700E-08 290702 + 63 290710 Cu-71 7.69260E-08 1.51970E-07 290710 + 64 290720 Cu-72 2.15070E-07 3.20710E-07 290720 + 65 290730 Cu-73 5.78690E-07 6.18040E-07 290730 + 66 290740 Cu-74 5.25890E-07 5.40710E-07 290740 + 67 290750 Cu-75 6.28220E-07 6.30120E-07 290750 + 68 290760 Cu-76 9.41600E-08 9.42590E-08 290760 + 69 290761 Cu-76m 9.41600E-08 9.42590E-08 290761 + 70 290770 Cu-77 7.04050E-08 7.04120E-08 290770 + 71 290780 Cu-78 4.45170E-09 4.45170E-09 290780 + 72 290790 Cu-79 4.76300E-10 4.76300E-10 290790 + 73 290800 Cu-80 5.92200E-12 5.92200E-12 290800 + 74 300690 Zn-69 2.46320E-13 2.70100E-08 300690 + 75 300691 Zn-69m 1.22340E-12 1.22340E-12 300691 + 76 300700 Zn-70 9.07110E-11 6.46270E-08 300700 + 77 300710 Zn-71 3.59690E-10 1.52330E-07 300710 + 78 300711 Zn-71m 1.78640E-09 1.78640E-09 300711 + 79 300720 Zn-72 4.67610E-08 3.67470E-07 300720 + 80 300730 Zn-73 2.24000E-08 7.72450E-07 300730 + 81 300731 Zn-73m 3.09820E-08 1.32010E-07 300731 + 82 300732 Zn-73m 2.02060E-07 2.02060E-07 300732 + 83 300740 Zn-74 1.50520E-06 2.06800E-06 300740 + 84 300750 Zn-75 3.57350E-06 4.18440E-06 300750 + 85 300760 Zn-76 8.10720E-06 8.29290E-06 300760 + 86 300770 Zn-77 1.07920E-05 1.15810E-05 300770 + 87 300771 Zn-77m 1.43690E-06 1.43690E-06 300771 + 88 300780 Zn-78 1.12170E-05 1.12220E-05 300780 + 89 300790 Zn-79 1.46420E-06 1.46440E-06 300790 + 90 300800 Zn-80 4.54180E-06 4.54180E-06 300800 + 91 300810 Zn-81 1.86450E-08 1.86450E-08 300810 + 92 300820 Zn-82 1.41340E-09 1.41340E-09 300820 + 93 310720 Ga-72 5.37560E-11 3.67530E-07 310720 + 94 310721 Ga-72m 5.28410E-12 1.22500E-08 310721 + 95 310730 Ga-73 3.01750E-09 8.76500E-07 310730 + 96 310740 Ga-74 2.20780E-08 1.58960E-06 310740 + 97 310741 Ga-74m 2.20780E-08 2.09000E-06 310741 + 98 310750 Ga-75 7.77140E-07 4.96150E-06 310750 + 99 310760 Ga-76 3.45980E-06 1.17530E-05 310760 + 100 310770 Ga-77 1.22300E-05 2.45290E-05 310770 + 101 310780 Ga-78 2.80460E-05 3.92870E-05 310780 + 102 310790 Ga-79 6.44000E-05 6.58450E-05 310790 + 103 310800 Ga-80 2.72480E-05 3.17910E-05 310800 + 104 310810 Ga-81 3.19140E-05 3.19310E-05 310810 + 105 310820 Ga-82 3.09260E-05 3.09270E-05 310820 + 106 310830 Ga-83 5.74290E-06 5.74290E-06 310830 + 107 310840 Ga-84 2.40950E-08 2.40950E-08 310840 + 108 310850 Ga-85 1.02240E-09 1.02240E-09 310850 + 109 320740 Ge-74 6.08820E-11 2.11220E-06 32074.82c + 110 320750 Ge-75 3.63470E-10 4.96460E-06 320750 + 111 320751 Ge-75m 2.72990E-09 2.01190E-07 320751 + 112 320760 Ge-76 1.24350E-07 1.18770E-05 32076.82c + 113 320770 Ge-77 5.39670E-06 1.01940E-05 320770 + 114 320771 Ge-77m 7.18550E-07 2.52480E-05 320771 + 115 320780 Ge-78 1.12190E-05 5.05640E-05 320780 + 116 320790 Ge-79 9.90210E-06 7.85690E-05 320790 + 117 320791 Ge-79m 7.43710E-05 7.44700E-05 320791 + 118 320800 Ge-80 2.13520E-04 2.49110E-04 320800 + 119 320810 Ge-81 4.21780E-04 4.40940E-04 320810 + 120 320811 Ge-81m 8.49230E-05 1.01490E-04 320811 + 121 320820 Ge-82 1.10900E-03 1.13550E-03 320820 + 122 320830 Ge-83 6.91590E-04 6.95230E-04 320830 + 123 320840 Ge-84 3.27260E-04 3.27270E-04 320840 + 124 320850 Ge-85 1.67770E-04 1.67770E-04 320850 + 125 320860 Ge-86 5.64210E-05 5.64210E-05 320860 + 126 320870 Ge-87 2.87810E-06 2.87810E-06 320870 + 127 320880 Ge-88 8.46140E-10 8.46140E-10 320880 + 128 330760 As-76 1.91190E-11 1.91190E-11 330760 + 129 330770 As-77 2.84360E-09 3.06480E-05 330770 + 130 330780 As-78 6.99600E-08 5.06340E-05 330780 + 131 330790 As-79 2.95130E-06 1.53010E-04 330790 + 132 330800 As-80 1.81730E-05 2.67280E-04 330800 + 133 330810 As-81 5.98930E-05 6.01310E-04 330810 + 134 330820 As-82 8.23030E-05 1.21780E-03 330820 + 135 330821 As-82m 2.86770E-04 2.86770E-04 330821 + 136 330830 As-83 1.11190E-03 1.84250E-03 330830 + 137 330840 As-84 6.76000E-04 8.33710E-04 330840 + 138 330841 As-84m 6.76000E-04 8.33710E-04 330841 + 139 330850 As-85 1.66600E-03 1.81030E-03 330850 + 140 330860 As-86 7.79430E-04 8.35850E-04 330860 + 141 330870 As-87 4.15470E-04 4.18350E-04 330870 + 142 330880 As-88 7.95090E-05 7.95100E-05 330880 + 143 330890 As-89 2.34020E-05 2.34020E-05 330890 + 144 330900 As-90 1.53830E-06 1.53830E-06 330900 + 145 340780 Se-78 1.19680E-11 5.06340E-05 34078.82c + 146 340790 Se-79 1.30220E-09 1.52930E-04 34079.82c + 147 340791 Se-79m 1.73380E-10 1.49390E-04 340791 + 148 340800 Se-80 1.08330E-07 2.67390E-04 34080.82c + 149 340810 Se-81 4.68860E-07 6.05290E-04 340810 + 150 340811 Se-81m 3.52140E-06 2.51080E-05 340811 + 151 340820 Se-82 1.16650E-04 1.62120E-03 34082.82c + 152 340830 Se-83 4.87360E-04 1.15180E-03 340830 + 153 340831 Se-83m 9.81280E-05 1.27850E-03 340831 + 154 340840 Se-84 2.35340E-03 4.41670E-03 340840 + 155 340850 Se-85 5.79250E-03 7.48040E-03 340850 + 156 340860 Se-86 8.69370E-03 9.31820E-03 340860 + 157 340870 Se-87 8.32310E-03 8.67700E-03 340870 + 158 340880 Se-88 5.37180E-03 5.45130E-03 340880 + 159 340890 Se-89 2.62300E-03 2.64640E-03 340890 + 160 340900 Se-90 7.98450E-04 7.99990E-04 340900 + 161 340910 Se-91 1.89930E-04 1.89930E-04 340910 + 162 340920 Se-92 2.95340E-05 2.95340E-05 340920 + 163 340930 Se-93 3.04490E-09 3.04490E-09 340930 + 164 350810 Br-81 5.51590E-10 6.05300E-04 35081.82c + 165 350820 Br-82 3.64980E-08 4.95670E-08 350820 + 166 350821 Br-82m 1.33900E-08 1.33900E-08 350821 + 167 350830 Br-83 2.35160E-06 2.43270E-03 350830 + 168 350840 Br-84 1.39470E-05 4.43070E-03 350840 + 169 350841 Br-84m 1.39470E-05 1.39470E-05 350841 + 170 350850 Br-85 5.16820E-04 7.99720E-03 350850 + 171 350860 Br-86 1.69930E-03 1.10170E-02 350860 + 172 350870 Br-87 6.01330E-03 1.47440E-02 350870 + 173 350880 Br-88 8.64780E-03 1.42520E-02 350880 + 174 350890 Br-89 1.00620E-02 1.25020E-02 350890 + 175 350900 Br-90 5.34930E-03 6.18920E-03 350900 + 176 350910 Br-91 4.30330E-03 4.45330E-03 350910 + 177 350920 Br-92 1.37560E-03 1.40510E-03 350920 + 178 350930 Br-93 5.09050E-04 5.09050E-04 350930 + 179 350940 Br-94 4.87000E-05 4.87000E-05 350940 + 180 350950 Br-95 8.67130E-06 8.67130E-06 350950 + 181 360830 Kr-83 1.15780E-10 2.43270E-03 36083.82c + 182 360831 Kr-83m 2.33120E-11 2.43050E-03 360831 + 183 360840 Kr-84 2.25560E-08 4.44460E-03 36084.82c + 184 360850 Kr-85 1.20640E-05 1.73420E-03 36085.82c + 185 360851 Kr-85m 2.42900E-06 7.98660E-03 360851 + 186 360860 Kr-86 2.71620E-04 1.16590E-02 36086.82c + 187 360870 Kr-87 1.25330E-03 1.65820E-02 360870 + 188 360880 Kr-88 7.14670E-03 2.22060E-02 360880 + 189 360890 Kr-89 1.74750E-02 2.97370E-02 360890 + 190 360900 Kr-90 2.50860E-02 3.06430E-02 360900 + 191 360910 Kr-91 3.04730E-02 3.45010E-02 360910 + 192 360920 Kr-92 2.44700E-02 2.57560E-02 360920 + 193 360930 Kr-93 1.28210E-02 1.30180E-02 360930 + 194 360940 Kr-94 5.61690E-03 5.63150E-03 360940 + 195 360950 Kr-95 1.62520E-03 1.63390E-03 360950 + 196 360960 Kr-96 4.81460E-04 4.81460E-04 360960 + 197 360970 Kr-97 4.32950E-05 4.32950E-05 360970 + 198 360980 Kr-98 6.78840E-06 6.78840E-06 360980 + 199 370860 Rb-86 9.62750E-10 2.98250E-09 37086.82c + 200 370861 Rb-86m 2.01980E-09 2.01980E-09 370861 + 201 370870 Rb-87 4.31850E-06 1.65870E-02 37087.82c + 202 370880 Rb-88 4.22120E-05 2.22480E-02 370880 + 203 370890 Rb-89 4.43850E-04 3.01810E-02 370890 + 204 370900 Rb-90 1.14850E-04 2.68850E-02 370900 + 205 370901 Rb-90m 1.16840E-03 5.17660E-03 370901 + 206 370910 Rb-91 6.99940E-03 4.15000E-02 370910 + 207 370920 Rb-92 1.38980E-02 3.96540E-02 370920 + 208 370930 Rb-93 2.63030E-02 3.93840E-02 370930 + 209 370940 Rb-94 1.58850E-02 2.15010E-02 370940 + 210 370950 Rb-95 1.21920E-02 1.37970E-02 370950 + 211 370960 Rb-96 3.08740E-03 4.98100E-03 370960 + 212 370961 Rb-96m 3.08740E-03 3.32070E-03 370961 + 213 370970 Rb-97 2.91700E-03 2.95790E-03 370970 + 214 370980 Rb-98 3.00760E-04 3.00760E-04 370980 + 215 370981 Rb-98m 3.00760E-04 3.07070E-04 370981 + 216 370990 Rb-99 1.55970E-04 1.55970E-04 370990 + 217 371000 Rb-100 6.02600E-06 6.02600E-06 371000 + 218 371010 Rb-101 9.79920E-07 9.79920E-07 371010 + 219 380880 Sr-88 8.46140E-10 2.22480E-02 38088.82c + 220 380890 Sr-89 1.11580E-05 3.01920E-02 38089.82c + 221 380900 Sr-90 9.81710E-05 3.20250E-02 38090.82c + 222 380910 Sr-91 6.01180E-04 4.21010E-02 380910 + 223 380920 Sr-92 3.79670E-03 4.40020E-02 380920 + 224 380930 Sr-93 1.19850E-02 5.29890E-02 380930 + 225 380940 Sr-94 2.94800E-02 4.99960E-02 380940 + 226 380950 Sr-95 3.65990E-02 4.98770E-02 380950 + 227 380960 Sr-96 4.64570E-02 5.31730E-02 380960 + 228 380970 Sr-97 3.17100E-02 3.39670E-02 380970 + 229 380980 Sr-98 2.05330E-02 2.11240E-02 380980 + 230 380990 Sr-99 8.40010E-03 8.53160E-03 380990 + 231 381000 Sr-100 2.93140E-03 2.93710E-03 381000 + 232 381010 Sr-101 5.97490E-04 5.98470E-04 381010 + 233 381020 Sr-102 1.10780E-04 1.10780E-04 381020 + 234 381030 Sr-103 4.18260E-06 4.18260E-06 381030 + 235 390910 Y-91 8.68050E-10 4.21010E-02 39091.82c + 236 390911 Y-91m 4.31120E-09 2.47710E-02 390911 + 237 390920 Y-92 3.48110E-06 4.40060E-02 390920 + 238 390930 Y-93 1.12760E-05 5.30850E-02 390930 + 239 390931 Y-93m 8.46870E-05 1.33450E-02 390931 + 240 390940 Y-94 4.72500E-04 5.04680E-02 390940 + 241 390950 Y-95 2.52030E-03 5.23970E-02 390950 + 242 390960 Y-96 2.15690E-03 5.53390E-02 390960 + 243 390961 Y-96m 4.52490E-03 4.53340E-03 390961 + 244 390970 Y-97 3.22190E-03 3.22620E-02 390970 + 245 390971 Y-97m 1.19090E-02 2.02350E-02 390971 + 246 390972 Y-97m 4.09280E-03 4.09280E-03 390972 + 247 390980 Y-98 3.99680E-03 2.51210E-02 390980 + 248 390981 Y-98m 1.93760E-02 1.93760E-02 390981 + 249 390990 Y-99 2.82710E-02 3.68250E-02 390990 + 250 391000 Y-100 8.15600E-03 1.10770E-02 391000 + 251 391001 Y-100m 8.15600E-03 8.16310E-03 391001 + 252 391010 Y-101 1.09550E-02 1.15450E-02 391010 + 253 391020 Y-102 1.87710E-03 1.92950E-03 391020 + 254 391021 Y-102m 1.87710E-03 1.92950E-03 391021 + 255 391030 Y-103 1.32990E-03 1.33410E-03 391030 + 256 391040 Y-104 1.46480E-04 1.46480E-04 391040 + 257 391050 Y-105 2.71750E-05 2.71750E-05 391050 + 258 391060 Y-106 1.66910E-09 1.66910E-09 391060 + 259 400930 Zr-93 1.89540E-06 5.30870E-02 40093.82c + 260 400940 Zr-94 1.40650E-05 5.04820E-02 40094.82c + 261 400950 Zr-95 1.09410E-04 5.25060E-02 40095.82c + 262 400960 Zr-96 8.62620E-04 6.07510E-02 40096.82c + 263 400970 Zr-97 3.37210E-03 5.72640E-02 400970 + 264 400980 Zr-98 1.34520E-02 5.78410E-02 400980 + 265 400990 Zr-99 2.50530E-02 6.13540E-02 400990 + 266 401000 Zr-100 4.37030E-02 6.28410E-02 401000 + 267 401010 Zr-101 4.23990E-02 5.41340E-02 401010 + 268 401020 Zr-102 3.93830E-02 4.31600E-02 401020 + 269 401030 Zr-103 2.12740E-02 2.25140E-02 401030 + 270 401040 Zr-104 8.99870E-03 9.13770E-03 401040 + 271 401050 Zr-105 2.40280E-03 2.42460E-03 401050 + 272 401060 Zr-106 5.89850E-04 5.89850E-04 401060 + 273 401070 Zr-107 3.45680E-05 3.45680E-05 401070 + 274 401080 Zr-108 2.65650E-06 2.65650E-06 401080 + 275 401090 Zr-109 4.70900E-11 4.70900E-11 401090 + 276 410960 Nb-96 1.31630E-09 1.31630E-09 410960 + 277 410970 Nb-97 1.66650E-05 5.72840E-02 410970 + 278 410971 Nb-97m 3.35530E-06 5.44320E-02 410971 + 279 410980 Nb-98 2.23600E-05 5.78630E-02 410980 + 280 410981 Nb-98m 7.79100E-05 7.79100E-05 410981 + 281 410990 Nb-99 6.49370E-04 3.98790E-02 410990 + 282 410991 Nb-99m 1.30750E-04 2.27090E-02 410991 + 283 411000 Nb-100 4.14660E-04 6.32560E-02 411000 + 284 411001 Nb-100m 2.01020E-03 2.01020E-03 411001 + 285 411010 Nb-101 9.27810E-03 6.34120E-02 411010 + 286 411020 Nb-102 8.00700E-03 5.11670E-02 411020 + 287 411021 Nb-102m 8.00700E-03 8.00700E-03 411021 + 288 411030 Nb-103 2.83640E-02 5.08780E-02 411030 + 289 411040 Nb-104 9.21850E-03 1.83900E-02 411040 + 290 411041 Nb-104m 9.21850E-03 9.21850E-03 411041 + 291 411050 Nb-105 1.49420E-02 1.73420E-02 411050 + 292 411060 Nb-106 5.76360E-03 6.34570E-03 411060 + 293 411070 Nb-107 2.90200E-03 2.93530E-03 411070 + 294 411080 Nb-108 2.49220E-04 2.51880E-04 411080 + 295 411090 Nb-109 5.12440E-05 5.12440E-05 411090 + 296 411100 Nb-110 2.54510E-05 2.54510E-05 411100 + 297 411110 Nb-111 1.76690E-10 1.76690E-10 411110 + 298 411120 Nb-112 1.13810E-05 1.13810E-05 411120 + 299 420990 Mo-99 1.26010E-05 6.21470E-02 42099.82c + 300 421000 Mo-100 1.49260E-04 6.54160E-02 42100.82c + 301 421010 Mo-101 7.78090E-04 6.41900E-02 421010 + 302 421020 Mo-102 3.71420E-03 6.28880E-02 421020 + 303 421030 Mo-103 9.33710E-03 6.02310E-02 421030 + 304 421040 Mo-104 1.81750E-02 4.60630E-02 421040 + 305 421050 Mo-105 1.87450E-02 3.60770E-02 421050 + 306 421060 Mo-106 1.71360E-02 2.33720E-02 421060 + 307 421070 Mo-107 1.12640E-02 1.40390E-02 421070 + 308 421080 Mo-108 2.81760E-03 3.06030E-03 421080 + 309 421090 Mo-109 6.15800E-04 6.70740E-04 421090 + 310 421100 Mo-110 1.97310E-04 2.12580E-04 421100 + 311 421110 Mo-111 4.51450E-05 4.51450E-05 421110 + 312 421120 Mo-112 1.13820E-05 2.27630E-05 421120 + 313 421130 Mo-113 6.12740E-06 6.12740E-06 421130 + 314 421140 Mo-114 2.58080E-11 2.58080E-11 421140 + 315 431020 Tc-102 6.16500E-06 6.28940E-02 431020 + 316 431021 Tc-102m 6.16500E-06 6.16500E-06 431021 + 317 431030 Tc-103 9.90170E-05 6.03300E-02 431030 + 318 431040 Tc-104 3.01780E-04 4.63650E-02 431040 + 319 431050 Tc-105 1.14850E-03 3.72260E-02 431050 + 320 431060 Tc-106 1.56020E-03 2.49320E-02 431060 + 321 431070 Tc-107 3.06460E-03 1.71030E-02 431070 + 322 431080 Tc-108 1.19250E-03 4.25640E-03 431080 + 323 431090 Tc-109 7.54330E-04 1.42150E-03 431090 + 324 431100 Tc-110 3.87370E-04 6.00420E-04 431100 + 325 431110 Tc-111 2.36640E-04 2.81790E-04 431110 + 326 431120 Tc-112 5.68850E-05 7.91750E-05 431120 + 327 431130 Tc-113 4.28710E-05 4.89980E-05 431130 + 328 431140 Tc-114 2.04040E-05 2.04040E-05 431140 + 329 431150 Tc-115 1.36250E-08 1.36250E-08 431150 + 330 431160 Tc-116 2.57950E-10 2.57950E-10 431160 + 331 441030 Ru-103 3.67120E-07 6.03310E-02 44103.82c + 332 441031 Ru-103m 1.02720E-06 1.02720E-06 441031 + 333 441040 Ru-104 1.78340E-05 4.63820E-02 44104.82c + 334 441050 Ru-105 4.24900E-05 3.72680E-02 44105.82c + 335 441060 Ru-106 1.30910E-04 2.50630E-02 44106.82c + 336 441070 Ru-107 2.00840E-04 1.73040E-02 441070 + 337 441080 Ru-108 2.82360E-04 4.53990E-03 441080 + 338 441090 Ru-109 1.95660E-04 1.61630E-03 441090 + 339 441100 Ru-110 2.93300E-04 8.93480E-04 441100 + 340 441110 Ru-111 2.59760E-04 5.42740E-04 441110 + 341 441120 Ru-112 3.18750E-04 4.00260E-04 441120 + 342 441130 Ru-113 9.49500E-05 1.89240E-04 441130 + 343 441131 Ru-113m 9.49500E-05 9.49500E-05 441131 + 344 441140 Ru-114 1.42760E-04 1.61830E-04 441140 + 345 441150 Ru-115 3.16830E-05 3.16950E-05 441150 + 346 441160 Ru-116 2.41480E-05 2.41480E-05 441160 + 347 441170 Ru-117 1.10520E-05 1.10520E-05 441170 + 348 441180 Ru-118 3.95550E-09 3.95550E-09 441180 + 349 441190 Ru-119 3.99250E-11 3.99250E-11 441190 + 350 441200 Ru-120 1.05050E-07 1.05050E-07 441200 + 351 451060 Rh-106 5.23940E-07 2.50640E-02 451060 + 352 451061 Rh-106m 1.42820E-06 1.42820E-06 451061 + 353 451070 Rh-107 7.38460E-09 1.73040E-02 451070 + 354 451080 Rh-108 1.66170E-08 4.53990E-03 451080 + 355 451081 Rh-108m 5.79010E-08 5.79010E-08 451081 + 356 451090 Rh-109 9.58540E-07 1.61720E-03 451090 + 357 451100 Rh-110 1.24380E-05 9.05910E-04 451100 + 358 451101 Rh-110m 2.92810E-07 2.92810E-07 451101 + 359 451110 Rh-111 1.01700E-04 6.44440E-04 451110 + 360 451120 Rh-112 2.84730E-05 4.28730E-04 451120 + 361 451121 Rh-112m 2.84730E-05 2.84730E-05 451121 + 362 451130 Rh-113 6.74400E-05 3.04150E-04 451130 + 363 451140 Rh-114 6.63800E-05 2.28290E-04 451140 + 364 451141 Rh-114m 6.63800E-05 6.63800E-05 451141 + 365 451150 Rh-115 1.74220E-04 2.06100E-04 451150 + 366 451160 Rh-116 5.18120E-05 7.59260E-05 451160 + 367 451161 Rh-116m 1.41230E-04 1.41230E-04 451161 + 368 451170 Rh-117 1.21460E-04 1.32280E-04 451170 + 369 451180 Rh-118 1.76370E-05 1.76410E-05 451180 + 370 451190 Rh-119 9.14320E-06 9.14320E-06 451190 + 371 451200 Rh-120 1.37160E-05 1.38210E-05 451200 + 372 451210 Rh-121 3.94670E-06 3.94670E-06 451210 + 373 451220 Rh-122 2.69100E-07 2.69100E-07 451220 + 374 461090 Pd-109 1.47250E-11 1.61720E-03 461090 + 375 461091 Pd-109m 3.23650E-11 8.08620E-04 461091 + 376 461100 Pd-110 2.49840E-09 9.06210E-04 46110.82c + 377 461110 Pd-111 1.62330E-08 6.43790E-04 461110 + 378 461111 Pd-111m 3.56800E-08 2.61340E-06 461111 + 379 461120 Pd-112 1.02790E-06 4.58230E-04 461120 + 380 461130 Pd-113 3.22750E-06 3.16410E-04 461130 + 381 461131 Pd-113m 9.03050E-06 9.03050E-06 461131 + 382 461140 Pd-114 3.06320E-05 3.25300E-04 461140 + 383 461150 Pd-115 5.45660E-05 2.42730E-04 461150 + 384 461151 Pd-115m 1.19930E-04 1.49860E-04 461151 + 385 461160 Pd-116 2.41920E-04 4.59070E-04 461160 + 386 461170 Pd-117 9.68620E-05 4.42560E-04 461170 + 387 461171 Pd-117m 2.12900E-04 2.12900E-04 461171 + 388 461180 Pd-118 2.38010E-04 2.55140E-04 461180 + 389 461190 Pd-119 1.27950E-04 1.37910E-04 461190 + 390 461200 Pd-120 8.22690E-05 9.58060E-05 461200 + 391 461210 Pd-121 2.74620E-05 3.08730E-05 461210 + 392 461220 Pd-122 5.39740E-06 5.66650E-06 461220 + 393 461230 Pd-123 7.61100E-06 7.61100E-06 461230 + 394 461240 Pd-124 2.56300E-06 2.56300E-06 461240 + 395 471120 Ag-112 5.11730E-11 4.58230E-04 471120 + 396 471130 Ag-113 3.50710E-10 2.07340E-04 471130 + 397 471131 Ag-113m 2.63410E-09 3.02990E-04 471131 + 398 471140 Ag-114 1.19680E-08 3.25370E-04 471140 + 399 471141 Ag-114m 5.80190E-08 5.80190E-08 471141 + 400 471150 Ag-115 2.08430E-07 2.20450E-04 471150 + 401 471151 Ag-115m 1.56550E-06 2.04970E-04 471151 + 402 471160 Ag-116 3.56700E-06 4.63220E-04 471160 + 403 471161 Ag-116m 9.72300E-06 9.72300E-06 471161 + 404 471170 Ag-117 3.89830E-06 2.40210E-04 471170 + 405 471171 Ag-117m 2.92790E-05 2.50560E-04 471171 + 406 471180 Ag-118 1.50970E-05 2.78720E-04 471180 + 407 471181 Ag-118m 7.31870E-05 1.09660E-04 471181 + 408 471190 Ag-119 1.50490E-05 8.40060E-05 471190 + 409 471191 Ag-119m 1.13030E-04 1.81990E-04 471191 + 410 471200 Ag-120 3.59420E-05 1.23890E-04 471200 + 411 471201 Ag-120m 6.01080E-05 1.08010E-04 471201 + 412 471210 Ag-121 6.86640E-05 9.94530E-05 471210 + 413 471220 Ag-122 2.59650E-05 3.16320E-05 471220 + 414 471221 Ag-122m 2.79940E-05 2.79940E-05 471221 + 415 471230 Ag-123 4.82750E-05 5.58860E-05 471230 + 416 471240 Ag-124 1.23470E-05 2.15660E-05 471240 + 417 471241 Ag-124m 1.33120E-05 1.33120E-05 471241 + 418 471250 Ag-125 1.27200E-05 1.27200E-05 471250 + 419 471260 Ag-126 1.83880E-05 1.83880E-05 471260 + 420 471270 Ag-127 9.94390E-06 9.94390E-06 471270 + 421 471280 Ag-128 5.88800E-06 5.88800E-06 471280 + 422 471290 Ag-129 2.35660E-08 2.35660E-08 471290 + 423 471300 Ag-130 7.94240E-10 7.94240E-10 471300 + 424 481150 Cd-115 6.01340E-11 3.64960E-04 481150 + 425 481151 Cd-115m 2.27730E-10 1.74170E-05 48515.82c + 426 481160 Cd-116 2.24170E-08 4.72390E-04 48116.82c + 427 481170 Cd-117 8.60230E-08 3.76820E-04 481170 + 428 481171 Cd-117m 3.25770E-07 9.93330E-05 481171 + 429 481180 Cd-118 5.05810E-06 3.48480E-04 481180 + 430 481190 Cd-119 2.40790E-06 2.26400E-04 481190 + 431 481191 Cd-119m 6.73730E-06 4.87420E-05 481191 + 432 481200 Cd-120 4.80380E-05 2.39970E-04 481200 + 433 481210 Cd-121 2.53310E-05 1.14390E-04 481210 + 434 481211 Cd-121m 7.08750E-05 8.12660E-05 481211 + 435 481220 Cd-122 1.13370E-04 1.73000E-04 481220 + 436 481230 Cd-123 1.83690E-05 6.41040E-05 481230 + 437 481231 Cd-123m 5.13960E-05 6.15690E-05 481231 + 438 481240 Cd-124 1.73220E-04 2.01420E-04 481240 + 439 481250 Cd-125 1.84180E-05 2.47780E-05 481250 + 440 481251 Cd-125m 5.15340E-05 5.78940E-05 481251 + 441 481260 Cd-126 4.76660E-04 4.95050E-04 481260 + 442 481270 Cd-127 4.76200E-04 4.86140E-04 481270 + 443 481280 Cd-128 6.22370E-04 6.28260E-04 481280 + 444 481290 Cd-129 1.02460E-04 1.02470E-04 481290 + 445 481291 Cd-129m 2.86670E-04 2.86680E-04 481291 + 446 481300 Cd-130 1.91340E-04 1.91340E-04 481300 + 447 481310 Cd-131 2.04830E-05 2.04830E-05 481310 + 448 481320 Cd-132 4.87970E-06 4.87970E-06 481320 + 449 491170 In-117 2.41450E-11 2.92670E-04 491170 + 450 491171 In-117m 4.86160E-12 3.46840E-04 491171 + 451 491180 In-118 2.13830E-10 3.48480E-04 491180 + 452 491181 In-118m 3.45300E-10 7.39470E-10 491181 + 453 491182 In-118m 3.99770E-10 3.99770E-10 491182 + 454 491190 In-119 3.14460E-08 8.21280E-05 491190 + 455 491191 In-119m 6.33140E-09 2.04500E-04 491191 + 456 491200 In-120 1.79870E-12 2.39970E-04 491200 + 457 491201 In-120m 1.79870E-12 1.79870E-12 491201 + 458 491202 In-120m 1.79870E-12 1.79870E-12 491202 + 459 491210 In-121 3.81160E-06 1.24530E-04 491210 + 460 491211 In-121m 7.67440E-07 7.66330E-05 491211 + 461 491220 In-122 1.01020E-05 1.83100E-04 491220 + 462 491221 In-122m 8.44710E-06 8.44710E-06 491221 + 463 491222 In-122m 8.44710E-06 8.44710E-06 491222 + 464 491230 In-123 1.34020E-05 9.40750E-05 491230 + 465 491231 In-123m 2.69840E-06 4.76980E-05 491231 + 466 491240 In-124 2.16200E-05 2.23040E-04 491240 + 467 491241 In-124m 2.33090E-05 2.33090E-05 491241 + 468 491250 In-125 7.94640E-05 1.49220E-04 491250 + 469 491251 In-125m 1.60000E-05 2.89180E-05 491251 + 470 491260 In-126 1.20490E-04 6.15540E-04 491260 + 471 491261 In-126m 1.29910E-04 1.29910E-04 491261 + 472 491270 In-127 5.47860E-04 5.47860E-04 491270 + 473 491271 In-127m 1.10310E-04 5.96450E-04 491271 + 474 491280 In-128 3.69900E-04 1.14300E-03 491280 + 475 491281 In-128m 1.44840E-04 7.73100E-04 491281 + 476 491282 In-128m 5.54960E-04 5.54960E-04 491282 + 477 491290 In-129 1.81550E-03 2.10550E-03 491290 + 478 491291 In-129m 3.65540E-04 4.71350E-04 491291 + 479 491300 In-130 5.91800E-04 7.77160E-04 491300 + 480 491301 In-130m 8.61690E-04 8.61690E-04 491301 + 481 491302 In-130m 1.20030E-03 1.20030E-03 491302 + 482 491310 In-131 8.60450E-04 8.88970E-04 491310 + 483 491311 In-131m 8.60450E-04 8.63370E-04 491311 + 484 491312 In-131m 8.60450E-04 8.60450E-04 491312 + 485 491320 In-132 4.64010E-04 4.65960E-04 491320 + 486 491330 In-133 8.00860E-05 9.62110E-05 491330 + 487 491331 In-133m 1.61250E-05 1.61250E-05 491331 + 488 491340 In-134 6.10810E-06 6.10810E-06 491340 + 489 491350 In-135 5.91280E-09 5.91280E-09 491350 + 490 501230 Sn-123 2.58870E-11 7.17250E-06 50123.82c + 491 501231 Sn-123m 9.25210E-12 1.34600E-04 501231 + 492 501240 Sn-124 6.41640E-06 2.52770E-04 50124.82c + 493 501250 Sn-125 2.34320E-05 4.86380E-05 50125.82c + 494 501251 Sn-125m 8.37480E-06 1.61300E-04 501251 + 495 501260 Sn-126 1.81890E-04 9.31450E-04 50126.82c + 496 501270 Sn-127 2.19750E-04 4.33290E-04 501270 + 497 501271 Sn-127m 7.85400E-05 1.00520E-03 501271 + 498 501280 Sn-128 3.36310E-04 2.95100E-03 501280 + 499 501281 Sn-128m 9.16700E-04 1.47170E-03 501281 + 500 501290 Sn-129 9.13680E-04 3.26640E-03 501290 + 501 501291 Sn-129m 2.55640E-03 2.78060E-03 501291 + 502 501300 Sn-130 3.67410E-03 5.43540E-03 501300 + 503 501301 Sn-130m 1.00150E-02 1.11100E-02 501301 + 504 501310 Sn-131 6.00640E-03 7.69420E-03 501310 + 505 501311 Sn-131m 1.68060E-02 1.77040E-02 501311 + 506 501320 Sn-132 2.85690E-02 2.91170E-02 501320 + 507 501330 Sn-133 9.55230E-03 9.57070E-03 501330 + 508 501340 Sn-134 2.70830E-03 2.71020E-03 501340 + 509 501350 Sn-135 3.68490E-04 3.68500E-04 501350 + 510 501360 Sn-136 5.71170E-05 5.71170E-05 501360 + 511 501370 Sn-137 7.44530E-06 7.44530E-06 501370 + 512 511250 Sb-125 6.40530E-12 2.09940E-04 51125.82c + 513 511260 Sb-126 4.60090E-10 5.50200E-10 51126.82c + 514 511261 Sb-126m 2.87380E-10 6.43620E-10 511261 + 515 511262 Sb-126m 3.56240E-10 3.56240E-10 511262 + 516 511270 Sb-127 1.98920E-05 1.45840E-03 511270 + 517 511280 Sb-128 2.94690E-05 2.98190E-03 511280 + 518 511281 Sb-128m 4.12160E-05 4.12160E-05 511281 + 519 511290 Sb-129 1.34230E-04 5.01440E-03 511290 + 520 511291 Sb-129m 9.93370E-05 1.48960E-03 511291 + 521 511300 Sb-130 4.99750E-04 1.14900E-02 511300 + 522 511301 Sb-130m 4.99750E-04 6.05490E-03 511301 + 523 511310 Sb-131 7.58540E-03 3.29840E-02 511310 + 524 511320 Sb-132 8.08810E-03 3.72050E-02 511320 + 525 511321 Sb-132m 7.16090E-03 7.16090E-03 511321 + 526 511330 Sb-133 4.29590E-02 5.29900E-02 511330 + 527 511340 Sb-134 4.54350E-03 6.83160E-03 511340 + 528 511341 Sb-134m 1.23840E-02 1.24230E-02 511341 + 529 511350 Sb-135 1.12570E-02 1.15650E-02 511350 + 530 511360 Sb-136 3.00260E-03 3.04690E-03 511360 + 531 511370 Sb-137 9.53300E-04 9.56430E-04 511370 + 532 511380 Sb-138 8.06050E-05 8.06050E-05 511380 + 533 511390 Sb-139 2.45810E-05 2.45810E-05 511390 + 534 521280 Te-128 4.77430E-10 3.02160E-03 52128.82c + 535 521290 Te-129 1.41000E-08 5.51510E-03 521290 + 536 521291 Te-129m 3.94510E-08 2.06880E-03 52529.82c + 537 521300 Te-130 3.43690E-05 1.75800E-02 52130.82c + 538 521310 Te-131 1.04660E-04 3.10640E-02 521310 + 539 521311 Te-131m 2.92820E-04 2.93360E-03 521311 + 540 521320 Te-132 3.44930E-03 4.78150E-02 52132.82c + 541 521330 Te-133 3.83180E-03 5.11470E-02 521330 + 542 521331 Te-133m 1.07210E-02 1.98880E-02 521331 + 543 521340 Te-134 4.67930E-02 6.78610E-02 521340 + 544 521350 Te-135 4.73330E-02 5.75790E-02 521350 + 545 521360 Te-136 4.97100E-02 5.27200E-02 521360 + 546 521370 Te-137 2.25230E-02 2.30110E-02 521370 + 547 521380 Te-138 1.36430E-02 1.37240E-02 521380 + 548 521390 Te-139 2.21300E-03 2.23760E-03 521390 + 549 521400 Te-140 8.82020E-04 8.82020E-04 521400 + 550 521410 Te-141 9.99280E-05 9.99280E-05 521410 + 551 521420 Te-142 2.04500E-05 2.04500E-05 521420 + 552 531310 I-131 2.91690E-08 3.33810E-02 53131.82c + 553 531320 I-132 1.72550E-06 4.78180E-02 531320 + 554 531321 I-132m 1.52770E-06 1.52770E-06 531321 + 555 531330 I-133 6.68030E-05 6.76710E-02 531330 + 556 531331 I-133m 4.94370E-05 4.94370E-05 531331 + 557 531340 I-134 2.93470E-04 6.84080E-02 531340 + 558 531341 I-134m 2.59830E-04 2.59830E-04 531341 + 559 531350 I-135 6.54890E-03 6.41280E-02 53135.82c + 560 531360 I-136 3.77770E-03 5.68420E-02 531360 + 561 531361 I-136m 1.02970E-02 1.06410E-02 531361 + 562 531370 I-137 3.11330E-02 5.43200E-02 531370 + 563 531380 I-138 2.02050E-02 3.30640E-02 531380 + 564 531390 I-139 2.47030E-02 2.69410E-02 531390 + 565 531400 I-140 8.63360E-03 9.51560E-03 531400 + 566 531410 I-141 5.99570E-03 6.09560E-03 531410 + 567 531420 I-142 9.32440E-04 9.52890E-04 531420 + 568 531430 I-143 2.42890E-04 2.42890E-04 531430 + 569 531440 I-144 2.46190E-05 2.46190E-05 531440 + 570 541330 Xe-133 1.03080E-09 6.76710E-02 54133.82c + 571 541331 Xe-133m 2.88410E-09 1.92620E-03 541331 + 572 541340 Xe-134 1.63960E-06 6.84200E-02 54134.82c + 573 541341 Xe-134m 4.46920E-06 1.04450E-05 541341 + 574 541350 Xe-135 2.63620E-05 6.41640E-02 54135.82c + 575 541351 Xe-135m 7.37580E-05 1.06600E-02 541351 + 576 541360 Xe-136 1.75290E-03 7.27670E-02 54136.82c + 577 541370 Xe-137 7.47830E-03 6.00200E-02 541370 + 578 541380 Xe-138 2.60160E-02 5.99680E-02 541380 + 579 541390 Xe-139 3.13700E-02 5.65550E-02 541390 + 580 541400 Xe-140 4.76470E-02 5.75580E-02 541400 + 581 541410 Xe-141 3.74520E-02 4.25060E-02 541410 + 582 541420 Xe-142 2.70020E-02 2.78140E-02 541420 + 583 541430 Xe-143 9.21820E-03 9.37380E-03 541430 + 584 541440 Xe-144 4.25230E-03 4.26710E-03 541440 + 585 541450 Xe-145 7.90810E-04 7.90810E-04 541450 + 586 541460 Xe-146 2.10400E-04 2.10400E-04 541460 + 587 541470 Xe-147 1.87320E-05 1.87320E-05 541470 + 588 551360 Cs-136 5.12730E-07 6.96030E-07 55136.82c + 589 551361 Cs-136m 3.66590E-07 3.66590E-07 551361 + 590 551370 Cs-137 2.51450E-05 6.00450E-02 55137.82c + 591 551380 Cs-138 9.17950E-05 6.01840E-02 551380 + 592 551381 Cs-138m 1.53520E-04 1.53520E-04 551381 + 593 551390 Cs-139 1.19340E-03 5.77490E-02 551390 + 594 551400 Cs-140 2.68970E-03 6.02660E-02 551400 + 595 551410 Cs-141 1.43960E-02 5.69830E-02 551410 + 596 551420 Cs-142 1.57030E-02 4.35100E-02 551420 + 597 551430 Cs-143 2.55520E-02 3.49600E-02 551430 + 598 551440 Cs-144 6.28600E-03 1.35980E-02 551440 + 599 551441 Cs-144m 6.28600E-03 6.30580E-03 551441 + 600 551450 Cs-145 9.73280E-03 1.04990E-02 551450 + 601 551460 Cs-146 3.10430E-03 3.30090E-03 551460 + 602 551470 Cs-147 1.41170E-03 1.42970E-03 551470 + 603 551480 Cs-148 2.54860E-04 2.54860E-04 551480 + 604 551490 Cs-149 2.61090E-05 2.61090E-05 551490 + 605 551500 Cs-150 7.35000E-09 7.35000E-09 551500 + 606 561380 Ba-138 1.96790E-06 6.02150E-02 56138.82c + 607 561390 Ba-139 2.55590E-05 5.77740E-02 561390 + 608 561400 Ba-140 1.90610E-04 6.04570E-02 56140.82c + 609 561410 Ba-141 9.52790E-04 5.79360E-02 561410 + 610 561420 Ba-142 4.29580E-03 4.83800E-02 561420 + 611 561430 Ba-143 1.18200E-02 4.66420E-02 561430 + 612 561440 Ba-144 2.87090E-02 4.65260E-02 561440 + 613 561450 Ba-145 2.70690E-02 3.65350E-02 561450 + 614 561460 Ba-146 2.84930E-02 3.17330E-02 561460 + 615 561470 Ba-147 1.36470E-02 1.47330E-02 561470 + 616 561480 Ba-148 8.81530E-03 9.00620E-03 561480 + 617 561490 Ba-149 2.07660E-03 2.10270E-03 561490 + 618 561500 Ba-150 6.07030E-04 6.07040E-04 561500 + 619 561510 Ba-151 7.10640E-05 7.10640E-05 561510 + 620 561520 Ba-152 1.02530E-05 1.02530E-05 561520 + 621 561530 Ba-153 4.22380E-10 4.22380E-10 561530 + 622 571410 La-141 1.00060E-06 5.79370E-02 571410 + 623 571420 La-142 4.72170E-06 4.83840E-02 571420 + 624 571430 La-143 7.36210E-05 4.67160E-02 571430 + 625 571440 La-144 3.77750E-04 4.69040E-02 571440 + 626 571450 La-145 1.93130E-03 3.84660E-02 571450 + 627 571460 La-146 1.18240E-03 3.29150E-02 571460 + 628 571461 La-146m 2.48060E-03 2.48060E-03 571461 + 629 571470 La-147 1.04450E-02 2.52140E-02 571470 + 630 571480 La-148 9.02040E-03 1.80000E-02 571480 + 631 571490 La-149 8.10130E-03 1.01950E-02 571490 + 632 571500 La-150 3.03880E-03 3.64580E-03 571500 + 633 571510 La-151 1.52130E-03 1.59240E-03 571510 + 634 571520 La-152 3.15010E-04 3.25260E-04 571520 + 635 571530 La-153 6.16280E-05 6.16280E-05 571530 + 636 571540 La-154 8.60310E-06 8.60310E-06 571540 + 637 571550 La-155 2.22370E-09 2.22370E-09 571550 + 638 581430 Ce-143 8.33940E-07 4.67160E-02 58143.82c + 639 581440 Ce-144 1.27080E-05 4.69160E-02 58144.82c + 640 581450 Ce-145 5.43050E-05 3.85210E-02 581450 + 641 581460 Ce-146 3.69570E-04 3.57650E-02 581460 + 642 581470 Ce-147 1.42150E-03 2.66360E-02 581470 + 643 581480 Ce-148 4.81740E-03 2.29600E-02 581480 + 644 581490 Ce-149 6.67500E-03 1.68260E-02 581490 + 645 581500 Ce-150 9.39800E-03 1.29450E-02 581500 + 646 581510 Ce-151 5.72770E-03 7.33970E-03 581510 + 647 581520 Ce-152 4.15940E-03 4.46500E-03 581520 + 648 581530 Ce-153 1.55170E-03 1.61330E-03 581530 + 649 581540 Ce-154 5.87060E-04 5.95660E-04 581540 + 650 581550 Ce-155 1.06220E-04 1.06220E-04 581550 + 651 581560 Ce-156 3.82620E-07 3.82620E-07 581560 + 652 581570 Ce-157 3.48420E-09 3.48420E-09 581570 + 653 591460 Pr-146 3.29540E-09 3.57650E-02 591460 + 654 591470 Pr-147 3.74950E-06 2.66390E-02 591470 + 655 591480 Pr-148 2.93330E-06 2.29630E-02 591480 + 656 591481 Pr-148m 1.42210E-05 1.42210E-05 591481 + 657 591490 Pr-149 1.00440E-04 1.69260E-02 591490 + 658 591500 Pr-150 2.35600E-04 1.31810E-02 591500 + 659 591510 Pr-151 7.56050E-04 8.09580E-03 591510 + 660 591520 Pr-152 9.68830E-04 5.44390E-03 591520 + 661 591530 Pr-153 1.61520E-03 3.22230E-03 591530 + 662 591540 Pr-154 9.61230E-04 1.55310E-03 591540 + 663 591550 Pr-155 5.28820E-04 6.35040E-04 591550 + 664 591560 Pr-156 1.06270E-04 1.06650E-04 591560 + 665 591570 Pr-157 2.02700E-05 2.02740E-05 591570 + 666 591580 Pr-158 1.99250E-07 1.99250E-07 591580 + 667 591590 Pr-159 7.89360E-09 7.89360E-09 591590 + 668 601480 Nd-148 1.00880E-06 2.29780E-02 60148.82c + 669 601490 Nd-149 2.09170E-06 1.69280E-02 601490 + 670 601500 Nd-150 1.06880E-05 1.31920E-02 60150.82c + 671 601510 Nd-151 5.05820E-05 8.14630E-03 601510 + 672 601520 Nd-152 2.03420E-04 5.64730E-03 601520 + 673 601530 Nd-153 3.97550E-04 3.61980E-03 601530 + 674 601540 Nd-154 8.57930E-04 2.41100E-03 601540 + 675 601550 Nd-155 8.02580E-04 1.44050E-03 601550 + 676 601560 Nd-156 4.95180E-04 6.00230E-04 601560 + 677 601570 Nd-157 1.82440E-04 2.01420E-04 601570 + 678 601580 Nd-158 8.65730E-05 8.67720E-05 601580 + 679 601590 Nd-159 1.56630E-05 1.56710E-05 601590 + 680 601600 Nd-160 4.23750E-07 4.23750E-07 601600 + 681 601610 Nd-161 8.25810E-09 8.25810E-09 601610 + 682 611510 Pm-151 4.81300E-10 8.14630E-03 61151.82c + 683 611520 Pm-152 2.84420E-09 5.64730E-03 611520 + 684 611521 Pm-152m 5.97960E-09 5.97960E-09 611521 + 685 611522 Pm-152m 7.81090E-09 7.81090E-09 611522 + 686 611530 Pm-153 2.28590E-06 3.62210E-03 611530 + 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3.89980E-06 4.01780E-06 621620 + 707 621630 Sm-163 7.08020E-07 7.16460E-07 621630 + 708 621640 Sm-164 1.36030E-07 1.36030E-07 621640 + 709 621650 Sm-165 6.44070E-09 6.44070E-09 621650 + 710 631560 Eu-156 1.48050E-11 6.57530E-04 63156.82c + 711 631570 Eu-157 5.27060E-10 2.43900E-04 63157.82c + 712 631580 Eu-158 7.73920E-09 1.15690E-04 631580 + 713 631590 Eu-159 1.30750E-07 8.38820E-05 631590 + 714 631600 Eu-160 5.13950E-07 3.43480E-05 631600 + 715 631610 Eu-161 1.43170E-06 1.19510E-05 631610 + 716 631620 Eu-162 1.32640E-06 5.34420E-06 631620 + 717 631630 Eu-163 1.59190E-06 2.30840E-06 631630 + 718 631640 Eu-164 6.33780E-07 7.69810E-07 631640 + 719 631650 Eu-165 2.39650E-07 2.46090E-07 631650 + 720 631660 Eu-166 2.72380E-08 2.72380E-08 631660 + 721 631670 Eu-167 4.34230E-09 4.34230E-09 631670 + 722 641590 Gd-159 1.18550E-11 8.38820E-05 641590 + 723 641600 Gd-160 4.94470E-10 3.43480E-05 64160.82c + 724 641610 Gd-161 4.13190E-09 1.19550E-05 641610 + 725 641620 Gd-162 3.60760E-08 5.38030E-06 641620 + 726 641630 Gd-163 1.07190E-07 2.41560E-06 641630 + 727 641640 Gd-164 3.14070E-07 1.08390E-06 641640 + 728 641650 Gd-165 2.34100E-07 4.80190E-07 641650 + 729 641660 Gd-166 1.78440E-07 2.05680E-07 641660 + 730 641670 Gd-167 6.19510E-08 6.62930E-08 641670 + 731 641680 Gd-168 2.10120E-08 2.10120E-08 641680 + 732 641690 Gd-169 2.10680E-09 2.10680E-09 641690 + 733 651620 Tb-162 4.06190E-12 5.38030E-06 651620 + 734 651630 Tb-163 1.27450E-10 2.41570E-06 651630 + 735 651640 Tb-164 1.08890E-09 1.08500E-06 651640 + 736 651650 Tb-165 7.32020E-09 4.87510E-07 651650 + 737 651660 Tb-166 1.30570E-08 2.18740E-07 651660 + 738 651670 Tb-167 3.17710E-08 9.80640E-08 651670 + 739 651680 Tb-168 2.09740E-08 4.19860E-08 651680 + 740 651690 Tb-169 1.45660E-08 1.66730E-08 651690 + 741 651700 Tb-170 3.49120E-09 3.49120E-09 651700 + 742 651710 Tb-171 9.52370E-10 9.52370E-10 651710 + 743 661650 Dy-165 2.56720E-12 4.87510E-07 661650 + 744 661660 Dy-166 5.34010E-11 2.18790E-07 661660 + 745 661670 Dy-167 3.65970E-10 9.84300E-08 661670 + 746 661680 Dy-168 2.07180E-09 4.40580E-08 661680 + 747 661690 Dy-169 3.18190E-09 1.98550E-08 661690 + 748 661700 Dy-170 5.15270E-09 8.64390E-09 661700 + 749 661710 Dy-171 2.75560E-09 3.70800E-09 661710 + 750 661720 Dy-172 1.41020E-09 1.41020E-09 661720 + 751 661730 Dy-173 3.12900E-10 3.12900E-10 661730 + 752 671680 Ho-168 3.82280E-13 4.40590E-08 671680 + 753 671690 Ho-169 1.57200E-11 1.98700E-08 671690 + 754 671700 Ho-170 5.03180E-11 5.03180E-11 671700 + 755 671701 Ho-170m 1.84600E-11 8.66240E-09 671701 + 756 671710 Ho-171 2.98480E-10 4.00640E-09 671710 + 757 671720 Ho-172 3.20700E-10 1.73090E-09 671720 + 758 671730 Ho-173 4.71370E-10 7.84270E-10 671730 + 759 671740 Ho-174 2.19750E-10 2.19750E-10 671740 + 760 671750 Ho-175 9.55770E-11 9.55770E-11 671750 + 761 681720 Er-172 5.29790E-12 1.73620E-09 681720 + 762 681730 Er-173 2.00520E-11 8.04320E-10 681730 + 763 681740 Er-174 7.16530E-11 2.91400E-10 681740 + 764 681750 Er-175 6.27510E-11 1.58330E-10 681750 + 765 681760 Er-176 5.74110E-11 5.74110E-11 681760 + 766 681770 Er-177 2.27300E-11 2.27300E-11 681770 + 767 691750 Tm-175 1.21030E-12 1.59540E-10 691750 + 768 691760 Tm-176 2.70230E-12 6.01130E-11 691760 + 769 691770 Tm-177 7.76730E-12 3.04970E-11 691770 + 770 691780 Tm-178 5.76860E-12 5.76860E-12 691780 + 771 691790 Tm-179 4.88740E-12 4.88740E-12 691790 + + Neutron-induced fission: + + Interpolation region : 2 / 2 + Interpolation energy : 1.40000E+01 MeV + Number of products : 1037 / 1146 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 1.30120E-05 1.30120E-05 1001.82c + 2 10020 H-2 3.97660E-06 3.97660E-06 1002.82c + 3 10030 H-3 6.49900E-05 6.49900E-05 1003.82c + 4 20040 He-4 8.22600E-04 8.22600E-04 2004.82c + 5 190500 K-50 2.14670E-12 2.14670E-12 190500 + 6 190510 K-51 1.16000E-12 1.16000E-12 190510 + 7 200500 Ca-50 2.64520E-11 2.85210E-11 200500 + 8 200510 Ca-51 2.22670E-11 2.28820E-11 200510 + 9 200520 Ca-52 2.47380E-11 2.47380E-11 200520 + 10 200530 Ca-53 7.94820E-12 7.94820E-12 200530 + 11 200540 Ca-54 3.12010E-12 3.12010E-12 200540 + 12 210500 Sc-50 7.45480E-12 3.72500E-11 210500 + 13 210501 Sc-50m 1.65090E-12 3.01720E-11 210501 + 14 210510 Sc-51 4.17690E-11 6.51460E-11 210510 + 15 210520 Sc-52 6.66250E-11 9.32530E-11 210520 + 16 210530 Sc-53 1.24310E-10 1.29870E-10 210530 + 17 210540 Sc-54 7.80060E-11 8.11260E-11 210540 + 18 210550 Sc-55 7.46210E-11 7.46210E-11 210550 + 19 210560 Sc-56 2.03680E-11 2.03680E-11 210560 + 20 210570 Sc-57 6.74230E-12 6.74230E-12 210570 + 21 220510 Ti-51 3.44690E-12 6.85930E-11 220510 + 22 220520 Ti-52 3.15240E-11 1.24780E-10 220520 + 23 220530 Ti-53 8.38550E-11 2.13730E-10 220530 + 24 220540 Ti-54 2.87310E-10 3.68440E-10 220540 + 25 220550 Ti-55 4.01630E-10 4.76250E-10 220550 + 26 220560 Ti-56 6.53020E-10 6.75610E-10 220560 + 27 220570 Ti-57 3.54170E-10 3.58690E-10 220570 + 28 220580 Ti-58 2.62700E-10 2.62700E-10 220580 + 29 220590 Ti-59 6.13440E-11 6.13440E-11 220590 + 30 220600 Ti-60 1.54110E-11 1.54110E-11 220600 + 31 220610 Ti-61 1.44070E-12 1.44070E-12 220610 + 32 230530 V-53 5.68360E-12 2.19410E-10 230530 + 33 230540 V-54 2.99180E-11 3.98350E-10 230540 + 34 230550 V-55 2.34730E-10 7.10980E-10 230550 + 35 230560 V-56 5.39830E-10 1.21650E-09 230560 + 36 230570 V-57 1.61370E-09 1.97130E-09 230570 + 37 230580 V-58 1.78820E-09 2.05090E-09 230580 + 38 230590 V-59 2.55250E-09 2.61380E-09 230590 + 39 230600 V-60 1.07480E-09 1.09020E-09 230600 + 40 230610 V-61 6.78700E-10 6.80140E-10 230610 + 41 230620 V-62 1.34070E-10 1.34070E-10 230620 + 42 230630 V-63 1.87520E-10 1.87520E-10 230630 + 43 230640 V-64 6.18240E-12 6.18240E-12 230640 + 44 230650 V-65 1.01110E-12 1.01110E-12 230650 + 45 240550 Cr-55 5.30610E-12 7.16290E-10 240550 + 46 240560 Cr-56 7.48270E-11 1.29920E-09 240560 + 47 240570 Cr-57 3.35160E-10 3.93930E-09 240570 + 48 240580 Cr-58 2.05030E-09 2.46050E-09 240580 + 49 240590 Cr-59 4.13760E-09 6.75140E-09 240590 + 50 240600 Cr-60 9.75610E-09 1.08870E-08 240600 + 51 240610 Cr-61 9.43480E-09 1.00740E-08 240610 + 52 240620 Cr-62 1.16830E-08 1.18830E-08 240620 + 53 240630 Cr-63 2.79580E-08 2.80800E-08 240630 + 54 240640 Cr-64 6.32640E-09 6.33260E-09 240640 + 55 240650 Cr-65 1.90160E-09 1.90260E-09 240650 + 56 240660 Cr-66 6.56390E-11 6.56390E-11 240660 + 57 240670 Cr-67 2.92630E-12 2.92630E-12 240670 + 58 250570 Mn-57 5.99180E-12 3.94530E-09 250570 + 59 250580 Mn-58 5.67260E-11 2.51720E-09 250580 + 60 250581 Mn-58m 3.50540E-12 3.50540E-12 250581 + 61 250590 Mn-59 7.26300E-10 7.47770E-09 250590 + 62 250600 Mn-60 1.46020E-10 1.13050E-08 250600 + 63 250601 Mn-60m 2.36290E-09 2.36290E-09 250601 + 64 250610 Mn-61 1.32580E-08 2.33320E-08 250610 + 65 250620 Mn-62 2.12820E-08 2.72230E-08 250620 + 66 250621 Mn-62m 2.09200E-09 8.03330E-09 250621 + 67 250630 Mn-63 3.19810E-07 3.47890E-07 250630 + 68 250640 Mn-64 1.13730E-07 1.20060E-07 250640 + 69 250650 Mn-65 2.19390E-07 2.21290E-07 250650 + 70 250660 Mn-66 1.31930E-08 1.32590E-08 250660 + 71 250670 Mn-67 4.08680E-09 4.08970E-09 250670 + 72 250680 Mn-68 8.97410E-10 8.97410E-10 250680 + 73 250690 Mn-69 6.66670E-11 6.66670E-11 250690 + 74 260590 Fe-59 4.18490E-12 7.48190E-09 260590 + 75 260600 Fe-60 9.43480E-11 1.34900E-08 260600 + 76 260610 Fe-61 7.99460E-10 2.41320E-08 260610 + 77 260620 Fe-62 8.20990E-09 4.34670E-08 260620 + 78 260630 Fe-63 5.05320E-07 8.53210E-07 260630 + 79 260640 Fe-64 3.13080E-07 4.33140E-07 260640 + 80 260650 Fe-65 8.71800E-07 1.09310E-06 260650 + 81 260660 Fe-66 3.07060E-07 3.20320E-07 260660 + 82 260670 Fe-67 1.53360E-07 1.57450E-07 260670 + 83 260680 Fe-68 2.20770E-07 2.21680E-07 260680 + 84 260690 Fe-69 2.90290E-08 2.90800E-08 260690 + 85 260700 Fe-70 1.69820E-08 1.69820E-08 260700 + 86 260710 Fe-71 1.53920E-09 1.53920E-09 260710 + 87 260720 Fe-72 2.71460E-10 2.71460E-10 260720 + 88 270610 Co-61 3.53700E-12 2.41350E-08 270610 + 89 270620 Co-62 1.14310E-11 4.34790E-08 270620 + 90 270621 Co-62m 5.16210E-11 5.16210E-11 270621 + 91 270630 Co-63 7.92410E-09 8.61130E-07 270630 + 92 270640 Co-64 4.27530E-07 8.60670E-07 270640 + 93 270650 Co-65 1.51930E-06 2.61240E-06 270650 + 94 270660 Co-66 5.15350E-07 8.35670E-07 270660 + 95 270670 Co-67 5.20000E-07 6.77450E-07 270670 + 96 270680 Co-68 1.08780E-06 1.43520E-06 270680 + 97 270681 Co-68m 4.71100E-07 6.94820E-07 270681 + 98 270690 Co-69 8.70570E-07 8.97610E-07 270690 + 99 270700 Co-70 5.79300E-07 5.79300E-07 270700 + 100 270701 Co-70m 5.79300E-07 5.96280E-07 270701 + 101 270710 Co-71 5.09360E-07 5.10900E-07 270710 + 102 270720 Co-72 1.60930E-07 1.61200E-07 270720 + 103 270730 Co-73 4.20630E-08 4.20630E-08 270730 + 104 270740 Co-74 3.63010E-09 3.63010E-09 270740 + 105 270750 Co-75 4.23320E-10 4.23320E-10 270750 + 106 280630 Ni-63 1.10200E-11 8.61140E-07 280630 + 107 280640 Ni-64 2.28230E-10 8.60900E-07 28064.82c + 108 280650 Ni-65 6.16020E-09 2.61860E-06 280650 + 109 280660 Ni-66 1.92190E-08 8.54890E-07 280660 + 110 280670 Ni-67 7.30830E-07 1.40830E-06 280670 + 111 280680 Ni-68 7.79420E-07 2.57100E-06 280680 + 112 280690 Ni-69 7.04450E-07 1.59310E-06 280690 + 113 280691 Ni-69m 7.04450E-07 7.04450E-07 280691 + 114 280700 Ni-70 3.47560E-06 4.65120E-06 280700 + 115 280710 Ni-71 7.55920E-06 8.07010E-06 280710 + 116 280720 Ni-72 1.57810E-05 1.59420E-05 280720 + 117 280730 Ni-73 1.00980E-05 1.01400E-05 280730 + 118 280740 Ni-74 6.83180E-06 6.83540E-06 280740 + 119 280750 Ni-75 5.46260E-07 5.46680E-07 280750 + 120 280760 Ni-76 8.48090E-08 8.48090E-08 280760 + 121 280770 Ni-77 3.30970E-09 3.30970E-09 280770 + 122 280780 Ni-78 1.88480E-10 1.88480E-10 280780 + 123 290650 Cu-65 6.47100E-12 2.61860E-06 29065.82c + 124 290660 Cu-66 3.62950E-11 8.54920E-07 290660 + 125 290670 Cu-67 1.01700E-09 1.40930E-06 290670 + 126 290680 Cu-68 3.63510E-09 2.58840E-06 290680 + 127 290681 Cu-68m 1.64150E-08 1.64150E-08 290681 + 128 290690 Cu-69 7.04430E-07 3.00200E-06 290690 + 129 290700 Cu-70 1.03800E-07 1.27740E-06 290700 + 130 290701 Cu-70m 2.10950E-06 2.34730E-06 290701 + 131 290702 Cu-70m 1.03800E-07 4.75500E-06 290702 + 132 290710 Cu-71 3.77870E-06 1.18490E-05 290710 + 133 290720 Cu-72 1.14690E-05 2.74110E-05 290720 + 134 290730 Cu-73 2.82650E-05 3.84050E-05 290730 + 135 290740 Cu-74 2.50560E-05 3.19000E-05 290740 + 136 290750 Cu-75 6.12860E-05 6.18240E-05 290750 + 137 290760 Cu-76 1.01280E-05 1.01710E-05 290760 + 138 290761 Cu-76m 1.01280E-05 1.01710E-05 290761 + 139 290770 Cu-77 4.78180E-06 4.78510E-06 290770 + 140 290780 Cu-78 3.28710E-07 3.28900E-07 290780 + 141 290790 Cu-79 6.98230E-08 6.98230E-08 290790 + 142 290800 Cu-80 4.09760E-09 4.09760E-09 290800 + 143 300680 Zn-68 4.58330E-11 2.59110E-06 300680 + 144 300690 Zn-69 6.17780E-11 3.00250E-06 300690 + 145 300691 Zn-69m 4.91790E-10 4.91790E-10 300691 + 146 300700 Zn-70 2.91110E-08 6.99740E-06 300700 + 147 300710 Zn-71 2.65520E-08 1.18750E-05 300710 + 148 300711 Zn-71m 2.11370E-07 2.11370E-07 300711 + 149 300720 Zn-72 2.86740E-06 3.02790E-05 300720 + 150 300730 Zn-73 9.27820E-07 4.75970E-05 300730 + 151 300731 Zn-73m 1.31990E-06 8.26400E-06 300731 + 152 300732 Zn-73m 1.38880E-05 1.38880E-05 300732 + 153 300740 Zn-74 7.05390E-05 1.04600E-04 300740 + 154 300750 Zn-75 1.47370E-04 2.07340E-04 300750 + 155 300760 Zn-76 1.93680E-04 2.13720E-04 300760 + 156 300770 Zn-77 1.15290E-04 1.24880E-04 300770 + 157 300771 Zn-77m 9.60480E-06 9.60480E-06 300771 + 158 300780 Zn-78 9.94200E-05 9.97870E-05 300780 + 159 300790 Zn-79 4.76330E-05 4.76640E-05 300790 + 160 300800 Zn-80 2.44690E-05 2.44730E-05 300800 + 161 300810 Zn-81 3.41970E-06 3.41970E-06 300810 + 162 300820 Zn-82 1.11420E-07 1.11420E-07 300820 + 163 300830 Zn-83 3.87170E-09 3.87170E-09 300830 + 164 310700 Ga-70 1.28740E-11 1.28740E-11 310700 + 165 310710 Ga-71 7.39030E-10 1.20880E-05 310710 + 166 310720 Ga-72 1.99550E-08 3.03000E-05 310720 + 167 310721 Ga-72m 1.23310E-09 1.01010E-06 310721 + 168 310730 Ga-73 4.96860E-07 5.50380E-05 310730 + 169 310740 Ga-74 1.13750E-06 8.04430E-05 310740 + 170 310741 Ga-74m 1.13750E-06 1.05740E-04 310741 + 171 310750 Ga-75 1.89830E-05 2.26320E-04 310750 + 172 310760 Ga-76 8.10540E-05 2.94770E-04 310760 + 173 310770 Ga-77 1.52860E-04 2.82540E-04 310770 + 174 310780 Ga-78 1.91210E-04 2.91620E-04 310780 + 175 310790 Ga-79 3.94620E-04 4.41660E-04 310790 + 176 310800 Ga-80 3.87050E-04 4.11780E-04 310800 + 177 310810 Ga-81 3.32660E-04 3.35820E-04 310810 + 178 310820 Ga-82 8.19290E-05 8.20400E-05 310820 + 179 310830 Ga-83 2.24620E-05 2.24660E-05 310830 + 180 310840 Ga-84 9.65880E-07 9.65880E-07 310840 + 181 310850 Ga-85 5.11730E-08 5.11730E-08 310850 + 182 310860 Ga-86 1.67560E-09 1.67560E-09 310860 + 183 320720 Ge-72 1.12640E-11 3.03000E-05 32072.82c + 184 320730 Ge-73 4.29040E-10 5.50380E-05 32073.82c + 185 320731 Ge-73m 5.38950E-11 5.42300E-05 320731 + 186 320740 Ge-74 2.61680E-08 1.06900E-04 32074.82c + 187 320750 Ge-75 3.80990E-08 2.26810E-04 320750 + 188 320751 Ge-75m 4.57340E-07 9.51010E-06 320751 + 189 320760 Ge-76 8.39240E-06 3.03160E-04 32076.82c + 190 320770 Ge-77 3.90400E-05 9.33410E-05 320770 + 191 320771 Ge-77m 3.25230E-06 2.85800E-04 320771 + 192 320780 Ge-78 1.26580E-04 4.18590E-04 320780 + 193 320790 Ge-79 3.50890E-05 4.92570E-04 320790 + 194 320791 Ge-79m 4.21200E-04 4.21860E-04 320791 + 195 320800 Ge-80 1.28550E-03 1.73720E-03 320800 + 196 320810 Ge-81 1.87600E-03 2.04490E-03 320810 + 197 320811 Ge-81m 2.35670E-04 3.84020E-04 320811 + 198 320820 Ge-82 2.48690E-03 2.55980E-03 320820 + 199 320830 Ge-83 1.27270E-03 1.28750E-03 320830 + 200 320840 Ge-84 5.53300E-04 5.53590E-04 320840 + 201 320850 Ge-85 8.08230E-05 8.08740E-05 320850 + 202 320860 Ge-86 2.25740E-05 2.25760E-05 320860 + 203 320870 Ge-87 2.38850E-06 2.38850E-06 320870 + 204 320880 Ge-88 2.42750E-08 2.42750E-08 320880 + 205 320890 Ge-89 7.28230E-10 7.28230E-10 320890 + 206 330740 As-74 2.48640E-12 2.48640E-12 330740 + 207 330750 As-75 5.05440E-11 2.26810E-04 33075.82c + 208 330751 As-75m 3.12300E-10 3.16530E-09 330751 + 209 330760 As-76 9.16720E-09 9.16720E-09 330760 + 210 330770 As-77 2.24540E-07 3.25060E-04 330770 + 211 330780 As-78 9.76290E-07 4.19570E-04 330780 + 212 330790 As-79 3.00620E-05 9.27620E-04 330790 + 213 330800 As-80 1.19930E-04 1.85720E-03 330800 + 214 330810 As-81 6.91490E-04 3.11650E-03 330810 + 215 330820 As-82 2.79930E-04 2.83970E-03 330820 + 216 330821 As-82m 1.58380E-03 1.58380E-03 330821 + 217 330830 As-83 3.89970E-03 5.24700E-03 330830 + 218 330840 As-84 1.84610E-03 2.09870E-03 330840 + 219 330841 As-84m 1.84610E-03 2.09870E-03 330841 + 220 330850 As-85 2.08910E-03 2.15860E-03 330850 + 221 330860 As-86 1.15520E-03 1.17780E-03 330860 + 222 330870 As-87 4.37570E-04 4.39960E-04 330870 + 223 330880 As-88 6.98150E-05 6.98390E-05 330880 + 224 330890 As-89 8.75090E-06 8.75160E-06 330890 + 225 330900 As-90 1.78430E-07 1.78430E-07 330900 + 226 330910 As-91 8.46020E-09 8.46020E-09 330910 + 227 340770 Se-77 3.99780E-12 3.25060E-04 34077.82c + 228 340771 Se-77m 4.79890E-11 4.79890E-11 340771 + 229 340780 Se-78 3.26710E-09 4.19570E-04 34078.82c + 230 340790 Se-79 1.16010E-06 9.28370E-04 34079.82c + 231 340791 Se-79m 9.66400E-08 9.05750E-04 340791 + 232 340800 Se-80 4.52200E-06 1.86170E-03 34080.82c + 233 340810 Se-81 6.83230E-06 3.20530E-03 340810 + 234 340811 Se-81m 8.20150E-05 1.93890E-04 340811 + 235 340820 Se-82 4.44770E-04 4.86830E-03 34082.82c + 236 340830 Se-83 1.72140E-03 3.61320E-03 340830 + 237 340831 Se-83m 2.16240E-04 3.57730E-03 340831 + 238 340840 Se-84 7.92280E-03 1.25890E-02 340840 + 239 340850 Se-85 7.09890E-03 9.17130E-03 340850 + 240 340860 Se-86 1.15190E-02 1.23760E-02 340860 + 241 340870 Se-87 6.71160E-03 7.08380E-03 340870 + 242 340880 Se-88 3.69070E-03 3.76050E-03 340880 + 243 340890 Se-89 1.52700E-03 1.53580E-03 340890 + 244 340900 Se-90 4.09830E-04 4.10010E-04 340900 + 245 340910 Se-91 6.72700E-05 6.72780E-05 340910 + 246 340920 Se-92 1.03140E-05 1.03140E-05 340920 + 247 340930 Se-93 6.30360E-08 6.30360E-08 340930 + 248 340940 Se-94 1.84590E-09 1.84590E-09 340940 + 249 350790 Br-79 4.36930E-12 5.07250E-07 35079.82c + 250 350791 Br-79m 2.69970E-11 2.69970E-11 350791 + 251 350800 Br-80 1.96130E-10 1.30580E-09 350800 + 252 350801 Br-80m 1.10970E-09 1.10970E-09 350801 + 253 350810 Br-81 9.21850E-08 3.20550E-03 35081.82c + 254 350820 Br-82 2.68660E-06 3.26730E-06 350820 + 255 350821 Br-82m 5.94950E-07 5.94950E-07 350821 + 256 350830 Br-83 3.61860E-05 7.22670E-03 350830 + 257 350840 Br-84 1.29370E-04 1.27190E-02 350840 + 258 350841 Br-84m 1.29370E-04 1.29370E-04 350841 + 259 350850 Br-85 1.19510E-03 1.03660E-02 350850 + 260 350860 Br-86 3.99140E-03 1.63670E-02 350860 + 261 350870 Br-87 9.27110E-03 1.63920E-02 350870 + 262 350880 Br-88 9.68260E-03 1.35260E-02 350880 + 263 350890 Br-89 1.21430E-02 1.35590E-02 350890 + 264 350900 Br-90 6.73160E-03 7.15570E-03 350900 + 265 350910 Br-91 4.02360E-03 4.07670E-03 350910 + 266 350920 Br-92 9.70800E-04 9.81110E-04 350920 + 267 350930 Br-93 2.54570E-04 2.54630E-04 350930 + 268 350940 Br-94 2.74120E-05 2.74140E-05 350940 + 269 350950 Br-95 7.18810E-06 7.18810E-06 350950 + 270 350960 Br-96 1.40950E-08 1.40950E-08 350960 + 271 360820 Kr-82 5.56110E-10 3.28220E-06 36082.82c + 272 360830 Kr-83 2.23580E-08 7.22670E-03 36083.82c + 273 360831 Kr-83m 2.80850E-09 7.22030E-03 360831 + 274 360840 Kr-84 9.14040E-06 1.28570E-02 36084.82c + 275 360850 Kr-85 4.39160E-05 2.27680E-03 36085.82c + 276 360851 Kr-85m 5.51670E-06 1.03550E-02 360851 + 277 360860 Kr-86 6.01870E-04 1.73810E-02 36086.82c + 278 360870 Kr-87 1.83180E-03 1.87190E-02 360870 + 279 360880 Kr-88 6.50250E-03 2.10340E-02 360880 + 280 360890 Kr-89 1.33290E-02 2.67360E-02 360890 + 281 360900 Kr-90 2.24480E-02 2.86590E-02 360900 + 282 360910 Kr-91 2.32620E-02 2.68480E-02 360910 + 283 360920 Kr-92 1.95320E-02 2.03620E-02 360920 + 284 360930 Kr-93 9.37560E-03 9.47630E-03 360930 + 285 360940 Kr-94 4.09620E-03 4.10440E-03 360940 + 286 360950 Kr-95 7.57020E-04 7.64210E-04 360950 + 287 360960 Kr-96 1.46680E-04 1.46690E-04 360960 + 288 360970 Kr-97 1.54060E-05 1.54060E-05 360970 + 289 360980 Kr-98 1.81450E-06 1.81450E-06 360980 + 290 360990 Kr-99 3.11760E-09 3.11760E-09 360990 + 291 370850 Rb-85 5.87790E-09 1.04160E-02 37085.82c + 292 370860 Rb-86 4.94460E-08 2.22430E-07 37086.82c + 293 370861 Rb-86m 1.72980E-07 1.72980E-07 370861 + 294 370870 Rb-87 2.15040E-05 1.87400E-02 37087.82c + 295 370880 Rb-88 1.04690E-04 2.11390E-02 370880 + 296 370890 Rb-89 7.89040E-04 2.75260E-02 370890 + 297 370900 Rb-90 1.47060E-04 2.52170E-02 370900 + 298 370901 Rb-90m 2.37970E-03 6.12830E-03 370901 + 299 370910 Rb-91 8.82610E-03 3.56740E-02 370910 + 300 370920 Rb-92 1.36790E-02 3.40410E-02 370920 + 301 370930 Rb-93 2.44730E-02 3.39950E-02 370930 + 302 370940 Rb-94 2.16080E-02 2.56890E-02 370940 + 303 370950 Rb-95 1.58000E-02 1.65480E-02 370950 + 304 370960 Rb-96 2.95630E-03 4.54110E-03 370960 + 305 370961 Rb-96m 2.95630E-03 3.02740E-03 370961 + 306 370970 Rb-97 2.43850E-03 2.45300E-03 370970 + 307 370980 Rb-98 2.17140E-04 2.17140E-04 370980 + 308 370981 Rb-98m 2.17140E-04 2.18830E-04 370981 + 309 370990 Rb-99 9.36430E-05 9.36460E-05 370990 + 310 371000 Rb-100 5.02530E-06 5.02530E-06 371000 + 311 371010 Rb-101 1.03940E-06 1.03940E-06 371010 + 312 380870 Sr-87 8.61960E-10 9.69910E-10 38087.82c + 313 380871 Sr-87m 1.08280E-10 1.08280E-10 380871 + 314 380880 Sr-88 2.96250E-06 2.11410E-02 38088.82c + 315 380890 Sr-89 1.09430E-05 2.75360E-02 38089.82c + 316 380900 Sr-90 1.47460E-04 3.13330E-02 38090.82c + 317 380910 Sr-91 9.00130E-04 3.65740E-02 380910 + 318 380920 Sr-92 3.82210E-03 3.83380E-02 380920 + 319 380930 Sr-93 9.07000E-03 4.51840E-02 380930 + 320 380940 Sr-94 2.14520E-02 4.59690E-02 380940 + 321 380950 Sr-95 2.62160E-02 4.19490E-02 380950 + 322 380960 Sr-96 3.59590E-02 4.20210E-02 380960 + 323 380970 Sr-97 2.64800E-02 2.83470E-02 380970 + 324 380980 Sr-98 1.68990E-02 1.73200E-02 380980 + 325 380990 Sr-99 5.05260E-03 5.13160E-03 380990 + 326 381000 Sr-100 1.55510E-03 1.55980E-03 381000 + 327 381010 Sr-101 2.29190E-04 2.30230E-04 381010 + 328 381020 Sr-102 3.28380E-05 3.28380E-05 381020 + 329 381030 Sr-103 2.02930E-06 2.02930E-06 381030 + 330 381040 Sr-104 5.45260E-09 5.45260E-09 381040 + 331 390900 Y-90 1.95150E-09 3.13330E-02 39090.82c + 332 390901 Y-90m 5.57750E-09 5.57750E-09 390901 + 333 390910 Y-91 2.31410E-07 3.65760E-02 39091.82c + 334 390911 Y-91m 1.84220E-06 2.15210E-02 390911 + 335 390920 Y-92 2.34310E-05 3.83620E-02 390920 + 336 390930 Y-93 1.94140E-05 4.54360E-02 390930 + 337 390931 Y-93m 2.33050E-04 1.15400E-02 390931 + 338 390940 Y-94 1.04760E-03 4.70170E-02 390940 + 339 390950 Y-95 4.23420E-03 4.61830E-02 390950 + 340 390960 Y-96 1.84060E-03 4.38690E-02 390960 + 341 390961 Y-96m 6.43930E-03 6.44640E-03 390961 + 342 390970 Y-97 2.11480E-03 2.63690E-02 390970 + 343 390971 Y-97m 9.79340E-03 1.96430E-02 390971 + 344 390972 Y-97m 7.04180E-03 7.04180E-03 390972 + 345 390980 Y-98 2.73690E-03 2.00570E-02 390980 + 346 390981 Y-98m 2.14620E-02 2.14620E-02 390981 + 347 390990 Y-99 3.30170E-02 3.81610E-02 390990 + 348 391000 Y-100 1.01210E-02 1.16710E-02 391000 + 349 391001 Y-100m 1.01210E-02 1.01240E-02 391001 + 350 391010 Y-101 1.11690E-02 1.13960E-02 391010 + 351 391020 Y-102 1.07380E-03 1.08930E-03 391020 + 352 391021 Y-102m 1.07380E-03 1.08930E-03 391021 + 353 391030 Y-103 7.52380E-04 7.54410E-04 391030 + 354 391040 Y-104 9.00700E-05 9.00760E-05 391040 + 355 391050 Y-105 1.39140E-05 1.39140E-05 391050 + 356 391060 Y-106 2.06680E-08 2.06680E-08 391060 + 357 391070 Y-107 5.85200E-10 5.85200E-10 391070 + 358 400920 Zr-92 1.39060E-09 3.83620E-02 40092.82c + 359 400930 Zr-93 5.95520E-06 4.54420E-02 40093.82c + 360 400940 Zr-94 3.71430E-05 4.70540E-02 40094.82c + 361 400950 Zr-95 2.05340E-04 4.63890E-02 40095.82c + 362 400960 Zr-96 1.19450E-03 5.15250E-02 40096.82c + 363 400970 Zr-97 3.79670E-03 5.18560E-02 400970 + 364 400980 Zr-98 1.08190E-02 5.21940E-02 400980 + 365 400990 Zr-99 1.84430E-02 5.60620E-02 400990 + 366 401000 Zr-100 3.39340E-02 5.56220E-02 401000 + 367 401010 Zr-101 3.38090E-02 4.53110E-02 401010 + 368 401020 Zr-102 2.24110E-02 2.45430E-02 401020 + 369 401030 Zr-103 1.20630E-02 1.27650E-02 401030 + 370 401040 Zr-104 4.54470E-03 4.62960E-03 401040 + 371 401050 Zr-105 9.92320E-04 1.00350E-03 401050 + 372 401060 Zr-106 2.21350E-04 2.21370E-04 401060 + 373 401070 Zr-107 3.02910E-05 3.02920E-05 401070 + 374 401080 Zr-108 5.13870E-06 5.13870E-06 401080 + 375 401090 Zr-109 2.52110E-09 2.52110E-09 401090 + 376 410950 Nb-95 1.59620E-06 4.63620E-02 41095.82c + 377 410951 Nb-95m 2.00510E-07 5.01360E-04 410951 + 378 410960 Nb-96 1.72000E-06 1.72000E-06 410960 + 379 410970 Nb-97 4.98040E-05 5.19130E-02 410970 + 380 410971 Nb-97m 6.25630E-06 4.92950E-02 410971 + 381 410980 Nb-98 4.28480E-05 5.22370E-02 410980 + 382 410981 Nb-98m 2.42420E-04 2.42420E-04 410981 + 383 410990 Nb-99 1.44320E-03 3.72910E-02 410990 + 384 410991 Nb-99m 1.81290E-04 2.08120E-02 410991 + 385 411000 Nb-100 4.98630E-04 5.61200E-02 411000 + 386 411001 Nb-100m 3.91020E-03 3.91020E-03 411001 + 387 411010 Nb-101 1.17990E-02 5.71100E-02 411010 + 388 411020 Nb-102 6.22550E-03 3.07690E-02 411020 + 389 411021 Nb-102m 6.22550E-03 6.22550E-03 411021 + 390 411030 Nb-103 2.46370E-02 3.74020E-02 411030 + 391 411040 Nb-104 8.75450E-03 1.33980E-02 411040 + 392 411041 Nb-104m 8.75450E-03 8.75450E-03 411041 + 393 411050 Nb-105 1.36730E-02 1.46660E-02 411050 + 394 411060 Nb-106 5.15460E-03 5.37370E-03 411060 + 395 411070 Nb-107 1.99210E-03 2.02130E-03 411070 + 396 411080 Nb-108 5.71720E-04 5.76860E-04 411080 + 397 411090 Nb-109 1.92260E-04 1.92260E-04 411090 + 398 411100 Nb-110 3.69790E-05 3.69790E-05 411100 + 399 411110 Nb-111 5.79570E-06 5.79570E-06 411110 + 400 411120 Nb-112 1.29760E-05 1.29760E-05 411120 + 401 420970 Mo-97 1.36830E-09 5.19130E-02 42097.82c + 402 420980 Mo-98 6.34880E-06 5.24860E-02 42098.82c + 403 420990 Mo-99 2.59680E-05 5.77130E-02 42099.82c + 404 421000 Mo-100 2.80240E-04 6.03110E-02 42100.82c + 405 421010 Mo-101 1.03750E-03 5.81480E-02 421010 + 406 421020 Mo-102 2.90450E-03 3.98990E-02 421020 + 407 421030 Mo-103 7.19540E-03 4.46100E-02 421030 + 408 421040 Mo-104 1.27090E-02 3.50990E-02 421040 + 409 421050 Mo-105 1.34790E-02 2.81370E-02 421050 + 410 421060 Mo-106 1.44180E-02 1.96710E-02 421060 + 411 421070 Mo-107 7.14860E-03 9.08440E-03 421070 + 412 421080 Mo-108 5.20160E-03 5.76700E-03 421080 + 413 421090 Mo-109 2.14470E-03 2.32740E-03 421090 + 414 421100 Mo-110 9.24880E-04 9.47070E-04 421100 + 415 421110 Mo-111 2.16940E-04 2.22740E-04 421110 + 416 421120 Mo-112 9.43210E-05 1.07300E-04 421120 + 417 421130 Mo-113 1.12970E-05 1.12970E-05 421130 + 418 421140 Mo-114 1.04560E-05 1.04560E-05 421140 + 419 421150 Mo-115 1.13760E-06 1.13760E-06 421150 + 420 431000 Tc-100 4.45020E-09 4.45020E-09 431000 + 421 431010 Tc-101 6.23590E-06 5.81540E-02 431010 + 422 431020 Tc-102 1.52540E-05 3.99140E-02 431020 + 423 431021 Tc-102m 1.52540E-05 1.52540E-05 431021 + 424 431030 Tc-103 2.71590E-04 4.48810E-02 431030 + 425 431040 Tc-104 8.30010E-04 3.59290E-02 431040 + 426 431050 Tc-105 2.98340E-03 3.11210E-02 431050 + 427 431060 Tc-106 4.89730E-03 2.45690E-02 431060 + 428 431070 Tc-107 7.28780E-03 1.63720E-02 431070 + 429 431080 Tc-108 7.24980E-03 1.30290E-02 431080 + 430 431090 Tc-109 7.23810E-03 9.55320E-03 431090 + 431 431100 Tc-110 4.31900E-03 5.26840E-03 431100 + 432 431110 Tc-111 2.91760E-03 3.14030E-03 431110 + 433 431120 Tc-112 1.28780E-03 1.39290E-03 431120 + 434 431130 Tc-113 5.79630E-04 5.90930E-04 431130 + 435 431140 Tc-114 1.11880E-04 1.22340E-04 431140 + 436 431150 Tc-115 2.84930E-05 2.96310E-05 431150 + 437 431160 Tc-116 9.62450E-07 9.62450E-07 431160 + 438 431170 Tc-117 4.63830E-10 4.63830E-10 431170 + 439 441030 Ru-103 3.68930E-09 4.48810E-02 44103.82c + 440 441031 Ru-103m 1.69330E-08 1.69330E-08 441031 + 441 441040 Ru-104 1.51460E-05 3.59440E-02 44104.82c + 442 441050 Ru-105 1.02910E-04 3.12240E-02 44105.82c + 443 441060 Ru-106 3.76800E-04 2.49450E-02 44106.82c + 444 441070 Ru-107 7.72700E-04 1.71450E-02 441070 + 445 441080 Ru-108 2.33060E-03 1.53670E-02 441080 + 446 441090 Ru-109 3.52740E-03 1.30750E-02 441090 + 447 441100 Ru-110 5.81310E-03 1.10790E-02 441100 + 448 441110 Ru-111 5.14710E-03 8.30830E-03 441110 + 449 441120 Ru-112 6.25670E-03 7.67110E-03 441120 + 450 441130 Ru-113 1.81700E-03 3.28200E-03 441130 + 451 441131 Ru-113m 1.81700E-03 1.81700E-03 441131 + 452 441140 Ru-114 2.31190E-03 2.43050E-03 441140 + 453 441150 Ru-115 7.02730E-04 7.28230E-04 441150 + 454 441160 Ru-116 2.07930E-04 2.08770E-04 441160 + 455 441170 Ru-117 2.67540E-05 2.67540E-05 441170 + 456 441180 Ru-118 1.74290E-05 1.74290E-05 441180 + 457 441190 Ru-119 5.55190E-09 5.55190E-09 441190 + 458 441200 Ru-120 3.44560E-07 3.44560E-07 441200 + 459 451050 Rh-105 1.97330E-09 3.12240E-02 45105.82c + 460 451051 Rh-105m 1.64390E-10 8.86370E-03 451051 + 461 451060 Rh-106 1.80970E-07 2.49450E-02 451060 + 462 451061 Rh-106m 8.17230E-07 8.17230E-07 451061 + 463 451070 Rh-107 9.79870E-06 1.71550E-02 451070 + 464 451080 Rh-108 9.11370E-06 1.53760E-02 451080 + 465 451081 Rh-108m 5.15630E-05 5.15630E-05 451081 + 466 451090 Rh-109 2.36920E-04 1.33120E-02 451090 + 467 451100 Rh-110 5.05840E-04 1.15850E-02 451100 + 468 451101 Rh-110m 7.59890E-06 7.59890E-06 451101 + 469 451110 Rh-111 1.41050E-03 9.71880E-03 451110 + 470 451120 Rh-112 1.20510E-03 8.87620E-03 451120 + 471 451121 Rh-112m 1.20510E-03 1.20510E-03 451121 + 472 451130 Rh-113 4.37350E-03 8.56410E-03 451130 + 473 451140 Rh-114 2.39560E-03 4.82770E-03 451140 + 474 451141 Rh-114m 2.39560E-03 2.39560E-03 451141 + 475 451150 Rh-115 6.21170E-03 6.94050E-03 451150 + 476 451160 Rh-116 6.03710E-04 8.10780E-04 451160 + 477 451161 Rh-116m 2.72620E-03 2.72620E-03 451161 + 478 451170 Rh-117 1.80740E-03 1.83430E-03 451170 + 479 451180 Rh-118 7.09770E-04 7.26480E-04 451180 + 480 451190 Rh-119 2.54340E-04 2.54350E-04 451190 + 481 451200 Rh-120 3.91580E-05 3.95030E-05 451200 + 482 451210 Rh-121 1.76020E-05 1.76020E-05 451210 + 483 451220 Rh-122 1.30630E-06 1.30630E-06 451220 + 484 461080 Pd-108 5.88730E-09 1.54280E-02 46108.82c + 485 461090 Pd-109 4.92830E-07 1.33140E-02 461090 + 486 461091 Pd-109m 1.81660E-06 6.65780E-03 461091 + 487 461100 Pd-110 2.18920E-05 1.16150E-02 46110.82c + 488 461110 Pd-111 1.34400E-05 9.75790E-03 461110 + 489 461111 Pd-111m 4.95420E-05 8.84170E-05 461111 + 490 461120 Pd-112 2.27070E-04 1.03080E-02 461120 + 491 461130 Pd-113 1.00590E-04 9.12630E-03 461130 + 492 461131 Pd-113m 4.61660E-04 4.61660E-04 461131 + 493 461140 Pd-114 1.28500E-03 8.50830E-03 461140 + 494 461150 Pd-115 3.88280E-04 6.51620E-03 461150 + 495 461151 Pd-115m 1.43120E-03 2.43900E-03 461151 + 496 461160 Pd-116 2.88290E-03 6.41990E-03 461160 + 497 461170 Pd-117 8.61600E-04 5.89300E-03 461170 + 498 461171 Pd-117m 3.17590E-03 3.17590E-03 461171 + 499 461180 Pd-118 6.62990E-03 7.33520E-03 461180 + 500 461190 Pd-119 3.28030E-03 3.53700E-03 461190 + 501 461200 Pd-120 1.91450E-03 1.95410E-03 461200 + 502 461210 Pd-121 5.32120E-04 5.47330E-04 461210 + 503 461220 Pd-122 2.32350E-04 2.33660E-04 461220 + 504 461230 Pd-123 5.11360E-05 5.11360E-05 461230 + 505 461240 Pd-124 1.62280E-05 1.62280E-05 461240 + 506 471100 Ag-110 4.90090E-11 5.20190E-11 471100 + 507 471101 Ag-110m 2.21310E-10 2.21310E-10 47510.82c + 508 471110 Ag-111 1.19060E-09 9.73320E-03 47111.82c + 509 471111 Ag-111m 1.42910E-08 9.70610E-03 471111 + 510 471120 Ag-112 2.59380E-06 1.03110E-02 471120 + 511 471130 Ag-113 8.65430E-07 5.98770E-03 471130 + 512 471131 Ag-113m 1.03890E-05 8.74950E-03 471131 + 513 471140 Ag-114 4.65680E-06 8.54950E-03 471140 + 514 471141 Ag-114m 3.65170E-05 3.65170E-05 471141 + 515 471150 Ag-115 1.86850E-05 5.66330E-03 471150 + 516 471151 Ag-115m 2.24300E-04 4.22750E-03 471151 + 517 471160 Ag-116 8.41700E-05 6.52680E-03 471160 + 518 471161 Ag-116m 3.80090E-04 3.80090E-04 471161 + 519 471170 Ag-117 7.51790E-05 3.25260E-03 471170 + 520 471171 Ag-117m 9.02440E-04 3.84890E-03 471171 + 521 471180 Ag-118 3.42960E-04 8.16210E-03 471180 + 522 471181 Ag-118m 2.68940E-03 3.73810E-03 471181 + 523 471190 Ag-119 3.94600E-04 2.16310E-03 471190 + 524 471191 Ag-119m 4.73670E-03 6.50520E-03 471191 + 525 471200 Ag-120 1.27130E-03 3.95570E-03 471200 + 526 471201 Ag-120m 3.63340E-03 4.61040E-03 471201 + 527 471210 Ag-121 5.31740E-03 5.86320E-03 471210 + 528 471220 Ag-122 1.01740E-03 1.25110E-03 471220 + 529 471221 Ag-122m 1.94880E-03 1.94880E-03 471221 + 530 471230 Ag-123 2.00580E-03 2.05690E-03 471230 + 531 471240 Ag-124 2.32770E-04 4.71930E-04 471240 + 532 471241 Ag-124m 4.45870E-04 4.45870E-04 471241 + 533 471250 Ag-125 2.85230E-04 2.85230E-04 471250 + 534 471260 Ag-126 9.43390E-05 9.43390E-05 471260 + 535 471270 Ag-127 1.69040E-05 1.69040E-05 471270 + 536 471280 Ag-128 5.32550E-06 5.32550E-06 471280 + 537 471290 Ag-129 7.21880E-09 7.21880E-09 471290 + 538 481130 Cd-113 1.97180E-10 9.03420E-03 48113.82c + 539 481131 Cd-113m 1.21830E-09 1.03520E-04 481131 + 540 481140 Cd-114 6.54990E-08 8.54960E-03 48114.82c + 541 481150 Cd-115 3.16660E-07 8.57980E-03 481150 + 542 481151 Cd-115m 1.95650E-06 4.25520E-04 48515.82c + 543 481160 Cd-116 1.43450E-05 6.89850E-03 48116.82c + 544 481170 Cd-117 1.49080E-05 5.43870E-03 481170 + 545 481171 Cd-117m 9.21120E-05 1.53900E-03 481171 + 546 481180 Cd-118 6.88870E-04 1.10570E-02 481180 + 547 481190 Cd-119 2.48920E-04 7.83570E-03 481190 + 548 481191 Cd-119m 1.14250E-03 2.22410E-03 481191 + 549 481200 Cd-120 3.09060E-03 9.95070E-03 481200 + 550 481210 Cd-121 7.08340E-04 5.95900E-03 481210 + 551 481211 Cd-121m 3.25110E-03 3.86370E-03 481211 + 552 481220 Cd-122 5.82280E-03 9.02270E-03 481220 + 553 481230 Cd-123 8.81120E-04 2.56430E-03 481230 + 554 481231 Cd-123m 4.04410E-03 4.41830E-03 481231 + 555 481240 Cd-124 5.19980E-03 5.89420E-03 481240 + 556 481250 Cd-125 5.06540E-04 6.49150E-04 481250 + 557 481251 Cd-125m 2.32490E-03 2.46750E-03 481251 + 558 481260 Cd-126 1.96280E-03 2.05710E-03 481260 + 559 481270 Cd-127 8.00020E-04 8.16920E-04 481270 + 560 481280 Cd-128 3.36630E-04 3.41960E-04 481280 + 561 481290 Cd-129 1.71180E-05 1.71210E-05 481290 + 562 481291 Cd-129m 7.85660E-05 7.85700E-05 481291 + 563 481300 Cd-130 1.46560E-05 1.46560E-05 481300 + 564 481310 Cd-131 8.62130E-07 8.62130E-07 481310 + 565 481320 Cd-132 5.35440E-09 5.35440E-09 481320 + 566 491150 In-115 2.46020E-10 8.57630E-03 49115.82c + 567 491151 In-115m 3.09040E-11 8.57980E-03 491151 + 568 491160 In-116 7.76560E-10 7.76560E-10 491160 + 569 491161 In-116m 1.44040E-09 4.39360E-09 491161 + 570 491162 In-116m 2.95320E-09 2.95320E-09 491162 + 571 491170 In-117 1.75730E-07 4.32880E-03 491170 + 572 491171 In-117m 2.20760E-08 5.00760E-03 491171 + 573 491180 In-118 1.18570E-06 1.10580E-02 491180 + 574 491181 In-118m 2.19920E-06 6.64500E-06 491181 + 575 491182 In-118m 4.50890E-06 4.50890E-06 491182 + 576 491190 In-119 5.28310E-05 3.43060E-03 491190 + 577 491191 In-119m 6.63660E-06 7.08550E-03 491191 + 578 491200 In-120 5.72080E-05 1.00080E-02 491200 + 579 491201 In-120m 5.72080E-05 5.72080E-05 491201 + 580 491202 In-120m 5.72080E-05 5.72080E-05 491202 + 581 491210 In-121 6.91240E-04 6.61040E-03 491210 + 582 491211 In-121m 8.68330E-05 4.03880E-03 491211 + 583 491220 In-122 4.21100E-04 9.44380E-03 491220 + 584 491221 In-122m 6.01750E-04 6.01750E-04 491221 + 585 491222 In-122m 6.01750E-04 6.01750E-04 491222 + 586 491230 In-123 3.22050E-03 8.37920E-03 491230 + 587 491231 In-123m 4.04560E-04 2.22850E-03 491231 + 588 491240 In-124 1.67010E-03 7.56430E-03 491240 + 589 491241 In-124m 3.19890E-03 3.19890E-03 491241 + 590 491250 In-125 6.62310E-03 9.40130E-03 491250 + 591 491251 In-125m 8.31990E-04 1.17040E-03 491251 + 592 491260 In-126 2.15990E-03 4.21700E-03 491260 + 593 491261 In-126m 4.13710E-03 4.13710E-03 491261 + 594 491270 In-127 5.70660E-03 5.70660E-03 491270 + 595 491271 In-127m 7.16860E-04 1.53380E-03 491271 + 596 491280 In-128 1.02210E-03 1.72510E-03 491280 + 597 491281 In-128m 3.61010E-04 7.02960E-04 491281 + 598 491282 In-128m 2.65010E-03 2.65010E-03 491282 + 599 491290 In-129 2.39350E-03 2.47230E-03 491290 + 600 491291 In-129m 3.00670E-04 3.18050E-04 491291 + 601 491300 In-130 2.07730E-04 2.21900E-04 491300 + 602 491301 In-130m 6.73240E-04 6.73240E-04 491301 + 603 491302 In-130m 5.02030E-04 5.02030E-04 491302 + 604 491310 In-131 1.83590E-04 1.86290E-04 491310 + 605 491311 In-131m 1.83590E-04 1.83590E-04 491311 + 606 491312 In-131m 1.83590E-04 1.83590E-04 491312 + 607 491320 In-132 6.12860E-05 6.12880E-05 491320 + 608 491330 In-133 4.94630E-06 5.56770E-06 491330 + 609 491331 In-133m 6.21360E-07 6.21360E-07 491331 + 610 491340 In-134 3.50750E-08 3.50750E-08 491340 + 611 491350 In-135 1.84050E-09 1.84050E-09 491350 + 612 501180 Sn-118 1.63940E-09 1.10640E-02 50118.82c + 613 501190 Sn-119 2.30460E-07 1.01210E-02 50119.82c + 614 501191 Sn-119m 1.42390E-06 3.10060E-03 501191 + 615 501200 Sn-120 6.73750E-06 1.01290E-02 50120.82c + 616 501210 Sn-121 4.07340E-06 1.04520E-02 501210 + 617 501211 Sn-121m 1.86960E-05 7.67540E-04 501211 + 618 501220 Sn-122 1.38040E-04 1.07850E-02 50122.82c + 619 501230 Sn-123 2.70280E-04 9.09130E-04 50123.82c + 620 501231 Sn-123m 5.88880E-05 1.00280E-02 501231 + 621 501240 Sn-124 1.11310E-03 1.18760E-02 50124.82c + 622 501250 Sn-125 1.77620E-03 3.36430E-03 50125.82c + 623 501251 Sn-125m 3.87000E-04 9.37070E-03 501251 + 624 501260 Sn-126 4.94410E-03 1.33090E-02 50126.82c + 625 501270 Sn-127 5.18000E-03 7.40430E-03 501270 + 626 501271 Sn-127m 1.12860E-03 6.13410E-03 501271 + 627 501280 Sn-128 1.90750E-03 1.48960E-02 501280 + 628 501281 Sn-128m 8.61350E-03 1.12640E-02 501281 + 629 501290 Sn-129 1.69480E-03 4.22210E-03 501290 + 630 501291 Sn-129m 7.77840E-03 8.04160E-03 501291 + 631 501300 Sn-130 2.57750E-03 3.23910E-03 501300 + 632 501301 Sn-130m 1.16400E-02 1.23790E-02 501301 + 633 501310 Sn-131 1.90850E-03 2.26480E-03 501310 + 634 501311 Sn-131m 8.75950E-03 8.95110E-03 501311 + 635 501320 Sn-132 6.56300E-03 6.62900E-03 501320 + 636 501330 Sn-133 1.07190E-03 1.07280E-03 501330 + 637 501340 Sn-134 2.40680E-04 2.40690E-04 501340 + 638 501350 Sn-135 2.21380E-05 2.21400E-05 501350 + 639 501360 Sn-136 4.75180E-06 4.75180E-06 501360 + 640 501370 Sn-137 7.50620E-09 7.50620E-09 501370 + 641 511220 Sb-122 5.12020E-07 1.69430E-06 511220 + 642 511221 Sb-122m 1.18230E-06 1.18230E-06 511221 + 643 511230 Sb-123 7.91870E-06 1.09450E-02 51123.82c + 644 511240 Sb-124 4.90910E-06 1.77890E-05 51124.82c + 645 511241 Sb-124m 4.56010E-06 1.71740E-05 511241 + 646 511242 Sb-124m 1.26140E-05 1.26140E-05 511242 + 647 511250 Sb-125 9.01830E-05 1.28250E-02 51125.82c + 648 511260 Sb-126 1.52190E-04 1.68190E-04 51126.82c + 649 511261 Sb-126m 5.50200E-05 1.14250E-04 511261 + 650 511262 Sb-126m 5.92300E-05 5.92300E-05 511262 + 651 511270 Sb-127 8.87010E-04 1.44260E-02 511270 + 652 511280 Sb-128 9.74920E-04 1.58970E-02 511280 + 653 511281 Sb-128m 7.31880E-04 7.31880E-04 511281 + 654 511290 Sb-129 1.89660E-03 1.11290E-02 511290 + 655 511291 Sb-129m 2.57540E-03 6.59620E-03 511291 + 656 511300 Sb-130 4.11210E-03 1.35410E-02 511300 + 657 511301 Sb-130m 4.11210E-03 1.03010E-02 511301 + 658 511310 Sb-131 1.98490E-02 3.10650E-02 511310 + 659 511320 Sb-132 9.09540E-03 1.57240E-02 511320 + 660 511321 Sb-132m 1.44620E-02 1.44620E-02 511321 + 661 511330 Sb-133 2.49360E-02 2.60500E-02 511330 + 662 511340 Sb-134 1.28460E-03 1.48670E-03 511340 + 663 511341 Sb-134m 5.80100E-03 5.80330E-03 511341 + 664 511350 Sb-135 2.55800E-03 2.57690E-03 511350 + 665 511360 Sb-136 6.09490E-04 6.12820E-04 511360 + 666 511370 Sb-137 1.27630E-04 1.27630E-04 511370 + 667 511380 Sb-138 9.30300E-06 9.30300E-06 511380 + 668 511390 Sb-139 3.23900E-06 3.23900E-06 511390 + 669 521240 Te-124 1.47130E-06 2.35540E-05 52124.82c + 670 521250 Te-125 1.76630E-07 1.28260E-02 52125.82c + 671 521251 Te-125m 1.09140E-06 2.87090E-03 521251 + 672 521260 Te-126 6.58740E-06 2.73030E-04 52126.82c + 673 521270 Te-127 3.66120E-06 1.43890E-02 521270 + 674 521271 Te-127m 1.68040E-05 2.39400E-03 52527.82c + 675 521280 Te-128 1.14720E-04 1.67180E-02 52128.82c + 676 521290 Te-129 5.99830E-05 1.42600E-02 521290 + 677 521291 Te-129m 2.75310E-04 7.59750E-03 52529.82c + 678 521300 Te-130 1.72670E-03 2.55690E-02 52130.82c + 679 521310 Te-131 9.31530E-04 3.09290E-02 521310 + 680 521311 Te-131m 4.27550E-03 6.76260E-03 521311 + 681 521320 Te-132 1.60470E-02 4.62330E-02 52132.82c + 682 521330 Te-133 4.76550E-03 3.09300E-02 521330 + 683 521331 Te-133m 2.18720E-02 2.63790E-02 521331 + 684 521340 Te-134 4.40610E-02 5.17520E-02 521340 + 685 521350 Te-135 2.37610E-02 2.60330E-02 521350 + 686 521360 Te-136 1.77530E-02 1.83270E-02 521360 + 687 521370 Te-137 4.94860E-03 5.01370E-03 521370 + 688 521380 Te-138 1.63030E-03 1.63960E-03 521380 + 689 521390 Te-139 1.91000E-04 1.94240E-04 521390 + 690 521400 Te-140 6.30360E-05 6.30360E-05 521400 + 691 521410 Te-141 5.35950E-06 5.35950E-06 521410 + 692 521420 Te-142 1.05330E-06 1.05330E-06 521420 + 693 531280 I-128 7.60850E-07 7.60850E-07 531280 + 694 531290 I-129 2.51460E-06 1.70730E-02 53129.82c + 695 531300 I-130 1.62040E-05 1.92180E-05 53130.82c + 696 531301 I-130m 3.58830E-06 3.58830E-06 531301 + 697 531310 I-131 2.14360E-04 3.64860E-02 53131.82c + 698 531320 I-132 3.52450E-04 4.70670E-02 531320 + 699 531321 I-132m 5.60400E-04 5.60400E-04 531321 + 700 531330 I-133 2.02200E-03 5.74610E-02 531330 + 701 531331 I-133m 2.74570E-03 2.74570E-03 531331 + 702 531340 I-134 4.13740E-03 6.23170E-02 531340 + 703 531341 I-134m 6.57850E-03 6.57850E-03 531341 + 704 531350 I-135 2.44150E-02 5.04480E-02 53135.82c + 705 531360 I-136 4.83530E-03 2.32370E-02 531360 + 706 531361 I-136m 2.18350E-02 2.19100E-02 531361 + 707 531370 I-137 2.97600E-02 3.47270E-02 531370 + 708 531380 I-138 1.15350E-02 1.30710E-02 531380 + 709 531390 I-139 1.15090E-02 1.17030E-02 531390 + 710 531400 I-140 2.62980E-03 2.69280E-03 531400 + 711 531410 I-141 1.08180E-03 1.08720E-03 531410 + 712 531420 I-142 1.57580E-04 1.58630E-04 531420 + 713 531430 I-143 2.70470E-05 2.70470E-05 531430 + 714 531440 I-144 1.10020E-06 1.10020E-06 531440 + 715 541300 Xe-130 7.33430E-07 2.05250E-05 54130.82c + 716 541310 Xe-131 1.54240E-07 3.64870E-02 54131.82c + 717 541311 Xe-131m 7.07900E-07 3.97020E-04 541311 + 718 541320 Xe-132 6.53450E-06 4.71680E-02 54132.82c + 719 541321 Xe-132m 1.50880E-05 1.50880E-05 541321 + 720 541330 Xe-133 3.31720E-05 5.76460E-02 54133.82c + 721 541331 Xe-133m 1.52250E-04 1.78780E-03 541331 + 722 541340 Xe-134 2.16630E-04 6.36630E-02 54134.82c + 723 541341 Xe-134m 9.78270E-04 1.12960E-03 541341 + 724 541350 Xe-135 7.53760E-04 5.45910E-02 54135.82c + 725 541351 Xe-135m 3.45950E-03 1.17880E-02 541351 + 726 541360 Xe-136 1.37230E-02 6.11270E-02 54136.82c + 727 541370 Xe-137 1.87260E-02 5.18890E-02 541370 + 728 541380 Xe-138 2.83650E-02 4.18900E-02 541380 + 729 541390 Xe-139 2.68010E-02 3.76080E-02 541390 + 730 541400 Xe-140 2.85920E-02 3.12630E-02 541400 + 731 541410 Xe-141 1.50530E-02 1.59520E-02 541410 + 732 541420 Xe-142 8.34310E-03 8.47290E-03 541420 + 733 541430 Xe-143 1.94870E-03 1.96540E-03 541430 + 734 541440 Xe-144 5.59020E-04 5.59680E-04 541440 + 735 541450 Xe-145 7.89780E-05 7.89780E-05 541450 + 736 541460 Xe-146 2.27680E-05 2.27680E-05 541460 + 737 541470 Xe-147 2.46910E-06 2.46910E-06 541470 + 738 551330 Cs-133 5.74820E-09 5.76460E-02 55133.82c + 739 551340 Cs-134 1.35800E-06 3.51730E-06 55134.82c + 740 551341 Cs-134m 2.15930E-06 2.15930E-06 551341 + 741 551350 Cs-135 1.76590E-05 5.47030E-02 55135.82c + 742 551351 Cs-135m 2.39790E-05 2.39790E-05 551351 + 743 551360 Cs-136 1.65490E-04 2.75720E-04 55136.82c + 744 551361 Cs-136m 2.20450E-04 2.20450E-04 551361 + 745 551370 Cs-137 2.47070E-03 5.43590E-02 55137.82c + 746 551380 Cs-138 1.22120E-03 4.59390E-02 551380 + 747 551381 Cs-138m 3.49010E-03 3.49010E-03 551381 + 748 551390 Cs-139 1.03330E-02 4.79410E-02 551390 + 749 551400 Cs-140 1.14110E-02 4.26810E-02 551400 + 750 551410 Cs-141 2.14720E-02 3.74470E-02 551410 + 751 551420 Cs-142 1.80520E-02 2.65140E-02 551420 + 752 551430 Cs-143 1.64000E-02 1.83630E-02 551430 + 753 551440 Cs-144 3.44120E-03 5.70770E-03 551440 + 754 551441 Cs-144m 3.44120E-03 3.44320E-03 551441 + 755 551450 Cs-145 3.38830E-03 3.46490E-03 551450 + 756 551460 Cs-146 9.07580E-04 9.28880E-04 551460 + 757 551470 Cs-147 2.31960E-04 2.34330E-04 551470 + 758 551480 Cs-148 1.76640E-05 1.76640E-05 551480 + 759 551490 Cs-149 3.75250E-06 3.75250E-06 551490 + 760 551500 Cs-150 1.15620E-09 1.15620E-09 551500 + 761 561360 Ba-136 8.61230E-07 3.90700E-04 56136.82c + 762 561361 Ba-136m 3.88910E-06 3.88910E-06 561361 + 763 561370 Ba-137 6.46870E-06 5.43950E-02 56137.82c + 764 561371 Ba-137m 2.96890E-05 5.13450E-02 561371 + 765 561380 Ba-138 3.79490E-04 4.69810E-02 56138.82c + 766 561390 Ba-139 1.34080E-03 4.92820E-02 561390 + 767 561400 Ba-140 3.75680E-03 4.64370E-02 56140.82c + 768 561410 Ba-141 6.47290E-03 4.39200E-02 561410 + 769 561420 Ba-142 1.46350E-02 4.14500E-02 561420 + 770 561430 Ba-143 1.80080E-02 3.62520E-02 561430 + 771 561440 Ba-144 2.34230E-02 3.11650E-02 561440 + 772 561450 Ba-145 1.58730E-02 1.89740E-02 561450 + 773 561460 Ba-146 1.17600E-02 1.26240E-02 561460 + 774 561470 Ba-147 4.34600E-03 4.51800E-03 561470 + 775 561480 Ba-148 1.49760E-03 1.51080E-03 561480 + 776 561490 Ba-149 3.30250E-04 3.34000E-04 561490 + 777 561500 Ba-150 8.78810E-05 8.78820E-05 561500 + 778 561510 Ba-151 7.35220E-06 7.35220E-06 561510 + 779 561520 Ba-152 8.33020E-09 8.33020E-09 561520 + 780 561530 Ba-153 1.05690E-10 1.05690E-10 561530 + 781 571380 La-138 2.78990E-06 2.78990E-06 57138.82c + 782 571390 La-139 1.18730E-05 4.92930E-02 57139.82c + 783 571400 La-140 4.32190E-05 4.64810E-02 57140.82c + 784 571410 La-141 2.52430E-04 4.41720E-02 571410 + 785 571420 La-142 6.08210E-04 4.20580E-02 571420 + 786 571430 La-143 2.43100E-03 3.86830E-02 571430 + 787 571440 La-144 4.53790E-03 3.57030E-02 571440 + 788 571450 La-145 9.45170E-03 2.84260E-02 571450 + 789 571460 La-146 2.13760E-03 1.47610E-02 571460 + 790 571461 La-146m 7.47810E-03 7.47810E-03 571461 + 791 571470 La-147 1.06270E-02 1.51510E-02 571470 + 792 571480 La-148 5.06400E-03 6.57020E-03 571480 + 793 571490 La-149 3.97320E-03 4.30580E-03 571490 + 794 571500 La-150 1.42080E-03 1.50870E-03 571500 + 795 571510 La-151 4.54410E-04 4.61760E-04 571510 + 796 571520 La-152 9.36750E-05 9.36830E-05 571520 + 797 571530 La-153 7.12400E-06 7.12410E-06 571530 + 798 571540 La-154 1.53950E-06 1.53950E-06 571540 + 799 571550 La-155 4.56570E-10 4.56570E-10 571550 + 800 581410 Ce-141 2.14350E-06 4.41740E-02 58141.82c + 801 581420 Ce-142 2.63460E-05 4.20850E-02 58142.82c + 802 581430 Ce-143 8.66660E-05 3.87700E-02 58143.82c + 803 581440 Ce-144 4.43850E-04 3.61470E-02 58144.82c + 804 581450 Ce-145 1.36030E-03 2.97860E-02 581450 + 805 581460 Ce-146 3.92920E-03 2.61690E-02 581460 + 806 581470 Ce-147 6.08890E-03 2.12400E-02 581470 + 807 581480 Ce-148 7.64940E-03 1.42800E-02 581480 + 808 581490 Ce-149 8.14670E-03 1.24330E-02 581490 + 809 581500 Ce-150 7.67420E-03 9.14210E-03 581500 + 810 581510 Ce-151 3.56750E-03 4.03490E-03 581510 + 811 581520 Ce-152 1.88340E-03 1.97140E-03 581520 + 812 581530 Ce-153 4.28390E-04 4.35510E-04 581530 + 813 581540 Ce-154 1.35200E-04 1.36740E-04 581540 + 814 581550 Ce-155 1.21130E-05 1.21140E-05 581550 + 815 581560 Ce-156 6.80990E-08 6.80990E-08 581560 + 816 581570 Ce-157 1.09700E-09 1.09700E-09 581570 + 817 591430 Pr-143 1.31290E-09 3.87700E-02 59143.82c + 818 591440 Pr-144 1.62380E-09 3.61470E-02 591440 + 819 591441 Pr-144m 2.62760E-08 4.98830E-04 591441 + 820 591450 Pr-145 5.97860E-06 2.97920E-02 591450 + 821 591460 Pr-146 4.30910E-05 2.62120E-02 591460 + 822 591470 Pr-147 2.28640E-04 2.14690E-02 591470 + 823 591480 Pr-148 5.41760E-05 1.43340E-02 591480 + 824 591481 Pr-148m 4.24830E-04 4.24830E-04 591481 + 825 591490 Pr-149 1.51800E-03 1.39510E-02 591490 + 826 591500 Pr-150 2.46790E-03 1.16100E-02 591500 + 827 591510 Pr-151 3.49480E-03 7.52970E-03 591510 + 828 591520 Pr-152 2.73520E-03 4.70930E-03 591520 + 829 591530 Pr-153 1.83450E-03 2.26820E-03 591530 + 830 591540 Pr-154 8.30550E-04 9.66420E-04 591540 + 831 591550 Pr-155 3.27510E-04 3.39620E-04 591550 + 832 591560 Pr-156 7.85680E-05 7.86360E-05 591560 + 833 591570 Pr-157 1.50510E-05 1.50520E-05 591570 + 834 591580 Pr-158 8.92130E-08 8.92130E-08 591580 + 835 591590 Pr-159 3.91790E-09 3.91790E-09 591590 + 836 601460 Nd-146 1.26470E-06 2.62130E-02 60146.82c + 837 601470 Nd-147 3.70450E-06 2.14720E-02 60147.82c + 838 601480 Nd-148 2.16150E-05 1.47810E-02 60148.82c + 839 601490 Nd-149 8.66460E-05 1.40380E-02 601490 + 840 601500 Nd-150 3.69540E-04 1.19800E-02 60150.82c + 841 601510 Nd-151 7.93930E-04 8.32370E-03 601510 + 842 601520 Nd-152 1.64520E-03 6.35450E-03 601520 + 843 601530 Nd-153 1.61750E-03 3.88570E-03 601530 + 844 601540 Nd-154 1.86030E-03 2.82670E-03 601540 + 845 601550 Nd-155 1.08310E-03 1.42490E-03 601550 + 846 601560 Nd-156 6.60640E-04 7.38100E-04 601560 + 847 601570 Nd-157 2.14640E-04 2.28730E-04 601570 + 848 601580 Nd-158 7.90250E-05 7.91140E-05 601580 + 849 601590 Nd-159 1.26080E-05 1.26120E-05 601590 + 850 601600 Nd-160 1.74410E-07 1.74410E-07 601600 + 851 601610 Nd-161 5.89350E-09 5.89350E-09 601610 + 852 611490 Pm-149 7.96110E-09 1.40380E-02 61149.82c + 853 611500 Pm-150 1.44390E-06 1.44390E-06 611500 + 854 611510 Pm-151 1.02760E-05 8.33390E-03 61151.82c + 855 611520 Pm-152 4.15810E-06 6.35870E-03 611520 + 856 611521 Pm-152m 1.00370E-05 1.00370E-05 611521 + 857 611522 Pm-152m 2.25700E-05 2.25700E-05 611522 + 858 611530 Pm-153 1.31520E-04 4.01720E-03 611530 + 859 611540 Pm-154 1.02100E-04 2.92880E-03 611540 + 860 611541 Pm-154m 1.02100E-04 1.02100E-04 611541 + 861 611550 Pm-155 3.10320E-04 1.73520E-03 611550 + 862 611560 Pm-156 3.23020E-04 1.06110E-03 611560 + 863 611570 Pm-157 2.95190E-04 5.23920E-04 611570 + 864 611580 Pm-158 2.06200E-04 2.85340E-04 611580 + 865 611590 Pm-159 1.14330E-04 1.26910E-04 611590 + 866 611600 Pm-160 2.70420E-05 2.72150E-05 611600 + 867 611610 Pm-161 4.79760E-06 4.80350E-06 611610 + 868 611620 Pm-162 1.49960E-06 1.49960E-06 611620 + 869 611630 Pm-163 1.47270E-08 1.47270E-08 611630 + 870 621510 Sm-151 4.45320E-10 8.33390E-03 62151.82c + 871 621520 Sm-152 1.78500E-08 6.39130E-03 62152.82c + 872 621530 Sm-153 5.09020E-07 4.02000E-03 62153.82c + 873 621531 Sm-153m 2.33630E-06 2.33630E-06 621531 + 874 621540 Sm-154 1.97770E-05 3.05070E-03 62154.82c + 875 621550 Sm-155 2.53280E-05 1.76050E-03 621550 + 876 621560 Sm-156 8.50640E-05 1.14620E-03 621560 + 877 621570 Sm-157 1.09840E-04 6.33770E-04 621570 + 878 621580 Sm-158 1.43110E-04 4.28470E-04 621580 + 879 621590 Sm-159 1.07250E-04 2.34210E-04 621590 + 880 621600 Sm-160 7.54270E-05 1.02570E-04 621600 + 881 621610 Sm-161 4.62660E-05 5.10700E-05 621610 + 882 621620 Sm-162 1.34930E-05 1.49930E-05 621620 + 883 621630 Sm-163 9.76920E-06 9.78390E-06 621630 + 884 621640 Sm-164 1.75920E-06 1.75920E-06 621640 + 885 621650 Sm-165 2.36220E-08 2.36220E-08 621650 + 886 631540 Eu-154 2.18370E-10 6.36650E-10 63154.82c + 887 631541 Eu-154m 4.18280E-10 4.18280E-10 631541 + 888 631550 Eu-155 1.71220E-08 1.76050E-03 63155.82c + 889 631560 Eu-156 1.59610E-07 1.14630E-03 63156.82c + 890 631570 Eu-157 2.72080E-06 6.36490E-04 63157.82c + 891 631580 Eu-158 8.03560E-06 4.36510E-04 631580 + 892 631590 Eu-159 2.21440E-05 2.56360E-04 631590 + 893 631600 Eu-160 1.32390E-05 1.15810E-04 631600 + 894 631610 Eu-161 2.70860E-05 7.81550E-05 631610 + 895 631620 Eu-162 1.94700E-05 3.44630E-05 631620 + 896 631630 Eu-163 1.46450E-05 2.44290E-05 631630 + 897 631640 Eu-164 1.40760E-05 1.58350E-05 631640 + 898 631650 Eu-165 5.76350E-06 5.78710E-06 631650 + 899 631660 Eu-166 1.33260E-07 1.33260E-07 631660 + 900 631670 Eu-167 5.58280E-08 5.58280E-08 631670 + 901 641560 Gd-156 4.17020E-11 1.14630E-03 64156.82c + 902 641570 Gd-157 6.91940E-10 6.36490E-04 64157.82c + 903 641580 Gd-158 1.80060E-08 4.36530E-04 64158.82c + 904 641590 Gd-159 1.39210E-06 2.57750E-04 641590 + 905 641600 Gd-160 5.52450E-06 1.21330E-04 64160.82c + 906 641610 Gd-161 3.19040E-06 8.13460E-05 641610 + 907 641620 Gd-162 1.49640E-05 4.94270E-05 641620 + 908 641630 Gd-163 8.13190E-06 3.25610E-05 641630 + 909 641640 Gd-164 7.03420E-06 2.28690E-05 641640 + 910 641650 Gd-165 5.76170E-06 1.15490E-05 641650 + 911 641660 Gd-166 4.48250E-06 4.61580E-06 641660 + 912 641670 Gd-167 4.87320E-06 4.92900E-06 641670 + 913 641680 Gd-168 1.16370E-07 1.16370E-07 641680 + 914 641690 Gd-169 2.19140E-08 2.19140E-08 641690 + 915 651590 Tb-159 4.28670E-11 2.57750E-04 65159.82c + 916 651600 Tb-160 4.91560E-10 4.91560E-10 65160.82c + 917 651610 Tb-161 1.00660E-08 8.13560E-05 651610 + 918 651620 Tb-162 5.83400E-08 4.94850E-05 651620 + 919 651630 Tb-163 4.43550E-07 3.30040E-05 651630 + 920 651640 Tb-164 1.75870E-06 2.46280E-05 651640 + 921 651650 Tb-165 3.84030E-06 1.53890E-05 651650 + 922 651660 Tb-166 1.57310E-06 6.18890E-06 651660 + 923 651670 Tb-167 3.24810E-06 8.17710E-06 651670 + 924 651680 Tb-168 1.07030E-06 1.18670E-06 651680 + 925 651690 Tb-169 5.78220E-07 6.00130E-07 651690 + 926 651700 Tb-170 9.64450E-08 9.64450E-08 651700 + 927 651710 Tb-171 2.51710E-08 2.51710E-08 651710 + 928 661620 Dy-162 4.06860E-11 4.94850E-05 66162.82c + 929 661630 Dy-163 5.61190E-10 3.30050E-05 66163.82c + 930 661640 Dy-164 1.06150E-08 2.46390E-05 66164.82c + 931 661650 Dy-165 4.76900E-08 1.54410E-05 661650 + 932 661651 Dy-165m 3.97290E-09 3.97290E-09 661651 + 933 661660 Dy-166 1.43040E-07 6.33190E-06 661660 + 934 661670 Dy-167 7.88100E-07 8.96520E-06 661670 + 935 661680 Dy-168 3.98680E-07 1.58530E-06 661680 + 936 661690 Dy-169 6.25580E-07 1.22570E-06 661690 + 937 661700 Dy-170 5.72080E-07 6.68520E-07 661700 + 938 661710 Dy-171 2.21900E-07 2.47070E-07 661710 + 939 661720 Dy-172 1.05310E-07 1.05310E-07 661720 + 940 661730 Dy-173 1.53680E-08 1.53680E-08 661730 + 941 671640 Ho-164 2.12030E-13 1.16950E-12 671640 + 942 671650 Ho-165 4.85710E-11 1.54410E-05 67165.82c + 943 671660 Ho-166 4.35680E-11 6.33190E-06 671660 + 944 671661 Ho-166m 1.96740E-10 1.96740E-10 671661 + 945 671670 Ho-167 8.87750E-09 8.97410E-06 671670 + 946 671680 Ho-168 1.93800E-09 1.59280E-06 671680 + 947 671681 Ho-168m 5.53870E-09 5.53870E-09 671681 + 948 671690 Ho-169 7.12830E-08 1.29700E-06 671690 + 949 671700 Ho-170 7.92990E-08 7.92990E-08 671700 + 950 671701 Ho-170m 1.75610E-08 6.86090E-07 671701 + 951 671710 Ho-171 2.05950E-07 4.53020E-07 671710 + 952 671720 Ho-172 1.37340E-07 2.42650E-07 671720 + 953 671730 Ho-173 1.11580E-07 1.26950E-07 671730 + 954 671740 Ho-174 3.32900E-08 3.32900E-08 671740 + 955 671750 Ho-175 1.38720E-08 1.38720E-08 671750 + 956 681670 Er-167 2.40110E-12 8.97410E-06 68167.82c + 957 681671 Er-167m 2.00020E-13 1.07230E-06 681671 + 958 681680 Er-168 1.49330E-11 1.59280E-06 68168.82c + 959 681690 Er-169 2.52550E-10 1.29720E-06 681690 + 960 681700 Er-170 2.26360E-09 7.67650E-07 68170.82c + 961 681710 Er-171 7.84160E-09 4.60860E-07 681710 + 962 681720 Er-172 3.10010E-08 2.73650E-07 681720 + 963 681730 Er-173 3.66360E-08 1.63580E-07 681730 + 964 681740 Er-174 5.93510E-08 9.26410E-08 681740 + 965 681750 Er-175 3.49900E-08 4.88620E-08 681750 + 966 681760 Er-176 2.35810E-08 2.35810E-08 681760 + 967 681770 Er-177 6.18280E-09 6.18280E-09 681770 + 968 691710 Tm-171 2.08420E-11 4.60880E-07 691710 + 969 691720 Tm-172 1.44160E-10 2.73790E-07 691720 + 970 691730 Tm-173 1.10310E-09 1.64690E-07 691730 + 971 691740 Tm-174 2.84440E-09 9.54850E-08 691740 + 972 691750 Tm-175 9.70320E-09 5.85650E-08 691750 + 973 691760 Tm-176 9.34860E-09 3.29300E-08 691760 + 974 691770 Tm-177 1.32710E-08 1.94540E-08 691770 + 975 691780 Tm-178 6.69700E-09 6.69700E-09 691780 + 976 691790 Tm-179 3.99180E-09 3.99180E-09 691790 + 977 701740 Yb-174 1.59800E-11 9.55010E-08 701740 + 978 701750 Yb-175 8.66960E-11 5.86590E-08 701750 + 979 701751 Yb-175m 7.22230E-12 4.51020E-08 701751 + 980 701760 Yb-176 1.27570E-10 3.18120E-08 701760 + 981 701761 Yb-176m 4.46280E-10 1.69110E-08 701761 + 982 701770 Yb-177 1.12410E-09 2.07190E-08 701770 + 983 701771 Yb-177m 1.41210E-10 1.95950E-08 701771 + 984 701780 Yb-178 3.61240E-09 1.03090E-08 701780 + 985 701790 Yb-179 3.04150E-09 7.03330E-09 701790 + 986 701800 Yb-180 3.26900E-09 3.26900E-09 701800 + 987 701810 Yb-181 1.45630E-09 1.45630E-09 701810 + 988 711770 Lu-177 4.75400E-12 2.07250E-08 711770 + 989 711771 Lu-177m 3.96060E-12 4.28150E-12 711771 + 990 711780 Lu-178 1.36640E-11 1.03230E-08 711780 + 991 711781 Lu-178m 3.15520E-11 3.15520E-11 711781 + 992 711790 Lu-179 2.17850E-10 7.26930E-09 711790 + 993 711791 Lu-179m 1.81480E-11 7.05150E-09 711791 + 994 711800 Lu-180 7.41930E-11 1.86380E-09 711800 + 995 711801 Lu-180m 7.41930E-11 3.34320E-09 711801 + 996 711802 Lu-180m 2.36000E-10 2.36000E-10 711802 + 997 711810 Lu-181 9.50540E-10 2.40680E-09 711810 + 998 711820 Lu-182 7.01340E-10 7.01340E-10 711820 + 999 711830 Lu-183 6.64110E-10 6.64110E-10 711830 + 1000 711840 Lu-184 2.34400E-10 2.34400E-10 711840 + 1001 721800 Hf-180 1.31930E-12 3.65890E-09 72180.82c + 1002 721801 Hf-180m 4.61560E-12 1.22610E-10 721801 + 1003 721810 Hf-181 2.43500E-11 2.43120E-09 721810 + 1004 721820 Hf-182 2.41710E-11 7.61030E-10 721820 + 1005 721821 Hf-182m 8.45590E-11 8.45590E-11 721821 + 1006 721830 Hf-183 1.52430E-10 8.16540E-10 721830 + 1007 721840 Hf-184 6.54300E-11 1.82630E-10 721840 + 1008 721841 Hf-184m 2.28900E-10 3.46100E-10 721841 + 1009 721850 Hf-185 1.91990E-10 1.91990E-10 721850 + 1010 721860 Hf-186 1.45910E-10 1.45910E-10 721860 + 1011 721870 Hf-187 4.53520E-11 4.53520E-11 721870 + 1012 721880 Hf-188 1.82900E-11 1.82900E-11 721880 + 1013 731830 Ta-183 3.05360E-12 8.19590E-10 731830 + 1014 731840 Ta-184 9.57130E-12 5.38300E-10 731840 + 1015 731850 Ta-185 1.72310E-11 2.28860E-10 731850 + 1016 731851 Ta-185m 1.96340E-11 1.96340E-11 731851 + 1017 731860 Ta-186 4.06260E-11 1.86540E-10 731860 + 1018 731870 Ta-187 6.84990E-11 1.13850E-10 731870 + 1019 731880 Ta-188 3.91530E-11 5.74430E-11 731880 + 1020 731890 Ta-189 2.62850E-11 2.62850E-11 731890 + 1021 731900 Ta-190 6.16300E-12 6.16300E-12 731900 + 1022 741860 W-186 9.23110E-13 1.88210E-10 74186.82c + 1023 741870 W-187 4.46970E-12 1.18320E-10 741870 + 1024 741880 W-188 1.47260E-11 7.21690E-11 741880 + 1025 741890 W-189 1.41000E-11 4.03850E-11 741890 + 1026 741900 W-190 5.41060E-12 2.40670E-11 741900 + 1027 741901 W-190m 1.24930E-11 1.24930E-11 741901 + 1028 741910 W-191 9.04790E-12 9.04790E-12 741910 + 1029 741920 W-192 5.25560E-12 5.25560E-12 741920 + 1030 751900 Re-190 3.23000E-13 2.49050E-11 751900 + 1031 751901 Re-190m 1.13000E-12 1.13000E-12 751901 + 1032 751910 Re-191 4.14040E-12 1.31880E-11 751910 + 1033 751920 Re-192 3.39230E-12 8.64790E-12 751920 + 1034 751930 Re-193 3.79010E-12 3.79010E-12 751930 + 1035 751940 Re-194 1.56850E-12 1.56850E-12 751940 + 1036 761940 Os-194 1.38560E-12 2.95410E-12 761940 + 1037 761950 Os-195 1.00010E-12 1.00010E-12 761950 + + Nuclide 93235.82c -- neptunium 235 (Np-235) is using NFY data from Th-232 + + Nuclide 93236.82c -- neptunium 236 (Np-236) is using NFY data from U-235 + + Nuclide 93237.82c -- neptunium 237 (Np-237) + + Neutron-induced fission: + + Interpolation region : 1 / 2 + Interpolation energy : 2.53000E-08 MeV + Number of products : 891 / 976 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 3.25860E-05 3.25860E-05 1001.82c + 2 10020 H-2 9.95850E-06 9.95850E-06 1002.82c + 3 10030 H-3 1.25000E-04 1.25000E-04 1003.82c + 4 20040 He-4 2.06000E-03 2.06000E-03 2004.82c + 5 230560 V-56 1.99070E-12 1.99070E-12 230560 + 6 230570 V-57 4.37760E-12 4.37760E-12 230570 + 7 230580 V-58 4.06940E-12 4.06940E-12 230580 + 8 230590 V-59 3.90360E-12 3.90360E-12 230590 + 9 230600 V-60 1.29800E-12 1.29800E-12 230600 + 10 240570 Cr-57 2.24330E-12 9.85890E-12 240570 + 11 240580 Cr-58 1.02530E-11 1.10670E-11 240580 + 12 240590 Cr-59 2.15620E-11 2.54660E-11 240590 + 13 240600 Cr-60 3.98390E-11 4.11370E-11 240600 + 14 240610 Cr-61 3.10710E-11 3.10710E-11 240610 + 15 240620 Cr-62 2.31390E-11 2.31390E-11 240620 + 16 240630 Cr-63 6.05160E-12 6.05160E-12 240630 + 17 240640 Cr-64 1.27300E-12 1.27300E-12 240640 + 18 250590 Mn-59 6.82640E-12 3.22920E-11 250590 + 19 250600 Mn-60 2.72950E-12 4.66540E-11 250600 + 20 250601 Mn-60m 2.42410E-11 2.42410E-11 250601 + 21 250610 Mn-61 1.04210E-10 1.35280E-10 250610 + 22 250620 Mn-62 1.49330E-10 1.60900E-10 250620 + 23 250621 Mn-62m 2.68080E-11 3.83780E-11 250621 + 24 250630 Mn-63 2.67300E-10 2.73350E-10 250630 + 25 250640 Mn-64 1.53270E-10 1.54540E-10 250640 + 26 250650 Mn-65 9.23480E-11 9.23480E-11 250650 + 27 250660 Mn-66 1.99490E-11 1.99490E-11 250660 + 28 250670 Mn-67 3.30310E-12 3.30310E-12 250670 + 29 260600 Fe-60 1.49460E-12 6.96030E-11 260600 + 30 260610 Fe-61 1.39340E-11 1.49220E-10 260610 + 31 260620 Fe-62 1.20890E-10 3.20170E-10 260620 + 32 260630 Fe-63 3.88080E-10 6.61430E-10 260630 + 33 260640 Fe-64 1.12630E-09 1.28080E-09 260640 + 34 260650 Fe-65 1.60450E-09 1.69680E-09 260650 + 35 260660 Fe-66 2.09690E-09 2.11690E-09 260660 + 36 260670 Fe-67 9.77190E-10 9.80490E-10 260670 + 37 260680 Fe-68 4.15810E-10 4.15810E-10 260680 + 38 260690 Fe-69 7.00600E-11 7.00600E-11 260690 + 39 260700 Fe-70 8.93190E-12 8.93190E-12 260700 + 40 270620 Co-62 4.80160E-13 3.20660E-10 270620 + 41 270621 Co-62m 1.12460E-12 1.12460E-12 270621 + 42 270630 Co-63 3.04940E-11 6.91930E-10 270630 + 43 270640 Co-64 2.04660E-10 1.48550E-09 270640 + 44 270650 Co-65 1.45670E-09 3.15360E-09 270650 + 45 270660 Co-66 4.04270E-09 6.15950E-09 270660 + 46 270670 Co-67 9.85060E-09 1.08310E-08 270670 + 47 270680 Co-68 5.49840E-09 8.13410E-09 270680 + 48 270681 Co-68m 4.85060E-09 5.27130E-09 270681 + 49 270690 Co-69 1.09570E-08 1.10220E-08 270690 + 50 270700 Co-70 2.02080E-09 2.02080E-09 270700 + 51 270701 Co-70m 2.02080E-09 2.02970E-09 270701 + 52 270710 Co-71 1.38930E-09 1.38930E-09 270710 + 53 270720 Co-72 2.15740E-10 2.15740E-10 270720 + 54 270730 Co-73 1.23760E-11 1.23760E-11 270730 + 55 280640 Ni-64 2.39510E-12 1.48790E-09 28064.82c + 56 280650 Ni-65 4.55960E-11 3.19910E-09 280650 + 57 280660 Ni-66 7.17620E-10 6.87720E-09 280660 + 58 280670 Ni-67 3.89220E-09 1.47230E-08 280670 + 59 280680 Ni-68 2.01390E-08 3.10190E-08 280680 + 60 280690 Ni-69 2.30560E-08 3.39680E-08 280690 + 61 280691 Ni-69m 2.30560E-08 2.30560E-08 280691 + 62 280700 Ni-70 9.25420E-08 9.65920E-08 280700 + 63 280710 Ni-71 8.19390E-08 8.33280E-08 280710 + 64 280720 Ni-72 8.46870E-07 8.47090E-07 280720 + 65 280730 Ni-73 1.40170E-08 1.40290E-08 280730 + 66 280740 Ni-74 6.23070E-09 6.23070E-09 280740 + 67 280750 Ni-75 7.97520E-11 7.97520E-11 280750 + 68 280760 Ni-76 4.95340E-11 4.95340E-11 280760 + 69 290660 Cu-66 1.91740E-12 6.87910E-09 290660 + 70 290670 Cu-67 6.74910E-11 1.47910E-08 290670 + 71 290680 Cu-68 2.68720E-10 3.18160E-08 290680 + 72 290681 Cu-68m 6.29400E-10 6.29400E-10 290681 + 73 290690 Cu-69 1.11720E-08 6.81970E-08 290690 + 74 290700 Cu-70 3.68660E-09 2.67290E-08 290700 + 75 290701 Cu-70m 4.10710E-08 4.60850E-08 290701 + 76 290702 Cu-70m 3.68660E-09 1.00280E-07 290702 + 77 290710 Cu-71 2.11320E-07 2.94650E-07 290710 + 78 290720 Cu-72 4.75140E-07 1.32220E-06 290720 + 79 290730 Cu-73 1.01810E-06 1.03210E-06 290730 + 80 290740 Cu-74 5.44760E-07 5.50990E-07 290740 + 81 290750 Cu-75 4.66030E-08 4.66820E-08 290750 + 82 290760 Cu-76 4.37590E-08 4.37840E-08 290760 + 83 290761 Cu-76m 4.37590E-08 4.37840E-08 290761 + 84 290770 Cu-77 7.47750E-09 7.47750E-09 290770 + 85 290780 Cu-78 9.43560E-10 9.43560E-10 290780 + 86 290790 Cu-79 5.93740E-11 5.93740E-11 290790 + 87 300680 Zn-68 2.03350E-12 3.19190E-08 300680 + 88 300690 Zn-69 1.37290E-11 6.82700E-08 300690 + 89 300691 Zn-69m 5.93740E-11 5.93740E-11 300691 + 90 300700 Zn-70 1.98930E-09 1.47030E-07 300700 + 91 300710 Zn-71 4.01740E-09 2.98670E-07 300710 + 92 300711 Zn-71m 1.73750E-08 1.73750E-08 300711 + 93 300720 Zn-72 2.51150E-07 1.57340E-06 300720 + 94 300730 Zn-73 5.07840E-08 1.34900E-06 300730 + 95 300731 Zn-73m 6.94240E-08 2.66070E-07 300731 + 96 300732 Zn-73m 3.93280E-07 3.93280E-07 300732 + 97 300740 Zn-74 3.74110E-06 4.29370E-06 300740 + 98 300750 Zn-75 1.09450E-06 1.14090E-06 300750 + 99 300760 Zn-76 4.69210E-06 4.77830E-06 300760 + 100 300770 Zn-77 2.71920E-06 2.93450E-06 300770 + 101 300771 Zn-77m 4.15690E-07 4.15690E-07 300771 + 102 300780 Zn-78 7.75270E-06 7.75370E-06 300780 + 103 300790 Zn-79 4.62720E-06 4.62720E-06 300790 + 104 300800 Zn-80 4.44450E-08 4.44450E-08 300800 + 105 300810 Zn-81 2.18920E-09 2.18920E-09 300810 + 106 300820 Zn-82 1.03540E-10 1.03540E-10 300820 + 107 310710 Ga-71 7.40370E-11 3.16110E-07 310710 + 108 310720 Ga-72 2.19660E-09 1.57580E-06 310720 + 109 310721 Ga-72m 2.47320E-10 5.26730E-08 310721 + 110 310730 Ga-73 3.01850E-08 1.57580E-06 310730 + 111 310740 Ga-74 2.12090E-07 3.59140E-06 310740 + 112 310741 Ga-74m 2.12090E-07 4.50580E-06 310741 + 113 310750 Ga-75 4.24910E-07 1.56580E-06 310750 + 114 310760 Ga-76 9.38450E-06 1.41630E-05 310760 + 115 310770 Ga-77 7.83700E-06 1.09790E-05 310770 + 116 310780 Ga-78 1.08540E-05 1.86680E-05 310780 + 117 310790 Ga-79 2.62180E-05 3.07850E-05 310790 + 118 310800 Ga-80 1.65630E-05 1.66080E-05 310800 + 119 310810 Ga-81 7.60550E-06 7.60750E-06 310810 + 120 310820 Ga-82 3.00230E-06 3.00240E-06 310820 + 121 310830 Ga-83 8.04970E-08 8.04970E-08 310830 + 122 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9.44490E-06 320850 + 142 320860 Ge-86 8.63610E-08 8.63610E-08 320860 + 143 320870 Ge-87 1.58350E-09 1.58350E-09 320870 + 144 330750 As-75 1.48540E-12 1.57560E-06 33075.82c + 145 330751 As-75m 4.85990E-12 2.62080E-11 330751 + 146 330760 As-76 2.58470E-09 2.58470E-09 330760 + 147 330770 As-77 4.69640E-08 1.72960E-05 330770 + 148 330780 As-78 1.55070E-06 6.52190E-05 330780 + 149 330790 As-79 1.23400E-05 1.46450E-04 330790 + 150 330800 As-80 6.62760E-05 3.41200E-04 330800 + 151 330810 As-81 2.54040E-04 5.95440E-04 330810 + 152 330820 As-82 1.61830E-04 5.31880E-04 330820 + 153 330821 As-82m 4.88360E-04 4.88360E-04 330821 + 154 330830 As-83 1.19450E-03 1.34780E-03 330830 + 155 330840 As-84 4.48800E-04 4.61960E-04 330840 + 156 330841 As-84m 4.48800E-04 4.61960E-04 330841 + 157 330850 As-85 7.30700E-04 7.38820E-04 330850 + 158 330860 As-86 1.82340E-04 1.82430E-04 330860 + 159 330870 As-87 5.65910E-05 5.65930E-05 330870 + 160 330880 As-88 5.72980E-06 5.72980E-06 330880 + 161 330890 As-89 2.78060E-08 2.78060E-08 330890 + 162 340770 Se-77 1.43330E-12 1.72960E-05 34077.82c + 163 340771 Se-77m 9.37570E-12 9.37570E-12 340771 + 164 340780 Se-78 2.06720E-09 6.52210E-05 34078.82c + 165 340790 Se-79 7.31160E-08 1.46450E-04 34079.82c + 166 340791 Se-79m 1.11770E-08 1.42990E-04 340791 + 167 340800 Se-80 7.53110E-06 3.48730E-04 34080.82c + 168 340810 Se-81 1.03080E-05 6.73130E-04 340810 + 169 340811 Se-81m 6.74300E-05 8.88050E-05 340811 + 170 340820 Se-82 4.43670E-04 1.46390E-03 34082.82c + 171 340830 Se-83 1.37400E-03 1.85990E-03 340830 + 172 340831 Se-83m 3.17700E-04 1.18100E-03 340831 + 173 340840 Se-84 4.79940E-03 5.88460E-03 340840 + 174 340850 Se-85 6.54410E-03 7.18060E-03 340850 + 175 340860 Se-86 6.16820E-03 6.29910E-03 340860 + 176 340870 Se-87 3.43540E-03 3.48330E-03 340870 + 177 340880 Se-88 1.36300E-03 1.36870E-03 340880 + 178 340890 Se-89 3.17830E-04 3.17860E-04 340890 + 179 340900 Se-90 7.00180E-05 7.00180E-05 340900 + 180 340910 Se-91 5.22120E-06 5.22120E-06 340910 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2.83610E-05 350930 + 201 350940 Br-94 6.54780E-08 6.54780E-08 350940 + 202 350950 Br-95 1.84220E-09 1.84220E-09 350950 + 203 360820 Kr-82 7.24780E-10 6.00710E-06 36082.82c + 204 360830 Kr-83 4.39040E-08 3.08920E-03 36083.82c + 205 360831 Kr-83m 1.01520E-08 3.08650E-03 360831 + 206 360840 Kr-84 1.26190E-05 6.28970E-03 36084.82c + 207 360850 Kr-85 1.63350E-04 2.30940E-03 36085.82c + 208 360851 Kr-85m 3.77700E-05 9.95300E-03 360851 + 209 360860 Kr-86 2.00800E-03 1.43140E-02 36086.82c + 210 360870 Kr-87 5.67070E-03 1.88160E-02 360870 + 211 360880 Kr-88 1.34600E-02 2.22250E-02 360880 + 212 360890 Kr-89 2.03940E-02 2.61890E-02 360890 + 213 360900 Kr-90 2.37150E-02 2.58280E-02 360900 + 214 360910 Kr-91 1.61080E-02 1.69580E-02 360910 + 215 360920 Kr-92 9.25320E-03 9.37060E-03 360920 + 216 360930 Kr-93 3.16980E-03 3.17890E-03 360930 + 217 360940 Kr-94 9.06970E-04 9.06990E-04 360940 + 218 360950 Kr-95 1.44570E-04 1.44570E-04 360950 + 219 360960 Kr-96 1.34600E-05 1.34600E-05 360960 + 220 360970 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4.21790E-03 391000 + 280 391001 Y-100m 3.94670E-03 3.94700E-03 391001 + 281 391010 Y-101 3.05660E-03 3.08120E-03 391010 + 282 391020 Y-102 2.50590E-04 2.50610E-04 391020 + 283 391021 Y-102m 2.50590E-04 2.50610E-04 391021 + 284 391030 Y-103 9.36430E-05 9.36430E-05 391030 + 285 391040 Y-104 4.65020E-06 4.65020E-06 391040 + 286 391050 Y-105 1.63420E-09 1.63420E-09 391050 + 287 400920 Zr-92 3.30530E-06 4.27550E-02 40092.82c + 288 400930 Zr-93 3.72360E-05 5.17650E-02 40093.82c + 289 400940 Zr-94 2.83550E-04 5.40350E-02 40094.82c + 290 400950 Zr-95 1.28550E-03 5.93640E-02 40095.82c + 291 400960 Zr-96 6.25380E-03 6.04720E-02 40096.82c + 292 400970 Zr-97 1.32130E-02 5.97320E-02 400970 + 293 400980 Zr-98 3.27340E-02 6.55020E-02 400980 + 294 400990 Zr-99 3.89720E-02 5.98120E-02 400990 + 295 401000 Zr-100 4.85660E-02 5.66920E-02 401000 + 296 401010 Zr-101 3.06770E-02 3.37830E-02 401010 + 297 401020 Zr-102 1.73570E-02 1.78410E-02 401020 + 298 401030 Zr-103 4.80360E-03 4.89020E-03 401030 + 299 401040 Zr-104 9.72100E-04 9.76340E-04 401040 + 300 401050 Zr-105 1.38430E-04 1.38430E-04 401050 + 301 401060 Zr-106 1.23470E-05 1.23470E-05 401060 + 302 401070 Zr-107 4.24080E-09 4.24080E-09 401070 + 303 410950 Nb-95 2.16340E-06 5.93310E-02 41095.82c + 304 410951 Nb-95m 5.00220E-07 6.41840E-04 410951 + 305 410960 Nb-96 3.94760E-05 3.94760E-05 410960 + 306 410970 Nb-97 2.86590E-04 6.00840E-02 410970 + 307 410971 Nb-97m 6.62650E-05 5.68400E-02 410971 + 308 410980 Nb-98 4.00830E-04 6.59030E-02 410980 + 309 410981 Nb-98m 1.20960E-03 1.20960E-03 410981 + 310 410990 Nb-99 5.46280E-03 4.37300E-02 410990 + 311 410991 Nb-99m 1.26310E-03 2.32740E-02 410991 + 312 411000 Nb-100 2.71480E-03 5.94070E-02 411000 + 313 411001 Nb-100m 1.14170E-02 1.14170E-02 411001 + 314 411010 Nb-101 2.94500E-02 6.32330E-02 411010 + 315 411020 Nb-102 1.51680E-02 3.30090E-02 411020 + 316 411021 Nb-102m 1.51680E-02 1.51680E-02 411021 + 317 411030 Nb-103 2.88570E-02 3.37470E-02 411030 + 318 411040 Nb-104 5.62300E-03 6.60130E-03 411040 + 319 411041 Nb-104m 5.62300E-03 5.62300E-03 411041 + 320 411050 Nb-105 4.80150E-03 4.93820E-03 411050 + 321 411060 Nb-106 1.00940E-03 1.02160E-03 411060 + 322 411070 Nb-107 1.82570E-04 1.82570E-04 411070 + 323 411080 Nb-108 8.40220E-06 8.40220E-06 411080 + 324 411090 Nb-109 5.84030E-09 5.84030E-09 411090 + 325 411100 Nb-110 3.07600E-11 3.07600E-11 411100 + 326 420970 Mo-97 4.33290E-06 6.00890E-02 42097.82c + 327 420980 Mo-98 3.63580E-05 6.71490E-02 42098.82c + 328 420990 Mo-99 2.74400E-04 6.68130E-02 42099.82c + 329 421000 Mo-100 1.86180E-03 7.26860E-02 42100.82c + 330 421010 Mo-101 5.63510E-03 6.88680E-02 421010 + 331 421020 Mo-102 1.63500E-02 6.45260E-02 421020 + 332 421030 Mo-103 2.32210E-02 5.69750E-02 421030 + 333 421040 Mo-104 2.34360E-02 3.57370E-02 421040 + 334 421050 Mo-105 1.44070E-02 1.93070E-02 421050 + 335 421060 Mo-106 7.95490E-03 8.94140E-03 421060 + 336 421070 Mo-107 2.03170E-03 2.20380E-03 421070 + 337 421080 Mo-108 5.30680E-04 5.38560E-04 421080 + 338 421090 Mo-109 5.94700E-05 5.94750E-05 421090 + 339 421100 Mo-110 2.35490E-06 2.35490E-06 421100 + 340 421110 Mo-111 2.33700E-06 2.33700E-06 421110 + 341 421120 Mo-112 1.73680E-10 1.73680E-10 421120 + 342 431000 Tc-100 5.22230E-06 5.22230E-06 431000 + 343 431010 Tc-101 5.38060E-05 6.89220E-02 431010 + 344 431020 Tc-102 1.67470E-04 6.46940E-02 431020 + 345 431021 Tc-102m 1.67470E-04 1.67470E-04 431021 + 346 431030 Tc-103 1.63540E-03 5.86100E-02 431030 + 347 431040 Tc-104 3.04140E-03 3.87790E-02 431040 + 348 431050 Tc-105 6.28820E-03 2.55950E-02 431050 + 349 431060 Tc-106 5.62030E-03 1.45620E-02 431060 + 350 431070 Tc-107 4.44550E-03 6.64930E-03 431070 + 351 431080 Tc-108 1.64820E-03 2.18710E-03 431080 + 352 431090 Tc-109 5.88810E-04 6.47970E-04 431090 + 353 431100 Tc-110 1.29690E-04 1.32070E-04 431100 + 354 431110 Tc-111 3.62380E-05 3.85510E-05 431110 + 355 431120 Tc-112 1.04610E-05 1.04610E-05 431120 + 356 431130 Tc-113 1.15050E-06 1.15050E-06 431130 + 357 431140 Tc-114 1.14700E-06 1.14700E-06 431140 + 358 431150 Tc-115 2.02820E-11 2.02820E-11 431150 + 359 441020 Ru-102 4.99970E-06 6.48660E-02 44102.82c + 360 441030 Ru-103 8.74040E-06 5.86400E-02 44103.82c + 361 441031 Ru-103m 2.11010E-05 2.11010E-05 441031 + 362 441040 Ru-104 1.25470E-04 3.89040E-02 44104.82c + 363 441050 Ru-105 3.87140E-04 2.59820E-02 44105.82c + 364 441060 Ru-106 8.59550E-04 1.54210E-02 44106.82c + 365 441070 Ru-107 8.28950E-04 7.47830E-03 441070 + 366 441080 Ru-108 8.85890E-04 3.07350E-03 441080 + 367 441090 Ru-109 4.08960E-04 1.05650E-03 441090 + 368 441100 Ru-110 2.29310E-04 3.61330E-04 441100 + 369 441110 Ru-111 1.10950E-04 1.49660E-04 441110 + 370 441120 Ru-112 7.43580E-05 8.47450E-05 441120 + 371 441130 Ru-113 1.03540E-05 1.66730E-05 441130 + 372 441131 Ru-113m 1.03540E-05 1.03540E-05 441131 + 373 441140 Ru-114 9.17560E-06 1.02480E-05 441140 + 374 441150 Ru-115 2.28310E-06 2.28310E-06 441150 + 375 441160 Ru-116 1.10670E-08 1.10670E-08 441160 + 376 441170 Ru-117 2.75400E-10 2.75400E-10 441170 + 377 441180 Ru-118 6.41160E-12 6.41160E-12 441180 + 378 441200 Ru-120 4.59110E-10 4.59110E-10 441200 + 379 451050 Rh-105 9.92220E-09 2.59830E-02 45105.82c + 380 451051 Rh-105m 1.51680E-09 7.37580E-03 451051 + 381 451060 Rh-106 1.84710E-06 1.54230E-02 451060 + 382 451061 Rh-106m 4.32640E-06 4.32640E-06 451061 + 383 451070 Rh-107 1.34060E-05 7.49170E-03 451070 + 384 451080 Rh-108 8.36430E-06 3.08190E-03 451080 + 385 451081 Rh-108m 2.52410E-05 2.52410E-05 451081 + 386 451090 Rh-109 5.11440E-05 1.10760E-03 451090 + 387 451100 Rh-110 4.01390E-05 4.01470E-04 451100 + 388 451101 Rh-110m 1.07150E-06 1.07150E-06 451101 + 389 451110 Rh-111 7.12820E-05 2.20940E-04 451110 + 390 451120 Rh-112 3.13810E-05 1.16130E-04 451120 + 391 451121 Rh-112m 3.13810E-05 3.13810E-05 451121 + 392 451130 Rh-113 9.20370E-05 1.13890E-04 451130 + 393 451140 Rh-114 3.38320E-05 4.40850E-05 451140 + 394 451141 Rh-114m 3.38320E-05 3.38320E-05 451141 + 395 451150 Rh-115 3.99500E-05 4.22280E-05 451150 + 396 451160 Rh-116 6.96870E-06 6.97960E-06 451160 + 397 451161 Rh-116m 1.63220E-05 1.63220E-05 451161 + 398 451170 Rh-117 1.18850E-05 1.18850E-05 451170 + 399 451180 Rh-118 6.07310E-06 6.07310E-06 451180 + 400 451190 Rh-119 1.23980E-06 1.23980E-06 451190 + 401 451200 Rh-120 7.71810E-07 7.72270E-07 451200 + 402 451210 Rh-121 6.04950E-08 6.04950E-08 451210 + 403 451220 Rh-122 2.34520E-09 2.34520E-09 451220 + 404 461070 Pd-107 7.36420E-11 7.49170E-03 46107.82c + 405 461071 Pd-107m 1.38400E-10 1.38400E-10 461071 + 406 461080 Pd-108 9.04860E-09 3.10710E-03 46108.82c + 407 461090 Pd-109 4.13180E-07 1.10880E-03 461090 + 408 461091 Pd-109m 7.76520E-07 5.54580E-04 461091 + 409 461100 Pd-110 3.53250E-06 4.06070E-04 46110.82c + 410 461110 Pd-111 8.11640E-07 2.22630E-04 461110 + 411 461111 Pd-111m 1.52540E-06 2.40910E-06 461111 + 412 461120 Pd-112 1.16230E-05 1.59130E-04 461120 + 413 461130 Pd-113 8.42560E-06 1.42650E-04 461130 + 414 461131 Pd-113m 2.03400E-05 2.03400E-05 461131 + 415 461140 Pd-114 7.80130E-05 1.55930E-04 461140 + 416 461150 Pd-115 2.73590E-05 6.80600E-05 461150 + 417 461151 Pd-115m 5.14180E-05 5.75490E-05 461151 + 418 461160 Pd-116 1.10630E-04 1.33930E-04 461160 + 419 461170 Pd-117 2.80640E-05 9.28690E-05 461170 + 420 461171 Pd-117m 5.27430E-05 5.27430E-05 461171 + 421 461180 Pd-118 4.25060E-05 4.84020E-05 461180 + 422 461190 Pd-119 1.48770E-05 1.61630E-05 461190 + 423 461200 Pd-120 6.29030E-06 7.02500E-06 461200 + 424 461210 Pd-121 1.28530E-06 1.33760E-06 461210 + 425 461220 Pd-122 3.34060E-06 3.34290E-06 461220 + 426 461230 Pd-123 2.85450E-07 2.85450E-07 461230 + 427 461240 Pd-124 2.32550E-08 2.32550E-08 461240 + 428 471100 Ag-110 2.76100E-11 2.84890E-11 471100 + 429 471101 Ag-110m 6.46690E-11 6.46690E-11 47510.82c + 430 471110 Ag-111 3.93870E-10 2.22170E-04 47111.82c + 431 471111 Ag-111m 2.57650E-09 2.21520E-04 471111 + 432 471120 Ag-112 4.37440E-08 1.59170E-04 471120 + 433 471130 Ag-113 8.96060E-08 9.39410E-05 471130 + 434 471131 Ag-113m 5.86150E-07 1.37190E-04 471131 + 435 471140 Ag-114 4.40700E-07 1.58220E-04 471140 + 436 471141 Ag-114m 1.85340E-06 1.85340E-06 471141 + 437 471150 Ag-115 1.21110E-06 6.75360E-05 471150 + 438 471151 Ag-115m 7.92210E-06 7.92440E-05 471151 + 439 471160 Ag-116 1.28960E-05 1.48640E-04 471160 + 440 471161 Ag-116m 3.02040E-05 3.02040E-05 471161 + 441 471170 Ag-117 1.37150E-05 6.83180E-05 471170 + 442 471171 Ag-117m 8.97150E-05 1.36150E-04 471171 + 443 471180 Ag-118 2.10020E-05 1.01540E-04 471180 + 444 471181 Ag-118m 8.83280E-05 9.52470E-05 471181 + 445 471190 Ag-119 1.29870E-05 2.10680E-05 471190 + 446 471191 Ag-119m 8.49510E-05 9.30330E-05 471191 + 447 471200 Ag-120 2.23610E-05 3.89170E-05 471200 + 448 471201 Ag-120m 3.17300E-05 3.52420E-05 471201 + 449 471210 Ag-121 3.98390E-05 4.11730E-05 471210 + 450 471220 Ag-122 5.39570E-06 8.73860E-06 471220 + 451 471221 Ag-122m 4.86030E-06 4.86030E-06 471221 + 452 471230 Ag-123 1.33100E-06 1.61640E-06 471230 + 453 471240 Ag-124 4.27900E-06 6.22950E-06 471240 + 454 471241 Ag-124m 3.85440E-06 3.85440E-06 471241 + 455 471250 Ag-125 1.38030E-06 1.38030E-06 471250 + 456 471260 Ag-126 2.52990E-07 2.52990E-07 471260 + 457 471270 Ag-127 4.08450E-08 4.08450E-08 471270 + 458 471280 Ag-128 2.16180E-09 2.16180E-09 471280 + 459 481120 Cd-112 5.60270E-12 1.59170E-04 48112.82c + 460 481130 Cd-113 5.13900E-11 1.41710E-04 48113.82c + 461 481131 Cd-113m 1.68130E-10 1.62430E-06 481131 + 462 481140 Cd-114 1.08280E-08 1.58240E-04 48114.82c + 463 481150 Cd-115 3.28770E-08 1.24460E-04 481150 + 464 481151 Cd-115m 1.07560E-07 5.82180E-06 48515.82c + 465 481160 Cd-116 4.65890E-06 1.81690E-04 48116.82c + 466 481170 Cd-117 2.22610E-06 1.55260E-04 481170 + 467 481171 Cd-117m 7.28320E-06 5.05500E-05 481171 + 468 481180 Cd-118 2.30830E-05 1.80810E-04 481180 + 469 481190 Cd-119 1.27120E-05 1.16280E-04 481190 + 470 481191 Cd-119m 3.06900E-05 4.12240E-05 481191 + 471 481200 Cd-120 8.93440E-05 1.50460E-04 481200 + 472 481210 Cd-121 1.69420E-05 5.38130E-05 481210 + 473 481211 Cd-121m 4.09000E-05 4.52020E-05 481211 + 474 481220 Cd-122 9.35870E-05 1.07190E-04 481220 + 475 481230 Cd-123 1.59830E-05 1.73080E-05 481230 + 476 481231 Cd-123m 3.85840E-05 3.88810E-05 481231 + 477 481240 Cd-124 4.20230E-05 5.01730E-05 481240 + 478 481250 Cd-125 1.05120E-05 1.12020E-05 481250 + 479 481251 Cd-125m 2.53770E-05 2.60670E-05 481251 + 480 481260 Cd-126 4.77140E-05 4.79670E-05 481260 + 481 481270 Cd-127 4.98450E-05 4.98860E-05 481270 + 482 481280 Cd-128 3.12550E-05 3.12570E-05 481280 + 483 481290 Cd-129 3.82610E-07 3.82610E-07 481290 + 484 481291 Cd-129m 9.23680E-07 9.23680E-07 481291 + 485 481300 Cd-130 1.32580E-06 1.32580E-06 481300 + 486 481310 Cd-131 2.01000E-09 2.01000E-09 481310 + 487 491150 In-115 1.97670E-11 1.24060E-04 49115.82c + 488 491151 In-115m 4.57070E-12 1.24460E-04 491151 + 489 491160 In-116 3.28750E-10 3.28750E-10 491160 + 490 491161 In-116m 5.03880E-10 9.91920E-10 491161 + 491 491162 In-116m 4.88040E-10 4.88040E-10 491162 + 492 491170 In-117 4.08740E-08 1.30180E-04 491170 + 493 491171 In-117m 9.45100E-09 1.43060E-04 491171 + 494 491180 In-118 3.02340E-07 1.81120E-04 491180 + 495 491181 In-118m 4.63410E-07 9.05960E-07 491181 + 496 491182 In-118m 4.48830E-07 4.48830E-07 491182 + 497 491190 In-119 1.00700E-06 5.93420E-05 491190 + 498 491191 In-119m 2.32850E-07 1.05300E-04 491191 + 499 491200 In-120 1.25800E-06 1.51720E-04 491200 + 500 491201 In-120m 1.25800E-06 1.25800E-06 491201 + 501 491202 In-120m 1.25800E-06 1.25800E-06 491202 + 502 491210 In-121 2.40150E-05 8.78360E-05 491210 + 503 491211 In-121m 5.55290E-06 4.12420E-05 491211 + 504 491220 In-122 1.85540E-05 1.25740E-04 491220 + 505 491221 In-122m 1.31640E-05 1.31640E-05 491221 + 506 491222 In-122m 1.31640E-05 1.31640E-05 491222 + 507 491230 In-123 7.13690E-05 1.15140E-04 491230 + 508 491231 In-123m 1.65020E-05 2.89240E-05 491231 + 509 491240 In-124 5.20860E-05 1.02260E-04 491240 + 510 491241 In-124m 4.69190E-05 4.69190E-05 491241 + 511 491250 In-125 1.06580E-04 1.38010E-04 491250 + 512 491251 In-125m 2.46430E-05 3.04840E-05 491251 + 513 491260 In-126 1.47180E-04 1.95140E-04 491260 + 514 491261 In-126m 1.32570E-04 1.32570E-04 491261 + 515 491270 In-127 6.50240E-04 6.50240E-04 491270 + 516 491271 In-127m 1.50350E-04 2.00240E-04 491271 + 517 491280 In-128 4.06540E-04 6.03290E-04 491280 + 518 491281 In-128m 1.65490E-04 1.96740E-04 491281 + 519 491282 In-128m 5.15270E-04 5.15270E-04 491282 + 520 491290 In-129 9.30130E-04 9.31080E-04 491290 + 521 491291 In-129m 2.15070E-04 2.15470E-04 491291 + 522 491300 In-130 1.41990E-04 1.43270E-04 491300 + 523 491301 In-130m 1.58590E-04 1.58590E-04 491301 + 524 491302 In-130m 2.69830E-04 2.69830E-04 491302 + 525 491310 In-131 6.72500E-05 6.79370E-05 491310 + 526 491311 In-131m 6.72500E-05 6.72500E-05 491311 + 527 491312 In-131m 6.72500E-05 6.72500E-05 491312 + 528 491320 In-132 1.46760E-05 1.46760E-05 491320 + 529 491330 In-133 1.03980E-06 1.28020E-06 491330 + 530 491331 In-133m 2.40420E-07 2.40420E-07 491331 + 531 501170 Sn-117 1.37170E-12 2.05860E-04 50117.82c + 532 501171 Sn-117m 4.48780E-12 4.43540E-07 501171 + 533 501180 Sn-118 2.24400E-10 1.82030E-04 50118.82c + 534 501190 Sn-119 1.43130E-09 1.58750E-04 50119.82c + 535 501191 Sn-119m 4.68280E-09 5.36140E-05 501191 + 536 501210 Sn-121 3.76460E-07 1.27440E-04 501210 + 537 501211 Sn-121m 9.08840E-07 1.08590E-05 501211 + 538 501220 Sn-122 3.84620E-06 1.55910E-04 50122.82c + 539 501230 Sn-123 8.46890E-06 1.72470E-05 50123.82c + 540 501231 Sn-123m 3.50810E-06 1.38790E-04 501231 + 541 501240 Sn-124 3.11690E-05 1.80350E-04 50124.82c + 542 501250 Sn-125 5.26650E-05 7.59770E-05 50125.82c + 543 501251 Sn-125m 2.18150E-05 1.66990E-04 501251 + 544 501260 Sn-126 2.12890E-04 5.41990E-04 50126.82c + 545 501270 Sn-127 5.25400E-04 7.78840E-04 501270 + 546 501271 Sn-127m 2.17630E-04 8.13280E-04 501271 + 547 501280 Sn-128 9.38920E-04 4.25670E-03 501280 + 548 501281 Sn-128m 2.19920E-03 2.71450E-03 501281 + 549 501290 Sn-129 1.43910E-03 2.48660E-03 501290 + 550 501291 Sn-129m 3.47430E-03 3.57340E-03 501291 + 551 501300 Sn-130 2.29580E-03 2.66810E-03 501300 + 552 501301 Sn-130m 5.37720E-03 5.57800E-03 501301 + 553 501310 Sn-131 1.41080E-03 1.54110E-03 501310 + 554 501311 Sn-131m 3.40600E-03 3.47610E-03 501311 + 555 501320 Sn-132 1.95260E-03 1.96840E-03 501320 + 556 501330 Sn-133 2.40000E-04 2.40190E-04 501330 + 557 501340 Sn-134 2.75860E-05 2.75860E-05 501340 + 558 501350 Sn-135 4.11940E-07 4.11940E-07 501350 + 559 501360 Sn-136 7.68210E-09 7.68210E-09 501360 + 560 511230 Sb-123 9.70780E-12 1.56040E-04 51123.82c + 561 511240 Sb-124 4.84360E-07 1.13780E-06 51124.82c + 562 511241 Sb-124m 3.70350E-07 8.71240E-07 511241 + 563 511242 Sb-124m 5.00890E-07 5.00890E-07 511242 + 564 511250 Sb-125 8.28170E-06 2.51250E-04 51125.82c + 565 511260 Sb-126 3.62960E-06 4.49660E-06 51126.82c + 566 511261 Sb-126m 2.68360E-06 6.19330E-06 511261 + 567 511262 Sb-126m 3.50970E-06 3.50970E-06 511262 + 568 511270 Sb-127 9.54240E-05 1.68750E-03 511270 + 569 511280 Sb-128 1.64580E-04 4.43130E-03 511280 + 570 511281 Sb-128m 2.80840E-04 2.80840E-04 511281 + 571 511290 Sb-129 2.25260E-03 7.00030E-03 511290 + 572 511291 Sb-129m 1.37650E-03 3.16320E-03 511291 + 573 511300 Sb-130 4.74280E-03 1.02000E-02 511300 + 574 511301 Sb-130m 4.74280E-03 7.53180E-03 511301 + 575 511310 Sb-131 2.59780E-02 3.09950E-02 511310 + 576 511320 Sb-132 1.31260E-02 1.50940E-02 511320 + 577 511321 Sb-132m 9.67400E-03 9.67400E-03 511321 + 578 511330 Sb-133 2.56810E-02 2.59260E-02 511330 + 579 511340 Sb-134 1.72000E-03 1.74300E-03 511340 + 580 511341 Sb-134m 4.02880E-03 4.02880E-03 511341 + 581 511350 Sb-135 1.66960E-03 1.66990E-03 511350 + 582 511360 Sb-136 2.25540E-04 2.25550E-04 511360 + 583 511370 Sb-137 2.87000E-05 2.87000E-05 511370 + 584 511380 Sb-138 4.77710E-08 4.77710E-08 511380 + 585 521260 Te-126 2.90350E-10 9.82320E-06 52126.82c + 586 521270 Te-127 1.25120E-06 1.68510E-03 521270 + 587 521271 Te-127m 3.02070E-06 2.81120E-04 52527.82c + 588 521280 Te-128 2.17430E-05 4.72390E-03 52128.82c + 589 521290 Te-129 3.13990E-05 8.36680E-03 521290 + 590 521291 Te-129m 7.58010E-05 3.86330E-03 52529.82c + 591 521300 Te-130 1.32380E-03 1.90550E-02 52130.82c + 592 521310 Te-131 1.38000E-03 3.11140E-02 521310 + 593 521311 Te-131m 3.33160E-03 5.81310E-03 521311 + 594 521320 Te-132 1.74670E-02 4.22350E-02 52132.82c + 595 521330 Te-133 9.61180E-03 3.59030E-02 521330 + 596 521331 Te-133m 2.32040E-02 2.76880E-02 521331 + 597 521340 Te-134 4.46230E-02 5.06540E-02 521340 + 598 521350 Te-135 1.75500E-02 1.89950E-02 521350 + 599 521360 Te-136 8.41950E-03 8.62170E-03 521360 + 600 521370 Te-137 1.36490E-03 1.37950E-03 521370 + 601 521380 Te-138 3.19600E-04 3.19650E-04 521380 + 602 521390 Te-139 2.08640E-05 2.08640E-05 521390 + 603 521400 Te-140 3.09530E-06 3.09530E-06 521400 + 604 521410 Te-141 6.69840E-09 6.69840E-09 521410 + 605 531280 I-128 1.35870E-06 1.35870E-06 531280 + 606 531290 I-129 2.92190E-08 9.79630E-03 53129.82c + 607 531300 I-130 7.43340E-06 1.00990E-05 53130.82c + 608 531301 I-130m 3.17360E-06 3.17360E-06 531301 + 609 531310 I-131 1.48140E-04 3.58550E-02 53131.82c + 610 531320 I-132 4.22860E-04 4.29260E-02 531320 + 611 531321 I-132m 3.11650E-04 3.11650E-04 531321 + 612 531330 I-133 3.93520E-03 6.50860E-02 531330 + 613 531331 I-133m 2.40480E-03 2.40480E-03 531331 + 614 531340 I-134 8.50420E-03 6.52820E-02 531340 + 615 531341 I-134m 6.26780E-03 6.26780E-03 531341 + 616 531350 I-135 5.48940E-02 7.38880E-02 53135.82c + 617 531360 I-136 1.45160E-02 2.31580E-02 531360 + 618 531361 I-136m 3.39990E-02 3.40200E-02 531361 + 619 531370 I-137 4.42870E-02 4.56450E-02 531370 + 620 531380 I-138 1.36340E-02 1.39330E-02 531380 + 621 531390 I-139 9.52430E-03 9.54520E-03 531390 + 622 531400 I-140 1.98180E-03 1.98490E-03 531400 + 623 531410 I-141 4.21100E-04 4.21110E-04 531410 + 624 531420 I-142 3.99440E-05 3.99440E-05 531420 + 625 531430 I-143 4.61940E-06 4.61940E-06 531430 + 626 531440 I-144 1.08720E-09 1.08720E-09 531440 + 627 541310 Xe-131 3.90850E-07 3.58560E-02 54131.82c + 628 541311 Xe-131m 9.43550E-07 3.90400E-04 541311 + 629 541320 Xe-132 2.11650E-06 4.29740E-02 54132.82c + 630 541321 Xe-132m 2.39910E-06 2.39910E-06 541321 + 631 541330 Xe-133 1.19960E-05 6.51270E-02 54133.82c + 632 541331 Xe-133m 2.89600E-05 1.88150E-03 541331 + 633 541340 Xe-134 1.43630E-04 6.59060E-02 54134.82c + 634 541341 Xe-134m 3.36410E-04 4.80570E-04 541341 + 635 541350 Xe-135 8.12390E-04 7.65770E-02 54135.82c + 636 541351 Xe-135m 1.96120E-03 1.41590E-02 541351 + 637 541360 Xe-136 1.60330E-02 7.61780E-02 54136.82c + 638 541370 Xe-137 2.37150E-02 6.71320E-02 541370 + 639 541380 Xe-138 3.61830E-02 5.03130E-02 541380 + 640 541390 Xe-139 2.25570E-02 3.13510E-02 541390 + 641 541400 Xe-140 2.24990E-02 2.43880E-02 541400 + 642 541410 Xe-141 5.81870E-03 6.16140E-03 541410 + 643 541420 Xe-142 2.24990E-03 2.28170E-03 541420 + 644 541430 Xe-143 3.22420E-04 3.25190E-04 541430 + 645 541440 Xe-144 5.00500E-05 5.00510E-05 541440 + 646 541450 Xe-145 7.95260E-06 7.95260E-06 541450 + 647 541460 Xe-146 5.80660E-09 5.80660E-09 541460 + 648 551330 Cs-133 2.01520E-09 6.51270E-02 55133.82c + 649 551340 Cs-134 5.88420E-07 1.02210E-06 55134.82c + 650 551341 Cs-134m 4.33680E-07 4.33680E-07 551341 + 651 551350 Cs-135 1.90640E-05 7.66930E-02 55135.82c + 652 551351 Cs-135m 1.16490E-05 1.16490E-05 551351 + 653 551360 Cs-136 1.61480E-04 2.08800E-04 55136.82c + 654 551361 Cs-136m 9.46360E-05 9.46360E-05 551361 + 655 551370 Cs-137 3.20170E-03 7.03340E-02 55137.82c + 656 551380 Cs-138 4.23400E-03 5.94140E-02 551380 + 657 551381 Cs-138m 6.00800E-03 6.00800E-03 551381 + 658 551390 Cs-139 2.43470E-02 5.56980E-02 551390 + 659 551400 Cs-140 3.01490E-02 5.45390E-02 551400 + 660 551410 Cs-141 4.44290E-02 5.05960E-02 551410 + 661 551420 Cs-142 2.68330E-02 2.91100E-02 551420 + 662 551430 Cs-143 2.12440E-02 2.15670E-02 551430 + 663 551440 Cs-144 3.32620E-03 5.03810E-03 551440 + 664 551441 Cs-144m 3.32620E-03 3.32640E-03 551441 + 665 551450 Cs-145 2.10020E-03 2.10780E-03 551450 + 666 551460 Cs-146 3.11580E-04 3.11590E-04 551460 + 667 551470 Cs-147 5.82250E-05 5.82250E-05 551470 + 668 551480 Cs-148 5.37080E-06 5.37080E-06 551480 + 669 551490 Cs-149 5.36520E-10 5.36520E-10 551490 + 670 561360 Ba-136 6.12910E-09 2.56140E-04 56136.82c + 671 561361 Ba-136m 1.43560E-08 1.43560E-08 561361 + 672 561370 Ba-137 2.71150E-06 7.03430E-02 56137.82c + 673 561371 Ba-137m 6.54600E-06 6.64010E-02 561371 + 674 561380 Ba-138 1.96270E-04 6.07520E-02 56138.82c + 675 561390 Ba-139 9.65310E-04 5.66640E-02 561390 + 676 561400 Ba-140 4.05170E-03 5.85910E-02 56140.82c + 677 561410 Ba-141 6.82970E-03 5.74260E-02 561410 + 678 561420 Ba-142 1.72770E-02 4.67400E-02 561420 + 679 561430 Ba-143 2.06840E-02 4.20590E-02 561430 + 680 561440 Ba-144 2.25390E-02 2.93810E-02 561440 + 681 561450 Ba-145 9.12270E-03 1.09730E-02 561450 + 682 561460 Ba-146 5.23320E-03 5.51710E-03 561460 + 683 561470 Ba-147 1.14340E-03 1.18640E-03 561470 + 684 561480 Ba-148 3.44070E-04 3.48090E-04 561480 + 685 561490 Ba-149 3.24140E-05 3.24140E-05 561490 + 686 561500 Ba-150 1.65420E-07 1.65420E-07 561500 + 687 561510 Ba-151 1.88730E-09 1.88730E-09 561510 + 688 571380 La-138 1.54100E-09 1.54100E-09 57138.82c + 689 571390 La-139 6.63780E-06 5.66700E-02 57139.82c + 690 571400 La-140 7.02010E-05 5.86610E-02 57140.82c + 691 571410 La-141 4.03400E-04 5.78290E-02 571410 + 692 571420 La-142 1.25960E-03 4.80000E-02 571420 + 693 571430 La-143 6.42080E-03 4.84800E-02 571430 + 694 571440 La-144 1.30300E-02 4.24100E-02 571440 + 695 571450 La-145 2.40170E-02 3.49900E-02 571450 + 696 571460 La-146 6.44930E-03 1.19660E-02 571460 + 697 571461 La-146m 1.16010E-02 1.16010E-02 571461 + 698 571470 La-147 1.78690E-02 1.90570E-02 571470 + 699 571480 La-148 8.28880E-03 8.63560E-03 571480 + 700 571490 La-149 4.50660E-03 4.53890E-03 571490 + 701 571500 La-150 9.49600E-04 9.49760E-04 571500 + 702 571510 La-151 1.65590E-04 1.65590E-04 571510 + 703 571520 La-152 2.17520E-05 2.17520E-05 571520 + 704 571530 La-153 5.99230E-09 5.99230E-09 571530 + 705 571540 La-154 2.94080E-11 2.94080E-11 571540 + 706 581410 Ce-141 1.00480E-08 5.78290E-02 58141.82c + 707 581420 Ce-142 7.48920E-06 4.80080E-02 58142.82c + 708 581430 Ce-143 4.43850E-05 4.85240E-02 58143.82c + 709 581440 Ce-144 3.05680E-04 4.27160E-02 58144.82c + 710 581450 Ce-145 1.23170E-03 3.62220E-02 581450 + 711 581460 Ce-146 3.65960E-03 2.72270E-02 581460 + 712 581470 Ce-147 5.59950E-03 2.46560E-02 581470 + 713 581480 Ce-148 9.95150E-03 1.86510E-02 581480 + 714 581490 Ce-149 7.17700E-03 1.16780E-02 581490 + 715 581500 Ce-150 5.01130E-03 5.93540E-03 581500 + 716 581510 Ce-151 1.28520E-03 1.45210E-03 581510 + 717 581520 Ce-152 4.44650E-04 4.65090E-04 581520 + 718 581530 Ce-153 3.48950E-05 3.49010E-05 581530 + 719 581540 Ce-154 1.31640E-06 1.31640E-06 581540 + 720 581550 Ce-155 9.09960E-09 9.09960E-09 581550 + 721 581560 Ce-156 1.05080E-10 1.05080E-10 581560 + 722 591430 Pr-143 1.54140E-09 4.85240E-02 59143.82c + 723 591440 Pr-144 9.21030E-08 4.27170E-02 591440 + 724 591441 Pr-144m 8.18010E-07 5.90280E-04 591441 + 725 591450 Pr-145 1.23770E-05 3.62340E-02 591450 + 726 591460 Pr-146 1.18910E-04 2.73460E-02 591460 + 727 591470 Pr-147 5.73290E-04 2.52300E-02 591470 + 728 591480 Pr-148 3.47760E-04 1.89980E-02 591480 + 729 591481 Pr-148m 1.46250E-03 1.46250E-03 591481 + 730 591490 Pr-149 5.37790E-03 1.70560E-02 591490 + 731 591500 Pr-150 5.67580E-03 1.16110E-02 591500 + 732 591510 Pr-151 6.27360E-03 7.72570E-03 591510 + 733 591520 Pr-152 3.02940E-03 3.49470E-03 591520 + 734 591530 Pr-153 1.65520E-03 1.68990E-03 591530 + 735 591540 Pr-154 3.03810E-04 3.05120E-04 591540 + 736 591550 Pr-155 8.43390E-05 8.43480E-05 591550 + 737 591560 Pr-156 7.98320E-06 7.98330E-06 591560 + 738 591570 Pr-157 1.39990E-08 1.39990E-08 591570 + 739 591580 Pr-158 9.39720E-11 9.39720E-11 591580 + 740 601460 Nd-146 4.83880E-09 2.73460E-02 60146.82c + 741 601470 Nd-147 8.82840E-07 2.52300E-02 60147.82c + 742 601480 Nd-148 9.67270E-06 2.04710E-02 60148.82c + 743 601490 Nd-149 7.15680E-05 1.71270E-02 601490 + 744 601500 Nd-150 2.76790E-04 1.18880E-02 60150.82c + 745 601510 Nd-151 6.00860E-04 8.32660E-03 601510 + 746 601520 Nd-152 1.07130E-03 4.56600E-03 601520 + 747 601530 Nd-153 8.48270E-04 2.53820E-03 601530 + 748 601540 Nd-154 6.32560E-04 9.37680E-04 601540 + 749 601550 Nd-155 2.09940E-04 2.94500E-04 601550 + 750 601560 Nd-156 6.91860E-05 7.69530E-05 601560 + 751 601570 Nd-157 1.04190E-05 1.04320E-05 601570 + 752 601580 Nd-158 2.97930E-07 2.98020E-07 601580 + 753 601590 Nd-159 7.41460E-09 7.41460E-09 601590 + 754 601600 Nd-160 2.54880E-10 2.54880E-10 601600 + 755 601610 Nd-161 2.75560E-12 2.75560E-12 601610 + 756 611490 Pm-149 1.71690E-08 1.71280E-02 61149.82c + 757 611500 Pm-150 2.62510E-06 2.62510E-06 611500 + 758 611510 Pm-151 1.04850E-05 8.33710E-03 61151.82c + 759 611520 Pm-152 1.30870E-05 4.57910E-03 611520 + 760 611521 Pm-152m 2.61320E-05 2.61320E-05 611521 + 761 611522 Pm-152m 2.89050E-05 2.89050E-05 611522 + 762 611530 Pm-153 1.96210E-04 2.73440E-03 611530 + 763 611540 Pm-154 1.14120E-04 1.05180E-03 611540 + 764 611541 Pm-154m 1.14120E-04 1.14120E-04 611541 + 765 611550 Pm-155 3.24000E-04 6.18500E-04 611550 + 766 611560 Pm-156 1.71710E-04 2.48660E-04 611560 + 767 611570 Pm-157 1.18520E-04 1.28950E-04 611570 + 768 611580 Pm-158 2.68480E-05 2.71460E-05 611580 + 769 611590 Pm-159 8.93070E-06 8.93810E-06 611590 + 770 611600 Pm-160 3.73740E-06 3.73770E-06 611600 + 771 611610 Pm-161 1.44520E-08 1.44550E-08 611610 + 772 611620 Pm-162 7.82000E-11 7.82000E-11 611620 + 773 611630 Pm-163 5.91670E-12 5.91670E-12 611630 + 774 621510 Sm-151 7.07730E-10 8.33710E-03 62151.82c + 775 621520 Sm-152 3.17440E-08 4.63420E-03 62152.82c + 776 621530 Sm-153 1.32820E-07 2.73480E-03 62153.82c + 777 621531 Sm-153m 3.20660E-07 3.20660E-07 621531 + 778 621540 Sm-154 3.83630E-06 1.16980E-03 62154.82c + 779 621550 Sm-155 1.32050E-05 6.31710E-04 621550 + 780 621560 Sm-156 1.99640E-05 2.68630E-04 621560 + 781 621570 Sm-157 1.43280E-05 1.43280E-04 621570 + 782 621580 Sm-158 1.02280E-05 3.73760E-05 621580 + 783 621590 Sm-159 5.10350E-06 1.40500E-05 621590 + 784 621600 Sm-160 2.49160E-06 6.21920E-06 621600 + 785 621610 Sm-161 3.45360E-06 3.46810E-06 621610 + 786 621620 Sm-162 4.80930E-08 4.81710E-08 621620 + 787 621630 Sm-163 1.10840E-08 1.10900E-08 621630 + 788 621640 Sm-164 4.02010E-10 4.02010E-10 621640 + 789 621650 Sm-165 7.11500E-12 7.11500E-12 621650 + 790 631540 Eu-154 3.71310E-10 7.05780E-10 63154.82c + 791 631541 Eu-154m 3.34470E-10 3.34470E-10 631541 + 792 631550 Eu-155 2.00440E-08 6.31730E-04 63155.82c + 793 631560 Eu-156 2.66160E-06 2.71290E-04 63156.82c + 794 631570 Eu-157 2.60490E-06 1.45890E-04 63157.82c + 795 631580 Eu-158 3.83570E-06 4.12110E-05 631580 + 796 631590 Eu-159 2.55170E-06 1.66020E-05 631590 + 797 631600 Eu-160 4.98330E-06 1.12030E-05 631600 + 798 631610 Eu-161 3.45360E-06 6.92170E-06 631610 + 799 631620 Eu-162 4.15240E-07 4.63410E-07 631620 + 800 631630 Eu-163 8.04360E-07 8.15450E-07 631630 + 801 631640 Eu-164 5.71820E-08 5.75840E-08 631640 + 802 631650 Eu-165 6.97770E-09 6.98480E-09 631650 + 803 631660 Eu-166 3.05090E-10 3.05090E-10 631660 + 804 631670 Eu-167 9.99870E-12 9.99870E-12 631670 + 805 641560 Gd-156 2.86600E-11 2.71290E-04 64156.82c + 806 641570 Gd-157 6.23530E-10 1.45890E-04 64157.82c + 807 641580 Gd-158 6.73330E-09 4.12180E-05 64158.82c + 808 641590 Gd-159 3.72280E-08 1.66390E-05 641590 + 809 641600 Gd-160 2.86790E-07 1.14890E-05 64160.82c + 810 641610 Gd-161 7.39720E-07 7.66140E-06 641610 + 811 641620 Gd-162 8.07660E-07 1.27110E-06 641620 + 812 641630 Gd-163 9.31850E-07 1.74730E-06 641630 + 813 641640 Gd-164 4.83870E-07 5.41450E-07 641640 + 814 641650 Gd-165 1.42690E-07 1.49670E-07 641650 + 815 641660 Gd-166 3.85980E-08 3.89030E-08 641660 + 816 641670 Gd-167 3.63510E-09 3.64510E-09 641670 + 817 641680 Gd-168 3.05440E-10 3.05440E-10 641680 + 818 641690 Gd-169 1.02590E-11 1.02590E-11 641690 + 819 651590 Tb-159 9.30530E-12 1.66390E-05 65159.82c + 820 651600 Tb-160 2.27530E-10 2.27530E-10 65160.82c + 821 651610 Tb-161 4.04470E-09 7.66540E-06 651610 + 822 651620 Tb-162 4.86400E-09 1.27590E-06 651620 + 823 651630 Tb-163 8.04370E-07 2.55170E-06 651630 + 824 651640 Tb-164 1.00920E-07 6.42370E-07 651640 + 825 651650 Tb-165 1.49360E-07 2.99030E-07 651650 + 826 651660 Tb-166 8.69530E-08 1.25860E-07 651660 + 827 651670 Tb-167 4.37480E-08 4.73930E-08 651670 + 828 651680 Tb-168 9.30180E-09 9.60720E-09 651680 + 829 651690 Tb-169 2.00950E-09 2.01980E-09 651690 + 830 651700 Tb-170 1.49480E-10 1.49480E-10 651700 + 831 651710 Tb-171 9.94680E-12 9.94680E-12 651710 + 832 661620 Dy-162 3.29680E-12 1.27590E-06 66162.82c + 833 661630 Dy-163 1.72550E-10 2.55180E-06 66163.82c + 834 661640 Dy-164 1.39130E-09 6.43760E-07 66164.82c + 835 661650 Dy-165 4.78390E-09 3.04530E-07 661650 + 836 661651 Dy-165m 7.31310E-10 7.31310E-10 661651 + 837 661660 Dy-166 1.81770E-08 1.44030E-07 661660 + 838 661670 Dy-167 2.03540E-08 6.77470E-08 661670 + 839 661680 Dy-168 2.14870E-08 3.10940E-08 661680 + 840 661690 Dy-169 1.02290E-08 1.22490E-08 661690 + 841 661700 Dy-170 4.24690E-09 4.39640E-09 661700 + 842 661710 Dy-171 7.47300E-10 7.57250E-10 661710 + 843 661720 Dy-172 1.24420E-10 1.24420E-10 661720 + 844 661730 Dy-173 7.18260E-12 7.18260E-12 661730 + 845 671650 Ho-165 5.99820E-12 3.04560E-07 67165.82c + 846 671660 Ho-166 1.76090E-11 1.44050E-07 671660 + 847 671661 Ho-166m 4.12440E-11 4.12440E-11 671661 + 848 671670 Ho-167 4.28520E-10 6.81760E-08 671670 + 849 671680 Ho-168 4.79830E-10 3.22520E-08 671680 + 850 671681 Ho-168m 6.80870E-10 6.80870E-10 671681 + 851 671690 Ho-169 2.99070E-09 1.52390E-08 671690 + 852 671700 Ho-170 1.88370E-09 1.88370E-09 671700 + 853 671701 Ho-170m 8.04250E-10 5.20060E-09 671701 + 854 671710 Ho-171 2.36200E-09 3.11920E-09 671710 + 855 671720 Ho-172 8.98030E-10 1.02240E-09 671720 + 856 671730 Ho-173 3.03000E-10 3.10180E-10 671730 + 857 671740 Ho-174 3.85070E-11 3.85070E-11 671740 + 858 671750 Ho-175 5.10380E-12 5.10380E-12 671750 + 859 681680 Er-168 3.27540E-12 3.22580E-08 68168.82c + 860 681690 Er-169 2.44680E-11 1.52640E-08 681690 + 861 681700 Er-170 1.37770E-10 7.22210E-09 68170.82c + 862 681710 Er-171 2.96770E-10 3.41600E-09 681710 + 863 681720 Er-172 5.86940E-10 1.60940E-09 681720 + 864 681730 Er-173 4.23070E-10 7.33250E-10 681730 + 865 681740 Er-174 2.74310E-10 3.12820E-10 681740 + 866 681750 Er-175 8.66900E-11 9.17940E-11 681750 + 867 681760 Er-176 2.49190E-11 2.49190E-11 681760 + 868 681770 Er-177 2.53720E-12 2.53720E-12 681770 + 869 691710 Tm-171 1.32240E-12 3.41730E-09 691710 + 870 691720 Tm-172 7.35150E-12 1.61670E-09 691720 + 871 691730 Tm-173 3.18250E-11 7.65080E-10 691730 + 872 691740 Tm-174 4.83400E-11 3.61160E-10 691740 + 873 691750 Tm-175 7.71480E-11 1.68940E-10 691750 + 874 691760 Tm-176 4.75330E-11 7.24520E-11 691760 + 875 691770 Tm-177 2.55490E-11 2.80860E-11 691770 + 876 691780 Tm-178 5.87120E-12 5.87120E-12 691780 + 877 691790 Tm-179 1.34990E-12 1.34990E-12 691790 + 878 701750 Yb-175 2.04650E-12 1.71300E-10 701750 + 879 701751 Yb-175m 3.12840E-13 1.30400E-10 701751 + 880 701760 Yb-176 2.98070E-12 7.66360E-11 701760 + 881 701761 Yb-176m 5.36170E-12 4.15880E-11 701761 + 882 701770 Yb-177 8.19100E-12 3.81710E-11 701770 + 883 701771 Yb-177m 1.89400E-12 2.99800E-11 701771 + 884 701780 Yb-178 1.15240E-11 1.73950E-11 701780 + 885 701790 Yb-179 5.78980E-12 7.13970E-12 701790 + 886 701800 Yb-180 2.53420E-12 2.53420E-12 701800 + 887 711790 Lu-179 1.23990E-12 8.56910E-12 711790 + 888 711791 Lu-179m 1.89540E-13 7.32920E-12 711791 + 889 711800 Lu-180 3.92610E-13 2.14530E-12 711800 + 890 711801 Lu-180m 3.92610E-13 2.92680E-12 711801 + 891 711810 Lu-181 1.29440E-12 1.29440E-12 711810 + + Neutron-induced fission: + + Interpolation region : 2 / 2 + Interpolation energy : 4.00000E-01 MeV + Number of products : 896 / 979 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 3.25860E-05 3.25860E-05 1001.82c + 2 10020 H-2 9.95850E-06 9.95850E-06 1002.82c + 3 10030 H-3 1.25000E-04 1.25000E-04 1003.82c + 4 20040 He-4 2.06000E-03 2.06000E-03 2004.82c + 5 230560 V-56 1.53460E-12 1.53460E-12 230560 + 6 230570 V-57 3.71370E-12 3.71370E-12 230570 + 7 230580 V-58 3.82800E-12 3.82800E-12 230580 + 8 230590 V-59 4.01450E-12 4.01450E-12 230590 + 9 230600 V-60 1.44150E-12 1.44150E-12 230600 + 10 240570 Cr-57 1.59220E-12 8.35350E-12 240570 + 11 240580 Cr-58 8.17940E-12 8.94500E-12 240580 + 12 240590 Cr-59 1.86390E-11 2.26540E-11 240590 + 13 240600 Cr-60 3.72570E-11 3.86980E-11 240600 + 14 240610 Cr-61 3.18100E-11 3.18100E-11 240610 + 15 240620 Cr-62 2.61610E-11 2.61610E-11 240620 + 16 240630 Cr-63 7.37670E-12 7.37670E-12 240630 + 17 240640 Cr-64 1.69810E-12 1.69810E-12 240640 + 18 250590 Mn-59 5.12120E-12 2.77750E-11 250590 + 19 250600 Mn-60 1.96900E-12 4.29710E-11 250600 + 20 250601 Mn-60m 2.00310E-11 2.00310E-11 250601 + 21 250610 Mn-61 9.39410E-11 1.25750E-10 250610 + 22 250620 Mn-62 1.50060E-10 1.63140E-10 250620 + 23 250621 Mn-62m 2.35000E-11 3.65810E-11 250621 + 24 250630 Mn-63 2.84880E-10 2.92260E-10 250630 + 25 250640 Mn-64 1.77450E-10 1.79150E-10 250640 + 26 250650 Mn-65 1.16600E-10 1.16600E-10 250650 + 27 250660 Mn-66 2.69630E-11 2.69630E-11 250660 + 28 250670 Mn-67 4.83880E-12 4.83880E-12 250670 + 29 260600 Fe-60 1.01220E-12 6.17110E-11 260600 + 30 260610 Fe-61 1.05620E-11 1.36310E-10 260610 + 31 260620 Fe-62 1.02450E-10 3.02170E-10 260620 + 32 260630 Fe-63 3.55980E-10 6.48240E-10 260630 + 33 260640 Fe-64 1.12970E-09 1.30890E-09 260640 + 34 260650 Fe-65 1.73760E-09 1.85420E-09 260650 + 35 260660 Fe-66 2.44330E-09 2.47030E-09 260660 + 36 260670 Fe-67 1.22810E-09 1.23290E-09 260670 + 37 260680 Fe-68 5.72970E-10 5.72970E-10 260680 + 38 260690 Fe-69 1.02920E-10 1.02920E-10 260690 + 39 260700 Fe-70 1.39950E-11 1.39950E-11 260700 + 40 270620 Co-62 3.09810E-13 3.02490E-10 270620 + 41 270630 Co-63 2.43570E-11 6.72590E-10 270630 + 42 270640 Co-64 1.80690E-10 1.48950E-09 270640 + 43 270650 Co-65 1.41470E-09 3.26890E-09 270650 + 44 270660 Co-66 4.21220E-09 6.68250E-09 270660 + 45 270670 Co-67 1.11280E-08 1.23610E-08 270670 + 46 270680 Co-68 7.27550E-09 1.02810E-08 270680 + 47 270681 Co-68m 5.43050E-09 6.01070E-09 270681 + 48 270690 Co-69 1.44490E-08 1.45450E-08 270690 + 49 270700 Co-70 2.83240E-09 2.83240E-09 270700 + 50 270701 Co-70m 2.83240E-09 2.84640E-09 270701 + 51 270710 Co-71 2.10150E-09 2.10150E-09 270710 + 52 270720 Co-72 4.61110E-10 4.61110E-10 270720 + 53 270730 Co-73 2.52240E-11 2.52240E-11 270730 + 54 270740 Co-74 1.06700E-12 1.06700E-12 270740 + 55 280640 Ni-64 1.76640E-12 1.49130E-09 28064.82c + 56 280650 Ni-65 3.73800E-11 3.30630E-09 280650 + 57 280660 Ni-66 6.46960E-10 7.32940E-09 280660 + 58 280670 Ni-67 3.83490E-09 1.61960E-08 280670 + 59 280680 Ni-68 2.18910E-08 3.53230E-08 280680 + 60 280690 Ni-69 2.67700E-08 4.11690E-08 280690 + 61 280691 Ni-69m 2.67700E-08 2.67700E-08 280691 + 62 280700 Ni-70 1.14820E-07 1.20500E-07 280700 + 63 280710 Ni-71 1.08950E-07 1.11050E-07 280710 + 64 280720 Ni-72 1.56790E-07 1.57250E-07 280720 + 65 280730 Ni-73 2.53230E-08 2.53480E-08 280730 + 66 280740 Ni-74 7.60480E-09 7.60590E-09 280740 + 67 280750 Ni-75 4.08800E-10 4.08800E-10 280750 + 68 280760 Ni-76 5.99570E-11 5.99570E-11 280760 + 69 280770 Ni-77 1.49300E-12 1.49300E-12 280770 + 70 290660 Cu-66 1.48050E-12 7.33090E-09 290660 + 71 290670 Cu-67 5.82370E-11 1.62540E-08 290670 + 72 290680 Cu-68 2.31820E-10 3.60850E-08 290680 + 73 290681 Cu-68m 6.31890E-10 6.31890E-10 290681 + 74 290690 Cu-69 1.17420E-08 7.96800E-08 290690 + 75 290700 Cu-70 3.70140E-09 3.04420E-08 290700 + 76 290701 Cu-70m 4.72700E-08 5.34800E-08 290701 + 77 290702 Cu-70m 3.70140E-09 1.24200E-07 290702 + 78 290710 Cu-71 2.58570E-07 3.69620E-07 290710 + 79 290720 Cu-72 8.23840E-07 9.81090E-07 290720 + 80 290730 Cu-73 7.60740E-07 7.86090E-07 290730 + 81 290740 Cu-74 6.08790E-07 6.16400E-07 290740 + 82 290750 Cu-75 2.21230E-07 2.21630E-07 290750 + 83 290760 Cu-76 4.87770E-08 4.88070E-08 290760 + 84 290761 Cu-76m 4.87770E-08 4.88070E-08 290761 + 85 290770 Cu-77 1.36690E-08 1.36700E-08 290770 + 86 290780 Cu-78 1.79460E-09 1.79460E-09 290780 + 87 290790 Cu-79 1.24970E-10 1.24970E-10 290790 + 88 300680 Zn-68 1.65270E-12 3.61880E-08 300680 + 89 300690 Zn-69 1.09600E-11 7.97460E-08 300690 + 90 300691 Zn-69m 5.44310E-11 5.44310E-11 300691 + 91 300700 Zn-70 1.95410E-09 1.77130E-07 300700 + 92 300710 Zn-71 3.85410E-09 3.73480E-07 300710 + 93 300711 Zn-71m 1.91420E-08 1.91420E-08 300711 + 94 300720 Zn-72 1.43830E-06 2.41940E-06 300720 + 95 300730 Zn-73 1.39930E-07 1.75070E-06 300730 + 96 300731 Zn-73m 1.93550E-07 8.24690E-07 300731 + 97 300732 Zn-73m 1.26230E-06 1.26230E-06 300732 + 98 300740 Zn-74 3.82430E-06 4.44850E-06 300740 + 99 300750 Zn-75 2.29480E-06 2.51010E-06 300750 + 100 300760 Zn-76 1.35180E-05 1.36140E-05 300760 + 101 300770 Zn-77 2.11930E-06 2.27410E-06 300770 + 102 300771 Zn-77m 2.82180E-07 2.82180E-07 300771 + 103 300780 Zn-78 1.16010E-05 1.16030E-05 300780 + 104 300790 Zn-79 4.68870E-06 4.68880E-06 300790 + 105 300800 Zn-80 7.25040E-08 7.25040E-08 300800 + 106 300810 Zn-81 4.14920E-09 4.14920E-09 300810 + 107 300820 Zn-82 1.35820E-10 1.35820E-10 300820 + 108 310710 Ga-71 7.04490E-11 3.92690E-07 310710 + 109 310720 Ga-72 3.08520E-09 2.42280E-06 310720 + 110 310721 Ga-72m 3.03270E-10 8.09190E-08 310721 + 111 310730 Ga-73 4.10820E-08 2.42290E-06 310730 + 112 310740 Ga-74 1.97430E-07 3.68190E-06 310740 + 113 310741 Ga-74m 1.97430E-07 4.64590E-06 310741 + 114 310750 Ga-75 2.29480E-06 4.80490E-06 310750 + 115 310760 Ga-76 4.50610E-06 1.81200E-05 310760 + 116 310770 Ga-77 1.68100E-05 1.92250E-05 310770 + 117 310780 Ga-78 3.01640E-05 4.18280E-05 310780 + 118 310790 Ga-79 2.81310E-05 3.27590E-05 310790 + 119 310800 Ga-80 3.15690E-05 3.16420E-05 310800 + 120 310810 Ga-81 2.01690E-05 2.01730E-05 310810 + 121 310820 Ga-82 4.10930E-06 4.10940E-06 310820 + 122 310830 Ga-83 1.48470E-07 1.48470E-07 310830 + 123 310840 Ga-84 4.78370E-09 4.78370E-09 310840 + 124 320720 Ge-72 1.20870E-12 2.42280E-06 32072.82c + 125 320730 Ge-73 3.70460E-11 2.42300E-06 32073.82c + 126 320731 Ge-73m 7.45900E-12 2.38740E-06 320731 + 127 320740 Ge-74 2.95120E-09 4.84630E-06 32074.82c + 128 320750 Ge-75 4.09240E-09 4.83970E-06 320750 + 129 320751 Ge-75m 3.07370E-08 2.22930E-07 320751 + 130 320760 Ge-76 1.14790E-06 1.92680E-05 32076.82c + 131 320770 Ge-77 6.35800E-06 1.01720E-05 320770 + 132 320771 Ge-77m 8.46530E-07 2.00720E-05 320771 + 133 320780 Ge-78 6.03320E-05 1.02190E-04 320780 + 134 320790 Ge-79 2.34150E-05 6.31320E-05 320790 + 135 320791 Ge-79m 1.75870E-04 1.75910E-04 320791 + 136 320800 Ge-80 3.67780E-04 4.01820E-04 320800 + 137 320810 Ge-81 4.66670E-04 4.77520E-04 320810 + 138 320811 Ge-81m 9.39620E-05 1.02790E-04 320811 + 139 320820 Ge-82 5.61000E-04 5.64290E-04 320820 + 140 320830 Ge-83 2.48630E-04 2.48730E-04 320830 + 141 320840 Ge-84 7.35780E-05 7.35790E-05 320840 + 142 320850 Ge-85 9.42680E-06 9.42680E-06 320850 + 143 320860 Ge-86 1.36470E-06 1.36470E-06 320860 + 144 320870 Ge-87 1.42980E-09 1.42980E-09 320870 + 145 330750 As-75 4.21850E-12 4.83980E-06 33075.82c + 146 330751 As-75m 1.59750E-11 8.28560E-11 330751 + 147 330760 As-76 1.99590E-09 1.99590E-09 330760 + 148 330770 As-77 6.13520E-08 2.64910E-05 330770 + 149 330780 As-78 1.78100E-06 1.03970E-04 330780 + 150 330790 As-79 1.64110E-05 2.48420E-04 330790 + 151 330800 As-80 8.12020E-05 4.83020E-04 330800 + 152 330810 As-81 3.93790E-04 9.73070E-04 330810 + 153 330820 As-82 1.86330E-04 7.50620E-04 330820 + 154 330821 As-82m 6.49220E-04 6.49220E-04 330821 + 155 330830 As-83 2.07220E-03 2.32890E-03 330830 + 156 330840 As-84 6.55800E-04 6.89280E-04 330840 + 157 330841 As-84m 6.55800E-04 6.89280E-04 330841 + 158 330850 As-85 7.15720E-04 7.23830E-04 330850 + 159 330860 As-86 1.82590E-04 1.83950E-04 330860 + 160 330870 As-87 4.24070E-05 4.24080E-05 330870 + 161 330880 As-88 1.85090E-06 1.85090E-06 330880 + 162 330890 As-89 1.99760E-08 1.99760E-08 330890 + 163 340770 Se-77 1.40340E-12 2.64910E-05 34077.82c + 164 340771 Se-77m 1.05410E-11 1.05410E-11 340771 + 165 340780 Se-78 2.57760E-09 1.03970E-04 34078.82c + 166 340790 Se-79 1.05440E-07 2.48400E-04 34079.82c + 167 340791 Se-79m 1.40390E-08 2.42550E-04 340791 + 168 340800 Se-80 1.12650E-05 4.94290E-04 34080.82c + 169 340810 Se-81 1.46090E-05 1.09730E-03 340810 + 170 340811 Se-81m 1.09720E-04 1.44650E-04 340811 + 171 340820 Se-82 5.40600E-04 1.94040E-03 34082.82c + 172 340830 Se-83 2.06570E-03 2.90500E-03 340830 + 173 340831 Se-83m 4.15920E-04 1.90740E-03 340831 + 174 340840 Se-84 5.76790E-03 7.30380E-03 340840 + 175 340850 Se-85 5.99400E-03 6.61930E-03 340850 + 176 340860 Se-86 5.17580E-03 5.30560E-03 340860 + 177 340870 Se-87 2.66210E-03 2.69800E-03 340870 + 178 340880 Se-88 1.11780E-03 1.11970E-03 340880 + 179 340890 Se-89 2.06620E-04 2.06640E-04 340890 + 180 340900 Se-90 6.30270E-05 6.30270E-05 340900 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1.50200E-04 350920 + 201 350930 Br-93 3.38920E-05 3.38920E-05 350930 + 202 350940 Br-94 6.00030E-08 6.00030E-08 350940 + 203 350950 Br-95 1.79000E-09 1.79000E-09 350950 + 204 360820 Kr-82 7.47040E-10 4.11000E-06 36082.82c + 205 360830 Kr-83 6.12400E-08 4.90140E-03 36083.82c + 206 360831 Kr-83m 1.23300E-08 4.89700E-03 360831 + 207 360840 Kr-84 1.73860E-05 7.87710E-03 36084.82c + 208 360850 Kr-85 1.88260E-04 2.18110E-03 36085.82c + 209 360851 Kr-85m 3.79040E-05 9.24220E-03 360851 + 210 360860 Kr-86 1.93380E-03 1.33730E-02 36086.82c + 211 360870 Kr-87 5.78610E-03 1.73370E-02 360870 + 212 360880 Kr-88 1.44250E-02 2.16900E-02 360880 + 213 360890 Kr-89 1.45580E-02 1.82480E-02 360890 + 214 360900 Kr-90 2.28590E-02 2.47700E-02 360900 + 215 360910 Kr-91 1.55120E-02 1.63710E-02 360910 + 216 360920 Kr-92 8.80660E-03 8.93010E-03 360920 + 217 360930 Kr-93 3.11150E-03 3.12240E-03 360930 + 218 360940 Kr-94 8.21260E-04 8.21280E-04 360940 + 219 360950 Kr-95 1.23950E-04 1.23950E-04 360950 + 220 360960 Kr-96 2.44940E-05 2.44940E-05 360960 + 221 360970 Kr-97 1.23680E-08 1.23680E-08 360970 + 222 370840 Rb-84 6.71390E-11 2.07990E-10 370840 + 223 370841 Rb-84m 1.40850E-10 1.40850E-10 370841 + 224 370850 Rb-85 2.24590E-08 9.44550E-03 37085.82c + 225 370860 Rb-86 1.32190E-06 4.09500E-06 37086.82c + 226 370861 Rb-86m 2.77310E-06 2.77310E-06 370861 + 227 370870 Rb-87 1.10130E-04 1.74470E-02 37087.82c + 228 370880 Rb-88 4.30200E-04 2.21200E-02 370880 + 229 370890 Rb-89 1.96780E-03 2.02160E-02 370890 + 230 370900 Rb-90 6.62620E-04 2.24520E-02 370900 + 231 370901 Rb-90m 6.74100E-03 9.98090E-03 370901 + 232 370910 Rb-91 1.83770E-02 3.47480E-02 370910 + 233 370920 Rb-92 2.08620E-02 2.97920E-02 370920 + 234 370930 Rb-93 2.07610E-02 2.38930E-02 370930 + 235 370940 Rb-94 9.91370E-03 1.07290E-02 370940 + 236 370950 Rb-95 5.88380E-03 6.00510E-03 370950 + 237 370960 Rb-96 7.59750E-04 1.15730E-03 370960 + 238 370961 Rb-96m 7.59750E-04 7.71540E-04 370961 + 239 370970 Rb-97 4.11510E-04 4.11520E-04 370970 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1.54070E-05 381010 + 260 381020 Sr-102 2.27470E-08 2.27470E-08 381020 + 261 390890 Y-89 1.01450E-10 2.02900E-02 39089.82c + 262 390891 Y-89m 5.03840E-10 1.95630E-06 390891 + 263 390900 Y-90 1.56110E-08 3.31610E-02 39090.82c + 264 390901 Y-90m 2.61080E-08 2.61080E-08 390901 + 265 390910 Y-91 5.04780E-06 3.86330E-02 39091.82c + 266 390911 Y-91m 2.50700E-05 2.27370E-02 390911 + 267 390920 Y-92 1.87490E-04 4.48670E-02 390920 + 268 390930 Y-93 1.62630E-04 5.23430E-02 390930 + 269 390931 Y-93m 1.22150E-03 1.39730E-02 390931 + 270 390940 Y-94 3.70860E-03 5.08000E-02 390940 + 271 390950 Y-95 1.43830E-02 5.54530E-02 390950 + 272 390960 Y-96 6.91370E-03 3.49940E-02 390960 + 273 390961 Y-96m 1.45040E-02 1.45080E-02 390961 + 274 390970 Y-97 5.71530E-03 1.71860E-02 390970 + 275 390971 Y-97m 2.11260E-02 2.89030E-02 390971 + 276 390972 Y-97m 7.26010E-03 7.26010E-03 390972 + 277 390980 Y-98 3.99680E-03 8.79890E-03 390980 + 278 390981 Y-98m 1.93760E-02 1.93760E-02 390981 + 279 390990 Y-99 2.15620E-02 2.27670E-02 390990 + 280 391000 Y-100 3.43670E-03 3.69490E-03 391000 + 281 391001 Y-100m 3.43670E-03 3.43690E-03 391001 + 282 391010 Y-101 2.66030E-03 2.67530E-03 391010 + 283 391020 Y-102 2.43020E-04 2.43030E-04 391020 + 284 391021 Y-102m 2.43020E-04 2.43030E-04 391021 + 285 391030 Y-103 8.00310E-05 8.00310E-05 391030 + 286 391040 Y-104 4.82070E-06 4.82070E-06 391040 + 287 391050 Y-105 1.84560E-09 1.84560E-09 391050 + 288 400920 Zr-92 8.74260E-07 4.48680E-02 40092.82c + 289 400930 Zr-93 2.59150E-05 5.23690E-02 40093.82c + 290 400940 Zr-94 2.48120E-04 5.10480E-02 40094.82c + 291 400950 Zr-95 1.26180E-03 5.67150E-02 40095.82c + 292 400960 Zr-96 6.21340E-03 5.57390E-02 40096.82c + 293 400970 Zr-97 1.50570E-02 6.30640E-02 400970 + 294 400980 Zr-98 3.21740E-02 6.00460E-02 400980 + 295 400990 Zr-99 4.61650E-02 6.85800E-02 400990 + 296 401000 Zr-100 4.30270E-02 5.01250E-02 401000 + 297 401010 Zr-101 2.48230E-02 2.75220E-02 401010 + 298 401020 Zr-102 1.42640E-02 1.47330E-02 401020 + 299 401030 Zr-103 4.07800E-03 4.15210E-03 401030 + 300 401040 Zr-104 1.16310E-03 1.16750E-03 401040 + 301 401050 Zr-105 1.18520E-04 1.18520E-04 401050 + 302 401060 Zr-106 1.48120E-05 1.48120E-05 401060 + 303 401070 Zr-107 6.36570E-09 6.36570E-09 401070 + 304 410950 Nb-95 2.87340E-06 5.66840E-02 41095.82c + 305 410951 Nb-95m 5.78540E-07 6.13290E-04 410951 + 306 410960 Nb-96 3.63470E-05 3.63470E-05 410960 + 307 410970 Nb-97 3.12910E-04 6.34400E-02 410970 + 308 410971 Nb-97m 6.30020E-05 6.00040E-02 410971 + 309 410980 Nb-98 3.06940E-04 6.03530E-02 410980 + 310 410981 Nb-98m 1.06950E-03 1.06950E-03 410981 + 311 410990 Nb-99 6.94180E-03 5.08170E-02 410990 + 312 410991 Nb-99m 1.39770E-03 2.66350E-02 410991 + 313 411000 Nb-100 2.44910E-03 5.25740E-02 411000 + 314 411001 Nb-100m 1.18730E-02 1.18730E-02 411001 + 315 411010 Nb-101 2.97530E-02 5.72750E-02 411010 + 316 411020 Nb-102 1.47640E-02 2.94970E-02 411020 + 317 411021 Nb-102m 1.47640E-02 1.47640E-02 411021 + 318 411030 Nb-103 2.72840E-02 3.14360E-02 411030 + 319 411040 Nb-104 6.12300E-03 7.29220E-03 411040 + 320 411041 Nb-104m 6.12300E-03 6.12300E-03 411041 + 321 411050 Nb-105 5.44810E-03 5.56520E-03 411050 + 322 411060 Nb-106 1.43410E-03 1.44870E-03 411060 + 323 411070 Nb-107 2.69600E-04 2.69610E-04 411070 + 324 411080 Nb-108 1.64510E-05 1.64510E-05 411080 + 325 411090 Nb-109 2.65250E-06 2.65250E-06 411090 + 326 411100 Nb-110 8.42890E-11 8.42890E-11 411100 + 327 420970 Mo-97 2.78500E-06 6.34420E-02 42097.82c + 328 420980 Mo-98 4.23480E-05 6.14650E-02 42098.82c + 329 420990 Mo-99 3.19360E-04 7.72380E-02 42099.82c + 330 421000 Mo-100 1.72780E-03 6.61750E-02 42100.82c + 331 421010 Mo-101 5.13070E-03 6.24060E-02 421010 + 332 421020 Mo-102 1.48710E-02 5.91330E-02 421020 + 333 421030 Mo-103 2.08060E-02 5.22490E-02 421030 + 334 421040 Mo-104 2.56790E-02 3.91810E-02 421040 + 335 421050 Mo-105 1.70410E-02 2.25770E-02 421050 + 336 421060 Mo-106 1.21220E-02 1.35220E-02 421060 + 337 421070 Mo-107 4.11030E-03 4.36470E-03 421070 + 338 421080 Mo-108 1.01710E-03 1.03290E-03 421080 + 339 421090 Mo-109 1.30230E-04 1.32550E-04 421090 + 340 421100 Mo-110 2.09100E-05 2.09100E-05 421100 + 341 421110 Mo-111 4.45990E-06 4.45990E-06 421110 + 342 421120 Mo-112 5.15070E-10 5.15070E-10 421120 + 343 431000 Tc-100 8.64960E-06 8.64960E-06 431000 + 344 431010 Tc-101 6.36780E-05 6.24690E-02 431010 + 345 431020 Tc-102 1.62750E-04 5.92950E-02 431020 + 346 431021 Tc-102m 1.62750E-04 1.62750E-04 431021 + 347 431030 Tc-103 1.49910E-03 5.37490E-02 431030 + 348 431040 Tc-104 3.13850E-03 4.23200E-02 431040 + 349 431050 Tc-105 6.73020E-03 2.93070E-02 431050 + 350 431060 Tc-106 7.61000E-03 2.11320E-02 431060 + 351 431070 Tc-107 8.17370E-03 1.25380E-02 431070 + 352 431080 Tc-108 3.77570E-03 4.80930E-03 431080 + 353 431090 Tc-109 1.69970E-03 1.83150E-03 431090 + 354 431100 Tc-110 5.09470E-04 5.30430E-04 431100 + 355 431110 Tc-111 1.34150E-04 1.38560E-04 431110 + 356 431120 Tc-112 1.99950E-05 1.99950E-05 431120 + 357 431130 Tc-113 4.90160E-06 4.90160E-06 431130 + 358 431140 Tc-114 1.95310E-09 1.95310E-09 431140 + 359 431150 Tc-115 4.12360E-11 4.12360E-11 431150 + 360 441020 Ru-102 3.31360E-06 5.94620E-02 44102.82c + 361 441030 Ru-103 7.85950E-06 5.37780E-02 44103.82c + 362 441031 Ru-103m 2.19900E-05 2.19900E-05 441031 + 363 441040 Ru-104 1.77440E-04 4.24970E-02 44104.82c + 364 441050 Ru-105 3.68570E-04 2.96760E-02 44105.82c + 365 441060 Ru-106 1.20090E-03 2.23330E-02 44106.82c + 366 441070 Ru-107 1.60890E-03 1.41470E-02 441070 + 367 441080 Ru-108 1.79290E-03 6.60360E-03 441080 + 368 441090 Ru-109 1.16270E-03 2.99300E-03 441090 + 369 441100 Ru-110 9.63900E-04 1.49410E-03 441100 + 370 441110 Ru-111 4.85050E-04 6.23910E-04 441110 + 371 441120 Ru-112 2.89630E-04 3.09680E-04 441120 + 372 441130 Ru-113 4.16500E-05 6.70240E-05 441130 + 373 441131 Ru-113m 4.16500E-05 4.16500E-05 441131 + 374 441140 Ru-114 3.24650E-05 3.24670E-05 441140 + 375 441150 Ru-115 6.07400E-06 6.07400E-06 441150 + 376 441160 Ru-116 2.15900E-08 2.15900E-08 441160 + 377 441170 Ru-117 4.01180E-10 4.01180E-10 441170 + 378 441200 Ru-120 1.25580E-09 1.25580E-09 441200 + 379 451050 Rh-105 1.13730E-06 2.96770E-02 45105.82c + 380 451051 Rh-105m 1.51420E-07 8.42440E-03 451051 + 381 451060 Rh-106 2.20830E-06 2.23350E-02 451060 + 382 451061 Rh-106m 6.01920E-06 6.01920E-06 451061 + 383 451070 Rh-107 4.10660E-05 1.41880E-02 451070 + 384 451080 Rh-108 1.83150E-05 6.62190E-03 451080 + 385 451081 Rh-108m 6.38170E-05 6.38170E-05 451081 + 386 451090 Rh-109 1.66750E-04 3.15970E-03 451090 + 387 451100 Rh-110 1.52990E-04 1.64710E-03 451100 + 388 451101 Rh-110m 3.60160E-06 3.60160E-06 451101 + 389 451110 Rh-111 2.89650E-04 9.13560E-04 451110 + 390 451120 Rh-112 1.32400E-04 4.42080E-04 451120 + 391 451121 Rh-112m 1.32400E-04 1.32400E-04 451121 + 392 451130 Rh-113 2.59730E-04 3.47580E-04 451130 + 393 451140 Rh-114 1.00090E-04 1.32580E-04 451140 + 394 451141 Rh-114m 1.00090E-04 1.00090E-04 451141 + 395 451150 Rh-115 1.30570E-04 1.36630E-04 451150 + 396 451160 Rh-116 1.41380E-05 1.41590E-05 451160 + 397 451161 Rh-116m 3.85370E-05 3.85370E-05 451161 + 398 451170 Rh-117 3.23430E-05 3.23430E-05 451170 + 399 451180 Rh-118 6.74640E-06 6.74640E-06 451180 + 400 451190 Rh-119 4.35170E-09 4.35170E-09 451190 + 401 451200 Rh-120 2.28270E-06 2.28400E-06 451200 + 402 451210 Rh-121 2.06830E-07 2.06830E-07 451210 + 403 451220 Rh-122 7.49650E-09 7.49650E-09 451220 + 404 461070 Pd-107 2.48820E-10 1.41880E-02 46107.82c + 405 461071 Pd-107m 5.46890E-10 5.46890E-10 461071 + 406 461080 Pd-108 2.28200E-08 6.68580E-03 46108.82c + 407 461090 Pd-109 9.02080E-08 3.16000E-03 461090 + 408 461091 Pd-109m 1.98270E-07 1.58010E-03 461091 + 409 461100 Pd-110 6.96630E-06 1.65770E-03 46110.82c + 410 461110 Pd-111 4.18330E-06 9.23470E-04 461110 + 411 461111 Pd-111m 9.19470E-06 1.28490E-05 461111 + 412 461120 Pd-112 6.49610E-05 6.39450E-04 461120 + 413 461130 Pd-113 2.64590E-05 4.48070E-04 461130 + 414 461131 Pd-113m 7.40310E-05 7.40310E-05 461131 + 415 461140 Pd-114 1.54250E-04 3.86920E-04 461140 + 416 461150 Pd-115 6.93320E-05 1.99900E-04 461150 + 417 461151 Pd-115m 1.52390E-04 1.72230E-04 461151 + 418 461160 Pd-116 2.97450E-04 3.50150E-04 461160 + 419 461170 Pd-117 5.56200E-05 2.10410E-04 461170 + 420 461171 Pd-117m 1.22250E-04 1.22250E-04 461171 + 421 461180 Pd-118 1.31520E-04 1.38070E-04 461180 + 422 461190 Pd-119 8.40770E-05 8.42170E-05 461190 + 423 461200 Pd-120 1.80460E-05 2.02230E-05 461200 + 424 461210 Pd-121 3.68870E-06 3.86750E-06 461210 + 425 461220 Pd-122 3.73520E-06 3.74270E-06 461220 + 426 461230 Pd-123 8.12260E-07 8.12260E-07 461230 + 427 461240 Pd-124 5.70050E-08 5.70050E-08 461240 + 428 471100 Ag-110 1.24430E-10 1.29040E-10 471100 + 429 471101 Ag-110m 3.39160E-10 3.39160E-10 47510.82c + 430 471110 Ag-111 1.77440E-09 9.22360E-04 47111.82c + 431 471111 Ag-111m 1.33270E-08 9.19450E-04 471111 + 432 471120 Ag-112 2.10040E-07 6.39660E-04 471120 + 433 471130 Ag-113 5.75890E-07 2.96950E-04 471130 + 434 471131 Ag-113m 4.32530E-06 4.33390E-04 471131 + 435 471140 Ag-114 2.77620E-06 4.03160E-04 471140 + 436 471141 Ag-114m 1.34590E-05 1.34590E-05 471141 + 437 471150 Ag-115 9.27970E-06 2.14450E-04 471150 + 438 471151 Ag-115m 6.96960E-05 2.82120E-04 471151 + 439 471160 Ag-116 2.99480E-05 3.84990E-04 471160 + 440 471161 Ag-116m 8.16320E-05 8.16320E-05 471161 + 441 471170 Ag-117 2.28080E-05 1.44600E-04 471170 + 442 471171 Ag-117m 1.71300E-04 2.76510E-04 471171 + 443 471180 Ag-118 5.07630E-05 2.78090E-04 471180 + 444 471181 Ag-118m 2.46100E-04 2.65840E-04 471181 + 445 471190 Ag-119 3.45810E-05 7.66900E-05 471190 + 446 471191 Ag-119m 2.59730E-04 3.01840E-04 471191 + 447 471200 Ag-120 7.15660E-05 1.29710E-04 471200 + 448 471201 Ag-120m 1.19680E-04 1.29800E-04 471201 + 449 471210 Ag-121 1.51200E-04 1.55060E-04 471210 + 450 471220 Ag-122 1.61760E-05 1.99180E-05 471220 + 451 471221 Ag-122m 1.74400E-05 1.74400E-05 471221 + 452 471230 Ag-123 1.87560E-05 1.95680E-05 471230 + 453 471240 Ag-124 9.59460E-06 1.48240E-05 471240 + 454 471241 Ag-124m 1.03440E-05 1.03440E-05 471241 + 455 471250 Ag-125 6.17850E-06 6.17850E-06 471250 + 456 471260 Ag-126 6.29440E-07 6.29440E-07 471260 + 457 471270 Ag-127 9.53900E-08 9.53900E-08 471270 + 458 471280 Ag-128 3.03440E-09 3.03440E-09 471280 + 459 481120 Cd-112 2.23940E-11 6.39660E-04 48112.82c + 460 481130 Cd-113 1.84660E-10 4.47840E-04 48113.82c + 461 481131 Cd-113m 6.99320E-10 5.13470E-06 481131 + 462 481140 Cd-114 3.40350E-08 4.03190E-04 48114.82c + 463 481150 Cd-115 1.17960E-07 4.18600E-04 481150 + 464 481151 Cd-115m 4.46720E-07 1.92930E-05 48515.82c + 465 481160 Cd-116 9.29670E-06 4.71020E-04 48116.82c + 466 481170 Cd-117 5.40610E-06 3.21060E-04 481170 + 467 481171 Cd-117m 2.04730E-05 1.09340E-04 481171 + 468 481180 Cd-118 8.09720E-05 5.15900E-04 481180 + 469 481190 Cd-119 3.59880E-05 3.76170E-04 481190 + 470 481191 Cd-119m 1.00690E-04 1.39040E-04 481191 + 471 481200 Cd-120 2.56310E-04 4.67790E-04 481200 + 472 481210 Cd-121 6.50770E-05 2.03930E-04 481210 + 473 481211 Cd-121m 1.82080E-04 1.98280E-04 481211 + 474 481220 Cd-122 3.02540E-04 3.39900E-04 481220 + 475 481230 Cd-123 3.95080E-05 5.55260E-05 481230 + 476 481231 Cd-123m 1.10540E-04 1.14110E-04 481231 + 477 481240 Cd-124 1.47850E-04 1.67830E-04 481240 + 478 481250 Cd-125 4.09540E-05 4.40430E-05 481250 + 479 481251 Cd-125m 1.14590E-04 1.17680E-04 481251 + 480 481260 Cd-126 1.49680E-04 1.50310E-04 481260 + 481 481270 Cd-127 1.15340E-04 1.15430E-04 481270 + 482 481280 Cd-128 4.69890E-05 4.69920E-05 481280 + 483 481290 Cd-129 2.61230E-06 2.61230E-06 481290 + 484 481291 Cd-129m 7.30920E-06 7.30920E-06 481291 + 485 481300 Cd-130 2.68490E-06 2.68490E-06 481300 + 486 481310 Cd-131 2.16150E-09 2.16150E-09 481310 + 487 491150 In-115 9.15310E-11 4.16960E-04 49115.82c + 488 491151 In-115m 1.84290E-11 4.18600E-04 491151 + 489 491160 In-116 9.96410E-10 9.96410E-10 491160 + 490 491161 In-116m 1.60900E-09 3.47180E-09 491161 + 491 491162 In-116m 1.86280E-09 1.86280E-09 491162 + 492 491170 In-117 1.11340E-07 2.73990E-04 491170 + 493 491171 In-117m 2.24180E-08 2.95920E-04 491171 + 494 491180 In-118 4.15740E-07 5.16320E-04 491180 + 495 491181 In-118m 6.71330E-07 1.43770E-06 491181 + 496 491182 In-118m 7.77230E-07 7.77230E-07 491182 + 497 491190 In-119 2.91660E-06 1.97290E-04 491190 + 498 491191 In-119m 5.87250E-07 3.40490E-04 491191 + 499 491200 In-120 1.08280E-05 4.78620E-04 491200 + 500 491201 In-120m 1.08280E-05 1.08280E-05 491201 + 501 491202 In-120m 1.08280E-05 1.08280E-05 491202 + 502 491210 In-121 7.98500E-05 3.48630E-04 491210 + 503 491211 In-121m 1.60770E-05 1.51330E-04 491211 + 504 491220 In-122 7.97010E-05 4.19600E-04 491220 + 505 491221 In-122m 6.66450E-05 6.66450E-05 491221 + 506 491222 In-122m 6.66450E-05 6.66450E-05 491222 + 507 491230 In-123 2.46840E-04 3.76750E-04 491230 + 508 491231 In-123m 4.97000E-05 8.94190E-05 491231 + 509 491240 In-124 1.14620E-04 2.82450E-04 491240 + 510 491241 In-124m 1.23580E-04 1.23580E-04 491241 + 511 491250 In-125 4.42060E-04 5.80820E-04 491250 + 512 491251 In-125m 8.90070E-05 1.11970E-04 491251 + 513 491260 In-126 3.67920E-04 5.18230E-04 491260 + 514 491261 In-126m 3.96670E-04 3.96670E-04 491261 + 515 491270 In-127 1.76690E-03 1.76690E-03 491270 + 516 491271 In-127m 3.55770E-04 4.71200E-04 491271 + 517 491280 In-128 6.20780E-04 9.10840E-04 491280 + 518 491281 In-128m 2.43070E-04 2.90060E-04 491281 + 519 491282 In-128m 9.31350E-04 9.31350E-04 491282 + 520 491290 In-129 1.57120E-03 1.57850E-03 491290 + 521 491291 In-129m 3.16340E-04 3.19000E-04 491291 + 522 491300 In-130 1.37810E-04 1.40400E-04 491300 + 523 491301 In-130m 2.00660E-04 2.00660E-04 491301 + 524 491302 In-130m 2.79510E-04 2.79510E-04 491302 + 525 491310 In-131 7.26930E-05 7.34350E-05 491310 + 526 491311 In-131m 7.26930E-05 7.26930E-05 491311 + 527 491312 In-131m 7.26930E-05 7.26930E-05 491312 + 528 491320 In-132 1.57270E-05 1.57270E-05 491320 + 529 491330 In-133 3.71740E-08 4.46590E-08 491330 + 530 491331 In-133m 7.48490E-09 7.48490E-09 491331 + 531 501170 Sn-117 2.53960E-12 4.30530E-04 50117.82c + 532 501171 Sn-117m 9.61740E-12 9.33530E-07 501171 + 533 501180 Sn-118 8.67440E-10 5.17770E-04 50118.82c + 534 501190 Sn-119 5.47070E-09 5.18740E-04 50119.82c + 535 501191 Sn-119m 2.07170E-08 1.78250E-04 501191 + 536 501210 Sn-121 8.15180E-11 4.89300E-04 501210 + 537 501211 Sn-121m 2.28080E-10 3.94950E-05 501211 + 538 501220 Sn-122 1.12030E-05 5.64090E-04 50122.82c + 539 501230 Sn-123 2.20940E-05 5.08180E-05 50123.82c + 540 501231 Sn-123m 7.89640E-06 4.45340E-04 501231 + 541 501240 Sn-124 1.18670E-04 5.24700E-04 50124.82c + 542 501250 Sn-125 1.46690E-04 2.44800E-04 50125.82c + 543 501251 Sn-125m 5.24280E-05 6.47110E-04 501251 + 544 501260 Sn-126 5.59550E-04 1.47770E-03 50126.82c + 545 501270 Sn-127 1.46170E-03 2.15040E-03 501270 + 546 501271 Sn-127m 5.22410E-04 2.06860E-03 501271 + 547 501280 Sn-128 1.39850E-03 7.05270E-03 501280 + 548 501281 Sn-128m 3.81200E-03 4.74340E-03 501281 + 549 501290 Sn-129 2.26220E-03 3.99180E-03 501290 + 550 501291 Sn-129m 6.32970E-03 6.49770E-03 501291 + 551 501300 Sn-130 2.38970E-03 2.76970E-03 501300 + 552 501301 Sn-130m 6.51380E-03 6.75580E-03 501301 + 553 501310 Sn-131 1.44600E-03 1.58680E-03 501310 + 554 501311 Sn-131m 4.04590E-03 4.12170E-03 501311 + 555 501320 Sn-132 2.31520E-03 2.33100E-03 501320 + 556 501330 Sn-133 2.43130E-04 2.43140E-04 501330 + 557 501340 Sn-134 3.40080E-05 3.40080E-05 501340 + 558 501350 Sn-135 3.49700E-07 3.49700E-07 501350 + 559 501360 Sn-136 7.22000E-09 7.22000E-09 501360 + 560 511230 Sb-123 3.11260E-11 4.96160E-04 51123.82c + 561 511240 Sb-124 1.16320E-06 2.99360E-06 51124.82c + 562 511241 Sb-124m 9.38330E-07 2.44060E-06 511241 + 563 511242 Sb-124m 1.50230E-06 1.50230E-06 511242 + 564 511250 Sb-125 3.32800E-05 9.25190E-04 51125.82c + 565 511260 Sb-126 1.76240E-05 2.10760E-05 51126.82c + 566 511261 Sb-126m 1.10080E-05 2.46540E-05 511261 + 567 511262 Sb-126m 1.36460E-05 1.36460E-05 511262 + 568 511270 Sb-127 2.41220E-04 4.46020E-03 511270 + 569 511280 Sb-128 3.37220E-04 7.40690E-03 511280 + 570 511281 Sb-128m 4.71650E-04 4.71650E-04 511281 + 571 511290 Sb-129 3.35060E-03 1.14510E-02 511290 + 572 511291 Sb-129m 2.47960E-03 5.72840E-03 511291 + 573 511300 Sb-130 4.90200E-03 1.10500E-02 511300 + 574 511301 Sb-130m 4.90200E-03 8.27990E-03 511301 + 575 511310 Sb-131 2.65410E-02 3.22500E-02 511310 + 576 511320 Sb-132 1.33380E-02 1.56690E-02 511320 + 577 511321 Sb-132m 1.18090E-02 1.18090E-02 511321 + 578 511330 Sb-133 2.63650E-02 2.66140E-02 511330 + 579 511340 Sb-134 1.72890E-03 1.75710E-03 511340 + 580 511341 Sb-134m 4.71240E-03 4.71250E-03 511341 + 581 511350 Sb-135 1.51460E-03 1.51490E-03 511350 + 582 511360 Sb-136 2.30120E-04 2.30120E-04 511360 + 583 511370 Sb-137 2.33490E-05 2.33490E-05 511370 + 584 511380 Sb-138 4.48920E-08 4.48920E-08 511380 + 585 521260 Te-126 9.01660E-10 4.22790E-05 52126.82c + 586 521270 Te-127 1.55530E-06 4.44840E-03 521270 + 587 521271 Te-127m 4.35180E-06 7.39370E-04 52527.82c + 588 521280 Te-128 2.34690E-05 7.88500E-03 52128.82c + 589 521290 Te-129 5.89320E-05 1.40200E-02 521290 + 590 521291 Te-129m 1.64890E-04 6.82020E-03 52529.82c + 591 521300 Te-130 1.54350E-03 2.08730E-02 52130.82c + 592 521310 Te-131 1.36700E-03 3.23800E-02 521310 + 593 521311 Te-131m 3.82490E-03 6.40680E-03 521311 + 594 521320 Te-132 1.87190E-02 4.61970E-02 52132.82c + 595 521330 Te-133 8.73730E-03 3.58360E-02 521330 + 596 521331 Te-133m 2.44470E-02 2.90500E-02 521331 + 597 521340 Te-134 4.72780E-02 5.39820E-02 521340 + 598 521350 Te-135 1.53800E-02 1.66950E-02 521350 + 599 521360 Te-136 7.31270E-03 7.51610E-03 521360 + 600 521370 Te-137 1.18890E-03 1.20080E-03 521370 + 601 521380 Te-138 3.57510E-04 3.57560E-04 521380 + 602 521390 Te-139 2.17540E-05 2.17540E-05 521390 + 603 521400 Te-140 6.06880E-06 6.06880E-06 521400 + 604 521410 Te-141 5.55160E-09 5.55160E-09 521410 + 605 531280 I-128 4.04590E-10 4.04590E-10 531280 + 606 531290 I-129 5.49270E-08 1.65430E-02 53129.82c + 607 531300 I-130 7.85670E-06 1.02780E-05 53130.82c + 608 531301 I-130m 2.88240E-06 2.88240E-06 531301 + 609 531310 I-131 1.62350E-04 3.76040E-02 53131.82c + 610 531320 I-132 4.47420E-04 4.69850E-02 531320 + 611 531321 I-132m 3.96130E-04 3.96130E-04 531321 + 612 531330 I-133 4.12180E-03 6.69740E-02 531330 + 613 531331 I-133m 3.05030E-03 3.05030E-03 531331 + 614 531340 I-134 1.01460E-02 7.29030E-02 531340 + 615 531341 I-134m 8.98250E-03 8.98250E-03 531341 + 616 531350 I-135 5.66220E-02 7.33170E-02 53135.82c + 617 531360 I-136 1.20210E-02 1.95550E-02 531360 + 618 531361 I-136m 3.27660E-02 3.27840E-02 531361 + 619 531370 I-137 3.60070E-02 3.71940E-02 531370 + 620 531380 I-138 1.31410E-02 1.34760E-02 531380 + 621 531390 I-139 8.50010E-03 8.52180E-03 531390 + 622 531400 I-140 1.87940E-03 1.88550E-03 531400 + 623 531410 I-141 3.41720E-04 3.41730E-04 531410 + 624 531420 I-142 3.68860E-05 3.68860E-05 531420 + 625 531430 I-143 3.69460E-06 3.69460E-06 531430 + 626 531440 I-144 1.07280E-09 1.07280E-09 531440 + 627 541310 Xe-131 3.41470E-09 3.76040E-02 54131.82c + 628 541311 Xe-131m 9.55430E-09 4.08460E-04 541311 + 629 541320 Xe-132 3.10090E-06 4.70480E-02 54132.82c + 630 541321 Xe-132m 4.15430E-06 4.15430E-06 541321 + 631 541330 Xe-133 1.24480E-05 6.70220E-02 54133.82c + 632 541331 Xe-133m 3.48270E-05 1.94120E-03 541331 + 633 541340 Xe-134 1.47340E-04 7.36590E-02 54134.82c + 634 541341 Xe-134m 4.01610E-04 6.08210E-04 541341 + 635 541350 Xe-135 7.18840E-04 7.59620E-02 54135.82c + 636 541351 Xe-135m 2.01130E-03 1.41150E-02 541351 + 637 541360 Xe-136 1.66350E-02 7.13920E-02 54136.82c + 638 541370 Xe-137 2.36540E-02 5.91450E-02 541370 + 639 541380 Xe-138 3.77450E-02 5.13420E-02 541380 + 640 541390 Xe-139 2.14060E-02 2.92680E-02 541390 + 641 541400 Xe-140 2.01430E-02 2.19250E-02 541400 + 642 541410 Xe-141 4.67450E-03 4.95370E-03 541410 + 643 541420 Xe-142 2.28630E-03 2.31540E-03 541420 + 644 541430 Xe-143 3.19690E-04 3.21910E-04 541430 + 645 541440 Xe-144 4.85910E-05 4.85920E-05 541440 + 646 541450 Xe-145 5.54410E-06 5.54410E-06 541450 + 647 541460 Xe-146 6.10230E-09 6.10230E-09 541460 + 648 551330 Cs-133 2.12660E-09 6.70220E-02 55133.82c + 649 551340 Cs-134 6.21950E-07 1.17260E-06 55134.82c + 650 551341 Cs-134m 5.50650E-07 5.50650E-07 551341 + 651 551350 Cs-135 1.45990E-05 7.60720E-02 55135.82c + 652 551351 Cs-135m 1.08040E-05 1.08040E-05 551351 + 653 551360 Cs-136 1.55330E-04 2.10860E-04 55136.82c + 654 551361 Cs-136m 1.11060E-04 1.11060E-04 551361 + 655 551370 Cs-137 2.98400E-03 6.21290E-02 55137.82c + 656 551380 Cs-138 4.25800E-03 6.13680E-02 551380 + 657 551381 Cs-138m 7.12100E-03 7.12100E-03 551381 + 658 551390 Cs-139 2.63300E-02 5.55980E-02 551390 + 659 551400 Cs-140 3.15870E-02 5.35140E-02 551400 + 660 551410 Cs-141 3.70890E-02 4.20490E-02 551410 + 661 551420 Cs-142 2.65890E-02 2.88990E-02 551420 + 662 551430 Cs-143 1.94470E-02 1.97670E-02 551430 + 663 551440 Cs-144 3.06310E-03 4.64200E-03 551440 + 664 551441 Cs-144m 3.06310E-03 3.06320E-03 551441 + 665 551450 Cs-145 1.71260E-03 1.71790E-03 551450 + 666 551460 Cs-146 3.21490E-04 3.21500E-04 551460 + 667 551470 Cs-147 4.74540E-05 4.74540E-05 551470 + 668 551480 Cs-148 6.86680E-06 6.86680E-06 551480 + 669 551490 Cs-149 4.06900E-10 4.06900E-10 551490 + 670 561360 Ba-136 2.45390E-07 2.67300E-04 56136.82c + 671 561361 Ba-136m 6.68860E-07 6.68860E-07 561361 + 672 561370 Ba-137 4.39180E-07 6.21310E-02 56137.82c + 673 561371 Ba-137m 1.22880E-06 5.86510E-02 561371 + 674 561380 Ba-138 2.12620E-04 6.29340E-02 56138.82c + 675 561390 Ba-139 9.75610E-04 5.65740E-02 561390 + 676 561400 Ba-140 4.07940E-03 5.75930E-02 56140.82c + 677 561410 Ba-141 5.96180E-03 4.80110E-02 561410 + 678 561420 Ba-142 1.93640E-02 4.85870E-02 561420 + 679 561430 Ba-143 2.10770E-02 4.06690E-02 561430 + 680 561440 Ba-144 2.15000E-02 2.77710E-02 561440 + 681 561450 Ba-145 7.86100E-03 9.37890E-03 561450 + 682 561460 Ba-146 5.27720E-03 5.56660E-03 561460 + 683 561470 Ba-147 1.03770E-03 1.07340E-03 561470 + 684 561480 Ba-148 3.08750E-04 3.13890E-04 561480 + 685 561490 Ba-149 3.19480E-05 3.19480E-05 561490 + 686 561500 Ba-150 1.28860E-07 1.28860E-07 561500 + 687 561510 Ba-151 1.53410E-09 1.53410E-09 561510 + 688 571380 La-138 1.60330E-09 1.60330E-09 57138.82c + 689 571390 La-139 6.62280E-06 5.65800E-02 57139.82c + 690 571400 La-140 8.10600E-05 5.76740E-02 57140.82c + 691 571410 La-141 3.82030E-04 4.83930E-02 571410 + 692 571420 La-142 1.31640E-03 4.99040E-02 571420 + 693 571430 La-143 6.70200E-03 4.73710E-02 571430 + 694 571440 La-144 1.35960E-02 4.13670E-02 571440 + 695 571450 La-145 2.17960E-02 3.11750E-02 571450 + 696 571460 La-146 5.99440E-03 1.15610E-02 571460 + 697 571461 La-146m 1.25760E-02 1.25760E-02 571461 + 698 571470 La-147 1.52740E-02 1.63490E-02 571470 + 699 571480 La-148 6.52760E-03 6.84040E-03 571480 + 700 571490 La-149 3.08150E-03 3.11330E-03 571490 + 701 571500 La-150 7.16840E-04 7.16970E-04 571500 + 702 571510 La-151 1.35020E-04 1.35020E-04 571510 + 703 571520 La-152 1.86980E-05 1.86980E-05 571520 + 704 571530 La-153 7.81610E-09 7.81610E-09 571530 + 705 571540 La-154 4.76230E-11 4.76230E-11 571540 + 706 581410 Ce-141 9.71530E-09 4.83930E-02 58141.82c + 707 581420 Ce-142 9.66730E-06 4.99140E-02 58142.82c + 708 581430 Ce-143 4.62790E-05 4.74170E-02 58143.82c + 709 581440 Ce-144 3.76530E-04 4.17430E-02 58144.82c + 710 581450 Ce-145 1.11230E-03 3.22870E-02 581450 + 711 581460 Ce-146 4.14370E-03 2.82800E-02 581460 + 712 581470 Ce-147 5.52520E-03 2.18740E-02 581470 + 713 581480 Ce-148 9.15310E-03 1.60370E-02 581480 + 714 581490 Ce-149 5.17870E-03 8.26780E-03 581490 + 715 581500 Ce-150 3.72760E-03 4.42520E-03 581500 + 716 581510 Ce-151 9.66740E-04 1.10290E-03 581510 + 717 581520 Ce-152 3.59630E-04 3.77200E-04 581520 + 718 581530 Ce-153 9.10730E-05 9.10810E-05 581530 + 719 581540 Ce-154 9.63720E-06 9.63720E-06 581540 + 720 581550 Ce-155 2.04030E-08 2.04030E-08 581550 + 721 581560 Ce-156 3.21910E-10 3.21910E-10 581560 + 722 591430 Pr-143 1.53850E-09 4.74170E-02 59143.82c + 723 591440 Pr-144 8.05880E-08 4.17440E-02 591440 + 724 591441 Pr-144m 8.19830E-07 5.76850E-04 591441 + 725 591450 Pr-145 1.66620E-05 3.23040E-02 591450 + 726 591460 Pr-146 1.10200E-04 2.83900E-02 591460 + 727 591470 Pr-147 5.60000E-04 2.24340E-02 591470 + 728 591480 Pr-148 2.85380E-04 1.63220E-02 591480 + 729 591481 Pr-148m 1.38350E-03 1.38350E-03 591481 + 730 591490 Pr-149 4.57960E-03 1.28470E-02 591490 + 731 591500 Pr-150 5.29380E-03 9.71900E-03 591500 + 732 591510 Pr-151 5.60240E-03 6.70530E-03 591510 + 733 591520 Pr-152 3.25410E-03 3.63190E-03 591520 + 734 591530 Pr-153 2.31520E-03 2.40580E-03 591530 + 735 591540 Pr-154 5.40330E-04 5.49910E-04 591540 + 736 591550 Pr-155 1.57360E-04 1.57380E-04 591550 + 737 591560 Pr-156 5.12430E-05 5.12430E-05 591560 + 738 591570 Pr-157 4.38890E-08 4.38890E-08 591570 + 739 591580 Pr-158 3.66500E-10 3.66500E-10 591580 + 740 591590 Pr-159 2.40780E-12 2.40780E-12 591590 + 741 601460 Nd-146 5.08510E-09 2.83900E-02 60146.82c + 742 601470 Nd-147 1.72690E-07 2.24340E-02 60147.82c + 743 601480 Nd-148 1.17750E-05 1.77180E-02 60148.82c + 744 601490 Nd-149 4.09700E-05 1.28880E-02 601490 + 745 601500 Nd-150 2.45340E-04 9.96440E-03 60150.82c + 746 601510 Nd-151 4.75350E-04 7.18060E-03 601510 + 747 601520 Nd-152 9.18340E-04 4.55020E-03 601520 + 748 601530 Nd-153 1.06270E-03 3.46850E-03 601530 + 749 601540 Nd-154 8.87280E-04 1.43720E-03 601540 + 750 601550 Nd-155 4.66990E-04 6.25760E-04 601550 + 751 601560 Nd-156 1.57340E-04 2.07190E-04 601560 + 752 601570 Nd-157 4.65640E-05 4.66050E-05 601570 + 753 601580 Nd-158 1.17010E-06 1.17050E-06 601580 + 754 601590 Nd-159 3.37280E-08 3.37300E-08 601590 + 755 601600 Nd-160 5.55200E-10 5.55200E-10 601600 + 756 601610 Nd-161 3.86950E-12 3.86950E-12 601610 + 757 611490 Pm-149 1.30210E-08 1.28880E-02 61149.82c + 758 611500 Pm-150 3.31680E-06 3.31680E-06 611500 + 759 611510 Pm-151 1.65100E-05 7.19720E-03 61151.82c + 760 611520 Pm-152 1.23050E-05 4.56250E-03 611520 + 761 611521 Pm-152m 2.58690E-05 2.58690E-05 611521 + 762 611522 Pm-152m 3.37910E-05 3.37910E-05 611522 + 763 611530 Pm-153 3.00880E-04 3.76940E-03 611530 + 764 611540 Pm-154 2.15100E-04 1.65230E-03 611540 + 765 611541 Pm-154m 2.15100E-04 2.15100E-04 611541 + 766 611550 Pm-155 8.08520E-04 1.43430E-03 611550 + 767 611560 Pm-156 6.32710E-04 8.39900E-04 611560 + 768 611570 Pm-157 3.44590E-04 3.91190E-04 611570 + 769 611580 Pm-158 1.22850E-04 1.24020E-04 611580 + 770 611590 Pm-159 1.70240E-05 1.70580E-05 611590 + 771 611600 Pm-160 4.12910E-06 4.12970E-06 611600 + 772 611610 Pm-161 2.06500E-08 2.06540E-08 611610 + 773 611620 Pm-162 5.64410E-10 5.64410E-10 611620 + 774 611630 Pm-163 9.57410E-12 9.57410E-12 611630 + 775 621510 Sm-151 1.10170E-06 7.19820E-03 62151.82c + 776 621520 Sm-152 3.01450E-08 4.62220E-03 62152.82c + 777 621530 Sm-153 1.59630E-07 3.77000E-03 62153.82c + 778 621531 Sm-153m 4.46630E-07 4.46630E-07 621531 + 779 621540 Sm-154 3.85500E-06 1.87120E-03 62154.82c + 780 621550 Sm-155 2.77600E-05 1.46200E-03 621550 + 781 621560 Sm-156 7.66010E-05 9.16500E-04 621560 + 782 621570 Sm-157 5.58860E-05 4.47080E-04 621570 + 783 621580 Sm-158 3.07150E-05 1.54740E-04 621580 + 784 621590 Sm-159 3.40490E-05 5.11150E-05 621590 + 785 621600 Sm-160 1.65170E-05 2.06360E-05 621600 + 786 621610 Sm-161 1.86660E-06 1.88730E-06 621610 + 787 621620 Sm-162 3.45200E-07 3.45760E-07 621620 + 788 621630 Sm-163 1.77570E-08 1.77670E-08 621630 + 789 621640 Sm-164 1.43780E-09 1.43780E-09 621640 + 790 621650 Sm-165 2.09010E-11 2.09010E-11 621650 + 791 631540 Eu-154 5.49960E-10 1.14290E-09 63154.82c + 792 631541 Eu-154m 5.92940E-10 5.92940E-10 631541 + 793 631550 Eu-155 4.63500E-08 1.46210E-03 63155.82c + 794 631560 Eu-156 5.27100E-07 9.17030E-04 63156.82c + 795 631570 Eu-157 1.39710E-05 4.61050E-04 63157.82c + 796 631580 Eu-158 8.77590E-06 1.63520E-04 631580 + 797 631590 Eu-159 2.55380E-05 7.66530E-05 631590 + 798 631600 Eu-160 4.12920E-06 2.47650E-05 631600 + 799 631610 Eu-161 9.78050E-06 1.16680E-05 631610 + 800 631620 Eu-162 5.79620E-06 6.14200E-06 631620 + 801 631630 Eu-163 2.58150E-06 2.59930E-06 631630 + 802 631640 Eu-164 2.13120E-06 2.13260E-06 631640 + 803 631650 Eu-165 2.08430E-08 2.08640E-08 631650 + 804 631660 Eu-166 9.03810E-10 9.03810E-10 631660 + 805 631670 Eu-167 2.95760E-11 2.95760E-11 631670 + 806 641560 Gd-156 9.65760E-11 9.17030E-04 64156.82c + 807 641570 Gd-157 1.91510E-09 4.61050E-04 64157.82c + 808 641580 Gd-158 2.60870E-08 1.63540E-04 64158.82c + 809 641590 Gd-159 1.67950E-07 7.68200E-05 641590 + 810 641600 Gd-160 6.23350E-07 2.53880E-05 64160.82c + 811 641610 Gd-161 1.03040E-06 1.26980E-05 641610 + 812 641620 Gd-162 2.27250E-06 8.41450E-06 641620 + 813 641630 Gd-163 1.48040E-06 4.07970E-06 641630 + 814 641640 Gd-164 1.71860E-06 3.85120E-06 641640 + 815 641650 Gd-165 4.16730E-07 4.37590E-07 641650 + 816 641660 Gd-166 1.12660E-07 1.13560E-07 641660 + 817 641670 Gd-167 1.05330E-08 1.05630E-08 641670 + 818 641680 Gd-168 8.90800E-10 8.90800E-10 641680 + 819 641690 Gd-169 2.97750E-11 2.97750E-11 641690 + 820 651590 Tb-159 4.33410E-11 7.68200E-05 65159.82c + 821 651600 Tb-160 4.90150E-10 4.90150E-10 65160.82c + 822 651610 Tb-161 5.63340E-09 1.27040E-05 651610 + 823 651620 Tb-162 3.44020E-08 8.44890E-06 651620 + 824 651630 Tb-163 1.34020E-07 4.21370E-06 651630 + 825 651640 Tb-164 3.58000E-07 4.20920E-06 651640 + 826 651650 Tb-165 4.39090E-07 8.76680E-07 651650 + 827 651660 Tb-166 2.53830E-07 3.67390E-07 651660 + 828 651670 Tb-167 1.27660E-07 1.38220E-07 651670 + 829 651680 Tb-168 2.71440E-08 2.80350E-08 651680 + 830 651690 Tb-169 5.88070E-09 5.91050E-09 651690 + 831 651700 Tb-170 4.34370E-10 4.34370E-10 651700 + 832 651710 Tb-171 2.89070E-11 2.89070E-11 651710 + 833 661620 Dy-162 2.25290E-11 8.44890E-06 66162.82c + 834 661630 Dy-163 2.64810E-10 4.21390E-06 66163.82c + 835 661640 Dy-164 4.79220E-09 4.21400E-06 66164.82c + 836 661650 Dy-165 1.38300E-08 8.92310E-07 661650 + 837 661651 Dy-165m 1.84130E-09 1.84130E-09 661651 + 838 661660 Dy-166 5.17510E-08 4.19150E-07 661660 + 839 661670 Dy-167 5.76230E-08 1.95850E-07 661670 + 840 661680 Dy-168 6.12870E-08 8.93220E-08 661680 + 841 661690 Dy-169 2.90600E-08 3.49710E-08 661690 + 842 661700 Dy-170 1.20620E-08 1.24960E-08 661700 + 843 661710 Dy-171 2.10880E-09 2.13770E-09 661710 + 844 661720 Dy-172 3.53780E-10 3.53780E-10 661720 + 845 661730 Dy-173 2.03810E-11 2.03810E-11 661730 + 846 671650 Ho-165 1.68800E-11 8.92370E-07 67165.82c + 847 671660 Ho-166 4.42940E-11 4.19190E-07 671660 + 848 671661 Ho-166m 1.20740E-10 1.20740E-10 671661 + 849 671670 Ho-167 1.20620E-09 1.97050E-07 671670 + 850 671680 Ho-168 1.22660E-09 9.25890E-08 671680 + 851 671681 Ho-168m 2.05140E-09 2.05140E-09 671681 + 852 671690 Ho-169 8.48830E-09 4.34590E-08 671690 + 853 671700 Ho-170 5.54880E-09 5.54880E-09 671700 + 854 671701 Ho-170m 2.03570E-09 1.45320E-08 671701 + 855 671710 Ho-171 6.66840E-09 8.80610E-09 671710 + 856 671720 Ho-172 2.53630E-09 2.89010E-09 671720 + 857 671730 Ho-173 8.59640E-10 8.80020E-10 671730 + 858 671740 Ho-174 1.09240E-10 1.09240E-10 671740 + 859 671750 Ho-175 1.45420E-11 1.45420E-11 671750 + 860 681680 Er-168 8.88650E-12 9.26090E-08 68168.82c + 861 681690 Er-169 6.64370E-11 4.35250E-08 681690 + 862 681700 Er-170 3.75490E-10 2.04560E-08 68170.82c + 863 681710 Er-171 8.05980E-10 9.61210E-09 681710 + 864 681720 Er-172 1.60870E-09 4.49880E-09 681720 + 865 681730 Er-173 1.15780E-09 2.03780E-09 681730 + 866 681740 Er-174 7.55580E-10 8.64820E-10 681740 + 867 681750 Er-175 2.38030E-10 2.52570E-10 681750 + 868 681760 Er-176 6.86670E-11 6.86670E-11 681760 + 869 681770 Er-177 6.98060E-12 6.98060E-12 681770 + 870 691710 Tm-171 3.53320E-12 9.61560E-09 691710 + 871 691720 Tm-172 1.97430E-11 4.51850E-09 691720 + 872 691730 Tm-173 8.61940E-11 2.12400E-09 691730 + 873 691740 Tm-174 1.31230E-10 9.96050E-10 691740 + 874 691750 Tm-175 2.10550E-10 4.63120E-10 691750 + 875 691760 Tm-176 1.29320E-10 1.97990E-10 691760 + 876 691770 Tm-177 6.98230E-11 7.68040E-11 691770 + 877 691780 Tm-178 1.61450E-11 1.61450E-11 691780 + 878 691790 Tm-179 3.74110E-12 3.74110E-12 691790 + 879 701740 Yb-174 1.41500E-12 9.97460E-10 701740 + 880 701750 Yb-175 5.41030E-12 4.69250E-10 701750 + 881 701751 Yb-175m 7.20360E-13 3.57320E-10 701751 + 882 701760 Yb-176 7.04700E-12 2.08440E-10 701760 + 883 701761 Yb-176m 1.47840E-11 1.13780E-10 701761 + 884 701770 Yb-177 2.19700E-11 1.03200E-10 701770 + 885 701771 Yb-177m 4.42360E-12 8.12270E-11 701771 + 886 701780 Yb-178 3.05840E-11 4.67290E-11 701780 + 887 701790 Yb-179 1.53720E-11 1.91130E-11 701790 + 888 701800 Yb-180 6.75630E-12 6.75630E-12 701800 + 889 701810 Yb-181 1.28820E-12 1.28820E-12 701810 + 890 711780 Lu-178 5.74250E-13 4.73030E-11 711780 + 891 711790 Lu-179 3.30110E-12 2.28540E-11 711790 + 892 711791 Lu-179m 4.39520E-13 1.95530E-11 711791 + 893 711800 Lu-180 9.45760E-13 5.63410E-12 711800 + 894 711801 Lu-180m 9.45760E-13 7.70210E-12 711801 + 895 711802 Lu-180m 1.67470E-12 1.67470E-12 711802 + 896 711810 Lu-181 3.40740E-12 4.69560E-12 711810 + + Nuclide 93238.82c -- neptunium 238 (Np-238) + + Neutron-induced fission: + + Interpolation region : 1 / 2 + Interpolation energy : 2.53000E-08 MeV + Number of products : 964 / 1066 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 2.94220E-05 2.94220E-05 1001.82c + 2 10020 H-2 8.99170E-06 8.99170E-06 1002.82c + 3 10030 H-3 1.25000E-04 1.25000E-04 1003.82c + 4 20040 He-4 1.86000E-03 1.86000E-03 2004.82c + 5 200500 Ca-50 3.06960E-12 3.06960E-12 200500 + 6 200510 Ca-51 2.70200E-12 2.70200E-12 200510 + 7 200520 Ca-52 2.64890E-12 2.64890E-12 200520 + 8 210500 Sc-50 7.73470E-13 4.13080E-12 210500 + 9 210501 Sc-50m 3.30230E-13 3.39980E-12 210501 + 10 210510 Sc-51 5.17200E-12 7.92700E-12 210510 + 11 210520 Sc-52 9.34910E-12 1.19450E-11 210520 + 12 210530 Sc-53 1.64440E-11 1.64440E-11 210530 + 13 210540 Sc-54 1.07430E-11 1.07430E-11 210540 + 14 210550 Sc-55 8.46500E-12 8.46500E-12 210550 + 15 210560 Sc-56 2.07490E-12 2.07490E-12 210560 + 16 220520 Ti-52 3.50420E-12 1.54490E-11 220520 + 17 220530 Ti-53 1.12420E-11 2.76860E-11 220530 + 18 220540 Ti-54 3.92370E-11 4.99800E-11 220540 + 19 220550 Ti-55 5.86870E-11 6.71520E-11 220550 + 20 220560 Ti-56 8.74760E-11 8.95510E-11 220560 + 21 220570 Ti-57 4.54320E-11 4.54320E-11 220570 + 22 220580 Ti-58 2.69510E-11 2.69510E-11 220580 + 23 220590 Ti-59 5.31530E-12 5.31530E-12 220590 + 24 230540 V-54 4.07980E-12 5.40600E-11 230540 + 25 230550 V-55 3.38280E-11 1.00980E-10 230550 + 26 230560 V-56 9.08710E-11 1.80560E-10 230560 + 27 230570 V-57 2.56420E-10 3.01720E-10 230570 + 28 230580 V-58 2.99350E-10 3.26300E-10 230580 + 29 230590 V-59 3.73270E-10 3.78580E-10 230590 + 30 230600 V-60 1.48550E-10 1.48550E-10 230600 + 31 230610 V-61 6.83050E-11 6.83050E-11 230610 + 32 230620 V-62 1.07980E-11 1.07980E-11 230620 + 33 230630 V-63 1.45810E-12 1.45810E-12 230630 + 34 240560 Cr-56 9.45840E-12 1.91220E-10 240560 + 35 240570 Cr-57 5.20390E-11 6.13590E-10 240570 + 36 240580 Cr-58 3.28310E-10 3.93570E-10 240580 + 37 240590 Cr-59 7.39080E-10 1.11770E-09 240590 + 38 240600 Cr-60 1.64310E-09 1.79570E-09 240600 + 39 240610 Cr-61 1.54650E-09 1.61070E-09 240610 + 40 240620 Cr-62 1.60260E-09 1.61390E-09 240620 + 41 240630 Cr-63 5.11000E-10 5.11950E-10 240630 + 42 240640 Cr-64 1.67910E-10 1.67910E-10 240640 + 43 240650 Cr-65 2.07850E-11 2.07850E-11 240650 + 44 240660 Cr-66 2.22480E-12 2.22480E-12 240660 + 45 250580 Mn-58 8.13330E-12 4.01700E-10 250580 + 46 250590 Mn-59 1.22680E-10 1.24030E-09 250590 + 47 250600 Mn-60 5.19770E-11 1.90080E-09 250600 + 48 250601 Mn-60m 4.61630E-10 4.61630E-10 250601 + 49 250610 Mn-61 2.57700E-09 4.18770E-09 250610 + 50 250620 Mn-62 4.14990E-09 4.95690E-09 250620 + 51 250621 Mn-62m 7.45000E-10 1.55200E-09 250621 + 52 250630 Mn-63 9.03320E-09 9.54520E-09 250630 + 53 250640 Mn-64 6.31810E-09 6.48600E-09 250640 + 54 250650 Mn-65 5.29380E-09 5.31460E-09 250650 + 55 250660 Mn-66 1.36940E-09 1.37160E-09 250660 + 56 250670 Mn-67 3.45150E-10 3.45150E-10 250670 + 57 250680 Mn-68 3.16730E-11 3.16730E-11 250680 + 58 250690 Mn-69 2.69260E-12 2.69260E-12 250690 + 59 260600 Fe-60 1.35200E-11 2.32290E-09 260600 + 60 260610 Fe-61 1.44480E-10 4.33220E-09 260610 + 61 260620 Fe-62 1.58930E-09 8.09810E-09 260620 + 62 260630 Fe-63 5.37750E-09 1.49230E-08 260630 + 63 260640 Fe-64 2.00480E-08 2.65340E-08 260640 + 64 260650 Fe-65 3.16190E-08 3.69340E-08 260650 + 65 260660 Fe-66 4.92280E-08 5.06000E-08 260660 + 66 260670 Fe-67 2.73950E-08 2.77400E-08 260670 + 67 260680 Fe-68 1.74910E-08 1.75230E-08 260680 + 68 260690 Fe-69 3.65160E-09 3.65370E-09 260690 + 69 260700 Fe-70 1.06990E-09 1.06990E-09 260700 + 70 260710 Fe-71 3.40170E-11 3.40170E-11 260710 + 71 260720 Fe-72 3.17680E-12 3.17680E-12 260720 + 72 270620 Co-62 3.17270E-12 8.10140E-09 270620 + 73 270621 Co-62m 7.43130E-12 7.43130E-12 270621 + 74 270630 Co-63 2.35320E-10 1.51580E-08 270630 + 75 270640 Co-64 1.79690E-09 2.83310E-08 270640 + 76 270650 Co-65 1.58390E-08 5.27730E-08 270650 + 77 270660 Co-66 4.45260E-08 9.51260E-08 270660 + 78 270670 Co-67 1.33870E-07 1.61610E-07 270670 + 79 270680 Co-68 8.84930E-08 1.36420E-07 270680 + 80 270681 Co-68m 7.80670E-08 9.58460E-08 270681 + 81 270690 Co-69 2.17670E-07 2.21070E-07 270690 + 82 270700 Co-70 7.27400E-08 7.27400E-08 270700 + 83 270701 Co-70m 7.27400E-08 7.38100E-08 270701 + 84 270710 Co-71 3.29520E-08 3.29860E-08 270710 + 85 270720 Co-72 7.82620E-09 7.82940E-09 270720 + 86 270730 Co-73 1.14830E-09 1.14830E-09 270730 + 87 270740 Co-74 1.33640E-11 1.33640E-11 270740 + 88 280640 Ni-64 1.10190E-11 2.83420E-08 28064.82c + 89 280650 Ni-65 2.23400E-10 5.29960E-08 280650 + 90 280660 Ni-66 3.97290E-09 9.90990E-08 280660 + 91 280670 Ni-67 2.35200E-08 1.85130E-07 280670 + 92 280680 Ni-68 1.59050E-07 3.45600E-07 280680 + 93 280690 Ni-69 1.87280E-07 4.06140E-07 280690 + 94 280691 Ni-69m 1.87280E-07 1.87280E-07 280691 + 95 280700 Ni-70 1.80110E-06 1.94760E-06 280700 + 96 280710 Ni-71 6.36510E-07 6.69500E-07 280710 + 97 280720 Ni-72 9.82070E-07 9.89900E-07 280720 + 98 280730 Ni-73 3.38000E-07 3.39150E-07 280730 + 99 280740 Ni-74 2.86100E-08 2.86230E-08 280740 + 100 280750 Ni-75 4.64270E-09 4.64270E-09 280750 + 101 280760 Ni-76 9.46310E-10 9.46310E-10 280760 + 102 280770 Ni-77 4.64220E-11 4.64220E-11 280770 + 103 290660 Cu-66 5.98100E-12 9.91040E-08 290660 + 104 290670 Cu-67 2.47970E-10 1.85380E-07 290670 + 105 290680 Cu-68 1.11830E-09 3.48920E-07 290680 + 106 290681 Cu-68m 2.61920E-09 2.61920E-09 290681 + 107 290690 Cu-69 5.35580E-08 6.46970E-07 290690 + 108 290700 Cu-70 2.86680E-08 2.37760E-07 290700 + 109 290701 Cu-70m 3.19380E-07 4.18190E-07 290701 + 110 290702 Cu-70m 2.86680E-08 1.97630E-06 290702 + 111 290710 Cu-71 1.61720E-06 2.28670E-06 290710 + 112 290720 Cu-72 2.59820E-06 3.58810E-06 290720 + 113 290730 Cu-73 5.12610E-06 5.46520E-06 290730 + 114 290740 Cu-74 9.14350E-07 9.43050E-07 290740 + 115 290750 Cu-75 2.59590E-06 2.60050E-06 290750 + 116 290760 Cu-76 6.65550E-07 6.66020E-07 290760 + 117 290761 Cu-76m 6.65550E-07 6.66020E-07 290761 + 118 290770 Cu-77 1.75860E-07 1.75910E-07 290770 + 119 290780 Cu-78 1.48980E-08 1.48980E-08 290780 + 120 290790 Cu-79 1.70310E-09 1.70310E-09 290790 + 121 290800 Cu-80 5.94550E-11 5.94550E-11 290800 + 122 300680 Zn-68 5.02960E-12 3.49340E-07 300680 + 123 300690 Zn-69 3.29140E-11 6.47150E-07 300690 + 124 300691 Zn-69m 1.42350E-10 1.42350E-10 300691 + 125 300700 Zn-70 8.41170E-09 2.33280E-06 300700 + 126 300710 Zn-71 8.33100E-09 2.29500E-06 300710 + 127 300711 Zn-71m 3.60300E-08 3.60300E-08 300711 + 128 300720 Zn-72 7.29930E-07 4.31800E-06 300720 + 129 300730 Zn-73 2.62670E-07 7.10410E-06 300730 + 130 300731 Zn-73m 3.59080E-07 1.37610E-06 300731 + 131 300732 Zn-73m 2.03410E-06 2.03410E-06 300732 + 132 300740 Zn-74 3.47290E-06 4.50700E-06 300740 + 133 300750 Zn-75 6.05570E-06 8.58510E-06 300750 + 134 300760 Zn-76 1.59790E-05 1.72910E-05 300760 + 135 300770 Zn-77 1.59350E-05 1.73290E-05 300770 + 136 300771 Zn-77m 2.43600E-06 2.43600E-06 300771 + 137 300780 Zn-78 2.14090E-05 2.14250E-05 300780 + 138 300790 Zn-79 8.09380E-06 8.09460E-06 300790 + 139 300800 Zn-80 5.74270E-06 5.74280E-06 300800 + 140 300810 Zn-81 3.07550E-08 3.07550E-08 300810 + 141 300820 Zn-82 1.75230E-09 1.75230E-09 300820 + 142 300830 Zn-83 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3.66600E-04 421090 + 379 421100 Mo-110 7.85440E-05 7.85450E-05 421100 + 380 421110 Mo-111 1.55350E-05 1.55350E-05 421110 + 381 421120 Mo-112 1.57320E-09 1.57320E-09 421120 + 382 421130 Mo-113 1.12690E-11 1.12690E-11 421130 + 383 431000 Tc-100 9.54630E-07 9.54630E-07 431000 + 384 431010 Tc-101 1.88660E-05 6.94080E-02 431010 + 385 431020 Tc-102 1.02560E-04 6.91710E-02 431020 + 386 431021 Tc-102m 1.02560E-04 1.02560E-04 431021 + 387 431030 Tc-103 1.13390E-03 6.71340E-02 431030 + 388 431040 Tc-104 3.06880E-03 5.71110E-02 431040 + 389 431050 Tc-105 7.38040E-03 4.14320E-02 431050 + 390 431060 Tc-106 8.56850E-03 2.73540E-02 431060 + 391 431070 Tc-107 8.74600E-03 1.44670E-02 431070 + 392 431080 Tc-108 5.99520E-03 8.27670E-03 431080 + 393 431090 Tc-109 2.87300E-03 3.23760E-03 431090 + 394 431100 Tc-110 8.32930E-04 9.11640E-04 431100 + 395 431110 Tc-111 3.40890E-04 3.56260E-04 431110 + 396 431120 Tc-112 3.72650E-05 3.72660E-05 431120 + 397 431130 Tc-113 8.62060E-06 8.62060E-06 431130 + 398 431140 Tc-114 2.31230E-06 2.31230E-06 431140 + 399 431150 Tc-115 7.46800E-11 7.46800E-11 431150 + 400 441010 Ru-101 1.04810E-06 6.94090E-02 44101.82c + 401 441020 Ru-102 4.87020E-09 6.92740E-02 44102.82c + 402 441030 Ru-103 6.48330E-06 6.71560E-02 44103.82c + 403 441031 Ru-103m 1.56520E-05 1.56520E-05 441031 + 404 441040 Ru-104 9.78350E-05 5.72090E-02 44104.82c + 405 441050 Ru-105 4.15900E-04 4.18480E-02 44105.82c + 406 441060 Ru-106 1.19520E-03 2.85490E-02 44106.82c + 407 441070 Ru-107 1.53620E-03 1.60030E-02 441070 + 408 441080 Ru-108 2.67830E-03 1.09580E-02 441080 + 409 441090 Ru-109 1.77020E-03 5.00560E-03 441090 + 410 441100 Ru-110 1.31090E-03 2.22220E-03 441100 + 411 441110 Ru-111 5.79130E-04 9.35950E-04 441110 + 412 441120 Ru-112 1.51730E-04 1.89060E-04 441120 + 413 441130 Ru-113 1.44520E-05 2.98310E-05 441130 + 414 441131 Ru-113m 1.44520E-05 1.44520E-05 441131 + 415 441140 Ru-114 1.52940E-05 1.74550E-05 441140 + 416 441150 Ru-115 3.46640E-06 3.46650E-06 441150 + 417 441160 Ru-116 1.46490E-08 1.46490E-08 441160 + 418 441170 Ru-117 5.24270E-10 5.24270E-10 441170 + 419 441180 Ru-118 1.00790E-11 1.00790E-11 441180 + 420 441200 Ru-120 5.67480E-09 5.67480E-09 441200 + 421 451050 Rh-105 1.33620E-08 4.18480E-02 45105.82c + 422 451051 Rh-105m 2.04270E-09 1.18800E-02 451051 + 423 451060 Rh-106 1.71170E-06 2.85510E-02 451060 + 424 451061 Rh-106m 4.00930E-06 4.00930E-06 451061 + 425 451070 Rh-107 2.57180E-05 1.60290E-02 451070 + 426 451080 Rh-108 2.00490E-05 1.09780E-02 451080 + 427 451081 Rh-108m 6.05000E-05 6.05000E-05 451081 + 428 451090 Rh-109 1.43980E-04 5.14960E-03 451090 + 429 451100 Rh-110 1.38210E-04 2.36040E-03 451100 + 430 451101 Rh-110m 3.68940E-06 3.68940E-06 451101 + 431 451110 Rh-111 1.97090E-04 1.13300E-03 451110 + 432 451120 Rh-112 6.94650E-05 2.58520E-04 451120 + 433 451121 Rh-112m 6.94650E-05 6.94650E-05 451121 + 434 451130 Rh-113 8.28710E-05 1.19930E-04 451130 + 435 451140 Rh-114 3.40880E-05 5.15510E-05 451140 + 436 451141 Rh-114m 3.40880E-05 3.40880E-05 451141 + 437 451150 Rh-115 4.48250E-05 4.82840E-05 451150 + 438 451160 Rh-116 8.27710E-06 8.29160E-06 451160 + 439 451161 Rh-116m 1.93870E-05 1.93870E-05 451161 + 440 451170 Rh-117 7.24670E-06 7.24720E-06 451170 + 441 451180 Rh-118 3.38150E-06 3.38150E-06 451180 + 442 451190 Rh-119 1.49640E-06 1.49640E-06 451190 + 443 451200 Rh-120 1.48150E-06 1.48720E-06 451200 + 444 451210 Rh-121 2.70720E-07 2.70720E-07 451210 + 445 451220 Rh-122 1.66740E-08 1.66740E-08 451220 + 446 461060 Pd-106 1.14850E-06 2.85560E-02 46106.82c + 447 461070 Pd-107 1.47920E-10 1.60290E-02 46107.82c + 448 461071 Pd-107m 2.77990E-10 2.77990E-10 461071 + 449 461080 Pd-108 2.56210E-06 1.10410E-02 46108.82c + 450 461090 Pd-109 9.95330E-08 5.14990E-03 461090 + 451 461091 Pd-109m 1.87060E-07 2.57500E-03 461091 + 452 461100 Pd-110 5.07880E-06 2.36910E-03 46110.82c + 453 461110 Pd-111 2.38270E-06 1.13750E-03 461110 + 454 461111 Pd-111m 4.47800E-06 9.01020E-06 461111 + 455 461120 Pd-112 9.41340E-06 3.37400E-04 461120 + 456 461130 Pd-113 5.32020E-06 1.38090E-04 461130 + 457 461131 Pd-113m 1.28440E-05 1.28440E-05 461131 + 458 461140 Pd-114 3.08280E-05 1.16470E-04 461140 + 459 461150 Pd-115 1.58970E-05 6.01200E-05 461150 + 460 461151 Pd-115m 2.98750E-05 3.68860E-05 461151 + 461 461160 Pd-116 4.94240E-05 7.71030E-05 461160 + 462 461170 Pd-117 2.10020E-05 6.78170E-05 461170 + 463 461171 Pd-117m 3.94690E-05 3.94690E-05 461171 + 464 461180 Pd-118 2.48370E-05 2.81200E-05 461180 + 465 461190 Pd-119 1.94760E-05 2.10610E-05 461190 + 466 461200 Pd-120 1.03810E-05 1.18170E-05 461200 + 467 461210 Pd-121 1.48230E-06 1.71630E-06 461210 + 468 461220 Pd-122 1.51390E-06 1.53060E-06 461220 + 469 461230 Pd-123 9.46360E-07 9.46360E-07 461230 + 470 461240 Pd-124 1.93230E-07 1.93230E-07 461240 + 471 471100 Ag-110 1.49480E-10 1.54240E-10 471100 + 472 471101 Ag-110m 3.50130E-10 3.50130E-10 47510.82c + 473 471110 Ag-111 1.85490E-09 1.13430E-03 47111.82c + 474 471111 Ag-111m 1.21340E-08 1.13120E-03 471111 + 475 471120 Ag-112 7.96700E-08 3.37480E-04 471120 + 476 471130 Ag-113 7.82780E-08 9.08940E-05 471130 + 477 471131 Ag-113m 5.12050E-07 1.32750E-04 471131 + 478 471140 Ag-114 2.21300E-07 1.17620E-04 471140 + 479 471141 Ag-114m 9.30700E-07 9.30700E-07 471141 + 480 471150 Ag-115 1.06500E-06 5.69510E-05 471150 + 481 471151 Ag-115m 6.96680E-06 5.71350E-05 471151 + 482 471160 Ag-116 4.12330E-06 8.18050E-05 471160 + 483 471161 Ag-116m 9.65770E-06 9.65770E-06 471161 + 484 471170 Ag-117 6.06650E-06 4.43900E-05 471170 + 485 471171 Ag-117m 3.96840E-05 7.35920E-05 471171 + 486 471180 Ag-118 9.94810E-06 5.28500E-05 471180 + 487 471181 Ag-118m 4.18380E-05 4.58580E-05 471181 + 488 471190 Ag-119 8.93470E-06 1.94650E-05 471190 + 489 471191 Ag-119m 5.84460E-05 6.89770E-05 471191 + 490 471200 Ag-120 2.02720E-05 3.90150E-05 471200 + 491 471201 Ag-120m 2.87660E-05 3.46740E-05 471201 + 492 471210 Ag-121 2.82450E-05 2.99570E-05 471210 + 493 471220 Ag-122 8.79690E-06 1.03280E-05 471220 + 494 471221 Ag-122m 7.92410E-06 7.92410E-06 471221 + 495 471230 Ag-123 1.23520E-05 1.32980E-05 471230 + 496 471240 Ag-124 5.74240E-06 8.52190E-06 471240 + 497 471241 Ag-124m 5.17260E-06 5.17260E-06 471241 + 498 471250 Ag-125 4.93970E-06 4.93970E-06 471250 + 499 471260 Ag-126 3.34510E-06 3.34510E-06 471260 + 500 471270 Ag-127 3.15050E-06 3.15050E-06 471270 + 501 471280 Ag-128 4.62280E-08 4.62280E-08 471280 + 502 471290 Ag-129 2.27760E-09 2.27760E-09 471290 + 503 481120 Cd-112 1.19180E-11 3.37480E-04 48112.82c + 504 481130 Cd-113 4.83650E-11 1.37110E-04 48113.82c + 505 481131 Cd-113m 1.58230E-10 1.57160E-06 481131 + 506 481140 Cd-114 7.62620E-09 1.17630E-04 48114.82c + 507 481150 Cd-115 2.17570E-08 9.75130E-05 481150 + 508 481151 Cd-115m 7.11820E-08 4.66700E-06 48515.82c + 509 481160 Cd-116 1.13430E-06 9.20180E-05 48116.82c + 510 481170 Cd-117 1.41130E-06 9.03280E-05 481170 + 511 481171 Cd-117m 4.61720E-06 2.92680E-05 481171 + 512 481180 Cd-118 1.57430E-05 9.56490E-05 481180 + 513 481190 Cd-119 5.69190E-06 8.44020E-05 481190 + 514 481191 Cd-119m 1.37410E-05 2.34740E-05 481191 + 515 481200 Cd-120 8.15230E-05 1.42380E-04 481200 + 516 481210 Cd-121 1.69810E-05 4.38080E-05 481210 + 517 481211 Cd-121m 4.09950E-05 4.41260E-05 481211 + 518 481220 Cd-122 7.06630E-05 8.89150E-05 481220 + 519 481230 Cd-123 1.39270E-05 2.48110E-05 481230 + 520 481231 Cd-123m 3.36210E-05 3.60440E-05 481231 + 521 481240 Cd-124 1.13300E-04 1.24400E-04 481240 + 522 481250 Cd-125 6.05220E-05 6.29920E-05 481250 + 523 481251 Cd-125m 1.46110E-04 1.48580E-04 481251 + 524 481260 Cd-126 3.78720E-04 3.82070E-04 481260 + 525 481270 Cd-127 2.84340E-04 2.87490E-04 481270 + 526 481280 Cd-128 1.11230E-04 1.11280E-04 481280 + 527 481290 Cd-129 1.02790E-05 1.02800E-05 481290 + 528 481291 Cd-129m 2.48150E-05 2.48160E-05 481291 + 529 481300 Cd-130 1.11880E-06 1.11880E-06 481300 + 530 481310 Cd-131 3.62250E-08 3.62250E-08 481310 + 531 481320 Cd-132 1.66990E-09 1.66990E-09 481320 + 532 491150 In-115 1.92990E-11 9.73050E-05 49115.82c + 533 491151 In-115m 4.46250E-12 9.75140E-05 491151 + 534 491160 In-116 1.75750E-10 1.75750E-10 491160 + 535 491161 In-116m 2.69370E-10 5.30270E-10 491161 + 536 491162 In-116m 2.60900E-10 2.60900E-10 491162 + 537 491170 In-117 2.49470E-08 7.55970E-05 491170 + 538 491171 In-117m 5.76850E-09 8.32300E-05 491171 + 539 491180 In-118 6.61730E-08 9.57150E-05 491180 + 540 491181 In-118m 1.01430E-07 1.98290E-07 491181 + 541 491182 In-118m 9.82350E-08 9.82350E-08 491182 + 542 491190 In-119 1.21330E-06 3.71270E-05 491190 + 543 491191 In-119m 2.80550E-07 7.65280E-05 491191 + 544 491200 In-120 1.96340E-06 1.44340E-04 491200 + 545 491201 In-120m 1.96340E-06 1.96340E-06 491201 + 546 491202 In-120m 1.96340E-06 1.96340E-06 491202 + 547 491210 In-121 5.97770E-06 6.52230E-05 491210 + 548 491211 In-121m 1.38220E-06 3.04360E-05 491211 + 549 491220 In-122 1.16450E-05 1.00560E-04 491220 + 550 491221 In-122m 8.26200E-06 8.26200E-06 491221 + 551 491222 In-122m 8.26200E-06 8.26200E-06 491222 + 552 491230 In-123 4.91590E-05 9.24480E-05 491230 + 553 491231 In-123m 1.13670E-05 2.89330E-05 491231 + 554 491240 In-124 3.39800E-05 1.58380E-04 491240 + 555 491241 In-124m 3.06080E-05 3.06080E-05 491241 + 556 491250 In-125 2.10960E-04 3.89690E-04 491250 + 557 491251 In-125m 4.87790E-05 8.16210E-05 491251 + 558 491260 In-126 3.55540E-04 7.37610E-04 491260 + 559 491261 In-126m 3.20270E-04 3.20270E-04 491261 + 560 491270 In-127 1.54590E-03 1.54590E-03 491270 + 561 491271 In-127m 3.57460E-04 6.44950E-04 491271 + 562 491280 In-128 8.86250E-04 1.35830E-03 491280 + 563 491281 In-128m 3.60760E-04 4.72040E-04 491281 + 564 491282 In-128m 1.12330E-03 1.12330E-03 491282 + 565 491290 In-129 2.01520E-03 2.04010E-03 491290 + 566 491291 In-129m 4.65970E-04 4.76270E-04 491291 + 567 491300 In-130 3.42860E-04 3.43940E-04 491300 + 568 491301 In-130m 3.82940E-04 3.82940E-04 491301 + 569 491302 In-130m 6.51560E-04 6.51560E-04 491302 + 570 491310 In-131 1.68440E-04 1.70190E-04 491310 + 571 491311 In-131m 1.68440E-04 1.68440E-04 491311 + 572 491312 In-131m 1.68440E-04 1.68440E-04 491312 + 573 491320 In-132 5.76090E-05 5.76100E-05 491320 + 574 491330 In-133 5.52690E-06 6.80480E-06 491330 + 575 491331 In-133m 1.27790E-06 1.27790E-06 491331 + 576 491340 In-134 1.18390E-08 1.18390E-08 491340 + 577 501170 Sn-117 7.48350E-13 1.19630E-04 50117.82c + 578 501171 Sn-117m 2.44840E-12 2.57570E-07 501171 + 579 501180 Sn-118 1.47810E-10 9.59150E-05 50118.82c + 580 501190 Sn-119 1.02760E-09 1.09370E-04 50119.82c + 581 501191 Sn-119m 3.36210E-09 3.35440E-05 501191 + 582 501210 Sn-121 3.71690E-12 9.36380E-05 501210 + 583 501211 Sn-121m 8.97310E-12 7.38870E-06 501211 + 584 501220 Sn-122 9.85230E-10 1.17080E-04 50122.82c + 585 501230 Sn-123 2.88210E-06 9.93050E-06 50123.82c + 586 501231 Sn-123m 1.19390E-06 1.15530E-04 501231 + 587 501240 Sn-124 3.35870E-05 2.22580E-04 50124.82c + 588 501250 Sn-125 3.99930E-05 1.05820E-04 50125.82c + 589 501251 Sn-125m 1.65660E-05 4.22050E-04 501251 + 590 501260 Sn-126 3.35070E-04 1.39740E-03 50126.82c + 591 501270 Sn-127 8.62450E-04 1.46500E-03 501270 + 592 501271 Sn-127m 3.57250E-04 1.94110E-03 501271 + 593 501280 Sn-128 1.30450E-03 6.84170E-03 501280 + 594 501281 Sn-128m 3.05560E-03 4.17880E-03 501281 + 595 501290 Sn-129 2.35540E-03 4.65470E-03 501290 + 596 501291 Sn-129m 5.68630E-03 5.90350E-03 501291 + 597 501300 Sn-130 3.43690E-03 4.33460E-03 501300 + 598 501301 Sn-130m 8.05010E-03 8.53430E-03 501301 + 599 501310 Sn-131 2.41790E-03 2.74410E-03 501310 + 600 501311 Sn-131m 5.83710E-03 6.01290E-03 501311 + 601 501320 Sn-132 4.67340E-03 4.73680E-03 501320 + 602 501330 Sn-133 6.45050E-04 6.46080E-04 501330 + 603 501340 Sn-134 9.44500E-05 9.44540E-05 501340 + 604 501350 Sn-135 7.19950E-06 7.19950E-06 501350 + 605 501360 Sn-136 1.30430E-07 1.30430E-07 501360 + 606 501370 Sn-137 1.92280E-09 1.92280E-09 501370 + 607 511230 Sb-123 4.15770E-12 1.25460E-04 51123.82c + 608 511240 Sb-124 6.97520E-11 1.63850E-10 51124.82c + 609 511241 Sb-124m 5.33340E-11 1.25470E-10 511241 + 610 511242 Sb-124m 7.21340E-11 7.21340E-11 511242 + 611 511250 Sb-125 1.64140E-06 5.29510E-04 51125.82c + 612 511260 Sb-126 3.69430E-06 4.57690E-06 51126.82c + 613 511261 Sb-126m 2.73150E-06 6.30390E-06 511261 + 614 511262 Sb-126m 3.57240E-06 3.57240E-06 511262 + 615 511270 Sb-127 8.91810E-05 3.49530E-03 511270 + 616 511280 Sb-128 1.63070E-04 7.01480E-03 511280 + 617 511281 Sb-128m 2.78260E-04 2.78260E-04 511281 + 618 511290 Sb-129 1.78510E-03 9.99790E-03 511290 + 619 511291 Sb-129m 1.09090E-03 4.04250E-03 511291 + 620 511300 Sb-130 4.53230E-03 1.31340E-02 511300 + 621 511301 Sb-130m 4.53230E-03 8.79940E-03 511301 + 622 511310 Sb-131 2.27130E-02 3.14700E-02 511310 + 623 511320 Sb-132 1.79060E-02 2.26430E-02 511320 + 624 511321 Sb-132m 1.31970E-02 1.31970E-02 511321 + 625 511330 Sb-133 3.35730E-02 3.42350E-02 511330 + 626 511340 Sb-134 3.76480E-03 3.84400E-03 511340 + 627 511341 Sb-134m 8.81820E-03 8.81890E-03 511341 + 628 511350 Sb-135 3.18430E-03 3.19000E-03 511350 + 629 511360 Sb-136 7.08730E-04 7.08820E-04 511360 + 630 511370 Sb-137 7.18780E-05 7.18790E-05 511370 + 631 511380 Sb-138 5.14630E-06 5.14630E-06 511380 + 632 511390 Sb-139 1.13820E-08 1.13820E-08 511390 + 633 521260 Te-126 2.05650E-10 9.99840E-06 52126.82c + 634 521270 Te-127 6.24080E-09 3.48150E-03 521270 + 635 521271 Te-127m 1.50660E-08 5.76030E-04 52527.82c + 636 521280 Te-128 8.09870E-06 7.29110E-03 52128.82c + 637 521290 Te-129 2.25840E-05 1.16350E-02 521290 + 638 521291 Te-129m 5.45220E-05 5.06950E-03 52529.82c + 639 521300 Te-130 6.55350E-04 2.25890E-02 52130.82c + 640 521310 Te-131 8.58750E-04 3.07740E-02 521310 + 641 521311 Te-131m 2.07320E-03 4.59270E-03 521311 + 642 521320 Te-132 1.19760E-02 4.78160E-02 52132.82c + 643 521330 Te-133 8.43520E-03 4.13560E-02 521330 + 644 521331 Te-133m 2.03640E-02 2.62870E-02 521331 + 645 521340 Te-134 5.39770E-02 6.71350E-02 521340 + 646 521350 Te-135 2.49120E-02 2.77170E-02 521350 + 647 521360 Te-136 1.48520E-02 1.54780E-02 521360 + 648 521370 Te-137 3.44540E-03 3.48210E-03 521370 + 649 521380 Te-138 7.46580E-04 7.51730E-04 521380 + 650 521390 Te-139 6.70540E-05 6.70650E-05 521390 + 651 521400 Te-140 8.54370E-06 8.54370E-06 521400 + 652 521410 Te-141 2.05800E-06 2.05800E-06 521410 + 653 521420 Te-142 2.02260E-09 2.02260E-09 521420 + 654 531290 I-129 1.24330E-06 1.35120E-02 53129.82c + 655 531300 I-130 4.27310E-06 5.80550E-06 53130.82c + 656 531301 I-130m 1.82430E-06 1.82430E-06 531301 + 657 531310 I-131 3.53930E-05 3.44370E-02 53131.82c + 658 531320 I-132 2.14300E-04 4.81660E-02 531320 + 659 531321 I-132m 1.57950E-04 1.57950E-04 531321 + 660 531330 I-133 1.66960E-03 6.57320E-02 531330 + 661 531331 I-133m 1.02030E-03 1.02030E-03 531331 + 662 531340 I-134 7.01090E-03 7.91940E-02 531340 + 663 531341 I-134m 5.16710E-03 5.16710E-03 531341 + 664 531350 I-135 3.50520E-02 6.27690E-02 53135.82c + 665 531360 I-136 1.60490E-02 3.15790E-02 531360 + 666 531361 I-136m 3.75890E-02 3.76420E-02 531361 + 667 531370 I-137 4.94880E-02 5.29130E-02 531370 + 668 531380 I-138 2.37790E-02 2.44830E-02 531380 + 669 531390 I-139 1.24660E-02 1.25330E-02 531390 + 670 531400 I-140 3.60950E-03 3.61800E-03 531400 + 671 531410 I-141 1.10640E-03 1.10850E-03 531410 + 672 531420 I-142 1.24610E-04 1.24610E-04 531420 + 673 531430 I-143 1.63820E-05 1.63820E-05 531430 + 674 531440 I-144 3.49310E-06 3.49310E-06 531440 + 675 541310 Xe-131 1.06100E-09 3.44370E-02 54131.82c + 676 541311 Xe-131m 2.56130E-09 3.74060E-04 541311 + 677 541320 Xe-132 1.42450E-07 4.81880E-02 54132.82c + 678 541321 Xe-132m 1.61470E-07 1.61470E-07 541321 + 679 541330 Xe-133 4.98280E-06 6.57490E-02 54133.82c + 680 541331 Xe-133m 1.20290E-05 1.88300E-03 541331 + 681 541340 Xe-134 5.89330E-05 7.95100E-02 54134.82c + 682 541341 Xe-134m 1.38040E-04 2.56880E-04 541341 + 683 541350 Xe-135 3.57690E-04 6.39230E-02 54135.82c + 684 541351 Xe-135m 8.63510E-04 1.12260E-02 541351 + 685 541360 Xe-136 1.12720E-02 8.39320E-02 54136.82c + 686 541370 Xe-137 1.85360E-02 6.93080E-02 541370 + 687 541380 Xe-138 3.42210E-02 5.86350E-02 541380 + 688 541390 Xe-139 2.20980E-02 3.37390E-02 541390 + 689 541400 Xe-140 2.15130E-02 2.50270E-02 541400 + 690 541410 Xe-141 1.22580E-02 1.31650E-02 541410 + 691 541420 Xe-142 4.53420E-03 4.63420E-03 541420 + 692 541430 Xe-143 7.16170E-04 7.27400E-04 541430 + 693 541440 Xe-144 1.42390E-04 1.44490E-04 541440 + 694 541450 Xe-145 1.77380E-05 1.77380E-05 541450 + 695 541460 Xe-146 6.88150E-08 6.88150E-08 541460 + 696 541470 Xe-147 6.72900E-10 6.72900E-10 541470 + 697 551340 Cs-134 2.95360E-08 5.13050E-08 55134.82c + 698 551341 Cs-134m 2.17690E-08 2.17690E-08 551341 + 699 551350 Cs-135 5.02690E-06 6.39980E-02 55135.82c + 700 551351 Cs-135m 3.07190E-06 3.07190E-06 551351 + 701 551360 Cs-136 6.20000E-05 8.01680E-05 55136.82c + 702 551361 Cs-136m 3.63350E-05 3.63350E-05 551361 + 703 551370 Cs-137 1.59780E-03 7.09050E-02 55137.82c + 704 551380 Cs-138 2.45820E-03 6.39190E-02 551380 + 705 551381 Cs-138m 3.48820E-03 3.48820E-03 551381 + 706 551390 Cs-139 1.37860E-02 4.75250E-02 551390 + 707 551400 Cs-140 1.93180E-02 4.43510E-02 551400 + 708 551410 Cs-141 4.26560E-02 5.58320E-02 551410 + 709 551420 Cs-142 3.79740E-02 4.25990E-02 551420 + 710 551430 Cs-143 2.11850E-02 2.19090E-02 551430 + 711 551440 Cs-144 5.35500E-03 8.17330E-03 551440 + 712 551441 Cs-144m 5.35500E-03 5.35540E-03 551441 + 713 551450 Cs-145 3.77370E-03 3.79060E-03 551450 + 714 551460 Cs-146 8.60330E-04 8.60390E-04 551460 + 715 551470 Cs-147 1.87130E-04 1.87130E-04 551470 + 716 551480 Cs-148 9.86090E-06 9.86090E-06 551480 + 717 551490 Cs-149 4.01210E-09 4.01210E-09 551490 + 718 561360 Ba-136 2.54510E-09 9.83430E-05 56136.82c + 719 561361 Ba-136m 5.96110E-09 5.96110E-09 561361 + 720 561370 Ba-137 8.30720E-07 7.09080E-02 56137.82c + 721 561371 Ba-137m 2.00550E-06 6.69360E-02 561371 + 722 561380 Ba-138 6.48290E-05 6.46460E-02 56138.82c + 723 561390 Ba-139 3.43820E-04 4.78690E-02 561390 + 724 561400 Ba-140 1.75560E-03 4.61070E-02 56140.82c + 725 561410 Ba-141 4.31670E-03 6.01480E-02 561410 + 726 561420 Ba-142 1.39880E-02 5.69460E-02 561420 + 727 561430 Ba-143 1.46910E-02 3.65030E-02 561430 + 728 561440 Ba-144 2.08760E-02 3.20080E-02 561440 + 729 561450 Ba-145 1.33110E-02 1.66820E-02 561450 + 730 561460 Ba-146 8.18160E-03 8.97310E-03 561460 + 731 561470 Ba-147 2.48400E-03 2.62030E-03 561470 + 732 561480 Ba-148 5.70830E-04 5.78220E-04 561480 + 733 561490 Ba-149 7.83660E-05 7.83700E-05 561490 + 734 561500 Ba-150 7.62360E-06 7.62360E-06 561500 + 735 561510 Ba-151 1.55370E-08 1.55370E-08 561510 + 736 561520 Ba-152 1.94320E-10 1.94320E-10 561520 + 737 571390 La-139 2.48170E-06 4.78720E-02 57139.82c + 738 571400 La-140 1.62310E-05 4.61230E-02 57140.82c + 739 571410 La-141 1.93430E-04 6.03420E-02 571410 + 740 571420 La-142 5.71270E-04 5.75170E-02 571420 + 741 571430 La-143 2.59510E-03 3.90980E-02 571430 + 742 571440 La-144 6.93640E-03 3.89440E-02 571440 + 743 571450 La-145 1.60860E-02 3.27680E-02 571450 + 744 571460 La-146 6.86980E-03 1.58430E-02 571460 + 745 571461 La-146m 1.23570E-02 1.23570E-02 571461 + 746 571470 La-147 1.75490E-02 2.01720E-02 571470 + 747 571480 La-148 9.54780E-03 1.01240E-02 571480 + 748 571490 La-149 4.64850E-03 4.72650E-03 571490 + 749 571500 La-150 1.47110E-03 1.47870E-03 571500 + 750 571510 La-151 3.39610E-04 3.39630E-04 571510 + 751 571520 La-152 4.78980E-05 4.78980E-05 571520 + 752 571530 La-153 6.69550E-06 6.69550E-06 571530 + 753 571540 La-154 5.13240E-10 5.13240E-10 571540 + 754 581410 Ce-141 1.02900E-06 6.03430E-02 58141.82c + 755 581420 Ce-142 2.00840E-06 5.75190E-02 58142.82c + 756 581430 Ce-143 2.02870E-05 3.91180E-02 58143.82c + 757 581440 Ce-144 1.18970E-04 3.90630E-02 58144.82c + 758 581450 Ce-145 5.23500E-04 3.32910E-02 581450 + 759 581460 Ce-146 2.41760E-03 3.06180E-02 581460 + 760 581470 Ce-147 3.64530E-03 2.38170E-02 581470 + 761 581480 Ce-148 6.41940E-03 1.66100E-02 581480 + 762 581490 Ce-149 5.41990E-03 1.01200E-02 581490 + 763 581500 Ce-150 4.17190E-03 5.61070E-03 581500 + 764 581510 Ce-151 1.93260E-03 2.27510E-03 581510 + 765 581520 Ce-152 6.52850E-04 6.97860E-04 581520 + 766 581530 Ce-153 1.22800E-04 1.29500E-04 581530 + 767 581540 Ce-154 1.84200E-05 1.84210E-05 581540 + 768 581550 Ce-155 2.63250E-06 2.63250E-06 581550 + 769 581560 Ce-156 1.74220E-09 1.74220E-09 581560 + 770 581570 Ce-157 9.94520E-12 9.94520E-12 581570 + 771 591440 Pr-144 8.83830E-08 3.90630E-02 591440 + 772 591441 Pr-144m 7.84970E-07 5.39830E-04 591441 + 773 591450 Pr-145 8.40960E-06 3.33000E-02 591450 + 774 591460 Pr-146 4.91040E-05 3.06670E-02 591460 + 775 591470 Pr-147 3.06530E-04 2.41230E-02 591470 + 776 591480 Pr-148 1.49500E-04 1.67590E-02 591480 + 777 591481 Pr-148m 6.28730E-04 6.28730E-04 591481 + 778 591490 Pr-149 2.64440E-03 1.27650E-02 591490 + 779 591500 Pr-150 4.38120E-03 9.99190E-03 591500 + 780 591510 Pr-151 5.16320E-03 7.43830E-03 591510 + 781 591520 Pr-152 3.42050E-03 4.11920E-03 591520 + 782 591530 Pr-153 1.93880E-03 2.06760E-03 591530 + 783 591540 Pr-154 6.93500E-04 7.11800E-04 591540 + 784 591550 Pr-155 2.05950E-04 2.08580E-04 591550 + 785 591560 Pr-156 3.53630E-05 3.53650E-05 591560 + 786 591570 Pr-157 5.22900E-06 5.22900E-06 591570 + 787 591580 Pr-158 2.68220E-09 2.68220E-09 591580 + 788 591590 Pr-159 3.74900E-11 3.74900E-11 591590 + 789 601460 Nd-146 2.18460E-09 3.06670E-02 60146.82c + 790 601470 Nd-147 7.94080E-08 2.41230E-02 60147.82c + 791 601480 Nd-148 3.59510E-06 1.73910E-02 60148.82c + 792 601490 Nd-149 2.05950E-05 1.27850E-02 601490 + 793 601500 Nd-150 1.28560E-04 1.01200E-02 60150.82c + 794 601510 Nd-151 3.77510E-04 7.81580E-03 601510 + 795 601520 Nd-152 9.25730E-04 5.04490E-03 601520 + 796 601530 Nd-153 1.01810E-03 3.08570E-03 601530 + 797 601540 Nd-154 8.47950E-04 1.55970E-03 601540 + 798 601550 Nd-155 4.66000E-04 6.75540E-04 601550 + 799 601560 Nd-156 1.82900E-04 2.17640E-04 601560 + 800 601570 Nd-157 5.51970E-05 6.00920E-05 601570 + 801 601580 Nd-158 6.50880E-06 6.51150E-06 601580 + 802 601590 Nd-159 1.19480E-07 1.19520E-07 601590 + 803 601600 Nd-160 3.04040E-09 3.04040E-09 601600 + 804 601610 Nd-161 4.27670E-11 4.27670E-11 601610 + 805 611490 Pm-149 7.13270E-09 1.27850E-02 61149.82c + 806 611500 Pm-150 2.18040E-06 2.18040E-06 611500 + 807 611510 Pm-151 1.61360E-05 7.83200E-03 61151.82c + 808 611520 Pm-152 7.34740E-06 5.05220E-03 611520 + 809 611521 Pm-152m 1.46720E-05 1.46720E-05 611521 + 810 611522 Pm-152m 1.62290E-05 1.62290E-05 611522 + 811 611530 Pm-153 1.55600E-04 3.24130E-03 611530 + 812 611540 Pm-154 1.36030E-04 1.69580E-03 611540 + 813 611541 Pm-154m 1.36030E-04 1.36030E-04 611541 + 814 611550 Pm-155 4.55210E-04 1.13080E-03 611550 + 815 611560 Pm-156 3.55300E-04 5.72940E-04 611560 + 816 611570 Pm-157 2.63220E-04 3.23310E-04 611570 + 817 611580 Pm-158 1.20070E-04 1.26580E-04 611580 + 818 611590 Pm-159 2.94450E-05 2.95640E-05 611590 + 819 611600 Pm-160 6.28930E-06 6.29230E-06 611600 + 820 611610 Pm-161 9.79990E-08 9.80420E-08 611610 + 821 611620 Pm-162 4.92000E-09 4.92000E-09 611620 + 822 611630 Pm-163 1.72640E-11 1.72640E-11 611630 + 823 621510 Sm-151 4.25680E-10 7.83200E-03 62151.82c + 824 621520 Sm-152 1.98210E-08 5.08320E-03 62152.82c + 825 621530 Sm-153 3.92600E-07 3.24270E-03 62153.82c + 826 621531 Sm-153m 9.47800E-07 9.47800E-07 621531 + 827 621540 Sm-154 5.28070E-06 1.83710E-03 62154.82c + 828 621550 Sm-155 1.44760E-05 1.14520E-03 621550 + 829 621560 Sm-156 1.44970E-05 5.87430E-04 621560 + 830 621570 Sm-157 4.30530E-05 3.66370E-04 621570 + 831 621580 Sm-158 6.09620E-05 1.87550E-04 621580 + 832 621590 Sm-159 4.21430E-05 7.17190E-05 621590 + 833 621600 Sm-160 1.25730E-05 1.88490E-05 621600 + 834 621610 Sm-161 3.80340E-06 3.90140E-06 621610 + 835 621620 Sm-162 1.40820E-06 1.41310E-06 621620 + 836 621630 Sm-163 1.20030E-08 1.20200E-08 621630 + 837 621640 Sm-164 1.32010E-09 1.32010E-09 621640 + 838 621650 Sm-165 1.75450E-10 1.75450E-10 621650 + 839 631540 Eu-154 3.43650E-10 6.53210E-10 63154.82c + 840 631541 Eu-154m 3.09560E-10 3.09560E-10 631541 + 841 631550 Eu-155 2.14170E-08 1.14530E-03 63155.82c + 842 631560 Eu-156 3.95600E-06 5.91390E-04 63156.82c + 843 631570 Eu-157 5.23040E-06 3.71600E-04 63157.82c + 844 631580 Eu-158 7.79780E-06 1.95350E-04 631580 + 845 631590 Eu-159 1.53120E-05 8.70310E-05 631590 + 846 631600 Eu-160 1.00500E-05 2.88990E-05 631600 + 847 631610 Eu-161 8.87180E-06 1.27730E-05 631610 + 848 631620 Eu-162 1.26310E-05 1.40440E-05 631620 + 849 631630 Eu-163 8.36260E-07 8.48280E-07 631630 + 850 631640 Eu-164 6.62900E-07 6.64220E-07 631640 + 851 631650 Eu-165 8.88470E-08 8.90220E-08 631650 + 852 631660 Eu-166 4.26600E-09 4.26600E-09 631660 + 853 631670 Eu-167 2.75710E-10 2.75710E-10 631670 + 854 641560 Gd-156 4.14800E-11 5.91390E-04 64156.82c + 855 641570 Gd-157 8.75180E-10 3.71600E-04 64157.82c + 856 641580 Gd-158 1.89300E-08 1.95370E-04 64158.82c + 857 641590 Gd-159 1.11900E-07 8.71420E-05 641590 + 858 641600 Gd-160 4.78590E-07 2.93770E-05 64160.82c + 859 641610 Gd-161 3.80120E-06 1.65740E-05 641610 + 860 641620 Gd-162 1.14820E-06 1.51920E-05 641620 + 861 641630 Gd-163 3.98190E-07 1.24650E-06 641630 + 862 641640 Gd-164 5.28830E-07 1.19300E-06 641640 + 863 641650 Gd-165 9.65860E-07 1.05490E-06 641650 + 864 641660 Gd-166 2.92420E-07 2.96690E-07 641660 + 865 641670 Gd-167 4.34390E-08 4.37150E-08 641670 + 866 641680 Gd-168 5.80070E-09 5.80070E-09 641680 + 867 641690 Gd-169 2.71220E-10 2.71220E-10 641690 + 868 651590 Tb-159 3.46070E-11 8.71430E-05 65159.82c + 869 651600 Tb-160 3.64510E-10 3.64510E-10 65160.82c + 870 651610 Tb-161 6.41530E-09 1.65810E-05 651610 + 871 651620 Tb-162 5.39480E-08 1.52460E-05 651620 + 872 651630 Tb-163 3.21300E-08 1.27860E-06 651630 + 873 651640 Tb-164 8.44070E-08 1.27750E-06 651640 + 874 651650 Tb-165 8.41450E-07 1.89630E-06 651650 + 875 651660 Tb-166 8.61300E-07 1.15800E-06 651660 + 876 651670 Tb-167 3.82440E-07 4.26160E-07 651670 + 877 651680 Tb-168 1.04280E-07 1.10080E-07 651680 + 878 651690 Tb-169 3.19330E-08 3.22040E-08 651690 + 879 651700 Tb-170 3.00610E-09 3.00610E-09 651700 + 880 651710 Tb-171 3.05770E-10 3.05770E-10 651710 + 881 661620 Dy-162 3.67440E-11 1.52460E-05 66162.82c + 882 661630 Dy-163 5.46900E-11 1.27870E-06 66163.82c + 883 661640 Dy-164 1.01200E-09 1.27850E-06 66164.82c + 884 661650 Dy-165 1.96000E-08 1.91890E-06 661650 + 885 661651 Dy-165m 2.99620E-09 2.99620E-09 661651 + 886 661660 Dy-166 7.57040E-08 1.23370E-06 661660 + 887 661670 Dy-167 1.19570E-07 5.45720E-07 661670 + 888 661680 Dy-168 1.74960E-07 2.85040E-07 661680 + 889 661690 Dy-169 9.83190E-08 1.30520E-07 661690 + 890 661700 Dy-170 5.34860E-08 5.64920E-08 661700 + 891 661710 Dy-171 1.15700E-08 1.18760E-08 661710 + 892 661720 Dy-172 2.82950E-09 2.82950E-09 661720 + 893 661730 Dy-173 2.12870E-10 2.12870E-10 661730 + 894 671650 Ho-165 2.78940E-11 1.91900E-06 67165.82c + 895 671660 Ho-166 6.83730E-11 1.23380E-06 671660 + 896 671661 Ho-166m 1.60150E-10 1.60150E-10 671661 + 897 671670 Ho-167 2.47410E-09 5.48200E-07 671670 + 898 671680 Ho-168 3.23050E-09 2.92830E-07 671680 + 899 671681 Ho-168m 4.58400E-09 4.58400E-09 671681 + 900 671690 Ho-169 2.57550E-08 1.56280E-07 671690 + 901 671700 Ho-170 1.81700E-08 1.81700E-08 671700 + 902 671701 Ho-170m 7.75740E-09 6.42490E-08 671701 + 903 671710 Ho-171 3.00150E-08 4.18910E-08 671710 + 904 671720 Ho-172 1.38190E-08 1.66480E-08 671720 + 905 671730 Ho-173 6.25300E-09 6.46590E-09 671730 + 906 671740 Ho-174 9.97850E-10 9.97850E-10 671740 + 907 671750 Ho-175 1.92110E-10 1.92110E-10 671750 + 908 681680 Er-168 2.16190E-11 2.92880E-07 68168.82c + 909 681690 Er-169 1.70140E-10 1.56450E-07 681690 + 910 681700 Er-170 1.13700E-09 8.35560E-08 68170.82c + 911 681710 Er-171 2.72970E-09 4.46200E-08 681710 + 912 681720 Er-172 7.09910E-09 2.37480E-08 681720 + 913 681730 Er-173 5.83820E-09 1.23040E-08 681730 + 914 681740 Er-174 5.04480E-09 6.04270E-09 681740 + 915 681750 Er-175 1.89320E-09 2.08530E-09 681750 + 916 681760 Er-176 7.25100E-10 7.25100E-10 681760 + 917 681770 Er-177 9.12970E-11 9.12970E-11 681770 + 918 691710 Tm-171 1.34020E-11 4.46340E-08 691710 + 919 691720 Tm-172 8.10400E-11 2.38290E-08 691720 + 920 691730 Tm-173 4.26520E-10 1.27310E-08 691730 + 921 691740 Tm-174 7.33750E-10 6.77640E-09 691740 + 922 691750 Tm-175 1.50910E-09 3.59440E-09 691750 + 923 691760 Tm-176 1.04620E-09 1.77130E-09 691760 + 924 691770 Tm-177 7.31160E-10 8.22460E-10 691770 + 925 691780 Tm-178 2.08020E-10 2.08020E-10 691780 + 926 691790 Tm-179 6.57550E-11 6.57550E-11 691790 + 927 701740 Yb-174 7.89300E-12 6.78430E-09 701740 + 928 701750 Yb-175 3.17140E-11 3.63100E-09 701750 + 929 701751 Yb-175m 4.84810E-12 2.77250E-09 701751 + 930 701760 Yb-176 5.57000E-11 1.82860E-09 701760 + 931 701761 Yb-176m 1.00190E-10 9.85840E-10 701761 + 932 701770 Yb-177 1.69600E-10 1.03130E-09 701770 + 933 701771 Yb-177m 3.92160E-11 8.61670E-10 701771 + 934 701780 Yb-178 3.19410E-10 5.27430E-10 701780 + 935 701790 Yb-179 1.84720E-10 2.50480E-10 701790 + 936 701800 Yb-180 1.03590E-10 1.03590E-10 701800 + 937 701810 Yb-181 2.34200E-11 2.34200E-11 701810 + 938 711770 Lu-177 2.76870E-12 1.03430E-09 711770 + 939 711771 Lu-177m 1.08240E-12 1.09990E-12 711771 + 940 711780 Lu-178 6.05230E-12 5.33480E-10 711780 + 941 711781 Lu-178m 6.86070E-12 6.86070E-12 711781 + 942 711790 Lu-179 3.82410E-11 2.94560E-10 711790 + 943 711791 Lu-179m 5.84590E-12 2.56320E-10 711791 + 944 711800 Lu-180 1.32250E-11 8.13780E-11 711800 + 945 711801 Lu-180m 1.32250E-11 1.16810E-10 711801 + 946 711802 Lu-180m 1.94910E-11 1.94910E-11 711802 + 947 711810 Lu-181 5.55510E-11 7.89710E-11 711810 + 948 711820 Lu-182 2.64730E-11 2.64730E-11 711820 + 949 711830 Lu-183 1.23340E-11 1.23340E-11 711830 + 950 711840 Lu-184 2.05460E-12 2.05460E-12 711840 + 951 721800 Hf-180 6.49320E-13 1.51320E-10 72180.82c + 952 721801 Hf-180m 1.16800E-12 1.09140E-11 721801 + 953 721810 Hf-181 4.58770E-12 8.35590E-11 721810 + 954 721820 Hf-182 4.43800E-12 3.42640E-11 721820 + 955 721821 Hf-182m 7.98300E-12 7.98300E-12 721821 + 956 721830 Hf-183 1.05380E-11 2.28720E-11 721830 + 957 721840 Hf-184 3.38690E-12 4.41420E-12 721840 + 958 721841 Hf-184m 6.09230E-12 7.11960E-12 721841 + 959 721850 Hf-185 3.69110E-12 3.69110E-12 721850 + 960 721860 Hf-186 1.45500E-12 1.45500E-12 721860 + 961 731840 Ta-184 1.25590E-12 1.27900E-11 731840 + 962 731850 Ta-185 1.81330E-12 6.38260E-12 731850 + 963 731860 Ta-186 1.91980E-12 3.37480E-12 731860 + 964 731870 Ta-187 1.39330E-12 1.39330E-12 731870 + + Neutron-induced fission: + + Interpolation region : 2 / 2 + Interpolation energy : 4.00000E-01 MeV + Number of products : 931 / 1025 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 2.94220E-05 2.94220E-05 1001.82c + 2 10020 H-2 8.99170E-06 8.99170E-06 1002.82c + 3 10030 H-3 1.25000E-04 1.25000E-04 1003.82c + 4 20040 He-4 1.86000E-03 1.86000E-03 2004.82c + 5 220540 Ti-54 1.91080E-12 1.91080E-12 220540 + 6 220550 Ti-55 3.26700E-12 3.26700E-12 220550 + 7 220560 Ti-56 4.88480E-12 4.88480E-12 220560 + 8 220570 Ti-57 3.02250E-12 3.02250E-12 220570 + 9 220580 Ti-58 1.67940E-12 1.67940E-12 220580 + 10 230550 V-55 1.71360E-12 4.98060E-12 230550 + 11 230560 V-56 5.46590E-12 1.03600E-11 230560 + 12 230570 V-57 1.56420E-11 1.86550E-11 230570 + 13 230580 V-58 2.03950E-11 2.20740E-11 230580 + 14 230590 V-59 2.45770E-11 2.45770E-11 230590 + 15 230600 V-60 1.15590E-11 1.15590E-11 230600 + 16 230610 V-61 5.25190E-12 5.25190E-12 230610 + 17 240570 Cr-57 4.03340E-12 4.02740E-11 240570 + 18 240580 Cr-58 2.40490E-11 2.84640E-11 240580 + 19 240590 Cr-59 6.20520E-11 8.66290E-11 240590 + 20 240600 Cr-60 1.38980E-10 1.50850E-10 240600 + 21 240610 Cr-61 1.54140E-10 1.59080E-10 240610 + 22 240620 Cr-62 1.54670E-10 1.54670E-10 240620 + 23 240630 Cr-63 5.79590E-11 5.79590E-11 240630 + 24 240640 Cr-64 1.82520E-11 1.82520E-11 240640 + 25 240650 Cr-65 2.55580E-12 2.55580E-12 240650 + 26 250590 Mn-59 9.29130E-12 9.59200E-11 250590 + 27 250600 Mn-60 4.14050E-12 1.59840E-10 250600 + 28 250601 Mn-60m 4.21220E-11 4.21220E-11 250601 + 29 250610 Mn-61 2.31830E-10 3.90910E-10 250610 + 30 250620 Mn-62 4.37990E-10 5.15320E-10 250620 + 31 250621 Mn-62m 6.85910E-11 1.45930E-10 250621 + 32 250630 Mn-63 9.37250E-10 9.95210E-10 250630 + 33 250640 Mn-64 7.49080E-10 7.67330E-10 250640 + 34 250650 Mn-65 6.05870E-10 6.08430E-10 250650 + 35 250660 Mn-66 1.86000E-10 1.86000E-10 250660 + 36 250670 Mn-67 4.72990E-11 4.72990E-11 250670 + 37 250680 Mn-68 4.81650E-12 4.81650E-12 250680 + 38 260600 Fe-60 1.29830E-12 1.98410E-10 260600 + 39 260610 Fe-61 1.63690E-11 4.07280E-10 260610 + 40 260620 Fe-62 1.75100E-10 8.36350E-10 260620 + 41 260630 Fe-63 7.02020E-10 1.69720E-09 260630 + 42 260640 Fe-64 2.53900E-09 3.30630E-09 260640 + 43 260650 Fe-65 4.59790E-09 5.20630E-09 260650 + 44 260660 Fe-66 7.24940E-09 7.43540E-09 260660 + 45 260670 Fe-67 4.85060E-09 4.89790E-09 260670 + 46 260680 Fe-68 2.93070E-09 2.93550E-09 260680 + 47 260690 Fe-69 6.98800E-10 6.98800E-10 260690 + 48 260700 Fe-70 1.29270E-10 1.29270E-10 260700 + 49 260710 Fe-71 1.05170E-11 1.05170E-11 260710 + 50 270620 Co-62 3.30750E-13 8.36690E-10 270620 + 51 270630 Co-63 2.74440E-11 1.72470E-09 270630 + 52 270640 Co-64 2.40110E-10 3.54640E-09 270640 + 53 270650 Co-65 2.05550E-09 7.26180E-09 270650 + 54 270660 Co-66 6.92500E-09 1.43600E-08 270660 + 55 270670 Co-67 2.12850E-08 2.61830E-08 270670 + 56 270680 Co-68 1.70810E-08 2.49470E-08 270680 + 57 270681 Co-68m 1.27490E-08 1.57340E-08 270681 + 58 270690 Co-69 3.79890E-08 3.86390E-08 270690 + 59 270700 Co-70 9.54800E-09 9.54800E-09 270700 + 60 270701 Co-70m 9.54800E-09 9.67730E-09 270701 + 61 270710 Co-71 9.43530E-09 9.44580E-09 270710 + 62 270720 Co-72 1.83120E-09 1.83120E-09 270720 + 63 270730 Co-73 3.80180E-10 3.80180E-10 270730 + 64 270740 Co-74 8.94320E-12 8.94320E-12 270740 + 65 280640 Ni-64 1.54890E-12 3.54800E-09 28064.82c + 66 280650 Ni-65 3.61080E-11 7.29790E-09 280650 + 67 280660 Ni-66 6.51540E-10 1.50120E-08 280660 + 68 280670 Ni-67 4.65820E-09 3.08410E-08 280670 + 69 280680 Ni-68 3.00360E-08 6.32370E-08 280680 + 70 280690 Ni-69 4.08460E-08 7.90980E-08 280690 + 71 280691 Ni-69m 4.08460E-08 4.08460E-08 280691 + 72 280700 Ni-70 1.93670E-07 2.12900E-07 280700 + 73 280710 Ni-71 2.30820E-07 2.40270E-07 280710 + 74 280720 Ni-72 2.48190E-07 2.50020E-07 280720 + 75 280730 Ni-73 1.43900E-07 1.44280E-07 280730 + 76 280740 Ni-74 2.10030E-08 2.10120E-08 280740 + 77 280750 Ni-75 7.80320E-09 7.80320E-09 280750 + 78 280760 Ni-76 6.67310E-10 6.67310E-10 280760 + 79 280770 Ni-77 2.65800E-11 2.65800E-11 280770 + 80 290660 Cu-66 1.01930E-12 1.50130E-08 290660 + 81 290670 Cu-67 4.33210E-11 3.08840E-08 290670 + 82 290680 Cu-68 1.97770E-10 6.38870E-08 290680 + 83 290681 Cu-68m 5.39090E-10 5.39090E-10 290681 + 84 290690 Cu-69 1.03230E-08 1.30270E-07 290690 + 85 290700 Cu-70 3.71860E-09 3.28790E-08 290700 + 86 290701 Cu-70m 4.74900E-08 5.83210E-08 290701 + 87 290702 Cu-70m 3.71860E-09 2.16610E-07 290702 + 88 290710 Cu-71 2.96420E-07 5.36690E-07 290710 + 89 290720 Cu-72 6.89660E-07 9.39680E-07 290720 + 90 290730 Cu-73 2.69790E-06 2.84220E-06 290730 + 91 290740 Cu-74 7.01740E-07 7.22880E-07 290740 + 92 290750 Cu-75 2.88390E-06 2.89160E-06 290750 + 93 290760 Cu-76 3.70530E-07 3.70860E-07 290760 + 94 290761 Cu-76m 3.70530E-07 3.70860E-07 290761 + 95 290770 Cu-77 9.09550E-08 9.09820E-08 290770 + 96 290780 Cu-78 1.21840E-08 1.21840E-08 290780 + 97 290790 Cu-79 8.77970E-10 8.77970E-10 290790 + 98 290800 Cu-80 2.44600E-11 2.44600E-11 290800 + 99 300680 Zn-68 1.02740E-12 6.39750E-08 300680 + 100 300690 Zn-69 6.95300E-12 1.30310E-07 300690 + 101 300691 Zn-69m 3.45330E-11 3.45330E-11 300691 + 102 300700 Zn-70 1.27780E-09 2.69100E-07 300700 + 103 300710 Zn-71 2.94140E-09 5.39630E-07 300710 + 104 300711 Zn-71m 1.46090E-08 1.46090E-08 300711 + 105 300720 Zn-72 2.02190E-07 1.14190E-06 300720 + 106 300730 Zn-73 5.91520E-08 3.24990E-06 300730 + 107 300731 Zn-73m 8.18140E-08 3.48610E-07 300731 + 108 300732 Zn-73m 5.33580E-07 5.33580E-07 300732 + 109 300740 Zn-74 1.40340E-06 2.22750E-06 300740 + 110 300750 Zn-75 9.37270E-06 1.21740E-05 300750 + 111 300760 Zn-76 1.70440E-05 1.77750E-05 300760 + 112 300770 Zn-77 1.11150E-05 1.19460E-05 300770 + 113 300771 Zn-77m 1.47990E-06 1.47990E-06 300771 + 114 300780 Zn-78 2.02760E-05 2.02890E-05 300780 + 115 300790 Zn-79 4.52840E-06 4.52880E-06 300790 + 116 300800 Zn-80 2.48670E-06 2.48670E-06 300800 + 117 300810 Zn-81 8.05190E-07 8.05190E-07 300810 + 118 300820 Zn-82 9.26050E-10 9.26050E-10 300820 + 119 310710 Ga-71 3.61330E-11 5.54270E-07 310710 + 120 310720 Ga-72 1.06860E-09 1.14310E-06 310720 + 121 310721 Ga-72m 1.05040E-10 3.81530E-08 310721 + 122 310730 Ga-73 4.06610E-08 3.55740E-06 310730 + 123 310740 Ga-74 3.50870E-07 2.28460E-06 310740 + 124 310741 Ga-74m 3.50870E-07 2.57840E-06 310741 + 125 310750 Ga-75 2.88390E-06 1.50580E-05 310750 + 126 310760 Ga-76 4.44620E-06 2.22210E-05 310760 + 127 310770 Ga-77 2.00030E-05 3.26890E-05 310770 + 128 310780 Ga-78 3.58730E-05 5.62210E-05 310780 + 129 310790 Ga-79 5.50960E-05 5.95660E-05 310790 + 130 310800 Ga-80 2.81830E-05 3.07300E-05 310800 + 131 310810 Ga-81 2.09350E-05 2.16800E-05 310810 + 132 310820 Ga-82 3.97980E-06 3.98070E-06 310820 + 133 310830 Ga-83 1.67610E-06 1.67610E-06 310830 + 134 310840 Ga-84 1.89370E-08 1.89370E-08 310840 + 135 310850 Ga-85 6.29590E-10 6.29590E-10 310850 + 136 320730 Ge-73 2.93470E-11 3.55740E-06 32073.82c + 137 320731 Ge-73m 5.90890E-12 3.50520E-06 320731 + 138 320740 Ge-74 8.72230E-10 2.93010E-06 32074.82c + 139 320750 Ge-75 6.34020E-09 1.51120E-05 320750 + 140 320751 Ge-75m 4.76190E-08 6.49940E-07 320751 + 141 320760 Ge-76 7.41060E-07 2.29620E-05 32076.82c + 142 320770 Ge-77 7.84570E-06 1.42550E-05 320770 + 143 320771 Ge-77m 1.04460E-06 3.37340E-05 320771 + 144 320780 Ge-78 4.83480E-05 1.04620E-04 320780 + 145 320790 Ge-79 1.31240E-05 7.64930E-05 320790 + 146 320791 Ge-79m 9.85660E-05 9.86560E-05 320791 + 147 320800 Ge-80 2.53640E-04 2.86950E-04 320800 + 148 320810 Ge-81 2.44660E-04 2.55760E-04 320810 + 149 320811 Ge-81m 4.92610E-05 5.86980E-05 320811 + 150 320820 Ge-82 3.47910E-04 3.51660E-04 320820 + 151 320830 Ge-83 1.60100E-04 1.61170E-04 320830 + 152 320840 Ge-84 6.53360E-05 6.53420E-05 320840 + 153 320850 Ge-85 8.40840E-06 8.40900E-06 320850 + 154 320860 Ge-86 6.65610E-06 6.65610E-06 320860 + 155 320870 Ge-87 1.17050E-08 1.17050E-08 320870 + 156 320880 Ge-88 6.29070E-10 6.29070E-10 320880 + 157 330750 As-75 4.91980E-12 1.51120E-05 33075.82c + 158 330751 As-75m 1.86310E-11 2.13610E-10 330751 + 159 330760 As-76 9.95080E-10 9.95080E-10 330760 + 160 330770 As-77 4.07920E-08 4.16200E-05 330770 + 161 330780 As-78 7.79830E-07 1.05400E-04 330780 + 162 330790 As-79 5.28290E-06 1.76490E-04 330790 + 163 330800 As-80 3.31550E-05 3.20100E-04 330800 + 164 330810 As-81 1.48950E-04 4.62820E-04 330810 + 165 330820 As-82 9.06940E-05 4.42360E-04 330820 + 166 330821 As-82m 3.16010E-04 3.16010E-04 330821 + 167 330830 As-83 7.88020E-04 9.56250E-04 330830 + 168 330840 As-84 3.53800E-04 3.83530E-04 330840 + 169 330841 As-84m 3.53800E-04 3.83530E-04 330841 + 170 330850 As-85 5.62350E-04 5.69580E-04 330850 + 171 330860 As-86 1.95100E-04 2.01760E-04 330860 + 172 330870 As-87 6.94520E-05 6.94640E-05 330870 + 173 330880 As-88 1.05010E-05 1.05020E-05 330880 + 174 330890 As-89 3.13030E-06 3.13030E-06 330890 + 175 330900 As-90 4.09600E-09 4.09600E-09 330900 + 176 340770 Se-77 8.51750E-13 4.16200E-05 34077.82c + 177 340771 Se-77m 6.39710E-12 6.39710E-12 340771 + 178 340780 Se-78 1.03910E-09 1.05400E-04 34078.82c + 179 340790 Se-79 3.27090E-08 1.76430E-04 34079.82c + 180 340791 Se-79m 4.35500E-09 1.72310E-04 340791 + 181 340800 Se-80 4.97320E-06 3.25080E-04 34080.82c + 182 340810 Se-81 3.12200E-06 4.89370E-04 340810 + 183 340811 Se-81m 2.34480E-05 4.00620E-05 340811 + 184 340820 Se-82 1.83030E-04 9.41390E-04 34082.82c + 185 340830 Se-83 6.15120E-04 9.59900E-04 340830 + 186 340831 Se-83m 1.23850E-04 7.36390E-04 340831 + 187 340840 Se-84 2.62840E-03 3.51970E-03 340840 + 188 340850 Se-85 3.62970E-03 4.14050E-03 340850 + 189 340860 Se-86 4.73430E-03 4.88020E-03 340860 + 190 340870 Se-87 3.22000E-03 3.27880E-03 340870 + 191 340880 Se-88 1.82000E-03 1.83050E-03 340880 + 192 340890 Se-89 4.98510E-04 5.01640E-04 340890 + 193 340900 Se-90 1.06690E-04 1.06690E-04 340900 + 194 340910 Se-91 1.39070E-05 1.39070E-05 340910 + 195 340920 Se-92 2.21200E-06 2.21200E-06 340920 + 196 340930 Se-93 1.44450E-09 1.44450E-09 340930 + 197 350790 Br-79 1.12520E-12 9.64990E-08 35079.82c + 198 350791 Br-79m 4.26110E-12 4.26110E-12 350791 + 199 350800 Br-80 7.09090E-11 3.17980E-10 350800 + 200 350801 Br-80m 2.47070E-10 2.47070E-10 350801 + 201 350810 Br-81 2.04630E-08 4.89410E-04 35081.82c + 202 350820 Br-82 4.66130E-07 6.33040E-07 350820 + 203 350821 Br-82m 1.71010E-07 1.71010E-07 350821 + 204 350830 Br-83 1.34060E-05 1.70970E-03 350830 + 205 350840 Br-84 8.10350E-05 3.60070E-03 350840 + 206 350841 Br-84m 8.10350E-05 8.10350E-05 350841 + 207 350850 Br-85 9.16500E-04 5.05700E-03 350850 + 208 350860 Br-86 2.37770E-03 7.25790E-03 350860 + 209 350870 Br-87 5.24700E-03 8.54390E-03 350870 + 210 350880 Br-88 6.97710E-03 8.82860E-03 350880 + 211 350890 Br-89 6.45110E-03 6.91360E-03 350890 + 212 350900 Br-90 2.76180E-03 2.87140E-03 350900 + 213 350910 Br-91 1.52320E-03 1.53420E-03 350910 + 214 350920 Br-92 3.06020E-04 3.08230E-04 350920 + 215 350930 Br-93 7.14500E-05 7.14510E-05 350930 + 216 350940 Br-94 4.06390E-06 4.06390E-06 350940 + 217 350950 Br-95 1.42470E-08 1.42470E-08 350950 + 218 360820 Kr-82 1.65360E-10 6.37300E-07 36082.82c + 219 360830 Kr-83 9.03570E-09 1.70970E-03 36083.82c + 220 360831 Kr-83m 1.81930E-09 1.70820E-03 360831 + 221 360840 Kr-84 5.76410E-06 3.68750E-03 36084.82c + 222 360850 Kr-85 5.36350E-05 1.14460E-03 36085.82c + 223 360851 Kr-85m 1.07990E-05 5.05960E-03 360851 + 224 360860 Kr-86 6.37260E-04 8.10960E-03 36086.82c + 225 360870 Kr-87 2.24910E-03 1.11700E-02 360870 + 226 360880 Kr-88 8.82110E-03 1.80330E-02 360880 + 227 360890 Kr-89 1.51710E-02 2.18160E-02 360890 + 228 360900 Kr-90 1.96910E-02 2.21630E-02 360900 + 229 360910 Kr-91 1.80870E-02 1.94160E-02 360910 + 230 360920 Kr-92 1.45210E-02 1.47760E-02 360920 + 231 360930 Kr-93 5.04210E-03 5.06780E-03 360930 + 232 360940 Kr-94 1.73330E-03 1.73450E-03 360940 + 233 360950 Kr-95 2.33260E-04 2.33270E-04 360950 + 234 360960 Kr-96 4.89060E-05 4.89060E-05 360960 + 235 360970 Kr-97 1.18130E-07 1.18130E-07 360970 + 236 360980 Kr-98 2.60320E-09 2.60320E-09 360980 + 237 370850 Rb-85 4.72190E-09 5.12150E-03 37085.82c + 238 370860 Rb-86 6.13870E-07 1.90170E-06 37086.82c + 239 370861 Rb-86m 1.28780E-06 1.28780E-06 370861 + 240 370870 Rb-87 3.12860E-05 1.12010E-02 37087.82c + 241 370880 Rb-88 2.05870E-04 1.82390E-02 370880 + 242 370890 Rb-89 1.57080E-03 2.33870E-02 370890 + 243 370900 Rb-90 3.56530E-04 1.97900E-02 370900 + 244 370901 Rb-90m 3.62710E-03 6.52600E-03 370901 + 245 370910 Rb-91 1.23630E-02 3.17790E-02 370910 + 246 370920 Rb-92 2.03660E-02 3.51420E-02 370920 + 247 370930 Rb-93 2.35060E-02 2.85930E-02 370930 + 248 370940 Rb-94 1.47360E-02 1.64580E-02 370940 + 249 370950 Rb-95 8.81750E-03 9.04590E-03 370950 + 250 370960 Rb-96 1.42590E-03 2.17420E-03 370960 + 251 370961 Rb-96m 1.42590E-03 1.44940E-03 370961 + 252 370970 Rb-97 8.21980E-04 8.22090E-04 370970 + 253 370980 Rb-98 5.89600E-05 5.89600E-05 370980 + 254 370981 Rb-98m 5.89600E-05 5.89620E-05 370981 + 255 370990 Rb-99 1.47470E-05 1.47470E-05 370990 + 256 371000 Rb-100 1.65380E-08 1.65380E-08 371000 + 257 380870 Sr-87 7.89940E-10 9.48510E-10 38087.82c + 258 380871 Sr-87m 1.59050E-10 1.59050E-10 380871 + 259 380880 Sr-88 8.40070E-06 1.82470E-02 38088.82c + 260 380890 Sr-89 4.48760E-05 2.34320E-02 38089.82c + 261 380900 Sr-90 4.45410E-04 2.65920E-02 38090.82c + 262 380910 Sr-91 2.11650E-03 3.38960E-02 380910 + 263 380920 Sr-92 1.03240E-02 4.58660E-02 380920 + 264 380930 Sr-93 2.01410E-02 4.99960E-02 380930 + 265 380940 Sr-94 3.94060E-02 5.49800E-02 380940 + 266 380950 Sr-95 3.79840E-02 4.65430E-02 380950 + 267 380960 Sr-96 3.73430E-02 4.01570E-02 380960 + 268 380970 Sr-97 1.88130E-02 1.94370E-02 380970 + 269 380980 Sr-98 9.54930E-03 9.66140E-03 380980 + 270 380990 Sr-99 2.03130E-03 2.04370E-03 380990 + 271 381000 Sr-100 4.40400E-04 4.40420E-04 381000 + 272 381010 Sr-101 5.74610E-05 5.74610E-05 381010 + 273 381020 Sr-102 7.42650E-06 7.42650E-06 381020 + 274 381030 Sr-103 1.56150E-09 1.56150E-09 381030 + 275 390900 Y-90 5.87530E-09 2.65920E-02 39090.82c + 276 390901 Y-90m 9.82570E-09 9.82570E-09 390901 + 277 390910 Y-91 1.83120E-06 3.39070E-02 39091.82c + 278 390911 Y-91m 9.09480E-06 1.99520E-02 390911 + 279 390920 Y-92 9.62540E-05 4.59620E-02 390920 + 280 390930 Y-93 9.99270E-05 5.08470E-02 390930 + 281 390931 Y-93m 7.50510E-04 1.32620E-02 390931 + 282 390940 Y-94 2.77570E-03 5.77550E-02 390940 + 283 390950 Y-95 1.06670E-02 5.72100E-02 390950 + 284 390960 Y-96 6.64060E-03 4.68020E-02 390960 + 285 390961 Y-96m 1.39310E-02 1.39360E-02 390961 + 286 390970 Y-97 5.65920E-03 2.24020E-02 390970 + 287 390971 Y-97m 2.09180E-02 2.95600E-02 390971 + 288 390972 Y-97m 7.18880E-03 7.18880E-03 390972 + 289 390980 Y-98 5.42930E-03 1.50910E-02 390980 + 290 390981 Y-98m 2.63210E-02 2.63210E-02 390981 + 291 390990 Y-99 2.35830E-02 2.56300E-02 390990 + 292 391000 Y-100 4.87850E-03 5.31620E-03 391000 + 293 391001 Y-100m 4.87850E-03 4.87920E-03 391001 + 294 391010 Y-101 4.73480E-03 4.79130E-03 391010 + 295 391020 Y-102 4.81170E-04 4.84680E-04 391020 + 296 391021 Y-102m 4.81170E-04 4.84680E-04 391021 + 297 391030 Y-103 1.84200E-04 1.84200E-04 391030 + 298 391040 Y-104 1.29610E-05 1.29610E-05 391040 + 299 391050 Y-105 1.44480E-08 1.44480E-08 391050 + 300 400920 Zr-92 1.10600E-06 4.59630E-02 40092.82c + 301 400930 Zr-93 1.49350E-05 5.08610E-02 40093.82c + 302 400940 Zr-94 1.27050E-04 5.78820E-02 40094.82c + 303 400950 Zr-95 7.48280E-04 5.79590E-02 40095.82c + 304 400960 Zr-96 4.43640E-03 6.51990E-02 40096.82c + 305 400970 Zr-97 1.09540E-02 6.50700E-02 400970 + 306 400980 Zr-98 3.17990E-02 7.27000E-02 400980 + 307 400990 Zr-99 3.70270E-02 6.22700E-02 400990 + 308 401000 Zr-100 4.22310E-02 5.23780E-02 401000 + 309 401010 Zr-101 3.13270E-02 3.61660E-02 401010 + 310 401020 Zr-102 2.05850E-02 2.15220E-02 401020 + 311 401030 Zr-103 6.39640E-03 6.56700E-03 401030 + 312 401040 Zr-104 1.93460E-03 1.94640E-03 401040 + 313 401050 Zr-105 2.92910E-04 2.92920E-04 401050 + 314 401060 Zr-106 4.75620E-05 4.75620E-05 401060 + 315 401070 Zr-107 5.89770E-06 5.89770E-06 401070 + 316 401080 Zr-108 5.00820E-10 5.00820E-10 401080 + 317 410950 Nb-95 3.28040E-06 5.79270E-02 41095.82c + 318 410951 Nb-95m 6.60500E-07 6.26820E-04 410951 + 319 410960 Nb-96 2.23350E-05 2.23350E-05 410960 + 320 410970 Nb-97 1.72300E-04 6.52770E-02 410970 + 321 410971 Nb-97m 3.46910E-05 6.18820E-02 410971 + 322 410980 Nb-98 2.35290E-04 7.29350E-02 410980 + 323 410981 Nb-98m 8.19810E-04 8.19810E-04 410981 + 324 410990 Nb-99 3.83340E-03 4.36620E-02 410990 + 325 410991 Nb-99m 7.71850E-04 2.36870E-02 410991 + 326 411000 Nb-100 1.73190E-03 5.41090E-02 411000 + 327 411001 Nb-100m 8.39610E-03 8.39610E-03 411001 + 328 411010 Nb-101 2.83130E-02 6.44790E-02 411010 + 329 411020 Nb-102 1.55300E-02 3.70520E-02 411020 + 330 411021 Nb-102m 1.55300E-02 1.55300E-02 411021 + 331 411030 Nb-103 2.95270E-02 3.60940E-02 411030 + 332 411040 Nb-104 7.79750E-03 9.74800E-03 411040 + 333 411041 Nb-104m 7.79750E-03 7.79750E-03 411041 + 334 411050 Nb-105 8.33570E-03 8.62520E-03 411050 + 335 411060 Nb-106 2.17370E-03 2.22080E-03 411060 + 336 411070 Nb-107 4.83010E-04 4.88690E-04 411070 + 337 411080 Nb-108 6.24140E-05 6.24140E-05 411080 + 338 411090 Nb-109 6.80610E-06 6.80610E-06 411090 + 339 411100 Nb-110 6.28910E-10 6.28910E-10 411100 + 340 420970 Mo-97 2.04640E-06 6.52790E-02 42097.82c + 341 420980 Mo-98 3.49650E-05 7.37900E-02 42098.82c + 342 420990 Mo-99 1.56560E-04 6.70320E-02 42099.82c + 343 421000 Mo-100 9.52730E-04 6.34580E-02 42100.82c + 344 421010 Mo-101 3.55990E-03 6.80390E-02 421010 + 345 421020 Mo-102 1.18760E-02 6.44580E-02 421020 + 346 421030 Mo-103 1.73360E-02 5.34400E-02 421030 + 347 421040 Mo-104 2.54010E-02 4.30830E-02 421040 + 348 421050 Mo-105 2.03200E-02 2.88990E-02 421050 + 349 421060 Mo-106 1.47430E-02 1.68930E-02 421060 + 350 421070 Mo-107 4.80640E-03 5.26960E-03 421070 + 351 421080 Mo-108 1.49230E-03 1.55170E-03 421080 + 352 421090 Mo-109 2.45510E-04 2.51450E-04 421090 + 353 421100 Mo-110 4.41300E-05 4.41300E-05 421100 + 354 421110 Mo-111 1.49210E-05 1.49210E-05 421110 + 355 421120 Mo-112 4.23020E-06 4.23020E-06 421120 + 356 421130 Mo-113 1.04360E-11 1.04360E-11 421130 + 357 431000 Tc-100 9.06060E-07 9.06060E-07 431000 + 358 431010 Tc-101 3.76130E-05 6.80760E-02 431010 + 359 431020 Tc-102 1.01690E-04 6.45590E-02 431020 + 360 431021 Tc-102m 1.01690E-04 1.01690E-04 431021 + 361 431030 Tc-103 8.63310E-04 5.43030E-02 431030 + 362 431040 Tc-104 2.23920E-03 4.53230E-02 431040 + 363 431050 Tc-105 5.49090E-03 3.43900E-02 431050 + 364 431060 Tc-106 6.60170E-03 2.34950E-02 431060 + 365 431070 Tc-107 6.96980E-03 1.22390E-02 431070 + 366 431080 Tc-108 3.75470E-03 5.30770E-03 431080 + 367 431090 Tc-109 1.83470E-03 2.08480E-03 431090 + 368 431100 Tc-110 5.07290E-04 5.51570E-04 431100 + 369 431110 Tc-111 1.39210E-04 1.54060E-04 431110 + 370 431120 Tc-112 2.81990E-05 3.23410E-05 431120 + 371 431130 Tc-113 4.91890E-06 4.91890E-06 431130 + 372 431140 Tc-114 1.84090E-09 1.84090E-09 431140 + 373 431150 Tc-115 6.09900E-11 6.09900E-11 431150 + 374 441020 Ru-102 6.36550E-06 6.46670E-02 44102.82c + 375 441030 Ru-103 2.05540E-06 5.43110E-02 44103.82c + 376 441031 Ru-103m 5.75090E-06 5.75090E-06 441031 + 377 441040 Ru-104 9.24740E-05 4.54150E-02 44104.82c + 378 441050 Ru-105 2.87750E-04 3.46770E-02 44105.82c + 379 441060 Ru-106 9.33990E-04 2.44290E-02 44106.82c + 380 441070 Ru-107 1.41170E-03 1.36510E-02 441070 + 381 441080 Ru-108 1.70540E-03 7.01480E-03 441080 + 382 441090 Ru-109 1.16000E-03 3.24340E-03 441090 + 383 441100 Ru-110 6.91060E-04 1.24240E-03 441100 + 384 441110 Ru-111 2.52090E-04 4.06640E-04 441110 + 385 441120 Ru-112 9.30550E-05 1.25270E-04 441120 + 386 441130 Ru-113 1.40540E-05 2.56460E-05 441130 + 387 441131 Ru-113m 1.40540E-05 1.40540E-05 441131 + 388 441140 Ru-114 1.19210E-05 1.19230E-05 441140 + 389 441150 Ru-115 3.50090E-06 3.50090E-06 441150 + 390 441160 Ru-116 6.92020E-07 6.92020E-07 441160 + 391 441170 Ru-117 4.17760E-10 4.17760E-10 441170 + 392 441180 Ru-118 1.10260E-11 1.10260E-11 441180 + 393 441200 Ru-120 5.30720E-09 5.30720E-09 441200 + 394 451050 Rh-105 1.67620E-06 3.46790E-02 45105.82c + 395 451051 Rh-105m 2.23180E-07 9.84430E-03 451051 + 396 451060 Rh-106 3.50450E-06 2.44320E-02 451060 + 397 451061 Rh-106m 9.55250E-06 9.55250E-06 451061 + 398 451070 Rh-107 3.28510E-05 1.36840E-02 451070 + 399 451080 Rh-108 1.69720E-05 7.03180E-03 451080 + 400 451081 Rh-108m 5.91350E-05 5.91350E-05 451081 + 401 451090 Rh-109 1.31520E-04 3.37490E-03 451090 + 402 451100 Rh-110 1.28470E-04 1.37090E-03 451100 + 403 451101 Rh-110m 3.02430E-06 3.02430E-06 451101 + 404 451110 Rh-111 1.35620E-04 5.42260E-04 451110 + 405 451120 Rh-112 3.63030E-05 1.61570E-04 451120 + 406 451121 Rh-112m 3.63030E-05 3.63030E-05 451121 + 407 451130 Rh-113 7.51870E-05 1.07860E-04 451130 + 408 451140 Rh-114 2.17380E-05 3.36690E-05 451140 + 409 451141 Rh-114m 2.17380E-05 2.17380E-05 451141 + 410 451150 Rh-115 3.43090E-05 3.78090E-05 451150 + 411 451160 Rh-116 2.97200E-06 3.65650E-06 451160 + 412 451161 Rh-116m 8.10100E-06 8.10100E-06 451161 + 413 451170 Rh-117 7.70920E-06 7.70960E-06 451170 + 414 451180 Rh-118 1.38900E-06 1.38900E-06 451180 + 415 451190 Rh-119 7.17650E-07 7.17650E-07 451190 + 416 451200 Rh-120 2.03980E-06 2.04510E-06 451200 + 417 451210 Rh-121 2.57060E-07 2.57060E-07 451210 + 418 451220 Rh-122 1.80500E-08 1.80500E-08 451220 + 419 461070 Pd-107 1.25870E-10 1.36840E-02 46107.82c + 420 461071 Pd-107m 2.76660E-10 2.76660E-10 461071 + 421 461080 Pd-108 1.52750E-08 7.09090E-03 46108.82c + 422 461090 Pd-109 9.45790E-07 3.37790E-03 461090 + 423 461091 Pd-109m 2.07880E-06 1.68950E-03 461091 + 424 461100 Pd-110 7.22640E-06 1.38110E-03 46110.82c + 425 461110 Pd-111 3.10920E-06 5.49770E-04 461110 + 426 461111 Pd-111m 6.83380E-06 9.00290E-06 461111 + 427 461120 Pd-112 1.40990E-05 2.11970E-04 461120 + 428 461130 Pd-113 2.77520E-06 1.18400E-04 461130 + 429 461131 Pd-113m 7.76480E-06 7.76480E-06 461131 + 430 461140 Pd-114 2.38410E-05 7.92490E-05 461140 + 431 461150 Pd-115 1.16040E-05 4.64030E-05 461150 + 432 461151 Pd-115m 2.55050E-05 3.09950E-05 461151 + 433 461160 Pd-116 5.74380E-05 6.91950E-05 461160 + 434 461170 Pd-117 1.29300E-05 4.91000E-05 461170 + 435 461171 Pd-117m 2.84200E-05 2.84200E-05 461171 + 436 461180 Pd-118 2.70870E-05 2.84350E-05 461180 + 437 461190 Pd-119 9.32950E-06 1.01680E-05 461190 + 438 461200 Pd-120 7.01560E-06 8.97430E-06 461200 + 439 461210 Pd-121 1.43410E-06 1.65630E-06 461210 + 440 461220 Pd-122 6.47870E-06 6.49680E-06 461220 + 441 461230 Pd-123 9.49200E-07 9.49200E-07 461230 + 442 461240 Pd-124 2.00110E-07 2.00110E-07 461240 + 443 471100 Ag-110 6.56450E-11 6.80790E-11 471100 + 444 471101 Ag-110m 1.78930E-10 1.78930E-10 47510.82c + 445 471110 Ag-111 6.52640E-10 5.49470E-04 47111.82c + 446 471111 Ag-111m 4.90180E-09 5.47630E-04 471111 + 447 471120 Ag-112 4.42990E-08 2.12010E-04 471120 + 448 471130 Ag-113 8.25670E-08 7.80640E-05 471130 + 449 471131 Ag-113m 6.20130E-07 1.14000E-04 471131 + 450 471140 Ag-114 3.59730E-07 8.13520E-05 471140 + 451 471141 Ag-114m 1.74400E-06 1.74400E-06 471141 + 452 471150 Ag-115 9.87210E-07 4.50380E-05 471150 + 453 471151 Ag-115m 7.41460E-06 4.84590E-05 471151 + 454 471160 Ag-116 3.34350E-06 7.30860E-05 471160 + 455 471161 Ag-116m 9.11350E-06 9.11350E-06 471161 + 456 471170 Ag-117 3.62320E-06 3.12790E-05 471170 + 457 471171 Ag-117m 2.72130E-05 5.17630E-05 471171 + 458 471180 Ag-118 6.76940E-06 4.62620E-05 471180 + 459 471181 Ag-118m 3.28180E-05 3.68830E-05 471181 + 460 471190 Ag-119 6.07130E-06 1.11560E-05 471190 + 461 471191 Ag-119m 4.56000E-05 5.06840E-05 471191 + 462 471200 Ag-120 1.20760E-05 2.57010E-05 471200 + 463 471201 Ag-120m 2.01960E-05 2.46830E-05 471201 + 464 471210 Ag-121 2.29450E-05 2.45970E-05 471210 + 465 471220 Ag-122 4.50860E-06 1.10050E-05 471220 + 466 471221 Ag-122m 4.86090E-06 4.86090E-06 471221 + 467 471230 Ag-123 1.21460E-05 1.30950E-05 471230 + 468 471240 Ag-124 4.54030E-06 7.18790E-06 471240 + 469 471241 Ag-124m 4.89500E-06 4.89500E-06 471241 + 470 471250 Ag-125 1.17140E-05 1.17140E-05 471250 + 471 471260 Ag-126 4.49510E-06 4.49510E-06 471260 + 472 471270 Ag-127 3.13060E-06 3.13060E-06 471270 + 473 471280 Ag-128 4.43830E-08 4.43830E-08 471280 + 474 471290 Ag-129 2.22060E-09 2.22060E-09 471290 + 475 481120 Cd-112 7.45320E-12 2.12010E-04 48112.82c + 476 481130 Cd-113 3.34300E-11 1.17760E-04 48113.82c + 477 481131 Cd-113m 1.26600E-10 1.34980E-06 481131 + 478 481140 Cd-114 4.53430E-09 8.13570E-05 48114.82c + 479 481150 Cd-115 1.53460E-08 7.96260E-05 481150 + 480 481151 Cd-115m 5.81160E-08 3.76790E-06 48515.82c + 481 481160 Cd-116 9.34540E-07 8.25870E-05 48116.82c + 482 481170 Cd-117 1.46400E-07 6.27350E-05 481170 + 483 481171 Cd-117m 5.54420E-07 1.79020E-05 481171 + 484 481180 Cd-118 1.04170E-05 7.84390E-05 481180 + 485 481190 Cd-119 2.64540E-06 5.89070E-05 481190 + 486 481191 Cd-119m 7.40160E-06 1.29800E-05 481191 + 487 481200 Cd-120 3.57790E-05 7.70290E-05 481200 + 488 481210 Cd-121 9.06200E-06 3.10890E-05 481210 + 489 481211 Cd-121m 2.53550E-05 2.79250E-05 481211 + 490 481220 Cd-122 4.88550E-05 6.47210E-05 481220 + 491 481230 Cd-123 9.59410E-06 2.03120E-05 481230 + 492 481231 Cd-123m 2.68440E-05 2.92290E-05 481231 + 493 481240 Cd-124 6.67740E-05 7.64020E-05 481240 + 494 481250 Cd-125 2.54480E-05 3.13050E-05 481250 + 495 481251 Cd-125m 7.12010E-05 7.70580E-05 481251 + 496 481260 Cd-126 1.75350E-04 1.79850E-04 481260 + 497 481270 Cd-127 1.44040E-04 1.47170E-04 481270 + 498 481280 Cd-128 8.38190E-05 8.38630E-05 481280 + 499 481290 Cd-129 8.12490E-06 8.12600E-06 481290 + 500 481291 Cd-129m 2.27330E-05 2.27340E-05 481291 + 501 481300 Cd-130 3.73880E-06 3.73880E-06 481300 + 502 481310 Cd-131 3.76710E-08 3.76710E-08 481310 + 503 481320 Cd-132 1.68070E-09 1.68070E-09 481320 + 504 491150 In-115 1.26920E-11 7.94120E-05 49115.82c + 505 491151 In-115m 2.55560E-12 7.96260E-05 491151 + 506 491160 In-116 1.18800E-10 1.18800E-10 491160 + 507 491161 In-116m 1.91840E-10 4.13940E-10 491161 + 508 491162 In-116m 2.22100E-10 2.22100E-10 491162 + 509 491170 In-117 1.37500E-08 5.00950E-05 491170 + 510 491171 In-117m 2.76860E-09 5.77670E-05 491171 + 511 491180 In-118 4.34070E-08 7.84830E-05 491180 + 512 491181 In-118m 7.00940E-08 1.50110E-07 491181 + 513 491182 In-118m 8.11500E-08 8.11500E-08 491182 + 514 491190 In-119 1.48130E-06 2.31560E-05 491190 + 515 491191 In-119m 2.98240E-07 5.35070E-05 491191 + 516 491200 In-120 1.16910E-06 7.81980E-05 491200 + 517 491201 In-120m 1.16910E-06 1.16910E-06 491201 + 518 491202 In-120m 1.16910E-06 1.16910E-06 491202 + 519 491210 In-121 5.37160E-06 4.40280E-05 491210 + 520 491211 In-121m 1.08160E-06 2.17000E-05 491211 + 521 491220 In-122 7.51320E-06 7.22340E-05 491220 + 522 491221 In-122m 6.28240E-06 6.28240E-06 491221 + 523 491222 In-122m 6.28240E-06 6.28240E-06 491222 + 524 491230 In-123 2.43840E-05 5.95470E-05 491230 + 525 491231 In-123m 4.90950E-06 1.92860E-05 491231 + 526 491240 In-124 3.03830E-05 1.06790E-04 491240 + 527 491241 In-124m 3.27580E-05 3.27580E-05 491241 + 528 491250 In-125 1.07870E-04 1.99910E-04 491250 + 529 491251 In-125m 2.17190E-05 3.80400E-05 491251 + 530 491260 In-126 1.97950E-04 3.77790E-04 491260 + 531 491261 In-126m 2.13410E-04 2.13410E-04 491261 + 532 491270 In-127 9.82150E-04 9.82150E-04 491270 + 533 491271 In-127m 1.97750E-04 3.44920E-04 491271 + 534 491280 In-128 5.56250E-04 8.57920E-04 491280 + 535 491281 In-128m 2.17800E-04 3.01670E-04 491281 + 536 491282 In-128m 8.34540E-04 8.34540E-04 491282 + 537 491290 In-129 1.44950E-03 1.47230E-03 491290 + 538 491291 In-129m 2.91860E-04 3.00050E-04 491291 + 539 491300 In-130 2.04350E-04 2.07960E-04 491300 + 540 491301 In-130m 2.97550E-04 2.97550E-04 491301 + 541 491302 In-130m 4.14470E-04 4.14470E-04 491302 + 542 491310 In-131 1.00560E-04 1.01620E-04 491310 + 543 491311 In-131m 1.00560E-04 1.00560E-04 491311 + 544 491312 In-131m 1.00560E-04 1.00560E-04 491312 + 545 491320 In-132 4.14470E-05 4.14480E-05 491320 + 546 491330 In-133 2.29650E-06 2.75890E-06 491330 + 547 491331 In-133m 4.62390E-07 4.62390E-07 491331 + 548 491340 In-134 2.47240E-08 2.47240E-08 491340 + 549 501170 Sn-117 4.90290E-13 8.06530E-05 50117.82c + 550 501171 Sn-117m 1.85670E-12 1.70680E-07 501171 + 551 501180 Sn-118 9.64790E-11 7.86340E-05 50118.82c + 552 501190 Sn-119 5.51830E-10 7.36690E-05 50119.82c + 553 501191 Sn-119m 2.08980E-09 2.09210E-05 501191 + 554 501210 Sn-121 1.00060E-12 6.43500E-05 501210 + 555 501211 Sn-121m 2.79960E-12 4.98760E-06 501211 + 556 501220 Sn-122 3.35540E-10 8.48000E-05 50122.82c + 557 501230 Sn-123 3.68450E-06 8.22440E-06 50123.82c + 558 501231 Sn-123m 1.31680E-06 7.56100E-05 501231 + 559 501240 Sn-124 1.37900E-05 1.53330E-04 50124.82c + 560 501250 Sn-125 2.15730E-05 5.53420E-05 50125.82c + 561 501251 Sn-125m 7.71020E-06 2.11890E-04 501251 + 562 501260 Sn-126 1.66300E-04 7.59880E-04 50126.82c + 563 501270 Sn-127 5.63330E-04 9.46140E-04 501270 + 564 501271 Sn-127m 2.01330E-04 1.14320E-03 501271 + 565 501280 Sn-128 7.70090E-04 4.56170E-03 501280 + 566 501281 Sn-128m 2.09910E-03 2.93360E-03 501281 + 567 501290 Sn-129 1.45230E-03 3.06800E-03 501290 + 568 501291 Sn-129m 4.06330E-03 4.22010E-03 501291 + 569 501300 Sn-130 2.14180E-03 2.70510E-03 501300 + 570 501301 Sn-130m 5.83810E-03 6.19680E-03 501301 + 571 501310 Sn-131 1.64990E-03 1.84470E-03 501310 + 572 501311 Sn-131m 4.61650E-03 4.72140E-03 501311 + 573 501320 Sn-132 5.14870E-03 5.19250E-03 501320 + 574 501330 Sn-133 8.24690E-04 8.25120E-04 501330 + 575 501340 Sn-134 1.46710E-04 1.46720E-04 501340 + 576 501350 Sn-135 1.86740E-06 1.86740E-06 501350 + 577 501360 Sn-136 5.93690E-08 5.93690E-08 501360 + 578 501370 Sn-137 2.61260E-09 2.61260E-09 501370 + 579 511240 Sb-124 2.12500E-11 5.46910E-11 51124.82c + 580 511241 Sb-124m 1.71420E-11 4.45870E-11 511241 + 581 511242 Sb-124m 2.74450E-11 2.74450E-11 511242 + 582 511250 Sb-125 2.92820E-06 2.70160E-04 51125.82c + 583 511260 Sb-126 4.99570E-06 5.97410E-06 51126.82c + 584 511261 Sb-126m 3.12040E-06 6.98850E-06 511261 + 585 511262 Sb-126m 3.86810E-06 3.86810E-06 511262 + 586 511270 Sb-127 6.48700E-05 2.15420E-03 511270 + 587 511280 Sb-128 1.16870E-04 4.68440E-03 511280 + 588 511281 Sb-128m 1.63470E-04 1.63470E-04 511281 + 589 511290 Sb-129 1.06350E-03 6.67600E-03 511290 + 590 511291 Sb-129m 7.87020E-04 2.89700E-03 511291 + 591 511300 Sb-130 2.58810E-03 8.39150E-03 511300 + 592 511301 Sb-130m 2.58810E-03 5.68650E-03 511301 + 593 511310 Sb-131 1.28990E-02 1.94650E-02 511310 + 594 511320 Sb-132 1.44960E-02 1.96890E-02 511320 + 595 511321 Sb-132m 1.28350E-02 1.28350E-02 511321 + 596 511330 Sb-133 3.49040E-02 3.57540E-02 511330 + 597 511340 Sb-134 4.64140E-03 4.76340E-03 511340 + 598 511341 Sb-134m 1.26520E-02 1.26520E-02 511341 + 599 511350 Sb-135 8.11790E-04 8.13280E-04 511350 + 600 511360 Sb-136 2.37710E-04 2.37750E-04 511360 + 601 511370 Sb-137 1.17450E-04 1.17450E-04 511370 + 602 511380 Sb-138 7.12400E-06 7.12400E-06 511380 + 603 511390 Sb-139 1.49830E-08 1.49830E-08 511390 + 604 521260 Te-126 5.40500E-11 1.19840E-05 52126.82c + 605 521270 Te-127 2.06060E-07 2.14650E-03 521270 + 606 521271 Te-127m 5.76550E-07 3.55580E-04 52527.82c + 607 521280 Te-128 3.91560E-06 4.84590E-03 52128.82c + 608 521290 Te-129 1.06180E-05 7.86810E-03 521290 + 609 521291 Te-129m 2.97070E-05 3.54240E-03 52529.82c + 610 521300 Te-130 4.11170E-04 1.44890E-02 52130.82c + 611 521310 Te-131 5.17670E-04 1.90560E-02 521310 + 612 521311 Te-131m 1.44840E-03 3.00680E-03 521311 + 613 521320 Te-132 1.21500E-02 4.46730E-02 52132.82c + 614 521330 Te-133 9.72310E-03 4.51450E-02 521330 + 615 521331 Te-133m 2.72050E-02 3.33920E-02 521331 + 616 521340 Te-134 7.33400E-02 9.08720E-02 521340 + 617 521350 Te-135 9.29900E-05 8.17340E-04 521350 + 618 521360 Te-136 1.84630E-03 2.10220E-03 521360 + 619 521370 Te-137 3.83700E-03 3.89690E-03 521370 + 620 521380 Te-138 8.63290E-04 8.70410E-04 521380 + 621 521390 Te-139 8.48030E-05 8.48180E-05 521390 + 622 521400 Te-140 1.01960E-05 1.01960E-05 521400 + 623 521410 Te-141 3.33750E-06 3.33750E-06 521410 + 624 521420 Te-142 2.14650E-09 2.14650E-09 521420 + 625 531290 I-129 7.91090E-07 9.17960E-03 53129.82c + 626 531300 I-130 2.18820E-06 2.86250E-06 53130.82c + 627 531301 I-130m 8.02780E-07 8.02780E-07 531301 + 628 531310 I-131 3.50140E-05 2.14660E-02 53131.82c + 629 531320 I-132 2.07220E-04 4.50390E-02 531320 + 630 531321 I-132m 1.83470E-04 1.83470E-04 531321 + 631 531330 I-133 2.03150E-03 7.62290E-02 531330 + 632 531331 I-133m 1.50340E-03 1.50340E-03 531331 + 633 531340 I-134 1.27620E-02 1.14670E-01 531340 + 634 531341 I-134m 1.13000E-02 1.13000E-02 531341 + 635 531350 I-135 2.79680E-02 2.87850E-02 53135.82c + 636 531360 I-136 7.70520E-03 9.86570E-03 531360 + 637 531361 I-136m 2.10030E-02 2.10610E-02 531361 + 638 531370 I-137 5.93540E-02 6.31890E-02 531370 + 639 531380 I-138 2.47970E-02 2.56130E-02 531380 + 640 531390 I-139 1.38310E-02 1.39160E-02 531390 + 641 531400 I-140 3.93660E-03 3.94680E-03 531400 + 642 531410 I-141 1.16470E-03 1.16800E-03 531410 + 643 531420 I-142 1.20170E-04 1.20170E-04 531420 + 644 531430 I-143 2.07680E-05 2.07680E-05 531430 + 645 531440 I-144 1.87300E-06 1.87300E-06 531440 + 646 541310 Xe-131 3.42030E-10 2.14660E-02 54131.82c + 647 541311 Xe-131m 9.56970E-10 2.33160E-04 541311 + 648 541320 Xe-132 4.91680E-07 4.50650E-02 54132.82c + 649 541321 Xe-132m 6.58720E-07 6.58720E-07 541321 + 650 541330 Xe-133 6.17670E-06 7.62520E-02 54133.82c + 651 541331 Xe-133m 1.72820E-05 2.18700E-03 541331 + 652 541340 Xe-134 8.76140E-05 1.15260E-01 54134.82c + 653 541341 Xe-134m 2.38820E-04 4.98710E-04 541341 + 654 541350 Xe-135 1.19060E-04 2.92070E-02 54135.82c + 655 541351 Xe-135m 3.33110E-04 5.08520E-03 541351 + 656 541360 Xe-136 4.96710E-03 4.00010E-02 54136.82c + 657 541370 Xe-137 2.59220E-02 8.63610E-02 541370 + 658 541380 Xe-138 4.12820E-02 6.69010E-02 541380 + 659 541390 Xe-139 2.65800E-02 3.94990E-02 541390 + 660 541400 Xe-140 2.25350E-02 2.63600E-02 541400 + 661 541410 Xe-141 1.19960E-02 1.29490E-02 541410 + 662 541420 Xe-142 4.62910E-03 4.72750E-03 541420 + 663 541430 Xe-143 8.57490E-04 8.70700E-04 541430 + 664 541440 Xe-144 1.34550E-04 1.35670E-04 541440 + 665 541450 Xe-145 1.54380E-05 1.54380E-05 541450 + 666 541460 Xe-146 6.79340E-08 6.79340E-08 541460 + 667 541470 Xe-147 7.92450E-10 7.92450E-10 541470 + 668 551340 Cs-134 2.78670E-08 5.25400E-08 55134.82c + 669 551341 Cs-134m 2.46730E-08 2.46730E-08 551341 + 670 551350 Cs-135 1.07310E-06 2.92390E-02 55135.82c + 671 551351 Cs-135m 7.94120E-07 7.94120E-07 551351 + 672 551360 Cs-136 2.39960E-05 3.25750E-05 55136.82c + 673 551361 Cs-136m 1.71570E-05 1.71570E-05 551361 + 674 551370 Cs-137 2.00150E-03 8.83630E-02 55137.82c + 675 551380 Cs-138 2.66970E-03 7.31870E-02 551380 + 676 551381 Cs-138m 4.46480E-03 4.46480E-03 551381 + 677 551390 Cs-139 2.02100E-02 5.97090E-02 551390 + 678 551400 Cs-140 2.62530E-02 5.26190E-02 551400 + 679 551410 Cs-141 4.86500E-02 6.16100E-02 551410 + 680 551420 Cs-142 3.82530E-02 4.29720E-02 551420 + 681 551430 Cs-143 2.12600E-02 2.21260E-02 551430 + 682 551440 Cs-144 5.07000E-03 7.73720E-03 551440 + 683 551441 Cs-144m 5.07000E-03 5.07040E-03 551441 + 684 551450 Cs-145 3.71740E-03 3.73210E-03 551450 + 685 551460 Cs-146 8.51080E-04 8.51140E-04 551460 + 686 551470 Cs-147 1.85840E-04 1.85840E-04 551470 + 687 551480 Cs-148 1.13050E-05 1.13050E-05 551480 + 688 551490 Cs-149 3.39380E-09 3.39380E-09 551490 + 689 561360 Ba-136 5.40150E-10 4.11550E-05 56136.82c + 690 561361 Ba-136m 1.47230E-09 1.47230E-09 561361 + 691 561370 Ba-137 3.13190E-07 8.83640E-02 56137.82c + 692 561371 Ba-137m 8.76310E-07 8.34150E-02 561371 + 693 561380 Ba-138 9.15380E-05 7.41270E-02 56138.82c + 694 561390 Ba-139 4.21990E-04 6.01310E-02 561390 + 695 561400 Ba-140 2.04850E-03 5.46670E-02 56140.82c + 696 561410 Ba-141 4.69260E-03 6.63030E-02 561410 + 697 561420 Ba-142 1.61520E-02 5.94870E-02 561420 + 698 561430 Ba-143 1.85670E-02 4.05780E-02 561430 + 699 561440 Ba-144 2.26450E-02 3.32030E-02 561440 + 700 561450 Ba-145 1.34570E-02 1.67760E-02 561450 + 701 561460 Ba-146 7.85620E-03 8.63940E-03 561460 + 702 561470 Ba-147 2.82350E-03 2.95920E-03 561470 + 703 561480 Ba-148 5.45930E-04 5.54400E-04 561480 + 704 561490 Ba-149 7.78370E-05 7.78400E-05 561490 + 705 561500 Ba-150 9.28170E-06 9.28170E-06 561500 + 706 561510 Ba-151 1.33530E-08 1.33530E-08 561510 + 707 561520 Ba-152 1.58910E-10 1.58910E-10 561520 + 708 571390 La-139 2.09830E-06 6.01330E-02 57139.82c + 709 571400 La-140 2.65300E-05 5.46940E-02 57140.82c + 710 571410 La-141 1.91820E-04 6.64940E-02 571410 + 711 571420 La-142 6.05380E-04 6.00930E-02 571420 + 712 571430 La-143 3.11350E-03 4.36910E-02 571430 + 713 571440 La-144 7.88980E-03 4.10930E-02 571440 + 714 571450 La-145 1.79640E-02 3.47400E-02 571450 + 715 571460 La-146 6.49670E-03 1.51360E-02 571460 + 716 571461 La-146m 1.36290E-02 1.36290E-02 571461 + 717 571470 La-147 1.98000E-02 2.27610E-02 571470 + 718 571480 La-148 1.00900E-02 1.06420E-02 571480 + 719 571490 La-149 4.69100E-03 4.76850E-03 571490 + 720 571500 La-150 1.39640E-03 1.40570E-03 571500 + 721 571510 La-151 3.66640E-04 3.66650E-04 571510 + 722 571520 La-152 3.61580E-05 3.61580E-05 571520 + 723 571530 La-153 5.78000E-06 5.78000E-06 571530 + 724 571540 La-154 4.16690E-10 4.16690E-10 571540 + 725 581410 Ce-141 3.83390E-09 6.64940E-02 58141.82c + 726 581420 Ce-142 4.37500E-06 6.00970E-02 58142.82c + 727 581430 Ce-143 1.89770E-05 4.37100E-02 58143.82c + 728 581440 Ce-144 1.38040E-04 4.12310E-02 58144.82c + 729 581450 Ce-145 5.24150E-04 3.52640E-02 581450 + 730 581460 Ce-146 2.46930E-03 3.12350E-02 581460 + 731 581470 Ce-147 4.02460E-03 2.67860E-02 581470 + 732 581480 Ce-148 6.50220E-03 1.72120E-02 581480 + 733 581490 Ce-149 5.82750E-03 1.05670E-02 581490 + 734 581500 Ce-150 4.58360E-03 5.95130E-03 581500 + 735 581510 Ce-151 2.01290E-03 2.38170E-03 581510 + 736 581520 Ce-152 5.86830E-04 6.20800E-04 581520 + 737 581530 Ce-153 9.79060E-05 1.03690E-04 581530 + 738 581540 Ce-154 1.86220E-05 1.86220E-05 581540 + 739 581550 Ce-155 2.97860E-06 2.97860E-06 581550 + 740 581560 Ce-156 1.36140E-09 1.36140E-09 581560 + 741 581570 Ce-157 1.09550E-11 1.09550E-11 581570 + 742 591440 Pr-144 1.47550E-09 4.12310E-02 591440 + 743 591441 Pr-144m 1.50110E-08 5.68980E-04 591441 + 744 591450 Pr-145 1.06140E-05 3.52750E-02 591450 + 745 591460 Pr-146 4.33710E-05 3.12780E-02 591460 + 746 591470 Pr-147 2.75470E-04 2.70610E-02 591470 + 747 591480 Pr-148 1.21920E-04 1.73330E-02 591480 + 748 591481 Pr-148m 5.91080E-04 5.91080E-04 591481 + 749 591490 Pr-149 1.98860E-03 1.25560E-02 591490 + 750 591500 Pr-150 3.13470E-03 9.08600E-03 591500 + 751 591510 Pr-151 4.44060E-03 6.82230E-03 591510 + 752 591520 Pr-152 3.13410E-03 3.75550E-03 591520 + 753 591530 Pr-153 1.50690E-03 1.61010E-03 591530 + 754 591540 Pr-154 7.43880E-04 7.62380E-04 591540 + 755 591550 Pr-155 1.91680E-04 1.94660E-04 591550 + 756 591560 Pr-156 2.41610E-05 2.41620E-05 591560 + 757 591570 Pr-157 2.24580E-06 2.24580E-06 591570 + 758 591580 Pr-158 2.51020E-09 2.51020E-09 591580 + 759 591590 Pr-159 2.89160E-11 2.89160E-11 591590 + 760 601460 Nd-146 2.19140E-09 3.12780E-02 60146.82c + 761 601470 Nd-147 1.03510E-06 2.70620E-02 60147.82c + 762 601480 Nd-148 4.34840E-06 1.79290E-02 60148.82c + 763 601490 Nd-149 2.53520E-05 1.25810E-02 601490 + 764 601500 Nd-150 1.23050E-04 9.20910E-03 60150.82c + 765 601510 Nd-151 2.98320E-04 7.12070E-03 601510 + 766 601520 Nd-152 6.90620E-04 4.44620E-03 601520 + 767 601530 Nd-153 6.14310E-04 2.22440E-03 601530 + 768 601540 Nd-154 7.79050E-04 1.54140E-03 601540 + 769 601550 Nd-155 4.02110E-04 5.97420E-04 601550 + 770 601560 Nd-156 1.65850E-04 1.89500E-04 601560 + 771 601570 Nd-157 4.60430E-05 4.81450E-05 601570 + 772 601580 Nd-158 1.12370E-05 1.12390E-05 601580 + 773 601590 Nd-159 1.26670E-07 1.26700E-07 601590 + 774 601600 Nd-160 4.54990E-09 4.54990E-09 601600 + 775 601610 Nd-161 6.86550E-11 6.86550E-11 601610 + 776 611490 Pm-149 5.65640E-09 1.25810E-02 61149.82c + 777 611500 Pm-150 1.85630E-06 1.85630E-06 611500 + 778 611510 Pm-151 1.28050E-05 7.13350E-03 61151.82c + 779 611520 Pm-152 5.85060E-06 4.45200E-03 611520 + 780 611521 Pm-152m 1.23000E-05 1.23000E-05 611521 + 781 611522 Pm-152m 1.60670E-05 1.60670E-05 611522 + 782 611530 Pm-153 1.14660E-04 2.33900E-03 611530 + 783 611540 Pm-154 1.43600E-04 1.68500E-03 611540 + 784 611541 Pm-154m 1.43600E-04 1.43600E-04 611541 + 785 611550 Pm-155 3.83950E-04 9.81380E-04 611550 + 786 611560 Pm-156 3.77700E-04 5.67200E-04 611560 + 787 611570 Pm-157 2.70620E-04 3.18770E-04 611570 + 788 611580 Pm-158 1.35970E-04 1.47210E-04 611580 + 789 611590 Pm-159 4.26110E-05 4.27370E-05 611590 + 790 611600 Pm-160 9.90990E-06 9.91440E-06 611600 + 791 611610 Pm-161 1.56480E-07 1.56550E-07 611610 + 792 611620 Pm-162 4.69290E-09 4.69290E-09 611620 + 793 611630 Pm-163 6.28610E-11 6.28610E-11 611630 + 794 621510 Sm-151 4.23890E-10 7.13350E-03 62151.82c + 795 621520 Sm-152 1.70040E-08 4.48040E-03 62152.82c + 796 621530 Sm-153 2.17360E-07 2.33990E-03 62153.82c + 797 621531 Sm-153m 6.08160E-07 6.08160E-07 621531 + 798 621540 Sm-154 2.06770E-06 1.83070E-03 62154.82c + 799 621550 Sm-155 1.58820E-05 9.97260E-04 621550 + 800 621560 Sm-156 2.74520E-05 5.94650E-04 621560 + 801 621570 Sm-157 5.16480E-05 3.70410E-04 621570 + 802 621580 Sm-158 7.75260E-05 2.24740E-04 621580 + 803 621590 Sm-159 3.66900E-05 7.94460E-05 621590 + 804 621600 Sm-160 2.72520E-05 3.71400E-05 621600 + 805 621610 Sm-161 9.85440E-06 1.00110E-05 621610 + 806 621620 Sm-162 3.82090E-06 3.82560E-06 621620 + 807 621630 Sm-163 6.21210E-08 6.21840E-08 621630 + 808 621640 Sm-164 6.66910E-09 6.66910E-09 621640 + 809 621650 Sm-165 1.31660E-10 1.31660E-10 621650 + 810 631540 Eu-154 3.34180E-10 6.94480E-10 63154.82c + 811 631541 Eu-154m 3.60300E-10 3.60300E-10 631541 + 812 631550 Eu-155 9.92720E-07 9.98250E-04 63155.82c + 813 631560 Eu-156 1.09810E-06 5.95750E-04 63156.82c + 814 631570 Eu-157 5.61430E-06 3.76030E-04 63157.82c + 815 631580 Eu-158 1.79780E-05 2.42720E-04 631580 + 816 631590 Eu-159 2.60380E-05 1.05480E-04 631590 + 817 631600 Eu-160 1.85800E-05 5.57200E-05 631600 + 818 631610 Eu-161 2.46350E-05 3.46460E-05 631610 + 819 631620 Eu-162 1.14630E-05 1.52890E-05 631620 + 820 631630 Eu-163 2.47120E-06 2.53340E-06 631630 + 821 631640 Eu-164 1.13260E-06 1.13930E-06 631640 + 822 631650 Eu-165 6.83810E-08 6.85130E-08 631650 + 823 631660 Eu-166 3.81060E-09 3.81060E-09 631660 + 824 631670 Eu-167 1.59690E-10 1.59690E-10 631670 + 825 641560 Gd-156 4.18890E-11 5.95750E-04 64156.82c + 826 641570 Gd-157 1.15020E-09 3.76030E-04 64157.82c + 827 641580 Gd-158 2.80560E-08 2.42750E-04 64158.82c + 828 641590 Gd-159 1.74190E-07 1.05660E-04 641590 + 829 641600 Gd-160 2.47740E-06 5.81970E-05 64160.82c + 830 641610 Gd-161 1.23180E-06 3.58780E-05 641610 + 831 641620 Gd-162 2.54720E-06 1.78360E-05 641620 + 832 641630 Gd-163 2.47120E-06 5.00460E-06 641630 + 833 641640 Gd-164 3.39790E-06 4.53720E-06 641640 + 834 641650 Gd-165 1.02960E-06 1.09810E-06 641650 + 835 641660 Gd-166 3.14010E-07 3.17820E-07 641660 + 836 641670 Gd-167 3.66350E-08 3.67950E-08 641670 + 837 641680 Gd-168 3.68340E-09 3.68340E-09 641680 + 838 641690 Gd-169 1.55080E-10 1.55080E-10 641690 + 839 651590 Tb-159 4.81920E-11 1.05660E-04 65159.82c + 840 651600 Tb-160 9.24490E-10 9.24490E-10 65160.82c + 841 651610 Tb-161 1.59060E-08 3.58940E-05 651610 + 842 651620 Tb-162 8.48110E-08 1.79210E-05 651620 + 843 651630 Tb-163 2.05520E-07 5.21010E-06 651630 + 844 651640 Tb-164 6.52350E-07 5.18950E-06 651640 + 845 651650 Tb-165 8.62130E-07 1.96020E-06 651650 + 846 651660 Tb-166 5.70690E-07 8.88510E-07 651660 + 847 651670 Tb-167 3.21160E-07 3.57950E-07 651670 + 848 651680 Tb-168 7.99620E-08 8.36450E-08 651680 + 849 651690 Tb-169 1.91610E-08 1.93160E-08 651690 + 850 651700 Tb-170 1.72900E-09 1.72900E-09 651700 + 851 651710 Tb-171 1.38060E-10 1.38060E-10 651710 + 852 661610 Dy-161 2.08050E-12 3.58940E-05 66161.82c + 853 661620 Dy-162 6.45090E-11 1.79210E-05 66162.82c + 854 661630 Dy-163 4.65320E-10 5.21060E-06 66163.82c + 855 661640 Dy-164 8.90650E-09 5.19840E-06 66164.82c + 856 661650 Dy-165 2.77100E-08 1.99160E-06 661650 + 857 661651 Dy-165m 3.68940E-09 3.68940E-09 661651 + 858 661660 Dy-166 1.07940E-07 9.96450E-07 661660 + 859 661670 Dy-167 1.37400E-07 4.95350E-07 661670 + 860 661680 Dy-168 1.56890E-07 2.40530E-07 661680 + 861 661690 Dy-169 8.30550E-08 1.02370E-07 661690 + 862 661700 Dy-170 3.76020E-08 3.93310E-08 661700 + 863 661710 Dy-171 7.75950E-09 7.89760E-09 661710 + 864 661720 Dy-172 1.43690E-09 1.43690E-09 661720 + 865 661730 Dy-173 9.93090E-11 9.93090E-11 661730 + 866 671640 Ho-164 4.30490E-13 1.60390E-12 671640 + 867 671641 Ho-164m 1.17340E-12 1.17340E-12 671641 + 868 671650 Ho-165 3.74260E-11 1.99170E-06 67165.82c + 869 671660 Ho-166 1.00970E-10 9.96550E-07 671660 + 870 671661 Ho-166m 2.75210E-10 2.75210E-10 671661 + 871 671670 Ho-167 2.80260E-09 4.98160E-07 671670 + 872 671680 Ho-168 3.06870E-09 2.48710E-07 671680 + 873 671681 Ho-168m 5.13200E-09 5.13200E-09 671681 + 874 671690 Ho-169 2.16010E-08 1.23970E-07 671690 + 875 671700 Ho-170 1.57320E-08 1.57320E-08 671700 + 876 671701 Ho-170m 5.77140E-09 4.51020E-08 671701 + 877 671710 Ho-171 2.03820E-08 2.82800E-08 671710 + 878 671720 Ho-172 8.59810E-09 1.00350E-08 671720 + 879 671730 Ho-173 3.11320E-09 3.21250E-09 671730 + 880 671740 Ho-174 4.57210E-10 4.57210E-10 671740 + 881 671750 Ho-175 6.71350E-11 6.71350E-11 671750 + 882 681670 Er-167 1.28440E-12 4.98160E-07 68167.82c + 883 681671 Er-167m 1.71010E-13 5.95260E-08 681671 + 884 681680 Er-168 2.67920E-11 2.48760E-07 68168.82c + 885 681690 Er-169 2.01130E-10 1.24170E-07 681690 + 886 681700 Er-170 1.13100E-09 6.19650E-08 68170.82c + 887 681710 Er-171 2.63140E-09 3.09110E-08 681710 + 888 681720 Er-172 5.31670E-09 1.53520E-08 681720 + 889 681730 Er-173 4.17130E-09 7.38380E-09 681730 + 890 681740 Er-174 2.86370E-09 3.32090E-09 681740 + 891 681750 Er-175 9.96360E-10 1.06350E-09 681750 + 892 681760 Er-176 3.04430E-10 3.04430E-10 681760 + 893 681770 Er-177 3.56850E-11 3.56850E-11 681770 + 894 691710 Tm-171 1.32350E-11 3.09240E-08 691710 + 895 691720 Tm-172 7.39720E-11 1.54260E-08 691720 + 896 691730 Tm-173 3.14940E-10 7.69870E-09 691730 + 897 691740 Tm-174 5.08530E-10 3.82940E-09 691740 + 898 691750 Tm-175 8.23570E-10 1.88710E-09 691750 + 899 691760 Tm-176 5.46050E-10 8.50480E-10 691760 + 900 691770 Tm-177 3.08490E-10 3.44180E-10 691770 + 901 691780 Tm-178 7.72170E-11 7.72170E-11 691780 + 902 691790 Tm-179 1.85880E-11 1.85880E-11 691790 + 903 701740 Yb-174 6.83410E-12 3.83630E-09 701740 + 904 701750 Yb-175 2.60800E-11 1.91660E-09 701750 + 905 701751 Yb-175m 3.47250E-12 1.45650E-09 701751 + 906 701760 Yb-176 3.28770E-11 9.02910E-10 701760 + 907 701761 Yb-176m 6.89730E-11 4.94210E-10 701761 + 908 701770 Yb-177 1.08440E-10 4.74450E-10 701770 + 909 701771 Yb-177m 2.18330E-11 3.66010E-10 701771 + 910 701780 Yb-178 1.49550E-10 2.26770E-10 701780 + 911 701790 Yb-179 7.94860E-11 9.80740E-11 701790 + 912 701800 Yb-180 3.61340E-11 3.61340E-11 701800 + 913 701810 Yb-181 7.50310E-12 7.50310E-12 701810 + 914 711770 Lu-177 1.74470E-12 4.76380E-10 711770 + 915 711780 Lu-178 3.29340E-12 2.30060E-10 711780 + 916 711781 Lu-178m 4.41230E-12 4.41230E-12 711781 + 917 711790 Lu-179 1.80000E-11 1.18470E-10 711790 + 918 711791 Lu-179m 2.39650E-12 1.00470E-10 711791 + 919 711800 Lu-180 5.40930E-12 3.09700E-11 711800 + 920 711801 Lu-180m 5.40930E-12 4.15430E-11 711801 + 921 711802 Lu-180m 9.57840E-12 9.57840E-12 711802 + 922 711810 Lu-181 1.94500E-11 2.69530E-11 711810 + 923 711820 Lu-182 8.25090E-12 8.25090E-12 711820 + 924 711830 Lu-183 3.00090E-12 3.00090E-12 711830 + 925 721800 Hf-180 3.41170E-13 5.75710E-11 72180.82c + 926 721801 Hf-180m 7.15730E-13 5.50490E-12 721801 + 927 721810 Hf-181 2.47650E-12 2.94300E-11 721810 + 928 721820 Hf-182 1.62550E-12 1.13090E-11 721820 + 929 721821 Hf-182m 3.41010E-12 3.41010E-12 721821 + 930 721830 Hf-183 3.96920E-12 6.97010E-12 721830 + 931 721841 Hf-184m 1.85500E-12 1.85500E-12 721841 + + Nuclide 93239.82c -- neptunium 239 (Np-239) is using NFY data from U-238 + + Nuclide 94236.82c -- plutonium 236 (Pu-236) is using NFY data from Th-232 + + Nuclide 94237.82c -- plutonium 237 (Pu-237) is using NFY data from U-235 + + Nuclide 94238.82c -- plutonium 238 (Pu-238) + + Neutron-induced fission: + + Interpolation region : 1 / 2 + Interpolation energy : 2.53000E-08 MeV + Number of products : 1019 / 1084 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 3.82810E-05 3.82810E-05 1001.82c + 2 10020 H-2 1.16990E-05 1.16990E-05 1002.82c + 3 10030 H-3 1.44000E-04 1.44000E-04 1003.82c + 4 20040 He-4 2.42000E-03 2.42000E-03 2004.82c + 5 210510 Sc-51 1.37880E-12 1.37880E-12 210510 + 6 210520 Sc-52 2.45790E-12 2.45790E-12 210520 + 7 210530 Sc-53 3.83610E-12 3.83610E-12 210530 + 8 210540 Sc-54 2.36900E-12 2.36900E-12 210540 + 9 210550 Sc-55 1.64510E-12 1.64510E-12 210550 + 10 220520 Ti-52 1.29280E-12 3.75070E-12 220520 + 11 220530 Ti-53 4.11080E-12 7.94690E-12 220530 + 12 220540 Ti-54 1.17410E-11 1.41100E-11 220540 + 13 220550 Ti-55 1.74450E-11 1.90900E-11 220550 + 14 220560 Ti-56 2.32510E-11 2.32510E-11 220560 + 15 220570 Ti-57 1.22590E-11 1.22590E-11 220570 + 16 220580 Ti-58 5.59750E-12 5.59750E-12 220580 + 17 220590 Ti-59 1.05520E-12 1.05520E-12 220590 + 18 230540 V-54 1.31570E-12 1.54260E-11 230540 + 19 230550 V-55 9.22630E-12 2.83160E-11 230550 + 20 230560 V-56 2.48630E-11 4.81510E-11 230560 + 21 230570 V-57 6.19280E-11 7.41500E-11 230570 + 22 230580 V-58 6.28730E-11 6.84710E-11 230580 + 23 230590 V-59 6.46270E-11 6.56820E-11 230590 + 24 230600 V-60 2.47990E-11 2.47990E-11 230600 + 25 230610 V-61 9.73060E-12 9.73060E-12 230610 + 26 230620 V-62 1.39500E-12 1.39500E-12 230620 + 27 240560 Cr-56 4.31780E-12 5.27650E-11 240560 + 28 240570 Cr-57 2.29830E-11 1.51610E-10 240570 + 29 240580 Cr-58 1.07870E-10 1.21560E-10 240580 + 30 240590 Cr-59 2.26010E-10 2.91690E-10 240590 + 31 240600 Cr-60 4.23210E-10 4.48590E-10 240600 + 32 240610 Cr-61 3.84610E-10 3.93760E-10 240610 + 33 240620 Cr-62 3.11580E-10 3.12970E-10 240620 + 34 240630 Cr-63 9.14620E-11 9.14620E-11 240630 + 35 240640 Cr-64 2.22480E-11 2.22480E-11 240640 + 36 240650 Cr-65 2.51810E-12 2.51810E-12 240650 + 37 250580 Mn-58 3.47160E-12 1.25040E-10 250580 + 38 250590 Mn-59 4.06690E-11 3.32360E-10 250590 + 39 250600 Mn-60 1.59640E-11 4.80860E-10 250600 + 40 250601 Mn-60m 1.41790E-10 1.41790E-10 250601 + 41 250610 Mn-61 6.58720E-10 1.05250E-09 250610 + 42 250620 Mn-62 9.43260E-10 1.09980E-09 250620 + 43 250621 Mn-62m 1.69340E-10 3.25830E-10 250621 + 44 250630 Mn-63 1.65710E-09 1.74860E-09 250630 + 45 250640 Mn-64 9.70950E-10 9.93200E-10 250640 + 46 250650 Mn-65 6.40580E-10 6.43100E-10 250650 + 47 250660 Mn-66 1.54760E-10 1.54760E-10 250660 + 48 250670 Mn-67 3.06770E-11 3.06770E-11 250670 + 49 250680 Mn-68 2.18870E-12 2.18870E-12 250680 + 50 260600 Fe-60 8.45620E-12 6.14800E-10 260600 + 51 260610 Fe-61 8.09960E-11 1.13350E-09 260610 + 52 260620 Fe-62 6.61940E-10 2.08750E-09 260620 + 53 260630 Fe-63 2.00290E-09 3.75150E-09 260630 + 54 260640 Fe-64 5.44520E-09 6.43840E-09 260640 + 55 260650 Fe-65 7.74420E-09 8.38730E-09 260650 + 56 260660 Fe-66 9.88790E-09 1.00430E-08 260660 + 57 260670 Fe-67 4.89090E-09 4.92160E-09 260670 + 58 260680 Fe-68 2.08740E-09 2.08960E-09 260680 + 59 260690 Fe-69 3.74790E-10 3.74790E-10 260690 + 60 260700 Fe-70 8.19030E-11 8.19030E-11 260700 + 61 260710 Fe-71 2.40080E-12 2.40080E-12 260710 + 62 270620 Co-62 2.11620E-12 2.08970E-09 270620 + 63 270621 Co-62m 4.95660E-12 4.95660E-12 270621 + 64 270630 Co-63 1.15620E-10 3.86710E-09 270630 + 65 270640 Co-64 6.92300E-10 7.13070E-09 270640 + 66 270650 Co-65 4.62240E-09 1.30100E-08 270650 + 67 270660 Co-66 1.19370E-08 2.19800E-08 270660 + 68 270670 Co-67 2.80600E-08 3.29820E-08 270670 + 69 270680 Co-68 1.42660E-08 2.16160E-08 270680 + 70 270681 Co-68m 1.25850E-08 1.47010E-08 270681 + 71 270690 Co-69 2.64910E-08 2.68400E-08 270690 + 72 270700 Co-70 7.44650E-09 7.44650E-09 270700 + 73 270701 Co-70m 7.44650E-09 7.52840E-09 270701 + 74 270710 Co-71 2.66390E-09 2.66630E-09 270710 + 75 270720 Co-72 4.78970E-10 4.78970E-10 270720 + 76 270730 Co-73 5.06840E-11 5.06840E-11 270730 + 77 280640 Ni-64 1.07330E-11 7.14140E-09 28064.82c + 78 280650 Ni-65 1.76140E-10 1.31860E-08 280650 + 79 280660 Ni-66 2.36100E-09 2.43410E-08 280660 + 80 280670 Ni-67 1.17760E-08 4.47580E-08 280670 + 81 280680 Ni-68 5.19590E-08 8.11940E-08 280680 + 82 280690 Ni-69 5.24300E-08 7.90010E-08 280690 + 83 280691 Ni-69m 5.24300E-08 5.24300E-08 280691 + 84 280700 Ni-70 4.07380E-07 4.22350E-07 280700 + 85 280710 Ni-71 1.21100E-07 1.23770E-07 280710 + 86 280720 Ni-72 1.23870E-07 1.24350E-07 280720 + 87 280730 Ni-73 3.45840E-08 3.46350E-08 280730 + 88 280740 Ni-74 2.61120E-09 2.61120E-09 280740 + 89 280750 Ni-75 6.16270E-10 6.16270E-10 280750 + 90 280760 Ni-76 4.41720E-11 4.41720E-11 280760 + 91 280770 Ni-77 1.89230E-12 1.89230E-12 280770 + 92 290660 Cu-66 7.09640E-12 2.43480E-08 290660 + 93 290670 Cu-67 2.03610E-10 4.49610E-08 290670 + 94 290680 Cu-68 6.36550E-10 8.30830E-08 290680 + 95 290681 Cu-68m 1.49090E-09 1.49090E-09 290681 + 96 290690 Cu-69 2.14010E-08 1.52830E-07 290690 + 97 290700 Cu-70 9.27890E-09 7.17560E-08 290700 + 98 290701 Cu-70m 1.03370E-07 1.24950E-07 290701 + 99 290702 Cu-70m 9.27890E-09 4.31630E-07 290702 + 100 290710 Cu-71 3.95030E-07 5.18800E-07 290710 + 101 290720 Cu-72 5.02590E-07 6.26940E-07 290720 + 102 290730 Cu-73 7.17890E-07 7.52530E-07 290730 + 103 290740 Cu-74 4.88990E-07 4.91610E-07 290740 + 104 290750 Cu-75 5.53800E-07 5.54410E-07 290750 + 105 290760 Cu-76 1.76030E-08 1.76260E-08 290760 + 106 290761 Cu-76m 1.76030E-08 1.76260E-08 290761 + 107 290770 Cu-77 1.01440E-08 1.01460E-08 290770 + 108 290780 Cu-78 6.12900E-10 6.12900E-10 290780 + 109 290790 Cu-79 4.97090E-11 4.97090E-11 290790 + 110 300680 Zn-68 9.05920E-12 8.33310E-08 300680 + 111 300690 Zn-69 4.44410E-11 1.53070E-07 300690 + 112 300691 Zn-69m 1.92200E-10 1.92200E-10 300691 + 113 300700 Zn-70 7.50390E-09 5.51790E-07 300700 + 114 300710 Zn-71 6.15670E-09 5.24950E-07 300710 + 115 300711 Zn-71m 2.66260E-08 2.66260E-08 300711 + 116 300720 Zn-72 3.38020E-07 9.64960E-07 300720 + 117 300730 Zn-73 9.67940E-08 1.35640E-06 300730 + 118 300731 Zn-73m 1.32320E-07 5.07120E-07 300731 + 119 300732 Zn-73m 7.49590E-07 7.49590E-07 300732 + 120 300740 Zn-74 4.88990E-07 1.00000E-06 300740 + 121 300750 Zn-75 2.21520E-06 2.75070E-06 300750 + 122 300760 Zn-76 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6.27500E-02 42098.82c + 359 420990 Mo-99 9.50540E-04 5.91190E-02 42099.82c + 360 421000 Mo-100 5.37820E-03 6.48840E-02 42100.82c + 361 421010 Mo-101 1.33600E-02 6.51750E-02 421010 + 362 421020 Mo-102 3.60380E-02 7.18440E-02 421020 + 363 421030 Mo-103 4.43990E-02 6.85690E-02 421030 + 364 421040 Mo-104 4.33430E-02 5.30090E-02 421040 + 365 421050 Mo-105 2.53110E-02 2.92720E-02 421050 + 366 421060 Mo-106 1.31310E-02 1.38770E-02 421060 + 367 421070 Mo-107 3.79650E-03 3.91160E-03 421070 + 368 421080 Mo-108 1.01600E-03 1.02510E-03 421080 + 369 421090 Mo-109 1.48270E-04 1.50290E-04 421090 + 370 421100 Mo-110 1.05680E-05 1.05680E-05 421100 + 371 421110 Mo-111 1.96660E-09 1.96660E-09 421110 + 372 421120 Mo-112 2.33480E-11 2.33480E-11 421120 + 373 430980 Tc-98 1.42560E-09 1.42560E-09 430980 + 374 430990 Tc-99 2.13240E-06 5.91190E-02 43099.82c + 375 430991 Tc-99m 4.93070E-07 5.20610E-02 430991 + 376 431000 Tc-100 3.23160E-05 3.23160E-05 431000 + 377 431010 Tc-101 2.28940E-04 6.54040E-02 431010 + 378 431020 Tc-102 5.78550E-04 7.24230E-02 431020 + 379 431021 Tc-102m 5.78550E-04 5.78550E-04 431021 + 380 431030 Tc-103 5.44640E-03 7.40150E-02 431030 + 381 431040 Tc-104 1.00100E-02 6.30190E-02 431040 + 382 431050 Tc-105 2.14070E-02 5.06790E-02 431050 + 383 431060 Tc-106 1.93750E-02 3.32520E-02 431060 + 384 431070 Tc-107 1.60680E-02 1.99800E-02 431070 + 385 431080 Tc-108 7.18130E-03 8.20720E-03 431080 + 386 431090 Tc-109 3.71060E-03 3.86010E-03 431090 + 387 431100 Tc-110 4.45020E-04 4.55590E-04 431100 + 388 431110 Tc-111 1.17190E-04 1.17190E-04 431110 + 389 431120 Tc-112 2.32020E-05 2.32020E-05 431120 + 390 431130 Tc-113 4.24400E-06 4.24400E-06 431130 + 391 431140 Tc-114 2.19590E-11 2.19590E-11 431140 + 392 441010 Ru-101 2.96210E-06 6.54070E-02 44101.82c + 393 441020 Ru-102 2.31080E-05 7.30240E-02 44102.82c + 394 441030 Ru-103 4.87800E-05 7.41810E-02 44103.82c + 395 441031 Ru-103m 1.17760E-04 1.17760E-04 441031 + 396 441040 Ru-104 9.46140E-04 6.39650E-02 44104.82c + 397 441050 Ru-105 2.90940E-03 5.35880E-02 44105.82c + 398 441060 Ru-106 6.54730E-03 3.98000E-02 44106.82c + 399 441070 Ru-107 8.32340E-03 2.83030E-02 441070 + 400 441080 Ru-108 9.33930E-03 1.75500E-02 441080 + 401 441090 Ru-109 7.20450E-03 1.10620E-02 441090 + 402 441100 Ru-110 2.40120E-03 2.85660E-03 441100 + 403 441110 Ru-111 6.83610E-04 8.01150E-04 441110 + 404 441120 Ru-112 1.69750E-04 1.92910E-04 441120 + 405 441130 Ru-113 6.37000E-06 1.34940E-05 441130 + 406 441131 Ru-113m 6.37000E-06 6.37000E-06 441131 + 407 441140 Ru-114 1.20890E-05 1.20890E-05 441140 + 408 441150 Ru-115 6.25540E-09 6.25540E-09 441150 + 409 441160 Ru-116 1.55490E-10 1.55490E-10 441160 + 410 441200 Ru-120 8.85000E-11 8.85000E-11 441200 + 411 451030 Rh-103 2.74310E-10 7.41810E-02 45103.82c + 412 451031 Rh-103m 1.79440E-09 7.32930E-02 451031 + 413 451040 Rh-104 1.23890E-06 4.97270E-06 451040 + 414 451041 Rh-104m 3.73870E-06 3.73870E-06 451041 + 415 451050 Rh-105 2.08390E-05 5.36120E-02 45105.82c + 416 451051 Rh-105m 3.18570E-06 1.52160E-02 451051 + 417 451060 Rh-106 3.23260E-05 3.98320E-02 451060 + 418 451061 Rh-106m 7.57140E-05 7.57140E-05 451061 + 419 451070 Rh-107 4.04130E-04 2.87070E-02 451070 + 420 451080 Rh-108 1.72890E-04 1.77220E-02 451080 + 421 451081 Rh-108m 5.21710E-04 5.21710E-04 451081 + 422 451090 Rh-109 1.54040E-03 1.26020E-02 451090 + 423 451100 Rh-110 7.65040E-04 3.62160E-03 451100 + 424 451101 Rh-110m 2.04220E-05 2.04220E-05 451101 + 425 451110 Rh-111 7.12530E-04 1.51370E-03 451110 + 426 451120 Rh-112 1.58160E-04 3.51070E-04 451120 + 427 451121 Rh-112m 1.58160E-04 1.58160E-04 451121 + 428 451130 Rh-113 1.63470E-04 1.80150E-04 451130 + 429 451140 Rh-114 3.72620E-05 4.93510E-05 451140 + 430 451141 Rh-114m 3.72620E-05 3.72620E-05 451141 + 431 451150 Rh-115 3.74430E-05 3.74490E-05 451150 + 432 451160 Rh-116 1.16920E-06 1.16930E-06 451160 + 433 451161 Rh-116m 2.73850E-06 2.73850E-06 451161 + 434 451170 Rh-117 1.97020E-06 1.97020E-06 451170 + 435 451180 Rh-118 5.11030E-10 5.11030E-10 451180 + 436 451190 Rh-119 1.19290E-11 1.19290E-11 451190 + 437 451200 Rh-120 1.58780E-07 1.58870E-07 451200 + 438 451210 Rh-121 1.24720E-08 1.24720E-08 451210 + 439 451220 Rh-122 3.52670E-10 3.52670E-10 451220 + 440 461060 Pd-106 1.66790E-08 3.99080E-02 46106.82c + 441 461070 Pd-107 2.09340E-06 2.87130E-02 46107.82c + 442 461071 Pd-107m 3.93430E-06 3.93430E-06 461071 + 443 461080 Pd-108 2.96700E-05 1.82740E-02 46108.82c + 444 461090 Pd-109 2.24130E-05 1.26670E-02 461090 + 445 461091 Pd-109m 4.21210E-05 6.34320E-03 461091 + 446 461100 Pd-110 8.92950E-05 3.73140E-03 46110.82c + 447 461110 Pd-111 3.39640E-05 1.59260E-03 461110 + 448 461111 Pd-111m 6.38310E-05 6.98850E-05 461111 + 449 461120 Pd-112 9.80140E-05 6.07240E-04 461120 + 450 461130 Pd-113 3.41140E-05 2.96620E-04 461130 + 451 461131 Pd-113m 8.23560E-05 8.23560E-05 461131 + 452 461140 Pd-114 8.84730E-05 1.75090E-04 461140 + 453 461150 Pd-115 3.10450E-05 6.81600E-05 461150 + 454 461151 Pd-115m 5.83450E-05 6.37830E-05 461151 + 455 461160 Pd-116 6.64630E-05 7.03710E-05 461160 + 456 461170 Pd-117 1.09530E-05 3.35080E-05 461170 + 457 461171 Pd-117m 2.05850E-05 2.05850E-05 461171 + 458 461180 Pd-118 1.32280E-05 1.32290E-05 461180 + 459 461190 Pd-119 4.27170E-06 4.28110E-06 461190 + 460 461200 Pd-120 2.51400E-05 2.52910E-05 461200 + 461 461210 Pd-121 5.04500E-06 5.05580E-06 461210 + 462 461220 Pd-122 8.61100E-07 8.61450E-07 461220 + 463 461230 Pd-123 9.51090E-08 9.51090E-08 461230 + 464 461240 Pd-124 9.00170E-09 9.00170E-09 461240 + 465 471080 Ag-108 2.43890E-10 2.93590E-10 471080 + 466 471081 Ag-108m 5.71260E-10 5.71260E-10 471081 + 467 471090 Ag-109 3.98180E-09 1.26670E-02 47109.82c + 468 471091 Ag-109m 2.60470E-08 1.26600E-02 471091 + 469 471100 Ag-110 6.59800E-08 6.80810E-08 471100 + 470 471101 Ag-110m 1.54540E-07 1.54540E-07 47510.82c + 471 471110 Ag-111 7.12340E-07 1.60880E-03 47111.82c + 472 471111 Ag-111m 4.65980E-06 1.59950E-03 471111 + 473 471120 Ag-112 1.93060E-06 6.09170E-04 471120 + 474 471130 Ag-113 5.62500E-07 1.97280E-04 471130 + 475 471131 Ag-113m 3.67960E-06 2.87720E-04 471131 + 476 471140 Ag-114 2.70550E-06 1.89170E-04 471140 + 477 471141 Ag-114m 1.13780E-05 1.13780E-05 471141 + 478 471150 Ag-115 6.33390E-06 8.09790E-05 471150 + 479 471151 Ag-115m 4.14330E-05 1.18520E-04 471151 + 480 471160 Ag-116 1.57730E-05 8.83600E-05 471160 + 481 471161 Ag-116m 3.69430E-05 3.69430E-05 471161 + 482 471170 Ag-117 7.83630E-06 2.86710E-05 471170 + 483 471171 Ag-117m 5.12610E-05 6.80150E-05 471171 + 484 471180 Ag-118 1.30680E-05 4.77140E-05 471180 + 485 471181 Ag-118m 5.49590E-05 5.68500E-05 471181 + 486 471190 Ag-119 5.66600E-06 7.80660E-06 471190 + 487 471191 Ag-119m 3.70640E-05 3.92050E-05 471191 + 488 471200 Ag-120 1.21440E-05 3.58580E-05 471200 + 489 471201 Ag-120m 1.72320E-05 2.98770E-05 471201 + 490 471210 Ag-121 1.77780E-05 2.28200E-05 471210 + 491 471220 Ag-122 1.05120E-06 1.91260E-06 471220 + 492 471221 Ag-122m 9.46850E-07 9.46850E-07 471221 + 493 471230 Ag-123 7.73460E-06 7.82970E-06 471230 + 494 471240 Ag-124 2.11910E-06 3.08250E-06 471240 + 495 471241 Ag-124m 1.90880E-06 1.90880E-06 471241 + 496 471250 Ag-125 4.00800E-06 4.00800E-06 471250 + 497 471260 Ag-126 2.26360E-06 2.26360E-06 471260 + 498 471270 Ag-127 2.20270E-08 2.20270E-08 471270 + 499 471280 Ag-128 6.80580E-10 6.80580E-10 471280 + 500 481110 Cd-111 1.65270E-10 1.61680E-03 48111.82c + 501 481111 Cd-111m 5.40710E-10 5.40710E-10 481111 + 502 481120 Cd-112 1.30980E-08 6.09190E-04 48112.82c + 503 481130 Cd-113 2.78910E-08 2.97480E-04 48113.82c + 504 481131 Cd-113m 9.12490E-08 3.50210E-06 481131 + 505 481140 Cd-114 1.17310E-06 1.90340E-04 48114.82c + 506 481150 Cd-115 4.86550E-07 1.67700E-04 481150 + 507 481151 Cd-115m 1.59190E-06 8.98400E-06 48515.82c + 508 481160 Cd-116 3.90670E-06 1.26990E-04 48116.82c + 509 481170 Cd-117 5.07080E-06 7.69860E-05 481170 + 510 481171 Cd-117m 1.65900E-05 3.72810E-05 481171 + 511 481180 Cd-118 3.58730E-05 1.17130E-04 481180 + 512 481190 Cd-119 1.56330E-05 5.87420E-05 481190 + 513 481191 Cd-119m 3.77410E-05 4.16450E-05 481191 + 514 481200 Cd-120 7.70650E-05 1.31750E-04 481200 + 515 481210 Cd-121 1.67760E-05 3.72120E-05 481210 + 516 481211 Cd-121m 4.05010E-05 4.28850E-05 481211 + 517 481220 Cd-122 6.39800E-05 6.68390E-05 481220 + 518 481230 Cd-123 1.81400E-05 2.45470E-05 481230 + 519 481231 Cd-123m 4.37910E-05 4.52170E-05 481231 + 520 481240 Cd-124 1.16520E-04 1.20550E-04 481240 + 521 481250 Cd-125 3.29570E-05 3.49610E-05 481250 + 522 481251 Cd-125m 7.95630E-05 8.15670E-05 481251 + 523 481260 Cd-126 1.24940E-04 1.27200E-04 481260 + 524 481270 Cd-127 7.11430E-05 7.11650E-05 481270 + 525 481280 Cd-128 2.55040E-05 2.55050E-05 481280 + 526 481290 Cd-129 8.87600E-07 8.87600E-07 481290 + 527 481291 Cd-129m 2.14280E-06 2.14280E-06 481291 + 528 481300 Cd-130 2.63620E-08 2.63620E-08 481300 + 529 491130 In-113 1.39450E-11 3.49720E-06 49113.82c + 530 491131 In-113m 3.22430E-12 3.22430E-12 491131 + 531 491140 In-114 1.14780E-10 4.48970E-10 491140 + 532 491141 In-114m 1.75920E-10 3.46320E-10 491141 + 533 491142 In-114m 1.70390E-10 1.70390E-10 491142 + 534 491150 In-115 1.27550E-08 1.68320E-04 49115.82c + 535 491151 In-115m 2.94920E-09 1.67710E-04 491151 + 536 491160 In-116 3.82460E-08 3.82460E-08 491160 + 537 491161 In-116m 5.86210E-08 1.15400E-07 491161 + 538 491162 In-116m 5.67770E-08 5.67770E-08 491162 + 539 491170 In-117 1.30890E-06 7.80950E-05 491170 + 540 491171 In-117m 3.02640E-07 7.14220E-05 491171 + 541 491180 In-118 4.70150E-07 1.17600E-04 491180 + 542 491181 In-118m 7.20620E-07 1.40880E-06 491181 + 543 491182 In-118m 6.97950E-07 6.97950E-07 491182 + 544 491190 In-119 1.73440E-06 5.19970E-05 491190 + 545 491191 In-119m 4.01050E-07 5.35220E-05 491191 + 546 491200 In-120 6.72700E-06 1.38470E-04 491200 + 547 491201 In-120m 6.72700E-06 6.72700E-06 491201 + 548 491202 In-120m 6.72700E-06 6.72700E-06 491202 + 549 491210 In-121 4.64810E-05 1.02320E-04 491210 + 550 491211 In-121m 1.07480E-05 3.54270E-05 491211 + 551 491220 In-122 2.14710E-05 8.83100E-05 491220 + 552 491221 In-122m 1.52330E-05 1.52330E-05 491221 + 553 491222 In-122m 1.52330E-05 1.52330E-05 491222 + 554 491230 In-123 8.79610E-05 1.40230E-04 491230 + 555 491231 In-123m 2.03390E-05 3.78340E-05 491231 + 556 491240 In-124 7.57480E-05 1.96300E-04 491240 + 557 491241 In-124m 6.82320E-05 6.82320E-05 491241 + 558 491250 In-125 5.01970E-04 6.00270E-04 491250 + 559 491251 In-125m 1.16070E-04 1.34290E-04 491251 + 560 491260 In-126 6.08700E-04 7.35900E-04 491260 + 561 491261 In-126m 5.48300E-04 5.48300E-04 491261 + 562 491270 In-127 1.31950E-03 1.31950E-03 491270 + 563 491271 In-127m 3.05100E-04 3.76260E-04 491271 + 564 491280 In-128 4.20230E-04 6.16790E-04 491280 + 565 491281 In-128m 1.71060E-04 1.96560E-04 491281 + 566 491282 In-128m 5.32620E-04 5.32620E-04 491282 + 567 491290 In-129 4.29870E-04 4.32020E-04 491290 + 568 491291 In-129m 9.93970E-05 1.00290E-04 491291 + 569 491300 In-130 3.47610E-05 3.47870E-05 491300 + 570 491301 In-130m 3.88260E-05 3.88260E-05 491301 + 571 491302 In-130m 6.60590E-05 6.60590E-05 491302 + 572 491310 In-131 7.38760E-06 7.46280E-06 491310 + 573 491311 In-131m 7.38760E-06 7.38760E-06 491311 + 574 491312 In-131m 7.38760E-06 7.38760E-06 491312 + 575 491320 In-132 2.04730E-07 2.04730E-07 491320 + 576 491330 In-133 3.54580E-09 4.36570E-09 491330 + 577 491331 In-133m 8.19880E-10 8.19880E-10 491331 + 578 501160 Sn-116 8.26070E-11 1.53730E-07 50116.82c + 579 501170 Sn-117 5.61910E-10 1.15880E-04 50117.82c + 580 501171 Sn-117m 1.83840E-09 2.67920E-07 501171 + 581 501180 Sn-118 6.73050E-08 1.19090E-04 50118.82c + 582 501190 Sn-119 4.99870E-07 1.04660E-04 50119.82c + 583 501191 Sn-119m 1.63540E-06 4.86100E-05 501191 + 584 501200 Sn-120 1.83530E-06 1.53760E-04 50120.82c + 585 501210 Sn-121 1.28870E-09 1.34730E-04 501210 + 586 501211 Sn-121m 3.11110E-09 1.15950E-05 501211 + 587 501220 Sn-122 1.19800E-05 1.30760E-04 50122.82c + 588 501230 Sn-123 2.32030E-05 3.38940E-05 50123.82c + 589 501231 Sn-123m 9.61120E-06 1.76980E-04 501231 + 590 501240 Sn-124 8.64050E-05 3.50940E-04 50124.82c + 591 501250 Sn-125 2.43980E-04 3.45380E-04 50125.82c + 592 501251 Sn-125m 1.01060E-04 7.34230E-04 501251 + 593 501260 Sn-126 1.98720E-03 3.27400E-03 50126.82c + 594 501270 Sn-127 2.85520E-03 3.36950E-03 501270 + 595 501271 Sn-127m 1.18270E-03 2.36160E-03 501271 + 596 501280 Sn-128 2.98610E-03 1.11300E-02 501280 + 597 501281 Sn-128m 6.99410E-03 7.52670E-03 501281 + 598 501290 Sn-129 2.45190E-03 2.93830E-03 501290 + 599 501291 Sn-129m 5.91910E-03 5.96510E-03 501291 + 600 501300 Sn-130 2.76330E-03 2.85420E-03 501300 + 601 501301 Sn-130m 6.47230E-03 6.52130E-03 501301 + 602 501310 Sn-131 1.00020E-03 1.01450E-03 501310 + 603 501311 Sn-131m 2.41450E-03 2.42220E-03 501311 + 604 501320 Sn-132 1.17800E-03 1.17820E-03 501320 + 605 501330 Sn-133 4.99140E-05 4.99150E-05 501330 + 606 501340 Sn-134 7.15780E-06 7.15780E-06 501340 + 607 501350 Sn-135 4.16210E-08 4.16210E-08 501350 + 608 511180 Sb-118 2.28390E-12 2.28390E-12 511180 + 609 511181 Sb-118m 3.24070E-12 3.24070E-12 511181 + 610 511190 Sb-119 2.89640E-10 3.81710E-10 511190 + 611 511191 Sb-119m 9.20680E-11 9.20680E-11 511191 + 612 511220 Sb-122 5.65110E-12 1.20570E-11 511220 + 613 511221 Sb-122m 6.40590E-12 6.40590E-12 511221 + 614 511230 Sb-123 3.86560E-06 2.14740E-04 51123.82c + 615 511240 Sb-124 2.11150E-06 4.96000E-06 51124.82c + 616 511241 Sb-124m 1.61450E-06 3.79800E-06 511241 + 617 511242 Sb-124m 2.18360E-06 2.18360E-06 511242 + 618 511250 Sb-125 2.60280E-05 1.10560E-03 51125.82c + 619 511260 Sb-126 4.76030E-05 5.89750E-05 51126.82c + 620 511261 Sb-126m 3.51960E-05 8.12270E-05 511261 + 621 511262 Sb-126m 4.60310E-05 4.60310E-05 511262 + 622 511270 Sb-127 7.12580E-04 6.44370E-03 511270 + 623 511280 Sb-128 1.07950E-03 1.22750E-02 511280 + 624 511281 Sb-128m 1.84190E-03 1.84190E-03 511281 + 625 511290 Sb-129 6.58310E-03 1.35550E-02 511290 + 626 511291 Sb-129m 4.02290E-03 7.00540E-03 511291 + 627 511300 Sb-130 9.32900E-03 1.54440E-02 511300 + 628 511301 Sb-130m 9.32900E-03 1.25900E-02 511301 + 629 511310 Sb-131 2.50280E-02 2.84650E-02 511310 + 630 511320 Sb-132 9.76270E-03 1.09410E-02 511320 + 631 511321 Sb-132m 7.19530E-03 7.19530E-03 511321 + 632 511330 Sb-133 8.60500E-03 8.65610E-03 511330 + 633 511340 Sb-134 4.02510E-04 4.08460E-04 511340 + 634 511341 Sb-134m 9.42790E-04 9.42790E-04 511341 + 635 511350 Sb-135 1.99030E-04 1.99060E-04 511350 + 636 511360 Sb-136 1.06970E-05 1.06970E-05 511360 + 637 511370 Sb-137 7.86780E-07 7.86780E-07 511370 + 638 511380 Sb-138 2.75780E-09 2.75780E-09 511380 + 639 521240 Te-124 1.34960E-11 5.90950E-06 52124.82c + 640 521250 Te-125 2.49710E-10 1.10560E-03 52125.82c + 641 521251 Te-125m 8.16990E-10 2.47410E-04 521251 + 642 521260 Te-126 9.05330E-06 1.37880E-04 52126.82c + 643 521270 Te-127 7.98560E-06 6.44500E-03 521270 + 644 521271 Te-127m 1.92780E-05 1.08120E-03 52527.82c + 645 521280 Te-128 2.74870E-04 1.43260E-02 52128.82c + 646 521290 Te-129 3.90880E-04 1.75110E-02 521290 + 647 521291 Te-129m 9.43630E-04 9.00820E-03 52529.82c + 648 521300 Te-130 9.90610E-03 3.79400E-02 52130.82c + 649 521310 Te-131 6.08620E-03 3.58360E-02 521310 + 650 521311 Te-131m 1.46930E-02 1.69720E-02 521311 + 651 521320 Te-132 5.50060E-02 7.31420E-02 52132.82c + 652 521330 Te-133 1.38430E-02 2.71130E-02 521330 + 653 521331 Te-133m 3.34180E-02 3.49150E-02 521331 + 654 521340 Te-134 3.90740E-02 4.04560E-02 521340 + 655 521350 Te-135 9.75310E-03 9.92260E-03 521350 + 656 521360 Te-136 3.18300E-03 3.19230E-03 521360 + 657 521370 Te-137 3.94420E-04 3.94820E-04 521370 + 658 521380 Te-138 7.82660E-05 7.82690E-05 521380 + 659 521390 Te-139 1.96160E-06 1.96160E-06 521390 + 660 521400 Te-140 3.47800E-08 3.47800E-08 521400 + 661 531270 I-127 7.53050E-10 6.47090E-03 53127.82c + 662 531280 I-128 6.63560E-08 6.63560E-08 531280 + 663 531290 I-129 9.09060E-06 2.08530E-02 53129.82c + 664 531300 I-130 6.90810E-05 9.38550E-05 53130.82c + 665 531301 I-130m 2.94930E-05 2.94930E-05 531301 + 666 531310 I-131 9.76340E-04 5.02200E-02 53131.82c + 667 531320 I-132 2.33800E-03 7.69620E-02 531320 + 668 531321 I-132m 1.72320E-03 1.72320E-03 531321 + 669 531330 I-133 1.10940E-02 7.37910E-02 531330 + 670 531331 I-133m 6.77920E-03 6.77920E-03 531331 + 671 531340 I-134 1.81230E-02 7.16280E-02 531340 + 672 531341 I-134m 1.33570E-02 1.33570E-02 531341 + 673 531350 I-135 4.80930E-02 5.80160E-02 53135.82c + 674 531360 I-136 6.34060E-03 9.53890E-03 531360 + 675 531361 I-136m 1.48510E-02 1.48570E-02 531361 + 676 531370 I-137 1.11580E-02 1.15460E-02 531370 + 677 531380 I-138 2.67960E-03 2.75290E-03 531380 + 678 531390 I-139 1.36560E-03 1.36760E-03 531390 + 679 531400 I-140 1.61510E-04 1.61540E-04 531400 + 680 531410 I-141 2.96990E-05 2.96990E-05 531410 + 681 531420 I-142 1.69550E-06 1.69550E-06 531420 + 682 531430 I-143 2.12340E-09 2.12340E-09 531430 + 683 541290 Xe-129 1.54070E-10 6.58140E-10 54129.82c + 684 541291 Xe-129m 5.04070E-10 5.04070E-10 541291 + 685 541300 Xe-130 4.54030E-08 9.86190E-05 54130.82c + 686 541310 Xe-131 3.24330E-06 5.02310E-02 54131.82c + 687 541311 Xe-131m 7.82970E-06 5.53310E-04 541311 + 688 541320 Xe-132 5.08070E-05 7.73120E-02 54132.82c + 689 541321 Xe-132m 5.75930E-05 5.75930E-05 541321 + 690 541330 Xe-133 1.93010E-04 7.44500E-02 54133.82c + 691 541331 Xe-133m 4.65960E-04 2.56630E-03 541331 + 692 541340 Xe-134 1.39320E-03 7.65920E-02 54134.82c + 693 541341 Xe-134m 3.26330E-03 3.57060E-03 541341 + 694 541350 Xe-135 4.60730E-03 7.36220E-02 54135.82c + 695 541351 Xe-135m 1.11230E-02 2.07000E-02 541351 + 696 541360 Xe-136 5.15680E-02 7.67150E-02 54136.82c + 697 541370 Xe-137 4.05670E-02 5.15080E-02 541370 + 698 541380 Xe-138 3.71620E-02 3.99030E-02 541380 + 699 541390 Xe-139 1.78980E-02 1.91470E-02 541390 + 700 541400 Xe-140 1.10480E-02 1.12010E-02 541400 + 701 541410 Xe-141 2.94690E-03 2.97080E-03 541410 + 702 541420 Xe-142 7.62910E-04 7.64180E-04 541420 + 703 541430 Xe-143 5.95860E-05 5.95870E-05 541430 + 704 541440 Xe-144 1.02580E-05 1.02580E-05 541440 + 705 541450 Xe-145 1.40870E-08 1.40870E-08 541450 + 706 551320 Cs-132 7.05980E-09 7.05980E-09 551320 + 707 551330 Cs-133 1.38710E-06 7.44510E-02 55133.82c + 708 551340 Cs-134 4.80860E-06 8.35260E-06 55134.82c + 709 551341 Cs-134m 3.54400E-06 3.54400E-06 551341 + 710 551350 Cs-135 9.75120E-05 7.39030E-02 55135.82c + 711 551351 Cs-135m 5.95880E-05 5.95880E-05 551351 + 712 551360 Cs-136 6.15430E-04 7.95770E-04 55136.82c + 713 551361 Cs-136m 3.60670E-04 3.60670E-04 551361 + 714 551370 Cs-137 6.98660E-03 5.84950E-02 55137.82c + 715 551380 Cs-138 6.59290E-03 5.40740E-02 551380 + 716 551381 Cs-138m 9.35510E-03 9.35510E-03 551381 + 717 551390 Cs-139 2.90100E-02 4.81570E-02 551390 + 718 551400 Cs-140 2.07460E-02 3.19480E-02 551400 + 719 551410 Cs-141 2.26150E-02 2.55870E-02 551410 + 720 551420 Cs-142 8.90580E-03 9.66780E-03 551420 + 721 551430 Cs-143 3.95890E-03 4.01820E-03 551430 + 722 551440 Cs-144 3.80760E-04 5.81100E-04 551440 + 723 551441 Cs-144m 3.80760E-04 3.80760E-04 551441 + 724 551450 Cs-145 1.53160E-04 1.53170E-04 551450 + 725 551460 Cs-146 1.07530E-05 1.07530E-05 551460 + 726 551470 Cs-147 1.21990E-06 1.21990E-06 551470 + 727 551480 Cs-148 5.67120E-10 5.67120E-10 551480 + 728 561340 Ba-134 3.09270E-09 8.35570E-06 56134.82c + 729 561350 Ba-135 2.09950E-08 7.16800E-08 56135.82c + 730 561351 Ba-135m 5.06850E-08 5.06850E-08 561351 + 731 561360 Ba-136 2.66830E-06 9.85020E-04 56136.82c + 732 561361 Ba-136m 6.24970E-06 6.24970E-06 561361 + 733 561370 Ba-137 4.20460E-05 5.86390E-02 56137.82c + 734 561371 Ba-137m 1.01500E-04 5.53210E-02 561371 + 735 561380 Ba-138 1.85080E-03 5.77020E-02 56138.82c + 736 561390 Ba-139 7.06180E-03 5.52180E-02 561390 + 737 561400 Ba-140 1.86210E-02 5.05690E-02 56140.82c + 738 561410 Ba-141 2.45220E-02 5.01090E-02 561410 + 739 561420 Ba-142 3.59770E-02 4.57110E-02 561420 + 740 561430 Ba-143 2.30750E-02 2.70460E-02 561430 + 741 561440 Ba-144 1.55660E-02 1.63410E-02 561440 + 742 561450 Ba-145 5.15040E-03 5.28320E-03 561450 + 743 561460 Ba-146 1.90740E-03 1.91700E-03 561460 + 744 561470 Ba-147 3.02050E-04 3.02920E-04 561470 + 745 561480 Ba-148 5.81670E-05 5.81670E-05 561480 + 746 561490 Ba-149 3.97200E-06 3.97200E-06 561490 + 747 561500 Ba-150 3.70330E-09 3.70330E-09 561500 + 748 571370 La-137 6.63510E-09 6.63510E-09 571370 + 749 571380 La-138 2.70260E-07 2.70260E-07 57138.82c + 750 571390 La-139 4.81170E-05 5.52670E-02 57139.82c + 751 571400 La-140 2.45320E-04 5.08140E-02 57140.82c + 752 571410 La-141 1.38700E-03 5.14960E-02 571410 + 753 571420 La-142 2.82270E-03 4.85330E-02 571420 + 754 571430 La-143 8.72860E-03 3.57750E-02 571430 + 755 571440 La-144 1.12760E-02 2.76170E-02 571440 + 756 571450 La-145 1.42210E-02 1.95040E-02 571450 + 757 571460 La-146 2.45190E-03 4.36890E-03 571460 + 758 571461 La-146m 4.41040E-03 4.41040E-03 571461 + 759 571470 La-147 4.52480E-03 4.82800E-03 571470 + 760 571480 La-148 1.29020E-03 1.34810E-03 571480 + 761 571490 La-149 3.15270E-04 3.19230E-04 571490 + 762 571500 La-150 6.03010E-05 6.03050E-05 571500 + 763 571510 La-151 7.71800E-06 7.71800E-06 571510 + 764 571520 La-152 7.96580E-09 7.96580E-09 571520 + 765 571530 La-153 9.38940E-11 9.38940E-11 571530 + 766 581390 Ce-139 5.06540E-10 1.72940E-09 581390 + 767 581391 Ce-139m 1.22290E-09 1.22290E-09 581391 + 768 581400 Ce-140 3.72540E-06 5.08180E-02 58140.82c + 769 581410 Ce-141 3.64630E-05 5.15330E-02 58141.82c + 770 581420 Ce-142 1.74490E-04 4.87080E-02 58142.82c + 771 581430 Ce-143 6.21010E-04 3.63950E-02 58143.82c + 772 581440 Ce-144 2.53700E-03 3.01540E-02 58144.82c + 773 581450 Ce-145 5.73800E-03 2.52420E-02 581450 + 774 581460 Ce-146 9.84130E-03 1.86210E-02 581460 + 775 581470 Ce-147 8.69120E-03 1.35190E-02 581470 + 776 581480 Ce-148 9.90870E-03 1.12610E-02 581480 + 777 581490 Ce-149 4.22190E-03 4.53830E-03 581490 + 778 581500 Ce-150 2.56940E-03 2.62810E-03 581500 + 779 581510 Ce-151 4.98800E-04 5.06520E-04 581510 + 780 581520 Ce-152 1.14710E-04 1.14720E-04 581520 + 781 581530 Ce-153 8.61250E-06 8.61260E-06 581530 + 782 581540 Ce-154 2.14050E-08 2.14050E-08 581540 + 783 581550 Ce-155 2.58830E-10 2.58830E-10 581550 + 784 591420 Pr-142 1.33010E-09 4.44550E-09 59142.82c + 785 591421 Pr-142m 3.11540E-09 3.11540E-09 591421 + 786 591430 Pr-143 8.06060E-07 3.63960E-02 59143.82c + 787 591440 Pr-144 1.48340E-07 3.01550E-02 591440 + 788 591441 Pr-144m 1.31750E-06 4.17420E-04 591441 + 789 591450 Pr-145 5.91430E-05 2.53010E-02 591450 + 790 591460 Pr-146 2.63790E-04 1.88840E-02 591460 + 791 591470 Pr-147 7.46450E-04 1.42660E-02 591470 + 792 591480 Pr-148 2.93660E-04 1.15550E-02 591480 + 793 591481 Pr-148m 1.23500E-03 1.23500E-03 591481 + 794 591490 Pr-149 2.43360E-03 6.97190E-03 591490 + 795 591500 Pr-150 2.53020E-03 5.15830E-03 591500 + 796 591510 Pr-151 2.48130E-03 2.98780E-03 591510 + 797 591520 Pr-152 8.97340E-04 1.01210E-03 591520 + 798 591530 Pr-153 3.10540E-04 3.19100E-04 591530 + 799 591540 Pr-154 3.96930E-05 3.97140E-05 591540 + 800 591550 Pr-155 7.45980E-06 7.46010E-06 591550 + 801 591560 Pr-156 2.16350E-08 2.16350E-08 591560 + 802 591570 Pr-157 5.24640E-10 5.24640E-10 591570 + 803 591580 Pr-158 3.47080E-12 3.47080E-12 591580 + 804 601440 Nd-144 1.19430E-09 3.01550E-02 60144.82c + 805 601450 Nd-145 7.49400E-07 2.53020E-02 60145.82c + 806 601460 Nd-146 6.71280E-06 1.88910E-02 60146.82c + 807 601470 Nd-147 2.66790E-05 1.42920E-02 60147.82c + 808 601480 Nd-148 1.49810E-04 1.29400E-02 60148.82c + 809 601490 Nd-149 3.34200E-04 7.30610E-03 601490 + 810 601500 Nd-150 8.17120E-04 5.97540E-03 60150.82c + 811 601510 Nd-151 1.15340E-03 4.14120E-03 601510 + 812 601520 Nd-152 1.69540E-03 2.70750E-03 601520 + 813 601530 Nd-153 1.04170E-03 1.36080E-03 601530 + 814 601540 Nd-154 5.26180E-04 5.65890E-04 601540 + 815 601550 Nd-155 1.57520E-04 1.64980E-04 601550 + 816 601560 Nd-156 4.19350E-05 4.19560E-05 601560 + 817 601570 Nd-157 4.48920E-06 4.48970E-06 601570 + 818 601580 Nd-158 4.01560E-08 4.01600E-08 601580 + 819 601590 Nd-159 9.10010E-10 9.10010E-10 601590 + 820 601600 Nd-160 1.66550E-11 1.66550E-11 601600 + 821 611470 Pm-147 1.59540E-09 1.42920E-02 61147.82c + 822 611480 Pm-148 1.67130E-08 1.86700E-08 61148.82c + 823 611481 Pm-148m 3.91460E-08 3.91460E-08 61548.82c + 824 611490 Pm-149 5.67290E-07 7.30660E-03 61149.82c + 825 611500 Pm-150 9.21530E-06 9.21530E-06 611500 + 826 611510 Pm-151 4.72550E-05 4.18850E-03 61151.82c + 827 611520 Pm-152 2.01050E-05 2.72760E-03 611520 + 828 611521 Pm-152m 4.01480E-05 4.01480E-05 611521 + 829 611522 Pm-152m 4.44070E-05 4.44070E-05 611522 + 830 611530 Pm-153 2.28670E-04 1.58950E-03 611530 + 831 611540 Pm-154 1.14380E-04 6.80280E-04 611540 + 832 611541 Pm-154m 1.14380E-04 1.14380E-04 611541 + 833 611550 Pm-155 2.29760E-04 3.94740E-04 611550 + 834 611560 Pm-156 1.18400E-04 1.60360E-04 611560 + 835 611570 Pm-157 5.61490E-05 6.06390E-05 611570 + 836 611580 Pm-158 1.05760E-05 1.06160E-05 611580 + 837 611590 Pm-159 2.38460E-06 2.38550E-06 611590 + 838 611600 Pm-160 3.12150E-08 3.12310E-08 611600 + 839 611610 Pm-161 8.46850E-10 8.46850E-10 611610 + 840 611620 Pm-162 8.41870E-12 8.41870E-12 611620 + 841 621490 Sm-149 2.12530E-10 7.30660E-03 62149.82c + 842 621500 Sm-150 6.75330E-09 9.22200E-06 62150.82c + 843 621510 Sm-151 1.39220E-07 4.18860E-03 62151.82c + 844 621520 Sm-152 5.09960E-06 2.81730E-03 62152.82c + 845 621530 Sm-153 7.32660E-06 1.61450E-03 62153.82c + 846 621531 Sm-153m 1.76870E-05 1.76870E-05 621531 + 847 621540 Sm-154 5.30930E-05 8.47760E-04 62154.82c + 848 621550 Sm-155 9.28360E-05 4.87580E-04 621550 + 849 621560 Sm-156 1.22470E-04 2.82830E-04 621560 + 850 621570 Sm-157 9.41840E-05 1.54820E-04 621570 + 851 621580 Sm-158 5.13590E-05 6.19760E-05 621580 + 852 621590 Sm-159 2.54380E-05 2.78230E-05 621590 + 853 621600 Sm-160 1.23900E-05 1.24210E-05 621600 + 854 621610 Sm-161 8.30230E-07 8.31080E-07 621610 + 855 621620 Sm-162 2.06620E-08 2.06700E-08 621620 + 856 621630 Sm-163 1.03590E-09 1.03590E-09 621630 + 857 621640 Sm-164 1.43340E-11 1.43340E-11 621640 + 858 631520 Eu-152 1.17730E-10 2.49030E-10 63152.82c + 859 631521 Eu-152m 2.80390E-11 2.80390E-11 631521 + 860 631522 Eu-152m 1.31300E-10 1.31300E-10 631522 + 861 631530 Eu-153 9.24850E-09 1.61450E-03 63153.82c + 862 631540 Eu-154 3.50200E-07 6.65660E-07 63154.82c + 863 631541 Eu-154m 3.15460E-07 3.15460E-07 631541 + 864 631550 Eu-155 7.44660E-07 4.88320E-04 63155.82c + 865 631560 Eu-156 2.93900E-06 2.85760E-04 63156.82c + 866 631570 Eu-157 5.23580E-06 1.60060E-04 63157.82c + 867 631580 Eu-158 1.13260E-05 7.33020E-05 631580 + 868 631590 Eu-159 1.50990E-05 4.29220E-05 631590 + 869 631600 Eu-160 5.78100E-06 1.82020E-05 631600 + 870 631610 Eu-161 5.81170E-06 6.64280E-06 631610 + 871 631620 Eu-162 7.88540E-07 8.09210E-07 631620 + 872 631630 Eu-163 1.78730E-07 1.79770E-07 631630 + 873 631640 Eu-164 6.46170E-09 6.47600E-09 631640 + 874 631650 Eu-165 1.75790E-09 1.75790E-09 631650 + 875 631660 Eu-166 5.32020E-11 5.32020E-11 631660 + 876 631670 Eu-167 1.08150E-12 1.08150E-12 631670 + 877 641540 Gd-154 3.25300E-11 6.65560E-07 64154.82c + 878 641550 Gd-155 1.38250E-10 4.88320E-04 64155.82c + 879 641551 Gd-155m 3.33740E-10 3.33740E-10 641551 + 880 641560 Gd-156 1.18460E-08 2.85780E-04 64156.82c + 881 641570 Gd-157 1.06090E-07 1.60170E-04 64157.82c + 882 641580 Gd-158 1.51040E-06 7.48120E-05 64158.82c + 883 641590 Gd-159 1.58950E-06 4.45120E-05 641590 + 884 641600 Gd-160 7.43180E-06 2.56340E-05 64160.82c + 885 641610 Gd-161 2.49050E-06 9.13330E-06 641610 + 886 641620 Gd-162 2.36560E-06 3.17480E-06 641620 + 887 641630 Gd-163 7.90840E-07 9.70610E-07 641630 + 888 641640 Gd-164 5.71880E-07 5.78360E-07 641640 + 889 641650 Gd-165 1.86030E-07 1.87790E-07 641650 + 890 641660 Gd-166 3.27060E-08 3.27590E-08 641660 + 891 641670 Gd-167 1.77350E-09 1.77460E-09 641670 + 892 641680 Gd-168 8.88530E-11 8.88530E-11 641680 + 893 641690 Gd-169 2.00480E-12 2.00480E-12 641690 + 894 651570 Tb-157 1.82480E-11 1.82480E-11 651570 + 895 651580 Tb-158 3.08840E-10 3.43400E-10 651580 + 896 651581 Tb-158m 3.47730E-11 3.47730E-11 651581 + 897 651590 Tb-159 6.53730E-09 4.45180E-05 65159.82c + 898 651600 Tb-160 4.54100E-08 4.54100E-08 65160.82c + 899 651610 Tb-161 1.69860E-07 9.30310E-06 651610 + 900 651620 Tb-162 2.39500E-07 3.41430E-06 651620 + 901 651630 Tb-163 1.58160E-06 2.55220E-06 651630 + 902 651640 Tb-164 2.46270E-07 8.24630E-07 651640 + 903 651650 Tb-165 7.47710E-07 9.35500E-07 651650 + 904 651660 Tb-166 3.52960E-07 3.85720E-07 651660 + 905 651670 Tb-167 8.16220E-08 8.33970E-08 651670 + 906 651680 Tb-168 1.01800E-08 1.02690E-08 651680 + 907 651690 Tb-169 1.36470E-09 1.36670E-09 651690 + 908 651700 Tb-170 6.77790E-11 6.77790E-11 651700 + 909 651710 Tb-171 2.63140E-12 2.63140E-12 651710 + 910 661590 Dy-159 1.38720E-12 1.38720E-12 661590 + 911 661600 Dy-160 3.03700E-11 4.54400E-08 66160.82c + 912 661610 Dy-161 3.09100E-10 9.30340E-06 66161.82c + 913 661620 Dy-162 2.57110E-09 3.41690E-06 66162.82c + 914 661630 Dy-163 1.76880E-08 2.56990E-06 66163.82c + 915 661640 Dy-164 3.41500E-08 8.58810E-07 66164.82c + 916 661650 Dy-165 1.92320E-07 1.15660E-06 661650 + 917 661651 Dy-165m 2.94000E-08 2.94000E-08 661651 + 918 661660 Dy-166 3.52960E-07 7.38680E-07 661660 + 919 661670 Dy-167 2.22910E-07 3.06310E-07 661670 + 920 661680 Dy-168 1.32020E-07 1.42290E-07 661680 + 921 661690 Dy-169 3.97310E-08 4.10980E-08 661690 + 922 661700 Dy-170 1.08220E-08 1.08900E-08 661700 + 923 661710 Dy-171 1.07390E-09 1.07650E-09 661710 + 924 661720 Dy-172 9.04680E-11 9.04680E-11 661720 + 925 661730 Dy-173 3.54180E-12 3.54180E-12 661730 + 926 671630 Ho-163 1.16120E-11 1.33870E-11 671630 + 927 671631 Ho-163m 1.77510E-12 1.77510E-12 671631 + 928 671640 Ho-164 2.05130E-11 6.85580E-11 671640 + 929 671641 Ho-164m 4.80450E-11 4.80450E-11 671641 + 930 671650 Ho-165 2.56600E-09 1.15980E-06 67165.82c + 931 671660 Ho-166 3.20380E-09 7.41880E-07 671660 + 932 671661 Ho-166m 7.50420E-09 7.50420E-09 671661 + 933 671670 Ho-167 3.10650E-08 3.37370E-07 671670 + 934 671680 Ho-168 1.57510E-08 1.80280E-07 671680 + 935 671681 Ho-168m 2.23500E-08 2.23500E-08 671681 + 936 671690 Ho-169 5.20940E-08 9.31920E-08 671690 + 937 671700 Ho-170 2.02360E-08 2.02360E-08 671700 + 938 671701 Ho-170m 8.63970E-09 1.95290E-08 671701 + 939 671710 Ho-171 1.40790E-08 1.51550E-08 671710 + 940 671720 Ho-172 2.76430E-09 2.85480E-09 671720 + 941 671730 Ho-173 6.12240E-10 6.15780E-10 671730 + 942 671740 Ho-174 5.01680E-11 5.01680E-11 671740 + 943 671750 Ho-175 3.61070E-12 3.61070E-12 671750 + 944 681650 Er-165 1.13660E-12 1.13660E-12 681650 + 945 681660 Er-166 2.93900E-11 7.41910E-07 68166.82c + 946 681670 Er-167 1.92070E-10 3.37590E-07 68167.82c + 947 681671 Er-167m 2.93620E-11 4.03430E-08 681671 + 948 681680 Er-168 1.52240E-09 1.81910E-07 68168.82c + 949 681690 Er-169 4.79600E-09 9.79880E-08 681690 + 950 681700 Er-170 1.29180E-08 5.26840E-08 68170.82c + 951 681710 Er-171 1.27390E-08 2.78940E-08 681710 + 952 681720 Er-172 1.13890E-08 1.42440E-08 681720 + 953 681730 Er-173 5.27150E-09 5.88730E-09 681730 + 954 681740 Er-174 2.20350E-09 2.25370E-09 681740 + 955 681750 Er-175 3.82800E-10 3.86410E-10 681750 + 956 681760 Er-176 5.87250E-11 5.87250E-11 681760 + 957 681770 Er-177 3.63000E-12 3.63000E-12 681770 + 958 691690 Tm-169 1.45260E-11 9.80020E-08 691690 + 959 691700 Tm-170 9.92650E-11 9.92650E-11 691700 + 960 691710 Tm-171 5.31260E-10 2.84260E-08 691710 + 961 691720 Tm-172 1.05370E-09 1.52970E-08 691720 + 962 691730 Tm-173 2.29500E-09 8.18230E-09 691730 + 963 691740 Tm-174 1.91810E-09 4.17180E-09 691740 + 964 691750 Tm-175 1.54090E-09 1.92730E-09 691750 + 965 691760 Tm-176 5.11170E-10 5.69900E-10 691760 + 966 691770 Tm-177 1.67350E-10 1.70980E-10 691770 + 967 691780 Tm-178 2.08440E-11 2.08440E-11 691780 + 968 691790 Tm-179 2.79090E-12 2.79090E-12 691790 + 969 701720 Yb-172 1.13320E-11 1.53090E-08 701720 + 970 701730 Yb-173 6.08830E-11 8.24320E-09 701730 + 971 701740 Yb-174 2.66420E-10 4.43820E-09 701740 + 972 701750 Yb-175 3.96960E-10 2.38500E-09 701750 + 973 701751 Yb-175m 6.06830E-11 1.54470E-09 701751 + 974 701760 Yb-176 2.49300E-10 1.19430E-09 701760 + 975 701761 Yb-176m 4.48430E-10 7.33380E-10 701761 + 976 701770 Yb-177 3.71760E-10 6.28700E-10 701770 + 977 701771 Yb-177m 8.59600E-11 2.56940E-10 701771 + 978 701780 Yb-178 2.70770E-10 2.91610E-10 701780 + 979 701790 Yb-179 8.13950E-11 8.41860E-11 701790 + 980 701800 Yb-180 2.21510E-11 2.21510E-11 701800 + 981 701810 Yb-181 2.19610E-12 2.19610E-12 701810 + 982 711750 Lu-175 5.30570E-12 2.39030E-09 71175.82c + 983 711760 Lu-176 1.24160E-11 8.57540E-11 71176.82c + 984 711761 Lu-176m 6.90270E-12 6.90270E-12 711761 + 985 711770 Lu-177 4.55170E-11 6.78300E-10 711770 + 986 711771 Lu-177m 1.77940E-11 1.80810E-11 711771 + 987 711780 Lu-178 3.66790E-11 3.28290E-10 711780 + 988 711781 Lu-178m 4.15790E-11 4.15790E-11 711781 + 989 711790 Lu-179 9.27080E-11 1.91070E-10 711790 + 990 711791 Lu-179m 1.41720E-11 9.83580E-11 711791 + 991 711800 Lu-180 1.70420E-11 4.91970E-11 711800 + 992 711801 Lu-180m 1.70420E-11 3.91930E-11 711801 + 993 711802 Lu-180m 2.51160E-11 2.51160E-11 711802 + 994 711810 Lu-181 2.88390E-11 3.10350E-11 711810 + 995 711820 Lu-182 5.65790E-12 5.65790E-12 711820 + 996 711830 Lu-183 1.25240E-12 1.25240E-12 711830 + 997 721780 Hf-178 1.11920E-12 3.73000E-10 72178.82c + 998 721781 Hf-178m 1.84660E-12 4.35920E-11 721781 + 999 721790 Hf-179 5.92970E-12 2.00920E-10 72179.82c + 1000 721791 Hf-179m 1.85100E-12 1.85100E-12 721791 + 1001 721792 Hf-179m 2.07580E-12 2.07580E-12 721792 + 1002 721800 Hf-180 9.47630E-12 1.07780E-10 72180.82c + 1003 721801 Hf-180m 1.70460E-11 2.96040E-11 721801 + 1004 721810 Hf-181 2.61330E-11 5.71680E-11 721810 + 1005 721820 Hf-182 8.34150E-12 2.03010E-11 721820 + 1006 721821 Hf-182m 1.50040E-11 1.50040E-11 721821 + 1007 721830 Hf-183 1.08010E-11 1.20530E-11 721830 + 1008 721840 Hf-184 1.61240E-12 1.61240E-12 721840 + 1009 721841 Hf-184m 2.90020E-12 2.90020E-12 721841 + 1010 731810 Ta-181 1.09170E-12 5.82600E-11 73181.82c + 1011 731820 Ta-182 7.72980E-13 1.08660E-11 73182.82c + 1012 731821 Ta-182m 7.88990E-13 1.00930E-11 731821 + 1013 731822 Ta-182m 6.01430E-13 9.30400E-12 731822 + 1014 731830 Ta-183 4.70930E-12 1.67630E-11 731830 + 1015 731840 Ta-184 3.93380E-12 8.44640E-12 731840 + 1016 731850 Ta-185 2.12740E-12 3.15780E-12 731850 + 1017 731851 Ta-185m 1.03040E-12 1.03040E-12 731851 + 1018 731860 Ta-186 1.04680E-12 1.04680E-12 731860 + 1019 741860 W-186 1.08200E-12 2.47780E-12 74186.82c + + Neutron-induced fission: + + Interpolation region : 2 / 2 + Interpolation energy : 4.00000E-01 MeV + Number of products : 985 / 1051 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 3.82810E-05 3.82810E-05 1001.82c + 2 10020 H-2 1.16990E-05 1.16990E-05 1002.82c + 3 10030 H-3 1.44000E-04 1.44000E-04 1003.82c + 4 20040 He-4 2.42000E-03 2.42000E-03 2004.82c + 5 210530 Sc-53 1.52800E-12 1.52800E-12 210530 + 6 210540 Sc-54 1.00410E-12 1.00410E-12 210540 + 7 220530 Ti-53 1.63540E-12 3.16340E-12 220530 + 8 220540 Ti-54 5.00110E-12 6.00520E-12 220540 + 9 220550 Ti-55 7.90490E-12 7.90490E-12 220550 + 10 220560 Ti-56 1.12670E-11 1.12670E-11 220560 + 11 220570 Ti-57 6.30210E-12 6.30210E-12 220570 + 12 220580 Ti-58 3.08300E-12 3.08300E-12 220580 + 13 230550 V-55 4.26700E-12 1.21720E-11 230550 + 14 230560 V-56 1.22190E-11 2.35050E-11 230560 + 15 230570 V-57 3.24920E-11 3.87750E-11 230570 + 16 230580 V-58 3.51430E-11 3.82260E-11 230580 + 17 230590 V-59 3.87490E-11 3.87490E-11 230590 + 18 230600 V-60 1.58100E-11 1.58100E-11 230600 + 19 230610 V-61 6.62330E-12 6.62330E-12 230610 + 20 230620 V-62 1.01050E-12 1.01050E-12 230620 + 21 240560 Cr-56 2.13150E-12 2.57910E-11 240560 + 22 240570 Cr-57 1.20300E-11 8.12310E-11 240570 + 23 240580 Cr-58 6.04950E-11 6.81400E-11 240580 + 24 240590 Cr-59 1.35130E-10 1.73880E-10 240590 + 25 240600 Cr-60 2.70820E-10 2.87030E-10 240600 + 26 240610 Cr-61 2.61240E-10 2.67470E-10 240610 + 27 240620 Cr-62 2.26690E-10 2.27700E-10 240620 + 28 240630 Cr-63 7.08720E-11 7.08720E-11 240630 + 29 240640 Cr-64 1.84750E-11 1.84750E-11 240640 + 30 240650 Cr-65 2.22560E-12 2.22560E-12 240650 + 31 250580 Mn-58 2.00010E-12 7.01400E-11 250580 + 32 250590 Mn-59 2.47920E-11 1.98670E-10 250590 + 33 250600 Mn-60 9.14960E-12 3.06880E-10 250600 + 34 250601 Mn-60m 9.30800E-11 9.30800E-11 250601 + 35 250610 Mn-61 4.55840E-10 7.23310E-10 250610 + 36 250620 Mn-62 7.08810E-10 8.22660E-10 250620 + 37 250621 Mn-62m 1.11000E-10 2.24850E-10 250621 + 38 250630 Mn-63 1.30880E-09 1.37970E-09 250630 + 39 250640 Mn-64 8.17000E-10 8.35470E-10 250640 + 40 250650 Mn-65 5.77320E-10 5.79550E-10 250650 + 41 250660 Mn-66 1.48370E-10 1.48370E-10 250660 + 42 250670 Mn-67 3.14450E-11 3.14450E-11 250670 + 43 250680 Mn-68 2.39410E-12 2.39410E-12 250680 + 44 260600 Fe-60 5.49960E-12 3.94760E-10 260600 + 45 260610 Fe-61 5.58620E-11 7.79170E-10 260610 + 46 260620 Fe-62 4.88800E-10 1.53630E-09 260620 + 47 260630 Fe-63 1.57510E-09 2.95480E-09 260630 + 48 260640 Fe-64 4.59010E-09 5.42560E-09 260640 + 49 260650 Fe-65 6.95060E-09 7.53020E-09 260650 + 50 260660 Fe-66 9.50090E-09 9.64930E-09 260660 + 51 260670 Fe-67 4.99460E-09 5.02610E-09 260670 + 52 260680 Fe-68 2.28780E-09 2.29020E-09 260680 + 53 260690 Fe-69 4.38240E-10 4.38240E-10 260690 + 54 260700 Fe-70 6.69090E-11 6.69090E-11 260700 + 55 260710 Fe-71 3.53600E-12 3.53600E-12 260710 + 56 270620 Co-62 1.41980E-12 1.53780E-09 270620 + 57 270621 Co-62m 3.87020E-12 3.87020E-12 270621 + 58 270630 Co-63 9.26080E-11 3.04740E-09 270630 + 59 270640 Co-64 5.90370E-10 6.01590E-09 270640 + 60 270650 Co-65 4.22090E-09 1.17510E-08 270650 + 61 270660 Co-66 1.15960E-08 2.12450E-08 270660 + 62 270670 Co-67 2.91510E-08 3.41770E-08 270670 + 63 270680 Co-68 1.70410E-08 2.45620E-08 270680 + 64 270681 Co-68m 1.27200E-08 1.50410E-08 270681 + 65 270690 Co-69 3.15220E-08 3.19300E-08 270690 + 66 270700 Co-70 6.15200E-09 6.15200E-09 270700 + 67 270701 Co-70m 6.15200E-09 6.21890E-09 270701 + 68 270710 Co-71 3.99400E-09 3.99750E-09 270710 + 69 270720 Co-72 9.41660E-10 9.41660E-10 270720 + 70 270730 Co-73 1.93520E-11 1.93520E-11 270730 + 71 280640 Ni-64 9.17260E-12 6.02510E-09 28064.82c + 72 280650 Ni-65 1.60120E-10 1.19110E-08 280650 + 73 280660 Ni-66 2.29590E-09 2.35410E-08 280660 + 74 280670 Ni-67 1.21650E-08 4.63420E-08 280670 + 75 280680 Ni-68 5.76050E-08 9.00060E-08 280680 + 76 280690 Ni-69 6.20200E-08 9.36300E-08 280690 + 77 280691 Ni-69m 6.20200E-08 6.20200E-08 280691 + 78 280700 Ni-70 2.39590E-07 2.51960E-07 280700 + 79 280710 Ni-71 5.94190E-07 5.98190E-07 280710 + 80 280720 Ni-72 6.67930E-07 6.68870E-07 280720 + 81 280730 Ni-73 1.31310E-08 1.31500E-08 280730 + 82 280740 Ni-74 2.09620E-09 2.09620E-09 280740 + 83 280750 Ni-75 1.76930E-09 1.76930E-09 280750 + 84 280760 Ni-76 1.35330E-10 1.35330E-10 280760 + 85 280770 Ni-77 3.88190E-12 3.88190E-12 280770 + 86 290660 Cu-66 6.98000E-12 2.35480E-08 290660 + 87 290670 Cu-67 2.13970E-10 4.65560E-08 290670 + 88 290680 Cu-68 6.39680E-10 9.21100E-08 290680 + 89 290681 Cu-68m 1.74360E-09 1.74360E-09 290681 + 90 290690 Cu-69 2.57250E-08 1.81370E-07 290690 + 91 290700 Cu-70 6.88710E-09 5.73360E-08 290700 + 92 290701 Cu-70m 8.79560E-08 1.00900E-07 290701 + 93 290702 Cu-70m 6.88710E-09 2.58850E-07 290702 + 94 290710 Cu-71 3.54610E-07 9.52800E-07 290710 + 95 290720 Cu-72 9.97930E-07 1.66680E-06 290720 + 96 290730 Cu-73 2.76860E-07 2.90010E-07 290730 + 97 290740 Cu-74 1.06620E-07 1.08740E-07 290740 + 98 290750 Cu-75 1.98600E-06 1.98770E-06 290750 + 99 290760 Cu-76 5.42300E-08 5.42980E-08 290760 + 100 290761 Cu-76m 5.42300E-08 5.42980E-08 290761 + 101 290770 Cu-77 2.09030E-08 2.09070E-08 290770 + 102 290780 Cu-78 2.13800E-09 2.13800E-09 290780 + 103 290790 Cu-79 1.00190E-10 1.00190E-10 290790 + 104 300680 Zn-68 1.01580E-11 9.24000E-08 300680 + 105 300690 Zn-69 4.73970E-11 1.81660E-07 300690 + 106 300691 Zn-69m 2.35400E-10 2.35400E-10 300691 + 107 300700 Zn-70 6.25970E-09 3.59950E-07 300700 + 108 300710 Zn-71 8.26250E-09 9.61060E-07 300710 + 109 300711 Zn-71m 4.10360E-08 4.10360E-08 300711 + 110 300720 Zn-72 1.33580E-06 3.00260E-06 300720 + 111 300730 Zn-73 6.02480E-08 7.05320E-07 300730 + 112 300731 Zn-73m 8.33310E-08 3.55070E-07 300731 + 113 300732 Zn-73m 5.43470E-07 5.43470E-07 300732 + 114 300740 Zn-74 7.93350E-07 9.71670E-07 300740 + 115 300750 Zn-75 5.95810E-06 7.87790E-06 300750 + 116 300760 Zn-76 1.31770E-05 1.32840E-05 300760 + 117 300770 Zn-77 1.79720E-06 1.93780E-06 300770 + 118 300771 Zn-77m 2.39290E-07 2.39290E-07 300771 + 119 300780 Zn-78 3.15220E-06 3.15440E-06 300780 + 120 300790 Zn-79 2.99150E-07 2.99200E-07 300790 + 121 300800 Zn-80 5.24980E-08 5.24980E-08 300800 + 122 300810 Zn-81 2.08390E-09 2.08390E-09 300810 + 123 300820 Zn-82 1.24470E-10 1.24470E-10 300820 + 124 310700 Ga-70 5.11320E-12 5.11320E-12 310700 + 125 310710 Ga-71 2.44290E-10 1.00230E-06 310710 + 126 310720 Ga-72 7.58380E-09 3.01090E-06 310720 + 127 310721 Ga-72m 7.45470E-10 1.00790E-07 310721 + 128 310730 Ga-73 2.50880E-08 1.00220E-06 310730 + 129 310740 Ga-74 4.91350E-08 8.14730E-07 310740 + 130 310741 Ga-74m 4.91350E-08 1.02080E-06 310741 + 131 310750 Ga-75 4.96490E-06 1.28430E-05 310750 + 132 310760 Ga-76 7.09480E-06 2.03790E-05 310760 + 133 310770 Ga-77 1.83300E-05 2.03870E-05 310770 + 134 310780 Ga-78 1.99660E-05 2.31240E-05 310780 + 135 310790 Ga-79 2.90890E-05 2.93840E-05 310790 + 136 310800 Ga-80 8.57100E-06 8.62370E-06 310800 + 137 310810 Ga-81 6.32440E-06 6.32630E-06 310810 + 138 310820 Ga-82 3.81630E-07 3.81750E-07 310820 + 139 310830 Ga-83 3.81560E-08 3.81560E-08 310830 + 140 310840 Ga-84 1.49170E-09 1.49170E-09 310840 + 141 320720 Ge-72 9.40780E-12 3.01090E-06 32072.82c + 142 320730 Ge-73 6.31330E-11 1.00220E-06 32073.82c + 143 320731 Ge-73m 1.27120E-11 9.87450E-07 320731 + 144 320740 Ge-74 1.75810E-09 1.07170E-06 32074.82c + 145 320750 Ge-75 2.52910E-08 1.30580E-05 320750 + 146 320751 Ge-75m 1.89950E-07 7.03660E-07 320751 + 147 320760 Ge-76 2.02710E-06 2.24060E-05 32076.82c + 148 320770 Ge-77 1.88700E-05 2.32210E-05 320770 + 149 320771 Ge-77m 2.51240E-06 2.29000E-05 320771 + 150 320780 Ge-78 8.19550E-05 1.05110E-04 320780 + 151 320790 Ge-79 1.29370E-05 4.61390E-05 320790 + 152 320791 Ge-79m 9.71630E-05 9.72070E-05 320791 + 153 320800 Ge-80 2.39170E-04 2.48550E-04 320800 + 154 320810 Ge-81 1.28650E-04 1.31920E-04 320810 + 155 320811 Ge-81m 2.59030E-05 2.85730E-05 320811 + 156 320820 Ge-82 1.54940E-04 1.55260E-04 320820 + 157 320830 Ge-83 4.49510E-05 4.49760E-05 320830 + 158 320840 Ge-84 1.25170E-05 1.25170E-05 320840 + 159 320850 Ge-85 4.71000E-07 4.71000E-07 320850 + 160 320860 Ge-86 2.98230E-08 2.98230E-08 320860 + 161 320870 Ge-87 6.66020E-10 6.66020E-10 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7.64680E-03 7.75280E-03 401020 + 320 401030 Zr-103 1.78390E-03 1.80280E-03 401030 + 321 401040 Zr-104 3.85810E-04 3.85820E-04 401040 + 322 401050 Zr-105 3.02790E-05 3.02790E-05 401050 + 323 401060 Zr-106 3.87290E-06 3.87290E-06 401060 + 324 401070 Zr-107 5.64680E-10 5.64680E-10 401070 + 325 410930 Nb-93 1.12370E-09 1.34990E-09 41093.82c + 326 410931 Nb-93m 2.26240E-10 2.26240E-10 410931 + 327 410940 Nb-94 3.77030E-08 6.01350E-08 41094.82c + 328 410941 Nb-94m 2.25450E-08 2.25450E-08 410941 + 329 410950 Nb-95 2.15330E-05 5.60800E-02 41095.82c + 330 410951 Nb-95m 4.33560E-06 6.10280E-04 410951 + 331 410960 Nb-96 1.60200E-04 1.60200E-04 410960 + 332 410970 Nb-97 9.60420E-04 6.34170E-02 410970 + 333 410971 Nb-97m 1.93380E-04 5.93740E-02 410971 + 334 410980 Nb-98 8.56810E-04 6.75830E-02 410980 + 335 410981 Nb-98m 2.98540E-03 2.98540E-03 410981 + 336 410990 Nb-99 1.16570E-02 4.55930E-02 410990 + 337 410991 Nb-99m 2.34710E-03 2.18530E-02 410991 + 338 411000 Nb-100 4.06070E-03 4.35910E-02 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421030 Mo-103 3.15410E-02 5.20850E-02 421030 + 359 421040 Mo-104 3.27170E-02 4.06840E-02 421040 + 360 421050 Mo-105 1.70670E-02 1.98280E-02 421050 + 361 421060 Mo-106 8.93540E-03 9.42650E-03 421060 + 362 421070 Mo-107 2.41970E-03 2.48860E-03 421070 + 363 421080 Mo-108 5.97140E-04 6.01560E-04 421080 + 364 421090 Mo-109 6.90050E-05 6.90060E-05 421090 + 365 421100 Mo-110 7.30110E-06 7.30110E-06 421100 + 366 421110 Mo-111 1.22780E-09 1.22780E-09 421110 + 367 421120 Mo-112 1.45870E-11 1.45870E-11 421120 + 368 430980 Tc-98 1.59730E-09 1.59730E-09 430980 + 369 430990 Tc-99 2.50450E-06 6.80850E-02 43099.82c + 370 430991 Tc-99m 5.04280E-07 5.99550E-02 430991 + 371 431000 Tc-100 2.97060E-05 2.97060E-05 431000 + 372 431010 Tc-101 2.37610E-04 6.57700E-02 431010 + 373 431020 Tc-102 5.31600E-04 6.31620E-02 431020 + 374 431021 Tc-102m 5.31600E-04 5.31600E-04 431021 + 375 431030 Tc-103 4.08560E-03 5.61710E-02 431030 + 376 431040 Tc-104 8.02640E-03 4.87100E-02 431040 + 377 431050 Tc-105 1.44340E-02 3.42620E-02 431050 + 378 431060 Tc-106 1.26040E-02 2.20310E-02 431060 + 379 431070 Tc-107 1.00960E-02 1.25850E-02 431070 + 380 431080 Tc-108 4.14350E-03 4.74540E-03 431080 + 381 431090 Tc-109 1.51150E-03 1.58010E-03 431090 + 382 431100 Tc-110 2.89140E-04 2.96440E-04 431100 + 383 431110 Tc-111 7.71160E-05 7.71170E-05 431110 + 384 431120 Tc-112 4.74220E-06 4.74220E-06 431120 + 385 431130 Tc-113 1.09370E-09 1.09370E-09 431130 + 386 431140 Tc-114 1.17280E-11 1.17280E-11 431140 + 387 441010 Ru-101 9.90650E-07 6.57710E-02 44101.82c + 388 441020 Ru-102 1.94590E-05 6.37130E-02 44102.82c + 389 441030 Ru-103 3.50640E-05 5.63040E-02 44103.82c + 390 441031 Ru-103m 9.81060E-05 9.81060E-05 441031 + 391 441040 Ru-104 7.53950E-04 4.94640E-02 44104.82c + 392 441050 Ru-105 1.99990E-03 3.62620E-02 44105.82c + 393 441060 Ru-106 4.69240E-03 2.67230E-02 44106.82c + 394 441070 Ru-107 5.42680E-03 1.80110E-02 441070 + 395 441080 Ru-108 5.77510E-03 1.05220E-02 441080 + 396 441090 Ru-109 2.96580E-03 4.54480E-03 441090 + 397 441100 Ru-110 1.46620E-03 1.76250E-03 441100 + 398 441110 Ru-111 4.08750E-04 4.85940E-04 441110 + 399 441120 Ru-112 1.22070E-04 1.26740E-04 441120 + 400 441130 Ru-113 6.65250E-06 9.97980E-06 441130 + 401 441131 Ru-113m 6.65250E-06 6.65250E-06 441131 + 402 441140 Ru-114 2.88070E-06 2.88070E-06 441140 + 403 441150 Ru-115 9.42680E-07 9.42680E-07 441150 + 404 441160 Ru-116 1.15000E-10 1.15000E-10 441160 + 405 441170 Ru-117 2.48170E-12 2.48170E-12 441170 + 406 441200 Ru-120 6.37420E-11 6.37420E-11 441200 + 407 451030 Rh-103 1.88830E-10 5.63040E-02 45103.82c + 408 451031 Rh-103m 1.41830E-09 5.56300E-02 451031 + 409 451040 Rh-104 2.19480E-07 9.83230E-07 451040 + 410 451041 Rh-104m 7.64740E-07 7.64740E-07 451041 + 411 451050 Rh-105 1.63710E-05 3.62810E-02 45105.82c + 412 451051 Rh-105m 2.17970E-06 1.02960E-02 451051 + 413 451060 Rh-106 2.04520E-05 2.67430E-02 451060 + 414 451061 Rh-106m 5.57470E-05 5.57470E-05 451061 + 415 451070 Rh-107 2.65210E-04 1.82770E-02 451070 + 416 451080 Rh-108 9.96320E-05 1.06210E-02 451080 + 417 451081 Rh-108m 3.47150E-04 3.47150E-04 451081 + 418 451090 Rh-109 6.55410E-04 5.20020E-03 451090 + 419 451100 Rh-110 5.84020E-04 2.34650E-03 451100 + 420 451101 Rh-110m 1.37490E-05 1.37490E-05 451101 + 421 451110 Rh-111 4.34070E-04 9.20010E-04 451110 + 422 451120 Rh-112 8.92800E-05 2.16020E-04 451120 + 423 451121 Rh-112m 8.92800E-05 8.92800E-05 451121 + 424 451130 Rh-113 9.01920E-05 1.03500E-04 451130 + 425 451140 Rh-114 1.63230E-05 1.92060E-05 451140 + 426 451141 Rh-114m 1.63230E-05 1.63230E-05 451141 + 427 451150 Rh-115 1.41410E-05 1.50810E-05 451150 + 428 451160 Rh-116 7.82010E-07 7.82120E-07 451160 + 429 451161 Rh-116m 2.13160E-06 2.13160E-06 451161 + 430 451170 Rh-117 1.18690E-08 1.18710E-08 451170 + 431 451180 Rh-118 3.29730E-10 3.29730E-10 451180 + 432 451190 Rh-119 9.46880E-12 9.46880E-12 451190 + 433 451200 Rh-120 1.13300E-07 1.13360E-07 451200 + 434 451210 Rh-121 7.28730E-09 7.28730E-09 451210 + 435 451220 Rh-122 2.56790E-10 2.56790E-10 451220 + 436 461060 Pd-106 1.13300E-08 2.67990E-02 46106.82c + 437 461070 Pd-107 9.01700E-07 1.82800E-02 46107.82c + 438 461071 Pd-107m 1.98190E-06 1.98190E-06 461071 + 439 461080 Pd-108 1.13080E-05 1.09800E-02 46108.82c + 440 461090 Pd-109 1.20600E-05 5.23880E-03 461090 + 441 461091 Pd-109m 2.65060E-05 2.62660E-03 461091 + 442 461100 Pd-110 6.54530E-05 2.42570E-03 46110.82c + 443 461110 Pd-111 2.13680E-05 9.74670E-04 461110 + 444 461111 Pd-111m 4.69650E-05 5.06450E-05 461111 + 445 461120 Pd-112 7.47510E-05 3.80050E-04 461120 + 446 461130 Pd-113 1.47420E-05 1.59490E-04 461130 + 447 461131 Pd-113m 4.12490E-05 4.12490E-05 461131 + 448 461140 Pd-114 6.33460E-05 9.88750E-05 461140 + 449 461150 Pd-115 1.65070E-05 3.24770E-05 461150 + 450 461151 Pd-115m 3.62820E-05 3.84720E-05 461151 + 451 461160 Pd-116 5.82800E-05 6.11940E-05 461160 + 452 461170 Pd-117 4.52540E-06 1.44840E-05 461170 + 453 461171 Pd-117m 9.94660E-06 9.94660E-06 461171 + 454 461180 Pd-118 7.32820E-06 7.32850E-06 461180 + 455 461190 Pd-119 1.01990E-06 1.02660E-06 461190 + 456 461200 Pd-120 2.04400E-06 2.15160E-06 461200 + 457 461210 Pd-121 1.02120E-06 1.02750E-06 461210 + 458 461220 Pd-122 6.11380E-07 6.11640E-07 461220 + 459 461230 Pd-123 5.56060E-08 5.56060E-08 461230 + 460 461240 Pd-124 6.68680E-09 6.68680E-09 461240 + 461 471080 Ag-108 1.34640E-10 1.66570E-10 471080 + 462 471081 Ag-108m 3.67010E-10 3.67010E-10 471081 + 463 471090 Ag-109 1.43880E-09 5.23880E-03 47109.82c + 464 471091 Ag-109m 1.08060E-08 5.23620E-03 471091 + 465 471100 Ag-110 2.44940E-07 2.54020E-07 471100 + 466 471101 Ag-110m 6.67640E-07 6.67640E-07 47510.82c + 467 471110 Ag-111 2.20570E-07 9.85320E-04 47111.82c + 468 471111 Ag-111m 1.65660E-06 9.79180E-04 471111 + 469 471120 Ag-112 1.89640E-06 3.81950E-04 471120 + 470 471130 Ag-113 6.69360E-07 1.08400E-04 471130 + 471 471131 Ag-113m 5.02730E-06 1.57750E-04 471131 + 472 471140 Ag-114 3.28340E-07 1.00790E-04 471140 + 473 471141 Ag-114m 1.59180E-06 1.59180E-06 471141 + 474 471150 Ag-115 2.43640E-06 3.92610E-05 471150 + 475 471151 Ag-115m 1.82990E-05 6.24610E-05 471151 + 476 471160 Ag-116 7.03690E-06 6.93810E-05 471160 + 477 471161 Ag-116m 1.91810E-05 1.91810E-05 471161 + 478 471170 Ag-117 6.12090E-06 1.65560E-05 471170 + 479 471171 Ag-117m 4.59720E-05 5.32140E-05 471171 + 480 471180 Ag-118 6.73570E-06 2.68340E-05 471180 + 481 471181 Ag-118m 3.26540E-05 3.37020E-05 471181 + 482 471190 Ag-119 4.91400E-06 5.42730E-06 471190 + 483 471191 Ag-119m 3.69070E-05 3.74200E-05 471191 + 484 471200 Ag-120 7.26700E-06 1.32400E-05 471200 + 485 471201 Ag-120m 1.21530E-05 1.32290E-05 471201 + 486 471210 Ag-121 2.04220E-06 3.06690E-06 471210 + 487 471220 Ag-122 4.90630E-07 1.10230E-06 471220 + 488 471221 Ag-122m 5.28970E-07 5.28970E-07 471221 + 489 471230 Ag-123 5.12650E-06 5.18210E-06 471230 + 490 471240 Ag-124 1.96790E-06 3.03540E-06 471240 + 491 471241 Ag-124m 2.12160E-06 2.12160E-06 471241 + 492 471250 Ag-125 1.07400E-06 1.07400E-06 471250 + 493 471260 Ag-126 1.09880E-06 1.09880E-06 471260 + 494 471270 Ag-127 1.39590E-08 1.39590E-08 471270 + 495 471280 Ag-128 4.14500E-10 4.14500E-10 471280 + 496 481110 Cd-111 8.33550E-11 9.90220E-04 48111.82c + 497 481111 Cd-111m 3.15670E-10 3.15670E-10 481111 + 498 481120 Cd-112 7.95000E-09 3.81960E-04 48112.82c + 499 481130 Cd-113 1.32560E-08 1.63330E-04 48113.82c + 500 481131 Cd-113m 5.01980E-08 1.92420E-06 481131 + 501 481140 Cd-114 6.11420E-07 1.01410E-04 48114.82c + 502 481150 Cd-115 6.69060E-07 8.55760E-05 481150 + 503 481151 Cd-115m 2.53370E-06 6.23270E-06 48515.82c + 504 481160 Cd-116 3.88450E-06 9.12960E-05 48116.82c + 505 481170 Cd-117 2.82100E-06 5.42050E-05 481170 + 506 481171 Cd-117m 1.06830E-05 2.58760E-05 481171 + 507 481180 Cd-118 2.74750E-05 7.41930E-05 481180 + 508 481190 Cd-119 1.02030E-05 5.03370E-05 481190 + 509 481191 Cd-119m 2.85470E-05 3.12610E-05 481191 + 510 481200 Cd-120 5.72260E-05 7.88000E-05 481200 + 511 481210 Cd-121 1.10250E-05 1.37710E-05 481210 + 512 481211 Cd-121m 3.08460E-05 3.11670E-05 481211 + 513 481220 Cd-122 4.89570E-05 5.05880E-05 481220 + 514 481230 Cd-123 1.13430E-05 1.55850E-05 481230 + 515 481231 Cd-123m 3.17380E-05 3.26820E-05 481231 + 516 481240 Cd-124 6.96170E-05 7.37100E-05 481240 + 517 481250 Cd-125 2.41660E-05 2.47030E-05 481250 + 518 481251 Cd-125m 6.76140E-05 6.81510E-05 481251 + 519 481260 Cd-126 7.71330E-05 7.82320E-05 481260 + 520 481270 Cd-127 4.00950E-05 4.01090E-05 481270 + 521 481280 Cd-128 1.25890E-05 1.25890E-05 481280 + 522 481290 Cd-129 5.44580E-07 5.44580E-07 481290 + 523 481291 Cd-129m 1.52370E-06 1.52370E-06 481291 + 524 481300 Cd-130 1.55460E-08 1.55460E-08 481300 + 525 491130 In-113 7.88220E-12 1.92160E-06 49113.82c + 526 491131 In-113m 1.58700E-12 1.58700E-12 491131 + 527 491140 In-114 5.28290E-11 2.30460E-10 491140 + 528 491141 In-114m 8.53080E-11 1.84070E-10 491141 + 529 491142 In-114m 9.87640E-11 9.87640E-11 491142 + 530 491150 In-115 6.41060E-09 8.75370E-05 49115.82c + 531 491151 In-115m 1.29070E-09 8.55780E-05 491151 + 532 491160 In-116 2.41240E-08 2.41240E-08 491160 + 533 491161 In-116m 3.89560E-08 8.40560E-08 491161 + 534 491162 In-116m 4.51000E-08 4.51000E-08 491162 + 535 491170 In-117 9.27790E-07 5.46100E-05 491170 + 536 491171 In-117m 1.86810E-07 5.02560E-05 491171 + 537 491180 In-118 1.03160E-06 7.52250E-05 491180 + 538 491181 In-118m 1.66590E-06 3.56750E-06 491181 + 539 491182 In-118m 1.92860E-06 1.92860E-06 491182 + 540 491190 In-119 8.48970E-07 3.94940E-05 491190 + 541 491191 In-119m 1.70930E-07 4.56820E-05 491191 + 542 491200 In-120 3.06550E-06 8.18650E-05 491200 + 543 491201 In-120m 3.06550E-06 3.06550E-06 491201 + 544 491202 In-120m 3.06550E-06 3.06550E-06 491202 + 545 491210 In-121 2.29460E-05 5.89160E-05 491210 + 546 491211 In-121m 4.62010E-06 1.37530E-05 491211 + 547 491220 In-122 1.25900E-05 6.31790E-05 491220 + 548 491221 In-122m 1.05280E-05 1.05280E-05 491221 + 549 491222 In-122m 1.05280E-05 1.05280E-05 491222 + 550 491230 In-123 4.69480E-05 8.40580E-05 491230 + 551 491231 In-123m 9.45280E-06 2.06090E-05 491231 + 552 491240 In-124 5.17290E-05 1.25440E-04 491240 + 553 491241 In-124m 5.57710E-05 5.57710E-05 491241 + 554 491250 In-125 3.11240E-04 3.91220E-04 491250 + 555 491251 In-125m 6.26670E-05 7.55460E-05 491251 + 556 491260 In-126 2.98490E-04 3.76720E-04 491260 + 557 491261 In-126m 3.21810E-04 3.21810E-04 491261 + 558 491270 In-127 8.57540E-04 8.57540E-04 491270 + 559 491271 In-127m 1.72660E-04 2.12770E-04 491271 + 560 491280 In-128 2.15030E-04 3.11810E-04 491280 + 561 491281 In-128m 8.41940E-05 9.67840E-05 491281 + 562 491282 In-128m 3.22600E-04 3.22600E-04 491282 + 563 491290 In-129 2.89710E-04 2.91230E-04 491290 + 564 491291 In-129m 5.83320E-05 5.88760E-05 491291 + 565 491300 In-130 2.50450E-05 2.50600E-05 491300 + 566 491301 In-130m 3.64670E-05 3.64670E-05 491301 + 567 491302 In-130m 5.07980E-05 5.07980E-05 491302 + 568 491310 In-131 5.77840E-06 5.83720E-06 491310 + 569 491311 In-131m 5.77840E-06 5.77840E-06 491311 + 570 491312 In-131m 5.77840E-06 5.77840E-06 491312 + 571 491320 In-132 1.24540E-07 1.24540E-07 491320 + 572 491330 In-133 2.67230E-09 3.21040E-09 491330 + 573 491331 In-133m 5.38060E-10 5.38060E-10 491331 + 574 501160 Sn-116 5.92390E-11 1.08240E-07 50116.82c + 575 501170 Sn-117 3.38000E-10 8.11970E-05 50117.82c + 576 501171 Sn-117m 1.28000E-09 1.87340E-07 501171 + 577 501180 Sn-118 4.07180E-08 7.88600E-05 50118.82c + 578 501190 Sn-119 9.57120E-08 8.30760E-05 50119.82c + 579 501191 Sn-119m 3.62460E-07 3.60410E-05 501191 + 580 501200 Sn-120 9.72870E-11 8.79960E-05 50120.82c + 581 501210 Sn-121 2.68860E-07 7.18620E-05 501210 + 582 501211 Sn-121m 7.52240E-07 7.42650E-06 501211 + 583 501220 Sn-122 6.11530E-06 9.03500E-05 50122.82c + 584 501230 Sn-123 1.20740E-05 1.84830E-05 50123.82c + 585 501231 Sn-123m 4.31520E-06 1.02570E-04 501231 + 586 501240 Sn-124 7.03150E-05 2.51530E-04 50124.82c + 587 501250 Sn-125 1.55380E-04 2.21470E-04 50125.82c + 588 501251 Sn-125m 5.55350E-05 4.56210E-04 501251 + 589 501260 Sn-126 1.09350E-03 1.79350E-03 50126.82c + 590 501270 Sn-127 1.81950E-03 2.15370E-03 501270 + 591 501271 Sn-127m 6.50300E-04 1.38490E-03 501271 + 592 501280 Sn-128 1.63730E-03 6.73450E-03 501280 + 593 501281 Sn-128m 4.46280E-03 4.78540E-03 501281 + 594 501290 Sn-129 1.51380E-03 1.83300E-03 501290 + 595 501291 Sn-129m 4.23550E-03 4.26650E-03 501291 + 596 501300 Sn-130 1.39180E-03 1.46040E-03 501300 + 597 501301 Sn-130m 3.79360E-03 3.83740E-03 501301 + 598 501310 Sn-131 5.59170E-04 5.70370E-04 501310 + 599 501311 Sn-131m 1.56450E-03 1.57060E-03 501311 + 600 501320 Sn-132 7.06700E-04 7.06830E-04 501320 + 601 501330 Sn-133 4.05640E-05 4.05650E-05 501330 + 602 501340 Sn-134 7.32070E-06 7.32070E-06 501340 + 603 501350 Sn-135 3.95970E-08 3.95970E-08 501350 + 604 511180 Sb-118 1.29200E-12 1.29200E-12 511180 + 605 511181 Sb-118m 2.16060E-12 2.16060E-12 511181 + 606 511190 Sb-119 2.07750E-10 2.91170E-10 511190 + 607 511191 Sb-119m 8.34200E-11 8.34200E-11 511191 + 608 511220 Sb-122 3.56910E-12 8.35080E-12 511220 + 609 511221 Sb-122m 4.78170E-12 4.78170E-12 511221 + 610 511230 Sb-123 1.02510E-06 1.22080E-04 51123.82c + 611 511240 Sb-124 6.59900E-07 1.69840E-06 51124.82c + 612 511241 Sb-124m 5.32340E-07 1.38460E-06 511241 + 613 511242 Sb-124m 8.52270E-07 8.52270E-07 511242 + 614 511250 Sb-125 1.05240E-05 6.88210E-04 51125.82c + 615 511260 Sb-126 2.79230E-05 3.33910E-05 51126.82c + 616 511261 Sb-126m 1.74410E-05 3.90610E-05 511261 + 617 511262 Sb-126m 2.16200E-05 2.16200E-05 511262 + 618 511270 Sb-127 4.81390E-04 4.02000E-03 511270 + 619 511280 Sb-128 7.52760E-04 7.52520E-03 511280 + 620 511281 Sb-128m 1.05280E-03 1.05280E-03 511281 + 621 511290 Sb-129 4.36660E-03 9.13750E-03 511290 + 622 511291 Sb-129m 3.23140E-03 5.36460E-03 511291 + 623 511300 Sb-130 5.69200E-03 9.07110E-03 511300 + 624 511301 Sb-130m 5.69200E-03 7.61070E-03 511301 + 625 511310 Sb-131 1.67860E-02 1.89270E-02 511310 + 626 511320 Sb-132 5.57880E-03 6.28560E-03 511320 + 627 511321 Sb-132m 4.93930E-03 4.93930E-03 511321 + 628 511330 Sb-133 6.58230E-03 6.62410E-03 511330 + 629 511340 Sb-134 3.07910E-04 3.13990E-04 511340 + 630 511341 Sb-134m 8.39290E-04 8.39300E-04 511341 + 631 511350 Sb-135 1.98200E-04 1.98230E-04 511350 + 632 511360 Sb-136 2.44210E-05 2.44210E-05 511360 + 633 511370 Sb-137 9.95690E-07 9.95690E-07 511370 + 634 511380 Sb-138 3.33800E-09 3.33800E-09 511380 + 635 521250 Te-125 4.39780E-07 6.90310E-04 52125.82c + 636 521251 Te-125m 1.66540E-06 1.55660E-04 521251 + 637 521260 Te-126 7.41360E-08 6.70580E-05 52126.82c + 638 521270 Te-127 3.41790E-06 4.01690E-03 521270 + 639 521271 Te-127m 9.56310E-06 6.72040E-04 52527.82c + 640 521280 Te-128 1.45970E-04 8.68610E-03 52128.82c + 641 521290 Te-129 2.47930E-04 1.21740E-02 521290 + 642 521291 Te-129m 6.93710E-04 6.66320E-03 52529.82c + 643 521300 Te-130 5.90500E-03 2.25870E-02 52130.82c + 644 521310 Te-131 3.56690E-03 2.33930E-02 521310 + 645 521311 Te-131m 9.98010E-03 1.14950E-02 521311 + 646 521320 Te-132 3.36330E-02 4.48580E-02 52132.82c + 647 521330 Te-133 9.60360E-03 1.99860E-02 521330 + 648 521331 Te-133m 2.68700E-02 2.80160E-02 521331 + 649 521340 Te-134 3.67920E-02 3.79760E-02 521340 + 650 521350 Te-135 1.02420E-02 1.04130E-02 521350 + 651 521360 Te-136 3.55930E-03 3.58020E-03 521360 + 652 521370 Te-137 4.69320E-04 4.69830E-04 521370 + 653 521380 Te-138 8.79940E-05 8.79970E-05 521380 + 654 521390 Te-139 3.98540E-06 3.98540E-06 521390 + 655 521400 Te-140 3.41870E-08 3.41870E-08 521400 + 656 531270 I-127 4.69180E-10 4.03300E-03 53127.82c + 657 531280 I-128 3.95850E-08 3.95850E-08 531280 + 658 531290 I-129 2.06820E-06 1.46410E-02 53129.82c + 659 531300 I-130 3.75170E-05 4.90790E-05 53130.82c + 660 531301 I-130m 1.37640E-05 1.37640E-05 531301 + 661 531310 I-131 5.73170E-04 3.30470E-02 53131.82c + 662 531320 I-132 1.24780E-03 4.70560E-02 531320 + 663 531321 I-132m 1.10470E-03 1.10470E-03 531321 + 664 531330 I-133 7.05670E-03 5.53780E-02 531330 + 665 531331 I-133m 5.22230E-03 5.22230E-03 531331 + 666 531340 I-134 1.39700E-02 6.40300E-02 531340 + 667 531341 I-134m 1.23690E-02 1.23690E-02 531341 + 668 531350 I-135 4.88190E-02 5.92320E-02 53135.82c + 669 531360 I-136 6.46870E-03 1.00560E-02 531360 + 670 531361 I-136m 1.76320E-02 1.76390E-02 531361 + 671 531370 I-137 1.41390E-02 1.46000E-02 531370 + 672 531380 I-138 3.23540E-03 3.31780E-03 531380 + 673 531390 I-139 1.37130E-03 1.37530E-03 531390 + 674 531400 I-140 1.58470E-04 1.58500E-04 531400 + 675 531410 I-141 3.54920E-05 3.54920E-05 531410 + 676 531420 I-142 9.66560E-07 9.66560E-07 531420 + 677 531430 I-143 2.61560E-09 2.61560E-09 531430 + 678 541300 Xe-130 2.59100E-08 5.13070E-05 54130.82c + 679 541310 Xe-131 1.61000E-06 3.30530E-02 54131.82c + 680 541311 Xe-131m 4.50480E-06 3.63460E-04 541311 + 681 541320 Xe-132 3.68580E-05 4.72970E-02 54132.82c + 682 541321 Xe-132m 4.93800E-05 4.93800E-05 541321 + 683 541330 Xe-133 1.33860E-04 5.58860E-02 54133.82c + 684 541331 Xe-133m 3.74530E-04 1.95080E-03 541331 + 685 541340 Xe-134 1.06280E-03 6.82740E-02 54134.82c + 686 541341 Xe-134m 2.89690E-03 3.18140E-03 541341 + 687 541350 Xe-135 4.06270E-03 7.45350E-02 54135.82c + 688 541351 Xe-135m 1.13670E-02 2.11460E-02 541351 + 689 541360 Xe-136 5.47880E-02 8.34320E-02 54136.82c + 690 541370 Xe-137 5.01820E-02 6.40090E-02 541370 + 691 541380 Xe-138 4.39350E-02 4.72120E-02 541380 + 692 541390 Xe-139 1.78120E-02 1.90670E-02 541390 + 693 541400 Xe-140 1.15000E-02 1.16510E-02 541400 + 694 541410 Xe-141 2.84580E-03 2.87410E-03 541410 + 695 541420 Xe-142 8.99440E-04 9.00170E-04 541420 + 696 541430 Xe-143 9.00020E-05 9.00040E-05 541430 + 697 541440 Xe-144 1.08420E-05 1.08420E-05 541440 + 698 541450 Xe-145 1.63410E-08 1.63410E-08 541450 + 699 551320 Cs-132 4.29440E-09 4.29440E-09 551320 + 700 551330 Cs-133 1.01490E-06 5.58870E-02 55133.82c + 701 551340 Cs-134 4.43890E-06 8.36900E-06 55134.82c + 702 551341 Cs-134m 3.93010E-06 3.93010E-06 551341 + 703 551350 Cs-135 8.69980E-05 7.48140E-02 55135.82c + 704 551351 Cs-135m 6.43820E-05 6.43820E-05 551351 + 705 551360 Cs-136 6.15170E-04 8.35080E-04 55136.82c + 706 551361 Cs-136m 4.39830E-04 4.39830E-04 551361 + 707 551370 Cs-137 8.98480E-03 7.29940E-02 55137.82c + 708 551380 Cs-138 7.26320E-03 6.43140E-02 551380 + 709 551381 Cs-138m 1.21470E-02 1.21470E-02 551381 + 710 551390 Cs-139 2.91640E-02 4.82310E-02 551390 + 711 551400 Cs-140 2.16590E-02 3.33120E-02 551400 + 712 551410 Cs-141 2.34140E-02 2.62900E-02 551410 + 713 551420 Cs-142 9.99440E-03 1.08920E-02 551420 + 714 551430 Cs-143 4.92080E-03 5.01020E-03 551430 + 715 551440 Cs-144 5.52100E-04 8.38670E-04 551440 + 716 551441 Cs-144m 5.52100E-04 5.52100E-04 551441 + 717 551450 Cs-145 1.99150E-04 1.99170E-04 551450 + 718 551460 Cs-146 1.45550E-05 1.45550E-05 551460 + 719 551470 Cs-147 2.91920E-06 2.91920E-06 551470 + 720 551480 Cs-148 8.94050E-10 8.94050E-10 551480 + 721 561340 Ba-134 2.68340E-09 8.37170E-06 56134.82c + 722 561350 Ba-135 1.90120E-08 7.22080E-08 56135.82c + 723 561351 Ba-135m 5.31960E-08 5.31960E-08 561351 + 724 561360 Ba-136 2.09870E-06 1.06280E-03 56136.82c + 725 561361 Ba-136m 5.72060E-06 5.72060E-06 561361 + 726 561370 Ba-137 3.91530E-05 7.31430E-02 56137.82c + 727 561371 Ba-137m 1.09550E-04 6.90150E-02 561371 + 728 561380 Ba-138 2.36210E-03 6.89840E-02 56138.82c + 729 561390 Ba-139 7.12150E-03 5.53530E-02 561390 + 730 561400 Ba-140 1.94560E-02 5.27680E-02 56140.82c + 731 561410 Ba-141 2.46810E-02 5.09710E-02 561410 + 732 561420 Ba-142 4.12150E-02 5.21890E-02 561420 + 733 561430 Ba-143 2.87480E-02 3.37030E-02 561430 + 734 561440 Ba-144 2.13090E-02 2.24250E-02 561440 + 735 561450 Ba-145 6.75630E-03 6.92900E-03 561450 + 736 561460 Ba-146 2.74740E-03 2.76070E-03 561460 + 737 561470 Ba-147 4.93520E-04 4.95610E-04 561470 + 738 561480 Ba-148 1.09520E-04 1.09520E-04 561480 + 739 561490 Ba-149 4.93790E-06 4.93790E-06 561490 + 740 561500 Ba-150 5.27050E-09 5.27050E-09 561500 + 741 571370 La-137 8.41470E-09 8.41470E-09 571370 + 742 571380 La-138 2.07300E-06 2.07300E-06 57138.82c + 743 571390 La-139 4.78690E-05 5.54010E-02 57139.82c + 744 571400 La-140 2.67810E-04 5.30350E-02 57140.82c + 745 571410 La-141 1.40950E-03 5.23810E-02 571410 + 746 571420 La-142 3.10860E-03 5.52980E-02 571420 + 747 571430 La-143 1.05330E-02 4.42360E-02 571430 + 748 571440 La-144 1.50420E-02 3.74670E-02 571440 + 749 571450 La-145 1.81900E-02 2.51190E-02 571450 + 750 571460 La-146 3.14800E-03 5.90870E-03 571460 + 751 571461 La-146m 6.60420E-03 6.60420E-03 571461 + 752 571470 La-147 6.83540E-03 7.33140E-03 571470 + 753 571480 La-148 2.02500E-03 2.13410E-03 571480 + 754 571490 La-149 5.72740E-04 5.77660E-04 571490 + 755 571500 La-150 7.49210E-05 7.49260E-05 571500 + 756 571510 La-151 1.97850E-06 1.97850E-06 571510 + 757 571520 La-152 9.74960E-07 9.74960E-07 571520 + 758 571530 La-153 1.30970E-10 1.30970E-10 571530 + 759 581390 Ce-139 4.54220E-10 1.72510E-09 581390 + 760 581391 Ce-139m 1.27090E-09 1.27090E-09 581391 + 761 581400 Ce-140 2.94180E-06 5.30380E-02 58140.82c + 762 581410 Ce-141 3.06020E-05 5.24110E-02 58141.82c + 763 581420 Ce-142 1.93060E-04 5.54910E-02 58142.82c + 764 581430 Ce-143 7.71970E-04 4.50080E-02 58143.82c + 765 581440 Ce-144 3.32810E-03 4.07950E-02 58144.82c + 766 581450 Ce-145 7.70290E-03 3.28220E-02 581450 + 767 581460 Ce-146 1.44730E-02 2.69860E-02 581460 + 768 581470 Ce-147 1.40880E-02 2.14190E-02 581470 + 769 581480 Ce-148 1.39650E-02 1.61070E-02 581480 + 770 581490 Ce-149 6.14240E-03 6.71400E-03 581490 + 771 581500 Ce-150 3.05740E-03 3.13030E-03 581500 + 772 581510 Ce-151 6.09150E-04 6.11190E-04 581510 + 773 581520 Ce-152 1.46810E-04 1.47730E-04 581520 + 774 581530 Ce-153 1.12740E-05 1.12740E-05 581530 + 775 581540 Ce-154 3.16110E-08 3.16110E-08 581540 + 776 581550 Ce-155 3.52080E-10 3.52080E-10 581550 + 777 591420 Pr-142 2.59440E-07 9.66610E-07 59142.82c + 778 591421 Pr-142m 7.07170E-07 7.07170E-07 591421 + 779 591430 Pr-143 3.96240E-06 4.50120E-02 59143.82c + 780 591440 Pr-144 9.70810E-07 4.08060E-02 591440 + 781 591441 Pr-144m 9.87620E-06 5.72830E-04 591441 + 782 591450 Pr-145 9.07330E-05 3.29130E-02 591450 + 783 591460 Pr-146 3.42880E-04 2.73290E-02 591460 + 784 591470 Pr-147 1.34840E-03 2.27680E-02 591470 + 785 591480 Pr-148 4.54710E-04 1.65620E-02 591480 + 786 591481 Pr-148m 2.20440E-03 2.20440E-03 591481 + 787 591490 Pr-149 4.67850E-03 1.13920E-02 591490 + 788 591500 Pr-150 3.75590E-03 6.88620E-03 591500 + 789 591510 Pr-151 3.16790E-03 3.77910E-03 591510 + 790 591520 Pr-152 1.07260E-03 1.22040E-03 591520 + 791 591530 Pr-153 3.68580E-04 3.79780E-04 591530 + 792 591540 Pr-154 7.03260E-05 7.03570E-05 591540 + 793 591550 Pr-155 1.03120E-05 1.03120E-05 591550 + 794 591560 Pr-156 3.30140E-08 3.30140E-08 591560 + 795 591570 Pr-157 7.93920E-10 7.93920E-10 591570 + 796 591580 Pr-158 5.12400E-12 5.12400E-12 591580 + 797 601440 Nd-144 1.60150E-09 4.08060E-02 60144.82c + 798 601450 Nd-145 3.37020E-08 3.29130E-02 60145.82c + 799 601460 Nd-146 5.82510E-06 2.73350E-02 60146.82c + 800 601470 Nd-147 4.77610E-05 2.28160E-02 60147.82c + 801 601480 Nd-148 2.65620E-04 1.90320E-02 60148.82c + 802 601490 Nd-149 7.68060E-04 1.21610E-02 601490 + 803 601500 Nd-150 1.68960E-03 8.57580E-03 60150.82c + 804 601510 Nd-151 2.34920E-03 6.12830E-03 601510 + 805 601520 Nd-152 2.72730E-03 3.94770E-03 601520 + 806 601530 Nd-153 1.57860E-03 1.95840E-03 601530 + 807 601540 Nd-154 9.17470E-04 9.87830E-04 601540 + 808 601550 Nd-155 2.21950E-04 2.32260E-04 601550 + 809 601560 Nd-156 6.84070E-05 6.84390E-05 601560 + 810 601570 Nd-157 7.42820E-06 7.42890E-06 601570 + 811 601580 Nd-158 5.39240E-08 5.39290E-08 601580 + 812 601590 Nd-159 1.31220E-09 1.31220E-09 601590 + 813 601600 Nd-160 1.88870E-11 1.88870E-11 601600 + 814 611470 Pm-147 3.25010E-09 2.28160E-02 61147.82c + 815 611480 Pm-148 2.51960E-08 2.86300E-08 61148.82c + 816 611481 Pm-148m 6.86790E-08 6.86790E-08 61548.82c + 817 611490 Pm-149 9.87600E-07 1.21620E-02 61149.82c + 818 611500 Pm-150 2.06860E-05 2.06860E-05 611500 + 819 611510 Pm-151 8.61910E-05 6.21450E-03 61151.82c + 820 611520 Pm-152 2.88990E-05 3.97660E-03 611520 + 821 611521 Pm-152m 6.07550E-05 6.07550E-05 611521 + 822 611522 Pm-152m 7.93620E-05 7.93620E-05 611522 + 823 611530 Pm-153 3.48570E-04 2.30690E-03 611530 + 824 611540 Pm-154 1.71940E-04 1.15980E-03 611540 + 825 611541 Pm-154m 1.71940E-04 1.71940E-04 611541 + 826 611550 Pm-155 3.46750E-04 5.79010E-04 611550 + 827 611560 Pm-156 1.94470E-04 2.62910E-04 611560 + 828 611570 Pm-157 1.04830E-04 1.12260E-04 611570 + 829 611580 Pm-158 1.28480E-05 1.29020E-05 611580 + 830 611590 Pm-159 7.60530E-06 7.60660E-06 611590 + 831 611600 Pm-160 3.69550E-08 3.69740E-08 611600 + 832 611610 Pm-161 1.05130E-09 1.05130E-09 611610 + 833 611620 Pm-162 1.91250E-11 1.91250E-11 611620 + 834 621490 Sm-149 3.80420E-10 1.21620E-02 62149.82c + 835 621500 Sm-150 1.12000E-08 2.06970E-05 62150.82c + 836 621510 Sm-151 1.97810E-06 6.21650E-03 62151.82c + 837 621520 Sm-152 3.89800E-06 4.12060E-03 62152.82c + 838 621530 Sm-153 7.15040E-06 2.33410E-03 62153.82c + 839 621531 Sm-153m 2.00070E-05 2.00070E-05 621531 + 840 621540 Sm-154 7.31590E-05 1.40490E-03 62154.82c + 841 621550 Sm-155 1.26530E-04 7.05540E-04 621550 + 842 621560 Sm-156 2.05160E-04 4.68070E-04 621560 + 843 621570 Sm-157 1.38060E-04 2.50320E-04 621570 + 844 621580 Sm-158 7.89150E-05 9.18180E-05 621580 + 845 621590 Sm-159 4.18310E-05 4.94360E-05 621590 + 846 621600 Sm-160 1.55240E-05 1.55610E-05 621600 + 847 621610 Sm-161 9.68790E-07 9.69840E-07 621610 + 848 621620 Sm-162 4.94270E-08 4.94460E-08 621620 + 849 621630 Sm-163 8.96350E-10 8.96350E-10 621630 + 850 621640 Sm-164 1.13110E-11 1.13110E-11 621640 + 851 631520 Eu-152 1.84610E-10 4.29130E-10 63152.82c + 852 631521 Eu-152m 4.21820E-11 4.21820E-11 631521 + 853 631522 Eu-152m 2.44520E-10 2.44520E-10 631522 + 854 631530 Eu-153 1.41440E-08 2.33410E-03 63153.82c + 855 631540 Eu-154 8.60000E-08 1.78720E-07 63154.82c + 856 631541 Eu-154m 9.27200E-08 9.27200E-08 631541 + 857 631550 Eu-155 2.80940E-06 7.08350E-04 63155.82c + 858 631560 Eu-156 7.43040E-06 4.75500E-04 63156.82c + 859 631570 Eu-157 1.66910E-05 2.67010E-04 63157.82c + 860 631580 Eu-158 1.55970E-05 1.07420E-04 631580 + 861 631590 Eu-159 2.09110E-05 7.03470E-05 631590 + 862 631600 Eu-160 1.55220E-05 3.10830E-05 631600 + 863 631610 Eu-161 3.87520E-06 4.84500E-06 631610 + 864 631620 Eu-162 1.59010E-06 1.63960E-06 631620 + 865 631630 Eu-163 1.53250E-06 1.53340E-06 631630 + 866 631640 Eu-164 5.41840E-09 5.42970E-09 631640 + 867 631650 Eu-165 7.55000E-10 7.55000E-10 631650 + 868 631660 Eu-166 2.56960E-11 2.56960E-11 631660 + 869 641540 Gd-154 5.26850E-11 1.78740E-07 64154.82c + 870 641550 Gd-155 2.02790E-10 7.08350E-04 64155.82c + 871 641551 Gd-155m 5.67380E-10 5.67380E-10 641551 + 872 641560 Gd-156 2.16490E-08 4.75520E-04 64156.82c + 873 641570 Gd-157 1.85490E-06 2.68870E-04 64157.82c + 874 641580 Gd-158 2.75260E-06 1.10170E-04 64158.82c + 875 641590 Gd-159 1.90120E-06 7.22480E-05 641590 + 876 641600 Gd-160 1.94030E-06 3.30230E-05 64160.82c + 877 641610 Gd-161 7.75010E-06 1.25950E-05 641610 + 878 641620 Gd-162 6.57560E-06 8.21520E-06 641620 + 879 641630 Gd-163 7.66240E-07 2.29960E-06 641630 + 880 641640 Gd-164 2.48550E-07 2.53980E-07 641640 + 881 641650 Gd-165 8.34410E-08 8.41960E-08 641650 + 882 641660 Gd-166 1.66630E-08 1.66890E-08 641660 + 883 641670 Gd-167 9.06330E-10 9.06330E-10 641670 + 884 641680 Gd-168 3.99400E-11 3.99400E-11 641680 + 885 651570 Tb-157 3.85390E-11 3.85390E-11 651570 + 886 651580 Tb-158 5.15530E-10 5.65900E-10 651580 + 887 651581 Tb-158m 5.06760E-11 5.06760E-11 651581 + 888 651590 Tb-159 1.17620E-08 7.22600E-05 65159.82c + 889 651600 Tb-160 6.36760E-08 6.36760E-08 65160.82c + 890 651610 Tb-161 2.51670E-07 1.28470E-05 651610 + 891 651620 Tb-162 1.64390E-06 9.85910E-06 651620 + 892 651630 Tb-163 6.72220E-07 2.97190E-06 651630 + 893 651640 Tb-164 2.26760E-07 4.80740E-07 651640 + 894 651650 Tb-165 3.55380E-07 4.39580E-07 651650 + 895 651660 Tb-166 1.53220E-07 1.69910E-07 651660 + 896 651670 Tb-167 4.46250E-08 4.55310E-08 651670 + 897 651680 Tb-168 4.88710E-09 4.92700E-09 651680 + 898 651690 Tb-169 5.73600E-10 5.73600E-10 651690 + 899 651700 Tb-170 2.48050E-11 2.48050E-11 651700 + 900 661590 Dy-159 2.23930E-12 2.23930E-12 661590 + 901 661600 Dy-160 4.53290E-11 6.37210E-08 66160.82c + 902 661610 Dy-161 4.75060E-10 1.28470E-05 66161.82c + 903 661620 Dy-162 7.37400E-09 9.86640E-06 66162.82c + 904 661630 Dy-163 1.84790E-08 2.99030E-06 66163.82c + 905 661640 Dy-164 5.17130E-07 9.97900E-07 66164.82c + 906 661650 Dy-165 4.91500E-07 9.95050E-07 661650 + 907 661651 Dy-165m 6.54400E-08 6.54400E-08 661651 + 908 661660 Dy-166 2.17600E-07 3.87510E-07 661660 + 909 661670 Dy-167 1.26520E-07 1.72050E-07 661670 + 910 661680 Dy-168 6.64910E-08 7.14180E-08 661680 + 911 661690 Dy-169 1.75010E-08 1.80750E-08 661690 + 912 661700 Dy-170 4.19680E-09 4.22160E-09 661700 + 913 661710 Dy-171 3.63760E-10 3.63760E-10 661710 + 914 661720 Dy-172 2.68620E-11 2.68620E-11 661720 + 915 671630 Ho-163 1.31960E-11 1.49530E-11 671630 + 916 671631 Ho-163m 1.75700E-12 1.75700E-12 671631 + 917 671640 Ho-164 1.87320E-11 6.97900E-11 671640 + 918 671641 Ho-164m 5.10580E-11 5.10580E-11 671641 + 919 671650 Ho-165 1.34640E-09 9.97860E-07 67165.82c + 920 671660 Ho-166 1.70880E-09 3.89220E-07 671660 + 921 671661 Ho-166m 4.65780E-09 4.65780E-09 671661 + 922 671670 Ho-167 1.87490E-08 1.90800E-07 671670 + 923 671680 Ho-168 7.58170E-09 9.16160E-08 671680 + 924 671681 Ho-168m 1.26790E-08 1.26790E-08 671681 + 925 671690 Ho-169 2.44070E-08 4.24820E-08 671690 + 926 671700 Ho-170 8.69140E-09 8.69140E-09 671700 + 927 671701 Ho-170m 3.18860E-09 7.41020E-09 671701 + 928 671710 Ho-171 5.11690E-09 5.48070E-09 671710 + 929 671720 Ho-172 8.79960E-10 9.06820E-10 671720 + 930 671730 Ho-173 1.71840E-10 1.71840E-10 671730 + 931 671740 Ho-174 1.23020E-11 1.23020E-11 671740 + 932 681660 Er-166 1.84080E-11 3.89240E-07 68166.82c + 933 681670 Er-167 1.23520E-10 1.90940E-07 68167.82c + 934 681671 Er-167m 1.64450E-11 2.28160E-08 681671 + 935 681680 Er-168 8.52360E-10 9.25310E-08 68168.82c + 936 681690 Er-169 2.34750E-09 4.48290E-08 681690 + 937 681700 Er-170 5.57740E-09 2.16790E-08 68170.82c + 938 681710 Er-171 4.82860E-09 1.03090E-08 681710 + 939 681720 Er-172 3.81360E-09 4.72040E-09 681720 + 940 681730 Er-173 1.55420E-09 1.72600E-09 681730 + 941 681740 Er-174 5.74340E-10 5.86640E-10 681740 + 942 681750 Er-175 8.65310E-11 8.65310E-11 681750 + 943 681760 Er-176 1.15910E-11 1.15910E-11 681760 + 944 691690 Tm-169 7.64780E-12 4.48370E-08 691690 + 945 691700 Tm-170 4.57890E-11 4.57890E-11 691700 + 946 691710 Tm-171 2.16140E-10 1.05250E-08 691710 + 947 691720 Tm-172 3.75650E-10 5.09610E-09 691720 + 948 691730 Tm-173 7.23910E-10 2.44990E-09 691730 + 949 691740 Tm-174 5.32160E-10 1.11880E-09 691740 + 950 691750 Tm-175 3.74510E-10 4.61040E-10 691750 + 951 691760 Tm-176 1.08420E-10 1.20010E-10 691760 + 952 691770 Tm-177 3.14000E-11 3.14000E-11 691770 + 953 691780 Tm-178 3.41790E-12 3.41790E-12 691780 + 954 701720 Yb-172 4.29330E-12 5.10040E-09 701720 + 955 701730 Yb-173 2.02590E-11 2.47020E-09 701730 + 956 701740 Yb-174 7.82900E-11 1.19710E-09 701740 + 957 701750 Yb-175 1.03110E-10 5.77880E-10 701750 + 958 701751 Yb-175m 1.37290E-11 3.68730E-10 701751 + 959 701760 Yb-176 5.04790E-11 2.59800E-10 701760 + 960 701761 Yb-176m 1.05900E-10 1.65910E-10 701761 + 961 701770 Yb-177 7.52720E-11 1.21830E-10 701770 + 962 701771 Yb-177m 1.51560E-11 4.65560E-11 701771 + 963 701780 Yb-178 4.72790E-11 5.06970E-11 701780 + 964 701790 Yb-179 1.23550E-11 1.23550E-11 701790 + 965 701800 Yb-180 2.94140E-12 2.94140E-12 701800 + 966 711750 Lu-175 1.46830E-12 5.79350E-10 71175.82c + 967 711760 Lu-176 3.15270E-12 1.97430E-11 71176.82c + 968 711761 Lu-176m 1.50280E-12 1.50280E-12 711761 + 969 711770 Lu-177 9.08250E-12 1.31910E-10 711770 + 970 711771 Lu-177m 4.32470E-12 4.43230E-12 711771 + 971 711780 Lu-178 6.25370E-12 5.69510E-11 711780 + 972 711781 Lu-178m 8.37830E-12 8.37830E-12 711781 + 973 711790 Lu-179 1.54430E-11 2.98540E-11 711790 + 974 711791 Lu-179m 2.05610E-12 1.44110E-11 711791 + 975 711800 Lu-180 2.24400E-12 6.82350E-12 711800 + 976 711801 Lu-180m 2.24400E-12 5.18540E-12 711801 + 977 711802 Lu-180m 3.97360E-12 3.97360E-12 711802 + 978 711810 Lu-181 3.62200E-12 3.62200E-12 711810 + 979 721790 Hf-179 9.91420E-13 3.15660E-11 72179.82c + 980 721800 Hf-180 1.30290E-12 1.54240E-11 72180.82c + 981 721801 Hf-180m 2.73320E-12 4.72000E-12 721801 + 982 721810 Hf-181 3.47090E-12 7.09290E-12 721810 + 983 721820 Hf-182 8.79080E-13 1.65360E-12 721820 + 984 721821 Hf-182m 1.84420E-12 1.84420E-12 721821 + 985 721830 Hf-183 1.10400E-12 1.10400E-12 721830 + + Nuclide 94239.82c -- plutonium 239 (Pu-239) + + Neutron-induced fission: + + Interpolation region : 1 / 2 + Interpolation energy : 2.53000E-08 MeV + Number of products : 1006 / 1093 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 4.08000E-05 4.08000E-05 1001.82c + 2 10020 H-2 1.34700E-05 1.34700E-05 1002.82c + 3 10030 H-3 1.42000E-04 1.42000E-04 1003.82c + 4 20040 He-4 2.19000E-03 2.19190E-03 2004.82c + 5 20060 He-6 4.09800E-05 4.09800E-05 20060 + 6 20080 He-8 6.87000E-07 6.87000E-07 20080 + 7 30070 Li-7 1.40000E-06 1.50500E-06 3007.82c + 8 30090 Li-9 1.14000E-06 1.14000E-06 30090 + 9 40090 Be-9 1.14000E-06 1.71570E-06 4009.82c + 10 40100 Be-10 1.05000E-05 1.05000E-05 40100 + 11 40110 Be-11 7.52000E-07 7.52000E-07 40110 + 12 40120 Be-12 4.73000E-07 4.73000E-07 40120 + 13 60080 C-8 6.87000E-07 6.87000E-07 60080 + 14 60140 C-14 3.01000E-06 3.01000E-06 60140 + 15 200500 Ca-50 1.11660E-12 1.11660E-12 200500 + 16 210510 Sc-51 2.19030E-12 2.19030E-12 210510 + 17 210520 Sc-52 3.17810E-12 3.17810E-12 210520 + 18 210530 Sc-53 5.01670E-12 5.01670E-12 210530 + 19 210540 Sc-54 2.51670E-12 2.51670E-12 210540 + 20 210550 Sc-55 1.76640E-12 1.76640E-12 210550 + 21 220520 Ti-52 2.26000E-12 5.43810E-12 220520 + 22 220530 Ti-53 5.82660E-12 1.08430E-11 220530 + 23 220540 Ti-54 1.64430E-11 1.89600E-11 220540 + 24 220550 Ti-55 2.02790E-11 2.20450E-11 220550 + 25 220560 Ti-56 2.74280E-11 2.74280E-11 220560 + 26 220570 Ti-57 1.14080E-11 1.14080E-11 220570 + 27 220580 Ti-58 5.44550E-12 5.44550E-12 220580 + 28 230540 V-54 2.57230E-12 2.15320E-11 230540 + 29 230550 V-55 1.78330E-11 3.98780E-11 230550 + 30 230560 V-56 3.94060E-11 6.68680E-11 230560 + 31 230570 V-57 9.44950E-11 1.05870E-10 230570 + 32 230580 V-58 8.21920E-11 8.76370E-11 230580 + 33 230590 V-59 9.20970E-11 9.20970E-11 230590 + 34 230600 V-60 2.96130E-11 2.96130E-11 230600 + 35 230610 V-61 1.16130E-11 1.16130E-11 230610 + 36 230620 V-62 1.48340E-12 1.48340E-12 230620 + 37 240560 Cr-56 8.69760E-12 7.59890E-11 240560 + 38 240570 Cr-57 3.54330E-11 2.10990E-10 240570 + 39 240580 Cr-58 1.70950E-10 1.88480E-10 240580 + 40 240590 Cr-59 3.17080E-10 4.09180E-10 240590 + 41 240600 Cr-60 6.07100E-10 6.37410E-10 240600 + 42 240610 Cr-61 4.50090E-10 4.61010E-10 240610 + 43 240620 Cr-62 3.94730E-10 3.96210E-10 240620 + 44 240630 Cr-63 1.02780E-10 1.02780E-10 240630 + 45 240640 Cr-64 2.70370E-11 2.70370E-11 240640 + 46 240650 Cr-65 2.76570E-12 2.76570E-12 240650 + 47 250580 Mn-58 7.20500E-12 1.95680E-10 250580 + 48 250590 Mn-59 8.87440E-11 4.97920E-10 250590 + 49 250600 Mn-60 2.84990E-11 6.95020E-10 250600 + 50 250601 Mn-60m 2.53110E-10 2.53110E-10 250601 + 51 250610 Mn-61 1.15760E-09 1.61860E-09 250610 + 52 250620 Mn-62 1.45940E-09 1.65750E-09 250620 + 53 250621 Mn-62m 2.62000E-10 4.60100E-10 250621 + 54 250630 Mn-63 2.76750E-09 2.87030E-09 250630 + 55 250640 Mn-64 1.42490E-09 1.45190E-09 250640 + 56 250650 Mn-65 1.02800E-09 1.03080E-09 250650 + 57 250660 Mn-66 2.21130E-10 2.21130E-10 250660 + 58 250670 Mn-67 4.68170E-11 4.68170E-11 250670 + 59 250680 Mn-68 3.19720E-12 3.19720E-12 250680 + 60 260600 Fe-60 1.79130E-11 9.36930E-10 260600 + 61 260610 Fe-61 1.34510E-10 1.75310E-09 260610 + 62 260620 Fe-62 1.15550E-09 3.27310E-09 260620 + 63 260630 Fe-63 3.03640E-09 5.90670E-09 260630 + 64 260640 Fe-64 8.77710E-09 1.02290E-08 260640 + 65 260650 Fe-65 1.10850E-08 1.21160E-08 260650 + 66 260660 Fe-66 1.52750E-08 1.54960E-08 260660 + 67 260670 Fe-67 6.53040E-09 6.57720E-09 260670 + 68 260680 Fe-68 3.21790E-09 3.22110E-09 260680 + 69 260690 Fe-69 5.53660E-10 5.53660E-10 260690 + 70 260700 Fe-70 8.74900E-11 8.74900E-11 260700 + 71 260710 Fe-71 5.52170E-12 5.52170E-12 260710 + 72 270620 Co-62 4.49070E-12 3.27770E-09 270620 + 73 270621 Co-62m 1.05180E-11 1.05180E-11 270621 + 74 270630 Co-63 2.54230E-10 6.16090E-09 270630 + 75 270640 Co-64 1.29440E-09 1.15230E-08 270640 + 76 270650 Co-65 9.20850E-09 2.13240E-08 270650 + 77 270660 Co-66 2.07170E-08 3.62130E-08 270660 + 78 270670 Co-67 5.09090E-08 5.74860E-08 270670 + 79 270680 Co-68 2.41910E-08 3.64910E-08 270680 + 80 270681 Co-68m 2.13400E-08 2.46000E-08 270681 + 81 270690 Co-69 5.19650E-08 5.24800E-08 270690 + 82 270700 Co-70 8.51700E-09 8.51700E-09 270700 + 83 270701 Co-70m 8.51700E-09 8.60450E-09 270701 + 84 270710 Co-71 7.91750E-09 7.92300E-09 270710 + 85 270720 Co-72 5.02810E-10 5.02810E-10 270720 + 86 270730 Co-73 1.25550E-10 1.25550E-10 270730 + 87 270740 Co-74 9.46820E-12 9.46820E-12 270740 + 88 280640 Ni-64 2.19760E-11 1.15450E-08 28064.82c + 89 280650 Ni-65 3.07740E-10 2.16320E-08 280650 + 90 280660 Ni-66 4.30230E-09 4.05150E-08 280660 + 91 280670 Ni-67 1.80190E-08 7.55050E-08 280670 + 92 280680 Ni-68 8.94630E-08 1.38780E-07 280680 + 93 280690 Ni-69 8.43400E-08 1.36290E-07 280690 + 94 280691 Ni-69m 8.43400E-08 8.43400E-08 280691 + 95 280700 Ni-70 3.28030E-07 3.45150E-07 280700 + 96 280710 Ni-71 5.23600E-07 5.31520E-07 280710 + 97 280720 Ni-72 1.24820E-07 1.25320E-07 280720 + 98 280730 Ni-73 6.61530E-08 6.62790E-08 280730 + 99 280740 Ni-74 3.69090E-08 3.69190E-08 280740 + 100 280750 Ni-75 1.76330E-09 1.76330E-09 280750 + 101 280760 Ni-76 2.14930E-10 2.14930E-10 280760 + 102 280770 Ni-77 1.05280E-11 1.05280E-11 280770 + 103 290660 Cu-66 1.44340E-11 4.05300E-08 290660 + 104 290670 Cu-67 4.17090E-10 7.59220E-08 290670 + 105 290680 Cu-68 1.17860E-09 1.42280E-07 290680 + 106 290681 Cu-68m 2.76070E-09 2.76070E-09 290681 + 107 290690 Cu-69 4.44990E-08 2.65130E-07 290690 + 108 290700 Cu-70 1.09390E-08 8.07720E-08 290700 + 109 290701 Cu-70m 1.21860E-07 1.39670E-07 290701 + 110 290702 Cu-70m 1.09390E-08 3.56090E-07 290702 + 111 290710 Cu-71 5.23620E-07 1.05510E-06 290710 + 112 290720 Cu-72 5.04380E-07 6.29700E-07 290720 + 113 290730 Cu-73 1.80600E-06 1.87230E-06 290730 + 114 290740 Cu-74 1.32080E-06 1.35780E-06 290740 + 115 290750 Cu-75 7.43640E-07 7.45380E-07 290750 + 116 290760 Cu-76 7.79900E-07 7.80010E-07 290760 + 117 290761 Cu-76m 7.79900E-07 7.80010E-07 290761 + 118 290770 Cu-77 5.50250E-08 5.50350E-08 290770 + 119 290780 Cu-78 7.96850E-09 7.96850E-09 290780 + 120 290790 Cu-79 1.50930E-10 1.50930E-10 290790 + 121 290800 Cu-80 2.52970E-11 2.52970E-11 290800 + 122 300680 Zn-68 1.67980E-11 1.42730E-07 300680 + 123 300690 Zn-69 7.44140E-11 2.65530E-07 300690 + 124 300691 Zn-69m 3.21830E-10 3.21830E-10 300691 + 125 300700 Zn-70 8.56840E-09 4.97460E-07 300700 + 126 300710 Zn-71 1.43140E-08 1.06950E-06 300710 + 127 300711 Zn-71m 6.19050E-08 6.19050E-08 300711 + 128 300720 Zn-72 5.04390E-07 1.13410E-06 300720 + 129 300730 Zn-73 1.78630E-07 2.98680E-06 300730 + 130 300731 Zn-73m 2.44200E-07 9.35880E-07 300731 + 131 300732 Zn-73m 1.38340E-06 1.38340E-06 300732 + 132 300740 Zn-74 9.90720E-06 1.12910E-05 300740 + 133 300750 Zn-75 7.43610E-06 8.17880E-06 300750 + 134 300760 Zn-76 1.48150E-05 1.63520E-05 300760 + 135 300770 Zn-77 1.05560E-05 1.14180E-05 300770 + 136 300771 Zn-77m 1.61370E-06 1.61370E-06 300771 + 137 300780 Zn-78 1.89110E-05 1.89190E-05 300780 + 138 300790 Zn-79 5.32050E-07 5.32120E-07 300790 + 139 300800 Zn-80 2.61590E-06 2.61590E-06 300800 + 140 300810 Zn-81 9.61600E-09 9.61600E-09 300810 + 141 300820 Zn-82 3.83040E-10 3.83040E-10 300820 + 142 310700 Ga-70 7.05310E-12 7.05310E-12 310700 + 143 310710 Ga-71 4.54950E-10 1.13180E-06 310710 + 144 310720 Ga-72 3.54470E-09 1.13800E-06 310720 + 145 310721 Ga-72m 3.99110E-10 3.81880E-08 310721 + 146 310730 Ga-73 1.36080E-07 3.81460E-06 310730 + 147 310740 Ga-74 6.60500E-07 9.62420E-06 310740 + 148 310741 Ga-74m 6.60500E-07 1.19520E-05 310741 + 149 310750 Ga-75 3.71890E-06 1.18980E-05 310750 + 150 310760 Ga-76 8.58230E-06 2.49340E-05 310760 + 151 310770 Ga-77 4.02680E-05 5.24930E-05 310770 + 152 310780 Ga-78 7.55700E-05 9.44960E-05 310780 + 153 310790 Ga-79 2.90500E-05 2.95750E-05 310790 + 154 310800 Ga-80 5.73170E-05 5.99340E-05 310800 + 155 310810 Ga-81 2.15450E-05 2.15540E-05 310810 + 156 310820 Ga-82 1.82480E-06 1.82520E-06 310820 + 157 310830 Ga-83 1.16240E-07 1.16240E-07 310830 + 158 310840 Ga-84 4.11130E-09 4.11130E-09 310840 + 159 310850 Ga-85 1.85500E-10 1.85500E-10 310850 + 160 320720 Ge-72 4.02790E-12 1.13800E-06 32072.82c + 161 320730 Ge-73 2.46850E-10 3.81490E-06 32073.82c + 162 320731 Ge-73m 5.70780E-11 3.75860E-06 320731 + 163 320740 Ge-74 2.32590E-08 1.26350E-05 32074.82c + 164 320750 Ge-75 2.01610E-08 1.20500E-05 320750 + 165 320751 Ge-75m 1.31880E-07 6.07790E-07 320751 + 166 320760 Ge-76 2.34050E-06 2.72740E-05 32076.82c + 167 320770 Ge-77 2.03300E-05 3.08940E-05 320770 + 168 320771 Ge-77m 3.10790E-06 5.56010E-05 320771 + 169 320780 Ge-78 1.83470E-04 2.77990E-04 320780 + 170 320790 Ge-79 1.24440E-05 4.52070E-05 320790 + 171 320791 Ge-79m 8.14030E-05 8.14470E-05 320791 + 172 320800 Ge-80 7.81620E-04 8.44120E-04 320800 + 173 320810 Ge-81 4.99980E-04 5.11450E-04 320810 + 174 320811 Ge-81m 1.15610E-04 1.24760E-04 320811 + 175 320820 Ge-82 4.16170E-04 4.17650E-04 320820 + 176 320830 Ge-83 1.02460E-04 1.02540E-04 320830 + 177 320840 Ge-84 3.50770E-05 3.50780E-05 320840 + 178 320850 Ge-85 5.16420E-06 5.16440E-06 320850 + 179 320860 Ge-86 7.29700E-08 7.29700E-08 320860 + 180 320870 Ge-87 1.60290E-09 1.60290E-09 320870 + 181 330740 As-74 4.43830E-12 4.43830E-12 330740 + 182 330750 As-75 5.20640E-11 1.20500E-05 33075.82c + 183 330751 As-75m 1.70340E-10 3.52670E-10 330751 + 184 330760 As-76 8.12920E-09 8.12920E-09 330760 + 185 330770 As-77 3.80030E-07 7.63110E-05 330770 + 186 330780 As-78 6.31740E-06 2.84310E-04 330780 + 187 330790 As-79 1.09090E-05 1.34310E-04 330790 + 188 330800 As-80 1.80740E-04 1.02490E-03 330800 + 189 330810 As-81 6.86730E-04 1.32170E-03 330810 + 190 330820 As-82 2.04150E-04 6.21800E-04 330820 + 191 330821 As-82m 6.16070E-04 6.16070E-04 330821 + 192 330830 As-83 8.66180E-04 9.72510E-04 330830 + 193 330840 As-84 2.43500E-04 2.59510E-04 330840 + 194 330841 As-84m 2.43500E-04 2.59510E-04 330841 + 195 330850 As-85 2.90170E-04 2.94610E-04 330850 + 196 330860 As-86 5.52050E-05 5.52780E-05 330860 + 197 330870 As-87 1.37820E-05 1.37840E-05 330870 + 198 330880 As-88 4.09920E-07 4.09920E-07 330880 + 199 330890 As-89 2.29920E-08 2.29920E-08 330890 + 200 330900 As-90 5.04360E-10 5.04360E-10 330900 + 201 340760 Se-76 2.05680E-12 8.13130E-09 34076.82c + 202 340770 Se-77 2.70830E-11 7.63110E-05 34077.82c + 203 340771 Se-77m 1.77170E-10 1.77170E-10 340771 + 204 340780 Se-78 2.10590E-06 2.86420E-04 34078.82c + 205 340790 Se-79 1.49710E-07 1.34400E-04 34079.82c + 206 340791 Se-79m 2.28850E-08 1.31150E-04 340791 + 207 340800 Se-80 3.44530E-05 1.05930E-03 34080.82c + 208 340810 Se-81 2.30490E-05 1.49540E-03 340810 + 209 340811 Se-81m 1.50770E-04 1.98220E-04 340811 + 210 340820 Se-82 7.96190E-04 2.03410E-03 34082.82c + 211 340830 Se-83 1.52840E-03 1.87890E-03 340830 + 212 340831 Se-83m 3.53400E-04 9.76170E-04 340831 + 213 340840 Se-84 3.89160E-03 4.47470E-03 340840 + 214 340850 Se-85 3.44470E-03 3.69270E-03 340850 + 215 340860 Se-86 2.69650E-03 2.73570E-03 340860 + 216 340870 Se-87 1.27110E-03 1.28280E-03 340870 + 217 340880 Se-88 4.98820E-04 4.99230E-04 340880 + 218 340890 Se-89 1.15790E-04 1.15810E-04 340890 + 219 340900 Se-90 2.50770E-05 2.50770E-05 340900 + 220 340910 Se-91 1.83020E-06 1.83020E-06 340910 + 221 340920 Se-92 6.78420E-09 6.78420E-09 340920 + 222 350790 Br-79 1.41330E-11 7.35030E-08 35079.82c + 223 350791 Br-79m 4.62380E-11 4.62380E-11 350791 + 224 350800 Br-80 3.36860E-09 1.35340E-08 350800 + 225 350801 Br-80m 1.01650E-08 1.01650E-08 350801 + 226 350810 Br-81 5.71460E-07 1.49610E-03 35081.82c + 227 350820 Br-82 5.12830E-06 7.26520E-06 350820 + 228 350821 Br-82m 2.18950E-06 2.18950E-06 350821 + 229 350830 Br-83 8.63920E-05 2.94140E-03 350830 + 230 350840 Br-84 2.00020E-04 4.67470E-03 350840 + 231 350841 Br-84m 2.00020E-04 2.00020E-04 350841 + 232 350850 Br-85 1.89480E-03 5.58750E-03 350850 + 233 350860 Br-86 3.38880E-03 6.12450E-03 350860 + 234 350870 Br-87 4.72390E-03 6.01160E-03 350870 + 235 350880 Br-88 3.22470E-03 3.72800E-03 350880 + 236 350890 Br-89 2.57390E-03 2.68070E-03 350890 + 237 350900 Br-90 1.10920E-03 1.13470E-03 350900 + 238 350910 Br-91 3.79630E-04 3.81080E-04 350910 + 239 350920 Br-92 6.34810E-05 6.34880E-05 350920 + 240 350930 Br-93 1.15820E-05 1.15820E-05 350930 + 241 350940 Br-94 9.01970E-07 9.01970E-07 350940 + 242 350950 Br-95 1.55980E-09 1.55980E-09 350950 + 243 360810 Kr-81 7.31660E-11 8.43510E-11 360810 + 244 360811 Kr-81m 1.11850E-11 1.11850E-11 360811 + 245 360820 Kr-82 6.74140E-09 7.32450E-06 36082.82c + 246 360830 Kr-83 2.42040E-06 2.94440E-03 36083.82c + 247 360831 Kr-83m 5.59640E-07 2.93940E-03 360831 + 248 360840 Kr-84 2.33990E-05 4.89820E-03 36084.82c + 249 360850 Kr-85 1.36020E-04 1.34560E-03 36085.82c + 250 360851 Kr-85m 3.14510E-05 5.60990E-03 360851 + 251 360860 Kr-86 1.46840E-03 7.74370E-03 36086.82c + 252 360870 Kr-87 3.74080E-03 9.85130E-03 360870 + 253 360880 Kr-88 9.17410E-03 1.30300E-02 360880 + 254 360890 Kr-89 1.22140E-02 1.47960E-02 360890 + 255 360900 Kr-90 1.31540E-02 1.40860E-02 360900 + 256 360910 Kr-91 8.00170E-03 8.32760E-03 360910 + 257 360920 Kr-92 4.56880E-03 4.61910E-03 360920 + 258 360930 Kr-93 1.57020E-03 1.57450E-03 360930 + 259 360940 Kr-94 4.41830E-04 4.42100E-04 360940 + 260 360950 Kr-95 5.52250E-05 5.52270E-05 360950 + 261 360960 Kr-96 6.62050E-06 6.62050E-06 360960 + 262 360970 Kr-97 9.21180E-07 9.21180E-07 360970 + 263 370840 Rb-84 4.89640E-10 1.37040E-09 370840 + 264 370841 Rb-84m 8.80760E-10 8.80760E-10 370841 + 265 370850 Rb-85 9.08940E-08 5.75510E-03 37085.82c + 266 370860 Rb-86 2.13610E-06 5.97850E-06 37086.82c + 267 370861 Rb-86m 3.84240E-06 3.84240E-06 370861 + 268 370870 Rb-87 9.54350E-05 9.94670E-03 37087.82c + 269 370880 Rb-88 3.59700E-04 1.33900E-02 370880 + 270 370890 Rb-89 2.21120E-03 1.70070E-02 370890 + 271 370900 Rb-90 5.71450E-04 1.29950E-02 370900 + 272 370901 Rb-90m 5.07520E-03 6.91770E-03 370901 + 273 370910 Rb-91 1.24020E-02 2.07300E-02 370910 + 274 370920 Rb-92 1.33380E-02 1.79570E-02 370920 + 275 370930 Rb-93 1.31150E-02 1.46940E-02 370930 + 276 370940 Rb-94 6.65050E-03 7.08930E-03 370940 + 277 370950 Rb-95 3.49830E-03 3.55220E-03 370950 + 278 370960 Rb-96 3.77570E-04 5.71180E-04 370960 + 279 370961 Rb-96m 3.77570E-04 3.80780E-04 370961 + 280 370970 Rb-97 1.86590E-04 1.87450E-04 370970 + 281 370980 Rb-98 8.87700E-06 8.87700E-06 370980 + 282 370981 Rb-98m 8.87700E-06 8.87700E-06 370981 + 283 370990 Rb-99 3.78600E-06 3.78600E-06 370990 + 284 371000 Rb-100 1.52100E-09 1.52100E-09 371000 + 285 380860 Sr-86 5.83780E-10 5.97880E-06 38086.82c + 286 380870 Sr-87 8.65640E-07 1.06520E-06 38087.82c + 287 380871 Sr-87m 2.00160E-07 2.00160E-07 380871 + 288 380880 Sr-88 1.83160E-05 1.34080E-02 38088.82c + 289 380890 Sr-89 1.14360E-04 1.71210E-02 38089.82c + 290 380900 Sr-90 1.03530E-03 2.07680E-02 38090.82c + 291 380910 Sr-91 3.54940E-03 2.42790E-02 380910 + 292 380920 Sr-92 1.26030E-02 3.07660E-02 380920 + 293 380930 Sr-93 2.24780E-02 3.76830E-02 380930 + 294 380940 Sr-94 3.29970E-02 3.96760E-02 380940 + 295 380950 Sr-95 2.86990E-02 3.20220E-02 380950 + 296 380960 Sr-96 2.04100E-02 2.11420E-02 380960 + 297 380970 Sr-97 8.44700E-03 8.58860E-03 380970 + 298 380980 Sr-98 2.96700E-03 2.98410E-03 380980 + 299 380990 Sr-99 6.62550E-04 6.65730E-04 380990 + 300 381000 Sr-100 1.31590E-04 1.31590E-04 381000 + 301 381010 Sr-101 8.73090E-06 8.73090E-06 381010 + 302 381020 Sr-102 2.03980E-08 2.03980E-08 381020 + 303 390890 Y-89 1.73830E-07 1.71220E-02 39089.82c + 304 390891 Y-89m 7.51780E-07 2.40210E-06 390891 + 305 390900 Y-90 7.70370E-07 2.07700E-02 39090.82c + 306 390901 Y-90m 1.09310E-06 1.09310E-06 390901 + 307 390910 Y-91 5.50440E-06 2.43080E-02 39091.82c + 308 390911 Y-91m 2.38060E-05 1.43080E-02 390911 + 309 390920 Y-92 1.90000E-04 3.09560E-02 390920 + 310 390930 Y-93 2.16240E-04 3.93140E-02 390930 + 311 390931 Y-93m 1.41460E-03 1.08440E-02 390931 + 312 390940 Y-94 4.55440E-03 4.42300E-02 390940 + 313 390950 Y-95 1.50670E-02 4.70890E-02 390950 + 314 390960 Y-96 7.55220E-03 2.86960E-02 390960 + 315 390961 Y-96m 1.35850E-02 1.35870E-02 390961 + 316 390970 Y-97 5.42700E-03 1.29000E-02 390970 + 317 390971 Y-97m 1.84980E-02 2.37510E-02 390971 + 318 390972 Y-97m 4.97050E-03 4.97050E-03 390972 + 319 390980 Y-98 3.66260E-03 6.64670E-03 390980 + 320 390981 Y-98m 1.54030E-02 1.54030E-02 390981 + 321 390990 Y-99 1.43360E-02 1.50030E-02 390990 + 322 391000 Y-100 2.44190E-03 2.57250E-03 391000 + 323 391001 Y-100m 2.44190E-03 2.44200E-03 391001 + 324 391010 Y-101 1.63210E-03 1.64060E-03 391010 + 325 391020 Y-102 1.40650E-04 1.40660E-04 391020 + 326 391021 Y-102m 1.40650E-04 1.40660E-04 391021 + 327 391030 Y-103 4.66660E-05 4.66660E-05 391030 + 328 391040 Y-104 6.80470E-06 6.80470E-06 391040 + 329 391050 Y-105 1.85100E-09 1.85100E-09 391050 + 330 400910 Zr-91 6.75080E-10 2.43080E-02 40091.82c + 331 400920 Zr-92 6.19870E-06 3.09620E-02 40092.82c + 332 400930 Zr-93 3.86470E-05 3.93520E-02 40093.82c + 333 400940 Zr-94 3.74530E-04 4.46050E-02 40094.82c + 334 400950 Zr-95 1.71610E-03 4.88050E-02 40095.82c + 335 400960 Zr-96 7.62080E-03 4.99230E-02 40096.82c + 336 400970 Zr-97 1.52670E-02 5.32750E-02 400970 + 337 400980 Zr-98 3.04780E-02 5.22350E-02 400980 + 338 400990 Zr-99 3.78150E-02 5.25860E-02 400990 + 339 401000 Zr-100 4.21740E-02 4.71650E-02 401000 + 340 401010 Zr-101 2.46610E-02 2.63150E-02 401010 + 341 401020 Zr-102 1.40400E-02 1.43110E-02 401020 + 342 401030 Zr-103 3.70980E-03 3.75330E-03 401030 + 343 401040 Zr-104 1.09290E-03 1.09910E-03 401040 + 344 401050 Zr-105 1.17750E-04 1.17750E-04 401050 + 345 401060 Zr-106 1.67430E-05 1.67430E-05 401060 + 346 401070 Zr-107 7.72830E-09 7.72830E-09 401070 + 347 410940 Nb-94 6.05080E-09 1.02940E-08 41094.82c + 348 410941 Nb-94m 4.26420E-09 4.26420E-09 410941 + 349 410950 Nb-95 3.94150E-06 4.87810E-02 41095.82c + 350 410951 Nb-95m 9.11380E-07 5.28180E-04 410951 + 351 410960 Nb-96 5.86350E-05 5.86350E-05 410960 + 352 410970 Nb-97 4.31850E-04 5.38070E-02 410970 + 353 410971 Nb-97m 9.98550E-05 5.07370E-02 410971 + 354 410980 Nb-98 4.68680E-04 5.27040E-02 410980 + 355 410981 Nb-98m 1.41430E-03 1.41430E-03 410981 + 356 410990 Nb-99 6.75500E-03 4.04080E-02 410990 + 357 410991 Nb-99m 1.56190E-03 2.09140E-02 410991 + 358 411000 Nb-100 2.89050E-03 5.00550E-02 411000 + 359 411001 Nb-100m 1.21570E-02 1.21570E-02 411001 + 360 411010 Nb-101 2.94560E-02 5.57710E-02 411010 + 361 411020 Nb-102 1.51210E-02 2.94320E-02 411020 + 362 411021 Nb-102m 1.51210E-02 1.51210E-02 411021 + 363 411030 Nb-103 3.01340E-02 3.38870E-02 411030 + 364 411040 Nb-104 7.47750E-03 8.57830E-03 411040 + 365 411041 Nb-104m 7.47750E-03 7.47750E-03 411041 + 366 411050 Nb-105 7.14010E-03 7.25650E-03 411050 + 367 411060 Nb-106 1.44820E-03 1.46470E-03 411060 + 368 411070 Nb-107 2.97940E-04 2.97950E-04 411070 + 369 411080 Nb-108 2.15430E-05 2.15430E-05 411080 + 370 411090 Nb-109 3.01210E-06 3.01210E-06 411090 + 371 411100 Nb-110 1.49450E-10 1.49450E-10 411100 + 372 420960 Mo-96 1.89200E-06 6.05270E-05 42096.82c + 373 420970 Mo-97 7.36900E-06 5.38140E-02 42097.82c + 374 420980 Mo-98 7.10100E-05 5.41890E-02 42098.82c + 375 420990 Mo-99 5.06680E-04 6.14100E-02 42099.82c + 376 421000 Mo-100 2.77160E-03 6.49830E-02 42100.82c + 377 421010 Mo-101 7.55410E-03 6.33260E-02 421010 + 378 421020 Mo-102 2.17810E-02 6.63330E-02 421020 + 379 421030 Mo-103 3.17310E-02 6.56270E-02 421030 + 380 421040 Mo-104 4.29160E-02 5.90860E-02 421040 + 381 421050 Mo-105 2.95270E-02 3.67260E-02 421050 + 382 421060 Mo-106 1.83450E-02 1.97620E-02 421060 + 383 421070 Mo-107 5.75130E-03 6.03270E-03 421070 + 384 421080 Mo-108 1.74230E-03 1.76290E-03 421080 + 385 421090 Mo-109 2.87940E-04 2.90570E-04 421090 + 386 421100 Mo-110 3.78270E-05 3.78270E-05 421100 + 387 421110 Mo-111 2.09410E-06 2.09410E-06 421110 + 388 421120 Mo-112 4.68440E-10 4.68440E-10 421120 + 389 430990 Tc-99 1.44550E-08 6.14080E-02 43099.82c + 390 430991 Tc-99m 3.34250E-09 5.40780E-02 430991 + 391 431000 Tc-100 1.79860E-05 1.79860E-05 431000 + 392 431010 Tc-101 9.90080E-05 6.34240E-02 431010 + 393 431020 Tc-102 2.95780E-04 6.66290E-02 431020 + 394 431021 Tc-102m 2.95780E-04 2.95780E-04 431021 + 395 431030 Tc-103 3.02450E-03 6.86520E-02 431030 + 396 431040 Tc-104 7.33420E-03 6.64200E-02 431040 + 397 431050 Tc-105 1.77920E-02 5.45180E-02 431050 + 398 431060 Tc-106 1.83650E-02 3.81270E-02 431060 + 399 431070 Tc-107 1.67220E-02 2.27550E-02 431070 + 400 431080 Tc-108 8.15770E-03 9.92210E-03 431080 + 401 431090 Tc-109 3.88810E-03 4.17710E-03 431090 + 402 431100 Tc-110 1.18030E-03 1.21820E-03 431100 + 403 431110 Tc-111 2.64060E-04 2.66130E-04 431110 + 404 431120 Tc-112 3.83570E-05 3.83570E-05 431120 + 405 431130 Tc-113 2.45180E-05 2.45180E-05 431130 + 406 431140 Tc-114 6.02360E-06 6.02360E-06 431140 + 407 431150 Tc-115 2.40640E-06 2.40640E-06 431150 + 408 441010 Ru-101 2.91040E-06 6.34270E-02 44101.82c + 409 441020 Ru-102 9.25940E-06 6.69340E-02 44102.82c + 410 441030 Ru-103 1.68650E-05 6.87090E-02 44103.82c + 411 441031 Ru-103m 4.07150E-05 4.07150E-05 441031 + 412 441040 Ru-104 5.37070E-04 6.69580E-02 44104.82c + 413 441050 Ru-105 1.83120E-03 5.63490E-02 44105.82c + 414 441060 Ru-106 5.27730E-03 4.34040E-02 44106.82c + 415 441070 Ru-107 7.03210E-03 2.97870E-02 441070 + 416 441080 Ru-108 8.94350E-03 1.88690E-02 441080 + 417 441090 Ru-109 5.65670E-03 9.83100E-03 441090 + 418 441100 Ru-110 3.50750E-03 4.72520E-03 441100 + 419 441110 Ru-111 1.23370E-03 1.50040E-03 441110 + 420 441120 Ru-112 4.36080E-04 4.75620E-04 441120 + 421 441130 Ru-113 6.96150E-05 1.27570E-04 441130 + 422 441131 Ru-113m 6.96150E-05 6.96150E-05 441131 + 423 441140 Ru-114 4.80450E-05 5.40200E-05 441140 + 424 441150 Ru-115 4.81230E-06 6.87370E-06 441150 + 425 441160 Ru-116 3.04480E-06 3.04480E-06 441160 + 426 441170 Ru-117 1.39680E-10 1.39680E-10 441170 + 427 451040 Rh-104 2.82330E-07 1.13320E-06 451040 + 428 451041 Rh-104m 8.51970E-07 8.51970E-07 451041 + 429 451050 Rh-105 9.49280E-06 5.63600E-02 45105.82c + 430 451051 Rh-105m 1.45120E-06 1.59980E-02 451051 + 431 451060 Rh-106 2.16870E-05 4.34260E-02 451060 + 432 451061 Rh-106m 5.07970E-05 5.07970E-05 451061 + 433 451070 Rh-107 2.84720E-04 3.00720E-02 451070 + 434 451080 Rh-108 1.51330E-04 1.90200E-02 451080 + 435 451081 Rh-108m 4.56650E-04 4.56650E-04 451081 + 436 451090 Rh-109 1.19060E-03 1.10220E-02 451090 + 437 451100 Rh-110 1.26790E-03 5.99300E-03 451100 + 438 451101 Rh-110m 3.38440E-05 3.38440E-05 451101 + 439 451110 Rh-111 1.21850E-03 2.71890E-03 451110 + 440 451120 Rh-112 2.99090E-04 7.74720E-04 451120 + 441 451121 Rh-112m 2.99090E-04 2.99090E-04 451121 + 442 451130 Rh-113 4.60770E-04 6.23150E-04 451130 + 443 451140 Rh-114 1.03710E-04 1.57750E-04 451140 + 444 451141 Rh-114m 1.03710E-04 1.03710E-04 451141 + 445 451150 Rh-115 9.19980E-05 9.88890E-05 451150 + 446 451160 Rh-116 1.09620E-05 1.39740E-05 451160 + 447 451161 Rh-116m 2.56750E-05 2.56750E-05 451161 + 448 451170 Rh-117 1.44240E-05 1.44240E-05 451170 + 449 451180 Rh-118 2.47700E-08 2.47700E-08 451180 + 450 451190 Rh-119 1.16970E-09 1.16970E-09 451190 + 451 451200 Rh-120 9.71440E-12 9.71440E-12 451200 + 452 451210 Rh-121 1.67420E-07 1.67420E-07 451210 + 453 451220 Rh-122 9.30670E-09 9.30670E-09 451220 + 454 461060 Pd-106 1.69170E-09 4.34760E-02 46106.82c + 455 461070 Pd-107 1.13650E-06 3.00750E-02 46107.82c + 456 461071 Pd-107m 2.13590E-06 2.13590E-06 461071 + 457 461080 Pd-108 2.15710E-05 1.94980E-02 46108.82c + 458 461090 Pd-109 1.25700E-05 1.10580E-02 461090 + 459 461091 Pd-109m 2.36220E-05 5.53440E-03 461091 + 460 461100 Pd-110 1.12830E-04 6.13970E-03 46110.82c + 461 461110 Pd-111 3.55980E-05 2.80040E-03 461110 + 462 461111 Pd-111m 6.69020E-05 7.77770E-05 461111 + 463 461120 Pd-112 1.78380E-04 1.25220E-03 461120 + 464 461130 Pd-113 5.19080E-05 8.00370E-04 461130 + 465 461131 Pd-113m 1.25310E-04 1.25310E-04 461131 + 466 461140 Pd-114 2.55000E-04 5.16460E-04 461140 + 467 461150 Pd-115 7.47770E-05 1.71700E-04 461150 + 468 461151 Pd-115m 1.40530E-04 1.54890E-04 461151 + 469 461160 Pd-116 2.60320E-04 2.99970E-04 461160 + 470 461170 Pd-117 5.22960E-05 1.65000E-04 461170 + 471 461171 Pd-117m 9.82840E-05 9.82840E-05 461171 + 472 461180 Pd-118 9.32340E-05 9.32580E-05 461180 + 473 461190 Pd-119 2.78320E-05 2.78330E-05 461190 + 474 461200 Pd-120 1.43160E-05 1.43390E-05 461200 + 475 461210 Pd-121 2.88820E-05 2.90270E-05 461210 + 476 461220 Pd-122 1.17290E-05 1.17380E-05 461220 + 477 461230 Pd-123 5.82500E-07 5.82500E-07 461230 + 478 461240 Pd-124 1.42170E-07 1.42170E-07 461240 + 479 471090 Ag-109 3.40950E-10 1.10580E-02 47109.82c + 480 471091 Ag-109m 2.23030E-09 1.10520E-02 471091 + 481 471100 Ag-110 3.14880E-07 3.24910E-07 471100 + 482 471101 Ag-110m 7.37520E-07 7.37520E-07 47510.82c + 483 471110 Ag-111 5.55500E-07 2.81160E-03 47111.82c + 484 471111 Ag-111m 3.63380E-06 2.79920E-03 471111 + 485 471120 Ag-112 3.02900E-06 1.25520E-03 471120 + 486 471130 Ag-113 1.52110E-06 5.32350E-04 471130 + 487 471131 Ag-113m 9.94990E-06 7.76360E-04 471131 + 488 471140 Ag-114 4.63210E-06 5.40570E-04 471140 + 489 471141 Ag-114m 1.94810E-05 1.94810E-05 471141 + 490 471150 Ag-115 6.38730E-06 1.80160E-04 471150 + 491 471151 Ag-115m 4.17830E-05 2.30640E-04 471151 + 492 471160 Ag-116 4.11040E-05 3.46850E-04 471160 + 493 471161 Ag-116m 9.62760E-05 9.62760E-05 471161 + 494 471170 Ag-117 3.39970E-05 1.34790E-04 471170 + 495 471171 Ag-117m 2.22390E-04 3.04900E-04 471171 + 496 471180 Ag-118 4.74540E-05 2.14670E-04 471180 + 497 471181 Ag-118m 1.99580E-04 2.12910E-04 471181 + 498 471190 Ag-119 2.99280E-05 4.38440E-05 471190 + 499 471191 Ag-119m 1.95770E-04 2.09690E-04 471191 + 500 471200 Ag-120 3.39960E-05 6.17450E-05 471200 + 501 471201 Ag-120m 4.82390E-05 5.54080E-05 471201 + 502 471210 Ag-121 9.17310E-05 1.20680E-04 471210 + 503 471220 Ag-122 3.07380E-05 4.24770E-05 471220 + 504 471221 Ag-122m 2.76890E-05 2.76890E-05 471221 + 505 471230 Ag-123 3.13870E-05 3.19690E-05 471230 + 506 471240 Ag-124 5.48670E-06 8.10000E-06 471240 + 507 471241 Ag-124m 4.94230E-06 4.94230E-06 471241 + 508 471250 Ag-125 5.67150E-06 5.67150E-06 471250 + 509 471260 Ag-126 9.21550E-07 9.21550E-07 471260 + 510 471270 Ag-127 1.01250E-07 1.01250E-07 471270 + 511 471280 Ag-128 3.33360E-09 3.33360E-09 471280 + 512 481110 Cd-111 1.83340E-11 2.82560E-03 48111.82c + 513 481111 Cd-111m 5.99840E-11 5.99840E-11 481111 + 514 481120 Cd-112 2.34220E-09 1.25520E-03 48112.82c + 515 481130 Cd-113 8.31240E-09 8.02660E-04 48113.82c + 516 481131 Cd-113m 2.71960E-08 9.23090E-06 481131 + 517 481140 Cd-114 5.88640E-07 5.41160E-04 48114.82c + 518 481150 Cd-115 5.63530E-07 3.47250E-04 481150 + 519 481151 Cd-115m 1.84370E-06 1.75300E-05 48515.82c + 520 481160 Cd-116 2.13450E-05 4.58690E-04 48116.82c + 521 481170 Cd-117 8.44980E-06 3.36030E-04 481170 + 522 481171 Cd-117m 2.76450E-05 1.21460E-04 481171 + 523 481180 Cd-118 1.16610E-04 4.56900E-04 481180 + 524 481190 Cd-119 6.36500E-05 2.95260E-04 481190 + 525 481191 Cd-119m 1.53660E-04 1.75580E-04 481191 + 526 481200 Cd-120 2.80990E-04 3.77640E-04 481200 + 527 481210 Cd-121 6.87670E-05 1.76840E-04 481210 + 528 481211 Cd-121m 1.66010E-04 1.78620E-04 481211 + 529 481220 Cd-122 3.72580E-04 4.42740E-04 481220 + 530 481230 Cd-123 5.33810E-05 7.95410E-05 481230 + 531 481231 Cd-123m 1.28870E-04 1.34690E-04 481231 + 532 481240 Cd-124 5.30580E-04 5.41140E-04 481240 + 533 481250 Cd-125 5.44320E-05 5.72680E-05 481250 + 534 481251 Cd-125m 1.31410E-04 1.34240E-04 481251 + 535 481260 Cd-126 1.83550E-04 1.84470E-04 481260 + 536 481270 Cd-127 8.40020E-05 8.41030E-05 481270 + 537 481280 Cd-128 3.08820E-05 3.08850E-05 481280 + 538 481290 Cd-129 2.79800E-06 2.79800E-06 481290 + 539 481291 Cd-129m 6.75480E-06 6.75480E-06 481291 + 540 481300 Cd-130 1.07970E-07 1.07970E-07 481300 + 541 481310 Cd-131 2.05790E-09 2.05790E-09 481310 + 542 491140 In-114 2.22010E-11 8.68430E-11 491140 + 543 491141 In-114m 3.40290E-11 6.69870E-11 491141 + 544 491142 In-114m 3.29580E-11 3.29580E-11 491142 + 545 491150 In-115 2.73900E-09 3.47420E-04 49115.82c + 546 491151 In-115m 6.33320E-10 3.47250E-04 491151 + 547 491160 In-116 1.88830E-08 1.88830E-08 491160 + 548 491161 In-116m 2.89430E-08 5.69750E-08 491161 + 549 491162 In-116m 2.80320E-08 2.80320E-08 491162 + 550 491170 In-117 1.15620E-06 2.94890E-04 491170 + 551 491171 In-117m 2.67330E-07 3.10070E-04 491171 + 552 491180 In-118 9.31810E-07 4.57830E-04 491180 + 553 491181 In-118m 1.42820E-06 2.79220E-06 491181 + 554 491182 In-118m 1.38330E-06 1.38330E-06 491182 + 555 491190 In-119 8.48500E-06 2.27450E-04 491190 + 556 491191 In-119m 1.96190E-06 2.68900E-04 491191 + 557 491200 In-120 1.19080E-05 3.89550E-04 491200 + 558 491201 In-120m 1.19080E-05 1.19080E-05 491201 + 559 491202 In-120m 1.19080E-05 1.19080E-05 491202 + 560 491210 In-121 6.62350E-05 3.06010E-04 491210 + 561 491211 In-121m 1.53150E-05 1.32590E-04 491211 + 562 491220 In-122 8.58590E-05 5.28600E-04 491220 + 563 491221 In-122m 6.09160E-05 6.09160E-05 491221 + 564 491222 In-122m 6.09160E-05 6.09160E-05 491222 + 565 491230 In-123 1.46830E-04 3.04510E-04 491230 + 566 491231 In-123m 3.39500E-05 9.04980E-05 491231 + 567 491240 In-124 2.74300E-04 8.15440E-04 491240 + 568 491241 In-124m 2.47080E-04 2.47080E-04 491241 + 569 491250 In-125 4.97960E-04 6.59610E-04 491250 + 570 491251 In-125m 1.15140E-04 1.45000E-04 491251 + 571 491260 In-126 6.05540E-04 7.90010E-04 491260 + 572 491261 In-126m 5.45460E-04 5.45460E-04 491261 + 573 491270 In-127 1.16060E-03 1.16060E-03 491270 + 574 491271 In-127m 2.68370E-04 3.52470E-04 491271 + 575 491280 In-128 3.28960E-04 4.93750E-04 491280 + 576 491281 In-128m 1.33910E-04 1.64790E-04 491281 + 577 491282 In-128m 4.16940E-04 4.16940E-04 491282 + 578 491290 In-129 5.39370E-04 5.46120E-04 491290 + 579 491291 In-129m 1.24710E-04 1.27510E-04 491291 + 580 491300 In-130 6.52870E-05 6.53910E-05 491300 + 581 491301 In-130m 7.29190E-05 7.29190E-05 491301 + 582 491302 In-130m 1.24070E-04 1.24070E-04 491302 + 583 491310 In-131 1.81200E-05 1.83070E-05 491310 + 584 491311 In-131m 1.81200E-05 1.81200E-05 491311 + 585 491312 In-131m 1.81200E-05 1.81200E-05 491312 + 586 491320 In-132 1.09550E-06 1.09550E-06 491320 + 587 491330 In-133 2.77650E-08 3.41850E-08 491330 + 588 491331 In-133m 6.41990E-09 6.41990E-09 491331 + 589 501160 Sn-116 1.73230E-11 7.58760E-08 50116.82c + 590 501170 Sn-117 1.33770E-10 4.58910E-04 50117.82c + 591 501171 Sn-117m 4.37640E-10 1.00520E-06 501171 + 592 501180 Sn-118 2.53470E-08 4.60670E-04 50118.82c + 593 501190 Sn-119 8.43880E-08 4.81650E-04 50119.82c + 594 501191 Sn-119m 2.76090E-07 2.05760E-04 501191 + 595 501200 Sn-120 4.45530E-06 4.17820E-04 50120.82c + 596 501210 Sn-121 1.85850E-06 4.34580E-04 501210 + 597 501211 Sn-121m 4.48660E-06 3.91520E-05 501211 + 598 501220 Sn-122 4.10490E-05 6.91480E-04 50122.82c + 599 501230 Sn-123 2.24900E-05 4.57060E-05 50123.82c + 600 501231 Sn-123m 9.31600E-06 3.81110E-04 501231 + 601 501240 Sn-124 1.97540E-04 1.26010E-03 50124.82c + 602 501250 Sn-125 1.95040E-04 3.06460E-04 50125.82c + 603 501251 Sn-125m 8.07910E-05 7.73980E-04 501251 + 604 501260 Sn-126 1.58040E-03 2.91830E-03 50126.82c + 605 501270 Sn-127 2.41010E-03 2.86250E-03 501270 + 606 501271 Sn-127m 9.98320E-04 2.05660E-03 501271 + 607 501280 Sn-128 2.07550E-03 7.84770E-03 501280 + 608 501281 Sn-128m 4.86140E-03 5.27840E-03 501281 + 609 501290 Sn-129 2.33170E-03 2.94730E-03 501290 + 610 501291 Sn-129m 5.62890E-03 5.68710E-03 501291 + 611 501300 Sn-130 2.47910E-03 2.64990E-03 501300 + 612 501301 Sn-130m 5.80680E-03 5.89880E-03 501301 + 613 501310 Sn-131 1.22980E-03 1.26490E-03 501310 + 614 501311 Sn-131m 2.96890E-03 2.98780E-03 501311 + 615 501320 Sn-132 1.63610E-03 1.63720E-03 501320 + 616 501330 Sn-133 1.43190E-04 1.43190E-04 501330 + 617 501340 Sn-134 1.21350E-05 1.21350E-05 501340 + 618 501350 Sn-135 2.24550E-07 2.24550E-07 501350 + 619 501360 Sn-136 5.14750E-09 5.14750E-09 501360 + 620 511190 Sb-119 7.00720E-11 9.23460E-11 511190 + 621 511191 Sb-119m 2.22740E-11 2.22740E-11 511191 + 622 511200 Sb-120 1.05620E-09 1.05620E-09 511200 + 623 511201 Sb-120m 1.49870E-09 1.49870E-09 511201 + 624 511220 Sb-122 7.49500E-12 1.59910E-11 511220 + 625 511221 Sb-122m 8.49600E-12 8.49600E-12 511221 + 626 511230 Sb-123 2.09500E-06 4.28910E-04 51123.82c + 627 511240 Sb-124 2.48610E-06 5.84010E-06 51124.82c + 628 511241 Sb-124m 1.90090E-06 4.47200E-06 511241 + 629 511242 Sb-124m 2.57100E-06 2.57100E-06 511242 + 630 511250 Sb-125 2.41670E-05 1.10460E-03 51125.82c + 631 511260 Sb-126 2.77630E-05 3.43950E-05 51126.82c + 632 511261 Sb-126m 2.05270E-05 4.73730E-05 511261 + 633 511262 Sb-126m 2.68460E-05 2.68460E-05 511262 + 634 511270 Sb-127 4.57000E-04 5.37610E-03 511270 + 635 511280 Sb-128 5.21290E-04 8.40100E-03 511280 + 636 511281 Sb-128m 8.89510E-04 8.89510E-04 511281 + 637 511290 Sb-129 4.62580E-03 1.12670E-02 511290 + 638 511291 Sb-129m 2.82670E-03 5.67020E-03 511291 + 639 511300 Sb-130 7.22300E-03 1.28220E-02 511300 + 640 511301 Sb-130m 7.22300E-03 1.01720E-02 511301 + 641 511310 Sb-131 2.18640E-02 2.61170E-02 511310 + 642 511320 Sb-132 9.56930E-03 1.12060E-02 511320 + 643 511321 Sb-132m 7.05270E-03 7.05270E-03 511321 + 644 511330 Sb-133 1.21390E-02 1.22840E-02 511330 + 645 511340 Sb-134 7.17870E-04 7.27970E-04 511340 + 646 511341 Sb-134m 1.68140E-03 1.68140E-03 511341 + 647 511350 Sb-135 5.47320E-04 5.47500E-04 511350 + 648 511360 Sb-136 5.64480E-05 5.64520E-05 511360 + 649 511370 Sb-137 4.62720E-06 4.62720E-06 511370 + 650 511380 Sb-138 2.41810E-08 2.41810E-08 511380 + 651 521250 Te-125 3.31980E-07 1.10600E-03 52125.82c + 652 521251 Te-125m 1.08610E-06 2.48260E-04 521251 + 653 521260 Te-126 1.52470E-06 7.66610E-05 52126.82c + 654 521270 Te-127 1.78350E-06 5.36080E-03 521270 + 655 521271 Te-127m 4.30550E-06 8.90250E-04 52527.82c + 656 521280 Te-128 8.82410E-05 9.34670E-03 52128.82c + 657 521290 Te-129 1.66740E-04 1.40740E-02 521290 + 658 521291 Te-129m 4.02520E-04 6.97910E-03 52529.82c + 659 521300 Te-130 4.20800E-03 2.72030E-02 52130.82c + 660 521310 Te-131 3.31940E-03 2.94670E-02 521310 + 661 521311 Te-131m 8.01360E-03 1.01050E-02 521311 + 662 521320 Te-132 3.15440E-02 4.98030E-02 52132.82c + 663 521330 Te-133 1.38670E-02 3.02590E-02 521330 + 664 521331 Te-133m 3.34770E-02 3.56020E-02 521331 + 665 521340 Te-134 4.39300E-02 4.64240E-02 521340 + 666 521350 Te-135 1.70330E-02 1.75040E-02 521350 + 667 521360 Te-136 5.64680E-03 5.69620E-03 521360 + 668 521370 Te-137 1.11790E-03 1.12030E-03 521370 + 669 521380 Te-138 1.94780E-04 1.94800E-04 521380 + 670 521390 Te-139 1.59460E-05 1.59460E-05 521390 + 671 521400 Te-140 2.33490E-07 2.33490E-07 521400 + 672 521410 Te-141 2.93180E-09 2.93180E-09 521410 + 673 531270 I-127 1.67910E-10 5.38220E-03 53127.82c + 674 531280 I-128 6.45870E-09 6.45870E-09 531280 + 675 531290 I-129 4.24790E-06 1.66600E-02 53129.82c + 676 531300 I-130 2.24260E-05 3.04680E-05 53130.82c + 677 531301 I-130m 9.57440E-06 9.57440E-06 531301 + 678 531310 I-131 3.22120E-04 3.77720E-02 53131.82c + 679 531320 I-132 8.62690E-04 5.12130E-02 531320 + 680 531321 I-132m 6.35810E-04 6.35810E-04 531321 + 681 531330 I-133 5.31530E-03 6.81930E-02 531330 + 682 531331 I-133m 3.24810E-03 3.24810E-03 531331 + 683 531340 I-134 1.10810E-02 6.54840E-02 531340 + 684 531341 I-134m 8.16690E-03 8.16690E-03 531341 + 685 531350 I-135 4.80370E-02 6.55410E-02 53135.82c + 686 531360 I-136 9.33830E-03 1.50510E-02 531360 + 687 531361 I-136m 2.18730E-02 2.18890E-02 531361 + 688 531370 I-137 2.13330E-02 2.24320E-02 531370 + 689 531380 I-138 5.79460E-03 5.97710E-03 531380 + 690 531390 I-139 2.93140E-03 2.94740E-03 531390 + 691 531400 I-140 4.76530E-04 4.76760E-04 531400 + 692 531410 I-141 7.99140E-05 7.99170E-05 531410 + 693 531420 I-142 4.70810E-06 4.70810E-06 531420 + 694 531430 I-143 1.00710E-06 1.00710E-06 531430 + 695 541300 Xe-130 4.03630E-09 3.20040E-05 54130.82c + 696 541310 Xe-131 5.78620E-08 3.77720E-02 54131.82c + 697 541311 Xe-131m 1.39690E-07 4.10410E-04 541311 + 698 541320 Xe-132 1.43810E-05 5.13320E-02 54132.82c + 699 541321 Xe-132m 1.63010E-05 1.63010E-05 541321 + 700 541330 Xe-133 7.23700E-05 6.84400E-02 54133.82c + 701 541331 Xe-133m 1.74710E-04 2.11580E-03 541331 + 702 541340 Xe-134 5.28570E-04 6.74390E-02 54134.82c + 703 541341 Xe-134m 1.23800E-03 1.42590E-03 541341 + 704 541350 Xe-135 2.54210E-03 7.41180E-02 54135.82c + 705 541351 Xe-135m 6.13690E-03 1.69570E-02 541351 + 706 541360 Xe-136 3.07600E-02 6.91590E-02 54136.82c + 707 541370 Xe-137 3.97650E-02 6.10560E-02 541370 + 708 541380 Xe-138 4.33990E-02 4.93480E-02 541380 + 709 541390 Xe-139 2.83570E-02 3.10600E-02 541390 + 710 541400 Xe-140 1.83130E-02 1.87620E-02 541400 + 711 541410 Xe-141 5.93520E-03 5.99950E-03 541410 + 712 541420 Xe-142 1.58550E-03 1.58940E-03 541420 + 713 541430 Xe-143 2.53740E-04 2.54340E-04 541430 + 714 541440 Xe-144 2.96930E-05 2.96930E-05 541440 + 715 541450 Xe-145 7.65450E-06 7.65450E-06 541450 + 716 541460 Xe-146 1.89420E-09 1.89420E-09 541460 + 717 551330 Cs-133 6.40970E-08 6.84400E-02 55133.82c + 718 551340 Cs-134 3.22520E-06 5.60230E-06 55134.82c + 719 551341 Cs-134m 2.37710E-06 2.37710E-06 551341 + 720 551350 Cs-135 3.86310E-05 7.42820E-02 55135.82c + 721 551351 Cs-135m 2.36070E-05 2.36070E-05 551351 + 722 551360 Cs-136 3.06400E-04 3.96180E-04 55136.82c + 723 551361 Cs-136m 1.79560E-04 1.79560E-04 551361 + 724 551370 Cs-137 4.74000E-03 6.57960E-02 55137.82c + 725 551380 Cs-138 4.29320E-03 5.85760E-02 551380 + 726 551381 Cs-138m 6.09180E-03 6.09180E-03 551381 + 727 551390 Cs-139 2.29940E-02 5.40540E-02 551390 + 728 551400 Cs-140 2.17580E-02 4.05230E-02 551400 + 729 551410 Cs-141 2.75110E-02 3.35140E-02 551410 + 730 551420 Cs-142 1.40060E-02 1.55920E-02 551420 + 731 551430 Cs-143 7.35960E-03 7.61230E-03 551430 + 732 551440 Cs-144 9.93300E-04 1.51900E-03 551440 + 733 551441 Cs-144m 9.93300E-04 9.93490E-04 551441 + 734 551450 Cs-145 4.27360E-04 4.34630E-04 551450 + 735 551460 Cs-146 3.89100E-05 3.89120E-05 551460 + 736 551470 Cs-147 1.77560E-06 1.77560E-06 551470 + 737 551480 Cs-148 7.59650E-09 7.59650E-09 551480 + 738 561350 Ba-135 2.37020E-09 8.09200E-09 56135.82c + 739 561351 Ba-135m 5.72190E-09 5.72190E-09 561351 + 740 561360 Ba-136 7.79770E-07 4.88570E-04 56136.82c + 741 561361 Ba-136m 1.82640E-06 1.82640E-06 561361 + 742 561370 Ba-137 2.14120E-05 6.58690E-02 56137.82c + 743 561371 Ba-137m 5.16920E-05 6.21630E-02 561371 + 744 561380 Ba-138 9.42050E-04 6.06750E-02 56138.82c + 745 561390 Ba-139 3.91340E-03 5.79670E-02 561390 + 746 561400 Ba-140 1.23570E-02 5.28800E-02 56140.82c + 747 561410 Ba-141 1.77140E-02 5.12280E-02 561410 + 748 561420 Ba-142 3.22990E-02 4.80160E-02 561420 + 749 561430 Ba-143 2.95770E-02 3.71130E-02 561430 + 750 561440 Ba-144 2.26850E-02 2.47140E-02 561440 + 751 561450 Ba-145 9.48400E-03 9.86200E-03 561450 + 752 561460 Ba-146 3.86750E-03 3.90140E-03 561460 + 753 561470 Ba-147 9.78250E-04 9.79520E-04 561470 + 754 561480 Ba-148 1.83260E-04 1.83270E-04 561480 + 755 561490 Ba-149 4.38550E-05 4.38550E-05 561490 + 756 561500 Ba-150 9.75300E-07 9.75300E-07 561500 + 757 561510 Ba-151 6.60820E-10 6.60820E-10 561510 + 758 571370 La-137 9.25470E-07 9.25470E-07 571370 + 759 571380 La-138 8.97140E-07 8.97140E-07 57138.82c + 760 571390 La-139 1.27580E-05 5.79800E-02 57139.82c + 761 571400 La-140 1.09260E-04 5.29890E-02 57140.82c + 762 571410 La-141 7.07330E-04 5.19350E-02 571410 + 763 571420 La-142 1.57200E-03 4.95880E-02 571420 + 764 571430 La-143 7.05760E-03 4.41710E-02 571430 + 765 571440 La-144 1.10460E-02 3.57600E-02 571440 + 766 571450 La-145 1.61600E-02 2.60220E-02 571450 + 767 571460 La-146 3.67630E-03 7.57770E-03 571460 + 768 571461 La-146m 6.61270E-03 6.61270E-03 571461 + 769 571470 La-147 7.18220E-03 8.16240E-03 571470 + 770 571480 La-148 2.84440E-03 3.02710E-03 571480 + 771 571490 La-149 1.07400E-03 1.11770E-03 571490 + 772 571500 La-150 1.93160E-04 1.94140E-04 571500 + 773 571510 La-151 3.33640E-05 3.33650E-05 571510 + 774 571520 La-152 1.10030E-06 1.10030E-06 571520 + 775 571530 La-153 1.68820E-06 1.68820E-06 571530 + 776 581400 Ce-140 2.09880E-06 5.29910E-02 58140.82c + 777 581410 Ce-141 2.13020E-06 5.19370E-02 58141.82c + 778 581420 Ce-142 7.07830E-05 4.96590E-02 58142.82c + 779 581430 Ce-143 3.31490E-04 4.45020E-02 58143.82c + 780 581440 Ce-144 1.86240E-03 3.76230E-02 58144.82c + 781 581450 Ce-145 4.42090E-03 3.04430E-02 581450 + 782 581460 Ce-146 1.09080E-02 2.50980E-02 581460 + 783 581470 Ce-147 1.17730E-02 1.99350E-02 581470 + 784 581480 Ce-148 1.21330E-02 1.51760E-02 581480 + 785 581490 Ce-149 7.24660E-03 8.35390E-03 581490 + 786 581500 Ce-150 4.02200E-03 4.21090E-03 581500 + 787 581510 Ce-151 1.33860E-03 1.37200E-03 581510 + 788 581520 Ce-152 3.79340E-04 3.80370E-04 581520 + 789 581530 Ce-153 9.56570E-05 9.73450E-05 581530 + 790 581540 Ce-154 3.88350E-06 3.88350E-06 581540 + 791 581550 Ce-155 6.91190E-09 6.91190E-09 581550 + 792 581560 Ce-156 1.25370E-10 1.25370E-10 581560 + 793 591430 Pr-143 1.00710E-06 4.45030E-02 59143.82c + 794 591440 Pr-144 1.93910E-07 3.76240E-02 591440 + 795 591441 Pr-144m 1.72220E-06 5.20890E-04 591441 + 796 591450 Pr-145 2.87570E-05 3.04720E-02 591450 + 797 591460 Pr-146 1.88350E-04 2.52870E-02 591460 + 798 591470 Pr-147 7.60500E-04 2.06960E-02 591470 + 799 591480 Pr-148 3.02230E-04 1.54780E-02 591480 + 800 591481 Pr-148m 1.27110E-03 1.27110E-03 591481 + 801 591490 Pr-149 3.83060E-03 1.21840E-02 591490 + 802 591500 Pr-150 4.10610E-03 8.31700E-03 591500 + 803 591510 Pr-151 3.87370E-03 5.24570E-03 591510 + 804 591520 Pr-152 1.89870E-03 2.27970E-03 591520 + 805 591530 Pr-153 1.28970E-03 1.38650E-03 591530 + 806 591540 Pr-154 2.62820E-04 2.66680E-04 591540 + 807 591550 Pr-155 4.71950E-05 4.72020E-05 591550 + 808 591560 Pr-156 2.59280E-06 2.59290E-06 591560 + 809 591570 Pr-157 1.89960E-08 1.89960E-08 591570 + 810 591580 Pr-158 3.23450E-10 3.23450E-10 591580 + 811 601450 Nd-145 3.44290E-09 3.04720E-02 60145.82c + 812 601460 Nd-146 1.85490E-06 2.52890E-02 60146.82c + 813 601470 Nd-147 1.77990E-05 2.07140E-02 60147.82c + 814 601480 Nd-148 1.01380E-04 1.68500E-02 60148.82c + 815 601490 Nd-149 3.99420E-04 1.25840E-02 601490 + 816 601500 Nd-150 1.43650E-03 9.75350E-03 60150.82c + 817 601510 Nd-151 2.56100E-03 7.80670E-03 601510 + 818 601520 Nd-152 3.72310E-03 6.00280E-03 601520 + 819 601530 Nd-153 3.78340E-03 5.16990E-03 601530 + 820 601540 Nd-154 1.77730E-03 2.04400E-03 601540 + 821 601550 Nd-155 7.29880E-04 7.77150E-04 601550 + 822 601560 Nd-156 2.12480E-04 2.15000E-04 601560 + 823 601570 Nd-157 7.94950E-05 7.95130E-05 601570 + 824 601580 Nd-158 1.03470E-05 1.03470E-05 601580 + 825 601590 Nd-159 2.24770E-08 2.24770E-08 601590 + 826 601600 Nd-160 6.64280E-10 6.64280E-10 601600 + 827 601610 Nd-161 4.05640E-12 4.05640E-12 601610 + 828 611480 Pm-148 3.11020E-09 3.47440E-09 61148.82c + 829 611481 Pm-148m 7.28480E-09 7.28480E-09 61548.82c + 830 611490 Pm-149 2.74840E-06 1.25870E-02 61149.82c + 831 611500 Pm-150 4.88450E-06 4.88450E-06 611500 + 832 611510 Pm-151 4.26360E-05 7.84940E-03 61151.82c + 833 611520 Pm-152 2.81790E-05 6.03100E-03 611520 + 834 611521 Pm-152m 5.62700E-05 5.62700E-05 611521 + 835 611522 Pm-152m 6.22410E-05 6.22410E-05 611522 + 836 611530 Pm-153 6.59090E-04 5.82900E-03 611530 + 837 611540 Pm-154 3.47800E-04 2.39180E-03 611540 + 838 611541 Pm-154m 3.47800E-04 3.47800E-04 611541 + 839 611550 Pm-155 8.87920E-04 1.66510E-03 611550 + 840 611560 Pm-156 4.84630E-04 6.99630E-04 611560 + 841 611570 Pm-157 3.11870E-04 3.91380E-04 611570 + 842 611580 Pm-158 1.52600E-04 1.62950E-04 611580 + 843 611590 Pm-159 2.66900E-05 2.67120E-05 611590 + 844 611600 Pm-160 2.69280E-06 2.69350E-06 611600 + 845 611610 Pm-161 2.51990E-08 2.52030E-08 611610 + 846 611620 Pm-162 4.94990E-10 4.94990E-10 611620 + 847 611630 Pm-163 1.00320E-11 1.00320E-11 611630 + 848 621500 Sm-150 1.14400E-09 4.88560E-06 62150.82c + 849 621510 Sm-151 3.61250E-08 7.84940E-03 62151.82c + 850 621520 Sm-152 4.40940E-06 6.15390E-03 62152.82c + 851 621530 Sm-153 1.95000E-05 5.89550E-03 62153.82c + 852 621531 Sm-153m 4.70750E-05 4.70750E-05 621531 + 853 621540 Sm-154 1.11980E-04 2.85160E-03 62154.82c + 854 621550 Sm-155 2.36030E-04 1.90110E-03 621550 + 855 621560 Sm-156 4.15610E-04 1.11520E-03 621560 + 856 621570 Sm-157 3.78440E-04 7.69820E-04 621570 + 857 621580 Sm-158 4.66340E-04 6.29290E-04 621580 + 858 621590 Sm-159 1.19840E-04 1.46560E-04 621590 + 859 621600 Sm-160 5.11310E-05 5.38170E-05 621600 + 860 621610 Sm-161 1.10260E-05 1.10510E-05 621610 + 861 621620 Sm-162 9.99340E-07 9.99840E-07 621620 + 862 621630 Sm-163 2.50500E-08 2.50600E-08 621630 + 863 621640 Sm-164 1.66170E-09 1.66170E-09 621640 + 864 621650 Sm-165 1.00920E-11 1.00920E-11 621650 + 865 631530 Eu-153 4.80260E-09 5.89550E-03 63153.82c + 866 631540 Eu-154 3.33740E-08 6.34370E-08 63154.82c + 867 631541 Eu-154m 3.00630E-08 3.00630E-08 631541 + 868 631550 Eu-155 2.80040E-06 1.90390E-03 63155.82c + 869 631560 Eu-156 3.89480E-06 1.11910E-03 63156.82c + 870 631570 Eu-157 2.56490E-05 7.95470E-04 63157.82c + 871 631580 Eu-158 5.81120E-05 6.87400E-04 631580 + 872 631590 Eu-159 6.18260E-05 2.08380E-04 631590 + 873 631600 Eu-160 6.06310E-05 1.14450E-04 631600 + 874 631610 Eu-161 2.20610E-05 3.31120E-05 631610 + 875 631620 Eu-162 9.99170E-06 1.09910E-05 631620 + 876 631630 Eu-163 1.98990E-06 2.01500E-06 631630 + 877 631640 Eu-164 9.50370E-07 9.52030E-07 631640 + 878 631650 Eu-165 1.62230E-08 1.62330E-08 631650 + 879 631660 Eu-166 4.85880E-10 4.85880E-10 631660 + 880 631670 Eu-167 1.54090E-11 1.54090E-11 631670 + 881 641550 Gd-155 4.67170E-11 1.90390E-03 64155.82c + 882 641551 Gd-155m 1.12780E-10 1.12780E-10 641551 + 883 641560 Gd-156 6.60250E-09 1.11910E-03 64156.82c + 884 641570 Gd-157 1.50480E-06 7.96980E-04 64157.82c + 885 641580 Gd-158 1.69380E-06 6.89100E-04 64158.82c + 886 641590 Gd-159 8.15120E-06 2.16530E-04 641590 + 887 641600 Gd-160 1.61690E-05 1.30620E-04 64160.82c + 888 641610 Gd-161 1.56380E-05 4.87500E-05 641610 + 889 641620 Gd-162 1.29940E-05 2.39850E-05 641620 + 890 641630 Gd-163 1.19410E-05 1.39560E-05 641630 + 891 641640 Gd-164 7.60290E-06 8.55490E-06 641640 + 892 641650 Gd-165 8.59690E-07 8.75920E-07 641650 + 893 641660 Gd-166 6.18850E-07 6.19340E-07 641660 + 894 641670 Gd-167 9.21020E-09 9.22560E-09 641670 + 895 641680 Gd-168 8.82020E-10 8.82020E-10 641680 + 896 641690 Gd-169 2.23190E-11 2.23190E-11 641690 + 897 651580 Tb-158 3.48870E-10 3.87910E-10 651580 + 898 651581 Tb-158m 3.92810E-11 3.92810E-11 651581 + 899 651590 Tb-159 5.99930E-09 2.16540E-04 65159.82c + 900 651600 Tb-160 5.44380E-08 5.44380E-08 65160.82c + 901 651610 Tb-161 3.21480E-07 4.90720E-05 651610 + 902 651620 Tb-162 2.99860E-06 2.69840E-05 651620 + 903 651630 Tb-163 9.95090E-07 1.49510E-05 651630 + 904 651640 Tb-164 2.85150E-06 1.14060E-05 651640 + 905 651650 Tb-165 1.71950E-06 2.59540E-06 651650 + 906 651660 Tb-166 6.17700E-07 1.23700E-06 651660 + 907 651670 Tb-167 5.97300E-07 6.06530E-07 651670 + 908 651680 Tb-168 4.91440E-08 5.00260E-08 651680 + 909 651690 Tb-169 8.82410E-09 8.84640E-09 651690 + 910 651700 Tb-170 4.73620E-10 4.73620E-10 651700 + 911 651710 Tb-171 2.47690E-11 2.47690E-11 651710 + 912 661600 Dy-160 1.47620E-11 5.44530E-08 66160.82c + 913 661610 Dy-161 2.05520E-10 4.90720E-05 66161.82c + 914 661620 Dy-162 4.19990E-09 2.69880E-05 66162.82c + 915 661630 Dy-163 2.64380E-08 1.49780E-05 66163.82c + 916 661640 Dy-164 2.43790E-07 1.16500E-05 66164.82c + 917 661650 Dy-165 1.83540E-07 2.80640E-06 661650 + 918 661651 Dy-165m 2.80580E-08 2.80580E-08 661651 + 919 661660 Dy-166 6.18890E-07 1.85590E-06 661660 + 920 661670 Dy-167 2.98350E-07 9.04880E-07 661670 + 921 661680 Dy-168 3.17620E-07 3.67650E-07 661680 + 922 661690 Dy-169 1.00500E-07 1.09350E-07 661690 + 923 661700 Dy-170 3.48070E-08 3.52810E-08 661700 + 924 661710 Dy-171 3.70120E-09 3.72600E-09 661710 + 925 661720 Dy-172 4.50210E-10 4.50210E-10 661720 + 926 661730 Dy-173 1.92630E-11 1.92630E-11 661730 + 927 671630 Ho-163 9.53010E-12 1.09870E-11 671630 + 928 671631 Ho-163m 1.45690E-12 1.45690E-12 671631 + 929 671640 Ho-164 6.72630E-11 2.24810E-10 671640 + 930 671641 Ho-164m 1.57550E-10 1.57550E-10 671641 + 931 671650 Ho-165 1.41630E-09 2.80840E-06 67165.82c + 932 671660 Ho-166 1.75790E-09 1.85770E-06 671660 + 933 671661 Ho-166m 4.11730E-09 4.11730E-09 671661 + 934 671670 Ho-167 2.61990E-08 9.31080E-07 671670 + 935 671680 Ho-168 2.03200E-08 4.16650E-07 671680 + 936 671681 Ho-168m 2.88330E-08 2.88330E-08 671681 + 937 671690 Ho-169 8.77490E-08 1.97100E-07 671690 + 938 671700 Ho-170 3.49070E-08 3.49070E-08 671700 + 939 671701 Ho-170m 1.49030E-08 5.01840E-08 671701 + 940 671710 Ho-171 3.06380E-08 3.43640E-08 671710 + 941 671720 Ho-172 6.81600E-09 7.26620E-09 671720 + 942 671730 Ho-173 1.94930E-09 1.96860E-09 671730 + 943 671740 Ho-174 1.59550E-10 1.59550E-10 671740 + 944 671750 Ho-175 1.58490E-11 1.58490E-11 671750 + 945 681660 Er-166 6.80740E-12 1.85770E-06 68166.82c + 946 681670 Er-167 5.74830E-11 9.31140E-07 68167.82c + 947 681671 Er-167m 8.78740E-12 1.11260E-07 681671 + 948 681680 Er-168 8.82350E-10 4.17680E-07 68168.82c + 949 681690 Er-169 3.10340E-09 2.00200E-07 681690 + 950 681700 Er-170 1.09480E-08 9.60390E-08 68170.82c + 951 681710 Er-171 1.14810E-08 4.58450E-08 681710 + 952 681720 Er-172 1.42150E-08 2.14810E-08 681720 + 953 681730 Er-173 6.75280E-09 8.72140E-09 681730 + 954 681740 Er-174 3.30450E-09 3.46400E-09 681740 + 955 681750 Er-175 6.23350E-10 6.39200E-10 681750 + 956 681760 Er-176 1.38690E-10 1.38690E-10 681760 + 957 681770 Er-177 9.14850E-12 9.14850E-12 681770 + 958 691690 Tm-169 5.19080E-12 2.00200E-07 691690 + 959 691700 Tm-170 3.91920E-11 3.91920E-11 691700 + 960 691710 Tm-171 2.83890E-10 4.61290E-08 691710 + 961 691720 Tm-172 6.68580E-10 2.21500E-08 691720 + 962 691730 Tm-173 1.90170E-09 1.06230E-08 691730 + 963 691740 Tm-174 1.54720E-09 5.01120E-09 691740 + 964 691750 Tm-175 1.62380E-09 2.26300E-09 691750 + 965 691760 Tm-176 6.15140E-10 7.53830E-10 691760 + 966 691770 Tm-177 2.51770E-10 2.60920E-10 691770 + 967 691780 Tm-178 3.28300E-11 3.28300E-11 691780 + 968 691790 Tm-179 5.97720E-12 5.97720E-12 691790 + 969 701720 Yb-172 3.07030E-12 2.21530E-08 701720 + 970 701730 Yb-173 1.82630E-11 1.06410E-08 701730 + 971 701740 Yb-174 9.94600E-11 5.11070E-09 701740 + 972 701750 Yb-175 1.65880E-10 2.45420E-09 701750 + 973 701751 Yb-175m 2.53580E-11 1.76790E-09 701751 + 974 701760 Yb-176 1.49930E-10 1.10880E-09 701760 + 975 701761 Yb-176m 2.69680E-10 6.46600E-10 701761 + 976 701770 Yb-177 2.28700E-10 5.42500E-10 701770 + 977 701771 Yb-177m 5.28810E-11 3.13800E-10 701771 + 978 701780 Yb-178 2.06980E-10 2.39810E-10 701780 + 979 701790 Yb-179 6.63070E-11 7.22840E-11 701790 + 980 701800 Yb-180 2.31710E-11 2.31710E-11 701800 + 981 701810 Yb-181 2.49450E-12 2.49450E-12 701810 + 982 711750 Lu-175 1.24300E-12 2.45550E-09 71175.82c + 983 711760 Lu-176 3.56870E-12 6.82290E-11 71176.82c + 984 711761 Lu-176m 1.98400E-12 1.98400E-12 711761 + 985 711770 Lu-177 1.71550E-11 5.61190E-10 711770 + 986 711771 Lu-177m 6.70660E-12 6.81490E-12 711771 + 987 711780 Lu-178 1.46440E-11 2.54450E-10 711780 + 988 711781 Lu-178m 1.65990E-11 1.65990E-11 711781 + 989 711790 Lu-179 4.90270E-11 1.28810E-10 711790 + 990 711791 Lu-179m 7.49480E-12 7.97790E-11 711791 + 991 711800 Lu-180 9.31760E-12 3.24280E-11 711800 + 992 711801 Lu-180m 9.31760E-12 3.24890E-11 711801 + 993 711802 Lu-180m 1.37320E-11 1.37320E-11 711802 + 994 711810 Lu-181 2.01280E-11 2.26230E-11 711810 + 995 711820 Lu-182 4.53340E-12 4.53340E-12 711820 + 996 711830 Lu-183 1.30750E-12 1.30750E-12 711830 + 997 721790 Hf-179 1.17030E-12 1.30750E-10 72179.82c + 998 721800 Hf-180 2.47750E-12 6.24370E-11 72180.82c + 999 721801 Hf-180m 4.45650E-12 1.13220E-11 721801 + 1000 721810 Hf-181 7.36160E-12 2.99840E-11 721810 + 1001 721820 Hf-182 3.29820E-12 1.03230E-11 721820 + 1002 721821 Hf-182m 5.93280E-12 5.93280E-12 721821 + 1003 721830 Hf-183 4.41840E-12 5.72590E-12 721830 + 1004 721841 Hf-184m 1.40030E-12 1.40030E-12 721841 + 1005 731830 Ta-183 1.21370E-12 6.93960E-12 731830 + 1006 731850 Ta-185 7.12770E-13 1.05800E-12 731850 + + Neutron-induced fission: + + Interpolation region : 2 / 2 + Interpolation energy : 4.00000E-01 MeV + Number of products : 1078 / 1142 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 3.46420E-05 3.46420E-05 1001.82c + 2 10020 H-2 1.05870E-05 1.05870E-05 1002.82c + 3 10030 H-3 1.42000E-04 1.42000E-04 1003.82c + 4 20040 He-4 2.19000E-03 2.19000E-03 2004.82c + 5 190500 K-50 1.69840E-12 1.69840E-12 190500 + 6 200500 Ca-50 3.51900E-11 3.63960E-11 200500 + 7 200510 Ca-51 2.36500E-11 2.36500E-11 200510 + 8 200520 Ca-52 1.85890E-11 1.85890E-11 200520 + 9 200530 Ca-53 4.43900E-12 4.43900E-12 200530 + 10 200540 Ca-54 1.05560E-12 1.05560E-12 200540 + 11 210500 Sc-50 1.25930E-11 5.30960E-11 210500 + 12 210501 Sc-50m 4.62000E-12 4.10160E-11 210501 + 13 210510 Sc-51 6.29390E-11 8.69610E-11 210510 + 14 210520 Sc-52 8.50900E-11 1.04640E-10 210520 + 15 210530 Sc-53 1.23190E-10 1.26300E-10 210530 + 16 210540 Sc-54 5.80840E-11 5.91400E-11 210540 + 17 210550 Sc-55 3.74090E-11 3.74090E-11 210550 + 18 210560 Sc-56 7.37130E-12 7.37130E-12 210560 + 19 210570 Sc-57 1.40420E-12 1.40420E-12 210570 + 20 220500 Ti-50 1.13300E-12 5.47420E-11 22050.82c + 21 220510 Ti-51 7.63650E-12 9.45970E-11 220510 + 22 220520 Ti-52 5.83530E-11 1.62990E-10 220520 + 23 220530 Ti-53 1.39810E-10 2.66110E-10 220530 + 24 220540 Ti-54 3.63410E-10 4.22550E-10 220540 + 25 220550 Ti-55 4.15660E-10 4.53070E-10 220550 + 26 220560 Ti-56 5.14970E-10 5.22810E-10 220560 + 27 220570 Ti-57 2.00580E-10 2.01520E-10 220570 + 28 220580 Ti-58 8.87190E-11 8.87190E-11 220580 + 29 220590 Ti-59 1.39700E-11 1.39700E-11 220590 + 30 220600 Ti-60 2.00470E-12 2.00470E-12 220600 + 31 230530 V-53 1.23220E-11 2.78430E-10 230530 + 32 230540 V-54 5.69500E-11 4.79500E-10 230540 + 33 230550 V-55 3.59330E-10 8.12400E-10 230550 + 34 230560 V-56 7.36590E-10 1.26000E-09 230560 + 35 230570 V-57 1.61990E-09 1.82080E-09 230570 + 36 230580 V-58 1.31910E-09 1.40780E-09 230580 + 37 230590 V-59 1.35180E-09 1.36580E-09 230590 + 38 230600 V-60 4.07320E-10 4.09320E-10 230600 + 39 230610 V-61 1.47160E-10 1.47160E-10 230610 + 40 230620 V-62 1.76620E-11 1.76620E-11 230620 + 41 230630 V-63 2.00470E-12 2.00470E-12 230630 + 42 240540 Cr-54 1.01170E-12 4.80510E-10 24054.82c + 43 240550 Cr-55 1.26720E-11 8.25070E-10 240550 + 44 240560 Cr-56 1.57680E-10 1.42500E-09 240560 + 45 240570 Cr-57 5.97090E-10 3.53690E-09 240570 + 46 240580 Cr-58 2.64600E-09 2.92760E-09 240580 + 47 240590 Cr-59 4.54280E-09 5.90860E-09 240590 + 48 240600 Cr-60 7.97830E-09 8.39650E-09 240600 + 49 240610 Cr-61 5.50390E-09 5.64220E-09 240610 + 50 240620 Cr-62 4.43390E-09 4.45230E-09 240620 + 51 240630 Cr-63 1.08040E-09 1.08170E-09 240630 + 52 240640 Cr-64 2.63870E-10 2.63870E-10 240640 + 53 240650 Cr-65 2.52700E-11 2.52700E-11 240650 + 54 240660 Cr-66 2.32060E-12 2.32060E-12 240660 + 55 250570 Mn-57 1.47090E-11 3.55160E-09 250570 + 56 250580 Mn-58 1.13860E-10 3.04140E-09 250580 + 57 250581 Mn-58m 1.11920E-11 1.11920E-11 250581 + 58 250590 Mn-59 1.25700E-09 7.16560E-09 250590 + 59 250600 Mn-60 3.31880E-10 9.11660E-09 250600 + 60 250601 Mn-60m 3.37620E-09 3.37620E-09 250601 + 61 250610 Mn-61 1.39090E-08 1.95510E-08 250610 + 62 250620 Mn-62 1.66190E-08 1.88460E-08 250620 + 63 250621 Mn-62m 2.60270E-09 4.82880E-09 250621 + 64 250630 Mn-63 2.82940E-08 2.93760E-08 250630 + 65 250640 Mn-64 1.36590E-08 1.39230E-08 250640 + 66 250650 Mn-65 9.01750E-09 9.04280E-09 250650 + 67 250660 Mn-66 1.81370E-09 1.81600E-09 250660 + 68 250670 Mn-67 3.55270E-10 3.55270E-10 250670 + 69 250680 Mn-68 2.29430E-11 2.29430E-11 250680 + 70 250690 Mn-69 2.46470E-12 2.46470E-12 250690 + 71 260590 Fe-59 1.19450E-11 7.17750E-09 260590 + 72 260600 Fe-60 2.30300E-10 1.23350E-08 260600 + 73 260610 Fe-61 1.59800E-09 2.11490E-08 260610 + 74 260620 Fe-62 1.25170E-08 3.61910E-08 260620 + 75 260630 Fe-63 3.05130E-08 5.98890E-08 260630 + 76 260640 Fe-64 8.10570E-08 9.49800E-08 260640 + 77 260650 Fe-65 9.47250E-08 1.03770E-07 260650 + 78 260660 Fe-66 1.19380E-07 1.21200E-07 260660 + 79 260670 Fe-67 4.76850E-08 4.80400E-08 260670 + 80 260680 Fe-68 2.17220E-08 2.17460E-08 260680 + 81 260690 Fe-69 5.12470E-09 5.12660E-09 260690 + 82 260700 Fe-70 2.02300E-10 2.02300E-10 260700 + 83 260710 Fe-71 3.71660E-11 3.71660E-11 260710 + 84 260720 Fe-72 1.04240E-12 1.04240E-12 260720 + 85 270610 Co-61 1.02680E-11 2.11600E-08 270610 + 86 270620 Co-62 4.43020E-11 3.62370E-08 270620 + 87 270621 Co-62m 1.20760E-10 1.20760E-10 270621 + 88 270630 Co-63 2.54180E-09 6.24300E-08 270630 + 89 270640 Co-64 1.20470E-08 1.07030E-07 270640 + 90 270650 Co-65 7.78080E-08 1.81580E-07 270650 + 91 270660 Co-66 1.62160E-07 2.83360E-07 270660 + 92 270670 Co-67 3.64750E-07 4.12790E-07 270670 + 93 270680 Co-68 1.74540E-07 2.50730E-07 270680 + 94 270681 Co-68m 1.30280E-07 1.52380E-07 270681 + 95 270690 Co-69 1.20240E-06 1.20720E-06 270690 + 96 270700 Co-70 1.92900E-08 1.92900E-08 270700 + 97 270701 Co-70m 1.92900E-08 1.94930E-08 270701 + 98 270710 Co-71 5.10510E-08 5.10880E-08 270710 + 99 270720 Co-72 2.95370E-09 2.95470E-09 270720 + 100 270730 Co-73 4.94560E-10 4.94560E-10 270730 + 101 270740 Co-74 1.87850E-11 1.87850E-11 270740 + 102 280630 Ni-63 6.12790E-12 6.24370E-08 280630 + 103 280640 Ni-64 2.01290E-10 1.07230E-07 28064.82c + 104 280650 Ni-65 2.58890E-09 1.84170E-07 280650 + 105 280660 Ni-66 3.28670E-08 3.16220E-07 280660 + 106 280670 Ni-67 1.27650E-07 5.40440E-07 280670 + 107 280680 Ni-68 5.80960E-07 9.19960E-07 280680 + 108 280690 Ni-69 6.01200E-07 1.79630E-06 280690 + 109 280691 Ni-69m 6.01200E-07 6.01200E-07 280691 + 110 280700 Ni-70 1.02890E-06 1.06770E-06 280700 + 111 280710 Ni-71 1.30120E-06 1.35230E-06 280710 + 112 280720 Ni-72 1.39600E-06 1.39890E-06 280720 + 113 280730 Ni-73 2.49980E-07 2.50480E-07 280730 + 114 280740 Ni-74 6.84690E-08 6.84880E-08 280740 + 115 280750 Ni-75 3.55960E-09 3.55960E-09 280750 + 116 280760 Ni-76 6.81390E-10 6.81390E-10 280760 + 117 280770 Ni-77 2.00290E-11 2.00290E-11 280770 + 118 290650 Cu-65 4.12110E-12 1.84170E-07 29065.82c + 119 290660 Cu-66 1.12900E-10 3.16340E-07 290660 + 120 290670 Cu-67 2.96200E-09 5.43400E-07 290670 + 121 290680 Cu-68 6.96500E-09 9.42870E-07 290680 + 122 290681 Cu-68m 1.89850E-08 1.89850E-08 290681 + 123 290690 Cu-69 3.90230E-07 2.78770E-06 290690 + 124 290700 Cu-70 2.13610E-08 1.84990E-07 290700 + 125 290701 Cu-70m 2.72800E-07 3.27250E-07 290701 + 126 290702 Cu-70m 2.13610E-08 1.08900E-06 290702 + 127 290710 Cu-71 5.20490E-06 6.55720E-06 290710 + 128 290720 Cu-72 1.39590E-06 2.79490E-06 290720 + 129 290730 Cu-73 3.98660E-06 4.23710E-06 290730 + 130 290740 Cu-74 1.41030E-06 1.47880E-06 290740 + 131 290750 Cu-75 1.19250E-06 1.19600E-06 290750 + 132 290760 Cu-76 7.14650E-07 7.14990E-07 290760 + 133 290761 Cu-76m 7.14650E-07 7.14990E-07 290761 + 134 290770 Cu-77 1.09500E-07 1.09520E-07 290770 + 135 290780 Cu-78 7.45930E-09 7.45930E-09 290780 + 136 290790 Cu-79 4.87080E-10 4.87080E-10 290790 + 137 290800 Cu-80 1.80450E-11 1.80450E-11 290800 + 138 300670 Zn-67 1.73720E-12 5.43400E-07 300670 + 139 300680 Zn-68 1.09850E-10 9.46020E-07 300680 + 140 300690 Zn-69 5.84540E-10 2.79120E-06 300690 + 141 300691 Zn-69m 2.90320E-09 2.90320E-09 300691 + 142 300700 Zn-70 1.84870E-08 1.40170E-06 300700 + 143 300710 Zn-71 7.87130E-08 6.63590E-06 300710 + 144 300711 Zn-71m 3.90940E-07 3.90940E-07 300711 + 145 300720 Zn-72 2.79180E-06 5.58670E-06 300720 + 146 300730 Zn-73 8.15750E-07 9.86040E-06 300730 + 147 300731 Zn-73m 1.12830E-06 4.80750E-06 300731 + 148 300732 Zn-73m 7.35850E-06 7.35850E-06 300732 + 149 300740 Zn-74 1.97430E-05 2.12640E-05 300740 + 150 300750 Zn-75 1.07090E-05 1.18850E-05 300750 + 151 300760 Zn-76 4.86040E-05 5.00130E-05 300760 + 152 300770 Zn-77 2.12530E-05 2.27780E-05 300770 + 153 300771 Zn-77m 2.82970E-06 2.82970E-06 300771 + 154 300780 Zn-78 2.76560E-05 2.76640E-05 300780 + 155 300790 Zn-79 4.28800E-06 4.28820E-06 300790 + 156 300800 Zn-80 1.71090E-07 1.71110E-07 300800 + 157 300810 Zn-81 6.85860E-09 6.85860E-09 300810 + 158 300820 Zn-82 3.75490E-10 3.75490E-10 300820 + 159 310690 Ga-69 1.30940E-12 2.79120E-06 310690 + 160 310700 Ga-70 1.57110E-11 1.57110E-11 310700 + 161 310710 Ga-71 2.83470E-09 7.02970E-06 310710 + 162 310720 Ga-72 2.00040E-08 5.60860E-06 310720 + 163 310721 Ga-72m 1.96630E-09 1.88120E-07 310721 + 164 310730 Ga-73 4.98460E-07 1.40380E-05 310730 + 165 310740 Ga-74 7.05100E-07 1.71820E-05 310740 + 166 310741 Ga-74m 7.05100E-07 2.19690E-05 310741 + 167 310750 Ga-75 1.07080E-05 2.25930E-05 310750 + 168 310760 Ga-76 2.42940E-05 7.43060E-05 310760 + 169 310770 Ga-77 5.80750E-05 8.22670E-05 310770 + 170 310780 Ga-78 6.98650E-05 9.75850E-05 310780 + 171 310790 Ga-79 7.72290E-05 8.14620E-05 310790 + 172 310800 Ga-80 3.83890E-05 3.85610E-05 310800 + 173 310810 Ga-81 2.26290E-05 2.26350E-05 310810 + 174 310820 Ga-82 1.38410E-06 1.38450E-06 310820 + 175 310830 Ga-83 1.40970E-06 1.40970E-06 310830 + 176 310840 Ga-84 4.98420E-09 4.98420E-09 310840 + 177 310850 Ga-85 2.00560E-10 2.00560E-10 310850 + 178 320720 Ge-72 2.25170E-11 5.60870E-06 32072.82c + 179 320730 Ge-73 9.38610E-10 1.40390E-05 32073.82c + 180 320731 Ge-73m 1.88990E-10 1.38320E-05 320731 + 181 320740 Ge-74 4.15730E-08 2.27150E-05 32074.82c + 182 320750 Ge-75 1.57280E-07 2.39310E-05 320750 + 183 320751 Ge-75m 1.18130E-06 2.08500E-06 320751 + 184 320760 Ge-76 7.14560E-06 8.14520E-05 32076.82c + 185 320770 Ge-77 5.49710E-05 7.19920E-05 320770 + 186 320771 Ge-77m 7.31910E-06 8.95870E-05 320771 + 187 320780 Ge-78 1.45420E-04 2.43080E-04 320780 + 188 320790 Ge-79 3.44160E-05 1.26030E-04 320790 + 189 320791 Ge-79m 2.58480E-04 2.58610E-04 320791 + 190 320800 Ge-80 5.60080E-04 6.01330E-04 320800 + 191 320810 Ge-81 3.46440E-04 3.57910E-04 320810 + 192 320811 Ge-81m 6.97530E-05 7.93110E-05 320811 + 193 320820 Ge-82 4.15230E-04 4.16840E-04 320820 + 194 320830 Ge-83 1.10420E-04 1.11310E-04 320830 + 195 320840 Ge-84 4.06630E-05 4.06640E-05 320840 + 196 320850 Ge-85 1.34930E-06 1.34950E-06 320850 + 197 320860 Ge-86 7.89420E-08 7.89420E-08 320860 + 198 320870 Ge-87 1.66430E-09 1.66430E-09 320870 + 199 330740 As-74 8.58760E-12 8.58760E-12 330740 + 200 330750 As-75 9.04410E-11 2.39320E-05 33075.82c + 201 330751 As-75m 3.42500E-10 9.68000E-10 330751 + 202 330760 As-76 2.47080E-08 2.47080E-08 330760 + 203 330770 As-77 7.26540E-07 1.45280E-04 330770 + 204 330780 As-78 7.27470E-06 2.50350E-04 330780 + 205 330790 As-79 2.57210E-05 4.00010E-04 330790 + 206 330800 As-80 1.45990E-04 7.47320E-04 330800 + 207 330810 As-81 4.50050E-04 8.86480E-04 330810 + 208 330820 As-82 1.59100E-04 5.75940E-04 330820 + 209 330821 As-82m 5.54360E-04 5.54360E-04 330821 + 210 330830 As-83 1.18370E-03 1.29940E-03 330830 + 211 330840 As-84 3.40450E-04 3.58690E-04 330840 + 212 330841 As-84m 3.40450E-04 3.58690E-04 330841 + 213 330850 As-85 3.44100E-04 3.45260E-04 330850 + 214 330860 As-86 6.70970E-05 6.71760E-05 330860 + 215 330870 As-87 2.06210E-05 2.06230E-05 330870 + 216 330880 As-88 1.93160E-06 1.93160E-06 330880 + 217 330890 As-89 2.45030E-08 2.45030E-08 330890 + 218 330900 As-90 5.13130E-10 5.13130E-10 330900 + 219 340760 Se-76 6.08390E-12 2.47140E-08 34076.82c + 220 340770 Se-77 4.70690E-11 1.45280E-04 34077.82c + 221 340771 Se-77m 3.53520E-10 3.53520E-10 340771 + 222 340780 Se-78 2.66220E-08 2.50380E-04 34078.82c + 223 340790 Se-79 4.55790E-07 4.00310E-04 34079.82c + 224 340791 Se-79m 6.06860E-08 3.90600E-04 340791 + 225 340800 Se-80 1.47480E-05 7.62070E-04 34080.82c + 226 340810 Se-81 1.53490E-05 1.01700E-03 340810 + 227 340811 Se-81m 1.15280E-04 1.47100E-04 340811 + 228 340820 Se-82 5.37940E-04 1.66820E-03 34082.82c + 229 340830 Se-83 1.47340E-03 1.94170E-03 340830 + 230 340831 Se-83m 2.96670E-04 1.12880E-03 340831 + 231 340840 Se-84 3.82870E-03 4.62100E-03 340840 + 232 340850 Se-85 3.72780E-03 4.01930E-03 340850 + 233 340860 Se-86 3.15930E-03 3.20750E-03 340860 + 234 340870 Se-87 1.44270E-03 1.46010E-03 340870 + 235 340880 Se-88 5.93110E-04 5.95040E-04 340880 + 236 340890 Se-89 1.18140E-04 1.18170E-04 340890 + 237 340900 Se-90 2.25300E-05 2.25310E-05 340900 + 238 340910 Se-91 9.66640E-07 9.66640E-07 340910 + 239 340920 Se-92 7.80460E-09 7.80460E-09 340920 + 240 350790 Br-79 3.74890E-11 2.18910E-07 35079.82c + 241 350791 Br-79m 1.41970E-10 1.41970E-10 350791 + 242 350800 Br-80 2.21330E-09 9.92520E-09 350800 + 243 350801 Br-80m 7.71190E-09 7.71190E-09 350801 + 244 350810 Br-81 3.89430E-07 1.01750E-03 35081.82c + 245 350820 Br-82 6.07540E-06 8.25080E-06 350820 + 246 350821 Br-82m 2.22890E-06 2.22890E-06 350821 + 247 350830 Br-83 9.17510E-05 3.16230E-03 350830 + 248 350840 Br-84 2.00760E-04 4.82180E-03 350840 + 249 350841 Br-84m 2.00760E-04 2.00760E-04 350841 + 250 350850 Br-85 1.84830E-03 5.86760E-03 350850 + 251 350860 Br-86 3.28070E-03 6.48820E-03 350860 + 252 350870 Br-87 4.77210E-03 6.23810E-03 350870 + 253 350880 Br-88 3.59860E-03 4.19700E-03 350880 + 254 350890 Br-89 2.69650E-03 2.80550E-03 350890 + 255 350900 Br-90 1.10790E-03 1.13060E-03 350900 + 256 350910 Br-91 4.47510E-04 4.48270E-04 350910 + 257 350920 Br-92 6.47340E-05 6.47420E-05 350920 + 258 350930 Br-93 1.62400E-05 1.62400E-05 350930 + 259 350940 Br-94 4.92340E-08 4.92340E-08 350940 + 260 350950 Br-95 1.50200E-09 1.50200E-09 350950 + 261 360810 Kr-81 4.98150E-11 5.64480E-11 360810 + 262 360811 Kr-81m 6.63260E-12 6.63260E-12 360811 + 263 360820 Kr-82 5.69500E-09 8.31000E-06 36082.82c + 264 360830 Kr-83 1.17340E-06 3.16370E-03 36083.82c + 265 360831 Kr-83m 2.36270E-07 3.15970E-03 360831 + 266 360840 Kr-84 2.10160E-05 5.04360E-03 36084.82c + 267 360850 Kr-85 1.48480E-04 1.41800E-03 36085.82c + 268 360851 Kr-85m 2.98970E-05 5.88790E-03 360851 + 269 360860 Kr-86 1.36520E-03 8.01000E-03 36086.82c + 270 360870 Kr-87 3.72440E-03 1.00870E-02 360870 + 271 360880 Kr-88 9.30110E-03 1.36120E-02 360880 + 272 360890 Kr-89 1.21860E-02 1.48740E-02 360890 + 273 360900 Kr-90 1.30480E-02 1.39900E-02 360900 + 274 360910 Kr-91 8.41740E-03 8.79750E-03 360910 + 275 360920 Kr-92 4.60050E-03 4.65490E-03 360920 + 276 360930 Kr-93 1.50470E-03 1.50990E-03 360930 + 277 360940 Kr-94 4.07350E-04 4.07360E-04 360940 + 278 360950 Kr-95 5.78350E-05 5.78370E-05 360950 + 279 360960 Kr-96 9.48000E-06 9.48000E-06 360960 + 280 360970 Kr-97 8.60020E-07 8.60020E-07 360970 + 281 370840 Rb-84 5.10150E-10 1.58040E-09 370840 + 282 370841 Rb-84m 1.07020E-09 1.07020E-09 370841 + 283 370850 Rb-85 1.01880E-07 6.04600E-03 37085.82c + 284 370860 Rb-86 6.88180E-07 2.13190E-06 37086.82c + 285 370861 Rb-86m 1.44370E-06 1.44370E-06 370861 + 286 370870 Rb-87 1.06900E-04 1.01940E-02 37087.82c + 287 370880 Rb-88 4.35730E-04 1.40480E-02 370880 + 288 370890 Rb-89 2.20220E-03 1.70760E-02 370890 + 289 370900 Rb-90 5.20220E-04 1.28660E-02 370900 + 290 370901 Rb-90m 5.29230E-03 7.12220E-03 370901 + 291 370910 Rb-91 1.32480E-02 2.20450E-02 370910 + 292 370920 Rb-92 1.32330E-02 1.78880E-02 370920 + 293 370930 Rb-93 1.28010E-02 1.43160E-02 370930 + 294 370940 Rb-94 6.37310E-03 6.77760E-03 370940 + 295 370950 Rb-95 3.45510E-03 3.51160E-03 370950 + 296 370960 Rb-96 4.20150E-04 6.37110E-04 370960 + 297 370961 Rb-96m 4.20150E-04 4.24740E-04 370961 + 298 370970 Rb-97 1.70620E-04 1.71420E-04 370970 + 299 370980 Rb-98 9.47000E-06 9.47000E-06 370980 + 300 370981 Rb-98m 9.47000E-06 9.47000E-06 370981 + 301 370990 Rb-99 9.21630E-07 9.21630E-07 370990 + 302 371000 Rb-100 1.61290E-09 1.61290E-09 371000 + 303 380860 Sr-86 5.98040E-10 2.13240E-06 38086.82c + 304 380870 Sr-87 9.03240E-07 1.08460E-06 38087.82c + 305 380871 Sr-87m 1.81860E-07 1.81860E-07 380871 + 306 380880 Sr-88 2.41760E-05 1.40720E-02 38088.82c + 307 380890 Sr-89 9.90420E-05 1.71750E-02 38089.82c + 308 380900 Sr-90 1.01250E-03 2.08150E-02 38090.82c + 309 380910 Sr-91 3.57630E-03 2.56220E-02 380910 + 310 380920 Sr-92 1.24250E-02 3.05130E-02 380920 + 311 380930 Sr-93 2.27650E-02 3.75650E-02 380930 + 312 380940 Sr-94 3.21460E-02 3.85410E-02 380940 + 313 380950 Sr-95 2.68040E-02 3.00990E-02 380950 + 314 380960 Sr-96 1.97360E-02 2.05430E-02 380960 + 315 380970 Sr-97 7.65420E-03 7.78390E-03 380970 + 316 380980 Sr-98 3.06370E-03 3.08150E-03 380980 + 317 380990 Sr-99 5.91100E-04 5.91870E-04 380990 + 318 381000 Sr-100 1.26360E-04 1.26360E-04 381000 + 319 381010 Sr-101 1.27960E-05 1.27960E-05 381010 + 320 381020 Sr-102 2.05440E-08 2.05440E-08 381020 + 321 390890 Y-89 1.09520E-09 1.71750E-02 39089.82c + 322 390891 Y-89m 5.43910E-09 1.66100E-06 390891 + 323 390900 Y-90 9.02500E-08 2.08150E-02 39090.82c + 324 390901 Y-90m 1.50930E-07 1.50930E-07 390901 + 325 390910 Y-91 8.43620E-06 2.56720E-02 39091.82c + 326 390911 Y-91m 4.18990E-05 1.51160E-02 390911 + 327 390920 Y-92 2.13330E-04 3.07270E-02 390920 + 328 390930 Y-93 1.83060E-04 3.91230E-02 390930 + 329 390931 Y-93m 1.37490E-03 1.07750E-02 390931 + 330 390940 Y-94 4.39440E-03 4.29360E-02 390940 + 331 390950 Y-95 1.50970E-02 4.51960E-02 390950 + 332 390960 Y-96 6.91630E-03 2.74610E-02 390960 + 333 390961 Y-96m 1.45100E-02 1.45120E-02 390961 + 334 390970 Y-97 4.50940E-03 1.12890E-02 390970 + 335 390971 Y-97m 1.66680E-02 2.24090E-02 390971 + 336 390972 Y-97m 5.72830E-03 5.72830E-03 390972 + 337 390980 Y-98 3.35140E-03 6.43290E-03 390980 + 338 390981 Y-98m 1.62480E-02 1.62480E-02 390981 + 339 390990 Y-99 1.35590E-02 1.41520E-02 390990 + 340 391000 Y-100 2.57870E-03 2.70430E-03 391000 + 341 391001 Y-100m 2.57870E-03 2.57890E-03 391001 + 342 391010 Y-101 1.84960E-03 1.86210E-03 391010 + 343 391020 Y-102 1.38710E-04 1.38720E-04 391020 + 344 391021 Y-102m 1.38710E-04 1.38720E-04 391021 + 345 391030 Y-103 4.97700E-05 4.97700E-05 391030 + 346 391040 Y-104 4.21310E-06 4.21310E-06 391040 + 347 391050 Y-105 1.67210E-09 1.67210E-09 391050 + 348 400910 Zr-91 7.15270E-10 2.56720E-02 40091.82c + 349 400920 Zr-92 2.63430E-06 3.07290E-02 40092.82c + 350 400930 Zr-93 4.87930E-05 3.91710E-02 40093.82c + 351 400940 Zr-94 3.49750E-04 4.32850E-02 40094.82c + 352 400950 Zr-95 1.71320E-03 4.69090E-02 40095.82c + 353 400960 Zr-96 7.55010E-03 4.95410E-02 40096.82c + 354 400970 Zr-97 1.41920E-02 4.94360E-02 400970 + 355 400980 Zr-98 3.27060E-02 5.50510E-02 400980 + 356 400990 Zr-99 3.57540E-02 4.96900E-02 400990 + 357 401000 Zr-100 4.14990E-02 4.67570E-02 401000 + 358 401010 Zr-101 2.44940E-02 2.63700E-02 401010 + 359 401020 Zr-102 1.31440E-02 1.34120E-02 401020 + 360 401030 Zr-103 3.63160E-03 3.67780E-03 401030 + 361 401040 Zr-104 9.27930E-04 9.31770E-04 401040 + 362 401050 Zr-105 1.18740E-04 1.18740E-04 401050 + 363 401060 Zr-106 1.15150E-05 1.15150E-05 401060 + 364 401070 Zr-107 7.35960E-09 7.35960E-09 401070 + 365 410940 Nb-94 6.91630E-09 1.10310E-08 41094.82c + 366 410941 Nb-94m 4.13570E-09 4.13570E-09 410941 + 367 410950 Nb-95 7.90950E-06 4.68900E-02 41095.82c + 368 410951 Nb-95m 1.59250E-06 5.08380E-04 410951 + 369 410960 Nb-96 6.07010E-05 6.07010E-05 410960 + 370 410970 Nb-97 4.11150E-04 4.99300E-02 410970 + 371 410971 Nb-97m 8.27830E-05 4.70710E-02 410971 + 372 410980 Nb-98 4.55540E-04 5.55060E-02 410980 + 373 410981 Nb-98m 1.58730E-03 1.58730E-03 410981 + 374 410990 Nb-99 6.85660E-03 3.86540E-02 410990 + 375 410991 Nb-99m 1.38050E-03 1.96660E-02 410991 + 376 411000 Nb-100 2.93930E-03 4.96970E-02 411000 + 377 411001 Nb-100m 1.42500E-02 1.42500E-02 411001 + 378 411010 Nb-101 3.38100E-02 6.01800E-02 411010 + 379 411020 Nb-102 1.54000E-02 2.88120E-02 411020 + 380 411021 Nb-102m 1.54000E-02 1.54000E-02 411021 + 381 411030 Nb-103 2.75060E-02 3.11840E-02 411030 + 382 411040 Nb-104 6.81450E-03 7.74790E-03 411040 + 383 411041 Nb-104m 6.81450E-03 6.81450E-03 411041 + 384 411050 Nb-105 6.44710E-03 6.56440E-03 411050 + 385 411060 Nb-106 1.36030E-03 1.37160E-03 411060 + 386 411070 Nb-107 2.98330E-04 2.98340E-04 411070 + 387 411080 Nb-108 2.20740E-05 2.20740E-05 411080 + 388 411090 Nb-109 2.24190E-06 2.24190E-06 411090 + 389 411100 Nb-110 1.34840E-10 1.34840E-10 411100 + 390 420960 Mo-96 1.84890E-09 6.07030E-05 42096.82c + 391 420970 Mo-97 2.58010E-06 4.99330E-02 42097.82c + 392 420980 Mo-98 7.40150E-05 5.71680E-02 42098.82c + 393 420990 Mo-99 4.38880E-04 5.83660E-02 42099.82c + 394 421000 Mo-100 2.83670E-03 6.67830E-02 42100.82c + 395 421010 Mo-101 8.53160E-03 6.87110E-02 421010 + 396 421020 Mo-102 2.36140E-02 6.78270E-02 421020 + 397 421030 Mo-103 3.16090E-02 6.28010E-02 421030 + 398 421040 Mo-104 4.24340E-02 5.71000E-02 421040 + 399 421050 Mo-105 2.85580E-02 3.50720E-02 421050 + 400 421060 Mo-106 1.78140E-02 1.91420E-02 421060 + 401 421070 Mo-107 5.85010E-03 6.13190E-03 421070 + 402 421080 Mo-108 1.89900E-03 1.92000E-03 421080 + 403 421090 Mo-109 3.37170E-04 3.39130E-04 421090 + 404 421100 Mo-110 3.58410E-05 3.58410E-05 421100 + 405 421110 Mo-111 6.82100E-06 6.82100E-06 421110 + 406 421120 Mo-112 2.02650E-06 2.02650E-06 421120 + 407 421130 Mo-113 2.30890E-06 2.30890E-06 421130 + 408 430990 Tc-99 7.67180E-07 5.83650E-02 43099.82c + 409 430991 Tc-99m 1.54470E-07 5.13970E-02 430991 + 410 431000 Tc-100 9.95640E-06 9.95640E-06 431000 + 411 431010 Tc-101 1.35580E-04 6.88470E-02 431010 + 412 431020 Tc-102 3.30310E-04 6.81570E-02 431020 + 413 431021 Tc-102m 3.30310E-04 3.30310E-04 431021 + 414 431030 Tc-103 2.84690E-03 6.56480E-02 431030 + 415 431040 Tc-104 6.83490E-03 6.39350E-02 431040 + 416 431050 Tc-105 1.60320E-02 5.11040E-02 431050 + 417 431060 Tc-106 1.70510E-02 3.61930E-02 431060 + 418 431070 Tc-107 1.85300E-02 2.46620E-02 431070 + 419 431080 Tc-108 1.03310E-02 1.22530E-02 431080 + 420 431090 Tc-109 5.67210E-03 6.00940E-03 431090 + 421 431100 Tc-110 1.15180E-03 1.18770E-03 431100 + 422 431110 Tc-111 3.81180E-04 3.87970E-04 431110 + 423 431120 Tc-112 6.22370E-05 6.42210E-05 431120 + 424 431130 Tc-113 4.64750E-05 4.87840E-05 431130 + 425 431140 Tc-114 5.87110E-06 5.87110E-06 431140 + 426 431150 Tc-115 3.54830E-06 3.54830E-06 431150 + 427 441000 Ru-100 9.95560E-07 1.09520E-05 44100.82c + 428 441010 Ru-101 1.92940E-09 6.88470E-02 44101.82c + 429 441020 Ru-102 7.33060E-06 6.84950E-02 44102.82c + 430 441030 Ru-103 1.61050E-05 6.57090E-02 44103.82c + 431 441031 Ru-103m 4.50610E-05 4.50610E-05 441031 + 432 441040 Ru-104 4.51530E-04 6.43860E-02 44104.82c + 433 441050 Ru-105 1.52480E-03 5.26290E-02 44105.82c + 434 441060 Ru-106 4.18240E-03 4.03750E-02 44106.82c + 435 441070 Ru-107 5.94270E-03 3.06050E-02 441070 + 436 441080 Ru-108 8.44090E-03 2.06990E-02 441080 + 437 441090 Ru-109 7.59790E-03 1.36030E-02 441090 + 438 441100 Ru-110 4.36350E-03 5.55070E-03 441100 + 439 441110 Ru-111 2.17260E-03 2.56150E-03 441110 + 440 441120 Ru-112 5.35810E-04 6.02570E-04 441120 + 441 441130 Ru-113 1.26420E-04 2.35280E-04 441130 + 442 441131 Ru-113m 1.26420E-04 1.26420E-04 441131 + 443 441140 Ru-114 1.19470E-04 1.25470E-04 441140 + 444 441150 Ru-115 2.49280E-05 2.79680E-05 441150 + 445 441160 Ru-116 1.25880E-05 1.25880E-05 441160 + 446 441170 Ru-117 1.23050E-10 1.23050E-10 441170 + 447 451040 Rh-104 2.34840E-07 1.05200E-06 451040 + 448 451041 Rh-104m 8.18260E-07 8.18260E-07 451041 + 449 451050 Rh-105 8.72400E-06 5.26390E-02 45105.82c + 450 451051 Rh-105m 1.16160E-06 1.49410E-02 451051 + 451 451060 Rh-106 1.85780E-05 4.03940E-02 451060 + 452 451061 Rh-106m 5.06400E-05 5.06400E-05 451061 + 453 451070 Rh-107 2.30420E-04 3.08350E-02 451070 + 454 451080 Rh-108 1.07300E-04 2.08060E-02 451080 + 455 451081 Rh-108m 3.73880E-04 3.73880E-04 451081 + 456 451090 Rh-109 9.43270E-04 1.45460E-02 451090 + 457 451100 Rh-110 6.79070E-04 6.22980E-03 451100 + 458 451101 Rh-110m 1.59860E-05 1.59860E-05 451101 + 459 451110 Rh-111 1.30610E-03 3.86760E-03 451110 + 460 451120 Rh-112 3.09260E-04 9.11840E-04 451120 + 461 451121 Rh-112m 3.09260E-04 3.09260E-04 451121 + 462 451130 Rh-113 6.90090E-04 9.88580E-04 451130 + 463 451140 Rh-114 1.56100E-04 2.81620E-04 451140 + 464 451141 Rh-114m 1.56100E-04 1.56100E-04 451141 + 465 451150 Rh-115 2.23480E-04 2.51520E-04 451150 + 466 451160 Rh-116 1.51770E-05 2.76290E-05 451160 + 467 451161 Rh-116m 4.13690E-05 4.13690E-05 451161 + 468 451170 Rh-117 1.17980E-05 1.17980E-05 451170 + 469 451180 Rh-118 2.16100E-08 2.16100E-08 451180 + 470 451190 Rh-119 1.23220E-09 1.23220E-09 451190 + 471 451200 Rh-120 1.01950E-11 1.01950E-11 451200 + 472 451210 Rh-121 1.30550E-07 1.30550E-07 451210 + 473 451220 Rh-122 5.12240E-09 5.12240E-09 451220 + 474 461060 Pd-106 1.48540E-09 4.04440E-02 46106.82c + 475 461070 Pd-107 6.33120E-07 3.08370E-02 46107.82c + 476 461071 Pd-107m 1.39160E-06 1.39160E-06 461071 + 477 461080 Pd-108 1.10030E-05 2.11910E-02 46108.82c + 478 461090 Pd-109 1.73020E-05 1.46020E-02 461090 + 479 461091 Pd-109m 3.80300E-05 7.31120E-03 461091 + 480 461100 Pd-110 8.77320E-05 6.33350E-03 46110.82c + 481 461110 Pd-111 5.96690E-05 4.01890E-03 461110 + 482 461111 Pd-111m 1.31150E-04 1.46620E-04 461111 + 483 461120 Pd-112 2.01350E-04 1.42250E-03 461120 + 484 461130 Pd-113 7.13990E-05 1.25980E-03 461130 + 485 461131 Pd-113m 1.99770E-04 1.99770E-04 461131 + 486 461140 Pd-114 4.66400E-04 9.04120E-04 461140 + 487 461150 Pd-115 1.21600E-04 3.60910E-04 461150 + 488 461151 Pd-115m 2.67280E-04 3.03800E-04 461151 + 489 461160 Pd-116 3.26470E-04 3.95470E-04 461160 + 490 461170 Pd-117 4.87590E-05 1.67730E-04 461170 + 491 461171 Pd-117m 1.07170E-04 1.07170E-04 461171 + 492 461180 Pd-118 7.88070E-05 7.88280E-05 461180 + 493 461190 Pd-119 3.37560E-05 3.37570E-05 461190 + 494 461200 Pd-120 1.63840E-05 1.64020E-05 461200 + 495 461210 Pd-121 2.34120E-05 2.35250E-05 461210 + 496 461220 Pd-122 6.57040E-06 6.57550E-06 461220 + 497 461230 Pd-123 5.50770E-07 5.50770E-07 461230 + 498 461240 Pd-124 7.35520E-08 7.35520E-08 461240 + 499 471090 Ag-109 4.01940E-10 1.46020E-02 47109.82c + 500 471091 Ag-109m 3.01890E-09 1.45940E-02 471091 + 501 471100 Ag-110 1.23770E-08 1.28360E-08 471100 + 502 471101 Ag-110m 3.37380E-08 3.37380E-08 47510.82c + 503 471110 Ag-111 1.60180E-07 4.03970E-03 47111.82c + 504 471111 Ag-111m 1.20300E-06 4.01990E-03 471111 + 505 471120 Ag-112 5.06300E-06 1.42750E-03 471120 + 506 471130 Ag-113 3.51970E-06 8.45920E-04 471130 + 507 471131 Ag-113m 2.64350E-05 1.23270E-03 471131 + 508 471140 Ag-114 1.00090E-05 9.62650E-04 471140 + 509 471141 Ag-114m 4.85230E-05 4.85230E-05 471141 + 510 471150 Ag-115 1.41360E-05 3.79050E-04 471150 + 511 471151 Ag-115m 1.06170E-04 4.83110E-04 471151 + 512 471160 Ag-116 5.71800E-05 4.62000E-04 471160 + 513 471161 Ag-116m 1.55860E-04 1.55860E-04 471161 + 514 471170 Ag-117 2.21530E-05 1.21030E-04 471170 + 515 471171 Ag-117m 1.66390E-04 2.50250E-04 471171 + 516 471180 Ag-118 3.34730E-05 1.72190E-04 471180 + 517 471181 Ag-118m 1.62280E-04 1.73550E-04 471181 + 518 471190 Ag-119 2.92170E-05 4.60960E-05 471190 + 519 471191 Ag-119m 2.19440E-04 2.36320E-04 471191 + 520 471200 Ag-120 2.86200E-05 5.76280E-05 471200 + 521 471201 Ag-120m 4.78630E-05 5.60640E-05 471201 + 522 471210 Ag-121 6.59060E-05 8.93670E-05 471210 + 523 471220 Ag-122 2.23420E-05 2.89180E-05 471220 + 524 471221 Ag-122m 2.40880E-05 2.40880E-05 471221 + 525 471230 Ag-123 3.36530E-05 3.42040E-05 471230 + 526 471240 Ag-124 8.35600E-06 1.29340E-05 471240 + 527 471241 Ag-124m 9.00900E-06 9.00900E-06 471241 + 528 471250 Ag-125 2.67600E-06 2.67600E-06 471250 + 529 471260 Ag-126 1.90060E-06 1.90060E-06 471260 + 530 471270 Ag-127 9.91550E-08 9.91550E-08 471270 + 531 471280 Ag-128 3.39580E-09 3.39580E-09 471280 + 532 481110 Cd-111 2.32670E-11 4.05980E-03 48111.82c + 533 481111 Cd-111m 8.81130E-11 8.81130E-11 481111 + 534 481120 Cd-112 2.93540E-09 1.42750E-03 48112.82c + 535 481130 Cd-113 1.29640E-08 1.27510E-03 48113.82c + 536 481131 Cd-113m 4.90930E-08 1.46740E-05 481131 + 537 481140 Cd-114 1.10730E-06 9.63760E-04 48114.82c + 538 481150 Cd-115 1.39510E-06 7.29150E-04 481150 + 539 481151 Cd-115m 5.28310E-06 3.82370E-05 48515.82c + 540 481160 Cd-116 1.56950E-05 6.24200E-04 48116.82c + 541 481170 Cd-117 9.84690E-06 2.87360E-04 481170 + 542 481171 Cd-117m 3.72900E-05 1.16050E-04 481171 + 543 481180 Cd-118 1.25270E-04 3.99850E-04 481180 + 544 481190 Cd-119 5.40790E-05 3.13450E-04 481190 + 545 481191 Cd-119m 1.51310E-04 1.74360E-04 481191 + 546 481200 Cd-120 2.83970E-04 3.76920E-04 481200 + 547 481210 Cd-121 5.39080E-05 1.33940E-04 481210 + 548 481211 Cd-121m 1.50830E-04 1.60170E-04 481211 + 549 481220 Cd-122 2.26100E-04 2.79110E-04 481220 + 550 481230 Cd-123 3.79840E-05 6.59740E-05 481230 + 551 481231 Cd-123m 1.06280E-04 1.12500E-04 481231 + 552 481240 Cd-124 3.02690E-04 3.20120E-04 481240 + 553 481250 Cd-125 6.13250E-05 6.26630E-05 481250 + 554 481251 Cd-125m 1.71590E-04 1.72920E-04 481251 + 555 481260 Cd-126 1.37320E-04 1.39220E-04 481260 + 556 481270 Cd-127 9.88520E-05 9.89510E-05 481270 + 557 481280 Cd-128 2.82460E-05 2.82490E-05 481280 + 558 481290 Cd-129 6.76810E-07 6.76810E-07 481290 + 559 481291 Cd-129m 1.89370E-06 1.89370E-06 481291 + 560 481300 Cd-130 1.09130E-07 1.09130E-07 481300 + 561 481310 Cd-131 2.32790E-09 2.32790E-09 481310 + 562 491140 In-114 4.10700E-11 1.79160E-10 491140 + 563 491141 In-114m 6.63200E-11 1.43100E-10 491141 + 564 491142 In-114m 7.67800E-11 7.67800E-11 491142 + 565 491150 In-115 6.40250E-09 7.30940E-04 49115.82c + 566 491151 In-115m 1.28910E-09 7.29160E-04 491151 + 567 491160 In-116 2.48940E-08 2.48940E-08 491160 + 568 491161 In-116m 4.01980E-08 8.67370E-08 491161 + 569 491162 In-116m 4.65380E-08 4.65380E-08 491162 + 570 491170 In-117 1.10230E-06 2.64370E-04 491170 + 571 491171 In-117m 2.21940E-07 2.65330E-04 491171 + 572 491180 In-118 4.74280E-07 4.00320E-04 491180 + 573 491181 In-118m 7.65860E-07 1.64010E-06 491181 + 574 491182 In-118m 8.86660E-07 8.86660E-07 491182 + 575 491190 In-119 1.53200E-05 2.35810E-04 491190 + 576 491191 In-119m 3.08450E-06 2.86440E-04 491191 + 577 491200 In-120 1.72830E-05 3.94200E-04 491200 + 578 491201 In-120m 1.72830E-05 1.72830E-05 491201 + 579 491202 In-120m 1.72830E-05 1.72830E-05 491202 + 580 491210 In-121 6.26360E-05 2.69130E-04 491210 + 581 491211 In-121m 1.26120E-05 1.01440E-04 491211 + 582 491220 In-122 4.41970E-05 3.23300E-04 491220 + 583 491221 In-122m 3.69570E-05 3.69570E-05 491221 + 584 491222 In-122m 3.69570E-05 3.69570E-05 491222 + 585 491230 In-123 1.80870E-04 3.12440E-04 491230 + 586 491231 In-123m 3.64180E-05 8.33300E-05 491231 + 587 491240 In-124 1.38600E-04 4.58710E-04 491240 + 588 491241 In-124m 1.49430E-04 1.49430E-04 491241 + 589 491250 In-125 6.45580E-04 8.48500E-04 491250 + 590 491251 In-125m 1.29990E-04 1.62660E-04 491251 + 591 491260 In-126 4.66470E-04 6.05700E-04 491260 + 592 491261 In-126m 5.02920E-04 5.02920E-04 491261 + 593 491270 In-127 1.66700E-03 1.66700E-03 491270 + 594 491271 In-127m 3.35650E-04 4.34600E-04 491271 + 595 491280 In-128 4.48850E-04 6.52850E-04 491280 + 596 491281 In-128m 1.75750E-04 2.04000E-04 491281 + 597 491282 In-128m 6.73400E-04 6.73400E-04 491282 + 598 491290 In-129 6.08110E-04 6.10010E-04 491290 + 599 491291 In-129m 1.22440E-04 1.23120E-04 491291 + 600 491300 In-130 7.20960E-05 7.22010E-05 491300 + 601 491301 In-130m 1.04980E-04 1.04980E-04 491301 + 602 491302 In-130m 1.46230E-04 1.46230E-04 491302 + 603 491310 In-131 1.83180E-05 1.85070E-05 491310 + 604 491311 In-131m 1.83180E-05 1.83180E-05 491311 + 605 491312 In-131m 1.83180E-05 1.83180E-05 491312 + 606 491320 In-132 2.28610E-06 2.28610E-06 491320 + 607 491330 In-133 2.65160E-08 3.18550E-08 491330 + 608 491331 In-133m 5.33890E-09 5.33890E-09 491331 + 609 501160 Sn-116 2.33310E-11 1.11650E-07 50116.82c + 610 501170 Sn-117 1.16840E-10 4.04730E-04 50117.82c + 611 501171 Sn-117m 4.42460E-10 9.01180E-07 501171 + 612 501180 Sn-118 2.38810E-08 4.02000E-04 50118.82c + 613 501190 Sn-119 8.45420E-08 5.06620E-04 50119.82c + 614 501191 Sn-119m 3.20160E-07 2.13360E-04 501191 + 615 501200 Sn-120 4.81510E-06 4.33580E-04 50120.82c + 616 501210 Sn-121 1.85660E-06 3.68410E-04 501210 + 617 501211 Sn-121m 5.19460E-06 3.56830E-05 501211 + 618 501220 Sn-122 2.31250E-05 4.20340E-04 50122.82c + 619 501230 Sn-123 3.82720E-05 6.20920E-05 50123.82c + 620 501231 Sn-123m 1.36780E-05 3.85620E-04 501231 + 621 501240 Sn-124 1.33440E-04 7.41580E-04 50124.82c + 622 501250 Sn-125 2.75360E-04 4.18690E-04 50125.82c + 623 501251 Sn-125m 9.84140E-05 9.66240E-04 501251 + 624 501260 Sn-126 1.01800E-03 2.12960E-03 50126.82c + 625 501270 Sn-127 2.24440E-03 2.89410E-03 501270 + 626 501271 Sn-127m 8.02140E-04 2.25100E-03 501271 + 627 501280 Sn-128 1.79670E-03 8.02050E-03 501280 + 628 501281 Sn-128m 4.89750E-03 5.57090E-03 501281 + 629 501290 Sn-129 1.71040E-03 2.37860E-03 501290 + 630 501291 Sn-129m 4.78550E-03 4.85050E-03 501291 + 631 501300 Sn-130 2.92560E-03 3.12330E-03 501300 + 632 501301 Sn-130m 7.97440E-03 8.10050E-03 501301 + 633 501310 Sn-131 1.33560E-03 1.37110E-03 501310 + 634 501311 Sn-131m 3.73710E-03 3.75620E-03 501311 + 635 501320 Sn-132 1.68950E-03 1.69180E-03 501320 + 636 501330 Sn-133 1.68770E-04 1.68770E-04 501330 + 637 501340 Sn-134 1.07740E-05 1.07740E-05 501340 + 638 501350 Sn-135 1.90420E-07 1.90420E-07 501350 + 639 501360 Sn-136 5.20160E-09 5.20160E-09 501360 + 640 511190 Sb-119 8.09750E-11 1.13490E-10 511190 + 641 511191 Sb-119m 3.25150E-11 3.25150E-11 511191 + 642 511200 Sb-120 1.11020E-09 1.11020E-09 511200 + 643 511201 Sb-120m 1.85670E-09 1.85670E-09 511201 + 644 511220 Sb-122 4.20200E-12 9.83160E-12 511220 + 645 511221 Sb-122m 5.62960E-12 5.62960E-12 511221 + 646 511230 Sb-123 1.86740E-06 4.49580E-04 51123.82c + 647 511240 Sb-124 1.12000E-06 2.88250E-06 51124.82c + 648 511241 Sb-124m 9.03480E-07 2.35000E-06 511241 + 649 511242 Sb-124m 1.44650E-06 1.44650E-06 511242 + 650 511250 Sb-125 2.00180E-05 1.40490E-03 51125.82c + 651 511260 Sb-126 3.30830E-05 3.95620E-05 51126.82c + 652 511261 Sb-126m 2.06640E-05 4.62790E-05 511261 + 653 511262 Sb-126m 2.56150E-05 2.56150E-05 511262 + 654 511270 Sb-127 4.95410E-04 5.64060E-03 511270 + 655 511280 Sb-128 6.39360E-04 8.69210E-03 511280 + 656 511281 Sb-128m 8.94240E-04 8.94240E-04 511281 + 657 511290 Sb-129 3.08850E-03 8.59900E-03 511290 + 658 511291 Sb-129m 2.28570E-03 4.71080E-03 511291 + 659 511300 Sb-130 7.50100E-03 1.46750E-02 511300 + 660 511301 Sb-130m 7.50100E-03 1.15510E-02 511301 + 661 511310 Sb-131 2.30210E-02 2.81480E-02 511310 + 662 511320 Sb-132 9.47980E-03 1.11720E-02 511320 + 663 511321 Sb-132m 8.39320E-03 8.39320E-03 511321 + 664 511330 Sb-133 1.29970E-02 1.31680E-02 511330 + 665 511340 Sb-134 7.55920E-04 7.64880E-04 511340 + 666 511341 Sb-134m 2.06050E-03 2.06050E-03 511341 + 667 511350 Sb-135 4.75740E-04 4.75890E-04 511350 + 668 511360 Sb-136 5.77350E-05 5.77390E-05 511360 + 669 511370 Sb-137 5.30260E-06 5.30260E-06 511370 + 670 511380 Sb-138 1.90270E-08 1.90270E-08 511380 + 671 521250 Te-125 2.79420E-07 1.40630E-03 52125.82c + 672 521251 Te-125m 1.05820E-06 3.15440E-04 521251 + 673 521260 Te-126 1.90000E-06 8.12620E-05 52126.82c + 674 521270 Te-127 4.45950E-06 5.63490E-03 521270 + 675 521271 Te-127m 1.24780E-05 9.42010E-04 52527.82c + 676 521280 Te-128 1.09350E-04 9.66350E-03 52128.82c + 677 521290 Te-129 1.40910E-04 1.10180E-02 521290 + 678 521291 Te-129m 3.94270E-04 5.73170E-03 52529.82c + 679 521300 Te-130 4.91030E-03 3.11360E-02 52130.82c + 680 521310 Te-131 3.26120E-03 3.15450E-02 521310 + 681 521311 Te-131m 9.12480E-03 1.13780E-02 521311 + 682 521320 Te-132 3.11480E-02 5.07130E-02 52132.82c + 683 521330 Te-133 1.24260E-02 2.98020E-02 521330 + 684 521331 Te-133m 3.47690E-02 3.70460E-02 521331 + 685 521340 Te-134 4.61080E-02 4.90060E-02 521340 + 686 521350 Te-135 1.52510E-02 1.56620E-02 521350 + 687 521360 Te-136 5.24730E-03 5.29810E-03 521360 + 688 521370 Te-137 9.82390E-04 9.85090E-04 521370 + 689 521380 Te-138 1.44230E-04 1.44250E-04 521380 + 690 521390 Te-139 1.10980E-05 1.10980E-05 521390 + 691 521400 Te-140 1.90090E-07 1.90090E-07 521400 + 692 521410 Te-141 2.79990E-09 2.79990E-09 521410 + 693 531270 I-127 1.87440E-10 5.65750E-03 53127.82c + 694 531280 I-128 9.70230E-09 9.70230E-09 531280 + 695 531290 I-129 4.28250E-06 1.31430E-02 53129.82c + 696 531300 I-130 2.55330E-05 3.34010E-05 53130.82c + 697 531301 I-130m 9.36720E-06 9.36720E-06 531301 + 698 531310 I-131 3.92020E-04 4.09260E-02 53131.82c + 699 531320 I-132 9.56470E-04 5.23980E-02 531320 + 700 531321 I-132m 8.46830E-04 8.46830E-04 531321 + 701 531330 I-133 5.72090E-03 7.03190E-02 531330 + 702 531331 I-133m 4.23370E-03 4.23370E-03 531331 + 703 531340 I-134 1.27050E-02 7.27020E-02 531340 + 704 531341 I-134m 1.12490E-02 1.12490E-02 531341 + 705 531350 I-135 4.95360E-02 6.51980E-02 53135.82c + 706 531360 I-136 7.84800E-03 1.31610E-02 531360 + 707 531361 I-136m 2.13920E-02 2.14070E-02 531361 + 708 531370 I-137 1.87030E-02 1.96680E-02 531370 + 709 531380 I-138 5.08990E-03 5.22510E-03 531380 + 710 531390 I-139 2.67080E-03 2.68190E-03 531390 + 711 531400 I-140 4.36140E-04 4.36330E-04 531400 + 712 531410 I-141 8.00960E-05 8.00990E-05 531410 + 713 531420 I-142 6.63020E-06 6.63020E-06 531420 + 714 531430 I-143 1.97880E-06 1.97880E-06 531430 + 715 541300 Xe-130 7.11710E-09 3.49070E-05 54130.82c + 716 541310 Xe-131 7.53910E-08 4.09270E-02 54131.82c + 717 541311 Xe-131m 2.10940E-07 4.44750E-04 541311 + 718 541320 Xe-132 1.66090E-05 5.25550E-02 54132.82c + 719 541321 Xe-132m 2.22510E-05 2.22510E-05 541321 + 720 541330 Xe-133 7.88740E-05 7.06190E-02 54133.82c + 721 541331 Xe-133m 2.20690E-04 2.22220E-03 541331 + 722 541340 Xe-134 6.06610E-04 7.52200E-02 54134.82c + 723 541341 Xe-134m 1.65350E-03 1.91220E-03 541341 + 724 541350 Xe-135 2.60760E-03 7.49930E-02 54135.82c + 725 541351 Xe-135m 7.29600E-03 1.80590E-02 541351 + 726 541360 Xe-136 3.53690E-02 7.12150E-02 54136.82c + 727 541370 Xe-137 3.93430E-02 5.80090E-02 541370 + 728 541380 Xe-138 4.04040E-02 4.56150E-02 541380 + 729 541390 Xe-139 2.47610E-02 2.72210E-02 541390 + 730 541400 Xe-140 1.68330E-02 1.72460E-02 541400 + 731 541410 Xe-141 5.26800E-03 5.33290E-03 541410 + 732 541420 Xe-142 1.39990E-03 1.40570E-03 541420 + 733 541430 Xe-143 2.25320E-04 2.26510E-04 541430 + 734 541440 Xe-144 3.57470E-05 3.57470E-05 541440 + 735 541450 Xe-145 8.14840E-08 8.14840E-08 541450 + 736 541460 Xe-146 1.85310E-09 1.85310E-09 541460 + 737 551320 Cs-132 1.25350E-09 1.25350E-09 551320 + 738 551330 Cs-133 8.87370E-08 7.06190E-02 55133.82c + 739 551340 Cs-134 2.28560E-06 4.30920E-06 55134.82c + 740 551341 Cs-134m 2.02360E-06 2.02360E-06 551341 + 741 551350 Cs-135 4.53520E-05 7.51800E-02 55135.82c + 742 551351 Cs-135m 3.35620E-05 3.35620E-05 551351 + 743 551360 Cs-136 3.51220E-04 4.76770E-04 55136.82c + 744 551361 Cs-136m 2.51110E-04 2.51110E-04 551361 + 745 551370 Cs-137 5.08900E-03 6.30980E-02 55137.82c + 746 551380 Cs-138 4.06310E-03 5.51820E-02 551380 + 747 551381 Cs-138m 6.79490E-03 6.79490E-03 551381 + 748 551390 Cs-139 2.29280E-02 5.01490E-02 551390 + 749 551400 Cs-140 2.23450E-02 3.95930E-02 551400 + 750 551410 Cs-141 2.58730E-02 3.12090E-02 551410 + 751 551420 Cs-142 1.33740E-02 1.47770E-02 551420 + 752 551430 Cs-143 6.74960E-03 6.97490E-03 551430 + 753 551440 Cs-144 8.85650E-04 1.36320E-03 551440 + 754 551441 Cs-144m 8.85650E-04 8.85650E-04 551441 + 755 551450 Cs-145 4.09240E-04 4.09320E-04 551450 + 756 551460 Cs-146 5.16110E-05 5.16130E-05 551460 + 757 551470 Cs-147 7.41200E-06 7.41200E-06 551470 + 758 551480 Cs-148 6.05600E-09 6.05600E-09 551480 + 759 561350 Ba-135 2.69540E-09 1.02370E-08 56135.82c + 760 561351 Ba-135m 7.54160E-09 7.54160E-09 561351 + 761 561360 Ba-136 1.19260E-06 6.06770E-04 56136.82c + 762 561361 Ba-136m 3.25070E-06 3.25070E-06 561361 + 763 561370 Ba-137 2.11850E-05 6.31790E-02 56137.82c + 764 561371 Ba-137m 5.92730E-05 5.96240E-02 561371 + 765 561380 Ba-138 1.05000E-03 5.75230E-02 56138.82c + 766 561390 Ba-139 3.99890E-03 5.41480E-02 561390 + 767 561400 Ba-140 1.33230E-02 5.29160E-02 56140.82c + 768 561410 Ba-141 1.76640E-02 4.88730E-02 561410 + 769 561420 Ba-142 3.28290E-02 4.77200E-02 561420 + 770 561430 Ba-143 2.77710E-02 3.46750E-02 561430 + 771 561440 Ba-144 2.01840E-02 2.20050E-02 561440 + 772 561450 Ba-145 8.70660E-03 9.06470E-03 561450 + 773 561460 Ba-146 3.40600E-03 3.45240E-03 561460 + 774 561470 Ba-147 8.19270E-04 8.24570E-04 561470 + 775 561480 Ba-148 1.76280E-04 1.76290E-04 561480 + 776 561490 Ba-149 2.03650E-05 2.03650E-05 561490 + 777 561500 Ba-150 4.00760E-06 4.00760E-06 561500 + 778 561510 Ba-151 4.45430E-10 4.45430E-10 561510 + 779 571370 La-137 2.03640E-09 2.03640E-09 571370 + 780 571380 La-138 5.30030E-08 5.30030E-08 57138.82c + 781 571390 La-139 2.01870E-05 5.41680E-02 57139.82c + 782 571400 La-140 1.50840E-04 5.30670E-02 57140.82c + 783 571410 La-141 7.63220E-04 4.96360E-02 571410 + 784 571420 La-142 1.84210E-03 4.95620E-02 571420 + 785 571430 La-143 7.53140E-03 4.22070E-02 571430 + 786 571440 La-144 1.11300E-02 3.31350E-02 571440 + 787 571450 La-145 1.63260E-02 2.53910E-02 571450 + 788 571460 La-146 3.28740E-03 6.73980E-03 571460 + 789 571461 La-146m 6.89660E-03 6.89660E-03 571461 + 790 571470 La-147 6.66940E-03 7.49470E-03 571470 + 791 571480 La-148 2.79200E-03 2.96770E-03 571480 + 792 571490 La-149 1.04900E-03 1.06930E-03 571490 + 793 571500 La-150 2.03630E-04 2.07640E-04 571500 + 794 571510 La-151 3.96860E-05 3.96860E-05 571510 + 795 571520 La-152 8.40780E-08 8.40780E-08 571520 + 796 571530 La-153 2.49180E-09 2.49180E-09 571530 + 797 581400 Ce-140 1.06710E-06 5.30680E-02 58140.82c + 798 581410 Ce-141 7.19150E-06 4.96430E-02 58141.82c + 799 581420 Ce-142 1.02700E-04 4.96650E-02 58142.82c + 800 581430 Ce-143 3.61390E-04 4.25680E-02 58143.82c + 801 581440 Ce-144 1.85950E-03 3.49940E-02 58144.82c + 802 581450 Ce-145 4.72790E-03 3.01190E-02 581450 + 803 581460 Ce-146 1.12810E-02 2.49170E-02 581460 + 804 581470 Ce-147 1.10550E-02 1.85500E-02 581470 + 805 581480 Ce-148 1.21690E-02 1.51520E-02 581480 + 806 581490 Ce-149 7.32790E-03 8.38780E-03 581490 + 807 581500 Ce-150 4.18380E-03 4.38580E-03 581500 + 808 581510 Ce-151 1.32200E-03 1.36170E-03 581510 + 809 581520 Ce-152 3.59250E-04 3.59330E-04 581520 + 810 581530 Ce-153 5.83930E-05 5.83960E-05 581530 + 811 581540 Ce-154 7.80260E-06 7.80260E-06 581540 + 812 581550 Ce-155 5.53650E-09 5.53650E-09 581550 + 813 581560 Ce-156 9.62560E-11 9.62560E-11 581560 + 814 591420 Pr-142 3.14380E-10 1.17130E-09 59142.82c + 815 591421 Pr-142m 8.56920E-10 8.56920E-10 591421 + 816 591430 Pr-143 5.31220E-08 4.25680E-02 59143.82c + 817 591440 Pr-144 9.03140E-07 3.50040E-02 591440 + 818 591441 Pr-144m 9.18790E-06 4.92090E-04 591441 + 819 591450 Pr-145 5.01250E-05 3.01690E-02 591450 + 820 591460 Pr-146 1.85310E-04 2.51030E-02 591460 + 821 591470 Pr-147 7.78580E-04 1.93280E-02 591470 + 822 591480 Pr-148 2.90770E-04 1.54420E-02 591480 + 823 591481 Pr-148m 1.40960E-03 1.40960E-03 591481 + 824 591490 Pr-149 3.99870E-03 1.23860E-02 591490 + 825 591500 Pr-150 4.18690E-03 8.57270E-03 591500 + 826 591510 Pr-151 4.00480E-03 5.36650E-03 591510 + 827 591520 Pr-152 2.02040E-03 2.38010E-03 591520 + 828 591530 Pr-153 1.10250E-03 1.16060E-03 591530 + 829 591540 Pr-154 2.39600E-04 2.47350E-04 591540 + 830 591550 Pr-155 5.04330E-05 5.04390E-05 591550 + 831 591560 Pr-156 6.74170E-06 6.74180E-06 591560 + 832 591570 Pr-157 1.95870E-08 1.95870E-08 591570 + 833 591580 Pr-158 2.13450E-10 2.13450E-10 591580 + 834 601450 Nd-145 4.24390E-09 3.01690E-02 60145.82c + 835 601460 Nd-146 1.84610E-06 2.51050E-02 60146.82c + 836 601470 Nd-147 1.56710E-05 1.93440E-02 60147.82c + 837 601480 Nd-148 1.31270E-04 1.69830E-02 60148.82c + 838 601490 Nd-149 4.63890E-04 1.28500E-02 601490 + 839 601500 Nd-150 1.52210E-03 1.00950E-02 60150.82c + 840 601510 Nd-151 2.63320E-03 7.99970E-03 601510 + 841 601520 Nd-152 3.78320E-03 6.16330E-03 601520 + 842 601530 Nd-153 3.54980E-03 4.71040E-03 601530 + 843 601540 Nd-154 2.00190E-03 2.24920E-03 601540 + 844 601550 Nd-155 8.72670E-04 9.23290E-04 601550 + 845 601560 Nd-156 2.79760E-04 2.86320E-04 601560 + 846 601570 Nd-157 8.94710E-05 8.94890E-05 601570 + 847 601580 Nd-158 1.07220E-06 1.07240E-06 601580 + 848 601590 Nd-159 1.28640E-06 1.28640E-06 601590 + 849 601600 Nd-160 4.74060E-10 4.74060E-10 601600 + 850 601610 Nd-161 3.86390E-12 3.86390E-12 601610 + 851 611470 Pm-147 6.13840E-10 1.93440E-02 61147.82c + 852 611480 Pm-148 4.00940E-09 4.55580E-09 61148.82c + 853 611481 Pm-148m 1.09290E-08 1.09290E-08 61548.82c + 854 611490 Pm-149 1.85300E-06 1.28520E-02 61149.82c + 855 611500 Pm-150 7.01480E-06 7.01480E-06 611500 + 856 611510 Pm-151 5.79910E-05 8.05770E-03 61151.82c + 857 611520 Pm-152 2.71750E-05 6.19050E-03 611520 + 858 611521 Pm-152m 5.71320E-05 5.71320E-05 611521 + 859 611522 Pm-152m 7.46290E-05 7.46290E-05 611522 + 860 611530 Pm-153 5.66910E-04 5.27730E-03 611530 + 861 611540 Pm-154 2.83230E-04 2.53250E-03 611540 + 862 611541 Pm-154m 2.83230E-04 2.83230E-04 611541 + 863 611550 Pm-155 8.35230E-04 1.75850E-03 611550 + 864 611560 Pm-156 5.53030E-04 8.39350E-04 611560 + 865 611570 Pm-157 3.99080E-04 4.88570E-04 611570 + 866 611580 Pm-158 1.28440E-04 1.29510E-04 611580 + 867 611590 Pm-159 2.57340E-05 2.70170E-05 611590 + 868 611600 Pm-160 4.29790E-06 4.29840E-06 611600 + 869 611610 Pm-161 8.70880E-07 8.70880E-07 611610 + 870 611620 Pm-162 4.31320E-10 4.31320E-10 611620 + 871 611630 Pm-163 7.93790E-12 7.93790E-12 611630 + 872 621500 Sm-150 1.92360E-09 7.01670E-06 62150.82c + 873 621510 Sm-151 1.07510E-06 8.05880E-03 62151.82c + 874 621520 Sm-152 1.08660E-05 6.33310E-03 62152.82c + 875 621530 Sm-153 9.53170E-06 5.31350E-03 62153.82c + 876 621531 Sm-153m 2.66690E-05 2.66690E-05 621531 + 877 621540 Sm-154 8.99500E-05 2.90570E-03 62154.82c + 878 621550 Sm-155 2.37940E-04 1.99650E-03 621550 + 879 621560 Sm-156 4.40200E-04 1.27950E-03 621560 + 880 621570 Sm-157 5.31910E-04 1.02050E-03 621570 + 881 621580 Sm-158 4.20460E-04 5.49980E-04 621580 + 882 621590 Sm-159 1.64720E-04 1.91740E-04 621590 + 883 621600 Sm-160 6.01870E-05 6.44740E-05 621600 + 884 621610 Sm-161 1.91630E-05 2.00340E-05 621610 + 885 621620 Sm-162 5.82440E-06 5.82480E-06 621620 + 886 621630 Sm-163 2.22410E-08 2.22490E-08 621630 + 887 621640 Sm-164 1.02880E-09 1.02880E-09 621640 + 888 621650 Sm-165 1.48090E-11 1.48090E-11 621650 + 889 631520 Eu-152 5.76780E-11 1.34070E-10 63152.82c + 890 631521 Eu-152m 1.31790E-11 1.31790E-11 631521 + 891 631522 Eu-152m 7.63930E-11 7.63930E-11 631522 + 892 631530 Eu-153 6.14660E-09 5.31350E-03 63153.82c + 893 631540 Eu-154 4.04840E-08 8.41320E-08 63154.82c + 894 631541 Eu-154m 4.36480E-08 4.36480E-08 631541 + 895 631550 Eu-155 5.04400E-06 2.00150E-03 63155.82c + 896 631560 Eu-156 6.74020E-06 1.28630E-03 63156.82c + 897 631570 Eu-157 3.20400E-05 1.05250E-03 63157.82c + 898 631580 Eu-158 4.17510E-05 5.91730E-04 631580 + 899 631590 Eu-159 8.35590E-05 2.75300E-04 631590 + 900 631600 Eu-160 4.61910E-05 1.10660E-04 631600 + 901 631610 Eu-161 2.61260E-05 4.61600E-05 631610 + 902 631620 Eu-162 9.15230E-06 1.49770E-05 631620 + 903 631630 Eu-163 6.46550E-06 6.48770E-06 631630 + 904 631640 Eu-164 2.54390E-07 2.55420E-07 631640 + 905 631650 Eu-165 2.66250E-08 2.66400E-08 631650 + 906 631660 Eu-166 5.80650E-10 5.80650E-10 631660 + 907 631670 Eu-167 9.37350E-11 9.37350E-11 631670 + 908 641550 Gd-155 7.28870E-11 2.00150E-03 64155.82c + 909 641551 Gd-155m 2.03930E-10 2.03930E-10 641551 + 910 641560 Gd-156 1.09250E-08 1.28630E-03 64156.82c + 911 641570 Gd-157 1.68490E-07 1.05270E-03 64157.82c + 912 641580 Gd-158 7.45770E-06 5.99190E-04 64158.82c + 913 641590 Gd-159 1.92880E-05 2.94590E-04 641590 + 914 641600 Gd-160 1.50390E-05 1.25700E-04 64160.82c + 915 641610 Gd-161 2.17680E-05 6.79280E-05 641610 + 916 641620 Gd-162 1.58070E-05 3.07840E-05 641620 + 917 641630 Gd-163 1.00570E-05 1.65450E-05 641630 + 918 641640 Gd-164 5.91320E-06 6.16860E-06 641640 + 919 641650 Gd-165 3.45670E-06 3.48330E-06 641650 + 920 641660 Gd-166 6.28420E-07 6.29000E-07 641660 + 921 641670 Gd-167 6.26130E-08 6.27070E-08 641670 + 922 641680 Gd-168 8.16590E-10 8.16590E-10 641680 + 923 641690 Gd-169 6.17090E-11 6.17090E-11 641690 + 924 651570 Tb-157 3.37700E-11 3.37700E-11 651570 + 925 651580 Tb-158 4.66430E-10 5.12000E-10 651580 + 926 651581 Tb-158m 4.58490E-11 4.58490E-11 651581 + 927 651590 Tb-159 1.15000E-08 2.94600E-04 65159.82c + 928 651600 Tb-160 6.98780E-08 6.98780E-08 65160.82c + 929 651610 Tb-161 1.74170E-06 6.96700E-05 651610 + 930 651620 Tb-162 1.20330E-06 3.19870E-05 651620 + 931 651630 Tb-163 3.31110E-06 1.98560E-05 651630 + 932 651640 Tb-164 2.53410E-06 8.70270E-06 651640 + 933 651650 Tb-165 8.64160E-07 4.34750E-06 651650 + 934 651660 Tb-166 1.25690E-06 1.88590E-06 651660 + 935 651670 Tb-167 2.44700E-06 2.50970E-06 651670 + 936 651680 Tb-168 5.21030E-08 5.29200E-08 651680 + 937 651690 Tb-169 2.74920E-08 2.75540E-08 651690 + 938 651700 Tb-170 1.71040E-09 1.71040E-09 651700 + 939 651710 Tb-171 1.00790E-10 1.00790E-10 651710 + 940 661600 Dy-160 2.34690E-11 6.99010E-08 66160.82c + 941 661610 Dy-161 4.30820E-10 6.96700E-05 66161.82c + 942 661620 Dy-162 6.53680E-09 3.19940E-05 66162.82c + 943 661630 Dy-163 3.78190E-08 1.98940E-05 66163.82c + 944 661640 Dy-164 8.44710E-07 9.54760E-06 66164.82c + 945 661650 Dy-165 7.62610E-07 5.20940E-06 661650 + 946 661651 Dy-165m 1.01540E-07 1.01540E-07 661651 + 947 661660 Dy-166 7.12630E-07 2.59850E-06 661660 + 948 661670 Dy-167 2.44690E-06 4.95660E-06 661670 + 949 661680 Dy-168 3.70560E-07 4.23480E-07 661680 + 950 661690 Dy-169 3.51660E-07 3.79210E-07 661690 + 951 661700 Dy-170 1.39400E-07 1.41110E-07 661700 + 952 661710 Dy-171 1.69980E-08 1.70990E-08 661710 + 953 661720 Dy-172 2.31530E-09 2.31530E-09 661720 + 954 661730 Dy-173 1.14240E-10 1.14240E-10 661730 + 955 671630 Ho-163 1.63460E-11 1.85220E-11 671630 + 956 671631 Ho-163m 2.17630E-12 2.17630E-12 671631 + 957 671640 Ho-164 7.12470E-11 2.65450E-10 671640 + 958 671641 Ho-164m 1.94200E-10 1.94200E-10 671641 + 959 671650 Ho-165 3.83410E-09 5.21550E-06 67165.82c + 960 671660 Ho-166 3.06220E-09 2.60160E-06 671660 + 961 671661 Ho-166m 8.34680E-09 8.34680E-09 671661 + 962 671670 Ho-167 2.55720E-07 5.21230E-06 671670 + 963 671680 Ho-168 1.66680E-07 8.67530E-07 671680 + 964 671681 Ho-168m 2.78760E-07 2.78760E-07 671681 + 965 671690 Ho-169 3.45330E-07 7.24540E-07 671690 + 966 671700 Ho-170 1.66710E-07 1.66710E-07 671700 + 967 671701 Ho-170m 6.11600E-08 2.02270E-07 671701 + 968 671710 Ho-171 1.58730E-07 1.75830E-07 671710 + 969 671720 Ho-172 4.03670E-08 4.26820E-08 671720 + 970 671730 Ho-173 1.31360E-08 1.32500E-08 671730 + 971 671740 Ho-174 1.24870E-09 1.24870E-09 671740 + 972 671750 Ho-175 1.37610E-10 1.37610E-10 671750 + 973 681660 Er-166 1.54870E-11 2.60160E-06 68166.82c + 974 681670 Er-167 6.71990E-10 5.21310E-06 68167.82c + 975 681671 Er-167m 8.94720E-11 6.22920E-07 681671 + 976 681680 Er-168 1.35820E-09 8.70280E-07 68168.82c + 977 681690 Er-169 1.40700E-08 7.38610E-07 681690 + 978 681700 Er-170 5.61130E-08 4.25090E-07 68170.82c + 979 681710 Er-171 6.71140E-08 2.42940E-07 681710 + 980 681720 Er-172 9.31370E-08 1.35820E-07 681720 + 981 681730 Er-173 5.12600E-08 6.45100E-08 681730 + 982 681740 Er-174 2.88010E-08 3.00500E-08 681740 + 983 681750 Er-175 6.15010E-09 6.28770E-09 681750 + 984 681760 Er-176 1.53340E-09 1.53340E-09 681760 + 985 681770 Er-177 1.16960E-10 1.16960E-10 681770 + 986 691690 Tm-169 2.80640E-11 7.38640E-07 691690 + 987 691700 Tm-170 2.40900E-10 2.40900E-10 691700 + 988 691710 Tm-171 1.93690E-09 2.44880E-07 691710 + 989 691720 Tm-172 5.13290E-09 1.40950E-07 691720 + 990 691730 Tm-173 1.64610E-08 8.09710E-08 691730 + 991 691740 Tm-174 1.55220E-08 4.55720E-08 691740 + 992 691750 Tm-175 1.81360E-08 2.44240E-08 691750 + 993 691760 Tm-176 7.85550E-09 9.38890E-09 691760 + 994 691770 Tm-177 3.67600E-09 3.79300E-09 691770 + 995 691780 Tm-178 5.50360E-10 5.50360E-10 691780 + 996 691790 Tm-179 1.11630E-10 1.11630E-10 691790 + 997 701710 Yb-171 1.68910E-13 2.44880E-07 701710 + 998 701711 Yb-171m 1.26860E-12 1.26860E-12 701711 + 999 701720 Yb-172 2.75420E-11 1.40980E-07 701720 + 1000 701730 Yb-173 1.85790E-10 8.11570E-08 701730 + 1001 701740 Yb-174 1.14030E-09 4.67130E-08 701740 + 1002 701750 Yb-175 2.16240E-09 2.68740E-08 701750 + 1003 701751 Yb-175m 2.87910E-10 1.90940E-08 701751 + 1004 701760 Yb-176 1.93410E-09 1.45060E-08 701760 + 1005 701761 Yb-176m 4.05760E-09 8.75210E-09 701761 + 1006 701770 Yb-177 3.87440E-09 8.44750E-09 701770 + 1007 701771 Yb-177m 7.80090E-10 4.57310E-09 701771 + 1008 701780 Yb-178 3.87400E-09 4.42440E-09 701780 + 1009 701790 Yb-179 1.41230E-09 1.52390E-09 701790 + 1010 701800 Yb-180 5.61580E-10 5.61580E-10 701800 + 1011 701810 Yb-181 6.87880E-11 6.87880E-11 701810 + 1012 711740 Lu-174 3.34370E-13 1.24050E-12 711740 + 1013 711750 Lu-175 1.89580E-11 2.68930E-08 71175.82c + 1014 711760 Lu-176 6.42120E-11 9.39420E-10 71176.82c + 1015 711761 Lu-176m 3.06080E-11 3.06080E-11 711761 + 1016 711770 Lu-177 3.08420E-10 8.78990E-09 711770 + 1017 711771 Lu-177m 1.46860E-10 1.50510E-10 711771 + 1018 711772 Lu-177m 7.30810E-12 7.30810E-12 711772 + 1019 711780 Lu-178 2.91760E-10 4.71610E-09 711780 + 1020 711781 Lu-178m 3.90880E-10 3.90880E-10 711781 + 1021 711790 Lu-179 1.21180E-09 2.89710E-09 711790 + 1022 711791 Lu-179m 1.61350E-10 1.68530E-09 711791 + 1023 711800 Lu-180 2.41000E-10 8.55670E-10 711800 + 1024 711801 Lu-180m 2.41000E-10 8.02580E-10 711801 + 1025 711802 Lu-180m 4.26750E-10 4.26750E-10 711802 + 1026 711810 Lu-181 6.35530E-10 7.04320E-10 711810 + 1027 711820 Lu-182 1.62420E-10 1.62420E-10 711820 + 1028 711830 Lu-183 5.30390E-11 5.30390E-11 711830 + 1029 711840 Lu-184 5.06090E-12 5.06090E-12 711840 + 1030 721770 Hf-177 9.07120E-13 8.91140E-09 72177.82c + 1031 721771 Hf-177m 4.27980E-13 1.20600E-10 721771 + 1032 721772 Hf-177m 2.53030E-14 3.67940E-12 721772 + 1033 721780 Hf-178 4.48300E-12 5.12090E-09 72178.82c + 1034 721781 Hf-178m 8.36060E-12 4.00290E-10 721781 + 1035 721782 Hf-178m 1.04580E-12 1.04580E-12 721782 + 1036 721790 Hf-179 3.20450E-11 2.95250E-09 72179.82c + 1037 721791 Hf-179m 9.27260E-12 9.27260E-12 721791 + 1038 721792 Hf-179m 1.40090E-11 1.40090E-11 721792 + 1039 721800 Hf-180 7.14810E-11 1.69060E-09 72180.82c + 1040 721801 Hf-180m 1.49960E-10 3.63340E-10 721801 + 1041 721810 Hf-181 2.66040E-10 9.70360E-10 721810 + 1042 721820 Hf-182 1.19760E-10 3.87710E-10 721820 + 1043 721821 Hf-182m 2.51250E-10 2.51250E-10 721821 + 1044 721830 Hf-183 2.04850E-10 2.57890E-10 721830 + 1045 721840 Hf-184 3.72640E-11 3.97940E-11 721840 + 1046 721841 Hf-184m 7.81760E-11 8.07060E-11 721841 + 1047 721850 Hf-185 2.47800E-11 2.47800E-11 721850 + 1048 721860 Hf-186 6.20810E-12 6.20810E-12 721860 + 1049 731810 Ta-181 7.58910E-12 9.77950E-10 73181.82c + 1050 731820 Ta-182 6.52860E-12 1.65950E-10 73182.82c + 1051 731821 Ta-182m 7.13130E-12 1.59420E-10 731821 + 1052 731822 Ta-182m 6.56710E-12 1.52290E-10 731822 + 1053 731830 Ta-183 6.51160E-11 3.23010E-10 731830 + 1054 731840 Ta-184 6.16040E-11 1.82100E-10 731840 + 1055 731850 Ta-185 4.53040E-11 9.71160E-11 731850 + 1056 731851 Ta-185m 2.70320E-11 2.70320E-11 731851 + 1057 731860 Ta-186 3.14690E-11 3.76770E-11 731860 + 1058 731870 Ta-187 1.47730E-11 1.47730E-11 731870 + 1059 731880 Ta-188 2.22180E-12 2.22180E-12 731880 + 1060 741840 W-184 4.47470E-12 1.86580E-10 74184.82c + 1061 741850 W-185 2.54620E-12 1.06790E-10 741850 + 1062 741851 W-185m 7.12410E-12 7.12410E-12 741851 + 1063 741860 W-186 1.69150E-11 6.14410E-11 74186.82c + 1064 741861 W-186m 6.84880E-12 6.84880E-12 741861 + 1065 741870 W-187 1.85200E-11 3.32930E-11 741870 + 1066 741880 W-188 1.54780E-11 1.77000E-11 741880 + 1067 741890 W-189 5.66680E-12 5.66680E-12 741890 + 1068 741900 W-190 9.66390E-13 2.26110E-12 741900 + 1069 741901 W-190m 1.29470E-12 1.29470E-12 741901 + 1070 751870 Re-187 1.82040E-12 3.51130E-11 75187.82c + 1071 751880 Re-188 7.24570E-13 2.03990E-11 751880 + 1072 751881 Re-188m 1.97500E-12 1.97500E-12 751881 + 1073 751890 Re-189 5.45540E-12 1.11220E-11 751890 + 1074 751900 Re-190 1.16930E-12 4.54900E-12 751900 + 1075 751901 Re-190m 2.45300E-12 2.45300E-12 751901 + 1076 751910 Re-191 2.54390E-12 2.54390E-12 751910 + 1077 761910 Os-191 8.33980E-13 3.59810E-12 761910 + 1078 761920 Os-192 6.31570E-13 1.37300E-12 761920 + + Nuclide 94240.82c -- plutonium 240 (Pu-240) + + Neutron-induced fission: + + Interpolation region : 1 / 1 + Interpolation energy : 4.00000E-01 MeV + Number of products : 950 / 1036 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 4.39890E-05 4.39890E-05 1001.82c + 2 10020 H-2 1.34430E-05 1.34430E-05 1002.82c + 3 10030 H-3 1.91790E-04 1.91790E-04 1003.82c + 4 20040 He-4 2.78090E-03 2.78090E-03 2004.82c + 5 220560 Ti-56 1.56370E-12 1.56370E-12 220560 + 6 230560 V-56 1.91200E-12 3.47570E-12 230560 + 7 230570 V-57 6.11000E-12 6.11000E-12 230570 + 8 230580 V-58 5.81490E-12 5.81490E-12 230580 + 9 230590 V-59 9.08550E-12 9.08550E-12 230590 + 10 230600 V-60 2.88940E-12 2.88940E-12 230600 + 11 230610 V-61 1.50510E-12 1.50510E-12 230610 + 12 240570 Cr-57 1.72850E-12 1.24660E-11 240570 + 13 240580 Cr-58 1.21090E-11 1.32720E-11 240580 + 14 240590 Cr-59 2.52140E-11 3.43000E-11 240590 + 15 240600 Cr-60 6.34130E-11 6.63930E-11 240600 + 16 240610 Cr-61 5.09950E-11 5.24100E-11 240610 + 17 240620 Cr-62 6.34870E-11 6.34870E-11 240620 + 18 240630 Cr-63 1.68880E-11 1.68880E-11 240630 + 19 240640 Cr-64 5.74220E-12 5.74220E-12 240640 + 20 250590 Mn-59 6.78000E-12 4.10790E-11 250590 + 21 250600 Mn-60 2.05750E-12 7.08570E-11 250600 + 22 250601 Mn-60m 2.09310E-11 2.09310E-11 250601 + 23 250610 Mn-61 1.35580E-10 1.87990E-10 250610 + 24 250620 Mn-62 1.99220E-10 2.30960E-10 250620 + 25 250621 Mn-62m 3.11990E-11 6.29420E-11 250621 + 26 250630 Mn-63 5.03830E-10 5.20720E-10 250630 + 27 250640 Mn-64 2.74550E-10 2.80290E-10 250640 + 28 250650 Mn-65 2.83620E-10 2.83620E-10 250650 + 29 250660 Mn-66 6.28540E-11 6.28540E-11 250660 + 30 250670 Mn-67 1.72190E-11 1.72190E-11 250670 + 31 250680 Mn-68 1.24490E-12 1.24490E-12 250680 + 32 260600 Fe-60 1.19850E-12 9.05800E-11 260600 + 33 260610 Fe-61 1.07130E-11 1.98700E-10 260610 + 34 260620 Fe-62 1.41610E-10 4.35520E-10 260620 + 35 260630 Fe-63 4.09690E-10 9.30410E-10 260630 + 36 260640 Fe-64 1.65370E-09 1.93400E-09 260640 + 37 260650 Fe-65 2.41040E-09 2.69400E-09 260650 + 38 260660 Fe-66 4.56840E-09 4.63120E-09 260660 + 39 260670 Fe-67 2.07470E-09 2.09190E-09 260670 + 40 260680 Fe-68 1.46840E-09 1.46960E-09 260680 + 41 260690 Fe-69 2.71320E-10 2.71320E-10 260690 + 42 260700 Fe-70 5.38080E-11 5.38080E-11 260700 + 43 260710 Fe-71 3.10830E-12 3.10830E-12 260710 + 44 270620 Co-62 3.08850E-13 4.35830E-10 270620 + 45 270630 Co-63 2.94020E-11 9.59810E-10 270630 + 46 270640 Co-64 1.72900E-10 2.10690E-09 270640 + 47 270650 Co-65 1.90100E-09 4.59500E-09 270650 + 48 270660 Co-66 4.73940E-09 9.37060E-09 270660 + 49 270670 Co-67 1.63040E-08 1.83960E-08 270670 + 50 270680 Co-68 9.68500E-09 1.40440E-08 270680 + 51 270681 Co-68m 7.22900E-09 8.71770E-09 270681 + 52 270690 Co-69 2.77600E-08 2.80120E-08 270690 + 53 270700 Co-70 4.69960E-09 4.69960E-09 270700 + 54 270701 Co-70m 4.69960E-09 4.75340E-09 270701 + 55 270710 Co-71 5.41380E-09 5.41690E-09 270710 + 56 270720 Co-72 7.86830E-10 7.86830E-10 270720 + 57 270730 Co-73 1.22240E-10 1.22240E-10 270730 + 58 270740 Co-74 2.60400E-12 2.60400E-12 270740 + 59 280640 Ni-64 2.10500E-12 2.10900E-09 28064.82c + 60 280650 Ni-65 3.81750E-11 4.63320E-09 280650 + 61 280660 Ni-66 8.08980E-10 1.01800E-08 280660 + 62 280670 Ni-67 3.90490E-09 2.23010E-08 280670 + 63 280680 Ni-68 2.99340E-08 4.86170E-08 280680 + 64 280690 Ni-69 3.25710E-08 6.03030E-08 280690 + 65 280691 Ni-69m 3.25710E-08 3.25710E-08 280691 + 66 280700 Ni-70 1.72480E-07 1.81930E-07 280700 + 67 280710 Ni-71 1.51520E-07 1.56940E-07 280710 + 68 280720 Ni-72 2.02440E-07 2.03230E-07 280720 + 69 280730 Ni-73 5.50310E-08 5.51530E-08 280730 + 70 280740 Ni-74 1.18990E-08 1.19020E-08 280740 + 71 280750 Ni-75 1.88270E-09 1.88270E-09 280750 + 72 280760 Ni-76 4.23380E-10 4.23380E-10 280760 + 73 280770 Ni-77 8.99650E-12 8.99650E-12 280770 + 74 290660 Cu-66 1.47900E-12 1.01810E-08 290660 + 75 290670 Cu-67 6.79250E-11 2.23690E-08 290670 + 76 290680 Cu-68 2.22730E-10 4.93500E-08 290680 + 77 290681 Cu-68m 6.07120E-10 6.07120E-10 290681 + 78 290690 Cu-69 1.47530E-08 1.07630E-07 290690 + 79 290700 Cu-70 3.59430E-09 3.11840E-08 290700 + 80 290701 Cu-70m 4.59020E-08 5.51790E-08 290701 + 81 290702 Cu-70m 3.59430E-09 1.85530E-07 290702 + 82 290710 Cu-71 3.41920E-07 4.98860E-07 290710 + 83 290720 Cu-72 6.18310E-07 8.21540E-07 290720 + 84 290730 Cu-73 2.38340E-06 2.43860E-06 290730 + 85 290740 Cu-74 4.67650E-07 4.79580E-07 290740 + 86 290750 Cu-75 7.00970E-07 7.02820E-07 290750 + 87 290760 Cu-76 1.40940E-07 1.41150E-07 290760 + 88 290761 Cu-76m 1.40940E-07 1.41150E-07 290761 + 89 290770 Cu-77 5.97120E-08 5.97210E-08 290770 + 90 290780 Cu-78 5.07550E-09 5.07550E-09 290780 + 91 290790 Cu-79 4.59160E-10 4.59160E-10 290790 + 92 290800 Cu-80 1.37610E-11 1.37610E-11 290800 + 93 300680 Zn-68 2.20500E-12 4.94490E-08 300680 + 94 300690 Zn-69 1.15340E-11 1.07700E-07 300690 + 95 300691 Zn-69m 5.72850E-11 5.72850E-11 300691 + 96 300700 Zn-70 2.28800E-09 2.37310E-07 300700 + 97 300710 Zn-71 3.78960E-09 5.02650E-07 300710 + 98 300711 Zn-71m 1.88210E-08 1.88210E-08 300711 + 99 300720 Zn-72 3.21530E-07 1.14310E-06 300720 + 100 300730 Zn-73 8.27210E-08 3.00880E-06 300730 + 101 300731 Zn-73m 1.14410E-07 4.87510E-07 300731 + 102 300732 Zn-73m 7.46190E-07 7.46190E-07 300732 + 103 300740 Zn-74 2.70320E-06 3.20740E-06 300740 + 104 300750 Zn-75 3.10690E-06 3.78940E-06 300750 + 105 300760 Zn-76 2.19860E-05 2.22640E-05 300760 + 106 300770 Zn-77 8.78920E-06 9.43400E-06 300770 + 107 300771 Zn-77m 1.17020E-06 1.17020E-06 300771 + 108 300780 Zn-78 1.00440E-05 1.00490E-05 300780 + 109 300790 Zn-79 3.39130E-06 3.39150E-06 300790 + 110 300800 Zn-80 2.35180E-07 2.35190E-07 300800 + 111 300810 Zn-81 8.66400E-09 8.66400E-09 300810 + 112 300820 Zn-82 5.32590E-10 5.32590E-10 300820 + 113 310710 Ga-71 8.81120E-11 5.21560E-07 310710 + 114 310720 Ga-72 1.95530E-09 1.14520E-06 310720 + 115 310721 Ga-72m 1.92200E-10 3.82800E-08 310721 + 116 310730 Ga-73 5.62690E-08 3.43810E-06 310730 + 117 310740 Ga-74 1.04850E-07 2.58900E-06 310740 + 118 310741 Ga-74m 1.04850E-07 3.31220E-06 310741 + 119 310750 Ga-75 6.21450E-06 1.00040E-05 310750 + 120 310760 Ga-76 1.25690E-05 3.48330E-05 310760 + 121 310770 Ga-77 3.32070E-05 4.32260E-05 310770 + 122 310780 Ga-78 3.68260E-05 4.69190E-05 310780 + 123 310790 Ga-79 4.74410E-05 5.07880E-05 310790 + 124 310800 Ga-80 2.84630E-05 2.86990E-05 310800 + 125 310810 Ga-81 2.41900E-05 2.41980E-05 310810 + 126 310820 Ga-82 3.64930E-06 3.64980E-06 310820 + 127 310830 Ga-83 1.82740E-07 1.82740E-07 310830 + 128 310840 Ga-84 6.59190E-09 6.59190E-09 310840 + 129 310850 Ga-85 1.54130E-10 1.54130E-10 310850 + 130 320720 Ge-72 1.20960E-12 1.14520E-06 32072.82c + 131 320730 Ge-73 4.75080E-11 3.43820E-06 32073.82c + 132 320731 Ge-73m 9.56540E-12 3.38770E-06 320731 + 133 320740 Ge-74 2.08820E-09 3.41920E-06 32074.82c + 134 320750 Ge-75 6.50520E-09 1.00590E-05 320750 + 135 320751 Ge-75m 4.88580E-08 4.49010E-07 320751 + 136 320760 Ge-76 2.12940E-06 3.69620E-05 32076.82c + 137 320770 Ge-77 5.86170E-06 1.42230E-05 320770 + 138 320771 Ge-77m 7.80450E-07 4.40070E-05 320771 + 139 320780 Ge-78 7.37410E-05 1.20710E-04 320780 + 140 320790 Ge-79 1.99400E-05 7.66000E-05 320790 + 141 320791 Ge-79m 1.49760E-04 1.49840E-04 320791 + 142 320800 Ge-80 5.08250E-04 5.39830E-04 320800 + 143 320810 Ge-81 3.70850E-04 3.83350E-04 320810 + 144 320811 Ge-81m 7.46690E-05 8.51180E-05 320811 + 145 320820 Ge-82 4.71000E-04 4.73940E-04 320820 + 146 320830 Ge-83 1.67980E-04 1.68100E-04 320830 + 147 320840 Ge-84 4.76580E-05 4.76600E-05 320840 + 148 320850 Ge-85 3.93000E-06 3.93010E-06 320850 + 149 320860 Ge-86 7.23930E-06 7.23930E-06 320860 + 150 320870 Ge-87 2.62830E-09 2.62830E-09 320870 + 151 330750 As-75 9.58430E-12 1.00590E-05 33075.82c + 152 330751 As-75m 3.62960E-11 1.71000E-10 330751 + 153 330760 As-76 3.17190E-09 3.17190E-09 330760 + 154 330770 As-77 1.12770E-07 4.99810E-05 330770 + 155 330780 As-78 1.61520E-06 1.22320E-04 330780 + 156 330790 As-79 1.35720E-05 2.34010E-04 330790 + 157 330800 As-80 7.73770E-05 6.17210E-04 330800 + 158 330810 As-81 2.91960E-04 7.59580E-04 330810 + 159 330820 As-82 1.44140E-04 6.18080E-04 330820 + 160 330821 As-82m 5.02210E-04 5.02210E-04 330821 + 161 330830 As-83 1.05590E-03 1.22920E-03 330830 + 162 330840 As-84 3.38240E-04 3.59770E-04 330840 + 163 330841 As-84m 3.38240E-04 3.59770E-04 330841 + 164 330850 As-85 3.65790E-04 3.69170E-04 330850 + 165 330860 As-86 8.89120E-05 9.61510E-05 330860 + 166 330870 As-87 2.65420E-05 2.65450E-05 330870 + 167 330880 As-88 1.05750E-06 1.05750E-06 330880 + 168 330890 As-89 5.12670E-08 5.12670E-08 330890 + 169 330900 As-90 8.30290E-10 8.30290E-10 330900 + 170 340770 Se-77 2.86920E-12 4.99810E-05 34077.82c + 171 340771 Se-77m 2.15500E-11 2.15500E-11 340771 + 172 340780 Se-78 3.48490E-09 1.22320E-04 34078.82c + 173 340790 Se-79 8.50520E-08 2.33980E-04 34079.82c + 174 340791 Se-79m 1.13240E-08 2.28480E-04 340791 + 175 340800 Se-80 4.78240E-06 6.21990E-04 34080.82c + 176 340810 Se-81 9.71690E-06 8.42220E-04 340810 + 177 340811 Se-81m 7.29800E-05 1.00250E-04 340811 + 178 340820 Se-82 3.71190E-04 1.49150E-03 34082.82c + 179 340830 Se-83 8.25540E-04 1.26850E-03 340830 + 180 340831 Se-83m 1.66220E-04 9.53380E-04 340831 + 181 340840 Se-84 2.93460E-03 3.73430E-03 340840 + 182 340850 Se-85 2.90530E-03 3.22500E-03 340850 + 183 340860 Se-86 2.94260E-03 3.01110E-03 340860 + 184 340870 Se-87 1.59860E-03 1.62110E-03 340870 + 185 340880 Se-88 6.17230E-04 6.18290E-04 340880 + 186 340890 Se-89 1.72820E-04 1.72870E-04 340890 + 187 340900 Se-90 4.85510E-05 4.85520E-05 340900 + 188 340910 Se-91 6.28270E-06 6.28270E-06 340910 + 189 340920 Se-92 1.68960E-08 1.68960E-08 340920 + 190 350790 Br-79 3.36560E-12 1.27970E-07 35079.82c + 191 350791 Br-79m 1.27450E-11 1.27450E-11 350791 + 192 350800 Br-80 3.37550E-10 1.51370E-09 350800 + 193 350801 Br-80m 1.17610E-09 1.17610E-09 350801 + 194 350810 Br-81 9.53140E-08 8.42370E-04 35081.82c + 195 350820 Br-82 2.67020E-06 3.62630E-06 350820 + 196 350821 Br-82m 9.79610E-07 9.79610E-07 350821 + 197 350830 Br-83 2.69750E-05 2.24890E-03 350830 + 198 350840 Br-84 8.53800E-05 3.81970E-03 350840 + 199 350841 Br-84m 8.53800E-05 8.53800E-05 350841 + 200 350850 Br-85 9.74860E-04 4.19980E-03 350850 + 201 350860 Br-86 2.34750E-03 5.35860E-03 350860 + 202 350870 Br-87 4.25310E-03 5.88030E-03 350870 + 203 350880 Br-88 2.75650E-03 3.38220E-03 350880 + 204 350890 Br-89 2.79270E-03 2.95210E-03 350890 + 205 350900 Br-90 1.25050E-03 1.30040E-03 350900 + 206 350910 Br-91 6.02780E-04 6.07740E-04 350910 + 207 350920 Br-92 9.46660E-05 9.46830E-05 350920 + 208 350930 Br-93 2.44290E-05 2.44290E-05 350930 + 209 350940 Br-94 1.05630E-07 1.05630E-07 350940 + 210 350950 Br-95 3.12720E-09 3.12720E-09 350950 + 211 360820 Kr-82 8.28480E-10 3.65060E-06 36082.82c + 212 360830 Kr-83 2.75420E-08 2.24890E-03 36083.82c + 213 360831 Kr-83m 5.54540E-09 2.24690E-03 360831 + 214 360840 Kr-84 2.11990E-05 3.92630E-03 36084.82c + 215 360850 Kr-85 5.26680E-05 9.59070E-04 36085.82c + 216 360851 Kr-85m 1.06040E-05 4.20360E-03 360851 + 217 360860 Kr-86 8.34210E-04 6.34040E-03 36086.82c + 218 360870 Kr-87 2.63840E-03 8.59770E-03 360870 + 219 360880 Kr-88 6.18850E-03 9.76030E-03 360880 + 220 360890 Kr-89 1.14500E-02 1.43060E-02 360890 + 221 360900 Kr-90 1.25840E-02 1.36860E-02 360900 + 222 360910 Kr-91 8.95040E-03 9.46790E-03 360910 + 223 360920 Kr-92 5.29330E-03 5.37330E-03 360920 + 224 360930 Kr-93 2.27850E-03 2.28640E-03 360930 + 225 360940 Kr-94 7.18210E-04 7.18240E-04 360940 + 226 360950 Kr-95 1.36910E-04 1.36910E-04 360950 + 227 360960 Kr-96 1.56450E-05 1.56450E-05 360960 + 228 360970 Kr-97 2.94840E-08 2.94840E-08 360970 + 229 370840 Rb-84 2.87550E-11 8.90810E-11 370840 + 230 370841 Rb-84m 6.03260E-11 6.03260E-11 370841 + 231 370850 Rb-85 1.29470E-08 4.26310E-03 37085.82c + 232 370860 Rb-86 1.22720E-07 3.80180E-07 37086.82c + 233 370861 Rb-86m 2.57460E-07 2.57460E-07 370861 + 234 370870 Rb-87 3.32820E-05 8.63100E-03 37087.82c + 235 370880 Rb-88 1.66940E-04 9.92720E-03 370880 + 236 370890 Rb-89 1.50760E-03 1.58130E-02 370890 + 237 370900 Rb-90 3.29920E-04 1.23600E-02 370900 + 238 370901 Rb-90m 3.35640E-03 5.14650E-03 370901 + 239 370910 Rb-91 1.04550E-02 1.99230E-02 370910 + 240 370920 Rb-92 1.19130E-02 1.72860E-02 370920 + 241 370930 Rb-93 1.28200E-02 1.51140E-02 370930 + 242 370940 Rb-94 6.47750E-03 7.19170E-03 370940 + 243 370950 Rb-95 4.39240E-03 4.52600E-03 370950 + 244 370960 Rb-96 6.99000E-04 1.05980E-03 370960 + 245 370961 Rb-96m 6.99000E-04 7.06530E-04 370961 + 246 370970 Rb-97 3.85740E-04 3.85770E-04 370970 + 247 370980 Rb-98 1.94950E-05 1.94950E-05 370980 + 248 370981 Rb-98m 1.94950E-05 1.94950E-05 370981 + 249 370990 Rb-99 5.94120E-06 5.94120E-06 370990 + 250 371000 Rb-100 4.79260E-09 4.79260E-09 371000 + 251 380870 Sr-87 1.82310E-09 2.18910E-09 38087.82c + 252 380871 Sr-87m 3.67080E-10 3.67080E-10 380871 + 253 380880 Sr-88 6.34930E-06 9.93360E-03 38088.82c + 254 380890 Sr-89 4.87940E-05 1.58620E-02 38089.82c + 255 380900 Sr-90 5.39250E-04 1.79120E-02 38090.82c + 256 380910 Sr-91 2.25400E-03 2.21770E-02 380910 + 257 380920 Sr-92 9.59530E-03 2.70930E-02 380920 + 258 380930 Sr-93 2.08820E-02 3.65110E-02 380930 + 259 380940 Sr-94 2.99060E-02 3.67610E-02 380940 + 260 380950 Sr-95 2.80590E-02 3.23380E-02 380950 + 261 380960 Sr-96 2.15210E-02 2.28890E-02 380960 + 262 380970 Sr-97 1.01060E-02 1.03980E-02 380970 + 263 380980 Sr-98 4.44560E-03 4.48280E-03 380980 + 264 380990 Sr-99 1.25670E-03 1.26170E-03 380990 + 265 381000 Sr-100 2.80150E-04 2.80150E-04 381000 + 266 381010 Sr-101 3.36690E-05 3.36690E-05 381010 + 267 381020 Sr-102 4.00770E-06 4.00770E-06 381020 + 268 390890 Y-89 8.85800E-11 1.58620E-02 39089.82c + 269 390891 Y-89m 4.39940E-10 1.52940E-06 390891 + 270 390900 Y-90 3.89020E-07 1.79130E-02 39090.82c + 271 390901 Y-90m 6.50580E-07 6.50580E-07 390901 + 272 390910 Y-91 2.63720E-06 2.21930E-02 39091.82c + 273 390911 Y-91m 1.30980E-05 1.30610E-02 390911 + 274 390920 Y-92 9.59170E-05 2.71890E-02 390920 + 275 390930 Y-93 1.03730E-04 3.73940E-02 390930 + 276 390931 Y-93m 7.79070E-04 9.91560E-03 390931 + 277 390940 Y-94 2.56240E-03 3.93230E-02 390940 + 278 390950 Y-95 1.15110E-02 4.38490E-02 390950 + 279 390960 Y-96 6.23420E-03 2.91260E-02 390960 + 280 390961 Y-96m 1.30790E-02 1.30810E-02 390961 + 281 390970 Y-97 4.64590E-03 1.36560E-02 390970 + 282 390971 Y-97m 1.71730E-02 2.34400E-02 390971 + 283 390972 Y-97m 5.90160E-03 5.90160E-03 390972 + 284 390980 Y-98 2.97080E-03 7.45360E-03 390980 + 285 390981 Y-98m 1.44020E-02 1.44020E-02 390981 + 286 390990 Y-99 1.47000E-02 1.59640E-02 390990 + 287 391000 Y-100 3.35270E-03 3.63110E-03 391000 + 288 391001 Y-100m 3.35270E-03 3.35310E-03 391001 + 289 391010 Y-101 2.83980E-03 2.87290E-03 391010 + 290 391020 Y-102 2.85440E-04 2.87330E-04 391020 + 291 391021 Y-102m 2.85440E-04 2.87330E-04 391021 + 292 391030 Y-103 1.09610E-04 1.09610E-04 391030 + 293 391040 Y-104 8.51390E-06 8.51390E-06 391040 + 294 391050 Y-105 7.61950E-09 7.61950E-09 391050 + 295 400920 Zr-92 1.89130E-06 2.71910E-02 40092.82c + 296 400930 Zr-93 1.63410E-05 3.74100E-02 40093.82c + 297 400940 Zr-94 1.71180E-04 3.94940E-02 40094.82c + 298 400950 Zr-95 9.58090E-04 4.48070E-02 40095.82c + 299 400960 Zr-96 5.70230E-03 4.79280E-02 40096.82c + 300 400970 Zr-97 1.39210E-02 5.25300E-02 400970 + 301 400980 Zr-98 3.29170E-02 5.45290E-02 400980 + 302 400990 Zr-99 4.23540E-02 5.80800E-02 400990 + 303 401000 Zr-100 4.53290E-02 5.22800E-02 401000 + 304 401010 Zr-101 2.42480E-02 2.71490E-02 401010 + 305 401020 Zr-102 1.41670E-02 1.47220E-02 401020 + 306 401030 Zr-103 5.48560E-03 5.58720E-03 401030 + 307 401040 Zr-104 1.84680E-03 1.85460E-03 401040 + 308 401050 Zr-105 2.92870E-04 2.92880E-04 401050 + 309 401060 Zr-106 5.12970E-05 5.12970E-05 401060 + 310 401070 Zr-107 3.93730E-06 3.93730E-06 401070 + 311 401080 Zr-108 9.64460E-10 9.64460E-10 401080 + 312 410940 Nb-94 5.20500E-10 8.30180E-10 41094.82c + 313 410941 Nb-94m 3.11240E-10 3.11240E-10 410941 + 314 410950 Nb-95 7.87250E-07 4.47810E-02 41095.82c + 315 410951 Nb-95m 1.58510E-07 4.84230E-04 410951 + 316 410960 Nb-96 2.84100E-05 2.84100E-05 410960 + 317 410970 Nb-97 2.22930E-04 5.27980E-02 410970 + 318 410971 Nb-97m 4.48870E-05 4.99740E-02 410971 + 319 410980 Nb-98 2.43160E-04 5.47720E-02 410980 + 320 410981 Nb-98m 8.47240E-04 8.47240E-04 410981 + 321 410990 Nb-99 5.11070E-03 4.22650E-02 410990 + 322 410991 Nb-99m 1.02900E-03 2.24020E-02 410991 + 323 411000 Nb-100 2.47560E-03 5.47550E-02 411000 + 324 411001 Nb-100m 1.20010E-02 1.20010E-02 411001 + 325 411010 Nb-101 3.26320E-02 5.97810E-02 411010 + 326 411020 Nb-102 1.51780E-02 2.99010E-02 411020 + 327 411021 Nb-102m 1.51780E-02 1.51780E-02 411021 + 328 411030 Nb-103 2.58830E-02 3.14700E-02 411030 + 329 411040 Nb-104 6.52250E-03 8.38120E-03 411040 + 330 411041 Nb-104m 6.52250E-03 6.52250E-03 411041 + 331 411050 Nb-105 7.95950E-03 8.24910E-03 411050 + 332 411060 Nb-106 2.87170E-03 2.92240E-03 411060 + 333 411070 Nb-107 7.07180E-04 7.10970E-04 411070 + 334 411080 Nb-108 8.18170E-05 8.18180E-05 411080 + 335 411090 Nb-109 1.18870E-05 1.18870E-05 411090 + 336 411100 Nb-110 1.18090E-09 1.18090E-09 411100 + 337 420960 Mo-96 9.78820E-07 2.93890E-05 42096.82c + 338 420970 Mo-97 3.79740E-06 5.28020E-02 42097.82c + 339 420980 Mo-98 3.99860E-05 5.56590E-02 42098.82c + 340 420990 Mo-99 2.30490E-04 6.44500E-02 42099.82c + 341 421000 Mo-100 1.80700E-03 6.85640E-02 42100.82c + 342 421010 Mo-101 6.19790E-03 6.59790E-02 421010 + 343 421020 Mo-102 2.16230E-02 6.67020E-02 421020 + 344 421030 Mo-103 3.44990E-02 6.59770E-02 421030 + 345 421040 Mo-104 4.70340E-02 6.20700E-02 421040 + 346 421050 Mo-105 2.98040E-02 3.80440E-02 421050 + 347 421060 Mo-106 2.15620E-02 2.43960E-02 421060 + 348 421070 Mo-107 7.36620E-03 8.03960E-03 421070 + 349 421080 Mo-108 3.15770E-03 3.23600E-03 421080 + 350 421090 Mo-109 7.49260E-04 7.59640E-04 421090 + 351 421100 Mo-110 1.13500E-04 1.13500E-04 421100 + 352 421110 Mo-111 1.93070E-05 1.93070E-05 421110 + 353 421120 Mo-112 8.51190E-06 8.51190E-06 421120 + 354 421130 Mo-113 4.01430E-11 4.01430E-11 421130 + 355 430990 Tc-99 1.80810E-09 6.44480E-02 43099.82c + 356 430991 Tc-99m 3.64060E-10 5.67550E-02 430991 + 357 431000 Tc-100 4.12560E-06 4.12560E-06 431000 + 358 431010 Tc-101 6.24790E-05 6.60410E-02 431010 + 359 431020 Tc-102 1.42370E-04 6.68450E-02 431020 + 360 431021 Tc-102m 1.42370E-04 1.42370E-04 431021 + 361 431030 Tc-103 1.80830E-03 6.77860E-02 431030 + 362 431040 Tc-104 4.70730E-03 6.67770E-02 431040 + 363 431050 Tc-105 1.41450E-02 5.21890E-02 431050 + 364 431060 Tc-106 2.07110E-02 4.51070E-02 431060 + 365 431070 Tc-107 1.93910E-02 2.74310E-02 431070 + 366 431080 Tc-108 9.28450E-03 1.25240E-02 431080 + 367 431090 Tc-109 6.07530E-03 6.83090E-03 431090 + 368 431100 Tc-110 1.94840E-03 2.06210E-03 431100 + 369 431110 Tc-111 7.63320E-04 7.82610E-04 431110 + 370 431120 Tc-112 1.57290E-04 1.65630E-04 431120 + 371 431130 Tc-113 7.82600E-05 7.82600E-05 431130 + 372 431140 Tc-114 6.02250E-05 6.02250E-05 431140 + 373 431150 Tc-115 9.39930E-06 9.39930E-06 431150 + 374 441010 Ru-101 1.02160E-06 6.60430E-02 44101.82c + 375 441020 Ru-102 1.07320E-08 6.69870E-02 44102.82c + 376 441030 Ru-103 9.16260E-06 6.78210E-02 44103.82c + 377 441031 Ru-103m 2.56360E-05 2.56360E-05 441031 + 378 441040 Ru-104 2.54880E-04 6.70320E-02 44104.82c + 379 441050 Ru-105 9.62430E-04 5.31520E-02 44105.82c + 380 441060 Ru-106 4.62010E-03 4.97270E-02 44106.82c + 381 441070 Ru-107 7.04420E-03 3.44750E-02 441070 + 382 441080 Ru-108 1.13440E-02 2.38740E-02 441080 + 383 441090 Ru-109 9.07810E-03 1.59040E-02 441090 + 384 441100 Ru-110 5.54420E-03 7.60550E-03 441100 + 385 441110 Ru-111 2.59530E-03 3.38040E-03 441110 + 386 441120 Ru-112 1.10850E-03 1.27730E-03 441120 + 387 441130 Ru-113 2.15550E-04 3.99890E-04 441130 + 388 441131 Ru-113m 2.15550E-04 2.15550E-04 441131 + 389 441140 Ru-114 2.76410E-04 3.34050E-04 441140 + 390 441150 Ru-115 7.48900E-05 8.29420E-05 441150 + 391 441160 Ru-116 2.78010E-08 2.78010E-08 441160 + 392 441170 Ru-117 7.99420E-06 7.99420E-06 441170 + 393 441180 Ru-118 1.01390E-11 1.01390E-11 441180 + 394 451040 Rh-104 2.11070E-07 9.45540E-07 451040 + 395 451041 Rh-104m 7.35430E-07 7.35430E-07 451041 + 396 451050 Rh-105 7.79300E-06 5.31610E-02 45105.82c + 397 451051 Rh-105m 1.03760E-06 1.50900E-02 451051 + 398 451060 Rh-106 7.23070E-06 4.97340E-02 451060 + 399 451061 Rh-106m 1.97090E-05 1.97090E-05 451061 + 400 451070 Rh-107 1.59780E-04 3.46350E-02 451070 + 401 451080 Rh-108 8.51970E-05 2.39590E-02 451080 + 402 451081 Rh-108m 2.96850E-04 2.96850E-04 451081 + 403 451090 Rh-109 1.09460E-03 1.69990E-02 451090 + 404 451100 Rh-110 1.05890E-03 8.66430E-03 451100 + 405 451101 Rh-110m 2.49270E-05 2.49270E-05 451101 + 406 451110 Rh-111 1.41840E-03 4.79880E-03 451110 + 407 451120 Rh-112 4.21960E-04 1.69920E-03 451120 + 408 451121 Rh-112m 4.21960E-04 4.21960E-04 451121 + 409 451130 Rh-113 8.18540E-04 1.32620E-03 451130 + 410 451140 Rh-114 2.19230E-04 5.53460E-04 451140 + 411 451141 Rh-114m 2.19230E-04 2.19230E-04 451141 + 412 451150 Rh-115 2.53760E-04 3.36510E-04 451150 + 413 451160 Rh-116 1.80770E-05 1.82680E-05 451160 + 414 451161 Rh-116m 4.92740E-05 4.92740E-05 451161 + 415 451170 Rh-117 1.62580E-06 9.45600E-06 451170 + 416 451180 Rh-118 6.19950E-08 6.20050E-08 451180 + 417 451190 Rh-119 6.67810E-06 6.67810E-06 451190 + 418 451200 Rh-120 5.70010E-11 5.70010E-11 451200 + 419 451210 Rh-121 1.51850E-07 1.51850E-07 451210 + 420 451220 Rh-122 8.30000E-09 8.30000E-09 451220 + 421 461070 Pd-107 3.07920E-07 3.46360E-02 46107.82c + 422 461071 Pd-107m 6.76800E-07 6.76800E-07 461071 + 423 461080 Pd-108 7.57710E-06 2.42640E-02 46108.82c + 424 461090 Pd-109 7.46010E-06 1.70230E-02 461090 + 425 461091 Pd-109m 1.63970E-05 8.51590E-03 461091 + 426 461100 Pd-110 6.87640E-05 8.75800E-03 46110.82c + 427 461110 Pd-111 3.77590E-05 4.89190E-03 461110 + 428 461111 Pd-111m 8.29910E-05 1.02190E-04 461111 + 429 461120 Pd-112 1.85250E-04 2.30640E-03 461120 + 430 461130 Pd-113 5.88240E-05 1.54960E-03 461130 + 431 461131 Pd-113m 1.64590E-04 1.64590E-04 461131 + 432 461140 Pd-114 3.01760E-04 1.07450E-03 461140 + 433 461150 Pd-115 8.58270E-05 3.92480E-04 461150 + 434 461151 Pd-115m 1.88640E-04 2.37500E-04 461151 + 435 461160 Pd-116 2.19320E-04 2.86860E-04 461160 + 436 461170 Pd-117 4.49410E-05 1.53180E-04 461170 + 437 461171 Pd-117m 9.87790E-05 9.87790E-05 461171 + 438 461180 Pd-118 9.47950E-05 9.48550E-05 461180 + 439 461190 Pd-119 1.33560E-05 2.00340E-05 461190 + 440 461200 Pd-120 6.25020E-06 6.27090E-06 461200 + 441 461210 Pd-121 1.36110E-05 1.37420E-05 461210 + 442 461220 Pd-122 7.25870E-06 7.26700E-06 461220 + 443 461230 Pd-123 5.66000E-07 5.66000E-07 461230 + 444 461240 Pd-124 1.58950E-07 1.58950E-07 461240 + 445 471100 Ag-110 1.10930E-09 1.15040E-09 471100 + 446 471101 Ag-110m 3.02370E-09 3.02370E-09 47510.82c + 447 471110 Ag-111 1.62690E-08 4.89530E-03 47111.82c + 448 471111 Ag-111m 1.22190E-07 4.87720E-03 471111 + 449 471120 Ag-112 9.05390E-07 2.30730E-03 471120 + 450 471130 Ag-113 1.19570E-06 1.02240E-03 471130 + 451 471131 Ag-113m 8.98030E-06 1.49280E-03 471131 + 452 471140 Ag-114 4.72220E-06 1.10210E-03 471140 + 453 471141 Ag-114m 2.28930E-05 2.28930E-05 471141 + 454 471150 Ag-115 3.32130E-06 3.63210E-04 471150 + 455 471151 Ag-115m 2.49450E-05 3.49420E-04 471151 + 456 471160 Ag-116 1.13310E-05 3.00050E-04 471160 + 457 471161 Ag-116m 3.08870E-05 3.08870E-05 471161 + 458 471170 Ag-117 1.69500E-05 1.05770E-04 471170 + 459 471171 Ag-117m 1.27310E-04 2.03900E-04 471171 + 460 471180 Ag-118 2.00040E-05 1.46620E-04 471180 + 461 471181 Ag-118m 9.69760E-05 1.10540E-04 471181 + 462 471190 Ag-119 1.72490E-05 2.72660E-05 471190 + 463 471191 Ag-119m 1.29550E-04 1.39570E-04 471191 + 464 471200 Ag-120 3.50450E-05 6.10630E-05 471200 + 465 471201 Ag-120m 5.86080E-05 6.17440E-05 471201 + 466 471210 Ag-121 1.92540E-05 3.29590E-05 471210 + 467 471220 Ag-122 2.21330E-06 9.48030E-06 471220 + 468 471221 Ag-122m 2.38630E-06 2.38630E-06 471221 + 469 471230 Ag-123 1.61930E-05 1.67590E-05 471230 + 470 471240 Ag-124 4.98520E-06 7.83160E-06 471240 + 471 471241 Ag-124m 5.37480E-06 5.37480E-06 471241 + 472 471250 Ag-125 8.09310E-06 8.09310E-06 471250 + 473 471260 Ag-126 2.26700E-06 2.26700E-06 471260 + 474 471270 Ag-127 4.03100E-07 4.03100E-07 471270 + 475 471280 Ag-128 1.59230E-08 1.59230E-08 471280 + 476 471290 Ag-129 5.81070E-10 5.81070E-10 471290 + 477 481120 Cd-112 1.83380E-10 2.30730E-03 48112.82c + 478 481130 Cd-113 1.03150E-09 1.54210E-03 48113.82c + 479 481131 Cd-113m 3.90620E-09 1.76790E-05 481131 + 480 481140 Cd-114 1.58590E-07 1.10220E-03 48114.82c + 481 481150 Cd-115 2.05570E-07 6.10490E-04 481150 + 482 481151 Cd-115m 7.78470E-07 2.97440E-05 48515.82c + 483 481160 Cd-116 7.22580E-06 3.36310E-04 48116.82c + 484 481170 Cd-117 6.69380E-06 2.38750E-04 481170 + 485 481171 Cd-117m 2.53490E-05 9.07320E-05 481171 + 486 481180 Cd-118 4.39010E-05 2.55740E-04 481180 + 487 481190 Cd-119 2.46640E-05 1.77870E-04 481190 + 488 481191 Cd-119m 6.90080E-05 8.26420E-05 481191 + 489 481200 Cd-120 1.25200E-04 2.25160E-04 481200 + 490 481210 Cd-121 1.90280E-05 4.85430E-05 481210 + 491 481211 Cd-121m 5.32380E-05 5.66820E-05 481211 + 492 481220 Cd-122 8.73240E-05 9.91910E-05 481220 + 493 481230 Cd-123 2.13170E-05 3.50330E-05 481230 + 494 481231 Cd-123m 5.96440E-05 6.26950E-05 481231 + 495 481240 Cd-124 1.75460E-04 1.85970E-04 481240 + 496 481250 Cd-125 6.41980E-05 6.82440E-05 481250 + 497 481251 Cd-125m 1.79620E-04 1.83670E-04 481251 + 498 481260 Cd-126 3.21280E-04 3.23550E-04 481260 + 499 481270 Cd-127 1.85120E-04 1.85520E-04 481270 + 500 481280 Cd-128 8.92450E-05 8.92610E-05 481280 + 501 481290 Cd-129 5.77710E-06 5.77740E-06 481290 + 502 481291 Cd-129m 1.61640E-05 1.61640E-05 481291 + 503 481300 Cd-130 4.97860E-06 4.97860E-06 481300 + 504 481310 Cd-131 1.14720E-08 1.14720E-08 481310 + 505 491150 In-115 2.93320E-10 6.09710E-04 49115.82c + 506 491151 In-115m 5.90590E-11 6.10490E-04 491151 + 507 491160 In-116 1.04830E-09 1.04830E-09 491160 + 508 491161 In-116m 1.69280E-09 3.65270E-09 491161 + 509 491162 In-116m 1.95990E-09 1.95990E-09 491162 + 510 491170 In-117 1.34280E-07 2.13150E-04 491170 + 511 491171 In-117m 2.70370E-08 2.20200E-04 491171 + 512 491180 In-118 2.29760E-07 2.55970E-04 491180 + 513 491181 In-118m 3.71010E-07 7.94530E-07 491181 + 514 491182 In-118m 4.29530E-07 4.29530E-07 491182 + 515 491190 In-119 9.64090E-06 1.18510E-04 491190 + 516 491191 In-119m 1.94110E-06 1.62690E-04 491191 + 517 491200 In-120 2.08420E-06 2.27240E-04 491200 + 518 491201 In-120m 2.08420E-06 2.08420E-06 491201 + 519 491202 In-120m 2.08420E-06 2.08420E-06 491202 + 520 491210 In-121 1.20310E-05 8.54770E-05 491210 + 521 491211 In-121m 2.42230E-06 3.46160E-05 491211 + 522 491220 In-122 2.23980E-05 1.21590E-04 491220 + 523 491221 In-122m 1.87290E-05 1.87290E-05 491221 + 524 491222 In-122m 1.87290E-05 1.87290E-05 491222 + 525 491230 In-123 3.71170E-05 1.09900E-04 491230 + 526 491231 In-123m 7.47330E-06 3.24200E-05 491231 + 527 491240 In-124 4.48930E-05 2.30860E-04 491240 + 528 491241 In-124m 4.84010E-05 4.84010E-05 491241 + 529 491250 In-125 3.79000E-04 5.95330E-04 491250 + 530 491251 In-125m 7.63100E-05 1.11890E-04 491251 + 531 491260 In-126 4.50990E-04 7.74540E-04 491260 + 532 491261 In-126m 4.86240E-04 4.86240E-04 491261 + 533 491270 In-127 1.45800E-03 1.45800E-03 491270 + 534 491271 In-127m 2.93570E-04 4.79090E-04 491271 + 535 491280 In-128 5.06870E-04 7.94600E-04 491280 + 536 491281 In-128m 1.98470E-04 2.87730E-04 491281 + 537 491282 In-128m 7.60460E-04 7.60460E-04 491282 + 538 491290 In-129 1.28520E-03 1.30150E-03 491290 + 539 491291 In-129m 2.58770E-04 2.64640E-04 491291 + 540 491300 In-130 1.87910E-04 1.92710E-04 491300 + 541 491301 In-130m 2.73610E-04 2.73610E-04 491301 + 542 491302 In-130m 3.81130E-04 3.81130E-04 491302 + 543 491310 In-131 5.33010E-05 5.38550E-05 491310 + 544 491311 In-131m 5.33010E-05 5.33010E-05 491311 + 545 491312 In-131m 5.33010E-05 5.33010E-05 491312 + 546 491320 In-132 1.62180E-05 1.62180E-05 491320 + 547 491330 In-133 1.87940E-07 2.25780E-07 491330 + 548 491331 In-133m 3.78410E-08 3.78410E-08 491331 + 549 491340 In-134 3.30800E-09 3.30800E-09 491340 + 550 501170 Sn-117 3.53650E-12 3.29640E-04 50117.82c + 551 501171 Sn-117m 1.33930E-11 7.26250E-07 501171 + 552 501180 Sn-118 9.63180E-10 2.56770E-04 50118.82c + 553 501190 Sn-119 4.07560E-09 2.72110E-04 50119.82c + 554 501191 Sn-119m 1.54340E-08 1.07070E-04 501191 + 555 501200 Sn-120 4.55610E-07 2.31870E-04 50120.82c + 556 501210 Sn-121 1.00760E-11 1.17510E-04 501210 + 557 501211 Sn-121m 2.81930E-11 9.68320E-06 501211 + 558 501220 Sn-122 9.20710E-06 1.68250E-04 50122.82c + 559 501230 Sn-123 2.98490E-06 1.13640E-05 50123.82c + 560 501231 Sn-123m 1.06680E-06 1.35010E-04 501231 + 561 501240 Sn-124 7.28760E-05 3.52140E-04 50124.82c + 562 501250 Sn-125 8.81020E-05 1.88670E-04 50125.82c + 563 501251 Sn-125m 3.14880E-05 6.38150E-04 501251 + 564 501260 Sn-126 8.66610E-04 2.13070E-03 50126.82c + 565 501270 Sn-127 1.65540E-03 2.22370E-03 501270 + 566 501271 Sn-127m 5.91630E-04 1.95710E-03 501271 + 567 501280 Sn-128 1.73540E-03 8.02080E-03 501280 + 568 501281 Sn-128m 4.73030E-03 5.49080E-03 501281 + 569 501290 Sn-129 2.66880E-03 4.09650E-03 501290 + 570 501291 Sn-129m 7.46720E-03 7.60570E-03 501291 + 571 501300 Sn-130 3.82850E-03 4.34710E-03 501300 + 572 501301 Sn-130m 1.04360E-02 1.07660E-02 501301 + 573 501310 Sn-131 1.46950E-03 1.57270E-03 501310 + 574 501311 Sn-131m 4.11160E-03 4.16720E-03 501311 + 575 501320 Sn-132 3.03760E-03 3.05400E-03 501320 + 576 501330 Sn-133 4.91700E-04 4.91740E-04 501330 + 577 501340 Sn-134 7.97480E-05 7.97490E-05 501340 + 578 501350 Sn-135 1.98970E-06 1.98970E-06 501350 + 579 501360 Sn-136 4.08570E-08 4.08570E-08 501360 + 580 511200 Sb-120 2.32690E-11 2.32690E-11 511200 + 581 511201 Sb-120m 3.89140E-11 3.89140E-11 511201 + 582 511230 Sb-123 1.00380E-11 1.46370E-04 51123.82c + 583 511240 Sb-124 1.11570E-06 2.87150E-06 51124.82c + 584 511241 Sb-124m 9.00050E-07 2.34100E-06 511241 + 585 511242 Sb-124m 1.44100E-06 1.44100E-06 511242 + 586 511250 Sb-125 2.43500E-05 8.51160E-04 51125.82c + 587 511260 Sb-126 1.21180E-05 1.44910E-05 51126.82c + 588 511261 Sb-126m 7.56900E-06 1.69520E-05 511261 + 589 511262 Sb-126m 9.38280E-06 9.38280E-06 511262 + 590 511270 Sb-127 2.01360E-04 4.38220E-03 511270 + 591 511280 Sb-128 2.64280E-04 8.29830E-03 511280 + 592 511281 Sb-128m 3.69630E-04 3.69630E-04 511281 + 593 511290 Sb-129 2.82250E-03 1.16060E-02 511290 + 594 511291 Sb-129m 2.08880E-03 5.89160E-03 511291 + 595 511300 Sb-130 7.03100E-03 1.67610E-02 511300 + 596 511301 Sb-130m 7.03100E-03 1.24140E-02 511301 + 597 511310 Sb-131 2.34740E-02 2.92140E-02 511310 + 598 511320 Sb-132 8.85930E-03 1.19130E-02 511320 + 599 511321 Sb-132m 7.84370E-03 7.84370E-03 511321 + 600 511330 Sb-133 1.32910E-02 1.37960E-02 511330 + 601 511340 Sb-134 1.21500E-03 1.28140E-03 511340 + 602 511341 Sb-134m 3.31180E-03 3.31200E-03 511341 + 603 511350 Sb-135 1.43110E-03 1.43270E-03 511350 + 604 511360 Sb-136 1.70710E-04 1.70740E-04 511360 + 605 511370 Sb-137 2.65820E-05 2.65820E-05 511370 + 606 511380 Sb-138 9.02320E-07 9.02320E-07 511380 + 607 511390 Sb-139 4.07190E-09 4.07190E-09 511390 + 608 521260 Te-126 2.41710E-06 3.14870E-05 52126.82c + 609 521270 Te-127 2.99080E-06 4.37600E-03 521270 + 610 521271 Te-127m 8.36820E-06 7.30530E-04 52527.82c + 611 521280 Te-128 2.59000E-05 8.68060E-03 52128.82c + 612 521290 Te-129 5.60570E-05 1.42460E-02 521290 + 613 521291 Te-129m 1.56840E-04 6.97340E-03 52529.82c + 614 521300 Te-130 2.34380E-03 3.15180E-02 52130.82c + 615 521310 Te-131 1.66760E-03 3.00140E-02 521310 + 616 521311 Te-131m 4.66580E-03 7.00470E-03 521311 + 617 521320 Te-132 2.63230E-02 4.60800E-02 52132.82c + 618 521330 Te-133 1.36780E-02 3.22050E-02 521330 + 619 521331 Te-133m 3.82700E-02 4.06570E-02 521331 + 620 521340 Te-134 5.42920E-02 5.91080E-02 521340 + 621 521350 Te-135 1.97160E-02 2.09520E-02 521350 + 622 521360 Te-136 9.79030E-03 9.94580E-03 521360 + 623 521370 Te-137 2.46230E-03 2.47590E-03 521370 + 624 521380 Te-138 6.90720E-04 6.91620E-04 521380 + 625 521390 Te-139 5.27310E-05 5.27350E-05 521390 + 626 521400 Te-140 1.15120E-05 1.15120E-05 521400 + 627 521410 Te-141 2.29440E-08 2.29440E-08 521410 + 628 531280 I-128 1.89560E-10 1.89560E-10 531280 + 629 531290 I-129 1.46510E-06 1.68280E-02 53129.82c + 630 531300 I-130 2.42930E-06 3.17790E-06 53130.82c + 631 531301 I-130m 8.91220E-07 8.91220E-07 531301 + 632 531310 I-131 9.58200E-05 3.56430E-02 53131.82c + 633 531320 I-132 2.42540E-04 4.65070E-02 531320 + 634 531321 I-132m 2.14740E-04 2.14740E-04 531321 + 635 531330 I-133 2.44630E-03 7.00040E-02 531330 + 636 531331 I-133m 1.81040E-03 1.81040E-03 531331 + 637 531340 I-134 6.55730E-03 7.13370E-02 531340 + 638 531341 I-134m 5.80570E-03 5.80570E-03 531341 + 639 531350 I-135 4.99710E-02 7.09230E-02 53135.82c + 640 531360 I-136 8.18350E-03 1.81660E-02 531360 + 641 531361 I-136m 2.23060E-02 2.23430E-02 531361 + 642 531370 I-137 2.21350E-02 2.45800E-02 531370 + 643 531380 I-138 8.15000E-03 8.79800E-03 531380 + 644 531390 I-139 6.08050E-03 6.13320E-03 531390 + 645 531400 I-140 1.25270E-03 1.26420E-03 531400 + 646 531410 I-141 2.73140E-04 2.73160E-04 531410 + 647 531420 I-142 2.33200E-05 2.33200E-05 531420 + 648 531430 I-143 2.14060E-07 2.14060E-07 531430 + 649 531440 I-144 2.77380E-09 2.77380E-09 531440 + 650 541310 Xe-131 2.32360E-09 3.56430E-02 54131.82c + 651 541311 Xe-131m 6.50130E-09 3.87160E-04 541311 + 652 541320 Xe-132 1.30250E-06 4.65400E-02 54132.82c + 653 541321 Xe-132m 1.74500E-06 1.74500E-06 541321 + 654 541330 Xe-133 2.00730E-05 7.00800E-02 54133.82c + 655 541331 Xe-133m 5.61640E-05 2.04870E-03 541331 + 656 541340 Xe-134 1.58190E-04 7.20600E-02 54134.82c + 657 541341 Xe-134m 4.31180E-04 5.64710E-04 541341 + 658 541350 Xe-135 1.12980E-03 7.51240E-02 54135.82c + 659 541351 Xe-135m 3.16120E-03 1.48700E-02 541351 + 660 541360 Xe-136 2.51700E-02 6.72780E-02 54136.82c + 661 541370 Xe-137 3.96410E-02 6.30900E-02 541370 + 662 541380 Xe-138 4.82170E-02 5.71500E-02 541380 + 663 541390 Xe-139 3.15350E-02 3.71850E-02 541390 + 664 541400 Xe-140 2.50780E-02 2.62820E-02 541400 + 665 541410 Xe-141 8.25340E-03 8.47500E-03 541410 + 666 541420 Xe-142 3.78730E-03 3.80490E-03 541420 + 667 541430 Xe-143 6.83800E-04 6.83930E-04 541430 + 668 541440 Xe-144 1.27330E-04 1.27330E-04 541440 + 669 541450 Xe-145 1.34650E-05 1.34650E-05 541450 + 670 541460 Xe-146 2.39810E-08 2.39810E-08 541460 + 671 551330 Cs-133 2.25790E-09 7.00800E-02 55133.82c + 672 551340 Cs-134 5.06010E-07 9.54010E-07 55134.82c + 673 551341 Cs-134m 4.48000E-07 4.48000E-07 551341 + 674 551350 Cs-135 6.86480E-06 7.52260E-02 55135.82c + 675 551351 Cs-135m 5.08020E-06 5.08020E-06 551351 + 676 551360 Cs-136 6.68870E-05 9.07990E-05 55136.82c + 677 551361 Cs-136m 4.78230E-05 4.78230E-05 551361 + 678 551370 Cs-137 1.80700E-03 6.48970E-02 55137.82c + 679 551380 Cs-138 2.29170E-03 6.25460E-02 551380 + 680 551381 Cs-138m 3.83260E-03 3.83260E-03 551381 + 681 551390 Cs-139 1.86120E-02 5.57970E-02 551390 + 682 551400 Cs-140 2.11780E-02 4.74640E-02 551400 + 683 551410 Cs-141 2.64680E-02 3.49530E-02 551410 + 684 551420 Cs-142 1.44060E-02 1.82040E-02 551420 + 685 551430 Cs-143 1.05300E-02 1.12110E-02 551430 + 686 551440 Cs-144 1.81080E-03 2.84030E-03 551440 + 687 551441 Cs-144m 1.81080E-03 1.81120E-03 551441 + 688 551450 Cs-145 1.28780E-03 1.30060E-03 551450 + 689 551460 Cs-146 2.13330E-04 2.13350E-04 551460 + 690 551470 Cs-147 3.04230E-05 3.04230E-05 551470 + 691 551480 Cs-148 1.70230E-06 1.70230E-06 551480 + 692 551490 Cs-149 1.38940E-09 1.38940E-09 551490 + 693 561360 Ba-136 2.27340E-07 1.15560E-04 56136.82c + 694 561361 Ba-136m 6.19680E-07 6.19680E-07 561361 + 695 561370 Ba-137 2.26150E-06 6.49060E-02 56137.82c + 696 561371 Ba-137m 6.32740E-06 6.12690E-02 561371 + 697 561380 Ba-138 3.22930E-04 6.35970E-02 56138.82c + 698 561390 Ba-139 1.53130E-03 5.73280E-02 561390 + 699 561400 Ba-140 6.66380E-03 5.41280E-02 56140.82c + 700 561410 Ba-141 1.12010E-02 4.61540E-02 561410 + 701 561420 Ba-142 2.83180E-02 4.67060E-02 561420 + 702 561430 Ba-143 3.03900E-02 4.15080E-02 561430 + 703 561440 Ba-144 2.79050E-02 3.17460E-02 561440 + 704 561450 Ba-145 1.25670E-02 1.37120E-02 561450 + 705 561460 Ba-146 7.30770E-03 7.49940E-03 561460 + 706 561470 Ba-147 2.00850E-03 2.03070E-03 561470 + 707 561480 Ba-148 6.20620E-04 6.21900E-04 561480 + 708 561490 Ba-149 7.71640E-05 7.71650E-05 561490 + 709 561500 Ba-150 1.63020E-05 1.63020E-05 561500 + 710 561510 Ba-151 6.08780E-09 6.08780E-09 561510 + 711 571380 La-138 1.38360E-09 1.38360E-09 57138.82c + 712 571390 La-139 1.05650E-06 5.73290E-02 57139.82c + 713 571400 La-140 3.56510E-05 5.41630E-02 57140.82c + 714 571410 La-141 1.79130E-04 4.63330E-02 571410 + 715 571420 La-142 6.17910E-04 4.73240E-02 571420 + 716 571430 La-143 3.03000E-03 4.45380E-02 571430 + 717 571440 La-144 7.09170E-03 3.88380E-02 571440 + 718 571450 La-145 1.49270E-02 2.86390E-02 571450 + 719 571460 La-146 3.61570E-03 1.11150E-02 571460 + 720 571461 La-146m 7.58530E-03 7.58530E-03 571461 + 721 571470 La-147 9.48170E-03 1.15150E-02 571470 + 722 571480 La-148 3.88580E-03 4.50550E-03 571480 + 723 571490 La-149 2.19780E-03 2.27460E-03 571490 + 724 571500 La-150 5.14690E-04 5.30990E-04 571500 + 725 571510 La-151 1.10120E-04 1.10130E-04 571510 + 726 571520 La-152 7.32790E-06 7.32790E-06 571520 + 727 571530 La-153 3.42970E-08 3.42970E-08 571530 + 728 571540 La-154 2.63320E-10 2.63320E-10 571540 + 729 581410 Ce-141 8.97500E-07 4.63340E-02 58141.82c + 730 581420 Ce-142 1.73150E-05 4.73410E-02 58142.82c + 731 581430 Ce-143 9.80680E-05 4.46360E-02 58143.82c + 732 581440 Ce-144 5.68510E-04 3.94060E-02 58144.82c + 733 581450 Ce-145 2.28930E-03 3.09280E-02 581450 + 734 581460 Ce-146 6.81230E-03 2.55130E-02 581460 + 735 581470 Ce-147 9.74710E-03 2.12620E-02 581470 + 736 581480 Ce-148 1.27110E-02 1.72480E-02 581480 + 737 581490 Ce-149 8.77620E-03 1.10330E-02 581490 + 738 581500 Ce-150 6.59780E-03 7.11450E-03 581500 + 739 581510 Ce-151 2.31830E-03 2.42890E-03 581510 + 740 581520 Ce-152 9.97820E-04 1.00470E-03 581520 + 741 581530 Ce-153 2.03760E-04 2.03790E-04 581530 + 742 581540 Ce-154 3.08720E-05 3.08720E-05 581540 + 743 581550 Ce-155 2.55270E-06 2.55270E-06 581550 + 744 581560 Ce-156 2.21150E-09 2.21150E-09 581560 + 745 581570 Ce-157 3.35550E-11 3.35550E-11 581570 + 746 591430 Pr-143 1.50750E-09 4.46360E-02 59143.82c + 747 591440 Pr-144 7.94740E-08 3.94070E-02 591440 + 748 591441 Pr-144m 8.08510E-07 5.44590E-04 591441 + 749 591450 Pr-145 6.74110E-06 3.09350E-02 591450 + 750 591460 Pr-146 3.64690E-05 2.55490E-02 591460 + 751 591470 Pr-147 2.32060E-04 2.14940E-02 591470 + 752 591480 Pr-148 1.18510E-04 1.73670E-02 591480 + 753 591481 Pr-148m 5.74540E-04 5.74540E-04 591481 + 754 591490 Pr-149 2.09850E-03 1.31320E-02 591490 + 755 591500 Pr-150 3.02520E-03 1.01400E-02 591500 + 756 591510 Pr-151 4.43410E-03 6.86300E-03 591510 + 757 591520 Pr-152 2.49270E-03 3.49870E-03 591520 + 758 591530 Pr-153 1.66220E-03 1.86490E-03 591530 + 759 591540 Pr-154 4.23150E-04 4.53830E-04 591540 + 760 591550 Pr-155 1.72260E-04 1.74810E-04 591550 + 761 591560 Pr-156 1.75360E-05 1.75380E-05 591560 + 762 591570 Pr-157 3.79100E-06 3.79100E-06 591570 + 763 591580 Pr-158 3.00510E-09 3.00510E-09 591580 + 764 591590 Pr-159 5.48110E-11 5.48110E-11 591590 + 765 601460 Nd-146 9.56640E-07 2.55500E-02 60146.82c + 766 601470 Nd-147 3.58760E-06 2.14980E-02 60147.82c + 767 601480 Nd-148 2.90750E-05 1.79710E-02 60148.82c + 768 601490 Nd-149 1.18050E-04 1.32500E-02 601490 + 769 601500 Nd-150 5.56230E-04 1.06960E-02 60150.82c + 770 601510 Nd-151 1.48240E-03 8.34540E-03 601510 + 771 601520 Nd-152 2.83610E-03 6.33480E-03 601520 + 772 601530 Nd-153 3.08680E-03 4.95170E-03 601530 + 773 601540 Nd-154 2.20850E-03 2.66230E-03 601540 + 774 601550 Nd-155 1.39300E-03 1.56830E-03 601550 + 775 601560 Nd-156 7.09320E-04 7.26620E-04 601560 + 776 601570 Nd-157 2.07010E-04 2.10560E-04 601570 + 777 601580 Nd-158 4.51500E-05 4.51530E-05 601580 + 778 601590 Nd-159 2.30240E-07 2.30300E-07 601590 + 779 601600 Nd-160 1.10990E-08 1.10990E-08 601600 + 780 601610 Nd-161 1.23720E-10 1.23720E-10 601610 + 781 611480 Pm-148 1.03140E-10 1.17190E-10 61148.82c + 782 611481 Pm-148m 2.81120E-10 2.81120E-10 61548.82c + 783 611490 Pm-149 1.71370E-08 1.32500E-02 61149.82c + 784 611500 Pm-150 3.38190E-07 3.38190E-07 611500 + 785 611510 Pm-151 1.22050E-05 8.35760E-03 61151.82c + 786 611520 Pm-152 8.26920E-06 6.34300E-03 611520 + 787 611521 Pm-152m 1.73850E-05 1.73850E-05 611521 + 788 611522 Pm-152m 2.27090E-05 2.27090E-05 611522 + 789 611530 Pm-153 1.97830E-04 5.14960E-03 611530 + 790 611540 Pm-154 1.67100E-04 2.82940E-03 611540 + 791 611541 Pm-154m 1.67100E-04 1.67100E-04 611541 + 792 611550 Pm-155 6.96380E-04 2.26470E-03 611550 + 793 611560 Pm-156 6.56320E-04 1.38290E-03 611560 + 794 611570 Pm-157 5.83580E-04 7.94140E-04 611570 + 795 611580 Pm-158 1.67740E-04 2.12890E-04 611580 + 796 611590 Pm-159 5.45210E-05 5.47510E-05 611590 + 797 611600 Pm-160 2.57070E-05 2.57180E-05 611600 + 798 611610 Pm-161 4.36850E-07 4.36970E-07 611610 + 799 611620 Pm-162 1.87270E-08 1.87270E-08 611620 + 800 611630 Pm-163 3.20850E-10 3.20850E-10 611630 + 801 621510 Sm-151 8.69670E-10 8.35760E-03 62151.82c + 802 621520 Sm-152 2.93380E-06 6.38610E-03 62152.82c + 803 621530 Sm-153 2.28380E-06 5.15820E-03 62153.82c + 804 621531 Sm-153m 6.38990E-06 6.38990E-06 621531 + 805 621540 Sm-154 2.60710E-05 3.02260E-03 62154.82c + 806 621550 Sm-155 1.17190E-04 2.38190E-03 621550 + 807 621560 Sm-156 3.03230E-04 1.68620E-03 621560 + 808 621570 Sm-157 4.90010E-04 1.28410E-03 621570 + 809 621580 Sm-158 3.43600E-04 5.56500E-04 621580 + 810 621590 Sm-159 2.30590E-04 2.85400E-04 621590 + 811 621600 Sm-160 1.11420E-04 1.37070E-04 621600 + 812 621610 Sm-161 5.67270E-05 5.71640E-05 621610 + 813 621620 Sm-162 1.27690E-05 1.27880E-05 621620 + 814 621630 Sm-163 2.95990E-07 2.96310E-07 621630 + 815 621640 Sm-164 1.68930E-08 1.68930E-08 621640 + 816 621650 Sm-165 6.54160E-10 6.54160E-10 621650 + 817 631540 Eu-154 9.82030E-10 2.04080E-09 63154.82c + 818 631541 Eu-154m 1.05880E-09 1.05880E-09 631541 + 819 631550 Eu-155 2.55340E-06 2.38440E-03 63155.82c + 820 631560 Eu-156 5.84940E-06 1.69200E-03 63156.82c + 821 631570 Eu-157 1.13780E-05 1.29550E-03 63157.82c + 822 631580 Eu-158 1.40680E-05 5.70570E-04 631580 + 823 631590 Eu-159 3.33930E-05 3.18790E-04 631590 + 824 631600 Eu-160 4.72310E-05 1.84300E-04 631600 + 825 631610 Eu-161 5.04950E-05 1.07660E-04 631610 + 826 631620 Eu-162 7.02340E-05 8.30220E-05 631620 + 827 631630 Eu-163 2.01130E-05 2.04090E-05 631630 + 828 631640 Eu-164 6.70920E-06 6.72610E-06 631640 + 829 631650 Eu-165 5.00620E-07 5.01270E-07 631650 + 830 631660 Eu-166 1.57830E-08 1.57830E-08 631660 + 831 631670 Eu-167 1.05670E-09 1.05670E-09 631670 + 832 641560 Gd-156 2.68050E-10 1.69200E-03 64156.82c + 833 641570 Gd-157 6.20780E-09 1.29550E-03 64157.82c + 834 641580 Gd-158 1.17180E-07 5.70690E-04 64158.82c + 835 641590 Gd-159 6.61530E-07 3.19450E-04 641590 + 836 641600 Gd-160 1.28760E-05 1.97180E-04 64160.82c + 837 641610 Gd-161 1.26240E-05 1.20280E-04 641610 + 838 641620 Gd-162 3.19610E-05 1.14980E-04 641620 + 839 641630 Gd-163 1.34150E-05 3.38240E-05 641630 + 840 641640 Gd-164 6.71030E-06 1.34360E-05 641640 + 841 641650 Gd-165 1.53440E-05 1.58450E-05 641650 + 842 641660 Gd-166 1.87290E-06 1.88870E-06 641660 + 843 641670 Gd-167 2.14320E-07 2.15380E-07 641670 + 844 641680 Gd-168 2.81200E-08 2.81200E-08 641680 + 845 641690 Gd-169 1.05100E-09 1.05100E-09 641690 + 846 651590 Tb-159 2.85010E-10 3.19450E-04 65159.82c + 847 651600 Tb-160 4.31370E-09 4.31370E-09 65160.82c + 848 651610 Tb-161 8.49510E-08 1.20370E-04 651610 + 849 651620 Tb-162 6.26130E-07 1.15610E-04 651620 + 850 651630 Tb-163 1.88370E-06 3.57080E-05 651630 + 851 651640 Tb-164 1.91930E-06 1.53560E-05 651640 + 852 651650 Tb-165 7.94750E-06 2.37930E-05 651650 + 853 651660 Tb-166 5.95500E-06 7.84370E-06 651660 + 854 651670 Tb-167 2.64030E-06 2.85570E-06 651670 + 855 651680 Tb-168 5.27590E-07 5.55710E-07 651680 + 856 651690 Tb-169 1.81410E-07 1.82460E-07 651690 + 857 651700 Tb-170 1.19110E-08 1.19110E-08 651700 + 858 651710 Tb-171 1.18790E-09 1.18790E-09 651710 + 859 661610 Dy-161 9.27890E-12 1.20370E-04 66161.82c + 860 661620 Dy-162 7.11070E-10 1.15610E-04 66162.82c + 861 661630 Dy-163 3.88570E-09 3.57120E-05 66163.82c + 862 661640 Dy-164 3.81680E-08 1.53940E-05 66164.82c + 863 661650 Dy-165 2.25590E-07 2.40480E-05 661650 + 864 661651 Dy-165m 3.00360E-08 3.00360E-08 661651 + 865 661660 Dy-166 7.88130E-07 8.63180E-06 661660 + 866 661670 Dy-167 9.68630E-07 3.82430E-06 661670 + 867 661680 Dy-168 1.42780E-06 1.98350E-06 661680 + 868 661690 Dy-169 6.65230E-07 8.47690E-07 661690 + 869 661700 Dy-170 3.54410E-07 3.66320E-07 661700 + 870 661710 Dy-171 5.60340E-08 5.72220E-08 661710 + 871 661720 Dy-172 1.39040E-08 1.39040E-08 661720 + 872 661730 Dy-173 7.60240E-10 7.60240E-10 661730 + 873 671640 Ho-164 1.69450E-12 6.31340E-12 671640 + 874 671641 Ho-164m 4.61890E-12 4.61890E-12 671641 + 875 671650 Ho-165 4.40550E-10 2.40490E-05 67165.82c + 876 671660 Ho-166 6.47730E-10 8.63250E-06 671660 + 877 671661 Ho-166m 1.76560E-09 1.76560E-09 671661 + 878 671670 Ho-167 2.77680E-08 3.85210E-06 671670 + 879 671680 Ho-168 2.38360E-08 2.04700E-06 671680 + 880 671681 Ho-168m 3.98630E-08 3.98630E-08 671681 + 881 671690 Ho-169 2.36410E-07 1.08410E-06 671690 + 882 671700 Ho-170 1.23560E-07 1.23560E-07 671700 + 883 671701 Ho-170m 4.53300E-08 4.11650E-07 671701 + 884 671710 Ho-171 1.97660E-07 2.54880E-07 671710 + 885 671720 Ho-172 6.84930E-08 8.23970E-08 671720 + 886 671730 Ho-173 3.16610E-08 3.24210E-08 671730 + 887 671740 Ho-174 3.41050E-09 3.41050E-09 671740 + 888 671750 Ho-175 6.89900E-10 6.89900E-10 671750 + 889 681670 Er-167 1.10530E-11 3.85210E-06 68167.82c + 890 681671 Er-167m 1.47170E-12 4.60290E-07 681671 + 891 681680 Er-168 2.90130E-10 2.04750E-06 68168.82c + 892 681690 Er-169 1.86730E-09 1.08600E-06 681690 + 893 681700 Er-170 1.20700E-08 5.47280E-07 68170.82c + 894 681710 Er-171 2.11020E-08 2.75980E-07 681710 + 895 681720 Er-172 5.62170E-08 1.38610E-07 681720 + 896 681730 Er-173 3.44110E-08 6.68320E-08 681730 + 897 681740 Er-174 2.79260E-08 3.13360E-08 681740 + 898 681750 Er-175 8.19200E-09 8.88190E-09 681750 + 899 681760 Er-176 3.26240E-09 3.26240E-09 681760 + 900 681770 Er-177 2.89640E-10 2.89640E-10 681770 + 901 691700 Tm-170 8.23120E-12 8.23120E-12 691700 + 902 691710 Tm-171 1.42820E-10 2.76130E-07 691710 + 903 691720 Tm-172 6.41120E-10 1.39260E-07 691720 + 904 691730 Tm-173 3.41720E-09 7.02490E-08 691730 + 905 691740 Tm-174 3.97860E-09 3.53150E-08 691740 + 906 691750 Tm-175 8.73940E-09 1.76210E-08 691750 + 907 691760 Tm-176 4.61770E-09 7.88010E-09 691760 + 908 691770 Tm-177 3.18030E-09 3.46990E-09 691770 + 909 691780 Tm-178 6.38610E-10 6.38610E-10 691780 + 910 691790 Tm-179 2.16580E-10 2.16580E-10 691790 + 911 701730 Yb-173 6.16480E-12 7.02560E-08 701730 + 912 701740 Yb-174 6.95510E-11 3.53850E-08 701740 + 913 701750 Yb-175 2.19670E-10 1.78700E-08 701750 + 914 701751 Yb-175m 2.92480E-11 1.35980E-08 701751 + 915 701760 Yb-176 3.54890E-10 8.51100E-09 701760 + 916 701761 Yb-176m 7.44510E-10 4.68460E-09 701761 + 917 701770 Yb-177 8.72190E-10 4.51770E-09 701770 + 918 701771 Yb-177m 1.75610E-10 3.64560E-09 701771 + 919 701780 Yb-178 1.55370E-09 2.19230E-09 701780 + 920 701790 Yb-179 7.10640E-10 9.27220E-10 701790 + 921 701800 Yb-180 3.90460E-10 3.90460E-10 701800 + 922 701810 Yb-181 6.54590E-11 6.54590E-11 701810 + 923 711760 Lu-176 1.99780E-12 4.70450E-10 71176.82c + 924 711770 Lu-177 1.76620E-11 4.53740E-09 711770 + 925 711771 Lu-177m 8.40990E-12 8.61920E-12 711771 + 926 711780 Lu-178 2.63320E-11 2.21860E-09 711780 + 927 711781 Lu-178m 3.52770E-11 3.52770E-11 711781 + 928 711790 Lu-179 1.99600E-10 1.15340E-09 711790 + 929 711791 Lu-179m 2.65760E-11 9.53800E-10 711791 + 930 711800 Lu-180 4.43710E-11 3.01070E-10 711800 + 931 711801 Lu-180m 4.43710E-11 4.34830E-10 711801 + 932 711802 Lu-180m 7.85690E-11 7.85690E-11 711802 + 933 711810 Lu-181 2.07240E-10 2.72700E-10 711810 + 934 711820 Lu-182 7.51980E-11 7.51980E-11 711820 + 935 711830 Lu-183 3.57840E-11 3.57840E-11 711830 + 936 711840 Lu-184 4.05970E-12 4.05970E-12 711840 + 937 721790 Hf-179 9.09290E-13 1.15500E-09 72179.82c + 938 721800 Hf-180 3.41550E-12 5.68210E-10 72180.82c + 939 721801 Hf-180m 7.16540E-12 4.64500E-11 721801 + 940 721810 Hf-181 1.97390E-11 2.92440E-10 721810 + 941 721820 Hf-182 1.78900E-11 1.08850E-10 721820 + 942 721821 Hf-182m 3.75300E-11 3.75300E-11 721821 + 943 721830 Hf-183 3.49690E-11 7.07530E-11 721830 + 944 721840 Hf-184 9.60400E-12 1.16340E-11 721840 + 945 721841 Hf-184m 2.01480E-11 2.21780E-11 721841 + 946 721850 Hf-185 9.15630E-12 9.15630E-12 721850 + 947 731830 Ta-183 3.08510E-12 7.38380E-11 731830 + 948 731840 Ta-184 3.79480E-12 3.76070E-11 731840 + 949 731850 Ta-185 5.50050E-12 1.79390E-11 731850 + 950 731851 Ta-185m 3.28200E-12 3.28200E-12 731851 + + Nuclide 94241.82c -- plutonium 241 (Pu-241) + + Neutron-induced fission: + + Interpolation region : 1 / 2 + Interpolation energy : 2.53000E-08 MeV + Number of products : 958 / 1071 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 2.94220E-05 2.94220E-05 1001.82c + 2 10020 H-2 8.99170E-06 8.99170E-06 1002.82c + 3 10030 H-3 1.41000E-04 1.41000E-04 1003.82c + 4 20040 He-4 1.86000E-03 1.86000E-03 2004.82c + 5 210530 Sc-53 1.98420E-12 1.98420E-12 210530 + 6 210540 Sc-54 1.16690E-12 1.16690E-12 210540 + 7 210550 Sc-55 1.26230E-12 1.26230E-12 210550 + 8 220540 Ti-54 4.05280E-12 5.21970E-12 220540 + 9 220550 Ti-55 5.80820E-12 7.07050E-12 220550 + 10 220560 Ti-56 1.04980E-11 1.04980E-11 220560 + 11 220570 Ti-57 4.97030E-12 4.97030E-12 220570 + 12 220580 Ti-58 3.96060E-12 3.96060E-12 220580 + 13 230550 V-55 2.89680E-12 9.96730E-12 230550 + 14 230560 V-56 6.71810E-12 1.72310E-11 230560 + 15 230570 V-57 2.44570E-11 2.94120E-11 230570 + 16 230580 V-58 2.67220E-11 3.06830E-11 230580 + 17 230590 V-59 4.20210E-11 4.20210E-11 230590 + 18 230600 V-60 1.41450E-11 1.41450E-11 230600 + 19 230610 V-61 8.89800E-12 8.89800E-12 230610 + 20 230620 V-62 1.28840E-12 1.28840E-12 230620 + 21 240570 Cr-57 3.33410E-12 5.71750E-11 240570 + 22 240580 Cr-58 2.84500E-11 3.45870E-11 240580 + 23 240590 Cr-59 5.71050E-11 9.91260E-11 240590 + 24 240600 Cr-60 1.51370E-10 1.66050E-10 240600 + 25 240610 Cr-61 1.35850E-10 1.44210E-10 240610 + 26 240620 Cr-62 1.81750E-10 1.83040E-10 240620 + 27 240630 Cr-63 4.97940E-11 4.97940E-11 240630 + 28 240640 Cr-64 2.07050E-11 2.07050E-11 240640 + 29 240650 Cr-65 2.42620E-12 2.42620E-12 240650 + 30 250590 Mn-59 8.21140E-12 1.07340E-10 250590 + 31 250600 Mn-60 2.98760E-12 1.72090E-10 250600 + 32 250601 Mn-60m 2.65340E-11 2.65340E-11 250601 + 33 250610 Mn-61 2.02770E-10 3.46980E-10 250610 + 34 250620 Mn-62 2.96360E-10 3.87890E-10 250620 + 35 250621 Mn-62m 5.32050E-11 1.44720E-10 250621 + 36 250630 Mn-63 7.80040E-10 8.29830E-10 250630 + 37 250640 Mn-64 4.82100E-10 5.02810E-10 250640 + 38 250650 Mn-65 5.40590E-10 5.43020E-10 250650 + 39 250660 Mn-66 1.18150E-10 1.18150E-10 250660 + 40 250670 Mn-67 3.80490E-11 3.80490E-11 250670 + 41 250680 Mn-68 3.22810E-12 3.22810E-12 250680 + 42 260610 Fe-61 7.63210E-12 3.54620E-10 260610 + 43 260620 Fe-62 1.10880E-10 6.43490E-10 260620 + 44 260630 Fe-63 3.25030E-10 1.15490E-09 260630 + 45 260640 Fe-64 1.52760E-09 2.03040E-09 260640 + 46 260650 Fe-65 2.25840E-09 2.80140E-09 260650 + 47 260660 Fe-66 4.18160E-09 4.29980E-09 260660 + 48 260670 Fe-67 2.08160E-09 2.11960E-09 260670 + 49 260680 Fe-68 1.74200E-09 1.74520E-09 260680 + 50 260690 Fe-69 3.17860E-10 3.17860E-10 260690 + 51 260700 Fe-70 6.97070E-11 6.97070E-11 260700 + 52 260710 Fe-71 4.56690E-12 4.56690E-12 260710 + 53 270630 Co-63 1.23210E-11 1.16720E-09 270630 + 54 270640 Co-64 8.56260E-11 2.11600E-09 270640 + 55 270650 Co-65 1.02610E-09 3.82750E-09 270650 + 56 270660 Co-66 2.44330E-09 6.74300E-09 270660 + 57 270670 Co-67 9.32620E-09 1.14460E-08 270670 + 58 270680 Co-68 5.65040E-09 9.02640E-09 270680 + 59 270681 Co-68m 4.98460E-09 6.75210E-09 270681 + 60 270690 Co-69 1.71290E-08 1.74250E-08 270690 + 61 270700 Co-70 3.00820E-09 3.00820E-09 270700 + 62 270701 Co-70m 3.00820E-09 3.07800E-09 270701 + 63 270710 Co-71 3.98810E-09 3.99270E-09 270710 + 64 270720 Co-72 5.98580E-10 5.98580E-10 270720 + 65 270730 Co-73 9.13900E-11 9.13900E-11 270730 + 66 270740 Co-74 3.24360E-12 3.24360E-12 270740 + 67 280650 Ni-65 9.73820E-12 3.83730E-09 280650 + 68 280660 Ni-66 2.13210E-10 6.95630E-09 280660 + 69 280670 Ni-67 1.15500E-09 1.26010E-08 280670 + 70 280680 Ni-68 1.03330E-08 2.29100E-08 280680 + 71 280690 Ni-69 1.06200E-08 2.78700E-08 280690 + 72 280691 Ni-69m 1.06200E-08 1.06200E-08 280691 + 73 280700 Ni-70 5.84680E-08 6.45540E-08 280700 + 74 280710 Ni-71 5.49160E-08 5.89090E-08 280710 + 75 280720 Ni-72 7.56790E-08 7.62780E-08 280720 + 76 280730 Ni-73 9.39510E-08 9.40420E-08 280730 + 77 280740 Ni-74 7.00600E-09 7.00920E-09 280740 + 78 280750 Ni-75 1.08300E-09 1.08300E-09 280750 + 79 280760 Ni-76 1.57730E-10 1.57730E-10 280760 + 80 280770 Ni-77 5.43730E-12 5.43730E-12 280770 + 81 280780 Ni-78 1.22020E-12 1.22020E-12 280780 + 82 290670 Cu-67 1.06060E-11 1.26120E-08 290670 + 83 290680 Cu-68 4.55260E-11 2.30450E-08 290680 + 84 290681 Cu-68m 1.06630E-10 1.06630E-10 290681 + 85 290690 Cu-69 2.76490E-09 4.12550E-08 290690 + 86 290700 Cu-70 7.90370E-10 6.82660E-09 290700 + 87 290701 Cu-70m 8.80530E-09 1.20720E-08 290701 + 88 290702 Cu-70m 7.90370E-10 6.53450E-08 290702 + 89 290710 Cu-71 7.48450E-08 1.33750E-07 290710 + 90 290720 Cu-72 1.32570E-07 2.08850E-07 290720 + 91 290730 Cu-73 2.81850E-07 3.75890E-07 290730 + 92 290740 Cu-74 1.46660E-07 1.53690E-07 290740 + 93 290750 Cu-75 4.81180E-07 4.82250E-07 290750 + 94 290760 Cu-76 2.66330E-08 2.67110E-08 290760 + 95 290761 Cu-76m 2.66330E-08 2.67110E-08 290761 + 96 290770 Cu-77 1.93330E-08 1.93380E-08 290770 + 97 290780 Cu-78 5.45230E-09 5.45350E-09 290780 + 98 290790 Cu-79 1.15240E-09 1.15240E-09 290790 + 99 290800 Cu-80 3.71290E-11 3.71290E-11 290800 + 100 300690 Zn-69 1.15320E-12 4.12610E-08 300690 + 101 300691 Zn-69m 4.98750E-12 4.98750E-12 300691 + 102 300700 Zn-70 2.27780E-10 7.51680E-08 300700 + 103 300710 Zn-71 4.77200E-10 1.34230E-07 300710 + 104 300711 Zn-71m 2.06380E-09 2.06380E-09 300711 + 105 300720 Zn-72 3.81880E-08 2.47040E-07 300720 + 106 300730 Zn-73 1.01760E-08 4.39380E-07 300730 + 107 300731 Zn-73m 1.39110E-08 5.33130E-08 300731 + 108 300732 Zn-73m 7.88030E-08 7.88030E-08 300732 + 109 300740 Zn-74 5.48930E-07 7.19500E-07 300740 + 110 300750 Zn-75 4.81180E-07 9.47350E-07 300750 + 111 300760 Zn-76 2.25480E-06 2.30740E-06 300760 + 112 300770 Zn-77 1.45770E-06 1.58840E-06 300770 + 113 300771 Zn-77m 2.22830E-07 2.22830E-07 300771 + 114 300780 Zn-78 6.69330E-06 6.69940E-06 300780 + 115 300790 Zn-79 2.01690E-06 2.01740E-06 300790 + 116 300800 Zn-80 3.56510E-07 3.56550E-07 300800 + 117 300810 Zn-81 2.43770E-08 2.43770E-08 300810 + 118 300820 Zn-82 2.12470E-09 2.12470E-09 300820 + 119 300830 Zn-83 4.98350E-11 4.98350E-11 300830 + 120 310710 Ga-71 5.30480E-12 1.36300E-07 310710 + 121 310720 Ga-72 1.22070E-10 2.47170E-07 310720 + 122 310721 Ga-72m 1.37450E-11 8.24510E-09 310721 + 123 310730 Ga-73 3.50620E-09 4.82290E-07 310730 + 124 310740 Ga-74 1.07560E-08 5.58440E-07 310740 + 125 310741 Ga-74m 1.07560E-08 7.30250E-07 310741 + 126 310750 Ga-75 4.81180E-07 1.42850E-06 310750 + 127 310760 Ga-76 2.37350E-07 2.54480E-06 310760 + 128 310770 Ga-77 2.28060E-06 3.98040E-06 310770 + 129 310780 Ga-78 9.84270E-06 1.65680E-05 310780 + 130 310790 Ga-79 4.03440E-05 4.23350E-05 310790 + 131 310800 Ga-80 2.82470E-05 2.86050E-05 310800 + 132 310810 Ga-81 2.94890E-05 2.95120E-05 310810 + 133 310820 Ga-82 1.16710E-05 1.16730E-05 310820 + 134 310830 Ga-83 6.11600E-07 6.11650E-07 310830 + 135 310840 Ga-84 2.78480E-08 2.78480E-08 310840 + 136 310850 Ga-85 1.05070E-09 1.05070E-09 310850 + 137 320730 Ge-73 1.40260E-12 4.82290E-07 32073.82c + 138 320731 Ge-73m 3.24310E-13 4.75210E-07 320731 + 139 320740 Ge-74 1.10150E-10 7.41120E-07 32074.82c + 140 320750 Ge-75 3.82020E-10 1.43140E-06 320750 + 141 320751 Ge-75m 2.49900E-09 5.96400E-08 320751 + 142 320760 Ge-76 1.18670E-07 2.66340E-06 32076.82c + 143 320770 Ge-77 7.28800E-07 1.50620E-06 320770 + 144 320771 Ge-77m 1.11410E-07 4.09180E-06 320771 + 145 320780 Ge-78 1.41720E-05 3.07780E-05 320780 + 146 320790 Ge-79 8.11110E-06 5.24700E-05 320790 + 147 320791 Ge-79m 5.30590E-05 5.31220E-05 320791 + 148 320800 Ge-80 2.08790E-04 2.40910E-04 320800 + 149 320810 Ge-81 2.79890E-04 2.95650E-04 320810 + 150 320811 Ge-81m 6.47180E-05 7.82300E-05 320811 + 151 320820 Ge-82 4.70890E-04 4.80300E-04 320820 + 152 320830 Ge-83 2.76120E-04 2.76530E-04 320830 + 153 320840 Ge-84 1.16560E-04 1.16570E-04 320840 + 154 320850 Ge-85 5.61050E-06 5.61150E-06 320850 + 155 320860 Ge-86 2.83010E-06 2.83010E-06 320860 + 156 320870 Ge-87 1.11540E-08 1.11540E-08 320870 + 157 320880 Ge-88 4.08590E-10 4.08590E-10 320880 + 158 330750 As-75 3.10790E-13 1.43140E-06 33075.82c + 159 330751 As-75m 1.01680E-12 1.89090E-11 330751 + 160 330760 As-76 5.76320E-11 5.76320E-11 330760 + 161 330770 As-77 1.20030E-07 4.94070E-06 330770 + 162 330780 As-78 3.93700E-07 3.11720E-05 330780 + 163 330790 As-79 4.03360E-06 1.07500E-04 330790 + 164 330800 As-80 3.22710E-05 2.73180E-04 330800 + 165 330810 As-81 1.54030E-04 5.27130E-04 330810 + 166 330820 As-82 1.07400E-04 5.87700E-04 330820 + 167 330821 As-82m 3.24090E-04 3.24090E-04 330821 + 168 330830 As-83 9.54580E-04 1.24370E-03 330830 + 169 330840 As-84 4.27460E-04 4.79840E-04 330840 + 170 330841 As-84m 4.27460E-04 4.79840E-04 330841 + 171 330850 As-85 4.77550E-04 4.82380E-04 330850 + 172 330860 As-86 1.81140E-04 1.83970E-04 330860 + 173 330870 As-87 5.83970E-05 5.84080E-05 330870 + 174 330880 As-88 1.18160E-05 1.18160E-05 330880 + 175 330890 As-89 1.75790E-07 1.75790E-07 330890 + 176 330900 As-90 3.13230E-09 3.13230E-09 330900 + 177 340780 Se-78 1.92790E-10 3.11720E-05 34078.82c + 178 340790 Se-79 5.83140E-07 1.08120E-04 34079.82c + 179 340791 Se-79m 8.91440E-08 1.05040E-04 340791 + 180 340800 Se-80 4.03430E-06 2.77210E-04 34080.82c + 181 340810 Se-81 3.37560E-06 5.52560E-04 340810 + 182 340811 Se-81m 2.20810E-05 4.10040E-05 340811 + 183 340820 Se-82 1.48230E-04 1.06000E-03 34082.82c + 184 340830 Se-83 6.02360E-04 1.05080E-03 340830 + 185 340831 Se-83m 1.39280E-04 9.35920E-04 340831 + 186 340840 Se-84 2.48670E-03 3.55120E-03 340840 + 187 340850 Se-85 2.88000E-03 3.31700E-03 340850 + 188 340860 Se-86 4.44370E-03 4.57590E-03 340860 + 189 340870 Se-87 3.25210E-03 3.30150E-03 340870 + 190 340880 Se-88 1.59920E-03 1.61100E-03 340880 + 191 340890 Se-89 3.93020E-04 3.93200E-04 340890 + 192 340900 Se-90 9.37320E-05 9.37350E-05 340900 + 193 340910 Se-91 1.81510E-06 1.81510E-06 340910 + 194 340920 Se-92 1.90320E-06 1.90320E-06 340920 + 195 340930 Se-93 7.13640E-10 7.13640E-10 340930 + 196 350800 Br-80 3.38850E-11 1.36140E-10 350800 + 197 350801 Br-80m 1.02250E-10 1.02250E-10 350801 + 198 350810 Br-81 1.66800E-08 5.52600E-04 35081.82c + 199 350820 Br-82 3.09330E-07 4.38230E-07 350820 + 200 350821 Br-82m 1.32070E-07 1.32070E-07 350821 + 201 350830 Br-83 1.37320E-05 2.00040E-03 350830 + 202 350840 Br-84 5.95850E-05 3.61070E-03 350840 + 203 350841 Br-84m 5.95850E-05 5.95850E-05 350841 + 204 350850 Br-85 5.11810E-04 3.82880E-03 350850 + 205 350860 Br-86 1.13860E-03 5.71450E-03 350860 + 206 350870 Br-87 2.81740E-03 6.13490E-03 350870 + 207 350880 Br-88 4.01530E-03 5.64100E-03 350880 + 208 350890 Br-89 3.77510E-03 4.13760E-03 350890 + 209 350900 Br-90 1.80770E-03 1.90180E-03 350900 + 210 350910 Br-91 8.42250E-04 8.43680E-04 350910 + 211 350920 Br-92 1.84790E-04 1.86690E-04 350920 + 212 350930 Br-93 4.41480E-05 4.41490E-05 350930 + 213 350940 Br-94 3.51020E-06 3.51020E-06 350940 + 214 350950 Br-95 1.52020E-08 1.52020E-08 350950 + 215 360820 Kr-82 1.24980E-10 4.41520E-07 36082.82c + 216 360830 Kr-83 5.54530E-09 2.00040E-03 36083.82c + 217 360831 Kr-83m 1.28220E-09 1.99860E-03 360831 + 218 360840 Kr-84 3.81030E-06 3.67410E-03 36084.82c + 219 360850 Kr-85 2.37610E-05 8.49190E-04 36085.82c + 220 360851 Kr-85m 5.49410E-06 3.82800E-03 360851 + 221 360860 Kr-86 3.54780E-04 6.22330E-03 36086.82c + 222 360870 Kr-87 1.13520E-03 7.49400E-03 360870 + 223 360880 Kr-88 3.94590E-03 9.79240E-03 360880 + 224 360890 Kr-89 6.89600E-03 1.09180E-02 360890 + 225 360900 Kr-90 1.08540E-02 1.24570E-02 360900 + 226 360910 Kr-91 9.55020E-03 1.02870E-02 360910 + 227 360920 Kr-92 7.99650E-03 8.15140E-03 360920 + 228 360930 Kr-93 3.52420E-03 3.54080E-03 360930 + 229 360940 Kr-94 1.16930E-03 1.17030E-03 360940 + 230 360950 Kr-95 1.97790E-04 1.97810E-04 360950 + 231 360960 Kr-96 4.01090E-05 4.01090E-05 360960 + 232 360970 Kr-97 3.86770E-06 3.86770E-06 360970 + 233 360980 Kr-98 2.01400E-09 2.01400E-09 360980 + 234 370850 Rb-85 2.49540E-09 3.85800E-03 37085.82c + 235 370860 Rb-86 3.30590E-08 9.25260E-08 37086.82c + 236 370861 Rb-86m 5.94660E-08 5.94660E-08 370861 + 237 370870 Rb-87 2.02360E-05 7.51430E-03 37087.82c + 238 370880 Rb-88 1.21250E-04 9.91360E-03 370880 + 239 370890 Rb-89 7.08990E-04 1.16270E-02 370890 + 240 370900 Rb-90 1.92710E-04 1.11070E-02 370900 + 241 370901 Rb-90m 1.71160E-03 3.34090E-03 370901 + 242 370910 Rb-91 5.47030E-03 1.57570E-02 370910 + 243 370920 Rb-92 9.23980E-03 1.73910E-02 370920 + 244 370930 Rb-93 1.37100E-02 1.72640E-02 370930 + 245 370940 Rb-94 8.63890E-03 9.80190E-03 370940 + 246 370950 Rb-95 6.26540E-03 6.45900E-03 370950 + 247 370960 Rb-96 1.02030E-03 1.55950E-03 370960 + 248 370961 Rb-96m 1.02030E-03 1.03970E-03 370961 + 249 370970 Rb-97 6.99760E-04 7.03370E-04 370970 + 250 370980 Rb-98 4.64130E-05 4.64130E-05 370980 + 251 370981 Rb-98m 4.64130E-05 4.64140E-05 370981 + 252 370990 Rb-99 2.32700E-05 2.32700E-05 370990 + 253 371000 Rb-100 1.90980E-08 1.90980E-08 371000 + 254 380870 Sr-87 3.01980E-10 3.71590E-10 38087.82c + 255 380871 Sr-87m 6.98240E-11 6.98240E-11 380871 + 256 380880 Sr-88 2.62020E-06 9.91630E-03 38088.82c + 257 380890 Sr-89 1.93510E-05 1.16460E-02 38089.82c + 258 380900 Sr-90 2.15650E-04 1.45770E-02 38090.82c + 259 380910 Sr-91 9.05590E-04 1.66630E-02 380910 + 260 380920 Sr-92 4.55830E-03 2.21910E-02 380920 + 261 380930 Sr-93 1.05810E-02 2.85930E-02 380930 + 262 380940 Sr-94 2.13660E-02 3.07330E-02 380940 + 263 380950 Sr-95 2.57900E-02 3.19030E-02 380950 + 264 380960 Sr-96 2.60480E-02 2.80950E-02 380960 + 265 380970 Sr-97 1.51510E-02 1.56840E-02 380970 + 266 380980 Sr-98 7.77360E-03 7.86370E-03 380980 + 267 380990 Sr-99 2.10800E-03 2.12760E-03 380990 + 268 381000 Sr-100 5.94810E-04 5.94830E-04 381000 + 269 381010 Sr-101 5.29470E-05 5.29470E-05 381010 + 270 381020 Sr-102 6.95050E-06 6.95050E-06 381020 + 271 381030 Sr-103 3.52420E-09 3.52420E-09 381030 + 272 390900 Y-90 4.04180E-07 1.45780E-02 39090.82c + 273 390901 Y-90m 5.73530E-07 5.73530E-07 390901 + 274 390910 Y-91 1.19240E-06 1.66690E-02 39091.82c + 275 390911 Y-91m 5.15720E-06 9.80880E-03 390911 + 276 390920 Y-92 3.99450E-05 2.22310E-02 390920 + 277 390930 Y-93 5.66680E-05 2.90200E-02 390930 + 278 390931 Y-93m 3.70690E-04 7.52580E-03 390931 + 279 390940 Y-94 1.37950E-03 3.21130E-02 390940 + 280 390950 Y-95 6.34110E-03 3.82440E-02 390950 + 281 390960 Y-96 4.17080E-03 3.22700E-02 390960 + 282 390961 Y-96m 7.50220E-03 7.50620E-03 390961 + 283 390970 Y-97 4.34790E-03 1.78340E-02 390970 + 284 390971 Y-97m 1.48200E-02 2.03380E-02 390971 + 285 390972 Y-97m 3.98210E-03 3.98210E-03 390972 + 286 390980 Y-98 4.08370E-03 1.19470E-02 390980 + 287 390981 Y-98m 1.71740E-02 1.71740E-02 390981 + 288 390990 Y-99 2.04590E-02 2.25910E-02 390990 + 289 391000 Y-100 5.22750E-03 5.81830E-03 391000 + 290 391001 Y-100m 5.22750E-03 5.22810E-03 391001 + 291 391010 Y-101 4.26140E-03 4.31350E-03 391010 + 292 391020 Y-102 5.09200E-04 5.12480E-04 391020 + 293 391021 Y-102m 5.09200E-04 5.12480E-04 391021 + 294 391030 Y-103 2.93390E-04 2.93390E-04 391030 + 295 391040 Y-104 3.49240E-05 3.49240E-05 391040 + 296 391050 Y-105 2.80240E-06 2.80240E-06 391050 + 297 400920 Zr-92 9.51190E-07 2.22320E-02 40092.82c + 298 400930 Zr-93 7.01180E-06 2.90280E-02 40093.82c + 299 400940 Zr-94 9.21190E-05 3.22050E-02 40094.82c + 300 400950 Zr-95 4.65310E-04 3.87090E-02 40095.82c + 301 400960 Zr-96 2.66120E-03 4.24530E-02 40096.82c + 302 400970 Zr-97 7.44010E-03 4.68730E-02 400970 + 303 400980 Zr-98 2.14960E-02 5.03790E-02 400980 + 304 400990 Zr-99 3.15540E-02 5.38150E-02 400990 + 305 401000 Zr-100 4.81930E-02 5.91860E-02 401000 + 306 401010 Zr-101 3.02340E-02 3.45980E-02 401010 + 307 401020 Zr-102 2.33680E-02 2.43660E-02 401020 + 308 401030 Zr-103 9.87010E-03 1.01430E-02 401030 + 309 401040 Zr-104 3.69690E-03 3.72930E-03 401040 + 310 401050 Zr-105 6.56740E-04 6.58990E-04 401050 + 311 401060 Zr-106 1.16280E-04 1.16280E-04 401060 + 312 401070 Zr-107 1.28870E-05 1.28870E-05 401070 + 313 401080 Zr-108 3.21860E-09 3.21860E-09 401080 + 314 410950 Nb-95 7.71510E-07 3.86860E-02 41095.82c + 315 410951 Nb-95m 1.78390E-07 4.18370E-04 410951 + 316 410960 Nb-96 1.11910E-05 1.11910E-05 410960 + 317 410970 Nb-97 8.87570E-05 4.69820E-02 410970 + 318 410971 Nb-97m 2.05230E-05 4.45720E-02 410971 + 319 410980 Nb-98 1.49750E-04 5.05280E-02 410980 + 320 410981 Nb-98m 4.51890E-04 4.51890E-04 410981 + 321 410990 Nb-99 2.76680E-03 3.71860E-02 410990 + 322 410991 Nb-99m 6.39740E-04 2.04430E-02 410991 + 323 411000 Nb-100 1.80280E-03 6.09890E-02 411000 + 324 411001 Nb-100m 7.58170E-03 7.58170E-03 411001 + 325 411010 Nb-101 2.06560E-02 5.52540E-02 411010 + 326 411020 Nb-102 1.35470E-02 3.79130E-02 411020 + 327 411021 Nb-102m 1.35470E-02 1.35470E-02 411021 + 328 411030 Nb-103 3.55610E-02 4.57040E-02 411030 + 329 411040 Nb-104 1.09370E-02 1.46760E-02 411040 + 330 411041 Nb-104m 1.09370E-02 1.09370E-02 411041 + 331 411050 Nb-105 1.41260E-02 1.47780E-02 411050 + 332 411060 Nb-106 5.72390E-03 5.83890E-03 411060 + 333 411070 Nb-107 2.04290E-03 2.05530E-03 411070 + 334 411080 Nb-108 3.56170E-04 3.56170E-04 411080 + 335 411090 Nb-109 4.57390E-05 4.57390E-05 411090 + 336 411100 Nb-110 2.94600E-06 2.94600E-06 411100 + 337 420970 Mo-97 2.34200E-09 4.69820E-02 42097.82c + 338 420980 Mo-98 1.43540E-05 5.09950E-02 42098.82c + 339 420990 Mo-99 1.21500E-04 5.73430E-02 42099.82c + 340 421000 Mo-100 9.48780E-04 6.95190E-02 42100.82c + 341 421010 Mo-101 3.07470E-03 5.83280E-02 421010 + 342 421020 Mo-102 1.18540E-02 6.33140E-02 421020 + 343 421030 Mo-103 2.28570E-02 6.85750E-02 421030 + 344 421040 Mo-104 4.04450E-02 6.62950E-02 421040 + 345 421050 Mo-105 3.47640E-02 4.95530E-02 421050 + 346 421060 Mo-106 3.64070E-02 4.21060E-02 421060 + 347 421070 Mo-107 1.80630E-02 2.00170E-02 421070 + 348 421080 Mo-108 8.97360E-03 9.31350E-03 421080 + 349 421090 Mo-109 2.25720E-03 2.29830E-03 421090 + 350 421100 Mo-110 4.54790E-04 4.56560E-04 421100 + 351 421110 Mo-111 3.31630E-05 3.31630E-05 421110 + 352 421120 Mo-112 5.07850E-06 5.07850E-06 421120 + 353 421130 Mo-113 1.00280E-06 1.00280E-06 421130 + 354 431000 Tc-100 3.28560E-06 3.28560E-06 431000 + 355 431010 Tc-101 1.70220E-05 5.83450E-02 431010 + 356 431020 Tc-102 8.20500E-05 6.33960E-02 431020 + 357 431021 Tc-102m 8.20500E-05 8.20500E-05 431021 + 358 431030 Tc-103 1.03170E-03 6.96070E-02 431030 + 359 431040 Tc-104 2.99610E-03 6.92920E-02 431040 + 360 431050 Tc-105 9.15320E-03 5.87060E-02 431050 + 361 431060 Tc-106 1.59850E-02 5.80910E-02 431060 + 362 431070 Tc-107 2.42410E-02 4.42580E-02 431070 + 363 431080 Tc-108 1.89190E-02 2.82450E-02 431080 + 364 431090 Tc-109 1.26800E-02 1.49660E-02 431090 + 365 431100 Tc-110 5.00930E-03 5.46620E-03 431100 + 366 431110 Tc-111 1.45490E-03 1.48780E-03 431110 + 367 431120 Tc-112 1.90060E-04 1.95030E-04 431120 + 368 431130 Tc-113 1.40780E-04 1.41780E-04 431130 + 369 431140 Tc-114 1.70290E-04 1.70290E-04 431140 + 370 431150 Tc-115 1.30030E-04 1.30030E-04 431150 + 371 431160 Tc-116 2.78120E-05 2.78120E-05 431160 + 372 441020 Ru-102 1.98600E-06 6.34800E-02 44102.82c + 373 441030 Ru-103 3.05110E-06 6.96170E-02 44103.82c + 374 441031 Ru-103m 7.36590E-06 7.36590E-06 441031 + 375 441040 Ru-104 1.12820E-04 6.94040E-02 44104.82c + 376 441050 Ru-105 5.36900E-04 5.92430E-02 44105.82c + 377 441060 Ru-106 2.58260E-03 6.06740E-02 44106.82c + 378 441070 Ru-107 5.41220E-03 4.96700E-02 441070 + 379 441080 Ru-108 1.13930E-02 3.96500E-02 441080 + 380 441090 Ru-109 1.10040E-02 2.59600E-02 441090 + 381 441100 Ru-110 9.09990E-03 1.45640E-02 441100 + 382 441110 Ru-111 3.47720E-03 4.96790E-03 441110 + 383 441120 Ru-112 1.03260E-03 1.23490E-03 441120 + 384 441130 Ru-113 3.48200E-04 6.65020E-04 441130 + 385 441131 Ru-113m 3.48200E-04 3.48200E-04 441131 + 386 441140 Ru-114 9.10660E-04 1.08850E-03 441140 + 387 441150 Ru-115 3.31690E-04 4.46480E-04 441150 + 388 441160 Ru-116 1.92570E-04 2.16980E-04 441160 + 389 441170 Ru-117 7.70510E-05 7.70510E-05 441170 + 390 441180 Ru-118 5.73240E-05 5.73240E-05 441180 + 391 451050 Rh-105 8.10380E-07 5.92440E-02 45105.82c + 392 451051 Rh-105m 1.23880E-07 1.68180E-02 451051 + 393 451060 Rh-106 3.19990E-06 6.06770E-02 451060 + 394 451061 Rh-106m 7.49510E-06 7.49510E-06 451061 + 395 451070 Rh-107 1.05740E-04 4.97760E-02 451070 + 396 451080 Rh-108 9.09330E-05 3.97410E-02 451080 + 397 451081 Rh-108m 2.74410E-04 2.74410E-04 451081 + 398 451090 Rh-109 1.15020E-03 2.71110E-02 451090 + 399 451100 Rh-110 1.49360E-03 1.60570E-02 451100 + 400 451101 Rh-110m 3.98710E-05 3.98710E-05 451101 + 401 451110 Rh-111 1.54830E-03 6.51630E-03 451110 + 402 451120 Rh-112 3.14220E-04 1.54910E-03 451120 + 403 451121 Rh-112m 3.14220E-04 3.14220E-04 451121 + 404 451130 Rh-113 8.86990E-04 1.72610E-03 451130 + 405 451140 Rh-114 5.75550E-04 1.66500E-03 451140 + 406 451141 Rh-114m 5.75550E-04 5.75550E-04 451141 + 407 451150 Rh-115 6.58750E-04 1.10660E-03 451150 + 408 451160 Rh-116 4.74170E-05 2.63630E-04 451160 + 409 451161 Rh-116m 1.11060E-04 1.11060E-04 451161 + 410 451170 Rh-117 7.76730E-05 1.55500E-04 451170 + 411 451180 Rh-118 1.43980E-05 6.93660E-05 451180 + 412 451190 Rh-119 2.69640E-08 2.69640E-08 451190 + 413 451200 Rh-120 2.25410E-10 2.25410E-10 451200 + 414 451220 Rh-122 1.61890E-07 1.61890E-07 451220 + 415 461070 Pd-107 7.46280E-07 4.97780E-02 46107.82c + 416 461071 Pd-107m 1.40250E-06 1.40250E-06 461071 + 417 461080 Pd-108 9.97980E-06 4.00250E-02 46108.82c + 418 461090 Pd-109 7.97160E-06 2.71340E-02 461090 + 419 461091 Pd-109m 1.49810E-05 1.35700E-02 461091 + 420 461100 Pd-110 6.32090E-05 1.61610E-02 46110.82c + 421 461110 Pd-111 3.48480E-05 6.59190E-03 461110 + 422 461111 Pd-111m 6.54920E-05 9.15570E-05 461111 + 423 461120 Pd-112 1.02870E-04 1.96620E-03 461120 + 424 461130 Pd-113 5.96840E-05 1.92990E-03 461130 + 425 461131 Pd-113m 1.44090E-04 1.44090E-04 461131 + 426 461140 Pd-114 6.05790E-04 2.84640E-03 461140 + 427 461150 Pd-115 1.91430E-04 1.17900E-03 461150 + 428 461151 Pd-115m 3.59760E-04 5.20430E-04 461151 + 429 461160 Pd-116 5.25110E-04 8.99810E-04 461160 + 430 461170 Pd-117 1.43030E-04 5.69350E-04 461170 + 431 461171 Pd-117m 2.68800E-04 2.68800E-04 461171 + 432 461180 Pd-118 2.59800E-04 3.27140E-04 461180 + 433 461190 Pd-119 1.22230E-04 1.22260E-04 461190 + 434 461200 Pd-120 2.64990E-05 2.64990E-05 461200 + 435 461210 Pd-121 1.69240E-05 1.69240E-05 461210 + 436 461220 Pd-122 3.53610E-05 3.55230E-05 461220 + 437 461230 Pd-123 1.09100E-05 1.09100E-05 461230 + 438 461240 Pd-124 2.14610E-06 2.14610E-06 461240 + 439 471100 Ag-110 9.14410E-10 9.43540E-10 471100 + 440 471101 Ag-110m 2.14180E-09 2.14180E-09 47510.82c + 441 471110 Ag-111 9.78300E-08 6.58450E-03 47111.82c + 442 471111 Ag-111m 6.39950E-07 6.56370E-03 471111 + 443 471120 Ag-112 2.54060E-06 1.96880E-03 471120 + 444 471130 Ag-113 1.19740E-06 1.27080E-03 471130 + 445 471131 Ag-113m 7.83250E-06 1.85580E-03 471131 + 446 471140 Ag-114 3.75820E-06 2.86590E-03 471140 + 447 471141 Ag-114m 1.58060E-05 1.58060E-05 471141 + 448 471150 Ag-115 1.19150E-05 1.05630E-03 471150 + 449 471151 Ag-115m 7.79410E-05 8.75060E-04 471151 + 450 471160 Ag-116 4.17740E-05 9.47450E-04 471160 + 451 471161 Ag-116m 9.78460E-05 9.78460E-05 471161 + 452 471170 Ag-117 3.09020E-05 3.44790E-04 471170 + 453 471171 Ag-117m 2.02150E-04 4.86820E-04 471171 + 454 471180 Ag-118 4.15320E-05 4.12700E-04 471180 + 455 471181 Ag-118m 1.74670E-04 2.21440E-04 471181 + 456 471190 Ag-119 5.78770E-05 1.19010E-04 471190 + 457 471191 Ag-119m 3.78600E-04 4.39730E-04 471191 + 458 471200 Ag-120 6.57880E-05 1.18530E-04 471200 + 459 471201 Ag-120m 9.33520E-05 1.06600E-04 471201 + 460 471210 Ag-121 3.72480E-04 3.89360E-04 471210 + 461 471220 Ag-122 1.02230E-04 1.37760E-04 471220 + 462 471221 Ag-122m 9.20880E-05 9.20880E-05 471221 + 463 471230 Ag-123 1.34570E-04 1.45480E-04 471230 + 464 471240 Ag-124 4.21630E-05 6.32980E-05 471240 + 465 471241 Ag-124m 3.79790E-05 3.79790E-05 471241 + 466 471250 Ag-125 4.86700E-05 4.86700E-05 471250 + 467 471260 Ag-126 2.77830E-05 2.77830E-05 471260 + 468 471270 Ag-127 4.94190E-06 4.94190E-06 471270 + 469 471280 Ag-128 5.65150E-08 5.65150E-08 471280 + 470 471290 Ag-129 3.29550E-09 3.29550E-09 471290 + 471 481120 Cd-112 7.78760E-11 1.96880E-03 48112.82c + 472 481130 Cd-113 2.34780E-07 1.91720E-03 48113.82c + 473 481131 Cd-113m 7.68120E-07 2.27390E-05 481131 + 474 481140 Cd-114 2.09700E-07 2.86610E-03 48114.82c + 475 481150 Cd-115 3.61800E-07 1.66700E-03 481150 + 476 481151 Cd-115m 1.18370E-06 8.21770E-05 48515.82c + 477 481160 Cd-116 1.85830E-05 1.05800E-03 48116.82c + 478 481170 Cd-117 2.59450E-06 6.33270E-04 481170 + 479 481171 Cd-117m 8.48850E-06 1.80210E-04 481171 + 480 481180 Cd-118 1.00780E-04 6.44120E-04 481180 + 481 481190 Cd-119 8.17190E-05 5.80950E-04 481190 + 482 481191 Cd-119m 1.97280E-04 2.56790E-04 481191 + 483 481200 Cd-120 2.29120E-04 4.14800E-04 481200 + 484 481210 Cd-121 1.13730E-04 4.62410E-04 481210 + 485 481211 Cd-121m 2.74560E-04 3.15240E-04 481211 + 486 481220 Cd-122 4.92180E-04 7.22020E-04 481220 + 487 481230 Cd-123 1.51300E-04 2.70360E-04 481230 + 488 481231 Cd-123m 3.65250E-04 3.91740E-04 481231 + 489 481240 Cd-124 1.01660E-03 1.09880E-03 481240 + 490 481250 Cd-125 2.38520E-04 2.62850E-04 481250 + 491 481251 Cd-125m 5.75810E-04 6.00150E-04 481251 + 492 481260 Cd-126 6.68190E-04 6.95970E-04 481260 + 493 481270 Cd-127 3.08940E-04 3.13880E-04 481270 + 494 481280 Cd-128 1.20760E-04 1.20820E-04 481280 + 495 481290 Cd-129 1.20790E-05 1.20810E-05 481290 + 496 481291 Cd-129m 2.91610E-05 2.91630E-05 481291 + 497 481300 Cd-130 1.49850E-05 1.49850E-05 481300 + 498 481310 Cd-131 5.72590E-08 5.72590E-08 481310 + 499 481320 Cd-132 1.77870E-09 1.77870E-09 481320 + 500 491150 In-115 3.52550E-10 1.66580E-03 49115.82c + 501 491151 In-115m 8.15180E-11 1.66700E-03 491151 + 502 491160 In-116 1.93350E-09 1.93350E-09 491160 + 503 491161 In-116m 2.96360E-09 5.83410E-09 491161 + 504 491162 In-116m 2.87040E-09 2.87040E-09 491162 + 505 491170 In-117 1.91250E-07 5.05240E-04 491170 + 506 491171 In-117m 4.42210E-08 5.83140E-04 491171 + 507 491180 In-118 4.25670E-07 6.44550E-04 491180 + 508 491181 In-118m 6.52440E-07 1.27550E-06 491181 + 509 491182 In-118m 6.31920E-07 6.31920E-07 491182 + 510 491190 In-119 2.25070E-05 3.64910E-04 491190 + 511 491191 In-119m 5.20410E-06 5.30240E-04 491191 + 512 491200 In-120 1.35660E-05 4.28370E-04 491200 + 513 491201 In-120m 1.35660E-05 1.35660E-05 491201 + 514 491202 In-120m 1.35660E-05 1.35660E-05 491202 + 515 491210 In-121 5.49230E-05 5.29740E-04 491210 + 516 491211 In-121m 1.27000E-05 3.19370E-04 491211 + 517 491220 In-122 8.00960E-05 8.02120E-04 491220 + 518 491221 In-122m 5.68270E-05 5.68270E-05 491221 + 519 491222 In-122m 5.68270E-05 5.68270E-05 491222 + 520 491230 In-123 3.37990E-04 8.08690E-04 491230 + 521 491231 In-123m 7.81510E-05 2.69540E-04 491231 + 522 491240 In-124 2.03810E-04 1.30260E-03 491240 + 523 491241 In-124m 1.83580E-04 1.83580E-04 491241 + 524 491250 In-125 7.05220E-04 1.43120E-03 491250 + 525 491251 In-125m 1.63060E-04 3.00110E-04 491251 + 526 491260 In-126 6.54680E-04 1.35060E-03 491260 + 527 491261 In-126m 5.89720E-04 5.89720E-04 491261 + 528 491270 In-127 1.41640E-03 1.41640E-03 491270 + 529 491271 In-127m 3.27500E-04 6.41390E-04 491271 + 530 491280 In-128 4.36270E-04 7.34670E-04 491280 + 531 491281 In-128m 1.77590E-04 2.98400E-04 491281 + 532 491282 In-128m 5.52950E-04 5.52950E-04 491282 + 533 491290 In-129 8.71900E-04 9.01320E-04 491290 + 534 491291 In-129m 2.01600E-04 2.13950E-04 491291 + 535 491300 In-130 1.93280E-04 2.07750E-04 491300 + 536 491301 In-130m 2.15880E-04 2.15880E-04 491301 + 537 491302 In-130m 3.67310E-04 3.67310E-04 491302 + 538 491310 In-131 1.22230E-04 1.23530E-04 491310 + 539 491311 In-131m 1.22230E-04 1.22230E-04 491311 + 540 491312 In-131m 1.22230E-04 1.22230E-04 491312 + 541 491320 In-132 4.22880E-05 4.22890E-05 491320 + 542 491330 In-133 6.39890E-06 7.87850E-06 491330 + 543 491331 In-133m 1.47960E-06 1.47960E-06 491331 + 544 491340 In-134 2.38200E-08 2.38200E-08 491340 + 545 501170 Sn-117 4.75570E-12 8.13720E-04 50117.82c + 546 501171 Sn-117m 1.55590E-11 1.72140E-06 501171 + 547 501180 Sn-118 1.21980E-09 6.45830E-04 50118.82c + 548 501190 Sn-119 8.10990E-09 8.65490E-04 50119.82c + 549 501191 Sn-119m 2.65330E-08 3.29680E-04 501191 + 550 501200 Sn-120 5.13840E-07 4.56010E-04 50120.82c + 551 501210 Sn-121 4.96850E-06 8.46100E-04 501210 + 552 501211 Sn-121m 1.19950E-05 7.20050E-05 501211 + 553 501220 Sn-122 7.14260E-05 9.87200E-04 50122.82c + 554 501230 Sn-123 1.09460E-04 1.71120E-04 50123.82c + 555 501231 Sn-123m 4.53410E-05 1.06190E-03 501231 + 556 501240 Sn-124 1.43320E-04 1.62950E-03 50124.82c + 557 501250 Sn-125 3.33490E-04 5.75250E-04 50125.82c + 558 501251 Sn-125m 1.38140E-04 1.62770E-03 501251 + 559 501260 Sn-126 1.15220E-03 3.09700E-03 50126.82c + 560 501270 Sn-127 1.63790E-03 2.18990E-03 501270 + 561 501271 Sn-127m 6.78440E-04 2.17970E-03 501271 + 562 501280 Sn-128 1.62360E-03 6.71420E-03 501280 + 563 501281 Sn-128m 3.80300E-03 4.35590E-03 501281 + 564 501290 Sn-129 2.46270E-03 3.48210E-03 501290 + 565 501291 Sn-129m 5.94530E-03 6.04120E-03 501291 + 566 501300 Sn-130 3.53180E-03 4.04790E-03 501300 + 567 501301 Sn-130m 8.27220E-03 8.54950E-03 501301 + 568 501310 Sn-131 2.72360E-03 2.96040E-03 501310 + 569 501311 Sn-131m 6.57520E-03 6.70270E-03 501311 + 570 501320 Sn-132 6.27070E-03 6.31970E-03 501320 + 571 501330 Sn-133 1.15590E-03 1.15710E-03 501330 + 572 501340 Sn-134 2.21630E-04 2.21640E-04 501340 + 573 501350 Sn-135 1.38580E-05 1.38580E-05 501350 + 574 501360 Sn-136 2.93030E-06 2.93030E-06 501360 + 575 501370 Sn-137 3.28870E-09 3.28870E-09 501370 + 576 511200 Sb-120 2.32950E-11 2.32950E-11 511200 + 577 511201 Sb-120m 3.30560E-11 3.30560E-11 511201 + 578 511210 Sb-121 8.57750E-09 8.62240E-04 51121.82c + 579 511230 Sb-123 3.38800E-05 1.26690E-03 51123.82c + 580 511240 Sb-124 7.18670E-06 1.68820E-05 51124.82c + 581 511241 Sb-124m 5.49510E-06 1.29270E-05 511241 + 582 511242 Sb-124m 7.43210E-06 7.43210E-06 511242 + 583 511250 Sb-125 5.46110E-05 2.25750E-03 51125.82c + 584 511260 Sb-126 2.91190E-05 3.60750E-05 51126.82c + 585 511261 Sb-126m 2.15300E-05 4.96880E-05 511261 + 586 511262 Sb-126m 2.81580E-05 2.81580E-05 511262 + 587 511270 Sb-127 1.75610E-04 4.54530E-03 511270 + 588 511280 Sb-128 1.41220E-04 6.86410E-03 511280 + 589 511281 Sb-128m 2.40970E-04 2.40970E-04 511281 + 590 511290 Sb-129 1.26770E-03 8.33960E-03 511290 + 591 511291 Sb-129m 7.74640E-04 3.79520E-03 511291 + 592 511300 Sb-130 3.08180E-03 1.14040E-02 511300 + 593 511301 Sb-130m 3.08180E-03 7.35650E-03 511301 + 594 511310 Sb-131 1.84090E-02 2.80720E-02 511310 + 595 511320 Sb-132 1.40820E-02 2.04020E-02 511320 + 596 511321 Sb-132m 1.03790E-02 1.03790E-02 511321 + 597 511330 Sb-133 2.74370E-02 2.86320E-02 511330 + 598 511340 Sb-134 2.82600E-03 3.01140E-03 511340 + 599 511341 Sb-134m 6.61910E-03 6.62060E-03 511341 + 600 511350 Sb-135 2.86240E-03 2.87420E-03 511350 + 601 511360 Sb-136 6.49720E-04 6.51770E-04 511360 + 602 511370 Sb-137 9.49860E-05 9.49870E-05 511370 + 603 511380 Sb-138 2.80560E-06 2.80560E-06 511380 + 604 511390 Sb-139 3.62180E-08 3.62180E-08 511390 + 605 521260 Te-126 2.51270E-10 7.88070E-05 52126.82c + 606 521270 Te-127 4.25730E-09 4.52730E-03 521270 + 607 521271 Te-127m 1.02780E-08 7.49050E-04 52527.82c + 608 521280 Te-128 1.17650E-05 7.10820E-03 52128.82c + 609 521290 Te-129 1.97310E-05 9.93760E-03 521290 + 610 521291 Te-129m 4.76340E-05 4.58200E-03 52529.82c + 611 521300 Te-130 6.24410E-04 1.93850E-02 52130.82c + 612 521310 Te-131 8.68770E-04 2.76060E-02 521310 + 613 521311 Te-131m 2.09730E-03 4.34480E-03 521311 + 614 521320 Te-132 1.51840E-02 4.59650E-02 52132.82c + 615 521330 Te-133 1.13560E-02 4.07060E-02 521330 + 616 521331 Te-133m 2.74160E-02 3.23690E-02 521331 + 617 521340 Te-134 6.35590E-02 7.36380E-02 521340 + 618 521350 Te-135 3.17240E-02 3.42530E-02 521350 + 619 521360 Te-136 2.01390E-02 2.07290E-02 521360 + 620 521370 Te-137 5.49030E-03 5.53870E-03 521370 + 621 521380 Te-138 1.50570E-03 1.50850E-03 521380 + 622 521390 Te-139 1.86980E-04 1.87020E-04 521390 + 623 521400 Te-140 4.12520E-05 4.12520E-05 521400 + 624 521410 Te-141 1.92130E-06 1.92130E-06 521410 + 625 521420 Te-142 5.23840E-09 5.23840E-09 521420 + 626 531290 I-129 8.48810E-07 1.16340E-02 53129.82c + 627 531300 I-130 2.47660E-06 3.36480E-06 53130.82c + 628 531301 I-130m 1.05740E-06 1.05740E-06 531301 + 629 531310 I-131 2.48260E-05 3.10630E-02 53131.82c + 630 531320 I-132 1.39680E-04 4.61930E-02 531320 + 631 531321 I-132m 1.02940E-04 1.02940E-04 531321 + 632 531330 I-133 1.30730E-03 6.95160E-02 531330 + 633 531331 I-133m 7.98840E-04 7.98840E-04 531331 + 634 531340 I-134 4.62710E-03 8.15970E-02 531340 + 635 531341 I-134m 3.41020E-03 3.41020E-03 531341 + 636 531350 I-135 3.13700E-02 6.56230E-02 53135.82c + 637 531360 I-136 1.11830E-02 3.19950E-02 531360 + 638 531361 I-136m 2.61930E-02 2.62760E-02 531361 + 639 531370 I-137 3.39270E-02 3.93950E-02 531370 + 640 531380 I-138 1.43160E-02 1.57300E-02 531380 + 641 531390 I-139 9.95250E-03 1.01390E-02 531390 + 642 531400 I-140 2.86910E-03 2.91030E-03 531400 + 643 531410 I-141 6.66760E-04 6.68680E-04 531410 + 644 531420 I-142 9.37360E-05 9.37410E-05 531420 + 645 531430 I-143 1.06550E-05 1.06550E-05 531430 + 646 531440 I-144 8.97560E-07 8.97560E-07 531440 + 647 541310 Xe-131 4.41340E-10 3.10630E-02 54131.82c + 648 541311 Xe-131m 1.06550E-09 3.37400E-04 541311 + 649 541320 Xe-132 4.86750E-07 4.62080E-02 54132.82c + 650 541321 Xe-132m 5.51750E-07 5.51750E-07 541321 + 651 541330 Xe-133 5.61230E-06 6.95350E-02 54133.82c + 652 541331 Xe-133m 1.35490E-05 1.99220E-03 541331 + 653 541340 Xe-134 8.32130E-05 8.19530E-02 54134.82c + 654 541341 Xe-134m 1.94910E-04 2.73340E-04 541341 + 655 541350 Xe-135 5.47780E-04 6.74200E-02 54135.82c + 656 541351 Xe-135m 1.32240E-03 1.21560E-02 541351 + 657 541360 Xe-136 1.51630E-02 7.59950E-02 54136.82c + 658 541370 Xe-137 2.54750E-02 6.31430E-02 541370 + 659 541380 Xe-138 4.24560E-02 5.83460E-02 541380 + 660 541390 Xe-139 3.36440E-02 4.30610E-02 541390 + 661 541400 Xe-140 3.68750E-02 3.96550E-02 541400 + 662 541410 Xe-141 1.54800E-02 1.60320E-02 541410 + 663 541420 Xe-142 6.62090E-03 6.69550E-03 541420 + 664 541430 Xe-143 1.62630E-03 1.63310E-03 541430 + 665 541440 Xe-144 2.99850E-04 3.00390E-04 541440 + 666 541450 Xe-145 4.87240E-05 4.87240E-05 541450 + 667 541460 Xe-146 6.64020E-06 6.64020E-06 541460 + 668 541470 Xe-147 2.24740E-09 2.24740E-09 541470 + 669 551340 Cs-134 1.16030E-08 2.01550E-08 55134.82c + 670 551341 Cs-134m 8.55180E-09 8.55180E-09 551341 + 671 551350 Cs-135 4.01540E-06 6.75000E-02 55135.82c + 672 551351 Cs-135m 2.45370E-06 2.45370E-06 551351 + 673 551360 Cs-136 3.69600E-05 4.77900E-05 55136.82c + 674 551361 Cs-136m 2.16600E-05 2.16600E-05 551361 + 675 551370 Cs-137 9.00740E-04 6.40440E-02 55137.82c + 676 551380 Cs-138 1.36520E-03 6.12800E-02 551380 + 677 551381 Cs-138m 1.93710E-03 1.93710E-03 551381 + 678 551390 Cs-139 9.79560E-03 5.28560E-02 551390 + 679 551400 Cs-140 1.47800E-02 5.44420E-02 551400 + 680 551410 Cs-141 2.53040E-02 4.13530E-02 551410 + 681 551420 Cs-142 2.06880E-02 2.73760E-02 551420 + 682 551430 Cs-143 1.64490E-02 1.80750E-02 551430 + 683 551440 Cs-144 3.27380E-03 5.20390E-03 551440 + 684 551441 Cs-144m 3.27380E-03 3.27500E-03 551441 + 685 551450 Cs-145 2.39260E-03 2.43930E-03 551450 + 686 551460 Cs-146 4.74750E-04 4.80930E-04 551460 + 687 551470 Cs-147 9.01140E-05 9.01160E-05 551470 + 688 551480 Cs-148 1.13160E-05 1.13160E-05 551480 + 689 551490 Cs-149 2.89110E-06 2.89110E-06 551490 + 690 551500 Cs-150 2.44110E-10 2.44110E-10 551500 + 691 561360 Ba-136 8.57420E-10 5.86230E-05 56136.82c + 692 561361 Ba-136m 2.00830E-09 2.00830E-09 561361 + 693 561370 Ba-137 1.59140E-06 6.40490E-02 56137.82c + 694 561371 Ba-137m 3.84190E-06 6.04610E-02 561371 + 695 561380 Ba-138 1.15970E-04 6.17640E-02 56138.82c + 696 561390 Ba-139 6.06870E-04 5.34630E-02 561390 + 697 561400 Ba-140 3.21360E-03 5.76560E-02 56140.82c + 698 561410 Ba-141 5.71340E-03 4.70660E-02 561410 + 699 561420 Ba-142 1.68560E-02 4.45280E-02 561420 + 700 561430 Ba-143 2.31750E-02 4.11200E-02 561430 + 701 561440 Ba-144 2.89490E-02 3.59730E-02 561440 + 702 561450 Ba-145 1.91060E-02 2.12650E-02 561450 + 703 561460 Ba-146 1.16880E-02 1.21260E-02 561460 + 704 561470 Ba-147 4.30660E-03 4.37390E-03 561470 + 705 561480 Ba-148 1.18550E-03 1.19400E-03 561480 + 706 561490 Ba-149 2.20130E-04 2.23020E-04 561490 + 707 561500 Ba-150 2.95630E-05 2.95630E-05 561500 + 708 561510 Ba-151 3.03510E-06 3.03510E-06 561510 + 709 561520 Ba-152 1.68490E-09 1.68490E-09 561520 + 710 571390 La-139 1.52500E-08 5.34630E-02 57139.82c + 711 571400 La-140 1.08590E-05 5.76670E-02 57140.82c + 712 571410 La-141 8.74070E-05 4.71540E-02 571410 + 713 571420 La-142 2.70020E-04 4.47980E-02 571420 + 714 571430 La-143 1.62030E-03 4.27400E-02 571430 + 715 571440 La-144 3.71160E-03 3.96840E-02 571440 + 716 571450 La-145 9.40830E-03 3.06730E-02 571450 + 717 571460 La-146 3.56490E-03 1.56910E-02 571460 + 718 571461 La-146m 6.41250E-03 6.41250E-03 571461 + 719 571470 La-147 1.21160E-02 1.64950E-02 571470 + 720 571480 La-148 6.70500E-03 7.89520E-03 571480 + 721 571490 La-149 3.76070E-03 3.98280E-03 571490 + 722 571500 La-150 9.69130E-04 9.98690E-04 571500 + 723 571510 La-151 2.64260E-04 2.67300E-04 571510 + 724 571520 La-152 3.03370E-05 3.03390E-05 571520 + 725 571530 La-153 4.61420E-06 4.61420E-06 571530 + 726 571540 La-154 4.86160E-09 4.86160E-09 571540 + 727 571550 La-155 1.09530E-10 1.09530E-10 571550 + 728 581410 Ce-141 1.18370E-09 4.71540E-02 58141.82c + 729 581420 Ce-142 9.28220E-06 4.48070E-02 58142.82c + 730 581430 Ce-143 2.71180E-05 4.27670E-02 58143.82c + 731 581440 Ce-144 2.58140E-04 3.99420E-02 58144.82c + 732 581450 Ce-145 9.70670E-04 3.16440E-02 581450 + 733 581460 Ce-146 3.42840E-03 2.55320E-02 581460 + 734 581470 Ce-147 5.82150E-03 2.23160E-02 581470 + 735 581480 Ce-148 1.00250E-02 1.79760E-02 581480 + 736 581490 Ce-149 9.99090E-03 1.39450E-02 581490 + 737 581500 Ce-150 8.21480E-03 9.18650E-03 581500 + 738 581510 Ce-151 4.43970E-03 4.70880E-03 581510 + 739 581520 Ce-152 2.01890E-03 2.04740E-03 581520 + 740 581530 Ce-153 3.80580E-04 3.85190E-04 581530 + 741 581540 Ce-154 9.61350E-05 9.61400E-05 581540 + 742 581550 Ce-155 1.60700E-05 1.60700E-05 581550 + 743 581560 Ce-156 3.87360E-06 3.87360E-06 581560 + 744 581570 Ce-157 4.72990E-10 4.72990E-10 581570 + 745 591440 Pr-144 4.55650E-10 3.99420E-02 591440 + 746 591441 Pr-144m 4.04680E-09 5.51190E-04 591441 + 747 591450 Pr-145 9.55290E-07 3.16450E-02 591450 + 748 591460 Pr-146 1.70640E-05 2.55490E-02 591460 + 749 591470 Pr-147 1.45270E-04 2.24610E-02 591470 + 750 591480 Pr-148 7.96100E-05 1.80550E-02 591480 + 751 591481 Pr-148m 3.34810E-04 3.34810E-04 591481 + 752 591490 Pr-149 1.29570E-03 1.52410E-02 591490 + 753 591500 Pr-150 1.96850E-03 1.11550E-02 591500 + 754 591510 Pr-151 3.58580E-03 8.29460E-03 591510 + 755 591520 Pr-152 3.73580E-03 5.78560E-03 591520 + 756 591530 Pr-153 2.56910E-03 2.95250E-03 591530 + 757 591540 Pr-154 1.02690E-03 1.12240E-03 591540 + 758 591550 Pr-155 3.80920E-04 3.96990E-04 591550 + 759 591560 Pr-156 9.41580E-05 9.80320E-05 591560 + 760 591570 Pr-157 3.92350E-05 3.92360E-05 591570 + 761 591580 Pr-158 8.69260E-08 8.69260E-08 591580 + 762 591590 Pr-159 3.17760E-09 3.17760E-09 591590 + 763 601460 Nd-146 9.99530E-10 2.55490E-02 60146.82c + 764 601470 Nd-147 1.85410E-08 2.24610E-02 60147.82c + 765 601480 Nd-148 1.73370E-05 1.84080E-02 60148.82c + 766 601490 Nd-149 7.38200E-05 1.53140E-02 601490 + 767 601500 Nd-150 2.86050E-04 1.14410E-02 60150.82c + 768 601510 Nd-151 7.05770E-04 9.00040E-03 601510 + 769 601520 Nd-152 1.44500E-03 7.23060E-03 601520 + 770 601530 Nd-153 1.69180E-03 4.64430E-03 601530 + 771 601540 Nd-154 2.40080E-03 3.52320E-03 601540 + 772 601550 Nd-155 1.75740E-03 2.15710E-03 601550 + 773 601560 Nd-156 1.16190E-03 1.25980E-03 601560 + 774 601570 Nd-157 5.12920E-04 5.49650E-04 601570 + 775 601580 Nd-158 1.33780E-04 1.33870E-04 601580 + 776 601590 Nd-159 2.78910E-05 2.78940E-05 601590 + 777 601600 Nd-160 1.11930E-05 1.11930E-05 601600 + 778 601610 Nd-161 9.08710E-09 9.08710E-09 601610 + 779 611490 Pm-149 9.63430E-07 1.53150E-02 61149.82c + 780 611500 Pm-150 1.73710E-06 1.73710E-06 611500 + 781 611510 Pm-151 8.07720E-06 9.00850E-03 61151.82c + 782 611520 Pm-152 8.07930E-06 7.23870E-03 611520 + 783 611521 Pm-152m 1.61330E-05 1.61330E-05 611521 + 784 611522 Pm-152m 1.78450E-05 1.78450E-05 611522 + 785 611530 Pm-153 1.35830E-04 4.78010E-03 611530 + 786 611540 Pm-154 1.57350E-04 3.68060E-03 611540 + 787 611541 Pm-154m 1.57350E-04 1.57350E-04 611541 + 788 611550 Pm-155 6.57710E-04 2.81480E-03 611550 + 789 611560 Pm-156 8.88090E-04 2.14790E-03 611560 + 790 611570 Pm-157 9.21090E-04 1.47080E-03 611570 + 791 611580 Pm-158 6.62380E-04 7.96310E-04 611580 + 792 611590 Pm-159 2.83350E-04 3.11280E-04 611590 + 793 611600 Pm-160 1.40060E-04 1.51150E-04 611600 + 794 611610 Pm-161 4.51510E-05 4.51600E-05 611610 + 795 611620 Pm-162 5.64580E-07 5.64580E-07 611620 + 796 611630 Pm-163 1.88380E-08 1.88380E-08 611630 + 797 621520 Sm-152 2.41890E-06 7.27510E-03 62152.82c + 798 621530 Sm-153 1.01240E-06 4.78360E-03 62153.82c + 799 621531 Sm-153m 2.44400E-06 2.44400E-06 621531 + 800 621540 Sm-154 3.41560E-05 3.87210E-03 62154.82c + 801 621550 Sm-155 1.29540E-04 2.94430E-03 621550 + 802 621560 Sm-156 3.26920E-04 2.47480E-03 621560 + 803 621570 Sm-157 5.96420E-04 2.06720E-03 621570 + 804 621580 Sm-158 8.37020E-04 1.63340E-03 621580 + 805 621590 Sm-159 7.79750E-04 1.09140E-03 621590 + 806 621600 Sm-160 5.87800E-04 7.38540E-04 621600 + 807 621610 Sm-161 3.42090E-04 3.87250E-04 621610 + 808 621620 Sm-162 1.30500E-04 1.31070E-04 621620 + 809 621630 Sm-163 1.94840E-05 1.95030E-05 621630 + 810 621640 Sm-164 6.40960E-07 6.40960E-07 621640 + 811 621650 Sm-165 3.13840E-08 3.13840E-08 621650 + 812 631540 Eu-154 1.47550E-10 2.80470E-10 63154.82c + 813 631541 Eu-154m 1.32920E-10 1.32920E-10 631541 + 814 631550 Eu-155 1.41290E-08 2.94430E-03 63155.82c + 815 631560 Eu-156 1.93320E-06 2.47670E-03 63156.82c + 816 631570 Eu-157 1.38190E-05 2.08100E-03 63157.82c + 817 631580 Eu-158 3.60660E-05 1.66950E-03 631580 + 818 631590 Eu-159 1.31250E-04 1.22260E-03 631590 + 819 631600 Eu-160 1.89970E-04 9.28510E-04 631600 + 820 631610 Eu-161 2.70460E-04 6.57710E-04 631610 + 821 631620 Eu-162 2.22410E-04 3.53480E-04 631620 + 822 631630 Eu-163 6.49460E-05 8.44490E-05 631630 + 823 631640 Eu-164 6.76960E-06 7.41060E-06 631640 + 824 631650 Eu-165 1.50330E-05 1.50640E-05 631650 + 825 631660 Eu-166 3.79300E-07 3.79300E-07 631660 + 826 631670 Eu-167 3.99000E-08 3.99000E-08 631670 + 827 641570 Gd-157 8.40870E-10 2.08100E-03 64157.82c + 828 641580 Gd-158 4.20140E-08 1.66950E-03 64158.82c + 829 641590 Gd-159 7.96390E-06 1.23060E-03 641590 + 830 641600 Gd-160 3.91430E-05 9.67660E-04 64160.82c + 831 641610 Gd-161 4.51040E-05 7.02810E-04 641610 + 832 641620 Gd-162 1.37900E-04 4.91370E-04 641620 + 833 641630 Gd-163 8.43620E-05 1.68810E-04 641630 + 834 641640 Gd-164 6.76940E-05 7.51050E-05 641640 + 835 641650 Gd-165 3.75810E-05 5.26450E-05 641650 + 836 641660 Gd-166 7.27830E-06 7.65760E-06 641660 + 837 641670 Gd-167 2.67610E-06 2.71600E-06 641670 + 838 641680 Gd-168 6.25090E-07 6.25090E-07 641680 + 839 641690 Gd-169 3.28490E-08 3.28490E-08 641690 + 840 651590 Tb-159 8.70580E-11 1.23060E-03 65159.82c + 841 651600 Tb-160 2.03810E-09 2.03810E-09 65160.82c + 842 651610 Tb-161 6.99450E-08 7.02880E-04 651610 + 843 651620 Tb-162 5.30330E-07 4.91900E-04 651620 + 844 651630 Tb-163 6.49200E-06 1.75300E-04 651630 + 845 651640 Tb-164 1.35370E-05 8.86420E-05 651640 + 846 651650 Tb-165 7.51510E-06 6.01610E-05 651650 + 847 651660 Tb-166 2.18340E-05 2.94920E-05 651660 + 848 651670 Tb-167 1.42670E-05 1.69830E-05 651670 + 849 651680 Tb-168 4.53930E-06 5.16440E-06 651680 + 850 651690 Tb-169 2.10300E-06 2.13590E-06 651690 + 851 651700 Tb-170 2.06710E-07 2.06710E-07 651700 + 852 651710 Tb-171 3.80710E-08 3.80710E-08 651710 + 853 661620 Dy-162 2.11810E-10 4.91900E-04 66162.82c + 854 661630 Dy-163 2.08210E-09 1.75310E-04 66163.82c + 855 661640 Dy-164 3.78540E-08 8.86790E-05 66164.82c + 856 661650 Dy-165 1.95510E-05 8.26340E-05 661650 + 857 661651 Dy-165m 2.98880E-06 2.98880E-06 661651 + 858 661660 Dy-166 1.23050E-06 3.07220E-05 661660 + 859 661670 Dy-167 2.11010E-06 1.90930E-05 661670 + 860 661680 Dy-168 5.16730E-06 1.03320E-05 661680 + 861 661690 Dy-169 3.02320E-06 5.15910E-06 661690 + 862 661700 Dy-170 2.32010E-06 2.52680E-06 661700 + 863 661710 Dy-171 6.04110E-07 6.42180E-07 661710 + 864 661720 Dy-172 2.37670E-07 2.37670E-07 661720 + 865 661730 Dy-173 1.92470E-08 1.92470E-08 661730 + 866 671640 Ho-164 5.96100E-13 1.99230E-12 671640 + 867 671641 Ho-164m 1.39620E-12 1.39620E-12 671641 + 868 671650 Ho-165 1.95920E-10 8.27010E-05 67165.82c + 869 671660 Ho-166 4.19270E-10 3.07230E-05 671660 + 870 671661 Ho-166m 9.82030E-10 9.82030E-10 671661 + 871 671670 Ho-167 2.38330E-08 1.91170E-05 671670 + 872 671680 Ho-168 3.78050E-08 1.04230E-05 671680 + 873 671681 Ho-168m 5.36430E-08 5.36430E-08 671681 + 874 671690 Ho-169 4.61900E-07 5.62090E-06 671690 + 875 671700 Ho-170 3.31950E-07 3.31950E-07 671700 + 876 671701 Ho-170m 1.41720E-07 2.66850E-06 671701 + 877 671710 Ho-171 9.32690E-07 1.57490E-06 671710 + 878 671720 Ho-172 4.68060E-07 7.05730E-07 671720 + 879 671730 Ho-173 3.05510E-07 3.24760E-07 671730 + 880 671740 Ho-174 5.56340E-08 5.56340E-08 671740 + 881 671750 Ho-175 1.85680E-08 1.85680E-08 671750 + 882 681670 Er-167 3.09380E-12 1.91170E-05 68167.82c + 883 681671 Er-167m 4.72940E-13 2.28430E-06 681671 + 884 681680 Er-168 1.42900E-10 1.04230E-05 68168.82c + 885 681690 Er-169 1.23280E-09 5.62220E-06 681690 + 886 681700 Er-170 1.22290E-08 3.01270E-06 68170.82c + 887 681710 Er-171 3.64720E-08 1.61130E-06 681710 + 888 681720 Er-172 1.52100E-07 8.57830E-07 681720 + 889 681730 Er-173 1.28840E-07 4.53600E-07 681730 + 890 681740 Er-174 1.76470E-07 2.32100E-07 681740 + 891 681750 Er-175 7.67570E-08 9.53250E-08 681750 + 892 681760 Er-176 4.20580E-08 4.20580E-08 681760 + 893 681770 Er-177 6.28850E-09 6.28850E-09 681770 + 894 691700 Tm-170 2.90040E-12 2.90040E-12 691700 + 895 691710 Tm-171 8.92680E-11 1.61140E-06 691710 + 896 691720 Tm-172 6.22390E-10 8.58450E-07 691720 + 897 691730 Tm-173 4.95330E-09 4.58550E-07 691730 + 898 691740 Tm-174 9.90290E-09 2.42010E-07 691740 + 899 691750 Tm-175 3.45230E-08 1.29850E-07 691750 + 900 691760 Tm-176 2.40680E-08 6.61260E-08 691760 + 901 691770 Tm-177 2.72690E-08 3.35580E-08 691770 + 902 691780 Tm-178 9.30930E-09 9.30930E-09 691780 + 903 691790 Tm-179 4.48560E-09 4.48560E-09 691790 + 904 701730 Yb-173 2.78980E-12 4.58550E-07 701730 + 905 701740 Yb-174 5.69100E-11 2.42060E-07 701740 + 906 701750 Yb-175 2.80840E-10 1.30170E-07 701750 + 907 701751 Yb-175m 4.29320E-11 1.00030E-07 701751 + 908 701760 Yb-176 7.32890E-10 6.47390E-08 701760 + 909 701761 Yb-176m 1.31830E-09 3.43810E-08 701761 + 910 701770 Yb-177 2.65220E-09 3.68230E-08 701770 + 911 701771 Yb-177m 6.13240E-10 3.41710E-08 701771 + 912 701780 Yb-178 8.66450E-09 1.79740E-08 701780 + 913 701790 Yb-179 5.27020E-09 9.75580E-09 701790 + 914 701800 Yb-180 4.36290E-09 4.36290E-09 701800 + 915 701810 Yb-181 1.24970E-09 1.24970E-09 701810 + 916 711760 Lu-176 1.16340E-12 3.43930E-09 71176.82c + 917 711770 Lu-177 2.05400E-11 3.68450E-08 711770 + 918 711771 Lu-177m 8.02970E-12 8.15950E-12 711771 + 919 711780 Lu-178 5.68810E-11 1.80310E-08 711780 + 920 711781 Lu-178m 6.44790E-11 6.44790E-11 711781 + 921 711790 Lu-179 5.61040E-10 1.04030E-08 711790 + 922 711791 Lu-179m 8.57670E-11 9.84160E-09 711791 + 923 711800 Lu-180 2.08780E-10 2.64850E-09 711800 + 924 711801 Lu-180m 2.08780E-10 4.57170E-09 711801 + 925 711802 Lu-180m 3.07690E-10 3.07690E-10 711802 + 926 711810 Lu-181 1.57950E-09 2.82920E-09 711810 + 927 711820 Lu-182 8.37980E-10 8.37980E-10 711820 + 928 711830 Lu-183 5.89280E-10 5.89280E-10 711830 + 929 711840 Lu-184 1.19550E-10 1.19550E-10 711840 + 930 721790 Hf-179 8.07950E-13 1.04040E-08 72179.82c + 931 721800 Hf-180 5.25660E-12 5.10230E-09 72180.82c + 932 721801 Hf-180m 9.45540E-12 1.63300E-10 721801 + 933 721810 Hf-181 4.92090E-11 2.87840E-09 721810 + 934 721820 Hf-182 7.86770E-11 9.76100E-10 721820 + 935 721821 Hf-182m 1.41520E-10 1.41520E-10 721821 + 936 721830 Hf-183 2.03080E-10 7.92360E-10 721830 + 937 721840 Hf-184 1.10780E-10 1.70560E-10 721840 + 938 721841 Hf-184m 1.99280E-10 2.59050E-10 721841 + 939 721850 Hf-185 1.43670E-10 1.43670E-10 721850 + 940 721860 Hf-186 8.31250E-11 8.31250E-11 721860 + 941 721870 Hf-187 1.38800E-11 1.38800E-11 721870 + 942 721880 Hf-188 3.90050E-12 3.90050E-12 721880 + 943 731830 Ta-183 6.17100E-12 7.98530E-10 731830 + 944 731840 Ta-184 1.39580E-11 4.43570E-10 731840 + 945 731850 Ta-185 3.54050E-11 1.96220E-10 731850 + 946 731851 Ta-185m 1.71480E-11 1.71480E-11 731851 + 947 731860 Ta-186 3.89380E-11 1.22060E-10 731860 + 948 731870 Ta-187 4.90520E-11 6.29320E-11 731870 + 949 731880 Ta-188 1.82850E-11 2.21850E-11 731880 + 950 731890 Ta-189 9.28000E-12 9.28000E-12 731890 + 951 731900 Ta-190 1.09600E-12 1.09600E-12 731900 + 952 741860 W-186 1.99640E-12 1.24700E-10 74186.82c + 953 741870 W-187 4.74370E-12 6.76760E-11 741870 + 954 741880 W-188 1.38980E-11 3.60830E-11 741880 + 955 741890 W-189 8.91820E-12 1.81980E-11 741890 + 956 741900 W-190 3.78050E-12 9.16200E-12 741900 + 957 741901 W-190m 4.28550E-12 4.28550E-12 741901 + 958 751900 Re-190 3.89170E-13 9.87040E-12 751900 + + Neutron-induced fission: + + Interpolation region : 2 / 2 + Interpolation energy : 4.00000E-01 MeV + Number of products : 927 / 1035 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 2.94220E-05 2.94220E-05 1001.82c + 2 10020 H-2 8.99170E-06 8.99170E-06 1002.82c + 3 10030 H-3 1.41000E-04 1.41000E-04 1003.82c + 4 20040 He-4 1.86000E-03 1.86000E-03 2004.82c + 5 220550 Ti-55 1.24200E-12 1.24200E-12 220550 + 6 220560 Ti-56 2.92520E-12 2.92520E-12 220560 + 7 220570 Ti-57 1.90080E-12 1.90080E-12 220570 + 8 220580 Ti-58 2.05100E-12 2.05100E-12 220580 + 9 230560 V-56 1.61160E-12 4.54250E-12 230560 + 10 230570 V-57 7.91890E-12 9.81400E-12 230570 + 11 230580 V-58 1.16430E-11 1.36940E-11 230580 + 12 230590 V-59 2.37440E-11 2.37440E-11 230590 + 13 230600 V-60 1.08190E-11 1.08190E-11 230600 + 14 230610 V-61 9.21840E-12 9.21840E-12 230610 + 15 230620 V-62 1.78310E-12 1.78310E-12 230620 + 16 240580 Cr-58 1.06420E-11 1.33810E-11 240580 + 17 240590 Cr-59 2.78470E-11 5.15910E-11 240590 + 18 240600 Cr-60 9.79280E-11 1.09300E-10 240600 + 19 240610 Cr-61 1.18170E-10 1.26840E-10 240610 + 20 240620 Cr-62 2.05930E-10 2.07710E-10 240620 + 21 240630 Cr-63 7.57720E-11 7.57720E-11 240630 + 22 240640 Cr-64 4.29090E-11 4.29090E-11 240640 + 23 240650 Cr-65 6.73170E-12 6.73170E-12 240650 + 24 240660 Cr-66 1.14860E-12 1.14860E-12 240660 + 25 250590 Mn-59 3.46120E-12 5.50520E-11 250590 + 26 250600 Mn-60 1.49740E-12 1.12550E-10 250600 + 27 250601 Mn-60m 1.52340E-11 1.52340E-11 250601 + 28 250610 Mn-61 1.53250E-10 2.80090E-10 250610 + 29 250620 Mn-62 2.97970E-10 4.01820E-10 250620 + 30 250621 Mn-62m 4.66630E-11 1.50520E-10 250621 + 31 250630 Mn-63 1.01000E-09 1.08580E-09 250630 + 32 250640 Mn-64 8.43860E-10 8.86770E-10 250640 + 33 250650 Mn-65 1.23690E-09 1.24360E-09 250650 + 34 250660 Mn-66 3.57450E-10 3.58600E-10 250660 + 35 250670 Mn-67 1.55950E-10 1.55950E-10 250670 + 36 250680 Mn-68 1.79520E-11 1.79520E-11 250680 + 37 250690 Mn-69 2.48620E-12 2.48620E-12 250690 + 38 260610 Fe-61 5.04800E-12 2.85130E-10 260610 + 39 260620 Fe-62 9.52680E-11 6.47610E-10 260620 + 40 260630 Fe-63 3.70990E-10 1.45680E-09 260630 + 41 260640 Fe-64 2.32930E-09 3.21610E-09 260640 + 42 260650 Fe-65 4.49390E-09 5.73750E-09 260650 + 43 260660 Fe-66 1.07480E-08 1.11070E-08 260660 + 44 260670 Fe-67 7.20070E-09 7.35670E-09 260670 + 45 260680 Fe-68 7.99330E-09 8.01180E-09 260680 + 46 260690 Fe-69 1.91810E-09 1.92000E-09 260690 + 47 260700 Fe-70 5.63160E-10 5.63160E-10 260700 + 48 260710 Fe-71 5.09360E-11 5.09360E-11 260710 + 49 260720 Fe-72 2.41370E-12 2.41370E-12 260720 + 50 270630 Co-63 1.23560E-11 1.46910E-09 270630 + 51 270640 Co-64 1.16060E-10 3.33210E-09 270640 + 52 270650 Co-65 1.80580E-09 7.54330E-09 270650 + 53 270660 Co-66 5.60330E-09 1.67100E-08 270660 + 54 270670 Co-67 2.83490E-08 3.57060E-08 270670 + 55 270680 Co-68 2.44640E-08 3.76680E-08 270680 + 56 270681 Co-68m 1.82610E-08 2.64070E-08 270681 + 57 270690 Co-69 8.84000E-08 9.01860E-08 270690 + 58 270700 Co-70 2.06690E-08 2.06690E-08 270700 + 59 270701 Co-70m 2.06690E-08 2.12320E-08 270701 + 60 270710 Co-71 3.70400E-08 3.70910E-08 270710 + 61 270720 Co-72 3.10930E-09 3.11170E-09 270720 + 62 270730 Co-73 1.42610E-09 1.42610E-09 270730 + 63 270740 Co-74 9.95170E-11 9.95170E-11 270740 + 64 270750 Co-75 9.24940E-12 9.24940E-12 270750 + 65 280650 Ni-65 1.52850E-11 7.55860E-09 280650 + 66 280660 Ni-66 4.32820E-10 1.71430E-08 280660 + 67 280670 Ni-67 3.14450E-09 3.88500E-08 280670 + 68 280680 Ni-68 3.69330E-08 8.87060E-08 280680 + 69 280690 Ni-69 4.90380E-08 1.38320E-07 280690 + 70 280691 Ni-69m 4.90380E-08 4.90380E-08 280691 + 71 280700 Ni-70 3.53060E-07 3.94960E-07 280700 + 72 280710 Ni-71 4.46180E-07 4.83270E-07 280710 + 73 280720 Ni-72 3.36140E-07 3.39250E-07 280720 + 74 280730 Ni-73 2.53500E-07 2.54930E-07 280730 + 75 280740 Ni-74 1.79340E-07 1.79440E-07 280740 + 76 280750 Ni-75 2.81170E-08 2.81260E-08 280750 + 77 280760 Ni-76 4.11320E-09 4.11320E-09 280760 + 78 280770 Ni-77 1.01170E-10 1.01170E-10 280770 + 79 280780 Ni-78 4.38140E-12 4.38140E-12 280780 + 80 290670 Cu-67 2.59210E-11 3.88760E-08 290670 + 81 290680 Cu-68 1.32070E-10 8.91410E-08 290680 + 82 290681 Cu-68m 3.59990E-10 3.59990E-10 290681 + 83 290690 Cu-69 1.14710E-08 1.98830E-07 290690 + 84 290700 Cu-70 3.85740E-09 3.84600E-08 290700 + 85 290701 Cu-70m 4.92630E-08 6.92040E-08 290701 + 86 290702 Cu-70m 3.85740E-09 3.98820E-07 290702 + 87 290710 Cu-71 1.04220E-06 1.52550E-06 290710 + 88 290720 Cu-72 1.06410E-06 1.40340E-06 290720 + 89 290730 Cu-73 2.88380E-06 3.13870E-06 290730 + 90 290740 Cu-74 7.24530E-06 7.42520E-06 290740 + 91 290750 Cu-75 2.90890E-06 2.93660E-06 290750 + 92 290760 Cu-76 1.38920E-06 1.39120E-06 290760 + 93 290761 Cu-76m 1.38920E-06 1.39120E-06 290761 + 94 290770 Cu-77 1.46230E-06 1.46240E-06 290770 + 95 290780 Cu-78 2.54890E-08 2.54930E-08 290780 + 96 290790 Cu-79 3.34580E-09 3.34580E-09 290790 + 97 290800 Cu-80 8.51940E-11 8.51940E-11 290800 + 98 300690 Zn-69 3.90120E-12 1.98850E-07 300690 + 99 300691 Zn-69m 1.93760E-11 1.93760E-11 300691 + 100 300700 Zn-70 1.12880E-09 4.53070E-07 300700 + 101 300710 Zn-71 2.83850E-09 1.52830E-06 300710 + 102 300711 Zn-71m 1.40970E-08 1.40970E-08 300711 + 103 300720 Zn-72 1.38570E-07 1.54190E-06 300720 + 104 300730 Zn-73 1.26460E-07 4.01040E-06 300730 + 105 300731 Zn-73m 1.74900E-07 7.45250E-07 300731 + 106 300732 Zn-73m 1.14070E-06 1.14070E-06 300732 + 107 300740 Zn-74 4.34740E-06 1.18750E-05 300740 + 108 300750 Zn-75 2.47270E-05 2.76020E-05 300750 + 109 300760 Zn-76 3.61170E-05 3.88580E-05 300760 + 110 300770 Zn-77 1.67750E-05 1.93550E-05 300770 + 111 300771 Zn-77m 2.23360E-06 2.23360E-06 300771 + 112 300780 Zn-78 1.93600E-05 1.93870E-05 300780 + 113 300790 Zn-79 6.45640E-06 6.45790E-06 300790 + 114 300800 Zn-80 7.08370E-06 7.08380E-06 300800 + 115 300810 Zn-81 1.26900E-06 1.26900E-06 300810 + 116 300820 Zn-82 2.62490E-09 2.62490E-09 300820 + 117 300830 Zn-83 4.91920E-11 4.91920E-11 300830 + 118 310710 Ga-71 3.25850E-11 1.54240E-06 310710 + 119 310720 Ga-72 4.15330E-10 1.54240E-06 310720 + 120 310721 Ga-72m 4.08260E-11 5.14180E-08 310721 + 121 310730 Ga-73 3.44990E-08 4.61530E-06 310730 + 122 310740 Ga-74 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320771 Ge-77m 1.54650E-06 5.12660E-05 320771 + 143 320780 Ge-78 5.25700E-05 1.08070E-04 320780 + 144 320790 Ge-79 1.74560E-05 9.73180E-05 320790 + 145 320791 Ge-79m 1.31100E-04 1.31220E-04 320791 + 146 320800 Ge-80 3.47080E-04 3.89470E-04 320800 + 147 320810 Ge-81 3.50410E-04 3.69580E-04 320810 + 148 320811 Ge-81m 7.05530E-05 8.69730E-05 320811 + 149 320820 Ge-82 4.30380E-04 4.36260E-04 320820 + 150 320830 Ge-83 2.77160E-04 2.79130E-04 320830 + 151 320840 Ge-84 7.39830E-05 7.39930E-05 320840 + 152 320850 Ge-85 1.70850E-05 1.70860E-05 320850 + 153 320860 Ge-86 9.96060E-06 9.96060E-06 320860 + 154 320870 Ge-87 1.45070E-08 1.45070E-08 320870 + 155 320880 Ge-88 3.51470E-10 3.51470E-10 320880 + 156 330750 As-75 4.50850E-12 2.91070E-05 33075.82c + 157 330751 As-75m 1.70730E-11 3.78930E-10 330751 + 158 330760 As-76 9.25640E-10 9.25640E-10 330760 + 159 330770 As-77 3.91830E-08 6.29210E-05 330770 + 160 330780 As-78 4.14950E-06 1.12210E-04 330780 + 161 330790 As-79 6.45740E-06 2.29740E-04 330790 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390950 Y-95 6.34850E-03 3.76890E-02 390950 + 281 390960 Y-96 4.06790E-03 3.20140E-02 390960 + 282 390961 Y-96m 8.53410E-03 8.53770E-03 390961 + 283 390970 Y-97 3.92620E-03 1.65510E-02 390970 + 284 390971 Y-97m 1.45120E-02 2.06840E-02 390971 + 285 390972 Y-97m 4.98740E-03 4.98740E-03 390972 + 286 390980 Y-98 3.58250E-03 1.06090E-02 390980 + 287 390981 Y-98m 1.73680E-02 1.73680E-02 390981 + 288 390990 Y-99 2.01180E-02 2.20900E-02 390990 + 289 391000 Y-100 4.75680E-03 5.24140E-03 391000 + 290 391001 Y-100m 4.75680E-03 4.75770E-03 391001 + 291 391010 Y-101 4.49520E-03 4.56670E-03 391010 + 292 391020 Y-102 5.17900E-04 5.22750E-04 391020 + 293 391021 Y-102m 5.17900E-04 5.22750E-04 391021 + 294 391030 Y-103 2.84110E-04 2.84110E-04 391030 + 295 391040 Y-104 2.52390E-05 2.52390E-05 391040 + 296 391050 Y-105 4.00380E-06 4.00380E-06 391050 + 297 400920 Zr-92 1.82830E-09 2.34660E-02 40092.82c + 298 400930 Zr-93 2.01740E-06 3.00920E-02 40093.82c + 299 400940 Zr-94 6.64010E-05 3.30750E-02 40094.82c + 300 400950 Zr-95 4.68760E-04 3.81580E-02 40095.82c + 301 400960 Zr-96 2.65480E-03 4.32230E-02 40096.82c + 302 400970 Zr-97 7.26580E-03 4.59630E-02 400970 + 303 400980 Zr-98 2.01940E-02 4.79200E-02 400980 + 304 400990 Zr-99 2.99250E-02 5.16880E-02 400990 + 305 401000 Zr-100 4.24750E-02 5.24260E-02 401000 + 306 401010 Zr-101 3.33280E-02 3.79460E-02 401010 + 307 401020 Zr-102 2.57600E-02 2.67770E-02 401020 + 308 401030 Zr-103 9.77590E-03 1.00390E-02 401030 + 309 401040 Zr-104 3.71820E-03 3.74200E-03 401040 + 310 401050 Zr-105 6.52050E-04 6.55260E-04 401050 + 311 401060 Zr-106 1.52430E-04 1.52430E-04 401060 + 312 401070 Zr-107 7.06940E-06 7.06940E-06 401070 + 313 401080 Zr-108 3.02690E-09 3.02690E-09 401080 + 314 410950 Nb-95 1.54490E-08 3.81350E-02 41095.82c + 315 410951 Nb-95m 3.11070E-09 4.12240E-04 410951 + 316 410960 Nb-96 9.56910E-06 9.56910E-06 410960 + 317 410970 Nb-97 9.00570E-05 4.60710E-02 410970 + 318 410971 Nb-97m 1.81330E-05 4.37050E-02 410971 + 319 410980 Nb-98 1.25470E-04 4.80450E-02 410980 + 320 410981 Nb-98m 4.37170E-04 4.37170E-04 410981 + 321 410990 Nb-99 2.72140E-03 3.57790E-02 410990 + 322 410991 Nb-99m 5.47940E-04 1.95690E-02 410991 + 323 411000 Nb-100 1.34990E-03 5.37760E-02 411000 + 324 411001 Nb-100m 6.54450E-03 6.54450E-03 411001 + 325 411010 Nb-101 2.14200E-02 5.93660E-02 411010 + 326 411020 Nb-102 1.36890E-02 4.04660E-02 411020 + 327 411021 Nb-102m 1.36890E-02 1.36890E-02 411021 + 328 411030 Nb-103 3.52130E-02 4.52530E-02 411030 + 329 411040 Nb-104 1.17590E-02 1.55100E-02 411040 + 330 411041 Nb-104m 1.17590E-02 1.17590E-02 411041 + 331 411050 Nb-105 1.53850E-02 1.60330E-02 411050 + 332 411060 Nb-106 5.61220E-03 5.76260E-03 411060 + 333 411070 Nb-107 1.91440E-03 1.92120E-03 411070 + 334 411080 Nb-108 3.24090E-04 3.24090E-04 411080 + 335 411090 Nb-109 4.41780E-05 4.41780E-05 411090 + 336 411100 Nb-110 3.21150E-06 3.21150E-06 411100 + 337 420970 Mo-97 2.27290E-09 4.60710E-02 42097.82c + 338 420980 Mo-98 1.55130E-05 4.84980E-02 42098.82c + 339 420990 Mo-99 1.11150E-04 5.50680E-02 42099.82c + 340 421000 Mo-100 7.98590E-04 6.11190E-02 42100.82c + 341 421010 Mo-101 3.19320E-03 6.25590E-02 421010 + 342 421020 Mo-102 1.16960E-02 6.58510E-02 421020 + 343 421030 Mo-103 2.11110E-02 6.63790E-02 421030 + 344 421040 Mo-104 3.96390E-02 6.71660E-02 421040 + 345 421050 Mo-105 3.63460E-02 5.23660E-02 421050 + 346 421060 Mo-106 3.57020E-02 4.13210E-02 421060 + 347 421070 Mo-107 1.67190E-02 1.85450E-02 421070 + 348 421080 Mo-108 8.61670E-03 8.92630E-03 421080 + 349 421090 Mo-109 2.21220E-03 2.25210E-03 421090 + 350 421100 Mo-110 5.30250E-04 5.32180E-04 421100 + 351 421110 Mo-111 4.60500E-05 4.60500E-05 421110 + 352 421120 Mo-112 1.71370E-05 1.71370E-05 421120 + 353 421130 Mo-113 2.31900E-06 2.31900E-06 421130 + 354 431000 Tc-100 2.91210E-06 2.91210E-06 431000 + 355 431010 Tc-101 2.92580E-05 6.25880E-02 431010 + 356 431020 Tc-102 7.85850E-05 6.59300E-02 431020 + 357 431021 Tc-102m 7.85850E-05 7.85850E-05 431021 + 358 431030 Tc-103 9.59820E-04 6.73380E-02 431030 + 359 431040 Tc-104 3.03860E-03 7.02040E-02 431040 + 360 431050 Tc-105 9.66510E-03 6.20310E-02 431050 + 361 431060 Tc-106 1.58600E-02 5.71810E-02 431060 + 362 431070 Tc-107 2.33700E-02 4.19150E-02 431070 + 363 431080 Tc-108 1.82870E-02 2.72250E-02 431080 + 364 431090 Tc-109 1.33970E-02 1.56370E-02 431090 + 365 431100 Tc-110 5.83310E-03 6.36570E-03 431100 + 366 431110 Tc-111 2.19030E-03 2.23620E-03 431110 + 367 431120 Tc-112 5.20840E-04 5.37620E-04 431120 + 368 431130 Tc-113 1.54390E-04 1.56710E-04 431130 + 369 431140 Tc-114 4.83070E-05 4.83070E-05 431140 + 370 431150 Tc-115 2.58090E-05 2.58090E-05 431150 + 371 431160 Tc-116 5.15340E-06 5.15340E-06 431160 + 372 441020 Ru-102 1.02630E-06 6.60090E-02 44102.82c + 373 441030 Ru-103 3.46030E-06 6.73520E-02 44103.82c + 374 441031 Ru-103m 9.68170E-06 9.68170E-06 441031 + 375 441040 Ru-104 1.16300E-04 7.03200E-02 44104.82c + 376 441050 Ru-105 5.65320E-04 6.25970E-02 44105.82c + 377 441060 Ru-106 2.41740E-03 5.95980E-02 44106.82c + 378 441070 Ru-107 4.84720E-03 4.67620E-02 441070 + 379 441080 Ru-108 1.08010E-02 3.80390E-02 441080 + 380 441090 Ru-109 1.13360E-02 2.69630E-02 441090 + 381 441100 Ru-110 1.11590E-02 1.75220E-02 441100 + 382 441110 Ru-111 5.88650E-03 8.13080E-03 441110 + 383 441120 Ru-112 2.83140E-03 3.37220E-03 441120 + 384 441130 Ru-113 4.71430E-04 8.55760E-04 441130 + 385 441131 Ru-113m 4.71430E-04 4.71430E-04 441131 + 386 441140 Ru-114 3.17150E-04 3.66000E-04 441140 + 387 441150 Ru-115 9.40950E-05 1.16830E-04 441150 + 388 441160 Ru-116 3.10640E-05 3.55870E-05 441160 + 389 441170 Ru-117 6.78970E-06 6.78970E-06 441170 + 390 441180 Ru-118 2.67870E-06 2.67870E-06 441180 + 391 451050 Rh-105 8.83380E-07 6.25980E-02 45105.82c + 392 451051 Rh-105m 1.17620E-07 1.77700E-02 451051 + 393 451060 Rh-106 3.43610E-06 5.96010E-02 451060 + 394 451061 Rh-106m 9.36590E-06 9.36590E-06 451061 + 395 451070 Rh-107 9.62930E-05 4.68580E-02 451070 + 396 451080 Rh-108 7.80570E-05 3.81170E-02 451080 + 397 451081 Rh-108m 2.71970E-04 2.71970E-04 451081 + 398 451090 Rh-109 1.07260E-03 2.80360E-02 451090 + 399 451100 Rh-110 1.65500E-03 1.91770E-02 451100 + 400 451101 Rh-110m 3.89620E-05 3.89620E-05 451101 + 401 451110 Rh-111 2.34950E-03 1.04800E-02 451110 + 402 451120 Rh-112 8.02550E-04 4.17480E-03 451120 + 403 451121 Rh-112m 8.02550E-04 8.02550E-04 451121 + 404 451130 Rh-113 1.10720E-03 2.19870E-03 451130 + 405 451140 Rh-114 2.06010E-04 5.72280E-04 451140 + 406 451141 Rh-114m 2.06010E-04 2.06010E-04 451141 + 407 451150 Rh-115 1.22050E-04 2.39000E-04 451150 + 408 451160 Rh-116 9.74510E-06 4.50870E-05 451160 + 409 451161 Rh-116m 2.65630E-05 2.65630E-05 451161 + 410 451170 Rh-117 1.36040E-05 2.03650E-05 451170 + 411 451180 Rh-118 4.01990E-06 6.58850E-06 451180 + 412 451190 Rh-119 2.87000E-09 2.87000E-09 451190 + 413 451200 Rh-120 6.04500E-11 6.04500E-11 451200 + 414 451220 Rh-122 1.86800E-08 1.86800E-08 451220 + 415 461070 Pd-107 3.15730E-07 4.68590E-02 46107.82c + 416 461071 Pd-107m 6.93970E-07 6.93970E-07 461071 + 417 461080 Pd-108 7.25660E-06 3.83960E-02 46108.82c + 418 461090 Pd-109 7.19080E-06 2.80590E-02 461090 + 419 461091 Pd-109m 1.58050E-05 1.40340E-02 461091 + 420 461100 Pd-110 1.00540E-04 1.93170E-02 46110.82c + 421 461110 Pd-111 4.54350E-05 1.05870E-02 461110 + 422 461111 Pd-111m 9.98650E-05 1.41790E-04 461111 + 423 461120 Pd-112 2.28700E-04 5.20600E-03 461120 + 424 461130 Pd-113 5.42740E-05 2.40480E-03 461130 + 425 461131 Pd-113m 1.51860E-04 1.51860E-04 461131 + 426 461140 Pd-114 1.83090E-04 9.61380E-04 461140 + 427 461150 Pd-115 3.77460E-05 2.51460E-04 461150 + 428 461151 Pd-115m 8.29640E-05 1.17670E-04 461151 + 429 461160 Pd-116 1.10650E-04 1.82300E-04 461160 + 430 461170 Pd-117 1.47970E-05 6.78760E-05 461170 + 431 461171 Pd-117m 3.25220E-05 3.25220E-05 461171 + 432 461180 Pd-118 4.54620E-05 5.18580E-05 461180 + 433 461190 Pd-119 1.52060E-05 1.52090E-05 461190 + 434 461200 Pd-120 5.00340E-06 5.00350E-06 461200 + 435 461210 Pd-121 3.42820E-06 3.42820E-06 461210 + 436 461220 Pd-122 8.72980E-06 8.74850E-06 461220 + 437 461230 Pd-123 1.54980E-06 1.54980E-06 461230 + 438 461240 Pd-124 5.59290E-07 5.59290E-07 461240 + 439 471100 Ag-110 1.28220E-09 1.32970E-09 471100 + 440 471101 Ag-110m 3.49490E-09 3.49490E-09 47510.82c + 441 471110 Ag-111 1.28890E-07 1.05740E-02 47111.82c + 442 471111 Ag-111m 9.68010E-07 1.05410E-02 471111 + 443 471120 Ag-112 5.34660E-06 5.21140E-03 471120 + 444 471130 Ag-113 1.08710E-06 1.58210E-03 471130 + 445 471131 Ag-113m 8.16440E-06 2.31090E-03 471131 + 446 471140 Ag-114 2.40380E-06 9.75430E-04 471140 + 447 471141 Ag-114m 1.16530E-05 1.16530E-05 471141 + 448 471150 Ag-115 1.72370E-06 2.25000E-04 471150 + 449 471151 Ag-115m 1.29460E-05 1.89090E-04 471151 + 450 471160 Ag-116 3.79490E-06 1.86720E-04 471160 + 451 471161 Ag-116m 1.03440E-05 1.03440E-05 471161 + 452 471170 Ag-117 3.65810E-06 4.12810E-05 471170 + 453 471171 Ag-117m 2.74750E-05 6.14130E-05 471171 + 454 471180 Ag-118 1.09760E-05 8.02760E-05 471180 + 455 471181 Ag-118m 5.32090E-05 6.06230E-05 471181 + 456 471190 Ag-119 7.96160E-06 1.55660E-05 471190 + 457 471191 Ag-119m 5.97960E-05 6.74010E-05 471191 + 458 471200 Ag-120 1.81020E-05 3.27400E-05 471200 + 459 471201 Ag-120m 3.02730E-05 3.27750E-05 471201 + 460 471210 Ag-121 3.60180E-05 3.94370E-05 471210 + 461 471220 Ag-122 7.31130E-06 1.60600E-05 471220 + 462 471221 Ag-122m 7.88260E-06 7.88260E-06 471221 + 463 471230 Ag-123 2.42120E-05 2.57620E-05 471230 + 464 471240 Ag-124 1.07590E-05 1.71180E-05 471240 + 465 471241 Ag-124m 1.16000E-05 1.16000E-05 471241 + 466 471250 Ag-125 1.80960E-05 1.80960E-05 471250 + 467 471260 Ag-126 5.01760E-06 5.01760E-06 471260 + 468 471270 Ag-127 3.14850E-06 3.14850E-06 471270 + 469 471280 Ag-128 5.54540E-08 5.54540E-08 471280 + 470 471290 Ag-129 6.55920E-09 6.55920E-09 471290 + 471 481120 Cd-112 1.98040E-10 5.21140E-03 48112.82c + 472 481130 Cd-113 8.83310E-10 2.38670E-03 48113.82c + 473 481131 Cd-113m 3.34510E-09 2.73560E-05 481131 + 474 481140 Cd-114 8.67810E-08 9.75520E-04 48114.82c + 475 481150 Cd-115 8.20230E-08 3.57150E-04 481150 + 476 481151 Cd-115m 3.10620E-07 1.76250E-05 48515.82c + 477 481160 Cd-116 3.24630E-06 1.99690E-04 48116.82c + 478 481170 Cd-117 5.66430E-07 7.82870E-05 481170 + 479 481171 Cd-117m 2.14510E-06 2.34330E-05 481171 + 480 481180 Cd-118 1.73970E-05 1.33440E-04 481180 + 481 481190 Cd-119 4.36870E-06 7.95530E-05 481190 + 482 481191 Cd-119m 1.22230E-05 2.00070E-05 481191 + 483 481200 Cd-120 7.00890E-05 1.23480E-04 481200 + 484 481210 Cd-121 1.58170E-05 5.11340E-05 481210 + 485 481211 Cd-121m 4.42560E-05 4.83760E-05 481211 + 486 481220 Cd-122 7.60980E-05 1.00040E-04 481220 + 487 481230 Cd-123 2.33520E-05 4.44380E-05 481230 + 488 481231 Cd-123m 6.53370E-05 7.00300E-05 481231 + 489 481240 Cd-124 2.16660E-04 2.39560E-04 481240 + 490 481250 Cd-125 8.57700E-05 9.48180E-05 481250 + 491 481251 Cd-125m 2.39980E-04 2.49030E-04 481251 + 492 481260 Cd-126 3.40270E-04 3.45290E-04 481260 + 493 481270 Cd-127 2.18170E-04 2.21320E-04 481270 + 494 481280 Cd-128 1.10030E-04 1.10090E-04 481280 + 495 481290 Cd-129 2.21520E-05 2.21550E-05 481290 + 496 481291 Cd-129m 6.19800E-05 6.19830E-05 481291 + 497 481300 Cd-130 1.40750E-05 1.40750E-05 481300 + 498 481310 Cd-131 5.92460E-08 5.92460E-08 481310 + 499 481320 Cd-132 1.76680E-09 1.76680E-09 481320 + 500 491150 In-115 1.11050E-10 3.56920E-04 49115.82c + 501 491151 In-115m 2.23590E-11 3.57150E-04 491151 + 502 491160 In-116 4.18640E-10 4.18640E-10 491160 + 503 491161 In-116m 6.76020E-10 1.45870E-09 491161 + 504 491162 In-116m 7.82650E-10 7.82650E-10 491162 + 505 491170 In-117 3.02730E-08 6.36120E-05 491170 + 506 491171 In-117m 6.09530E-09 7.21070E-05 491171 + 507 491180 In-118 9.30780E-08 1.33530E-04 491180 + 508 491181 In-118m 1.50300E-07 3.21880E-07 491181 + 509 491182 In-118m 1.74010E-07 1.74010E-07 491182 + 510 491190 In-119 1.15020E-06 3.28840E-05 491190 + 511 491191 In-119m 2.31590E-07 7.20950E-05 491191 + 512 491200 In-120 1.11090E-06 1.24590E-04 491200 + 513 491201 In-120m 1.11090E-06 1.11090E-06 491201 + 514 491202 In-120m 1.11090E-06 1.11090E-06 491202 + 515 491210 In-121 7.12080E-06 7.31430E-05 491210 + 516 491211 In-121m 1.43380E-06 3.53460E-05 491211 + 517 491220 In-122 3.78200E-06 1.03820E-04 491220 + 518 491221 In-122m 3.16250E-06 3.16250E-06 491221 + 519 491222 In-122m 3.16250E-06 3.16250E-06 491222 + 520 491230 In-123 3.70850E-05 1.20030E-04 491230 + 521 491231 In-123m 7.46690E-06 3.89950E-05 491231 + 522 491240 In-124 4.63640E-05 2.85930E-04 491240 + 523 491241 In-124m 4.99860E-05 4.99860E-05 491241 + 524 491250 In-125 3.46050E-04 6.40460E-04 491250 + 525 491251 In-125m 6.96750E-05 1.19110E-04 491251 + 526 491260 In-126 3.29920E-04 6.75200E-04 491260 + 527 491261 In-126m 3.55690E-04 3.55690E-04 491261 + 528 491270 In-127 1.20620E-03 1.20620E-03 491270 + 529 491271 In-127m 2.42850E-04 4.64170E-04 491271 + 530 491280 In-128 5.17520E-04 8.30250E-04 491280 + 531 491281 In-128m 2.02640E-04 3.12730E-04 491281 + 532 491282 In-128m 7.76440E-04 7.76440E-04 491282 + 533 491290 In-129 2.36790E-03 2.43020E-03 491290 + 534 491291 In-129m 4.76770E-04 4.99170E-04 491291 + 535 491300 In-130 3.07090E-04 3.20680E-04 491300 + 536 491301 In-130m 4.47140E-04 4.47140E-04 491301 + 537 491302 In-130m 6.22860E-04 6.22860E-04 491302 + 538 491310 In-131 1.32650E-04 1.34060E-04 491310 + 539 491311 In-131m 1.32650E-04 1.32650E-04 491311 + 540 491312 In-131m 1.32650E-04 1.32650E-04 491312 + 541 491320 In-132 4.17960E-05 4.17970E-05 491320 + 542 491330 In-133 2.69250E-06 3.23460E-06 491330 + 543 491331 In-133m 5.42120E-07 5.42120E-07 491331 + 544 491340 In-134 2.24030E-08 2.24030E-08 491340 + 545 501170 Sn-117 5.34090E-13 1.01760E-04 50117.82c + 546 501171 Sn-117m 2.02260E-12 2.16730E-07 501171 + 547 501180 Sn-118 3.40210E-10 1.33860E-04 50118.82c + 548 501190 Sn-119 1.12730E-09 1.00950E-04 50119.82c + 549 501191 Sn-119m 4.26920E-09 2.97120E-05 501191 + 550 501200 Sn-120 1.92380E-07 1.27000E-04 50120.82c + 551 501210 Sn-121 4.51140E-07 1.07640E-04 501210 + 552 501211 Sn-121m 1.26230E-06 9.54820E-06 501211 + 553 501220 Sn-122 3.37360E-06 1.13520E-04 50122.82c + 554 501230 Sn-123 8.88610E-06 1.80370E-05 50123.82c + 555 501231 Sn-123m 3.17590E-06 1.53050E-04 501231 + 556 501240 Sn-124 7.05390E-05 4.06450E-04 50124.82c + 557 501250 Sn-125 1.14340E-04 2.22520E-04 50125.82c + 558 501251 Sn-125m 4.08640E-05 6.92240E-04 501251 + 559 501260 Sn-126 5.34130E-04 1.56820E-03 50126.82c + 560 501270 Sn-127 9.92190E-04 1.46230E-03 501270 + 561 501271 Sn-127m 3.54610E-04 1.55160E-03 501271 + 562 501280 Sn-128 1.08360E-03 5.64410E-03 501280 + 563 501281 Sn-128m 2.95380E-03 3.73020E-03 501281 + 564 501290 Sn-129 3.15040E-03 5.82120E-03 501290 + 565 501291 Sn-129m 8.81460E-03 9.07330E-03 501291 + 566 501300 Sn-130 4.39370E-03 5.24580E-03 501300 + 567 501301 Sn-130m 1.19760E-02 1.25180E-02 501301 + 568 501310 Sn-131 2.50520E-03 2.76210E-03 501310 + 569 501311 Sn-131m 7.00930E-03 7.14770E-03 501311 + 570 501320 Sn-132 6.07440E-03 6.11890E-03 501320 + 571 501330 Sn-133 1.10300E-03 1.10350E-03 501330 + 572 501340 Sn-134 1.61610E-04 1.61620E-04 501340 + 573 501350 Sn-135 1.37750E-05 1.37750E-05 501350 + 574 501360 Sn-136 5.48940E-06 5.48940E-06 501360 + 575 501370 Sn-137 3.24650E-09 3.24650E-09 501370 + 576 511200 Sb-120 9.69440E-12 9.69440E-12 511200 + 577 511201 Sb-120m 1.62130E-11 1.62130E-11 511201 + 578 511210 Sb-121 1.48430E-09 1.09780E-04 51121.82c + 579 511230 Sb-123 3.45070E-06 1.74530E-04 51123.82c + 580 511240 Sb-124 3.27220E-06 8.42160E-06 51124.82c + 581 511241 Sb-124m 2.63970E-06 6.86580E-06 511241 + 582 511242 Sb-124m 4.22610E-06 4.22610E-06 511242 + 583 511250 Sb-125 1.08200E-05 9.25590E-04 51125.82c + 584 511260 Sb-126 1.40930E-05 1.68530E-05 51126.82c + 585 511261 Sb-126m 8.80260E-06 1.97140E-05 511261 + 586 511262 Sb-126m 1.09120E-05 1.09120E-05 511262 + 587 511270 Sb-127 1.33240E-04 3.14720E-03 511270 + 588 511280 Sb-128 1.41230E-04 5.79240E-03 511280 + 589 511281 Sb-128m 1.97520E-04 1.97520E-04 511281 + 590 511290 Sb-129 2.02660E-03 1.32900E-02 511290 + 591 511291 Sb-129m 1.49980E-03 6.03640E-03 511291 + 592 511300 Sb-130 4.34060E-03 1.58450E-02 511300 + 593 511301 Sb-130m 4.34060E-03 1.05990E-02 511301 + 594 511310 Sb-131 1.83800E-02 2.82900E-02 511310 + 595 511320 Sb-132 1.27270E-02 1.88460E-02 511320 + 596 511321 Sb-132m 1.12690E-02 1.12690E-02 511321 + 597 511330 Sb-133 2.62970E-02 2.74280E-02 511330 + 598 511340 Sb-134 2.29000E-03 2.42560E-03 511340 + 599 511341 Sb-134m 6.24200E-03 6.24350E-03 511341 + 600 511350 Sb-135 2.95780E-03 2.97030E-03 511350 + 601 511360 Sb-136 5.69860E-04 5.73700E-04 511360 + 602 511370 Sb-137 6.82690E-05 6.82700E-05 511370 + 603 511380 Sb-138 4.83720E-06 4.83720E-06 511380 + 604 511390 Sb-139 3.68920E-08 3.68920E-08 511390 + 605 521260 Te-126 3.75940E-06 3.75670E-05 52126.82c + 606 521270 Te-127 8.28450E-07 3.13780E-03 521270 + 607 521271 Te-127m 2.31790E-06 5.20950E-04 52527.82c + 608 521280 Te-128 1.19420E-05 5.99480E-03 52128.82c + 609 521290 Te-129 3.75650E-05 1.58550E-02 521290 + 610 521291 Te-129m 1.05110E-04 7.32140E-03 52529.82c + 611 521300 Te-130 1.06180E-03 2.75060E-02 52130.82c + 612 521310 Te-131 7.94900E-04 2.77620E-02 521310 + 613 521311 Te-131m 2.22410E-03 4.48900E-03 521311 + 614 521320 Te-132 1.52890E-02 4.54040E-02 52132.82c + 615 521330 Te-133 9.72390E-03 3.80040E-02 521330 + 616 521331 Te-133m 2.72070E-02 3.19520E-02 521331 + 617 521340 Te-134 5.98790E-02 6.90100E-02 521340 + 618 521350 Te-135 3.44300E-02 3.70270E-02 521350 + 619 521360 Te-136 1.90580E-02 1.95700E-02 521360 + 620 521370 Te-137 5.29980E-03 5.33460E-03 521370 + 621 521380 Te-138 1.40420E-03 1.40900E-03 521380 + 622 521390 Te-139 1.95410E-04 1.95450E-04 521390 + 623 521400 Te-140 2.82280E-05 2.82280E-05 521400 + 624 521410 Te-141 9.62020E-07 9.62020E-07 521410 + 625 521420 Te-142 3.58830E-09 3.58830E-09 521420 + 626 531290 I-129 1.24630E-08 1.85630E-02 53129.82c + 627 531300 I-130 1.86800E-06 2.44360E-06 53130.82c + 628 531301 I-130m 6.85310E-07 6.85310E-07 531301 + 629 531310 I-131 3.09810E-05 3.13400E-02 53131.82c + 630 531320 I-132 1.24190E-04 4.56230E-02 531320 + 631 531321 I-132m 1.09950E-04 1.09950E-04 531321 + 632 531330 I-133 1.22630E-03 6.64990E-02 531330 + 633 531331 I-133m 9.07500E-04 9.07500E-04 531331 + 634 531340 I-134 4.25560E-03 7.69470E-02 531340 + 635 531341 I-134m 3.76780E-03 3.76780E-03 531341 + 636 531350 I-135 3.31080E-02 7.01360E-02 53135.82c + 637 531360 I-136 9.35240E-03 2.90020E-02 531360 + 638 531361 I-136m 2.54930E-02 2.55720E-02 531361 + 639 531370 I-137 3.45050E-02 3.97690E-02 531370 + 640 531380 I-138 1.50290E-02 1.63490E-02 531380 + 641 531390 I-139 1.15480E-02 1.17430E-02 531390 + 642 531400 I-140 2.48070E-03 2.50890E-03 531400 + 643 531410 I-141 6.45100E-04 6.46060E-04 531410 + 644 531420 I-142 6.49940E-05 6.49980E-05 531420 + 645 531430 I-143 5.21350E-06 5.21350E-06 531430 + 646 531440 I-144 2.10250E-08 2.10250E-08 531440 + 647 541310 Xe-131 4.10510E-10 3.13400E-02 54131.82c + 648 541311 Xe-131m 1.14860E-09 3.40410E-04 541311 + 649 541320 Xe-132 1.74520E-06 4.56420E-02 54132.82c + 650 541321 Xe-132m 2.33800E-06 2.33800E-06 541321 + 651 541330 Xe-133 7.38270E-06 6.65270E-02 54133.82c + 652 541331 Xe-133m 2.06560E-05 1.91350E-03 541331 + 653 541340 Xe-134 8.54400E-05 7.73520E-02 54134.82c + 654 541341 Xe-134m 2.32890E-04 3.19550E-04 541341 + 655 541350 Xe-135 5.60250E-04 7.21840E-02 54135.82c + 656 541351 Xe-135m 1.56760E-03 1.31460E-02 541351 + 657 541360 Xe-136 1.42740E-02 7.14330E-02 54136.82c + 658 541370 Xe-137 2.41230E-02 6.21730E-02 541370 + 659 541380 Xe-138 4.21890E-02 5.88230E-02 541380 + 660 541390 Xe-139 3.71910E-02 4.80170E-02 541390 + 661 541400 Xe-140 3.29840E-02 3.53950E-02 541400 + 662 541410 Xe-141 1.47890E-02 1.53160E-02 541410 + 663 541420 Xe-142 6.44160E-03 6.49240E-03 541420 + 664 541430 Xe-143 1.61070E-03 1.61380E-03 541430 + 665 541440 Xe-144 3.14100E-04 3.14110E-04 541440 + 666 541450 Xe-145 4.54060E-05 4.54060E-05 541450 + 667 541460 Xe-146 6.23240E-06 6.23240E-06 541460 + 668 541470 Xe-147 1.67900E-09 1.67900E-09 541470 + 669 551340 Cs-134 1.27960E-08 2.41260E-08 55134.82c + 670 551341 Cs-134m 1.13300E-08 1.13300E-08 551341 + 671 551350 Cs-135 3.39360E-06 7.22690E-02 55135.82c + 672 551351 Cs-135m 2.51140E-06 2.51140E-06 551351 + 673 551360 Cs-136 4.00120E-05 5.43150E-05 55136.82c + 674 551361 Cs-136m 2.86070E-05 2.86070E-05 551361 + 675 551370 Cs-137 9.92490E-04 6.31660E-02 55137.82c + 676 551380 Cs-138 1.35590E-03 6.20150E-02 551380 + 677 551381 Cs-138m 2.26760E-03 2.26760E-03 551381 + 678 551390 Cs-139 1.16100E-02 5.96270E-02 551390 + 679 551400 Cs-140 1.41540E-02 4.95560E-02 551400 + 680 551410 Cs-141 2.46320E-02 3.99640E-02 551410 + 681 551420 Cs-142 2.00270E-02 2.65120E-02 551420 + 682 551430 Cs-143 1.60960E-02 1.77030E-02 551430 + 683 551440 Cs-144 3.25210E-03 5.18450E-03 551440 + 684 551441 Cs-144m 3.25210E-03 3.25320E-03 551441 + 685 551450 Cs-145 2.33500E-03 2.37860E-03 551450 + 686 551460 Cs-146 5.15370E-04 5.21170E-04 551460 + 687 551470 Cs-147 9.56390E-05 9.56410E-05 551470 + 688 551480 Cs-148 8.79700E-06 8.79700E-06 551480 + 689 551490 Cs-149 8.99250E-07 8.99250E-07 551490 + 690 561360 Ba-136 2.45580E-07 6.95340E-05 56136.82c + 691 561361 Ba-136m 6.69410E-07 6.69410E-07 561361 + 692 561370 Ba-137 1.18310E-06 6.31700E-02 56137.82c + 693 561371 Ba-137m 3.31040E-06 5.96320E-02 561371 + 694 561380 Ba-138 1.29690E-04 6.25760E-02 56138.82c + 695 561390 Ba-139 7.67870E-04 6.03950E-02 561390 + 696 561400 Ba-140 3.14430E-03 5.27000E-02 56140.82c + 697 561410 Ba-141 6.08030E-03 4.60450E-02 561410 + 698 561420 Ba-142 1.88990E-02 4.57010E-02 561420 + 699 561430 Ba-143 2.56670E-02 4.32460E-02 561430 + 700 561440 Ba-144 2.95230E-02 3.65080E-02 561440 + 701 561450 Ba-145 1.73350E-02 1.94470E-02 561450 + 702 561460 Ba-146 1.05290E-02 1.10030E-02 561460 + 703 561470 Ba-147 3.74570E-03 3.81630E-03 561470 + 704 561480 Ba-148 1.13560E-03 1.14220E-03 561480 + 705 561490 Ba-149 1.89090E-04 1.89990E-04 561490 + 706 561500 Ba-150 2.61230E-05 2.61230E-05 561500 + 707 561510 Ba-151 6.38530E-06 6.38530E-06 561510 + 708 561520 Ba-152 1.09940E-09 1.09940E-09 561520 + 709 571390 La-139 1.12330E-06 6.03960E-02 57139.82c + 710 571400 La-140 1.31090E-05 5.27130E-02 57140.82c + 711 571410 La-141 8.47790E-05 4.61290E-02 571410 + 712 571420 La-142 3.07100E-04 4.60090E-02 571420 + 713 571430 La-143 1.97020E-03 4.52160E-02 571430 + 714 571440 La-144 4.47190E-03 4.09800E-02 571440 + 715 571450 La-145 1.14310E-02 3.08780E-02 571450 + 716 571460 La-146 3.69730E-03 1.47010E-02 571460 + 717 571461 La-146m 7.75670E-03 7.75670E-03 571461 + 718 571470 La-147 1.09710E-02 1.47920E-02 571470 + 719 571480 La-148 5.73130E-03 6.86970E-03 571480 + 720 571490 La-149 3.10290E-03 3.29210E-03 571490 + 721 571500 La-150 1.01650E-03 1.04260E-03 571500 + 722 571510 La-151 2.50070E-04 2.56450E-04 571510 + 723 571520 La-152 2.85080E-05 2.85090E-05 571520 + 724 571530 La-153 5.02940E-06 5.02940E-06 571530 + 725 571540 La-154 3.11740E-09 3.11740E-09 571540 + 726 571550 La-155 9.59340E-11 9.59340E-11 571550 + 727 581410 Ce-141 1.17280E-09 4.61290E-02 58141.82c + 728 581420 Ce-142 7.76320E-06 4.60160E-02 58142.82c + 729 581430 Ce-143 3.86470E-05 4.52550E-02 58143.82c + 730 581440 Ce-144 3.02540E-04 4.12830E-02 58144.82c + 731 581450 Ce-145 1.16810E-03 3.20460E-02 581450 + 732 581460 Ce-146 4.43680E-03 2.68940E-02 581460 + 733 581470 Ce-147 7.00420E-03 2.17960E-02 581470 + 734 581480 Ce-148 1.17880E-02 1.87040E-02 581480 + 735 581490 Ce-149 9.28350E-03 1.25580E-02 581490 + 736 581500 Ce-150 7.56300E-03 8.57750E-03 581500 + 737 581510 Ce-151 3.40950E-03 3.66770E-03 581510 + 738 581520 Ce-152 1.47060E-03 1.49740E-03 581520 + 739 581530 Ce-153 4.00310E-04 4.05340E-04 581530 + 740 581540 Ce-154 7.69520E-05 7.69550E-05 581540 + 741 581550 Ce-155 7.87070E-06 7.87080E-06 581550 + 742 581560 Ce-156 1.31550E-06 1.31550E-06 581560 + 743 581570 Ce-157 1.82810E-10 1.82810E-10 581570 + 744 591440 Pr-144 6.84250E-10 4.12820E-02 591440 + 745 591441 Pr-144m 6.96100E-09 5.69690E-04 591441 + 746 591450 Pr-145 7.07040E-06 3.20540E-02 591450 + 747 591460 Pr-146 1.97710E-05 2.69140E-02 591460 + 748 591470 Pr-147 1.43080E-04 2.19390E-02 591470 + 749 591480 Pr-148 7.69180E-05 1.87810E-02 591480 + 750 591481 Pr-148m 3.72890E-04 3.72890E-04 591481 + 751 591490 Pr-149 1.67260E-03 1.42300E-02 591490 + 752 591500 Pr-150 2.82240E-03 1.14000E-02 591500 + 753 591510 Pr-151 4.16480E-03 7.83250E-03 591510 + 754 591520 Pr-152 2.80670E-03 4.30660E-03 591520 + 755 591530 Pr-153 2.07330E-03 2.47660E-03 591530 + 756 591540 Pr-154 6.95010E-04 7.71470E-04 591540 + 757 591550 Pr-155 2.61790E-04 2.69660E-04 591550 + 758 591560 Pr-156 4.58310E-05 4.71460E-05 591560 + 759 591570 Pr-157 1.21160E-05 1.21160E-05 591570 + 760 591580 Pr-158 2.88190E-08 2.88190E-08 591580 + 761 591590 Pr-159 7.84460E-10 7.84460E-10 591590 + 762 601460 Nd-146 1.03900E-06 2.69150E-02 60146.82c + 763 601470 Nd-147 4.65740E-06 2.19440E-02 60147.82c + 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1.97780E-05 1.97780E-05 611522 + 784 611530 Pm-153 1.71690E-04 5.75480E-03 611530 + 785 611540 Pm-154 1.70940E-04 3.47120E-03 611540 + 786 611541 Pm-154m 1.70940E-04 1.70940E-04 611541 + 787 611550 Pm-155 7.09380E-04 2.59720E-03 611550 + 788 611560 Pm-156 6.33400E-04 1.47390E-03 611560 + 789 611570 Pm-157 5.73060E-04 8.44150E-04 611570 + 790 611580 Pm-158 2.57610E-04 3.21750E-04 611580 + 791 611590 Pm-159 8.61830E-05 9.60270E-05 611590 + 792 611600 Pm-160 2.57810E-05 2.81020E-05 611600 + 793 611610 Pm-161 3.55540E-06 3.55640E-06 611610 + 794 611620 Pm-162 5.32770E-08 5.32770E-08 611620 + 795 611630 Pm-163 2.96700E-09 2.96700E-09 611630 + 796 621510 Sm-151 2.34390E-10 9.00190E-03 62151.82c + 797 621520 Sm-152 1.10020E-06 7.04120E-03 62152.82c + 798 621530 Sm-153 2.32100E-06 5.76360E-03 62153.82c + 799 621531 Sm-153m 6.49420E-06 6.49420E-06 621531 + 800 621540 Sm-154 3.27650E-05 3.67490E-03 62154.82c + 801 621550 Sm-155 1.08300E-04 2.70550E-03 621550 + 802 621560 Sm-156 2.40170E-04 1.71410E-03 621560 + 803 621570 Sm-157 3.64780E-04 1.20890E-03 621570 + 804 621580 Sm-158 4.39180E-04 7.60940E-04 621580 + 805 621590 Sm-159 3.14200E-04 4.10280E-04 621590 + 806 621600 Sm-160 1.85180E-04 2.13210E-04 621600 + 807 621610 Sm-161 5.92500E-05 6.28060E-05 621610 + 808 621620 Sm-162 1.91280E-05 1.91810E-05 621620 + 809 621630 Sm-163 1.07010E-06 1.07310E-06 621630 + 810 621640 Sm-164 1.86640E-07 1.86640E-07 621640 + 811 621650 Sm-165 1.65000E-09 1.65000E-09 621650 + 812 631540 Eu-154 1.97380E-10 4.10180E-10 63154.82c + 813 631541 Eu-154m 2.12800E-10 2.12800E-10 631541 + 814 631550 Eu-155 1.31320E-06 2.70680E-03 63155.82c + 815 631560 Eu-156 3.94780E-06 1.71800E-03 63156.82c + 816 631570 Eu-157 4.04460E-06 1.21300E-03 63157.82c + 817 631580 Eu-158 1.89300E-05 7.79870E-04 631580 + 818 631590 Eu-159 3.94140E-05 4.49700E-04 631590 + 819 631600 Eu-160 4.45440E-05 2.57750E-04 631600 + 820 631610 Eu-161 3.79290E-05 1.00740E-04 631610 + 821 631620 Eu-162 2.81320E-05 4.73130E-05 631620 + 822 631630 Eu-163 1.62810E-05 1.73540E-05 631630 + 823 631640 Eu-164 6.58800E-06 6.77460E-06 631640 + 824 631650 Eu-165 1.06780E-06 1.06940E-06 631650 + 825 631660 Eu-166 8.32800E-08 8.32800E-08 631660 + 826 631670 Eu-167 2.60350E-09 2.60350E-09 631670 + 827 641570 Gd-157 1.34810E-06 1.21430E-03 64157.82c + 828 641580 Gd-158 3.23340E-08 7.79910E-04 64158.82c + 829 641590 Gd-159 3.69430E-06 4.53390E-04 641590 + 830 641600 Gd-160 8.20450E-06 2.65960E-04 64160.82c + 831 641610 Gd-161 1.06670E-05 1.11400E-04 641610 + 832 641620 Gd-162 1.68800E-05 6.41930E-05 641620 + 833 641630 Gd-163 2.27960E-05 4.01500E-05 641630 + 834 641640 Gd-164 2.52550E-05 3.20300E-05 641640 + 835 641650 Gd-165 2.13560E-06 3.20500E-06 641650 + 836 641660 Gd-166 4.26350E-06 4.34680E-06 641660 + 837 641670 Gd-167 2.11340E-07 2.13940E-07 641670 + 838 641680 Gd-168 3.02650E-08 3.02650E-08 641680 + 839 641690 Gd-169 2.12830E-09 2.12830E-09 641690 + 840 651590 Tb-159 4.80300E-11 4.53390E-04 65159.82c + 841 651600 Tb-160 1.01500E-09 1.01500E-09 65160.82c + 842 651610 Tb-161 1.81560E-08 1.11420E-04 651610 + 843 651620 Tb-162 1.03870E-07 6.42970E-05 651620 + 844 651630 Tb-163 2.17100E-06 4.23210E-05 651630 + 845 651640 Tb-164 3.29410E-06 3.53240E-05 651640 + 846 651650 Tb-165 3.20350E-06 6.40850E-06 651650 + 847 651660 Tb-166 3.19770E-06 7.54450E-06 651660 + 848 651670 Tb-167 1.68320E-06 1.89710E-06 651670 + 849 651680 Tb-168 6.64560E-07 6.94820E-07 651680 + 850 651690 Tb-169 1.65850E-07 1.67980E-07 651690 + 851 651700 Tb-170 1.28350E-08 1.28350E-08 651700 + 852 651710 Tb-171 1.78870E-09 1.78870E-09 651710 + 853 661620 Dy-162 5.76950E-11 6.42970E-05 66162.82c + 854 661630 Dy-163 8.74210E-10 4.23220E-05 66163.82c + 855 661640 Dy-164 2.43190E-08 3.53480E-05 66164.82c + 856 661650 Dy-165 2.98940E-08 6.44230E-06 661650 + 857 661651 Dy-165m 3.98020E-09 3.98020E-09 661651 + 858 661660 Dy-166 1.06590E-06 8.61040E-06 661660 + 859 661670 Dy-167 2.44470E-07 2.14160E-06 661670 + 860 661680 Dy-168 3.66410E-07 1.06120E-06 661680 + 861 661690 Dy-169 2.89060E-07 4.57040E-07 661690 + 862 661700 Dy-170 1.74490E-07 1.87320E-07 661700 + 863 661710 Dy-171 3.50210E-08 3.68100E-08 661710 + 864 661720 Dy-172 1.09000E-08 1.09000E-08 661720 + 865 661730 Dy-173 6.98950E-10 6.98950E-10 661730 + 866 671640 Ho-164 6.42520E-13 2.39390E-12 671640 + 867 671641 Ho-164m 1.75140E-12 1.75140E-12 671641 + 868 671650 Ho-165 2.96510E-11 6.44240E-06 67165.82c + 869 671660 Ho-166 1.94030E-10 8.61060E-06 671660 + 870 671661 Ho-166m 5.28880E-10 5.28880E-10 671661 + 871 671670 Ho-167 3.56990E-09 2.14520E-06 671670 + 872 671680 Ho-168 3.10720E-09 1.06950E-06 671680 + 873 671681 Ho-168m 5.19630E-09 5.19630E-09 671681 + 874 671690 Ho-169 5.49920E-08 5.12030E-07 671690 + 875 671700 Ho-170 3.22310E-08 3.22310E-08 671700 + 876 671701 Ho-170m 1.18240E-08 1.99150E-07 671701 + 877 671710 Ho-171 6.58800E-08 1.02690E-07 671710 + 878 671720 Ho-172 2.64990E-08 3.73990E-08 671720 + 879 671730 Ho-173 1.37170E-08 1.44160E-08 671730 + 880 671740 Ho-174 1.91610E-09 1.91610E-09 671740 + 881 671750 Ho-175 4.98470E-10 4.98470E-10 671750 + 882 681680 Er-168 1.73620E-11 1.06960E-06 68168.82c + 883 681690 Er-169 1.95000E-10 5.12220E-07 681690 + 884 681700 Er-170 1.47230E-09 2.32850E-07 68170.82c + 885 681710 Er-171 3.29730E-09 1.05990E-07 681710 + 886 681720 Er-172 1.07190E-08 4.81180E-08 681720 + 887 681730 Er-173 7.17520E-09 2.15910E-08 681730 + 888 681740 Er-174 7.46640E-09 9.38250E-09 681740 + 889 681750 Er-175 2.57540E-09 3.07390E-09 681750 + 890 681760 Er-176 1.13600E-09 1.13600E-09 681760 + 891 681770 Er-177 1.29300E-10 1.29300E-10 681770 + 892 691710 Tm-171 1.09090E-11 1.06000E-07 691710 + 893 691720 Tm-172 5.88360E-11 4.81770E-08 691720 + 894 691730 Tm-173 3.59750E-10 2.19510E-08 691730 + 895 691740 Tm-174 5.39740E-10 9.92220E-09 691740 + 896 691750 Tm-175 1.45370E-09 4.52760E-09 691750 + 897 691760 Tm-176 8.16790E-10 1.95280E-09 691760 + 898 691770 Tm-177 7.01460E-10 8.30760E-10 691770 + 899 691780 Tm-178 1.84230E-10 1.84230E-10 691780 + 900 691790 Tm-179 7.11400E-11 7.11400E-11 691790 + 901 701740 Yb-174 4.20470E-12 9.92640E-09 701740 + 902 701750 Yb-175 1.61510E-11 4.54590E-09 701750 + 903 701751 Yb-175m 2.15040E-12 3.48840E-09 701751 + 904 701760 Yb-176 2.92750E-11 1.93970E-09 701760 + 905 701761 Yb-176m 6.14160E-11 1.03780E-09 701761 + 906 701770 Yb-177 8.99660E-11 9.38840E-10 701770 + 907 701771 Yb-177m 1.81140E-11 8.48870E-10 701771 + 908 701780 Yb-178 2.15670E-10 3.99900E-10 701780 + 909 701790 Yb-179 1.05850E-10 1.76990E-10 701790 + 910 701800 Yb-180 6.78490E-11 6.78490E-11 701800 + 911 701810 Yb-181 1.47640E-11 1.47640E-11 701810 + 912 711770 Lu-177 8.70570E-13 9.39810E-10 711770 + 913 711780 Lu-178 1.74540E-12 4.01650E-10 711780 + 914 711781 Lu-178m 2.33840E-12 2.33840E-12 711781 + 915 711790 Lu-179 1.50210E-11 1.94010E-10 711790 + 916 711791 Lu-179m 2.00000E-12 1.78990E-10 711791 + 917 711800 Lu-180 3.87620E-12 4.31710E-11 711800 + 918 711801 Lu-180m 3.87620E-12 7.17250E-11 711801 + 919 711802 Lu-180m 6.86370E-12 6.86370E-12 711802 + 920 711810 Lu-181 2.37610E-11 3.85250E-11 711810 + 921 711820 Lu-182 1.00450E-11 1.00450E-11 711820 + 922 711830 Lu-183 5.48520E-12 5.48520E-12 711830 + 923 721820 Hf-182 1.11410E-12 1.21410E-11 721820 + 924 721821 Hf-182m 2.33740E-12 2.33740E-12 721821 + 925 721830 Hf-183 2.45380E-12 7.93900E-12 721830 + 926 721841 Hf-184m 1.87850E-12 1.87850E-12 721841 + 927 721850 Hf-185 1.01110E-12 1.01110E-12 721850 + + Nuclide 94242.82c -- plutonium 242 (Pu-242) + + Neutron-induced fission: + + Interpolation region : 1 / 1 + Interpolation energy : 4.00000E-01 MeV + Number of products : 938 / 1075 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 3.74950E-05 3.74950E-05 1001.82c + 2 10020 H-2 1.14590E-05 1.14590E-05 1002.82c + 3 10030 H-3 1.63480E-04 1.63480E-04 1003.82c + 4 20040 He-4 2.37030E-03 2.37030E-03 2004.82c + 5 200520 Ca-52 1.54770E-12 1.54770E-12 200520 + 6 210520 Sc-52 3.33880E-12 4.85550E-12 210520 + 7 210530 Sc-53 7.50750E-12 7.50750E-12 210530 + 8 210540 Sc-54 4.53840E-12 4.53840E-12 210540 + 9 210550 Sc-55 5.18120E-12 5.18120E-12 210550 + 10 210560 Sc-56 1.08590E-12 1.08590E-12 210560 + 11 220520 Ti-52 1.08830E-12 5.94390E-12 220520 + 12 220530 Ti-53 3.12500E-12 1.06330E-11 220530 + 13 220540 Ti-54 1.52090E-11 1.97470E-11 220540 + 14 220550 Ti-55 2.24030E-11 2.75840E-11 220550 + 15 220560 Ti-56 4.26180E-11 4.37040E-11 220560 + 16 220570 Ti-57 2.03260E-11 2.03260E-11 220570 + 17 220580 Ti-58 1.75600E-11 1.75600E-11 220580 + 18 220590 Ti-59 3.09930E-12 3.09930E-12 220590 + 19 230550 V-55 1.10350E-11 3.86190E-11 230550 + 20 230560 V-56 2.62540E-11 7.00190E-11 230560 + 21 230570 V-57 1.01820E-10 1.22080E-10 230570 + 22 230580 V-58 1.17500E-10 1.35060E-10 230580 + 23 230590 V-59 1.96250E-10 1.99350E-10 230590 + 24 230600 V-60 6.78140E-11 6.78140E-11 230600 + 25 230610 V-61 4.56510E-11 4.56510E-11 230610 + 26 230620 V-62 6.69610E-12 6.69610E-12 230620 + 27 230630 V-63 1.14230E-12 1.14230E-12 230630 + 28 240560 Cr-56 2.20280E-12 7.27100E-11 240560 + 29 240570 Cr-57 1.18650E-11 2.41510E-10 240570 + 30 240580 Cr-58 1.13850E-10 1.40860E-10 240580 + 31 240590 Cr-59 2.36130E-10 4.35480E-10 240590 + 32 240600 Cr-60 6.79010E-10 7.49560E-10 240600 + 33 240610 Cr-61 6.35600E-10 6.78510E-10 240610 + 34 240620 Cr-62 9.18090E-10 9.25190E-10 240620 + 35 240630 Cr-63 2.55740E-10 2.56480E-10 240630 + 36 240640 Cr-64 1.17650E-10 1.17650E-10 240640 + 37 240650 Cr-65 1.40930E-11 1.40930E-11 240650 + 38 240660 Cr-66 1.87270E-12 1.87270E-12 240660 + 39 250580 Mn-58 1.45100E-12 1.42310E-10 250580 + 40 250590 Mn-59 3.12420E-11 4.66720E-10 250590 + 41 250600 Mn-60 1.07280E-11 7.72840E-10 250600 + 42 250601 Mn-60m 1.09140E-10 1.09140E-10 250601 + 43 250610 Mn-61 9.11990E-10 1.59050E-09 250610 + 44 250620 Mn-62 1.42510E-09 1.88770E-09 250620 + 45 250621 Mn-62m 2.23180E-10 6.85770E-10 250621 + 46 250630 Mn-63 3.95000E-09 4.20650E-09 250630 + 47 250640 Mn-64 2.63490E-09 2.75250E-09 250640 + 48 250650 Mn-65 3.22190E-09 3.23600E-09 250650 + 49 250660 Mn-66 7.17780E-10 7.19650E-10 250660 + 50 250670 Mn-67 2.50390E-10 2.50390E-10 250670 + 51 250680 Mn-68 2.25040E-11 2.25040E-11 250680 + 52 250690 Mn-69 2.45720E-12 2.45720E-12 250690 + 53 260600 Fe-60 2.33620E-12 8.71770E-10 260600 + 54 260610 Fe-61 2.71480E-11 1.61770E-09 260610 + 55 260620 Fe-62 4.44800E-10 3.01830E-09 260620 + 56 260630 Fe-63 1.37420E-09 5.58070E-09 260630 + 57 260640 Fe-64 7.37980E-09 1.01320E-08 260640 + 58 260650 Fe-65 1.15320E-08 1.47680E-08 260650 + 59 260660 Fe-66 2.29930E-08 2.37130E-08 260660 + 60 260670 Fe-67 1.21080E-08 1.23580E-08 260670 + 61 260680 Fe-68 1.14650E-08 1.14880E-08 260680 + 62 260690 Fe-69 2.14400E-09 2.14590E-09 260690 + 63 260700 Fe-70 5.15900E-10 5.15900E-10 260700 + 64 260710 Fe-71 3.54780E-11 3.54780E-11 260710 + 65 260720 Fe-72 3.16350E-12 3.16350E-12 260720 + 66 270620 Co-62 3.71280E-13 3.01870E-09 270620 + 67 270621 Co-62m 1.01200E-12 1.01200E-12 270621 + 68 270630 Co-63 4.40760E-11 5.62480E-09 270630 + 69 270640 Co-64 3.47560E-10 1.04800E-08 270640 + 70 270650 Co-65 4.72750E-09 1.94960E-08 270650 + 71 270660 Co-66 1.18550E-08 3.55680E-08 270660 + 72 270670 Co-67 5.05130E-08 6.28710E-08 270670 + 73 270680 Co-68 3.61300E-08 5.54330E-08 270680 + 74 270681 Co-68m 2.69680E-08 3.86060E-08 270681 + 75 270690 Co-69 1.10120E-07 1.12120E-07 270690 + 76 270700 Co-70 2.07480E-08 2.07480E-08 270700 + 77 270701 Co-70m 2.07480E-08 2.12640E-08 270701 + 78 270710 Co-71 3.08690E-08 3.09040E-08 270710 + 79 270720 Co-72 4.81490E-09 4.81810E-09 270720 + 80 270730 Co-73 7.04020E-10 7.04020E-10 270730 + 81 270740 Co-74 1.82840E-11 1.82840E-11 270740 + 82 270750 Co-75 1.56740E-12 1.56740E-12 270750 + 83 280640 Ni-64 1.44930E-12 1.04810E-08 28064.82c + 84 280650 Ni-65 3.24690E-11 1.95280E-08 280650 + 85 280660 Ni-66 8.11130E-10 3.63790E-08 280660 + 86 280670 Ni-67 4.86790E-09 6.77390E-08 280670 + 87 280680 Ni-68 5.10780E-08 1.26930E-07 280680 + 88 280690 Ni-69 5.53900E-08 1.66380E-07 280690 + 89 280691 Ni-69m 5.53900E-08 5.53900E-08 280691 + 90 280700 Ni-70 3.44260E-07 3.86270E-07 280700 + 91 280710 Ni-71 3.51180E-07 3.82080E-07 280710 + 92 280720 Ni-72 5.32440E-07 5.37260E-07 280720 + 93 280730 Ni-73 1.25920E-07 1.26620E-07 280730 + 94 280740 Ni-74 3.61900E-08 3.62080E-08 280740 + 95 280750 Ni-75 5.55720E-09 5.55880E-09 280750 + 96 280760 Ni-76 1.38340E-09 1.38340E-09 280760 + 97 280770 Ni-77 5.47570E-11 5.47570E-11 280770 + 98 280780 Ni-78 2.92380E-12 2.92380E-12 280780 + 99 290670 Cu-67 3.44860E-11 6.77740E-08 290670 + 100 290680 Cu-68 1.55370E-10 1.27450E-07 290680 + 101 290681 Cu-68m 4.23500E-10 4.23500E-10 290681 + 102 290690 Cu-69 1.20310E-08 2.33810E-07 290690 + 103 290700 Cu-70 3.42180E-09 3.50140E-08 290700 + 104 290701 Cu-70m 4.37000E-08 6.31850E-08 290701 + 105 290702 Cu-70m 3.42180E-09 3.89700E-07 290702 + 106 290710 Cu-71 4.21710E-07 8.03790E-07 290710 + 107 290720 Cu-72 7.96700E-07 1.33400E-06 290720 + 108 290730 Cu-73 1.60140E-06 1.72800E-06 290730 + 109 290740 Cu-74 2.14490E-06 2.18120E-06 290740 + 110 290750 Cu-75 1.01960E-06 1.02510E-06 290750 + 111 290760 Cu-76 2.10940E-07 2.11640E-07 290760 + 112 290761 Cu-76m 2.10940E-07 2.11640E-07 290761 + 113 290770 Cu-77 1.87810E-07 1.87860E-07 290770 + 114 290780 Cu-78 2.02940E-08 2.02970E-08 290780 + 115 290790 Cu-79 2.66370E-09 2.66370E-09 290790 + 116 290800 Cu-80 6.87190E-11 6.87190E-11 290800 + 117 300690 Zn-69 2.94890E-12 2.33820E-07 300690 + 118 300691 Zn-69m 1.46460E-11 1.46460E-11 300691 + 119 300700 Zn-70 7.92560E-10 4.37610E-07 300700 + 120 300710 Zn-71 1.71390E-09 8.05510E-07 300710 + 121 300711 Zn-71m 8.51210E-09 8.51210E-09 300711 + 122 300720 Zn-72 1.77620E-07 1.51160E-06 300720 + 123 300730 Zn-73 1.79290E-07 2.96400E-06 300730 + 124 300731 Zn-73m 2.47990E-07 1.05670E-06 300731 + 125 300732 Zn-73m 1.61730E-06 1.61730E-06 300732 + 126 300740 Zn-74 1.54160E-06 3.75870E-06 300740 + 127 300750 Zn-75 5.38760E-06 6.38310E-06 300750 + 128 300760 Zn-76 1.54450E-05 1.58620E-05 300760 + 129 300770 Zn-77 1.27370E-05 1.37730E-05 300770 + 130 300771 Zn-77m 1.69590E-06 1.69590E-06 300771 + 131 300780 Zn-78 2.72380E-05 2.72600E-05 300780 + 132 300790 Zn-79 2.86780E-06 2.86900E-06 300790 + 133 300800 Zn-80 9.76670E-06 9.76680E-06 300800 + 134 300810 Zn-81 2.95960E-08 2.95960E-08 300810 + 135 300820 Zn-82 1.09110E-09 1.09110E-09 300820 + 136 300830 Zn-83 8.44730E-11 8.44730E-11 300830 + 137 310710 Ga-71 1.49700E-11 8.14030E-07 310710 + 138 310720 Ga-72 4.02530E-10 1.51200E-06 310720 + 139 310721 Ga-72m 3.95680E-11 5.04060E-08 310721 + 140 310730 Ga-73 1.20700E-08 3.78470E-06 310730 + 141 310740 Ga-74 2.97650E-08 2.87110E-06 310740 + 142 310741 Ga-74m 2.97650E-08 3.78840E-06 310741 + 143 310750 Ga-75 1.03110E-06 7.41420E-06 310750 + 144 310760 Ga-76 4.77090E-06 2.06330E-05 310760 + 145 310770 Ga-77 1.44450E-05 2.90660E-05 310770 + 146 310780 Ga-78 2.38740E-05 5.11710E-05 310780 + 147 310790 Ga-79 6.57740E-05 6.86060E-05 310790 + 148 310800 Ga-80 1.95350E-05 2.93040E-05 310800 + 149 310810 Ga-81 4.56580E-05 4.56850E-05 310810 + 150 310820 Ga-82 4.07950E-06 4.08060E-06 310820 + 151 310830 Ga-83 9.31740E-07 9.31820E-07 310830 + 152 310840 Ga-84 4.59720E-08 4.59720E-08 310840 + 153 310850 Ga-85 1.26380E-09 1.26380E-09 310850 + 154 320730 Ge-73 2.95080E-12 3.78470E-06 32073.82c + 155 320731 Ge-73m 5.94120E-13 3.72910E-06 320731 + 156 320740 Ge-74 1.97860E-10 3.81840E-06 32074.82c + 157 320750 Ge-75 6.68890E-10 7.41980E-06 320750 + 158 320751 Ge-75m 5.02380E-09 3.01590E-07 320751 + 159 320760 Ge-76 2.65570E-07 2.08980E-05 32076.82c + 160 320770 Ge-77 3.18670E-06 8.78980E-06 320770 + 161 320771 Ge-77m 4.24290E-07 2.94900E-05 320771 + 162 320780 Ge-78 2.39100E-05 7.51420E-05 320780 + 163 320790 Ge-79 9.13080E-06 8.03200E-05 320790 + 164 320791 Ge-79m 6.85780E-05 6.86810E-05 320791 + 165 320800 Ge-80 2.30590E-04 2.65330E-04 320800 + 166 320810 Ge-81 2.04940E-04 2.27230E-04 320810 + 167 320811 Ge-81m 4.12630E-05 6.06910E-05 320811 + 168 320820 Ge-82 1.71120E-04 1.74680E-04 320820 + 169 320830 Ge-83 2.97040E-04 2.97660E-04 320830 + 170 320840 Ge-84 2.11420E-04 2.11430E-04 320840 + 171 320850 Ge-85 1.21040E-05 1.21050E-05 320850 + 172 320860 Ge-86 2.54820E-06 2.54820E-06 320860 + 173 320870 Ge-87 1.82720E-08 1.82720E-08 320870 + 174 320880 Ge-88 5.94360E-10 5.94360E-10 320880 + 175 330750 As-75 3.27430E-13 7.41990E-06 33075.82c + 176 330751 As-75m 1.24000E-12 9.17180E-11 330751 + 177 330760 As-76 1.36260E-10 1.36260E-10 330760 + 178 330770 As-77 1.14970E-08 3.26880E-05 330770 + 179 330780 As-78 2.31930E-07 7.53740E-05 330780 + 180 330790 As-79 2.87000E-06 1.49120E-04 330790 + 181 330800 As-80 1.47130E-05 2.80040E-04 330800 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1.72250E-02 370920 + 261 370930 Rb-93 1.32030E-02 1.69060E-02 370930 + 262 370940 Rb-94 6.83220E-03 8.24450E-03 370940 + 263 370950 Rb-95 5.35520E-03 5.72920E-03 370950 + 264 370960 Rb-96 1.39250E-03 2.15470E-03 370960 + 265 370961 Rb-96m 1.39250E-03 1.43650E-03 370961 + 266 370970 Rb-97 1.18700E-03 1.19250E-03 370970 + 267 370980 Rb-98 8.23300E-05 8.23300E-05 370980 + 268 370981 Rb-98m 8.23300E-05 8.31800E-05 370981 + 269 370990 Rb-99 3.40290E-05 3.40290E-05 370990 + 270 371000 Rb-100 2.76700E-06 2.76700E-06 371000 + 271 371010 Rb-101 2.25270E-09 2.25270E-09 371010 + 272 380880 Sr-88 8.61800E-09 8.08630E-03 38088.82c + 273 380890 Sr-89 7.92340E-06 9.66170E-03 38089.82c + 274 380900 Sr-90 1.12690E-04 1.54570E-02 38090.82c + 275 380910 Sr-91 6.44780E-04 1.73230E-02 380910 + 276 380920 Sr-92 3.88250E-03 2.13440E-02 380920 + 277 380930 Sr-93 1.07010E-02 2.82030E-02 380930 + 278 380940 Sr-94 2.19040E-02 2.98090E-02 380940 + 279 380950 Sr-95 2.50770E-02 3.06020E-02 380950 + 280 380960 Sr-96 2.74540E-02 3.03380E-02 380960 + 281 380970 Sr-97 1.47690E-02 1.56730E-02 380970 + 282 380980 Sr-98 8.15350E-03 8.31300E-03 380980 + 283 380990 Sr-99 3.35550E-03 3.38430E-03 380990 + 284 381000 Sr-100 9.41690E-04 9.44300E-04 381000 + 285 381010 Sr-101 1.72980E-04 1.72980E-04 381010 + 286 381020 Sr-102 3.00070E-05 3.00070E-05 381020 + 287 381030 Sr-103 1.96370E-06 1.96370E-06 381030 + 288 390900 Y-90 3.85350E-10 1.54570E-02 39090.82c + 289 390901 Y-90m 6.44450E-10 6.44450E-10 390901 + 290 390910 Y-91 1.85920E-08 1.73240E-02 39091.82c + 291 390911 Y-91m 9.23380E-08 1.01920E-02 390911 + 292 390920 Y-92 2.04740E-05 2.13640E-02 390920 + 293 390930 Y-93 2.49020E-05 2.84150E-02 390930 + 294 390931 Y-93m 1.87030E-04 7.24460E-03 390931 + 295 390940 Y-94 7.18600E-04 3.05270E-02 390940 + 296 390950 Y-95 4.24890E-03 3.48510E-02 390950 + 297 390960 Y-96 3.41260E-03 3.37540E-02 390960 + 298 390961 Y-96m 7.15940E-03 7.16330E-03 390961 + 299 390970 Y-97 3.79500E-03 1.72710E-02 390970 + 300 390971 Y-97m 1.40270E-02 2.02150E-02 390971 + 301 390972 Y-97m 4.82070E-03 4.82070E-03 390972 + 302 390980 Y-98 3.47320E-03 1.17860E-02 390980 + 303 390981 Y-98m 1.68380E-02 1.68380E-02 390981 + 304 390990 Y-99 2.01160E-02 2.35080E-02 390990 + 305 391000 Y-100 4.91310E-03 5.85200E-03 391000 + 306 391001 Y-100m 4.91310E-03 4.91510E-03 391001 + 307 391010 Y-101 6.15300E-03 6.32350E-03 391010 + 308 391020 Y-102 9.07900E-04 9.22080E-04 391020 + 309 391021 Y-102m 9.07900E-04 9.22080E-04 391021 + 310 391030 Y-103 4.84310E-04 4.86270E-04 391030 + 311 391040 Y-104 5.17340E-05 5.17340E-05 391040 + 312 391050 Y-105 1.02620E-05 1.02620E-05 391050 + 313 391060 Y-106 1.26530E-09 1.26530E-09 391060 + 314 400930 Zr-93 1.18310E-06 2.84160E-02 40093.82c + 315 400940 Zr-94 2.69340E-05 3.05540E-02 40094.82c + 316 400950 Zr-95 2.16560E-04 3.50680E-02 40095.82c + 317 400960 Zr-96 1.72800E-03 4.26620E-02 40096.82c + 318 400970 Zr-97 5.43900E-03 4.43430E-02 400970 + 319 400980 Zr-98 1.86410E-02 4.70540E-02 400980 + 320 400990 Zr-99 3.11280E-02 5.42900E-02 400990 + 321 401000 Zr-100 4.33850E-02 5.40980E-02 401000 + 322 401010 Zr-101 3.43680E-02 4.07820E-02 401010 + 323 401020 Zr-102 2.68770E-02 2.86700E-02 401020 + 324 401030 Zr-103 1.18660E-02 1.23180E-02 401030 + 325 401040 Zr-104 5.33570E-03 5.38490E-03 401040 + 326 401050 Zr-105 1.32640E-03 1.33460E-03 401050 + 327 401060 Zr-106 2.92110E-04 2.92110E-04 401060 + 328 401070 Zr-107 4.12690E-05 4.12690E-05 401070 + 329 401080 Zr-108 1.40360E-08 1.40360E-08 401080 + 330 410950 Nb-95 7.56640E-07 3.50470E-02 41095.82c + 331 410951 Nb-95m 1.52350E-07 3.79010E-04 410951 + 332 410960 Nb-96 3.01820E-06 3.01820E-06 410960 + 333 410970 Nb-97 3.48490E-05 4.43850E-02 410970 + 334 410971 Nb-97m 7.01670E-06 4.21540E-02 410971 + 335 410980 Nb-98 6.01010E-05 4.71140E-02 410980 + 336 410981 Nb-98m 2.09410E-04 2.09410E-04 410981 + 337 410990 Nb-99 1.71620E-03 3.64340E-02 410990 + 338 410991 Nb-99m 3.45540E-04 2.03240E-02 410991 + 339 411000 Nb-100 9.12850E-04 5.50110E-02 411000 + 340 411001 Nb-100m 4.42550E-03 4.42550E-03 411001 + 341 411010 Nb-101 1.83480E-02 5.91300E-02 411010 + 342 411020 Nb-102 1.33610E-02 4.20300E-02 411020 + 343 411021 Nb-102m 1.33610E-02 1.33610E-02 411021 + 344 411030 Nb-103 3.34810E-02 4.57990E-02 411030 + 345 411040 Nb-104 1.05700E-02 1.59730E-02 411040 + 346 411041 Nb-104m 1.05700E-02 1.05700E-02 411041 + 347 411050 Nb-105 1.55340E-02 1.68540E-02 411050 + 348 411060 Nb-106 6.78760E-03 7.07680E-03 411060 + 349 411070 Nb-107 3.25760E-03 3.29730E-03 411070 + 350 411080 Nb-108 7.82270E-04 7.82280E-04 411080 + 351 411090 Nb-109 1.57070E-04 1.57070E-04 411090 + 352 411100 Nb-110 1.00990E-05 1.00990E-05 411100 + 353 411110 Nb-111 6.49420E-10 6.49420E-10 411110 + 354 420970 Mo-97 9.72380E-07 4.43850E-02 42097.82c + 355 420980 Mo-98 9.13700E-07 4.73240E-02 42098.82c + 356 420990 Mo-99 5.62380E-05 5.64080E-02 42099.82c + 357 421000 Mo-100 4.09260E-04 5.98460E-02 42100.82c + 358 421010 Mo-101 1.98560E-03 6.11160E-02 421010 + 359 421020 Mo-102 9.14650E-03 6.45370E-02 421020 + 360 421030 Mo-103 1.86260E-02 6.44400E-02 421030 + 361 421040 Mo-104 3.79130E-02 6.47270E-02 421040 + 362 421050 Mo-105 3.65410E-02 5.34270E-02 421050 + 363 421060 Mo-106 3.50490E-02 4.20050E-02 421060 + 364 421070 Mo-107 2.02190E-02 2.33670E-02 421070 + 365 421080 Mo-108 1.19700E-02 1.27240E-02 421080 + 366 421090 Mo-109 4.72410E-03 4.86530E-03 421090 + 367 421100 Mo-110 1.38520E-03 1.39130E-03 421100 + 368 421110 Mo-111 2.20220E-04 2.20220E-04 421110 + 369 421120 Mo-112 3.64890E-05 3.64890E-05 421120 + 370 421130 Mo-113 1.66740E-05 1.66740E-05 421130 + 371 421140 Mo-114 8.90370E-06 8.90370E-06 421140 + 372 431000 Tc-100 2.62620E-09 2.62620E-09 431000 + 373 431010 Tc-101 8.28610E-06 6.11240E-02 431010 + 374 431020 Tc-102 3.54660E-05 6.45730E-02 431020 + 375 431021 Tc-102m 3.54660E-05 3.54660E-05 431021 + 376 431030 Tc-103 4.99670E-04 6.49390E-02 431030 + 377 431040 Tc-104 1.72390E-03 6.64510E-02 431040 + 378 431050 Tc-105 6.29090E-03 5.97180E-02 431050 + 379 431060 Tc-106 1.09020E-02 5.29070E-02 431060 + 380 431070 Tc-107 2.30170E-02 4.63840E-02 431070 + 381 431080 Tc-108 2.12460E-02 3.39950E-02 431080 + 382 431090 Tc-109 1.82110E-02 2.30510E-02 431090 + 383 431100 Tc-110 9.11960E-03 1.05130E-02 431100 + 384 431110 Tc-111 4.68060E-03 4.89930E-03 431110 + 385 431120 Tc-112 1.42020E-03 1.45590E-03 431120 + 386 431130 Tc-113 5.23850E-04 5.40520E-04 431130 + 387 431140 Tc-114 1.58980E-04 1.67880E-04 431140 + 388 431150 Tc-115 4.78540E-05 4.78540E-05 431150 + 389 431160 Tc-116 1.67640E-05 1.67640E-05 431160 + 390 431170 Tc-117 6.76600E-06 6.76600E-06 431170 + 391 441020 Ru-102 1.07290E-06 6.46090E-02 44102.82c + 392 441030 Ru-103 7.75730E-07 6.49420E-02 44103.82c + 393 441031 Ru-103m 2.17050E-06 2.17050E-06 441031 + 394 441040 Ru-104 6.17920E-05 6.65130E-02 44104.82c + 395 441050 Ru-105 2.44940E-04 5.99630E-02 44105.82c + 396 441060 Ru-106 1.26070E-03 5.41680E-02 44106.82c + 397 441070 Ru-107 3.63200E-03 5.00160E-02 441070 + 398 441080 Ru-108 9.70750E-03 4.37210E-02 441080 + 399 441090 Ru-109 1.29010E-02 3.59370E-02 441090 + 400 441100 Ru-110 1.46870E-02 2.51960E-02 441100 + 401 441110 Ru-111 9.30110E-03 1.42220E-02 441110 + 402 441120 Ru-112 5.75270E-03 7.22560E-03 441120 + 403 441130 Ru-113 1.13510E-03 2.21520E-03 441130 + 404 441131 Ru-113m 1.13510E-03 1.13510E-03 441131 + 405 441140 Ru-114 1.04020E-03 1.20400E-03 441140 + 406 441150 Ru-115 3.14220E-04 3.57260E-04 441150 + 407 441160 Ru-116 8.55910E-05 1.00310E-04 441160 + 408 441170 Ru-117 2.47760E-05 3.15420E-05 441170 + 409 441180 Ru-118 4.78480E-06 4.78480E-06 441180 + 410 451050 Rh-105 1.51020E-06 5.99650E-02 45105.82c + 411 451051 Rh-105m 2.01080E-07 1.70220E-02 451051 + 412 451060 Rh-106 1.10040E-06 5.41690E-02 451060 + 413 451061 Rh-106m 2.99930E-06 2.99930E-06 451061 + 414 451070 Rh-107 4.24100E-05 5.00580E-02 451070 + 415 451080 Rh-108 4.26910E-05 4.37640E-02 451080 + 416 451081 Rh-108m 1.48750E-04 1.48750E-04 451081 + 417 451090 Rh-109 6.40640E-04 3.65780E-02 451090 + 418 451100 Rh-110 1.38910E-03 2.65850E-02 451100 + 419 451101 Rh-110m 3.27010E-05 3.27010E-05 451101 + 420 451110 Rh-111 2.58440E-03 1.68070E-02 451110 + 421 451120 Rh-112 1.11020E-03 8.33580E-03 451120 + 422 451121 Rh-112m 1.11020E-03 1.11020E-03 451121 + 423 451130 Rh-113 1.86310E-03 4.64580E-03 451130 + 424 451140 Rh-114 3.50130E-04 1.55490E-03 451140 + 425 451141 Rh-114m 3.50130E-04 3.50130E-04 451141 + 426 451150 Rh-115 2.53400E-04 6.10930E-04 451150 + 427 451160 Rh-116 1.80350E-05 1.17900E-04 451160 + 428 451161 Rh-116m 4.91580E-05 4.91580E-05 451161 + 429 451170 Rh-117 2.48180E-05 5.59100E-05 451170 + 430 451180 Rh-118 2.39340E-06 6.98160E-06 451180 + 431 451190 Rh-119 3.77530E-09 3.77530E-09 451190 + 432 451200 Rh-120 5.79270E-11 5.79270E-11 451200 + 433 451210 Rh-121 2.40210E-12 2.40210E-12 451210 + 434 451220 Rh-122 2.40870E-08 2.40870E-08 451220 + 435 461080 Pd-108 1.89400E-06 4.39150E-02 46108.82c + 436 461090 Pd-109 3.98820E-06 3.65910E-02 461090 + 437 461091 Pd-109m 8.76580E-06 1.82980E-02 461091 + 438 461100 Pd-110 5.44040E-05 2.66720E-02 46110.82c + 439 461110 Pd-111 4.31710E-05 1.69010E-02 461110 + 440 461111 Pd-111m 9.48890E-05 1.62120E-04 461111 + 441 461120 Pd-112 2.25960E-04 9.67190E-03 461120 + 442 461130 Pd-113 6.93740E-05 4.90930E-03 461130 + 443 461131 Pd-113m 1.94110E-04 1.94110E-04 461131 + 444 461140 Pd-114 2.44050E-04 2.14910E-03 461140 + 445 461150 Pd-115 3.26990E-05 5.67770E-04 461150 + 446 461151 Pd-115m 7.18710E-05 1.60580E-04 461151 + 447 461160 Pd-116 6.74220E-05 2.34480E-04 461160 + 448 461170 Pd-117 1.13070E-05 9.22740E-05 461170 + 449 461171 Pd-117m 2.48530E-05 2.48530E-05 461171 + 450 461180 Pd-118 1.19700E-05 1.87480E-05 461180 + 451 461190 Pd-119 1.56180E-05 1.56220E-05 461190 + 452 461200 Pd-120 2.54130E-06 2.54130E-06 461200 + 453 461210 Pd-121 2.20130E-06 2.20130E-06 461210 + 454 461220 Pd-122 5.53640E-06 5.56050E-06 461220 + 455 461230 Pd-123 2.12960E-06 2.12960E-06 461230 + 456 461240 Pd-124 8.95490E-07 8.95490E-07 461240 + 457 471100 Ag-110 1.67460E-10 1.73660E-10 471100 + 458 471101 Ag-110m 4.56450E-10 4.56450E-10 47510.82c + 459 471110 Ag-111 3.96810E-09 1.68610E-02 47111.82c + 460 471111 Ag-111m 2.98030E-08 1.68130E-02 471111 + 461 471120 Ag-112 4.22570E-07 9.67230E-03 471120 + 462 471130 Ag-113 5.88820E-07 3.22040E-03 471130 + 463 471131 Ag-113m 4.42240E-06 4.70550E-03 471131 + 464 471140 Ag-114 9.14780E-07 2.15440E-03 471140 + 465 471141 Ag-114m 4.43480E-06 4.43480E-06 471141 + 466 471150 Ag-115 4.51380E-07 4.78850E-04 471150 + 467 471151 Ag-115m 3.39010E-06 3.04420E-04 471151 + 468 471160 Ag-116 2.81900E-06 2.37760E-04 471160 + 469 471161 Ag-116m 7.68400E-06 7.68400E-06 471161 + 470 471170 Ag-117 1.32730E-06 5.08310E-05 471170 + 471 471171 Ag-117m 9.96870E-06 5.61060E-05 471171 + 472 471180 Ag-118 4.09370E-07 1.83900E-05 471180 + 473 471181 Ag-118m 1.98460E-06 4.66480E-06 471181 + 474 471190 Ag-119 1.37730E-06 9.18820E-06 471190 + 475 471191 Ag-119m 1.03450E-05 1.81560E-05 471191 + 476 471200 Ag-120 3.80370E-06 7.90420E-06 471200 + 477 471201 Ag-120m 6.36130E-06 7.63190E-06 471201 + 478 471210 Ag-121 6.60350E-06 8.79880E-06 471210 + 479 471220 Ag-122 1.18070E-06 6.74120E-06 471220 + 480 471221 Ag-122m 1.27290E-06 1.27290E-06 471221 + 481 471230 Ag-123 1.49280E-05 1.70580E-05 471230 + 482 471240 Ag-124 4.65290E-06 8.05670E-06 471240 + 483 471241 Ag-124m 5.01650E-06 5.01650E-06 471241 + 484 471250 Ag-125 1.33880E-05 1.33880E-05 471250 + 485 471260 Ag-126 1.68970E-05 1.68970E-05 471260 + 486 471270 Ag-127 5.68480E-06 5.68480E-06 471270 + 487 471280 Ag-128 3.24670E-07 3.24670E-07 471280 + 488 471290 Ag-129 4.14030E-08 4.14030E-08 471290 + 489 471300 Ag-130 5.50880E-10 5.50880E-10 471300 + 490 481130 Cd-113 1.53130E-10 4.85870E-03 48113.82c + 491 481131 Cd-113m 5.79920E-10 5.56770E-05 481131 + 492 481140 Cd-114 2.46270E-08 2.15450E-03 48114.82c + 493 481150 Cd-115 2.83330E-08 6.84780E-04 481150 + 494 481151 Cd-115m 1.07300E-07 3.47020E-05 48515.82c + 495 481160 Cd-116 1.07960E-06 2.46070E-04 48116.82c + 496 481170 Cd-117 4.71590E-07 8.23730E-05 481170 + 497 481171 Cd-117m 1.78590E-06 2.34550E-05 481171 + 498 481180 Cd-118 2.39430E-06 2.35360E-05 481180 + 499 481190 Cd-119 2.12030E-06 2.48700E-05 481190 + 500 481191 Cd-119m 5.93240E-06 1.05270E-05 481191 + 501 481200 Cd-120 7.62690E-06 2.03390E-05 481200 + 502 481210 Cd-121 6.37740E-06 1.42570E-05 481210 + 503 481211 Cd-121m 1.78440E-05 1.87630E-05 481211 + 504 481220 Cd-122 2.45470E-05 3.25610E-05 481220 + 505 481230 Cd-123 9.43880E-06 2.33990E-05 481230 + 506 481231 Cd-123m 2.64090E-05 2.95150E-05 481231 + 507 481240 Cd-124 7.71800E-05 8.77370E-05 481240 + 508 481250 Cd-125 5.85030E-05 6.51970E-05 481250 + 509 481251 Cd-125m 1.63690E-04 1.70380E-04 481251 + 510 481260 Cd-126 5.05810E-04 5.22710E-04 481260 + 511 481270 Cd-127 3.88420E-04 3.94110E-04 481270 + 512 481280 Cd-128 2.11370E-04 2.11690E-04 481280 + 513 481290 Cd-129 4.10480E-05 4.10690E-05 481290 + 514 481291 Cd-129m 1.14850E-04 1.14870E-04 481291 + 515 481300 Cd-130 4.86920E-05 4.86930E-05 481300 + 516 481310 Cd-131 1.04640E-06 1.04640E-06 481310 + 517 481320 Cd-132 2.24440E-08 2.24440E-08 481320 + 518 491150 In-115 2.19660E-11 6.85240E-04 49115.82c + 519 491151 In-115m 4.42280E-12 6.84780E-04 491151 + 520 491160 In-116 4.90760E-11 4.90760E-11 491160 + 521 491161 In-116m 7.92470E-11 1.70990E-10 491161 + 522 491162 In-116m 9.17470E-11 9.17470E-11 491162 + 523 491170 In-117 4.53350E-09 6.57110E-05 491170 + 524 491171 In-117m 9.12800E-10 7.58460E-05 491171 + 525 491180 In-118 3.45050E-09 2.35400E-05 491180 + 526 491181 In-118m 5.57180E-09 1.19320E-08 491181 + 527 491182 In-118m 6.45070E-09 6.45070E-09 491182 + 528 491190 In-119 2.62420E-07 1.44450E-05 491190 + 529 491191 In-119m 5.28380E-08 2.25280E-05 491191 + 530 491200 In-120 3.09920E-07 2.06490E-05 491200 + 531 491201 In-120m 3.09920E-07 3.09920E-07 491201 + 532 491202 In-120m 3.09920E-07 3.09920E-07 491202 + 533 491210 In-121 7.38680E-06 3.10830E-05 491210 + 534 491211 In-121m 1.48730E-06 1.09430E-05 491211 + 535 491220 In-122 9.18360E-07 3.34790E-05 491220 + 536 491221 In-122m 7.67920E-07 7.67920E-07 491221 + 537 491222 In-122m 7.67920E-07 7.67920E-07 491222 + 538 491230 In-123 2.24120E-05 5.88150E-05 491230 + 539 491231 In-123m 4.51260E-06 2.10240E-05 491231 + 540 491240 In-124 1.24210E-05 1.00160E-04 491240 + 541 491241 In-124m 1.33910E-05 1.33910E-05 491241 + 542 491250 In-125 1.31180E-04 3.32770E-04 491250 + 543 491251 In-125m 2.64120E-05 6.04030E-05 491251 + 544 491260 In-126 2.73970E-04 7.96680E-04 491260 + 545 491261 In-126m 2.95380E-04 2.95380E-04 491261 + 546 491270 In-127 1.28940E-03 1.28940E-03 491270 + 547 491271 In-127m 2.59610E-04 6.53720E-04 491271 + 548 491280 In-128 5.63380E-04 9.95670E-04 491280 + 549 491281 In-128m 2.20590E-04 4.32290E-04 491281 + 550 491282 In-128m 8.45230E-04 8.45230E-04 491282 + 551 491290 In-129 2.46270E-03 2.57850E-03 491290 + 552 491291 In-129m 4.95860E-04 5.37780E-04 491291 + 553 491300 In-130 4.18150E-04 4.65170E-04 491300 + 554 491301 In-130m 6.08850E-04 6.08850E-04 491301 + 555 491302 In-130m 8.48110E-04 8.48110E-04 491302 + 556 491310 In-131 2.84210E-04 2.88120E-04 491310 + 557 491311 In-131m 2.84210E-04 2.84230E-04 491311 + 558 491312 In-131m 2.84210E-04 2.84210E-04 491312 + 559 491320 In-132 1.38140E-04 1.38150E-04 491320 + 560 491330 In-133 1.78600E-05 2.14560E-05 491330 + 561 491331 In-133m 3.59600E-06 3.59600E-06 491331 + 562 491340 In-134 1.73140E-07 1.73140E-07 491340 + 563 491350 In-135 5.05780E-09 5.05780E-09 491350 + 564 501180 Sn-118 3.73120E-12 2.35520E-05 50118.82c + 565 501190 Sn-119 3.05600E-11 3.57120E-05 50119.82c + 566 501191 Sn-119m 1.15730E-10 1.30500E-05 501191 + 567 501200 Sn-120 4.80650E-09 2.12740E-05 50120.82c + 568 501210 Sn-121 1.97080E-08 4.11680E-05 501210 + 569 501211 Sn-121m 5.51410E-08 3.57630E-06 501211 + 570 501220 Sn-122 1.26220E-11 3.50150E-05 50122.82c + 571 501230 Sn-123 2.20220E-06 6.68640E-06 50123.82c + 572 501231 Sn-123m 7.87080E-07 7.61420E-05 501231 + 573 501240 Sn-124 5.18170E-05 1.65370E-04 50124.82c + 574 501250 Sn-125 9.71930E-05 1.53400E-04 50125.82c + 575 501251 Sn-125m 3.47370E-05 3.71700E-04 501251 + 576 501260 Sn-126 5.91240E-04 1.68780E-03 50126.82c + 577 501270 Sn-127 9.76860E-04 1.47940E-03 501270 + 578 501271 Sn-127m 3.49140E-04 1.78520E-03 501271 + 579 501280 Sn-128 9.75850E-04 5.47670E-03 501280 + 580 501281 Sn-128m 2.65990E-03 3.50520E-03 501281 + 581 501290 Sn-129 2.61030E-03 5.45220E-03 501290 + 582 501291 Sn-129m 7.30340E-03 7.57790E-03 501291 + 583 501300 Sn-130 4.83040E-03 6.01190E-03 501300 + 584 501301 Sn-130m 1.31670E-02 1.39130E-02 501301 + 585 501310 Sn-131 3.54430E-03 4.09560E-03 501310 + 586 501311 Sn-131m 9.91670E-03 1.02130E-02 501311 + 587 501320 Sn-132 1.08680E-02 1.10240E-02 501320 + 588 501330 Sn-133 2.67770E-03 2.68100E-03 501330 + 589 501340 Sn-134 5.59280E-04 5.59330E-04 501340 + 590 501350 Sn-135 6.45910E-05 6.45960E-05 501350 + 591 501360 Sn-136 1.18890E-05 1.18890E-05 501360 + 592 501370 Sn-137 3.03870E-08 3.03870E-08 501370 + 593 511210 Sb-121 3.48300E-11 4.19690E-05 51121.82c + 594 511240 Sb-124 1.21040E-12 3.11520E-12 51124.82c + 595 511241 Sb-124m 9.76420E-13 2.53970E-12 511241 + 596 511242 Sb-124m 1.56330E-12 1.56330E-12 511242 + 597 511250 Sb-125 2.35080E-05 5.48610E-04 51125.82c + 598 511260 Sb-126 1.84080E-05 2.20130E-05 51126.82c + 599 511261 Sb-126m 1.14980E-05 2.57510E-05 511261 + 600 511262 Sb-126m 1.42530E-05 1.42530E-05 511262 + 601 511270 Sb-127 1.48870E-04 3.41350E-03 511270 + 602 511280 Sb-128 9.04880E-05 5.57170E-03 511280 + 603 511281 Sb-128m 1.26560E-04 1.26560E-04 511281 + 604 511290 Sb-129 1.04120E-03 1.09660E-02 511290 + 605 511291 Sb-129m 7.70520E-04 4.55940E-03 511291 + 606 511300 Sb-130 2.25270E-03 1.52210E-02 511300 + 607 511301 Sb-130m 2.25270E-03 9.20910E-03 511301 + 608 511310 Sb-131 1.48940E-02 2.92030E-02 511310 + 609 511320 Sb-132 1.27730E-02 2.37970E-02 511320 + 610 511321 Sb-132m 1.13090E-02 1.13090E-02 511321 + 611 511330 Sb-133 3.35190E-02 3.62950E-02 511330 + 612 511340 Sb-134 2.96660E-03 3.43760E-03 511340 + 613 511341 Sb-134m 8.08640E-03 8.09320E-03 511341 + 614 511350 Sb-135 5.89680E-03 5.95140E-03 511350 + 615 511360 Sb-136 1.44470E-03 1.45300E-03 511360 + 616 511370 Sb-137 2.74300E-04 2.74310E-04 511370 + 617 511380 Sb-138 2.60110E-05 2.60110E-05 511380 + 618 511390 Sb-139 4.03280E-06 4.03280E-06 511390 + 619 521270 Te-127 1.91260E-06 3.40710E-03 521270 + 620 521271 Te-127m 5.35140E-06 5.67870E-04 52527.82c + 621 521280 Te-128 1.14140E-05 5.70520E-03 52128.82c + 622 521290 Te-129 1.10390E-05 1.27980E-02 521290 + 623 521291 Te-129m 3.08880E-05 5.63560E-03 52529.82c + 624 521300 Te-130 3.16710E-04 2.47470E-02 52130.82c + 625 521310 Te-131 3.32230E-04 2.78830E-02 521310 + 626 521311 Te-131m 9.29570E-04 3.26760E-03 521311 + 627 521320 Te-132 9.20790E-03 4.43140E-02 52132.82c + 628 521330 Te-133 8.09730E-03 4.31850E-02 521330 + 629 521331 Te-133m 2.26560E-02 2.89340E-02 521331 + 630 521340 Te-134 5.75420E-02 7.00040E-02 521340 + 631 521350 Te-135 3.86920E-02 4.39460E-02 521350 + 632 521360 Te-136 2.69080E-02 2.82540E-02 521360 + 633 521370 Te-137 9.08500E-03 9.22490E-03 521370 + 634 521380 Te-138 3.83220E-03 3.85820E-03 521380 + 635 521390 Te-139 4.92150E-04 4.96180E-04 521390 + 636 521400 Te-140 1.48330E-04 1.48330E-04 521400 + 637 521410 Te-141 9.29850E-06 9.29850E-06 521410 + 638 521420 Te-142 1.90630E-06 1.90630E-06 521420 + 639 531290 I-129 5.24070E-10 1.48840E-02 53129.82c + 640 531300 I-130 9.92930E-07 1.29890E-06 53130.82c + 641 531301 I-130m 3.64270E-07 3.64270E-07 531301 + 642 531310 I-131 1.15160E-05 3.04760E-02 53131.82c + 643 531320 I-132 3.07830E-05 4.43680E-02 531320 + 644 531321 I-132m 2.72540E-05 2.72540E-05 531321 + 645 531330 I-133 4.27130E-04 6.77990E-02 531330 + 646 531331 I-133m 3.16090E-04 3.16090E-04 531331 + 647 531340 I-134 1.62810E-03 7.30400E-02 531340 + 648 531341 I-134m 1.44150E-03 1.44150E-03 531341 + 649 531350 I-135 2.30760E-02 6.70220E-02 53135.82c + 650 531360 I-136 8.71250E-03 3.71050E-02 531360 + 651 531361 I-136m 2.37480E-02 2.38860E-02 531361 + 652 531370 I-137 3.52270E-02 4.44190E-02 531370 + 653 531380 I-138 1.66940E-02 2.03090E-02 531380 + 654 531390 I-139 1.54520E-02 1.59480E-02 531390 + 655 531400 I-140 4.74320E-03 4.89150E-03 531400 + 656 531410 I-141 2.11580E-03 2.12510E-03 531410 + 657 531420 I-142 2.32250E-04 2.34160E-04 531420 + 658 531430 I-143 4.74330E-05 4.74330E-05 531430 + 659 531440 I-144 1.76280E-06 1.76280E-06 531440 + 660 541310 Xe-131 2.75570E-07 3.04770E-02 54131.82c + 661 541311 Xe-131m 7.71030E-07 3.31800E-04 541311 + 662 541320 Xe-132 3.68940E-09 4.43720E-02 54132.82c + 663 541321 Xe-132m 4.94290E-09 4.94290E-09 541321 + 664 541330 Xe-133 5.95770E-07 6.78010E-02 54133.82c + 665 541331 Xe-133m 1.66690E-06 1.93150E-03 541331 + 666 541340 Xe-134 1.83120E-05 7.31420E-02 54134.82c + 667 541341 Xe-134m 4.99160E-05 8.30700E-05 541341 + 668 541350 Xe-135 1.80490E-04 6.76380E-02 54135.82c + 669 541351 Xe-135m 5.05010E-04 1.15690E-02 541351 + 670 541360 Xe-136 7.35070E-03 7.12290E-02 54136.82c + 671 541370 Xe-137 1.74830E-02 6.00910E-02 541370 + 672 541380 Xe-138 3.93420E-02 6.01380E-02 541380 + 673 541390 Xe-139 3.72200E-02 5.20600E-02 541390 + 674 541400 Xe-140 3.97440E-02 4.46270E-02 541400 + 675 541410 Xe-141 2.26510E-02 2.43880E-02 541410 + 676 541420 Xe-142 1.17170E-02 1.19120E-02 541420 + 677 541430 Xe-143 3.26790E-03 3.29710E-03 541430 + 678 541440 Xe-144 9.74990E-04 9.76050E-04 541440 + 679 541450 Xe-145 1.42580E-04 1.42580E-04 541450 + 680 541460 Xe-146 2.30420E-05 2.30420E-05 541460 + 681 541470 Xe-147 2.36550E-08 2.36550E-08 541470 + 682 551350 Cs-135 1.06270E-06 6.77090E-02 55135.82c + 683 551351 Cs-135m 7.86420E-07 7.86420E-07 551351 + 684 551360 Cs-136 9.07240E-06 1.23160E-05 55136.82c + 685 551361 Cs-136m 6.48650E-06 6.48650E-06 551361 + 686 551370 Cs-137 2.76210E-04 6.03670E-02 55137.82c + 687 551380 Cs-138 4.95070E-04 6.13030E-02 551380 + 688 551381 Cs-138m 8.27930E-04 8.27930E-04 551381 + 689 551390 Cs-139 5.64370E-03 5.77040E-02 551390 + 690 551400 Cs-140 9.64030E-03 5.42780E-02 551400 + 691 551410 Cs-141 2.74250E-02 5.18460E-02 551410 + 692 551420 Cs-142 2.04430E-02 3.23450E-02 551420 + 693 551430 Cs-143 1.82100E-02 2.15030E-02 551430 + 694 551440 Cs-144 3.95930E-03 6.89100E-03 551440 + 695 551441 Cs-144m 3.95930E-03 3.96280E-03 551441 + 696 551450 Cs-145 4.72840E-03 4.86540E-03 551450 + 697 551460 Cs-146 1.21440E-03 1.23580E-03 551460 + 698 551470 Cs-147 3.11730E-04 3.11750E-04 551470 + 699 551480 Cs-148 2.61520E-05 2.61520E-05 551480 + 700 551490 Cs-149 4.83620E-06 4.83620E-06 551490 + 701 551500 Cs-150 2.30010E-09 2.30010E-09 551500 + 702 561370 Ba-137 4.48950E-07 6.03690E-02 56137.82c + 703 561371 Ba-137m 1.25620E-06 5.69880E-02 561371 + 704 561380 Ba-138 2.88590E-05 6.14900E-02 56138.82c + 705 561390 Ba-139 1.98030E-04 5.79020E-02 561390 + 706 561400 Ba-140 1.20540E-03 5.54830E-02 56140.82c + 707 561410 Ba-141 3.84970E-03 5.56950E-02 561410 + 708 561420 Ba-142 1.27090E-02 4.54060E-02 561420 + 709 561430 Ba-143 2.26420E-02 4.40130E-02 561430 + 710 561440 Ba-144 3.06690E-02 4.00170E-02 561440 + 711 561450 Ba-145 2.09020E-02 2.52470E-02 561450 + 712 561460 Ba-146 1.58530E-02 1.70020E-02 561460 + 713 561470 Ba-147 5.75930E-03 5.98880E-03 561470 + 714 561480 Ba-148 2.71220E-03 2.73180E-03 561480 + 715 561490 Ba-149 5.18300E-04 5.23140E-04 561490 + 716 561500 Ba-150 1.47170E-04 1.47170E-04 561500 + 717 561510 Ba-151 1.10440E-05 1.10440E-05 561510 + 718 561520 Ba-152 1.80900E-08 1.80900E-08 561520 + 719 561530 Ba-153 1.59030E-10 1.59030E-10 561530 + 720 571400 La-140 2.95720E-06 5.54860E-02 57140.82c + 721 571410 La-141 1.16330E-05 5.57070E-02 571410 + 722 571420 La-142 8.61880E-05 4.54920E-02 571420 + 723 571430 La-143 5.92050E-04 4.46050E-02 571430 + 724 571440 La-144 2.01940E-03 4.20360E-02 571440 + 725 571450 La-145 7.03370E-03 3.22810E-02 571450 + 726 571460 La-146 3.04320E-03 2.00450E-02 571460 + 727 571461 La-146m 6.38430E-03 6.38430E-03 571461 + 728 571470 La-147 1.27650E-02 1.87650E-02 571470 + 729 571480 La-148 7.03240E-03 9.75550E-03 571480 + 730 571490 La-149 4.83390E-03 5.35480E-03 571490 + 731 571500 La-150 1.91560E-03 2.06280E-03 571500 + 732 571510 La-151 7.61030E-04 7.72070E-04 571510 + 733 571520 La-152 1.40410E-04 1.40430E-04 571520 + 734 571530 La-153 2.53590E-05 2.53590E-05 571530 + 735 571540 La-154 3.98870E-08 3.98870E-08 571540 + 736 571550 La-155 1.33210E-09 1.33210E-09 571550 + 737 581420 Ce-142 9.53290E-07 4.54930E-02 58142.82c + 738 581430 Ce-143 5.82010E-06 4.46110E-02 58143.82c + 739 581440 Ce-144 6.29730E-05 4.20990E-02 58144.82c + 740 581450 Ce-145 3.71280E-04 3.26520E-02 581450 + 741 581460 Ce-146 1.89270E-03 2.83220E-02 581460 + 742 581470 Ce-147 4.33910E-03 2.31040E-02 581470 + 743 581480 Ce-148 9.77640E-03 1.96070E-02 581480 + 744 581490 Ce-149 9.55740E-03 1.48930E-02 581490 + 745 581500 Ce-150 1.06690E-02 1.26760E-02 581500 + 746 581510 Ce-151 5.20160E-03 5.98220E-03 581510 + 747 581520 Ce-152 2.93400E-03 3.06600E-03 581520 + 748 581530 Ce-153 8.65000E-04 8.90360E-04 581530 + 749 581540 Ce-154 2.41830E-04 2.41870E-04 581540 + 750 581550 Ce-155 3.93040E-05 3.93050E-05 581550 + 751 581560 Ce-156 6.85130E-06 6.85130E-06 581560 + 752 581570 Ce-157 2.26770E-09 2.26770E-09 581570 + 753 591450 Pr-145 1.88310E-08 3.26520E-02 591450 + 754 591460 Pr-146 3.14610E-06 2.83260E-02 591460 + 755 591470 Pr-147 3.09990E-05 2.31350E-02 591470 + 756 591480 Pr-148 2.87110E-05 1.96360E-02 591480 + 757 591481 Pr-148m 1.39190E-04 1.39190E-04 591481 + 758 591490 Pr-149 5.77130E-04 1.54700E-02 591490 + 759 591500 Pr-150 1.48060E-03 1.41570E-02 591500 + 760 591510 Pr-151 3.39060E-03 9.37270E-03 591510 + 761 591520 Pr-152 3.02450E-03 6.09600E-03 591520 + 762 591530 Pr-153 2.98960E-03 3.87600E-03 591530 + 763 591540 Pr-154 9.84600E-04 1.22490E-03 591540 + 764 591550 Pr-155 7.31060E-04 7.70360E-04 591550 + 765 591560 Pr-156 1.03900E-04 1.10750E-04 591560 + 766 591570 Pr-157 2.57550E-05 2.57570E-05 591570 + 767 591580 Pr-158 2.35450E-06 2.35450E-06 591580 + 768 591590 Pr-159 1.18720E-08 1.18720E-08 591590 + 769 601470 Nd-147 1.15390E-09 2.31350E-02 60147.82c + 770 601480 Nd-148 9.70770E-07 1.97760E-02 60148.82c + 771 601490 Nd-149 2.23690E-05 1.54920E-02 601490 + 772 601500 Nd-150 1.34690E-04 1.42910E-02 60150.82c + 773 601510 Nd-151 4.81100E-04 9.85390E-03 601510 + 774 601520 Nd-152 1.53270E-03 7.62870E-03 601520 + 775 601530 Nd-153 2.51320E-03 6.38920E-03 601530 + 776 601540 Nd-154 2.88730E-03 4.11220E-03 601540 + 777 601550 Nd-155 2.37920E-03 3.15260E-03 601550 + 778 601560 Nd-156 1.36150E-03 1.47090E-03 601560 + 779 601570 Nd-157 3.82890E-04 4.07000E-04 601570 + 780 601580 Nd-158 1.53390E-04 1.55740E-04 601580 + 781 601590 Nd-159 1.95680E-05 1.95800E-05 601590 + 782 601600 Nd-160 2.12770E-06 2.12770E-06 601600 + 783 601610 Nd-161 1.01440E-08 1.01440E-08 601610 + 784 611500 Pm-150 2.40000E-06 2.40000E-06 611500 + 785 611510 Pm-151 1.38250E-06 9.85520E-03 61151.82c + 786 611520 Pm-152 2.01370E-06 7.63070E-03 611520 + 787 611521 Pm-152m 4.23350E-06 4.23350E-06 611521 + 788 611522 Pm-152m 5.53000E-06 5.53000E-06 611522 + 789 611530 Pm-153 8.12800E-05 6.47040E-03 611530 + 790 611540 Pm-154 6.89850E-05 4.18120E-03 611540 + 791 611541 Pm-154m 6.89850E-05 6.89850E-05 611541 + 792 611550 Pm-155 4.61700E-04 3.61430E-03 611550 + 793 611560 Pm-156 5.84600E-04 2.05550E-03 611560 + 794 611570 Pm-157 5.13330E-04 9.20340E-04 611570 + 795 611580 Pm-158 3.21140E-04 4.76920E-04 611580 + 796 611590 Pm-159 1.95460E-04 2.15010E-04 611590 + 797 611600 Pm-160 4.46290E-05 4.67370E-05 611600 + 798 611610 Pm-161 1.43530E-05 1.43630E-05 611610 + 799 611620 Pm-162 2.02580E-06 2.02580E-06 611620 + 800 611630 Pm-163 1.95860E-08 1.95860E-08 611630 + 801 621520 Sm-152 3.11890E-10 7.64050E-03 62152.82c + 802 621530 Sm-153 5.15200E-07 6.47240E-03 62153.82c + 803 621531 Sm-153m 1.44150E-06 1.44150E-06 621531 + 804 621540 Sm-154 8.84670E-06 4.25910E-03 62154.82c + 805 621550 Sm-155 5.46130E-05 3.66890E-03 621550 + 806 621560 Sm-156 1.46140E-04 2.20160E-03 621560 + 807 621570 Sm-157 1.90180E-04 1.11050E-03 621570 + 808 621580 Sm-158 2.80820E-04 7.57780E-04 621580 + 809 621590 Sm-159 3.13240E-04 5.28340E-04 621590 + 810 621600 Sm-160 1.74640E-04 2.21250E-04 621600 + 811 621610 Sm-161 5.12560E-05 6.56190E-05 621610 + 812 621620 Sm-162 4.65480E-05 4.85740E-05 621620 + 813 621630 Sm-163 5.65530E-06 5.67490E-06 621630 + 814 621640 Sm-164 2.33800E-07 2.33800E-07 621640 + 815 621650 Sm-165 2.41410E-09 2.41410E-09 621650 + 816 631550 Eu-155 9.32480E-10 3.66890E-03 63155.82c + 817 631560 Eu-156 1.68340E-08 2.20160E-03 63156.82c + 818 631570 Eu-157 7.05490E-06 1.11760E-03 63157.82c + 819 631580 Eu-158 1.17860E-05 7.69570E-04 631580 + 820 631590 Eu-159 2.40060E-05 5.52340E-04 631590 + 821 631600 Eu-160 2.34340E-05 2.44690E-04 631600 + 822 631610 Eu-161 3.90210E-05 1.04640E-04 631610 + 823 631620 Eu-162 2.43230E-05 7.28970E-05 631620 + 824 631630 Eu-163 1.50840E-05 2.07590E-05 631630 + 825 631640 Eu-164 1.77950E-06 2.01330E-06 631640 + 826 631650 Eu-165 3.21900E-07 3.24310E-07 631650 + 827 631660 Eu-166 5.59450E-08 5.59450E-08 631660 + 828 631670 Eu-167 3.37510E-08 3.37510E-08 631670 + 829 641570 Gd-157 2.73220E-11 1.11760E-03 64157.82c + 830 641580 Gd-158 1.31660E-09 7.69570E-04 64158.82c + 831 641590 Gd-159 2.08230E-08 5.52370E-04 641590 + 832 641600 Gd-160 2.12870E-06 2.46810E-04 64160.82c + 833 641610 Gd-161 1.23210E-05 1.16960E-04 641610 + 834 641620 Gd-162 1.41940E-05 8.70910E-05 641620 + 835 641630 Gd-163 9.43220E-06 3.01910E-05 641630 + 836 641640 Gd-164 7.11890E-06 9.13220E-06 641640 + 837 641650 Gd-165 1.31160E-06 1.63590E-06 641650 + 838 641660 Gd-166 1.39300E-06 1.44890E-06 641660 + 839 641670 Gd-167 1.73300E-06 1.76680E-06 641670 + 840 641680 Gd-168 1.83920E-07 1.83920E-07 641680 + 841 641690 Gd-169 1.21910E-08 1.21910E-08 641690 + 842 651600 Tb-160 2.81350E-11 2.81350E-11 65160.82c + 843 651610 Tb-161 1.00800E-09 1.16960E-04 651610 + 844 651620 Tb-162 1.27320E-08 8.71040E-05 651620 + 845 651630 Tb-163 1.05680E-07 3.02970E-05 651630 + 846 651640 Tb-164 1.65120E-07 9.29730E-06 651640 + 847 651650 Tb-165 1.88670E-07 1.82460E-06 651650 + 848 651660 Tb-166 3.61550E-07 1.81050E-06 651660 + 849 651670 Tb-167 1.73320E-06 3.49990E-06 651670 + 850 651680 Tb-168 6.24230E-07 8.08150E-07 651680 + 851 651690 Tb-169 3.71200E-07 3.83390E-07 651690 + 852 651700 Tb-170 5.38220E-08 5.38220E-08 651700 + 853 651710 Tb-171 1.54720E-08 1.54720E-08 651710 + 854 661630 Dy-163 2.21070E-11 3.02970E-05 66163.82c + 855 661640 Dy-164 3.94600E-10 9.29770E-06 66164.82c + 856 661650 Dy-165 6.65910E-10 1.82530E-06 661650 + 857 661651 Dy-165m 8.86620E-11 8.86620E-11 661651 + 858 661660 Dy-166 1.47690E-08 1.82530E-06 661660 + 859 661670 Dy-167 1.50960E-07 3.65090E-06 661670 + 860 661680 Dy-168 3.19390E-07 1.12750E-06 661680 + 861 661690 Dy-169 2.37390E-07 6.20780E-07 661690 + 862 661700 Dy-170 2.78060E-07 3.31880E-07 661700 + 863 661710 Dy-171 1.05590E-07 1.21060E-07 661710 + 864 661720 Dy-172 5.48480E-08 5.48480E-08 661720 + 865 661730 Dy-173 6.34000E-09 6.34000E-09 661730 + 866 671660 Ho-166 1.44010E-12 1.82530E-06 671660 + 867 671661 Ho-166m 3.92530E-12 3.92530E-12 671661 + 868 671670 Ho-167 6.09960E-10 3.65150E-06 671670 + 869 671680 Ho-168 7.88510E-10 1.12960E-06 671680 + 870 671681 Ho-168m 1.31870E-09 1.31870E-09 671681 + 871 671690 Ho-169 1.54530E-08 6.36230E-07 671690 + 872 671700 Ho-170 1.84700E-08 1.84700E-08 671700 + 873 671701 Ho-170m 6.77600E-09 3.38660E-07 671701 + 874 671710 Ho-171 7.99000E-08 2.00960E-07 671710 + 875 671720 Ho-172 5.13770E-08 1.06220E-07 671720 + 876 671730 Ho-173 4.89520E-08 5.52920E-08 671730 + 877 671740 Ho-174 1.39970E-08 1.39970E-08 671740 + 878 671750 Ho-175 6.38240E-09 6.38240E-09 671750 + 879 681690 Er-169 1.26430E-11 6.36250E-07 681690 + 880 681700 Er-170 2.25170E-10 3.57350E-07 68170.82c + 881 681710 Er-171 1.13040E-09 2.02090E-07 681710 + 882 681720 Er-172 6.90080E-09 1.13130E-07 681720 + 883 681730 Er-173 8.81340E-09 6.41050E-08 681730 + 884 681740 Er-174 2.04890E-08 3.44860E-08 681740 + 885 681750 Er-175 1.16150E-08 1.79970E-08 681750 + 886 681760 Er-176 8.61210E-09 8.61210E-09 681760 + 887 681770 Er-177 1.98010E-09 1.98010E-09 681770 + 888 691720 Tm-172 9.56680E-12 1.13140E-07 691720 + 889 691730 Tm-173 1.30020E-10 6.42350E-08 691730 + 890 691740 Tm-174 4.63550E-10 3.49500E-08 691740 + 891 691750 Tm-175 2.39570E-09 2.03930E-08 691750 + 892 691760 Tm-176 2.29860E-09 1.09110E-08 691760 + 893 691770 Tm-177 4.24380E-09 6.22390E-09 691770 + 894 691780 Tm-178 2.06110E-09 2.06110E-09 691780 + 895 691790 Tm-179 1.30780E-09 1.30780E-09 691790 + 896 701750 Yb-175 6.48500E-12 2.04000E-08 701750 + 897 701751 Yb-175m 8.63440E-13 1.57040E-08 701751 + 898 701760 Yb-176 2.35450E-11 1.04330E-08 701760 + 899 701761 Yb-176m 4.93950E-11 5.50470E-09 701761 + 900 701770 Yb-177 1.65550E-10 6.42280E-09 701770 + 901 701771 Yb-177m 3.33320E-11 6.25720E-09 701771 + 902 701780 Yb-178 8.45770E-10 2.90690E-09 701780 + 903 701790 Yb-179 6.76010E-10 1.98380E-09 701790 + 904 701800 Yb-180 8.86020E-10 8.86020E-10 701800 + 905 701810 Yb-181 3.66230E-10 3.66230E-10 701810 + 906 711780 Lu-178 1.83880E-12 2.90870E-09 711780 + 907 711781 Lu-178m 2.46340E-12 2.46340E-12 711781 + 908 711790 Lu-179 3.03840E-11 2.01820E-09 711790 + 909 711791 Lu-179m 4.04540E-12 1.98790E-09 711791 + 910 711800 Lu-180 1.69750E-11 4.83500E-10 711800 + 911 711801 Lu-180m 1.69750E-11 9.03000E-10 711801 + 912 711802 Lu-180m 3.00580E-11 3.00580E-11 711802 + 913 711810 Lu-181 2.23370E-10 5.89600E-10 711810 + 914 711820 Lu-182 1.51700E-10 1.51700E-10 711820 + 915 711830 Lu-183 1.60370E-10 1.60370E-10 711830 + 916 711840 Lu-184 5.09950E-11 5.09950E-11 711840 + 917 721810 Hf-181 2.45140E-12 5.92050E-10 721810 + 918 721820 Hf-182 5.18550E-12 1.61450E-10 721820 + 919 721821 Hf-182m 1.08790E-11 1.08790E-11 721821 + 920 721830 Hf-183 2.31280E-11 1.83500E-10 721830 + 921 721840 Hf-184 1.94740E-11 4.49710E-11 721840 + 922 721841 Hf-184m 4.08540E-11 6.63520E-11 721841 + 923 721850 Hf-185 3.60410E-11 3.60410E-11 721850 + 924 721860 Hf-186 2.89680E-11 2.89680E-11 721860 + 925 721870 Hf-187 7.45740E-12 7.45740E-12 721870 + 926 721880 Hf-188 3.08350E-12 3.08350E-12 721880 + 927 731840 Ta-184 1.06630E-12 1.12390E-10 731840 + 928 731850 Ta-185 3.69880E-12 4.19470E-11 731850 + 929 731851 Ta-185m 2.20700E-12 2.20700E-12 731851 + 930 731860 Ta-186 6.22620E-12 3.51940E-11 731860 + 931 731870 Ta-187 1.29160E-11 2.03730E-11 731870 + 932 731880 Ta-188 6.69880E-12 9.78230E-12 731880 + 933 731890 Ta-189 4.55470E-12 4.55470E-12 731890 + 934 741880 W-188 2.19910E-12 1.19810E-11 741880 + 935 741890 W-189 1.90210E-12 6.45680E-12 741890 + 936 741900 W-190 1.19520E-12 2.79640E-12 741900 + 937 741901 W-190m 1.60120E-12 1.60120E-12 741901 + 938 741910 W-191 1.24810E-12 1.24810E-12 741910 + + Nuclide 94243.82c -- plutonium 243 (Pu-243) is using NFY data from Cm-245 + + Nuclide 94244.82c -- plutonium 244 (Pu-244) is using NFY data from U-233 + + Nuclide 95241.82c -- americium 241 (Am-241) + + Neutron-induced fission: + + Interpolation region : 1 / 2 + Interpolation energy : 2.53000E-08 MeV + Number of products : 1144 / 1195 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 3.74900E-05 3.74900E-05 1001.82c + 2 10020 H-2 1.14570E-05 1.14570E-05 1002.82c + 3 10030 H-3 1.65000E-04 1.65000E-04 1003.82c + 4 20040 He-4 2.37000E-03 2.37000E-03 2004.82c + 5 190500 K-50 1.97480E-12 1.97480E-12 190500 + 6 200500 Ca-50 1.82610E-11 1.96630E-11 200500 + 7 200510 Ca-51 2.35600E-11 2.35600E-11 200510 + 8 200520 Ca-52 1.43210E-11 1.43210E-11 200520 + 9 200530 Ca-53 6.77460E-12 6.77460E-12 200530 + 10 200540 Ca-54 1.50470E-12 1.50470E-12 200540 + 11 210500 Sc-50 5.28600E-12 2.69320E-11 210500 + 12 210501 Sc-50m 2.25680E-12 2.19200E-11 210501 + 13 210510 Sc-51 2.06560E-11 4.45020E-11 210510 + 14 210520 Sc-52 4.93930E-11 6.54600E-11 210520 + 15 210530 Sc-53 5.30360E-11 5.77780E-11 210530 + 16 210540 Sc-54 5.19070E-11 5.34120E-11 210540 + 17 210550 Sc-55 2.29640E-11 2.29640E-11 210550 + 18 210560 Sc-56 9.76730E-12 9.76730E-12 210560 + 19 210570 Sc-57 1.73830E-12 1.73830E-12 210570 + 20 220510 Ti-51 3.64550E-12 4.81480E-11 220510 + 21 220520 Ti-52 1.94600E-11 8.49200E-11 220520 + 22 220530 Ti-53 8.14720E-11 1.39250E-10 220530 + 23 220540 Ti-54 1.69810E-10 2.23220E-10 220540 + 24 220550 Ti-55 3.02580E-10 3.25540E-10 220550 + 25 220560 Ti-56 3.01860E-10 3.12200E-10 220560 + 26 220570 Ti-57 2.44190E-10 2.45350E-10 220570 + 27 220580 Ti-58 8.39090E-11 8.39090E-11 220580 + 28 220590 Ti-59 2.24750E-11 2.24750E-11 220590 + 29 220600 Ti-60 3.18550E-12 3.18550E-12 220600 + 30 230530 V-53 2.88010E-12 1.42130E-10 230530 + 31 230540 V-54 2.51390E-11 2.48360E-10 230540 + 32 230550 V-55 9.73970E-11 4.22940E-10 230550 + 33 230560 V-56 3.75960E-10 6.88900E-10 230560 + 34 230570 V-57 6.57400E-10 9.02020E-10 230570 + 35 230580 V-58 9.37530E-10 1.02140E-09 230580 + 36 230590 V-59 6.08700E-10 6.31180E-10 230590 + 37 230600 V-60 4.03210E-10 4.06400E-10 230600 + 38 230610 V-61 1.16970E-10 1.16970E-10 230610 + 39 230620 V-62 2.69500E-11 2.69500E-11 230620 + 40 230630 V-63 2.52070E-12 2.52070E-12 230630 + 41 240550 Cr-55 5.67850E-12 4.28620E-10 240550 + 42 240560 Cr-56 5.18860E-11 7.44390E-10 240560 + 43 240570 Cr-57 3.68290E-10 2.08380E-09 240570 + 44 240580 Cr-58 1.12190E-09 1.32620E-09 240580 + 45 240590 Cr-59 2.83080E-09 3.46200E-09 240590 + 46 240600 Cr-60 4.15290E-09 4.56630E-09 240600 + 47 240610 Cr-61 5.16750E-09 5.27750E-09 240610 + 48 240620 Cr-62 2.97640E-09 3.00420E-09 240620 + 49 240630 Cr-63 1.33220E-09 1.33380E-09 240630 + 50 240640 Cr-64 2.84160E-10 2.84160E-10 240640 + 51 240650 Cr-65 4.71650E-11 4.71650E-11 240650 + 52 240660 Cr-66 3.90370E-12 3.90370E-12 240660 + 53 250570 Mn-57 4.18160E-12 2.08800E-09 250570 + 54 250580 Mn-58 5.08990E-11 1.37710E-09 250580 + 55 250581 Mn-58m 5.73100E-12 5.73100E-12 250581 + 56 250590 Mn-59 3.27220E-10 3.78920E-09 250590 + 57 250600 Mn-60 1.92200E-10 4.95480E-09 250600 + 58 250601 Mn-60m 1.70700E-09 1.70700E-09 250601 + 59 250610 Mn-61 5.01460E-09 1.02920E-08 250610 + 60 250620 Mn-62 9.66920E-09 1.11710E-08 250620 + 61 250621 Mn-62m 1.73580E-09 3.23800E-09 250621 + 62 250630 Mn-63 1.16540E-08 1.29880E-08 250630 + 63 250640 Mn-64 1.10190E-08 1.13030E-08 250640 + 64 250650 Mn-65 4.69900E-09 4.74620E-09 250650 + 65 250660 Mn-66 1.89860E-09 1.90250E-09 250660 + 66 250670 Mn-67 3.19490E-10 3.19490E-10 250670 + 67 250680 Mn-68 3.98020E-11 3.98020E-11 250680 + 68 250690 Mn-69 2.05340E-12 2.05340E-12 250690 + 69 260590 Fe-59 5.96900E-12 3.79520E-09 260590 + 70 260600 Fe-60 8.68450E-11 6.55240E-09 260600 + 71 260610 Fe-61 9.86590E-10 1.12790E-08 260610 + 72 260620 Fe-62 4.98230E-09 1.93910E-08 260620 + 73 260630 Fe-63 1.98070E-08 3.27950E-08 260630 + 74 260640 Fe-64 3.99570E-08 5.12600E-08 260640 + 75 260650 Fe-65 6.89860E-08 7.37320E-08 260650 + 76 260660 Fe-66 6.57780E-08 6.76800E-08 260660 + 77 260670 Fe-67 5.05850E-08 5.09040E-08 260670 + 78 260680 Fe-68 1.65780E-08 1.66180E-08 260680 + 79 260690 Fe-69 4.24000E-09 4.24160E-09 260690 + 80 260700 Fe-70 6.35550E-10 6.35550E-10 260700 + 81 260710 Fe-71 9.17670E-11 9.17670E-11 260710 + 82 270610 Co-61 3.42390E-12 1.12820E-08 270610 + 83 270620 Co-62 2.42360E-11 1.94160E-08 270620 + 84 270621 Co-62m 5.67670E-11 5.67670E-11 270621 + 85 270630 Co-63 7.82910E-10 3.35780E-08 270630 + 86 270640 Co-64 6.57430E-09 5.78350E-08 270640 + 87 270650 Co-65 2.45820E-08 9.83140E-08 270650 + 88 270660 Co-66 9.06820E-08 1.58360E-07 270660 + 89 270670 Co-67 1.51320E-07 2.02220E-07 270670 + 90 270680 Co-68 1.10010E-07 1.66990E-07 270680 + 91 270681 Co-68m 9.70440E-08 1.13960E-07 270681 + 92 270690 Co-69 1.29120E-07 1.33070E-07 270690 + 93 270700 Co-70 4.54390E-08 4.54390E-08 270700 + 94 270701 Co-70m 4.54390E-08 4.60740E-08 270701 + 95 270710 Co-71 3.52010E-08 3.52930E-08 270710 + 96 270720 Co-72 1.43310E-09 1.43310E-09 270720 + 97 270730 Co-73 7.84470E-11 7.84470E-11 270730 + 98 270740 Co-74 3.12010E-11 3.12010E-11 270740 + 99 280630 Ni-63 4.27790E-12 3.35820E-08 280630 + 100 280640 Ni-64 9.42960E-11 5.79290E-08 28064.82c + 101 280650 Ni-65 1.60720E-09 9.99210E-08 280650 + 102 280660 Ni-66 1.39480E-08 1.72310E-07 280660 + 103 280670 Ni-67 9.39880E-08 2.96210E-07 280670 + 104 280680 Ni-68 2.74110E-07 4.99410E-07 280680 + 105 280690 Ni-69 3.32870E-07 4.64600E-07 280690 + 106 280691 Ni-69m 3.32870E-07 3.32870E-07 280691 + 107 280700 Ni-70 1.64890E-06 1.74040E-06 280700 + 108 280710 Ni-71 2.07150E-06 2.10680E-06 280710 + 109 280720 Ni-72 1.78420E-07 1.79850E-07 280720 + 110 280730 Ni-73 4.69290E-08 4.70070E-08 280730 + 111 280740 Ni-74 5.09860E-08 5.10170E-08 280740 + 112 280750 Ni-75 7.85070E-09 7.85070E-09 280750 + 113 280760 Ni-76 7.71990E-10 7.71990E-10 280760 + 114 280770 Ni-77 3.59990E-11 3.59990E-11 280770 + 115 290650 Cu-65 1.64230E-12 9.99230E-08 29065.82c + 116 290660 Cu-66 6.94620E-11 1.72380E-07 290660 + 117 290670 Cu-67 1.19990E-09 2.97410E-07 290670 + 118 290680 Cu-68 4.62740E-09 5.13140E-07 290680 + 119 290681 Cu-68m 1.08390E-08 1.08390E-08 290681 + 120 290690 Cu-69 8.55090E-08 8.82980E-07 290690 + 121 290700 Cu-70 4.01860E-08 3.08550E-07 290700 + 122 290701 Cu-70m 4.47700E-07 5.36730E-07 290701 + 123 290702 Cu-70m 4.01860E-08 1.78060E-06 290702 + 124 290710 Cu-71 2.07150E-06 4.17830E-06 290710 + 125 290720 Cu-72 7.59850E-07 9.39700E-07 290720 + 126 290730 Cu-73 1.34640E-06 1.39340E-06 290730 + 127 290740 Cu-74 2.06090E-06 2.11200E-06 290740 + 128 290750 Cu-75 8.83700E-07 8.91430E-07 290750 + 129 290760 Cu-76 2.12710E-07 2.13100E-07 290760 + 130 290761 Cu-76m 2.12710E-07 2.13100E-07 290761 + 131 290770 Cu-77 5.36480E-08 5.36840E-08 290770 + 132 290780 Cu-78 7.91580E-09 7.91580E-09 290780 + 133 290790 Cu-79 4.72610E-10 4.72610E-10 290790 + 134 290800 Cu-80 3.14980E-11 3.14980E-11 290800 + 135 300670 Zn-67 1.90430E-12 2.97410E-07 300670 + 136 300680 Zn-68 6.65510E-11 5.14940E-07 300680 + 137 300690 Zn-69 3.30170E-10 8.84740E-07 300690 + 138 300691 Zn-69m 1.42790E-09 1.42790E-09 300691 + 139 300700 Zn-70 2.70680E-08 2.29550E-06 300700 + 140 300710 Zn-71 7.71220E-08 4.25540E-06 300710 + 141 300711 Zn-71m 3.33540E-07 3.33540E-07 300711 + 142 300720 Zn-72 1.34870E-06 2.28840E-06 300720 + 143 300730 Zn-73 8.53620E-08 1.92600E-06 300730 + 144 300731 Zn-73m 1.16690E-07 4.47220E-07 300731 + 145 300732 Zn-73m 6.61060E-07 6.61060E-07 300732 + 146 300740 Zn-74 1.03050E-05 1.24480E-05 300740 + 147 300750 Zn-75 1.55630E-05 1.64300E-05 300750 + 148 300760 Zn-76 2.37020E-05 2.41220E-05 300760 + 149 300770 Zn-77 2.12580E-06 2.34200E-06 300770 + 150 300771 Zn-77m 3.24980E-07 3.24980E-07 300771 + 151 300780 Zn-78 1.06110E-05 1.06190E-05 300780 + 152 300790 Zn-79 2.55900E-06 2.55920E-06 300790 + 153 300800 Zn-80 1.75140E-07 1.75170E-07 300800 + 154 300810 Zn-81 1.26530E-08 1.26530E-08 300810 + 155 300820 Zn-82 4.56530E-10 4.56530E-10 300820 + 156 310700 Ga-70 3.97670E-11 3.97670E-11 310700 + 157 310710 Ga-71 1.60950E-09 4.59060E-06 310710 + 158 310720 Ga-72 6.04400E-09 2.29510E-06 310720 + 159 310721 Ga-72m 6.80520E-10 7.69310E-08 310721 + 160 310730 Ga-73 3.81230E-08 2.29460E-06 310730 + 161 310740 Ga-74 8.17100E-07 1.07660E-05 310740 + 162 310741 Ga-74m 8.17100E-07 1.32650E-05 310741 + 163 310750 Ga-75 4.44660E-06 2.08760E-05 310750 + 164 310760 Ga-76 1.42210E-05 3.83430E-05 310760 + 165 310770 Ga-77 3.92130E-05 4.17180E-05 310770 + 166 310780 Ga-78 3.18320E-05 4.24840E-05 310780 + 167 310790 Ga-79 4.35040E-05 4.60300E-05 310790 + 168 310800 Ga-80 3.40800E-05 3.42560E-05 310800 + 169 310810 Ga-81 1.23090E-05 1.23210E-05 310810 + 170 310820 Ga-82 1.03550E-06 1.03600E-06 310820 + 171 310830 Ga-83 8.06310E-08 8.06310E-08 310830 + 172 310840 Ga-84 5.13840E-09 5.13840E-09 310840 + 173 310850 Ga-85 8.38380E-11 8.38380E-11 310850 + 174 320720 Ge-72 8.38870E-12 2.29510E-06 32072.82c + 175 320730 Ge-73 1.91350E-10 2.29490E-06 32073.82c + 176 320731 Ge-73m 4.42460E-11 2.26100E-06 320731 + 177 320740 Ge-74 2.64120E-08 1.41090E-05 32074.82c + 178 320750 Ge-75 5.54200E-08 2.12940E-05 320750 + 179 320751 Ge-75m 3.62530E-07 1.19760E-06 320751 + 180 320760 Ge-76 9.48080E-06 4.78240E-05 32076.82c + 181 320770 Ge-77 2.12580E-05 2.98020E-05 320770 + 182 320771 Ge-77m 3.24980E-06 4.49670E-05 320771 + 183 320780 Ge-78 9.01900E-05 1.32710E-04 320780 + 184 320790 Ge-79 2.40930E-05 7.63200E-05 320790 + 185 320791 Ge-79m 1.57610E-04 1.57680E-04 320791 + 186 320800 Ge-80 4.05850E-04 4.41570E-04 320800 + 187 320810 Ge-81 2.23290E-04 2.29700E-04 320810 + 188 320811 Ge-81m 5.16300E-05 5.68630E-05 320811 + 189 320820 Ge-82 2.07210E-04 2.08060E-04 320820 + 190 320830 Ge-83 4.95210E-05 4.95750E-05 320830 + 191 320840 Ge-84 1.44230E-05 1.44250E-05 320840 + 192 320850 Ge-85 1.10040E-06 1.10050E-06 320850 + 193 320860 Ge-86 5.16350E-08 5.16350E-08 320860 + 194 320870 Ge-87 1.97270E-09 1.97270E-09 320870 + 195 330740 As-74 1.11670E-11 1.11670E-11 330740 + 196 330750 As-75 1.13280E-10 2.12950E-05 33075.82c + 197 330751 As-75m 3.70610E-10 7.29890E-10 330751 + 198 330760 As-76 2.43110E-08 2.43110E-08 330760 + 199 330770 As-77 3.14550E-07 6.65400E-05 330770 + 200 330780 As-78 2.65260E-06 1.35370E-04 330780 + 201 330790 As-79 3.07070E-05 2.58400E-04 330790 + 202 330800 As-80 1.36340E-04 5.77910E-04 330800 + 203 330810 As-81 3.64940E-04 6.50930E-04 330810 + 204 330820 As-82 1.58160E-04 3.66220E-04 330820 + 205 330821 As-82m 4.77290E-04 4.77290E-04 330821 + 206 330830 As-83 6.83090E-04 7.34220E-04 330830 + 207 330840 As-84 1.51460E-04 1.57970E-04 330840 + 208 330841 As-84m 1.51460E-04 1.57970E-04 330841 + 209 330850 As-85 1.70290E-04 1.71240E-04 330850 + 210 330860 As-86 4.16760E-05 4.17280E-05 330860 + 211 330870 As-87 6.29940E-06 6.30140E-06 330870 + 212 330880 As-88 3.20620E-07 3.20620E-07 330880 + 213 330890 As-89 1.39350E-08 1.39350E-08 330890 + 214 330900 As-90 3.67360E-10 3.67360E-10 330900 + 215 340760 Se-76 7.92610E-12 2.43190E-08 34076.82c + 216 340770 Se-77 7.50100E-11 6.65410E-05 34077.82c + 217 340771 Se-77m 4.90680E-10 4.90680E-10 340771 + 218 340780 Se-78 2.34300E-08 1.35390E-04 34078.82c + 219 340790 Se-79 6.23760E-07 2.58970E-04 34079.82c + 220 340791 Se-79m 9.53540E-08 2.52370E-04 340791 + 221 340800 Se-80 1.70200E-05 5.94930E-04 34080.82c + 222 340810 Se-81 1.77860E-05 7.84990E-04 340810 + 223 340811 Se-81m 1.16340E-04 1.39710E-04 340811 + 224 340820 Se-82 3.98470E-04 1.24200E-03 34082.82c + 225 340830 Se-83 8.46230E-04 1.11080E-03 340830 + 226 340831 Se-83m 1.95670E-04 6.65790E-04 340831 + 227 340840 Se-84 2.20680E-03 2.56000E-03 340840 + 228 340850 Se-85 2.10960E-03 2.25690E-03 340850 + 229 340860 Se-86 1.56890E-03 1.59780E-03 340860 + 230 340870 Se-87 6.37620E-04 6.42950E-04 340870 + 231 340880 Se-88 1.83840E-04 1.84160E-04 340880 + 232 340890 Se-89 3.96850E-05 3.96990E-05 340890 + 233 340900 Se-90 1.44090E-05 1.44090E-05 340900 + 234 340910 Se-91 2.08990E-07 2.08990E-07 340910 + 235 340920 Se-92 5.63660E-09 5.63660E-09 340920 + 236 350780 Br-78 3.59320E-12 3.59320E-12 350780 + 237 350790 Br-79 5.53180E-11 1.41560E-07 35079.82c + 238 350791 Br-79m 1.80980E-10 1.80980E-10 350791 + 239 350800 Br-80 4.82540E-09 1.93870E-08 350800 + 240 350801 Br-80m 1.45620E-08 1.45620E-08 350801 + 241 350810 Br-81 3.92870E-07 7.85460E-04 35081.82c + 242 350820 Br-82 2.03170E-06 2.87830E-06 350820 + 243 350821 Br-82m 8.67410E-07 8.67410E-07 350821 + 244 350830 Br-83 5.14180E-05 1.82800E-03 350830 + 245 350840 Br-84 1.51130E-04 2.71110E-03 350840 + 246 350841 Br-84m 1.51130E-04 1.51130E-04 350841 + 247 350850 Br-85 1.21310E-03 3.47000E-03 350850 + 248 350860 Br-86 1.88610E-03 3.48390E-03 350860 + 249 350870 Br-87 2.84250E-03 3.48730E-03 350870 + 250 350880 Br-88 2.02610E-03 2.21150E-03 350880 + 251 350890 Br-89 1.55360E-03 1.59020E-03 350890 + 252 350900 Br-90 5.28940E-04 5.43390E-04 350900 + 253 350910 Br-91 2.27460E-04 2.27620E-04 350910 + 254 350920 Br-92 1.99700E-05 1.99760E-05 350920 + 255 350930 Br-93 1.86820E-06 1.86820E-06 350930 + 256 350940 Br-94 4.43990E-08 4.43990E-08 350940 + 257 350950 Br-95 9.27900E-10 9.27900E-10 350950 + 258 360810 Kr-81 1.85120E-10 2.13420E-10 360810 + 259 360811 Kr-81m 2.83000E-11 2.83000E-11 360811 + 260 360820 Kr-82 1.07490E-08 2.90990E-06 36082.82c + 261 360830 Kr-83 1.90630E-06 1.83030E-03 36083.82c + 262 360831 Kr-83m 4.40780E-07 1.82680E-03 360831 + 263 360840 Kr-84 1.23280E-05 2.87460E-03 36084.82c + 264 360850 Kr-85 1.40720E-04 8.94710E-04 36085.82c + 265 360851 Kr-85m 3.25380E-05 3.49690E-03 360851 + 266 360860 Kr-86 8.79710E-04 4.45120E-03 36086.82c + 267 360870 Kr-87 2.06290E-03 5.61080E-03 360870 + 268 360880 Kr-88 4.65790E-03 6.94550E-03 360880 + 269 360890 Kr-89 6.94010E-03 8.43980E-03 360890 + 270 360900 Kr-90 7.83880E-03 8.29400E-03 360900 + 271 360910 Kr-91 5.22460E-03 5.41330E-03 360910 + 272 360920 Kr-92 2.46500E-03 2.47960E-03 360920 + 273 360930 Kr-93 7.29910E-04 7.30540E-04 360930 + 274 360940 Kr-94 1.97090E-04 1.97100E-04 360940 + 275 360950 Kr-95 2.66110E-05 2.66120E-05 360950 + 276 360960 Kr-96 9.72250E-07 9.72250E-07 360960 + 277 360970 Kr-97 1.15270E-08 1.15270E-08 360970 + 278 370830 Rb-83 1.24170E-11 4.23920E-11 370830 + 279 370831 Rb-83m 2.99750E-11 2.99750E-11 370831 + 280 370840 Rb-84 1.31530E-09 3.68130E-09 370840 + 281 370841 Rb-84m 2.36600E-09 2.36600E-09 370841 + 282 370850 Rb-85 1.20060E-07 3.64340E-03 37085.82c + 283 370860 Rb-86 1.05630E-06 2.95630E-06 37086.82c + 284 370861 Rb-86m 1.90000E-06 1.90000E-06 370861 + 285 370870 Rb-87 6.53720E-05 5.67620E-03 37087.82c + 286 370880 Rb-88 3.18460E-04 7.26390E-03 370880 + 287 370890 Rb-89 1.81100E-03 1.02510E-02 370890 + 288 370900 Rb-90 4.29580E-04 7.76620E-03 370900 + 289 370901 Rb-90m 3.81530E-03 4.90020E-03 370901 + 290 370910 Rb-91 8.87150E-03 1.42850E-02 370910 + 291 370920 Rb-92 8.44970E-03 1.09290E-02 370920 + 292 370930 Rb-93 7.91230E-03 8.64500E-03 370930 + 293 370940 Rb-94 4.17690E-03 4.37260E-03 370940 + 294 370950 Rb-95 2.24710E-03 2.27300E-03 370950 + 295 370960 Rb-96 2.32620E-04 3.49630E-04 370960 + 296 370961 Rb-96m 2.32620E-04 2.33080E-04 370961 + 297 370970 Rb-97 1.15750E-04 1.15760E-04 370970 + 298 370980 Rb-98 2.96380E-06 2.96380E-06 370980 + 299 370981 Rb-98m 2.96380E-06 2.96380E-06 370981 + 300 370990 Rb-99 5.94290E-08 5.94290E-08 370990 + 301 371000 Rb-100 1.79470E-09 1.79470E-09 371000 + 302 380860 Sr-86 1.17020E-09 2.95730E-06 38086.82c + 303 380870 Sr-87 5.43000E-08 6.68170E-08 38087.82c + 304 380871 Sr-87m 1.25550E-08 1.25550E-08 380871 + 305 380880 Sr-88 1.40000E-05 7.27790E-03 38088.82c + 306 380890 Sr-89 1.05030E-04 1.03560E-02 38089.82c + 307 380900 Sr-90 9.44820E-04 1.34840E-02 38090.82c + 308 380910 Sr-91 3.30480E-03 1.75900E-02 380910 + 309 380920 Sr-92 1.00180E-02 2.10680E-02 380920 + 310 380930 Sr-93 1.64770E-02 2.54430E-02 380930 + 311 380940 Sr-94 2.42670E-02 2.83930E-02 380940 + 312 380950 Sr-95 1.81220E-02 2.02460E-02 380950 + 313 380960 Sr-96 1.13900E-02 1.18380E-02 380960 + 314 380970 Sr-97 5.10710E-03 5.19420E-03 380970 + 315 380980 Sr-98 1.87620E-03 1.88170E-03 380980 + 316 380990 Sr-99 3.83460E-04 3.83510E-04 380990 + 317 381000 Sr-100 6.37820E-05 6.37840E-05 381000 + 318 381010 Sr-101 5.17590E-06 5.17590E-06 381010 + 319 381020 Sr-102 1.12870E-08 1.12870E-08 381020 + 320 390880 Y-88 1.12610E-10 1.95610E-10 390880 + 321 390881 Y-88m 8.29970E-11 8.29970E-11 390881 + 322 390890 Y-89 2.66300E-09 1.03560E-02 39089.82c + 323 390891 Y-89m 1.15170E-08 1.00970E-06 390891 + 324 390900 Y-90 2.12580E-06 1.34890E-02 39090.82c + 325 390901 Y-90m 3.01650E-06 3.01650E-06 390901 + 326 390910 Y-91 7.55200E-06 1.76300E-02 39091.82c + 327 390911 Y-91m 3.26610E-05 1.03820E-02 390911 + 328 390920 Y-92 2.66900E-04 2.13350E-02 390920 + 329 390930 Y-93 2.30530E-04 2.71810E-02 390930 + 330 390931 Y-93m 1.50800E-03 7.87480E-03 390931 + 331 390940 Y-94 5.43150E-03 3.38250E-02 390940 + 332 390950 Y-95 1.70850E-02 3.73310E-02 390950 + 333 390960 Y-96 7.42040E-03 1.92600E-02 390960 + 334 390961 Y-96m 1.33480E-02 1.33490E-02 390961 + 335 390970 Y-97 4.46870E-03 9.02270E-03 390970 + 336 390971 Y-97m 1.52310E-02 1.92780E-02 390971 + 337 390972 Y-97m 4.09270E-03 4.09270E-03 390972 + 338 390980 Y-98 2.74590E-03 4.62760E-03 390980 + 339 390981 Y-98m 1.15480E-02 1.15480E-02 390981 + 340 390990 Y-99 1.02310E-02 1.06150E-02 390990 + 341 391000 Y-100 1.75420E-03 1.81760E-03 391000 + 342 391001 Y-100m 1.75420E-03 1.75430E-03 391001 + 343 391010 Y-101 1.09840E-03 1.10340E-03 391010 + 344 391020 Y-102 9.19700E-05 9.19750E-05 391020 + 345 391021 Y-102m 9.19700E-05 9.19750E-05 391021 + 346 391030 Y-103 2.40710E-05 2.40710E-05 391030 + 347 391040 Y-104 6.40590E-08 6.40590E-08 391040 + 348 391050 Y-105 1.52710E-09 1.52710E-09 391050 + 349 400910 Zr-91 6.94310E-09 1.76300E-02 40091.82c + 350 400920 Zr-92 7.26090E-06 2.13430E-02 40092.82c + 351 400930 Zr-93 5.33430E-05 2.72340E-02 40093.82c + 352 400940 Zr-94 4.73170E-04 3.42980E-02 40094.82c + 353 400950 Zr-95 2.31210E-03 3.96430E-02 40095.82c + 354 400960 Zr-96 9.97380E-03 4.25980E-02 40096.82c + 355 400970 Zr-97 2.01950E-02 4.95740E-02 400970 + 356 400980 Zr-98 4.03710E-02 5.63170E-02 400980 + 357 400990 Zr-99 4.10200E-02 5.14710E-02 400990 + 358 401000 Zr-100 3.47750E-02 3.83300E-02 401000 + 359 401010 Zr-101 1.65830E-02 1.76950E-02 401010 + 360 401020 Zr-102 8.31660E-03 8.49350E-03 401020 + 361 401030 Zr-103 2.45720E-03 2.47930E-03 401030 + 362 401040 Zr-104 6.29200E-04 6.29260E-04 401040 + 363 401050 Zr-105 6.84600E-05 6.84610E-05 401050 + 364 401060 Zr-106 3.22830E-07 3.22830E-07 401060 + 365 401070 Zr-107 6.75320E-09 6.75320E-09 401070 + 366 410930 Nb-93 4.93570E-10 6.07690E-10 41093.82c + 367 410931 Nb-93m 1.14120E-10 1.14120E-10 410931 + 368 410940 Nb-94 3.68960E-08 6.27680E-08 41094.82c + 369 410941 Nb-94m 2.60020E-08 2.60020E-08 410941 + 370 410950 Nb-95 6.65690E-06 3.96280E-02 41095.82c + 371 410951 Nb-95m 1.53920E-06 4.29830E-04 410951 + 372 410960 Nb-96 1.04310E-04 1.04310E-04 410960 + 373 410970 Nb-97 7.15290E-04 5.04540E-02 410970 + 374 410971 Nb-97m 1.65390E-04 4.72840E-02 410971 + 375 410980 Nb-98 7.87870E-04 5.71050E-02 410980 + 376 410981 Nb-98m 2.37750E-03 2.37750E-03 410981 + 377 410990 Nb-99 1.08900E-02 4.38490E-02 410990 + 378 410991 Nb-99m 2.51800E-03 2.14590E-02 410991 + 379 411000 Nb-100 4.46650E-03 4.27970E-02 411000 + 380 411001 Nb-100m 1.87840E-02 1.87840E-02 411001 + 381 411010 Nb-101 3.70120E-02 5.47070E-02 411010 + 382 411020 Nb-102 1.46320E-02 2.31260E-02 411020 + 383 411021 Nb-102m 1.46320E-02 1.46320E-02 411021 + 384 411030 Nb-103 2.54540E-02 2.79330E-02 411030 + 385 411040 Nb-104 6.14650E-03 6.77670E-03 411040 + 386 411041 Nb-104m 6.14650E-03 6.14650E-03 411041 + 387 411050 Nb-105 5.83700E-03 5.90450E-03 411050 + 388 411060 Nb-106 1.14940E-03 1.14970E-03 411060 + 389 411070 Nb-107 2.81430E-04 2.81440E-04 411070 + 390 411080 Nb-108 2.79770E-05 2.79770E-05 411080 + 391 411090 Nb-109 1.29690E-08 1.29690E-08 411090 + 392 411100 Nb-110 4.24890E-10 4.24890E-10 411100 + 393 420960 Mo-96 1.72480E-08 1.04330E-04 42096.82c + 394 420970 Mo-97 1.59060E-05 5.04700E-02 42097.82c + 395 420980 Mo-98 1.21850E-04 5.96050E-02 42098.82c + 396 420990 Mo-99 8.44700E-04 6.57240E-02 42099.82c + 397 421000 Mo-100 4.40630E-03 6.59870E-02 42100.82c + 398 421010 Mo-101 1.11830E-02 6.58910E-02 421010 + 399 421020 Mo-102 2.95250E-02 6.72820E-02 421020 + 400 421030 Mo-103 3.78960E-02 6.58370E-02 421030 + 401 421040 Mo-104 4.39470E-02 5.69640E-02 421040 + 402 421050 Mo-105 2.66580E-02 3.25140E-02 421050 + 403 421060 Mo-106 1.50400E-02 1.61550E-02 421060 + 404 421070 Mo-107 5.54360E-03 5.80990E-03 421070 + 405 421080 Mo-108 1.71440E-03 1.74060E-03 421080 + 406 421090 Mo-109 2.66110E-04 2.66120E-04 421090 + 407 421100 Mo-110 3.77210E-05 3.77210E-05 421100 + 408 421110 Mo-111 3.00050E-06 3.00050E-06 421110 + 409 421120 Mo-112 7.44870E-10 7.44870E-10 421120 + 410 430980 Tc-98 3.00760E-09 3.00760E-09 430980 + 411 430990 Tc-99 2.70060E-06 6.57250E-02 43099.82c + 412 430991 Tc-99m 6.24440E-07 5.78770E-02 430991 + 413 431000 Tc-100 2.75670E-05 2.75670E-05 431000 + 414 431010 Tc-101 2.47780E-04 6.61380E-02 431010 + 415 431020 Tc-102 5.53100E-04 6.78360E-02 431020 + 416 431021 Tc-102m 5.53100E-04 5.53100E-04 431021 + 417 431030 Tc-103 5.45750E-03 7.12940E-02 431030 + 418 431040 Tc-104 1.28140E-02 6.97780E-02 431040 + 419 431050 Tc-105 2.94630E-02 6.19770E-02 431050 + 420 431060 Tc-106 2.56960E-02 4.18510E-02 431060 + 421 431070 Tc-107 2.28650E-02 2.86750E-02 431070 + 422 431080 Tc-108 1.11900E-02 1.29320E-02 431080 + 423 431090 Tc-109 5.59350E-03 5.85820E-03 431090 + 424 431100 Tc-110 2.04700E-03 2.08470E-03 431100 + 425 431110 Tc-111 5.65650E-04 5.68620E-04 431110 + 426 431120 Tc-112 5.83390E-05 5.83400E-05 431120 + 427 431130 Tc-113 9.78020E-06 9.78020E-06 431130 + 428 431140 Tc-114 7.06870E-10 7.06870E-10 431140 + 429 441010 Ru-101 4.14230E-06 6.61420E-02 44101.82c + 430 441020 Ru-102 2.00980E-05 6.84090E-02 44102.82c + 431 441030 Ru-103 3.78840E-05 7.14230E-02 44103.82c + 432 441031 Ru-103m 9.14560E-05 9.14560E-05 441031 + 433 441040 Ru-104 1.02010E-03 7.07980E-02 44104.82c + 434 441050 Ru-105 3.18460E-03 6.51610E-02 44105.82c + 435 441060 Ru-106 9.01640E-03 5.08670E-02 44106.82c + 436 441070 Ru-107 1.27170E-02 4.13920E-02 441070 + 437 441080 Ru-108 1.62100E-02 2.91470E-02 441080 + 438 441090 Ru-109 1.02660E-02 1.61200E-02 441090 + 439 441100 Ru-110 8.04640E-03 1.01300E-02 441100 + 440 441110 Ru-111 3.54530E-03 4.11480E-03 441110 + 441 441120 Ru-112 1.25650E-03 1.31470E-03 441120 + 442 441130 Ru-113 1.39650E-04 2.18550E-04 441130 + 443 441131 Ru-113m 1.39650E-04 1.39650E-04 441131 + 444 441140 Ru-114 6.52140E-05 6.52150E-05 441140 + 445 441150 Ru-115 1.03950E-05 1.03950E-05 441150 + 446 441160 Ru-116 1.03160E-06 1.03160E-06 441160 + 447 441170 Ru-117 1.10700E-06 1.10700E-06 441170 + 448 451030 Rh-103 4.36860E-10 7.14230E-02 45103.82c + 449 451031 Rh-103m 2.85770E-09 7.05680E-02 451031 + 450 451040 Rh-104 1.04740E-06 4.20390E-06 451040 + 451 451041 Rh-104m 3.16060E-06 3.16060E-06 451041 + 452 451050 Rh-105 3.02720E-05 6.51960E-02 45105.82c + 453 451051 Rh-105m 4.62770E-06 1.85030E-02 451051 + 454 451060 Rh-106 4.53890E-05 5.09130E-02 451060 + 455 451061 Rh-106m 1.06310E-04 1.06310E-04 451061 + 456 451070 Rh-107 7.82580E-04 4.21740E-02 451070 + 457 451080 Rh-108 4.29350E-04 2.95760E-02 451080 + 458 451081 Rh-108m 1.29560E-03 1.29560E-03 451081 + 459 451090 Rh-109 3.44430E-03 1.95650E-02 451090 + 460 451100 Rh-110 4.63480E-03 1.47650E-02 451100 + 461 451101 Rh-110m 1.23720E-04 1.23720E-04 451101 + 462 451110 Rh-111 5.57220E-03 9.68700E-03 451110 + 463 451120 Rh-112 1.50720E-03 2.82190E-03 451120 + 464 451121 Rh-112m 1.50720E-03 1.50720E-03 451121 + 465 451130 Rh-113 1.50190E-03 1.79030E-03 451130 + 466 451140 Rh-114 2.33850E-04 2.99090E-04 451140 + 467 451141 Rh-114m 2.33850E-04 2.33850E-04 451141 + 468 451150 Rh-115 1.51250E-04 1.61630E-04 451150 + 469 451160 Rh-116 1.04730E-05 1.15160E-05 451160 + 470 451161 Rh-116m 2.45300E-05 2.45300E-05 451161 + 471 451170 Rh-117 8.85210E-06 9.93640E-06 451170 + 472 451180 Rh-118 1.15050E-06 1.15050E-06 451180 + 473 451190 Rh-119 1.02920E-10 1.02920E-10 451190 + 474 451220 Rh-122 2.42970E-09 2.42970E-09 451220 + 475 461060 Pd-106 2.98270E-08 5.10190E-02 46106.82c + 476 461070 Pd-107 3.40690E-06 4.21840E-02 46107.82c + 477 461071 Pd-107m 6.40270E-06 6.40270E-06 461071 + 478 461080 Pd-108 4.42440E-05 3.09160E-02 46108.82c + 479 461090 Pd-109 5.29080E-05 1.97170E-02 461090 + 480 461091 Pd-109m 9.94320E-05 9.88180E-03 461091 + 481 461100 Pd-110 5.57700E-04 1.54470E-02 46110.82c + 482 461110 Pd-111 2.94550E-04 1.03750E-02 461110 + 483 461111 Pd-111m 5.53550E-04 5.92300E-04 461111 + 484 461120 Pd-112 1.15190E-03 5.48110E-03 461120 + 485 461130 Pd-113 2.23170E-04 2.55220E-03 461130 + 486 461131 Pd-113m 5.38770E-04 5.38770E-04 461131 + 487 461140 Pd-114 5.29680E-04 1.06260E-03 461140 + 488 461150 Pd-115 7.06930E-05 2.21360E-04 461150 + 489 461151 Pd-115m 1.32860E-04 1.56330E-04 461151 + 490 461160 Pd-116 1.27040E-04 1.63090E-04 461160 + 491 461170 Pd-117 1.73050E-05 5.97970E-05 461170 + 492 461171 Pd-117m 3.25220E-05 3.25220E-05 461171 + 493 461180 Pd-118 2.64640E-05 2.75810E-05 461180 + 494 461190 Pd-119 1.09390E-05 1.09390E-05 461190 + 495 461200 Pd-120 1.99130E-08 1.99130E-08 461200 + 496 461210 Pd-121 7.74840E-10 7.74840E-10 461210 + 497 461220 Pd-122 2.34920E-06 2.35160E-06 461220 + 498 461230 Pd-123 3.32710E-07 3.32710E-07 461230 + 499 461240 Pd-124 3.28260E-08 3.28260E-08 461240 + 500 471080 Ag-108 7.45940E-10 8.97940E-10 471080 + 501 471081 Ag-108m 1.74720E-09 1.74720E-09 471081 + 502 471090 Ag-109 9.69480E-08 1.97180E-02 47109.82c + 503 471091 Ag-109m 6.34180E-07 1.97080E-02 471091 + 504 471100 Ag-110 1.31470E-06 1.35660E-06 471100 + 505 471101 Ag-110m 3.07940E-06 3.07940E-06 47510.82c + 506 471110 Ag-111 3.05590E-06 1.05060E-02 47111.82c + 507 471111 Ag-111m 1.99900E-05 1.04360E-02 471111 + 508 471120 Ag-112 5.25830E-05 5.53370E-03 471120 + 509 471130 Ag-113 1.05530E-05 1.72710E-03 471130 + 510 471131 Ag-113m 6.90330E-05 2.51300E-03 471131 + 511 471140 Ag-114 1.82550E-05 1.15770E-03 471140 + 512 471141 Ag-114m 7.67720E-05 7.67720E-05 471141 + 513 471150 Ag-115 1.10620E-05 2.30610E-04 471150 + 514 471151 Ag-115m 7.23650E-05 2.75950E-04 471151 + 515 471160 Ag-116 3.05870E-05 1.97970E-04 471160 + 516 471161 Ag-116m 7.16430E-05 7.16430E-05 471161 + 517 471170 Ag-117 1.82110E-05 5.70510E-05 471170 + 518 471171 Ag-117m 1.19130E-04 1.49030E-04 471171 + 519 471180 Ag-118 2.14400E-05 8.36640E-05 471180 + 520 471181 Ag-118m 9.01700E-05 9.41130E-05 471181 + 521 471190 Ag-119 1.40210E-05 1.94910E-05 471190 + 522 471191 Ag-119m 9.17190E-05 9.71880E-05 471191 + 523 471200 Ag-120 1.83470E-05 2.79930E-05 471200 + 524 471201 Ag-120m 2.60340E-05 2.60440E-05 471201 + 525 471210 Ag-121 2.30620E-05 2.30630E-05 471210 + 526 471220 Ag-122 6.64830E-06 9.00000E-06 471220 + 527 471221 Ag-122m 5.98870E-06 5.98870E-06 471221 + 528 471230 Ag-123 7.69100E-06 8.02370E-06 471230 + 529 471240 Ag-124 2.12960E-06 3.12160E-06 471240 + 530 471241 Ag-124m 1.91830E-06 1.91830E-06 471241 + 531 471250 Ag-125 2.33700E-06 2.33700E-06 471250 + 532 471260 Ag-126 4.38990E-07 4.38990E-07 471260 + 533 471270 Ag-127 5.55690E-08 5.55690E-08 471270 + 534 471280 Ag-128 2.75630E-09 2.75630E-09 471280 + 535 481110 Cd-111 2.34190E-07 1.05590E-02 48111.82c + 536 481111 Cd-111m 7.66210E-07 7.66210E-07 481111 + 537 481120 Cd-112 1.26070E-07 5.53380E-03 48112.82c + 538 481130 Cd-113 2.29130E-07 2.60220E-03 48113.82c + 539 481131 Cd-113m 7.49630E-07 3.06100E-05 481131 + 540 481140 Cd-114 1.00800E-06 1.15870E-03 48114.82c + 541 481150 Cd-115 6.64380E-07 4.29640E-04 481150 + 542 481151 Cd-115m 2.17360E-06 2.18090E-05 48515.82c + 543 481160 Cd-116 1.34130E-05 2.78730E-04 48116.82c + 544 481170 Cd-117 4.92450E-06 1.57700E-04 481170 + 545 481171 Cd-117m 1.61110E-05 6.04700E-05 481171 + 546 481180 Cd-118 6.44320E-05 2.03620E-04 481180 + 547 481190 Cd-119 2.95450E-05 1.36480E-04 481190 + 548 481191 Cd-119m 7.13250E-05 8.10710E-05 481191 + 549 481200 Cd-120 1.40900E-04 1.85300E-04 481200 + 550 481210 Cd-121 2.98610E-05 5.05140E-05 481210 + 551 481211 Cd-121m 7.20890E-05 7.44990E-05 481211 + 552 481220 Cd-122 9.47280E-05 1.09720E-04 481220 + 553 481230 Cd-123 1.91320E-05 2.56990E-05 481230 + 554 481231 Cd-123m 4.61880E-05 4.76480E-05 481231 + 555 481240 Cd-124 1.27780E-04 1.31860E-04 481240 + 556 481250 Cd-125 3.26090E-05 3.37770E-05 481250 + 557 481251 Cd-125m 7.87210E-05 7.98900E-05 481251 + 558 481260 Cd-126 8.86830E-05 8.91220E-05 481260 + 559 481270 Cd-127 5.80690E-05 5.81250E-05 481270 + 560 481280 Cd-128 1.34200E-05 1.34230E-05 481280 + 561 481290 Cd-129 2.67520E-07 2.67520E-07 481290 + 562 481291 Cd-129m 6.45830E-07 6.45830E-07 481291 + 563 481300 Cd-130 4.43480E-08 4.43480E-08 481300 + 564 481310 Cd-131 1.31960E-09 1.31960E-09 481310 + 565 491130 In-113 1.47450E-10 3.05670E-05 49113.82c + 566 491131 In-113m 3.40930E-11 3.40930E-11 491131 + 567 491140 In-114 1.04040E-09 4.06950E-09 491140 + 568 491141 In-114m 1.59460E-09 3.13900E-09 491141 + 569 491142 In-114m 1.54440E-09 1.54440E-09 491142 + 570 491150 In-115 2.88570E-08 4.30000E-04 49115.82c + 571 491151 In-115m 6.67240E-09 4.29650E-04 491151 + 572 491160 In-116 9.43980E-08 9.43980E-08 491160 + 573 491161 In-116m 1.44690E-07 2.84820E-07 491161 + 574 491162 In-116m 1.40140E-07 1.40140E-07 491162 + 575 491170 In-117 1.83080E-06 1.43260E-04 491170 + 576 491171 In-117m 4.23320E-07 1.45870E-04 491171 + 577 491180 In-118 2.86380E-07 2.03910E-04 491180 + 578 491181 In-118m 4.38950E-07 8.58150E-07 491181 + 579 491182 In-118m 4.25150E-07 4.25150E-07 491182 + 580 491190 In-119 1.48070E-05 1.16070E-04 491190 + 581 491191 In-119m 3.42380E-06 1.26810E-04 491191 + 582 491200 In-120 5.91710E-06 1.91220E-04 491200 + 583 491201 In-120m 5.91710E-06 5.91710E-06 491201 + 584 491202 In-120m 5.91710E-06 5.91710E-06 491202 + 585 491210 In-121 4.23880E-05 1.34420E-04 491210 + 586 491211 In-121m 9.80110E-06 4.33020E-05 491211 + 587 491220 In-122 4.75040E-05 1.57220E-04 491220 + 588 491221 In-122m 3.37030E-05 3.37030E-05 491221 + 589 491222 In-122m 3.37030E-05 3.37030E-05 491222 + 590 491230 In-123 1.35040E-04 1.90060E-04 491230 + 591 491231 In-123m 3.12240E-05 4.95430E-05 491231 + 592 491240 In-124 1.26300E-04 2.58150E-04 491240 + 593 491241 In-124m 1.13760E-04 1.13760E-04 491241 + 594 491250 In-125 4.69480E-04 5.65530E-04 491250 + 595 491251 In-125m 1.08550E-04 1.26160E-04 491251 + 596 491260 In-126 3.74080E-04 4.63200E-04 491260 + 597 491261 In-126m 3.36960E-04 3.36960E-04 491261 + 598 491270 In-127 1.30400E-03 1.30400E-03 491270 + 599 491271 In-127m 3.01510E-04 3.59640E-04 491271 + 600 491280 In-128 3.36480E-04 4.86870E-04 491280 + 601 491281 In-128m 1.36970E-04 1.50390E-04 491281 + 602 491282 In-128m 4.26470E-04 4.26470E-04 491282 + 603 491290 In-129 3.72810E-04 3.73460E-04 491290 + 604 491291 In-129m 8.62020E-05 8.64700E-05 491291 + 605 491300 In-130 3.12620E-05 3.13050E-05 491300 + 606 491301 In-130m 3.49170E-05 3.49170E-05 491301 + 607 491302 In-130m 5.94090E-05 5.94090E-05 491302 + 608 491310 In-131 8.82340E-06 8.91450E-06 491310 + 609 491311 In-131m 8.82340E-06 8.82340E-06 491311 + 610 491312 In-131m 8.82340E-06 8.82340E-06 491312 + 611 491320 In-132 3.64690E-06 3.64690E-06 491320 + 612 491330 In-133 1.17090E-08 1.44160E-08 491330 + 613 491331 In-133m 2.70730E-09 2.70730E-09 491331 + 614 501160 Sn-116 2.23560E-10 3.79450E-07 50116.82c + 615 501170 Sn-117 1.56730E-09 2.20430E-04 50117.82c + 616 501171 Sn-117m 5.12780E-09 4.93240E-07 501171 + 617 501180 Sn-118 1.03730E-07 2.04880E-04 50118.82c + 618 501190 Sn-119 2.84550E-07 2.37000E-04 50119.82c + 619 501191 Sn-119m 9.30950E-07 1.05790E-04 501191 + 620 501200 Sn-120 2.21960E-06 2.05290E-04 50120.82c + 621 501210 Sn-121 7.11190E-07 1.75830E-04 501210 + 622 501211 Sn-121m 1.71690E-06 1.69440E-05 501211 + 623 501220 Sn-122 1.89830E-05 2.43640E-04 50122.82c + 624 501230 Sn-123 3.18270E-05 4.63180E-05 50123.82c + 625 501231 Sn-123m 1.31840E-05 2.38300E-04 501231 + 626 501240 Sn-124 1.48330E-04 5.20250E-04 50124.82c + 627 501250 Sn-125 2.14780E-04 3.10300E-04 50125.82c + 628 501251 Sn-125m 8.89650E-05 6.85130E-04 501251 + 629 501260 Sn-126 1.18830E-03 1.99090E-03 50126.82c + 630 501270 Sn-127 2.75630E-03 3.26460E-03 501270 + 631 501271 Sn-127m 1.14170E-03 2.29460E-03 501271 + 632 501280 Sn-128 1.76130E-03 6.79990E-03 501280 + 633 501281 Sn-128m 4.12530E-03 4.55180E-03 501281 + 634 501290 Sn-129 1.18300E-03 1.60320E-03 501290 + 635 501291 Sn-129m 2.85580E-03 2.89560E-03 501291 + 636 501300 Sn-130 1.05890E-03 1.14060E-03 501300 + 637 501301 Sn-130m 2.48010E-03 2.52420E-03 501301 + 638 501310 Sn-131 5.58530E-04 5.75620E-04 501310 + 639 501311 Sn-131m 1.34840E-03 1.35760E-03 501311 + 640 501320 Sn-132 6.02570E-04 6.06230E-04 501320 + 641 501330 Sn-133 6.45880E-05 6.45900E-05 501330 + 642 501340 Sn-134 6.55670E-06 6.55670E-06 501340 + 643 501350 Sn-135 2.09170E-07 2.09170E-07 501350 + 644 501360 Sn-136 2.43560E-09 2.43560E-09 501360 + 645 511180 Sb-118 8.99520E-12 8.99520E-12 511180 + 646 511181 Sb-118m 1.27640E-11 1.27640E-11 511181 + 647 511190 Sb-119 6.61780E-10 8.72140E-10 511190 + 648 511191 Sb-119m 2.10360E-10 2.10360E-10 511191 + 649 511200 Sb-120 8.94760E-09 8.94760E-09 511200 + 650 511201 Sb-120m 1.26960E-08 1.26960E-08 511201 + 651 511210 Sb-121 2.36510E-07 1.79870E-04 51121.82c + 652 511220 Sb-122 5.92440E-07 1.26400E-06 511220 + 653 511221 Sb-122m 6.71560E-07 6.71560E-07 511221 + 654 511230 Sb-123 1.28210E-06 2.85900E-04 51123.82c + 655 511240 Sb-124 3.37860E-06 7.93660E-06 51124.82c + 656 511241 Sb-124m 2.58340E-06 6.07730E-06 511241 + 657 511242 Sb-124m 3.49400E-06 3.49400E-06 511242 + 658 511250 Sb-125 2.96490E-05 1.02510E-03 51125.82c + 659 511260 Sb-126 3.67830E-05 4.55700E-05 51126.82c + 660 511261 Sb-126m 2.71960E-05 6.27640E-05 511261 + 661 511262 Sb-126m 3.55680E-05 3.55680E-05 511262 + 662 511270 Sb-127 8.88850E-04 6.44810E-03 511270 + 663 511280 Sb-128 8.95520E-04 7.75050E-03 511280 + 664 511281 Sb-128m 1.52810E-03 1.52810E-03 511281 + 665 511290 Sb-129 4.93080E-03 8.65090E-03 511290 + 666 511291 Sb-129m 3.01320E-03 4.46090E-03 511291 + 667 511300 Sb-130 6.13650E-03 8.53920E-03 511300 + 668 511301 Sb-130m 6.13650E-03 7.39860E-03 511301 + 669 511310 Sb-131 1.95420E-02 2.14750E-02 511310 + 670 511320 Sb-132 6.85310E-03 7.45940E-03 511320 + 671 511321 Sb-132m 5.05090E-03 5.05090E-03 511321 + 672 511330 Sb-133 8.50410E-03 8.56980E-03 511330 + 673 511340 Sb-134 5.15010E-04 5.20480E-04 511340 + 674 511341 Sb-134m 1.20630E-03 1.20630E-03 511341 + 675 511350 Sb-135 3.88210E-04 3.88380E-04 511350 + 676 511360 Sb-136 3.57610E-05 3.57630E-05 511360 + 677 511370 Sb-137 7.15740E-06 7.15740E-06 511370 + 678 511380 Sb-138 2.08770E-08 2.08770E-08 511380 + 679 521200 Te-120 6.86440E-12 6.86440E-12 52120.82c + 680 521210 Te-121 4.73910E-11 1.84920E-10 521210 + 681 521211 Te-121m 1.55050E-10 1.55050E-10 521211 + 682 521240 Te-124 1.77340E-11 9.45590E-06 52124.82c + 683 521250 Te-125 4.49190E-10 1.02510E-03 52125.82c + 684 521251 Te-125m 1.46960E-09 2.29380E-04 521251 + 685 521260 Te-126 5.45700E-06 1.05000E-04 52126.82c + 686 521270 Te-127 6.93260E-06 6.44590E-03 521270 + 687 521271 Te-127m 1.67360E-05 1.07930E-03 52527.82c + 688 521280 Te-128 1.82710E-04 9.40620E-03 52128.82c + 689 521290 Te-129 1.91130E-04 1.10230E-02 521290 + 690 521291 Te-129m 4.61410E-04 5.60000E-03 52529.82c + 691 521300 Te-130 4.15510E-03 2.00930E-02 52130.82c + 692 521310 Te-131 3.47440E-03 2.53530E-02 521310 + 693 521311 Te-131m 8.38760E-03 1.01070E-02 521311 + 694 521320 Te-132 2.84730E-02 4.09830E-02 52132.82c + 695 521330 Te-133 9.65540E-03 2.10830E-02 521330 + 696 521331 Te-133m 2.33100E-02 2.47920E-02 521331 + 697 521340 Te-134 2.61120E-02 2.78990E-02 521340 + 698 521350 Te-135 9.14460E-03 9.47780E-03 521350 + 699 521360 Te-136 2.99530E-03 3.02860E-03 521360 + 700 521370 Te-137 4.89860E-04 4.93510E-04 521370 + 701 521380 Te-138 7.88390E-05 7.88600E-05 521380 + 702 521390 Te-139 4.95260E-06 4.95260E-06 521390 + 703 521400 Te-140 1.37230E-07 1.37230E-07 521400 + 704 521410 Te-141 1.96670E-09 1.96670E-09 521410 + 705 531270 I-127 1.02640E-09 6.47180E-03 53127.82c + 706 531280 I-128 6.89070E-08 6.89070E-08 531280 + 707 531290 I-129 6.05560E-06 1.31010E-02 53129.82c + 708 531300 I-130 4.61150E-05 6.26540E-05 53130.82c + 709 531301 I-130m 1.96890E-05 1.96890E-05 531301 + 710 531310 I-131 6.62910E-04 3.40000E-02 53131.82c + 711 531320 I-132 1.48210E-03 4.34050E-02 531320 + 712 531321 I-132m 1.09240E-03 1.09240E-03 531321 + 713 531330 I-133 1.00240E-02 5.76860E-02 531330 + 714 531331 I-133m 6.12570E-03 6.12570E-03 531331 + 715 531340 I-134 1.84030E-02 5.95540E-02 531340 + 716 531341 I-134m 1.35640E-02 1.35640E-02 531341 + 717 531350 I-135 6.14960E-02 7.09740E-02 53135.82c + 718 531360 I-136 9.73030E-03 1.27660E-02 531360 + 719 531361 I-136m 2.27910E-02 2.27980E-02 531361 + 720 531370 I-137 2.16730E-02 2.21570E-02 531370 + 721 531380 I-138 6.22530E-03 6.29920E-03 531380 + 722 531390 I-139 3.28030E-03 3.28520E-03 531390 + 723 531400 I-140 5.05180E-04 5.05320E-04 531400 + 724 531410 I-141 6.87200E-05 6.87220E-05 531410 + 725 531420 I-142 5.16750E-06 5.16750E-06 531420 + 726 531430 I-143 9.67010E-09 9.67010E-09 531430 + 727 541290 Xe-129 1.15020E-10 4.91350E-10 54129.82c + 728 541291 Xe-129m 3.76320E-10 3.76320E-10 541291 + 729 541300 Xe-130 3.13040E-08 6.58350E-05 54130.82c + 730 541310 Xe-131 8.64440E-07 3.40030E-02 54131.82c + 731 541311 Xe-131m 2.08690E-06 3.71390E-04 541311 + 732 541320 Xe-132 1.66900E-05 4.35930E-02 54132.82c + 733 541321 Xe-132m 1.89190E-05 1.89190E-05 541321 + 734 541330 Xe-133 9.95360E-05 5.80260E-02 54133.82c + 735 541331 Xe-133m 2.40290E-04 1.88230E-03 541331 + 736 541340 Xe-134 7.04680E-04 6.22210E-02 54134.82c + 737 541341 Xe-134m 1.65050E-03 1.96250E-03 541341 + 738 541350 Xe-135 2.91500E-03 8.08140E-02 54135.82c + 739 541351 Xe-135m 7.03730E-03 1.87540E-02 541351 + 740 541360 Xe-136 3.64710E-02 7.34760E-02 54136.82c + 741 541370 Xe-137 3.85220E-02 5.95720E-02 541370 + 742 541380 Xe-138 3.48910E-02 4.11780E-02 541380 + 743 541390 Xe-139 1.68490E-02 1.98590E-02 541390 + 744 541400 Xe-140 9.90660E-03 1.03790E-02 541400 + 745 541410 Xe-141 2.06000E-03 2.11560E-03 541410 + 746 541420 Xe-142 6.87010E-04 6.90890E-04 541420 + 747 541430 Xe-143 5.35850E-05 5.35910E-05 541430 + 748 541440 Xe-144 9.33220E-06 9.33220E-06 541440 + 749 541450 Xe-145 8.58590E-08 8.58590E-08 541450 + 750 541460 Xe-146 7.97720E-10 7.97720E-10 541460 + 751 551320 Cs-132 7.81210E-09 7.81210E-09 551320 + 752 551330 Cs-133 3.59100E-07 5.80260E-02 55133.82c + 753 551340 Cs-134 7.01490E-06 1.21850E-05 55134.82c + 754 551341 Cs-134m 5.17010E-06 5.17010E-06 551341 + 755 551350 Cs-135 1.32880E-04 8.11400E-02 55135.82c + 756 551351 Cs-135m 8.12010E-05 8.12010E-05 551351 + 757 551360 Cs-136 9.40450E-04 1.21600E-03 55136.82c + 758 551361 Cs-136m 5.51150E-04 5.51150E-04 551361 + 759 551370 Cs-137 1.24970E-02 7.20690E-02 55137.82c + 760 551380 Cs-138 1.16050E-02 6.61220E-02 551380 + 761 551381 Cs-138m 1.64670E-02 1.64670E-02 551381 + 762 551390 Cs-139 4.76520E-02 6.75110E-02 551390 + 763 551400 Cs-140 3.39050E-02 4.42850E-02 551400 + 764 551410 Cs-141 2.92100E-02 3.13270E-02 551410 + 765 551420 Cs-142 1.50320E-02 1.57210E-02 551420 + 766 551430 Cs-143 6.91540E-03 6.96870E-03 551430 + 767 551440 Cs-144 8.51050E-04 1.28560E-03 551440 + 768 551441 Cs-144m 8.51050E-04 8.51050E-04 551441 + 769 551450 Cs-145 4.64150E-04 4.64230E-04 551450 + 770 551460 Cs-146 5.88400E-05 5.88410E-05 551460 + 771 551470 Cs-147 1.01900E-05 1.01900E-05 551470 + 772 551480 Cs-148 4.77510E-09 4.77510E-09 551480 + 773 561340 Ba-134 2.09360E-09 1.21870E-05 56134.82c + 774 561350 Ba-135 4.32470E-08 1.47650E-07 56135.82c + 775 561351 Ba-135m 1.04400E-07 1.04400E-07 561351 + 776 561360 Ba-136 1.92300E-06 1.49800E-03 56136.82c + 777 561361 Ba-136m 4.50420E-06 4.50420E-06 561361 + 778 561370 Ba-137 3.06170E-05 7.21740E-02 56137.82c + 779 561371 Ba-137m 7.39130E-05 6.81070E-02 561371 + 780 561380 Ba-138 1.46170E-03 7.07120E-02 56138.82c + 781 561390 Ba-139 4.96150E-03 7.24730E-02 561390 + 782 561400 Ba-140 1.37600E-02 5.80450E-02 56140.82c + 783 561410 Ba-141 1.47860E-02 4.61130E-02 561410 + 784 561420 Ba-142 2.80930E-02 4.39280E-02 561420 + 785 561430 Ba-143 1.70620E-02 2.39580E-02 561430 + 786 561440 Ba-144 1.17870E-02 1.35230E-02 561440 + 787 561450 Ba-145 4.29470E-03 4.70090E-03 561450 + 788 561460 Ba-146 1.80210E-03 1.85550E-03 561460 + 789 561470 Ba-147 2.85950E-04 2.93240E-04 561470 + 790 561480 Ba-148 5.65520E-05 5.65560E-05 561480 + 791 561490 Ba-149 8.89390E-06 8.89390E-06 561490 + 792 561500 Ba-150 2.29990E-08 2.29990E-08 561500 + 793 561510 Ba-151 6.09240E-10 6.09240E-10 561510 + 794 571370 La-137 1.18300E-08 1.18300E-08 571370 + 795 571380 La-138 6.76990E-06 6.76990E-06 57138.82c + 796 571390 La-139 1.04360E-04 7.25770E-02 57139.82c + 797 571400 La-140 5.05190E-04 5.85500E-02 57140.82c + 798 571410 La-141 1.95620E-03 4.80690E-02 571410 + 799 571420 La-142 5.04830E-03 4.89760E-02 571420 + 800 571430 La-143 1.41660E-02 3.81240E-02 571430 + 801 571440 La-144 1.89010E-02 3.24240E-02 571440 + 802 571450 La-145 2.36170E-02 2.83180E-02 571450 + 803 571460 La-146 4.73780E-03 6.59330E-03 571460 + 804 571461 La-146m 8.52220E-03 8.52220E-03 571461 + 805 571470 La-147 9.76490E-03 1.00580E-02 571470 + 806 571480 La-148 3.37220E-03 3.42860E-03 571480 + 807 571490 La-149 1.14320E-03 1.15210E-03 571490 + 808 571500 La-150 2.03000E-04 2.03020E-04 571500 + 809 571510 La-151 2.65740E-05 2.65750E-05 571510 + 810 571520 La-152 2.54980E-06 2.54980E-06 571520 + 811 571530 La-153 1.42810E-09 1.42810E-09 571530 + 812 581390 Ce-139 8.09580E-10 2.76400E-09 581390 + 813 581391 Ce-139m 1.95440E-09 1.95440E-09 581391 + 814 581400 Ce-140 2.30790E-06 5.85530E-02 58140.82c + 815 581410 Ce-141 1.02300E-05 4.80800E-02 58141.82c + 816 581420 Ce-142 1.05820E-04 4.90820E-02 58142.82c + 817 581430 Ce-143 3.10450E-04 3.84340E-02 58143.82c + 818 581440 Ce-144 1.48050E-03 3.39050E-02 58144.82c + 819 581450 Ce-145 3.90600E-03 3.22240E-02 581450 + 820 581460 Ce-146 7.93610E-03 2.30520E-02 581460 + 821 581470 Ce-147 8.28290E-03 1.83410E-02 581470 + 822 581480 Ce-148 9.03800E-03 1.24830E-02 581480 + 823 581490 Ce-149 4.47750E-03 5.61890E-03 581490 + 824 581500 Ce-150 2.46670E-03 2.66420E-03 581500 + 825 581510 Ce-151 4.83980E-04 5.10710E-04 581510 + 826 581520 Ce-152 1.59770E-04 1.62170E-04 581520 + 827 581530 Ce-153 2.68440E-05 2.68450E-05 581530 + 828 581540 Ce-154 2.27900E-07 2.27900E-07 581540 + 829 581550 Ce-155 7.84010E-09 7.84010E-09 581550 + 830 581560 Ce-156 1.54930E-10 1.54930E-10 581560 + 831 591420 Pr-142 2.74840E-09 9.18600E-09 59142.82c + 832 591421 Pr-142m 6.43750E-09 6.43750E-09 591421 + 833 591430 Pr-143 4.47140E-06 3.84390E-02 59143.82c + 834 591440 Pr-144 1.89040E-06 3.39230E-02 591440 + 835 591441 Pr-144m 1.67900E-05 4.84660E-04 591441 + 836 591450 Pr-145 1.19060E-04 3.23430E-02 591450 + 837 591460 Pr-146 5.72620E-04 2.36240E-02 591460 + 838 591470 Pr-147 1.97820E-03 2.03200E-02 591470 + 839 591480 Pr-148 7.50750E-04 1.32330E-02 591480 + 840 591481 Pr-148m 3.15740E-03 3.15740E-03 591481 + 841 591490 Pr-149 6.85900E-03 1.24780E-02 591490 + 842 591500 Pr-150 6.43170E-03 9.09590E-03 591500 + 843 591510 Pr-151 5.87050E-03 6.38120E-03 591510 + 844 591520 Pr-152 3.30160E-03 3.46390E-03 591520 + 845 591530 Pr-153 1.74750E-03 1.77420E-03 591530 + 846 591540 Pr-154 3.17300E-04 3.17530E-04 591540 + 847 591550 Pr-155 6.98570E-05 6.98650E-05 591550 + 848 591560 Pr-156 1.30620E-05 1.30620E-05 591560 + 849 591570 Pr-157 1.39430E-08 1.39430E-08 591570 + 850 591580 Pr-158 1.91110E-10 1.91110E-10 591580 + 851 601440 Nd-144 1.11930E-09 3.39240E-02 60144.82c + 852 601450 Nd-145 5.84830E-08 3.23430E-02 60145.82c + 853 601460 Nd-146 1.78630E-06 2.36260E-02 60146.82c + 854 601470 Nd-147 1.61350E-05 2.03360E-02 60147.82c + 855 601480 Nd-148 1.10350E-04 1.65010E-02 60148.82c + 856 601490 Nd-149 3.67980E-04 1.28460E-02 601490 + 857 601500 Nd-150 1.01390E-03 1.01100E-02 60150.82c + 858 601510 Nd-151 1.52170E-03 7.90290E-03 601510 + 859 601520 Nd-152 2.66750E-03 6.13140E-03 601520 + 860 601530 Nd-153 2.53570E-03 4.30990E-03 601530 + 861 601540 Nd-154 1.59320E-03 1.91070E-03 601540 + 862 601550 Nd-155 5.87110E-04 6.57330E-04 601550 + 863 601560 Nd-156 2.01270E-04 2.13980E-04 601560 + 864 601570 Nd-157 3.60150E-05 3.60280E-05 601570 + 865 601580 Nd-158 3.87630E-06 3.87650E-06 601580 + 866 601590 Nd-159 5.22860E-08 5.22860E-08 601590 + 867 601600 Nd-160 6.46330E-10 6.46330E-10 601600 + 868 601610 Nd-161 1.67900E-11 1.67900E-11 601610 + 869 611470 Pm-147 3.30800E-09 2.03360E-02 61147.82c + 870 611480 Pm-148 2.64820E-07 2.95830E-07 61148.82c + 871 611481 Pm-148m 6.20260E-07 6.20260E-07 61548.82c + 872 611490 Pm-149 8.00280E-06 1.28540E-02 61149.82c + 873 611500 Pm-150 3.54270E-05 3.54270E-05 611500 + 874 611510 Pm-151 1.47630E-04 8.05050E-03 61151.82c + 875 611520 Pm-152 1.02660E-04 6.23410E-03 611520 + 876 611521 Pm-152m 2.05000E-04 2.05000E-04 611521 + 877 611522 Pm-152m 2.26750E-04 2.26750E-04 611522 + 878 611530 Pm-153 1.36370E-03 5.67360E-03 611530 + 879 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Sm-156 5.11150E-04 2.31330E-03 621560 + 899 621570 Sm-157 5.22890E-04 1.41000E-03 621570 + 900 621580 Sm-158 2.99630E-04 4.84150E-04 621580 + 901 621590 Sm-159 2.53590E-04 3.26060E-04 621590 + 902 621600 Sm-160 4.21060E-05 4.91230E-05 621600 + 903 621610 Sm-161 2.77770E-05 2.78170E-05 621610 + 904 621620 Sm-162 7.94030E-07 7.94860E-07 621620 + 905 621630 Sm-163 6.21610E-08 6.21740E-08 621630 + 906 621640 Sm-164 2.49680E-09 2.49680E-09 621640 + 907 621650 Sm-165 3.37280E-11 3.37280E-11 621650 + 908 631520 Eu-152 5.20590E-10 1.10120E-09 63152.82c + 909 631521 Eu-152m 1.23990E-10 1.23990E-10 631521 + 910 631522 Eu-152m 5.80620E-10 5.80620E-10 631522 + 911 631530 Eu-153 3.49230E-08 5.69860E-03 63153.82c + 912 631540 Eu-154 1.65670E-06 3.14910E-06 63154.82c + 913 631541 Eu-154m 1.49240E-06 1.49240E-06 631541 + 914 631550 Eu-155 1.31170E-05 2.90700E-03 63155.82c + 915 631560 Eu-156 5.44120E-05 2.36770E-03 63156.82c + 916 631570 Eu-157 1.74140E-04 1.58410E-03 63157.82c + 917 631580 Eu-158 1.52300E-04 6.36450E-04 631580 + 918 631590 Eu-159 3.52990E-04 6.79050E-04 631590 + 919 631600 Eu-160 1.86920E-04 2.36040E-04 631600 + 920 631610 Eu-161 1.41970E-04 1.69790E-04 631610 + 921 631620 Eu-162 4.81480E-05 4.89430E-05 631620 + 922 631630 Eu-163 1.15480E-05 1.16100E-05 631630 + 923 631640 Eu-164 5.57590E-06 5.57840E-06 631640 + 924 631650 Eu-165 2.88710E-08 2.89050E-08 631650 + 925 631660 Eu-166 3.60970E-09 3.60970E-09 631660 + 926 631670 Eu-167 3.05030E-11 3.05030E-11 631670 + 927 641540 Gd-154 1.20140E-10 3.14860E-06 64154.82c + 928 641550 Gd-155 1.54180E-09 2.90700E-03 64155.82c + 929 641551 Gd-155m 3.72210E-09 3.72210E-09 641551 + 930 641560 Gd-156 1.04500E-07 2.36780E-03 64156.82c + 931 641570 Gd-157 2.56190E-06 1.58670E-03 64157.82c + 932 641580 Gd-158 1.15970E-05 6.49660E-04 64158.82c + 933 641590 Gd-159 2.50880E-05 7.04130E-04 641590 + 934 641600 Gd-160 3.74260E-05 2.73470E-04 64160.82c + 935 641610 Gd-161 4.32070E-05 2.12990E-04 641610 + 936 641620 Gd-162 2.67480E-05 7.56910E-05 641620 + 937 641630 Gd-163 2.02090E-05 3.18190E-05 641630 + 938 641640 Gd-164 1.11510E-05 1.67290E-05 641640 + 939 641650 Gd-165 4.95990E-06 4.98880E-06 641650 + 940 641660 Gd-166 9.56180E-07 9.59790E-07 641660 + 941 641670 Gd-167 3.91510E-08 3.91810E-08 641670 + 942 641680 Gd-168 8.56090E-09 8.56090E-09 641680 + 943 641690 Gd-169 1.40860E-10 1.40860E-10 641690 + 944 651570 Tb-157 2.50910E-10 2.50910E-10 651570 + 945 651580 Tb-158 1.73910E-06 1.93370E-06 651580 + 946 651581 Tb-158m 1.95810E-07 1.95810E-07 651581 + 947 651590 Tb-159 9.58690E-08 7.04230E-04 65159.82c + 948 651600 Tb-160 2.33990E-06 2.33990E-06 65160.82c + 949 651610 Tb-161 3.08620E-06 2.16080E-04 651610 + 950 651620 Tb-162 5.34970E-06 8.10410E-05 651620 + 951 651630 Tb-163 2.02090E-05 5.20280E-05 651630 + 952 651640 Tb-164 2.23030E-05 3.90320E-05 651640 + 953 651650 Tb-165 7.43980E-06 1.24290E-05 651650 + 954 651660 Tb-166 1.38030E-05 1.47630E-05 651660 + 955 651670 Tb-167 1.69780E-06 1.73700E-06 651670 + 956 651680 Tb-168 7.64620E-07 7.73180E-07 651680 + 957 651690 Tb-169 3.28710E-08 3.30120E-08 651690 + 958 651700 Tb-170 5.20000E-09 5.20000E-09 651700 + 959 651710 Tb-171 2.09840E-10 2.09840E-10 651710 + 960 661590 Dy-159 2.74470E-11 2.74470E-11 661590 + 961 661600 Dy-160 4.24750E-10 2.34030E-06 66160.82c + 962 661610 Dy-161 1.12740E-08 2.16090E-04 66161.82c + 963 661620 Dy-162 6.15900E-08 8.11020E-05 66162.82c + 964 661630 Dy-163 4.72460E-07 5.25010E-05 66163.82c + 965 661640 Dy-164 1.88200E-06 4.09170E-05 66164.82c + 966 661650 Dy-165 2.28770E-06 1.50580E-05 661650 + 967 661651 Dy-165m 3.49720E-07 3.49720E-07 661651 + 968 661660 Dy-166 2.76070E-06 1.75230E-05 661660 + 969 661670 Dy-167 2.68680E-06 4.42380E-06 661670 + 970 661680 Dy-168 5.52550E-06 6.29870E-06 661680 + 971 661690 Dy-169 1.03560E-06 1.06860E-06 661690 + 972 661700 Dy-170 3.97990E-07 4.03190E-07 661700 + 973 661710 Dy-171 7.49240E-08 7.51340E-08 661710 + 974 661720 Dy-172 6.47500E-09 6.47500E-09 661720 + 975 661730 Dy-173 4.40190E-10 4.40190E-10 661730 + 976 671620 Ho-162 4.46380E-12 1.09460E-11 671620 + 977 671621 Ho-162m 1.04550E-11 1.04550E-11 671621 + 978 671630 Ho-163 2.74050E-10 3.15950E-10 671630 + 979 671631 Ho-163m 4.18950E-11 4.18950E-11 671631 + 980 671640 Ho-164 1.83460E-09 6.13160E-09 671640 + 981 671641 Ho-164m 4.29700E-09 4.29700E-09 671641 + 982 671650 Ho-165 2.21040E-08 1.50880E-05 67165.82c + 983 671660 Ho-166 8.12360E-08 1.76050E-05 671660 + 984 671661 Ho-166m 1.90270E-07 1.90270E-07 671661 + 985 671670 Ho-167 1.69780E-06 6.12160E-06 671670 + 986 671680 Ho-168 1.14210E-06 9.05330E-06 671680 + 987 671681 Ho-168m 1.62060E-06 1.62060E-06 671681 + 988 671690 Ho-169 1.88710E-06 2.95570E-06 671690 + 989 671700 Ho-170 7.73820E-07 7.73820E-07 671700 + 990 671701 Ho-170m 3.30380E-07 7.33570E-07 671701 + 991 671710 Ho-171 4.61010E-07 5.36140E-07 671710 + 992 671720 Ho-172 1.71220E-07 1.77700E-07 671720 + 993 671730 Ho-173 2.90660E-08 2.95060E-08 671730 + 994 671740 Ho-174 4.92690E-09 4.92690E-09 671740 + 995 671750 Ho-175 3.57380E-10 3.57380E-10 671750 + 996 681640 Er-164 1.30520E-12 3.17130E-09 68164.82c + 997 681650 Er-165 2.21640E-11 2.21640E-11 681650 + 998 681660 Er-166 7.41100E-10 1.76050E-05 68166.82c + 999 681670 Er-167 2.61780E-09 6.12460E-06 68167.82c + 1000 681671 Er-167m 4.00190E-10 7.31880E-07 681671 + 1001 681680 Er-168 6.46660E-08 9.12610E-06 68168.82c + 1002 681690 Er-169 1.05510E-07 3.06120E-06 681690 + 1003 681700 Er-170 3.50190E-07 1.85760E-06 68170.82c + 1004 681710 Er-171 5.67590E-07 1.10370E-06 681710 + 1005 681720 Er-172 4.43010E-07 6.20700E-07 681720 + 1006 681730 Er-173 2.96360E-07 3.25870E-07 681730 + 1007 681740 Er-174 1.14780E-07 1.19710E-07 681740 + 1008 681750 Er-175 3.68730E-08 3.72300E-08 681750 + 1009 681760 Er-176 5.09560E-09 5.09560E-09 681760 + 1010 681770 Er-177 5.53290E-10 5.53290E-10 681770 + 1011 691680 Tm-168 5.83360E-11 5.83360E-11 691680 + 1012 691690 Tm-169 2.54140E-10 3.06150E-06 691690 + 1013 691700 Tm-170 3.95650E-09 3.95650E-09 691700 + 1014 691710 Tm-171 1.56850E-08 1.11940E-06 691710 + 1015 691720 Tm-172 5.13820E-08 6.72090E-07 691720 + 1016 691730 Tm-173 7.47140E-08 4.00580E-07 691730 + 1017 691740 Tm-174 1.11020E-07 2.30730E-07 691740 + 1018 691750 Tm-175 7.56530E-08 1.12880E-07 691750 + 1019 691760 Tm-176 4.22720E-08 4.73680E-08 691760 + 1020 691770 Tm-177 1.08180E-08 1.13710E-08 691770 + 1021 691780 Tm-178 2.80710E-09 2.80710E-09 691780 + 1022 691790 Tm-179 3.24820E-10 3.24820E-10 691790 + 1023 701700 Yb-170 2.94730E-12 3.95430E-09 701700 + 1024 701710 Yb-171 7.65010E-12 1.11950E-06 701710 + 1025 701711 Yb-171m 5.00430E-11 5.00430E-11 701711 + 1026 701720 Yb-172 4.96030E-10 6.72580E-07 701720 + 1027 701730 Yb-173 3.30430E-09 4.03890E-07 701730 + 1028 701740 Yb-174 1.16590E-08 2.42420E-07 701740 + 1029 701750 Yb-175 2.80620E-08 1.45230E-07 701750 + 1030 701751 Yb-175m 4.28990E-09 9.12100E-08 701751 + 1031 701760 Yb-176 1.37520E-08 8.10150E-08 701760 + 1032 701761 Yb-176m 2.47370E-08 4.84210E-08 701761 + 1033 701770 Yb-177 3.06520E-08 4.91110E-08 701770 + 1034 701771 Yb-177m 7.08760E-09 1.84590E-08 701771 + 1035 701780 Yb-178 2.11650E-08 2.39720E-08 701780 + 1036 701790 Yb-179 1.02020E-08 1.05270E-08 701790 + 1037 701800 Yb-180 2.42600E-09 2.42600E-09 701800 + 1038 701810 Yb-181 4.56360E-10 4.56360E-10 701810 + 1039 711730 Lu-173 2.20540E-12 2.20540E-12 711730 + 1040 711740 Lu-174 1.13280E-11 3.77080E-11 711740 + 1041 711741 Lu-174m 2.65340E-11 2.65340E-11 711741 + 1042 711750 Lu-175 2.70240E-10 1.45510E-07 71175.82c + 1043 711760 Lu-176 9.21570E-10 5.76360E-09 71176.82c + 1044 711761 Lu-176m 5.12330E-10 5.12330E-10 711761 + 1045 711770 Lu-177 2.30600E-09 5.16240E-08 711770 + 1046 711771 Lu-177m 9.01480E-10 9.16040E-10 711771 + 1047 711772 Lu-177m 2.91320E-11 2.91320E-11 711772 + 1048 711780 Lu-178 3.37210E-09 2.73440E-08 711780 + 1049 711781 Lu-178m 3.82240E-09 3.82240E-09 711781 + 1050 711790 Lu-179 6.32960E-09 1.78240E-08 711790 + 1051 711791 Lu-179m 9.67610E-10 1.14940E-08 711791 + 1052 711800 Lu-180 1.93220E-09 5.53510E-09 711800 + 1053 711801 Lu-180m 1.93220E-09 4.35820E-09 711801 + 1054 711802 Lu-180m 2.84770E-09 2.84770E-09 711802 + 1055 711810 Lu-181 2.79950E-09 3.25590E-09 711810 + 1056 711820 Lu-182 1.03930E-09 1.03930E-09 711820 + 1057 711830 Lu-183 1.76460E-10 1.76460E-10 711830 + 1058 711840 Lu-184 2.99350E-11 2.99350E-11 711840 + 1059 721760 Hf-176 3.89800E-12 5.15740E-10 72176.82c + 1060 721770 Hf-177 3.00070E-11 5.23900E-08 72177.82c + 1061 721771 Hf-177m 1.16590E-11 7.35690E-10 721771 + 1062 721772 Hf-177m 4.50690E-13 1.50170E-11 721772 + 1063 721780 Hf-178 8.40580E-11 3.14020E-08 72178.82c + 1064 721781 Hf-178m 1.38690E-10 3.97360E-09 721781 + 1065 721782 Hf-178m 1.25160E-11 1.25160E-11 721782 + 1066 721790 Hf-179 6.21570E-10 1.88600E-08 72179.82c + 1067 721791 Hf-179m 1.94030E-10 1.94030E-10 721791 + 1068 721792 Hf-179m 2.17590E-10 2.17590E-10 721792 + 1069 721800 Hf-180 7.58300E-10 1.12610E-08 72180.82c + 1070 721801 Hf-180m 1.36400E-09 2.78780E-09 721801 + 1071 721810 Hf-181 3.43690E-09 6.69280E-09 721810 + 1072 721820 Hf-182 9.58060E-10 2.72120E-09 721820 + 1073 721821 Hf-182m 1.72330E-09 1.72330E-09 721821 + 1074 721830 Hf-183 1.79380E-09 1.97030E-09 721830 + 1075 721840 Hf-184 2.48390E-10 2.63360E-10 721840 + 1076 721841 Hf-184m 4.46800E-10 4.61770E-10 721841 + 1077 721850 Hf-185 2.23540E-10 2.23540E-10 721850 + 1078 721860 Hf-186 3.09320E-11 3.09320E-11 721860 + 1079 721870 Hf-187 3.36260E-12 3.36260E-12 721870 + 1080 731790 Ta-179 1.88210E-12 2.48020E-12 731790 + 1081 731800 Ta-180 1.12010E-11 1.12010E-11 731800 + 1082 731801 Ta-180m 1.26970E-11 2.13390E-11 731801 + 1083 731810 Ta-181 9.46730E-11 6.78740E-09 73181.82c + 1084 731820 Ta-182 1.10790E-10 1.30960E-09 73182.82c + 1085 731821 Ta-182m 1.13080E-10 1.19880E-09 731821 + 1086 731822 Ta-182m 8.62000E-11 1.08570E-09 731822 + 1087 731830 Ta-183 4.50950E-10 2.42120E-09 731830 + 1088 731840 Ta-184 6.70530E-10 1.39570E-09 731840 + 1089 731850 Ta-185 3.08090E-10 6.80850E-10 731850 + 1090 731851 Ta-185m 1.49220E-10 1.49220E-10 731851 + 1091 731860 Ta-186 2.55810E-10 2.86740E-10 731860 + 1092 731870 Ta-187 6.55360E-11 6.88990E-11 731870 + 1093 731880 Ta-188 1.70230E-11 1.70230E-11 731880 + 1094 731890 Ta-189 1.97160E-12 1.97160E-12 731890 + 1095 741820 W-182 2.98320E-12 1.31260E-09 74182.82c + 1096 741830 W-183 4.65370E-12 2.44110E-09 74183.82c + 1097 741831 W-183m 1.52250E-11 9.75460E-11 741831 + 1098 741840 W-184 7.02040E-11 1.46590E-09 74184.82c + 1099 741850 W-185 5.71130E-11 8.75840E-10 741850 + 1100 741851 W-185m 1.37880E-10 1.37880E-10 741851 + 1101 741860 W-186 1.75610E-10 5.19250E-10 74186.82c + 1102 741861 W-186m 5.66480E-11 5.66480E-11 741861 + 1103 741870 W-187 2.27980E-10 2.96880E-10 741870 + 1104 741880 W-188 1.27970E-10 1.44990E-10 741880 + 1105 741890 W-189 6.17280E-11 6.37000E-11 741890 + 1106 741900 W-190 6.89080E-12 1.47020E-11 741900 + 1107 741901 W-190m 7.81120E-12 7.81120E-12 741901 + 1108 741910 W-191 2.76970E-12 2.76970E-12 741910 + 1109 751850 Re-185 1.62340E-12 8.77460E-10 75185.82c + 1110 751860 Re-186 3.56580E-12 3.56580E-12 751860 + 1111 751861 Re-186m 5.05970E-12 5.05970E-12 751861 + 1112 751870 Re-187 1.94950E-11 3.16370E-10 75187.82c + 1113 751880 Re-188 1.29780E-11 1.88370E-10 751880 + 1114 751881 Re-188m 3.03980E-11 3.03980E-11 751881 + 1115 751890 Re-189 4.40310E-11 1.07730E-10 751890 + 1116 751900 Re-190 1.44900E-11 4.10760E-11 751900 + 1117 751901 Re-190m 2.60630E-11 2.60630E-11 751901 + 1118 751910 Re-191 1.69380E-11 1.97080E-11 751910 + 1119 751920 Re-192 6.29450E-12 6.29450E-12 751920 + 1120 751930 Re-193 1.06980E-12 1.06980E-12 751930 + 1121 761880 Os-188 1.41380E-12 1.89780E-10 761880 + 1122 761890 Os-189 1.45500E-12 1.13950E-10 761890 + 1123 761891 Os-189m 4.76020E-12 1.58380E-11 761891 + 1124 761900 Os-190 5.99330E-12 6.80420E-11 761900 + 1125 761901 Os-190m 6.79370E-12 2.09720E-11 761901 + 1126 761910 Os-191 1.58820E-11 4.04450E-11 761910 + 1127 761911 Os-191m 4.85450E-12 4.85450E-12 761911 + 1128 761920 Os-192 7.59010E-12 2.15130E-11 761920 + 1129 761921 Os-192m 8.60390E-12 8.60390E-12 761921 + 1130 761930 Os-193 1.08430E-11 1.19130E-11 761930 + 1131 761940 Os-194 4.20730E-12 4.20730E-12 761940 + 1132 761950 Os-195 1.35460E-12 1.35460E-12 761950 + 1133 771920 Ir-192 6.22270E-13 2.98520E-12 771920 + 1134 771922 Ir-192m 6.22270E-13 1.74080E-12 771922 + 1135 771930 Ir-193 7.96160E-13 1.46310E-11 77193.82c + 1136 771931 Ir-193m 1.92200E-12 1.96340E-12 771931 + 1137 771940 Ir-194 1.34870E-12 6.90480E-12 771940 + 1138 771941 Ir-194m 1.34870E-12 1.34870E-12 771941 + 1139 771942 Ir-194m 1.34870E-12 1.34870E-12 771942 + 1140 771950 Ir-195 8.09340E-13 2.26160E-12 771950 + 1141 771951 Ir-195m 1.95390E-12 1.95390E-12 771951 + 1142 781950 Pt-195 3.44070E-13 5.29250E-12 781950 + 1143 781951 Pt-195m 8.30630E-13 1.42460E-12 781951 + 1144 781960 Pt-196 1.40120E-12 2.94880E-12 781960 + + Neutron-induced fission: + + Interpolation region : 2 / 2 + Interpolation energy : 4.00000E-01 MeV + Number of products : 1155 / 1203 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 3.74900E-05 3.74900E-05 1001.82c + 2 10020 H-2 1.14570E-05 1.14570E-05 1002.82c + 3 10030 H-3 1.65000E-04 1.65000E-04 1003.82c + 4 20040 He-4 2.37000E-03 2.37000E-03 2004.82c + 5 190500 K-50 1.01300E-12 1.01300E-12 190500 + 6 200500 Ca-50 8.49820E-12 9.21740E-12 200500 + 7 200510 Ca-51 1.16620E-11 1.16620E-11 200510 + 8 200520 Ca-52 7.80820E-12 7.80820E-12 200520 + 9 200530 Ca-53 3.97850E-12 3.97850E-12 200530 + 10 210500 Sc-50 2.31440E-12 1.22550E-11 210500 + 11 210501 Sc-50m 8.49080E-13 1.00660E-11 210501 + 12 210510 Sc-51 9.47580E-12 2.12940E-11 210510 + 13 210520 Sc-52 2.43930E-11 3.32390E-11 210520 + 14 210530 Sc-53 2.88530E-11 3.16380E-11 210530 + 15 210540 Sc-54 2.97820E-11 2.97820E-11 210540 + 16 210550 Sc-55 1.43290E-11 1.43290E-11 210550 + 17 210560 Sc-56 6.47030E-12 6.47030E-12 210560 + 18 210570 Sc-57 1.25750E-12 1.25750E-12 210570 + 19 220510 Ti-51 1.47270E-12 2.27670E-11 220510 + 20 220520 Ti-52 8.74600E-12 4.19850E-11 220520 + 21 220530 Ti-53 3.96440E-11 7.12820E-11 220530 + 22 220540 Ti-54 8.94320E-11 1.19210E-10 220540 + 23 220550 Ti-55 1.69220E-10 1.83550E-10 220550 + 24 220560 Ti-56 1.83350E-10 1.90230E-10 220560 + 25 220570 Ti-57 1.58260E-10 1.59100E-10 220570 + 26 220580 Ti-58 5.92100E-11 5.92100E-11 220580 + 27 220590 Ti-59 1.68820E-11 1.68820E-11 220590 + 28 220600 Ti-60 2.56450E-12 2.56450E-12 220600 + 29 230530 V-53 1.28500E-12 7.25670E-11 230530 + 30 230540 V-54 1.19730E-11 1.31190E-10 230540 + 31 230550 V-55 5.08260E-11 2.34370E-10 230550 + 32 230560 V-56 2.08970E-10 3.99680E-10 230560 + 33 230570 V-57 3.99540E-10 5.58170E-10 230570 + 34 230580 V-58 6.05660E-10 6.64870E-10 230580 + 35 230590 V-59 4.28580E-10 4.45460E-10 230590 + 36 230600 V-60 2.97580E-10 3.00140E-10 230600 + 37 230610 V-61 9.33340E-11 9.33340E-11 230610 + 38 230620 V-62 2.28560E-11 2.28560E-11 230620 + 39 230630 V-63 2.32370E-12 2.32370E-12 230630 + 40 240550 Cr-55 2.61580E-12 2.36990E-10 240550 + 41 240560 Cr-56 2.63210E-11 4.28240E-10 240560 + 42 240570 Cr-57 2.01240E-10 1.28910E-09 240570 + 43 240580 Cr-58 6.71040E-10 8.04010E-10 240580 + 44 240590 Cr-59 1.80660E-09 2.25210E-09 240590 + 45 240600 Cr-60 2.84490E-09 3.15060E-09 240600 + 46 240610 Cr-61 3.73780E-09 3.82550E-09 240610 + 47 240620 Cr-62 2.34520E-09 2.36890E-09 240620 + 48 240630 Cr-63 1.11720E-09 1.11870E-09 240630 + 49 240640 Cr-64 2.54970E-10 2.54970E-10 240640 + 50 240650 Cr-65 4.44890E-11 4.44890E-11 240650 + 51 240660 Cr-66 3.95200E-12 3.95200E-12 240660 + 52 250570 Mn-57 2.10140E-12 1.29120E-09 250570 + 53 250580 Mn-58 2.79650E-11 8.31980E-10 250580 + 54 250581 Mn-58m 2.74890E-12 2.74890E-12 250581 + 55 250590 Mn-59 1.95650E-10 2.44770E-09 250590 + 56 250600 Mn-60 1.07310E-10 3.38350E-09 250600 + 57 250601 Mn-60m 1.09170E-09 1.09170E-09 250601 + 58 250610 Mn-61 3.43570E-09 7.26120E-09 250610 + 59 250620 Mn-62 7.19620E-09 8.38060E-09 250620 + 60 250621 Mn-62m 1.12690E-09 2.31140E-09 250621 + 61 250630 Mn-63 9.26930E-09 1.03880E-08 250630 + 62 250640 Mn-64 9.16500E-09 9.42000E-09 250640 + 63 250650 Mn-65 4.21510E-09 4.25960E-09 250650 + 64 250660 Mn-66 1.79030E-09 1.79430E-09 250660 + 65 250670 Mn-67 3.25330E-10 3.25330E-10 250670 + 66 250680 Mn-68 1.44190E-10 1.44190E-10 250680 + 67 250690 Mn-69 5.66460E-12 5.66460E-12 250690 + 68 260590 Fe-59 3.16210E-12 2.45090E-09 260590 + 69 260600 Fe-60 5.01830E-11 4.39980E-09 260600 + 70 260610 Fe-61 6.09860E-10 7.87110E-09 260610 + 71 260620 Fe-62 3.38570E-09 1.40780E-08 260620 + 72 260630 Fe-63 1.44030E-08 2.47910E-08 260630 + 73 260640 Fe-64 3.11850E-08 4.06050E-08 260640 + 74 260650 Fe-65 5.67490E-08 6.10090E-08 260650 + 75 260660 Fe-66 5.82730E-08 6.00670E-08 260660 + 76 260670 Fe-67 4.73390E-08 4.76640E-08 260670 + 77 260680 Fe-68 5.66670E-08 5.68130E-08 260680 + 78 260690 Fe-69 1.08140E-08 1.08180E-08 260690 + 79 260700 Fe-70 6.49330E-10 6.49330E-10 260700 + 80 260710 Fe-71 3.14220E-11 3.14220E-11 260710 + 81 270610 Co-61 1.95540E-12 7.87300E-09 270610 + 82 270620 Co-62 1.34440E-11 1.40920E-08 270620 + 83 270621 Co-62m 3.66450E-11 3.66450E-11 270621 + 84 270630 Co-63 5.35150E-10 2.53260E-08 270630 + 85 270640 Co-64 4.75030E-09 4.53550E-08 270640 + 86 270650 Co-65 1.92930E-08 8.03020E-08 270650 + 87 270660 Co-66 7.51410E-08 1.35210E-07 270660 + 88 270670 Co-67 1.35820E-07 1.83480E-07 270670 + 89 270680 Co-68 3.79880E-07 5.50440E-07 270680 + 90 270681 Co-68m 2.83550E-07 3.41120E-07 270681 + 91 270690 Co-69 3.16500E-07 3.26560E-07 270690 + 92 270700 Co-70 4.36870E-08 4.36870E-08 270700 + 93 270701 Co-70m 4.36870E-08 4.43360E-08 270701 + 94 270710 Co-71 1.16580E-08 1.16890E-08 270710 + 95 270720 Co-72 1.61970E-09 1.61970E-09 270720 + 96 270730 Co-73 1.09710E-10 1.09710E-10 270730 + 97 270740 Co-74 4.31530E-11 4.31530E-11 270740 + 98 270750 Co-75 1.16950E-12 1.16950E-12 270750 + 99 280630 Ni-63 2.60440E-12 2.53290E-08 280630 + 100 280640 Ni-64 6.26370E-11 4.54180E-08 28064.82c + 101 280650 Ni-65 1.14200E-09 8.14440E-08 280650 + 102 280660 Ni-66 1.08050E-08 1.46010E-07 280660 + 103 280670 Ni-67 7.75880E-08 2.61070E-07 280670 + 104 280680 Ni-68 1.58500E-06 2.30930E-06 280680 + 105 280690 Ni-69 9.15700E-07 1.23900E-06 280690 + 106 280691 Ni-69m 9.15700E-07 9.15700E-07 280691 + 107 280700 Ni-70 9.52690E-07 1.04070E-06 280700 + 108 280710 Ni-71 5.36510E-07 5.48200E-07 280710 + 109 280720 Ni-72 1.92240E-07 1.93860E-07 280720 + 110 280730 Ni-73 6.12970E-08 6.14070E-08 280730 + 111 280740 Ni-74 6.75000E-08 6.75430E-08 280740 + 112 280750 Ni-75 1.09040E-08 1.09050E-08 280750 + 113 280760 Ni-76 1.06610E-09 1.06610E-09 280760 + 114 280770 Ni-77 5.32590E-11 5.32590E-11 280770 + 115 290650 Cu-65 1.08350E-12 8.14450E-08 29065.82c + 116 290660 Cu-66 4.92100E-11 1.46060E-07 290660 + 117 290670 Cu-67 9.34870E-10 2.62010E-07 290670 + 118 290680 Cu-68 1.17000E-08 2.34780E-06 290680 + 119 290681 Cu-68m 3.18920E-08 3.18920E-08 290681 + 120 290690 Cu-69 1.86250E-07 2.34100E-06 290690 + 121 290700 Cu-70 3.07630E-08 2.53990E-07 290700 + 122 290701 Cu-70m 3.92870E-07 4.46450E-07 290701 + 123 290702 Cu-70m 3.07630E-08 1.07150E-06 290702 + 124 290710 Cu-71 5.58020E-07 1.10620E-06 290710 + 125 290720 Cu-72 7.75570E-07 9.69430E-07 290720 + 126 290730 Cu-73 5.82380E-07 6.43790E-07 290730 + 127 290740 Cu-74 2.79850E-06 2.86620E-06 290740 + 128 290750 Cu-75 1.19840E-06 1.20910E-06 290750 + 129 290760 Cu-76 2.81200E-07 2.81730E-07 290760 + 130 290761 Cu-76m 2.81200E-07 2.81730E-07 290761 + 131 290770 Cu-77 8.21790E-08 8.22320E-08 290770 + 132 290780 Cu-78 1.24470E-08 1.24470E-08 290780 + 133 290790 Cu-79 6.81950E-10 6.81950E-10 290790 + 134 290800 Cu-80 3.41460E-11 3.41460E-11 290800 + 135 300670 Zn-67 1.32710E-12 2.62010E-07 300670 + 136 300680 Zn-68 1.73440E-10 2.35300E-06 300680 + 137 300690 Zn-69 5.83850E-10 2.34440E-06 300690 + 138 300691 Zn-69m 2.89980E-09 2.89980E-09 300691 + 139 300700 Zn-70 2.18660E-08 1.51700E-06 300700 + 140 300710 Zn-71 2.07670E-07 1.31390E-06 300710 + 141 300711 Zn-71m 1.03140E-06 1.03140E-06 300711 + 142 300720 Zn-72 1.36970E-06 2.33910E-06 300720 + 143 300730 Zn-73 1.44570E-07 1.64040E-06 300730 + 144 300731 Zn-73m 1.99960E-07 8.52030E-07 300731 + 145 300732 Zn-73m 1.30410E-06 1.30410E-06 300732 + 146 300740 Zn-74 1.49350E-05 1.78430E-05 300740 + 147 300750 Zn-75 1.61230E-05 1.72980E-05 300750 + 148 300760 Zn-76 2.43390E-05 2.48940E-05 300760 + 149 300770 Zn-77 1.10090E-05 1.18240E-05 300770 + 150 300771 Zn-77m 1.46580E-06 1.46580E-06 300771 + 151 300780 Zn-78 1.91660E-05 1.91790E-05 300780 + 152 300790 Zn-79 1.52890E-06 1.52920E-06 300790 + 153 300800 Zn-80 2.05400E-07 2.05430E-07 300800 + 154 300810 Zn-81 1.61340E-08 1.61340E-08 300810 + 155 300820 Zn-82 5.76090E-10 5.76090E-10 300820 + 156 310700 Ga-70 2.95510E-11 2.95510E-11 310700 + 157 310710 Ga-71 4.20390E-10 2.34570E-06 310710 + 158 310720 Ga-72 5.55780E-09 2.34520E-06 310720 + 159 310721 Ga-72m 5.46320E-10 7.84870E-08 310721 + 160 310730 Ga-73 4.35430E-08 2.33600E-06 310730 + 161 310740 Ga-74 9.34750E-07 1.50190E-05 310740 + 162 310741 Ga-74m 9.34750E-07 1.87780E-05 310741 + 163 310750 Ga-75 6.90790E-06 2.42060E-05 310750 + 164 310760 Ga-76 2.18910E-05 4.67850E-05 310760 + 165 310770 Ga-77 4.49050E-05 5.74620E-05 310770 + 166 310780 Ga-78 4.92830E-05 6.84820E-05 310780 + 167 310790 Ga-79 6.61330E-05 6.76420E-05 310790 + 168 310800 Ga-80 3.44200E-05 3.46270E-05 310800 + 169 310810 Ga-81 1.09620E-05 1.09770E-05 310810 + 170 310820 Ga-82 1.26520E-06 1.26580E-06 310820 + 171 310830 Ga-83 1.09750E-07 1.09750E-07 310830 + 172 310840 Ga-84 7.34410E-09 7.34410E-09 310840 + 173 310850 Ga-85 1.08350E-10 1.08350E-10 310850 + 174 320720 Ge-72 7.11370E-12 2.34520E-06 32072.82c + 175 320730 Ge-73 2.05020E-10 2.33620E-06 32073.82c + 176 320731 Ge-73m 4.12800E-11 2.30170E-06 320731 + 177 320740 Ge-74 2.85150E-08 1.97420E-05 32074.82c + 178 320750 Ge-75 2.70550E-07 2.65080E-05 320750 + 179 320751 Ge-75m 2.03200E-06 3.00030E-06 320751 + 180 320760 Ge-76 1.21580E-05 5.89430E-05 32076.82c + 181 320770 Ge-77 3.07910E-05 4.24880E-05 320770 + 182 320771 Ge-77m 4.09970E-06 6.15620E-05 320771 + 183 320780 Ge-78 1.14800E-04 1.83340E-04 320780 + 184 320790 Ge-79 2.65070E-05 1.01950E-04 320790 + 185 320791 Ge-79m 1.99080E-04 1.99180E-04 320791 + 186 320800 Ge-80 4.39020E-04 4.74950E-04 320800 + 187 320810 Ge-81 2.95700E-04 3.01590E-04 320810 + 188 320811 Ge-81m 5.95380E-05 6.42370E-05 320811 + 189 320820 Ge-82 2.96620E-04 2.97660E-04 320820 + 190 320830 Ge-83 7.01810E-05 7.02550E-05 320830 + 191 320840 Ge-84 1.65800E-05 1.65820E-05 320840 + 192 320850 Ge-85 1.46060E-06 1.46070E-06 320850 + 193 320860 Ge-86 8.24640E-08 8.24640E-08 320860 + 194 320870 Ge-87 3.68070E-09 3.68070E-09 320870 + 195 330740 As-74 1.10850E-11 1.10850E-11 330740 + 196 330750 As-75 1.11280E-10 2.65090E-05 33075.82c + 197 330751 As-75m 4.21400E-10 1.32150E-09 330751 + 198 330760 As-76 2.66020E-08 2.66020E-08 330760 + 199 330770 As-77 4.06130E-07 9.27590E-05 330770 + 200 330780 As-78 1.09410E-05 1.94280E-04 330780 + 201 330790 As-79 4.39870E-05 3.37160E-04 330790 + 202 330800 As-80 1.52960E-04 6.27910E-04 330800 + 203 330810 As-81 4.13530E-04 7.78710E-04 330810 + 204 330820 As-82 1.35330E-04 4.32990E-04 330820 + 205 330821 As-82m 4.71550E-04 4.71550E-04 330821 + 206 330830 As-83 9.32700E-04 1.00480E-03 330830 + 207 330840 As-84 2.22750E-04 2.30250E-04 330840 + 208 330841 As-84m 2.22750E-04 2.30250E-04 330841 + 209 330850 As-85 2.29920E-04 2.31180E-04 330850 + 210 330860 As-86 4.51070E-05 4.51890E-05 330860 + 211 330870 As-87 1.17440E-05 1.17480E-05 330870 + 212 330880 As-88 3.55090E-07 3.55090E-07 330880 + 213 330890 As-89 2.49190E-08 2.49190E-08 330890 + 214 330900 As-90 6.29200E-10 6.29200E-10 330900 + 215 340760 Se-76 9.78060E-12 2.66120E-08 34076.82c + 216 340770 Se-77 7.92680E-11 9.27600E-05 34077.82c + 217 340771 Se-77m 5.95350E-10 5.95350E-10 340771 + 218 340780 Se-78 2.99930E-08 1.94310E-04 34078.82c + 219 340790 Se-79 7.47350E-07 3.37820E-04 34079.82c + 220 340791 Se-79m 9.95060E-08 3.29270E-04 340791 + 221 340800 Se-80 1.87170E-05 6.46630E-04 34080.82c + 222 340810 Se-81 1.82850E-05 9.34240E-04 340810 + 223 340811 Se-81m 1.37340E-04 1.65290E-04 340811 + 224 340820 Se-82 5.19860E-04 1.42440E-03 34082.82c + 225 340830 Se-83 1.03090E-03 1.39300E-03 340830 + 226 340831 Se-83m 2.07570E-04 8.50930E-04 340831 + 227 340840 Se-84 2.85130E-03 3.36200E-03 340840 + 228 340850 Se-85 2.68530E-03 2.88050E-03 340850 + 229 340860 Se-86 2.49260E-03 2.52470E-03 340860 + 230 340870 Se-87 1.13880E-03 1.14870E-03 340870 + 231 340880 Se-88 2.36480E-04 2.36830E-04 340880 + 232 340890 Se-89 6.47690E-05 6.47940E-05 340890 + 233 340900 Se-90 1.20560E-05 1.20570E-05 340900 + 234 340910 Se-91 2.76440E-07 2.76440E-07 340910 + 235 340920 Se-92 7.19150E-09 7.19150E-09 340920 + 236 350780 Br-78 5.14950E-12 5.14950E-12 350780 + 237 350790 Br-79 5.66600E-11 1.84660E-07 35079.82c + 238 350791 Br-79m 2.14570E-10 2.14570E-10 350791 + 239 350800 Br-80 4.17660E-09 1.87290E-08 350800 + 240 350801 Br-80m 1.45520E-08 1.45520E-08 350801 + 241 350810 Br-81 2.73760E-06 9.37070E-04 35081.82c + 242 350820 Br-82 3.96820E-06 5.38910E-06 350820 + 243 350821 Br-82m 1.45580E-06 1.45580E-06 350821 + 244 350830 Br-83 6.39490E-05 2.30780E-03 350830 + 245 350840 Br-84 1.78840E-04 3.54090E-03 350840 + 246 350841 Br-84m 1.78840E-04 1.78840E-04 350841 + 247 350850 Br-85 1.53450E-03 4.41500E-03 350850 + 248 350860 Br-86 2.72020E-03 5.24490E-03 350860 + 249 350870 Br-87 4.50530E-03 5.65640E-03 350870 + 250 350880 Br-88 2.04130E-03 2.28080E-03 350880 + 251 350890 Br-89 2.58260E-03 2.64230E-03 350890 + 252 350900 Br-90 8.57110E-04 8.69230E-04 350900 + 253 350910 Br-91 2.66130E-04 2.66350E-04 350910 + 254 350920 Br-92 2.76560E-05 2.76630E-05 350920 + 255 350930 Br-93 3.28670E-06 3.28670E-06 350930 + 256 350940 Br-94 4.92880E-08 4.92880E-08 350940 + 257 350950 Br-95 9.82170E-10 9.82170E-10 350950 + 258 360810 Kr-81 1.90270E-10 2.15600E-10 360810 + 259 360811 Kr-81m 2.53330E-11 2.53330E-11 360811 + 260 360820 Kr-82 1.11380E-08 5.43510E-06 36082.82c + 261 360830 Kr-83 4.45680E-06 2.31320E-03 36083.82c + 262 360831 Kr-83m 8.97350E-07 2.30670E-03 360831 + 263 360840 Kr-84 2.35830E-05 3.74330E-03 36084.82c + 264 360850 Kr-85 1.52470E-04 1.10950E-03 36085.82c + 265 360851 Kr-85m 3.06990E-05 4.43860E-03 360851 + 266 360860 Kr-86 1.35570E-03 6.74260E-03 36086.82c + 267 360870 Kr-87 3.62840E-03 9.29560E-03 360870 + 268 360880 Kr-88 4.98820E-03 7.48880E-03 360880 + 269 360890 Kr-89 1.14850E-02 1.39690E-02 360890 + 270 360900 Kr-90 1.16090E-02 1.23180E-02 360900 + 271 360910 Kr-91 5.70510E-03 5.92730E-03 360910 + 272 360920 Kr-92 2.83400E-03 2.85470E-03 360920 + 273 360930 Kr-93 8.53060E-04 8.54150E-04 360930 + 274 360940 Kr-94 2.42850E-04 2.42870E-04 360940 + 275 360950 Kr-95 3.37070E-05 3.37080E-05 360950 + 276 360960 Kr-96 7.24790E-06 7.24790E-06 360960 + 277 360970 Kr-97 1.09960E-08 1.09960E-08 360970 + 278 370830 Rb-83 1.42910E-11 5.42780E-11 370830 + 279 370831 Rb-83m 3.99870E-11 3.99870E-11 370831 + 280 370840 Rb-84 1.41590E-09 4.38620E-09 370840 + 281 370841 Rb-84m 2.97030E-09 2.97030E-09 370841 + 282 370850 Rb-85 1.42910E-07 4.59830E-03 37085.82c + 283 370860 Rb-86 1.96110E-06 6.07540E-06 37086.82c + 284 370861 Rb-86m 4.11430E-06 4.11430E-06 370861 + 285 370870 Rb-87 1.37170E-04 9.43280E-03 37087.82c + 286 370880 Rb-88 3.80440E-04 7.86920E-03 370880 + 287 370890 Rb-89 3.48140E-03 1.74500E-02 370890 + 288 370900 Rb-90 7.32690E-04 1.16750E-02 370900 + 289 370901 Rb-90m 7.45380E-03 9.06500E-03 370901 + 290 370910 Rb-91 1.27880E-02 1.87150E-02 370910 + 291 370920 Rb-92 1.07330E-02 1.35880E-02 370920 + 292 370930 Rb-93 8.55820E-03 9.41500E-03 370930 + 293 370940 Rb-94 4.63620E-03 4.87730E-03 370940 + 294 370950 Rb-95 2.28110E-03 2.31410E-03 370950 + 295 370960 Rb-96 2.68070E-04 4.07350E-04 370960 + 296 370961 Rb-96m 2.68070E-04 2.71560E-04 370961 + 297 370970 Rb-97 1.21320E-04 1.21330E-04 370970 + 298 370980 Rb-98 5.01050E-06 5.01050E-06 370980 + 299 370981 Rb-98m 5.01050E-06 5.01050E-06 370981 + 300 370990 Rb-99 1.83720E-06 1.83720E-06 370990 + 301 371000 Rb-100 1.54730E-09 1.54730E-09 371000 + 302 380860 Sr-86 1.56010E-09 6.07660E-06 38086.82c + 303 380870 Sr-87 8.67030E-08 1.04110E-07 38087.82c + 304 380871 Sr-87m 1.74570E-08 1.74570E-08 380871 + 305 380880 Sr-88 1.44520E-05 7.88370E-03 38088.82c + 306 380890 Sr-89 2.07190E-04 1.76570E-02 38089.82c + 307 380900 Sr-90 1.63250E-03 2.21370E-02 38090.82c + 308 380910 Sr-91 4.76120E-03 2.34770E-02 380910 + 309 380920 Sr-92 1.38020E-02 2.75220E-02 380920 + 310 380930 Sr-93 2.05410E-02 3.03170E-02 380930 + 311 380940 Sr-94 2.83200E-02 3.29040E-02 380940 + 312 380950 Sr-95 1.87500E-02 2.09200E-02 380950 + 313 380960 Sr-96 1.19440E-02 1.24630E-02 380960 + 314 380970 Sr-97 4.81700E-03 4.90860E-03 380970 + 315 380980 Sr-98 1.68410E-03 1.69370E-03 380980 + 316 380990 Sr-99 2.83110E-04 2.84650E-04 380990 + 317 381000 Sr-100 6.00500E-05 6.00510E-05 381000 + 318 381010 Sr-101 6.55190E-06 6.55190E-06 381010 + 319 381020 Sr-102 1.04340E-08 1.04340E-08 381020 + 320 390880 Y-88 1.11460E-10 2.10150E-10 390880 + 321 390881 Y-88m 9.86860E-11 9.86860E-11 390881 + 322 390890 Y-89 3.88850E-09 1.76570E-02 39089.82c + 323 390891 Y-89m 1.93120E-08 1.72130E-06 390891 + 324 390900 Y-90 6.44450E-07 2.21380E-02 39090.82c + 325 390901 Y-90m 1.07770E-06 1.07770E-06 390901 + 326 390910 Y-91 1.29640E-05 2.35540E-02 39091.82c + 327 390911 Y-91m 6.43850E-05 1.38770E-02 390911 + 328 390920 Y-92 3.17430E-04 2.78390E-02 390920 + 329 390930 Y-93 2.56660E-04 3.25010E-02 390930 + 330 390931 Y-93m 1.92760E-03 9.51420E-03 390931 + 331 390940 Y-94 6.06610E-03 3.89700E-02 390940 + 332 390950 Y-95 1.83510E-02 3.92710E-02 390950 + 333 390960 Y-96 6.92540E-03 1.93900E-02 390960 + 334 390961 Y-96m 1.45290E-02 1.45300E-02 390961 + 335 390970 Y-97 3.70210E-03 8.00540E-03 390970 + 336 390971 Y-97m 1.36840E-02 1.81760E-02 390971 + 337 390972 Y-97m 4.70280E-03 4.70280E-03 390972 + 338 390980 Y-98 2.17150E-03 3.86530E-03 390980 + 339 390981 Y-98m 1.05280E-02 1.05280E-02 390981 + 340 390990 Y-99 8.42890E-03 8.71400E-03 390990 + 341 391000 Y-100 1.52410E-03 1.58380E-03 391000 + 342 391001 Y-100m 1.52410E-03 1.52420E-03 391001 + 343 391010 Y-101 1.03800E-03 1.04440E-03 391010 + 344 391020 Y-102 7.95050E-05 7.95100E-05 391020 + 345 391021 Y-102m 7.95050E-05 7.95100E-05 391021 + 346 391030 Y-103 2.85140E-05 2.85140E-05 391030 + 347 391040 Y-104 5.02410E-08 5.02410E-08 391040 + 348 391050 Y-105 1.25410E-09 1.25410E-09 391050 + 349 400910 Zr-91 1.37590E-06 2.35550E-02 40091.82c + 350 400920 Zr-92 5.77030E-06 2.78450E-02 40092.82c + 351 400930 Zr-93 7.03580E-05 3.25720E-02 40093.82c + 352 400940 Zr-94 5.56520E-04 3.95260E-02 40094.82c + 353 400950 Zr-95 2.36120E-03 4.16320E-02 40095.82c + 354 400960 Zr-96 1.03320E-02 4.42660E-02 40096.82c + 355 400970 Zr-97 2.01250E-02 4.74780E-02 400970 + 356 400980 Zr-98 3.73530E-02 5.15210E-02 400980 + 357 400990 Zr-99 3.32700E-02 4.18500E-02 400990 + 358 401000 Zr-100 3.02250E-02 3.33180E-02 401000 + 359 401010 Zr-101 1.49360E-02 1.59880E-02 401010 + 360 401020 Zr-102 7.75760E-03 7.91110E-03 401020 + 361 401030 Zr-103 2.14700E-03 2.17320E-03 401030 + 362 401040 Zr-104 5.37980E-04 5.38030E-04 401040 + 363 401050 Zr-105 6.86500E-05 6.86510E-05 401050 + 364 401060 Zr-106 8.00000E-06 8.00000E-06 401060 + 365 401070 Zr-107 6.59420E-09 6.59420E-09 401070 + 366 410930 Nb-93 5.98870E-10 7.19450E-10 41093.82c + 367 410931 Nb-93m 1.20580E-10 1.20580E-10 410931 + 368 410940 Nb-94 6.90380E-07 1.10110E-06 41094.82c + 369 410941 Nb-94m 4.12820E-07 4.12820E-07 410941 + 370 410950 Nb-95 1.36100E-05 4.16230E-02 41095.82c + 371 410951 Nb-95m 2.74030E-06 4.52510E-04 410951 + 372 410960 Nb-96 1.21610E-04 1.21610E-04 410960 + 373 410970 Nb-97 7.04290E-04 4.83240E-02 410970 + 374 410971 Nb-97m 1.41810E-04 4.52690E-02 410971 + 375 410980 Nb-98 6.47500E-04 5.21690E-02 410980 + 376 410981 Nb-98m 2.25610E-03 2.25610E-03 410981 + 377 410990 Nb-99 9.21380E-03 3.60080E-02 410990 + 378 410991 Nb-99m 1.85520E-03 1.72560E-02 410991 + 379 411000 Nb-100 3.46340E-03 3.67820E-02 411000 + 380 411001 Nb-100m 1.67910E-02 1.67910E-02 411001 + 381 411010 Nb-101 3.36310E-02 4.96190E-02 411010 + 382 411020 Nb-102 1.38790E-02 2.17900E-02 411020 + 383 411021 Nb-102m 1.38790E-02 1.38790E-02 411021 + 384 411030 Nb-103 2.37320E-02 2.59050E-02 411030 + 385 411040 Nb-104 5.58450E-03 6.12350E-03 411040 + 386 411041 Nb-104m 5.58450E-03 5.58450E-03 411041 + 387 411050 Nb-105 4.84610E-03 4.91390E-03 411050 + 388 411060 Nb-106 1.12960E-03 1.13750E-03 411060 + 389 411070 Nb-107 2.54160E-04 2.54170E-04 411070 + 390 411080 Nb-108 2.36810E-05 2.36810E-05 411080 + 391 411090 Nb-109 6.43490E-06 6.43490E-06 411090 + 392 420960 Mo-96 1.03590E-06 1.22650E-04 42096.82c + 393 420970 Mo-97 9.76140E-06 4.83340E-02 42097.82c + 394 420980 Mo-98 1.38970E-04 5.45640E-02 42098.82c + 395 420990 Mo-99 6.76980E-04 5.35960E-02 42099.82c + 396 421000 Mo-100 3.78470E-03 5.73570E-02 42100.82c + 397 421010 Mo-101 9.93550E-03 5.95550E-02 421010 + 398 421020 Mo-102 2.62680E-02 6.19370E-02 421020 + 399 421030 Mo-103 3.41930E-02 6.01050E-02 421030 + 400 421040 Mo-104 3.94310E-02 5.12160E-02 421040 + 401 421050 Mo-105 2.36450E-02 2.85270E-02 421050 + 402 421060 Mo-106 1.53470E-02 1.64490E-02 421060 + 403 421070 Mo-107 5.60310E-03 5.84350E-03 421070 + 404 421080 Mo-108 1.89450E-03 1.91750E-03 421080 + 405 421090 Mo-109 3.20400E-04 3.26020E-04 421090 + 406 421100 Mo-110 4.84700E-05 4.84700E-05 421100 + 407 421110 Mo-111 3.51460E-06 3.51460E-06 421110 + 408 421120 Mo-112 7.32070E-10 7.32070E-10 421120 + 409 430980 Tc-98 2.73900E-09 2.73900E-09 430980 + 410 430990 Tc-99 2.29430E-06 5.35970E-02 43099.82c + 411 430991 Tc-99m 4.61960E-07 4.71970E-02 430991 + 412 431000 Tc-100 1.52860E-05 1.52860E-05 431000 + 413 431010 Tc-101 2.02050E-04 5.97570E-02 431010 + 414 431020 Tc-102 5.45100E-04 6.24820E-02 431020 + 415 431021 Tc-102m 5.45100E-04 5.45100E-04 431021 + 416 431030 Tc-103 4.98810E-03 6.50930E-02 431030 + 417 431040 Tc-104 1.04620E-02 6.16780E-02 431040 + 418 431050 Tc-105 2.27450E-02 5.12720E-02 431050 + 419 431060 Tc-106 2.41680E-02 4.06160E-02 431060 + 420 431070 Tc-107 2.48640E-02 3.07070E-02 431070 + 421 431080 Tc-108 1.35620E-02 1.54810E-02 431080 + 422 431090 Tc-109 6.79730E-03 7.12160E-03 431090 + 423 431100 Tc-110 2.22650E-03 2.27500E-03 431100 + 424 431110 Tc-111 5.16980E-04 5.20460E-04 431110 + 425 431120 Tc-112 1.07640E-04 1.07640E-04 431120 + 426 431130 Tc-113 1.82660E-05 1.82660E-05 431130 + 427 431140 Tc-114 2.08920E-06 2.08920E-06 431140 + 428 441010 Ru-101 2.80880E-06 5.97600E-02 44101.82c + 429 441020 Ru-102 1.97300E-05 6.30470E-02 44102.82c + 430 441030 Ru-103 3.71730E-05 6.52340E-02 44103.82c + 431 441031 Ru-103m 1.04010E-04 1.04010E-04 441031 + 432 441040 Ru-104 7.80150E-04 6.24580E-02 44104.82c + 433 441050 Ru-105 2.47250E-03 5.37440E-02 44105.82c + 434 441060 Ru-106 7.63740E-03 4.82540E-02 44106.82c + 435 441070 Ru-107 1.18000E-02 4.25070E-02 441070 + 436 441080 Ru-108 1.70810E-02 3.25680E-02 441080 + 437 441090 Ru-109 1.25810E-02 1.96980E-02 441090 + 438 441100 Ru-110 9.81940E-03 1.20940E-02 441100 + 439 441110 Ru-111 3.79460E-03 4.31670E-03 441110 + 440 441120 Ru-112 1.83350E-03 1.94080E-03 441120 + 441 441130 Ru-113 2.09740E-04 3.31700E-04 441130 + 442 441131 Ru-113m 2.09740E-04 2.09740E-04 441131 + 443 441140 Ru-114 1.62710E-04 1.64660E-04 441140 + 444 441150 Ru-115 2.70470E-05 2.70470E-05 441150 + 445 441160 Ru-116 1.34510E-05 1.34510E-05 441160 + 446 441170 Ru-117 1.34600E-06 1.34600E-06 441170 + 447 451030 Rh-103 3.55670E-10 6.52340E-02 45103.82c + 448 451031 Rh-103m 2.67130E-09 6.44530E-02 451031 + 449 451040 Rh-104 1.21290E-06 5.43340E-06 451040 + 450 451041 Rh-104m 4.22600E-06 4.22600E-06 451041 + 451 451050 Rh-105 2.48810E-05 5.37720E-02 45105.82c + 452 451051 Rh-105m 3.31280E-06 1.52600E-02 451051 + 453 451060 Rh-106 3.55170E-05 4.82890E-02 451060 + 454 451061 Rh-106m 9.68130E-05 9.68130E-05 451061 + 455 451070 Rh-107 7.14460E-04 4.32220E-02 451070 + 456 451080 Rh-108 3.87240E-04 3.29550E-02 451080 + 457 451081 Rh-108m 1.34930E-03 1.34930E-03 451081 + 458 451090 Rh-109 3.28060E-03 2.29780E-02 451090 + 459 451100 Rh-110 4.06690E-03 1.61600E-02 451100 + 460 451101 Rh-110m 9.57400E-05 9.57400E-05 451101 + 461 451110 Rh-111 4.82240E-03 9.13910E-03 451110 + 462 451120 Rh-112 2.03040E-03 3.97120E-03 451120 + 463 451121 Rh-112m 2.03040E-03 2.03040E-03 451121 + 464 451130 Rh-113 3.01330E-03 3.44990E-03 451130 + 465 451140 Rh-114 5.55200E-04 7.19920E-04 451140 + 466 451141 Rh-114m 5.55200E-04 5.55200E-04 451141 + 467 451150 Rh-115 4.92000E-04 5.19130E-04 451150 + 468 451160 Rh-116 1.83090E-05 3.16420E-05 451160 + 469 451161 Rh-116m 4.99050E-05 4.99050E-05 451161 + 470 451170 Rh-117 1.49710E-05 1.62890E-05 451170 + 471 451180 Rh-118 4.58500E-09 4.58500E-09 451180 + 472 451190 Rh-119 1.06040E-10 1.06040E-10 451190 + 473 451220 Rh-122 5.24520E-09 5.24520E-09 451220 + 474 461060 Pd-106 8.89000E-07 4.83870E-02 46106.82c + 475 461070 Pd-107 2.74120E-06 4.32310E-02 46107.82c + 476 461071 Pd-107m 6.02500E-06 6.02500E-06 461071 + 477 461080 Pd-108 5.23040E-05 3.43570E-02 46108.82c + 478 461090 Pd-109 5.10580E-05 2.31420E-02 461090 + 479 461091 Pd-109m 1.12220E-04 1.16010E-02 461091 + 480 461100 Pd-110 5.02260E-04 1.67580E-02 46110.82c + 481 461110 Pd-111 2.12660E-04 9.68310E-03 461110 + 482 461111 Pd-111m 4.67410E-04 5.03970E-04 461111 + 483 461120 Pd-112 1.32510E-03 7.32660E-03 461120 + 484 461130 Pd-113 3.62060E-04 4.82500E-03 461130 + 485 461131 Pd-113m 1.01300E-03 1.01300E-03 461131 + 486 461140 Pd-114 1.33200E-03 2.60710E-03 461140 + 487 461150 Pd-115 2.31310E-04 7.21770E-04 461150 + 488 461151 Pd-115m 5.08420E-04 5.83790E-04 461151 + 489 461160 Pd-116 3.15470E-04 3.97020E-04 461160 + 490 461170 Pd-117 2.28860E-05 8.94790E-05 461170 + 491 461171 Pd-117m 5.03030E-05 5.03030E-05 461171 + 492 461180 Pd-118 3.32690E-05 3.32730E-05 461180 + 493 461190 Pd-119 9.38080E-06 9.38090E-06 461190 + 494 461200 Pd-120 7.00190E-06 7.00190E-06 461200 + 495 461210 Pd-121 1.56560E-09 1.56560E-09 461210 + 496 461220 Pd-122 5.17090E-06 5.17620E-06 461220 + 497 461230 Pd-123 8.47000E-07 8.47000E-07 461230 + 498 461240 Pd-124 6.25390E-08 6.25390E-08 461240 + 499 471080 Ag-108 7.16220E-10 8.86070E-10 471080 + 500 471081 Ag-108m 1.95230E-09 1.95230E-09 471081 + 501 471090 Ag-109 3.77710E-07 2.31450E-02 47109.82c + 502 471091 Ag-109m 2.83690E-06 2.31330E-02 471091 + 503 471100 Ag-110 9.12480E-07 9.46310E-07 471100 + 504 471101 Ag-110m 2.48720E-06 2.48720E-06 47510.82c + 505 471110 Ag-111 3.07230E-06 9.79660E-03 47111.82c + 506 471111 Ag-111m 2.30750E-05 9.73460E-03 471111 + 507 471120 Ag-112 7.28870E-05 7.39950E-03 471120 + 508 471130 Ag-113 1.86570E-05 3.27000E-03 471130 + 509 471131 Ag-113m 1.40120E-04 4.76040E-03 471131 + 510 471140 Ag-114 3.06710E-05 2.78650E-03 471140 + 511 471141 Ag-114m 1.48690E-04 1.48690E-04 471141 + 512 471150 Ag-115 3.61690E-05 7.73820E-04 471150 + 513 471151 Ag-115m 2.71650E-04 1.00360E-03 471151 + 514 471160 Ag-116 5.65680E-05 4.62840E-04 471160 + 515 471161 Ag-116m 1.54190E-04 1.54190E-04 471161 + 516 471170 Ag-117 2.05660E-05 7.72580E-05 471170 + 517 471171 Ag-117m 1.54460E-04 1.99200E-04 471171 + 518 471180 Ag-118 2.95570E-05 1.18770E-04 471180 + 519 471181 Ag-118m 1.43290E-04 1.48050E-04 471181 + 520 471190 Ag-119 1.62340E-05 2.09240E-05 471190 + 521 471191 Ag-119m 1.21930E-04 1.26620E-04 471191 + 522 471200 Ag-120 8.29150E-05 1.39020E-04 471200 + 523 471201 Ag-120m 1.38670E-04 1.42170E-04 471201 + 524 471210 Ag-121 3.44620E-05 3.44640E-05 471210 + 525 471220 Ag-122 9.83190E-06 1.50080E-05 471220 + 526 471221 Ag-122m 1.06000E-05 1.06000E-05 471221 + 527 471230 Ag-123 2.94650E-05 3.03120E-05 471230 + 528 471240 Ag-124 6.32870E-06 9.80290E-06 471240 + 529 471241 Ag-124m 6.82330E-06 6.82330E-06 471241 + 530 471250 Ag-125 2.05620E-06 2.05620E-06 471250 + 531 471260 Ag-126 7.19250E-07 7.19250E-07 471260 + 532 471270 Ag-127 4.23330E-08 4.23330E-08 471270 + 533 471280 Ag-128 1.62220E-09 1.62220E-09 471280 + 534 481110 Cd-111 1.72420E-09 9.84530E-03 48111.82c + 535 481111 Cd-111m 6.52940E-09 6.52940E-09 481111 + 536 481120 Cd-112 1.81550E-07 7.39970E-03 48112.82c + 537 481130 Cd-113 3.46440E-07 4.92760E-03 48113.82c + 538 481131 Cd-113m 1.31200E-06 5.78470E-05 481131 + 539 481140 Cd-114 1.24810E-05 2.79900E-03 48114.82c + 540 481150 Cd-115 3.92480E-06 1.50290E-03 481150 + 541 481151 Cd-115m 1.48630E-05 8.25360E-05 48515.82c + 542 481160 Cd-116 3.40250E-05 6.41800E-04 48116.82c + 543 481170 Cd-117 8.03600E-06 2.13080E-04 481170 + 544 481171 Cd-117m 3.04320E-05 8.98940E-05 481171 + 545 481180 Cd-118 1.02390E-04 3.08510E-04 481180 + 546 481190 Cd-119 3.34630E-05 1.70540E-04 481190 + 547 481191 Cd-119m 9.36270E-05 1.04090E-04 481191 + 548 481200 Cd-120 4.46710E-04 6.75290E-04 481200 + 549 481210 Cd-121 7.35340E-05 1.04400E-04 481210 + 550 481211 Cd-121m 2.05750E-04 2.09350E-04 481211 + 551 481220 Cd-122 2.52610E-04 2.78220E-04 481220 + 552 481230 Cd-123 5.07910E-05 7.55960E-05 481230 + 553 481231 Cd-123m 1.42110E-04 1.47630E-04 481231 + 554 481240 Cd-124 2.40900E-04 2.54110E-04 481240 + 555 481250 Cd-125 6.70570E-05 6.80850E-05 481250 + 556 481251 Cd-125m 1.87620E-04 1.88650E-04 481251 + 557 481260 Cd-126 1.40580E-04 1.41300E-04 481260 + 558 481270 Cd-127 4.20050E-05 4.20470E-05 481270 + 559 481280 Cd-128 8.25270E-06 8.25430E-06 481280 + 560 481290 Cd-129 2.37500E-07 2.37500E-07 481290 + 561 481291 Cd-129m 6.64520E-07 6.64520E-07 481291 + 562 481300 Cd-130 4.81720E-08 4.81720E-08 481300 + 563 481310 Cd-131 1.65910E-09 1.65910E-09 481310 + 564 491130 In-113 3.72150E-10 5.77660E-05 49113.82c + 565 491131 In-113m 7.49310E-11 7.49310E-11 491131 + 566 491140 In-114 2.47750E-09 1.08080E-08 491140 + 567 491141 In-114m 4.00070E-09 8.63250E-09 491141 + 568 491142 In-114m 4.63180E-09 4.63180E-09 491142 + 569 491150 In-115 1.15410E-07 1.51050E-03 49115.82c + 570 491151 In-115m 2.32380E-08 1.50300E-03 491151 + 571 491160 In-116 2.12890E-07 2.12890E-07 491160 + 572 491161 In-116m 3.43780E-07 7.41790E-07 491161 + 573 491162 In-116m 3.98010E-07 3.98010E-07 491162 + 574 491170 In-117 2.88760E-06 2.02110E-04 491170 + 575 491171 In-117m 5.81400E-07 1.97230E-04 491171 + 576 491180 In-118 6.00740E-07 3.09110E-04 491180 + 577 491181 In-118m 9.70070E-07 2.07740E-06 491181 + 578 491182 In-118m 1.12310E-06 1.12310E-06 491182 + 579 491190 In-119 1.09390E-05 1.40140E-04 491190 + 580 491191 In-119m 2.20260E-06 1.56390E-04 491191 + 581 491200 In-120 3.12080E-05 7.06500E-04 491200 + 582 491201 In-120m 3.12080E-05 3.12080E-05 491201 + 583 491202 In-120m 3.12080E-05 3.12080E-05 491202 + 584 491210 In-121 9.97050E-05 3.45280E-04 491210 + 585 491211 In-121m 2.00750E-05 8.93110E-05 491211 + 586 491220 In-122 8.04080E-05 3.58630E-04 491220 + 587 491221 In-122m 6.72360E-05 6.72360E-05 491221 + 588 491222 In-122m 6.72360E-05 6.72360E-05 491222 + 589 491230 In-123 3.52440E-04 5.21680E-04 491230 + 590 491231 In-123m 7.09620E-05 1.24940E-04 491231 + 591 491240 In-124 2.46290E-04 5.00400E-04 491240 + 592 491241 In-124m 2.65540E-04 2.65540E-04 491241 + 593 491250 In-125 9.77240E-04 1.19850E-03 491250 + 594 491251 In-125m 1.96760E-04 2.32260E-04 491251 + 595 491260 In-126 6.35950E-04 7.77250E-04 491260 + 596 491261 In-126m 6.85650E-04 6.85650E-04 491261 + 597 491270 In-127 1.22840E-03 1.22840E-03 491270 + 598 491271 In-127m 2.47330E-04 2.89370E-04 491271 + 599 491280 In-128 2.09800E-04 3.00200E-04 491280 + 600 491281 In-128m 8.21480E-05 9.04030E-05 491281 + 601 491282 In-128m 3.14760E-04 3.14760E-04 491282 + 602 491290 In-129 3.93780E-04 3.94440E-04 491290 + 603 491291 In-129m 7.92850E-05 7.95230E-05 491291 + 604 491300 In-130 3.53340E-05 3.53810E-05 491300 + 605 491301 In-130m 5.14490E-05 5.14490E-05 491301 + 606 491302 In-130m 7.16670E-05 7.16670E-05 491302 + 607 491310 In-131 9.79570E-06 9.89700E-06 491310 + 608 491311 In-131m 9.79570E-06 9.79570E-06 491311 + 609 491312 In-131m 9.79570E-06 9.79570E-06 491312 + 610 491320 In-132 9.36780E-07 9.36780E-07 491320 + 611 491330 In-133 1.00850E-08 1.21160E-08 491330 + 612 491331 In-133m 2.03060E-09 2.03060E-09 491331 + 613 501150 Sn-115 6.02860E-11 7.51480E-05 50115.82c + 614 501160 Sn-116 5.99600E-10 9.55280E-07 50116.82c + 615 501170 Sn-117 2.22460E-09 3.06460E-04 50117.82c + 616 501171 Sn-117m 8.42440E-09 6.97050E-07 501171 + 617 501180 Sn-118 1.78380E-07 3.11390E-04 50118.82c + 618 501190 Sn-119 4.35080E-07 2.89860E-04 50119.82c + 619 501191 Sn-119m 1.64760E-06 1.28250E-04 501191 + 620 501200 Sn-120 3.19970E-05 8.01000E-04 50120.82c + 621 501210 Sn-121 5.55040E-06 4.42360E-04 501210 + 622 501211 Sn-121m 1.55300E-05 5.46450E-05 501211 + 623 501220 Sn-122 5.06520E-05 5.43750E-04 50122.82c + 624 501230 Sn-123 6.96800E-05 1.09450E-04 50123.82c + 625 501231 Sn-123m 2.49040E-05 6.31750E-04 501231 + 626 501240 Sn-124 2.50790E-04 1.01670E-03 50124.82c + 627 501250 Sn-125 4.47240E-04 6.49690E-04 50125.82c + 628 501251 Sn-125m 1.59850E-04 1.38810E-03 501251 + 629 501260 Sn-126 1.83070E-03 3.29560E-03 50126.82c + 630 501270 Sn-127 2.09220E-03 2.57100E-03 501270 + 631 501271 Sn-127m 7.47770E-04 1.78470E-03 501271 + 632 501280 Sn-128 1.06390E-03 4.57880E-03 501280 + 633 501281 Sn-128m 2.89990E-03 3.21470E-03 501281 + 634 501290 Sn-129 1.34270E-03 1.77480E-03 501290 + 635 501291 Sn-129m 3.75690E-03 3.79890E-03 501291 + 636 501300 Sn-130 1.49700E-03 1.59390E-03 501300 + 637 501301 Sn-130m 4.08050E-03 4.14230E-03 501301 + 638 501310 Sn-131 6.94110E-04 7.13090E-04 501310 + 639 501311 Sn-131m 1.94210E-03 1.95230E-03 501311 + 640 501320 Sn-132 5.80740E-04 5.81690E-04 501320 + 641 501330 Sn-133 5.04230E-05 5.04250E-05 501330 + 642 501340 Sn-134 4.52340E-06 4.52340E-06 501340 + 643 501350 Sn-135 1.54980E-07 1.54980E-07 501350 + 644 501360 Sn-136 2.23250E-09 2.23250E-09 501360 + 645 511180 Sb-118 1.24320E-11 1.24320E-11 511180 + 646 511181 Sb-118m 2.07920E-11 2.07920E-11 511181 + 647 511190 Sb-119 8.84240E-10 1.23930E-09 511190 + 648 511191 Sb-119m 3.55060E-10 3.55060E-10 511191 + 649 511200 Sb-120 3.45800E-08 3.45800E-08 511200 + 650 511201 Sb-120m 5.78300E-08 5.78300E-08 511201 + 651 511210 Sb-121 6.77160E-07 4.55280E-04 51121.82c + 652 511220 Sb-122 4.26430E-11 9.97720E-11 511220 + 653 511221 Sb-122m 5.71290E-11 5.71290E-11 511221 + 654 511230 Sb-123 4.88640E-06 7.46090E-04 51123.82c + 655 511240 Sb-124 7.04280E-06 1.81260E-05 51124.82c + 656 511241 Sb-124m 5.68140E-06 1.47770E-05 511241 + 657 511242 Sb-124m 9.09590E-06 9.09590E-06 511242 + 658 511250 Sb-125 8.17580E-05 2.11960E-03 51125.82c + 659 511260 Sb-126 8.67690E-05 1.03760E-04 51126.82c + 660 511261 Sb-126m 5.41970E-05 1.21380E-04 511261 + 661 511262 Sb-126m 6.71840E-05 6.71840E-05 511262 + 662 511270 Sb-127 7.26120E-04 5.08190E-03 511270 + 663 511280 Sb-128 5.84080E-04 5.19220E-03 511280 + 664 511281 Sb-128m 8.16920E-04 8.16920E-04 511281 + 665 511290 Sb-129 3.97780E-03 8.37840E-03 511290 + 666 511291 Sb-129m 2.94370E-03 4.84310E-03 511291 + 667 511300 Sb-130 6.01050E-03 9.67550E-03 511300 + 668 511301 Sb-130m 6.01050E-03 8.08160E-03 511301 + 669 511310 Sb-131 2.36920E-02 2.63570E-02 511310 + 670 511320 Sb-132 6.59870E-03 7.18040E-03 511320 + 671 511321 Sb-132m 5.84230E-03 5.84230E-03 511321 + 672 511330 Sb-133 9.07110E-03 9.12230E-03 511330 + 673 511340 Sb-134 4.41970E-04 4.45740E-04 511340 + 674 511341 Sb-134m 1.20470E-03 1.20470E-03 511341 + 675 511350 Sb-135 2.95990E-04 2.96110E-04 511350 + 676 511360 Sb-136 5.06970E-05 5.06990E-05 511360 + 677 511370 Sb-137 1.78260E-06 1.78260E-06 511370 + 678 511380 Sb-138 1.61510E-08 1.61510E-08 511380 + 679 521200 Te-120 2.56660E-11 2.56660E-11 52120.82c + 680 521210 Te-121 1.23550E-10 5.38570E-10 521210 + 681 521211 Te-121m 4.67890E-10 4.67890E-10 521211 + 682 521240 Te-124 3.50150E-11 2.18200E-05 52124.82c + 683 521250 Te-125 4.29290E-07 2.12160E-03 52125.82c + 684 521251 Te-125m 1.62570E-06 4.75920E-04 521251 + 685 521260 Te-126 4.80590E-06 2.12960E-04 52126.82c + 686 521270 Te-127 8.56730E-06 5.09370E-03 521270 + 687 521271 Te-127m 2.39710E-05 8.61440E-04 52527.82c + 688 521280 Te-128 1.15810E-04 6.09560E-03 52128.82c + 689 521290 Te-129 2.00380E-04 1.10470E-02 521290 + 690 521291 Te-129m 5.60640E-04 5.97120E-03 52529.82c + 691 521300 Te-130 4.57760E-03 2.23350E-02 52130.82c + 692 521310 Te-131 3.67830E-03 3.05300E-02 521310 + 693 521311 Te-131m 1.02920E-02 1.24020E-02 521311 + 694 521320 Te-132 2.76860E-02 4.07090E-02 52132.82c + 695 521330 Te-133 8.36000E-03 2.02750E-02 521330 + 696 521331 Te-133m 2.33910E-02 2.49690E-02 521331 + 697 521340 Te-134 2.24880E-02 2.41840E-02 521340 + 698 521350 Te-135 7.24790E-03 7.50580E-03 521350 + 699 521360 Te-136 2.64660E-03 2.68980E-03 521360 + 700 521370 Te-137 3.97640E-04 3.98550E-04 521370 + 701 521380 Te-138 8.53010E-05 8.53170E-05 521380 + 702 521390 Te-139 3.46010E-06 3.46010E-06 521390 + 703 521400 Te-140 9.60220E-08 9.60220E-08 521400 + 704 521410 Te-141 1.92070E-09 1.92070E-09 521410 + 705 531270 I-127 9.53960E-10 5.11440E-03 53127.82c + 706 531280 I-128 4.62320E-08 4.62320E-08 531280 + 707 531290 I-129 1.05350E-05 1.32670E-02 53129.82c + 708 531300 I-130 5.78290E-05 7.56510E-05 53130.82c + 709 531301 I-130m 2.12160E-05 2.12160E-05 531301 + 710 531310 I-131 9.47450E-04 4.12750E-02 53131.82c + 711 531320 I-132 1.55400E-03 4.34460E-02 531320 + 712 531321 I-132m 1.37590E-03 1.37590E-03 531321 + 713 531330 I-133 9.44630E-03 5.73110E-02 531330 + 714 531331 I-133m 6.99070E-03 6.99070E-03 531331 + 715 531340 I-134 1.75420E-02 5.69010E-02 531340 + 716 531341 I-134m 1.55320E-02 1.55320E-02 531341 + 717 531350 I-135 5.16820E-02 5.91880E-02 53135.82c + 718 531360 I-136 7.80350E-03 1.04990E-02 531360 + 719 531361 I-136m 2.12710E-02 2.12770E-02 531361 + 720 531370 I-137 1.82210E-02 1.86130E-02 531370 + 721 531380 I-138 5.54870E-03 5.62860E-03 531380 + 722 531390 I-139 2.84110E-03 2.84460E-03 531390 + 723 531400 I-140 3.90200E-04 3.90300E-04 531400 + 724 531410 I-141 6.04570E-05 6.04590E-05 531410 + 725 531420 I-142 5.23490E-06 5.23490E-06 531420 + 726 531430 I-143 7.99610E-09 7.99610E-09 531430 + 727 541290 Xe-129 1.08890E-10 5.21260E-10 54129.82c + 728 541291 Xe-129m 4.12370E-10 4.12370E-10 541291 + 729 541300 Xe-130 9.87030E-07 8.00320E-05 54130.82c + 730 541310 Xe-131 1.93170E-06 4.12820E-02 54131.82c + 731 541311 Xe-131m 5.40480E-06 4.53730E-04 541311 + 732 541320 Xe-132 2.28600E-05 4.36920E-02 54132.82c + 733 541321 Xe-132m 3.06260E-05 3.06260E-05 541321 + 734 541330 Xe-133 9.48010E-05 5.76710E-02 54133.82c + 735 541331 Xe-133m 2.65250E-04 1.89660E-03 541331 + 736 541340 Xe-134 6.68850E-04 5.97500E-02 54134.82c + 737 541341 Xe-134m 1.82310E-03 2.18040E-03 541341 + 738 541350 Xe-135 2.46890E-03 6.84640E-02 54135.82c + 739 541351 Xe-135m 6.90770E-03 1.66790E-02 541351 + 740 541360 Xe-136 3.38630E-02 6.68490E-02 54136.82c + 741 541370 Xe-137 3.30820E-02 5.07840E-02 541370 + 742 541380 Xe-138 3.26290E-02 3.82380E-02 541380 + 743 541390 Xe-139 1.52360E-02 1.78380E-02 541390 + 744 541400 Xe-140 8.11710E-03 8.48380E-03 541400 + 745 541410 Xe-141 1.93060E-03 1.97970E-03 541410 + 746 541420 Xe-142 5.49040E-04 5.52970E-04 541420 + 747 541430 Xe-143 6.07150E-05 6.07200E-05 541430 + 748 541440 Xe-144 2.62330E-06 2.62330E-06 541440 + 749 541450 Xe-145 8.74540E-08 8.74540E-08 541450 + 750 541460 Xe-146 1.25050E-09 1.25050E-09 541460 + 751 551320 Cs-132 9.28630E-09 9.28630E-09 551320 + 752 551330 Cs-133 1.05000E-06 5.76730E-02 55133.82c + 753 551340 Cs-134 9.60180E-06 1.81030E-05 55134.82c + 754 551341 Cs-134m 8.50120E-06 8.50120E-06 551341 + 755 551350 Cs-135 1.06880E-04 6.87500E-02 55135.82c + 756 551351 Cs-135m 7.90930E-05 7.90930E-05 551351 + 757 551360 Cs-136 8.64910E-04 1.17410E-03 55136.82c + 758 551361 Cs-136m 6.18390E-04 6.18390E-04 551361 + 759 551370 Cs-137 1.14970E-02 6.22810E-02 55137.82c + 760 551380 Cs-138 1.00790E-02 6.19710E-02 551380 + 761 551381 Cs-138m 1.68560E-02 1.68560E-02 551381 + 762 551390 Cs-139 4.33590E-02 6.11970E-02 551390 + 763 551400 Cs-140 2.78860E-02 3.63710E-02 551400 + 764 551410 Cs-141 2.76080E-02 2.95890E-02 551410 + 765 551420 Cs-142 1.20170E-02 1.25690E-02 551420 + 766 551430 Cs-143 6.54710E-03 6.60730E-03 551430 + 767 551440 Cs-144 7.89400E-04 1.18670E-03 551440 + 768 551441 Cs-144m 7.89400E-04 7.89400E-04 551441 + 769 551450 Cs-145 5.48540E-04 5.48620E-04 551450 + 770 551460 Cs-146 8.65570E-05 8.65580E-05 551460 + 771 551470 Cs-147 2.80920E-06 2.80920E-06 551470 + 772 551480 Cs-148 5.11730E-09 5.11730E-09 551480 + 773 561340 Ba-134 2.02670E-09 1.81050E-05 56134.82c + 774 561350 Ba-135 3.53640E-08 1.34310E-07 56135.82c + 775 561351 Ba-135m 9.89460E-08 9.89460E-08 561351 + 776 561360 Ba-136 2.01030E-06 1.49080E-03 56136.82c + 777 561361 Ba-136m 5.47970E-06 5.47970E-06 561361 + 778 561370 Ba-137 2.61110E-05 6.23800E-02 56137.82c + 779 561371 Ba-137m 7.30580E-05 5.88660E-02 561371 + 780 561380 Ba-138 1.57930E-03 6.67530E-02 56138.82c + 781 561390 Ba-139 5.11200E-03 6.63090E-02 561390 + 782 561400 Ba-140 1.24820E-02 4.88530E-02 56140.82c + 783 561410 Ba-141 1.52190E-02 4.48080E-02 561410 + 784 561420 Ba-142 2.41560E-02 3.68330E-02 561420 + 785 561430 Ba-143 1.69980E-02 2.35350E-02 561430 + 786 561440 Ba-144 1.16500E-02 1.32720E-02 561440 + 787 561450 Ba-145 5.48890E-03 5.97140E-03 561450 + 788 561460 Ba-146 2.74170E-03 2.81680E-03 561460 + 789 561470 Ba-147 3.20300E-04 3.22310E-04 561470 + 790 561480 Ba-148 8.19010E-05 8.19050E-05 561480 + 791 561490 Ba-149 6.42740E-06 6.42740E-06 561490 + 792 561500 Ba-150 2.76320E-08 2.76320E-08 561500 + 793 561510 Ba-151 3.63310E-10 3.63310E-10 561510 + 794 571370 La-137 8.91350E-07 8.91350E-07 571370 + 795 571380 La-138 5.40800E-06 5.40800E-06 57138.82c + 796 571390 La-139 1.11120E-04 6.64210E-02 57139.82c + 797 571400 La-140 4.57160E-04 4.93100E-02 57140.82c + 798 571410 La-141 2.10980E-03 4.69180E-02 571410 + 799 571420 La-142 4.28440E-03 4.11170E-02 571420 + 800 571430 La-143 1.48430E-02 3.83780E-02 571430 + 801 571440 La-144 1.93590E-02 3.26310E-02 571440 + 802 571450 La-145 2.96680E-02 3.56390E-02 571450 + 803 571460 La-146 6.43210E-03 9.24890E-03 571460 + 804 571461 La-146m 1.34940E-02 1.34940E-02 571461 + 805 571470 La-147 9.65960E-03 9.98220E-03 571470 + 806 571480 La-148 4.73490E-03 4.81650E-03 571480 + 807 571490 La-149 1.32180E-03 1.32820E-03 571490 + 808 571500 La-150 3.12360E-04 3.12390E-04 571500 + 809 571510 La-151 2.44800E-05 2.44800E-05 571510 + 810 571520 La-152 5.69200E-06 5.69200E-06 571520 + 811 571530 La-153 1.15470E-09 1.15470E-09 571530 + 812 581390 Ce-139 3.03720E-07 1.15350E-06 581390 + 813 581391 Ce-139m 8.49780E-07 8.49780E-07 581391 + 814 581400 Ce-140 2.98240E-06 4.93130E-02 58140.82c + 815 581410 Ce-141 1.70330E-05 4.69350E-02 58141.82c + 816 581420 Ce-142 9.54840E-05 4.12130E-02 58142.82c + 817 581430 Ce-143 3.37470E-04 3.87150E-02 58143.82c + 818 581440 Ce-144 1.72250E-03 3.43530E-02 58144.82c + 819 581450 Ce-145 5.32490E-03 4.09640E-02 581450 + 820 581460 Ce-146 1.28750E-02 3.56180E-02 581460 + 821 581470 Ce-147 9.37130E-03 1.93530E-02 581470 + 822 581480 Ce-148 1.28460E-02 1.76810E-02 581480 + 823 581490 Ce-149 4.84590E-03 6.16390E-03 581490 + 824 581500 Ce-150 3.49970E-03 3.80360E-03 581500 + 825 581510 Ce-151 6.33670E-04 6.58490E-04 581510 + 826 581520 Ce-152 2.62620E-04 2.67970E-04 581520 + 827 581530 Ce-153 1.67990E-05 1.68000E-05 581530 + 828 581540 Ce-154 4.48970E-06 4.48970E-06 581540 + 829 581550 Ce-155 7.78230E-09 7.78230E-09 581550 + 830 581560 Ce-156 8.43560E-11 8.43560E-11 581560 + 831 591420 Pr-142 2.63510E-09 9.81800E-09 59142.82c + 832 591421 Pr-142m 7.18280E-09 7.18280E-09 591421 + 833 591430 Pr-143 3.68640E-06 3.87190E-02 59143.82c + 834 591440 Pr-144 1.80220E-06 3.43730E-02 591440 + 835 591441 Pr-144m 1.83340E-05 4.92390E-04 591441 + 836 591450 Pr-145 2.28030E-04 4.11920E-02 591450 + 837 591460 Pr-146 1.06170E-03 3.66790E-02 591460 + 838 591470 Pr-147 2.33660E-03 2.16900E-02 591470 + 839 591480 Pr-148 1.06400E-03 1.87450E-02 591480 + 840 591481 Pr-148m 5.15830E-03 5.15830E-03 591481 + 841 591490 Pr-149 9.09910E-03 1.52630E-02 591490 + 842 591500 Pr-150 1.01670E-02 1.39710E-02 591500 + 843 591510 Pr-151 6.64450E-03 7.30300E-03 591510 + 844 591520 Pr-152 4.87100E-03 5.13910E-03 591520 + 845 591530 Pr-153 1.70260E-03 1.71930E-03 591530 + 846 591540 Pr-154 4.86250E-04 4.90710E-04 591540 + 847 591550 Pr-155 9.50260E-05 9.50340E-05 591550 + 848 591560 Pr-156 1.69050E-05 1.69050E-05 591560 + 849 591570 Pr-157 1.04800E-08 1.04800E-08 591570 + 850 591580 Pr-158 1.76190E-10 1.76190E-10 591580 + 851 601440 Nd-144 1.13720E-09 3.43740E-02 60144.82c + 852 601450 Nd-145 8.90410E-08 4.11920E-02 60145.82c + 853 601460 Nd-146 2.79710E-06 3.66820E-02 60146.82c + 854 601470 Nd-147 2.24940E-05 2.17130E-02 60147.82c + 855 601480 Nd-148 1.83100E-04 2.40870E-02 60148.82c + 856 601490 Nd-149 5.00050E-04 1.57630E-02 601490 + 857 601500 Nd-150 1.78230E-03 1.57530E-02 60150.82c + 858 601510 Nd-151 1.99100E-03 9.29400E-03 601510 + 859 601520 Nd-152 4.43180E-03 9.57090E-03 601520 + 860 601530 Nd-153 2.81060E-03 4.52990E-03 601530 + 861 601540 Nd-154 2.30170E-03 2.79240E-03 601540 + 862 601550 Nd-155 7.07120E-04 8.02610E-04 601550 + 863 601560 Nd-156 2.03600E-04 2.20050E-04 601560 + 864 601570 Nd-157 3.07250E-05 3.07350E-05 601570 + 865 601580 Nd-158 6.78340E-07 6.78520E-07 601580 + 866 601590 Nd-159 4.35480E-08 4.35480E-08 601590 + 867 601600 Nd-160 7.31930E-10 7.31930E-10 601600 + 868 601610 Nd-161 1.43040E-11 1.43040E-11 601610 + 869 611470 Pm-147 4.65610E-09 2.17130E-02 61147.82c + 870 611480 Pm-148 5.61410E-08 6.37930E-08 61148.82c + 871 611481 Pm-148m 1.53030E-07 1.53030E-07 61548.82c + 872 611490 Pm-149 1.28570E-05 1.57760E-02 61149.82c + 873 611500 Pm-150 6.37710E-05 6.37710E-05 611500 + 874 611510 Pm-151 2.47100E-04 9.54110E-03 61151.82c + 875 611520 Pm-152 1.51190E-04 9.72210E-03 611520 + 876 611521 Pm-152m 3.17860E-04 3.17860E-04 611521 + 877 611522 Pm-152m 4.15210E-04 4.15210E-04 611522 + 878 611530 Pm-153 1.71520E-03 6.24510E-03 611530 + 879 611540 Pm-154 1.29660E-03 4.08900E-03 611540 + 880 611541 Pm-154m 1.29660E-03 1.29660E-03 611541 + 881 611550 Pm-155 2.89330E-03 3.69590E-03 611550 + 882 611560 Pm-156 1.74540E-03 1.96550E-03 611560 + 883 611570 Pm-157 9.40600E-04 9.71340E-04 611570 + 884 611580 Pm-158 2.04060E-04 2.04740E-04 611580 + 885 611590 Pm-159 1.05690E-04 1.05730E-04 611590 + 886 611600 Pm-160 5.65530E-06 5.65600E-06 611600 + 887 611610 Pm-161 4.04450E-06 4.04450E-06 611610 + 888 611620 Pm-162 9.37550E-10 9.37550E-10 611620 + 889 611630 Pm-163 2.00630E-11 2.00630E-11 611630 + 890 621490 Sm-149 5.88510E-10 1.57760E-02 62149.82c + 891 621500 Sm-150 3.07590E-08 6.38020E-05 62150.82c + 892 621510 Sm-151 6.00840E-07 9.54170E-03 62151.82c + 893 621520 Sm-152 9.47510E-06 1.04650E-02 62152.82c + 894 621530 Sm-153 1.35640E-05 6.29660E-03 62153.82c + 895 621531 Sm-153m 3.79510E-05 3.79510E-05 621531 + 896 621540 Sm-154 1.80390E-04 5.56590E-03 62154.82c + 897 621550 Sm-155 3.73040E-04 4.06890E-03 621550 + 898 621560 Sm-156 5.69710E-04 2.53520E-03 621560 + 899 621570 Sm-157 4.57040E-04 1.42840E-03 621570 + 900 621580 Sm-158 3.60480E-04 5.65240E-04 621580 + 901 621590 Sm-159 2.86810E-04 3.92540E-04 621590 + 902 621600 Sm-160 9.63280E-05 1.01970E-04 621600 + 903 621610 Sm-161 2.02170E-05 2.42620E-05 621610 + 904 621620 Sm-162 7.04570E-06 7.04660E-06 621620 + 905 621630 Sm-163 1.13330E-07 1.13350E-07 621630 + 906 621640 Sm-164 2.24730E-09 2.24730E-09 621640 + 907 621650 Sm-165 5.64020E-11 5.64020E-11 621650 + 908 631520 Eu-152 9.71100E-10 2.25730E-09 63152.82c + 909 631521 Eu-152m 2.21890E-10 2.21890E-10 631521 + 910 631522 Eu-152m 1.28620E-09 1.28620E-09 631522 + 911 631530 Eu-153 1.67980E-06 6.29830E-03 63153.82c + 912 631540 Eu-154 3.23650E-06 6.72590E-06 63154.82c + 913 631541 Eu-154m 3.48940E-06 3.48940E-06 631541 + 914 631550 Eu-155 1.88490E-05 4.08780E-03 63155.82c + 915 631560 Eu-156 7.13610E-05 2.60650E-03 63156.82c + 916 631570 Eu-157 1.87820E-04 1.61620E-03 63157.82c + 917 631580 Eu-158 2.52640E-04 8.17880E-04 631580 + 918 631590 Eu-159 3.65720E-04 7.58260E-04 631590 + 919 631600 Eu-160 2.89840E-04 3.91810E-04 631600 + 920 631610 Eu-161 2.62900E-04 2.87160E-04 631610 + 921 631620 Eu-162 5.28850E-05 5.99320E-05 631620 + 922 631630 Eu-163 3.79950E-05 3.81080E-05 631630 + 923 631640 Eu-164 8.12810E-07 8.15060E-07 631640 + 924 631650 Eu-165 5.62600E-08 5.63160E-08 631650 + 925 631660 Eu-166 8.58430E-10 8.58430E-10 631660 + 926 631670 Eu-167 2.73860E-11 2.73860E-11 631670 + 927 641540 Gd-154 1.85040E-10 6.72470E-06 64154.82c + 928 641550 Gd-155 2.45080E-09 4.08780E-03 64155.82c + 929 641551 Gd-155m 6.85710E-09 6.85710E-09 641551 + 930 641560 Gd-156 1.44070E-07 2.60670E-03 64156.82c + 931 641570 Gd-157 2.35050E-06 1.61860E-03 64157.82c + 932 641580 Gd-158 6.38270E-06 8.24270E-04 64158.82c + 933 641590 Gd-159 3.00330E-05 7.88290E-04 641590 + 934 641600 Gd-160 4.78240E-05 4.39630E-04 64160.82c + 935 641610 Gd-161 7.25900E-05 3.59750E-04 641610 + 936 641620 Gd-162 5.27730E-05 1.12700E-04 641620 + 937 641630 Gd-163 5.86250E-05 9.67330E-05 641630 + 938 641640 Gd-164 2.07940E-05 2.16090E-05 641640 + 939 641650 Gd-165 6.52260E-06 6.57890E-06 641650 + 940 641660 Gd-166 2.68680E-06 2.68770E-06 641660 + 941 641670 Gd-167 4.01800E-08 4.02070E-08 641670 + 942 641680 Gd-168 7.01120E-09 7.01120E-09 641680 + 943 641690 Gd-169 2.96490E-10 2.96490E-10 641690 + 944 651570 Tb-157 3.62630E-10 3.62630E-10 651570 + 945 651580 Tb-158 7.01820E-09 7.70390E-09 651580 + 946 651581 Tb-158m 6.89870E-10 6.89870E-10 651581 + 947 651590 Tb-159 1.37680E-07 7.88430E-04 65159.82c + 948 651600 Tb-160 5.63950E-06 5.63950E-06 65160.82c + 949 651610 Tb-161 1.21130E-05 3.71860E-04 651610 + 950 651620 Tb-162 1.40740E-05 1.26780E-04 651620 + 951 651630 Tb-163 2.75590E-05 1.24290E-04 651630 + 952 651640 Tb-164 2.77020E-05 4.93110E-05 651640 + 953 651650 Tb-165 3.05400E-05 3.71190E-05 651650 + 954 651660 Tb-166 2.68650E-06 5.37420E-06 651660 + 955 651670 Tb-167 2.20540E-06 2.24560E-06 651670 + 956 651680 Tb-168 7.21270E-07 7.28280E-07 651680 + 957 651690 Tb-169 8.24110E-08 8.27080E-08 651690 + 958 651700 Tb-170 5.88940E-09 5.88940E-09 651700 + 959 651710 Tb-171 2.88300E-10 2.88300E-10 651710 + 960 661590 Dy-159 3.04960E-11 3.04960E-11 661590 + 961 661600 Dy-160 9.41060E-10 5.64040E-06 66160.82c + 962 661610 Dy-161 2.52170E-08 3.71890E-04 66161.82c + 963 661620 Dy-162 1.23220E-07 1.26900E-04 66162.82c + 964 661630 Dy-163 1.35730E-06 1.25650E-04 66163.82c + 965 661640 Dy-164 2.72830E-06 5.20440E-05 66164.82c + 966 661650 Dy-165 6.33130E-06 4.42740E-05 661650 + 967 661651 Dy-165m 8.42980E-07 8.42980E-07 661651 + 968 661660 Dy-166 2.52310E-06 7.89730E-06 661660 + 969 661670 Dy-167 3.53610E-06 5.78170E-06 661670 + 970 661680 Dy-168 6.19750E-06 6.92580E-06 661680 + 971 661690 Dy-169 2.91500E-06 2.99770E-06 661690 + 972 661700 Dy-170 5.24240E-07 5.30130E-07 661700 + 973 661710 Dy-171 1.18180E-07 1.18470E-07 661710 + 974 661720 Dy-172 9.88360E-09 9.88360E-09 661720 + 975 661730 Dy-173 6.37120E-10 6.37120E-10 661730 + 976 671620 Ho-162 9.01900E-12 2.42610E-11 671620 + 977 671621 Ho-162m 2.45840E-11 2.45840E-11 671621 + 978 671630 Ho-163 9.18150E-10 1.04040E-09 671630 + 979 671631 Ho-163m 1.22250E-10 1.22250E-10 671631 + 980 671640 Ho-164 2.67310E-09 9.95940E-09 671640 + 981 671641 Ho-164m 7.28630E-09 7.28630E-09 671641 + 982 671650 Ho-165 6.90490E-08 4.43620E-05 67165.82c + 983 671660 Ho-166 2.83560E-08 7.92560E-06 671660 + 984 671661 Ho-166m 7.72940E-08 7.72940E-08 671661 + 985 671670 Ho-167 2.20510E-06 7.98680E-06 671670 + 986 671680 Ho-168 8.83110E-07 9.27840E-06 671680 + 987 671681 Ho-168m 1.47690E-06 1.47690E-06 671681 + 988 671690 Ho-169 2.39810E-06 5.39580E-06 671690 + 989 671700 Ho-170 2.08650E-06 2.08650E-06 671700 + 990 671701 Ho-170m 7.65450E-07 1.29560E-06 671701 + 991 671710 Ho-171 8.49730E-07 9.68200E-07 671710 + 992 671720 Ho-172 3.01970E-07 3.11850E-07 671720 + 993 671730 Ho-173 5.03470E-08 5.09840E-08 671730 + 994 671740 Ho-174 7.96610E-09 7.96610E-09 671740 + 995 671750 Ho-175 5.49090E-10 5.49090E-10 671750 + 996 681640 Er-164 1.62490E-12 5.15060E-09 68164.82c + 997 681650 Er-165 7.75530E-11 7.75530E-11 681650 + 998 681660 Er-166 3.27650E-10 7.92590E-06 68166.82c + 999 681670 Er-167 4.46080E-09 7.99190E-06 68167.82c + 1000 681671 Er-167m 5.93930E-10 9.54950E-07 681671 + 1001 681680 Er-168 8.80960E-08 9.37400E-06 68168.82c + 1002 681690 Er-169 3.77770E-07 5.77360E-06 681690 + 1003 681700 Er-170 5.90000E-07 3.97200E-06 68170.82c + 1004 681710 Er-171 1.15840E-06 2.12660E-06 681710 + 1005 681720 Er-172 8.90390E-07 1.20220E-06 681720 + 1006 681730 Er-173 5.77090E-07 6.28070E-07 681730 + 1007 681740 Er-174 2.16270E-07 2.24240E-07 681740 + 1008 681750 Er-175 6.52810E-08 6.58300E-08 681750 + 1009 681760 Er-176 8.62620E-09 8.62620E-09 681760 + 1010 681770 Er-177 8.76480E-10 8.76480E-10 681770 + 1011 691670 Tm-167 1.01810E-12 1.01810E-12 691670 + 1012 691680 Tm-168 9.03150E-11 9.03150E-11 691680 + 1013 691690 Tm-169 1.05950E-09 5.77460E-06 691690 + 1014 691700 Tm-170 7.58270E-09 7.58270E-09 691700 + 1015 691710 Tm-171 3.72220E-08 2.16380E-06 691710 + 1016 691720 Tm-172 1.16970E-07 1.31920E-06 691720 + 1017 691730 Tm-173 1.68480E-07 7.96550E-07 691730 + 1018 691740 Tm-174 2.37220E-07 4.61460E-07 691740 + 1019 691750 Tm-175 1.56760E-07 2.22590E-07 691750 + 1020 691760 Tm-176 8.27740E-08 9.14000E-08 691760 + 1021 691770 Tm-177 2.05590E-08 2.14360E-08 691770 + 1022 691780 Tm-178 5.03570E-09 5.03570E-09 691780 + 1023 691790 Tm-179 5.63230E-10 5.63230E-10 691790 + 1024 701700 Yb-170 6.49780E-12 7.57930E-09 701700 + 1025 701710 Yb-171 1.81220E-11 2.16400E-06 701710 + 1026 701711 Yb-171m 1.36110E-10 1.36110E-10 701711 + 1027 701720 Yb-172 1.30410E-09 1.32050E-06 701720 + 1028 701730 Yb-173 8.39650E-09 8.04960E-07 701730 + 1029 701740 Yb-174 2.86680E-08 4.90230E-07 701740 + 1030 701750 Yb-175 6.63050E-08 2.97720E-07 701750 + 1031 701751 Yb-175m 8.82810E-09 1.80220E-07 701751 + 1032 701760 Yb-176 2.79210E-08 1.67470E-07 701760 + 1033 701761 Yb-176m 5.85750E-08 1.04270E-07 701761 + 1034 701770 Yb-177 6.72820E-08 1.02260E-07 701770 + 1035 701771 Yb-177m 1.35470E-08 3.49820E-08 701771 + 1036 701780 Yb-178 4.42730E-08 4.93090E-08 701780 + 1037 701790 Yb-179 2.04120E-08 2.09750E-08 701790 + 1038 701800 Yb-180 4.60440E-09 4.60440E-09 701800 + 1039 701810 Yb-181 7.98540E-10 7.98540E-10 701810 + 1040 711730 Lu-173 6.61330E-12 6.61330E-12 711730 + 1041 711740 Lu-174 2.88310E-11 1.06960E-10 711740 + 1042 711741 Lu-174m 7.85880E-11 7.85880E-11 711741 + 1043 711750 Lu-175 7.41480E-10 2.98470E-07 71175.82c + 1044 711760 Lu-176 2.51230E-09 1.29400E-08 71176.82c + 1045 711761 Lu-176m 1.19760E-09 1.19760E-09 711761 + 1046 711770 Lu-177 5.43040E-09 1.08290E-07 711770 + 1047 711771 Lu-177m 2.58570E-09 2.65010E-09 711771 + 1048 711772 Lu-177m 1.28670E-10 1.28670E-10 711772 + 1049 711780 Lu-178 7.36540E-09 5.66740E-08 711780 + 1050 711781 Lu-178m 9.86760E-09 9.86760E-09 711781 + 1051 711790 Lu-179 1.51460E-08 3.81370E-08 711790 + 1052 711791 Lu-179m 2.01650E-09 2.29920E-08 711791 + 1053 711800 Lu-180 3.91040E-09 1.16300E-08 711800 + 1054 711801 Lu-180m 3.91040E-09 8.51480E-09 711801 + 1055 711802 Lu-180m 6.92420E-09 6.92420E-09 711802 + 1056 711810 Lu-181 5.87920E-09 6.67770E-09 711810 + 1057 711820 Lu-182 2.06700E-09 2.06700E-09 711820 + 1058 711830 Lu-183 3.41220E-10 3.41220E-10 711830 + 1059 711840 Lu-184 5.33680E-11 5.33680E-11 711840 + 1060 721760 Hf-176 1.18160E-11 1.20820E-09 72176.82c + 1061 721770 Hf-177 8.08830E-11 1.10530E-07 72177.82c + 1062 721771 Hf-177m 3.81610E-11 2.15590E-09 721771 + 1063 721772 Hf-177m 2.25620E-12 6.65940E-11 721772 + 1064 721780 Hf-178 2.12840E-10 6.72010E-08 72178.82c + 1065 721781 Hf-178m 3.96930E-10 1.03140E-08 721781 + 1066 721782 Hf-178m 4.96490E-11 4.96490E-11 721782 + 1067 721790 Hf-179 1.60290E-09 4.09130E-08 72179.82c + 1068 721791 Hf-179m 4.63830E-10 4.63830E-10 721791 + 1069 721792 Hf-179m 7.00730E-10 7.00730E-10 721792 + 1070 721800 Hf-180 1.74910E-09 2.47710E-08 72180.82c + 1071 721801 Hf-180m 3.66940E-09 7.13150E-09 721801 + 1072 721810 Hf-181 8.19040E-09 1.48680E-08 721810 + 1073 721820 Hf-182 2.01120E-09 5.85030E-09 721820 + 1074 721821 Hf-182m 4.21930E-09 4.21930E-09 721821 + 1075 721830 Hf-183 4.00220E-09 4.34340E-09 721830 + 1076 721840 Hf-184 4.79160E-10 5.05850E-10 721840 + 1077 721841 Hf-184m 1.00520E-09 1.03190E-09 721841 + 1078 721850 Hf-185 4.43060E-10 4.43060E-10 721850 + 1079 721860 Hf-186 5.79010E-11 5.79010E-11 721860 + 1080 721870 Hf-187 5.82010E-12 5.82010E-12 721870 + 1081 731790 Ta-179 5.68440E-12 7.96690E-12 731790 + 1082 731791 Ta-179m 2.15660E-12 2.28250E-12 731791 + 1083 731800 Ta-180 3.05250E-11 3.05250E-11 731800 + 1084 731801 Ta-180m 4.08950E-11 6.30020E-11 731801 + 1085 731810 Ta-181 2.69600E-10 1.51390E-08 73181.82c + 1086 731820 Ta-182 2.70310E-10 3.28470E-09 73182.82c + 1087 731821 Ta-182m 2.95270E-10 3.01440E-09 731821 + 1088 731822 Ta-182m 2.71900E-10 2.71910E-09 731822 + 1089 731830 Ta-183 1.19430E-09 5.53770E-09 731830 + 1090 731840 Ta-184 1.66380E-09 3.20160E-09 731840 + 1091 731850 Ta-185 6.81410E-10 1.53110E-09 731850 + 1092 731851 Ta-185m 4.06590E-10 4.06590E-10 731851 + 1093 731860 Ta-186 5.68870E-10 6.26770E-10 731860 + 1094 731870 Ta-187 1.39960E-10 1.45780E-10 731870 + 1095 731880 Ta-188 3.40010E-11 3.40010E-11 731880 + 1096 731890 Ta-189 3.76890E-12 3.76890E-12 731890 + 1097 741810 W-181 1.14750E-12 1.14750E-12 741810 + 1098 741820 W-182 9.58000E-12 3.29420E-09 74182.82c + 1099 741830 W-183 1.27450E-11 5.59870E-09 74183.82c + 1100 741831 W-183m 4.82660E-11 2.36550E-10 741831 + 1101 741840 W-184 2.05840E-10 3.40740E-09 74184.82c + 1102 741850 W-185 1.40390E-10 2.06420E-09 741850 + 1103 741851 W-185m 3.92790E-10 3.92790E-10 741851 + 1104 741860 W-186 4.32390E-10 1.23490E-09 74186.82c + 1105 741861 W-186m 1.75070E-10 1.75070E-10 741861 + 1106 741870 W-187 5.62520E-10 7.08300E-10 741870 + 1107 741880 W-188 3.05880E-10 3.39880E-10 741880 + 1108 741890 W-189 1.39950E-10 1.43720E-10 741890 + 1109 741900 W-190 1.33400E-11 3.12120E-11 741900 + 1110 741901 W-190m 1.78720E-11 1.78720E-11 741901 + 1111 741910 W-191 5.35000E-12 5.35000E-12 741910 + 1112 751850 Re-185 5.39630E-12 2.06960E-09 75185.82c + 1113 751860 Re-186 9.98700E-12 9.98700E-12 751860 + 1114 751861 Re-186m 1.67020E-11 1.67020E-11 751861 + 1115 751870 Re-187 5.79840E-11 7.66280E-10 75187.82c + 1116 751880 Re-188 3.26640E-11 4.61580E-10 751880 + 1117 751881 Re-188m 8.90360E-11 8.90360E-11 751881 + 1118 751890 Re-189 1.20250E-10 2.63970E-10 751890 + 1119 751900 Re-190 3.29970E-11 9.57740E-11 751900 + 1120 751901 Re-190m 6.92230E-11 6.92230E-11 751901 + 1121 751910 Re-191 4.03300E-11 4.56800E-11 751910 + 1122 751920 Re-192 1.40720E-11 1.40720E-11 751920 + 1123 751930 Re-193 2.30470E-12 2.30470E-12 751930 + 1124 761880 Os-188 4.77260E-12 4.66350E-10 761880 + 1125 761890 Os-189 4.14690E-12 2.83820E-10 761890 + 1126 761891 Os-189m 1.57040E-11 4.28480E-11 761891 + 1127 761900 Os-190 1.64160E-11 1.71840E-10 761900 + 1128 761901 Os-190m 2.19920E-11 5.96500E-11 761901 + 1129 761910 Os-191 4.54190E-11 1.03090E-10 761910 + 1130 761911 Os-191m 1.19940E-11 1.19940E-11 761911 + 1131 761920 Os-192 1.85300E-11 5.46420E-11 761920 + 1132 761921 Os-192m 2.48260E-11 2.48260E-11 761921 + 1133 761930 Os-193 2.76590E-11 2.99640E-11 761930 + 1134 761940 Os-194 1.01640E-11 1.01640E-11 761940 + 1135 761950 Os-195 3.00220E-12 3.00220E-12 761950 + 1136 771910 Ir-191 5.09720E-13 1.05030E-10 77191.82c + 1137 771911 Ir-191m 1.06490E-12 5.00860E-11 771911 + 1138 771920 Ir-192 1.98690E-12 9.18780E-12 771920 + 1139 771921 Ir-192m 1.98690E-12 1.98690E-12 771921 + 1140 771922 Ir-192m 1.98690E-12 5.21430E-12 771922 + 1141 771930 Ir-193 2.22120E-12 3.84000E-11 77193.82c + 1142 771931 Ir-193m 6.21480E-12 6.31890E-12 771931 + 1143 771940 Ir-194 3.88060E-12 1.79250E-11 771940 + 1144 771941 Ir-194m 3.88060E-12 3.88060E-12 771941 + 1145 771942 Ir-194m 3.88060E-12 3.88060E-12 771942 + 1146 771950 Ir-195 1.98520E-12 5.26510E-12 771950 + 1147 771951 Ir-195m 5.55440E-12 5.55440E-12 771951 + 1148 771960 Ir-196 1.95280E-12 1.95870E-12 771960 + 1149 771961 Ir-196m 1.95280E-12 1.95280E-12 771961 + 1150 781940 Pt-194 1.47450E-12 2.32800E-11 781940 + 1151 781950 Pt-195 9.94750E-13 1.43200E-11 781950 + 1152 781951 Pt-195m 2.78320E-12 4.47180E-12 781951 + 1153 781960 Pt-196 4.26190E-12 8.16750E-12 781960 + 1154 781970 Pt-197 1.03010E-12 3.81710E-12 781970 + 1155 781971 Pt-197m 2.88210E-12 2.88210E-12 781971 + + Nuclide 95642.82c -- americium 242 (Am-242) is using NFY data from Am-242m + + Nuclide 95242.82c -- americium 242m (Am-242m) + + Neutron-induced fission: + + Interpolation region : 1 / 2 + Interpolation energy : 2.53000E-08 MeV + Number of products : 1064 / 1134 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 3.32190E-05 3.32190E-05 1001.82c + 2 10020 H-2 1.01520E-05 1.01520E-05 1002.82c + 3 10030 H-3 1.60000E-04 1.60000E-04 1003.82c + 4 20040 He-4 2.10000E-03 2.10000E-03 2004.82c + 5 200500 Ca-50 4.33200E-12 4.33200E-12 200500 + 6 200510 Ca-51 4.67750E-12 4.67750E-12 200510 + 7 200520 Ca-52 3.48070E-12 3.48070E-12 200520 + 8 200530 Ca-53 1.30580E-12 1.30580E-12 200530 + 9 210500 Sc-50 1.27220E-12 6.08650E-12 210500 + 10 210501 Sc-50m 5.43170E-13 4.87520E-12 210501 + 11 210510 Sc-51 6.63760E-12 1.13850E-11 210510 + 12 210520 Sc-52 1.34420E-11 1.72450E-11 210520 + 13 210530 Sc-53 1.86630E-11 1.95770E-11 210530 + 14 210540 Sc-54 1.44260E-11 1.44260E-11 210540 + 15 210550 Sc-55 8.49790E-12 8.49790E-12 210550 + 16 210560 Sc-56 2.66640E-12 2.66640E-12 210560 + 17 220520 Ti-52 5.80860E-12 2.30530E-11 220520 + 18 220530 Ti-53 2.15670E-11 4.11440E-11 220530 + 19 220540 Ti-54 5.67980E-11 7.12240E-11 220540 + 20 220550 Ti-55 9.36960E-11 1.02190E-10 220550 + 21 220560 Ti-56 1.12910E-10 1.15580E-10 220560 + 22 220570 Ti-57 7.33290E-11 7.33290E-11 220570 + 23 220580 Ti-58 3.13920E-11 3.13920E-11 220580 + 24 220590 Ti-59 7.12310E-12 7.12310E-12 220590 + 25 220600 Ti-60 1.07120E-12 1.07120E-12 220600 + 26 230530 V-53 1.00020E-12 4.21440E-11 230530 + 27 230540 V-54 7.67040E-12 7.88940E-11 230540 + 28 230550 V-55 4.40460E-11 1.46240E-10 230550 + 29 230560 V-56 1.40890E-10 2.56690E-10 230560 + 30 230570 V-57 3.17590E-10 3.90700E-10 230570 + 31 230580 V-58 3.94220E-10 4.25610E-10 230580 + 32 230590 V-59 3.56250E-10 3.63370E-10 230590 + 33 230600 V-60 1.78150E-10 1.79220E-10 230600 + 34 230610 V-61 6.42940E-11 6.42940E-11 230610 + 35 230620 V-62 1.16950E-11 1.16950E-11 230620 + 36 230630 V-63 1.29580E-12 1.29580E-12 230630 + 37 240550 Cr-55 1.54300E-12 1.47780E-10 240550 + 38 240560 Cr-56 1.90400E-11 2.77290E-10 240560 + 39 240570 Cr-57 1.20660E-10 8.50290E-10 240570 + 40 240580 Cr-58 5.11070E-10 5.96190E-10 240580 + 41 240590 Cr-59 1.23320E-09 1.59660E-09 240590 + 42 240600 Cr-60 2.20230E-09 2.38540E-09 240600 + 43 240610 Cr-61 2.39180E-09 2.45220E-09 240610 + 44 240620 Cr-62 1.79140E-09 1.80360E-09 240620 + 45 240630 Cr-63 6.76570E-10 6.77410E-10 240630 + 46 240640 Cr-64 1.68530E-10 1.68530E-10 240640 + 47 240650 Cr-65 2.35390E-11 2.35390E-11 240650 + 48 240660 Cr-66 2.13710E-12 2.13710E-12 240660 + 49 250570 Mn-57 1.56770E-12 8.51850E-10 250570 + 50 250580 Mn-58 1.87170E-11 6.14910E-10 250580 + 51 250581 Mn-58m 2.10740E-12 2.10740E-12 250581 + 52 250590 Mn-59 1.86760E-10 1.78330E-09 250590 + 53 250600 Mn-60 9.21250E-11 2.57160E-09 250600 + 54 250601 Mn-60m 8.18200E-10 8.18200E-10 250601 + 55 250610 Mn-61 3.34790E-09 5.80010E-09 250610 + 56 250620 Mn-62 5.78220E-09 6.68390E-09 250620 + 57 250621 Mn-62m 1.03800E-09 1.93980E-09 250621 + 58 250630 Mn-63 9.52330E-09 1.02010E-08 250630 + 59 250640 Mn-64 7.40280E-09 7.57130E-09 250640 + 60 250650 Mn-65 4.38450E-09 4.40800E-09 250650 + 61 250660 Mn-66 1.38420E-09 1.38630E-09 250660 + 62 250670 Mn-67 2.80450E-10 2.80450E-10 250670 + 63 250680 Mn-68 2.78010E-11 2.78010E-11 250680 + 64 250690 Mn-69 1.92710E-12 1.92710E-12 250690 + 65 260590 Fe-59 1.77260E-12 1.78510E-09 260590 + 66 260600 Fe-60 3.57410E-11 3.33150E-09 260600 + 67 260610 Fe-61 3.97630E-10 6.19780E-09 260610 + 68 260620 Fe-62 2.90630E-09 1.15300E-08 260620 + 69 260630 Fe-63 1.08570E-08 2.10580E-08 260630 + 70 260640 Fe-64 2.87420E-08 3.63130E-08 260640 + 71 260650 Fe-65 4.76360E-08 5.20440E-08 260650 + 72 260660 Fe-66 5.77020E-08 5.90880E-08 260660 + 73 260670 Fe-67 3.77240E-08 3.80050E-08 260670 + 74 260680 Fe-68 1.62580E-08 1.62860E-08 260680 + 75 260690 Fe-69 3.98050E-09 3.98200E-09 260690 + 76 260700 Fe-70 4.65670E-10 4.65670E-10 260700 + 77 260710 Fe-71 1.79640E-11 1.79640E-11 260710 + 78 260720 Fe-72 1.78410E-12 1.78410E-12 260720 + 79 270610 Co-61 1.35930E-12 6.19910E-09 270610 + 80 270620 Co-62 9.92240E-12 1.15400E-08 270620 + 81 270621 Co-62m 2.32410E-11 2.32410E-11 270621 + 82 270630 Co-63 4.95850E-10 2.15540E-08 270630 + 83 270640 Co-64 3.82620E-09 4.01400E-08 270640 + 84 270650 Co-65 2.20890E-08 7.41330E-08 270650 + 85 270660 Co-66 7.10230E-08 1.30110E-07 270660 + 86 270670 Co-67 1.61060E-07 1.99060E-07 270670 + 87 270680 Co-68 1.06830E-07 1.62240E-07 270680 + 88 270681 Co-68m 9.42460E-08 1.10810E-07 270681 + 89 270690 Co-69 1.95890E-07 1.99590E-07 270690 + 90 270700 Co-70 3.80770E-08 3.80770E-08 270700 + 91 270701 Co-70m 3.80770E-08 3.85430E-08 270701 + 92 270710 Co-71 1.30380E-08 1.30560E-08 270710 + 93 270720 Co-72 4.71980E-09 4.72160E-09 270720 + 94 270730 Co-73 5.35670E-10 5.35670E-10 270730 + 95 270740 Co-74 4.46220E-11 4.46220E-11 270740 + 96 280630 Ni-63 1.20780E-12 2.15550E-08 280630 + 97 280640 Ni-64 4.06820E-11 4.01800E-08 28064.82c + 98 280650 Ni-65 7.61760E-10 7.48950E-08 280650 + 99 280660 Ni-66 9.45730E-09 1.39570E-07 280660 + 100 280670 Ni-67 6.03440E-08 2.59410E-07 280670 + 101 280680 Ni-68 2.57150E-07 4.76790E-07 280680 + 102 280690 Ni-69 3.34380E-07 5.31980E-07 280690 + 103 280691 Ni-69m 3.34380E-07 3.34380E-07 280691 + 104 280700 Ni-70 1.34000E-06 1.41660E-06 280700 + 105 280710 Ni-71 4.77460E-07 4.90520E-07 280710 + 106 280720 Ni-72 7.11150E-07 7.15870E-07 280720 + 107 280730 Ni-73 2.74990E-07 2.75530E-07 280730 + 108 280740 Ni-74 1.02850E-07 1.02890E-07 280740 + 109 280750 Ni-75 9.98500E-09 9.98500E-09 280750 + 110 280760 Ni-76 7.70760E-10 7.70760E-10 280760 + 111 280770 Ni-77 5.12740E-11 5.12740E-11 280770 + 112 290660 Cu-66 2.83830E-11 1.39600E-07 290660 + 113 290670 Cu-67 7.71440E-10 2.60180E-07 290670 + 114 290680 Cu-68 3.08740E-09 4.85950E-07 290680 + 115 290681 Cu-68m 7.23160E-09 7.23160E-09 290681 + 116 290690 Cu-69 9.40250E-07 1.80660E-06 290690 + 117 290700 Cu-70 2.87850E-08 2.25260E-07 290700 + 118 290701 Cu-70m 3.20680E-07 3.92950E-07 290701 + 119 290702 Cu-70m 2.87850E-08 1.44540E-06 290702 + 120 290710 Cu-71 1.24200E-06 1.73250E-06 290710 + 121 290720 Cu-72 1.56510E-06 2.28100E-06 290720 + 122 290730 Cu-73 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4.34850E-02 41095.82c + 359 410951 Nb-95m 1.21630E-06 4.71220E-04 410951 + 360 410960 Nb-96 6.97790E-05 6.97790E-05 410960 + 361 410970 Nb-97 4.07160E-04 5.00020E-02 410970 + 362 410971 Nb-97m 9.41440E-05 4.71440E-02 410971 + 363 410980 Nb-98 4.76420E-04 5.78270E-02 410980 + 364 410981 Nb-98m 1.43770E-03 1.43770E-03 410981 + 365 410990 Nb-99 6.25060E-03 3.59890E-02 410990 + 366 410991 Nb-99m 1.44530E-03 1.85460E-02 410991 + 367 411000 Nb-100 2.87050E-03 4.15360E-02 411000 + 368 411001 Nb-100m 1.20720E-02 1.20720E-02 411001 + 369 411010 Nb-101 2.99530E-02 5.07970E-02 411010 + 370 411020 Nb-102 1.40790E-02 2.55610E-02 411020 + 371 411021 Nb-102m 1.40790E-02 1.40790E-02 411021 + 372 411030 Nb-103 2.47570E-02 2.78990E-02 411030 + 373 411040 Nb-104 6.30150E-03 7.22510E-03 411040 + 374 411041 Nb-104m 6.30150E-03 6.30150E-03 411041 + 375 411050 Nb-105 6.85160E-03 6.98020E-03 411050 + 376 411060 Nb-106 2.18050E-03 2.20430E-03 411060 + 377 411070 Nb-107 5.29330E-04 5.31490E-04 411070 + 378 411080 Nb-108 7.46460E-05 7.46460E-05 411080 + 379 411090 Nb-109 1.07890E-05 1.07890E-05 411090 + 380 411100 Nb-110 1.16810E-09 1.16810E-09 411100 + 381 420960 Mo-96 1.74080E-09 6.97810E-05 42096.82c + 382 420970 Mo-97 2.32390E-06 5.00050E-02 42097.82c + 383 420980 Mo-98 6.07270E-05 5.93250E-02 42098.82c + 384 420990 Mo-99 3.75860E-04 5.45400E-02 42099.82c + 385 421000 Mo-100 2.17200E-03 5.57800E-02 42100.82c + 386 421010 Mo-101 6.53360E-03 5.73310E-02 421010 + 387 421020 Mo-102 1.93590E-02 5.89990E-02 421020 + 388 421030 Mo-103 2.59720E-02 5.38790E-02 421030 + 389 421040 Mo-104 3.54060E-02 4.90440E-02 421040 + 390 421050 Mo-105 2.60640E-02 3.30250E-02 421050 + 391 421060 Mo-106 2.17530E-02 2.38900E-02 421060 + 392 421070 Mo-107 8.20660E-03 8.71080E-03 421070 + 393 421080 Mo-108 3.47470E-03 3.54610E-03 421080 + 394 421090 Mo-109 7.58980E-04 7.68400E-04 421090 + 395 421100 Mo-110 1.34980E-04 1.34980E-04 421100 + 396 421110 Mo-111 7.36610E-06 7.36610E-06 421110 + 397 421120 Mo-112 7.14860E-07 7.14860E-07 421120 + 398 430990 Tc-99 8.45820E-07 5.45390E-02 43099.82c + 399 430991 Tc-99m 1.95580E-07 4.80280E-02 430991 + 400 431000 Tc-100 9.03170E-06 9.03170E-06 431000 + 401 431010 Tc-101 1.13410E-04 5.74440E-02 431010 + 402 431020 Tc-102 2.76280E-04 5.92750E-02 431020 + 403 431021 Tc-102m 2.76280E-04 2.76280E-04 431021 + 404 431030 Tc-103 2.49190E-03 5.63700E-02 431030 + 405 431040 Tc-104 6.09490E-03 5.51390E-02 431040 + 406 431050 Tc-105 1.57810E-02 4.88060E-02 431050 + 407 431060 Tc-106 2.18980E-02 4.57880E-02 431060 + 408 431070 Tc-107 2.40100E-02 3.27210E-02 431070 + 409 431080 Tc-108 1.60510E-02 1.96010E-02 431080 + 410 431090 Tc-109 1.06430E-02 1.14070E-02 431090 + 411 431100 Tc-110 4.27730E-03 4.41240E-03 431100 + 412 431110 Tc-111 1.26930E-03 1.27660E-03 431110 + 413 431120 Tc-112 2.00020E-04 2.00720E-04 431120 + 414 431130 Tc-113 2.43160E-05 2.43160E-05 431130 + 415 431140 Tc-114 1.33330E-06 1.33330E-06 431140 + 416 431150 Tc-115 4.42570E-11 4.42570E-11 431150 + 417 441010 Ru-101 1.85900E-09 5.74440E-02 44101.82c + 418 441020 Ru-102 6.84490E-06 5.95580E-02 44102.82c + 419 441030 Ru-103 1.75190E-05 5.64300E-02 44103.82c + 420 441031 Ru-103m 4.22920E-05 4.22920E-05 441031 + 421 441040 Ru-104 3.59380E-04 5.54980E-02 44104.82c + 422 441050 Ru-105 1.34090E-03 5.01470E-02 44105.82c + 423 441060 Ru-106 5.17620E-03 5.09640E-02 44106.82c + 424 441070 Ru-107 8.08950E-03 4.08100E-02 441070 + 425 441080 Ru-108 1.50080E-02 3.46180E-02 441080 + 426 441090 Ru-109 1.41670E-02 2.55670E-02 441090 + 427 441100 Ru-110 1.29820E-02 1.73930E-02 441100 + 428 441110 Ru-111 5.85810E-03 7.13770E-03 441110 + 429 441120 Ru-112 2.48380E-03 2.68330E-03 441120 + 430 441130 Ru-113 2.77730E-04 4.39250E-04 441130 + 431 441131 Ru-113m 2.77730E-04 2.77730E-04 441131 + 432 441140 Ru-114 1.82180E-04 1.83430E-04 441140 + 433 441150 Ru-115 3.91020E-05 3.91020E-05 441150 + 434 441160 Ru-116 1.82370E-05 1.82370E-05 441160 + 435 441170 Ru-117 4.41620E-06 4.41620E-06 441170 + 436 441180 Ru-118 3.29940E-06 3.29940E-06 441180 + 437 451040 Rh-104 7.97850E-07 3.20240E-06 451040 + 438 451041 Rh-104m 2.40770E-06 2.40770E-06 451041 + 439 451050 Rh-105 5.51520E-06 5.01530E-02 45105.82c + 440 451051 Rh-105m 8.43110E-07 1.42360E-02 451051 + 441 451060 Rh-106 2.08810E-05 5.09850E-02 451060 + 442 451061 Rh-106m 4.89080E-05 4.89080E-05 451061 + 443 451070 Rh-107 3.75920E-04 4.11860E-02 451070 + 444 451080 Rh-108 2.87480E-04 3.49060E-02 451080 + 445 451081 Rh-108m 8.67520E-04 8.67520E-04 451081 + 446 451090 Rh-109 3.06530E-03 2.86320E-02 451090 + 447 451100 Rh-110 4.48710E-03 2.18800E-02 451100 + 448 451101 Rh-110m 1.19780E-04 1.19780E-04 451101 + 449 451110 Rh-111 5.85200E-03 1.29900E-02 451110 + 450 451120 Rh-112 2.02150E-03 4.70480E-03 451120 + 451 451121 Rh-112m 2.02150E-03 2.02150E-03 451121 + 452 451130 Rh-113 2.50350E-03 3.08160E-03 451130 + 453 451140 Rh-114 4.48120E-04 6.31630E-04 451140 + 454 451141 Rh-114m 4.48120E-04 4.48120E-04 451141 + 455 451150 Rh-115 2.99400E-04 3.38610E-04 451150 + 456 451160 Rh-116 2.38480E-05 4.19780E-05 451160 + 457 451161 Rh-116m 5.58580E-05 5.58580E-05 451161 + 458 451170 Rh-117 2.83570E-05 3.28180E-05 451170 + 459 451180 Rh-118 4.61910E-06 7.78290E-06 451180 + 460 451190 Rh-119 3.16660E-10 3.16660E-10 451190 + 461 451200 Rh-120 4.97130E-12 4.97130E-12 451200 + 462 451220 Rh-122 3.44110E-09 3.44110E-09 451220 + 463 461060 Pd-106 1.78460E-09 5.10340E-02 46106.82c + 464 461070 Pd-107 7.78510E-07 4.11890E-02 46107.82c + 465 461071 Pd-107m 1.46310E-06 1.46310E-06 461071 + 466 461080 Pd-108 2.61870E-05 3.57990E-02 46108.82c + 467 461090 Pd-109 4.25160E-05 2.87550E-02 461090 + 468 461091 Pd-109m 7.99040E-05 1.43960E-02 461091 + 469 461100 Pd-110 4.24790E-04 2.24240E-02 46110.82c + 470 461110 Pd-111 2.26260E-04 1.35120E-02 461110 + 471 461111 Pd-111m 4.25210E-04 4.77170E-04 461111 + 472 461120 Pd-112 1.24240E-03 7.96870E-03 461120 + 473 461130 Pd-113 3.05520E-04 4.12470E-03 461130 + 474 461131 Pd-113m 7.37580E-04 7.37580E-04 461131 + 475 461140 Pd-114 8.20820E-04 1.90060E-03 461140 + 476 461150 Pd-115 1.22240E-04 4.34000E-04 461150 + 477 461151 Pd-115m 2.29730E-04 2.78900E-04 461151 + 478 461160 Pd-116 1.90400E-04 2.88240E-04 461160 + 479 461170 Pd-117 2.62930E-05 1.08750E-04 461170 + 480 461171 Pd-117m 4.94150E-05 4.94150E-05 461171 + 481 461180 Pd-118 2.04550E-05 2.80110E-05 461180 + 482 461190 Pd-119 6.73520E-06 6.73550E-06 461190 + 483 461200 Pd-120 1.28890E-06 1.28890E-06 461200 + 484 461210 Pd-121 6.86900E-07 6.86900E-07 461210 + 485 461220 Pd-122 7.13040E-07 7.16480E-07 461220 + 486 461230 Pd-123 4.57070E-07 4.57070E-07 461230 + 487 461240 Pd-124 6.31110E-08 6.31110E-08 461240 + 488 471090 Ag-109 1.02210E-07 2.87550E-02 47109.82c + 489 471091 Ag-109m 6.68630E-07 2.87410E-02 471091 + 490 471100 Ag-110 7.01710E-07 7.24070E-07 471100 + 491 471101 Ag-110m 1.64360E-06 1.64360E-06 47510.82c + 492 471110 Ag-111 1.95520E-06 1.35880E-02 47111.82c + 493 471111 Ag-111m 1.27900E-05 1.35220E-02 471111 + 494 471120 Ag-112 3.36510E-05 8.00230E-03 471120 + 495 471130 Ag-113 1.15170E-05 2.76250E-03 471130 + 496 471131 Ag-113m 7.53400E-05 4.02510E-03 471131 + 497 471140 Ag-114 1.95400E-05 2.00230E-03 471140 + 498 471141 Ag-114m 8.21800E-05 8.21800E-05 471141 + 499 471150 Ag-115 1.49590E-05 4.30810E-04 471150 + 500 471151 Ag-115m 9.78510E-05 4.71610E-04 471151 + 501 471160 Ag-116 2.68120E-05 3.18820E-04 471160 + 502 471161 Ag-116m 6.28010E-05 6.28010E-05 471161 + 503 471170 Ag-117 1.21520E-05 7.45610E-05 471170 + 504 471171 Ag-117m 7.94920E-05 1.33870E-04 471171 + 505 471180 Ag-118 1.42050E-05 6.43470E-05 471180 + 506 471181 Ag-118m 5.97410E-05 6.37450E-05 471181 + 507 471190 Ag-119 9.01720E-06 1.23850E-05 471190 + 508 471191 Ag-119m 5.89860E-05 6.23540E-05 471191 + 509 471200 Ag-120 1.14500E-05 1.83460E-05 471200 + 510 471201 Ag-120m 1.62470E-05 1.68910E-05 471201 + 511 471210 Ag-121 2.74570E-05 2.81420E-05 471210 + 512 471220 Ag-122 3.37560E-06 4.09200E-06 471220 + 513 471221 Ag-122m 3.04060E-06 3.04060E-06 471221 + 514 471230 Ag-123 1.25450E-05 1.30020E-05 471230 + 515 471240 Ag-124 4.44390E-06 6.50840E-06 471240 + 516 471241 Ag-124m 4.00290E-06 4.00290E-06 471241 + 517 471250 Ag-125 4.67580E-06 4.67580E-06 471250 + 518 471260 Ag-126 1.54210E-06 1.54210E-06 471260 + 519 471270 Ag-127 1.07960E-07 1.07960E-07 471270 + 520 471280 Ag-128 5.90060E-09 5.90060E-09 471280 + 521 471290 Ag-129 3.12490E-10 3.12490E-10 471290 + 522 481110 Cd-111 1.04380E-10 1.36560E-02 48111.82c + 523 481111 Cd-111m 3.41480E-10 3.41480E-10 481111 + 524 481120 Cd-112 1.42990E-06 8.00370E-03 48112.82c + 525 481130 Cd-113 1.58250E-07 4.16400E-03 48113.82c + 526 481131 Cd-113m 5.17750E-07 4.82790E-05 481131 + 527 481140 Cd-114 2.00020E-06 2.00430E-03 48114.82c + 528 481150 Cd-115 1.50380E-06 7.69220E-04 481150 + 529 481151 Cd-115m 4.92000E-06 4.05920E-05 48515.82c + 530 481160 Cd-116 8.81770E-06 3.86670E-04 48116.82c + 531 481170 Cd-117 4.13940E-06 1.60740E-04 481170 + 532 481171 Cd-117m 1.35430E-05 5.73360E-05 481171 + 533 481180 Cd-118 2.64200E-05 1.28380E-04 481180 + 534 481190 Cd-119 1.28320E-05 8.13790E-05 481190 + 535 481191 Cd-119m 3.09790E-05 3.71720E-05 481191 + 536 481200 Cd-120 5.73710E-05 8.63580E-05 481200 + 537 481210 Cd-121 1.83070E-05 4.35080E-05 481210 + 538 481211 Cd-121m 4.41940E-05 4.71350E-05 481211 + 539 481220 Cd-122 6.41270E-05 7.12600E-05 481220 + 540 481230 Cd-123 1.72800E-05 2.79210E-05 481230 + 541 481231 Cd-123m 4.17170E-05 4.40840E-05 481231 + 542 481240 Cd-124 1.28630E-04 1.37130E-04 481240 + 543 481250 Cd-125 4.22480E-05 4.45860E-05 481250 + 544 481251 Cd-125m 1.01990E-04 1.04330E-04 481251 + 545 481260 Cd-126 1.30850E-04 1.32390E-04 481260 + 546 481270 Cd-127 5.18830E-05 5.19910E-05 481270 + 547 481280 Cd-128 3.29440E-05 3.29500E-05 481280 + 548 481290 Cd-129 1.78780E-06 1.78800E-06 481290 + 549 481291 Cd-129m 4.31610E-06 4.31620E-06 481291 + 550 481300 Cd-130 1.31640E-07 1.31640E-07 481300 + 551 481310 Cd-131 5.19740E-09 5.19740E-09 481310 + 552 491140 In-114 7.69800E-11 3.01120E-10 491140 + 553 491141 In-114m 1.17990E-10 2.32270E-10 491141 + 554 491142 In-114m 1.14280E-10 1.14280E-10 491142 + 555 491150 In-115 4.74490E-09 7.71360E-04 49115.82c + 556 491151 In-115m 1.09710E-09 7.69230E-04 491151 + 557 491160 In-116 1.60650E-08 1.60650E-08 491160 + 558 491161 In-116m 2.46240E-08 4.84740E-08 491161 + 559 491162 In-116m 2.38500E-08 2.38500E-08 491162 + 560 491170 In-117 5.12600E-07 1.40260E-04 491170 + 561 491171 In-117m 1.18530E-07 1.48300E-04 491171 + 562 491180 In-118 3.28600E-07 1.28710E-04 491180 + 563 491181 In-118m 5.03660E-07 9.84640E-07 491181 + 564 491182 In-118m 4.87810E-07 4.87810E-07 491182 + 565 491190 In-119 3.83050E-06 5.30010E-05 491190 + 566 491191 In-119m 8.85700E-07 7.44340E-05 491191 + 567 491200 In-120 3.43770E-06 8.97960E-05 491200 + 568 491201 In-120m 3.43770E-06 3.43770E-06 491201 + 569 491202 In-120m 3.43770E-06 3.43770E-06 491202 + 570 491210 In-121 2.34470E-05 8.56460E-05 491210 + 571 491211 In-121m 5.42140E-06 3.42760E-05 491211 + 572 491220 In-122 2.18260E-05 9.30860E-05 491220 + 573 491221 In-122m 1.54850E-05 1.54850E-05 491221 + 574 491222 In-122m 1.54850E-05 1.54850E-05 491222 + 575 491230 In-123 7.79800E-05 1.30180E-04 491230 + 576 491231 In-123m 1.80310E-05 3.78420E-05 491231 + 577 491240 In-124 8.32290E-05 2.20360E-04 491240 + 578 491241 In-124m 7.49710E-05 7.49710E-05 491241 + 579 491250 In-125 3.74210E-04 4.99870E-04 491250 + 580 491251 In-125m 8.65250E-05 1.09770E-04 491251 + 581 491260 In-126 3.88700E-04 5.21100E-04 491260 + 582 491261 In-126m 3.50140E-04 3.50140E-04 491261 + 583 491270 In-127 1.04840E-03 1.04840E-03 491270 + 584 491271 In-127m 2.42410E-04 2.94400E-04 491271 + 585 491280 In-128 4.14810E-04 6.16600E-04 491280 + 586 491281 In-128m 1.68850E-04 2.01800E-04 491281 + 587 491282 In-128m 5.25740E-04 5.25740E-04 491282 + 588 491290 In-129 6.45020E-04 6.49340E-04 491290 + 589 491291 In-129m 1.49140E-04 1.50930E-04 491291 + 590 491300 In-130 7.64650E-05 7.65920E-05 491300 + 591 491301 In-130m 8.54040E-05 8.54040E-05 491301 + 592 491302 In-130m 1.45310E-04 1.45310E-04 491302 + 593 491310 In-131 2.90190E-05 2.93190E-05 491310 + 594 491311 In-131m 2.90190E-05 2.90190E-05 491311 + 595 491312 In-131m 2.90190E-05 2.90190E-05 491312 + 596 491320 In-132 4.26700E-06 4.26700E-06 491320 + 597 491330 In-133 3.77750E-08 4.65090E-08 491330 + 598 491331 In-133m 8.73440E-09 8.73440E-09 491331 + 599 491340 In-134 1.49210E-09 1.49210E-09 491340 + 600 501160 Sn-116 1.33520E-11 6.45530E-08 50116.82c + 601 501170 Sn-117 6.97800E-11 2.18710E-04 50117.82c + 602 501171 Sn-117m 2.28300E-10 4.78100E-07 501171 + 603 501180 Sn-118 6.24340E-09 1.29700E-04 50118.82c + 604 501190 Sn-119 2.42970E-08 1.23370E-04 50119.82c + 605 501191 Sn-119m 7.94930E-08 4.79610E-05 501191 + 606 501200 Sn-120 9.26650E-07 9.75990E-05 50120.82c + 607 501210 Sn-121 1.00630E-06 1.20230E-04 501210 + 608 501211 Sn-121m 2.42920E-06 1.21320E-05 501211 + 609 501220 Sn-122 7.13400E-06 1.31190E-04 50122.82c + 610 501230 Sn-123 1.41130E-05 2.40380E-05 50123.82c + 611 501231 Sn-123m 5.84600E-06 1.63940E-04 501231 + 612 501240 Sn-124 6.32090E-05 3.58540E-04 50124.82c + 613 501250 Sn-125 1.22280E-04 2.06720E-04 50125.82c + 614 501251 Sn-125m 5.06510E-05 5.75860E-04 501251 + 615 501260 Sn-126 7.71900E-04 1.64520E-03 50126.82c + 616 501270 Sn-127 1.37180E-03 1.78050E-03 501270 + 617 501271 Sn-127m 5.68260E-04 1.50040E-03 501271 + 618 501280 Sn-128 1.51500E-03 6.20600E-03 501280 + 619 501281 Sn-128m 3.54860E-03 4.07430E-03 501281 + 620 501290 Sn-129 1.53160E-03 2.26280E-03 501290 + 621 501291 Sn-129m 3.69740E-03 3.76660E-03 501291 + 622 501300 Sn-130 1.57700E-03 1.77710E-03 501300 + 623 501301 Sn-130m 3.69380E-03 3.80170E-03 501301 + 624 501310 Sn-131 9.65960E-04 1.02220E-03 501310 + 625 501311 Sn-131m 2.33200E-03 2.36220E-03 501311 + 626 501320 Sn-132 9.98370E-04 1.00270E-03 501320 + 627 501330 Sn-133 1.34970E-04 1.34980E-04 501330 + 628 501340 Sn-134 1.44990E-05 1.45000E-05 501340 + 629 501350 Sn-135 4.35470E-07 4.35470E-07 501350 + 630 501360 Sn-136 1.16460E-08 1.16460E-08 501360 + 631 511190 Sb-119 1.53370E-11 2.02120E-11 511190 + 632 511191 Sb-119m 4.87510E-12 4.87510E-12 511191 + 633 511200 Sb-120 2.65110E-10 2.65110E-10 511200 + 634 511201 Sb-120m 3.76190E-10 3.76190E-10 511201 + 635 511210 Sb-121 2.14270E-08 1.22970E-04 51121.82c + 636 511230 Sb-123 4.43180E-06 1.92410E-04 51123.82c + 637 511240 Sb-124 2.74650E-06 6.45180E-06 51124.82c + 638 511241 Sb-124m 2.10010E-06 4.94040E-06 511241 + 639 511242 Sb-124m 2.84030E-06 2.84030E-06 511242 + 640 511250 Sb-125 2.65570E-05 8.09130E-04 51125.82c + 641 511260 Sb-126 2.46120E-05 3.04910E-05 51126.82c + 642 511261 Sb-126m 1.81970E-05 4.19960E-05 511261 + 643 511262 Sb-126m 2.37990E-05 2.37990E-05 511262 + 644 511270 Sb-127 3.30280E-04 3.61110E-03 511270 + 645 511280 Sb-128 3.88090E-04 6.61790E-03 511280 + 646 511281 Sb-128m 6.62210E-04 6.62210E-04 511281 + 647 511290 Sb-129 3.31880E-03 8.05150E-03 511290 + 648 511291 Sb-129m 2.02810E-03 3.91130E-03 511291 + 649 511300 Sb-130 5.41950E-03 9.09740E-03 511300 + 650 511301 Sb-130m 5.41950E-03 7.32040E-03 511301 + 651 511310 Sb-131 2.17400E-02 2.51240E-02 511310 + 652 511320 Sb-132 7.11680E-03 8.11950E-03 511320 + 653 511321 Sb-132m 5.24520E-03 5.24520E-03 511321 + 654 511330 Sb-133 1.06650E-02 1.08020E-02 511330 + 655 511340 Sb-134 9.20550E-04 9.32630E-04 511340 + 656 511341 Sb-134m 2.15610E-03 2.15620E-03 511341 + 657 511350 Sb-135 6.83190E-04 6.83540E-04 511350 + 658 511360 Sb-136 1.21890E-04 1.21900E-04 511360 + 659 511370 Sb-137 1.43810E-05 1.43810E-05 511370 + 660 511380 Sb-138 6.20580E-08 6.20580E-08 511380 + 661 511390 Sb-139 1.33970E-09 1.33970E-09 511390 + 662 521210 Te-121 9.35580E-13 3.65060E-12 521210 + 663 521211 Te-121m 3.06090E-12 3.06090E-12 521211 + 664 521250 Te-125 1.85050E-11 8.09130E-04 52125.82c + 665 521251 Te-125m 6.05440E-11 1.81060E-04 521251 + 666 521260 Te-126 2.31400E-06 6.89220E-05 52126.82c + 667 521270 Te-127 1.59460E-06 3.60220E-03 521270 + 668 521271 Te-127m 3.84950E-06 5.98950E-04 52527.82c + 669 521280 Te-128 4.89290E-05 7.30520E-03 52128.82c + 670 521290 Te-129 8.06440E-05 9.88380E-03 521290 + 671 521291 Te-129m 1.94690E-04 4.77760E-03 52529.82c + 672 521300 Te-130 2.06790E-03 1.84860E-02 52130.82c + 673 521310 Te-131 2.09700E-03 2.66950E-02 521310 + 674 521311 Te-131m 5.06250E-03 7.07400E-03 521311 + 675 521320 Te-132 1.87700E-02 3.21350E-02 52132.82c + 676 521330 Te-133 8.98820E-03 2.20480E-02 521330 + 677 521331 Te-133m 2.16990E-02 2.35670E-02 521331 + 678 521340 Te-134 2.88520E-02 3.20460E-02 521340 + 679 521350 Te-135 9.16160E-03 9.75770E-03 521350 + 680 521360 Te-136 5.08340E-03 5.19210E-03 521360 + 681 521370 Te-137 1.03390E-03 1.04120E-03 521370 + 682 521380 Te-138 2.50280E-04 2.50340E-04 521380 + 683 521390 Te-139 1.62810E-05 1.62820E-05 521390 + 684 521400 Te-140 2.15550E-06 2.15550E-06 521400 + 685 521410 Te-141 1.19080E-08 1.19080E-08 521410 + 686 531280 I-128 3.31910E-09 3.31910E-09 531280 + 687 531290 I-129 1.52740E-06 1.16530E-02 53129.82c + 688 531300 I-130 1.87010E-05 2.54080E-05 53130.82c + 689 531301 I-130m 7.98420E-06 7.98420E-06 531301 + 690 531310 I-131 2.47740E-04 3.25320E-02 53131.82c + 691 531320 I-132 5.37780E-04 3.30130E-02 531320 + 692 531321 I-132m 3.96360E-04 3.96360E-04 531321 + 693 531330 I-133 4.54600E-03 4.88150E-02 531330 + 694 531331 I-133m 2.77800E-03 2.77800E-03 531331 + 695 531340 I-134 1.29650E-02 5.43480E-02 531340 + 696 531341 I-134m 9.55570E-03 9.55570E-03 531341 + 697 531350 I-135 4.99620E-02 5.97200E-02 53135.82c + 698 531360 I-136 1.03160E-02 1.55240E-02 531360 + 699 531361 I-136m 2.41630E-02 2.41780E-02 531361 + 700 531370 I-137 2.01950E-02 2.12210E-02 531370 + 701 531380 I-138 9.19880E-03 9.43340E-03 531380 + 702 531390 I-139 4.06640E-03 4.08270E-03 531390 + 703 531400 I-140 1.06480E-03 1.06700E-03 531400 + 704 531410 I-141 2.40320E-04 2.40330E-04 531410 + 705 531420 I-142 1.98070E-05 1.98070E-05 531420 + 706 531430 I-143 5.15850E-08 5.15850E-08 531430 + 707 531440 I-144 1.13000E-09 1.13000E-09 531440 + 708 541300 Xe-130 1.25370E-09 2.66860E-05 54130.82c + 709 541310 Xe-131 3.50130E-08 3.25320E-02 54131.82c + 710 541311 Xe-131m 8.45270E-08 3.53440E-04 541311 + 711 541320 Xe-132 3.33740E-06 3.30760E-02 54132.82c + 712 541321 Xe-132m 3.78310E-06 3.78310E-06 541321 + 713 541330 Xe-133 3.09920E-05 4.89210E-02 54133.82c + 714 541331 Xe-133m 7.48180E-05 1.46430E-03 541331 + 715 541340 Xe-134 2.88600E-04 5.55320E-02 54134.82c + 716 541341 Xe-134m 6.75970E-04 8.95750E-04 541341 + 717 541350 Xe-135 1.33710E-03 6.42060E-02 54135.82c + 718 541351 Xe-135m 3.22800E-03 1.30870E-02 541351 + 719 541360 Xe-136 2.70130E-02 6.80950E-02 54136.82c + 720 541370 Xe-137 3.09000E-02 5.12420E-02 541370 + 721 541380 Xe-138 3.48360E-02 4.41700E-02 541380 + 722 541390 Xe-139 1.40910E-02 1.78730E-02 541390 + 723 541400 Xe-140 1.10900E-02 1.21080E-02 541400 + 724 541410 Xe-141 4.92120E-03 5.11600E-03 541410 + 725 541420 Xe-142 1.49130E-03 1.50620E-03 541420 + 726 541430 Xe-143 2.21770E-04 2.21800E-04 541430 + 727 541440 Xe-144 3.86080E-05 3.86090E-05 541440 + 728 541450 Xe-145 3.56290E-06 3.56290E-06 541450 + 729 541460 Xe-146 7.44100E-09 7.44100E-09 541460 + 730 551330 Cs-133 1.70060E-06 4.89230E-02 55133.82c + 731 551340 Cs-134 1.47470E-06 2.56150E-06 55134.82c + 732 551341 Cs-134m 1.08680E-06 1.08680E-06 551341 + 733 551350 Cs-135 3.90020E-05 6.43480E-02 55135.82c + 734 551351 Cs-135m 2.38330E-05 2.38330E-05 551351 + 735 551360 Cs-136 3.42570E-04 4.42950E-04 55136.82c + 736 551361 Cs-136m 2.00760E-04 2.00760E-04 551361 + 737 551370 Cs-137 5.29400E-03 5.65360E-02 55137.82c + 738 551380 Cs-138 7.05880E-03 5.93410E-02 551380 + 739 551381 Cs-138m 1.00160E-02 1.00160E-02 551381 + 740 551390 Cs-139 3.16490E-02 4.95220E-02 551390 + 741 551400 Cs-140 3.25230E-02 4.46330E-02 551400 + 742 551410 Cs-141 3.91040E-02 4.42230E-02 551410 + 743 551420 Cs-142 1.89120E-02 2.04150E-02 551420 + 744 551430 Cs-143 1.05870E-02 1.08080E-02 551430 + 745 551440 Cs-144 2.13390E-03 3.23850E-03 551440 + 746 551441 Cs-144m 2.13390E-03 2.13400E-03 551441 + 747 551450 Cs-145 1.20940E-03 1.21280E-03 551450 + 748 551460 Cs-146 2.02190E-04 2.02200E-04 551460 + 749 551470 Cs-147 4.40530E-05 4.40530E-05 551470 + 750 551480 Cs-148 5.30900E-06 5.30900E-06 551480 + 751 551490 Cs-149 6.00120E-10 6.00120E-10 551490 + 752 561350 Ba-135 1.12880E-09 3.85390E-09 56135.82c + 753 561351 Ba-135m 2.72510E-09 2.72510E-09 561351 + 754 561360 Ba-136 5.35210E-07 5.45120E-04 56136.82c + 755 561361 Ba-136m 1.25360E-06 1.25360E-06 561361 + 756 561370 Ba-137 8.19740E-06 5.65640E-02 56137.82c + 757 561371 Ba-137m 1.97900E-05 5.33890E-02 561371 + 758 561380 Ba-138 4.73640E-04 6.17180E-02 56138.82c + 759 561390 Ba-139 1.69680E-03 5.12190E-02 561390 + 760 561400 Ba-140 7.48640E-03 5.21200E-02 56140.82c + 761 561410 Ba-141 1.28320E-02 5.70550E-02 561410 + 762 561420 Ba-142 2.76120E-02 4.82040E-02 561420 + 763 561430 Ba-143 2.30940E-02 3.38280E-02 561430 + 764 561440 Ba-144 1.83550E-02 2.27300E-02 561440 + 765 561450 Ba-145 8.36430E-03 9.43240E-03 561450 + 766 561460 Ba-146 4.19000E-03 4.37600E-03 561460 + 767 561470 Ba-147 1.15150E-03 1.18430E-03 561470 + 768 561480 Ba-148 2.58010E-04 2.61990E-04 561480 + 769 561490 Ba-149 2.38270E-05 2.38280E-05 561490 + 770 561500 Ba-150 5.41710E-06 5.41710E-06 561500 + 771 561510 Ba-151 3.59480E-09 3.59480E-09 561510 + 772 571380 La-138 2.10960E-06 2.10960E-06 57138.82c + 773 571390 La-139 2.35770E-05 5.12420E-02 57139.82c + 774 571400 La-140 1.65350E-04 5.22850E-02 57140.82c + 775 571410 La-141 1.09690E-03 5.81520E-02 571410 + 776 571420 La-142 2.54270E-03 5.07470E-02 571420 + 777 571430 La-143 1.11090E-02 4.49370E-02 571430 + 778 571440 La-144 2.02770E-02 4.30070E-02 571440 + 779 571450 La-145 3.09900E-02 4.04220E-02 571450 + 780 571460 La-146 7.79060E-03 1.21670E-02 571460 + 781 571461 La-146m 1.40130E-02 1.40130E-02 571461 + 782 571470 La-147 1.73950E-02 1.85800E-02 571470 + 783 571480 La-148 7.78750E-03 8.04850E-03 571480 + 784 571490 La-149 3.27280E-03 3.29650E-03 571490 + 785 571500 La-150 7.73080E-04 7.78500E-04 571500 + 786 571510 La-151 1.22090E-04 1.22090E-04 571510 + 787 571520 La-152 1.04350E-05 1.04350E-05 571520 + 788 571530 La-153 1.12070E-08 1.12070E-08 571530 + 789 571540 La-154 1.50340E-10 1.50340E-10 571540 + 790 581400 Ce-140 3.58530E-09 5.22850E-02 58140.82c + 791 581410 Ce-141 5.92990E-06 5.81580E-02 58141.82c + 792 581420 Ce-142 3.53130E-05 5.07820E-02 58142.82c + 793 581430 Ce-143 1.41360E-04 4.50790E-02 58143.82c + 794 581440 Ce-144 9.71870E-04 4.39790E-02 58144.82c + 795 581450 Ce-145 2.88490E-03 4.33070E-02 581450 + 796 581460 Ce-146 8.76760E-03 3.49480E-02 581460 + 797 581470 Ce-147 1.15130E-02 3.00930E-02 581470 + 798 581480 Ce-148 1.45600E-02 2.26550E-02 581480 + 799 581490 Ce-149 8.52650E-03 1.17980E-02 581490 + 800 581500 Ce-150 5.28160E-03 6.03910E-03 581500 + 801 581510 Ce-151 1.85340E-03 1.97610E-03 581510 + 802 581520 Ce-152 4.90170E-04 4.99980E-04 581520 + 803 581530 Ce-153 9.33380E-05 9.33490E-05 581530 + 804 581540 Ce-154 1.03920E-05 1.03920E-05 581540 + 805 581550 Ce-155 4.54000E-08 4.54000E-08 581550 + 806 581560 Ce-156 7.58800E-10 7.58800E-10 581560 + 807 591430 Pr-143 1.12310E-06 4.50800E-02 59143.82c + 808 591440 Pr-144 1.42440E-06 4.39930E-02 591440 + 809 591441 Pr-144m 1.26510E-05 6.19540E-04 591441 + 810 591450 Pr-145 8.59600E-05 4.33930E-02 591450 + 811 591460 Pr-146 3.81260E-04 3.53290E-02 591460 + 812 591470 Pr-147 1.84380E-03 3.19370E-02 591470 + 813 591480 Pr-148 8.01670E-04 2.34560E-02 591480 + 814 591481 Pr-148m 3.37150E-03 3.37150E-03 591481 + 815 591490 Pr-149 1.00720E-02 2.18700E-02 591490 + 816 591500 Pr-150 1.05230E-02 1.65620E-02 591500 + 817 591510 Pr-151 1.09220E-02 1.28980E-02 591510 + 818 591520 Pr-152 6.20280E-03 6.70340E-03 591520 + 819 591530 Pr-153 3.01690E-03 3.10970E-03 591530 + 820 591540 Pr-154 8.99540E-04 9.09870E-04 591540 + 821 591550 Pr-155 2.14310E-04 2.14360E-04 591550 + 822 591560 Pr-156 3.71880E-05 3.71890E-05 591560 + 823 591570 Pr-157 7.48820E-06 7.48820E-06 591570 + 824 591580 Pr-158 1.87150E-09 1.87150E-09 591580 + 825 591590 Pr-159 2.20830E-11 2.20830E-11 591590 + 826 601450 Nd-145 2.70160E-09 4.33930E-02 60145.82c + 827 601460 Nd-146 1.12860E-07 3.53290E-02 60146.82c + 828 601470 Nd-147 9.36660E-06 3.19470E-02 60147.82c + 829 601480 Nd-148 1.28520E-04 2.69560E-02 60148.82c + 830 601490 Nd-149 3.58010E-04 2.22280E-02 601490 + 831 601500 Nd-150 1.29480E-03 1.78570E-02 60150.82c + 832 601510 Nd-151 2.44400E-03 1.53420E-02 601510 + 833 601520 Nd-152 4.20270E-03 1.09060E-02 601520 + 834 601530 Nd-153 3.57980E-03 6.68950E-03 601530 + 835 601540 Nd-154 2.64070E-03 3.55060E-03 601540 + 836 601550 Nd-155 1.15540E-03 1.37080E-03 601550 + 837 601560 Nd-156 4.28590E-04 4.65250E-04 601560 + 838 601570 Nd-157 9.41940E-05 1.01200E-04 601570 + 839 601580 Nd-158 1.46020E-05 1.46040E-05 601580 + 840 601590 Nd-159 4.21550E-06 4.21550E-06 601590 + 841 601600 Nd-160 6.48700E-09 6.48700E-09 601600 + 842 601610 Nd-161 9.64660E-11 9.64660E-11 601610 + 843 611480 Pm-148 3.97250E-07 4.43770E-07 61148.82c + 844 611481 Pm-148m 9.30450E-07 9.30450E-07 61548.82c + 845 611490 Pm-149 3.97650E-06 2.22320E-02 61149.82c + 846 611500 Pm-150 4.48300E-05 4.48300E-05 611500 + 847 611510 Pm-151 2.24950E-04 1.55670E-02 61151.82c + 848 611520 Pm-152 1.28010E-04 1.10340E-02 611520 + 849 611521 Pm-152m 2.55630E-04 2.55630E-04 611521 + 850 611522 Pm-152m 2.82750E-04 2.82750E-04 611522 + 851 611530 Pm-153 1.60580E-03 8.29530E-03 611530 + 852 611540 Pm-154 1.09560E-03 4.64620E-03 611540 + 853 611541 Pm-154m 1.09560E-03 1.09560E-03 611541 + 854 611550 Pm-155 2.96540E-03 4.33620E-03 611550 + 855 611560 Pm-156 2.03200E-03 2.49720E-03 611560 + 856 611570 Pm-157 1.29820E-03 1.39940E-03 611570 + 857 611580 Pm-158 4.70220E-04 4.84830E-04 611580 + 858 611590 Pm-159 1.54040E-04 1.58250E-04 611590 + 859 611600 Pm-160 3.59090E-05 3.59150E-05 611600 + 860 611610 Pm-161 7.13280E-06 7.13290E-06 611610 + 861 611620 Pm-162 1.10430E-08 1.10430E-08 611620 + 862 611630 Pm-163 1.63080E-10 1.63080E-10 611630 + 863 621500 Sm-150 1.22680E-09 4.48310E-05 62150.82c + 864 621510 Sm-151 4.31370E-08 1.55670E-02 62151.82c + 865 621520 Sm-152 4.47540E-06 1.15770E-02 62152.82c + 866 621530 Sm-153 6.97720E-06 8.31920E-03 62153.82c + 867 621531 Sm-153m 1.68440E-05 1.68440E-05 621531 + 868 621540 Sm-154 1.28250E-04 5.87000E-03 62154.82c + 869 621550 Sm-155 2.51090E-04 4.58730E-03 621550 + 870 621560 Sm-156 5.94710E-04 3.09200E-03 621560 + 871 621570 Sm-157 5.99940E-04 1.99930E-03 621570 + 872 621580 Sm-158 6.26400E-04 1.11130E-03 621580 + 873 621590 Sm-159 2.82100E-04 4.40410E-04 621590 + 874 621600 Sm-160 1.56440E-04 1.92260E-04 621600 + 875 621610 Sm-161 4.41990E-05 5.13320E-05 621610 + 876 621620 Sm-162 1.50650E-05 1.50760E-05 621620 + 877 621630 Sm-163 3.74740E-07 3.74900E-07 621630 + 878 621640 Sm-164 1.68630E-08 1.68630E-08 621640 + 879 621650 Sm-165 4.75150E-10 4.75150E-10 621650 + 880 631530 Eu-153 2.74450E-09 8.31920E-03 63153.82c + 881 631540 Eu-154 1.56330E-06 2.97140E-06 63154.82c + 882 631541 Eu-154m 1.40820E-06 1.40820E-06 631541 + 883 631550 Eu-155 2.14740E-05 4.60870E-03 63155.82c + 884 631560 Eu-156 4.50680E-05 3.13700E-03 63156.82c + 885 631570 Eu-157 1.45880E-04 2.14520E-03 63157.82c + 886 631580 Eu-158 2.53990E-04 1.36520E-03 631580 + 887 631590 Eu-159 3.57250E-04 7.97660E-04 631590 + 888 631600 Eu-160 3.39980E-04 5.32240E-04 631600 + 889 631610 Eu-161 2.66820E-04 3.18150E-04 631610 + 890 631620 Eu-162 1.21810E-04 1.36890E-04 631620 + 891 631630 Eu-163 5.36570E-05 5.40320E-05 631630 + 892 631640 Eu-164 1.31590E-05 1.31760E-05 631640 + 893 631650 Eu-165 1.33210E-06 1.33260E-06 631650 + 894 631660 Eu-166 1.68490E-08 1.68490E-08 631660 + 895 631670 Eu-167 3.83590E-10 3.83590E-10 631670 + 896 641550 Gd-155 8.71990E-11 4.60870E-03 64155.82c + 897 641551 Gd-155m 2.10510E-10 2.10510E-10 641551 + 898 641560 Gd-156 8.45540E-09 3.13700E-03 64156.82c + 899 641570 Gd-157 1.60900E-07 2.14540E-03 64157.82c + 900 641580 Gd-158 7.30650E-06 1.37260E-03 64158.82c + 901 641590 Gd-159 1.12470E-05 8.08910E-04 641590 + 902 641600 Gd-160 3.45360E-05 5.66780E-04 64160.82c + 903 641610 Gd-161 4.56980E-05 3.63850E-04 641610 + 904 641620 Gd-162 9.05150E-05 2.27400E-04 641620 + 905 641630 Gd-163 3.62520E-05 9.02840E-05 641630 + 906 641640 Gd-164 3.02730E-05 4.34490E-05 641640 + 907 641650 Gd-165 1.19870E-05 1.33200E-05 641650 + 908 641660 Gd-166 1.31660E-06 1.33340E-06 641660 + 909 641670 Gd-167 2.14030E-07 2.14410E-07 641670 + 910 641680 Gd-168 2.80290E-08 2.80290E-08 641680 + 911 641690 Gd-169 2.15360E-10 2.15360E-10 641690 + 912 651580 Tb-158 3.49110E-10 3.88180E-10 651580 + 913 651581 Tb-158m 3.93080E-11 3.93080E-11 651581 + 914 651590 Tb-159 9.67240E-09 8.08920E-04 65159.82c + 915 651600 Tb-160 4.31430E-06 4.31430E-06 65160.82c + 916 651610 Tb-161 7.13640E-06 3.70990E-04 651610 + 917 651620 Tb-162 1.50780E-05 2.42480E-04 651620 + 918 651630 Tb-163 1.47720E-05 1.05060E-04 651630 + 919 651640 Tb-164 1.58000E-05 5.92490E-05 651640 + 920 651650 Tb-165 2.66470E-05 3.99670E-05 651650 + 921 651660 Tb-166 1.71160E-05 1.84490E-05 651660 + 922 651670 Tb-167 6.17270E-06 6.38710E-06 651670 + 923 651680 Tb-168 2.33680E-06 2.36480E-06 651680 + 924 651690 Tb-169 4.24600E-08 4.26750E-08 651690 + 925 651700 Tb-170 7.33640E-09 7.33640E-09 651700 + 926 651710 Tb-171 6.72850E-10 6.72850E-10 651710 + 927 661600 Dy-160 1.97180E-11 4.31430E-06 66160.82c + 928 661610 Dy-161 8.68200E-10 3.70990E-04 66161.82c + 929 661620 Dy-162 1.80270E-08 2.42500E-04 66162.82c + 930 661630 Dy-163 1.25350E-07 1.05180E-04 66163.82c + 931 661640 Dy-164 7.45340E-07 5.99950E-05 66164.82c + 932 661650 Dy-165 1.15560E-06 4.12950E-05 661650 + 933 661651 Dy-165m 1.76650E-07 1.76650E-07 661651 + 934 661660 Dy-166 1.31670E-06 1.97660E-05 661660 + 935 661670 Dy-167 1.23460E-06 7.62170E-06 661670 + 936 661680 Dy-168 4.67390E-06 7.03870E-06 661680 + 937 661690 Dy-169 4.84930E-07 5.27600E-07 661690 + 938 661700 Dy-170 8.14050E-07 8.21390E-07 661700 + 939 661710 Dy-171 7.01940E-07 7.02610E-07 661710 + 940 661720 Dy-172 1.42310E-08 1.42310E-08 661720 + 941 661730 Dy-173 9.32550E-10 9.32550E-10 661730 + 942 671630 Ho-163 2.48170E-11 2.86110E-11 671630 + 943 671631 Ho-163m 3.79380E-12 3.79380E-12 671631 + 944 671640 Ho-164 1.85460E-10 6.19870E-10 671640 + 945 671641 Ho-164m 4.34410E-10 4.34410E-10 671641 + 946 671650 Ho-165 1.04440E-08 4.13090E-05 67165.82c + 947 671660 Ho-166 1.83740E-08 1.97850E-05 671660 + 948 671661 Ho-166m 4.30350E-08 4.30350E-08 671661 + 949 671670 Ho-167 1.86110E-07 7.80780E-06 671670 + 950 671680 Ho-168 3.09090E-07 7.78420E-06 671680 + 951 671681 Ho-168m 4.38580E-07 4.38580E-07 671681 + 952 671690 Ho-169 7.55900E-07 1.28350E-06 671690 + 953 671700 Ho-170 2.89300E-07 2.89300E-07 671700 + 954 671701 Ho-170m 1.23510E-07 9.44900E-07 671701 + 955 671710 Ho-171 4.22400E-07 1.12500E-06 671710 + 956 671720 Ho-172 1.83250E-07 1.97480E-07 671720 + 957 671730 Ho-173 4.77050E-08 4.86380E-08 671730 + 958 671740 Ho-174 6.88940E-09 6.88940E-09 671740 + 959 671750 Ho-175 7.19180E-10 7.19180E-10 671750 + 960 681650 Er-165 1.34220E-12 1.34220E-12 681650 + 961 681660 Er-166 4.50250E-11 1.97850E-05 68166.82c + 962 681670 Er-167 4.20170E-10 7.80830E-06 68167.82c + 963 681671 Er-167m 6.42310E-11 9.33040E-07 681671 + 964 681680 Er-168 8.44020E-09 7.79480E-06 68168.82c + 965 681690 Er-169 8.56700E-09 1.29210E-06 681690 + 966 681700 Er-170 5.75800E-08 1.29180E-06 68170.82c + 967 681710 Er-171 1.64780E-07 1.28980E-06 681710 + 968 681720 Er-172 2.42960E-07 4.40440E-07 681720 + 969 681730 Er-173 1.68400E-07 2.17040E-07 681730 + 970 681740 Er-174 8.66320E-08 9.35210E-08 681740 + 971 681750 Er-175 2.71370E-08 2.78560E-08 681750 + 972 681760 Er-176 5.87690E-09 5.87690E-09 681760 + 973 681770 Er-177 6.43770E-10 6.43770E-10 681770 + 974 691680 Tm-168 1.62240E-12 1.62240E-12 691680 + 975 691690 Tm-169 7.80800E-12 1.29210E-06 691690 + 976 691700 Tm-170 1.82170E-10 1.82170E-10 691700 + 977 691710 Tm-171 2.20730E-09 1.29200E-06 691710 + 978 691720 Tm-172 1.01520E-08 4.50590E-07 691720 + 979 691730 Tm-173 2.60220E-08 2.43060E-07 691730 + 980 691740 Tm-174 3.63840E-08 1.29900E-07 691740 + 981 691750 Tm-175 3.84640E-08 6.63200E-08 691750 + 982 691760 Tm-176 2.25880E-08 2.84650E-08 691760 + 983 691770 Tm-177 9.12020E-09 9.76400E-09 691770 + 984 691780 Tm-178 2.05580E-09 2.05580E-09 691780 + 985 691790 Tm-179 3.54090E-10 3.54090E-10 691790 + 986 701710 Yb-171 1.84540E-13 1.29200E-06 701710 + 987 701711 Yb-171m 1.20720E-12 1.20720E-12 701711 + 988 701720 Yb-172 2.89710E-11 4.50620E-07 701720 + 989 701730 Yb-173 2.52750E-10 2.43310E-07 701730 + 990 701740 Yb-174 1.45460E-09 1.31360E-07 701740 + 991 701750 Yb-175 4.01630E-09 7.09500E-08 701750 + 992 701751 Yb-175m 6.13980E-10 5.16800E-08 701751 + 993 701760 Yb-176 3.47140E-09 3.61330E-08 701760 + 994 701761 Yb-176m 6.24430E-09 2.04770E-08 701761 + 995 701770 Yb-177 8.49320E-09 2.02210E-08 701770 + 996 701771 Yb-177m 1.96380E-09 1.17280E-08 701771 + 997 701780 Yb-178 8.00160E-09 1.00570E-08 701780 + 998 701790 Yb-179 3.84310E-09 4.19720E-09 701790 + 999 701800 Yb-180 1.35250E-09 1.35250E-09 701800 + 1000 701810 Yb-181 2.57780E-10 2.57780E-10 701810 + 1001 711740 Lu-174 3.40760E-13 1.13430E-12 711740 + 1002 711750 Lu-175 1.60730E-11 7.09670E-08 71175.82c + 1003 711760 Lu-176 7.20210E-11 2.11970E-09 71176.82c + 1004 711761 Lu-176m 4.00390E-11 4.00390E-11 711761 + 1005 711770 Lu-177 3.42440E-10 2.05940E-08 711770 + 1006 711771 Lu-177m 1.33870E-10 1.36040E-10 711771 + 1007 711772 Lu-177m 4.32620E-12 4.32620E-12 711772 + 1008 711780 Lu-178 5.00520E-10 1.05580E-08 711780 + 1009 711781 Lu-178m 5.67380E-10 5.67380E-10 711781 + 1010 711790 Lu-179 1.54420E-09 5.97750E-09 711790 + 1011 711791 Lu-179m 2.36070E-10 4.43330E-09 711791 + 1012 711800 Lu-180 4.77190E-10 1.74370E-09 711800 + 1013 711801 Lu-180m 4.77190E-10 1.82970E-09 711801 + 1014 711802 Lu-180m 7.03280E-10 7.03280E-10 711802 + 1015 711810 Lu-181 1.09180E-09 1.34960E-09 711810 + 1016 711820 Lu-182 3.97160E-10 3.97160E-10 711820 + 1017 711830 Lu-183 1.05300E-10 1.05300E-10 711830 + 1018 711840 Lu-184 1.54970E-11 1.54970E-11 711840 + 1019 721770 Hf-177 8.40130E-13 2.07030E-08 72177.82c + 1020 721771 Hf-177m 3.26430E-13 1.07790E-10 721771 + 1021 721772 Hf-177m 1.26180E-14 2.17570E-12 721772 + 1022 721780 Hf-178 4.06860E-12 1.11370E-08 72178.82c + 1023 721781 Hf-178m 6.71260E-12 5.74690E-10 721781 + 1024 721790 Hf-179 3.68970E-11 6.03880E-09 72179.82c + 1025 721791 Hf-179m 1.15180E-11 1.15180E-11 721791 + 1026 721792 Hf-179m 1.29160E-11 1.29160E-11 721792 + 1027 721800 Hf-180 7.84920E-11 3.22830E-09 72180.82c + 1028 721801 Hf-180m 1.41190E-10 4.92830E-10 721801 + 1029 721810 Hf-181 4.05850E-10 1.75540E-09 721810 + 1030 721820 Hf-182 1.79500E-10 7.12260E-10 721820 + 1031 721821 Hf-182m 3.22870E-10 3.22870E-10 721821 + 1032 721830 Hf-183 3.54240E-10 4.59540E-10 721830 + 1033 721840 Hf-184 6.61720E-11 7.39210E-11 721840 + 1034 721841 Hf-184m 1.19030E-10 1.26780E-10 721841 + 1035 721850 Hf-185 5.91920E-11 5.91920E-11 721850 + 1036 721860 Hf-186 1.31130E-11 1.31130E-11 721860 + 1037 721870 Hf-187 1.46970E-12 1.46970E-12 721870 + 1038 731810 Ta-181 5.14160E-12 1.76060E-09 73181.82c + 1039 731820 Ta-182 7.11460E-12 2.07180E-10 73182.82c + 1040 731821 Ta-182m 7.26190E-12 2.00060E-10 731821 + 1041 731822 Ta-182m 5.53550E-12 1.92800E-10 731822 + 1042 731830 Ta-183 5.20860E-11 5.11630E-10 731830 + 1043 731840 Ta-184 7.41810E-11 2.74880E-10 731840 + 1044 731850 Ta-185 5.39090E-11 1.39210E-10 731850 + 1045 731851 Ta-185m 2.61100E-11 2.61100E-11 731851 + 1046 731860 Ta-186 4.79750E-11 6.10880E-11 731860 + 1047 731870 Ta-187 1.97560E-11 2.12260E-11 731870 + 1048 731880 Ta-188 4.53990E-12 4.53990E-12 731880 + 1049 741840 W-184 2.80870E-12 2.77690E-10 74184.82c + 1050 741850 W-185 2.68070E-12 1.48360E-10 741850 + 1051 741851 W-185m 6.47160E-12 6.47160E-12 741851 + 1052 741860 W-186 1.48660E-11 8.07490E-11 74186.82c + 1053 741861 W-186m 4.79530E-12 4.79530E-12 741861 + 1054 741870 W-187 2.16100E-11 4.28360E-11 741870 + 1055 741880 W-188 1.68410E-11 2.13810E-11 741880 + 1056 741890 W-189 8.22220E-12 8.22220E-12 741890 + 1057 741900 W-190 1.38100E-12 2.94640E-12 741900 + 1058 741901 W-190m 1.56540E-12 1.56540E-12 741901 + 1059 751880 Re-188 6.39900E-13 2.35200E-11 751880 + 1060 751881 Re-188m 1.49880E-12 1.49880E-12 751881 + 1061 751890 Re-189 3.63260E-12 1.18550E-11 751890 + 1062 751900 Re-190 1.23060E-12 5.18640E-12 751900 + 1063 751901 Re-190m 2.21360E-12 2.21360E-12 751901 + 1064 751910 Re-191 2.31740E-12 2.31740E-12 751910 + + Neutron-induced fission: + + Interpolation region : 2 / 2 + Interpolation energy : 4.00000E-01 MeV + Number of products : 1061 / 1137 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 3.32190E-05 3.32190E-05 1001.82c + 2 10020 H-2 1.01520E-05 1.01520E-05 1002.82c + 3 10030 H-3 1.60000E-04 1.60000E-04 1003.82c + 4 20040 He-4 2.10000E-03 2.10000E-03 2004.82c + 5 190500 K-50 2.76810E-12 2.76810E-12 190500 + 6 190510 K-51 1.02270E-12 1.02270E-12 190510 + 7 200500 Ca-50 2.92420E-11 3.16880E-11 200500 + 8 200510 Ca-51 2.79210E-11 2.84630E-11 200510 + 9 200520 Ca-52 2.30600E-11 2.30600E-11 200520 + 10 200530 Ca-53 7.22090E-12 7.22090E-12 200530 + 11 200540 Ca-54 1.81720E-12 1.81720E-12 200540 + 12 210500 Sc-50 6.77520E-12 4.05220E-11 210500 + 13 210501 Sc-50m 2.48560E-12 3.41740E-11 210501 + 14 210510 Sc-51 3.99240E-11 6.88480E-11 210510 + 15 210520 Sc-52 7.59090E-11 1.00670E-10 210520 + 16 210530 Sc-53 1.17280E-10 1.22330E-10 210530 + 17 210540 Sc-54 7.98070E-11 8.16240E-11 210540 + 18 210550 Sc-55 5.12330E-11 5.12330E-11 210550 + 19 210560 Sc-56 1.26510E-11 1.26510E-11 210560 + 20 210570 Sc-57 2.43240E-12 2.43240E-12 210570 + 21 220510 Ti-51 2.50790E-12 7.13560E-11 220510 + 22 220520 Ti-52 2.34960E-11 1.24170E-10 220520 + 23 220530 Ti-53 8.35060E-11 2.05840E-10 220530 + 24 220540 Ti-54 2.56640E-10 3.38260E-10 220540 + 25 220550 Ti-55 3.91500E-10 4.42730E-10 220550 + 26 220560 Ti-56 4.99240E-10 5.12690E-10 220560 + 27 220570 Ti-57 2.70590E-10 2.72220E-10 220570 + 28 220580 Ti-58 1.26370E-10 1.26370E-10 220580 + 29 220590 Ti-59 2.34870E-11 2.34870E-11 220590 + 30 220600 Ti-60 3.21320E-12 3.21320E-12 220600 + 31 230530 V-53 3.12270E-12 2.08960E-10 230530 + 32 230540 V-54 2.47680E-11 3.63030E-10 230540 + 33 230550 V-55 1.78700E-10 6.21430E-10 230550 + 34 230560 V-56 5.15570E-10 1.02910E-09 230560 + 35 230570 V-57 1.28460E-09 1.55600E-09 230570 + 36 230580 V-58 1.48580E-09 1.61220E-09 230580 + 37 230590 V-59 1.49200E-09 1.51550E-09 230590 + 38 230600 V-60 5.96640E-10 5.99850E-10 230600 + 39 230610 V-61 2.15820E-10 2.15820E-10 230610 + 40 230620 V-62 3.11190E-11 3.11190E-11 230620 + 41 230630 V-63 2.29660E-12 2.29660E-12 230630 + 42 240550 Cr-55 3.01360E-12 6.24450E-10 240550 + 43 240560 Cr-56 4.67730E-11 1.08210E-09 240560 + 44 240570 Cr-57 2.87380E-10 3.12690E-09 240570 + 45 240580 Cr-58 1.52440E-09 1.84680E-09 240580 + 46 240590 Cr-59 3.46620E-09 4.98170E-09 240590 + 47 240600 Cr-60 6.57990E-09 7.19270E-09 240600 + 48 240610 Cr-61 6.17050E-09 6.37340E-09 240610 + 49 240620 Cr-62 5.01040E-09 5.04230E-09 240620 + 50 240630 Cr-63 1.11420E-09 1.11570E-09 240630 + 51 240640 Cr-64 3.79630E-10 3.79630E-10 240640 + 52 240650 Cr-65 4.10430E-11 4.10430E-11 240650 + 53 240660 Cr-66 3.22770E-12 3.22770E-12 240660 + 54 250570 Mn-57 2.77260E-12 3.12970E-09 250570 + 55 250580 Mn-58 3.76010E-11 1.88440E-09 250580 + 56 250581 Mn-58m 3.69610E-12 3.69610E-12 250581 + 57 250590 Mn-59 4.82730E-10 5.46440E-09 250590 + 58 250600 Mn-60 1.94190E-10 7.61410E-09 250600 + 59 250601 Mn-60m 1.97550E-09 1.97550E-09 250601 + 60 250610 Mn-61 9.18180E-09 1.55550E-08 250610 + 61 250620 Mn-62 1.48650E-08 1.73860E-08 250620 + 62 250621 Mn-62m 2.32790E-09 4.84910E-09 250621 + 63 250630 Mn-63 1.89220E-08 2.00380E-08 250630 + 64 250640 Mn-64 1.74840E-08 1.78640E-08 250640 + 65 250650 Mn-65 1.10370E-08 1.10780E-08 250650 + 66 250660 Mn-66 2.68220E-09 2.68540E-09 250660 + 67 250670 Mn-67 5.05110E-10 5.05110E-10 250670 + 68 250680 Mn-68 2.92930E-11 2.92930E-11 250680 + 69 250690 Mn-69 2.25490E-12 2.25490E-12 250690 + 70 260590 Fe-59 2.02790E-12 5.46640E-09 260590 + 71 260600 Fe-60 5.29210E-11 9.41530E-09 260600 + 72 260610 Fe-61 6.02960E-10 1.61580E-08 260610 + 73 260620 Fe-62 5.54670E-09 2.77820E-08 260620 + 74 260630 Fe-63 3.44860E-08 5.45240E-08 260630 + 75 260640 Fe-64 5.85460E-08 7.64100E-08 260640 + 76 260650 Fe-65 8.80470E-08 9.91250E-08 260650 + 77 260660 Fe-66 1.10840E-07 1.13530E-07 260660 + 78 260670 Fe-67 5.90000E-08 5.95050E-08 260670 + 79 260680 Fe-68 2.05910E-08 2.06210E-08 260680 + 80 260690 Fe-69 4.95870E-09 4.96040E-09 260690 + 81 260700 Fe-70 2.47670E-10 2.47670E-10 260700 + 82 260710 Fe-71 5.04200E-11 5.04200E-11 260710 + 83 260720 Fe-72 1.21290E-12 1.21290E-12 260720 + 84 270610 Co-61 1.40680E-12 1.61590E-08 270610 + 85 270620 Co-62 1.04180E-11 2.77930E-08 270620 + 86 270621 Co-62m 2.83990E-11 2.83990E-11 270621 + 87 270630 Co-63 5.48930E-10 5.50730E-08 270630 + 88 270640 Co-64 5.89750E-09 8.23070E-08 270640 + 89 270650 Co-65 4.18440E-08 1.40970E-07 270650 + 90 270660 Co-66 1.19120E-07 2.32650E-07 270660 + 91 270670 Co-67 2.91980E-07 3.51490E-07 270670 + 92 270680 Co-68 1.44960E-07 2.09540E-07 270680 + 93 270681 Co-68m 1.08200E-07 1.29170E-07 270681 + 94 270690 Co-69 3.30360E-07 3.34970E-07 270690 + 95 270700 Co-70 2.41700E-08 2.41700E-08 270700 + 96 270701 Co-70m 2.41700E-08 2.44180E-08 270701 + 97 270710 Co-71 6.07660E-08 6.08160E-08 270710 + 98 270720 Co-72 4.94010E-09 4.94130E-09 270720 + 99 270730 Co-73 5.18920E-10 5.18920E-10 270730 + 100 270740 Co-74 2.53270E-11 2.53270E-11 270740 + 101 270750 Co-75 1.21520E-12 1.21520E-12 270750 + 102 280640 Ni-64 3.58760E-11 8.23430E-08 28064.82c + 103 280650 Ni-65 7.39890E-10 1.41710E-07 280650 + 104 280660 Ni-66 1.12970E-08 2.43940E-07 280660 + 105 280670 Ni-67 6.80850E-08 4.19570E-07 280670 + 106 280680 Ni-68 5.52920E-07 8.30400E-07 280680 + 107 280690 Ni-69 3.99590E-07 7.31210E-07 280690 + 108 280691 Ni-69m 3.99590E-07 3.99590E-07 280691 + 109 280700 Ni-70 7.63600E-07 8.12190E-07 280700 + 110 280710 Ni-71 9.73330E-07 1.03420E-06 280710 + 111 280720 Ni-72 2.02100E-06 2.02590E-06 280720 + 112 280730 Ni-73 2.64910E-07 2.65430E-07 280730 + 113 280740 Ni-74 8.11260E-08 8.11510E-08 280740 + 114 280750 Ni-75 1.02400E-08 1.02410E-08 280750 + 115 280760 Ni-76 6.81640E-10 6.81640E-10 280760 + 116 280770 Ni-77 2.09450E-11 2.09450E-11 280770 + 117 290660 Cu-66 1.91360E-11 2.43960E-07 290660 + 118 290670 Cu-67 6.89510E-10 4.20260E-07 290670 + 119 290680 Cu-68 2.05740E-09 8.37170E-07 290680 + 120 290681 Cu-68m 5.60810E-09 5.60810E-09 290681 + 121 290690 Cu-69 1.16160E-07 1.24700E-06 290690 + 122 290700 Cu-70 1.29360E-08 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41095.82c + 359 410951 Nb-95m 5.14770E-07 3.71270E-04 410951 + 360 410960 Nb-96 4.74710E-05 4.74710E-05 410960 + 361 410970 Nb-97 3.19090E-04 4.34000E-02 410970 + 362 410971 Nb-97m 6.42480E-05 4.09510E-02 410971 + 363 410980 Nb-98 3.63670E-04 4.84260E-02 410980 + 364 410981 Nb-98m 1.26710E-03 1.26710E-03 410981 + 365 410990 Nb-99 5.97210E-03 3.43950E-02 410990 + 366 410991 Nb-99m 1.20250E-03 1.75480E-02 410991 + 367 411000 Nb-100 2.56210E-03 4.15420E-02 411000 + 368 411001 Nb-100m 1.24210E-02 1.24210E-02 411001 + 369 411010 Nb-101 2.99160E-02 5.07270E-02 411010 + 370 411020 Nb-102 1.44920E-02 2.60370E-02 411020 + 371 411021 Nb-102m 1.44920E-02 1.44920E-02 411021 + 372 411030 Nb-103 2.78800E-02 3.16560E-02 411030 + 373 411040 Nb-104 7.68250E-03 8.81520E-03 411040 + 374 411041 Nb-104m 7.68250E-03 7.68250E-03 411041 + 375 411050 Nb-105 8.40550E-03 8.57670E-03 411050 + 376 411060 Nb-106 2.36270E-03 2.39110E-03 411060 + 377 411070 Nb-107 6.70190E-04 6.70200E-04 411070 + 378 411080 Nb-108 9.09830E-05 9.09830E-05 411080 + 379 411090 Nb-109 1.17270E-05 1.17270E-05 411090 + 380 420970 Mo-97 5.05810E-06 4.34050E-02 42097.82c + 381 420980 Mo-98 4.88790E-05 4.97420E-02 42098.82c + 382 420990 Mo-99 3.80030E-04 5.19720E-02 42099.82c + 383 421000 Mo-100 2.18410E-03 5.61470E-02 42100.82c + 384 421010 Mo-101 6.43900E-03 5.71660E-02 421010 + 385 421020 Mo-102 1.97590E-02 6.02880E-02 421020 + 386 421030 Mo-103 2.99260E-02 6.15910E-02 421030 + 387 421040 Mo-104 4.34400E-02 6.00740E-02 421040 + 388 421050 Mo-105 3.22300E-02 4.07680E-02 421050 + 389 421060 Mo-106 2.50480E-02 2.73720E-02 421060 + 390 421070 Mo-107 1.07460E-02 1.13820E-02 421070 + 391 421080 Mo-108 4.59210E-03 4.67890E-03 421080 + 392 421090 Mo-109 9.46840E-04 9.57080E-04 421090 + 393 421100 Mo-110 1.95350E-04 1.95350E-04 421100 + 394 421110 Mo-111 9.72560E-06 9.72560E-06 421110 + 395 421120 Mo-112 1.55170E-09 1.55170E-09 421120 + 396 430990 Tc-99 3.99760E-09 5.19710E-02 43099.82c + 397 430991 Tc-99m 8.04900E-10 4.57670E-02 430991 + 398 431000 Tc-100 7.20280E-06 7.20280E-06 431000 + 399 431010 Tc-101 9.16680E-05 5.72580E-02 431010 + 400 431020 Tc-102 2.74710E-04 6.05620E-02 431020 + 401 431021 Tc-102m 2.74710E-04 2.74710E-04 431021 + 402 431030 Tc-103 3.05010E-03 6.46410E-02 431030 + 403 431040 Tc-104 7.56290E-03 6.76370E-02 431040 + 404 431050 Tc-105 1.97400E-02 6.05080E-02 431050 + 405 431060 Tc-106 2.55130E-02 5.28850E-02 431060 + 406 431070 Tc-107 3.18380E-02 4.32200E-02 431070 + 407 431080 Tc-108 2.12640E-02 2.59480E-02 431080 + 408 431090 Tc-109 1.36830E-02 1.46350E-02 431090 + 409 431100 Tc-110 5.43650E-03 5.63200E-03 431100 + 410 431110 Tc-111 1.65390E-03 1.66350E-03 431110 + 411 431120 Tc-112 2.80110E-04 2.80110E-04 431120 + 412 431130 Tc-113 3.83430E-05 3.83430E-05 431130 + 413 431140 Tc-114 8.78940E-06 8.78940E-06 431140 + 414 431150 Tc-115 9.68510E-07 9.68510E-07 431150 + 415 441020 Ru-102 9.98680E-06 6.08470E-02 44102.82c + 416 441030 Ru-103 1.52750E-05 6.46990E-02 44103.82c + 417 441031 Ru-103m 4.27380E-05 4.27380E-05 441031 + 418 441040 Ru-104 4.44160E-04 6.80820E-02 44104.82c + 419 441050 Ru-105 1.70110E-03 6.22100E-02 44105.82c + 420 441060 Ru-106 5.84060E-03 5.87250E-02 44106.82c + 421 441070 Ru-107 1.07890E-02 5.40090E-02 441070 + 422 441080 Ru-108 1.96430E-02 4.56030E-02 441080 + 423 441090 Ru-109 1.82440E-02 3.28700E-02 441090 + 424 441100 Ru-110 1.62280E-02 2.18580E-02 441100 + 425 441110 Ru-111 7.82140E-03 9.48910E-03 441110 + 426 441120 Ru-112 3.61670E-03 3.89540E-03 441120 + 427 441130 Ru-113 4.41550E-04 6.98480E-04 441130 + 428 441131 Ru-113m 4.41550E-04 4.41550E-04 441131 + 429 441140 Ru-114 2.76360E-04 2.84710E-04 441140 + 430 441150 Ru-115 7.74590E-05 7.82890E-05 441150 + 431 441160 Ru-116 2.70840E-05 2.70840E-05 441160 + 432 441170 Ru-117 7.89090E-06 7.89090E-06 441170 + 433 441180 Ru-118 6.38610E-07 6.38610E-07 441180 + 434 451030 Rh-103 1.17440E-07 6.47000E-02 45103.82c + 435 451031 Rh-103m 8.82060E-07 6.39250E-02 451031 + 436 451040 Rh-104 1.16840E-09 5.23420E-09 451040 + 437 451041 Rh-104m 4.07110E-09 4.07110E-09 451041 + 438 451050 Rh-105 7.92680E-06 6.22190E-02 45105.82c + 439 451051 Rh-105m 1.05540E-06 1.76610E-02 451051 + 440 451060 Rh-106 2.00800E-05 5.87450E-02 451060 + 441 451061 Rh-106m 5.47330E-05 5.47330E-05 451061 + 442 451070 Rh-107 4.63260E-04 5.44720E-02 451070 + 443 451080 Rh-108 3.46210E-04 4.59490E-02 451080 + 444 451081 Rh-108m 1.20630E-03 1.20630E-03 451081 + 445 451090 Rh-109 4.12160E-03 3.69910E-02 451090 + 446 451100 Rh-110 5.76980E-03 2.76270E-02 451100 + 447 451101 Rh-110m 1.35830E-04 1.35830E-04 451101 + 448 451110 Rh-111 7.84000E-03 1.73290E-02 451110 + 449 451120 Rh-112 2.79900E-03 6.69440E-03 451120 + 450 451121 Rh-112m 2.79900E-03 2.79900E-03 451121 + 451 451130 Rh-113 3.76050E-03 4.67970E-03 451130 + 452 451140 Rh-114 7.42800E-04 1.02770E-03 451140 + 453 451141 Rh-114m 7.42800E-04 7.42800E-04 451141 + 454 451150 Rh-115 6.20090E-04 6.98490E-04 451150 + 455 451160 Rh-116 3.88750E-05 6.58280E-05 451160 + 456 451161 Rh-116m 1.05970E-04 1.05970E-04 451161 + 457 451170 Rh-117 3.00220E-05 3.77770E-05 451170 + 458 451180 Rh-118 7.11970E-06 7.73210E-06 451180 + 459 451190 Rh-119 4.74880E-06 4.74880E-06 451190 + 460 451220 Rh-122 3.42800E-09 3.42800E-09 451220 + 461 461060 Pd-106 9.96350E-07 5.88010E-02 46106.82c + 462 461070 Pd-107 1.53440E-06 5.44770E-02 46107.82c + 463 461071 Pd-107m 3.37260E-06 3.37260E-06 461071 + 464 461080 Pd-108 4.21750E-05 4.71970E-02 46108.82c + 465 461090 Pd-109 4.08140E-05 3.71220E-02 461090 + 466 461091 Pd-109m 8.97060E-05 1.85850E-02 461091 + 467 461100 Pd-110 5.66920E-04 2.83300E-02 46110.82c + 468 461110 Pd-111 3.03580E-04 1.81010E-02 461110 + 469 461111 Pd-111m 6.67250E-04 7.36570E-04 461111 + 470 461120 Pd-112 1.67000E-03 1.11630E-02 461120 + 471 461130 Pd-113 4.11850E-04 6.24390E-03 461130 + 472 461131 Pd-113m 1.15230E-03 1.15230E-03 461131 + 473 461140 Pd-114 1.35700E-03 3.12750E-03 461140 + 474 461150 Pd-115 1.87960E-04 8.26200E-04 461150 + 475 461151 Pd-115m 4.13130E-04 5.14550E-04 461151 + 476 461160 Pd-116 3.03260E-04 4.75050E-04 461160 + 477 461170 Pd-117 3.37250E-05 1.45850E-04 461170 + 478 461171 Pd-117m 7.41250E-05 7.41250E-05 461171 + 479 461180 Pd-118 4.21890E-05 4.96950E-05 461180 + 480 461190 Pd-119 4.74980E-06 9.49860E-06 461190 + 481 461200 Pd-120 8.94240E-06 8.94240E-06 461200 + 482 461210 Pd-121 4.84200E-06 4.84200E-06 461210 + 483 461220 Pd-122 4.65060E-06 4.65400E-06 461220 + 484 461230 Pd-123 4.62190E-07 4.62190E-07 461230 + 485 461240 Pd-124 5.34590E-08 5.34590E-08 461240 + 486 471090 Ag-109 4.05910E-10 3.71220E-02 47109.82c + 487 471091 Ag-109m 3.04870E-09 3.71040E-02 471091 + 488 471100 Ag-110 1.05160E-06 1.09060E-06 471100 + 489 471101 Ag-110m 2.86650E-06 2.86650E-06 47510.82c + 490 471110 Ag-111 3.32440E-06 1.82380E-02 47111.82c + 491 471111 Ag-111m 2.49690E-05 1.81400E-02 471111 + 492 471120 Ag-112 6.41010E-05 1.12280E-02 471120 + 493 471130 Ag-113 1.68710E-05 4.18940E-03 471130 + 494 471131 Ag-113m 1.26710E-04 6.10580E-03 471131 + 495 471140 Ag-114 2.95380E-05 3.30020E-03 471140 + 496 471141 Ag-114m 1.43200E-04 1.43200E-04 471141 + 497 471150 Ag-115 2.71620E-05 8.19380E-04 471150 + 498 471151 Ag-115m 2.04010E-04 9.00470E-04 471151 + 499 471160 Ag-116 3.92130E-05 5.20680E-04 471160 + 500 471161 Ag-116m 1.06890E-04 1.06890E-04 471161 + 501 471170 Ag-117 2.07420E-05 1.07390E-04 471170 + 502 471171 Ag-117m 1.55790E-04 2.28710E-04 471171 + 503 471180 Ag-118 1.69430E-05 9.61240E-05 471180 + 504 471181 Ag-118m 8.21390E-05 8.92430E-05 471181 + 505 471190 Ag-119 1.33570E-05 1.81070E-05 471190 + 506 471191 Ag-119m 1.00320E-04 1.05070E-04 471191 + 507 471200 Ag-120 4.55360E-05 7.98520E-05 471200 + 508 471201 Ag-120m 7.61540E-05 8.06250E-05 471201 + 509 471210 Ag-121 5.52320E-05 6.00610E-05 471210 + 510 471220 Ag-122 1.22030E-05 1.68570E-05 471220 + 511 471221 Ag-122m 1.31570E-05 1.31570E-05 471221 + 512 471230 Ag-123 1.68670E-05 1.73290E-05 471230 + 513 471240 Ag-124 8.06060E-06 1.24590E-05 471240 + 514 471241 Ag-124m 8.69040E-06 8.69040E-06 471241 + 515 471250 Ag-125 9.55560E-06 9.55560E-06 471250 + 516 471260 Ag-126 3.06730E-06 3.06730E-06 471260 + 517 471270 Ag-127 7.83390E-08 7.83390E-08 471270 + 518 471280 Ag-128 2.67170E-09 2.67170E-09 471280 + 519 481120 Cd-112 9.31040E-09 1.12280E-02 48112.82c + 520 481130 Cd-113 6.09360E-07 6.31580E-03 48113.82c + 521 481131 Cd-113m 2.30760E-06 7.47390E-05 481131 + 522 481140 Cd-114 6.64960E-06 3.30690E-03 48114.82c + 523 481150 Cd-115 2.12910E-06 1.46500E-03 481150 + 524 481151 Cd-115m 8.06290E-06 7.59890E-05 48515.82c + 525 481160 Cd-116 1.86850E-05 6.39840E-04 48116.82c + 526 481170 Cd-117 4.67330E-06 2.55620E-04 481170 + 527 481171 Cd-117m 1.76980E-05 8.91320E-05 481171 + 528 481180 Cd-118 2.87170E-05 1.77500E-04 481180 + 529 481190 Cd-119 9.08310E-06 1.23210E-04 481190 + 530 481191 Cd-119m 2.54140E-05 3.44680E-05 481191 + 531 481200 Cd-120 1.96060E-04 3.26700E-04 481200 + 532 481210 Cd-121 3.03270E-05 8.41120E-05 481210 + 533 481211 Cd-121m 8.48530E-05 9.11290E-05 481211 + 534 481220 Cd-122 1.35720E-04 1.65730E-04 481220 + 535 481230 Cd-123 3.10220E-05 4.52060E-05 481230 + 536 481231 Cd-123m 8.67980E-05 8.99550E-05 481231 + 537 481240 Cd-124 2.20870E-04 2.37660E-04 481240 + 538 481250 Cd-125 5.51560E-05 5.99340E-05 481250 + 539 481251 Cd-125m 1.54320E-04 1.59100E-04 481251 + 540 481260 Cd-126 1.67410E-04 1.70480E-04 481260 + 541 481270 Cd-127 8.80790E-05 8.81570E-05 481270 + 542 481280 Cd-128 4.19520E-05 4.19550E-05 481280 + 543 481290 Cd-129 2.93500E-06 2.93500E-06 481290 + 544 481291 Cd-129m 8.21200E-06 8.21200E-06 481291 + 545 481300 Cd-130 6.77530E-08 6.77530E-08 481300 + 546 481310 Cd-131 1.02140E-09 1.02140E-09 481310 + 547 491140 In-114 5.69360E-11 2.48380E-10 491140 + 548 491141 In-114m 9.19410E-11 1.98380E-10 491141 + 549 491142 In-114m 1.06440E-10 1.06440E-10 491142 + 550 491150 In-115 6.75560E-09 1.46770E-03 49115.82c + 551 491151 In-115m 1.36020E-09 1.46500E-03 491151 + 552 491160 In-116 2.06850E-07 2.06850E-07 491160 + 553 491161 In-116m 3.34030E-07 7.20740E-07 491161 + 554 491162 In-116m 3.86710E-07 3.86710E-07 491162 + 555 491170 In-117 7.06100E-07 2.20890E-04 491170 + 556 491171 In-117m 1.42170E-07 2.35760E-04 491171 + 557 491180 In-118 7.14670E-07 1.78210E-04 491180 + 558 491181 In-118m 1.15400E-06 2.47140E-06 491181 + 559 491182 In-118m 1.33610E-06 1.33610E-06 491182 + 560 491190 In-119 5.88220E-06 5.85530E-05 491190 + 561 491191 In-119m 1.18430E-06 1.12490E-04 491191 + 562 491200 In-120 8.24780E-06 3.34950E-04 491200 + 563 491201 In-120m 8.24780E-06 8.24780E-06 491201 + 564 491202 In-120m 8.24780E-06 8.24780E-06 491202 + 565 491210 In-121 4.93700E-05 1.69620E-04 491210 + 566 491211 In-121m 9.94040E-06 6.57240E-05 491211 + 567 491220 In-122 3.44410E-05 2.00180E-04 491220 + 568 491221 In-122m 2.87990E-05 2.87990E-05 491221 + 569 491222 In-122m 2.87990E-05 2.87990E-05 491222 + 570 491230 In-123 1.33920E-04 2.36780E-04 491230 + 571 491231 In-123m 2.69650E-05 5.92670E-05 491231 + 572 491240 In-124 1.11940E-04 3.49600E-04 491240 + 573 491241 In-124m 1.20680E-04 1.20680E-04 491241 + 574 491250 In-125 5.70140E-04 7.57930E-04 491250 + 575 491251 In-125m 1.14800E-04 1.46040E-04 491251 + 576 491260 In-126 5.16620E-04 6.87090E-04 491260 + 577 491261 In-126m 5.56980E-04 5.56980E-04 491261 + 578 491270 In-127 1.57220E-03 1.57220E-03 491270 + 579 491271 In-127m 3.16550E-04 4.04700E-04 491271 + 580 491280 In-128 5.40900E-04 7.94650E-04 491280 + 581 491281 In-128m 2.11790E-04 2.53750E-04 491281 + 582 491282 In-128m 8.11510E-04 8.11510E-04 491282 + 583 491290 In-129 9.21050E-04 9.29260E-04 491290 + 584 491291 In-129m 1.85450E-04 1.88390E-04 491291 + 585 491300 In-130 8.59930E-05 8.60590E-05 491300 + 586 491301 In-130m 1.25210E-04 1.25210E-04 491301 + 587 491302 In-130m 1.74420E-04 1.74420E-04 491302 + 588 491310 In-131 3.14340E-05 3.17550E-05 491310 + 589 491311 In-131m 3.14340E-05 3.14340E-05 491311 + 590 491312 In-131m 3.14340E-05 3.14340E-05 491312 + 591 491320 In-132 6.09900E-06 6.09900E-06 491320 + 592 491330 In-133 1.78310E-08 2.14210E-08 491330 + 593 491331 In-133m 3.59020E-09 3.59020E-09 491331 + 594 501170 Sn-117 5.19620E-11 3.45600E-04 50117.82c + 595 501171 Sn-117m 1.96780E-10 7.52780E-07 501171 + 596 501180 Sn-118 6.07490E-09 1.80700E-04 50118.82c + 597 501190 Sn-119 2.10400E-08 1.64840E-04 50119.82c + 598 501191 Sn-119m 7.96800E-08 5.29760E-05 501191 + 599 501200 Sn-120 3.43270E-06 3.54880E-04 50120.82c + 600 501210 Sn-121 3.32180E-06 2.40780E-04 501210 + 601 501211 Sn-121m 9.29420E-06 2.85090E-05 501211 + 602 501220 Sn-122 2.14790E-05 2.79310E-04 50122.82c + 603 501230 Sn-123 2.97870E-05 4.78400E-05 50123.82c + 604 501231 Sn-123m 1.06460E-05 2.88650E-04 501231 + 605 501240 Sn-124 1.14890E-04 5.85170E-04 50124.82c + 606 501250 Sn-125 2.20910E-04 3.48940E-04 50125.82c + 607 501251 Sn-125m 7.89560E-05 8.54900E-04 501251 + 608 501260 Sn-126 1.17070E-03 2.41760E-03 50126.82c + 609 501270 Sn-127 1.94280E-03 2.55560E-03 501270 + 610 501271 Sn-127m 6.94380E-04 2.05570E-03 501271 + 611 501280 Sn-128 1.71590E-03 7.99920E-03 501280 + 612 501281 Sn-128m 4.67710E-03 5.48860E-03 501281 + 613 501290 Sn-129 1.93930E-03 2.95810E-03 501290 + 614 501291 Sn-129m 5.42610E-03 5.52500E-03 501291 + 615 501300 Sn-130 2.08240E-03 2.31820E-03 501300 + 616 501301 Sn-130m 5.67610E-03 5.82650E-03 501301 + 617 501310 Sn-131 1.04640E-03 1.10730E-03 501310 + 618 501311 Sn-131m 2.92780E-03 2.96060E-03 501311 + 619 501320 Sn-132 1.67900E-03 1.68510E-03 501320 + 620 501330 Sn-133 1.36830E-04 1.36830E-04 501330 + 621 501340 Sn-134 1.03080E-05 1.03080E-05 501340 + 622 501350 Sn-135 9.89350E-07 9.89350E-07 501350 + 623 501360 Sn-136 5.20000E-09 5.20000E-09 501360 + 624 511190 Sb-119 1.00520E-11 1.40880E-11 511190 + 625 511191 Sb-119m 4.03620E-12 4.03620E-12 511191 + 626 511200 Sb-120 6.52190E-10 6.52190E-10 511200 + 627 511201 Sb-120m 1.09070E-09 1.09070E-09 511201 + 628 511210 Sb-121 4.00660E-08 2.47210E-04 51121.82c + 629 511220 Sb-122 9.70880E-07 2.27160E-06 511220 + 630 511221 Sb-122m 1.30070E-06 1.30070E-06 511221 + 631 511230 Sb-123 1.05310E-10 3.36480E-04 51123.82c + 632 511240 Sb-124 3.07880E-06 7.92380E-06 51124.82c + 633 511241 Sb-124m 2.48360E-06 6.45990E-06 511241 + 634 511242 Sb-124m 3.97630E-06 3.97630E-06 511242 + 635 511250 Sb-125 4.21330E-05 1.24600E-03 51125.82c + 636 511260 Sb-126 3.92630E-05 4.69520E-05 51126.82c + 637 511261 Sb-126m 2.45240E-05 5.49250E-05 511261 + 638 511262 Sb-126m 3.04010E-05 3.04010E-05 511262 + 639 511270 Sb-127 4.83940E-04 5.09520E-03 511270 + 640 511280 Sb-128 5.79280E-04 8.60760E-03 511280 + 641 511281 Sb-128m 8.10220E-04 8.10220E-04 511281 + 642 511290 Sb-129 3.89420E-03 1.04620E-02 511290 + 643 511291 Sb-129m 2.88190E-03 5.64430E-03 511291 + 644 511300 Sb-130 6.44500E-03 1.16760E-02 511300 + 645 511301 Sb-130m 6.44500E-03 9.35820E-03 511301 + 646 511310 Sb-131 2.34020E-02 2.74700E-02 511310 + 647 511320 Sb-132 1.08570E-02 1.25420E-02 511320 + 648 511321 Sb-132m 9.61270E-03 9.61270E-03 511321 + 649 511330 Sb-133 1.50760E-02 1.52150E-02 511330 + 650 511340 Sb-134 1.05760E-03 1.06620E-03 511340 + 651 511341 Sb-134m 2.88270E-03 2.88280E-03 511341 + 652 511350 Sb-135 9.36930E-04 9.37710E-04 511350 + 653 511360 Sb-136 1.29020E-04 1.29020E-04 511360 + 654 511370 Sb-137 2.74430E-05 2.74430E-05 511370 + 655 511380 Sb-138 2.03500E-08 2.03500E-08 511380 + 656 521250 Te-125 7.59370E-12 1.24600E-03 52125.82c + 657 521251 Te-125m 2.87570E-11 2.78810E-04 521251 + 658 521260 Te-126 2.02190E-06 9.62090E-05 52126.82c + 659 521270 Te-127 1.85930E-06 5.08200E-03 521270 + 660 521271 Te-127m 5.20220E-06 8.44870E-04 52527.82c + 661 521280 Te-128 6.42430E-05 9.45290E-03 52128.82c + 662 521290 Te-129 1.03000E-04 1.31680E-02 521290 + 663 521291 Te-129m 2.88200E-04 6.70960E-03 52529.82c + 664 521300 Te-130 2.57440E-03 2.36090E-02 52130.82c + 665 521310 Te-131 2.03220E-03 2.89590E-02 521310 + 666 521311 Te-131m 5.68600E-03 7.88530E-03 521311 + 667 521320 Te-132 2.34420E-02 4.55970E-02 52132.82c + 668 521330 Te-133 9.12280E-03 2.66360E-02 521330 + 669 521331 Te-133m 2.55250E-02 2.81570E-02 521331 + 670 521340 Te-134 3.98940E-02 4.39880E-02 521340 + 671 521350 Te-135 1.42800E-02 1.50920E-02 521350 + 672 521360 Te-136 6.23920E-03 6.36030E-03 521360 + 673 521370 Te-137 1.21520E-03 1.22920E-03 521370 + 674 521380 Te-138 2.27360E-04 2.27380E-04 521380 + 675 521390 Te-139 1.36440E-05 1.36440E-05 521390 + 676 521400 Te-140 1.96980E-06 1.96980E-06 521400 + 677 521410 Te-141 2.97260E-09 2.97260E-09 521410 + 678 531280 I-128 2.18590E-09 2.18590E-09 531280 + 679 531290 I-129 8.11700E-06 1.56580E-02 53129.82c + 680 531300 I-130 1.70670E-05 2.23260E-05 53130.82c + 681 531301 I-130m 6.26120E-06 6.26120E-06 531301 + 682 531310 I-131 2.97800E-04 3.54860E-02 53131.82c + 683 531320 I-132 7.49300E-04 4.69170E-02 531320 + 684 531321 I-132m 6.63400E-04 6.63400E-04 531321 + 685 531330 I-133 4.59830E-03 5.78660E-02 531330 + 686 531331 I-133m 3.40290E-03 3.40290E-03 531331 + 687 531340 I-134 1.27300E-02 6.77290E-02 531340 + 688 531341 I-134m 1.12700E-02 1.12700E-02 531341 + 689 531350 I-135 5.61870E-02 7.12780E-02 53135.82c + 690 531360 I-136 1.11530E-02 1.75310E-02 531360 + 691 531361 I-136m 3.04000E-02 3.04190E-02 531361 + 692 531370 I-137 2.92640E-02 3.04710E-02 531370 + 693 531380 I-138 9.31880E-03 9.53190E-03 531380 + 694 531390 I-139 4.70630E-03 4.71990E-03 531390 + 695 531400 I-140 9.52650E-04 9.54620E-04 531400 + 696 531410 I-141 2.10870E-04 2.10870E-04 531410 + 697 531420 I-142 1.48890E-05 1.48890E-05 531420 + 698 531430 I-143 1.72390E-08 1.72390E-08 531430 + 699 541300 Xe-130 8.06590E-10 2.33290E-05 54130.82c + 700 541310 Xe-131 1.74810E-08 3.54860E-02 54131.82c + 701 541311 Xe-131m 4.89110E-08 3.85490E-04 541311 + 702 541320 Xe-132 6.95380E-06 4.70260E-02 54132.82c + 703 541321 Xe-132m 9.31620E-06 9.31620E-06 541321 + 704 541330 Xe-133 2.94420E-05 5.79780E-02 54133.82c + 705 541331 Xe-133m 8.23780E-05 1.72950E-03 541331 + 706 541340 Xe-134 3.05060E-04 6.91250E-02 54134.82c + 707 541341 Xe-134m 8.31540E-04 1.09080E-03 541341 + 708 541350 Xe-135 1.47690E-03 7.67920E-02 54135.82c + 709 541351 Xe-135m 4.13220E-03 1.58990E-02 541351 + 710 541360 Xe-136 2.69080E-02 7.68390E-02 54136.82c + 711 541370 Xe-137 3.34900E-02 6.24850E-02 541370 + 712 541380 Xe-138 3.51140E-02 4.46030E-02 541380 + 713 541390 Xe-139 1.77650E-02 2.21110E-02 541390 + 714 541400 Xe-140 1.21050E-02 1.30150E-02 541400 + 715 541410 Xe-141 4.28130E-03 4.45160E-03 541410 + 716 541420 Xe-142 1.17230E-03 1.18350E-03 541420 + 717 541430 Xe-143 1.71920E-04 1.71930E-04 541430 + 718 541440 Xe-144 2.65340E-05 2.65340E-05 541440 + 719 541450 Xe-145 9.73070E-07 9.73070E-07 541450 + 720 541460 Xe-146 1.89930E-09 1.89930E-09 541460 + 721 551330 Cs-133 1.42810E-08 5.79780E-02 55133.82c + 722 551340 Cs-134 1.64050E-06 3.09300E-06 55134.82c + 723 551341 Cs-134m 1.45250E-06 1.45250E-06 551341 + 724 551350 Cs-135 3.87000E-05 7.69550E-02 55135.82c + 725 551351 Cs-135m 2.86400E-05 2.86400E-05 551351 + 726 551360 Cs-136 3.81840E-04 5.18350E-04 55136.82c + 727 551361 Cs-136m 2.73010E-04 2.73010E-04 551361 + 728 551370 Cs-137 6.33120E-03 6.88170E-02 55137.82c + 729 551380 Cs-138 5.48500E-03 5.75180E-02 551380 + 730 551381 Cs-138m 9.17300E-03 9.17300E-03 551381 + 731 551390 Cs-139 2.88090E-02 5.09200E-02 551390 + 732 551400 Cs-140 2.77730E-02 4.07900E-02 551400 + 733 551410 Cs-141 3.53800E-02 3.98340E-02 551410 + 734 551420 Cs-142 2.02240E-02 2.14050E-02 551420 + 735 551430 Cs-143 1.09870E-02 1.11580E-02 551430 + 736 551440 Cs-144 1.87830E-03 2.84320E-03 551440 + 737 551441 Cs-144m 1.87830E-03 1.87830E-03 551441 + 738 551450 Cs-145 9.80660E-04 9.81590E-04 551450 + 739 551460 Cs-146 1.75440E-04 1.75440E-04 551460 + 740 551470 Cs-147 3.09580E-05 3.09580E-05 551470 + 741 551480 Cs-148 8.48560E-09 8.48560E-09 551480 + 742 561350 Ba-135 5.72310E-10 2.17360E-09 56135.82c + 743 561351 Ba-135m 1.60130E-09 1.60130E-09 561351 + 744 561360 Ba-136 2.70950E-07 6.55860E-04 56136.82c + 745 561361 Ba-136m 7.38550E-07 7.38550E-07 561361 + 746 561370 Ba-137 1.01790E-05 6.88550E-02 56137.82c + 747 561371 Ba-137m 2.84810E-05 6.49910E-02 561371 + 748 561380 Ba-138 4.91380E-04 5.97530E-02 56138.82c + 749 561390 Ba-139 1.85610E-03 5.27760E-02 561390 + 750 561400 Ba-140 6.31620E-03 4.71060E-02 56140.82c + 751 561410 Ba-141 1.00130E-02 4.98470E-02 561410 + 752 561420 Ba-142 2.19640E-02 4.35520E-02 561420 + 753 561430 Ba-143 1.97000E-02 3.07660E-02 561430 + 754 561440 Ba-144 1.70280E-02 2.08600E-02 561440 + 755 561450 Ba-145 7.24370E-03 8.10980E-03 561450 + 756 561460 Ba-146 3.37340E-03 3.53270E-03 561460 + 757 561470 Ba-147 8.69550E-04 8.91690E-04 561470 + 758 561480 Ba-148 1.81350E-04 1.81360E-04 561480 + 759 561490 Ba-149 1.85950E-05 1.85950E-05 561490 + 760 561500 Ba-150 1.96660E-06 1.96660E-06 561500 + 761 561510 Ba-151 6.32080E-10 6.32080E-10 561510 + 762 571380 La-138 1.25230E-08 1.25230E-08 57138.82c + 763 571390 La-139 3.21890E-05 5.28090E-02 57139.82c + 764 571400 La-140 1.47120E-04 4.72530E-02 57140.82c + 765 571410 La-141 9.14550E-04 5.07620E-02 571410 + 766 571420 La-142 2.27410E-03 4.58260E-02 571420 + 767 571430 La-143 8.80380E-03 3.95700E-02 571430 + 768 571440 La-144 1.49700E-02 3.58300E-02 571440 + 769 571450 La-145 2.29230E-02 3.10330E-02 571450 + 770 571460 La-146 5.58830E-03 9.12110E-03 571460 + 771 571461 La-146m 1.17240E-02 1.17240E-02 571461 + 772 571470 La-147 1.43980E-02 1.52900E-02 571470 + 773 571480 La-148 6.56050E-03 6.74120E-03 571480 + 774 571490 La-149 2.42620E-03 2.44470E-03 571490 + 775 571500 La-150 5.30550E-04 5.32520E-04 571500 + 776 571510 La-151 9.92050E-05 9.92060E-05 571510 + 777 571520 La-152 8.94740E-06 8.94740E-06 571520 + 778 571530 La-153 3.03140E-09 3.03140E-09 571530 + 779 581390 Ce-139 2.56670E-07 9.74820E-07 581390 + 780 581391 Ce-139m 7.18150E-07 7.18150E-07 581391 + 781 581400 Ce-140 1.61270E-09 4.72530E-02 58140.82c + 782 581410 Ce-141 4.00910E-06 5.07650E-02 58141.82c + 783 581420 Ce-142 2.78150E-05 4.58540E-02 58142.82c + 784 581430 Ce-143 1.39200E-04 3.97090E-02 58143.82c + 785 581440 Ce-144 8.23310E-04 3.66530E-02 58144.82c + 786 581450 Ce-145 2.31720E-03 3.33500E-02 581450 + 787 581460 Ce-146 6.42170E-03 2.72660E-02 581460 + 788 581470 Ce-147 8.29870E-03 2.35890E-02 581470 + 789 581480 Ce-148 1.04620E-02 1.72370E-02 581480 + 790 581490 Ce-149 6.66770E-03 9.09260E-03 581490 + 791 581500 Ce-150 4.04680E-03 4.56490E-03 581500 + 792 581510 Ce-151 1.27210E-03 1.37180E-03 581510 + 793 581520 Ce-152 3.87510E-04 3.95920E-04 581520 + 794 581530 Ce-153 4.86190E-05 4.86220E-05 581530 + 795 581540 Ce-154 2.98150E-06 2.98150E-06 581540 + 796 581550 Ce-155 1.14170E-08 1.14170E-08 581550 + 797 581560 Ce-156 1.54310E-10 1.54310E-10 581560 + 798 591430 Pr-143 9.84890E-07 3.97100E-02 59143.82c + 799 591440 Pr-144 8.80170E-07 3.66630E-02 591440 + 800 591441 Pr-144m 8.95410E-06 5.14750E-04 591441 + 801 591450 Pr-145 6.62600E-05 3.34160E-02 591450 + 802 591460 Pr-146 2.98730E-04 2.75650E-02 591460 + 803 591470 Pr-147 1.42450E-03 2.50140E-02 591470 + 804 591480 Pr-148 5.33720E-04 1.77710E-02 591480 + 805 591481 Pr-148m 2.58750E-03 2.58750E-03 591481 + 806 591490 Pr-149 6.99850E-03 1.60910E-02 591490 + 807 591500 Pr-150 7.66230E-03 1.22270E-02 591500 + 808 591510 Pr-151 7.66410E-03 9.03590E-03 591510 + 809 591520 Pr-152 4.39610E-03 4.79230E-03 591520 + 810 591530 Pr-153 2.11850E-03 2.16680E-03 591530 + 811 591540 Pr-154 6.19670E-04 6.22630E-04 591540 + 812 591550 Pr-155 1.48880E-04 1.48890E-04 591550 + 813 591560 Pr-156 2.09810E-05 2.09810E-05 591560 + 814 591570 Pr-157 2.95950E-06 2.95950E-06 591570 + 815 591580 Pr-158 4.71270E-10 4.71270E-10 591580 + 816 601450 Nd-145 9.52010E-10 3.34160E-02 60145.82c + 817 601460 Nd-146 3.97650E-06 2.75690E-02 60146.82c + 818 601470 Nd-147 1.09950E-05 2.50250E-02 60147.82c + 819 601480 Nd-148 7.62370E-05 2.04350E-02 60148.82c + 820 601490 Nd-149 2.51850E-04 1.63430E-02 601490 + 821 601500 Nd-150 9.78730E-04 1.32060E-02 60150.82c + 822 601510 Nd-151 1.70750E-03 1.07430E-02 601510 + 823 601520 Nd-152 2.86160E-03 7.65390E-03 601520 + 824 601530 Nd-153 2.46220E-03 4.62900E-03 601530 + 825 601540 Nd-154 1.90570E-03 2.52830E-03 601540 + 826 601550 Nd-155 8.38480E-04 9.87940E-04 601550 + 827 601560 Nd-156 3.01350E-04 3.21950E-04 601560 + 828 601570 Nd-157 7.78670E-05 8.06380E-05 601570 + 829 601580 Nd-158 9.74100E-06 9.74150E-06 601580 + 830 601590 Nd-159 9.55140E-07 9.55140E-07 601590 + 831 601600 Nd-160 1.88230E-09 1.88230E-09 601600 + 832 601610 Nd-161 1.61300E-11 1.61300E-11 601610 + 833 611480 Pm-148 2.65280E-07 3.01430E-07 61148.82c + 834 611481 Pm-148m 7.23080E-07 7.23080E-07 61548.82c + 835 611490 Pm-149 3.91680E-06 1.63470E-02 61149.82c + 836 611500 Pm-150 2.95270E-05 2.95270E-05 611500 + 837 611510 Pm-151 1.68690E-04 1.09120E-02 61151.82c + 838 611520 Pm-152 7.18710E-05 7.72580E-03 611520 + 839 611521 Pm-152m 1.51100E-04 1.51100E-04 611521 + 840 611522 Pm-152m 1.97370E-04 1.97370E-04 611522 + 841 611530 Pm-153 1.12510E-03 5.75410E-03 611530 + 842 611540 Pm-154 7.78150E-04 3.30650E-03 611540 + 843 611541 Pm-154m 7.78150E-04 7.78150E-04 611541 + 844 611550 Pm-155 2.00790E-03 2.99580E-03 611550 + 845 611560 Pm-156 1.43310E-03 1.75500E-03 611560 + 846 611570 Pm-157 9.46410E-04 1.02710E-03 611570 + 847 611580 Pm-158 3.50620E-04 3.60360E-04 611580 + 848 611590 Pm-159 1.01930E-04 1.02880E-04 611590 + 849 611600 Pm-160 2.41000E-05 2.41020E-05 611600 + 850 611610 Pm-161 5.50340E-06 5.50340E-06 611610 + 851 611620 Pm-162 3.14760E-09 3.14760E-09 611620 + 852 611630 Pm-163 5.55180E-11 5.55180E-11 611630 + 853 621500 Sm-150 4.52590E-10 2.95280E-05 62150.82c + 854 621510 Sm-151 1.48540E-08 1.09120E-02 62151.82c + 855 621520 Sm-152 9.94960E-06 8.08420E-03 62152.82c + 856 621530 Sm-153 5.76020E-06 5.77600E-03 62153.82c + 857 621531 Sm-153m 1.61170E-05 1.61170E-05 621531 + 858 621540 Sm-154 9.88750E-05 4.18350E-03 62154.82c + 859 621550 Sm-155 2.15070E-04 3.21090E-03 621550 + 860 621560 Sm-156 4.57270E-04 2.21230E-03 621560 + 861 621570 Sm-157 4.79040E-04 1.50610E-03 621570 + 862 621580 Sm-158 4.84100E-04 8.44480E-04 621580 + 863 621590 Sm-159 3.08780E-04 4.11710E-04 621590 + 864 621600 Sm-160 1.19870E-04 1.43910E-04 621600 + 865 621610 Sm-161 4.16530E-05 4.71560E-05 621610 + 866 621620 Sm-162 7.12860E-06 7.13170E-06 621620 + 867 621630 Sm-163 1.83780E-07 1.83840E-07 621630 + 868 621640 Sm-164 9.20190E-09 9.20190E-09 621640 + 869 621650 Sm-165 1.46850E-10 1.46850E-10 621650 + 870 631530 Eu-153 1.06990E-09 5.77600E-03 63153.82c + 871 631540 Eu-154 1.53810E-08 3.19630E-08 63154.82c + 872 631541 Eu-154m 1.65820E-08 1.65820E-08 631541 + 873 631550 Eu-155 1.09340E-05 3.22190E-03 63155.82c + 874 631560 Eu-156 3.67350E-05 2.24910E-03 63156.82c + 875 631570 Eu-157 1.12960E-04 1.61900E-03 63157.82c + 876 631580 Eu-158 1.74460E-04 1.01890E-03 631580 + 877 631590 Eu-159 2.58770E-04 6.70480E-04 631590 + 878 631600 Eu-160 2.41190E-04 3.85100E-04 631600 + 879 631610 Eu-161 1.83640E-04 2.30800E-04 631610 + 880 631620 Eu-162 8.21910E-05 8.93230E-05 631620 + 881 631630 Eu-163 3.90990E-05 3.92830E-05 631630 + 882 631640 Eu-164 1.09280E-05 1.09370E-05 631640 + 883 631650 Eu-165 2.57570E-07 2.57720E-07 631650 + 884 631660 Eu-166 5.15190E-09 5.15190E-09 631660 + 885 631670 Eu-167 3.00290E-10 3.00290E-10 631670 + 886 641550 Gd-155 2.44390E-11 3.22190E-03 64155.82c + 887 641551 Gd-155m 6.83800E-11 6.83800E-11 641551 + 888 641560 Gd-156 3.39480E-09 2.24910E-03 64156.82c + 889 641570 Gd-157 7.37000E-08 1.61910E-03 64157.82c + 890 641580 Gd-158 9.73800E-07 1.01990E-03 64158.82c + 891 641590 Gd-159 1.42710E-05 6.84750E-04 641590 + 892 641600 Gd-160 2.75430E-05 4.12640E-04 64160.82c + 893 641610 Gd-161 4.45620E-05 2.75360E-04 641610 + 894 641620 Gd-162 5.04150E-05 1.39740E-04 641620 + 895 641630 Gd-163 3.26820E-05 7.19650E-05 641630 + 896 641640 Gd-164 2.91080E-05 4.00450E-05 641640 + 897 641650 Gd-165 1.27910E-05 1.30490E-05 641650 + 898 641660 Gd-166 7.38400E-07 7.43550E-07 641660 + 899 641670 Gd-167 2.18180E-07 2.18480E-07 641670 + 900 641680 Gd-168 1.74340E-08 1.74340E-08 641680 + 901 641690 Gd-169 7.25650E-10 7.25650E-10 641690 + 902 651580 Tb-158 1.43030E-10 1.57000E-10 651580 + 903 651581 Tb-158m 1.40600E-11 1.40600E-11 651581 + 904 651590 Tb-159 5.76640E-09 6.84750E-04 65159.82c + 905 651600 Tb-160 9.23500E-07 9.23500E-07 65160.82c + 906 651610 Tb-161 3.66070E-06 2.79020E-04 651610 + 907 651620 Tb-162 9.75320E-06 1.49490E-04 651620 + 908 651630 Tb-163 1.85030E-05 9.04680E-05 651630 + 909 651640 Tb-164 2.17530E-05 6.17980E-05 651640 + 910 651650 Tb-165 1.91450E-05 3.21940E-05 651650 + 911 651660 Tb-166 9.60000E-06 1.03440E-05 651660 + 912 651670 Tb-167 9.33870E-06 9.55720E-06 651670 + 913 651680 Tb-168 3.91320E-06 3.93060E-06 651680 + 914 651690 Tb-169 2.83970E-07 2.84700E-07 651690 + 915 651700 Tb-170 4.37160E-09 4.37160E-09 651700 + 916 651710 Tb-171 4.70080E-10 4.70080E-10 651710 + 917 661600 Dy-160 1.42600E-11 9.23510E-07 66160.82c + 918 661610 Dy-161 3.22620E-10 2.79020E-04 66161.82c + 919 661620 Dy-162 7.60150E-09 1.49500E-04 66162.82c + 920 661630 Dy-163 7.76050E-08 9.05450E-05 66163.82c + 921 661640 Dy-164 9.08610E-07 6.27070E-05 66164.82c + 922 661650 Dy-165 2.41410E-06 3.49220E-05 661650 + 923 661651 Dy-165m 3.21420E-07 3.21420E-07 661651 + 924 661660 Dy-166 2.69450E-06 1.30380E-05 661660 + 925 661670 Dy-167 9.33500E-07 1.04910E-05 661670 + 926 661680 Dy-168 1.95580E-06 5.88640E-06 661680 + 927 661690 Dy-169 3.68110E-06 3.96580E-06 661690 + 928 661700 Dy-170 2.53570E-07 2.57940E-07 661700 + 929 661710 Dy-171 7.76620E-08 7.81320E-08 661710 + 930 661720 Dy-172 1.50970E-08 1.50970E-08 661720 + 931 661730 Dy-173 8.18920E-10 8.18920E-10 661730 + 932 671630 Ho-163 1.22490E-11 1.38800E-11 671630 + 933 671631 Ho-163m 1.63090E-12 1.63090E-12 671631 + 934 671640 Ho-164 1.11130E-10 4.14050E-10 671640 + 935 671641 Ho-164m 3.02920E-10 3.02920E-10 671641 + 936 671650 Ho-165 9.12050E-07 3.58410E-05 67165.82c + 937 671660 Ho-166 7.50120E-09 1.30460E-05 671660 + 938 671661 Ho-166m 2.04470E-08 2.04470E-08 671661 + 939 671670 Ho-167 9.33380E-07 1.14240E-05 671670 + 940 671680 Ho-168 3.65910E-07 6.86120E-06 671680 + 941 671681 Ho-168m 6.11940E-07 6.11940E-07 671681 + 942 671690 Ho-169 1.84000E-06 5.80580E-06 671690 + 943 671700 Ho-170 5.02230E-07 5.02230E-07 671700 + 944 671701 Ho-170m 1.84250E-07 4.42190E-07 671701 + 945 671710 Ho-171 7.50080E-07 8.28210E-07 671710 + 946 671720 Ho-172 2.52690E-07 2.67790E-07 671720 + 947 671730 Ho-173 7.49620E-08 7.57810E-08 671730 + 948 671740 Ho-174 8.74690E-09 8.74690E-09 671740 + 949 671750 Ho-175 8.99720E-10 8.99720E-10 671750 + 950 681650 Er-165 1.02690E-12 1.02690E-12 681650 + 951 681660 Er-166 1.31180E-11 1.30460E-05 68166.82c + 952 681670 Er-167 3.96070E-10 1.14250E-05 68167.82c + 953 681671 Er-167m 5.27340E-11 1.36510E-06 681671 + 954 681680 Er-168 6.62770E-09 6.87090E-06 68168.82c + 955 681690 Er-169 5.06760E-08 5.85650E-06 681690 + 956 681700 Er-170 4.76070E-08 9.92030E-07 68170.82c + 957 681710 Er-171 1.61170E-07 9.89380E-07 681710 + 958 681720 Er-172 3.54200E-07 6.21990E-07 681720 + 959 681730 Er-173 2.37660E-07 3.13440E-07 681730 + 960 681740 Er-174 1.33110E-07 1.41860E-07 681740 + 961 681750 Er-175 3.59510E-08 3.68510E-08 681750 + 962 681760 Er-176 8.51300E-09 8.51300E-09 681760 + 963 681770 Er-177 5.91930E-10 5.91930E-10 681770 + 964 691690 Tm-169 4.02660E-11 5.85650E-06 691690 + 965 691700 Tm-170 1.16290E-10 1.16290E-10 691700 + 966 691710 Tm-171 2.29530E-09 9.91680E-07 691710 + 967 691720 Tm-172 1.37170E-08 6.35700E-07 691720 + 968 691730 Tm-173 4.57570E-08 3.59200E-07 691730 + 969 691740 Tm-174 5.91240E-08 2.00980E-07 691740 + 970 691750 Tm-175 7.13340E-08 1.08180E-07 691750 + 971 691760 Tm-176 3.91540E-08 4.76670E-08 691760 + 972 691770 Tm-177 2.81410E-08 2.87330E-08 691770 + 973 691780 Tm-178 3.44760E-09 3.44760E-09 691780 + 974 691790 Tm-179 6.42120E-10 6.42120E-10 691790 + 975 701720 Yb-172 2.79390E-11 6.35730E-07 701720 + 976 701730 Yb-173 2.80250E-10 3.59480E-07 701730 + 977 701740 Yb-174 2.04340E-09 2.03030E-07 701740 + 978 701750 Yb-175 5.67380E-09 1.14610E-07 701750 + 979 701751 Yb-175m 7.55430E-10 8.40580E-08 701751 + 980 701760 Yb-176 5.43370E-09 6.09770E-08 701760 + 981 701761 Yb-176m 1.13990E-08 3.52330E-08 701761 + 982 701770 Yb-177 1.10010E-08 4.19490E-08 701770 + 983 701771 Yb-177m 2.21500E-09 3.09480E-08 701771 + 984 701780 Yb-178 1.50740E-08 1.85220E-08 701780 + 985 701790 Yb-179 6.74410E-09 7.38620E-09 701790 + 986 701800 Yb-180 2.55960E-09 2.55960E-09 701800 + 987 701810 Yb-181 3.99620E-10 3.99620E-10 701810 + 988 711740 Lu-174 2.99020E-13 1.10940E-12 711740 + 989 711750 Lu-175 2.15470E-11 1.14630E-07 71175.82c + 990 711760 Lu-176 1.11770E-10 3.63510E-09 71176.82c + 991 711761 Lu-176m 5.32750E-11 5.32750E-11 711761 + 992 711770 Lu-177 4.69560E-10 4.24700E-08 711770 + 993 711771 Lu-177m 2.23580E-10 2.29150E-10 711771 + 994 711772 Lu-177m 1.11260E-11 1.11260E-11 711772 + 995 711780 Lu-178 8.56980E-10 1.93790E-08 711780 + 996 711781 Lu-178m 1.14810E-09 1.14810E-09 711781 + 997 711790 Lu-179 3.64810E-09 1.15200E-08 711790 + 998 711791 Lu-179m 4.85720E-10 7.87190E-09 711791 + 999 711800 Lu-180 9.31510E-10 3.50180E-09 711800 + 1000 711801 Lu-180m 9.31510E-10 3.49110E-09 711801 + 1001 711802 Lu-180m 1.64950E-09 1.64950E-09 711802 + 1002 711810 Lu-181 2.53300E-09 2.93260E-09 711810 + 1003 711820 Lu-182 8.51270E-10 8.51270E-10 711820 + 1004 711830 Lu-183 2.56300E-10 2.56300E-10 711830 + 1005 711840 Lu-184 3.04560E-11 3.04560E-11 711840 + 1006 721780 Hf-178 5.44110E-12 2.05440E-08 72178.82c + 1007 721781 Hf-178m 1.01470E-11 1.15950E-09 721781 + 1008 721782 Hf-178m 1.26930E-12 1.26930E-12 721782 + 1009 721790 Hf-179 5.70150E-11 1.16190E-08 72179.82c + 1010 721791 Hf-179m 1.64980E-11 1.64980E-11 721791 + 1011 721792 Hf-179m 2.49240E-11 2.49240E-11 721792 + 1012 721800 Hf-180 1.40720E-10 6.50490E-09 72180.82c + 1013 721801 Hf-180m 2.95210E-10 1.12000E-09 721801 + 1014 721810 Hf-181 7.52790E-10 3.68540E-09 721810 + 1015 721820 Hf-182 3.67770E-10 1.54310E-09 721820 + 1016 721821 Hf-182m 7.71530E-10 7.71530E-10 721821 + 1017 721830 Hf-183 7.74680E-10 1.03100E-09 721830 + 1018 721840 Hf-184 1.42170E-10 1.57400E-10 721840 + 1019 721841 Hf-184m 2.98260E-10 3.13490E-10 721841 + 1020 721850 Hf-185 1.21470E-10 1.21470E-10 721850 + 1021 721860 Hf-186 2.93620E-11 2.93620E-11 721860 + 1022 721870 Hf-187 2.70290E-12 2.70290E-12 721870 + 1023 731801 Ta-180m 5.75180E-13 4.04700E-12 731801 + 1024 731810 Ta-181 1.01380E-11 3.69560E-09 73181.82c + 1025 731820 Ta-182 1.35120E-11 4.89350E-10 73182.82c + 1026 731821 Ta-182m 1.47590E-11 4.75840E-10 731821 + 1027 731822 Ta-182m 1.35910E-11 4.61080E-10 731822 + 1028 731830 Ta-183 1.42010E-10 1.17300E-09 731830 + 1029 731840 Ta-184 1.86720E-10 6.57610E-10 731840 + 1030 731850 Ta-185 1.44060E-10 3.51490E-10 731850 + 1031 731851 Ta-185m 8.59590E-11 8.59590E-11 731851 + 1032 731860 Ta-186 1.28560E-10 1.57920E-10 731860 + 1033 731870 Ta-187 5.90330E-11 6.17360E-11 731870 + 1034 731880 Ta-188 1.17560E-11 1.17560E-11 731880 + 1035 731890 Ta-189 2.23650E-12 2.23650E-12 731890 + 1036 741840 W-184 6.11140E-12 6.63720E-10 74184.82c + 1037 741850 W-185 5.18750E-12 3.71190E-10 741850 + 1038 741851 W-185m 1.45140E-11 1.45140E-11 741851 + 1039 741860 W-186 3.75080E-11 2.10620E-10 74186.82c + 1040 741861 W-186m 1.51860E-11 1.51860E-11 741861 + 1041 741870 W-187 5.46530E-11 1.16390E-10 741870 + 1042 741880 W-188 4.90090E-11 6.07650E-11 741880 + 1043 741890 W-189 2.23220E-11 2.45590E-11 741890 + 1044 741900 W-190 3.68060E-12 8.61160E-12 741900 + 1045 741901 W-190m 4.93100E-12 4.93100E-12 741901 + 1046 741910 W-191 1.37530E-12 1.37530E-12 741910 + 1047 751870 Re-187 2.76250E-12 1.19150E-10 75187.82c + 1048 751880 Re-188 1.66570E-12 6.69710E-11 751880 + 1049 751881 Re-188m 4.54030E-12 4.54030E-12 751881 + 1050 751890 Re-189 1.30570E-11 3.76160E-11 751890 + 1051 751900 Re-190 3.64050E-12 1.57350E-11 751900 + 1052 751901 Re-190m 7.63750E-12 7.63750E-12 751901 + 1053 751910 Re-191 8.29890E-12 9.67420E-12 751910 + 1054 751920 Re-192 2.84920E-12 2.84920E-12 751920 + 1055 761900 Os-190 5.68530E-13 2.12200E-11 761900 + 1056 761901 Os-190m 7.61670E-13 4.91650E-12 761901 + 1057 761910 Os-191 1.86030E-12 1.20260E-11 761910 + 1058 761920 Os-192 1.55590E-12 6.23160E-12 761920 + 1059 761921 Os-192m 2.08450E-12 2.08450E-12 761921 + 1060 761930 Os-193 2.51480E-12 2.51480E-12 761930 + 1061 761940 Os-194 1.45330E-12 1.45330E-12 761940 + + Nuclide 95243.82c -- americium 243 (Am-243) + + Neutron-induced fission: + + Interpolation region : 1 / 2 + Interpolation energy : 2.53000E-08 MeV + Number of products : 1018 / 1121 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 2.87890E-05 2.87890E-05 1001.82c + 2 10020 H-2 8.79830E-06 8.79830E-06 1002.82c + 3 10030 H-3 1.57000E-04 1.57000E-04 1003.82c + 4 20040 He-4 1.82000E-03 1.82000E-03 2004.82c + 5 200500 Ca-50 1.04220E-12 1.04220E-12 200500 + 6 200510 Ca-51 1.29310E-12 1.29310E-12 200510 + 7 200520 Ca-52 1.37270E-12 1.37270E-12 200520 + 8 210510 Sc-51 1.16010E-12 2.48060E-12 210510 + 9 210520 Sc-52 2.72300E-12 4.06820E-12 210520 + 10 210530 Sc-53 5.27670E-12 5.27670E-12 210530 + 11 210540 Sc-54 4.56770E-12 4.56770E-12 210540 + 12 210550 Sc-55 3.78860E-12 3.78860E-12 210550 + 13 210560 Sc-56 1.25120E-12 1.25120E-12 210560 + 14 220530 Ti-53 2.84340E-12 8.12010E-12 220530 + 15 220540 Ti-54 1.07210E-11 1.52890E-11 220540 + 16 220550 Ti-55 2.00600E-11 2.38490E-11 220550 + 17 220560 Ti-56 3.17470E-11 3.29980E-11 220560 + 18 220570 Ti-57 2.34130E-11 2.34130E-11 220570 + 19 220580 Ti-58 1.46830E-11 1.46830E-11 220580 + 20 220590 Ti-59 3.65370E-12 3.65370E-12 220590 + 21 230550 V-55 5.81620E-12 2.96650E-11 230550 + 22 230560 V-56 2.04360E-11 5.35040E-11 230560 + 23 230570 V-57 6.60190E-11 8.93620E-11 230570 + 24 230580 V-58 9.64100E-11 1.11090E-10 230580 + 25 230590 V-59 1.19830E-10 1.23480E-10 230590 + 26 230600 V-60 6.23960E-11 6.23960E-11 230600 + 27 230610 V-61 3.17230E-11 3.17230E-11 230610 + 28 230620 V-62 6.42420E-12 6.42420E-12 230620 + 29 240560 Cr-56 1.42220E-12 5.52840E-11 240560 + 30 240570 Cr-57 1.12340E-11 1.89110E-10 240570 + 31 240580 Cr-58 7.38390E-11 9.60580E-11 240580 + 32 240590 Cr-59 2.01810E-10 3.25290E-10 240590 + 33 240600 Cr-60 4.69750E-10 5.34050E-10 240600 + 34 240610 Cr-61 5.78200E-10 6.08020E-10 240610 + 35 240620 Cr-62 6.09010E-10 6.15430E-10 240620 + 36 240630 Cr-63 2.53580E-10 2.53580E-10 240630 + 37 240640 Cr-64 8.61980E-11 8.61980E-11 240640 + 38 240650 Cr-65 1.31520E-11 1.31520E-11 240650 + 39 240660 Cr-66 1.49210E-12 1.49210E-12 240660 + 40 250580 Mn-58 1.16500E-12 9.72230E-11 250580 + 41 250590 Mn-59 1.78730E-11 3.43170E-10 250590 + 42 250600 Mn-60 9.89170E-12 5.54040E-10 250600 + 43 250601 Mn-60m 8.78520E-11 8.78520E-11 250601 + 44 250610 Mn-61 5.28950E-10 1.13700E-09 250610 + 45 250620 Mn-62 1.04470E-09 1.35250E-09 250620 + 46 250621 Mn-62m 1.87560E-10 4.95270E-10 250621 + 47 250630 Mn-63 2.36830E-09 2.62190E-09 250630 + 48 250640 Mn-64 2.03160E-09 2.11780E-09 250640 + 49 250650 Mn-65 1.67270E-09 1.68580E-09 250650 + 50 250660 Mn-66 5.48140E-10 5.49630E-10 250660 + 51 250670 Mn-67 1.52400E-10 1.52400E-10 250670 + 52 250680 Mn-68 1.69870E-11 1.69870E-11 250680 + 53 250690 Mn-69 1.41990E-12 1.41990E-12 250690 + 54 260600 Fe-60 1.84520E-12 6.33640E-10 260600 + 55 260610 Fe-61 2.64440E-11 1.16340E-09 260610 + 56 260620 Fe-62 2.98180E-10 2.14590E-09 260620 + 57 260630 Fe-63 1.30150E-09 3.92340E-09 260630 + 58 260640 Fe-64 4.86260E-09 6.98040E-09 260640 + 59 260650 Fe-65 9.03960E-09 1.07260E-08 260650 + 60 260660 Fe-66 1.42160E-08 1.47660E-08 260660 + 61 260670 Fe-67 1.03850E-08 1.05370E-08 260670 + 62 260680 Fe-68 6.44900E-09 6.46630E-09 260680 + 63 260690 Fe-69 1.59200E-09 1.59310E-09 260690 + 64 260700 Fe-70 3.01880E-10 3.01880E-10 260700 + 65 260710 Fe-71 2.66010E-11 2.66010E-11 260710 + 66 260720 Fe-72 1.45200E-12 1.45200E-12 260720 + 67 270620 Co-62 4.10260E-13 2.14630E-09 270620 + 68 270630 Co-63 3.25220E-11 3.95590E-09 270630 + 69 270640 Co-64 3.09280E-10 7.28970E-09 270640 + 70 270650 Co-65 2.67400E-09 1.34000E-08 270650 + 71 270660 Co-66 9.33040E-09 2.40960E-08 270660 + 72 270670 Co-67 2.98710E-08 4.04080E-08 270670 + 73 270680 Co-68 2.29780E-08 3.64020E-08 270680 + 74 270681 Co-68m 2.02710E-08 2.68490E-08 270681 + 75 270690 Co-69 5.34060E-08 5.48880E-08 270690 + 76 270700 Co-70 1.38020E-08 1.38020E-08 270700 + 77 270701 Co-70m 1.38020E-08 1.41040E-08 270701 + 78 270710 Co-71 1.39210E-08 1.39480E-08 270710 + 79 270720 Co-72 2.27320E-09 2.27470E-09 270720 + 80 270730 Co-73 4.11940E-10 4.11940E-10 270730 + 81 270740 Co-74 2.87600E-11 2.87600E-11 270740 + 82 280640 Ni-64 1.48380E-12 7.29120E-09 28064.82c + 83 280650 Ni-65 3.62840E-11 1.34360E-08 280650 + 84 280660 Ni-66 6.63770E-10 2.47600E-08 280660 + 85 280670 Ni-67 5.18870E-09 4.55970E-08 280670 + 86 280680 Ni-68 3.37800E-08 8.41560E-08 280680 + 87 280690 Ni-69 4.58570E-08 1.00200E-07 280690 + 88 280691 Ni-69m 4.58570E-08 4.58570E-08 280691 + 89 280700 Ni-70 2.12120E-07 2.40030E-07 280700 + 90 280710 Ni-71 2.59350E-07 2.73300E-07 280710 + 91 280720 Ni-72 2.20560E-07 2.22830E-07 280720 + 92 280730 Ni-73 1.12480E-07 1.12890E-07 280730 + 93 280740 Ni-74 4.58940E-08 4.59230E-08 280740 + 94 280750 Ni-75 3.37350E-09 3.37350E-09 280750 + 95 280760 Ni-76 7.42800E-10 7.42800E-10 280760 + 96 280770 Ni-77 2.45270E-11 2.45270E-11 280770 + 97 280780 Ni-78 1.33430E-12 1.33430E-12 280780 + 98 290670 Cu-67 3.39840E-11 4.56310E-08 290670 + 99 290680 Cu-68 1.81500E-10 8.46940E-08 290680 + 100 290681 Cu-68m 4.25120E-10 4.25120E-10 290681 + 101 290690 Cu-69 8.29790E-09 1.54350E-07 290690 + 102 290700 Cu-70 3.42680E-09 2.86010E-08 290700 + 103 290701 Cu-70m 3.81760E-08 5.03490E-08 290701 + 104 290702 Cu-70m 3.42680E-09 2.43450E-07 290702 + 105 290710 Cu-71 2.41900E-07 5.15200E-07 290710 + 106 290720 Cu-72 8.27550E-07 1.05040E-06 290720 + 107 290730 Cu-73 1.07300E-06 1.18590E-06 290730 + 108 290740 Cu-74 9.56730E-07 1.00270E-06 290740 + 109 290750 Cu-75 4.39370E-07 4.42690E-07 290750 + 110 290760 Cu-76 1.39810E-07 1.40180E-07 290760 + 111 290761 Cu-76m 1.39810E-07 1.40180E-07 290761 + 112 290770 Cu-77 5.52010E-08 5.52260E-08 290770 + 113 290780 Cu-78 6.97910E-09 6.98040E-09 290780 + 114 290790 Cu-79 7.29680E-10 7.29680E-10 290790 + 115 290800 Cu-80 1.84130E-11 1.84130E-11 290800 + 116 300690 Zn-69 5.37730E-12 1.54380E-07 300690 + 117 300691 Zn-69m 2.32560E-11 2.32560E-11 300691 + 118 300700 Zn-70 8.70060E-10 2.85930E-07 300700 + 119 300710 Zn-71 2.32180E-09 5.17520E-07 300710 + 120 300711 Zn-71m 1.00410E-08 1.00410E-08 300711 + 121 300720 Zn-72 1.12460E-07 1.16280E-06 300720 + 122 300730 Zn-73 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4.29830E-03 411060 + 359 411070 Nb-107 1.45280E-03 1.45470E-03 411070 + 360 411080 Nb-108 2.61430E-04 2.61430E-04 411080 + 361 411090 Nb-109 4.01520E-05 4.01520E-05 411090 + 362 411100 Nb-110 9.73920E-07 9.73920E-07 411100 + 363 420970 Mo-97 7.41820E-09 4.15020E-02 42097.82c + 364 420980 Mo-98 2.22060E-05 4.87520E-02 42098.82c + 365 420990 Mo-99 2.01550E-04 5.13670E-02 42099.82c + 366 421000 Mo-100 1.29980E-03 5.66550E-02 42100.82c + 367 421010 Mo-101 4.39960E-03 5.72350E-02 421010 + 368 421020 Mo-102 1.51250E-02 5.98770E-02 421020 + 369 421030 Mo-103 2.63720E-02 6.32920E-02 421030 + 370 421040 Mo-104 4.36980E-02 6.47960E-02 421040 + 371 421050 Mo-105 3.66490E-02 4.91960E-02 421050 + 372 421060 Mo-106 3.28010E-02 3.69930E-02 421060 + 373 421070 Mo-107 1.61000E-02 1.74840E-02 421070 + 374 421080 Mo-108 8.03360E-03 8.28390E-03 421080 + 375 421090 Mo-109 2.15340E-03 2.18890E-03 421090 + 376 421100 Mo-110 4.81730E-04 4.82310E-04 421100 + 377 421110 Mo-111 6.02110E-05 6.02110E-05 421110 + 378 421120 Mo-112 2.91340E-06 2.91340E-06 421120 + 379 421130 Mo-113 2.29400E-10 2.29400E-10 421130 + 380 430990 Tc-99 8.19830E-07 5.13670E-02 43099.82c + 381 430991 Tc-99m 1.89560E-07 4.52340E-02 430991 + 382 431000 Tc-100 4.10440E-06 4.10440E-06 431000 + 383 431010 Tc-101 4.90950E-05 5.72850E-02 431010 + 384 431020 Tc-102 1.41170E-04 6.00180E-02 431020 + 385 431021 Tc-102m 1.41170E-04 1.41170E-04 431021 + 386 431030 Tc-103 1.83150E-03 6.51240E-02 431030 + 387 431040 Tc-104 5.16880E-03 6.99650E-02 431040 + 388 431050 Tc-105 1.64410E-02 6.56380E-02 431050 + 389 431060 Tc-106 2.43840E-02 6.13770E-02 431060 + 390 431070 Tc-107 3.51080E-02 5.25920E-02 431070 + 391 431080 Tc-108 2.64200E-02 3.47160E-02 431080 + 392 431090 Tc-109 1.98260E-02 2.20030E-02 431090 + 393 431100 Tc-110 8.81470E-03 9.29760E-03 431100 + 394 431110 Tc-111 3.53890E-03 3.59850E-03 431110 + 395 431120 Tc-112 6.73400E-04 6.76250E-04 431120 + 396 431130 Tc-113 1.04160E-04 1.04160E-04 431130 + 397 431140 Tc-114 1.05090E-05 1.05090E-05 431140 + 398 431150 Tc-115 7.19070E-07 7.19070E-07 431150 + 399 441020 Ru-102 3.03510E-06 6.01630E-02 44102.82c + 400 441030 Ru-103 1.03080E-05 6.51590E-02 44103.82c + 401 441031 Ru-103m 2.48860E-05 2.48860E-05 441031 + 402 441040 Ru-104 2.59890E-04 7.02250E-02 44104.82c + 403 441050 Ru-105 1.12570E-03 6.67630E-02 44105.82c + 404 441060 Ru-106 4.48810E-03 6.58650E-02 44106.82c + 405 441070 Ru-107 9.09720E-03 6.16890E-02 441070 + 406 441080 Ru-108 1.86820E-02 5.34150E-02 441080 + 407 441090 Ru-109 2.01550E-02 4.21440E-02 441090 + 408 441100 Ru-110 2.01710E-02 2.94650E-02 441100 + 409 441110 Ru-111 1.12000E-02 1.48090E-02 441110 + 410 441120 Ru-112 5.91710E-03 6.59070E-03 441120 + 411 441130 Ru-113 8.20150E-04 1.32760E-03 441130 + 412 441131 Ru-113m 8.20150E-04 8.20150E-04 441131 + 413 441140 Ru-114 4.62860E-04 4.72780E-04 441140 + 414 441150 Ru-115 8.58060E-05 8.64220E-05 441150 + 415 441160 Ru-116 3.61780E-05 3.61780E-05 441160 + 416 441170 Ru-117 1.25090E-05 1.25090E-05 441170 + 417 441180 Ru-118 4.25110E-06 4.25110E-06 441180 + 418 451040 Rh-104 4.24050E-10 1.70200E-09 451040 + 419 451041 Rh-104m 1.27970E-09 1.27970E-09 451041 + 420 451050 Rh-105 2.60590E-06 6.67660E-02 45105.82c + 421 451051 Rh-105m 3.98370E-07 1.89530E-02 451051 + 422 451060 Rh-106 1.27020E-05 6.58780E-02 451060 + 423 451061 Rh-106m 2.97510E-05 2.97510E-05 451061 + 424 451070 Rh-107 2.99550E-04 6.19880E-02 451070 + 425 451080 Rh-108 2.31030E-04 5.36460E-02 451080 + 426 451081 Rh-108m 6.97170E-04 6.97170E-04 451081 + 427 451090 Rh-109 3.09100E-03 4.52350E-02 451090 + 428 451100 Rh-110 5.03410E-03 3.44990E-02 451100 + 429 451101 Rh-110m 1.34380E-04 1.34380E-04 451101 + 430 451110 Rh-111 8.15470E-03 2.29630E-02 451110 + 431 451120 Rh-112 3.23690E-03 9.82760E-03 451120 + 432 451121 Rh-112m 3.23690E-03 3.23690E-03 451121 + 433 451130 Rh-113 4.70760E-03 6.44530E-03 451130 + 434 451140 Rh-114 9.10800E-04 1.38380E-03 451140 + 435 451141 Rh-114m 9.10800E-04 9.10800E-04 451141 + 436 451150 Rh-115 6.29000E-04 7.15620E-04 451150 + 437 451160 Rh-116 4.56550E-05 8.16980E-05 451160 + 438 451161 Rh-116m 1.06940E-04 1.06940E-04 451161 + 439 451170 Rh-117 5.97460E-05 7.21730E-05 451170 + 440 451180 Rh-118 1.11240E-05 1.52000E-05 451180 + 441 451190 Rh-119 4.39470E-06 4.39470E-06 451190 + 442 451200 Rh-120 3.53160E-12 3.53160E-12 451200 + 443 461070 Pd-107 1.70720E-06 6.19930E-02 46107.82c + 444 461071 Pd-107m 3.20840E-06 3.20840E-06 461071 + 445 461080 Pd-108 2.44410E-05 5.43680E-02 46108.82c + 446 461090 Pd-109 2.77480E-05 4.53150E-02 461090 + 447 461091 Pd-109m 5.21480E-05 2.26700E-02 461091 + 448 461100 Pd-110 3.21450E-04 3.49550E-02 46110.82c + 449 461110 Pd-111 2.44080E-04 2.35180E-02 461110 + 450 461111 Pd-111m 4.58720E-04 5.50570E-04 461111 + 451 461120 Pd-112 1.50060E-03 1.45650E-02 461120 + 452 461130 Pd-113 3.80680E-04 7.74500E-03 461130 + 453 461131 Pd-113m 9.19020E-04 9.19020E-04 461131 + 454 461140 Pd-114 1.20030E-03 3.49490E-03 461140 + 455 461150 Pd-115 1.56590E-04 8.00150E-04 461150 + 456 461151 Pd-115m 2.94290E-04 3.98200E-04 461151 + 457 461160 Pd-116 2.16390E-04 4.05020E-04 461160 + 458 461170 Pd-117 2.45760E-05 1.43380E-04 461170 + 459 461171 Pd-117m 4.61880E-05 4.61880E-05 461171 + 460 461180 Pd-118 2.60750E-05 4.08320E-05 461180 + 461 461190 Pd-119 2.92210E-06 7.31680E-06 461190 + 462 461200 Pd-120 1.50430E-06 1.50430E-06 461200 + 463 461210 Pd-121 1.33800E-09 1.33800E-09 461210 + 464 461220 Pd-122 8.96580E-11 8.96580E-11 461220 + 465 461230 Pd-123 5.02540E-07 5.02540E-07 461230 + 466 461240 Pd-124 1.24270E-07 1.24270E-07 461240 + 467 471090 Ag-109 1.79410E-10 4.53150E-02 47109.82c + 468 471091 Ag-109m 1.17360E-09 4.52930E-02 471091 + 469 471100 Ag-110 2.91010E-07 3.00280E-07 471100 + 470 471101 Ag-110m 6.81630E-07 6.81630E-07 47510.82c + 471 471110 Ag-111 1.14630E-06 2.35570E-02 47111.82c + 472 471111 Ag-111m 7.49820E-06 2.34650E-02 471111 + 473 471120 Ag-112 3.23920E-05 1.45970E-02 471120 + 474 471130 Ag-113 8.40110E-06 5.11860E-03 471130 + 475 471131 Ag-113m 5.49560E-05 7.47130E-03 471131 + 476 471140 Ag-114 1.34950E-05 3.56510E-03 471140 + 477 471141 Ag-114m 5.67530E-05 5.67530E-05 471141 + 478 471150 Ag-115 9.04070E-06 7.27870E-04 471150 + 479 471151 Ag-115m 5.91390E-05 6.41520E-04 471151 + 480 471160 Ag-116 1.44080E-05 4.21460E-04 471160 + 481 471161 Ag-116m 3.37460E-05 3.37460E-05 471161 + 482 471170 Ag-117 6.32790E-06 8.48030E-05 471170 + 483 471171 Ag-117m 4.13940E-05 1.13080E-04 471171 + 484 471180 Ag-118 6.61920E-06 5.54210E-05 471180 + 485 471181 Ag-118m 2.78380E-05 3.36750E-05 471181 + 486 471190 Ag-119 3.42840E-06 7.08680E-06 471190 + 487 471191 Ag-119m 2.24270E-05 2.60850E-05 471191 + 488 471200 Ag-120 3.71920E-06 6.70230E-06 471200 + 489 471201 Ag-120m 5.27740E-06 6.02960E-06 471201 + 490 471210 Ag-121 1.32190E-05 1.32200E-05 471210 + 491 471220 Ag-122 1.82330E-06 1.82340E-06 471220 + 492 471221 Ag-122m 1.64240E-06 1.64240E-06 471221 + 493 471230 Ag-123 7.81780E-06 8.32030E-06 471230 + 494 471240 Ag-124 3.98480E-06 5.90380E-06 471240 + 495 471241 Ag-124m 3.58950E-06 3.58950E-06 471241 + 496 471250 Ag-125 1.03220E-05 1.03220E-05 471250 + 497 471260 Ag-126 5.45550E-06 5.45550E-06 471260 + 498 471270 Ag-127 4.25120E-07 4.25120E-07 471270 + 499 471280 Ag-128 2.83390E-08 2.83390E-08 471280 + 500 471290 Ag-129 1.30400E-09 1.30400E-09 471290 + 501 481120 Cd-112 3.69040E-09 1.45970E-02 48112.82c + 502 481130 Cd-113 2.15800E-07 7.72020E-03 48113.82c + 503 481131 Cd-113m 7.06020E-07 8.92020E-05 481131 + 504 481140 Cd-114 2.61490E-06 3.56770E-03 48114.82c + 505 481150 Cd-115 1.16310E-06 1.17910E-03 481150 + 506 481151 Cd-115m 3.80530E-06 6.05020E-05 48515.82c + 507 481160 Cd-116 6.44990E-06 4.59630E-04 48116.82c + 508 481170 Cd-117 7.72200E-07 1.51190E-04 481170 + 509 481171 Cd-117m 2.52640E-06 4.32140E-05 481171 + 510 481180 Cd-118 6.72880E-06 8.20180E-05 481180 + 511 481190 Cd-119 1.27240E-06 3.09010E-05 481190 + 512 481191 Cd-119m 3.07190E-06 6.61530E-06 481191 + 513 481200 Cd-120 1.72020E-05 2.77030E-05 481200 + 514 481210 Cd-121 5.16060E-06 1.70000E-05 481210 + 515 481211 Cd-121m 1.24580E-05 1.38400E-05 481211 + 516 481220 Cd-122 5.02610E-05 5.37270E-05 481220 + 517 481230 Cd-123 8.25830E-06 1.50690E-05 481230 + 518 481231 Cd-123m 1.99370E-05 2.14530E-05 481231 + 519 481240 Cd-124 7.53200E-05 8.30130E-05 481240 + 520 481250 Cd-125 4.12580E-05 4.64190E-05 481250 + 521 481251 Cd-125m 9.96020E-05 1.04760E-04 481251 + 522 481260 Cd-126 1.70210E-04 1.75670E-04 481260 + 523 481270 Cd-127 1.08400E-04 1.08830E-04 481270 + 524 481280 Cd-128 7.46980E-05 7.47260E-05 481280 + 525 481290 Cd-129 4.11610E-06 4.11680E-06 481290 + 526 481291 Cd-129m 9.93690E-06 9.93750E-06 481291 + 527 481300 Cd-130 5.04650E-06 5.04650E-06 481300 + 528 481310 Cd-131 2.88480E-08 2.88480E-08 481310 + 529 491140 In-114 2.10170E-11 8.22110E-11 491140 + 530 491141 In-114m 3.22140E-11 6.34140E-11 491141 + 531 491142 In-114m 3.12000E-11 3.12000E-11 491142 + 532 491150 In-115 1.35570E-09 1.18070E-03 49115.82c + 533 491151 In-115m 3.13480E-10 1.17910E-03 491151 + 534 491160 In-116 4.59220E-09 4.59220E-09 491160 + 535 491161 In-116m 7.03870E-09 1.38560E-08 491161 + 536 491162 In-116m 6.81730E-09 6.81730E-09 491162 + 537 491170 In-117 1.46530E-07 1.20920E-04 491170 + 538 491171 In-117m 3.38810E-08 1.39240E-04 491171 + 539 491180 In-118 2.10270E-07 8.22280E-05 491180 + 540 491181 In-118m 3.22290E-07 6.30080E-07 491181 + 541 491182 In-118m 3.12160E-07 3.12160E-07 491182 + 542 491190 In-119 5.88190E-07 1.17640E-05 491190 + 543 491191 In-119m 1.36000E-07 2.80470E-05 491191 + 544 491200 In-120 2.49300E-07 2.79520E-05 491200 + 545 491201 In-120m 2.49300E-07 2.49300E-07 491201 + 546 491202 In-120m 2.49300E-07 2.49300E-07 491202 + 547 491210 In-121 3.55440E-06 2.32650E-05 491210 + 548 491211 In-121m 8.21870E-07 1.20960E-05 491211 + 549 491220 In-122 6.59540E-06 6.03220E-05 491220 + 550 491221 In-122m 4.67930E-06 4.67930E-06 491221 + 551 491222 In-122m 4.67930E-06 4.67930E-06 491222 + 552 491230 In-123 2.30860E-05 4.89440E-05 491230 + 553 491231 In-123m 5.33800E-06 1.60010E-05 491231 + 554 491240 In-124 2.40020E-05 1.07020E-04 491240 + 555 491241 In-124m 2.16210E-05 2.16210E-05 491241 + 556 491250 In-125 1.97950E-04 3.24930E-04 491250 + 557 491251 In-125m 4.57710E-05 6.99720E-05 491251 + 558 491260 In-126 3.00980E-04 4.76650E-04 491260 + 559 491261 In-126m 2.71120E-04 2.71120E-04 491261 + 560 491270 In-127 1.01750E-03 1.01750E-03 491270 + 561 491271 In-127m 2.35280E-04 3.44100E-04 491271 + 562 491280 In-128 5.18040E-04 8.03640E-04 491280 + 563 491281 In-128m 2.10870E-04 2.85600E-04 491281 + 564 491282 In-128m 6.56590E-04 6.56590E-04 491282 + 565 491290 In-129 1.13580E-03 1.14580E-03 491290 + 566 491291 In-129m 2.62620E-04 2.66820E-04 491291 + 567 491300 In-130 1.73640E-04 1.78510E-04 491300 + 568 491301 In-130m 1.93940E-04 1.93940E-04 491301 + 569 491302 In-130m 3.29980E-04 3.29980E-04 491302 + 570 491310 In-131 7.68790E-05 7.76890E-05 491310 + 571 491311 In-131m 7.68790E-05 7.68790E-05 491311 + 572 491312 In-131m 7.68790E-05 7.68790E-05 491312 + 573 491320 In-132 2.25010E-05 2.25010E-05 491320 + 574 491330 In-133 2.48680E-06 3.06180E-06 491330 + 575 491331 In-133m 5.75010E-07 5.75010E-07 491331 + 576 491340 In-134 7.47320E-09 7.47320E-09 491340 + 577 501170 Sn-117 9.55200E-12 1.94580E-04 50117.82c + 578 501171 Sn-117m 3.12510E-11 4.12020E-07 501171 + 579 501180 Sn-118 9.33680E-10 8.28640E-05 50118.82c + 580 501190 Sn-119 2.15420E-09 3.82500E-05 50119.82c + 581 501191 Sn-119m 7.04790E-09 1.06340E-05 501191 + 582 501200 Sn-120 1.14990E-07 2.85660E-05 50120.82c + 583 501210 Sn-121 2.82480E-07 3.54370E-05 501210 + 584 501211 Sn-121m 6.81930E-07 3.31750E-06 501211 + 585 501220 Sn-122 2.30400E-06 7.19860E-05 50122.82c + 586 501230 Sn-123 3.91880E-06 7.65040E-06 50123.82c + 587 501231 Sn-123m 1.62330E-06 6.28370E-05 501231 + 588 501240 Sn-124 4.20660E-05 1.70700E-04 50124.82c + 589 501250 Sn-125 6.22780E-05 1.17160E-04 50125.82c + 590 501251 Sn-125m 2.57970E-05 3.65810E-04 501251 + 591 501260 Sn-126 4.72270E-04 1.22240E-03 50126.82c + 592 501270 Sn-127 8.82040E-04 1.27860E-03 501270 + 593 501271 Sn-127m 3.65360E-04 1.32800E-03 501271 + 594 501280 Sn-128 1.21970E-03 5.53660E-03 501280 + 595 501281 Sn-128m 2.85670E-03 3.51330E-03 501281 + 596 501290 Sn-129 1.86310E-03 3.15390E-03 501290 + 597 501291 Sn-129m 4.49780E-03 4.61980E-03 501291 + 598 501300 Sn-130 2.77400E-03 3.23160E-03 501300 + 599 501301 Sn-130m 6.49740E-03 6.74380E-03 501301 + 600 501310 Sn-131 1.79070E-03 1.93960E-03 501310 + 601 501311 Sn-131m 4.32290E-03 4.40310E-03 501311 + 602 501320 Sn-132 3.31710E-03 3.34220E-03 501320 + 603 501330 Sn-133 4.55140E-04 4.55600E-04 501330 + 604 501340 Sn-134 8.81510E-05 8.81530E-05 501340 + 605 501350 Sn-135 5.91440E-06 5.91440E-06 501350 + 606 501360 Sn-136 9.06180E-08 9.06180E-08 501360 + 607 501370 Sn-137 2.33290E-09 2.33290E-09 501370 + 608 511190 Sb-119 8.59040E-13 1.13210E-12 511190 + 609 511200 Sb-120 1.46000E-11 1.46000E-11 511200 + 610 511201 Sb-120m 2.07160E-11 2.07160E-11 511201 + 611 511210 Sb-121 1.77320E-09 3.61820E-05 51121.82c + 612 511220 Sb-122 2.70320E-08 5.76750E-08 511220 + 613 511221 Sb-122m 3.06430E-08 3.06430E-08 511221 + 614 511230 Sb-123 1.11100E-06 7.15980E-05 51123.82c + 615 511240 Sb-124 8.97820E-07 2.10910E-06 51124.82c + 616 511241 Sb-124m 6.86500E-07 1.61500E-06 511241 + 617 511242 Sb-124m 9.28480E-07 9.28480E-07 511242 + 618 511250 Sb-125 1.27850E-05 4.95760E-04 51125.82c + 619 511260 Sb-126 2.10100E-05 2.60290E-05 51126.82c + 620 511261 Sb-126m 1.55340E-05 3.58500E-05 511261 + 621 511262 Sb-126m 2.03160E-05 2.03160E-05 511262 + 622 511270 Sb-127 1.58700E-04 2.76540E-03 511270 + 623 511280 Sb-128 2.07950E-04 5.75730E-03 511280 + 624 511281 Sb-128m 3.54830E-04 3.54830E-04 511281 + 625 511290 Sb-129 2.08920E-03 8.09080E-03 511290 + 626 511291 Sb-129m 1.27670E-03 3.58650E-03 511291 + 627 511300 Sb-130 4.31040E-03 1.09140E-02 511300 + 628 511301 Sb-130m 4.31040E-03 7.68220E-03 511301 + 629 511310 Sb-131 2.22180E-02 2.85610E-02 511310 + 630 511320 Sb-132 1.39730E-02 1.73150E-02 511320 + 631 511321 Sb-132m 1.02980E-02 1.02980E-02 511321 + 632 511330 Sb-133 2.36110E-02 2.40820E-02 511330 + 633 511340 Sb-134 2.25150E-03 2.32530E-03 511340 + 634 511341 Sb-134m 5.27370E-03 5.27430E-03 511341 + 635 511350 Sb-135 2.46470E-03 2.46940E-03 511350 + 636 511360 Sb-136 4.41000E-04 4.41060E-04 511360 + 637 511370 Sb-137 6.36670E-05 6.36680E-05 511370 + 638 511380 Sb-138 3.41130E-07 3.41130E-07 511380 + 639 511390 Sb-139 8.05280E-09 8.05280E-09 511390 + 640 521220 Te-122 1.79320E-11 5.61930E-08 52122.82c + 641 521260 Te-126 1.35870E-06 5.82190E-05 52126.82c + 642 521270 Te-127 6.54920E-07 2.75660E-03 521270 + 643 521271 Te-127m 1.58110E-06 4.57300E-04 52527.82c + 644 521280 Te-128 1.56850E-05 6.11520E-03 52128.82c + 645 521290 Te-129 2.95100E-05 9.61540E-03 521290 + 646 521291 Te-129m 7.12400E-05 4.39110E-03 52529.82c + 647 521300 Te-130 1.05530E-03 1.96510E-02 52130.82c + 648 521310 Te-131 1.15270E-03 2.84910E-02 521310 + 649 521311 Te-131m 2.78260E-03 5.06930E-03 521311 + 650 521320 Te-132 1.72740E-02 4.48870E-02 52132.82c + 651 521330 Te-133 9.67300E-03 3.44090E-02 521330 + 652 521331 Te-133m 2.33520E-02 2.75180E-02 521331 + 653 521340 Te-134 5.05590E-02 5.85430E-02 521340 + 654 521350 Te-135 2.12220E-02 2.33760E-02 521350 + 655 521360 Te-136 1.19400E-02 1.23390E-02 521360 + 656 521370 Te-137 2.86090E-03 2.89340E-03 521370 + 657 521380 Te-138 6.18910E-04 6.19250E-04 521380 + 658 521390 Te-139 2.95980E-05 2.96060E-05 521390 + 659 521400 Te-140 1.87580E-05 1.87580E-05 521400 + 660 521410 Te-141 5.86470E-08 5.86470E-08 521410 + 661 521420 Te-142 1.71880E-09 1.71880E-09 521420 + 662 531280 I-128 1.04540E-06 1.04540E-06 531280 + 663 531290 I-129 2.02110E-08 1.12400E-02 53129.82c + 664 531300 I-130 3.51410E-06 4.77440E-06 53130.82c + 665 531301 I-130m 1.50030E-06 1.50030E-06 531301 + 666 531310 I-131 7.52390E-05 3.25710E-02 53131.82c + 667 531320 I-132 3.09650E-04 4.53930E-02 531320 + 668 531321 I-132m 2.28220E-04 2.28220E-04 531321 + 669 531330 I-133 2.55560E-03 6.12290E-02 531330 + 670 531331 I-133m 1.56170E-03 1.56170E-03 531331 + 671 531340 I-134 9.02060E-03 7.40590E-02 531340 + 672 531341 I-134m 6.64840E-03 6.64840E-03 531341 + 673 531350 I-135 5.33290E-02 7.67050E-02 53135.82c + 674 531360 I-136 1.38930E-02 2.62750E-02 531360 + 675 531361 I-136m 3.25410E-02 3.25840E-02 531361 + 676 531370 I-137 4.00810E-02 4.29270E-02 531370 + 677 531380 I-138 1.44800E-02 1.50600E-02 531380 + 678 531390 I-139 9.72000E-03 9.74960E-03 531390 + 679 531400 I-140 2.24320E-03 2.26200E-03 531400 + 680 531410 I-141 6.08330E-04 6.08390E-04 531410 + 681 531420 I-142 8.41680E-05 8.41700E-05 531420 + 682 531430 I-143 1.38960E-05 1.38960E-05 531430 + 683 531440 I-144 9.84350E-07 9.84350E-07 531440 + 684 541310 Xe-131 2.25310E-09 3.25710E-02 54131.82c + 685 541311 Xe-131m 5.43930E-09 3.53790E-04 541311 + 686 541320 Xe-132 1.44060E-06 4.54280E-02 54132.82c + 687 541321 Xe-132m 1.63300E-06 1.63300E-06 541321 + 688 541330 Xe-133 1.34650E-05 6.12750E-02 54133.82c + 689 541331 Xe-133m 3.25050E-05 1.77530E-03 541331 + 690 541340 Xe-134 1.28720E-04 7.46420E-02 54134.82c + 691 541341 Xe-134m 3.01500E-04 4.54410E-04 541341 + 692 541350 Xe-135 8.16490E-04 7.94040E-02 54135.82c + 693 541351 Xe-135m 1.97110E-03 1.46340E-02 541351 + 694 541360 Xe-136 1.77180E-02 7.93680E-02 54136.82c + 695 541370 Xe-137 2.93610E-02 7.02960E-02 541370 + 696 541380 Xe-138 3.72840E-02 5.25010E-02 541380 + 697 541390 Xe-139 2.32450E-02 3.22500E-02 541390 + 698 541400 Xe-140 1.90040E-02 2.11830E-02 541400 + 699 541410 Xe-141 7.08040E-03 7.58210E-03 541410 + 700 541420 Xe-142 3.27080E-03 3.33950E-03 541420 + 701 541430 Xe-143 5.42840E-04 5.51570E-04 541430 + 702 541440 Xe-144 9.92410E-05 9.98320E-05 541440 + 703 541450 Xe-145 6.72880E-06 6.72880E-06 541450 + 704 541460 Xe-146 4.03900E-08 4.03900E-08 541460 + 705 541470 Xe-147 8.09810E-10 8.09810E-10 541470 + 706 551330 Cs-133 1.81030E-09 6.12750E-02 55133.82c + 707 551340 Cs-134 5.91010E-07 1.02660E-06 55134.82c + 708 551341 Cs-134m 4.35590E-07 4.35590E-07 551341 + 709 551350 Cs-135 6.12050E-06 7.95020E-02 55135.82c + 710 551351 Cs-135m 3.74020E-06 3.74020E-06 551351 + 711 551360 Cs-136 1.64230E-04 2.12360E-04 55136.82c + 712 551361 Cs-136m 9.62470E-05 9.62470E-05 551361 + 713 551370 Cs-137 2.87270E-03 7.31680E-02 55137.82c + 714 551380 Cs-138 3.59270E-03 6.02240E-02 551380 + 715 551381 Cs-138m 5.09800E-03 5.09800E-03 551381 + 716 551390 Cs-139 2.12120E-02 5.34620E-02 551390 + 717 551400 Cs-140 2.53180E-02 4.65050E-02 551400 + 718 551410 Cs-141 3.86470E-02 4.62380E-02 551410 + 719 551420 Cs-142 2.60600E-02 2.93930E-02 551420 + 720 551430 Cs-143 1.92440E-02 1.97930E-02 551430 + 721 551440 Cs-144 3.46930E-03 5.30100E-03 551440 + 722 551441 Cs-144m 3.46930E-03 3.46950E-03 551441 + 723 551450 Cs-145 2.59120E-03 2.59760E-03 551450 + 724 551460 Cs-146 4.53570E-04 4.53610E-04 551460 + 725 551470 Cs-147 1.03760E-04 1.03760E-04 551470 + 726 551480 Cs-148 1.37370E-05 1.37370E-05 551480 + 727 551490 Cs-149 2.72250E-09 2.72250E-09 551490 + 728 561360 Ba-136 5.75150E-09 2.60500E-04 56136.82c + 729 561361 Ba-136m 1.34710E-08 1.34710E-08 561361 + 730 561370 Ba-137 3.91460E-06 7.31820E-02 56137.82c + 731 561371 Ba-137m 9.45040E-06 6.90800E-02 561371 + 732 561380 Ba-138 1.55590E-04 6.13480E-02 56138.82c + 733 561390 Ba-139 7.38460E-04 5.42000E-02 561390 + 734 561400 Ba-140 3.19140E-03 4.96960E-02 56140.82c + 735 561410 Ba-141 6.41200E-03 5.26500E-02 561410 + 736 561420 Ba-142 1.71030E-02 4.68210E-02 561420 + 737 561430 Ba-143 2.03770E-02 4.00150E-02 561430 + 738 561440 Ba-144 2.13770E-02 2.86150E-02 561440 + 739 561450 Ba-145 1.04060E-02 1.26970E-02 561450 + 740 561460 Ba-146 6.36000E-03 6.77880E-03 561460 + 741 561470 Ba-147 1.76960E-03 1.84720E-03 561470 + 742 561480 Ba-148 5.22830E-04 5.33120E-04 561480 + 743 561490 Ba-149 6.56720E-05 6.56750E-05 561490 + 744 561500 Ba-150 9.85610E-06 9.85610E-06 561500 + 745 561510 Ba-151 1.26280E-08 1.26280E-08 561510 + 746 561520 Ba-152 2.27660E-10 2.27660E-10 561520 + 747 571380 La-138 1.52290E-09 1.52290E-09 57138.82c + 748 571390 La-139 7.89780E-06 5.42080E-02 57139.82c + 749 571400 La-140 3.36030E-05 4.97300E-02 57140.82c + 750 571410 La-141 3.33580E-04 5.29830E-02 571410 + 751 571420 La-142 1.02690E-03 4.78480E-02 571420 + 752 571430 La-143 4.70380E-03 4.47190E-02 571430 + 753 571440 La-144 1.01560E-02 3.87710E-02 571440 + 754 571450 La-145 1.91050E-02 3.18020E-02 571450 + 755 571460 La-146 6.19410E-03 1.29730E-02 571460 + 756 571461 La-146m 1.11420E-02 1.11420E-02 571461 + 757 571470 La-147 1.83060E-02 2.01550E-02 571470 + 758 571480 La-148 8.56630E-03 9.09760E-03 571480 + 759 571490 La-149 4.59290E-03 4.65830E-03 571490 + 760 571500 La-150 1.07610E-03 1.08600E-03 571500 + 761 571510 La-151 2.43970E-04 2.43980E-04 571510 + 762 571520 La-152 2.37960E-05 2.37960E-05 571520 + 763 571530 La-153 9.92260E-07 9.92260E-07 571530 + 764 571540 La-154 4.89740E-10 4.89740E-10 571540 + 765 581410 Ce-141 1.10950E-08 5.29830E-02 58141.82c + 766 581420 Ce-142 4.95910E-06 4.78520E-02 58142.82c + 767 581430 Ce-143 3.37820E-05 4.47530E-02 58143.82c + 768 581440 Ce-144 3.20820E-04 3.90910E-02 58144.82c + 769 581450 Ce-145 1.03070E-03 3.28320E-02 581450 + 770 581460 Ce-146 3.40370E-03 2.75190E-02 581460 + 771 581470 Ce-147 5.73580E-03 2.58910E-02 581470 + 772 581480 Ce-148 8.89540E-03 1.80580E-02 581480 + 773 581490 Ce-149 6.81650E-03 1.14390E-02 581490 + 774 581500 Ce-150 5.27120E-03 6.32780E-03 581500 + 775 581510 Ce-151 1.75000E-03 1.99540E-03 581510 + 776 581520 Ce-152 7.52070E-04 7.74430E-04 581520 + 777 581530 Ce-153 9.41110E-05 9.51030E-05 581530 + 778 581540 Ce-154 8.94280E-06 8.94330E-06 581540 + 779 581550 Ce-155 1.04150E-07 1.04150E-07 581550 + 780 581560 Ce-156 2.42530E-09 2.42530E-09 581560 + 781 581570 Ce-157 2.66210E-11 2.66210E-11 581570 + 782 591430 Pr-143 1.34830E-09 4.47530E-02 59143.82c + 783 591440 Pr-144 1.99250E-07 3.90930E-02 591440 + 784 591441 Pr-144m 1.76970E-06 5.41210E-04 591441 + 785 591450 Pr-145 1.82760E-05 3.28500E-02 591450 + 786 591460 Pr-146 1.03200E-04 2.76220E-02 591460 + 787 591470 Pr-147 5.20990E-04 2.64120E-02 591470 + 788 591480 Pr-148 2.76340E-04 1.83350E-02 591480 + 789 591481 Pr-148m 1.16220E-03 1.16220E-03 591481 + 790 591490 Pr-149 3.80540E-03 1.52440E-02 591490 + 791 591500 Pr-150 5.06040E-03 1.13880E-02 591500 + 792 591510 Pr-151 6.28860E-03 8.28400E-03 591510 + 793 591520 Pr-152 3.97830E-03 4.75330E-03 591520 + 794 591530 Pr-153 2.47460E-03 2.56920E-03 591530 + 795 591540 Pr-154 7.80900E-04 7.89790E-04 591540 + 796 591550 Pr-155 2.79250E-04 2.79350E-04 591550 + 797 591560 Pr-156 3.42930E-05 3.42950E-05 591560 + 798 591570 Pr-157 5.71480E-06 5.71480E-06 591570 + 799 591580 Pr-158 4.31060E-09 4.31060E-09 591580 + 800 591590 Pr-159 7.99070E-11 7.99070E-11 591590 + 801 601460 Nd-146 5.91060E-09 2.76220E-02 60146.82c + 802 601470 Nd-147 1.98050E-06 2.64140E-02 60147.82c + 803 601480 Nd-148 1.17820E-05 1.95090E-02 60148.82c + 804 601490 Nd-149 8.65670E-05 1.53310E-02 601490 + 805 601500 Nd-150 3.63680E-04 1.17520E-02 60150.82c + 806 601510 Nd-151 8.15360E-04 9.09940E-03 601510 + 807 601520 Nd-152 1.42980E-03 6.18310E-03 601520 + 808 601530 Nd-153 1.50010E-03 4.06930E-03 601530 + 809 601540 Nd-154 1.39100E-03 2.18080E-03 601540 + 810 601550 Nd-155 6.66230E-04 9.46520E-04 601550 + 811 601560 Nd-156 3.41860E-04 3.75590E-04 601560 + 812 601570 Nd-157 9.06250E-05 9.59750E-05 601570 + 813 601580 Nd-158 1.50480E-05 1.50520E-05 601580 + 814 601590 Nd-159 1.89130E-06 1.89140E-06 601590 + 815 601600 Nd-160 2.77730E-06 2.77730E-06 601600 + 816 601610 Nd-161 2.21860E-10 2.21860E-10 601610 + 817 611480 Pm-148 1.45190E-10 1.62200E-10 61148.82c + 818 611481 Pm-148m 3.40080E-10 3.40080E-10 61548.82c + 819 611490 Pm-149 1.96290E-06 1.53330E-02 61149.82c + 820 611500 Pm-150 5.91610E-06 5.91610E-06 611500 + 821 611510 Pm-151 2.76960E-05 9.12710E-03 61151.82c + 822 611520 Pm-152 2.88630E-05 6.21200E-03 611520 + 823 611521 Pm-152m 5.76360E-05 5.76360E-05 611521 + 824 611522 Pm-152m 6.37510E-05 6.37510E-05 611522 + 825 611530 Pm-153 4.00400E-04 4.46970E-03 611530 + 826 611540 Pm-154 3.10120E-04 2.49090E-03 611540 + 827 611541 Pm-154m 3.10120E-04 3.10120E-04 611541 + 828 611550 Pm-155 1.03920E-03 1.98570E-03 611550 + 829 611560 Pm-156 8.04860E-04 1.18040E-03 611560 + 830 611570 Pm-157 6.08190E-04 7.04170E-04 611570 + 831 611580 Pm-158 2.66390E-04 2.81450E-04 611580 + 832 611590 Pm-159 1.17570E-04 1.19480E-04 611590 + 833 611600 Pm-160 2.41480E-05 2.68990E-05 611600 + 834 611610 Pm-161 4.67650E-06 4.67670E-06 611610 + 835 611620 Pm-162 1.62870E-08 1.62870E-08 611620 + 836 611630 Pm-163 5.94020E-10 5.94020E-10 611630 + 837 621510 Sm-151 1.37250E-09 9.12710E-03 62151.82c + 838 621520 Sm-152 1.98380E-06 6.33540E-03 62152.82c + 839 621530 Sm-153 1.74300E-06 4.47560E-03 62153.82c + 840 621531 Sm-153m 4.20790E-06 4.20790E-06 621531 + 841 621540 Sm-154 2.28150E-05 2.82380E-03 62154.82c + 842 621550 Sm-155 5.61940E-05 2.04190E-03 621550 + 843 621560 Sm-156 1.50970E-04 1.33140E-03 621560 + 844 621570 Sm-157 1.61750E-04 8.65920E-04 621570 + 845 621580 Sm-158 1.89160E-04 4.70630E-04 621580 + 846 621590 Sm-159 1.36910E-04 2.56440E-04 621590 + 847 621600 Sm-160 7.33380E-05 1.00170E-04 621600 + 848 621610 Sm-161 3.18550E-05 3.65320E-05 621610 + 849 621620 Sm-162 1.12460E-05 1.12620E-05 621620 + 850 621630 Sm-163 3.74160E-06 3.74220E-06 621630 + 851 621640 Sm-164 2.54740E-08 2.54740E-08 621640 + 852 621650 Sm-165 8.65520E-10 8.65520E-10 621650 + 853 631530 Eu-153 1.32340E-10 4.47560E-03 63153.82c + 854 631540 Eu-154 1.32510E-09 2.51870E-09 63154.82c + 855 631541 Eu-154m 1.19360E-09 1.19360E-09 631541 + 856 631550 Eu-155 2.97050E-06 2.04490E-03 63155.82c + 857 631560 Eu-156 3.91760E-06 1.33530E-03 63156.82c + 858 631570 Eu-157 2.27650E-05 8.88680E-04 63157.82c + 859 631580 Eu-158 5.40620E-05 5.24690E-04 631580 + 860 631590 Eu-159 8.24130E-05 3.38860E-04 631590 + 861 631600 Eu-160 9.83780E-05 1.98540E-04 631600 + 862 631610 Eu-161 8.29930E-05 1.19530E-04 631610 + 863 631620 Eu-162 4.77500E-05 5.90120E-05 631620 + 864 631630 Eu-163 2.52730E-05 2.90150E-05 631630 + 865 631640 Eu-164 5.83840E-06 5.86390E-06 631640 + 866 631650 Eu-165 9.43740E-07 9.44610E-07 631650 + 867 631660 Eu-166 1.58980E-08 1.58980E-08 631660 + 868 631670 Eu-167 1.20170E-09 1.20170E-09 631670 + 869 641560 Gd-156 2.37770E-10 1.33530E-03 64156.82c + 870 641570 Gd-157 5.88310E-09 8.88690E-04 64157.82c + 871 641580 Gd-158 9.39510E-07 5.25630E-04 64158.82c + 872 641590 Gd-159 9.45310E-07 3.39800E-04 641590 + 873 641600 Gd-160 4.62330E-06 2.03170E-04 64160.82c + 874 641610 Gd-161 8.40090E-06 1.27930E-04 641610 + 875 641620 Gd-162 1.49540E-05 7.39660E-05 641620 + 876 641630 Gd-163 2.24080E-05 5.14230E-05 641630 + 877 641640 Gd-164 7.78030E-06 1.36440E-05 641640 + 878 641650 Gd-165 2.83140E-06 3.77600E-06 641650 + 879 641660 Gd-166 1.97730E-06 1.99320E-06 641660 + 880 641670 Gd-167 2.95650E-07 2.96850E-07 641670 + 881 641680 Gd-168 3.75680E-08 3.75680E-08 641680 + 882 641690 Gd-169 1.57520E-09 1.57520E-09 641690 + 883 651580 Tb-158 1.16700E-11 1.29760E-11 651580 + 884 651581 Tb-158m 1.31400E-12 1.31400E-12 651581 + 885 651590 Tb-159 3.29620E-10 3.39800E-04 65159.82c + 886 651600 Tb-160 5.87800E-09 5.87800E-09 65160.82c + 887 651610 Tb-161 9.34270E-07 1.28860E-04 651610 + 888 651620 Tb-162 4.79600E-07 7.44460E-05 651620 + 889 651630 Tb-163 3.73710E-06 5.51600E-05 651630 + 890 651640 Tb-164 5.83170E-06 1.94760E-05 651640 + 891 651650 Tb-165 1.03760E-05 1.41520E-05 651650 + 892 651660 Tb-166 1.97690E-06 3.97010E-06 651660 + 893 651670 Tb-167 2.57510E-06 2.87200E-06 651670 + 894 651680 Tb-168 1.32280E-06 1.36040E-06 651680 + 895 651690 Tb-169 1.81570E-07 1.83140E-07 651690 + 896 651700 Tb-170 1.88890E-08 1.88890E-08 651700 + 897 651710 Tb-171 1.70240E-09 1.70240E-09 651710 + 898 661610 Dy-161 1.55690E-11 1.28860E-04 66161.82c + 899 661620 Dy-162 5.29540E-10 7.44460E-05 66162.82c + 900 661630 Dy-163 8.91300E-09 5.51690E-05 66163.82c + 901 661640 Dy-164 5.62500E-08 1.95320E-05 66164.82c + 902 661650 Dy-165 2.57280E-07 1.44480E-05 661650 + 903 661651 Dy-165m 3.93310E-08 3.93310E-08 661651 + 904 661660 Dy-166 9.88380E-07 4.95850E-06 661660 + 905 661670 Dy-167 1.32600E-06 4.19800E-06 661670 + 906 661680 Dy-168 1.32260E-06 2.68300E-06 661680 + 907 661690 Dy-169 9.01460E-07 1.08460E-06 661690 + 908 661700 Dy-170 4.43390E-07 4.62280E-07 661700 + 909 661710 Dy-171 1.03350E-07 1.05050E-07 661710 + 910 661720 Dy-172 2.06690E-08 2.06690E-08 661720 + 911 661730 Dy-173 1.64100E-09 1.64100E-09 661730 + 912 671640 Ho-164 4.18610E-12 1.39910E-11 671640 + 913 671641 Ho-164m 9.80490E-12 9.80490E-12 671641 + 914 671650 Ho-165 4.42330E-10 1.44490E-05 67165.82c + 915 671660 Ho-166 7.88540E-10 4.95930E-06 671660 + 916 671661 Ho-166m 1.84700E-09 1.84700E-09 671661 + 917 671670 Ho-167 3.07370E-08 4.22870E-06 671670 + 918 671680 Ho-168 4.39860E-08 2.78910E-06 671680 + 919 671681 Ho-168m 6.24140E-08 6.24140E-08 671681 + 920 671690 Ho-169 2.45360E-07 1.33000E-06 671690 + 921 671700 Ho-170 1.86600E-07 1.86600E-07 671700 + 922 671701 Ho-170m 7.96650E-08 5.41940E-07 671701 + 923 671710 Ho-171 2.69180E-07 3.74230E-07 671710 + 924 671720 Ho-172 1.23660E-07 1.44330E-07 671720 + 925 671730 Ho-173 4.82730E-08 4.99140E-08 671730 + 926 671740 Ho-174 7.99100E-09 7.99100E-09 671740 + 927 671750 Ho-175 1.30810E-09 1.30810E-09 671750 + 928 681670 Er-167 2.00990E-11 4.22870E-06 68167.82c + 929 681671 Er-167m 3.07260E-12 5.05300E-07 681671 + 930 681680 Er-168 4.66310E-10 2.78980E-06 68168.82c + 931 681690 Er-169 3.02190E-09 1.33300E-06 681690 + 932 681700 Er-170 1.71250E-08 7.45660E-07 68170.82c + 933 681710 Er-171 4.21770E-08 4.16410E-07 681710 + 934 681720 Er-172 8.68420E-08 2.31170E-07 681720 + 935 681730 Er-173 7.39690E-08 1.23880E-07 681730 + 936 681740 Er-174 5.40410E-08 6.20320E-08 681740 + 937 681750 Er-175 2.10670E-08 2.23750E-08 681750 + 938 681760 Er-176 7.06640E-09 7.06640E-09 681760 + 939 681770 Er-177 9.54500E-10 9.54500E-10 681770 + 940 691690 Tm-169 1.01530E-12 1.33300E-06 691690 + 941 691700 Tm-170 1.74310E-11 1.74310E-11 691700 + 942 691710 Tm-171 2.45180E-10 4.16650E-07 691710 + 943 691720 Tm-172 1.37880E-09 2.32550E-07 691720 + 944 691730 Tm-173 5.90810E-09 1.29790E-07 691730 + 945 691740 Tm-174 1.01190E-08 7.21510E-08 691740 + 946 691750 Tm-175 1.72580E-08 3.96330E-08 691750 + 947 691760 Tm-176 1.26680E-08 1.97340E-08 691760 + 948 691770 Tm-177 7.77010E-09 8.72460E-09 691770 + 949 691780 Tm-178 2.15330E-09 2.15330E-09 691780 + 950 691790 Tm-179 5.69760E-10 5.69760E-10 691790 + 951 701720 Yb-172 1.39950E-12 2.32550E-07 701720 + 952 701730 Yb-173 1.76890E-11 1.29810E-07 701730 + 953 701740 Yb-174 1.68920E-10 7.23200E-08 701740 + 954 701750 Yb-175 6.60140E-10 4.03940E-08 701750 + 955 701751 Yb-175m 1.00920E-10 3.06180E-08 701751 + 956 701760 Yb-176 9.65390E-10 2.12760E-08 701760 + 957 701761 Yb-176m 1.73650E-09 1.16040E-08 701761 + 958 701770 Yb-177 3.05110E-09 1.24810E-08 701770 + 959 701771 Yb-177m 7.05490E-10 9.43010E-09 701771 + 960 701780 Yb-178 4.50070E-09 6.65400E-09 701780 + 961 701790 Yb-179 2.64970E-09 3.21950E-09 701790 + 962 701800 Yb-180 1.32610E-09 1.32610E-09 701800 + 963 701810 Yb-181 3.18080E-10 3.18080E-10 701810 + 964 711750 Lu-175 1.04750E-12 4.03950E-08 71175.82c + 965 711760 Lu-176 6.90200E-12 1.16730E-09 71176.82c + 966 711761 Lu-176m 3.83700E-12 3.83700E-12 711761 + 967 711770 Lu-177 5.76460E-11 1.25440E-08 711770 + 968 711771 Lu-177m 2.25360E-11 2.29000E-11 711771 + 969 711780 Lu-178 1.15660E-10 6.76970E-09 711780 + 970 711781 Lu-178m 1.31110E-10 1.31110E-10 711781 + 971 711790 Lu-179 5.86430E-10 3.89550E-09 711790 + 972 711791 Lu-179m 8.96480E-11 3.30910E-09 711791 + 973 711800 Lu-180 2.15380E-10 1.14480E-09 711800 + 974 711801 Lu-180m 2.15380E-10 1.54150E-09 711801 + 975 711802 Lu-180m 3.17420E-10 3.17420E-10 711802 + 976 711810 Lu-181 7.77390E-10 1.09550E-09 711810 + 977 711820 Lu-182 3.66780E-10 3.66780E-10 711820 + 978 711830 Lu-183 1.46350E-10 1.46350E-10 711830 + 979 711840 Lu-184 2.48690E-11 2.48690E-11 711840 + 980 721790 Hf-179 4.64600E-12 3.90330E-09 72179.82c + 981 721791 Hf-179m 1.45030E-12 1.45030E-12 721791 + 982 721792 Hf-179m 1.62640E-12 1.62640E-12 721792 + 983 721800 Hf-180 1.60100E-11 2.11850E-09 72180.82c + 984 721801 Hf-180m 2.87980E-11 1.87510E-10 721801 + 985 721810 Hf-181 1.13950E-10 1.20940E-09 721810 + 986 721820 Hf-182 8.63950E-11 5.18440E-10 721820 + 987 721821 Hf-182m 1.55400E-10 1.55400E-10 721821 + 988 721830 Hf-183 2.10630E-10 3.56980E-10 721830 + 989 721840 Hf-184 5.62930E-11 6.87270E-11 721840 + 990 721841 Hf-184m 1.01260E-10 1.13690E-10 721841 + 991 721850 Hf-185 6.29480E-11 6.29480E-11 721850 + 992 721860 Hf-186 2.16260E-11 2.16260E-11 721860 + 993 721870 Hf-187 3.01280E-12 3.01280E-12 721870 + 994 731820 Ta-182 1.27450E-12 9.37020E-11 73182.82c + 995 731821 Ta-182m 1.30090E-12 9.24270E-11 731821 + 996 731822 Ta-182m 9.91650E-13 9.11260E-11 731822 + 997 731830 Ta-183 1.57020E-11 3.72680E-10 731830 + 998 731840 Ta-184 2.76520E-11 2.10070E-10 731840 + 999 731850 Ta-185 3.26330E-11 1.11390E-10 731850 + 1000 731851 Ta-185m 1.58060E-11 1.58060E-11 731851 + 1001 731860 Ta-186 3.63800E-11 5.80060E-11 731860 + 1002 731870 Ta-187 2.29280E-11 2.59410E-11 731870 + 1003 731880 Ta-188 6.54220E-12 6.54220E-12 731880 + 1004 731890 Ta-189 1.77150E-12 1.77150E-12 731890 + 1005 741850 W-185 5.82610E-13 1.13380E-10 741850 + 1006 741851 W-185m 1.40650E-12 1.40650E-12 741851 + 1007 741860 W-186 5.48810E-12 6.52640E-11 74186.82c + 1008 741861 W-186m 1.77030E-12 1.77030E-12 741861 + 1009 741870 W-187 1.04050E-11 3.63460E-11 741870 + 1010 741880 W-188 1.28430E-11 1.93850E-11 741880 + 1011 741890 W-189 7.71840E-12 9.48990E-12 741890 + 1012 741900 W-190 1.84800E-12 3.94280E-12 741900 + 1013 741901 W-190m 2.09480E-12 2.09480E-12 741901 + 1014 751890 Re-189 1.84570E-12 1.13360E-11 751890 + 1015 751900 Re-190 7.46540E-13 5.30170E-12 751900 + 1016 751901 Re-190m 1.34290E-12 1.34290E-12 751901 + 1017 751910 Re-191 2.23570E-12 2.23570E-12 751910 + 1018 751920 Re-192 1.08430E-12 1.08430E-12 751920 + + Neutron-induced fission: + + Interpolation region : 2 / 2 + Interpolation energy : 4.00000E-01 MeV + Number of products : 994 / 1091 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 2.87890E-05 2.87890E-05 1001.82c + 2 10020 H-2 8.79830E-06 8.79830E-06 1002.82c + 3 10030 H-3 1.57000E-04 1.57000E-04 1003.82c + 4 20040 He-4 1.82000E-03 1.82000E-03 2004.82c + 5 200500 Ca-50 4.85930E-12 4.85930E-12 200500 + 6 200510 Ca-51 5.85750E-12 5.85750E-12 200510 + 7 200520 Ca-52 6.01030E-12 6.01030E-12 200520 + 8 200530 Ca-53 2.46120E-12 2.46120E-12 200530 + 9 210510 Sc-51 4.89060E-12 1.08680E-11 210510 + 10 210520 Sc-52 1.11490E-11 1.77780E-11 210520 + 11 210530 Sc-53 2.09610E-11 2.26840E-11 210530 + 12 210540 Sc-54 1.76770E-11 1.76770E-11 210540 + 13 210550 Sc-55 1.41120E-11 1.41120E-11 210550 + 14 210560 Sc-56 4.49940E-12 4.49940E-12 210560 + 15 210570 Sc-57 1.22560E-12 1.22560E-12 210570 + 16 220520 Ti-52 2.43720E-12 2.02150E-11 220520 + 17 220530 Ti-53 1.05250E-11 3.32090E-11 220530 + 18 220540 Ti-54 3.86750E-11 5.63520E-11 220540 + 19 220550 Ti-55 6.98890E-11 8.40010E-11 220550 + 20 220560 Ti-56 1.06350E-10 1.11250E-10 220560 + 21 220570 Ti-57 7.62530E-11 7.70740E-11 220570 + 22 220580 Ti-58 4.63090E-11 4.63090E-11 220580 + 23 220590 Ti-59 1.11100E-11 1.11100E-11 220590 + 24 220600 Ti-60 2.04460E-12 2.04460E-12 220600 + 25 230540 V-54 2.23590E-12 5.85880E-11 230540 + 26 230550 V-55 1.89080E-11 1.02910E-10 230550 + 27 230560 V-56 6.44240E-11 1.75910E-10 230560 + 28 230570 V-57 2.02060E-10 2.78900E-10 230570 + 29 230580 V-58 2.86550E-10 3.32860E-10 230580 + 30 230590 V-59 3.42210E-10 3.53320E-10 230590 + 31 230600 V-60 1.72160E-10 1.74200E-10 230600 + 32 230610 V-61 8.42550E-11 8.42550E-11 230610 + 33 230620 V-62 1.64350E-11 1.64350E-11 230620 + 34 230630 V-63 2.34070E-12 2.34070E-12 230630 + 35 240560 Cr-56 4.13480E-12 1.81160E-10 240560 + 36 240570 Cr-57 3.20820E-11 5.76160E-10 240570 + 37 240580 Cr-58 2.05500E-10 2.72070E-10 240580 + 38 240590 Cr-59 5.43220E-10 8.96540E-10 240590 + 39 240600 Cr-60 1.21860E-09 1.39790E-09 240600 + 40 240610 Cr-61 1.44800E-09 1.52720E-09 240610 + 41 240620 Cr-62 1.46510E-09 1.48230E-09 240620 + 42 240630 Cr-63 5.89550E-10 5.91070E-10 240630 + 43 240640 Cr-64 1.93120E-10 1.93120E-10 240640 + 44 240650 Cr-65 2.82390E-11 2.82390E-11 240650 + 45 240660 Cr-66 3.05600E-12 3.05600E-12 240660 + 46 250580 Mn-58 3.05090E-12 2.75120E-10 250580 + 47 250590 Mn-59 4.49260E-11 9.41470E-10 250590 + 48 250600 Mn-60 2.14200E-11 1.44430E-09 250600 + 49 250601 Mn-60m 2.17910E-10 2.17910E-10 250601 + 50 250610 Mn-61 1.25250E-09 2.77970E-09 250610 + 51 250620 Mn-62 2.43610E-09 3.17730E-09 250620 + 52 250621 Mn-62m 3.81500E-10 1.12270E-09 250621 + 53 250630 Mn-63 5.21710E-09 5.80820E-09 250630 + 54 250640 Mn-64 4.32760E-09 4.52070E-09 250640 + 55 250650 Mn-65 3.40880E-09 3.43700E-09 250650 + 56 250660 Mn-66 1.07160E-09 1.07470E-09 250660 + 57 250670 Mn-67 2.86210E-10 2.86210E-10 250670 + 58 250680 Mn-68 3.06770E-11 3.06770E-11 250680 + 59 250690 Mn-69 2.44110E-12 2.44110E-12 250690 + 60 260600 Fe-60 4.17050E-12 1.64140E-09 260600 + 61 260610 Fe-61 5.84650E-11 2.83820E-09 260610 + 62 260620 Fe-62 6.39570E-10 4.93950E-09 260620 + 63 260630 Fe-63 2.71490E-09 8.52310E-09 260630 + 64 260640 Fe-64 9.81000E-09 1.43310E-08 260640 + 65 260650 Fe-65 1.75200E-08 2.09570E-08 260650 + 66 260660 Fe-66 2.63560E-08 2.74310E-08 260660 + 67 260670 Fe-67 1.85740E-08 1.88600E-08 260670 + 68 260680 Fe-68 1.10810E-08 1.11120E-08 260680 + 69 260690 Fe-69 2.61940E-09 2.62130E-09 260690 + 70 260700 Fe-70 4.74320E-10 4.74320E-10 260700 + 71 260710 Fe-71 3.74300E-11 3.74300E-11 260710 + 72 260720 Fe-72 1.15510E-12 1.15510E-12 260720 + 73 270620 Co-62 7.34420E-13 4.94030E-09 270620 + 74 270621 Co-62m 2.00190E-12 2.00190E-12 270621 + 75 270630 Co-63 6.34060E-11 8.58650E-09 270630 + 76 270640 Co-64 5.89660E-10 1.49200E-08 270640 + 77 270650 Co-65 4.91650E-09 2.58740E-08 270650 + 78 270660 Co-66 1.65410E-08 4.39720E-08 270660 + 79 270670 Co-67 5.10280E-08 6.98880E-08 270670 + 80 270680 Co-68 4.07970E-08 6.16700E-08 270680 + 81 270681 Co-68m 3.04510E-08 4.17470E-08 270681 + 82 270690 Co-69 8.40580E-08 8.64960E-08 270690 + 83 270700 Co-70 2.08500E-08 2.08500E-08 270700 + 84 270701 Co-70m 2.08500E-08 2.13240E-08 270701 + 85 270710 Co-71 1.88240E-08 1.88610E-08 270710 + 86 270720 Co-72 1.77170E-09 1.77290E-09 270720 + 87 270730 Co-73 3.58710E-10 3.58710E-10 270730 + 88 270740 Co-74 2.36320E-11 2.36320E-11 270740 + 89 270750 Co-75 1.62220E-12 1.62220E-12 270750 + 90 280640 Ni-64 2.61840E-12 1.49230E-08 28064.82c + 91 280650 Ni-65 6.23770E-11 2.59360E-08 280650 + 92 280660 Ni-66 1.10520E-09 4.50770E-08 280660 + 93 280670 Ni-67 8.41280E-09 7.83010E-08 280670 + 94 280680 Ni-68 5.29530E-08 1.36360E-07 280680 + 95 280690 Ni-69 6.91300E-08 1.54760E-07 280690 + 96 280691 Ni-69m 6.91300E-08 6.91300E-08 280691 + 97 280700 Ni-70 3.06340E-07 3.48510E-07 280700 + 98 280710 Ni-71 6.71500E-07 6.90360E-07 280710 + 99 280720 Ni-72 5.98450E-07 6.00220E-07 280720 + 100 280730 Ni-73 9.44120E-08 9.47710E-08 280730 + 101 280740 Ni-74 3.64100E-08 3.64340E-08 280740 + 102 280750 Ni-75 7.92770E-09 7.92930E-09 280750 + 103 280760 Ni-76 1.07250E-09 1.07250E-09 280760 + 104 280770 Ni-77 4.89290E-11 4.89290E-11 280770 + 105 280780 Ni-78 1.11400E-12 1.11400E-12 280780 + 106 290660 Cu-66 1.17590E-12 4.50780E-08 290660 + 107 290670 Cu-67 5.16090E-11 7.83530E-08 290670 + 108 290680 Cu-68 2.41550E-10 1.37160E-07 290680 + 109 290681 Cu-68m 6.58430E-10 6.58430E-10 290681 + 110 290690 Cu-69 1.18880E-08 2.35780E-07 290690 + 111 290700 Cu-70 4.22460E-09 4.00190E-08 290700 + 112 290701 Cu-70m 5.39520E-08 7.15890E-08 290701 + 113 290702 Cu-70m 4.22460E-09 3.52740E-07 290702 + 114 290710 Cu-71 3.01660E-07 9.92020E-07 290710 + 115 290720 Cu-72 3.28490E-07 9.28710E-07 290720 + 116 290730 Cu-73 7.23400E-07 8.18170E-07 290730 + 117 290740 Cu-74 1.91000E-06 1.94660E-06 290740 + 118 290750 Cu-75 9.99240E-07 1.00700E-06 290750 + 119 290760 Cu-76 1.96680E-07 1.97220E-07 290760 + 120 290761 Cu-76m 1.96680E-07 1.97220E-07 290761 + 121 290770 Cu-77 1.07420E-07 1.07470E-07 290770 + 122 290780 Cu-78 6.23000E-09 6.23110E-09 290780 + 123 290790 Cu-79 1.00910E-09 1.00910E-09 290790 + 124 290800 Cu-80 2.83250E-11 2.83250E-11 290800 + 125 300690 Zn-69 6.44740E-12 2.35820E-07 300690 + 126 300691 Zn-69m 3.20220E-11 3.20220E-11 300691 + 127 300700 Zn-70 1.13460E-09 4.12050E-07 300700 + 128 300710 Zn-71 2.45670E-09 9.94480E-07 300710 + 129 300711 Zn-71m 1.22010E-08 1.22010E-08 300711 + 130 300720 Zn-72 7.74200E-08 1.00610E-06 300720 + 131 300730 Zn-73 4.10630E-08 1.10120E-06 300730 + 132 300731 Zn-73m 5.67950E-08 2.42000E-07 300731 + 133 300732 Zn-73m 3.70410E-07 3.70410E-07 300732 + 134 300740 Zn-74 9.54870E-07 2.93670E-06 300740 + 135 300750 Zn-75 7.87460E-06 8.85230E-06 300750 + 136 300760 Zn-76 1.00610E-05 1.04500E-05 300760 + 137 300770 Zn-77 7.24600E-06 7.83590E-06 300770 + 138 300771 Zn-77m 9.64770E-07 9.64770E-07 300771 + 139 300780 Zn-78 2.07840E-06 2.08520E-06 300780 + 140 300790 Zn-79 3.21330E-06 3.21370E-06 300790 + 141 300800 Zn-80 1.86290E-07 1.86320E-07 300800 + 142 300810 Zn-81 1.35870E-08 1.35870E-08 300810 + 143 300820 Zn-82 6.59950E-10 6.59950E-10 300820 + 144 300830 Zn-83 1.99220E-11 1.99220E-11 300830 + 145 310710 Ga-71 2.23710E-11 1.00670E-06 310710 + 146 310720 Ga-72 3.15000E-10 1.00650E-06 310720 + 147 310721 Ga-72m 3.09630E-11 3.35560E-08 310721 + 148 310730 Ga-73 7.23300E-07 2.00970E-06 310730 + 149 310740 Ga-74 6.23850E-08 2.31170E-06 310740 + 150 310741 Ga-74m 6.23850E-08 2.99910E-06 310741 + 151 310750 Ga-75 1.55100E-06 1.04030E-05 310750 + 152 310760 Ga-76 4.02170E-06 1.44710E-05 310760 + 153 310770 Ga-77 1.33320E-05 2.16500E-05 310770 + 154 310780 Ga-78 6.23550E-06 8.36250E-06 310780 + 155 310790 Ga-79 3.11080E-05 3.42800E-05 310790 + 156 310800 Ga-80 1.23670E-05 1.25540E-05 310800 + 157 310810 Ga-81 1.03420E-05 1.03550E-05 310810 + 158 310820 Ga-82 2.21130E-06 2.21200E-06 310820 + 159 310830 Ga-83 2.16180E-06 2.16180E-06 310830 + 160 310840 Ga-84 8.25150E-09 8.25150E-09 310840 + 161 310850 Ga-85 2.53940E-10 2.53940E-10 310850 + 162 320730 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431060 Tc-106 2.34180E-02 6.09240E-02 431060 + 399 431070 Tc-107 3.49960E-02 5.27770E-02 431070 + 400 431080 Tc-108 2.72820E-02 3.58070E-02 431080 + 401 431090 Tc-109 2.06450E-02 2.27890E-02 431090 + 402 431100 Tc-110 9.28010E-03 9.81540E-03 431100 + 403 431110 Tc-111 3.70800E-03 3.76470E-03 431110 + 404 431120 Tc-112 6.67440E-04 6.72220E-04 431120 + 405 431130 Tc-113 9.93010E-05 9.93010E-05 431130 + 406 431140 Tc-114 1.46810E-05 1.46810E-05 431140 + 407 431150 Tc-115 1.67670E-06 1.67670E-06 431150 + 408 441020 Ru-102 3.02190E-06 5.97670E-02 44102.82c + 409 441030 Ru-103 6.07040E-06 6.45880E-02 44103.82c + 410 441031 Ru-103m 1.69850E-05 1.69850E-05 441031 + 411 441040 Ru-104 2.35120E-04 6.95050E-02 44104.82c + 412 441050 Ru-105 1.08130E-03 6.63810E-02 44105.82c + 413 441060 Ru-106 4.29690E-03 6.52210E-02 44106.82c + 414 441070 Ru-107 8.80070E-03 6.15780E-02 441070 + 415 441080 Ru-108 1.83020E-02 5.41280E-02 441080 + 416 441090 Ru-109 2.00510E-02 4.28260E-02 441090 + 417 441100 Ru-110 2.07070E-02 3.05190E-02 441100 + 418 441110 Ru-111 1.17850E-02 1.55600E-02 441110 + 419 441120 Ru-112 6.21200E-03 6.88130E-03 441120 + 420 441130 Ru-113 8.16750E-04 1.31820E-03 441130 + 421 441131 Ru-113m 8.16750E-04 8.16750E-04 441131 + 422 441140 Ru-114 4.75550E-04 4.89510E-04 441140 + 423 441150 Ru-115 1.07830E-04 1.09270E-04 441150 + 424 441160 Ru-116 3.41190E-05 3.41190E-05 441160 + 425 441170 Ru-117 1.18480E-05 1.18480E-05 441170 + 426 441180 Ru-118 2.58980E-06 2.58980E-06 441180 + 427 441190 Ru-119 7.07860E-07 7.07860E-07 441190 + 428 451040 Rh-104 3.79480E-10 1.70000E-09 451040 + 429 451041 Rh-104m 1.32220E-09 1.32220E-09 451041 + 430 451050 Rh-105 6.18210E-06 6.63880E-02 45105.82c + 431 451051 Rh-105m 8.23110E-07 1.88450E-02 451051 + 432 451060 Rh-106 1.34940E-05 6.52350E-02 451060 + 433 451061 Rh-106m 3.67820E-05 3.67820E-05 451061 + 434 451070 Rh-107 3.01390E-04 6.18790E-02 451070 + 435 451080 Rh-108 2.07060E-04 5.43350E-02 451080 + 436 451081 Rh-108m 7.21460E-04 7.21460E-04 451081 + 437 451090 Rh-109 3.21720E-03 4.60430E-02 451090 + 438 451100 Rh-110 4.95760E-03 3.54760E-02 451100 + 439 451101 Rh-110m 1.16710E-04 1.16710E-04 451101 + 440 451110 Rh-111 8.20210E-03 2.37620E-02 451110 + 441 451120 Rh-112 3.34100E-03 1.02220E-02 451120 + 442 451121 Rh-112m 3.34100E-03 3.34100E-03 451121 + 443 451130 Rh-113 4.89930E-03 6.62590E-03 451130 + 444 451140 Rh-114 1.01930E-03 1.50910E-03 451140 + 445 451141 Rh-114m 1.01930E-03 1.01930E-03 451141 + 446 451150 Rh-115 8.02960E-04 9.12350E-04 451150 + 447 451160 Rh-116 5.65980E-05 9.05910E-05 451160 + 448 451161 Rh-116m 1.54270E-04 1.54270E-04 451161 + 449 451170 Rh-117 7.22480E-05 8.39590E-05 451170 + 450 451180 Rh-118 2.10410E-05 2.35550E-05 451180 + 451 451190 Rh-119 2.12970E-06 2.80670E-06 451190 + 452 451200 Rh-120 3.72230E-12 3.72230E-12 451200 + 453 461070 Pd-107 9.26840E-07 6.18820E-02 46107.82c + 454 461071 Pd-107m 2.03720E-06 2.03720E-06 461071 + 455 461080 Pd-108 2.17310E-05 5.50780E-02 46108.82c + 456 461090 Pd-109 2.51380E-05 4.61230E-02 461090 + 457 461091 Pd-109m 5.52520E-05 2.30770E-02 461091 + 458 461100 Pd-110 3.70570E-04 3.59630E-02 46110.82c + 459 461110 Pd-111 2.26460E-04 2.43260E-02 461110 + 460 461111 Pd-111m 4.97760E-04 5.92800E-04 461111 + 461 461120 Pd-112 1.49680E-03 1.50600E-02 461120 + 462 461130 Pd-113 3.63010E-04 8.00460E-03 461130 + 463 461131 Pd-113m 1.01570E-03 1.01570E-03 461131 + 464 461140 Pd-114 1.19000E-03 3.71840E-03 461140 + 465 461150 Pd-115 1.70990E-04 9.91530E-04 461150 + 466 461151 Pd-115m 3.75820E-04 5.08290E-04 461151 + 467 461160 Pd-116 2.63380E-04 5.08240E-04 461160 + 468 461170 Pd-117 2.42080E-05 1.62060E-04 461170 + 469 461171 Pd-117m 5.32070E-05 5.32070E-05 461171 + 470 461180 Pd-118 2.37570E-05 4.66250E-05 461180 + 471 461190 Pd-119 1.23170E-05 1.51240E-05 461190 + 472 461200 Pd-120 4.10810E-06 4.10810E-06 461200 + 473 461210 Pd-121 1.78640E-09 1.78640E-09 461210 + 474 461220 Pd-122 6.79220E-11 6.79220E-11 461220 + 475 461230 Pd-123 5.43670E-07 5.43670E-07 461230 + 476 461240 Pd-124 1.48230E-07 1.48230E-07 461240 + 477 471090 Ag-109 1.61010E-10 4.61230E-02 47109.82c + 478 471091 Ag-109m 1.20930E-09 4.61010E-02 471091 + 479 471100 Ag-110 5.28720E-07 5.48320E-07 471100 + 480 471101 Ag-110m 1.44120E-06 1.44120E-06 47510.82c + 481 471110 Ag-111 9.16550E-07 2.43720E-02 47111.82c + 482 471111 Ag-111m 6.88390E-06 2.42750E-02 471111 + 483 471120 Ag-112 3.33250E-05 1.50930E-02 471120 + 484 471130 Ag-113 8.40540E-06 5.29400E-03 471130 + 485 471131 Ag-113m 6.31300E-05 7.72820E-03 471131 + 486 471140 Ag-114 1.48040E-05 3.80490E-03 471140 + 487 471141 Ag-114m 7.17710E-05 7.17710E-05 471141 + 488 471150 Ag-115 1.00990E-05 9.04260E-04 471150 + 489 471151 Ag-115m 7.58480E-05 8.11190E-04 471151 + 490 471160 Ag-116 1.65470E-05 5.27500E-04 471160 + 491 471161 Ag-116m 4.51040E-05 4.51040E-05 471161 + 492 471170 Ag-117 6.61900E-06 9.54940E-05 471170 + 493 471171 Ag-117m 4.97130E-05 1.30740E-04 471171 + 494 471180 Ag-118 4.72010E-06 5.67950E-05 471180 + 495 471181 Ag-118m 2.28830E-05 2.95480E-05 471181 + 496 471190 Ag-119 3.27840E-06 1.08400E-05 471190 + 497 471191 Ag-119m 2.46230E-05 3.21850E-05 471191 + 498 471200 Ag-120 6.10130E-06 1.26910E-05 471200 + 499 471201 Ag-120m 1.02040E-05 1.22580E-05 471201 + 500 471210 Ag-121 8.94700E-06 8.94880E-06 471210 + 501 471220 Ag-122 4.27670E-06 4.27670E-06 471220 + 502 471221 Ag-122m 4.61080E-06 4.61080E-06 471221 + 503 471230 Ag-123 2.22250E-06 2.76620E-06 471230 + 504 471240 Ag-124 5.82110E-06 9.10730E-06 471240 + 505 471241 Ag-124m 6.27590E-06 6.27590E-06 471241 + 506 471250 Ag-125 1.21470E-05 1.21470E-05 471250 + 507 471260 Ag-126 2.38750E-06 2.38750E-06 471260 + 508 471270 Ag-127 1.12440E-06 1.12440E-06 471270 + 509 471280 Ag-128 2.75100E-08 2.75100E-08 471280 + 510 471290 Ag-129 1.04080E-09 1.04080E-09 471290 + 511 481120 Cd-112 3.77450E-09 1.50930E-02 48112.82c + 512 481130 Cd-113 3.82980E-07 7.98510E-03 48113.82c + 513 481131 Cd-113m 1.45030E-06 9.29780E-05 481131 + 514 481140 Cd-114 1.72070E-06 3.80670E-03 48114.82c + 515 481150 Cd-115 1.04000E-06 1.47540E-03 481150 + 516 481151 Cd-115m 3.93840E-06 7.47020E-05 48515.82c + 517 481160 Cd-116 7.70730E-06 5.77600E-04 48116.82c + 518 481170 Cd-117 1.68530E-06 1.73470E-04 481170 + 519 481171 Cd-117m 6.38230E-06 5.29920E-05 481171 + 520 481180 Cd-118 8.52810E-06 8.27560E-05 481180 + 521 481190 Cd-119 2.58910E-06 4.01940E-05 481190 + 522 481191 Cd-119m 7.24400E-06 1.26640E-05 481191 + 523 481200 Cd-120 1.30150E-05 3.34280E-05 481200 + 524 481210 Cd-121 8.58570E-06 1.65990E-05 481210 + 525 481211 Cd-121m 2.40220E-05 2.49570E-05 481211 + 526 481220 Cd-122 4.08470E-05 4.97350E-05 481220 + 527 481230 Cd-123 8.64600E-06 1.09140E-05 481230 + 528 481231 Cd-123m 2.41910E-05 2.46990E-05 481231 + 529 481240 Cd-124 9.30190E-05 1.05250E-04 481240 + 530 481250 Cd-125 3.71020E-05 4.31750E-05 481250 + 531 481251 Cd-125m 1.03810E-04 1.09880E-04 481251 + 532 481260 Cd-126 1.91140E-04 1.93530E-04 481260 + 533 481270 Cd-127 1.40010E-04 1.41130E-04 481270 + 534 481280 Cd-128 6.51260E-05 6.51530E-05 481280 + 535 481290 Cd-129 5.41820E-06 5.41870E-06 481290 + 536 481291 Cd-129m 1.51600E-05 1.51600E-05 481291 + 537 481300 Cd-130 3.01220E-06 3.01220E-06 481300 + 538 481310 Cd-131 2.54960E-08 2.54960E-08 481310 + 539 491140 In-114 1.97170E-11 8.60130E-11 491140 + 540 491141 In-114m 3.18390E-11 6.87000E-11 491141 + 541 491142 In-114m 3.68610E-11 3.68610E-11 491142 + 542 491150 In-115 1.88260E-09 1.47630E-03 49115.82c + 543 491151 In-115m 3.79060E-10 1.47540E-03 491151 + 544 491160 In-116 5.55540E-09 5.55540E-09 491160 + 545 491161 In-116m 8.97080E-09 1.93570E-08 491161 + 546 491162 In-116m 1.03860E-08 1.03860E-08 491162 + 547 491170 In-117 1.86970E-07 1.42140E-04 491170 + 548 491171 In-117m 3.76460E-08 1.59820E-04 491171 + 549 491180 In-118 1.91570E-07 8.29480E-05 491180 + 550 491181 In-118m 3.09350E-07 6.62480E-07 491181 + 551 491182 In-118m 3.58150E-07 3.58150E-07 491182 + 552 491190 In-119 2.80810E-06 2.14180E-05 491190 + 553 491191 In-119m 5.65400E-07 3.68790E-05 491191 + 554 491200 In-120 1.34460E-06 3.47720E-05 491200 + 555 491201 In-120m 1.34460E-06 1.34460E-06 491201 + 556 491202 In-120m 1.34460E-06 1.34460E-06 491202 + 557 491210 In-121 1.01040E-05 4.08090E-05 491210 + 558 491211 In-121m 2.03450E-06 1.30430E-05 491211 + 559 491220 In-122 4.23180E-06 5.39660E-05 491220 + 560 491221 In-122m 3.53860E-06 3.53860E-06 491221 + 561 491222 In-122m 3.53860E-06 3.53860E-06 491222 + 562 491230 In-123 3.16770E-05 5.94550E-05 491230 + 563 491231 In-123m 6.37800E-06 1.42130E-05 491231 + 564 491240 In-124 3.40330E-05 1.39290E-04 491240 + 565 491241 In-124m 3.66920E-05 3.66920E-05 491241 + 566 491250 In-125 2.27350E-04 3.57900E-04 491250 + 567 491251 In-125m 4.57770E-05 6.82860E-05 491251 + 568 491260 In-126 2.79030E-04 4.72560E-04 491260 + 569 491261 In-126m 3.00830E-04 3.00830E-04 491261 + 570 491270 In-127 1.12890E-03 1.12890E-03 491270 + 571 491271 In-127m 2.27300E-04 3.68430E-04 491271 + 572 491280 In-128 4.79140E-04 7.31900E-04 491280 + 573 491281 In-128m 1.87610E-04 2.52760E-04 491281 + 574 491282 In-128m 7.18850E-04 7.18850E-04 491282 + 575 491290 In-129 1.20640E-03 1.22160E-03 491290 + 576 491291 In-129m 2.42900E-04 2.48370E-04 491291 + 577 491300 In-130 1.66050E-04 1.68960E-04 491300 + 578 491301 In-130m 2.41780E-04 2.41780E-04 491301 + 579 491302 In-130m 3.36790E-04 3.36790E-04 491302 + 580 491310 In-131 7.96820E-05 8.05180E-05 491310 + 581 491311 In-131m 7.96820E-05 7.96820E-05 491311 + 582 491312 In-131m 7.96820E-05 7.96820E-05 491312 + 583 491320 In-132 2.22210E-05 2.22210E-05 491320 + 584 491330 In-133 2.53130E-06 3.04090E-06 491330 + 585 491331 In-133m 5.09650E-07 5.09650E-07 491331 + 586 491340 In-134 7.42650E-09 7.42650E-09 491340 + 587 501170 Sn-117 9.91650E-12 2.26690E-04 50117.82c + 588 501171 Sn-117m 3.75530E-11 4.84330E-07 501171 + 589 501180 Sn-118 1.02590E-09 8.36160E-05 50118.82c + 590 501190 Sn-119 2.87470E-09 5.62450E-05 50119.82c + 591 501191 Sn-119m 1.08860E-08 1.93590E-05 501191 + 592 501200 Sn-120 1.62130E-07 3.76240E-05 50120.82c + 593 501210 Sn-121 4.09750E-07 5.39600E-05 501210 + 594 501211 Sn-121m 1.14650E-06 5.76950E-06 501211 + 595 501220 Sn-122 2.52930E-06 6.35740E-05 50122.82c + 596 501230 Sn-123 3.26240E-06 7.79530E-06 50123.82c + 597 501231 Sn-123m 1.16600E-06 7.03000E-05 501231 + 598 501240 Sn-124 4.01010E-05 2.16080E-04 50124.82c + 599 501250 Sn-125 7.10300E-05 1.31490E-04 50125.82c + 600 501251 Sn-125m 2.53860E-05 3.91120E-04 501251 + 601 501260 Sn-126 4.91510E-04 1.26740E-03 50126.82c + 602 501270 Sn-127 9.92560E-04 1.43260E-03 501270 + 603 501271 Sn-127m 3.54740E-04 1.40950E-03 501271 + 604 501280 Sn-128 1.20750E-03 5.94950E-03 501280 + 605 501281 Sn-128m 3.29120E-03 4.01010E-03 501281 + 606 501290 Sn-129 1.73700E-03 3.07710E-03 501290 + 607 501291 Sn-129m 4.86010E-03 4.99010E-03 501291 + 608 501300 Sn-130 2.53130E-03 2.98900E-03 501300 + 609 501301 Sn-130m 6.89980E-03 7.19130E-03 501301 + 610 501310 Sn-131 1.65040E-03 1.80470E-03 501310 + 611 501311 Sn-131m 4.61780E-03 4.70090E-03 501311 + 612 501320 Sn-132 3.27870E-03 3.30350E-03 501320 + 613 501330 Sn-133 3.82830E-04 3.83290E-04 501330 + 614 501340 Sn-134 6.40570E-05 6.40590E-05 501340 + 615 501350 Sn-135 4.96140E-06 4.96140E-06 501350 + 616 501360 Sn-136 7.59560E-08 7.59560E-08 501360 + 617 511190 Sb-119 1.11330E-12 1.56030E-12 511190 + 618 511200 Sb-120 1.95000E-11 1.95000E-11 511200 + 619 511201 Sb-120m 3.26120E-11 3.26120E-11 511201 + 620 511210 Sb-121 2.97530E-09 5.52550E-05 51121.82c + 621 511220 Sb-122 2.38270E-08 5.57480E-08 511220 + 622 511221 Sb-122m 3.19210E-08 3.19210E-08 511221 + 623 511230 Sb-123 2.21660E-06 8.03120E-05 51123.82c + 624 511240 Sb-124 7.74620E-07 1.99360E-06 51124.82c + 625 511241 Sb-124m 6.24880E-07 1.62530E-06 511241 + 626 511242 Sb-124m 1.00040E-06 1.00040E-06 511242 + 627 511250 Sb-125 2.03580E-05 5.42960E-04 51125.82c + 628 511260 Sb-126 1.82900E-05 2.18720E-05 51126.82c + 629 511261 Sb-126m 1.14240E-05 2.55860E-05 511261 + 630 511262 Sb-126m 1.41620E-05 1.41620E-05 511262 + 631 511270 Sb-127 2.07970E-04 3.05010E-03 511270 + 632 511280 Sb-128 2.46020E-04 6.20790E-03 511280 + 633 511281 Sb-128m 3.44090E-04 3.44090E-04 511281 + 634 511290 Sb-129 2.10000E-03 8.27940E-03 511290 + 635 511291 Sb-129m 1.55410E-03 4.04910E-03 511291 + 636 511300 Sb-130 4.33930E-03 1.09240E-02 511300 + 637 511301 Sb-130m 4.33930E-03 7.93490E-03 511301 + 638 511310 Sb-131 2.22530E-02 2.87590E-02 511310 + 639 511320 Sb-132 1.30070E-02 1.63100E-02 511320 + 640 511321 Sb-132m 1.15150E-02 1.15150E-02 511321 + 641 511330 Sb-133 2.38610E-02 2.42550E-02 511330 + 642 511340 Sb-134 1.94560E-03 1.99930E-03 511340 + 643 511341 Sb-134m 5.30330E-03 5.30380E-03 511341 + 644 511350 Sb-135 2.23010E-03 2.23400E-03 511350 + 645 511360 Sb-136 3.95380E-04 3.95430E-04 511360 + 646 511370 Sb-137 4.77690E-05 4.77690E-05 511370 + 647 511380 Sb-138 4.00200E-06 4.00200E-06 511380 + 648 511390 Sb-139 6.42540E-09 6.42540E-09 511390 + 649 521220 Te-122 1.81130E-11 5.43170E-08 52122.82c + 650 521260 Te-126 4.89620E-10 4.38770E-05 52126.82c + 651 521270 Te-127 1.18260E-06 3.04240E-03 521270 + 652 521271 Te-127m 3.30890E-06 5.05940E-04 52527.82c + 653 521280 Te-128 1.56330E-05 6.55520E-03 52128.82c + 654 521290 Te-129 3.27310E-05 1.00600E-02 521290 + 655 521291 Te-129m 9.15790E-05 4.82670E-03 52529.82c + 656 521300 Te-130 1.10660E-03 1.99650E-02 52130.82c + 657 521310 Te-131 1.08560E-03 2.86630E-02 521310 + 658 521311 Te-131m 3.03750E-03 5.33990E-03 521311 + 659 521320 Te-132 1.72170E-02 4.50420E-02 52132.82c + 660 521330 Te-133 8.56570E-03 3.35580E-02 521330 + 661 521331 Te-133m 2.39660E-02 2.81620E-02 521331 + 662 521340 Te-134 5.07570E-02 5.84070E-02 521340 + 663 521350 Te-135 2.19910E-02 2.39390E-02 521350 + 664 521360 Te-136 1.16490E-02 1.20020E-02 521360 + 665 521370 Te-137 2.84570E-03 2.87010E-03 521370 + 666 521380 Te-138 6.96590E-04 7.00590E-04 521380 + 667 521390 Te-139 4.45790E-05 4.45850E-05 521390 + 668 521400 Te-140 1.19160E-05 1.19160E-05 521400 + 669 521410 Te-141 4.77310E-08 4.77310E-08 521410 + 670 531280 I-128 1.66720E-10 1.66720E-10 531280 + 671 531290 I-129 2.32450E-08 1.18460E-02 53129.82c + 672 531300 I-130 7.31600E-06 9.57060E-06 53130.82c + 673 531301 I-130m 2.68400E-06 2.68400E-06 531301 + 674 531310 I-131 8.34260E-05 3.29650E-02 53131.82c + 675 531320 I-132 2.91790E-04 4.55560E-02 531320 + 676 531321 I-132m 2.58340E-04 2.58340E-04 531321 + 677 531330 I-133 2.47640E-03 6.11010E-02 531330 + 678 531331 I-133m 1.83260E-03 1.83260E-03 531331 + 679 531340 I-134 8.17980E-03 7.36630E-02 531340 + 680 531341 I-134m 7.24220E-03 7.24220E-03 531341 + 681 531350 I-135 5.14170E-02 7.53560E-02 53135.82c + 682 531360 I-136 1.23680E-02 2.44130E-02 531360 + 683 531361 I-136m 3.37120E-02 3.37550E-02 531361 + 684 531370 I-137 3.99720E-02 4.28000E-02 531370 + 685 531380 I-138 1.45970E-02 1.52530E-02 531380 + 686 531390 I-139 9.63430E-03 9.67890E-03 531390 + 687 531400 I-140 2.08720E-03 2.09910E-03 531400 + 688 531410 I-141 5.92320E-04 5.92370E-04 531410 + 689 531420 I-142 5.56610E-05 5.56610E-05 531420 + 690 531430 I-143 4.98070E-06 4.98070E-06 531430 + 691 531440 I-144 1.97880E-06 1.97880E-06 531440 + 692 541310 Xe-131 2.64460E-07 3.29660E-02 54131.82c + 693 541311 Xe-131m 7.39940E-07 3.58810E-04 541311 + 694 541320 Xe-132 3.02550E-06 4.56000E-02 54132.82c + 695 541321 Xe-132m 4.05340E-06 4.05340E-06 541321 + 696 541330 Xe-133 1.01470E-05 6.11390E-02 54133.82c + 697 541331 Xe-133m 2.83910E-05 1.76760E-03 541331 + 698 541340 Xe-134 1.29350E-04 7.43110E-02 54134.82c + 699 541341 Xe-134m 3.52580E-04 5.19150E-04 541341 + 700 541350 Xe-135 7.77050E-04 7.82190E-02 54135.82c + 701 541351 Xe-135m 2.17420E-03 1.46140E-02 541351 + 702 541360 Xe-136 1.75380E-02 7.84880E-02 54136.82c + 703 541370 Xe-137 2.83990E-02 6.92260E-02 541370 + 704 541380 Xe-138 3.69920E-02 5.23860E-02 541380 + 705 541390 Xe-139 2.34060E-02 3.23320E-02 541390 + 706 541400 Xe-140 1.95580E-02 2.15860E-02 541400 + 707 541410 Xe-141 7.25100E-03 7.73290E-03 541410 + 708 541420 Xe-142 3.23820E-03 3.28190E-03 541420 + 709 541430 Xe-143 5.12710E-04 5.16490E-04 541430 + 710 541440 Xe-144 1.12650E-04 1.13840E-04 541440 + 711 541450 Xe-145 8.79210E-06 8.79210E-06 541450 + 712 541460 Xe-146 3.14110E-08 3.14110E-08 541460 + 713 541470 Xe-147 8.06070E-10 8.06070E-10 541470 + 714 551330 Cs-133 1.80340E-09 6.11390E-02 55133.82c + 715 551340 Cs-134 5.39680E-07 1.01750E-06 55134.82c + 716 551341 Cs-134m 4.77820E-07 4.77820E-07 551341 + 717 551350 Cs-135 7.41540E-06 7.83200E-02 55135.82c + 718 551351 Cs-135m 5.48760E-06 5.48760E-06 551351 + 719 551360 Cs-136 1.43180E-04 1.94370E-04 55136.82c + 720 551361 Cs-136m 1.02370E-04 1.02370E-04 551361 + 721 551370 Cs-137 2.86050E-03 7.20860E-02 55137.82c + 722 551380 Cs-138 3.23030E-03 5.99920E-02 551380 + 723 551381 Cs-138m 5.40230E-03 5.40230E-03 551381 + 724 551390 Cs-139 2.08350E-02 5.31670E-02 551390 + 725 551400 Cs-140 2.48120E-02 4.64020E-02 551400 + 726 551410 Cs-141 3.83170E-02 4.60580E-02 551410 + 727 551420 Cs-142 2.62170E-02 2.94920E-02 551420 + 728 551430 Cs-143 1.90180E-02 1.95330E-02 551430 + 729 551440 Cs-144 3.32670E-03 5.10080E-03 551440 + 730 551441 Cs-144m 3.32670E-03 3.32690E-03 551441 + 731 551450 Cs-145 2.46420E-03 2.47260E-03 551450 + 732 551460 Cs-146 4.65750E-04 4.65780E-04 551460 + 733 551470 Cs-147 1.01650E-04 1.01650E-04 551470 + 734 551480 Cs-148 8.94100E-06 8.94100E-06 551480 + 735 551490 Cs-149 2.29790E-09 2.29790E-09 551490 + 736 561360 Ba-136 5.82480E-09 2.45570E-04 56136.82c + 737 561361 Ba-136m 1.58770E-08 1.58770E-08 561361 + 738 561370 Ba-137 1.87420E-06 7.20930E-02 56137.82c + 739 561371 Ba-137m 5.24400E-06 6.80540E-02 561371 + 740 561380 Ba-138 1.99530E-04 6.12180E-02 56138.82c + 741 561390 Ba-139 8.36850E-04 5.40030E-02 561390 + 742 561400 Ba-140 3.49350E-03 4.98950E-02 56140.82c + 743 561410 Ba-141 6.51720E-03 5.25750E-02 561410 + 744 561420 Ba-142 1.67660E-02 4.65790E-02 561420 + 745 561430 Ba-143 1.99070E-02 3.92830E-02 561430 + 746 561440 Ba-144 2.14940E-02 2.84490E-02 561440 + 747 561450 Ba-145 1.05810E-02 1.27660E-02 561450 + 748 561460 Ba-146 6.43830E-03 6.86690E-03 561460 + 749 561470 Ba-147 1.75080E-03 1.82570E-03 561470 + 750 561480 Ba-148 5.50420E-04 5.57120E-04 561480 + 751 561490 Ba-149 5.12780E-05 5.12800E-05 561490 + 752 561500 Ba-150 8.89660E-06 8.89660E-06 561500 + 753 561510 Ba-151 9.88310E-09 9.88310E-09 561510 + 754 561520 Ba-152 2.35160E-10 2.35160E-10 561520 + 755 571380 La-138 1.52100E-09 1.52100E-09 57138.82c + 756 571390 La-139 8.92100E-06 5.40120E-02 57139.82c + 757 571400 La-140 4.86960E-05 4.99440E-02 57140.82c + 758 571410 La-141 3.38140E-04 5.29140E-02 571410 + 759 571420 La-142 9.60290E-04 4.75390E-02 571420 + 760 571430 La-143 4.72860E-03 4.40110E-02 571430 + 761 571440 La-144 1.01720E-02 3.86210E-02 571440 + 762 571450 La-145 1.88030E-02 3.15690E-02 571450 + 763 571460 La-146 5.50540E-03 1.23720E-02 571460 + 764 571461 La-146m 1.15500E-02 1.15500E-02 571461 + 765 571470 La-147 1.82180E-02 2.00460E-02 571470 + 766 571480 La-148 8.79080E-03 9.34590E-03 571480 + 767 571490 La-149 4.54850E-03 4.59960E-03 571490 + 768 571500 La-150 1.10090E-03 1.10980E-03 571500 + 769 571510 La-151 2.74390E-04 2.74400E-04 571510 + 770 571520 La-152 3.08190E-05 3.08190E-05 571520 + 771 571530 La-153 2.00030E-06 2.00030E-06 571530 + 772 571540 La-154 4.00430E-10 4.00430E-10 571540 + 773 581410 Ce-141 9.87880E-07 5.29150E-02 58141.82c + 774 581420 Ce-142 1.29320E-05 4.75520E-02 58142.82c + 775 581430 Ce-143 5.18420E-05 4.40630E-02 58143.82c + 776 581440 Ce-144 3.16790E-04 3.89370E-02 58144.82c + 777 581450 Ce-145 1.11940E-03 3.26890E-02 581450 + 778 581460 Ce-146 3.48600E-03 2.74080E-02 581460 + 779 581470 Ce-147 5.84690E-03 2.58930E-02 581470 + 780 581480 Ce-148 8.96460E-03 1.83750E-02 581480 + 781 581490 Ce-149 7.01980E-03 1.15850E-02 581490 + 782 581500 Ce-150 5.35470E-03 6.43450E-03 581500 + 783 581510 Ce-151 1.76860E-03 2.04490E-03 581510 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8.50020E-04 8.77900E-04 591540 + 804 591550 Pr-155 2.85620E-04 2.85710E-04 591550 + 805 591560 Pr-156 4.04790E-05 4.04810E-05 591560 + 806 591570 Pr-157 1.05370E-05 1.05370E-05 591570 + 807 591580 Pr-158 3.46650E-09 3.46650E-09 591580 + 808 591590 Pr-159 5.71120E-11 5.71120E-11 591590 + 809 601460 Nd-146 6.87090E-09 2.74980E-02 60146.82c + 810 601470 Nd-147 1.99570E-06 2.64160E-02 60147.82c + 811 601480 Nd-148 1.49080E-05 2.00190E-02 60148.82c + 812 601490 Nd-149 9.68640E-05 1.55450E-02 601490 + 813 601500 Nd-150 3.69640E-04 1.20570E-02 60150.82c + 814 601510 Nd-151 7.96040E-04 9.34800E-03 601510 + 815 601520 Nd-152 1.62830E-03 6.43050E-03 601520 + 816 601530 Nd-153 1.62930E-03 4.37490E-03 601530 + 817 601540 Nd-154 1.54620E-03 2.42410E-03 601540 + 818 601550 Nd-155 7.25330E-04 1.01210E-03 601550 + 819 601560 Nd-156 3.44130E-04 3.84180E-04 601560 + 820 601570 Nd-157 8.53050E-05 9.51690E-05 601570 + 821 601580 Nd-158 1.92880E-05 1.92910E-05 601580 + 822 601590 Nd-159 9.28570E-07 9.28630E-07 601590 + 823 601600 Nd-160 1.02050E-08 1.02050E-08 601600 + 824 601610 Nd-161 1.67410E-10 1.67410E-10 601610 + 825 611480 Pm-148 1.33720E-10 1.51950E-10 61148.82c + 826 611481 Pm-148m 3.64510E-10 3.64510E-10 61548.82c + 827 611490 Pm-149 9.86810E-07 1.55460E-02 61149.82c + 828 611500 Pm-150 7.91160E-06 7.91160E-06 611500 + 829 611510 Pm-151 3.95410E-05 9.38750E-03 61151.82c + 830 611520 Pm-152 2.16860E-05 6.45210E-03 611520 + 831 611521 Pm-152m 4.55920E-05 4.55920E-05 611521 + 832 611522 Pm-152m 5.95550E-05 5.95550E-05 611522 + 833 611530 Pm-153 4.52500E-04 4.82740E-03 611530 + 834 611540 Pm-154 3.83580E-04 2.80770E-03 611540 + 835 611541 Pm-154m 3.83580E-04 3.83580E-04 611541 + 836 611550 Pm-155 1.12430E-03 2.13640E-03 611550 + 837 611560 Pm-156 9.53370E-04 1.33760E-03 611560 + 838 611570 Pm-157 6.74280E-04 7.69450E-04 611570 + 839 611580 Pm-158 2.77090E-04 2.96380E-04 611580 + 840 611590 Pm-159 1.23310E-04 1.24240E-04 611590 + 841 611600 Pm-160 1.76000E-05 1.76100E-05 611600 + 842 611610 Pm-161 1.02980E-05 1.02980E-05 611610 + 843 611620 Pm-162 1.47480E-08 1.47480E-08 611620 + 844 611630 Pm-163 4.20870E-10 4.20870E-10 611630 + 845 621510 Sm-151 1.97650E-09 9.38750E-03 62151.82c + 846 621520 Sm-152 9.94630E-07 6.55830E-03 62152.82c + 847 621530 Sm-153 5.26630E-07 4.82940E-03 62153.82c + 848 621531 Sm-153m 1.47350E-06 1.47350E-06 621531 + 849 621540 Sm-154 3.00060E-05 3.22130E-03 62154.82c + 850 621550 Sm-155 8.17160E-05 2.21810E-03 621550 + 851 621560 Sm-156 1.64600E-04 1.50220E-03 621560 + 852 621570 Sm-157 1.99890E-04 9.69340E-04 621570 + 853 621580 Sm-158 2.06320E-04 5.02730E-04 621580 + 854 621590 Sm-159 1.59600E-04 2.83860E-04 621590 + 855 621600 Sm-160 8.19800E-05 9.95430E-05 621600 + 856 621610 Sm-161 2.57520E-05 3.60500E-05 621610 + 857 621620 Sm-162 9.00360E-06 9.01830E-06 621620 + 858 621630 Sm-163 3.81790E-06 3.81830E-06 621630 + 859 621640 Sm-164 2.36700E-08 2.36700E-08 621640 + 860 621650 Sm-165 1.29410E-09 1.29410E-09 621650 + 861 631530 Eu-153 1.42970E-10 4.82940E-03 63153.82c + 862 631540 Eu-154 1.81130E-09 3.76420E-09 63154.82c + 863 631541 Eu-154m 1.95290E-09 1.95290E-09 631541 + 864 631550 Eu-155 1.03440E-07 2.21830E-03 63155.82c + 865 631560 Eu-156 7.89140E-06 1.51000E-03 63156.82c + 866 631570 Eu-157 3.23710E-05 1.00170E-03 63157.82c + 867 631580 Eu-158 6.62460E-05 5.68970E-04 631580 + 868 631590 Eu-159 1.00870E-04 3.84730E-04 631590 + 869 631600 Eu-160 9.58340E-05 1.95380E-04 631600 + 870 631610 Eu-161 8.87760E-05 1.24830E-04 631610 + 871 631620 Eu-162 6.38880E-05 7.29060E-05 631620 + 872 631630 Eu-163 3.53350E-05 3.91530E-05 631630 + 873 631640 Eu-164 7.74130E-06 7.76500E-06 631640 + 874 631650 Eu-165 1.15740E-05 1.15750E-05 631650 + 875 631660 Eu-166 2.37990E-08 2.37990E-08 631660 + 876 631670 Eu-167 8.32490E-10 8.32490E-10 631670 + 877 641560 Gd-156 3.21000E-10 1.51000E-03 64156.82c + 878 641570 Gd-157 9.57680E-07 1.00270E-03 64157.82c + 879 641580 Gd-158 9.17450E-07 5.69890E-04 64158.82c + 880 641590 Gd-159 3.71080E-06 3.88440E-04 641590 + 881 641600 Gd-160 7.88090E-06 2.03260E-04 64160.82c + 882 641610 Gd-161 1.36650E-05 1.38490E-04 641610 + 883 641620 Gd-162 1.34690E-05 8.63750E-05 641620 + 884 641630 Gd-163 1.14370E-05 5.05900E-05 641630 + 885 641640 Gd-164 1.06350E-05 1.84000E-05 641640 + 886 641650 Gd-165 4.81600E-06 1.63910E-05 641650 + 887 641660 Gd-166 1.68830E-06 1.71210E-06 641660 + 888 641670 Gd-167 9.83990E-07 9.84820E-07 641670 + 889 641680 Gd-168 3.39620E-08 3.39620E-08 641680 + 890 641690 Gd-169 4.99890E-10 4.99890E-10 641690 + 891 651580 Tb-158 1.28310E-11 1.40840E-11 651580 + 892 651581 Tb-158m 1.26120E-12 1.26120E-12 651581 + 893 651590 Tb-159 5.02580E-10 3.88440E-04 65159.82c + 894 651600 Tb-160 8.76770E-07 8.76770E-07 65160.82c + 895 651610 Tb-161 1.17610E-07 1.38610E-04 651610 + 896 651620 Tb-162 8.99080E-07 8.72740E-05 651620 + 897 651630 Tb-163 3.81310E-06 5.44030E-05 651630 + 898 651640 Tb-164 4.83200E-06 2.32320E-05 651640 + 899 651650 Tb-165 1.15450E-05 2.79360E-05 651650 + 900 651660 Tb-166 7.59570E-06 9.30780E-06 651660 + 901 651670 Tb-167 9.83890E-07 1.96870E-06 651670 + 902 651680 Tb-168 9.82880E-07 1.01680E-06 651680 + 903 651690 Tb-169 6.65900E-08 6.70900E-08 651690 + 904 651700 Tb-170 1.02080E-08 1.02080E-08 651700 + 905 651710 Tb-171 6.85670E-10 6.85670E-10 651710 + 906 661610 Dy-161 2.51110E-11 1.38610E-04 66161.82c + 907 661620 Dy-162 8.32570E-10 8.72750E-05 66162.82c + 908 661630 Dy-163 1.12870E-08 5.44150E-05 66163.82c + 909 661640 Dy-164 8.26010E-08 2.33150E-05 66164.82c + 910 661650 Dy-165 8.49820E-07 2.88970E-05 661650 + 911 661651 Dy-165m 1.13150E-07 1.13150E-07 661651 + 912 661660 Dy-166 1.30130E-06 1.06090E-05 661660 + 913 661670 Dy-167 1.96740E-06 3.93610E-06 661670 + 914 661680 Dy-168 9.82780E-07 1.99960E-06 661680 + 915 661690 Dy-169 3.72610E-07 4.39700E-07 661690 + 916 661700 Dy-170 2.72520E-07 2.82730E-07 661700 + 917 661710 Dy-171 4.81000E-08 4.87860E-08 661710 + 918 661720 Dy-172 7.22590E-09 7.22590E-09 661720 + 919 661730 Dy-173 4.35130E-10 4.35130E-10 661730 + 920 671630 Ho-163 1.41230E-12 1.60030E-12 671630 + 921 671640 Ho-164 6.34550E-12 2.36420E-11 671640 + 922 671641 Ho-164m 1.72970E-11 1.72970E-11 671641 + 923 671650 Ho-165 1.20250E-09 2.89000E-05 67165.82c + 924 671660 Ho-166 1.69770E-09 1.06110E-05 671660 + 925 671661 Ho-166m 4.62770E-09 4.62770E-09 671661 + 926 671670 Ho-167 3.47870E-08 3.97090E-06 671670 + 927 671680 Ho-168 3.67720E-07 2.97920E-06 671680 + 928 671681 Ho-168m 6.14960E-07 6.14960E-07 671681 + 929 671690 Ho-169 5.52480E-07 9.92180E-07 671690 + 930 671700 Ho-170 1.34600E-07 1.34600E-07 671700 + 931 671701 Ho-170m 4.93800E-08 3.32110E-07 671701 + 932 671710 Ho-171 1.41280E-07 1.90070E-07 671710 + 933 671720 Ho-172 4.94630E-08 5.66890E-08 671720 + 934 671730 Ho-173 1.47950E-08 1.52300E-08 671730 + 935 671740 Ho-174 1.86500E-09 1.86500E-09 671740 + 936 671750 Ho-175 2.29250E-10 2.29250E-10 671750 + 937 681660 Er-166 1.65930E-12 1.06110E-05 68166.82c + 938 681670 Er-167 2.62030E-11 3.97090E-06 68167.82c + 939 681671 Er-167m 3.48880E-12 4.74490E-07 681671 + 940 681680 Er-168 6.86090E-10 2.98300E-06 68168.82c + 941 681690 Er-169 1.58800E-09 9.93770E-07 681690 + 942 681700 Er-170 1.33520E-08 4.80060E-07 68170.82c + 943 681710 Er-171 2.49620E-08 2.15030E-07 681710 + 944 681720 Er-172 3.89590E-08 9.56480E-08 681720 + 945 681730 Er-173 2.55850E-08 4.08150E-08 681730 + 946 681740 Er-174 1.43220E-08 1.61870E-08 681740 + 947 681750 Er-175 4.26120E-09 4.49050E-09 681750 + 948 681760 Er-176 1.08690E-09 1.08690E-09 681760 + 949 681770 Er-177 1.10390E-10 1.10390E-10 681770 + 950 691700 Tm-170 1.55750E-11 1.55750E-11 691700 + 951 691710 Tm-171 1.65900E-10 2.15190E-07 691710 + 952 691720 Tm-172 7.08210E-10 9.63560E-08 691720 + 953 691730 Tm-173 2.32340E-09 4.31380E-08 691730 + 954 691740 Tm-174 3.04680E-09 1.92340E-08 691740 + 955 691750 Tm-175 3.95250E-09 8.44300E-09 691750 + 956 691760 Tm-176 2.22740E-09 3.31430E-09 691760 + 957 691770 Tm-177 1.03630E-09 1.14670E-09 691770 + 958 691780 Tm-178 2.17070E-10 2.17070E-10 691780 + 959 691790 Tm-179 4.36220E-11 4.36220E-11 691790 + 960 701730 Yb-173 8.00110E-12 4.31470E-08 701730 + 961 701740 Yb-174 5.82720E-11 1.92920E-08 701740 + 962 701750 Yb-175 1.76240E-10 8.64260E-09 701750 + 963 701751 Yb-175m 2.34650E-11 6.52450E-09 701751 + 964 701760 Yb-176 1.74320E-10 3.65200E-09 701760 + 965 701761 Yb-176m 3.65710E-10 2.02290E-09 701761 + 966 701770 Yb-177 4.74240E-10 1.71640E-09 701770 + 967 701771 Yb-177m 9.54870E-11 1.24220E-09 701771 + 968 701780 Yb-178 5.15690E-10 7.32760E-10 701780 + 969 701790 Yb-179 2.33590E-10 2.77210E-10 701790 + 970 701800 Yb-180 8.95910E-11 8.95910E-11 701800 + 971 701810 Yb-181 1.61180E-11 1.61180E-11 701810 + 972 711760 Lu-176 1.68870E-12 2.03980E-10 71176.82c + 973 711770 Lu-177 9.45520E-12 1.72690E-09 711770 + 974 711771 Lu-177m 4.50220E-12 4.61420E-12 711771 + 975 711780 Lu-178 1.39440E-11 7.46700E-10 711780 + 976 711781 Lu-178m 1.86820E-11 1.86820E-11 711781 + 977 711790 Lu-179 6.02160E-11 3.45450E-10 711790 + 978 711791 Lu-179m 8.01750E-12 2.85230E-10 711791 + 979 711800 Lu-180 1.53850E-11 8.14940E-11 711800 + 980 711801 Lu-180m 1.53850E-11 1.04980E-10 711801 + 981 711802 Lu-180m 2.72420E-11 2.72420E-11 711802 + 982 711810 Lu-181 4.53600E-11 6.14780E-11 711810 + 983 711820 Lu-182 1.61710E-11 1.61710E-11 711820 + 984 711830 Lu-183 4.90770E-12 4.90770E-12 711830 + 985 721800 Hf-180 1.29640E-12 1.51570E-10 72180.82c + 986 721801 Hf-180m 2.71970E-12 1.63410E-11 721801 + 987 721810 Hf-181 7.66770E-12 6.91460E-11 721810 + 988 721820 Hf-182 3.94200E-12 2.35860E-11 721820 + 989 721821 Hf-182m 8.27000E-12 8.27000E-12 721821 + 990 721830 Hf-183 8.13830E-12 1.30460E-11 721830 + 991 721840 Hf-184 1.49340E-12 1.49340E-12 721840 + 992 721841 Hf-184m 3.13310E-12 3.13310E-12 721841 + 993 721850 Hf-185 1.40010E-12 1.40010E-12 721850 + 994 731850 Ta-185 7.80120E-13 2.64570E-12 731850 + + Nuclide 95244.82c -- americium 244 (Am-244) is using NFY data from Cm-245 + + Nuclide 95644.82c -- americium 244m (Am-244m) is using NFY data from Cm-245 + + Nuclide 96240.82c -- curium 240 (Cm-240) is using NFY data from U-236 + + Nuclide 96241.82c -- curium 241 (Cm-241) is using NFY data from Np-238 + + Nuclide 96242.82c -- curium 242 (Cm-242) is using NFY data from U-238 + + Spontaneous fission: + + Decay constant : 4.92390E-08 + SF decay fraction : 6.10000E-08 + Number of products : 1012 / 1052 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 5.59970E-05 5.59970E-05 1001.82c + 2 10020 H-2 1.71130E-05 1.71130E-05 1002.82c + 3 10030 H-3 1.92000E-04 1.92000E-04 1003.82c + 4 20040 He-4 3.54000E-03 3.54000E-03 2004.82c + 5 220530 Ti-53 1.72840E-12 1.72840E-12 220530 + 6 220540 Ti-54 3.16410E-12 3.16410E-12 220540 + 7 220550 Ti-55 2.36520E-12 2.36520E-12 220550 + 8 220560 Ti-56 1.81700E-12 1.81700E-12 220560 + 9 230540 V-54 1.31960E-12 4.48370E-12 230540 + 10 230550 V-55 5.55400E-12 7.91920E-12 230550 + 11 230560 V-56 8.58430E-12 1.04010E-11 230560 + 12 230570 V-57 1.26230E-11 1.26230E-11 230570 + 13 230580 V-58 6.16290E-12 6.16290E-12 230580 + 14 230590 V-59 3.73480E-12 3.73480E-12 230590 + 15 240560 Cr-56 5.00320E-12 1.54550E-11 240560 + 16 240570 Cr-57 1.41760E-11 3.16790E-11 240570 + 17 240580 Cr-58 3.95930E-11 4.08260E-11 240580 + 18 240590 Cr-59 5.04710E-11 5.42060E-11 240590 + 19 240600 Cr-60 6.27260E-11 6.27260E-11 240600 + 20 240610 Cr-61 2.45560E-11 2.45560E-11 240610 + 21 240620 Cr-62 9.55010E-12 9.55010E-12 240620 + 22 240630 Cr-63 1.31140E-12 1.31140E-12 240630 + 23 250580 Mn-58 4.56990E-12 4.53950E-11 250580 + 24 250590 Mn-59 3.73900E-11 9.15960E-11 250590 + 25 250600 Mn-60 9.03290E-12 8.09850E-11 250600 + 26 250601 Mn-60m 8.02250E-11 8.02250E-11 250601 + 27 250610 Mn-61 2.06650E-10 2.31210E-10 250610 + 28 250620 Mn-62 1.50690E-10 1.55460E-10 250620 + 29 250621 Mn-62m 2.70520E-11 3.18270E-11 250621 + 30 250630 Mn-63 1.73720E-10 1.75030E-10 250630 + 31 250640 Mn-64 5.02280E-11 5.02280E-11 250640 + 32 250650 Mn-65 1.55520E-11 1.55520E-11 250650 + 33 250660 Mn-66 1.55440E-12 1.55440E-12 250660 + 34 260600 Fe-60 1.54810E-11 1.67470E-10 260600 + 35 260610 Fe-61 7.30080E-11 3.04210E-10 260610 + 36 260620 Fe-62 3.54520E-10 5.41810E-10 260620 + 37 260630 Fe-63 6.77040E-10 8.52070E-10 260630 + 38 260640 Fe-64 1.21100E-09 1.26120E-09 260640 + 39 260650 Fe-65 8.71650E-10 8.87200E-10 260650 + 40 260660 Fe-66 6.45450E-10 6.47000E-10 260660 + 41 260670 Fe-67 1.42330E-10 1.42330E-10 260670 + 42 260680 Fe-68 2.76020E-11 2.76020E-11 260680 + 43 260690 Fe-69 2.10820E-12 2.10820E-12 260690 + 44 270610 Co-61 1.13990E-12 3.05350E-10 270610 + 45 270620 Co-62 3.88360E-12 5.45780E-10 270620 + 46 270621 Co-62m 9.09640E-12 9.09640E-12 270621 + 47 270630 Co-63 1.54710E-10 1.00680E-09 270630 + 48 270640 Co-64 5.43410E-10 1.80460E-09 270640 + 49 270650 Co-65 2.20430E-09 3.09150E-09 270650 + 50 270660 Co-66 3.29970E-09 3.94670E-09 270660 + 51 270670 Co-67 4.73310E-09 4.87540E-09 270670 + 52 270680 Co-68 1.18680E-09 1.72420E-09 270680 + 53 270681 Co-68m 1.04700E-09 1.07470E-09 270681 + 54 270690 Co-69 1.30640E-09 1.30840E-09 270690 + 55 270700 Co-70 1.15750E-10 1.15750E-10 270700 + 56 270701 Co-70m 1.15750E-10 1.15750E-10 270701 + 57 270710 Co-71 3.44800E-11 3.44800E-11 270710 + 58 270720 Co-72 1.63270E-12 1.63270E-12 270720 + 59 280630 Ni-63 1.01840E-12 1.00780E-09 280630 + 60 280640 Ni-64 2.56590E-11 1.83030E-09 28064.82c + 61 280650 Ni-65 2.32300E-10 3.32380E-09 280650 + 62 280660 Ni-66 2.07200E-09 6.01870E-09 280660 + 63 280670 Ni-67 5.71840E-09 1.05940E-08 280670 + 64 280680 Ni-68 1.54880E-08 1.77630E-08 280680 + 65 280690 Ni-69 9.58150E-09 1.08770E-08 280690 + 66 280691 Ni-69m 9.58150E-09 9.58150E-09 280691 + 67 280700 Ni-70 2.32170E-08 2.34480E-08 280700 + 68 280710 Ni-71 8.75500E-09 8.78950E-09 280710 + 69 280720 Ni-72 3.26230E-09 3.26390E-09 280720 + 70 280730 Ni-73 4.34260E-10 4.34260E-10 280730 + 71 280740 Ni-74 4.66570E-11 4.66570E-11 280740 + 72 280750 Ni-75 1.72920E-12 1.72920E-12 280750 + 73 290660 Cu-66 1.97430E-11 6.03850E-09 290660 + 74 290670 Cu-67 3.73630E-10 1.09680E-08 290670 + 75 290680 Cu-68 6.42500E-10 1.96690E-08 290680 + 76 290681 Cu-68m 1.50490E-09 1.50490E-09 290681 + 77 290690 Cu-69 1.52740E-08 3.57320E-08 290690 + 78 290700 Cu-70 2.70780E-09 1.84450E-08 290700 + 79 290701 Cu-70m 3.01660E-08 3.14740E-08 290701 + 80 290702 Cu-70m 2.70780E-09 2.61560E-08 290702 + 81 290710 Cu-71 7.97410E-08 8.85300E-08 290710 + 82 290720 Cu-72 6.61090E-08 6.93730E-08 290720 + 83 290730 Cu-73 6.29640E-08 6.33980E-08 290730 + 84 290740 Cu-74 1.76980E-08 1.77450E-08 290740 + 85 290750 Cu-75 5.24960E-09 5.25130E-09 290750 + 86 290760 Cu-76 2.52010E-10 2.52010E-10 290760 + 87 290761 Cu-76m 2.52010E-10 2.52010E-10 290761 + 88 290770 Cu-77 4.01890E-11 4.01890E-11 290770 + 89 290780 Cu-78 1.00430E-12 1.00430E-12 290780 + 90 300680 Zn-68 2.53270E-11 1.99350E-08 300680 + 91 300690 Zn-69 8.25480E-11 3.61720E-08 300690 + 92 300691 Zn-69m 3.57000E-10 3.57000E-10 300691 + 93 300700 Zn-70 6.68180E-09 6.57120E-08 300700 + 94 300710 Zn-71 5.69940E-09 9.42300E-08 300710 + 95 300711 Zn-71m 2.46490E-08 2.46490E-08 300711 + 96 300720 Zn-72 1.41870E-07 2.11240E-07 300720 + 97 300730 Zn-73 2.61950E-08 2.26830E-07 300730 + 98 300731 Zn-73m 3.58090E-08 1.37240E-07 300731 + 99 300732 Zn-73m 2.02860E-07 2.02860E-07 300732 + 100 300740 Zn-74 4.63240E-07 4.81170E-07 300740 + 101 300750 Zn-75 3.21290E-07 3.26360E-07 300750 + 102 300760 Zn-76 2.29530E-07 2.30030E-07 300760 + 103 300770 Zn-77 4.26940E-08 4.59980E-08 300770 + 104 300771 Zn-77m 6.52670E-09 6.52670E-09 300771 + 105 300780 Zn-78 9.22850E-09 9.22950E-09 300780 + 106 300790 Zn-79 6.87760E-10 6.87760E-10 300790 + 107 300800 Zn-80 4.67790E-11 4.67790E-11 300800 + 108 310700 Ga-70 1.53430E-11 1.53430E-11 310700 + 109 310710 Ga-71 5.17470E-10 1.19400E-07 310710 + 110 310720 Ga-72 5.06950E-09 2.16880E-07 310720 + 111 310721 Ga-72m 5.70800E-10 7.60950E-09 310721 + 112 310730 Ga-73 6.53360E-08 3.93590E-07 310730 + 113 310740 Ga-74 1.11820E-07 5.56570E-07 310740 + 114 310741 Ga-74m 1.11820E-07 5.92990E-07 310741 + 115 310750 Ga-75 8.75140E-07 1.20150E-06 310750 + 116 310760 Ga-76 1.27020E-06 1.50020E-06 310760 + 117 310770 Ga-77 1.78270E-06 1.83200E-06 310770 + 118 310780 Ga-78 8.17510E-07 8.26750E-07 310780 + 119 310790 Ga-79 4.68400E-07 4.69080E-07 310790 + 120 310800 Ga-80 8.82230E-08 8.82700E-08 310800 + 121 310810 Ga-81 7.77120E-09 7.77120E-09 310810 + 122 310820 Ga-82 4.64710E-10 4.64710E-10 310820 + 123 310830 Ga-83 2.69720E-11 2.69720E-11 310830 + 124 320720 Ge-72 1.55610E-11 2.16900E-07 32072.82c + 125 320730 Ge-73 3.82380E-10 3.94070E-07 32073.82c + 126 320731 Ge-73m 8.84140E-11 3.87900E-07 320731 + 127 320740 Ge-74 1.15010E-08 7.16320E-07 32074.82c + 128 320750 Ge-75 1.32390E-08 1.30130E-06 320750 + 129 320751 Ge-75m 8.66010E-08 1.34660E-07 320751 + 130 320760 Ge-76 8.59150E-07 2.35940E-06 32076.82c + 131 320770 Ge-77 2.00990E-06 2.41640E-06 320770 + 132 320771 Ge-77m 3.07260E-07 2.13920E-06 320771 + 133 320780 Ge-78 6.11910E-06 6.94630E-06 320780 + 134 320790 Ge-79 1.44920E-06 2.29640E-06 320790 + 135 320791 Ge-79m 9.47980E-06 9.48050E-06 320791 + 136 320800 Ge-80 2.28360E-05 2.29250E-05 320800 + 137 320810 Ge-81 1.75800E-06 1.76580E-06 320810 + 138 320811 Ge-81m 4.06490E-07 4.09770E-07 320811 + 139 320820 Ge-82 1.02210E-06 1.02250E-06 320820 + 140 320830 Ge-83 1.59600E-07 1.59620E-07 320830 + 141 320840 Ge-84 1.68060E-08 1.68060E-08 320840 + 142 320850 Ge-85 5.34410E-10 5.34410E-10 320850 + 143 330740 As-74 6.02040E-12 6.02040E-12 330740 + 144 330750 As-75 9.62530E-11 1.30180E-06 33075.82c + 145 330751 As-75m 3.14910E-10 3.55310E-10 330751 + 146 330760 As-76 8.93950E-09 8.93950E-09 330760 + 147 330770 As-77 1.64380E-07 4.31350E-06 330770 + 148 330780 As-78 9.15760E-07 7.86200E-06 330780 + 149 330790 As-79 3.64280E-06 1.50400E-05 330790 + 150 330800 As-80 3.80550E-06 2.67310E-05 330800 + 151 330810 As-81 2.49140E-05 2.70850E-05 330810 + 152 330820 As-82 5.48500E-06 6.50750E-06 330820 + 153 330821 As-82m 1.65520E-05 1.65520E-05 330821 + 154 330830 As-83 1.93320E-05 1.94930E-05 330830 + 155 330840 As-84 3.91970E-06 3.92720E-06 330840 + 156 330841 As-84m 3.91970E-06 3.92720E-06 330841 + 157 330850 As-85 1.77370E-06 1.77420E-06 330850 + 158 330860 As-86 1.89230E-07 1.89230E-07 330860 + 159 330870 As-87 1.45780E-08 1.45780E-08 330870 + 160 330880 As-88 3.30210E-10 3.30210E-10 330880 + 161 340760 Se-76 5.47260E-12 8.94500E-09 34076.82c + 162 340770 Se-77 3.68010E-11 4.31380E-06 34077.82c + 163 340771 Se-77m 2.40730E-10 2.40730E-10 340771 + 164 340780 Se-78 1.18200E-08 7.87380E-06 34078.82c + 165 340790 Se-79 1.73900E-07 1.52330E-05 34079.82c + 166 340791 Se-79m 2.65850E-08 1.47110E-05 340791 + 167 340800 Se-80 3.80530E-06 3.05370E-05 34080.82c + 168 340810 Se-81 9.43750E-07 3.41990E-05 340810 + 169 340811 Se-81m 6.17360E-06 7.14590E-06 340811 + 170 340820 Se-82 5.13990E-05 7.44590E-05 34082.82c + 171 340830 Se-83 1.09880E-04 1.16910E-04 340830 + 172 340831 Se-83m 2.54080E-05 3.78890E-05 340831 + 173 340840 Se-84 2.00050E-04 2.08280E-04 340840 + 174 340850 Se-85 1.67070E-04 1.68520E-04 340850 + 175 340860 Se-86 1.25330E-04 1.25460E-04 340860 + 176 340870 Se-87 4.81130E-05 4.81250E-05 340870 + 177 340880 Se-88 9.22950E-06 9.22980E-06 340880 + 178 340890 Se-89 1.86090E-07 1.86090E-07 340890 + 179 340900 Se-90 8.13220E-09 8.13220E-09 340900 + 180 350780 Br-78 1.33900E-12 1.33900E-12 350780 + 181 350790 Br-79 4.42240E-11 8.42700E-09 35079.82c + 182 350791 Br-79m 1.44690E-10 1.44690E-10 350791 + 183 350800 Br-80 2.03220E-09 8.16470E-09 350800 + 184 350801 Br-80m 6.13250E-09 6.13250E-09 350801 + 185 350810 Br-81 1.62870E-07 3.43660E-05 35081.82c + 186 350820 Br-82 1.57550E-06 2.23200E-06 350820 + 187 350821 Br-82m 6.72630E-07 6.72630E-07 350821 + 188 350830 Br-83 1.93220E-05 1.74120E-04 350830 + 189 350840 Br-84 4.11220E-05 2.49410E-04 350840 + 190 350841 Br-84m 4.11220E-05 4.11220E-05 350841 + 191 350850 Br-85 2.61940E-04 4.30460E-04 350850 + 192 350860 Br-86 4.59570E-04 5.85030E-04 350860 + 193 350870 Br-87 5.62380E-04 6.10600E-04 350870 + 194 350880 Br-88 3.80610E-04 3.89760E-04 350880 + 195 350890 Br-89 2.03390E-04 2.03560E-04 350890 + 196 350900 Br-90 4.73780E-05 4.73860E-05 350900 + 197 350910 Br-91 1.83050E-06 1.83050E-06 350910 + 198 350920 Br-92 6.02220E-08 6.02220E-08 350920 + 199 350930 Br-93 2.25980E-09 2.25980E-09 350930 + 200 360800 Kr-80 1.14100E-12 7.48820E-09 36080.82c + 201 360810 Kr-81 5.33100E-11 6.14600E-11 360810 + 202 360811 Kr-81m 8.14960E-12 8.14960E-12 360811 + 203 360820 Kr-82 6.81200E-09 2.25490E-06 36082.82c + 204 360830 Kr-83 1.96180E-07 1.74360E-04 36083.82c + 205 360831 Kr-83m 4.53610E-08 1.74010E-04 360831 + 206 360840 Kr-84 1.17550E-05 3.02290E-04 36084.82c + 207 360850 Kr-85 6.12120E-05 1.56910E-04 36085.82c + 208 360851 Kr-85m 1.41540E-05 4.43910E-04 360851 + 209 360860 Kr-86 5.31670E-04 1.13200E-03 36086.82c + 210 360870 Kr-87 1.26180E-03 1.88320E-03 360870 + 211 360880 Kr-88 2.58470E-03 2.97710E-03 360880 + 212 360890 Kr-89 3.06250E-03 3.24900E-03 360890 + 213 360900 Kr-90 2.43010E-03 2.46620E-03 360900 + 214 360910 Kr-91 1.14730E-03 1.14880E-03 360910 + 215 360920 Kr-92 3.85330E-04 3.85370E-04 360920 + 216 360930 Kr-93 1.00640E-04 1.00640E-04 360930 + 217 360940 Kr-94 1.91650E-05 1.91650E-05 360940 + 218 360950 Kr-95 2.52060E-08 2.52060E-08 360950 + 219 370830 Rb-83 1.42200E-11 4.85480E-11 370830 + 220 370831 Rb-83m 3.43280E-11 3.43280E-11 370831 + 221 370840 Rb-84 1.19340E-09 3.34000E-09 370840 + 222 370841 Rb-84m 2.14660E-09 2.14660E-09 370841 + 223 370850 Rb-85 1.93970E-07 5.06020E-04 37085.82c + 224 370860 Rb-86 1.48930E-06 4.16820E-06 37086.82c + 225 370861 Rb-86m 2.67890E-06 2.67890E-06 370861 + 226 370870 Rb-87 9.99620E-05 1.98310E-03 37087.82c + 227 370880 Rb-88 5.05820E-04 3.48290E-03 370880 + 228 370890 Rb-89 1.42260E-03 4.67160E-03 370890 + 229 370900 Rb-90 2.84120E-04 2.50170E-03 370900 + 230 370901 Rb-90m 2.52340E-03 2.84600E-03 370901 + 231 370910 Rb-91 4.17750E-03 5.32630E-03 370910 + 232 370920 Rb-92 3.14610E-03 3.53150E-03 370920 + 233 370930 Rb-93 2.80840E-03 2.90920E-03 370930 + 234 370940 Rb-94 1.06170E-03 1.08070E-03 370940 + 235 370950 Rb-95 3.54200E-04 3.54220E-04 370950 + 236 370960 Rb-96 1.58140E-05 2.37200E-05 370960 + 237 370961 Rb-96m 1.58140E-05 1.58140E-05 370961 + 238 370970 Rb-97 2.59590E-07 2.59590E-07 370970 + 239 370980 Rb-98 1.97580E-09 1.97580E-09 370980 + 240 370981 Rb-98m 1.97580E-09 1.97580E-09 370981 + 241 380850 Sr-85 1.17310E-11 1.40800E-11 380850 + 242 380851 Sr-85m 2.71260E-12 2.71260E-12 380851 + 243 380860 Sr-86 3.19460E-09 4.17120E-06 38086.82c + 244 380870 Sr-87 3.54800E-06 4.36590E-06 38087.82c + 245 380871 Sr-87m 8.20390E-07 8.20390E-07 380871 + 246 380880 Sr-88 3.68380E-05 3.51970E-03 38088.82c + 247 380890 Sr-89 2.42280E-04 4.91390E-03 38089.82c + 248 380900 Sr-90 1.48900E-03 6.76270E-03 38090.82c + 249 380910 Sr-91 3.51420E-03 8.84050E-03 380910 + 250 380920 Sr-92 7.60180E-03 1.11740E-02 380920 + 251 380930 Sr-93 1.21060E-02 1.50840E-02 380930 + 252 380940 Sr-94 1.46260E-02 1.56280E-02 380940 + 253 380950 Sr-95 9.77040E-03 1.00970E-02 380950 + 254 380960 Sr-96 5.12310E-03 5.15160E-03 380960 + 255 380970 Sr-97 1.62810E-03 1.62830E-03 380970 + 256 380980 Sr-98 4.32540E-04 4.32540E-04 380980 + 257 380990 Sr-99 3.64420E-05 3.64420E-05 380990 + 258 381000 Sr-100 5.76020E-08 5.76020E-08 381000 + 259 390880 Y-88 5.22780E-10 9.08070E-10 390880 + 260 390881 Y-88m 3.85290E-10 3.85290E-10 390881 + 261 390890 Y-89 1.47360E-08 4.91400E-03 39089.82c + 262 390891 Y-89m 6.37290E-08 5.37380E-07 390891 + 263 390900 Y-90 1.95450E-06 6.76740E-03 39090.82c + 264 390901 Y-90m 2.77340E-06 2.77340E-06 390901 + 265 390910 Y-91 2.97360E-05 8.99880E-03 39091.82c + 266 390911 Y-91m 1.28600E-04 5.32990E-03 390911 + 267 390920 Y-92 5.52990E-04 1.17270E-02 390920 + 268 390930 Y-93 3.79000E-04 1.79420E-02 390930 + 269 390931 Y-93m 2.47920E-03 6.25380E-03 390931 + 270 390940 Y-94 6.98200E-03 2.26100E-02 390940 + 271 390950 Y-95 1.50370E-02 2.51340E-02 390950 + 272 390960 Y-96 5.76220E-03 1.09140E-02 390960 + 273 390961 Y-96m 1.03650E-02 1.03650E-02 390961 + 274 390970 Y-97 2.64950E-03 4.11330E-03 390970 + 275 390971 Y-97m 9.03050E-03 1.12140E-02 390971 + 276 390972 Y-97m 2.42660E-03 2.42660E-03 390972 + 277 390980 Y-98 1.29460E-03 1.72710E-03 390980 + 278 390981 Y-98m 5.44460E-03 5.44460E-03 390981 + 279 390990 Y-99 2.92320E-03 2.95960E-03 390990 + 280 391000 Y-100 3.58700E-04 3.58750E-04 391000 + 281 391001 Y-100m 3.58700E-04 3.58700E-04 391001 + 282 391010 Y-101 1.61530E-04 1.61530E-04 391010 + 283 391020 Y-102 1.52720E-07 1.52720E-07 391020 + 284 391021 Y-102m 1.52720E-07 1.52720E-07 391021 + 285 391030 Y-103 7.48490E-09 7.48490E-09 391030 + 286 400900 Zr-90 4.88170E-11 6.76740E-03 40090.82c + 287 400901 Zr-90m 2.05300E-10 2.55230E-10 400901 + 288 400910 Zr-91 2.21940E-08 8.99880E-03 40091.82c + 289 400920 Zr-92 2.24420E-05 1.17490E-02 40092.82c + 290 400930 Zr-93 2.38460E-04 1.81800E-02 40093.82c + 291 400940 Zr-94 1.70080E-03 2.43110E-02 40094.82c + 292 400950 Zr-95 4.92530E-03 3.00600E-02 40095.82c + 293 400960 Zr-96 1.64090E-02 3.76970E-02 40096.82c + 294 400970 Zr-97 2.50220E-02 4.09390E-02 400970 + 295 400980 Zr-98 3.92780E-02 4.63080E-02 400980 + 296 400990 Zr-99 2.77740E-02 3.06870E-02 400990 + 297 401000 Zr-100 2.09120E-02 2.16260E-02 401000 + 298 401010 Zr-101 7.87670E-03 8.03820E-03 401010 + 299 401020 Zr-102 3.11350E-03 3.11380E-03 401020 + 300 401030 Zr-103 6.61540E-04 6.61550E-04 401030 + 301 401040 Zr-104 1.11360E-04 1.11360E-04 401040 + 302 401050 Zr-105 5.52380E-08 5.52380E-08 401050 + 303 410930 Nb-93 5.50650E-09 6.77970E-09 41093.82c + 304 410931 Nb-93m 1.27320E-09 1.27320E-09 410931 + 305 410940 Nb-94 1.95430E-07 3.32470E-07 41094.82c + 306 410941 Nb-94m 1.37730E-07 1.37730E-07 410941 + 307 410950 Nb-95 9.91290E-05 3.01620E-02 41095.82c + 308 410951 Nb-95m 2.29210E-05 3.47670E-04 410951 + 309 410960 Nb-96 5.83370E-04 5.83370E-04 410960 + 310 410970 Nb-97 2.39670E-03 4.38900E-02 410970 + 311 410971 Nb-97m 5.54180E-04 3.94660E-02 410971 + 312 410980 Nb-98 1.95390E-03 4.82620E-02 410980 + 313 410981 Nb-98m 5.89610E-03 5.89610E-03 410981 + 314 410990 Nb-99 1.52010E-02 3.48910E-02 410990 + 315 410991 Nb-99m 3.51490E-03 1.48070E-02 410991 + 316 411000 Nb-100 5.06430E-03 2.66900E-02 411000 + 317 411001 Nb-100m 2.12990E-02 2.12990E-02 411001 + 318 411010 Nb-101 3.35380E-02 4.15760E-02 411010 + 319 411020 Nb-102 1.10550E-02 1.41690E-02 411020 + 320 411021 Nb-102m 1.10550E-02 1.10550E-02 411021 + 321 411030 Nb-103 1.52860E-02 1.59470E-02 411030 + 322 411040 Nb-104 2.64090E-03 2.75230E-03 411040 + 323 411041 Nb-104m 2.64090E-03 2.64090E-03 411041 + 324 411050 Nb-105 1.69100E-03 1.69100E-03 411050 + 325 411060 Nb-106 1.69480E-04 1.69480E-04 411060 + 326 411070 Nb-107 2.56930E-07 2.56930E-07 411070 + 327 411080 Nb-108 2.00270E-09 2.00270E-09 411080 + 328 420950 Mo-95 8.69180E-10 3.01820E-02 42095.82c + 329 420960 Mo-96 1.58020E-05 5.99170E-04 42096.82c + 330 420970 Mo-97 1.10800E-04 4.40010E-02 42097.82c + 331 420980 Mo-98 1.03210E-03 5.51900E-02 42098.82c + 332 420990 Mo-99 3.49540E-03 5.28980E-02 42099.82c + 333 421000 Mo-100 1.32930E-02 6.12820E-02 42100.82c + 334 421010 Mo-101 2.49490E-02 6.65250E-02 421010 + 335 421020 Mo-102 4.58160E-02 7.10410E-02 421020 + 336 421030 Mo-103 4.86650E-02 6.46160E-02 421030 + 337 421040 Mo-104 4.94870E-02 5.49060E-02 421040 + 338 421050 Mo-105 2.85740E-02 3.02440E-02 421050 + 339 421060 Mo-106 1.13180E-02 1.14800E-02 421060 + 340 421070 Mo-107 2.64480E-03 2.64500E-03 421070 + 341 421080 Mo-108 5.08600E-04 5.08600E-04 421080 + 342 421090 Mo-109 6.77350E-05 6.77350E-05 421090 + 343 421100 Mo-110 1.53230E-08 1.53230E-08 421100 + 344 430980 Tc-98 1.84410E-08 1.84410E-08 430980 + 345 430990 Tc-99 1.47900E-05 5.29150E-02 43099.82c + 346 430991 Tc-99m 3.41980E-06 4.65850E-02 430991 + 347 431000 Tc-100 1.83740E-04 1.83740E-04 431000 + 348 431010 Tc-101 1.36260E-03 6.78880E-02 431010 + 349 431020 Tc-102 2.22860E-03 7.32690E-02 431020 + 350 431021 Tc-102m 2.22860E-03 2.22860E-03 431021 + 351 431030 Tc-103 1.47570E-02 7.93720E-02 431030 + 352 431040 Tc-104 2.43060E-02 7.92120E-02 431040 + 353 431050 Tc-105 4.32140E-02 7.34580E-02 431050 + 354 431060 Tc-106 3.20440E-02 4.35240E-02 431060 + 355 431070 Tc-107 2.46160E-02 2.72610E-02 431070 + 356 431080 Tc-108 9.80950E-03 1.03180E-02 431080 + 357 431090 Tc-109 2.98570E-03 3.05310E-03 431090 + 358 431100 Tc-110 7.03020E-04 7.03030E-04 431100 + 359 431110 Tc-111 1.20650E-04 1.20650E-04 431110 + 360 431120 Tc-112 2.67010E-08 2.67010E-08 431120 + 361 431130 Tc-113 1.55110E-10 1.55110E-10 431130 + 362 441000 Ru-100 4.60820E-09 1.83740E-04 44100.82c + 363 441010 Ru-101 1.07580E-05 6.78990E-02 44101.82c + 364 441020 Ru-102 3.16680E-04 7.58150E-02 44102.82c + 365 441030 Ru-103 3.04150E-04 8.04110E-02 44103.82c + 366 441031 Ru-103m 7.34250E-04 7.34250E-04 441031 + 367 441040 Ru-104 5.29230E-03 8.45040E-02 44104.82c + 368 441050 Ru-105 1.30460E-02 8.65040E-02 44105.82c + 369 441060 Ru-106 2.32160E-02 6.67400E-02 44106.82c + 370 441070 Ru-107 2.52550E-02 5.25160E-02 441070 + 371 441080 Ru-108 2.72210E-02 3.75420E-02 441080 + 372 441090 Ru-109 1.51760E-02 1.82270E-02 441090 + 373 441100 Ru-110 1.00240E-02 1.07270E-02 441100 + 374 441110 Ru-111 3.73700E-03 3.85760E-03 441110 + 375 441120 Ru-112 7.16540E-04 7.16570E-04 441120 + 376 441130 Ru-113 5.22200E-05 7.83300E-05 441130 + 377 441131 Ru-113m 5.22200E-05 5.22200E-05 441131 + 378 441140 Ru-114 3.71590E-08 3.71590E-08 441140 + 379 441150 Ru-115 7.89050E-11 7.89050E-11 441150 + 380 451030 Rh-103 5.29340E-09 8.04110E-02 45103.82c + 381 451031 Rh-103m 3.46270E-08 7.94480E-02 451031 + 382 451040 Rh-104 3.07840E-06 1.23560E-05 451040 + 383 451041 Rh-104m 9.28960E-06 9.28960E-06 451041 + 384 451050 Rh-105 2.15900E-04 8.67530E-02 45105.82c + 385 451051 Rh-105m 3.30040E-05 2.45900E-02 451051 + 386 451060 Rh-106 2.78900E-04 6.70190E-02 451060 + 387 451061 Rh-106m 6.53250E-04 6.53250E-04 451061 + 388 451070 Rh-107 2.66770E-03 5.51840E-02 451070 + 389 451080 Rh-108 1.22770E-03 3.87700E-02 451080 + 390 451081 Rh-108m 3.70480E-03 3.70480E-03 451081 + 391 451090 Rh-109 7.60710E-03 2.58340E-02 451090 + 392 451100 Rh-110 8.29830E-03 1.90250E-02 451100 + 393 451101 Rh-110m 2.21520E-04 2.21520E-04 451101 + 394 451110 Rh-111 8.04850E-03 1.19060E-02 451110 + 395 451120 Rh-112 2.51080E-03 3.22740E-03 451120 + 396 451121 Rh-112m 2.51080E-03 2.51080E-03 451121 + 397 451130 Rh-113 1.03810E-03 1.14250E-03 451130 + 398 451140 Rh-114 1.55700E-04 1.55740E-04 451140 + 399 451141 Rh-114m 1.55700E-04 1.55700E-04 451141 + 400 451150 Rh-115 3.58250E-07 3.58330E-07 451150 + 401 451160 Rh-116 2.66320E-09 2.66320E-09 451160 + 402 451161 Rh-116m 6.23800E-09 6.23800E-09 451161 + 403 451170 Rh-117 7.15980E-11 7.15980E-11 451170 + 404 451180 Rh-118 2.36790E-12 2.36790E-12 451180 + 405 461050 Pd-105 5.02170E-09 8.67530E-02 46105.82c + 406 461060 Pd-106 3.62640E-05 6.77080E-02 46106.82c + 407 461070 Pd-107 2.43130E-05 5.52540E-02 46107.82c + 408 461071 Pd-107m 4.56920E-05 4.56920E-05 461071 + 409 461080 Pd-108 2.63400E-04 4.27380E-02 46108.82c + 410 461090 Pd-109 2.40900E-04 2.65280E-02 461090 + 411 461091 Pd-109m 4.52740E-04 1.33700E-02 461091 + 412 461100 Pd-110 1.65050E-03 2.08970E-02 46110.82c + 413 461110 Pd-111 6.55490E-04 1.34480E-02 461110 + 414 461111 Pd-111m 1.23190E-03 1.27950E-03 461111 + 415 461120 Pd-112 2.67010E-03 8.40830E-03 461120 + 416 461130 Pd-113 3.51740E-04 2.34340E-03 461130 + 417 461131 Pd-113m 8.49160E-04 8.49160E-04 461131 + 418 461140 Pd-114 7.93180E-04 1.10460E-03 461140 + 419 461150 Pd-115 3.75530E-05 4.35100E-05 461150 + 420 461151 Pd-115m 7.05770E-05 7.06280E-05 461151 + 421 461160 Pd-116 3.76820E-05 3.76910E-05 461160 + 422 461170 Pd-117 4.45130E-08 1.28240E-07 461170 + 423 461171 Pd-117m 8.36570E-08 8.36570E-08 461171 + 424 461180 Pd-118 3.26450E-08 3.26470E-08 461180 + 425 461190 Pd-119 1.06110E-09 1.06110E-09 461190 + 426 461200 Pd-120 3.33930E-11 3.33930E-11 461200 + 427 461220 Pd-122 1.40380E-08 1.40380E-08 461220 + 428 461230 Pd-123 1.90840E-10 1.90840E-10 461230 + 429 461240 Pd-124 2.27590E-11 2.27590E-11 461240 + 430 471080 Ag-108 5.39280E-09 6.49170E-09 471080 + 431 471081 Ag-108m 1.26310E-08 1.26310E-08 471081 + 432 471090 Ag-109 4.48290E-06 2.65610E-02 47109.82c + 433 471091 Ag-109m 2.93250E-05 2.65440E-02 471091 + 434 471100 Ag-110 4.66540E-06 4.81400E-06 471100 + 435 471101 Ag-110m 1.09280E-05 1.09280E-05 47510.82c + 436 471110 Ag-111 1.58910E-05 1.38450E-02 47111.82c + 437 471111 Ag-111m 1.03950E-04 1.37030E-02 471111 + 438 471120 Ag-112 1.04670E-04 8.51290E-03 471120 + 439 471130 Ag-113 2.06260E-05 1.64260E-03 471130 + 440 471131 Ag-113m 1.34920E-04 2.37890E-03 471131 + 441 471140 Ag-114 2.95410E-05 1.25840E-03 471140 + 442 471141 Ag-114m 1.24240E-04 1.24240E-04 471141 + 443 471150 Ag-115 3.58100E-06 5.63750E-05 471150 + 444 471151 Ag-115m 2.34250E-05 1.00150E-04 471151 + 445 471160 Ag-116 1.69030E-05 5.69700E-05 471160 + 446 471161 Ag-116m 3.95920E-05 3.95920E-05 471161 + 447 471170 Ag-117 8.68970E-07 1.27800E-06 471170 + 448 471171 Ag-117m 5.68430E-06 5.74840E-06 471171 + 449 471180 Ag-118 7.99640E-07 2.20830E-06 471180 + 450 471181 Ag-118m 3.36300E-06 3.36760E-06 471181 + 451 471190 Ag-119 1.39750E-07 1.40280E-07 471190 + 452 471191 Ag-119m 9.14150E-07 9.14680E-07 471191 + 453 471200 Ag-120 3.83120E-08 5.84500E-08 471200 + 454 471201 Ag-120m 5.43640E-08 5.43800E-08 471201 + 455 471210 Ag-121 4.39080E-09 4.39080E-09 471210 + 456 471220 Ag-122 1.08950E-06 1.10350E-06 471220 + 457 471221 Ag-122m 9.81400E-07 9.81400E-07 471221 + 458 471230 Ag-123 2.23340E-07 2.23530E-07 471230 + 459 471240 Ag-124 4.08440E-08 5.92630E-08 471240 + 460 471241 Ag-124m 3.67920E-08 3.67920E-08 471241 + 461 471250 Ag-125 2.37730E-08 2.37730E-08 471250 + 462 471260 Ag-126 1.45280E-09 1.45280E-09 471260 + 463 471270 Ag-127 1.05390E-10 1.05390E-10 471270 + 464 481100 Cd-110 1.53230E-09 1.55800E-05 48110.82c + 465 481110 Cd-111 1.24780E-08 1.39130E-02 48111.82c + 466 481111 Cd-111m 4.08240E-08 4.08240E-08 481111 + 467 481120 Cd-112 1.41590E-06 8.51440E-03 48112.82c + 468 481130 Cd-113 1.31490E-06 2.47200E-03 48113.82c + 469 481131 Cd-113m 4.30190E-06 3.27000E-05 481131 + 470 481140 Cd-114 3.49110E-05 1.29330E-03 48114.82c + 471 481150 Cd-115 6.31980E-06 1.36260E-04 481150 + 472 481151 Cd-115m 2.06760E-05 2.62280E-05 48515.82c + 473 481160 Cd-116 4.06920E-05 1.34880E-04 48116.82c + 474 481170 Cd-117 4.54130E-06 9.66800E-06 481170 + 475 481171 Cd-117m 1.48580E-05 1.64120E-05 481171 + 476 481180 Cd-118 2.49820E-05 2.91770E-05 481180 + 477 481190 Cd-119 6.86380E-06 7.84860E-06 481190 + 478 481191 Cd-119m 1.65700E-05 1.66400E-05 481191 + 479 481200 Cd-120 1.44870E-05 1.45800E-05 481200 + 480 481210 Cd-121 5.19340E-07 5.23270E-07 481210 + 481 481211 Cd-121m 1.25380E-06 1.25420E-06 481211 + 482 481220 Cd-122 2.39270E-05 2.60120E-05 481220 + 483 481230 Cd-123 1.68420E-06 1.86710E-06 481230 + 484 481231 Cd-123m 4.06580E-06 4.10650E-06 481231 + 485 481240 Cd-124 1.43720E-05 1.44500E-05 481240 + 486 481250 Cd-125 3.40090E-06 3.41280E-06 481250 + 487 481251 Cd-125m 8.21010E-06 8.22200E-06 481251 + 488 481260 Cd-126 5.73440E-06 5.73590E-06 481260 + 489 481270 Cd-127 1.01680E-06 1.01690E-06 481270 + 490 481280 Cd-128 8.46280E-08 8.46280E-08 481280 + 491 481290 Cd-129 7.44610E-10 7.44610E-10 481290 + 492 481291 Cd-129m 1.79760E-09 1.79760E-09 481291 + 493 491130 In-113 1.25980E-09 3.26560E-05 49113.82c + 494 491131 In-113m 2.91300E-10 2.91300E-10 491131 + 495 491140 In-114 6.66600E-09 2.60750E-08 491140 + 496 491141 In-114m 1.02170E-08 2.01130E-08 491141 + 497 491142 In-114m 9.89600E-09 9.89600E-09 491142 + 498 491150 In-115 8.65800E-08 1.55780E-04 49115.82c + 499 491151 In-115m 2.00190E-08 1.36280E-04 491151 + 500 491160 In-116 1.49430E-07 1.49430E-07 491160 + 501 491161 In-116m 2.29030E-07 4.50860E-07 491161 + 502 491162 In-116m 2.21830E-07 2.21830E-07 491162 + 503 491170 In-117 9.11130E-07 2.22720E-05 491170 + 504 491171 In-117m 2.10670E-07 9.32080E-06 491171 + 505 491180 In-118 6.21600E-06 3.53930E-05 491180 + 506 491181 In-118m 9.52760E-06 1.86260E-05 491181 + 507 491182 In-118m 9.22790E-06 9.22790E-06 491182 + 508 491190 In-119 2.18490E-05 3.98980E-05 491190 + 509 491191 In-119m 5.05200E-06 1.21730E-05 491191 + 510 491200 In-120 1.07590E-05 2.53380E-05 491200 + 511 491201 In-120m 1.07590E-05 1.07590E-05 491201 + 512 491202 In-120m 1.07590E-05 1.07590E-05 491202 + 513 491210 In-121 3.18220E-05 3.33450E-05 491210 + 514 491211 In-121m 7.35800E-06 7.70500E-06 491211 + 515 491220 In-122 5.91000E-06 3.19220E-05 491220 + 516 491221 In-122m 4.19300E-06 4.19300E-06 491221 + 517 491222 In-122m 4.19300E-06 4.19300E-06 491222 + 518 491230 In-123 6.08780E-06 1.07230E-05 491230 + 519 491231 In-123m 1.40760E-06 2.74650E-06 491231 + 520 491240 In-124 1.18340E-05 2.62840E-05 491240 + 521 491241 In-124m 1.06600E-05 1.06600E-05 491241 + 522 491250 In-125 6.47530E-05 7.46080E-05 491250 + 523 491251 In-125m 1.49720E-05 1.67520E-05 491251 + 524 491260 In-126 8.79640E-05 9.37000E-05 491260 + 525 491261 In-126m 7.92360E-05 7.92360E-05 491261 + 526 491270 In-127 1.88020E-04 1.88020E-04 491270 + 527 491271 In-127m 4.34760E-05 4.44930E-05 491271 + 528 491280 In-128 2.58010E-05 3.63890E-05 491280 + 529 491281 In-128m 1.05030E-05 1.05870E-05 491281 + 530 491282 In-128m 3.27020E-05 3.27020E-05 491282 + 531 491290 In-129 7.91110E-05 7.91130E-05 491290 + 532 491291 In-129m 1.82920E-05 1.82930E-05 491291 + 533 491300 In-130 7.91580E-06 7.91580E-06 491300 + 534 491301 In-130m 8.84120E-06 8.84120E-06 491301 + 535 491302 In-130m 1.50430E-05 1.50430E-05 491302 + 536 491310 In-131 1.88050E-08 1.89960E-08 491310 + 537 491311 In-131m 1.88050E-08 1.88050E-08 491311 + 538 491312 In-131m 1.88050E-08 1.88050E-08 491312 + 539 491320 In-132 1.29790E-09 1.29790E-09 491320 + 540 501150 Sn-115 1.39240E-11 6.81430E-06 50115.82c + 541 501160 Sn-116 5.43410E-10 6.00820E-07 50116.82c + 542 501170 Sn-117 6.44220E-10 2.72050E-05 50117.82c + 543 501171 Sn-117m 2.10770E-09 7.79890E-08 501171 + 544 501180 Sn-118 1.58820E-07 5.43080E-05 50118.82c + 545 501190 Sn-119 2.76450E-07 5.25720E-05 50119.82c + 546 501191 Sn-119m 9.04450E-07 3.69490E-05 501191 + 547 501200 Sn-120 8.96810E-06 5.58560E-05 50120.82c + 548 501210 Sn-121 3.88830E-06 5.12840E-05 501210 + 549 501211 Sn-121m 9.38670E-06 1.31640E-05 501211 + 550 501220 Sn-122 1.42930E-05 5.46010E-05 50122.82c + 551 501230 Sn-123 9.75440E-06 1.05720E-05 50123.82c + 552 501231 Sn-123m 4.04060E-06 1.66920E-05 501231 + 553 501240 Sn-124 4.49660E-05 8.19100E-05 50124.82c + 554 501250 Sn-125 1.50140E-04 1.62740E-04 50125.82c + 555 501251 Sn-125m 6.21910E-05 1.40950E-04 501251 + 556 501260 Sn-126 6.95610E-04 8.68850E-04 50126.82c + 557 501270 Sn-127 1.53420E-03 1.60750E-03 501270 + 558 501271 Sn-127m 6.35500E-04 7.94430E-04 501271 + 559 501280 Sn-128 8.52780E-04 2.91930E-03 501280 + 560 501281 Sn-128m 1.99740E-03 2.03010E-03 501281 + 561 501290 Sn-129 6.32840E-04 7.21850E-04 501290 + 562 501291 Sn-129m 1.52780E-03 1.53620E-03 501291 + 563 501300 Sn-130 5.06190E-04 5.26860E-04 501300 + 564 501301 Sn-130m 1.18560E-03 1.19670E-03 501301 + 565 501310 Sn-131 1.55290E-04 1.55320E-04 501310 + 566 501311 Sn-131m 3.74880E-04 3.74900E-04 501311 + 567 501320 Sn-132 1.11010E-04 1.11010E-04 501320 + 568 501330 Sn-133 4.24810E-07 4.24810E-07 501330 + 569 501340 Sn-134 1.21130E-08 1.21130E-08 501340 + 570 511180 Sb-118 1.12570E-11 1.12570E-11 511180 + 571 511181 Sb-118m 1.59740E-11 1.59740E-11 511181 + 572 511190 Sb-119 1.23260E-09 1.62440E-09 511190 + 573 511191 Sb-119m 3.91810E-10 3.91810E-10 511191 + 574 511200 Sb-120 1.34700E-08 1.34700E-08 511200 + 575 511201 Sb-120m 1.91130E-08 1.91130E-08 511201 + 576 511210 Sb-121 3.50030E-07 5.45830E-05 51121.82c + 577 511220 Sb-122 1.07990E-11 2.30400E-11 511220 + 578 511221 Sb-122m 1.22410E-11 1.22410E-11 511221 + 579 511230 Sb-123 6.15710E-10 2.72650E-05 51123.82c + 580 511240 Sb-124 1.82830E-08 4.29480E-08 51124.82c + 581 511241 Sb-124m 1.39800E-08 3.28870E-08 511241 + 582 511242 Sb-124m 1.89070E-08 1.89070E-08 511242 + 583 511250 Sb-125 2.65260E-05 3.30220E-04 51125.82c + 584 511260 Sb-126 4.09440E-05 5.07260E-05 51126.82c + 585 511261 Sb-126m 3.02730E-05 6.98660E-05 511261 + 586 511262 Sb-126m 3.95920E-05 3.95920E-05 511262 + 587 511270 Sb-127 8.75240E-04 3.27710E-03 511270 + 588 511280 Sb-128 1.01980E-03 4.00180E-03 511280 + 589 511281 Sb-128m 1.74020E-03 1.74020E-03 511281 + 590 511290 Sb-129 4.50170E-03 6.51950E-03 511290 + 591 511291 Sb-129m 2.75090E-03 3.51900E-03 511291 + 592 511300 Sb-130 4.83980E-03 5.96500E-03 511300 + 593 511301 Sb-130m 4.83980E-03 5.43810E-03 511301 + 594 511310 Sb-131 1.14040E-02 1.19340E-02 511310 + 595 511320 Sb-132 3.04700E-03 3.15800E-03 511320 + 596 511321 Sb-132m 2.24570E-03 2.24570E-03 511321 + 597 511330 Sb-133 1.63340E-03 1.63380E-03 511330 + 598 511340 Sb-134 8.40000E-05 8.40100E-05 511340 + 599 511341 Sb-134m 1.96750E-04 1.96750E-04 511341 + 600 511350 Sb-135 2.46520E-05 2.46520E-05 511350 + 601 511360 Sb-136 8.92090E-08 8.92090E-08 511360 + 602 521200 Te-120 6.67850E-12 6.67850E-12 52120.82c + 603 521210 Te-121 4.54370E-11 1.77290E-10 521210 + 604 521211 Te-121m 1.48650E-10 1.48650E-10 521211 + 605 521240 Te-124 1.26430E-11 5.11830E-08 52124.82c + 606 521250 Te-125 5.89530E-10 3.30220E-04 52125.82c + 607 521251 Te-125m 1.92880E-09 7.38930E-05 521251 + 608 521260 Te-126 3.01080E-07 1.11110E-04 52126.82c + 609 521270 Te-127 4.20370E-05 3.40530E-03 521270 + 610 521271 Te-127m 1.01480E-04 6.41540E-04 52527.82c + 611 521280 Te-128 4.78840E-04 6.15820E-03 52128.82c + 612 521290 Te-129 8.51810E-04 1.01770E-02 521290 + 613 521291 Te-129m 2.05640E-03 6.05940E-03 52529.82c + 614 521300 Te-130 1.19860E-02 2.33890E-02 52130.82c + 615 521310 Te-131 7.06680E-03 2.18290E-02 521310 + 616 521311 Te-131m 1.70600E-02 1.80160E-02 521311 + 617 521320 Te-132 3.73790E-02 4.27830E-02 52132.82c + 618 521330 Te-133 7.41450E-03 1.19480E-02 521330 + 619 521331 Te-133m 1.78990E-02 1.81820E-02 521331 + 620 521340 Te-134 1.74520E-02 1.77360E-02 521340 + 621 521350 Te-135 4.52470E-03 4.54550E-03 521350 + 622 521360 Te-136 7.24080E-04 7.24150E-04 521360 + 623 521370 Te-137 1.15790E-04 1.15790E-04 521370 + 624 521380 Te-138 5.86070E-07 5.86070E-07 521380 + 625 521390 Te-139 5.22010E-09 5.22010E-09 521390 + 626 531260 I-126 2.30590E-11 2.30590E-11 531260 + 627 531270 I-127 4.84820E-09 3.42070E-03 53127.82c + 628 531280 I-128 2.71090E-07 2.71090E-07 531280 + 629 531290 I-129 3.23460E-05 1.24510E-02 53129.82c + 630 531300 I-130 3.33790E-04 4.53500E-04 53130.82c + 631 531301 I-130m 1.42510E-04 1.42510E-04 531301 + 632 531310 I-131 2.96230E-03 3.90240E-02 53131.82c + 633 531320 I-132 6.16000E-03 5.28470E-02 531320 + 634 531321 I-132m 4.54000E-03 4.54000E-03 531321 + 635 531330 I-133 1.45620E-02 5.04080E-02 531330 + 636 531331 I-133m 8.89840E-03 8.89840E-03 531331 + 637 531340 I-134 2.05530E-02 5.30890E-02 531340 + 638 531341 I-134m 1.51480E-02 1.51480E-02 531341 + 639 531350 I-135 5.55770E-02 6.01230E-02 53135.82c + 640 531360 I-136 6.34990E-03 7.07580E-03 531360 + 641 531361 I-136m 1.48730E-02 1.48750E-02 531361 + 642 531370 I-137 7.40560E-03 7.51800E-03 531370 + 643 531380 I-138 8.27460E-04 8.28010E-04 531380 + 644 531390 I-139 1.94350E-04 1.94360E-04 531390 + 645 531400 I-140 1.83630E-05 1.83630E-05 531400 + 646 531410 I-141 3.47140E-08 3.47140E-08 531410 + 647 541290 Xe-129 5.95130E-10 2.54220E-09 54129.82c + 648 541291 Xe-129m 1.94710E-09 1.94710E-09 541291 + 649 541300 Xe-130 1.58810E-05 4.92180E-04 54130.82c + 650 541310 Xe-131 1.74720E-05 3.90830E-02 54131.82c + 651 541311 Xe-131m 4.21790E-05 4.66050E-04 541311 + 652 541320 Xe-132 2.98160E-04 5.41190E-02 54132.82c + 653 541321 Xe-132m 3.37980E-04 3.37980E-04 541321 + 654 541330 Xe-133 8.38660E-04 5.32710E-02 54133.82c + 655 541331 Xe-133m 2.02460E-03 3.45940E-03 541331 + 656 541340 Xe-134 3.46770E-03 6.50280E-02 54134.82c + 657 541341 Xe-134m 8.12230E-03 8.47070E-03 541341 + 658 541350 Xe-135 1.10440E-02 9.76090E-02 54135.82c + 659 541351 Xe-135m 2.66620E-02 3.65870E-02 541351 + 660 541360 Xe-136 8.16970E-02 1.04140E-01 54136.82c + 661 541370 Xe-137 5.21880E-02 5.92610E-02 541370 + 662 541380 Xe-138 3.09130E-02 3.17160E-02 541380 + 663 541390 Xe-139 8.96300E-03 9.14000E-03 541390 + 664 541400 Xe-140 2.71660E-03 2.73330E-03 541400 + 665 541410 Xe-141 5.68590E-04 5.68620E-04 541410 + 666 541420 Xe-142 5.86620E-05 5.86620E-05 541420 + 667 541430 Xe-143 1.65000E-07 1.65000E-07 541430 + 668 541440 Xe-144 3.44650E-09 3.44650E-09 541440 + 669 551310 Cs-131 1.22650E-09 1.22650E-09 551310 + 670 551320 Cs-132 8.04740E-08 8.04740E-08 551320 + 671 551330 Cs-133 1.08890E-05 5.32820E-02 55133.82c + 672 551340 Cs-134 6.83760E-05 1.18770E-04 55134.82c + 673 551341 Cs-134m 5.03940E-05 5.03940E-05 551341 + 674 551350 Cs-135 7.18210E-04 9.89860E-02 55135.82c + 675 551351 Cs-135m 4.38890E-04 4.38890E-04 551351 + 676 551360 Cs-136 4.05020E-03 5.23700E-03 55136.82c + 677 551361 Cs-136m 2.37360E-03 2.37360E-03 551361 + 678 551370 Cs-137 2.69280E-02 8.61890E-02 55137.82c + 679 551380 Cs-138 1.38340E-02 6.14500E-02 551380 + 680 551381 Cs-138m 1.96290E-02 1.96290E-02 551381 + 681 551390 Cs-139 3.31370E-02 4.22770E-02 551390 + 682 551400 Cs-140 1.74350E-02 2.01680E-02 551400 + 683 551410 Cs-141 1.13640E-02 1.19330E-02 551410 + 684 551420 Cs-142 3.52010E-03 3.57850E-03 551420 + 685 551430 Cs-143 9.28420E-04 9.28580E-04 551430 + 686 551440 Cs-144 8.19150E-05 1.22880E-04 551440 + 687 551441 Cs-144m 8.19150E-05 8.19150E-05 551441 + 688 551450 Cs-145 1.32360E-05 1.32360E-05 551450 + 689 551460 Cs-146 8.77010E-09 8.77010E-09 551460 + 690 561340 Ba-134 2.18040E-08 1.18790E-04 56134.82c + 691 561350 Ba-135 3.96120E-07 1.35240E-06 56135.82c + 692 561351 Ba-135m 9.56280E-07 9.56280E-07 561351 + 693 561360 Ba-136 4.40750E-05 6.57110E-03 56136.82c + 694 561361 Ba-136m 1.03230E-04 1.03230E-04 561361 + 695 561370 Ba-137 4.46150E-04 8.77120E-02 56137.82c + 696 561371 Ba-137m 1.07700E-03 8.24390E-02 561371 + 697 561380 Ba-138 9.93660E-03 7.51160E-02 56138.82c + 698 561390 Ba-139 1.81430E-02 6.04200E-02 561390 + 699 561400 Ba-140 3.21340E-02 5.23030E-02 56140.82c + 700 561410 Ba-141 2.73290E-02 3.92620E-02 561410 + 701 561420 Ba-142 3.30830E-02 3.66770E-02 561420 + 702 561430 Ba-143 1.69470E-02 1.78640E-02 561430 + 703 561440 Ba-144 6.88240E-03 7.04420E-03 561440 + 704 561450 Ba-145 1.58300E-03 1.59430E-03 561450 + 705 561460 Ba-146 3.13250E-04 3.13260E-04 561460 + 706 561470 Ba-147 2.21060E-05 2.21060E-05 561470 + 707 561480 Ba-148 4.18100E-08 4.18100E-08 561480 + 708 561490 Ba-149 3.75490E-10 3.75490E-10 561490 + 709 571360 La-136 1.31180E-09 2.62370E-09 571360 + 710 571361 La-136m 1.31180E-09 1.31180E-09 571361 + 711 571370 La-137 2.29190E-07 2.29190E-07 571370 + 712 571380 La-138 2.20300E-05 2.20300E-05 57138.82c + 713 571390 La-139 4.58940E-04 6.08790E-02 57139.82c + 714 571400 La-140 1.76720E-03 5.40700E-02 57140.82c + 715 571410 La-141 5.37740E-03 4.46390E-02 571410 + 716 571420 La-142 7.69120E-03 4.43680E-02 571420 + 717 571430 La-143 1.65010E-02 3.43650E-02 571430 + 718 571440 La-144 1.55880E-02 2.26320E-02 571440 + 719 571450 La-145 1.22910E-02 1.38850E-02 571450 + 720 571460 La-146 1.70040E-03 2.01370E-03 571460 + 721 571461 La-146m 3.05870E-03 3.05870E-03 571461 + 722 571470 La-147 1.57170E-03 1.59380E-03 571470 + 723 571480 La-148 2.82970E-04 2.83010E-04 571480 + 724 571490 La-149 5.28190E-05 5.28190E-05 571490 + 725 571500 La-150 7.35380E-06 7.35380E-06 571500 + 726 571510 La-151 1.57820E-09 1.57820E-09 571510 + 727 581390 Ce-139 6.62570E-09 2.26210E-08 581390 + 728 581391 Ce-139m 1.59950E-08 1.59950E-08 581391 + 729 581400 Ce-140 7.33680E-05 5.41430E-02 58140.82c + 730 581410 Ce-141 2.82560E-04 4.49220E-02 58141.82c + 731 581420 Ce-142 1.39250E-03 4.57610E-02 58142.82c + 732 581430 Ce-143 2.77120E-03 3.71370E-02 58143.82c + 733 581440 Ce-144 8.08660E-03 3.07190E-02 58144.82c + 734 581450 Ce-145 1.04870E-02 2.43720E-02 581450 + 735 581460 Ce-146 1.39440E-02 1.90160E-02 581460 + 736 581470 Ce-147 1.03880E-02 1.19820E-02 581470 + 737 581480 Ce-148 6.46520E-03 6.74900E-03 581480 + 738 581490 Ce-149 2.23460E-03 2.28690E-03 581490 + 739 581500 Ce-150 3.69130E-04 3.76290E-04 581500 + 740 581510 Ce-151 1.00800E-04 1.00800E-04 581510 + 741 581520 Ce-152 1.66270E-05 1.66270E-05 581520 + 742 581530 Ce-153 5.71300E-09 5.71300E-09 581530 + 743 581540 Ce-154 5.66460E-11 5.66460E-11 581540 + 744 591410 Pr-141 2.77710E-09 4.49220E-02 59141.82c + 745 591420 Pr-142 3.55750E-08 1.18900E-07 59142.82c + 746 591421 Pr-142m 8.33250E-08 8.33250E-08 591421 + 747 591430 Pr-143 1.59030E-05 3.71520E-02 59143.82c + 748 591440 Pr-144 8.60100E-06 3.08030E-02 591440 + 749 591441 Pr-144m 7.63890E-05 5.00290E-04 591441 + 750 591450 Pr-145 6.24510E-04 2.49970E-02 591450 + 751 591460 Pr-146 1.33860E-03 2.03550E-02 591460 + 752 591470 Pr-147 2.78980E-03 1.47720E-02 591470 + 753 591480 Pr-148 5.91230E-04 7.34020E-03 591480 + 754 591481 Pr-148m 2.48650E-03 2.48650E-03 591481 + 755 591490 Pr-149 4.06330E-03 6.35020E-03 591490 + 756 591500 Pr-150 2.65380E-03 3.03010E-03 591500 + 757 591510 Pr-151 1.24740E-03 1.34820E-03 591510 + 758 591520 Pr-152 3.93800E-04 4.10430E-04 591520 + 759 591530 Pr-153 1.15100E-04 1.15110E-04 591530 + 760 591540 Pr-154 1.50670E-05 1.50670E-05 591540 + 761 591550 Pr-155 1.38240E-08 1.38240E-08 591550 + 762 591560 Pr-156 1.20560E-10 1.20560E-10 591560 + 763 601440 Nd-144 1.95300E-08 3.08040E-02 60144.82c + 764 601450 Nd-145 6.60870E-06 2.50040E-02 60145.82c + 765 601460 Nd-146 5.77890E-05 2.04130E-02 60146.82c + 766 601470 Nd-147 2.14710E-04 1.49860E-02 60147.82c + 767 601480 Nd-148 6.57230E-04 1.04840E-02 60148.82c + 768 601490 Nd-149 6.96990E-04 7.04720E-03 601490 + 769 601500 Nd-150 1.13230E-03 4.16240E-03 60150.82c + 770 601510 Nd-151 2.01370E-03 3.36190E-03 601510 + 771 601520 Nd-152 2.10990E-03 2.52030E-03 601520 + 772 601530 Nd-153 1.21470E-03 1.32980E-03 601530 + 773 601540 Nd-154 4.16710E-04 4.31780E-04 601540 + 774 601550 Nd-155 9.90680E-05 9.90820E-05 601550 + 775 601560 Nd-156 3.45190E-05 3.45190E-05 601560 + 776 601570 Nd-157 2.47410E-08 2.47410E-08 601570 + 777 601580 Nd-158 2.19390E-10 2.19390E-10 601580 + 778 601590 Nd-159 3.08600E-12 3.08600E-12 601590 + 779 611460 Pm-146 9.74460E-10 9.74460E-10 611460 + 780 611470 Pm-147 6.64590E-08 1.49860E-02 61147.82c + 781 611480 Pm-148 3.34620E-07 3.73810E-07 61148.82c + 782 611481 Pm-148m 7.83770E-07 7.83770E-07 61548.82c + 783 611490 Pm-149 1.84920E-05 7.06570E-03 61149.82c + 784 611500 Pm-150 8.90900E-05 8.90900E-05 611500 + 785 611510 Pm-151 2.24310E-04 3.58620E-03 61151.82c + 786 611520 Pm-152 8.78450E-05 2.60820E-03 611520 + 787 611521 Pm-152m 1.75420E-04 1.75420E-04 611521 + 788 611522 Pm-152m 1.94030E-04 1.94030E-04 611522 + 789 611530 Pm-153 8.32040E-04 2.16180E-03 611530 + 790 611540 Pm-154 3.71650E-04 8.03430E-04 611540 + 791 611541 Pm-154m 3.71650E-04 3.71650E-04 611541 + 792 611550 Pm-155 4.37580E-04 5.36660E-04 611550 + 793 611560 Pm-156 1.46790E-04 1.81310E-04 611560 + 794 611570 Pm-157 1.73660E-05 1.73910E-05 611570 + 795 611580 Pm-158 3.43790E-07 3.44010E-07 611580 + 796 611590 Pm-159 3.59870E-08 3.59900E-08 611590 + 797 611600 Pm-160 3.14240E-10 3.14240E-10 611600 + 798 611610 Pm-161 4.48260E-12 4.48260E-12 611610 + 799 621490 Sm-149 4.50590E-09 7.06570E-03 62149.82c + 800 621500 Sm-150 1.81300E-07 8.92710E-05 62150.82c + 801 621510 Sm-151 1.33400E-05 3.59950E-03 62151.82c + 802 621520 Sm-152 4.94720E-05 3.02710E-03 62152.82c + 803 621530 Sm-153 2.91570E-05 2.26140E-03 62153.82c + 804 621531 Sm-153m 7.03890E-05 7.03890E-05 621531 + 805 621540 Sm-154 3.35830E-04 1.51090E-03 62154.82c + 806 621550 Sm-155 3.44570E-04 8.81230E-04 621550 + 807 621560 Sm-156 3.01250E-04 4.82560E-04 621560 + 808 621570 Sm-157 2.95230E-04 3.12620E-04 621570 + 809 621580 Sm-158 3.60370E-05 3.63810E-05 621580 + 810 621590 Sm-159 1.79650E-05 1.80010E-05 621590 + 811 621600 Sm-160 5.95600E-07 5.95910E-07 621600 + 812 621610 Sm-161 2.40550E-08 2.40600E-08 621610 + 813 621620 Sm-162 1.46490E-09 1.46490E-09 621620 + 814 621630 Sm-163 1.27170E-11 1.27170E-11 621630 + 815 631510 Eu-151 3.64200E-10 3.59950E-03 63151.82c + 816 631520 Eu-152 6.23920E-09 1.31980E-08 63152.82c + 817 631521 Eu-152m 1.48600E-09 1.48600E-09 631521 + 818 631522 Eu-152m 6.95880E-09 6.95880E-09 631522 + 819 631530 Eu-153 4.45290E-07 2.26180E-03 63153.82c + 820 631540 Eu-154 1.99050E-06 3.78350E-06 63154.82c + 821 631541 Eu-154m 1.79300E-06 1.79300E-06 631541 + 822 631550 Eu-155 8.23620E-06 8.89470E-04 63155.82c + 823 631560 Eu-156 2.58520E-05 5.08410E-04 63156.82c + 824 631570 Eu-157 3.47050E-05 3.47330E-04 63157.82c + 825 631580 Eu-158 4.50210E-05 8.14020E-05 631580 + 826 631590 Eu-159 6.28610E-05 8.08620E-05 631590 + 827 631600 Eu-160 1.74490E-05 1.80450E-05 631600 + 828 631610 Eu-161 3.35770E-06 3.38180E-06 631610 + 829 631620 Eu-162 5.41500E-07 5.42970E-07 631620 + 830 631630 Eu-163 3.85200E-08 3.85330E-08 631630 + 831 631640 Eu-164 1.12680E-09 1.12680E-09 631640 + 832 631650 Eu-165 2.69820E-11 2.69820E-11 631650 + 833 641540 Gd-154 1.86930E-09 3.78460E-06 64154.82c + 834 641550 Gd-155 1.03740E-08 8.89500E-04 64155.82c + 835 641551 Gd-155m 2.50440E-08 2.50440E-08 641551 + 836 641560 Gd-156 5.93170E-07 5.09000E-04 64156.82c + 837 641570 Gd-157 3.68010E-06 3.51010E-04 64157.82c + 838 641580 Gd-158 9.00460E-06 9.04210E-05 64158.82c + 839 641590 Gd-159 2.69290E-05 1.07790E-04 641590 + 840 641600 Gd-160 1.74450E-05 3.54900E-05 64160.82c + 841 641610 Gd-161 2.06480E-05 2.40300E-05 641610 + 842 641620 Gd-162 1.34760E-05 1.40190E-05 641620 + 843 641630 Gd-163 2.33150E-06 2.37000E-06 641630 + 844 641640 Gd-164 5.14100E-07 5.15230E-07 641640 + 845 641650 Gd-165 3.35630E-08 3.35900E-08 641650 + 846 641660 Gd-166 1.88680E-09 1.88680E-09 641660 + 847 641670 Gd-167 4.11610E-11 4.11610E-11 641670 + 848 651560 Tb-156 2.21530E-11 6.02690E-11 651560 + 849 651561 Tb-156m 3.20270E-11 3.20270E-11 651561 + 850 651562 Tb-156m 6.10040E-12 6.10040E-12 651562 + 851 651570 Tb-157 2.86440E-09 2.86440E-09 651570 + 852 651580 Tb-158 1.53570E-08 1.70750E-08 651580 + 853 651581 Tb-158m 1.72910E-09 1.72910E-09 651581 + 854 651590 Tb-159 4.25440E-07 1.08220E-04 65159.82c + 855 651600 Tb-160 8.98270E-07 8.98270E-07 65160.82c + 856 651610 Tb-161 3.26700E-06 2.72970E-05 651610 + 857 651620 Tb-162 6.55780E-06 2.05770E-05 651620 + 858 651630 Tb-163 6.29140E-06 8.66140E-06 651630 + 859 651640 Tb-164 2.84980E-06 3.36500E-06 651640 + 860 651650 Tb-165 1.23310E-06 1.26670E-06 651650 + 861 651660 Tb-166 1.71990E-07 1.73880E-07 651660 + 862 651670 Tb-167 2.92790E-08 2.93200E-08 651670 + 863 651680 Tb-168 1.50430E-09 1.50430E-09 651680 + 864 651690 Tb-169 6.32630E-11 6.32630E-11 651690 + 865 661580 Dy-158 3.37520E-12 2.84830E-09 661580 + 866 661590 Dy-159 1.35780E-10 1.35780E-10 661590 + 867 661600 Dy-160 2.34990E-09 9.00620E-07 66160.82c + 868 661610 Dy-161 2.26640E-08 2.73190E-05 66161.82c + 869 661620 Dy-162 6.73630E-06 2.73130E-05 66162.82c + 870 661630 Dy-163 7.10630E-07 9.37210E-06 66163.82c + 871 661640 Dy-164 1.93050E-06 5.30520E-06 66164.82c + 872 661650 Dy-165 1.40750E-06 2.88460E-06 661650 + 873 661651 Dy-165m 2.15170E-07 2.15170E-07 661651 + 874 661660 Dy-166 1.31890E-06 1.49280E-06 661660 + 875 661670 Dy-167 4.84580E-07 5.13900E-07 661670 + 876 661680 Dy-168 1.73890E-07 1.75390E-07 661680 + 877 661690 Dy-169 1.88980E-08 1.89610E-08 661690 + 878 661700 Dy-170 1.98490E-09 1.98490E-09 661700 + 879 661710 Dy-171 7.52020E-11 7.52020E-11 661710 + 880 661720 Dy-172 2.27560E-12 2.27560E-12 661720 + 881 671610 Ho-161 3.33270E-12 3.84220E-12 671610 + 882 671620 Ho-162 5.03050E-11 1.23360E-10 671620 + 883 671621 Ho-162m 1.17830E-10 1.17830E-10 671621 + 884 671630 Ho-163 2.50910E-09 2.89270E-09 671630 + 885 671631 Ho-163m 3.83570E-10 3.83570E-10 671631 + 886 671640 Ho-164 6.02080E-09 2.01230E-08 671640 + 887 671641 Ho-164m 1.41020E-08 1.41020E-08 671641 + 888 671650 Ho-165 1.16710E-07 3.00630E-06 67165.82c + 889 671660 Ho-166 6.04950E-08 1.55330E-06 671660 + 890 671661 Ho-166m 1.41690E-07 1.41690E-07 671661 + 891 671670 Ho-167 4.29830E-07 9.43730E-07 671670 + 892 671680 Ho-168 1.24210E-07 4.74970E-07 671680 + 893 671681 Ho-168m 1.76250E-07 1.76250E-07 671681 + 894 671690 Ho-169 1.97960E-07 2.16920E-07 671690 + 895 671700 Ho-170 3.31840E-08 3.31840E-08 671700 + 896 671701 Ho-170m 1.41680E-08 1.61530E-08 671701 + 897 671710 Ho-171 1.31330E-08 1.32080E-08 671710 + 898 671720 Ho-172 1.06210E-09 1.06440E-09 671720 + 899 671730 Ho-173 8.66390E-11 8.66390E-11 671730 + 900 671740 Ho-174 2.26490E-12 2.26490E-12 671740 + 901 681640 Er-164 1.24900E-11 1.04160E-08 68164.82c + 902 681650 Er-165 2.00200E-10 2.00200E-10 681650 + 903 681660 Er-166 2.68520E-09 1.55600E-06 68166.82c + 904 681670 Er-167 1.21510E-08 9.57750E-07 68167.82c + 905 681671 Er-167m 1.85750E-09 1.14640E-07 681671 + 906 681680 Er-168 6.40710E-08 5.40100E-07 68168.82c + 907 681690 Er-169 8.58230E-08 3.02740E-07 681690 + 908 681700 Er-170 1.16820E-07 1.66160E-07 68170.82c + 909 681710 Er-171 6.46830E-08 7.78910E-08 681710 + 910 681720 Er-172 3.33540E-08 3.44180E-08 681720 + 911 681730 Er-173 6.52550E-09 6.61210E-09 681730 + 912 681740 Er-174 1.29920E-09 1.30150E-09 681740 + 913 681750 Er-175 7.83560E-11 7.83560E-11 681750 + 914 681760 Er-176 4.00100E-12 4.00100E-12 681760 + 915 691670 Tm-167 1.37860E-11 1.37860E-11 691670 + 916 691680 Tm-168 1.70660E-10 1.70660E-10 691680 + 917 691690 Tm-169 1.70730E-09 3.04450E-07 691690 + 918 691700 Tm-170 5.42820E-09 5.42820E-09 691700 + 919 691710 Tm-171 1.86510E-08 9.65420E-08 691710 + 920 691720 Tm-172 1.89080E-08 5.33260E-08 691720 + 921 691730 Tm-173 2.11780E-08 2.77900E-08 691730 + 922 691740 Tm-174 8.77520E-09 1.00770E-08 691740 + 923 691750 Tm-175 3.56080E-09 3.63920E-09 691750 + 924 691760 Tm-176 4.56630E-10 4.60630E-10 691760 + 925 691770 Tm-177 7.06860E-11 7.06860E-11 691770 + 926 691780 Tm-178 3.34160E-12 3.34160E-12 691780 + 927 701700 Yb-170 1.78980E-11 5.43900E-09 701700 + 928 701710 Yb-171 2.14340E-11 9.67040E-08 701710 + 929 701711 Yb-171m 1.40210E-10 1.40210E-10 701711 + 930 701720 Yb-172 1.17160E-09 5.44980E-08 701720 + 931 701730 Yb-173 2.90570E-09 3.07110E-08 701730 + 932 701740 Yb-174 7.13730E-09 1.73060E-08 701740 + 933 701750 Yb-175 4.87230E-09 9.25630E-09 701750 + 934 701751 Yb-175m 7.44830E-10 3.54700E-09 701751 + 935 701760 Yb-176 1.51420E-09 4.40350E-09 701760 + 936 701761 Yb-176m 2.72380E-09 2.95410E-09 701761 + 937 701770 Yb-177 1.16740E-09 1.50800E-09 701770 + 938 701771 Yb-177m 2.69920E-10 3.40610E-10 701771 + 939 701780 Yb-178 4.81140E-10 4.84480E-10 701780 + 940 701790 Yb-179 4.77480E-11 4.77480E-11 701790 + 941 701800 Yb-180 4.50750E-12 4.50750E-12 701800 + 942 711730 Lu-173 1.48450E-11 1.48450E-11 711730 + 943 711740 Lu-174 2.76300E-11 9.19720E-11 711740 + 944 711741 Lu-174m 6.47170E-11 6.47170E-11 711741 + 945 711750 Lu-175 4.94190E-10 9.75150E-09 71175.82c + 946 711760 Lu-176 5.03560E-10 7.98960E-10 71176.82c + 947 711761 Lu-176m 2.79950E-10 2.79950E-10 711761 + 948 711770 Lu-177 1.08790E-09 2.69360E-09 711770 + 949 711771 Lu-177m 4.25300E-10 4.32170E-10 711771 + 950 711772 Lu-177m 1.37440E-11 1.37440E-11 711772 + 951 711780 Lu-178 4.68980E-10 9.53460E-10 711780 + 952 711781 Lu-178m 5.31620E-10 5.31620E-10 711781 + 953 711790 Lu-179 5.29220E-10 6.57870E-10 711790 + 954 711791 Lu-179m 8.09020E-11 1.28650E-10 711791 + 955 711800 Lu-180 3.83310E-11 8.79960E-11 711800 + 956 711801 Lu-180m 3.83310E-11 4.28380E-11 711801 + 957 711802 Lu-180m 5.64910E-11 5.64910E-11 711802 + 958 711810 Lu-181 3.44310E-11 3.44310E-11 711810 + 959 711820 Lu-182 2.59270E-12 2.59270E-12 711820 + 960 721750 Hf-175 1.06810E-12 1.06810E-12 721750 + 961 721760 Hf-176 1.29880E-11 2.92670E-10 72176.82c + 962 721770 Hf-177 4.36770E-11 3.09620E-09 72177.82c + 963 721771 Hf-177m 1.69710E-11 3.59000E-10 721771 + 964 721772 Hf-177m 6.56020E-13 7.52800E-12 721772 + 965 721780 Hf-178 9.24940E-11 1.74390E-09 72178.82c + 966 721781 Hf-178m 1.52600E-10 6.98000E-10 721781 + 967 721782 Hf-178m 1.37720E-11 1.37720E-11 721782 + 968 721790 Hf-179 1.90940E-10 9.83090E-10 72179.82c + 969 721791 Hf-179m 5.96060E-11 5.96060E-11 721791 + 970 721792 Hf-179m 6.68420E-11 6.68420E-11 721792 + 971 721800 Hf-180 1.40750E-10 5.39290E-10 72180.82c + 972 721801 Hf-180m 2.53170E-10 2.81420E-10 721801 + 973 721810 Hf-181 2.05450E-10 2.39880E-10 721810 + 974 721820 Hf-182 3.57800E-11 6.54040E-11 721820 + 975 721821 Hf-182m 6.43600E-11 6.43600E-11 721821 + 976 721830 Hf-183 1.77830E-11 1.77830E-11 721830 + 977 721840 Hf-184 1.14530E-12 1.14530E-12 721840 + 978 721841 Hf-184m 2.06020E-12 2.06020E-12 721841 + 979 731790 Ta-179 5.94060E-12 7.82810E-12 731790 + 980 731791 Ta-179m 1.81710E-12 1.88750E-12 731791 + 981 731800 Ta-180 1.04820E-11 1.04820E-11 731800 + 982 731801 Ta-180m 1.18830E-11 1.27550E-11 731801 + 983 731810 Ta-181 7.13820E-11 3.11260E-10 73181.82c + 984 731820 Ta-182 2.42950E-11 1.05330E-10 73182.82c + 985 731821 Ta-182m 2.47990E-11 8.10300E-11 731821 + 986 731822 Ta-182m 1.89030E-11 5.62320E-11 731822 + 987 731830 Ta-183 6.95200E-11 8.73030E-11 731830 + 988 731840 Ta-184 2.64400E-11 2.96460E-11 731840 + 989 731850 Ta-185 6.80910E-12 1.01070E-11 731850 + 990 731851 Ta-185m 3.29790E-12 3.29790E-12 731851 + 991 731860 Ta-186 1.19680E-12 1.19680E-12 731860 + 992 741820 W-182 5.18420E-12 1.10510E-10 74182.82c + 993 741830 W-183 2.70640E-12 9.88640E-11 74183.82c + 994 741831 W-183m 8.85460E-12 1.18230E-11 741831 + 995 741840 W-184 2.57930E-11 5.54380E-11 74184.82c + 996 741850 W-185 5.60290E-12 2.92360E-11 741850 + 997 741851 W-185m 1.35260E-11 1.35260E-11 741851 + 998 741860 W-186 1.01850E-11 1.47520E-11 74186.82c + 999 741861 W-186m 3.28530E-12 3.28530E-12 741861 + 1000 741870 W-187 4.20720E-12 4.20720E-12 741870 + 1001 741880 W-188 1.30920E-12 1.30920E-12 741880 + 1002 751850 Re-185 2.05390E-12 3.12900E-11 75185.82c + 1003 751860 Re-186 1.23950E-12 1.23950E-12 751860 + 1004 751861 Re-186m 1.75890E-12 1.75890E-12 751861 + 1005 751870 Re-187 5.35410E-12 9.56130E-12 75187.82c + 1006 751880 Re-188 9.82090E-13 4.59160E-12 751880 + 1007 751881 Re-188m 2.30030E-12 2.30030E-12 751881 + 1008 751890 Re-189 1.85910E-12 1.85910E-12 751890 + 1009 761880 Os-188 1.02830E-12 5.61990E-12 761880 + 1010 761890 Os-189 2.71440E-13 3.01860E-12 761890 + 1011 761891 Os-189m 8.88060E-13 1.07920E-12 761891 + 1012 761900 Os-190 6.16760E-13 1.31590E-12 761900 + + Nuclide 96243.82c -- curium 243 (Cm-243) + + Neutron-induced fission: + + Interpolation region : 1 / 2 + Interpolation energy : 2.53000E-08 MeV + Number of products : 1173 / 1216 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 4.08110E-05 4.08110E-05 1001.82c + 2 10020 H-2 1.24720E-05 1.24720E-05 1002.82c + 3 10030 H-3 1.96000E-04 1.96000E-04 1003.82c + 4 20040 He-4 2.58000E-03 2.58000E-03 2004.82c + 5 190500 K-50 1.28440E-11 1.28440E-11 190500 + 6 190510 K-51 4.17280E-12 4.17280E-12 190510 + 7 200500 Ca-50 1.83230E-10 1.94310E-10 200500 + 8 200510 Ca-51 1.50100E-10 1.52310E-10 200510 + 9 200520 Ca-52 1.05570E-10 1.05570E-10 200520 + 10 200530 Ca-53 2.76230E-11 2.76230E-11 200530 + 11 200540 Ca-54 5.71610E-12 5.71610E-12 200540 + 12 210500 Sc-50 4.66360E-11 2.58180E-10 210500 + 13 210501 Sc-50m 1.99110E-11 2.14220E-10 210501 + 14 210510 Sc-51 2.45990E-10 4.00410E-10 210510 + 15 210520 Sc-52 3.89740E-10 5.01490E-10 210520 + 16 210530 Sc-53 5.09380E-10 5.28720E-10 210530 + 17 210540 Sc-54 2.77730E-10 2.83450E-10 210540 + 18 210550 Sc-55 1.52510E-10 1.52510E-10 210550 + 19 210560 Sc-56 3.19750E-11 3.19750E-11 210560 + 20 210570 Sc-57 5.16200E-12 5.16200E-12 210570 + 21 220500 Ti-50 2.51720E-12 2.63370E-10 22050.82c + 22 220510 Ti-51 2.36330E-11 4.24050E-10 220510 + 23 220520 Ti-52 1.80340E-10 6.81830E-10 220520 + 24 220530 Ti-53 5.20420E-10 1.04910E-09 220530 + 25 220540 Ti-54 1.29030E-09 1.57380E-09 220540 + 26 220550 Ti-55 1.65440E-09 1.80690E-09 220550 + 27 220560 Ti-56 1.81290E-09 1.84660E-09 220560 + 28 220570 Ti-57 8.02170E-10 8.05630E-10 220570 + 29 220580 Ti-58 2.95600E-10 2.95600E-10 220580 + 30 220590 Ti-59 4.52900E-11 4.52900E-11 220590 + 31 220600 Ti-60 5.19190E-12 5.19190E-12 220600 + 32 230520 V-52 1.66350E-12 6.83490E-10 230520 + 33 230530 V-53 2.60900E-11 1.07520E-09 230530 + 34 230540 V-54 1.57000E-10 1.73080E-09 230540 + 35 230550 V-55 9.35150E-10 2.74210E-09 230550 + 36 230560 V-56 2.24420E-09 4.09320E-09 230560 + 37 230570 V-57 4.62790E-09 5.43110E-09 230570 + 38 230580 V-58 4.15870E-09 4.45430E-09 230580 + 39 230590 V-59 3.47820E-09 3.52350E-09 230590 + 40 230600 V-60 1.13000E-09 1.13520E-09 230600 + 41 230610 V-61 3.36150E-10 3.36150E-10 230610 + 42 230620 V-62 3.85370E-11 3.85370E-11 230620 + 43 230630 V-63 3.21610E-12 3.21610E-12 230630 + 44 240540 Cr-54 1.66410E-12 1.73240E-09 24054.82c + 45 240550 Cr-55 2.70620E-11 2.76910E-09 240550 + 46 240560 Cr-56 3.37860E-10 4.45280E-09 240560 + 47 240570 Cr-57 1.61990E-09 1.05930E-08 240570 + 48 240580 Cr-58 6.60910E-09 7.50000E-09 240580 + 49 240590 Cr-59 1.22270E-08 1.57500E-08 240590 + 50 240600 Cr-60 1.92160E-08 2.03710E-08 240600 + 51 240610 Cr-61 1.45850E-08 1.49010E-08 240610 + 52 240620 Cr-62 9.48790E-09 9.52760E-09 240620 + 53 240630 Cr-63 2.30710E-09 2.30920E-09 240630 + 54 240640 Cr-64 4.39780E-10 4.39780E-10 240640 + 55 240650 Cr-65 4.98440E-11 4.98440E-11 240650 + 56 240660 Cr-66 2.69030E-12 2.69030E-12 240660 + 57 250570 Mn-57 2.36110E-11 1.06160E-08 250570 + 58 250580 Mn-58 2.27120E-10 7.72710E-09 250580 + 59 250581 Mn-58m 2.55720E-11 2.55720E-11 250581 + 60 250590 Mn-59 2.32410E-09 1.80750E-08 250590 + 61 250600 Mn-60 8.30170E-10 2.20490E-08 250600 + 62 250601 Mn-60m 7.37310E-09 7.37310E-09 250601 + 63 250610 Mn-61 2.81050E-08 4.30060E-08 250610 + 64 250620 Mn-62 3.52090E-08 3.99730E-08 250620 + 65 250621 Mn-62m 6.32090E-09 1.10850E-08 250621 + 66 250630 Mn-63 5.10430E-08 5.33520E-08 250630 + 67 250640 Mn-64 2.59170E-08 2.63570E-08 250640 + 68 250650 Mn-65 1.72240E-08 1.72740E-08 250650 + 69 250660 Mn-66 2.78080E-09 2.78350E-09 250660 + 70 250670 Mn-67 2.20800E-10 2.20800E-10 250670 + 71 250680 Mn-68 1.00020E-11 1.00020E-11 250680 + 72 260590 Fe-59 1.89310E-11 1.80930E-08 260590 + 73 260600 Fe-60 3.74080E-10 2.89490E-08 260600 + 74 260610 Fe-61 3.21630E-09 4.62220E-08 260610 + 75 260620 Fe-62 2.26530E-08 7.37110E-08 260620 + 76 260630 Fe-63 6.12360E-08 1.14590E-07 260630 + 77 260640 Fe-64 1.42090E-07 1.68450E-07 260640 + 78 260650 Fe-65 2.22900E-07 2.40170E-07 260650 + 79 260660 Fe-66 1.90320E-07 1.93100E-07 260660 + 80 260670 Fe-67 4.18090E-08 4.20300E-08 260670 + 81 260680 Fe-68 1.14140E-08 1.14240E-08 260680 + 82 260690 Fe-69 3.51240E-09 3.51240E-09 260690 + 83 260700 Fe-70 1.81360E-10 1.81360E-10 260700 + 84 260710 Fe-71 3.71020E-12 3.71020E-12 260710 + 85 270610 Co-61 1.28280E-11 4.62350E-08 270610 + 86 270620 Co-62 7.57330E-11 7.37880E-08 270620 + 87 270621 Co-62m 1.77390E-10 1.77390E-10 270621 + 88 270630 Co-63 3.67780E-09 1.18270E-07 270630 + 89 270640 Co-64 2.04700E-08 1.88920E-07 270640 + 90 270650 Co-65 1.48060E-07 3.88230E-07 270650 + 91 270660 Co-66 5.37890E-07 7.30990E-07 270660 + 92 270670 Co-67 2.86210E-07 3.28240E-07 270670 + 93 270680 Co-68 1.02440E-07 1.53460E-07 270680 + 94 270681 Co-68m 9.03700E-08 1.02040E-07 270681 + 95 270690 Co-69 3.27380E-07 3.30650E-07 270690 + 96 270700 Co-70 2.41420E-08 2.41420E-08 270700 + 97 270701 Co-70m 2.41420E-08 2.43240E-08 270701 + 98 270710 Co-71 6.05510E-09 6.05880E-09 270710 + 99 270720 Co-72 1.04240E-09 1.04240E-09 270720 + 100 270730 Co-73 1.63790E-10 1.63790E-10 270730 + 101 270740 Co-74 8.70930E-12 8.70930E-12 270740 + 102 280630 Ni-63 8.00270E-12 1.18270E-07 280630 + 103 280640 Ni-64 2.63970E-10 1.89180E-07 28064.82c + 104 280650 Ni-65 3.92510E-07 7.80740E-07 280650 + 105 280660 Ni-66 4.96540E-08 7.80650E-07 280660 + 106 280670 Ni-67 4.50320E-07 7.78560E-07 280670 + 107 280680 Ni-68 5.59830E-07 7.67620E-07 280680 + 108 280690 Ni-69 6.79550E-07 1.00690E-06 280690 + 109 280691 Ni-69m 6.79550E-07 6.79550E-07 280691 + 110 280700 Ni-70 7.42640E-07 7.91110E-07 280700 + 111 280710 Ni-71 3.17390E-07 3.23450E-07 280710 + 112 280720 Ni-72 7.78220E-07 7.79260E-07 280720 + 113 280730 Ni-73 1.44210E-07 1.44370E-07 280730 + 114 280740 Ni-74 4.82820E-08 4.82910E-08 280740 + 115 280750 Ni-75 2.29110E-09 2.29110E-09 280750 + 116 280760 Ni-76 1.79180E-10 1.79180E-10 280760 + 117 280770 Ni-77 2.99440E-12 2.99440E-12 280770 + 118 290650 Cu-65 5.39360E-12 7.80750E-07 29065.82c + 119 290660 Cu-66 1.52440E-10 7.80800E-07 290660 + 120 290670 Cu-67 2.08280E-09 7.80640E-07 290670 + 121 290680 Cu-68 4.92690E-09 7.82240E-07 290680 + 122 290681 Cu-68m 1.15400E-08 1.15400E-08 290681 + 123 290690 Cu-69 3.05650E-07 1.99210E-06 290690 + 124 290700 Cu-70 5.65140E-08 3.92510E-07 290700 + 125 290701 Cu-70m 6.29600E-07 6.71980E-07 290701 + 126 290702 Cu-70m 5.65140E-08 8.47620E-07 290702 + 127 290710 Cu-71 1.14620E-06 1.46960E-06 290710 + 128 290720 Cu-72 7.78210E-07 1.55750E-06 290720 + 129 290730 Cu-73 3.75110E-06 3.89550E-06 290730 + 130 290740 Cu-74 8.54320E-07 9.02650E-07 290740 + 131 290750 Cu-75 1.65330E-06 1.65550E-06 290750 + 132 290760 Cu-76 1.13040E-07 1.13130E-07 290760 + 133 290761 Cu-76m 1.13040E-07 1.13130E-07 290761 + 134 290770 Cu-77 3.24070E-08 3.24100E-08 290770 + 135 290780 Cu-78 2.19500E-09 2.19500E-09 290780 + 136 290790 Cu-79 7.40100E-11 7.40100E-11 290790 + 137 300670 Zn-67 1.17150E-12 7.80640E-07 300670 + 138 300680 Zn-68 5.69120E-11 7.84140E-07 300680 + 139 300690 Zn-69 5.68530E-10 1.99510E-06 300690 + 140 300691 Zn-69m 2.45880E-09 2.45880E-09 300691 + 141 300700 Zn-70 2.69870E-08 1.56070E-06 300700 + 142 300710 Zn-71 1.83930E-08 1.48800E-06 300710 + 143 300711 Zn-71m 7.95480E-08 7.95480E-08 300711 + 144 300720 Zn-72 1.55630E-06 3.11380E-06 300720 + 145 300730 Zn-73 5.93490E-07 7.59830E-06 300730 + 146 300731 Zn-73m 8.11320E-07 3.10940E-06 300731 + 147 300732 Zn-73m 4.59610E-06 4.59610E-06 300732 + 148 300740 Zn-74 2.47750E-05 2.57360E-05 300740 + 149 300750 Zn-75 9.92030E-06 1.15210E-05 300750 + 150 300760 Zn-76 2.12380E-05 2.14610E-05 300760 + 151 300770 Zn-77 9.36960E-06 1.01180E-05 300770 + 152 300771 Zn-77m 1.43230E-06 1.43230E-06 300771 + 153 300780 Zn-78 3.59470E-06 3.59690E-06 300780 + 154 300790 Zn-79 3.09110E-07 3.09140E-07 300790 + 155 300800 Zn-80 3.39080E-08 3.39080E-08 300800 + 156 300810 Zn-81 1.20210E-09 1.20210E-09 300810 + 157 300820 Zn-82 3.42840E-11 3.42840E-11 300820 + 158 310700 Ga-70 2.17300E-11 2.17300E-11 310700 + 159 310710 Ga-71 4.76740E-10 1.56810E-06 310710 + 160 310720 Ga-72 1.26930E-08 3.12790E-06 310720 + 161 310721 Ga-72m 1.42910E-09 1.05180E-07 310721 + 162 310730 Ga-73 3.88060E-07 1.02840E-05 310730 + 163 310740 Ga-74 8.54250E-07 2.07970E-05 310740 + 164 310741 Ga-74m 8.54250E-07 2.65900E-05 310741 + 165 310750 Ga-75 1.57020E-05 2.72230E-05 310750 + 166 310760 Ga-76 2.97170E-05 5.11780E-05 310760 + 167 310770 Ga-77 4.95100E-05 6.03440E-05 310770 + 168 310780 Ga-78 4.22680E-05 4.58690E-05 310780 + 169 310790 Ga-79 3.91650E-05 3.94700E-05 310790 + 170 310800 Ga-80 9.79260E-06 9.82660E-06 310800 + 171 310810 Ga-81 6.68920E-06 6.69030E-06 310810 + 172 310820 Ga-82 2.10270E-07 2.10300E-07 310820 + 173 310830 Ga-83 1.48180E-08 1.48180E-08 310830 + 174 310840 Ga-84 4.17120E-10 4.17120E-10 310840 + 175 320720 Ge-72 1.26350E-11 3.12790E-06 32072.82c + 176 320730 Ge-73 8.39570E-10 1.02860E-05 32073.82c + 177 320731 Ge-73m 1.94130E-10 1.01340E-05 320731 + 178 320740 Ge-74 5.97510E-08 2.75040E-05 32074.82c + 179 320750 Ge-75 1.09600E-07 2.80490E-05 320750 + 180 320751 Ge-75m 7.16960E-07 1.80590E-06 320751 + 181 320760 Ge-76 9.33850E-06 6.05160E-05 32076.82c + 182 320770 Ge-77 3.27640E-05 4.51810E-05 320770 + 183 320771 Ge-77m 5.00870E-06 6.53530E-05 320771 + 184 320780 Ge-78 1.41030E-04 1.86930E-04 320780 + 185 320790 Ge-79 2.23340E-05 6.75560E-05 320790 + 186 320791 Ge-79m 1.46100E-04 1.46150E-04 320791 + 187 320800 Ge-80 2.88710E-04 2.99330E-04 320800 + 188 320810 Ge-81 1.49340E-04 1.52850E-04 320810 + 189 320811 Ge-81m 3.45310E-05 3.73350E-05 320811 + 190 320820 Ge-82 1.38080E-04 1.38250E-04 320820 + 191 320830 Ge-83 2.18300E-05 2.18400E-05 320830 + 192 320840 Ge-84 8.80860E-06 8.80870E-06 320840 + 193 320850 Ge-85 1.29760E-07 1.29760E-07 320850 + 194 320860 Ge-86 6.02530E-09 6.02530E-09 320860 + 195 320870 Ge-87 1.46370E-10 1.46370E-10 320870 + 196 330740 As-74 1.20590E-11 1.20590E-11 330740 + 197 330750 As-75 1.47010E-10 2.80500E-05 33075.82c + 198 330751 As-75m 4.80960E-10 1.02270E-09 330751 + 199 330760 As-76 2.55610E-08 2.55610E-08 330760 + 200 330770 As-77 8.99860E-07 9.90170E-05 330770 + 201 330780 As-78 1.16780E-05 1.98610E-04 330780 + 202 330790 As-79 4.09180E-05 2.48780E-04 330790 + 203 330800 As-80 1.19140E-04 4.18470E-04 330800 + 204 330810 As-81 3.49500E-04 5.39310E-04 330810 + 205 330820 As-82 1.06460E-04 2.44710E-04 330820 + 206 330821 As-82m 3.21250E-04 3.21250E-04 330821 + 207 330830 As-83 5.18960E-04 5.41750E-04 330830 + 208 330840 As-84 1.13130E-04 1.17070E-04 330840 + 209 330841 As-84m 1.13130E-04 1.17070E-04 330841 + 210 330850 As-85 8.90480E-05 8.91600E-05 330850 + 211 330860 As-86 2.69210E-05 2.69270E-05 330860 + 212 330870 As-87 7.27310E-06 7.27330E-06 330870 + 213 330880 As-88 4.51440E-08 4.51440E-08 330880 + 214 330890 As-89 1.19700E-09 1.19700E-09 330890 + 215 340760 Se-76 6.55500E-12 2.55680E-08 34076.82c + 216 340770 Se-77 5.75720E-11 9.90180E-05 34077.82c + 217 340771 Se-77m 3.76610E-10 3.76610E-10 340771 + 218 340780 Se-78 1.79640E-06 2.00410E-04 34078.82c + 219 340790 Se-79 3.15480E-06 2.52280E-04 34079.82c + 220 340791 Se-79m 4.82280E-07 2.43370E-04 340791 + 221 340800 Se-80 1.86140E-05 4.37090E-04 34080.82c + 222 340810 Se-81 1.35850E-05 6.41700E-04 340810 + 223 340811 Se-81m 8.88650E-05 1.08230E-04 340811 + 224 340820 Se-82 3.71450E-04 9.37410E-04 34082.82c + 225 340830 Se-83 6.67430E-04 8.62630E-04 340830 + 226 340831 Se-83m 1.54330E-04 5.01210E-04 340831 + 227 340840 Se-84 1.83240E-03 2.08580E-03 340840 + 228 340850 Se-85 1.31490E-03 1.39330E-03 340850 + 229 340860 Se-86 1.06590E-03 1.08510E-03 340860 + 230 340870 Se-87 4.13890E-04 4.20040E-04 340870 + 231 340880 Se-88 1.61740E-04 1.61790E-04 340880 + 232 340890 Se-89 2.15270E-05 2.15280E-05 340890 + 233 340900 Se-90 3.29100E-06 3.29100E-06 340900 + 234 340910 Se-91 1.29850E-08 1.29850E-08 340910 + 235 340920 Se-92 6.32800E-10 6.32800E-10 340920 + 236 350790 Br-79 4.15810E-11 1.36470E-07 35079.82c + 237 350791 Br-79m 1.36040E-10 1.36040E-10 350791 + 238 350800 Br-80 2.56670E-09 1.03120E-08 350800 + 239 350801 Br-80m 7.74530E-09 7.74530E-09 350801 + 240 350810 Br-81 9.55070E-07 6.42710E-04 35081.82c + 241 350820 Br-82 4.39100E-06 6.22070E-06 350820 + 242 350821 Br-82m 1.87470E-06 1.87470E-06 350821 + 243 350830 Br-83 5.86780E-05 1.42250E-03 350830 + 244 350840 Br-84 1.47720E-04 2.23350E-03 350840 + 245 350841 Br-84m 1.47720E-04 1.47720E-04 350841 + 246 350850 Br-85 9.65080E-04 2.35840E-03 350850 + 247 350860 Br-86 1.56190E-03 2.64700E-03 350860 + 248 350870 Br-87 2.31620E-03 2.73780E-03 350870 + 249 350880 Br-88 1.61590E-03 1.77780E-03 350880 + 250 350890 Br-89 1.04380E-03 1.06360E-03 350890 + 251 350900 Br-90 2.88100E-04 2.91390E-04 350900 + 252 350910 Br-91 9.93190E-05 9.93290E-05 350910 + 253 350920 Br-92 1.54760E-05 1.54770E-05 350920 + 254 350930 Br-93 1.19950E-07 1.19950E-07 350930 + 255 350940 Br-94 2.61600E-09 2.61600E-09 350940 + 256 360810 Kr-81 6.72720E-11 7.75560E-11 360810 + 257 360811 Kr-81m 1.02840E-11 1.02840E-11 360811 + 258 360820 Kr-82 6.44550E-09 6.27210E-06 36082.82c + 259 360830 Kr-83 1.47250E-06 1.42430E-03 36083.82c + 260 360831 Kr-83m 3.40480E-07 1.42160E-03 360831 + 261 360840 Kr-84 1.95330E-05 2.40080E-03 36084.82c + 262 360850 Kr-85 9.94780E-05 6.12110E-04 36085.82c + 263 360851 Kr-85m 2.30020E-05 2.37760E-03 360851 + 264 360860 Kr-86 8.03530E-04 3.51920E-03 36086.82c + 265 360870 Kr-87 2.00090E-03 4.78910E-03 360870 + 266 360880 Kr-88 4.58070E-03 6.38930E-03 360880 + 267 360890 Kr-89 5.59940E-03 6.58480E-03 360890 + 268 360900 Kr-90 5.68200E-03 5.92160E-03 360900 + 269 360910 Kr-91 3.20910E-03 3.29370E-03 360910 + 270 360920 Kr-92 1.71950E-03 1.72990E-03 360920 + 271 360930 Kr-93 3.83790E-04 3.83830E-04 360930 + 272 360940 Kr-94 9.19790E-05 9.19800E-05 360940 + 273 360950 Kr-95 1.64860E-05 1.64860E-05 360950 + 274 360960 Kr-96 3.29940E-08 3.29940E-08 360960 + 275 370840 Rb-84 6.81300E-10 1.90680E-09 370840 + 276 370841 Rb-84m 1.22550E-09 1.22550E-09 370841 + 277 370850 Rb-85 1.76760E-06 2.48270E-03 37085.82c + 278 370860 Rb-86 1.23370E-06 3.45270E-06 37086.82c + 279 370861 Rb-86m 2.21900E-06 2.21900E-06 370861 + 280 370870 Rb-87 9.95360E-05 4.88870E-03 37087.82c + 281 370880 Rb-88 3.87490E-04 6.77680E-03 370880 + 282 370890 Rb-89 1.43200E-03 8.01680E-03 370890 + 283 370900 Rb-90 3.17920E-04 5.55850E-03 370900 + 284 370901 Rb-90m 2.82360E-03 3.59810E-03 370901 + 285 370910 Rb-91 6.13620E-03 9.42990E-03 370910 + 286 370920 Rb-92 7.43290E-03 9.16280E-03 370920 + 287 370930 Rb-93 6.07020E-03 6.45510E-03 370930 + 288 370940 Rb-94 2.94290E-03 3.03430E-03 370940 + 289 370950 Rb-95 1.29640E-03 1.31240E-03 370950 + 290 370960 Rb-96 1.21670E-04 1.82530E-04 370960 + 291 370961 Rb-96m 1.21670E-04 1.21690E-04 370961 + 292 370970 Rb-97 4.96090E-05 4.96090E-05 370970 + 293 370980 Rb-98 1.55290E-06 1.55290E-06 370980 + 294 370981 Rb-98m 1.55290E-06 1.55290E-06 370981 + 295 370990 Rb-99 4.85800E-09 4.85800E-09 370990 + 296 380860 Sr-86 6.27640E-10 3.45320E-06 38086.82c + 297 380870 Sr-87 7.37260E-07 9.07220E-07 38087.82c + 298 380871 Sr-87m 1.70470E-07 1.70470E-07 380871 + 299 380880 Sr-88 2.36410E-05 6.80050E-03 38088.82c + 300 380890 Sr-89 1.25020E-04 8.14180E-03 38089.82c + 301 380900 Sr-90 8.61300E-04 9.92440E-03 38090.82c + 302 380910 Sr-91 2.36150E-03 1.17910E-02 380910 + 303 380920 Sr-92 7.62850E-03 1.68820E-02 380920 + 304 380930 Sr-93 1.08560E-02 1.75270E-02 380930 + 305 380940 Sr-94 1.77080E-02 2.05490E-02 380940 + 306 380950 Sr-95 1.36490E-02 1.48730E-02 380950 + 307 380960 Sr-96 9.01630E-03 9.24770E-03 380960 + 308 380970 Sr-97 3.19810E-03 3.23550E-03 380970 + 309 380980 Sr-98 1.12690E-03 1.12980E-03 380980 + 310 380990 Sr-99 1.93130E-04 1.93130E-04 380990 + 311 381000 Sr-100 2.96330E-05 2.96330E-05 381000 + 312 381010 Sr-101 4.26770E-08 4.26770E-08 381010 + 313 390880 Y-88 9.59000E-11 1.66580E-10 390880 + 314 390881 Y-88m 7.06800E-11 7.06800E-11 390881 + 315 390890 Y-89 1.61620E-07 8.14260E-03 39089.82c + 316 390891 Y-89m 6.98970E-07 1.48380E-06 390891 + 317 390900 Y-90 6.80130E-07 9.92600E-03 39090.82c + 318 390901 Y-90m 9.65070E-07 9.65070E-07 390901 + 319 390910 Y-91 1.19000E-05 1.18550E-02 39091.82c + 320 390911 Y-91m 5.14640E-05 6.98900E-03 390911 + 321 390920 Y-92 3.07450E-04 1.71890E-02 390920 + 322 390930 Y-93 2.10330E-04 1.91130E-02 390930 + 323 390931 Y-93m 1.37590E-03 5.76190E-03 390931 + 324 390940 Y-94 4.72850E-03 2.52770E-02 390940 + 325 390950 Y-95 1.21860E-02 2.70590E-02 390950 + 326 390960 Y-96 5.51600E-03 1.47640E-02 390960 + 327 390961 Y-96m 9.92200E-03 9.92280E-03 390961 + 328 390970 Y-97 3.35350E-03 6.20680E-03 390970 + 329 390971 Y-97m 1.14300E-02 1.43690E-02 390971 + 330 390972 Y-97m 3.07140E-03 3.07140E-03 390972 + 331 390980 Y-98 2.23370E-03 3.36350E-03 390980 + 332 390981 Y-98m 9.39430E-03 9.39430E-03 390981 + 333 390990 Y-99 7.49850E-03 7.69190E-03 390990 + 334 391000 Y-100 1.19840E-03 1.22780E-03 391000 + 335 391001 Y-100m 1.19840E-03 1.19840E-03 391001 + 336 391010 Y-101 6.42360E-04 6.42400E-04 391010 + 337 391020 Y-102 4.55690E-05 4.55690E-05 391020 + 338 391021 Y-102m 4.55690E-05 4.55690E-05 391021 + 339 391030 Y-103 1.21350E-05 1.21350E-05 391030 + 340 391040 Y-104 3.51700E-09 3.51700E-09 391040 + 341 400910 Zr-91 2.16410E-09 1.18550E-02 40091.82c + 342 400920 Zr-92 1.00060E-05 1.71990E-02 40092.82c + 343 400930 Zr-93 6.55520E-05 1.91790E-02 40093.82c + 344 400940 Zr-94 5.63850E-04 2.58410E-02 40094.82c + 345 400950 Zr-95 2.24450E-03 2.93030E-02 40095.82c + 346 400960 Zr-96 8.66460E-03 3.33630E-02 40096.82c + 347 400970 Zr-97 1.64400E-02 3.78500E-02 400970 + 348 400980 Zr-98 3.24240E-02 4.49800E-02 400980 + 349 400990 Zr-99 3.22310E-02 3.98030E-02 400990 + 350 401000 Zr-100 2.86160E-02 3.10310E-02 401000 + 351 401010 Zr-101 1.41710E-02 1.48180E-02 401010 + 352 401020 Zr-102 6.11580E-03 6.20340E-03 401020 + 353 401030 Zr-103 1.27910E-03 1.29030E-03 401030 + 354 401040 Zr-104 3.42530E-04 3.42530E-04 401040 + 355 401050 Zr-105 3.61830E-05 3.61830E-05 401050 + 356 401060 Zr-106 3.09080E-08 3.09080E-08 401060 + 357 410930 Nb-93 4.63930E-10 5.71200E-10 41093.82c + 358 410931 Nb-93m 1.07270E-10 1.07270E-10 410931 + 359 410940 Nb-94 2.23970E-06 3.81020E-06 41094.82c + 360 410941 Nb-94m 1.57840E-06 1.57840E-06 410941 + 361 410950 Nb-95 2.12540E-05 2.93120E-02 41095.82c + 362 410951 Nb-95m 4.91430E-06 3.21490E-04 410951 + 363 410960 Nb-96 1.49390E-04 1.49390E-04 410960 + 364 410970 Nb-97 8.52400E-04 3.88990E-02 410970 + 365 410971 Nb-97m 1.97100E-04 3.61730E-02 410971 + 366 410980 Nb-98 9.02210E-04 4.58820E-02 410980 + 367 410981 Nb-98m 2.72260E-03 2.72260E-03 410981 + 368 410990 Nb-99 1.12380E-02 3.67380E-02 410990 + 369 410991 Nb-99m 2.59840E-03 1.72460E-02 410991 + 370 411000 Nb-100 4.48070E-03 3.55120E-02 411000 + 371 411001 Nb-100m 1.88440E-02 1.88440E-02 411001 + 372 411010 Nb-101 3.74840E-02 5.23020E-02 411010 + 373 411020 Nb-102 1.35280E-02 1.97310E-02 411020 + 374 411021 Nb-102m 1.35280E-02 1.35280E-02 411021 + 375 411030 Nb-103 1.91930E-02 2.04830E-02 411030 + 376 411040 Nb-104 4.54730E-03 4.89030E-03 411040 + 377 411041 Nb-104m 4.54730E-03 4.54730E-03 411041 + 378 411050 Nb-105 3.56030E-03 3.59600E-03 411050 + 379 411060 Nb-106 6.41900E-04 6.41930E-04 411060 + 380 411070 Nb-107 1.48570E-04 1.48570E-04 411070 + 381 411080 Nb-108 1.47610E-05 1.47610E-05 411080 + 382 411090 Nb-109 3.39590E-06 3.39590E-06 411090 + 383 420960 Mo-96 1.93790E-06 1.51330E-04 42096.82c + 384 420970 Mo-97 1.65240E-05 3.89160E-02 42097.82c + 385 420980 Mo-98 1.94940E-04 4.88000E-02 42098.82c + 386 420990 Mo-99 1.19090E-03 5.48300E-02 42099.82c + 387 421000 Mo-100 5.85530E-03 6.02110E-02 42100.82c + 388 421010 Mo-101 1.47840E-02 6.70860E-02 421010 + 389 421020 Mo-102 3.25740E-02 6.58330E-02 421020 + 390 421030 Mo-103 3.45370E-02 5.50250E-02 421030 + 391 421040 Mo-104 4.42130E-02 5.37070E-02 421040 + 392 421050 Mo-105 2.52310E-02 2.87950E-02 421050 + 393 421060 Mo-106 1.41470E-02 1.47690E-02 421060 + 394 421070 Mo-107 5.16320E-03 5.30380E-03 421070 + 395 421080 Mo-108 1.08210E-03 1.09640E-03 421080 + 396 421090 Mo-109 2.19770E-04 2.22740E-04 421090 + 397 421100 Mo-110 3.72980E-05 3.72980E-05 421100 + 398 421110 Mo-111 5.12180E-06 5.12180E-06 421110 + 399 430980 Tc-98 1.18950E-09 1.18950E-09 430980 + 400 430990 Tc-99 5.54280E-06 5.48350E-02 43099.82c + 401 430991 Tc-99m 1.28160E-06 4.82850E-02 430991 + 402 431000 Tc-100 4.38830E-05 4.38830E-05 431000 + 403 431010 Tc-101 4.69700E-04 6.75560E-02 431010 + 404 431020 Tc-102 8.68700E-04 6.67020E-02 431020 + 405 431021 Tc-102m 8.68700E-04 8.68700E-04 431021 + 406 431030 Tc-103 6.77290E-03 6.17980E-02 431030 + 407 431040 Tc-104 1.57260E-02 6.94330E-02 431040 + 408 431050 Tc-105 2.97450E-02 5.85400E-02 431050 + 409 431060 Tc-106 2.63800E-02 4.11490E-02 431060 + 410 431070 Tc-107 2.98620E-02 3.51660E-02 431070 + 411 431080 Tc-108 1.01900E-02 1.12880E-02 431080 + 412 431090 Tc-109 7.62500E-03 7.84660E-03 431090 + 413 431100 Tc-110 2.74050E-03 2.77790E-03 431100 + 414 431110 Tc-111 6.88080E-04 6.93150E-04 431110 + 415 431120 Tc-112 8.25840E-05 8.25840E-05 431120 + 416 431130 Tc-113 1.07780E-05 1.07780E-05 431130 + 417 431140 Tc-114 9.23420E-07 9.23420E-07 431140 + 418 441010 Ru-101 6.09560E-06 6.75620E-02 44101.82c + 419 441020 Ru-102 3.71790E-05 6.76080E-02 44102.82c + 420 441030 Ru-103 7.47800E-05 6.20540E-02 44103.82c + 421 441031 Ru-103m 1.80530E-04 1.80530E-04 441031 + 422 441040 Ru-104 1.67740E-03 7.11100E-02 44104.82c + 423 441050 Ru-105 4.80000E-03 6.33400E-02 44105.82c + 424 441060 Ru-106 1.20370E-02 5.31860E-02 44106.82c + 425 441070 Ru-107 1.94240E-02 5.45900E-02 441070 + 426 441080 Ru-108 1.81190E-02 2.94130E-02 441080 + 427 441090 Ru-109 2.17210E-02 2.95620E-02 441090 + 428 441100 Ru-110 2.02580E-02 2.30350E-02 441100 + 429 441110 Ru-111 8.57130E-03 9.26570E-03 441110 + 430 441120 Ru-112 2.93040E-03 3.01250E-03 441120 + 431 441130 Ru-113 3.03390E-04 4.65150E-04 441130 + 432 441131 Ru-113m 3.03390E-04 3.03390E-04 441131 + 433 441140 Ru-114 9.66420E-05 9.75050E-05 441140 + 434 441150 Ru-115 7.06450E-06 7.06450E-06 441150 + 435 441160 Ru-116 2.97820E-06 2.97820E-06 441160 + 436 451030 Rh-103 4.83090E-10 6.20540E-02 45103.82c + 437 451031 Rh-103m 3.16010E-09 6.13100E-02 451031 + 438 451040 Rh-104 1.65450E-06 6.64090E-06 451040 + 439 451041 Rh-104m 4.99290E-06 4.99290E-06 451041 + 440 451050 Rh-105 6.90160E-05 6.34190E-02 45105.82c + 441 451051 Rh-105m 1.05510E-05 1.79910E-02 451051 + 442 451060 Rh-106 1.03800E-04 5.32900E-02 451060 + 443 451061 Rh-106m 2.43120E-04 2.43120E-04 451061 + 444 451070 Rh-107 1.67600E-03 5.62660E-02 451070 + 445 451080 Rh-108 6.32480E-04 3.00450E-02 451080 + 446 451081 Rh-108m 1.90860E-03 1.90860E-03 451081 + 447 451090 Rh-109 7.19900E-03 3.67610E-02 451090 + 448 451100 Rh-110 1.06200E-02 3.36540E-02 451100 + 449 451101 Rh-110m 2.83480E-04 2.83480E-04 451101 + 450 451110 Rh-111 1.50550E-02 2.43210E-02 451110 + 451 451120 Rh-112 4.71740E-03 7.72990E-03 451120 + 452 451121 Rh-112m 4.71740E-03 4.71740E-03 451121 + 453 451130 Rh-113 6.22810E-03 6.84490E-03 451130 + 454 451140 Rh-114 8.54750E-04 9.52270E-04 451140 + 455 451141 Rh-114m 8.54750E-04 8.54750E-04 451141 + 456 451150 Rh-115 5.43900E-04 5.50980E-04 451150 + 457 451160 Rh-116 3.38130E-05 3.67590E-05 451160 + 458 451161 Rh-116m 7.91970E-05 7.91970E-05 451161 + 459 451170 Rh-117 2.93310E-05 2.93310E-05 451170 + 460 451180 Rh-118 5.01400E-06 5.01400E-06 451180 + 461 451190 Rh-119 3.99970E-06 3.99970E-06 451190 + 462 461050 Pd-105 1.03410E-06 6.34200E-02 46105.82c + 463 461060 Pd-106 3.65730E-06 5.35370E-02 46106.82c + 464 461070 Pd-107 8.31120E-06 5.62900E-02 46107.82c + 465 461071 Pd-107m 1.56200E-05 1.56200E-05 461071 + 466 461080 Pd-108 1.43530E-04 3.20980E-02 46108.82c + 467 461090 Pd-109 2.31360E-04 3.74280E-02 461090 + 468 461091 Pd-109m 4.34820E-04 1.88150E-02 461091 + 469 461100 Pd-110 2.02690E-03 3.59650E-02 46110.82c + 470 461110 Pd-111 1.14340E-03 2.70060E-02 461110 + 471 461111 Pd-111m 2.14880E-03 2.24610E-03 461111 + 472 461120 Pd-112 4.42740E-03 1.68750E-02 461120 + 473 461130 Pd-113 1.27800E-03 1.12080E-02 461130 + 474 461131 Pd-113m 3.08540E-03 3.08540E-03 461131 + 475 461140 Pd-114 3.71100E-03 5.51800E-03 461140 + 476 461150 Pd-115 6.08570E-04 1.17750E-03 461150 + 477 461151 Pd-115m 1.14370E-03 1.22370E-03 461151 + 478 461160 Pd-116 7.86870E-04 9.02830E-04 461160 + 479 461170 Pd-117 6.46920E-05 2.15750E-04 461170 + 480 461171 Pd-117m 1.21580E-04 1.21580E-04 461171 + 481 461180 Pd-118 7.04710E-05 7.53390E-05 461180 + 482 461190 Pd-119 1.10030E-05 1.50030E-05 461190 + 483 461200 Pd-120 5.97870E-06 5.97870E-06 461200 + 484 461210 Pd-121 1.07230E-06 1.07230E-06 461210 + 485 461220 Pd-122 1.09280E-06 1.09280E-06 461220 + 486 461230 Pd-123 4.68170E-08 4.68170E-08 461230 + 487 461240 Pd-124 3.54380E-09 3.54380E-09 461240 + 488 471080 Ag-108 4.60050E-10 5.53800E-10 471080 + 489 471081 Ag-108m 1.07760E-09 1.07760E-09 471081 + 490 471090 Ag-109 5.62560E-07 3.74320E-02 47109.82c + 491 471091 Ag-109m 3.67990E-06 3.74130E-02 471091 + 492 471100 Ag-110 7.32290E-06 7.55620E-06 471100 + 493 471101 Ag-110m 1.71520E-05 1.71520E-05 47510.82c + 494 471110 Ag-111 2.02110E-05 2.76280E-02 47111.82c + 495 471111 Ag-111m 1.32210E-04 2.73790E-02 471111 + 496 471120 Ag-112 3.42600E-04 1.72170E-02 471120 + 497 471130 Ag-113 1.11050E-04 7.92050E-03 471130 + 498 471131 Ag-113m 7.26470E-04 1.14590E-02 471131 + 499 471140 Ag-114 1.78700E-04 6.44830E-03 471140 + 500 471141 Ag-114m 7.51540E-04 7.51540E-04 471141 + 501 471150 Ag-115 1.52050E-04 1.52370E-03 471150 + 502 471151 Ag-115m 9.94650E-04 2.43840E-03 471151 + 503 471160 Ag-116 2.01850E-04 1.13310E-03 471160 + 504 471161 Ag-116m 4.72790E-04 4.72790E-04 471161 + 505 471170 Ag-117 6.50240E-05 2.04890E-04 471170 + 506 471171 Ag-117m 4.25360E-04 5.33230E-04 471171 + 507 471180 Ag-118 3.74130E-05 1.70910E-04 471180 + 508 471181 Ag-118m 1.57350E-04 1.68120E-04 471181 + 509 471190 Ag-119 1.66070E-05 2.41080E-05 471190 + 510 471191 Ag-119m 1.08630E-04 1.16130E-04 471191 + 511 471200 Ag-120 1.27770E-05 2.35840E-05 471200 + 512 471201 Ag-120m 1.81310E-05 2.11200E-05 471201 + 513 471210 Ag-121 2.14610E-05 2.25300E-05 471210 + 514 471220 Ag-122 7.47750E-06 8.57030E-06 471220 + 515 471221 Ag-122m 6.73550E-06 6.73550E-06 471221 + 516 471230 Ag-123 1.51840E-05 1.52310E-05 471230 + 517 471240 Ag-124 2.84900E-06 4.13580E-06 471240 + 518 471241 Ag-124m 2.56640E-06 2.56640E-06 471241 + 519 471250 Ag-125 2.23400E-06 2.23400E-06 471250 + 520 471260 Ag-126 6.00940E-08 6.00940E-08 471260 + 521 471270 Ag-127 2.44070E-09 2.44070E-09 471270 + 522 481110 Cd-111 3.84670E-09 2.77650E-02 48111.82c + 523 481111 Cd-111m 1.25850E-08 1.25850E-08 481111 + 524 481120 Cd-112 5.48550E-06 1.72230E-02 48112.82c + 525 481130 Cd-113 6.39770E-06 1.19160E-02 48113.82c + 526 481131 Cd-113m 2.09310E-05 1.57870E-04 481131 + 527 481140 Cd-114 7.68480E-05 6.52510E-03 48114.82c + 528 481150 Cd-115 3.19990E-05 3.33810E-03 481150 + 529 481151 Cd-115m 1.04690E-04 2.48570E-04 48515.82c + 530 481160 Cd-116 1.94940E-04 1.77240E-03 48116.82c + 531 481170 Cd-117 3.33310E-05 5.80610E-04 481170 + 532 481171 Cd-117m 1.09050E-04 2.67890E-04 481171 + 533 481180 Cd-118 1.95430E-04 4.65530E-04 481180 + 534 481190 Cd-119 4.00280E-05 1.68220E-04 481190 + 535 481191 Cd-119m 9.66320E-05 1.08690E-04 481191 + 536 481200 Cd-120 1.68350E-04 2.05240E-04 481200 + 537 481210 Cd-121 4.27750E-05 6.29510E-05 481210 + 538 481211 Cd-121m 1.03260E-04 1.05620E-04 481211 + 539 481220 Cd-122 1.91780E-04 2.07090E-04 481220 + 540 481230 Cd-123 4.49250E-05 5.73880E-05 481230 + 541 481231 Cd-123m 1.08460E-04 1.11230E-04 481231 + 542 481240 Cd-124 2.44520E-04 2.49940E-04 481240 + 543 481250 Cd-125 3.77990E-05 3.89160E-05 481250 + 544 481251 Cd-125m 9.12510E-05 9.23680E-05 481251 + 545 481260 Cd-126 8.74740E-05 8.75340E-05 481260 + 546 481270 Cd-127 2.87580E-05 2.87600E-05 481270 + 547 481280 Cd-128 4.85990E-06 4.85990E-06 481280 + 548 481290 Cd-129 9.28110E-09 9.28110E-09 481290 + 549 481291 Cd-129m 2.24060E-08 2.24060E-08 481291 + 550 481300 Cd-130 7.18000E-10 7.18000E-10 481300 + 551 491130 In-113 8.42490E-10 1.57650E-04 49113.82c + 552 491131 In-113m 1.94810E-10 1.94810E-10 491131 + 553 491140 In-114 6.31780E-09 2.47130E-08 491140 + 554 491141 In-114m 9.68360E-09 1.90630E-08 491141 + 555 491142 In-114m 9.37900E-09 9.37900E-09 491142 + 556 491150 In-115 4.05240E-07 3.42030E-03 49115.82c + 557 491151 In-115m 9.37010E-08 3.33820E-03 491151 + 558 491160 In-116 7.40850E-07 7.40850E-07 491160 + 559 491161 In-116m 1.13550E-06 2.23540E-06 491161 + 560 491162 In-116m 1.09980E-06 1.09980E-06 491162 + 561 491170 In-117 9.00650E-06 5.74860E-04 491170 + 562 491171 In-117m 2.08250E-06 5.38250E-04 491171 + 563 491180 In-118 5.48080E-06 4.71010E-04 491180 + 564 491181 In-118m 8.40060E-06 1.64230E-05 491181 + 565 491182 In-118m 8.13640E-06 8.13640E-06 491182 + 566 491190 In-119 2.43180E-05 1.57950E-04 491190 + 567 491191 In-119m 5.62290E-06 1.57720E-04 491191 + 568 491200 In-120 1.65710E-05 2.21810E-04 491200 + 569 491201 In-120m 1.65710E-05 1.65710E-05 491201 + 570 491202 In-120m 1.65710E-05 1.65710E-05 491202 + 571 491210 In-121 9.12590E-05 2.18830E-04 491210 + 572 491211 In-121m 2.11010E-05 6.28510E-05 491211 + 573 491220 In-122 4.96240E-05 2.56710E-04 491220 + 574 491221 In-122m 3.52080E-05 3.52080E-05 491221 + 575 491222 In-122m 3.52080E-05 3.52080E-05 491222 + 576 491230 In-123 2.41960E-04 3.69610E-04 491230 + 577 491231 In-123m 5.59470E-05 9.69170E-05 491231 + 578 491240 In-124 2.52850E-04 5.02790E-04 491240 + 579 491241 In-124m 2.27770E-04 2.27770E-04 491241 + 580 491250 In-125 9.67090E-04 1.07810E-03 491250 + 581 491251 In-125m 2.23610E-04 2.43900E-04 491251 + 582 491260 In-126 7.19440E-04 8.06980E-04 491260 + 583 491261 In-126m 6.48060E-04 6.48060E-04 491261 + 584 491270 In-127 1.07100E-03 1.07100E-03 491270 + 585 491271 In-127m 2.47630E-04 2.76390E-04 491271 + 586 491280 In-128 1.42580E-04 2.05480E-04 491280 + 587 491281 In-128m 5.80400E-05 6.29000E-05 491281 + 588 491282 In-128m 1.80720E-04 1.80720E-04 491282 + 589 491290 In-129 1.47200E-04 1.47220E-04 491290 + 590 491291 In-129m 3.40350E-05 3.40440E-05 491291 + 591 491300 In-130 1.20950E-05 1.20960E-05 491300 + 592 491301 In-130m 1.35090E-05 1.35090E-05 491301 + 593 491302 In-130m 2.29850E-05 2.29850E-05 491302 + 594 491310 In-131 2.97490E-06 3.00520E-06 491310 + 595 491311 In-131m 2.97490E-06 2.97490E-06 491311 + 596 491312 In-131m 2.97490E-06 2.97490E-06 491312 + 597 491320 In-132 1.32830E-08 1.32830E-08 491320 + 598 501160 Sn-116 1.73350E-09 2.97790E-06 50116.82c + 599 501170 Sn-117 6.46050E-09 8.59620E-04 50117.82c + 600 501171 Sn-117m 2.11360E-08 1.97970E-06 501171 + 601 501180 Sn-118 4.01840E-07 4.87950E-04 50118.82c + 602 501190 Sn-119 4.67870E-07 3.08840E-04 50119.82c + 603 501191 Sn-119m 1.53070E-06 1.44230E-04 501191 + 604 501200 Sn-120 1.99160E-06 2.56980E-04 50120.82c + 605 501210 Sn-121 2.19730E-06 2.81690E-04 501210 + 606 501211 Sn-121m 5.30440E-06 3.00950E-05 501211 + 607 501220 Sn-122 4.14330E-05 3.68640E-04 50122.82c + 608 501230 Sn-123 6.33650E-05 9.15450E-05 50123.82c + 609 501231 Sn-123m 2.62480E-05 4.64590E-04 501231 + 610 501240 Sn-124 3.64020E-04 1.09460E-03 50124.82c + 611 501250 Sn-125 6.05480E-04 7.87590E-04 50125.82c + 612 501251 Sn-125m 2.50800E-04 1.39070E-03 501251 + 613 501260 Sn-126 3.01020E-03 4.46710E-03 50126.82c + 614 501270 Sn-127 2.79840E-03 3.21590E-03 501270 + 615 501271 Sn-127m 1.15920E-03 2.08720E-03 501271 + 616 501280 Sn-128 1.45990E-03 5.26550E-03 501280 + 617 501281 Sn-128m 3.41940E-03 3.60010E-03 501281 + 618 501290 Sn-129 1.10130E-03 1.26690E-03 501290 + 619 501291 Sn-129m 2.65850E-03 2.67420E-03 501291 + 620 501300 Sn-130 8.87430E-04 9.19040E-04 501300 + 621 501301 Sn-130m 2.07860E-03 2.09560E-03 501301 + 622 501310 Sn-131 3.43340E-04 3.49100E-04 501310 + 623 501311 Sn-131m 8.28860E-04 8.31970E-04 501311 + 624 501320 Sn-132 3.45450E-04 3.45460E-04 501320 + 625 501330 Sn-133 1.85830E-05 1.85830E-05 501330 + 626 501340 Sn-134 1.95980E-06 1.95980E-06 501340 + 627 501350 Sn-135 2.01790E-09 2.01790E-09 501350 + 628 511180 Sb-118 1.97800E-11 1.97800E-11 511180 + 629 511181 Sb-118m 2.80670E-11 2.80670E-11 511181 + 630 511190 Sb-119 1.43120E-09 1.88620E-09 511190 + 631 511191 Sb-119m 4.54950E-10 4.54950E-10 511191 + 632 511200 Sb-120 1.53250E-08 1.53250E-08 511200 + 633 511201 Sb-120m 2.17460E-08 2.17460E-08 511201 + 634 511210 Sb-121 7.76660E-07 2.89210E-04 51121.82c + 635 511220 Sb-122 1.53600E-06 3.27720E-06 511220 + 636 511221 Sb-122m 1.74120E-06 1.74120E-06 511221 + 637 511230 Sb-123 5.41670E-06 5.61560E-04 51123.82c + 638 511240 Sb-124 1.04290E-05 2.44970E-05 51124.82c + 639 511241 Sb-124m 7.97390E-06 1.87590E-05 511241 + 640 511242 Sb-124m 1.07850E-05 1.07850E-05 511242 + 641 511250 Sb-125 8.67880E-05 2.26500E-03 51125.82c + 642 511260 Sb-126 1.24170E-04 1.53830E-04 51126.82c + 643 511261 Sb-126m 9.18090E-05 2.11880E-04 511261 + 644 511262 Sb-126m 1.20070E-04 1.20070E-04 511262 + 645 511270 Sb-127 1.53070E-03 6.83380E-03 511270 + 646 511280 Sb-128 9.93400E-04 6.31990E-03 511280 + 647 511281 Sb-128m 1.69510E-03 1.69510E-03 511281 + 648 511290 Sb-129 4.69890E-03 7.93410E-03 511290 + 649 511291 Sb-129m 2.87140E-03 4.20850E-03 511291 + 650 511300 Sb-130 5.09400E-03 7.06080E-03 511300 + 651 511301 Sb-130m 5.09400E-03 6.14180E-03 511301 + 652 511310 Sb-131 1.70860E-02 1.82670E-02 511310 + 653 511320 Sb-132 6.11220E-03 6.45770E-03 511320 + 654 511321 Sb-132m 4.50480E-03 4.50480E-03 511321 + 655 511330 Sb-133 4.97310E-03 4.99200E-03 511330 + 656 511340 Sb-134 1.98720E-04 2.00340E-04 511340 + 657 511341 Sb-134m 4.65440E-04 4.65440E-04 511341 + 658 511350 Sb-135 8.96820E-05 8.96840E-05 511350 + 659 511360 Sb-136 4.84150E-06 4.84150E-06 511360 + 660 511370 Sb-137 2.10020E-08 2.10020E-08 511370 + 661 521200 Te-120 9.31260E-12 9.31260E-12 52120.82c + 662 521210 Te-121 7.35290E-11 2.86910E-10 521210 + 663 521211 Te-121m 2.40560E-10 2.40560E-10 521211 + 664 521220 Te-122 1.80550E-08 3.21000E-06 52122.82c + 665 521240 Te-124 8.14650E-11 2.91870E-05 52124.82c + 666 521250 Te-125 2.61440E-07 2.26620E-03 52125.82c + 667 521251 Te-125m 8.55360E-07 5.07700E-04 521251 + 668 521260 Te-126 1.50960E-05 3.51150E-04 52126.82c + 669 521270 Te-127 1.67750E-05 6.86300E-03 521270 + 670 521271 Te-127m 4.04970E-05 1.16670E-03 52527.82c + 671 521280 Te-128 3.94260E-04 8.34840E-03 52128.82c + 672 521290 Te-129 4.52740E-04 1.08730E-02 521290 + 673 521291 Te-129m 1.09300E-03 5.90310E-03 52529.82c + 674 521300 Te-130 6.14570E-03 1.93480E-02 52130.82c + 675 521310 Te-131 4.01540E-03 2.31630E-02 521310 + 676 521311 Te-131m 9.69360E-03 1.11560E-02 521311 + 677 521320 Te-132 3.02570E-02 4.12190E-02 52132.82c + 678 521330 Te-133 8.82980E-03 1.68400E-02 521330 + 679 521331 Te-133m 2.13160E-02 2.21800E-02 521331 + 680 521340 Te-134 2.13770E-02 2.20560E-02 521340 + 681 521350 Te-135 5.10300E-03 5.17940E-03 521350 + 682 521360 Te-136 1.53090E-03 1.53490E-03 521360 + 683 521370 Te-137 2.24920E-04 2.24930E-04 521370 + 684 521380 Te-138 4.14240E-05 4.14240E-05 521380 + 685 521390 Te-139 1.28120E-06 1.28120E-06 521390 + 686 521400 Te-140 1.85780E-09 1.85780E-09 521400 + 687 531270 I-127 1.97930E-06 6.89300E-03 53127.82c + 688 531280 I-128 2.08190E-06 2.08190E-06 531280 + 689 531290 I-129 3.17070E-05 1.30890E-02 53129.82c + 690 531300 I-130 1.17490E-04 1.59620E-04 53130.82c + 691 531301 I-130m 5.01610E-05 5.01610E-05 531301 + 692 531310 I-131 1.60150E-03 3.35780E-02 53131.82c + 693 531320 I-132 3.18120E-03 4.64170E-02 531320 + 694 531321 I-132m 2.34450E-03 2.34450E-03 531321 + 695 531330 I-133 1.23490E-02 5.50330E-02 531330 + 696 531331 I-133m 7.54620E-03 7.54620E-03 531331 + 697 531340 I-134 1.75320E-02 5.22120E-02 531340 + 698 531341 I-134m 1.29210E-02 1.29210E-02 531341 + 699 531350 I-135 3.97590E-02 4.49380E-02 53135.82c + 700 531360 I-136 5.85150E-03 7.38980E-03 531360 + 701 531361 I-136m 1.37060E-02 1.37090E-02 531361 + 702 531370 I-137 1.11290E-02 1.13500E-02 531370 + 703 531380 I-138 2.75950E-03 2.79830E-03 531380 + 704 531390 I-139 1.07900E-03 1.08030E-03 531390 + 705 531400 I-140 1.03030E-04 1.03030E-04 531400 + 706 531410 I-141 1.59890E-05 1.59890E-05 531410 + 707 531420 I-142 1.10280E-08 1.10280E-08 531420 + 708 541290 Xe-129 2.81690E-10 1.20330E-09 54129.82c + 709 541291 Xe-129m 9.21610E-10 9.21610E-10 541291 + 710 541300 Xe-130 1.56220E-06 1.69210E-04 54130.82c + 711 541310 Xe-131 6.67640E-06 3.36000E-02 54131.82c + 712 541311 Xe-131m 1.61180E-05 3.80830E-04 541311 + 713 541320 Xe-132 1.12220E-04 4.69850E-02 54132.82c + 714 541321 Xe-132m 1.27200E-04 1.27200E-04 541321 + 715 541330 Xe-133 3.52770E-04 5.62380E-02 54133.82c + 716 541331 Xe-133m 8.51630E-04 2.41810E-03 541331 + 717 541340 Xe-134 2.13010E-03 5.96290E-02 54134.82c + 718 541341 Xe-134m 4.98930E-03 5.28650E-03 541341 + 719 541350 Xe-135 6.00650E-03 6.53140E-02 54135.82c + 720 541351 Xe-135m 1.45000E-02 2.19190E-02 541351 + 721 541360 Xe-136 5.05680E-02 7.24040E-02 54136.82c + 722 541370 Xe-137 4.16120E-02 5.23720E-02 541370 + 723 541380 Xe-138 3.44520E-02 3.72080E-02 541380 + 724 541390 Xe-139 1.52460E-02 1.62300E-02 541390 + 725 541400 Xe-140 6.25540E-03 6.35220E-03 541400 + 726 541410 Xe-141 1.63820E-03 1.65080E-03 541410 + 727 541420 Xe-142 3.40740E-04 3.40750E-04 541420 + 728 541430 Xe-143 4.17870E-05 4.17870E-05 541430 + 729 541440 Xe-144 3.53930E-06 3.53930E-06 541440 + 730 541450 Xe-145 9.99800E-10 9.99800E-10 541450 + 731 551320 Cs-132 2.65650E-08 2.65650E-08 551320 + 732 551330 Cs-133 6.55440E-06 5.62440E-02 55133.82c + 733 551340 Cs-134 3.27300E-05 5.68520E-05 55134.82c + 734 551341 Cs-134m 2.41220E-05 2.41220E-05 551341 + 735 551350 Cs-135 3.42760E-04 6.59980E-02 55135.82c + 736 551351 Cs-135m 2.09460E-04 2.09460E-04 551351 + 737 551360 Cs-136 2.18050E-03 2.81950E-03 55136.82c + 738 551361 Cs-136m 1.27790E-03 1.27790E-03 551361 + 739 551370 Cs-137 1.79690E-02 7.03410E-02 55137.82c + 740 551380 Cs-138 1.15790E-02 6.20940E-02 551380 + 741 551381 Cs-138m 1.64290E-02 1.64290E-02 551381 + 742 551390 Cs-139 3.73550E-02 5.35850E-02 551390 + 743 551400 Cs-140 2.04410E-02 2.67940E-02 551400 + 744 551410 Cs-141 2.00630E-02 2.17140E-02 551410 + 745 551420 Cs-142 7.81470E-03 8.15460E-03 551420 + 746 551430 Cs-143 2.83690E-03 2.87840E-03 551430 + 747 551440 Cs-144 2.60460E-04 3.94120E-04 551440 + 748 551441 Cs-144m 2.60460E-04 2.60460E-04 551441 + 749 551450 Cs-145 1.19310E-04 1.19310E-04 551450 + 750 551460 Cs-146 9.75220E-06 9.75220E-06 551460 + 751 551470 Cs-147 4.48640E-09 4.48640E-09 551470 + 752 561340 Ba-134 6.54530E-09 5.68580E-05 56134.82c + 753 561350 Ba-135 5.46810E-07 1.86690E-06 56135.82c + 754 561351 Ba-135m 1.32010E-06 1.32010E-06 561351 + 755 561360 Ba-136 1.65210E-05 3.51360E-03 56136.82c + 756 561361 Ba-136m 3.86950E-05 3.86950E-05 561361 + 757 561370 Ba-137 2.06750E-04 7.10470E-02 56137.82c + 758 561371 Ba-137m 4.99120E-04 6.69010E-02 561371 + 759 561380 Ba-138 5.78310E-03 7.09990E-02 56138.82c + 760 561390 Ba-139 1.37560E-02 6.73410E-02 561390 + 761 561400 Ba-140 2.38530E-02 5.06470E-02 56140.82c + 762 561410 Ba-141 2.63620E-02 4.80760E-02 561410 + 763 561420 Ba-142 3.47790E-02 4.29810E-02 561420 + 764 561430 Ba-143 2.08070E-02 2.36510E-02 561430 + 765 561440 Ba-144 1.15760E-02 1.21050E-02 561440 + 766 561450 Ba-145 4.17030E-03 4.27390E-03 561450 + 767 561460 Ba-146 1.13330E-03 1.14170E-03 561460 + 768 561470 Ba-147 1.88330E-04 1.88330E-04 561470 + 769 561480 Ba-148 2.81990E-05 2.81990E-05 561480 + 770 561490 Ba-149 2.60250E-06 2.60250E-06 561490 + 771 561500 Ba-150 4.81300E-10 4.81300E-10 561500 + 772 571370 La-137 1.07250E-06 1.07250E-06 571370 + 773 571380 La-138 1.89460E-05 1.89460E-05 57138.82c + 774 571390 La-139 3.16030E-04 6.76570E-02 57139.82c + 775 571400 La-140 9.69550E-04 5.16170E-02 57140.82c + 776 571410 La-141 3.90140E-03 5.19780E-02 571410 + 777 571420 La-142 6.48100E-03 4.94620E-02 571420 + 778 571430 La-143 1.55180E-02 3.91690E-02 571430 + 779 571440 La-144 1.50030E-02 2.71080E-02 571440 + 780 571450 La-145 1.80920E-02 2.23660E-02 571450 + 781 571460 La-146 2.78550E-03 3.92720E-03 571460 + 782 571461 La-146m 5.01050E-03 5.01050E-03 571461 + 783 571470 La-147 4.48880E-03 4.67720E-03 571470 + 784 571480 La-148 1.39440E-03 1.42250E-03 571480 + 785 571490 La-149 3.89730E-04 3.92320E-04 571490 + 786 571500 La-150 6.20030E-05 6.20040E-05 571500 + 787 571510 La-151 6.11440E-06 6.11440E-06 571510 + 788 571520 La-152 1.54000E-09 1.54000E-09 571520 + 789 581390 Ce-139 1.80650E-09 6.16750E-09 581390 + 790 581391 Ce-139m 4.36100E-09 4.36100E-09 581391 + 791 581400 Ce-140 1.97940E-05 5.16360E-02 58140.82c + 792 581410 Ce-141 1.28040E-04 5.21060E-02 58141.82c + 793 581420 Ce-142 6.20300E-04 5.00820E-02 58142.82c + 794 581430 Ce-143 1.65420E-03 4.08230E-02 58143.82c + 795 581440 Ce-144 5.30200E-03 3.24100E-02 58144.82c + 796 581450 Ce-145 1.05800E-02 3.29460E-02 581450 + 797 581460 Ce-146 1.42230E-02 2.31610E-02 581460 + 798 581470 Ce-147 1.21390E-02 1.68160E-02 581470 + 799 581480 Ce-148 1.21240E-02 1.35520E-02 581480 + 800 581490 Ce-149 6.27140E-03 6.65990E-03 581490 + 801 581500 Ce-150 2.85930E-03 2.91960E-03 581500 + 802 581510 Ce-151 7.12950E-04 7.19060E-04 581510 + 803 581520 Ce-152 1.31400E-04 1.31400E-04 581520 + 804 581530 Ce-153 1.29370E-05 1.29370E-05 581530 + 805 581540 Ce-154 8.42770E-09 8.42770E-09 581540 + 806 581550 Ce-155 1.01950E-10 1.01950E-10 581550 + 807 591420 Pr-142 3.18380E-07 1.06410E-06 59142.82c + 808 591421 Pr-142m 7.45720E-07 7.45720E-07 591421 + 809 591430 Pr-143 1.63080E-05 4.08390E-02 59143.82c + 810 591440 Pr-144 4.92040E-06 3.24580E-02 591440 + 811 591441 Pr-144m 4.37010E-05 4.90940E-04 591441 + 812 591450 Pr-145 3.94230E-04 3.33400E-02 591450 + 813 591460 Pr-146 9.65510E-04 2.41260E-02 591460 + 814 591470 Pr-147 2.58200E-03 1.93980E-02 591470 + 815 591480 Pr-148 8.10570E-04 1.43630E-02 591480 + 816 591481 Pr-148m 3.40890E-03 3.40890E-03 591481 + 817 591490 Pr-149 6.98130E-03 1.36410E-02 591490 + 818 591500 Pr-150 6.23770E-03 9.15730E-03 591500 + 819 591510 Pr-151 5.26380E-03 5.98290E-03 591510 + 820 591520 Pr-152 1.79800E-03 1.92950E-03 591520 + 821 591530 Pr-153 5.91230E-04 6.04090E-04 591530 + 822 591540 Pr-154 1.18600E-04 1.18610E-04 591540 + 823 591550 Pr-155 2.00320E-05 2.00320E-05 591550 + 824 591560 Pr-156 2.70730E-06 2.70730E-06 591560 + 825 591570 Pr-157 3.07970E-10 3.07970E-10 591570 + 826 601440 Nd-144 4.69840E-09 3.24580E-02 60144.82c + 827 601450 Nd-145 7.02340E-06 3.33470E-02 60145.82c + 828 601460 Nd-146 4.78260E-05 2.41740E-02 60146.82c + 829 601470 Nd-147 1.65590E-04 1.95640E-02 60147.82c + 830 601480 Nd-148 7.07100E-04 1.84790E-02 60148.82c + 831 601490 Nd-149 1.70710E-03 1.53480E-02 601490 + 832 601500 Nd-150 3.92640E-03 1.30840E-02 60150.82c + 833 601510 Nd-151 5.25670E-03 1.12400E-02 601510 + 834 601520 Nd-152 5.86590E-03 7.79540E-03 601520 + 835 601530 Nd-153 3.69640E-03 4.30050E-03 601530 + 836 601540 Nd-154 2.03460E-03 2.15320E-03 601540 + 837 601550 Nd-155 6.02920E-04 6.23030E-04 601550 + 838 601560 Nd-156 1.86520E-04 1.89150E-04 601560 + 839 601570 Nd-157 2.30800E-05 2.30800E-05 601570 + 840 601580 Nd-158 3.96910E-06 3.96910E-06 601580 + 841 601590 Nd-159 1.11860E-09 1.11860E-09 601590 + 842 601600 Nd-160 2.08740E-11 2.08740E-11 601600 + 843 611470 Pm-147 7.59600E-07 1.95650E-02 61147.82c + 844 611480 Pm-148 4.82040E-07 5.38490E-07 61148.82c + 845 611481 Pm-148m 1.12910E-06 1.12910E-06 61548.82c + 846 611490 Pm-149 2.51150E-05 1.53730E-02 61149.82c + 847 611500 Pm-150 1.15640E-04 1.15640E-04 611500 + 848 611510 Pm-151 5.31350E-04 1.17710E-02 61151.82c + 849 611520 Pm-152 1.87080E-04 7.98250E-03 611520 + 850 611521 Pm-152m 3.73570E-04 3.73570E-04 611521 + 851 611522 Pm-152m 4.13200E-04 4.13200E-04 611522 + 852 611530 Pm-153 1.71320E-03 6.01370E-03 611530 + 853 611540 Pm-154 8.93300E-04 3.04650E-03 611540 + 854 611541 Pm-154m 8.93300E-04 8.93300E-04 611541 + 855 611550 Pm-155 1.66020E-03 2.28320E-03 611550 + 856 611560 Pm-156 9.12890E-04 1.10200E-03 611560 + 857 611570 Pm-157 3.97960E-04 4.21040E-04 611570 + 858 611580 Pm-158 1.21090E-04 1.25060E-04 611580 + 859 611590 Pm-159 2.29310E-05 2.29320E-05 611590 + 860 611600 Pm-160 4.07960E-06 4.07960E-06 611600 + 861 611610 Pm-161 3.54540E-09 3.54540E-09 611610 + 862 611620 Pm-162 3.82790E-11 3.82790E-11 611620 + 863 621490 Sm-149 1.83540E-09 1.53730E-02 62149.82c + 864 621500 Sm-150 2.77020E-06 1.18410E-04 62150.82c + 865 621510 Sm-151 2.95060E-05 1.18000E-02 62151.82c + 866 621520 Sm-152 7.47860E-05 8.84400E-03 62152.82c + 867 621530 Sm-153 8.47270E-05 6.30300E-03 62153.82c + 868 621531 Sm-153m 2.04540E-04 2.04540E-04 621531 + 869 621540 Sm-154 7.15130E-04 4.65490E-03 62154.82c + 870 621550 Sm-155 1.05280E-03 3.33600E-03 621550 + 871 621560 Sm-156 1.50740E-03 2.60940E-03 621560 + 872 621570 Sm-157 1.13150E-03 1.55250E-03 621570 + 873 621580 Sm-158 8.26440E-04 9.51500E-04 621580 + 874 621590 Sm-159 3.36790E-04 3.59730E-04 621590 + 875 621600 Sm-160 1.24260E-04 1.28330E-04 621600 + 876 621610 Sm-161 3.84130E-05 3.84170E-05 621610 + 877 621620 Sm-162 4.20700E-06 4.20700E-06 621620 + 878 621630 Sm-163 7.50690E-09 7.50690E-09 621630 + 879 621640 Sm-164 1.25340E-10 1.25340E-10 621640 + 880 621650 Sm-165 1.77350E-12 1.77350E-12 621650 + 881 631520 Eu-152 3.08480E-09 6.52530E-09 63152.82c + 882 631521 Eu-152m 7.34710E-10 7.34710E-10 631521 + 883 631522 Eu-152m 3.44050E-09 3.44050E-09 631522 + 884 631530 Eu-153 1.84510E-06 6.30480E-03 63153.82c + 885 631540 Eu-154 6.11800E-06 1.16290E-05 63154.82c + 886 631541 Eu-154m 5.51100E-06 5.51100E-06 631541 + 887 631550 Eu-155 4.35510E-05 3.37960E-03 63155.82c + 888 631560 Eu-156 9.65170E-05 2.70600E-03 63156.82c + 889 631570 Eu-157 2.37030E-04 1.78960E-03 63157.82c + 890 631580 Eu-158 2.64820E-04 1.21630E-03 631580 + 891 631590 Eu-159 3.49360E-04 7.09090E-04 631590 + 892 631600 Eu-160 2.56830E-04 3.85160E-04 631600 + 893 631610 Eu-161 1.66190E-04 2.04610E-04 631610 + 894 631620 Eu-162 6.47970E-05 6.90040E-05 631620 + 895 631630 Eu-163 1.25630E-05 1.25700E-05 631630 + 896 631640 Eu-164 8.11130E-07 8.11250E-07 631640 + 897 631650 Eu-165 1.16390E-08 1.16410E-08 631650 + 898 631660 Eu-166 2.66390E-10 2.66390E-10 631660 + 899 631670 Eu-167 4.06510E-12 4.06510E-12 631670 + 900 641540 Gd-154 8.42770E-10 1.16280E-05 64154.82c + 901 641550 Gd-155 6.71910E-09 3.37960E-03 64155.82c + 902 641551 Gd-155m 1.62210E-08 1.62210E-08 641551 + 903 641560 Gd-156 4.50270E-06 2.71050E-03 64156.82c + 904 641570 Gd-157 1.77800E-05 1.80740E-03 64157.82c + 905 641580 Gd-158 5.73420E-05 1.27370E-03 64158.82c + 906 641590 Gd-159 1.09390E-04 8.18480E-04 641590 + 907 641600 Gd-160 1.79680E-04 5.64840E-04 64160.82c + 908 641610 Gd-161 2.12450E-04 4.17060E-04 641610 + 909 641620 Gd-162 1.69200E-04 2.38200E-04 641620 + 910 641630 Gd-163 9.63870E-05 1.08960E-04 641630 + 911 641640 Gd-164 4.54800E-05 4.62910E-05 641640 + 912 641650 Gd-165 9.77600E-06 9.78760E-06 641650 + 913 641660 Gd-166 2.86480E-06 2.86510E-06 641660 + 914 641670 Gd-167 2.26900E-08 2.26940E-08 641670 + 915 641680 Gd-168 9.33360E-10 9.33360E-10 641680 + 916 641690 Gd-169 6.15580E-12 6.15580E-12 641690 + 917 651560 Tb-156 2.41160E-11 6.56100E-11 651560 + 918 651561 Tb-156m 3.48650E-11 3.48650E-11 651561 + 919 651562 Tb-156m 6.64110E-12 6.64110E-12 651562 + 920 651570 Tb-157 1.84780E-09 1.84780E-09 651570 + 921 651580 Tb-158 3.55590E-08 3.95390E-08 651580 + 922 651581 Tb-158m 4.00380E-09 4.00380E-09 651581 + 923 651590 Tb-159 2.43930E-06 8.20920E-04 65159.82c + 924 651600 Tb-160 4.88360E-06 4.88360E-06 65160.82c + 925 651610 Tb-161 1.67050E-05 4.33760E-04 651610 + 926 651620 Tb-162 2.18040E-05 2.60010E-04 651620 + 927 651630 Tb-163 5.26320E-05 1.61590E-04 651630 + 928 651640 Tb-164 2.83690E-05 7.46600E-05 651640 + 929 651650 Tb-165 3.28730E-05 4.26610E-05 651650 + 930 651660 Tb-166 1.71920E-05 2.00570E-05 651660 + 931 651670 Tb-167 1.08810E-05 1.09040E-05 651670 + 932 651680 Tb-168 2.00220E-06 2.00310E-06 651680 + 933 651690 Tb-169 1.52610E-08 1.52670E-08 651690 + 934 651700 Tb-170 2.17950E-10 2.17950E-10 651700 + 935 651710 Tb-171 1.26720E-11 1.26720E-11 651710 + 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Ho-162m 1.78840E-10 1.78840E-10 671621 + 956 671630 Ho-163 6.15240E-09 7.09290E-09 671630 + 957 671631 Ho-163m 9.40520E-10 9.40520E-10 671631 + 958 671640 Ho-164 1.75150E-08 5.85400E-08 671640 + 959 671641 Ho-164m 4.10250E-08 4.10250E-08 671641 + 960 671650 Ho-165 5.40100E-07 5.91810E-05 67165.82c + 961 671660 Ho-166 8.56880E-07 4.09570E-05 671660 + 962 671661 Ho-166m 2.00700E-06 2.00700E-06 671661 + 963 671670 Ho-167 1.97770E-06 2.67240E-05 671670 + 964 671680 Ho-168 1.24140E-06 1.80120E-05 671680 + 965 671681 Ho-168m 1.76150E-06 1.76150E-06 671681 + 966 671690 Ho-169 9.16680E-07 5.51540E-06 671690 + 967 671700 Ho-170 4.79980E-07 4.79980E-07 671700 + 968 671701 Ho-170m 2.04920E-07 9.12940E-07 671701 + 969 671710 Ho-171 1.86030E-06 1.87650E-06 671710 + 970 671720 Ho-172 2.84190E-07 2.87010E-07 671720 + 971 671730 Ho-173 1.54930E-08 1.55190E-08 671730 + 972 671740 Ho-174 2.68060E-09 2.68060E-09 671740 + 973 671750 Ho-175 1.27110E-10 1.27110E-10 671750 + 974 681640 Er-164 1.83420E-11 3.02840E-08 68164.82c + 975 681650 Er-165 4.77080E-10 4.77080E-10 681650 + 976 681660 Er-166 1.10590E-08 4.09680E-05 68166.82c + 977 681670 Er-167 8.57720E-07 2.77130E-05 68167.82c + 978 681671 Er-167m 1.31120E-07 3.32450E-06 681671 + 979 681680 Er-168 1.00100E-06 1.90230E-05 68168.82c + 980 681690 Er-169 6.84190E-07 6.19960E-06 681690 + 981 681700 Er-170 7.07770E-07 2.10070E-06 68170.82c + 982 681710 Er-171 1.13560E-06 3.01210E-06 681710 + 983 681720 Er-172 2.47040E-06 2.75740E-06 681720 + 984 681730 Er-173 6.89950E-07 7.05470E-07 681730 + 985 681740 Er-174 1.22830E-06 1.23100E-06 681740 + 986 681750 Er-175 3.99930E-08 4.01200E-08 681750 + 987 681760 Er-176 5.21910E-09 5.21910E-09 681760 + 988 681770 Er-177 2.56160E-10 2.56160E-10 681770 + 989 691660 Tm-166 3.76200E-13 1.05290E-12 691660 + 990 691670 Tm-167 3.57710E-11 3.57710E-11 691670 + 991 691680 Tm-168 7.22030E-10 7.22030E-10 691680 + 992 691690 Tm-169 4.88420E-09 6.20450E-06 691690 + 993 691700 Tm-170 1.14620E-08 1.14620E-08 691700 + 994 691710 Tm-171 1.12210E-07 3.12430E-06 691710 + 995 691720 Tm-172 5.61470E-07 3.31890E-06 691720 + 996 691730 Tm-173 3.31160E-07 1.03660E-06 691730 + 997 691740 Tm-174 6.74440E-07 1.90540E-06 691740 + 998 691750 Tm-175 7.41650E-07 7.81770E-07 691750 + 999 691760 Tm-176 1.39750E-07 1.44970E-07 691760 + 1000 691770 Tm-177 3.83020E-08 3.85580E-08 691770 + 1001 691780 Tm-178 4.04830E-09 4.04830E-09 691780 + 1002 691790 Tm-179 3.61980E-10 3.61980E-10 691790 + 1003 701700 Yb-170 1.50320E-11 1.14620E-08 701700 + 1004 701710 Yb-171 5.69920E-11 3.12470E-06 701710 + 1005 701711 Yb-171m 3.72810E-10 3.72810E-10 701711 + 1006 701720 Yb-172 1.23130E-08 3.33120E-06 701720 + 1007 701730 Yb-173 1.88410E-08 1.05550E-06 701730 + 1008 701740 Yb-174 1.88940E-07 2.09530E-06 701740 + 1009 701750 Yb-175 2.30500E-07 1.04750E-06 701750 + 1010 701751 Yb-175m 3.52370E-08 6.37200E-07 701751 + 1011 701760 Yb-176 1.39020E-07 5.01800E-07 701760 + 1012 701761 Yb-176m 2.50060E-07 3.22550E-07 701761 + 1013 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721792 + 1051 721800 Hf-180 1.48230E-08 9.26720E-08 72180.82c + 1052 721801 Hf-180m 2.66620E-08 3.62260E-08 721801 + 1053 721810 Hf-181 3.67670E-08 5.56650E-08 721810 + 1054 721820 Hf-182 1.00120E-08 2.06140E-08 721820 + 1055 721821 Hf-182m 1.80080E-08 1.80080E-08 721821 + 1056 721830 Hf-183 1.10640E-08 1.15600E-08 721830 + 1057 721840 Hf-184 1.35390E-09 1.36960E-09 721840 + 1058 721841 Hf-184m 2.43530E-09 2.45110E-09 721841 + 1059 721850 Hf-185 4.92470E-10 4.92470E-10 721850 + 1060 721860 Hf-186 5.23820E-11 5.23820E-11 721860 + 1061 721870 Hf-187 2.50390E-12 2.50390E-12 721870 + 1062 731780 Ta-178 3.59620E-12 3.59620E-12 731780 + 1063 731781 Ta-178m 5.64340E-12 6.46880E-12 731781 + 1064 731790 Ta-179 1.12860E-10 1.48710E-10 731790 + 1065 731791 Ta-179m 3.45200E-11 3.58590E-11 731791 + 1066 731792 Ta-179m 1.33860E-12 1.33860E-12 731792 + 1067 731800 Ta-180 3.98700E-10 3.98700E-10 731800 + 1068 731801 Ta-180m 4.51960E-10 5.64260E-10 731801 + 1069 731810 Ta-181 3.85860E-09 5.95400E-08 73181.82c + 1070 731820 Ta-182 2.40820E-09 1.71850E-08 73182.82c + 1071 731821 Ta-182m 2.45810E-09 1.47770E-08 731821 + 1072 731822 Ta-182m 1.87380E-09 1.23190E-08 731822 + 1073 731830 Ta-183 1.19450E-08 2.35050E-08 731830 + 1074 731840 Ta-184 8.96130E-09 1.27820E-08 731840 + 1075 731850 Ta-185 3.75760E-09 6.07010E-09 731850 + 1076 731851 Ta-185m 1.82000E-09 1.82000E-09 731851 + 1077 731860 Ta-186 1.49660E-09 1.54900E-09 731860 + 1078 731870 Ta-187 4.00800E-10 4.03300E-10 731870 + 1079 731880 Ta-188 4.13830E-11 4.13830E-11 731880 + 1080 731890 Ta-189 3.58160E-12 3.58160E-12 731890 + 1081 741800 W-180 4.28550E-13 7.33650E-11 741800 + 1082 741810 W-181 1.58360E-11 1.58360E-11 741810 + 1083 741820 W-182 1.57920E-10 1.73430E-08 74182.82c + 1084 741830 W-183 1.69310E-10 2.42300E-08 74183.82c + 1085 741831 W-183m 5.53940E-10 1.35380E-09 741831 + 1086 741840 W-184 2.66120E-09 1.54580E-08 74184.82c + 1087 741850 W-185 1.07700E-09 9.74700E-09 741850 + 1088 741851 W-185m 2.59990E-09 2.59990E-09 741851 + 1089 741860 W-186 3.33190E-09 5.96510E-09 74186.82c + 1090 741861 W-186m 1.07480E-09 1.07480E-09 741861 + 1091 741870 W-187 2.65120E-09 3.05450E-09 741870 + 1092 741880 W-188 1.36640E-09 1.40780E-09 741880 + 1093 741890 W-189 3.10640E-10 3.14220E-10 741890 + 1094 741900 W-190 2.83340E-11 6.04520E-11 741900 + 1095 741901 W-190m 3.21180E-11 3.21180E-11 741901 + 1096 741910 W-191 4.65290E-12 4.65290E-12 741910 + 1097 751830 Re-183 9.96930E-13 1.39940E-12 751830 + 1098 751840 Re-184 7.70680E-12 1.29410E-11 751840 + 1099 751841 Re-184m 6.94220E-12 6.94220E-12 751841 + 1100 751850 Re-185 1.11760E-10 9.85870E-09 75185.82c + 1101 751860 Re-186 1.37250E-10 1.37250E-10 751860 + 1102 751861 Re-186m 1.94760E-10 1.94760E-10 751861 + 1103 751870 Re-187 9.41770E-10 3.99630E-09 75187.82c + 1104 751880 Re-188 3.16110E-10 2.46430E-09 751880 + 1105 751881 Re-188m 7.40400E-10 7.40400E-10 751881 + 1106 751890 Re-189 1.08510E-09 1.39930E-09 751890 + 1107 751900 Re-190 1.75710E-10 3.80280E-10 751900 + 1108 751901 Re-190m 3.16050E-10 3.16050E-10 751901 + 1109 751910 Re-191 1.97140E-10 2.01790E-10 751910 + 1110 751920 Re-192 3.17590E-11 3.17590E-11 751920 + 1111 751930 Re-193 5.04370E-12 5.04370E-12 751930 + 1112 761860 Os-186 2.02470E-12 1.29810E-10 761860 + 1113 761870 Os-187 1.58870E-11 1.58870E-11 761870 + 1114 761880 Os-188 9.47250E-11 2.55900E-09 761880 + 1115 761890 Os-189 5.41070E-11 1.63230E-09 761890 + 1116 761891 Os-189m 1.77020E-10 3.21060E-10 761891 + 1117 761900 Os-190 2.24260E-10 1.04120E-09 761900 + 1118 761901 Os-190m 2.54220E-10 4.28810E-10 761901 + 1119 761910 Os-191 3.18500E-10 6.17640E-10 761910 + 1120 761911 Os-191m 9.73500E-11 9.73500E-11 761911 + 1121 761920 Os-192 1.45570E-10 3.25720E-10 761920 + 1122 761921 Os-192m 1.65020E-10 1.65020E-10 761921 + 1123 761930 Os-193 1.19730E-10 1.24770E-10 761930 + 1124 761940 Os-194 4.00400E-11 4.00400E-11 761940 + 1125 761950 Os-195 5.06610E-12 5.06610E-12 761950 + 1126 771890 Ir-189 5.53290E-13 1.88900E-12 771890 + 1127 771891 Ir-189m 1.01080E-12 1.33570E-12 771891 + 1128 771900 Ir-190 5.54280E-12 7.80260E-12 771900 + 1129 771901 Ir-190m 2.00970E-12 2.00970E-12 771901 + 1130 771902 Ir-190m 2.90840E-12 2.90840E-12 771902 + 1131 771910 Ir-191 1.35750E-11 6.63990E-10 77191.82c + 1132 771911 Ir-191m 2.58660E-11 3.24300E-10 771911 + 1133 771912 Ir-191m 6.90560E-12 6.90560E-12 771912 + 1134 771920 Ir-192 2.63520E-11 1.00510E-10 771920 + 1135 771921 Ir-192m 2.63520E-11 2.63520E-11 771921 + 1136 771922 Ir-192m 2.63520E-11 4.78040E-11 771922 + 1137 771930 Ir-193 4.00190E-11 2.70210E-10 77193.82c + 1138 771931 Ir-193m 9.66110E-11 9.70450E-11 771931 + 1139 771940 Ir-194 3.34200E-11 1.06880E-10 771940 + 1140 771941 Ir-194m 3.34200E-11 3.34200E-11 771941 + 1141 771942 Ir-194m 3.34200E-11 3.34200E-11 771942 + 1142 771950 Ir-195 1.78640E-11 2.50870E-11 771950 + 1143 771951 Ir-195m 4.31270E-11 4.31270E-11 771951 + 1144 771960 Ir-196 7.97400E-12 7.99790E-12 771960 + 1145 771961 Ir-196m 7.97400E-12 7.97400E-12 771961 + 1146 771970 Ir-197 1.22360E-12 1.23100E-12 771970 + 1147 771971 Ir-197m 2.95400E-12 2.95400E-12 771971 + 1148 781920 Pt-192 1.97880E-12 9.76640E-11 781920 + 1149 781930 Pt-193 2.57840E-12 8.80300E-12 781930 + 1150 781931 Pt-193m 6.22460E-12 6.22460E-12 781931 + 1151 781940 Pt-194 3.15610E-11 1.71860E-10 781940 + 1152 781950 Pt-195 1.24510E-11 1.09940E-10 781950 + 1153 781951 Pt-195m 3.00580E-11 4.31690E-11 781951 + 1154 781960 Pt-196 4.96640E-11 6.92990E-11 781960 + 1155 781970 Pt-197 8.58690E-12 3.27130E-11 781970 + 1156 781971 Pt-197m 2.07300E-11 2.36770E-11 781971 + 1157 781980 Pt-198 1.48320E-11 1.48320E-11 781980 + 1158 781990 Pt-199 1.32820E-12 3.27800E-12 781990 + 1159 781991 Pt-199m 1.94970E-12 1.94970E-12 781991 + 1160 791950 Au-195 4.03500E-13 1.37760E-12 791950 + 1161 791960 Au-196 1.18880E-12 3.97340E-12 791960 + 1162 791961 Au-196m 1.98230E-12 2.78460E-12 791961 + 1163 791970 Au-197 3.22780E-12 4.45150E-11 79197.82c + 1164 791971 Au-197m 7.79220E-12 8.57360E-12 791971 + 1165 791980 Au-198 8.15510E-12 1.21230E-11 791980 + 1166 791981 Au-198m 3.96790E-12 3.96790E-12 791981 + 1167 791990 Au-199 1.21270E-11 1.54050E-11 791990 + 1168 792000 Au-200 3.37560E-12 3.73160E-12 792000 + 1169 792001 Au-200m 1.97820E-12 1.97820E-12 792001 + 1170 801980 Hg-198 1.15640E-12 1.32790E-11 80198.82c + 1171 801990 Hg-199 8.01780E-13 1.81420E-11 80199.82c + 1172 801991 Hg-199m 1.93560E-12 1.93560E-12 801991 + 1173 802000 Hg-200 5.50730E-12 1.08610E-11 80200.82c + + Neutron-induced fission: + + Interpolation region : 2 / 2 + Interpolation energy : 4.00000E-01 MeV + Number of products : 1123 / 1169 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 4.08110E-05 4.08110E-05 1001.82c + 2 10020 H-2 1.24720E-05 1.24720E-05 1002.82c + 3 10030 H-3 1.96000E-04 1.96000E-04 1003.82c + 4 20040 He-4 2.58000E-03 2.58000E-03 2004.82c + 5 190500 K-50 5.39170E-12 5.39170E-12 190500 + 6 190510 K-51 1.73150E-12 1.73150E-12 190510 + 7 200500 Ca-50 8.54290E-11 9.00710E-11 200500 + 8 200510 Ca-51 6.95660E-11 7.04840E-11 200510 + 9 200520 Ca-52 4.88730E-11 4.88730E-11 200520 + 10 200530 Ca-53 1.27720E-11 1.27720E-11 200530 + 11 200540 Ca-54 2.63570E-12 2.63570E-12 200540 + 12 210500 Sc-50 2.51290E-11 1.23180E-10 210500 + 13 210501 Sc-50m 9.21900E-12 9.92900E-11 210501 + 14 210510 Sc-51 1.26560E-10 1.98020E-10 210510 + 15 210520 Sc-52 2.00830E-10 2.52560E-10 210520 + 16 210530 Sc-53 2.64810E-10 2.73750E-10 210530 + 17 210540 Sc-54 1.44680E-10 1.47320E-10 210540 + 18 210550 Sc-55 7.97570E-11 7.97570E-11 210550 + 19 210560 Sc-56 1.67540E-11 1.67540E-11 210560 + 20 210570 Sc-57 2.68590E-12 2.68590E-12 210570 + 21 220500 Ti-50 1.43370E-12 1.25850E-10 22050.82c + 22 220510 Ti-51 1.33020E-11 2.11320E-10 220510 + 23 220520 Ti-52 1.01360E-10 3.53920E-10 220520 + 24 220530 Ti-53 2.93710E-10 5.67460E-10 220530 + 25 220540 Ti-54 7.33660E-10 8.80980E-10 220540 + 26 220550 Ti-55 9.48100E-10 1.02790E-09 220550 + 27 220560 Ti-56 1.05130E-09 1.06890E-09 220560 + 28 220570 Ti-57 4.63660E-10 4.65460E-10 220570 + 29 220580 Ti-58 1.41450E-10 1.41450E-10 220580 + 30 220590 Ti-59 2.63520E-11 2.63520E-11 220590 + 31 220600 Ti-60 3.03980E-12 3.03980E-12 220600 + 32 230520 V-52 1.03910E-12 3.54960E-10 230520 + 33 230530 V-53 1.63250E-11 5.83780E-10 230530 + 34 230540 V-54 9.81540E-11 9.79130E-10 230540 + 35 230550 V-55 5.88500E-10 1.61640E-09 230550 + 36 230560 V-56 1.42610E-09 2.49640E-09 230560 + 37 230570 V-57 2.95320E-09 3.41730E-09 230570 + 38 230580 V-58 2.20640E-09 2.34780E-09 230580 + 39 230590 V-59 2.26440E-09 2.29080E-09 230590 + 40 230600 V-60 7.42370E-10 7.45410E-10 230600 + 41 230610 V-61 2.20630E-10 2.20630E-10 230610 + 42 230620 V-62 2.52940E-11 2.52940E-11 230620 + 43 230630 V-63 2.12580E-12 2.12580E-12 230630 + 44 240540 Cr-54 1.13820E-12 9.80270E-10 24054.82c + 45 240550 Cr-55 1.85100E-11 1.63490E-09 240550 + 46 240560 Cr-56 2.32720E-10 2.74280E-09 240560 + 47 240570 Cr-57 1.11240E-09 6.39430E-09 240570 + 48 240580 Cr-58 6.09840E-09 6.56800E-09 240580 + 49 240590 Cr-59 8.57640E-09 1.08670E-08 240590 + 50 240600 Cr-60 1.37160E-08 1.44750E-08 240600 + 51 240610 Cr-61 1.04430E-08 1.06500E-08 240610 + 52 240620 Cr-62 6.84900E-09 6.87500E-09 240620 + 53 240630 Cr-63 1.68080E-09 1.68220E-09 240630 + 54 240640 Cr-64 3.23120E-10 3.23120E-10 240640 + 55 240650 Cr-65 2.83100E-11 2.83100E-11 240650 + 56 240660 Cr-66 1.42860E-12 1.42860E-12 240660 + 57 250570 Mn-57 1.78370E-11 6.41210E-09 250570 + 58 250580 Mn-58 1.43640E-10 6.71160E-09 250580 + 59 250581 Mn-58m 1.41190E-11 1.41190E-11 250581 + 60 250590 Mn-59 1.77670E-09 1.26440E-08 250590 + 61 250600 Mn-60 5.67950E-10 1.57070E-08 250600 + 62 250601 Mn-60m 5.77780E-09 5.77780E-09 250601 + 63 250610 Mn-61 2.18790E-08 3.25290E-08 250610 + 64 250620 Mn-62 2.82380E-08 3.16750E-08 250620 + 65 250621 Mn-62m 4.42220E-09 7.85970E-09 250621 + 66 250630 Mn-63 4.08640E-08 4.25460E-08 250630 + 67 250640 Mn-64 2.09930E-08 2.13160E-08 250640 + 68 250650 Mn-65 1.08640E-08 1.08920E-08 250650 + 69 250660 Mn-66 1.62940E-09 1.63080E-09 250660 + 70 250670 Mn-67 3.18310E-10 3.18310E-10 250670 + 71 250680 Mn-68 1.79410E-11 1.79410E-11 250680 + 72 260590 Fe-59 1.55900E-11 1.26590E-08 260590 + 73 260600 Fe-60 3.11420E-10 2.11320E-08 260600 + 74 260610 Fe-61 2.67570E-09 3.52050E-08 260610 + 75 260620 Fe-62 1.90100E-08 5.85450E-08 260620 + 76 260630 Fe-63 5.21230E-08 9.46690E-08 260630 + 77 260640 Fe-64 1.23020E-07 1.44340E-07 260640 + 78 260650 Fe-65 1.50680E-07 1.61570E-07 260650 + 79 260660 Fe-66 1.20520E-07 1.22150E-07 260660 + 80 260670 Fe-67 6.52940E-08 6.56120E-08 260670 + 81 260680 Fe-68 2.23250E-08 2.23430E-08 260680 + 82 260690 Fe-69 3.25380E-09 3.25380E-09 260690 + 83 260700 Fe-70 6.69730E-11 6.69730E-11 260700 + 84 260710 Fe-71 5.31210E-12 5.31210E-12 260710 + 85 270610 Co-61 1.16210E-11 3.52170E-08 270610 + 86 270620 Co-62 6.17720E-11 5.86080E-08 270620 + 87 270621 Co-62m 1.68380E-10 1.68380E-10 270621 + 88 270630 Co-63 3.38770E-09 9.80570E-08 270630 + 89 270640 Co-64 1.90520E-08 1.63390E-07 270640 + 90 270650 Co-65 1.07600E-07 2.69170E-07 270650 + 91 270660 Co-66 3.59340E-07 4.81490E-07 270660 + 92 270670 Co-67 4.82890E-07 5.48500E-07 270670 + 93 270680 Co-68 2.33960E-07 3.32560E-07 270680 + 94 270681 Co-68m 1.74630E-07 1.97200E-07 270681 + 95 270690 Co-69 3.31080E-07 3.34110E-07 270690 + 96 270700 Co-70 9.75000E-09 9.75000E-09 270700 + 97 270701 Co-70m 9.75000E-09 9.81700E-09 270701 + 98 270710 Co-71 9.58130E-09 9.58660E-09 270710 + 99 270720 Co-72 2.68280E-09 2.68280E-09 270720 + 100 270730 Co-73 2.03120E-10 2.03120E-10 270730 + 101 270740 Co-74 1.08940E-11 1.08940E-11 270740 + 102 280630 Ni-63 7.85090E-12 9.80650E-08 280630 + 103 280640 Ni-64 2.61890E-10 1.63650E-07 28064.82c + 104 280650 Ni-65 3.97690E-09 2.73150E-07 280650 + 105 280660 Ni-66 3.57360E-08 5.17230E-07 280660 + 106 280670 Ni-67 2.09690E-07 7.58190E-07 280670 + 107 280680 Ni-68 8.04320E-07 1.23880E-06 280680 + 108 280690 Ni-69 7.24850E-07 1.05560E-06 280690 + 109 280691 Ni-69m 7.24850E-07 7.24850E-07 280691 + 110 280700 Ni-70 4.20680E-07 4.40250E-07 280700 + 111 280710 Ni-71 1.35120E-06 1.36080E-06 280710 + 112 280720 Ni-72 8.63620E-07 8.66300E-07 280720 + 113 280730 Ni-73 1.91890E-07 1.92090E-07 280730 + 114 280740 Ni-74 6.30680E-08 6.30790E-08 280740 + 115 280750 Ni-75 3.50390E-09 3.50390E-09 280750 + 116 280760 Ni-76 1.77990E-10 1.77990E-10 280760 + 117 280770 Ni-77 4.30340E-12 4.30340E-12 280770 + 118 290650 Cu-65 4.46340E-12 2.73150E-07 29065.82c + 119 290660 Cu-66 1.17590E-10 5.17340E-07 290660 + 120 290670 Cu-67 3.96860E-09 7.62160E-07 290670 + 121 290680 Cu-68 1.05380E-08 1.27350E-06 290680 + 122 290681 Cu-68m 2.87240E-08 2.87240E-08 290681 + 123 290690 Cu-69 3.47470E-07 2.12790E-06 290690 + 124 290700 Cu-70 4.41890E-08 3.38470E-07 290700 + 125 290701 Cu-70m 5.64340E-07 5.88560E-07 290701 + 126 290702 Cu-70m 4.41890E-08 4.84440E-07 290702 + 127 290710 Cu-71 1.29130E-06 2.65210E-06 290710 + 128 290720 Cu-72 3.07340E-06 3.93970E-06 290720 + 129 290730 Cu-73 4.39910E-06 4.59120E-06 290730 + 130 290740 Cu-74 4.85590E-06 4.91900E-06 290740 + 131 290750 Cu-75 4.63520E-06 4.63870E-06 290750 + 132 290760 Cu-76 1.21970E-07 1.22060E-07 290760 + 133 290761 Cu-76m 1.21970E-07 1.22060E-07 290761 + 134 290770 Cu-77 4.17160E-08 4.17200E-08 290770 + 135 290780 Cu-78 2.67760E-09 2.67760E-09 290780 + 136 290790 Cu-79 9.78190E-11 9.78190E-11 290790 + 137 300670 Zn-67 2.32630E-12 7.62160E-07 300670 + 138 300680 Zn-68 1.42990E-10 1.27820E-06 300680 + 139 300690 Zn-69 6.05490E-10 2.13150E-06 300690 + 140 300691 Zn-69m 3.00720E-09 3.00720E-09 300691 + 141 300700 Zn-70 1.29010E-08 1.10590E-06 300700 + 142 300710 Zn-71 1.13220E-07 2.76530E-06 300710 + 143 300711 Zn-71m 5.62310E-07 5.62310E-07 300711 + 144 300720 Zn-72 6.14510E-06 1.00850E-05 300720 + 145 300730 Zn-73 7.71320E-07 9.90820E-06 300730 + 146 300731 Zn-73m 1.06680E-06 4.54570E-06 300731 + 147 300732 Zn-73m 6.95770E-06 6.95770E-06 300732 + 148 300740 Zn-74 3.39370E-05 3.90180E-05 300740 + 149 300750 Zn-75 2.43400E-05 2.88200E-05 300750 + 150 300760 Zn-76 3.33490E-05 3.35900E-05 300760 + 151 300770 Zn-77 9.87340E-06 1.05720E-05 300770 + 152 300771 Zn-77m 1.31460E-06 1.31460E-06 300771 + 153 300780 Zn-78 1.42150E-05 1.42180E-05 300780 + 154 300790 Zn-79 4.60450E-07 4.60490E-07 300790 + 155 300800 Zn-80 4.63530E-08 4.63530E-08 300800 + 156 300810 Zn-81 1.31010E-09 1.31010E-09 300810 + 157 300820 Zn-82 4.12080E-11 4.12080E-11 300820 + 158 310690 Ga-69 1.00320E-12 2.13150E-06 310690 + 159 310700 Ga-70 1.10040E-11 1.10040E-11 310700 + 160 310710 Ga-71 9.47650E-10 3.32860E-06 310710 + 161 310720 Ga-72 4.17330E-08 1.01310E-05 310720 + 162 310721 Ga-72m 4.10220E-09 3.40130E-07 310721 + 163 310730 Ga-73 1.09940E-06 1.44860E-05 310730 + 164 310740 Ga-74 3.18010E-06 3.48290E-05 310740 + 165 310741 Ga-74m 3.18010E-06 4.21980E-05 310741 + 166 310750 Ga-75 1.73650E-05 4.61850E-05 310750 + 167 310760 Ga-76 2.73460E-05 6.09350E-05 310760 + 168 310770 Ga-77 7.58690E-05 8.70990E-05 310770 + 169 310780 Ga-78 6.46980E-05 7.89220E-05 310780 + 170 310790 Ga-79 6.47690E-05 6.52240E-05 310790 + 171 310800 Ga-80 1.98380E-05 1.98840E-05 310800 + 172 310810 Ga-81 6.83550E-06 6.83670E-06 310810 + 173 310820 Ga-82 2.31690E-07 2.31730E-07 310820 + 174 310830 Ga-83 1.65100E-08 1.65100E-08 310830 + 175 310840 Ga-84 3.97010E-10 3.97010E-10 310840 + 176 320720 Ge-72 4.26490E-11 1.01310E-05 32072.82c + 177 320730 Ge-73 1.40270E-09 1.44880E-05 32073.82c + 178 320731 Ge-73m 2.82420E-10 1.42740E-05 320731 + 179 320740 Ge-74 9.59350E-08 4.54750E-05 32074.82c + 180 320750 Ge-75 4.08190E-07 4.96570E-05 320750 + 181 320751 Ge-75m 3.06580E-06 4.91320E-06 320751 + 182 320760 Ge-76 1.06980E-05 7.16340E-05 32076.82c + 183 320770 Ge-77 4.92360E-05 6.70310E-05 320770 + 184 320771 Ge-77m 6.55560E-06 9.36540E-05 320771 + 185 320780 Ge-78 1.89440E-04 2.68420E-04 320780 + 186 320790 Ge-79 3.39500E-05 1.09220E-04 320790 + 187 320791 Ge-79m 2.54990E-04 2.55090E-04 320791 + 188 320800 Ge-80 4.54970E-04 4.75670E-04 320800 + 189 320810 Ge-81 2.13920E-04 2.17580E-04 320810 + 190 320811 Ge-81m 4.30720E-05 4.59390E-05 320811 + 191 320820 Ge-82 1.57750E-04 1.57940E-04 320820 + 192 320830 Ge-83 2.05340E-05 2.05450E-05 320830 + 193 320840 Ge-84 5.37180E-06 5.37190E-06 320840 + 194 320850 Ge-85 1.54790E-07 1.54790E-07 320850 + 195 320860 Ge-86 6.71890E-09 6.71890E-09 320860 + 196 320870 Ge-87 1.83850E-10 1.83850E-10 320870 + 197 330740 As-74 2.07970E-11 2.07970E-11 330740 + 198 330750 As-75 2.59520E-10 4.96600E-05 33075.82c + 199 330751 As-75m 9.82780E-10 2.45670E-09 330751 + 200 330760 As-76 3.30560E-08 3.30560E-08 330760 + 201 330770 As-77 9.76480E-07 1.43870E-04 330770 + 202 330780 As-78 1.15920E-05 2.80010E-04 330780 + 203 330790 As-79 5.67790E-05 4.10880E-04 330790 + 204 330800 As-80 1.83170E-04 6.58840E-04 330800 + 205 330810 As-81 3.80090E-04 6.43150E-04 330810 + 206 330820 As-82 1.00440E-04 2.58380E-04 330820 + 207 330821 As-82m 3.49970E-04 3.49970E-04 330821 + 208 330830 As-83 5.83830E-04 6.04960E-04 330830 + 209 330840 As-84 1.23760E-04 1.26170E-04 330840 + 210 330841 As-84m 1.23760E-04 1.26170E-04 330841 + 211 330850 As-85 1.05880E-04 1.06010E-04 330850 + 212 330860 As-86 2.38960E-05 2.39030E-05 330860 + 213 330870 As-87 3.26750E-06 3.26770E-06 330870 + 214 330880 As-88 5.26350E-08 5.26350E-08 330880 + 215 330890 As-89 1.54930E-09 1.54930E-09 330890 + 216 340760 Se-76 7.73820E-12 3.30640E-08 34076.82c + 217 340770 Se-77 8.09060E-11 1.43870E-04 34077.82c + 218 340771 Se-77m 6.07650E-10 6.07650E-10 340771 + 219 340780 Se-78 4.78810E-08 2.80060E-04 34078.82c + 220 340790 Se-79 5.16520E-06 4.16510E-04 34079.82c + 221 340791 Se-79m 6.87720E-07 4.01840E-04 340791 + 222 340800 Se-80 1.85860E-05 6.77430E-04 34080.82c + 223 340810 Se-81 1.67430E-05 7.85570E-04 340810 + 224 340811 Se-81m 1.25750E-04 1.48840E-04 340811 + 225 340820 Se-82 5.17340E-04 1.12570E-03 34082.82c + 226 340830 Se-83 9.24380E-04 1.14230E-03 340830 + 227 340831 Se-83m 1.86120E-04 5.73470E-04 340831 + 228 340840 Se-84 2.12540E-03 2.40070E-03 340840 + 229 340850 Se-85 1.69320E-03 1.78380E-03 340850 + 230 340860 Se-86 1.35660E-03 1.37310E-03 340860 + 231 340870 Se-87 5.24190E-04 5.26950E-04 340870 + 232 340880 Se-88 1.80990E-04 1.81040E-04 340880 + 233 340890 Se-89 3.17090E-05 3.17110E-05 340890 + 234 340900 Se-90 5.48770E-06 5.48770E-06 340900 + 235 340910 Se-91 1.65620E-08 1.65620E-08 340910 + 236 350790 Br-79 6.64110E-11 2.25350E-07 35079.82c + 237 350791 Br-79m 2.51500E-10 2.51500E-10 350791 + 238 350800 Br-80 3.81530E-09 1.71090E-08 350800 + 239 350801 Br-80m 1.32940E-08 1.32940E-08 350801 + 240 350810 Br-81 5.20840E-07 7.86160E-04 35081.82c + 241 350820 Br-82 4.06500E-06 5.52050E-06 350820 + 242 350821 Br-82m 1.49130E-06 1.49130E-06 350821 + 243 350830 Br-83 7.75480E-05 1.79340E-03 350830 + 244 350840 Br-84 1.52660E-04 2.55340E-03 350840 + 245 350841 Br-84m 1.52660E-04 1.52660E-04 350841 + 246 350850 Br-85 1.30070E-03 3.08450E-03 350850 + 247 350860 Br-86 1.92650E-03 3.29960E-03 350860 + 248 350870 Br-87 2.88260E-03 3.41140E-03 350870 + 249 350880 Br-88 2.16970E-03 2.35140E-03 350880 + 250 350890 Br-89 1.34980E-03 1.37900E-03 350890 + 251 350900 Br-90 3.94730E-04 4.00220E-04 350900 + 252 350910 Br-91 1.28400E-04 1.28410E-04 350910 + 253 350920 Br-92 1.97720E-05 1.97720E-05 350920 + 254 350930 Br-93 3.31400E-06 3.31400E-06 350930 + 255 350940 Br-94 3.08700E-09 3.08700E-09 350940 + 256 360810 Kr-81 8.40860E-11 9.52820E-11 360810 + 257 360811 Kr-81m 1.11960E-11 1.11960E-11 360811 + 258 360820 Kr-82 8.24160E-09 5.56450E-06 36082.82c + 259 360830 Kr-83 2.56000E-07 1.79370E-03 36083.82c + 260 360831 Kr-83m 5.15450E-08 1.79180E-03 360831 + 261 360840 Kr-84 2.14660E-05 2.72750E-03 36084.82c + 262 360850 Kr-85 1.50080E-04 8.20570E-04 36085.82c + 263 360851 Kr-85m 3.02180E-05 3.10970E-03 360851 + 264 360860 Kr-86 1.00580E-03 4.39100E-03 36086.82c + 265 360870 Kr-87 2.56950E-03 6.05280E-03 360870 + 266 360880 Kr-88 5.71760E-03 8.10590E-03 360880 + 267 360890 Kr-89 6.96770E-03 8.25070E-03 360890 + 268 360900 Kr-90 7.12600E-03 7.45350E-03 360900 + 269 360910 Kr-91 4.05050E-03 4.15980E-03 360910 + 270 360920 Kr-92 1.97660E-03 1.99210E-03 360920 + 271 360930 Kr-93 4.58440E-04 4.59500E-04 360930 + 272 360940 Kr-94 1.23970E-04 1.23970E-04 360940 + 273 360950 Kr-95 8.84820E-06 8.84820E-06 360950 + 274 360960 Kr-96 3.79160E-08 3.79160E-08 360960 + 275 370840 Rb-84 7.26200E-10 2.24970E-09 370840 + 276 370841 Rb-84m 1.52350E-09 1.52350E-09 370841 + 277 370850 Rb-85 1.08540E-06 3.26590E-03 37085.82c + 278 370860 Rb-86 3.86130E-06 1.19620E-05 37086.82c + 279 370861 Rb-86m 8.10070E-06 8.10070E-06 370861 + 280 370870 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38088.82c + 300 380890 Sr-89 1.52150E-04 1.03990E-02 38089.82c + 301 380900 Sr-90 1.11250E-03 1.30460E-02 38090.82c + 302 380910 Sr-91 3.42250E-03 1.60850E-02 380910 + 303 380920 Sr-92 1.02640E-02 2.07540E-02 380920 + 304 380930 Sr-93 1.51550E-02 2.30920E-02 380930 + 305 380940 Sr-94 2.13410E-02 2.45140E-02 380940 + 306 380950 Sr-95 1.49800E-02 1.63460E-02 380950 + 307 380960 Sr-96 9.92740E-03 1.01840E-02 380960 + 308 380970 Sr-97 3.44930E-03 3.48870E-03 380970 + 309 380980 Sr-98 1.16080E-03 1.16470E-03 380980 + 310 380990 Sr-99 2.01360E-04 2.01360E-04 380990 + 311 381000 Sr-100 2.83460E-05 2.83460E-05 381000 + 312 381010 Sr-101 3.55120E-08 3.55120E-08 381010 + 313 390880 Y-88 1.11220E-10 2.09700E-10 390880 + 314 390881 Y-88m 9.84750E-11 9.84750E-11 390881 + 315 390890 Y-89 1.83290E-07 1.04010E-02 39089.82c + 316 390891 Y-89m 9.10310E-07 1.91270E-06 390891 + 317 390900 Y-90 1.23220E-06 1.30490E-02 39090.82c + 318 390901 Y-90m 2.06060E-06 2.06060E-06 390901 + 319 390910 Y-91 7.36350E-06 1.61290E-02 39091.82c + 320 390911 Y-91m 3.65720E-05 9.50050E-03 390911 + 321 390920 Y-92 3.23790E-04 2.10780E-02 390920 + 322 390930 Y-93 2.59530E-04 2.53010E-02 390930 + 323 390931 Y-93m 1.94930E-03 7.72790E-03 390931 + 324 390940 Y-94 5.73900E-03 3.02530E-02 390940 + 325 390950 Y-95 1.46590E-02 3.10050E-02 390950 + 326 390960 Y-96 5.89140E-03 1.60770E-02 390960 + 327 390961 Y-96m 1.23600E-02 1.23600E-02 390961 + 328 390970 Y-97 3.30980E-03 6.39070E-03 390970 + 329 390971 Y-97m 1.22340E-02 1.61160E-02 390971 + 330 390972 Y-97m 4.20430E-03 4.20430E-03 390972 + 331 390980 Y-98 2.00530E-03 3.17000E-03 390980 + 332 390981 Y-98m 9.72170E-03 9.72170E-03 390981 + 333 390990 Y-99 6.72580E-03 6.92740E-03 390990 + 334 391000 Y-100 1.02790E-03 1.05600E-03 391000 + 335 391001 Y-100m 1.02790E-03 1.02790E-03 391001 + 336 391010 Y-101 6.02480E-04 6.02510E-04 391010 + 337 391020 Y-102 3.61430E-05 3.61430E-05 391020 + 338 391021 Y-102m 3.61430E-05 3.61430E-05 391021 + 339 391030 Y-103 1.18100E-05 1.18100E-05 391030 + 340 391040 Y-104 3.00610E-09 3.00610E-09 391040 + 341 400910 Zr-91 2.92270E-09 1.61290E-02 40091.82c + 342 400920 Zr-92 7.69070E-06 2.10860E-02 40092.82c + 343 400930 Zr-93 8.84740E-05 2.53900E-02 40093.82c + 344 400940 Zr-94 6.67470E-04 3.09210E-02 40094.82c + 345 400950 Zr-95 2.45190E-03 3.34570E-02 40095.82c + 346 400960 Zr-96 1.02270E-02 3.86770E-02 40096.82c + 347 400970 Zr-97 1.86780E-02 4.22430E-02 400970 + 348 400980 Zr-98 3.30660E-02 4.57330E-02 400980 + 349 400990 Zr-99 2.96180E-02 3.64370E-02 400990 + 350 401000 Zr-100 2.57190E-02 2.77930E-02 401000 + 351 401010 Zr-101 1.21830E-02 1.27890E-02 401010 + 352 401020 Zr-102 5.48310E-03 5.55280E-03 401020 + 353 401030 Zr-103 1.23040E-03 1.24130E-03 401030 + 354 401040 Zr-104 2.74610E-04 2.74610E-04 401040 + 355 401050 Zr-105 3.07930E-05 3.07930E-05 401050 + 356 401060 Zr-106 3.22020E-08 3.22020E-08 401060 + 357 410930 Nb-93 6.16720E-10 7.40900E-10 41093.82c + 358 410931 Nb-93m 1.24170E-10 1.24170E-10 410931 + 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3.29560E-03 3.32600E-03 411050 + 379 411060 Nb-106 6.60360E-04 6.60390E-04 411060 + 380 411070 Nb-107 1.34640E-04 1.34640E-04 411070 + 381 411080 Nb-108 2.25170E-05 2.25170E-05 411080 + 382 411090 Nb-109 1.82170E-06 1.82170E-06 411090 + 383 420960 Mo-96 3.36860E-06 1.51800E-04 42096.82c + 384 420970 Mo-97 1.85170E-05 4.34720E-02 42097.82c + 385 420980 Mo-98 2.19840E-04 4.96660E-02 42098.82c + 386 420990 Mo-99 1.00380E-03 5.00700E-02 42099.82c + 387 421000 Mo-100 5.25540E-03 5.35260E-02 42100.82c + 388 421010 Mo-101 1.20400E-02 5.59010E-02 421010 + 389 421020 Mo-102 2.89600E-02 5.91690E-02 421020 + 390 421030 Mo-103 3.40020E-02 5.39190E-02 421030 + 391 421040 Mo-104 3.85480E-02 4.65580E-02 421040 + 392 421050 Mo-105 2.38840E-02 2.71830E-02 421050 + 393 421060 Mo-106 1.50090E-02 1.56480E-02 421060 + 394 421070 Mo-107 4.73520E-03 4.86320E-03 421070 + 395 421080 Mo-108 1.58620E-03 1.60750E-03 421080 + 396 421090 Mo-109 2.46470E-04 2.48060E-04 421090 + 397 421100 Mo-110 3.15660E-05 3.15660E-05 421100 + 398 421110 Mo-111 1.77640E-06 1.77640E-06 421110 + 399 430980 Tc-98 1.20790E-09 1.20790E-09 430980 + 400 430990 Tc-99 7.83430E-06 5.00780E-02 43099.82c + 401 430991 Tc-99m 1.57740E-06 4.40930E-02 430991 + 402 431000 Tc-100 5.25320E-05 5.25320E-05 431000 + 403 431010 Tc-101 3.99730E-04 5.63010E-02 431010 + 404 431020 Tc-102 7.88050E-04 5.99570E-02 431020 + 405 431021 Tc-102m 7.88050E-04 7.88050E-04 431021 + 406 431030 Tc-103 6.46380E-03 6.03820E-02 431030 + 407 431040 Tc-104 1.30160E-02 5.95740E-02 431040 + 408 431050 Tc-105 2.70960E-02 5.42790E-02 431050 + 409 431060 Tc-106 2.68490E-02 4.24970E-02 431060 + 410 431070 Tc-107 2.66480E-02 3.15110E-02 431070 + 411 431080 Tc-108 1.45130E-02 1.61220E-02 431080 + 412 431090 Tc-109 7.97490E-03 8.22170E-03 431090 + 413 431100 Tc-110 2.41830E-03 2.44990E-03 431100 + 414 431110 Tc-111 6.71720E-04 6.73480E-04 431110 + 415 431120 Tc-112 8.26800E-05 8.26800E-05 431120 + 416 431130 Tc-113 8.07780E-06 8.07780E-06 431130 + 417 431140 Tc-114 1.53410E-10 1.53410E-10 431140 + 418 441010 Ru-101 2.05010E-06 5.63030E-02 44101.82c + 419 441020 Ru-102 4.58650E-05 6.07910E-02 44102.82c + 420 441030 Ru-103 6.95770E-05 6.06470E-02 44103.82c + 421 441031 Ru-103m 1.94670E-04 1.94670E-04 441031 + 422 441040 Ru-104 1.43790E-03 6.10120E-02 44104.82c + 423 441050 Ru-105 4.40680E-03 5.86860E-02 44105.82c + 424 441060 Ru-106 1.27160E-02 5.52130E-02 44106.82c + 425 441070 Ru-107 1.80830E-02 4.95940E-02 441070 + 426 441080 Ru-108 2.56430E-02 4.17710E-02 441080 + 427 441090 Ru-109 2.01360E-02 2.83520E-02 441090 + 428 441100 Ru-110 1.54390E-02 1.78880E-02 441100 + 429 441110 Ru-111 6.54530E-03 7.22000E-03 441110 + 430 441120 Ru-112 2.55680E-03 2.63880E-03 441120 + 431 441130 Ru-113 2.45740E-04 3.76100E-04 441130 + 432 441131 Ru-113m 2.45740E-04 2.45740E-04 441131 + 433 441140 Ru-114 7.40380E-05 7.40380E-05 441140 + 434 441150 Ru-115 8.97530E-06 8.97530E-06 441150 + 435 441160 Ru-116 7.73400E-07 7.73400E-07 441160 + 436 451030 Rh-103 1.15660E-07 6.06480E-02 45103.82c + 437 451031 Rh-103m 8.68670E-07 5.99210E-02 451031 + 438 451040 Rh-104 1.48640E-06 6.65900E-06 451040 + 439 451041 Rh-104m 5.17920E-06 5.17920E-06 451041 + 440 451050 Rh-105 6.54450E-05 5.87600E-02 45105.82c + 441 451051 Rh-105m 8.71370E-06 1.66680E-02 451051 + 442 451060 Rh-106 1.00250E-04 5.53130E-02 451060 + 443 451061 Rh-106m 2.73280E-04 2.73280E-04 451061 + 444 451070 Rh-107 1.54780E-03 5.11420E-02 451070 + 445 451080 Rh-108 8.82970E-04 4.26540E-02 451080 + 446 451081 Rh-108m 3.07650E-03 3.07650E-03 451081 + 447 451090 Rh-109 8.96450E-03 3.73170E-02 451090 + 448 451100 Rh-110 1.10520E-02 2.89400E-02 451100 + 449 451101 Rh-110m 2.60180E-04 2.60180E-04 451101 + 450 451110 Rh-111 1.31380E-02 2.03580E-02 451110 + 451 451120 Rh-112 4.07350E-03 6.71230E-03 451120 + 452 451121 Rh-112m 4.07350E-03 4.07350E-03 451121 + 453 451130 Rh-113 4.78790E-03 5.28690E-03 451130 + 454 451140 Rh-114 7.85700E-04 8.59760E-04 451140 + 455 451141 Rh-114m 7.85700E-04 7.85700E-04 451141 + 456 451150 Rh-115 4.59790E-04 4.68750E-04 451150 + 457 451160 Rh-116 2.13010E-05 2.20660E-05 451160 + 458 451161 Rh-116m 5.80630E-05 5.80630E-05 451161 + 459 451170 Rh-117 3.15230E-05 3.15230E-05 451170 + 460 451180 Rh-118 6.66090E-06 6.66090E-06 451180 + 461 451190 Rh-119 2.70260E-06 2.70260E-06 451190 + 462 461060 Pd-106 2.87330E-06 5.55890E-02 46106.82c + 463 461070 Pd-107 8.08490E-06 5.11680E-02 46107.82c + 464 461071 Pd-107m 1.77700E-05 1.77700E-05 461071 + 465 461080 Pd-108 1.70640E-04 4.59020E-02 46108.82c + 466 461090 Pd-109 2.11250E-04 3.79920E-02 461090 + 467 461091 Pd-109m 4.64310E-04 1.91230E-02 461091 + 468 461100 Pd-110 2.03720E-03 3.12370E-02 46110.82c + 469 461110 Pd-111 1.06410E-03 2.31070E-02 461110 + 470 461111 Pd-111m 2.33880E-03 2.42030E-03 461111 + 471 461120 Pd-112 5.49040E-03 1.62760E-02 461120 + 472 461130 Pd-113 1.21810E-03 9.91300E-03 461130 + 473 461131 Pd-113m 3.40810E-03 3.40810E-03 461131 + 474 461140 Pd-114 3.57190E-03 5.21740E-03 461140 + 475 461150 Pd-115 4.24900E-04 9.05740E-04 461150 + 476 461151 Pd-115m 9.33900E-04 1.00200E-03 461151 + 477 461160 Pd-116 6.66420E-04 7.46550E-04 461160 + 478 461170 Pd-117 5.05700E-05 1.93440E-04 461170 + 479 461171 Pd-117m 1.11150E-04 1.11150E-04 461171 + 480 461180 Pd-118 4.68630E-05 5.33300E-05 461180 + 481 461190 Pd-119 8.83340E-06 1.15360E-05 461190 + 482 461200 Pd-120 1.91010E-06 1.91010E-06 461200 + 483 461210 Pd-121 8.45040E-11 8.45040E-11 461210 + 484 461230 Pd-123 4.72110E-08 4.72110E-08 461230 + 485 461240 Pd-124 3.04260E-09 3.04260E-09 461240 + 486 471080 Ag-108 6.04650E-10 7.48040E-10 471080 + 487 471081 Ag-108m 1.64810E-09 1.64810E-09 471081 + 488 471090 Ag-109 5.35270E-07 3.79970E-02 47109.82c + 489 471091 Ag-109m 4.02020E-06 3.79780E-02 471091 + 490 471100 Ag-110 6.30340E-06 6.53700E-06 471100 + 491 471101 Ag-110m 1.71820E-05 1.71820E-05 47510.82c + 492 471110 Ag-111 1.88410E-05 2.38030E-02 47111.82c + 493 471111 Ag-111m 1.41510E-04 2.35510E-02 471111 + 494 471120 Ag-112 3.86700E-04 1.66630E-02 471120 + 495 471130 Ag-113 1.00300E-04 7.07810E-03 471130 + 496 471131 Ag-113m 7.53320E-04 1.02460E-02 471131 + 497 471140 Ag-114 1.80350E-04 6.27210E-03 471140 + 498 471141 Ag-114m 8.74350E-04 8.74350E-04 471141 + 499 471150 Ag-115 1.26970E-04 1.23340E-03 471150 + 500 471151 Ag-115m 9.53630E-04 2.12000E-03 471151 + 501 471160 Ag-116 1.82150E-04 9.58490E-04 471160 + 502 471161 Ag-116m 4.96510E-04 4.96510E-04 471161 + 503 471170 Ag-117 5.55930E-05 1.83170E-04 471170 + 504 471171 Ag-117m 4.17540E-04 5.14260E-04 471171 + 505 471180 Ag-118 3.51150E-05 1.53740E-04 471180 + 506 471181 Ag-118m 1.70230E-04 1.77860E-04 471181 + 507 471190 Ag-119 1.23450E-05 1.81120E-05 471190 + 508 471191 Ag-119m 9.27150E-05 9.84830E-05 471191 + 509 471200 Ag-120 7.46570E-06 1.33940E-05 471200 + 510 471201 Ag-120m 1.24850E-05 1.34400E-05 471201 + 511 471210 Ag-121 3.99760E-05 3.99760E-05 471210 + 512 471220 Ag-122 1.01300E-05 1.01300E-05 471220 + 513 471221 Ag-122m 1.09210E-05 1.09210E-05 471221 + 514 471230 Ag-123 2.52430E-05 2.52900E-05 471230 + 515 471240 Ag-124 1.03710E-06 1.59920E-06 471240 + 516 471241 Ag-124m 1.11810E-06 1.11810E-06 471241 + 517 471250 Ag-125 1.01670E-06 1.01670E-06 471250 + 518 471260 Ag-126 3.78520E-08 3.78520E-08 471260 + 519 471270 Ag-127 1.75850E-09 1.75850E-09 471270 + 520 481110 Cd-111 1.85430E-07 2.39220E-02 48111.82c + 521 481111 Cd-111m 7.02200E-07 7.02200E-07 481111 + 522 481120 Cd-112 5.37530E-06 1.66680E-02 48112.82c + 523 481130 Cd-113 6.58850E-06 1.06510E-02 48113.82c + 524 481131 Cd-113m 2.49510E-05 1.47320E-04 481131 + 525 481140 Cd-114 7.56530E-05 6.34770E-03 48114.82c + 526 481150 Cd-115 2.28830E-05 2.81120E-03 481150 + 527 481151 Cd-115m 8.66570E-05 2.06490E-04 48515.82c + 528 481160 Cd-116 1.30650E-04 1.55590E-03 48116.82c + 529 481170 Cd-117 2.62880E-05 5.42110E-04 481170 + 530 481171 Cd-117m 9.95520E-05 2.50300E-04 481171 + 531 481180 Cd-118 1.44190E-04 4.02870E-04 481180 + 532 481190 Cd-119 2.79180E-05 1.35460E-04 481190 + 533 481191 Cd-119m 7.81120E-05 8.71690E-05 481191 + 534 481200 Cd-120 7.78430E-05 9.97040E-05 481200 + 535 481210 Cd-121 4.09060E-05 7.67050E-05 481210 + 536 481211 Cd-121m 1.14450E-04 1.18630E-04 481211 + 537 481220 Cd-122 1.93640E-04 2.14690E-04 481220 + 538 481230 Cd-123 5.77210E-05 7.84130E-05 481230 + 539 481231 Cd-123m 1.61500E-04 1.66100E-04 481231 + 540 481240 Cd-124 2.94670E-04 2.96830E-04 481240 + 541 481250 Cd-125 4.22410E-05 4.27500E-05 481250 + 542 481251 Cd-125m 1.18190E-04 1.18700E-04 481251 + 543 481260 Cd-126 6.27750E-05 6.28130E-05 481260 + 544 481270 Cd-127 1.90500E-05 1.90520E-05 481270 + 545 481280 Cd-128 3.73350E-06 3.73350E-06 481280 + 546 481290 Cd-129 8.45270E-09 8.45270E-09 481290 + 547 481291 Cd-129m 2.36500E-08 2.36500E-08 481291 + 548 481300 Cd-130 8.12090E-10 8.12090E-10 481300 + 549 491130 In-113 5.31370E-10 1.47120E-04 49113.82c + 550 491131 In-113m 1.06990E-10 1.06990E-10 491131 + 551 491140 In-114 1.91820E-07 8.36790E-07 491140 + 552 491141 In-114m 3.09750E-07 6.68360E-07 491141 + 553 491142 In-114m 3.58610E-07 3.58610E-07 491142 + 554 491150 In-115 2.70000E-06 2.88030E-03 49115.82c + 555 491151 In-115m 5.43630E-07 2.81180E-03 491151 + 556 491160 In-116 1.02480E-06 1.02480E-06 491160 + 557 491161 In-116m 1.65490E-06 3.57080E-06 491161 + 558 491162 In-116m 1.91590E-06 1.91590E-06 491162 + 559 491170 In-117 9.92220E-06 5.38450E-04 491170 + 560 491171 In-117m 1.99780E-06 5.02610E-04 491171 + 561 491180 In-118 3.81130E-06 4.06680E-04 491180 + 562 491181 In-118m 6.15450E-06 1.31800E-05 491181 + 563 491182 In-118m 7.12520E-06 7.12520E-06 491182 + 564 491190 In-119 1.61010E-05 1.23290E-04 491190 + 565 491191 In-119m 3.24190E-06 1.25720E-04 491191 + 566 491200 In-120 7.10530E-06 1.06810E-04 491200 + 567 491201 In-120m 7.10530E-06 7.10530E-06 491201 + 568 491202 In-120m 7.10530E-06 7.10530E-06 491202 + 569 491210 In-121 1.14320E-04 2.59670E-04 491210 + 570 491211 In-121m 2.30180E-05 7.38900E-05 491211 + 571 491220 In-122 5.76010E-05 2.72290E-04 491220 + 572 491221 In-122m 4.81650E-05 4.81650E-05 491221 + 573 491222 In-122m 4.81650E-05 4.81650E-05 491222 + 574 491230 In-123 2.82160E-04 4.70520E-04 491230 + 575 491231 In-123m 5.68110E-05 1.12960E-04 491231 + 576 491240 In-124 2.48080E-04 5.44910E-04 491240 + 577 491241 In-124m 2.67470E-04 2.67470E-04 491241 + 578 491250 In-125 8.89670E-04 1.02880E-03 491250 + 579 491251 In-125m 1.79130E-04 2.01420E-04 491251 + 580 491260 In-126 4.60770E-04 5.23590E-04 491260 + 581 491261 In-126m 4.96780E-04 4.96780E-04 491261 + 582 491270 In-127 8.83180E-04 8.83180E-04 491270 + 583 491271 In-127m 1.77820E-04 1.96880E-04 491271 + 584 491280 In-128 1.82260E-04 2.57360E-04 491280 + 585 491281 In-128m 7.13670E-05 7.51000E-05 491281 + 586 491282 In-128m 2.73450E-04 2.73450E-04 491282 + 587 491290 In-129 2.04930E-04 2.04950E-04 491290 + 588 491291 In-129m 4.12610E-05 4.12700E-05 491291 + 589 491300 In-130 9.67930E-06 9.68010E-06 491300 + 590 491301 In-130m 1.40940E-05 1.40940E-05 491301 + 591 491302 In-130m 1.96320E-05 1.96320E-05 491302 + 592 491310 In-131 2.45890E-06 2.48390E-06 491310 + 593 491311 In-131m 2.45890E-06 2.45890E-06 491311 + 594 491312 In-131m 2.45890E-06 2.45890E-06 491312 + 595 491320 In-132 8.56840E-09 8.56840E-09 491320 + 596 501160 Sn-116 1.18370E-09 4.59680E-06 50116.82c + 597 501170 Sn-117 4.37370E-09 8.04350E-04 50117.82c + 598 501171 Sn-117m 1.65630E-08 1.85110E-06 501171 + 599 501180 Sn-118 2.99030E-07 4.20260E-04 50118.82c + 600 501190 Sn-119 1.40600E-07 2.42640E-04 50119.82c + 601 501191 Sn-119m 5.32460E-07 1.11910E-04 501191 + 602 501200 Sn-120 1.50270E-06 1.22540E-04 50120.82c + 603 501210 Sn-121 4.05380E-06 3.38940E-04 501210 + 604 501211 Sn-121m 1.13420E-05 4.07590E-05 501211 + 605 501220 Sn-122 3.64700E-05 4.05180E-04 50122.82c + 606 501230 Sn-123 7.89820E-05 1.14850E-04 50123.82c + 607 501231 Sn-123m 2.82280E-05 5.75840E-04 501231 + 608 501240 Sn-124 3.93400E-04 1.20580E-03 50124.82c + 609 501250 Sn-125 6.56010E-04 8.29800E-04 50125.82c + 610 501251 Sn-125m 2.34460E-04 1.29090E-03 501251 + 611 501260 Sn-126 2.47600E-03 3.49770E-03 50126.82c + 612 501270 Sn-127 2.86640E-03 3.21070E-03 501270 + 613 501271 Sn-127m 1.02450E-03 1.75890E-03 501271 + 614 501280 Sn-128 1.66050E-03 6.71750E-03 501280 + 615 501281 Sn-128m 4.52620E-03 4.79960E-03 501281 + 616 501290 Sn-129 1.11030E-03 1.33480E-03 501290 + 617 501291 Sn-129m 3.10660E-03 3.12840E-03 501291 + 618 501300 Sn-130 7.54900E-04 7.81440E-04 501300 + 619 501301 Sn-130m 2.05770E-03 2.07460E-03 501301 + 620 501310 Sn-131 2.54830E-04 2.59590E-04 501310 + 621 501311 Sn-131m 7.12990E-04 7.15560E-04 501311 + 622 501320 Sn-132 2.35510E-04 2.35520E-04 501320 + 623 501330 Sn-133 1.59420E-05 1.59420E-05 501330 + 624 501340 Sn-134 1.15880E-07 1.15880E-07 501340 + 625 501350 Sn-135 2.06700E-09 2.06700E-09 501350 + 626 511180 Sb-118 1.14750E-11 1.14750E-11 511180 + 627 511181 Sb-118m 1.91910E-11 1.91910E-11 511181 + 628 511190 Sb-119 8.72970E-10 1.22350E-09 511190 + 629 511191 Sb-119m 3.50530E-10 3.50530E-10 511191 + 630 511200 Sb-120 5.64480E-09 5.64480E-09 511200 + 631 511201 Sb-120m 9.44020E-09 9.44020E-09 511201 + 632 511210 Sb-121 8.32950E-07 3.48900E-04 51121.82c + 633 511220 Sb-122 1.39110E-06 3.25490E-06 511220 + 634 511221 Sb-122m 1.86380E-06 1.86380E-06 511221 + 635 511230 Sb-123 9.57750E-06 7.00270E-04 51123.82c + 636 511240 Sb-124 1.00230E-05 2.57950E-05 51124.82c + 637 511241 Sb-124m 8.08520E-06 2.10290E-05 511241 + 638 511242 Sb-124m 1.29440E-05 1.29440E-05 511242 + 639 511250 Sb-125 1.15480E-04 2.23620E-03 51125.82c + 640 511260 Sb-126 1.32180E-04 1.58070E-04 51126.82c + 641 511261 Sb-126m 8.25620E-05 1.84910E-04 511261 + 642 511262 Sb-126m 1.02350E-04 1.02350E-04 511262 + 643 511270 Sb-127 1.63200E-03 6.60160E-03 511270 + 644 511280 Sb-128 1.66910E-03 8.47060E-03 511280 + 645 511281 Sb-128m 2.33440E-03 2.33440E-03 511281 + 646 511290 Sb-129 6.16190E-03 9.97950E-03 511290 + 647 511291 Sb-129m 4.56010E-03 6.12420E-03 511291 + 648 511300 Sb-130 5.66600E-03 7.48480E-03 511300 + 649 511301 Sb-130m 5.66600E-03 6.70330E-03 511301 + 650 511310 Sb-131 1.39680E-02 1.49430E-02 511310 + 651 511320 Sb-132 4.22370E-03 4.45920E-03 511320 + 652 511321 Sb-132m 3.73950E-03 3.73950E-03 511321 + 653 511330 Sb-133 3.72570E-03 3.74170E-03 511330 + 654 511340 Sb-134 1.43420E-04 1.43520E-04 511340 + 655 511341 Sb-134m 3.90930E-04 3.90930E-04 511341 + 656 511350 Sb-135 9.93660E-05 9.93680E-05 511350 + 657 511360 Sb-136 6.66840E-06 6.66840E-06 511360 + 658 511370 Sb-137 1.66650E-08 1.66650E-08 511370 + 659 521210 Te-121 6.39920E-11 2.78950E-10 521210 + 660 521211 Te-121m 2.42340E-10 2.42340E-10 521211 + 661 521220 Te-122 1.63980E-08 3.18670E-06 52122.82c + 662 521240 Te-124 1.07450E-06 3.21270E-05 52124.82c + 663 521250 Te-125 1.06020E-06 2.24130E-03 52125.82c + 664 521251 Te-125m 4.01490E-06 5.04400E-04 521251 + 665 521260 Te-126 1.16380E-05 3.28730E-04 52126.82c + 666 521270 Te-127 1.73460E-05 6.64020E-03 521270 + 667 521271 Te-127m 4.85330E-05 1.13640E-03 52527.82c + 668 521280 Te-128 5.31300E-04 1.12530E-02 52128.82c + 669 521290 Te-129 5.75130E-04 1.42800E-02 521290 + 670 521291 Te-129m 1.60920E-03 8.34890E-03 52529.82c + 671 521300 Te-130 8.22530E-03 2.24130E-02 52130.82c + 672 521310 Te-131 4.08850E-03 2.04890E-02 521310 + 673 521311 Te-131m 1.14400E-02 1.26360E-02 521311 + 674 521320 Te-132 3.00570E-02 3.82560E-02 52132.82c + 675 521330 Te-133 6.85030E-03 1.34130E-02 521330 + 676 521331 Te-133m 1.91670E-02 1.98140E-02 521331 + 677 521340 Te-134 1.84570E-02 1.90070E-02 521340 + 678 521350 Te-135 5.01260E-03 5.09740E-03 521350 + 679 521360 Te-136 1.50830E-03 1.51390E-03 521360 + 680 521370 Te-137 2.15050E-04 2.15060E-04 521370 + 681 521380 Te-138 3.06610E-05 3.06610E-05 521380 + 682 521390 Te-139 1.99150E-06 1.99150E-06 521390 + 683 521400 Te-140 1.79400E-09 1.79400E-09 521400 + 684 531270 I-127 4.88470E-09 6.66750E-03 53127.82c + 685 531280 I-128 5.57980E-06 5.57980E-06 531280 + 686 531290 I-129 4.56210E-05 1.74150E-02 53129.82c + 687 531300 I-130 1.66790E-04 2.18190E-04 53130.82c + 688 531301 I-130m 6.11900E-05 6.11900E-05 531301 + 689 531310 I-131 1.68990E-03 3.21610E-02 53131.82c + 690 531320 I-132 2.88010E-03 4.33290E-02 531320 + 691 531321 I-132m 2.55000E-03 2.55000E-03 531321 + 692 531330 I-133 1.08420E-02 4.86240E-02 531330 + 693 531331 I-133m 8.02330E-03 8.02330E-03 531331 + 694 531340 I-134 1.53040E-02 4.75490E-02 531340 + 695 531341 I-134m 1.35500E-02 1.35500E-02 531341 + 696 531350 I-135 4.02840E-02 4.53810E-02 53135.82c + 697 531360 I-136 5.06180E-03 6.57880E-03 531360 + 698 531361 I-136m 1.37970E-02 1.38010E-02 531361 + 699 531370 I-137 1.04860E-02 1.06970E-02 531370 + 700 531380 I-138 2.15290E-03 2.18160E-03 531380 + 701 531390 I-139 7.58870E-04 7.60860E-04 531390 + 702 531400 I-140 1.01730E-04 1.01730E-04 531400 + 703 531410 I-141 1.77410E-05 1.77410E-05 531410 + 704 531420 I-142 8.47220E-09 8.47220E-09 531420 + 705 541290 Xe-129 3.24480E-10 1.55330E-09 54129.82c + 706 541291 Xe-129m 1.22880E-09 1.22880E-09 541291 + 707 541300 Xe-130 4.35700E-06 2.32340E-04 54130.82c + 708 541310 Xe-131 4.86000E-06 3.21790E-02 54131.82c + 709 541311 Xe-131m 1.35980E-05 3.62930E-04 541311 + 710 541320 Xe-132 1.03690E-04 4.39290E-02 54132.82c + 711 541321 Xe-132m 1.38920E-04 1.38920E-04 541321 + 712 541330 Xe-133 3.34600E-04 4.98950E-02 54133.82c + 713 541331 Xe-133m 9.36200E-04 2.32020E-03 541331 + 714 541340 Xe-134 1.94740E-03 5.51160E-02 54134.82c + 715 541341 Xe-134m 5.30820E-03 5.61980E-03 541341 + 716 541350 Xe-135 5.81500E-03 6.73240E-02 54135.82c + 717 541351 Xe-135m 1.62700E-02 2.37620E-02 541351 + 718 541360 Xe-136 5.00770E-02 7.11520E-02 54136.82c + 719 541370 Xe-137 4.00790E-02 5.01960E-02 541370 + 720 541380 Xe-138 2.58910E-02 2.80320E-02 541380 + 721 541390 Xe-139 1.09920E-02 1.16880E-02 541390 + 722 541400 Xe-140 5.68790E-03 5.78390E-03 541400 + 723 541410 Xe-141 1.53930E-03 1.55330E-03 541410 + 724 541420 Xe-142 3.52920E-04 3.52930E-04 541420 + 725 541430 Xe-143 4.49740E-05 4.49740E-05 541430 + 726 541440 Xe-144 3.23720E-06 3.23720E-06 541440 + 727 541450 Xe-145 1.04210E-09 1.04210E-09 541450 + 728 551320 Cs-132 2.89190E-08 2.89190E-08 551320 + 729 551330 Cs-133 4.69070E-06 4.98990E-02 55133.82c + 730 551340 Cs-134 3.45080E-05 6.50600E-05 55134.82c + 731 551341 Cs-134m 3.05520E-05 3.05520E-05 551341 + 732 551350 Cs-135 3.87270E-04 6.81400E-02 55135.82c + 733 551351 Cs-135m 2.86590E-04 2.86590E-04 551351 + 734 551360 Cs-136 2.13420E-03 2.89710E-03 55136.82c + 735 551361 Cs-136m 1.52590E-03 1.52590E-03 551361 + 736 551370 Cs-137 1.88300E-02 6.90260E-02 55137.82c + 737 551380 Cs-138 8.71550E-03 4.85530E-02 551380 + 738 551381 Cs-138m 1.45750E-02 1.45750E-02 551381 + 739 551390 Cs-139 2.86280E-02 4.03160E-02 551390 + 740 551400 Cs-140 1.95530E-02 2.53380E-02 551400 + 741 551410 Cs-141 1.87160E-02 2.02700E-02 551410 + 742 551420 Cs-142 7.53030E-03 7.88240E-03 551420 + 743 551430 Cs-143 2.73730E-03 2.78190E-03 551430 + 744 551440 Cs-144 2.95100E-04 4.45790E-04 551440 + 745 551441 Cs-144m 2.95100E-04 2.95100E-04 551441 + 746 551450 Cs-145 1.13170E-04 1.13170E-04 551450 + 747 551460 Cs-146 3.17300E-06 3.17300E-06 551460 + 748 551470 Cs-147 5.47820E-09 5.47820E-09 551470 + 749 561340 Ba-134 7.99140E-09 6.50680E-05 56134.82c + 750 561350 Ba-135 5.03720E-07 1.91310E-06 56135.82c + 751 561351 Ba-135m 1.40940E-06 1.40940E-06 561351 + 752 561360 Ba-136 2.04740E-05 3.73630E-03 56136.82c + 753 561361 Ba-136m 5.58090E-05 5.58090E-05 561361 + 754 561370 Ba-137 1.97990E-04 6.97780E-02 56137.82c + 755 561371 Ba-137m 5.53980E-04 6.57140E-02 561371 + 756 561380 Ba-138 5.14480E-03 5.64670E-02 56138.82c + 757 561390 Ba-139 1.11830E-02 5.14990E-02 561390 + 758 561400 Ba-140 2.37140E-02 4.90520E-02 56140.82c + 759 561410 Ba-141 2.59170E-02 4.61870E-02 561410 + 760 561420 Ba-142 3.36380E-02 4.15660E-02 561420 + 761 561430 Ba-143 2.04180E-02 2.31690E-02 561430 + 762 561440 Ba-144 1.29630E-02 1.35580E-02 561440 + 763 561450 Ba-145 4.18060E-03 4.27800E-03 561450 + 764 561460 Ba-146 1.42230E-03 1.42500E-03 561460 + 765 561470 Ba-147 2.66840E-04 2.66840E-04 561470 + 766 561480 Ba-148 4.76070E-05 4.76070E-05 561480 + 767 561490 Ba-149 1.08280E-06 1.08280E-06 561490 + 768 561500 Ba-150 5.62000E-10 5.62000E-10 561500 + 769 571370 La-137 5.33190E-06 5.33190E-06 571370 + 770 571380 La-138 2.01350E-05 2.01350E-05 57138.82c + 771 571390 La-139 2.95850E-04 5.17970E-02 57139.82c + 772 571400 La-140 1.05000E-03 5.01020E-02 57140.82c + 773 571410 La-141 4.08640E-03 5.02730E-02 571410 + 774 571420 La-142 6.80450E-03 4.83700E-02 571420 + 775 571430 La-143 1.62410E-02 3.94100E-02 571430 + 776 571440 La-144 1.80700E-02 3.16280E-02 571440 + 777 571450 La-145 1.80760E-02 2.23540E-02 571450 + 778 571460 La-146 3.08460E-03 4.50970E-03 571460 + 779 571461 La-146m 6.47130E-03 6.47130E-03 571461 + 780 571470 La-147 5.66920E-03 5.93620E-03 571470 + 781 571480 La-148 1.75520E-03 1.80260E-03 571480 + 782 571490 La-149 4.78900E-04 4.79980E-04 571490 + 783 571500 La-150 5.75440E-05 5.75450E-05 571500 + 784 571510 La-151 5.42000E-06 5.42000E-06 571510 + 785 571520 La-152 1.52750E-09 1.52750E-09 571520 + 786 581390 Ce-139 5.24390E-07 1.99160E-06 581390 + 787 581391 Ce-139m 1.46720E-06 1.46720E-06 581391 + 788 581400 Ce-140 2.62280E-05 5.01280E-02 58140.82c + 789 581410 Ce-141 1.36650E-04 5.04100E-02 58141.82c + 790 581420 Ce-142 6.98380E-04 4.90690E-02 58142.82c + 791 581430 Ce-143 1.93640E-03 4.13460E-02 58143.82c + 792 581440 Ce-144 6.85390E-03 3.84820E-02 58144.82c + 793 581450 Ce-145 1.18090E-02 3.41630E-02 581450 + 794 581460 Ce-146 1.87050E-02 2.96860E-02 581460 + 795 581470 Ce-147 1.63680E-02 2.23040E-02 581470 + 796 581480 Ce-148 1.42790E-02 1.60880E-02 581480 + 797 581490 Ce-149 6.57030E-03 7.04510E-03 581490 + 798 581500 Ce-150 2.95730E-03 3.01330E-03 581500 + 799 581510 Ce-151 7.23690E-04 7.29110E-04 581510 + 800 581520 Ce-152 1.33170E-04 1.33170E-04 581520 + 801 581530 Ce-153 1.84750E-05 1.84750E-05 581530 + 802 581540 Ce-154 9.40230E-09 9.40230E-09 581540 + 803 581550 Ce-155 1.28110E-10 1.28110E-10 581550 + 804 591420 Pr-142 2.82870E-07 1.05390E-06 59142.82c + 805 591421 Pr-142m 7.71030E-07 7.71030E-07 591421 + 806 591430 Pr-143 1.57010E-05 4.13620E-02 59143.82c + 807 591440 Pr-144 6.95960E-06 3.85590E-02 591440 + 808 591441 Pr-144m 7.08010E-05 6.01830E-04 591441 + 809 591450 Pr-145 4.43380E-04 3.46060E-02 591450 + 810 591460 Pr-146 1.43570E-03 3.11220E-02 591460 + 811 591470 Pr-147 4.06840E-03 2.63730E-02 591470 + 812 591480 Pr-148 1.06740E-03 1.71560E-02 591480 + 813 591481 Pr-148m 5.17450E-03 5.17450E-03 591481 + 814 591490 Pr-149 9.18910E-03 1.62340E-02 591490 + 815 591500 Pr-150 6.87660E-03 9.88990E-03 591500 + 816 591510 Pr-151 5.06280E-03 5.79190E-03 591510 + 817 591520 Pr-152 2.00150E-03 2.13480E-03 591520 + 818 591530 Pr-153 6.82540E-04 7.00900E-04 591530 + 819 591540 Pr-154 1.21360E-04 1.21370E-04 591540 + 820 591550 Pr-155 2.83590E-05 2.83590E-05 591550 + 821 591560 Pr-156 1.09000E-06 1.09000E-06 591560 + 822 591570 Pr-157 4.22380E-10 4.22380E-10 591570 + 823 601440 Nd-144 1.07910E-06 3.85610E-02 60144.82c + 824 601450 Nd-145 2.11830E-06 3.46090E-02 60145.82c + 825 601460 Nd-146 5.71440E-05 3.11790E-02 60146.82c + 826 601470 Nd-147 2.60620E-04 2.66330E-02 60147.82c + 827 601480 Nd-148 1.06470E-03 2.33950E-02 60148.82c + 828 601490 Nd-149 2.49590E-03 1.87300E-02 601490 + 829 601500 Nd-150 5.52090E-03 1.54110E-02 60150.82c + 830 601510 Nd-151 6.36720E-03 1.21590E-02 601510 + 831 601520 Nd-152 6.86220E-03 8.99700E-03 601520 + 832 601530 Nd-153 4.21080E-03 4.91170E-03 601530 + 833 601540 Nd-154 2.35930E-03 2.48070E-03 601540 + 834 601550 Nd-155 7.44870E-04 7.73260E-04 601550 + 835 601560 Nd-156 2.21060E-04 2.22120E-04 601560 + 836 601570 Nd-157 3.28670E-05 3.28670E-05 601570 + 837 601580 Nd-158 6.48320E-06 6.48320E-06 601580 + 838 601590 Nd-159 1.36140E-09 1.36140E-09 601590 + 839 601600 Nd-160 2.69660E-11 2.69660E-11 601600 + 840 611470 Pm-147 2.58260E-08 2.66330E-02 61147.82c + 841 611480 Pm-148 1.45300E-06 1.65100E-06 61148.82c + 842 611481 Pm-148m 3.96050E-06 3.96050E-06 61548.82c + 843 611490 Pm-149 4.00730E-05 1.87700E-02 61149.82c + 844 611500 Pm-150 1.66300E-04 1.66300E-04 611500 + 845 611510 Pm-151 5.86220E-04 1.27450E-02 61151.82c + 846 611520 Pm-152 2.13310E-04 9.21030E-03 611520 + 847 611521 Pm-152m 4.48440E-04 4.48440E-04 611521 + 848 611522 Pm-152m 5.85780E-04 5.85780E-04 611522 + 849 611530 Pm-153 2.29270E-03 7.20440E-03 611530 + 850 611540 Pm-154 1.19410E-03 3.67480E-03 611540 + 851 611541 Pm-154m 1.19410E-03 1.19410E-03 611541 + 852 611550 Pm-155 2.06920E-03 2.84250E-03 611550 + 853 611560 Pm-156 1.07990E-03 1.30200E-03 611560 + 854 611570 Pm-157 5.22210E-04 5.55080E-04 611570 + 855 611580 Pm-158 1.36110E-04 1.42590E-04 611580 + 856 611590 Pm-159 2.65350E-05 2.65360E-05 611590 + 857 611600 Pm-160 4.15190E-06 4.15190E-06 611600 + 858 611610 Pm-161 4.05720E-09 4.05720E-09 611610 + 859 611620 Pm-162 4.37990E-11 4.37990E-11 611620 + 860 621490 Sm-149 1.08290E-06 1.87710E-02 62149.82c + 861 621500 Sm-150 1.08630E-06 1.67390E-04 62150.82c + 862 621510 Sm-151 2.38510E-05 1.27690E-02 62151.82c + 863 621520 Sm-152 1.23580E-04 1.03680E-02 62152.82c + 864 621530 Sm-153 8.91110E-05 7.54280E-03 62153.82c + 865 621531 Sm-153m 2.49330E-04 2.49330E-04 621531 + 866 621540 Sm-154 8.99060E-04 5.76790E-03 62154.82c + 867 621550 Sm-155 1.36220E-03 4.20470E-03 621550 + 868 621560 Sm-156 1.87890E-03 3.18090E-03 621560 + 869 621570 Sm-157 1.44520E-03 2.00030E-03 621570 + 870 621580 Sm-158 1.02400E-03 1.16660E-03 621580 + 871 621590 Sm-159 4.19550E-04 4.46090E-04 621590 + 872 621600 Sm-160 1.54990E-04 1.59130E-04 621600 + 873 621610 Sm-161 3.07720E-05 3.07760E-05 621610 + 874 621620 Sm-162 9.78290E-06 9.78290E-06 621620 + 875 621630 Sm-163 7.84690E-09 7.84690E-09 621630 + 876 621640 Sm-164 1.48000E-10 1.48000E-10 621640 + 877 621650 Sm-165 2.27200E-12 2.27200E-12 621650 + 878 631510 Eu-151 3.75920E-10 1.27690E-02 63151.82c + 879 631520 Eu-152 3.49020E-09 8.11280E-09 63152.82c + 880 631521 Eu-152m 7.97470E-10 7.97470E-10 631521 + 881 631522 Eu-152m 4.62270E-09 4.62270E-09 631522 + 882 631530 Eu-153 2.82510E-07 7.54310E-03 63153.82c + 883 631540 Eu-154 4.73860E-06 9.84750E-06 63154.82c + 884 631541 Eu-154m 5.10890E-06 5.10890E-06 631541 + 885 631550 Eu-155 4.48090E-05 4.24950E-03 63155.82c + 886 631560 Eu-156 1.52420E-04 3.33330E-03 63156.82c + 887 631570 Eu-157 3.58520E-04 2.35880E-03 63157.82c + 888 631580 Eu-158 3.93070E-04 1.55970E-03 631580 + 889 631590 Eu-159 4.74830E-04 9.20920E-04 631590 + 890 631600 Eu-160 3.28050E-04 4.87180E-04 631600 + 891 631610 Eu-161 1.87430E-04 2.18210E-04 631610 + 892 631620 Eu-162 7.75330E-05 8.73160E-05 631620 + 893 631630 Eu-163 1.78330E-05 1.78410E-05 631630 + 894 631640 Eu-164 2.84090E-06 2.84110E-06 631640 + 895 631650 Eu-165 1.46940E-08 1.46960E-08 631650 + 896 631660 Eu-166 3.42340E-10 3.42340E-10 631660 + 897 631670 Eu-167 4.32340E-12 4.32340E-12 631670 + 898 641540 Gd-154 1.04470E-09 9.84660E-06 64154.82c + 899 641550 Gd-155 7.85920E-09 4.24950E-03 64155.82c + 900 641551 Gd-155m 2.19900E-08 2.19900E-08 641551 + 901 641560 Gd-156 5.44390E-06 3.33880E-03 64156.82c + 902 641570 Gd-157 2.50780E-05 2.38390E-03 64157.82c + 903 641580 Gd-158 8.18310E-05 1.64150E-03 64158.82c + 904 641590 Gd-159 1.64250E-04 1.08520E-03 641590 + 905 641600 Gd-160 2.56540E-04 7.43720E-04 64160.82c + 906 641610 Gd-161 2.70150E-04 4.88360E-04 641610 + 907 641620 Gd-162 2.25420E-04 3.12740E-04 641620 + 908 641630 Gd-163 1.08410E-04 1.26250E-04 641630 + 909 641640 Gd-164 4.83530E-05 5.11940E-05 641640 + 910 641650 Gd-165 1.47110E-05 1.47260E-05 641650 + 911 641660 Gd-166 5.03850E-06 5.03880E-06 641660 + 912 641670 Gd-167 2.36950E-08 2.36990E-08 641670 + 913 641680 Gd-168 4.31290E-10 4.31290E-10 641680 + 914 641690 Gd-169 1.03500E-11 1.03500E-11 641690 + 915 651560 Tb-156 2.77600E-11 8.21400E-11 651560 + 916 651561 Tb-156m 4.70410E-11 4.70410E-11 651561 + 917 651562 Tb-156m 7.35280E-12 7.35280E-12 651562 + 918 651570 Tb-157 2.60460E-09 2.60460E-09 651570 + 919 651580 Tb-158 4.91250E-08 5.39250E-08 651580 + 920 651581 Tb-158m 4.82890E-09 4.82890E-09 651581 + 921 651590 Tb-159 8.52230E-07 1.08600E-03 65159.82c + 922 651600 Tb-160 3.11100E-06 3.11100E-06 65160.82c + 923 651610 Tb-161 3.45360E-05 5.22890E-04 651610 + 924 651620 Tb-162 3.69190E-05 3.49650E-04 651620 + 925 651630 Tb-163 5.39820E-05 1.80230E-04 651630 + 926 651640 Tb-164 3.96730E-05 9.08670E-05 651640 + 927 651650 Tb-165 3.42970E-05 4.90230E-05 651650 + 928 651660 Tb-166 1.81410E-05 2.31800E-05 651660 + 929 651670 Tb-167 8.09520E-06 8.11890E-06 651670 + 930 651680 Tb-168 1.75420E-07 1.75850E-07 651680 + 931 651690 Tb-169 2.58720E-08 2.58820E-08 651690 + 932 651700 Tb-170 1.13650E-09 1.13650E-09 651700 + 933 651710 Tb-171 5.23630E-12 5.23630E-12 651710 + 934 661590 Dy-159 1.62080E-10 1.62080E-10 661590 + 935 661600 Dy-160 6.66050E-09 3.11770E-06 66160.82c + 936 661610 Dy-161 1.04830E-07 5.23000E-04 66161.82c + 937 661620 Dy-162 4.87760E-06 3.54530E-04 66162.82c + 938 661630 Dy-163 3.94060E-06 1.84170E-04 66163.82c + 939 661640 Dy-164 1.41650E-05 1.05070E-04 66164.82c + 940 661650 Dy-165 2.07130E-05 7.24320E-05 661650 + 941 661651 Dy-165m 2.75780E-06 2.75780E-06 661651 + 942 661660 Dy-166 3.11870E-05 5.43670E-05 661660 + 943 661670 Dy-167 1.82010E-05 2.63200E-05 661670 + 944 661680 Dy-168 7.92850E-06 8.10430E-06 661680 + 945 661690 Dy-169 6.50090E-06 6.52680E-06 661690 + 946 661700 Dy-170 4.20400E-06 4.20510E-06 661700 + 947 661710 Dy-171 6.68780E-09 6.69300E-09 661710 + 948 661720 Dy-172 4.97510E-10 4.97510E-10 661720 + 949 661730 Dy-173 2.67970E-11 2.67970E-11 661730 + 950 671610 Ho-161 1.36650E-11 1.54850E-11 671610 + 951 671611 Ho-161m 1.81950E-12 1.81950E-12 671611 + 952 671620 Ho-162 9.40420E-11 2.52970E-10 671620 + 953 671621 Ho-162m 2.56340E-10 2.56340E-10 671621 + 954 671630 Ho-163 6.79550E-09 7.70030E-09 671630 + 955 671631 Ho-163m 9.04780E-10 9.04780E-10 671631 + 956 671640 Ho-164 1.94700E-08 7.25390E-08 671640 + 957 671641 Ho-164m 5.30690E-08 5.30690E-08 671641 + 958 671650 Ho-165 2.93700E-06 7.54310E-05 67165.82c + 959 671660 Ho-166 5.40500E-07 5.49070E-05 671660 + 960 671661 Ho-166m 1.47330E-06 1.47330E-06 671661 + 961 671670 Ho-167 3.03350E-06 2.93530E-05 671670 + 962 671680 Ho-168 3.70790E-07 9.09220E-06 671680 + 963 671681 Ho-168m 6.20110E-07 6.20110E-07 671681 + 964 671690 Ho-169 2.78530E-06 9.31210E-06 671690 + 965 671700 Ho-170 1.53750E-06 1.53750E-06 671700 + 966 671701 Ho-170m 5.64040E-07 4.76920E-06 671701 + 967 671710 Ho-171 2.50380E-07 2.57070E-07 671710 + 968 671720 Ho-172 5.37090E-07 5.37590E-07 671720 + 969 671730 Ho-173 1.60590E-08 1.60860E-08 671730 + 970 671740 Ho-174 1.20090E-09 1.20090E-09 671740 + 971 671750 Ho-175 5.09790E-11 5.09790E-11 671750 + 972 681640 Er-164 1.89750E-11 3.75220E-08 68164.82c + 973 681650 Er-165 5.97530E-10 5.97530E-10 681650 + 974 681660 Er-166 1.41930E-08 5.49210E-05 68166.82c + 975 681670 Er-167 8.00210E-08 2.94440E-05 68167.82c + 976 681671 Er-167m 1.06540E-08 3.51820E-06 681671 + 977 681680 Er-168 2.74730E-07 9.37030E-06 68168.82c + 978 681690 Er-169 1.13990E-06 1.04520E-05 681690 + 979 681700 Er-170 1.05070E-06 7.35740E-06 68170.82c + 980 681710 Er-171 7.65570E-07 1.02260E-06 681710 + 981 681720 Er-172 4.31610E-07 9.69200E-07 681720 + 982 681730 Er-173 3.30880E-07 3.46970E-07 681730 + 983 681740 Er-174 1.33610E-07 1.34810E-07 681740 + 984 681750 Er-175 1.58200E-08 1.58710E-08 681750 + 985 681760 Er-176 1.54570E-09 1.54570E-09 681760 + 986 681770 Er-177 6.71640E-11 6.71640E-11 681770 + 987 691660 Tm-166 4.47400E-13 1.38600E-12 691660 + 988 691670 Tm-167 3.63180E-11 3.63180E-11 691670 + 989 691680 Tm-168 3.28120E-10 3.28120E-10 691680 + 990 691690 Tm-169 8.04670E-09 1.04600E-05 691690 + 991 691700 Tm-170 5.83860E-08 5.83860E-08 691700 + 992 691710 Tm-171 4.55850E-08 1.06820E-06 691710 + 993 691720 Tm-172 9.73160E-08 1.06650E-06 691720 + 994 691730 Tm-173 7.02020E-07 1.04900E-06 691730 + 995 691740 Tm-174 2.96350E-07 4.31160E-07 691740 + 996 691750 Tm-175 1.67840E-07 1.83710E-07 691750 + 997 691760 Tm-176 4.11090E-08 4.26550E-08 691760 + 998 691770 Tm-177 1.00060E-08 1.00730E-08 691770 + 999 691780 Tm-178 9.36140E-10 9.36140E-10 691780 + 1000 691790 Tm-179 7.45070E-11 7.45070E-11 691790 + 1001 701690 Yb-169 1.48110E-12 1.67830E-12 701690 + 1002 701700 Yb-170 7.41670E-11 5.83840E-08 701700 + 1003 701710 Yb-171 1.98300E-11 1.06840E-06 701710 + 1004 701711 Yb-171m 1.48940E-10 1.48940E-10 701711 + 1005 701720 Yb-172 2.07290E-09 1.06860E-06 701720 + 1006 701730 Yb-173 1.85860E-08 1.06760E-06 701730 + 1007 701740 Yb-174 8.10130E-08 5.12580E-07 701740 + 1008 701750 Yb-175 9.00150E-08 2.85710E-07 701750 + 1009 701751 Yb-175m 1.19850E-08 1.53440E-07 701751 + 1010 701760 Yb-176 3.61180E-08 1.44840E-07 701760 + 1011 701761 Yb-176m 7.57720E-08 9.70990E-08 701761 + 1012 701770 Yb-177 5.06390E-08 7.09080E-08 701770 + 1013 701771 Yb-177m 1.01960E-08 2.02690E-08 701771 + 1014 701780 Yb-178 2.83570E-08 2.92930E-08 701780 + 1015 701790 Yb-179 5.89230E-09 5.96680E-09 701790 + 1016 701800 Yb-180 1.05690E-09 1.05690E-09 701800 + 1017 701810 Yb-181 7.40840E-11 7.40840E-11 701810 + 1018 711730 Lu-173 3.27010E-11 3.27010E-11 711730 + 1019 711740 Lu-174 1.09140E-10 4.04910E-10 711740 + 1020 711741 Lu-174m 2.97500E-10 2.97500E-10 711741 + 1021 711750 Lu-175 2.85180E-09 2.88570E-07 71175.82c + 1022 711760 Lu-176 5.27310E-09 1.49830E-08 71176.82c + 1023 711761 Lu-176m 2.51350E-09 2.51350E-09 711761 + 1024 711770 Lu-177 1.34190E-08 8.58070E-08 711770 + 1025 711771 Lu-177m 6.38970E-09 6.54870E-09 711771 + 1026 711772 Lu-177m 3.17970E-10 3.17970E-10 711772 + 1027 711780 Lu-178 8.72490E-09 3.80180E-08 711780 + 1028 711781 Lu-178m 1.16890E-08 1.16890E-08 711781 + 1029 711790 Lu-179 1.69240E-08 2.51440E-08 711790 + 1030 711791 Lu-179m 2.25330E-09 8.22010E-09 711791 + 1031 711800 Lu-180 2.10940E-09 5.56020E-09 711800 + 1032 711801 Lu-180m 2.10940E-09 3.16630E-09 711801 + 1033 711802 Lu-180m 3.73530E-09 3.73530E-09 711802 + 1034 711810 Lu-181 2.89860E-09 2.97270E-09 711810 + 1035 711820 Lu-182 4.20190E-10 4.20190E-10 711820 + 1036 711830 Lu-183 6.20730E-11 6.20730E-11 711830 + 1037 711840 Lu-184 3.50950E-12 3.50950E-12 711840 + 1038 721750 Hf-175 2.57860E-12 2.57860E-12 721750 + 1039 721760 Hf-176 4.24690E-11 2.55360E-09 72176.82c + 1040 721770 Hf-177 2.03150E-10 9.13400E-08 72177.82c + 1041 721771 Hf-177m 9.58490E-11 5.32920E-09 721771 + 1042 721772 Hf-177m 5.66690E-12 1.64650E-10 721772 + 1043 721780 Hf-178 5.35200E-10 5.13670E-08 72178.82c + 1044 721781 Hf-178m 9.98120E-10 1.28130E-08 721781 + 1045 721782 Hf-178m 1.24850E-10 1.24850E-10 721782 + 1046 721790 Hf-179 2.15210E-09 2.88870E-08 72179.82c + 1047 721791 Hf-179m 6.22750E-10 6.22750E-10 721791 + 1048 721792 Hf-179m 9.40810E-10 9.40810E-10 721792 + 1049 721800 Hf-180 2.28850E-09 1.61290E-08 72180.82c + 1050 721801 Hf-180m 4.80110E-09 6.66870E-09 721801 + 1051 721810 Hf-181 5.58730E-09 8.56000E-09 721810 + 1052 721820 Hf-182 1.51320E-09 3.26670E-09 721820 + 1053 721821 Hf-182m 3.17460E-09 3.17460E-09 721821 + 1054 721830 Hf-183 1.33480E-09 1.39690E-09 721830 + 1055 721840 Hf-184 1.31890E-10 1.33640E-10 721840 + 1056 721841 Hf-184m 2.76680E-10 2.78440E-10 721841 + 1057 721850 Hf-185 4.74350E-11 4.74350E-11 721850 + 1058 721860 Hf-186 4.53780E-12 4.53780E-12 721860 + 1059 731781 Ta-178m 1.17720E-12 1.40590E-12 731781 + 1060 731790 Ta-179 1.95980E-11 2.74670E-11 731790 + 1061 731791 Ta-179m 7.43530E-12 7.86930E-12 731791 + 1062 731800 Ta-180 6.01740E-11 6.01740E-11 731800 + 1063 731801 Ta-180m 8.06160E-11 1.01290E-10 731801 + 1064 731810 Ta-181 5.71190E-10 9.13340E-09 73181.82c + 1065 731820 Ta-182 2.83740E-10 2.72030E-09 73182.82c + 1066 731821 Ta-182m 3.09930E-10 2.43660E-09 731821 + 1067 731822 Ta-182m 2.85410E-10 2.12670E-09 731822 + 1068 731830 Ta-183 1.40920E-09 2.80610E-09 731830 + 1069 731840 Ta-184 9.42110E-10 1.35420E-09 731840 + 1070 731850 Ta-185 3.28490E-10 5.71930E-10 731850 + 1071 731851 Ta-185m 1.96010E-10 1.96010E-10 731851 + 1072 731860 Ta-186 1.26120E-10 1.30660E-10 731860 + 1073 731870 Ta-187 3.02340E-11 3.02340E-11 731870 + 1074 731880 Ta-188 2.78500E-12 2.78500E-12 731880 + 1075 741810 W-181 2.21660E-12 2.21660E-12 741810 + 1076 741820 W-182 1.95870E-11 2.73990E-09 74182.82c + 1077 741830 W-183 1.69710E-11 2.88730E-09 74183.82c + 1078 741831 W-183m 6.42670E-11 1.59670E-10 741831 + 1079 741840 W-184 2.67970E-10 1.62360E-09 74184.82c + 1080 741850 W-185 8.71730E-11 9.03020E-10 741850 + 1081 741851 W-185m 2.43910E-10 2.43910E-10 741851 + 1082 741860 W-186 2.53820E-10 4.87910E-10 74186.82c + 1083 741861 W-186m 1.02770E-10 1.02770E-10 741861 + 1084 741870 W-187 1.91330E-10 2.21560E-10 741870 + 1085 741880 W-188 8.80500E-11 9.08350E-11 741880 + 1086 741890 W-189 1.79480E-11 1.79480E-11 741890 + 1087 741900 W-190 1.34830E-12 3.15470E-12 741900 + 1088 741901 W-190m 1.80640E-12 1.80640E-12 741901 + 1089 751840 Re-184 6.77820E-13 1.22880E-12 751840 + 1090 751850 Re-185 9.67060E-12 9.12690E-10 75185.82c + 1091 751860 Re-186 9.67570E-12 9.67570E-12 751860 + 1092 751861 Re-186m 1.61810E-11 1.61810E-11 751861 + 1093 751870 Re-187 6.57850E-11 2.87350E-10 75187.82c + 1094 751880 Re-188 1.76670E-11 1.56660E-10 751880 + 1095 751881 Re-188m 4.81560E-11 4.81560E-11 751881 + 1096 751890 Re-189 6.07270E-11 7.86750E-11 751890 + 1097 751900 Re-190 7.98830E-12 1.87850E-11 751900 + 1098 751901 Re-190m 1.67590E-11 1.67590E-11 751901 + 1099 751910 Re-191 8.89890E-12 8.89890E-12 751910 + 1100 751920 Re-192 1.28530E-12 1.28530E-12 751920 + 1101 761870 Os-187 1.04180E-12 1.04180E-12 761870 + 1102 761880 Os-188 5.57800E-12 1.62240E-10 761880 + 1103 761890 Os-189 2.55760E-12 9.09180E-11 761890 + 1104 761891 Os-189m 9.68540E-12 1.77760E-11 761891 + 1105 761900 Os-190 9.79170E-12 5.08120E-11 761900 + 1106 761901 Os-190m 1.31180E-11 2.22350E-11 761901 + 1107 761910 Os-191 1.40970E-11 2.67180E-11 761910 + 1108 761911 Os-191m 3.72240E-12 3.72240E-12 761911 + 1109 761920 Os-192 5.10400E-12 1.25210E-11 761920 + 1110 761921 Os-192m 6.83800E-12 6.83800E-12 761921 + 1111 761930 Os-193 4.13110E-12 4.13110E-12 761930 + 1112 761940 Os-194 1.24460E-12 1.24460E-12 761940 + 1113 771910 Ir-191 4.99720E-13 2.86160E-11 77191.82c + 1114 771911 Ir-191m 1.04400E-12 1.40090E-11 771911 + 1115 771920 Ir-192 9.69500E-13 3.79730E-12 771920 + 1116 771922 Ir-192m 9.69500E-13 1.85840E-12 771922 + 1117 771930 Ir-193 1.19250E-12 8.66010E-12 77193.82c + 1118 771931 Ir-193m 3.33650E-12 3.35090E-12 771931 + 1119 771940 Ir-194 9.94470E-13 3.23350E-12 771940 + 1120 771951 Ir-195m 1.20460E-12 1.20460E-12 771951 + 1121 781950 Pt-195 2.82260E-13 2.70720E-12 781950 + 1122 781951 Pt-195m 7.89740E-13 1.15600E-12 781951 + 1123 781960 Pt-196 1.13470E-12 1.13470E-12 781960 + + Nuclide 96244.82c -- curium 244 (Cm-244) + + Neutron-induced fission: + + Interpolation region : 1 / 2 + Interpolation energy : 2.53000E-08 MeV + Number of products : 1137 / 1194 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 3.82810E-05 3.82810E-05 1001.82c + 2 10020 H-2 1.16990E-05 1.16990E-05 1002.82c + 3 10030 H-3 1.91000E-04 1.91000E-04 1003.82c + 4 20040 He-4 2.42000E-03 2.42000E-03 2004.82c + 5 190500 K-50 2.34480E-12 2.34480E-12 190500 + 6 190510 K-51 1.06580E-12 1.06580E-12 190510 + 7 200500 Ca-50 2.52830E-11 2.74490E-11 200500 + 8 200510 Ca-51 2.28750E-11 2.34400E-11 200510 + 9 200520 Ca-52 2.11170E-11 2.11170E-11 200520 + 10 200530 Ca-53 6.48850E-12 6.48850E-12 200530 + 11 200540 Ca-54 1.91190E-12 1.91190E-12 200540 + 12 210500 Sc-50 5.05590E-12 3.42930E-11 210500 + 13 210501 Sc-50m 2.15850E-12 2.96070E-11 210501 + 14 210510 Sc-51 3.22010E-11 5.60630E-11 210510 + 15 210520 Sc-52 5.41700E-11 7.68110E-11 210520 + 16 210530 Sc-53 8.79040E-11 9.24460E-11 210530 + 17 210540 Sc-54 5.35260E-11 5.54380E-11 210540 + 18 210550 Sc-55 3.97820E-11 3.97820E-11 210550 + 19 210560 Sc-56 9.80350E-12 9.80350E-12 210560 + 20 210570 Sc-57 2.33210E-12 2.33210E-12 210570 + 21 220510 Ti-51 2.51940E-12 5.85830E-11 220510 + 22 220520 Ti-52 2.23110E-11 9.91220E-11 220520 + 23 220530 Ti-53 6.58590E-11 1.58310E-10 220530 + 24 220540 Ti-54 1.97970E-10 2.53410E-10 220540 + 25 220550 Ti-55 2.74950E-10 3.14730E-10 220550 + 26 220560 Ti-56 3.71340E-10 3.81910E-10 220560 + 27 220570 Ti-57 1.89100E-10 1.90660E-10 220570 + 28 220580 Ti-58 9.87340E-11 9.87340E-11 220580 + 29 220590 Ti-59 1.88560E-11 1.88560E-11 220590 + 30 220600 Ti-60 3.14120E-12 3.14120E-12 220600 + 31 230530 V-53 3.25840E-12 1.61560E-10 230530 + 32 230540 V-54 1.94260E-11 2.72830E-10 230540 + 33 230550 V-55 1.37550E-10 4.52280E-10 230550 + 34 230560 V-56 3.33860E-10 7.16340E-10 230560 + 35 230570 V-57 8.51590E-10 1.04170E-09 230570 + 36 230580 V-58 8.59060E-10 9.57790E-10 230580 + 37 230590 V-59 9.33420E-10 9.52280E-10 230590 + 38 230600 V-60 3.43490E-10 3.46630E-10 230600 + 39 230610 V-61 1.46980E-10 1.46980E-10 230610 + 40 230620 V-62 2.19280E-11 2.19280E-11 230620 + 41 230630 V-63 2.82500E-12 2.82500E-12 230630 + 42 240550 Cr-55 3.36700E-12 4.55650E-10 240550 + 43 240560 Cr-56 4.60050E-11 7.66520E-10 240560 + 44 240570 Cr-57 2.24410E-10 2.02820E-09 240570 + 45 240580 Cr-58 1.12760E-09 1.31920E-09 240580 + 46 240590 Cr-59 2.20660E-09 3.15890E-09 240590 + 47 240600 Cr-60 4.17510E-09 4.53050E-09 240600 + 48 240610 Cr-61 3.58230E-09 3.72050E-09 240610 + 49 240620 Cr-62 3.14890E-09 3.17180E-09 240620 + 50 240630 Cr-63 9.20280E-10 9.22120E-10 240630 + 51 240640 Cr-64 2.55310E-10 2.55310E-10 240640 + 52 240650 Cr-65 2.97820E-11 2.97820E-11 240650 + 53 240660 Cr-66 3.02550E-12 3.02550E-12 240660 + 54 250570 Mn-57 3.36850E-12 2.03150E-09 250570 + 55 250580 Mn-58 3.22480E-11 1.35140E-09 250580 + 56 250581 Mn-58m 3.63090E-12 3.63090E-12 250581 + 57 250590 Mn-59 3.80610E-10 3.53950E-09 250590 + 58 250600 Mn-60 1.35070E-10 4.80360E-09 250600 + 59 250601 Mn-60m 1.19960E-09 1.19960E-09 250601 + 60 250610 Mn-61 5.64360E-09 9.36410E-09 250610 + 61 250620 Mn-62 7.69520E-09 9.28110E-09 250620 + 62 250621 Mn-62m 1.38150E-09 2.96740E-09 250621 + 63 250630 Mn-63 1.41100E-08 1.50320E-08 250630 + 64 250640 Mn-64 8.14710E-09 8.40240E-09 250640 + 65 250650 Mn-65 5.77510E-09 5.80490E-09 250650 + 66 250660 Mn-66 1.36170E-09 1.36470E-09 250660 + 67 250670 Mn-67 3.03810E-10 3.03810E-10 250670 + 68 250680 Mn-68 1.69530E-11 1.69530E-11 250680 + 69 250690 Mn-69 1.84630E-12 1.84630E-12 250690 + 70 260590 Fe-59 2.74900E-12 3.54220E-09 260590 + 71 260600 Fe-60 5.77400E-11 5.92300E-09 260600 + 72 260610 Fe-61 4.99140E-10 9.86320E-09 260610 + 73 260620 Fe-62 4.19740E-09 1.64460E-08 260620 + 74 260630 Fe-63 1.18280E-08 2.68600E-08 260630 + 75 260640 Fe-64 3.37760E-08 4.21780E-08 260640 + 76 260650 Fe-65 4.50100E-08 5.08150E-08 260650 + 77 260660 Fe-66 5.85970E-08 5.99620E-08 260660 + 78 260670 Fe-67 2.81700E-08 2.84740E-08 260670 + 79 260680 Fe-68 9.80780E-09 9.82520E-09 260680 + 80 260690 Fe-69 2.52620E-09 2.52760E-09 260690 + 81 260700 Fe-70 4.00440E-10 4.00440E-10 260700 + 82 260710 Fe-71 9.17380E-12 9.17380E-12 260710 + 83 270610 Co-61 2.15730E-12 9.86540E-09 270610 + 84 270620 Co-62 1.21630E-11 1.64580E-08 270620 + 85 270621 Co-62m 2.84880E-11 2.84880E-11 270621 + 86 270630 Co-63 6.63850E-10 2.75240E-08 270630 + 87 270640 Co-64 3.73240E-09 4.59110E-08 270640 + 88 270650 Co-65 2.52200E-08 7.60350E-08 270650 + 89 270660 Co-66 5.89640E-08 1.18930E-07 270660 + 90 270670 Co-67 1.42600E-07 1.71070E-07 270670 + 91 270680 Co-68 1.32060E-07 1.95310E-07 270680 + 92 270681 Co-68m 1.16500E-07 1.26500E-07 270681 + 93 270690 Co-69 1.42590E-07 1.44940E-07 270690 + 94 270700 Co-70 2.51050E-08 2.51050E-08 270700 + 95 270701 Co-70m 2.51050E-08 2.55050E-08 270701 + 96 270710 Co-71 7.33100E-09 7.34020E-09 270710 + 97 270720 Co-72 5.46000E-10 5.46000E-10 270720 + 98 270730 Co-73 9.71480E-11 9.71480E-11 270730 + 99 270740 Co-74 1.08200E-11 1.08200E-11 270740 + 100 280630 Ni-63 1.35210E-12 2.75250E-08 280630 + 101 280640 Ni-64 4.77790E-11 4.59590E-08 28064.82c + 102 280650 Ni-65 7.02740E-10 7.67380E-08 280650 + 103 280660 Ni-66 9.18120E-09 1.28110E-07 280660 + 104 280670 Ni-67 4.21770E-08 2.13250E-07 280670 + 105 280680 Ni-68 1.41890E-07 4.01900E-07 280680 + 106 280690 Ni-69 1.88960E-07 3.32460E-07 280690 + 107 280691 Ni-69m 1.88960E-07 1.88960E-07 280691 + 108 280700 Ni-70 6.88490E-07 7.39100E-07 280700 + 109 280710 Ni-71 6.01090E-07 6.08430E-07 280710 + 110 280720 Ni-72 5.58670E-07 5.59220E-07 280720 + 111 280730 Ni-73 3.63740E-08 3.64710E-08 280730 + 112 280740 Ni-74 2.62740E-08 2.62850E-08 280740 + 113 280750 Ni-75 1.02480E-09 1.02480E-09 280750 + 114 280760 Ni-76 2.14500E-10 2.14500E-10 280760 + 115 280770 Ni-77 1.34250E-11 1.34250E-11 280770 + 116 290660 Cu-66 2.56640E-11 1.28130E-07 290660 + 117 290670 Cu-67 7.22900E-10 2.13970E-07 290670 + 118 290680 Cu-68 1.53180E-09 4.06450E-07 290680 + 119 290681 Cu-68m 3.58780E-09 3.58780E-09 290681 + 120 290690 Cu-69 7.33810E-08 5.94800E-07 290690 + 121 290700 Cu-70 1.87560E-08 1.42180E-07 290700 + 122 290701 Cu-70m 2.08950E-07 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359 410941 Nb-94m 4.16420E-07 4.16420E-07 410941 + 360 410950 Nb-95 5.77390E-06 2.79660E-02 41095.82c + 361 410951 Nb-95m 1.33510E-06 3.03570E-04 410951 + 362 410960 Nb-96 5.89060E-05 5.89060E-05 410960 + 363 410970 Nb-97 5.02520E-04 3.80300E-02 410970 + 364 410971 Nb-97m 1.16200E-04 3.56750E-02 410971 + 365 410980 Nb-98 5.34240E-04 4.41480E-02 410980 + 366 410981 Nb-98m 1.61220E-03 1.61220E-03 410981 + 367 410990 Nb-99 6.77140E-03 3.18680E-02 410990 + 368 410991 Nb-99m 1.56570E-03 1.59930E-02 410991 + 369 411000 Nb-100 3.07740E-03 3.68350E-02 411000 + 370 411001 Nb-100m 1.29430E-02 1.29430E-02 411001 + 371 411010 Nb-101 2.87150E-02 4.60120E-02 411010 + 372 411020 Nb-102 1.26430E-02 2.13950E-02 411020 + 373 411021 Nb-102m 1.26430E-02 1.26430E-02 411021 + 374 411030 Nb-103 2.18440E-02 2.42470E-02 411030 + 375 411040 Nb-104 5.36600E-03 6.03810E-03 411040 + 376 411041 Nb-104m 5.36600E-03 5.36600E-03 411041 + 377 411050 Nb-105 5.31170E-03 5.37990E-03 411050 + 378 411060 Nb-106 1.28920E-03 1.29610E-03 411060 + 379 411070 Nb-107 3.16960E-04 3.16960E-04 411070 + 380 411080 Nb-108 4.33970E-05 4.33970E-05 411080 + 381 411090 Nb-109 6.92460E-06 6.92460E-06 411090 + 382 420960 Mo-96 1.01500E-06 5.99210E-05 42096.82c + 383 420970 Mo-97 7.04090E-06 3.80370E-02 42097.82c + 384 420980 Mo-98 9.55500E-05 4.58560E-02 42098.82c + 385 420990 Mo-99 5.70320E-04 4.81110E-02 42099.82c + 386 421000 Mo-100 3.35650E-03 5.31340E-02 42100.82c + 387 421010 Mo-101 9.05820E-03 5.50700E-02 421010 + 388 421020 Mo-102 2.49370E-02 5.89750E-02 421020 + 389 421030 Mo-103 3.30510E-02 5.73040E-02 421030 + 390 421040 Mo-104 4.41210E-02 5.56100E-02 421040 + 391 421050 Mo-105 3.06690E-02 3.60160E-02 421050 + 392 421060 Mo-106 2.12210E-02 2.24780E-02 421060 + 393 421070 Mo-107 8.27910E-03 8.57970E-03 421070 + 394 421080 Mo-108 3.18580E-03 3.22740E-03 421080 + 395 421090 Mo-109 6.60830E-04 6.66880E-04 421090 + 396 421100 Mo-110 1.23990E-04 1.23990E-04 421100 + 397 421110 Mo-111 7.88560E-06 7.88560E-06 421110 + 398 421120 Mo-112 2.41450E-09 2.41450E-09 421120 + 399 430980 Tc-98 1.08090E-09 1.08090E-09 430980 + 400 430990 Tc-99 1.63460E-06 4.81110E-02 43099.82c + 401 430991 Tc-99m 3.77970E-07 4.23670E-02 430991 + 402 431000 Tc-100 1.32790E-05 1.32790E-05 431000 + 403 431010 Tc-101 1.69390E-04 5.52400E-02 431010 + 404 431020 Tc-102 4.59510E-04 5.94350E-02 431020 + 405 431021 Tc-102m 4.59510E-04 4.59510E-04 431021 + 406 431030 Tc-103 4.27940E-03 6.15840E-02 431030 + 407 431040 Tc-104 1.01920E-02 6.58020E-02 431040 + 408 431050 Tc-105 2.42740E-02 6.02900E-02 431050 + 409 431060 Tc-106 2.80990E-02 5.05770E-02 431060 + 410 431070 Tc-107 3.24770E-02 4.10570E-02 431070 + 411 431080 Tc-108 1.96420E-02 2.28730E-02 431080 + 412 431090 Tc-109 1.20440E-02 1.27070E-02 431090 + 413 431100 Tc-110 4.37590E-03 4.50000E-03 431100 + 414 431110 Tc-111 1.41070E-03 1.41850E-03 431110 + 415 431120 Tc-112 2.22380E-04 2.22380E-04 431120 + 416 431130 Tc-113 3.21010E-05 3.21010E-05 431130 + 417 431140 Tc-114 3.23650E-09 3.23650E-09 431140 + 418 441000 Ru-100 1.02140E-06 1.43000E-05 44100.82c + 419 441010 Ru-101 1.00690E-06 5.52410E-02 44101.82c + 420 441020 Ru-102 2.69350E-05 5.99210E-02 44102.82c + 421 441030 Ru-103 4.21540E-05 6.17280E-02 44103.82c + 422 441031 Ru-103m 1.01770E-04 1.01770E-04 441031 + 423 441040 Ru-104 9.52880E-04 6.67550E-02 44104.82c + 424 441050 Ru-105 3.33800E-03 6.36280E-02 44105.82c + 425 441060 Ru-106 1.08470E-02 6.14240E-02 44106.82c + 426 441070 Ru-107 1.82590E-02 5.93160E-02 441070 + 427 441080 Ru-108 2.96900E-02 5.25730E-02 441080 + 428 441090 Ru-109 2.52850E-02 3.79840E-02 441090 + 429 441100 Ru-110 2.19410E-02 2.64390E-02 441100 + 430 441110 Ru-111 1.04890E-02 1.19110E-02 441110 + 431 441120 Ru-112 4.75970E-03 4.98100E-03 441120 + 432 441130 Ru-113 5.58850E-04 8.68070E-04 441130 + 433 441131 Ru-113m 5.58850E-04 5.58850E-04 441131 + 434 441140 Ru-114 2.36930E-04 2.36930E-04 441140 + 435 441150 Ru-115 1.75220E-05 1.75220E-05 441150 + 436 441160 Ru-116 2.90730E-06 2.90730E-06 441160 + 437 441170 Ru-117 4.12200E-11 4.12200E-11 441170 + 438 451030 Rh-103 1.32360E-07 6.17290E-02 45103.82c + 439 451031 Rh-103m 8.65850E-07 6.09890E-02 451031 + 440 451040 Rh-104 4.97000E-07 1.99490E-06 451040 + 441 451041 Rh-104m 1.49980E-06 1.49980E-06 451041 + 442 451050 Rh-105 2.43250E-05 6.36560E-02 45105.82c + 443 451051 Rh-105m 3.71860E-06 1.80660E-02 451051 + 444 451060 Rh-106 6.29220E-05 6.14870E-02 451060 + 445 451061 Rh-106m 1.47380E-04 1.47380E-04 451061 + 446 451070 Rh-107 1.08030E-03 6.03960E-02 451070 + 447 451080 Rh-108 7.61680E-04 5.33350E-02 451080 + 448 451081 Rh-108m 2.29850E-03 2.29850E-03 451081 + 449 451090 Rh-109 8.03190E-03 4.60160E-02 451090 + 450 451100 Rh-110 1.12480E-02 3.76870E-02 451100 + 451 451101 Rh-110m 3.00250E-04 3.00250E-04 451101 + 452 451110 Rh-111 1.54590E-02 2.73700E-02 451110 + 453 451120 Rh-112 5.30000E-03 1.02810E-02 451120 + 454 451121 Rh-112m 5.30000E-03 5.30000E-03 451121 + 455 451130 Rh-113 7.15090E-03 8.29840E-03 451130 + 456 451140 Rh-114 1.24340E-03 1.48040E-03 451140 + 457 451141 Rh-114m 1.24340E-03 1.24340E-03 451141 + 458 451150 Rh-115 8.35620E-04 8.53130E-04 451150 + 459 451160 Rh-116 4.75580E-05 5.04340E-05 451160 + 460 451161 Rh-116m 1.11390E-04 1.11390E-04 451161 + 461 451170 Rh-117 4.51640E-05 4.51640E-05 451170 + 462 451180 Rh-118 9.84320E-06 9.84320E-06 451180 + 463 451190 Rh-119 2.96780E-06 2.96780E-06 451190 + 464 461060 Pd-106 1.61660E-08 6.16340E-02 46106.82c + 465 461070 Pd-107 7.26760E-06 6.04170E-02 46107.82c + 466 461071 Pd-107m 1.36580E-05 1.36580E-05 461071 + 467 461080 Pd-108 1.20570E-04 5.57540E-02 46108.82c + 468 461090 Pd-109 1.71770E-04 4.65110E-02 461090 + 469 461091 Pd-109m 3.22820E-04 2.33310E-02 461091 + 470 461100 Pd-110 1.80480E-03 3.97920E-02 46110.82c + 471 461110 Pd-111 1.12730E-03 3.00140E-02 461110 + 472 461111 Pd-111m 2.11850E-03 2.22800E-03 461111 + 473 461120 Pd-112 5.76280E-03 2.13440E-02 461120 + 474 461130 Pd-113 1.51700E-03 1.34780E-02 461130 + 475 461131 Pd-113m 3.66230E-03 3.66230E-03 461131 + 476 461140 Pd-114 4.46230E-03 7.18620E-03 461140 + 477 461150 Pd-115 6.87580E-04 1.53010E-03 461150 + 478 461151 Pd-115m 1.29220E-03 1.41610E-03 461151 + 479 461160 Pd-116 9.15730E-04 1.07760E-03 461160 + 480 461170 Pd-117 6.76680E-05 2.40290E-04 461170 + 481 461171 Pd-117m 1.27170E-04 1.27170E-04 461171 + 482 461180 Pd-118 7.78410E-05 8.73970E-05 461180 + 483 461190 Pd-119 1.28630E-05 1.58310E-05 461190 + 484 461200 Pd-120 2.98540E-06 2.98540E-06 461200 + 485 461210 Pd-121 2.00320E-06 2.00320E-06 461210 + 486 461220 Pd-122 2.90000E-12 2.90000E-12 461220 + 487 461230 Pd-123 7.47260E-08 7.47260E-08 461230 + 488 461240 Pd-124 1.78630E-08 1.78630E-08 461240 + 489 471080 Ag-108 3.95180E-10 4.75710E-10 471080 + 490 471081 Ag-108m 9.25620E-10 9.25620E-10 471081 + 491 471090 Ag-109 3.93540E-07 4.65130E-02 47109.82c + 492 471091 Ag-109m 2.57440E-06 4.64900E-02 471091 + 493 471100 Ag-110 3.26790E-06 3.37200E-06 471100 + 494 471101 Ag-110m 7.65410E-06 7.65410E-06 47510.82c + 495 471110 Ag-111 1.21470E-05 3.05560E-02 47111.82c + 496 471111 Ag-111m 7.94600E-05 3.03100E-02 471111 + 497 471120 Ag-112 2.52430E-04 2.15960E-02 471120 + 498 471130 Ag-113 8.57920E-05 9.27650E-03 471130 + 499 471131 Ag-113m 5.61210E-04 1.34670E-02 471131 + 500 471140 Ag-114 1.56510E-04 8.00090E-03 471140 + 501 471141 Ag-114m 6.58200E-04 6.58200E-04 471141 + 502 471150 Ag-115 1.24460E-04 1.77280E-03 471150 + 503 471151 Ag-115m 8.14120E-04 2.53010E-03 471151 + 504 471160 Ag-116 1.71600E-04 1.27330E-03 471160 + 505 471161 Ag-116m 4.01920E-04 4.01920E-04 471161 + 506 471170 Ag-117 4.95130E-05 1.96300E-04 471170 + 507 471171 Ag-117m 3.23890E-04 4.44030E-04 471171 + 508 471180 Ag-118 2.04140E-05 1.35640E-04 471180 + 509 471181 Ag-118m 8.58560E-05 9.83500E-05 471181 + 510 471190 Ag-119 3.93540E-06 1.18510E-05 471190 + 511 471191 Ag-119m 2.57440E-05 3.36590E-05 471191 + 512 471200 Ag-120 3.29100E-06 7.06930E-06 471200 + 513 471201 Ag-120m 4.66990E-06 6.16260E-06 471201 + 514 471210 Ag-121 2.00320E-06 4.00100E-06 471210 + 515 471220 Ag-122 3.14900E-06 3.14900E-06 471220 + 516 471221 Ag-122m 2.83650E-06 2.83650E-06 471221 + 517 471230 Ag-123 6.03290E-06 6.10760E-06 471230 + 518 471240 Ag-124 3.77820E-06 5.49770E-06 471240 + 519 471241 Ag-124m 3.40330E-06 3.40330E-06 471241 + 520 471250 Ag-125 3.16290E-06 3.16290E-06 471250 + 521 471260 Ag-126 3.65730E-07 3.65730E-07 471260 + 522 471270 Ag-127 4.54900E-08 4.54900E-08 471270 + 523 471280 Ag-128 1.76520E-09 1.76520E-09 471280 + 524 481110 Cd-111 2.30770E-07 3.07080E-02 48111.82c + 525 481111 Cd-111m 7.55010E-07 7.55010E-07 481111 + 526 481120 Cd-112 1.95440E-06 2.15980E-02 48112.82c + 527 481130 Cd-113 3.41570E-06 1.39680E-02 48113.82c + 528 481131 Cd-113m 1.11750E-05 1.71560E-04 481131 + 529 481140 Cd-114 5.18350E-05 8.05270E-03 48114.82c + 530 481150 Cd-115 2.00240E-05 3.63120E-03 481150 + 531 481151 Cd-115m 6.55120E-05 2.25860E-04 48515.82c + 532 481160 Cd-116 1.13170E-04 1.76420E-03 48116.82c + 533 481170 Cd-117 2.18060E-05 4.98880E-04 481170 + 534 481171 Cd-117m 7.13420E-05 2.07960E-04 481171 + 535 481180 Cd-118 7.86770E-05 2.72340E-04 481180 + 536 481190 Cd-119 1.12980E-05 5.08820E-05 481190 + 537 481191 Cd-119m 2.72740E-05 3.32000E-05 481191 + 538 481200 Cd-120 1.79110E-05 2.88630E-05 481200 + 539 481210 Cd-121 3.52040E-06 7.10330E-06 481210 + 540 481211 Cd-121m 8.49860E-06 8.91670E-06 481211 + 541 481220 Cd-122 2.29450E-05 2.89310E-05 481220 + 542 481230 Cd-123 1.14870E-05 1.64870E-05 481230 + 543 481231 Cd-123m 2.77320E-05 2.88450E-05 481231 + 544 481240 Cd-124 1.20110E-04 1.27300E-04 481240 + 545 481250 Cd-125 3.95710E-05 4.11520E-05 481250 + 546 481251 Cd-125m 9.55290E-05 9.71110E-05 481251 + 547 481260 Cd-126 1.13580E-04 1.13950E-04 481260 + 548 481270 Cd-127 5.42770E-05 5.43230E-05 481270 + 549 481280 Cd-128 2.36150E-05 2.36170E-05 481280 + 550 481290 Cd-129 8.98210E-07 8.98210E-07 481290 + 551 481291 Cd-129m 2.16840E-06 2.16840E-06 481291 + 552 481300 Cd-130 4.73750E-08 4.73750E-08 481300 + 553 481310 Cd-131 8.88110E-10 8.88110E-10 481310 + 554 491130 In-113 3.51370E-10 1.71320E-04 49113.82c + 555 491131 In-113m 8.12460E-11 8.12460E-11 491131 + 556 491140 In-114 2.98530E-09 1.16770E-08 491140 + 557 491141 In-114m 4.57570E-09 9.00750E-09 491141 + 558 491142 In-114m 4.43180E-09 4.43180E-09 491142 + 559 491150 In-115 7.90710E-07 3.67640E-03 49115.82c + 560 491151 In-115m 1.82830E-07 3.63140E-03 491151 + 561 491160 In-116 2.41220E-07 2.41220E-07 491160 + 562 491161 In-116m 3.69720E-07 7.27820E-07 491161 + 563 491162 In-116m 3.58090E-07 3.58090E-07 491162 + 564 491170 In-117 3.98590E-06 4.67730E-04 491170 + 565 491171 In-117m 9.21630E-07 4.61270E-04 491171 + 566 491180 In-118 9.79850E-07 2.73320E-04 491180 + 567 491181 In-118m 1.50190E-06 2.93610E-06 491181 + 568 491182 In-118m 1.45460E-06 1.45460E-06 491182 + 569 491190 In-119 5.62380E-06 4.63480E-05 491190 + 570 491191 In-119m 1.30040E-06 4.73080E-05 491191 + 571 491200 In-120 1.65820E-06 3.05210E-05 491200 + 572 491201 In-120m 1.65820E-06 1.65820E-06 491201 + 573 491202 In-120m 1.65820E-06 1.65820E-06 491202 + 574 491210 In-121 4.88070E-06 1.62600E-05 491210 + 575 491211 In-121m 1.12850E-06 5.83940E-06 491211 + 576 491220 In-122 2.47420E-06 3.14050E-05 491220 + 577 491221 In-122m 1.75540E-06 1.75540E-06 491221 + 578 491222 In-122m 1.75540E-06 1.75540E-06 491222 + 579 491230 In-123 2.04140E-05 5.40140E-05 491230 + 580 491231 In-123m 4.72020E-06 1.64520E-05 491231 + 581 491240 In-124 4.80280E-05 1.75330E-04 491240 + 582 491241 In-124m 4.32620E-05 4.32620E-05 491241 + 583 491250 In-125 3.50590E-04 4.67390E-04 491250 + 584 491251 In-125m 8.10640E-05 1.02520E-04 491251 + 585 491260 In-126 3.83280E-04 4.97230E-04 491260 + 586 491261 In-126m 3.45250E-04 3.45250E-04 491261 + 587 491270 In-127 1.00530E-03 1.00530E-03 491270 + 588 491271 In-127m 2.32460E-04 2.86780E-04 491271 + 589 491280 In-128 3.27360E-04 4.84230E-04 491280 + 590 491281 In-128m 1.33250E-04 1.56870E-04 491281 + 591 491282 In-128m 4.14910E-04 4.14910E-04 491282 + 592 491290 In-129 4.69590E-04 4.71760E-04 491290 + 593 491291 In-129m 1.08580E-04 1.09480E-04 491291 + 594 491300 In-130 4.02150E-05 4.02600E-05 491300 + 595 491301 In-130m 4.49170E-05 4.49170E-05 491301 + 596 491302 In-130m 7.64230E-05 7.64230E-05 491302 + 597 491310 In-131 8.78240E-06 8.87270E-06 491310 + 598 491311 In-131m 8.78240E-06 8.78240E-06 491311 + 599 491312 In-131m 8.78240E-06 8.78240E-06 491312 + 600 491320 In-132 3.66250E-07 3.66250E-07 491320 + 601 491330 In-133 1.15530E-08 1.42240E-08 491330 + 602 491331 In-133m 2.67130E-09 2.67130E-09 491331 + 603 501160 Sn-116 6.56690E-10 9.69690E-07 50116.82c + 604 501170 Sn-117 1.97820E-09 7.11760E-04 50117.82c + 605 501171 Sn-117m 6.47210E-09 1.60010E-06 501171 + 606 501180 Sn-118 9.65160E-08 2.76380E-04 50118.82c + 607 501190 Sn-119 7.55790E-08 9.13290E-05 50119.82c + 608 501191 Sn-119m 2.47270E-07 4.21180E-05 501191 + 609 501200 Sn-120 9.95040E-07 3.48340E-05 50120.82c + 610 501210 Sn-121 2.93370E-07 2.24600E-05 501210 + 611 501211 Sn-121m 7.08230E-07 2.55020E-06 501211 + 612 501220 Sn-122 3.98980E-06 3.89150E-05 50122.82c + 613 501230 Sn-123 6.39750E-06 1.05160E-05 50123.82c + 614 501231 Sn-123m 2.65000E-06 6.89980E-05 501231 + 615 501240 Sn-124 4.30530E-05 2.61650E-04 50124.82c + 616 501250 Sn-125 1.31640E-04 2.10590E-04 50125.82c + 617 501251 Sn-125m 5.45290E-05 5.45490E-04 501251 + 618 501260 Sn-126 9.95530E-04 1.84000E-03 50126.82c + 619 501270 Sn-127 1.71220E-03 2.10400E-03 501270 + 620 501271 Sn-127m 7.09230E-04 1.60750E-03 501271 + 621 501280 Sn-128 1.67680E-03 6.50320E-03 501280 + 622 501281 Sn-128m 3.92730E-03 4.34230E-03 501281 + 623 501290 Sn-129 1.67770E-03 2.20880E-03 501290 + 624 501291 Sn-129m 4.05010E-03 4.10040E-03 501291 + 625 501300 Sn-130 1.68600E-03 1.79110E-03 501300 + 626 501301 Sn-130m 3.94900E-03 4.00570E-03 501301 + 627 501310 Sn-131 7.67280E-04 7.84290E-04 501310 + 628 501311 Sn-131m 1.85230E-03 1.86150E-03 501311 + 629 501320 Sn-132 9.58670E-04 9.59050E-04 501320 + 630 501330 Sn-133 6.33640E-05 6.33660E-05 501330 + 631 501340 Sn-134 7.15120E-06 7.15120E-06 501340 + 632 501350 Sn-135 1.28030E-07 1.28030E-07 501350 + 633 501360 Sn-136 2.75560E-09 2.75560E-09 501360 + 634 511180 Sb-118 2.72460E-12 2.72460E-12 511180 + 635 511181 Sb-118m 3.86620E-12 3.86620E-12 511181 + 636 511190 Sb-119 1.60960E-10 2.12130E-10 511190 + 637 511191 Sb-119m 5.11660E-11 5.11660E-11 511191 + 638 511200 Sb-120 7.81910E-10 7.81910E-10 511200 + 639 511201 Sb-120m 1.10950E-09 1.10950E-09 511201 + 640 511210 Sb-121 2.73830E-08 2.30580E-05 51121.82c + 641 511220 Sb-122 1.65280E-07 3.52640E-07 511220 + 642 511221 Sb-122m 1.87360E-07 1.87360E-07 511221 + 643 511230 Sb-123 3.01610E-06 8.25300E-05 51123.82c + 644 511240 Sb-124 7.33040E-07 1.72200E-06 51124.82c + 645 511241 Sb-124m 5.60500E-07 1.31860E-06 511241 + 646 511242 Sb-124m 7.58070E-07 7.58070E-07 511242 + 647 511250 Sb-125 1.15960E-05 7.67680E-04 51125.82c + 648 511260 Sb-126 1.86220E-05 2.30700E-05 51126.82c + 649 511261 Sb-126m 1.37690E-05 3.17750E-05 511261 + 650 511262 Sb-126m 1.80070E-05 1.80070E-05 511262 + 651 511270 Sb-127 4.03770E-04 4.11530E-03 511270 + 652 511280 Sb-128 5.70840E-04 7.10910E-03 511280 + 653 511281 Sb-128m 9.74060E-04 9.74060E-04 511281 + 654 511290 Sb-129 4.05900E-03 8.99750E-03 511290 + 655 511291 Sb-129m 2.48040E-03 4.53050E-03 511291 + 656 511300 Sb-130 5.34450E-03 9.13840E-03 511300 + 657 511301 Sb-130m 5.34450E-03 7.34730E-03 511301 + 658 511310 Sb-131 1.78190E-02 2.04650E-02 511310 + 659 511320 Sb-132 7.60330E-03 8.56230E-03 511320 + 660 511321 Sb-132m 5.60370E-03 5.60370E-03 511321 + 661 511330 Sb-133 8.32450E-03 8.38910E-03 511330 + 662 511340 Sb-134 5.08430E-04 5.14380E-04 511340 + 663 511341 Sb-134m 1.19090E-03 1.19090E-03 511341 + 664 511350 Sb-135 3.68600E-04 3.68700E-04 511350 + 665 511360 Sb-136 4.27100E-05 4.27120E-05 511360 + 666 511370 Sb-137 5.99780E-06 5.99780E-06 511370 + 667 511380 Sb-138 1.39190E-08 1.39190E-08 511380 + 668 521210 Te-121 2.03030E-12 7.92200E-12 521210 + 669 521211 Te-121m 6.64230E-12 6.64230E-12 521211 + 670 521220 Te-122 7.09020E-10 3.44180E-07 52122.82c + 671 521250 Te-125 9.36590E-11 7.67680E-04 52125.82c + 672 521251 Te-125m 3.06420E-10 1.71780E-04 521251 + 673 521260 Te-126 2.09990E-06 5.24970E-05 52126.82c + 674 521270 Te-127 2.44370E-06 4.10720E-03 521270 + 675 521271 Te-127m 5.89940E-06 6.84080E-04 52527.82c + 676 521280 Te-128 9.96230E-05 8.14780E-03 52128.82c + 677 521290 Te-129 1.97870E-04 1.14030E-02 521290 + 678 521291 Te-129m 4.77670E-04 5.73160E-03 52529.82c + 679 521300 Te-130 3.98020E-03 2.04660E-02 52130.82c + 680 521310 Te-131 2.85330E-03 2.34700E-02 521310 + 681 521311 Te-131m 6.88820E-03 8.52670E-03 521311 + 682 521320 Te-132 2.69410E-02 4.11070E-02 52132.82c + 683 521330 Te-133 9.72190E-03 2.10220E-02 521330 + 684 521331 Te-133m 2.34700E-02 2.49210E-02 521331 + 685 521340 Te-134 3.55680E-02 3.73300E-02 521340 + 686 521350 Te-135 1.14840E-02 1.18020E-02 521350 + 687 521360 Te-136 4.47740E-03 4.51600E-03 521360 + 688 521370 Te-137 7.54140E-04 7.57200E-04 521370 + 689 521380 Te-138 1.71200E-04 1.71210E-04 521380 + 690 521390 Te-139 1.39800E-05 1.39800E-05 521390 + 691 521400 Te-140 1.19750E-07 1.19750E-07 521400 + 692 521410 Te-141 1.46450E-09 1.46450E-09 521410 + 693 531270 I-127 2.54140E-10 4.12370E-03 53127.82c + 694 531280 I-128 2.25550E-08 2.25550E-08 531280 + 695 531290 I-129 2.04430E-06 1.35260E-02 53129.82c + 696 531300 I-130 2.70260E-05 3.67180E-05 53130.82c + 697 531301 I-130m 1.15380E-05 1.15380E-05 531301 + 698 531310 I-131 4.41050E-04 3.06470E-02 53131.82c + 699 531320 I-132 1.03990E-03 4.28060E-02 531320 + 700 531321 I-132m 7.66410E-04 7.66410E-04 531321 + 701 531330 I-133 6.02580E-03 5.12900E-02 531330 + 702 531331 I-133m 3.68230E-03 3.68230E-03 531331 + 703 531340 I-134 1.35270E-02 6.05970E-02 531340 + 704 531341 I-134m 9.96940E-03 9.96940E-03 531341 + 705 531350 I-135 4.82380E-02 6.00400E-02 53135.82c + 706 531360 I-136 8.39200E-03 1.29190E-02 531360 + 707 531361 I-136m 1.96560E-02 1.96670E-02 531361 + 708 531370 I-137 1.85950E-02 1.93400E-02 531370 + 709 531380 I-138 4.88680E-03 5.04720E-03 531380 + 710 531390 I-139 2.46930E-03 2.48330E-03 531390 + 711 531400 I-140 3.66720E-04 3.66840E-04 531400 + 712 531410 I-141 5.67800E-05 5.67810E-05 531410 + 713 531420 I-142 9.79310E-07 9.79310E-07 531420 + 714 531430 I-143 1.22810E-08 1.22810E-08 531430 + 715 541300 Xe-130 1.37540E-08 3.85780E-05 54130.82c + 716 541310 Xe-131 5.93560E-07 3.06490E-02 54131.82c + 717 541311 Xe-131m 1.43290E-06 3.34320E-04 541311 + 718 541320 Xe-132 1.50480E-05 4.29450E-02 54132.82c + 719 541321 Xe-132m 1.70570E-05 1.70570E-05 541321 + 720 541330 Xe-133 9.12940E-05 5.16020E-02 54133.82c + 721 541331 Xe-133m 2.20400E-04 1.68030E-03 541331 + 722 541340 Xe-134 7.55810E-04 6.33520E-02 54134.82c + 723 541341 Xe-134m 1.77030E-03 1.99960E-03 541341 + 724 541350 Xe-135 3.28190E-03 7.11380E-02 54135.82c + 725 541351 Xe-135m 7.92310E-03 1.78350E-02 541351 + 726 541360 Xe-136 4.14400E-02 7.52840E-02 54136.82c + 727 541370 Xe-137 4.29200E-02 6.12710E-02 541370 + 728 541380 Xe-138 4.15130E-02 4.65360E-02 541380 + 729 541390 Xe-139 2.01690E-02 2.24430E-02 541390 + 730 541400 Xe-140 1.38100E-02 1.41550E-02 541400 + 731 541410 Xe-141 3.91970E-03 3.96480E-03 541410 + 732 541420 Xe-142 1.31820E-03 1.31890E-03 541420 + 733 541430 Xe-143 1.53050E-04 1.53060E-04 541430 + 734 541440 Xe-144 2.50650E-05 2.50650E-05 541440 + 735 541450 Xe-145 6.23370E-08 6.23370E-08 541450 + 736 541460 Xe-146 1.11090E-09 1.11090E-09 541460 + 737 551320 Cs-132 2.02350E-09 2.02350E-09 551320 + 738 551330 Cs-133 1.80160E-07 5.16020E-02 55133.82c + 739 551340 Cs-134 4.70600E-06 8.17440E-06 55134.82c + 740 551341 Cs-134m 3.46840E-06 3.46840E-06 551341 + 741 551350 Cs-135 8.23790E-05 7.13770E-02 55135.82c + 742 551351 Cs-135m 5.03410E-05 5.03410E-05 551351 + 743 551360 Cs-136 6.30750E-04 8.15580E-04 55136.82c + 744 551361 Cs-136m 3.69650E-04 3.69650E-04 551361 + 745 551370 Cs-137 7.62020E-03 6.88910E-02 55137.82c + 746 551380 Cs-138 6.55030E-03 6.06150E-02 551380 + 747 551381 Cs-138m 9.29470E-03 9.29470E-03 551381 + 748 551390 Cs-139 2.60580E-02 4.85010E-02 551390 + 749 551400 Cs-140 2.24400E-02 3.65960E-02 551400 + 750 551410 Cs-141 2.59530E-02 2.99210E-02 551410 + 751 551420 Cs-142 1.27870E-02 1.41030E-02 551420 + 752 551430 Cs-143 6.67640E-03 6.82870E-03 551430 + 753 551440 Cs-144 8.69800E-04 1.32900E-03 551440 + 754 551441 Cs-144m 8.69800E-04 8.69800E-04 551441 + 755 551450 Cs-145 4.17890E-04 4.17950E-04 551450 + 756 551460 Cs-146 5.22070E-05 5.22080E-05 551460 + 757 551470 Cs-147 2.96200E-06 2.96200E-06 551470 + 758 551480 Cs-148 5.64960E-09 5.64960E-09 551480 + 759 561350 Ba-135 1.08870E-08 3.71700E-08 56135.82c + 760 561351 Ba-135m 2.62830E-08 2.62830E-08 561351 + 761 561360 Ba-136 2.37870E-06 1.00840E-03 56136.82c + 762 561361 Ba-136m 5.57140E-06 5.57140E-06 561361 + 763 561370 Ba-137 3.78190E-05 6.90200E-02 56137.82c + 764 561371 Ba-137m 9.13010E-05 6.51240E-02 561371 + 765 561380 Ba-138 1.55860E-03 6.39400E-02 56138.82c + 766 561390 Ba-139 4.89030E-03 5.33910E-02 561390 + 767 561400 Ba-140 1.40650E-02 5.06610E-02 56140.82c + 768 561410 Ba-141 1.93160E-02 4.92370E-02 561410 + 769 561420 Ba-142 3.46240E-02 4.88390E-02 561420 + 770 561430 Ba-143 2.80750E-02 3.48340E-02 561430 + 771 561440 Ba-144 2.29250E-02 2.47060E-02 561440 + 772 561450 Ba-145 8.63450E-03 9.00010E-03 561450 + 773 561460 Ba-146 3.98610E-03 4.03170E-03 561460 + 774 561470 Ba-147 8.42670E-04 8.44790E-04 561470 + 775 561480 Ba-148 2.01710E-04 2.01710E-04 561480 + 776 561490 Ba-149 2.07850E-05 2.07850E-05 561490 + 777 561500 Ba-150 1.98010E-06 1.98010E-06 561500 + 778 561510 Ba-151 3.28310E-10 3.28310E-10 561510 + 779 571370 La-137 4.28190E-09 4.28190E-09 571370 + 780 571380 La-138 1.01440E-06 1.01440E-06 57138.82c + 781 571390 La-139 5.09620E-05 5.34420E-02 57139.82c + 782 571400 La-140 2.31720E-04 5.08930E-02 57140.82c + 783 571410 La-141 1.10710E-03 5.03440E-02 571410 + 784 571420 La-142 2.61220E-03 5.14510E-02 571420 + 785 571430 La-143 8.82030E-03 4.36540E-02 571430 + 786 571440 La-144 1.41320E-02 3.88380E-02 571440 + 787 571450 La-145 1.87560E-02 2.77560E-02 571450 + 788 571460 La-146 4.30870E-03 8.34040E-03 571460 + 789 571461 La-146m 7.75030E-03 7.75030E-03 571461 + 790 571470 La-147 9.65460E-03 1.05000E-02 571470 + 791 571480 La-148 3.42600E-03 3.62700E-03 571480 + 792 571490 La-149 1.28420E-03 1.30490E-03 571490 + 793 571500 La-150 2.06420E-04 2.08400E-04 571500 + 794 571510 La-151 3.55820E-05 3.55820E-05 571510 + 795 571520 La-152 2.96150E-06 2.96150E-06 571520 + 796 571530 La-153 2.02970E-09 2.02970E-09 571530 + 797 581400 Ce-140 1.99320E-06 5.08950E-02 58140.82c + 798 581410 Ce-141 1.99390E-05 5.03640E-02 58141.82c + 799 581420 Ce-142 1.41270E-04 5.15920E-02 58142.82c + 800 581430 Ce-143 5.78700E-04 4.42330E-02 58143.82c + 801 581440 Ce-144 2.65540E-03 4.14940E-02 58144.82c + 802 581450 Ce-145 6.26110E-03 3.40170E-02 581450 + 803 581460 Ce-146 1.35030E-02 2.95940E-02 581460 + 804 581470 Ce-147 1.51320E-02 2.56320E-02 581470 + 805 581480 Ce-148 1.65180E-02 2.01630E-02 581480 + 806 581490 Ce-149 9.21850E-03 1.05110E-02 581490 + 807 581500 Ce-150 5.46240E-03 5.66520E-03 581500 + 808 581510 Ce-151 1.49480E-03 1.53060E-03 581510 + 809 581520 Ce-152 4.27130E-04 4.29910E-04 581520 + 810 581530 Ce-153 4.16040E-05 4.16060E-05 581530 + 811 581540 Ce-154 8.01440E-06 8.01440E-06 581540 + 812 581550 Ce-155 6.31440E-09 6.31440E-09 581550 + 813 581560 Ce-156 8.99170E-11 8.99170E-11 581560 + 814 591420 Pr-142 7.24000E-10 2.41980E-09 59142.82c + 815 591421 Pr-142m 1.69580E-09 1.69580E-09 591421 + 816 591430 Pr-143 9.95200E-07 4.42340E-02 59143.82c + 817 591440 Pr-144 1.01500E-06 4.15030E-02 591440 + 818 591441 Pr-144m 9.01500E-06 5.81600E-04 591441 + 819 591450 Pr-145 8.24110E-05 3.41000E-02 591450 + 820 591460 Pr-146 4.10980E-04 3.00050E-02 591460 + 821 591470 Pr-147 1.52170E-03 2.71540E-02 591470 + 822 591480 Pr-148 6.13720E-04 2.07770E-02 591480 + 823 591481 Pr-148m 2.58110E-03 2.58110E-03 591481 + 824 591490 Pr-149 6.05990E-03 1.65710E-02 591490 + 825 591500 Pr-150 6.16020E-03 1.18250E-02 591500 + 826 591510 Pr-151 5.75040E-03 7.28100E-03 591510 + 827 591520 Pr-152 2.64360E-03 3.07380E-03 591520 + 828 591530 Pr-153 1.29880E-03 1.34020E-03 591530 + 829 591540 Pr-154 2.68730E-04 2.76690E-04 591540 + 830 591550 Pr-155 6.15540E-05 6.15600E-05 591550 + 831 591560 Pr-156 1.00920E-05 1.00920E-05 591560 + 832 591570 Pr-157 1.99240E-08 1.99240E-08 591570 + 833 591580 Pr-158 2.78940E-10 2.78940E-10 591580 + 834 601450 Nd-145 1.68210E-08 3.41000E-02 60145.82c + 835 601460 Nd-146 1.18310E-05 3.00170E-02 60146.82c + 836 601470 Nd-147 6.22670E-05 2.72160E-02 60147.82c + 837 601480 Nd-148 2.99590E-04 2.36580E-02 60148.82c + 838 601490 Nd-149 9.71380E-04 1.75420E-02 601490 + 839 601500 Nd-150 2.59510E-03 1.44200E-02 60150.82c + 840 601510 Nd-151 3.87880E-03 1.11600E-02 601510 + 841 601520 Nd-152 5.49040E-03 8.56420E-03 601520 + 842 601530 Nd-153 4.07390E-03 5.41410E-03 601530 + 843 601540 Nd-154 2.77480E-03 3.05150E-03 601540 + 844 601550 Nd-155 1.03390E-03 1.09570E-03 601550 + 845 601560 Nd-156 3.52580E-04 3.62400E-04 601560 + 846 601570 Nd-157 7.50230E-05 7.50420E-05 601570 + 847 601580 Nd-158 1.33770E-05 1.33770E-05 601580 + 848 601590 Nd-159 3.92130E-08 3.92130E-08 601590 + 849 601600 Nd-160 1.08140E-09 1.08140E-09 601600 + 850 601610 Nd-161 7.44510E-12 7.44510E-12 601610 + 851 611470 Pm-147 1.66480E-09 2.72160E-02 61147.82c + 852 611480 Pm-148 1.87630E-08 2.09610E-08 61148.82c + 853 611481 Pm-148m 4.39490E-08 4.39490E-08 61548.82c + 854 611490 Pm-149 3.96040E-06 1.75460E-02 61149.82c + 855 611500 Pm-150 4.55750E-05 4.55750E-05 611500 + 856 611510 Pm-151 1.81370E-04 1.13410E-02 61151.82c + 857 611520 Pm-152 9.02740E-05 8.65440E-03 611520 + 858 611521 Pm-152m 1.80270E-04 1.80270E-04 611521 + 859 611522 Pm-152m 1.99390E-04 1.99390E-04 611522 + 860 611530 Pm-153 1.09200E-03 6.50610E-03 611530 + 861 611540 Pm-154 7.03350E-04 3.75480E-03 611540 + 862 611541 Pm-154m 7.03350E-04 7.03350E-04 611541 + 863 611550 Pm-155 1.59270E-03 2.68840E-03 611550 + 864 611560 Pm-156 1.00290E-03 1.36530E-03 611560 + 865 611570 Pm-157 5.69570E-04 6.44610E-04 611570 + 866 611580 Pm-158 1.64510E-04 1.77890E-04 611580 + 867 611590 Pm-159 5.54050E-05 5.54440E-05 611590 + 868 611600 Pm-160 8.84800E-06 8.84910E-06 611600 + 869 611610 Pm-161 6.74520E-08 6.74590E-08 611610 + 870 611620 Pm-162 1.91420E-09 1.91420E-09 611620 + 871 611630 Pm-163 3.26530E-11 3.26530E-11 611630 + 872 621500 Sm-150 9.20570E-09 4.55840E-05 62150.82c + 873 621510 Sm-151 2.96720E-06 1.13440E-02 62151.82c + 874 621520 Sm-152 3.16280E-05 9.06570E-03 62152.82c + 875 621530 Sm-153 3.08830E-05 6.61150E-03 62153.82c + 876 621531 Sm-153m 7.45570E-05 7.45570E-05 621531 + 877 621540 Sm-154 3.68630E-04 4.82680E-03 62154.82c + 878 621550 Sm-155 6.50280E-04 3.33870E-03 621550 + 879 621560 Sm-156 1.01320E-03 2.37850E-03 621560 + 880 621570 Sm-157 9.67260E-04 1.61190E-03 621570 + 881 621580 Sm-158 8.24370E-04 1.00230E-03 621580 + 882 621590 Sm-159 3.85820E-04 4.41280E-04 621590 + 883 621600 Sm-160 1.48950E-04 1.57770E-04 621600 + 884 621610 Sm-161 3.70020E-05 3.70700E-05 621610 + 885 621620 Sm-162 8.88960E-06 8.89150E-06 621620 + 886 621630 Sm-163 1.02030E-07 1.02060E-07 621630 + 887 621640 Sm-164 4.83930E-09 4.83930E-09 621640 + 888 621650 Sm-165 6.64040E-11 6.64040E-11 621650 + 889 631520 Eu-152 1.82870E-10 3.86830E-10 63152.82c + 890 631521 Eu-152m 4.35550E-11 4.35550E-11 631521 + 891 631522 Eu-152m 2.03960E-10 2.03960E-10 631522 + 892 631530 Eu-153 2.23260E-08 6.61160E-03 63153.82c + 893 631540 Eu-154 1.05390E-06 2.00330E-06 63154.82c + 894 631541 Eu-154m 9.49360E-07 9.49360E-07 631541 + 895 631550 Eu-155 9.07860E-06 3.34780E-03 63155.82c + 896 631560 Eu-156 4.11330E-05 2.41960E-03 63156.82c + 897 631570 Eu-157 1.15470E-04 1.72730E-03 63157.82c + 898 631580 Eu-158 1.64790E-04 1.16710E-03 631580 + 899 631590 Eu-159 2.19210E-04 6.60490E-04 631590 + 900 631600 Eu-160 1.89990E-04 3.47760E-04 631600 + 901 631610 Eu-161 1.26780E-04 1.63850E-04 631610 + 902 631620 Eu-162 6.20990E-05 7.09910E-05 631620 + 903 631630 Eu-163 1.41350E-05 1.42370E-05 631630 + 904 631640 Eu-164 3.76100E-06 3.76580E-06 631640 + 905 631650 Eu-165 1.19090E-07 1.19160E-07 631650 + 906 631660 Eu-166 4.18770E-09 4.18770E-09 631660 + 907 631670 Eu-167 3.31750E-11 3.31750E-11 631670 + 908 641550 Gd-155 2.95800E-07 3.34880E-03 64155.82c + 909 641551 Gd-155m 7.14100E-07 7.14100E-07 641551 + 910 641560 Gd-156 2.01820E-06 2.42170E-03 64156.82c + 911 641570 Gd-157 3.94940E-06 1.73130E-03 64157.82c + 912 641580 Gd-158 2.19000E-05 1.18900E-03 64158.82c + 913 641590 Gd-159 4.59080E-05 7.06400E-04 641590 + 914 641600 Gd-160 9.73240E-05 4.45090E-04 64160.82c + 915 641610 Gd-161 8.68180E-05 2.50670E-04 641610 + 916 641620 Gd-162 1.32880E-04 2.03870E-04 641620 + 917 641630 Gd-163 7.44360E-05 8.86730E-05 641630 + 918 641640 Gd-164 3.94940E-05 4.32600E-05 641640 + 919 641650 Gd-165 1.06160E-05 1.07350E-05 641650 + 920 641660 Gd-166 1.94110E-06 1.94530E-06 641660 + 921 641670 Gd-167 2.67970E-08 2.68300E-08 641670 + 922 641680 Gd-168 5.60580E-09 5.60580E-09 641680 + 923 641690 Gd-169 7.25670E-11 7.25670E-11 641690 + 924 651570 Tb-157 1.05140E-10 1.05140E-10 651570 + 925 651580 Tb-158 2.73270E-09 3.03850E-09 651580 + 926 651581 Tb-158m 3.07690E-10 3.07690E-10 651581 + 927 651590 Tb-159 9.05570E-07 7.07300E-04 65159.82c + 928 651600 Tb-160 8.83870E-07 8.83870E-07 65160.82c + 929 651610 Tb-161 5.97680E-06 2.56640E-04 651610 + 930 651620 Tb-162 6.21010E-06 2.10080E-04 651620 + 931 651630 Tb-163 1.79000E-05 1.06570E-04 651630 + 932 651640 Tb-164 1.78630E-05 6.11230E-05 651640 + 933 651650 Tb-165 2.02660E-05 3.10010E-05 651650 + 934 651660 Tb-166 1.16470E-05 1.35920E-05 651660 + 935 651670 Tb-167 9.33380E-07 9.60210E-07 651670 + 936 651680 Tb-168 4.18430E-07 4.24040E-07 651680 + 937 651690 Tb-169 3.34930E-08 3.35660E-08 651690 + 938 651700 Tb-170 1.07770E-08 1.07770E-08 651700 + 939 651710 Tb-171 4.27280E-10 4.27280E-10 651710 + 940 661600 Dy-160 2.82840E-10 8.84150E-07 66160.82c + 941 661610 Dy-161 4.50430E-09 2.56650E-04 66161.82c + 942 661620 Dy-162 9.84230E-08 2.10180E-04 66162.82c + 943 661630 Dy-163 4.66870E-07 1.07040E-04 66163.82c + 944 661640 Dy-164 5.64090E-06 6.67660E-05 66164.82c + 945 661650 Dy-165 2.51120E-06 3.38880E-05 661650 + 946 661651 Dy-165m 3.83890E-07 3.83890E-07 661651 + 947 661660 Dy-166 6.79340E-06 2.03860E-05 661660 + 948 661670 Dy-167 2.80230E-06 3.76250E-06 661670 + 949 661680 Dy-168 3.61100E-06 4.03500E-06 661680 + 950 661690 Dy-169 1.27720E-06 1.31080E-06 661690 + 951 661700 Dy-170 1.03510E-06 1.04590E-06 661700 + 952 661710 Dy-171 9.03700E-08 9.07970E-08 661710 + 953 661720 Dy-172 1.70360E-08 1.70360E-08 661720 + 954 661730 Dy-173 8.96710E-10 8.96710E-10 661730 + 955 671620 Ho-162 2.99860E-12 7.35310E-12 671620 + 956 671621 Ho-162m 7.02340E-12 7.02340E-12 671621 + 957 671630 Ho-163 3.03060E-10 3.49390E-10 671630 + 958 671631 Ho-163m 4.63290E-11 4.63290E-11 671631 + 959 671640 Ho-164 1.39940E-09 4.67700E-09 671640 + 960 671641 Ho-164m 3.27760E-09 3.27760E-09 671641 + 961 671650 Ho-165 9.65050E-07 3.48610E-05 67165.82c + 962 671660 Ho-166 6.24010E-08 2.04480E-05 671660 + 963 671661 Ho-166m 1.46160E-07 1.46160E-07 671661 + 964 671670 Ho-167 2.02470E-07 3.96500E-06 671670 + 965 671680 Ho-168 3.73190E-07 4.93510E-06 671680 + 966 671681 Ho-168m 5.29540E-07 5.29540E-07 671681 + 967 671690 Ho-169 6.40840E-07 1.95160E-06 671690 + 968 671700 Ho-170 1.47270E-06 1.47270E-06 671700 + 969 671701 Ho-170m 6.28740E-07 1.67460E-06 671701 + 970 671710 Ho-171 9.43640E-07 1.03440E-06 671710 + 971 671720 Ho-172 3.57050E-07 3.74090E-07 671720 + 972 671730 Ho-173 1.10470E-07 1.11370E-07 671730 + 973 671740 Ho-174 7.95420E-09 7.95420E-09 671740 + 974 671750 Ho-175 1.20670E-09 1.20670E-09 671750 + 975 681650 Er-165 1.71040E-11 1.71040E-11 681650 + 976 681660 Er-166 4.55010E-10 2.04480E-05 68166.82c + 977 681670 Er-167 8.77370E-10 3.96600E-06 68167.82c + 978 681671 Er-167m 1.34120E-10 4.73920E-07 681671 + 979 681680 Er-168 2.53200E-08 4.96310E-06 68168.82c + 980 681690 Er-169 3.95640E-08 1.99120E-06 681690 + 981 681700 Er-170 6.83790E-07 3.83110E-06 68170.82c + 982 681710 Er-171 1.60360E-06 2.63800E-06 681710 + 983 681720 Er-172 1.02520E-06 1.39930E-06 681720 + 984 681730 Er-173 5.78230E-07 6.89600E-07 681730 + 985 681740 Er-174 2.21360E-07 2.29310E-07 681740 + 986 681750 Er-175 6.97320E-08 7.09390E-08 681750 + 987 681760 Er-176 1.60400E-08 1.60400E-08 681760 + 988 681770 Er-177 1.30780E-09 1.30780E-09 681770 + 989 691680 Tm-168 1.14020E-11 1.14020E-11 691680 + 990 691690 Tm-169 1.14220E-10 1.99130E-06 691690 + 991 691700 Tm-170 4.42430E-09 4.42430E-09 691700 + 992 691710 Tm-171 2.10070E-08 2.65900E-06 691710 + 993 691720 Tm-172 7.69830E-08 1.47630E-06 691720 + 994 691730 Tm-173 2.21620E-07 9.11220E-07 691730 + 995 691740 Tm-174 3.88510E-07 6.17820E-07 691740 + 996 691750 Tm-175 2.33790E-07 3.04730E-07 691750 + 997 691760 Tm-176 1.00800E-07 1.16840E-07 691760 + 998 691770 Tm-177 4.52490E-08 4.65570E-08 691770 + 999 691780 Tm-178 7.10980E-09 7.10980E-09 691780 + 1000 691790 Tm-179 1.36280E-09 1.36280E-09 691790 + 1001 701700 Yb-170 2.39820E-12 4.42090E-09 701700 + 1002 701710 Yb-171 3.65780E-12 2.65910E-06 701710 + 1003 701711 Yb-171m 2.39270E-11 2.39270E-11 701711 + 1004 701720 Yb-172 6.34760E-10 1.47690E-06 701720 + 1005 701730 Yb-173 3.99800E-09 9.15220E-07 701730 + 1006 701740 Yb-174 1.54180E-08 6.33270E-07 701740 + 1007 701750 Yb-175 3.97170E-08 3.50520E-07 701750 + 1008 701751 Yb-175m 6.07160E-09 2.40710E-07 701751 + 1009 701760 Yb-176 3.50800E-08 2.02870E-07 701760 + 1010 701761 Yb-176m 6.31000E-08 1.21520E-07 701761 + 1011 701770 Yb-177 6.35200E-08 1.24760E-07 701770 + 1012 701771 Yb-177m 1.46870E-08 6.12440E-08 701771 + 1013 701780 Yb-178 6.14500E-08 6.85600E-08 701780 + 1014 701790 Yb-179 2.28220E-08 2.41850E-08 701790 + 1015 701800 Yb-180 8.65300E-09 8.65300E-09 701800 + 1016 701810 Yb-181 1.11550E-09 1.11550E-09 701810 + 1017 711730 Lu-173 2.97160E-12 2.97160E-12 711730 + 1018 711740 Lu-174 8.01110E-12 2.66660E-11 711740 + 1019 711741 Lu-174m 1.87640E-11 1.87640E-11 711741 + 1020 711750 Lu-175 4.88990E-10 3.51010E-07 71175.82c + 1021 711760 Lu-176 1.43320E-09 1.35850E-08 71176.82c + 1022 711761 Lu-176m 7.96780E-10 7.96780E-10 711761 + 1023 711770 Lu-177 6.90810E-09 1.32290E-07 711770 + 1024 711771 Lu-177m 2.70060E-09 2.74420E-09 711771 + 1025 711772 Lu-177m 8.72730E-11 8.72730E-11 711772 + 1026 711780 Lu-178 6.64520E-09 7.52050E-08 711780 + 1027 711781 Lu-178m 7.53280E-09 7.53280E-09 711781 + 1028 711790 Lu-179 2.23410E-08 4.99410E-08 711790 + 1029 711791 Lu-179m 3.41530E-09 2.76000E-08 711791 + 1030 711800 Lu-180 5.02760E-09 1.55730E-08 711800 + 1031 711801 Lu-180m 5.02760E-09 1.36810E-08 711801 + 1032 711802 Lu-180m 7.40960E-09 7.40960E-09 711802 + 1033 711810 Lu-181 1.15750E-08 1.26910E-08 711810 + 1034 711820 Lu-182 2.96680E-09 2.96680E-09 711820 + 1035 711830 Lu-183 9.18800E-10 9.18800E-10 711830 + 1036 711840 Lu-184 9.48220E-11 9.48220E-11 711840 + 1037 721760 Hf-176 4.83500E-12 8.00860E-10 72176.82c + 1038 721770 Hf-177 3.42680E-11 1.34510E-07 72177.82c + 1039 721771 Hf-177m 1.33150E-11 2.18150E-09 721771 + 1040 721772 Hf-177m 5.14690E-13 4.41510E-11 721772 + 1041 721780 Hf-178 1.50840E-10 8.31600E-08 72178.82c + 1042 721781 Hf-178m 2.48870E-10 7.80410E-09 721781 + 1043 721782 Hf-178m 2.24590E-11 2.24590E-11 721782 + 1044 721790 Hf-179 9.50470E-10 5.15250E-08 72179.82c + 1045 721791 Hf-179m 2.96710E-10 2.96710E-10 721791 + 1046 721792 Hf-179m 3.32730E-10 3.32730E-10 721792 + 1047 721800 Hf-180 2.01790E-09 3.17560E-08 72180.82c + 1048 721801 Hf-180m 3.62970E-09 7.33450E-09 721801 + 1049 721810 Hf-181 6.78650E-09 1.94770E-08 721810 + 1050 721820 Hf-182 3.02570E-09 8.27830E-09 721820 + 1051 721821 Hf-182m 5.44250E-09 5.44250E-09 721821 + 1052 721830 Hf-183 4.77960E-09 5.69840E-09 721830 + 1053 721840 Hf-184 9.36700E-10 9.84110E-10 721840 + 1054 721841 Hf-184m 1.68490E-09 1.73230E-09 721841 + 1055 721850 Hf-185 5.78410E-10 5.78410E-10 721850 + 1056 721860 Hf-186 1.33410E-10 1.33410E-10 721860 + 1057 721870 Hf-187 1.09000E-11 1.09000E-11 721870 + 1058 731790 Ta-179 3.43540E-12 4.52690E-12 731790 + 1059 731791 Ta-179m 1.05080E-12 1.09160E-12 731791 + 1060 731800 Ta-180 1.70090E-11 1.70090E-11 731800 + 1061 731801 Ta-180m 1.92800E-11 4.20170E-11 731801 + 1062 731810 Ta-181 2.54470E-10 1.97320E-08 73181.82c + 1063 731820 Ta-182 2.25790E-10 3.78850E-09 73182.82c + 1064 731821 Ta-182m 2.30460E-10 3.56280E-09 731821 + 1065 731822 Ta-182m 1.75680E-10 3.33230E-09 731822 + 1066 731830 Ta-183 1.82100E-09 7.51940E-09 731830 + 1067 731840 Ta-184 1.78100E-09 4.49740E-09 731840 + 1068 731850 Ta-185 1.29870E-09 2.50610E-09 731850 + 1069 731851 Ta-185m 6.29010E-10 6.29010E-10 731851 + 1070 731860 Ta-186 8.33140E-10 9.66550E-10 731860 + 1071 731870 Ta-187 3.74610E-10 3.85510E-10 731870 + 1072 731880 Ta-188 5.90000E-11 5.90000E-11 731880 + 1073 731890 Ta-189 1.13410E-11 1.13410E-11 731890 + 1074 741820 W-182 5.17360E-12 3.79370E-09 74182.82c + 1075 741830 W-183 7.63800E-12 7.55200E-09 74183.82c + 1076 741831 W-183m 2.49890E-11 2.80650E-10 741831 + 1077 741840 W-184 1.80370E-10 4.67780E-09 74184.82c + 1078 741850 W-185 1.09910E-10 2.88140E-09 741850 + 1079 741851 W-185m 2.65330E-10 2.65330E-10 741851 + 1080 741860 W-186 6.09970E-10 1.77380E-09 74186.82c + 1081 741861 W-186m 1.96760E-10 1.96760E-10 741861 + 1082 741870 W-187 6.43670E-10 1.02920E-09 741870 + 1083 741880 W-188 5.06810E-10 5.65810E-10 741880 + 1084 741890 W-189 1.88700E-10 2.00040E-10 741890 + 1085 741900 W-190 3.36100E-11 7.17080E-11 741900 + 1086 741901 W-190m 3.80990E-11 3.80990E-11 741901 + 1087 741910 W-191 9.26890E-12 9.26890E-12 741910 + 1088 741920 W-192 1.18780E-12 1.18780E-12 741920 + 1089 751850 Re-185 3.97940E-12 2.88530E-09 75185.82c + 1090 751860 Re-186 7.52470E-12 7.52470E-12 751860 + 1091 751861 Re-186m 1.06770E-11 1.06770E-11 751861 + 1092 751870 Re-187 7.93100E-11 1.10850E-09 75187.82c + 1093 751880 Re-188 3.47790E-11 6.82050E-10 751880 + 1094 751881 Re-188m 8.14610E-11 8.14610E-11 751881 + 1095 751890 Re-189 2.11720E-10 4.11760E-10 751890 + 1096 751900 Re-190 5.13980E-11 1.65260E-10 751900 + 1097 751901 Re-190m 9.24520E-11 9.24520E-11 751901 + 1098 751910 Re-191 9.55700E-11 1.04840E-10 751910 + 1099 751920 Re-192 2.45640E-11 2.57520E-11 751920 + 1100 751930 Re-193 7.62400E-12 7.62400E-12 751930 + 1101 761880 Os-188 3.43760E-12 6.85490E-10 761880 + 1102 761890 Os-189 3.02060E-12 4.24660E-10 761890 + 1103 761891 Os-189m 9.88240E-12 5.22240E-11 761891 + 1104 761900 Os-190 2.16730E-11 2.61800E-10 761900 + 1105 761901 Os-190m 2.45680E-11 7.48620E-11 761901 + 1106 761910 Os-191 4.26670E-11 1.60550E-10 761910 + 1107 761911 Os-191m 1.30410E-11 1.30410E-11 761911 + 1108 761920 Os-192 3.26710E-11 9.11220E-11 761920 + 1109 761921 Os-192m 3.70340E-11 3.70340E-11 761921 + 1110 761930 Os-193 3.94200E-11 4.70440E-11 761930 + 1111 761940 Os-194 2.16600E-11 2.16600E-11 761940 + 1112 761950 Os-195 4.79320E-12 4.79320E-12 761950 + 1113 761960 Os-196 1.10890E-12 1.10890E-12 761960 + 1114 771910 Ir-191 6.07740E-13 1.62620E-10 77191.82c + 1115 771911 Ir-191m 1.15800E-12 7.72450E-11 771911 + 1116 771920 Ir-192 1.72290E-12 9.98290E-12 771920 + 1117 771921 Ir-192m 1.72290E-12 1.72290E-12 771921 + 1118 771922 Ir-192m 1.72290E-12 6.53740E-12 771922 + 1119 771930 Ir-193 4.37300E-12 6.19740E-11 77193.82c + 1120 771931 Ir-193m 1.05570E-11 1.07210E-11 771931 + 1121 771940 Ir-194 4.87620E-12 3.14120E-11 771940 + 1122 771941 Ir-194m 4.87620E-12 4.87620E-12 771941 + 1123 771942 Ir-194m 4.87620E-12 4.87620E-12 771942 + 1124 771950 Ir-195 4.65100E-12 1.00060E-11 771950 + 1125 771951 Ir-195m 1.12280E-11 1.12280E-11 771951 + 1126 771960 Ir-196 3.44080E-12 4.56000E-12 771960 + 1127 771961 Ir-196m 3.44080E-12 3.44080E-12 771961 + 1128 771971 Ir-197m 2.19230E-12 2.19230E-12 771971 + 1129 781940 Pt-194 1.47200E-12 3.77600E-11 781940 + 1130 781950 Pt-195 8.99880E-13 2.37450E-11 781950 + 1131 781951 Pt-195m 2.17240E-12 5.58580E-12 781951 + 1132 781960 Pt-196 6.62450E-12 1.46150E-11 781960 + 1133 781970 Pt-197 1.55120E-12 8.20070E-12 781970 + 1134 781971 Pt-197m 3.74490E-12 5.93170E-12 781971 + 1135 781980 Pt-198 4.17900E-12 4.17900E-12 781980 + 1136 781990 Pt-199 6.32070E-13 1.55990E-12 781990 + 1137 791990 Au-199 1.74010E-12 3.30000E-12 791990 + + Neutron-induced fission: + + Interpolation region : 2 / 2 + Interpolation energy : 4.00000E-01 MeV + Number of products : 1101 / 1172 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 3.82810E-05 3.82810E-05 1001.82c + 2 10020 H-2 1.16990E-05 1.16990E-05 1002.82c + 3 10030 H-3 1.91000E-04 1.91000E-04 1003.82c + 4 20040 He-4 2.42000E-03 2.42000E-03 2004.82c + 5 200500 Ca-50 1.27950E-12 1.27950E-12 200500 + 6 200510 Ca-51 1.18030E-12 1.18030E-12 200510 + 7 200520 Ca-52 1.31410E-12 1.31410E-12 200520 + 8 210510 Sc-51 1.92520E-12 3.13180E-12 210510 + 9 210520 Sc-52 3.52890E-12 4.81670E-12 210520 + 10 210530 Sc-53 6.84660E-12 6.84660E-12 210530 + 11 210540 Sc-54 4.35330E-12 4.35330E-12 210540 + 12 210550 Sc-55 3.82120E-12 3.82120E-12 210550 + 13 220520 Ti-52 1.24640E-12 6.06310E-12 220520 + 14 220530 Ti-53 3.98940E-12 1.08360E-11 220530 + 15 220540 Ti-54 1.54920E-11 1.98450E-11 220540 + 16 220550 Ti-55 2.30710E-11 2.68920E-11 220550 + 17 220560 Ti-56 3.68630E-11 3.68630E-11 220560 + 18 220570 Ti-57 1.81230E-11 1.81230E-11 220570 + 19 220580 Ti-58 1.13070E-11 1.13070E-11 220580 + 20 220590 Ti-59 2.05520E-12 2.05520E-12 220590 + 21 230540 V-54 1.34190E-12 2.11870E-11 230540 + 22 230550 V-55 1.27470E-11 3.96390E-11 230550 + 23 230560 V-56 3.30540E-11 6.99710E-11 230560 + 24 230570 V-57 1.00920E-10 1.18990E-10 230570 + 25 230580 V-58 1.11210E-10 1.22520E-10 230580 + 26 230590 V-59 1.46130E-10 1.48180E-10 230590 + 27 230600 V-60 5.19230E-11 5.19230E-11 230600 + 28 230610 V-61 2.43170E-11 2.43170E-11 230610 + 29 230620 V-62 3.41450E-12 3.41450E-12 230620 + 30 240560 Cr-56 3.66300E-12 7.41100E-11 240560 + 31 240570 Cr-57 1.96440E-11 2.36170E-10 240570 + 32 240580 Cr-58 1.34030E-10 1.58530E-10 240580 + 33 240590 Cr-59 2.86140E-10 4.34320E-10 240590 + 34 240600 Cr-60 6.51560E-10 7.04940E-10 240600 + 35 240610 Cr-61 5.63540E-10 5.86400E-10 240610 + 36 240620 Cr-62 5.95880E-10 5.99290E-10 240620 + 37 240630 Cr-63 1.65510E-10 1.65510E-10 240630 + 38 240640 Cr-64 5.10480E-11 5.10480E-11 240640 + 39 240650 Cr-65 5.41860E-12 5.41860E-12 240650 + 40 250580 Mn-58 3.19450E-12 1.61730E-10 250580 + 41 250590 Mn-59 5.14960E-11 4.85820E-10 250590 + 42 250600 Mn-60 1.77250E-11 7.43400E-10 250600 + 43 250601 Mn-60m 1.80320E-10 1.80320E-10 250601 + 44 250610 Mn-61 1.04520E-09 1.63160E-09 250610 + 45 250620 Mn-62 1.58160E-09 1.88130E-09 250620 + 46 250621 Mn-62m 2.47690E-10 5.47330E-10 250621 + 47 250630 Mn-63 3.39210E-09 3.55760E-09 250630 + 48 250640 Mn-64 2.01920E-09 2.07020E-09 250640 + 49 250650 Mn-65 1.67260E-09 1.67800E-09 250650 + 50 250660 Mn-66 3.68170E-10 3.68170E-10 250660 + 51 250670 Mn-67 8.43090E-11 8.43090E-11 250670 + 52 250680 Mn-68 6.09030E-12 6.09030E-12 250680 + 53 260600 Fe-60 6.38730E-12 9.09380E-10 260600 + 54 260610 Fe-61 6.41080E-11 1.69570E-09 260610 + 55 260620 Fe-62 7.38150E-10 3.16670E-09 260620 + 56 260630 Fe-63 2.24720E-09 5.80480E-09 260630 + 57 260640 Fe-64 8.18730E-09 1.02570E-08 260640 + 58 260650 Fe-65 1.15980E-08 1.32760E-08 260650 + 59 260660 Fe-66 1.78230E-08 1.81910E-08 260660 + 60 260670 Fe-67 8.20170E-09 8.28600E-09 260670 + 61 260680 Fe-68 4.76190E-09 4.76800E-09 260680 + 62 260690 Fe-69 8.22920E-10 8.22920E-10 260690 + 63 260700 Fe-70 1.33030E-10 1.33030E-10 260700 + 64 260710 Fe-71 4.36030E-12 4.36030E-12 260710 + 65 270620 Co-62 1.45670E-12 3.16820E-09 270620 + 66 270621 Co-62m 3.97080E-12 3.97080E-12 270621 + 67 270630 Co-63 1.22780E-10 5.92760E-09 270630 + 68 270640 Co-64 8.13500E-10 1.10710E-08 270640 + 69 270650 Co-65 7.29660E-09 2.05730E-08 270650 + 70 270660 Co-66 1.81750E-08 3.63660E-08 270660 + 71 270670 Co-67 5.22360E-08 6.05220E-08 270670 + 72 270680 Co-68 3.09560E-08 4.49220E-08 270680 + 73 270681 Co-68m 2.31060E-08 2.79320E-08 270681 + 74 270690 Co-69 6.81550E-08 6.89200E-08 270690 + 75 270700 Co-70 1.14640E-08 1.14640E-08 270700 + 76 270701 Co-70m 1.14640E-08 1.15970E-08 270701 + 77 270710 Co-71 6.18380E-09 6.18820E-09 270710 + 78 270720 Co-72 9.84090E-10 9.84090E-10 270720 + 79 270730 Co-73 9.20910E-11 9.20910E-11 270730 + 80 270740 Co-74 1.13670E-11 1.13670E-11 270740 + 81 280640 Ni-64 7.14020E-12 1.10780E-08 28064.82c + 82 280650 Ni-65 1.30810E-10 2.07030E-08 280650 + 83 280660 Ni-66 2.32080E-09 3.86870E-08 280660 + 84 280670 Ni-67 1.16110E-08 7.21330E-08 280670 + 85 280680 Ni-68 7.40730E-08 1.33650E-07 280680 + 86 280690 Ni-69 7.60550E-08 1.44290E-07 280690 + 87 280691 Ni-69m 7.60550E-08 7.60550E-08 280691 + 88 280700 Ni-70 3.30590E-07 3.53650E-07 280700 + 89 280710 Ni-71 5.31750E-07 5.37940E-07 280710 + 90 280720 Ni-72 2.00840E-07 2.01820E-07 280720 + 91 280730 Ni-73 4.02620E-08 4.03540E-08 280730 + 92 280740 Ni-74 4.19270E-08 4.19380E-08 280740 + 93 280750 Ni-75 1.89890E-09 1.89890E-09 280750 + 94 280760 Ni-76 1.70750E-10 1.70750E-10 280760 + 95 280770 Ni-77 6.66850E-12 6.66850E-12 280770 + 96 290660 Cu-66 4.52000E-12 3.86910E-08 290660 + 97 290670 Cu-67 1.78920E-10 7.23120E-08 290670 + 98 290680 Cu-68 6.02420E-10 1.35630E-07 290680 + 99 290681 Cu-68m 1.64210E-09 1.64210E-09 290681 + 100 290690 Cu-69 3.13870E-08 2.51730E-07 290690 + 101 290700 Cu-70 7.74420E-09 6.62300E-08 290700 + 102 290701 Cu-70m 9.89020E-08 1.16970E-07 290701 + 103 290702 Cu-70m 7.74420E-09 3.61400E-07 290702 + 104 290710 Cu-71 3.50710E-07 8.88650E-07 290710 + 105 290720 Cu-72 1.30060E-06 1.50240E-06 290720 + 106 290730 Cu-73 8.70080E-07 9.10430E-07 290730 + 107 290740 Cu-74 3.36290E-06 3.40490E-06 290740 + 108 290750 Cu-75 6.87790E-07 6.89660E-07 290750 + 109 290760 Cu-76 6.78300E-08 6.79150E-08 290760 + 110 290761 Cu-76m 6.78300E-08 6.79150E-08 290761 + 111 290770 Cu-77 4.57850E-08 4.57920E-08 290770 + 112 290780 Cu-78 2.28540E-09 2.28540E-09 290780 + 113 290790 Cu-79 1.69850E-10 1.69850E-10 290790 + 114 290800 Cu-80 5.51720E-12 5.51720E-12 290800 + 115 300680 Zn-68 5.09830E-12 1.35900E-07 300680 + 116 300690 Zn-69 2.57580E-11 2.51880E-07 300690 + 117 300691 Zn-69m 1.27930E-10 1.27930E-10 300691 + 118 300700 Zn-70 4.28880E-09 4.72330E-07 300700 + 119 300710 Zn-71 4.15200E-09 8.92800E-07 300710 + 120 300711 Zn-71m 2.06210E-08 2.06210E-08 300711 + 121 300720 Zn-72 3.24930E-07 1.82730E-06 300720 + 122 300730 Zn-73 7.63050E-08 1.43640E-06 300730 + 123 300731 Zn-73m 1.05540E-07 4.49700E-07 300731 + 124 300732 Zn-73m 6.88310E-07 6.88310E-07 300732 + 125 300740 Zn-74 7.56600E-06 1.09950E-05 300740 + 126 300750 Zn-75 7.78010E-06 8.44770E-06 300750 + 127 300760 Zn-76 6.40810E-06 6.54190E-06 300760 + 128 300770 Zn-77 5.78760E-06 6.21870E-06 300770 + 129 300771 Zn-77m 7.70590E-07 7.70590E-07 300771 + 130 300780 Zn-78 3.81120E-06 3.81360E-06 300780 + 131 300790 Zn-79 1.93380E-06 1.93390E-06 300790 + 132 300800 Zn-80 4.90760E-08 4.90820E-08 300800 + 133 300810 Zn-81 2.19760E-09 2.19760E-09 300810 + 134 300820 Zn-82 8.09750E-11 8.09750E-11 300820 + 135 310700 Ga-70 2.12310E-12 2.12310E-12 310700 + 136 310710 Ga-71 1.01400E-10 9.13520E-07 310710 + 137 310720 Ga-72 2.53880E-09 1.83010E-06 310720 + 138 310721 Ga-72m 2.49560E-10 6.11380E-08 310721 + 139 310730 Ga-73 4.53670E-08 1.82600E-06 310730 + 140 310740 Ga-74 5.08650E-07 9.13640E-06 310740 + 141 310741 Ga-74m 5.08650E-07 1.15040E-05 310741 + 142 310750 Ga-75 1.72890E-06 1.01770E-05 310750 + 143 310760 Ga-76 9.15310E-06 1.56950E-05 310760 + 144 310770 Ga-77 3.09150E-05 3.75190E-05 310770 + 145 310780 Ga-78 2.28710E-05 2.67100E-05 310780 + 146 310790 Ga-79 2.32120E-05 2.51210E-05 310790 + 147 310800 Ga-80 1.18530E-05 1.19020E-05 310800 + 148 310810 Ga-81 7.11900E-06 7.12100E-06 310810 + 149 310820 Ga-82 3.07150E-07 3.07230E-07 310820 + 150 310830 Ga-83 3.77450E-08 3.77450E-08 310830 + 151 310840 Ga-84 1.13960E-09 1.13960E-09 310840 + 152 320720 Ge-72 1.57600E-12 1.83010E-06 32072.82c + 153 320730 Ge-73 4.79680E-11 1.82600E-06 32073.82c + 154 320731 Ge-73m 9.65810E-12 1.79920E-06 320731 + 155 320740 Ge-74 1.04540E-08 1.20230E-05 32074.82c + 156 320750 Ge-75 1.01570E-07 1.10410E-05 320750 + 157 320751 Ge-75m 7.62830E-07 1.16990E-06 320751 + 158 320760 Ge-76 2.74580E-06 1.84410E-05 32076.82c + 159 320770 Ge-77 1.15710E-05 1.89920E-05 320770 + 160 320771 Ge-77m 1.54050E-06 3.90600E-05 320771 + 161 320780 Ge-78 4.28570E-05 6.95890E-05 320780 + 162 320790 Ge-79 1.30610E-05 4.20480E-05 320790 + 163 320791 Ge-79m 9.80990E-05 9.81360E-05 320791 + 164 320800 Ge-80 1.67960E-04 1.80710E-04 320800 + 165 320810 Ge-81 1.36520E-04 1.40170E-04 320810 + 166 320811 Ge-81m 2.74880E-05 3.04810E-05 320811 + 167 320820 Ge-82 1.20250E-04 1.20510E-04 320820 + 168 320830 Ge-83 3.88570E-05 3.88820E-05 320830 + 169 320840 Ge-84 1.04760E-05 1.04760E-05 320840 + 170 320850 Ge-85 1.10710E-06 1.10710E-06 320850 + 171 320860 Ge-86 1.78050E-08 1.78050E-08 320860 + 172 320870 Ge-87 3.22650E-10 3.22650E-10 320870 + 173 330740 As-74 1.32170E-12 1.32170E-12 330740 + 174 330750 As-75 1.78110E-11 1.10410E-05 33075.82c + 175 330751 As-75m 6.74500E-11 4.18420E-10 330751 + 176 330760 As-76 2.97100E-09 2.97100E-09 330760 + 177 330770 As-77 1.73200E-07 5.08030E-05 330770 + 178 330780 As-78 2.85780E-06 7.24470E-05 330780 + 179 330790 As-79 7.73350E-06 1.43990E-04 330790 + 180 330800 As-80 4.24360E-05 2.23150E-04 330800 + 181 330810 As-81 1.83860E-04 3.54210E-04 330810 + 182 330820 As-82 5.26170E-05 1.73120E-04 330820 + 183 330821 As-82m 1.83330E-04 1.83330E-04 330821 + 184 330830 As-83 4.56070E-04 4.96080E-04 330830 + 185 330840 As-84 1.07940E-04 1.12690E-04 330840 + 186 330841 As-84m 1.07940E-04 1.12690E-04 330841 + 187 330850 As-85 1.18760E-04 1.19710E-04 330850 + 188 330860 As-86 2.47990E-05 2.48170E-05 330860 + 189 330870 As-87 9.87800E-06 9.87830E-06 330870 + 190 330880 As-88 1.26650E-07 1.26650E-07 330880 + 191 330890 As-89 5.56330E-09 5.56330E-09 330890 + 192 340770 Se-77 6.42550E-12 5.08030E-05 34077.82c + 193 340771 Se-77m 4.82590E-11 4.82590E-11 340771 + 194 340780 Se-78 4.02280E-09 7.24510E-05 34078.82c + 195 340790 Se-79 1.01700E-07 1.44030E-04 34079.82c + 196 340791 Se-79m 1.35410E-08 1.40600E-04 340791 + 197 340800 Se-80 5.92360E-06 2.29070E-04 34080.82c + 198 340810 Se-81 5.60910E-06 4.01920E-04 340810 + 199 340811 Se-81m 4.21280E-05 5.48430E-05 340811 + 200 340820 Se-82 1.92900E-04 5.49360E-04 34082.82c + 201 340830 Se-83 4.26330E-04 6.05080E-04 340830 + 202 340831 Se-83m 8.58400E-05 4.03490E-04 340831 + 203 340840 Se-84 1.31990E-03 1.57130E-03 340840 + 204 340850 Se-85 1.32380E-03 1.42540E-03 340850 + 205 340860 Se-86 1.24020E-03 1.25840E-03 340860 + 206 340870 Se-87 6.04250E-04 6.12610E-04 340870 + 207 340880 Se-88 2.55940E-04 2.56070E-04 340880 + 208 340890 Se-89 4.61100E-05 4.61160E-05 340890 + 209 340900 Se-90 6.83200E-06 6.83200E-06 340900 + 210 340910 Se-91 4.03870E-08 4.03870E-08 340910 + 211 340920 Se-92 1.08250E-09 1.08250E-09 340920 + 212 350790 Br-79 6.08280E-12 7.87620E-08 35079.82c + 213 350791 Br-79m 2.30350E-11 2.30350E-11 350791 + 214 350800 Br-80 3.66630E-10 1.64410E-09 350800 + 215 350801 Br-80m 1.27750E-09 1.27750E-09 350801 + 216 350810 Br-81 1.07700E-07 4.02050E-04 35081.82c + 217 350820 Br-82 1.51330E-06 2.05520E-06 350820 + 218 350821 Br-82m 5.55190E-07 5.55190E-07 350821 + 219 350830 Br-83 2.82980E-05 1.03690E-03 350830 + 220 350840 Br-84 6.43850E-05 1.63570E-03 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4.36390E-04 2.93380E-03 36086.82c + 241 360870 Kr-87 1.39670E-03 4.08530E-03 360870 + 242 360880 Kr-88 3.54760E-03 5.65270E-03 360880 + 243 360890 Kr-89 5.18690E-03 6.40370E-03 360890 + 244 360900 Kr-90 5.81410E-03 6.17410E-03 360900 + 245 360910 Kr-91 4.16420E-03 4.29070E-03 360910 + 246 360920 Kr-92 2.35530E-03 2.36910E-03 360920 + 247 360930 Kr-93 6.63200E-04 6.64440E-04 360930 + 248 360940 Kr-94 1.89640E-04 1.89640E-04 360940 + 249 360950 Kr-95 2.37700E-05 2.37700E-05 360950 + 250 360960 Kr-96 3.71690E-06 3.71690E-06 360960 + 251 360970 Kr-97 1.81620E-09 1.81620E-09 360970 + 252 370840 Rb-84 1.05100E-10 3.25590E-10 370840 + 253 370841 Rb-84m 2.20490E-10 2.20490E-10 370841 + 254 370850 Rb-85 2.51550E-08 2.04040E-03 37085.82c + 255 370860 Rb-86 3.47750E-07 1.07730E-06 37086.82c + 256 370861 Rb-86m 7.29550E-07 7.29550E-07 370861 + 257 370870 Rb-87 5.37040E-05 4.13900E-03 37087.82c + 258 370880 Rb-88 1.87120E-04 5.83980E-03 370880 + 259 370890 Rb-89 9.42060E-04 7.34580E-03 370890 + 260 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1.11590E-02 380910 + 280 380920 Sr-92 5.66400E-03 1.45970E-02 380920 + 281 380930 Sr-93 9.79580E-03 1.72830E-02 380930 + 282 380940 Sr-94 1.64090E-02 1.99590E-02 380940 + 283 380950 Sr-95 1.42030E-02 1.57850E-02 380950 + 284 380960 Sr-96 1.16500E-02 1.20300E-02 380960 + 285 380970 Sr-97 4.68990E-03 4.75470E-03 380970 + 286 380980 Sr-98 1.81790E-03 1.82560E-03 380980 + 287 380990 Sr-99 3.22120E-04 3.22140E-04 380990 + 288 381000 Sr-100 6.27660E-05 6.27660E-05 381000 + 289 381010 Sr-101 3.72120E-06 3.72120E-06 381010 + 290 381020 Sr-102 3.96820E-09 3.96820E-09 381020 + 291 390890 Y-89 4.23810E-10 7.41060E-03 39089.82c + 292 390891 Y-89m 2.10490E-09 7.16410E-07 390891 + 293 390900 Y-90 1.09520E-06 9.09260E-03 39090.82c + 294 390901 Y-90m 1.83150E-06 1.83150E-06 390901 + 295 390910 Y-91 3.91040E-06 1.11820E-02 39091.82c + 296 390911 Y-91m 1.94220E-05 6.58480E-03 390911 + 297 390920 Y-92 1.48400E-04 1.47450E-02 390920 + 298 390930 Y-93 1.10740E-04 1.82260E-02 390930 + 299 390931 Y-93m 8.31720E-04 5.15670E-03 390931 + 300 390940 Y-94 2.68360E-03 2.26420E-02 390940 + 301 390950 Y-95 8.17550E-03 2.39610E-02 390950 + 302 390960 Y-96 3.91430E-03 1.59460E-02 390960 + 303 390961 Y-96m 8.21170E-03 8.21290E-03 390961 + 304 390970 Y-97 2.83660E-03 6.98030E-03 390970 + 305 390971 Y-97m 1.04850E-02 1.40750E-02 390971 + 306 390972 Y-97m 3.60330E-03 3.60330E-03 390972 + 307 390980 Y-98 2.12540E-03 3.95100E-03 390980 + 308 390981 Y-98m 1.03040E-02 1.03040E-02 390981 + 309 390990 Y-99 8.05640E-03 8.37900E-03 390990 + 310 391000 Y-100 1.47090E-03 1.53330E-03 391000 + 311 391001 Y-100m 1.47090E-03 1.47100E-03 391001 + 312 391010 Y-101 9.51600E-04 9.55230E-04 391010 + 313 391020 Y-102 7.29800E-05 7.29820E-05 391020 + 314 391021 Y-102m 7.29800E-05 7.29820E-05 391021 + 315 391030 Y-103 2.09040E-05 2.09040E-05 391030 + 316 391040 Y-104 1.73310E-08 1.73310E-08 391040 + 317 400910 Zr-91 2.94790E-10 1.11820E-02 40091.82c + 318 400920 Zr-92 9.78150E-07 1.47460E-02 40092.82c + 319 400930 Zr-93 3.17280E-05 1.82570E-02 40093.82c + 320 400940 Zr-94 2.75990E-04 2.29180E-02 40094.82c + 321 400950 Zr-95 1.16670E-03 2.51280E-02 40095.82c + 322 400960 Zr-96 5.71280E-03 2.98830E-02 40096.82c + 323 400970 Zr-97 1.18730E-02 3.39040E-02 400970 + 324 400980 Zr-98 2.58240E-02 3.98560E-02 400980 + 325 400990 Zr-99 2.72280E-02 3.54790E-02 400990 + 326 401000 Zr-100 2.79430E-02 3.09330E-02 401000 + 327 401010 Zr-101 1.49250E-02 1.58870E-02 401010 + 328 401020 Zr-102 8.07450E-03 8.21500E-03 401020 + 329 401030 Zr-103 2.19800E-03 2.21720E-03 401030 + 330 401040 Zr-104 5.95940E-04 5.95960E-04 401040 + 331 401050 Zr-105 8.89220E-05 8.89220E-05 401050 + 332 401060 Zr-106 1.22690E-05 1.22690E-05 401060 + 333 401070 Zr-107 1.65110E-09 1.65110E-09 401070 + 334 410940 Nb-94 4.25510E-09 6.78680E-09 41094.82c + 335 410941 Nb-94m 2.54440E-09 2.54440E-09 410941 + 336 410950 Nb-95 7.60570E-06 2.51210E-02 41095.82c + 337 410951 Nb-95m 1.53140E-06 2.73000E-04 410951 + 338 410960 Nb-96 7.43540E-05 7.43540E-05 410960 + 339 410970 Nb-97 4.15950E-04 3.44040E-02 410970 + 340 410971 Nb-97m 8.37500E-05 3.23090E-02 410971 + 341 410980 Nb-98 4.27760E-04 4.02840E-02 410980 + 342 410981 Nb-98m 1.49040E-03 1.49040E-03 410981 + 343 410990 Nb-99 6.42950E-03 2.91390E-02 410990 + 344 410991 Nb-99m 1.29450E-03 1.43510E-02 410991 + 345 411000 Nb-100 2.48840E-03 3.34220E-02 411000 + 346 411001 Nb-100m 1.20640E-02 1.20640E-02 411001 + 347 411010 Nb-101 2.58320E-02 4.17190E-02 411010 + 348 411020 Nb-102 1.14540E-02 1.96680E-02 411020 + 349 411021 Nb-102m 1.14540E-02 1.14540E-02 411021 + 350 411030 Nb-103 2.05540E-02 2.27710E-02 411030 + 351 411040 Nb-104 5.33350E-03 5.93070E-03 411040 + 352 411041 Nb-104m 5.33350E-03 5.33350E-03 411041 + 353 411050 Nb-105 5.29440E-03 5.38230E-03 411050 + 354 411060 Nb-106 1.30410E-03 1.31620E-03 411060 + 355 411070 Nb-107 3.67080E-04 3.67080E-04 411070 + 356 411080 Nb-108 4.25300E-05 4.25300E-05 411080 + 357 411090 Nb-109 3.29600E-06 3.29600E-06 411090 + 358 420960 Mo-96 9.29160E-07 7.52830E-05 42096.82c + 359 420970 Mo-97 7.44130E-06 3.44110E-02 42097.82c + 360 420980 Mo-98 1.02100E-04 4.18760E-02 42098.82c + 361 420990 Mo-99 5.25410E-04 4.37280E-02 42099.82c + 362 421000 Mo-100 2.89610E-03 4.83810E-02 42100.82c + 363 421010 Mo-101 8.14880E-03 4.98680E-02 421010 + 364 421020 Mo-102 2.23830E-02 5.35050E-02 421020 + 365 421030 Mo-103 3.06020E-02 5.33800E-02 421030 + 366 421040 Mo-104 4.09770E-02 5.23260E-02 421040 + 367 421050 Mo-105 2.74580E-02 3.28080E-02 421050 + 368 421060 Mo-106 1.92430E-02 2.05220E-02 421060 + 369 421070 Mo-107 8.18570E-03 8.53340E-03 421070 + 370 421080 Mo-108 3.33380E-03 3.37410E-03 421080 + 371 421090 Mo-109 7.23080E-04 7.25960E-04 421090 + 372 421100 Mo-110 1.19840E-04 1.19840E-04 421100 + 373 421110 Mo-111 1.18590E-05 1.18590E-05 421110 + 374 421120 Mo-112 1.03070E-09 1.03070E-09 421120 + 375 430990 Tc-99 7.69900E-07 4.37280E-02 43099.82c + 376 430991 Tc-99m 1.55020E-07 3.85070E-02 430991 + 377 431000 Tc-100 1.59280E-05 1.59280E-05 431000 + 378 431010 Tc-101 1.51950E-04 5.00200E-02 431010 + 379 431020 Tc-102 3.91300E-04 5.38960E-02 431020 + 380 431021 Tc-102m 3.91300E-04 3.91300E-04 431021 + 381 431030 Tc-103 4.18780E-03 5.75670E-02 431030 + 382 431040 Tc-104 1.03910E-02 6.27170E-02 431040 + 383 431050 Tc-105 2.53520E-02 5.81600E-02 431050 + 384 431060 Tc-106 2.91690E-02 4.96910E-02 431060 + 385 431070 Tc-107 3.10550E-02 3.95880E-02 431070 + 386 431080 Tc-108 1.80140E-02 2.13920E-02 431080 + 387 431090 Tc-109 1.20080E-02 1.27300E-02 431090 + 388 431100 Tc-110 4.88590E-03 5.00590E-03 431100 + 389 431110 Tc-111 1.62910E-03 1.64080E-03 431110 + 390 431120 Tc-112 3.08180E-04 3.08180E-04 431120 + 391 431130 Tc-113 3.82780E-05 3.82780E-05 431130 + 392 431140 Tc-114 1.98020E-09 1.98020E-09 431140 + 393 441010 Ru-101 9.30330E-07 5.00210E-02 44101.82c + 394 441020 Ru-102 2.14190E-05 5.43090E-02 44102.82c + 395 441030 Ru-103 3.23730E-05 5.76900E-02 44103.82c + 396 441031 Ru-103m 9.05770E-05 9.05770E-05 441031 + 397 441040 Ru-104 9.53540E-04 6.36710E-02 44104.82c + 398 441050 Ru-105 3.34130E-03 6.15010E-02 44105.82c + 399 441060 Ru-106 1.17420E-02 6.14330E-02 44106.82c + 400 441070 Ru-107 2.09200E-02 6.05080E-02 441070 + 401 441080 Ru-108 3.42050E-02 5.56070E-02 441080 + 402 441090 Ru-109 2.93920E-02 4.21140E-02 441090 + 403 441100 Ru-110 2.43080E-02 2.93120E-02 441100 + 404 441110 Ru-111 1.15250E-02 1.31700E-02 441110 + 405 441120 Ru-112 5.75530E-03 6.06160E-03 441120 + 406 441130 Ru-113 7.21200E-04 1.11730E-03 441130 + 407 441131 Ru-113m 7.21200E-04 7.21200E-04 441131 + 408 441140 Ru-114 3.23060E-04 3.23060E-04 441140 + 409 441150 Ru-115 2.21360E-05 2.21360E-05 441150 + 410 441160 Ru-116 5.54130E-06 5.54130E-06 441160 + 411 441170 Ru-117 3.30410E-11 3.30410E-11 441170 + 412 451040 Rh-104 8.78620E-07 3.93600E-06 451040 + 413 451041 Rh-104m 3.06140E-06 3.06140E-06 451041 + 414 451050 Rh-105 2.56180E-05 6.15300E-02 45105.82c + 415 451051 Rh-105m 3.41090E-06 1.74620E-02 451051 + 416 451060 Rh-106 5.57550E-05 6.14890E-02 451060 + 417 451061 Rh-106m 1.51970E-04 1.51970E-04 451061 + 418 451070 Rh-107 1.12980E-03 6.16380E-02 451070 + 419 451080 Rh-108 7.47900E-04 5.63550E-02 451080 + 420 451081 Rh-108m 2.60590E-03 2.60590E-03 451081 + 421 451090 Rh-109 9.48990E-03 5.16040E-02 451090 + 422 451100 Rh-110 1.42950E-02 4.36070E-02 451100 + 423 451101 Rh-110m 3.36540E-04 3.36540E-04 451101 + 424 451110 Rh-111 1.95460E-02 3.27170E-02 451110 + 425 451120 Rh-112 6.66700E-03 1.27290E-02 451120 + 426 451121 Rh-112m 6.66700E-03 6.66700E-03 451121 + 427 451130 Rh-113 9.00350E-03 1.04810E-02 451130 + 428 451140 Rh-114 1.73650E-03 2.05970E-03 451140 + 429 451141 Rh-114m 1.73650E-03 1.73650E-03 451141 + 430 451150 Rh-115 1.21300E-03 1.23510E-03 451150 + 431 451160 Rh-116 5.88900E-05 6.43710E-05 451160 + 432 451161 Rh-116m 1.60520E-04 1.60520E-04 451161 + 433 451170 Rh-117 6.78130E-05 6.78130E-05 451170 + 434 451180 Rh-118 1.86770E-05 1.86770E-05 451180 + 435 451190 Rh-119 4.43500E-06 4.43500E-06 451190 + 436 461060 Pd-106 1.02260E-06 6.16420E-02 46106.82c + 437 461070 Pd-107 6.85440E-06 6.16600E-02 46107.82c + 438 461071 Pd-107m 1.50660E-05 1.50660E-05 461071 + 439 461080 Pd-108 1.11620E-04 5.90730E-02 46108.82c + 440 461090 Pd-109 1.64890E-04 5.21310E-02 461090 + 441 461091 Pd-109m 3.62410E-04 2.61640E-02 461091 + 442 461100 Pd-110 2.15100E-03 4.60950E-02 46110.82c + 443 461110 Pd-111 1.29590E-03 3.60560E-02 461110 + 444 461111 Pd-111m 2.84850E-03 2.97930E-03 461111 + 445 461120 Pd-112 8.03840E-03 2.74340E-02 461120 + 446 461130 Pd-113 1.91340E-03 1.77480E-02 461130 + 447 461131 Pd-113m 5.35350E-03 5.35350E-03 461131 + 448 461140 Pd-114 6.45620E-03 1.02520E-02 461140 + 449 461150 Pd-115 8.97260E-04 2.12520E-03 461150 + 450 461151 Pd-115m 1.97210E-03 2.15150E-03 461151 + 451 461160 Pd-116 1.38800E-03 1.61290E-03 461160 + 452 461170 Pd-117 1.24990E-04 4.68070E-04 461170 + 453 461171 Pd-117m 2.74720E-04 2.74720E-04 461171 + 454 461180 Pd-118 1.17260E-04 1.35390E-04 461180 + 455 461190 Pd-119 2.22330E-05 2.66680E-05 461190 + 456 461200 Pd-120 7.46730E-06 7.46730E-06 461200 + 457 461210 Pd-121 1.69860E-06 1.69860E-06 461210 + 458 461220 Pd-122 3.49650E-12 3.49650E-12 461220 + 459 461230 Pd-123 1.17810E-07 1.17810E-07 461230 + 460 461240 Pd-124 2.27020E-08 2.27020E-08 461240 + 461 471090 Ag-109 2.58270E-07 5.21330E-02 47109.82c + 462 471091 Ag-109m 1.93970E-06 5.21080E-02 471091 + 463 471100 Ag-110 4.70480E-06 4.87920E-06 471100 + 464 471101 Ag-110m 1.28240E-05 1.28240E-05 47510.82c + 465 471110 Ag-111 1.32280E-05 3.67910E-02 47111.82c + 466 471111 Ag-111m 9.93520E-05 3.64730E-02 471111 + 467 471120 Ag-112 3.32540E-04 2.77660E-02 471120 + 468 471130 Ag-113 1.08590E-04 1.22610E-02 471130 + 469 471131 Ag-113m 8.15550E-04 1.78110E-02 471131 + 470 471140 Ag-114 2.27480E-04 1.15830E-02 471140 + 471 471141 Ag-114m 1.10280E-03 1.10280E-03 471141 + 472 471150 Ag-115 2.02190E-04 2.60870E-03 471150 + 473 471151 Ag-115m 1.51860E-03 4.07180E-03 471151 + 474 471160 Ag-116 2.68780E-04 1.92560E-03 471160 + 475 471161 Ag-116m 7.32620E-04 7.32620E-04 471161 + 476 471170 Ag-117 7.76150E-05 3.60670E-04 471170 + 477 471171 Ag-117m 5.82940E-04 8.16970E-04 471171 + 478 471180 Ag-118 3.19800E-05 2.19520E-04 471180 + 479 471181 Ag-118m 1.55040E-04 1.74400E-04 471181 + 480 471190 Ag-119 8.28050E-06 2.16150E-05 471190 + 481 471191 Ag-119m 6.21910E-05 7.55260E-05 471191 + 482 471200 Ag-120 5.04050E-06 1.32790E-05 471200 + 483 471201 Ag-120m 8.42950E-06 1.21630E-05 471201 + 484 471210 Ag-121 1.19370E-05 1.36310E-05 471210 + 485 471220 Ag-122 7.82380E-06 7.82380E-06 471220 + 486 471221 Ag-122m 8.43520E-06 8.43520E-06 471221 + 487 471230 Ag-123 2.04060E-05 2.05240E-05 471230 + 488 471240 Ag-124 5.90380E-06 9.10910E-06 471240 + 489 471241 Ag-124m 6.36520E-06 6.36520E-06 471241 + 490 471250 Ag-125 5.91660E-06 5.91660E-06 471250 + 491 471260 Ag-126 4.27180E-07 4.27180E-07 471260 + 492 471270 Ag-127 3.96970E-08 3.96970E-08 471270 + 493 471280 Ag-128 1.22130E-09 1.22130E-09 471280 + 494 481110 Cd-111 2.47760E-07 3.69750E-02 48111.82c + 495 481111 Cd-111m 9.38250E-07 9.38250E-07 481111 + 496 481120 Cd-112 2.49510E-06 2.77690E-02 48112.82c + 497 481130 Cd-113 4.94240E-06 1.84660E-02 48113.82c + 498 481131 Cd-113m 1.87170E-05 2.30690E-04 481131 + 499 481140 Cd-114 7.04800E-05 1.16530E-02 48114.82c + 500 481150 Cd-115 2.05590E-05 5.60190E-03 481150 + 501 481151 Cd-115m 7.78570E-05 3.21820E-04 48515.82c + 502 481160 Cd-116 2.14510E-04 2.82880E-03 48116.82c + 503 481170 Cd-117 2.92020E-05 9.06540E-04 481170 + 504 481171 Cd-117m 1.10590E-04 3.61870E-04 481171 + 505 481180 Cd-118 1.32220E-04 4.54630E-04 481180 + 506 481190 Cd-119 1.50360E-05 1.01370E-04 481190 + 507 481191 Cd-119m 4.20700E-05 5.28770E-05 481191 + 508 481200 Cd-120 3.86250E-05 5.95660E-05 481200 + 509 481210 Cd-121 8.05910E-06 2.02660E-05 481210 + 510 481211 Cd-121m 2.25490E-05 2.39730E-05 481211 + 511 481220 Cd-122 5.03930E-05 6.66520E-05 481220 + 512 481230 Cd-123 2.83680E-05 4.51640E-05 481230 + 513 481231 Cd-123m 7.93720E-05 8.31090E-05 481231 + 514 481240 Cd-124 3.07920E-04 3.20200E-04 481240 + 515 481250 Cd-125 7.33660E-05 7.63240E-05 481250 + 516 481251 Cd-125m 2.05270E-04 2.08230E-04 481251 + 517 481260 Cd-126 2.19780E-04 2.20210E-04 481260 + 518 481270 Cd-127 8.32750E-05 8.33150E-05 481270 + 519 481280 Cd-128 2.60090E-05 2.60100E-05 481280 + 520 481290 Cd-129 7.46770E-07 7.46770E-07 481290 + 521 481291 Cd-129m 2.08940E-06 2.08940E-06 481291 + 522 481300 Cd-130 2.77010E-08 2.77010E-08 481300 + 523 491140 In-114 1.89250E-09 8.25580E-09 491140 + 524 491141 In-114m 3.05600E-09 6.59410E-09 491141 + 525 491142 In-114m 3.53810E-09 3.53810E-09 491142 + 526 491150 In-115 1.15170E-06 5.64500E-03 49115.82c + 527 491151 In-115m 2.31890E-07 5.60220E-03 491151 + 528 491160 In-116 6.16930E-07 6.16930E-07 491160 + 529 491161 In-116m 9.96220E-07 2.14960E-06 491161 + 530 491162 In-116m 1.15330E-06 1.15330E-06 491162 + 531 491170 In-117 7.02670E-06 8.33710E-04 491170 + 532 491171 In-117m 1.41480E-06 8.37700E-04 491171 + 533 491180 In-118 1.91080E-06 4.56540E-04 491180 + 534 491181 In-118m 3.08560E-06 6.60780E-06 491181 + 535 491182 In-118m 3.57220E-06 3.57220E-06 491182 + 536 491190 In-119 1.46220E-05 8.25350E-05 491190 + 537 491191 In-119m 2.94410E-06 9.45730E-05 491191 + 538 491200 In-120 4.96680E-07 6.00630E-05 491200 + 539 491201 In-120m 4.96680E-07 4.96680E-07 491201 + 540 491202 In-120m 4.96680E-07 4.96680E-07 491202 + 541 491210 In-121 1.82600E-05 4.92640E-05 491210 + 542 491211 In-121m 3.67660E-06 1.71170E-05 491211 + 543 491220 In-122 6.68960E-06 7.33420E-05 491220 + 544 491221 In-122m 5.59370E-06 5.59370E-06 491221 + 545 491222 In-122m 5.59370E-06 5.59370E-06 491222 + 546 491230 In-123 5.57780E-05 1.51860E-04 491230 + 547 491231 In-123m 1.12310E-05 4.34200E-05 491231 + 548 491240 In-124 9.29340E-05 4.13140E-04 491240 + 549 491241 In-124m 1.00200E-04 1.00200E-04 491241 + 550 491250 In-125 7.34910E-04 9.79670E-04 491250 + 551 491251 In-125m 1.47970E-04 1.87760E-04 491251 + 552 491260 In-126 6.09920E-04 8.30130E-04 491260 + 553 491261 In-126m 6.57580E-04 6.57580E-04 491261 + 554 491270 In-127 1.46970E-03 1.46970E-03 491270 + 555 491271 In-127m 2.95920E-04 3.79230E-04 491271 + 556 491280 In-128 4.22050E-04 6.13320E-04 491280 + 557 491281 In-128m 1.65260E-04 1.91270E-04 491281 + 558 491282 In-128m 6.33200E-04 6.33200E-04 491282 + 559 491290 In-129 5.72590E-04 5.74680E-04 491290 + 560 491291 In-129m 1.15290E-04 1.16040E-04 491291 + 561 491300 In-130 5.16330E-05 5.16600E-05 491300 + 562 491301 In-130m 7.51810E-05 7.51810E-05 491301 + 563 491302 In-130m 1.04730E-04 1.04730E-04 491302 + 564 491310 In-131 1.46560E-05 1.48060E-05 491310 + 565 491311 In-131m 1.46560E-05 1.46560E-05 491311 + 566 491312 In-131m 1.46560E-05 1.46560E-05 491312 + 567 491320 In-132 2.21760E-07 2.21760E-07 491320 + 568 491330 In-133 6.78890E-09 8.15580E-09 491330 + 569 491331 In-133m 1.36690E-09 1.36690E-09 491331 + 570 501160 Sn-116 4.08480E-10 2.76690E-06 50116.82c + 571 501170 Sn-117 1.54610E-09 1.27690E-03 50117.82c + 572 501171 Sn-117m 5.85520E-09 2.84640E-06 501171 + 573 501180 Sn-118 1.06240E-07 4.63310E-04 50118.82c + 574 501190 Sn-119 9.07210E-08 1.72250E-04 50119.82c + 575 501191 Sn-119m 3.43560E-07 7.49060E-05 501191 + 576 501200 Sn-120 1.84730E-06 6.29060E-05 50120.82c + 577 501210 Sn-121 8.93350E-07 6.77590E-05 501210 + 578 501211 Sn-121m 2.49960E-06 8.08040E-06 501211 + 579 501220 Sn-122 1.07540E-05 9.53020E-05 50122.82c + 580 501230 Sn-123 8.11700E-06 1.96950E-05 50123.82c + 581 501231 Sn-123m 2.90100E-06 1.86610E-04 501231 + 582 501240 Sn-124 9.06830E-05 6.04020E-04 50124.82c + 583 501250 Sn-125 2.46820E-04 4.12300E-04 50125.82c + 584 501251 Sn-125m 8.82130E-05 1.09020E-03 501251 + 585 501260 Sn-126 1.82420E-03 3.31450E-03 50126.82c + 586 501270 Sn-127 2.97460E-03 3.54740E-03 501270 + 587 501271 Sn-127m 1.06310E-03 2.33660E-03 501271 + 588 501280 Sn-128 2.35810E-03 1.00320E-02 501280 + 589 501281 Sn-128m 6.42760E-03 7.06080E-03 501281 + 590 501290 Sn-129 1.94570E-03 2.57540E-03 501290 + 591 501291 Sn-129m 5.44410E-03 5.50520E-03 501291 + 592 501300 Sn-130 1.80260E-03 1.94420E-03 501300 + 593 501301 Sn-130m 4.91350E-03 5.00380E-03 501301 + 594 501310 Sn-131 8.38720E-04 8.67110E-04 501310 + 595 501311 Sn-131m 2.34670E-03 2.36200E-03 501311 + 596 501320 Sn-132 1.04160E-03 1.04180E-03 501320 + 597 501330 Sn-133 8.07870E-05 8.07880E-05 501330 + 598 501340 Sn-134 9.11600E-06 9.11600E-06 501340 + 599 501350 Sn-135 9.88690E-07 9.88690E-07 501350 + 600 511180 Sb-118 4.18320E-12 4.18320E-12 511180 + 601 511181 Sb-118m 6.99580E-12 6.99580E-12 511181 + 602 511190 Sb-119 1.56530E-10 2.19390E-10 511190 + 603 511191 Sb-119m 6.28550E-11 6.28550E-11 511191 + 604 511200 Sb-120 7.76350E-10 7.76350E-10 511200 + 605 511201 Sb-120m 1.29830E-09 1.29830E-09 511201 + 606 511210 Sb-121 6.68430E-08 6.96360E-05 51121.82c + 607 511220 Sb-122 3.15880E-07 7.39080E-07 511220 + 608 511221 Sb-122m 4.23200E-07 4.23200E-07 511221 + 609 511230 Sb-123 3.67760E-06 2.09980E-04 51123.82c + 610 511240 Sb-124 1.31320E-06 3.37970E-06 51124.82c + 611 511241 Sb-124m 1.05930E-06 2.75530E-06 511241 + 612 511242 Sb-124m 1.69600E-06 1.69600E-06 511242 + 613 511250 Sb-125 1.17950E-05 1.51430E-03 51125.82c + 614 511260 Sb-126 4.72970E-05 5.65600E-05 51126.82c + 615 511261 Sb-126m 2.95420E-05 6.61640E-05 511261 + 616 511262 Sb-126m 3.66220E-05 3.66220E-05 511262 + 617 511270 Sb-127 6.67790E-04 6.55180E-03 511270 + 618 511280 Sb-128 1.09340E-03 1.11810E-02 511280 + 619 511281 Sb-128m 1.52930E-03 1.52930E-03 511281 + 620 511290 Sb-129 5.90560E-03 1.23020E-02 511290 + 621 511291 Sb-129m 4.37040E-03 7.12300E-03 511291 + 622 511300 Sb-130 7.65850E-03 1.21050E-02 511300 + 623 511301 Sb-130m 7.65850E-03 1.01600E-02 511301 + 624 511310 Sb-131 2.24460E-02 2.56750E-02 511310 + 625 511320 Sb-132 7.14020E-03 8.18210E-03 511320 + 626 511321 Sb-132m 6.32180E-03 6.32180E-03 511321 + 627 511330 Sb-133 8.62040E-03 8.70270E-03 511330 + 628 511340 Sb-134 4.89830E-04 4.97500E-04 511340 + 629 511341 Sb-134m 1.33520E-03 1.33530E-03 511341 + 630 511350 Sb-135 3.26400E-04 3.27180E-04 511350 + 631 511360 Sb-136 2.83950E-05 2.83950E-05 511360 + 632 511370 Sb-137 7.91370E-07 7.91370E-07 511370 + 633 511380 Sb-138 5.35910E-09 5.35910E-09 511380 + 634 521210 Te-121 2.30020E-12 1.00270E-11 521210 + 635 521211 Te-121m 8.71080E-12 8.71080E-12 521211 + 636 521220 Te-122 9.61480E-10 7.20820E-07 52122.82c + 637 521250 Te-125 6.87680E-11 1.51430E-03 52125.82c + 638 521251 Te-125m 2.60420E-10 3.38840E-04 521251 + 639 521260 Te-126 4.58140E-08 1.13510E-04 52126.82c + 640 521270 Te-127 2.81310E-06 6.53640E-03 521270 + 641 521271 Te-127m 7.87090E-06 1.08760E-03 52527.82c + 642 521280 Te-128 1.41980E-04 1.27970E-02 52128.82c + 643 521290 Te-129 2.41940E-04 1.60820E-02 521290 + 644 521291 Te-129m 6.76930E-04 8.63110E-03 52529.82c + 645 521300 Te-130 5.90940E-03 2.81740E-02 52130.82c + 646 521310 Te-131 3.93580E-03 3.03000E-02 521310 + 647 521311 Te-131m 1.10120E-02 1.30680E-02 521311 + 648 521320 Te-132 3.57640E-02 5.02680E-02 52132.82c + 649 521330 Te-133 1.01850E-02 2.26340E-02 521330 + 650 521331 Te-133m 2.84960E-02 3.00020E-02 521331 + 651 521340 Te-134 3.34130E-02 3.52960E-02 521340 + 652 521350 Te-135 9.76650E-03 1.00470E-02 521350 + 653 521360 Te-136 3.78900E-03 3.81310E-03 521360 + 654 521370 Te-137 6.24920E-04 6.25320E-04 521370 + 655 521380 Te-138 1.09360E-04 1.09360E-04 521380 + 656 521390 Te-139 5.53040E-06 5.53040E-06 521390 + 657 521400 Te-140 5.00720E-08 5.00720E-08 521400 + 658 531270 I-127 2.20530E-10 6.56250E-03 53127.82c + 659 531280 I-128 1.74040E-08 1.74040E-08 531280 + 660 531290 I-129 1.21390E-06 1.92770E-02 53129.82c + 661 531300 I-130 4.66640E-05 6.10440E-05 53130.82c + 662 531301 I-130m 1.71190E-05 1.71190E-05 531301 + 663 531310 I-131 6.44160E-04 4.12670E-02 53131.82c + 664 531320 I-132 1.25550E-03 5.24790E-02 531320 + 665 531321 I-132m 1.11160E-03 1.11160E-03 531321 + 666 531330 I-133 7.29410E-03 6.00770E-02 531330 + 667 531331 I-133m 5.39790E-03 5.39790E-03 531331 + 668 531340 I-134 1.57690E-02 6.47050E-02 531340 + 669 531341 I-134m 1.39610E-02 1.39610E-02 531341 + 670 531350 I-135 4.86310E-02 5.86780E-02 53135.82c + 671 531360 I-136 6.26500E-03 1.00870E-02 531360 + 672 531361 I-136m 1.70770E-02 1.70860E-02 531361 + 673 531370 I-137 1.37220E-02 1.43350E-02 531370 + 674 531380 I-138 4.18010E-03 4.28260E-03 531380 + 675 531390 I-139 2.21980E-03 2.22530E-03 531390 + 676 531400 I-140 3.29490E-04 3.29540E-04 531400 + 677 531410 I-141 6.08170E-05 6.08170E-05 531410 + 678 531420 I-142 5.58200E-06 5.58200E-06 531420 + 679 531430 I-143 5.27440E-09 5.27440E-09 531430 + 680 541300 Xe-130 8.20760E-09 6.37910E-05 54130.82c + 681 541310 Xe-131 3.52320E-07 4.12690E-02 54131.82c + 682 541311 Xe-131m 9.85780E-07 4.49230E-04 541311 + 683 541320 Xe-132 1.88910E-05 5.26790E-02 54132.82c + 684 541321 Xe-132m 2.53090E-05 2.53090E-05 541321 + 685 541330 Xe-133 1.06350E-04 6.04810E-02 54133.82c + 686 541331 Xe-133m 2.97580E-04 2.00760E-03 541331 + 687 541340 Xe-134 8.17710E-04 6.80730E-02 54134.82c + 688 541341 Xe-134m 2.22890E-03 2.55000E-03 541341 + 689 541350 Xe-135 3.09900E-03 7.03380E-02 54135.82c + 690 541351 Xe-135m 8.67100E-03 1.83580E-02 541351 + 691 541360 Xe-136 4.06960E-02 6.88020E-02 54136.82c + 692 541370 Xe-137 3.56570E-02 4.92880E-02 541370 + 693 541380 Xe-138 3.62020E-02 4.04760E-02 541380 + 694 541390 Xe-139 1.85770E-02 2.06150E-02 541390 + 695 541400 Xe-140 1.31480E-02 1.34600E-02 541400 + 696 541410 Xe-141 3.84620E-03 3.89560E-03 541410 + 697 541420 Xe-142 1.18390E-03 1.18810E-03 541420 + 698 541430 Xe-143 1.25510E-04 1.25510E-04 541430 + 699 541440 Xe-144 1.69090E-05 1.69090E-05 541440 + 700 541450 Xe-145 2.12120E-08 2.12120E-08 541450 + 701 551320 Cs-132 1.21850E-09 1.21850E-09 551320 + 702 551330 Cs-133 1.14180E-07 6.04810E-02 55133.82c + 703 551340 Cs-134 1.81390E-06 3.41980E-06 55134.82c + 704 551341 Cs-134m 1.60590E-06 1.60590E-06 551341 + 705 551350 Cs-135 7.22910E-05 7.05740E-02 55135.82c + 706 551351 Cs-135m 5.34990E-05 5.34990E-05 551351 + 707 551360 Cs-136 5.22980E-04 7.09940E-04 55136.82c + 708 551361 Cs-136m 3.73920E-04 3.73920E-04 551361 + 709 551370 Cs-137 6.11600E-03 5.54040E-02 55137.82c + 710 551380 Cs-138 5.06330E-03 5.23980E-02 551380 + 711 551381 Cs-138m 8.46770E-03 8.46770E-03 551381 + 712 551390 Cs-139 2.35370E-02 4.41520E-02 551390 + 713 551400 Cs-140 2.17820E-02 3.52430E-02 551400 + 714 551410 Cs-141 2.58980E-02 2.97960E-02 551410 + 715 551420 Cs-142 1.20950E-02 1.32800E-02 551420 + 716 551430 Cs-143 6.02810E-03 6.15290E-03 551430 + 717 551440 Cs-144 6.66950E-04 1.01680E-03 551440 + 718 551441 Cs-144m 6.66950E-04 6.66950E-04 551441 + 719 551450 Cs-145 3.54530E-04 3.54550E-04 551450 + 720 551460 Cs-146 4.16310E-05 4.16310E-05 551460 + 721 551470 Cs-147 5.53180E-06 5.53180E-06 551470 + 722 551480 Cs-148 2.22870E-09 2.22870E-09 551480 + 723 561350 Ba-135 5.20680E-07 1.97750E-06 56135.82c + 724 561351 Ba-135m 1.45680E-06 1.45680E-06 561351 + 725 561360 Ba-136 9.53570E-07 9.00450E-04 56136.82c + 726 561361 Ba-136m 2.59920E-06 2.59920E-06 561361 + 727 561370 Ba-137 2.48200E-05 5.54980E-02 56137.82c + 728 561371 Ba-137m 6.94450E-05 5.23700E-02 561371 + 729 561380 Ba-138 1.40770E-03 5.54140E-02 56138.82c + 730 561390 Ba-139 4.39930E-03 4.85510E-02 561390 + 731 561400 Ba-140 1.32300E-02 4.84730E-02 56140.82c + 732 561410 Ba-141 1.91480E-02 4.89440E-02 561410 + 733 561420 Ba-142 3.17280E-02 4.51090E-02 561420 + 734 561430 Ba-143 2.47570E-02 3.08420E-02 561430 + 735 561440 Ba-144 1.90000E-02 2.03690E-02 561440 + 736 561450 Ba-145 7.47140E-03 7.78120E-03 561450 + 737 561460 Ba-146 3.70500E-03 3.74230E-03 561460 + 738 561470 Ba-147 7.88200E-04 7.92160E-04 561470 + 739 561480 Ba-148 2.02760E-04 2.02760E-04 561480 + 740 561490 Ba-149 1.26250E-05 1.26250E-05 561490 + 741 561500 Ba-150 1.97370E-06 1.97370E-06 561500 + 742 571370 La-137 1.85070E-09 1.85070E-09 571370 + 743 571380 La-138 1.74000E-06 1.74000E-06 57138.82c + 744 571390 La-139 4.79540E-05 4.85990E-02 57139.82c + 745 571400 La-140 2.09840E-04 4.86830E-02 57140.82c + 746 571410 La-141 1.18010E-03 5.01240E-02 571410 + 747 571420 La-142 2.56110E-03 4.76700E-02 571420 + 748 571430 La-143 7.81670E-03 3.86580E-02 571430 + 749 571440 La-144 1.13400E-02 3.17090E-02 571440 + 750 571450 La-145 1.61850E-02 2.39660E-02 571450 + 751 571460 La-146 3.76060E-03 7.50290E-03 571460 + 752 571461 La-146m 7.88940E-03 7.88940E-03 571461 + 753 571470 La-147 9.60970E-03 1.04030E-02 571470 + 754 571480 La-148 3.51240E-03 3.71440E-03 571480 + 755 571490 La-149 1.20970E-03 1.22230E-03 571490 + 756 571500 La-150 2.13960E-04 2.15930E-04 571500 + 757 571510 La-151 3.20660E-05 3.20660E-05 571510 + 758 571520 La-152 3.14500E-06 3.14500E-06 571520 + 759 571530 La-153 9.39680E-10 9.39680E-10 571530 + 760 581400 Ce-140 4.85060E-06 4.86880E-02 58140.82c + 761 581410 Ce-141 2.59430E-05 5.01500E-02 58141.82c + 762 581420 Ce-142 1.41390E-04 4.78110E-02 58142.82c + 763 581430 Ce-143 4.67060E-04 3.91250E-02 58143.82c + 764 581440 Ce-144 2.11950E-03 3.38280E-02 58144.82c + 765 581450 Ce-145 4.98050E-03 2.89470E-02 581450 + 766 581460 Ce-146 1.09780E-02 2.63700E-02 581460 + 767 581470 Ce-147 1.36080E-02 2.40110E-02 581470 + 768 581480 Ce-148 1.62830E-02 2.00150E-02 581480 + 769 581490 Ce-149 9.94990E-03 1.11610E-02 581490 + 770 581500 Ce-150 6.06540E-03 6.27550E-03 581500 + 771 581510 Ce-151 1.61430E-03 1.64660E-03 581510 + 772 581520 Ce-152 5.24410E-04 5.27370E-04 581520 + 773 581530 Ce-153 5.72250E-05 5.72260E-05 581530 + 774 581540 Ce-154 1.13730E-05 1.13730E-05 581540 + 775 581550 Ce-155 3.41160E-09 3.41160E-09 581550 + 776 591420 Pr-142 3.06240E-10 1.14100E-09 59142.82c + 777 591421 Pr-142m 8.34760E-10 8.34760E-10 591421 + 778 591430 Pr-143 1.74480E-06 3.91270E-02 59143.82c + 779 591440 Pr-144 8.64790E-07 3.38370E-02 591440 + 780 591441 Pr-144m 8.79770E-06 4.75600E-04 591441 + 781 591450 Pr-145 7.12810E-05 2.90180E-02 591450 + 782 591460 Pr-146 3.41940E-04 2.67120E-02 591460 + 783 591470 Pr-147 1.49300E-03 2.55040E-02 591470 + 784 591480 Pr-148 5.10500E-04 2.05250E-02 591480 + 785 591481 Pr-148m 2.47490E-03 2.47490E-03 591481 + 786 591490 Pr-149 5.61740E-03 1.67780E-02 591490 + 787 591500 Pr-150 5.85200E-03 1.21270E-02 591500 + 788 591510 Pr-151 6.30270E-03 7.94930E-03 591510 + 789 591520 Pr-152 3.13330E-03 3.66100E-03 591520 + 790 591530 Pr-153 1.36360E-03 1.42050E-03 591530 + 791 591540 Pr-154 3.14830E-04 3.26130E-04 591540 + 792 591550 Pr-155 8.97540E-05 8.97570E-05 591550 + 793 591560 Pr-156 1.29540E-05 1.29540E-05 591560 + 794 591570 Pr-157 1.20590E-08 1.20590E-08 591570 + 795 591580 Pr-158 1.14640E-10 1.14640E-10 591580 + 796 601450 Nd-145 6.06070E-09 2.90180E-02 60145.82c + 797 601460 Nd-146 7.08590E-06 2.67190E-02 60146.82c + 798 601470 Nd-147 5.43190E-05 2.55580E-02 60147.82c + 799 601480 Nd-148 3.19950E-04 2.33200E-02 60148.82c + 800 601490 Nd-149 9.79440E-04 1.77580E-02 601490 + 801 601500 Nd-150 2.61640E-03 1.47440E-02 60150.82c + 802 601510 Nd-151 4.20420E-03 1.21530E-02 601510 + 803 601520 Nd-152 5.96860E-03 9.62960E-03 601520 + 804 601530 Nd-153 4.34360E-03 5.76410E-03 601530 + 805 601540 Nd-154 3.31090E-03 3.63700E-03 601540 + 806 601550 Nd-155 1.49610E-03 1.58620E-03 601550 + 807 601560 Nd-156 4.36350E-04 4.48950E-04 601560 + 808 601570 Nd-157 8.76940E-05 8.77050E-05 601570 + 809 601580 Nd-158 2.37910E-05 2.37910E-05 601580 + 810 601590 Nd-159 3.10840E-06 3.10840E-06 601590 + 811 601600 Nd-160 7.22000E-10 7.22000E-10 601600 + 812 611470 Pm-147 8.58380E-10 2.55580E-02 61147.82c + 813 611480 Pm-148 2.55290E-07 2.90080E-07 61148.82c + 814 611481 Pm-148m 6.95850E-07 6.95850E-07 61548.82c + 815 611490 Pm-149 9.70700E-06 1.77670E-02 61149.82c + 816 611500 Pm-150 3.84330E-05 3.84330E-05 611500 + 817 611510 Pm-151 1.75860E-04 1.23290E-02 61151.82c + 818 611520 Pm-152 8.92260E-05 9.71880E-03 611520 + 819 611521 Pm-152m 1.87580E-04 1.87580E-04 611521 + 820 611522 Pm-152m 2.45030E-04 2.45030E-04 611522 + 821 611530 Pm-153 1.12560E-03 6.88970E-03 611530 + 822 611540 Pm-154 7.73400E-04 4.41040E-03 611540 + 823 611541 Pm-154m 7.73400E-04 7.73400E-04 611541 + 824 611550 Pm-155 2.04480E-03 3.63100E-03 611550 + 825 611560 Pm-156 1.15300E-03 1.60190E-03 611560 + 826 611570 Pm-157 6.60230E-04 7.47940E-04 611570 + 827 611580 Pm-158 1.90340E-04 2.14140E-04 611580 + 828 611590 Pm-159 6.34690E-05 6.65700E-05 611590 + 829 611600 Pm-160 7.58620E-06 7.58690E-06 611600 + 830 611610 Pm-161 3.27840E-06 3.27840E-06 611610 + 831 611620 Pm-162 1.27510E-09 1.27510E-09 611620 + 832 611630 Pm-163 2.03120E-11 2.03120E-11 611630 + 833 621500 Sm-150 9.86730E-07 3.94200E-05 62150.82c + 834 621510 Sm-151 1.11710E-07 1.23290E-02 62151.82c + 835 621520 Sm-152 4.90940E-05 1.02010E-02 62152.82c + 836 621530 Sm-153 3.11040E-05 7.00790E-03 62153.82c + 837 621531 Sm-153m 8.70260E-05 8.70260E-05 621531 + 838 621540 Sm-154 4.23210E-04 5.60700E-03 62154.82c + 839 621550 Sm-155 8.35180E-04 4.46620E-03 621550 + 840 621560 Sm-156 1.06500E-03 2.66690E-03 621560 + 841 621570 Sm-157 1.01290E-03 1.76080E-03 621570 + 842 621580 Sm-158 7.56380E-04 9.70530E-04 621580 + 843 621590 Sm-159 4.96660E-04 5.63240E-04 621590 + 844 621600 Sm-160 2.42930E-04 2.50500E-04 621600 + 845 621610 Sm-161 6.35090E-05 6.67870E-05 621610 + 846 621620 Sm-162 1.24650E-05 1.24660E-05 621620 + 847 621630 Sm-163 2.31960E-06 2.31960E-06 621630 + 848 621640 Sm-164 4.25580E-09 4.25580E-09 621640 + 849 621650 Sm-165 4.69890E-11 4.69890E-11 621650 + 850 631520 Eu-152 9.73220E-11 2.26220E-10 63152.82c + 851 631521 Eu-152m 2.22370E-11 2.22370E-11 631521 + 852 631522 Eu-152m 1.28900E-10 1.28900E-10 631522 + 853 631530 Eu-153 1.29210E-08 7.00790E-03 63153.82c + 854 631540 Eu-154 1.49130E-06 3.09910E-06 63154.82c + 855 631541 Eu-154m 1.60780E-06 1.60780E-06 631541 + 856 631550 Eu-155 1.53320E-05 4.48150E-03 63155.82c + 857 631560 Eu-156 5.65020E-05 2.72350E-03 63156.82c + 858 631570 Eu-157 1.19990E-04 1.88080E-03 63157.82c + 859 631580 Eu-158 1.82710E-04 1.15320E-03 631580 + 860 631590 Eu-159 3.03540E-04 8.66780E-04 631590 + 861 631600 Eu-160 2.89810E-04 5.40310E-04 631600 + 862 631610 Eu-161 1.81580E-04 2.48370E-04 631610 + 863 631620 Eu-162 7.48520E-05 8.73180E-05 631620 + 864 631630 Eu-163 3.24940E-05 3.48140E-05 631630 + 865 631640 Eu-164 1.08560E-05 1.08600E-05 631640 + 866 631650 Eu-165 1.68880E-07 1.68930E-07 631650 + 867 631660 Eu-166 5.07910E-09 5.07910E-09 631660 + 868 631670 Eu-167 1.05520E-10 1.05520E-10 631670 + 869 641550 Gd-155 2.47800E-10 4.48150E-03 64155.82c + 870 641551 Gd-155m 6.93320E-10 6.93320E-10 641551 + 871 641560 Gd-156 9.95460E-07 2.72440E-03 64156.82c + 872 641570 Gd-157 3.96100E-06 1.88480E-03 64157.82c + 873 641580 Gd-158 2.93630E-05 1.18260E-03 64158.82c + 874 641590 Gd-159 6.09120E-05 9.27690E-04 641590 + 875 641600 Gd-160 1.37960E-04 6.78270E-04 64160.82c + 876 641610 Gd-161 1.54600E-04 4.02970E-04 641610 + 877 641620 Gd-162 1.75290E-04 2.62610E-04 641620 + 878 641630 Gd-163 9.27510E-05 1.27570E-04 641630 + 879 641640 Gd-164 5.79010E-05 6.87610E-05 641640 + 880 641650 Gd-165 2.45920E-05 2.47610E-05 641650 + 881 641660 Gd-166 4.96080E-06 4.96590E-06 641660 + 882 641670 Gd-167 1.11910E-07 1.12020E-07 641670 + 883 641680 Gd-168 7.67410E-09 7.67410E-09 641680 + 884 641690 Gd-169 1.74450E-10 1.74450E-10 641690 + 885 651570 Tb-157 6.38050E-11 6.38050E-11 651570 + 886 651580 Tb-158 1.40920E-09 1.54690E-09 651580 + 887 651581 Tb-158m 1.38520E-10 1.38520E-10 651581 + 888 651590 Tb-159 5.72750E-08 9.27750E-04 65159.82c + 889 651600 Tb-160 5.64580E-07 5.64580E-07 65160.82c + 890 651610 Tb-161 9.82710E-06 4.12790E-04 651610 + 891 651620 Tb-162 1.35840E-05 2.76190E-04 651620 + 892 651630 Tb-163 2.20190E-05 1.49580E-04 651630 + 893 651640 Tb-164 3.01290E-05 9.88900E-05 651640 + 894 651650 Tb-165 3.07210E-05 5.54820E-05 651650 + 895 651660 Tb-166 1.98430E-05 2.48090E-05 651660 + 896 651670 Tb-167 8.20080E-06 8.31280E-06 651670 + 897 651680 Tb-168 8.06630E-07 8.14300E-07 651680 + 898 651690 Tb-169 1.46210E-07 1.46380E-07 651690 + 899 651700 Tb-170 3.60940E-09 3.60940E-09 651700 + 900 651710 Tb-171 6.15640E-10 6.15640E-10 651710 + 901 661600 Dy-160 1.74280E-10 5.64750E-07 66160.82c + 902 661610 Dy-161 3.69100E-09 4.12800E-04 66161.82c + 903 661620 Dy-162 1.13240E-06 2.77320E-04 66162.82c + 904 661630 Dy-163 1.15960E-06 1.50740E-04 66163.82c + 905 661640 Dy-164 8.43720E-06 1.07330E-04 66164.82c + 906 661650 Dy-165 5.42230E-06 6.16100E-05 661650 + 907 661651 Dy-165m 7.21950E-07 7.21950E-07 661651 + 908 661660 Dy-166 1.48770E-05 3.96860E-05 661660 + 909 661670 Dy-167 8.19930E-06 1.65120E-05 661670 + 910 661680 Dy-168 4.66520E-06 5.47950E-06 661680 + 911 661690 Dy-169 3.65230E-06 3.79870E-06 661690 + 912 661700 Dy-170 4.39330E-07 4.42940E-07 661700 + 913 661710 Dy-171 1.54760E-07 1.55380E-07 661710 + 914 661720 Dy-172 1.76750E-08 1.76750E-08 661720 + 915 661730 Dy-173 8.29000E-10 8.29000E-10 661730 + 916 671620 Ho-162 1.80130E-12 4.84540E-12 671620 + 917 671621 Ho-162m 4.90980E-12 4.90980E-12 671621 + 918 671630 Ho-163 2.42010E-10 2.74230E-10 671630 + 919 671631 Ho-163m 3.22220E-11 3.22220E-11 671631 + 920 671640 Ho-164 1.26930E-09 4.72900E-09 671640 + 921 671641 Ho-164m 3.45970E-09 3.45970E-09 671641 + 922 671650 Ho-165 7.08860E-08 6.16970E-05 67165.82c + 923 671660 Ho-166 9.31540E-08 3.97790E-05 671660 + 924 671661 Ho-166m 2.53920E-07 2.53920E-07 671661 + 925 671670 Ho-167 1.20650E-06 1.77190E-05 671670 + 926 671680 Ho-168 1.74550E-06 1.01300E-05 671680 + 927 671681 Ho-168m 2.91920E-06 2.91920E-06 671681 + 928 671690 Ho-169 2.43470E-06 6.23340E-06 671690 + 929 671700 Ho-170 1.33170E-06 1.33170E-06 671700 + 930 671701 Ho-170m 4.88540E-07 9.31480E-07 671701 + 931 671710 Ho-171 2.24680E-06 2.40220E-06 671710 + 932 671720 Ho-172 4.76800E-07 4.94480E-07 671720 + 933 671730 Ho-173 1.68540E-07 1.69370E-07 671730 + 934 671740 Ho-174 1.42290E-08 1.42290E-08 671740 + 935 671750 Ho-175 1.36080E-09 1.36080E-09 671750 + 936 681650 Er-165 1.13420E-11 1.13420E-11 681650 + 937 681660 Er-166 4.89610E-10 3.97800E-05 68166.82c + 938 681670 Er-167 3.23240E-09 1.77220E-05 68167.82c + 939 681671 Er-167m 4.30380E-10 2.11770E-06 681671 + 940 681680 Er-168 4.08360E-08 1.01850E-05 68168.82c + 941 681690 Er-169 1.52450E-07 6.38580E-06 681690 + 942 681700 Er-170 2.92800E-07 2.55590E-06 68170.82c + 943 681710 Er-171 1.08980E-06 3.49200E-06 681710 + 944 681720 Er-172 1.85150E-06 2.34600E-06 681720 + 945 681730 Er-173 8.13640E-07 9.83010E-07 681730 + 946 681740 Er-174 4.60660E-07 4.74890E-07 681740 + 947 681750 Er-175 8.51550E-08 8.65160E-08 681750 + 948 681760 Er-176 2.03550E-08 2.03550E-08 681760 + 949 681770 Er-177 1.37950E-09 1.37950E-09 681770 + 950 691680 Tm-168 1.19600E-11 1.19600E-11 691680 + 951 691690 Tm-169 3.71140E-10 6.38620E-06 691690 + 952 691700 Tm-170 1.49960E-09 1.49960E-09 691700 + 953 691710 Tm-171 4.16340E-08 3.53360E-06 691710 + 954 691720 Tm-172 9.75020E-08 2.44350E-06 691720 + 955 691730 Tm-173 3.63190E-07 1.34620E-06 691730 + 956 691740 Tm-174 3.30560E-07 8.05450E-07 691740 + 957 691750 Tm-175 3.71340E-07 4.57860E-07 691750 + 958 691760 Tm-176 1.51960E-07 1.72310E-07 691760 + 959 691770 Tm-177 7.19850E-08 7.33640E-08 691770 + 960 691780 Tm-178 9.64520E-09 9.64520E-09 691780 + 961 691790 Tm-179 1.78630E-09 1.78630E-09 691790 + 962 701710 Yb-171 3.55120E-12 3.53360E-06 701710 + 963 701711 Yb-171m 2.66720E-11 2.66720E-11 701711 + 964 701720 Yb-172 5.72480E-10 2.44400E-06 701720 + 965 701730 Yb-173 4.36630E-09 1.35060E-06 701730 + 966 701740 Yb-174 2.85670E-08 8.34050E-07 701740 + 967 701750 Yb-175 4.98480E-08 5.14340E-07 701750 + 968 701751 Yb-175m 6.63700E-09 3.59190E-07 701751 + 969 701760 Yb-176 4.60440E-08 2.96680E-07 701760 + 970 701761 Yb-176m 9.65960E-08 1.82750E-07 701761 + 971 701770 Yb-177 8.99330E-08 1.81410E-07 701770 + 972 701771 Yb-177m 1.81070E-08 9.14720E-08 701771 + 973 701780 Yb-178 9.00980E-08 9.97430E-08 701780 + 974 701790 Yb-179 2.97350E-08 3.15210E-08 701790 + 975 701800 Yb-180 1.17670E-08 1.17670E-08 701800 + 976 701810 Yb-181 1.25250E-09 1.25250E-09 701810 + 977 711730 Lu-173 2.49230E-12 2.49230E-12 711730 + 978 711740 Lu-174 9.59930E-12 3.56130E-11 711740 + 979 711741 Lu-174m 2.61660E-11 2.61660E-11 711741 + 980 711750 Lu-175 5.59600E-10 5.14900E-07 71175.82c + 981 711760 Lu-176 1.89720E-09 2.01730E-08 71176.82c + 982 711761 Lu-176m 9.04360E-10 9.04360E-10 711761 + 983 711770 Lu-177 9.76930E-09 1.92250E-07 711770 + 984 711771 Lu-177m 4.65170E-09 4.76740E-09 711771 + 985 711772 Lu-177m 2.31490E-10 2.31490E-10 711772 + 986 711780 Lu-178 8.84080E-09 1.08580E-07 711780 + 987 711781 Lu-178m 1.18440E-08 1.18440E-08 711781 + 988 711790 Lu-179 3.64430E-08 7.28160E-08 711790 + 989 711791 Lu-179m 4.85220E-09 3.63730E-08 711791 + 990 711800 Lu-180 6.99860E-09 2.25780E-08 711800 + 991 711801 Lu-180m 6.99860E-09 1.87660E-08 711801 + 992 711802 Lu-180m 1.23930E-08 1.23930E-08 711802 + 993 711810 Lu-181 1.80920E-08 1.93450E-08 711810 + 994 711820 Lu-182 4.22910E-09 4.22910E-09 711820 + 995 711830 Lu-183 1.35730E-09 1.35730E-09 711830 + 996 711840 Lu-184 1.14670E-10 1.14670E-10 711840 + 997 721760 Hf-176 3.92640E-12 9.07420E-10 72176.82c + 998 721770 Hf-177 2.94870E-11 1.96100E-07 72177.82c + 999 721771 Hf-177m 1.39120E-11 3.82050E-09 721771 + 1000 721772 Hf-177m 8.22510E-13 1.16570E-10 721772 + 1001 721780 Hf-178 1.55280E-10 1.20910E-07 72178.82c + 1002 721781 Hf-178m 2.89590E-10 1.21700E-08 721781 + 1003 721782 Hf-178m 3.62220E-11 3.62220E-11 721782 + 1004 721790 Hf-179 1.06290E-09 7.46560E-08 72179.82c + 1005 721791 Hf-179m 3.07560E-10 3.07560E-10 721791 + 1006 721792 Hf-179m 4.64650E-10 4.64650E-10 721792 + 1007 721800 Hf-180 2.50730E-09 4.59030E-08 72180.82c + 1008 721801 Hf-180m 5.26000E-09 1.14560E-08 721801 + 1009 721810 Hf-181 8.73560E-09 2.80800E-08 721810 + 1010 721820 Hf-182 3.96530E-09 1.16880E-08 721820 + 1011 721821 Hf-182m 8.31870E-09 8.31870E-09 721821 + 1012 721830 Hf-183 6.52010E-09 7.87740E-09 721830 + 1013 721840 Hf-184 1.19200E-09 1.24930E-09 721840 + 1014 721841 Hf-184m 2.50070E-09 2.55800E-09 721841 + 1015 721850 Hf-185 6.83850E-10 6.83850E-10 721850 + 1016 721860 Hf-186 1.63770E-10 1.63770E-10 721860 + 1017 721870 Hf-187 1.11150E-11 1.11150E-11 721870 + 1018 731790 Ta-179 3.17010E-12 4.44300E-12 731790 + 1019 731791 Ta-179m 1.20270E-12 1.27290E-12 731791 + 1020 731800 Ta-180 1.69070E-11 1.69070E-11 731800 + 1021 731801 Ta-180m 2.26500E-11 5.81650E-11 731801 + 1022 731810 Ta-181 3.31920E-10 2.84120E-08 73181.82c + 1023 731820 Ta-182 2.76510E-10 5.68150E-09 73182.82c + 1024 731821 Ta-182m 3.02040E-10 5.40500E-09 731821 + 1025 731822 Ta-182m 2.78140E-10 5.10300E-09 731822 + 1026 731830 Ta-183 2.89700E-09 1.07740E-08 731830 + 1027 731840 Ta-184 2.63780E-09 6.44520E-09 731840 + 1028 731850 Ta-185 1.85870E-09 3.65160E-09 731850 + 1029 731851 Ta-185m 1.10910E-09 1.10910E-09 731851 + 1030 731860 Ta-186 1.21650E-09 1.38030E-09 731860 + 1031 731870 Ta-187 5.76910E-10 5.88030E-10 731870 + 1032 731880 Ta-188 7.74520E-11 7.74520E-11 731880 + 1033 731890 Ta-189 1.43790E-11 1.43790E-11 731890 + 1034 741820 W-182 5.00120E-12 5.68660E-09 74182.82c + 1035 741830 W-183 7.23550E-12 1.08090E-08 74183.82c + 1036 741831 W-183m 2.74010E-11 3.93730E-10 741831 + 1037 741840 W-184 2.26780E-10 6.67190E-09 74184.82c + 1038 741850 W-185 1.18290E-10 4.10090E-09 741850 + 1039 741851 W-185m 3.30970E-10 3.30970E-10 741851 + 1040 741860 W-186 8.09100E-10 2.51750E-09 74186.82c + 1041 741861 W-186m 3.27600E-10 3.27600E-10 741861 + 1042 741870 W-187 8.61910E-10 1.44990E-09 741870 + 1043 741880 W-188 7.19970E-10 7.97420E-10 741880 + 1044 741890 W-189 2.38110E-10 2.52490E-10 741890 + 1045 741900 W-190 4.03350E-11 9.43740E-11 741900 + 1046 741901 W-190m 5.40390E-11 5.40390E-11 741901 + 1047 741910 W-191 1.00660E-11 1.00660E-11 741910 + 1048 741920 W-192 1.27000E-12 1.27000E-12 741920 + 1049 751850 Re-185 4.42590E-12 4.10530E-09 75185.82c + 1050 751860 Re-186 8.30990E-12 8.30990E-12 751860 + 1051 751861 Re-186m 1.38970E-11 1.38970E-11 751861 + 1052 751870 Re-187 1.16300E-10 1.56620E-09 75187.82c + 1053 751880 Re-188 4.41570E-11 9.61940E-10 751880 + 1054 751881 Re-188m 1.20360E-10 1.20360E-10 751881 + 1055 751890 Re-189 3.29160E-10 5.81650E-10 751890 + 1056 751900 Re-190 6.80010E-11 2.27430E-10 751900 + 1057 751901 Re-190m 1.42660E-10 1.42660E-10 751901 + 1058 751910 Re-191 1.44670E-10 1.54740E-10 751910 + 1059 751920 Re-192 3.38930E-11 3.51630E-11 751920 + 1060 751930 Re-193 1.08980E-11 1.08980E-11 751930 + 1061 761880 Os-188 3.80500E-12 9.65750E-10 761880 + 1062 761890 Os-189 3.03970E-12 5.96200E-10 761890 + 1063 761891 Os-189m 1.15110E-11 7.13230E-11 761891 + 1064 761900 Os-190 2.63740E-11 3.66740E-10 761900 + 1065 761901 Os-190m 3.53330E-11 1.12940E-10 761901 + 1066 761910 Os-191 5.50040E-11 2.24270E-10 761910 + 1067 761911 Os-191m 1.45250E-11 1.45250E-11 761911 + 1068 761920 Os-192 4.18800E-11 1.26530E-10 761920 + 1069 761921 Os-192m 5.61070E-11 5.61070E-11 761921 + 1070 761930 Os-193 5.20990E-11 6.29970E-11 761930 + 1071 761940 Os-194 2.95460E-11 2.95460E-11 761940 + 1072 761950 Os-195 5.48450E-12 5.48450E-12 761950 + 1073 761960 Os-196 1.31670E-12 1.31670E-12 761960 + 1074 771910 Ir-191 6.91900E-13 2.26890E-10 77191.82c + 1075 771911 Ir-191m 1.44560E-12 1.07790E-10 771911 + 1076 771920 Ir-192 2.26610E-12 1.40920E-11 771920 + 1077 771921 Ir-192m 2.26610E-12 2.26610E-12 771921 + 1078 771922 Ir-192m 2.26610E-12 9.56000E-12 771922 + 1079 771930 Ir-193 6.06620E-12 8.60360E-11 77193.82c + 1080 771931 Ir-193m 1.69730E-11 1.71920E-11 771931 + 1081 771940 Ir-194 7.00230E-12 4.35510E-11 771940 + 1082 771941 Ir-194m 7.00230E-12 7.00230E-12 771941 + 1083 771942 Ir-194m 7.00230E-12 7.00230E-12 771942 + 1084 771950 Ir-195 6.23810E-12 1.25950E-11 771950 + 1085 771951 Ir-195m 1.74540E-11 1.74540E-11 771951 + 1086 771960 Ir-196 4.86540E-12 6.19670E-12 771960 + 1087 771961 Ir-196m 4.86540E-12 4.86540E-12 771961 + 1088 771970 Ir-197 1.21690E-12 1.22540E-12 771970 + 1089 771971 Ir-197m 3.40470E-12 3.40470E-12 771971 + 1090 781940 Pt-194 1.79690E-12 5.23500E-11 781940 + 1091 781950 Pt-195 9.39770E-13 3.27460E-11 781950 + 1092 781951 Pt-195m 2.62940E-12 7.93540E-12 781951 + 1093 781960 Pt-196 9.05060E-12 2.00980E-11 781960 + 1094 781970 Pt-197 1.80950E-12 1.12150E-11 781970 + 1095 781971 Pt-197m 5.06290E-12 8.45910E-12 781971 + 1096 781980 Pt-198 5.75120E-12 5.75120E-12 781980 + 1097 781990 Pt-199 7.00720E-13 1.90640E-12 781990 + 1098 781991 Pt-199m 1.20570E-12 1.20570E-12 781991 + 1099 791980 Au-198 8.19520E-13 1.30810E-12 791980 + 1100 791990 Au-199 2.62310E-12 4.52950E-12 791990 + 1101 792000 Au-200 9.80370E-13 1.10650E-12 792000 + + Spontaneous fission: + + Decay constant : 1.22025E-09 + SF decay fraction : 1.38000E-06 + Number of products : 1080 / 1134 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 4.57150E-05 4.57150E-05 1001.82c + 2 10020 H-2 1.39710E-05 1.39710E-05 1002.82c + 3 10030 H-3 1.86000E-04 1.86000E-04 1003.82c + 4 20040 He-4 2.89000E-03 2.89000E-03 2004.82c + 5 200520 Ca-52 1.04610E-12 1.04610E-12 200520 + 6 210520 Sc-52 3.27920E-12 4.30440E-12 210520 + 7 210530 Sc-53 4.75530E-12 4.75530E-12 210530 + 8 210540 Sc-54 3.20850E-12 3.20850E-12 210540 + 9 210550 Sc-55 2.02030E-12 2.02030E-12 210550 + 10 220520 Ti-52 1.63030E-12 5.93470E-12 220520 + 11 220530 Ti-53 5.57860E-12 1.03340E-11 220530 + 12 220540 Ti-54 1.49710E-11 1.81800E-11 220540 + 13 220550 Ti-55 2.32970E-11 2.53170E-11 220550 + 14 220560 Ti-56 2.91800E-11 2.91800E-11 220560 + 15 220570 Ti-57 1.67660E-11 1.67660E-11 220570 + 16 220580 Ti-58 7.02220E-12 7.02220E-12 220580 + 17 220590 Ti-59 1.38490E-12 1.38490E-12 220590 + 18 230540 V-54 1.71910E-12 1.98990E-11 230540 + 19 230550 V-55 1.08680E-11 3.61850E-11 230550 + 20 230560 V-56 3.18580E-11 6.10880E-11 230560 + 21 230570 V-57 7.43430E-11 9.10590E-11 230570 + 22 230580 V-58 7.99780E-11 8.70000E-11 230580 + 23 230590 V-59 7.37920E-11 7.51770E-11 230590 + 24 230600 V-60 3.11750E-11 3.11750E-11 230600 + 25 230610 V-61 1.12830E-11 1.12830E-11 230610 + 26 230620 V-62 1.70920E-12 1.70920E-12 230620 + 27 240560 Cr-56 5.35360E-12 6.68060E-11 240560 + 28 240570 Cr-57 3.08860E-11 1.91180E-10 240570 + 29 240580 Cr-58 1.32180E-10 1.49580E-10 240580 + 30 240590 Cr-59 2.87710E-10 3.62890E-10 240590 + 31 240600 Cr-60 5.09970E-10 5.41820E-10 240600 + 32 240610 Cr-61 4.93890E-10 5.04500E-10 240610 + 33 240620 Cr-62 3.62880E-10 3.64590E-10 240620 + 34 240630 Cr-63 1.12800E-10 1.12800E-10 240630 + 35 240640 Cr-64 2.55750E-11 2.55750E-11 240640 + 36 240650 Cr-65 3.01280E-12 3.01280E-12 240650 + 37 250580 Mn-58 4.46970E-12 1.54050E-10 250580 + 38 250590 Mn-59 4.67310E-11 4.09620E-10 250590 + 39 250600 Mn-60 2.00860E-11 5.82420E-10 250600 + 40 250601 Mn-60m 1.78390E-10 1.78390E-10 250601 + 41 250610 Mn-61 7.60080E-10 1.26460E-09 250610 + 42 250620 Mn-62 1.14270E-09 1.32500E-09 250620 + 43 250621 Mn-62m 2.05140E-10 3.87430E-10 250621 + 44 250630 Mn-63 1.82790E-09 1.94070E-09 250630 + 45 250640 Mn-64 1.15360E-09 1.17920E-09 250640 + 46 250650 Mn-65 6.80010E-10 6.83020E-10 250650 + 47 250660 Mn-66 1.76140E-10 1.76140E-10 250660 + 48 250670 Mn-67 3.21890E-11 3.21890E-11 250670 + 49 250680 Mn-68 2.40400E-12 2.40400E-12 250680 + 50 260600 Fe-60 1.05750E-11 7.50880E-10 260600 + 51 260610 Fe-61 1.07220E-10 1.37180E-09 260610 + 52 260620 Fe-62 7.90270E-10 2.50270E-09 260620 + 53 260630 Fe-63 2.51940E-09 4.46010E-09 260630 + 54 260640 Fe-64 6.35140E-09 7.53060E-09 260640 + 55 260650 Fe-65 9.34450E-09 1.00270E-08 260650 + 56 260660 Fe-66 1.10020E-08 1.11780E-08 260660 + 57 260670 Fe-67 5.79890E-09 5.83110E-09 260670 + 58 260680 Fe-68 2.22380E-09 2.22620E-09 260680 + 59 260690 Fe-69 4.10000E-10 4.10000E-10 260690 + 60 260700 Fe-70 5.47820E-11 5.47820E-11 260700 + 61 260710 Fe-71 3.46450E-12 3.46450E-12 260710 + 62 270620 Co-62 2.73080E-12 2.50540E-09 270620 + 63 270621 Co-62m 6.39610E-12 6.39610E-12 270621 + 64 270630 Co-63 1.34760E-10 4.59490E-09 270630 + 65 270640 Co-64 8.63580E-10 8.39420E-09 270640 + 66 270650 Co-65 5.12530E-09 1.51530E-08 270650 + 67 270660 Co-66 1.41320E-08 2.53100E-08 270660 + 68 270670 Co-67 3.04880E-08 3.63190E-08 270670 + 69 270680 Co-68 1.61330E-08 2.43760E-08 270680 + 70 270681 Co-68m 1.42320E-08 1.64870E-08 270681 + 71 270690 Co-69 2.64600E-08 2.68410E-08 270690 + 72 270700 Co-70 5.25500E-09 5.25500E-09 270700 + 73 270701 Co-70m 5.25500E-09 5.30980E-09 270701 + 74 270710 Co-71 3.48760E-09 3.49110E-09 270710 + 75 270720 Co-72 4.81120E-10 4.81120E-10 270720 + 76 270730 Co-73 4.54810E-11 4.54810E-11 270730 + 77 270740 Co-74 1.81240E-12 1.81240E-12 270740 + 78 280640 Ni-64 1.37070E-11 8.40790E-09 28064.82c + 79 280650 Ni-65 2.30400E-10 1.53830E-08 280650 + 80 280660 Ni-66 2.82550E-09 2.81360E-08 280660 + 81 280670 Ni-67 1.49300E-08 5.12490E-08 280670 + 82 280680 Ni-68 5.89610E-08 9.18490E-08 280680 + 83 280690 Ni-69 6.08950E-08 8.74680E-08 280690 + 84 280691 Ni-69m 6.08950E-08 6.08950E-08 280691 + 85 280700 Ni-70 2.05030E-07 2.15590E-07 280700 + 86 280710 Ni-71 1.84080E-07 1.87570E-07 280710 + 87 280720 Ni-72 1.24270E-07 1.24750E-07 280720 + 88 280730 Ni-73 3.58190E-08 3.58650E-08 280730 + 89 280740 Ni-74 7.53200E-09 7.53380E-09 280740 + 90 280750 Ni-75 8.22170E-10 8.22170E-10 280750 + 91 280760 Ni-76 6.34070E-11 6.34070E-11 280760 + 92 280770 Ni-77 2.17850E-12 2.17850E-12 280770 + 93 290660 Cu-66 9.46710E-12 2.81450E-08 290660 + 94 290670 Cu-67 2.46350E-10 5.14950E-08 290670 + 95 290680 Cu-68 7.93810E-10 9.42050E-08 290680 + 96 290681 Cu-68m 1.85930E-09 1.85930E-09 290681 + 97 290690 Cu-69 2.34070E-08 1.71770E-07 290690 + 98 290700 Cu-70 7.13860E-09 5.24710E-08 290700 + 99 290701 Cu-70m 7.95280E-08 9.06640E-08 290701 + 100 290702 Cu-70m 7.13860E-09 2.22730E-07 290702 + 101 290710 Cu-71 3.33400E-07 5.20970E-07 290710 + 102 290720 Cu-72 5.47690E-07 6.72440E-07 290720 + 103 290730 Cu-73 6.96440E-07 7.32300E-07 290730 + 104 290740 Cu-74 4.11790E-07 4.19340E-07 290740 + 105 290750 Cu-75 2.26570E-07 2.27380E-07 290750 + 106 290760 Cu-76 2.71790E-08 2.72100E-08 290760 + 107 290761 Cu-76m 2.71790E-08 2.72100E-08 290761 + 108 290770 Cu-77 9.00170E-09 9.00390E-09 290770 + 109 290780 Cu-78 6.06760E-10 6.06760E-10 290780 + 110 290790 Cu-79 9.16150E-12 9.16150E-12 290790 + 111 300680 Zn-68 1.19430E-11 9.45140E-08 300680 + 112 300690 Zn-69 5.91380E-11 1.72080E-07 300690 + 113 300691 Zn-69m 2.55760E-10 2.55760E-10 300691 + 114 300700 Zn-70 6.00810E-09 3.15410E-07 300700 + 115 300710 Zn-71 1.05000E-08 5.31470E-07 300710 + 116 300711 Zn-71m 4.54110E-08 4.54110E-08 300711 + 117 300720 Zn-72 3.78310E-07 1.05080E-06 300720 + 118 300730 Zn-73 1.11540E-07 1.42820E-06 300730 + 119 300731 Zn-73m 1.52480E-07 5.84370E-07 300731 + 120 300732 Zn-73m 8.63780E-07 8.63780E-07 300732 + 121 300740 Zn-74 2.67800E-06 3.10530E-06 300740 + 122 300750 Zn-75 3.71640E-06 3.93660E-06 300750 + 123 300760 Zn-76 4.09720E-06 4.15080E-06 300760 + 124 300770 Zn-77 1.71240E-06 1.85230E-06 300770 + 125 300771 Zn-77m 2.61780E-07 2.61780E-07 300771 + 126 300780 Zn-78 6.87730E-07 6.88340E-07 300780 + 127 300790 Zn-79 3.25530E-08 3.25570E-08 300790 + 128 300800 Zn-80 2.34430E-08 2.34430E-08 300800 + 129 300810 Zn-81 9.59920E-10 9.59920E-10 300810 + 130 300820 Zn-82 3.07940E-11 3.07940E-11 300820 + 131 310700 Ga-70 5.59830E-12 5.59830E-12 310700 + 132 310710 Ga-71 2.68700E-10 5.77150E-07 310710 + 133 310720 Ga-72 4.74360E-09 1.05600E-06 310720 + 134 310721 Ga-72m 5.34100E-10 3.55460E-08 310721 + 135 310730 Ga-73 7.20920E-08 1.93220E-06 310730 + 136 310740 Ga-74 2.15260E-07 2.70570E-06 310740 + 137 310741 Ga-74m 2.15260E-07 3.32060E-06 310741 + 138 310750 Ga-75 2.39550E-06 6.33210E-06 310750 + 139 310760 Ga-76 6.19490E-06 1.03460E-05 310760 + 140 310770 Ga-77 1.23260E-05 1.43090E-05 310770 + 141 310780 Ga-78 1.12780E-05 1.19670E-05 310780 + 142 310790 Ga-79 2.54790E-06 2.58000E-06 310790 + 143 310800 Ga-80 5.49530E-06 5.51880E-06 310800 + 144 310810 Ga-81 1.18530E-06 1.18620E-06 310810 + 145 310820 Ga-82 1.19720E-07 1.19750E-07 310820 + 146 310830 Ga-83 1.62230E-08 1.62230E-08 310830 + 147 310840 Ga-84 4.60190E-10 4.60190E-10 310840 + 148 320720 Ge-72 6.51640E-12 1.05600E-06 32072.82c + 149 320730 Ge-73 2.24100E-10 1.93250E-06 32073.82c + 150 320731 Ge-73m 5.18180E-11 1.90390E-06 320731 + 151 320740 Ge-74 8.28940E-09 3.54410E-06 32074.82c + 152 320750 Ge-75 1.71520E-08 6.46140E-06 320750 + 153 320751 Ge-75m 1.12200E-07 3.65480E-07 320751 + 154 320760 Ge-76 1.47140E-06 1.18170E-05 32076.82c + 155 320770 Ge-77 6.16360E-06 9.06130E-06 320770 + 156 320771 Ge-77m 9.42230E-07 1.52510E-05 320771 + 157 320780 Ge-78 2.57240E-05 3.76930E-05 320780 + 158 320790 Ge-79 1.83840E-06 4.89340E-06 320790 + 159 320791 Ge-79m 1.20260E-05 1.20300E-05 320791 + 160 320800 Ge-80 6.65730E-05 7.22330E-05 320800 + 161 320810 Ge-81 8.46310E-05 8.53970E-05 320810 + 162 320811 Ge-81m 1.95690E-05 2.00750E-05 320811 + 163 320820 Ge-82 1.02770E-04 1.02870E-04 320820 + 164 320830 Ge-83 1.56760E-05 1.56860E-05 320830 + 165 320840 Ge-84 2.44560E-06 2.44570E-06 320840 + 166 320850 Ge-85 1.65230E-07 1.65230E-07 320850 + 167 320860 Ge-86 8.17160E-09 8.17160E-09 320860 + 168 320870 Ge-87 1.07780E-10 1.07780E-10 320870 + 169 330740 As-74 2.11450E-12 2.11450E-12 330740 + 170 330750 As-75 4.06000E-11 6.46170E-06 33075.82c + 171 330751 As-75m 1.32830E-10 2.42470E-10 330751 + 172 330760 As-76 6.00290E-09 6.00290E-09 330760 + 173 330770 As-77 1.41550E-07 2.15570E-05 330770 + 174 330780 As-78 1.38240E-06 3.90760E-05 330780 + 175 330790 As-79 1.88980E-05 3.53400E-05 330790 + 176 330800 As-80 1.32810E-04 2.05040E-04 330800 + 177 330810 As-81 1.03880E-04 2.09150E-04 330810 + 178 330820 As-82 1.69960E-05 1.19870E-04 330820 + 179 330821 As-82m 5.12880E-05 5.12880E-05 330821 + 180 330830 As-83 1.73800E-04 1.89750E-04 330830 + 181 330840 As-84 3.75710E-05 3.86730E-05 330840 + 182 330841 As-84m 3.75710E-05 3.86730E-05 330841 + 183 330850 As-85 5.58860E-05 5.60280E-05 330850 + 184 330860 As-86 8.63210E-06 8.64030E-06 330860 + 185 330870 As-87 8.85190E-07 8.85300E-07 330870 + 186 330880 As-88 4.73350E-08 4.73350E-08 330880 + 187 330890 As-89 1.85190E-09 1.85190E-09 330890 + 188 340760 Se-76 1.85130E-12 6.00480E-09 34076.82c + 189 340770 Se-77 1.97390E-11 2.15570E-05 34077.82c + 190 340771 Se-77m 1.29120E-10 1.29120E-10 340771 + 191 340780 Se-78 7.59810E-09 3.90830E-05 34078.82c + 192 340790 Se-79 4.45320E-08 3.53720E-05 34079.82c + 193 340791 Se-79m 6.80770E-09 3.45090E-05 340791 + 194 340800 Se-80 5.29030E-06 2.10330E-04 34080.82c + 195 340810 Se-81 9.16600E-06 2.78240E-04 340810 + 196 340811 Se-81m 5.99590E-05 6.74670E-05 340811 + 197 340820 Se-82 2.37700E-04 4.08850E-04 34082.82c + 198 340830 Se-83 7.28060E-04 7.96430E-04 340830 + 199 340831 Se-83m 1.68350E-04 2.89840E-04 340831 + 200 340840 Se-84 1.08940E-03 1.17900E-03 340840 + 201 340850 Se-85 1.17950E-03 1.22610E-03 340850 + 202 340860 Se-86 8.29140E-04 8.35060E-04 340860 + 203 340870 Se-87 2.96470E-04 2.97220E-04 340870 + 204 340880 Se-88 7.03600E-05 7.04070E-05 340880 + 205 340890 Se-89 8.14860E-06 8.15040E-06 340890 + 206 340900 Se-90 5.91980E-07 5.91980E-07 340900 + 207 340910 Se-91 1.61380E-08 1.61380E-08 340910 + 208 340920 Se-92 4.62760E-10 4.62760E-10 340920 + 209 350790 Br-79 4.40860E-12 1.93440E-08 35079.82c + 210 350791 Br-79m 1.44230E-11 1.44230E-11 350791 + 211 350800 Br-80 1.50320E-09 6.03940E-09 350800 + 212 350801 Br-80m 4.53620E-09 4.53620E-09 350801 + 213 350810 Br-81 1.87600E-07 2.78460E-04 35081.82c + 214 350820 Br-82 1.89100E-06 2.67900E-06 350820 + 215 350821 Br-82m 8.07360E-07 8.07360E-07 350821 + 216 350830 Br-83 3.45730E-05 1.12080E-03 350830 + 217 350840 Br-84 1.48510E-04 1.32750E-03 350840 + 218 350841 Br-84m 1.48510E-04 1.48510E-04 350841 + 219 350850 Br-85 7.81120E-04 2.00720E-03 350850 + 220 350860 Br-86 1.00270E-03 1.83780E-03 350860 + 221 350870 Br-87 1.03680E-03 1.33470E-03 350870 + 222 350880 Br-88 7.41170E-04 8.11520E-04 350880 + 223 350890 Br-89 6.45500E-04 6.53010E-04 350890 + 224 350900 Br-90 2.26420E-04 2.27020E-04 350900 + 225 350910 Br-91 8.41790E-05 8.41920E-05 350910 + 226 350920 Br-92 2.36890E-06 2.36940E-06 350920 + 227 350930 Br-93 1.37400E-05 1.37400E-05 350930 + 228 350940 Br-94 3.19750E-09 3.19750E-09 350940 + 229 360810 Kr-81 4.75780E-11 5.48510E-11 360810 + 230 360811 Kr-81m 7.27320E-12 7.27320E-12 360811 + 231 360820 Kr-82 4.08020E-09 2.70250E-06 36082.82c + 232 360830 Kr-83 2.01600E-07 1.12110E-03 36083.82c + 233 360831 Kr-83m 4.66140E-08 1.11990E-03 360831 + 234 360840 Kr-84 3.76150E-05 1.51360E-03 36084.82c + 235 360850 Kr-85 3.78920E-05 4.71870E-04 36085.82c + 236 360851 Kr-85m 8.76160E-06 2.01270E-03 360851 + 237 360860 Kr-86 8.38000E-04 2.70930E-03 36086.82c + 238 360870 Kr-87 1.92420E-03 3.27980E-03 360870 + 239 360880 Kr-88 4.03600E-03 4.88520E-03 360880 + 240 360890 Kr-89 4.91700E-03 5.53380E-03 360890 + 241 360900 Kr-90 3.88410E-03 4.07210E-03 360900 + 242 360910 Kr-91 1.95950E-03 2.02760E-03 360910 + 243 360920 Kr-92 1.02170E-03 1.03260E-03 360920 + 244 360930 Kr-93 2.66210E-04 2.70610E-04 360930 + 245 360940 Kr-94 7.70940E-05 7.70950E-05 360940 + 246 360950 Kr-95 8.44500E-07 8.44500E-07 360950 + 247 360960 Kr-96 4.89920E-08 4.89920E-08 360960 + 248 360970 Kr-97 1.01900E-09 1.01900E-09 360970 + 249 370830 Rb-83 8.73490E-12 2.98220E-11 370830 + 250 370831 Rb-83m 2.10870E-11 2.10870E-11 370831 + 251 370840 Rb-84 6.07120E-10 1.69920E-09 370840 + 252 370841 Rb-84m 1.09210E-09 1.09210E-09 370841 + 253 370850 Rb-85 8.78140E-08 2.05390E-03 37085.82c + 254 370860 Rb-86 6.99810E-07 1.95860E-06 37086.82c + 255 370861 Rb-86m 1.25880E-06 1.25880E-06 370861 + 256 370870 Rb-87 7.73270E-05 3.35710E-03 37087.82c + 257 370880 Rb-88 2.32760E-04 5.11800E-03 370880 + 258 370890 Rb-89 1.31960E-03 6.85340E-03 370890 + 259 370900 Rb-90 2.83750E-04 3.90260E-03 370900 + 260 370901 Rb-90m 2.52010E-03 3.05270E-03 370901 + 261 370910 Rb-91 3.91470E-03 5.94230E-03 370910 + 262 370920 Rb-92 4.44460E-03 5.47720E-03 370920 + 263 370930 Rb-93 4.33720E-03 4.60870E-03 370930 + 264 370940 Rb-94 1.64820E-03 1.72450E-03 370940 + 265 370950 Rb-95 5.40240E-04 5.41060E-04 370950 + 266 370960 Rb-96 8.00200E-05 1.20060E-04 370960 + 267 370961 Rb-96m 8.00200E-05 8.00440E-05 370961 + 268 370970 Rb-97 1.38460E-05 1.38470E-05 370970 + 269 370980 Rb-98 1.51610E-07 1.51610E-07 370980 + 270 370981 Rb-98m 1.51610E-07 1.51610E-07 370981 + 271 370990 Rb-99 5.93500E-09 5.93500E-09 370990 + 272 380860 Sr-86 8.17150E-10 1.95930E-06 38086.82c + 273 380870 Sr-87 2.99390E-08 3.68400E-08 38087.82c + 274 380871 Sr-87m 6.92250E-09 6.92250E-09 380871 + 275 380880 Sr-88 3.57250E-05 5.15370E-03 38088.82c + 276 380890 Sr-89 8.22110E-05 6.93560E-03 38089.82c + 277 380900 Sr-90 9.38660E-04 7.81460E-03 38090.82c + 278 380910 Sr-91 2.13000E-03 8.07230E-03 380910 + 279 380920 Sr-92 6.74360E-03 1.22850E-02 380920 + 280 380930 Sr-93 9.69290E-03 1.44110E-02 380930 + 281 380940 Sr-94 1.41780E-02 1.57750E-02 380940 + 282 380950 Sr-95 8.21850E-03 8.72910E-03 380950 + 283 380960 Sr-96 8.21680E-03 8.36430E-03 380960 + 284 380970 Sr-97 3.07640E-03 3.08680E-03 380970 + 285 380980 Sr-98 1.08910E-03 1.08940E-03 380980 + 286 380990 Sr-99 1.46780E-04 1.46780E-04 380990 + 287 381000 Sr-100 4.10850E-05 4.10850E-05 381000 + 288 381010 Sr-101 7.39600E-08 7.39600E-08 381010 + 289 381020 Sr-102 2.68880E-09 2.68880E-09 381020 + 290 390880 Y-88 6.42770E-11 1.11650E-10 390880 + 291 390881 Y-88m 4.73730E-11 4.73730E-11 390881 + 292 390890 Y-89 2.22580E-09 6.93560E-03 39089.82c + 293 390891 Y-89m 9.62620E-09 6.78150E-07 390891 + 294 390900 Y-90 7.15180E-06 7.83190E-03 39090.82c + 295 390901 Y-90m 1.01480E-05 1.01480E-05 390901 + 296 390910 Y-91 8.62410E-06 8.11830E-03 39091.82c + 297 390911 Y-91m 3.72980E-05 4.78670E-03 390911 + 298 390920 Y-92 2.33910E-04 1.25190E-02 390920 + 299 390930 Y-93 1.85710E-04 1.58120E-02 390930 + 300 390931 Y-93m 1.21480E-03 4.82110E-03 390931 + 301 390940 Y-94 3.03280E-03 1.88080E-02 390940 + 302 390950 Y-95 6.28300E-03 1.50120E-02 390950 + 303 390960 Y-96 4.30080E-03 1.26660E-02 390960 + 304 390961 Y-96m 7.73620E-03 7.73700E-03 390961 + 305 390970 Y-97 2.53530E-03 5.23820E-03 390970 + 306 390971 Y-97m 8.64140E-03 1.09580E-02 390971 + 307 390972 Y-97m 2.32200E-03 2.32200E-03 390972 + 308 390980 Y-98 2.26350E-03 3.35290E-03 390980 + 309 390981 Y-98m 9.51950E-03 9.51950E-03 390981 + 310 390990 Y-99 4.35270E-03 4.49980E-03 390990 + 311 391000 Y-100 1.01370E-03 1.05440E-03 391000 + 312 391001 Y-100m 1.01370E-03 1.01370E-03 391001 + 313 391010 Y-101 7.67740E-04 7.67810E-04 391010 + 314 391020 Y-102 5.23450E-05 5.23460E-05 391020 + 315 391021 Y-102m 5.23450E-05 5.23460E-05 391021 + 316 391030 Y-103 3.67920E-07 3.67920E-07 391030 + 317 391040 Y-104 7.72330E-09 7.72330E-09 391040 + 318 400910 Zr-91 2.64560E-09 8.11830E-03 40091.82c + 319 400920 Zr-92 2.03620E-07 1.25190E-02 40092.82c + 320 400930 Zr-93 4.81550E-05 1.58600E-02 40093.82c + 321 400940 Zr-94 4.43850E-04 1.92520E-02 40094.82c + 322 400950 Zr-95 1.29830E-03 1.63100E-02 40095.82c + 323 400960 Zr-96 7.78980E-03 2.82010E-02 40096.82c + 324 400970 Zr-97 1.34970E-02 3.04090E-02 400970 + 325 400980 Zr-98 3.37870E-02 4.63990E-02 400980 + 326 400990 Zr-99 2.37690E-02 2.82020E-02 400990 + 327 401000 Zr-100 3.14150E-02 3.34730E-02 401000 + 328 401010 Zr-101 1.55970E-02 1.63700E-02 401010 + 329 401020 Zr-102 7.36610E-03 7.46570E-03 401020 + 330 401030 Zr-103 1.67790E-03 1.67820E-03 401030 + 331 401040 Zr-104 4.78940E-04 4.78950E-04 401040 + 332 401050 Zr-105 4.11950E-05 4.11950E-05 401050 + 333 401060 Zr-106 7.27870E-08 7.27870E-08 401060 + 334 410930 Nb-93 6.86970E-10 8.45820E-10 41093.82c + 335 410931 Nb-93m 1.58850E-10 1.58850E-10 410931 + 336 410940 Nb-94 2.22400E-08 3.78350E-08 41094.82c + 337 410941 Nb-94m 1.56730E-08 1.56730E-08 410941 + 338 410950 Nb-95 3.87400E-06 1.63050E-02 41095.82c + 339 410951 Nb-95m 8.95750E-07 1.77100E-04 410951 + 340 410960 Nb-96 1.01770E-04 1.01770E-04 410960 + 341 410970 Nb-97 5.78530E-04 3.11210E-02 410970 + 342 410971 Nb-97m 1.33770E-04 2.90370E-02 410971 + 343 410980 Nb-98 8.51710E-04 4.72510E-02 410980 + 344 410981 Nb-98m 2.57020E-03 2.57020E-03 410981 + 345 410990 Nb-99 6.26030E-03 2.43200E-02 410990 + 346 410991 Nb-99m 1.44750E-03 1.18260E-02 410991 + 347 411000 Nb-100 3.59670E-03 3.70700E-02 411000 + 348 411001 Nb-100m 1.51260E-02 1.51260E-02 411001 + 349 411010 Nb-101 3.35480E-02 4.99180E-02 411010 + 350 411020 Nb-102 1.43580E-02 2.18230E-02 411020 + 351 411021 Nb-102m 1.43580E-02 1.43580E-02 411021 + 352 411030 Nb-103 2.18440E-02 2.35220E-02 411030 + 353 411040 Nb-104 5.44450E-03 5.92400E-03 411040 + 354 411041 Nb-104m 5.44450E-03 5.44450E-03 411041 + 355 411050 Nb-105 5.26930E-03 5.30990E-03 411050 + 356 411060 Nb-106 1.17120E-03 1.17130E-03 411060 + 357 411070 Nb-107 1.79000E-04 1.79000E-04 411070 + 358 411080 Nb-108 1.75940E-07 1.75940E-07 411080 + 359 411090 Nb-109 3.85710E-09 3.85710E-09 411090 + 360 420960 Mo-96 1.49100E-08 1.01790E-04 42096.82c + 361 420970 Mo-97 2.07650E-05 3.11420E-02 42097.82c + 362 420980 Mo-98 1.67170E-04 4.99880E-02 42098.82c + 363 420990 Mo-99 8.14430E-04 3.67240E-02 42099.82c + 364 421000 Mo-100 5.25500E-03 5.74510E-02 42100.82c + 365 421010 Mo-101 1.39680E-02 6.38860E-02 421010 + 366 421020 Mo-102 3.30100E-02 6.91910E-02 421020 + 367 421030 Mo-103 3.82500E-02 6.17790E-02 421030 + 368 421040 Mo-104 5.31790E-02 6.46310E-02 421040 + 369 421050 Mo-105 4.24610E-02 4.77330E-02 421050 + 370 421060 Mo-106 2.39510E-02 2.50800E-02 421060 + 371 421070 Mo-107 6.58980E-03 6.75810E-03 421070 + 372 421080 Mo-108 2.47850E-03 2.47870E-03 421080 + 373 421090 Mo-109 5.04790E-04 5.04790E-04 421090 + 374 421100 Mo-110 7.40180E-05 7.40180E-05 421100 + 375 421110 Mo-111 1.83180E-08 1.83180E-08 421110 + 376 430980 Tc-98 2.37810E-09 2.37810E-09 430980 + 377 430990 Tc-99 8.75630E-08 3.67230E-02 43099.82c + 378 430991 Tc-99m 2.02470E-08 3.23390E-02 430991 + 379 431000 Tc-100 3.08080E-05 3.08080E-05 431000 + 380 431010 Tc-101 4.44070E-04 6.43300E-02 431010 + 381 431020 Tc-102 8.57950E-04 7.00490E-02 431020 + 382 431021 Tc-102m 8.57950E-04 8.57950E-04 431021 + 383 431030 Tc-103 6.47240E-03 6.82510E-02 431030 + 384 431040 Tc-104 1.42430E-02 7.88750E-02 431040 + 385 431050 Tc-105 3.56890E-02 8.34220E-02 431050 + 386 431060 Tc-106 3.05940E-02 5.56740E-02 431060 + 387 431070 Tc-107 2.68470E-02 3.36050E-02 431070 + 388 431080 Tc-108 1.58070E-02 1.82880E-02 431080 + 389 431090 Tc-109 1.09160E-02 1.14180E-02 431090 + 390 431100 Tc-110 3.36650E-03 3.44050E-03 431100 + 391 431110 Tc-111 1.08870E-03 1.08870E-03 431110 + 392 431120 Tc-112 1.03650E-04 1.03650E-04 431120 + 393 431130 Tc-113 2.71730E-05 2.71730E-05 431130 + 394 431140 Tc-114 1.82620E-10 1.82620E-10 431140 + 395 441010 Ru-101 4.01490E-08 6.43300E-02 44101.82c + 396 441020 Ru-102 5.81500E-05 7.09650E-02 44102.82c + 397 441030 Ru-103 8.68860E-05 6.85480E-02 44103.82c + 398 441031 Ru-103m 2.09750E-04 2.09750E-04 441031 + 399 441040 Ru-104 1.66850E-03 8.05430E-02 44104.82c + 400 441050 Ru-105 6.00390E-03 8.94260E-02 44105.82c + 401 441060 Ru-106 1.47700E-02 7.04440E-02 44106.82c + 402 441070 Ru-107 1.88400E-02 5.24450E-02 441070 + 403 441080 Ru-108 2.88120E-02 4.71090E-02 441080 + 404 441090 Ru-109 2.91850E-02 4.05950E-02 441090 + 405 441100 Ru-110 2.04950E-02 2.39340E-02 441100 + 406 441110 Ru-111 1.13920E-02 1.24820E-02 441110 + 407 441120 Ru-112 5.11330E-03 5.21730E-03 441120 + 408 441130 Ru-113 2.87040E-04 4.55780E-04 441130 + 409 441131 Ru-113m 2.87040E-04 2.87040E-04 441131 + 410 441140 Ru-114 8.22370E-05 8.22370E-05 441140 + 411 441150 Ru-115 4.63390E-08 4.63390E-08 441150 + 412 441160 Ru-116 3.25320E-10 3.25320E-10 441160 + 413 451030 Rh-103 7.42930E-10 6.85480E-02 45103.82c + 414 451031 Rh-103m 4.85990E-09 6.77270E-02 451031 + 415 451040 Rh-104 2.97440E-06 1.19380E-05 451040 + 416 451041 Rh-104m 8.97560E-06 8.97560E-06 451041 + 417 451050 Rh-105 1.07230E-04 8.95500E-02 45105.82c + 418 451051 Rh-105m 1.63920E-05 2.54020E-02 451051 + 419 451060 Rh-106 1.33180E-04 7.05780E-02 451060 + 420 451061 Rh-106m 3.11930E-04 3.11930E-04 451061 + 421 451070 Rh-107 1.01500E-03 5.34600E-02 451070 + 422 451080 Rh-108 6.14680E-04 4.77240E-02 451080 + 423 451081 Rh-108m 1.85490E-03 1.85490E-03 451081 + 424 451090 Rh-109 7.14230E-03 4.77380E-02 451090 + 425 451100 Rh-110 8.27410E-03 3.22080E-02 451100 + 426 451101 Rh-110m 2.20870E-04 2.20870E-04 451101 + 427 451110 Rh-111 1.28910E-02 2.53730E-02 451110 + 428 451120 Rh-112 4.99040E-03 1.02080E-02 451120 + 429 451121 Rh-112m 4.99040E-03 4.99040E-03 451121 + 430 451130 Rh-113 3.92480E-03 4.52410E-03 451130 + 431 451140 Rh-114 8.09450E-04 8.91690E-04 451140 + 432 451141 Rh-114m 8.09450E-04 8.09450E-04 451141 + 433 451150 Rh-115 6.10540E-04 6.10590E-04 451150 + 434 451160 Rh-116 4.78570E-05 4.78570E-05 451160 + 435 451161 Rh-116m 1.12090E-04 1.12090E-04 451161 + 436 451170 Rh-117 8.96420E-09 8.96420E-09 451170 + 437 451180 Rh-118 6.06060E-11 6.06060E-11 451180 + 438 451190 Rh-119 1.99090E-12 1.99090E-12 451190 + 439 461060 Pd-106 6.73970E-08 7.08890E-02 46106.82c + 440 461070 Pd-107 6.21320E-06 5.34780E-02 46107.82c + 441 461071 Pd-107m 1.16770E-05 1.16770E-05 461071 + 442 461080 Pd-108 5.31380E-05 4.96320E-02 46108.82c + 443 461090 Pd-109 1.22480E-04 4.80900E-02 461090 + 444 461091 Pd-109m 2.30170E-04 2.40990E-02 461091 + 445 461100 Pd-110 1.22080E-03 3.36500E-02 46110.82c + 446 461110 Pd-111 8.81200E-04 2.74360E-02 461110 + 447 461111 Pd-111m 1.65610E-03 1.75760E-03 461111 + 448 461120 Pd-112 4.20230E-03 1.94000E-02 461120 + 449 461130 Pd-113 8.54210E-04 7.44050E-03 461130 + 450 461131 Pd-113m 2.06220E-03 2.06220E-03 461131 + 451 461140 Pd-114 2.32360E-03 4.02470E-03 461140 + 452 461150 Pd-115 5.15460E-04 1.12200E-03 461150 + 453 461151 Pd-115m 9.68740E-04 1.05740E-03 461151 + 454 461160 Pd-116 3.33190E-04 4.93140E-04 461160 + 455 461170 Pd-117 1.23420E-05 3.55460E-05 461170 + 456 461171 Pd-117m 2.31950E-05 2.31950E-05 461171 + 457 461180 Pd-118 1.55700E-07 1.55760E-07 461180 + 458 461190 Pd-119 1.33090E-08 1.33110E-08 461190 + 459 461200 Pd-120 6.50120E-10 6.50120E-10 461200 + 460 461210 Pd-121 1.79310E-11 1.79310E-11 461210 + 461 461230 Pd-123 8.24970E-09 8.24970E-09 461230 + 462 461240 Pd-124 1.60400E-09 1.60400E-09 461240 + 463 471080 Ag-108 1.38530E-09 1.66760E-09 471080 + 464 471081 Ag-108m 3.24460E-09 3.24460E-09 471081 + 465 471090 Ag-109 3.15360E-08 4.80910E-02 47109.82c + 466 471091 Ag-109m 2.06290E-07 4.80670E-02 471091 + 467 471100 Ag-110 1.19050E-06 1.22850E-06 471100 + 468 471101 Ag-110m 2.78860E-06 2.78860E-06 47510.82c + 469 471110 Ag-111 7.13470E-06 2.78260E-02 47111.82c + 470 471111 Ag-111m 4.66710E-05 2.76270E-02 471111 + 471 471120 Ag-112 1.28160E-04 1.95290E-02 471120 + 472 471130 Ag-113 2.12090E-05 4.98560E-03 471130 + 473 471131 Ag-113m 1.38740E-04 7.26360E-03 471131 + 474 471140 Ag-114 3.39090E-05 4.20130E-03 471140 + 475 471141 Ag-114m 1.42610E-04 1.42610E-04 471141 + 476 471150 Ag-115 4.42340E-05 1.19190E-03 471150 + 477 471151 Ag-115m 2.89360E-04 1.56510E-03 471151 + 478 471160 Ag-116 3.26910E-05 5.30420E-04 471160 + 479 471161 Ag-116m 7.65690E-05 7.65690E-05 471161 + 480 471170 Ag-117 1.14860E-05 3.48330E-05 471170 + 481 471171 Ag-117m 7.51330E-05 9.29050E-05 471171 + 482 471180 Ag-118 5.54110E-06 1.52380E-05 471180 + 483 471181 Ag-118m 2.33040E-05 2.33260E-05 471181 + 484 471190 Ag-119 3.02330E-07 3.08980E-07 471190 + 485 471191 Ag-119m 1.97770E-06 1.98430E-06 471191 + 486 471200 Ag-120 1.41330E-07 2.15970E-07 471200 + 487 471201 Ag-120m 2.00540E-07 2.00870E-07 471201 + 488 471210 Ag-121 5.14640E-08 5.14820E-08 471210 + 489 471220 Ag-122 3.64300E-10 3.64300E-10 471220 + 490 471221 Ag-122m 3.28160E-10 3.28160E-10 471221 + 491 471230 Ag-123 1.16120E-06 1.16950E-06 471230 + 492 471240 Ag-124 3.56750E-07 5.19030E-07 471240 + 493 471241 Ag-124m 3.21350E-07 3.21350E-07 471241 + 494 471250 Ag-125 3.00390E-07 3.00390E-07 471250 + 495 471260 Ag-126 7.10540E-08 7.10540E-08 471260 + 496 471270 Ag-127 7.96850E-09 7.96850E-09 471270 + 497 471280 Ag-128 4.05640E-10 4.05640E-10 471280 + 498 481100 Cd-110 1.26380E-09 3.97670E-06 48110.82c + 499 481110 Cd-111 7.07540E-09 2.79640E-02 48111.82c + 500 481111 Cd-111m 2.31490E-08 2.31490E-08 481111 + 501 481120 Cd-112 8.38280E-07 1.95290E-02 48112.82c + 502 481130 Cd-113 3.15570E-06 7.51750E-03 48113.82c + 503 481131 Cd-113m 1.03240E-05 9.65190E-05 481131 + 504 481140 Cd-114 3.69640E-05 4.23820E-03 48114.82c + 505 481150 Cd-115 1.83930E-05 2.34210E-03 481150 + 506 481151 Cd-115m 6.01770E-05 1.64860E-04 48515.82c + 507 481160 Cd-116 1.30930E-04 7.33330E-04 48116.82c + 508 481170 Cd-117 1.40670E-05 1.08700E-04 481170 + 509 481171 Cd-117m 4.60220E-05 7.35510E-05 481171 + 510 481180 Cd-118 2.35730E-05 5.25740E-05 481180 + 511 481190 Cd-119 7.19920E-06 9.33800E-06 481190 + 512 481191 Cd-119m 1.73800E-05 1.75340E-05 481191 + 513 481200 Cd-120 1.65210E-05 1.68630E-05 481200 + 514 481210 Cd-121 2.07190E-06 2.11800E-06 481210 + 515 481211 Cd-121m 5.00190E-06 5.00730E-06 481211 + 516 481220 Cd-122 4.84070E-07 4.84760E-07 481220 + 517 481230 Cd-123 3.08600E-06 4.04310E-06 481230 + 518 481231 Cd-123m 7.45000E-06 7.66290E-06 481231 + 519 481240 Cd-124 2.69620E-05 2.76410E-05 481240 + 520 481250 Cd-125 9.70350E-06 9.85370E-06 481250 + 521 481251 Cd-125m 2.34260E-05 2.35760E-05 481251 + 522 481260 Cd-126 3.89720E-05 3.90430E-05 481260 + 523 481270 Cd-127 1.32490E-05 1.32570E-05 481270 + 524 481280 Cd-128 3.44110E-06 3.44150E-06 481280 + 525 481290 Cd-129 5.58180E-08 5.58180E-08 481290 + 526 481291 Cd-129m 1.34750E-07 1.34750E-07 481291 + 527 481300 Cd-130 1.39120E-08 1.39120E-08 481300 + 528 491130 In-113 8.00550E-10 9.63850E-05 49113.82c + 529 491131 In-113m 1.85110E-10 1.85110E-10 491131 + 530 491140 In-114 5.45440E-09 2.13360E-08 491140 + 531 491141 In-114m 8.36020E-09 1.64570E-08 491141 + 532 491142 In-114m 8.09720E-09 8.09720E-09 491142 + 533 491150 In-115 3.20290E-07 2.39020E-03 49115.82c + 534 491151 In-115m 7.40590E-08 2.34220E-03 491151 + 535 491160 In-116 3.10430E-07 3.10430E-07 491160 + 536 491161 In-116m 4.75810E-07 9.36650E-07 491161 + 537 491162 In-116m 4.60840E-07 4.60840E-07 491162 + 538 491170 In-117 2.04790E-06 1.31230E-04 491170 + 539 491171 In-117m 4.73520E-07 1.01210E-04 491171 + 540 491180 In-118 6.30790E-07 5.32050E-05 491180 + 541 491181 In-118m 9.66830E-07 1.89020E-06 491181 + 542 491182 In-118m 9.36420E-07 9.36420E-07 491182 + 543 491190 In-119 8.73360E-06 2.77250E-05 491190 + 544 491191 In-119m 2.01940E-06 1.04870E-05 491191 + 545 491200 In-120 5.63840E-06 2.25020E-05 491200 + 546 491201 In-120m 5.63840E-06 5.63840E-06 491201 + 547 491202 In-120m 5.63840E-06 5.63840E-06 491202 + 548 491210 In-121 2.38920E-05 2.96960E-05 491210 + 549 491211 In-121m 5.52450E-06 6.92920E-06 491211 + 550 491220 In-122 2.12850E-06 2.61330E-06 491220 + 551 491221 In-122m 1.51010E-06 1.51010E-06 491221 + 552 491222 In-122m 1.51010E-06 1.51010E-06 491222 + 553 491230 In-123 1.23890E-05 2.12100E-05 491230 + 554 491231 In-123m 2.86450E-06 5.74870E-06 491231 + 555 491240 In-124 9.42980E-06 3.70710E-05 491240 + 556 491241 In-124m 8.49420E-06 8.49420E-06 491241 + 557 491250 In-125 7.73470E-05 1.05640E-04 491250 + 558 491251 In-125m 1.78850E-05 2.30220E-05 491251 + 559 491260 In-126 1.57530E-04 1.96580E-04 491260 + 560 491261 In-126m 1.41910E-04 1.41910E-04 491261 + 561 491270 In-127 6.07290E-04 6.07290E-04 491270 + 562 491271 In-127m 1.40420E-04 1.53680E-04 491271 + 563 491280 In-128 1.02560E-04 1.47740E-04 491280 + 564 491281 In-128m 4.17470E-05 4.51880E-05 491281 + 565 491282 In-128m 1.29990E-04 1.29990E-04 491282 + 566 491290 In-129 1.06110E-04 1.06240E-04 491290 + 567 491291 In-129m 2.45340E-05 2.45900E-05 491291 + 568 491300 In-130 1.59680E-05 1.59820E-05 491300 + 569 491301 In-130m 1.78350E-05 1.78350E-05 491301 + 570 491302 In-130m 3.03450E-05 3.03450E-05 491302 + 571 491310 In-131 1.45350E-05 1.46830E-05 491310 + 572 491311 In-131m 1.45350E-05 1.45350E-05 491311 + 573 491312 In-131m 1.45350E-05 1.45350E-05 491312 + 574 491320 In-132 1.33650E-07 1.33650E-07 491320 + 575 491330 In-133 3.79900E-09 4.67740E-09 491330 + 576 491331 In-133m 8.78420E-10 8.78420E-10 491331 + 577 501150 Sn-115 7.73610E-11 1.17110E-04 50115.82c + 578 501160 Sn-116 9.32560E-10 1.24800E-06 50116.82c + 579 501170 Sn-117 1.39790E-09 1.84780E-04 50117.82c + 580 501171 Sn-117m 4.57370E-09 4.51700E-07 501171 + 581 501180 Sn-118 3.06990E-08 5.51390E-05 50118.82c + 582 501190 Sn-119 8.74860E-08 3.79990E-05 50119.82c + 583 501191 Sn-119m 2.86220E-07 2.53330E-05 501191 + 584 501200 Sn-120 2.64560E-06 3.64310E-05 50120.82c + 585 501210 Sn-121 3.33820E-06 4.53800E-05 501210 + 586 501211 Sn-121m 8.05880E-06 1.14230E-05 501211 + 587 501220 Sn-122 7.96940E-06 1.39550E-05 50122.82c + 588 501230 Sn-123 8.00720E-08 1.69720E-06 50123.82c + 589 501231 Sn-123m 3.31680E-08 2.53750E-05 501231 + 590 501240 Sn-124 3.53710E-05 8.09360E-05 50124.82c + 591 501250 Sn-125 4.87430E-05 6.65880E-05 50125.82c + 592 501251 Sn-125m 2.01910E-05 1.31010E-04 501251 + 593 501260 Sn-126 3.70870E-04 7.10410E-04 50126.82c + 594 501270 Sn-127 7.75260E-04 1.01200E-03 501270 + 595 501271 Sn-127m 3.21140E-04 8.44330E-04 501271 + 596 501280 Sn-128 1.15820E-03 4.14860E-03 501280 + 597 501281 Sn-128m 2.71270E-03 2.84270E-03 501281 + 598 501290 Sn-129 9.46100E-04 1.06570E-03 501290 + 599 501291 Sn-129m 2.28400E-03 2.29530E-03 501291 + 600 501300 Sn-130 1.24200E-03 1.28390E-03 501300 + 601 501301 Sn-130m 2.90920E-03 2.93180E-03 501301 + 602 501310 Sn-131 5.83960E-04 6.12110E-04 501310 + 603 501311 Sn-131m 1.40970E-03 1.42490E-03 501311 + 604 501320 Sn-132 5.90370E-04 5.90510E-04 501320 + 605 501330 Sn-133 4.48410E-05 4.48420E-05 501330 + 606 501340 Sn-134 1.94460E-06 1.94460E-06 501340 + 607 501350 Sn-135 4.83220E-08 4.83220E-08 501350 + 608 511180 Sb-118 1.97050E-12 1.97050E-12 511180 + 609 511181 Sb-118m 2.79610E-12 2.79610E-12 511181 + 610 511190 Sb-119 2.34160E-10 3.08590E-10 511190 + 611 511191 Sb-119m 7.44320E-11 7.44320E-11 511191 + 612 511200 Sb-120 2.79090E-09 2.79090E-09 511200 + 613 511201 Sb-120m 3.96020E-09 3.96020E-09 511201 + 614 511210 Sb-121 1.44910E-07 4.80840E-05 51121.82c + 615 511220 Sb-122 6.33920E-06 1.35250E-05 511220 + 616 511221 Sb-122m 7.18580E-06 7.18580E-06 511221 + 617 511230 Sb-123 7.59860E-11 2.70720E-05 51123.82c + 618 511240 Sb-124 2.19460E-09 5.15530E-09 51124.82c + 619 511241 Sb-124m 1.67810E-09 3.94760E-09 511241 + 620 511242 Sb-124m 2.26950E-09 2.26950E-09 511242 + 621 511250 Sb-125 2.32650E-05 2.20860E-04 51125.82c + 622 511260 Sb-126 4.09070E-05 5.06800E-05 51126.82c + 623 511261 Sb-126m 3.02460E-05 6.98030E-05 511261 + 624 511262 Sb-126m 3.95570E-05 3.95570E-05 511262 + 625 511270 Sb-127 1.61420E-04 2.01770E-03 511270 + 626 511280 Sb-128 4.35420E-04 4.61080E-03 511280 + 627 511281 Sb-128m 7.42980E-04 7.42980E-04 511281 + 628 511290 Sb-129 2.15580E-03 4.73880E-03 511290 + 629 511291 Sb-129m 1.31730E-03 2.46500E-03 511291 + 630 511300 Sb-130 4.47440E-03 7.22420E-03 511300 + 631 511301 Sb-130m 4.47440E-03 5.94030E-03 511301 + 632 511310 Sb-131 1.54070E-02 1.74440E-02 511310 + 633 511320 Sb-132 6.09490E-03 6.68540E-03 511320 + 634 511321 Sb-132m 4.49210E-03 4.49210E-03 511321 + 635 511330 Sb-133 7.30880E-03 7.35400E-03 511330 + 636 511340 Sb-134 3.99250E-04 4.00870E-04 511340 + 637 511341 Sb-134m 9.35150E-04 9.35150E-04 511341 + 638 511350 Sb-135 3.34650E-04 3.34690E-04 511350 + 639 511360 Sb-136 6.36360E-06 6.36360E-06 511360 + 640 511370 Sb-137 2.87280E-07 2.87280E-07 511370 + 641 511380 Sb-138 6.65340E-09 6.65340E-09 511380 + 642 521200 Te-120 1.38910E-12 1.38910E-12 52120.82c + 643 521210 Te-121 2.17520E-11 8.48740E-11 521210 + 644 521211 Te-121m 7.11640E-11 7.11640E-11 521211 + 645 521220 Te-122 9.52470E-10 1.31740E-05 52122.82c + 646 521250 Te-125 4.33790E-11 2.20860E-04 52125.82c + 647 521251 Te-125m 1.41920E-10 4.94210E-05 521251 + 648 521260 Te-126 3.06560E-08 1.10740E-04 52126.82c + 649 521270 Te-127 4.15830E-07 2.01110E-03 521270 + 650 521271 Te-127m 1.00390E-06 3.33510E-04 52527.82c + 651 521280 Te-128 1.14810E-04 5.44180E-03 52128.82c + 652 521290 Te-129 1.40630E-04 6.14050E-03 521290 + 653 521291 Te-129m 3.39500E-04 3.17210E-03 52529.82c + 654 521300 Te-130 4.32850E-03 1.74930E-02 52130.82c + 655 521310 Te-131 3.50720E-03 2.16260E-02 521310 + 656 521311 Te-131m 8.46680E-03 9.86340E-03 521311 + 657 521320 Te-132 2.83120E-02 3.94890E-02 52132.82c + 658 521330 Te-133 1.11610E-02 2.21830E-02 521330 + 659 521331 Te-133m 2.69460E-02 2.82170E-02 521331 + 660 521340 Te-134 3.82410E-02 3.96290E-02 521340 + 661 521350 Te-135 1.13040E-02 1.15870E-02 521350 + 662 521360 Te-136 3.69480E-03 3.70020E-03 521360 + 663 521370 Te-137 6.49090E-04 6.49240E-04 521370 + 664 521380 Te-138 8.19360E-05 8.19430E-05 521380 + 665 521390 Te-139 1.68720E-06 1.68720E-06 521390 + 666 521400 Te-140 4.50470E-08 4.50470E-08 521400 + 667 531270 I-127 2.27680E-10 2.01910E-03 53127.82c + 668 531280 I-128 2.59610E-08 2.59610E-08 531280 + 669 531290 I-129 1.00760E-06 7.31520E-03 53129.82c + 670 531300 I-130 1.09830E-05 1.49220E-05 53130.82c + 671 531301 I-130m 4.68910E-06 4.68910E-06 531301 + 672 531310 I-131 4.99410E-04 2.99170E-02 53131.82c + 673 531320 I-132 1.33840E-03 4.16760E-02 531320 + 674 531321 I-132m 9.86410E-04 9.86410E-04 531321 + 675 531330 I-133 6.98720E-03 5.67190E-02 531330 + 676 531331 I-133m 4.26980E-03 4.26980E-03 531331 + 677 531340 I-134 1.45950E-02 6.47320E-02 531340 + 678 531341 I-134m 1.07560E-02 1.07560E-02 531341 + 679 531350 I-135 4.99230E-02 6.15100E-02 53135.82c + 680 531360 I-136 8.86560E-03 1.25760E-02 531360 + 681 531361 I-136m 2.07650E-02 2.07750E-02 531361 + 682 531370 I-137 2.02350E-02 2.08700E-02 531370 + 683 531380 I-138 5.74450E-03 5.82130E-03 531380 + 684 531390 I-139 2.09810E-03 2.09980E-03 531390 + 685 531400 I-140 2.58490E-04 2.58540E-04 531400 + 686 531410 I-141 5.33110E-06 5.33110E-06 531410 + 687 531420 I-142 1.24950E-07 1.24950E-07 531420 + 688 531430 I-143 3.05550E-09 3.05550E-09 531430 + 689 541290 Xe-129 5.78560E-11 2.47140E-10 54129.82c + 690 541291 Xe-129m 1.89290E-10 1.89290E-10 541291 + 691 541300 Xe-130 2.05350E-08 1.56920E-05 54130.82c + 692 541310 Xe-131 3.10270E-07 2.99190E-02 54131.82c + 693 541311 Xe-131m 7.49030E-07 3.25710E-04 541311 + 694 541320 Xe-132 3.60280E-05 4.18910E-02 54132.82c + 695 541321 Xe-132m 4.08390E-05 4.08390E-05 541321 + 696 541330 Xe-133 1.51270E-04 5.72350E-02 54133.82c + 697 541331 Xe-133m 3.65190E-04 1.97960E-03 541331 + 698 541340 Xe-134 9.99360E-04 6.83200E-02 54134.82c + 699 541341 Xe-134m 2.34070E-03 2.58810E-03 541341 + 700 541350 Xe-135 3.75090E-03 7.42010E-02 54135.82c + 701 541351 Xe-135m 9.05510E-03 1.92100E-02 541351 + 702 541360 Xe-136 4.08960E-02 7.56030E-02 54136.82c + 703 541370 Xe-137 5.32370E-02 7.30590E-02 541370 + 704 541380 Xe-138 6.45060E-02 7.02240E-02 541380 + 705 541390 Xe-139 2.78280E-02 2.97460E-02 541390 + 706 541400 Xe-140 1.33000E-02 1.35360E-02 541400 + 707 541410 Xe-141 3.65620E-03 3.66040E-03 541410 + 708 541420 Xe-142 4.87640E-04 4.87730E-04 541420 + 709 541430 Xe-143 7.07900E-05 7.07920E-05 541430 + 710 541440 Xe-144 1.00400E-06 1.00400E-06 541440 + 711 541450 Xe-145 1.51390E-08 1.51390E-08 541450 + 712 551320 Cs-132 3.95970E-09 3.95970E-09 551320 + 713 551330 Cs-133 3.10270E-07 5.72360E-02 55133.82c + 714 551340 Cs-134 4.83840E-06 8.40430E-06 55134.82c + 715 551341 Cs-134m 3.56590E-06 3.56590E-06 551341 + 716 551350 Cs-135 1.13360E-04 7.44990E-02 55135.82c + 717 551351 Cs-135m 6.92720E-05 6.92720E-05 551351 + 718 551360 Cs-136 5.89880E-04 7.62730E-04 55136.82c + 719 551361 Cs-136m 3.45700E-04 3.45700E-04 551361 + 720 551370 Cs-137 8.64270E-03 8.17020E-02 55137.82c + 721 551380 Cs-138 9.34780E-03 9.03160E-02 551380 + 722 551381 Cs-138m 1.32640E-02 1.32640E-02 551381 + 723 551390 Cs-139 3.32230E-02 6.29690E-02 551390 + 724 551400 Cs-140 2.64930E-02 4.00300E-02 551400 + 725 551410 Cs-141 2.67030E-02 3.03640E-02 551410 + 726 551420 Cs-142 8.79930E-03 9.28600E-03 551420 + 727 551430 Cs-143 3.53510E-03 3.60520E-03 551430 + 728 551440 Cs-144 4.57340E-04 6.86980E-04 551440 + 729 551441 Cs-144m 4.57340E-04 4.57340E-04 551441 + 730 551450 Cs-145 2.13340E-04 2.13350E-04 551450 + 731 551460 Cs-146 2.38600E-05 2.38600E-05 551460 + 732 551470 Cs-147 5.72170E-08 5.72170E-08 551470 + 733 551480 Cs-148 7.55330E-10 7.55330E-10 551480 + 734 561340 Ba-134 2.60320E-09 8.40690E-06 56134.82c + 735 561350 Ba-135 2.26450E-08 7.73140E-08 56135.82c + 736 561351 Ba-135m 5.46690E-08 5.46690E-08 561351 + 737 561360 Ba-136 2.62510E-06 9.44350E-04 56136.82c + 738 561361 Ba-136m 6.14870E-06 6.14870E-06 561361 + 739 561370 Ba-137 4.22980E-05 8.18460E-02 56137.82c + 740 561371 Ba-137m 1.02110E-04 7.72280E-02 561371 + 741 561380 Ba-138 2.63300E-03 9.54690E-02 56138.82c + 742 561390 Ba-139 7.24030E-03 7.02090E-02 561390 + 743 561400 Ba-140 1.91200E-02 5.91500E-02 56140.82c + 744 561410 Ba-141 2.42350E-02 5.45990E-02 561410 + 745 561420 Ba-142 2.98840E-02 3.92290E-02 561420 + 746 561430 Ba-143 2.54350E-02 2.90030E-02 561430 + 747 561440 Ba-144 2.06500E-02 2.15740E-02 561440 + 748 561450 Ba-145 5.59840E-03 5.78460E-03 561450 + 749 561460 Ba-146 1.80530E-03 1.82580E-03 561460 + 750 561470 Ba-147 3.93480E-04 3.93520E-04 561470 + 751 561480 Ba-148 6.15500E-05 6.15510E-05 561480 + 752 561490 Ba-149 3.50350E-07 3.50350E-07 561490 + 753 561500 Ba-150 6.92050E-09 6.92050E-09 561500 + 754 571370 La-137 1.10490E-08 1.10490E-08 571370 + 755 571380 La-138 4.56870E-07 4.56870E-07 57138.82c + 756 571390 La-139 1.01100E-04 7.03100E-02 57139.82c + 757 571400 La-140 3.36580E-04 5.94870E-02 57140.82c + 758 571410 La-141 1.78110E-03 5.63800E-02 571410 + 759 571420 La-142 2.46940E-03 4.16980E-02 571420 + 760 571430 La-143 8.23020E-03 3.72330E-02 571430 + 761 571440 La-144 1.32920E-02 3.48660E-02 571440 + 762 571450 La-145 1.32080E-02 1.89930E-02 571450 + 763 571460 La-146 2.94540E-03 4.77120E-03 571460 + 764 571461 La-146m 5.29810E-03 5.29810E-03 571461 + 765 571470 La-147 5.30670E-03 5.70050E-03 571470 + 766 571480 La-148 1.84640E-03 1.90770E-03 571480 + 767 571490 La-149 6.02410E-04 6.02760E-04 571490 + 768 571500 La-150 1.39300E-04 1.39310E-04 571500 + 769 571510 La-151 2.88320E-05 2.88320E-05 571510 + 770 571520 La-152 2.14850E-08 2.14850E-08 571520 + 771 571530 La-153 2.84570E-10 2.84570E-10 571530 + 772 581390 Ce-139 6.83510E-10 2.33360E-09 581390 + 773 581391 Ce-139m 1.65010E-09 1.65010E-09 581391 + 774 581400 Ce-140 7.43300E-08 5.94870E-02 58140.82c + 775 581410 Ce-141 1.10270E-05 5.63910E-02 58141.82c + 776 581420 Ce-142 2.13240E-04 4.19120E-02 58142.82c + 777 581430 Ce-143 6.35560E-04 3.78690E-02 58143.82c + 778 581440 Ce-144 3.45120E-03 3.83170E-02 58144.82c + 779 581450 Ce-145 5.15000E-03 2.41430E-02 581450 + 780 581460 Ce-146 1.05820E-02 2.06510E-02 581460 + 781 581470 Ce-147 1.06950E-02 1.63960E-02 581470 + 782 581480 Ce-148 1.14590E-02 1.33750E-02 581480 + 783 581490 Ce-149 8.13640E-03 8.73450E-03 581490 + 784 581500 Ce-150 3.26780E-03 3.40330E-03 581500 + 785 581510 Ce-151 7.25190E-04 7.54020E-04 581510 + 786 581520 Ce-152 2.40380E-04 2.40400E-04 581520 + 787 581530 Ce-153 2.35630E-05 2.35630E-05 581530 + 788 581540 Ce-154 1.18750E-07 1.18750E-07 581540 + 789 581550 Ce-155 1.83190E-09 1.83190E-09 581550 + 790 591420 Pr-142 1.48340E-09 4.95800E-09 59142.82c + 791 591421 Pr-142m 3.47460E-09 3.47460E-09 591421 + 792 591430 Pr-143 7.86260E-06 3.78770E-02 59143.82c + 793 591440 Pr-144 1.76050E-06 3.83340E-02 591440 + 794 591441 Pr-144m 1.56350E-05 5.44390E-04 591441 + 795 591450 Pr-145 5.01240E-05 2.41930E-02 591450 + 796 591460 Pr-146 3.09170E-04 2.09600E-02 591460 + 797 591470 Pr-147 1.06400E-03 1.74590E-02 591470 + 798 591480 Pr-148 4.23910E-04 1.37990E-02 591480 + 799 591481 Pr-148m 1.78280E-03 1.78280E-03 591481 + 800 591490 Pr-149 5.62570E-03 1.43600E-02 591490 + 801 591500 Pr-150 4.10070E-03 7.50400E-03 591500 + 802 591510 Pr-151 3.01390E-03 3.76790E-03 591510 + 803 591520 Pr-152 2.06590E-03 2.30640E-03 591520 + 804 591530 Pr-153 8.19510E-04 8.42930E-04 591530 + 805 591540 Pr-154 1.54790E-04 1.54910E-04 591540 + 806 591550 Pr-155 5.86750E-05 5.86770E-05 591550 + 807 591560 Pr-156 1.51400E-07 1.51400E-07 591560 + 808 591570 Pr-157 3.73370E-09 3.73370E-09 591570 + 809 591580 Pr-158 3.68560E-11 3.68560E-11 591580 + 810 601440 Nd-144 1.43420E-09 3.83350E-02 60144.82c + 811 601450 Nd-145 2.78890E-08 2.41930E-02 60145.82c + 812 601460 Nd-146 5.96740E-06 2.09660E-02 60146.82c + 813 601470 Nd-147 3.07550E-05 1.74900E-02 60147.82c + 814 601480 Nd-148 2.44920E-04 1.58270E-02 60148.82c + 815 601490 Nd-149 1.03030E-03 1.53900E-02 601490 + 816 601500 Nd-150 2.53610E-03 1.00400E-02 60150.82c + 817 601510 Nd-151 2.92010E-03 6.68800E-03 601510 + 818 601520 Nd-152 5.23500E-03 7.54140E-03 601520 + 819 601530 Nd-153 3.25720E-03 4.10010E-03 601530 + 820 601540 Nd-154 2.54540E-03 2.70030E-03 601540 + 821 601550 Nd-155 9.19600E-04 9.78280E-04 601550 + 822 601560 Nd-156 2.76850E-04 2.77000E-04 601560 + 823 601570 Nd-157 6.73080E-06 6.73430E-06 601570 + 824 601580 Nd-158 3.98850E-07 3.98890E-07 601580 + 825 601590 Nd-159 5.53520E-09 5.53520E-09 601590 + 826 601600 Nd-160 1.32810E-10 1.32810E-10 601600 + 827 611470 Pm-147 2.36430E-09 1.74900E-02 61147.82c + 828 611480 Pm-148 1.84440E-06 2.06040E-06 61148.82c + 829 611481 Pm-148m 4.32010E-06 4.32010E-06 61548.82c + 830 611490 Pm-149 1.72510E-05 1.54080E-02 61149.82c + 831 611500 Pm-150 1.47150E-05 1.47150E-05 611500 + 832 611510 Pm-151 1.69570E-04 6.85760E-03 61151.82c + 833 611520 Pm-152 5.78890E-05 7.59930E-03 611520 + 834 611521 Pm-152m 1.15600E-04 1.15600E-04 611521 + 835 611522 Pm-152m 1.27860E-04 1.27860E-04 611522 + 836 611530 Pm-153 9.98630E-04 5.09880E-03 611530 + 837 611540 Pm-154 8.26250E-04 3.52660E-03 611540 + 838 611541 Pm-154m 8.26250E-04 8.26250E-04 611541 + 839 611550 Pm-155 1.45400E-03 2.43230E-03 611550 + 840 611560 Pm-156 7.91960E-04 1.06900E-03 611560 + 841 611570 Pm-157 5.65910E-04 5.72640E-04 611570 + 842 611580 Pm-158 8.01850E-05 8.05840E-05 611580 + 843 611590 Pm-159 3.33600E-06 3.34150E-06 611590 + 844 611600 Pm-160 2.46940E-07 2.47070E-07 611600 + 845 611610 Pm-161 5.93380E-09 5.93380E-09 611610 + 846 611620 Pm-162 2.21730E-10 2.21730E-10 611620 + 847 611630 Pm-163 2.04750E-12 2.04750E-12 611630 + 848 621490 Sm-149 5.16750E-10 1.54080E-02 62149.82c + 849 621500 Sm-150 1.38410E-08 1.47290E-05 62150.82c + 850 621510 Sm-151 2.76570E-07 6.85790E-03 62151.82c + 851 621520 Sm-152 1.00930E-05 7.85290E-03 62152.82c + 852 621530 Sm-153 2.43190E-05 5.18180E-03 62153.82c + 853 621531 Sm-153m 5.87100E-05 5.87100E-05 621531 + 854 621540 Sm-154 3.68040E-04 4.72090E-03 62154.82c + 855 621550 Sm-155 6.73110E-04 3.10540E-03 621550 + 856 621560 Sm-156 9.27060E-04 1.99600E-03 621560 + 857 621570 Sm-157 6.00060E-04 1.17270E-03 621570 + 858 621580 Sm-158 6.40260E-04 7.20840E-04 621580 + 859 621590 Sm-159 1.88770E-04 1.92110E-04 621590 + 860 621600 Sm-160 7.56820E-05 7.59280E-05 621600 + 861 621610 Sm-161 2.72070E-06 2.72660E-06 621610 + 862 621620 Sm-162 5.27350E-07 5.27570E-07 621620 + 863 621630 Sm-163 1.65940E-08 1.65960E-08 621630 + 864 621640 Sm-164 5.24550E-10 5.24550E-10 621640 + 865 621650 Sm-165 7.05860E-12 7.05860E-12 621650 + 866 631520 Eu-152 3.90110E-10 8.25220E-10 63152.82c + 867 631521 Eu-152m 9.29150E-11 9.29150E-11 631521 + 868 631522 Eu-152m 4.35100E-10 4.35100E-10 631522 + 869 631530 Eu-153 3.24410E-08 5.18180E-03 63153.82c + 870 631540 Eu-154 3.44310E-07 6.54460E-07 63154.82c + 871 631541 Eu-154m 3.10150E-07 3.10150E-07 631541 + 872 631550 Eu-155 6.91920E-06 3.11230E-03 63155.82c + 873 631560 Eu-156 1.88850E-05 2.01490E-03 63156.82c + 874 631570 Eu-157 6.22780E-05 1.23500E-03 63157.82c + 875 631580 Eu-158 3.99760E-05 7.60820E-04 631580 + 876 631590 Eu-159 5.64770E-05 2.48590E-04 631590 + 877 631600 Eu-160 7.55260E-05 1.51450E-04 631600 + 878 631610 Eu-161 5.32180E-05 5.59450E-05 631610 + 879 631620 Eu-162 3.44770E-05 3.50050E-05 631620 + 880 631630 Eu-163 2.59180E-06 2.60840E-06 631630 + 881 631640 Eu-164 2.46780E-07 2.47300E-07 631640 + 882 631650 Eu-165 1.76880E-08 1.76950E-08 631650 + 883 631660 Eu-166 5.28110E-10 5.28110E-10 631660 + 884 631670 Eu-167 1.19030E-11 1.19030E-11 631670 + 885 641540 Gd-154 1.80750E-10 6.54510E-07 64154.82c + 886 641550 Gd-155 1.10290E-09 3.11230E-03 64155.82c + 887 641551 Gd-155m 2.66260E-09 2.66260E-09 641551 + 888 641560 Gd-156 9.40760E-08 2.01500E-03 64156.82c + 889 641570 Gd-157 9.63430E-07 1.23590E-03 64157.82c + 890 641580 Gd-158 1.99880E-05 7.80810E-04 64158.82c + 891 641590 Gd-159 1.88290E-05 2.67420E-04 641590 + 892 641600 Gd-160 5.65610E-05 2.08020E-04 64160.82c + 893 641610 Gd-161 1.77270E-05 7.36720E-05 641610 + 894 641620 Gd-162 5.16600E-05 8.66650E-05 641620 + 895 641630 Gd-163 2.57570E-05 2.83650E-05 641630 + 896 641640 Gd-164 1.07480E-05 1.09950E-05 641640 + 897 641650 Gd-165 2.14570E-06 2.16340E-06 641650 + 898 641660 Gd-166 3.18880E-07 3.19410E-07 641660 + 899 641670 Gd-167 2.21250E-08 2.21370E-08 641670 + 900 641680 Gd-168 1.13060E-09 1.13060E-09 641680 + 901 641690 Gd-169 2.91310E-11 2.91310E-11 641690 + 902 651570 Tb-157 1.65200E-10 1.65200E-10 651570 + 903 651580 Tb-158 3.90890E-09 4.34630E-09 651580 + 904 651581 Tb-158m 4.40120E-10 4.40120E-10 651581 + 905 651590 Tb-159 4.21440E-08 2.67460E-04 65159.82c + 906 651600 Tb-160 4.18240E-07 4.18240E-07 65160.82c + 907 651610 Tb-161 1.35150E-06 7.50230E-05 651610 + 908 651620 Tb-162 7.03350E-06 9.36980E-05 651620 + 909 651630 Tb-163 1.04520E-05 3.88170E-05 651630 + 910 651640 Tb-164 1.00710E-05 2.10660E-05 651640 + 911 651650 Tb-165 7.99530E-06 1.01590E-05 651650 + 912 651660 Tb-166 2.97200E-06 3.29140E-06 651660 + 913 651670 Tb-167 9.37900E-07 9.60040E-07 651670 + 914 651680 Tb-168 1.37640E-07 1.38770E-07 651680 + 915 651690 Tb-169 1.80320E-08 1.80610E-08 651690 + 916 651700 Tb-170 1.01420E-09 1.01420E-09 651700 + 917 651710 Tb-171 3.88880E-11 3.88880E-11 651710 + 918 661590 Dy-159 8.70290E-12 8.70290E-12 661590 + 919 661600 Dy-160 3.04690E-10 4.18550E-07 66160.82c + 920 661610 Dy-161 3.01620E-09 7.50260E-05 66161.82c + 921 661620 Dy-162 7.91120E-08 9.37770E-05 66162.82c + 922 661630 Dy-163 3.33020E-07 3.91500E-05 66163.82c + 923 661640 Dy-164 1.43460E-06 2.25030E-05 66164.82c + 924 661650 Dy-165 2.42980E-06 1.29520E-05 661650 + 925 661651 Dy-165m 3.71440E-07 3.71440E-07 661651 + 926 661660 Dy-166 4.10260E-06 7.39400E-06 661660 + 927 661670 Dy-167 2.99910E-06 3.95910E-06 661670 + 928 661680 Dy-168 1.79810E-06 1.93690E-06 661680 + 929 661690 Dy-169 6.11600E-07 6.29660E-07 661690 + 930 661700 Dy-170 1.61940E-07 1.62950E-07 661700 + 931 661710 Dy-171 1.83040E-08 1.83430E-08 661710 + 932 661720 Dy-172 1.52820E-09 1.52820E-09 661720 + 933 661730 Dy-173 6.66680E-11 6.66680E-11 661730 + 934 671620 Ho-162 3.65170E-12 8.95480E-12 671620 + 935 671621 Ho-162m 8.55330E-12 8.55330E-12 671621 + 936 671630 Ho-163 2.16670E-10 2.49790E-10 671630 + 937 671631 Ho-163m 3.31220E-11 3.31220E-11 671631 + 938 671640 Ho-164 9.78350E-10 3.26990E-09 671640 + 939 671641 Ho-164m 2.29160E-09 2.29160E-09 671641 + 940 671650 Ho-165 3.14140E-08 1.29910E-05 67165.82c + 941 671660 Ho-166 3.77470E-08 7.43180E-06 671660 + 942 671661 Ho-166m 8.84130E-08 8.84130E-08 671661 + 943 671670 Ho-167 3.97120E-07 4.35630E-06 671670 + 944 671680 Ho-168 2.34650E-07 2.50280E-06 671680 + 945 671681 Ho-168m 3.32970E-07 3.32970E-07 671681 + 946 671690 Ho-169 7.52970E-07 1.38260E-06 671690 + 947 671700 Ho-170 3.29020E-07 3.29020E-07 671700 + 948 671701 Ho-170m 1.40470E-07 3.03430E-07 671701 + 949 671710 Ho-171 2.24340E-07 2.42680E-07 671710 + 950 671720 Ho-172 5.04650E-08 5.19930E-08 671720 + 951 671730 Ho-173 1.06870E-08 1.07540E-08 671730 + 952 671740 Ho-174 1.01750E-09 1.01750E-09 671740 + 953 671750 Ho-175 7.23620E-11 7.23620E-11 671750 + 954 681650 Er-165 1.76460E-11 1.76460E-11 681650 + 955 681660 Er-166 3.70850E-10 7.43210E-06 68166.82c + 956 681670 Er-167 3.01910E-09 4.35970E-06 68167.82c + 957 681671 Er-167m 4.61530E-10 5.21000E-07 681671 + 958 681680 Er-168 2.37930E-08 2.52830E-06 68168.82c + 959 681690 Er-169 8.34840E-08 1.46610E-06 681690 + 960 681700 Er-170 2.16150E-07 8.48600E-07 68170.82c + 961 681710 Er-171 2.40840E-07 4.83520E-07 681710 + 962 681720 Er-172 2.12020E-07 2.64010E-07 681720 + 963 681730 Er-173 1.08650E-07 1.19400E-07 681730 + 964 681740 Er-174 4.53990E-08 4.64160E-08 681740 + 965 681750 Er-175 9.00440E-09 9.07680E-09 681750 + 966 681760 Er-176 1.32520E-09 1.32520E-09 681760 + 967 681770 Er-177 9.11770E-11 9.11770E-11 681770 + 968 691680 Tm-168 1.38940E-11 1.38940E-11 691680 + 969 691690 Tm-169 2.50570E-10 1.46640E-06 691690 + 970 691700 Tm-170 1.88870E-09 1.88870E-09 691700 + 971 691710 Tm-171 9.74140E-09 4.93260E-07 691710 + 972 691720 Tm-172 2.18450E-08 2.85860E-07 691720 + 973 691730 Tm-173 4.50600E-08 1.64460E-07 691730 + 974 691740 Tm-174 4.34660E-08 8.98820E-08 691740 + 975 691750 Tm-175 3.43080E-08 4.33850E-08 691750 + 976 691760 Tm-176 1.26450E-08 1.39700E-08 691760 + 977 691770 Tm-177 3.96250E-09 4.05370E-09 691770 + 978 691780 Tm-178 5.76930E-10 5.76930E-10 691780 + 979 691790 Tm-179 7.47790E-11 7.47790E-11 691790 + 980 701700 Yb-170 1.41490E-12 1.88760E-09 701700 + 981 701710 Yb-171 2.96040E-12 4.93290E-07 701710 + 982 701711 Yb-171m 1.93660E-11 1.93660E-11 701711 + 983 701720 Yb-172 2.52060E-10 2.86110E-07 701720 + 984 701730 Yb-173 1.47120E-09 1.65940E-07 701730 + 985 701740 Yb-174 6.33670E-09 9.62340E-08 701740 + 986 701750 Yb-175 1.06580E-08 5.56720E-08 701750 + 987 701751 Yb-175m 1.62930E-09 3.50360E-08 701751 + 988 701760 Yb-176 6.37170E-09 2.99590E-08 701760 + 989 701761 Yb-176m 1.14610E-08 1.84460E-08 701761 + 990 701770 Yb-177 1.05170E-08 1.70030E-08 701770 + 991 701771 Yb-177m 2.43180E-09 6.48550E-09 701771 + 992 701780 Yb-178 7.71120E-09 8.28810E-09 701780 + 993 701790 Yb-179 2.59850E-09 2.67330E-09 701790 + 994 701800 Yb-180 6.80850E-10 6.80850E-10 701800 + 995 701810 Yb-181 7.61550E-11 7.61550E-11 701810 + 996 711730 Lu-173 1.13320E-12 1.13320E-12 711730 + 997 711740 Lu-174 4.43590E-12 1.47660E-11 711740 + 998 711741 Lu-174m 1.03900E-11 1.03900E-11 711741 + 999 711750 Lu-175 1.41300E-10 5.58130E-08 71175.82c + 1000 711760 Lu-176 3.60960E-10 2.20560E-09 71176.82c + 1001 711761 Lu-176m 2.00670E-10 2.00670E-10 711761 + 1002 711770 Lu-177 1.24920E-09 1.83640E-08 711770 + 1003 711771 Lu-177m 4.88350E-10 4.96240E-10 711771 + 1004 711772 Lu-177m 1.57810E-11 1.57810E-11 711772 + 1005 711780 Lu-178 1.16570E-09 9.45380E-09 711780 + 1006 711781 Lu-178m 1.32140E-09 1.32140E-09 711781 + 1007 711790 Lu-179 2.83490E-09 5.94160E-09 711790 + 1008 711791 Lu-179m 4.33380E-10 3.10670E-09 711791 + 1009 711800 Lu-180 5.81040E-10 1.64010E-09 711800 + 1010 711801 Lu-180m 5.81040E-10 1.26190E-09 711801 + 1011 711802 Lu-180m 8.56320E-10 8.56320E-10 711802 + 1012 711810 Lu-181 9.55680E-10 1.03180E-09 711810 + 1013 711820 Lu-182 2.13020E-10 2.13020E-10 711820 + 1014 711830 Lu-183 4.47380E-11 4.47380E-11 711830 + 1015 711840 Lu-184 4.22080E-12 4.22080E-12 711840 + 1016 721760 Hf-176 1.69500E-12 2.02180E-10 72176.82c + 1017 721770 Hf-177 1.12340E-11 1.87720E-08 72177.82c + 1018 721771 Hf-177m 4.36510E-12 3.96520E-10 721771 + 1019 721772 Hf-177m 1.68740E-13 8.05950E-12 721772 + 1020 721780 Hf-178 3.81780E-11 1.08820E-08 72178.82c + 1021 721781 Hf-178m 6.29880E-11 1.39010E-09 721781 + 1022 721782 Hf-178m 5.68440E-12 5.68440E-12 721782 + 1023 721790 Hf-179 2.23110E-10 6.31360E-09 72179.82c + 1024 721791 Hf-179m 6.96480E-11 6.96480E-11 721791 + 1025 721792 Hf-179m 7.81030E-11 7.81030E-11 721792 + 1026 721800 Hf-180 3.39350E-10 3.64900E-09 72180.82c + 1027 721801 Hf-180m 6.10400E-10 1.03860E-09 721801 + 1028 721810 Hf-181 1.04800E-09 2.07980E-09 721810 + 1029 721820 Hf-182 3.26780E-10 7.86670E-10 721820 + 1030 721821 Hf-182m 5.87790E-10 5.87790E-10 721821 + 1031 721830 Hf-183 4.65360E-10 5.10100E-10 721830 + 1032 721840 Hf-184 6.89480E-11 7.10590E-11 721840 + 1033 721841 Hf-184m 1.24020E-10 1.26130E-10 721841 + 1034 721850 Hf-185 3.78450E-11 3.78450E-11 721850 + 1035 721860 Hf-186 5.50540E-12 5.50540E-12 721860 + 1036 731790 Ta-179 8.67160E-13 1.14270E-12 731790 + 1037 731800 Ta-180 3.98900E-12 3.98900E-12 731800 + 1038 731801 Ta-180m 4.52170E-12 7.74130E-12 731801 + 1039 731810 Ta-181 4.34150E-11 2.12330E-09 73181.82c + 1040 731820 Ta-182 3.44330E-11 4.37290E-10 73182.82c + 1041 731821 Ta-182m 3.51460E-11 4.02860E-10 731821 + 1042 731822 Ta-182m 2.67910E-11 3.67710E-10 731822 + 1043 731830 Ta-183 1.97180E-10 7.07280E-10 731830 + 1044 731840 Ta-184 1.88740E-10 3.85930E-10 731840 + 1045 731850 Ta-185 9.93240E-11 1.85270E-10 731850 + 1046 731851 Ta-185m 4.81060E-11 4.81060E-11 731851 + 1047 731860 Ta-186 5.37880E-11 5.92930E-11 731860 + 1048 731870 Ta-187 1.67300E-11 1.67300E-11 731870 + 1049 731880 Ta-188 2.41630E-12 2.41630E-12 731880 + 1050 741820 W-182 1.14100E-12 4.38430E-10 74182.82c + 1051 741830 W-183 1.54470E-12 7.13880E-10 74183.82c + 1052 741831 W-183m 5.05380E-12 2.91010E-11 741831 + 1053 741840 W-184 2.81600E-11 4.14090E-10 74184.82c + 1054 741850 W-185 1.58070E-11 2.39240E-10 741850 + 1055 741851 W-185m 3.81610E-11 3.81610E-11 741851 + 1056 741860 W-186 5.85830E-11 1.36850E-10 74186.82c + 1057 741861 W-186m 1.88980E-11 1.88980E-11 741861 + 1058 741870 W-187 5.58660E-11 7.25960E-11 741870 + 1059 741880 W-188 3.30440E-11 3.54600E-11 741880 + 1060 741890 W-189 1.10320E-11 1.10320E-11 741890 + 1061 741900 W-190 1.34080E-12 2.86070E-12 741900 + 1062 741901 W-190m 1.51990E-12 1.51990E-12 741901 + 1063 751860 Re-186 1.03320E-12 1.03320E-12 751860 + 1064 751861 Re-186m 1.46610E-12 1.46610E-12 751861 + 1065 751870 Re-187 7.73730E-12 8.03330E-11 75187.82c + 1066 751880 Re-188 3.25800E-12 4.63490E-11 751880 + 1067 751881 Re-188m 7.63100E-12 7.63100E-12 751881 + 1068 751890 Re-189 1.41740E-11 2.52060E-11 751890 + 1069 751900 Re-190 3.09780E-12 8.49930E-12 751900 + 1070 751901 Re-190m 5.57210E-12 5.57210E-12 751901 + 1071 751910 Re-191 4.06870E-12 4.06870E-12 751910 + 1072 761890 Os-189 3.85330E-13 2.68520E-11 761890 + 1073 761891 Os-189m 1.26070E-12 3.85260E-12 761891 + 1074 761900 Os-190 1.95450E-12 1.57010E-11 761900 + 1075 761901 Os-190m 2.21560E-12 5.24680E-12 761901 + 1076 761910 Os-191 3.49070E-12 8.62630E-12 761910 + 1077 761911 Os-191m 1.06690E-12 1.06690E-12 761911 + 1078 761920 Os-192 1.84860E-12 3.68480E-12 761920 + 1079 761921 Os-192m 2.09550E-12 2.09550E-12 761921 + 1080 761930 Os-193 1.99260E-12 1.99260E-12 761930 + + Nuclide 96245.82c -- curium 245 (Cm-245) + + Neutron-induced fission: + + Interpolation region : 1 / 2 + Interpolation energy : 2.53000E-08 MeV + Number of products : 1112 / 1184 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 3.60660E-05 3.60660E-05 1001.82c + 2 10020 H-2 1.10220E-05 1.10220E-05 1002.82c + 3 10030 H-3 1.85000E-04 1.85000E-04 1003.82c + 4 20040 He-4 2.28000E-03 2.28000E-03 2004.82c + 5 190500 K-50 1.18450E-12 1.18450E-12 190500 + 6 200500 Ca-50 8.41660E-12 9.25760E-12 200500 + 7 200510 Ca-51 9.19830E-12 9.19830E-12 200510 + 8 200520 Ca-52 1.03800E-11 1.03800E-11 200520 + 9 200530 Ca-53 3.88800E-12 3.88800E-12 200530 + 10 200540 Ca-54 1.50040E-12 1.50040E-12 200540 + 11 210500 Sc-50 1.17270E-12 1.08090E-11 210500 + 12 210501 Sc-50m 5.00650E-13 9.75820E-12 210501 + 13 210510 Sc-51 9.30650E-12 1.87120E-11 210510 + 14 210520 Sc-52 1.85430E-11 2.98820E-11 210520 + 15 210530 Sc-53 3.67440E-11 3.94660E-11 210530 + 16 210540 Sc-54 2.80140E-11 2.95140E-11 210540 + 17 210550 Sc-55 2.55320E-11 2.55320E-11 210550 + 18 210560 Sc-56 7.46910E-12 7.46910E-12 210560 + 19 210570 Sc-57 2.30990E-12 2.30990E-12 210570 + 20 220520 Ti-52 4.94250E-12 3.48240E-11 220520 + 21 220530 Ti-53 1.77160E-11 5.71820E-11 220530 + 22 220540 Ti-54 6.81300E-11 9.76440E-11 220540 + 23 220550 Ti-55 1.11570E-10 1.37100E-10 220550 + 24 220560 Ti-56 1.78710E-10 1.86940E-10 220560 + 25 220570 Ti-57 1.13280E-10 1.14830E-10 220570 + 26 220580 Ti-58 7.75970E-11 7.75970E-11 220580 + 27 220590 Ti-59 1.78820E-11 1.78820E-11 220590 + 28 220600 Ti-60 3.77980E-12 3.77980E-12 220600 + 29 230540 V-54 4.47520E-12 1.02120E-10 230540 + 30 230550 V-55 3.91100E-11 1.76210E-10 230550 + 31 230560 V-56 1.11000E-10 2.98290E-10 230560 + 32 230570 V-57 3.56760E-10 4.71240E-10 230570 + 33 230580 V-58 4.51570E-10 5.29170E-10 230580 + 34 230590 V-59 5.91440E-10 6.09320E-10 230590 + 35 230600 V-60 2.65090E-10 2.68870E-10 230600 + 36 230610 V-61 1.46290E-10 1.46290E-10 230610 + 37 230620 V-62 2.71910E-11 2.71910E-11 230620 + 38 230630 V-63 4.49310E-12 4.49310E-12 230630 + 39 240560 Cr-56 9.46810E-12 3.09640E-10 240560 + 40 240570 Cr-57 5.84970E-11 9.51190E-10 240570 + 41 240580 Cr-58 3.83600E-10 4.89430E-10 240580 + 42 240590 Cr-59 8.83210E-10 1.49250E-09 240590 + 43 240600 Cr-60 2.04420E-09 2.32180E-09 240600 + 44 240610 Cr-61 2.15820E-09 2.29570E-09 240610 + 45 240620 Cr-62 2.36500E-09 2.39380E-09 240620 + 46 240630 Cr-63 8.53830E-10 8.56750E-10 240630 + 47 240640 Cr-64 3.15420E-10 3.15420E-10 240640 + 48 240650 Cr-65 4.57510E-11 4.57510E-11 240650 + 49 240660 Cr-66 5.79700E-12 5.79700E-12 240660 + 50 250580 Mn-58 7.00780E-12 4.96440E-10 250580 + 51 250590 Mn-59 1.02530E-10 1.59510E-09 250590 + 52 250600 Mn-60 4.45630E-11 2.41190E-09 250600 + 53 250601 Mn-60m 3.95790E-10 3.95790E-10 250601 + 54 250610 Mn-61 2.36120E-09 4.65690E-09 250610 + 55 250620 Mn-62 3.87980E-09 5.07670E-09 250620 + 56 250621 Mn-62m 6.96510E-10 1.89340E-09 250621 + 57 250630 Mn-63 8.77950E-09 9.63620E-09 250630 + 58 250640 Mn-64 6.44080E-09 6.75620E-09 250640 + 59 250650 Mn-65 5.69660E-09 5.74240E-09 250650 + 60 250660 Mn-66 1.61730E-09 1.62310E-09 250660 + 61 250670 Mn-67 4.78240E-10 4.78240E-10 250670 + 62 250680 Mn-68 5.01070E-11 5.01070E-11 250680 + 63 250690 Mn-69 4.89460E-12 4.89460E-12 250690 + 64 260600 Fe-60 1.12480E-11 2.77350E-09 260600 + 65 260610 Fe-61 1.24210E-10 4.78110E-09 260610 + 66 260620 Fe-62 1.32450E-09 8.29460E-09 260620 + 67 260630 Fe-63 4.57970E-09 1.42160E-08 260630 + 68 260640 Fe-64 1.69460E-08 2.37020E-08 260640 + 69 260650 Fe-65 2.70190E-08 3.27610E-08 260650 + 70 260660 Fe-66 4.22170E-08 4.38400E-08 260660 + 71 260670 Fe-67 2.57140E-08 2.61920E-08 260670 + 72 260680 Fe-68 1.69190E-08 1.69700E-08 260680 + 73 260690 Fe-69 3.77760E-09 3.78130E-09 260690 + 74 260700 Fe-70 8.05370E-10 8.05370E-10 260700 + 75 260710 Fe-71 2.57300E-11 2.57300E-11 260710 + 76 260720 Fe-72 1.51200E-12 1.51200E-12 260720 + 77 270620 Co-62 2.34070E-12 8.29700E-09 270620 + 78 270621 Co-62m 5.48260E-12 5.48260E-12 270621 + 79 270630 Co-63 1.64910E-10 1.43810E-08 270630 + 80 270640 Co-64 1.21150E-09 2.49140E-08 270640 + 81 270650 Co-65 1.02620E-08 4.30230E-08 270650 + 82 270660 Co-66 2.83560E-08 7.21960E-08 270660 + 83 270670 Co-67 8.77260E-08 1.13920E-07 270670 + 84 270680 Co-68 5.69240E-08 9.06490E-08 270680 + 85 270681 Co-68m 5.02160E-08 6.74520E-08 270681 + 86 270690 Co-69 1.36670E-07 1.40190E-07 270690 + 87 270700 Co-70 3.10290E-08 3.10290E-08 270700 + 88 270701 Co-70m 3.10290E-08 3.18340E-08 270701 + 89 270710 Co-71 1.27680E-08 1.27940E-08 270710 + 90 270720 Co-72 1.73350E-09 1.73500E-09 270720 + 91 270730 Co-73 8.02500E-10 8.02500E-10 270730 + 92 270740 Co-74 9.03950E-11 9.03950E-11 270740 + 93 270750 Co-75 5.55100E-12 5.55100E-12 270750 + 94 280640 Ni-64 8.75810E-12 2.49230E-08 28064.82c + 95 280650 Ni-65 1.62040E-10 4.31850E-08 280650 + 96 280660 Ni-66 2.63910E-09 7.48350E-08 280660 + 97 280670 Ni-67 1.56160E-08 1.29530E-07 280670 + 98 280680 Ni-68 9.84700E-08 2.24250E-07 280680 + 99 280690 Ni-69 1.10400E-07 2.49180E-07 280690 + 100 280691 Ni-69m 1.10400E-07 1.10400E-07 280691 + 101 280700 Ni-70 6.50670E-07 7.13530E-07 280700 + 102 280710 Ni-71 2.05530E-07 2.18320E-07 280710 + 103 280720 Ni-72 2.17620E-07 2.19350E-07 280720 + 104 280730 Ni-73 1.67830E-07 1.68630E-07 280730 + 105 280740 Ni-74 1.24210E-07 1.24300E-07 280740 + 106 280750 Ni-75 1.69930E-08 1.69990E-08 280750 + 107 280760 Ni-76 2.74850E-09 2.74850E-09 280760 + 108 280770 Ni-77 1.04360E-10 1.04360E-10 280770 + 109 280780 Ni-78 4.41630E-12 4.41630E-12 280780 + 110 290660 Cu-66 4.31340E-12 7.48390E-08 290660 + 111 290670 Cu-67 1.63770E-10 1.29700E-07 290670 + 112 290680 Cu-68 6.55010E-10 2.26190E-07 290680 + 113 290681 Cu-68m 1.53420E-09 1.53420E-09 290681 + 114 290690 Cu-69 2.78910E-08 3.87480E-07 290690 + 115 290700 Cu-70 9.22560E-09 7.86840E-08 290700 + 116 290701 Cu-70m 1.02780E-07 1.38920E-07 290701 + 117 290702 Cu-70m 9.22560E-09 7.22760E-07 290702 + 118 290710 Cu-71 3.16150E-07 5.34470E-07 290710 + 119 290720 Cu-72 3.46620E-07 5.65980E-07 290720 + 120 290730 Cu-73 7.79020E-07 9.47650E-07 290730 + 121 290740 Cu-74 6.28790E-07 7.53360E-07 290740 + 122 290750 Cu-75 3.92300E-06 3.93970E-06 290750 + 123 290760 Cu-76 6.80800E-07 6.82170E-07 290760 + 124 290761 Cu-76m 6.80800E-07 6.82170E-07 290761 + 125 290770 Cu-77 2.13510E-07 2.13610E-07 290770 + 126 290780 Cu-78 2.14330E-08 2.14370E-08 290780 + 127 290790 Cu-79 1.92090E-09 1.92090E-09 290790 + 128 290800 Cu-80 6.37750E-11 6.37750E-11 290800 + 129 300680 Zn-68 4.29170E-12 2.26440E-07 300680 + 130 300690 Zn-69 2.34510E-11 3.87600E-07 300690 + 131 300691 Zn-69m 1.01420E-10 1.01420E-10 300691 + 132 300700 Zn-70 3.39520E-09 8.38160E-07 300700 + 133 300710 Zn-71 2.96870E-08 5.64160E-07 300710 + 134 300711 Zn-71m 1.28390E-07 1.28390E-07 300711 + 135 300720 Zn-72 4.35250E-07 1.00120E-06 300720 + 136 300730 Zn-73 2.31130E-07 2.38970E-06 300730 + 137 300731 Zn-73m 3.15960E-07 1.21090E-06 300731 + 138 300732 Zn-73m 1.78990E-06 1.78990E-06 300732 + 139 300740 Zn-74 9.43190E-06 1.03230E-05 300740 + 140 300750 Zn-75 1.24220E-05 1.62440E-05 300750 + 141 300760 Zn-76 2.85970E-05 2.99410E-05 300760 + 142 300770 Zn-77 7.77030E-06 8.57790E-06 300770 + 143 300771 Zn-77m 1.18790E-06 1.18790E-06 300771 + 144 300780 Zn-78 1.88830E-05 1.89060E-05 300780 + 145 300790 Zn-79 4.47290E-06 4.47380E-06 300790 + 146 300800 Zn-80 3.87050E-07 3.87110E-07 300800 + 147 300810 Zn-81 2.46110E-08 2.46110E-08 300810 + 148 300820 Zn-82 1.55730E-09 1.55730E-09 300820 + 149 300830 Zn-83 4.29000E-11 4.29000E-11 300830 + 150 310700 Ga-70 1.47780E-12 1.47780E-12 310700 + 151 310710 Ga-71 4.05610E-11 6.92590E-07 310710 + 152 310720 Ga-72 6.35020E-10 1.00190E-06 310720 + 153 310721 Ga-72m 7.15000E-11 3.34330E-08 310721 + 154 310730 Ga-73 4.17430E-08 3.32640E-06 310730 + 155 310740 Ga-74 3.14390E-07 8.29260E-06 310740 + 156 310741 Ga-74m 3.14390E-07 1.06370E-05 310741 + 157 310750 Ga-75 3.26890E-06 1.95130E-05 310750 + 158 310760 Ga-76 6.80780E-06 3.67490E-05 310760 + 159 310770 Ga-77 4.70260E-05 5.61980E-05 310770 + 160 310780 Ga-78 3.43290E-05 5.32930E-05 310780 + 161 310790 Ga-79 4.65310E-05 5.09470E-05 310790 + 162 310800 Ga-80 1.66100E-05 1.69990E-05 310800 + 163 310810 Ga-81 1.43100E-05 1.43330E-05 310810 + 164 310820 Ga-82 1.98080E-06 1.98240E-06 310820 + 165 310830 Ga-83 3.17770E-07 3.17810E-07 310830 + 166 310840 Ga-84 1.51700E-08 1.51700E-08 310840 + 167 310850 Ga-85 5.46940E-10 5.46940E-10 310850 + 168 320730 Ge-73 4.12440E-11 3.32650E-06 32073.82c + 169 320731 Ge-73m 9.53670E-12 3.27760E-06 320731 + 170 320740 Ge-74 4.88790E-09 1.09570E-05 32074.82c + 171 320750 Ge-75 1.13060E-08 1.95980E-05 320750 + 172 320751 Ge-75m 7.39570E-08 8.54490E-07 320751 + 173 320760 Ge-76 6.80740E-06 4.35560E-05 32076.82c + 174 320770 Ge-77 9.71050E-06 2.06700E-05 320770 + 175 320771 Ge-77m 1.48450E-06 5.76820E-05 320771 + 176 320780 Ge-78 6.60560E-05 1.19390E-04 320780 + 177 320790 Ge-79 1.71970E-05 7.25250E-05 320790 + 178 320791 Ge-79m 1.12490E-04 1.12570E-04 320791 + 179 320800 Ge-80 2.95350E-04 3.14050E-04 320800 + 180 320810 Ge-81 2.27470E-04 2.34940E-04 320810 + 181 320811 Ge-81m 5.25970E-05 5.87670E-05 320811 + 182 320820 Ge-82 2.94530E-04 2.96210E-04 320820 + 183 320830 Ge-83 7.92550E-05 7.94660E-05 320830 + 184 320840 Ge-84 3.73910E-05 3.73960E-05 320840 + 185 320850 Ge-85 3.36980E-06 3.37030E-06 320850 + 186 320860 Ge-86 1.86580E-07 1.86580E-07 320860 + 187 320870 Ge-87 5.96610E-09 5.96610E-09 320870 + 188 320880 Ge-88 2.37590E-10 2.37590E-10 320880 + 189 330750 As-75 1.54500E-11 1.95980E-05 33075.82c + 190 330751 As-75m 5.05460E-11 3.06890E-10 330751 + 191 330760 As-76 3.19720E-09 3.19720E-09 330760 + 192 330770 As-77 1.03560E-07 6.74960E-05 330770 + 193 330780 As-78 8.58120E-07 1.20250E-04 330780 + 194 330790 As-79 1.60990E-05 1.96690E-04 330790 + 195 330800 As-80 5.76210E-05 3.71680E-04 330800 + 196 330810 As-81 2.32300E-04 5.25420E-04 330810 + 197 330820 As-82 9.49500E-05 3.91160E-04 330820 + 198 330821 As-82m 2.86530E-04 2.86530E-04 330821 + 199 330830 As-83 7.38500E-04 8.22010E-04 330830 + 200 330840 As-84 2.35300E-04 2.52220E-04 330840 + 201 330841 As-84m 2.35300E-04 2.52220E-04 330841 + 202 330850 As-85 2.95870E-04 2.98770E-04 330850 + 203 330860 As-86 7.54420E-05 7.56290E-05 330860 + 204 330870 As-87 2.38530E-05 2.38590E-05 330870 + 205 330880 As-88 2.04400E-06 2.04420E-06 330880 + 206 330890 As-89 6.00590E-08 6.00590E-08 330890 + 207 330900 As-90 1.31110E-09 1.31110E-09 330900 + 208 340770 Se-77 4.52900E-12 6.74960E-05 34077.82c + 209 340771 Se-77m 2.96260E-11 2.96260E-11 340771 + 210 340780 Se-78 2.87500E-09 1.20260E-04 34078.82c + 211 340790 Se-79 7.75800E-07 1.97480E-04 34079.82c + 212 340791 Se-79m 1.18600E-07 1.92150E-04 340791 + 213 340800 Se-80 7.80630E-06 3.79480E-04 34080.82c + 214 340810 Se-81 5.79180E-06 5.69070E-04 340810 + 215 340811 Se-81m 3.78870E-05 5.67490E-05 340811 + 216 340820 Se-82 2.04050E-04 8.81740E-04 34082.82c + 217 340830 Se-83 5.54250E-04 8.50530E-04 340830 + 218 340831 Se-83m 1.28160E-04 6.54590E-04 340831 + 219 340840 Se-84 1.58840E-03 2.15790E-03 340840 + 220 340850 Se-85 1.87300E-03 2.13100E-03 340850 + 221 340860 Se-86 1.95300E-03 2.00740E-03 340860 + 222 340870 Se-87 1.11770E-03 1.13790E-03 340870 + 223 340880 Se-88 4.67130E-04 4.69170E-04 340880 + 224 340890 Se-89 8.94290E-05 8.94890E-05 340890 + 225 340900 Se-90 1.67600E-05 1.67610E-05 340900 + 226 340910 Se-91 3.76900E-07 3.76900E-07 340910 + 227 340920 Se-92 1.97030E-08 1.97030E-08 340920 + 228 340930 Se-93 5.84910E-10 5.84910E-10 340930 + 229 350790 Br-79 4.36600E-12 1.07620E-07 35079.82c + 230 350791 Br-79m 1.42840E-11 1.42840E-11 350791 + 231 350800 Br-80 2.76650E-10 1.11150E-09 350800 + 232 350801 Br-80m 8.34850E-10 8.34850E-10 350801 + 233 350810 Br-81 6.06330E-08 5.69160E-04 35081.82c + 234 350820 Br-82 3.80690E-06 5.39320E-06 350820 + 235 350821 Br-82m 1.62530E-06 1.62530E-06 350821 + 236 350830 Br-83 1.48360E-05 1.52000E-03 350830 + 237 350840 Br-84 6.59400E-05 2.22380E-03 350840 + 238 350841 Br-84m 6.59400E-05 6.59400E-05 350841 + 239 350850 Br-85 6.23670E-04 2.75470E-03 350850 + 240 350860 Br-86 1.26210E-03 3.26950E-03 350860 + 241 350870 Br-87 2.60270E-03 3.74520E-03 350870 + 242 350880 Br-88 2.49580E-03 2.96730E-03 350880 + 243 350890 Br-89 1.87700E-03 1.95950E-03 350890 + 244 350900 Br-90 6.98010E-04 7.14850E-04 350900 + 245 350910 Br-91 3.17480E-04 3.17780E-04 350910 + 246 350920 Br-92 5.10960E-05 5.11160E-05 350920 + 247 350930 Br-93 7.95730E-06 7.95790E-06 350930 + 248 350940 Br-94 1.24090E-07 1.24090E-07 350940 + 249 350950 Br-95 3.83700E-09 3.83700E-09 350950 + 250 360820 Kr-82 6.48880E-10 5.43290E-06 36082.82c + 251 360830 Kr-83 2.55410E-08 1.52000E-03 36083.82c + 252 360831 Kr-83m 5.90570E-09 1.51860E-03 360831 + 253 360840 Kr-84 2.25590E-06 2.29200E-03 36084.82c + 254 360850 Kr-85 2.64530E-05 6.20780E-04 36085.82c + 255 360851 Kr-85m 6.11650E-06 2.75630E-03 360851 + 256 360860 Kr-86 3.81260E-04 3.74470E-03 36086.82c + 257 360870 Kr-87 1.28660E-03 5.13660E-03 360870 + 258 360880 Kr-88 3.41120E-03 6.45600E-03 360880 + 259 360890 Kr-89 5.28770E-03 7.14680E-03 360890 + 260 360900 Kr-90 6.31950E-03 6.92200E-03 360900 + 261 360910 Kr-91 4.99960E-03 5.27070E-03 360910 + 262 360920 Kr-92 3.36440E-03 3.40400E-03 360920 + 263 360930 Kr-93 1.26460E-03 1.26720E-03 360930 + 264 360940 Kr-94 3.97120E-04 3.97160E-04 360940 + 265 360950 Kr-95 5.15060E-05 5.15100E-05 360950 + 266 360960 Kr-96 5.62380E-06 5.62380E-06 360960 + 267 360970 Kr-97 2.76700E-08 2.76700E-08 360970 + 268 360980 Kr-98 1.27920E-09 1.27920E-09 360980 + 269 370840 Rb-84 5.95620E-11 1.66700E-10 370840 + 270 370841 Rb-84m 1.07140E-10 1.07140E-10 370841 + 271 370850 Rb-85 1.26710E-08 2.78720E-03 37085.82c + 272 370860 Rb-86 3.98000E-07 1.11390E-06 37086.82c + 273 370861 Rb-86m 7.15900E-07 7.15900E-07 370861 + 274 370870 Rb-87 1.58510E-05 5.15250E-03 37087.82c + 275 370880 Rb-88 1.26620E-04 6.58260E-03 370880 + 276 370890 Rb-89 6.92190E-04 7.83900E-03 370890 + 277 370900 Rb-90 1.83080E-04 6.26550E-03 370900 + 278 370901 Rb-90m 1.62600E-03 2.53140E-03 370901 + 279 370910 Rb-91 4.56350E-03 9.83420E-03 370910 + 280 370920 Rb-92 6.40070E-03 9.80470E-03 370920 + 281 370930 Rb-93 8.27690E-03 9.54850E-03 370930 + 282 370940 Rb-94 4.54590E-03 4.94010E-03 370940 + 283 370950 Rb-95 2.45690E-03 2.50710E-03 370950 + 284 370960 Rb-96 3.38600E-04 5.11960E-04 370960 + 285 370961 Rb-96m 3.38600E-04 3.41310E-04 370961 + 286 370970 Rb-97 1.88950E-04 1.88980E-04 370970 + 287 370980 Rb-98 7.39050E-06 7.39050E-06 370980 + 288 370981 Rb-98m 7.39050E-06 7.39170E-06 370981 + 289 370990 Rb-99 3.37020E-06 3.37020E-06 370990 + 290 371000 Rb-100 4.74760E-09 4.74760E-09 371000 + 291 380870 Sr-87 2.65350E-09 3.26530E-09 38087.82c + 292 380871 Sr-87m 6.13560E-10 6.13560E-10 380871 + 293 380880 Sr-88 3.06530E-06 6.58570E-03 38088.82c + 294 380890 Sr-89 2.50830E-05 7.86400E-03 38089.82c + 295 380900 Sr-90 2.52220E-04 8.98340E-03 38090.82c + 296 380910 Sr-91 1.04340E-03 1.08780E-02 380910 + 297 380920 Sr-92 4.46000E-03 1.43980E-02 380920 + 298 380930 Sr-93 1.04250E-02 2.03390E-02 380930 + 299 380940 Sr-94 1.74480E-02 2.21050E-02 380940 + 300 380950 Sr-95 1.41600E-02 1.65200E-02 380950 + 301 380960 Sr-96 1.14590E-02 1.21200E-02 380960 + 302 380970 Sr-97 5.49290E-03 5.63550E-03 380970 + 303 380980 Sr-98 2.36890E-03 2.38320E-03 380980 + 304 380990 Sr-99 5.13780E-04 5.16610E-04 380990 + 305 381000 Sr-100 1.55060E-04 1.55060E-04 381000 + 306 381010 Sr-101 1.55330E-05 1.55330E-05 381010 + 307 381020 Sr-102 2.49030E-06 2.49030E-06 381020 + 308 390890 Y-89 1.40400E-10 7.86400E-03 39089.82c + 309 390891 Y-89m 6.07210E-10 7.58630E-07 390891 + 310 390900 Y-90 1.42730E-08 8.98340E-03 39090.82c + 311 390901 Y-90m 2.02530E-08 2.02530E-08 390901 + 312 390910 Y-91 1.88570E-06 1.08880E-02 39091.82c + 313 390911 Y-91m 8.15530E-06 6.40810E-03 390911 + 314 390920 Y-92 7.15050E-05 1.44700E-02 390920 + 315 390930 Y-93 8.26310E-05 2.09620E-02 390930 + 316 390931 Y-93m 5.40530E-04 5.63010E-03 390931 + 317 390940 Y-94 2.00270E-03 2.41080E-02 390940 + 318 390950 Y-95 6.71940E-03 2.32390E-02 390950 + 319 390960 Y-96 4.10970E-03 1.62310E-02 390960 + 320 390961 Y-96m 7.39230E-03 7.39370E-03 390961 + 321 390970 Y-97 3.14040E-03 8.03180E-03 390970 + 322 390971 Y-97m 1.07040E-02 1.38430E-02 390971 + 323 390972 Y-97m 2.87620E-03 2.87620E-03 390972 + 324 390980 Y-98 2.30080E-03 4.68400E-03 390980 + 325 390981 Y-98m 9.67620E-03 9.67620E-03 390981 + 326 390990 Y-99 8.73690E-03 9.25470E-03 390990 + 327 391000 Y-100 2.17070E-03 2.32470E-03 391000 + 328 391001 Y-100m 2.17070E-03 2.17080E-03 391001 + 329 391010 Y-101 2.09620E-03 2.11150E-03 391010 + 330 391020 Y-102 1.90140E-04 1.91320E-04 391020 + 331 391021 Y-102m 1.90140E-04 1.91320E-04 391021 + 332 391030 Y-103 7.13960E-05 7.13960E-05 391030 + 333 391040 Y-104 8.85440E-06 8.85440E-06 391040 + 334 391050 Y-105 8.26030E-09 8.26030E-09 391050 + 335 400920 Zr-92 9.64250E-07 1.44710E-02 40092.82c + 336 400930 Zr-93 1.59250E-05 2.09780E-02 40093.82c + 337 400940 Zr-94 1.10870E-04 2.42180E-02 40094.82c + 338 400950 Zr-95 6.29390E-04 2.38690E-02 40095.82c + 339 400960 Zr-96 3.48710E-03 2.71230E-02 40096.82c + 340 400970 Zr-97 8.32250E-03 3.10100E-02 400970 + 341 400980 Zr-98 2.05820E-02 3.47540E-02 400980 + 342 400990 Zr-99 2.31040E-02 3.22230E-02 400990 + 343 401000 Zr-100 3.12690E-02 3.57430E-02 401000 + 344 401010 Zr-101 2.13410E-02 2.34710E-02 401010 + 345 401020 Zr-102 1.34980E-02 1.38680E-02 401020 + 346 401030 Zr-103 3.99740E-03 4.06390E-03 401030 + 347 401040 Zr-104 1.26300E-03 1.27110E-03 401040 + 348 401050 Zr-105 1.93070E-04 1.93080E-04 401050 + 349 401060 Zr-106 2.19920E-05 2.19920E-05 401060 + 350 401070 Zr-107 1.88850E-06 1.88850E-06 401070 + 351 410940 Nb-94 1.37340E-09 2.33650E-09 41094.82c + 352 410941 Nb-94m 9.67890E-10 9.67890E-10 410941 + 353 410950 Nb-95 7.61110E-07 2.38550E-02 41095.82c + 354 410951 Nb-95m 1.75990E-07 2.58040E-04 410951 + 355 410960 Nb-96 2.90790E-05 2.90790E-05 410960 + 356 410970 Nb-97 1.87250E-04 3.12410E-02 410970 + 357 410971 Nb-97m 4.32970E-05 2.95180E-02 410971 + 358 410980 Nb-98 2.50370E-04 3.50040E-02 410980 + 359 410981 Nb-98m 7.55530E-04 7.55530E-04 410981 + 360 410990 Nb-99 3.62220E-03 2.42410E-02 410990 + 361 410991 Nb-99m 8.37530E-04 1.26960E-02 410991 + 362 411000 Nb-100 2.24240E-03 3.79850E-02 411000 + 363 411001 Nb-100m 9.43060E-03 9.43060E-03 411001 + 364 411010 Nb-101 2.93610E-02 5.28320E-02 411010 + 365 411020 Nb-102 1.51810E-02 2.90490E-02 411020 + 366 411021 Nb-102m 1.51810E-02 1.51810E-02 411021 + 367 411030 Nb-103 2.75880E-02 3.16520E-02 411030 + 368 411040 Nb-104 7.35600E-03 8.62980E-03 411040 + 369 411041 Nb-104m 7.35600E-03 7.35600E-03 411041 + 370 411050 Nb-105 8.41230E-03 8.60300E-03 411050 + 371 411060 Nb-106 2.09970E-03 2.12140E-03 411060 + 372 411070 Nb-107 6.13660E-04 6.15480E-04 411070 + 373 411080 Nb-108 7.83010E-05 7.83010E-05 411080 + 374 411090 Nb-109 7.95790E-06 7.95790E-06 411090 + 375 411100 Nb-110 3.01310E-09 3.01310E-09 411100 + 376 420960 Mo-96 1.02240E-09 2.90800E-05 42096.82c + 377 420970 Mo-97 4.57350E-06 3.12450E-02 42097.82c + 378 420980 Mo-98 3.39490E-05 3.57940E-02 42098.82c + 379 420990 Mo-99 1.84960E-04 3.68670E-02 42099.82c + 380 421000 Mo-100 1.67240E-03 4.90890E-02 42100.82c + 381 421010 Mo-101 6.23380E-03 5.90660E-02 421010 + 382 421020 Mo-102 2.06980E-02 6.49280E-02 421020 + 383 421030 Mo-103 2.92910E-02 6.09520E-02 421030 + 384 421040 Mo-104 4.37160E-02 5.98390E-02 421040 + 385 421050 Mo-105 3.32460E-02 4.17980E-02 421050 + 386 421060 Mo-106 2.28850E-02 2.49480E-02 421060 + 387 421070 Mo-107 1.02470E-02 1.08300E-02 421070 + 388 421080 Mo-108 4.72710E-03 4.80150E-03 421080 + 389 421090 Mo-109 1.11490E-03 1.12180E-03 421090 + 390 421100 Mo-110 2.52580E-04 2.52580E-04 421100 + 391 421110 Mo-111 2.43280E-05 2.43280E-05 421110 + 392 421120 Mo-112 2.43940E-08 2.43940E-08 421120 + 393 430990 Tc-99 4.64020E-09 3.68660E-02 43099.82c + 394 430991 Tc-99m 1.07290E-09 3.24650E-02 430991 + 395 431000 Tc-100 3.07500E-06 3.07500E-06 431000 + 396 431010 Tc-101 1.00540E-04 5.91670E-02 431010 + 397 431020 Tc-102 2.67650E-04 6.51950E-02 431020 + 398 431021 Tc-102m 2.67650E-04 2.67650E-04 431021 + 399 431030 Tc-103 2.74800E-03 6.37000E-02 431030 + 400 431040 Tc-104 7.55360E-03 6.73930E-02 431040 + 401 431050 Tc-105 2.09690E-02 6.27670E-02 431050 + 402 431060 Tc-106 2.42800E-02 4.92280E-02 431060 + 403 431070 Tc-107 3.07640E-02 4.15940E-02 431070 + 404 431080 Tc-108 2.07060E-02 2.55140E-02 431080 + 405 431090 Tc-109 1.42910E-02 1.54070E-02 431090 + 406 431100 Tc-110 6.41530E-03 6.66810E-03 431100 + 407 431110 Tc-111 2.50380E-03 2.52790E-03 431110 + 408 431120 Tc-112 5.64800E-04 5.64820E-04 431120 + 409 431130 Tc-113 1.04620E-04 1.04620E-04 431130 + 410 431140 Tc-114 6.57270E-06 6.57270E-06 431140 + 411 431150 Tc-115 5.62510E-10 5.62510E-10 431150 + 412 441010 Ru-101 1.66140E-09 5.91670E-02 44101.82c + 413 441020 Ru-102 1.24520E-06 6.54640E-02 44102.82c + 414 441030 Ru-103 1.86680E-05 6.37640E-02 44103.82c + 415 441031 Ru-103m 4.50680E-05 4.50680E-05 441031 + 416 441040 Ru-104 5.17250E-04 6.79100E-02 44104.82c + 417 441050 Ru-105 1.95600E-03 6.47230E-02 44105.82c + 418 441060 Ru-106 6.85360E-03 5.60810E-02 44106.82c + 419 441070 Ru-107 1.32980E-02 5.48920E-02 441070 + 420 441080 Ru-108 2.60720E-02 5.15980E-02 441080 + 421 441090 Ru-109 2.42230E-02 3.96200E-02 441090 + 422 441100 Ru-110 2.54270E-02 3.20930E-02 441100 + 423 441110 Ru-111 1.36910E-02 1.62270E-02 441110 + 424 441120 Ru-112 9.76860E-03 1.03320E-02 441120 + 425 441130 Ru-113 1.20640E-03 1.90710E-03 441130 + 426 441131 Ru-113m 1.20640E-03 1.20640E-03 441131 + 427 441140 Ru-114 5.04780E-04 5.10920E-04 441140 + 428 441150 Ru-115 5.52210E-05 5.52210E-05 441150 + 429 441160 Ru-116 8.12070E-06 8.12070E-06 441160 + 430 441170 Ru-117 2.03420E-06 2.03420E-06 441170 + 431 451040 Rh-104 2.04120E-09 8.19290E-09 451040 + 432 451041 Rh-104m 6.15970E-09 6.15970E-09 451041 + 433 451050 Rh-105 1.72650E-05 6.47430E-02 45105.82c + 434 451051 Rh-105m 2.63930E-06 1.83760E-02 451051 + 435 451060 Rh-106 2.77860E-05 5.61090E-02 451060 + 436 451061 Rh-106m 6.50820E-05 6.50820E-05 451061 + 437 451070 Rh-107 5.33060E-04 5.54260E-02 451070 + 438 451080 Rh-108 4.79160E-04 5.20770E-02 451080 + 439 451081 Rh-108m 1.44590E-03 1.44590E-03 451081 + 440 451090 Rh-109 5.24890E-03 4.48690E-02 451090 + 441 451100 Rh-110 8.86880E-03 4.09610E-02 451100 + 442 451101 Rh-110m 2.36750E-04 2.36750E-04 451101 + 443 451110 Rh-111 1.45480E-02 3.07750E-02 451110 + 444 451120 Rh-112 8.01050E-03 1.83430E-02 451120 + 445 451121 Rh-112m 8.01050E-03 8.01050E-03 451121 + 446 451130 Rh-113 1.24390E-02 1.49490E-02 451130 + 447 451140 Rh-114 2.31900E-03 2.83000E-03 451140 + 448 451141 Rh-114m 2.31900E-03 2.31900E-03 451141 + 449 451150 Rh-115 1.75630E-03 1.81150E-03 451150 + 450 451160 Rh-116 1.05640E-04 1.13720E-04 451160 + 451 451161 Rh-116m 2.47440E-04 2.47440E-04 451161 + 452 451170 Rh-117 9.80720E-05 1.00060E-04 451170 + 453 451180 Rh-118 2.26580E-05 2.26580E-05 451180 + 454 451190 Rh-119 6.49940E-06 6.49940E-06 451190 + 455 451200 Rh-120 3.09870E-06 3.09870E-06 451200 + 456 451210 Rh-121 6.23720E-07 6.23720E-07 451210 + 457 461060 Pd-106 2.10120E-09 5.61740E-02 46106.82c + 458 461070 Pd-107 1.63970E-06 5.54300E-02 46107.82c + 459 461071 Pd-107m 3.08160E-06 3.08160E-06 461071 + 460 461080 Pd-108 6.15640E-05 5.35850E-02 46108.82c + 461 461090 Pd-109 8.36790E-05 4.51100E-02 461090 + 462 461091 Pd-109m 1.57260E-04 2.25920E-02 461091 + 463 461100 Pd-110 1.06470E-03 4.22630E-02 46110.82c + 464 461110 Pd-111 7.50830E-04 3.25230E-02 461110 + 465 461111 Pd-111m 1.41110E-03 1.53420E-03 461111 + 466 461120 Pd-112 5.75340E-03 3.21070E-02 461120 + 467 461130 Pd-113 1.75680E-03 2.09470E-02 461130 + 468 461131 Pd-113m 4.24100E-03 4.24100E-03 461131 + 469 461140 Pd-114 5.67950E-03 1.08280E-02 461140 + 470 461150 Pd-115 1.05310E-03 2.78090E-03 461150 + 471 461151 Pd-115m 1.97920E-03 2.24220E-03 461151 + 472 461160 Pd-116 1.71270E-03 2.07380E-03 461160 + 473 461170 Pd-117 1.81320E-04 6.22810E-04 461170 + 474 461171 Pd-117m 3.40760E-04 3.40760E-04 461171 + 475 461180 Pd-118 2.05400E-04 2.27400E-04 461180 + 476 461190 Pd-119 4.29730E-05 4.96560E-05 461190 + 477 461200 Pd-120 1.98490E-05 2.28490E-05 461200 + 478 461210 Pd-121 2.49520E-06 3.03430E-06 461210 + 479 461220 Pd-122 1.27870E-06 1.27870E-06 461220 + 480 461240 Pd-124 6.96880E-08 6.96880E-08 461240 + 481 471090 Ag-109 2.34500E-07 4.51120E-02 47109.82c + 482 471091 Ag-109m 1.53400E-06 4.50900E-02 471091 + 483 471100 Ag-110 2.99830E-06 3.09380E-06 471100 + 484 471101 Ag-110m 7.02270E-06 7.02270E-06 47510.82c + 485 471110 Ag-111 7.91760E-06 3.28340E-02 47111.82c + 486 471111 Ag-111m 5.17930E-05 3.26400E-02 471111 + 487 471120 Ag-112 2.20720E-04 3.23280E-02 471120 + 488 471130 Ag-113 7.87530E-05 1.41340E-02 471130 + 489 471131 Ag-113m 5.15160E-04 2.05740E-02 471131 + 490 471140 Ag-114 1.57780E-04 1.16500E-02 471140 + 491 471141 Ag-114m 6.63540E-04 6.63540E-04 471141 + 492 471150 Ag-115 1.46140E-04 2.96790E-03 471150 + 493 471151 Ag-115m 9.55960E-04 3.76960E-03 471151 + 494 471160 Ag-116 2.55890E-04 2.36570E-03 471160 + 495 471161 Ag-116m 5.99360E-04 5.99360E-04 471161 + 496 471170 Ag-117 9.00620E-05 4.55500E-04 471170 + 497 471171 Ag-117m 5.89140E-04 9.00540E-04 471171 + 498 471180 Ag-118 6.61550E-05 3.88450E-04 471180 + 499 471181 Ag-118m 2.78230E-04 3.10730E-04 471181 + 500 471190 Ag-119 2.09190E-05 4.57470E-05 471190 + 501 471191 Ag-119m 1.36840E-04 1.61670E-04 471191 + 502 471200 Ag-120 2.07480E-05 4.73010E-05 471200 + 503 471201 Ag-120m 2.94410E-05 4.08650E-05 471201 + 504 471210 Ag-121 3.43130E-05 3.73390E-05 471210 + 505 471220 Ag-122 7.06450E-06 8.34320E-06 471220 + 506 471221 Ag-122m 6.36350E-06 6.36350E-06 471221 + 507 471230 Ag-123 1.50880E-05 1.50880E-05 471230 + 508 471240 Ag-124 9.18200E-06 1.33870E-05 471240 + 509 471241 Ag-124m 8.27100E-06 8.27100E-06 471241 + 510 471250 Ag-125 1.21930E-05 1.21930E-05 471250 + 511 471260 Ag-126 1.56330E-06 1.56330E-06 471260 + 512 471270 Ag-127 1.46420E-07 1.46420E-07 471270 + 513 471280 Ag-128 5.28160E-09 5.28160E-09 471280 + 514 471290 Ag-129 3.40440E-10 3.40440E-10 471290 + 515 481110 Cd-111 2.14300E-10 3.29970E-02 48111.82c + 516 481111 Cd-111m 7.01110E-10 7.01110E-10 481111 + 517 481120 Cd-112 3.22000E-06 3.23310E-02 48112.82c + 518 481130 Cd-113 1.81370E-06 2.12990E-02 48113.82c + 519 481131 Cd-113m 5.93400E-06 2.50300E-04 481131 + 520 481140 Cd-114 5.07500E-05 1.17010E-02 48114.82c + 521 481150 Cd-115 1.89460E-05 5.70710E-03 481150 + 522 481151 Cd-115m 6.19840E-05 3.19700E-04 48515.82c + 523 481160 Cd-116 1.51710E-04 3.08080E-03 48116.82c + 524 481170 Cd-117 3.89870E-05 1.05420E-03 481170 + 525 481171 Cd-117m 1.27550E-04 4.14350E-04 481171 + 526 481180 Cd-118 1.66390E-04 7.38170E-04 481180 + 527 481190 Cd-119 2.69860E-05 2.11530E-04 481190 + 528 481191 Cd-119m 6.51480E-05 8.80220E-05 481191 + 529 481200 Cd-120 9.22420E-05 1.65290E-04 481200 + 530 481210 Cd-121 2.00930E-05 5.35310E-05 481210 + 531 481211 Cd-121m 4.85080E-05 5.24100E-05 481211 + 532 481220 Cd-122 7.48190E-05 8.95260E-05 481220 + 533 481230 Cd-123 2.13990E-05 3.37500E-05 481230 + 534 481231 Cd-123m 5.16610E-05 5.44110E-05 481231 + 535 481240 Cd-124 1.75460E-04 1.92970E-04 481240 + 536 481250 Cd-125 4.07450E-05 4.68420E-05 481250 + 537 481251 Cd-125m 9.83650E-05 1.04460E-04 481251 + 538 481260 Cd-126 1.91760E-04 1.93320E-04 481260 + 539 481270 Cd-127 9.00160E-05 9.01620E-05 481270 + 540 481280 Cd-128 3.77140E-05 3.77190E-05 481280 + 541 481290 Cd-129 2.00540E-06 2.00550E-06 481290 + 542 481291 Cd-129m 4.84120E-06 4.84140E-06 481291 + 543 481300 Cd-130 1.33340E-07 1.33340E-07 481300 + 544 481310 Cd-131 4.26500E-09 4.26500E-09 481310 + 545 491140 In-114 4.85160E-10 1.89780E-09 491140 + 546 491141 In-114m 7.43620E-10 1.46390E-09 491141 + 547 491142 In-114m 7.20230E-10 7.20230E-10 491142 + 548 491150 In-115 4.52300E-08 5.74150E-03 49115.82c + 549 491151 In-115m 1.04580E-08 5.70720E-03 491151 + 550 491160 In-116 6.73450E-07 6.73450E-07 491160 + 551 491161 In-116m 1.03220E-06 2.03200E-06 491161 + 552 491162 In-116m 9.99760E-07 9.99760E-07 491162 + 553 491170 In-117 6.05550E-06 9.60860E-04 491170 + 554 491171 In-117m 1.40020E-06 9.73800E-04 491171 + 555 491180 In-118 4.63580E-06 7.42800E-04 491180 + 556 491181 In-118m 7.10540E-06 1.38910E-05 491181 + 557 491182 In-118m 6.88190E-06 6.88190E-06 491182 + 558 491190 In-119 1.84580E-05 1.37800E-04 491190 + 559 491191 In-119m 4.26790E-06 1.95420E-04 491191 + 560 491200 In-120 6.19340E-06 1.71480E-04 491200 + 561 491201 In-120m 6.19340E-06 6.19340E-06 491201 + 562 491202 In-120m 6.19340E-06 6.19340E-06 491202 + 563 491210 In-121 2.58260E-05 9.67630E-05 491210 + 564 491211 In-121m 5.97170E-06 4.14740E-05 491211 + 565 491220 In-122 1.79680E-05 1.07490E-04 491220 + 566 491221 In-122m 1.27480E-05 1.27480E-05 491221 + 567 491222 In-122m 1.27480E-05 1.27480E-05 491222 + 568 491230 In-123 7.10650E-05 1.35270E-04 491230 + 569 491231 In-123m 1.64320E-05 4.03920E-05 491231 + 570 491240 In-124 6.93500E-05 2.62320E-04 491240 + 571 491241 In-124m 6.24690E-05 6.24690E-05 491241 + 572 491250 In-125 3.44800E-04 4.71690E-04 491250 + 573 491251 In-125m 7.97270E-05 1.04150E-04 491251 + 574 491260 In-126 4.56290E-04 6.49610E-04 491260 + 575 491261 In-126m 4.11010E-04 4.11010E-04 491261 + 576 491270 In-127 1.33390E-03 1.33390E-03 491270 + 577 491271 In-127m 3.08420E-04 3.98590E-04 491271 + 578 491280 In-128 4.08670E-04 6.12750E-04 491280 + 579 491281 In-128m 1.66360E-04 2.04070E-04 491281 + 580 491282 In-128m 5.17970E-04 5.17970E-04 491282 + 581 491290 In-129 6.13230E-04 6.18070E-04 491290 + 582 491291 In-129m 1.41790E-04 1.43800E-04 491291 + 583 491300 In-130 7.61410E-05 7.62700E-05 491300 + 584 491301 In-130m 8.50430E-05 8.50430E-05 491301 + 585 491302 In-130m 1.44690E-04 1.44690E-04 491302 + 586 491310 In-131 2.66910E-05 2.69670E-05 491310 + 587 491311 In-131m 2.66910E-05 2.66910E-05 491311 + 588 491312 In-131m 2.66910E-05 2.66910E-05 491312 + 589 491320 In-132 2.29970E-06 2.29970E-06 491320 + 590 491330 In-133 4.82350E-08 5.93880E-08 491330 + 591 491331 In-133m 1.11530E-08 1.11530E-08 491331 + 592 491340 In-134 1.46360E-09 1.46360E-09 491340 + 593 501160 Sn-116 1.12460E-10 2.70550E-06 50116.82c + 594 501170 Sn-117 5.08180E-10 1.47600E-03 50117.82c + 595 501171 Sn-117m 1.66260E-09 3.27540E-06 501171 + 596 501180 Sn-118 4.61500E-08 7.56840E-04 50118.82c + 597 501190 Sn-119 3.04140E-07 3.23580E-04 50119.82c + 598 501191 Sn-119m 9.95060E-07 1.25480E-04 501191 + 599 501200 Sn-120 2.08900E-06 1.85960E-04 50120.82c + 600 501210 Sn-121 5.47990E-07 1.36860E-04 501210 + 601 501211 Sn-121m 1.32290E-06 1.22850E-05 501211 + 602 501220 Sn-122 4.47400E-06 1.37480E-04 50122.82c + 603 501230 Sn-123 1.32140E-05 2.35260E-05 50123.82c + 604 501231 Sn-123m 5.47340E-06 1.70820E-04 501231 + 605 501240 Sn-124 6.71710E-05 3.91960E-04 50124.82c + 606 501250 Sn-125 1.22290E-04 2.01960E-04 50125.82c + 607 501251 Sn-125m 5.06540E-05 5.46810E-04 501251 + 608 501260 Sn-126 9.06820E-04 1.97020E-03 50126.82c + 609 501270 Sn-127 1.60670E-03 2.12660E-03 501270 + 610 501271 Sn-127m 6.65530E-04 1.87530E-03 501271 + 611 501280 Sn-128 1.36960E-03 5.70830E-03 501280 + 612 501281 Sn-128m 3.20800E-03 3.72600E-03 501281 + 613 501290 Sn-129 1.58880E-03 2.28500E-03 501290 + 614 501291 Sn-129m 3.83570E-03 3.90150E-03 501291 + 615 501300 Sn-130 2.03260E-03 2.23180E-03 501300 + 616 501301 Sn-130m 4.76090E-03 4.86830E-03 501301 + 617 501310 Sn-131 1.21590E-03 1.26760E-03 501310 + 618 501311 Sn-131m 2.93550E-03 2.96330E-03 501311 + 619 501320 Sn-132 1.90640E-03 1.90880E-03 501320 + 620 501330 Sn-133 1.77810E-04 1.77820E-04 501330 + 621 501340 Sn-134 2.44360E-05 2.44360E-05 501340 + 622 501350 Sn-135 3.99020E-07 3.99020E-07 501350 + 623 501360 Sn-136 1.13510E-08 1.13510E-08 501360 + 624 511190 Sb-119 6.17610E-11 8.13930E-11 511190 + 625 511191 Sb-119m 1.96320E-11 1.96320E-11 511191 + 626 511200 Sb-120 6.19440E-10 6.19440E-10 511200 + 627 511201 Sb-120m 8.78960E-10 8.78960E-10 511201 + 628 511210 Sb-121 3.48370E-08 1.39650E-04 51121.82c + 629 511220 Sb-122 2.99630E-07 6.39280E-07 511220 + 630 511221 Sb-122m 3.39650E-07 3.39650E-07 511221 + 631 511230 Sb-123 5.12510E-06 1.99470E-04 51123.82c + 632 511240 Sb-124 8.59700E-07 2.01950E-06 51124.82c + 633 511241 Sb-124m 6.57350E-07 1.54640E-06 511241 + 634 511242 Sb-124m 8.89050E-07 8.89050E-07 511242 + 635 511250 Sb-125 1.68180E-05 7.65590E-04 51125.82c + 636 511260 Sb-126 1.98910E-05 2.46430E-05 51126.82c + 637 511261 Sb-126m 1.47070E-05 3.39420E-05 511261 + 638 511262 Sb-126m 1.92350E-05 1.92350E-05 511262 + 639 511270 Sb-127 3.83600E-04 4.38550E-03 511270 + 640 511280 Sb-128 3.53810E-04 6.08390E-03 511280 + 641 511281 Sb-128m 6.03730E-04 6.03730E-04 511281 + 642 511290 Sb-129 2.61170E-03 7.37930E-03 511290 + 643 511291 Sb-129m 1.59590E-03 3.54660E-03 511291 + 644 511300 Sb-130 4.18140E-03 8.84740E-03 511300 + 645 511301 Sb-130m 4.18140E-03 6.61560E-03 511301 + 646 511310 Sb-131 1.80480E-02 2.22790E-02 511310 + 647 511320 Sb-132 1.06530E-02 1.25620E-02 511320 + 648 511321 Sb-132m 7.85170E-03 7.85170E-03 511321 + 649 511330 Sb-133 1.27290E-02 1.29110E-02 511330 + 650 511340 Sb-134 8.28130E-04 8.48450E-04 511340 + 651 511341 Sb-134m 1.93970E-03 1.93970E-03 511341 + 652 511350 Sb-135 6.62580E-04 6.62900E-04 511350 + 653 511360 Sb-136 9.63670E-05 9.63750E-05 511360 + 654 511370 Sb-137 1.17340E-05 1.17340E-05 511370 + 655 511380 Sb-138 5.60250E-08 5.60250E-08 511380 + 656 511390 Sb-139 2.26740E-09 2.26740E-09 511390 + 657 521210 Te-121 9.23760E-13 3.60450E-12 521210 + 658 521211 Te-121m 3.02220E-12 3.02220E-12 521211 + 659 521220 Te-122 3.04570E-10 6.22960E-07 52122.82c + 660 521230 Te-123 2.38290E-09 1.01790E-08 52123.82c + 661 521231 Te-123m 7.79610E-09 7.79610E-09 521231 + 662 521250 Te-125 2.02190E-11 7.65590E-04 52125.82c + 663 521251 Te-125m 6.61490E-11 1.71310E-04 521251 + 664 521260 Te-126 1.56310E-06 5.53960E-05 52126.82c + 665 521270 Te-127 7.80170E-07 4.37080E-03 521270 + 666 521271 Te-127m 1.88340E-06 7.24590E-04 52527.82c + 667 521280 Te-128 5.67920E-05 6.72270E-03 52128.82c + 668 521290 Te-129 9.13090E-05 9.08170E-03 521290 + 669 521291 Te-129m 2.20430E-04 4.38910E-03 52529.82c + 670 521300 Te-130 2.30550E-03 1.77680E-02 52130.82c + 671 521310 Te-131 2.06370E-03 2.39800E-02 521310 + 672 521311 Te-131m 4.98190E-03 6.76560E-03 521311 + 673 521320 Te-132 2.52950E-02 4.57090E-02 52132.82c + 674 521330 Te-133 9.89770E-03 2.51500E-02 521330 + 675 521331 Te-133m 2.38940E-02 2.61270E-02 521331 + 676 521340 Te-134 3.49960E-02 3.78870E-02 521340 + 677 521350 Te-135 1.36590E-02 1.42330E-02 521350 + 678 521360 Te-136 5.83700E-03 5.92320E-03 521360 + 679 521370 Te-137 1.18900E-03 1.19500E-03 521370 + 680 521380 Te-138 3.24820E-04 3.24880E-04 521380 + 681 521390 Te-139 3.51720E-05 3.51740E-05 521390 + 682 521400 Te-140 1.18730E-06 1.18730E-06 521400 + 683 521410 Te-141 7.59250E-09 7.59250E-09 521410 + 684 531270 I-127 1.38910E-10 4.38820E-03 53127.82c + 685 531280 I-128 4.95160E-09 4.95160E-09 531280 + 686 531290 I-129 3.04170E-06 1.07090E-02 53129.82c + 687 531300 I-130 1.27970E-05 1.73860E-05 53130.82c + 688 531301 I-130m 5.46340E-06 5.46340E-06 531301 + 689 531310 I-131 2.71460E-04 2.95960E-02 53131.82c + 690 531320 I-132 7.99990E-04 4.70160E-02 531320 + 691 531321 I-132m 5.89610E-04 5.89610E-04 531321 + 692 531330 I-133 4.85120E-03 5.45200E-02 531330 + 693 531331 I-133m 2.96450E-03 2.96450E-03 531331 + 694 531340 I-134 1.11290E-02 5.70290E-02 531340 + 695 531341 I-134m 8.20210E-03 8.20210E-03 531341 + 696 531350 I-135 4.49330E-02 5.91660E-02 53135.82c + 697 531360 I-136 7.81240E-03 1.37530E-02 531360 + 698 531361 I-136m 1.82990E-02 1.83160E-02 531361 + 699 531370 I-137 1.77110E-02 1.88910E-02 531370 + 700 531380 I-138 7.62960E-03 7.93400E-03 531380 + 701 531390 I-139 5.19540E-03 5.23060E-03 531390 + 702 531400 I-140 9.15700E-04 9.16890E-04 531400 + 703 531410 I-141 2.06810E-04 2.06820E-04 531410 + 704 531420 I-142 1.50810E-05 1.50810E-05 531420 + 705 531430 I-143 5.30140E-08 5.30140E-08 531430 + 706 531440 I-144 9.45510E-10 9.45510E-10 531440 + 707 541300 Xe-130 2.64050E-09 1.82630E-05 54130.82c + 708 541310 Xe-131 2.91830E-07 2.95970E-02 54131.82c + 709 541311 Xe-131m 7.04510E-07 3.22170E-04 541311 + 710 541320 Xe-132 1.18590E-05 4.71240E-02 54132.82c + 711 541321 Xe-132m 1.34430E-05 1.34430E-05 541321 + 712 541330 Xe-133 5.87590E-05 5.47210E-02 54133.82c + 713 541331 Xe-133m 1.41850E-04 1.69370E-03 541331 + 714 541340 Xe-134 4.69180E-04 5.87860E-02 54134.82c + 715 541341 Xe-134m 1.09890E-03 1.28760E-03 541341 + 716 541350 Xe-135 2.37510E-03 6.71820E-02 54135.82c + 717 541351 Xe-135m 5.73380E-03 1.55010E-02 541351 + 718 541360 Xe-136 3.01830E-02 6.34810E-02 54136.82c + 719 541370 Xe-137 3.11720E-02 4.92550E-02 541370 + 720 541380 Xe-138 4.32390E-02 5.12650E-02 541380 + 721 541390 Xe-139 3.12320E-02 3.60350E-02 541390 + 722 541400 Xe-140 1.95140E-02 2.03890E-02 541400 + 723 541410 Xe-141 6.64580E-03 6.81300E-03 541410 + 724 541420 Xe-142 2.05550E-03 2.06680E-03 541420 + 725 541430 Xe-143 3.32000E-04 3.32030E-04 541430 + 726 541440 Xe-144 5.01000E-05 5.01010E-05 541440 + 727 541450 Xe-145 3.61170E-06 3.61170E-06 541450 + 728 541460 Xe-146 5.68110E-09 5.68110E-09 541460 + 729 551330 Cs-133 5.06520E-08 5.47210E-02 55133.82c + 730 551340 Cs-134 1.12530E-06 1.95460E-06 55134.82c + 731 551341 Cs-134m 8.29340E-07 8.29340E-07 551341 + 732 551350 Cs-135 4.21700E-05 6.73430E-02 55135.82c + 733 551351 Cs-135m 2.57700E-05 2.57700E-05 551351 + 734 551360 Cs-136 3.84990E-04 4.97800E-04 55136.82c + 735 551361 Cs-136m 2.25620E-04 2.25620E-04 551361 + 736 551370 Cs-137 4.49860E-03 5.37540E-02 55137.82c + 737 551380 Cs-138 5.17080E-03 6.23790E-02 551380 + 738 551381 Cs-138m 7.33720E-03 7.33720E-03 551381 + 739 551390 Cs-139 3.11010E-02 6.71360E-02 551390 + 740 551400 Cs-140 2.46610E-02 4.50530E-02 551400 + 741 551410 Cs-141 2.93620E-02 3.61790E-02 551410 + 742 551420 Cs-142 1.52880E-02 1.73510E-02 551420 + 743 551430 Cs-143 9.05630E-03 9.38650E-03 551430 + 744 551440 Cs-144 1.33610E-03 2.05290E-03 551440 + 745 551441 Cs-144m 1.33610E-03 1.33620E-03 551441 + 746 551450 Cs-145 6.70340E-04 6.73770E-04 551450 + 747 551460 Cs-146 1.18280E-04 1.18280E-04 551460 + 748 551470 Cs-147 1.88770E-05 1.88770E-05 551470 + 749 551480 Cs-148 2.36290E-08 2.36290E-08 551480 + 750 551490 Cs-149 6.25480E-10 6.25480E-10 551490 + 751 561350 Ba-135 2.20520E-09 7.52880E-09 56135.82c + 752 561351 Ba-135m 5.32360E-09 5.32360E-09 561351 + 753 561360 Ba-136 1.61870E-06 6.16020E-04 56136.82c + 754 561361 Ba-136m 3.79130E-06 3.79130E-06 561361 + 755 561370 Ba-137 1.67080E-05 5.38110E-02 56137.82c + 756 561371 Ba-137m 4.03350E-05 5.07840E-02 561371 + 757 561380 Ba-138 9.76650E-04 6.47500E-02 56138.82c + 758 561390 Ba-139 4.52570E-03 7.16620E-02 561390 + 759 561400 Ba-140 1.15940E-02 5.66470E-02 56140.82c + 760 561410 Ba-141 1.62250E-02 5.24040E-02 561410 + 761 561420 Ba-142 2.96400E-02 4.71450E-02 561420 + 762 561430 Ba-143 2.70470E-02 3.63450E-02 561430 + 763 561440 Ba-144 2.18250E-02 2.45770E-02 561440 + 764 561450 Ba-145 9.52560E-03 1.01200E-02 561450 + 765 561460 Ba-146 4.59470E-03 4.70160E-03 561460 + 766 561470 Ba-147 1.40230E-03 1.41580E-03 561470 + 767 561480 Ba-148 3.52420E-04 3.52440E-04 561480 + 768 561490 Ba-149 6.43960E-05 6.43970E-05 561490 + 769 561500 Ba-150 3.51860E-06 3.51860E-06 561500 + 770 561510 Ba-151 1.90430E-09 1.90430E-09 561510 + 771 571380 La-138 1.07330E-06 1.07330E-06 57138.82c + 772 571390 La-139 3.38060E-05 7.16960E-02 57139.82c + 773 571400 La-140 1.83430E-04 5.68300E-02 57140.82c + 774 571410 La-141 7.90610E-04 5.31950E-02 571410 + 775 571420 La-142 1.83330E-03 4.89780E-02 571420 + 776 571430 La-143 7.01640E-03 4.33620E-02 571430 + 777 571440 La-144 1.13540E-02 3.59310E-02 571440 + 778 571450 La-145 1.62280E-02 2.63480E-02 571450 + 779 571460 La-146 3.91890E-03 8.62040E-03 571460 + 780 571461 La-146m 7.04910E-03 7.04910E-03 571461 + 781 571470 La-147 9.67170E-03 1.10890E-02 571470 + 782 571480 La-148 4.62330E-03 4.97460E-03 571480 + 783 571490 La-149 2.02990E-03 2.09400E-03 571490 + 784 571500 La-150 4.48790E-04 4.52310E-04 571500 + 785 571510 La-151 6.74250E-05 6.74270E-05 571510 + 786 571520 La-152 1.29530E-05 1.29530E-05 571520 + 787 571530 La-153 1.38630E-08 1.38630E-08 571530 + 788 571540 La-154 1.96540E-10 1.96540E-10 571540 + 789 581400 Ce-140 1.18740E-06 5.68320E-02 58140.82c + 790 581410 Ce-141 1.34530E-05 5.32080E-02 58141.82c + 791 581420 Ce-142 8.97820E-05 4.90680E-02 58142.82c + 792 581430 Ce-143 3.31210E-04 4.36930E-02 58143.82c + 793 581440 Ce-144 1.69170E-03 3.76220E-02 58144.82c + 794 581450 Ce-145 4.09780E-03 3.04460E-02 581450 + 795 581460 Ce-146 9.99460E-03 2.56640E-02 581460 + 796 581470 Ce-147 1.33370E-02 2.44260E-02 581470 + 797 581480 Ce-148 1.71740E-02 2.21780E-02 581480 + 798 581490 Ce-149 1.11720E-02 1.32490E-02 581490 + 799 581500 Ce-150 6.73840E-03 7.17850E-03 581500 + 800 581510 Ce-151 2.15900E-03 2.22720E-03 581510 + 801 581520 Ce-152 8.06460E-04 8.18630E-04 581520 + 802 581530 Ce-153 1.83560E-04 1.83570E-04 581530 + 803 581540 Ce-154 3.08350E-05 3.08350E-05 581540 + 804 581550 Ce-155 3.18610E-06 3.18610E-06 581550 + 805 581560 Ce-156 1.01030E-09 1.01030E-09 581560 + 806 591430 Pr-143 1.02490E-06 4.36940E-02 59143.82c + 807 591440 Pr-144 2.92740E-07 3.76250E-02 591440 + 808 591441 Pr-144m 2.60000E-06 5.21770E-04 591441 + 809 591450 Pr-145 4.61320E-05 3.04920E-02 591450 + 810 591460 Pr-146 2.06250E-04 2.58700E-02 591460 + 811 591470 Pr-147 1.02570E-03 2.54520E-02 591470 + 812 591480 Pr-148 4.84690E-04 2.26630E-02 591480 + 813 591481 Pr-148m 2.03840E-03 2.03840E-03 591481 + 814 591490 Pr-149 5.92160E-03 1.91710E-02 591490 + 815 591500 Pr-150 6.22220E-03 1.34010E-02 591500 + 816 591510 Pr-151 6.00620E-03 8.23340E-03 591510 + 817 591520 Pr-152 4.11070E-03 4.93050E-03 591520 + 818 591530 Pr-153 2.68980E-03 2.87240E-03 591530 + 819 591540 Pr-154 7.78610E-04 8.09250E-04 591540 + 820 591550 Pr-155 2.09320E-04 2.12510E-04 591550 + 821 591560 Pr-156 2.74910E-05 2.74920E-05 591560 + 822 591570 Pr-157 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2.25910E-04 651640 + 919 651650 Tb-165 4.75070E-05 1.13100E-04 651650 + 920 651660 Tb-166 3.25730E-05 5.82970E-05 651660 + 921 651670 Tb-167 1.92420E-05 2.12690E-05 651670 + 922 651680 Tb-168 7.13370E-06 7.22210E-06 651680 + 923 651690 Tb-169 4.04140E-06 4.04600E-06 651690 + 924 651700 Tb-170 5.86700E-08 5.86700E-08 651700 + 925 651710 Tb-171 3.66000E-09 3.66000E-09 651710 + 926 661600 Dy-160 1.30410E-10 4.35210E-07 66160.82c + 927 661610 Dy-161 2.83170E-09 7.39350E-04 66161.82c + 928 661620 Dy-162 6.81330E-08 5.17730E-04 66162.82c + 929 661630 Dy-163 9.39140E-07 3.19030E-04 66163.82c + 930 661640 Dy-164 7.85430E-06 2.33770E-04 66164.82c + 931 661650 Dy-165 1.31860E-05 1.28260E-04 661650 + 932 661651 Dy-165m 2.01580E-06 2.01580E-06 661651 + 933 661660 Dy-166 2.17110E-05 8.00080E-05 661660 + 934 661670 Dy-167 1.51880E-05 3.64570E-05 661670 + 935 661680 Dy-168 1.42670E-05 2.14890E-05 661680 + 936 661690 Dy-169 1.61640E-05 2.02100E-05 661690 + 937 661700 Dy-170 7.49350E-06 7.55220E-06 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721820 + 1034 721821 Hf-182m 5.22650E-09 5.22650E-09 721821 + 1035 721830 Hf-183 5.03710E-09 6.75160E-09 721830 + 1036 721840 Hf-184 1.09770E-09 1.19670E-09 721840 + 1037 721841 Hf-184m 1.97450E-09 2.07350E-09 721841 + 1038 721850 Hf-185 8.02800E-10 8.02800E-10 721850 + 1039 721860 Hf-186 2.27520E-10 2.27520E-10 721860 + 1040 721870 Hf-187 2.11700E-11 2.11700E-11 721870 + 1041 721880 Hf-188 1.90860E-12 1.90860E-12 721880 + 1042 731790 Ta-179 1.06600E-12 1.40470E-12 731790 + 1043 731800 Ta-180 6.17230E-12 6.17230E-12 731800 + 1044 731801 Ta-180m 6.99670E-12 2.78950E-11 731801 + 1045 731810 Ta-181 1.14290E-10 2.36550E-08 73181.82c + 1046 731820 Ta-182 1.26890E-10 3.38650E-09 73182.82c + 1047 731821 Ta-182m 1.29520E-10 3.25960E-09 731821 + 1048 731822 Ta-182m 9.87260E-11 3.13010E-09 731822 + 1049 731830 Ta-183 1.18780E-09 7.93940E-09 731830 + 1050 731840 Ta-184 1.28600E-09 4.55610E-09 731840 + 1051 731850 Ta-185 1.12960E-09 2.47950E-09 731850 + 1052 731851 Ta-185m 5.47110E-10 5.47110E-10 731851 + 1053 731860 Ta-186 8.49970E-10 1.07750E-09 731860 + 1054 731870 Ta-187 4.31950E-10 4.53120E-10 731870 + 1055 731880 Ta-188 7.94810E-11 8.13900E-11 731880 + 1056 731890 Ta-189 1.84540E-11 1.84540E-11 731890 + 1057 731900 Ta-190 1.41560E-12 1.41560E-12 731900 + 1058 741820 W-182 1.47390E-12 3.38800E-09 74182.82c + 1059 741830 W-183 2.53910E-12 7.95030E-09 74183.82c + 1060 741831 W-183m 8.30700E-12 2.78250E-10 741831 + 1061 741840 W-184 7.02860E-11 4.62640E-09 74184.82c + 1062 741850 W-185 5.23530E-11 2.65820E-09 741850 + 1063 741851 W-185m 1.26390E-10 1.26390E-10 741851 + 1064 741860 W-186 3.58260E-10 1.55150E-09 74186.82c + 1065 741861 W-186m 1.15570E-10 1.15570E-10 741861 + 1066 741870 W-187 4.20610E-10 8.73730E-10 741870 + 1067 741880 W-188 3.89330E-10 4.70720E-10 741880 + 1068 741890 W-189 1.66290E-10 1.84740E-10 741890 + 1069 741900 W-190 3.38140E-11 7.35610E-11 741900 + 1070 741901 W-190m 3.83310E-11 3.83310E-11 741901 + 1071 741910 W-191 1.10360E-11 1.10360E-11 741910 + 1072 741920 W-192 1.81010E-12 1.81010E-12 741920 + 1073 751850 Re-185 1.04390E-12 2.65930E-09 75185.82c + 1074 751860 Re-186 2.45710E-12 2.45710E-12 751860 + 1075 751861 Re-186m 3.48650E-12 3.48650E-12 751861 + 1076 751870 Re-187 3.05880E-11 9.04320E-10 75187.82c + 1077 751880 Re-188 1.59580E-11 5.24060E-10 751880 + 1078 751881 Re-188m 3.73790E-11 3.73790E-11 751881 + 1079 751890 Re-189 1.16100E-10 3.00840E-10 751890 + 1080 751900 Re-190 3.12950E-11 1.30520E-10 751900 + 1081 751901 Re-190m 5.62930E-11 5.62930E-11 751901 + 1082 751910 Re-191 6.87140E-11 7.97500E-11 751910 + 1083 751920 Re-192 2.14320E-11 2.32420E-11 751920 + 1084 751930 Re-193 7.64870E-12 7.64870E-12 751930 + 1085 761890 Os-189 8.61750E-13 3.04520E-10 761890 + 1086 761891 Os-189m 2.81940E-12 3.37550E-11 761891 + 1087 761900 Os-190 7.29110E-12 1.76710E-10 761900 + 1088 761901 Os-190m 8.26490E-12 3.88880E-11 761901 + 1089 761910 Os-191 1.70510E-11 1.02010E-10 761910 + 1090 761911 Os-191m 5.21180E-12 5.21180E-12 761911 + 1091 761920 Os-192 1.63150E-11 5.58340E-11 761920 + 1092 761921 Os-192m 1.84950E-11 1.84950E-11 761921 + 1093 761930 Os-193 2.17720E-11 2.94210E-11 761930 + 1094 761940 Os-194 1.34160E-11 1.34160E-11 761940 + 1095 761950 Os-195 3.55920E-12 3.55920E-12 761950 + 1096 761960 Os-196 1.02300E-12 1.02300E-12 761960 + 1097 771920 Ir-192 4.89680E-13 3.87330E-12 771920 + 1098 771922 Ir-192m 4.89680E-13 2.89400E-12 771922 + 1099 771930 Ir-193 1.45620E-12 3.43920E-11 77193.82c + 1100 771931 Ir-193m 3.51550E-12 3.61770E-12 771931 + 1101 771940 Ir-194 1.81490E-12 1.70460E-11 771940 + 1102 771941 Ir-194m 1.81490E-12 1.81490E-12 771941 + 1103 771942 Ir-194m 1.81490E-12 1.81490E-12 771942 + 1104 771950 Ir-195 2.11090E-12 5.92490E-12 771950 + 1105 771951 Ir-195m 5.09600E-12 5.09600E-12 771951 + 1106 771960 Ir-196 1.85000E-12 2.87860E-12 771960 + 1107 771961 Ir-196m 1.85000E-12 1.85000E-12 771961 + 1108 771971 Ir-197m 1.34380E-12 1.34380E-12 771971 + 1109 781960 Pt-196 1.99890E-12 6.72190E-12 781960 + 1110 781970 Pt-197 5.25640E-13 3.60900E-12 781970 + 1111 781971 Pt-197m 1.26900E-12 2.60940E-12 781971 + 1112 781980 Pt-198 1.68360E-12 1.68360E-12 781980 + + Neutron-induced fission: + + Interpolation region : 2 / 2 + Interpolation energy : 4.00000E-01 MeV + Number of products : 1138 / 1204 + Cumulative yield cut-off : 0.00000E+00 + + Columns: + + 1. Index + 2. Product ZAI + 3. Product name + 4. Independent yield + 5. Cumulative yield + 6. Target in data + + 1 10010 H-1 3.60660E-05 3.60660E-05 1001.82c + 2 10020 H-2 1.10220E-05 1.10220E-05 1002.82c + 3 10030 H-3 1.85000E-04 1.85000E-04 1003.82c + 4 20040 He-4 2.28000E-03 2.28000E-03 2004.82c + 5 200500 Ca-50 7.34650E-12 7.34650E-12 200500 + 6 200510 Ca-51 7.02670E-12 7.02670E-12 200510 + 7 200520 Ca-52 7.16820E-12 7.16820E-12 200520 + 8 200530 Ca-53 2.40950E-12 2.40950E-12 200530 + 9 210500 Sc-50 1.61440E-12 9.45400E-12 210500 + 10 210501 Sc-50m 5.92280E-13 7.93880E-12 210501 + 11 210510 Sc-51 1.04580E-11 1.76280E-11 210510 + 12 210520 Sc-52 1.87560E-11 2.65040E-11 210520 + 13 210530 Sc-53 3.33780E-11 3.50650E-11 210530 + 14 210540 Sc-54 2.23740E-11 2.23740E-11 210540 + 15 210550 Sc-55 1.86660E-11 1.86660E-11 210550 + 16 210560 Sc-56 5.10410E-12 5.10410E-12 210560 + 17 210570 Sc-57 1.39830E-12 1.39830E-12 210570 + 18 220520 Ti-52 7.52240E-12 3.40260E-11 220520 + 19 220530 Ti-53 2.34980E-11 5.85630E-11 220530 + 20 220540 Ti-54 7.80850E-11 1.00460E-10 220540 + 21 220550 Ti-55 1.17180E-10 1.35850E-10 220550 + 22 220560 Ti-56 1.75450E-10 1.81020E-10 220560 + 23 220570 Ti-57 9.85880E-11 9.95250E-11 220570 + 24 220580 Ti-58 6.01190E-11 6.01190E-11 220580 + 25 220590 Ti-59 1.30920E-11 1.30920E-11 220590 + 26 220600 Ti-60 2.57560E-12 2.57560E-12 220600 + 27 230530 V-53 1.21260E-12 5.97750E-11 230530 + 28 230540 V-54 7.70540E-12 1.08160E-10 230540 + 29 230550 V-55 5.92650E-11 1.95110E-10 230550 + 30 230560 V-56 1.53970E-10 3.35280E-10 230560 + 31 230570 V-57 4.34320E-10 5.33550E-10 230570 + 32 230580 V-58 4.90890E-10 5.51010E-10 230580 + 33 230590 V-59 6.05880E-10 6.18970E-10 230590 + 34 230600 V-60 2.51770E-10 2.54350E-10 230600 + 35 230610 V-61 1.26030E-10 1.26030E-10 230610 + 36 230620 V-62 2.20200E-11 2.20200E-11 230620 + 37 230630 V-63 3.42660E-12 3.42660E-12 230630 + 38 240550 Cr-55 1.34050E-12 1.96450E-10 240550 + 39 240560 Cr-56 1.96900E-11 3.57110E-10 240560 + 40 240570 Cr-57 1.02690E-10 1.07490E-09 240570 + 41 240580 Cr-58 5.81910E-10 6.92110E-10 240580 + 42 240590 Cr-59 1.24680E-09 1.86580E-09 240590 + 43 240600 Cr-60 2.66060E-09 2.92250E-09 240600 + 44 240610 Cr-61 2.55340E-09 2.67190E-09 240610 + 45 240620 Cr-62 2.61250E-09 2.63570E-09 240620 + 46 240630 Cr-63 8.80940E-10 8.83170E-10 240630 + 47 240640 Cr-64 2.90320E-10 2.90320E-10 240640 + 48 240650 Cr-65 4.14460E-11 4.14460E-11 240650 + 49 240660 Cr-66 5.13280E-12 5.13280E-12 240660 + 50 250570 Mn-57 1.52630E-12 1.07640E-09 250570 + 51 250580 Mn-58 1.61140E-11 7.08230E-10 250580 + 52 250581 Mn-58m 1.58400E-12 1.58400E-12 250581 + 53 250590 Mn-59 2.07130E-10 2.07290E-09 250590 + 54 250600 Mn-60 7.10130E-11 3.07660E-09 250600 + 55 250601 Mn-60m 7.22430E-10 7.22430E-10 250601 + 56 250610 Mn-61 3.77300E-09 6.44490E-09 250610 + 57 250620 Mn-62 5.86670E-09 7.18450E-09 250620 + 58 250621 Mn-62m 9.18740E-10 2.23660E-09 250621 + 59 250630 Mn-63 1.21080E-08 1.29910E-08 250630 + 60 250640 Mn-64 7.91790E-09 8.20820E-09 250640 + 61 250650 Mn-65 6.81670E-09 6.85810E-09 250650 + 62 250660 Mn-66 1.86940E-09 1.87450E-09 250660 + 63 250670 Mn-67 5.14440E-10 5.14440E-10 250670 + 64 250680 Mn-68 5.09430E-11 5.09430E-11 250680 + 65 250690 Mn-69 2.36270E-11 2.36270E-11 250690 + 66 260590 Fe-59 1.30960E-12 2.07420E-09 260590 + 67 260600 Fe-60 3.02010E-11 3.74610E-09 260600 + 68 260610 Fe-61 2.84400E-10 6.72930E-09 260610 + 69 260620 Fe-62 2.70120E-09 1.21220E-08 260620 + 70 260630 Fe-63 8.46310E-09 2.14540E-08 260630 + 71 260640 Fe-64 3.55810E-08 4.37890E-08 260640 + 72 260650 Fe-65 4.24650E-08 4.93230E-08 260650 + 73 260660 Fe-66 6.37460E-08 6.56210E-08 260660 + 74 260670 Fe-67 3.59630E-08 3.64770E-08 260670 + 75 260680 Fe-68 2.20330E-08 2.20900E-08 260680 + 76 260690 Fe-69 2.30810E-08 2.30990E-08 260690 + 77 260700 Fe-70 1.74970E-09 1.74970E-09 260700 + 78 260710 Fe-71 5.88830E-11 5.88830E-11 260710 + 79 260720 Fe-72 8.80200E-12 8.80200E-12 260720 + 80 270610 Co-61 1.15120E-12 6.73040E-09 270610 + 81 270620 Co-62 6.34980E-12 1.21290E-08 270620 + 82 270621 Co-62m 1.73080E-11 1.73080E-11 270621 + 83 270630 Co-63 4.33220E-10 2.18870E-08 270630 + 84 270640 Co-64 2.68670E-09 4.64760E-08 270640 + 85 270650 Co-65 2.13230E-08 7.06460E-08 270650 + 86 270660 Co-66 5.55430E-08 1.21160E-07 270660 + 87 270670 Co-67 1.57270E-07 1.93750E-07 270670 + 88 270680 Co-68 1.02210E-07 1.52210E-07 270680 + 89 270681 Co-68m 7.62910E-08 9.99970E-08 270681 + 90 270690 Co-69 1.82580E-06 1.84730E-06 270690 + 91 270700 Co-70 8.47750E-08 8.47750E-08 270700 + 92 270701 Co-70m 8.47750E-08 8.65250E-08 270701 + 93 270710 Co-71 3.60700E-08 3.61290E-08 270710 + 94 270720 Co-72 1.23770E-08 1.23860E-08 270720 + 95 270730 Co-73 1.10860E-09 1.10860E-09 270730 + 96 270740 Co-74 5.26640E-11 5.26640E-11 270740 + 97 270750 Co-75 5.23420E-12 5.23420E-12 270750 + 98 280640 Ni-64 2.85810E-11 4.65040E-08 28064.82c + 99 280650 Ni-65 4.78300E-10 7.11240E-08 280650 + 100 280660 Ni-66 7.04710E-09 1.28210E-07 280660 + 101 280670 Ni-67 3.69110E-08 2.30660E-07 280670 + 102 280680 Ni-68 2.10080E-07 4.30760E-07 280680 + 103 280690 Ni-69 9.12800E-07 2.74160E-06 280690 + 104 280691 Ni-69m 9.12800E-07 9.12800E-07 280691 + 105 280700 Ni-70 2.31770E-06 2.48900E-06 280700 + 106 280710 Ni-71 9.45760E-07 9.81890E-07 280710 + 107 280720 Ni-72 3.01890E-06 3.03130E-06 280720 + 108 280730 Ni-73 9.85750E-07 9.86860E-07 280730 + 109 280740 Ni-74 8.63020E-08 8.63550E-08 280740 + 110 280750 Ni-75 1.95250E-08 1.95300E-08 280750 + 111 280760 Ni-76 1.96260E-09 1.96260E-09 280760 + 112 280770 Ni-77 9.56290E-11 9.56290E-11 280770 + 113 280780 Ni-78 5.77580E-12 5.77580E-12 280780 + 114 290660 Cu-66 1.68070E-11 1.28230E-07 290660 + 115 290670 Cu-67 5.43960E-10 2.31200E-07 290670 + 116 290680 Cu-68 1.70120E-09 4.36360E-07 290680 + 117 290681 Cu-68m 4.63710E-09 4.63710E-09 290681 + 118 290690 Cu-69 3.56790E-07 4.01120E-06 290690 + 119 290700 Cu-70 3.56400E-08 3.26340E-07 290700 + 120 290701 Cu-70m 4.55160E-07 5.81390E-07 290701 + 121 290702 Cu-70m 3.56400E-08 2.52460E-06 290702 + 122 290710 Cu-71 9.45730E-07 1.92760E-06 290710 + 123 290720 Cu-72 3.01850E-06 6.04980E-06 290720 + 124 290730 Cu-73 1.97150E-06 2.95840E-06 290730 + 125 290740 Cu-74 9.48040E-07 1.03470E-06 290740 + 126 290750 Cu-75 4.16620E-06 4.18540E-06 290750 + 127 290760 Cu-76 5.33050E-07 5.34030E-07 290760 + 128 290761 Cu-76m 5.33050E-07 5.34030E-07 290761 + 129 290770 Cu-77 2.22500E-07 2.22600E-07 290770 + 130 290780 Cu-78 1.96130E-08 1.96190E-08 290780 + 131 290790 Cu-79 1.73350E-09 1.73350E-09 290790 + 132 290800 Cu-80 5.46470E-11 5.46470E-11 290800 + 133 300680 Zn-68 1.79620E-11 4.37120E-07 300680 + 134 300690 Zn-69 3.74820E-10 4.01340E-06 300690 + 135 300691 Zn-69m 1.86160E-09 1.86160E-09 300691 + 136 300700 Zn-70 1.98730E-08 3.03530E-06 300700 + 137 300710 Zn-71 1.33310E-08 1.94100E-06 300710 + 138 300711 Zn-71m 6.62070E-08 6.62070E-08 300711 + 139 300720 Zn-72 1.00620E-06 7.05600E-06 300720 + 140 300730 Zn-73 3.45770E-07 5.34190E-06 300730 + 141 300731 Zn-73m 4.78240E-07 2.03770E-06 300731 + 142 300732 Zn-73m 3.11900E-06 3.11900E-06 300732 + 143 300740 Zn-74 9.48000E-06 1.06610E-05 300740 + 144 300750 Zn-75 2.29130E-05 2.69680E-05 300750 + 145 300760 Zn-76 3.19930E-05 3.30450E-05 300760 + 146 300770 Zn-77 2.13340E-05 2.29770E-05 300770 + 147 300771 Zn-77m 2.84060E-06 2.84060E-06 300771 + 148 300780 Zn-78 1.53970E-05 1.54180E-05 300780 + 149 300790 Zn-79 5.40570E-06 5.40650E-06 300790 + 150 300800 Zn-80 3.47560E-07 3.47620E-07 300800 + 151 300810 Zn-81 1.97760E-08 1.97760E-08 300810 + 152 300820 Zn-82 1.24470E-09 1.24470E-09 300820 + 153 300830 Zn-83 3.80350E-11 3.80350E-11 300830 + 154 310700 Ga-70 1.23770E-11 1.23770E-11 310700 + 155 310710 Ga-71 3.19130E-10 2.00750E-06 310710 + 156 310720 Ga-72 1.17270E-08 7.06890E-06 310720 + 157 310721 Ga-72m 1.15280E-09 2.36260E-07 310721 + 158 310730 Ga-73 1.35740E-07 7.03710E-06 310730 + 159 310740 Ga-74 3.90160E-07 8.67870E-06 310740 + 160 310741 Ga-74m 3.90160E-07 1.10510E-05 310741 + 161 310750 Ga-75 6.24730E-06 3.32150E-05 310750 + 162 310760 Ga-76 1.38540E-05 4.68990E-05 310760 + 163 310770 Ga-77 6.03810E-05 8.47790E-05 310770 + 164 310780 Ga-78 3.73900E-05 5.28780E-05 310780 + 165 310790 Ga-79 7.58150E-05 8.11510E-05 310790 + 166 310800 Ga-80 2.40750E-05 2.44240E-05 310800 + 167 310810 Ga-81 2.35630E-05 2.35810E-05 310810 + 168 310820 Ga-82 1.72780E-06 1.72900E-06 310820 + 169 310830 Ga-83 2.20370E-07 2.20410E-07 310830 + 170 310840 Ga-84 1.06540E-08 1.06540E-08 310840 + 171 310850 Ga-85 4.12570E-10 4.12570E-10 310850 + 172 320720 Ge-72 9.32010E-12 7.06890E-06 32072.82c + 173 320730 Ge-73 1.88710E-10 7.03730E-06 32073.82c + 174 320731 Ge-73m 3.79970E-11 6.93380E-06 320731 + 175 320740 Ge-74 8.22980E-09 1.14500E-05 32074.82c + 176 320750 Ge-75 2.56470E-08 3.34330E-05 320750 + 177 320751 Ge-75m 1.92620E-07 1.52120E-06 320751 + 178 320760 Ge-76 1.06600E-06 4.79650E-05 32076.82c + 179 320770 Ge-77 1.06550E-05 2.70330E-05 320770 + 180 320771 Ge-77m 1.41870E-06 8.61970E-05 320771 + 181 320780 Ge-78 1.02070E-04 1.55020E-04 320780 + 182 320790 Ge-79 2.01740E-05 1.07200E-04 320790 + 183 320791 Ge-79m 1.51520E-04 1.51640E-04 320791 + 184 320800 Ge-80 3.64660E-04 3.91890E-04 320800 + 185 320810 Ge-81 2.71630E-04 2.83430E-04 320810 + 186 320811 Ge-81m 5.46910E-05 6.46790E-05 320811 + 187 320820 Ge-82 3.29220E-04 3.30660E-04 320820 + 188 320830 Ge-83 8.37280E-05 8.38740E-05 320830 + 189 320840 Ge-84 2.16770E-05 2.16800E-05 320840 + 190 320850 Ge-85 1.98090E-06 1.98130E-06 320850 + 191 320860 Ge-86 1.48530E-07 1.48530E-07 320860 + 192 320870 Ge-87 4.43090E-09 4.43090E-09 320870 + 193 320880 Ge-88 2.31190E-10 2.31190E-10 320880 + 194 330740 As-74 1.26000E-12 1.26000E-12 330740 + 195 330750 As-75 4.78920E-11 3.34340E-05 33075.82c + 196 330751 As-75m 1.81370E-10 6.37740E-10 330751 + 197 330760 As-76 6.16600E-09 6.16600E-09 330760 + 198 330770 As-77 2.27880E-07 9.70810E-05 330770 + 199 330780 As-78 2.19690E-06 1.57220E-04 330780 + 200 330790 As-79 7.55470E-06 2.60320E-04 330790 + 201 330800 As-80 6.24250E-05 4.54320E-04 330800 + 202 330810 As-81 2.29160E-04 5.76620E-04 330810 + 203 330820 As-82 8.82480E-05 4.18910E-04 330820 + 204 330821 As-82m 3.07480E-04 3.07480E-04 330821 + 205 330830 As-83 6.07540E-04 6.93760E-04 330830 + 206 330840 As-84 1.74990E-04 1.84790E-04 330840 + 207 330841 As-84m 1.74990E-04 1.84790E-04 330841 + 208 330850 As-85 2.23440E-04 2.25140E-04 330850 + 209 330860 As-86 6.97190E-05 6.98670E-05 330860 + 210 330870 As-87 2.70360E-05 2.70400E-05 330870 + 211 330880 As-88 5.01940E-06 5.01960E-06 330880 + 212 330890 As-89 5.60470E-08 5.60470E-08 330890 + 213 330900 As-90 1.25070E-09 1.25070E-09 330900 + 214 340760 Se-76 1.76330E-12 6.16780E-09 34076.82c + 215 340770 Se-77 1.15580E-11 9.70810E-05 34077.82c + 216 340771 Se-77m 8.68060E-11 8.68060E-11 340771 + 217 340780 Se-78 6.63640E-09 1.57220E-04 34078.82c + 218 340790 Se-79 9.53630E-07 2.61260E-04 34079.82c + 219 340791 Se-79m 1.26970E-07 2.54280E-04 340791 + 220 340800 Se-80 3.43390E-06 4.57750E-04 34080.82c + 221 340810 Se-81 5.25620E-06 6.21330E-04 340810 + 222 340811 Se-81m 3.94780E-05 6.01780E-05 340811 + 223 340820 Se-82 2.38260E-04 9.64650E-04 34082.82c + 224 340830 Se-83 5.10920E-04 7.60930E-04 340830 + 225 340831 Se-83m 1.02870E-04 5.47130E-04 340831 + 226 340840 Se-84 1.58210E-03 2.00070E-03 340840 + 227 340850 Se-85 1.78760E-03 1.98630E-03 340850 + 228 340860 Se-86 1.85880E-03 1.90980E-03 340860 + 229 340870 Se-87 9.08900E-04 9.31780E-04 340870 + 230 340880 Se-88 4.46140E-04 4.51160E-04 340880 + 231 340890 Se-89 1.22500E-04 1.22560E-04 340890 + 232 340900 Se-90 1.81760E-05 1.81770E-05 340900 + 233 340910 Se-91 3.93910E-07 3.93910E-07 340910 + 234 340920 Se-92 1.98620E-08 1.98620E-08 340920 + 235 340930 Se-93 5.21160E-10 5.21160E-10 340930 + 236 350790 Br-79 8.58140E-12 1.42440E-07 35079.82c + 237 350791 Br-79m 3.24980E-11 3.24980E-11 350791 + 238 350800 Br-80 5.26440E-10 2.36070E-09 350800 + 239 350801 Br-80m 1.83430E-09 1.83430E-09 350801 + 240 350810 Br-81 1.02860E-07 6.21460E-04 35081.82c + 241 350820 Br-82 1.52710E-06 2.07390E-06 350820 + 242 350821 Br-82m 5.60230E-07 5.60230E-07 350821 + 243 350830 Br-83 3.18320E-05 1.33990E-03 350830 + 244 350840 Br-84 5.65150E-05 2.05720E-03 350840 + 245 350841 Br-84m 5.65150E-05 5.65150E-05 350841 + 246 350850 Br-85 5.81860E-04 2.56810E-03 350850 + 247 350860 Br-86 1.29440E-03 3.20420E-03 350860 + 248 350870 Br-87 2.37120E-03 3.30740E-03 350870 + 249 350880 Br-88 2.35940E-03 2.81560E-03 350880 + 250 350890 Br-89 1.94800E-03 2.06100E-03 350890 + 251 350900 Br-90 8.30880E-04 8.49140E-04 350900 + 252 350910 Br-91 3.45140E-04 3.45450E-04 350910 + 253 350920 Br-92 6.66120E-05 6.66320E-05 350920 + 254 350930 Br-93 7.05850E-06 7.05900E-06 350930 + 255 350940 Br-94 1.26600E-07 1.26600E-07 350940 + 256 350950 Br-95 4.12110E-09 4.12110E-09 350950 + 257 360810 Kr-81 1.55130E-11 1.75780E-11 360810 + 258 360811 Kr-81m 2.06540E-12 2.06540E-12 360811 + 259 360820 Kr-82 1.24470E-09 2.08850E-06 36082.82c + 260 360830 Kr-83 3.59980E-08 1.33990E-03 36083.82c + 261 360831 Kr-83m 7.24800E-09 1.33870E-03 360831 + 262 360840 Kr-84 3.92650E-06 2.11770E-03 36084.82c + 263 360850 Kr-85 3.38120E-05 5.88130E-04 36085.82c + 264 360851 Kr-85m 6.80790E-06 2.57080E-03 360851 + 265 360860 Kr-86 3.28870E-04 3.61610E-03 36086.82c + 266 360870 Kr-87 1.15860E-03 4.57170E-03 360870 + 267 360880 Kr-88 3.36000E-03 6.27760E-03 360880 + 268 360890 Kr-89 5.46940E-03 7.44870E-03 360890 + 269 360900 Kr-90 7.12800E-03 7.83730E-03 360900 + 270 360910 Kr-91 5.35910E-03 5.65750E-03 360910 + 271 360920 Kr-92 3.44650E-03 3.49590E-03 360920 + 272 360930 Kr-93 1.13780E-03 1.14010E-03 360930 + 273 360940 Kr-94 3.76490E-04 3.76530E-04 360940 + 274 360950 Kr-95 4.85660E-05 4.85700E-05 360950 + 275 360960 Kr-96 1.32060E-05 1.32060E-05 360960 + 276 360970 Kr-97 3.45280E-08 3.45280E-08 360970 + 277 360980 Kr-98 1.47380E-09 1.47380E-09 360980 + 278 370840 Rb-84 8.03550E-11 2.48930E-10 370840 + 279 370841 Rb-84m 1.68580E-10 1.68580E-10 370841 + 280 370850 Rb-85 1.76580E-08 2.60880E-03 37085.82c + 281 370860 Rb-86 3.22620E-07 9.99430E-07 37086.82c + 282 370861 Rb-86m 6.76810E-07 6.76810E-07 370861 + 283 370870 Rb-87 1.30380E-05 4.58470E-03 37087.82c + 284 370880 Rb-88 1.32730E-04 6.41030E-03 370880 + 285 370890 Rb-89 7.14850E-04 8.16350E-03 370890 + 286 370900 Rb-90 1.84970E-04 7.07280E-03 370900 + 287 370901 Rb-90m 1.88170E-03 2.90680E-03 370901 + 288 370910 Rb-91 5.25350E-03 1.09110E-02 370910 + 289 370920 Rb-92 7.00290E-03 1.04990E-02 370920 + 290 370930 Rb-93 8.03570E-03 9.18000E-03 370930 + 291 370940 Rb-94 4.88940E-03 5.26310E-03 370940 + 292 370950 Rb-95 2.77750E-03 2.82520E-03 370950 + 293 370960 Rb-96 3.75690E-04 5.73070E-04 370960 + 294 370961 Rb-96m 3.75690E-04 3.82050E-04 370961 + 295 370970 Rb-97 1.97880E-04 1.97910E-04 370970 + 296 370980 Rb-98 1.49610E-05 1.49610E-05 370980 + 297 370981 Rb-98m 1.49610E-05 1.49620E-05 370981 + 298 370990 Rb-99 5.01200E-06 5.01200E-06 370990 + 299 371000 Rb-100 5.87560E-09 5.87560E-09 371000 + 300 380860 Sr-86 1.30630E-10 9.99510E-07 38086.82c + 301 380870 Sr-87 3.68830E-09 4.42870E-09 38087.82c + 302 380871 Sr-87m 7.42620E-10 7.42620E-10 380871 + 303 380880 Sr-88 2.00840E-06 6.41230E-03 38088.82c + 304 380890 Sr-89 2.21260E-05 8.18570E-03 38089.82c + 305 380900 Sr-90 2.68540E-04 1.01730E-02 38090.82c + 306 380910 Sr-91 1.12370E-03 1.20350E-02 380910 + 307 380920 Sr-92 4.43460E-03 1.50620E-02 380920 + 308 380930 Sr-93 8.71750E-03 1.83010E-02 380930 + 309 380940 Sr-94 1.68120E-02 2.17870E-02 380940 + 310 380950 Sr-95 1.57110E-02 1.83700E-02 380950 + 311 380960 Sr-96 1.36220E-02 1.43590E-02 380960 + 312 380970 Sr-97 6.47430E-03 6.62460E-03 380970 + 313 380980 Sr-98 2.86920E-03 2.89780E-03 380980 + 314 380990 Sr-99 6.38430E-04 6.42640E-04 380990 + 315 381000 Sr-100 1.53080E-04 1.53090E-04 381000 + 316 381010 Sr-101 1.51160E-05 1.51160E-05 381010 + 317 381020 Sr-102 2.01340E-06 2.01340E-06 381020 + 318 381030 Sr-103 1.59190E-09 1.59190E-09 381030 + 319 390890 Y-89 2.17440E-10 8.18570E-03 39089.82c + 320 390891 Y-89m 1.08000E-09 7.90100E-07 390891 + 321 390900 Y-90 3.77980E-07 1.01740E-02 39090.82c + 322 390901 Y-90m 6.32120E-07 6.32120E-07 390901 + 323 390910 Y-91 1.86220E-06 1.20460E-02 39091.82c + 324 390911 Y-91m 9.24880E-06 7.08990E-03 390911 + 325 390920 Y-92 7.27980E-05 1.51350E-02 390920 + 326 390930 Y-93 6.65920E-05 1.88670E-02 390930 + 327 390931 Y-93m 5.00150E-04 5.07970E-03 390931 + 328 390940 Y-94 1.90790E-03 2.36940E-02 390940 + 329 390950 Y-95 6.99190E-03 2.53620E-02 390950 + 330 390960 Y-96 3.77290E-03 1.81340E-02 390960 + 331 390961 Y-96m 7.91510E-03 7.91680E-03 390961 + 332 390970 Y-97 3.04460E-03 8.78800E-03 390970 + 333 390971 Y-97m 1.12540E-02 1.53330E-02 390971 + 334 390972 Y-97m 3.86750E-03 3.86750E-03 390972 + 335 390980 Y-98 2.43270E-03 5.33050E-03 390980 + 336 390981 Y-98m 1.17930E-02 1.17930E-02 390981 + 337 390990 Y-99 1.08140E-02 1.14580E-02 390990 + 338 391000 Y-100 2.15900E-03 2.31110E-03 391000 + 339 391001 Y-100m 2.15900E-03 2.15920E-03 391001 + 340 391010 Y-101 1.77490E-03 1.78980E-03 391010 + 341 391020 Y-102 1.66550E-04 1.67500E-04 391020 + 342 391021 Y-102m 1.66550E-04 1.67500E-04 391021 + 343 391030 Y-103 6.81640E-05 6.81660E-05 391030 + 344 391040 Y-104 3.97510E-06 3.97510E-06 391040 + 345 391050 Y-105 9.33690E-09 9.33690E-09 391050 + 346 400910 Zr-91 3.42830E-10 1.20460E-02 40091.82c + 347 400920 Zr-92 1.93110E-08 1.51350E-02 40092.82c + 348 400930 Zr-93 1.21040E-05 1.88790E-02 40093.82c + 349 400940 Zr-94 1.22590E-04 2.38170E-02 40094.82c + 350 400950 Zr-95 6.16230E-04 2.59780E-02 40095.82c + 351 400960 Zr-96 3.45860E-03 2.95210E-02 40096.82c + 352 400970 Zr-97 8.87130E-03 3.40660E-02 400970 + 353 400980 Zr-98 2.23240E-02 3.92230E-02 400980 + 354 400990 Zr-99 2.63160E-02 3.76000E-02 400990 + 355 401000 Zr-100 3.05370E-02 3.49860E-02 401000 + 356 401010 Zr-101 1.81440E-02 1.99500E-02 401010 + 357 401020 Zr-102 1.09250E-02 1.12490E-02 401020 + 358 401030 Zr-103 3.47770E-03 3.54080E-03 401030 + 359 401040 Zr-104 1.16480E-03 1.16840E-03 401040 + 360 401050 Zr-105 1.89080E-04 1.89090E-04 401050 + 361 401060 Zr-106 1.80840E-05 1.80840E-05 401060 + 362 401070 Zr-107 1.98940E-06 1.98940E-06 401070 + 363 401080 Zr-108 2.05390E-09 2.05390E-09 401080 + 364 410940 Nb-94 6.27930E-07 1.00150E-06 41094.82c + 365 410941 Nb-94m 3.75470E-07 3.75470E-07 410941 + 366 410950 Nb-95 2.52850E-06 2.59650E-02 41095.82c + 367 410951 Nb-95m 5.09100E-07 2.81160E-04 410951 + 368 410960 Nb-96 3.15110E-05 3.15110E-05 410960 + 369 410970 Nb-97 2.09230E-04 3.43180E-02 410970 + 370 410971 Nb-97m 4.21280E-05 3.24210E-02 410971 + 371 410980 Nb-98 2.55620E-04 3.94780E-02 410980 + 372 410981 Nb-98m 8.90670E-04 8.90670E-04 410981 + 373 410990 Nb-99 4.37650E-03 2.84340E-02 410990 + 374 410991 Nb-99m 8.81190E-04 1.47180E-02 410991 + 375 411000 Nb-100 1.95300E-03 3.69390E-02 411000 + 376 411001 Nb-100m 9.46800E-03 9.46800E-03 411001 + 377 411010 Nb-101 2.38570E-02 4.38070E-02 411010 + 378 411020 Nb-102 1.21790E-02 2.34280E-02 411020 + 379 411021 Nb-102m 1.21790E-02 1.21790E-02 411021 + 380 411030 Nb-103 2.45650E-02 2.81060E-02 411030 + 381 411040 Nb-104 6.67350E-03 7.84460E-03 411040 + 382 411041 Nb-104m 6.67350E-03 6.67350E-03 411041 + 383 411050 Nb-105 7.50460E-03 7.69130E-03 411050 + 384 411060 Nb-106 2.23690E-03 2.25480E-03 411060 + 385 411070 Nb-107 6.55000E-04 6.56920E-04 411070 + 386 411080 Nb-108 8.00580E-05 8.00600E-05 411080 + 387 411090 Nb-109 1.38700E-05 1.38700E-05 411090 + 388 411100 Nb-110 5.45370E-09 5.45370E-09 411100 + 389 420960 Mo-96 1.09620E-09 3.15120E-05 42096.82c + 390 420970 Mo-97 4.02840E-06 3.43220E-02 42097.82c + 391 420980 Mo-98 3.29420E-05 4.04020E-02 42098.82c + 392 420990 Mo-99 2.41180E-04 4.30990E-02 42099.82c + 393 421000 Mo-100 1.69520E-03 4.81020E-02 42100.82c + 394 421010 Mo-101 5.16580E-03 4.89730E-02 421010 + 395 421020 Mo-102 1.67880E-02 5.23940E-02 421020 + 396 421030 Mo-103 2.57390E-02 5.38530E-02 421030 + 397 421040 Mo-104 3.95350E-02 5.41760E-02 421040 + 398 421050 Mo-105 3.12410E-02 3.89030E-02 421050 + 399 421060 Mo-106 2.52530E-02 2.74460E-02 421060 + 400 421070 Mo-107 1.11330E-02 1.17560E-02 421070 + 401 421080 Mo-108 5.13530E-03 5.21210E-03 421080 + 402 421090 Mo-109 1.25610E-03 1.26820E-03 421090 + 403 421100 Mo-110 3.03090E-04 3.03090E-04 421100 + 404 421110 Mo-111 2.26770E-05 2.26770E-05 421110 + 405 421120 Mo-112 4.03110E-08 4.03110E-08 421120 + 406 421130 Mo-113 6.23900E-10 6.23900E-10 421130 + 407 430990 Tc-99 1.66900E-06 4.31000E-02 43099.82c + 408 430991 Tc-99m 3.36040E-07 3.79530E-02 430991 + 409 431000 Tc-100 6.09390E-06 6.09390E-06 431000 + 410 431010 Tc-101 7.86790E-05 4.90520E-02 431010 + 411 431020 Tc-102 2.38960E-04 5.26330E-02 431020 + 412 431021 Tc-102m 2.38960E-04 2.38960E-04 431021 + 413 431030 Tc-103 2.50190E-03 5.63550E-02 431030 + 414 431040 Tc-104 6.61980E-03 6.07960E-02 431040 + 415 431050 Tc-105 1.85250E-02 5.74280E-02 431050 + 416 431060 Tc-106 2.48180E-02 5.22640E-02 431060 + 417 431070 Tc-107 3.28150E-02 4.45700E-02 431070 + 418 431080 Tc-108 2.33090E-02 2.85280E-02 431080 + 419 431090 Tc-109 1.64360E-02 1.76980E-02 431090 + 420 431100 Tc-110 7.13020E-03 7.43350E-03 431100 + 421 431110 Tc-111 2.93380E-03 2.95620E-03 431110 + 422 431120 Tc-112 5.39670E-04 5.39710E-04 431120 + 423 431130 Tc-113 1.08120E-04 1.08120E-04 431130 + 424 431140 Tc-114 1.07520E-05 1.07520E-05 431140 + 425 431150 Tc-115 9.66880E-07 9.66880E-07 431150 + 426 441010 Ru-101 1.38750E-09 4.90520E-02 44101.82c + 427 441020 Ru-102 8.05460E-06 5.28800E-02 44102.82c + 428 441030 Ru-103 1.42720E-05 5.64090E-02 44103.82c + 429 441031 Ru-103m 3.99320E-05 3.99320E-05 441031 + 430 441040 Ru-104 4.47830E-04 6.12430E-02 44104.82c + 431 441050 Ru-105 1.87330E-03 5.93010E-02 44105.82c + 432 441060 Ru-106 6.95550E-03 5.92190E-02 44106.82c + 433 441070 Ru-107 1.34030E-02 5.79730E-02 441070 + 434 441080 Ru-108 2.55570E-02 5.40990E-02 441080 + 435 441090 Ru-109 2.57770E-02 4.34630E-02 441090 + 436 441100 Ru-110 2.60980E-02 3.35290E-02 441100 + 437 441110 Ru-111 1.47930E-02 1.77570E-02 441110 + 438 441120 Ru-112 8.37440E-03 8.91380E-03 441120 + 439 441130 Ru-113 1.27650E-03 2.01580E-03 441130 + 440 441131 Ru-113m 1.27650E-03 1.27650E-03 441131 + 441 441140 Ru-114 6.77770E-04 6.87960E-04 441140 + 442 441150 Ru-115 8.21420E-05 8.29700E-05 441150 + 443 441160 Ru-116 8.19310E-06 8.19310E-06 441160 + 444 441170 Ru-117 4.56420E-06 4.56420E-06 441170 + 445 441180 Ru-118 3.74750E-11 3.74750E-11 441180 + 446 451040 Rh-104 8.86540E-07 3.97150E-06 451040 + 447 451041 Rh-104m 3.08900E-06 3.08900E-06 451041 + 448 451050 Rh-105 1.15010E-05 5.93140E-02 45105.82c + 449 451051 Rh-105m 1.53130E-06 1.68360E-02 451051 + 450 451060 Rh-106 2.26720E-05 5.92420E-02 451060 + 451 451061 Rh-106m 6.18000E-05 6.18000E-05 451061 + 452 451070 Rh-107 5.65430E-04 5.85390E-02 451070 + 453 451080 Rh-108 4.47270E-04 5.45460E-02 451080 + 454 451081 Rh-108m 1.55840E-03 1.55840E-03 451081 + 455 451090 Rh-109 5.92800E-03 4.93910E-02 451090 + 456 451100 Rh-110 9.97520E-03 4.35040E-02 451100 + 457 451101 Rh-110m 2.34830E-04 2.34830E-04 451101 + 458 451110 Rh-111 1.64250E-02 3.41820E-02 451110 + 459 451120 Rh-112 6.91700E-03 1.58310E-02 451120 + 460 451121 Rh-112m 6.91700E-03 6.91700E-03 451121 + 461 451130 Rh-113 1.19890E-02 1.46430E-02 451130 + 462 451140 Rh-114 2.57540E-03 3.26350E-03 451140 + 463 451141 Rh-114m 2.57540E-03 2.57540E-03 451141 + 464 451150 Rh-115 2.29710E-03 2.38000E-03 451150 + 465 451160 Rh-116 1.47590E-04 1.55790E-04 451160 + 466 451161 Rh-116m 4.02310E-04 4.02310E-04 451161 + 467 451170 Rh-117 1.37030E-04 1.41500E-04 451170 + 468 451180 Rh-118 3.01890E-05 3.01890E-05 451180 + 469 451190 Rh-119 1.34520E-05 1.34520E-05 451190 + 470 451200 Rh-120 2.52480E-06 2.52480E-06 451200 + 471 461060 Pd-106 2.19820E-09 5.93040E-02 46106.82c + 472 461070 Pd-107 2.17760E-06 5.85460E-02 46107.82c + 473 461071 Pd-107m 4.78640E-06 4.78640E-06 461071 + 474 461080 Pd-108 5.24560E-05 5.61570E-02 46108.82c + 475 461090 Pd-109 7.92320E-05 4.96450E-02 461090 + 476 461091 Pd-109m 1.74150E-04 2.48700E-02 461091 + 477 461100 Pd-110 1.15620E-03 4.48950E-02 46110.82c + 478 461110 Pd-111 8.17370E-04 3.62740E-02 461110 + 479 461111 Pd-111m 1.79650E-03 1.93330E-03 461111 + 480 461120 Pd-112 5.81240E-03 2.85600E-02 461120 + 481 461130 Pd-113 1.73880E-03 2.12470E-02 461130 + 482 461131 Pd-113m 4.86520E-03 4.86520E-03 461131 + 483 461140 Pd-114 7.35180E-03 1.31910E-02 461140 + 484 461150 Pd-115 1.31160E-03 3.60430E-03 461150 + 485 461151 Pd-115m 2.88300E-03 3.22850E-03 461151 + 486 461160 Pd-116 2.48390E-03 3.04200E-03 461160 + 487 461170 Pd-117 2.53560E-04 9.53270E-04 461170 + 488 461171 Pd-117m 5.57330E-04 5.57330E-04 461171 + 489 461180 Pd-118 2.84030E-04 3.13340E-04 461180 + 490 461190 Pd-119 7.74610E-05 9.10630E-05 461190 + 491 461200 Pd-120 2.21150E-05 2.44900E-05 461200 + 492 461210 Pd-121 3.16490E-06 3.16490E-06 461210 + 493 461220 Pd-122 4.13480E-10 4.13480E-10 461220 + 494 461230 Pd-123 1.15420E-11 1.15420E-11 461230 + 495 461240 Pd-124 1.41380E-07 1.41380E-07 461240 + 496 471090 Ag-109 2.32870E-07 4.96470E-02 47109.82c + 497 471091 Ag-109m 1.74900E-06 4.96220E-02 471091 + 498 471100 Ag-110 2.13240E-06 2.21140E-06 471100 + 499 471101 Ag-110m 5.81240E-06 5.81240E-06 47510.82c + 500 471110 Ag-111 7.77990E-06 3.66800E-02 47111.82c + 501 471111 Ag-111m 5.84320E-05 3.64480E-02 471111 + 502 471120 Ag-112 1.92260E-04 2.87520E-02 471120 + 503 471130 Ag-113 7.93830E-05 1.43840E-02 471130 + 504 471131 Ag-113m 5.96220E-04 2.09420E-02 471131 + 505 471140 Ag-114 1.88030E-04 1.42900E-02 471140 + 506 471141 Ag-114m 9.11570E-04 9.11570E-04 471141 + 507 471150 Ag-115 2.17860E-04 4.02080E-03 471150 + 508 471151 Ag-115m 1.63620E-03 5.57970E-03 471151 + 509 471160 Ag-116 3.66550E-04 3.46850E-03 471160 + 510 471161 Ag-116m 9.99150E-04 9.99150E-04 471161 + 511 471170 Ag-117 1.39540E-04 7.07660E-04 471170 + 512 471171 Ag-117m 1.04810E-03 1.52470E-03 471171 + 513 471180 Ag-118 8.43170E-05 5.38820E-04 471180 + 514 471181 Ag-118m 4.08760E-04 4.53560E-04 471181 + 515 471190 Ag-119 3.15200E-05 7.70520E-05 471190 + 516 471191 Ag-119m 2.36740E-04 2.82270E-04 471191 + 517 471200 Ag-120 2.81900E-05 6.24180E-05 471200 + 518 471201 Ag-120m 4.71440E-05 5.93890E-05 471201 + 519 471210 Ag-121 4.85620E-05 5.17180E-05 471210 + 520 471220 Ag-122 1.82470E-05 1.82470E-05 471220 + 521 471221 Ag-122m 1.96720E-05 1.96720E-05 471221 + 522 471230 Ag-123 4.62780E-05 4.62780E-05 471230 + 523 471240 Ag-124 1.04250E-05 1.61870E-05 471240 + 524 471241 Ag-124m 1.12400E-05 1.12400E-05 471241 + 525 471250 Ag-125 7.92360E-06 7.92360E-06 471250 + 526 471260 Ag-126 2.20850E-06 2.20850E-06 471260 + 527 471270 Ag-127 1.80180E-07 1.80180E-07 471270 + 528 471280 Ag-128 7.46330E-09 7.46330E-09 471280 + 529 471290 Ag-129 4.68210E-10 4.68210E-10 471290 + 530 481110 Cd-111 2.18010E-10 3.68620E-02 48111.82c + 531 481111 Cd-111m 8.25590E-10 8.25590E-10 481111 + 532 481120 Cd-112 1.96850E-06 2.87540E-02 48112.82c + 533 481130 Cd-113 2.88240E-06 2.16770E-02 48113.82c + 534 481131 Cd-113m 1.09160E-05 2.59590E-04 481131 + 535 481140 Cd-114 4.10660E-05 1.43310E-02 48114.82c + 536 481150 Cd-115 2.33650E-05 8.09200E-03 481150 + 537 481151 Cd-115m 8.84840E-05 4.48500E-04 48515.82c + 538 481160 Cd-116 1.92000E-04 4.59970E-03 48116.82c + 539 481170 Cd-117 4.47990E-05 1.71090E-03 481170 + 540 481171 Cd-117m 1.69650E-04 6.44460E-04 481171 + 541 481180 Cd-118 2.20020E-04 1.02640E-03 481180 + 542 481190 Cd-119 4.00350E-05 3.60830E-04 481190 + 543 481191 Cd-119m 1.12020E-04 1.50540E-04 481191 + 544 481200 Cd-120 1.50280E-04 2.50110E-04 481200 + 545 481210 Cd-121 3.06930E-05 7.70070E-05 481210 + 546 481211 Cd-121m 8.58770E-05 9.12810E-05 481211 + 547 481220 Cd-122 1.48640E-04 1.86560E-04 481220 + 548 481230 Cd-123 4.47930E-05 8.26640E-05 481230 + 549 481231 Cd-123m 1.25330E-04 1.33750E-04 481231 + 550 481240 Cd-124 3.68650E-04 3.90440E-04 481240 + 551 481250 Cd-125 1.00900E-04 1.04860E-04 481250 + 552 481251 Cd-125m 2.82320E-04 2.86280E-04 481251 + 553 481260 Cd-126 3.16950E-04 3.19160E-04 481260 + 554 481270 Cd-127 1.13350E-04 1.13530E-04 481270 + 555 481280 Cd-128 4.76350E-05 4.76430E-05 481280 + 556 481290 Cd-129 2.39170E-06 2.39190E-06 481290 + 557 481291 Cd-129m 6.69170E-06 6.69200E-06 481291 + 558 481300 Cd-130 1.52440E-07 1.52440E-07 481300 + 559 481310 Cd-131 4.42270E-09 4.42270E-09 481310 + 560 491140 In-114 3.84520E-10 1.67740E-09 491140 + 561 491141 In-114m 6.20920E-10 1.33980E-09 491141 + 562 491142 In-114m 7.18860E-10 7.18860E-10 491142 + 563 491150 In-115 4.36390E-08 8.13600E-03 49115.82c + 564 491151 In-115m 8.78660E-09 8.09210E-03 491151 + 565 491160 In-116 8.08200E-07 8.08200E-07 491160 + 566 491161 In-116m 1.30510E-06 2.81600E-06 491161 + 567 491162 In-116m 1.51090E-06 1.51090E-06 491162 + 568 491170 In-117 8.99330E-06 1.53060E-03 491170 + 569 491171 In-117m 1.81070E-06 1.57950E-03 491171 + 570 491180 In-118 3.28860E-06 1.02970E-03 491180 + 571 491181 In-118m 5.31040E-06 1.13720E-05 491181 + 572 491182 In-118m 6.14800E-06 6.14800E-06 491182 + 573 491190 In-119 2.16680E-05 2.25470E-04 491190 + 574 491191 In-119m 4.36280E-06 3.30440E-04 491191 + 575 491200 In-120 8.73480E-06 2.58850E-04 491200 + 576 491201 In-120m 8.73480E-06 8.73480E-06 491201 + 577 491202 In-120m 8.73480E-06 8.73480E-06 491202 + 578 491210 In-121 4.62160E-05 1.64160E-04 491210 + 579 491211 In-121m 9.30530E-06 6.03770E-05 491211 + 580 491220 In-122 3.35140E-05 2.20070E-04 491220 + 581 491221 In-122m 2.80240E-05 2.80240E-05 491221 + 582 491222 In-122m 2.80240E-05 2.80240E-05 491222 + 583 491230 In-123 1.32920E-04 2.90640E-04 491230 + 584 491231 In-123m 2.67620E-05 8.54530E-05 491231 + 585 491240 In-124 1.35530E-04 5.25980E-04 491240 + 586 491241 In-124m 1.46120E-04 1.46120E-04 491241 + 587 491250 In-125 7.36930E-04 1.07340E-03 491250 + 588 491251 In-125m 1.48380E-04 2.03050E-04 491251 + 589 491260 In-126 6.00970E-04 9.20130E-04 491260 + 590 491261 In-126m 6.47930E-04 6.47930E-04 491261 + 591 491270 In-127 1.57040E-03 1.57040E-03 491270 + 592 491271 In-127m 3.16190E-04 4.29720E-04 491271 + 593 491280 In-128 4.93560E-04 7.34460E-04 491280 + 594 491281 In-128m 1.93260E-04 2.40900E-04 491281 + 595 491282 In-128m 7.40480E-04 7.40480E-04 491282 + 596 491290 In-129 7.81040E-04 7.87740E-04 491290 + 597 491291 In-129m 1.57260E-04 1.59650E-04 491291 + 598 491300 In-130 7.39290E-05 7.40760E-05 491300 + 599 491301 In-130m 1.07650E-04 1.07650E-04 491301 + 600 491302 In-130m 1.49950E-04 1.49950E-04 491302 + 601 491310 In-131 2.08000E-05 2.10160E-05 491310 + 602 491311 In-131m 2.08000E-05 2.08000E-05 491311 + 603 491312 In-131m 2.08000E-05 2.08000E-05 491312 + 604 491320 In-132 4.02600E-06 4.02600E-06 491320 + 605 491330 In-133 4.37070E-08 5.25070E-08 491330 + 606 491331 In-133m 8.80020E-09 8.80020E-09 491331 + 607 491340 In-134 1.53100E-09 1.53100E-09 491340 + 608 501160 Sn-116 1.61640E-10 3.62440E-06 50116.82c + 609 501170 Sn-117 4.26260E-10 2.36610E-03 50117.82c + 610 501171 Sn-117m 1.61420E-09 5.21640E-06 501171 + 611 501180 Sn-118 3.95340E-08 1.04120E-03 50118.82c + 612 501190 Sn-119 6.19430E-08 5.37700E-04 50119.82c + 613 501191 Sn-119m 2.34580E-07 2.03920E-04 501191 + 614 501200 Sn-120 2.21770E-06 2.78530E-04 50120.82c + 615 501210 Sn-121 6.22050E-07 2.21620E-04 501210 + 616 501211 Sn-121m 1.74040E-06 2.03370E-05 501211 + 617 501220 Sn-122 1.23460E-05 2.88480E-04 50122.82c + 618 501230 Sn-123 2.22650E-05 4.44240E-05 50123.82c + 619 501231 Sn-123m 7.95770E-06 3.61890E-04 501231 + 620 501240 Sn-124 1.51710E-04 8.23810E-04 50124.82c + 621 501250 Sn-125 2.58750E-04 4.40070E-04 50125.82c + 622 501251 Sn-125m 9.24790E-05 1.18760E-03 501251 + 623 501260 Sn-126 1.43140E-03 3.00240E-03 50126.82c + 624 501270 Sn-127 2.22720E-03 2.83930E-03 501270 + 625 501271 Sn-127m 7.96010E-04 2.18110E-03 501271 + 626 501280 Sn-128 1.81600E-03 8.24090E-03 501280 + 627 501281 Sn-128m 4.95000E-03 5.69050E-03 501281 + 628 501290 Sn-129 1.85630E-03 2.71990E-03 501290 + 629 501291 Sn-129m 5.19380E-03 5.27770E-03 501291 + 630 501300 Sn-130 1.99380E-03 2.19660E-03 501300 + 631 501301 Sn-130m 5.43470E-03 5.56400E-03 501301 + 632 501310 Sn-131 1.00440E-03 1.04470E-03 501310 + 633 501311 Sn-131m 2.81010E-03 2.83180E-03 501311 + 634 501320 Sn-132 1.48690E-03 1.49100E-03 501320 + 635 501330 Sn-133 1.52490E-04 1.52500E-04 501330 + 636 501340 Sn-134 2.34570E-05 2.34580E-05 501340 + 637 501350 Sn-135 3.81900E-07 3.81900E-07 501350 + 638 501360 Sn-136 1.25630E-08 1.25630E-08 501360 + 639 511190 Sb-119 5.92950E-11 8.31050E-11 511190 + 640 511191 Sb-119m 2.38100E-11 2.38100E-11 511191 + 641 511200 Sb-120 4.95520E-10 4.95520E-10 511200 + 642 511201 Sb-120m 8.28680E-10 8.28680E-10 511201 + 643 511210 Sb-121 3.46490E-08 2.26210E-04 51121.82c + 644 511220 Sb-122 2.08140E-07 4.87000E-07 511220 + 645 511221 Sb-122m 2.78860E-07 2.78860E-07 511221 + 646 511230 Sb-123 7.53300E-06 4.13850E-04 51123.82c + 647 511240 Sb-124 3.62150E-06 9.32050E-06 51124.82c + 648 511241 Sb-124m 2.92140E-06 7.59860E-06 511241 + 649 511242 Sb-124m 4.67720E-06 4.67720E-06 511242 + 650 511250 Sb-125 4.15040E-05 1.66920E-03 51125.82c + 651 511260 Sb-126 4.07910E-05 4.87790E-05 51126.82c + 652 511261 Sb-126m 2.54780E-05 5.70620E-05 511261 + 653 511262 Sb-126m 3.15840E-05 3.15840E-05 511262 + 654 511270 Sb-127 5.23720E-04 5.54410E-03 511270 + 655 511280 Sb-128 6.64120E-04 8.93850E-03 511280 + 656 511281 Sb-128m 9.28880E-04 9.28880E-04 511281 + 657 511290 Sb-129 3.70620E-03 9.87220E-03 511290 + 658 511291 Sb-129m 2.74280E-03 5.38150E-03 511291 + 659 511300 Sb-130 5.39400E-03 1.03730E-02 511300 + 660 511301 Sb-130m 5.39400E-03 8.17600E-03 511301 + 661 511310 Sb-131 1.93170E-02 2.31930E-02 511310 + 662 511320 Sb-132 8.32140E-03 9.81240E-03 511320 + 663 511321 Sb-132m 7.36750E-03 7.36750E-03 511321 + 664 511330 Sb-133 1.12320E-02 1.13880E-02 511330 + 665 511340 Sb-134 7.25140E-04 7.44650E-04 511340 + 666 511341 Sb-134m 1.97660E-03 1.97660E-03 511341 + 667 511350 Sb-135 6.74420E-04 6.74730E-04 511350 + 668 511360 Sb-136 1.01840E-04 1.01850E-04 511360 + 669 511370 Sb-137 1.10090E-05 1.10090E-05 511370 + 670 511380 Sb-138 4.77980E-08 4.77980E-08 511380 + 671 511390 Sb-139 1.59700E-09 1.59700E-09 511390 + 672 521210 Te-121 1.33760E-12 5.83060E-12 521210 + 673 521211 Te-121m 5.06540E-12 5.06540E-12 521211 + 674 521220 Te-122 3.39260E-10 4.74680E-07 52122.82c + 675 521230 Te-123 2.51730E-09 1.20500E-08 52123.82c + 676 521231 Te-123m 9.53280E-09 9.53280E-09 521231 + 677 521250 Te-125 6.12850E-11 1.66920E-03 52125.82c + 678 521251 Te-125m 2.32090E-10 3.73510E-04 521251 + 679 521260 Te-126 2.20420E-06 1.00060E-04 52126.82c + 680 521270 Te-127 4.36210E-06 5.53840E-03 521270 + 681 521271 Te-127m 1.22050E-05 9.25840E-04 52527.82c + 682 521280 Te-128 9.51490E-05 9.92910E-03 52128.82c + 683 521290 Te-129 1.37060E-04 1.25660E-02 521290 + 684 521291 Te-129m 3.83490E-04 6.48900E-03 52529.82c + 685 521300 Te-130 2.93540E-03 2.14840E-02 52130.82c + 686 521310 Te-131 2.05660E-03 2.49910E-02 521310 + 687 521311 Te-131m 5.75410E-03 7.61100E-03 521311 + 688 521320 Te-132 2.33490E-02 4.05290E-02 52132.82c + 689 521330 Te-133 8.72550E-03 2.27630E-02 521330 + 690 521331 Te-133m 2.44140E-02 2.63830E-02 521331 + 691 521340 Te-134 3.70480E-02 3.98740E-02 521340 + 692 521350 Te-135 1.39750E-02 1.45600E-02 521350 + 693 521360 Te-136 6.10130E-03 6.19170E-03 521360 + 694 521370 Te-137 1.35780E-03 1.36340E-03 521370 + 695 521380 Te-138 2.94840E-04 2.94890E-04 521380 + 696 521390 Te-139 1.79710E-05 1.79730E-05 521390 + 697 521400 Te-140 3.99880E-06 3.99880E-06 521400 + 698 521410 Te-141 6.67250E-09 6.67250E-09 521410 + 699 531270 I-127 1.78180E-10 5.56070E-03 53127.82c + 700 531280 I-128 9.63010E-09 9.63010E-09 531280 + 701 531290 I-129 2.00910E-06 1.49690E-02 53129.82c + 702 531300 I-130 3.31890E-05 4.34170E-05 53130.82c + 703 531301 I-130m 1.21760E-05 1.21760E-05 531301 + 704 531310 I-131 3.00130E-04 3.13040E-02 53131.82c + 705 531320 I-132 7.70350E-04 4.18860E-02 531320 + 706 531321 I-132m 6.82050E-04 6.82050E-04 531321 + 707 531330 I-133 4.41130E-03 5.22050E-02 531330 + 708 531331 I-133m 3.26450E-03 3.26450E-03 531331 + 709 531340 I-134 1.10840E-02 6.05450E-02 531340 + 710 531341 I-134m 9.81320E-03 9.81320E-03 531341 + 711 531350 I-135 4.44730E-02 5.90330E-02 53135.82c + 712 531360 I-136 7.79970E-03 1.40120E-02 531360 + 713 531361 I-136m 2.12600E-02 2.12810E-02 531361 + 714 531370 I-137 2.07360E-02 2.20770E-02 531370 + 715 531380 I-138 6.91000E-03 7.18630E-03 531380 + 716 531390 I-139 3.79830E-03 3.81630E-03 531390 + 717 531400 I-140 7.67400E-04 7.71400E-04 531400 + 718 531410 I-141 1.72300E-04 1.72310E-04 531410 + 719 531420 I-142 2.16010E-05 2.16010E-05 531420 + 720 531430 I-143 4.65050E-08 4.65050E-08 531430 + 721 531440 I-144 9.82860E-10 9.82860E-10 531440 + 722 541300 Xe-130 4.73890E-09 4.53700E-05 54130.82c + 723 541310 Xe-131 5.31020E-07 3.13060E-02 54131.82c + 724 541311 Xe-131m 1.48580E-06 3.41510E-04 541311 + 725 541320 Xe-132 1.11880E-05 4.20080E-02 54132.82c + 726 541321 Xe-132m 1.49890E-05 1.49890E-05 541321 + 727 541330 Xe-133 5.05960E-05 5.23970E-02 54133.82c + 728 541331 Xe-133m 1.41560E-04 1.62750E-03 541331 + 729 541340 Xe-134 5.18820E-04 6.27040E-02 54134.82c + 730 541341 Xe-134m 1.41420E-03 1.63990E-03 541341 + 731 541350 Xe-135 2.27690E-03 6.75840E-02 54135.82c + 732 541351 Xe-135m 6.37050E-03 1.61160E-02 541351 + 733 541360 Xe-136 3.29600E-02 6.96870E-02 54136.82c + 734 541370 Xe-137 3.57740E-02 5.67970E-02 541370 + 735 541380 Xe-138 3.89990E-02 4.61780E-02 541380 + 736 541390 Xe-139 2.13540E-02 2.48680E-02 541390 + 737 541400 Xe-140 1.58000E-02 1.65360E-02 541400 + 738 541410 Xe-141 5.60960E-03 5.75110E-03 541410 + 739 541420 Xe-142 1.87910E-03 1.89530E-03 541420 + 740 541430 Xe-143 3.05660E-04 3.05690E-04 541430 + 741 541440 Xe-144 6.01390E-05 6.01400E-05 541440 + 742 541450 Xe-145 2.97610E-06 2.97610E-06 541450 + 743 541460 Xe-146 5.39300E-09 5.39300E-09 541460 + 744 551320 Cs-132 1.00760E-09 1.00760E-09 551320 + 745 551330 Cs-133 1.00470E-06 5.23980E-02 55133.82c + 746 551340 Cs-134 1.62330E-06 3.06050E-06 55134.82c + 747 551341 Cs-134m 1.43720E-06 1.43720E-06 551341 + 748 551350 Cs-135 4.20860E-05 6.77540E-02 55135.82c + 749 551351 Cs-135m 3.11450E-05 3.11450E-05 551351 + 750 551360 Cs-136 4.55140E-04 6.17840E-04 55136.82c + 751 551361 Cs-136m 3.25410E-04 3.25410E-04 551361 + 752 551370 Cs-137 5.81470E-03 6.26120E-02 55137.82c + 753 551380 Cs-138 4.55550E-03 5.69050E-02 551380 + 754 551381 Cs-138m 7.61850E-03 7.61850E-03 551381 + 755 551390 Cs-139 2.23330E-02 4.72010E-02 551390 + 756 551400 Cs-140 2.07890E-02 3.73270E-02 551400 + 757 551410 Cs-141 2.59130E-02 3.16680E-02 551410 + 758 551420 Cs-142 1.48440E-02 1.67360E-02 551420 + 759 551430 Cs-143 8.38110E-03 8.68550E-03 551430 + 760 551440 Cs-144 1.37310E-03 2.11800E-03 551440 + 761 551441 Cs-144m 1.37310E-03 1.37310E-03 551441 + 762 551450 Cs-145 7.29230E-04 7.32060E-04 551450 + 763 551460 Cs-146 1.26410E-04 1.26420E-04 551460 + 764 551470 Cs-147 1.88020E-05 1.88020E-05 551470 + 765 551480 Cs-148 2.22790E-08 2.22790E-08 551480 + 766 551490 Cs-149 6.38040E-10 6.38040E-10 551490 + 767 561350 Ba-135 2.51380E-09 9.54720E-09 56135.82c + 768 561351 Ba-135m 7.03340E-09 7.03340E-09 561351 + 769 561360 Ba-136 1.34130E-06 7.85550E-04 56136.82c + 770 561361 Ba-136m 3.65610E-06 3.65610E-06 561361 + 771 561370 Ba-137 2.21570E-05 6.26960E-02 56137.82c + 772 561371 Ba-137m 6.19950E-05 5.91670E-02 561371 + 773 561380 Ba-138 1.04500E-03 5.93970E-02 56138.82c + 774 561390 Ba-139 3.23160E-03 5.04330E-02 561390 + 775 561400 Ba-140 1.01570E-02 4.74840E-02 56140.82c + 776 561410 Ba-141 1.45430E-02 4.62110E-02 561410 + 777 561420 Ba-142 2.92770E-02 4.61550E-02 561420 + 778 561430 Ba-143 2.63260E-02 3.49370E-02 561430 + 779 561440 Ba-144 2.38690E-02 2.67110E-02 561440 + 780 561450 Ba-145 1.06260E-02 1.12710E-02 561450 + 781 561460 Ba-146 5.14220E-03 5.25600E-03 561460 + 782 561470 Ba-147 1.45550E-03 1.46890E-03 561470 + 783 561480 Ba-148 3.65150E-04 3.65170E-04 561480 + 784 561490 Ba-149 4.77240E-05 4.77250E-05 561490 + 785 561500 Ba-150 3.97780E-06 3.97780E-06 561500 + 786 561510 Ba-151 2.00410E-09 2.00410E-09 561510 + 787 571370 La-137 1.99990E-09 1.99990E-09 571370 + 788 571380 La-138 2.01720E-06 2.01720E-06 57138.82c + 789 571390 La-139 3.39650E-05 5.04670E-02 57139.82c + 790 571400 La-140 1.46190E-04 4.76310E-02 57140.82c + 791 571410 La-141 7.67410E-04 4.69790E-02 571410 + 792 571420 La-142 1.97900E-03 4.81340E-02 571420 + 793 571430 La-143 6.90990E-03 4.18470E-02 571430 + 794 571440 La-144 1.16520E-02 3.83630E-02 571440 + 795 571450 La-145 1.76770E-02 2.89480E-02 571450 + 796 571460 La-146 4.20610E-03 9.46210E-03 571460 + 797 571461 La-146m 8.82390E-03 8.82390E-03 571461 + 798 571470 La-147 1.12580E-02 1.27280E-02 571470 + 799 571480 La-148 4.98560E-03 5.34950E-03 571480 + 800 571490 La-149 1.96650E-03 2.01400E-03 571490 + 801 571500 La-150 4.51360E-04 4.55340E-04 571500 + 802 571510 La-151 7.32520E-05 7.32540E-05 571510 + 803 571520 La-152 1.18340E-05 1.18340E-05 571520 + 804 571530 La-153 1.07300E-08 1.07300E-08 571530 + 805 571540 La-154 1.85990E-10 1.85990E-10 571540 + 806 581400 Ce-140 9.99750E-07 4.76320E-02 58140.82c + 807 581410 Ce-141 1.19720E-05 4.69910E-02 58141.82c + 808 581420 Ce-142 9.73540E-05 4.82310E-02 58142.82c + 809 581430 Ce-143 3.63570E-04 4.22100E-02 58143.82c + 810 581440 Ce-144 1.79670E-03 4.01590E-02 58144.82c + 811 581450 Ce-145 4.50890E-03 3.34570E-02 581450 + 812 581460 Ce-146 1.08570E-02 2.91430E-02 581460 + 813 581470 Ce-147 1.36640E-02 2.63920E-02 581470 + 814 581480 Ce-148 1.73200E-02 2.26980E-02 581480 + 815 581490 Ce-149 1.13040E-02 1.33020E-02 581490 + 816 581500 Ce-150 7.35750E-03 7.80050E-03 581500 + 817 581510 Ce-151 2.54660E-03 2.62060E-03 581510 + 818 581520 Ce-152 8.82130E-04 8.93250E-04 581520 + 819 581530 Ce-153 1.31600E-04 1.31610E-04 581530 + 820 581540 Ce-154 2.48290E-05 2.48290E-05 581540 + 821 581550 Ce-155 3.52090E-08 3.52090E-08 581550 + 822 581560 Ce-156 9.41200E-10 9.41200E-10 581560 + 823 591420 Pr-142 3.07990E-10 1.14750E-09 59142.82c + 824 591421 Pr-142m 8.39510E-10 8.39510E-10 591421 + 825 591430 Pr-143 9.92010E-07 4.22110E-02 59143.82c + 826 591440 Pr-144 1.61630E-06 4.01770E-02 591440 + 827 591441 Pr-144m 1.64430E-05 5.70620E-04 591441 + 828 591450 Pr-145 8.04500E-05 3.35380E-02 591450 + 829 591460 Pr-146 2.90760E-04 2.94340E-02 591460 + 830 591470 Pr-147 1.21480E-03 2.76070E-02 591470 + 831 591480 Pr-148 4.73070E-04 2.31710E-02 591480 + 832 591481 Pr-148m 2.29340E-03 2.29340E-03 591481 + 833 591490 Pr-149 6.15590E-03 1.94580E-02 591490 + 834 591500 Pr-150 6.87270E-03 1.46730E-02 591500 + 835 591510 Pr-151 7.22810E-03 9.84870E-03 591510 + 836 591520 Pr-152 4.14990E-03 5.04400E-03 591520 + 837 591530 Pr-153 2.18450E-03 2.31550E-03 591530 + 838 591540 Pr-154 7.22840E-04 7.47510E-04 591540 + 839 591550 Pr-155 1.59990E-04 1.60030E-04 591550 + 840 591560 Pr-156 1.99320E-05 1.99330E-05 591560 + 841 591570 Pr-157 6.00880E-06 6.00880E-06 591570 + 842 591580 Pr-158 2.35840E-09 2.35840E-09 591580 + 843 591590 Pr-159 5.29500E-11 5.29500E-11 591590 + 844 601450 Nd-145 4.75760E-09 3.35380E-02 60145.82c + 845 601460 Nd-146 6.92390E-06 2.94410E-02 60146.82c + 846 601470 Nd-147 3.36740E-05 2.76410E-02 60147.82c + 847 601480 Nd-148 2.30010E-04 2.56940E-02 60148.82c + 848 601490 Nd-149 7.30510E-04 2.01890E-02 601490 + 849 601500 Nd-150 2.39970E-03 1.70730E-02 60150.82c + 850 601510 Nd-151 4.18280E-03 1.40320E-02 601510 + 851 601520 Nd-152 6.43450E-03 1.14790E-02 601520 + 852 601530 Nd-153 5.68610E-03 8.00150E-03 601530 + 853 601540 Nd-154 4.75370E-03 5.50120E-03 601540 + 854 601550 Nd-155 2.13350E-03 2.29410E-03 601550 + 855 601560 Nd-156 9.75840E-04 9.95620E-04 601560 + 856 601570 Nd-157 2.43740E-04 2.49360E-04 601570 + 857 601580 Nd-158 5.41020E-05 5.41040E-05 601580 + 858 601590 Nd-159 6.00170E-06 6.00170E-06 601590 + 859 601600 Nd-160 1.02710E-08 1.02710E-08 601600 + 860 601610 Nd-161 1.38890E-10 1.38890E-10 601610 + 861 611470 Pm-147 8.66610E-10 2.76410E-02 61147.82c + 862 611480 Pm-148 5.64770E-09 6.41740E-09 61148.82c + 863 611481 Pm-148m 1.53940E-08 1.53940E-08 61548.82c + 864 611490 Pm-149 3.97980E-06 2.01920E-02 61149.82c + 865 611500 Pm-150 3.18410E-05 3.18410E-05 611500 + 866 611510 Pm-151 1.50910E-04 1.41820E-02 61151.82c + 867 611520 Pm-152 7.45440E-05 1.15530E-02 611520 + 868 611521 Pm-152m 1.56720E-04 1.56720E-04 611521 + 869 611522 Pm-152m 2.04710E-04 2.04710E-04 611522 + 870 611530 Pm-153 1.15200E-03 9.15350E-03 611530 + 871 611540 Pm-154 9.11450E-04 6.41270E-03 611540 + 872 611541 Pm-154m 9.11450E-04 9.11450E-04 611541 + 873 611550 Pm-155 2.42690E-03 4.72100E-03 611550 + 874 611560 Pm-156 1.80270E-03 2.79830E-03 611560 + 875 611570 Pm-157 1.33880E-03 1.58820E-03 611570 + 876 611580 Pm-158 5.37460E-04 5.91580E-04 611580 + 877 611590 Pm-159 1.95720E-04 2.01710E-04 611590 + 878 611600 Pm-160 3.69750E-05 3.69850E-05 611600 + 879 611610 Pm-161 1.35370E-05 1.35370E-05 611610 + 880 611620 Pm-162 1.85840E-06 1.85840E-06 611620 + 881 611630 Pm-163 4.01710E-10 4.01710E-10 611630 + 882 621500 Sm-150 3.16400E-09 3.18440E-05 62150.82c + 883 621510 Sm-151 9.90900E-07 1.41830E-02 62151.82c + 884 621520 Sm-152 2.26940E-05 1.19370E-02 62152.82c + 885 621530 Sm-153 2.27310E-05 9.23990E-03 62153.82c + 886 621531 Sm-153m 6.36000E-05 6.36000E-05 621531 + 887 621540 Sm-154 3.50030E-04 7.67410E-03 62154.82c + 888 621550 Sm-155 6.98540E-04 5.41950E-03 621550 + 889 621560 Sm-156 1.42690E-03 4.22520E-03 621560 + 890 621570 Sm-157 1.61140E-03 3.19960E-03 621570 + 891 621580 Sm-158 1.62900E-03 2.22060E-03 621580 + 892 621590 Sm-159 9.90080E-04 1.19180E-03 621590 + 893 621600 Sm-160 5.56660E-04 5.93550E-04 621600 + 894 621610 Sm-161 1.78750E-04 1.92290E-04 621610 + 895 621620 Sm-162 6.54300E-05 6.72880E-05 621620 + 896 621630 Sm-163 9.04180E-06 9.04220E-06 621630 + 897 621640 Sm-164 4.20140E-08 4.20140E-08 621640 + 898 621650 Sm-165 7.75190E-10 7.75190E-10 621650 + 899 631520 Eu-152 1.12440E-10 2.61360E-10 63152.82c + 900 631521 Eu-152m 2.56910E-11 2.56910E-11 631521 + 901 631522 Eu-152m 1.48920E-10 1.48920E-10 631522 + 902 631530 Eu-153 9.91200E-07 9.24090E-03 63153.82c + 903 631540 Eu-154 1.43460E-06 2.98120E-06 63154.82c + 904 631541 Eu-154m 1.54670E-06 1.54670E-06 631541 + 905 631550 Eu-155 1.39480E-05 5.43350E-03 63155.82c + 906 631560 Eu-156 4.09590E-05 4.26620E-03 63156.82c + 907 631570 Eu-157 1.41160E-04 3.34070E-03 63157.82c + 908 631580 Eu-158 2.52470E-04 2.47310E-03 631580 + 909 631590 Eu-159 4.27680E-04 1.61950E-03 631590 + 910 631600 Eu-160 4.14500E-04 1.00800E-03 631600 + 911 631610 Eu-161 3.97370E-04 5.89660E-04 631610 + 912 631620 Eu-162 1.69410E-04 2.36700E-04 631620 + 913 631630 Eu-163 9.27540E-05 1.01800E-04 631630 + 914 631640 Eu-164 2.39780E-05 2.40200E-05 631640 + 915 631650 Eu-165 1.82800E-06 1.82880E-06 631650 + 916 631660 Eu-166 4.21040E-08 4.21040E-08 631660 + 917 631670 Eu-167 2.05290E-09 2.05290E-09 631670 + 918 641550 Gd-155 2.62090E-07 5.43450E-03 64155.82c + 919 641551 Gd-155m 7.33300E-07 7.33300E-07 641551 + 920 641560 Gd-156 1.99310E-06 4.26820E-03 64156.82c + 921 641570 Gd-157 2.00250E-06 3.34270E-03 64157.82c + 922 641580 Gd-158 2.59580E-05 2.49900E-03 64158.82c + 923 641590 Gd-159 6.82260E-05 1.68780E-03 641590 + 924 641600 Gd-160 1.77440E-04 1.18550E-03 64160.82c + 925 641610 Gd-161 2.28570E-04 8.18230E-04 641610 + 926 641620 Gd-162 2.88780E-04 5.25480E-04 641620 + 927 641630 Gd-163 1.80860E-04 2.82660E-04 641630 + 928 641640 Gd-164 1.31480E-04 1.55500E-04 641640 + 929 641650 Gd-165 5.12220E-05 5.30510E-05 641650 + 930 641660 Gd-166 1.85260E-05 1.85680E-05 641660 + 931 641670 Gd-167 3.58350E-06 3.58550E-06 641670 + 932 641680 Gd-168 1.08210E-07 1.08210E-07 641680 + 933 641690 Gd-169 2.01360E-09 2.01360E-09 641690 + 934 651570 Tb-157 1.05150E-10 1.05150E-10 651570 + 935 651580 Tb-158 1.76200E-09 1.93410E-09 651580 + 936 651581 Tb-158m 1.73200E-10 1.73200E-10 651581 + 937 651590 Tb-159 5.48560E-08 1.68780E-03 65159.82c + 938 651600 Tb-160 9.72650E-07 9.72650E-07 65160.82c + 939 651610 Tb-161 4.82850E-06 8.23060E-04 651610 + 940 651620 Tb-162 1.39090E-05 5.39390E-04 651620 + 941 651630 Tb-163 3.32800E-05 3.15940E-04 651630 + 942 651640 Tb-164 3.81800E-05 1.93680E-04 651640 + 943 651650 Tb-165 4.74530E-05 1.00500E-04 651650 + 944 651660 Tb-166 2.77670E-05 4.63350E-05 651660 + 945 651670 Tb-167 2.32980E-05 2.68840E-05 651670 + 946 651680 Tb-168 7.49760E-06 7.60580E-06 651680 + 947 651690 Tb-169 2.96220E-06 2.96420E-06 651690 + 948 651700 Tb-170 2.74100E-08 2.74100E-08 651700 + 949 651710 Tb-171 3.73700E-09 3.73700E-09 651710 + 950 661600 Dy-160 1.73350E-10 9.72820E-07 66160.82c + 951 661610 Dy-161 4.44460E-09 8.23060E-04 66161.82c + 952 661620 Dy-162 9.46270E-08 5.39480E-04 66162.82c + 953 661630 Dy-163 2.70820E-06 3.18640E-04 66163.82c + 954 661640 Dy-164 1.70150E-06 1.95380E-04 66164.82c + 955 661650 Dy-165 9.66690E-06 1.11430E-04 661650 + 956 661651 Dy-165m 1.28710E-06 1.28710E-06 661651 + 957 661660 Dy-166 2.77320E-05 7.40670E-05 661660 + 958 661670 Dy-167 2.32740E-05 5.01580E-05 661670 + 959 661680 Dy-168 2.43570E-05 3.19630E-05 661680 + 960 661690 Dy-169 5.92380E-06 8.88800E-06 661690 + 961 661700 Dy-170 1.78810E-06 1.81550E-06 661700 + 962 661710 Dy-171 9.85040E-07 9.88780E-07 661710 + 963 661720 Dy-172 9.40560E-08 9.40560E-08 661720 + 964 661730 Dy-173 3.48880E-09 3.48880E-09 661730 + 965 671620 Ho-162 3.52490E-12 9.48190E-12 671620 + 966 671621 Ho-162m 9.60810E-12 9.60810E-12 671621 + 967 671630 Ho-163 2.74740E-10 3.11320E-10 671630 + 968 671631 Ho-163m 3.65800E-11 3.65800E-11 671631 + 969 671640 Ho-164 1.27440E-09 4.74830E-09 671640 + 970 671641 Ho-164m 3.47390E-09 3.47390E-09 671641 + 971 671650 Ho-165 6.63570E-08 1.11520E-04 67165.82c + 972 671660 Ho-166 1.00380E-07 7.41680E-05 671660 + 973 671661 Ho-166m 2.73630E-07 2.73630E-07 671661 + 974 671670 Ho-167 2.15170E-06 5.23090E-05 671670 + 975 671680 Ho-168 1.40210E-06 3.56980E-05 671680 + 976 671681 Ho-168m 2.34490E-06 2.34490E-06 671681 + 977 671690 Ho-169 1.97440E-06 1.08620E-05 671690 + 978 671700 Ho-170 1.96210E-06 1.96210E-06 671700 + 979 671701 Ho-170m 7.19850E-07 2.53540E-06 671701 + 980 671710 Ho-171 9.85000E-07 1.97380E-06 671710 + 981 671720 Ho-172 1.87700E-06 1.97110E-06 671720 + 982 671730 Ho-173 2.76270E-07 2.79760E-07 671730 + 983 671740 Ho-174 7.29770E-08 7.29770E-08 671740 + 984 671750 Ho-175 1.48890E-08 1.48890E-08 671750 + 985 681650 Er-165 1.26040E-11 1.26040E-11 681650 + 986 681660 Er-166 5.03430E-10 7.41680E-05 68166.82c + 987 681670 Er-167 5.75690E-09 5.23160E-05 68167.82c + 988 681671 Er-167m 7.66500E-10 6.25130E-06 681671 + 989 681680 Er-168 8.69950E-08 3.57970E-05 68168.82c + 990 681690 Er-169 9.87200E-07 1.18500E-05 681690 + 991 681700 Er-170 4.70910E-07 4.96840E-06 68170.82c + 992 681710 Er-171 2.95470E-06 4.92850E-06 681710 + 993 681720 Er-172 1.87690E-06 3.84800E-06 681720 + 994 681730 Er-173 1.45770E-06 1.73750E-06 681730 + 995 681740 Er-174 9.40010E-07 1.01300E-06 681740 + 996 681750 Er-175 9.14720E-07 9.29610E-07 681750 + 997 681760 Er-176 4.29230E-08 4.29230E-08 681760 + 998 681770 Er-177 2.93890E-09 2.93890E-09 681770 + 999 691670 Tm-167 1.57550E-12 1.57550E-12 691670 + 1000 691680 Tm-168 2.58090E-11 2.58090E-11 691680 + 1001 691690 Tm-169 3.61720E-10 1.18500E-05 691690 + 1002 691700 Tm-170 1.99380E-09 1.99380E-09 691700 + 1003 691710 Tm-171 3.16640E-08 4.96010E-06 691710 + 1004 691720 Tm-172 1.21910E-07 3.96990E-06 691720 + 1005 691730 Tm-173 2.44140E-07 1.98160E-06 691730 + 1006 691740 Tm-174 9.39970E-07 1.95300E-06 691740 + 1007 691750 Tm-175 9.14680E-07 1.84430E-06 691750 + 1008 691760 Tm-176 1.79360E-07 2.22280E-07 691760 + 1009 691770 Tm-177 6.67650E-08 6.97040E-08 691770 + 1010 691780 Tm-178 1.53330E-08 1.53330E-08 691780 + 1011 691790 Tm-179 3.38520E-09 3.38520E-09 691790 + 1012 701710 Yb-171 2.92880E-12 4.96020E-06 701710 + 1013 701711 Yb-171m 2.19970E-11 2.19970E-11 701711 + 1014 701720 Yb-172 6.16360E-10 3.97050E-06 701720 + 1015 701730 Yb-173 2.67540E-09 1.98430E-06 701730 + 1016 701740 Yb-174 3.82930E-08 1.99130E-06 701740 + 1017 701750 Yb-175 1.29050E-07 1.99050E-06 701750 + 1018 701751 Yb-175m 1.71820E-08 1.43730E-06 701751 + 1019 701760 Yb-176 3.66960E-08 3.17150E-07 701760 + 1020 701761 Yb-176m 7.69840E-08 1.88130E-07 701761 + 1021 701770 Yb-177 1.24640E-07 2.19440E-07 701770 + 1022 701771 Yb-177m 2.50960E-08 9.48000E-08 701771 + 1023 701780 Yb-178 8.42570E-08 9.95900E-08 701780 + 1024 701790 Yb-179 3.42390E-08 3.76240E-08 701790 + 1025 701800 Yb-180 1.42600E-08 1.42600E-08 701800 + 1026 701810 Yb-181 2.07010E-09 2.07010E-09 701810 + 1027 711730 Lu-173 1.32790E-12 1.32790E-12 711730 + 1028 711740 Lu-174 1.14850E-11 4.26100E-11 711740 + 1029 711741 Lu-174m 3.13070E-11 3.13070E-11 711741 + 1030 711750 Lu-175 1.03280E-09 1.99160E-06 71175.82c + 1031 711760 Lu-176 1.14920E-09 1.99620E-08 71176.82c + 1032 711761 Lu-176m 5.47790E-10 5.47790E-10 711761 + 1033 711770 Lu-177 4.14740E-09 2.24050E-07 711770 + 1034 711771 Lu-177m 1.97480E-09 2.02400E-09 711771 + 1035 711772 Lu-177m 9.82740E-11 9.82740E-11 711772 + 1036 711780 Lu-178 5.66430E-09 1.05250E-07 711780 + 1037 711781 Lu-178m 7.58870E-09 7.58870E-09 711781 + 1038 711790 Lu-179 2.38660E-08 6.46680E-08 711790 + 1039 711791 Lu-179m 3.17770E-09 4.08020E-08 711791 + 1040 711800 Lu-180 5.17300E-09 1.94700E-08 711800 + 1041 711801 Lu-180m 5.17300E-09 1.94330E-08 711801 + 1042 711802 Lu-180m 9.16000E-09 9.16000E-09 711802 + 1043 711810 Lu-181 1.44530E-08 1.65230E-08 711810 + 1044 711820 Lu-182 4.24720E-09 4.24720E-09 711820 + 1045 711830 Lu-183 1.45390E-09 1.45390E-09 711830 + 1046 711840 Lu-184 1.63350E-10 1.63350E-10 711840 + 1047 721760 Hf-176 2.22900E-12 5.49500E-10 72176.82c + 1048 721770 Hf-177 1.22500E-11 2.25680E-07 72177.82c + 1049 721771 Hf-177m 5.77950E-12 1.62180E-09 721771 + 1050 721772 Hf-177m 3.41700E-13 4.94790E-11 721772 + 1051 721780 Hf-178 7.82180E-11 1.13080E-07 72178.82c + 1052 721781 Hf-178m 1.45870E-10 7.75280E-09 721781 + 1053 721782 Hf-178m 1.82460E-11 1.82460E-11 721782 + 1054 721790 Hf-179 5.88180E-10 6.56860E-08 72179.82c + 1055 721791 Hf-179m 1.70200E-10 1.70200E-10 721791 + 1056 721792 Hf-179m 2.57120E-10 2.57120E-10 721792 + 1057 721800 Hf-180 1.29720E-09 3.77680E-08 72180.82c + 1058 721801 Hf-180m 2.72150E-09 7.30150E-09 721801 + 1059 721810 Hf-181 5.36280E-09 2.18860E-08 721810 + 1060 721820 Hf-182 2.52010E-09 8.98770E-09 721820 + 1061 721821 Hf-182m 5.28680E-09 5.28680E-09 721821 + 1062 721830 Hf-183 4.67620E-09 6.13010E-09 721830 + 1063 721840 Hf-184 8.90860E-10 9.72540E-10 721840 + 1064 721841 Hf-184m 1.86890E-09 1.95060E-09 721841 + 1065 721850 Hf-185 6.89640E-10 6.89640E-10 721850 + 1066 721860 Hf-186 1.87370E-10 1.87370E-10 721860 + 1067 721870 Hf-187 1.69540E-11 1.69540E-11 721870 + 1068 721880 Hf-188 1.47380E-12 1.47380E-12 721880 + 1069 731790 Ta-179 1.34990E-12 1.89200E-12 731790 + 1070 731800 Ta-180 7.08630E-12 7.08630E-12 731800 + 1071 731801 Ta-180m 9.49370E-12 3.21280E-11 731801 + 1072 731810 Ta-181 1.33620E-10 2.20200E-08 73181.82c + 1073 731820 Ta-182 1.24890E-10 3.45330E-09 73182.82c + 1074 731821 Ta-182m 1.36420E-10 3.32840E-09 731821 + 1075 731822 Ta-182m 1.25620E-10 3.19200E-09 731822 + 1076 731830 Ta-183 1.22930E-09 7.35940E-09 731830 + 1077 731840 Ta-184 1.27630E-09 4.19940E-09 731840 + 1078 731850 Ta-185 9.87740E-10 2.26670E-09 731850 + 1079 731851 Ta-185m 5.89360E-10 5.89360E-10 731851 + 1080 731860 Ta-186 7.65530E-10 9.52900E-10 731860 + 1081 731870 Ta-187 3.76060E-10 3.93010E-10 731870 + 1082 731880 Ta-188 6.65020E-11 6.79760E-11 731880 + 1083 731890 Ta-189 1.48250E-11 1.48250E-11 731890 + 1084 731900 Ta-190 1.10680E-12 1.10680E-12 731900 + 1085 741820 W-182 1.90580E-12 3.45520E-09 74182.82c + 1086 741830 W-183 2.74350E-12 7.37250E-09 74183.82c + 1087 741831 W-183m 1.03890E-11 2.60610E-10 741831 + 1088 741840 W-184 8.00150E-11 4.27950E-09 74184.82c + 1089 741850 W-185 5.00510E-11 2.45680E-09 741850 + 1090 741851 W-185m 1.40040E-10 1.40040E-10 741851 + 1091 741860 W-186 3.37980E-10 1.42790E-09 74186.82c + 1092 741861 W-186m 1.36840E-10 1.36840E-10 741861 + 1093 741870 W-187 4.04720E-10 7.97730E-10 741870 + 1094 741880 W-188 3.57490E-10 4.25470E-10 741880 + 1095 741890 W-189 1.46510E-10 1.61330E-10 741890 + 1096 741900 W-190 2.62650E-11 6.25590E-11 741900 + 1097 741901 W-190m 3.51870E-11 3.51870E-11 741901 + 1098 741910 W-191 9.01370E-12 9.01370E-12 741910 + 1099 741920 W-192 1.40850E-12 1.40850E-12 741920 + 1100 751850 Re-185 1.30820E-12 2.45810E-09 75185.82c + 1101 751860 Re-186 2.58750E-12 2.58750E-12 751860 + 1102 751861 Re-186m 4.32730E-12 4.32730E-12 751861 + 1103 751870 Re-187 3.34990E-11 8.31230E-10 75187.82c + 1104 751880 Re-188 1.47620E-11 4.80470E-10 751880 + 1105 751881 Re-188m 4.02390E-11 4.02390E-11 751881 + 1106 751890 Re-189 1.13280E-10 2.74610E-10 751890 + 1107 751900 Re-190 2.65560E-11 1.14520E-10 751900 + 1108 751901 Re-190m 5.57110E-11 5.57110E-11 751901 + 1109 751910 Re-191 6.15310E-11 7.05450E-11 751910 + 1110 751920 Re-192 1.82680E-11 1.96760E-11 751920 + 1111 751930 Re-193 6.30030E-12 6.30030E-12 751930 + 1112 761890 Os-189 8.67390E-13 2.78770E-10 761890 + 1113 761891 Os-189m 3.28480E-12 3.15240E-11 761891 + 1114 761900 Os-190 7.08070E-12 1.61390E-10 761900 + 1115 761901 Os-190m 9.48630E-12 3.97930E-11 761901 + 1116 761910 Os-191 1.76740E-11 9.28860E-11 761910 + 1117 761911 Os-191m 4.66700E-12 4.66700E-12 761911 + 1118 761920 Os-192 1.40490E-11 5.02950E-11 761920 + 1119 761921 Os-192m 1.88230E-11 1.88230E-11 761921 + 1120 761930 Os-193 1.98240E-11 2.61240E-11 761930 + 1121 761940 Os-194 1.17820E-11 1.17820E-11 761940 + 1122 761950 Os-195 2.97560E-12 2.97560E-12 761950 + 1123 771920 Ir-192 5.30380E-13 4.03800E-12 771920 + 1124 771922 Ir-192m 5.30380E-13 2.97730E-12 771922 + 1125 771930 Ir-193 1.34220E-12 3.12220E-11 77193.82c + 1126 771931 Ir-193m 3.75520E-12 3.84600E-12 771931 + 1127 771940 Ir-194 1.77760E-12 1.53370E-11 771940 + 1128 771941 Ir-194m 1.77760E-12 1.77760E-12 771941 + 1129 771942 Ir-194m 1.77760E-12 1.77760E-12 771942 + 1130 771950 Ir-195 1.75350E-12 4.97440E-12 771950 + 1131 771951 Ir-195m 4.90620E-12 4.90620E-12 771951 + 1132 771960 Ir-196 1.63090E-12 1.63570E-12 771960 + 1133 771961 Ir-196m 1.63090E-12 1.63090E-12 771961 + 1134 771971 Ir-197m 1.18910E-12 1.18910E-12 771971 + 1135 781960 Pt-196 1.97970E-12 5.24140E-12 781960 + 1136 781970 Pt-197 4.47740E-13 3.23410E-12 781970 + 1137 781971 Pt-197m 1.25280E-12 2.43890E-12 781971 + 1138 781980 Pt-198 1.51570E-12 1.51570E-12 781980 + + Nuclide 96246.82c -- curium 246 (Cm-246) is using NFY data from U-233 + + Nuclide 96247.82c -- curium 247 (Cm-247) is using NFY data from U-233 + + Nuclide 96248.82c -- curium 248 (Cm-248) is using NFY data from U-233 + + Nuclide 96249.82c -- curium 249 (Cm-249) is using NFY data from U-233 + + Nuclide 96250.82c -- curium 250 (Cm-250) is using NFY data from U-233 + + --- Table 4: Lost transmutation paths: + + No lost transmutation paths. + + + --- Table 1: Summary of material compositions: + + 6 materials included in calculation + + +Material "fuel": + + - Material is included in majorant + - Material is included in geometry + - Atom density 8.02292E-02 1/barn*cm + - Mass density 4.96020E+00 g/cm3 + - Volume 2.27175E+07 cm3 + - Mass 1.12683E+08 g + - Photon emission rate 0.00000E+00 1/s + - Neutron emission rate 0.00000E+00 1/s + - 1655 nuclides in composition + - No nuclides associated with S(a,b) data + - 24.69 Mb of memory allocated for data + +Isotopic composition (non-zero densities): + +------------------------------------------------------------------- + Nuclide a. weight temp a. dens a. frac m. frac +------------------------------------------------------------------- + 1001.82c 1.00783 900.0 1.18035E-09 1.47122E-08 3.98248E-10 + 1002.82c 2.01410 900.0 6.03514E-11 7.52237E-10 4.06935E-11 + 1003.82c 3.01605 900.0 4.04988E-09 5.04789E-08 4.08919E-09 + 2003.82c 3.01493 900.0 1.86083E-12 2.31940E-11 1.87820E-12 + 2004.82c 4.00258 900.0 3.18090E-08 3.96476E-07 4.26233E-08 + 20060 6.01889 900.0 5.31208E-17 6.62113E-16 1.07038E-16 + 20080 8.03393 900.0 6.14397E-22 7.65802E-21 1.65247E-21 + 3006.82c 6.01507 900.0 1.19687E-06 1.49181E-05 2.41015E-06 + 3007.82c 7.01600 900.0 2.05883E-02 2.56618E-01 4.83578E-02 + 30080 8.02249 900.0 7.58655E-15 9.45609E-14 2.03756E-14 + 30090 9.02679 900.0 1.60293E-19 1.99793E-18 4.84400E-19 + 40080 8.00531 900.0 2.05784E-34 2.56495E-33 5.51502E-34 + 4009.82c 9.01220 900.0 4.84275E-13 6.03614E-12 1.46110E-12 + 40100 10.01353 900.0 4.10694E-12 5.11901E-11 1.37677E-11 + 40110 11.02168 900.0 7.61236E-20 9.48826E-19 2.80882E-19 + 40120 12.02692 900.0 5.95014E-21 7.41642E-20 2.39573E-20 + 50090 9.01333 900.0 7.12517E-37 8.88102E-36 2.15000E-36 + 5010.82c 10.01294 900.0 4.06942E-12 5.07224E-11 1.36412E-11 + 5011.82c 11.00928 900.0 7.23568E-16 9.01876E-15 2.66683E-15 + 50120 12.01431 900.0 1.12159E-20 1.39799E-19 4.51119E-20 + 60120 11.99999 900.0 3.83104E-13 4.77511E-12 1.53905E-12 + 60130 13.00331 900.0 1.41439E-15 1.76293E-14 6.15713E-15 + 60140 14.00319 900.0 1.24591E-12 1.55293E-11 5.84076E-12 + 60150 15.01065 900.0 1.35448E-18 1.68827E-17 6.80660E-18 + 70130 13.00573 900.0 8.84680E-32 1.10269E-30 3.85192E-31 + 7014.82c 14.00307 900.0 2.13393E-18 2.65979E-17 1.00037E-17 + 7015.82c 14.99986 900.0 4.27272E-09 5.32564E-08 2.14560E-08 + 70160 16.00610 900.0 3.10212E-13 3.86657E-12 1.66227E-12 + 70170 17.00841 900.0 2.79301E-26 3.48129E-25 1.59035E-25 + 80150 15.00308 900.0 6.73379E-25 8.39319E-24 3.38218E-24 + 8016.82c 15.99492 900.0 1.55939E-08 1.94367E-07 8.35013E-08 + 8017.82c 16.99913 900.0 8.53435E-12 1.06375E-10 4.85684E-11 + 80180 17.99912 900.0 8.76023E-11 1.09190E-09 5.27866E-10 + 80190 19.00355 900.0 8.51773E-14 1.06167E-12 5.41896E-13 + 90180 18.00094 900.0 1.78160E-13 2.22064E-12 1.07365E-12 + 9019.82c 18.99820 900.0 5.18290E-02 6.46012E-01 3.29642E-01 + 90200 20.00001 900.0 1.71200E-13 2.13388E-12 1.14628E-12 + 100200 19.99245 900.0 5.56681E-09 6.93862E-08 3.72588E-08 + 100210 20.99385 900.0 1.69030E-12 2.10684E-11 1.18799E-11 + 190500 49.97279 900.0 7.27604E-26 9.06906E-25 1.21727E-24 + 190510 50.97641 900.0 2.04021E-26 2.54297E-25 3.48178E-25 + 200450 44.95620 900.0 7.71888E-33 9.62103E-32 1.16172E-31 + 200460 45.95367 900.0 1.31534E-29 1.63947E-28 2.02355E-28 + 200470 46.95456 900.0 1.59566E-28 1.98887E-27 2.50827E-27 + 200480 47.95254 900.0 1.08602E-34 1.35365E-33 1.74344E-33 + 200490 48.95566 900.0 2.33894E-23 2.91532E-22 3.83336E-22 + 200500 49.95756 900.0 7.13866E-23 8.89782E-22 1.19392E-21 + 200510 50.96149 900.0 2.44386E-23 3.04609E-22 4.16941E-22 + 200520 51.96511 900.0 7.77171E-24 9.68688E-23 1.35203E-22 + 200530 52.97004 900.0 3.68312E-26 4.59075E-25 6.53135E-25 + 200540 53.97437 900.0 6.27145E-27 7.81691E-26 1.13322E-25 + 21045.82c 44.95591 900.0 5.54633E-35 6.91311E-34 8.34737E-34 + 210470 46.95245 900.0 3.91087E-29 4.87462E-28 6.14736E-28 + 210480 47.95224 900.0 1.86808E-31 2.32843E-30 2.99889E-30 + 210490 48.95001 900.0 1.53425E-22 1.91233E-21 2.51423E-21 + 210500 49.95222 900.0 1.02982E-21 1.28359E-20 1.72216E-20 + 210501 49.95222 900.0 2.11401E-24 2.63497E-23 3.53524E-23 + 210510 50.95362 900.0 1.82453E-22 2.27415E-21 3.11232E-21 + 210520 51.95664 900.0 1.10229E-22 1.37392E-21 1.91731E-21 + 210530 52.95965 900.0 4.47687E-23 5.58010E-22 7.93737E-22 + 210540 53.96327 900.0 1.57610E-24 1.96450E-23 2.84735E-23 + 210550 54.96821 900.0 4.65688E-25 5.80447E-24 8.56966E-24 + 210560 55.97284 900.0 6.85750E-26 8.54739E-25 1.28499E-24 + 210570 56.97777 900.0 3.14671E-27 3.92215E-26 6.00232E-26 + 22047.82c 46.95134 900.0 1.35266E-29 1.68599E-28 2.12615E-28 + 22048.82c 47.94795 900.0 1.35703E-28 1.69145E-27 2.17830E-27 + 22049.82c 48.94788 900.0 1.58390E-20 1.97422E-19 2.59548E-19 + 22050.82c 49.94480 900.0 3.90712E-18 4.86994E-17 6.53287E-17 + 220510 50.94666 900.0 6.16426E-21 7.68331E-20 1.05137E-19 + 220520 51.94685 900.0 2.90208E-21 3.61724E-20 5.04692E-20 + 220530 52.94977 900.0 1.35546E-21 1.68949E-20 2.40275E-20 + 220540 53.95107 900.0 8.96911E-23 1.11794E-21 1.61997E-21 + 220550 54.95530 900.0 2.44710E-23 3.05014E-22 4.50214E-22 + 220560 55.95821 900.0 9.06618E-24 1.13003E-22 1.69842E-22 + 220570 56.96395 900.0 1.19535E-24 1.48992E-23 2.27957E-23 + 220580 57.96697 900.0 5.92454E-25 7.38452E-24 1.14972E-23 + 220590 58.97291 900.0 6.71251E-26 8.36666E-25 1.32524E-24 + 220600 59.97673 900.0 1.31140E-26 1.63456E-25 2.63314E-25 + 220610 60.98318 900.0 5.53559E-28 6.89972E-27 1.13014E-26 + 230500 49.94717 900.0 5.15126E-30 6.42067E-29 8.61353E-29 + 230510 50.94394 900.0 6.36270E-18 7.93065E-17 1.08515E-16 + 230520 51.94473 900.0 6.50939E-21 8.11348E-20 1.13198E-19 + 230530 52.94432 900.0 4.56019E-21 5.68394E-20 8.08274E-20 + 230540 53.94643 900.0 3.79068E-21 4.72481E-20 6.84600E-20 + 230550 54.94723 900.0 7.88313E-22 9.82576E-21 1.45011E-20 + 230560 55.95054 900.0 3.61418E-23 4.50482E-22 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8.96761E-27 + 832100 209.98387 900.0 7.82315E-30 9.75100E-29 5.49952E-28 + 832110 210.98749 900.0 7.23508E-31 9.01800E-30 5.11042E-29 + 832120 211.99112 900.0 5.01916E-27 6.25602E-26 3.56210E-25 + 832130 212.99474 900.0 4.74917E-30 5.91950E-29 3.38644E-28 + 832140 213.99836 900.0 5.32139E-34 6.63273E-33 3.81235E-32 + 832150 215.00198 900.0 1.19988E-33 1.49556E-32 8.63647E-32 + 842100 209.98286 900.0 9.90676E-31 1.23481E-29 6.96422E-29 + 842110 210.98649 900.0 7.98749E-36 9.95583E-35 5.64185E-34 + 842120 211.98910 900.0 2.65592E-37 3.31041E-36 1.88488E-35 + 842140 213.99533 900.0 1.96099E-34 2.44424E-33 1.40487E-32 + 842150 214.99896 900.0 1.02609E-35 1.27895E-34 7.38549E-34 + 842160 216.00157 900.0 3.65745E-31 4.55875E-30 2.64479E-29 + 842180 218.00881 900.0 8.50232E-35 1.05975E-33 6.20538E-33 + 852170 217.00519 900.0 5.74009E-35 7.15462E-34 4.17010E-33 + 852190 219.01142 900.0 1.52381E-34 1.89932E-33 1.11726E-32 + 862180 218.00579 900.0 4.34971E-32 5.42160E-31 3.17457E-30 + 862190 219.00941 900.0 2.29196E-32 2.85676E-31 1.68045E-30 + 862200 220.01101 900.0 1.37896E-28 1.71878E-27 1.01567E-26 + 862220 222.01725 900.0 1.52719E-31 1.90354E-30 1.13511E-29 + 872210 221.01463 900.0 5.10769E-31 6.36637E-30 3.77922E-29 + 872220 222.01725 900.0 2.29543E-34 2.86109E-33 1.70612E-32 + 872230 223.01986 900.0 1.79660E-29 2.23934E-28 1.34138E-27 + 882210 221.01362 900.0 2.39087E-36 2.98005E-35 1.76902E-34 + 882220 222.01523 900.0 4.37024E-29 5.44719E-28 3.24822E-27 + 882230 223.01885 900.0 5.68719E-27 7.08868E-26 4.24616E-25 + 882240 224.02045 900.0 7.75951E-25 9.67167E-24 5.81941E-23 + 882250 225.02408 900.0 1.50634E-27 1.87755E-26 1.13478E-25 + 882260 226.02568 900.0 1.05122E-25 1.31027E-24 7.95442E-24 + 882280 228.03091 900.0 1.71734E-29 2.14055E-28 1.31102E-27 + 892250 225.02307 900.0 1.53926E-27 1.91858E-26 1.15957E-25 + 892260 226.02568 900.0 4.78110E-28 5.95929E-27 3.61778E-26 + 892270 227.02728 900.0 6.83696E-22 8.52178E-21 5.19635E-20 + 892280 228.03091 900.0 1.75293E-33 2.18491E-32 1.33818E-31 + 902260 226.02467 900.0 2.21694E-27 2.76326E-26 1.67752E-25 + 90227.82c 227.02729 900.0 9.56271E-26 1.19192E-24 7.26802E-24 + 90228.82c 228.02889 900.0 8.75183E-22 1.09085E-20 6.68107E-20 + 90229.82c 229.03150 900.0 3.10918E-21 3.87538E-20 2.38396E-19 + 90230.82c 230.03613 900.0 2.08632E-18 2.60044E-17 1.60669E-16 + 902310 231.03673 900.0 1.59890E-15 1.99292E-14 1.23669E-13 + 902320 232.03833 900.0 6.36039E-17 7.92776E-16 4.94083E-15 + 902340 234.04356 900.0 1.73543E-14 2.16309E-13 1.35976E-12 + 912290 229.03251 900.0 3.69848E-25 4.60990E-24 2.83581E-23 + 912300 230.03412 900.0 3.95880E-22 4.93437E-21 3.04869E-20 + 91231.82c 231.03471 900.0 4.77638E-15 5.95342E-14 3.69431E-13 + 91232.82c 232.03833 900.0 4.93049E-18 6.14550E-17 3.83007E-16 + 91233.82c 233.03994 900.0 9.88351E-19 1.23191E-17 7.71078E-17 + 912340 234.04356 900.0 2.82832E-19 3.52529E-18 2.21606E-17 + 912341 234.04356 900.0 5.79476E-19 7.22275E-18 4.54034E-17 + 922300 230.03412 900.0 2.20342E-24 2.74641E-23 1.69686E-22 + 922310 231.03673 900.0 2.03157E-24 2.53220E-23 1.57133E-22 + 92232.82c 232.03329 900.0 2.16891E-17 2.70340E-16 1.68480E-15 + 92233.82c 233.03994 900.0 8.65672E-14 1.07900E-12 6.75368E-12 + 92234.82c 234.04053 900.0 9.01625E-11 1.12381E-09 7.06438E-09 + 92235.82c 235.04415 900.0 3.94150E-04 4.91279E-03 3.10147E-02 + 922351 235.04415 900.0 1.26787E-15 1.58031E-14 9.97656E-14 + 92236.82c 236.04556 900.0 2.64774E-07 3.30021E-06 2.09232E-05 + 92237.82c 237.04878 900.0 1.68092E-09 2.09514E-08 1.33395E-07 + 92238.82c 238.05078 900.0 7.41363E-03 9.24056E-02 5.90823E-01 + 922390 239.05461 900.0 3.42284E-09 4.26632E-08 2.73931E-07 + 922400 240.05621 900.0 3.16966E-33 3.95076E-32 2.54732E-31 + 932330 233.04095 900.0 3.64482E-34 4.54300E-33 2.84358E-32 + 932340 234.04255 900.0 5.88301E-28 7.33275E-27 4.60947E-26 + 93235.82c 235.04415 900.0 3.01497E-20 3.75794E-19 2.37241E-18 + 93236.82c 236.04677 900.0 9.20379E-18 1.14719E-16 7.27314E-16 + 932361 236.04677 900.0 9.52821E-24 1.18762E-22 7.52950E-22 + 93237.82c 237.04817 900.0 5.57914E-10 6.95400E-09 4.42753E-08 + 93238.82c 238.05098 900.0 4.93697E-13 6.15358E-12 3.93448E-11 + 93239.82c 239.05259 900.0 4.08701E-07 5.09417E-06 3.27082E-05 + 932400 240.05621 900.0 2.97688E-12 3.71047E-11 2.39238E-10 + 932401 240.05621 900.0 6.10636E-13 7.61114E-12 4.90741E-11 + 942340 234.04356 900.0 6.96364E-34 8.67968E-33 5.45619E-32 + 942350 235.04516 900.0 2.39270E-29 2.98232E-28 1.88276E-27 + 94236.82c 236.04576 900.0 1.06862E-21 1.33195E-20 8.44452E-20 + 94237.82c 237.04837 900.0 1.30781E-17 1.63009E-16 1.03786E-15 + 942371 237.04837 900.0 2.74565E-31 3.42225E-30 2.17891E-29 + 94238.82c 238.04998 900.0 2.90503E-13 3.62091E-12 2.31513E-11 + 94239.82c 239.05198 900.0 4.56989E-07 5.69604E-06 3.65725E-05 + 94240.82c 240.05379 900.0 1.08824E-09 1.35642E-08 8.74564E-08 + 94241.82c 241.05681 900.0 1.27740E-11 1.59219E-10 1.03087E-09 + 94242.82c 242.05841 900.0 5.71245E-15 7.12016E-14 4.62913E-13 + 94243.82c 243.06203 900.0 1.19019E-18 1.48348E-17 9.68478E-17 + 94244.82c 244.06465 900.0 2.89283E-22 3.60570E-21 2.36366E-20 + 942450 245.06827 900.0 7.21980E-27 8.99896E-26 5.92337E-25 + 952390 239.05259 900.0 2.45551E-27 3.06062E-26 1.96513E-25 + 952400 240.05520 900.0 9.41940E-24 1.17406E-22 7.56992E-22 + 95241.82c 241.05681 900.0 2.42301E-15 3.02011E-14 1.95538E-13 + 95642.82c 242.05942 900.0 2.32214E-18 2.89438E-17 1.88177E-16 + 95242.82c 242.05942 900.0 4.28174E-19 5.33689E-18 3.46976E-17 + 95243.82c 243.06102 900.0 4.43691E-18 5.53029E-17 3.61038E-16 + 95244.82c 244.06465 900.0 1.56167E-22 1.94651E-21 1.27600E-20 + 95644.82c 244.06465 900.0 1.55606E-22 1.93952E-21 1.27142E-20 + 952450 245.06625 900.0 1.50324E-26 1.87368E-25 1.23330E-24 + 96240.82c 240.05520 900.0 3.96122E-29 4.93738E-28 3.18344E-27 + 96241.82c 241.05781 900.0 6.71220E-27 8.36627E-26 5.41680E-25 + 96242.82c 242.05841 900.0 2.11156E-18 2.63191E-17 1.71112E-16 + 96243.82c 243.06102 900.0 1.58371E-22 1.97398E-21 1.28868E-20 + 96244.82c 244.06263 900.0 5.77324E-21 7.19593E-20 4.71713E-19 + 962441 244.06263 900.0 1.46031E-28 1.82017E-27 1.19317E-26 + 96245.82c 245.06524 900.0 1.58742E-24 1.97861E-23 1.30236E-22 + 96246.82c 246.06685 900.0 1.41580E-28 1.76470E-27 1.16631E-26 + 96247.82c 247.06946 900.0 6.98522E-33 8.70658E-32 5.77771E-31 + 96248.82c 248.07207 900.0 1.71154E-36 2.13332E-35 1.42142E-34 + sum 8.02292E-02 1.00000E+00 1.00000E+00 +------------------------------------------------------------------- + +Material "ctrlPois": + + - Material is included in majorant + - Material is included in geometry + - Atom density 8.62582E-02 1/barn*cm + - Mass density 5.87300E+00 g/cm3 + - Volume 1.11635E+04 cm3 + - Mass 6.55632E+04 g + - Photon emission rate 0.00000E+00 1/s + - Neutron emission rate 0.00000E+00 1/s + - 1655 nuclides in composition + - No nuclides associated with S(a,b) data + - 24.69 Mb of memory allocated for data + +Isotopic composition (non-zero densities): + +------------------------------------------------------------------- + Nuclide a. weight temp a. dens a. frac m. frac +------------------------------------------------------------------- + 1001.82c 1.00783 900.0 1.60678E-11 1.86276E-10 4.57867E-12 + 1002.82c 2.01410 900.0 5.18761E-15 6.01404E-14 2.95423E-15 + 1003.82c 3.01605 900.0 1.89861E-17 2.20107E-16 1.61908E-17 + 2003.82c 3.01493 900.0 2.89424E-18 3.35532E-17 2.46722E-18 + 2004.82c 4.00258 900.0 9.24041E-11 1.07125E-09 1.04575E-10 + 5011.82c 11.00928 900.0 1.82787E-35 2.11907E-34 5.68985E-35 + 60120 11.99999 900.0 2.47462E-37 2.86885E-36 8.39625E-37 + 60130 13.00331 900.0 9.00414E-11 1.04386E-09 3.31049E-10 + 60140 14.00319 900.0 4.48213E-21 5.19618E-20 1.77463E-20 + 7014.82c 14.00307 900.0 3.03925E-27 3.52344E-26 1.20333E-26 + 7015.82c 14.99986 900.0 8.21708E-37 9.52614E-36 3.48498E-36 + 8016.82c 15.99492 900.0 5.17714E-02 6.00191E-01 2.34136E-01 + 8017.82c 16.99913 900.0 1.43224E-13 1.66041E-12 6.88394E-13 + 80180 17.99912 900.0 1.19553E-23 1.38600E-22 6.08428E-23 + 100210 20.99385 900.0 8.02308E-22 9.30124E-21 4.76244E-21 + 100220 21.99142 900.0 7.82276E-29 9.06900E-28 4.86418E-28 + 110240 23.99100 900.0 6.77669E-13 7.85629E-12 4.59687E-12 + 110250 24.98998 900.0 6.30380E-33 7.30806E-32 4.45415E-32 + 12024.82c 23.98504 900.0 1.67145E-12 1.93773E-11 1.13352E-11 + 12025.82c 24.98584 900.0 8.40204E-20 9.74057E-19 5.93574E-19 + 12026.82c 25.98260 900.0 4.13430E-15 4.79294E-14 3.03726E-14 + 120270 26.98431 900.0 3.26803E-14 3.78866E-13 2.49341E-13 + 13027.82c 26.98154 900.0 2.08382E-02 2.41579E-01 1.58973E-01 + 130280 27.98188 900.0 7.08593E-14 8.21479E-13 5.60621E-13 + 130290 28.98046 900.0 7.69723E-31 8.92347E-30 6.30719E-30 + 14028.82c 27.97734 900.0 1.79848E-10 2.08499E-09 1.42268E-09 + 14029.82c 28.97652 900.0 8.10451E-19 9.39564E-18 6.64001E-18 + 14030.82c 30.00002 900.0 3.18413E-27 3.69140E-26 2.70090E-26 + 140310 30.97540 900.0 2.38581E-36 2.76589E-35 2.08953E-35 + 15031.82c 30.97378 900.0 2.11592E-35 2.45300E-34 1.85306E-34 + 60147.82c 146.91609 900.0 5.77918E-37 6.69986E-36 2.40066E-35 + 60148.82c 147.91668 900.0 3.76961E-28 4.37015E-27 1.57656E-26 + 601490 148.92030 900.0 4.01467E-29 4.65425E-28 1.69044E-27 + 60150.82c 149.92090 900.0 6.85240E-29 7.94406E-28 2.90470E-27 + 601510 150.92351 900.0 3.40772E-33 3.95061E-32 1.45418E-31 + 61148.82c 147.91668 900.0 2.90060E-31 3.36270E-30 1.21311E-29 + 61149.82c 148.91829 900.0 6.16090E-28 7.14239E-27 2.59411E-26 + 611500 149.92090 900.0 2.05999E-29 2.38817E-28 8.73220E-28 + 61151.82c 150.92150 900.0 1.75435E-26 2.03383E-25 7.48623E-25 + 611520 151.92310 900.0 5.62633E-28 6.52266E-27 2.41682E-26 + 611530 152.92370 900.0 1.30354E-31 1.51120E-30 5.63630E-30 + 611540 153.92631 900.0 1.32503E-33 1.53612E-32 5.76680E-32 + 62148.82c 147.91467 900.0 5.56522E-32 6.45181E-31 2.32750E-30 + 62149.82c 148.91728 900.0 3.73642E-28 4.33168E-27 1.57325E-26 + 62150.82c 149.91687 900.0 1.47715E-24 1.71247E-23 6.26138E-23 + 62151.82c 150.91645 900.0 4.17854E-16 4.84422E-15 1.78302E-14 + 62152.82c 151.92007 900.0 3.37018E-15 3.90708E-14 1.44765E-13 + 62153.82c 152.92168 900.0 1.68463E-15 1.95301E-14 7.28399E-14 + 62154.82c 153.92227 900.0 1.58046E-15 1.83224E-14 6.87829E-14 + 621550 154.92489 900.0 7.70554E-18 8.93311E-17 3.37536E-16 + 621560 155.92548 900.0 1.15071E-30 1.33403E-29 5.07315E-29 + 621570 156.92810 900.0 3.57259E-18 4.14174E-17 1.58518E-16 + 63151.82c 150.91948 900.0 2.35349E-20 2.72842E-19 1.00428E-18 + 63152.82c 151.92209 900.0 1.12329E-24 1.30225E-23 4.82515E-23 + 63153.82c 152.92168 900.0 2.24797E-15 2.60609E-14 9.71975E-14 + 63154.82c 153.92227 900.0 1.04959E-15 1.21680E-14 4.56792E-14 + 631541 153.92328 900.0 9.81867E-24 1.13829E-22 4.27320E-22 + 63155.82c 154.92287 900.0 1.19751E-14 1.38829E-13 5.24556E-13 + 63156.82c 155.92548 900.0 3.78986E-15 4.39363E-14 1.67085E-13 + 63157.82c 156.92507 900.0 1.32562E-15 1.53680E-14 5.88175E-14 + 631580 157.92768 900.0 1.99318E-17 2.31071E-16 8.90020E-16 + 631600 159.93190 900.0 1.13398E-19 1.31464E-18 5.12787E-18 + 64152.82c 151.92007 900.0 6.38577E-29 7.40309E-28 2.74299E-27 + 641530 152.92168 900.0 6.50923E-34 7.54621E-33 2.81446E-32 + 64154.82c 153.92127 900.0 2.98133E-04 3.45629E-03 1.29749E-02 + 64155.82c 154.92287 900.0 2.02397E-03 2.34641E-02 8.86576E-02 + 64156.82c 155.92205 900.0 2.79953E-03 3.24553E-02 1.23421E-01 + 64157.82c 156.92406 900.0 2.14024E-03 2.48120E-02 9.49615E-02 + 64158.82c 157.92466 900.0 3.39716E-03 3.93837E-02 1.51692E-01 + 641590 158.92626 900.0 1.63344E-09 1.89366E-08 7.33998E-08 + 64160.82c 159.92686 900.0 2.98956E-03 3.46583E-02 1.35184E-01 + 641610 160.92947 900.0 1.98985E-12 2.30685E-11 9.05423E-11 + 65159.82c 158.92525 900.0 7.10636E-09 8.23848E-08 3.19327E-07 + 65160.82c 159.92686 900.0 6.13046E-14 7.10710E-13 2.77211E-12 + 651610 160.92745 900.0 2.62924E-09 3.04811E-08 1.19635E-07 + 651620 161.92906 900.0 7.95161E-32 9.21839E-31 3.64063E-30 + 651630 162.93066 900.0 1.75759E-35 2.03759E-34 8.09687E-34 + 66160.82c 159.92484 900.0 1.01959E-15 1.18202E-14 4.61039E-14 + 66161.82c 160.92644 900.0 9.15829E-10 1.06173E-08 4.16714E-08 + 66162.82c 161.92704 900.0 8.81712E-15 1.02218E-13 4.03685E-13 + 66163.82c 162.92864 900.0 4.34890E-19 5.04172E-18 2.00342E-17 + 66164.82c 163.92823 900.0 2.99073E-24 3.46718E-23 1.38620E-22 + 661650 164.93185 900.0 9.92675E-31 1.15082E-29 4.62922E-29 + 661651 164.93185 900.0 6.41934E-33 7.44201E-32 2.99358E-31 + 67165.82c 164.92983 900.0 6.01332E-30 6.97131E-29 2.80421E-28 + 671660 165.93245 900.0 1.07359E-35 1.24462E-34 5.03693E-34 + 671661 165.93245 900.0 7.85659E-37 9.10823E-36 3.68605E-35 + 68166.82c 165.93043 900.0 3.88352E-36 4.50221E-35 1.82200E-34 + sum 8.62582E-02 1.00000E+00 1.00000E+00 +------------------------------------------------------------------- + +Material "zrh": + + - Material is included in majorant + - Material is included in geometry + - Atom density 9.75972E-02 1/barn*cm + - Mass density 5.66000E+00 g/cm3 + - Volume 0.00000E+00 cm3 + - Mass 0.00000E+00 g + - Photon emission rate 0.00000E+00 1/s + - Neutron emission rate 0.00000E+00 1/s + - 7 nuclides in composition + - 1 nuclides associated with S(a,b) data + - 11.96 Mb of memory allocated for data + +Isotopic composition (non-zero densities): + +------------------------------------------------------------------- + Nuclide a. weight temp a. dens a. frac m. frac +------------------------------------------------------------------- + 40090.82c 89.90473 900.0 1.88774E-02 1.93422E-01 4.97925E-01 + 40091.82c 90.90563 900.0 4.11688E-03 4.21823E-02 1.09799E-01 + 40092.82c 91.90501 900.0 6.29249E-03 6.44741E-02 1.69668E-01 + 40094.82c 93.90631 900.0 6.37689E-03 6.53388E-02 1.75688E-01 + 40096.82c 95.90830 900.0 1.02735E-03 1.05264E-02 2.89077E-02 + 1001.82s 1.00783 900.0 6.08992E-02 6.23985E-01 1.80068E-02 (s) + 1002.82c 2.01410 900.0 7.00422E-06 7.17666E-05 4.13886E-06 + sum 9.75972E-02 1.00000E+00 1.00000E+00 +------------------------------------------------------------------- + +Material "sic": + + - Material is included in majorant + - Material is included in geometry + - Atom density 9.64414E-02 1/barn*cm + - Mass density 3.21000E+00 g/cm3 + - Volume 0.00000E+00 cm3 + - Mass 0.00000E+00 g + - Photon emission rate 0.00000E+00 1/s + - Neutron emission rate 0.00000E+00 1/s + - 4 nuclides in composition + - No nuclides associated with S(a,b) data + - 11.96 Mb of memory allocated for data + +Isotopic composition (non-zero densities): + +------------------------------------------------------------------- + Nuclide a. weight temp a. dens a. frac m. frac +------------------------------------------------------------------- + 14028.82c 27.97734 900.0 4.44728E-02 4.61138E-01 6.43653E-01 + 14029.82c 28.97652 900.0 2.25927E-03 2.34264E-02 3.38661E-02 + 14030.82c 30.00002 900.0 1.48976E-03 1.54473E-02 2.31201E-02 + 6000.82c 12.00110 900.0 4.82196E-02 4.99989E-01 2.99361E-01 + sum 9.64414E-02 1.00000E+00 1.00000E+00 +------------------------------------------------------------------- + +Material "hast": + + - Material is included in majorant + - Material is included in geometry + - Atom density 8.75838E-02 1/barn*cm + - Mass density 8.86000E+00 g/cm3 + - Volume 0.00000E+00 cm3 + - Mass 0.00000E+00 g + - Photon emission rate 0.00000E+00 1/s + - Neutron emission rate 0.00000E+00 1/s + - 36 nuclides in composition + - No nuclides associated with S(a,b) data + - 12.00 Mb of memory allocated for data + +Isotopic composition (non-zero densities): + +------------------------------------------------------------------- + Nuclide a. weight temp a. dens a. frac m. frac +------------------------------------------------------------------- + 28058.82c 57.93570 900.0 4.45151E-02 5.08257E-01 4.83366E-01 + 28060.82c 59.93079 900.0 1.65762E-02 1.89261E-01 1.86191E-01 + 28061.82c 60.93143 900.0 2.96883E-03 3.38970E-02 3.39038E-02 + 28064.82c 63.92818 900.0 5.48747E-04 6.26540E-03 6.57486E-03 + 24050.82c 49.94606 900.0 3.24924E-04 3.70986E-03 3.04162E-03 + 24052.82c 51.93999 900.0 6.02529E-03 6.87946E-02 5.86546E-02 + 24053.82c 52.94079 900.0 6.70304E-04 7.65329E-03 6.65096E-03 + 24054.82c 53.93937 900.0 1.63764E-04 1.86980E-03 1.65557E-03 + 42092.82c 91.90683 900.0 1.36083E-03 1.55375E-02 2.34409E-02 + 42094.82c 93.90510 900.0 8.35490E-04 9.53932E-03 1.47046E-02 + 42095.82c 94.90589 900.0 1.42757E-03 1.62995E-02 2.53930E-02 + 42096.82c 95.90467 900.0 1.48392E-03 1.69429E-02 2.66731E-02 + 42097.82c 96.90597 900.0 8.43975E-04 9.63621E-03 1.53286E-02 + 42098.82c 97.90536 900.0 2.11805E-03 2.41831E-02 3.88655E-02 + 42100.82c 99.90746 900.0 8.32292E-04 9.50281E-03 1.55846E-02 + 26054.82c 53.93962 900.0 1.85761E-04 2.12095E-03 1.87795E-03 + 26056.82c 55.93491 900.0 2.80950E-03 3.20779E-02 2.94533E-02 + 26057.82c 56.93541 900.0 6.37763E-05 7.28175E-04 6.80556E-04 + 26058.82c 57.93329 900.0 8.27820E-06 9.45175E-05 8.98848E-05 + 14028.82c 27.97734 900.0 1.60023E-03 1.82708E-02 8.39095E-03 + 14029.82c 28.97652 900.0 7.87606E-05 8.99261E-04 4.27738E-04 + 14030.82c 30.00002 900.0 4.51661E-05 5.15691E-04 2.53955E-04 + 25055.82c 54.93805 900.0 5.82737E-04 6.65349E-03 6.00024E-03 + 23000.82c 50.94161 900.0 5.23711E-04 5.97955E-03 5.00020E-03 + 6000.82c 12.00110 900.0 2.66963E-04 3.04809E-03 6.00475E-04 + 27059.82c 58.93317 900.0 1.80873E-05 2.06515E-04 1.99782E-04 + 74182.82c 181.94803 900.0 2.33139E-05 2.66190E-04 7.95031E-04 + 74183.82c 182.95064 900.0 1.25205E-05 1.42955E-04 4.29317E-04 + 74184.82c 183.95124 900.0 2.66626E-05 3.04424E-04 9.19236E-04 + 74186.82c 185.95445 900.0 2.44730E-05 2.79423E-04 8.52934E-04 + 13027.82c 26.98154 900.0 3.95511E-04 4.51580E-03 2.00008E-03 + 22046.82c 45.95276 900.0 1.91587E-05 2.18748E-04 1.65007E-04 + 22047.82c 46.95134 900.0 1.69102E-05 1.93075E-04 1.48806E-04 + 22048.82c 47.94795 900.0 1.64074E-04 1.87334E-03 1.47446E-03 + 22049.82c 48.94788 900.0 1.17947E-05 1.34668E-04 1.08204E-04 + 22050.82c 49.94480 900.0 1.10679E-05 1.26369E-04 1.03604E-04 + sum 8.75838E-02 1.00000E+00 1.00000E+00 +------------------------------------------------------------------- + +Material "air": + + - Material is included in majorant + - Material is included in geometry + - Atom density 5.11533E-05 1/barn*cm + - Mass density 1.22500E-03 g/cm3 + - Volume 0.00000E+00 cm3 + - Mass 0.00000E+00 g + - Photon emission rate 0.00000E+00 1/s + - Neutron emission rate 0.00000E+00 1/s + - 2 nuclides in composition + - No nuclides associated with S(a,b) data + - 11.96 Mb of memory allocated for data + +Isotopic composition (non-zero densities): + +------------------------------------------------------------------- + Nuclide a. weight temp a. dens a. frac m. frac +------------------------------------------------------------------- + 8016.82c 15.99492 900.0 1.07422E-05 2.10000E-01 2.32914E-01 + 7014.82c 14.00307 900.0 4.04111E-05 7.90000E-01 7.67086E-01 + sum 5.11533E-05 1.00000E+00 1.00000E+00 +------------------------------------------------------------------- diff --git a/tests/unit_tests/test_app.py b/tests/unit_tests/test_app.py index 03ab4d27c..db0e0fa5d 100644 --- a/tests/unit_tests/test_app.py +++ b/tests/unit_tests/test_app.py @@ -54,6 +54,7 @@ def test_read_main_input(cwd, codename, ext): elif codename == 'serpent': assert depcode_input['template_input_file_path'] == \ str((input_path / 'tap_template.ini').resolve()) + assert depcode_input['zaid_convention'] == 'serpent' assert simulation_input['db_name'] == \ str((data_path / f'../{codename}_data/saltproc_runtime/saltproc_results.h5').resolve()) diff --git a/tests/unit_tests/test_serpent_depcode.py b/tests/unit_tests/test_serpent_depcode.py index 691d16f09..a7114ac0e 100644 --- a/tests/unit_tests/test_serpent_depcode.py +++ b/tests/unit_tests/test_serpent_depcode.py @@ -7,7 +7,8 @@ from saltproc import SerpentDepcode -def test_create_nuclide_name_map_zam_to_serpent(serpent_depcode): +def test_create_nuclide_name_map_zam_to_serpent(serpent_depcode, cwd): + old_runtime_inputfile = serpent_depcode.runtime_inputfile nuc_code_map = serpent_depcode.map_nuclide_code_zam_to_serpent() assert nuc_code_map[380880] == '38088.09c' assert nuc_code_map[962400] == '96240.09c' @@ -18,6 +19,38 @@ def test_create_nuclide_name_map_zam_to_serpent(serpent_depcode): assert nuc_code_map[420931] == '420931' assert nuc_code_map[410911] == '410911' + serpent_depcode.zaid_convention = 'mcnp' + serpent_depcode.runtime_inputfile = str(cwd / 'serpent_data' / 'tap_reference_mcnp') + nuc_code_map = serpent_depcode.map_nuclide_code_zam_to_serpent() + assert nuc_code_map[380880] == '38088.82c' + assert nuc_code_map[962400] == '96240.82c' + assert nuc_code_map[952421] == '95642.82c' + assert nuc_code_map[952420] == '95242.82c' + assert nuc_code_map[471101] == '47510.82c' + assert nuc_code_map[340831] == '340831' + assert nuc_code_map[300732] == '300732' + assert nuc_code_map[511262] == '511262' + assert nuc_code_map[420931] == '420931' + assert nuc_code_map[410911] == '410911' + + serpent_depcode.zaid_convention = 'nndc' + serpent_depcode.runtime_inputfile = str(cwd / 'serpent_data' / 'tap_reference_nndc') + nuc_code_map = serpent_depcode.map_nuclide_code_zam_to_serpent() + + assert nuc_code_map[380880] == '38088.82c' + assert nuc_code_map[962400] == '96240.82c' + assert nuc_code_map[952421] == '95242.82c' + assert nuc_code_map[952420] == '95642.82c' + assert nuc_code_map[471101] == '47510.82c' + assert nuc_code_map[340831] == '340831' + assert nuc_code_map[300732] == '300732' + assert nuc_code_map[511262] == '511262' + assert nuc_code_map[420931] == '420931' + assert nuc_code_map[410911] == '410911' + + serpent_depcode.runtime_inputfile = old_runtime_inputfile + serpent_depcode.zaid_convention = 'serpent' + def test_convert_nuclide_code_to_zam(serpent_depcode): assert serpent_depcode.convert_nuclide_code_to_zam(47310) == 471101 @@ -94,6 +127,42 @@ def test_convert_nuclide_code_to_name(serpent_depcode): assert serpent_depcode.convert_nuclide_code_to_name('390972') == 'Y97m2' assert serpent_depcode.convert_nuclide_code_to_name('491142') == 'In114m2' + serpent_depcode.zaid_convention = 'mcnp' + assert serpent_depcode.convert_nuclide_code_to_name('92235.82c') == 'U235' + assert serpent_depcode.convert_nuclide_code_to_name('38088.82c') == 'Sr88' + assert serpent_depcode.convert_nuclide_code_to_name('95642.82c') == 'Am242m1' + assert serpent_depcode.convert_nuclide_code_to_name('95242.82c') == 'Am242' + assert serpent_depcode.convert_nuclide_code_to_name('61548.82c') == 'Pm148m1' + assert serpent_depcode.convert_nuclide_code_to_name('20060') == 'He6' + assert serpent_depcode.convert_nuclide_code_to_name('110241') == 'Na24m1' + assert serpent_depcode.convert_nuclide_code_to_name('170381') == 'Cl38m1' + assert serpent_depcode.convert_nuclide_code_to_name('310741') == 'Ga74m1' + assert serpent_depcode.convert_nuclide_code_to_name('290702') == 'Cu70m2' + assert serpent_depcode.convert_nuclide_code_to_name('250621') == 'Mn62m1' + assert serpent_depcode.convert_nuclide_code_to_name('300732') == 'Zn73m2' + assert serpent_depcode.convert_nuclide_code_to_name('370981') == 'Rb98m1' + assert serpent_depcode.convert_nuclide_code_to_name('390972') == 'Y97m2' + assert serpent_depcode.convert_nuclide_code_to_name('491142') == 'In114m2' + + serpent_depcode.zaid_convention = 'nndc' + assert serpent_depcode.convert_nuclide_code_to_name('92235.82c') == 'U235' + assert serpent_depcode.convert_nuclide_code_to_name('38088.82c') == 'Sr88' + assert serpent_depcode.convert_nuclide_code_to_name('95242.82c') == 'Am242m1' + assert serpent_depcode.convert_nuclide_code_to_name('95642.82c') == 'Am242' + assert serpent_depcode.convert_nuclide_code_to_name('61548.82c') == 'Pm148m1' + assert serpent_depcode.convert_nuclide_code_to_name('20060') == 'He6' + assert serpent_depcode.convert_nuclide_code_to_name('110241') == 'Na24m1' + assert serpent_depcode.convert_nuclide_code_to_name('170381') == 'Cl38m1' + assert serpent_depcode.convert_nuclide_code_to_name('310741') == 'Ga74m1' + assert serpent_depcode.convert_nuclide_code_to_name('290702') == 'Cu70m2' + assert serpent_depcode.convert_nuclide_code_to_name('250621') == 'Mn62m1' + assert serpent_depcode.convert_nuclide_code_to_name('300732') == 'Zn73m2' + assert serpent_depcode.convert_nuclide_code_to_name('370981') == 'Rb98m1' + assert serpent_depcode.convert_nuclide_code_to_name('390972') == 'Y97m2' + assert serpent_depcode.convert_nuclide_code_to_name('491142') == 'In114m2' + + serpent_depcode.zaid_convention = 'serpent' + def test_read_step_metadata(serpent_depcode): serpent_depcode.read_step_metadata()